Text

2022 Annual Radioactive Effluent Release Report
	ML23116A218
Person / Time
Site:	Kewaunee
Issue date:	04/26/2023
From:	Jeffery Lynch; Kewaunee Solutions
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	KS-2023-012
	Download: ML23116A218 (1)
	v • d • e

April 26, 2023 KS-2023-012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Kewaunee Solutions, Inc.

Facility Operating License No. DPR-43 NRC Docket No. 50-305

Subject:

Kewaunee Power Station 2022 Annual Radioactive Effluent Release Report Enclosed is the Kewaunee Power Station (KPS) 2022 Annual Radioactive Effluent Release Report for January through December 2022. This report is submitted to meet the requirements of KPS Technical Requirements Manual (TRM) Section 10.3. Also included are Revision 20 of the Offsite Dose Calculation Manual (ODCM), Revision 24 of the Radiological Environmental Monitoring Manual (REMM) and Revision 0 of the Kewaunee Solutions Radwaste Process Control Program. These are submitted to meet the requirements of KPS TRM Section 10.1.1.

If you have any questions or require additional information, please contact Mr. Joseph R. Lynch at 508-728-1421.

Respectfully, Joseph R. Lynch Licensing Manager Kewaunee Solutions, Inc.

Commitments made in this letter: None

~

KEWAUNE SOL TIO S Joseph R. Lynch Digitally signed by Joseph R.

Lynch Date: 2023.04.26 07:31:57

-04'00'

KS-2023-012 Page 2 of 2 Kewaunee Power Station, N490 Highway 42, Kewaunee, WI 54216 Attachments:

1.

Kewaunee Solutions Kewaunee Power Station Annual Radioactive Effluent Release Report.

2.

Kewaunee Solutions Kewaunee Power Station Offsite Dose Calculation Manual (ODCM), Revision 20.

3.

Kewaunee Solutions Kewaunee Power Station Radiological Environmental Monitoring Manual (REMM), Revision 24.

4.

Kewaunee Solutions Radwaste Process Control Program, Revision 0.

cc:

Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Mr. Karl Sturzebecher, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop O8-D15 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Robert Busch Wisconsin Department of Health Services Radiation Protection Section Attn: Radioactive Materials Program P.O. Box 2659 Madison, WI 53701-2659 Ms. Deborah Russo American Nuclear Insurers (ANI) 95 Glastonbury Blvd.

Suite 300 Glastonbury, CT 06033-4453

KS-2023-012 Kewaunee Power Station, N490 Highway 42, Kewaunee, WI 54216 ATTACHMENT 1 Kewaunee Solutions Kewaunee Power Station Annual Radioactive Effluent Release Report (20 Pages)

DOCKET 50-305 KEWAUNEE SOLUTIONS KEWAUNEE POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1 - December 31, 2022

Page 2 of 20 Table of Contents Section Description 0.0 Summary............................................................................................................ 3 1.0 Introduction........................................................................................................ 4 1.1 Effluent Dose Limits.......................................................................................... 4 2.0 Gaseous Effluents.............................................................................................. 5 2.1 Lower Limits of Detection (LLD) for Gaseous Effluents................................. 5 2.2 Gaseous Effluent Data....................................................................................... 6 Table 2.1 Gaseous Effluents - Summation of all Releases (Continuous Mode) 7 Table 2.2 Dose from Gaseous Effluents............................................................ 8 3.0 Liquid Effluents............................................................................................... 10 3.1 Lower Limits of Detection (LLD) for Liquid Effluents.................................. 10 3.2 Liquid Batch Release Statistics....................................................................... 10 3.3 Liquid Effluent Data........................................................................................ 10 Table 3.1 Liquid Effluents - Summation of all Releases (Batch Mode)......... 11 Table 3.2 Dose from Liquid Effluents............................................................. 12 3.4 Ground Water Monitoring........................................................................... 13 4.0 Meteorological Data........................................................................................ 15 5.0 Solid Waste Disposal....................................................................................... 15 Table 5.1 Solid Waste and Irradiated Fuel Shipments.................................... 16 6.0 Supplemental Information............................................................................... 19 Appendix A Solid Radioactive Waste Process Control Program (PCP) Revision 0 Appendix B Offsite Dose Calculation Manual (ODCM) Revision 20 Appendix C Radiological Environmental Monitoring Manual (REMM) Revision 24

Page 3 of 20 0.0

SUMMARY

On February 25, 2013, Dominion Energy Kewaunee (DEK) submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).

Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel in the reactor vessel, as specified in 10 CFR 50.82(a)(2).

On June 15, 2017, the transfer of all spent fuel from the KPS Spent Fuel Pool (SFP) to the Independent Spent Fuel Storage Installation (ISFSI) was completed. All remaining irradiated materials were removed from the SFP in October 2017.

All radioactive liquid was drained from systems in the Auxiliary Building by the end of the first week of August 2018.

The remaining effluent release paths are continuous gaseous radioactive releases from the Auxiliary Building Vent and batch liquid radioactive waste releases to Lake Michigan. Batch gaseous radioactive releases and continuous liquid radioactive releases are no longer performed.

On June 28, 2022, Dominion Energy Kewaunee (DEK) was sold to Energy Solutions and assumed the new company name of Kewaunee Solutions. The sale included the Kewaunee Power Station and ISFSI, and transfer of the operating license DPR-43.

In 2022 there were no identified gaseous radionuclides released from the Auxiliary Building Vent, and no batch liquid radioactive waste releases to Lake Michigan.

In 2022 there were no solid and /or oil waste shipments off site.

Page 4 of 20

1.0 INTRODUCTION

This report is being submitted in accordance with the requirements of Kewaunee Technical Requirements Manual, Section 10.3.2 and the Offsite Dose Calculation Manual, Section 15.2. It includes data from all effluent releases made from January 1 - December 31, 2022. The report contains summaries of the gaseous and liquid releases made to the environment including the quantity, characterization, time duration and calculated radiation dose at the site boundary resulting from these releases. The report also includes a summation of solid radioactive waste disposal and the revisions to the Solid Radioactive Waste Process Control Program (PCP), Offsite Dose Calculation Manual (ODCM) and Radiological Environmental Monitoring Manual (REMM). Values indicated as 0 (zero) in this report refer to actual values less than the detection limits. A table of these less than detectable (LLD) values is identified in sections 2.1 and 3.1.

1.1 Effluent Dose Limits Specifications are set to ensure that offsite doses are maintained as low as reasonably achievable while still allowing for practical and dependable evolutions at the Kewaunee Power Station.

The Kewaunee Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in:

1.

The calculation of radioactive liquid effluent monitoring instrumentation alarm/trip set points.

2.

The calculation of radioactive liquid and gaseous concentrations, dose rates and cumulative quarterly and annual doses. The ODCM methodology is acceptable for use in demonstrating compliance with 10 CFR 20.1301/1302; 10 CFR 50, Appendix I; and 40 CFR 190.

Page 5 of 20 2.0 GASEOUS EFFLUENTS 2.1 Lower Limits of Detection (LLD) for Gaseous Effluents Gaseous radioactive effluents are released in the continuous mode. Batch gaseous radioactive releases are no longer performed. The Auxiliary Building ventilation stack was sampled continuously for Particulates, Gross Alpha, and Strontium 90, by an "off-line" sample train. This stack was also grab-sampled monthly for Tritium.

The LLD's for gaseous radio-analyses, as listed in Table 13.2.1-1 of the Kewaunee ODCM are:

Analysis LLD (µCi/ml)

Particulate Gamma Emitters 1.00E-11 Particulate Gross Alpha 1.00E-11 Strontium 90 1.00E-11 Tritium (H-3) 1.00E-06 The nominal "a priori" LLD values are shown below.

Isotope a priori LLD (µCi/ml)

a. Particulate emissions:

Mn-54 1.11E-13 Co-60 3.57E-13 Cs-134 4.69E-13 Cs-137 1.68E-13 Ce-144 1.24E-12

b. Composite particulate samples:

Sr-90 1.00E-14 Gross Alpha 1.00E-14 These "a priori" LLDs represent the capabilities of the counting systems in use, not an after the fact "a posteriori" limit for a particular measurement.

Page 6 of 20 2.2 Gaseous Effluent Data Table 2.1 presents a quarterly summation of the total activity released and average release rates of gaseous effluents (continuous mode). Table 2.2 presents the dose limits for gaseous effluents, and the calculated doses this year from gaseous effluents.

Page 7 of 20 Table 2.1 Gaseous Effluents - Summation of all Releases (Continuous Mode) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Particulates Total Activity Released (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (µCi/sec) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium Total Activity Released (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (µCi/sec) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Released (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 8 of 20 Table 2.2 Dose from Gaseous Effluents The offsite dose limits from radioactive materials in gaseous effluents are specified in Section 13.2.3 of the Kewaunee ODCM and can be summarized as follows:

Organ Quarterly Limit 7.5 mrem Annual Limit 15.0 mrem The following offsite doses were calculated using equation 2.2 from the Kewaunee ODCM. Calculated offsite doses versus quarterly and annual limits are shown below.

In 2022 there were no identified gaseous radionuclides released from the Auxiliary Building Vent.

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual

1. Organ Dose Specification (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 Total Body Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Bone Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Liver Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 9 of 20 Table 2.2 (continued)

Dose from Gaseous Effluents 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Thyroid Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kidney Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Lung Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 GI-LLI Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 10 of 20 3.0 LIQUID EFFLUENTS 3.1 Lower Limits of Detection (LLD) for Liquid Effluents Liquid radioactive effluents are released as batch releases. Continuous liquid radioactive releases are no longer performed. Each batch is sampled prior to release and analyzed for gamma emitters and tritium. A fraction of each sample is retained for a proportional composite which is then analyzed for Gross Alpha, Strontium 90, Iron 55 and Nickel 63.

The LLD's for liquid batch release radio-analyses, as listed in Table 13.1.1-1 of the Kewaunee ODCM are:

Analysis LLD (µCi/ml)

Principal Gamma Emitters 1.00 E-06 Tritium (H-3) 1.00 E-05 Gross Alpha 5.00 E-07 Strontium 90 5.00 E-08 Iron 55 1.00 E-06 Nickel 63 1.00 E-04 There were no batch liquid radioactive waste releases to Lake Michigan in 2022, therefore there are no a priori LLD values shown below.

3.2 Liquid Batch Release Statistics The following is a summation of all liquid batch releases during 2022.

Number of batch releases...................................0 Total time for all batch releases (min)...............0 Maximum time for a batch release (min)...........0 Minimum time for a batch release (min)............0 Average time for a batch release (min)...............0 3.3 Liquid Effluent Data The following Table 3.1 presents a quarterly summation of the total activity released (batch mode) and average concentration for all liquid effluents. It also presents the gross alpha activity released, volume of waste released, and volume of dilution water used. Table 3.2 presents the doses from liquid effluents for each quarter and the calculated doses this year from liquid effluents.

Page 11 of 20 Table 3.1 Liquid Effluents - Summation of all Releases (Batch Mode) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total Fission and Activation Products Total Release (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Concentration

(µCi/ml) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium Total Release (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Concentration

(µCi/ml) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification Limit(3.0E-3 µCi/ml) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gross Alpha Activity Total Release (Ci) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Volume of Waste Released Total (liters) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Volume of Dilution Water Total (liters) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 There were no batch liquid radioactive waste releases to Lake Michigan in 2022.

Page 12 of 20 Table 3.2 Dose from Liquid Effluents There were no batch liquid radioactive releases to Lake Michigan in 2022.

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Total Body Specification (mrem) 1.50E+00 1.50E+00 1.50E+00 1.50E+00 3.00E+00 Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Organs Specification (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 Bone Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Liver Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Thyroid Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kidney Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Lung Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 GI-LLI Actual Dose (mrem) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

% of Specification 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Page 13 of 20 3.4 Ground Water Monitoring The Kewaunee Power Station has 14 wells used to sample for groundwater contamination. Eight of the wells are located to monitor for leakage from the Auxiliary Building (AB). The other six wells are designated as Monitoring Wells (MW) and sample areas outside the industrial security area to identify any spread of contamination. As the data below indicates there was no gamma activity identified and the tritium in all the AB and MW wells was below Minimum Detectable Concentrations (MDC). The tritium levels have decreased to below MDC in the AB and MW wells since the plant was permanently shut down in 2013. There were no voluntary ground water communications, no spills, and no leaks in 2022. Changes to the Groundwater Protection Program, including abandonment of the eight AB monitoring wells and the installation of seven new MW monitoring wells, were initiated during the fall of 2022 to support the transition from the SAFSTOR to DECON method of decommissioning of the site in 2023. A description of the changes made to the Groundwater Protection Program will be included with the sample results in the 2023 annual report.

Sample Point Sample Date Tritium pCi/L Total Gamma Activity

µCi/ml AB-707 4/21/2022

<340 None Detected AB-708 4/21/2022

<340 None Detected AB-709 5/5/2022

<272 None Detected AB-710 5/5/2022

<272 None Detected AB-711 6/23/2022

<278 None Detected AB-712 6/23/2022

<278 None Detected

Page 14 of 20 Sample Point Sample Date Tritium pCi/L Total Gamma Activity

µCi/ml AB-715 7/4/2022

<254 None Detected AB-717 7/4/2022

<254 None Detected MW-701 8/25/2022

<381 None Detected MW-702 8/25/2022

<381 None Detected MW-703 9/26/2022

<254 None Detected MW-704 9/26/2022

<254 None Detected MW-705 10/13/2022

<349 None Detected MW-706 10/13/2022

<349 None Detected

Page 15 of 20 4.0 METEOROLOGICAL DATA Meteorological data is no longer required to be reported in accordance with the Kewaunee ODCM Rev. 19, Section 15.2.

5.0 SOLID WASTE DISPOSAL Table 5.1 is a summation of solid and oil radioactive waste shipped during 2022. Presented are the types of waste streams, waste classification, and major nuclides.

In 2022 there were no solid and /or oil waste shipments off site.

Page 16 of 20 Table 5.1 Solid Waste and Irradiated Fuel Shipments A. Solid Radioactive Waste Shipped Off-Site for Burial or Disposal

1.

Type of Waste with Estimate of Major Nuclide Composition Resins, Filters, and Evaporator Bottoms Volume Curies Shipped Waste Class ft3 m3 Curies A

0.00E+00 0.00E+00 0.00E+00 B

0.00E+00 0.00E+00 0.00E+00 C

0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 0.00E+00 0.00E+00 0.00E+00 Major nuclides for the above table: NA Dry Active Waste Volume Curies Shipped Waste Class ft3 m3 Curies A

0.00E+00 0.00E+00 0.00E+00 B

0.00E+00 0.00E+00 0.00E+00 C

0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 0.00E+00 0.00E+00 0.00E+00 Major nuclides for the above table: NA

Page 17 of 20 Table 5.1 (continued)

Solid Waste and Irradiated Fuel Shipments Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A

0.00E+00 0.00E+00 0.00E+00 B

0.00E+00 0.00E+00 0.00E+00 C

0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 0.00E+00 0.00E+00 0.00E+00 Major nuclides for the above table: NA Other Waste -Oil Volume Curies Shipped Waste Class ft3 m3 Curies A

0.00E+00 0.00E+00 0.00E+00 B

0.00E+00 0.00E+00 0.00E+00 C

0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 0.00E+00 0.00E+00 0.00E+00 Major nuclides for the above table: NA Sum of All Low-Level Waste Volume Curies Shipped Waste Class ft3 m3 Curies A

0.00E+00 0.00E+00 0.00E+00 B

0.00E+00 0.00E+00 0.00E+00 C

0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 All 0.00E+00 0.00E+00 0.00E+00 Major nuclides for the above table: NA

Page 18 of 20 Table 5.1 (continued)

Solid Waste and Irradiated Fuel Shipments B.

Irradiated Fuel Shipments Number of Shipments Mode of Transportation Destination None NA NA No irradiated fuel shipments were made from the Kewaunee Power Station during 2022.

Page 19 of 20 6.0 SUPPLEMENTAL INFORMATION 6.1 Abnormal Releases or Abnormal Discharges No abnormal releases or abnormal discharges were made from the Kewaunee Power Station during the report period.

6.2 Non-routine Planned Discharges No non-routine planned discharges were made from the Kewaunee Power Station during the reporting period.

6.3 Program Revisions In accordance with Technical Requirements Manual Section 10.1.1.c.3 and the Offsite Dose Calculation Manual Section 15.2.f, revisions to the Process Control Program, Offsite Dose Calculation Manual, or the Radiological Environmental Monitoring Program for the report period are listed below.

6.3.1 Process Control Program Revision 0 of the Kewaunee Solutions Radwaste Process Control Program was issued November 7, 2022. See Appendix A.

6.3.2 Offsite Dose Calculation Manual Revision 20 of the Kewaunee Solutions Offsite Dose Calculation Manual was issued November 7, 2022. See Appendix B.

6.3.3 Radiological Environmental Monitoring Manual Revision 24 of the Kewaunee Power Station Radiological Environmental Monitoring Manual (REMM) was issued November 7, 2022. See Appendix C.

6.4 Major Changes to the Radioactive Liquid, Gaseous and Solid Waste Systems There were no changes to the radioactive liquid, gaseous, or solid waste systems during the reporting period.

6.5 Effluent Monitoring System Inoperability There were no effluent radiation monitors inoperable for the consecutive time period listed in the ODCM for this report period.

Page 20 of 20 6.6 Corrections to Previous Reports None.

6.7 Other None.

KS-2023-012 Kewaunee Power Station, N490 Highway 42, Kewaunee, WI 54216 ATTACHMENT 2 Kewaunee Solutions Kewaunee Power Station Offsite Dose Calculation Manual (ODCM),

Revision 20 (112 Pages)

Kewaunee Solutions Kewaunee Power Station OFFSITE DOSE CALCULATION MANUAL (ODCM)

Revision: 20 Date: November 7, 2022 Approved By:

KS Radiation Protection Manager (RPM) (Print/Sign)

Date Approved By:

KS Licensing Manager (Print/Sign)

Date Approved By:

Kewaunee Solutions Project General Manager (Print/Sign)

Date Approved By:

KS Project Operations Review Committee Chairman (Print/Sign)

Date David S Villicana Digitally signed by David S Villicana DN: cn=David S Villicana, o=EnergySolutions, ou=RP, email=Dsvillicana@energysolutions.com, c=US Date: 2022.08.30 11:14:12 -05'00' Joseph R. Lynch Digitally signed by Joseph R. Lynch Date: 2022.08.30 13:47:22 -04'00' Ron Worster Digitally signed by Ron Worster Date: 2022.08.30 12:34:11 -06'00' Digitally signed by Frank Coon DN: O=Energysolutions, CN=Frank Coon, E=fcoon-ext@energysolutions.com Reason: I am the author of this document Location:

Date: 2022-09-10 11:25:24 Foxit PhantomPDF Version: 9.4.1 Frank Coon

Kewaunee Solutions Kewaunee Power Station ODCM Offsite Dose Calculation Manual (ODCM)

Revision 20 ii RECORD OF REVISIONS Revision Revision Title Description and Reason for Change 20 Changed company name on coversheet from Dominion Energy Kewaunee to Kewaunee Solutions to reflect ownership change.

20 Changed titles of approvers on coversheet to Kewaunee Solutions managers and Project Operations Review Committee to reflect ownership change.

20 Added Record of Revisions to allow for tracking of changes.

20 Added Kewaunee Solutions to page headers and the coversheets for PART I and PART II to reflect ownership change.

20 Minor editorial changes throughout page v - 10 CFR 20 and deleted reference to APPENDICES A-D that had no content and were deleted; section 2.6 CFR 50 and 40 CFR 190; units at top of Table 2.2 (page 1 of 2) corrected to m3; Deleted pages A-1, B-1, C-1, and D-1 that had no content and are no longer applicable (they are blank in current Rev 19).

20 Section 13.0.1, page 13.0.1-3, changed definition of Process Control Program definition changed FSRG to Project Operations Review Committee (PORC). PORC is the KS review committee that replaced FSRG for review of the PCP.

20 Section 15.1, page 15.1-1, changed FSRG to Project Operations Review Committee (PORC) for review of major changes to radioactive waste systems in section (three places on this page). PORC is the review committee that replaced FSRG for review of the changes 20 Section 15.1, page 15.1-1, changed footnote (1) at bottom of page from USAR to DSAR. DSAR has replaced USAR for KPS

Kewaunee Solutions Kewaunee Power Station ODCM TOC Offsite Dose Calculation Manual (ODCM)

Revision 20 iii TABLE OF CONTENTS PAGE PART I - RADIOLOGICAL EFFLUENT CONTROLS NORMAL CONDITIONS AND BASES

11.0 INTRODUCTION

11.0-1 12.0 (Not Used) 13.0 USE AND APPLICATION 13.0.1 Definitions 13.0.1-1 13.0.2 Logical Connectors 13.0.2-1 13.0.3 Restoration Times 13.0.3-1 13.0.4 Frequency 13.0.4-1 13.0.5 ODCM Normal Condition (DNC) Applicability 13.0.5-1 13.0.6 ODCM Verification Requirement (DVR) 13.0.6-1 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration 13.1.1-1 13.1.2 Liquid Effluents Dose 13.1.2-1 13.1.3 Liquid Radwaste Treatment System 13.1.3-1 13.1.4 Liquid Holdup Tanks 13.1.4-1 13.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.1 Gaseous Effluents Dose Rate 13.2.1-1 13.2.2 Content Deleted. No Longer Applicable 13.2.2-1 13.2.3 Gaseous Effluents Dose - Particulate 13.2.3-1 13.2.4 Gaseous Radwaste Treatment System 13.2.4-1 13.2.5 Content Deleted. No Longer Applicable 13.2.5-1 13.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-1 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-1 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 13.4.1 Radioactive Effluents Total Dose 13.4.1-1

Kewaunee Solutions Kewaunee Power Station ODCM TOC Offsite Dose Calculation Manual (ODCM)

Revision 20 iv PAGE 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.1 Monitoring Program 13.5.1-1 13.5.2 Land Use Census 13.5.2-1 13.5.3 Interlaboratory Comparison Program 13.5.3-1 14.0 DESIGN FEATURES 14.1 Gaseous and Liquid Effluent Release Points 14.1-1 15.0 ADMINISTRATIVE CONTROLS 15.1 Major Changes to Radioactive Waste Systems 15.1-1 15.2 Radioactive Effluent Release Report 15.2-1 15.3 Special Reports 15.3-1

Kewaunee Solutions Kewaunee Power Station ODCM TOC Offsite Dose Calculation Manual (ODCM)

Revision 20 v

PART II CALCULATIONAL METHODOLOGIES PAGE 1.0 LIQUID EFFLUENT METHODOLOGY 1.1 Radiation Monitoring Instrumentation and Controls 1.0-1 1.2 Liquid Effluent Monitor Setpoint Determination 1.0-1 1.3 Liquid Effluent Concentration Limits - 10 CFR 20 1.0-4 1.4 Liquid Effluent Dose Calculation - 10 CFR 50 1.0-4 1.5 Liquid Effluent Dose Projections 1.0-7 2.0 GASEOUS EFFLUENT METHODOLOGIES 2.1 Radiation Monitoring Instrumentation and Controls 2.0-1 2.2 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 2.0-2 2.3 Gaseous Effluent Dose Calculations - 10 CFR 50 2.0-3 2.4 Gaseous Effluent Dose Projection 2.0-4 2.5 Environmental Radiation Protection Standards 40 CFR 190 2.0-5 2.6 Total Dose 2.0-5

Kewaunee Solutions Kewaunee Power Station ODCM TOC Offsite Dose Calculation Manual (ODCM)

Revision 20 vi LIST OF TABLES PAGE PART I - RADIOLOGICAL EFFLUENT CONTROLS 13.1.1-1 Radioactive Liquid Waste Sampling and Analysis 13.1.1-3 13.2.1-1 Radioactive Gaseous Waste Sampling and Analysis 13.2.1-3 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-5 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-3 PART II - CALCULATIONAL METHODOLOGIES 1.1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATIONS 1.0-9 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTORS 1.0-10 1.3 BIOACCUMULATION FACTORS 1.0-12 2.1 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS 2.0-7 2.2 Ri INHALATION PATHWAY DOSE FACTORS-ADULT 2.0-9 2.3 Ri INHALATION PATHWAY DOSE FACTORS-TEEN 2.0-11 2.4 Ri INHALATION PATHWAY DOSE FACTORS-CHILD 2.0-13 2.5 Ri INHALATION PATHWAY DOSE FACTORS-INFANT 2.0-15 2.6 Ri VEGETATION PATHWAY DOSE FACTORS-ADULT 2.0-17 2.7 Ri VEGETATION PATHWAY DOSE FACTORS-TEEN 2.0-19 2.8 Ri VEGETATION PATHWAY DOSE FACTORS-CHILD 2.0-21 2.9 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-ADULT 2.0-23 2.10 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-TEEN 2.0-25 2.11 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-CHILD 2.0-27 2.12 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-INFANT 2.0-29 2.13 Ri GROUND PLANE PATHWAY DOSE FACTORS 2.0-31

Kewaunee Solutions Kewaunee Power Station ODCM TOC Offsite Dose Calculation Manual (ODCM)

Revision 20 vii LIST OF FIGURES PAGE PART I - RADIOLOGICAL EFFLUENT CONTROLS 14.1-1 LOCATION OF RADIOACTIVE EFFLUENT RELEASE POINTS 14.1-2 PART II - CALCULATIONAL METHODOLOGIES 1

LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM 1.0-8 2

GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM 2.0-6

Kewaunee Solutions Kewaunee Power Station Offsite Dose Calculation Manual PART I - RADIOACTIVE EFFLUENT CONTROLS

Kewaunee Solutions Kewaunee Power Station ODCM 11.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 11.0 - 1

11.0 INTRODUCTION

The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Requirements Manual Section 10.1.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part II.

