Text

Annual Radioactive Effluent Release Report for 2016
	ML17118A011
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/28/2017
From:	Pyle S; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	0CAN041702
	Download: ML17118A011 (181)
	v • d • e

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 0CAN041702 April 28, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Annual Radioactive Effluent Release Report for 2016 Arkansas Nuclear One, Units 1 and 2 Docket No. 50-313 and 50-368 License No. DPR-51 and NPF-6

Dear Sir or Madam:

Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2) Technical Specifications (TSs) 5.6.3 and 6.6.3, respectively, require the submittal of an Annual Radioactive Effluent Release Report.

The information which fulfills this reporting requirement for ANO-1 and ANO-2 for the 2016 calendar year is enclosed.

ANO-1 TS 5.6.3 and ANO-2 TS 6.6.3 require this report to be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. 10 CFR 50.36a(a)(2) states that the interval between submittals for this report must not exceed 12 months.

Liquid and gaseous release data show that the dose from both ANO-1 and ANO-2 was considerably below the Offsite Dose Calculation Manual limits. The data reveals that radioactive effluents had an overall minimal dose contribution to the surrounding environment.

No new commitments have been identified in this letter.

If you have any questions or require additional information, please contact me.

Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/rwc

Enclosure:

Annual Radioactive Effluent Release Report for 2016

0CAN041702 Page 2 of 2 cc: Mr. Kriss Kennedy Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1A One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

ENCLOSURE TO 0CAN041702 ARKANSAS NUCLER ONE ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2016

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 TABLE OF CONTENTS

1. EXECUTIVE

SUMMARY

...................................................................................................... 2

2. INTRODUCTION .................................................................................................................. 3

3. RADIOACTIVE EFFLUENT MONITORING RESULTS ...................................................... 5

4.

SUMMARY

OF RADIOACTIVE WASTE SHIPMENTS ...................................................... 11

5. ADDITIONAL REQUIRED INFORMATION........................................................................ 14 APPENDIX A:EFFLUENT AND RADIOACTIVE WASTE DATA ................................................. 16 APPENDIX B: GROUND WATER PROTECTION PROGRAM DATA AND ANALYSIS ............. 54 APPENDIX C: METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS ........................... 71 APPENDIX D:REVISED OFFSITE DOSE CALCULATION MANUAL ........................................ 74 1

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

1. EXECUTIVE

SUMMARY

This report is published to provide information regarding radioactive effluent monitoring at Arkansas Nuclear One (ANO) nuclear power plant. The 2016 Annual Radioactive Effluent Release Report (ARERR) covers the period from January 1, 2016, through December 31, 2016.

The ARERR is produced annually, to document plant releases and offsite dose resulting from these releases. The data presented indicate that the operation of ANO-1 and ANO-2 results in offsite radiation exposures that are well below the applicable allowable levels set by the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

Data on releases of radioactive isotopes in liquid and gaseous effluents, as well as regulatory limits and sampling methods for these releases, are contained in the body of the report and in Appendix A.

Regulatory limits for radioactive effluents pertain to allowable offsite doses rather than to quantities of radioactivity released. The highest potential single organ dose to a person living offsite due to iodines, particulates, tritium, and carbon-14 released from the plant was calculated to be 0.51 mrem, which is 2.1% of the applicable limit found in 10 CFR Part 50, Appendix I.

During 2016, no direct radiation dose to members of the public beyond the site boundary was attributed to the operation of ANO-1&2, based on analysis of readings of thermoluminescent dosimeters (TLD) placed at various locations near the ANO site. The offsite dose due to effluents is a small fraction of the 40 CFR 190 limits. Therefore, the combined direct radiation and effluent dose due to ANO-1&2 was in compliance with 40 CFR 190 in 2016.

Data on radioactivity contained in radioactive waste shipments from ANO-1&2 to offsite locations are contained in the body of the report and in Appendix A. Appendix B of this report describes the ANO Ground Water Protection Program. This program was established as part of the sites commitment to conformance with an industry-wide ground water protection initiative.

This appendix also contains the results of 2016 quarterly/semi-annual ground water sampling, from approximately 20 monitor wells around ANO. One well of these monitor wells, MW-17; has yielded sporadic trace quantities of tritium that have been attributed to the recapture of tritium in precipitation from the plants monitored gaseous effluent. Appendix C of this report contains the meteorological joint frequency distribution tables for 2016. The Offsite Dose Calculation Manual (ODCM) was revised in 2016, and the revised ODCM is shown as Appendix D. Additional sections of the report address ODCM required monitors which were out of service for more than 30 days in 2016, major changes in radioactive waste processing, and the contents of outside temporary tanks, abnormal releases, and errata to previous years' reports.

2

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

2. INTRODUCTION ANO is a two unit site consisting of a Babcock & Wilcox (Unit 1) and a Combustion Engineering (Unit 2) nuclear steam supply system. Both liquid and gaseous effluents are released in accordance with the ODCM. This report is a summary of the effluent data in accordance with ANO-1 Technical Specification (TS) 5.6.3 and Unit 2 TS 6.6.3.

Noble Gases:

Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. These noble gases are released continuously at low levels while the reactor is operating. Noble gas releases to the environment are reduced by plant systems which delay release of these gases from the plant, which allows a portion of the noble gas activity to decay within plant systems prior to release. Noble gases are biologically and chemically nonreactive and are readily dispersed in the atmosphere. They do not concentrate in humans or other organisms; however, they contribute to human radiation dose by being an external source of radiation exposure to the body.

Iodines and Particulates:

ANO-1&2 is required to calculate offsite dose due to releases of iodine-131 and iodine-133, which are radioisotopes of iodine with half-lives of 8 days and 1 day, respectively, and particulates with half-lives greater than 8 days in gaseous and liquid effluents, and tritium. The principal radioactive particulates released are fission products (e.g., yttrium-91m and barium-139) and activation products (e.g., cobalt-58 and cobalt-60). Annual releases of these radionuclides are well within industry norms. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing and radioactive waste systems, minimize their discharge. The main contribution of radioactive iodine to human radiation dose is to the thyroid gland, where the body concentrates iodine.

This exposure results from inhalation or ingestion of these iodines. Radioactive cesiums and cobalts, when ingested or inhaled, contribute to radiation exposure of tissues such as the muscle, liver, and intestines. These iodines and particulates are also a source of external radiation exposure if deposited on the ground.

Tritium:

Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in radioactive liquid and gaseous effluents.

Carbon-14:

U.S. nuclear power plants are expected to report releases of carbon-14 (C-14). The releases reported are based on calculations involving the thermal power rating of the unit and 2016 Year-To-Date (YTD) capacity factors. The calculation performed for this report estimated a total 2016 C-14 releases of 6.62 curies for ANO-1 and 10.36 curies for ANO-2.

3

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Plant Effluent Monitoring:

Effluents are strictly monitored to ensure that radioactivity released to the environment is as low as reasonably achievable and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance programs for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring. The radioactive waste treatment systems at ANO-1&2 are designed to collect, process, and/or delay the release of liquid and gaseous wastes that contain radioactivity The waste gas decay system provides additional delay for such gases. Radioactivity monitoring systems are used to verify that all releases are below regulatory limits. These instruments provide a continuous indication of radioactivity present at the release points. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure that applicable limits will not be exceeded. In some cases, these alarms restrict the release.

All liquid and gaseous radioactive effluents are evaluated to identify the specific concentrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition than monitoring instruments.

A meteorological tower is located on the ANO site. It is linked to computers that record the meteorological data. This data is used in calculating dispersion and deposition factors, which are essentially dilution factors between plant release points and locations offsite. Coupled with the effluent release data, these factors are used to calculate dose to the public. Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program constantly sample the air in the surrounding environment. Also, frequent samples of other environmental media, such as water and vegetation, are collected to verify that the station radiological effluent program is being appropriately implemented without adverse impact to the surrounding environment.

Exposure Pathways to People Radiological exposure pathways define the methods by which people may become exposed to radioactive material. The major pathways of concern are those that could cause the highest calculated radiation dose. These projected pathways are determined from the type and amount of radioactive material released the environmental transport mechanism, and the use of the environment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological and meteorological characteristics of the area. An important factor in evaluating the exposure pathways is the use of the environment. This is evaluated in the Biennial Land Use Census. Many factors are considered, such as the locations of homes, gardens, and milk or meat animals in the area. The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposition of radioactive material on plants, deposition on soil, inhalation and ingestion by animals raised for human consumption, and inhalation by humans. The release of radioactive material in liquid effluents involves pathways such as drinking water and fish consumption. Although radionuclides can reach humans by many different pathways, some result in greater dose than others. The most significant pathway is the exposure pathway that will provide the greatest dose to a population, or to a specific individual. Identification of the most significant pathway depends on the radionuclides involved, the age and diet of the individual, and the location of the individuals 4

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 residence. Doses delivered to the total body and to specific organs are calculated. The organ receiving the greatest dose is important in determining compliance with dose limits. The standard assumptions used in dose calculation result in conservative dose estimates.

Dose Assessment Dose is energy deposited by radiation in an exposed individual. Whole body exposure to radiation involves the exposure of all organs. Most exposures due to external sources of radiation are of this type. Both non-radioactive and radioactive elements can enter the body through inhalation or ingestion. When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue. The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the organ. Some radionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time. The form of the radionuclide (soluble vs.

insoluble) and the method of uptake also influence residence times in the body.

The maximum dose to the general public in the area surrounding ANO-1&2 is calculated for periods of gaseous release and for each liquid release. The dose due to radioactive material released in gaseous effluents is calculated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the locations of exposure pathways (for example cow milk, goat milk, vegetable gardens and residences), and usage factors (inhalation and food consumption). The dose due to radioactive material released in liquid effluents is calculated using factors such as radionuclide concentrations, the total volume of liquid released, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption). These calculations produce a conservative estimation of the dose.

3. RADIOACTIVE EFFLUENT MONITORING RESULTS This section summarizes the results of effluent monitoring and offsite dose calculation for the year 2016. Calculated offsite doses are compared with Nuclear Regulatory Commission limits, and these limits are summarized in Appendix A. Appendix A also contains a detailed discussion of the methods used to determine quantities of radioactivity released in effluents, the types of solid radioactive waste shipped offsite, as well as tables of individual radionuclides released in effluents and shipped as solid radioactive waste.

Data in the following liquid effluent tables represent continuous and batch releases for ANO-1&2.

5

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Table 1 - Fission and Activation Products Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 5.07E-02 1.38E-02 4.13E-02 4.53E-02 Avg. Concentration 1.54E-10 3.75E-11 1.09E-10 2.70E-10 (uCi/ml)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 2.17E-03 4.26E-03 3.74E-03 8.16E-03 Avg. Concentration 6.60E-12 1.16E-11 9.86E-12 4.86E-11 (uCi/ml)

Table 2 -Tritium Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 1.52E+02 1.57E+02 2.07E+02 3.87E+01 Avg. Concentration 4.62E-07 4.25E-07 5.46E-07 2.30E-07 (uCi/ml)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 6.76E+01 1.07E+02 6.72E+01 2.87E+02 Avg. Concentration 2.06E-07 2.91E-07 1.77E-07 1.71E-06 (uCi/ml)

Table 3 - Dissolved and Entrained Gases Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 1.35E-02 1.75E-02 1.00E-01 1.05E-02 Avg. Concentration 4.13E-11 4.73E-11 2.64E-10 6.26E-11 (uCi/ml)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 7.43E-04 1.24E-04 6.75E-04 2.08E-03 Avg. Concentration 2.26E-12 3.36E-13 1.78E-12 1.24E-11 (uCi/ml) 6

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Table 4 - Liquid Effluents Dose Receptor with Highest Single Organ Dose ANO-1 Dose to Organ (mrem)

Bone 3.57E-02 Liver 6.80E-02 Thyroid 1.43E-03 Kidney 2.29E-02 Lung 8.26E-03 GI-Li 4.11E-03 Total Body 5.19E-02 ANO-2 Dose to Organ (mrem)

Bone 7.76E-03 Liver 1.26E-02 Thyroid 1.60E-03 Kidney 5.29E-03 Lung 2.85E-03 GI-Li 1.87E-03 Total Body 8.90E-03 The highest single organ dose is 6.80E-02 mrem to the liver on ANO-1. This is 0.68% of the federal limit of 10 mrem specified in 10 CFR 50, Appendix I.

The highest total body dose for any given unit was 5.19E-02 mrem on ANO-1. This is 1.73% of the federal limit of 3 mrem specified in 10 CFR 50, Appendix I. Dose estimates are conservative in nature and are well below the federal limits for organ and total body dose.

7

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Data in the following gaseous effluent tables represent continuous and batch releases for ANO 1&2.

Table 5 - Fission and Activation Gases Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 0.00E+00 1.71E-01 1.25E+01 2.49E+00 Average Release Rate for Period 0.00E+00 2.17E-02 1.57E+00 3.13E-01 (uCi/sec)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 1.07E+00 1.21E-05 1.08E-01 1.20E+01 Average Release Rate for Period 1.36E-01 1.54E-06 1.36E-02 1.50E+00 (uCi/sec)

Table 6 - Radioiodines and Halogens Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 0.00E+00 0.00E+00 1.25E-05 1.87E-04 Average Release Rate for Period 0.00E+00 0.00E+00 1.58EE-06 2.35E-05 (uCi/sec)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 0.00E+00 0.00E+00 8.71E-06 1.99E-06 Average Release Rate for Period 0.00E+00 0.00E+00 1.10E-06 2.50E-07 (uCi/sec) 8

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Table 7 - Particulates Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 0.00E+00 0.00E+00 0.00E+00 2.30E-04 Average Release Rate for Period 0.00E+00 0.00E+00 0.00E+00 2.89E-05 (uCi/sec)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate for Period 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (uCi/sec)

Table 8 - Tritium Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 2.77E+00 2.60E+00 4.63E+00 4.99E+00 Average Release Rate for Period 3.53E-01 3.31E-01 5.83E-01 6.28E-01 (uCi/sec)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 3.85E+00 5.68E+00 5.06E+00 2.71E+00 Average Release Rate for Period 4.90E-01 7.23E-01 6.37E-01 3.41E-01 (uCi/sec)

Table 9 - Carbon-14 Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 2.11E+00 2.13E+00 1.99E+00 3.99E-01 Average Release Rate for Period 2.68E-01 2.71E-01 2.50E-01 5.02E-02 (uCi/sec)

ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Release (Curies) 2.54E+00 2.88E+00 2.85E+00 2.09E+00 Average Release Rate for Period 3.23E-01 3.66E-01 3.59E-01 2.63E-01 (uCi/sec) 9

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Table 10 - Gaseous Effluents Dose Receptor with Highest Single Organ Dose ANO-1 Dose to Organ (mrem)

Bone 1.83E-01 Liver 1.03E-01 Thyroid 1.81E-01 Kidney 1.03E-01 Lung 1.03E-01 GI-Li 1.03E-01 Skin 2.57E-05 Total Body 1.03E-01 ANO-2 Dose to Organ (mrem)

Bone 2.86E-01 Liver 1.33E-01 Thyroid 1.36E-01 Kidney 1.33E-01 Lung 1.33E-01 GI-Li 1.33E-01 Skin 1.60E-07 Total Body 1.33E-01 The highest single organ dose is 2.86E-01 mrem to the bone between ANO-1&2. This is 1.91%

of the federal limit of 15 mrem specified in 10 CFR 50, Appendix I. (The ANO 1&2 ODCM requires maximum receptor dose calculation for releases of I-131, I-133, H-3, and particulates with half-lives greater than 8 days; for these isotopes, the thyroid is the highest dose organ.

When C-14 is added, bone becomes the highest dose organ.)

In addition, gamma and beta air dose at the site boundary due to noble gases was calculated.

In 2016, the highest gamma air dose was 7.73E-02 mrad, 0.77% of the 10 mrad annual limit; highest beta air dose in 2016 was 2.73E-02 mrad, 0.14% of the 20 mrad annual limit.

Summary Discussion:

The highest single organ dose is 2.86E-01 mrem to the bone. This is 1.91% of the federal limit of 15 mrem specified in 10 CFR 50, Appendix I. (The ANO-1&2 ODCM requires maximum receptor dose calculation for releases of I-131, I-133, H-3, and particulates with half-lives greater than 8 days; for these isotopes, the thyroid is the highest dose organ. When C-14 is added, bone becomes the highest dose organ. In 2016, the highest gamma air dose was 7.73E-02 mrad, 0.77% of the 10 mrad annual limit; highest beta air dose in 2016 was 2.73E-02 mrad, 0.14% of the 20 mrad annual limit.

10

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Title 40, Part 190 of the Code of Federal Regulations (CFR) requires that dose to an individual in the unrestricted area from the uranium fuel cycle, including direct radiation dose, be limited to 25 mrem/year to the total body/other organs and 75 mrem/year to the thyroid. During 2016, there was no direct radiation dose attributed to the operation of ANO 1&2 beyond the site boundary, based on analysis of offsite TLD readings. Based on Dose Summary Table (Page 42) located in Appendix A, the offsite dose due to effluents for ANO-1&2 is 1.14% and 0.43% of 40 CFR 190 limits for the total body and thyroid, respectively. Therefore, ANO-1&2 was in compliance with 40 CFR 190 in 2016. Potential dose to visitors at ANO-1&2 due to all radioactive effluents, including noble gases, was also calculated. The ODCM considers persons visiting the ANO-1&2 Training Center (8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months a day for 52 weeks). Using ODCM assumptions about these categories of visitors, the maximum potential dose to a visitor to ANO-1&2 in 2016 was 7.68E-02 mrem to the maximally exposed organ (thyroid) and 6.72E-02 mrem to the total body. These doses are below the annual maximum offsite doses due to gaseous effluents shown in Dose Summary Table (Page 42), and are very small fractions of the 100 mrem/year limit for individual members of the public due to licensed operation of the plant provided in 10 CFR 20.1301.

4.

SUMMARY

OF RADIOACTIVE WASTE SHIPMENTS:

The radioactivity and volume of ANO solid waste shipped offsite is summarized in the following table:

Table 10 - ANO-1 Waste Shipped Offsite Type of Waste Units 12 Month Period Est. activity error, %

Resins, Filters, and Cubic meters 4.67E+01

+/- 25 Evaporator Bottoms Curies 8.28E+01 Dry compressible Cubic meters 4.42E+02 waste, contaminated +/- 25 equipment Curies 1.65E+00 Irradiated Cubic meters 0.00E+00

+/- 25 components Curies 0.00E+00 Cubic meters 0.00E+00 Other +/- 25 Curies 0.00E+00 11

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Table 11 - ANO-2 Waste Shipped Offsite Type of Waste Units 12 Month Period Est. activity error, %

Resins, Filters, and Cubic meters 4.78E+01

+/- 25 Evaporator Bottoms Curies 2.30E+01 Dry compressible Cubic meters 0.00E+00 waste, contaminated +/- 25 equipment Curies 0.00E+00 Irradiated Cubic meters 0.00E+00

+/- 25 components Curies 0.00E+00 Cubic meters 0.00E+00 Other +/- 25 Curies 0.00E+00 Table 12 - ANO-Common Waste Shipped Offsite Type of Waste Units 12 Month Period Est. activity error, %

Resins, Filters, and Cubic meters 2.55E+00

+/- 25 Evaporator Bottoms Curies 2.19E-03 Dry compressible Cubic meters 4.94E+02 waste, contaminated +/- 25 equipment Curies 1.34E+00 Irradiated Cubic meters 0.00E+00

+/- 25 components Curies 0.00E+00 Cubic meters 1.43E+01 Other +/- 25 Curies 2.30E-01 12

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Table 13 - ANO 1 Total Waste Shipped Number of Shipments Mode of Transportation Destination 11 Hittman Transport Bear Creek Operations 5 (2 shared with ANO-2) Hittman Transport Gallaher Road Operations 1 Hittman Transport Erwin Resin Solutions 1 Landstar Ranger Bear Creek Operations Total ANO-1 Shipments 18 Table 14 - ANO 2 Total Waste Shipped Number of Shipments Mode of Transportation Destination 3 (2 shared with ANO-1) Hittman Transport Gallaher Road Operations Total ANO-2 Shipments 3 Table 15 - ANO 1 & 2 (Common) Total Waste Shipped Number of Shipments Mode of Transportation Destination 19 Hittman Transport Bear Creek Operations 1 CAST Bear Creek Operations 1 Landstar Ranger Bear Creek Operations Total ANO-Common 21 Shipments Total Offsite Shipments 40 13

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

5. ADDITIONAL REQUIRED INFORMATION APPENDICES Appendix A, Effluent and Radioactive Waste Data, provides more detailed data on radiological effluents and radioactive waste shipments. Appendix B contains a description of the ANO-1&2 Integrated Groundwater Protection Program, 2016 sampling data for this program, and a discussion of sampling results. Appendix C contains meteorological joint frequency distributions of wind speed and wind direction by atmospheric stability class, for all of 2016. Appendix D contains the revised ODCM.

ODCM REVISION In accordance with ANO-1&2 TSs, changes to the ODCM shall be included in the ARERR for the period in which the change(s) was made effective.

The ODCM was revised two times during 2016 to include the following:

Rev 026 (June 27, 2016)

Changed location of control broadleaf vegetation sample site from current location at intersection of AR Highways 27 and 154 to within the Ozark National Forest at the intersection of Forest Service Roads 36 and 1618A. The change was performed due to forest and broadleaf eradication of previous control location.

Rev 027 (November 29, 2016)

Basis (B) 2.5.1, Radiological Environmental Monitoring, background data is updated to include explanation for sample location choice associated with air station #2. Revised explanation for air station samples in highest D/Q and also in the vicinity of a community.

Defined community as it relates to this location.

PROCESS CONTROL PROGRAM REVISIONS As required by ODCM Section 5.0, a description of changes made to the Entergy fleet Process Control Program (EN-RW-105) shall be included in the ARERR for the period in which the change was made effective.

There were no changes to EN-RW-105, Process Control Program, for the year 2016.

ODCM MONITORS OUT OF SERVICE There was one radiation monitor (radmonitor) out-of-service for greater than 30 days which requires reporting with the ARERR. See below for details.

On December 26, 2015, SPING-4 (ANO-1 Emergency Piping Penetration Room Ventilation Radmonitor) noble gas channels (Channels 5, 7, and 9) were declared out-of-service due to spurious alarms (reference CR-ANO-C-05096). Parts for repair of SPING-4 are obsolete and require refurbishment to repair Channel 5. In this instance, the SPING was thoroughly checked and returned to Chemistry to place back in-service. SPING-4 is considered an applicable 14

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 radiation monitor due to the auto-start function of the ventilation fans in the event pressure within the room gets too high. SPING-4 was returned to service on February 2, 2016. During the out-of-service time from December 26, 2015, to February 2, 2016, the SPING-4 ventilation fan ran for ~5.50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months for maintenance run of the fan. This time period is the only time gaseous effluents were being released via this pathway. Alternate sampling apparatus was installed during release via this pathway to ensure effluents being released were within federal limits. There were no samples during this period that indicated release of any radioactive effluents. Currently, ANO is upgrading the ventilation stack monitors, which is scheduled to be completed by the end of 2018 to reduce out-of-service time for all stack monitors. (reference CR-ANO-1-2016-00363, for monitors out-of-service > 30 days.)

OUTSIDE TEMPORARY TANKS There were no temporary tanks utilized in 2016 for the purpose of storing liquid radwaste.

MAJOR CHANGES TO RADIOACIVE WASTE SYSTEMS There were no major changes to radioactive waste systems in 2016.

ABNORMAL RADIOLOGICAL RELEASES There were no abnormal (e.g. unplanned) releases for ANO-1 or ANO-2 in 2016.

ERRATA/CORRECTIONS TO PREVIOUS ARERRs No prior corrections are required.

LLD LEVELS In accordance with ODCM, Appendix 1, lower limits of detection (LLDs) higher than required shall be documented in the ARERR:

During 2016, there were no LLDs higher than required by the ODCM.

15

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Appendix A Effluent and Radioactive Waste Data 16

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 REGULATORY LIMITS FOR RADIOACTIVE EFFLUENTS The ODCM contains the limits to which ANO must adhere. Because of the "as low as reasonably achievable" (ALARA) philosophy at ANO, actions are taken to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from both ANO-1&2 is considerably below the ODCM limits. This data reveals that the radioactive effluents have an overall minimal dose contribution to the surrounding environment.

The following are the limits required by the ODCM:

A. Gaseous Effluents

1. Dose rate due to radioactive materials released in gaseous effluent to unrestricted areas shall be limited to the following:

a. Noble gases Less than or equal to 500 mrem/year to the total body Less than or equal to 3000 mrem/year to the skin

b. Iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days Less than or equal to 1500 mrem/yr to any organ

2. Dose - Noble Gases Quarterly Less than or equal to 5 mrads gamma Less than or equal to 10 mrads beta Yearly Less than or equal to 10 mrads gamma Less than or equal to 20 mrads beta

3. Dose - Iodine-131, Tritium, and Radionuclides in Particulate Form Quarterly Less than or equal to 7.5 mrem to any organ Yearly Less than or equal to 15 mrem to any organ 17

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 B. Liquid Effluents

1. Concentration The concentration of radioactive material released to the discharge canal shall be limited to the concentration specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0E-4 microcuries/ml.

2. Dose Quarterly Less than or equal to 1.5 mrem total body Less than or equal to 5 mrem critical organ Yearly Less than or equal to 3 mrem total body Less than or equal to 10 mrem critical organ MEASUREMENTS APPROXIMATIONS OF TOTAL ACTIVITY IN RADIOACTIVE EFFLUENTS As required by NRC Regulatory Guide 1.21, this section describes the methods used to measure the total radioactivity in effluent releases and to estimate the overall errors associated with these measurements.

A. GASEUOUS EFFLUENTS ANO continuously releases gases and other activation products through a total of ten ventilation pathways. There are additional Waste Gas tanks that allow for further decay of high activity short-lived gases. Weekly a release permit is generated for the prior weeks release through the ventilation pathways as a batch release. This is done due to a known volume of gases. Primarily tritium is released continuously, while the remaining contributors, (i.e. fission gases, radioiodines, particulates) are normally only released for such activities as a refueling outage or plant transients.

I. FISSION AND ACTIVATION GASES Samples are obtained from each of the ten plant radiation monitors (SPINGs) which continuously monitor the ventilation exhaust points. The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples. The summary values reported are the sums of all fission and activation gases quantified at all monitored release points.

18

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 II. RADIOIODINES Samples are obtained from each of the ten plant radiation monitors (SPINGs) which continuously monitor the ten ventilation exhaust points. The radioiodines are entrained on charcoal and then quantified by gamma spectroscopy analysis. For each sample, the duration of sampling and continuous flow rate through the charcoal are used in determining the concentration of radioiodines. From the flow rate of the ventilation system, a rate of release can be determined. The summary values reported are the sums of all radioiodines quantified at all monitored release points.

III. PARTICULATES Samples are obtained from each of the ten plant effluent radiation monitors (SPINGs) which continuously monitor the ten ventilation exhaust points. The particulates are collected on a filter and then quantified by gamma spectroscopy analysis. For each sample, the duration of sampling and the continuous flow rate through the filter are used in determining the concentration of particulates. From the flow rate of the ventilation system, a rate of release can be determined. Quarterly, the filters from each ventilation release point are composited and then radiochemically separated and analyzed for strontium (Sr)-89/90 and iron (Fe)-55. The summary values reported are the sums of all particulates quantified at all monitored release points.

IV. TRITIUM Samples are obtained from each of the ten plant effluent radiation monitors (SPINGs) which continuously monitor the ten ventilation exhaust points. The sample is passed a calcium chloride desiccant. The sample is then distilled and the water collected is analyzed for tritium using liquid scintillation counting techniques. For each sample, the duration of sample and sample flow rate is used to determine the concentration. From the flow rate of the ventilation system, a release rate can be determined. The summary values reported are the sums of all tritium quantified at all monitored release points.

V. GROSS ALPHA The gaseous particulate samples are collected and sent to Teledyne for gross alpha analysis. Permits are updated accordingly in the presence of gross alpha.

VI. CARBON-14 Carbon-14 releases are calculated using a method published by the Electric Power Research Institute in December 2010. Plant rated thermal power and monthly capacity factors were used in the calculation of quarterly releases. Release rates are calculated using the total curies divided by total seconds in each applicable quarter.

19

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 B. LIQUID EFFLUENTS The liquid radwaste processing system and the liquid effluent monitoring system are described in ANO-1&2 Safety Analysis Report (SAR). Most liquid releases are performed as batch release. Gamma spec and tritium samples are analyzed prior to the release to quantify the release.

There are two continuous release streams, Unit 1&2 Turbine Building Sump are sampled daily for gamma spec and tritium daily. A weekly release is performed for these release streams.

C. STATISTICAL MEASURMENT UNCERTAINTIES The statistical uncertainty of the measurements in this section have been estimated, calculated using the square root of the sum of the squares for estimates in each area and summarized in the following table:

Measurement Type Sample Type One Sigma Uncertainty Fission and Activation Gases Gaseous 24%

Radioiodines Gaseous 20%

Particulates Gaseous 22%

Tritium Gaseous 21%

Gross Alpha Gaseous 31%

Fission and Activation Products Liquid 21%

Tritium Liquid 12%

Gross Alpha Liquid 27%

Volume of Waste Release Liquid 8%

Volume of Dilution Water Liquid 10%

LIQUID RELEASES As required by Regulatory Guide 1.21, Revision 1, Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, a summary of data for liquid and gas releases is provided in the ARERR.

Calculated offsite doses are compared with Nuclear Regulatory Commission limits, and these limits are summarized in Appendix A. Appendix A also contains a detailed discussion of the methods used to determine quantities of radioactivity released in effluents, the types of solid radioactive waste shipped offsite, as well as tables of individual radionuclides released in effluents and shipped as solid radioactive waste.

The summary of liquid and gaseous effluents for both ANO-1&2 is as follows.

20

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 REPORT CATEGORY: LIQUID CONTINUOUS AND BATCH RELEASES TABLE 5A ANO-1 Batch Continuous Number of releases 124 35 Total time for all releases 2.32E+04 2.43E+05 (minutes)

Maximum time for a release 8.65E+02 1.03E+04 (minutes)

Average time for a release 1.87E+02 6.94E+03 (minutes)

Minimum time for a release 7.00E+00 1.23E+03 (minutes) 21

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 2A REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 A. Fission and Activation Products ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 5.07E-02 1.38E-02 4.13E-02 4.53E-02 21 Avg. Concentration 1.54E-10 3.75E-11 1.09E-10 2.70E-10 (uCi/ml)

Percent of Limit 5.15E-01 1.25E-01 3.63E-01 8.98E-01 B. Tritium ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 1.52E+02 1.57E+02 2.07E+02 3.87E+01 12 Avg. Concentration 4.62E-07 4.25E-07 5.46E-07 2.30E-07 (uCi/ml)

Percent of Limit 1.54E-02 1.42E-02 1.82E-02 7.68E-03 C. Dissolved and Entrained Gases Summary ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 1.35E-02 1.75E-02 1.00E-01 1.05E-02 22 Avg. Concentration 4.13E-11 4.73E-11 2.64E-10 6.26E-11 (uCi/ml)

Percent of Limit 2.06E-05 2.36E-05 1.32E-04 3.13E-05 D. Gross Alpha Activity ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 27 Avg. Concentration 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (uCi/ml)

E. Volumes Uncertainty ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4

(%)

Primary Liquid Release 1.53E+07 1.26E+07 5.72E+06 3.54E+06 8 Volume (liters)

Dilution Volume (liters) 3.28E+11 3.69E+11 3.79E+11 1.68E+11 10 22

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 2B REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Products Na-24 CURIES 3.453E-04 5.393E-04 6.079E-04 0.000E+00 Cr-51 CURIES 4.575E-05 0.000E+00 2.486E-04 6.391E-03 Mn-54 CURIES 2.061E-04 1.287E-05 2.766E-04 3.586E-04 Fe-55 CURIES 3.583E-03 3.304E-03 1.477E-03 4.744E-03 Fe-59 CURIES 0.000E+00 0.000E+00 0.000E+00 7.050E-04 Co-58 CURIES 2.332E-03 4.532E-04 3.884E-03 6.747E-03 Co-60 CURIES 1.972E-03 1.611E-03 7.251E-03 8.577E-03 Sr-85 CURIES 1.011E-05 1.866E-05 5.966E-05 0.000E+00 Sr-92 CURIES 0.000E+00 0.000E+00 7.465E-06 1.092E-05 Y-91m CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Zr-95 CURIES 1.784E-04 4.184E-05 4.314E-04 1.826E-03 Nb-95 CURIES 3.396E-04 1.503E-04 9.842E-04 3.697E-03 Nb-97 CURIES 0.000E+00 0.000E+00 0.000E+00 5.224E-06 Mo-99 CURIES 0.000E+00 3.987E-05 2.219E-05 0.000E+00 Tc-99m CURIES 0.000E+00 0.000E+00 2.259E-05 0.000E+00 Ru-105 CURIES 1.991E-05 2.466E-05 2.297E-05 0.000E+00 Ag-110m CURIES 6.687E-04 4.623E-04 1.030E-03 2.571E-03 Sb-122 CURIES 0.000E+00 0.000E+00 0.000E+00 2.441E-05 Sb-124 CURIES 8.859E-05 1.947E-04 6.514E-05 3.975E-03 Sb-125 CURIES 0.000E+00 5.124E-04 2.137E-04 1.066E-03 I-131 CURIES 5.851E-05 0.000E+00 4.128E-04 2.652E-04 I-133 CURIES 0.000E+00 0.000E+00 1.704E-04 0.000E+00 I-134 CURIES 0.000E+00 0.000E+00 0.000E+00 8.483E-05 Cs-134 CURIES 2.413E-02 9.008E-04 1.322E-02 2.180E-03 Cs-136 CURIES 1.949E-06 2.679E-06 0.000E+00 1.001E-05 Cs-137 CURIES 1.611E-02 1.824E-03 1.078E-02 1.918E-03 Cs-138 CURIES 0.000E+00 0.000E+00 2.096E-05 0.000E+00 W-187 CURIES 0.000E+00 0.000E+00 0.000E+00 5.362E-05 Total CURIES 5.009E-02 1.009E-02 4.121E-02 4.521E-02 Tritium H-3 CURIES 1.514E+02 1.556E+02 2.070E+02 3.870E+01 Dissolved and Entrained Gases Kr-85 CURIES 2.328E-03 6.888E-03 1.377E-02 0.000E+00 Xe-131m CURIES 2.265E-04 1.579E-04 0.000E+00 0.000E+00 Xe-133 CURIES 1.099E-02 1.002E-02 8.646E-02 1.051E-02 Total CURIES 1.355E-02 1.706E-02 1.002E-01 1.051E-02

In the above table, 0.00E+00 is used when no radioactivity was detected and represents < Minimum Detectable Activity 23

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 2B REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 12-31-2016 CONTINUOUS RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Products Na-24 CURIES 0.000E+00 8.872E-05 0.000E+00 0.000E+00 Mn-54 CURIES 0.000E+00 1.952E-05 0.000E+00 0.000E+00 Co-58 CURIES 0.000E+00 1.141E-05 0.000E+00 0.000E+00 Co-60 CURIES 0.000E+00 5.518E-05 0.000E+00 0.000E+00 Cs-134 CURIES 3.390E-04 2.091E-03 6.052E-05 3.857E-05 Cs-137 CURIES 2.332E-04 1.469E-03 5.893E-05 3.739E-05 Total CURIES 5.721E-04 3.735E-03 1.194E-04 7.596E-05 Tritium H-3 CURIES 2.488E-01 1.225E+00 1.206E-02 5.374E-03 Dissolved and Entrained Gases Kr-88 CURIES 0.000E+00 1.633E-04 0.000E+00 0.000E+00 Xe-133 CURIES 0.000E+00 2.251E-04 0.000E+00 0.000E+00 Total CURIES 0.000E+00 3.884E-04 0.000E+00 0.000E+00

In the above table, 0.00E+00 is used when no radioactivity was detected and represents < Minimum Detectable Activity 24

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 REPORT CATEGORY: LIQUID CONTINUOUS AND BATCH RELEASES TABLE 5A ANO-2 Batch Continuous Number of releases 26 0 Total time for all releases 1.00E+04 0 (minutes)

Maximum time for a release 9.84E+02 0 (minutes)

Average time for a release 3.84E+02 0 (minutes)

Minimum time for a release 1.84E+02 0 (minutes) 25

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 2A REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 A. Fission and Activation Products ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 2.17E-03 4.26E-03 3.74E-03 8.16E-03 21 Avg. Concentration 6.60E-12 1.16E-11 9.86E-12 4.86E-11 (uCi/ml)

Percent of Limit 2.20E-02 3.85E-02 3.29E-02 1.62E-01 B. Tritium ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 6.76E+01 1.07E+02 6.72E+01 2.87E+02 12 Avg. Concentration 2.06E-07 2.91E-07 1.77E-07 1.71E-06 (uCi/ml)

Percent of Limit 6.87E-03 9.71E-03 5.91E-03 5.69E-02 C. Dissolved and Entrained Gases Summary ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 7.43E-04 1.24E-04 6.75E-04 2.08E-03 22 Avg. Concentration 2.26E-12 3.36E-013 1.78E-12 1.24E-11 (uCi/ml)

Percent of Limit 1.13E-06 1.68E-07 8.90E-07 6.20E-06 D. Gross Alpha Activity ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 27 Avg. Concentration 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (uCi/ml)

E. Volumes ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Primary Liquid Release 4.97E+05 5.15E+05 2.48E+05 7.54E+05 8 Volume (liters)

Dilution Volume (liters) 3.28E+11 3.69E+11 3.79E+11 1.68E+11 10 26

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 2B REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Products Mn-54 CURIES 6.957E-05 3.886E-05 0.000E+00 0.000E+00 Fe-55 CURIES 0.000E+00 1.494E-03 2.041E-03 2.197E-03 Fe-59 CURIES 2.727E-05 0.000E+00 0.000E+00 1.368E-04 Co-58 CURIES 1.504E-04 1.256E-04 1.348E-05 4.759E-05 Co-60 CURIES 6.746E-04 3.415E-04 3.375E-05 4.328E-05 Zr-95 CURIES 0.000E+00 4.013E-06 0.000E+00 0.000E+00 Nb-94 CURIES 0.000E+00 0.000E+00 0.000E+00 1.387E-06 Nb-95 CURIES 0.000E+00 1.251E-05 0.000E+00 0.000E+00 Ag-110m CURIES 8.469E-06 1.031E-05 0.000E+00 0.000E+00 Sb-124 CURIES 8.936E-05 3.796E-04 5.033E-05 2.770E-05 Sb-125 CURIES 8.073E-04 1.031E-03 4.902E-04 1.069E-03 Cs-134 CURIES 1.264E-05 3.684E-05 7.540E-05 2.704E-04 Cs-137 CURIES 3.267E-04 7.904E-04 1.032E-03 4.368E-03 Total CURIES 2.166E-03 4.264E-03 3.736E-03 8.162E-03 Tritium H-3 CURIES 6.765E+01 1.075E+02 6.723E+01 2.870E+02 Dissolved and Entrained Gases Xe-133 CURIES 7.428E-04 1.239E-04 6.748E-04 2.085E-03 Total CURIES 7.428E-04 1.239E-04 6.748E-04 2.085E-03

In the above table, 0.00E+00 is used when no radioactivity was detected and represents < Minimum Detectable Activity 27

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 2B REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 CONTINUOUS RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Products NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Tritium H-3 CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Dissolved and Entrained Gases NONE CURIES 0.000E+00 2.251E-04 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00

In the above table, 0.00E+00 is used when no radioactivity was detected and represents <Minimum Detectable Activity 28

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

4.

