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Annual Radioactive Effluent Release Report
	ML13130A005
Person / Time
Site:	Kewaunee
Issue date:	04/05/2013
From:	Stafford J; Dominion Energy Kewaunee, Dominion
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	13-171
	Download: ML13130A005 (311)
	v • d • e

Dominion Energy Kewaunee, Inc.

N490 Hwy 42, Kewaunee, WI 54216 ~Dominioni Web Address: www.dorn.com APR 0 5 2013 ATTN: Document Control Desk Serial No.13-171 U. S. Nuclear Regulatory Commission LIC/NW/RO Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION 2012 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Kewaunee Power Station (KPS) 2012 Annual Radioactive Effluent Release Report for January through December 2012. This report is submitted to meet the requirements of KPS Technical Specification 5.6.2 and 10 CFR 50.36a(a)(2).

If you have questions or require additional information, please feel free to contact Mr.

Richard Repshas at 920-388-8217.

Very truly yours, Jeffrey T. Stafford Director Safety and Licensing, Kewaunee Power Station Commitments made by this letter: NONE ta 44

Serial No.13-171 Page 2 of 2 cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. K. D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D15 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station Mr. W. A. Nestel Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339 Mr. Don Hendrikse WI Division of Public Health Radiation Protection Section Room 150 Madison, WI 53701-2659 Ms. Deborah Russo American Nuclear Insurers 95 Glastonbury Blvd.

Glastonbury, CT 06033

%7 Dominion 2012 Annual Raioacuvq.

Effluent Release Report Kewaunee Poweý, t,.4tw j,,.

Dominion Energy Kewaunec, h'i.

DOCKET 50-305 KEWAUNEE NUCLEAR POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January I - December 31, 2012 Dominion Energy Kewaunee, Inc.

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Table of Contents Section Description 0 .0 Sum m ary .................................................................................................... .. 3 1.0 Introduction .................................................................................................. . .3 1.1 E ffl uent D ose ............................................................................................... 3 2.0 G aseous Effl uents ........................................................................................ 4 2.1 Lower Limits of Detection (LLD) for Gaseous Effluents .............................. 4 2.2 Gaseous Batch Release Statistics .................................................................. 6 2.3 Gaseous Effluent Data ................................................................................. 6 Table 2.1 Gaseous Effluents - Summation of all Releases ........................... 7 Table 2.2 Gaseous Effluents ................................................................. 8 Table 2.3A Gaseous Release Total ............................................................. 10 Table 2.3B Gaseous Release Continuous .................................................... 18 Table 2.3C Gaseous Release Batch ............................................................. 26 Table 2.4 Dose From Gaseous Effluents .................................................... 34 2.4 Estimation of Carbon-14 in Gaseous Releases ................................. 35 3.0 Liquid Effl uents ........................................................................................... 36 3.1 Lower Limits of Detection (LLD) for. Liquid Effluents .............................. 36 3.2 Liquid Batch Release Statistics ........................................................................ 38 3.3 Liquid Effl uent Data .................................................................................... 38 Table 3.1 Liquid Effluents - Summation of all Releases ........................... 39 Table 3.2A Liquid Effluents - Batch Releases 1st Quarter ......................... 40 Table 3.2B Liquid Effluents - Batch Releases 2nd Quarter ........................ 42 Table 3.2C Liquid Effluents - Batch Releases 3rd Quarter ........................ 44 Table 3.2D Liquid Effluents - Batch Releases 4th Quarter ........................ 46 Table 3.3A Liquid Effluents - Continuous Releases 1st Quarter ................. 48 Table 3.3B Liquid Effluents - Continuous Releases 2nd Quarter .............. 50 Table 3.3C Liquid Effluents - Continuous Releases 3rd Quarter ............... 52 Table 3.3D Liquid Effluents - Continuous Releases 4th Quarter ............... 54 Table 3.4 Dose From Liquid Effluents ...................................................... 56 3.4 Ground Water Monitoring .......................................................................... 58 4.0 U nplanned Releases .................................................................................... 58 5.0 Meteorological Data ................................................................................... 60 6.0 Solid W aste Disposal ................................................................................. 60 "Table 6.1 Solid Waste and Irradiated Fuel Shipments ................................ 61 7.0 Program R evisions ...................................................................................... 63 8.0 Reportable O ccurrences ............................................................................... 63 Appendix A Meteorological Data Appendix B KPS Offsite Dose Calculation Manual (ODCM), Rev. 14 Appendix C KPS Radiological Environemntal Monitoring manual (REMM), Rev. 19 Page 2 of 63

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0.0

SUMMARY

During 2012 all solid, liquid, and gaseous radioactive effluents from the Kewaunee Power Station were well below regulatory limits. For individual effluent streams, the quarterly limit most closely approached was:

GASEOUS: Ingestion Pathway-Organ TBody Quarterly Limit (mRems) 7.5 Actual Dose (mRems) 5.766E-04 (Id Quarter)

% of Specification 7.688E-03 LIQUID: Ingestion Pathway-Organ Bone Quarterly Limit (mRems) 5.0 Actual Dose (mRems) 1.729E-02 (2nd Quarter)

% of Limit 3.458E-01 SOLID: No upper limit for solid radioactive waste applies.

Cubic Meters Shipped 4.68E+01 m 3 (1.65E+03 ft3 )

1.0 INTRODUCTION

This report is being submitted in accordance with the requirements of Kewaunee Technical Specifications, Section 5.6.2 and the Offsite Dose Calculation Manual, Section 15.2. It includes data from all effluent releases made from January 1 - December 31, 2012. 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, revisions to the Process Control Program and the Offsite Dose Calculation Manual, and addresses the cumulative meteorological data.

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 operation of the Kewaunee Power Station.

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

1.) The calculation of radioactive liquid and gaseous 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 3 of 63

I 2.0 GASEOUS EFFLUENTS I 2.1 Lower Limits of Detection (LLD) for Gaseous Effluents I

Gaseous radioactive effluents are released in both the continuous mode and the batch mode.. The auxiliary building stack is sampled continuously for particulates, halogens and Strontium by an "off-I line" sample train. This stack is also grab-sampled weekly for gaseous gamma emitters. Batch releases are sampled prior to release for principal gaseous and particulate gamma emitters, halogens and tritium. I The LLD's for gaseous radioanalyses, as listed in Table 13.2. 1-1 of the Kewaunee ODCM are:

Analysis LLD (ýtCi/ml) I Gaseous Gamma Emitters Iodine 131 1.OOE-04 3.OOE-12 I Particulate Gamma Emitters Particulate Gross Alpha I.OOE- I1 1.OOE- 11 I Strontium 89, 90 1.OOE- I 1 Noble Gases, Gross Beta or Gamma 1.00E-06 I

The nominal "a priori" LLD values are shown below.

I Isotope a priori LLD (utCi/ml)

a. Gaseous emissions:

I Kr-87 Kr-88 5.61E-08 1.02E-07 I

Xe-133 6.68E-08 Xe-133m.,

Xe-135 2.75E-07 2.99E-08 I

Xe-138 1.13 E-07 I

Page 4 of 63 I

b. Particulate emissions:

Mn-54 1.11 E- 13 Fe-59 2.27E-13 Co-58 2.28E-13 Co-60 3.57E-13 Zn-65 1.68E-13 Mo-99 2.73E- 13

.Cs- 134 4.69E-13 Cs-137- 1.68E-13 Ce- 141 2.08E-13 Ce- 144 1.24E- 12

c. Other identifiable gamma emitters:

Ar-41 3.97E-10 Kr-85 8.63E-05.

Kr-85m 4.62E-08.

Kr-89 2.04E-06 Xe-127 4.201-08 Xe-131m 1.82E-06 Xe-135m 1.90E-08 Xe-137 2.88E-07 1-131 1.32E-13

d. Composite particulate samples:

Sr-89 1.00E-14 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 5 of 63

2.2 Gaseous Batch Release Statistics The following is a summation of all gaseous batch releases made during 2012.

Number of batch releases .................................. 43 Total time for all batch releases (min) ............... 3534.0 Maximum time for a batch release (min) ........... 1440.0 Average time for a batch release (min) ................... 82.2 Minimum time for a batch release .(min).................. 15.0 2.3 Gaseous Effluent Data The following table 2.1 presents a quarterly summation of the total activity released and average release rates of four categories of gaseous effluents. Table 2.2 lists the quarterly sums of individual gaseous radionuclides released by continuous and batch modes.: Table 2.3 is essentially. the same data, but is presented as monthly summations. Table 2.4 presents the dose limits for gaseous effluents, and the calculated doses this year from gaseous effluents.

. . .3' ) . . -!*

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Table 2.1 Annual Radioactive Effluent Release Report 2012 Gaseous Effluents - Summation of all Releases Carbon- 14 Total Annual Activity Released (Ci) 6.290E+00 Fission and Activation Gases 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Activity Released (Ci) 0.000E+00 5.162E-02 O.OOOE+00 * .OOOEO00 Average Release Rate (ViCi/sec) O.OOOE+00 6.566E-03 0.000E+00 0.OOOE+/-OO lodines .

0.OOOE+00 Total Activity Released (Ci) .:. 0.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+/-OO Average Release Rate (ptCi/sec) 0.0013+O00 ,,'0.OOOE+00 0.OOOE+0O Particulates Total Activity Released (Ci) 0.OOOE+00 7.060E-07 0.OOOE+00 0.OOOE+0O Average Release Rate (pCi/sec) O.OOOE+00 8.979E-08 0.OOOE+0O 0.OOOE+OO Gross Alpha Released (Ci) O.OOOE+00 1.139E-05 O.OOOE+00 0.OOOE+/-00 Tritium Total Activity Released (Ci) 2.900E+00 3.732E+01 1.623E+01 9.08 1E+00 Average Release Rate (fiCi/sec) 3.689E-0 I 4.747E+00 2.064E+00 1.155E+00 Page 7 of 63

I Table 2.2 Annual Radioactive Effluent Release Report 2012 I

Gaseous Effluents I

Nuclides Released (Ci)

Continuous Mode I

I st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases I

Total O.OOOE+O0 O.OOOE+O0 O.OOOE+O0 O.OOOE+00 I lodines Total O.OOOE+O0 O.OOOE+00 O.OOOE-O0 0.000E+00 I

Particulates Co-58 O.OooE+O0 7.060E-07 O.OOOE+00 O.OOOE+O0 I

Total O.OOOE+O0 7.060E-07 O.OOOE+00 0.0001E+00 I

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Table 2.2(cont)

Annual Radioactive Effluent Release Report 2012 Gaseous Effluents Nuclides Released (Ci)

Batch Mode Fission Gases Xe-133 O.OOOE+O0 5.103E-02 O.OOOE+00 O.OOOE+O0 Xe-133m O.OOOE+O0 4.527E-04 O.OOOE+00 0.00013+/-00 Xe-135 O.OOOE+O0 1.446E-04 O.OOOE+00 O.OOOE+00 Total O.O001EO0 5.162E-02 0.600E+00 O.OOOE+O0ý Iodines Total O.OOOE+O0 0.000E+00 O.O00OD-OO O.OOOE+00 Particulates Total 0.OOOE+/-00 0.00O13+00 O.OOOE+00 0.OOOE+00 Page 9 of 63

Table 2.3A Annual Radioactive Effluent Release Report 2012 1st Quarter Gaseous Release Total of all Releases Noble Gasses (Curies)

Isotope January February March Total Total 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Particulates (Curies)

Isotope January February March Total Total O.OOOE+00 O.OOOE+00 o.oooE+00 O.OOOE+00 Halogens (Curies)

Isotope January February March Total -

Total 0.000E+00 O.OOOE+O0 0.000E+00 O.OOOE+O0 Page 10 of 63

Table 2.3A (Con't)

Annual Radioactive Effluent Release Report 2012 1st Quarter Gaseous Release Total of all Releases Summary January February March Total Total Noble Gases (Ci) O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+O0 Total Halogens (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+/-00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Tritium (Ci) 8.318E-01 1.374E+00 6.948E-0 I 2.900E+00 Total Particulate Gross Alpha (Ci) O.OOOE+O0 O.OOOE+00 O.OOOE+O0 0.000E+00 Page 11 0'f 63

I Table 2.3A (Con't)

Annual Radioactive Effluent Release Report 2012 2nd Quarter Gaseous Release Total of all Releases I Noble Gasses (Curies)

I Isotope April May June Total U Xe-133 5.088E-02 1.452E-04 O.OOOE+O0 5.103E-02 Xe-133m Xe-135 4.527E-04 1.446E-04 O.OOOE+00 0.000E+00 O.OOOE+O0 O.OO0E+O0 4.527E-04 1.446E-04 I

Total 5.148E-02 1.'452E-04 O.O00E+O0 5.162E-02 I

Particulates (Curies)

Isotope April '

I May June Total Co-58 7.06013-07 O.OOOE+00 0.OOOE+00 7.060E-07 I Total 7.060E-07 0.000E+00 0.000E+00 7.060E-07 Halogens (Curies)

Isotope April May June Total I

Total 0.OOOE+00 0.000E+00 O.OOOE+00 0.OOOE+00 I

U I

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Table 2.3A (Con't)

Annual Radioactive Effluent Release Report 2012 2nd Quarter Gaseous Release Total.of all Releases .

Summary April May June Total Total Noble Gases (Ci) 5.148E-02. 1.452E-04 O.OOOE+/-00: 5.162E-02 Total Halogens (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) 7.060E-07, O.OOOE+00 O.OOOE+00 7.060E-07.

Total Tritium (Ci) 2.02.8E+O 1 5.860E+00 1.1 19E+O1 3.732E+01 Total Particulate Gross Alpha (Ci) 1.139E-05 O.OOOE+00 O.OOOE+00 1.139E-05 Page 13 of 63

Table 2.3A (con't)

Annual Radioactive Effluent Release Report 2012 3rd Quarter Gaseous Release Total of all Releases Noble Gasses (Curies),

Isotope July August September Total Total O.OOOE+O0 O.OOOE+00 O.OOOE+00 O.OOOE+00 Particulates (Curies)

Isotope July August September Total Total O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 Halogens (Curies)

Isotope July August September Total Total O.OOOE+00 0.000E+00 O.OOOE+00 O.O00E+O0 Page 14 of 63

Table 2.3A (Con't)

Annual Radioactive Effluent Release Report 2012 3rd Quarter Gaseous Release Total of all Releases Summary July August September Total Total Noble Gases (Ci) 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Halogens (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days -

(Ci) 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Tritium (Ci) 9.97 1E-01 6.422E+00, 8.806E+00 1.623E+01 Total Particulate Gross Alpha (Ci) O.OOOE+O0 O.OOOE+O0 O.OOOE+00 O.OOOE+00 Page 15 of 63.

Table 2.3A (Con't)

Annual Radioactive Effluent Release Report 2012 4th Quarter Gaseous Release Total of all Releases Noble Gasses (Curies)

Isotope October November December Total Total O.OOOE+00 O.OOOE+00. O.OOOE+00 O.OOOE+00 Particulates (Curies)

Isotope October November December Total Total O.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 Halogens (Curies)

Isotope October November December Total Total 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 Page 16 of 63

Table 2.3A (Con't)

Annual Radioactive Effluent ReleaseReport 2012 4th Quarter Gaseous Release' Total of all Releases Summary October November December Total Total Noble Gases (Ci) O.OOOE+00 0.OOOE+OO O.OOOEO00 0.OOOE+/-00 Total Halogens (Ci) O.OOOE+00 0.OOOE+/-0O O.OOOE+/-00 O.OOOE+/-00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) 0.OOOE+00 0.OOOE+O0 O.OOOE+00 O.OOOE+00 Total Tritium (Ci) 4.971 E+00 2.802E+00 1.308E+00 9.081E+00 Total Particulate Gross Alpha (Ci) 0.OOOE+00 O.OOOE-i00 O.OOOE+00 O.OOOE+00 Page 17 of 63

I Table 2.3B Annual Radioactive Effluent Release Report 2012 I

1st Quarter Gaseous Release Continuous Mode Only I Noble Gasses (Curies) I Isotope January February March Total U

Total 0.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 I

Particulates (Curies)

Isotope January February March Total I

Total O.O00E+00 0.OOOE+00 O.OOOE+0O. 0.OOOE+/-00 I Halogens (Curies) I Isotope January February March Total Total 0.000E+00 0.000E+00 0.OOOE+00 O.OOOE+00 I

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Table 2.3B (Con't)

Annual RadioactiveEffluent Release Report 2012 1st Quarter Gaseous Release Continuous Mode Only Summary January February March Total Total Noble Gases (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Halogens (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) 0.000E+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Tritium (Ci) 8.311 E-01 1.373E+00 6.948E-01 2.899E+00 Total Particulate Gross Alpha (Ci) O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+/-OO Page 19of63

I Table 2.38 (Con't)

I Annual Radioactive Effluent Release Report 2012 2nd Quarter Gaseous Release Continuous Mode Only

'I Noble Gasses (Curies) I Isotope April May June Total I

Total O.OOOE+00O O.OOOE+OO O.OOOE+00. O.OOOE+00 I

Particulates (Curies)

Isotope April May June Total I

Co-58 Total 7.060E-07 7.060E-07 O.OOOE+00 0.000E+00 O.OOOE+00 O.O00QE-OO 7.060E-07 7.060E-07 I

Halogens (Curies)

I Isotope April May June Total I Total O.OOOE+00 O.OOOE+O0 0.000EE+00 0.000E+00 I

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Table 2.3B (Con't)

Annual Radioactive Effluent Release Report 2012 2nd Quarter Gaseous Release Continuous Mode Only Summary April May June Total Total Noble Gases (Ci) O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOEO00 Total Halogens (Ci) O.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) 7.060E-07 U0. E+OO 0 .000E+/-00 7.060E-07 Total Tritium (Ci) 1.529E+01 5.858E+00 1.118E+01I 3.233E+01 Total Particulate Gross Alpha (Ci) 1.13SE-05 O.'OOOE+0O' 0.000E+00 1.138E-05 Page 21 of 63

Table 2.3B (con't)

Annual Radioactive Effluent Release Report 2012 3rd Quarter Gaseous Release Continuous Mode Only Noble Gasses (Curies)

Isotope July August September Total Total O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 Particulates (Curies)

Isotope July August September Total Total 0.000E+00 0.000E+00 O.O00E01o+ O.OOOE+00 Halogens (Curies)

Isotope July August September Total Total O.OOOE+00 O.O00OE-O0 O.OOOE+00 0.000E+00 Page 22 of 63

Table 2.3B (Con't)

Annual Radioactive Effluent Release Report 2012 3rd Quarter Gaseous Release, Continuous Mode Only Summary July August September Total Total Noble Gases (Ci) 0.000E+00 o.OOOE+00 0.OOOE+00 0.OOOE+00 Total Halogens (Ci) 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) O.OOOE+00 0.OOOE+00 O.OOOE+00 O.000E-+00 Total Tritium (Ci) 9.947E-0 1 6.42 1E+00 8.804E+00 1.622E+01 Total Particulate Gross Alpha (Ci) 0.0OOE+00 0.OOOE+00 O.OOOE+00 .0.0013t00 Page 23 of 63

Table 2.3B (Con't)

Annual Radioactive Effluent Release Report 2012 4th Quarter Gaseous Release Continuous Mode Only Noble Gasses (Curies)

Isotope October November December Total Total 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Particulates (Curies)

Isotope October November December Total Total O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Halogens (Curies)

Isotope October November December Total Total 0.000E+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 Page 24 of 63

Table 2.3B (Con't)

Annual Radioactive Effluent Release Report 2012 4th Quarter Gaseous Release Continuous Mode Only Summary October November December Total Total Noble Gases (Ci) O.OOOE+O0 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Halogens (Ci) O.OOOE+O0 O.OOOE+00 O.OOOE+00 0.000E+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 Total Tritium (Ci) 4.967E+00 2.800E+00 1.296E+00 9.064E+00 Total Particulate Gross Alpha (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Page 25 of 63

Table 2.3C Annual Radioactive Effluent Release Report 2012 1st Quarter Gaseous Release Batch Mode Only Noble Gasses (Curies)

Isotope January February March Total Total O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Particulates (Curies)

Isotope January February March Total Total O.OOOE+00 O.OOOE+00 O.OOOE+O0 O.OOOE+00 Halogens (Curies)

Isotope January February March Total Total O.OOOE+00 O.OOOE+O0 O.OOOE+00. O.OOOE+00 Page 26 of 63

Table 2.3C (Con't)

Annual Radioactive Effluent Release Report 1st Quarter Gaseous 2012 Release Batch Mode Only Summary January February March Total Total Noble Gases (Ci) O.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 Total Halogens (Ci) 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) O:OOOE4-O0 0.00013+00 0.000E+00 0.000E+00 Total Tritium (Ci) 6.992E-04 9.365E-04 2.5188E-05 1.661E-03 Total Particulate Gross Alpha (Ci) O.0001E+00 O.001E+00 0.000+/-E+00 0.000E+00 Page 27 of 63

3 Table 2.3C (Con't)

Annual Radioactive Effluent Release Report 2012 I 2nd Quarter Gaseous Release Batch Mode Only i Noble Gasses (Curies)

Isotope April May June Total i

Xe-133 5.088E-02 1.452E-04 O.000E+00 5-103E-02 Xe- 1331n 4.527E-04 0.000E+00 O.000E+00 4.5217E-04 Xe-1 35 1.446E-04 0.000E+00 O.000E+00 1.446E-04 Total 5.148E-02 1.452E-04 O.OOOE+00 5.162E-02 Particulates (Curies)

Isotope April May June Total Total 0.000E+00 O.OOOE+o0 0.000E+00 0.00013+/-00 Halogens (Curies) I Isotope April May June Total I

Total O.OOOE+00 0.000E+00 0.000E+00" 0.0003E+00 I

I I

Page 28 of 63 I

Table 2.3C (Con't)

Annual Radioactive Effluent Release Report 2012 2nd Quarter Gaseous Release Batch Mode Only Summary April May June Total Total Noble Gases (Ci) 5.148E-02 1.452E-04 O.OOOE+O0 5.162E-02 Total Halogens (Ci) O.OOOE+00 O.O00E+O0 O.OOOE+O0 O.OOOE+00 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) O.OOOE+00 0.000E+00 O.OOOE+O0 O.OOOE+00 Total Tritium (Ci) 4.983E+00 2.190E-03 4.675E-03 4.990E+00 Total Particulate Gross Alpha (Ci) 2.242E-09, 0.O000E+00 0.000E+00 2.242E-09, Page 29 of 63

i, I

Table 2.3C (con't)

Annual Radioactive Effluent Release Report 2012 3rd Quarter Gaseous Release I

Batch Mode Only Noble Gasses (Curies)

I Isotope July August September Total I Total O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+00 I

Particulates (Curies)

Isotope July August September Total 1

Total O.OOOE+00 O.OOOE+00 O.OOOE+00 0.000E+O0 I Halogens (Curies) I Isotope July August September Total I

Total O.OOOE+00 0.0001E+00 O.OOOE+00 O.OOOE+00 U

I U

I I

U Page 30 of 63

Table 2.3C (Con't)

Annual Radioactive Effluent Release Report 2012 3rd Quarter Gaseous Release Batch Mode Only Summary July August September Total Total Noble Gases (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+O0.

Total Halogens (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+O0 Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Total Tritium (Ci) 2.389E-03 7.069E-04 2.430E-03 5.525E-03

-Total Particulate Gross Alpha (Ci) 0.000E+00 0.0OOE+00 O.OOOE+00 0.000E+00 Page 31 of 63

Table 2.3C (Con't)

Annual Radioactive Effluent Release Report 2012 4th Quarter Gaseous Release Batch Mode Only Noble Gasses (Curies)

Isotope October November December Total Total 0.000 E+/-00 O0.00E+00 0.000E+00 0.OOOE+00 Particulates (Curie-s)

Isotope October November December Total Total 0.OOOE+00 0.000E+00 0.OOOE+00 O.OOOE+00 Halogens (Curies)

Isotope October November December Total Total O.OOOE+00 O.000E+00 0.OOOE+00 O.OOOE+00 Page 32 of 63

Table 2.3C (Con't)

Annual Radioactive Effluent Release Report 2012 4th Quarter Gaseous Release Batch Mode Only Summary October November December Total Total Noble Gases (Ci) 0.( )OOE+00 0.OOOE+00o o.OOOE'+0O 0.OOOE+/-00 Total Halogens (Ci) 0. )OOE+00 0.OOOE+/-00 0.OOOE+0O 0.OOOE+/-OO Total Particulate Gross Beta-Gamma Half-Lives>8 Days (Ci) 0.( OOE+00 0.OOOE+00 O.OOOE+0O 0.OOOE+00 Total Tritium (Ci) 3.315E-03 1.625E-03 1.214E-02 1.709E-02 Total Particulate Gross Alpha (Ci) O.OOOE+00 0.000E+00 0.000E+00 O.OOOE+00 Page 33 of 63

Table 2.4 Annual Radioactive Effluent Release Report 2012 Dose From Gaseous Effluents The offsite dose limits from radioactive materials in gaseous effluents are specified in Section 13.2.2 and 13.2.3 of the Kewaunee ODCM and can be summarized as follows:

Air Dose Air Dose Limit Gamma Beta Organ Quarterly 5.0 mRad 10.0 mRad 7.5 rnRem Arnual 10.0 mRad 20.0 mRad 15.0 mRem The total release of gaseous effluents during each quarter of 2012 was within limits. Thefollowing offsite doses were calculated using equations 2.7, 2.8, and 2.11 from the Kewaunee ODCM.

Calculated offsite doses versus quarterly limits are shown below:

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr I. Gamma- Air Dose Specification (mRads) 5.OOOE+00 5.OOOE+00 5.OOOE+00 5.OOOE+00 Actual Dose (mRads) 0.OOOE+00 2.104E-06 0.OOOE+00 0.OOOE+00

% of Specification 0.OOOE+00 4.208E-05 0.000E+00 0.000E+00

2. Beta- Air Dose Specification (mRads) 1.0003E+0 1 1.000E+01 1.000E+01 1.000E+01 Actual Dose (mRads) 0.OOOE+00 6.23 1E;-06. 0.OOOE+00 0.OOOE+00

% of Specification 0.OOOE+00 6.231 E-05 0.OOOE+00 0.OOOE+00

3. Ingestion Pathway-Organ Specification (mRems) 7.500E+00 7.500E+00 7.500E+00 7:500E+00 Actual Dose (mRems) 6.127E-05 5.766E-04 2.418E-05 S1353E-05

% of Specification 8.169E-04 7.688E-03 3.224E-04 1.804E-04 Liver TBody Liver Liver Page 34 of 63

Table 2.4 (Con't)

Annual Radioactive Effluent Release Report 2012 Dose From Gaseous Effluents In addition, the cumulative annual offsite doses for the period January 1 - December 31, 2012 versus the Kewaunee ODCM annual limits were:

Annual

1. Gamma- Air Dose Specification (mRads) I.000E+01 Actual Dose (mRads) 2.104E-06

% of Specification 2.104E-05

2. Beta- Air Dose Specification (mRads) 2.OOOE+01 Actual Dose (mRads) 6.23 1E-06

% of Specification 3.116E-05

3. Ingestion Pathway-Organ Specification (mRems) 1.500E+01 Actual Dose (mRems) 6.755E-04

% of Specification 4.504E-03 TBody 2.4 Estimation of Carbon-14 in Gaseous Releases The total estimated C-14 released was 6.29 Ci.

30% of the estimated C- 14 released. was assumed to, be in the form of CO 2 ..

The highest estimated C-14 doses at the highest X/Q for ingestion and inhalation receptor (one mile west) were:

1.94E-01 mRem as Child Bone Dose 3:88E-02 mRem as Child Whole Body Page 35 of 63

I 3.0 LIQUID EFFLUENTS I 3.1 Lower Limits of Detection (LLD) for Liquid Effluents Liquid radioactive effluents are released as both batch releases and continuous releases. Each batch is I

sampled prior to release and analyzed for gamma emitters and tritium. A fraction of each sample is

.retained for a monthly proportional composite which is then analyzed for Gross Alpha, Strontium 89, Strontium 90, Iron 55 and Nickel 63.

I The LLD's for liquid batch release radioarialyses, as listed in Table 13.1.1-i of the Kewaunee ODCM are:

Analysis LLD (.tCi/ml)

Principal Gamma Emitters 1.00 E-06 Iodine 131 1.00 E-06 Tritium Gross Alpha 1.00 E-05 5.00 E-07 I

Strontium 89, 90,.

Iron 55 5.00 E-08 1.00 E-06 I

The actual obtained,"a priori" LLD values for batch releases are shown below. U Isotope 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Average a priori..

Mn-54 1.12E-07 I.35E-07 1.40E-07 .9.92E-08 LLD. (jiCi/ml) 1.22E-07 I

Fe-59 Co-58 2.44E-07 1.IOE-07 2.99E-09 1.77E-07

.5.30E-08 1.80E-07

.3.92E-08 1.3 1E-07

.8.48E-08

" .50E-07 I

Co-60 1.60E-07 1.78E-07' 4.80E-07 2.34E-08 1.35E-07 Zn-65 Mo-99 2.75E-07 7.98E-07' 5.95E-08

.1.68E-07 4.50E-07

9. 50E-07 4.42E-08 9.37E-07 2.07E-07 7.13E-07 I

Cs-134 Cs-137 8.92E-08 1.1OE-07 2.67E-098 2.3 1E-08 1.50E-07 1.80E-07 7.66E-08 9.51E-08 8.56E-08 I 02E-07 U Ce-141 8.83E-08 1.34E-07' 2.1 OE-07 *6.93E-08 1.25E-07 Ce- 144 1-131 4.72E-07 7.02E-08 9.39E-07 1.36E-07 8.20E-07 1.40E-07 3.69E-07 7.77E-08 6.50E-07

. .06E-07 I

H-3 2.5 1E-06 3.43E-06 2.90E-06 2..69E-06 2. 89E-06 Sr-89 Sr-90 9.19E-09 8.76E-09 1.43E-08 1.11E-08 6.31 E-09 6.35E-09 1..02E-08 7.22E-09 I

8.63E-09 5.19E-09 Gross Alpha, Fe-55 6.91E-09 9.08E-07 7.89E-09 8.68E-07 8.9 6E-09 8.15E-07 5.63E-09 7.99E-07 7.35E-09 8.48E-07 I

Ni-63 1.12E-07 1.28E-07 9.32E-08 1.18 E-07 1.13E-07 I

Page 36 of 63 I

U

Continuous liquid releases are grab sampled weekly and analyzed for principal gamma emitters. A fraction of each weekly sample is retained for a monthly proportional composite which is then analyzed for Gross Alpha, Strontium 89, Strontium 90, Iron 55 and Nickel 63.

The LLD's.for liquid continuous release radioanalyses, as listed in Table 13.1.1-1 of the Kewaunee ODCM are:

Analysis LLD (ýtCi/ml)

Principal Gamma Emitters 5.00 E-07 Iodine 131 1.00 E-06 Tritium 1.00 E-05 Gross Alpha 5.00 E-07 Strontium 89, 90 5.00 E-08 Iron 55 1.00 E-06 The actual obtained "a priori" LLD values for continuous releases are shown below.

Isotope 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Average a priori LLD (pCi/ml)

Mn-54 1.16E-08 8.87E-09 1.70E-08 7.04E-09 1.1 IE-08 Fe-59 2.73E-08 1.98E-08 3.80E-08 1.57E-08 2.52E-08 Co-58 :1.

.l4E-08 1.3 1E-08 1.80E-08 7.87E-09

1.26E-08 Co-60 1.18E-08 1.43E-08 2.OOE-08 1.05E-08 1.42E-08 Zn-65

2.43E-08 3.08E-08 2 .40E-08 2.02E 2.48E-08 Mo-99 1.05E-07 .8.68E-08 1.30E-07. 1.02E-07 1.06E-07 Cs-134 6.97E-09 1.13E-08 1.30E-08' ,9.61E-09 .1.02E-08 Cs-137 1.07E-08 1.43E-08 , 1.70E-08 1.24E-08 . 1.36E-08 Ce- 141 " 1.59E-08 1.65E-08 2.20E-08 1.54E-08,,. .1.75E-08 Ce- 144 '6.93E-08 6.85E-08 8.70E-08. 7.64E-08. 7.53E-08 1-131 9.68E-09 1.17E-08 1.40E-08 9.39E-09 1:. 12E-08 H-3 2.5 1E-06 3 .43E-06 2.90E-06 2.69E-06 ',"2.89E-06 Sr-89 1.20E-08 S..09E-08 I .04E-08 .7.15E-09: 1l.01E-08

1.05E-08 Sr-90 5.88E-09 5 .77E-09 6.17E-09 7.08E-09 Gross Alpha 4.40E-09 4.34E-09 5.12E-09 5.31E-09 . 4.79E-09 Fe-55 9.03E-07 8.95E-07 7.98E-07 7.85E-07:.,. .8.45E-07 Ni-63 1.11E-07 9.28E-08 1.02E-07 1,..16E-07 , .05E-07.

Page 37 of 63

I 3.2 Liquid Batch Release Statistics I The following is a summation of all liquid batch releases during 2012.

I Release Tvye Number Gallons Released I A& B WCT A CVC Monitor Tank 2

6 1,860 37,240 I

B CVC Monitor Tank 6 30,520 A SGBT Monitor Tank B SGBT Monitor Tank 19 24 169,833 219,046 I

Total time for all batch releases (min) ............. 24,080 1 Maximum time for a batch release (min) ........... 2,077 Minimum time for a batch release (mrin) ............. 16 I Average time for a batch release (min) .................. 422.5 I 3.3 Liquid Effluent Data I

The following Table 3.1 presents a quarterly summatioh of the total activity released and average concentration for all liquid effluents. It also presents the gross alpha activity released, volume of waste I

released and volume of dilution water used. Tables'3.2 and 3.3 are monthly summations of the same information in Table 3.1. Table 3.2 contains the quantity of the individual isotopes released to the unrestricted area for batchreleases. Table 3.3 presents a monthly surmnation of gross radioactivity, I

tritium, gross alpha and isotopic activity for the secondary blowdown and leakage releases. It also presents the monthly total volume for these releases and dilution volumes. Table 3.4 presents the doses from liquid effluents for each quarter and the calculated doses this year from liquid effluents.

I I

Page 38 of 63 I

TABLE 3.1 Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Summation of all Releases Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Fission and Activation Products Total Release Excluding H3 and Dissolved Gases (Ci) 2.061E-02 3.143E-02 5.766E-03 1.149E-02 Average Concentration (jICi/ml) 3.862E-11 1.496E-10 2.172E-11 4.106E-11 Tritium Total Release (Ci) 3.652E+01 1.098E+02 1.813E+01 7.208E+00 Average Concentration (FCi/ml) 6.843E-08 5.225E-07 6.828E-08 2.575E-08

% of Tech. Spec.

Limit(3.0E-3 paCi/ml) 2.281E-03 1.742E-02 2.276E-03 8.583E-04 Dissolved Gases Total Release (Ci) O.OOOE+OO O..OOOE.+00 0.OOOE+/-0O. 0.OOOE+00' Average Concentration' (iiCi/ml) 0.000E+00,.. 0.000E+00' .0..OOOE+0O .0.OOOE+OO

% of Tech. Spec. 0.00OE+00 O.OOOE+00 Limit(2.oE-4 laCi/ml) 0..OOOE+00.-ý O.OOOE+/-00 Gross Alpha Activity Total Release (Ci) 0.060E+00 O.OOOE+/-00 0.OOOE+/-00 0.OOOE+00 Volume of Waste Released Batch (liters) 4.579E+05 7.085E+05 3.240E+05 2.450E+05 Continuous (liters) 2.592E+07 2.266e+07 2.205E+07 2.437E+07 Total (liters) 2.638E+07 2.336E+07 2.238E+07 2.462E+07 Volume of Dilution Water Batch (liters) 4.76 1E+09 6.777E+09 3.240E+09 1.926E+09 Continuous (liters) 5.289E+1 I 2.034E+1 I 2.622E+1 1 2.780E+ 1I Total (liters) 5.336E+1 I 2.IOE+l I 2.654E+1 I 2.800E+1 I Page 39 of 63

TABLE 3.2A Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases January Feblruary March Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) 1.371E-02 4.262E-03 2.632E-03 2.061 E-02 Avg. Cone.

(VCCi/ml) 4.607E-09 3.93 1E-09 3.758E-09 Tritium Total Release (Ci) 2.788E+01 5.793E+00 2.844E+00 3.652E+0 1 Avg. Conc.

(piCi/ml) 9.366E-06 5.344E-06 4.061 E-06 Dissolved Gases Total Release (Ci) 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 Avg. Cone.

(ýICi/ml) 0.OOOE+00 0.OOOE+00 0.OOOE+00 Gross Alpha Activity Total Release (Ci) 0.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+0O Avg. Cone.

(gCi/ml) 0.OOOE+00 0.OOOE+00 O.OOOE+00 Volume of Waste Released (liters) 2.829E+05 1.075E+05 6.751 E+04 4.579E+05 Volume of Dilution Water (liters) 2.977E+09 1.084E+09 7.002E+08 4.761 E+09 Page 40 of 63

TABLE 3.2A (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases Isotope (Ci) January February March Total Ag- 1I10m 3.02 1E-04 1.963E-05 3.027E-05 3.520E-04 Co-57 8.663E-06 O.OOOE+00 0.OOOE+00 8.663E-06 Co-58 8.227E-05 0.OOOE+00 0.OOOE+00 8.227E-05 Co-60 3.153 E-03 4.570E-04 2.118E-04 3.822E-03 Fe-55 7.044E-03 2.678E-03 1.681 E-03 1. 140E-02 H-3 2.788E+01 5.793E+00 2.844E+00 3.652E1+01 Mn-54 2.1 12E-04 0.OOOE+00 1.332E-05 2.245E-04 Ni-63 2.914E-03 1.108E-03 6.954E-04 4.717E-03 Total 2.790E+0 1 5.797E+00 2.847E+00 3.654E+01 Page 41 of 63

TABLE 3.2B Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases April May June Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) 1.376E-02 1.086E-02 6.821 E-03 3.143E-02 Avg. Conc.

([tCi/ml) 7.708E-09 3.102E-09 4.569E-09 Tritium Total Release (Ci) 2.295E+01 6.955E+O 1 1.725E+01 1.098E+02 Avg. Conc.

([tCi/ml) 1.286E-05 1.987E-05 1. 156E-05 Dissolved Gases Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(hICi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Gross Alpha Activity Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(pCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Volume of Waste Released (liters) 2.451 E+05 3.028E+05 1.606E+05 7.085E+05 Volume of Dilution Water (liters) 1.784E+09 3.500E+09 1.493E+09 6.777E+09 Page 42 of 63

TABLE 3.2B (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases Isotope (Ci) April May June Total Ag- I1Oim 1.484E-04 1.587E-05 1.435E-04 3.078E-04 Co-57 2.451 E-05 O.OOOE+00 O.OOOE+00 2.451 E-05 Co-58 1.070E-03 2.138E-03 6.569E-04 3.865E-03 Co-60 5.281 E-03 2.575E-04 1.302E-04 5.669E-03 Cr-51 2.430E-04 O.OOOE+00 2.340E-04 4.769E-04 Fe-55 3.260E-03 4.027E-03 2.136E-03 9.423E-03 H-3 2.295E+O 1 6.955E+01 1.725E+01 1.098E+02 Mn-54 3.209E-04 0.000E+00 O.OOOE+oo 3.209E-04 Ni-63 3.3)33E-03 4.118E-03 2.184E-03 9.635E-03 Sb-124 O.OOOE+00 O.OOOE+00 1.392E-04 1.392E-04 Sb-125 7.518E-05 2.994E-04 1.197E-03 1.571E-03 Total 2.296E+O 1 6.956E+01 1.726E+OI 1.098E+02 Page 43 of 63

TABLE 3.2C Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases July August September Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) 2.607E-03 1.742F,-03 1.418E-03 5.766E-03 Avg. Conc.

1.740E-09 1.301lE-09 (IlCi/ml) 2.267E-09 Tritium Total Release (Ci) 1.024E+O1 4.067E+00 3.791 E+00 1.810E+01 Avg. Cone.

(ýtCi/ml) 8.906E-06 4.064E-06 3.480E-06 Dissolved Gases Total Release (Ci) O.OOOE+00 0.000E+00 0.000E+00 0.000E+00 Avg. Conc.

(pCi/ml) 0.OOOE+00 0.000E+00 0.000E+00 Gross Alpha Activity Total Release (Ci) 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 Avg. Conc.

(l[Ci/ml) 0.OOOE+00 0.OOOE+00 0.OOOE+00 Volume of Waste Released (liters) 1.152E+05 1.028E+05 1.060E+05 3.240E+05 I

Volume of Dilution Water (liters) 1.150E+09 1.0011E+09 1.089E+09 3.240E+09 Page 44 of 63

TABLE 3.2C (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases Isotope (Ci) July August September Total Ag-I 10m 6.807E-05 7.173E-05 3.090E-05 1.707E-04 Co-58 3.709E-04 2.858E-04 8.601 E-05 7.428E-04 Co-60 4.391 E-05 1.707E-04 5.033E-05 2.649E-04 Fe-55 1.152E-03 1.028E-03 1.060E-03 3.240E-03 H-3 1.024E+01 4.067E+00 3.791 E+00 1.810E+01 Nb-95 5.633E-06 O.OOOE+00 0.000E+00 5.633E-06 Ni-63 2.074E-04 1.851E-04 1.907E-04 5.833E-04 Sb- 124 9.158E-05 O.OOOE+00 0.000E+00 9.158E-05 Sb-125 6.669E-04 O.000E+00 0.OOOE+00 6.669E-04 Total 1.024E+01 4.069E+00 3.792E+00 1.8111E+01

,i Page 45 of 63

TABLE 3.2D Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases October November December Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) 5.869E-03 4.417E-03 1.209E-03 1 149E-02 Avg. Conc.

(pCi/ml) 7.375E-09 5.996E-09 3.072E-09 Tritium Total Release (Ci) 2.962E+00 1.915E+00 2.320E+00 7.198E+00 Avg. Conc.