Part I, Radiological Effluent Controls, includes: (1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Requirements Manual 10.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Requirements Manual 10.3.1 and 10.3.2, respectively.

Part II, Calculational Methodologies: provides the methodology to manually calculate radiation dose rates and doses to individual persons in UNRESTRICTED AREAS due to the routine release of gaseous and liquid effluents. Computer programs are utilized to routinely estimate the doses due to radioactivity in gaseous and liquid effluents. Manual dose calculations are performed when computerized calculations are not available.

The methodology stated in this manual is acceptable for use in demonstrating compliance with 10 CFR 20.1302; 10 CFR 50, Appendix I; and 40 CFR 190.

More conservative calculational methods and/or conditions (e.g., location and/or exposure pathways) expected to yield higher computed doses than appropriate for the maximally exposed person may be assumed in the dose evaluations.

The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations. Changes will be made to the ODCM calculational methodologies and parameters as is deemed necessary to assure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are ALARA.

11.1 Change Process Instructions for defining the responsibilities and requirements for revision and control of both the ODCM and the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) are located in approved station procedure for Revision and Control of the REMM and ODCM.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.1 - 1 13.0 USE AND APPLICATION 13.0.1 Definitions

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

Terms defined in the OFFSITE DOSE CALCULATION MANUAL appear in capitalized type and are applicable throughout the Radiological Effluent Controls Normal Conditions and Bases and the Calculational Methodologies.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes CONTINGENCY MEASURES to be taken under designated Nonconformances within specified Restoration Times.

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 FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST consists of injecting a simulated signal into the channel as close to the primary sensor as practicable to verify that it is FUNCTIONAL, including alarm and/or trip initiating action.

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. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

FUNCTIONAL -

FUNCTIONALITY A structure, system or component (SSC), shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s) as set forth in the Current License Basis. FUNCTIONALITY does not apply to specified safety functions, but does apply to the ability of non-TS SSCs to perform other specified functions that have a necessary support function.

MAJOR DECOMMISSIONING ACTIVITY MAJOR DECOMMISSIONING ACTIVITY means, for a nuclear power reactor facility, any activity that results in permanent removal of major radioactive components, permanently modifies the structure of the containment, or results in dismantling components for shipment containing greater than Class C waste in accordance with 10 CFR 61.55.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC means any individual except when that individual is receiving an OCCUPATIONAL DOSE.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.1 - 2 OCCUPATIONAL DOSE OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individuals assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. OCCUPATIONAL DOSE does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75, from voluntary participation in medical research programs, or as a MEMBER OF THE PUBLIC.

OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive liquid effluents, in the calculation of liquid effluent monitoring alarm/trip setpoints, in the conduct of the Radiological Environmental Monitoring Program. Shall also contain the Radioactive Effluent Controls and Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Requirements Manual 10.3.1 and 10.3.2.

ODCM NORMAL CONDITIONS (DNC)

Specify minimum requirements for ensuring safe plant decommissioning activities. The Contingency Measures associated with a DNC state Nonconformances that typically describe the ways in which the requirements of the DNC can fail to be met. Specified with each stated Nonconformance are Contingency Measures and Restoration Time(s).

ODCM VERIFICATION REQUIREMENTS (DVR)

Verification requirements are requirements relating to test, calibration, or inspection to assure that the necessary FUNCTIONALITY of systems and components are maintained, that plant decommissioning activities will be maintained within the current licensing basis, and that the ODCM Normal Condition (DNC) will be met.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.1 - 3 PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formulae, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes, based on demonstrated processing of actual or simulated wet solid wastes, will be accomplished in such a way as to ensure compliance with 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71, Federal and State regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste.

Licensee initiated changes to the PCP, which was approved by the Commission prior to implementation:

1. Shall be documented and records of reviews performed shall be retained as required by the quality assurance program. The documentation shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s).

b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

2. Shall become effective upon review and acceptance by the Project Operations Review Committee (PORC).

PUBLIC DOSE PUBLIC DOSE means the dose received by a MEMBER OF THE PUBLIC from exposure to radiation or to radioactive material released by a licensee, or to any other source of radiation under the control of a licensee. PUBLIC DOSE does not include OCCUPATIONAL DOSE or doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75, or from voluntary participation in medical research programs.

PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)

The REMM shall contain the current methodology and parameters used in the conduct of the radiological environmental monitoring program.

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, leased, nor otherwise controlled by the licensee. (See Plant Drawing A-408)

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

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.1 - 4 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on tritium or other non-particulate effluents.

VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a VENTING process.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.2 - 1 13.0 USE AND APPLICATION 13.0.2 Logical Connectors Logical Connectors are discussed in Section 7.2 of the Technical Requirements Manual and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.3 - 1 13.0 USE AND APPLICATION 13.0.3 Restoration Times Restoration Times are discussed in Section 7.3 of the Technical Requirements Manual and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.

When "Immediately" is used as a Restoration Time, the Contingency Measure should be pursued without delay in a controlled manner.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.4 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.4 - 1 13.0 USE AND APPLICATION 13.0.4 Frequency Frequency is discussed in Section 7.4 of the Technical Requirements Manual and is applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.5 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.5 - 1 13.0 USE AND APPLICATION 13.0.5 ODCM Normal Condition (DNC) Applicability DNC 13.0.5.1 DNCs shall be met during the specified conditions in the Applicability.

DNC 13.0.5.2 Upon discovery of a failure to meet the DNC, the Contingency Measures of the associated Nonconformance shall be met, except as provided in DNC 13.0.5.4.

DNC 13.0.5.3 When it is discovered that a DNC has not been met and the associated contingency measures are not satisfied within the specified restoration time (or an associated contingency measure is not provided), the equipment subject to the DNC is in a nonconforming condition. In this situation, appropriate actions shall be taken as necessary to provide assurance of continued safe plant decommissioning activities. In addition a Condition Report shall be initiated and assessment of reasonable assurance of safety shall be conducted. Items to be considered for this assessment include the following:

Availability of redundant or backup equipment; Compensatory measures, including limited administrative controls; Safety function and events protected against; Probability of needing the safety function; and Conservatism and margins.

If this assessment concludes that safety is sufficiently assured, then plant decommissioning activities may continue while prompt corrective action is taken.

DNC 13.0.5.4 Equipment removed from service or declared nonfunctional to comply with Contingency Measures 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 DNC 13.0.5.2 for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONALITY.

Kewaunee Solutions Kewaunee Power Station ODCM 13.0.6 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.0.6 - 1 13.0 USE AND APPLICATION 13.0.6 ODCM VERIFICATION REQUIREMENTS (DVR) Applicability DVR 13.0.6.1 DVRs shall be met during the specified conditions in the Applicability for individual DNCs, unless otherwise stated in the DVR. Failure to meet a DVR, whether such failure is experienced during the performance of the DVR or between performances of the DVR, shall be failure to meet the DNC. Failure to perform a DVR within the specified Frequency shall be failure to meet the DNC except as provided in DVR 13.0.6.3. DVRs do not have to be performed on nonfunctional equipment or variables outside specified limits.

DVR 13.0.6.2 Each Verification Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified DVR frequency.

DVR 13.0.6.3 When it is discovered that a DVR frequency (including the 1.25 times extension) has not been met, the equipment subject to the DVR is in a nonconforming condition. In this situation, a Condition Report shall be initiated and, if indicated, determination to evaluate the impact on plant safety shall be performed in a timely fashion and in accordance with plant procedures.

Actions should be taken to restore conformance with the DNCs / DVRs in a timely fashion.

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.1 - 1 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration DNC 13.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to:

a.

10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.

APPLICABILITY:

During release via the monitored pathway.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeds limits.

A.1 Initiate ACTION to restore concentration to within limits.

Immediately B. CONTINGENCY MEASURES OR RESTORATION TIME not met.

B.1 Initiate a CR AND B.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.

In accordance with Corrective Action Program In accordance with Radioactive Effluent Release Report

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.1 - 2 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.1.1 Perform radioactive liquid waste sampling and activity analysis.

In accordance with Table 13.1.1-1

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

In this DVR the results of DVR 13.1.1.1 shall be used in accordance with the methodology and parameters of the ODCM.

DVR 13.1.1.2 Verify the results of the DVR 13.1.1.1 analyses to assure that the concentrations at the point of release are maintained within the limits of DNC 13.1.1.

In accordance with Table 13.1.1-1

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.1 - 3 Table 13.1.1-1 (Page 1 of 2)

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

(a)

1. Batch Waste Release Tanks (b)

a.

Principal Gamma Emitters(c)

Grab Sample Each Batch (f)

Each Batch (g) 1 x 10-6 Ci/ml

b.

H-3 Grab Sample Each Batch (f)

Each Batch (g) 1 x 10-5 Ci/ml

c.

Gross Alpha Composite (d)

Each Batch (f) 184 days (e) 5 x 10-7 Ci/ml

d.

Sr-90 Composite (d)

Each Batch (f) 184 days (e) 5 x 10-8 Ci/ml

e.

Fe-55 Composite (d)

Each Batch (f) 184 days (e) 1 x 10-6 Ci/ml

f.

Ni-63 Composite (d)

Each Batch (f) 184 days (e) 1 x 10-4 Ci/ml

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.1 - 4 Table 13.1.1-1 (Page 2 of 2)

Radioactive Liquid Waste Sampling and Analysis (a) The LLD is defined, for purposes of these DNCs, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a real signal.

For a particular measurement system, which may include radiochemical separation:

x Where:

LLD is the a priori lower limit of detection as defined above, as Ci per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

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

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

(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

(c) The principal gamma emitters for which the LLD requirement applies, includes the following radionuclides:

Mn-54, Fe-59, Co-60, Cs-134, Cs-137, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identified, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Section 15.2.

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

(e) At a minimum, analyze semi-annually if batch releases were made within the six (6) month period. A grab sample of the batch volume can substitute for the composite.

(f) Draw sample for each batch volume.

(g) Complete prior to each release.

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.1 - 5 BASES This DNC is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),

Currie, L.A., Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry, Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.2 - 1 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.2 Liquid Effluents Dose DNC 13.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials released in liquid effluents released to UNRESTRICTED AREAS shall be limited to:

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

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

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents to UNRESTRICTED AREAS exceeds limits.

A.1 Prepare and submit to the NRC, pursuant to Section 15.3, a Special Report that (1) Identifies the cause(s) for exceeding the limit(s) and; (2) Defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DNC 13.1.2.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.2 - 2 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B.

Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents exceeds 2 times the limits.

B.1 Calculate the annual dose to a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the facility (including outside storage tanks, etc.).

AND B.2 Verify that the limits of DNC 13.4.1 have not been exceeded.

Immediately Immediately C.

CONTINGENCY MEASURE B.2 and Associated RESTORATION TIME not met.

C.1 Prepare and submit to the NRC, pursuant to Section 15.3, a Special Report, as defined in 10 CFR 20.2203 (a)(4), of CONTINGENCY MEASURE A.1 shall also include the following:

(1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DNC 13.4.1 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.2 - 3 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.2.1 Determine cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year in accordance with the methodology and parameters in the ODCM.

31 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.2 - 4 BASES This DNC is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR 50. The DNC implements the guides set forth in Section II.A of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.3 - 1 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.3 Liquid Radwaste Treatment System DNC 13.1.3 The Liquid Radwaste Treatment System, as described in the ODCM, shall be used to reduce the radioactive material in liquid wastes prior to their discharge when the projected dose, due to the liquid effluent, to UNRESTRICTED AREAS would exceed in a 31 day period:

a.

> 0.06 mrem to the total body; or

b.

> 0.2 mrem to any organ.

APPLICABILITY:

At all times, except for the parts of the system taken permanently out of service.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Radioactive liquid waste being discharged without treatment and in excess of the above limits.

A.1 Prepare and submit to the NRC, pursuant to Section 15.3, a Special Report that includes:

(1) An explanation of why liquid radwaste was being discharged without treatment, identification of any non-functional /

inoperable equipment or subsystems, and the reason for the non-functional / inoperability, (2) ACTION(s) taken to restore the non-functional

/ inoperable equipment to FUNCTIONAL /

OPERABLE status, and (3) Summary description of ACTION(s) taken to prevent a recurrence.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.3 - 2 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.3.1 Project the doses due to liquid effluents from the facility to UNRESTRICTED AREAS in accordance with the methodology and parameters specified in the ODCM.

31 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.3 - 3 BASES The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable.

This DNC implements the requirements of 10 CFR Part 50.36a, July 1967 Atomic Energy Commission (AEC) General Design Criteria 70 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.4 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.4 - 1 13.1 LIQUID EFFLUENTS 13.1.4 Liquid Holdup Tanks DNC 13.1.4 The quantity of radioactivity contained in unprotected outdoor liquid storage tanks shall be limited to less than the amount that would result in concentrations less than the limits in 10 CFR20, Appendix B, Table II, Column 2, at the nearest potable water supply and surface water supply in an UNRESTRICTED AREA, excluding tritium.

APPLICABILITY:

At all times.

ACTIONS VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.4.1 Sample and analyze radioactive liquid located in unprotected outdoor liquid storage tanks for level of radioactivity.

31 days during addition of radioactive liquid to the tanks NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Level of radioactivity exceeds the limits in any listed tank.

A.1 Suspend addition of radioactive material.

AND A.2 Initiate measures to reduce content to within the limits.

AND A.3 Describe the events leading to the condition in the Radioactive Effluent Release Report.

Immediately 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Prior to submittal of next Radioactive Effluent Release Report

Kewaunee Solutions Kewaunee Power Station ODCM 13.1.4 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.1.4 - 2 13.1.4 Liquid Holdup Tanks BASES The tanks listed in this Normal Condition include outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the radwaste treatment system.

Technical Requirements Manual 10.1.3 requires a program to ensure that the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of any such tanks contents, the resulting concentration would be less than the limits of 10 CFR 20, Appendix B Table II, Column 2 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA. Tank quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, Postulated Radioactive Release due to Tank Failures.

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.1 - 1 13.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.1 Gaseous Effluents Dose Rate DNC 13.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

For tritium and for all radionuclides in particulate form with half-lives 8 days, 1500 mrem/yr to any organ.

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

The dose rate(s) at or beyond the SITE BOUNDARY due to radioactive gaseous effluents exceeds limits.

A.1 Restore the release rate to within the limit.

Immediately B. CONTINGENCY MEASURES OR RESTORATION TIME not met.

B.1 Initiate a CR AND B.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.

In accordance with Corrective Action Program In accordance with Radioactive Effluent Release Report

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.1 - 2 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.1.1 The dose rate due to tritium and all radionuclides in particulate form with half-lives 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 13.2.1-1 In accordance with Table 13.2.1-1

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.1 - 3 Table 13.2.1-1 (Page 1 of 2)

Radioactive Gaseous Waste Sampling and Analysis GASEOUS RELEASE TYPE TYPE OF ACTIVITY ANALYSIS SAMPLE TYPE SAMPLE FREQUENCY MINIMUM ANALYSIS FREQUENCY LOWER LIMIT OF DETECTION (LLD) (a)

1. Auxiliary Building Vent

a.

Principal Gamma Emitters (b)

Particulate Sample Continuous (c) 31 days (SAFSTOR) 7 days (Major Decommissioning Activities*)

1 x 10-11 µCi/ml

b.

Gross Alpha Particulate Sample Continuous (c) 31 days (SAFSTOR) 7 days (Major Decommissioning Activities*)

1 x 10-11 Ci/ml

c.

H-3 Grab Sample 31 days 31 days 1 x 10-6 Ci/ml

d.

Sr-90 Composite Particulate Sample Continuous (c) 184 days (d) 1 x 10-11 Ci/ml

Reference 10 CFR 50.2

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.1 - 4 Table 13.2.1-1 (Page 2 of 2)

Radioactive Gaseous Waste Sampling and Analysis (a) The LLD is defined, for purposes of these DNCs, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a real signal.

For a particular measurement system, which may include radiochemical separation:

x exp Where:

LLD is the a priori lower limit of detection as defined above, as Ci per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

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

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

(b) The principal gamma emitters for which the LLD requirement applies exclusively are the following radionuclides: Mn-54, Co-60, Cs-134, Cs-137, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Section 15.2.

(c) The ratio of the sample flow rate to the sampled flow stream flow rate shall be known (based on sampler and ventilation system flow measuring devices or periodic flow estimates) for the time period covered by each dose or dose rate calculation made in accordance with ODCM DNC 13.2.1 and 13.2.3.

(d) At a minimum, analyze semi-annually.

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.1 - 5 BASES This DNC is provided to ensure that the dose rates at any time to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY are less than or equal to 1500 mrem/yr to any organ. This dose rate limit provides additional assurance that radioactive material discharged in gaseous effluents will be maintained ALARA, and ensure that the exposures of MEMBERS OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, will not exceed the annual average concentrations specified in Appendix B, Table 2, Column 1 of 10 CFR 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),

Currie, L.A., Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry, Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.2 - 1 13.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.2 Gaseous Effluent Dose - Noble Gas Content deleted. No longer applicable.

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.3 - 1 13.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.3 Gaseous Effluent Dose - Tritium and Particulate DNC 13.2.3 The dose to a MEMBER OF THE PUBLIC from tritium, and all radionuclides in particulate form with half-lives 8 days, in gaseous effluents, released to areas at or beyond the SITE BOUNDARY (Plant Drawing A-408) shall be limited to the following:

a.

7.5 mrem to any organ during any calendar quarter, and

b.

15 mrem to any organ during any calendar year.

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

The calculated dose from the release of tritium, and radionuclides in particulate form with half-lives 8 days released in gaseous effluents at or beyond the SITE BOUNDARY exceeds limits.

A.1 Prepare and submit to the NRC, pursuant to Section 15.3, a Special Report that (1) Identifies the cause(s) for exceeding the limit(s) and; (2) Defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DNC 13.2.3.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.3 - 2 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B.

Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in gaseous effluents exceeds 2 times the limits.

B.1 Calculate the annual dose to a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the facility (including outside storage tanks, etc.).

AND B.2 Verify that the limits of DNC 13.4.1 have not been exceeded.

Immediately Immediately C.

CONTINGENCY MEASURE B.2 and Associated RESTORATION TIME not met.

C.1 Prepare and submit to the NRC, pursuant to Section 15.3, a Special Report, as defined in 10 CFR 20.2203 (a)(4), of CONTINGENCY MEASURE A.1 shall also include the following:

(1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DNC 13.4.1 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.3 - 3 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.3.1 Determine cumulative dose contributions for the current calendar quarter and current calendar year for tritium, and radionuclides in particulate form with half-lives 8 days in accordance with the methodology and parameters in the ODCM.

31 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.3 - 4 BASES This DNC is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The DNCs are the guides set forth in Section II.C of Appendix I.

The contingency measures provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable.

The ODCM calculational methods specified in the DVRs implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate limitations for tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto broad leaf 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.

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.4 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.4 - 1 13.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.4 GASEOUS RADWASTE TREATMENT SYSTEM DNC 13.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (Plant Drawing A-408) would be:

a.

> 0.3 mrem to any organ in 31 day period.

APPLICABILITY:

At all times, except for the parts of the system taken permanently out of service.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Radioactive gaseous waste is being discharged without treatment.

AND Projected doses due to the gaseous effluent, from the facility, at and beyond the SITE BOUNDARY would exceed limits.

A.1 Prepare and submit to the NRC, pursuant to Section 15.3, a Special Report that includes the following:

(1) Explanation of why gaseous radwaste was being discharged without treatment, (2) Identification of any non-functional /

inoperable equipment or subsystems and the reason for the non-functional /

inoperability, (3) ACTION(s) taken to restore the non-functional

/ inoperable equipment to FUNCTIONAL /

OPERABLE status, and (4) Summary description of ACTION(s) taken to prevent a recurrence.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.4 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.4 - 2 VERIFICATION REQUIREMENTS VERIFICATIONS FREQUENCY DVR 13.2.4.1 Project the doses due to gaseous effluents from each facility at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

31 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.4 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.4 - 3 BASES The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable.

This DNC implements the requirements of 10 CFR 50.36a, July 1967 AEC General Design Criteria 70 and the design objectives given in section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Kewaunee Solutions Kewaunee Power Station ODCM 13.2.5 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.2.5 - 1 13.2 GASEOUS EFFLUENTS 13.2.5 Gas Storage Tanks Content deleted. No longer applicable.

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.1 - 1 13.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DNC 13.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 13.3.1-1 shall be FUNCTIONAL with:

a. The minimum FUNCTIONAL channel(s) in service.

b.

The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1 are not exceeded.

APPLICABILITY:

During release via the monitored pathway.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required.

A.1 Suspend the release of radioactive liquid effluents monitored by the affected channel.

OR A.2 Declare the channel non-functional.

OR A.3 Change the setpoint so it is acceptably conservative.

Immediately Immediately Immediately

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.1 - 2 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B.

Liquid Radwaste Effluent Line (R-18) non-functional prior to or during effluent releases.

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

Prior to initiating an effluent release, complete sections B.1.1 and B.1.2.

B.1.1 Analyze at least 2 independent samples in accordance with Table 13.1.1-1.