SUMMARY

OF GASEOUS EFFLUENT DATA As required by Regulatory Guide 1.21, Revision 1, a summary of data for gaseous releases is provided in the ARERR. At ANO only ground level releases are used to maintain a conservative does estimate. The summary of gaseous effluents for both Unit 1 and Unit 2 is as follows:

ANO-1 REPORT CATEGORY: GASEOUS CONTINUOUS AND BATCH RELEASES TABLE 5B ANO-1 Batch Continuous Number of releases 106 0 Total time for all releases 8.43E+05 0 (minutes)

Maximum time for a release 4.46E+04 0 (minutes)

Average time for a release 7.95E+03 0 (minutes)

Minimum time for a release 4.00E+00 0 (minutes) 29

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 REPORT CATEGORY: ANNUAL GASEOUS CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 1A REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 A. Fission and Activation Gases ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 1.71E-01 1.25E+01 2.49E+00 24 Avg. Release Rate 0.00E+00 2.17E-02 1.57E+00 3.13E-01 (uCi/sec)

Percent of Limit 0.00E+00 3.05E-04 2.20E-02 4.39E-03 B. Iodines and Halogens ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 1.25E-05 1.87E-04 20 Avg. Release Rate 0.00E+00 0.00E+00 1.58E-06 2.35E-05 (uCi/sec)

Percent of Limit 0.00E+00 0.00E+00 4.50E-06 6.71E-05 C. Particulates ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 0.00E+00 2.30E-04 22 Avg. Release Rate 0.00E+00 0.00E+00 0.00E+00 2.89E-05 (uCi/sec)

Percent of Limit 0.00E+00 0.00E+00 0.00E+00 8.27E-05 D. Tritium ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 2.77E+00 2.60E+00 4.63E+00 4.99E+00 21 Avg. Release Rate 3.53E-01 3.31E-01 5.83E-01 6.28E-01 (uCi/sec)

Percent of Limit 4.94E-04 4.63E-04 8.163E-04 8.795E-04 E. Carbon-14 ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Release (Curies) 2.11E+00 2.13E+00 1.99E+00 3.99E-01 Avg. Release Rate 2.68E-01 2.71E-01 2.50E-01 5.02E-02 (uCi/sec)

F. Gross Alpha ANO-1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 31 30

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 REPORT CATEGORY: ANNUAL GASEOUS CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 1B GROUND RELEASE REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Gases Ar-41 CURIES 0.000E+00 0.000E+00 4.297E-03 0.000E+00 Kr-85 CURIES 0.000E+00 1.710E-01 9.097E-01 1.320E-01 Xe-133 CURIES 0.000E+00 0.000E+00 1.160E+01 2.358E+00 Xe-135 CURIES 0.000E+00 0.000E+00 7.856E-05 0.000E+00 Total CURIES 0.000E+00 1.710E-01 1.251E+01 2.490E+00 Iodines and Halogens I-131 CURIES 0.000E+00 0.000E+00 1.252E-05 1.866E-04 I-133 CURIES 0.000E+00 0.000E+00 8.174E-09 0.000E+00 Total CURIES 0.000E+00 0.000E+00 1.253E-05 1.866E-04 Particulates Sr-85 CURIES 0.000E+00 0.000E+00 0.000E+00 2.228E-04 Ag-110m CURIES 0.000E+00 0.000E+00 0.000E+00 7.265E-06 Total CURIES 0.000E+00 0.000E+00 0.000E+00 2.300E-04 Tritium H-3 CURIES 2.772E+00 2.599E+00 4.635E+00 4.994E+00 Gross Alpha NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00

In the above table, 0.00E+00 is used when no radioactivity was detected and represents < Minimum Detectable Activity 31

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 REPORT CATEGORY: ANNUAL GASEOUS CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 1B GROUND RELEASE REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 CONTINUOUS RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Products NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Tritium H-3 CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Dissolved and Entrained Gases NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00

In the above table, 0.00E+00 is used when no radioactivity was detected and represents < Minimum Detectable Activity 32

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: GASEOUS CONTINUOUS AND BATCH RELEASES TABLE 5B ANO-2 Batch Continuous Number of releases 103 0 Total time for all releases 8.19E+05 0 (minutes)

Maximum time for a release 1.06E+04 0 (minutes)

Average time for a release 7.95E+03 0 (minutes)

Minimum time for a release 5.70E+01 0 (minutes) 33

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: ANNUAL GASEOUS CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 1A REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 A. Fission and Activation Gases ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 1.07E+00 1.21E-05 1.08E-01 1.20E+01 24 Avg. Release Rate 1.36E-01 1.54E-06 1.36E-02 1.50E+00 (uCi/sec)

Percent of Limit 1.90E-03 2.15E-08 1.91E-04 2.106E-02 B. Iodines and Halogens ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 8.71E-06 1.99E-06 20 Avg. Release Rate 0.00E+00 0.00E+00 1.10E-06 2.50E-07 (uCi/sec)

Percent of Limit 0.00E+00 0.00E+00 3.13E-06 7.14E-07 C. Particulates ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 22 Avg. Release Rate 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (uCi/sec)

Percent of Limit 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 3.85E+00 5.68E+00 5.06E+00 2.71E+00 21 Avg. Release Rate 4.90E-01 7.23E-01 6.37E-01 3.41E-01 (uCi/sec)

Percent of Limit 6.86E-04 1.01E-03 8.91E-04 4.78E-04 E. Carbon-14 ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Release (Curies) 2.54E+00 2.88E+00 2.85E+00 2.09E+00 Avg. Release Rate 3.23E-01 3.66E-01 3.59E-01 2.63E-01 (uCi/sec)

E. Gross Alpha ANO-2 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty (%)

Total Release (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 31 34

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: ANNUAL GASEOUS CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 1B GROUND RELEASE REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Gases Ar-41 CURIES 1.062E+00 0.000E+00 8.939E-02 1.196E+01 Kr-85 CURIES 0.000E+00 0.000E+00 3.262E-03 0.000E+00 Xe-133 CURIES 7.500E-03 1.208E-05 1.584E-02 0.000E+00 Total CURIES 1.069E+00 1.208E-05 1.085E-01 1.196E+01 Iodines and Halogens I-131 CURIES 0.000E+00 0.000E+00 7.961E-06 1.987E-06 I-133 CURIES 0.000E+00 0.000E+00 7.535E-07 0.000E+00 Total CURIES 0.000E+00 0.000E+00 8.714E-06 1.987E-06 Particulates NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Tritium H-3 CURIES 3.855E+00 5.681E+00 5.060E+00 2.714E+00 Gross Alpha NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00

In the above table, 0.00E+00 is used when no radioactivity was detected and represents < Minimum Detectable Activity 35

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 REPORT CATEGORY: ANNUAL GASEOUS CONTINUOUS AND BATCH RELEASES REG. GUIDE 1.21 TABLE 1B GROUND RELEASE REPORTING PERIOD: STARTING: 1-JAN-2016 ENDING: 31-DEC-2016 CONTINUOUS RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 3 QUARTER 4 Fission and Activation Products NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Tritium H-3 CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Dissolved and Entrained Gases NONE CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Total CURIES 0.000E+00 0.000E+00 0.000E+00 0.000E+00

In the above table, 0.00E+00 is used when no radioactivity was detected and represents <Minimum Detectable Activity 36

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 RADIATION DOSES The following is a summary of the annual radiation doses due to radiological effluents during 2016 calculated in accordance with the ODCM.

ANO-1 Liquid Radwaste Effluents Dose Limits (mrem): Total Body = 1.5/Qtr 3/Yr, Organs = 5/Qtr 10/Yr A. Critical Organ Dose Bone Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.84E-02 2.61E-03 9.28E-03 5.39E-03 3.57E-02 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 3.69E-01 5.22E-02 1.86E-01 1.08E-01 3.57E-01 Liver Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 3.55E-02 4.87E-03 1.76E-02 1.01E-02 6.80E-02 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 7.10E-01 9.75E-02 3.51E-01 2.01E-01 6.80E-01 Thyroid Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 2.65E-04 2.24E-04 4.51E-04 4.87E-04 1.43E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 5.31E-03 4.48E-03 9.02E-03 9.74E-03 1.43E-02 Kidney Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.18E-02 1.76E-03 5.96E-03 3.39E-03 2.29E-02 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 2.37E-01 3.52E-02 1.19E-01 6.79E-02 2.29E-01 Lung Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 4.09E-03 7.39E-04 2.16E-03 1.27E-03 8.26E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 8.18E-02 1.48E-02 4.33E-02 2.53E-02 8.26E-02 GI-Li Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 9.71E-04 3.43E-04 7.58E-04 2.04E-03 4.11E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 1.94E-02 6.87E-03 1.52E-02 4.08E-02 4.11E-02 B. Total Body Total Body Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 2.72E-02 3.69E-03 1.34E-02 7.64E-03 5.19E-02 Limit (mrem) 1.50 1.50 1.50 1.50 3.00 Percent of Limit 1.81E+00 2.46E-01 8.91E-01 5.10E-01 1.73E+00 37

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 Gaseous Radwaste Effluents Iodine, H-3, and Particulate (ITP) - Dose Limits (mrem) = 7.5/Qtr 15/Yr Noble Gas Air Dose Limits (mrad) = Gamma 5/Qtr 10/Yr, Beta 10/Qtr 20/Yr A. Critical Organ Dose Bone Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 0.00E+00 0.00E+00 1.88E-05 3.01E-04 3.20E-04 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 0.00E+00 0.00E+00 2.51E-04 4.02E-03 2.14E-03 Liver Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.22E-02 1.14E-02 2.04E-02 2.21E-02 6.62E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 1.63E-01 1.52E-01 2.72E-01 2.95E-01 4.41E-01 Thyroid Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.22E-02 1.14E-02 2.38E-02 1.17E-01 1.44E-01 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 1.63E-01 1.52E-01 3.17E-01 1.564E+00 9.59E-01 Kidney Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.22E-02 1.14E-02 2.04E-02 2.22E-02 6.63E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 1.63E-01 1.52E-01 2.72E-01 2.97E-01 4.42E-01 Lung Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.22E-02 1.14E-02 2.04E-02 2.20E-02 6.60E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 1.63E-01 1.52E-01 2.72E-01 2.94E-01 4.40E-01 GI-Li Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.22E-02 1.14E-02 2.04E-02 2.21E-02 6.61E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 1.63E-01 1.52E-01 2.72E-01 2.94E-01 4.41E-01 Skin Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 0.00E+00 0.00E+00 2.02E-07 2.55E-05 2.57E-05 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 0.00E+00 0.00E+00 2.69E-06 3.40E-04 1.71E-04 38

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 B. Total Body Total Body Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.22E-02 1.14E-02 2.04E-02 2.21E-02 6.61E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 1.63E-01 1.52E-01 2.72E-01 2.94E-01 4.41E-01 C. Noble Gas Gamma Air Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrad) 0.00E+00 1.87E-06 2.63E-03 5.29E-04 3.16E-03 Limit (mrad) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 0.00E+00 3.74E-05 5.26E-02 1.06E-02 3.16E-02 Beta Air Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrad) 0.00E+00 2.11E-04 8.86E-03 1.73E-03 1.08E-02 Limit (mrad) 10.00 10.00 10.00 10.00 20.00 Percent of Limit 0.00E+00 2.11E-03 8.86E-02 1.73E-02 5.40E-02 39

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 Liquid Radwaste Effluents Dose Limits (mrem): Total Body = 1.5/Qtr 3/Yr, Organs = 5/Qtr 10/Yr A. Critical Organ Dose Bone Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.78E-04 3.88E-04 5.01E-04 6.69E-03 7.76E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 3.56E-03 7.76E-03 1.00E-02 1.34E-01 7.76E-02 Liver Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 3.58E-04 6.93E-04 7.97E-04 1.07E-02 1.26E-02 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 7.16E-03 1.39E-02 1.594E-02 2.14E-01 1.26E-01 Thyroid Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.06E-04 1.51E-04 9.01E-05 1.25E-03 1.60E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 2.11E-03 3.03E-03 1.80E-03 2.51E-02 1.60E-02 Kidney Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.90E-04 3.33E-04 3.27E-04 4.44E-03 5.29E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 3.81E-03 6.66E-03 6.54E-03 8.88E-02 5.29E-02 Lung Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.34E-04 2.14E-04 1.72E-04 2.33E-03 2.85E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 2.67E-03 4.28E-03 3.44E-03 4.65E-02 2.85E-02 GI-Li Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.23E-04 1.71E-04 1.07E-04 1.47E-03 1.87E-03 Limit (mrem) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 2.45E-03 3.42E-03 2.14E-03 2.94E-02 1.87E-02 B. Total Body Total Body Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 2.74E-04 5.10E-04 5.61E-04 7.55E-03 8.90E-03 Limit (mrem) 1.50 1.50 1.50 1.50 3.00 Percent of Limit 1.83E-02 3.40E-02 3.74E-02 5.04E-01 2.97E-01 40

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 Gaseous Radwaste Effluents Iodine, H-3, and Particulate (ITP) - Dose Limits (mrem) = 7.5/Qtr 15/Yr Noble Gas Air Dose Limits (mrad) = Gamma 5/Qtr 10/Yr, Beta 10/Qtr 20/Yr A. Critical Organ Dose Bone Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 0.00E+00 0.00E+00 1.20E-05 2.99E-06 1.50E-05 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 0.00E+00 0.00E+00 1.60E-04 3.99E-05 9.97E-05 Liver Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.70E-02 2.50E-02 2.23E-02 1.19E-02 7.61E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 2.26E-01 3.33E-01 2.97E-01 1.59E-01 5.08E-01 Thyroid Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.70E-02 2.50E-02 2.44E-02 1.25E-02 7.89E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 2.26E-01 3.33E-01 3.26E-01 1.66E-01 5.26E-01 Kidney Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.70E-02 2.50E-02 2.23E-02 1.19E-02 7.62E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 2.26E-01 3.33E-01 2.97E-01 1.59E-01 5.08E-01 Lung Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.70E-02 2.50E-02 2.23E-02 1.19E-02 7.61E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 2.26E-01 3.33E-01 2.97E-01 1.59E-01 5.08E-01 GI-Li Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.70E-02 2.50E-02 2.23E-02 1.19E-02 7.61E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 2.26E-01 3.33E-01 2.97E-01 1.59E-01 5.08E-01 Skin Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 0.00E+00 0.00E+00 1.28E-07 3.20E-08 1.60E-07 Limit (mrem) 7.50 7.50 7.50 7.50 15.00 Percent of Limit 0.00E+00 0.00E+00 1.71E-06 4.26E-07 1.07E-06 41

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 B. Total Body Total Body Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrem) 1.70E-02 2.50E-02 2.23E-02 1.19E-02 7.61E-02 Limit (mrem) 7.50 7.50 7.50 7.50 15.0 Percent of Limit 2.26E-01 3.33E-01 2.97E-01 1.59E-01 5.08E-01 C. Noble Gas Gamma Air Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrad) 6.26E-03 2.70E-09 5.31E-04 7.05E-02 7.73E-02 Limit (mrad) 5.00 5.00 5.00 5.00 10.00 Percent of Limit 1.25E-01 5.40E-08 1.06E-02 1.41E+00 7.73E-01 Beta Air Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Dose (mrad) 2.21E-03 8.04E-09 2.01E-04 2.49E-02 2.73E-02 Limit (mrad) 10.00 10.00 10.00 10.00 20.00 Percent of Limit 2.21E-02 8.04E-08 2.01E-03 2.49E-01 1.37E-01 42

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

SUMMARY

OF DOSE TO MEMBERS OF THE PUBLIC (40CFR190 Radioactive Effluents Impact)

The following is a summary of the annual radiation dose to members of the public (in mrem) due to activities inside the site boundary.

BONE LIVER TBODY THYROID KIDNEY GI-LLI LUNG SKIN ANO-1 Gaseous Effluent Iodine/Tritium 3.20E-04 6.62E-02 6.61E-02 1.44E-01 6.63E-02 6.61E-02 6.60E-02 2.57E-05 Particulate Noble Gas 1.85E-03 6.20E-03 Carbon-14 1.83E-01 3.65E-02 3.65E-02 3.65E-02 3.65E-02 3.65E-02 3.65E-02 Liquid Effluent Fish 3.57E-02 6.80E-02 5.19E-02 1.43E-03 2.29E-02 4.11E-03 8.26E-03 0.00E+00 Sediment 1.12E-03 1.31E-03 Unit 1 Total 2.19E-01 1.71E-01 1.57E-01 1.82E-01 1.26E-01 1.07E-01 1.11E-01 7.51E-03 ANO-2 Gaseous Effluent Iodine/Tritium 1.50E-05 7.61E-02 7.61E-02 7.89E-02 7.62E-02 7.61E-02 7.61E-02 1.60E-07 Particulate Noble Gas 5.14E-02 8.24E-02 Carbon-14 2.86E-01 5.71E-02 5.71E-02 5.71E-02 5.71E-02 5.71E-02 5.71E-02 Liquid Effluent Fish 7.76E-03 1.26E-02 8.90E-03 1.60E-03 5.29E-03 1.87E-03 2.85E-03 0.00E+00 Sediment 1.02E-04 1.19E-04 Unit 2 Total 2.94E-01 1.46E-01 1.94E-01 1.38E-01 1.39E-01 1.35E-01 1.36E-01 8.25E-02 ANO Site Site Total 5.13E-01 3.17E-01 3.51E-01 3.20E-01 2.65E-01 2.42E-01 2.47E-01 9.01E-02 Limit (40CFR190) 25 25 25 75 25 25 25 25

% Limit 2.05E+00 1.27E+00 1.40E+00 4.27E-01 1.06E+00 9.68E-01 9.88E-01 3.60E-01 43

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

8. SOLID WASTE

SUMMARY

As required by Regulatory Guide 1.21, Revision 1, a summary of data for solid wastes shipped offsite is provided in the ARERR.

ANO-1&2 complies with the extensive federal regulations which govern radioactive waste shipments. Radioactive solid waste shipments from the ANO-1&2 site consist of waste generated during water treatment, radioactive trash, irradiated components, etc. Shipment destinations are either a licensed burial site or intermediate processing facilities. Waste shipped to intermediate processing facilities is shipped directly from these facilities to a licensed burial site after processing. The following tables contain estimates of major nuclide composition, by class of waste, of ANO-1&2 radwaste shipped offsite in 2016. The waste volumes shown in these tables are the volumes shipped, not the final volumes sent for burial after processing.

a. Resins, Filters and Evaporator Bottoms ANO-1 Waste Characterization ANO-1 Class A Isotope Percent Abundance Curies H-3 0.37% 8.55E-02 C-14 2.71% 6.25E-01 Mn-54 3.93% 9.07E-01 Fe-55 21.95% 5.06E+00 Co-57 0.09% 2.03E-02 Co-58 0.52% 1.20E-01 Co-60 46.85% 1.08E+01 Ni-59 0.07% 1.71E-02 Ni-63 20.34% 4.69E+00 Zn-65 0.49% 1.12E-01 Sr-89 0.00% 3.84E-05 Sr-90 0.04% 9.46E-03 Nb-95 0.00% 3.31E-05 Tc-99 0.28% 6.34E-02 Sb-125 0.26% 6.00E-02 I-129 0.05% 1.24E-02 Cs-134 0.15% 3.42E-02 Cs-137 1.89% 4.36E-01 Total Curies 2.31E+01 44

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 Class B Isotope Percent Abundance Curies H-3 0.10% 6.27E-02 Be-7 0.02% 1.27E-02 C-14 2.27% 1.36E+00 Mn-54 3.11% 1.86E+00 Fe-55 20.29% 1.22E+01 Co-57 0.08% 4.58E-02 Co-58 0.83% 4.97E-01 Co-60 41.08% 2.46E+01 Ni-59 0.12% 6.98E-02 Ni-63 22.61% 1.35E+01 Zn-65 0.47% 2.80E-01 Sr-89 0.00% 4.14E-04 Sr-90 0.06% 3.72E-02 Nb-95 0.00% 1.94E-04 Zr-95 0.00% 1.40E-03 Tc-99 0.02% 1.17E-02 Ag-110m 0.13% 7.53E-02 Sn-113 0.00% 6.33E-04 Sb-124 0.00% 2.68E-03 Sb-125 1.37% 8.23E-01 I-129 0.00% 1.66E-03 Cs-134 0.51% 3.08E-01 Cs-137 6.85% 4.10E+00 Ce-144 0.05% 3.02E-02 Pu-238 0.00% 1.87E-04 Am-241 0.00% 2.99E-05 Cm-242 0.00% 1.28E-06 Cm-243 0.00% 1.06E-04 Cm-244 0.00% 1.04E-04 Total Curies 5.99E+01 45

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-1 Total Isotope Percent Abundance Curies H-3 0.18% 1.48E-01 Be-7 0.02% 1.27E-02 C-14 2.40% 1.99E+00 Mn-54 3.34% 2.77E+00 Fe-55 20.75% 1.72E+01 Co-57 0.08% 6.61E-02 Co-58 0.74% 6.17E-01 Co-60 42.69% 3.54E+01 Ni-59 0.10% 8.69E-02 Ni-63 21.98% 1.82E+01 Zn-65 0.47% 3.92E-01 Sr-89 0.00% 4.52E-04 Sr-90 0.06% 4.67E-02 Nb-95 0.00% 2.27E-04 Zr-95 0.00% 1.40E-03 Tc-99 0.09% 7.51E-02 Ag-110m 0.09% 7.53E-02 Sn-113 0.00% 6.33E-04 Sb-124 0.00% 2.68E-03 Sb-125 1.06% 8.83E-01 I-129 0.02% 1.41E-02 Cs-134 0.41% 3.42E-01 Cs-137 5.47% 4.54E+00 Ce-144 0.04% 3.02E-02 Pu-238 0.00% 1.87E-04 Am-241 0.00% 2.99E-05 Cm-242 0.00% 1.28E-06 Cm-243 0.00% 1.06E-04 Cm-244 0.00% 1.04E-04 Total Curies 8.29E+01 Notes:

There were zero Class C shipments.

The values listed for H-3, C-14, Tc-99 and I-129 in the above table contain LLD values calculated and reported on Manifests.

46

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 Waste Characterization ANO-2 Class A Isotope Percent Abundance Curies H-3 0.34% 1.07E-02 C-14 0.34% 1.09E-02 Co-60 0.00% 3.00E-05 Sr-89 89.79% 2.84E+00 Sr-90 9.01% 2.85E-01 Tc-99 0.34% 1.07E-02 I-129 0.06% 1.82E-03 Cs-137 0.12% 3.91E-03 Total Curies 3.16E+00 ANO-2 Class B Isotope Percent Abundance Curies H-3 0.39% 7.81E-02 C-14 0.40% 8.01E-02 Co-60 0.00% 1.85E-04 Sr-89 85.61% 1.70E+01 Sr-90 13.14% 2.61E+00 Tc-99 0.38% 7.56E-02 I-129 0.04% 7.48E-03 Cs-137 0.04% 7.04E-03 Total Curies 1.99E+01 47

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-2 Total Isotope Percent Abundance Curies H-3 0.39% 8.88E-02 C-14 0.40% 9.10E-02 Co-60 0.00% 2.15E-04 Sr-89 86.18% 1.98E+01 Sr-90 12.58% 2.90E+00 Tc-99 0.38% 8.63E-02 I-129 0.04% 9.30E-03 Cs-137 0.04% 1.09E-02 Total Curies 2.30E+01 Notes:

There were zero Class C shipments.

The values listed for H-3, C-14, Tc-99 and I-129 in the above table contain LLD values calculated and reported on Manifests.

ANO-Common Waste Characterization ANO-Common Class A/Total Isotope Percent Abundance Curies H-3 24.99% 4.01E-03 C-14 22.25% 3.57E-03 Co-60 0.11% 1.76E-05 Tc-99 32.59% 5.23E-03 I-129 6.54% 1.05E-03 Cs-137 13.52% 2.17E-03 Total Curies 1.60E-02 Notes:

There were zero Class B & C shipments.

The values listed for H-3, C-14, Tc-99 and I-129 in the above table contain LLD values calculated and reported on Manifests.

48

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

b. Dry compressible waste, contaminated equipment, etc.

ANO-1 Waste Characterization ANO-1 Class A/Total Isotope Percent Abundance Curies H-3 2.77% 4.74E-02 C-14 0.64% 1.10E-02 Mn-54 0.25% 4.36E-03 Fe-55 8.41% 1.44E-01 Co-58 1.62% 2.77E-02 Co-60 8.82% 1.51E-01 Ni-63 63.07% 1.08E+00 Nb-95 0.54% 9.27E-03 Tc-99 1.04% 1.78E-02 Sb-125 1.37% 2.34E-02 I-129 0.01% 2.07E-04 Cs-134 1.12% 1.92E-02 Cs-137 10.34% 1.77E-01 Total Curies 1.71E+00 Notes:

There were zero Class B & C shipments.

The values listed for H-3, C-14, Tc-99 and I-129 in the above table contain LLD values calculated and reported on Manifests.

ANO-2 Waste Characterization No waste for this category.

49

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-Common Waste Characterization ANO-Common Class A/Total Isotope Percent Abundance Curies H-3 9.33% 1.45E-01 C-14 4.13% 6.40E-02 Mn-54 0.75% 1.16E-02 Fe-55 0.86% 1.33E-02 Co-58 5.26% 8.15E-02 Co-60 10.51% 1.63E-01 Ni-63 28.96% 4.49E-01 Sr-90 1.05% 1.63E-02 Zr-95 5.42% 8.40E-02 Nb-95 8.18% 1.27E-01 Tc-99 3.38% 5.25E-02 Sb-125 0.14% 2.16E-03 I-129 0.63% 9.80E-03 Cs-134 0.11% 1.78E-03 Cs-137 21.28% 3.30E-01 Total Curies 1.55E+00 Notes:

There were zero Class B & C shipments.

The values listed for H-3, C-14, Tc-99 and I-129 in the above table contain LLD values calculated and reported on Manifests.

50

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

c. Irradiated components, control rods, etc. - No waste for this category

d. Other ANO-1 Waste Characterization No waste for this category ANO-2 Waste Characterization No waste for this category ANO-Common Waste Characterization ANO-Common Class A/Total Isotope Percent Abundance Curies H-3 10.44% 2.79E-02 C-14 80.08% 2.14E-01 Co-60 0.06% 1.59E-04 Tc-99 3.34% 8.93E-03 I-129 0.24% 6.42E-04 Cs-137 5.84% 1.56E-02 Total Curies 2.67E-01 Notes:

There were zero Class B & C shipments.

The values listed for H-3, C-14, Tc-99 and I-129 in the above table contain LLD values calculated and reported on Manifests.

51

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016

e. Shipping Manifests ANO-1 Waste Shipping Manifest Information ANO-1 Manifests Manifest Number Date Shipped Comment RSR 2016-012 27-JAN-16 RSR 2016-014 3-FEB-16 RSR 2016-031 10-MAR-16 180 ft3 ANO-1, 540 ft3 ANO-2 RSR 2016-075 20-JUL-16 RSR 2016-088 23-AUG-16 341 ft3 ANO-1, 426 ft3 ANO-2 RSR 2016-101 5-OCT-16 RSR 2016-107 18-OCT-16 RSR 2016-108 19-OCT-16 RSR 2016-109 24-OCT-16 RSR 2016-114 25-OCT-16 RSR 2016-118 2-NOV-16 RSR 2016-119 26-OCT-16 RSR 2016-127 9-NOV-16 RSR 2016-144 6-DEC-16 RSR 2016-147 5-DEC-16 RSR 2016-148 6-DEC-16 RSR 2016-149 7-DEC-16 RSR 2016-150 8-DEC-16 ANO-2 Waste Shipping Manifest Information ANO-2 Manifests Manifest Number Date Shipped Comment RSR 2016-028 8-MAR-16 RSR 2016-031 10-MAR-16 180 ft3 ANO-1, 540 ft3 ANO-2 RSR 2016-088 23-AUG-16 341 ft3 ANO-1, 426 ft3 ANO-2 52

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-Common Waste Shipping Manifest Information ANO-Common Manifests Manifest Number Date Shipped Comment RSR 2016-001 7-JAN-16 RSR 2016-005 12-JAN-16 RSR 2016-007 14-JAN-16 RSR 2016-022 23-FEB-16 RSR 2016-023 25-FEB-16 RSR 2016-025 26-FEB-16 RSR 2016-032 16-MAR-16 RSR 2016-036 29-MAR-16 RSR 2016-037 24-MAR-16 RSR 2016-040 7-APR-16 RSR 2016-041 12-APR-16 RSR 2016-045 14-APR-16 RSR 2016-049 19-APR-16 RSR 2016-050 21-APR-16 RSR 2016-051 26-APR-16 RSR 2016-052 28-APR-16 RSR 2016-053 5-MAY-16 RSR 2016-058 17-MAY-16 RSR 2016-059 19-MAY-16 RSR 2016-091 30-AUG-16 RSR 2016-096 16-SEP-16 53

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Appendix B Ground Water Protection Program Data and Analysis 54

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 RADIOACTIVE GROUND WATER MONITORING PROGRAM (RGWMP) DATA NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document, Objective 2.4, Annual Reporting, requires documentation of all on-site ground water sample results and a description of any significant on-site leaks/spills into ground water for each calendar year in the ARERR as contained in the appropriate reporting procedure.

A. NEI 07-07, Objective 2.4, Annual Reporting, Acceptance Criteria b.i, requires that ground water sample results that are taken in support of the Ground Water Protection Initiative (GPI) but are not part of the Radiological Environmental Monitoring Program (REMP) (e.g. samples obtained during the investigatory phase of the action plan) are reported in the ARERR. Additionally, Entergys procedure EN-CY-111, Radiological Ground Water Monitoring Program, Step 5.15[3] requires that a listing of non-REMP wells and a summary of pertinent sample results from the Radiological Ground Water Monitoring Program (RGWMP) are reported in the ARERR and an estimate of the doses to a member of the public associated with off-site releases of licensed radioactive material via ground water is included in the ARERR.

In 2016, there were no non-REMP designated ground water wells installed at ANO.

