Text

Kewaunee Power Station - 2013 Annual Radioactive Effluent Release Report
	ML14126A088
Person / Time
Site:	Kewaunee
Issue date:	04/29/2014
From:	Stafford J T; Dominion Energy Kewaunee
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	14-149
	Download: ML14126A088 (557)
	v • d • e

Dominion Energy Kewaunee, Inc.N490 Hwy 42, Kewaunee, WI 54216Web Address:

www.dom.com APR 2 9 2014ATTN: Document Control DeskU. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Serial No. 14-149LIC/NW/R0 Docket No.: 50-305License No.: DPR-43DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATION2013 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTEnclosed is the Kewaunee Power Station (KPS) 2013 Annual Radioactive EffluentRelease Report for January through December 2013. This report is submitted to meetthe 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. StaffordDirector Safety and Licensing, Kewaunee Power StationCommitments made by this letter: NONE Serial No. 14-149Page 2 of 2cc: Regional Administrator, Region IIIU. S. Nuclear Regulatory Commission 2443 Warrenville RoadSuite 210Lisle, IL 60532-4352 Mr. Christopher GrattonProject ManagerU.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D1511555 Rockville PikeRockville, MD 20852-2738 Mr. W. C. Huffman Jr.Project ManagerU.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D1511555 Rockville PikeRockville, MD 20852-2738 Mr. W. A. NestelInstitute of Nuclear Power Operations 700 Galleria ParkwayAtlanta, GA 30339Mr. Don Hendrikse WI Division of Public HealthRadiation Protection SectionRoom 150Madison, WI 53701-2659 Ms. Deborah RussoAmerican Nuclear Insurers95 Glastonbury Blvd.Glastonbury, CT 06033 00S00S00000SSSS0SS0S0SiADominion 2013AnnualRadioactive EffluentReleaseReportKewaunee Power StationDominion Energy Kewaunee, Inc.

0000000000000000000S00000,0S00S0000000000000DOCKET 50-305KEWAUNEE POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTJanuary 1 -December 31, 2013 S00SSSS000S0SSSThis page intentionally left blank 5S0SSSS0S00SSSSSSS0SSSSS

Table of Contents* Section Description 0.0 Sum m ary ......................................................................................................

31.0 Introduction....................................

................

31.1 Effluent D ose Lim its .....................................................................................

32.0 G aseous Effl uents .........................................................................................

52.1 Lower Limits of Detection (LLD) for Gaseous Effluents

............................

52.2 Gaseous Batch Release Statistics

.................................................................

72.3 Gaseous Effl uent Data ...................................................................................

7Table 2.1 Gaseous Effluents

-Summation of all Releases

...........................

8Table 2.2 Gaseous Effluent

-Continuous Mode .....................

9Table 2.3 Gaseous Release -Batch Mode .................................................

10Table 2.4 Dose from Gaseous Effluents

.....................................................

112.4 Estimation of Carbon-14 in Gaseous Releases

..................................

133.0 Liquid Effluents

........................................................................................

143.1 Lower Limits of Detection (LLD) for Liquid Effluents

...............................

143.2 Liquid Batch Release Statistics

...................................................................

163.3 Liquid Effluent Data .......................................

16Table 3.1 Liquid Effluents

-Summation of all Releases

............................

17Table 3.2 Liquid Effluents

-Batch Mode ...................................................

18Table 3.3 Liquid Effluents

-Continuous Mode ..........................................

19Table 3.4 Dose from Liquid Effluents

.......................................................

203.4 Ground Water Monitoring

..........................................................................

224.0 U nplanned Releases

...................................................................................

245.0 M eteorological D ata ..................................................................................

246.0 Solid W aste D isposal ................................................................................

24Table 6.1 Solid Waste and Irradiated Fuel Shipments

...............................

257.0 Program Revisions

.....................................................................................

338.0 Reportable Occurrences

..............................................................................

35Appendix A Meteorological DataAppendix B KPS Offsite Dose Calculation Manual (ODCM), Rev. 15Appendix C KPS Offsite Dose Calculation Manual (ODCM), Rev. 16Appendix D KPS Radiological Environmental Monitoring manual (REMM), Rev. 20Appendix E Documentation for Major Changes to Radioactive Waste Treatment SystemsP0* ae2o3S 0000000000000000000000000000000000000000000 0*t 0.0 SUMMARYOn October 22, 2012, Dominion made known the decision to permanently shut down the Kewaunee*t Power Station (KPS). On February 25, 2013, Dominion Energy Kewaunee (DEK) submitted a* certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(l)(i),

stating that*t DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 theNRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10CFR 50.82(a)(1)(ii).

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

During 2013 all solid, liquid, and gaseous radioactive effluents from the Kewaunee Power Station werewell below regulatory limits. For individual effluent

streams, the quarterly limit most closelyapproached was:* GASEOUS:

Ingestion Pathway-Organ Total Body* Quarterly Limit (mRem) 7.5 ndActual Dose (mRem) 5.42E-04 (2 Quarter)* % of Specification 7.23E-03* LIQUID: Ingestion Pathway-Organ GI-LLI* Quarterly Limit (mRem) 5.0Actual Dose (mRem) 5.03E-03 (2nd Quarter)% of Limit 1.OIE-01* SOLID: No upper limit for solid radioactive waste applies.Cubic Meters Shipped 3.19E+01 m3 (1.31E+03 ft3)*t

1.0 INTRODUCTION

This report is being submitted in accordance with the requirements of Kewaunee Technical

t Specifications, Section 5.6.2 and the Offsite Dose Calculation Manual, Section 15.2. It includes datafrom all effluent releases made from January 1 -December 31, 2013. The report contains summaries ofthe gaseous and liquid releases made to the environment including the quantity, characterization, timeSt duration and calculated radiation dose at the site boundary resulting from these releases.

The reportalso includes a summation of solid radioactive waste disposal, revisions to the Process ControlProgram 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.*t 1.1 Effluent Dose LimitsSpecifications are set to ensure that offsite doses are maintained as low as reasonably achievable while*t still allowing for practical and dependable operation of the Kewaunee Power Station.*t The Kewaunee Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters

__ used in:Page 3 of 35 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 andcumulative quarterly and annual doses. The ODCM methodology is acceptable for usein demonstrating compliance with 10 CFR 20.1301/1302; 10 CFR 50, Appendix I; and40 CFR 190.Page 4 of 350000000SS0000000SSSSSSSSS000SSS0SSSS0S0SSSS0 00000000SSSSS0000S002.0 GASEOUS EFFLUENTS 2.1 Lower Limits of Detection (LLD) for Gaseous Effluents Gaseous radioactive effluents are released in both the continuous mode and the batch mode. Theauxiliary building stack is sampled continuously for particulates, halogens and Strontium by an "off-line" sample train. This stack is also grab-sampled weekly for gaseous gamma emitters.

Batch releasesare sampled prior to release for principal gaseous and particulate gamma emitters, halogens and tritium.The LLD's for gaseous radio-analyses, as listed in Table 13.2.1-1 of the Kewaunee ODCM are:AnalysisLLD (gCi/ml)Gaseous Gamma EmittersIodine 131Particulate Gamma EmittersParticulate Gross AlphaStrontium 89, 90Noble Gases, Gross Beta or Gamma1.OOE-043.OOE- 121.OOE- 1IL.OOE- 1IL.OOE- 111.OOE-06The nominal "a priori" LLD values are shown below.Isotopea priori LLD (jtCi/ml)

a. Gaseous emissions:

Kr-87Kr-88Xe-133Xe-133mXe-135Xe-1385.61 E-081.02E-076.68E-082.75E-072.99E-081.13E-07Page 5 of 35

b. Particulate emissions:

Mn-54Fe-59Co-58Co-60Zn-65Mo-99Cs-134Cs-137Ce-141Ce-1441.11E-132.27E-132.28E-133.57E-131.68E-132.73E-134.69E- 131.68E-132.08E-131.24E-12c. Other identifiable gamma emitters:

Ar-41Kr-85Kr-85mKr-89Xe-127Xe-131mXe-135mXe-1371-1313.97E-108.63E-054.62E-082.04E-064.20E-081.82E-061.90E-082.88E-071.32E-1300000S00S0SSSSSSSSSSSSSSSSSSSSS00SSSSSSSS0S0d. Composite particulate samples:Sr-89 1.OOE-14Sr-90 1.00E- 14Gross Alpha 1.OOE-14These "a priori" LLDs represent the capabilities of the counting systems in use, not an after the fact "aposteriori" limit for a particular measurement.

Page 6 of 35 00S0000S00000000SSS0S0S00S002.2 Gaseous Batch Release Statistics The following is a summation of all gaseous batch releases made during 2013.Number of batch releases

.................................

27Total time for all batch releases (min) ...............

2490.0Maximum time for a batch release (min) ...........

1440.0Average time for a batch release (min) ...................

92.1Minimum time for a batch release (min) .................

16.02.3 Gaseous Effluent DataTable 2.1 presents a quarterly summation of the total activity released and average release rates ofgaseous effluents.

Table 2.2 lists the quarterly sums of individual gaseous radionuclide released bycontinuous mode. Table 2.3 lists the quarterly sums of individual gaseous radionuclide released bybatch mode. Table 2.4 presents the dose limits for gaseous effluents, and the calculated doses this yearfrom gaseous effluents.

Page 7 of 35 Table 2.1Gaseous Effluents

-Summation of all ReleasesFission and Activation GasesTotal Activity Released (Ci)Average Release Rate (ItCi/sec) 1 st QuarterO.OOE+00O.OOE+002nd Quarter1.79E-022.27E-033rd QuarterO.OOE+00O.OOE+004th Quarter TotalO.OOE+00O.OOE+001.79E-025.67E-04lodinesTotal Activity Released (Ci)Average Release Rate (gtCi/sec)

O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00Particulates Total Activity Released (Ci)Average Release Rate (jtCi/sec)

O.OOE+00O.OOE+006.84E-068.68E-07O.OOE+00O.OOE+002.8 1E-053.564E-06 3.49E-051.11 E-06Tritium00000000000000000000000000000000000000000000Total Activity Released (Ci)Average Release Rate (ptCi/sec)

Gross Alpha Released (Ci)8.54E+001.08E+002.05E+012.60E+001.32E+011.67E+007.95E+001.01E+005.02E+011.59E+00O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Carbon-14 Total AnnualActivity Released (Ci)2.41E+00Page 8 of 35 00SS000000000S000S000Table 2.2Gaseous Effluents

-Ground Level -Nuclides Released (Ci)Continuous Mode1 st Quarter2nd Quarter3rd Quarter4th QuarterTotalFission GasesTotalO.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00 O.OOE+00O.OOE+00 O.OOE+00IodinesTotalParticulates Co-58Nb-95Cs-137 mTotalGross AlphaTritiumO.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+008.54E+005.84E-061.OOE-06O.OOE+006.84E-06O.OOE+005.57E+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+001.32E+01O.OOE+00O.OOE+002.8 1E-052.8 1E-055.84E-061.OOE-062.8 1E-053.49E-05O.OOE+00 O.OOE+007.95E+00 3.52E+01000000000(1) Cs- 137 isotope was in contaminated oil that was transferred to the heating boiler for disposal as partof the continuous release process.Page 9 of 35 0000Table 2.3Gaseous Effluents