AND B.1.2 -----------NOTE----------------

Verification ACTION will be performed by at least 2 separate technically qualified members of the facility staff.

Independently verify the release rate calculations and discharge line valving.

OR B.2 Suspend release of radioactive effluents via this pathway.

Prior to initiating a release Prior to initiating a release Immediately

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.1 - 3 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. CONTINGENCY MEASURES OR RESTORATION TIME of A or B not met.

C.1 Initiate a CR AND C.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.

In accordance with Corrective Action Program In accordance with Radioactive Effluent Release Report

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.1 - 4 VERIFICATION REQUIREMENTS

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

Refer to Table 13.3.1-1 to determine which DVRs apply for each function.

VERIFICATION FREQUENCY DVR 13.3.1.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DVR 13.3.1.2 Perform SOURCE CHECK.

Prior to release DVR 13.3.1.3 Perform CHANNEL FUNCTIONAL TEST 92 days DVR 13.3.1.4 Perform CHANNEL CALIBRATION.

18 months

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.1 - 5 Table 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CHANNELS PER INSTRUMENT VERIFICATION REQUIREMENTS

1.

Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (R-18) 1 DVR 13.3.1.1 DVR 13.3.1.2 DVR 13.3.1.3 DVR 13.3.1.4

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.1 - 6 BASES The radioactive liquid effluent instrumentation, required FUNCTIONAL by this DNC, is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluent. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten (10) times the values 10 CFR Part 20, Appendix B, Table 2, Column 2. The FUNCTIONALITY and use of this instrumentation is consistent with the appropriate requirements of July 1967 AEC General Design Criteria 17, 18, and 70.

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.2 - 1 13.3 INSTRUMENTATION 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DNC 13.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 13.3.2-1 shall be FUNCTIONAL with:

a. The minimum FUNCTIONAL channel(s) in service.

APPLICABILITY:

During release via the monitored pathway.

ACTIONS

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

Separate NON-CONFORMANCE entry is allowed for each channel.

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Less than the minimum number of channels FUNCTIONAL.

A.1 Restore non-functional channel(s) to FUNCTIONAL status.

30 days.

B.

Sampler Flow rate Measuring Devices (for the Auxiliary Building Ventilation Sampler) non-functional prior to or during releases B.1 Estimate the flow rate for the non-functional channel(s).

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter C.

Particulate Samplers (for the Auxiliary Building Ventilation system) non-functional prior to or during releases C.1 Continuously collect samples using auxiliary sampling equipment as required in Table 13.2.1-1.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D. CONTINGENCY MEASURES OR RESTORATION TIME A, B, or C not met.

D.1 Initiate a CR AND D.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.

In accordance with Corrective Action Program In accordance with Radioactive Effluent Release Report

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.2 - 2 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.3.2.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DVR 13.3.2.2 Perform CHANNEL CHECK.

31 days DVR 13.3.2.3 Perform CHANNEL FUNCTIONAL TEST.

92 days DVR 13.3.2.4 Perform CHANNEL CALIBRATION.

18 months

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.2 - 3 Table 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT REQUIRED CHANNELS PER INSTRUMENT NON-CONFORMANCE VERIFICATION REQUIREMENTS

1. Auxiliary Building Vent

a. Particulate Sampler (R-13 or R-14)

b. Sample Flow-Rate Monitor (R-13 or R-14) 1 1

C B

DVR 13.3.2.2 DVR 13.3.2.1 DVR 13.3.2.3 DVR 13.3.2.4

Kewaunee Solutions Kewaunee Power Station ODCM 13.3.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.3.2 - 4 BASES The radioactive gaseous effluent instrumentation, required FUNCTIONAL by this DNC, is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of July 1967 AEC General Design Criteria 17, 18, and 70.

Kewaunee Solutions Kewaunee Power Station ODCM 13.4.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.4.1 - 1 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 13.4.1 Radioactive Effluents Total Dose DNC 13.4.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to 75 mrem.

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Estimated dose or dose commitment due to direct radiation and the release of radioactive materials in liquid or gaseous effluents exceeds the limits.

A.1 Verify the condition resulting in doses exceeding these limits has been corrected.

Immediately B.

CONTINGENCY MEASURES A.1 and RESTORATION TIME not met.

B.1 --------------NOTE-------------

This is the Special Report required by DNC 13.1.2, or 13.2.3 supplemented with the following.

Submit a Special Report, pursuant to Section 15.3, including a request for a variance in accordance with the provisions of 40 CFR 190. This submission is considered a timely request, and a variance is granted until staff ACTION on the request is complete.

30 days

Kewaunee Solutions Kewaunee Power Station ODCM 13.4.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.4.1 - 2 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with VERIFICATION REQUIREMENTS 13.1.2.1, and 13.2.3.1 in accordance with the methodology and parameters in the ODCM.

12 months DVR 13.4.1.2 Cumulative dose contributions from direct radiation from the facility shall be determined in accordance with the methodology and parameters in the ODCM.

This requirement is applicable only under conditions set forth in ODCM DNC 13.4.1.A.

12 months

Kewaunee Solutions Kewaunee Power Station ODCM 13.4.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.4.1 - 3 BASES This normal condition is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The DNC requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the facility remains within twice the dose design objectives of Appendix I, and if direct radiation doses from the facility are kept small.

The Special Report will describe a course of ACTION that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff ACTION is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM Normal Condition 13.3.1 and 13.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Kewaunee Solutions Kewaunee Power Station ODCM 13.5.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.5.1 - 1 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.1 Monitoring Program This Kewaunee Program is established by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and implemented by approved station procedures. This program is required by Technical Requirements Manual 10.1.1 and ODCM.

The radiological environmental monitoring program required by this DNC provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant decommissioning activities. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

Kewaunee Solutions Kewaunee Power Station ODCM 13.5.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.5.2 - 1 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.2 Land Use Census Program This Kewaunee Land Use Census Program is implemented by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and Land Use Census Program procedure.

BASES This DNC is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via broad leaf vegetation will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of broad leaf vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a broad leaf vegetation yield of 2 kg/m2.

Kewaunee Solutions Kewaunee Power Station ODCM 13.5.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 13.5.3 - 1 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.3 Interlaboratory Comparison Program This Kewaunee Interlaboratory Comparison Program is implemented by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and approved station procedures.

BASES The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring (developed using the guidance in Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April 1975) in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

Kewaunee Solutions Kewaunee Power Station ODCM 14.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 14.1 - 1 14.0 DESIGN FEATURES 14.1 GASEOUS AND LIQUID EFFLUENT RELEASE POINTS 14.1.1 Figure 14.1-1 presents the locations of radioactive effluent release points at the plant. The Figure does not depict changes made at the facility since permanent plant shutdown, however no changes have been made to radioactive effluent release points depicted on the Figure.

14.1.2 Plant drawing A-408, Radiological Survey Site Map depicts the site area by illustrating the SITE BOUNDARY.

Kewaunee Solutions Kewaunee Power Station ODCM 14.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 14.1 - 2 FIGURE 14.1-1

-$.T.H.<f,l N

KEWAUNEE COUNTY

~

CARI.TOIi IRIILS PARK LAKE MICHIGAN I

---z -----,=-----

1 CARL TOll IRA.I.$ PAR!

LEGEND A

CONTAINMENT BUILDING VENT ELEVA TION 775' B = AUXILARY BUILDING VENT ELEVATION 597' C = EFFLUENT LIQUID DISCHARGE ELEV A TION 580'

~I

Kewaunee Solutions Kewaunee Power Station ODCM 15.1 Offsite Dose Calculation Manual (ODCM)

Revision 20 15.1 - 1 15.0 ADMINISTRATIVE CONTROLS 15.1 Major Changes to Radioactive Waste Systems(1)

Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Project Operations Review Committee (PORC). The discussion of each change shall contain:

a.

A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59,

b.

Sufficient information to totally support the reason for the change without benefit of additional or supplemental information,

c.

A description of the equipment, components and processes involved and the interfaces with other plant systems, d

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

e.

An evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto,

f.

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

g.

An estimate of the exposure to plant operating personnel as a result of the change, and

h.

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

Changes shall become effective upon review and acceptance by the PORC.

(1) Licensees may choose to submit the information called for in this requirement as part of the periodic DSAR update.

Kewaunee Solutions Kewaunee Power Station ODCM 15.2 Offsite Dose Calculation Manual (ODCM)

Revision 20 15.2 - 1 15.0 ADMINISTRATIVE CONTROLS 15.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include:

a.

A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility following the format of Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974.

b.

An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the facility during the previous calendar year.

c.

An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from facility releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

d.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the ODCM and the PCP, and in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

e.

A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

f.

Any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to DNC 13.5.2.

Kewaunee Solutions Kewaunee Power Station ODCM 15.3 Offsite Dose Calculation Manual (ODCM)

Revision 20 15.3 - 1 15.0 ADMINISTRATIVE CONTROLS 15.3 Special Reports Special reports may be required covering inspections, tests, and maintenance activities. These special reports are determined on an individual basis. Their preparation and submittal are designated in the ODCM Contingency Measures for each Normal Condition.

Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix D, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington D.C. 20555 within the time period specified for each report.

These Special Report(s) are in lieu of a Licensee Event Report

Kewaunee Solutions Kewaunee Power Station Offsite Dose Calculation Manual PART II - CALCULATIONAL METHODOLOGIES

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 1 1.0 LIQUID EFFLUENTS METHODOLOGY 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls installed at Kewaunee for controlling and monitoring normal radioactive material releases in accordance with July 1967 AEC General Design Criteria 17 and 70, are summarized as follows:

1) Alarm (and Automatic Termination) - R-18 provides this function on the liquid radwaste effluent line.

2) Liquid Tank Controls - All radioactive liquid tanks are located inside the Auxiliary Building and contain the suitable confinement systems and drains to prevent direct, unmonitored release to the environment. A liquid radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 1.

1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of Technical Requirements Manual 10.1.2 and ODCM Normal Condition 13.3.1, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of ODCM Normal Condition 13.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREA shall be limited to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides. The following equation(1) must be satisfied to meet the liquid effluent restrictions:

f

)

f F

(

C 10 c

(1.1)

(1) Adapted from NUREG-0133 to include the application of 10 times the Effluent Concentration (EC) of 10 CFR 20, Appendix B, Table 2, Column 2.

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 2 where:

10xC = ten times the effluent concentration limit of 10 CFR 20, Appendix B, Table 2, Column 2, in µCi/ml.

c =

the setpoint, in µCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of ODCM Normal Condition 13.1.1.

f =

the flow rate at the radiation monitor location in volume per unit time, but in the same units as F, below.

F =

the dilution water flow rate as measured prior to the release point, in volume per unit time.

[Note that if no dilution is provided, c C. Also, note that when (F) is large compared to (f), then (F + f) F.]

1.2.1 Liquid Effluent Monitors (Radwaste)

The setpoints for the liquid effluent monitors at the Kewaunee Power Station are determined by the following equations:

SP

bkg (1.2) where:

SP

=

alarm setpoint corresponding to the maximum allowable release rate (cpm)

Ci

=

the concentration of radionuclide i in the liquid effluent

(µCi/ml), to include gamma emitters only 10xECi

=

ten times the EC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table 2, Column 2 (µCi/ml)

SENi

=

the sensitivity value to which the monitor is calibrated for radionuclide i (cpm per µCi/ml). The default calibration value from Table 1.1 may be used for gamma emitting radionuclides in lieu of nuclide specific values.

DW

=

the dilution water flow rate at the time of release (gal/min).

RR

=

the liquid effluent release rate (gal/min).

bkg

=

the background of the monitor (cpm).

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 3 The radioactivity monitor setpoint equation (1.2) remains valid during periods when the dilution water is at its lowest or zero. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.

At its lowest value, (DW + RR) equals RR and equation (1.2) reverts to the following equation:

bkg

)

EC (10 C

)

SEN (C

SP i

i i

i

(1.3) 1.2.2 Conservative Default Values Non-gamma emitting radionuclides (H-3, Fe-55, Ni-63, Sr-90) are not detected by the effluent monitor and, therefore, are not directly included in the above setpoint equation. These non-gamma radionuclides can, however, contribute a sizable fraction of the total EC limit. The method specified below for establishing default setpoints provides conservatism to account for these non-gamma emitters and ensures that the setpoint meets the requirements of ODCM Normal Condition 13.3.1 including all radionuclides.

Conservative alarm setpoints can be determined through the use of generic default parameters based on the following:

a) substitution of a default effective EC (ECe) value where:

)

(EC C

C EC i

i i

e (1.4) b)

substitution of the lowest operational dilution water flow, in gal/min and, c) substitution of the highest effluent release rate, in gal/min, d) substitution of a default monitor sensitivity.

The default setpoint equation is provided below:

SP ECe SEN DW RR RR bkg (1.5)

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 4 1.3 Liquid Effluent Concentration Limits - 10 CFR 20 ODCM Normal Condition 13.1.1 limits the concentration of radioactive material in liquid effluents (after dilution) to less than ten times the concentrations as specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases.

Release rates are controlled and radiation monitor alarm setpoints are established to ensure that these concentration limits are not exceeded. In the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of ODCM Normal Condition 13.1.1 may be performed using the following equation:

where:

C EC RR RR DW (1.6)

Ci

= concentration of radionuclide i in the undiluted liquid effluent (µCi/ml) 10xECi

= ten times the EC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table 2, Column 2 (µCi/ml)

RR

= the liquid effluent release rate (gal/min)

DW

= the dilution water flow rate at the time of the release (gal/min) 1.4 Liquid Effluent Dose Calculation - 10 CFR 50 ODCM Normal Condition 13.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from the Kewaunee Power Station to:

during any calendar quarter; 1.5 mrem to total body 5.0 mrem to any organ during any calendar year; 3.0 mrem to total body 10.0 mrem to any organ

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 5 Per Verification Requirement 13.1.2.1, the following calculational methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Kewaunee.

D C A (1.7) where:

Do

=

dose or dose commitment to organ o, including total body (mrem)

Aio

= site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per µCi/ml) (Table 1.2)

Ci

= average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (µCi/ml)

VOL

= volume of liquid effluent released (gal)

RR

= the liquid effluent release rate (gal/min)

DW

= average dilution water discharge rate during release period (gal/min) 1.67E-02

= conversion factor (hr/min)

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 6 The site-related ingestion doses/dose commitment factors (Aio) are presented in Table 1.2 and have been derived in accordance with guidance of NUREG-0133 by the equation:

i i

F w

w io

)]DF BF (U

)

D 05[(U 1.14E A

(1.8) where:

Aio

= composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish ingestion and water consumption pathways (mrem/hr per µCi/ml) 1.14E+05 = conversion factor (pCi/µCi x ml/kg ÷hr/yr)

Uw

= adult water consumption (730 kg/yr)

Dw

= dilution factor from the near field area within 1/4 mile of the release point to the nearest potable water intake for the adult water consumption (84(2), unitless)

UF

= adult fish consumption (21 kg/yr)

BFi

= bioaccumulation factor for radionuclide i in fish from Table 1.3 (pCi/kg per pCi/1)

DFi

= dose conversion factor for radionuclide i for adults in pre-selected organ o, from Table E-11 of Regulatory Guide 1.109, 1977 and NUREG 0172, 1977 (mrem/pCi)

The radionuclides included in the periodic dose assessment per the requirements of ODCM Normal Condition 13.1.2 and Verification Requirement 13.1.2.1 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per Verification Requirement 13.1.1.1, Table 13.1.1-1.

Radionuclides requiring radiochemical analysis (e.g., Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Table 13.1.1-1.

(2) Adapted from the Kewaunee Final Environmental Statement,Section V.

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 7 1.5 Liquid Effluent Dose Projections ODCM Normal Condition 13.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the 31 day projected doses exceed:

0.06 mrem to the total body, or 0.2 mrem to any organ.

The applicable liquid waste streams and processing systems are as delineated in Figure 1.

Dose projections are made at least once per 31 days by the following equations:

d)

(31 D

D tb tbp

(1.9) d)

÷ (31 D

=

D max maxp (1.10) where:

Dtbp

= the total body dose projection for current 31 day period (mrem)

Dtb

= the total body dose to date for current 31 day period as determined by equation (1.7) (mrem)

Dmaxp

= the maximum organ dose projection for current 31 day period (mrem)

Dmax

= the maximum organ dose to date for current 31 day period as determined by equation (1.7) (mrem) d

= the number of days to date for current 31 day period 31

= the number of days in a 31 day period

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 8 Aux ili ar-y Buil dl ng I

Sludge 1 ___

Equipment an~ T Int er-c ept T cmk Floo r-Or a Tns Con t ainment Sump Was t e t--- 1Hold -Up Tank Laundry ~n d ____.,., I Laundr y 1-------8Fflte..

1, ------I Wast e Condensa t e Sho wer Dr a ins Tank s Ta nks Hot LEGEND:

<=> Sarnp le/Mon1to r l><l Isolati on Dev ic

<Damper-o r Val v e)

.Auto I so lat ion

' ' ~

I Fl ow Tot alizer Flo,w I ndic at or Rad iati on tv1onit o, L ___j/ Au t o I solat ion ODCM FIGURE 1 Auxilliar y Buildin St an dplpe LIQUID RAD IOACTIVE EFFLUENT FL OW DIAGRAM

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 9 Table 1.1 Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Units Comments ECe calculated

µCi/ml Calculate as needed Ci measured

µCi/ml Taken from gamma spectral analysis of liquid effluent ECi as determined

µCi/ml Taken from 10 CFR 20, Appendix B, Table 2, Col. 2 Sensitivity (SEN)

R-18 1.0E+08 cpm per

µCi/ml Radwaste effluent (value based on Cs-137)

Refer to Plant Drawing E-2021 Release Rate (RR)

R-18 as determined gpm Determined prior to release; release rate can be adjusted for ODCM limit compliance

Background

(bkg)

R-18 3as determined cpm Determined prior to release Setpoint (SP)

R-18*

calculated cpm Default alarm setpoints at conservative values may be used as deemed appropriate and desirable for assuring regulatory compliance and for maintaining releases ALARA.

The alarm setpoint for R-18 cannot exceed the linear calibration range of the radiation monitor in accordance with CAP 37265 and DCR 26981 (5.00E+05+bkg cpm).

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 10 Table 1.2 (Page 1 of 2)

Site Related Ingestion Dose Commitment Factors (mrem/hr per µCi/ml)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 P-32 1.39E+6 8.62E+4 5.36E+4 1.56E+5 Cr-51 1.28E+0 7.63E-1 2.81E-1 1.69E+0 3.21E+2 Mn-54 4.38E+3 8.36E+2 1.30E+3 1.34E+4 Mn-56 1.10E+2 1.96E+1 1.40E+2 3.52E+3 Fe-55 6.61E+2 4.57E+2 1.06E+2 2.55E+2 2.62E+2 Fe-59 1.04E+3 2.45E+3 9.40E+2 6.85E+2 8.17E+3 Co-57 2.11E+1 3.51E+1 5.36E+2 Co-58 8.99E+1 2.02E+2 1.82E+3 Co-60 2.58E+2 5.70E+2 4.85E+3 Ni-63 3.13E+4 2.17E+3 1.05E+3 4.52E+2 Ni-65 1.27E+2 1.65E+1 7.52E+0 4.18E+2 Cu-64 1.01E+1 4.72E+0 2.53E+1 8.57E+2 Zn-65 2.32E+4 7.38E+4 3.33E+4 4.93E+4 4.65E+4 Zn-69 4.93E+1 9.43E+1 6.56E+0 6.13E+1 1.42E+1 Br-82 2.27E+3 2.61E+3 Br-83 4.05E+1 5.83E+1 Br-84 5.24E+1 4.12E-4 Br-85 2.15E+0 Rb-86 1.01E+5 4.71E+4 1.99E+4 Rb-88 2.90E+2 1.54E+2 4.00E-9 Rb-89 1.92E+2 1.35E+2 Sr-89 2.24E+4 6.44E+2 3.60E+3 Sr-90 5.52E+5 1.35E+5 1.59E+4 Sr-91 4.13E+2 1.67E+1 1.97E+3 Sr-92 1.57E+2 6.77E+0 3.10E+3 Y-90 5.85E-1 1.57E-2 6.21E+3 Y-91m 5.53E-3 2.14E-4 1.62E-2 Y-91 8.58E+0 2.29E-1 4.72E+3 Y-92 5.14E-2 1.50E-3 9.00E+2 Y-93 1.63E-1 4.50E-3 5.17E+3 Zr-95 2.70E-1 8.67E-2 5.87E-2 1.36E-1 2.75E+2 Zr-97 1.49E-2 3.01E-3 1.38E-3 4.55E-3 9.34E+2 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 Nb-97 3.75E+0 9.48E-1 3.46E-1 1.11E+0 3.50E+3 Mo-99 1.07E+2 2.04E+1 2.43E+2 2.49E+2 Tc-99m 9.11E-3 2.58E-2 3.28E-1 3.91E-1 1.26E-2 1.52E+1 Tc-101 9.37E-3 1.35E-2 1.32E-1 2.43E-1 6.90E-3 Ru-103 4.61E+0 1.99E+0 1.76E+1 5.39E+2 Ru-105 3.84E-1 1.52E-1 4.96E+0 2.35E+2 Ru-106 6.86E+1 8.68E+0 1.32E+2 4.44E+3 Rh-103m Rh-106

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 11 Table 1.2 (Page 2 of 2)

Site Related Ingestion Dose Commitment Factors (mrem/hr per µCi/ml)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Ag-110m 1.04E+0 9.62E-1 5.71E-1 1.89E+0 3.92E+2 Sb-124 9.48E+0 1.79E-1 3.76E+0 2.30E-2 7.38E+0 2.69E+2 Sb-125 6.06E+0 6.77E-2 1.44E+0 6.16E-3 4.67E+0 6.67E+1 Te-125m 2.57E+3 9.31E+2 3.44E+2 7.73E+2 1.04E+4 1.03E+4 Te-127m 6.49E+3 2.32E+3 7.91E+2 1.66E+3 2.64E+4 2.18E+4 Te-127 1.05E+2 3.79E+1 2.28E+1 7.81E+1 4.29E+2 8.32E+3 Te-129m 1.10E+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 5.55E+4 Te-129 3.01E+1 1.13E+1 7.33E+0 2.31E+1 1.27E+2 2.27E+1 Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+4 Te-131 1.89E+1 7.89E+0 5.96E+0 1.55E+1 8.27E+1 2.67E+0 Te-132 2.42E+3 1.56E+3 1.47E+3 1.73E+3 1.50E+4 7.39E+4 I-130 2.79E+1 8.23E+1 3.25E+1 6.97E+3 1.28E+2 7.08E+1 I-131 1.54E+2 2.20E+2 1.26E+2 7.20E+4 3.76E+2 5.79E+1 I-132 7.49E+0 2.00E+1 7.01E+0 7.01E+2 3.19E+1 3.76E+0 I-133 5.24E+1 9.11E+1 2.78E+1 1.34E+4 1.59E+2 8.19E+1 I-134 3.91E+0 1.06E+1 3.80E+0 1.84E+2 1.69E+1 9.26E-3 I-135 1.63E+1 4.28E+1 1.58E+1 2.82E+3 6.86E+1 4.83E+1 Cs-134 2.98E+5 7.09E+5 5.79E+5 2.29E+5 7.61E+4 1.24E+4 Cs-136 3.12E+4 1.23E+5 8.86E+4 6.85E+4 9.39E+3 1.40E+4 Cs-137 3.82E+5 5.22E+5 3.42E+5 1.77E+5 5.89E+4 1.01E+4 Cs-138 2.64E+2 5.22E+2 2.59E+2 3.84E+2 3.79E+1 2.23E-3 Ba-139 1.02E+0 7.30E-4 3.00E-2 6.83E-4 4.14E-4 1.82E+0 Ba-140 2.15E+2 2.69E-1 1.41E+1 9.16E-2 1.54E-1 4.42E+2 Ba-141 4.98E-1 3.76E-4 1.68E-2 3.50E-4 2.13E-4 Ba-142 2.25E-1 2.31E-4 1.42E-2 1.95E-4 1.31E-4 La-140 1.52E-1 7.67E-2 2.03E-2 5.63E+3 La-142 7.79E-3 3.54E-3 8.82E-4 2.59E+1 Ce-141 3.17E-2 2.14E-2 2.43E-3 9.95E-3 8.19E+1 Ce-143 5.58E-3 4.13E+0 4.57E-4 1.82E-3 1.54E+2 Ce-144 1.65E+0 6.90E-1 8.87E-2 4.10E-1 5.58E+2 Pr-143 5.60E-1 2.25E-1 2.77E-2 1.30E-1 2.45E+3 Pr-144 1.83E-3 7.61E-4 9.31E-5 4.29E-4 Nd-147 3.83E-1 4.42E-1 2.65E-2 2.59E-1 2.12E+3 W-187 2.96E+2 2.47E+2 8.65E+1 8.10E+4 Np-239 2.97E-2 2.92E-3 1.61E-3 9.10E-3 5.98E+2

Kewaunee Solutions Kewaunee Power Station ODCM 1.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 1.0 - 12 Table 1.3 Bioaccumulation Factors (BFi)

(pCi/kg per pCi/liter)*

Element Freshwater Fish H

9.0E-01 C

4.6E+03 Na 1.0E+02 P

3.0E+03 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+01 Y

2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 Ag 2.3E+00 Sb 1.0E+00 Te 4.0E+02 I

1.5E+01 Cs 2.0E+03 Ba 4.0E+00 La 2.5E+01 Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 W

1.2E+03 Np 1.0E+01

Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which is adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564, Rev. 1, October 1972.