There were no new REMP designated ground water wells installed in 2016. There were four previously installed (prior to 2010) REMP designated ground water wells. The results of the samples collected from the REMP designated ground water wells are included in the 2016 Annual Radiological Environmental Operating Report (AREOR) as required by NEI 07-07.

ANO did not show any positive results during storm water sampling activities in 2016.

B. NEI 07-07, Objective 2.4, Acceptance Criteria c.ii, requires that a description of all spills or leaks that were communicated per NEI 07-07, Objective 2.2, Voluntary Communication, be included in the ARERR. Additionally, Entergys procedure EN-RP-113, Response to Contaminated Spills/Leaks, requires that the following be included in the ARERR:

1. Spills/leaks documented on Attachment 9.1 that was released to the environment or outside the spent fuel pool enclosure, SHALL be documented in the next ARERR.

2. The documentation in the ARERR report will contain:

Description of event Impact of event Remediation of event Radioactive contamination content and levels of event Discussion of impact on groundwater, if any 55

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 C. Program Data Analysis Summary:

In 2016, there were no spills/leaks that required communication per NEI 07-07 Objective 2.2 or inclusion in the ARERR per EN-RP-113.

A search of the ANO Corrective Action Program was conducted using radioactive spill(s) as the search criteria. Zero items were found.

Entergys procedure EN-CY-108, Monitoring of Non-Radioactive Systems, requires that verified positive results associated with the sampling of designated nonradioactive or cross-contaminated systems are to be included in the sites ARERR, unless already reported under an existing monitored ODCM release point.

Discussion:

In 2016, there was one ground water sample point, Ground Water Monitoring Well-17 (MW-17), where a positive detection of tritium was found. During routine quarterly sampling of this well a detectable amount of tritium was confirmed by offsite vendor analysis. The increase in tritium in MW-17 is suspected to be atmospheric recapture.

There are no indications of underground piping leaks. The levels indicated below, 553 pCi/L and 412 pCi/L are well below the ODCM requirement of 3000 pCi/L for non-drinking water sources. The tritium minimum detectable activity (MDA) imposed by ANO on offsite vendor analysis is 400 pCi/L. This allows ANO chemistry to closely trend ground water tritium and initiate remediation action quicker if a leak is detected.

All other ground water wells were found to be less than MDA for tritium and gamma emitters.

See results below:

Station Collection Date Analysis Result Activity Error MDC Units Flag MW-17 06/02/2016 13:50 H-3 (DIST) 553 553 243 314 pCi/L +

MW-17 09/14/2016 15:59 H-3 (DIST) 412 412 222 306 pCi/L +

Legend:

Flag U identifies the samples analysis is less than MDA.

Flag + identifies a positive analysis for radioactivity for a particular nuclide.

56

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 ANO-Common GROUND WATER RAW DATA (CHRONOLOGICAL):

Station Collection Date Analysis Result Activity Error MDC Units Flag MW-03 3/16/2016 11:57 H-3 (DIST) <360 -97.1 211 360 pCi/L U MW-03 3/16/2016 11:57 MN-54 <5.81 2.88 3.02 5.81 pCi/L U MW-03 3/16/2016 11:57 CO-58 <6.404 -0.6489 4.008 6.404 pCi/L U MW-03 3/16/2016 11:57 FE-59 <11.65 0.9442 6.956 11.65 pCi/L U MW-03 3/16/2016 11:57 CO-60 <5.636 -0.7796 3.664 5.636 pCi/L U MW-03 3/16/2016 11:57 ZN-65 <12.79 1.447 8.756 12.79 pCi/L U MW-03 3/16/2016 11:57 NB-95 <6.869 -1.543 4.4 6.869 pCi/L U MW-03 3/16/2016 11:57 ZR-95 <10.82 -3.067 7.069 10.82 pCi/L U MW-03 3/16/2016 11:57 I-131 <11.31 0.5482 6.756 11.31 pCi/L U MW-03 3/16/2016 11:57 CS-134 <5.93 -1.292 4.433 5.93 pCi/L U MW-03 3/16/2016 11:57 CS-137 <7.275 1.796 4.18 7.275 pCi/L U MW-03 3/16/2016 11:57 BA-140 <28.02 -15.74 19.1 28.02 pCi/L U MW-03 3/16/2016 11:57 LA-140 <10.73 1.315 6.333 10.73 pCi/L U MW-10 3/16/2016 12:35 H-3 (DIST) <351 -187 198 351 pCi/L U MW-10 3/16/2016 12:35 MN-54 <7.058 2.787 3.913 7.058 pCi/L U MW-10 3/16/2016 12:35 CO-58 <6.054 1.166 3.497 6.054 pCi/L U MW-10 3/16/2016 12:35 FE-59 <17.29 11.09 9.015 17.29 pCi/L U MW-10 3/16/2016 12:35 CO-60 <6.959 3.491 3.537 6.959 pCi/L U MW-10 3/16/2016 12:35 ZN-65 <14.56 0.119 8.923 14.56 pCi/L U MW-10 3/16/2016 12:35 NB-95 <7.418 1.353 4.344 7.418 pCi/L U MW-10 3/16/2016 12:35 ZR-95 <12.18 -0.6007 7.501 12.18 pCi/L U MW-10 3/16/2016 12:35 I-131 <13.46 6.542 7.534 13.46 pCi/L U MW-10 3/16/2016 12:35 CS-134 <5.746 -12.68 5.041 5.746 pCi/L U MW-10 3/16/2016 12:35 CS-137 <6.023 -0.4854 3.734 6.023 pCi/L U MW-10 3/16/2016 12:35 BA-140 <32.6 -4.327 20.26 32.6 pCi/L U MW-10 3/16/2016 12:35 LA-140 <8.838 -3.027 6.244 8.838 pCi/L U MW-12 3/16/2016 13:22 H-3 (DIST) <347 74.9 216 347 pCi/L U MW-12 3/16/2016 13:22 MN-54 <6.434 -0.6578 4.01 6.434 pCi/L U MW-12 3/16/2016 13:22 CO-58 <5.869 -2.167 3.996 5.869 pCi/L U MW-12 3/16/2016 13:22 FE-59 <11.73 2.695 6.393 11.73 pCi/L U MW-12 3/16/2016 13:22 CO-60 <7.827 1.994 4.311 7.827 pCi/L U 57

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-12 3/16/2016 13:22 ZN-65 <13.85 -5.258 9.653 13.85 pCi/L U MW-12 3/16/2016 13:22 NB-95 <7.233 -0.783 4.48 7.233 pCi/L U MW-12 3/16/2016 13:22 ZR-95 <11.85 -3.118 7.687 11.85 pCi/L U MW-12 3/16/2016 13:22 I-131 <12.18 2.3 7.309 12.18 pCi/L U MW-12 3/16/2016 13:22 CS-134 <7.074 3.535 4.023 7.074 pCi/L U MW-12 3/16/2016 13:22 CS-137 <7.283 2.34 3.941 7.283 pCi/L U MW-12 3/16/2016 13:22 BA-140 <36.31 14.91 19.34 36.31 pCi/L U MW-12 3/16/2016 13:22 LA-140 <11.57 0.854 6.962 11.57 pCi/L U DUP-MW-12 3/16/2016 13:25 H-3 (DIST) <347 -146 199 347 pCi/L U DUP-MW-12 3/16/2016 13:25 MN-54 <6.441 1.186 3.681 6.441 pCi/L U DUP-MW-12 3/16/2016 13:25 CO-58 <7.06 3.828 3.642 7.06 pCi/L U DUP-MW-12 3/16/2016 13:25 FE-59 <14.21 3.693 7.993 14.21 pCi/L U DUP-MW-12 3/16/2016 13:25 CO-60 <5.323 0.276 3.2 5.323 pCi/L U DUP-MW-12 3/16/2016 13:25 ZN-65 <10.69 -0.7629 7.783 10.69 pCi/L U DUP-MW-12 3/16/2016 13:25 NB-95 <7.207 3.439 4.232 7.207 pCi/L U DUP-MW-12 3/16/2016 13:25 ZR-95 <8.182 -4.694 5.792 8.182 pCi/L U DUP-MW-12 3/16/2016 13:25 I-131 <9.956 -6.179 6.819 9.956 pCi/L U DUP-MW-12 3/16/2016 13:25 CS-134 <6.229 -1.628 4.777 6.229 pCi/L U DUP-MW-12 3/16/2016 13:25 CS-137 <7.451 -1.642 4.622 7.451 pCi/L U DUP-MW-12 3/16/2016 13:25 BA-140 <35.01 1.897 21.51 35.01 pCi/L U DUP-MW-12 3/16/2016 13:25 LA-140 <11.61 0.02041 7.225 11.61 pCi/L U MW-06 3/16/2016 14:03 H-3 (DIST) <364 -41 218 364 pCi/L U MW-06 3/16/2016 14:03 MN-54 <6.188 0.1572 3.698 6.188 pCi/L U MW-06 3/16/2016 14:03 CO-58 <7.425 3.354 3.794 7.425 pCi/L U MW-06 3/16/2016 14:03 FE-59 <16.22 3.905 9.074 16.22 pCi/L U MW-06 3/16/2016 14:03 CO-60 <4.644 -1.469 3.455 4.644 pCi/L U MW-06 3/16/2016 14:03 ZN-65 <13.92 1.837 9.059 13.92 pCi/L U MW-06 3/16/2016 14:03 NB-95 <7.48 1.427 4.234 7.48 pCi/L U MW-06 3/16/2016 14:03 ZR-95 <8.672 -3.144 6.003 8.672 pCi/L U MW-06 3/16/2016 14:03 I-131 <13.01 1.67 7.925 13.01 pCi/L U MW-06 3/16/2016 14:03 CS-134 <6.533 2.015 3.936 6.533 pCi/L U MW-06 3/16/2016 14:03 CS-137 <6.975 1.372 3.908 6.975 pCi/L U MW-06 3/16/2016 14:03 BA-140 <34.21 -3.645 20.8 34.21 pCi/L U MW-06 3/16/2016 14:03 LA-140 <11.11 4.444 5.286 11.11 pCi/L U 58

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-07 3/16/2016 14:09 H-3 (DIST) <364 -221 204 364 pCi/L U MW-07 3/16/2016 14:09 MN-54 <7.382 0.3701 4.379 7.382 pCi/L U MW-07 3/16/2016 14:09 CO-58 <6.612 -0.3367 4.016 6.612 pCi/L U MW-07 3/16/2016 14:09 FE-59 <12.32 -0.258 7.554 12.32 pCi/L U MW-07 3/16/2016 14:09 CO-60 <4.733 -0.5918 3.103 4.733 pCi/L U MW-07 3/16/2016 14:09 ZN-65 <13.17 -2.842 8.578 13.17 pCi/L U MW-07 3/16/2016 14:09 NB-95 <7.465 1.933 4.192 7.465 pCi/L U MW-07 3/16/2016 14:09 ZR-95 <12.58 4.578 6.831 12.58 pCi/L U MW-07 3/16/2016 14:09 I-131 <10.72 -9.751 7.643 10.72 pCi/L U MW-07 3/16/2016 14:09 CS-134 <5.49 -0.6674 4.09 5.49 pCi/L U MW-07 3/16/2016 14:09 CS-137 <6.784 -1.311 4.209 6.784 pCi/L U MW-07 3/16/2016 14:09 BA-140 <31.91 -13.04 21.66 31.91 pCi/L U MW-07 3/16/2016 14:09 LA-140 <8.144 -7.249 7.115 8.144 pCi/L U MW-104 3/16/2016 15:40 H-3 (DIST) <362 -97.7 212 362 pCi/L U MW-104 3/16/2016 15:40 MN-54 <5.999 0.04011 3.68 5.999 pCi/L U MW-104 3/16/2016 15:40 CO-58 <7.85 2.4 4.322 7.85 pCi/L U MW-104 3/16/2016 15:40 FE-59 <14.22 1.713 8.057 14.22 pCi/L U MW-104 3/16/2016 15:40 CO-60 <6.741 1.388 3.603 6.741 pCi/L U MW-104 3/16/2016 15:40 ZN-65 <9.658 -15.68 9.882 9.658 pCi/L U MW-104 3/16/2016 15:40 NB-95 <6.077 -1.083 3.978 6.077 pCi/L U MW-104 3/16/2016 15:40 ZR-95 <11.85 0.2127 7.211 11.85 pCi/L U MW-104 3/16/2016 15:40 I-131 <12.76 0.8971 7.489 12.76 pCi/L U MW-104 3/16/2016 15:40 CS-134 <5.533 -1.68 4.344 5.533 pCi/L U MW-104 3/16/2016 15:40 CS-137 <8.194 1.297 4.762 8.194 pCi/L U MW-104 3/16/2016 15:40 BA-140 <31.28 -7.359 20.19 31.28 pCi/L U MW-104 3/16/2016 15:40 LA-140 <11.59 2.154 6.31 11.59 pCi/L U MW-19 3/16/2016 15:57 H-3 (DIST) <348 -41.7 208 348 pCi/L U MW-19 3/16/2016 15:57 MN-54 <8.158 0.4885 4.93 8.158 pCi/L U MW-19 3/16/2016 15:57 CO-58 <7.847 1.377 4.55 7.847 pCi/L U MW-19 3/16/2016 15:57 FE-59 <16.09 0.9586 9.39 16.09 pCi/L U MW-19 3/16/2016 15:57 CO-60 <6.498 -2.83 4.689 6.498 pCi/L U MW-19 3/16/2016 15:57 ZN-65 <12.28 -10.39 9.735 12.28 pCi/L U MW-19 3/16/2016 15:57 NB-95 <9.997 3.061 5.673 9.997 pCi/L U MW-19 3/16/2016 15:57 ZR-95 <12.92 -3.034 8.487 12.92 pCi/L U 59

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-19 3/16/2016 15:57 I-131 <12.59 0.4498 7.447 12.59 pCi/L U MW-19 3/16/2016 15:57 CS-134 <7.756 0.5334 5.32 7.756 pCi/L U MW-19 3/16/2016 15:57 CS-137 <6.366 -0.3857 3.958 6.366 pCi/L U MW-19 3/16/2016 15:57 BA-140 <36.02 -5.267 22.55 36.02 pCi/L U MW-19 3/16/2016 15:57 LA-140 <12.44 3.31 6.532 12.44 pCi/L U MW-102 3/16/2016 17:06 H-3 (DIST) <370 -93.7 218 370 pCi/L U MW-102 3/16/2016 17:06 MN-54 <6.11 -0.7093 3.856 6.11 pCi/L U MW-102 3/16/2016 17:06 CO-58 <7.82 1.705 4.337 7.82 pCi/L U MW-102 3/16/2016 17:06 FE-59 <17.8 4.158 9.898 17.8 pCi/L U MW-102 3/16/2016 17:06 CO-60 <8.263 2.344 4.358 8.263 pCi/L U MW-102 3/16/2016 17:06 ZN-65 <10.84 -2.909 7.614 10.84 pCi/L U MW-102 3/16/2016 17:06 NB-95 <8.163 2.656 4.37 8.163 pCi/L U MW-102 3/16/2016 17:06 ZR-95 <11.44 2.033 6.355 11.44 pCi/L U MW-102 3/16/2016 17:06 I-131 <13.68 0.4854 8.382 13.68 pCi/L U MW-102 3/16/2016 17:06 CS-134 <6.223 -5.971 4.704 6.223 pCi/L U MW-102 3/16/2016 17:06 CS-137 <5.326 -3.355 3.996 5.326 pCi/L U MW-102 3/16/2016 17:06 BA-140 <33.79 6.788 19.69 33.79 pCi/L U MW-102 3/16/2016 17:06 LA-140 <5.799 -0.0051 3.604 5.799 pCi/L U MW-17 3/16/2016 17:07 H-3 (DIST) <355 202 231 355 pCi/L U MW-17 3/16/2016 17:07 MN-54 <6.661 -2.645 3.946 6.661 pCi/L U MW-17 3/16/2016 17:07 CO-58 <5.84 -1.136 3.225 5.84 pCi/L U MW-17 3/16/2016 17:07 FE-59 <14.34 -0.8361 7.573 14.34 pCi/L U MW-17 3/16/2016 17:07 CO-60 <7.378 1.124 3.458 7.378 pCi/L U MW-17 3/16/2016 17:07 ZN-65 <14.05 -0.4677 7.289 14.05 pCi/L U MW-17 3/16/2016 17:07 NB-95 <7.634 0.382 4.037 7.634 pCi/L U MW-17 3/16/2016 17:07 ZR-95 <13.25 6.611 5.948 13.25 pCi/L U MW-17 3/16/2016 17:07 I-131 <12.76 -1.946 7.365 12.76 pCi/L U MW-17 3/16/2016 17:07 CS-134 <6.724 2.364 3.719 6.724 pCi/L U MW-17 3/16/2016 17:07 CS-137 <5.23 -3.303 3.335 5.23 pCi/L U MW-17 3/16/2016 17:07 BA-140 <34.37 -4.037 19.27 34.37 pCi/L U MW-17 3/16/2016 17:07 LA-140 <8.15 -3.351 4.785 8.15 pCi/L U MW-15 3/17/2016 8:53 H-3 (DIST) <366 -67.9 217 366 pCi/L U MW-15 3/17/2016 8:53 MN-54 <1.536 -0.4583 0.9815 1.536 pCi/L U MW-15 3/17/2016 8:53 CO-58 <1.553 0.2265 0.9542 1.553 pCi/L U 60

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-15 3/17/2016 8:53 FE-59 <3.295 0.5882 1.92 3.295 pCi/L U MW-15 3/17/2016 8:53 CO-60 <1.486 -0.5979 0.9331 1.486 pCi/L U MW-15 3/17/2016 8:53 ZN-65 <3.031 -1.358 2.141 3.031 pCi/L U MW-15 3/17/2016 8:53 NB-95 <1.707 1.384 0.9921 1.707 pCi/L U MW-15 3/17/2016 8:53 ZR-95 <2.746 0.2853 1.686 2.746 pCi/L U MW-15 3/17/2016 8:53 I-131 <3.003 1.357 1.742 3.003 pCi/L U MW-15 3/17/2016 8:53 CS-134 <1.45 -0.3014 1.007 1.45 pCi/L U MW-15 3/17/2016 8:53 CS-137 <1.732 0.8169 1.142 1.732 pCi/L U MW-15 3/17/2016 8:53 BA-140 <7.787 -1.102 4.76 7.787 pCi/L U MW-15 3/17/2016 8:53 LA-140 <2.723 -0.3021 1.678 2.723 pCi/L U DUP-MW-15 3/17/2016 9:15 H-3 (DIST) <364 -194 206 364 pCi/L U DUP-MW-15 3/17/2016 9:15 MN-54 <7.576 2.446 4.258 7.576 pCi/L U DUP-MW-15 3/17/2016 9:15 CO-58 <7.439 -2.345 4.878 7.439 pCi/L U DUP-MW-15 3/17/2016 9:15 FE-59 <14.39 -0.3079 8.888 14.39 pCi/L U DUP-MW-15 3/17/2016 9:15 CO-60 <6.018 0.7664 3.505 6.018 pCi/L U DUP-MW-15 3/17/2016 9:15 ZN-65 <14.38 6.229 8.415 14.38 pCi/L U DUP-MW-15 3/17/2016 9:15 NB-95 <10.18 5.569 5.585 10.18 pCi/L U DUP-MW-15 3/17/2016 9:15 ZR-95 <12.15 -2.328 7.76 12.15 pCi/L U DUP-MW-15 3/17/2016 9:15 I-131 <13.9 -0.3818 8.408 13.9 pCi/L U DUP-MW-15 3/17/2016 9:15 CS-134 <7.489 -0.1025 5.308 7.489 pCi/L U DUP-MW-15 3/17/2016 9:15 CS-137 <7.003 -0.01458 4.258 7.003 pCi/L U DUP-MW-15 3/17/2016 9:15 BA-140 <32.96 -9.578 21.17 32.96 pCi/L U DUP-MW-15 3/17/2016 9:15 LA-140 <11.87 6.148 5.832 11.87 pCi/L U MW-14 3/17/2016 9:34 H-3 (DIST) <367 -12.4 222 367 pCi/L U MW-14 3/17/2016 9:34 MN-54 <5.722 -1.553 3.948 5.722 pCi/L U MW-14 3/17/2016 9:34 CO-58 <6.88 -0.9344 4.453 6.88 pCi/L U MW-14 3/17/2016 9:34 FE-59 <19.92 -1.983 12.22 19.92 pCi/L U MW-14 3/17/2016 9:34 CO-60 <8.2 2.262 4.253 8.2 pCi/L U MW-14 3/17/2016 9:34 ZN-65 <14.32 -4.074 11.39 14.32 pCi/L U MW-14 3/17/2016 9:34 NB-95 <7.325 0.1425 4.456 7.325 pCi/L U MW-14 3/17/2016 9:34 ZR-95 <11.44 -0.1126 7.037 11.44 pCi/L U MW-14 3/17/2016 9:34 I-131 <11.92 -2.695 7.461 11.92 pCi/L U MW-14 3/17/2016 9:34 CS-134 <5.402 -5.438 5.308 5.402 pCi/L U MW-14 3/17/2016 9:34 CS-137 <8.562 1.935 4.848 8.562 pCi/L U 61

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-14 3/17/2016 9:34 BA-140 <39.82 12.69 22.01 39.82 pCi/L U MW-14 3/17/2016 9:34 LA-140 <13.75 -1.122 8.655 13.75 pCi/L U MW-09 3/17/2016 10:25 H-3 (DIST) <367 -78.4 217 367 pCi/L U MW-09 3/17/2016 10:25 MN-54 <6.455 -1.26 4.175 6.455 pCi/L U MW-09 3/17/2016 10:25 CO-58 <7.285 -1.327 4.659 7.285 pCi/L U MW-09 3/17/2016 10:25 FE-59 <14.94 1.492 8.758 14.94 pCi/L U MW-09 3/17/2016 10:25 CO-60 <8.096 0.4086 4.886 8.096 pCi/L U MW-09 3/17/2016 10:25 ZN-65 <12.14 -8.19 9.683 12.14 pCi/L U MW-09 3/17/2016 10:25 NB-95 <8.65 0.9665 5.032 8.65 pCi/L U MW-09 3/17/2016 10:25 ZR-95 <13.28 0.5496 7.865 13.28 pCi/L U MW-09 3/17/2016 10:25 I-131 <11.76 0.6218 7.274 11.76 pCi/L U MW-09 3/17/2016 10:25 CS-134 <7.251 2.241 4.368 7.251 pCi/L U MW-09 3/17/2016 10:25 CS-137 <6.737 -2.482 4.51 6.737 pCi/L U MW-09 3/17/2016 10:25 BA-140 <36.75 -19.48 24.5 36.75 pCi/L U MW-09 3/17/2016 10:25 LA-140 <5.057 -10.95 7.918 5.057 pCi/L U MW-04 3/17/2016 11:25 H-3 (DIST) <364 -203 206 364 pCi/L U MW-04 3/17/2016 11:25 MN-54 <4.455 -0.6296 2.844 4.455 pCi/L U MW-04 3/17/2016 11:25 CO-58 <5.14 0.8473 2.977 5.14 pCi/L U MW-04 3/17/2016 11:25 FE-59 <8.094 -0.4027 4.94 8.094 pCi/L U MW-04 3/17/2016 11:25 CO-60 <5.118 -0.4234 3.218 5.118 pCi/L U MW-04 3/17/2016 11:25 ZN-65 <9.446 -1.005 6.886 9.446 pCi/L U MW-04 3/17/2016 11:25 NB-95 <6.035 1.407 3.45 6.035 pCi/L U MW-04 3/17/2016 11:25 ZR-95 <8.03 0.2481 4.813 8.03 pCi/L U MW-04 3/17/2016 11:25 I-131 <8.744 -0.04429 5.271 8.744 pCi/L U MW-04 3/17/2016 11:25 CS-134 <4.306 -1.946 3.344 4.306 pCi/L U MW-04 3/17/2016 11:25 CS-137 <5.326 -0.6704 3.289 5.326 pCi/L U MW-04 3/17/2016 11:25 BA-140 <25.58 8.171 14.65 25.58 pCi/L U MW-04 3/17/2016 11:25 LA-140 <7.794 -0.2856 4.719 7.794 pCi/L U MW-08 3/17/2016 12:28 H-3 (DIST) <364 -170 208 364 pCi/L U MW-08 3/17/2016 12:28 MN-54 <6.783 -1.059 4.247 6.783 pCi/L U MW-08 3/17/2016 12:28 CO-58 <5.792 -2.216 3.897 5.792 pCi/L U MW-08 3/17/2016 12:28 FE-59 <13.8 -0.9114 8.592 13.8 pCi/L U MW-08 3/17/2016 12:28 CO-60 <5.821 -2.837 4.352 5.821 pCi/L U MW-08 3/17/2016 12:28 ZN-65 <13.58 -13.92 10.9 13.58 pCi/L U 62

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-08 3/17/2016 12:28 NB-95 <7.905 0.6479 4.632 7.905 pCi/L U MW-08 3/17/2016 12:28 ZR-95 <11 -6.875 7.722 11 pCi/L U MW-08 3/17/2016 12:28 I-131 <11.06 1.574 6.566 11.06 pCi/L U MW-08 3/17/2016 12:28 CS-134 <7.115 2.815 4.491 7.115 pCi/L U MW-08 3/17/2016 12:28 CS-137 <7.78 -4.554 5.835 7.78 pCi/L U MW-08 3/17/2016 12:28 BA-140 <36.31 9.641 21.19 36.31 pCi/L U MW-08 3/17/2016 12:28 LA-140 <11.03 -6.173 8.358 11.03 pCi/L U MW-02 3/17/2016 12:30 H-3 (DIST) <368 -126 214 368 pCi/L U MW-02 3/17/2016 12:30 MN-54 <7.67 2.457 4.088 7.67 pCi/L U MW-02 3/17/2016 12:30 CO-58 <4.877 -0.9058 3.135 4.877 pCi/L U MW-02 3/17/2016 12:30 FE-59 <8.718 -6.739 7.376 8.718 pCi/L U MW-02 3/17/2016 12:30 CO-60 <6.915 -0.901 4.445 6.915 pCi/L U MW-02 3/17/2016 12:30 ZN-65 <13.73 -2.66 8.894 13.73 pCi/L U MW-02 3/17/2016 12:30 NB-95 <7.733 -1.946 4.89 7.733 pCi/L U MW-02 3/17/2016 12:30 ZR-95 <11.43 0.6763 6.607 11.43 pCi/L U MW-02 3/17/2016 12:30 I-131 <11.47 3.441 6.569 11.47 pCi/L U MW-02 3/17/2016 12:30 CS-134 <4.748 -2.503 4.165 4.748 pCi/L U MW-02 3/17/2016 12:30 CS-137 <7.882 2.633 4.416 7.882 pCi/L U MW-02 3/17/2016 12:30 BA-140 <29.55 -3.918 19.31 29.55 pCi/L U MW-02 3/17/2016 12:30 LA-140 <9.95 0.0661 6.053 9.95 pCi/L U EB-MW-02 3/17/2016 13:30 H-3 (DIST) <342 65.6 213 342 pCi/L U MW-05 3/17/2016 15:25 H-3 (DIST) <370 87.4 231 370 pCi/L U MW-05 3/17/2016 15:25 MN-54 <9.615 1.05 5.634 9.615 pCi/L U MW-05 3/17/2016 15:25 CO-58 <7.043 -0.1369 4.25 7.043 pCi/L U MW-05 3/17/2016 15:25 FE-59 <19.15 6.523 10.58 19.15 pCi/L U MW-05 3/17/2016 15:25 CO-60 <10.18 4.978 5.127 10.18 pCi/L U MW-05 3/17/2016 15:25 ZN-65 <17.79 0.02863 12.76 17.79 pCi/L U MW-05 3/17/2016 15:25 NB-95 <10.03 3.594 5.52 10.03 pCi/L U MW-05 3/17/2016 15:25 ZR-95 <15.15 6.627 7.999 15.15 pCi/L U MW-05 3/17/2016 15:25 I-131 <13.16 0.2372 7.812 13.16 pCi/L U MW-05 3/17/2016 15:25 CS-134 <7.68 1.999 5.034 7.68 pCi/L U MW-05 3/17/2016 15:25 CS-137 <6.91 -5.217 5.22 6.91 pCi/L U MW-05 3/17/2016 15:25 BA-140 <38.47 -12.76 25.17 38.47 pCi/L U MW-05 3/17/2016 15:25 LA-140 <13.5 -0.5736 8.342 13.5 pCi/L U 63

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag EB-MW-05 3/17/2016 16:06 H-3 (DIST) <366 -257 202 366 pCi/L U MW-13 6/2/2016 9:52 SAMPLE U MW-12 6/2/2016 11:10 H-3 (DIST) <320 71.1 201 320 pCi/L U MW-12 6/2/2016 11:10 MN-54 <5.091 0.6182 3.045 5.091 pCi/L U MW-12 6/2/2016 11:10 CO-58 <6.088 2.456 3.421 6.088 pCi/L U MW-12 6/2/2016 11:10 FE-59 <9.479 -3.836 6.287 9.479 pCi/L U MW-12 6/2/2016 11:10 CO-60 <5.285 0.1719 3.144 5.285 pCi/L U MW-12 6/2/2016 11:10 ZN-65 <10.71 3.254 6.613 10.71 pCi/L U MW-12 6/2/2016 11:10 NB-95 <5.884 1.587 3.406 5.884 pCi/L U MW-12 6/2/2016 11:10 ZR-95 <10.42 6.201 5.559 10.42 pCi/L U MW-12 6/2/2016 11:10 I-131 <12.65 -1.4 7.673 12.65 pCi/L U MW-12 6/2/2016 11:10 CS-134 <5.394 2.195 3.452 5.394 pCi/L U MW-12 6/2/2016 11:10 CS-137 <5.189 -2.267 3.44 5.189 pCi/L U MW-12 6/2/2016 11:10 BA-140 <29.36 5.354 17.12 29.36 pCi/L U MW-12 6/2/2016 11:10 LA-140 <8.096 -4.812 6.074 8.096 pCi/L U MW-14 6/2/2016 12:10 H-3 (DIST) <313 94.1 200 313 pCi/L U MW-14 6/2/2016 12:10 MN-54 <3.875 -2.045 2.563 3.875 pCi/L U MW-14 6/2/2016 12:10 CO-58 <3.71 -2.052 2.486 3.71 pCi/L U MW-14 6/2/2016 12:10 FE-59 <9.87 1.188 5.877 9.87 pCi/L U MW-14 6/2/2016 12:10 CO-60 <4.097 -0.3399 2.577 4.097 pCi/L U MW-14 6/2/2016 12:10 ZN-65 <9.202 -6.67 6.398 9.202 pCi/L U MW-14 6/2/2016 12:10 NB-95 <4.817 0.636 2.831 4.817 pCi/L U MW-14 6/2/2016 12:10 ZR-95 <7.959 1.465 4.622 7.959 pCi/L U MW-14 6/2/2016 12:10 I-131 <10.7 -7.395 7.095 10.7 pCi/L U MW-14 6/2/2016 12:10 CS-134 <4.315 -2.186 3.4 4.315 pCi/L U MW-14 6/2/2016 12:10 CS-137 <3.85 -2.79 2.59 3.85 pCi/L U MW-14 6/2/2016 12:10 BA-140 <25.17 -1.759 15.79 25.17 pCi/L U MW-14 6/2/2016 12:10 LA-140 <8.992 2.417 5.006 8.992 pCi/L U DUP-MW-14 6/2/2016 12:25 H-3 (DIST) <314 138 205 314 pCi/L U DUP-MW-14 6/2/2016 12:25 MN-54 <3.794 -1.23 2.468 3.794 pCi/L U DUP-MW-14 6/2/2016 12:25 CO-58 <4.52 -1.261 2.895 4.52 pCi/L U DUP-MW-14 6/2/2016 12:25 FE-59 <9.283 -0.9743 5.873 9.283 pCi/L U DUP-MW-14 6/2/2016 12:25 CO-60 <4.033 -1.146 2.583 4.033 pCi/L U DUP-MW-14 6/2/2016 12:25 ZN-65 <9.261 -2.513 6.065 9.261 pCi/L U 64

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag DUP-MW-14 6/2/2016 12:25 NB-95 <4.553 0.2742 2.734 4.553 pCi/L U DUP-MW-14 6/2/2016 12:25 ZR-95 <8.007 0.9577 4.75 8.007 pCi/L U DUP-MW-14 6/2/2016 12:25 I-131 <11.45 -3.044 7.369 11.45 pCi/L U DUP-MW-14 6/2/2016 12:25 CS-134 <4.136 -1.977 3.11 4.136 pCi/L U DUP-MW-14 6/2/2016 12:25 CS-137 <4.201 -3.496 2.892 4.201 pCi/L U DUP-MW-14 6/2/2016 12:25 BA-140 <29.79 16.13 16.46 29.79 pCi/L U DUP-MW-14 6/2/2016 12:25 LA-140 <8.235 -2.532 5.387 8.235 pCi/L U MW-17 6/2/2016 13:50 H-3 (DIST) 553 553 243 314 pCi/L +

MW-17 6/2/2016 13:50 MN-54 <5.958 1.837 3.436 5.958 pCi/L U MW-17 6/2/2016 13:50 CO-58 <4.538 -2.142 3.124 4.538 pCi/L U MW-17 6/2/2016 13:50 FE-59 <11.23 -2.787 7.177 11.23 pCi/L U MW-17 6/2/2016 13:50 CO-60 <6.161 4.076 3.043 6.161 pCi/L U MW-17 6/2/2016 13:50 ZN-65 <11.61 0.2274 6.965 11.61 pCi/L U MW-17 6/2/2016 13:50 NB-95 <6.174 1.391 3.601 6.174 pCi/L U MW-17 6/2/2016 13:50 ZR-95 <8.9 0.2627 5.389 8.9 pCi/L U MW-17 6/2/2016 13:50 I-131 <12.77 -3.973 8.143 12.77 pCi/L U MW-17 6/2/2016 13:50 CS-134 <4.407 -5.29 3.201 4.407 pCi/L U MW-17 6/2/2016 13:50 CS-137 <4.985 0.646 2.921 4.985 pCi/L U MW-17 6/2/2016 13:50 BA-140 <32.81 -1.819 19.65 32.81 pCi/L U MW-17 6/2/2016 13:50 LA-140 <14.76 6.544 7.843 14.76 pCi/L U MW-19 6/2/2016 14:42 H-3 (DIST) <317 29 195 317 pCi/L U MW-19 6/2/2016 14:42 MN-54 <4.419 -0.8692 2.774 4.419 pCi/L U MW-19 6/2/2016 14:42 CO-58 <4.753 -2.218 3.092 4.753 pCi/L U MW-19 6/2/2016 14:42 FE-59 <10.89 -2.869 7.035 10.89 pCi/L U MW-19 6/2/2016 14:42 CO-60 <4.765 0.5402 2.791 4.765 pCi/L U MW-19 6/2/2016 14:42 ZN-65 <8.579 -2.953 6.691 8.579 pCi/L U MW-19 6/2/2016 14:42 NB-95 <4.849 -1.079 3.035 4.849 pCi/L U MW-19 6/2/2016 14:42 ZR-95 <8.558 -0.4413 5.229 8.558 pCi/L U MW-19 6/2/2016 14:42 I-131 <12.51 4.987 7.463 12.51 pCi/L U MW-19 6/2/2016 14:42 CS-134 <4.713 0.9879 3.16 4.713 pCi/L U MW-19 6/2/2016 14:42 CS-137 <4.807 -1.009 2.973 4.807 pCi/L U MW-19 6/2/2016 14:42 BA-140 <29.55 -2.318 17.77 29.55 pCi/L U MW-19 6/2/2016 14:42 LA-140 <8.389 -3.995 5.677 8.389 pCi/L U MW-10 6/2/2016 16:42 H-3 (DIST) <314 206 212 314 pCi/L U 65