(iLCi/rnl) 3.723E-06 2.600E-06 5.893E-06 Dissolved Gases Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(ýICi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Gross Alpha Activity Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

([tCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Volume of Waste Released (liters) 1.072E+05 1.056E+05 3.218E+04 2.450E+05 Volume of Dilution Water (liters) 7.956E+08 7.366E+08 3.936E+08 1.926E+09 Page 46 of 63

TABLE 3.2D (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Batch Releases Isotope (Ci) October November December Total Ag- IOin 2.13 1E-04 5.172E-05 9.752E-06 2.746E-04 Co-57 1.614E-05 O.OOOE+00 O.OOOE+00 1.614E-05..

Co-58 5.587E-04 1.944E-04 3.926E-05 7.923 E-04 Co-60 1.106E-03 3.323E-04 O.OOOE+00 1.438E-03 Fe-55 3.430E-03 3.380E-03 1.030E-03 7.839E-03 H-3 2.962E+00 1.915E+00 2.320E+00 7.198E+00 Mn-54 1.111E-04 3.1151E-05 O.OOOE+00 1.422E-04 Ni-63 4.341E-04 4.277E-04 1.303E-04 9.9221E-04 Total 2.968E+00 1.920E+00 2.321E+00 7.209E+00 Page 47 of 63

TABLE 3.3A Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases January. February March Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) O.OOOE+00 O.OOOE+O0 O.OOOE+00 O.OOOE+00 Avg. Conc.

(PCi/ml) O.OOOE+00 O.O00E+O0 O.OOOE+00 Tritium Total Release (Ci) 8.528E-04 o.oooE+00 1.509E-05 8.679E-04 Avg. Conc.

(ýtCi/ml) 1.250E- I1 O.OOOE+00 4.844E- 13 Dissolved Gases Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

([tCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Gross Alpha Activity Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Cone.

(gCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Volume of Waste Released (liters) 1.11 5E+07 7.578E+06 7.198E+06 2.592E+07 Volume of Dilution Water (liters) 6.821E+10 4.295E+l I 3.116E+I0 5.289E+1 I Page 48 of 63

TABLE 3.3A (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases Isotope (Ci) Januar y February March Tot*

al-0 H-3 8.5281E-04 O.OOOE+00 1.509E-05 8.6 79E-04 Total 8.5281E-04 O.OOOE+00 1.509E-05 8.6'

.1 1. 11 Page 49 of 63

TABLE 3.3B Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases April May June Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 Avg. Conc.

(pCi/ml) 0.OOOE+00 O.OOOE+00 0.OOOE+00 Tritium Total Release (Ci) 5.747E-02 0.OOOE+00 1.148E-04 5.758E-02 Avg. Conc.

([ICi/ml) 1.686E-09 0.OOOE+00 1.250E-12 Dissolved Gases Total Release (Ci) O.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 Avg. Conc.

([tCi/ml) O.OOOE+00 0.OOOE+00 0.OOOE+00 Gross Alpha Activity Total Release (Ci) O.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 Avg. Conc.

([tCi/ml) 0.OOOE+00 O.OOOE+00 0.000E+00 Volume of Waste Released (liters) 6.736E+06 1.021E+07 5.713E+06 2.266E+07 Volume of Dilution Water (liters) 3.407E+10 7.753E+10 9.176E+10 2.034E+1 1 Page 50 of 63

TABLE 3.3B (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases Isotope (Ci) April May June Tot al H-3 5.7471E-02 0.000E+00 1.148E-04 5.7:58E-02 Total 5.7471E-02 O.OOOE+00 1.148E-04 5.7:58E-02 Page 51 of 63

TABLE 3.3C Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases July August September Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(iiCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Tritium Total Release (Ci) 7.549E-03 4.347E-03 1.433E-02 2.622E-02 Avg. Conc.

(PCi/ml) 7.803E- I11 4.163E- I1 2.346E-10 Dissolved Gases Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(PCi/ml) O.OOOE+00 O.OOOE+00 O.OOE+00 Gross Alpha Activity Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 Avg. Conc.

(VCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Volume of Waste Released (liters) 9.595E+06 6.645E+06 5.813E+06 2.205E+07 Volume of Dilution Water (liters) 9.674E+10 1.044E+ 1I 6.106E+ 10 2.622E+1 1 Page 52 of 63

TABLE 3.3C (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases Isotope (Ci) July August September Tot al H-3 7.549]E-03 4.347E-03 1.433E-02 2.6 22E-02 Total 7.549]E-03 4.347E-03 1.433E-02 2.6 22E-02 Page 53 of 63

TABLE 3.3D Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases October November December Total Gross Radioactivity Total Release Excluding H3 and Dissolved Gases (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(PCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Tritium Total Release (Ci) 1.696E-03 4.928E-03 4. 1OOE-03 1.073E-02 Avg. Conc.

(VtCi/ml) 1.738E-1 I 8.078E- 1I 3.433E- I1 Dissolved Gases Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(PiCi/ml) O.OOOE+00 0.000E+00 O.OOOE+00 Gross Alpha Activity Total Release (Ci) O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Avg. Conc.

(PCi/ml) O.OOOE+00 O.OOOE+00 O.OOOE+00 Volume of Waste Released (liters) 7.901E+06 6.270E+06 1.020E+07 2.437E+07 Volume of Dilution Water (liters) 9.761E+10 6.100E+10 1.194E+ 11 2.780E+1 I Page 54 of 63

TABLE 3.3D (Con't)

Annual Radioactive Effluent Release Report 2012 Liquid Effluents - Continuous Releases Isotope (Ci) Octob er November December Tot.al

-03W 4.928E-03 4.1OOE-03 1.0' H-3 1.6961 73 E-02 Total 1.6961E-03 4.928E-03 4.1OOE-03 1.0' 73E-02 Page 55 of 63

I Table 3.4 I Annual Radioactive Effluent Report 2012 Dose From Liquid Effluents I

The dose to a member of the public from total liquid radioactive releases for each quarter was below the Kewaunee ODCM limits of 1.5 morerms to the total body and less than or equal to 5 mrems to any organ. Additionally, the dose to a member of the public from total liquid radioactive releases for the I

year was below the Kewaunee ODCM limits of 3 mrems to the total body and less than or equal to 10 mrems to any organ. I Instantaneous release concentrations are limited .by the individual radionuclide concentrations established in 10 CFR 20, Appendix B, for unrestricted areas. During the report, period, none of the isotopes released exceed the concentrations specified in Appendix B. The following offsite doses were I

calculated using equation 1.7 from the Kewaunee ODCM. .

Organ Dose Quarterly Percent I

1st Qtr Dose Total Limit of Limit Total Body mRem 4.536E-04 mRem 1.5 3.024E-02 U

Bone Liver 3.411 E-03 6.487E-04 5.0 5.0 6.822E-02 1.297E-02 I Thyroid Kidney 2.656E-04 2.720E-04 5.0 5.0 5.311E-03 5.441 E-03 I Lung 3.295E-04 5.0 6.591E-03 GI-LLI 8.593E-04 5.0 1.719E-02 I

Organ 2nd Qtr Dose Dose Total Quarterly Limit Percent of Limit I

mRem mRem Total Body 2.995E-03 1.5 1.997E-01I I

Bone 1.729E-02 5.0 3.458E-01 Liver Thyroid 3.727E-03 1.981E-03 5.0 5.0 7.453E-02 3.963E-02 I

Kidney 2.031 E-03 5.0. 4.063E-02 Lung GI-LLI 2.116E-03 6.025E-03 5.0 5.0 4.232E-02 1.205E-01 I

I m

Page 56 of 63 I

Table 3.4 (Con't)

Annual Radioactive Effluent Report 2012 Dose From Liquid Effluents Organ Dose Quarterly Percent 3rd Qtr Dose Total' Limit of Limit mRem mRem Total Body 1.594E-04 1.5 1.063E-02 Bone 4.486E-04 5.0 8.973E-03 Liver 1.95 1E-04 5.0 3.903E-03 Thyroid 1.317E-04 5.0 2.634E-03 Kidney 1.318E-04 5.0 2.635E-03 Lung 1:500E-04 5.0 2.999E-03 GI-LLI 4.043E-04 5.0 8.086E-03 Organ Dose Quarterly Percent 4th Qtr Dose Total Limit of Limit mRem miRern Total Body 1.179E-04 1.5 7.857E-03 Bone 7.967E-04 5.0 1.593E-02 Liver 2.020E-04 5.0 4.040E-03 Thyroid 5.239E-05 5.0 1.048E-03 Kidney 5.649E-05 5.0 1.130E-03 Lung 9.638E-05 5.0 1.928E-03 GI-LLI 3.374E-04 5.0 6.749E-03 Calculated Dose This Year Organ Dose Quarterly Percent Total Limit of Limit mRem mRem Total Body 3.726E-03 3.0 1.242E-01:

Bone 2.195E-02 10.0 2.195E-01 Liver 4.773E-03 10.0 4.773E-02 Thyroid 2.431 E-03 10.0 2.431 E-02, Kidney 2.492E-03 10.0 2.492E-02 Lung 2.692E-03 10.0 2.692E-02 GI-LLI 7.626E-03 10.0 7.626E-02 Page 57.of 63

I 3.4 Ground Water Monitoring I

Sample Point Tritium Total Gamma Activity I Sample Date pCiIL ttCi/ml AB-707 03/01/12 919 None Detected U 05/01/12 1257 None Detected 07/26/12 11/16/12 1764 1883 None None Detected Detected I

AB-708 03/01/12 05/01/12 668 868 None None Detected Detected U

07/26/12 11/16/12 1245 1603 None None Detected Detected I AB-709 03/02/12

.05/29/12 275 282 None None Detected Detected I

07/27/12 679 None Detected AB-710 11/16/12 03/01/12 424 None Detected I 1025 None Detected 05/01/12 05/29/12 2111 918 None Detected None Detected I AB-711 07/26/12 11/16/12

.865

-945 None Detected None Detected I 03/01/12 05/01/12 872 706 None None Detected Detected I

07/26/412 -605 None Detected AB-712 11/16/.12

,832 None Detected 03/02/12 04/19/12 263 286 None Detected None Detected I 07/27/12 236 None Detected AB-715 1.1/16/12.

455.

-None Detected I

03/01/12 309 None Detected 04/14/12 07/26/12

<251 377 None None Detected Detected I

11/16/12 287 None Detected i

I Page 58 of 63 I

Sample Point Tritium Total Gamma Activity Sample Date pCi/L utCi/ml AB-717 03/01/12 <233 None Detected 05/30/12 <269 None Detected 07/26/12 <235 None Detected 11/16/12 <262 None Detected MW-701 03/01/12 <204 None Detected 04/14W12 <251 None Detected 07/26/12 " <235 None Detected 11/16/12 <262 None Detected MW-702 03/02/12 <204 None Detected 05/11/12 <239 None Detected 07/27/12 <235 None Detected 1 f/26/12 <262 None Detected MW-703 03/01/12 <204 None Detected 05/11/12 <239 None Detected 07/27/12 <235 None Detected

.11/26/12 <262 None Detected MW-704 03/01/12 - <204 None Detected 05/30/12 -. 269 None Detected 07/27/i2 <235 None Detected MW-705 03/01/12 351 None Detected 04/19/12. 261 None Detected 07/26/12, <235 None Detected

-11/16/12 <262 None Detected MW-706 03/02/,12 . <204 None Detected 04/19/12. <258 None Detected 07/26-/12 <235 None Detected 1-11/16/12 . <262 None Detected Page 59 of 63

4.0 UNPLANNED RELEASES No unplanned releases were made from the Kewaunee Power Station during the report period.

5.0 METEOROLOGICAL DATA See Appendix A for missing meteorological data and the joint frequency distribution tables.

6.0 SOLID WASTE DISPOSAL Table 6.1 is a summation of solid radioactive waste shipped during 2012. Presented are the types of waste, major nuclide composition, disposition of the waste and shipping containers used.

Table 6.1 contains the radionuclide content (curies) and percent abundance for each type of waste.

Page 60 of 63

Table 6.1 Annual Radioactive Effluent Report 2012 Solid Waste and Irradiated Fuel Shipments A. Solid Radioactive Waste Shipped Off-Site for Burial or Disposal

1. Type of Waste Ci Ci % Error M3

a. Resins, Filters and Evap Bottoms 5.75E+01 +25.0 5.27E+00

b. Dry Active Waste (DAW) 7.25E-02 +/-25.0 4.15E+01

c. Irradiated Components 0.OOE+00 +/-25.0 0.OOE+00 d.. Other Radioactive Waste 0.06E+00 +25-0 0.OOE+00

2. Estimate of Major Nuclide by Composition

a. Resins, Filters and Evap Bottoms Nuclide % Abundance Ci H-3 0.181 1.04E-01 Be-7 0.003 1.94E-03 C-14 0.041 2.33E-02 Cr-51 0.097 5.60E-02 Mn-54 2.182 1.25E+00 Fe-55 20.253 1.16E+O1 Fe-59 0.001 4.36E-04 Co-57 0.318 1.83E-01 Co-58 1.611 9.26E-01 Co-60 15.245 8.76E+00 Ni-59 0.671 3.86E-01 Ni-63 57.938 3.33E+01 Zn-65 0.026 1.52E-02 Sr-89 0.000 1.12E-04 Sr-90 0.004 2.11 E-03 Zr-95 0.021 1.20E-02

." f..

Nb-94 0.014 7.9 1E-03 Nb-95 0.015 8.50E-03 Tc-99 0.096 5.53E-02 Ag-110m 0.038 2.18E-02 Sn-113 0.000 7.85E-05 Sb-125 0.577 3.32E-01 1-129 0.000 5.15E-05 Cs-137 0.168 9.63E-02 Ce-144 0.498 2.86E-01 Pu-241 0.001 8.04E-04 Page 61 of 63

I

b. Dry Active Waste (DAW)

I Nuclide H-3

% Abundance 2.516 Ci 1.82E-03 I Cr-51 1.744 1.26E-03 Mn-54 Fe-55 2.085 10.494 1.5 1E-03 7.60E-03 I Fe-59 0.208 1.50E-04 Co-57 Co-58 0.291 40.226 2.11 E-04 2.91 E-02 I

Co-60 8.375 6.07E-03 Ni-63

Zn-65 14.102 0.170 1.02E-02 1.23E-04 U

Zr-95 6.551 4.75E-03 Nb-95 Tc-99 10.040 1.678 7.27E-03 1.22E-03 I

Ag- 11On 0.103 7.47E-05 Sn-1 13 Sb-125 0.131 1.068 9.46E-05 7.74E-04 I

Cs-137 Ce-144 0.076 0.142 5.54E-05 1.03E-04 I

c. Irradiated Components Nuclide % Abundance Ci I None N/A N/A

d. Other Was;te I Nuclide % Abundance Ci None N/A N/A I

3. Solid Waste Disposition Date of Shipment Mode of Transportation Destination I

02/22/12 Hittman Transport Studsvik Processing Facility Erwin 03/31/12 06/05/12 Hittman Transport Hittman Transport Studsvik Processing Facility Erwin Bear Creek Processing Facility I

09/05/12 Hittman Transport Clive Disposal Facility B. Irradiated Fuel Shipments I No irradiated fuel shipments were made from the Kewaunee Power Station during 2012.

I I

Page 62 of 63 I

I

7.0 PROGRAM REVISIONS In accordance with Technical Specification 5.6.2, the revisions to the Process Control Program, Offsite Dose Calculation Manual, Radiological Environmental Monitoring Program and radioactive waste treatment systems are listed below.

7.1 Process Control Program There were no revisions made to the Process Control Program.

7.2 Offsite Dose Calculation Manual The Kewaunee Power Station Offsite Dose Calculation Manual (ODCM) was revised during this report period. Appendix B is a copy of the Kewaunee Power Station ODCM Revision 14, Api'il 18, 2012.

7.3 Radiological Environmental Monitoring Manual The Kewaunee Power Station Radiological. Environmental Monitoring Manual (REMM) was revised during this report period. Appendix C is a copy of the Kewaunee Power Station REMM Revision 19, September 6, 2012.

7.4 Major Changes to the Radioactive Liquid, Gaseous and Solid Waste Treatment Systems There were no changes to the radioactive waste systems (liquid, gaseous or solids).

8.0 REPORTABLE OCCURRENCES None t,.r Page 63 of 63

U I

I I

I U

I This Page Intentionally Left Blank I

I I

Appendix A Kewaunee Power Station 2012 Meteorological Data Missing Data First Quarter: 54.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Second Quarter: 79.0 hours0 days 0 hours 0 weeks 0 months Third Quarter: 15.0 hours0 days 0 hours 0 weeks 0 months Fourth Quarter: 54.0 hours0 days 0 hours 0 weeks 0 months Note: A total of 202.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months of data is missing or otherwise unavailable. This represents the availability of 97.64% of the data for the year.

APPENDIX A Kewaunee Power Station 2012 Meteorological Data I

First Quarter 2012 Stability Class A I

Wind Direction I CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL NNE N 0 0

0.25 0.5 3

2 10 8

8.25 11.25 0

2 0.75 0 21.5 24.5 I NE 0 0 3.25 26 2.5 0 0 31.75 ENE E

0 0 0.5 0 11 5.5 12.25 6

0 4

0 0 0.25 0 23.25 16.25 I

ESE 0 0 7.5. 3 0.75 0 0 11.25 SE SSE 0

0 0.75 0

6.7.5 2.25 3.75 6.25 5.25 14.25 15.5 0

13.5 0 16.5 51.75 I

S 0 1.5 9.5 14.25 13 11.5 10 59.75 SSW SW 0

0 0.5 0 21.25 6.

13.5

,.5 2.5 2.75

.0 1.25 0.25 0.5 37.5 16 I 0.25 11.5 4.25 0 0 27.5 WSW 0 1i..5 WNW W 0.25 0.25 2.25 3.75 10.25 8.75 23.75 23.5.

14.5 19 0.25 0

0 0

51.25 55.25 I

0 41.75 NW NNW TOTAL 0.5 0

I 12.25 2

0 9.25 2.5 120.25 15:.5 15.75 198 14 7.5 123.75 0.5 31 0

25.25 0 25.75 511.5 3

Stability Class B I Wind Direction N

CALM 0

1-3 0

4-7 5.25 8-12 3.75-13-18 4.25 19-24 3.5

>24 0

TOTAL 16.75 I

NNE' NE' 0

0 0

0 1

0 7.25 4 3.75 0.25:

0 0

8.75 7.5 I

0.75 0 0 0 0.75 ENE E

0 0

0.25 0

0 0

0 0 0.5 0 0.25 0.5 I

ESE 0 SE SSE 0

0 0

0.5, 1.25 0

1.75 0- 0.5, 1.25 0.75 4 4.5 5.5 6.5 I

S 0 0 1.5.. 0.75 3.25 0.75 0.25 0

SSW SW 0

0 0.25 4.25 6 2.75 3.75 0.75 1 0.25 0 0 0

9.5 9.5 I WSW 0 0.25 1.75 2.25 0.5 0 0 4.75 WNW W 0 0.25 0.25 1.5 0.5, 3.

4.5.

4 2

1.75 0

0 0

0 7.25 10.5 I NW 0 0 5.5 2.25 3 0 0 10.75 NNW TOTAL 0

0.25 0.75 3

2.25 31.5 41.5 4 7.75 30 6.25 0 0 5.5 14.75 118 i

Page A2 of A15 I

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Stability Class C Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.25 2 5.25 5.5 1.25 0 14.25 NNE 0 0 0.75 3 2.5 0 0 6.25 NE 0 0 0 4 0 0 0 4 ENE 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 ESE 0 0 0 0.75 0.25 1.5 0.5 3 SE 0 0 0 0.25 0.5 0.5 0 1.25 SSE 0 0 0.75 0.75 1.5 0 0.5 3.5 3

S 0 0 1.75 2.25 0,25 0.75 8 SSW 0 0 8.5 6.75 0.25 0 0 15.5 SW 0 0 4 3 1.75 0.25 0 9 WSW 0 0.25 2.25 2.25 2.75 0 0 7.5 W 0.25 0 3.75 8 3.25- .0 0 15.25 WNW 0.25. 2 3.75 6 2.5 0 0 14.5 NW 0 0.5 515 3.75 1.75 0 0 11.5 NNW 0 0 2.5 2.25 15 0 0 19.75 TOTAL 0.5 3 35.5 49 39.75 3.75 1.75 133.25 Stability Class D Wind Direction CALM 1-3 4-7 8-12 13-18 19-24, >24 TOTAL N 0 1.25 9.57 5.. " 1 0 0 16.75 NNE 0 0.5 5.75 16.25 15.25 1 0. 38.75 NE 0 1.5 2 4.5 0 0 0 8 ENE 0 0.5 I 0 0 0 0 1.5 E 0 0.25 0. 0 0.75 4.75 1.. 6.75 ESE 0 1 0.25 0 1.5 0.25 0 3 SE 0 0 0.5 0.75 0.75 0.25 0,. 2.25 SSE 0 0.25 4.75 0.75 1.25 0.5 0 7.5 S 0, 2 4.5 12.75 6 4.251 01. 29.5 SSW 0 2.5- 30.25 20 3.25 0 0 56 SW 0 1.75 10.25 8.25 4.75 1 0,, 26 WSW 0.25 3.75 19.5 10.25 4.5 0.5 0 38.75 W 0.5, 2.75 9 25 26.25 0. 0 63.5 WNW 0.25 6.5 11.5 41.25. 10.25 0 0 69.75 NW 0.25 2.25 10.5 16.75 14 0.5 0 44.25 NNW, 0 0.75- 8.25 8.25 6.5 0.25: 0 24 TOTAL 1.25 27.5 127.5 169.75 96 13.25. 1 436.25 Page A3 of Al5

APPENDIX A Kewaunee Power Station 2012 Meteorological Data I

Stability Class E I

Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I

N 0 1.25 9.25 3 0 0 0 13.5 NNE NE 0

0 0.5 0.5 6.5 4.75 18.25 2

12 0

0.25 0

0 0

37.5 7.25 I

.0 0 ENE E

0 0 0.25 0

1 1.5 0.5 0

0 0

0 0 0 1.5 0.75 I ESE 0 2 0.25 0 0 0 3.25 SE SSE 0.25 0 0.75 1.25 1.25 0

0.25 0

2.25 0 0 0

0.75 5.5 I S 1.5 2 9.5 13.75 2.75 1 0 30.5 SSW SW 2.5 0.75 7.5 4 17.75 5.25 11.75 21.75 8.25 0.75 5.25 0.75 0 0 0

46.75 27.75 I WSW 0.25 1 17.25 11.75 0 0 42 WNW W

0.25 0 7.5 2.75 10.75 10.25 41.5 20.75 15.75 4.75 0

0 0

0 75.5 38.75 I

NW 0 3.25 10.25 6 4 0.25 4.0 0 23.75 NNW TOTAL 5.5 0

35.5 2 9.5 110.75*

2.5 155:5 57.25

.0 4.5 0

0 14 369 I

Stability Class F I

Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I

N 0 :0 3.25 1 0 0 0 4.25 NNE NE 0

0

'0

-0 1.75 0.25 3.5 0.75 0.75 0

' 0 0

0

,0 6

1 I ENE 0 0.. 0.25. 0.75 0 0 0 1 ESE E 0 0

0.25 0

1.75 0.5 1.25 0

0 0 '0 0 0 0

3.25 0.5 I

1 1.5 0 0 0 2.5 SE 0 0

. SSE S 0.5 0 0.75 2

3.75 9.5 8.75' 5 2.75 1

0 0

12.25 21.75 I

0.5 0 0 30.75 SSW WSW SW, 1.75 0.75 0

2.5 2.25 4.25 14.5 10.75 16.25 11..5 6.5 16 3.25 1.5 '0 0 0 0

22.75 38.75 I

WNW W 4.25 2

4.75 2

18.25 17.25 26 5.5 0.25 0

0 0

53.5 26.75 I NW 2.25 2.5 9 3.5 0 0 0 17.25 NNW TOTAL 0.25 11.75 0.25 21.5 7.25 115.25 0.5 92 10 0 0 0

0 0

8.25 250.5 I Page A4 of A15

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Stability Class G Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.5 0.75 0 0 0 0 1.25 NNE 0 1.5 1.25 0.5 0.25 0 0 3.5 NE 0 1.25 1.25 0.25 -0 0 0. 2.75 ENE 0 0.5 0 0 0 0 0 0.5 E 0 1.25 0 0 0 0 0 1.25 ESE 0 0.25 0 0 .0 0 0 0.25 SE 0 0.75 1.5 .0 0 0 0 2.25 SSE ,0 3.5 15.25 19.5 0.25 0 0 38.5 S 0.5 6 32 20.5 1 0 0, 60 SSW 3.75 10 17 2 0 0 0 32.75 SW 1.75 11.5 20.5 6.5 0 .0 0 40.25 WSW 0.25 8.5 25.25 3.25 0 0 0 37.25 W 0.5 2.5 25.75 9.25 0.25 0 0 38.25 WNW 0.5 1.5 24 0.25 .0 0 0 26.25 NW 1. 3.25 7-.5 1.25 0 0 0 23 NNW .0 0.75 1.75 0.25 0 0 0 2.75 TOTAL 8.25 53.5 183.75 63.5 1.75 0 0 310.75 Second Quarter 2012 Stability Class A Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.25 7.25 6:.5 9.5 1..5 0 25 NNE 0 0 7,5- 40 23.25 6.25 2 79 NE 0 0.5 27 37.25 3.5 0 0. 68.25 ENE 0 1.2.5 24 8.5 ,.0 0 0O 33.75 E 10 1.25 24 2.75 0 .0 0,. 28 ESE 0 0.75 1.6 11.25 0.75 0 0 28.75 SE 0 1.25 12.25 4.75 0.5 0 0O 18.75 SSE .0 0.25 5.5 14.5, 4.2.5 0.75'.) 0 25.25 S 0 0.7.5 2.75 4.1 6.75 1.75 0 16 SSW .0 -0 *0 ,0 2.5 1.5 0. 4 SW 0 :1 1.25 2.25 3.75 0.75 0, 9 WSW '0 1.5 2.25 9.75 2 0 0 15.5 W .0 0.75 5 21.25. 7.5 0.25 0 34.75 WNW 0 0.25 7 12.5 17.25 1 0 38 NW 0 0.25 2.75 13.5 6.5 0 0 23 NNW 0 .3 3 0 11 0 0O 17 TOTAL 0 10.25 151 202.75 85.5 12.5 2 464 Page A5 ofAl5

APPENDIX A I Kewaunee Power Station 2012 Meteorological Data Stability Class B Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0.25 1 0 0 0 1.25 NNE 0 0 0.25 7.75 4.25 2.25 3.25 17.75 NE 0 0 3.75 1.75 0 0 0 5.5 ENE 0 0 2.5 2.25 0 0 0 4.75 E 0 0 2.25 0 0 0 0. 2.25 l ESE 0 0.5 0.5 0 0 0 0 1 SE 0 0.25 2 0 0.75 0 .0 3 SSE 0 0.5 1.5 1.75 0 0 0 3.75 S 0 0.5 1 0.25 1 0.25 0.- 3 SSW 0 0.25 1.25 1 .0 0 0 2.5 SW 0 0 0 0.5 0 0.5 0 01 WSW 0 0 0 0.75 0 0 0 0.75 W 0 0 0.25 1.75 3.75 0 0 5.75 WN W 0 0 1 4.25 1.5 0 0 6.75 i NW 0 0 1 5.25 0.25 0 0 6.5 NNW 0 0 0.25 2.25 1.25 0 0 3.75

TOTAL 0 2 17.75 30.5 12.75 3 3.25 69.25 Stability Class C i Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0.5 0.5.

NNE NE 0

0 0.5 0 2.5 3.75 7.5 6.5 3.25 4.25 0 0 0

0 0

13.25 1

15 3

ENE 0 0 4.75 3.75 0 0 .0 8.5 E 0 0 3.25 1 0 0 0 4.25 ESE 0 0 1.75 0.75 0 0 0 2.5 SE 0 0.25 4 0.5 0 0 SSE S

0 0

0.75 0 0.75 2 3.75 1.75 0.25 0.75 0

0 0

4.75 6.75 3.25 U

SSW 0 0 1.5 0.25 0 0 0 1.75 WSW SW 0 0

0 0

0.5 0.5 0.75 1.25 0.25 0 0, 0.25 0

0 1.25 2.25 U

W 0 0 0.75 2. 0.5, 0 0 3.25 WNW 0 0 1.25 2.75 5.5, 0.75 0. 10.25 l NW 0 0 1.25 8.25 0 0 0. 9.5 NNW 0 0 0.75 2.5 0 0 0 3.25 TOTAL 0 1.5 29.75 43.75 14.75 1 0 ,, 90.75 Page A6 of A15

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Stability Class D Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 3.25 7.5 1 0 0 11.75 NNE 0 0.5 .13. 27.5 14.25 0.75 0 56 NE 0 1.25 19 4.5 0.5 0 0 25.25 ENE 0 1 9 2.25 0 0 0 12.25 E 0 2.25 4 1.75 0 0 0 8 ESE 0 1.5 4.5 3.5 0 0 .. 0 9.5 SE 0.25 1.5 9 0.75 0 0 .0 11.5 SSE 0.25 1 8.5 9.5 1.25 0 0 20.5 S 0 1 6.25 11 1.5 0 0 19.75 SSW 0 0'25 3.25 3.75 0 0 ,0 7.25 SW 0 0.25 1.25 2.25 0 0.75 0 4.5 WSW 0, 1 1.25 4.75 0 0.5 0:5 8 W 0 2.5 3.25 6.25 0.25 0.5 0.75 13.5 WNW 0 1.25 2.75 5 0 0.25 ,0 9.25 NW 0 0.75 4.2,5. 1.75 0 0 Q 6.75 NNW 0 1 6.25 4.75 .0 0 0 12 TOTAL 0.5 17 98.75 96.75. 18.75 2.75 1.25 235.75 Stability Class E Wind Direction CALM. 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1.75 16.75 5.5 0.25 0 0 24.25 NNE 0 1.75 18.75 9.75 1.75 , 0 0. 32 NE 0 1.25 21.25 3 0.25 0 0.. 25.75 ENE 0 3.5 7.75 0.75 0 0 '0 12 E 0, 4.75 5.75 0.5 0 0 0 11 ESE 0 5.75 11.75 1 0 0 0 18.5 SE 0: 4.25 12.5 1 0.5 0 0 . 18.25 SSE 0, 3.75 9.5 11.25 1.75 0 0 26.25 S 0 5.5- 17 31.75 8.5 0.5 0 63.25 SSW 0 1.25 20.25* 10 4 0 0 35.5 SW 0' 2.25 3.75' 1.75 0.25 0 0... 8 WSW 0 0.75 2.25 7 0 0 ,0 10 W 0 1.25 5.25 8.25 0 0 0 14.75 WNW 0 3 10.25 16.25 0.25 0 0 29.75 NW 0 2.25 7.5 6.75 0.25 0.25 0 17 NNW 0- 0.25 17 6.25 0 0 0 : 23.5 TOTAL 0 43.25 187.25 120.75 17.75 0.75 0 369.75 Page A7 of A15

APPENDIX A Kewaunee Power Station 2012 Meteorological Data I

Stability Class F I

Wind Direction CALM 1-3 4-7 19-24 >24 I

8-.12 13-18 TOTAL NNE N 0 0

1.25 2.75 7.5 7.75 4.75 1.5 0.25 0.25 0 0

0 1 .175 12.25 I NE 0 2.75 8 0.25 0 0 0 11

.1 ENE E

0 0 1.75 4.25 1.75 0.5 0.5 0

0 0

0 5.75 4

I ESE 0 2 3.25 0 0 0 0 5.25 SE SSE 0

0 2

4.5 3.75 15.5 0.75 14

.0 15.

0 0

6.5 49 I

S 0 4.25 20.5 18.25 0.5 0.25 0 43.75 SSW SW 0

'0 3.75 4.5 25 7.25 2.5 0.75 0

0 0.25 0

0 0

31.5 12.5 I

WSW 0 2 12.25 3 0 0 0 17.25 WNW W 0 0

5 2

14.5 7 6.5 4 0.25 0

0 0

23.75 15.5 I

NW 0 NNW TOTAL 0

0 2.25 3.5 45.25 5.5 16.25 160 4.25 3.75 65.25 16.25 0

0 0

0 0.5 0

0 0

12 23.5 287.25 I

Stability Class G I

Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL I

N 0 NNE NE 0

0 2.5 1.25 4.25 8.5 7.25

.3 0.5 0

1 0.

0 0

11.5 4.25 12.5 I

ENE ESE E

0.5 0.25 0

0.25 1.25 2

5.25 7.75 11.25 0.5 1

0 0

6.5 11 I 1.25 0.5 0. 0 14.25 SE SSE 0

0 2.25 3.25 9.5 41.25 1.25 31.5 0.75 12 6

6 0

0 13.75 94 I S 0.25 10.5 63 53.25 6.75 0.75. 0 134.5 SSW SW 0.25 0

10 14 25.5 18.25 2.5 0

0 0,

0 0

38.25 32.25 I

WSW 0 15 21.25 4 0 40.25 WNW W 0 0

7.25 9

42.75 37.5 8.25 0

0 0

0 51 54.75 I

NW 0 5 16.75 10.5 20 0 32.25 NNW TOTAL 1.25 0

92.75 5 22 340.75 10.25 126.75 0

20 6.75 0

0 0

37.25 588.25 I

Page A8 of A15 I

I

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Third Quarter 2012 Stability Class A Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.25 3.25. 0.75 0.75 0 0 5 NNE 0 0 6.75 10 3.5 0 ,0 20.25 NE 0 0 24 6.75 0 0 0, 30.75 ENE 0 0.25 11.5 8.5 0 0 0 20.25 E 0 0 15.25 11.75 0 0 0. 27 ESE 0 0.5 17.25 0.25 0 0 .,0 18 SE 0 0.75 19.5 .2 0 0 0 22.25 SSE 0 0.25 7.5 13.25 0.75 0 0 21.75 S 0 0.25 1 4.25 2.75 0 0 8.25 SSW 0 0.25 2.5 4.25 0, 0 0 7 SW 0 1.25 6.5 :9 3.25 0 0 20 WSW 0 0 9.75 12.25 0 0 0 22 W 0 0.25 .7 6 0.25 0 0 13.5 WNW 0 0.75 13.25 12.7.5 0 0 26.75 NW 0 0.75 10.75 13.75 0.25 0 10 25.5 NNW 0 0.5 9.25 ... 5 1.75 .0 0 16.5 TOTAL 0 6 165 120.5 13.25 0 0 304.75 Stability Class B Wind Direction CALM 1-3 4-7.,. , 8-12 13-18 19-24 >24 TOTAL N 0 0.25 0.5 1.75 0 0 0 2.5 NNE 0 0.25 2.75 5.75 - 6- 0 .0. 14.75 NE 0 0 6.25 0.5. 0, 0 ,0 6.75 ENE 0 0 4 0.25. 0 0 .0 4.25 E 0 0.25 3.25 1 0 0 :01 4.5 ESE 0 0. 1.5 0. 0 0 0. 1.5 SE 0 0, 2.75 0.25 0 0.. 3 SSE 0 0 1.5 2.25 0.5 0- 0 4.25 S 0 0 0.5. 0 1 0 0-1. 1.5 SSW 0. 0 1.25 0.5 0, 0 0 1.75 SW 0 0.25 0.75 0 0. 0 0 1 WSW 0 0.5. 2.75 3.25 0 0; 0 6.5 W 0 0 3.75 2.25 0 0 0 6 W/NW 0 0 3.75-. 2 0.25 0 0 6 NW 0 0.25 0.5 1.5 0 0 0..,

2.25 NNW 0 0 0.75 1.5 0 0 0 2.25 TOTAL 0 1.75 36.5 22.75 7.75 0 0 68.75 Page A9 of Al5

APPENDIX A Kewaunee Power Station 2012 Meteorological Data U

Stability Class C I

Wind Direction I CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL NNE N 0 0

0 0

0.75 2.75 1.5) 3 0.25 1.75 0.75 0 0 0

2.5 8.25 I NE 0 0.25 9.5 1.5 0 0 0 11.25 ENE E

0 0 0.25 0

3.75 4 2.5 2.25 0

0 0

0 6.5 6.25 I

ESE 0 0 3.75 0 0 0 0 3.75 SE SSE 0

0 0

0 3.25 3.25 1.75 0

0.25 0 0 0

0 0

3.25 5.25 I

S 0 0.25 0.75. 1.5 0.25 0 0 2.75 SSW SW 0

0 0.25 0 1.25 0.75 0.5 1

0.25 0 0 0

0

.0

.2.25 1.75 I

WSW 0 0.25 2 2.5 0 0 0 4.75 WNW W 0 0

0.5 0

3.75 3.25 0.25 1.5 0

0 0

'0 0

0 4.5 4.75 I

NW 0 0 1 2.5 0 0 0 3.5 NNW TOTAL 0

0 1.75 0 0.5.

44.25 23.25 1 0.25 3 0.75 0 0 0

1.75 73 I

Stability Class D I

Wind Direction CALM 1-3 4-7 8-12 13-1.8. 19-24 >24 TOTAL I

0 NNE N

NE 0

0 0

0.5 0.75 0

3.5 9

1,7 6.2.5 11.5 7

8.25 12.5 0.25

.2

.0 0

0.25 0

18.5 35.25 25 I

ENEE 0

.0 0.5 0.25 14 4.5 9.25 2.5

-0 0

0 0 '0 0 23.75 7.25 I ESE 0 6.75 0.5 0 0 0 8.25 SE SSE 0

0 0.5 8.5 12.5 0.75 12

.0 1.5 0

0 .0 0 10.25 26.5 I S 0 1.25 4 13.5 0.7.5 0 0 19.5 SSW SW 0

0 0.25 0 4.75 4.5 2.25 5 1.25 0.5 0

0 0

0 11 7.5 I

WSW 0 1.5 3.75 3.75 0.5 0 0 9.5 WNW W 0 0

0.25 0.5 9.25 5.5 4.75 2 0 0

0 0

0 0.