-Ground Level -Nuclides Released (Ci)Batch Mode1 st Quarter2nd Quarter3rd Quarter4th QuarterTotalFission GasesXe-133Xe-133mTotallodinesTotalParticulates TotalTritiumO.OOE+00O.OOE+00O.OOE+001.78E-023.77E-051.78E-02O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+001.78E-023.77E-051.78E-02O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+00O.OOE+003.68E-03O.OOE+00O.OOE+001.49E+01O.OOE+00O.OOE+002.83E-03O.OOE+00O.OOE+00O.OOE+00O.OOE+001.49E+010000000000000000000000000000000000000Gross AlphaO.OOE+00 O.OOE+00Page 10 of 35 00S000S000S00000S0000S0000Table 2.4Dose from Gaseous Effluents The offsite dose limits from radioactive materials in gaseous effluents are specified in Section 13.2.2and 13.2.3 of the Kewaunee ODCM and can be summarized as follows:LimitQuarterly AnnualAir DoseGamma5.0 mrad10.0 mradAir DoseBeta10.0 mrad20.0 mradOrgan7.5 mrem15.0 mremThe total releases of gaseous effluents during 2013 for each quarter and for the year were within limits.The following offsite doses were calculated using equations 2.7, 2.8, and 2.11 from the KewauneeODCM. Calculated offsite doses versus quarterly and annual limits are shown below:1 st Qtr1. Gamma- Air DoseSpecification (mrad)Actual Dose (mrad)% of Specification

2. Beta- Air DoseSpecification (mrad)Actual Dose (mrad)% of Specification

3. Organ DoseSpecification (mrem)Total BodyActual Dose (mrem)% of Specification BoneActual Dose (mrem)% of Specification 5.OOE+000.OOE+000.OOE+001.00E+010.OOE+000.OOE+007.50E+002.26E-043.01E-030.00E+000.OOE+002nd Qtr5.OOE+001.49E-072.98E-061.00E+014.43E-074.43E-067.50E+005.42E-047.23E-031.40E-071.86E-063rd Qtr5.OOE+000.OOE+000.OOE+001.00E+010.OOE+000.OOE+004th Qtr5.OOE+000.OOE+000.OOE+001.00E+010.OOE+000.OOE+00Annual1.00E+011.49E-071.49E-062.OOE+014.43E-072.22E-067.50E+00 7.50E+00 1.50E+013.48E-044.64E-030.OOE+000.OOE+002. 1OE-042.8 1E-035.99E-057.99E-041.33E-038.85E-036.01E-054.01 E-04Page 11 of 35 Table 2.4 (continued)

Dose from Gaseous Effluents 1 st Qtr 2nd Qtr 3rd QtrLiverActual Dose (mrem)% of Specification ThyroidActual Dose (mrem)% of Specification KidneyActual Dose (mrem)% of Specification LungActual Dose (mrem)% of Specification GI-LLIActual Dose (mrem)% of Specification 2.26E-043.01E-032.26E-043.01E-032.26E-043.01E-032.26E-043.01E-032.26E-043.01E-035.42E-047.23E-035.42E-047.23E-035.42E-047.23E-035.42E-047.23E-035.42E-047.23E-033.48E-044.64E-033.48E-044.64E-033.48E-044.64E-034th Qtr2.11 E-042.81E-03Annual1.33E-038.85E-032. 1OE-04 1.33E-032.8 1E-03 8.85E-032.11E-042.8 1E-033.48E-04 2.1OE-044.64E-03 2.8 1E-031.33E-038.85E-031.33E-038.85E-031.33E-038.85E-033.48E-044.64E-032.1OE-042.8 1E-0360600000000000S0S000000000000000000000000S0Page 12 of 35 00000000000000000000000000000000000000000002.4 Estimation of Carbon-14 in Gaseous ReleasesPer Nuclear Engineering in Innsbrook the Cycle 31 flux values are bounding and conservative and canbe used for all future cycles (reference KW-CALC-000-C 11988).Based on 127 days on line in 2013 and 331 days on line in 2012 (34 day refueling shutdown in 2012)the following ratio was determined

-127/331 = 0.3837.The total estimated C-14 released is 6.29 Ci (2012 value) x 0.3837 = 2.41 Ci.30% of the estimated C-14 released was assumed to be in the form of CO2.The highest estimated C-14 doses at the highest X/Q for ingestion and inhalation receptor (one milewest) were:1.94E-01 mrem (2012 value) x 0.3837 = 7.44E-02 mrem as Child Bone Dose3.88E-02 mrem (2012 value) x 0.3837 = 1.49E-02 mrem as Child Whole BodyPage 13 of 35 3.0 LIQUID EFFLUENTS 3.1 Lower Limits of Detection (LLD) for Liquid Effluents Liquid radioactive effluents are released as both batch releases and continuous releases.

Each batch issampled prior to release and analyzed for gamma emitters and tritium.

A fraction of each sample isretained 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 batch release radio-analyses, as listed in Table 13.1.1-1 of the Kewaunee ODCMare:AnalysisPrincipal Gamma EmittersIodine 131TritiumGross AlphaStrontium 89, 90Iron 55LLD (VCi/ml)1.00 E-061.00 E-061.00 E-055.00 E-075.00 E-081.00 E-06The actual obtained "a priori" LLD values for batch releases are shown below.IsotopeMn-54Fe-59Co-58Co-60Zn-65Mo-99Cs-134Cs-137Ce-141Ce-1441-131H-3Sr-89Sr-90Gross AlphaFe-55Ni-631 st Quarter1.33E-072.22E-071.31E-071.33E-074.42E-089.40E-071.03E-079.5 1E-081.04E-073.09E-079.29E-082.69E-06L.O1E-087.36E-097.84E-096.76E-071.22E-072nd Quarter1.33E-073.92E-081.31E-072.34E-084.42E-086.98E-071.35E-089.5 1E-089.42E-085.43E-079.28E-083.16E-063.48E-086.94E-098.74E-097.77E-071.36E-073rd Quarter1.75E-082.22E-079.73E-082.34E-084.42E-081.23E-071.03E-079.5 1E-081.04E-075.43E-079.28E-083.1OE-069.57E-097.12E-091.13E-087.87E-071.19E-074th Quarter9.53E-083.78E-081.65E-082.05E-074.26E-088.99E-071.18E-071.22E-071.24E-073.54E-077.42E-083.OOE-06NANANANANAAverage a prioriLLD (pCi/ml)9.47E-081.30E-079.40E-089.62E-084.38E-086.65E-078.44E-081.02E-071.07E-074.37E-078.82E-082.99E-061.82E-087.14E-099.29E-097.47E-071.26E-070000000000000000000000000000000000000000000Page 14 of 35 000S000S000S000S00S0SSS0Continuous liquid releases are grab-sampled weekly and analyzed for principal gamma emitters.

Afraction of each weekly sample is retained for a monthly proportional composite which is then analyzedfor 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 KewauneeODCM are:Analysis LLD (gtCi/ml)

Principal Gamma EmittersIodine 131TritiumGross AlphaStrontium 89, 90Iron 555.00 E-071.00 E-061.00 E-055.00 E-075.00 E-081.00 E-06The actual obtained "a priori" LLD values for continuous releases are shown below.IsotopeMn-54Fe-59Co-58Co-60Zn-65Mo-99Cs-134Cs-137Ce- 141Ce- 1441-131H-3Sr-89Sr-90Gross AlphaFe-55Ni-631 st Quarter1.38E-081.80E-081.08E-081.38E-082.94E-089.03E-089.02E-099.94E-091.73E-087.94E-081.01E-082.69E-078.70E-095.69E-094.37E-096.80E-071.17E-072nd Quarter1.52E-082.47E-081.14E-081.1 8E-081.49E-081.05E-079.91 E-099.26E-091.77E-088.38E-088.48E-093.16E-063.71E-087.83E-094.94E-097.91 E-071.15E-073rd Quarter1.28E-081.99E-081.25E-081.55E-082.43E-087.78E-081.22E-081.17E-081.77E-086.76E-081.13E-083.1OE-066.32E-097.48E-071.16E-079.29E-096.50E-094th Quarter4.39E-092.47E-081.20E-081.38E-082.61E-088.24E-089.48E-091.33E-081.68E-082.36E-089.36E-093.OOE-061.08E-086.29E-094.71E-096.76E-071.24E-07Average a prioriLLD (jiCi/ml) 1.1 5E-082.18E-081.17E-081.37E-082.37E-088.89E-081.02E-081.11E-081.74E-086.36E-089.81 E-092.38E-061.57E-081.92E-073.25E-085.39E-079.06E-08Page 15 of 35 3.2 Liquid Batch Release Statistics The following is a summation of all liquid batch releases during 2013.Number of batch releases

..................................

46Total time for all batch releases (min) .............

33,000Maximum time for a batch release (min) ...........

2,020Minimum time for a batch release (min) ............

30Average time for a batch release (min) ..................

7183.3 Liquid Effluent DataThe following Table 3.1 presents a quarterly summation of the total activity released and averageconcentration for all liquid effluents.

It also presents the gross alpha activity

released, volume of wastereleased and volume of dilution water used. Table 3.2 contains the quantity of the individual isotopesreleased to the unrestricted area for batch releases.

Table 3.3 contains the quantity of the individual isotopes released to the unrestricted area for continuous releases.

Table 3.4 presents the doses fromliquid effluents for each quarter and the calculated doses this year from liquid effluents.

Page 16 of 35S0S00SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS 0000SSSS00S00S00SSS0Table 3.1Liquid Effluents

-Summation of all Releases1 st QtrFission and Activation ProductsTotal Release (Ci)Average Concentration (gCi/ml)TritiumTotal Release (Ci)Average Concentration (jICi/ml)

% of Tech. Spec.Limit(3.OE-3 ptCi/ml)Dissolved and Entrained GasesTotal Release (Ci)Average Concentration (jiCi/ml)

% of Tech. Spec.Limit(2.OE-4 gaCi/ml)Gross Alpha ActivityTotal Release (Ci)Volume of Waste ReleasedTotal (liters)Volume of Dilution WaterTotal (liters)9.16E-045.71E-124.62E+012.88E-079.60E-030.OOE+000.OOE+000.OOE+002nd Qtr1.12E-021.0LE-101.85E+021.67E-065.57E-027.67E-056.92E-133.46E-073rd Qtr3.80E-033.47E-1 15.12E+014.68E-071.56E-020.OOE+000.OOE+000.OOE+004th QtrO.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Total1.59E-024.17E-112.82E+027.39E-072.46E-027.67E-052.OOE-131.OOE-070.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+002.49E+07 1.26E+07 6.12E+06 3.39E+06 4.70E+071.60E+ 1I1.I11E+11 I .09E+1 I 2.14E+/-09 3.82E+11I Page 17 of 35 Table 3.2Liquid Effluents