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-10 6/2/2016 16:42 MN-54 <4.34 -2.916 3.146 4.34 pCi/L U MW-10 6/2/2016 16:42 CO-58 <5.28 -0.5014 3.365 5.28 pCi/L U MW-10 6/2/2016 16:42 FE-59 <10.56 -5.349 7.111 10.56 pCi/L U MW-10 6/2/2016 16:42 CO-60 <5.332 0.3156 3.193 5.332 pCi/L U MW-10 6/2/2016 16:42 ZN-65 <9.363 -1.866 6.929 9.363 pCi/L U MW-10 6/2/2016 16:42 NB-95 <5.618 -1.103 3.629 5.618 pCi/L U MW-10 6/2/2016 16:42 ZR-95 <8.359 0.7299 5.082 8.359 pCi/L U MW-10 6/2/2016 16:42 I-131 <14.03 -1.127 8.456 14.03 pCi/L U MW-10 6/2/2016 16:42 CS-134 <5.297 -0.7942 3.817 5.297 pCi/L U MW-10 6/2/2016 16:42 CS-137 <5.648 1.597 3.292 5.648 pCi/L U MW-10 6/2/2016 16:42 BA-140 <33.07 12.24 18.86 33.07 pCi/L U MW-10 6/2/2016 16:42 LA-140 <8.461 -5.198 6.448 8.461 pCi/L U EB-MW-10 6/2/2016 17:00 H-3 (DIST) <312 -4.09 189 312 pCi/L U MW-19 9/14/2016 9:11 H-3 (DIST) <314 157 205 314 pCi/L U MW-19 9/14/2016 9:11 MN-54 <5.544 -2.049 3.617 5.544 pCi/L U MW-19 9/14/2016 9:11 CO-58 <5.344 -0.6694 3.361 5.344 pCi/L U MW-19 9/14/2016 9:11 FE-59 <13.22 -1.568 8.057 13.22 pCi/L U MW-19 9/14/2016 9:11 CO-60 <5.497 -1.899 3.571 5.497 pCi/L U MW-19 9/14/2016 9:11 ZN-65 <9.718 -1.165 6.968 9.718 pCi/L U MW-19 9/14/2016 9:11 NB-95 <6.186 0.01804 3.792 6.186 pCi/L U MW-19 9/14/2016 9:11 ZR-95 <10.02 -1.033 6.248 10.02 pCi/L U MW-19 9/14/2016 9:11 I-131 <14.88 -6.674 9.188 14.88 pCi/L U MW-19 9/14/2016 9:11 CS-134 <5.332 -0.804 3.818 5.332 pCi/L U MW-19 9/14/2016 9:11 CS-137 <5.578 -1.74 3.551 5.578 pCi/L U MW-19 9/14/2016 9:11 BA-140 <36.58 13.31 21.03 36.58 pCi/L U MW-19 9/14/2016 9:11 LA-140 <10.58 -6.602 7.512 10.58 pCi/L U MW-10 9/14/2016 10:16 H-3 (DIST) <305 -92.4 176 305 pCi/L U MW-10 9/14/2016 10:16 MN-54 <4.201 -0.4621 2.583 4.201 pCi/L U MW-10 9/14/2016 10:16 CO-58 <5.028 1.706 2.851 5.028 pCi/L U MW-10 9/14/2016 10:16 FE-59 <9.474 0.0186 5.833 9.474 pCi/L U MW-10 9/14/2016 10:16 CO-60 <3.572 -2.083 2.473 3.572 pCi/L U MW-10 9/14/2016 10:16 ZN-65 <10.15 2.132 6.874 10.15 pCi/L U MW-10 9/14/2016 10:16 NB-95 <4.735 1.089 2.726 4.735 pCi/L U MW-10 9/14/2016 10:16 ZR-95 <7.009 -1.397 4.36 7.009 pCi/L U 66

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-10 9/14/2016 10:16 I-131 <10.78 -1.004 6.567 10.78 pCi/L U MW-10 9/14/2016 10:16 CS-134 <3.895 -0.9369 2.914 3.895 pCi/L U MW-10 9/14/2016 10:16 CS-137 <4.762 1.658 2.673 4.762 pCi/L U MW-10 9/14/2016 10:16 BA-140 <29.28 0.271 18.06 29.28 pCi/L U MW-10 9/14/2016 10:16 LA-140 <7.301 -3.282 5.059 7.301 pCi/L U MW-12 9/14/2016 11:45 H-3 (DIST) <304 -12.4 183 304 pCi/L U MW-12 9/14/2016 11:45 MN-54 <5.46 -1.359 3.477 5.46 pCi/L U MW-12 9/14/2016 11:45 CO-58 <5.932 1.294 3.404 5.932 pCi/L U MW-12 9/14/2016 11:45 FE-59 <12.61 5.927 6.793 12.61 pCi/L U MW-12 9/14/2016 11:45 CO-60 <6.338 0.5289 3.719 6.338 pCi/L U MW-12 9/14/2016 11:45 ZN-65 <10.51 -8.804 7.959 10.51 pCi/L U MW-12 9/14/2016 11:45 NB-95 <6.217 0.2621 3.702 6.217 pCi/L U MW-12 9/14/2016 11:45 ZR-95 <8.621 -0.9452 5.316 8.621 pCi/L U MW-12 9/14/2016 11:45 I-131 <13.91 0.4521 8.334 13.91 pCi/L U MW-12 9/14/2016 11:45 CS-134 <5.383 0.9207 3.7 5.383 pCi/L U MW-12 9/14/2016 11:45 CS-137 <5.334 0.5902 3.096 5.334 pCi/L U MW-12 9/14/2016 11:45 BA-140 <36.85 9.069 21.75 36.85 pCi/L U MW-12 9/14/2016 11:45 LA-140 <13.1 0.04611 7.977 13.1 pCi/L U MW-14 9/14/2016 14:26 H-3 (DIST) <309 54.1 193 309 pCi/L U MW-14 9/14/2016 14:26 MN-54 <3.705 0.1911 2.172 3.705 pCi/L U MW-14 9/14/2016 14:26 CO-58 <4.024 -1.569 2.745 4.024 pCi/L U MW-14 9/14/2016 14:26 FE-59 <9.149 -0.2989 5.522 9.149 pCi/L U MW-14 9/14/2016 14:26 CO-60 <3.238 -0.3108 2.021 3.238 pCi/L U MW-14 9/14/2016 14:26 ZN-65 <7.669 -2.047 4.909 7.669 pCi/L U MW-14 9/14/2016 14:26 NB-95 <3.927 -1.194 2.624 3.927 pCi/L U MW-14 9/14/2016 14:26 ZR-95 <8.231 1.463 4.955 8.231 pCi/L U MW-14 9/14/2016 14:26 I-131 <11.72 -0.7436 7.215 11.72 pCi/L U MW-14 9/14/2016 14:26 CS-134 <3.856 1.999 3.227 3.856 pCi/L U MW-14 9/14/2016 14:26 CS-137 <4.5 0.2272 2.771 4.5 pCi/L U MW-14 9/14/2016 14:26 BA-140 <29.64 13.98 16.84 29.64 pCi/L U MW-14 9/14/2016 14:26 LA-140 <7.648 -4.84 5.643 7.648 pCi/L U DUP-MW-14 9/14/2016 14:36 H-3 (DIST) <313 -74.7 182 313 pCi/L U DUP-MW-14 9/14/2016 14:36 MN-54 <4.191 -0.1196 2.577 4.191 pCi/L U DUP-MW-14 9/14/2016 14:36 CO-58 <4.662 -0.9146 2.934 4.662 pCi/L U 67

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag DUP-MW-14 9/14/2016 14:36 FE-59 <9.12 -0.8256 5.56 9.12 pCi/L U DUP-MW-14 9/14/2016 14:36 CO-60 <3.766 -0.8418 2.41 3.766 pCi/L U DUP-MW-14 9/14/2016 14:36 ZN-65 <9.32 -1.426 5.739 9.32 pCi/L U DUP-MW-14 9/14/2016 14:36 NB-95 <5.074 1.459 2.966 5.074 pCi/L U DUP-MW-14 9/14/2016 14:36 ZR-95 <7.537 -4.843 5.045 7.537 pCi/L U DUP-MW-14 9/14/2016 14:36 I-131 <13.66 4.463 8.075 13.66 pCi/L U DUP-MW-14 9/14/2016 14:36 CS-134 <4.28 0.2045 2.963 4.28 pCi/L U DUP-MW-14 9/14/2016 14:36 CS-137 <4.391 -0.3497 2.68 4.391 pCi/L U DUP-MW-14 9/14/2016 14:36 BA-140 <28.32 -8.494 17.52 28.32 pCi/L U DUP-MW-14 9/14/2016 14:36 LA-140 <10.39 2.493 6.055 10.39 pCi/L U MW-17 9/14/2016 15:59 H-3 (DIST) 412 412 222 306 pCi/L +

MW-17 9/14/2016 15:59 MN-54 <5.747 0.7738 3.454 5.747 pCi/L U MW-17 9/14/2016 15:59 CO-58 <6.383 0.7116 3.849 6.383 pCi/L U MW-17 9/14/2016 15:59 FE-59 <14.3 0.8887 8.453 14.3 pCi/L U MW-17 9/14/2016 15:59 CO-60 <6.807 5.347 3.381 6.807 pCi/L U MW-17 9/14/2016 15:59 ZN-65 <10.51 -9.435 7.481 10.51 pCi/L U MW-17 9/14/2016 15:59 NB-95 <5.806 -0.9967 3.671 5.806 pCi/L U MW-17 9/14/2016 15:59 ZR-95 <10.18 -0.8521 6.335 10.18 pCi/L U MW-17 9/14/2016 15:59 I-131 <14.95 -2.409 9.024 14.95 pCi/L U MW-17 9/14/2016 15:59 CS-134 <5.916 -2.519 3.778 5.916 pCi/L U MW-17 9/14/2016 15:59 CS-137 <5.121 -0.8195 3.208 5.121 pCi/L U MW-17 9/14/2016 15:59 BA-140 <39.93 -0.008983 24.06 39.93 pCi/L U MW-17 9/14/2016 15:59 LA-140 <10.43 -3.879 7.126 10.43 pCi/L U EB-MW-17 9/14/2016 16:10 H-3 (DIST) <311 -36.2 185 311 pCi/L U MW-19 12/15/2016 9:10 H-3 (DIST) <283 -134 162 283 pCi/L U MW-19 12/15/2016 9:10 MN-54 <4.06 -1.588 2.681 4.06 pCi/L U MW-19 12/15/2016 9:10 CO-58 <4.363 0.7713 2.625 4.363 pCi/L U MW-19 12/15/2016 9:10 FE-59 <7.011 -4.215 4.791 7.011 pCi/L U MW-19 12/15/2016 9:10 CO-60 <4.53 3.093 2.38 4.53 pCi/L U MW-19 12/15/2016 9:10 ZN-65 <7.946 1.436 5.375 7.946 pCi/L U MW-19 12/15/2016 9:10 NB-95 <4.663 2.686 2.626 4.663 pCi/L U MW-19 12/15/2016 9:10 ZR-95 <7.101 2.284 4.128 7.101 pCi/L U MW-19 12/15/2016 9:10 I-131 <7.075 -0.1218 4.349 7.075 pCi/L U MW-19 12/15/2016 9:10 CS-134 <3.621 -1.65 2.721 3.621 pCi/L U 68

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-19 12/15/2016 9:10 CS-137 <4.284 -0.9515 2.692 4.284 pCi/L U MW-19 12/15/2016 9:10 BA-140 <19.77 7.136 11.23 19.77 pCi/L U MW-19 12/15/2016 9:10 LA-140 <6.931 1.399 4.006 6.931 pCi/L U MW-10 12/15/2016 10:56 H-3 (DIST) <278 -87.1 163 278 pCi/L U MW-10 12/15/2016 10:56 MN-54 <4.886 -1.751 3.18 4.886 pCi/L U MW-10 12/15/2016 10:56 CO-58 <5.224 -0.8031 3.259 5.224 pCi/L U MW-10 12/15/2016 10:56 FE-59 <9.767 -3.625 6.615 9.767 pCi/L U MW-10 12/15/2016 10:56 CO-60 <6.067 2.487 3.25 6.067 pCi/L U MW-10 12/15/2016 10:56 ZN-65 <11.24 0.8285 7.895 11.24 pCi/L U MW-10 12/15/2016 10:56 NB-95 <6.63 3.8 3.624 6.63 pCi/L U MW-10 12/15/2016 10:56 ZR-95 <9.529 2.821 5.402 9.529 pCi/L U MW-10 12/15/2016 10:56 I-131 <10.59 3.022 6.21 10.59 pCi/L U MW-10 12/15/2016 10:56 CS-134 <5.091 0.8006 3.357 5.091 pCi/L U MW-10 12/15/2016 10:56 CS-137 <4.654 -2.638 3.094 4.654 pCi/L U MW-10 12/15/2016 10:56 BA-140 <26.03 -2.318 16.47 26.03 pCi/L U MW-10 12/15/2016 10:56 LA-140 <9.431 0.002815 5.734 9.431 pCi/L U MW-12 12/15/2016 12:16 H-3 (DIST) <284 173 184 284 pCi/L U MW-12 12/15/2016 12:16 MN-54 <5.689 2.031 3.248 5.689 pCi/L U MW-12 12/15/2016 12:16 CO-58 <5.577 -1.033 3.444 5.577 pCi/L U MW-12 12/15/2016 12:16 FE-59 <10.63 1.346 6.357 10.63 pCi/L U MW-12 12/15/2016 12:16 CO-60 <5.292 -0.4295 3.229 5.292 pCi/L U MW-12 12/15/2016 12:16 ZN-65 <10.72 -2.71 8.186 10.72 pCi/L U MW-12 12/15/2016 12:16 NB-95 <6.645 3.582 4.251 6.645 pCi/L U MW-12 12/15/2016 12:16 ZR-95 <10.09 2.99 5.786 10.09 pCi/L U MW-12 12/15/2016 12:16 I-131 <10.12 0.6402 6.023 10.12 pCi/L U MW-12 12/15/2016 12:16 CS-134 <5.736 2.589 3.836 5.736 pCi/L U MW-12 12/15/2016 12:16 CS-137 <5.504 0.7189 3.332 5.504 pCi/L U MW-12 12/15/2016 12:16 BA-140 <26.11 -6.914 16.48 26.11 pCi/L U MW-12 12/15/2016 12:16 LA-140 <8.337 -2.81 5.46 8.337 pCi/L U MW-14 12/15/2016 13:27 H-3 (DIST) <284 -16.4 171 284 pCi/L U MW-14 12/15/2016 13:27 MN-54 <4.008 -0.7718 2.485 4.008 pCi/L U MW-14 12/15/2016 13:27 CO-58 <4.05 -1.693 2.602 4.05 pCi/L U MW-14 12/15/2016 13:27 FE-59 <8.036 -4.262 5.472 8.036 pCi/L U MW-14 12/15/2016 13:27 CO-60 <4.283 0.858 2.527 4.283 pCi/L U 69

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Station Collection Date Analysis Result Activity Error MDC Units Flag MW-14 12/15/2016 13:27 ZN-65 <8.709 2.317 5.729 8.709 pCi/L U MW-14 12/15/2016 13:27 NB-95 <4.426 0.8629 2.554 4.426 pCi/L U MW-14 12/15/2016 13:27 ZR-95 <6.733 -0.8121 4.099 6.733 pCi/L U MW-14 12/15/2016 13:27 I-131 <8.154 5.114 4.546 8.154 pCi/L U MW-14 12/15/2016 13:27 CS-134 <4.057 -1.91 3.117 4.057 pCi/L U MW-14 12/15/2016 13:27 CS-137 <4.799 0.4857 2.944 4.799 pCi/L U MW-14 12/15/2016 13:27 BA-140 <21.21 5.968 12.47 21.21 pCi/L U MW-14 12/15/2016 13:27 LA-140 <6.874 1.45 3.917 6.874 pCi/L U DUP-MW-14 12/15/2016 13:33 H-3 (DIST) <279 -39.2 166 279 pCi/L U DUP-MW-14 12/15/2016 13:33 MN-54 <5.264 1.153 3.136 5.264 pCi/L U DUP-MW-14 12/15/2016 13:33 CO-58 <5.098 -0.7163 3.249 5.098 pCi/L U DUP-MW-14 12/15/2016 13:33 FE-59 <10.28 -4.061 6.665 10.28 pCi/L U DUP-MW-14 12/15/2016 13:33 CO-60 <4.654 0.5765 2.72 4.654 pCi/L U DUP-MW-14 12/15/2016 13:33 ZN-65 <10.82 -16.61 8.308 10.82 pCi/L U DUP-MW-14 12/15/2016 13:33 NB-95 <6.344 4.89 3.443 6.344 pCi/L U DUP-MW-14 12/15/2016 13:33 ZR-95 <8.65 0.2613 5.32 8.65 pCi/L U DUP-MW-14 12/15/2016 13:33 I-131 <9.727 -2.564 6.034 9.727 pCi/L U DUP-MW-14 12/15/2016 13:33 CS-134 <5.052 -34.67 5.396 5.052 pCi/L U DUP-MW-14 12/15/2016 13:33 CS-137 <6.091 0.7584 3.677 6.091 pCi/L U DUP-MW-14 12/15/2016 13:33 BA-140 <24.53 -3.152 15.28 24.53 pCi/L U DUP-MW-14 12/15/2016 13:33 LA-140 <8.623 0.9452 5.114 8.623 pCi/L U MW-17 12/15/2016 14:53 H-3 (DIST) <280 250 186 280 pCi/L U MW-17 12/15/2016 14:53 MN-54 <5.231 -1.919 3.508 5.231 pCi/L U MW-17 12/15/2016 14:53 CO-58 <5.183 -0.3249 3.265 5.183 pCi/L U MW-17 12/15/2016 14:53 FE-59 <12.83 -0.4999 7.771 12.83 pCi/L U MW-17 12/15/2016 14:53 CO-60 <4.476 -0.2929 2.773 4.476 pCi/L U MW-17 12/15/2016 14:53 ZN-65 <9.903 -6.077 6.886 9.903 pCi/L U MW-17 12/15/2016 14:53 NB-95 <6.08 0.1819 3.741 6.08 pCi/L U MW-17 12/15/2016 14:53 ZR-95 <10.62 3.027 6.176 10.62 pCi/L U MW-17 12/15/2016 14:53 I-131 <14.92 0.6499 8.947 14.92 pCi/L U MW-17 12/15/2016 14:53 CS-134 <5.135 -7.839 3.909 5.135 pCi/L U MW-17 12/15/2016 14:53 CS-137 <5.773 3.25 3.144 5.773 pCi/L U MW-17 12/15/2016 14:53 BA-140 <34.56 8.445 20.19 34.56 pCi/L U MW-17 12/15/2016 14:53 LA-140 <7.909 -6.368 6.362 7.909 pCi/L U 70

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Appendix C METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS 71

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 REPORT CATEGORY: METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS REG. GUIDE 1.21 TABLE 4A WS/WD Joint Frequency Distribution (percent)

WS (MPH), WD (Sect), JFD (%)

57 Meter Period 01/01/2016 - 12/31/2016 WS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Freq Lim/Dir.

2 1.19 0.87 1.42 2.11 1.68 1.35 1.06 0.73 0.56 0.60 0.48 0.68 0.73 0.94 0.56 0.38 15.34 4 0.27 0.60 1.09 1.76 1.76 1.53 1.18 0.62 0.53 0.31 0.26 0.37 0.62 0.71 0.23 0.27 12.11 6 0.38 0.66 1.48 3.83 3.02 2.08 1.43 1.28 0.72 0.43 0.21 0.34 0.82 1.03 0.52 0.31 18.56 8 0.32 0.56 1.21 2.51 3.03 1.98 1.61 1.50 1.12 0.60 0.22 0.25 0.47 1.43 0.45 0.29 17.55 10 0.31 0.41 0.55 0.81 2.37 1.32 1.05 1.59 1.21 0.68 0.18 0.08 0.33 1.79 0.60 0.27 13.55 15 0.30 0.21 0.08 0.18 1.85 1.71 0.60 1.08 0.81 0.34 0.27 0.16 0.42 2.27 1.04 0.85 12.17 20 0.00 0.00 0.01 0.02 0.09 0.52 0.06 0.03 0.01 0.00 0.06 0.07 0.16 0.66 0.63 0.08 2.40

>20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.03 0.45 0.21 0.00 0.70 Freq 2.77 3.31 5.84 11.23 13.82 10.49 6.99 6.85 4.97 2.95 1.68 1.95 3.59 9.27 4.22 2.45 92.38 72

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 REPORT CATEGORY: METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS REG. GUIDE 1.21 TABLE 4B 57 Meter 10 Meter Sigma Delta Wind Wind Dew Wind Wind Dew Temperature Theta Temp Direction Speed Point Direction Speed Point (Deg C)

(Deg) (Deg C) (Deg) (MPH) (Deg C) (Deg) (MPH) (Deg C)

Maximum 34.57 4.90 359.49 26.11 23.83 359.92 23.60 25.18 43.91 Minimum 0.00 -5.00 0.00 0.00 -50.00 0.00 0.00 -50.00 -50.00 Sigma 3.52 1.65 95.52 4.20 10.49 93.14 2.90 11.51 10.67 Average 4.59 -0.47 154.36 6.49 6.13 144.81 3.85 7.81 18.18 Percent 92.40% 92.40% 92.40% 92.40% 92.40% 99.76% 94.08% 99.76% 99.76%

Sigma Theta Delta T Stability Percent Percent Stability Class Class A 10.17 A 10.17 B 0.74 B 0.74 C 0.79 C 0.79 D 34.67 D 34.67 E 36.73 E 36.73 F 8.78 F 8.78 G 0.50 G 0.50 Total 92.38 Total 92.38 73

ANO-1 & 2 RADIOACTIVE EFFLUENT REPORT 2016 Appendix D REVISED OFFSITE DOSE CALCULATION MANUAL 74

ARKANSAS NUCLEAR ONE OFFSITE DOSE CALCULATION MANUAL REVISION 27 Changes are indicated by beginning the affected information with a revision bar on the right side of the page which stops at the end of the change. Deletions of entire paragraphs or sections have a revision bar to the right of the page where text was deleted. The amendment number is indicated at the bottom of the affected page near the left margin and indicates the latest revision to the information contained on that page. Absence of a revision bar on a replacement page means the page was reprinted for word processing purposes only. However, general formatting changes may have been made to all pages.

ARKANSAS NUCLEAR ONE ODCM TABLE OF CONTENTS Section Title Page

1.0 INTRODUCTION

..............................................................................................................5 2.0 LIQUID EFFLUENTS .......................................................................................................5 2.1 Radioactive Liquid Effluent Monitor Setpoint ........................................................5 2.2 Liquid Dose Calculation ........................................................................................7 2.2.1 Dose Calculations for Aquatic Foods.....................................................7 2.2.2 Dose Calculations for Potable Water .....................................................9 2.3 Liquid Projected Dose Calculation .....................................................................10 3.0 GASEOUS EFFLUENTS................................................................................................10 3.1 Gaseous Monitor Setpoints ................................................................................10 3.1.1 Batch Release Setpoint Calculations...................................................10 3.1.2 Eberline SPING (Final Effluent) Monitor Setpoint Calculations ...........11 3.2 Airborne Release Dose Rate Effects ..................................................................13 3.2.1 Noble Gas Release Rate .....................................................................13 3.2.2 I-131, Tritium and Particulate Release Dose Rate Effects ..................15 3.3 Dose Due to Noble Gases ..................................................................................15 3.3.1 Beta and Gamma Air Doses from Noble Gas Releases ......................15 3.4 Dose Due to I-131, Tritium and Particulates in Gaseous Effluents ....................16 3.4.1 Total Dose from Atmospherically Released Radionuclide ...................17 3.5 Gaseous Effluent Projected Dose Calculation ...................................................24 3.6 Dose to the Public Inside the Site Boundary ......................................................24 3.6.1 Liquid Releases ...................................................................................24 3.6.2 Airborne Release .................................................................................25 4.0 ENVIRONMENTAL SAMPLING STATIONS - RADIOLOGICAL ...................................26 5.0 REPORTING REQUIREMENTS ....................................................................................27 5.1 Annual Radiological Environmental Operating Report .......................................27 5.2 Radioactive Effluent Release Report .................................................................28 Revision 27 2

ARKANSAS NUCLEAR ONE ODCM TABLE OF CONTENTS (continued)

Figure Title Page FIGURE 4-1 Radiological Sample Stations (Far Field) ....................................................30 FIGURE 4-1A Radiological Sample Stations (Near Field) .................................................31 FIGURE 4-1B Radiological Sample Stations (Site Map) ....................................................32 FIGURE 4-2 Maximum Area Boundary for Radioactive Release Calculation (Exclusion Areas) ........................................................................................33 Table Title Page TABLE 4-1 Environmental Sampling Stations - Radiological ........................................34 APPENDIX 1 RADIOLOGICAL EFFLUENT CONTROLS Section Title Page 1.0 DEFINITIONS ................................................................................................................40 2.0 LIMITATION AND SURVEILLANCE APPLICABILITY ...................................................43 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ........45 2.1.1 Radioactive Liquid Effluent Monitoring Instrumentation..........................45 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION...48 2.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation .....................48 2.3 RADIOACTIVE LIQUID EFFLUENTS ..................................................................53 2.3.1 Liquid Radioactive Material Release ......................................................53 2.4 RADIOACTIVE GASEOUS EFFLUENTS ............................................................57 2.4.1 Gaseous Radioactive Material Release..................................................57 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING ..........................................62 2.5.1 Sample Locations ...................................................................................62 2.5.2 Land Use Census ...................................................................................70 2.5.2 Interlaboratory Comparison Program .....................................................72 Revision 27 3

ARKANSAS NUCLEAR ONE ODCM APPENDIX 1 RADIOLOGICAL EFFLUENT CONTROLS BASES Section Title Page B 2.0 LIMITATION AND SURVEILLANCE APPLICABILITY..................................................73 B 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ....76 B 2.1.1 Radioactive Liquid Effluent Monitoring Instrumentation .................76 B 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..............................................................81 B 2.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation ............81 B 2.3 RADIOACTIVE LIQUID EFFLUENTS .............................................................87 B 2.3.1 Liquid Radioactive Material Release .............................................87 B 2.4 RADIOACTIVE GASEOUS EFFLUENTS........................................................93 B 2.4.1 Gaseous Radioactive Material Release .........................................93 B 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING .....................................98 B 2.5.1 Sample Locations ..........................................................................98 B 2.5.2 Land Use Census ........................................................................101 B 2.5.3 Interlaboratory Comparison Program...........................................103 Revision 27 4

ARKANSAS NUCLEAR ONE ODCM

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) provides guidance for making release rate and dose calculations for radioactive liquid and gaseous effluents from Arkansas Nuclear One -

Units 1 and 2 (ANO-1 and ANO-2). The methodology is drawn from NUREG-0133, Rev. 0.

Parameters contained within this manual were taken from NUREG-0133 and Regulatory Guide (RG) 1.109 except as noted for site specific values. These numbers and the calculational method may be changed as provided for in the Technical Specifications (TSs).

The following references are utilized in conjunction with the limitations included in this manual concerning the indicated subjects:

Subject ANO-1 ANO-2 Process Control Program (PCP) EN RW-105 EN RW-105 Radioactive Effluent Controls Program TS 5.5.4 TS 6.5.4 Annual Radiological Environmental Monitoring Report TS 5.6.2 TS 6.6.2 Radioactive Effluent Release Report TS 5.6.3 TS 6.6.3 ODCM TS 5.5.1 TS 6.5.1 2.0 LIQUID EFFLUENTS 2.1 Radioactive Liquid Effluent Monitor Setpoint ODCM Limitation L 2.1.1, Radioactive Liquid Effluent Instrumentation, requires that the radioactive liquid effluents be monitored with the alarm/trip setpoints adjusted to ensure that the limits of the radioactive liquid effluent concentration limitations are not exceeded. These concentrations are for the site. The alarm/trip setpoint on the liquid effluent monitor is dependent upon the dilution water flow rate, radwaste tank flow rate, isotopic composition of the radioactive liquid to be discharged, a gross gamma count of the liquid to be discharged, background count rate of the monitor, and the efficiency of the monitor. Due to the fact that these are variables, an adjustable setpoint is used. The setpoint must be calculated and the monitor setpoint set prior to the release of each batch of radioactive liquid effluents. The following methodology is used for the setpoint determination for the following monitors.

ANO-1: RE-4642 - Liquid Radwaste Monitor ANO-2: 2RE-2330 - Liquid Radwaste Monitor 2RE-4423 - Liquid Radwaste Monitor

1) A sample from each tank (batch) to be discharged is obtained and counted for gross gamma (Cs-137 equivalent) and a gamma isotopic analysis is performed.

2) A dilution factor (DF) for the tank is calculated based upon the results of the gamma isotopic analysis and the Maximum Permissible Concentration (MPC) of each detected radionuclide.

Revision 27 5

ARKANSAS NUCLEAR ONE ODCM DF is calculated as follows:

DF = i(Ci/MPCi) + CTNG/MPCTNG where:

DF = dilution factor; Ci = concentration of isotope i, (µCi/ml);

MPCi = maximum permissible concentration of isotope i, (from 10 CFR 20, Appendix B, Table II, Column 2 in µCi/ml);

CTNG = total concentration of noble gases (µCi/ml); and MPCTNG = 2 x 10-4 (µCi/ml) per Limitation L 2.3.1.a

3) The dilution water flowrate is normally the number of ANO-1 circulating water pumps in operation at the time of release. Each circulating water pump has an approximate flowrate of 191,500 gallons per minute (gpm) (this flowrate may be reduced due to throttling of circulating water pump flow and/or circulating water bay configuration).

However, under specific conditions and under strict controls, lower dilution water flowrates utilizing service water and cooling tower blowdown flowrates may be used.

4) The theoretical release rate, Fm, of the tank (batch) to be released is expressed in terms of the dilution water flowrate, such that for each volume of dilution water released, a given volume of liquid radwaste may be combined. This may be expressed as follows:

Fm = DV/DF where:

Fm = theoretical release rate (gpm);

DV = Dilution volume (gpm). When ANO-1 circulating water pumps are running, DV is the number of ANO-1 circulating water pumps in operation multiplied by the approximate flowrate of an ANO-1 circulating water pump (normally 191,500 gpm) or an indicated flow rate. The minimum total flow rate shall be greater than or equal to 100,000 gpm. Otherwise DV is dilution volume provided by service water and cooling tower blowdown flowrate; and DF = dilution factor as calculated in Step 2 above.

Note: In the above equation, the theoretical release rate (Fm) approaches zero as the dilution factor increases. The actual flowrate (FA) will normally be equal to the theoretical release rate for high activity releases. For low activity releases, the theoretical release rate becomes large and may exceed the capacity of the pump discharging the tank. In these cases, the actual release rate may be set to the maximum flowrate of the discharge pump.

5) The monitor setpoint is calculated by incorporating the monitor reading prior to starting the release (i.e., background countrate), and a factor which is the amount of increase in the release concentration that would be needed to exceed the radioactive liquid concentration limitation. The monitor setpoint is expressed as follows:

Revision 27 6

ARKANSAS NUCLEAR ONE ODCM ML = A*(K*FM/FA) + B where:

ML = monitor setpoint (counts per minute or cpm);

A = allocation fraction for the specific unit. (Typically, these values are set at 0.45, but may be adjusted up or down as needed. However, the total site allocation can not exceed 1.0.)

K = monitor countrate (cpm) expected based on the gross activity of the release (this value is obtained from a graph of activity (µCi/ml) versus output countrate for the monitor (cpm));

FM/FA = number of times the activity would have to increase to exceed the radioactive liquid effluent-concentration limitation; and B = background countrate (cpm) prior to the release.

To permit the computer to calculate the setpoint, an equation for the expected countrate (K) is expressed as follows:

K = Offset

SASlope where:

Log of the detector response in cpm Slope =

Log of activity concentration in Ci/ml SA = Gross gamma (Cs-137 equivalent) activity for the tank (Ci/ml); and Offset = detector response (cpm) for the minimum detectable sample activity calculated from the calibration data.

Note: I&C personnel use varying concentrations of Cs-137 to determine the response curve; therefore, a Cs-137 equivalent activity must be used to accurately predict the countrate.

Combining terms, the equation for determining the monitor setpoint may be expressed as follows:

ML = A[(Offset

SASlope)FM/FA] + B 2.2 Liquid Dose Calculation The dose or dose commitment to an individual in the unrestricted area shall be less than or equal to the limits specified in Radioactive Liquid Effluents - Dose Limitations. The dose limits are on a per reactor basis. This value is calculated using the adult as the maximum exposed individual via the aquatic foods (Sport Freshwater Fish) and the potable water pathways.

2.2.1 Dose Calculations for Aquatic Foods The concentrations of radionuclides in aquatic foods are assumed to be directly related to the concentrations in water. The equilibrium ratios between the two concentrations are called bioaccumulation factors.

Revision 27 7

ARKANSAS NUCLEAR ONE ODCM Two different pathways are calculated for aquatic foods: sport and commercial freshwater fish.

The internal dose d from the consumption of aquatic foods in pathway p to organ j of individuals of age group a from all nuclides i is computed as follows (see Chapter 4 of NUREG-0133 and RG 1.109-12, equation A-3):

dp (r,,a,j) = i[{(1100)(e -itp )(Bi)}(M)(Ua)(F) (Qi)(Daij)]

-1 The total dose from both aquatic food pathways is then:

D(r,,a,j) = dp (r,,a,j)

P where:

r = user-selected distance from the release point to the receptor location, in kilometers.