11.5 10.75 I

NW 0 0.25 4 8.25 0.25 0 0 12.75 NNW 0 0 4.75 9 0 0 0

13.75 TOTAL 0 8.5 116.25 98.25 25.75 2 0.25 251 I Page AIO of A15 I

I

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Stability Class E Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2.25 19.5 9.5 0.25 0 0 31.5 NNE 0 1 16.75 20.75 1.5 0.5 0 40.5 NE 0 3 19.75 2.25 0 0 0 25 ENE 0 2.75 11 3.25 0 0 0 17 E 0 3 4.75 0.75 0.25 0 0 8.75 ESE 0 1.75 6.5 1.25 0 0 0 9.5 SE 0 2.5 9 0.5 0 0 0 12 SSE 0 2.5 17.5 16.75 3.25 0 0 40 S 0 4 19 22.5 1.5 0.75 0 47.75 SSW 0 3.5 2715 11.5 0.5 0 0 43

.9 SW 0 2.5 3 0.25. 0 0 14.75 WSW 0 1.75 8.5 4 1.25 0 0 15.5 W 0 2.25 7.75 0.75 0 0 0. 10.75 WNW 0 1.75 14 2.75 0 0 0 18.5 NW 0 0.25 11.5 8.75 0.25 0 0 20.75 NNW 0 2 18.75 220.75 15.75 1 0 0 37.5 TOTAL 0 36.75' 124' 10 1.25 392.75 Stability Class F Wind Direction CALM 1-32 4-7 8-12. 13-18 19-24 >24 TOTAL 3.5 211 .0 N 0 5.25 0.25. 0 30 NNE 0 2.25 8.75 4.25 0.25 0 0. 15.5 NE 0 2.75 0.5 .0 0 .0 14.25 ENE 0 2.25 6.25 1 .0 9.5 1.25 0.75 0

0.0 0 2

E '0 0 0 ESE 0 2 2 0.25 .0 0 0 4.25 SE 0 1.254. 3.5 0 0 0 4.75 SSE 0 7 12.25.. 0.75 0 0 24 S '0 7.75 27.75 11 0.5 0 0 47 SSW .0 8.5 64.75 2.75 0 0 10 76 SW 0 7 14.25 2. 0." .0 0 23.25 WSW 0 3.75 10.25 4.25 0.25 0 18.5 W 0 2.5 1.3 2.25 0.25 0 18 0

WNW 0 0.75 21.75, 3.75 0 0 .0 26.25 NW 0 2.5 14.5.. 5.25 0.25 0 0 22.5 NNW 0 3.25 23.5 1.75 0.25 0 0 28.75 TOTAL 0 55.25 250 56.5' 2.75 .364.5 Page All ofAl5

APPENDIX A i Kewaunee Power Station 2012 Meteorological Data Stability ClassGG Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 3

AA N 0 .2 21.5 3 0 0 0 28.75 NNE NE

.0 0 1.75 2 4.25 7.25 6.25 0.5 2

0 0

0 14.5 9.5 3

ENE 0 0.75 2 0.5 0 :0 0 3.25 E 0 1.5 1.5 0.25 0 0 0 3.25 ESE 0 1 1 0 0 0 0 2

.SE 0 1.75 4.75 0.5 0 0 0 7 SSE 0 4 17.75 14.25 1.5 0 0 37.5 I S .0 10 43.75 12.75 0.25. 1.25 .0 68 SSW 0.25 17.5 41.75 0.5 0 0 0. 60 SW 0 .18 47 0.25 0 0 0. 65.25 WSW 0 21 65.5 5.25 0 0 0 91.75 W 0 17.25 82.75 7.75 0.25 0 0 108 WNW .0 20.25 52.75 2.5 .0 0 0 75.5 NW 0 24.75 52.25 5.5 0 0 0 82.5 NNW 0 24.75 41.75 3 0 0 0 69.5 TOTAL 0.25 170.5 487.5 62.75 4 1.25 0 726.25 I

Fourth Quarter 2012 Stability Class A i Wind Direction CALM 1 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.5 6.5 6.25 5 5 1 24.25 NNE .0 0 6.75 8.25 4.75 1.5 NE ENE 10 0

0.25 0.5 7..5 4.75 3.25 13.5 9.5 7.5 1.75 0

.0 0

0 21.25 20.5 28 3

E 0 1 5 8.25 2.75 0.5 0 17.5 ESE 0 0.5 2 6.75 2 0 0 11.25 SE "0 1.75 .2 0.75 4.25, '0 0 8.75 SSE 0 1.25 3.25 8.5 1.5 0 0 14.5 S 0 0 4 5.75 6.5 1.25 0 17.5 SSW 0 0 6 8 3 0 0.25 17.25 SW 0 0.25 3.5 11.75 2.75 0 0 18.25 WSW W

0 0

0.5 0.25 9.2.5 6.25 3.5 9.5 16.25 2

0.75 0 0 0

15.25 33 U

WNW 0. 0 5-5 6.25 3.25 1 0 16 NW 0 0 3 18.25 3 4.5 0 28.75 NNW 0 0.5 5.25 TOTAL 0 7.25 80.5 18 136.5 6.5 80.5 1.25 17.5 1.25 2.5 32.75 324.75 3 Page A12 of A15 I

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Stability Class B Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.25 4.5 6 2.5 2.5 0 15.75 NNE 0 0 3 3 0.5 1.25 0 7.75 NE 0 0 4.25 0 0 0 0 4.25 ENE 0 *0 1 2.25 1 0 0 4.25 E 0 0.25 0.5 8 3.75 0 0 12.5 ESE 0 0 0 2.5 0 0 0 2.5 SE 0 0.25 0 3.75 0 0 0 4 SSE 0 0.25 0 2.25 3 0 0 5.5 1S 4

'0 0 1.75 2.5 0 0 8.25 SSW 0 0.5 4.75- 3.25 1.25 *0 0 9.75 SW 0 0.25 3.75 0.75 0.25 0 0 5 WSW 0 0.5 2.75 2 2 ~0 0 7.25

W 0 3.25 1.25 1.25 0.5 7.25 0

WNW 0 -1 3.5 4 0.75 0 0 9.25 NW 0 1.75 0.5- 7 1.5 0 0 10.75 NNW 0 2 4.75 11.25 2.25 0 0 20.25 TOTAL 0 8 38.25 61.25 22.5 4.25 134.25 Stability Class C Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 7.75 12.75 3 0.75 , '. .0 24.25 NNE 0 .0 2.75 -.3, 0.5 0.25 1.25 7.75 NE 0 ,0 2.75 0 0 .0 0 2.75 ENE .0 0 1 1.5 0.5 0 0. 3

,E 0 0.5 0.75. 8.25 1.5 0 '0 11 ESE 0 0.25 1.25 0 0 0 0 1.5 SE .01 0 0 5.25 0 5.25 SSE .0 0.5 0.25 0.75 3.25 0.25 0 5 S .0 0.5: 1.5 6 4.5 .0 0 12.5 SSW .0 1.25 4.75 3 2.75 0 0 11.75 SW 0 0. 0.75 2 0 0 0 3.75 WSW 0 0.75 2.75 2.75 .3 0 0 9.25 W 0 0.75 2 1.5 1.25 0 0 5.5 WNW 0 0 3.25 1.75 0 0. 9 NW 0 0.5 0.5,' .3 2.75 0 .0 6.75 NNW 0 0 3.75 8.5 6.5 4.25 0., 23 TOTAL 0 6 35.75 62.25 31.25 5.5 1.25 142 Page A13 ofAl5

APPENDIX A 3 Kewaunee Power Station 2012 Meteorological Data Stability ClassDD Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0.5 10 31 12.25 4.5 1.5 59.75 NNE 0 0 2.5 9.25 0 0.25 1.75 13.75 NE 0 0 4 3.25 0 0 0 7.25 ENE 0 0.25 1.25 1.5 0.5 0 0 3.5 E 0 0.75 1.5 7.25 8.5 2 0 20 ESE 0 0.5 1.25 3.25 1 2.5 0 8.5 SE 0 0.75 0.75 0.75 10.25 2 0 14.5 SSE 0 0.5 4 7.5 11.25 0.75 0 24 S 0 0 6.25 22.75 10 0 0 39 SSW 0 2 27.5 8.75 1.25 0 0 39.5 WSW SW 0 0

1.5 4.5 11.25 6.5 5.75 6 0.5 2

0 0

19.25 18.75 3

W 0 5.75 18.75 14 6 1.75 0 46.25 WNW 0 4 17.25 15.25 1 0 0 37.5 I NW 0 0.5 13.5 8.25 4 0 0 26.25 NNW 0 0.75 21.25 35.75 9.5 12.25 0.5 80 TOTAL 0 22.25 147.5 180.25 78 26 3.75 457.75 Stability Class E 3 Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2.75 8.75 I7' 0.75 0 0 29.25 NNE 0 0.5> 1.5 3.5 1.5 0 0 7 NE ENE 0

0 0.25 0 1.25 0.5 0.25 0

0 0

1.5 0.75 3

E 0 0.25 0 0 0 0 .0 0.25 ESE SE 0

0 0.5 1.25 2

1 4.5 0

0.25 0 0 1

0 0

2.5 8

I SSE 0 0.5 3.5 7.25 6.5 1.25 0 19 SSW

S 0 0

2.75 4

16.25 38.5 13 34 1.25 0.25 0

0 0

0 33.25 76.75 I

SW 0 3 16.5 13 0 0 0 32.5 WSW 0 3 13 10.25 0.75 0 0 27 W 0 4.25 9 34 5.75 2.25 0 55.25 WNW .0 1.75 27.25 15.25 0.25 0 ~I 0 44.5 NW 0 0.75 23.5 12 0 0 0 36.25 NNW 0 3 16.5 27.75 0 0 0 47.25 TOTAL 0 28.5 179 191.75 17.25 4.5 0 421 3 Page A14 of AI'5

APPENDIX A Kewaunee Power Station 2012 Meteorological Data Stability Class F Wind Direction CALM 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 6.75 4.5 0 0 0 11.25 0 0.25 0.75 0 0 0 1 NNE 0 NE 0 0 2.25 0.25 .0 .0 0 2.5 ENE 0 0.25 0.25 0 0 0 0 0.5 E 0 0 0 0 0 0 0 0 ESE 0 0.25 0 0 0 0 0 0.25 SE 0 0.25. 1.25 0 0 0 0 1.5 SSE 0 1 0.25 1.75 1.5 0 4.5 4.5 18.75 S 0 2.25 9.75. 2.25 0 0 3.5 23 5 0 0 31.5 SSW 0 0 SW 0 0.25 10 0.75 0 0 0 11 WSW 0 1.75 15.25 8.25. 0.25 0 0 25.5 W 0 1.75 23.5 5.75 0.5 0 0 31.5 WNW .. 0 3.5 22.25 7.75 1.5 0 0 35 NW ,0 2.25 11 .5 1 0 0 19.25 NNW 0 0.25. 18.05 - 8.25 0 0 .00 27.25 17.25 144.5 50.25 9.25 0 221.25 TOTAL 0 Stability Class G Wind Direction CALM 1-3 4-7.1-,. 8-12 13-18: 19-2.4 >24 TOTAL N 0 2.75 10.5 2.5 *1 0.25 0 17 NNE 0 1.25 3,5 9.25 8.75 1.75 0. 24.5 "0 "

NE 0 .2 2.25. _.0 0 4.25 1..s) 0; ENE ,0 1.75 0. .0 0 3.5 E 0 1.5 2.75 0.25 :0. .,0 *0 4.5 ESE 0 0.75 5.75 1.75 -0 0 0 8.25

.SE 0 81 5.5 0.75 1 0 0 8.25 1 ,1 25 SSE 0 15.75 6.5 0.75 Ss'.0 1.5 18.75 6.25 2 .00. 29.5 4.25,., 11 :0 ,0 55 SSW 0 36.25 3.5 .'0 SW 0 33:5 3.5 0.5 44.5

0 WSW 0 10.75 31 1.25 1.25 0 *0 44.25 W 0 8.5 25 3.5 3.5 0 0 40.5 WNW 0 4.5 31.75 11.25 8.75 0 0 56.25 23.5 16.75 4.5 0 46.5 NW 0 1.75 0 NNW 0 7.5 19.5 10.75 3.5 0 0 41.25 TOTAL 0 57.75 267 85.25 38 ,5 453 Page AI5 ofAl5

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I I Appendix B I

Kewaunee Power Station 3 Offsite Dose Calculation Manual (ODCM)

Revision 14 I April 18, 2012 U

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Dominion Energy Kewaunee, Inc.

Kewaunee Power Station OFFSITE DOSE CALCULATION MANUAL (ODCM)

Revision 14 DATE: April 18, 2012 Approved By: James M. Hale 04-06-2012 Manager - Radiological Protection and Chemistry Date Approved By: Thomas L. Breene 04-09-2012 Manager - Regulatory Affairs Date Reviewed By: Jeffrey T. Stafford 04-17-2012 Facility Safety Review Committee Date Approved By: Roy L. Simmons 04-18-2012 Site Vice President Date

KEWAUNEE POWER STATION ODCM TOC OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

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

11.0 INTRODUCTION

11.0-1 1 12.0 (Not Used) 3 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 3 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 3 13.2.1 13.2.2 13.2.3 Gaseous Effluents Dose Rate Gaseous Effluents Dose - Noble Gas Gaseous Effluents Dose - Iodine and Particulate 13.2.1-1 13.2.2-1 13.2.3-1 I

13.2.4 13.2.5 Gaseous Radwaste Treatment System Gas Storage Tanks 13.2.4-1 13.2.5-1 3 13.3 INSTRUMENTATION 13.3.1 13.3.2 Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.1-1 13.3.2-1 3

13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 3 13.4.1 Radioactive Effluents Total Dose 13.4.1-1 I

3 ii I

KEWAUNEE POWER STATION ODCM TOC OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 Radwaste Treatment Systems 15.1-1 15.2. Radioactive Effluent Release Report 15.2-1 15.3. Special Reports . . , 15.3-1 IIi

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM TOC Revision 14 I

April 18, 2012 I

PART II CALCULATIONAL METHODOLOGIES

'PAGE I 1.0 LIQUID EFFLUENT METHODOLOGY 1.1 1.2 Radiation Monitoring Instrumentation and Controls Liquid Effluent Monitor Setpoint Determination 1.0-1 1.0-1 I

1.3 Liquid Effluent Concentration Limits - 10CFR 20 1.0-4 1.4 1.5 Liquid Effluent Dose Calculation - 10 CFR 50 Liquid Effluent Dose Projections 1.0-5 1.0-7 I

1.6 Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams 1.0-8 2.0 1.7 Heating Boiler Blowdown Operation with Primary-to-Secondary Leak GASEOUS EFFLUENT METHODOLOGIES 1.0-9 3

2.1 2.2 Radiation Monitoring Instrumentation and Controls Gaseous Effluent Monitor Setpoint Determination 2.0-1 2.0-3 I

2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 2.0-5 2.4 2.5 Gaseous Effluent Dose Calculations- 10 CFR 50 Gaseous Effluent Dose Projection 2.0-7 2.0-10 I

2.6 Environmental Radiation Protection Standards 40 CFR 190. 2.0-11 2.7 2.8 Incineration of Radioactively Contaminated Oil Total Dose 2.0-11 2.0-11 I APPENDICES I Appendix A Technical Basis for Effective Dose Factors Liquid Radioactive Effluents ...... A-1 Table A-1 Table A-2 Adult Dose Contributions Fish and Drinking Water Pathways ..... A-5 Adult Liver and Total Body Dose Assessment .............. A-6 I

Appendix B Technical Basis for Effective Dose Factors - Gaseous Radioactive Effluents .. B-1 Table B-1 Effective Dose Factors - Noble Gases .................... B-5 I Appendix C Evaluation of Conservative, Default Effective EC Value for Liquid Effluents.. C-1 Table C-1 Calculation of Effective EC (ECe) . . "."."........................ C-4 I Appendix D Onsite Disposal of Low-Level Radioactively. Contaminated Waste Streams ..... D-1 I

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KEWAUNEE POWER STATION ODCM TOC OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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- 13.3.2-5 PART II CALCULATIONAL METHODOLOGIES 1.1 PARAMETERS FOR LIQUID ALARM SETP.OINT, DETERMINATIONS 1.0-11 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTORS 1.0-12 1.3 BIOACCUMULATION FACTORS 1.0-14 2.1 DOSE FACTORS FOR NOBLE GASES, 2.0-15 2.2 PARAMETERS FOR GASEOUS A.LARM SETPOINT DETERMINATIONS 2.0-16 2.3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS 2.0-17 2.4 Ri INHALATION PATHWAY DOSE FACTORS-ADULT 2.0-18 2.5 Ri INHALATION PATHWAY DOSE FACTORS-TEEN 2.0-20 2.6 R, INHALATION PATHWAY DOSE FACTORS-CHILD , 2.0-22 2.7 Ri INHALATION PATHWAY DOSE FACTORS-INFANT 2.0-24 2.8 Ri VEGETATION PATHWAY DOSE FACTORS-ADULT 2.0-26 2.9 R.VEGETATION PATHWAY DOSE FACTORS-TEEN 2.0-28 2.10 Ri VEGETATION PATHWAY DOSE FACTORS-CHILD 2.0-30 2.11 R, GRASS-COW-MILK PATHWAY DOSE FACTORS-ADULT , 2.0-32 2.12 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-TEEN 2.0-34 2.13 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-CHILD 2.0-36 2.14 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-INFANT 2.0-38 2.15 Ri GROUND PLANE PATHWAY DOSE FACTORS 2.0-40 V

KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM T-O Revision 14 April 18, 2012 3

LIST OF FIGURES PAGE PART I - RADIOLOGICAL EFFLUENT CONTROLS 3 14.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENT 14.1-2 PART II CALCULATIONAL METHODOLOGIES 3 1 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM 1.0-10 2 GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM 2.0-13 I 3 SIMPLIFIED HEATING BOILER FUEL OIL PIPING SYSTEM 2.0-14 3 I

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

I KEWAUNEE POWER STATION ODCM 11.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

11.0 INTRODUCTION

The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. 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 Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively.

I 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. Long term cumulativeeffects are usually calculated I

through computer programs employing approved methodology, often using real-time meteorology in the case of gaseous effluents. Other computer programs are utilized to routinely estimate the doses due to radioactivity in liquid effluents'. Manual dose calculations are I

performed when computerized calculations are not available.

The stated in this manual is acceptable for use in demonstrating compliance with methodology1OCFR50, 10CFR20.1302; Appendix I; and 40CFR190.

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. . 3 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 10CFR50.36a and Appendix I for demonstrating radioactive effluents areALARA.

11.1 Change Process I 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.

I 10 11.~0-1 1

KEWAUNEE POWER STATION ODCM 13.0.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 13.0 USE AND APPLICATION 13.0.1 Definitions

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

Terms defined in both Kewaunee Technical Specifications and 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 ACTION Action shall be that part of a Normal Condition which prescribes remedial measures required under designated conditions.

CHANNEL CHECK CHANNEL CHECK is a qualitative determination of acceptable FUNCTIONALITY by. observation of channel behavior during operation. ..This . determination shall include, where -possible, comparison of the channel indication with other indications derived from independent. channels measuring the same variable.

?I , a A, ikIr ii--i * .

kUflMINNI"LL FUNCTIONA L 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 CALIBRATIC N CHANNEL-. CALIBRATION consists, of the adjustment of channel output as necessary, such that it responds with acceptable, range and accuracy, to known values of the parameter that the channel monitors!.

Calibration shall encompass the entire channel, including alarm and/or trip, and shall be deemed to include the CHANNEL FUNCTIONAL TEST.

FUNCTIONAL/

FUNCTIONALITY As defined in the Technical Requirements Manual GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM is any system RADWASTE * . designed and installed to reduce radioactive gaseous effluents by TREATMENT collecting off-gases from the primary system and providing for delay or SYSTEM holdup for the purpose of reducing the total radioactivity released to the environment.

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

13.0.1 - 1

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.1 Revision 14 I

April 18, 2012 OCCUPATIONAL OCCUPATIONAL DOSE means the dose received by an individual in I

DOSE the course of employment in which the individual's 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 I

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, i

from voluntary participation in medical research programs, or as a OFFSITE DOSE MEMBER OF THE PUBLIC.

The OFFSITE DOSE CALCULATION MANUAL shall contain the I

CALCULATION current methodology and parameters used in the calculation of offsite MANUAL doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip I

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 TS 5.6.1 and TS 5.6.2.

I ODCM NORMAL CONDITIONS (DNC)

Specify minimum requirements for ensuring safe operation of the Unit.

The Contingency Measures associated with a DNC state I Nonconformances that typically describe the ways in which the requirements of tne.DNC can fail to be met. Specified with each stated Nonconformance are Contingency Measures and Restoration Time(s).

I ODCM VERIFICATION REQUIREMENTS Verification requirements are requirements relating to test, calibration, or inspection to assure that the necessary FUNCTIONALITY of systems and components are maintained, that facility operation will be I

(DVR) maintained within the current licensing basis, and that the ODCM Normal Condition (DNC) for operation will be met. I PROCESS The PROCESS CONTROL PROGRAM shall contain the current CONTROL PROGRAM 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 I

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 I

governing the dispdsal of the tadioactiye.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 I

" retained as required by the quality assurance program. The documentation shall contain:

a. Sufficient information to support the change together with the U

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 FSRC.

I 13.0.1 -2 I

KEWAUNEE POWER STATION O.DCM 13.0.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 - PUR(3ING 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.

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

MONITORING MANUAL (REM M)

SITE BOUNDAFRY The SITE BOUNDARY shall be that line beyond which the land is neither owned, leased, .nor otherwise controlled by the licensee.

SOURCE CHE(CK A SOURCE CHECK.shall bethe qualitative assessment of channel response whed the channel sensor is exposed to a source of increased radioactivity. .

UNRESTRICTE-D An UNRESTRICTED AREA-shall be any areaat or beyond the SITE AREA BOUNDARY, access to which is'not cdntrolled 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 ihdustrial, Commercial, institutional, and/or recreational purposes. (See Plant. Drawing A-408)

A VENTILATION EXHAUST TREATMENT SYSTEM is any system VENTILATION designed and installed to reduce ga'seou-s radioiodine or radioactive EXHAUST TREATMENT material in particulate f6rm)irin effluents by passing ventilation or vent SYSTEM exhaust gases throUggh charcoal and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. 'Such a system is not considered to have, any effect on noble gas effluents. Engineered Safety Feature atmospheric cleanup systems (i.e., Auxiliary Building special ventilation, Shield Building ventilation, spent fuel pool ventilation) are not considered to. be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING is the controlled process of discharging air or gas from a VENTING 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.

13.0.1 -3

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.2 Revision 14 I

April 18, 2012 13.0 USE AND APPLICATION I

13.0.2 Logical Cbnnectors I Logical Connectors are discussed in Section 1.2 of the Technical Specifications and are applicable throughout the OFFSITE DOSECALCULATION MANUAL and Bases.

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13.0.2-1 I

KEWAUNEE POWER STATION ODCM 13.0.3 OFFSITE DOSE CALCULATION MANUAL *Revision 14 April 18, 2012 13.0 USE AND APPLICATION 13.0.3 Restoration Times Restoration Times are the same as Completion Times as discussed in Section. 1.3 of the Technical Specifications 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.

13.0.3-1

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.4 Revision 14 I

April 18, 2012 13.0 USE AND APPLICATION I

13.0.4 Frequency I Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases I

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13.0.4-1 I

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KEWAUNEE POWER STATION ODCM 13.0.5 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 13.0 USE AND APPLICATION 13.0.5 ODCM Normal Condition (DNC) Applicability DNC 13.0.5.1 DNCs shall be met during the MODES or other 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 operations. 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; 0 Safety function and events protected against; 0 Probability of needing the safety function; 0 Conservatism and margins; and a Probabilistic Risk Assessment or Individual Plant Evaluation results that determine how operating the plant in the manner proposed will impact core damage frequency.

If this assessment concludes that safety is sufficiently assured, the facility may continue to operate 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.

13.0.5 - 1

KEWAUNEE POWER STATION ODCM 13.0.6 I

OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I 13.0 USE AND APPLICATION 13.0.6 ODCM VERIFICATION REQUIREMENTS (DVR) Applicability i

DVR 13.0.6.1 DVRs shall be met during the MODES or other 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 I

the DNC except as provided in DVR 13.0.6.3. DVR's do not have to be performed on nonfunctional equipment or variables outside specified limits I 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. I 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, I

determination to evaluate the impact on plant safety shall be performed in a timely fashion and in accordance with plant procedures.

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

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I 13.0.6 - 1 I I

KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 (Figure 14.1-1) 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; and

b. 2 X 10-4 pCi/ml total activity concentration for;dissolved or entrained noble gases.

APPLICABILITY: During release via the monitored pathway.

ACTIONS NON-CONFORMANCE: . CONTINGENCY MEASURES RESTORATION TIME A. Concentration of . A.1 Initiate ACTION to restore Immediately radioactive material concentration to within limits.

released in liquid effluents . ....

to UNRESTRICTED AREAS exceeds limits.

B. CONTINGENCY B.1 Initiate a CR In accordance MEASURES with Corrective OR Action Program AND RESTORATION TIME not met.

B.2 Explain in the next Radioactive In accordance Effluent Release Report why with Radioactive the CONTINGENCY Effluent Release MEASURE was not met in a Report timely manner.

13.1.1 -1

KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 VERIFICATION REQUIREMENTS I

VERIFICATION FREQUENCY DVR 13.1.1.1 Perform radioactive liquid waste sampling and activity In accordance with I

analysis. Table 13.1.1-1 I

NOTE -------------------------------------- In accordance with I In this DVR the results of DVR 13.1.1.1 shall be used in accordance Table 13.1.1-1 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.

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I 13.1.1 2 I

KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 13.1.1-1 (Page I of 2)

Radioactive Liquid Waste Sanipling and Analysis LOWER LIMIT OF MINIMUM.

TYPE OF

DETECTION (LLD)

LIQUID RELEASE SAMPLE ANALYSIS ACTIVITY SAMPLE TYPE (a)

TYPE FREQUENCY FREQUENCY ANALYSIS

1. Batch Waste Release Tanks (b)

a. Principal Gamma Emitters(c) Grab Sample Each Batch (h) Each Batch (h) 1 x 10-6 PCi/ml

b. 1-131 Grab Sample Each Batch (h) Each. Batch (h) lx 10-6 pCi/ml Dissolved and

c. Entrained Gases Grab Sample Each Batch (h) 31 days 1 x 10.5 pCi/ml (gamma emitters)

d. H-3 Composite (d) Each batch (h) 31 days 1 x 10"5 pCi/ml

e. Gross Alpha Composite (d) Each batch (h) 31 days 5 x 10-, pCi/ml

f. Sr-89 Composite (d) Each batch (h) 92 days 5 x 10" pCi/ml

g. Sr-90 Composite (d) Each batch (h) 92 days 5 x 10.' pCi/ml

h. Fe-55 Composite (d) Each batch (h) 92 days 1 x 10 p.Ci/ml

2. Continuous Releases (e)

(SG Blowdown)

(TB Sump) (g)

a. Principal Gamma Emitters (c) Grab Sample 7 days 7 days 5 x 10-7 pCi/ml

b. 1-131 Grab Sample 7 days 7 days 1 x 106 PCi/mI Dissolved and

c. Entrained Gases Grab Sample 7 days 7 days 1 x 10.5 pCi/mI (gamma emitters)

d. H-3 Grab Sample 7 days 31 days(f) 1 x 10s pCi/ml

e. Gross Alpha Composite (f) 7 days 31 days(f) 5 x 10.7 pCi/ml

f. Sr-89 Composite (1) 7 days 92 days(f) 5 x 10.' pCi/ml

g. Sr-90 Composite (f) 7 days 92 days(f) 5 x 10.8 ptCi/ml

h. Fe-55 Composite (f) 7 days 92 days(f) 1 x 10- pCi/mI 13.1.1-3

KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 13.1.1-I (Page 2 of 2)

Radioactive Liquid Waste Sampling and Analysis I (a) The LLD is defined, for purposes of these DNC's, 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. . .3 For a particular measurement system, which may include radiochemical separation:

SILD 4.66* Sb, E'V'2.22 x 106 "Y*exp(-At) I Where:

" LLD is the a priori lower limit of detection as defined above,' as 1iCi 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, I 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, k is the radioactive decay constant for the particular radionuclide, and 3

At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y and At should be used in the calculation. 3 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 I 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-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-137, Ce-141, 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 DNC 15.2.

I (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. I (e) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(f) As a minimum, the monthly and quarterly composite samples shall be compromised of weekly grab samples.

(g) During periods of identified primary - to - secondary leakage (with the secondary gamma activity >1.OE-06 pCi/ml), grab I

I samples are collected daily and analyzed by gamma spectroscopy. (Appendix C)

(h) Complete prior to each release.

13.1.1 -4

KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 IL.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its concentration limit in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

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).

13.1.1 -5

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.2 Revision 14 I

April 18, 2012 13.1 RADIOACTIVE LIQUID EFFLUENTS I 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: I

a. _<1.5 mrem to the total body and _<5 mrem to any organ during any b.

calendar quarter; and

_ 3 mrem to the total body and _<10 mrem to any organ during any i

calendar year.

APPLICABILITY: At all times.

I ACTIONS i

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME i

A. Calculated dose to a A.1 Prepare and submit to the 30 days MEMBER OF THE PUBLIC from the release NRC, pursuant to DNC 15.3, a Special Report that, I

of radioactive materials in " (1) Identifies the cause(s) liquid effluents to UNRESTRICTED AREAS exceeds limits. '(2) for exceeding the limit(s) and; Defines the corrective I

" actions that have been take.n to reduce the releases and the I

proposed corrective

, actions to be taken to assure that subsequent I releases will be in compliance with DNC 13.1.2. I i

13.1.2-1

KEWAUNEE POWER STATION ODCM 13.1.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes.

of radioactive materials in contributions from direct liquid effluents exceeds-2 radiation from the units times the limits. (including outside storage tanks, etc.).

AND Immediately B.2 Verify that the limits of DNC 13.4 have not been exceeded.-

C. CONTINGENCY C.1 Prepare and submit to the 30 days MEASURE B.2 and NRC, puýsuantto DNC 15.3, Associated a Special Report, as defined RESTORATION TIME not in 10 CFR 20.2203 (a)(4), of met. 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 "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.

13.1.2 -2

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.2 Revision 14 U

April 18, 2012 VERIFICATION REQUIREMENTS I VERIFICATION FREQUENCY I

DVR 13:1.2.1 Determine cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year in accordance with the I

methodology and parameters in the ODCM.

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13.1.2 -. 3 I I

KEWAUNEE POWER STATION ODCM 13.1.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 BASES This DNC is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix 1,10 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.

13.1.2-4

I KEWAUNEE POWER STATION ODOM 13.1.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.3 Liquid Radwaste Treatment System I

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 I

UNRESTRICTED AREAS would exceed in a 31 day period:

a.

b. -

> 0.06 mrem to the total body; or

> 0.2 mrem to any organ.

I APPLICABILITY: At all times I ACTIONS I

NON-CONFORMANCE CONTINGENCY MEASURES I

RESTORATION TIME A. Radioactive liquid waste I

A.1 Prepare and submit to the 30 days being discharged without NRC, pursuant to DNC 15.3, treatment and in excess of a Special Report that the above limits, includes:

(1) An explanation of why liquid radwaste was being discharged without I

treatment, identification of any non-functional /

inoperable equipment or I

subsystems, and the reason for the non-functional / inoperability, (2) ACTION(s) taken to I

restore the non-functional / inoperable equipment to I

FUNCTIONAL I OPERABLE status, and (3) Summary description of I

ACTION(s) taken to prevent a recurrence.

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I 13.1.3-1 I

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KEWAUNEE POWER STATION ODCM 13.1.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.3.1. Project the doses due to liquid effluents from the unit 31 days to .UNRESTRICTED AREAS in accordance with the methodology and parameters specified in the ODCM.

13.1.3 -2

KEWAUNEE POWER STATION ODCM 13.1.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 I April 18, 2012 BASES I 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, General Design Criterion 60 of Appendix A to 10 CFR Part 50 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 1,10 CFR Part 50, for liquid effluents.

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" I 13.1.3 -3

KEWAUNEE POWER STATION ODCM 13.1.4 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 potablevwater supply and surface water supply in an UNRESTRICTED AREA, excluding tritium and dissolved or entrained gases.

APPLICABILITY: At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.

listed tank.

AND A.2 Initiate measures to reduce 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months content to within the limits.

AND A:3 Describe the events leading to Prior to submittal of the condition in the next Radioactive Radioactive Effluent Release Effluent Release Report. Report VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.4.1 Sample and analyze radioactive liquid located in 31 days during unprotected outdoor liquid storage tanks for level of addition of radioactivity, radioactive liquid to the tanks 13.1.4- 1

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.4 Revision 14 April 18, 2012 1

13.1 LIQUID EFFLUENTS 3 13.1.4 Liquid Holdup Tanks BASES I The tanks listed in this Normal Condition include outdoor tanks that are not surrounded by I 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 Specification 5.5.10.c requires a program to ensure that the quantity of radioactive I material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of any such tank's 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 UNRESTRECTED AREA. Tank quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures." 3 13..4I I

": I I

"" I I

13.1.4 -2I

KEWAUNEE POWER STATION ODCM 13.2.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 noble gases, < 500 mrem/yr to the total body and

< 3000 mrem/yr to the skin and

b. For 1-131, 1-133, 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 A.1 Restore the release rate to Immediately beyond the SITE within the limit.

BOUNDARY due to radioactive gaseous effluents exceeds limits.

B. CONTINGENCY B.1 Initiate a CR In accordance with MEASURES Corrective Action OR Program AND RESTORATION TIME not met.

B.2 Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report CONTINGENCY MEASURE was not met in a timely manner.

13.2.1 -1

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.1 Revision 14 I

April 18, 2012 VERIFICATION REQUIREMENTS 3 VERIFICATION FREQUENCY I DVR 13.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the In accordance with Table 13.2.1-1 I

above limits in accordance with the methodology and parameters in the ODCM.

1 DVR 13.2.1.2 The dose rate due to 1-131, 1-133, tritium and all radionuclides in particulate form with half-lives

> 8 days in gaseous effluents shall be determined In accordance with Table 13.2.1-1 I 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 I

I I

I 1

I I

13.2.1 -2 I,

KEWAUNEE POWER STATION ODCM 13.2.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 13.2.1-1 (Page 1 of 2)

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

TYPE TYPE FREQUENCY ANALYSIS FREQUENCY (a)

1. Waste Gas Storage Principal Gamma Grab Tank Each Tank (d) Each Tank (d) 1 x 104 pCi/ml Emitters (b) Sample

2. Containment Purge Principal Gamma Grab Each Purge (d) Each Purge (d) S10 x0- I.LCi/ml Emitters (b) Sample

3. Auxiliary Building and Containment Principal Gamma Grab Sample 31 days ,31 days 1 X 10 1Ci/ml Emitters (b)

Building Vent Silica Gel,

a. H-3 . Grab 31 days :31 days 1 X 106pCi/mI Sample Charcoal

b. 1-131 Continuous (c) 7 days 3 x 10.12 PCi/ml Sample Principal Gamma Emitters (b) Particulate

c. Continuous (c) 7 days 1 x 10'1 pCi/ml Sample (1-131, Others)

Composite

d. Gross Alpha Particulate Continuous (c) 31 days 1 x 10-11 pCi/ml Sample Composite

e. Sr-89, Sr-90 Particulate Continuous (c) 92 days 1 x 10-" pCi/ml Sample Noble Gases

f. Gross Beta or Noble Gas Monitor Continuous (c) Continuous (c) 1 x 106 pCi/ml Gamma 13.2.1 -3

I KEWAUNEE POWER STATION ODCM 13.2.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

Table 13.2.1-1 (Page 2 of 2)

Radioactive Gaseous Waste Sampling and Analysis I (a) The LLD is defined, for purposes of these DNC's, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD 4 66

. *Sb 6

E'V*2.22 x 10 y exp -At)

Where:

LLD is the a priori lower limit of detection as defined above, as pCi per unit mass or volume, sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, I

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 At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

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

I 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: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65,I Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be 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 ODCM 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, 13.2.2, and 13.2.3.I (d) Complete prior to each release.

1 13.2.1-4

KEWAUNEE POWER STATION ODCM 13.2.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin. This also restricts releases, at all times, for the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/yr. These dose rate limits provide additional assurance that radioactive material discharged in gaseous effluents will be maintained ALARA, and coupled with the requirements of ODCM DNC 13.2.2, 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-21 5 (June 1975).

13.2.1 -5

I Er\WAUNErE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.2 Revision 14 I

April 18, 2012 13.2 RADIOACTIVE GASEOUS EFFLUENTS U 13.2.2 Gaseous Effluent Dose - Noble Gas DNC 13.2.2 The air dose due to noble gases released in gaseous effluents from the unit to areas at or beyond the SITE BOUNDARY (Plant Drawing A-408)

I shall be limited to the following:

a. < 5 mrad for gamma radiation and _<10 mrad for beta radiation during any calendar quarter, and I

b. < 10 mrad for gamma radiation and < 20 mrad for beta radiation during any calendar year. I APPLICABILITY: At all times.

I ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME I

A. The calculated air dose at A.1 Prepare and submit to the 30 days U

or beyond the SITE NRC, pursuant to DNC 15.3, BOUNDARY due to noble gases released in gaseous effluents exceeds limits.

a Special Report that (1) Identifies the cause(s)

I for exceeding the limit(s) and;

..(2) Defines the corrective actions that have been I

taken to reduce the releases and the proposed corrective I

actions to be taken to assure that subsequent releases will be in compliance with DNC 13.2.2.

I I

13.2.2-1 I I

KEWAUNEE POWER STATION ODCM 13.2.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a B.1 . Calculate the annualdose to Immediately MEMBER OF THE a MEMBER OF THE

-PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the units times the limits. (including outside storage tanks, etc.).

AND Immediately B.2 Verify that the limits of DNC 1.3.4 have not been exceeded.,

C. CONTINGENCY C.1 Prepare and submit to the 30 days MEASURE B.2 and NRC., pursuant to DNC 15.3, Associated a Special Report, as defined RESTORATION TIME not 'in 10G CFR 20.2203 (a)(4), of CONTINGENCY MEASURE met. : . 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

'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.

13.2.2 - 2

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.2 Revision 14 I

April 18, 2012 VERIFICATION REQUIREMENTS II VERIFICATION FREQUENCY I

DVR 13.2.2.1 Determine cumulative dose contributions for the current calendar quarter and current calendar year in accordance with the methodology and parameters in 31 days I

the ODCM.

I I

1 I

13.2.2-3 I

I

KEWAUNEE POWER STATION ODCM 13.2.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 BASES This DNC is provided to implement the requirements of Sections JI.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The DNC implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept. "as low as is reasonably achievable." The VERIFICATION REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I.be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The dose calculation methodology and parameters established.in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

13.2.2-4

I KEVVAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.3 Revision 14 I

April 18, 2012 13.2 RADIOACTIVE GASEOUS EFFLUENTS I 13..2. 3 DNC 13.2.3 Gaseous Effluent Dose - iodine, Tritium and Particulate The dose to a MEMBER OF THE PUBLIC from 1-131,1-133, tritium, and I

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:

I

a. _<7.5 mrem to any organ during any calendar quarter, and I

b. _ 15 mrem to any organ during any calendar year.

APPLICABILITY: At all times.

I ACTIONS I NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME I A. The calculated dose from the release of 1-131, 1-133, tritium, and radionuclides A.1 Prepare and submit to the NRC, pursuant to DNC 15.3, a Special Report that 30 days

.I in particulate form with (1) Identifies the cause(s) half-lives > 8 days released in gaseous for exceeding the limit(s) and; i

effluents at or beyond the * :(2) Defines the corrective SITE BOUNDARY exceeds limits.

actions that have been taken to reduce the releases and the I

proposed corrective actions to be taken to assure that subsequent I

releases will be in compliance with DNC

-13.2.3. I, 13.2.3 - 1 I

I

KEWAUNEE POWER STATION ODCM 13.2.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a B.1 Calculate the annual dose.to Immediately MEMBER OF THE a, MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid efflu.ents exceeds 2 . radiation from the units times the limits. " (including outside storage tanks, etc.).

AND B.2 Verify that the limits of DNC Immediately 13.4 have not been exceeded.

C. CONTINGENCY C. 1 Prepare and submit to the 30 days MEASURE B.2 and NRC, pursuant to DNC 15.3, Associated .a Special Report, as defined RESTORATION TIME not". " in' 10 CFR 20.2203 (a)(4), of met. met*CONTINGENCY MEASURE

. .: A.I shall also include the following:

(1) The corrective action(s) to be taken to prevent recurrence of exceeding the limits of DNC 13.4 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.

13.2.3-2

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.3 Revision 14 i

April 18, 2012 VERIFICATION REQUIREMENTS II VERIFICATION FREQUENCY I

DVR 13.2.3.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year for 1-131, 1-133, tritium, and radionuclides in

!I particulate form with half-lives > 8 days in accordance with the methodology and parameters in the ODCM.

I I

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I 13.2.3 - 3

KEWAUNEE POWER STATION ODCM 13.2.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 BASES This DNC is provided to implement the requirements of Sections.ll.C, IIl.A and IV.A of Appendix 1, 10 CFR Part 50. The DNC's 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 DVR's 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 iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

13.2.3-4

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.4 Revision 14 I

April 18, 2012 13.2 RADIOACTIVE GASEOUS EFFLUENTS I 13.2.4 GASEOUS RADWASTE TREATMENT SYSTEM DNC 13.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce I

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 I

be:

a. > 0.2 mrad for gamma radiation; or I

b.

c.

> 0.4 mrad for beta radiation; or

> 0.3 mrem to any organ in 31 day period. (Ventilation Exhaust I

Treatment System only)

APPLICABILITY: At all times. I ACTIONS -

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION B

TIME I

A. Radioactive gaseous A.1 Prepare and submit to the 30 days waste is being discharged without treatment.

NRC, pursuant to DNC 15.3, a Special Report that i

AND includes the following:

Projected doses due to the (1) Explanation of why gaseous radwaste was I gaseous effluent, from the being discharged without unit, at and beyond the treatment, SITE BOUNDARY would (2) Identification of any exceed limits, non-functional /

inoperable equipment or subsystems and the I

reason for the non-functional/

inoperability, (3) ACTION(s) taken to restore the non-functional / I inoperable equipment to FUNCTIONAL /

OPERABLE status, and (4) Summary description of I

ACTION(s) taken to prevent a recurrence. I 13.2.4 - 1

KEWAUNEE POWER STATION ODCM 13.2.4 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.4.1 Project the doses due.to gaseous effluents from each 31 days unit at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

13.2.4-2

I KEWAUNEE POWER STATION ODCM 13.2.4 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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, General Design Criterion 60 of Appendix A to 10 CFR Part 50, 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 I 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.

I 13.2.4 -I

KEWAUNEE POWER STATION ODCM 13.2.5 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 13.2 GASEOUS EFFLUENTS 13.2.5 Gas Storage Tanks DNC 13.2.5 The radioactivity contained in each gas storage tank shall be limited to

<52,000 Curies of noble gasl (Considered as Xe-133)

APPLICABILITY: At all times.

ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits, radioactive material.

AND A.2 Reduce tank contents to within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the limits.

13.2.5- 1

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.5 Revision 14 I

April 18, 2012 VERIFICATION REQUIREMENTS I

VERIFICATION FREQUENCY I DVR 13.2.5.1 Verify quantity of radioactive material contained in each gas storage tank is < 52,000 curies of noble 31.days I

-gases (considered as Xe-133). AND I

NOTE -------

Not required to be performed if the I

most recent Reactor Coolant System specific I

activity DOSE EQUIVALENT 1-131 is

I

-<1.0 pCi/gm I

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the I

tank I

I I

I 13.2.5 - 2 I

I

KEWAUNEE POWER STATION ODCM 13.2.5 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 BASES This verification implements the requirement of Technical Specification 5.5.10.b. which requires a program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of > 0.5 rem to any individual in an UNRESTRICTED AREA, in the event of an uncontrolled release of the tanks contents. Contents of the tank quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, "Postulated Radioactive Release due to Waste-Gas System Leak or Failure."

Radiological analysis for a waste gas decay tank rupture assumes the activity in a gas decay tank is taken to be the maximum amount that could accumulate from operation with cladding defects in 1 percent of the fuel elements. This is at least ten times the expected number of defective fuel elements. The maximum activity is obtained by assuming the noble gases, xenonand krypton, are accumulated with no release over a full core cycle. The gas decay tank inventory is calculated assuming nuclide decay, degassing of the reactor coolant with letdown at the maximum rate, and periodic purging to the gas decay tank. The maximum inventory for each nuclide during the degas and PURGE cycle is given in Appendix D, Table D.7-1. (reference 1)

The resultant dose consequence for this accident is 0.1 rem whole body at the SITE BOUNDARY. Summing the activities in USAR Table D.7-1 (reference 4) results in 42,792.74 curies. Using the noble gas dose conversion factors (DCF) contained in USAR Table D.8-1 (reference 5) referenced to Xe-133 results in a curie content of 52,000 curies when considered as Xe-133. Kewaunee Power Station does not have a calculation correcting the waste gas decay tank activity to a SITE BOUNDARY consequence of < 0.5 rem, therefore by limiting the activity in a waste gas decay tank to that which results in 0.1 rem at the SITE BOUNDARY, the 0.5 rem limit will not be exceeded.