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 1 2.0 Gaseous Effluents Methodology 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Kewaunee for controlling and monitoring normal radioactive material releases in accordance with July 1967 AEC General Design Criteria 17 and 70, are summarized as follows:

2.1.2 Auxiliary Building Vent The Auxiliary Building vent receives discharges from the Auxiliary Building radwaste processing area ventilation and Auxiliary Building general area. All effluents pass through the R-13 and/or R-14 channels which contain a particulate sampler.

Effluent flow rates are determined by installed flow measurement equipment, if available, or fan operation (fan configuration). Sampler flow rates are determined by flow rate instrumentation.

2.1.2 Non-routine Discharge Locations Periodically, non-routine breaches are made in the Auxiliary and Containment buildings that might allow the release of the atmosphere, which contains some levels of radioactivity. These breaches include, but are not limited to, opening the Containment equipment hatch, holes cut in walls or ceilings to allow for moving equipment in or out of the Radiologically Controlled Areas (RCAs). All efforts to maintain these areas at negative pressure will be made. IF negative pressure cannot be maintained (i.e., more exhaust than supply fan volume),

THEN supply ventilation to the area must be secured. If the auxiliary building ventilation is out of service (e.g., loss of power or fan failure), a conservative release rate of 5125 cfm may be used (KPS Modification No. KW-16-02022, SAFSTOR III Ventilation). Criteria for determining if and when a release occurs from these areas is provided in implementing procedures. As possible, the effects of these possible releases shall be evaluated beforehand. Any actual releases shall be documented and included in the monthly, quarterly and annual reports as appropriate.

A gaseous radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 2.

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 2 2.2 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 2.2.1 SITE BOUNDARY Dose Rate - Tritium and Particulates ODCM Normal Condition 13.2.1.a limits the dose rate to 1500 mrem/yr to any organ for tritium and particulates with half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period for continuous releases per Table 13.2.1-1. The following equation may be used for the dose rate evaluation:

Do Q

Ri Qi D Q Ri Qi (2.1) where:

o D

=

average organ dose rate over the sampling time period (mrem/yr)

/Q

=

atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m³) from Table 2.1 D/Q

=

atmospheric deposition to the controlling SITE BOUNDARY location for the ground plane exposure pathway (1/m2) from Table 2.1 Ri

=

dose factor for radionuclide i, (mrem/yr per Ci/m³) for the TEEN inhalation pathway from Table 2.3 and the ground plane exposure pathway (m2 - mrem/yr per Ci/sec) from Table 2.13 i

Q

=

average release rate over the appropriate sampling period and analysis frequency for radionuclide i, tritium or other radionuclide in particulate form with half-life greater than 8 days (Ci/sec)

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 3 2.3 Gaseous Effluent Dose Calculations - 10 CFR 50 2.3.1 UNRESTRICTED AREA Dose - Tritium and Particulates Per the requirements of ODCM Normal Condition 13.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit ( 7.5 mrem) and calendar year limit ( 15 mrem) to any organ.

The following equation may be used to evaluate the maximum organ dose due to releases of tritium and particulates with half-lives greater than 8 days:

i i

p aop Q

R SF W

08 3.17E D

(2.2) where:

Daop

=

dose or dose commitment for age group a to organ o, including the total body, via pathway p from tritium and radionuclides in particulate form with half-life greater than eight days (mrem)

W

=

atmospheric dispersion or deposition parameter to the controlling location(s) as identified in Table 2.1

/Q

=

atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m³)

D/Q

=

atmospheric deposition for ground plane, vegetation, and milk exposure pathways (1/m²)

Ri

=

dose factor for radionuclide i, (mrem/yr per Ci/m³) or (m² - mrem/yr per Ci/sec) from Table 2.2 through 2.13 for each age group a and the applicable pathway p as identified in Table 2.1. Values for Ri were derived in accordance with the methods described in NUREG-0133. For additional ODCM DCFs that may be used in active DECON, refer to Table D-1 through D-3 in Calculation RA-0065, Rev 0.

Qi

=

cumulative release over the period of interest for radionuclide i -

radioactive material in particulate form with half-life greater than 8 days (Ci).

SFp

=

seasonal correction factor to account for the fraction of the period that the applicable exposure pathway does exist.

1)

For milk and vegetation exposure pathways:

of months in the period that grazing occurs total of months in period

=

0.5 for annual calculations

2)

For inhalation and ground plane exposure pathways: = 1.0 The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Kewaunee as identified by the annual land-use census. Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2.1.

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 4 2.4 Gaseous Effluent Dose Projection ODCM Normal Condition 13.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses exceed one-half the annual design objective rate in any 31 days, i.e., exceeding:

0.3 mrem, maximum organ.

The applicable gaseous release sources and processing systems are as delineated in Figure 2.

Dose projections are performed at least once per 31 days by the following equations:

(

)

d

÷ 31 x

D

=

D max maxp (2.3) where:

Dmaxp

= maximum organ dose projection for current 31 day period (mrem)

Dmax

= maximum organ dose to date for current 31 day period as determined by equation (2.2) (mrem) d

= number of days to date in current 31 day period 31

= number of days in a 31 day period

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 5 2.5 Environmental Radiation Protection Standards 40 CFR 190 For the purpose of implementing ODCM Normal Condition 13.4.1 on the EPA environmental radiation protection standard and Technical Requirements Manual 10.3.2 on reporting requirements, dose calculations may be performed using the above equations with the substitution of average or actual meteorological parameters for the period of interest and actual applicable pathways as needed. Any exposure attributable to on-site sources will be evaluated based on the results of the environmental monitoring program (TLD measurements) or by calculational methods. NUREG-0543 describes acceptable methods for demonstrating compliance with 40 CFR Part 190 when radioactive effluents exceed the Appendix I portion of the specifications.

2.6 Total Dose The purpose of this section is to describe the method used to calculate the cumulative dose contributions from liquid and gaseous effluents in accordance with KPS Technical Requirements Manual 10.1.2 for total dose. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40 CFR 190, Environmental Standards for the Uranium Fuel Cycle.

Compliance with the KPS Technical Requirements Manual 10.1.2 dose objectives for the maximum individual demonstrates compliance with the EPA limits to any MEMBER OF THE PUBLIC, since the design dose objectives from 10 CFR 50, Appendix I are much lower than the 40 CFR 190 dose limits to the general public.

With the calculated doses from the releases of radioactive materials in liquid or gaseous effluents exceeding twice the limits outlined in ODCM DNC 13.1.2 and 13.2.3, a special analysis shall be performed. The purpose of this analysis is to demonstrate if the total dose to any MEMBER OF THE PUBLIC (real individual) from all uranium fuel cycle sources (including direct radiation contributions from the facility, from outside storage areas and from all real pathways) is limited to less than or equal to 25 mrem per year to the total body or any organ, except the thyroid, which is limited to 75 mrem per year.

If required, the total dose to a MEMBER OF THE PUBLIC will be calculated for all significant effluent release points for all real pathways including direct radiation.

Effluent releases from Point Beach Nuclear Plant must also be considered due to its proximity. Calculations will be based on the equations in Sections 1.4 and 2.3.1, with the exception that usage factors and other site specific parameters may be modified using more realistic assumptions, where appropriate.

The direct radiation component from the facility can be determined using environmental TLD results. These results will be corrected for natural background and for actual occupancy time of any areas accessible to the general public at the location of maximum direct radiation. It is recognized that by including the results from the environmental TLDs into the sum of total dose component, the direct radiation dose may be overestimated. The TLD measurements may include the exposure from ground plane deposition, and shoreline deposition, which have already been included in the summation of the significant dose pathways to the general public. However, this conservative method can be used, if required, as well as any other method for estimating the direct radiation dose from contained radioactive sources within the facility. The methodology used to incorporate the direct radiation component into total dose estimates will be outlined whenever total doses are reported.

Therefore, the total dose will be determined based on the most realistic site specific data and parameters to assess the real dose to any MEMBER OF THE PUBLIC.

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 6 Isolat io n De v ier!

,,Damper o r Valv e)

[eJ Pr efilte r

[5J HEPA Filt er-Aux ili,c1r y Buildin,*

A uxiliar-y Bu i'lding Vent St ock t

!Sample Sk id l Aux llf ar y Bu lldl Vent tlot l o PI Tt-a ln B ODCI\\~ FIGURE 2 ASEOUS RADIOAC TIVE EFFLUENT FL h lSpen t Fuel Pool Ve nt 11ot lo n PITr-ai n °'

I AGRAM

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 7 Table 2.1 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations ODCM Normal Condition Location Pathways Atmospheric Dispersion

/Q (sec/m3)

D/Q (1/m2) 13.2.1.b Site Boundary (0.81 mile, N)

Inhalation, Ground Plane 2.50E-06 8.7E-09 13.2.3 Garden 4 (0.96 mile SSW)

Inhalation, Vegetation, Milk, and Ground Plane 8.30E-07 3.20E-09 The following tables from TSD 18-017, Dispersion and Deposition Coefficients for KPS SAFSTOR and DECON, are placed here as a reference as needed for additional detailed calculations. Table 2.1 uses the /Q values as listed under Auxiliary Vent SAFSTOR Winter under column No Decay and Undepleted.

Table 18 - Recommended /Q and D/Q Values for Site Boundary Calculations Release Type cfm Sector Distance from Site (miles)

/Q No Decay Undepleted (sec/m3)

/Q 2.260 Day Decay Undepleted (sec/m3)

/Q 8.000 Day Decay Depleted (sec/m3)

D/Q (m-2)

Ground Release 0

NNW 0.81 1.8E-06 1.8E-06 1.6E-06 7.7E-09 Auxiliary Vent Normal Ops 54,000 N

0.81 1.2E-06 1.2E-06 1.0E-06 6.4E-09 Reactor Vent Normal Ops 26,000 N

0.99 7.7E-08 7.7E-08 7.6E-08 2.7E-09 Auxiliary Vent SAFSTOR Summer 36,125 N

0.81 1.8E-06 1.8E-06 1.6E-06 7.9E-09 Auxiliary Vent SAFSTOR Winter 9,000 N

0.81 2.5E-06 2.5E-06 2.2E-06 8.7E-09 Auxiliary Vent Out-Of-Service 5,125 N

0.81 2.6E-06 2.5E-06 2.3E-06 8.7E-09

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 8 Table 69 - Release Point Critical Receptors, Dispersion and Deposition Coefficients Release Type cfm Critical Receptor Sector Distance from Site (miles)

/Q No Decay Undepleted (sec/m3)

/Q 2.260 Day Decay Undepleted (sec/m3)

/Q 8.000 Day Decay Depleted (sec/m3)

D/Q (m-2)

Ground Release 0

Garden 4 SSW 0.96 5.40E-07 5.40E-07 4.70E-07 4.30E-09 Auxiliary Vent Normal Ops 54000 Garden 4 SSW 0.96 3.20E-07 3.20E-07 2.90E-07 2.40E-09 Reactor Vent Normal Ops 26000 Milk 4 SW 1.3 6.50E-08 6.40E-08 6.30E-08 1.30E-09 Auxiliary Vent SAFSTOR Summer 36125 Garden 4 SSW 0.96 5.00E-07 4.90E-07 4.40E-07 2.80E-09 Auxiliary Vent SAFSTOR Winter 9000 Garden 4 SSW 0.96 8.30E-07 8.20E-07 7.30E-07 3.20E-09 Auxiliary Vent Out-Of-Service 5125 Garden 4 SW 1.3 8.90E-07 8.80E-07 7.50E-07 3.20E-09

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 9 Table 2.2 (Page 1 of 2)

Ri Inhalation Pathway Dose Factors - ADULT (mrem/yr per µCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 P-32 1.32E+6 7.71E+4 8.64E+4 5.01E+4 Cr-51 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 3.96E+4 9.84E+3 1.40E+6 7.74E+4 6.30E+3 Mn-56 1.24E+0 1.30E+0 9.44E+3 2.02E+4 1.83E-1 Fe-55 2.46E+4 1.70E+4 7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 1.02E+6 1.88E+5 1.06E+4 Co-57 6.92E+2 3.70E+5 3.14E+4 6.71E+2 Co-58 1.58E+3 9.28E+5 1.06E+5 2.07E+3 Co-60 1.15E+4 5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 1.78E+5 1.34E+4 1.45E+4 Ni-65 1.54E+0 2.10E-1 5.60E+3 1.23E+4 9.12E-2 Cu-64 1.46E+0 4.62E+0 6.78E+3 4.90E+4 6.15E-1 Zn-65 3.24E+4 1.03E+5 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Zn-69 3.38E-2 6.51E-2 4.22E-2 9.20E+2 1.63E+1 4.52E-3 Br-82 1.04E+4 1.35E+4 Br-83 2.32E+2 2.41E+2 Br-84 1.64E-3 3.13E+2 Br-85 1.28E+1 Rb-86 1.35E+5 1.66E+4 5.90E+4 Rb-88 3.87E+2 3.34E-9 1.93E+2 Rb-89 2.56E+2 1.70E+2 Sr-89 3.04E+5 1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6 Sr-91 6.19E+1 3.65E+4 1.91E+5 2.50E+0 Sr-92 6.74E+0 1.65E+4 4.30E+4 2.91E-1 Y-90 2.09E+3 1.70E+5 5.06E+5 5.61E+1 Y-91m 2.61E-1 1.92E+3 1.33E+0 1.02E-2 Y-91 4.62E+5 1.70E+6 3.85E+5 1.24E+4 Y-92 1.03E+1 1.57E+4 7.35E+4 3.02E-1 Y-93 9.44E+1 4.85E+4 4.22E+5 2.61E+0 Zr-95 1.07E+5 3.44E+4 5.42E+4 1.77E+6 1.50E+5 2.33E+4 Zr-97 9.68E+1 1.96E+1 2.97E+1 7.87E+4 5.23E+5 9.04E+0 Nb-95 1.41E+4 7.82E+3 7.74E+3 5.05E+5 1.04E+5 4.21E+3 Nb-97 2.22E-1 5.62E-2 6.54E-2 2.40E+3 2.42E+2 2.05E-2 Mo-99 1.21E+2 2.91E+2 9.12E+4 2.48E+5 2.30E+1 Tc-99m 1.03E-3 2.91E-3 4.42E-2 7.64E+2 4.16E+3 3.70E-2 Tc-101 4.18E-5 6.02E-5 1.08E-3 3.99E+2 5.90E-4

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 10 Table 2.2 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - ADULT (mrem/yr per µCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.53E+3 5.83E+3 5.05E+5 1.10E+5 6.58E+2 Ru-105 7.90E-1 1.02E+0 1.10E+4 4.82E+4 3.11E-1 Ru-106 6.91E+4 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Rh-103m Rh-106 Ag-110m 1.08E+4 1.00E+4 1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 1.74E+6 1.01E+5 1.26E+4 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-127 1.40E+0 6.42E-1 1.06E+0 5.10E+0 6.51E+3 5.74E+4 3.10E-1 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 Te-129 4.98E-2 2.39E-2 3.90E-2 1.87E-1 1.94E+3 1.57E+2 1.24E-2 Te-131m 6.99E+1 4.36E+1 5.50E+1 3.09E+2 1.46E+5 5.56E+5 2.90E+1 Te-131 1.11E-2 5.95E-3 9.36E-3 4.37E-2 1.39E+3 1.84E+1 3.59E-3 Te-132 2.60E+2 2.15E+2 1.90E+2 1.46E+3 2.88E+5 5.10E+5 1.62E+2 I-130 4.58E+3 1.34E+4 1.14E+6 2.09E+4 7.69E+3 5.28E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.28E+3 2.05E+4 I-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 4.06E+2 1.16E+3 I-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 8.88E+3 4.52E+3 I-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 1.01E+0 6.15E+2 I-135 2.68E+3 6.98E+3 4.48E+5 1.11E+4 5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21E+5 2.22E+5 7.52E+4 8.40E+3 4.28E+5 Cs-138 3.31E+2 6.21E+2 4.80E+2 4.86E+1 1.86E-3 3.24E+2 Ba-139 9.36E-1 6.66E-4 6.22E-4 3.76E+3 8.96E+2 2.74E-2 Ba-140 3.90E+4 4.90E+1 1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ba-141 1.00E-1 7.53E-5 7.00E-5 1.94E+3 1.16E-7 3.36E-3 Ba-142 2.63E-2 2.70E-5 2.29E-5 1.19E+3 1.66E-3 La-140 3.44E+2 1.74E+2 1.36E+5 4.58E+5 4.58E+1 La-142 6.83E-1 3.10E-1 6.33E+3 2.11E+3 7.72E-2 Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-143 1.86E+2 1.38E+2 6.08E+1 7.98E+4 2.26E+5 1.53E+1 Ce-144 3.43E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.00E+5 4.64E+2 Pr-144 3.01E-2 1.25E-2 7.05E-3 1.02E+3 2.15E-8 1.53E-3 Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1.73E+5 3.65E+2 W-187 8.48E+0 7.08E+0 2.90E+4 1.55E+5 2.48E+0 Np-239 2.30E+2 2.26E+1 7.00E+1 3.76E+4 1.19E+5 1.24E+1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 11 Table 2.3 (Page 1 of 2)

Ri Inhalation Pathway Dose Factors - TEEN (mrem/yr per µCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 Na-24 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 P-32 1.89E+6 1.10E+5 9.28E+4 7.16E+4 Cr-51 7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 Mn-54 5.11E+4 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Mn-56 1.70E+0 1.79E+0 1.52E+4 5.74E+4 2.52E-1 Fe-55 3.34E+4 2.38E+4 1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 1.53E+6 1.78E+5 1.43E+4 Co-57 6.92E+2 5.86E+5 3.14E+4 9.20E+2 Co-58 2.07E+3 1.34E+6 9.52E+4 2.78E+3 Co-60 1.51E+4 8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 3.07E+5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 9.36E+3 3.67E+4 1.27E-1 Cu-64 2.03E+0 6.41E+0 1.11E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 6.02E-2 1.58E+3 2.85E+2 6.46E-3 Br-82 1.82E+4 Br-83 3.44E+2 Br-84 4.33E+2 Br-85 1.83E+1 Rb-86 1.90E+5 1.77E+4 8.40E+4 Rb-88 5.46E+2 2.92E-5 2.72E+2 Rb-89 3.52E+2 3.38E-7 2.33E+2 Sr-89 4.34E+5 2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 1.65E+7 7.65E+5 6.68E+6 Sr-91 8.80E+1 6.07E+4 2.59E+5 3.51E+0 Sr-92 9.52E+0 2.74E+4 1.19E+5 4.06E-1 Y-90 2.98E+3 2.93E+5 5.59E+5 8.00E+1 Y-91m 3.70E-1 3.20E+3 3.02E+1 1.42E-2 Y-91 6.61E+5 2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-97 1.38E+2 2.72E+1 4.12E+1 1.30E+5 6.30E+5 1.26E+1 Nb-95 1.86E+4 1.03E+4 1.00E+4 7.51E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 1.69E+2 4.11E+2 1.54E+5 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 1.52E-3 6.67E+2 8.72E-7 8.24E-4

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 12 Table 2.3 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - TEEN (mrem/yr per µCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.10E+3 7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-105 1.12E+0 1.41E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m Rh-106 Ag-110m 1.38E+4 1.31E+4 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-127 2.01E+0 9.12E-1 1.42E+0 7.28E+0 1.12E+4 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 Te-129 7.10E-2 3.38E-2 5.18E-2 2.66E-1 3.30E+3 1.62E+3 1.76E-2 Te-131m 9.84E+1 6.01E+1 7.25E+1 4.39E+2 2.38E+5 6.21E+5 4.02E+1 Te-131 1.58E-2 8.32E-3 1.24E-2 6.18E-2 2.34E+3 1.51E+1 5.04E-3 Te-132 3.60E+2 2.90E+2 2.46E+2 1.95E+3 4.49E+5 4.63E+5 2.19E+2 I-130 6.24E+3 1.79E+4 1.49E+6 2.75E+4 9.12E+3 7.17E+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 I-132 1.59E+3 4.38E+3 1.51E+5 6.92E+3 1.27E+3 1.58E+3 I-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 1.03E+4 6.22E+3 I-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 2.04E+1 8.40E+2 I-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 6.95E+3 3.49E+3 Cs-134 5.02E+5 1.13E+6 3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 3.04E+5 1.21E+5 8.48E+3 3.11E+5 Cs-138 4.66E+2 8.56E+2 6.62E+2 7.87E+1 2.70E-1 4.46E+2 Ba-139 1.34E+0 9.44E-4 8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5.47E+4 6.70E+1 2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 1.42E-1 1.06E-4 9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ba-142 3.70E-2 3.70E-5 3.14E-5 1.91E+3 2.27E-3 La-140 4.79E+2 2.36E+2 2.14E+5 4.87E+5 6.26E+1 La-142 9.60E-1 4.25E-1 1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-143 2.66E+2 1.94E+2 8.64E+1 1.30E+5 2.55E+5 2.16E+1 Ce-144 4.89E+6 2.02E+6 1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 1.01E-2 1.75E+3 2.35E-4 2.18E-3 Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+0 4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 1.00E+2 6.49E+4 1.32E+5 1.77E+1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 13 Table 2.4 (Page 1 of 2)