-NuclidesBatch ModeReleased (Ci)I st Qtr2nd Qtr3rd Qtr4th Qtr* TotalFission and Activation ProductsMn-54Fe-55Co-57Co-58Co-60Ni-63Nb-95Ag-I 10mSn-I 17mSb- 124Sb- 125Total ReleaseO.OOE+004.81E-04O.OOE+002.72E-051.58E-053.04E-04O.OOE+003.65E-053.81 E-06O.OOE+004.74E-059.16E-041.77E-042.38E-033.69E-052.87E-043.38E-034.01E-039.62E-055.3 1E-04O.OOE+001.78E-053.19E-041.12E-02O.OOE+002.22E-03O.OOE+001.36E-047.72E-053.64E-04O.OOE+001.60E-04O.OOE+001.19E-047.16E-043.80E-03NANANANANANANANANANANANA1.77E-045.08E-033.69E-054.50E-043.47E-034.68E-039.62E-057.28E-043.81 E-061.37E-041.08E-031.59E-020SSSSSSS000S0000000000S000000SSSSSS0Dissolved and Entrained GasesXe-133Total ReleaseO.OOE+00 7.67E-05O.OOE+00 7.67E-05O.OOE+00O.OOE+00NANA7.67E-057.67E-05TritiumTotal Release4.62E+01 1.85E+02 5.12E+01 NA2.82E+2Gross Alpha ActivityTotal ReleaseO.OOE+00 O.OOE+00 O.OOE+00 NAO.OOE+00*There were no batch releases in the 4th quarter.Page 18 of 35 Table 3.3Liquid Effluents

-Nuclides Released (Ci)Continuous Mode1st Qtr2nd Qtr3rd Qtr4th Qtr TotalFission and Activation ProductsTotal ReleaseO.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Dissolved and Entrained GasesTotal ReleaseO.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00TritiumTotal Release1.51E-02 6.44E-03O.OOE+00 O.OOE+00 2.15E-02SSSSSSSSSSSSSSSSSSSSSSSGross Alpha ActivityTotal ReleaseO.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Page 19 of 35 Table 3.4Dose from Liquid Effluents The dose to a member of the public from total liquid radioactive releases for each quarter was belowthe Kewaunee ODCM limits of 1.5 mrem to the total body and less than or equal to 5 mrem to anyorgan. Additionally, the dose to a member of the public from total liquid radioactive releases for theyear was below the Kewaunee ODCM limits of 3 mrem to the total body and less than or equal to 10mrem to any organ.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 theisotopes released exceed the concentrations specified in Appendix B. The following offsite doses werecalculated using equation 1.7 from the Kewaunee ODCM.1st QtrTotal BodySpecification (mrem)Actual Dose (mrem)% of Specification OrizansSpecification (mrem)BoneActual Dose (mrem)% of Specification LiverActual Dose (mrem)% of Specification ThyroidActual Dose (mrem)% of Specification KidneyActual Dose (mrem)% of Specification 2nd Qtr1.50E+001.49E-039.95E-023rd Qtr1.50E+003.87E-042.58E-024th Qtr1.50E+000.OOE+000.OOE+00Annual3.OOE+002.22E-037.41E-021.50E+003.44E-042.30E-025.OOE+002.17E-044.35E-033.55E-047.11 E-033.36E-046.72E-033.36E-046.72E-03S00S0S000S0000000000000000000000000000S00005.OOE+00 5.OOE+00 5.OOE+00 1.OOE+012.80E-035.60E-021.60E-033.20E-021.35E-032.69E-021.35E-032.71 E-022.83E-04 0.OOE+00 3.30E-035.66E-03 0.OOE+00 3.30E-024.12E-048.24E-030.OOE+000.OOE+002.37E-032.37E-023.72E-04 O.OOE+00 2.05E-037.43E-03 0.OOE+00 2.05E-023.72E-047.43E-030.OOE+000.OOE+002.06E-032.06E-02Page 20 of 35 000000S0S0000S0S00S000Table 3.4 (continued)

Dose from Liquid Effluents 1 st QtrLungActual Dose (mrem)% of Specification GI-LLIActual Dose (mrem)% of Specification 3.39E-046.77E-033.45E-046.90E-032nd Qtr1.36E-032.72E-025.03E-031.01E-013rd Qtr4th QtrAnnual3.84E-04 O.OOE+00 2.08E-037.69E-03 O.OOE+00 2.08E-024.05E-048.1OE-03O.OOE+00O.OOE+005.78E-035.78E-02Page 21 of 35 3.4 Ground Water Monitoring Sample Point Tritium Total Gamma ActivitySample Date pCi/L iRCi/mIAB-70703/26/13 2194 None Detected04/24/13 1149 (1)05/29/13 1038 None Detected07/02/13 1917 None Detected07/25/13 1802 None Detected08/29/13 1219 None Detected09/06/13 1429 None Detected01/04/14 (2) 1204 None DetectedAB-70803/26/13 1181 None Detected07/02/13 1036 None Detected09/06/13 953 None Detected01/04/14 (2) 856 None DetectedAB-70903/26/13 575 None Detected07/03/13 463 None Detected09/11/13 548 None Detected01/10/14 (2) 904 None DetectedAB-71003/26/13 985 None Detected07/03/13 966 None Detected09/06/13 809 None Detected01/04/14 (2) 877 None DetectedAB-71103/25/13 978 None Detected07/03/13 952 None Detected09/06/13 805 None Detected01/04/14 (2) 1060 None DetectedAB-71203/25/13

<241 None Detected07/03/13 251 None Detected09/11/13 554 None Detected01/10/14 (2) 419 None DetectedAB-71503/25/13 624 None Detected07/03/13 1623 None Detected09/11/13 759 None Detected01/04/14 (2) 553 None Detected00000000000000000000000000000000000000000Page 22 of 35 S0SS000SSS000S000S00S00S000Sample Point Tritium Total Gamma ActivitySample Date pCi/L ttCi/mlAB-71703/26/13

<241 None Detected07/03/13

<239 None Detected09/12/13

<280 None Detected01/10/14 (2) <253 None DetectedMW-70103/26/13

<241 None Detected07/03/13

<219 None Detected09/11 / 13 <240 None DetectedMW-70203/26/13

<241 None Detected07/02/13

<219 None Detected09/11/13

<240 None DetectedMW-70304/01/13

<241 None Detected07/02/13

<219 None Detected09/11/13

<240 None DetectedMW-70404/01/13

<241 None Detected07/02/13

<219 None Detected09/11/13

<240 None DetectedMW-70503/26/13

<241 None Detected07/03/13

<219 None Detected09/12/13

<240 None DetectedMW-70603/26/13

<241 None Detected07/03/13

<219 None Detected09/12/13

<240 None Detected(1) The sample at location AB-707 on 4/24/13 was an additional sample for tritium -the sample wasnot analyzed for Total Gamma Activity.

(2) Due to schedule and winter weather conditions wells AB707, AB708, AB709, AB7 10, AB711,AB712, AB715, and AB717 were sampled for 4th quarter in January 2014. Wells MW701, MW702,MW703, MW704, MW705, and MW706 were not sampled for 4th quarter 2013. Condition Report538443 was submitted.

Page 23 of 35 4.0 UNPLANNED or ABNORMAL RELEASES or ABNORMAL DISCHARGES No unplanned or abnormal releases or abnormal discharges were made from the Kewaunee PowerStation during the report period.5.0 METEOROLOGICAL DATASee Appendix A for missing meteorological data and the joint frequency distribution tables for thereport period.6.0 SOLID WASTE DISPOSALTable 6.1 is a summation of solid radioactive waste shipped during 2013. Presented are the types ofwaste, major nuclide composition, disposition of the waste and shipping containers used. Table 6.1 alsocontains the radionuclide content (curies) and percent abundance for each type of waste.6060006060000000000000000000000000000000000Page 24 of 35 0000S0000S00000S0S000000S0STable 6.1Solid Waste and Irradiated Fuel Shipments A. Solid Radioactive Waste Shipped Off-Site for Burial or Disposal1. Type of Waste with Estimate of Major Nuclide Composition Resins, Filters, and Volume Curies ShippedEvaporator BottomsWaste Class f3 m3 CuriesA 1.94E+02 5.49E+00 1.30E+O 1B 1.63E+02 4.62E+00 1.45E+02C O.00E+00 0.OOE+00 0.OOE+00All 3.57E+02 1.01E+01 1.58E+02Estimate of Major Nuclides for Resins, Filters, and Evaporator Bottoms:Class ANuclideH-3C-14Mn-54Fe-55Co-57Co-58Co-60Ni-59Ni-63Sr-90Nb-95Ag-li0mSb-125Cs-137Ce-144Pu-238Pu-239Pu-241Nuclide% Abundance 0.0200.0692.4208.1500.3403.11813.2530.78971.0130.0030.0240.0120.5580.1590.0680.0000.0000.004% Abundance 0.0200.0480.879Curies2.56E-038.94E-033.14E-011.06E+004.42E-024.05E-011.72E+001.02E-019.22E+004.15E-043.15E-031.61E-037.25E-022.06E-028.81E-035.96E-061.97E-064.76E-04Curies2.89E-026.96E-021.28E+00Class BH-3C-14Mn-54Page 25 of 35 000Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments Fe-55 5.942 8.62E+00Co-57 0.457 6.63E-01Co-58 6.442 9.35E+00Co-60 7.737 1.12E+O1Ni-59 0.635 9.21E-01Ni-63 77.073 1.12E+02Zn-65 0.080 1.16E-01Sr-89 0.001 9.06E-04Sr-90 0.004 5.29E-03Sb-125 0.406 5.89E-01Cs-137 0.208 3.02E-01Ce-144 0.063 9.14E-02Pu-238 0.000 2.67E-05Pu-239 0.000 1.79E-05Pu-241 0.005 6.82E-03Am-241 0.000 8.73E-06Cm-243 0.000 8.78E-06Class All Nuclide % Abundance CuriesH-3 0.020 3.15E-02C-14 0.050 7.85E-02Mn-54 1.006 1.59E+00Fe-55 6.124 9.68E+00Co-57 0.447 7.07E-01Co-58 6.169 9.75E+00Co-60 8.190 1.29E+01Ni-59 0.647 1.02E+00Ni-63 76.575 1.21E+02Zn-65 0.073 1.16E-01Sr-89 0.001 9.06E-04Sr-90 0.004 5.70E-03Nb-95 0.002 3.15E-03Ag-110m 0.001 1.61E-03Sb-125 0.419 6.62E-01Cs-137 0.204 3.22E-01Ce-144 0.063 1.00E-01Pu-238 0.000 3.26E-05Pu-239 0.000 1.98E-05Pu-241 0.005 7.30E-03Am-241 0.000 8.73E-06Cm-243 0.000 8.78E-0606Page 26 of 3566 000000S00S0000S00S00S0000SS0Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments Dry Active Waste Volume Curies ShippedWaste Class fW3 m3 CuriesA 5.OOE+02 1.42E+01 1.34E-01B 0.OOE+00 0.OOE+00 0.OOE+00C 0.OOE+00 0.OOE+00 O.00E+00All 5.00E+02 1.42E+01 1.34E-01Estimate of Major Nuclides for Dry Active Waste:Class ANuclideH-3Cr-51Mn-54Fe-55Fe-59Co-57Co-58Co-60Ni-63Zn-65Zr-95Nb-95Tc-99Ag-i 1OimSn- 113Sb- 125Cs-137Ce-144Nuclide% Abundance 0.4775.0630.82312.3060.3840.23154.7493.08710.0450.0894.0437.4880.5790.0240.1390.2650.1370.070% Abundance 0.4775.0630.82312.3060.3840.23154.7493.08710.0450.089Curies6.38E-046.76E-031.1OE-031.64E-025.14E-043.08E-047.32E-024.12E-031.34E-021.18E-045.40E-031.00E-027.74E-043.25E-051.86E-043.55E-041.84E-049.34E-05Curies6.38E-046.76E-031.1OE-031.64E-025.14E-043.08E-047.32E-024.12E-031.34E-021.1 8E-04Class AllH-3Cr-51Mn-54Fe-55Fe-59Co-57Co-58Co-60Ni-63Zn-65Page 27 of 35 Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments Zr-95Nb-95Tc-99Ag-1 10mSn- 113Sb- 125Cs-137Ce-1444.0437.4880.5790.0240.1390.2650.1370.0705.40E-031.00E-027.74E-043.25E-051.86E-043.55E-041.84E-049.34E-05Irradiated Components Volume Curies ShippedWaste Class fW3 m3 CuriesA 0.OOE+00 0.OOE+00 0.OOE+00B 0.OOE+00 0.OOE+00 0.OOE+00C 0.OOE+00 0.OOE+00 0.OOE+00All O.OOE+00 0.OOE+00 0.OOE+00Estimate of Major Nuclides for Irradiated Components:

Nuclide % Abundance CuriesNone NA NAOther Waste(DAW-Asbestos)

Volume Curies ShippedWaste Class W3 m3 CuriesA 2.70E+02 7.65E+00 2.89E-04B 0.OOE+00 0.OOE+00 0.OOE+00C 0.OOE+00 0.O0E+00 0.OOE+00All 2.70E+02 7.65E+00 2.89E-0400000000000000000000000000000000000000000000Estimate of Major Nuclides for Other Waste:Class A Nuclide % Abundance H-3 0.448Cr-51 5.629Mn-54 0.785Fe-55 11.610Fe-59 0.403Page 28 of 35Curies1.30E-061.63E-052.27E-063.36E-051.16E-06 00S0000S0S0000S0000S000000000Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments Co-57Co-58Co-60Ni-63Zn-65Zr-95Nb-95Tc-99Ag-ll0mSn- 113Sb-125Cs-137Ce-144Class All NuclideH-3Cr-51Mn-54Fe-55Fe-59Co-57Co-58Co-60Ni-63Zn-65Zr-95Nb-95Tc-99Ag-li0mSn-ill3Sb-125Cs-137Ce- 1440.22155.1732.9059.4270.0854.1038.0610.5430.0230.1370.2500.1290.067% Abundance 0.4485.6290.78511.6100.4030.22155.1732.9059.4270.0854.1038.0610.5430.0230.1370.2500.1290.0676.39E-071.60E-048.40E-062.73E-052.46E-071.1 9E-052.33E-051.57E-066.74E-083.95E-077.24E-073.73E-071.93E-07Curies1.30E-061.63E-052.27E-063.36E-051.16E-066.39E-071.60E-048.40E-062.73E-052.46E-071.19E-052.33E-051.57E-066.74E-083.95E-077.24E-073.73E-071.93E-07Sum of All Low-Level Volume Curies ShippedWaste Volume CuriesShipped Waste Class ft3 m3 CuriesA 9.64E+02 2.73E+01 1.31E+01B 1.63E+02 4.62E+00 1.45E+02C 0.OOE+00 0.OOE+00 0.OOE+00All 1.13E+03 3.19E+01 1.58E+02Page 29 of 35 Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments Estimate of Major Nuclides for All Low-Level Waste:Class ANuclideH-3C-14Cr-51Mn-54Fe-55Fe-59Co-57Co-58Co-60Ni-59Ni-63Zn-65Sr-90Zr-95Nb-95Tc-99Ag- I10mSn-l 13Sb-125Cs-137Ce-144Pu-238Pu-239Pu-241Nuclide% Abundance 0.0240.0680.0522.4048.1920.0040.3393.64513.1490.78170.3910.0010.0030.0410.1000.0060.0130.0010.5550.1590.0680.0000.0000.004% Abundance 0.0200.0480.8795.9420.4576.4427.7370.63577.0730.0800.0010.004Curies3.20E-038.94E-036.78E-033.16E-011.08E+005.15E-044.45E-024.78E-011.73E+001.02E-019.24E+001.19E-044.15E-045.41E-031.32E-027.75E-041.64E-031.86E-047.28E-022.08E-028.91E-035.96E-061.97E-064.76E-04Curies2.89E-026.96E-021.28E+008.62E+006.63E-019.35E+001.12E+019.21 E-011.12E+021.16E-019.06E-045.29E-030000000000000000000000000000000000000000000Class BH-3C-14Mn-54Fe-55Co-57Co-58Co-60Ni-59Ni-63Zn-65Sr-89Sr-90Page 30 of 35 00S00000000000000S00SSS00000S00Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments Class AllSb-125Cs-137Ce-144Pu-238Pu-239Pu-241Am-241Cm-243NuclideH-3C-14Cr-51Mn-54Fe-55Fe-59Co-57Co-58Co-60Ni-59Ni-63Zn-65Sr-89Sr-90Zr-95Nb-95Tc-99Ag-110mSn-l13Sb-125Cs-137Ce-144Pu-238Pu-239Pu-241Am-241Cm-2430.4060.2080.0630.0000.0000.0050.0000.000% Abundance 0.0200.0500.0041.0066.1290.0000.4476.2108.1860.64776.5190.0730.0010.0040.0030.0080.0000.0010.0000.4190.2040.0630.0000.0000.0050.0000.0005.89E-013.02E-019.14E-022.67E-051.79E-056.82E-038.73E-068.78E-06Curies3.2 1E-027.85E-026.78E-031.59E+009.70E+005.15 E-047.08E-019.82E+001.30E+011.02E+001.21E+021.16E-019.06E-045.70E-035.41E-031.32E-027.75E-041.64E-031.86E-046.62E-013.23E-011.OOE-013.26E-051.98E-057.30E-038.73E-068.78E-06Page 31 of 35 Table 6.1 (continued)

Solid Waste and Irradiated Fuel Shipments

2. Solid Waste Disposition Number of Shipments 32Mode of Transportation Hittman Transport Hittman Transport Destination Energy Solutions, LLCStudsvik Processing

Facility, LLCB. Irradiated Fuel Shipments Number of Shipments NoneMode of Transportation NADestination NANo irradiated fuel shipments were made from the Kewaunee Power Station during 2013.Page 32 of 350000000000000000000000000000000000000 00* 7.0 PROGRAM REVISIONS 0In accordance with Technical Specification 5.6.2, the revisions to the Process Control Program, OffsiteDose Calculation Manual, Radiological Environmental Monitoring Program and radioactive waste0 treatment systems are listed below.7.1 Process Control ProgramThere were no revisions made to the Process Control Program.0* 7.2 Offsite Dose Calculation ManualThe Kewaunee Power Station Offsite Dose Calculation Manual (ODCM) was revised twice during this0report period. Appendix B is a copy of the Kewaunee Power Station ODCM Revision 15, June 6,* 2013. Appendix C is a copy of the Kewaunee Power Station ODCM Revision 16, December 5, 2013.* 7.3 Radiological Environmental Monitoring ManualSThe Kewaunee Power Station Radiological Environmental Monitoring Manual (REMM) was revised* during this report period. Appendix D is a copy of the Kewaunee Power Station REMM Revision 20,* October 31, 2013.7.4 Major Changes to the Radioactive Liquid, Gaseous and Solid Waste Treatment SystemsThe following changes were made to the radioactive waste systems (liquid, gaseous or solids):a) System abandonment evaluations were performed using procedure OP-KW-DEC-SYC-001, System Evaluation and Categorization, and documented on Attachment B, SSC Category*Determination Document.

The following is a summary from the applicable Attachment B forthe changes made to the following radioactive waste treatment systems:* 07-Steam Generator Blowdown Treatment System* 18-Reactor Building Ventilation System* 32B-Waste Gaseous System* 35- Chemical and Volume Control SystemS*On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently

cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the0certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR*50.82(a)(10(ii).

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

000S*Page 33 of 35S0 000Steam Generator Blowdown Treatment SystemBeing that the reactor is defueled, and the Reactor Coolant System (RCS) and Secondary Systems are no longer in operation; the Steam Generator Blowdown Treatment System nolonger performs a function or provides support for decommissioning, except as follows:

Onetrain is being maintained available to support draining and processing waste water for systemslocated in the auxiliary building.

Reactor Building Ventilation SystemBeing that the reactor is defueled, and the RCS and associated systems are no longer inoperation; the Reactor Building Ventilation (RBV) System no longer performs prevention ormitigating function or provides support for decommissioning.

Waste Gaseous SystemThe gas decay tanks contain the gases vented from the RCS, the Volume Control Tank (VCT),and the liquid Chemical and Volume Control (CVCS) holdup tanks. Following theabandonment of the RCS and CVCS systems the waste gas decay tanks and associated pipingwere discharged and vented to atmosphere.

No new gases will be produced as the CVCS wasdrained and vented and the reactor vessel has been defueled.

Chemical and Volume Control SystemBeing that the reactor is defueled, and the RCS and associated systems are no longer inoperation; there will be no liquid waste created and no releases from the CVCS.b) Refer to Attachment E, Documentation for Major Changes to Radioactive Waste Treatment Systems in 2013, for information to support the reason for the changes, including a description of the equipment, components, and processes involved and interfaces with other plant systems.c) The changes described in Attachment E either reduced or eliminated the release paths ofradioactive effluents from the specified systems.

The Steam Generator Blowdown Treatment system has been reduced to one train to support draining and processing waste water in theauxiliary building.

There will no longer be any releases of radioactive material or any furtherexposures to individuals in the UNRESTRICTED AREA and to the general population fromthe Reactor Building Ventilation, Waste Gaseous, and Chemical and Volume Control systems.d) There is no exposure expected by plant personnel as a result of the changes to these wastetreatment systems.e) Refer to Attachment E, Documentation for Major Changes to Radioactive Waste Treatment Systems in 2013, for FSRC review and approval documentation of these changes to theradioactive waste treatment systems.00Page 34 of 35000 00* 8.0 REPORTABLE OCCURRENCES S* 8.1 Condition Report 516118, ODCM Channel Checks Not Performed for R-12 and R-21On 5/19/2013 it was discovered that the R-12 and R-21 channel checks required by the ODCM per* DVR 13.3.2.2 were not being performed per procedure SP-87-149, Shift Instrument Channel Checks -* Shutdown.

ODCM Table 13.3.2-1 requires one noble gas activity monitor to be functional when the* containment building 36" ventilation system is in service.

A channel check is required to be performed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to verify the monitor is functional.

This performance check was not performed asrequired placing the monitors in a nonconforming condition.

Upon discovery of the missed0 performance checks, in accordance with DVR 13.0.6.3

-Actions should be taken to restore* conformance with the DNCs / DVRs in a timely fashion, a partial SP-87-149 procedure was performed.

No abnormal conditions were found and conformance was restored to R-12 and R-21.* The plant had been permanently shut down on 5/7/2013 and certified defueled on 5/15/2013.

This* placed the plant in a NO MODE condition.

SP-87-149 lists the plant initial conditions as either MODE* 5 or MODE 6. It was determined that this was the reason why the channel checks were not performed.

A revision to procedure OSP-MI-002, Daily Instrument Channel Checks, was submitted on the day ofdiscovery and was issued on 5/20/2014 to include the required R-12 and R-21 channel checks. This* procedure is not limited to any MODE classification.