DVR 13.2.5 frequency is modified by a note that restricts performing the verification when additions are made to a tank to only when the reactor coolant system DOSE EQUIVALENT Iodine 131 (DEI-131) activity is greater than 1.0 pCi/gm (microcurie per gram). A calculation has shown that when a 1% failed fuel assumption is used the resultant RCS DOSE EQUIVALENT XE-1 33 activity would be 595 [.Ci/gm (reference 2). Engineering experience is that with 1.0 pCi/gm DEI-131 RCS activity, the associated DEX-133 activity is approximately 200 pCi/gm. If with an assumption of 1% failed fuel calculations results are 595 pLCi/gm

.DEX-1 33, and the dose consequences calculation also yields a 0.1 rem whole body at the SITE BOUNDARY by calculation then a gas decay tank on fill cannot exceed the activity limits of this requirement and the once per 31 day frequency is adequate.

Reference

1. USAR Section 14.2.3, Accidental Release-Waste Gas

2. Calculation Cl1 833, Kewaunee Power Station RCS Specific Activity Dose Equivalent Xenon -133 Indicator

3. Calculation CN-CRA-99-46, Revision 3, Kewaunee GDT Rupture and VCT Rupture Radiation Dose Analysis for the 7.4% Power Uprate Program.

4. USAR Table D.7-1 Inventory of Gas Decay Tank After Shutdown and Degassing of the RCS (Based on 1 percent of Fuel Defects)

5. USAR Table D.8-1, Nuclide Parameters 13.2.5-3

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 14 I

April 18, 2012 13.3 INSTRUMENTATION i

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:

I a.

b.

The minimum FUNCTIONAL channel(s) in service.

The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1 I

are not exceeded.

APPLICABILITY: During release via the monitored pathway.

I ACTIONS I

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

Separate NON-CONFORMANCE entry is allowed for each channel.

1 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME I

A. Liquid effluent monitoring A.1 Suspend the release of Immediately instrumentation channel alarm/trip setpoint less radioactive liquid, effluents monitored by the affected I

conservative than required. channel.

OR I A.2 Declare the channel Immediately non-functional. I OR A.3 Change the setpoint so it is acceptably conservative.

Immediately I I

I 13.3.1 - 1 I

1

KEWAUNEE POWER STATION ODCM 13.3.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. One or more required B.1 Restore non-functional 30 days channels non-functional. channel(s) to FUNCTIONAL status.

C. Liquid Radwaste Effluent NOTE---------

Line (R-18) non-functional Prior to initiating an effluent prior to or during effluent release, complete sections releases. C.1.1 and C.1.2 C.1.1 Analyze at least 2 Prior to initiating a independent. samples in -. release accordance with Table

' " 13.1.1-1.

AND C.2.--- ----NOTE-----

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

Independently verify the Prior to initiating a release rate calculations and release discharge line valving.

OR C.2 Suspend release of Immediately radioactive effluents via this pathway 13.3.1 -2

I K'EWAUNEE POWER STATI,1ON,1 OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 14 I

April 18, 2012 ACTIONS (continued) '

I N0ON-CON FOR MANCE CONTINGENCY MEASURES RESTORATION TIME I D. Steam Generator Effluent Line (R-19) non-functional prior to or during effluent D.1 Collect and analyze grab samples for gross radioactivity (beta or gamma)

At least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with identified primary to I

releases at a lower limit of detection of at least 1 x 10-6 1ICi/ml.

secondary leakage (with secondary side activity > 1 x 105 I

pCi/ml).

OR I

At least once a week when no indication of primary I

to secondary leakage; I

--------------- NOTE Failure to complete sampling and I

analysis prior to 12 monitor is declared is a violation of this hours after the non-functional DNC.

I E.1 Collect and analyze grab I E. Service Water System samples for gross radioactivity Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Effluent ,Line (R-20 or R-

16) non-functional prior to or during (beta or gamma) at a lower limit of detection of at least 1 x 10-6 1ICi/ml.

I effluent releases I

I I

13.3.1 -3 I

KEWAUNEE POWER STATION ODCM 13.3.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME F. CONTINGENCY F.1 Initiate a CR In accordance with MEASURES Corrective Action OR Program AND RESTORATION TIME of A, B,C, DorE E not met. F.2 Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report CONTINGENY MEASURE was not met in a timely manner.

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 PerformCHANNEL 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 SOURCE CHECK. 31 days DVR 13.3.1.4 Perform CHANNEL FUNCTIONAL TEST 92 days DVR 13.3.1.5 Perform CHANNEL CALIBRATION. 18 months 13.3.1 -4

3 KEWAUNEE POWER STATION ODCM 13.3.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation I

REQUIRED, SIJ.NSTRUMENT CHANNELS PER INSTRUMENT VERIFICATION REQUIREMENTS I

1 Gross Radioactivity Monitors Providing Alarm and Automatic Termination of I

Release

a. Liquid RadwasteEffluent Line (R-18) 1 DVR DVR 13.3.1.1 13.3.1.2 3

DVR 13.3.1.4 DVR 13.3.1.5 II

b. Steam Generator Blowdown Efi*lient Line (R-19) 1 DVR DVR DVR 13.3.1.1 13.3.1.3 13.3.1.4 I

DVR 13.3.1.5

2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm but not I

Providing Automatic Termination of Release Service Water System Effluent Lii Be 1 DVR 13.3.1.1 I

a. DVR 13.3.1.3 (Component Cooling R-20) DVR DVR 13.3.1.4 13.3.1.5 I

b. Service Water System Effluent Line 1 DVR DVR 13.3.1.1 13.3.1.3 I

(Containment Fan Cooling R-16) DVR 13.3.1.4 DVR 13.3.1.5 I

13.3.1 -5

KEWAUNEE POWER STATION ODCM 13.3.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 General Design Criteria 60, 63 and 64 of Appendix A to.

10 CFR Part 50.

13.3.1 -6

3 KEWAUNEE POWER STATION ODCM 13.3.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 13.3 INSTRUMENTATION I 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:

3

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

b. The alarm/trip setpoints set to ensure that the limits of DNC 13.2.1 are I

not exceeded.

APPLICABILITY: At all times I

ACTIONS I

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

Separate NON-CONFORMANCE entry is allowed for each channel.

I NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Gaseous effluent A.1 Suspend the release of Immediately I

monitoring instrumentation channel alarm/trip setpoint less conservative than radioactive gaseous effluents monitored by the affected channel.

I required.

OR I

A.2 Declare the channel Immediately OR non-functional.

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

Immediately I B. Less than the minimum B.1 Restore non-functional 30 days.

I number of channels channel(s) to FUNCTIONAL. FUNCTIONAL status.

I I

I 13.3.2 - 1 I

I

KEWAUNEE POWER STATION ODCM 13.3.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. Noble Gas Activity effluent NOTE ----------- Prior to initiating a monitoring for the Waste Prior to initiating an release Gas Holdup System effluent release, complete non-functional prior to or sections C.1.1 and C.1.2.

during releases C.1.1 Analyze at least 2 independent samples in accordance with Table 13.2.1-1.

AND C.1.2 ------- NOTE ---------

Verification ACTION will Prior to initiating a be performed by at least 2 release technically qualified members of the facility staff. -

Independently verify the release rate calculations and discharge line valving.

OR C.2 Suspend release of Immediately radioactive effluents via this pathway D. Noble Gas Activity effluent D. 1 Taki grab'samples. .12 hours.'

monitoring for the Auxiliary " .* .

Building Ventilation System AND and the Condenser Evacuation System Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months non-functional prior to or thereafter during releases AND D.2 Analyze samples for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time of gross activity, sampling completion 13.3.2-2

i KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 14 I

April 18, 2012 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME I

I E. Noble Gas Activity effluent E.1 Suspend PURGING of Immediately monitoring for the Containment Purge System, 2" line and 36" Radioactive effluents via this pathway. I duct (auto-isolation) non-functional prior to or during releases I

F. Sampler Flow rate Measuring Devices (for the F.1 Estimate the flow rate for the non-functional 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months I Auxiliary Building channel(s). AND Ventilationor Containment Building Ventilation Sampler) non-functional Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter I

prior to or during releases I

G. Radioiodine and Particulate G.1 Continuously collect 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Samplers (for the Auxiliary Building samples using auxiliary sampling equipment as required in I

Ventilation or Containment Table 13.2.1-1.

Building Ventilation system) non-functional prior to or during releases I

H. CONTINGENCY H.1 Initiate a CR In accordance with I

MEASURES Corrective Action OR A, B, AND Program I RESTORATION TIME C, D, E, F, or G not met. H.2 Explain in the next In accordance with I Radioactive Effluent Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in Release Report I

a timely manner.

I 13.3.2-3 I

KEWAUNEE POWER STATION ODCM 13.3.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.3.2.1 Perform CHANNEL CHECK. Prior to release DVR 13.3.2.2 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DVR 13.3.2.3 Perform CHANNEL CHECK. 7 days DVR 13.3.2.4 Perform SOURCE CHECK. Prior to release DVR 13.3.2.5 Perform SOURCE CHECK. 31 days DVR 13.3.2.6 Perform CHANNEL FUNCTIONAL TEST. . 92 days DVR 13.3.2.7 Perform CHANNEL CALIBRATION. 18 months' 13.3.2-4

3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 14 I

April 18, 2012 Table 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation I

.INSTRUMENT REQUIRED CHANNELS PER NON-CONFORMANCE VERIFICATION REQUIREMENTS I

1. Waste Gas Holdup System INSTRUMENT DVR 13.3.2.1 I

DVR 13.3.2.4

a. Noble Gas Activity Monitor (R-13 or R-14) 1 C DVR DVR 13.3.2.6 13.3.2.7 I

2. Condenser Evacuation System

a. Noble Gas Activity (R-15) 1 D DVR DVR DVR 13.3.2.2 13.3.2.5 13.3.2.6 U

DVR 13.3.2.7

3. Auxiliary Building Vent I

a. Noble Gas Activity Monitor (R-13 or R-14) 1 D DVR DVR DVR 13.3.2.2 13.3.2.5 13.3.2.6 I

DVR 13.3.2.7

b. Radioiodine and Particulate Sampler 1 G DVR 13.3.2.3 I

(R-13 or R-14)

c. Sample Flow-Rate Monitor (R-13 or R-14) 1 F DVR 13.3.2.2 DVR 13.3.2.6 DVR 13.3.2.7 I

4. Containment Building Vent I

a. Radioiodine and 1 G DVR 13.3.2.3 Particulate Sampler (R-21) 1 F DVR 13.3.2.2 I

b. Sample Flow-Rate Monitor DVR 13.3.2.6 (R-21) DVR 13.3.2.7 I

5. Containment Purge 2" line

a. Noble Gas Activity Monitor 1 E DVR DVR 13.3.2.2 13.3.2.5 I

(R-13 or R-14) DVR 13.3.2.6 DVR 13.3.2.7 I

6. Containment Purge 36" line DVR 13.3.2.2

a. Noble Gas Activity Monitor (R-12 or R-21) 1 E DVR DVR DVR 13.3.2.4 13.3.2.6 13.3.2.7 I

13.3.2-5 I I

KEWAUNEE POWER STATION ODCM 13.3.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 alarm/trip will occur prior to exceeding the dose rate limits of ODCM DNC 13.2.1. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.

13.3.2-6

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.4.1 Revision 14 I

April 18, 2012 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE I 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 I

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.

I APPLICABILITY: At all times.

ACTIONS I

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME I

A. Estimated dose or dose commitment due to direct A.1 Verify the condition resulting in doses exceeding these Immediately I radiation and the release limits has been corrected.

of radioactive materials in liquid or gaseous effluents exceeds the limits.

I B. CONTINGENCY B.1 --------- NOTE-------

I MEASURES A.1 and This is the Special Report RESTORATION TIME not met.

required by DNC 13.1.2, 13.2.2, or 13.2.3 supplemented with the I

following.

30 days I

Submit a Special Report, pursuant to DNC 15.3, including a request for a variance in accordance with I

the provisions of 40 CFR 190. This submission is considered a timely request, I

and a variance is granted until staff ACTION on the request is complete. I I

I 13.4.1 -1 I I

KEWAUNEE POWER STATION ODCM 13.4.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.4.1.1 Cumulative dose contributions from liquid and 12 months gaseous effluents shall be determined in accordance with VERIFICATION REQUIREMENTS 13.1.2.1, 13.2.2.1, and 13.2.3.1 in accordance with the methodology and parameters in the ODCM.

DVR 13.4.1.2 Cumulative dose contributions from direct radiation 12 months from the reactor unit 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.

13.4.1 L 2

i KEWAUNEE POWER STATION ODCM 13.4. 1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 BASES 3 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 I 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 reactor remains within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor 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 I

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.

I 13.4.1 -I

KEWAUNEE POWER STATION ODCM 13.5.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 Specification 5.5.1 .a, 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 station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels, of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

13.5.1 -1

KEWAUNEE POWER STATION ODCM 13.5.2 a

OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 13.5.2 Land Use Census Program This Kewaunee Land Use Census Program is implemented by the RADIOLOGICAL I ENVIRONMENTAL MONITORING MANUAL (REMM) and Land Use Census Program procedure. 5 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 con sulting 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 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed I

in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/M 2 .

I 13.5.2-I

KEWAUNEE POWER STATION ODCM 13.5.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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.

13.5.3- 1

£ K'EWvAUINEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 14.1 Revision 14 I

April 18, 2012 14.0 DESIGN FEATURES I

14.1 GASEOUS AND LIQUID EFFLUENT RELEASE POINTS I 14.1.1 Plant drawing A-408, "Radiological Survey Site Map" depicts the site area by illustrating the SITE BOUNDARY and the restricted areas. Plant drawing A-449, "Plan of Plant Area, Fence, Lighting, and CCTV Support Structure" shows the I

layout of the site buildings. MEMBERS OF THE PUBLIC are restricted from access 14.1.2 to all areas of the Owner Controlled Area (OCA).

Figure 14.1-1 presents the locations of radioactive effluent release points at the I

plant. The plant drawings referenced above are not included as part of the ODCM but can be found in the plant drawing system. I I

i I

I U

.II I

I I

I

£ 14.1 - 1 I

M -M mm m N m - m s m m -m m m m KEWAUNEE POWER STATION ODCM 14.1 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 FIGURE 14.1-1 KEWAUNEE COUNTY DISPOSALAREA FOR SLIGHTLY CONTAMINATE SLUDGES; SEPTEMBER14. 1994 K-94-195 SCHOOL FOREST CARLTONTRAILSPARK C r LAKE MICHIGAN LEGEND A CONTAINMENT BUILDING VENT ELEVATION 775' B AUXILARY BUILDING VENT ELEVATION G75' C EFFLUENT LIOUID DISCHARGE ELEVATION 580' 14.1 -2

3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 15.1 Revision 14 3

April 18, 2012 3

15.0 ADMINISTRATIVE CONTROLS 15.1 Major Changes to Radioactive Waste Systems(1i 3 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 FSRC. The discussion of each change shall contain:

I

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, I

b. Sufficient information tototally support the reason for the change without benefit of additional or supplemental information, I

c. A description of the equipment, components and processes involved and the interfaces with other plant systems, I 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 I

thereto, i

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 *' 3

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

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

I

"')Licensees may choose to submit the information called for in this requirement as part of the periodic USAR update.

15.1 -I

KEWAUNEE POWER STATION ODCM 15.2 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 unit 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 annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability.. In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data onsite in a file that shall be provided to the NRC upon request. .

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

d. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle.sources, including doses from primary effluent pathways and direct radiation, 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).

15.2- 1

3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 15.2 Revision 14 April 18, 2012 I

e. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. 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.

f. 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.

g. 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.

I I

15.2-2

KEWAUNEE POWER STATION ODCM 15.3 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 15.0 ADMINISTRATIVE CONTROLS 15.3 Special Reports Special reports maybe 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 inAppendix 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 15.3- 1

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

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 10 CFR 50, Appendix A, Criteria 60 and 64, are summarized as follows:

1) Alarm (and Automatic Termination) - R-18 provides this function on the liquid radwaste effluent line, R-19 on the Steam Generator blowdown.

2) Alarm (only) - R-20 and R-16 provide alarm functions for the Service Water discharges.

3) Composite Samples - Samples are collected weekly from the steam generator blowdown and analyzed by gamma spectroscopy. Samples are collected weekly from the Turbine Building Sump and analyzed by gamma spectroscopy. The weekly samples are composited for monthly tritium and gross alpha analyses and for quarterly Sr-89, Sr-90, and Fe-55 analyses. During periods of identified primary-to-secondary leakage (with the -secondary activity > 1.OE-05 pCi/ml),

grab samples from the Turbine Building sump are collecied daily and analyzed by gamma spectroscopy. These samples are composited for monthly tritium and gross alpha analyses and for quarterly Sr-89, Sr-90, and Fe-55 analyses.

4) 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 Specification 5.5.3.b 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 and 2.OE-04 pCi/mI for dissolved or entrained noble gases). The following equation 1 must be satisified to meet the liquid effluent restrictions:

c:1x C(F +f) f c< (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.

1.0-1

K\ EWAU1NEE POWER STATI IUN ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 where:

10xC = ten times the effluent concentration limit of 10 CFR 20, Appendix B, Table 2, Column 2, in pCi/.l. For dissolved and entrained noble gases equals 2x 10-4 pCi/ml.

C= the setpoint, in pCi/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 nodilution. 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, Steam Generator Blowdown and Service Water)

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

~*CW xL*(CX>SEN. )

SP< X i + bkg (1.2)

-ECi 10 BCx where:

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

Ci = the concentration of radionuclide "i" in the liquid effluent (pCi), 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 (pCi/ml) 1.0-2

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision.14 April 18, 2012 SENi = the sensitivity value to which the monitor is calibrated for radionuclide "i" (cpm per pCi/ml). The default calibration value from Table 1..1 may be used for gamma emitting radionuclides in lieu of nuclide specific values.

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

RR = the liquid effluent release rate (gal/min) bkg the background of the monitor (cpm)

The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is at its lowest. Reduction of the waste stream flow.(RR) may be necessary during these periods to meet the discharge criteria.

At its lowest value, CW will equal RR and equation (1.2) reverts to the following equation:

,__,(C i x SENi)

SP < Z + bkg (1.3)

(1 Ci) 1.2.2 Conservative Default Values Non-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) 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 (refer to. Appendix..C). 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. Refer to Appendix C for further discussion.

Conservative alarm setpoints have been determined through the use of generic, default parameters. Table 1.1 summarizes all current default values in use for Kewaunee. They are based upon the following:

a) substitution of the default effective EC (ECe) value of 1.OE-06 pCi/ml (refer to Appendix C for justification),

where:

EC,- 1 (1.4)

(EC1 )

1.0-3

KEVVAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

b) substitution of the lowest operational circulating water flow, in gal/min; and, 3 C) uibhstitutinn of the highest effluent release rat* , in gal/mi, d) substitution of the default monitor sensitivity. I The default setpoint equation is provided below: I sP<E C RxlxENxCWR+bkg (1.5) 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 in the Circulating Water System) 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. Noble gases are limited to a diluted concentration of 2E-04 pCi/ml. 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:

E[(C +(10 x EC,)) x (RR CW)]* 1 (1.6)

Ci l0xECi

=

-=

concentration of radionuclide "i" in the undiluted liquid effluent (PCi/ml) ten times the EC value corresponding to radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml) a

= , 2E-04 pCi/ml for dissolved or entrained noble gases RR = the liquid effluent release rate (gal/min)

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

'!I 1.0-4

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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.

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..

Do 1.67E - 02 x VOLxZ(CI xA 1 0 ) (1.7)

CW where:

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

Ao = site-related ingestion dose commitment factor to the total body or any organ b"ofor radionuclide "i"(mrem/hr per pCi/ml) (Table 1.2)

Ci- average concentration of radionuclide "i", in undiluted liquid effluent representative of the volume VOL (pCi/ml)

VOL = volume of liquid effluent released (gal)

CW - average circulating water.. discharge rate during release period (gal/min) 1.67E-02 = conversion factor (hr/min) 1.0-5

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 The site-related ingestion doses/dose commitment factors (Ai,) are presented in Table 1.2 and have been derived in accordance with guidance of NUREG-0133 by the equation:

Ai. =1.14E+05[(U. + DS)+(UFxBFi)]DF. (1.8) where:

Ai. = 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 pCi/ml) 1.14E+05 conversion factor (pCi/pCi x ml/kg +hr/yr)

U= adult water consumption (7.30 kg/yr)

Dw= dilution factor from the near field area within 11/4 mile of the release point to the nearest potable water intake for the adult water consumption (842, 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-89 and 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.

In lieu of the individual radionuclide dose assessment as presented above, the following simplified dose calculational equation may be used for demonstrating compliance with the dose limits of ODCM Normal Condition 13.1.2. (Refer to Appendix A for the derivation and justification for this simplified method.)

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

1.0-6

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Total Body 9.67E+03xVOL CW(1.9)

Maximum Organ Dmax =1.18E+04xVOL

" ~CW x-Ci (1.10) where:

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

VOL = volume of liquid effluent released (gal)

CW *average circulating water discharge rate during release period (gal/min)

Dtb = conservatively evaluated total body dose (mrem)

Dmax = conservatively evaluated maximum organ dose (mrem) 9.67E+03 = product of the hour-to-minute conversion factor (hr/min) and the conservative total body dose conversion factor (Cs-134, total body

--5.79E+05 mrem/hr per pCi/ml) 1.18E+04 = product-of the hour-to-minute conversion factor (hr/min) and the conservative maximum organ dose conversion factor (Cs-134, liver -- 7.09E+05 mrem/hr per pCi/ml..

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.

1.0-7

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Dose projections are made at least once per 31 days by the following equations:

DUp =D,*b(31 -d) (1.11)

D ...... ,, m (31 + d) (1.12) where: .1 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). or (1.9) (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) or (1.10) (mrem) d'= the number of.days to date for current 31 day period 31 = the number of days in a 31 day period 1.6 Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams During the normal operation of Kewaunee, the potential exists for in-plant process streams, which are not normally radioactive to become contaminated with very low levels of radioactive materials. These waste streams are normally separated from the radioactive streams. However, due mainly to infrequent, minor system leaks, and anticipated operation occurrences, the potential exists for these systems to become slightly contaminated. At Kewaunee, the secondary system demineralizer resins, the service water pretreatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels. During the yearly testing of a batch of pre-treatment sludge, it was found approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.

The potential radiation doses to MEMBERS OF THE PUBLIC from these onsite disposal methods are well below 1 mrem per year. This dose is in keeping with the guidelines of the National Council on Radiation Protection (NCRP) in their Report No. 91, in which the NCRP established a "negligible individual risk level" at a dose rate of 1 mrem per year.

It is for these type wastes that the NRC acknowledged in Information Notice No. 83-05 and 88-22 that the levels of radioactive material are so low that control and disposal as a radwaste are not warranted. The potential risks to man are negligible and the disposal costs as a radwaste are unwarranted and costly.

1.0-8

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 This waste material will be monitored and evaluated prior to disposal to ensure its radioactive material content is negligible. It shall then be disposed of in a normal conventional manner with records being maintained of all materials disposed of using these methods.

Approvals for specific alternate disposal methods are listed in Appendix D. Currently, only service water pretreatment (SWPT) facility lagoon sludge and sewage treatment plant sludge have been approved for disposal by land spreading.

1.7 Heating Boiler Blowdown Operation with Primary-to-Secondary Leak During operation with a primary-to-secondary leak, the potential exists for non-radioactive systems to become contaminated. One such system is the heating system.

Activity is transferred from the reactor coolant system into the secondary main steam system through the leak and then into the heating system. Heating boiler operation following operation with a primary-to-secondary leak will result in the heating boiler becoming contaminated.

When the heating boiler is operated, it must be periodically blown down to remove impurities, which collect in.the system. This blowdown is normally directed to the steam generator blowdown tank but can be diverted to the circulating water discharge. Either way, the blowdown becomes a release. path. for radioactivity to the environment. The heating boiler blowdown is sampled, using current plant procedures, whenever the primary-to-secondary leakage exceeds 10 gallons per day and the gross gamma activity exceeds 1.OE-06 pCi/ml or tritium activity exceeds 1.OE-05 pCi/ml. The results of these samples allow for the activity being released to the environment to be quantified. This is similar to the method used for the turbine building sump release path.. The radioactive effluent limits of 10 CFR Part 20, 40 CFR 190, and Technical Specifications can therefore be maintained..

.1.0-9

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Turbine Building Turbine Building SWPT Lagoon Alternate Drains sump Normal (Sample Sink)

, Radiation .I ""F A

...... *] onitors I_1) SG Blowdown - Turbine Building (Air Ejector) X * -- F TreatmentTanks Standpipe Steam Generator Excanger / Auxiliary Building Blowdown Auto Exchanger Standpipe Isolationl Heater Condenser SGBT (Start-Up Motor) Drain Huts Normal SG Blowdown-I Tank Heating Boiler Tank Blow Down Alternate ,

RFFLOW ',

OCDMFIG1 .FLO Legend:

Graphics No: PC3069

= Sampler/Monitor

,= Isolalion Device (damper or valve)

Auto Isolalion

- This flow path shall only be used if projected does comply will) ODCM and lechnical specification (CA81074)

LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM 1.0-10

- - -- U Iil*Il - i m l mmf i

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 1.1 Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value* Units Comments ECe calculated 1.0E-06** PCi/mi Calculate for each batch to be released Taken from gamma spectral analysis Ci measured N/A ICi/ml of liquid effluent Taken from 10 CFR 20, Appendix B, EC* as determined N/A pCi/mI Table 2, Col. 2 Sensitivity (SEN)

R-18 as determined 1.0E+08 Radwaste effluent R-1 9 as determined 1.0E+08. cpm per Steam Generator blowdown R-20 as determined 1.0E+08 pCi/mI Service Water.- component cooling R-16 as determined 9;8E+07 Service Water - containment fan cooling CW as determined 2.58E+05 gpm Circulating Water System default =

Caseeie 25Eg winter, single CW pump Release Rate (RR)

R-1 8 as determined 8.OE+01 Determined prior to release; release rate can be adjusted. for requirement gpm compliance R-19 as determined 2.OE+/-02 Steam Generator A and B combined R-20 as determined 5.OE+03 Service Water- component cooling R-16 as determined 1.5E+03 Service Water - Containment fan cooling

Background

(bkg)

R-18 as determined 2.OE+03 cpm. Nominal values only; actual values R-19 as determined 8.OE+01 may be used in lieu of these reference R-20 asdetermined' 6.0E+01 values R-16 as determined 8.0E+01 Setpoint* (SP)

I R-18 calculated 5.00E+05+bkg cpm Default alarm setpoints; more R-19 calculated. 5:OOE+05+bkg conservative values may be used as R-20 calculated 5.16E+04+bkg deem appropriate and desirable for R-16 calculated. 1.68E+05+bkg assuring regulatory compliance and for maintaining releases ALARA.

Setpoint* (SP) with no Circulating Water System flow, CW=0 R-18 calculated 6.25E+04+bkg For outages with no Circulating Water R-19 calculated 2.50E+04+bkg cpm System flow (CW=0) and a dilution flow R-20 calculated 11.00E+03+bkg as provided by the Service Water R-16 calculated 3.26E+03+bkg system of 5,000 gpm total.***

Refer to Calculation # C1 0690 for the default setpoint calculation.

- Refer to Appendix C for derivation SW flow is based on N-SW-02 Operating Parameters and Service Water Pump Flow Curves.

The default alarm setpoints for R-18 and R-19 are based upon the linear calibration range of those radiation monitors in accordance with CAP 37265 and DCR 26981.

1.0-11

I KEW'AU NEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

Table 1.2 (Page 1 of 2)

Nucid*e;I"'-4^

Site Related Inqestion Dose Commitment Factors Bone Liver (mrem/hr per uCi/mI)

T.Body Thyroid riuney Lung GI-LLI I

H-3 C-14 Na-24 3.13E+4 3.3 OE-1 6.2.6E+3 6.26E+3 6.26EF 4.09E+2 4.0O9E+2 4.09E+2 4.09Ed 3.30E-1 3.30E- 1.1- 3.30E-1 6.26E+3 3.330E-1 6.2 6E+3 6 26E+3 4.0 9E+2 4.09E+2 3.30E-1

'I 31 4.09E+2 ..................... .. !1.I56E+5 5 ..6 .......

I P-32 1.39E+6 8.6 2E+4 5.36E+4 .......

Cr-51 Mn-54 - 1.28E+0 _7.63E- 2.81E-i 1.6 *9E+0

...... ... 3.21_.4..

....... ..E+2

.. +.4 4.3* 8E+3 8.36E+2 1.30E+3 1.34.E+4 Mn-56 1.11 )E+2 E ....

I7 +2 .... .0 . . . . ....

._..E..-.......2

.. F. -. 5.........

Fe-55 Fe-59 6.61 E+2 1.04E+3 4.5:7E+2 2.4. 5E+3 9.40E+2 1.96E+1 1.06E+2 -

1.40E+2 2.5 5E+2 6.8 5E+2 3.52E+3 2.62E+2 8.17E+3 II 2.1 1E+1 3.51E+1 Co-57 .... "..... ..... ....

5.36E+2 ... -.

Co-58 Co-60 3.13E+4 8.9 9E+i 2.5E8E+2 2.02E+2 _. ..---.

5.70E+2 1.82E+3

.4.85E+3 4.52E+2

'I Ni-63 2..1 7E+3 1.05E+3 . -

Ni-65 Cu-64

.Z.....C....6..

Zn-65 1.27E+2 2.32E+4 1.605E+1 1E+1 . 4.72E+O .

7.3*8E+4 3.33E+4 7.52E+0 2......3 2.53E+1 4.93E+4 E !._.

4.18E+2 8.57E+2 4.65E+4 I

9.4: 3E+1 6.56E+0 Zn-69 Br-82

...B...

a r8............

4 4.93E+1

_2.27E+3

.....4.05E i ___-1 6.13E+1 - 1.42E+1 2.61E+3 11 I

RBr-85

.b..6

.......... ..........-..... 5.24E + 1 _ -4.12E-4 Br-86 - 2.15E+0 Rb-88 1.011E+5 4.71E+4 . .- -.99E+4 2.9()E+2 1.54E+2 4.00E-9 Rb-89 Sr-89 2.24E+4 5.52E+5 1.92?E+2 1.35E+2 6.44E+2

- 3.60E+3 ii Sr-90 - 1.35E+5' 1.59E+4 Sr-91 Sr-92 Y-90 4.13E+2 1.57E+2 5.85E-1 S. .. 6.77E+0

.i1.67E+i .

1.57E-2 1.97E+3 3.10E+3 6.21EF+3 .3.....

I 2.14E-4__-

I Y-91m 5.53E-3 ......... 2.219E -4

...... - ..62E-2 Y-91 8.58E+0 - 2.29E-1 - 4.72E+3 Y-92 5.14E-2 .. 1.50E-3 - 9.OOE+2 Y-93 1.63E-1. 5.17E+3 I

Zr-95 4.50E-3 - -

2.70E-1 8.67E-2 -..5...87 E-.2- -__ 1.36E-1 - -....... 2.75E+2 Zr-97 ....

......... .4 + ...........

Nb-95 1.49E-2 3.01 E-3 .1.38F-3 - 4.55E-3 - 9.34E+2 Nb-97 4.47E+2 2.49E+2 ....... 1.34E+2 - 2.46E+2 - 1.51 E+6 Mo-99 3.75E+0 9.11E-3 9.48E-1 -.3..46§E-1 1.07E+2 2.04E+ 1 1.11E+0 2.43E+2

- E-..

3.50E+3 2.49E+2

..,5

. . E i ..

I Tc-99m 2.58E-2 3.28E-1 - 3.91 E-1 1.26E-2 1.52F+1 Tc-101 Ru-103 Ru-105 9.37E-3 4.61 E+O 3.84E-1 1.35E-2 1.32E-1 1.9.9E.+0 2.43E-1 1.76E+1 4.96E+0 6.9 OE-3 5.39E+2 2.35E+2 I

Ru-106 Rh-i 03m.

Rh-1 06 6.86E+1 8.68E+0 - 1.32E+2 - 4.44E+3 I

1.0-12 I

I

KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 1.2 (Page 2 of 2)

Site Related Inoestion Dose Commitment Factors (mrem/hr per pCi/ml)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Ag-1 1Orn 1.O4E+0 . 9.62E-1 ........

............ ...... 1.89E+0 3.92E+2 124 9 .48E+0 1 7.9.E.71 2. 30E-2 7.3 -8E+0 2.69E+2 3.76E+0

.6E*_.

....... ....... 6....77.E-.2-..

.6... ...6.i._16..E._-.3 4.6 67E.+O. 6.67E+1

..S-b.-.l 25.

Te-125m 2.57E+3 9.31 E+2 3.44E+2 7.73E+2 1.04E+4 1.03E+4 Te-1 27m *6.49.E+3 .2.32E+3 7.91 E+2 1.66E+3 2.64E+4 E-. 2.18E+4 Te-127 !* .........

5 E.....

... 3.79E ..........

8 E...

÷..1..7.81._E+ 4.29E+2.... 8.32E+3

. +1

......4 .....

9I,._.

Te-129m 1.10E+4 4.11 E+3 1..74E

.........+3. 3.79E+3 4.60E+4 1E.- 5.55E+4 Te-129 3.01 E+1 1.13E+1 7.33E+0 2.31E+1 1.27E+2 2.27E+1 Te-1 31 m. 1.66E+3 8.11

....... ... E+2 6.76E+2 1.28E+3 .8.22 E+3. 8.05E+4 1.89E+1 5.96E+0 1.55E+1 Te.-1 31 7.89E+O

. ... ......................... 8.27E+1 TE2.67E+0 Te-1 32 2.42E+3 1.56E+3 1.4.7E+3 1.73E+3 1.50E+4 7.39E+4 1-130 2..9 *............... 8.23E+1

.3

.............. . 6 .97E+3- 1.28E+2 1-131 1.54E+2 1.26E+2 1-12 4E+2OO~i 7.1

+0-37.F08+

...... .. 2.20E+2

................................ 7.20E+4 .3.76E+2 5.79E+1 7-1-132 7.49E+0 2.00E+1 7.01E.÷O

........ 7.01 E+/-2 3.19E+1 3.76.E.+_0...

5.24E+1

. ... 8 .... . .* ........

1-133 .... 8 2.....7 1 E........

3.911E+0 ........ .9.11

........ E+1 1.34E+4 1.59E+2 1-134 1.06E+1 -"1.84E+2 1.69E+1 - 9.26E-3 1-135 1.63E+1 4.28E+1 o .2.82E+3 6.86E+. I......i. 1-13

- 163Ei .......................

428E~

158E1 44.83E+1. .. E÷.....

2.98E+5----- 7.09E+5 .*

÷

!...2. _.

E_.......

.. Cs-134

. ........................ - .- 8.8_6.E+4. ...

' ..... 2.29E+5 7.6 Cs-34 Et4 2.9E÷5 7.9E+

5.9E+_

... 1.24E+4 3.12E

..... +*4 1.23E+5 ...

Cs-136 6.85E+4 9.3 9E+3 1.40E+4 3.82E+5 3.42E+5 ... .:...... .....

Cs-1 37 5.22E+5 ... .... . 1.77E+5 5.8 9E+4 1.01 E+4 2 .64E+2 2.59E.+2-Cs-138 5.22E+2 3.84E+2 3.7 9E+1* 2.23E-3 Ba-139 -3.00.E.-.-2...... , 6_83.E_-.4 ... 4.1Ba-39.0E+0 7.3E-4 3.0E-24E-4i.82F+0

...... -.--.. 2.15E+2

.... -7..,..3.0..E--4.

Ba-140 2.69E-1 1.41E+1 9.16E-2_ 1.524E-1 4.42E+2

. ...................................... 18.6 2..........

Ba-141 4.98.E-71 ...... S3.50E-4_ 2.1 3E ........

........ -3,76..E.71 Ba-142 1.95E-4 .1.3 14E-4 1.525E-1 -. 2....31E.4 2..03E-2, -.

La-140 7..6.7.E-2 8.82E-4.-

5 . - .63 L:.............. 3........

Laý142 .7.7.9 E-3 3 .54E-3 .. . :.........

..........2 .._ 9. .. +..........

Ce-141 .......

3

..1 7E--2......

.. 2.14E-2

......2.._._....

.. E-3 .

... 9.95E Ce-i4

- 1.65E0690E 1.87E2 5.63E+3

.... ....*.....!9.E.+...

. 4.57E Pr-

-4360-i .2SFi 277E2 2.59E+1

...Ce-143

. 4.13E+O .. ....... ........ 1.82E-3, 5 .58E+2 Ce-144 5.5.60E -!..........6,.901E.-1 4.10E-1 Pr-143 2.77E -2.

...... 1.30E-I Nd-147

.383E1 W1E5- 4-42-1-2.5F-28 2.2+3i

.4E+3ii Pr-144 1,83E-73 4.29E-4 Nd-147 31.8-3.E-71 2.65E-2

...4,4-2.E-1. _2.59E.-i!.. 8.10E+4 W-1 8 7 2.96E+2 2.47E+2

......9.10OE-3 Np-239 2.97E-2 2.92E-3 1.61E-3 5.98E+2 Np-239 2.97E-2 2.92E-3 1.61 E-3 - 5.98E+2 1.0-13

I KEVVAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 14 I

April 18, 2012 Table 1.3 Bioaccumulation Factors (BFi)

(pCi/kg per pCi/liter)* I Element Freshwater Fish H

C 4.6E+03 I

.... .. Na

......... 1.OE+02

.........P..........

Cr C .E......................

P.OE+03 2 ....0 2 .........

I Mn 2.OE+02 Fe Co CuNi F.OE+02 5.OE+01

'L2.......

-......... I

.... .Ni

. ... 1.OE+02 Cu Zn Zn2.OE+01

... Br Rb Y

B.3E+02 ROE+03 2.OE+O1 S.2E+01 I

S -r...

Y .-

.................. -' :* 0

.... .. l ll..... .. ... . ... ... Ii..

....... ......I..... II- .......

N

.......... b

.... N3.OE+01 Mo 2.oE+01 Tc Ru Rh

.Ag

.... A3.3E+00 I

Sb Te 4.OE+02 ..-_...

1.5E+01 I Cs 2.0E+03

....... Cs.........

Ba La ------

. Ba Ce.

4.0E+00 L25E+01 1.OE+00 I

Ce

........ Nd Pr.......-...

I.....-....

Pr 2.5E,+01 2.5E+01 1.2E+03 I

....... .W

... 1.5E+01 No Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus I

which is adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564, Rev. 1, October 1972. i 1.0-14 I

I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 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 10 CFR 50, Appendix A, Criteria 60 and 64, are summarized as follows:

2.1.1 Waste Gas Holdup System The vent header gases are collected by the waste gas holdup system. Gases may be recycled to provide cover gas for the CVCS hold-up tanks or held in the waste gas tanks for decay prior to release. Waste gas decay tanks are batch released after sampling and analysis. The tanks are discharged via the Auxiliary Building vent. R-13 and/or R-14 provide noble gas monitoring and automatic isolation.

2.1.2 Condenser Evacuation System The air ejector discharge is monitored by R-1 5. Releases from this system are normally via the Auxiliary Building vent and are monitored by R-13 and/or R-14.

2.1.3 Containment Purge Containment purge and ventilation is via the containment stack for the 36-inch RBV system but via the auxiliary building stack for the 2-inch vent and mini-purge blower system. The stack radiation monitoring system consists of:

" a noble gas activity monitor providing alarm and automatic termination of release (R-12 and R-21),

an iodine sampler, and

a particulate sampler.

Effluent flow rates are determined empirically as a function of fan operation (fan curves).

Sampler flow rates are determined by flow rate instrumentation.

2.1.4 Auxiliary Building Vent The Auxiliary Building vent receives discharges from the waste gas holdup system, condenser evacuation system, fuel storage area ventilation, Auxiliary Building radwaste processing area ventilation, 2-inch containment pressure relief purge/vent system, and AuxiliaryBuilding general area. All effluents pass through the R-13 and/or R-14 channels which contain:

a noble gas monitor

an iodine sampler, and

a particulate sampler.

2.0- 1

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 The noble gas monitor provides auto isolation of any waste gas decay tank release and diverts other releases through the special ventilation system. Effluent flow rates are determined by installed flow measurement equipment or as a function of fan operation (fan curves). Sampler flow rates are determined by flow rate instrumentation.

2.1.5 Containment Mini-PurgeNent System Slight pressure buildup in containment is a recurring event resulting from normal operation of the plant. Prior to exceeding 2 psig in containment, this excess pressure is vented off. Air from containment is routed to the Auxiliary Building ventilation system, via the post-LOCA hydrogen recombiner piping and then out through the Auxiliary Building vent stack. The system is also designed to allow a continuous supply of fresh air to be introduced into containment via a mini-blower to purge gases. An alarm of the Auxiliary Building vent stack monitor (R-13 or R-14) or the containment building airborne radioactivity monitors (R-11, R-12) provides automatic isolation.

2.1.6 Steam Generator PORV Release With Primary-to-Secondary Leakage IF the plant is operating with Steam Generator leakage from the primary side to the secondary, THEN release of steam through the Steam Generator PORVs will constitute a radiological release. There are no monitors on this release path, so accurate data collection is important.

The appropriate procedures provide directions for release permit preparations.

2.1.7 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 during outages, 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. 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.

2.1.8 Miscellaneous Releases -

IF the plant is experiencing primary-to-secondary leaks in the steam generators, THEN the secondary steam release, effluent,, gaseous side willwhich become contaminated.

will need Any release to be accounted of effluent for in the steam will constitute release -an program.

Historically, if this condition had existed, the affects were considered to be minimal, and therefore were NOT included in the ODCM. The potential sources are too numerous to specifically'call out here. However, in the event conditions arise that such releases occur, the methods outlined in the ODCM for dose calculation of the releases will be applied, and the results included in the annual effluent release report.