It may be different from the controlling distance specified for the potable water pathway (0.4 km);

= user-selected sector (one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc.). This sector may be different from the controlling sector specified for the potable water pathway (S);

A = user-selected age group: infant, child, teen, adult. It is the same controlling age group used in the potable water pathway (adult);

J = user-selected organ: bone, liver, total body, thyroid, kidney, lung, GI-LLI. It is the same controlling organ used in the potable water pathway (liver);

{} = represents the concentration factor stored in the database; Note: Only one concentration factor is needed to represent the two pathways since sport and commercial use the same bioaccumulation factor for a given pathway.

1100 = factor to convert from (Ci/yr)/(ft3/sec) to Ci/liter; i = decay constant of nuclide i in hr-1; tp = environmental transit time, release to receptor; Note: This value should be set to 0 hours0 days 0 hours 0 weeks 0 months (i.e., no decay correction) for the above equation in order to be consistent with the equation presented in Chapter 4 of NUREG-0133. For maximum individual dose calculations, this value is set to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , which is the minimum transit time recommended by RG 1.109, Appendix A, 2.b.

Bi = bioaccumulation factor for nuclide i, in Ci/kg per Ci/liter. Cesium has a site specific number based on carnivorous and bottom feeder sport fish of 400 Ci/kg per Ci/liter (0CAN048408, dated April 13, 1984); Niobium has a site specific number based upon freshwater fish of 300 Ci/kg per Ci/liter.

M = dimensionless mixing ratio (reciprocal of the dilution factor) at the point of exposure; Revision 27 8

ARKANSAS NUCLEAR ONE ODCM Ua = annual usage factor that specifies the intake rate for an individual of age group a, in kilograms/year. The program selects this usage factor in accordance with the controlling age group a as specified previously by the user; F = average flow rate in ft3/sec. This value is based on total dilution volume for the quarter divided by time into the quarter; Qi = number of curies of nuclide i released; and Daij = ingestion dose factor for age group a, nuclide i, and organ j, in mrem per Ci ingested. The program selects the ingestion dose factor according to the user-specified controlling age group a and controlling organ j.

2.2.2 Dose Calculations for Potable Water The dose D from ingestion of water to organ j of individuals of age group a due to all nuclides i is calculated as follows (See Chapter 4 of NUREG-0133 and NRC RG 1.109-12, equation A-2):

Note: The potable water pathway is used only during the time that the Russellville Water System is using the Arkansas River as a water source. The Russellville Water Works will notify ANO when they are using the Arkansas River as a water source.

D (r,,a,j) = i [{(1100)(e -itp )}(M)(Ua)(F )(Qi)(Daij)]

-1 where:

r = user-selected distance (0.4 km) from the release point to the receptor location, in kilometers. It may be different from the controlling distance selected for the aquatic food pathway;

= user-selected sector; (one of the sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc.). It may be different from the controlling sector for the aquatic food pathway; a = user-selected age group (infant, child, teen, adult). The same controlling age group is used for all liquid pathways (adult);

j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI). The same controlling organ is used for all liquid pathways (liver).

{} = the expression in brackets represents the concentration factor stored in the database; 1100 = factor to convert from (Ci/yr)/(ft3/sec) to Ci/liter; M = dimensionless mixing ratio (reciprocal of the dilution factor) at the point of exposure; i = decay constant of nuclide i in hr-1; and tp = environmental transit time, release to receptor.

Note: This value is set to 0 hours0 days 0 hours 0 weeks 0 months (i.e., no decay correction) for the above equation to be consistent with the equation presented in Chapter 4 of NUREG-0133.

Revision 27 9

ARKANSAS NUCLEAR ONE ODCM Ua = annual usage factor that specifies the intake rate for an individual of age group a, in liters/year. The program selects this usage factor according to the user-specified controlling age group a; F = average flow rate in ft3/sec; this value is based on total dilution volume for one quarter divided by time into the quarter; Qi = number of curies of nuclide i in the release; and Daij = ingestion dose factor, for age group a, nuclide i, and organ j, in mrem per Ci ingested. The program selects the ingestion dose factor according to the user-specified controlling age group a and controlling organ j.

2.3 Liquid Projected Dose Calculation The quarterly projected dose is based upon the methodology of Section 2.2 and is expressed as follows:

DQP = 92(DQC + DRP)/T where:

DQP = quarterly projected dose (mrem);

92 = number of days per quarter; DQC = cumulative dose for the quarter (mrem);

DRP = dose for current release (mrem); and T = current days into quarter; 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Monitor Setpoints Note: Sections 3.1.1 and 3.1.2 below detail two methods of calculating setpoints at ANO.

These methods cover two different sets of monitors of which only one will be in-service at any one time.

3.1.1 Batch Release Setpoint Calculations 3.1.1.a This section applies to the following gaseous radiation monitors (these releases are also monitored by the SPING monitors in Section 3.1.2):

ANO-1: RE-4830 - Waste Gas Holdup System Monitor*

RX-9820 - Reactor Building Purge and Ventilation SPING ANO-2: 2RE-8233 - Containment Building Purge Monitor*

2RE-2429 - Waste Gas Holdup System Monitor*

2RX-9820 - Containment Building Purge and Ventilation SPING

These monitors provide automatic isolation.

Revision 27 10

ARKANSAS NUCLEAR ONE ODCM The setpoints to be used during a batch type of release (i.e., Reactor Building

[Containment] Purge, release from the Waste Gas Holdup System or any other non-routine release) will be calculated for each release before it occurs.

3.1.1.b The basic methodology for determining a monitor setpoint is based upon the expected concentration at the monitor (CM). This is in turn based upon the fraction of an MPC assigned to this release point. Batch releases are maintained below the assigned MPC fraction by controlling the release rate. The calculated value of S may not exceed the equivalent of 1 MPC at site boundary. If value of S for RX (2RX) -9820 is less than SPING Channel 5 high alarm setpoint, then the high alarm setpoint may be used as a default value. If the value of S for RE-4830 and 2RE-2429 is less than 50,000 cpm, then 50,000 cpm may be used as a minimum setpoint. If the value of S for 2RE-8233 is less than 1,000 cpm, then 1,000 cpm may be used as a minimum setpoint.

S = 1.2(CM)(K) + (2.0)(B) where:

S = monitor setpoint (cpm);

CM = Xe-133 equivalent concentration at the monitor (Ci/ml);

K = conversion factor determined from response curve of monitor (cpm per Ci/ml). This value is 1.0 when calculating S for RX (2RX) -9820.

2.0 = factor to accommodate random count rate fluctuations; B = background count rate at the monitor (cpm).

1.2 = Safety Factor to correct for instrument uncertainties.

3.1.2 Eberline SPING (Final Effluent) Monitor Setpoint Calculations 3.1.2.a This section applies to the following gaseous radiation monitors:

ANO-1: RX-9820 - Reactor Building Purge and Ventilation SPING RX-9825 - Auxiliary Building Ventilation SPING RX-9830 - Spent Fuel Pool Area Ventilation SPING RX-9835 - Emergency Penetration Room Ventilation SPING ANO-2: 2RX-9820 - Containment Building Purge and Ventilation SPING 2RX-9825 - Auxiliary Building Ventilation SPING 2RX-9830 - Spent Fuel Pool Area Ventilation SPING 2RX-9835 - Emergency Penetration Room Ventilation SPING 2RX-9845 - Auxiliary Building Extension Ventilation SPING 2RX-9850 - Radwaste Storage Building Ventilation SPING The determination of setpoints for the above monitors is based on an assigned fraction of the MPC of noble gas activity at the site boundary (Xe-133 equivalent) released from the above release points. The total of these fractions is always less than 1.00. The assigned fractions are based on the vent flow rates, atmospheric dilution rate, and the ventilation system(s) in operation.

Revision 27 11

ARKANSAS NUCLEAR ONE ODCM Note: The fact that an effluent monitor is in alarm does not necessarily mean that radioactive gases are being released at such a rate that the MPC limit is being exceeded. The alarm would indicate that radioactive gases are being released at a rate that is exceeding the fractional allocation of an MPC allotted to that particular release point. Consideration must be given to the release rate of radioactive gases via all of the release pathways.

The initial fractions of an MPC allocated to the release points are given below. The allocations may be changed as needed, to allow for operational transients, but may not exceed a site total of 1.00.

Monitor Number Monitor Name Fractional Allocation RX-9820 Reactor Building Purge and Ventilation 0.1000 RX-9825 Auxiliary Building Ventilation 0.2000 RX-9830 Spent Fuel Pool Area Ventilation 0.1500 RX-9835 Emergency Penetration Room Ventilation 0.0001 Monitor Number Monitor Name Fractional Allocation 2RX-9820 Containment Building Purge and Ventilation 0.1000 2RX-9825 Auxiliary Building Ventilation 0.2000 2RX-9830 Spent Fuel Pool Area Ventilation 0.1500 2RX-9835 Emergency Penetration Room Ventilation 0.0001 2RX-9840 PASS Building Ventilation 0.0100 2RX-9845 Auxiliary Building Extension Ventilation 0.0100 2RX-9850 Radwaste Storage Building Ventilation 0.0100 Note: The setpoints to be used during a batch release (i.e., Reactor Building

[Containment] Purge or Waste Gas Holdup System) will be calculated for each release before it occurs.

3.1.2.b SPING monitor setpoints may be calculated as follows:

Xe-133 eq (µCi/cc)

Setpoint (Ci/cc) =A F(9.4390E-9)(TMPC) where:

A = allocation fraction (the fraction of an MPC at the site boundary (of noble gas Xe-133 eq activity) assigned to the particular release point);

Xe-133 eq = Xenon-133 equivalent concentration; F = discharge flow of the particular release point in cubic feet per minute (cfm) 2.0E-5(sec/m3) 9.4390E-9 = 2.8317E-2(cm/cf) 60(sec/min)

Revision 27 12

ARKANSAS NUCLEAR ONE ODCM where:

2.0E-5 = the annual average gaseous dispersion factor (corrected for radioactive decay) as defined in Section 2.3 of the ANO-1/ANO-2 Safety Analysis Report (SAR); and TMPC = total MPCs at site boundary.

3.2 Airborne Release Dose Rate Effects 3.2.1 Noble Gas Release Rate 3.2.1.a To calculate the noble gas release dose rate, the average ground-level concentration of radionuclide i at the receptor location must first be determined from the following equation (see RG 1.109-20 equation B-4).

xi () = (3.17 x 104)(Qi)[D1X/Q()]

where:

xi () = average ground level concentration in Ci/m3 of nuclide i at the user-specified controlling distance in sector (1.05 km);

() = one of the sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

3.17 x 104 = number of Ci per Ci divided by the number of seconds/year; Qi = release rate of nuclide i in curies/yr and D1X/Q() = annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle at the receptor location in sec/m3. This value is 2.0E-5 sec/m3 for short term releases.

The annual dose to the total body and skin due to noble gas can be calculated according to Sections 3.1.2.b and 3.2.1.c.

3.2.1.b Annual Total Body Dose Rate The annual average total body dose rate to the maximally exposed individual is calculated as follows:

DT() = (RBPF)(SF)(i [xi()

DFBi]

where:

DT() = total body dose rate due to immersion in a semi-infinite cloud of gas at the controlling distance in sector , in mrem/yr. The program computes one total body dose rate value for each sector in which the user has specified a controlling distance and reports only the maximum value;

= one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

Revision 27 13

ARKANSAS NUCLEAR ONE ODCM RBPF = Reactor Building (Containment) Purge Factor - This factor is used to calculate the length of time (fractional duty cycle) that the purge fans will be in operation. It is calculated by comparing the highest dose rate (DOSER) to its applicable release limit, taking into account the allocation factor for the release point (RBPF = Allocation

Limit/DOSER). This factor is calculated only for ANO-1 and ANO-2 Reactor Building (Containment) purges. For all other releases, this factor is set to 1.0; SF = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The NRC recommended value is 0.7 (for maximum individual) xi() = average ground-level concentration of nuclide i at the receptor location in the sector at angle from the release point, as defined in Section 3.2.1.a; and DFBi = total body dose factor for a semi-infinite cloud of radionuclide i, which includes the attenuation of 5 g/cm² of tissue, in mrem-m3/Ci-yr 3.2.1.c Annual Skin Dose Rate The annual dose rate to the skin of the maximally exposed individual due to noble gases is calculated as follows (see RG 1.109-20 equation B-9):

DS() = RBPF[(1.11)(SF)(i(xi())(DFi) + i(xi())(DFSi)]

where:

DS() = skin dose due to immersion in a semi-infinite cloud of gas at the user-specified controlling distance in sector , in mrem; Note: The program computes a skin dose value for each sector in which the user as specified a controlling distance, but prints out only the maximum value.

RBPF = Reactor Building [Containment] Purge Factor as defined in Section 3.2.1.b.

1.11 = average ratio of tissue to air energy absorption coefficient; SF = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The value is 0.7 (for maximum individual);

xi() = is the average ground-level concentration of nuclide i at the receptor location in the sector at angle from the release point, as defined in Section 3.2.1;

= one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

DF = gamma air dose factor for a semi-infinite cloud of radionuclide i, in mrad-m3/Ci-yr; and DFSi = beta skin dose factor for a semi-infinite cloud of radionuclide i, which includes the attenuation by the outer dead layer of skin, in mrem-m3/Ci-yr.

Revision 27 14

ARKANSAS NUCLEAR ONE ODCM 3.2.2 I-131, Tritium and Particulate Release Dose Rate Effects The annual dose rate to the maximally exposed individual for I-131, tritium and radionuclides in particulate form with half-lives greater than eight days is calculated as follows:

DRTOT = (RBPF)(DRI + DRG + DRM) where:

RBPF = Reactor Building (Containment) Purge Factor as defined in Section 3.2.1.b; I

DR = dose rate to the controlling age group (infant) associated with the inhalation of radioiodines and particulates, as calculated in Section 3.4.1.b; DRG = dose rate from direct exposure to activity deposited on the ground plane, as calculated in Section 3.4.1.a; and DRM = dose rate to the controlling age group (infant) and the controlling organ for ingestion of food (milk), as calculated in Section 3.4.1.d.

Calculation of the annual dose rate considers the infant as the most restrictive age group. The organs that are considered as contributing to the dose rate are: skin, bone, liver, total body, thyroid, kidney, lung, and GI-LLI. The food pathway for the infant is considered to be from milk only. All three pathways will contribute to the total body dose, while the skin will be affected by only the ground plane pathway. The other organs are affected only by the inhalation and food pathways.

3.3 Dose Due to Noble Gases The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation for any calendar quarter for each unit. The objective of less than or equal to 10 mrad of gamma radiation and 20 mrad of beta radiation for a calendar year per unit (2.5 mrad and 5 mrad respectively per quarter) should be used for planning releases.

Note: The following equations have been simplified from equations in NUREG-0133, Revision 0, in that there are no free-standing stacks at ANO. The equations were further simplified in that there are no long term (i.e., continuous) releases. The individual stack vents are sampled weekly, or are assigned a release period of 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months per sample (i.e., considered as short term (batch) releases). Individual samples are to be taken for each waste gas release and Reactor (Containment) Building purge.

3.3.1 Beta and Gamma Air Doses from Noble Gas Releases Using the average ground level concentration of radionuclide i at the receptor location calculated in Section 3.2.1.a, the associated annual gamma or beta air dose may be calculated by the following equation (see RG 1.109-20 equation B-5).

D() or D() = i [(xi())(DFi or DFi)]

where:

D() or D() = the gamma or beta air dose for the controlling distance in sector (only the maximum value is reported), and DFi or DFi = gamma or beta air dose factors for a uniform semi-annual infinite cloud of nuclide i, in mrad-m3/Ci-yr.

Revision 27 15

ARKANSAS NUCLEAR ONE ODCM 3.4 Dose Due to I-131, Tritium, and Particulates in Gaseous Effluents The calculational methodology for determining the dose to an individual from I-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to unrestricted areas as specified in the Limitations is in this section.

The child is the controlling age group unless stated otherwise.

The inhalation and ground plane pathways are considered to exist at all locations. The grass-cow-milk, grass-cow-meat, and vegetation pathways are used where applicable.

It is assumed that iodines are in the elemental form.

A dispersion parameter of 2.0E-5 sec/m3 (per ANO-1/ANO-2 SAR, Section 2.3) is used for w in the inhalation pathway since the majority of gaseous activity released from the site is within the 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time frame (i.e., Reactor Building [Containment] purges and Waste Gas Decay tanks).

The equation is:

DTOT = DG + DI + DV + DL + DM + DF where:

DTOT = total dose; DG = dose contribution from ground plane deposition as calculated in Section 3.4.1.a; I

D = dose contribution from inhalation of radioiodines, tritium, and particulates (> 8 days) as calculated in Section 3.4.1.b; DV = dose contributions from consumption of vegetation (defined as produce) for humans and stored feed for cattle. See Section 3.4.1.c for calculations; DL dose contributions from consumption of fresh leafy vegetables (defined as garden products) for humans and pasture grass for cattle. See Section 3.4.1.c for calculations; DM = dose contribution from consumption of cow's milk; and Note: Consumption by the cow of both stored feeds and pasture grasses is taken into account when calculating this dose contribution. Concentration factors for both food sources are calculated.

DF = dose contribution from consumption of meat.

Note: Consumption by the cow of both stored feeds and pasture grasses is taken into account when calculating this dose contribution. Concentration factors for both types of animal are calculated.

Revision 27 16

ARKANSAS NUCLEAR ONE ODCM 3.4.1 Total Dose from Atmospherically Released Radionuclide After the calculation of the concentration factors from the applicable parts of Section 3.4.1, the maximum individual dose as calculated for controlling age group a and controlling organ j, in sector at the controlling distance r is given from:

DG(r,,j,a) (Section 3.4.1.a) for ground plane deposition DI(r,,j,a) (Section 3.4.1.b) for inhalation V V DV(r,,j,a) = DFIijaUaCi(r,) for produce i

L L DL(r,,j,a) = DFIijaUaCi(r,) for leafy vegetables i

M M DM(r,,j,a) = DFIijaUaCi(r,) for cow's milk i

F F DF(r,,j,a) = DFIijaUaCi(r,) for meat i

where:

a = controlling age group (infant, child, teen, or adult);

j = controlling organ (bone, liver, total body, thyroid, kidney, lung, or GI-LLI);

r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers (the controlling distance is the same for all airborne pathways, 1.05 km);

= one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

DFIija = dose conversion factor for ingestion of nuclide i, organ j, and age group a, in mrem/Ci; Note: Values used in these tables are taken from Tables E-11 through E-14 of RG 1.109. DFIija is selected according to the controlling organ and age group as specified in the database.

UVa, UaL, UM a, Ua F

= ingestion rates for produce, leafy vegetables, cow's milk, and meat, respectively, for individuals in age group a. Values used are taken from Table E-5 of RG 1.109.);

CVi, DLi, CiM, DiF = concentration of nuclide i for produce, leafy vegetables, cow's milk, and meat, respectively, in Ci/kg or Ci/liter.

The program calculates that maximum individual dose for each sector surrounding the plant in which the user has specified a controlling distance for each of the following pathways: A) ground plane deposition; B) inhalation and the ingestion of; C) produce; D) leafy vegetables; E) cow's milk; and F) meat. Only the receptor point receiving the maximum dose value is printed.

Revision 27 17

ARKANSAS NUCLEAR ONE ODCM 3.4.1.a Dose from Ground Plane Deposition The dose DG from direct exposure to activity deposited on the ground plane is calculated as follows (see RG 1.109-24, equations C-1 and C-2):

- it b DG(R,,j,a) = {(SF)(1.0 x 1012)(i[(i-1)(1 - e )]}(DOQ(r,))(Qi)(DFGij) where:

r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers. The controlling distance is the same for all airborne pathways (1.05 km);

= one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

a = user-selected age group (infant, child, teen, adult) which is the same controlling age group used for all airborne pathways (child);

j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI) which is the same controlling organ used for all airborne pathways;

{} = represents the concentration factor stored in the database; SF = dimensionless attenuation factor accounting for the dose reduction due to shielding by residential structures. The value is 0.7 (for maximum individual);

1.0 x 1012 = number of Ci per Ci; i = decay constant of nuclide i in hr-1; tb = length of time over which the accumulation is evaluated (nominally 15 years which is the approximate midpoint of facility operating life or 1.31 x 105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months );

DOQ(r,) = average relative deposition of the effluent at the receptor location r in sector

, considering depletion of the plume during transport, in m2 (1.7E-8/m2);

Qi = release of nuclide i in curies, and DFGij = open field ground plane dose conversion factor for organ j (total body or skin) from radionuclide i, in mrem-m2/Ci-hr. The dose factor is selected according to the user-specified controlling age group a and controlling organ j.

3.4.1.b Dose from Inhalation of Radionuclides in Air The dose DI to organ j of age group a associated via inhalation of radioiodines and particulates is (see RG 1.109-25, Equations C-3 and C-4):

DI(r,,j,a) = (3.17 x 104)(Ra)(i[(Qi)(D2DPX/Q(r,))(DFAija)]

where:

r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers. The controlling distance is the same for all airborne pathways (1.05 km);

= one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

Revision 27 18

ARKANSAS NUCLEAR ONE ODCM j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI) and is the same controlling organ as that used for all airborne pathways; a = user-selected age group (infant, child, teen, adult) and is the same controlling age group as that used for all airborne pathways; 3.17 x 104 = number of Ci/Ci divided by the number of seconds/year; Ra = annual air intake for individuals in age group a (in m3/year). The air intake factor is selected in accordance with the user-specified controlling age group; Qi = release of nuclide i in curies; D2DPX/Q(r,) = annual average atmospheric dispersion factor of the radionuclide at the receptor location r in sector (in sec/m3) as calculated; and Note: This includes depletion (for radioiodines and particulates) and radioactive decay of the plume.

DFAija = inhalation dose factor for radionuclide i, organ j, and age group a.

The inhalation dose factor is selected in accordance with the user-specified controlling age group a and controlling organ j.

3.4.1.c Dose from Nuclide Concentrations in Vegetation Note: To reduce the computational overhead of the computer, the calculations for dose resulting from nuclide concentrations in forage, produce and leafy vegetables is performed in three steps.

First, the concentration factors (CF) are computed and stored in the database. The concentration factor includes all the parameters that are considered constant for each nuclide and agricultural activity, such as the radioactive decay constant, removal rate constant, exposure time, etc.

Second, the deposition rate from the plume is multiplied by the concentration factor and the nuclide activity to produce the nuclide concentration as follows:

V Ci(r,) = (CFi)(DOQ(r,))(Qi) where:

V Ci(r,) = concentration of nuclide i at the receptor location (r,);

CFi = concentration factor of nuclide i; DOQ(r,) = relative deposition of nuclide i. For the short term dispersion option, DOQ is replaced by (F x DOQ), where F is the short term dispersion correction factor; Qi = quantity of nuclide i released in curies.

For carbon-14 and tritium, the nuclide concentration is calculated from the concentration factor times the decayed and depleted X/Q for radioiodines and particulates (D2DPX/Q), times the quantity of nuclide i released in curies. For the short term dispersion option, D2DPX/Q is replaced by F x D2DPX/Q, where F is the short term dispersion correction factor.

Revision 27 19

ARKANSAS NUCLEAR ONE ODCM V

CT(r,) = (CFT)(D2DPX/Q(r,))(QT) for tritium, and CFV14(r,) = (CF14)(D2DPX/Q(r,))(Q14) for carbon-14 Third, the nuclide concentrations for a particular pathway (produce, leafy vegetables, cow's milk, and meat) are summed and multiplied by: 1) the ingestion rate for a particular age group and

2) the dose conversion factor:

V D(r,,j,a) = i [(DFIija)(Ua)(Ci(r,))]

where:

r = user-selected distance from the release point to the receptor location in a particular sector, in kilometers (1.05 km);

= one of sixteen 22.5° sectors surrounding the reactor site, designated N, NNE, NE, etc. (WNW);

j = user-selected organ (bone, liver, total body, thyroid, kidney, lung, GI-LLI), and is the same controlling organ as that used for all airborne pathways; a = user-selected age group (infant, child, teen, adult), and is the same controlling age group as that used for all airborne pathways; DFIija = dose conversion factor for ingestion of nuclide i, organ j, and age group a, in mrem/Ci, according to the controlling organ and age group; Ua = annual ingestion rate of food in a particular pathway (kilograms/year or liters/year) for individuals in age group a, according to the controlling age group; and V

Ci(r,) = concentration of nuclide i at the receptor location (r,).

3.4.1.c.1 Calculating Vegetation Concentration Factors NUREG-0133 calculations for radioiodines and particulate radionuclides (except tritium and carbon-14), the concentration factor of nuclide i in and on vegetation is estimated as follows:

V r - t CFi = (CONST)( )(e i h)(f)

(Yv)(i) where:

V CFi = concentration factor of radionuclide i in vegetation (forage, produce, or leafy vegetables), in m2-hr/kg; CONST = 1.14 x 108 number of Ci per Ci (1012) divided by the number of hours per year (8760);

r = is the fraction of deposited activity retained on crops, leafy vegetables, or pasture grass, from airborne radioiodine and particulate deposition:

r = 1.00 for radioiodines r = 0.20 for particulates Yv = agricultural productivity (yield or vegetation area density), in kg (wet weight)/m2:

Ys = 2.0 kg/m2 for stored animal feed for grass-animal-man pathways Y = 0.7 kg/m2 for pasture grass for grass-animal-man pathways Revision 27 20

ARKANSAS NUCLEAR ONE ODCM Y1 = 2.0 kg/m2 for leafy vegetation (fresh) for crop/vegetation-man pathways Yg = 2.0 kg/m2 for garden produce (stored vegetables) for crop/vegetation-man pathways i = is the decay constant of nuclide i in hr-1; th = is a holdup time that represents the time interval between harvest and consumption of the food, in hours:

th = 0 hours0 days 0 hours 0 weeks 0 months for pasture grass consumed by animals th = 2160 hours0.025 days 0.6 hours 0.00357 weeks 8.2188e-4 months for stored feed consumed by animals th = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for leafy vegetables consumed by humans th = 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months for produce consumed by humans f = is the fraction of leafy vegetables or produce grown in garden of interest:

f = 0.76 for the fraction of produce ingested, grown in garden of interest (this is fg in equation C-13 of RG 1.109) f = 1.00 for the fraction of leafy vegetables grown in garden of interest (this is f1 in equation C-13 of RG 1.109) f = 1.00 for all other pathways 3.4.1.c.2 Concentration Factor for Carbon-14 For carbon-14, the concentration factor in and on vegetation is estimated as follows (see RG 1.109-26, equation C-8):

CFV14 = (2.2 x 107)()

where:

CFV14 = concentration factor of carbon-14 in and on vegetation, in m2-hr/kg; and

= is defined as the ratio of total annual release time (for C-14 atmospheric releases) to the total annual time during which photosynthesis occurs (taken to be 4400 hours0.0509 days 1.222 hours 0.00728 weeks 0.00167 months ), under the condition that the value of should never exceed unity.

For continuous C-14 releases, is taken to be unity (thus, the value of 2.2 x 107 is stored for CFV14 in lieu of a site specific value for ).

3.4.1.c.3 Concentration Factor for Tritium The concentration factor for tritium in vegetation is calculated from the tritium concentration in air surrounding the vegetation (see RG 1.109-27, equation C-9):

V 1.2 x 107 CF T =

H where:

V CFT = concentration factor for tritium in vegetation (in m2-hr/kg); and H = absolute humidity at the location of the vegetation, in g/m3 (the regulatory default value for H is 8.0 grams/m3).

V Thus, the value 1.5 x 106 is stored for CFT in lieu of a site specific value for H.

Revision 27 21

ARKANSAS NUCLEAR ONE ODCM 3.4.1.c.4 Nuclide Concentrations in Produce and Leafy Vegetables The concentrations in and on produce and leafy vegetables of all radioiodine and particulate nulcides i (except carbon-14 and tritium) are calculated as follows:

CVi(r,) = (CFVi)(DOQ(r,))(Qi) for produce; and CLi(r,) = (CFLi)(DOQ(r,))(Qi) for leafy vegetables where:

CFVi = concentration factor of nuclide i in produce; CFiL = concentration factor of nuclide i in leafy vegetables; L

Note that the difference between CFVi and CFi are the values for th and f1.

DOQ(r,) = relative deposition of the radionuclide i at the receptor (r,); and Qi = release of nuclide i (in curies).

The C-14 and H-3 nuclide concentrations are calculated from the concentration factors times the decayed and depleted radioiodine relative deposition D2DPX/Q times the fraction grown in the garden of interest (fg = 0.76, f1 = 1.0):

CVT(r,) = (CFVT)(D2DPX/Q(r,))(QT)(fg)

CTL(r,) = (CFLT)(D2DPX/Q(r,))(QT)(f1) for tritium V V C14 (r,) = (CF14 )(D2DPX/Q(r,))(Q14)(fg)

C14L (r,) = (CF14L )(D2DPX/Q(r,))(Q14)(f1) for carbon-14 3.4.1.d Nuclide Concentration in Cow's Milk The radionuclide concentration in cow's milk is dependent upon the quantity and contamination level of feed consumed by the animal. The concentration is estimated (see RG 1.109-27, equations C-10 and C-11) as follows:

m - i t f v v1 v1 Ci(r,) = {(Fm)(QF)(e )[(fp)(fs)(CFi) + (1 - fp)(CFi) + (fp)(1 - fs)(CFi)]}(D(r,)(Qi) where:

m Ci(r,) = is the concentration of nuclide i in cow's milk at the receptor location (r,), in Ci/liter;

{} = the expression in brackets represents the concentration factor (note that the concentration factor for cow's milk involves two different vegetation concentration factors (see below));

Fm = average fraction of the cow's daily intake of radionuclide i (which appears in each liter of milk), in days/liter; QF = amount of feed consumed by the cow per day, in kg/day (wet weight);

Revision 27 22

ARKANSAS NUCLEAR ONE ODCM i = decay constant of nuclide i in hr-1; tf = average transport time of the activity from the feed into the milk and to the receptor (a value of 2 days is assumed);

fp = fraction of the year that cows graze on pasture; fs = fraction of daily feed that is pasture grass when the cow grazes on pasture; v

CFi = vegetation concentration factor of nuclide i on pasture grass with the holdup time th = 0 days, in Ci/kg (refer to the explanation of the vegetation concentration factor calculation);

v1 CFi = vegetation concentration factor of nuclide i in stored feeds with the holdup time th = 90 days, in Ci/kg (refer to the explanation of the vegetation concentration factor calculations);

D(r,) = relative deposition DOQ(r,) of the radionuclides, except carbon-14 and tritium.

For carbon-14 and tritium, the decayed and depleted dispersion factor D2DPX/Q(r,) for radioiodines and particulates (in sec/m3) is used; and Qi = is the release of nuclide i in curies.

3.4.1.e Nuclide Concentration in Meat The radionuclide concentration in meat is dependent upon the quantity and contamination level of feed consumed by the animal. The concentration is estimated (see RG 1.109-27, equations C-11 and C-12) as follows:

f -i ts v v1 v1 Ci(r,) = {(Ff)(QF)(e )[(fp)(fs)(CFi) + (1- fp)(CFi) +(fp)(1 - fs)(CFi)]}(D(r,)(Qi) where:

Note: All parameters used in this pathway are for beef cattle.

f Ci(r,) = concentration of nuclide i in animal flesh at the receptor location (r,) in Ci/liter;

{} = the expression in brackets represents the concentration factor (note that the concentration factor for meat involves two different vegetation concentration factors);

Ff = average fraction of the animal's daily intake of radionuclide i which appears in each kilogram of flesh (in days/kg);

Qf = amount of feed consumed by the animal per day in kg/day (wet weight);

i = decay constant of nuclide i in hr-1; ts = average time from slaughter of the animal to consumption by humans (20 days);

fp = fraction of the year that animals graze on pasture; fs = fraction of daily feed that is pasture grass when the animal grazes on pasture; v1 CFi = vegetation concentration factor of nuclide i on pasture grass with the holdup time th = 0 days in Ci/kg (refer to the explanation of the vegetation concentration factor calculation);

v1 CFi = vegetation concentration factor of nuclide i in stored feeds with the holdup time th = 90 days, in Ci/kg (refer to the explanation of the vegetation concentration factor calculation);

Revision 27 23

ARKANSAS NUCLEAR ONE ODCM D(r,) = relative deposition DOQ(r,) of the radionuclides, except carbon-14 and tritium.

For carbon-14 and tritium, the decayed and depleted dispersion factor D2DPX/Q(r,) for radioiodines and particulates (in sec/m3) is used; Qi = is the release of nuclide i (in curies).

3.5 Gaseous Effluent Projected Dose Calculation 3.5.1 The quarterly projected dose is based upon the methodology of Sections 3.3 and 3.4, and is expressed as follows:

DQC + DRP DQP = ( )(92)

T where:

DQP = Quarterly projected dose (mrem);

DQC = cumulative dose for the quarter (mrem);

DRP = dose for current release (mrem);

T = current days into quarter; and 92 = number of days per quarter.

3.6 Dose to the Public Inside the Site Boundary 3.6.1 Liquid Releases Dose to the public inside the site boundary due to liquid releases will be due to ingestion of fish caught from the discharge canal and exposure to sediment along the discharge canal bank while fishing.

3.6.1.a Dose Due to Ingestion of Fish Dose due to ingestion of fish is calculated using the methodology given in Section 2.2, Liquid Dose Calculation.

3.6.1.b Dose Due to Exposure to Shoreline Sediments Dose from external exposure to shoreline sediments is calculated from equation A-7 of RG 1.109, Rev. 1, 10/77.

(Uap)(Mp)(W)

Rapj = 110,000( (i [(Qi)(Ti)(Daipj)(e-i tp)(1-e-i tb)]

F where:

Rapj = is the total annual dose to organ j of individuals of age group a from all of the nuclides i in pathway in mrem/yr; Uap = is the usage factor that specifies exposure time for the maximum individual of age group a in hours from Table E-5 of RG 1.109. Sixty-seven hours for shoreline recreation for a teen was chosen. Adult is the controlling age group for ingestion but the maximum usage factor (teen) was used rather than the adult factor to ensure a conservative dose estimate; Revision 27 24

ARKANSAS NUCLEAR ONE ODCM Mp = is the mixing ratio (reciprocal of dilution factor);

W = is the shoreline width factor from Table A-2 of RG 1.109. The discharge canal value of 0.1 was chosen; F = is the flow rate of the liquid effluent in ft3/sec. This was determined by:

.134 ft3 1 yr 1 hr F(ft3/sec) = waste volume (gal/yr) * *

1 gal 8760 hr 3600 sec where:

Qi = is the release of nuclide i in Ci/yr; Ti = is the radioactive half-life of nuclide i, in days, from Radioactive Decay Data Tables, Technical Information Center, U. S. Dept. of Energy, 1981; Daipj = is the dose factor specific to age group a, nuclide i, and organ j from Table E-6 of RG 1.109; i = is the radioactive decay constant of nuclide i in hr-1; tp = is the average transit time for nuclides to reach the point of exposure. A value of 0 hours0 days 0 hours 0 weeks 0 months was chosen due to the proximity of the discharge canal to the plant; and tb = is the period of time for which sediment is exposed to the contaminated water in hours. The mid-point of plant operating life, 15 years was chosen per RG 1.109.