8.2 Condition Report 516164, R-15 Condenser Air Ejector Radiation

Monitor, ShutdownBases statement excerpt from the ODCM related to gaseous effluent instrumentation:

"The radioactive gaseous effluent instrumentation, required FUNCTIONAL by this DNC, is providedto monitor and control, as applicable, the releases of radioactive materials in gaseous effluents duringactual or potential releases of gaseous effluents."

The plant had been permanently shut down on 5/7/2013 and certified defueled on 5/15/2013.

The MainSteam system was no longer required, which eliminated the effluent release path to the condensers.

Therefore, R- 15 was no longer required and subsequently shut down'000S0000000*Page 35 of 3500 60000000000000000000000000000000000000000 0S0S* Appendix A00* Kewaunee Power Station0S* 2013 Meteorological Data0Missing Data00 First Quarter:

17.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months sSSecond Quarter:

5.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months s* Third Quarter:

1.50 hour5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months sSFourth Quarter:

47.50 hour5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months sSS*Note: A total of 72.00 hours0 days 0 hours 0 weeks 0 months of data is missing or otherwise

unavailable.

This represents the availability of 99.18% of theSdata for the year.S* is urer 77 or* eodQate:52 orS hr ure:15 or0 orhQatr 75 or00* oe oa f7.0husofdt smsigo tews0 nvial.Ti ersnsth viaiiyo 91%o h* aafr h er0S APPENDIX AKewaunee Power Station 2013 Meteorological DataFirst Ouarter 2013Stability Class AWind SpeedWind Direction NNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-3000000000000000004-77.25312.252.56.25101.252.252.2562.757.59.51218.594.258-12139.7517.536.754087.252.254.7516.7555.539.521.2528.7523813-1821.2515.7510.255.2510.251320.756.50004.252124.757.259.7517009.250030100000.256.50102100000.250.2500000000000.541.537.754010.7526.518.2521.7515.759.54.510.752490.573.7541.557523.7519-24 >24 TOTAL0S00000S00000000000000S0000Stability Class BWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30000000000000.250000.254-71.750.5300.51.2500.751.51.7512.2543.51.51.75258-125.5100.25100015.57.53.251.757.5107868.2513-186.753.251.523.500.50600.250.59.52.2522.2540.2519-24 >24 TOTAL012.7510000.51.250.75000000016.2503.25000000000000003.251420.755.52.2551.251223.759.254.54.521.2515.7510.512153.25Page A2 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological Data0S000000S00000SStability Class CWind Direction CALMN 0NNE 0NE 0ENE 0' E 0ESE 0SE 0SSE 0S 0SSW 0SW 0WSW 0W 0WNW 0.NW 0NNW 0TOTAL 0Stability Class DWind Direction CALMN 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0SW 0WSW 0W 0WNW 0NW 0NNW 0TOTAL 0Wind Speed1-3000000000000.750.2500.7501.754-71.51.251.750.250.50.2500.250.251.25133.52.2533.254.2536.58-1260.521.750.250011.756.53.54.515246.55.578.7513-1816.7551.500.5001000.75263.255.2504219-2405.752.5000102.25000.25010012.75>2401.25000000000000001.25TOTAL24.2513.757.7521.250.2512.254.257.7517.251123.531.2515.759.75173Wind Speed1-31.500011.750.250.750.51.52.252.50.750.51.251.5164-77.252.252.252.750.51.2536.2512.5299.7520.2522.511.7512.2511.75155.258-1228.54.7500.251.251.7525.2510.258.7510.512.252256.52724.75215.7513-1827.55.25001.504.5177.251.7588.7514.25512.7511.512519-240000002.7511.752.75001.252.754.750.25026.25>2400000000000000000TOTAL64.7512.252.2534.254.7512.54133.254130.54562.2578.553.549.5538.25Page A3 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class EWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-300.25000.250.250.750.253.542.52.75210.50.2518.254-75.751.7511112.754.58.2526.519.751211.752218.7516153.758-12100.5000.50.50.254.256.52220.511.2518.2523.51620.25154.2513-182.5000001.2532.250.251.55.59.50.253.53.7533.2519-2400000000.75000.51.750.250.25003.5>2400000000000000000TOTAL18.252.5111.751.75512.7520.552.7544.7533.2541.754738.7540.25363060S00S00000000S000000Stability Class FWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30.2500.2500.50.2500.250.532.753.55.251.51.250.75204-70.7500.250.250.251.252.253.755.2510.516.25121525.517.57.75118.58-120.7500001.254.754.751.51.52.255.2510.7512.255.751.552.2513-1800000020.5000.75000003.2519-24 >24 TOTAL1.7500.50.250.752.7599.257.25152220.753139.2524.510194000Page A4 of A 17 500 000000000000000S0000APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class GWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-31.5100.2500.250.25001.7535.75411.251.521.54-740000000.751.55.515.525.252739.253213.75164.58-1200000000.25000.250.751.507.5010.2513-1800000000000.75000000.7519-2400000000000000000>2400000000000000000TOTAL5.5100.2500.250.2511.57.2519.531.7532.540.2540.7515.25197Page A5 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataSecond Ouarter 2013Stability Class AWind SpeedWind Direction NNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-300000000.25000000000.254-75.759.57.7575.543.52132.753.751.7565.53.7572.58-1212.561.2525.7511.57.2536.58.510.256.52.254.7523.2529.252312.25247.7513-1814.7555.254.2512.751001480.2513.257.255.511.57.2514619-240180.254.50009.252001.752.25000.538.5>2401.750000020.2500000004TOTAL33145.753835.7513.757103621.59.75613.534.540.754023.7550966660660S000o0SS0000oS0S0oooo0ooo0So0000Stability Class BWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-3000000000.2500000000.254-72.7543.251.250.51.2500.51.252.500.250.50.752.751.7523.258-12313.52.51.52.750.250.751.52.2530.511.2572.250.543.513-182.7511.560.52004.53.750.250001.2530.53619-24 >24 TOTAL0.753000000.250.2500.750.2500005.2502.75000000000000002.759.2534.7511.753.255.251.50.756.757.755.751.251.51.75982.75111Page A6 of A17 00000000000000S0000S000APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class CWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-3000.250000.250000000000.54-72.252.7563.56.2510.2510.251.500.250.250.254.51.531.58-125.511.756.51.510.253.50.53.251.250.750.7526.51.25248.2513-1828.50000.5012.7500.500.752.253.50.252219-24050000010.500.5000007>2405.75000000000000005.75TOTAL9.7533.7512.7557.251.7543.56.752.751.751399.253.75115Stability Class DWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30.250.250.753.52110.250.250.2511.250.250.7500.25134-73.7514.2517.2512.54.52.252.533.258.7523.25347.753.2595.258-12739.563.2501.254.25107.7581.7524.259.757.25411613-181.7524.250.250.2500.2533.560.755.750.502.257.751.755819-240100000.752.25000.5000004.5>2400000000000000000TOTAL12.7579.2524.2519.56.54.7511.51917.2517.751177.516.7522.759.25286.75Page A7 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class EWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-31.753.756.255.52.753.251.51.753.52.252.753.50.752.251.752.75464-7113328.75106.7554.7511.51319.756.56.2585.255.757.25182.58-127.532.254.252.750.7501.56.516.25111.751.752.751.7508.259913-180.51700000.752.53.50.252.251.750.250.7510.2530.7519-24 >24 TOTAL00000000.75000000000.750000000000000000020.758639.2518.2510.25,8.258.52336.2533.2513.2513.2511.75108.518.5359Stability Class FWind Direction 00000S00S00000S0000000000000000000000000000Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-31.751.55.753.55.2533.53.753.757.754.53.7521.52.250.7554.254-715.251613.54.2533.254.75152024.757.756.757.757.52.7518.5170.758-126.513.253.250000.2513.2510.54.52.250.503.50.51.756013-1804.25000001.250.7500000.5006.7523.53522.57.758.256.258.533.25353714.5119.75135.521291.7519-24 >24 TOTALPage A8 of A17 00000S000000S00.00APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class GWind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM0.250.250.25000.250000.2500.2500001.51-36.757.756.56.2564.56.254.5912.513.75125.756.25119.251284-75.57166.252.75614.7564.7555.7519.25142013.258.755.256265.258-120.256.757.250011.2532.7539.25110.53.53.250.5199.2513-1804.2500000.254.752.250.250000.25001219-2400000000.25000000000.25>2400000000000000000TOTAL12.75263012.58.7511.7522.5107106.2533.2528.7532.7522.518.516.7516.25506.25Page A9 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataThird Ouarter 2013Stability Class AWind SpeedWind Direction NNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30.50.2501.750.750.51.250.750.2500.2510.7510.750.25104-77.7513.7517.258.5683.514.58.2544.7597.7511.2516.259.7515.5219.758-1210.5395.50.5220.25612.259.755.757.259.58.2513.2513.7511.25174.7513-182.25701.750008.530040.50.2500.2527.500000000000000000000000000000000002160,22.7512.590.754.2521.7529.751710.516.522.2520.7530.7524.2527.2543219-24 >24 TOTAL666666606060S0S00S0000000Stability Class BWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30100.2501.250.2510000000.250.254.254-70.543.75619.251.251.251.750.2511.752.253.2551.751.7554.758-122.55.25008.2500.51.255.7520.5111.751.51.532.7513-180.51.250000020.25000.50.250004.7500.25000000000000000.253.511.753.756.2527.52.5266.2532.253.754.56.753.53.596.7519-24 >24 TOTALPage A10 of A17 Kewaunee PowerSS000S0000000S00APPENDIX AStation 2013 Meteorological DataWind SpeedStability Class CWind Direction NNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30.250.750.2500.752.5110.250.2500000.2507.254-70.7532.254.25537.7531.252.250.750.7512.75.2.751.7542.258-126.255.7501.759.750.751.57.753.750.250.50.7501.2S0.25242.2513-180.25000.251.25001.751.25000.500.25005.519-2400000000000000.25000.25>2400000000000000000TOTAL7.59.52.56.2516.756.2510.2513.56.52.751.25214.53.253.7597.5Stability Class DWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30.50.512.251.252.251.53.251.5I3.253.251.752.50.5127.254-76.7564.752.755.53.51410.756.5113.5435.54.257.599.258-125.511.7500.252.7540.250.75171530.50.75211.54.25106.2513-180.251.500.250.25000.750.5002.251.2500.507.519-2400000000000000000>2400000000000000000TOTAL1319.755.755.59.754616.2531.7523.5157.2510.25896.7512.75240.25Page All of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class EWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-31.751.5222.50.525.75543.51.751.250.751.251.5374-777.254.753.5368.519.2525.533.7511.2566.754.257.2512.5166.58-1225.750.250077.257.7525.521.758.52.755.253.51.50.512.25174.513-1800.250000010.53.750000000.2514.75000000000.7500000000.750000000000000000010.7514.7575.55.583.7518.256156.7546.2517.51311.56.5926.5393.519-24 >24 TOTAL00000000000000000000000000000000000000Stability Class FWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-32.51.521.51.50.51.52911.54.552.521.53524-76.51.254.7561.250.752.251026258.75117.2510.54.758.25134.258-120.2500000101.254.590.750.53.750.75002.2512313-1800000006.25200000008.2500000000000000000000000000000000009.252.756.757.52.751.2510522.754637.2513.7519.7510.512.56.2513.5317.519-24 >24 TOTALPage A12 of A17 0000000S000000000000APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class GWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM00.2500.250.50.250000000.2500.250.52.251-310.752.51.251.250.753.55.57.2512.7513.752149281513.517202.754-730.750.25001.25530.254625.2527.2532.548.2533.523.2517293.58-1200000013.259616.750.250.2500000126.513-1800000003.250.750000000419-2400000000000000000>2400000000000000000TOTAL13.753.51.51.51.25523.75136.7576.2539.2548.581.576.548.53734.5629Page A13 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataFourth Ouarter 2013Stability Class AWind SpeedWind Direction NNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-300.250.2500.751.50000.250.250.50.50.751.2506.254-78.752.522624.252.756.251313.2517.7521.598.7516135.758-1233.758.755.50.75710.753.257165.751115.551.543.51721.5258.513-188.2513.758.256.510.254.50610.25013.54.522.259.751316146.7519-24 >24 TOTAL06.250000013.2580200.2510030.7500000000.5000000000.550.7531.5169.252418.757.529.540.5194038.2596644053.5578.5006060S00S000SS00S0SSSSSS0S0SStability Class BWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30000.250.750.25000000000.250.251.754-70.7500.250120.25011.256.2510.2583.2536.543.758-124.251.750.50.25020057.75510.516.75163779.7513-1831001.25000.250.25123.753.520.754.252319-24 >24 TOTAL00.7500000110003.500.2506.50000000000000000083.50.750.534.250.251.257.251013.2524.531.7521.257.2518154.75Page A14 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological Data000000000000S00000000Stability Class CWind Direction CALMN 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0SW 0WSW 0W 0WNW 0NW 0NNW 0TOTAL 0Stability Class DWind Direction CALMN 0NNE 0NE 0ENE 0E 0ESE 0SE 0SSE 0S 0SSW 0SW 0WSW 0W 0WNW 0NW 0NNW 0TOTAL 0Wind Speed1-300000.50.250000.50.251.750.750.50.7516.254-70.250.250.500.252.750.50.750.7543.56.57.254.254.54408-1261.7500.750.250.751.250.752.2531.55.58.25124.258.556.7513-182.250.750000.2500.52.7504.252.754.51.250.53.523.2519-2400.250000.2500.7500000.50001.75>2400000000000000000TOTAL8.530.50.7514.251.752.755.757.59.516.521.25181017128Wind Speed1-30.250.25000.251.2500001.251.751.751.751.50.510.54-73.750.50.752.7553.53.252.5413.758.7514.251827.512.515.5136.258-121.58.750.54.753.2542.57.59.5174.251038.7525.2512.523.25173.2513-1864.251.25001.56.25612.251.254.252135.2541077.2519-2401.50000.251.251.5700.51.25000013.25>2400.5000000.51.500000002.5TOTAL11.515.752.57.58.510.513.251834.25321929.2571.559.7530.549.25413Page A15 of A17 APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class EWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-30.7510.750.510.750.751.50.25024.54.53.52.251.7525.754-76.51.2501.7530.75211.7511.2523.515.7522.533.2529.257.256.251768-122.753.500.253.750.51.510.2515.257.2515.7522.2522.7521.589.7514513-1825.5000000.51.7505.754.7533.250329.519-24 >24 TOTAL01.5000000000000001.5000000000000000001212.750.752.57.7524.252428.530.7539.255463.557.517.520.75377.75Stability Class FWind Direction 000000000000000000000000000000000000000000Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-33.252.751.52.25111.50.750.7521.7541.2517.75537.54-74.751.753.250.50.753.751.2558.5188.518.521.752113.2512.51438-1201.500.51.251.751.2511.254.50.250.55.57.7511.252.756.556.513-1801.250000001.2500000002.519-24 >24 TOTAL000000000000000000000000000000000087.254.753.2536.54171520.2510.752830.7533.2523.7524239.5Page A16 of A17 00000000S0000000000APPENDIX AKewaunee Power Station 2013 Meteorological DataStability Class GWind Direction Wind SpeedNNNENEENEEESESESSESSSWSWWSWWWNWNWNNWTOTALCALM000000000000000001-353.531.251.521.2534.56.25410.56.754.253.75565.54-76.750.7541.750.752.51.58.75109.751050.533.532.7511.753.75188.758-120000.250.750.750.52.250.250000.50.58.250.7514.7513-180000000000000000019-2400000000000000000>2400000000000000000TOTAL11.754.2573.2535.253.251414.7516146140.7537.523.759.5269Page A17 of A17 000000000000000000000This page intentionally left blank0000000000000000000000 0000000000000* Appendix B0* Kewaunee Power Station0O* Offsite Dose Calculation 0 aul(DM* aul(DM0* Revision 150 June 6, 20130000000000000000 000000000000000000000This page intentionally left blank 00000000000000000000000 0000000000000000S000000o0000SDominion Energy Kewaunee, Inc.Kewaunee Power StationOFFSITE DOSE CALCUMANUAL (OD115ApprovedApproved By:Reviewed By:Approved By:I James M. Hale-Radiological Protection and Chemistry 06-04-2013 DateRichard P. RepshasManager -Regulatory AffairsJeffrey T. StaffordFacility Safety Review Committee A. J. JordanSite Vice President 06-04-2013 Date06-04-2013 Date06-06-2013 Date KEWAUNEE POWER STATION ODCM TOC WOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 201300TABLE OF CONTENTS PAGE0PART I -RADIOLOGICAL EFFLUENT CONTROLS NORMAL CONDITIONS AND BASES