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

2.0-2

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 2.2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Containment and Auxiliary Building Vent Monitor Per the requirements of ODCM Normal Condition 13.3.2, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed corresponding dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin. Based on a grab sample analysis of the applicable release (i.e., grab sample of the Containment vent or Auxiliary Building vent), the radiation monitoring alarm setpoints may be established by the following calculational method:

FRACrb.= [4.72E + 02X x/Qx VFx ,(Ci.xKi)] 500 (2.1)

FRACski. = [4.72E + 02 x x/Q x VF x (_(Ci x (Li + 1.1 Mi))]+ 3000 (2.2) where:

FRACtb = fraction of the allowable release rate for the total, body based on the identified radionuclide concentrations and the release flow rate FRACski. = fraction of the allowable release rate for skin based on the identified radionuclide concentrations and the release flow rate X/Q annual average meteorological dispersion for direct exposure to noble gas at the.controlling SITE BOUNDARY location (sec/m3 , from Table 2.3)

VF ventilation system flow rate for the applicable release point and monitor (ft 3/min, from Table 2.2)

C, ,= . concentration of noble gas. radionuclide "i"as determined by radioanalysis of grab sample ([LCi/cm 3 ) -

Ki . total body dose conversion, -factor for noble gas radionuclide 'T' (mrem/yr per [tCi/m 3 , from. Table 2.1)

Li = beta skin dose conversion factor for noble gas- radionuclide "r' (mrem/yr per iCi/m3, from Table 2.1)

M= gamma air dose conversion factor for noble, gas radionuclide '"T (mrad/yr per [.iCi/m 3; from Table 2.1)

1.1 = nmrem skin dose per mrad gamma air dose (mrem/mrad) 4.72E+02 = conversion factor (cm3 /ft3 x min/sec) 500 = total body dose rate limit (mrem/yr) 3000 = skin dose rate limit (mrem/yr) 2.0-3

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoint I for the Containment and Auxiliary Building vent monitors at Kewaunee may be calculated:

SP = [I (Ci x SEN) + FRAC]+ bkg (2.3) i where:

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

SENi = the sensitivity value to which the monitor is calibrated for radionuclide 'T" (cpm per iCi/cm 3), use the default value from Table 2.2 if radionuclide specific sensitivities are not available I bkg background of the monitor (cpm) 2.2.2 Conservative Default Values I A conservative alarm setpoint can. be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release I

flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2.2. These values are based upon:

a) substitution of the maximum ventilation flow rate, U

b) substitution of a radionuclide distribution1 Xe-133m, 1% Kr-88 and 1% Kr-85; and, comprised of 95% Xe-133, 2% Xe-135, 1% I c) application of an administrative multiplier ' of 0.5 to conservatively assure that any simultaneous releases do not exceed the maximum allowable release rate.

I For this radionuclide distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table.2.2.

I I

I

'Adopted from ANSI N237-1976/ANS-18.1, Source Term Specifications, Table 6.

2.0 -4 I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 2.3.1 SITE BOUNDARY Dose Rate - Noble Gases.

ODCM Normal Condition 13.2.1.a limits the dose rate at the SITE BOUNDARY due to noble gas releases to < 500 mrem/yr to the total body, and < 3000 mrem/yr to the skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in the alarm setpoints being exceeded, an evaluation of the UNRESTRICTED AREA dose rate resulting from the release may be performed using the following equations:

Dtb=x/QxY KixQi (2.4) and D*sX/Qx--' (Li,+ 1.1Mi)XQ " (2.5) where:

D ib = total body dose rate (mrem/yr)

Ds skin dose rate (mrem/yr) x/Q atmospheric dispersion for direct exposure to noble gas at the controlling SITE BOUNDARY (sec/m3, from Table 2.3)

Q1 average release rate of radionuclide "i" over the release period under evaluation (p.Ci/sec)

K, total body dose conversion factor for noble gas radionuclide "i" (mrem/yr per 1.Ci/m 3 , from Table 2.1)

Li beta skin dose conversion factor for noble gas radionuclide "i" (mrem/yr per pCi/m 3 , from Table 2.1)

Mi gamma air dose conversion factor for noble gas radionuclide "i" (mrad/yr per pCi/m 3, from Table 2.1) 1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 2.0-5

I KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

Actual meteorological conditions concurrent with the release period, or the default, annual average dispersion parameters as presented in Table 2.3 may be used for evaluating the 3

gaseous effluent dose rate.

2.3.2 SITE BOUNDARY Dose Rate - Radioiodine and Particulates I ODCM Normal Condition 13.2.1 .b limits the dose rate to < 1500 mrem/yr to any organ for 1-131, 1-133,. 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 U the sampling and analysis time period for continuous releases (e.g., nominally once per 7 days) and for batch releases on the time period over which any batch release is to occur. The following equation may be used for the dose rate evaluation:

Do =X/Qxl RxQij (2.6) 1 where: 3 Do = average organ dose rate over the sampling time period (mrem/yr)

X/Q= atmospheric dispersion to the controlling SITE BOUNDARY for the inhalation pathway (sec/rin3 , from Table 2.3) 1 dose parameter for radionuclide "i", (mrem/yr per _LCi/m 3 ) for the child R=

inhalation pathway from Table 2.6 1 Q. average release rate over the appropriate sampling period and analysis frequency for radionuclide "i", k-131, 1-133, tritium or other radionuclide in .3 particulate form with half-life greater than 8 days (jiCi/sec)

By substituting 1500 mrem/yr for Do solving forQi, an allowable release rate for 1-131 can be determined. Based on the annual average meteorological dispersion (see Table 2.3) and the most limiting potential pathway, age group and. organ .(inhalation pathway, child thyroid -

.Ri = 1.62E+07 mrem/yr per ipCi/m 3) the allowable release ra.te .for 1-131 is 6.43 pCi/sec. An added conservatism factor of 0.25 has been included, in this calculation to account for any I

potential dose contribution from other radioactive particulate material. For a 7-day period, which is the nominal sampling and analysis frequency for 1-131, the cumulative allowable release is 3.9 Ci. Therefore, as long as the 1-131 releases in any 7-day period do not exceed 3.9 Ci, no I

additional analyses are needed to verify compliance with the ODCM Normal Condition 13.2.1.b limits on allowable release rate. 5 I

2.0-61

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 2.4 Gaseous Effluent Dose Calculations - 10 CFR 50 2.4.1 UNRESTRICTED AREA Dose - Noble Gases ODCM Normal Condition 13.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of (< 5 mrad, gamma-air and _<10 mrad, beta-air) and the calendar year limits (<10 mrad, gamma-air and *< 20 mrad, beta-air). The following equations may be used to calculate the gamma-air and beta-air doses:

Dy 3.17E- 08 x z/QxEY(Mi x Q) (2.7) and Dp 3.17E- 08 x X/Q x Y (N, x Q) (2.8) where:

Dy air dose due to gamma emissions for noble gas radionuclides (mrad)

D= air dose due to beta emissions for noble gas radionuclides (mrad)

X/Q atmospheric dispersion to the controlling SITE BOUNDARY (sec/m3 , from Table 2.3)

Q cumulative release of noble gas radionuclide "i" over the period of interest (VCi)

M= air dose factor. due to gamma emissions from noble gas radionuclide "iT (mrad/yr per pCi/m 3 from Table 2.1)

Ni'= air dose factor due to beta emissions from noble gas radionuclide "i" 3

(mrad/yr per [iCi/m , Table 2.1) 3.17E-08 conversion factor (yr/sec)

In lieu of the individual noble gas radionuclide dose' assessment as presented above, the following simplified dose calculational equation may be used for verifying compliance with the dose limits for justification of this ODCM Normalmethod) simplified Condition 13.2.2. (Refer to: Appendix B for the derivation and D3.17EO-08

. D, =- 0.5 x /Q x M'ff x,, Q1 (2.9) 0.50 and Dp = 3 . 7E x8 /Q x Neffx ZQi (2.10) 0.50 2.0.7

I KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

where: 3

+.3+effective gamma-air dlose factor (mrad/yr per lCi/m3 )

,.,.r=,,_

Neff 1,1 E+03 effective beta-air dose factor (mrad/yr per pCi/mr3 ) I 0.50 conservatism factor Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2.3, may be used for the evaluation of the gamma-air and beta-air doses.

2.4.2 UNRESTRICTED AREA Dose - Radioiodine 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 1-131, 1-133, tritium and particulates with half-lives greater than 8 days:

I Da.op = 3.17E - 08x W x SFpx E (R x Q) (2.11) 3 where:

Daop dose or dose commitment for age group "a" to organ "o", including the total body, via pathway :"p" from 1-131, 1-133, tritium and radionuclides in particulate form with half-life greater than eight days (mrem)

W atmospheric dispersion parameter to the controlling location(s) as

=

-identified in Table 2.3 5 X/Q . atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/mr3 )

D/Q atmospheric deposition for vegetation, milk and ground plane exposure pathways (/mi2 )

R dose factor for radionuclide "i",(mrem/yr per jiCi/m3 ) or (m2 - mrem/yr per I 1 .tCi/sec) from Table 2.4 through 2.15 for each age group "a" and the applicable pathway "p" as identified in Table 2.3. Values for R, were derived in accordance with the methods described in NUREG-01 33.

Q cumulative release over the period of interest for radionuclide "i" -- 1-131 or radioactive material in particulate form with half-life greater than 8 days (t-2Ci).

2.0-81

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 SFp seasonal correction factor to account for the fraction of the period that the applicable exposure pathway does exist.

1) For rnilk and vegetation exposure pathways:

of months in the period that grazingoccurs total # of months in period

= 0.5 for annual calculations

2) For inhalation and ground plane exposure pathways: = 1.0 In lieu of the individual radionuclide (1-131 and particulates) dose assessment as presented above, the following simplified dose calculational equation may be used for verifying compliance with the dose limits of ODCM Normal Condition 13.2.3.

D..... 3.17E - 08x W x SFpx Ri - 131 XZQi (2.12) where:

Dmax = maximum organ dose (mrem)

RI-13 = 1-131 dose parameter for the thyroid for the identified controlling pathway 1.05E+1 2 infant thyroid dose parameter with the grass-cow-milk pathway controlling (mi2 - mrem/yr per ýtCi/sec)

The ground plane exposure and inhalation pathways need not be considered when the above-simplified calculational method is used because of the overall negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground plane exposure pathway may represent a higher dose contribution than either the vegetation or grass-cow-milk pathway. However, use of the 1-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclide- has a higher dose parameter for any organ via any pathway than 1-131 for the thyroid via the grass-cow-milk pathway.

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 2.3. .

2.0-9

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 2.5 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:

0.2 mrad, gamma air,

0.4 mrad, beta air, or

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, = D, x (31 d) (2.13)

D&P=DQ6x(31d) - . (2.14)

'Dmaxp = Dmax X(31+ d) (2.15) where:

Dyp gamma air dose projection for current 31 day period (mrad)

D= gamma air dose to date for current 31 day period as determined by equation (2.7) or (2.9) (mrad)

D- beta air dose projection for current 31 day period (mrad)

Do beta air dose to date for current 31 day period as determined by equation (2.8) or (2.10) (mrad).,

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

Dinax maximum organ dose to date for current 31 day period as determined by equation (2.11) or (2.12) (mrem) d , , = number of days to date in current 31 day period 31 . = number of days in a 31 day period 2.0- 10

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 2.6 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 Specification 5.6.2 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. 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.

2.7 Incineration of Radioactively Contaminated Oil During plant operation, radioactively contaminated oils are generated from various pieces of equipment operating in the plant. The largest source of contaminated oil is the reactor coolant pump lubricating oil, which is periodically changed for preventive maintenance reasons. 10 CFR Part 20 allows licensees to incinerate radioactively contaminated oils on site provided that the total radioactive effluents from the facility conform to the requirements of 10 CFR Part 50, Appendix I.

Radioactively contaminated oil, which is designated for incineration, will be collected in containers, which are uniquely serialized such that the contents can be identified and tracked. Each container will be sampled and analyzed for radioactivity. The. isotopic concentrations will be recorded for each container.

The heating boiler will be utilized to incinerate the radioactively contaminated oil collected on site. A gaseous radwaste effluent dose calculation, as prescribed in Section 2.3 of the ODCM, will be performed to insure' that the limits established by ODCM Normal Condition 13.2.1, 13.2.2 and 13.2.3 are not exceeded. Release of the activity is assumed to occur at the time the contaminated oil is transferred into the heating boiler fuel oil storage tank and will be accounted for using established plant procedures. This will be valid for an assumedrelease from the fuel oil storage tank vent, fill piping, or from the boiler exhaust stack. See Figure 3 for a description of the heating boiler fuel oil system.

2.8 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 Specifications for total dose.. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40CFR1 90, "Environmental Standards for the Uranium Fuel Cycle".

Compliance with the KPS Technical Specification dose objectives for the maximum individual demonstrates compliance with the EPA limits to any MEMBER OF THE PUBLIC, since the design dose objectives from 10CFR50, Appendix I are much lower than-the 40CFR190 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, 13.2.2, 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 reactor unit, 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.

2.0-11

I/Z-A/Av M I'IIr I-O I

r\EVV/INrF POWEIR STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 April 18, 2012 I

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 U

in Sections 1.4, 2.4.1, and 2.4.2, 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 I

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 noble gases, ground plane deposition, and shoreline deposition, which have already been included in the i 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 i contained radioactive sources within the facility. The methodology used to incorporate the direct 3 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.1 2 -

I

-I 2.O- 1

= 11111111 M -M M IIIIIII0 M M-o= " M N n 0 -f KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Auxiliary Building Veni Slack

<= Sampler/Monitor p Preflter I>< Isolalion Device h Hepa filler I (damper or valve) 3 Way Valve c Charcoal filler Auto Isolation The shield building ventilation and special ventilation are ESF systems and are nolpart of the normal effluent processing system. They are irnluded for completeness only-The conlainmenl air sampler (R11) and radiation monitor (R12) can also be aligned as needed for sampling containment vent.

GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM 2.0 - 13

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Figure .3 Simplified Heating Boiler Fuel Oil Piping System roof 3' vent cap with flame arrester 3" fill unit 3' rod &sample unit t

j i- Valve Rack*-

I L - -

Heating Boiler Fuel Oil Storage Tank healing bofler 30,000 Galtons fuel oil pumps 2.0 - 14

- n -M w IM w ow 1111 M- M 1 I~10 ow M

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.1 Dose Factors for Noble Gases Total Body Dose Skin Dose Factor Gamma Air Dose Beta Air Dose Factor Ki Li (mremlyr per Factor Mi Factor Ni Radionuclide (mremlyr per pCi/rn 3) (mrad/yr per (mrad/yr per pCi/m 3) pCi/m 3) pCi/rn3)

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85rm 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 2.0-15

I KEVVAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.2 I Parameters for Gaseous Alarm Setpoint Determinations I

Parameter Actual Value Default Value* Units Comments X/Q calculated 3.6E-06 sec/m3 Licensing technical specification value I

Containment - normal plus VF fan curves 26,000 54,000 cfm purge modes Auxiliary Building - normal I

operation pCi/m 3 C1 Kispecific measured*

nuclide N/A N/A mrem/yr per Values from Table 2.1 iJ______i/m_______

i npclidefNiAcmrem/yr per Values from Table 2.1 Lispecific nuclide nuclide N/A NIA_______

N/A m/yrnper mrem/yr per

________Valuesfrom__Table_2.1 Values from Table 2.1 I

3 specific jCi/M Sensitivity**

(SEN)

I R-12 as determined 2.32E+07 cpm per Containment R-21 R-13 2.32E+07 2.32E+07 pCi/cm 3 Containment Auxiliary Building i R-14 2.32E+07 Auxiliary Building

Background

(bkg)

R-12 4.OE+02 Nominal values only; actual I

R-21 4.OE+01 cpm values may be used in lieu of R-13 R-14 6.OE+02 9.OE+02 these reference values. I Setpoint* (SP)

R-12 calculated 2.8E+05+bkg Default alarm setpoints; more conservative values may be I R-21 calculated 2.8E+05+bkg cpm used as deemed appropriate R-13 R-14 calculated calculated 1.3E+05+bkg 1.3E+05+bkg and desirable for ensuring regulatory compliance and for maintaining releases ALARA.

I

Refer to Calculation # C10690 for the default setpoint calculation.

- Conservatively based on Xe-1 33 sensitivity. I 2.0- 16

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations Atmospheric Dispersion ODCM Normal Condition Location Pathways x/Q (seclm 3 ) D/Q (l/m2 )

13.2.1.a Site Boundary Noble gases 7.44E-07 N/A (0.81 mile, NNW) Direct exposure 13.2.1.b Site Boundary Inhalation, 7.44E-07 N/A (0.81 mile, NNW) Ground Plane 13.2.2 Site Boundary Gamma Air 7.44E-07 N/A (0.81 mile, NNV) Beta Air Residence/dairy Inhalation, 13.2.3 . (1.3 mile sW) Vegetation, Milk 3.95E-08 1.86E-09 (1.3 ** and Ground Plane 2.0- 17

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 i

April 18, 2012 Table 2.4 (Page 1 of 2)

R, Inhalation Pathway Dose Factors- ADULT I (mrem/yr per PCi/m 3)

I Nuclide H-3 -

Bone Liver 1.26E+3 Thyroid 1.26E+3 Kidney 1.26E+3 Lung 1.26E+3 GI-LLI 1.26E+3 T.Body 1.26E+3 I C-14 Na-24 P-32 1.82E+4 1.02E+4 1.32E+6 3.41E+3 1.02E+4 7.71E+4 -

3.41E+3 1.02E+4 3.41E+3 1.02E+4 3.41E+3 1.02E+4 3.41E+3 1.02E+4 8.64E+4 3.41E+3 1.02E+4 5.01E+4 I

Cr-51 - 5.95E+1 2.28E+1 1.44E+4 Mn-54 Mn-56 3.96E+4 1.24E+0 9.84E+3 1.30E+O 1.40E+6 9.44E+3 3.32E+3 7.74E+4 2.02E+4 1.OOE+2 6.30E+3 1.83E-1 I

Fe-55 2.46E+4 1.70E+4 7.21E+4 6.03E+3 3.94E+3 I

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 6.71 E+2 Co-58 - 1.58E+3 - 9.28E+5 1.06E+5 2.07E+3 Co-60 Ni-63 4.32E+5 1.15E+4 3.14E+4 -

- 5.97E+6

.1.78E+5 2.85E+5 1.34E+4 1.48E+4 1.45E+4 I

Ni-65 1.54E+0 2.10E-1 - -.... 5.60E+3 1.23E+4 9.12E-2 Cu-64 Zn-65 Zn-69 3.24E+4 1.46E+0 1.03E+5 4.62E+0 6.90E+4 6.78E+3 8.64E+5 4.90E+4 5.34E+4 6.15E-1 4.66E+4 I 3.38E-2 6.51E-2 - 4.22E-2 9.20E+2 1.63E+1 4.52E-3 Br-82 Br-83 Br-84 1.04E+4 2.32E+2 1.64E-3 1.35E+4 2.41 E+2 3.13E+2 I

Br-85 Rb-86 Rb-88 -

- 1.35E+5 3.87E+2 1.66E+4 3.34E-9 1.28E+1 5.90E+4 1.93E+2 i

Rb-89 2.56E+2 - 1.70E+2 Sr-89 Sr-90 3.04E+5 9.92E+7 -

1.40E+6 9.60E+6 3.50E+5 7.22E+5

.8.72E+3 6.10E+6 i

Sr-91 6.19E+1 - 3.65E+4 1.91E+5 2.50E+0 Sr-92 Y-90 6.74E+O 2.09E+3 1.65E+4 1.70E+5 4.30E+4 5.06E+5 2.91 E-1 5.61E+1 I

Y-91m 2.61E-1 - 1.92E+3 1.33E+0 1.02E-2 Y-91 Y-92 4.62E+5 1.03E+1 1.70E+6 1.57E+4 3.85E+5 7.35E+4 1.24E+4 3.02E-1 I.

Y-93 9.44E+1 - 4.85E+4 4.22E+5 2.61 E+0 Zr-95 Zr-97 Nb-95 1.07E+5 9.68E+1 1.41E+4 3.44E+4 1.96E+1 7.82E+3 5.42E+4 2.97E+1 7.74E+3 1.77E+6 7.87E+4 5.05E+5 1.50E+5 5.23E+5 1.04E+5 2.33E+4 9.04E+0 4.21E+3 I

Nb-97.

Mo-99 Tc-99m 2.22E-1 1.03E-3 5.62E-2 1.21 E+2 2.91E-3 6.54E-2 2.91 E+2 4.42E-2 2.40E+3 9.12E+4 7.64E+2 2.42E+2 2.48E+5 4.16E+3 2.05E-2 2.30E+1 3.70E-2 I

Tc-101 4.18E-5 6.02E-5 1.08E-3 3.99E+2 5.90E-4 I

2.0- 18 I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.4 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - ADULT (mrem/yr per pCi/rn)

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.OOE+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+O 6.42E-1. 1.06E+O 5.10E+O 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 5.1OE+5 1.62E+2 1-130 4.58E+3 1.34E+4 1.14E+6 2;09E+4 - 7.69E+3 5.28E+3 1-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 - 6.28E+3 2.05E+4 1-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 - 4.06E+2 1.16E+3 1-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 - 8.88E+3 4.52E+3 1-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 - 1.01E+0 6.15E+2 1-135 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 1.20 E+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-1 39 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.OOE-1 7.53E-5 7.OOE-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.OOE+5 4.64E+2 Pr-144 3.01E 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 2.21 E+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 2.0- 19

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.5 (Page 1 of 2) I Ri Inhalation Pathway Dose Factors - TEEN (mrem/yr per pCi/m 3) I Nuclide H-3 Bone Liver 1.27E+3 Thyroid 1.27E+3 Kidney 1.27E+3 Lung 1.27E+3 GI-LLI 1.27E+3 T.Body 1.27E+3 I

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 P-32 1.38E+4 1.89E+6 1.38E+4 1.10E+5 1.38E+4 1.38E+4 1.38E+4 1.38E+4 9.28E+4 1.38E+4 7.16E+4 I

Cr-51 - - 7.50E+1 3.07E+1 2.10E+4 3.OOE+3 1.35E+2 Mn-54 Mn-56 Fe-55 3.34E+4 5.11E+4 1.70E+O

2.38E+4 1.27E+4 1.79E+O 1.98E+6 1.52E+4 1.24E+5 6.68E+4 5.74E+4 6.39E+3 8.40E+3 2.52E-1 5.54E+3 I

Fe-59 Co-57 Co-58 1.59E+4 3.70E+4 6.92E+2 2.07E+3 1.53E+6 5.86E+5

.-1.34E+6 1.78E+5 3.14E+4 9.52E+4 1.43E+4 9.20E+2 2.78E+3 I

Co-60 Ni-63 Ni-65 5.80E+5 2.18E+O 1.51E+4 4.34E+4 2.93E-1 8.72E+6 3.07E+5 9.36E+3 2.59E+5 1.42E+4 3.67E+4 1.98E+4 1.98E+4 1.27E-1 I

Cu-64 Zn-65 Zn-69 3.86E+4 4.83E-2 2.03E+0 1.34E+5 9.20E-2 6.41E+0 8.64E+4 6.02E-2 1.11E+4 1.24E+6 1.58E+3 6.14E+4 4.66E+4 2.85E+2 8.48E-1 6.24E+4 6.46E-3 I

Br-82 1.82E+4 I

Br-83 -.- - 3.44E+2 Br-84 * - - - 4.33E+2 Br-85 - 1.83E+1 Rb-86 Rb-88 1.90E+5 5.46E+2

" .1.77E+4 2.92E-5 8.40E+4 2.72E+2 I

Rb-89 - 3.52E+2 - 3.38E-7 2.33E+2 Sr-89 Sr-90 4.34E+5 1.08E+8

....- 2.42E+6 1.65E+7 3.71 E+5 7.65E+5 1.25E+4 6.68E+6 I Sr-91 8.80E+1 .6.07E+4 2.59E+5 3.51E+0 Sr-92 Y-90 Y-91m 9.52E+0 2.98E+3 3.70E-1

-2.74E+4 2.93E+5 3.20E+3 1.19E+5 5.59E+5 3.02E+1 4.06E-1 8.00E+1 1.42E-2 I

,Y-91 Y-92 Y-93 6.61E+5 1.47E+ 1 1.35E+2 2.94.E+6 2.68E+4 8.32E+4 4.09E+5

.1.65E+5 5.79E+5 1.77E+4 4.29E-1 3.72E+0 I

Zr-95 1..46E+5 4.58E+4 6.74E+4 2.69E+6 1.49E+5. 3.15E+4 Zr-97 Nb-95 1.38E+2 1.86E+4 2.72E+1 1.03E+4 4.12E+1 1.OOE+4 1.30E+5 7.51E+5 6.30E+5 9.68E+4 1.26E+1 5.66E+3 I

Nb-97 3.14E-1 7.78E-2 - 9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 Tc-99m 1.38E-3 1.69E+2 3.86E-3 4.11E+2 5.76E-2 1.54E+5 1.15E+3 2.69E+5 6.13E+3 3.22E+1 4.99E-2 I

Tc-101 5.92E-5 8.40E-5 - 1.52E-3 6.67E+2 8.72E-7 8.24E-4 2.0 - 20 I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.5 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - TEEN (mrem/yr per pCi/m 3)

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+O - 1.41E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 - 1.90E+5 1.61 E+7 9.60E+5 1.24E+4 Rh-103m - - -

Rh-106 - -

Ag-110m 1.38E+4 1.31 E+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+O 9.12E-1 1.42E+O 7.28E+O 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 1.51 E+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 1-130 6.24E+3 1.79E+4 1.49E+6 2.75E+4 9.12E+3 7.17E+3 1-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3 1.51 E+5 6.92E+3 1.27E+3 1.58E+3 1-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 1.03E+4 6.22E+3 1-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 2.04E+1 8.40E+2 1-135 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 1.21 E+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 5.31 E+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+O - 4.74E+4 1.77E+5 3.43E+O Np-239 3.38E+2 3.19E+1 - 1.OOE+2 6.49E+4 1.32E+5 1.77E+1 2.0 - 21

I 1ZE-ýAUNE r\,-VuU1,4-'- POWER rOvvr-m STl~r-AT IONq STTl OFFSITE DOSECALCULATION MANUAL ODCM 2.0 Revision 14 U

April 18, 2012 Table 2.6 (Page 1 of 2)

R, Inhalation Pathway Dose Factors - CHILD I (mrem/yr per pLCi/rn 3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body I

H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 Na-24 3.59E+4 1.61E+4 6.73E+3 1:61E+4 6.73E+3 1.61E+4 6.73E+3 1.61E+4 6.73E+3 1.61E+4 6.73E+3 1.61E+4 6.73E+3 1.61E+4 I

P-32 Cr-51 2.60E+6 1.14E+5 -

8.55E+1 2.43E+1 1.70E+4 4.22E+4 1.08E+3 9.88E+4 1.54E+2 I Mn-54 - 4.29E+4 - 1.OOE+4 1.58E+6 2.29E+4 9.51E+3 Mn-56 Fe-55 4.74E+4 1.66E+O 2.52E+4 1.67E+0 1.31E+4 1.11E+5 1.23E+5 2.87E+3 3.12E-1 7.77E+3 I Fe-59 2.07E+4 3.34E÷4 - - 1.27E+6 7.07E+4 1.67E+4 Co-57 Co-58 9.03E+2 1.77E+3 5.07E+5 1.11E+6 1.32E+4 3.44E+4 1.07E+3 3.16E+3 I Co-60 - 1.31E+4 - - 7.07E+6 9.62E+4 2.26E+4 Ni-63 Ni-65 8.21E+5 2.99E+0 4.63E+4 2.96E-1

- 2.75E+5 8.18E+3 6.33E+3 8.40E+4 2.80E+4 1.64E-1 I Cu-64 - 1.99E+O - 6.03E+O 9.58E+3 3.67E+4 1.07E+0 Zn-65 Zn-69 4.26E+4 6.70E-2 1.13E+5 9.66E-2 7.14E+4 5.85E-2 9.95E+5 1.42E+3 1.63E+4 1.02E+4 7.03E+4 8.92E-3 I Br-82 ... .. -. - 2.09E+4 Br-83 Br-84 ....

- - - - - 4.74E+2 5.48E+2 I Br-85 - - - ., - 2.53E+1 Rb-86 Rb-88 1.98E+5..

5.62E+2.

- ,-7.99E+3 1.72E+1 1.14E+5 3.66E+2 I Rb-89 - 3.45E+2- - - 1.89E+0 2.90E+2 Sr-89 Sr-90 5.99E+5 1.01E+8 2.16E+6 1.48E+7 1.67E+-5 3.43E+5 1.72E+4 6.44E+6 I Sr-91 1.21E+2 - 5.33E+4 1.74E+5 4.59E+O Sr-92 Y-90 Y-91m 1.31E+1 4.11E+3 5.07E-1 2.40E+4 2.62E+5 2.81E+3 2.42E+5 2.68E+5 1.72E+3 5.25E-1 1.11E+2 1.84E-2 I

Y-91-.

Y-92 Y-93 9.14E+5 2.04E+1 1.86E+2 2.63E+6 2.39E+4 7.44E+4 1.84E+5 2.39E+5 3.89E+5 2.44E+4 5.81 E-1 5.11E+0 I

Zr-95 Zr-97 Nb-95 1.90E+5 1.88E+2 2.35E+4 4.18E+4 2.72E+1 9.18E+3 5.96E+4 3.89E+1 8.62E+3 2.23E+6 1.13E+5 6.14E+5 6.11E+4 3.51E+5 3.70E+4 3.70E+4 1.60E+1 6.55E+3 I

Nb-97 Mo-99 Tc-99m 4.29E-1 1.78E-3 7.70E-2 1.72E+2 3.48E 18.55E-2 3.92E+2 5.07E-2 3.42E+3 1.35E+5 9.51E+2 2.78E+4 1.27E+5 4.81E+3 3.60E-2 4.26E+1 5.77E-2 I

Tc-101 8.10E-5 8.51E-5 1.45E-3 2.0 - 22 5.85E+2 1.63E+1 1.08E-3 I

I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.6 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - CHILD (mrem/yr per pCi/rn3)

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+O 1.59E+4 9.95E+4 5.55E-1 Ru-106 1.36E+5 - 1.84E+5 1.43E4-7 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.OOE+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 - 3.24E+6 1.64E+5 2.OOE+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+O 9.51E-1 1.96E+0 7.07E+0 1.OOE+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.OOE+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 1-130 8.18E+3 1.64E+4 1.85E+6 2.45E+4 - 5.11E+3 8.44E+3 1-131 4.81E+4 4.81E+4 1.62E+7.. 7.88E+4 - 2.84E+3 2.73E+4 1-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 - 3.20E+3 1.88E+3 1-133 1.66E+4 2.03E+4 3.85E+6' 3.38E+4 5.48E+3 7.70E+3 1-134 1.17E+3 2.16E+3_ 5.07E+4 3.30E+3 9.55E+2 9.95E+2 1-135 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 6.36E73 Ba-142 5.OOE-2 3.60E-5 __.. ... 2.91E-5 1.64E+3 2.74E+O 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.OOE+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.OOE-3 Nd-147 1.08E+4 8.73E+3 4.81E+3 3.28E+5 8.21E+4 6.81 E+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 2.0-23

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.7 (Page 1 of 2) I Ri Inhalation Pathway Dose Factors - INFANT (mrem/yr per iCi/m3) I Nuclide H-3 C-14 Bone 2.65E+4 Liver 6.47E+2 5.31E+3 Thyroid 6.47E+2 5.31E+3 Kidney 6.47E+2 5.31E+3 Lung 6.47E+2 5.31E+3 GI-LLI 6.47E+2 5.31E+3 T.Body 6.47E+2 5.31E+3 I

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 Cr-51 2.03E+6 1.12E+5 5.75E+1 1.32E+1 1.28E+4 1.61E+4 3.57E+2 7.74E+4 8.95E+1 I

Mn-54 - 2.53E+4 - 4.98E+3 1.OOE+6 7.06E+3 4.98E+3 Mn-56 Fe-55 1.97E+4 1.54E+0 1.17E+4 1.10E+0 1.25E+4 8.69E+4 7.17E+4 1.09E+3 2.21E-1 3.33E+3 I

Fe-59 1.36E+4 2.35E+4 - 1.02E+6 2.48E+4 9.48E+3 Co-57 Co-58 6.51E+2 1.22E+3

-3.79E+5 7.77E+5 4.86E+3 1,.11E+4 6.41E+2 1.82E+3 I Co-60 - 8.02E+3 - 4.51E+6 3.19E+4 1.18E+4 Ni-63 Ni-65 Cu-64 3.39E+5 2.39E+0 2.04E+4 2.84E-1 1.88E+O 2.09E+5

-8.12E+3 3.98E+0 9.30E+3 2.42E+3 5.01E+4 1.50E+4 1.16E+4 1.23E-1

.7.74E-1 I

Zn-65 Zn-69 Br-82 1.93E+4 5.39E-2 6.26E+4 9.67E-2 3.25E+4. 6.47E+5 4.02E-2. 1.47E+3 5.14E+4 1.32E+4 3.11E+4 7.18E-3 1.33E+4 I

Br-83 . 3.81E+2 Br-84 Br-85 4.OOE+2 2.04E+1 I

Rb-86 - 1.90E+5 - - 3.04E+3 8.82E+4 Rb-88 Rb-89 5.57E+2 3.21E+2 3.39E+2 6.82E+1 2.87E+2 2.06E+2 I

Sr-89 3.98E+5 - - 2.03E+6 6.40E+4 1.14E+4 Sr-90 Sr-91 4.09E+7 9.56E+1 1.12E+7 5.26E+4 1.31E+5 7.34E+4 2.59E+6 3.46E+0 I Sr-92 1.05E+1 -- - 2.38E+4 1.40E+5 3.91E-1 Y-90 Y-91m Y-91 3.29E+3 4.07E-1 5.88E+5 2.69E+5 2.79E+3 2.45E+6 1.04E+5 2.35E+3 7.03E+4 8.82E+1 1.39E-2 1.57E+4 I

Y-92 Y-93 Zr-95 1.64E+1 1.50E+2 1.15E+5 2.79E+4 -

3.11E+4 2.45E+4 7.64E+4 1.75E+6 1.27E+5 1.67E+5 2.17E+4 4.61E-1 4.07E+0 2.03E+4 I

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 Mo-99 3.42E-1 7.29E-2 1.65E+2 5.70E-2 2.65E+2 3.32E+3 1.35E+5 2.69E+4 4.87E+4 2.63E-2 3.23E+1 I

I 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 - 19.79E-4 5.84E+2 8.44E+2 8.12E-4 2.0 - 24

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.7 (Page 2 of 2)

Ri Inhalation Pathway Dose Factors - INFANT (mrem/yr per .LCi/m 3)

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+O - 8.99E-1 1.57E+4 4.84E+4 4.1OE-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.OOE+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+O 4.86E+O 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.OOE+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 1-130 6.36E+3 1.39E+4 1.60E+6 1.53E+4 - 1.99E+3 5.57E+3 1-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 - 1.06E+3 1.96E+4 1-132 1.69E+3 3.54E+3 1.69E+5- 3.95E+3 1.90E+3 1.26E+3 1-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 - 2.16E+3 5.60E+3 1-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 - 1.29E+3 6.65E+2 1-135 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 - 1190E+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 7.81 E+2 - 4.1OE+2 6.54E+1 8.76E+2 3.98E+2 Ba-139 1.48E+0 9.84E-4 - 5.92E-4 5.95E+3 5.1-OE+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.OOE+2 - 1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+O 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.OOE+2 W-187 1.30E+1 9.02E+O -... 3.96E+4 3.56E+4 3.12E+O Np-239 3.71E+2 3.32E+1 - 6.62E+1 5.95E+4 2.49E+4 1.88E+1 2.0 - 25

3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.8 (Page 1 of 2) I R1 Vegetation Pathway Dose Factors - ADULT (mrem/yr per iCi/m 3) for H-3 and C-14 (M 2

x mrem/yr i[Ci/sec) for others I Nuclide H-3 C-14 Bone 8.97E+5 Liver 2.26E+3 1.79E+5 Thyroid 2.26E+3 1.79E+5 Kidney 2.26E+3 1.79E+5 Lung 2.26E+3 1.79E+5 GI-LLI 2.26E+3 1.79E+5 T.Body 2.26E+3 1.79E+5 I

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 Cr-51 -

1.40E+9 8.73E+7

- 2.79E+4 1.03E+4 1.58E+8 6.19E+4 1.17E+7 5.42E+7 4.66E+4 I

Mn-54 - 3.11E+8 - 9.27E+7 - 9.54E+8 5.94E+7 Mn-56 Fe-55 2.09E+8 1.61E+1 1.45E+8 2.04E+1

- 5.13E+2 8.06E+7 8.29E+7 2.85E+0 3.37E+7 I

Fe-59 1.27E+8 2.99E+8 - - 8.35E+7 9.96E+8 1.14E+8 Co-57 Co-58 1.17E+7 3.09E+7 2.97E+8 6.26E+8 1.95E+7 6.92E+7 I

Co-60 -1.67E+8 - - - 3.14E+9 3.69E+8 Ni-63 Ni-65 Cu-64 1.04E+10 6.15E+1 7.21E+8 7.99E+O 9.27E+3 2.34E+4

- 1.50E+8 2.03E+2 7.90E+5 3.49E+8 3.65E+0 I

- - 4.35E+3 Zn-65 Zn-69 Br-82 3.17E+8 8.75E-6 1.01E+9 1.67E-5 6.75E+8 1.09E-5 6.36E+8 2.51E-6 1.73E+6 4.56E+8 1.16E-6 1.51E+6 I

Br-83 Br-84 Br-85 4.63E+0 3.21 E+O I

Rb-86 - 2.19E+8 4.32E+7 1.02E+8 I

R b-88 -- . - ....

Rb-89 - - - -

Sr-89 9.96E+9 -- - 1.60E+9 2.86E+8 Sr-90 Sr-91 6.05E+11 3.20E+5 1.75E+10 1.52E+6 1.48E+11 1.29E+4 I

Sr-92 4.27E+2 - 8.46E+3 1.85E+1 Y-90 Y-91m 1.33E+4 5.83E-9 1.41E+8 1.71E-8 3.56E+2

- I Y-91 5.13E+6 -- - 2.82E+9 1.37E+5 Y-92 Y-93 Zr-95 9.01E-1 1.74E+2 1.19E+6 3.81E+5 5.97E+5

.1.58E+4 5.52E+6 1.21E+9 2.63E-2 4.80E+0 2.58E+5 I

Zr-97 3.33E+2 6.73E+1 - 1.02E+2 - 2.08E+7 3.08E+1 Nb-95 Nb-97 Mo-99 1.42E+5 2.90E-6 7.91E+4 7.34E-7 6.25E+6

-_8.56E-7 7.81E+4 1.41E+7 4.80E+8 2.71E-3 1.45E+7 4.25E+4 2.68E-7 1.19E+6 I

I Tc-99m 3.06E+0 8.66E+O - 1.32E+2 4.24E+0 5.12E+3 1.10E+2 Tc-101 - I - I- - I -

2.0 - 26

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.8 (Page 2 of 2)

Ri Vegetation Pathway Dose Factors - ADULT (mrem/yr per [iCi/m 3) for H-3 and C-14 (M 2

x mrem/yr tCi/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-11im 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 5.1OE-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 1-130 3.96E+5 1.17E+6 9.90E+7 1.82E+6 - 1.01E+6 4.61E+5 1-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 3.05E+7 6.63E+7 1-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 2.89E+1 5.38E+1 1-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 3.31E+6 1.12E+6 1-134 1.06E-4 2.88E-4 5.OOE-3 4.59E-4 2.51E-7 1.03E-4 1-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 - 1.21E+5 3.94E+4 1.11E+1 Cs-134 4.66E+9 0 - 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+8 - 9.24E+7 1.27E4:7 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 2.1OE-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 7 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.E+ 1.40E+2 - 4.37E+2 - 2.87E+7 7.72E+1 2.0 - 27

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 U

April 18, 2012 Table 2.9 (Page 1 of 2)

Ri Vegetation Pathway Dose Factors - TEEN I

k.rIe, r, per ... fI' 1,.,, H-3 and C-,14-It X mrem/yr pCi/sec) for others I

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 C-14 1.45E+6 2.59E+3 2.91E+5 2.59E+3 2.91E+5 2.59E+3 2.91E+5 2.59E+3 2.91E+5 2.59E+3 2.91E+5 2.59E+3 2.91E+5 I

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 Cr-51 -

1.61 E+9 9.96E+7 3.44E+4 1.36E+4 8.85E+4 1.35E+8 1.04E+7 6.23E+7 6.20E+4 I Mn-54 - 4.52E+8 - 1.35E+8 - 9.27E+8 8.97E+7 Mn-56 Fe-55 Fe-59 3.25E+8 1.81E+8 1.45E+1 2.31E+8 4.22E+8 1.83E+1 - 9.54E+2 1.46E+8 9.98E+7 1.33E+8 9.98E+8 2.58E+0 5.38E+7 1.63E+8 N

Co-57 Co-58 Co-60 1.79E+7 4.38E+7 2.49E+8 3.34E+8 6.04E+8 3.24E+9 3.OOE+7 1.01 E+8 5.60E+8 I

Ni-63 1.61EE+-10 1.13E+9 1.81E+8 5.45E+8 Ni-65 Cu-64 5.73E+1 7.32E+0 8.40E+3 2.12E+4 -

3.97E+2 6.51EE+5 3.33E+0 3.95E+3 I

Zn-65 4.24E+8 1.47E+9 9.41E+8 - 6.23E+8 6.86E+8 I

Zn-69 8.19E-6 1.56E-5 . 1.02E-5 - 2.88E-5 1.09E-6 Br-82 -- " - 1.33E+6 Br-83 - _ 13.01E+0 Br-84 Br-85 -

I 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 U

Sr-90 Sr-91 Sr-92 7.51E+11 2.99E+5 3.97E+2

-2.11E+10 1.36E+6 1.01 E+4 1.85E+11 1.19E+4 1.69E+1 I

Y-90 1.24E+4 1.02E+8 3.34E+2 I

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 Zr-95 1.63E+2 1.74E+6 5.49E+5

- 8.07E+5 -

4.98E+6 1.27E+9 4.47E+0 3.78E+5 I

Zr-97 3.09E+2 6.11E+1 - 9.26E+1 - 1.65E+7 2.81E+1 Nb-95 Nb-97 1.92E+5 2.69E-6 1.06E+5 6.67E-7 1.03E+5 7.80E-7 4.55E+8 1.59E-2 5.86E+4 2.44E-7 I Mo-99 5.74E+6 - 1.31E+7 - 1.03E+7 1.09E+6 Tc-99m Tc-101 2.70E+O 7.54E+0 -

1.12E+2 4.19E+0 4.95E+3 9.77E+1 I

2.0 - 28 I I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.9 (Page 2 of 2)

Rj Vegetation Pathway Dose Factors - TEEN 3

(mrem/yr per GuCi/m ) for H-3 and C-14 (ml 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-11Orn 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.OOE+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 1.51 E-4 Te-131m 8.44E+5 4.05E+5 6.09E+5 4.22E+6 - 3.25Et7 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 1-130 3.54E+5 1.02E+6 8.35E+7 1.58E+6 - 7.87E+5 4.09E+5 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 - 2.13E+7 5.79E+7 1-132 5.18E+1 1.36E+2 4.57E+3, 2.14E+2 - 5.91E+1 4.87E+1 1-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 - 2.53E+6 1.02E+6 1-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 - 3.35E-6 9.13E-5 1-135 3.68E+4 9.48E+4 6.1OE+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 - i5.08E+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 - 2.1OE+7 7.24Et1 2.0 - 29

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.10 (Page 1 of 2)

R, Vegetation Pathway Dose Factors - CHILD I

(M.rem.. /yr per ..I I.m for H-3 and C-14 (ik "ti/sec) mrem/yr for others I

Nuclide Bone H-3 C-14 3.50E+6 Liver 4.01E+3 7.01E+5 Thyroid 4.01E+3 7.01E+5 Kidney 4.01E+3 7.01E+5 Lung 4.01E+3 7.01E+5 GI-LLI 4.01E+3 7.01E+5 T.Body 4.01E+3 7.01E+5 I

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 Cr-51 3.37E+9 1.58E+8 -

6.54E+4 1.79E+4 9.30E+7 1.19E+5 6.25E+6 1.30E+8 1.18E+5 I

Mn-54 - 6.61E+8 - 1.85E+8 - 5.55E+8 1.76E+8 Mn-56 Fe-55 8.OOE+8 1.90E+1 4.24E+8 2.29E+1

- 2.75E+3 2.40E+8 7.86E+7 4.28E+O 1.31 E+8 I

Fe-59 4.01 E+8 6.49E+8 - - 1.88E+8 6.76E+8 3.23E+8 Co-57 Co-58 2.99E+7 6.47E+7 2.45E+8 3.77E+8 6.04E+7 1.98E+8 I

Co-60 - 3.78E+8 - 2.1OE+9 1.12E+9 Ni-63 Ni-65 Cu-64 3.95E+10 1.05E+2 2.11E+9 9.89E+O 1.11E+4 2.68E+4, 1.42E+8 1.21E+3 5.20E+5 1.34E+9 5.77E+0 I 6.69E+3 Zn-65 Zn-69 Br-82 8.12E+8 1.51E-5 2.16E+9 2.18E-5 1.36E+9 1.32E-5 3.80E+8 1.38E-3 1.35E+9 2.02E-6 2.04E+6 I

Br-83 Br-84 Br-85 5.55E+0 I

Rb-86 4.52E+8 12.91E+7 2.78E+8 I

Rb-88 -- .