3.6.2 Airborne Release 3.6.2.a Dose Due to Noble Gases Dose to fisherman at the discharge canal can be calculated by the ratio of dispersion factor for the discharge canal (1.6E-4 sec/m3 from Table 2-45 SAR, Unit 1, 100 meters downwind in a southerly direction) and the usage factor of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months of shoreline recreation to the values used in Section 3.3 of this manual.

1.6E-4 67 hr Dose at discharge canal = DT() *

2.0E-5 8760 hr where DT() is the noble gas dose calculated by Section 3.3.

3.6.2.b Dose Due to Iodine, Tritium and Particulates from Gaseous Effluents Section 3.4 calculates total dose for iodine, tritium and particulates as the sum of:

DTOT = DG + DI + DV + DL + DM + DF where:

DG = ground plane deposition; DL = consumption of fresh leafy vegetables; DI = inhalation; Dm = consumption of milk; and Dv = consumption of vegetation; DF = consumption of meat and poultry Revision 27 25

ARKANSAS NUCLEAR ONE ODCM The only contributions relevant to fishing activities at the discharge canal are ground plane deposition and inhalation. As DG and DI are not independently available, a conservative estimate can be obtained by using the same correction factor developed for noble gas dose to the total dose calculated in Section 3.4 for iodine, tritium and particulates. Depletion of the plume as it travels downwind can be ignored since the fraction remaining in the plume at 100 meters (discharge canal) and 1046 meters (site boundary) are both greater than 90%

according to Figure 3 of RG 1.111.

The only activity inside the plant site by members of the public that might contribute a significant dose is fishing along the banks of the discharge canal. Travel along public roads would involve short exposure time and tours of the facility are conducted according to radiological control procedures enforced at the plant to control exposure. Fishing is the only uncontrolled activity.

4.0 ENVIRONMENTAL SAMPLING STATIONS - RADIOLOGICAL Section 1.0 of the ODCM provides reference to the Radioactivty Effluent Controls Program governed by ANO-1 TS 5.5.4 and ANO-2 TS 6.5.4. However, a Radiological Environmental Monitoring Program is also necessary to meet the intent of the purpose of the ODCM.

The Radiological Environmental Monitoring Program is established to provide radiation and radionuclide monitoring in the environs surrounding the site. The program provides a method for representative measurements of radioactivity in the highest potential exposure pathways. In addition, the program provides for verification of the accuracy of the effluent monitoring program and modeling of envronmental exposure pathways.

The Radiological Environmental Monitoring Program is established by the ODCM and conforms to the guidance contained in 10 CFR 50, Appendix I. The program also provides for:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters of the ODCM,

2. A land use census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made, if required by the results of the census, and

3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

Environmental samples are collected as specified in the Limitations. The approximate locations of selected sample sites are shown on Figures 4-1, 4-1A, and 4-1B for illustrative purposes.

Table 4-1 lists the approximate distances and directions of the sample stations from the plant.

Revision 27 26

ARKANSAS NUCLEAR ONE ODCM 5.0 REPORTING REQUIREMENTS 5.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report is submitted by May 15 of each year and contains a summary of the Radiological Environmental Monitoring Program for the reporting period. This report meets the requirements of TS 5.6.2 (ANO-1) and TS 6.6.2 (ANO-2), and is consistent with the objectives outlined in the ODCM and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report is formatted consistent with RG 1.21, Revision 1, to the extent possible. A single submittal is normally prepared incorporating the data for both ANO units (common information is combined).

The Annual Radiological Environmental Operating Report includes the following:

1. Summarized and tabulated results of all radiological environmental samples and environmental radiation measurements required by the ODCM.

2. A summary description of the Radiological Environmental Monitoring Program.

3. A map of the sampling locations with concurrent table providing distances and directions from the Reactor (Containment) Building. Because the ODCM contains this information and the ODCM is submitted as part of the Radioactive Effluent Release Report, reference to the Radioactive Effluent Release Report submittal date and letter number may be included in the Annual Radiological Environmental Operating Report in lieu of submitting the sample location map and table.

4. A summary of the land use census results in accordance with Surveillance S 2.5.2.2.

5. A summary of the Interlaboratory Comparison Program in accordance with, Surveillance S 2.5.3.1.

As required by the Limitations, the report shall include the following for the conditions listed below:

1. A description of the condition or event and, if applicable, equipment involved.

2. The cause of the condition or event.

3. Actions taken to restore the condition and prevent/minimize recurrence.

4. The consequences of the condition or event.

Revision 27 27

ARKANSAS NUCLEAR ONE ODCM Required Limitation Description Action 2.5.1 A.2 Sample not taken at required location*

Sample equipment out-of-service (OOS)

Sample frequency not met Monitoring/analysis lower limit of detection (LLD) not met Concentration limits not met Dose from other radionuclides exceed concentration limits 2.5.1 B.1 New sample location identified 2.5.2 A.1 New sample location identified 2.5.3 A.1 Interlaboratory Comparison Program requirements not met NA NA Other harmful effects or evidence of irreversible damage detected

The report shall include a summary of information not available for reporting at the time of submittal. Such missing information shall be submitted in a supplemental letter when data becomes available.

5.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report is submitted prior to May 1 of each year, but not more than 12 months from the previous years submittal, and includes a summary of the quantities of radioactive liquid effluents, gaseous effluents, and solid waste released from the site. This report meets the requirements of TS 5.6.3 (ANO-1), TS 6.6.3 (ANO-2), 10 CFR 50.36a, and 10 CFR 50, Appendix I, Section IV.B.1. The report is formatted consistent with RG 1.21, Revision 1. A single submittal is normally prepared incorporating the data from both ANO units (common information is combined).

In general, the Radioactive Effluent Release Report includes the following:

1. A description of changes to the ODCM and PCP implemented during the reporting period.

TS 5.6.3 (ANO-1) and TS 6.6.3 (ANO-2) contain a description of the ODCM change process.

2. A summary of the hourly meteorological data collected over the previous calendar year. In lieu of including this information in the report, it is permissible to retain this summary available for NRC review, if so noted in the report.

3. A summary of radiation doses due to radiological effluents during the previous calendar year, calculated in accordance with the methodology specified in the ODCM.

4. The radiation dose to members of the public while performing activities inside the site boundary. The calculated dose includes only contributions directly attributed to operation of the units.

5. A description of major changes to the radioactive waste systems (liquid/gaseous/solid) during the previous calendar year, if not included in the cycle SAR update.

Revision 27 28

ARKANSAS NUCLEAR ONE ODCM As required by the Limitations, the report shall include the following for the conditions listed below:

1. A description of the condition or event and, if applicable, equipment involved.

2. The cause of the condition or event.

3. Actions taken to restore the condition and prevent/minimize recurrence.

4. The consequences of the condition or event.

Required Limitation Description Action 2.1.1 D.1 Liquid radioactive monitoring equipment OOS > 30 days 2.2.1 G.1 Gaseous radioactive monitoring equipment OOS > 30 days 2.3.1 A.2 Liquid radioactive release limits exceeded 2.3.1 F.1 Liquid radioactive monitor LLD exceeded 2.4.1 A.2 Gaseous radioactive release limits exceeded 2.4.1 E.1 Gaseous radioactive monitor LLD exceeded Revision 27 29

ARKANSAS NUCLEAR ONE ODCM FIGURE 4-1 RADIOLOGICAL SAMPLE STATIONS 1

0° 16 340° 20° 2

US HWY 7 TO HARRISON 320° 40° 15 INTERSTATE 40 TO FORT SMITH 3

SR 5 PINEY BAY USE AREA Dover SR 333 300° 125 60° 164 EAST TO MORELAND 153 U.S.

HWY 64 14 4 SR 24 TO 14 MORELAND 116 280° ARKANSAS RIVER 80° INTERSTATE 40 LONDON 16 US HWY 64 13 J I H G F E D C B A 5 DELAWARE STATE PARK 127 ARKANSAS TECH 111 DARDANELLE UNIVERSITY 260° STATE PARK 100° U.S. HWY 22 HWY 524 LAKE DARDANELLE RUSSELLVILLE DARDANELLE STATE PARK 6

DARDANELLE LOCK AND DAM 12 HWY 22 DAM SITE EAST PARK HWY 7T 6

240° 120° HWY 155 HWY 7 SR 247 TO MT. NEBO HWY 27 POTTSVILLE STATE PARK DARDANELLE 137 11 220° HWY 28 140° 7

HWY 7 200° 160° 10 180° 8 HWY 27 TO HWY 7 TO DANVILLE 9

HOT SPRINGS DANVILLE INSET (SEE INSET) N FS Rd 1618A W E 55 AR Hwy 307 FS Rd 36 Ozark National Forest boundary S AR Hwy 27 AR Hwy 10 Entergy Substation Petit Jean River 7

57 AR HWY 10 Cowger Lake City of Danville Arkansas Nuclear One AR Hwy 80 AR Hwy 27 REMP Sample Locations (Far Field)

Revision 27 30

ARKANSAS NUCLEAR ONE ODCM FIGURE 4-1A RADIOLOGICAL SAMPLE STATIONS SR 333 152 3 108 Training 145 Center 146 109 147 13 1 West Access Rd. 10 56 2 8C 36 Scott Ln.

151 148 8S May Rd. Bunker Cemetery Bunker Hill Ln.

Hill Rd.

149 150 4 110 Arkansas Nuclear One REMP Sample Locations (Near Field)

Lake Dardanelle Revised 24May05 Revision 27 31

ARKANSAS NUCLEAR ONE ODCM FIGURE 4-1B RADIOLOGICAL SAMPLE STATIONS 62 58 STR-3 Switch STR-2 Yard STR-4 STR-6 West Access Road 64 STR-5 63 STR-1 N

Lake Dardanelle W E S

Arkansas Nuclear One REMP Sample Locations Site Map Revision 27 32

ARKANSAS NUCLEAR ONE ODCM FIGURE 4-2 MAXIMUM AREA BOUNDARY FOR RADIOACTIVE RELEASE CALCULATION (Exclusion Areas)

GASES - 1046 METER RADIUS LIQUIDS - END OF DISCHARGE CANAL (POINT A)

EMERGENCY

RESPONSE

FACILITY N EVACUATION ROUTE 2 HWY. 333 COOLING TOWER SWITCHYARD UNIT 2 EVACUATION ROUTE 3 UNIT 1 EVACUATION ROUTE 1 0.65 MILE RADIUS POINT A Revision 27 33

ARKANSAS NUCLEAR ONE ODCM TABLE 4-1 Environmental Sampling Stations - Radiological Approximate Sample Direction and Station Sample Types Sample Station Location Distance from Plant Airborne radioiodines The thermoluminescent dosimeter (TLD) is 1 88° - 0.5 miles Airborne particulates on a pole near the meteorology tower Direct radiation approx. 0.6 miles east of ANO.

Traveling from ANO, go approx. 0.2 miles west toward Gate 4. Turn left (at the east Airborne radioiodines end of the sewage treatment plant) and go 2 243° - 0.5 miles Airborne particulates approx. 0.1 miles. Turn right and go Direct radiation approx. 0.1 miles. The sample station is on the right.

If traveling west on Highway (Hwy) 333, go approx. 0.35 miles from Gate 2 at ANO.

TLD is located on utility pole on south side of Hwy 333 S.

3 5° - 0.7 miles Direct radiation If traveling east on Highway 333, go approx. 0.9 miles from junction of Hwy 333 and Flatwood Road. TLD is located on utility pole on south side of Hwy 333 S.

Go approx. 0.25 miles south from bridge over intake canal. Turn right onto May Road. Proceed approx. 0.1 miles west of 4 181° - 0.5 miles Direct radiation May Cemetery entrance. The TLD is located on a utility pole on the south side of May Road.

Go to the Entergy local office which is Airborne radioiodines located off Hwy 7T in Russellville, 6 111° - 6.8 miles Airborne particulates Arkansas (AR) (305 South Knoxville Direct radiation Avenue). The sample station is against the east wall of the back lot.

Turn west at junction of Hwy 7 and Hwy 27 in Dardanelle, AR. Proceed to junction of Hwy 27 and Hwy 10 in Danville, AR. Turn Airborne radioiodines 210° - right onto Hwy 10 and proceed a short 7 Airborne particulates 19.0 miles distance to the Entergy supply yard, which Direct radiation is on the right adjacent to an Entergy substation. The sample station is in the southwest corner of the supply yard.

166° - 0.2 miles Surface water (composite) 8 243° - 0.9 miles Shoreline sediment Plant discharge canal 212° - 0.5 miles Fish Revision 27 34

ARKANSAS NUCLEAR ONE ODCM TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Approximate Sample Direction and Station Sample Types Sample Station Location Distance from Plant 95° - 0.5 miles Surface water (grab) is collected at plant 10 Surface water (grab)

(intake canal) intake canal.

Traveling from Hwy 333, turn south onto Flatwood Road. Go approx. 1.0 miles.

13 273° - 0.5 miles Broad leaf vegetation The sample may be collected from either side of Flatwood Road.

From junction of Hwy 7 and Water Works Road, go approx. 0.8 miles west on Water 14 70° - 5.1 miles Drinking water Works Road. The sample station is on the left at the intake to the Russellville city water system from the Illinois Bayou.

Panther Bay, located on the south side of Shoreline sediment 16 287° - 5.5 miles the AR River across from the mouth of Fish Piney Creek.

The sample station is at the Wastewater 153° - Pond water 36 Holding Pond on the ANO site east of the 0.02 miles Pond sediment discharge canal.

Travel south on Hwy 27 and west on Hwy 307 to the western edge of the Ozark National Forest. Hwy 307 becomes Forest 217° -

55 Broad leaf vegetation Service (FS) Rd 36; proceed ~ 3/4 mile on 13.1 miles FS Rd 36 to its intersection with FS Rd 1618A. The sample station is located at this intersection.

Traveling west from ANO, the sample Airborne radioiodines station is located at the west end of the 56 264° - 0.4 miles Airborne particulates sewage treatment plant near the facility Direct radiation blower building.

Go to Danville and turn left on Fifth Street.

208° - Go approx. three blocks. The Danville 57 Drinking water 19.5 miles public water supply treatment facility is located on the left.

GWM - 1; North of Protected Area on owner controlled area (OCA), west of north 58 22° - 0.3 miles Groundwater Security Check Point, east side of access road.

GWM - 101; North of Protected Area on 62 34° - 0.5 miles Groundwater OCA, east of outside receiving building.

Revision 27 35

ARKANSAS NUCLEAR ONE ODCM TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Approximate Sample Direction and Station Sample Types Sample Station Location Distance from Plant GWM - 103; South of Protected Area on 63 206° - 0.1 miles Groundwater OCA, northeast of Stator Rewind Building near woodline.

GWM - 13; South of Oily Water Separator, 64 112° - 0.1 miles Groundwater northwest corner of ANO-2 Intake Structure, inside the Protected Area.

If traveling from Hwy 333, turn south onto Flatwood Road and go approx. 0.4 miles.

The TLD is on a utility pole on the right.

108 306° - 0.9 miles Direct radiation If traveling north on Flatwood Road, go approx. 0.4 miles from sample station 109.

The TLD is on a utility pole on the left.

Traveling from Hwy 333, turn south onto Flatwood Road. Go approx. 0.8 miles. The 109 291° - 0.6 miles Direct radiation TLD is on a utility pole on the left across from the junction of Flatwood Road and Round Mountain Road.

From bridge over intake canal, go south approx. 0.25 miles. Turn left and go 110 138° - 0.8 miles Direct radiation approx. 0.25 miles. Turn right on Bunker Hill Lane. The TLD is on the first utility pole on the left.

From junction of Hwy 64 and Hwy 326 (Marina Road), go approx. 2.1 miles on 111 120° - 2.0 miles Direct radiation Marina Road. The TLD is on a utility pole on the left just prior to curve.

Go one block south of the west junction of Hwy 333 and Hwy 64 in London, AR. The 116 318° - 1.8 miles Direct radiation TLD is on a utility pole north of the railroad tracks.

Traveling north on Hwy 7, turn left onto Water Street in Dover, AR. Go one block and turn left onto South Elizabeth Street.

125 46° - 8.7 miles Direct radiation Go one block and turn right onto College Street. The TLD is on a utility pole at the southeast corner of the red brick school building, which is located on top of hill.

Revision 27 36

ARKANSAS NUCLEAR ONE ODCM TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Approximate Sample Direction and Station Sample Types Sample Station Location Distance from Plant The TLD is located on Arkansas Tech Campus on N. Glenwood Street. If traveling south on Hwy 7 from I- 40, turn right on N. Glenwood. Follow N. Glenwood 127 100° - 5.2 miles Direct radiation for approx. 0.6 miles. The TLD is located on a utility pole (with a No Parking sign on it) across from the northeast corner of Paine Hall.

At junction of Hwy 7 and Hwy 28 in Dardanelle, AR, go approx. 0.2 miles on 137 151° - 8.2 miles Direct radiation Hwy 28. The TLD is on a speed limit sign on the right in front of the Morris R. Moore Arkansas National Guard Armory.

The TLD is located near the west entrance to the Reeves E. Ritchie Training Center 145 28° - 0.6 miles Direct radiation (RERTC) on a utility pole on the north side of Hwy 333.

The TLD is located on the south end of the 146 45° - 0.6 miles Direct radiation east parking lot at the RERTC. The TLD is located on a utility pole.

The TLD is located on the west side of 147 61° - 0.6 miles Direct radiation Bunker Hill Road, approx. 100 yards from the intersection with Hwy 333.

Traveling east from ANO, turn right on Bunker Hill Road. Travel south for approx.

148 122° - 0.6 miles Direct radiation 0.25 miles to the intersection with Scott Lane. The TLD is located on the county road sign post.

Traveling south on Bunker Hill Road, turn right on May Road. Travel approx.

149 156° - 0.5 miles Direct radiation 0.4 miles. The TLD is located on a Notice sign on the north side of May Road.

Traveling south on Bunker Hill Road, turn right on May Road. Travel approx.

150 205° - 0.6 miles Direct radiation 0.8 miles. The TLD is located just past the McCurley Place turn off on the north side of May Road on a utility pole.

Revision 27 37

ARKANSAS NUCLEAR ONE ODCM TABLE 4-1 Environmental Sampling Stations - Radiological (continued)

Approximate Sample Direction and Station Sample Types Sample Station Location Distance from Plant Traveling west from ANO, turn south on plant road along the east side of the 151 225° - 0.4 miles Direct radiation sewage treatment plant. The TLD is located at the end of this road, near the lake on a metal post.

Traveling west on Hwy 333 from the RERTC, travel approx. 0.7 miles. The TLD 152 338° - 0.8 miles Direct radiation is located on the south side of Hwy 333 on a utility pole.

Travel Hwy 64 west to Knoxville Elementary School. The TLD is located 153 304° - 9.2 miles Direct radiation near the school entrance gate on a utility pole.

120° - East side of GSB drainage ditch near lift STR - 1 Storm water runoff 0.33 miles station.

351° - Inside protected area near Sally Port from STR - 2 Storm water runoff

< 0.10 miles drainage ditch along fence.

Outside Protected Area near Sally Port STR - 3 0.2° - 0.13 miles Storm water runoff from drainage ditch along fence.

102° - East side of Oily Water Separator from STR - 4 Storm water runoff 0.10 miles storm drain.

170° - West side of discharge canal from storm STR - 5 Storm water runoff

< 0.10 miles drain.

90° - East side of chemistry chemical storage STR - 6 Storm water runoff

< 0.10 miles area storm drain.

Revision 27 38

ARKANSAS NUCLEAR ONE ODCM APPENDIX 1 RADIOLOGICAL EFFLUENT CONTROLS Revision 27 39

ARKANSAS NUCLEAR ONE ODCM 1.0 DEFINITIONS

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

The defined terms of this section appear in capitalized type and are applicable throughout these Limitations and Bases.

Term Definition ACTION(S) ACTIONS shall be that part of a Limitation that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

BATCH RELEASE A BATCH RELEASE is the discharge of liquid or gaseous wastes of a discrete volume.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel FUNCTIONALITY and the CHANNEL TEST. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL TEST A CHANNEL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify FUNCTIONALITY of all devices in the channel required for channel FUNCTIONALITY. The CHANNEL TEST may be performed by means of any series of sequential, overlapping, or total steps.

CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of liquid waste of a non-discrete volume, e.g. from a volume of a system that has an input flow during the continuous release.

EXCLUSION AREA The EXCLUSION AREA is that area surrounding ANO within a minimum radius of 0.65 miles of the Reactor (Containment) Buildings and controlled to the extent necessary by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

Revision 27 40

ARKANSAS NUCLEAR ONE ODCM 1.0 DEFINITIONS (continued)

Term Definition FUNCTIONAL-FUNCTIONALITY A system, subsystem, train, component, or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s), as set forth in the current license basis (CLB) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified function(s) are also capable of performing their related support function(s).

GASEOUS RADWASTE A GASEOUS RADWASTE TREATMENT SYSTEM is TREATMENT SYSTEM any system designed and installed to reduce radioactive gaseous effluents by collecting gases from radioactive systems and providing for decay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

LIQUID RADWASTE A LIQUID RADWASTE TREATMENT SYSTEM is a TREATMENT SYSTEM system designed and used for holdup, filtration, and/or demineralization of radioactive liquid effluents prior to their release to the environment.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from the category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

MODE(S) Refer to Definitions section of ANO-1 and ANO-2 TSs.

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to reduce the airborne radioactivity concentration in such a manner that replacement air or gas is required to purify the confinement.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

Revision 27 41

ARKANSAS NUCLEAR ONE ODCM 1.0 DEFINITIONS (continued)

Term Definition VENTILATION EXHAUST A VENTILATION EXHAUST TREATMENT SYSTEM is any TREATMENT SYSTEM system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area beyond the EXCLUSION AREA boundary.

Revision 27 42

ARKANSAS NUCLEAR ONE ODCM 2.0 LIMITITATION (L) APPLICABILITY L 2.0.1 Limitations shall be met during the specified conditions in the Applicability, except as provided in L 2.0.2.

L 2.0.2 Upon discovery of a failure to meet a Limitation, the applicable ACTIONS of the associated Limitation shall be met, except as provided in L 3.0.5. If the Limitation is met or is no longer applicable prior to expiration of the specified Completion Time(s),

completion of the ACTIONS is not required, unless otherwise stated.

L 2.0.3 When a Limitation is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, immediately initiate a condition report to document the condition and determine any limitations for continued operation of the plant.

Exceptions to this Limitation are stated in the individual Limitations.

L 2.0.4 When a Limitation is not met, entry into a MODE or other specified condition in the Applicability shall only be made when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time.

L 2.0.5 Equipment removed from service or declared non-functional to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY of other equipment. This is an exception to L 2.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONALITY.

Revision 27 43

ARKANSAS NUCLEAR ONE ODCM 2.0 SURVEILLANCE (S) APPLICABILITY S 2.0.1 Surveillances shall be met during the specified conditions in the Applicability for individual Limitations, unless otherwise stated in the Surveillance. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limitation. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the Limitation except as provided in S 2.0.3.

Surveillances are not required to be performed on non-functional equipment or variables outside specified limits.

S 2.0.2 The specified Frequency for each Surveillance is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. If an Action completion time requires periodic performance on a "once per . . ." basis, the above Frequency extension applies to each performance after the initial performance.

S 2.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the Limitation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the Limitation must immediately be declared not met, and the applicable ACTIONS must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Limitation must immediately be declared not met, and the applicable ACTIONS must be entered.

S 2.0.4 Entry into a specified condition in the Applicability of a Limitation shall only be made when the Limitation's Surveillances have been met within their specified Frequency, except as provided by S 2.0.3. When a Limitation is not met due to Surveillances not having been met, entry into a specified condition in the Applicability shall only be made in accordance with L 2.0.4.

Revision 27 44

ARKANSAS NUCLEAR ONE ODCM L 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION L 2.1.1 The following Radioactive Liquid Effluent Monitoring Instrumentation shall be FUNCTIONAL:

a. Liquid Radwaste Effluent Radiation Monitor with alarm/trip function

b. Liquid Radwaste Effluent Flow Monitor

c. One Main Steam Line Radiation Monitor per Steam Generator (ANO-1 only)

APPLICABILITY: Liquid Radwaste Effluent Monitor - during releases via the associated pathway Main Steam Line Radiation Monitors - MODES 1, 2, 3, and 4 ACTIONS

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

Separate Condition entry is allowed for each instrument.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required Liquid Radwaste A.1 Suspend the release of Immediately Effluent Radiation Monitor radioactive effluents non-functional. monitored by the affected channel.

AND A.2.1 Restore the monitor to a Prior to release of FUNCTIONAL status. radioactive effluents monitored by the OR affected channel A.2.2.1 Analyze two independent Prior to release of samples of the associated radioactive effluents tank contents. monitored by the affected channel AND A.2.2.2 Computer input data Prior to release of verified by two qualified radioactive effluents individuals. monitored by the affected channel AND Revision 27 45

ARKANSAS NUCLEAR ONE ODCM L 2.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2.3 Correct discharge valve Prior to release of lineup independently radioactive effluents verified by two qualified monitored by the individuals. affected channel B. Required Liquid Radwaste B.1 Estimate flow. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Effluent Flow Monitor non-functional. OR B.2 Suspend the release of Immediately radioactive effluents monitored by the affected channel.

C. One or more required Main C.1 Establish pre-planned 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Steam Line Radiation alternate monitoring method Monitor non-functional. of monitoring.

AND C.2 Restore the affected Main 7 days Steam Line Radiation Monitor(s) to a FUNCTIONAL status.

D. Required Action(s) and/or D.1 Initiate a condition report to Immediately Completion Time(s) of document the condition and Conditions A, B, and/or C determine any limitations for not met. the continued effluent release operations.

E. Required Radioactive E.1 Initiate a condition report to Immediately Liquid Effluent Monitoring document and track the Instrument non-functional condition for inclusion in the for > 30 days. Radioactive Effluent Release Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Revision 27 46

ARKANSAS NUCLEAR ONE ODCM L 2.1.1 SURVEILLANCES SURVEILLANCE FREQUENCY S 2.1.1.1 Perform a CHANNEL CHECK of required instrumentation. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S 2.1.1.2 -----------------------------------NOTE------------------------------------

Not applicable to Liquid Radwaste Effluent Flow Monitor.

Perform a CHANNEL TEST of the required instrumentation. 92 days S 2.1.1.3 Perform a CHANNEL CALIBRATION on the required 18 months instrumentation.

S 2.1.1.4 -----------------------------------NOTES-----------------------------------

1. SOURCE CHECK not required when background radioactivity is greater than the check source.

2. Not applicable to Liquid Radwaste Effluent Flow Monitor or Main Steam Line Radiation Monitors.

Perform a SOURCE CHECK on the required Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior instrumentation. to release of radioactive effluents monitored by the channel Revision 27 47

ARKANSAS NUCLEAR ONE ODCM L 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION L 2.2.1 The following Radioactive Gaseous Effluent Monitoring Instrumentation shall be FUNCTIONAL:

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

Refer to ANO-2 Technical Specification (TS) 3.3.3.1 for ANO-2 Containment Building Purge System Process Monitor operability requirements and associated ACTIONS.

a. Waste Gas Holdup Systems

1. Gas Activity Process Monitor with alarm/trip function

2. Effluent Flow Process Monitor

b. Reactor (Containment) Building Purge and Ventilation, Auxiliary Building Ventilation, Spent Fuel Pool Area Ventilation, Emergency Penetration Room Ventilation, Low Level Radwaste Building Ventilation, and ANO-2 Auxiliary Building Extension Ventilation SPING Monitors

1. Noble Gas Activity Monitor

2. Iodine Sampler

3. Particulate Sampler

4. Effluent Flow Monitor

5. Sampler Flow Monitor APPLICABILITY:

1. SPINGS 4 and 8 - when Emergency Penetration Room Ventilation is capable of auto-start

2. All Radioactive Gaseous Effluent Monitoring Instrumentation - during releases via the associated pathway Revision 27 48

ARKANSAS NUCLEAR ONE ODCM ACTIONS

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

Separate Condition entry is allowed for each instrument.

CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE-------------- A.1 Suspend the release of Immediately Applicable to releases radioactive effluents associated with Waste Gas monitored by the affected Holdup Systems and channel.

PURGE of the ANO-1 Reactor Building. AND A.2.1 Restore the monitor to a Prior to release of Required Waste Gas FUNCTIONAL status. radioactive effluents Holdup and/or Reactor monitored by the Building Purge System OR affected channel Gas Activity Process and/or Noble Gas Activity A.2.2.1 Analyze two independent Prior to release of Monitor non-functional. samples of the Waste Gas radioactive effluents Holdup Tank and/or monitored by the Reactor Building contents. affected channel AND A.2.2.2 Computer input data Prior to release of verified by two qualified radioactive effluents individuals. monitored by the affected channel AND A.2.2.3 -------------NOTE-------------

Not applicable to Reactor Building Purge System.

Correct discharge valve Prior to release of lineup independently radioactive effluents verified by two qualified monitored by the individuals. affected channel Revision 27 49

ARKANSAS NUCLEAR ONE ODCM L 2.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Effluent or B.1 Estimate flow. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Sampler Flow Monitor non-functional. OR B.2 Suspend the release of Immediately radioactive effluents monitored by the affected channel.

C. --------------NOTE-------------- --------------------NOTE------------------

1. Applicable to releases If ANO-1 Reactor Building Purge other than those and Ventilation required Noble Gas described in Condition A Activity Monitor inoperable and above. moving irradiated fuel within the ANO-1 Reactor Building, refer to

2. Applicable to SPINGS 4 ANO-1 TS 3.9.3.

and 8 only when -----------------------------------------------

pathway is in service.

C.1 Obtain sample of effluent. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Noble Gas Activity AND Monitor non-functional.

C.2 Analyze sample of effluent. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following completion of Required Action C.1 D. --------------NOTE-------------- D.1 Verify effluent samples are 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Applicable to SPINGS 4 continuously collected by and 8 only when pathway auxiliary sampling equipment.

is in service.

AND Required Iodine and/or D.2 Replace Iodine and/or 7 days Particulate Sampler non- Particulate cartridges (as functional. applicable).

AND D.3 Analyze Iodine and/or Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Particulate cartridges (as following replacement applicable).

Revision 27 50

ARKANSAS NUCLEAR ONE ODCM L 2.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action(s) and/or E.1 Suspend the release of Immediately Completion Time(s) of radioactive effluents monitored Condition C and/or by the affected channel.

Condition D not met.

F. Required Action(s) and/or F.1 Initiate a condition report to Immediately Completion Time(s) document the condition and Condition A, B, and/or E determine any limitations for not met. the continued effluent release operations.

G. Required Radioactive G.1 Initiate a condition report to Immediately Gaseous Effluent document and track the Monitoring Instrument condition for inclusion in the non-functional for Radioactive Effluent Release

> 30 days. Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

SURVEILLANCES SURVEILLANCE FREQUENCY S 2.2.1.1 -----------------------------------NOTE------------------------------------

Not applicable to Iodine and Particulate Samplers Perform a CHANNEL CHECK of required instrumentation. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S 2.2.1.2 Verify presence of required Iodine Sampler Cartridge and 7 days required Particulate Sample Filter.

S 2.2.1.3 Perform a CHANNEL TEST of the required Reactor Building 31 days prior to Purge and Ventilation System Gas Activity Process and initiating Reactor Noble Gas Activity Monitors. Building Purge and/or Ventilation activities Revision 27 51

ARKANSAS NUCLEAR ONE ODCM L 2.2.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.2.1.4 -----------------------------------NOTES-----------------------------------

SOURCE CHECK not required when background radioactivity is greater than the check source.

Perform a SOURCE CHECK on the required Noble Gas 31 days Activity Monitors.

S 2.2.1.5 -----------------------------------NOTES-----------------------------------

1. SOURCE CHECK not required when background radioactivity is greater than the check source.

2. Only applicable to Waste Gas Holdup and Reactor Building Purge Systems.

Perform a SOURCE CHECK on the required Gas Activity Within 14 days prior Process and Noble Gas Activity Monitors. to release of radioactive effluents monitored by the channel S 2.2.1.6 Perform a CHANNEL TEST of the required Noble Gas 92 days Activity Monitors.

S 2.2.1.7 -----------------------------------NOTE------------------------------------

Not applicable to Iodine and Particulate Samplers Perform a CHANNEL CALIBRATION on the required 18 months instrumentation.

Revision 27 52

ARKANSAS NUCLEAR ONE ODCM L 2.3 RADIOACTIVE LIQUID EFFLUENTS L 2.3.1 Radioactive material released to the discharge canal shall:

a. For dissolved or entrained noble gases, be limited to a total concentration of 2 x 10-4 µCi/ml.

b. For radioactive nuclides other than dissolved or entrained noble gases, be limited to the concentration specified in 10 CFR 20, Appendix B, Table II, Column 2.

c. During any calendar quarter, result in a dose commitment to a MEMBER OF THE PUBLIC of 1.5 mrem to the total body and 5 mrem to any organ.

d. During any calendar year, result in a dose commitment to a MEMBER OF THE PUBLIC of 3 mrem to the total body and 10 mrem to any organ.

e. Be processed by a LIQUID RADWASTE TREATMENT SYSTEM when accumulative dose during a calendar quarter is projected to exceed 0.18 mrem to the total body and/or 0.625 mrem to any organ.

APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each Limitation L 2.3.1.a through L 2.3.1.e above and for each BATCH RELEASE and CONTINUOUS RELEASE Surveillance requirement not met.

CONDITION REQUIRED ACTION COMPLETION TIME A. Any limit listed in L 2.3.1.a A.1 Initiate action to restore to Immediately through L 2.3.1.e not met. within limit.

AND A.2 Initiate a condition report to Immediately document the condition, determine any limitations for the continued effluent release operations, and track the condition for inclusion in the Radioactive Effluent Release Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

Revision 27 53

ARKANSAS NUCLEAR ONE ODCM L 2.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. --------------NOTE-------------- B.1 Verify associated effluent Immediately Only applicable to BATCH release suspended.

RELEASE.

AND Sampling and/or analysis B.2 Initiate a condition report to Immediately requirements not met. document the condition and determine any limitations for the continued effluent release operations.

C. --------------NOTE-------------- C.1 Obtain a grab sample of the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Only applicable to associated secondary CONTINUOUS RELEASE coolant.

of secondary coolant.

AND Secondary coolant dose C.2 Perform gamma isotopic and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following equivalent I-131 (DEI) I-131 analysis of sample. sample acquisition

> 0.01 µCi/ml.