Ri Inhalation Pathway Dose Factors - CHILD (mrem/yr per Ci/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 P-32 2.60E+6 1.14E+5 4.22E+4 9.88E+4 Cr-51 8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 4.29E+4 1.00E+4 1.58E+6 2.29E+4 9.51E+3 Mn-56 1.66E+0 1.67E+0 1.31E+4 1.23E+5 3.12E-1 Fe-55 4.74E+4 2.52E+4 1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4 Co-57 9.03E+2 5.07E+5 1.32E+4 1.07E+3 Co-58 1.77E+3 1.11E+6 3.44E+4 3.16E+3 Co-60 1.31E+4 7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 2.75E+5 6.33E+3 2.80E+4 Ni-65 2.99E+0 2.96E-1 8.18E+3 8.40E+4 1.64E-1 Cu-64 1.99E+0 6.03E+0 9.58E+3 3.67E+4 1.07E+0 Zn-65 4.26E+4 1.13E+5 7.14E+4 9.95E+5 1.63E+4 7.03E+4 Zn-69 6.70E-2 9.66E-2 5.85E-2 1.42E+3 1.02E+4 8.92E-3 Br-82 2.09E+4 Br-83 4.74E+2 Br-84 5.48E+2 Br-85 2.53E+1 Rb-86 1.98E+5 7.99E+3 1.14E+5 Rb-88 5.62E+2 1.72E+1 3.66E+2 Rb-89 3.45E+2 1.89E+0 2.90E+2 Sr-89 5.99E+5 2.16E+6 1.67E+5 1.72E+4 Sr-90 1.01E+8 1.48E+7 3.43E+5 6.44E+6 Sr-91 1.21E+2 5.33E+4 1.74E+5 4.59E+0 Sr-92 1.31E+1 2.40E+4 2.42E+5 5.25E-1 Y-90 4.11E+3 2.62E+5 2.68E+5 1.11E+2 Y-91m 5.07E-1 2.81E+3 1.72E+3 1.84E-2 Y-91 9.14E+5 2.63E+6 1.84E+5 2.44E+4 Y-92 2.04E+1 2.39E+4 2.39E+5 5.81E-1 Y-93 1.86E+2 7.44E+4 3.89E+5 5.11E+0 Zr-95 1.90E+5 4.18E+4 5.96E+4 2.23E+6 6.11E+4 3.70E+4 Zr-97 1.88E+2 2.72E+1 3.89E+1 1.13E+5 3.51E+5 1.60E+1 Nb-95 2.35E+4 9.18E+3 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-97 4.29E-1 7.70E-2 8.55E-2 3.42E+3 2.78E+4 3.60E-2 Mo-99 1.72E+2 3.92E+2 1.35E+5 1.27E+5 4.26E+1 Tc-99m 1.78E-3 3.48E-3 5.07E-2 9.51E+2 4.81E+3 5.77E-2 Tc-101 8.10E-5 8.51E-5 1.45E-3 5.85E+2 1.63E+1 1.08E-3

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 14 Table 2.4 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - CHILD (mrem/yr per Ci/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.79E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-105 1.53E+0 1.34E+0 1.59E+4 9.95E+4 5.55E-1 Ru-106 1.36E+5 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Rh-103m -

Rh-106 Ag-110m 1.69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1.92E+3 4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-127 2.77E+0 9.51E-1 1.96E+0 7.07E+0 1.00E+4 5.62E+4 6.11E-1 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-1 2.93E+3 2.55E+4 2.38E-2 Te-131m 1.34E+2 5.92E+1 9.77E+1 4.00E+2 2.06E+5 3.08E+5 5.07E+1 Te-131 2.17E-2 8.44E-3 1.70E-2 5.88E-2 2.05E+3 1.33E+3 6.59E-3 Te-132 4.81E+2 2.72E+2 3.17E+2 1.77E+3 3.77E+5 1.38E+5 2.63E+2 I-130 8.18E+3 1.64E+4 1.85E+6 2.45E+4 5.11E+3 8.44E+3 I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 2.84E+3 2.73E+4 I-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 3.20E+3 1.88E+3 I-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 5.48E+3 7.70E+3 I-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 9.55E+2 9.95E+2 I-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-138 6.33E+2 8.40E+2 6.22E+2 6.81E+1 2.70E+2 5.55E+2 Ba-139 1.84E+0 9.84E-4 8.62E-4 5.77E+3 5.77E+4 5.37E-2 Ba-140 7.40E+4 6.48E+1 2.11E+1 1.74E+6 1.02E+5 4.33E+3 Ba-141 1.96E-1 1.09E-4 9.47E-5 2.92E+3 2.75E+2 6.36E-3 Ba-142 5.00E-2 3.60E-5 2.91E-5 1.64E+3 2.74E+0 2.79E-3 La-140 6.44E+2 2.25E+2 1.83E+5 2.26E+5 7.55E+1 La-142 1.30E+0 4.11E-1 8.70E+3 7.59E+4 1.29E-1 Ce-141 3.92E+4 1.95E+4 8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-143 3.66E+2 1.99E+2 8.36E+1 1.15E+5 1.27E+5 2.87E+1 Ce-144 6.77E+6 2.12E+6 1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 3.00E+3 4.33E+5 9.73E+4 9.14E+2 Pr-144 5.96E-2 1.85E-2 9.77E-3 1.57E+3 1.97E+2 3.00E-3 Nd-147 1.08E+4 8.73E+3 4.81E+3 3.28E+5 8.21E+4 6.81E+2 W-187 1.63E+1 9.66E+0 4.11E+4 9.10E+4 4.33E+0 Np-239 4.66E+2 3.34E+1 9.73E+1 5.81E+4 6.40E+4 2.35E+1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 15 Table 2.5 (Page 1 of 2)

Ri Inhalation Pathway Dose Factors - INFANT (mrem/yr per Ci/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 Na-24 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 P-32 2.03E+6 1.12E+5 1.61E+4 7.74E+4 Cr-51 5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 2.53E+4 4.98E+3 1.00E+6 7.06E+3 4.98E+3 Mn-56 1.54E+0 1.10E+0 1.25E+4 7.17E+4 2.21E-1 Fe-55 1.97E+4 1.17E+4 8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 1.02E+6 2.48E+4 9.48E+3 Co-57 6.51E+2 3.79E+5 4.86E+3 6.41E+2 Co-58 1.22E+3 7.77E+5 1.11E+4 1.82E+3 Co-60 8.02E+3 4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 1.16E+4 Ni-65 2.39E+0 2.84E-1 8.12E+3 5.01E+4 1.23E-1 Cu-64 1.88E+0 3.98E+0 9.30E+3 1.50E+4 7.74E-1 Zn-65 1.93E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4 3.11E+4 Zn-69 5.39E-2 9.67E-2 4.02E-2 1.47E+3 1.32E+4 7.18E-3 Br-82 1.33E+4 Br-83 3.81E+2 Br-84 4.00E+2 Br-85 2.04E+1 Rb-86 1.90E+5 3.04E+3 8.82E+4 Rb-88 5.57E+2 3.39E+2 2.87E+2 Rb-89 3.21E+2 6.82E+1 2.06E+2 Sr-89 3.98E+5 2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 1.12E+7 1.31E+5 2.59E+6 Sr-91 9.56E+1 5.26E+4 7.34E+4 3.46E+0 Sr-92 1.05E+1 2.38E+4 1.40E+5 3.91E-1 Y-90 3.29E+3 2.69E+5 1.04E+5 8.82E+1 Y-91m 4.07E-1 2.79E+3 2.35E+3 1.39E-2 Y-91 5.88E+5 2.45E+6 7.03E+4 1.57E+4 Y-92 1.64E+1 2.45E+4 1.27E+5 4.61E-1 Y-93 1.50E+2 7.64E+4 1.67E+5 4.07E+0 Zr-95 1.15E+5 2.79E+4 3.11E+4 1.75E+6 2.17E+4 2.03E+4 Zr-97 1.50E+2 2.56E+1 2.59E+1 1.10E+5 1.40E+5 1.17E+1 Nb-95 1.57E+4 6.43E+3 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Nb-97 3.42E-1 7.29E-2 5.70E-2 3.32E+3 2.69E+4 2.63E-2 Mo-99 1.65E+2 2.65E+2 1.35E+5 4.87E+4 3.23E+1 Tc-99m 1.40E-3 2.88E-3 3.11E-2 8.11E+2 2.03E+3 3.72E-2 Tc-101 6.51E-5 8.23E-5 9.79E-4 5.84E+2 8.44E+2 8.12E-4

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 16 Table 2.5 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - INFANT (mrem/yr per Ci/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.02E+3 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-105 1.22E+0 8.99E-1 1.57E+4 4.84E+4 4.10E-1 Ru-106 8.68E+4 1.07E+5 1.16E+7 1.64E+5 1.09E+4 Rh-103m -

Rh-106 Ag-110m 9.98E+3 7.22E+3 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 2.65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 1.64E+6 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-127 2.23E+0 9.53E-1 1.85E+0 4.86E+0 1.03E+4 2.44E+4 4.89E-1 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-1 3.00E+3 2.63E+4 1.88E-2 Te-131m 1.07E+2 5.50E+1 8.93E+1 2.65E+2 1.99E+5 1.19E+5 3.63E+1 Te-131 1.74E-2 8.22E-3 1.58E-2 3.99E-2 2.06E+3 8.22E+3 5.00E-3 Te-132 3.72E+2 2.37E+2 2.79E+2 1.03E+3 3.40E+5 4.41E+4 1.76E+2 I-130 6.36E+3 1.39E+4 1.60E+6 1.53E+4 1.99E+3 5.57E+3 I-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 1.06E+3 1.96E+4 I-132 1.69E+3 3.54E+3 1.69E+5 3.95E+3 1.90E+3 1.26E+3 I-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 2.16E+3 5.60E+3 I-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 1.29E+3 6.65E+2 I-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-138 5.05E+2 7.81E+2 4.10E+2 6.54E+1 8.76E+2 3.98E+2 Ba-139 1.48E+0 9.84E-4 5.92E-4 5.95E+3 5.10E+4 4.30E-2 Ba-140 5.60E+4 5.60E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ba-141 1.57E-1 1.08E-4 6.50E-5 2.97E+3 4.75E+3 4.97E-3 Ba-142 3.98E-2 3.30E-5 1.90E-5 1.55E+3 6.93E+2 1.96E-3 La-140 5.05E+2 2.00E+2 1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+0 3.77E-1 8.22E+3 5.95E+4 9.04E-2 Ce-141 2.77E+4 1.67E+4 5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-143 2.93E+2 1.93E+2 5.64E+1 1.16E+5 4.97E+4 2.21E+1 Ce-144 3.19E+6 1.21E+6 5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 1.97E+3 4.33E+5 3.72E+4 6.99E+2 Pr-144 4.79E-2 1.85E-2 6.72E-3 1.61E+3 4.28E+3 2.41E-3 Nd-147 7.94E+3 8.13E+3 3.15E+3 3.22E+5 3.12E+4 5.00E+2 W-187 1.30E+1 9.02E+0 3.96E+4 3.56E+4 3.12E+0 Np-239 3.71E+2 3.32E+1 6.62E+1 5.95E+4 2.49E+4 1.88E+1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 17 Table 2.6 (Page 1 of 2)

Ri Vegetation Pathway Dose Factors - ADULT (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 P-32 1.40E+9 8.73E+7 -

1.58E+8 5.42E+7 Cr-51 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 3.11E+8 -

9.27E+7 9.54E+8 5.94E+7 Mn-56 1.61E+1 -

2.04E+1 5.13E+2 2.85E+0 Fe-55 2.09E+8 1.45E+8 -

8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 -

8.35E+7 9.96E+8 1.14E+8 Co-57 1.17E+7 -

2.97E+8 1.95E+7 Co-58 3.09E+7 -

6.26E+8 6.92E+7 Co-60 1.67E+8 -

3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 -

1.50E+8 3.49E+8 Ni-65 6.15E+1 7.99E+0 -

2.03E+2 3.65E+0 Cu-64 9.27E+3 -

2.34E+4 7.90E+5 4.35E+3 Zn-65 3.17E+8 1.01E+9 -

6.75E+8 6.36E+8 4.56E+8 Zn-69 8.75E-6 1.67E 1.09E-5 2.51E-6 1.16E-6 Br-82 1.73E+6 1.51E+6 Br-83 4.63E+0 3.21E+0 Br-84 Br-85 Rb-86 2.19E+8 -

4.32E+7 1.02E+8 Rb-88 Rb-89 Sr-89 9.96E+9 1.60E+9 2.86E+8 Sr-90 6.05E+11 -

1.75E+10 1.48E+11 Sr-91 3.20E+5 1.52E+6 1.29E+4 Sr-92 4.27E+2 8.46E+3 1.85E+1 Y-90 1.33E+4 1.41E+8 3.56E+2 Y-91m 5.83E-9 1.71E-8 Y-91 5.13E+6 2.82E+9 1.37E+5 Y-92 9.01E-1 1.58E+4 2.63E-2 Y-93 1.74E+2 5.52E+6 4.80E+0 Zr-95 1.19E+6 3.81E+5 -

5.97E+5 1.21E+9 2.58E+5 Zr-97 3.33E+2 6.73E+1 -

1.02E+2 2.08E+7 3.08E+1 Nb-95 1.42E+5 7.91E+4 -

7.81E+4 4.80E+8 4.25E+4 Nb-97 2.90E-6 7.34E 8.56E-7 2.71E-3 2.68E-7 Mo-99 6.25E+6 -

1.41E+7 1.45E+7 1.19E+6 Tc-99m 3.06E+0 8.66E+0 -

1.32E+2 4.24E+0 5.12E+3 1.10E+2 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 18 Table 2.6 (Page 2 of 2)

Ri Vegetation Pathway Dose Factors - ADULT (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 4.80E+6 -

1.83E+7 5.61E+8 2.07E+6 Ru-105 5.39E+1 -

6.96E+2 3.30E+4 2.13E+1 Ru-106 1.93E+8 -

3.72E+8 1.25E+10 2.44E+7 Rh-103m -

Rh-106 Ag-110m 1.06E+7 9.76E+6 1.92E+7 3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 1.17E+9 4.26E+7 Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 4.54E+5 1.25E+3 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 1.28E+9 4.03E+7 Te-129 6.65E-4 2.50E-4 5.10E-4 2.79E-3 5.02E-4 1.62E-4 Te-131m 9.12E+5 4.46E+5 7.06E+5 4.52E+6 4.43E+7 3.72E+5 Te-131 Te-132 4.29E+6 2.77E+6 3.06E+6 2.67E+7 1.31E+8 2.60E+6 I-130 3.96E+5 1.17E+6 9.90E+7 1.82E+6 1.01E+6 4.61E+5 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.05E+7 6.63E+7 I-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 2.89E+1 5.38E+1 I-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 3.31E+6 1.12E+6 I-134 1.06E-4 2.88E-4 5.00E-3 4.59E-4 2.51E-7 1.03E-4 I-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 1.21E+5 3.94E+4 Cs-134 4.66E+9 1.11E+10 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+8 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 2.95E+9 9.81E+8 1.68E+8 5.70E+9 Cs-138 Ba-139 2.95E-2 2.10E-5 1.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-140 1.29E+8 1.62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ba-141 Ba-142 La-140 1.97E+3 9.92E+2 7.28E+7 2.62E+2 La-142 1.40E-4 6.35E-5 4.64E-1 1.58E-5 Ce-141 1.96E+5 1.33E+5 6.17E+4 5.08E+8 1.51E+4 Ce-143 1.00E+3 7.42E+5 3.26E+2 2.77E+7 8.21E+1 Ce-144 3.29E+7 1.38E+7 8.16E+6 1.11E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 1.47E+4 2.78E+8 3.14E+3 Pr-144 Nd-147 3.34E+4 3.86E+4 2.25E+4 1.85E+8 2.31E+3 W-187 3.82E+4 3.19E+4 1.05E+7 1.12E+4 Np-239 1.42E+3 1.40E+2 4.37E+2 2.87E+7 7.72E+1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 19 Table 2.7 (Page 1 of 2)

Ri Vegetation Pathway Dose Factors - TEEN (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 P-32 1.61E+9 9.96E+7 1.35E+8 6.23E+7 Cr-51 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 4.52E+8 1.35E+8 9.27E+8 8.97E+7 Mn-56 1.45E+1 1.83E+1 9.54E+2 2.58E+0 Fe-55 3.25E+8 2.31E+8 1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 1.33E+8 9.98E+8 1.63E+8 Co-57 1.79E+7 3.34E+8 3.00E+7 Co-58 4.38E+7 6.04E+8 1.01E+8 Co-60 2.49E+8 3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 1.81E+8 5.45E+8 Ni-65 5.73E+1 7.32E+0 3.97E+2 3.33E+0 Cu-64 8.40E+3 2.12E+4 6.51E+5 3.95E+3 Zn-65 4.24E+8 1.47E+9 9.41E+8 6.23E+8 6.86E+8 Zn-69 8.19E-6 1.56E-5 1.02E-5 2.88E-5 1.09E-6 Br-82 1.33E+6 Br-83 3.01E+0 Br-84 Br-85 Rb-86 2.73E+8 4.05E+7 1.28E+8 Rb-88 Rb-89 Sr-89 1.51E+10 -

1.80E+9 4.33E+8 Sr-90 7.51E+11 -

2.11E+10 1.85E+11 Sr-91 2.99E+5 1.36E+6 1.19E+4 Sr-92 3.97E+2 1.01E+4 1.69E+1 Y-90 1.24E+4 1.02E+8 3.34E+2 Y-91m 5.43E-9 2.56E-7 Y-91 7.87E+6 3.23E+9 2.11E+5 Y-92 8.47E-1 2.32E+4 2.45E-2 Y-93 1.63E+2 4.98E+6 4.47E+0 Zr-95 1.74E+6 5.49E+5 8.07E+5 1.27E+9 3.78E+5 Zr-97 3.09E+2 6.11E+1 9.26E+1 1.65E+7 2.81E+1 Nb-95 1.92E+5 1.06E+5 1.03E+5 4.55E+8 5.86E+4 Nb-97 2.69E-6 6.67E-7 7.80E-7 1.59E-2 2.44E-7 Mo-99 5.74E+6 1.31E+7 1.03E+7 1.09E+6 Tc-99m 2.70E+0 7.54E+0 1.12E+2 4.19E+0 4.95E+3 9.77E+1 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 20 Table 2.7 (Page 2 of 2)

Ri Vegetation Pathway Dose Factors - TEEN (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 6.87E+6 2.42E+7 5.74E+8 2.94E+6 Ru-105 5.00E+1 6.31E+2 4.04E+4 1.94E+1 Ru-106 3.09E+8 5.97E+8 1.48E+10 3.90E+7 Rh-103m Rh-106 Ag-110m 1.52E+7 1.44E+7 2.74E+7 4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 1.88E+8 1.66E+9 5.00E+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 1.37E+9 6.56E+7 Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4 4.19E+5 1.17E+3 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 1.38E+9 5.81E+7 Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E-3 3.40E-3 1.51E-4 Te-131m 8.44E+5 4.05E+5 6.09E+5 4.22E+6 3.25E+7 3.38E+5 Te-131 Te-132 3.90E+6 2.47E+6 2.60E+6 2.37E+7 7.82E+7 2.32E+6 I-130 3.54E+5 1.02E+6 8.35E+7 1.58E+6 7.87E+5 4.09E+5 I-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 2.13E+7 5.79E+7 I-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 5.91E+1 4.87E+1 I-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 2.53E+6 1.02E+6 I-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 3.35E-6 9.13E-5 I-135 3.68E+4 9.48E+4 6.10E+6 1.50E+5 1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E+8 9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 -

4.59E+9 1.78E+9 1.92E+8 4.69E+9 Cs-138 Ba-139 2.77E-2 1.95E-5 1.84E-5 1.34E-5 2.47E-1 8.08E-4 Ba-140 1.38E+8 1.69E+5 5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ba-141 Ba-142 La-140 1.80E+3 8.84E+2 5.08E+7 2.35E+2 La-142 1.28E-4 5.69E-5 1.73E+0 1.42E-5 Ce-141 2.82E+5 1.88E+5 8.86E+4 5.38E+8 2.16E+4 Ce-143 9.37E+2 6.82E+5 3.06E+2 2.05E+7 7.62E+1 Ce-144 5.27E+7 2.18E+7 1.30E+7 1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 1.65E+4 2.34E+8 3.55E+3 Pr-144 Nd-147 3.63E+4 3.94E+4 2.32E+4 1.42E+8 2.36E+3 W-187 3.55E+4 2.90E+4 7.84E+6 1.02E+4 Np-239 1.38E+3 1.30E+2 4.09E+2 2.10E+7 7.24E+1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 21 Table 2.8 (Page 1 of 2)

Ri Vegetation Pathway Dose Factors - CHILD (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 Na-24 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 P-32 3.37E+9 1.58E+8 9.30E+7 1.30E+8 Cr-51 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 6.61E+8 1.85E+8 5.55E+8 1.76E+8 Mn-56 1.90E+1 2.29E+1 2.75E+3 4.28E+0 Fe-55 8.00E+8 4.24E+8 2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 1.88E+8 6.76E+8 3.23E+8 Co-57 2.99E+7 2.45E+8 6.04E+7 Co-58 6.47E+7 3.77E+8 1.98E+8 Co-60 3.78E+8 2.10E+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 1.42E+8 1.34E+9 Ni-65 1.05E+2 9.89E+0 1.21E+3 5.77E+0 Cu-64 1.11E+4 2.68E+4 5.20E+5 6.69E+3 Zn-65 8.12E+8 2.16E+9 1.36E+9 3.80E+8 1.35E+9 Zn-69 1.51E-5 2.18E-5 1.32E-5 1.38E-3 2.02E-6 Br-82 2.04E+6 Br-83 5.55E+0 Br-84 Br-85 Rb-86 4.52E+8 2.91E+7 2.78E+8 Rb-88 Rb-89 Sr-89 3.59E+10 -

1.39E+9 1.03E+9 Sr-90 1.24E+12 -

1.67E+10 3.15E+11 Sr-91 5.50E+5 1.21E+6 2.08E+4 Sr-92 7.28E+2 1.38E+4 2.92E+1 Y-90 2.30E+4 6.56E+7 6.17E+2 Y-91m 9.94E-9 1.95E-5 Y-91 1.87E+7 2.49E+9 5.01E+5 Y-92 1.56E+0 4.51E+4 4.46E-2 Y-93 3.01E+2 4.48E+6 8.25E+0 Zr-95 3.90E+6 8.58E+5 1.23E+6 8.95E+8 7.64E+5 Zr-97 5.64E+2 8.15E+1 1.17E+2 1.23E+7 4.81E+1 Nb-95 4.10E+5 1.59E+5 1.50E+5 2.95E+8 1.14E+5 Nb-97 4.90E-6 8.85E-7 9.82E-7 2.73E-1 4.13E-7 Mo-99 7.83E+6 1.67E+7 6.48E+6 1.94E+6 Tc-99m 4.65E+0 9.12E+0 1.33E+2 4.63E+0 5.19E+3 1.51E+2 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 22 Table 2.8 (Page 2 of 2)