Rb-89 -

Sr-89 3.59E+10 - 1.39E+9 1.03E+9 Sr-90 Sr-91

.1.24E+12 5.50E+5 1.67E+10 1.21E+6 3.15E+11 2.08E+4 I

Sr-92 7.28E+2 - - 1.38E+4 2.92E+1 Y-90 Y-91m 2.30E+4 9.94E-9

"" - 6.56E+7 1.95E-5 6.17E+2 I

Y-91 1.87E+7 -- 2.49E+9 5.01E+5 Y-92 Y-93 Zr-95 1.56E+0 3.01E+2 3.90E+6 8.58E+5 - 1.23E+6 -

4.51E+4 4.48E+6 8.95E+8 4.46E-2 8.25E+O 7.64E+5 I

Zr-97 Nb-95 Nb-97 5.64E+2 4.1OE+5 4.90E-6 8.15E+1 1.59E+5 8.85E-7 1.17E+2 1.50E+5 9.82E-7 1.23E+7 2.95E+8 2.73E-1 4.81E+1 1.14E+5 4.13E-7 I

Mo-99 7.83E+6 1.67E+7 -

6.48E+6 1.94E+6 I

Tc-99m 4.65E+O 9.12E+0 - .1.33E+2 4.63E+0 5.19E+3 1.51E+2 T o-101lI-- - - - - -

2.0 - 30 I 3

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.10 (Page 2 of 2)

R, Vegetation Pathway Dose Factors - CHILD (mrem/yr per ICi/m3) for H-3 and C-14 (m 2 x mrem/yr pLCi/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-11Orn 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 3.51 E+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.OOE+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 8.22E74 3.37E-3 - 7.17E-2 2.74E-4 Te-131m 1.54E+6 5.33E+5 1.1OE+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 1-130 6.21E+5 1.26E+6- 1:.38E+8 1.88E+6 - 5.87E+5 6.47E+5 1-131 1.43E+8 1.44E+8 4..76E-10. 2.36E+8 - 1.28E+7 8.18E+7 1-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 1.79E+6 1.68E+6 1-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 - 2.10E-4 1.46E-4 1-135 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 0s-1 38 I-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 2.0 - 31

U KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, .2012 Table 2.11 (Page 1 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - ADULT I

(mrern/yr per 1.Ci/m 3) for H-3 and C-14 (m2 x mrem/yr iLCi/sec) for others I

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 C-14 3.63E+5 7.63E+2 7.26E+4 7.63E+2 7.26E+4 7.63E+2 7.26E+4 7.63E+2 7.26E+4 7.63E+2 7.26E+4 7.63E+2 7.26E+4 I Na-24 P-32 Cr-51 2.54E+6 1.71E+10 2.54E+6 1.06E+9 2.54E+6 1.71 E+4 2.54E+6 6.30E+3 2.54E+6 3.80E+4 2.54E+6 1.92E+9 7.20E+6 2.54E+6 6.60E+8 2.86E+4 1

Mn-54 - 8.40E+6 - 2.50E+6 2.57E+7 1.60E+6 I

Mn-56 - 4.23E-3 - 5.38E 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.OOE+7 - 1.95E+7 2.33E+8 2.68E+7 Co-57 Co-58 1.28E+6 4.72E+6 3.25E+7 9.57E+7 2.13E+6 1.06E+7 I

Co-60 - 1.64E+7 - 3.08E+8 3.62E+7 Ni-63 Ni-65 6.73E+9 3.70E-1 4.66E+8 4.81 E-2 9.73E+7 1.22E+0 2.26E+8 2.19E-2 I Cu-64 - 2.41E+4 6.08E+4 - 2.05E+6 1.13E+4 Zn-65 Zn-69 Br-82 1.37E+9 4.36E+9 2.92E+9 - 2.75E+9 1.97E+9 3.72E+7 3.25E+7 i

Br-83 Br-84 Br-85 1.49E-1 1.03E-1 i

Rb-86 2.59E+9 5.11E+8 1.21E+9 I

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 Sr-92 3.13E+4 4.89E-1

- - 1.49E+5 9.68E+O 1.27E+3 2.11E-2 I

Y-90 Y-91m 7.07E+1 7.50E+5 1.90E+O I

Y-91 8.60E+3 .- - 4.73E+6 2.30E+2 Y-92 Y-93 Zr-95 5.42E-5 2.33E-1 9.46E+2 3.03E+2 4.76E+2 9.49E-1 7.39E+3 9.62E+5 1.58E-6 6.43E-3 2.05E+2 I

Zr-97 Nb-95 Nb-97 4.26E-1 8.25E+4 8.59E-2 4.59E+4 1.30E-1 4.54E+4 2.66E+4 2.79E+8 5.47E-9 3.93E-2 2.47E+4 I

Mo-99 - 2.52E+7 - 5.72E+7 - 5.85E+7 4.80E+6 Tc-99m Tc-101 3.25E+O 9.19E+0 - 11.40E+2 4.50E+O 5.44E+3 1.17E+2 I 2.0 - 32

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.11 (Page 2 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - ADULT 3

(mrem/yr per ,Ci/rn ) for H-3 and C-14 (M 2

x mrem/yr l-,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-2 - 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.OOE+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-131rm 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 1-130 4.26E+5 1.26E+6 1.07E+8' 1.96E+6 - 1.08E+6 4.96E+5 1-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 - 1.12E+8 2.43E+8 1-132 1.64E-1 4.37E-1 1.53E+1 6.97E 8.22E-2 1.53E-1 1-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 6.20E+6 2.1OE+6 1-134 -------

k-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 --- 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-t 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+O 7 7.39E+4 1.98E-1 2.0 - 33

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.12 (Page 1 of 2)

R, Grass-Cow-Milk Pathway Dose Factors - TEEN I

(m,,em/,yr per p.,I/.,,, for H-3 and C-I (_ 2 X mrem/yr . .I. o te I

Nuclide Bone H-3 C-14 6.70E+5 Liver 9.94E+2 1.34E+5 Thyroid 9.94E+2 1.34E+5 Kidney 9.94E+2 1.34E+5 Lung 9.94E+2 1.34E+5 GI-LLI 9.94E+2 1.34E+5 T.Body 9.94E+2 1.34E+5 I

Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 P-32 Cr-51 3.15E+10 1.95E+9 2.78E+4 1.10E+4 4.44E+6 7.13E+4 4.44E+6 2.65E+9 8.40E+6 4.44E+6 1.22E+9 5.OOE+4 I

Mn-54 - 1.40E+7 - 4.17E+6 - 2.87E+7 2.78E+6 Mn-56 Fe-55 4.45E+7 7.51E-3 3.16E+7 9.50E-3 -

2.00E+7 4.94E-1 1.37E+7 1.33E-3 7.36E+6 I

Fe-59 5.20E+7 1.21E+8 - 3.82E+7 2.87E+8 4.68E+7 Co-57 Co-58 2.25E+6 7.95E+6

- 4.19E+7 1.10E+8 3.76E+6 1.83E+7 I

Co-60 - 2.78E+7 - 3.62E+8 6.26E+7 Ni-63 Ni-65 1.18E+10 6.78E-1 8.35E+8 8.66E-2 1.33E+8 4.70E+0 4.01E+8 3.94E-2 I Cu-64 - 4.29E+4 - 1.09E+5 - 3.33E+6 2.02E+4 Zn-65 Zn-69 Br-82 2.11E+9 7.31E+9 - 4.68E+9 -

3.10E+9 3.41E+9 5.64E+7 I

Br-83 Br-84 Br-85 1.91E-1 Rb-86 - 4.73E+9 - 7.OOE+8 2.22E+9 Rb-88 Rb-89

- I Sr-89 2.67E+9 - 3.18E+8 7.66E+7 Sr-90 Sr-91 6.61E+10 5.75E+4 1.86E+9 2.61 E+5 1.63E+10 2.29E+3 I

Sr-92 8.95E-1 - 2.28E+1 3.81 E-2 Y-90 Y-91m 1.30E+2 1.07E+6 3.50E+0 I

Y-91. 1.58E+4 - - - 6.48E+6 4.24E+2 Y-92 Y-93 Zr-95 1.OOE-4 4.30E-1 1.65E+3 5.22E+2

- 7.67E+2 2.75E+0 1.31E+4 1.20E+6 2.90E-6 1.18E-2 3.59E+2 I

Zr-97 Nb-95 Nb-97 -

7.75E-1 1.41E+5 1.53E-1 7.80E+4 2.32E-1 7.57E+4 4.15E+4 3.34E+8 6.34E-8 7.06E-2 4.30E+4 I

Mo-99 - 4.56E+7 1.04E+8 8.16E+7 8.69E+6 I

Tc-99m 5.64E+0 1.57E+1 - 2.34E+2 8.73E+0 1.03E+4 2.04E+2 Tc-101 .....

2.0 - 34 I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.12 (Page 2 of 2)

R, Grass-Cow-Milk Pathway Dose Factors - TEEN (mrem/yr per pCi/m 3) for H-3 and C-14 (M 2

x mrem/yr iCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.81 E+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.OOE+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 - 2.1OE+8 1.OOE+7 Te-127 1.24E+3 4.41EE+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 1-130 7.49E+5 2.17E+6 1.77E+8 3.34E+6 - 1.67E+6 8.66E+5 1-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 - 1.49E-8 4.04E+8 1-132 2.90E-1 7.59E-1 2.56E+1 1.20E+0 - 3.31E-1 2.72E-1 1-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 - 9.30E+6 3.75E+6 1-134 _ -

1-135 2.47E+4 6.35E+4 4.08E+6 1.OOE+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.OOE+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 6.81 E+2 Ce-143 7.69E+1 5.60E+4 - 2.51E+1 _ 1.68E+6 6.25E+O 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 2.0 - 35

I KEVVAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.13 (Page 1 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - CHILD I

1/y per i.Cilm 3 for H-3, and C'- 14 (i

.mre mrem/yr iLCi/sec) for others I

Nuclide H-3 C-14 Bone 1.65E+6 Liver 1.57E+3 3.29E+5 Thyroid 1.57E+3 3.29E+5 Kidney 1.57E+3 3.29E+5 Lung 1.57E+3 3.29E+5 GI-LLI 1.57E+3 3.29E+5 T.Body 1.57E+3 3.29E+5 I

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 Cr-51 7.77E+10 3.64E+9 -

5.66E+.4 1.55E+4 1.03E+5 2.15E+9 5.41E+6 3.OOE+9 1.02E+5 I

Mn-54 - 2.09E+7 - 5.87E+6 - 1.76E+7 5.58E+6 Mn-56 Fe-55 1.12E+8 1.31E-2 5.93E+7

- 1.58E-2 -

3.35E+7 1.90E+O 1.10E+7 2.95E-3 1.84E+7 I

Fe-59 1.20E+8 1.95E+8 - 15.65E+7 2.03E+8 9.71E+7 Co-57 Co-58 3.84E+6 1.21EE+7 3.14E+7 7.08E+7 7.77E+6 3.72E+7 I Co-60 - 4.32E+7 - - - 2.39E+8 1.27E+8 Ni-63 Ni-65 Cu-64 2.96E+10 1.66E+0

-7.55E+4 1.59E+9 1.56E-1 1.82E+5 -

1.07E+8 1.91E+1 3.54E+6 1.01E+9 9.11E-2 4.56E+4 I

Zn-65 Zn-69 Br-82 4.13E+9 1.10E+10 - 6.94E+9

- 1.93E+9 2.14E-9 6.85E+9 1.15E+8 I

Br-83 4.69E-1 Br-84 Br-85 I

Rb-86 8.77E+9 - 5.64E+8 5.39E+9 I

Rb-88 -

Rb-89 - -

Sr-89 6.62E+9 -- - 2.56E+8 1.89E+8 Sr-90 Sr-91 1.12E+11 -

1.41E+5 . -

1.51E+9 3.12E+5 2.83E+10 5.33E+3 I Sr-92 2.19E+O - 4.14E+1 8.76E-2 Y-90 Y-91m Y-91 3.22E+2 3.91E+4 9.15E+5 5.21E+6 8.61E+0 1.04E+3 I

Y-92 Y-93 Zr-95 2.46E-4 1.06E+0 3.84E+3 8.45E+2

- 1.21E+3 -

7.10E+0 1.57E+4 8.81E+5 7.03E-6 2.90E-2 7.52E+2 I

Zr-97 1.89E+0 2.72E-1 - 3.91E-1 - 4.13E+4 1.61E-1 Nb-95 Nb-97 3.18E+5 1.24E+5 - 1.16E+5 2.29E+8 1.45E-6 8.84E+4 I

Mo-99 - 8.29E+7 - 1.77E+8 - 6.86E+7 2.05E+7 Tc-99m Tc-101 -

1.29E+1 2.54E+1 3.68E+2 1.29E+1 1.44E+4 4.20E+2 I

2.0 - 36 I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.13 (Page 2 of 2)

R, Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem/yr per i.Ci/rn 3) for H-3 and C-14 (m2 x mrem/yr pLCi/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.OOE+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.OOE+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 1-130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 - 1.66E+6 1.82E+6 1-131 1.30E+9 1.31E+9 4.34E411 2.15E+9 - 1.17E+8 7.46E+8 1-132 6.86E-1 1.26E+0 5.85E+1 1:93E+0 - 1.48E+O 5.80E-1 1-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 - 8.77E+6 8.23E+6 1-134 - " - - -

1-135 5.84E+4 1.05E+5 9.30E+6 1.-61E+5 8.OOE+4 4.97E+4 Cs-134 2.26E+10 3.71EE+10 - 1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs-136 1.OOE+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 - 5.71 E+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 2.0 -37

I KEVVAUNEE POVVER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.14 (Page 1 of 2)

Ri Grass-Cow-Milk'Pathway Dose Factors - INFANT I

(..re/.yr,per u....I..) for H-3 and C-14 (mn x mrem/yr ia*ilsec) for others I

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 Na-24 3.23E+6 1.61E+7 6.89E+5 1.61E+7 6.89E+5 1.61E+7 6.89E+5 1.61E+7 6.89E+5 1.61E+7 6.89E+5 1.61E+7 6.89E+5 1.61E+7 I 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 Fe-55 1.35E+8 3.21E-2 8.72E+7 2.76E-2 -

4.27E+7 2.91E+O 5.53E-3 1.11E+7 2.33E+7 I

Fe-59 2.25E+8 3.93E+8 - 1.16E+8 1.88E+8 1.55E+8 Co-57 Co-58 8.95E+6 2.43E+7 3.05E+7 1.46E+7 6.05E+7 6.06E+7 I Co-60 - 8.81E+7 - 2.1OE+8 2.08E+8 Ni-63 Ni-65 Cu-64 3.49E+10 3.51 E+0 2.16E+9 3.97E-1 1.88E+5

- 3.17E+5 1.07E+8 3.02E+1 1.21E+9 1.81 E-1 3.85E+6 8.69E+4 I

Zn-65 Zn-69 Br-82 5.55E+9 1.90E+10 -

9.23E+9 -

1.61E+10 8.78E+9 7.36E-9 -

1.94E+8 I

Br-83 - 9.95E-1 Br-84 i 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 Sr-91 1.22E+11 2.94E+5 -

- 1.52E+9 3.48E+5 3.10E+10 1.06E+4 I Sr-92 4.65E+O - - 5.01E+1 1.73E-1 Y-90 Y-91m Y-91 6.80E+2 7.33E+4 9.39E+5 5.26E+6 1.82E+1 1.95E+3 I

Y-92 Y-93 Zr-95 5.22E-4 2.25E+0 6.83E+3 1.66E+3 1.79E+3 -

9.97E+0 1.78E+4 8.28E+5 1.47E-5 6.13E-2 1.18E+3 I

Zr-97 3.99E+0 6.85E-1 6.91 E-1 4.37E+4 3.13E-1 Nb-95 Nb-97 5.93E+5 2.44E+5 1.75E+5 2.06E+8 3.70E-6 1.41E+5 I

Mo-99 - 2.12E+8 - 3.17E+8 - 6.98E+7 4.13E+7 Tc-99m Tc-101 2.69E+1, 5.55E+1 - 5.97E+2 2.90E+1 1.61 E+4 7.15E+2 I 2.0 - 38

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.14 (Page 2 of 2)

Ri Grass-Cow-Milk Pathway Dose Factors - INFANT (mrem/yr per i.Ci/rn 3) for H-3 and C-14 (M 2

x mrem/yr pLCi/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 i..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 5.1OE+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 2.1OE+7 1.04E+7 1.54E+7. 6.51E+7 . 3.85E+7 9.72E+6 1-130 3.60E+6 7.92E+6 8.88E+8 8.70E+6 1.70E+6 3.18E+6 1-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 1.15E+8 1.41E+9 1-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 - 2.34E+0 1.03E+0 1-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 ' 9.16E+6 1.58E+7 1-134 - - 1.01 E-9 .. -

1-135 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.OOE+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 7.41 E+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 2.0 - 39

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 14 I

April 18, 2012 Table 2.15 (Page 1 of 2)

Ri Ground Plane Pathway Dose Factors I

km

,n/ 2 x mremn/yr per itk*,/ec*....

I Nuclide H-3 C-14 Any Organ i

Na-24 P-32 Cr-51 1.21E+7 4.68E+6 I

Mn-54 1.34E+9 Mn-56 Fe-55 9.05E+5 I Fe-59 2.75E+8 Co-57 Co-58 4.37E+8 3.82E+8 I

Co-60 2.16E+10 Ni-63 Ni-65 2.97E+5 Cu-64 Zn-65 6.09E+5 7.45E+8 I

Zn-69 Br-82 4.57E+7 Br-83 Br-84 Br-85 4.89E+3 2.03E+5 I Rb-86 8.98E+6 Rb-88 Rb-89 3.29E+4 1.21E+5 I

Sr-89 2.16E+4 Sr-90 Sr-91 2.19E+6 I

Sr-92 7.77E+5 Y-90 Y-91m 4.48E+3 1.01E+5 I Y-91 1.08E+6 Y-92.

Y-93 Zr-95 1.80E+5 1.85E+5 2.48E+8 I

Zr-97 Nb-95 Nb-97 2.94E+6 1.36E+8 2.28E+6 I

Mo-99 4.05E+6 Tc-99m Tc-101 1.83E+5 2.04E+4 I

Ru-103 1.09E+8 2.0 -40 I

KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table 2.15 (Page 2 of 2)

R1 Ground Plane Pathway Dose Factors (M 2 x mrem/yr per ltCi/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.OOE+7 Te-129 2.60E+4 Te-131 m 8.03E+6 Te-131 2.93E+4 Te-132 4.22E+6 1-130 5.53E+6 1-131 1.72E+7 1-132 1.24E+6 1-133 2.47E+6 1-134 4.49E+5 1-135 2.56E+6 Cs-1 34 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 2.0-41

I KEVVAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 14 I

April 18, 2012 APPENDIX A I

TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS - LIQUID RADIOACTIVE EFFLUENTS I

I I

A-I I

I

KEWAUNEE POWER STATION ODCM App-A OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Technical Basis for Effective Dose Factors -

Liquid Effluent Releases To verify that the current approach to determining environmental doses using a simplified method has remained consistent since the previous analysis (performed using effluent data from 1981-1983), a similar evaluation was performed using the liquid effluent release data from 2000-2002. From the effluent data, the dose contribution of the radionuclide mixture can be obtained to provide a simplified method of determining compliance with the dose limits of ODCM Normal Condition 13.1.2. For the radionuclide distribution of effluents from the Kewaunee Power Station, the controlling organ is either the GI-LLI or the liver. The calculated GI-LL1 dose is almost exclusively dictated by the Nb-95 releases; the liver dose is mostly a function of the Cs-134 and Fe-55 releases. The radionuclides, Fe-55, Co-58, Co-60, Sr-90, and Cs-137 contribute essentially all of the calculated total body dose. The results of this evaluation are presented in Table A-I. The individual nuclide doses used in the dose comparisons of Table A-I were calculated using the total curies released via batch and continuous releases as reported in the Annual Radioactive Effluent Release Report, weighted by the appropriate dose factors.

Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is negligible. From 2000-2002, the maximum tritium release from the Kewaunee Power Station to Lake Michigan was 270 curies.

The calculated total body dose from such a release is 1.36E-02 mrem/yr via the fish ingestion and drinking water pathways. This amounts to 0.07% of the design objective dose of 3 mrerm/yr.

Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation.

For purposes of simplifying the details of the dose calculational process, it is conservative to identify a controlling, dose significant radionuclide and limit the calculational process to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculational method that is simplified while also being conservative.

While not present in the 2000-2002 liquid effluent releases, it still remains conservative to use the Cs-134 dose conversion factor (7.09E+05 mrem/hr per !aCi/ml, liver) to evaluate the maximum organ dose. Only the reactor-generated radionuclide Nb-95 has a higher dose conversion factor (1.5]E+06 mrem/hr per jiCi/ml, GI-LL1). However, since Nb-95 releases are typically less than 5% of the total releases, it is conservative to use the Cs-134 factor. By this approach, the maximum organ dose will be routinely overestimated. For 2000, using this simplified conservative method (CW value of 2.OOE+05 gpm) would overestimate the maximum organ dose as reported in the Annual Radioactive Effluent Release Report by a factor of 234; for 2001, the conservatism is a factor of 109; and for 2002, a factor of 730. This comparison is shown in Table A-2.

A-2

KEWAUNEE POWER STATION ODCM App-A OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 For the total body calculation, the Cs-134 dose factor (5.79E+05 mrem/hr per iLtCi/ml, total body) is again used since it is higher than the identified dominant nuclides. For 2000, using this simplified conservative dose calculational method would overestimate the total body dose by a factor of 253; for 2001, the conservatism is a factor of 105; and for 2002, a factor of 601.

For evaluating compliance with the dose limits of ODCM Normal Condition 13.1.2 the following simplified equations may be used:

Total Body DtbDb==1.67E- 02 x VOL x Acs-134. T8XECi (A.1I)

CW where:

Dtb = dose to the total body (mrem)

ACsJ34,TB = 5.79E+05, total body ingestion dose conversion factor for Cs-134 (mrem/hr per ptCi/ml)

VOL = volume of liquid effluent released (gal)

YXCi = total concentration of all radionuclides (jiCi/ml)

CW = average circulating water discharge rate during release period (gal/inin) 1.67E-02 = conversion factor (hr/min)

Substituting the value for the Cs-134 total body dose conversion factor, the equation simplifies to:

Dit = 9.67E + 03 x VOL xjC (A.2)

CW Maximum Organ Dom= 1.6 7 E - 02 x VOL x AcS-134. LxZCi (A.3)

CW where:

Dmax = maximum organ dose (mrem)

Ac*-134,L = 7.09E+05, liver ingestion dose conversion factor for Cs-134 (mrem/hr per VtCi/ml)

A-3

KEWAUNEE POWER STATION ODCM App-A OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Substituting the value for Acs-134,Liver the equation simplifies to:

Dm.... 1_'8E+04xVOL CWnxZC (A.4)

Only the total body dose need be evaluated by this simplified method since it represents the more limiting (compared with the maximum organ dose) for demonstrating compliance with ODCM Normal Condition 13.1.2.

A-4

KEWAUNEE POWER STATION ODCM App-A OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table A-1 Adult Dose Contributions Fish and Drinking Water Pathways 2000 2001 2002 Radio- Release TB GI-LLI Liver Release TB GI-LLI Liver Release TB GI-LLI Liver nuclide (Ci) Dose Dose Dose (Ci) Dose Dose Dose (Ci) Dose Dose Dose Frac. Frac. Frac. Frac. Frac. Frac. Frac. IFrac. Frac.

Fe-55 4.81E 0.03 0.02 0.10 0.04 0.03 0.13 3.69E 0.19 0.02 0.84 02 02 02 Co-58 8.07E- 0.01 0.03 4 *.09E- 0.01 0.02 4.94E- 0.05 0.02 0.02 03 03 03 Fe-59 2.77E- 2.44E-

1.65E- 0

~~0.01 0.02 00 04 04 04 Co-60 4.71E- 0.62 0.04 0.01 03 0.02 0.05 0.01 2.07E- 0.06 0.02 0.03

_____ 03 03 _____ 03 ____

Br-82 4.94E- 0.01 1.44E- N/D 04 04 Sr-90 2.25E- 0.18 0.01 2.50E- 0.25 0.01 9.76E-04 04 05 Nb-95 3.41 E- 0.89 2.39E- 0.86 2.45E- 0.91 04 04 04 Cs-137 3.70E- 0.75 0.01 0.88 2.74E- 0.68 0.01 0.85 3.04E- 0.05

0.08 04 04 06

Less than 0.01 N/D = not detected A-5 Mm mm mmmm -mm m m m m m m m

KEWAUNEE POWER STATION ODCM App-A OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table A-2 Adult Liver and Total Body Dose Assessment Dose Via the Simplified Method Versus the Actual Calculated Dose 2000 2001 2002 Simplified Liver Dose (mRem)* 1. 16E+00 9.87E-01 7.88E-01 Actual Liver Dose (mRem)** 4.97E-03 9.02E-03 1.08E-03 Simplified divided by Actual 234 109 730 Simplified Total Body Dose (mRem)

9.53E-01 8.09E-01 6.46E-0 I Actual Total Body Dose (mRem)

- 3.77E-03 7.73E-03 1.07E-03 Simplified divided by Actual 253 105 601

Assuming 2.OOE+05 gpm circulating water flow

- From the Annual Radioactive Effluent Release Report A-6

KEWAUNEE POWER STATION ODCM App-B OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 APPENDIX B TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -

GASEOUS RADIOACTIVE EFFLUENTS B-1

KEWAUNEE POWER STATION ODCM App-B OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 APPENDIX B Technical Basis for Effective Dose Factors -

Gaseous Radioactive Effluents Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors, which are radionuclide specific. These effective factors, which can be based on typical radionuclide distributions of releases, can be applied to the total radioactivity released to approximate the dose in the environment (i.e., instead of having to perform individual radionuclide dose analyses only a single multiplication (Ke~f, Meff or Neff) times the total quantity of radioactive material released would be needed). This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

Keff= I(K<ix fi) (B.1) where:

Ken- = the effective total body dose factor due to gamma emissions from all noble gases released Ki - the total body dose factor due to gamma emissions from each noble gas radionuclide "i" released fii - the fractional abundance of noble gas radionuclide "i" relative to the total noble gas activity (L + I. IM)e, = I[(Li + 1.1 Nt)x f] (B.2) where:

(L + 1.1 M)er = the effective skin dose factor due to beta and gamma emissions from all noble gases released (Li + 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide "i" released Merff Z(M x f') (B.3)

B-2

I KEWAUNEE POWER STATION ODCM App-B I OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 3 where:

Merf = the effective air dose factor due to gamma emissions from all noble gases released I Mi the air dose factor due to gamma emissions from each noble gas radionuclide "i" released Nfr= Z(Nix fi) (B.4) where:U Neoc = the effective air dose factor due to beta emissions from all noble gases released 3 Ni the air dose factor due to beta emissions from each noble gas radionuclide "i" released 3 Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from Kewaunee I have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful evaluations difficult. For the years of 2000, 2001 and 2002, the total noble gas releases have been limited to 2.54E-04 Ci for 2000, 1.37E-01 Ci for 2001, and 1.91E-02 Ci for 2002. Therefore, in order to provide a reasonable basis for the derivation of the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.1, "Source I

Term Specifications," has been used as representing a typical distribution. The effective dose factors as derived are presented in Table B-1.

Application 3 To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used. This conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

I For evaluating compliance with the dose limits of ODCM Normal Condition 13.2.2, the following simplified equations may be used:

3 .7 E 8 Dy xX/Qx Mffx iQ, (B.5) 0.50 D= 7E 08 X/Q x x Nf- x ZQi (B.6) 0.50 where:

B-3

KEWAUNEE POWER STATION ODCM App-B OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Dy = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)

= air dose due to beta emissions for the cumulative release of all noble gases (mrad) z/Q = atmospheric dispersion to the controlling SITE BOUNDARY (sec/mi3 )

Merr = 5.3E+02, effective gamma-air dose factor (mrad/yr per VtCi/rn)

Neff = 1.1E+03, effective beta-air dose factor (mrad/yr per 3 ViCi/m )

Y XQ = cumulative release for all noble ga' radionuclides (ýtCi) 3.17E-08 = conversion factor (yr/sec) 0.50 - conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to:

D,=3.5E-05,xX/Qx-Q1 (B.7) and D= 7.OE-05xX/Qx E Q (B.8)

The effective dose factors are used on a very limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable. Dose assessments using the detailed, radionuclide dependent calculation are performed at least annually for preparation of the Radioactive Effluent Reports. Comparisonscan be performed at this time to assure that the use of the effective dose factors does not substantially underestimate actual doses.

B-4

I KEWAUNEE POWER STATION ODCM App-B I

OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I Table B-1 I Effective Dose Factors - Noble Gases Total Body Effective Dose Factor Skin Effective Dose Factor I

Radionuclide I _f_

Keff (mnrem/yr per piCi/mn3)

(L+I.1 M)eff (mremn/yr per jiCi/m 3) I Noble Gases - Total Body and Skin Kr-85 0.01 -- 1.4E+01 I Kr-88 0.01 1.5E+02 1.9E+02 Xe-133m 0.01 2.5E+00 I.4E+01 I Xe- 133 0.9 3.OE+02 6.6E+02 Xe-135 0.02 3.6E+01 7.9E+01 I TOTAL 4.8E+02 9.6E+02 Noble Gases - Air I Gamma Air Effective Beta Air Effective Radionuclide fi Dose Factor Mwer (mrad/yr per ýtCi/m 3)

Dose Factor Neff (mrad/yr per jiCi/m 3)

I Kr-85 Kr-88 0.01 0.01 1.5E+02 2.0E+01 2.9E+01 I

Xe-133m Xe-133 0.01 0.95 3.3E+00 3.4E+02 1.5E+01 1.0E+03 3

Xe-135 TOTAL 0.02 3.8E+01 5.3E+02 4.9E+01

1. 1E+03 I

B-5

KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 APPENDIX C EVALUATION OF CONSERVATIVE, DEFAULT EFFECTIVE EC VALUE FOR LIQUID EFFLUENTS C-1

I KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

Appendix C Evaluation of Conservative, Default Effective EC Value i for Liquid Effluents I

In accordance with the requirements of ODCM Normal Condition 13.3.1 the radioactive liquid effluent monitors shall be FUNCTIONAL with alarm setpoints established to ensure that tile concentration of radioactive material at the discharge point does not exceed 10 times the value of 10 CFR 20, Appendix B, Table 2, Column 2 for all radionuclides other than noble gases and a I

value of 2X10-4 [tCi/mi for noble gases. The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide I distribution and corresponding EC values.

In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established. This default setpoint can be conservatively based on an evaluation of the radionuclide distribution of the liquid effluents from Kewaunee and the ECe value for this distribution. 3 The effective EC value for a radionuclide distribution can be calculated by the equation:

ECe = - (C. 1) where: 3 ECe = an effective EC value for a mixture of radionuclide (ýtCi/ml)

C= concentration of radionuclide "i" in the mixture 3 ECI the 10 CFR 20, Appendix B, Table 2, Column 2 EC value for radionuclide I"'

(Y.tCi/mI) I Based on the above equation and the radionuclide distribution in the effluents for past years from Kewaunee, an ECe value can be determined. Effluent release data from 2000-2002 was used to generate the results presented in Table C-I. The most limiting effective EC (for gamma emitting 1

radionuclides) was for the calendar year 2001, with a calculated value of 5.98E-06 [iCi/ml. For conservatism in establishing the alarm setpoints, a default effective EC value of 1.OE-06 jtCi/ml was selected. The overall conservatism of this value is reaffirmed for future releases considering I

that I.OE-06 ýtCi/ml is as or more restrictive than the individual EC values for the principal fission and activation products of Co-58, Co-60 and Cs-137. Overall, use of this effective EC I C-2

KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 value provides a factor of six (6) conservatism based on the 2000-2002 radionuclide distribution for gamma emitters.

Being a non-gamma emitter, tritium is not detected by the effluent monitor. While tritium accounts for nearly all of the activity, it is not a significant contributor when determining the alarm setpoint for release rate evaluations. Examining releases over the years 2000-2002, the average, diluted H-3 contribution to its limiting concentration (i.e., fraction of concentration limit - 10 x EC) in liquid effluents was 0.004%. This contribution is not expected to change significantly over time, since the concentration of H-3 in effluents can be expected to remain fairly consistent in effluent releases regardless of fuel conditions, activation product releases, and waste processing.

Based on relative abundances, other non-gamma emitting radionuclides (Fe-55 and Sr-89/90) contributed up to 30% of the concentration limit (30% for CY 2001). It is reasonable to assume that the abundances of these non-gammas will remain the same relative to other fission and/or activation products under varying conditions. Therefore, uinder conditions of elevated effluent radionuclide levels, the gamma-emitting radionuclides can be expected to be the main contributors to limiting conditions on liquid effluent concentrations, as established in Technical Specification 5.5.3.b and ODCM, Normal Condition 13.1.1. Note that including the non-gammas (excluding tritium) in the evaluation results in a higher effective EC value.

Therefore, under conditions of elevatedeffluent levels, the main contributor to the limiting conditions of the liquid effluent concentration would be the gamma-emitting radionuclides. The factor of six (6) conservatism in the effective EC determination (discussed above) provides adequate consideration for the contribution from non-gamma emitting radionuclides, and provides a conservative basis for establishing an alarm setpoint consistent with the requirements of Technical Specification 5.5.3.b and ODCM Normal Condition 13.1 .1.

The Heating Boiler Blow Down and Turbine Building Sump are discharged to the lake with no installed radiation monitor. Using the default effective EC value of 1.OE-06 ltCi/ml for increased monitoring is consistent with the ODCM methodology if an installed radiation monitor was available.

C-3

KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Table C-1 Calculation of Effective EC (EC,)

"2000 2001 22002 Nuclide EC (pCi/mI)

Release (Q) Cj/EC, Frac. Release (CQ) Cj/EC, Frac. Release (Ci) Cj/EC, Frac.

Na-24 5.OOE-05 1.03E-03 2.06E+01 4.89E-03 2.18E-04 4.35 E+00 1.27E-03 O.OOE+00 O.00E+00 0.OOE+00 Cr-51 5.OOE-04 1.44E-03 2.89E+00 6.85E-04 8.26E-04 1.65E+00 4.83E-04 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 3.00E-05 1.49E-04 4.97E+00 1.18E-03 3.30E-04 1.1OE+'0I 3.22E-03 6.41E-05 2.14E+00 9.83E-04 Fe-55 1.00E-04 4.81E-02 4.81E+02 1.14E-01 4.85E-02 4.85E+02 1.42E-01 3.69E-02 3.69E+02 1.70E-0I Co-57 6.OOE-05 0.OOE+00 0.OOE+00 0.OOE+00 2.42E-05 4.03E-01 1.18E-04 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 2.OOE-05 8.07E-03 4.04E+02 9.59E-02 4.09E-03 2.05E+02 5.99E-02 4.94E-03 2.47E+02 1.!14E-0 I Fe-59 1.00E-05 2.77E-04 2.77E+O1 6.57E-03 2.44E-04 2.44E+01 7.14E-03 1.65E-04 1.65E+01 7.61E-03 Co-60 3.OOE-06 4.71E-03 1.57E+0j 3.73E-01 4.3 1E-03 1.44E+03 4.21E-01 2.07E-03 6.89E+02 3.17E-0 I Br-82 4.OOE-05 4.94E-04 1.23E+01 2.93E-03 1.44E-04 3.59E+00 1.05E-03 0.00E+00 0.OOE+00 0.OOE+00 Sr-89 8.OOE-06 3.42E-04 4.27E+01 1.01E-02 2.59E-04 3.24E+01 9.48E-03 5.98E-04 7.48E+0I 3.44E-02 Sr-90 5.OOE-07 2.25E-04 4.50E+02 1.07E-01 2.50E-04 5.OOE+02 1.46E-01 9.76E-05 1.95E+02 8.98E-02 Zr-95 2.OOE-05 1.16E-04 5.79E+00 1.38E-03 7.18E-05 3.59E+00 1.05 E-03 5.24E-05 2.62E+00 1.20E-03 Nb-95 3.OOE-05 3.41E-04 1.14E+01 2.70E-03 2.39E-04 7.95E+00 2.33E-03 2.45E-04 8.17E+00 3.76E-03 Ag- IOim 6.OOE-06 2.85E-03 4.74E+02 1.13E-01 1.63E-03 2.72E+02 7.97E-02 2.86E-03 4.76E+02 2.19E-0 I Sn-1 13 3.OOE-05 9.65E-05 3.22E+00 7.64E-04 5.08E-05 1.69E+00 4.95E-04 7.06E-05 2.35E+00 1.08E-03 Sb-124 7.OOE-06 5,61E-04 8.01E+01 I1.90E-02 1.81E-04 2.59E+01 7.59E-03 4.34E-05 6.20E+00 285E-03 Sb-125 3.OOE-05 4.86E-03 1.62E+02 3.85E-02 1.02E-03 3.41E+01 9.99E-03 2.46E-03 8.18E+01 3.76E-02 1-132 1.00E-04 0,00E+00 0.OOE+00 0.OOE+00 7.75E-08 7.75E-04 2.27E-07 0.OOE+00 0.OOE+00 0.OOE+00 1-133 7.OOE-06 6.16E-04 8.80E+01 2.09E-02 6.32E-04 9.03E+0I 2.65E-02 0.OOE+00 0.OOE+00 0.OOE+00 1-135 3.OOE-05 0.OOE+00 0.OOE+00 0.OOE+00 4.61E -05 1.54E+00 4.50E-04 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 1.OOE-06 3.70E-04 3.70E+02 8.78E-02 2.74E-04 2.74E+02 8.02E-02 3.04E-06 3.04E+00 1.40E-03 Total 7.46E-02 4.21E+03 1.00E+00 6.34E-02 3.42E+03 1.00E+00 5.06E-02 2.17E+03 1.00E+00 Non-Gamma Fraction 0.23 0.30 0.29 Gamma Fraction 0.77 0.70 0.71 EC, (GCi/ml, total) 1.77E-05 i1.86E-05 2.33E-05 ECe (gaCi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06 C-4

- mm - - m --

mm m -m - m

KEWAUNEE POWER STýATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 APPENDIX D On-site Disposal of Low-Level Radioactively Contaminated Waste Streams D-1

I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 14 I

April 18, 2012 Appendix D consists of hard copies of the following reference documents:

I DESCRIPTION DATE DOCKET NUMBER I

Operating License DPR-43 Kewaunee Nuclear Power Plant October 17, 1991 NRC-9 1-148 I

Disposal of Low Level Radioactive 50-305 Material Proposed Disposal of Low Level I

Radioactive Waste Sludge Onsite at the June 17, 1992 K92-119 Kewaunee Nuclear Power Plant (TAC No. M75047) 50-305 I Safety Evaluation For An Amendment To An Approved 10 CFR 20.302 Application September 14, 1994 K-94-195 I For The Kewaunee Nuclear Plant 50-305 (TAC No. M89719)

Alternate Disposal Of Contaminated I

Sewage Treatment Plant Sludge In November 13, 1995 K-95-172 Accordance With 10 CFR 20.2002 (TAC No. M93844) 50-305 I

Onsite Disposal Of Contaminated Sludge K-97-64 Pursuant To 10 CFR 20.2002 (TAC No. M9741 1)

April 9, 1997 50-305 I Adapted from N I D-2

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 WPSC (414) 433-1598 INkC 91-1461 TELECOPIER (4 414,1433-5544 EAYN 5;E2G ý9S3 WISCONSIN PUBLIC SERVICE CORPORATION 1c - K M Barlow, MGE J N Morrison D2 A J Ruege D2 N E Boys, \VPL .J R Mucller D2 C A Schrock KNP Larry Nielsen, ANFC D S Nalepka KNP C S Smoker KNP D R Berg KNP L A Nulh~ls D2 (NSRAC)

D A Bollrnm 06 C R Steinhardt D2 R P Pulec D2 I J Wallace KNP R S Drahcim KNP J S Richmond D2 K H Evers D2 K H Weinhauer KNP D J Ristau D2 S F Wonxiak D2 M L Marchi KNP D J RopOn KNP D L Masarik KNP QA Vault KNP October 17, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk -rI Washington, D.C. 20555 Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Disposal of Low Level Radioactive Malerial

References:

1) Letter from K.H.Evers to Document Control Desk dated September 12, 1989

2) Letter from M.J.Davis to K.H.Evers dated February 13, 1990

3) Letter from L.Sridharon (%VDNR) to M.Vandenbusch dated June 13, 1991 In reference 1, pursuant io the regulation of 10 CFR 20.302, Wisconsin Public Service Corporation (WPSC) requested authorization for the alternative disposal of very-low-level radioactive materials from the Kewaunee Nuclear Power Plant. In reference 2, the US NRC identified additional questions that needed to be addressed in order to complete their review.