D. Annual dose limits of D.1 Apply for a variance from the Prior to exceed L 2.3.1.d projected to NRC to permit releases in 40 CFR 190 limits exceed 40 CFR 190 limits. excess of 40 CFR 190 limits. Immediately E. Required Action(s) and/or E.1 Initiate a condition report to Immediately Completion Time(s) of document the condition and Conditions C and/or D not determine any limitations for met. the continued effluent release operations.

OR Sampling and/or analysis requirements not met.

Revision 27 54

ARKANSAS NUCLEAR ONE ODCM L 2.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Lower Limit(s) of Detection F.1 Initiate a condition report to Immediately (LLD) not met. document and track the condition for inclusion in the Radioactive Effluent Release Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

SURVEILLANCES SURVEILLANCE FREQUENCY S 2.3.1.1 -----------------------------------NOTE------------------------------------

Only applicable to BATCH RELEASE.

Obtain representative sample of each batch. Prior to release AND Perform gamma isotopic and I-131 analysis of sample. Prior to release AND Perform dissolved and entrained gas analysis of sample. 31 days following sample acquisition AND Perform gross alpha composite and H-3 analysis of sample. 31 days following sample acquisition AND Perform Sr-89, Sr-90, and Fe-55 composite analysis of 92 days following sample. sample acquisition Revision 27 55

ARKANSAS NUCLEAR ONE ODCM L 2.3.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.3.1.2 -----------------------------------NOTE------------------------------------

Only applicable to CONTINUOUS RELEASE.

Obtain representative sample of effluent. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND Perform gamma isotopic and I-131 analysis. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following sample acquisition AND Perform dissolved and entrained gas analysis. 31 days following sample acquisition AND Perform gross alpha composite and H-3 analysis. 31 days following sample acquisition AND Perform Sr-89, Sr-90, and Fe-55 composite analysis. 92 days following sample acquisition S 2.3.1.3 Using data acquired by performance of S 2.3.1.1 and Within 7 days S.2.3.1.2, verify Limitations L 2.3.1.a through L 2.3.1.e following completion continue to be met. of each required analysis S 2.3.1.4 Using data acquired by performance of S 2.3.1.1 and 31 days S.2.3.1.2, verify the limits of 40 CFR 190 are not projected to be exceeded.

S 2.3.1.5 Verify the following LLDs are met: 12 months Gamma isotopic 5 x 10-7 µCi/ml I-131 and Fe-55 1 x 10-6 µCi/ml Dissolved/entrained gases (gamma emitters) 1 x 10-5 µCi/ml H-3 1 x 10-5 µCi/ml Gross alpha 1 x 10-7 µCi/ml Sr-89 and Sr-90 5 x 10-8 µCi/ml Revision 27 56

ARKANSAS NUCLEAR ONE ODCM L 2.4 RADIOACTIVE GASEOUS EFFLUENTS L 2.4.1 Radioactive Gaseous Effluent releases to unrestricted areas shall:

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

Dose rates associated with Reactor (Containment) Building Purge operations may be averaged over a one hour interval.

a. For noble gases, be limited to:

1. A total body dose rate of 500 mrem/yr.

2. A skin dose rate of 3000 mrem/yr.

3. A dose commitment to a MEMBER OF THE PUBLIC in any calendar quarter of 5 mrads gamma and 10 mrads beta radiation.

4. A dose commitment to a MEMBER OF THE PUBLIC in any calendar year of 10 mrads gamma and 20 mrads beta radiation.

b. For I-131, H-3, and for all radionuclides in particulate form having a half life of

> 8 days, be limited to:

1. An organ dose rate of 1500 mrem/yr.

2. A dose commitment to a MEMBER OF THE PUBLIC in any calendar quarter of 7.5 mrem to any organ.

3. A dose commitment to a MEMBER OF THE PUBLIC in any calendar year of 15 mrem to any organ.

c. Be processed by a VENTILATION EXHAUST TREATMENT SYSTEM when:

1. For noble gases, the dose over a calendar quarter is project to exceed 0.625 mrads gamma and/or 1.25 mrads beta radiation.

2. For I-131, H-3, and for all radionuclides in particulate form having a half life of > 8 days, the dose over a calendar quarter is project to exceed 1.0 mrem to any organ.

d. Be processed by the GASEOUS RADWASTE TREATMENT SYSTEM when degasifying the Reactor Coolant System (RCS), if projected dose would exceed 0.625 mrads gamma and/or 1.25 mrads beta radiation over a calendar quarter.

APPLICABILITY: At all times.

Revision 27 57

ARKANSAS NUCLEAR ONE ODCM L 2.4.1 ACTIONS

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

Separate Condition entry is allowed for each Limitation L 2.4.1.a through L 2.4.1.d above and for each Surveillance requirement not met.

CONDITION REQUIRED ACTION COMPLETION TIME A. Any limit listed in L 2.4.1.a A.1 Initiate action to restore to Immediately through L 2.4.1.d not met. within limit.

AND A.2 Initiate a condition report to Immediately document the condition, determine any limitations for the continued effluent release operations, and track the condition for inclusion in the Radioactive Effluent Release Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

B. Sampling and/or analysis B.1 Verify associated effluent Immediately requirements of S 2.4.1.1 release suspended.

not met.

AND B.2 Initiate a condition report to Immediately document the condition and determine any limitations for the continued effluent release operations.

C. Annual dose limits of C.1 Apply for a variance from the Prior to exceed L 2.4.1.a.4 and/or NRC to permit releases in 40 CFR 190 limits L 2.4.1.b.4 projected to excess of 40 CFR 190 limits. Immediately exceed 40 CFR 190 limits.

Revision 27 58

ARKANSAS NUCLEAR ONE ODCM L 2.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action(s) and/or D.1 Initiate a condition report to Immediately Completion Time(s) of document the condition and Condition C not met. determine any limitations for the continued effluent release OR operations.

Sampling and/or analysis requirements of S 2.4.1.2 not met.

E. Lower Limit(s) of Detection E.1 Initiate a condition report to Immediately (LLD) not met. document and track the condition for inclusion in the Radioactive Effluent Release Report pursuant to TS 5.6.3 (ANO-1) / TS 6.6.3 (ANO-2).

SURVEILLANCES SURVEILLANCE FREQUENCY S 2.4.1.1 -----------------------------------NOTE------------------------------------

Only applicable to Waste Gas Storage Tank and Reactor Building Purge release.

Obtain representative sample of gas to be released. Prior to release AND Analyze sample for principal gamma emitters. Prior to release AND

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

Only applicable to Reactor Building Purge release.

Perform H-3 analysis of sample. Prior to release Revision 27 59

ARKANSAS NUCLEAR ONE ODCM L 2.4.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.4.1.2 -----------------------------------NOTE------------------------------------

Only applicable to Auxiliary Building, Spent Fuel Pool Area, Auxiliary Building Extension Area (ANO-2), Low Level Radwaste Building, Emergency Penetration Room, and Reactor (Containment) Building Ventilation systems.

The following effluent samples shall be obtained to support the radioactive analysis specified:

a. ------------------------------------NOTE-------------------------------

Only applicable to Reactor Building Ventilation when Reactor Vessel Head is removed.

Representative sample for H-3 analysis. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

b. ------------------------------------NOTE-------------------------------

Only applicable to Spent Fuel Pool Area Ventilation.

Representative sample for H-3 analysis. 7 days

c. Charcoal sample for I-131 analysis. 7 days

d. Particulate sample for principal gamma emmiters 7 days analysis.

e. Particulate sample for composite gross alpha analysis. 31 days

f. Representative sample for principal gamma emmiters 31 days analysis.

g. Representative sample for H-3 analysis. 31 days

h. Particulate sample of for Sr-89 and Sr-90 composite 92 days analysis.

AND (continued) (continued)

Revision 27 60

ARKANSAS NUCLEAR ONE ODCM S 2.4.1.2 (continued)

Complete analysis of above samples:

i. Samples a, b, c, and d 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following sample acquisition

j. Samples e, f, and g 31 days following sample acquisition

k. Sample h 60 days following sample acquisition S 2.4.1.3 Record SPING Noble Gas activity. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months S 2.4.1.4 Using data acquired by performance of S 2.4.1.1 and 31 days S.2.4.1.2, verify Limitations L 2.4.1.a through L 2.4.1.d continue to be met.

S 2.4.1.5 Using data acquired by performance of S 2.4.1.1 and 31 days S.2.4.1.2, verify the limits of 40 CFR 190 are not projected to be exceeded.

S 2.4.1.6 Verify the following LLDs are met: 12 months Principal gamma emitters (gaseous) 1 x 10-4 µCi/ml Principal gamma emitters (particulate) 1 x 10-11 µCi/ml I-131 1 x 10-12 µCi/ml H-3 1 x 10-6 µCi/ml Gross alpha 1 x 10-11 µCi/ml Sr-89 and Sr-90 1 x 10-11 µCi/ml Noble gas (dose equivalent Xe-133) 1 x 10-6 µCi/ml Revision 27 61

ARKANSAS NUCLEAR ONE ODCM L 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING L 2.5.1 The following environmental sample locations shall be designated and maintained:

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

Other instruments may be used in place of, or in addition to, integrating dosimeters.

Pathway / Sample Type # Location Samples close to site boundary in or near different 3 sectors having the highest calculated annual average ground-level D/Q Airborne Radionuclide and Sample from the vicinity of a community having the Particulate 1 highest calculated annual average ground-level D/Q Background information sample from a control location 1

10-20 miles from one reactor building Inner ring stations with 2 or more dosimeters in each 16 meteorological sector in the general area of the site boundary Direct Radiation Stations with 2 or more dosimeters in special interest 8 areas such as population centers, nearby residences, schools, and in 1-2 areas to serve as control locations.

Surface 1 Indicator location influenced by plant discharge Water 1 Control location uninfluenced by plant discharge Drinking 1 Indicator location influenced by plant discharge Water 1 Control location uninfluenced by plant discharge Waterborne Shoreline 1 Indicator location influenced by plant discharge Sediment 1 Control location uninfluenced by plant discharge Ground 1 Indicator location influenced by plant discharge Water 1 Control location uninfluenced by plant discharge Indicator location within 5 miles of one reactor, if 1

commercially available Milk Control location > 5 miles from one reactor when an 1

indicator exists Sample of commercially and/or recreationally important 1

species in vicinity of plant discharge Fish Ingestion Sample of same species in area not influenced by plant 1

discharge Sample of broadleaf (edible or inedible) near the site 1 boundary from one of the highest anticipated annual Food average ground-level D/Q sectors Products Sample location of broadleaf vegetation (edible or 1 inedible) from a control location 10-20 miles from one reactor Revision 27 62

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each sample location and Surveillance requirement.

CONDITION REQUIRED ACTION COMPLETION TIME A. Sample location A.1 Initiate action to restore to Immediately requirement not met. within limits.

OR AND Required sample A.2 Initiate a condition report to Immediately equipment non-functional. document and track the condition for inclusion in the OR Annual Radiological Environmental Operating Sample Frequency not met. Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

OR Sample analysis Frequency not met.

OR One or more Lower Limit(s) of Detection (LLD) listed in Table 2.5-1 not met.

OR One or more limits listed in Table 2.5-2 not met.

OR Dose to a MEMBER OF THE PUBLIC from radionuclides other than those listed in Table 2.5-2 projected to exceed calendar year limits of L 2.3.1 and/or L 2.4.1.

Revision 27 63

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Sample(s) from required B.1 Identify and add to the 30 days sample location(s) Radiological Environment unavailable. Monitoring Program, locations for obtaining replacement samples.

SURVEILLANCES SURVEILLANCE FREQUENCY S 2.5.1.1 -----------------------------------NOTE------------------------------------

Only applicable to Airborne Radionuclide and Particulate.

Collect sample from continuous sampler. 14 days AND Perform I-131 analysis of radioiodine canister. 14 days following sample acquisition AND Perform gross beta analysis of particulate sampler. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 14 days following filter change S 2.5.1.2 -----------------------------------NOTE------------------------------------

Only applicable to Direct Radiation locations.

Collect sample from required location. 92 days AND Perform gamma dose analysis of sample. 60 days following sample acquisition Revision 27 64

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.5.1.3 -----------------------------------NOTE------------------------------------

Only applicable to Surface Water samples.

Collect sample from required location. 92 days AND Perform gamma isotopic analysis of sample. 21 days following sample acquisition AND Perform H-3 analysis of sample. 31 days following sample acquisition S 2.5.1.4 -----------------------------------NOTE------------------------------------

Only applicable to Drinking and Ground Water samples.

Collect sample from required location. 92 days AND Perform gamma isotopic analysis of sample. 21 days following sample acquisition AND Perform H-3 analysis of sample. 31 days following sample acquisition AND Perform I-131 analysis of sample. 21 days following sample acquisition AND Perform gross beta analysis of sample. 31 days following sample acquisition Revision 27 65

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.5.1.5 -----------------------------------NOTE------------------------------------

Only applicable to Waterborne Shoreline Sediment samples.

Collect sample from required location. 12 months AND Perform gamma isotopic analysis of sample. 60 days following sample acquisition S 2.5.1.6 -----------------------------------NOTE------------------------------------

Only applicable to Milk samples.

Collect sample from required location. 92 days AND Perform gamma isotopic analysis of sample. 21 days following sample acquisition AND Perform I-131 analysis of sample. 21 days following sample acquisition S 2.5.1.7 -----------------------------------NOTE------------------------------------

Only applicable to edible portions of Fish samples.

Collect sample from required location. 12 months AND Perform gamma isotopic analysis of sample. 60 days following sample acquisition Revision 27 66

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY S 2.5.1.8 ----------------------------------NOTES-----------------------------------

1. Only applicable to Food Product samples.

2. Only applicable if Milk sampling not performed.

Collect sample from required location. 12 months AND Perform gamma isotopic analysis of sample. 21 days following sample acquisition AND Perform I-131 analysis of sample. 21 days following sample acquisition S 2.5.1.9 Verify the LLDs listed in Table 2.5-1 are met. 12 months S 2.5.1.10 Verify radioactivity concentrations are less than or equal to 92 days the limits listed in Table 2.5-2, when averaged over a calendar quarter.

Revision 27 67

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 TABLE 2.5-1 MAXIMUM VALUES OF THE LOWER LIMITS OF DETECTION (LLD)

Water Airborne Particulate or Gas Fish Food Products Sediment Analyses Milk (pCi/l)

(pCi/l) (pCi/m3) (pCi/kg, wet) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4(a) 1 x 10-2(b)

H-3 2000(c)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1(d) 7 x 10-2(e) 1 60 Cs-134 15 5 x 10-2(f) 130 15 60 150

-2(f)

Cs-137 18 6 x 10 150 18 80 180 Ba-140 60 60 La-140 15 15 (a)

LLD for drinking water.

(b)

Only applicable to particulate.

(c)

LLD for drinking water. When no drinking water pathway exists, a value of 3000 pCi/l may be used.

(d)

LLD for drinking water. When no drinking water pathway exists, a gamma isotopic analysis LLD value of 15 pCi/l may be used.

(e)

Only applicable to gas.

(f)

Only applicable to particulate gamma isotopic analysis.

Revision 27 68

ARKANSAS NUCLEAR ONE ODCM L 2.5.1 TABLE 2.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate or Gas Analyses Water (pCi/l) Fish (pCi/kg, wet) Milk (pCi/l) Food Products (pCi/kg, wet)

(pCi/m3)

H-3 2 x 104(a)

Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 x 104 Zn-65 3 x 102 2 x 104 Zr-95, Nb-95 4 x 102(b)

I-131 2(c) 0.9 3 1 x 102 Cs-134 30 10(d) 1 x 103 60 1 x 103 Cs-137 50 20(d) 2 x 103 70 2 x 103 Ba-140, La-140 2 x 102(b) 3 x 102(b)

(a)

Drinking water samples.

(b)

Total for parent and daughter.

(c)

LLD for drinking water. When no drinking water pathway exists, a value of 20 pCi/l may be used.

(d)

Applicable when performing a gamma isotopic analysis of individual particulate samples with gross beta activity more than 10 times the yearly mean of control samples.

Revision 27 69

ARKANSAS NUCLEAR ONE ODCM L 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING L 2.5.2 -----------------------------------------------------NOTE---------------------------------------------------

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

The location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a 5 mile distance from one reactor (containment) building shall be identified.

APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each sample location.

CONDITION REQUIRED ACTION COMPLETION TIME A. New sample location A.1 Initiate a condition report to Immediately identified which yields a document and track the calculated dose due to condition for inclusion in the I-131, H-3, and/or Annual Radiological particulates projected to Environmental Operating exceed 40 CFR 190 limits. Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

OR AND New sample location identified which yields a A.2.1 Identify and add the new 30 days calculated dose via the sample location to the same exposure pathway in Radiological Environment excess of values calculated Monitoring Program.

at sample locations of Limitation L 2.51. AND A.2.2 Delete the previous Within 90 days sample location via the following October 31 associated exposure of the year in which pathway from the the new sample Radiological Environment location was Monitoring Program. identified.

Revision 27 70

ARKANSAS NUCLEAR ONE ODCM L 2.5.2 SURVEILLANCES

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

S 2.0.2 is not applicable to the Surveillances of this Limitation.

SURVEILLANCE FREQUENCY S 2.5.2.1 A land use census to identify the locations described in 24 months between Limitation L 2.5.2 shall be performed by door-to-door survey, June 1 and aerial survey, or by consulting local agricultural authorities. October 1 S 2.5.2.2 Include the results of S 2.5.2.1 in the Annual Radiological 12 months Environmental Operating Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

Revision 27 71

ARKANSAS NUCLEAR ONE ODCM L 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING L 2.5.3 Radioactive materials supplied as part of the Interlaboratory Comparison Program shall be analyzed.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Limitation not met. A.1 Initiate a condition report to Immediately document and track the condition for inclusion in the Annual Radiological Environmental Operating Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

SURVEILLANCES

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

S 2.0.2 is not applicable to the Surveillances of this Limitation.

SURVEILLANCE FREQUENCY S 2.5.3.1 Include the results of analyses performed as part of the 12 months Interlaboratory Comparison Program in the next Annual Radiological Environmental Operating Report pursuant to TS 5.6.2 (ANO-1) / TS 6.6.2 (ANO-2).

Revision 27 72

ARKANSAS NUCLEAR ONE ODCM B 2.0 LIMITITATION (L) APPLICABILITY BASES Limitations L 2.0.1 through L 2.0.5 establish the general requirements applicable to all Limitations and apply at all times, unless otherwise stated.

B 2.0.1 L 2.0.1 establishes the Applicability statement within each individual Limitation as the requirement for when the Limitation is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Limitation).

B 2.0.2 L 2.0.2 establishes that upon discovery of a failure to meet a Limitation, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of a Limitation are not met. This Limitation establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Limitation; and

b. Completion of the Required Actions is not required when a Limitation is met within the specified Completion Time, unless otherwise specified.

Completing the Required Actions is not required when a Limitation is no longer applicable, unless otherwise stated in the individual Specification.

B 2.0.3 L 2.0.3 establishes the Required Actions that must be implemented when a Limitation is not met and the condition is not specifically addressed by the associated Conditions. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. This requirement is intended to provide assurance that plant management is aware of the condition and to ensure that the condition is evaluated for its affect on continued operation of the plant.

B 2.0.4 L 2.0.4 establishes Limitations on changes in MODES or other specified conditions in the Applicability when a Limitation is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the Limitation would not be met, in accordance with Limitation L 2.0.4.a, L 2.0.4.b, or L 2.0.4.c.

Revision 27 73

ARKANSAS NUCLEAR ONE ODCM BASES LIMITATION APPLICABILITY (continued)

B 2.0.4 L 2.0.4 allows entry into a MODE or other specified condition in the (continued) Applicability with the Limitation not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions. The provisions of this Limitation should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to FUNCTIONAL status before entering an associated MODE or other specified condition in the Applicability.

Upon entry into a MODE or other specified condition in the Applicability with the Limitation not met, L 2.0.1 and L 2.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the Limitation is met, or until the unit is not within the Applicability of the Limitation.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by S 2.0.1.

Therefore, utilizing L 2.0.4 is not a violation of S 2.0.1 or S 2.0.4 for any Surveillances that have not been performed on equipment. However, Surveillances must be met to ensure FUNCTIONALITY prior to declaring the associated equipment FUNCTIONAL (or variable within limits) and restoring compliance with the affected Limitation.

B 2.0.5 L 2.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared non-functional to comply with ACTIONS. The sole purpose of this Limitation is to provide an exception to L 2.0.2 (e.g., to not comply with the applicable Required Actions) to allow the performance of required testing to demonstrate:

a. The FUNCTIONALITY of the equipment being returned to service; or

b. The FUNCTIONALITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate FUNCTIONALITY.

This Limitation does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the FUNCTIONALITY of the equipment being returned to service is restarting a ventilation system that has been secured to comply with Required Actions and must be restarted to perform the required testing.

Revision 27 74

ARKANSAS NUCLEAR ONE ODCM B 2.0 SURVEILLANCE (S) APPLICABILITY BASES S 2.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual Limitations, unless otherwise stated in the individual Surveillance. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limitation. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the Limitation except as provided in S 2.0.3. Surveillances are not required to be performed on non-functional equipment or variables outside specified limits.

S 2.0.2 The specified Frequency for each Surveillance is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

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

If a Completion Time requires periodic performance on a "once per . . ." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Limitation are stated in the individual Limitations.

S 2.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the Limitation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the Limitation must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Limitation must immediately be declared not met, and the applicable Condition(s) must be entered.

S 2.0.4 Entry into a MODE or other specified condition in the Applicability of a Limitation shall only be made when the Limitation's Surveillances have been met within their specified Frequency, except as provided by S 2.0.3. When a Limitation is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with L 2.0.4.

Revision 27 75

ARKANSAS NUCLEAR ONE ODCM B 2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION BASES BACKGROUND The Radioactive Liquid Effluent Monitoring Instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases.

LIMITATION The following Radioactive Liquid Effluent Monitoring Instrumentation is required to be FUNCTIONAL:

ANO-1: RE-4642 - Liquid Radwaste Monitor RE-2682 - A Main Steam Line Radiation Monitor RE-2681 - B Main Steam Line Radiation Monitor ANO-2: 2RE-2330 - Liquid Radwaste Monitor 2RE-4423 - Liquid Radwaste Monitor Both radiation monitoring and flow monitoring capability are required to be FUNCTIONAL for each Liquid Radwaste Monitor. With regard to Liquid Radwaste radiation monitoring, the alarm/trip function must also be FUNCTIONAL. The alarm/trip setpoints for these instruments are calculated in accordance with the methods contained in ODCM Section 2.1 to ensure that the alarm/trip will occur prior to potentially exceeding the limits of 10 CFR Part 20.

With regard to the Main Steam Line Radiation Monitors, these monitors must have a measurement range capability from 10-1 mR/hr to 104 mR/hr.

APPLICABILITY The Liquid Radwaste Monitors are required to be FUNCTIONAL during any release via the pathway in which the monitor is installed. The Main Steam Line Radiation Monitors are required to be FUNCTIONAL in MODES 1, 2, 3, and 4.

ACTIONS The following ACTIONS are generally applicable to the pathway in which a radioactive liquid release is in progress. Because more than one release could occur simultaneously, the ACTIONS are modified by a Note that permits separate Condition entry for each non-functional Radioactive Liquid Effluent Monitoring Instrument.

Revision 27 76

ARKANSAS NUCLEAR ONE ODCM B 2.1 ACTIONS (continued)

A.1 If the radiation monitoring feature of the Radioactive Liquid Effluent Monitoring Instrument is non-functional, any release via the associated pathway must be suspended immediately. This prevents the release of unmonitored effluents to the environment.

A.2.1 In addition to Required Action A.1, a non-functional radiation monitoring feature of a Radioactive Liquid Effluent Monitoring Instrument must be returned to a FUNCTIONAL status prior to the restart or subsequent release of effluents via the associated pathway. This prevents the release of unmonitored effluents to the environment. Exceptions to this requirement are included in Required Actions A.2.2.1 through A.2.2.3 below.

A.2.2.1 through A.2.2.3 In lieu of performing Required Action A.2.1 above, grab samples may be obtained and analyzed to provide a backup monitoring method for the effluent release. Because of the importance of monitoring radioactive liquid releases, two independent samples of the effluent must be obtained and analyzed. The independency required is with regard to obtaining and analyzing each sample separately. Two independent personnel are not required to obtain and analyze the two samples.

Notwithstanding the above, computer input data and the discharge valve lineup associated with the effluent release path must be verified by two independent, qualified individuals.

Integrity of independence is maintained by preventing interaction between personnel during the verification process. With regard to valve lineups, independent verification is conducted such that each check constitutes actual identification of the valve and a determination of both required and actual valve position.

B.1 and B.2 If the flow monitoring feature of the Radioactive Liquid Effluent Monitoring Instrument is non-functional, the flow rate may be estimated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of initial loss of the instrument and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, for the duration of the effluent release. Flow rate data is necessary to calculate the amount of radioactive released via the effluent discharge. The 4-hour Completion Time is reasonable because a significant change in flow rate over the course of an effluent release is unlikely.

S 2.0.2 is not applicable to the initial flow estimation, but may be applied to the flow estimations thereafter. Pump curves may be used to estimate flow.

Revision 27 77

ARKANSAS NUCLEAR ONE ODCM B 2.1 ACTIONS (continued)

C.1 If one or more Main Steam Line Radiation Monitors is non-functional, the pre-planned alternate monitoring method of monitoring must be established within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The alternate method chosen should ensure continued monitoring of the Main Steam system for radiation while operating in MODES 1, 2, 3, or 4. In addition, the affected monitor(s) must be restored to a FUNCTIONAL status within 7 days.

D.1 If the Required Actions and associated Completion Times of Conditions A, B, and/or C cannot be met, then additional measures may be necessary to ensure continued safe operation or to reduce overall station risk. Therefore, a condition report must be initiated immediately to assess the impact on continued effluent release operations given the degraded condition.

E.1 Instrumentation installed to ensure radiological monitoring of effluent releases is expected to be normally available in accordance with the design function or purpose of the equipment.

During releases via a respective pathway, instrumentation that remains non-functional for greater than 30 days may indicate inappropriate importance placed on the equipment or over-reliance on the backup sampling method for effluent release monitoring. As an incentive to avoid either of these conditions, Radioactive Liquid Effluent Monitoring Instrumentation that remains non-functional for more than 30 days must be included in the Radioactive Effluent Release Report submitted pursuant to TS 5.6.3 (ANO-1) or TS 6.6.3 (ANO-2). In order to ensure inclusion, Required Action E.1 requires the condition to be tracked via a condition report.

Information to be provided in the respective Radioactive Effluent Release Report should include 1) the component number and noun name, 2) the failure mode, 3) the reason for continued inoperability, and 4) the expected return to service date.

SURVEILLANCES S 2.1.1.1 Performance of the CHANNEL CHECK every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provides reasonable assurance for prompt identification of a gross failure of instrumentation. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. Where parameter comparison is not possible, the CHANNEL CHECK will continue to identify gross instrument failure such as loss of power, unexpected upscale readings, failed-low indications, etc. The CHANNEL CHECK is key in verifying that the instrumentation continues to operate properly between CHANNEL CALIBRATIONs. The Frequency is based on unit operating experience that demonstrates channel failure is rare.

Revision 27 78

ARKANSAS NUCLEAR ONE ODCM B 2.1 SURVEILLANCES (continued)

S 2.1.1.2 A CHANNEL TEST is performed on the radiation monitoring portion of each required instrument channel to ensure the entire channel will perform the intended functions. The CHANNEL TEST demonstrates that automatic isolation of the associated pathway and Control Room alarm occur should the instrument indicate measured levels above the trip setpoint.

The channel test also demonstrates that alarm occurs when any of the following conditions exist:

A. Power to the detector is lost.

B. The instrument indicates a downscale failure.

C. Instrument controls are not set in the operate mode.

Any setpoint adjustment shall be consistent with Section 2.1 of the ODCM.

The Surveillance is modified by a Note clarifying that the CHANNEL TEST is applicable only to the radiation detection portion of the monitor function and is not applicable to the flow monitoring function. The Frequency of 92 days is based on unit operating experience, with regard to channel FUNCTIONALITY and drift, which demonstrates that failure of a channel in any 92-day interval is a rare event, especially in light of the infrequency of radioactive liquid releases.

S 2.1.1.3 CHANNEL CALIBRATION is a complete check of the instrument channel, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drift (as required) to ensure that the instrument channel remains FUNCTIONAL between successive tests. CHANNEL CALIBRATION shall find that measurement errors and setpoint errors are within the assumptions of the setpoint calculations. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the setpoint calculations. This Frequency is justified by the assumption of at least an 18 month calibration interval to determine the magnitude of equipment drift or deviation in the setpoint calculations.

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

Revision 27 79

ARKANSAS NUCLEAR ONE ODCM B 2.1 SURVEILLANCES (continued)

S 2.1.1.4 A SOURCE CHECK provides a qualitative assessment of channel response when the channel sensor is exposed to the radioactive source. This check is performed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to release of effluent via the associated flow path. When a SOURCE CHECK can be performed, it provides verification that the sensor will respond to an increase in radiation level. Note 1, however, does not require a SOURCE CHECK when the background radiation at the sensor is greater than the check source. This is acceptable because of the other required tests above (CHANNEL CHECK, CHANNEL TEST, CHANNEL CALIBRATION). The 8-hour restriction is reasonable because it is unlikely that the sensor will unexpectedly fail in any 8-hour period.

Note 2 provides clarification that the SOURCE CHECK applies only to the radiation detection portion of the Liquid Radwaste Monitor and is not applicable to the flow monitor portion or to the Main Steam Line Radiation Monitors.

Revision 27 80

ARKANSAS NUCLEAR ONE ODCM B 2.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION BASES BACKGROUND The Radioactive Gaseous Effluent Monitoring Instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases.

LIMITATION The following Radioactive Gaseous Effluent Monitoring Instrumentation is required to be FUNCTIONAL:

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

Refer to ANO-2 Technical Specification (TS) 3.3.3.1 for ANO-2 Containment Building Purge System Process Monitor (2RE-8233) operability requirements and associated ACTIONS.

ANO-1: RE-4830 - Waste Gas Holdup System Process Monitor*

RX-9820 - Reactor Building Purge and Ventilation SPING RX-9825 - Auxiliary Building Ventilation SPING RX-9830 - Spent Fuel Pool Area Ventilation SPING RX-9835 - Emergency Penetration Room Ventilation SPING ANO-2: 2RE-2429 - Waste Gas Holdup System Process Monitor*

2RX-9820 - Containment Building Purge and Ventilation SPING 2RX-9825 - Auxiliary Building Ventilation SPING 2RX-9830 - Spent Fuel Pool Area Ventilation SPING 2RX-9835 - Emergency Penetration Room Ventilation SPING 2RX-9845 - Auxiliary Building Extension Ventilation SPING 2RX-9850 - Radwaste Storage Building Ventilation SPING

These monitors provide automatic isolation.

The radiation monitoring (process gas and SPING noble gas) and effluent flow monitoring capability are required to be FUNCTIONAL for each monitor. For SPING monitors the sample flow monitoring, the iodine sample, and the particulate sampler must also be FUNCTIONAL. With regard to Waste Gas Holdup System radiation monitoring, the alarm/trip function must also be FUNCTIONAL. The alarm/trip setpoints for specified instruments are calculated in accordance with the methods contained in ODCM Section 3.1 to ensure that the alarm/trip will occur prior to potentially exceeding the limits of 10 CFR Part 20.105. Note that the PURGE function of the ANO-1 and ANO-2 Reactor (Containment) Building is treated separately from the ventilation function.

Performance of a SOURCE CHECK on a given radiation monitor does not require the monitor to be declared non-functional due to the short period of time required to perform this test.

Revision 27 81

ARKANSAS NUCLEAR ONE ODCM B 2.2 APPLICABILITY The above monitors are required to be FUNCTIONAL during any release via the pathway in which the monitor is installed. Because SPINGs 4 and 8 monitor the Emergency Penetration Room Ventilation of ANO-1 and ANO-2, respectively, and because these ventilation systems are normally aligned for auto-start capability to aid in accident mitigation, these SPINGs must be FUNCTIONAL whenever the associated ventilation system is available for auto-start.

ACTIONS The following ACTIONS are applicable to the pathway in which a radioactive gaseous release is in progress. Because more than one release could occur simultaneously, the ACTIONS are modified by a Note that permits separate Condition entry for each non-functional Radioactive Gaseous Effluent Monitoring Instrument.

A.1 If the radiation monitoring feature, including the alarm/trip function for monitors having an automatic isolation feature, of the Waste Gas Holdup or ANO-1 Reactor Building Purge and Ventilation System Gas Activity Process or Noble Gas Activity Monitor(s) is non-functional, any release via the associated pathway must be suspended immediately. This prevents the release of unmonitored effluents to the environment.

A.2.1 In addition to Required Action A.1, a non-functional Waste Gas Holdup or ANO-1 Reactor Building Purge and Ventilation System Gas Activity Process or Noble Gas Activity Monitor, including the alarm/trip function for monitors having an automatic isolation feature, must be returned to a FUNCTIONAL status prior to the restart or subsequent release of effluents via the associated pathway. This prevents the release of unmonitored effluents to the environment. Exceptions to this requirement are included in Required Actions A.2.2.1 through A.2.2.3 below.

A.2.2.1 through A.2.2.3 In lieu of performing Required Action A.2.1 above, grab samples may be obtained and analyzed to provide a backup monitoring method for the effluent release. Because of the importance of monitoring radioactive gaseous releases, two independent samples of the effluent must be obtained and analyzed. The independency required is with regard to obtaining and analyzing each sample separately. Two independent personnel are not required to obtain and analyze the two samples.

Revision 27 82

ARKANSAS NUCLEAR ONE ODCM B 2.2 ACTIONS (continued)

A.2.2.1 through A.2.2.3 (continued)

Notwithstanding the above, computer input data and the discharge valve lineup associated with the effluent release path must be verified by two independent, qualified individuals.

Integrity of independence is maintained by preventing interaction between personnel during the verification process. With regard to valve lineups, independent verification is conducted such that each check constitutes actual identification of the valve and a determination of both required and actual valve position. Required Action A.2.2.3 is modified by a Note that excepts the valve lineup requirement from the ANO-1 Reactor Building Purge and Ventilation System since no manual valves are manipulated for this release path.

B.1 and B.2 If the flow monitoring features of the Radioactive Gaseous Effluent Monitoring Instrumentation is non-functional, the flow rate may be estimated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of initial loss of the instrument and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, for the duration of the effluent release. Flow rate data is necessary to calculate the amount of radioactive released via the effluent discharge.

Therefore, if flow cannot be estimated, it is necessary to suspend the release of radioactive effluents monitored by the affected channel. The 4-hour Completion Time is reasonable because a significant change in flow rate over the course of an effluent release is unlikely.