11.0 INTRODUCTION

11.0-112.0 (Not Used)S13.0 USE AND APPLICATION 13.0.1 Definitions 13.0.1-113.0.2 Logical Connectors 13.0.2-113.0.3 Restoration Times 13.0.3-113.0.4 Frequency 13.0.4-113.0.5 ODCM Normal Condition (DNC) Applicability 13.0.5-113.0.6 ODCM Verification Requirement (DVR) 13.0.6-113.1 RADIOACTIVE LIQUID EFFLUENTS5 13.1.1 Liquid Effluents Concentration 13.1.1-113.1.2 Liquid Effluents Dose 13.1.2-113.1.3 Liquid Radwaste Treatme 13.1.3-113.1.4 Liquid Holdup Tanks 13.1.4-1-013.2 RADIOACTIVE GAS S F NTS13.2.1 Gaseous Eff! 13.2.1-1 513.2.2 Gaseous E s oble Gas 13.2.2-113.2.3 Gaseou Dose- Iodine and Particulate 13.2.3-113.2.4 Gaseous Treatment System 13.2.4-1 013.2.5 GGas rage nks 13.2.5-113.3 IN R ION13.3.1 R tive Liquid Effluent Monitoring Instrumentation 13.3.1-113.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-113.4 RADIOACTIVE EFFLUENTS TOTAL DOSE013.4.1 Radioactive Effluents Total Dose 13.4.1-10 000000000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM TOCRevision 15June 6, 201313.513.5.113.5.213.5.314.014.115.0RADIOLOGICAL ENVIRONMENTAL MONITORING PAGE13.5.1-113.5.2-113.5.3-1Monitoring ProgramLand Use CensusInterlaboratory Comparison ProgramDESIGN FEATURES000000000000000000000000000Gaseous and Liquid Effluent Release PointsADMINISTRATIVE CONTROLSMajor Changes to Radwaste Treatment SystemsRadioactive Effluent Release ReportSpecial Reports <<14.1-115.1-115.2-115.3-115.115.215.3iii 00KEWAUNEE POWER STATION ODCM TOC 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20130PART II CALCULATIONAL METHODOLOGIES PAGE1.0 LIQUID EFFLUENT METHODOLOGY 1.1 Radiation Monitoring Instrumentation and Controls 1.0-11.2 Liquid Effluent Monitor Setpoint Determination 1.0-11.3 Liquid Effluent Concentration Limits -10CFR 20 1.0-41.4 Liquid Effluent Dose Calculation

-10 CFR 50 1.0-51.5 Liquid Effluent Dose Projections 1.0-7 01.6 Onsite Disposal of Low-Level Radioactively Contaminated e ams 1.0-82.0 GASEOUS EFFLUENT METHODOLOGIES,

-2.1 Radiation Monitoring Instrumentation and Controls 2.0-12.2 Gaseous Effluent Monitor Setpoint Determinati 2.0-32.3 Gaseous Effluent Instantaneous Dose Rate culatio -"0 CFR 20 2.0-52.4 Gaseous Effluent Dose Calculations

-1 MytR 2.0-72.5 Gaseous Effluent Dose Projection 2.0-102.6 Environmental Radiation Protection R 190 2.0-112.7 Incineration of Radioactively Conpa 2.0-112.8 Total Dose 2.0-11 0APPENDICES Appendix A Technical Basis fofe e e Factors -Liquid Radioactive Effluents

....... A-1Table A-1 ACo butions Fish and Drinking Water Pathways

..... A-5Table A-2 u i Total Body Dose Assessment

.............................

A-6 0Appendix B Technica r Effective Dose Factors -Gaseous Radioactive Effluents

.. B-1Tabl B-1 e e Dose Factors -Noble Gases ........................................

B-5 0Appendix C a onservative, Default Effective EC Value for Liquid Effluents

....C-11 alculation of Effective EC (ECe) ...........................................

C-4Appendix D 0 isposal of Low-Level Radioactively Contaminated Waste Streams ..... D-100SS0S0S'V0S0S S0* KEWAUNEE POWER STATION ODCM TOCOFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 20130LIST OF TABLES PAGE0l PART I -RADIOLOGICAL EFFLUENT CONTROLS13.1.1-1 Radioactive Liquid Waste Sampling and Analysis 13.1.1-313.2.1-1 Radioactive Gaseous Waste Sampling and Analysis 13.2.1-313.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-513.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-5*PART II CALCULATIONAL METHODOLOGIES "12STREAEINETODOECMI1.1 PARAMETERS FOR LIQUID ALARM SETPOIN IONS 1.0-11~1.2 SITE RELATED INGESTION DOSE COMMI -IIT FA," \ ORS 1.0-121.3 BIOACCUMULATION FACTORS 1.0-14* 2.1 DOSE FACTORS FOR NOBLE GA 2.0-152.2 PARAMETERS FOR GASEOUS NT DETERMINATIONS 2.0-162.3 CONTROLLING LOCATION AND ATMOSPHERIC DISPERSION FOR DOSE L S 2.0-172.4 R1 INHALATION Y FACTORS-ADULT 2.0-182.5 R1 INHALATION PA D D FACTORS-TEEN 2.0-20* 2.6 R1 INHALATIO

-SE FACTORS-CHILD 2.0-222.7 Ra INHALA _W AY DOSE FACTORS-INFANT 2.0-24* 2.8 R VEGETA, HWAY DOSE FACTORS-ADULT 2.0-26*2.9 R1 VE TIO )PATHWAY DOSE FACTORS-TEEN 2.0-28O 2.10 PATHWAY DOSE FACTORS-CHILD 2.0-302.11 AS COW-MILK PATHWAY DOSE FACTORS-ADULT 2.0-322.12 Ri G S-COW-MILK PATHWAY DOSE FACTORS-TEEN 2.0-342.13 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-CHILD 2.0-36* 2.14 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-INFANT 2.0-382.15 Ri GROUND PLANE PATHWAY DOSE FACTORS 2.0-4000000e KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM TOCRevision 15June 6, 20130000LIST OF FIGURESPART I -RADIOLOGICAL EFFLUENT CONTROLSPAGE14.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTPART II CALCULATIONAL METHODOLOGIES 14.1-2123LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAMGASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRSIMPLIFIED HEATING BOILER FUEL OIL PIPIKO;Sý 1.0-102.0-132.0-140000000000000000000000000000000vi 00000000000000000000000000000000000000'0Kewaunee Power StationOffsite Dose Calculation Manual KEWAUNEE POWER STATION ODCM 11.0 VOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013

11.0 INTRODUCTION

The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established andmaintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of twoparts: Radiological Effluent

Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent

Controls, includes:

(1) The Radioactive Effluent ControlSpecifications (RECS) and Radiological Environmental Monitoring Programs (REMP) requiredby Technical Specification 5.5.1 and (2) descriptions of the information that should be includedin the Annual Radiological Environmental Operating and Radioactive Effluent Release Reportsrequired by Technical Specifications 5.6.1 and 5.6.2 respectively.