Ri Vegetation Pathway Dose Factors - CHILD (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.55E+7 3.89E+7 3.99E+8 5.94E+6 Ru-105 9.17E+1 8.06E+2 5.98E+4 3.33E+1 Ru-106 7.45E+8 1.01E+9 1.16E+10 9.30E+7 Rh-103m Rh-106 Ag-110m 3.22E+7 2.17E+7 4.05E+7 2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 3.38E+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 1.07E+9 1.57E+8 Te-127 1.00E+4 2.70E+3 6.93E+3 2.85E+4 3.91E+5 2.15E+3 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 1.04E+9 1.33E+8 Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E-3 7.17E-2 2.74E-4 Te-131m 1.54E+6 5.33E+5 1.10E+6 5.16E+6 2.16E+7 5.68E+5 Te-131 Te-132 6.98E+6 3.09E+6 4.50E+6 2.87E+7 3.11E+7 3.73E+6 I-130 6.21E+5 1.26E+6 1.38E+8 1.88E+6 5.87E+5 6.47E+5 I-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 1.28E+7 8.18E+7 I-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 1.99E+2 7.77E+1 I-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 1.79E+6 1.68E+6 I-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 2.10E-4 1.46E-4 I-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+10 -

8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 -

7.46E+9 2.68E+9 1.43E+8 3.38E+9 Cs-138 Ba-139 5.11E-2 2.73E-5 2.38E-5 1.61E-5 2.95E+0 1.48E-3 Ba-140 2.77E+8 2.43E+5 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ba-141 Ba-142 La-140 3.23E+3 1.13E+3 3.15E+7 3.81E+2 La-142 2.32E-4 7.40E-5 1.47E+1 2.32E-5 Ce-141 6.35E+5 3.26E+5 1.43E+5 4.07E+8 4.84E+4 Ce-143 1.73E+3 9.36E+5 3.93E+2 1.37E+7 1.36E+2 Ce-144 1.27E+8 3.98E+7 2.21E+7 1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 2.41E+4 1.60E+8 7.37E+3 Pr-144 Nd-147 7.16E+4 5.80E+4 3.18E+4 9.18E+7 4.49E+3 W-187 6.47E+4 3.83E+4 5.38E+6 1.72E+4 Np-239 2.55E+3 1.83E+2 5.30E+2 1.36E+7 1.29E+2

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 23 Table 2.9 (Page 1 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - ADULT (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 1.92E+9 6.60E+8 Cr-51 1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 8.40E+6 2.50E+6 2.57E+7 1.60E+6 Mn-56 4.23E-3 5.38E-3 1.35E-1 7.51E-4 Fe-55 2.51E+7 1.73E+7 9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 1.95E+7 2.33E+8 2.68E+7 Co-57 1.28E+6 3.25E+7 2.13E+6 Co-58 4.72E+6 9.57E+7 1.06E+7 Co-60 1.64E+7 3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 9.73E+7 2.26E+8 Ni-65 3.70E-1 4.81E-2 1.22E+0 2.19E-2 Cu-64 2.41E+4 6.08E+4 2.05E+6 1.13E+4 Zn-65 1.37E+9 4.36E+9 2.92E+9 2.75E+9 1.97E+9 Zn-69 Br-82 3.72E+7 3.25E+7 Br-83 1.49E-1 1.03E-1 Br-84 Br-85 Rb-86 2.59E+9 5.11E+8 1.21E+9 Rb-88 Rb-89 Sr-89 1.45E+9 2.33E+8 4.16E+7 Sr-90 4.68E+10 -

1.35E+9 1.15E+10 Sr-91 3.13E+4 1.49E+5 1.27E+3 Sr-92 4.89E-1 9.68E+0 2.11E-2 Y-90 7.07E+1 7.50E+5 1.90E+0 Y-91m Y-91 8.60E+3 4.73E+6 2.30E+2 Y-92 5.42E-5 9.49E-1 1.58E-6 Y-93 2.33E-1 7.39E+3 6.43E-3 Zr-95 9.46E+2 3.03E+2 4.76E+2 9.62E+5 2.05E+2 Zr-97 4.26E-1 8.59E-2 1.30E-1 2.66E+4 3.93E-2 Nb-95 8.25E+4 4.59E+4 4.54E+4 2.79E+8 2.47E+4 Nb-97 5.47E Mo-99 2.52E+7 5.72E+7 5.85E+7 4.80E+6 Tc-99m 3.25E+0 9.19E+0 1.40E+2 4.50E+0 5.44E+3 1.17E+2 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 24 Table 2.9 (Page 2 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - ADULT (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.02E+3 -

3.89E+3 -

1.19E+5 4.39E+2 Ru-105 8.57E 1.11E 5.24E-1 3.38E-4 Ru-106 2.04E+4 -

3.94E+4 -

1.32E+6 2.58E+3 Rh-103m -

Rh-106 Ag-110m 5.83E+7 5.39E+7 1.06E+8 -

2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.00E+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -

6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -

1.54E+8 5.58E+6 Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 -

5.30E+4 1.45E+2 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 -

3.04E+8 9.57E+6 Te-129 Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79E+6 -

1.75E+7 1.47E+5 Te-131 Te-132 2.39E+6 1.55E+6 1.71E+6 1.49E+7 -

7.32E+7 1.45E+6 I-130 4.26E+5 1.26E+6 1.07E+8 1.96E+6 -

1.08E+6 4.96E+5 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 -

1.12E+8 2.43E+8 I-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 8.22E-2 1.53E-1 I-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 -

6.20E+6 2.10E+6 I-134 I-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 -

4.10E+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 -

4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 1.03E+9 5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 -

3.43E+9 1.14E+9 1.95E+8 6.61E+9 Cs-138 Ba-139 4.70E -

8.34E-8 1.38E-9 Ba-140 2.69E+7 3.38E+4 1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-141 Ba-142 La-140 4.49E+0 2.26E+0 1.66E+5 5.97E-1 La-142 3.03E-8 Ce-141 4.84E+3 3.27E+3 1.52E+3 -

1.25E+7 3.71E+2 Ce-143 4.19E+1 3.09E+4 1.36E+1 -

1.16E+6 3.42E+0 Ce-144 3.58E+5 1.50E+5 8.87E+4 -

1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 3.68E+1 -

6.96E+5 7.88E+0 Pr-144 Nd-147 9.42E+1 1.09E+2 6.37E+1 -

5.23E+5 6.52E+0 W-187 6.56E+3 5.48E+3 1.80E+6 1.92E+3 Np-239 3.66E+0 3.60E-1 1.12E+0 -

7.39E+4 1.98E-1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 25 Table 2.10 (Page 1 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - TEEN (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr-51 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-54 1.40E+7 4.17E+6 2.87E+7 2.78E+6 Mn-56 7.51E-3 9.50E-3 4.94E-1 1.33E-3 Fe-55 4.45E+7 3.16E+7 2.00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 2.25E+6 4.19E+7 3.76E+6 Co-58 7.95E+6 1.10E+8 1.83E+7 Co-60 2.78E+7 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 1.33E+8 4.01E+8 Ni-65 6.78E-1 8.66E-2 4.70E+0 3.94E-2 Cu-64 4.29E+4 1.09E+5 3.33E+6 2.02E+4 Zn-65 2.11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 Zn-69 Br-82 5.64E+7 Br-83 1.91E-1 Br-84 Br-85 Rb-86 4.73E+9 7.00E+8 2.22E+9 Rb-88 Rb-89 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 6.61E+10 -

1.86E+9 1.63E+10 Sr-91 5.75E+4 2.61E+5 2.29E+3 Sr-92 8.95E-1 2.28E+1 3.81E-2 Y-90 1.30E+2 1.07E+6 3.50E+0 Y-91m Y-91 1.58E+4 6.48E+6 4.24E+2 Y-92 1.00E-4 2.75E+0 2.90E-6 Y-93 4.30E-1 1.31E+4 1.18E-2 Zr-95 1.65E+3 5.22E+2 7.67E+2 1.20E+6 3.59E+2 Zr-97 7.75E-1 1.53E-1 2.32E-1 4.15E+4 7.06E-2 Nb-95 1.41E+5 7.80E+4 7.57E+4 3.34E+8 4.30E+4 Nb-97 6.34E-8 Mo-99 4.56E+7 1.04E+8 8.16E+7 8.69E+6 Tc-99m 5.64E+0 1.57E+1 2.34E+2 8.73E+0 1.03E+4 2.04E+2 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 26 Table 2.10 (Page 2 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - TEEN (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.81E+3 6.40E+3 -

1.52E+5 7.75E+2 Ru-105 1.57E-3 1.97E-2 1.26E+0 6.08E-4 Ru-106 3.75E+4 7.23E+4 -

1.80E+6 4.73E+3 Rh-103m -

Rh-106 Ag-110m 9.63E+7 9.11E+7 1.74E+8 -

2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01E+7 9.25E+8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 3.21E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -

2.10E+8 1.00E+7 Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 -

9.61E+4 2.68E+2 Te-129m 1.11E+8 4.10E+7 3.57E+7 4.62E+8 -

4.15E+8 1.75E+7 Te-129 1.67E-9 2.18E-9 Te-131m 6.57E+5 3.15E+5 4.74E+5 3.29E+6 -

2.53E+7 2.63E+5 Te-131 Te-132 4.28E+6 2.71E+6 2.86E+6 2.60E+7 -

8.58E+7 2.55E+6 I-130 7.49E+5 2.17E+6 1.77E+8 3.34E+6 -

1.67E+6 8.66E+5 I-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 -

1.49E+8 4.04E+8 I-132 2.90E-1 7.59E-1 2.56E+1 1.20E+0 -

3.31E-1 2.72E-1 I-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 -

9.30E+6 3.75E+6 I-134 I-135 2.47E+4 6.35E+4 4.08E+6 1.00E+5 7.03E+4 2.35E+4 Cs-134 9.81E+9 2.31E+10 -

7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Cs-138 Ba-139 8.69E-8 7.75E-7 2.53E-9 Ba-140 4.85E+7 5.95E+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ba-141 Ba-142 La-140 8.06E+0 3.96E+0 2.27E+5 1.05E+0 La-142 2.23E-7 Ce-141 8.87E+3 5.92E+3 2.79E+3 -

1.69E+7 6.81E+2 Ce-143 7.69E+1 5.60E+4 2.51E+1 -

1.68E+6 6.25E+0 Ce-144 6.58E+5 2.72E+5 1.63E+5 -

1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 6.77E+1 -

9.61E+5 1.45E+1 Pr-144 Nd-147 1.81E+2 1.97E+2 1.16E+2 -

7.11E+5 1.18E+1 W-187 1.20E+4 9.78E+3 2.65E+6 3.43E+3 Np-239 6.99E+0 6.59E-1 2.07E+0 -

1.06E+5 3.66E-1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 27 Table 2.11 (Page 1 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 P-32 7.77E+10 3.64E+9 2.15E+9 3.00E+9 Cr-51 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn-54 2.09E+7 5.87E+6 1.76E+7 5.58E+6 Mn-56 1.31E-2 1.58E-2 1.90E+0 2.95E-3 Fe-55 1.12E+8 5.93E+7 3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 5.65E+7 2.03E+8 9.71E+7 Co-57 3.84E+6 3.14E+7 7.77E+6 Co-58 1.21E+7 7.08E+7 3.72E+7 Co-60 4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 1.07E+8 1.01E+9 Ni-65 1.66E+0 1.56E-1 1.91E+1 9.11E-2 Cu-64 7.55E+4 1.82E+5 3.54E+6 4.56E+4 Zn-65 4.13E+9 1.10E+10 6.94E+9 1.93E+9 6.85E+9 Zn-69 2.14E-9 Br-82 1.15E+8 Br-83 4.69E-1 Br-84 Br-85 Rb-86 8.77E+9 5.64E+8 5.39E+9 Rb-88 Rb-89 Sr-89 6.62E+9 2.56E+8 1.89E+8 Sr-90 1.12E+11 -

1.51E+9 2.83E+10 Sr-91 1.41E+5 3.12E+5 5.33E+3 Sr-92 2.19E+0 4.14E+1 8.76E-2 Y-90 3.22E+2 9.15E+5 8.61E+0 Y-91m Y-91 3.91E+4 5.21E+6 1.04E+3 Y-92 2.46E-4 7.10E+0 7.03E-6 Y-93 1.06E+0 1.57E+4 2.90E-2 Zr-95 3.84E+3 8.45E+2 1.21E+3 8.81E+5 7.52E+2 Zr-97 1.89E+0 2.72E-1 3.91E-1 4.13E+4 1.61E-1 Nb-95 3.18E+5 1.24E+5 1.16E+5 2.29E+8 8.84E+4 Nb-97 1.45E-6 Mo-99 8.29E+7 1.77E+8 6.86E+7 2.05E+7 Tc-99m 1.29E+1 2.54E+1 3.68E+2 1.29E+1 1.44E+4 4.20E+2 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 28 Table 2.11 (Page 2 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 4.29E+3 1.08E+4 1.11E+5 1.65E+3 Ru-105 3.82E-3 3.36E-2 2.49E+0 1.39E-3 Ru-106 9.24E+4 1.25E+5 1.44E+6 1.15E+4 Rh-103m Rh-106 Ag-110m 2.09E+8 1.41E+8 2.63E+8 1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.00E+7 2.07E+7 7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 1.68E+8 2.47E+7 Te-127 3.06E+3 8.25E+2 2.12E+3 8.71E+3 1.20E+5 6.56E+2 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.00E+8 3.32E+8 4.23E+7 Te-129 2.87E-9 6.12E-8 Te-131m 1.60E+6 5.53E+5 1.14E+6 5.35E+6 2.24E+7 5.89E+5 Te-131 Te-132 1.02E+7 4.52E+6 6.58E+6 4.20E+7 4.55E+7 5.46E+6 I-130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 1.66E+6 1.82E+6 I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.17E+8 7.46E+8 I-132 6.86E-1 1.26E+0 5.85E+1 1.93E+0 1.48E+0 5.80E-1 I-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 8.77E+6 8.23E+6 I-134 I-135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 8.00E+4 4.97E+4 Cs-134 2.26E+10 3.71E+10 -

1.15E+10 4.13E+9 2.00E+8 7.83E+9 Cs-136 1.00E+9 2.76E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 1.01E+10 3.62E+9 1.93E+8 4.55E+9 Cs-138 Ba-139 2.14E-7 1.23E-5 6.19E-9 Ba-140 1.17E+8 1.03E+5 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ba-141 Ba-142 La-140 1.93E+1 6.74E+0 1.88E+5 2.27E+0 La-142 2.51E-6 Ce-141 2.19E+4 1.09E+4 4.78E+3 1.36E+7 1.62E+3 Ce-143 1.89E+2 1.02E+5 4.29E+1 1.50E+6 1.48E+1 Ce-144 1.62E+6 5.09E+5 2.82E+5 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 1.17E+2 7.80E+5 3.59E+1 Pr-144 Nd-147 4.45E+2 3.60E+2 1.98E+2 5.71E+5 2.79E+1 W-187 2.91E+4 1.72E+4 2.42E+6 7.73E+3 Np-239 1.72E+1 1.23E+0 3.57E+0 9.14E+4 8.68E-1

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 29 Table 2.12 (Page 1 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - INFANT (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 Na-24 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 P-32 1.60E+11 9.42E+9 2.17E+9 6.21E+9 Cr-51 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 3.89E+7 8.63E+6 1.43E+7 8.83E+6 Mn-56 3.21E-2 2.76E-2 2.91E+0 5.53E-3 Fe-55 1.35E+8 8.72E+7 4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 1.16E+8 1.88E+8 1.55E+8 Co-57 8.95E+6 3.05E+7 1.46E+7 Co-58 2.43E+7 6.05E+7 6.06E+7 Co-60 8.81E+7 2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 1.07E+8 1.21E+9 Ni-65 3.51E+0 3.97E-1 3.02E+1 1.81E-1 Cu-64 1.88E+5 3.17E+5 3.85E+6 8.69E+4 Zn-65 5.55E+9 1.90E+10 9.23E+9 1.61E+10 8.78E+9 Zn-69 7.36E-9 Br-82 1.94E+8 Br-83 9.95E-1 Br-84 Br-85 Rb-86 2.22E+10 5.69E+8 1.10E+10 Rb-88 Rb-89 Sr-89 1.26E+10 -

2.59E+8 3.61E+8 Sr-90 1.22E+11 -

1.52E+9 3.10E+10 Sr-91 2.94E+5 3.48E+5 1.06E+4 Sr-92 4.65E+0 5.01E+1 1.73E-1 Y-90 6.80E+2 9.39E+5 1.82E+1 Y-91m Y-91 7.33E+4 5.26E+6 1.95E+3 Y-92 5.22E-4 9.97E+0 1.47E-5 Y-93 2.25E+0 1.78E+4 6.13E-2 Zr-95 6.83E+3 1.66E+3 1.79E+3 8.28E+5 1.18E+3 Zr-97 3.99E+0 6.85E-1 6.91E-1 4.37E+4 3.13E-1 Nb-95 5.93E+5 2.44E+5 1.75E+5 2.06E+8 1.41E+5 Nb-97 3.70E-6 Mo-99 2.12E+8 3.17E+8 6.98E+7 4.13E+7 Tc-99m 2.69E+1 5.55E+1 5.97E+2 2.90E+1 1.61E+4 7.15E+2 Tc-101

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 30 Table 2.12 (Page 2 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - INFANT (mrem/yr per Ci/m3) for H-3 and C-14 (m² x mrem/yr Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 8.69E+3 1.81E+4 1.06E+5 2.91E+3 Ru-105 8.06E-3 5.92E-2 3.21E+0 2.71E-3 Ru-106 1.90E+5 2.25E+5 1.44E+6 2.38E+4 Rh-103m Rh-106 Ag-110m 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1.70E+8 5.10E+7 Te-127 6.50E+3 2.18E+3 5.29E+3 1.59E+4 1.36E+5 1.40E+3 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 3.34E+8 8.62E+7 Te-129 2.08E-9 1.75E-9 5.18E-9 1.66E-7 Te-131m 3.38E+6 1.36E+6 2.76E+6 9.35E+6 2.29E+7 1.12E+6 Te-131 Te-132 2.10E+7 1.04E+7 1.54E+7 6.51E+7 3.85E+7 9.72E+6 I-130 3.60E+6 7.92E+6 8.88E+8 8.70E+6 1.70E+6 3.18E+6 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 1.15E+8 1.41E+9 I-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 2.34E+0 1.03E+0 I-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 9.16E+6 1.58E+7 I-134 1.01E-9 I-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 -

1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Cs-138 Ba-139 4.55E-7 2.88E-5 1.32E-8 Ba-140 2.41E+8 2.41E+5 5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ba-141 Ba-142 La-140 4.03E+1 1.59E+1 1.87E+5 4.09E+0 La-142 5.21E-6 Ce-141 4.33E+4 2.64E+4 8.15E+3 1.37E+7 3.11E+3 Ce-143 4.00E+2 2.65E+5 7.72E+1 1.55E+6 3.02E+1 Ce-144 2.33E+6 9.52E+5 3.85E+5 1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 2.08E+2 7.89E+5 7.41E+1 Pr-144 Nd-147 8.82E+2 9.06E+2 3.49E+2 5.74E+5 5.55E+1 W-187 6.12E+4 4.26E+4 2.50E+6 1.47E+4 Np-239 3.64E+1 3.25E+0 6.49E+0 9.40E+4 1.84E+0

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 31 Table 2.13 (Page 1 of 2)

Ri Ground Plane Pathway Dose Factors (m2 x mrem/yr per Ci/sec)

Nuclide Any Organ H-3 C-14 Na-24 1.21E+7 P-32 Cr-51 4.68E+6 Mn-54 1.34E+9 Mn-56 9.05E+5 Fe-55 Fe-59 2.75E+8 Co-57 4.37E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 Ni-65 2.97E+5 Cu-64 6.09E+5 Zn-65 7.45E+8 Zn-69 Br-82 4.57E+7 Br-83 4.89E+3 Br-84 2.03E+5 Br-85 Rb-86 8.98E+6 Rb-88 3.29E+4 Rb-89 1.21E+5 Sr-89 2.16E+4 Sr-90 Sr-91 2.19E+6 Sr-92 7.77E+5 Y-90 4.48E+3 Y-91m 1.01E+5 Y-91 1.08E+6 Y-92 1.80E+5 Y-93 1.85E+5 Zr-95 2.48E+8 Zr-97 2.94E+6 Nb-95 1.36E+8 Nb-97 2.28E+6 Mo-99 4.05E+6 Tc-99m 1.83E+5 Tc-101 2.04E+4 Ru-103 1.09E+8

Kewaunee Solutions Kewaunee Power Station ODCM 2.0 Offsite Dose Calculation Manual (ODCM)

Revision 20 2.0 - 32 Table 2.13 (Page 2 of 2)

Ri Ground Plane Pathway Dose Factors (m2 x mrem/yr per Ci/sec)

Nuclide Any Organ Ru-105 6.36E+5 Ru-106 4.21E+8 Rh-103m Rh-106 Ag-110m 3.47E+9 Sb-124 2.87E+9 Sb-125 6.49E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-127 3.00E+3 Te-129m 2.00E+7 Te-129 2.60E+4 Te-131m 8.03E+6 Te-131 2.93E+4 Te-132 4.22E+6 I-130 5.53E+6 I-131 1.72E+7 I-132 1.24E+6 I-133 2.47E+6 I-134 4.49E+5 I-135 2.56E+6 Cs-134 6.75E+9 Cs-136 1.49E+8 Cs-137 1.04E+10 Cs-138 3.59E+5 Ba-139 1.06E+5 Ba-140 2.05E+7 Ba-141 4.18E+4 Ba-142 4.49E+4 La-140 1.91E+7 La-142 7.36E+5 Ce-141 1.36E+7 Ce-143 2.32E+6 Ce-144 6.95E+7 Pr-143 Pr-144 1.83E+3 Nd-147 8.40E+6 W-187 2.36E+6 Np-239 1.71E+6

KS-2023-012 Kewaunee Power Station, N490 Highway 42, Kewaunee, WI 54216 ATTACHMENT 3 Kewaunee Solutions Kewaunee Power Station Radiological Environmental Monitoring Manual (REMM), Revision 24 (36 Pages)

Kewaunee Solutions Kewaunee Power Station RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)

Revision: 24 Date: November 7, 2022 Approved By:

KS Radiation Protection Manager (RPM) (Print/Sign)

Date Approved By:

KS Licensing Manager (Print/Sign)

Date Approved By:

Kewaunee Solutions Project General Manager (Print/Sign)

Date Approved By:

KS Project Operations Review Committee Chairman (Print/Sign)

Date David S Villicana Digitally signed by David S Villicana DN: cn=David S Villicana, o=EnergySolutions, ou=RP, email=Dsvillicana@energysolutions.com, c=US Date: 2022.09.08 06:04:32 -05'00' Joseph R. Lynch Digitally signed by Joseph R. Lynch Date: 2022.09.08 07:16:00 -04'00' Ron Worster Digitally signed by Ron Worster Date: 2022.09.08 06:09:52 -06'00' D igitally signed by Frank Coon DN: O=Energysolutions, CN=Frank Coon, E=fcoon-ext@energysolutions.com Reason: I am the author of this document Location:

Date: 2022-09-21 11:32:46 F oxit PhantomPDF Version: 9.4.1 Frank Coon

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 RECORD OF REVISIONS Revision Revision Title Description and Reason for Change 24 Changed company name on coversheet from Dominion Energy Kewaunee to Kewaunee Solutions to reflect ownership change.

24 Changed titles of approvers on coversheet to Kewaunee Solutions managers and Project Operations Review Committee to reflect ownership change.

24 Added Record of Revisions to allow for tracking of changes.

24 Added Kewaunee Solutions to page headers to reflect ownership change.

24 Section 3.5, page 3-3, Quality Assurance Program, changed Dominion Energy Kewaunee to Kewaunee Solutions to reflect ownership change.