Attachment I provides our response to the questions.

WPSC requested the State of Wisconsin Department of Natural Resources (WDNR) to review the disposal options for the service water pretreatment lagoon sludges. in reference 3, the WDNR completed a review of the most appropriate on site disposal methods for the slightly contaminated service water pretreatment lagoon sludges. The two proposed methods that the WDNR evaluated included in-situ.capping of the sludge in the wastewater treatment lagoon and on site landspreading. In Attachment I, Appendix A, WPSC evaluated the on site landspreading D-3

i KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 14 I

April 18, 2012 Document Control Desk I

October 17, 1991 Page 2 I

application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that I

either disposal method was acceptable provided:

- if the material is to be left in the lagoon, it would be capped in. accordance with Wisconsin State statutes.

I

- if the on site landspreading option is utilized, the material would be spread by either disking into the soil or by spiking into the ground.

I WPSC will abide by the WDNR landspreading requirements which include locational and performance standards. Should there be any additional questions please feel free to contact a member of my staff.

I Sincerely, I

(_". i 11j--A,t C. A. Schrock Manager - Nuclear Engineering I D Mfjms Attach, I

cc - US NRC - Region III Mr. Patrick Castleman, US NRC L IC',D.JM\ N492 I D-4 I

I

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 ATTACHMENT I To Letter from K. H. Evers (WPSC) to Document Control Desk (NRC)

Dated October 17, 1991 D-5

I KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk I October 17, 1991 Attachment 1, Page I References 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989.

I NRC Question #1 On page 4 of your submittal, the average input to the Sewage Treatment System is approximately 11,000 gallons per day. In the Final Environmental Statement, this system is to be operated below its design capacity of 9,000 gallons per day. Discuss this deviation from the design capacity, and provide information to justify the higher output for this system.

WPSC Response The original Sewage Treatment System installed at the Kewaunee Nuclear Power Plant (KNPP) was replaced in 1986 with a higher capacity system. The original system was designed for an onsite work force of around 150 people.

It was a limited capacity aerobic treatment system which included the onsite lagoon for additional retention. Because of this limited capacity and more stringent conditions on system effluent to Lake Michigan, an aerobic digester I system was installed, which has a higher capacity, and uses current technology.

The estimated input volume to the Sewage Treatment System used in the September 12. 1989 application was 11,000 gallons per day. This value was based on past operating data. The increase in influent from the original design basis included in the Final Environmental Statement is due mainly to an increase in the number of individuals and facilities (e.g., training and simulator building) located onsite. Design changes to the system were I required to accommodate these new facilities.

I D-6

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk October 17, 1991 Attachment I, Page 2 The current volumes of sewage sludge were used as the basis for the potential dose analysis and corresponding radionuclide concentration limits. This increase has no significant effect on the dose modeling. (Refer to the response to NRC Question #2, below.)

NRC Question #2 Provide information regarding how the disposal plan assures that the annual dose to any exposed individual will be kept b~elow I mrem per year.

WPSC Response The dose pathway modeling used for determining the radioactive material concentration limits was based on NRC modeling. The computer code IMPACTS-BRC was used as the basis for calculating the potential doses from the alternative disposal methods, This modeling includes reasonable conservative exposure pathway scenarios for the various disposal methods.

Administrative controls will be established to ensure that the actual disposal of any slightly contaminated materials from KNPP are within the bounds of the evaluation. Samples from each of the waste streams will be collected and analyzed by gamma spectroscopy prior to release for disposal. A system lower limit of detection (LLD) of 5E-07 jtCi/ml for the principal gamma emitting radionuclides will be required. This LLD ensures the identification of any contaminated materials at a fraction of the allowable concentration limits for the alternative disposal.

The results of these analyses will be used to ensure that any detectable levels of radioactive material are within the limits for alternative disposal. Any materials with levels of radioactive material above the concentration limits D-7

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk-October 17, 1991 Attachment 1, Page 3 (and of plant origin) will be treated as a radioactive waste and appropriately controlled.

Records will be maintained to ensure that the cumulative disposal of any U contaminated materials are maintained within the bounds of the evaluation. In addition to a comparison of the individual radionuclide concentration limits, a 3 record of the total amount of radioactive material disposed of will be maintained. Cumulative totals will be maintained to ensure that the total activity does not exceed the quantity assumed in the derivation of the limits.

In developing the concentration limits presented in Table I of reference 1, it I was assumed the total annual design basis volume of 27,000 :ft3 would be contaminated at the derived limit. The dose commitment from each radionuclide was individually evaluated as if it were the only radioactive material present. To determine if a mixture of radionuclides meets the limit, the sum-of-the-fractions rule should be applied (i.e., the sum of each radionuclide's concentration divided by its limiting concentration must be less 3 than one).

.The concentration limits of Table 1 of reference I also have an implied total activity I limit. This limit is determined by multiplying the individual radionuclide concentration limit by the total estimated waste volume of 27,000 ft3. These total I activity limits are presented in Table A of this response, for each radionuclide individually. For a mixture of radionuclides, a total. annual activity limit may be 3 determined by normalizing the concentrations so that the sum-of-the-fractions for the mixture equals one (1). These resultant adjusted concentrations may be multiplied by the 27,000 ft3 waste volume to determine the corresponding toal activity limit of the mixture.,

D-8

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk October 17, 1991 Attachment 1, Page 4 A Disposal Log will be maintained on a calendar year basis for all disposals of any very-low-level radioactive materials. The log will contain as a minimum the following information:

Disposal location

- Description of waste

Shipmentldisposal date

Waste volume

Radionuclide concentrations (gamma emitters)

Year-to-date radionuclide activity

- Year-to-date waste volume In addition to the above Disposal Log, a record file will be kept for each individual disposal. This file will contain, as a minimum, the following information:

" Waste identification

Sample gamma spectroscopy results

- Identified radionuclide concentrations and total activity NRC Question #3 Revise Appendix B, Section A of your submittal, "Radiation Exposure During Transport," by adding the cumulative dose to the exposed population per reactor year for both the transportation worker and the general public (onlookers along mute).

\VPsC Response The potential exposure to the general public (onlookers along route) is modeled by the IMPACTS-BRC code. As addressed in NUREG/CR-3585, this modeling is based on an integration of the source strength, an assumed D-9

m KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 m April 18, 2012 Document Control Desk 3 October 17, .1991.

Attachment 1, Page 5 3 population density along route and vehicular speed. For a conservative evaluation of the potential exposure to the general public from the transport of I the KNPP waste, a population density of 610 persons/mi 2 was assumed. This value is conservative for the KNPP site area where the average population i density is less than 53 persons/mi 2 . A transport distance of 45 miles was assumed. The IMPACTS-BRC modeling assumes five (5) tons of material are i transported per shipment. For the assumed KNPP waste volume, this shipment weight translates into a total of 167 shipments per year. With a m vehicular speed of 20 miles per hour, the resultant total population exposure time is 375 person-hours per year. At the concentration limits established for m the alternative disposal, the potential onlooker doses during transport will be less than 0.01 person-rem.per year. For the modeling of the exposure to the i transport worker, the IMPACTS-BRC model assumes two drivers per vehicle.

As presented in the September 12, 1989 submittal, the maximum dose to the 3 driver is less than I.mrem per year (<0.001 rem/yr). Therefore, the total collective dose to the transport workers will be twice the individual dose, i.e., m less than 0.002 person-tern. Including the population dose of <0.01 person-rem per year, the total collective dose to both the transport workers and the population is less than 0.02 person-rem (0.002 person-rem + 0.01 person-rem

< 0.02 person-rem). m For the disposal of the existing 15,000 ft3 of contaminated sludges, the 3 population dose due to the transportation of the waste is calculated to be 0.0002 person-rem. The estimated collective exposure to the transport worker 3 is 0.00007 person-rem. The total collective dose due to transport of the waste is 0.00027 person-rem. 3 D-10 D_,o m

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk October 17, 1991 Attachment 1, Page 6.

Additional Potential Disposal Method The Wisconsin Department of Natural Resources has requested Wisconsin Public Service to examine the feasibility of land application of the lagoon sludges in lieu of dispxosal in the Kewaunee County Landfill. Land application is also an option for the disposal of the sewage sludges. Therefore, WPS .

requests that the option for onsite disposal at the KNPP site by land application be included in the alternative disposal methods which was determined to be acceptable in our September 12, L989 submittal.

The potential pathways of exposure as evaluated in the September 12, 1989 submittal conservatively bound any additional pathways of exposure that would result from onsite land spreading of the waste. Attachment A to this response provides an overview of the land spreading disposal method. Also, the pathways of exposure applicable to the onsite land application are evaluated; and a comparison to the controlling pathways and radionuclide concentrations as presented in the September 12, 1989 submittal are discussed. From a modeling standpoint, the two exposure scenarios , "Radiation Exposure During Transport" and "Radiation Exposure to Landfill Operator," appropriately characterize any potential exposure to workers involved with the land spreading of the waste. Thne other post-disposal exposure scenarios, "Intruder Scenario", "Intruder Well", and "Exposed Waste Scenario," as described in NUREG/CR.-3585 (and as discussed in Appendix C of the submittal) reasonably bound any potential exposures from either ground waste migration or post-release from the Kewaunee site. In no case is .there a higher potential for exposure from land application than the pathways and potential exposures that were used for the derivation of the limits for alternative disposal.

Therefore, no revisions are needed to the radionuclide concentration limits proposed in the September 12, 1989 submittal to include the option for disposal by onsite land spreading of the waste.

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I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 14 U

April 18, 2012 Document Control Desk I

October 17, 1991 Attachment 1, Page 7 I Table A I Radionuclide Quantity Limits I for Alternative Disposal Limiting I

Limiting Annual Nuclide Concentration (1Ci/nml)

Quantity (Ci) I H-3 C- 14 9.65E-04 4.55E-05 0.7382 0.0348 I

Cr-51 3.13E-04 0.2394 Mn-54 Fe-55 1.14E-05 IAOOE-02 0.0087 7.6500 I

Fe-59 7.90E-06 0.0060 Co-58 Co-60

1. 16E-05 3.74E-06 0.0089 0.0029 I Ni-63 1.00E-02 7.6500 Sr-90 Zr-95 3.45E-03 6.28E-06 2.6393 0.0048 I Nb-95 1.23E-05 0.0094 Mo-99 Tc-99 1-129 6.73E-05 2,70E-04 2.50E-06 0.0515 0.2066 0.0019 I

1-131 C,-134 Cs-137 2.68E-05 6.16E-06 1,71E-05 0.0205 0.0047 0.0131 I

Ba-140 5.52E-05 0.0422 La- 140 4.17E-06 0.0032 I Transuranics

.TRU (T'/2 > 5 yrs)

Pu-241 8.91E-05 2.85E-03 0.0682 2.1803 I

Cm-242 1.00E-02 7.6500 Assumes annual quantity of KNPP wastes is 27,000 ft3 or I 7.65E8 mils.

I D-12 I

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk October 17, 1991 Attachment 1. Page 8 Appendix A Evaluation of Onsite Land Application for Alternative Disposal of Very-Low-Level Contaminated Materials Overview Land spreading of lagoon sludges onsite at the Kewaunee Nuclear Power Plant has been recommended by personnel from the Wisconsin Department of Natural Resources (DNR) as a desirable alternative to the use of the Kewaunee County Landfill for disposal. This method of disposal is also a recommended practice for disposing of sewage treatment facility sludges.

Therefore, WPS requests that this disposal method be included in the options available for the alternative disposal of very-low-level radioactively contaminated materials from KNPP.

Description of Disposal Method The disposal of KNPP sludges will be performed by beneficial land application to a dedicated disposal area located onsice at the Kewaunee Nuclear Power Plant. Typical methods of land spreading will be employed. KNPP sludges will be loaded onto appropriate vehicles (e.g.,

tanker truck, sludge spreader, etc.) and applied to the dedicated disposal area. The dedicated disposal area will be periodically plowed to a depth of 6 inches.

Onsite disposal of water treatment and sewage sludges are allowed by EPA and State of Wisconsin Department of Natural Resources with the criteria and limits for land spreading being specified by the potential use of the land. The two land use criteria are 1) Agricultural land that covers any lands upon which food crops are grown or animals aie grazed for hurnan consumption, and 2) Non-Agricultural land that covers lands which do not represent ingestion pathways to man. To be conservative, the Agricultural Land Application limits of sludge contaminants will he applied to the KNPP wastes even though the less restrictive Non-Agricultural Land Application sludge contamination limits are allowed. Therefore, no more than 50 metric tons of sludge per heciare will be applied to the dedicated disposal site. This limit will ensure that any land application will not exceed the bounds of the dosc analysis as D-13

I KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk October 17, 1991 Attachment 1, Page 9 3 performed previously. In addition, other limitations as applied to land application by the State of Wisconsin Department of Natural Resources will be followed (e.g., control of I runoff/erosion, proximity to well sresidences/surface water, etc.).

Applicable Pathways of Exposure 3 The pathways of exposure applicable for land spreading are not appreciably different from the pathways evaluated for the disposal methods at the Kewaunee County Landfill or the 3 Green Bay Metropolitan Sewerage District facilities. The major exposure pathways are discussed below: 3 Direct Exposure to Workers Any potential exposures to workers involved in the removal, transport and land spreading of the sludges are reasonably bound by the evaluation of the exposure to the transport worker in the September 12, 1989 submittal. The I transport worker has been assumed to be exposed for 460 hours0.00532 days 0.128 hours 7.60582e-4 weeks 1.7503e-4 months per year at one (1) meter from unshielded waste. For the land spreading of these wastes, 3 it is estimated that the total exposure time for the removal and disposal of the lagoon sludges will require 'no longer than a three week period per year (i.e., 3 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months ).

The potential exposure to a worker onsite after land spreading, has been 1 estimated at no more that 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months per year. Such an individual would be involved in land maintenance activities, such as plowing and mowing. As modeled in the September 12, 1989 submittal, an exposure of 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months per year to the landfill operator has been assumed. For this exposure, the KN"PP3 materials are mixed with other landfill waste: a 1:13 mixing of KNPP materials to other waste is assumed. This mixing is not significantly different 3 from the type of mixing that will occur in the field with the sludges being D-14 I

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk October 17, 1991 Attachment 1, Page 10 plowed into the soil to a depth of six (6) inches. With a land spreading of 50 metric tons per hectare per year, a mixing ratio of 1:30 will be achieved.

Therefore, the resultant dose to the exposed worker would be less than the I mrem per year dose to the transport worker as evaluated in the September 12, 1989 submittal.

Post Disposal Exposure - Intruder Scenario The IMPACTS-BRC model, as applied to the disposal of the KNPP waste, assumes a loss of institutional controls 10 years after closure of the site (See Appendix B of the September 12, 1989 submittal). An individual is assumed to reside in a house built on the disposal area. This individual receives a direct exposure (from the uncovered waste), an inhalation exposure (from resuspension), and an ingestion exposure (from growing 1/2 of his food crops). For modeling purposes, it is assumed that the waste is mixed at a ratio of 1:13 with other soils during the resident's construction process.

The onsite land application of KNPP waste will be limited by the Agricultural Land Application sludge concentrations even though the less restrictive Non-Agricultural Land Application sludge concentrations are applicable since a "dedicated land disposal" site will be used (i.e., no crops will be grown on the disposal site).

Therefore, provided the KNPP waste does not exceed the Non-Agricultural maximum sludge concentrations for heavy metal or organic chemicals, unlimited application of waste to the dedicated land disposal site is allowed. However, to be conservative, the land application of KNPP wastes will be limited to 5 metric tons per hectare per year.

The intruder scenario as evaluated in the September 12, 1989 submittal conservatively bounds this exposure pathway for the on-site land spreading.

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KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Document Control Desk i October 17, 1991 Attachment 1, Page 11I Post Disposal - Intruder Well i The intruder well pathway for onsite land disposal is essentially the same as the I intruder well pathway as evaluated by the IMPACTS-BRC model. It is conservatively assumed that the well is located at the edge of the disposal site. As modeled, locating i the well at the disposal site edge in "downstream flow" direction maximizes the calculated hypothetical dose. (Additional discussion of this modeling is presented in 3 NTJREG/CR-3585, Volume 2).

The potential dose for the intruder well scenario for the land spreading disposal would be less than 0.001 mrem per year. The modeling as presented in the September 12, 3 1989 submittal reasonably bounds any hypothetical well water exposure pathway.

In summary, the modeling of the exposure scenarios, as presented in the September 1 12, 1989 submittal, conservatively bounds the hypothetically exposures for the on-site land spreading. In no case is it likely that any individual, either on-site or off-site, will receive a dose in excess of I mrem per year from the disposal of the slightly contaminated materials.

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KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D,C 205M June 17, 1992 Docket No. 50-305 Mr. C. A. Schrock Manager - Nuclear Engineering Wisconsin Public Service Corporation P. 0. Box 19002 Green Bay, Wisconsin 54037-9002

Dear Mr. Schrock:

SUBJECT- PROPOSED DISPOSAL OF LOW LEVEL RADIOACTIVE WASTE SLUDGE ONSITE AT THE KEWAUNEE NUCLEAR POWER PLANT (TAC NO. M75047)

By letters dated September 12, 1989, and October 17, 1991, you submitted a request pursuant to 10 CFR 20.302 for the disposal of waste sludge onsite at the Kewaunee Nuclear Power Plant. We have completed our review of the request and find your procedures, including documented commitments, to be acceptable.

This approval is granted provided that the enclosed safety evaluation is permanently incorporated into your Offsite Dose Calculation Manual (ODCM) as an Appendix, and that future modifications of these commitments are reported to the NRC.

Issuance of this safety evaluation completes all effort on TAC No. M75047.

Sincerely, Allen G. Hansen, Project Manager Project Directorate IlU-3 Division of Reactor Projects II[I[V/V Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/enclosure:

See next page NItRC LETTER D15TRIBUTION 71'A Hans~on (MG&E) J P Gie-,er D2 C A Schrock D2 J D Loock (%WPL) M L Marchi KNP C R Steinha'dt D2 Ulftrr Nielsenf (ANFC) D L Masarik KNP TJWebbKNP J L Delant (NSRAC) R P Pulec D2 (2) S F Wozniak D2 D A Bodlon G36 D J Ristau D2 QA Vault KNP Nii 11Evers KNP A J Ruege D2 D-17

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 i sconsi- Public serv ice Corpor~aLion Kewwiunee tNcle,.r Power Plant David Baker. Esquire

.(:ley aid Lardner P.O- Box 2.93 Orlando, Florida 32-082 Glen Kunesh. Chairman Town of Carlton Route I Kewaunee, Wisconsin 54216 Mr. flarold Reckelberq, Chairrian Kewaunee County '39ýrd Kewaunee County Courthouse Kewaunee. Wisconsin 54216 Chairman Public Ser.'ice C',rrmission of Wisconsin Bill Farr-s State Office Boildinq ftadý_n, ýdisc~onsin 53702 I

Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U.S. Nuclear Regulatory Commission Resident Inspectors Office Route k1, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt. Road Glen Ellyn, Illinois 60137 I

Mr. Robert S. Cullen Chief Engineer Wisconsin Public Service Conmnission P.O. Box 7854 Madison, Wisconsin 53707 1 D-18

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012

,,rUNITED STATES NUCLEAR REGULATORY COMMISSION

~Th~IIII~r~ ~WASH].O170N. D.C. 20565 S EIUA1iiQ

FEiY B THE CFFICE OF 'UCLEAR R.ACTOR REGULATIOj DISPOSAL OF LO~.'j..gVEL RADIOACTIVELY REL.AT!NG TO DQJ.{.Ej.JY COtTM IINATF.D WASVTE AT THE KFWAUNEE NUCLEAR POWER PLANT WISCONSIN PUBLIC ýSERVICE COPPORATIOIN WISCONSIN POWER AND LIGHT COMPANY I.AD.SON GAS AID ELECTRIC C(ONPANY DOCKET NO. 50-305 1.0 INTRODUCT!ON In reference 1, Wisconsin Public Service Corporation (WPSC) requested approval pursuant to Section 20.302 of Title 10 of the Code of Federal Regulations (CFR) for the disposal of licensed material not previously considered in the Kewaunee Final Environmetital Statement (FES) dated December 1972. Additional related material from the licensee, from the State of Wisconsin, and from the staff are contairned in references 2 through 5.

The WPSC request contains a detailed description of the licensed material (i.e., contaminated ,ludqe] subject to thi.s 10 CFP 20.302 request, based un radioactivity absorbed from liquid discharges of licensed material. The 15,000 cubic feet of contaminated sludge identified in the request contains a total radionuclide inventory of 0.17 mCi of Cesium-137 and Cobalt-60.

In its submittal, the licensee addres;ed specific information requested in accordance with 10 CFR 20.302(a), provided a detailed description of the licensed material, thoroughly analyzed and evaluated the information pertinent to the effects on the environment of the proposed disposal of licensed material, and co,-mitted to follow specific p'rocedures to minimize the risk of unexpected exposures.

2.0 DESCRIPTI1rIi OF HtkSTE During the normal operation of Kewaunee, the potential exists for in-plant process streams which are not normally radioactive to become contaminated with very low levels of radioactive materials. These waste streams are normally spara.t4d from the radioactive streams. However, due mainly to infrequent, minor svytem leaks, and anticipated operational occurrences, the potential exists for these systems to become slightly cuntaminated. At Kewaunee. the see¢66daey system demlneralizey resins, the survice watew pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contamainated at very low levels.

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1 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

-2 - I Ouri. .theyearly testing of a batch of pre-treatm.en..t sludge, it was found that aproximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.

3.0 PROPOSED DISPOSAL METHOD 3 WPSC plans to dispose of +/-he 15,000 cubic feet of contaminated sludge cnsize pursuant to 10 CFR 20,302. The sludge is currently contained in an cnsite lagoon at the KNPP sewage treatment facility. The disposal of the sludge wili be by land application to an area located onsite at KNPP, as shown in Figure 1. The area will be periodically plowed to a depth of 6 inches.

I Table i lists the principal nuclides identified in the sludge. The activity is based on measurements made in 1989. The radionuclide half-lives, which are dominated by 30-year Cs-137, meet the staff's 10 CFR 20.30Z guidelines I

(reference G), which apply to radlonuclides with half-lives less th-.n 35 years.

Nuclide Total Activity (mCi)

Co-60 Cs-137 0.076 0-094 3

0.170 3 4.0 RA[) IOLOG ICAL IMPACT; The licensee has evaluated the following potential exposure path)ways to members of the general public from the radionuclides in the sludge: (1) external exposure caused by groundshine from the disposal site; (2) internal I

exposure from inhalation of re-suspended radionuclides; and (3j interna!

exposure from ingesting ground water. The staff has reviewed the licensee's calculational methods and assumptions and finds that they are consistent with NRC Regulatory Guide 1.10, "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. The staff finds the assessment methodology acceptable. 5 Table 2 lists the doses calculated by the licensee for the maximally exposed member of the public based on a total activity of 0.170 mki disposed of in the current year, as well as the cumulative impact of similar disposals during subsequent years. For any repetitive disposals, the licensee must reapply to the HRC when a particular disposal would exceed the following boundary I

conditions, (1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.

D-20

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Whole Body Dos kceivOd by Maximally Exposed Individual Pathway (mrem/year)

Groundshine 0.034 Inhalation 0.008 Groundwater Ingestion 0.007 rOTAL 0.-...-

As shown in Table 2, the annual dose Is expected to be on the order of 0.1 mrem or less. Such a dose is a small fraction of the 300 mrem received annually by members of the general public from sources of natural background radiation.

The guidelines used by the NRUstaff for onsite disposal of licensed niaterial are oresented in lable 3, along with the staff's evaluation of how each guideline has been satisfied.

The licensee's procedures and commitments as documented in the submittal are acceptable, provided that they are permanently Incorporated into the licensee's Offsite Dose. Calculation Manual (ODCM) as an Appendix, and that Future modifications be reported to NRC In accordance with the applicable OLICH change protocol.

Based orn the above findings, the staff finds the licensee's proposal to dispose of the low level radioactive waste sludge onsite in the manner described in the WPSC letter dated September 12, 1989, to be acceptable. The 5tate of Wisconsin has also approved these procedures (reference 5).

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I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 14 I

April 18, 2012 I

iA(BL[ "

I 20.302 Guideline for Onsite Disposa!,

1. The radioactive material should Staff's Evalgation

1. Due to the nature of the I

be disposed of in a manner that it disposed material , recycl ing to the is unlikely that the material would be recycled.

general public is not considered I ikely. I

2. Doses to the total body and any 2. lhis quideline is addressed in body organ of a maximally exposed Individual (a member of the general public or a non-occupationally exposed worker) from the probable Table 2, I

pathways of exposure to the disposed material should be less than

.I mrem/year. I

3. Doses to the total body and any 3, Bpcause the material will be body organ of an inadvertent intruder from the probable pathways of exposure should be less than 5 mrem/year.

land-spread, the staff considers the maximally exposed individual scenario to also address the intruder scenario.

i

4. Doses to the total body and any body organ of an individual from assumed recycling of the disposed

4. Even if recycling were to occur after release from regulatory control, the dose to the maximally I

material at the time the disposal expcsed member of the public is not site is released from regulatory control from all likely pathways of exposure should be less than I mreni.

expected tu exceed 1 Crem/year, based on the exposure scenarios considered in this analysis.

I I

U D-22 I

I

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 EE F-ME4CENCS (1) WPSC letter from K. if. Evers to NIRC,oo*rurnot Control Desk, September 12, 1989, (2) Memorandum from L. J. Currirjhm,. DREP, to J. R1.Hannon, "Request For Additional Information," December 1. 1989, (3) NRC letter from M. J. 0---v4s tc K. H. Evers of WPSC dated February 13, 1990.

(4) WPSC letter fror, K. H. Evers to tiC Docuiment Control Desk, October 17, 1991.

(5) Letter from L. Sridhar-,n of the S.ate of Wisconsin Department of Natural Resources to M. Vanenbusrch of W'*SC. dated June 13, 1991.

(6) E. F. Branagan Jr. and K. J- Cornr, "'Disposal of Contaminated Radioactive Wastes from Nuclear Power Plants," presented at the Health Physics Society's midyear Syrposiwi,, on Health Physics Considerations in Decontaminnation/Decommissioning, Kncxville, TIN, February 1986 (CONF-860203).

Principal Contributor: J. ,iAons Date: June 17, 1992 D-23

KEVWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 iKý?aunoe NiuClear~ Pcwt2r Plant Site Area Map D-24

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012

tpA '!L

t. K-V2 I1/E4 0 UNITED STATES

~ NUCLEAR REGULATORY COMMISSION

C

~~mTW' WASHINGTON. OC. M56-1 o

0 September 14. 1994 Mr. C. A. Schrock Manager - Nuclear Engineering Wisconsin Public Service Corporation Post OFfice Box 19002 Green Bay, WI 54307-9002

SUBJECT:

SAFETY EVALUATION FOR AN AMENDMIENT TO AN APPROVED 10 CFR 20.302 APPLICATION FOR THE KEWAUNEE NUCLEAR PLANT (TAC NO. MB9719)

Dear Mr. Schrock:

By letter dated June 23, 1994, as supplemented June 29, 1994, you requested approval to use another onsite area for the disposal of contaminated waste sludge in addition to the location approved by the NRC on June 17, 1992. The staff has completed its review of your request and finds that your proposal meets the radiological boundary conditions approved in the June 17, 1992, Safety Evaluation, and is therefore acceptable. The staff also Finds that your proposal is in accordance with 10 CFR 20.2002 which replaced 20,302 on January 1, 1994.

This approval is granted provided that the enclosed Safety Evaluation Is permanently incorporated into your Offsite. Dose Calculation Manual (ODCM) as an Appendix, and that future modificationsof these comeitments are reported to the NRC.

Sincerely, Richard J. Laufer, Acting Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

Safety Evaluation cc w/enclosure:

see nnxt page T A Hsnaoca (Moa&t X A go" 1 fl0 C SSmokew KNP hMW S'it' (WPlL) M L UwA.E DU?

LMxY NIfclac (ANTC) C R Steinhudi D2 D L M*Om& XNp C A SkenicyXN-P D A Eko[com 06 J X MoriNGoDt TIJwebb KNp D E Colo KNp L A Nugbada (NsRAc)

X II Even KNP S F Wom~iak D)2 R P puke D2 (2)

I PGiester KNp QA VXUIl XNP C A Schrok 1)2 D-25

U KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: 3 Foley & Lardner Attention: Mr. Bradley D. Jackson One South Pinckney Street P. 0. Box 1497 Madison, Wisconsin 53701-1497 Chairman Town of Carlton Route 1 Kewaunee. Wisconsin 54216 Mr. Harold Reckelberg, Chairman Kewaunee County Boardm I

Kewaunee County Courthouse Kewaunee, Wisconsin 54216 Chairman Public Service Commission of I

Wisconsin Hill Farms State OfficeBuilding Madison, Wisconsin 53702 I Attorney General 114. East, State Capitol Madison, Wisconsin 53702 U. S. Nuclear Regulatory Commission Resident Inspectors Office Route #1, Box 999 Kewaunee, .Wisconsin 54216 Regional Administrator - Region III U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4531 Mr. Robert S. Cullen Chief Engineer Wisconsin Pu~blic Service Commission P. O. Box 7854 Madison, Wisconsin 53707 I

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KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20r66ý SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELY CONTAN[NATED WASTE SLUDGE AT THE KEWAUNEE NUCLEAR POWER PLANT WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADISON CAS AND ELECTRIC COHPANY DOCKET NO. 5*-305

1.0 INTRODUCTION

By letter dated June 23, 1994, and as supplemented on June 29, 1994, Wisconsin Public Service Corporation (the licensee) requested approval to use another onsite area for the disposal of contaminated waste sludge in addition to the location approved by the NRC on June 17, 1992.

2.0 EVALUATION A Safety Evaluation (SE) dated June 17, 1992, approved the licensee's request pursuant to 10 CFR 20.302 for the disposal of IS,000 cubic feet of contaminated waste :sludge by land application at the Kewaunee Nuclear Power Plant (KNPP) at a specific onsite location. The SE imposed the following boundary conditions:

1. The annual disposal must be less than a total activity of 0.2 mCi.

2. The whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year.

3. The disposal must be the same site.

The site designated in the SE was an unused area adjacent to the onsite lagoon at the KNPP sewage treatment facility. In 1993, approximately 7500 cubic feet of the original 15,000 cubic feet of contaminated sludge was spread on that location. The licensee has now proposed to dispose of the remaining contaminated sludge at another onsite location northwest. of the plant (see Attachment). The licensee has coiimitted that the new disposal. location will meet all the radiological boundary conditions contained in the SE for the 10 CFR 20.30Z application approved on June 17, 199Z. Additionally, the licensee has stated that this additional disposal site will meet all applicable Wisconsin Department of Natural Resources (WDNR) application requirements (i.e., sludge application rate and frequency of spreading rate),

in addition to WMIR landspreading requirements regarding location and performance standards that were required at the original disposal site, D-27

1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 14 I

April 18, 2012 I

3.0 CONCLUS[ON I

The staff finds the licensee's proposal to dispose of the low-level radioactive waste sludge in the additional onsite location to be within the radiological boundary conditions approved In the June 17, 1992, SE and is therefore acceptable. The staff also finds that your proposal is in I

accordance with 10 CFR 20.2002 which replaced 20.302 on January 1, 1994.

As stated in the NRC's June 17, 1992, approval of the licensee's 10 CFR Z0.302 application, the licensee is required to pernanently incorporate this I

modification into the Offsite Dose Calculation Hanual as an Appendix, and that future modification of this commitment be reported to the NRC.

Principal Contributor- S. Klementowicz I

.Date. September 14,

Attachment:

1994 KNPP Site Area Map I I

I I

D-28 I

I

M IM Mao M M m M M" m m m mM m KEWAUNEE POWER STATION 0DCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 5,.

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I KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I UNITED STATES .., 'c i-v--2 I

NUCLEAR REGULATORY COMMISSION A,~IIIrd WASHIkNGTON, D.C. -c.56&-00G Not'eraber 13, 1ý95 I

Mr. H. L. Marchi I

Manager - Nuclear Business Group-Wisconsin. Public Service Corporation Post Office Box 19002 Green Bay, WI 54307-9002 I

SUBJECT:

ALTERNATE DISPOSAL OF CONTAMINATED SEWAGE TREAThENT PLANT SLUDGE IN ACCORDANCE WITH 10 CFR 20.2002 (TAC NO. M93844)

Dear Mr. Harchi:

3 By letter dated October 17, 1995, as supplemented on November 3, 1995, you requested approval for the onsite disposal of contaminated sewage treatment sludge in accordance with 10 CFR 20.2002. This request was sipilar to a previous disposal request that was approved by the NRC on June 17, 1992.

The staff has completed its review of your request and finds that your proposal meets the radiological boundary conditions approved in the June 17, 1992. Safety Evaluation, and Is therefore acceptable.

This approval Is granted provided that the enclosed safety evaluation is I

permanently incorporated into you Offsite Dose Calculation Manual (OCMI) as an Appendix, and that future modifications of those cosaitsents are reported to the NRC. 3 SIncerely, Richard J. Laufer, Project Manager Project Directorate 111-3 I

Division of Reactor Projects IIl/IV Docket No. 50-305 Office of Nuclear Reactor Regulation I

Enclosure:

Safety Evaluation cc: See next page I

U&JU3ýJot LETl Tr A Ifansoo (MGc&.E)

M W Seitz (WPL)

K 1 Even KN4P M I. Manhi D'2 ITIBiN IPS C S Smoker KNPF C R Strinbarldl D2 I

Lirry NiteIbe (ANFC) J K Jubin (NSRAC) CA Stemitzky ICNP(Lsic)

D A Bollom Q6 D F 132y DI R P Puloc K.NP (3)

C A Schrock M~P SF Wozaialz D2 BJ Domnizick IKiNP (Com) U D-30 I I

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 Hr. H. L. Marchl Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc:

Foley A Lardner Attention: Hr. Bradley 0. Jackson One South Pinckney Street P. 0. Box 1497 Hadison, Wisconsin 53701-1497 Chairman Town of Carlton Route I Kewaunee, Wisconsin S4216 Hr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse Kewaunee, Wisconsin 54216 Chairman Public Service Comzission of Wisconsin Hill Farms State Office Building Madison, Vlsconsln 5370Z Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U. S. Nuclear Regulatory Coamlsslon Resident Inspectors Office

'Route 11, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator - Region I1I U. S. Nuclear Regulatory Comiussion 801 Warrenville Road Lisle, Illinois 60532-4531 Mr. Robert S. Cullen Chief Engineer Wisconsin Public Service Comission P. 0. Box 7854 Madison, Wisconsin 53707 D-31

I KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 I April 18, 2012 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. O,31I SAFEIEY._EYALUATION-BY-TUlEOFf-ICE DE-NUCLEAR REACTORREGULATI' RELATING TO.ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELY COfPIrAINATED SEWAGE TREATMENT SLUDGE AT lBE KEWAHNEE NUCLMEA POWER PLANT WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADISON GAS AND FLECTRIC COMPANY DOCKET NO, 50-305 By letter dktgd Ocqbor 17, 1995, as supple..nted on Ngve r 3, 1995,b1 Wisconsin Public Service Corporation (the licensee) requested approval for the onsite request disposal that was ofapproved contaminated sewage sludge similar to a previous disposal by the NRC on June 17. 1992.

2.0 BACKGROUID I In a letter dated September 12, 1989, the licensee requested authorization for the alternate disposal of very-low-level radioactive material. In a Safety Evaluation (SE) dated June 17, 1992, the N(RC approved the licensee's request pursuant to 10 CFR 20.302 (new 10 CFR 20.2002) for the disposal of 15,000 cubic feet of contaminated waste sludge by land application at the Kewaunee U

Nuclear Power Plant (KNPP) Iocation. The SE imposed the following boundary conditions:

1. The annual disposal must be less than a total activity of 0.2 mCi.

2. The whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year. 3

3. The disposal must be at the same site.

The licensee completed the disposal of the contaminated waste sludge discussed in the SE dated June 17, 1992. The licensee is now requesting authorization to dispose of additional contaminated waste sludge within the boundary I

conditions of the previously approved disposal.

3.0 EVALUATION 3 The 1icensee has proposed to dispose of approximately 6000 gallons (800 cubic feet) of sewage sludge similar to the material approved for disposal In the SE dated June 17, 1992. The principal radionuclides identified in the waste sludge and their activity based on measurements In May 1995 are: Co-58, D

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KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012

-z-0.0009 mCi; Co-60, 0.0008 mci; and Cr-51, 0.0006 mCi. The total combined activity Is 0.0023 mCi. This activity is well below the boundary value of 0.2 mCi. Additionally, Cr-51 with it short half-life (27.7 day) will have undergone significant decay froa its initial value of 0.0006 mCi.

The licensee has comitted that the new disposal will meet all the radiological boundary conditions, on a cumulative basis, contained In the SE for the 10 CFR 20.302 application approved on June 17, 1992. Additionally, the licensee has stated that all applicable permits for this disposal have been obtained from the Wisconsin Department of Natural Resources.

4.0 CONCLUSION

The staff finds the licensee's proposal to dispose of.the low-level radioactive waste sludge pursuant to 10 CFR 20.2002. on the licensee's site (see Attachment), is within the radlological boundary conditions approved in the June 17, 1992, SER and is therefore acceptable.

The licensee is required to permanently incorporate this uodification into the Offsite Dose Calculation Hanual as. an Appendix, and to ensure that future modifications of these commitments, are reported to the NRC.

Principal Contributor: S. Klementowicz Date: November 13, 1995

Attachment:

KIIPP Site Area-Hap D-33

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 KEWAUMEELjjqr t: %CLE4R NuCL E,4R PO WER ANT SITE AREA MA f _

jJ D-34

- M IM w m- m a IM m m m m a ~ I

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 UNITED STATES A'eec 0/ -/Vv NUCLEAR REGULATORY COMMISSION IWASHINGTON, D.C. 2ro,4-ow April 9, 19' Mr. M. L. Marchi Manager - Nuclear Business Group Wisconsin Public Service Corporation Post Office Box 19002 Green Bay, WI 54307-9002

SUBJECT:

ONSITE DISPOSAL OF CONTAMINATED SLUDGE PURSUANT 10 10 CFR 20.2002 (TAC NO. M97411)

Dear Mr. Marchi:

By letter dated December 10, 1996, you requested that the U.S. Nuclear Regulatory Comiission (NRC) review the applicability of a 10 CFR 20.203 (now 20.2002) application approved on June 17, 1992, for additional disposals of a similar nature.

The staff has completed its review of your request and agrees with your determination that the 10 CFR 20.203 application for onsite disposal, of sludge contaminated with licensed radioactive material, which was approvedl on June 1.7, 1992, contains bounding conditions that are applicable for additional onsite disposals of a similar nature. A copy of the Safety Evaluation is enclosed.