A Control Room RDACS trouble alarm is received when sample flows are not within predetermined limits (among other SPING conditions). With regard to SPINGs 4 or 8, procedures require a temporary sample pump to be installed when the sample flow channel is non-functional, which may be used to meet Required Action B.1, even if the flow path is in auto-standby status. With the temporary sample pump installed, Required Action D.1 will be met should the flow path auto start. Therefore, as indicated below, Condition D is not required to be considered while the SPING 4 and 8 flow paths are idle.

S 2.0.2 is not applicable to the initial flow estimation, but may be applied to the flow estimations thereafter. Pump curves may be used to estimate flow.

C.1 and C.2 Condition C is modified by two notes. Note 1 omits this Condition from being applicable to the Waste Gas Holdup or ANO-1 Reactor Building Purge and Ventilation System Gas Activity Process or Noble Gas Activity Monitors. These monitors are addressed in Condition A.

Note 2 requires the associated Required Actions and Completion Times of Condition C be applied to SPINGS 4 and 8 (Emergency Penetration Room Ventilation of ANO-1 and ANO-2, respectively) only when the pathway is in service, since noble gas activity sampling and analysis cannot be performed when the pathway is idle.

Revision 27 83

ARKANSAS NUCLEAR ONE ODCM B 2.2 ACTIONS (continued)

C.1 and C.2 (continued)

With the exception of Waste Gas Holdup System releases or during a PURGE of the ANO-1 Reactor Building, releases may continue via an associated pathway when the Noble Gas Activity Monitor(s) is non-functional, provided a sample of the effluent is obtained once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This prevents the release of unmonitored effluents to the environment. ACTIONS C.1 and C.2 are modified by a note, referring to ANO-1 TS 3.9.3 for additional ACTIONS that may be necessary if the required ANO-1 Reactor Building Purge and Ventilation System Noble Gas Activity Monitor is inoperable.

S 2.0.2 is not applicable to the initial sample and analysis, but may be applied to the sample and analysis thereafter.

D.1, D.2, and D.2 Condition D is modified by a Note which requires the associated Required Actions and Completion Times of Condition D be applied to SPINGS 4 and 8 (Emergency Penetration Room Ventilation of ANO-1 and ANO-2, respectively) only when the pathway is in service, since iodine and particulate sampling and analysis cannot be performed when the pathway is idle.

If one or more required Iodine and/or Particulate Samplers are non-functional, auxiliary sampling equipment must be established within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The backup Iodine and Particulate cartridges must be replaced every 7 days. Following replacement, the respective cartridge must be analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . This prevents the release of unmonitored effluents to the environment.

E.1 If the Required Actions and associated Completion Times of Condition C and/or D cannot be met, then releases via the associated pathway must be suspended. This prevents the release of unmonitored effluents to the environment.

F.1 If the Required Actions and associated Completion Times of Condition A, B, and/or E cannot be met, then additional measures may be necessary to ensure continued safe operation or to reduce overall station risk. Therefore, a condition report must be initiated immediately to assess the impact on continued effluent release operations given the degraded condition.

Revision 27 84

ARKANSAS NUCLEAR ONE ODCM B 2.2 ACTIONS (continued)

G.1 Instrumentation installed to ensure radiological monitoring of effluent releases is expected to be normally available in accordance with the design function or purpose of the equipment.

Instrumentation that remains non-functional for greater than 30 days may indicate inappropriate importance placed on the equipment or over-reliance on the backup sampling method for effluent release monitoring. As an incentive to avoid either of these conditions, Radioactive Gaseous Effluent Monitoring Instrumentation that remains non-functional for more than 30 days must be included in the Radioactive Effluent Release Report submitted pursuant to TS 5.6.3 (ANO-1) or TS 6.6.3 (ANO-2). In order to ensure inclusion, Required Action G.1 requires the condition to be tracked via a condition report.

Information to be provided in the respective Radioactive Effluent Release Report should include 1) the component number and noun name, 2) the failure mode, 3) the reason for continued inoperability, and 4) the expected return to service date.

SURVEILLANCES S 2.2.1.1 Performance of the CHANNEL CHECK every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provides reasonable assurance for prompt identification of a gross failure of instrumentation. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. Where parameter comparison is not possible, the CHANNEL CHECK will continue to identify gross instrument failure such as loss of power, unexpected upscale readings, failed-low indications, etc. The CHANNEL CHECK is key in verifying that the instrumentation continues to operate properly between CHANNEL CALIBRATIONs. The Frequency is based on unit operating experience that demonstrates channel failure is rare.

This Surveillance is modified by a Note the exempts the Iodine and Particulate Samplers from a CHANNEL CHECK since these components do not have electronic features or indications.

S 2.2.1.2 A local check must be made every 7 days to verify that required Iodine Sampler cartridges and Particulate Sample filters are in place. The 7-day Frequency is reasonable because it is unlikely a cartridge or filter could be inadvertently removed from the system.

Revision 27 85

ARKANSAS NUCLEAR ONE ODCM B 2.2 SURVEILLANCES (continued)

S 2.2.1.3 and S 2.2.1.6 A CHANNEL TEST is performed on required Gas Activity Process and Noble Gas Activity Monitors to ensure the entire channel will perform the intended functions. For the Waste Gas Holdup and ANO-2 Containment Building Purge Systems, the CHANNEL TEST demonstrates that automatic isolation of the associated pathway and Control Room alarm occur should the instrument indicate measured levels above the trip setpoint. The channel test also demonstrates that alarm occurs when any of the following conditions exist:

A. Power to the detector is lost.

B. The instrument indicates a downscale failure.

C. Instrument controls are not set in the operate mode.

Any setpoint adjustment shall be consistent with Section 3.1 of the ODCM.

Because the alarm/trip function and/or the importance of the release path, a CHANNEL TEST of the associated Gas Activity Process and Noble Gas Activity Monitors is required within 31 days prior to release via the Waste Gas Holdup or ANO-1 Reactor Building Purge and Ventilation Systems. This ensures the monitors are FUNCTIONAL within a reasonable period of time before such a release is commenced. All active pathway Gas Activity Process and Noble Gas Activity Monitors undergo a CHANNEL TEST once every 92 days. This Frequency is reasonable because each has a Control Room alarm function.

S 2.2.1.4 and S 2.2.1.5 A SOURCE CHECK provides a qualitative assessment of channel response when the channel sensor is exposed to the radioactive source. This check is performed within 14 days prior to release of effluent via the Waste Gas Holdup or ANO-1 Reactor Building Purge Systems. The 14-day restriction is reasonable because it is unlikely that the sensor will unexpectedly fail in any 14-day period. All active pathway Gas Activity Process and Noble Gas Activity Monitors must undergo a SOURCE CHECK every 31 days. This Frequency is reasonable because each has a Control Room alarm function.

When a SOURCE CHECK can be performed, it provides verification that the sensor will respond to an increase in radiation level. Note 1 of S 2.2.1.5 and the Note associated with S 2.2.1.4 does not require a SOURCE CHECK when the background radiation at the sensor is greater than the check source. This is acceptable because of the other required tests above (CHANNEL CHECK, CHANNEL TEST, and CHANNEL CALIBRATION).

Revision 27 86

ARKANSAS NUCLEAR ONE ODCM B 2.2 SURVEILLANCES (continued)

S 2.2.1.7 CHANNEL CALIBRATION is a complete check of the instrument channel, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drift (as required) to ensure that the instrument channel remains FUNCTIONAL between successive tests. CHANNEL CALIBRATION shall find that measurement errors and setpoint errors are within the assumptions of the setpoint calculations. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the setpoint calculations. This Frequency is justified by the assumption of at least an 18 month calibration interval to determine the magnitude of equipment drift or deviation in the setpoint calculations.

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

This Surveillance is modified by a Note the exempts the Iodine and Particulate Samplers from a CHANNEL CALIBRATION since these components do not have electronic features or indications.

Revision 27 87

ARKANSAS NUCLEAR ONE ODCM B 2.3 RADIOACTIVE LIQUID EFFLUENTS BASES BACKGROUND This Limitation is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limit provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures greater than the Section II.A design objectives of 10 CFR 50, Appendix I, to a MEMBER OF THE PUBLIC.

LIMITATION The concentration limit for noble gases is based upon the assumption that Xe-133 is the controlling radioisotope and its maximum permissible concentration (MPC) in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

Radioactive nuclides other than dissolved or entrained noble gases must be maintained within the limits of 10 CFR 20, Appendix B, Table II, Column 2 values. The various dose limitations are conservative with regard to 10 CFR 20 requirements in order to provide a margin of safety through the use of as low as reasonably achievable (ALARA) practices.

Necessary portions of the LIQUID RADWASTE TREATMENT SYSTEM shall be used to reduce the radioactive materials in liquid waste prior to discharge when it is projected that the cumulative dose during a calendar quarter due to liquid effluent releases would exceed 0.18 mrem to the total body or 0.625 mrem to any organ. The provisions of this Limitation do not apply to the laundry tanks due to their incompatibility with the radwaste system.

The specified limits governing the use of appropriate portions of the LIQUID RADWASTE TREATMENT SYSTEM are a suitable fraction of the guide set forth in Section II.A of 10 CFR 50, Appendix I, for liquid effluents. The values of 0.18 mrem and 0.625 mrem are approximately 25% of the yearly design objectives on a quarterly basis. The yearly design objectives are provided in 10 CFR 50, Appendix I, Section II.

APPLICABILITY The Limitations are required to be met at all times.

ACTIONS Because more than one Limitation or Surveillance requirement may not be met at a given time, the ACTIONS are modified by a Note that permits separate Condition entry for each Limitation and/or Surveillance requirement that is not met.

Revision 27 88

ARKANSAS NUCLEAR ONE ODCM B 2.3 ACTIONS (continued)

A.1 and A.2 If any Limitation L 2.3.1.a through L 2.3.1.e is not met, action must be initiated immediately to restore the parameter within limits. This could require a reduction in offsite releases scheduled for the near future or further processing of effluents prior to release. In any event, a condition report must be initiated to determine whether additional actions are necessary to permit continued operations involving radioactive liquid effluent releases given the current circumstances. In addition, corrective action must be issued to identify and track the Limitation that was exceeded for inclusion in the annual Radioactive Effluent Release Report. However, the condition need not be reported in the annual Radioactive Effluent Release Report if reported otherwise (i.e., in accordance with reporting requirements of 10 CFR 20, 10 CFR 50.72, 10 CFR 50.73, or 40 CFR 190).

B.1 and B.2 If the sampling and/or analysis requirements of S 2.3.1.1 are not met, the release must be terminated. This action prevents or minimizes the potential for an unmonitored offsite radioactive liquid release. Such release may commence or be re-initiated once the sampling and analysis requirements of S 2.3.1.1 are met. Regardless, a condition report must be initiated to determine whether additional actions are necessary to permit continued operations involving radioactive liquid effluent releases given the current circumstances. If a condition report has already been initiated relevant to this Condition, then this assessment may be performed in conjunction with that condition report; a second condition report is not required.

C.1 and C.2 This ACTION is modified a Note, limiting its applicability to only a CONTINUOUS RELEASE of secondary coolant.

With elevated dose equivalent I-131 (DEI) activity in the secondary coolant, it is prudent to modify the frequencies for obtaining and analyzing grab samples. Therefore, with secondary coolant DEI > 0.01 µCi/ml, sample frequency is modified from once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The analysis of the sample must be completed with 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of sample acquisition. More frequent monitoring of the secondary coolant will assist in detecting further increases in activity and provide personnel better opportunity for in developing corrective action plans, as necessary.

Revision 27 89

ARKANSAS NUCLEAR ONE ODCM B 2.3 ACTIONS (continued)

D.1 In accordance with 40 CFR 190, a variance must be received from the regulatory authority (NRC) if offsite dose to a member of the public will, or has exceeded, limits established in 40 CFR 190. Because Surveillance S 2.3.1.3 tracks the accumulated dose to members of the public over specified time periods (calendar quarter or calendar year), the dose may be projected and a determination made with regard to whether it is likely 40 CFR 190 limits will be exceeded. If 40 CFR 190 limits are projected to be exceeded, an application for a variance from the NRC must be submitted prior to the estimated date in which any 40 CFR 190 limit will be exceeded. The variance will allow continued offsite liquid and gaseous releases in excess of 40 CFR 190 limits. Note that the variance is normally expected to remain in effect until the end of the current calendar year since 40 CFR 190 limits only apply to the calculated annual dose to members of the public.

If application for variance cannot be made prior to exceeding any 40 CFR 190 limit, it may be prudent to notify the NRC by phone as soon as possible of the need for a variance, providing the expected date in which the application will be submitted. Note that the NRC may provide verbal approval for variance in situations where time is a factor.

E.1 If the Required Actions and associated Completion Times of Conditions C and/or D cannot be met or if the sampling and/or analysis requirements denoted in Surveillances S 2.3.1.1 and/or S 2.3.1.2 are not met, then additional measures may be necessary to ensure continued safe operation or to reduce overall station risk. Therefore, a condition report must be initiated immediately to assess the impact on continued effluent release operations given the requirements that are not being met.

F.1 Surveillance S 2.3.1.5 establishes required capability of various sample analyses. A given analysis must be capable of detecting respective radioactivity at a reasonably low threshold in order to ensure radioactive liquid releases to the public are carefully and accurately monitored.

If the stated thresholds can not be met, a condition report must be initiated and corrective action issued to ensure the condition is included and described in the annual Radioactive Effluent Release Report.

Revision 27 90

ARKANSAS NUCLEAR ONE ODCM SURVEILLANCES S 2.3.1.1 and S 2.3.1.2 All radioactive liquid effluent releases are required to be monitored. Because a BATCH RELEASE is of a known quantity and of finite duration, sampling of batch effluents must be performed prior to release. In addition, the sample must undergo a gamma isotopic and DEI analysis prior to the release to provide high confidence that radioactive release limits will not be exceeded. Remaining analyses may then be completed at the designated Frequency during or following the release.

For a BATCH RELEASE, a composite sample, one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released, is performed.

In order to ensure a representative sample, the batch shall be thoroughly mixed before the sample is obtained.

Unlike the BATCH RELEASE, a CONTINUOUS RELEASE must be monitored at a set Frequency. While gross activity monitoring is available for various release paths as is recommended by Regulatory Guide (RG) 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, such monitoring does not provide the necessary breakdown and quantification of radioactivities being discharged. Therefore, the ODCM requires grab samples and analyses of these effluents at a specified Frequency.

To be representative of the quantities and concentrations of radioactive materials in liquid effluents, a CONTINUOUS RELEASE sample must be proportional to the rate of flow of the effluent stream.

S 2.3.1.3 Limitation L 2.3.1 establishes limits on radioactive liquid concentrations discharged from the plant and the accumulative dose that may be received by a MEMBER OF THE PUBLIC as a result of such releases. In order to determine that these limits are met and being maintained, the results of analyses required by Surveillances S 2.3.1.1 and S 2.3.1.2 must be compared to the Limitation requirements on a specified Frequency. Therefore, analysis results obtained within a given 7-day period must be considered, in some cases along with previous analysis results of all liquid release over a specified period of time (calendar quarter or calendar year),

to ensure limits are not exceeded.

S 2.3.1.4 In accordance with 40 CFR 190, a variance must be received from the regulatory authority (NRC) is offsite dose to a member of the public will, or has exceeded, limits established in 40 CFR 190. Because Surveillance S 2.3.1.3 tracks the accumulated dose to members of the public over specified time periods (calendar quarter or calendar year), the dose may be projected and a determination made with regard to whether it is likely 40 CFR 190 limits will be exceeded. The 31-day Frequency is acceptable because associated ODCM limits for these releases are significantly less than those described in 40 CFR 190 and, therefore, it is unlikely any 40 CFR 190 limit would be exceeded in any 31-day period.

Revision 27 91

ARKANSAS NUCLEAR ONE ODCM B 2.3 SURVEILLANCES (continued)

S 2.3.1.5 The Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a real signal. This Surveillance contains a list of isotopes and required LLD for each. Sample analysis sensitivity must be such that radioactivities can be detected and measured at the LLD value.

It should be recognized that the LLD is an a Priori (before the fact) limit representing the capability of measurement system and not an a Posteriori (after the fact) limit for a particular measurement.

For a particular measurement system (which may include radio-chemical separation):

4.66Sb LLD =

E

V

T

2.22

Y

e-t where:

LLD = lower limit of detection as defined above (as pCi per unit mass or volume)

Sb = standard deviation of the background or blank sample counts

= square root of either the background or the blank sample counts E = counting efficiency (as counts per transformation)

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

T = elapsed count time 2.22 = number of transformations per minute per picocurie Y = fractional radiochemical yield (when applicable)

= radioactive decay constant for the particular radionuclide t = elapsed time between sample collection (or end of the sample collection period) and time of counting Typical values of E, V, Y and t should be used in the calculation.

For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentration of such radionuclides using observed ratios with those radionuclides which are measurable.

Revision 27 92

ARKANSAS NUCLEAR ONE ODCM B 2.3 SURVEILLANCES (continued)

S 2.3.1.5 (continued)

The principal gamma emitters for which the LLD limitation will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD requirements not being met, the reasons shall be documented in the Radioactive Effluent Release Report as stated in Required Action F.1 of this Limitation, or the Annual Radiological Environmental Operating Report as stated in L 2.5.1, Required Action A.2.

Revision 27 93

ARKANSAS NUCLEAR ONE ODCM B 2.4 RADIOACTIVE GASEOUS EFFLUENTS BASES BACKGROUND This Limitation is provided to ensure that radioactive materials released in gaseous effluents from the site to unrestricted areas will be less than the limits specified in 10 CFR Part 20. This Limitation also implements the requirements of Sections II.C, III.A, and IV.A of 10 CFR 50, Appendix I.

Figure 4-2 illustrates the maximum area boundary for radioactive release calculations. For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary.

LIMITATION Radioactive nuclides must be maintained within the limits of 10 CFR 20. The various dose rate and dose limitations are conservative with regard to 10 CFR 20 requirements in order to provide a margin of safety through the use of as low as reasonably achievable (ALARA) practices.

The necessary VENTILATION EXHAUST TREATMENT SYSTEMs shall be used to reduce the radioactive materials in gases prior to discharge when it is projected that the cumulative dose during a calendar quarter due to gaseous effluent releases would exceed values specified in this Limitation. The specified limits governing the use of the VENTILATION EXHAUST TREATMENT SYSTEMs are a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of 10 CFR Part 50, Appendix I, for gaseous effluents.

APPLICABILITY The Limitations are required to be met at all times.

ACTIONS Because more than one Limitation or Surveillance requirement may not be met at a given time, the ACTIONS are modified by a Note that permits separate Condition entry for each Limitation and/or Surveillance requirement that is not met.

Revision 27 94

ARKANSAS NUCLEAR ONE ODCM B 2.4 ACTIONS (continued)

A.1 and A.2 If any Limitation L 2.4.1.a through L 2.4.1.d is not met, action must be initiated immediately to restore the parameter within limits. This could require a reduction in offsite releases scheduled for the near future or further processing of effluents prior to release. In any event, a condition report must be initiated to determine whether additional actions are necessary to permit continued operations involving radioactive gaseous effluent releases given the current circumstances. In addition, corrective action must be issued to identify and track the Limitation that was exceeded for inclusion in the annual Radioactive Effluent Release Report. However, the condition need not be reported in the annual Radioactive Effluent Release Report if reported otherwise (i.e., in accordance with reporting requirements of 10 CFR 20, 10 CFR 50.72, 10 CFR 50.73, or 40 CFR 190).

B.1 and B.2 If the sampling and/or analysis requirements of S 2.4.1.1 are not met, the release must be terminated. This action prevents or minimizes the potential for an unmonitored offsite radioactive liquid release. Such release may commence or be re-initiated once the sampling and analysis requirements of S 2.4.1.1 are met. Regardless, a condition report must be initiated to determine whether additional actions are necessary to permit continued operations involving radioactive liquid effluent releases given the current circumstances. If a condition report has already been initiated relevant to this Condition, then this assessment may be performed in conjunction with that condition report; a second Condition Report is not required.

C.1 In accordance with 40 CFR 190, a variance must be received from the regulatory authority (NRC) if offsite dose to a member of the public will, or has exceeded, limits established in 40 CFR 190. Because Surveillance S 2.4.1.3 tracks the accumulated dose to members of the public over specified time periods (calendar quarter or calendar year), the dose may be projected and a determination made with regard to whether it is likely 40 CFR 190 limits will be exceeded. If 40 CFR 190 limits are projected to be exceeded, an application for a variance from the NRC must be submitted prior to the estimated date in which any 40 CFR 190 limit will be exceeded. The variance will allow continued offsite liquid and gaseous releases in excess of 40 CFR 190 limits. Note that the variance is normally expected to remain in effect until the end of the current calendar year since 40 CFR 190 limits only apply to the calculated annual dose to members of the public.

If application for variance cannot be made prior to exceeding any 40 CFR 190 limit, it may be prudent to notify the NRC by phone as soon as possible of the need for a variance, providing the expected date in which the application will be submitted. Note that the NRC may provide verbal approval for variance in situations where time is a factor.

Revision 27 95

ARKANSAS NUCLEAR ONE ODCM B 2.4 ACTIONS (continued)

D.1 If the Required Actions and associated Completion Times of Condition C cannot be met or if the sampling and/or analysis requirements denoted in Surveillances S 2.4.1.2 are not met, then additional measures may be necessary to ensure continued safe operation or to reduce overall station risk. Therefore, a condition report must be initiated immediately to assess the impact on continued effluent release operations given the requirements that are not being met.

E.1 Surveillance S 2.4.1.5 establishes required capability of various sample analyses. A given analysis must be capable of detecting respective radioactivity at a reasonably low threshold in order to ensure radioactive gaseous releases to the public are carefully and accurately monitored. If the stated thresholds can not be met, a condition report must be initiated and corrective action issued to ensure the condition is included and described in the annual Radioactive Effluent Release Report.

SURVEILLANCES Continuous gaseous release paths are monitored by instrumentation denoted in Limitation L 2.2.1. Limitation L 2.2.1 provides Required Actions and Completion Times for circumstances when required instrumentation is out of service. Therefore, the Surveillances associated with this Limitation (L 2.4.1) envelop only required grab, charcoal, and particulate samples necessary to verify 10 CFR 20 limits will be met.

The Surveillance Limitations implement the requirements in 10 CFR 50, Appendix I, Section III.A, that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in this manual for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in RG 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977, and RG 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1, July 1977. The equations in this manual provided for determining the air doses at and beyond the site boundary are based upon the historical average atmospheric conditions.

The release rate limitations for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at or beyond the site boundary. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

Revision 27 96

ARKANSAS NUCLEAR ONE ODCM B 2.4 SURVEILLANCES (continued)

S 2.4.1.1 and S 2.4.1.2 All radioactive gaseous effluent releases are required to be monitored. Because a Waste Gas Holdup Tank or Reactor (Containment) Building Purge release is of a known (or estimated) quantity and of finite duration, sampling of these effluents must be performed prior to release.

In addition, the sample must be analyzed for principal gamma emitters and tritium prior to the release in order to provide high confidence that radioactive release limits will not be exceeded.

S 2.4.1.3 To meet the intent of the continuous monitoring requirement for noble gases, the noble gas activity from each SPING operating on an activity flow path must be recorded at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The current, highest, and average activity recorded from a particular SPING over the required grab sample period designated in other Surveillances associated with this Limitation are used to scale the noble gas and tritium activity obtained from the associated grab sample. The final resulting activity is used, in part, to support completion of S 2.4.1.4 and S 2.4.1.5 below.

S 2.4.1.4 Limitation L 2.4.1 establishes limits on radioactive gases discharged from the plant and the dose rates and accumulative dose that may be received by a MEMBER OF THE PUBLIC as a result of such releases. In order to determine that these limits are met and being maintained, the results of analyses required by Surveillances S 2.4.1.1 and S 2.4.1.2, as adjusted by readings taken in accordance with S 2.4.1.3 as appropriate must be compared to the Limitation requirements on a specified Frequency. Therefore, analysis results obtained within a given 31-day period must be considered, in some cases along with previous analysis results of all gaseous releases over a specified period of time (calendar quarter or calendar year), to ensure limits are not exceeded.

The ratio of the sample flow rate to the sampled stream flow rate must be known for the time period covered by each dose or dose rate calculation made in accordance with this Limitation.

S 2.4.1.5 In accordance with 40 CFR 190, a variance must be received from the regulatory authority (NRC) is offsite dose to a member of the public will, or has exceeded, limits established in 40 CFR 190. Because Surveillance S 2.4.1.3 tracks the accumulated dose to members of the public over specified time periods (calendar quarter or calendar year), the dose may be projected and a determination made with regard to whether it is likely 40 CFR 190 limits will be exceeded. The 31-day Frequency is acceptable because associated ODCM limits for these releases are significantly less than those described in 40 CFR 190 and, therefore, it is unlikely any 40 CFR 190 limit would be exceeded in any 31-day period.

Revision 27 97

ARKANSAS NUCLEAR ONE ODCM B 2.4 SURVEILLANCES (continued)

S 2.4.1.6 The Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a real signal. This Surveillance contains a list of isotopes and required LLD for each. Sample analysis sensitivity must be such that radioactivies can be detected and measured at the LLD value. The Surveillance also contains the LLD for the Noble Gas Monitors associated with Limitation 2.2.1.

For an explanation of the LLD calculation, refer to the S 2.3.1.5 Bases.

For certain radionuclides with low gamma yield or low energies, or for certain radionuclides mixtures, it may not be possible to measure radionuclides in concentrations near the LLD.

Under these circumstances, the LLD may be increased inversely proportional to the magnitude of the gamma yield (i.e., (1 x 10-4/I)), where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be > 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 1.

The principal gamma emitters for which the LLD limitation will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.

Revision 27 98

ARKANSAS NUCLEAR ONE ODCM B 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 2.5.1 Environmental Sampling BASES BACKGROUND The ODCM includes, in tables and figures, specific parameters of distance and direction from the centerline of one reactor, and additional description where pertinent, for each sample location required by the Radiological Environmental Monitoring Program. NUREG-0133, "Preparation of Radiological Technical Specifications for Nuclear Power Plants," October 1978, and Radiological Assessment Branch Technical Position (BTP), Revision 1, November 1979, provide guidance with regard to environmental sampling.

With regard to the aforementioned BTP, one airborne sample location should be from the vicinity of a community having the highest calculated annual average ground-level D/Q.

Community as defined by Websters dictionary is people with common interests living in a particular area; broadly: the area itself. The local municipalities of London, Russellville, and Dardanelle are all part of the River Valley community located near Dardanelle Lake and the Arkansas River. The grouping of houses that reside within WSW (highest D/Q) sector are located in London which is part of the River Valley community. Air Station #2 per the above mentioned NRC BTP meets the requirements of being located within the highest D/Q and also in the vicinity of a community. Reference CR-ANO-C-2016-2732.

The approximate locations of selected sample sites are shown on ODCM Figures 4-1, 4-1A, and 4-1B for illustrative purposes. ODCM Table 4-1 lists the approximate distances and directions of the sample stations from the plant.

D/Q refers to a radiological deposition rate considering prevalent winds around the site and is used to determine natural settling of effluents from the atmosphere.

LIMITATION This Limitation specifies the sample locations and distances, sample analysis type and frequency, and parameters to be sampled as part of the Radiological Environmental Monitoring Program.

The Limitation is modified by a Note that permits other instrumentation to be used in place of, or in addition to, integrating dosimeters for measuring and recording dose rate continuously.

For the purposes of this Limitation, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet considered as two or more dosimeters.

Film badges should not be used for measuring direct radiation.

APPLICABILITY The Limitations are required to be met at all times.

Revision 27 99

ARKANSAS NUCLEAR ONE ODCM B 2.5.1 ACTIONS Because more than one Limitation or Surveillance requirement may not be met at a given time, the ACTIONS are modified by a Note that permits separate Condition entry for each Limitation and/or Surveillance requirement that is not met.

A.1 and A.2 Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunctions, every effort shall be made to complete corrective action before the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report.

This ACTION lists several items that would result in the intent of the Radiological Environmental Monitoring Program not being met. In addition, this ACTION provides guidance for conditions where radionuclides other than those listed in Table 2.5-2 could result in a noteworthy dose to a MEMBER OF THE PUBLIC. Immediate action is required to restore conditions needed to meet the intent of the Radiological Environmental Monitoring Program.

All deviations from the Limitations and Surveillances required to meet the intent of the Radiological Environmental Monitoring Program must be reported in the Annual Radiological Environmental Operating Report. However, the condition need not be reported in the Annual Radiological Environmental Operating Report if reported otherwise (i.e., in accordance with reporting requirements of 10 CFR 20, 10 CFR 50.72, 10 CFR 50.73, or 40 CFR 190).

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at one or more required locations exceeding the limits of Table 2.5-2 when averaged over any calendar quarter, the condition must be reported in accordance with Required Action A.2. The report should include an evaluation of any release conditions, environmental factors or other aspects which caused the limits to be exceeded, and define the actions taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC will remain less than the calendar year limits of Limitations L 2.3.1 and L 2.4.1. When more than one of the radionuclides in Table 2.5-2 is detected in the sampling medium, the information shall be included in the report if:

Concentration 1 Concentration 2 etc.

+ + 1.0 Reporting Level 1 Reporting Level 2 etc.

B.1 In addition to the requirements of Required Actions A.1 and A.2, a new location must be identified and added to the Radiological Environmental Monitoring Program within 30 days when required samples cannot be obtained from designated locations. Note that broad leaf samples are only required when milk samples are unavailable, pursuant to S 2.5.1.8.

Revision 27 100

ARKANSAS NUCLEAR ONE ODCM B 2.5.1 ACTIONS (continued)

B.1 (continued)

The specific locations from which samples were unavailable may then be deleted from the monitoring program. The cause(s) of the unavailability of samples the new location(s) for obtaining replacement samples shall be identified in next Annual Radiological Environmental Operating Report. The report shall also include a revised Table 4-1 reflecting the new location(s).

SURVEILLANCES S 2.5.1.1 through S 2.5.1.8 These Surveillances ensure samples are collected and analyzed at specified frequencies of the parameters, and from the locations, designated in Limitation L 2.5.1. The approximate locations of selected sample sites are shown on ODCM Figures 4-1, 4-1A, and 4-1B for illustrative purposes. ODCM Table 4-1 lists the approximate distances and directions of the sample stations from the plant.

Note that the gross beta analysis of required particulate samplers should not be performed within the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following particulate filter change. This is to allow for radon and thoron daughter decay. If it is discovered that the particulate gross beta activity is more than 10 times the yearly mean of control samples for any medium, consideration should be given to performing a gamma isotopic analysis of the individual particulate samples. Also note that particulate samples may need to be collected more frequently than the specified 14-day Frequency due to dust or other accumulation of matter.

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

S 2.5.1.9 The Lower Limit of Detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a real signal. Table 2.5-1 contains a list of isotopes and required LLD for each. Sample analysis sensitivity must be such that radioactivities can be detected and measured at the LLD value.

For an explanation of the LLD calculation, refer to the S 2.3.1.5 Bases.

S 2.5.1.10 With the level of radioactivity as the result of plant effluents in an environmental sampling medium at one or more required locations exceeding the limits of Table 2.5-2 when averaged over any calendar quarter, the condition must be reported in accordance with Required Action A.2.

Revision 27 101

ARKANSAS NUCLEAR ONE ODCM B 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 2.5.2 Land Use Census BASES BACKGROUND The surveys required by this Limitation ensure that changes in environmental conditions as they relate to radioactive effluent releases from the site are identified and accounted for in the overall dose commitment to the public.

LIMITATION This Limitation ensures changes in the use of unrestricted areas are identified and that modifications are subsequently included in the Radiological Environmental Monitoring Program. The census satisfies 10 CFR 50, Appendix I, Section IV.B.3.

Restricting the census to gardens of > 500 ft2 provides assurance that significant exposure pathway 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 RG 1.109 for consumption by a child. This minimum garden size was determined assuming

1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage) and, 2) a vegetation yield of 2 kg/m2.

The Limitation is modified by a Note that permits broad leaf vegetation sampling to be performed at the site boundary in the directional sector having the highest D/Q in lieu of performing a garden census. D/Q refers to a radiological deposition rate considering prevalent winds around the site and is used to determine natural settling of effluents from the atmosphere.

APPLICABILITY The Limitations are required to be met at all times.

ACTIONS Because more than one new sample location may be identified during a given census, the ACTIONS are modified by a Note permit separate Condition entry for each new location identified.

Revision 27 102

ARKANSAS NUCLEAR ONE ODCM B 2.5.2 ACTIONS (continued)

A.1, A.2.1, and A.2.2 When new locations are discovered that indicate higher radioactivity levels than current locations being sample pursuant to Limitation L 2.5.1 or if radioactivity levels at a new location are projected to exceed 40 CFR 190 limits (with regard to I-131, H-3, and particulate sources),

a condition report must be immediately initiated. Initiating a condition report will ensure reporting criteria is evaluated for the given condition. Regardless of any other report, the new location must be included in the next Annual Radiological Environmental Operating Report.

In addition to the requirements of Required Action A.1, the new location must be added to the Radiological Environmental Monitoring Program within 30 days. Following October 31 of the year in which the census is taken, the old sample location in this same pathway may be deleted from the Radiological Environmental Monitoring Program. This is expected to be performed within 90 days following the October 31 limit.

SURVEILLANCES S 2.5.2.1 through S 2.5.2.2 The land use census must be performed every 24 months and between the dates of June 1 and October 1 of the given year. The results of the census must be reported in the next Annual Radiological Environmental Operating Report.

The Surveillance requirements are modified by a Note that prevents the use of S 2.0.2.

Therefore, the 25% Frequency extension associated with S 2.0.2 cannot be applied to the Surveillances associated with this Limitation. This is because the Frequencies are associated with strict performance and reporting dates which cannot be exceeded.

Revision 27 103

ARKANSAS NUCLEAR ONE ODCM B 2.5 RADIOLOGICAL ENVIRONMENTAL MONITORING B 2.5.3 Interlaboratory Comparison Program BASES BACKGROUND This Limitation refers to the off-site radiochemistry laboratory. The Limitation provides independent checks on the accuracy of the measurements of radioactive material in environmental samples.

LIMITATION The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

APPLICABILITY The Limitations are required to be met at all times.

ACTION A.1 Failure to meet the requirements of the Interlaboratory Comparison Program requires initiating a condition report to ensure the circumstances are included in the next Annual Radiological Environmental Operating Report.

SURVEILLANCE S 2.5.3.1 The results of the Interlaboratory Comparison Program analyses must be reported in the next Annual Radiological Environmental Operating Report.

Revision 27 104

0CAN041702, Annual Radioactive Effluent Release Report for 2016

Contents

Text

SUBJECT:

Dear Sir or Madam:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

RESPONSE

Navigation menu

0CAN041702, Annual Radioactive Effluent Release Report for 2016

Text

SUBJECT:

Dear Sir or Madam:

Enclosure:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

RESPONSE

Navigation menu

Search