Part II, Calculational Methodologies:

provides the methodology to man h ula radiation dose rates and doses to individual persons in UNRESTRICTED ARI t -outinerelease of gaseous and liquid effluents.

Long term cumulative effe su I.calculated through computer programs employing approved methodologyg

-timemeteorology in the case of gaseous effluents.

Other compu rog utilized to routinely estimate the doses due to radioactivity in liquid effluents.

I calculations areperformed when computerized calculations are not ava e.The methodology stated in this manual is acce se emonstrating compliance with1OCFR20.1302;

10CFR50, Appendix I; and 40 1More conservative calculational method /"r, ions (e.g., location and/or exposurepathways) expected to yield higher co ed an appropriate for the maximally exposedperson may be assumed in the dose a .The ODCM will be maintained a ion use as a reference guide and training documentof accepted methodologies ti .Changes will be made to the ODCM calculational methodologies and para rns is ed necessary to assure reasonable conservatism inkeeping with the p nc ,1'Oe CFR50.36a and Appendix I for demonstrating radioactive effluents are ALARA. \11.1 Change Pr s> 0Instructions f the responsibilities and requirements for revision and control of both theODCM and th e D) .OGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) arelocated in approv d-_ation procedure for Revision and Control of the REMM and ODCM.0000006611.0- 1 0660 W KEWAUNEE POWER STATION ODCM 13.0.1* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013S13.0 USE AND APPLICATION 13.0.1 Definitions S----------

NOTE --.-..--.-.----.-.-.-.-...-----.--------------

*Terms defined in both Kewaunee Technical Specifications and the OFFSITE DOSE*CALCULATION MANUAL appear in capitalized type and are applicable throughout theRadiological Effluent Controls Normal Conditions and Bases and the Calculational

Methodologies.

------------

---- -----------------------

Term Definition ACTION Action shall be that part of a Normal Conditi h Q ibesremedial measures required under design itiCHANNEL CHECK CHANNEL CHECK is a qualita 'e ion of acceptable FUNCTIONALITY by observa; I f c! nnel behavior duringoperation.

This determinat' where possible, comparison of the channel ic n other indications derivedfrom independent ch rin e same variable.

CHANNEL* FUNCTIONAL TEST A CHANNEL FUNCT_ consists of injecting a simulated signal into the ch the primary sensor as practicable toCANLverify that it i including alarm and/or trip initiating el ~ CHANNEL action. CALIBRATION CHANN IB ION consists of the adjustment of channelo O such that it responds with acceptable range andaq ac k h values of the parameter that the channel monitors.shall encompass the entire channel, including alarm and/ortE* shall be deemed to include the CHANNEL FUNCTIONAL

) FUNCTIONAL/

FUNCTIONA fined in the Technical Requirements Manual* GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM is any systemRADWASTE designed and installed to reduce radioactive gaseous effluents byTREATMENT collecting off-gases from the primary system and providing for delay orSYSTEM holdup for the purpose of reducing the total radioactivity released tothe environment.

MEMBER(S)

OF THE MEMBER(S)

OF THE PUBLIC means any individual except when that* PUBLIC individual is receiving an OCCUPATIONAL DOSE.1SSS*13.0.1 -1SSS KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.1Revision 15June 6, 2013OCCUPATIONAL DOSEOFFSITE DOSECALCULATION MANUALODCM NORMALCONDITIONS (DNC)OCCUPATIONAL DOSE means the dose received by an individual inthe course of employment in which the individual's assigned dutiesinvolve exposure to radiation or to radioactive material from licensedand unlicensed sources of radiation, whether in the possession of thelicensee or other person. OCCUPATIONAL DOSE does not includedoses received from background radiation, from any medicaladministration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75,from voluntary participation in medical research

programs, or as aMEMBER OF THE PUBLIC.The OFFSITE DOSE CALCULATION MANUAL shall tain thecurrent methodology and parameters used in the of offsitedoses due to radioactive gaseous and liquid effl in thcalculation of gaseous and liquid effluent mo ing\ ,lprr psetpoints, in the conduct of the Radiologic nv' m~al Monitoring Program.

Shall also contain the Radioactiv enlgontrols andRadiological Environmental Operatin

.e EffluentRelease Reports required by TS 5. and ...Specify minimum requirement e s'b ,dfe operation of thefacility.

The Contingency Me re soclfed with a DNC stateNonconformances that ty lyecrSehe ways in which therequirements of the DN ca Specified with eachstated Nonconforma o ngency Measures and Restoration Time(s).Verification r requirements relating to test, calibration, or inspecti o as e that the necessary FUNCTIONALITY ofsystems ýd po ts are maintained, that facility operation will bemaint in current licensing basis, and that the ODCMNo n in NC) for operation will be met.CESS CONTROL PROGRAM shall contain the currentsampling,

analyses, tests, and determinations to be made toensl t at the processing and packaging of solid radioactive wastes,as on demonstrated processing of actual or simulated wet solides, 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 andState regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste.Licensee initiated changes to the PCP, which was approved by theCommission prior to implementation:

1. Shall be documented and records of reviews performed shall beretained as required by the quality assurance program.

Thedocumentation shall contain:a. Sufficient information to support the change together with theappropriate analyses or evaluations justifying the change(s).

b. A determination that the change will maintain the overallconformance of the solidified waste product to existingrequirements of Federal, State, or other applicable regulations.

2. Shall become effective upon review and acceptance by the FSRC.00000S00000000000000000000000000000000000060ODCMVERIFICATION REQUIREMENTS (DVR)PROCESSCONTROLPROGRAM13.0.1-2 U KEWAUNEE POWER STATION ODCM 13.0.1O OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013O PUBLIC DOSE PUBLIC DOSE means the dose received by a MEMBER OF THEPUBLIC from exposure to radiation or to radioactive material releasedby a licensee, or to any other source of radiation under the control of aO licensee.

PUBLIC DOSE does not include OCCUPATIONAL DOSE orO doses received from background radiation, from any medicaladministration the individual has received, from exposure to individuals O administered radioactive material and released under 10 CFR 35.75,O or from voluntary participation in medical research programs.

PURGE -PURGING PURGE or PURGING is the controlled process of discharging air orgas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating condition, in such r thatreplacement air or gas is required to purify the co i eme .RADIOLOGICAL The REMM shall contain the current method y d .._, leters usedENVIRONMENTAL in the conduct of the radiological environme to program.O MONITORING MANUAL (REMM) <e b tldO SITE BOUNDARY The SITE BOUNDARY shall b t I* which the land isneither owned, leased, nor otl o ed by the licensee.

O SOURCE CHECK A SOURCE CHECK sh e tive assessment of channelresponse when the cha n r is exposed to a source of increased radioactivity.

UNRESTRICTED An UNRES C AR shall be any area at or beyond the SITEAREA BOUND, ee which is not controlled by the licensee forpurpos2es ec of individuals from exposure to radiation andradi .s, or any area within the SITE BOUNDARY usedfo si tal rters or for industrial, commercial, institutional, creational purposes.

(See Plant Drawing A-408)VENTILATION T INEXHAUST TREATMENT SYSTEM is any systemO EXHAUST e'N ed and installed to reduce gaseous radioiodine or radioactive O TREATMENT r'ial in particulate form in effluents by passing ventilation or vent* SYSTEM )) exhaust gases through charcoal and/or HEPA filters for the purpose ofremoving iodines or particulates from the gaseous exhaust streamprior to the release to the environment.

Such a system is notconsidered to have any effect on noble gas effluents.

Engineered Safety Feature atmospheric cleanup systems (i.e., Auxiliary Buildingspecial ventilation, Shield Building ventilation, spent fuel poolventilation) are not considered to be VENTILATION EXHAUSTTREATMENT SYSTEM components.

VENTING VENTING is the controlled process of discharging air or gas from aconfinement to maintain temperature,

pressure, humidity, O concentration or other operating condition, in such a manner thatO 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 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.2Revision 15June 6, 20130000013.0 USE AND APPLICATION 13.0.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and areapplicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.0S00000000000000000000000000000000013.0.2-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.3Revision 15June 6, 201313.0 USE AND APPLICATION 13.0.3 Restoration TimesRestoration Times are the same as Completion Times as discussed in Section 1.3 of theTechnical Specifications and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.0SS0SSSSSSSSSSSSSSSSSSSSSSSSSSSSSWhen "Immediately" is used as a Restoration Time, the Contingency Measure should bepursued without delay in a controlled manner.13.0.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.4Revision 15June 6, 201313.0 USE AND APPLICATION 13.0.4 Frequency Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases000000000000000000000000000000000000000S013.0.4-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.5Revision 15June 6, 201313.0 USE AND APPLICATION 13.0.5 ODCM Normal Condition (DNC) Applicability 000S000000SS000000000DNC 13.0.5.1 DNCs shall be met during the specified conditions in the Applicability.

DNC 13.0.5.2 Upon discovery of a failure to meet the DNC, the Contingency Measures of theassociated 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 r" n time (oran associated contingency measure is not provided),

the e men bject tothe DNC is in a nonconforming condition.

In this situati2V, a pri actionsshall be taken as necessary to provide assurance of in lantoperations.

In addition a Condition Report shall be i an sessment ofreasonable assurance of safety shall be conduc t consid forthis assessment include the following:

Availability of redundant or backup e* Compensatory

measures, includina istrative controls;

" Safety function and events pr d I" Probability of needing the sa and" Conservatism and marIf this assessment c ud at sa ety is sufficiently

assured, the facility maycontinue to operat il roi'i corrective action is taken.DNC 13.0.5.4 Equipment r ice or declared nonfunctional to comply withContingen e res y be returned to service under administrative controlsolely to required to demonstrate its FUNCTIONALITY or theFUN QTIO f other equipment.

This is an exception to DNC 13.0.5.2 forthe e to service under administrative control to perform the testingir onstrate FUNCTIONALITY.

I13.0.5-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.6Revision 15June 6, 201313.0 USE AND APPLICATION 13.0.6 ODCM VERIFICATION REQUIREMENTS (DVR) Applicability DVR 13.0.6.1DVR 13.0.6.2DVR 13.0.6.3DVRs shall be met during the specified conditions in the Applicability forindividual DNCs, unless otherwise stated in the DVR. Failure to meet a DVR,whether such failure is experienced during the performance of the DVR orbetween performances of the DVR, shall be failure to meet the DNC. Failure toperform a DVR within the specified Frequency shall be failure to meet theDNC except as provided in DVR 13.0.6.3.