Sincerely, Richard J. Laufer, Project Manager Project Directorate 111-3 Division of Reactor Projects I1I/!V Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

Safety Evaluation cc: See next page NR~C+/-IEII~IRIB NO T A IHjioa(u4GE K 11Evevy KNp M W Scitz (WPL) M L Rarvcji D2 H D Cure( (SPC) D2 C R Stcizij*r1 JBe~uxM KNP (NSRAC)

D A BoIlom 0j6 R P Puloc CNp (3)

D E Day D S F WomiAk D2 C A Sdixrmk KNP BJDaVnkk1PRRcwchxko KN-P (Comr/USAR)

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I Kr'EWAUNEE PWVVER S'T ATIN ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

Mr, M. L. Marchi Wisconsin. Publ ic Service Corporation Yewaunee Nuclear Power Plant I

cc: 5 Foley & Lardner Attention: Mr. Bradley D. Jackson One South Pinckney Street P. 0. Box 1497 Madison. Wisconsin 53701-1497 Chairman Town oF Carlton Route I Kewaunee, Wisconsin 54216 Mr. Harold Reckelberg, Chairman Kewaunee County BoardI I Kewaunee County Courthouse Kewaunee, Wisconsin 54216 Chairman Wisconsin Public Service Commission 3

610 N. Whitney Way Madison, Wisconsin 53705-2729 Attorney General 114 East, State Capitol Madison, Wisconsin 5370Z U. S. Nuclear Regulatory Commission Resident Inspectors Office I

Route #1,Box 999 Kewaunee, Wisconsin 54216 1.II Regional Administrator - Region U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4531 Mr. Robert S. Cullen Chief Engineer Wisconsin Public Service Commission 610 N. Whitney Way Madison, Wisconsin 53705-2829 I

I

£ I

I D-36I U

KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012

-UNITED STATES L 2 NUCLEAR REGULATORY COMMISSION WASHINGTON. O.C. 2=6Sa-O~M SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO QNSITEi DISPOSAL OF CONTAMInATeD SLUDGE AT THr KEWAUNEE NUCLEAR *O0ER PLANT WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADISON GAS AND ELECTRIC COMPANY I2.KET NO. 50-305

1.0 INTRODUCTION

By letter dated December 1D, 1996, Wisconsin Public Service Corporation (the licensee) requested that the U.S. Nuclear Regulatory Commisslon (NRC) review its determination that NRC approval, pursuant to 10 CFR 20.2002, for the onsite disposal of. contaminated sludge at the Kewaunee Nuclear Power Plant (KNPP) is not required, provided such disposals are conducted within the limits and bounding conditions approved by the NRC in its June 17, 199Z, Safety Evaluation (SE).

2.0 BACKGROUND

In a letter dated September 12, 1989, the licensee requested authorization for the alternate disposal of sludge contaminated with licensed radioactive material. In an SE dated June 17, 1992, the NRC approved the licensee's request pursuant to 10 CFR 20.302 (new 10 CFR 20,2002) for the disposal of 15,000 cubic feet of contaminated waste sludge by land application at the KNPP location. The SE imposed boundary conditions as follows:

1. The annual disposal must be less than a total activity of 0.2 mCI;

2. The whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and

3. The disposal must be at the same site.

The SE also stated that for any repetitive disposals, the licensee must reapply to the NRC when a particular disposal would exceed the boundary conditions.

3.0 EVALUAtION The licensee has determined that NRC approval for future onsite disposals of sludge contaminated with licensed radioactive material is not required provided the disposals comply with the limits and conditions of the SE issued on June .17, 1992. The licensee has also developed a sludge sampling and analysis procedure that implements the guidance contained in NRC Information D-37

I KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 I

1 Notice 88-22. Specifically, the licensee's procedure will require the analysis of sludge samples using a detection system design and operating 3

characteristics that yield a lower limit of detection for Co-58, Co-60, Cs-134, and Cs-137 consistent with measurements of environmental samples.

licensee has provided a site map (attached) that specifies the acceptable onsite disposal areas for the contaminated sludge.

The I

4.0 CONCLUSION

I The staff agrees with the licensee's determination that additional onsitce disposals of contaminated sludge, which are conducted within the bounding limits and conditions contained in the June 17, 1992, SE and within the areas spec.ified in the attached site map, do not re~quire specific NRC approval. 3 The licensee should permanently incorporate this Safety Evaluation int.o the Offsite Dose Calculation Manual as an Appendlx.

Principal Contributor: S. Klernentowicz 3 Date: April 9, 1997

Attachment:

KNPP Site Map 3 D

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mmmm m"mm.mm mmmmm mm mm KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 14 April 18, 2012 r

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This Page Intentionally Left Blank

Appendix C Kewaunee Power Station Radiological Environmental Monitoring Manual (REMM)

Revision 19 September 6, 2012

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This Page Intentionally Left Blank I

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Dominion Energy Kewaunee, Inc.

Kewaunee Power Station RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)

Revision 19 DATE: September 6, 2012 Approved By: JM Hale 08/21/2012 Manager - Radiological Protection and Chemistry Date Approved By: RP Repshas 08/27/2012 Licensing Supervisor Date Reviewed By: Jeffrey T. Stafford 09/04/2012 Facility Safety Review Committee Date Approved By: AJ Jordan 09/06/2012 Site Vice-President Date

I

.,VV K' EEJ*I POWERA EWANE FV\L- -*.V STrATINR C-.Iv ,,.R I1/'-1rI I*./1*

RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL N i MrviTMIvI T%..),,%ý'

Revision 19 I September 6, 2012 I

Table of Contents 1.0 In tro d u ctio n ................................................................................................................... 1-1 I 1.1 1.2 P u rp o se ................................................................................................................

S c o pe ...................................................................................................................

1-1 1-1 I 1.3 Im plem entation .................................................................................................... 1-1 2.0 REM P Requirements .................................................................................................... 2-1 I 2.1 2.2 ODCM REM M 13.5 Requirements ..................................................................................

Requirements .........................................................................................

2-1 2-2 I REM M 2.2.1/2.3.1 M onitoring Program ............................................................. 2-3 REM M REMM 2.2.2/2.3.2 Land Use Census ..................................................................

2.2.3/2.3.3 Interlaboratory Comparison Program ................................

2-7 2-10 I REM M 2.4.1 Reporting Requirements ............................................................. 2-12 3.0 REM P Implementation ................................................................................................. 3-1 I 3.1 3.2 Sampling Requirements ......................................................................................

Analysis M ethodology .........................................................................................

3-1 3-1 I 3.3 Detection capability (LLD) Requirements .......................................................... 3-1 3.4 3.5 Contracted Vendor (CV) Reporting Requirements .............................................

Quality Control Program .....................................................................................

3-2 3-3 I 3.6 Sample Descriptions ............................................................................................ 3-3 I

Tables & Figures Table Table 2.2.1-A 2.2.1-B Radiological Environmental Monitoring Program Type and Frequency of Collection I

Table Table 2.2.1-C 2.2.1-D Sampling Locations, Kewaunee Power Station Reporting Levels for Radioactivity Concentrations in Environmental I Samples Table 2.3.1-A Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) I Figure 1 Figure 2 Environmental Sampling Location Ground Monitoring Wells I

KEWAUNEE POWER STATION REMM 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 1.0 Inti-oduction 1.1 Prttpose 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 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 high potential radiation exposures of MEMBERS OF THE PUBLIC resulting from plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to LOCFR 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.

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 operation of the Kewaunee Power Station 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.

1.3 Implementation This document is considered, by reference, to.be part of the Offsite Dose Calculation Manual. This is as required by KPS TS 5.5.1. 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.

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I KEWAUNEE POWER STATION REMM 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 I September 6, 2012 The REMP is setup to be implemented by a vendor and controlled by KPS in accordance with Nuclear Administrative Directive NAD-0.1.20, "Radiological Environmental Monitoring 3

Program." Monthly reviews of the vendor's progress report are checked and approved by KPS in

accordance with Surveillance Procedure SP-63-276. Annual reviews and submittals of the vendor'sI report and raw data are checked and approved by KPS in accordance with Surveillance Procedure SP-63-280. All sample collection, preparation, and analysis are performed by the vendor except where noted. Surveillance Procedure SP-63-164 outlines the environmental sample collection performed by KPS. Current vendor Quality Control Program Manuals and implementing procedures I

shall be kept on file at 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 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 TS and REMM requirements associated with the REMP. The 3

second section, 3.0 REMP Implementation, describes the specific requirements used to implement the REMP. 5 1-2

KEWAUNEE POWER STATION REMM 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 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 I OCFR50.59 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.

2.1 ODCM 13.5 Requirements ODCM 13.5 provides the programmatic control, which requires a program to monitor the 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.

Technical Specification 5.6.1 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.

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I KEWAUNEE POWER STATION REMM 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 2.2 REMM Requirements I 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. 3 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.

I I

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KEWAUNEE POWER STATION REMM 2.2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 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 A.1 Prepare and submit to the In accordance with Monitoring Program not NRC in the Annual the Annual conducted as specified in Radiological Environmental Radiological REMM Table 2.2.1-A. Operating Report, a Environmental description of the reasons Operating Report for not conducting the frequency.

program as required and the plans for preventing a recurrence.

B. Level of radioactivity in an B.1 -------- NOTES-------

environmental sampling 1. Only applicable if the medium at a specified radioactivity/radionuclides location exceeds the are the result of plant reporting levels of REMM effluents.

Table 2.2.1-D when 2. For radionuclides other than averaged over any those in REMM calendar quarter. Table 2.2.1-D, this report shall indicate the OR methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.

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I KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM 2.2.1 Revision 19 I

ACTIONS (continued)

September 6, 2012 I

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME I

More than one of the Prepare and submit to the 30 days radionuclides in REMM Table 2.2.1-D are detected in the environmental NRC, a Special Report, pursuant to DNC 15.3, that (1) Identifies the cause(s)

I sampling medium and Concentration 1 + (2) for exceeding the limit(s) and Defines the corrective I

Reporting level 1 actions to be taken to Concentration 2 +

Reporting level 2

... > 1.0. reduce radioactive effluents so that the I

potential annual dose OR to a MEMBER OF THE PUBLIC is less than the calendar year I

limits of DNC 13.1.2, Radionuclides other than those in REMM Table 2.2.1-D are detected DNC 13.2.2, DNC 13.2.3 I

in an environmental sampling medium at a specified location which are OR B.2 -------- NOTES-------

I the result of plant effluents

1. Only applicable if the and the potential annual dose to a MEMBER OF THE PUBLIC from all radioactivity/radionuclides are not the result of plant I

radionuclides is > the effluents.

calendar year limits of DNC 13.1.2, DNC 13.2.2,

2. For radionuclides other than those in REMM Table 2.2.1-D, this report I

DNC 13.2.3 shall indicate the methodology and parameters used to I

estimate the potential annual dose to a MEMBER OF THE PUBLIC. I Report and describe the In accordance with the condition in the Annual Radiological Environmental Operating Report.

Annual Radiological Environmental Operating Report U

frequency. I 2-4 I

KEWAUNEE POWER STATION REMM 2.2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. Milk or fresh leafy C.1 Identify specific alternative 30 days vegetation samples locations for obtaining unavailable from one or replacement samples and more of the sample add them to the locations required by Radiological Environmental REMM Table 2.2.1-A. 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.

VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.1 Collect and analyze radiological environmental In accordance with monitoring samples pursuant to the requirements of REMM REMM Table 2.2.1-A and the detection capabilities Table 2.2.1-A required by Table 2.2.1 -A 2-5

I KEWAUNEE POWER STATION REMM 2.2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 I September 6, 2012 BASES The radiological environmental monitoring program required by this requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 1 OCFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of I

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 3

routine environmental measurements in industrial laboratories. Itshould 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). i 2-6

KEWAUNEE POWER STATION REMM 2.2.2 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 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 milk animal and the nearest residence, and the nearest garden > 50 m2 (500 ft2 ) producing broad leaf vegetation, sampling of 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 4c shall be followed, including analysis of control samples.

APPLICABILITY: At all times.

ACTIONS NON-CONFORMANCE .CONTINGENCY MEASURES RESTORATION TIME A. Land use census identifies A.1 I:dentify the new location(s) In accordance with location(s) that yields a in the next Radiological the Radiological calculated dose, dose Environmental Operating Environmental commitment greater than Program. Operating Report.

the values currently being calculated in ODCM 13.2.3.1 2-7

U rKEWAUNEZE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM 2.2.2 Revision 19 I

September 6, 2012 NON-CONFORMANCE [CONTINGENCY MEASURES RESTORATION TIME I

B. Land use census identifies B.1 Add the new location(s) to 30 days I location(s) that yields a the Radiological calculated dose, or dose commitment (via the same exposure pathway) greater Environmental Operating Program. I than 20% at a location AND from which samples are currently being obtained in B.2 Delete the sampling In accordance with I

accordance with REMM locations(s), excluding the Radiological 2.2.1. control station location, having the lowest calculated dose, dose commitment(s)

Environmental Operating Report. I or D/Q value, via the same exposure pathway, from the Radiological Environmental I

Operating Program.

AND I B.3 Submit in the next Radiological Environmental Operating Report I

documentation for a change which includes revised figures(s) and table(s) I reflecting the new location(s) with information supporting the change in sampling locations.

I VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY I

REMM 2.3.2 Conduct the land use census during the growing 12 months I

season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, reporting the results of the land use census in 1

the Annual Radiological Environmental Operating Report, or by consulting local agriculture authorities.

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KEWAUNEE POWER STATION REMM 2.2.2 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 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 10CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:

1. 20% of the garden was used for growing leafy vegetation (i.e., similar to lettuce and cabbage), and

2. A vegetation yield of 2 kg/m 2.

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I KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM 2.2.3 Revision 19 I

September 6, 2012 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON I

PROGRAM REMM 2.2.3 Analyses shall be performed on all radioactive materials, supplied as part I

of an Interlaboratory Comparison Program that has been approved by the APPLICABILITY:

Commission.

At all times.

I ACTIONS I NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Analyses not performed as A.1 Report the corrective actions In accordance with I

required. taken to prevent a the Annual recurrence to the NRC in the Annual Radiological Environmental Operating Radiological Environmental Operating Report.

I Report.

I VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY I

REMM 2.3.3 Report a summary of the results obtained as part of the Interlaboratory Comparison Program in the Annual In accordance with the Annual I

Radiological Environmental Operating Report. Radiological Environmental Operating Report.

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I 2-10 I

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KEWAUNEE POWER STATION REMM 2.2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 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 10CFR Part 50.

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I KEWAUNEE POWER STATION REMM 2.4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 I September 6, 2012 REMM 2.4.1 Reporting Requiremtents I 2.4.1 The Annual Radiological Environm.ental 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, 3

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 operation on the I

environment. The reports shall also include the results of land use censuses required by REMM 2.2.2.

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b. The results of analyses of radiological environmental samples and of environmental radiation measurements taken during the period pursuant to3 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 3 KPS TS 5.6.1 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 TS 5.6.1, as the method for reporting deviations from the current I

program during the reporting period, and require that this information be included in the Annual Radiological Environmental Operating Report.

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KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 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 will be maintained in KPS's vault.

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).

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I KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 I September 6, 2012 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 together with graphic representations where trends are evident, and the status of field collections. One copy of the reports will be submitted within 30 to 60 days of the reporting month.

3 Annual Reports 3 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. Draft copies of each annual report will be due 60 days after completion of the annual period.

After final review of the draft document, one photoready copy of the revised annual report will be sent to KPS for printing.

Non-Routine Reports 5 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 i 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. i 3-25

KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 3.5 Quality Control Pr-ogram To insure the validity of the data, the CV maintains a quality control (QC) program, which employs quality control checks, with documentation, of the analytical phase of its environmental monitoring studies. The program is defined in the CV's QC Program Manual, and procedures are presented in the CV QC Procedures Manual. The program shall be reviewed and meet the requirements of Regulatory Guide 4.15 and 10CFR2 1. All data related to quality control will be available for review by Dominion Energy Kewaunee upon reasonable prior notification. Proprietary information will be identified so that it may be treated accordingly.

Updated copies of the Quality Control Program Manual and the Quality Assurance Program Manual will be maintained in KPS's vault.

3.6 Sample Descriptions A description of each of the samples required by this. program follows:

Airborne Particulates Airborne particulates are collected at six locations (K-lf, K-2, K-8, K-31, K-41, and K-43) on a continuous basis on a 47 mm diameter membrane filter of 0.8 micron porosity at a volumetric rate of approximately one cubic foot per minute (CFM). The filters are changed weekly, placed in glassine protective envelopes, and dispatched by U.S. Mail 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 concentration 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/m 3 .

Airborne Iodine All air samplers are equipped with charcoal traps installed behind the particulate filters for collection of airborne 1-13 1. The traps are changed once every week. Iodine-131 is measured by Gamma Isotopic Analysis.

Periphyton (Slime) or Aquatic Vegetation Periphyton (slime) or aquatic plant samples are collected at or near locations used for surface water sampling. They are collected twice during the year (2nd and 3rd quarter), if available. The samples are analyzed for gross beta activity and, if available in sufficient quantity, for Sr-89, Sr-90, and by Gamma Isotopic Analysis. Reporting units are pCi/g wet weight.

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I KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 I

Fish I Fish are collected three times per year (second, third, and fourth quarters) near the discharge area (K-ld). Flesh is separated from the bones and analyzed for gross beta activity and by Gamma I Isotopic Analysis. The bones are analyzed for gross beta activity and Sr-89 and Sr-90. Reporting units are pCi/g wet weight. 3 Domestic Meat Domestic meat (chickens) may be collected once a year during the 3rd quarter, from three locations I in the vicinity of the plant (K-24, K-29, and K-32). Samples may not be available every year at every location due to farmer preference. At least one control and one indicator should be collected. The flesh is analyzed for gross alpha, gross beta, and by Gamma Isotopic Analysis to identify and I quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

Ambient Radiation 3 Two packets of thermoluminescent dosimeters (CaSO 4: Dy cards) are placed at twenty-two locations, six of which are air sampling locations (K-I f, K-2, K-8, K-31, K-41, and K-43), three of which are milk sampling locations (K-3, K-5, and K-39), eight of which are ISFSI area locations 3

(K-11 through K- 1s), and the remaining four locations are K -15, K- 17, K-27, and K-30. 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 insure 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 manufacturer (Teledyne Isotopes) 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 I

background. Maximum Error (I 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 I TLDs.

Tests for uniformity and reproducibility of TLDs as specified in ANSI N545-1981 and NRC I Regulatory Guide 4.13, are performed annually.

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KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 Well Water One gallon water samples are taken once every three months from four off-site wells, (K- 10, K-11, K- 13, and K-38) and two on-site wells (K- 1h and K- 1g). 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-89, and Sr-90. Samples from K-lh and K-lg are also analyzed for gross alpha.

Reporting units are pCi/I.

Precipitation A monthly cumulative sample of precipitation is taken at Location K- 11. This sample is analyzed for tritium. Reporting units are pCi/l.

Milk Milk samples are collected from three herds that graze within three miles of the reactor site (K-38, K-44, and K-34); from four herds that graze between 3-7 miles of the reactor site (K-3, K-5, K-35, and K-39); and one from a dairy in Green Bay (K-42), 28.1 miles from the reactor site.

The samples are collected twice per month during the grazing period (May through October) and monthly for the rest of the year. To prevent spoilage the samples are treated with preservative. All samples are analyzed by Gamma Isotopic Analysis and for iodine -131 immediately after they are received at the laboratory. To achieve required minimum sensitivity of 0.5 pCi/l, iodine is separated on an ion exchange column, precipitated as palladium iodide and beta counted. Monthly samples and monthly composites of semimonthly samples are then analyzed for Sr-89 and Sr-90. Potassium and calcium are determined and the "'Cs/gK and 9°Sr/gCa ratios are calculated. Reporting units are pCi/I except for stable potassium and calcium, which are reported in g/l.

If milk samples are not available, green leafy vegetables will be collected on a monthly basis (when available) from Locations K-23A, K-23B, and K-26.

Grass Grass is collected three times per year (2nd, 3rd, and 4th quarters) from the six dairy farms (K-3, K-5, K-35, K-34, K-38, and K-39) and from two on-site locations (K-lb and K-if). The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet 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 six dairy farms. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

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I KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 I September 6, 2012 Vegetables and Grain I Annually, during the 3rd quarter, samples of five varieties of vegetables grown and marketed for human consumption are collected from K-26, 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 varieties of grain or leafy vegetables from the highest predicted X/Q and D/Q, if available, are collected annually from the I farmland owned by Dominion Energy Kewaunee (K-23 a and b) and rented to a private individual for growing crops. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.

Quarterly samples of eggs can be taken from K-24 and K-32. At least one control and one indicator should be collected. The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides. Reporting units are pCi/g wet weight.

I Soil 3 Twice during the growing season samples of the top two inches of soil are collected from the six dairy farms and from an on-site location (K-if). The soil is analyzed for gross alpha and gross beta activities, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting manmade radionuclides. Reporting units are pCi/g dry weight.

Surface Water I Surface water is sampled monthly from Lake Michigan at the KPS discharge (K-Id), two samples (north and south ends), of Two Creeks Park, 2.5 miles south of the reactor site (K- 14a, K-14b). Samples are collected monthly at the Green Bay Municipal Pumping station between Kewaunee and Green Bay (K-9). Raw and treated water is collected. Monthly samples are also taken, when available, from each of the three creeks (K-la, K-i b, K- 1e) that pass through the reactor site and from the drainage pond (K-1k) south of the plant. The I

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.

b.

c.

The total residue, The dissolved solids, and The suspended solids.

3 The samples are also analyzed for K-40 and by Gamma Isotopic Analysis. Quarterly composites from all locations are analyzed for tritium, Sr-89 and Sr-90. Reporting units are pCil.

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KEWAUNEE POWER STATION REMM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 19 September 6, 2012 Bottom Sediments Five samples of Lake Michigan bottom sediments, one at the discharge (K-Id), one from 500 feet north of the discharge (K-Ic), one from 500 feet south of the discharge (K- lj), and one at the Two Creeks Park (K-14), one at the Green Bay Municipal Pumping Station (K-9) are collected semi-annually (May and November). The samples are collected at the beach in about 2-3 feet of water. All samples are analyzed for gross beta activity, for Sr-89 and Sr-90 and by Gamma isotopic Analysis. Since it is known that the specific activity of the sediments (i.e., the amount of radioactivity per unit mass of sediment) increases with decreasing particle size, the sampling procedure will assure collection of very fine particles. Reporting units are pCi/g dry weight.

Ground Monitoring Wells Figure 2 shows the location of 14 installed groundwater monitoring wells. The wells and location are identified with a diamond shape in Figure 2. The wells are labeled MW (Monitoring Well) and AB (Auxiliary Building).

The Groundwater Protection Program consists of the 14 wells in addition to the two on-site wells already in the REMM (K-lg and K-lh).

Results of analyses and a description of anyevent above Reporting Levels will be included in the Annual Radiological Environmental Operating Reportfor K- Ig, K-1 h and in the annual Radioactive Effluent Release Report for the other 14 wells.

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Table 2.2.1-A RadiologicalEn viromnental Monitoring Program_ II Exposure Pathway Mininmum F Available Sample Sampling,and hCollection Type of 1.

And/Or Sample Direct Radiationc Required Samples a 13 Inner Ring locations Locations h K-5, K-25, K-27, Analysis Frequency See Table 2.2.1-B Analysis Gamma dose U

I K-43, K-11; K-30, K-11, K-lm, K-in, K-lo, K-lp, K-lq, K-br, K-is 6 Outer Ring locations K-2, K-3., K-IS, K-17, K-8, K-31, K-39 I

1 Control location K-41 I Population center I Special interest location K-43 K-8 I

2. Airborne Radioiodine and Particulates I Nearby resident 3 samples close to the site boundary in highest K-27 K-If, K-2, K-43, K-8, K-31 See Table 2.2.1.B Continuous lodine (l-131) by Gamma I

U average X/Q sampler operation Isotopicf Iodine; charcoal I sample from the closest K-43 Particulates Particulates; community having the highest X/Q I sample from a control K-41d See Table 2.2.1 -B See Table 2.2. 1-B gross beta analysise Gamma isotopic I

of composite I

location (by location) f

3. Waterborne

a. Surface' I Upstream sample K-la, K-9', K-id Grab sample Gross Beta, I Downstream sample K-le, K-14a, K-14b, K-1k, K-lb See Table 2.2. 1-B Gamma isotopic K-40 I

i Composite of grab samples for tritium, K-40 and I

b. Ground 1-2 location likely to be affected d K-ig, K-lhh Grab sample See Table 2.2.1 -B Sr 89/90 Gamma isotopic r, I

tritium and K-40 analysis Gross Beta, I

one well for Sr 89/90 I

I Rev. 19 Page 1 of 4 September 6, 2012 I

Table 2.2.1-A RadiologicalEnvironmentalMonitoring Program Exposure Pathway And/Or Sample Minimum Required Samples a Available Sample Locations h 1nCllcio Sampling, Collection and and Analysis Frequency T

Tyeo Analysis Aayi

c. Drinking 1-3 samples of nearest K-10, K-11, K-13, K-38 Grab sample Gross beta and water supply See Table 2.2.1-B gamma isotopic*

analysis. Tritium and K-40 analysis of the composite of monthly grab samples.'

d. Sediment from I sample from K-14, K-ic, K-id, Grab sample Gamma isotopicf shoreline downstream area with K-lj, K-9 See Table 2.2. 1-B analysis potential for recreational Gross Beta, value Sr 89/90

4. Ingestion

a. Milk Samples from milking K-5k, K-38, K-34, See Table 2.2. 1-B 1-131 animals in 4 locations K-44 Gamma Isotopic within 5 km having the SR highest dose potential. 89/90 I alternate location K-3, K-39 I control location K-35, K-42

b. Fish 3 random samplings of K-id See Table 2.2.1-B Gamma isotopic' commercially and and Gross Beta recreationally important on edible species in the vicinity of portions, Gross the discharge. Beta and Sr 89/90 on bones

c. Food Products Samples of grain or leafy 2 samples K-23a, See Table 2.2.1-B Gamma isotopic vegetables grown nearest K-23b - and one more r and 1-131 each of two different location if available Analysis.

offsite locations within 5 miles of the plant if milk sampling is not I sample 15-30 kin performed. distant if milk sampling is not performed. K-26 Rev. 19 Page 2 of 4 September 6, 2012

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Table 2.2.1-A 1

Radiological En vihonmental Monitoring Program_ I Exposure Pathway J

Minimuru l1 Available Sample 1 Sampling, Type of U

jI b Collection and And/Or Sample Required Samplesa Locations b Analysis Frequency Analysis

5. Miscellaneous samples I

not identified in NUREG-0472

a. Aquatic Slime None required K-lk See Table 2.2.1-B Gross Beta activity and if I

K-ia, K-lb, K-le available Sr-89, K-14, K-id Sr-90 and Gamma

b. Soil None required K-9 (control)

K-if, K-5, K-35, K-39 IsotopicC Gross Alpha/Beta I

K-34, K-38 K-3, (control)

See Table 2.2.1 -B Sr-89 and Sr-90 Gamma Isotopicr I

c. Cattle feed None required K-5, K-35, K-39 K-34, K-38 See Table 2.2.1-B Gross Beta Sr-89 and Sr-90 I

K-3,(control) Gamma

d. Grass None required K-ib, K-if, K-35, Isotopic' Gross Beta I

K-39 K-5, K-34, K-38 K-3,(control)

See Table 2.2.1-B Sr-89 and Sr-90 Gamma I

Isotopic'

e. Domestic Meat None required K-24, K-29 See Table 2.2. 1-B Gross Alpha/Beta I

K-32 (control) Gamma

f. Eggs None required K-32 See Table 2.2. 1-B Isotopicý Gross Beta I

I K-24 Sr-89/90 Gamma

_sotopicf I

g. Precipitation None required K-11 See Table 2.2.1-B Tritium I

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Table 2.2.1-A Radiological EnvironmnentalMonitoringPrograin Exposure Pathway Minimum Available Sample bCollection Sampling,and Tyeo And/Or Sample Required Samples a Locations AnCllcio Analysis and Frequency Analysis Aayi Table Notations

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 to 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. l.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 ofechoice 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. Ground 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 analysis 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. K-5 is about 5.1 kin, closest Milk Location available.

Rev. 19 Page 4 of 4 September 6, 2012

I Table 2.2.1-B Type and Frequency of Collection i

Location jWeekly Monthly Quarterly Se-mi-An nually Annually K-la SW SCU K-Ib SW GRa SL' K-Ic K-Id SW FIa BSb BS' SLC I

K-le K-If API', A]

SW GRa TLD SO SL' I

K-lg WW K-Ih WW K- Ij BSb I

K-Ik SW SL' K-Il K-Im TLD TLD I

K-In K-lo TLD TLD I K- Ip TLD K-I q K-] r TLD TLD I

K-Is K-2 K-3 AP9,, Al MIc GR' TLD TLD TLD SO CF' i

K-5 K-8 AP',, Al MIC GRa TLD TLD SO CF*

I K-9 SWi BS' SL K-10 K-1I PR WW WW I

K-13 K- 14 K- 15 SWh WW TLD BS' SL I K- 17 K-23a TLD GRN/GLVe I

K-23b GRN/GLVe K-24 K-25 EG TLD DM I K-26 VE/GLVe K-27 TLD K-29 DM Rev. 19 Page 1 of 2 September 6, 2012

Table 2.2.1-B Type and Frequency of Collection Location Weekly Monthly Quarterly Semi-Annually Annually K-30 TLD K-31 API', Al TLD K-32 EG DM K-34 MIC GRa SO CFd K-35 MIC GRa SO CF' K-38 MIc GRa WW SO CFd K-39 MIC TLD GRa SO CFd K-41 APg', Al TLD K-42 MIC K-43 AP', Al TLD K-44 MIc

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. Monthly from November through April; semimonthly from May through October

d. First (January, February, March) quarter only

e. Alternate if milk is not available

f. Second and third quarters

g. The frequency may be increased dependent on the dust loading.

h. Two water samples are collected, North (K- 14a) and South (K- 14b) of Two Creeks Rd.

i. Two samples, raw and treated Code Description Code Description Code Description At Airborne Iodine FI Fish SO Soil AP Airborne Particulate GR Grass SW Surface Water BS Bottom Sediment GRN Grain TLD Thermoluminescent Dosimeter CF Cattle feed MI Milk VE Vegetables DM Domestic Meat PR Precipitation WW Well Water EG Eggs SL Slime GLV Green Leafy Vegetables Rev. 19 Page 2 of 2 September 6, 2012

i Table 2.2.1-C I Sampling Locations, Kewiaunee Power Station Code Typea Distance (Miles)b and Location U

Sector K-1 Onsite K-la 1 0.62 N North Creek K-lb K-1c 1

1 0.12 N 0.10 N Middle Creek 500' North of Condenser Discharge I

K-Id K-le 1

I 0.10 E 0.12S Condenser Discharge South Creek I K-if 1 0.12 S Meteorological Tower K-lg K-lh 1

1 0.06 W 0.12 NW South Well North Well I

K-Ij K-lk 1

1 0.10 S 0.60 SW 500' south otf Condenser Discharge Drainage Pond, south of plant I K-11 1 0.13 N ISFSI Southeast K-Im K-in 1

1 0.15 N 0.16 N ISFSI East ISFSI Northwest I

K-lo K-lp K-lq 1

1 I

0.16 N 0.17 N 0.16 N ISFSI North ISFSI Northwest ISFSI West I

K-Ir K-Is I

1 0.13 N 0.12 N ISFS1 West ISFSI Southwest I

K-2 C 8.91 NNE WPS Operations Building in Kewaunee K-3 K-5 C

1 5.9 N 3.2 NNW Lyle and John Siegmund Farm, N2815 Hy 42, Kewaunee Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee I

K-8 C 4.85 WSW Saint Isadore the Farmer Church, 18424 Tisch Mills Rd, Tisch Mil Mills Green Bay Municipal Pumping Station, six miles east of Green I

K-9 K-10 C

I 11.5 NNE 1.35 NNE Bay (sample source is Lake Michigan from Rostok Intake 2 miles north of Kewaunee)

Turner Farm, Kewaunee Site I

K-i 1 K-13 K-14 1

C I

0.96 NW 3.0 SSW 2.6 S Harlan lhlenfeldt Farm, N879 Hy 42, Kewaunee Rand's General Store, Two Creeks Two Creeks Park, 2.5 miles south of site I

K-I5 K-17 C

I 9.25 NW 4.0 W Gas Substation, 1.5 miles north of Stangelville Jansky's Farm, N885 Cty Tk B, Kewaunee I

K-20( c) 1 2.5 N Carl Struck Farm, N1596 Lakeshore Dr., Kewaunee Rev. 19 Page 1 of 2 September 6, 2012 I

Table 2.2.1-C Sampling Locations, Kewaunee Power Station Distance Code Typea (Miles)b and Location Sector K-23a 1 0.5 W 0.5 n-files west of plant, Kewaunee site K-23b I 0.6N 0.6 miles north of plant, Kewaunee site K-24 1 5.4 N Fictum Farm, N2653 Hy 42, Kewaunee K-25 1 1.9 SW Wotachek Farm, E3968 Cty Tk BB, Two Rivers K-26(d) C 9.1 SSW Sandy's Vegetable Stand (8.0 miles south of "BB")

K-27 1 1.53 NW Schleis Farn, E4298 Sandy Bay Rd K-29 1 5.34 W Kunesh Farm, E3873 Cty Tk G, Kewaunee K-30 I 0.8 N End of site boundary K-31 1 6.35 NNW E. Krok Substation, Krok Road K-32 C 7.8 N Piggly Wiggly, 931 Marquette Dr., Kewaunee K-34 1 2.7 N Leon and Vicky Struck Farm, N 1549 Lakeshore Drive, Kewaunee K-35(e) C 6.71 WNW Duane Ducat Farm, N 1215 Sleepy Hollow, Kewaunee K-36(f) I Fiala's Fish Market, 216 Milwaukee, Kewaunee K-38 I 2.45 WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee K-39 1 3.46 N Francis Wotja Farm, N1859 Lakeshore Road, Kewaunee K-41 (g) C 22 NW KPS-EOF, 3060 Voyager Drive, Green Bay K-42 (h) C 28.1 W Lamers Dairy Products obtain from Green Bay Markets (i)

K-43 0) 1 2.71 SSW Gary Maigatter Property, 17333 Highway 42, Two Rivers K-44 1 2.63 SW Gerald and Betty Schleis, 4728 Schleis Rd., Two Rivers

a. I = indicator; C = control.

b. Distances are measured from reactor stack.

c. Location removed from program in 2007

d. Location K-18 was changed because Schmidt's Food Stand went out of business. It was replaced by Bertler's Fruit Stand (K-26). Replaced with Sandy's Vegetable in 2007.

e. Removed from the program in Fall of 2001, back to program in August 2008.

f. Removed from the program in Fall of 2001, back to program in August 2008.

g. Location replaces K-16, January of 2007

h. Location replaces K-28 as of March 2010

i. Lamers Dairy is actually located in Appleton. The herds providing milk to Lamers are located nearer to Appleton than the plant to provide adequate distance for purposes of a control location.

j. K-7 moved to a nearby location and relabeled K-43, within 0-2 miles of original, August/September 2010.

Rev. 19 Page 2 of 2 September 6, 2012

£ Table 2.2.1-D Reporting Levels for Radioactivity Concentrationsin Environmental Samples II Medium Radionuclide Reporting Levels CV to KPSW KPS to NRC" 3 Airborne Particulate or Gases (pCi/rn3) Gross Beta I --

1-131 (Charcoal)

Cs-134 0.1 1

0.9 10 I

Precipitation (pCi/1)

Cs-137 H-3 1,000 1 20

-- I Water (pCi/1) Gross Alpha 10 --

Gross Beta H-3 30 10,000 20,000c U

Mn-54 Fe-59 Co-58 100 40 100 1,000 400 1,000 I

Co-60 Zr-Nb-95 30 40 300 400 I

I Cs- 134 10 30 Cs- 137 20 50 Ba-La- 140 100 200 Sr-89 Sr-90 8d 8-

- I Zn-65 30 300 Milk (pCi/I) 1-131 Cs- 134 1.0 20 60 3 U Cs- 137 Ba-La-140 20 100 70 300 I Sr-89 10 --

Grass, Cattle Feed, and Vegetables (pCi/g wet)

Gross Beta 1-131 30 0.1 0.1 I

Cs- 134 Cs-137 0.2 0.2 2 1

I Sr-89 I - -

Sr-90 I --

I I

Page 1 of 2 Rev. 19 September 6, 2012 I

1

Table 2.2.1-D Reporting Levels for Radioactivity Concentrationsin EnvironnentalSamples Reporting Levels Medium Radionuclide CV to KPSa KPS to NRCh Eggs (pCi/g wet) Gross Beta 30 --

Cs- 134 0.2 1 Cs- 137 0.2 2 Sr-89 I --

Sr-90 I --

Soil, Bottom Sediments (pCi/g) Gross Beta 50 - -

Cs-134 5 - -

Cs- 137 5 --

Sr-89 5 --

Sr-90 5 --

Meat (pCi/g wet) Gross Beta (Flesh, 10 - -

Bones)

Cs-134 (Flesh) 1.0 1.0 Cs-137 (Flesh) 2 2.0 Sr-89 (Bones) 2 --

Sr-90 (Bones) 2 --

Fish (pCi/g wet) Gross Beta (Flesh, 10 --

Bones)

Mn-54 -- 30.0 Fe-59 -- 10.0 Co-58 -- 30.0 Co-60 -- 10.0 Cs-134 (Flesh) 1 1.0 Cs- 137 (Flesh) 2 2.0 Sr-89 (Bones) 2 --

Sr-90 (Bones) 2 --

Zn-65 (Bones) -- 20

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 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

d. The Sr-89/90 values are based on the EPA drinking water standards. See note "f." of Table 2.3.1-A for further information Rev. 19 Page 2 of 2 September 6, 2012

Table 2.3.1-A Detection Capabilitiesfor Environmental Sample Analysis' Lower Limit of Detection (LLD) b,c Water Airborne Fish Food Products Sediment Analysis Particulate or3 Milk (pCi/I)

Anals(pCi/1) Gases (pCi/m ) (pCi/kg, wet) (pCi/kg, wet) (pCi/kg, dry)

Gross Beta 4 0.01 H-3 2000' Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zr-Nb-95 15 1-131 1e 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Zn-65 30 260 Sr-89/90 f 5 Rev. 19 Page 1 of 3 September 6, 2012 m-mm m mmm mmm m m m W

Table Notationsfor 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:

LLD = 4"66sb E x V x 2.22 x Y x exp(--yAt)

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,

,yis the radioactive decay constant for the particular radionuclide, and At 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 At should be used in calculation.

Rev. 19 Page 2 of 3 September 6, 2012

I I

Table Notationsfor Table 2.3.1-A (con 't) I 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 U

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 I

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. I

e. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used. I

f. 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.

I I

Rev. 19 I

Page 3 of 3 September 6, 2012 I

FIGURE1 El, -

c i s ANY)

D

- 4 ,I ... U K-3

- -~ - + -,' 4 -,',---- I 1~~~

K-35I Ey q- K-1

ý3 /7-'

_ . -,. -I . -- .--- -

16o !

-43 .~

o~

8 -

8 174~~1 74- =

lIl U'

Rev. 19 Page I of I September 6, 2012

FIGURE 2 NOTES we0or* afttw IW.45" 2644041 6000.8 UW-0701 ?P'Ic 725M 260484 600.81 L LOCATIONS OF U dITORMNWELLSSUR~VEYEDBY STS ON jJ*W 2L 2007. *M-0102 C~* 782?2a w4440 to?."?

.0702 Tftt 30527L z44409 Goo.2

2. LOCATI~kS OF WATERSUPPLYWELLSARE £57 b'AEO. 74-01-03IMFC IM72a3 2144304 402.44 Ww.3-030MONO 11476M 248 M S M10.0 143-074 OFCUM 7,4029 260426 604.33 00704 TPV 7,93* 21042h 44.

.OroS IM"A7826. 264482 604.212 LEGENDs 7OM~8 MM"64. Z64482 605.3"1 I

,610?6 CALý nsVLz 26440 G0&403 A$ 0107 AO0707 "KV

~aftQo31460.4

,- -0?00 IPIC 382A$L t9540 2044000 2644562 20404 am".?0 606.3231 600.412 as 0one CDOUND 31045L 2640450 506.067 As 0306 IPVC MAS4I 24021" 101.SMS SUPPLY WELL. As ow~l MUN 31446.5 264441 40433 A* 0"0 7400 t1044 264441 605.824 AO 0On0 CRW*O 36421. 2644ft0 404.145 MONITORINAEG BELL.

AD 0130 IPVO AS 0713O~lkR ASh073 i P*C ash 07332343 i

ai 0712 amI As 0715OPOL As 0731 IWYC 395012" VISMIL 31942".

2040420 605.9a72 26444? 6000.A4 2944043?7400.4 WA942A426444367 600504U 35100 2%444 605.05 31l32 264413 100.721 31191. 2644537 402421 I

As 0717 3214NO 34409. 2644M4 400.471 as 0717 7 PVC 345109. 2044010 40S.221F 7307!. C0lOWAtES AMC IN nW0 MI2 DOCOSM3STATE FLAWEU)75h I

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Rev. 19 I

Page 1 of 1 September 6, 2012 I

ML13130A005: Difference between revisions

Latest revision as of 16:21, 1 March 2020

Contents

Text

SUMMARY

1.0 INTRODUCTION

11.0 INTRODUCTION

11.0 INTRODUCTION

Background

- n -M w IM w ow 1111 M- M 1 I~10 ow M

Background

References:

Dear Mr. Schrock:

Enclosure:

SUBJECT:

Dear Mr. Schrock:

Enclosure:

1.0 INTRODUCTION

Attachment:

SUBJECT:

Dear Mr. Harchi:

Enclosure:

4.0 CONCLUSION

Attachment:

SUBJECT:

Dear Mr. Marchi:

Enclosure:

1.0 INTRODUCTION

2.0 BACKGROUND

4.0 CONCLUSION

Attachment:

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ML13130A005: Difference between revisions

Latest revision as of 16:21, 1 March 2020

Text

SUMMARY

1.0 INTRODUCTION

11.0 INTRODUCTION

11.0 INTRODUCTION

Background

- n -M w IM w ow 1111 M- M 1 I~10 ow M

Background

References:

Dear Mr. Schrock:

Enclosure:

SUBJECT:

Dear Mr. Schrock:

Enclosure:

1.0 INTRODUCTION

Attachment:

SUBJECT:

Dear Mr. Harchi:

Enclosure:

4.0 CONCLUSION

Attachment:

SUBJECT:

Dear Mr. Marchi:

Enclosure:

1.0 INTRODUCTION

2.0 BACKGROUND

4.0 CONCLUSION

Attachment:

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