24 Section 3.6, page 3-4, Ambient Radiation, changed insure to ensure. Editorial change.

24 Section 3.6, page 3-5, Vegetation, changed Dominion Energy Kewaunee to Kewaunee Solutions to reflect ownership change.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Table of Contents 1.0 Introduction................................................................................................................... 1-1 1.1 Purpose................................................................................................................ 1-1 1.2 Scope................................................................................................................... 1-1 1.3 Implementation................................................................................................... 1-2 2.0 REMP Requirements.................................................................................................... 2-1 2.1 ODCM 13.5 Requirements................................................................................. 2-1 2.2 REMM Requirements......................................................................................... 2-2 REMM 2.2.1/2.3.1 Monitoring Program............................................................ 2-3 REMM 2.2.2/2.3.2 Land Use Census................................................................. 2-7 REMM 2.2.3/2.3.3 Interlaboratory Comparison Program................................ 2-10 REMM 2.4.1 Reporting Requirements............................................................. 2-11 3.0 REMP Implementation................................................................................................ 3-1 3.1 Sampling Requirements...................................................................................... 3-1 3.2 Analysis Methodology........................................................................................ 3-1 3.3 Detection capability (LLD) Requirements.......................................................... 3-1 3.4 Contracted Vendor (CV) Reporting Requirements............................................. 3-2 3.5 Quality Assurance Program................................................................................ 3-3 3.6 Sample Descriptions........................................................................................... 3-4 Tables & Figures Table 2.2.1-A Radiological Environmental Monitoring Program Table 2.2.1-B Type and Frequency of Collection Table 2.2.1-C Sampling Locations, Kewaunee Power Station Table 2.2.1-D Reporting Levels for Radioactivity Concentrations in Environmental Samples Table 2.3.1-A Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)

Figure 1 Environmental Sampling Location Figure 2 Ground Monitoring Wells

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 1-1 1.0 Introduction 1.1 Purpose The purpose of this document is to define the Radiological Environmental Monitoring Program (REMP) for the Kewaunee Power Station (KPS). The REMP is required by the Offsite Dose Calculation Manual (ODCM) 13.5.

This document is known as the Radiological Environmental Monitoring Manual (REMM) and is intended to serve as a tool for program administration and as a guidance document for contractors which implement the monitoring program.

1.2 Scope This program defines the sampling and analysis schedule which was developed to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from plant decommissioning activities. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby verifies that the measurable concentrations of radioactivity and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the development of this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. This program has been developed in accordance with NUREG 0472.

On October 22, 2012, Dominion made known the decision to permanently shut down the Kewaunee Power Station (KPS). On February 25, 2013, Dominion Energy Kewaunee (DEK) submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013, the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii). Therefore, the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel in the reactor vessel, as specified in 10 CFR 50.82(a)(2). On June 15th, 2017, transfer of all spent nuclear fuel into dry cask storage was completed.

On April 24, 2017, Radiation Safety and Control Services, Inc. (RSCS) submitted Technical Support Document No.16-086 Rev. 2, Kewaunee Shut-Down Environmental Radionuclides of Concern and Radiological Environmental Monitoring Manual Changes, to KPS. This document evaluated the radionuclides of concern for environmental releases after permanent shutdown of KPS. The result of the evaluation was the optimization of the environmental program due to radioactive decay and reduced source terms during the decommissioning phase of the plant.

The program will provide field and analytical data on the air, aquatic, and terrestrial radioecology of the area near the Kewaunee Power Station so as to:

1. Determine the effects of the decommissioning activities on the environment.

2. Serve as a gauge of the operating effectiveness of in-plant control of waste discharges; and

3. Provide data on the radiation dose to the public by direct or indirect pathways of exposure.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 1-2 1.3 Implementation This document is considered, by reference, to be part of the Offsite Dose Calculation Manual. This is as required by KPS Technical Requirements Manual (TRM) 10.1.1. The REMM is controlled as a separate document for ease of revision, use in the field and use by contractors. This format was approved by the NRC as part of TS Amendment No. 64, which provided Radiological Effluent Technical Specifications (RETS) for KPS.

The REMP is set up to be implemented by a vendor and controlled by KPS in accordance with procedure RP-KW-113, Radiological Effluent and Environmental Monitoring Programs. Monthly reviews of the vendors progress report are performed by KPS in accordance with this manual in section 3.4. Annual reviews and submittals of the vendors report and monitoring data are checked and approved by KPS in accordance with procedure RP-KW-HSP-HPE-280, Annual Effluent and Environmental Report Review and Submittal. All sample collection, preparation, and analysis are performed by the vendor except where noted. Procedure RP-KW-HSP-HPE-164, Environmental Sample Collection, outlines the environmental sample collection performed by KPS.

Periodic reviews of monitoring data and an annual land use census will be used to develop modifications to the existing monitoring program. Upon approval, these modifications will be incorporated into this document per RP-KW-280, Revision and Control of ODCM and REMM, so that it will accurately reflect the current radiological environmental monitoring program in effect for KPS.

The remainder of this document is divided into two sections. The first section, 2.0 REMP Requirements, describes the different TRM and REMM requirements associated with the REMP. The second section, 3.0 REMP Implementation, describes the specific requirements used to implement the REMP.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-1 2.0 REMP Requirements KPS TS Amendment No. 104 implemented the guidance provided in Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS). These changes included:

1. Incorporation of programmatic controls in the Administrative Controls section of the TS to satisfy existing regulatory requirements for RETS, and

2. Relocation of the procedural details on radioactive effluents monitoring, radiological environmental monitoring, reporting details, and other related specifications from the TS to the ODCM.

Relocating the procedural details to the ODCM allows for revising these requirements using the 10 CFR 50.59 process instead of requiring prior NRC approval using the TS Amendment process.

The RETS requirements were incorporated verbatim into the ODCM, Revision 6. Several of these requirements pertain only to the environmental monitoring program and therefore have been relocated into this document (REMM, Revision 3 and 4) and are identified as REMM requirements.

All KPS TS related REMM requirements were removed from KPS TS and placed in the Technical Requirements Manual as part of TRM Revision 0 on 4/26/2016.

2.1 ODCM 13.5 Requirements ODCM 13.5 provides the programmatic control, which requires a program to monitor for radiation and radionuclides in the environs of the plant. This is the reason for the existence of the REMP.

ODCM 13.5 also provides the programmatic control which requires:

a.

The program to perform the monitoring, sampling, analysis, and reporting in accordance with the methodology and parameters in the ODCM,

b.

A land use census to be performed, and

c.

Participation in an Interlaboratory Comparison Program.

The details of each requirement are described in the REMM requirements stated below.

TRM 10.3.1 requires an Annual Radiological Environmental Operating Report, be submitted to the NRC each year. The specific contents of this report are detailed in REMM 2.4.1. Additional specific reporting requirements are listed in the other REMM requirements.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-2 2.2 REMM Requirements The following REMM requirements include the procedural details that were originally located in the KPS RETS section and then relocated into Revision 6 of the ODCM, as discussed above. These requirements are specific to the radiological environmental monitoring program and have been relocated into this document for ease of use and completeness.

The REMM requirements for the Monitoring Program, Land Use Census, and the Interlaboratory Comparison Program include a detailed operating requirement (numbered 2.2.1, 2.2.2, and 2.2.3 respectively) and an associated verification requirement (numbered 2.3.1, 2.3.2, and 2.3.3 respectively), along with the basis for the requirement. Reporting requirements are listed in requirement REMM 2.4.1.

ODCM 13.0, USE AND APPLICATION, apply to both the ODCM and REMM.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REMM 2.2.1 The radiological environmental monitoring program shall be conducted as specified in Table 2.2.1-A.

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Radiological Environmental Monitoring Program not conducted as specified in REMM Table 2.2.1-A.

A.1 Prepare and submit to the NRC in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

In accordance with the Annual Radiological Environmental Operating Report frequency.

B. Level of radioactivity in an environmental sampling medium at a specified location exceeds the reporting levels of REMM Table 2.2.1-D when averaged over any calendar quarter.

OR B.1 -------------NOTES-------------

1. Only applicable if the radioactivity/radionuclides are the result of plant effluents.

2. For radionuclides other than those in REMM Table 2.2.1-D, this report shall indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-4 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME More than one of the radionuclides in REMM Table 2.2.1-D are detected in the environmental sampling medium and Concentration 1 +

Reporting level 1 Concentration 2 + 1.0.

Reporting level 2 OR Radionuclides other than those in REMM Table 2.2.1-D are detected in an environmental sampling medium at a specified location which are the result of plant effluents and the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is the calendar year limits of DNC 13.1.2, DNC 13.2.2, DNC 13.2.3 Prepare and submit to the NRC, a Special Report, pursuant to DNC 15.3, that (1)

Identifies the cause(s) for exceeding the limit(s) and (2)

Defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of DNC 13.1.2, DNC 13.2.2, DNC 13.2.3 OR B.2

NOTES-------------

1. Only applicable if the radioactivity/radionuclides are not the result of plant effluents.

2. For radionuclides other than those in REMM Table 2.2.1-D, this report shall indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

Report and describe the condition in the Annual Radiological Environmental Operating Report.

30 days In accordance with the Annual Radiological Environmental Operating Report frequency.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-5 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. Broad leaf vegetation samples unavailable from one or more of the sample locations required by REMM Table 2.2.1-A.

C.1 Identify specific alternative locations for obtaining replacement samples and add them to the Radiological Environmental Operating Program.

AND C.2 When changes in sampling locations are permanent, then the sampling schedule in the REMM will be updated to reflect the new routine and alternative sampling locations. This revision will be submitted in the next Annual Radiological Environmental Operating Report.

30 days VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.1 Collect and analyze radiological environmental monitoring samples pursuant to the requirements of REMM Table 2.2.1-A and the detection capabilities required by Table 2.2.1-A.

In accordance with REMM Table 2.2.1-A

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-6 BASES The radiological environmental monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station decommissioning activities. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. Program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 2.3.1-A are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry, Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-7 RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS REMM 2.2.2 A land use census shall:

a.

Be conducted,

b.

Identify within a distance of 8 km (5 miles) the location, in each of the 10 meteorological sectors, of the nearest residence, and the nearest garden > 50 m2 (500 ft2) producing broad leaf vegetation. Sampling of broad leaf vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Requirements for broad leaf vegetation sampling in REMM Table 2.2.1-A item 4b shall be followed, including analysis of control samples.

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Land use census identifies location(s) that yields a calculated dose, dose commitment greater than the values currently being calculated in ODCM 13.2.3.1.

A.1 Identify the new location(s) in the next Radiological Environmental Operating Program.

In accordance with the Radiological Environmental Operating Report.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-8 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Land use census identifies location(s) that yields a calculated dose, or dose commitment (via the same exposure pathway) greater than 20% at a location from which samples are currently being obtained in accordance with REMM 2.2.1.

B.1 Add the new location(s) to the Radiological Environmental Operating Program.

AND B.2 Delete the sampling locations(s), excluding the control station location, having the lowest calculated dose, dose commitment(s) or D/Q value, via the same exposure pathway, from the Radiological Environmental Operating Program.

AND B.3 Submit in the next Radiological Environmental Operating Report documentation for a change which includes revised figures(s) and table(s) reflecting the new location(s) with information supporting the change in sampling locations.

30 days In accordance with Radiological Environmental Operating Report.

VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.2 Conduct the land use census during the growing season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities.

Report the results of the land use census in the Annual Radiological Environmental Operating.

12 months

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-9 BASES This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the door-to-door survey, from aerial survey or from consulting with local agricultural authorities. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via broad leaf vegetation will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of broad leaf vegetation assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:

1.

20% of the garden was used for growing broad leaf vegetation (e.g., similar to lettuce and cabbage), and

2.

A broad leaf vegetation yield of 2 kg/m2.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-10 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM REMM 2.2.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY:

At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A.

Analyses not performed as required.

A.1 Report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report.

In accordance with the Annual Radiological Environmental Operating Report.

VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.3 Report a summary of the results obtained as part of the Interlaboratory Comparison Program in the Annual Radiological Environmental Operating Report.

In accordance with the Annual Radiological Environmental Operating Report.

BASES The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 2-11 REMM 2.4.1 Reporting Requirements 2.4.1 The Annual Radiological Environmental Operating Report shall include:

a.

Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant decommissioning activities on the environment. The reports shall also include the results of land use censuses required by REMM 2.2.2.

b.

The results of analyses of radiological environmental samples and of environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the Radiological Environmental Monitoring Manual (REMM), as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report when applicable.

c.

A summary description of the radiological environmental monitoring program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by REMM 2.2.3; discussion of all deviations from the sampling schedule of Table 2.2.1-A; and discussion of all analyses in which the LLD required by Table 2.3.1-A was not achievable.

Discussion KPS TRM 10.3.1 provides the programmatic control, which requires that an Annual Radiological Environmental Operating Report be submitted to the NRC. It also states that this report shall include summaries, interpretations, and analysis of trends of the results of the REMP for the reporting period.

The procedural details of this report are included in this requirement. REMM 2.2.1/2.3.1, 2.2.2/2.3.2, and 2.2.3/2.3.3 also include specific reporting requirements. These requirements reference this REMM, along with TRM 10.3.1, as the method for reporting deviations from the current program during the reporting period, and require that this information be included in the Annual Radiological Environmental Operating Report.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 3-1 3.0 REMP Implementation The Radiological Environmental Monitoring Program for KPS is under the direction of a Contracted Vendor (CV). This section describes this program, as required by REMM 2.2.1 and the process the CV uses to perform it.

3.1 Sampling Requirements Table 2.2.1-A identifies the various samples required by the REMP. Identified in the available sample locations column in Table 2.2.1-A are the sample locations selected, in conjunction with the vendor, to meet or exceed the REMP requirements. Table 2.2.1-B includes the same requirements as in Table 2.2.1-A, but presents the information in a different format by identifying the type of samples required at each location and the collection frequency. Table 2.2.1-C identifies the location and description of each sample location. Figure 1 shows the physical location of each sample point on an area map.

3.2 Analysis Methodology Analytical procedures and counting methods employed by the CV will follow those recommended by the U.S. Public Health Service publication, Radioassay Procedures for Environmental Samples, January 1967; and the U.S. Atomic Energy Commission Health and Safety Laboratory, HASL Procedures Manual (HASL-300), 1972. The manual is also available on-line at www.eml.st.dhs.gov/publications/procman.

Updated copies shall be kept on file at KPS or can be obtained from the CV with sufficient notification.

3.3 Detection Capability (LLD) Requirements The required detection capabilities for environmental sample and analysis are tabulated in terms of lower limits of detection (LLDs) in Table 2.3.1-A. The LLDs required by Table 2.3.1-A are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry, Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 3-2 3.4 Contracted Vendor Reporting Requirements Monthly Progress Reports Monthly progress reports will include a tabulation of completed analytical data on samples obtained during the previous 30 day period. Included in the report are the status of field collections and graphic representations indicating possible trends. One copy of the reports will be submitted within 30 to 60 days of the reporting month. Monthly progress reports are reviewed for:

Reasonableness Consistency Accuracy Completeness Recognition of deficiencies Examination of any past deficiencies and corrective actions taken Recommendations for any modifications or improvements to the REMM Notify the vendor of any unusual or abnormal data noted during the review, including an evaluation of the applicability of REMM Specification 2.2.1.b.

The review shall include determination of the need to make notifications to State and Local Agencies due to levels of radioactive materials in water samples.

Annual Reports Annual reports will be submitted in two parts. Part I, to be submitted to the NRC, will be prepared in accordance with NRC Regulatory Guide 4.8. It will contain an introductory statement, a summary of results, description of the program, discussion of the results, and summary table. Part II of the annual report will include tables of analytical data for all samples collected during the reporting period, together with graphic presentation where trends are evident and statistical evaluation of the results. Gamma scan data will be complemented by figures of representative spectra if requested by KPS.

Non-Routine Reports If analyses of any samples collected show abnormally high levels of radioactivity, KPS will be notified by telephone immediately after data becomes available.

Action Limits The CV will report any radioactive concentrations found in the environmental samples which exceed the reporting levels shown in Table 2.2.1-D, CV to KPS column. These levels are set below the NRC required reporting levels (KPS to NRC column) so actions can be initiated to prevent exceeding the NRC concentration limits.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 3-3 3.5 Quality Assurance Program To ensure the validity of the data, the CV maintains a Quality Assurance (QA) Program, which employs quality control checks, with documentation of the analytical phase of its environmental monitoring studies. The program and procedures are defined in the CVs Quality Manual. The program shall be reviewed and meet the requirements of Regulatory Guide 4.15 and 10 CFR 20. All data related to quality control will be available for review by Kewaunee Solutions upon reasonable prior notification. Proprietary information will be identified so that it may be treated accordingly.

Updated copies of the Quality Manual shall be kept on file at KPS or can be obtained from the CV with sufficient notification.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 3-4 3.6 Sample Descriptions A description of each of the samples required by this program follows:

Ambient Radiation Two packets of thermo-luminescent dosimeters (CaSO4: Dy cards) are placed at fifteen locations as follows:

Four at the ISFSI fence as part of inner ring locations (K-1m, K-1o, K-1q, K-1r)

Four inner ring locations (K-1f, K-25, K-27, K-30)

Six outer ring locations (K-3, K-5, K-8, K-17, K-39, K-43)

One control location (K-2)

One packet is changed quarterly and one annually. Annual TLDs will serve as an emergency set to be read when needed. They will be exchanged annually (without reading) if not read during the year. To ensure the precision of the measurement, each packet will contain two cards with four dosimeters each (four sensitive areas each for a total of eight). For protection against moisture each set of cards is sealed in a plastic bag and placed in a plastic container.

Each card is individually calibrated for self-irradiation and light response. Fading is guaranteed by the TLD vendor not to exceed 20% in one year. Minimum sensitivity for the multi-area dosimeter is 0.5 mR defined as 3 times the standard deviation of the background. Maximum Error (1 standard deviation) - 60Co Gamma +/-0.2 mR or +/-3%, whichever is greater. The maximum spread between areas on the same dosimeter is 3.5% at 1 standard deviation.

Reporting units for TLDs are mR/91 days for quarterly TLDs and mR/exposure period for annual TLDs.

Tests for uniformity and reproducibility of TLDs as specified in NRC Regulatory Guide 4.13 are performed annually.

Airborne Particulates Airborne particulates are collected at four locations (K-1f, K-2(control), K-8, and K-43) on a continuous basis on a 47 mm diameter filter at a volumetric rate of approximately one cubic foot per minute (CFM). The filters are changed weekly, placed in protective envelopes, and delivered to the CV for Gamma Isotopic Analysis. Filter samples are analyzed weekly for gross beta activity after sufficient time (usually 3 to 5 days) has elapsed to allow decay of Radon and Thoron daughters. If gross beta concentrations in air particulate samples are greater than ten (10) times the yearly mean of the control samples, gamma isotopic analysis shall be performed on the individual samples. Quarterly composites from each location receive Gamma Isotopic Analysis using a Germanium detector. All identifiable gamma-emitters are quantified. Reporting units are pCi/m3.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 3-5 Surface Water Surface water is sampled quarterly from Lake Michigan at the KPS discharge (K-1d).

Samples are collected quarterly at the Green Bay Municipal Pumping station between Kewaunee and Green Bay (K-9) - both raw and treated water is collected.

Quarterly samples are also taken, when available, from creek locations (K-1b, K-1e) that pass through the reactor site. The samples are taken at a point near the mouth of each creek and at the shore of the drainage pond. The water is analyzed for gross beta activity in:

a.

The total residue,

b.

The dissolved solids, and

c.

The suspended solids.

The samples are also analyzed for K-40, Gamma Isotopic Analysis, tritium, and Sr-90. Reporting units are pCi/l.

Well Water One gallon of drinking water samples are taken once every three months from one off-site well, (K-13) and three on-site wells (K-1h, K-1t, and K-1u). All samples are analyzed for gross beta in the total residue, K-40, tritium, and by Gamma Isotopic Analysis. Samples from one on-site well are analyzed for Sr-90. Samples from K-1h, K-1t, and K-1u are also analyzed for gross alpha. Reporting units are pCi/l.

Shoreline Sediment Shoreline sediment samples are taken semi-annually from three locations (K-1c, K-1j, K-9) in areas with potential for recreational value. Samples are analyzed for gross beta, Sr-90 and Gamma Isotopic Analysis. Reporting units are pCi/g dry weight.

Fish Fish are collected once per year (third quarter) near the discharge area (K-1d). An alternate source for fish is a local fish market (e.g., LaFonds in Kewaunee). Flesh is separated from the bones and analyzed for gross beta activity and by Gamma Isotopic Analysis. The bones are analyzed for gross beta activity and Sr-90. Reporting units are pCi/g wet weight.

Vegetation Annually, during the 3rd quarter, samples of broad leaf vegetation grown and marketed for human consumption are collected from K-26 (control), depending upon the availability of samples. If samples are not available from this location, samples may be obtained from any local source so there is some sample of record. The location will be documented. In addition, two samples of broad leaf vegetation from the highest predicted X/Q and D/Q, if available, are collected annually from the farmland owned by Kewaunee Solutions (K-23 a and b) and rented to a private individual for growing crops. Reporting units are pCi/g wet weight.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 3-6 Soil Twice during the growing season samples of the top two inches of soil are collected from five locations (K-1f, K-3(control), K-34, K-35 (control), K-38). The soil is analyzed for gross alpha and gross beta activities, for Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting manmade radionuclides. Reporting units are pCi/g dry weight.

Cattle feed Once per year, during the first quarter when grass is not available, cattle feed (such as hay or silage) is collected from the five dairy farms (K-3 (control), K-34, K-35 (control), K-38, K-45). The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

Grass Grass is collected three times per year (2nd, 3rd, and 4th quarters) from the six dairy farms (K-3(control), K-5, K-35 (control), K-34, K-38, and K-39) and from two on-site locations (K-1b and K-1f). The samples are analyzed for gross beta activity, for Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Groundwater Monitoring Wells The Groundwater Protection Program (RP-KW-502, Groundwater Protection Program) consists of 14 wells. Figure 2 shows the locations of the 14 installed groundwater monitoring wells. The wells and locations are identified with a diamond shape in Figure 2. The wells are labeled MW (Monitoring Well) and AB (Auxiliary Building).

Results of analyses and a description of any event above Reporting Levels will be included in the Annual Radioactive Effluent Release Report for the 14 wells.

Any results exceeding the limits of Table 2.2.1-D shall be reported in accordance with section 2.2.1-B of the REMM, as well as:

Informal notification to the State and Local Agencies before the end of the next business day.

Providing a copy of the written 30 day NRC report to State and Local Agencies.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 1 of 3 Table 2.2.1-A Radiological Environmental Monitoring Program Exposure Pathway And/Or Sample Minimum Required Samples a Available Sample Locations b

Sampling, Collection and Analysis Frequency Type of Analysis

1.

Ambient Radiationc 8 Inner Ring locations K-1f, K-1m, K-1o, K-1q, K-1r, K-25, K-27, K-30, See Table 2.2.1-B Gamma dose 6 Outer Ring locations K-3, K-5, K-8, K-17, K-39, K-43 1 Control location K-2 1 Population center K-43 1 Special interest location K-8 1 Nearby resident K-27

2.

Airborne Particulates 3 samples close to the site boundary in highest average X/Q K-1f, K-8, K-43 See Table 2.2.1.B Continuous sampler operation 1 sample from the closest community having the highest X/Q K-43 Particulates See Table 2.2.1-B Particulates; gross beta analysise Gamma isotopicf of composite (by location) 1 sample from a control location K-2d See Table 2.2.1-B

3.

Waterborne

a.

Surfaceg 1 Upstream sample 1 Downstream sample K-1b, K-1d K-1e, K-9J Grab sample See Table 2.2.1-B Gross Beta, Gamma isotopicf K-40 tritium, and Sr-90 i

b.

Well 1-2 locations likely to be affected d 1 off-site location K-1h, K-1th, K-1uh K-13 Grab sample See Table 2.2.1-B Gamma isotopicf, tritium and K-40 analysis Gross Beta, One onsite well for Sr-90 3 onsite wells for gross alpha

c.

Shoreline Sediment 1 sample from downstream area with potential for recreational value K-1c, K-1j, K-9 Grab sample See Table 2.2.1-B Gamma isotopic f analysis Gross Beta, Sr-90

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 2 of 3 Table 2.2.1-A Radiological Environmental Monitoring Program Exposure Pathway And/Or Sample Minimum Required Samples a Available Sample Locations b

Sampling, Collection and Analysis Frequency Type of Analysis

4.

Ingestion

a.

Fish 1 random sample of commercially and recreationally important species in the vicinity of the plant.

K-1d See Table 2.2.1-B Gamma Isotopicf and Gross Beta on edible portions, Gross Beta and Sr-90 on bones

b.

Food Products Two samples of broad leaf vegetation grown nearest each of two different offsite locations within 5 miles of the plant since milk sampling is no longer performed.k 1 sample 15-30 km distant since milk sampling is no longer performed.

K-23a, K-23b K-26 (control)

See Table 2.2.1-B Gamma Isotopicf Analysis.

5.

Miscellaneous samples not identified in NUREG-0472k

a.

Soil None required K-1f, K-34, K-35 (control)

K-38 Gross Alpha/Beta K-3 (control)

See Table 2.2.1-B Sr-90 Gamma Isotopicf

b.

Cattle feed None required K-35 (control)

Gross Beta K-34, K-38, K-45 See Table 2.2.1-B Sr-90 K-3 (control)

Gamma Isotopicf

c.

Grass None required K-1b, K-1f, K-35 (control), K-39 Gross Beta K-5, K-34, K-38 See Table 2.2.1-B Sr-90 K-3 (control)

Gamma Isotopicf

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 3 of 3 Table Notations for Table 2.2.1-A

a.

The samples listed in this column describe the minimum sampling required to meet REMP requirements.

b.

Additional details of sample locations are provided in Table 2.2.1-C and Figure 1. The REMP requires that samples be taken from each of the available sample locations listed (see section 3.1). Deviations from the required sampling schedule will occur 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 malfunction, reasonable efforts shall be made to complete corrective actions prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented, as required by REMM 2.4.1.c, in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the REMM. The cause of the unavailability of samples for that pathway and the new location(s) for obtaining replacement samples will be identified in the Annual Radiological Environmental Operating Report.

c.

For the purposes of this table, each location will have 2 packets of thermoluminescent dosimeters (TLDs). The TLDs are CaSO4: Dy cards with 2 cards/packet and 4 dosimeters/card (four sensitive areas each for a total of eight dosimeters/packet). The NRC guidance of 40 stations is not an absolute number. The number of direct radiation monitoring stations has been reduced according to geographical limitations; e.g., Lake Michigan. The frequency of analysis or readout for TLD systems depends upon the characteristics of the specific system used and selection is made to obtain optimum dose information with minimal fading.

d.

The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

e.

Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

f.

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

g.

The upstream sample shall be taken at a distance beyond significant influence of the discharge. The downstream sample shall be taken in an area near the mixing zone.

h.

Well water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

i.

In the event elevated analyses are reported by CV for gamma isotopic or tritium, a review will be conducted with the option to retest additional analysis for hard to detect isotopes or alpha emitters. The additional test may include Fe-55, Ni-63, or alpha emitters anticipated on current plant conditions.

j.

Two samples to be collected, Raw and Treated

k.

See Regulatory Guide 4.1, Revision 2. Broad leaf vegetation, as well as grass, soil, and cattle feed, are a sufficient substitute if milk samples are not performed.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 1 of 2 Table 2.2.1-B Type and Frequency of Collection Location Weekly Monthly Quarterly Semi-Annually Annually K-1b SW GRa K-1c SSb K-1d SW FIc K-1e SW K-1f APg GRa TLD SO K-1h WW K-1j SSb K-1m TLD K-1o TLD K-1q TLD K-1r TLD K-1t WW K-1u WW K-2 APg TLD K-3 GRa TLD SO CFd K-5 GRa TLD K-8 APg TLD K-9 SWf SSb K-13 WW K-17 TLD K-23a BLVe K-23b BLVe K-25 TLD K-26 BLVe K-27 TLD K-30 TLD K-34 GRa SO CFd K-35 GRa SO CFd K-38 GRa SO CFd K-39 GRa TLD K-43 APg TLD K-45 CFd

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 2 of 2 Table Notations for Table 2.2.1-B

a.

Three times a year, second (April, May, June), third (July, August, September), and fourth (October, November, December) quarters

b.

To be collected in May and November

c.

Annually in third quarter (July, August, or September)

d.

First (January, February, March) quarter only

e.

Alternate since milk sampling is no longer performed

f.

Two samples, raw and treated

g.

The frequency may be increased dependent on the dust loading.

Code Description Code Description Code Description AP Airborne Particulate GR Grass SW Surface Water CF Cattle feed SO Soil WW Well Water FI BLV Fish Broad Leaf Vegetation SS TLD Shoreline Sediment Thermo-luminescent Dosimeter

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 1 of 3 Table 2.2.1-C Sampling Locations, Kewaunee Power Station Code Typea Distance (Miles)b and Sector Location K-1 Onsite - generic code K-1b I

0.12 N Middle Creek 87328.62W 442044.80N K-1c I

0.10 N 500 North of Condenser Discharge 87324.21W 442039.76N K-1d I

0.10 E Condenser Discharge 87321.87W 442032.71N K-1e I

0.12 S South Creek 87325.03W 442025.04N K-1f I

0.12 S Maintenance Waste Oil and Material Storage Building 873214W 442126N K-1h I

0.12 NW North Well 873218.05W 442039.15N K-1j I

0.10 S 500 south of Condenser Discharge 873158.75W 442029.33N K-1m I

0.15 N ISFSI East 87328.78W 442037.13N K-1o I

0.16 N ISFSI North 87329.19W 442040.11N K-1q I

0.16 N ISFSI West 873213.41W 442039.86N K-1r I

0.13 N ISFSI West 873214.25W 442039.09N K-1t I

0.10 ESE Gatehouse 87324.47W 442030.79N K-1u I

0.05 SSW Maintenance Building 873321W 442119N K-2 C

8.91 NNE WPS Operations Building in Kewaunee 872959.62W 442825.49N K-3f I/C 5.9 N Lyle and John Siegmund Farm, N2815 Hwy 42, Kewaunee 873235.98W 442539.21N K-5 I

3.2 NNW Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee 873347.10W 44232.83N

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 2 of 3 Table 2.2.1-C Sampling Locations, Kewaunee Power Station Code Typea Distance (Miles)b and Sector Location K-8 I

4.85 WSW Saint Isadore the Farmer Church, 18424 Tisch Mills Rd, Tisch Mills 873750.85W 441918.48N K-9 C

11.5 NNE Green Bay Municipal Pumping Station, six miles east of Green Bay (sample source is Lake Michigan from Rostok Intake 2 miles north of Kewaunee) 874616.94W 442916.55 K-13 C

3.0 SSW Rands General Store, Two Creeks 873348.23W 44188.69N K-17 I

4.0 W Klimeshs Farm, N885 Cty Tk B, Kewaunee 873647.52W 442121.62N K-23a I

0.5 W 0.5 miles west of plant, Kewaunee site 87323.38W 442112.12N K-23b I

0.6N 0.6 miles north of plant, Kewaunee site 873243.93W 442032.36N K-25 I

1.9 SW Wotachek Farm, E3968 Cty Tk BB, Two Rivers 873410.67W 441938.81N K-26c C

9.1 SSW Wilferts Vegetable Stand 7528 Manitou Dr., Two Rivers 87393.75W 441121.60N K-27 I

1.53 NW Schleis Farm, E4298 Sandy Bay Rd 87336.93W 442122.96N K-30 I

0.8 N End of site boundary 87322.61W 442112.86N K-34 I

2.7 N Leon & Vicky Struck Farm, N1549 Lakeshore Dr, Kewaunee 873114.33W 442248.13N K-35d C

6.71 WNW Duane Ducat Farm, N1215 Sleepy Hollow, Kewaunee 87401.53W 442210.90N K-38 I

2.45 WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee 873456.92W 442122.64N K-39 I

3.46 N Francis Wotja Farm, N1859 Lakeshore Road, Kewaunee 873114.28W 442328.25N K-43e I

2.71 SSW Gary Maigatter Property, 17333 Highway 42, Two Rivers 873342.99W 441826.63N K-45 I

5.1 N Wakkers Dairy, N2348 Highway 42, Kewaunee 873229.76W 442432.5N

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 3 of 3 Table Notations for Table 2.2.1-C

a. I = indicator; C = control.

b. Distances are measured from reactor stack.

c. Location K-18 was changed because Schmidts Food Stand went out of business. It was replaced by Bertlers Fruit Stand (K-26). It was replaced with Sandys Vegetable in 2007.

The location as of 2009 is Wilferts Vegetable Stand.

d. Removed from the program in fall of 2001, back to program in August 2008.

e. K-7 moved to a nearby location and relabeled K-43, within 0.2 miles of original, August/September 2010.

f. Location K-3 is an indicator for ambient radiation and a control for soil, cattle feed, and grass.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 1 of 1 Table 2.2.1-D Reporting Levels for Radioactivity Concentrations in Environmental Samples Medium Radionuclide Reporting Levels CV to KPSa KPS to NRCb Airborne Particulate (pCi/m3)

Gross Beta 1

Cs-134 1

10 Cs-137 1

20 Water (pCi/l)

Gross Alpha 10 Gross Beta 30 H-3 10,000 20,000c Mn-54 100 1,000 Co-60 30 300 Cs-134 10 30 Cs-137 20 50 Sr-90 8d Grass, Cattle Feed, and Broad Leaf Vegetation (pCi/g wet)

Gross Beta 30 Cs-134 0.2 1

Cs-137 0.2 2

Sr-90 1

Soil, Shoreline Sediments (pCi/g)

Gross Beta 50 Cs-134 5

Cs-137 5

Sr-90 5

Fish (pCi/g wet)

Gross Beta (Flesh, Bones) 10 Mn-54 30.0 Co-60 10.0 Cs-134 (Flesh) 1 1.0 Cs-137 (Flesh) 2 2.0 Sr-90 (Bones) 2

a.

Radionuclides will be monitored by the CV and concentrations above the listed limits will be reported to KPS.

b.

Concentrations above the listed limits will be reported to NRC as required by REMM 2.2.1.b.

c.

For drinking water samples, this is 40 CFR Part 141 value. If no drinking water pathway exists, then a value of 30,000 pCi/l may be used.

d.

The Sr-90 values are based on the EPA drinking water standards. See note e of Table 2.3.1-A for further information

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 1 of 3 Table 2.3.1-A Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD) b,c Analysis Water (pCi/l)

Airborne Particulate (pCi/m3)

Fish (pCi/kg, wet)

Food Products (pCi/kg, wet)

Sediment (pCi/kg, dry)

Gross Beta 4

0.01 H-3 2000d Mn-54 15 130 Co-60 15 130 Cs-134 15 0.05 130 60 150 Cs-137 18 0.06 150 80 180 Sr-90e 5

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 2 of 3 Table Notations for Table 2.3.1-A

a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environment Operating Report.

b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

c. The LLD is defined, for purposes of these requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal.

For a particular measurement system, which may include radiochemical separation:

Where:

LLD is the a priori lower limit of detection as defined above, as picocuries per unit mass or

volume, Sb is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, is the radioactive decay constant for the particular radionuclide, and t for environmental samples is the 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 calculation.

4.66sb LLD =--------------

E X

V X

2.22 X

Y x

e - All t

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 3 of 3 Table Notations for Table 2.3.1-A (con't)

It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

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

e. This is NOT a NUREG-0472 required value. It is based on EPA drinking water standards, which tie into the NEI Groundwater Protection Initiative that was implemented at KPS on August 4, 2006.

Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

Revision 24 Page 1 of 1 Figure 1 F IG E l EN'I' ON.\\iENT AL S,lt~ U,

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Kewaunee Solutions Kewaunee Power Station REMM Radiological Environmental Monitoring Manual (REMM)

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KS-2023-012 Kewaunee Power Station, N490 Highway 42, Kewaunee, WI 54216 ATTACHMENT 4 Kewaunee Solutions Radwaste Process Control Program, Revision 0 (8 Pages)

Kewaunee Solutions Radwaste Process Control Program Program No. KS-WM-PG-002 Revision No. 0 Level of Use: R (Review procedure before use, refer to it during use as needed)

Preparer (Print Name/Sign)

Date:

Reviewer (Print Name/Sign)

Date:

Licensing Manager or designee has established required program & regulatory reviews:

SIGNATURE___________________________DATE: ____________ (*new procedures only*)

Responsible Manager or designee has reviewed and determined training impact and required actions:

Hold for Training?

YES NO SIGNATURE__________________________DATE: ____________

Regulatory Required Reviews (attach completed review forms as applicable)

Part 50 License:

10 CFR 50.59 YES NO Conditions of License:

PSP: 10 CFR 50.54(p)

YES NO Part 72 License:

10 CFR 72.48 YES NO Conditions of License:

E-Plan: 10 CFR 50.54(q)

YES NO Fire Protection:

10 CFR 50.48(f)

YES NO Termination of License:

10 CFR 50.82(a)(6) and 50.82(a)(7)

YES NO Program Required Reviews RP:

YES SIGNATURE___________________________________DATE: ____________

NO QA:

YES NO SIGNATURE___________________________________DATE: ____________

PORC:

YES NO ISR:

YES NO PORC CHAIRMAN SIGNATURE___________________________________DATE: ____________

Approval Section RESPONSIBLE SIGNATURE___________________________________DATE: ____________

MANAGER:

Effective Date: 11/07/22 (assigned by Document Control or Responsible Manager)

James A. Miller Digitally signed by James A.

Miller Date: 2022.04.01 12:12:14 -04'00' James A. Miller Digitally signed by James A. Miller Date: 2022.04.01 12:13:03 -04'00' David Villicana Digitally signed by David Villicana Date: 2022.04.01 11:27:00 -05'00' G A Bergeron Digitally signed by G A Bergeron Date: 2022.04.01 12:52:11 -04'00' Joseph R. Lynch Digitally signed by Joseph R.

Lynch Date: 2022.04.01 13:26:05 -04'00' Amanda Wood Digitally signed by Amanda Wood Date: 2022.04.18 14:40:40 -04'00' Frank Coon Digitally signed by Frank Coon Date: 2022.04.20 08:39:11 -05'00'

~

KEWAUNEE SOLUTIONS

~

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 RECORD OF REVISIONS Revision Revision Title Description and Reason for Change 0

Initial issue. New Kewaunee Solutions procedure.

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 Table of Contents 1

PURPOSE AND SCOPE..................................................................................................... 4 1.1 Purpose...................................................................................................................... 4 1.2 Scope.......................................................................................................................... 4 2

REFERENCES..................................................................................................................... 4 2.1 Procedures................................................................................................................ 4 2.2 Other References...................................................................................................... 4 3

GENERAL............................................................................................................................ 5 3.1 Definitions................................................................................................................. 5 3.2 Responsibilities......................................................................................................... 5 3.3 Precautions and Limitations................................................................................... 5 3.4 Records...................................................................................................................... 5 4

REQUIREMENTS AND GUIDANCE.............................................................................. 6 4.1 General Instructions................................................................................................ 6 4.2 Administrative Controls.......................................................................................... 7 5

ATTACHMENTS AND FORMS....................................................................................... 8

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 1

PURPOSE AND SCOPE 1.1 Purpose 1.1.1 The purpose of this document is to establish a Process Control Program (PCP) that ensures processing and packaging of solid radioactive waste resulting from treatment of gaseous and liquid effluents and from other sources that is compliant with:

A. Applicable federal and state regulations (Refs. 2.2.1 through 2.2.6)

B. Disposal site requirements (Refs. 2.2.10 and 2.2.11)

C. Other requirements governing the disposal of radioactive waste (Refs. 2.2.1 through 2.2.9) 1.2 Scope 1.2.1 The scope of this document applies to all personnel performing activities associated with the processing and packaging of solid radioactive waste.

2 REFERENCES 2.1 Procedures 2.1.1 KS-AD-PR-001, Kewaunee Solutions Procedure Control 2.1.2 KS-AD-PR-004, Kewaunee Solutions Document Control 2.1.3 KS-QA-PG-001, Kewaunee Solutions Decommissioning Quality Assurance Program (DQAP) 2.1.4 RP-KW-HSP-HPE-280, Annual Effluent and Environmental Report Review and Submittal 2.1.5 KS-WM-PG-001, Kewaunee Solutions Waste Management Program 2.1.6 KS-WM1-PR-012, Kewaunee Solutions Packaging Solid Radioactive Waste 2.1.7 KS-AD-PR-006, Kewaunee Solutions Records 2.1.8 KS-QA-PN-001, Kewaunee Solutions QA Program Implementation 2.2 Other References 2.2.1 10 Code of Federal Regulations (CFR) Part 20, Standards for Protection Against Radiation 2.2.2 10 CFR Part 50, Appendix A, General Design Criteria 60, Control of Releases of Radioactive Material to the Environment 2.2.3 10 CFR Part 50.36a, Technical Specifications on Effluents from Nuclear Power Reactors 2.2.4 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 2.2.5 10 CFR Part 71, Packaging and Transportation of Radioactive Materials 2.2.6 49 CFR, Transportation 2.2.7 Decommissioning Safety Analysis Report (DSAR) for the Kewaunee Power Station 2.2.8 Nuclear Regulatory Report (NUREG) 1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, U.S. Nuclear Regulatory Commission, April 1991 2.2.9 Nuclear Regulatory Commission (NRC) Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications and the Relocation of Procedural Details of RETs to the Offsite Dose Calculation Manual or to the Process Control Program, January 31, 1989 2.2.10 USNRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Form, Rev. 1, January 1991 2.2.11 EnergySolutions, Utah Department of Environmental Quality, Division of Radiation Control, Radioactive Material License, License Number UT 2300249 3

GENERAL 3.1 Definitions None 3.2 Responsibilities 3.2.1 The Waste Manager has overall responsibility for solid radioactive waste activities at Kewaunee Power Station (KPS).

3.2.2 Kewaunee Solutions (KS) subcontractors have the role and associated responsibilities of a vendor in accordance with this procedure.

3.2.3 KS Radiation Protection Manager has the responsibility of the Radiation Protection Program (RPM).

3.3 Precautions and Limitations 3.3.1 Verify level of use requirements on the first page of the document in accordance with KS-AD-PR-001 (Ref. 2.1.1). Verify current revision in accordance with KS-AD-PR-004 (Ref 2.1.2).

3.4 Records 3.4.1 All Waste Management records will be maintained in accordance with KS-WM-PG-001 (Ref. 2.1.5).

3.4.2 Records generated from the use of this procedure shall be processed in accordance with KS-AD-PR-006 (Ref. 2.1.7).

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 4

REQUIREMENTS AND GUIDANCE 4.1 General Instructions 4.1.1 Wet Waste A. Process liquid wet waste in accordance with:

1. Specific site procedures that provide sufficient instructions for safe and efficient processing, immobilizing and, stabilizing of wet wastes in accordance with KS-WM1-PR-012 (Ref. 2.1.6).

2. Shipment and disposal requirements that meet the criteria on Free Standing Water (FSW) in accordance with USNRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Form (Ref. 2.2.10) and EnergySolutions, Utah Department of Environmental Quality, Division of Radiation Control, Radioactive Material License (Ref. 2.2.11).

3. Approved procedures that contain provisions for correcting processed waste in which FSW is detected in excess of FSW limits and criteria.

B. Ensure vendor procedures are approved by the KS Radiological Protection Manager (RPM) and Waste Manager prior to use.

4.1.2 Solidification A. Qualified vendors shall supply solidification Process Control Programs (PCPs), procedures, and topical reports to the KS RPM for approval.

B. These documents should include:

1.

Process description 2.

Solidification media used 3.

Process control parameters 4.

Parameter boundary conditions 5.

Waste form properties 6.

Specific instructions to ensure systems are operated within process parameters 7.

Pre-solidification laboratory sample mixing criteria 8.

Sampling frequency and acceptance criteria 9.

Exothermic reaction process control parameters C. Solidification vendor documentation shall include provisions to verify FSW criteria are met for the specific waste type being solidified.

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 D. The vendor supplied PCP shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 (Refs. 2.2.1, 2.2.4, 2.2.5), State regulations, burial site requirements, and other requirements governing the disposal of solid radioactive waste.

4.1.3 Containers, Shipping Casks, and Packaging A. Solid radioactive waste is processed, packaged, and shipped in accordance with approved site procedures.

B. Procedures provide specific instructions that ensure compliance with applicable federal, state, and burial site requirements.

4.1.4 Shipping and Disposal Prepare, load, and ship solid radioactive waste in accordance with specific site procedures to meet federal, state, and burial site requirements.

4.1.5 Oily/Mixed Wastes Radioactive wastes containing oil or hazardous substances are processed in accordance with approved site procedures to ensure compliance with applicable requirements.

4.1.6 Special Cases A. Unique wastes may require special techniques or processes. Process special case waste in accordance with specific site procedures to meet applicable requirements.

B. Implementing procedures are reviewed and approved by the Waste Manager.

C. Special processes developed under this provision should be documented as a change to the PCP per Section 4.2.2 of this procedure.

4.2 Administrative Controls 4.2.1 Quality Assurance A. Quality Assurance shall be implemented in a graded approach as described in KS-QA-PG-001 (Ref. 2.1.3).

B. Waste Management will perform periodic assessments of this PCP to verify compliance with the specified aspects of this procedure.

KS-WM-PG-002 Kewaunee Solutions Radwaste Process Control Program Revision 0 4.2.2 Changes to the Process Control Programs (PCPs)

A. Licensee-initiated changes to the PCP:

1. Should be documented, and records of reviews be retained in accordance with KS-QA-PN-001 (Ref. 2.1.8). This documentation should contain:

i. Sufficient information to support the change(s), together with the appropriate analyses or evaluations justifying the change(s),

ii. A determination that the change(s) will maintain the overall conformance of the solidified waste product to the existing requirements of federal, state, and other applicable regulations, and iii. Documentation that the change has been reviewed and found acceptable through execution of the applicable regulatory review process for the project.

2. Changes made to the PCP should be communicated to the Radiation Protection, Chemistry, and Environmental Managers for inclusion in the Annual Radioactive Effluent Release Report in accordance with RP-KW-HSP-HPE-280 (Ref. 2.1.4).

5 ATTACHMENTS AND FORMS None

ML23116A218

Text

Subject:

SUMMARY

1.0 INTRODUCTION

11.0 INTRODUCTION

11.0 INTRODUCTION

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