DVR's do not have to be performed on nonfunctional equipment or variables outside specified IiEach Verification Requirement shall be performed withi Pee cifie) timeinterval with a maximum allowable extension not to e ed 5 , e specified DVR frequency.

When it is discovered that a DVR frequency din, 5 times extension) has not been met, the equipment subject t94 i i a nonconforming condition.

In this situation, a Condition rt sitiated and, if indicated, determination to evaluate the impact afeh all be performed in atimely fashion and in accordance

,ro res.Actions should be taken to resto' nce with the DNCs / DVRs in atimely fashion.

/-I0000000000000000000000000000000000000000000013.0.6-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration ODCM 13.1.1Revision 15June 6, 2013DNC 13.1.1The concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS (Figure 14.1-1) shall be limited to:a. 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table2, Column 2 for radionuclides other than dissolved or entrained noble gases;andb. 2 x 104 pCi/mI total activity concentration for dissolved or entrained noblegases.APPLICABILITY:

During release via the monitored pathway.ACTIONS6 9/>00000S00S00SiNON-CONFORMANCE CONTINGENCY METIONA. Concentration ofradioactive materialreleased in liquid effluents to UNRESTRICTED AREAS exceeds limits.Immediately B. CONTINGEN MEASURESORRESTORATI, not met.eaCRIn accordance with Corrective Action ProgramANDB.2 Explain in the next Radioactive Effluent Release Report whythe CONTINGENCY MEASURE was not met in atimely manner.In accordance with Radioactive Effluent ReleaseReport(__________________________________

1 ______________________________________

.1 ____________________

13.1.1 -1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.1Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY

+DVR 13.1.1.1Perform radioactive liquid waste sampling and activityanalysis.

In accordance withTable 13.1.1-1---- ----- -----.-..-.-.-

..----------

NOTE --.......-----------

-In this DVR the results of DVR 13.1.1.1 shall be used in accord;with the methodology and parameters of the ODCM.ance with1.1-1DVR 13.1.1.2Verify the results of the DVR 13.1.1.1assure that the concentrations at the Iare maintained within the limits of DOI0000000000000000000000000000000000000000000013.1.1-2 00000000S0000000000S0SS000S0KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.1Revision 15June 6, 2013Table 13.1.1-1 (Page 1 of 2)Radioactive Liquid Waste Sampling and AnalysisLIQUID RELEASETYPE1. Batch Waste ReleaseTanks (b)2. Continuous Releases (e)(SG Blowdown)

(TB Sump)TYPE OFACTIVITYANALYSISMINIMUMSAMPLE ANALYSISFREQUENCY FREQUENCY LOWER LIMIT OFDETECTION (LLD)(a)SAMPLE TYPEa. Principal GammaEmitters(c)

b. 1-131Dissolved andc. Entrained Gases(gamma emitters)

d. H-3e. Gross Alphaf. Sr-89g. Sr-90h. Fe-55Grab Sample Each Batch (g)Grab Sample Each Batch (g)Grab Sample Each Batclh,(qg Composite (d)Composite (d)31 days31 days92 days92 days92 daysh Batch (g)Each Batch (g)1 x 10-6 ICi/ml1 x 10-4 ACi/ml1 x 10-5 PCi/mI1 x 105 PCi/mI5 x 10:7 liCilml5 x 10.8 gCi/ml5 x 10.8 AiCi/ml1 x 106 AICi/ml5 x 10U jiCi/ml1 x 108 i+/-Ci/ml1 x 10" pCi/ml1 x 107 , Cic/ml5 x 10-7 gCi/ml5 x 10e liCi/ml5 x 108 AiCi/mlI x 10-6 ACi/mla.Grab Sample7 days7 daysGrab Sample7 days7 days'-NDbsoted andtrained Gases Grab Sample 7 days 7 daysmma emitters)

.d. H-3 Grab Sample 7 days 31 days(f)e. Gross Alpha Composite (f) 7 days 31 days(f)f. Sr-89 Composite (f) 7 days 92 days(f)g. Sr-90 Composite (f) 7 days 92 days(f)h. Fe-55 Composite (f) 7 days 92 days(f)13.1.1-3 0KEWAUNEE POWER STATION ODCM 13.1.1 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Table 13.1.1-1 (Page 2 of 2)Radioactive Liquid Waste Sampling and Analysis(a) The LLD is defined, for purposes of these DNC's, as the smallest concentration of radioactive material in a sample that Swill yield a net count, above system background, that will be detected with 95% probability with only 5% probability offalsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

4.66

SbLLD = E*V*2.22 x 106*Y* exp(-&AA0 Where:* LLD is the a Prori lower limit of detection as defined above, as RCi per uni ss v0 Sb is the standard deviation of the background counting rate or of the cou f a nk sample as appropriate, as counts per minute,* E is the counting efficiency, as counts per disintegration, 0 V is the sample size in units of mass or volume,* 2.22 x 106 is the number of disintegrations per minute per curi* Y is the fractional radiochemical yield, when applicable,

.is the radioactive decay constant for the particular 0 a* Typical values of E, V, Y and At should be used i : iod.It should be recognized that the LLD is defin sa r. ore the fact) limit representing the capability of ameasurement system and not as an a ot' ()limit for a particular measurement..0 (b) A batch release is the discharge of discrete volume. Prior to sampling for analyses, each batch shall beisolated, and then thoroughly mixedo<ass frepr ntative sampling.

(c) The principal gamma emitters h L.l6 quirement

applies, includes the following radionuclides:

Mn-54, Fe-59,Co-58, Co-60, Zn-65, Mo-9 , S-13 Cs- Ce-141, and Ce-144. This list does not mean that only these nuclides areto be considered.

Other 9s that are identified, together with those of the above nuclides, shall also beanalyzed and reported i active Effluent Release Report pursuant to DNC 15.2.(d) A composite samp one in icle quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the me of sa ling employed results in a specimen that is representative of the liquids released.

(e) A continuou lea .charge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that hasan input fiov release.(f) As a minimum, t thly and quarterly composite samples shall be compromised of weekly grab samples.(g) Complete prior to each release.0000000013.1.1 -4 01000 0* KEWAUNEE POWER STATION ODCM 13.1.1OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013*BASES0This 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 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the*1 levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures

within (1) the Section II.A design objectives of Appendix 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 fordissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling 0radioisotope 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 wa pies re tabulated interms of the lower limits of detection (LLDs). Detailed discussion of er detection limits* can be found in HASL Procedures Manual, HASL-300 (revised an y, urre, .A., "Limits forQualitative Detection and Quantitative Determination

-Applicati io istry," Anal. Chem. 40,586-93 (1968), and Hartwell, J.K., "Detection Limits for Radi alyting Techniques,"

Atlantic* Richfield Hanford Company Report ARH-SA-215 (June 19000* K000-000;00000*13.1.1 -5000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.2Revision 15June 6, 201300000013.1.2DNC 13.1.2Liquid Effluents DoseThe dose or dose commitment to a MEMBER OF THE PUBLIC fromradioactive materials released in liquid effluents released toUNRESTRICTED AREAS shall be limited to:a. < 1.5 mrem to the total body and < 5 mrem to any organ during anycalendar quarter; andb. < 3 mrem to the total body and < 10 mrem to any organ during anycalendar year.APPLICABILITY:

At all times.ACTIONSCalculated dose to aMEMBER OF THEPUBLIC from the releaseof radioactive materials inliquid effluents toUNRESTRICTED AREASexceeds limits.00000000000000000000000000000000013.1.2- 1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.2Revision 15June 6, 201300000000S0000SS0000S0000000ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Calculated dose to aMEMBER OF THEPUBLIC from the releaseof radioactive materials inliquid effluents exceeds 2times the limits.B.1 Calculate the annual dose toa MEMBER OF THEPUBLIC which includescontributions from directradiation from the facility(including outside storagetanks, etc.).Immediately ANDB.2 Verify that the limits of DN13.4 have not beenexceeded.

C. CONTINGENCY MEASURE B.2 andAssociated RESTORATION TIME notmet.30 daysC90 N,01 5. 3,ý'~sefefi nedr. (a)(4), ofMEASUREdclude thee rrective action(s) be taken to prevent"/ currence of exceeding the limits of DNC 13.4and the schedule forachieving conformance, (2) An analysis thatestimates the dose to aMEMBER OF THEPUBLIC from uraniumfuel cycle sources,including all effluentpathways and directradiation, for thecalendar year thatincludes the release(s),

and(3) Describes the levels ofradiation andconcentrations ofradioactive materialinvolved and the causeof the exposure levels orconcentrations.

13.1.2-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.2Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION DVR 13.1.2.1 Determine cumulative dose contributions from liquideffluents for the current calendar quarter and thecurrent calendar year in accordance with themethodology and parameters in the ODCM.31 days00000000000000000000000000000000000000013.1.2-3 KEWAUNEE POWER STATION ODCM 13.1.2* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013* 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. TheACTION 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 therequirements in Section III.A of Appendix I that conformance with the guides of Appendix I be0shown by calculational procedures based on models and data, such that the actual exposure of*l 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 I re se rates ofradioactive materials in liquid effluents are consistent with the meth og in* Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Ies ofReactor Effluents for the Purpose of Evaluating Compliance i 0, Appendix I,"Revision 1, October 1977 and Regulatory Guide 1.113, "Esf in ispersion ofEffluents from Accidental and Routine Reactor Releases f urp e of Implementing

D Appendix I," April 1977.0*.0000000000*13.1.2-4 000e KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.3Revision 15June 6, 201313.1.3DNC 13.1.3Liquid Radwaste Treatment SystemThe Liquid Radwaste Treatment System, as described in the ODCM, shallbe used to reduce the radioactive material in liquid wastes prior to theirdischarge when the projected dose, due to the liquid effluent, toUNRESTRICTED AREAS would exceed in a 31 day period:a. > 0.06 mrem to the total body; orb. > 0.2 mrem to any organ.APPLICABILITY:

At all1 times, except for the parts of the system takenservice.ACTIONSof IA. Radioactive liquid wastebeing discharged withouttreatment and in excess ofthe above limits.30 daysion of whyadwaste wasein ischarged without\\eatment, identification

/f fany non-functional/

inoperable equipment orsubsystems, and thereason for the non-functional

/ inoperability, (2) ACTION(s) taken torestore the non-functional

/ inoperable equipment toFUNCTIONAL IOPERABLE status, and(3) Summary description ofACTION(s) taken to000000000000000000000000000000000000S6S66prevent a recurrence.

13.1.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.3Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION 0000000000000000000000000000000DVR 13.1.3.1 Project the doses due to liquid effluents from thefacility to UNRESTRICTED AREAS in accordance withthe methodology and parameters specified in theODCM.31 daysI13.1.3-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.3Revision 15June 6, 2013BASESThe requirement that the appropriate portions of this system be used, when specified, providesassurance that the releases of radioactive materials in liquid effluents will be kept "as low as isreasonably achievable."

This DNC implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 ofAppendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to10 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 objectivess1 nSection II.A of Appendix 1, 10 CFR Part 50, for liquid effluents.

r llz\00000000000000000000000000000000000000013.1.3-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.4Revision 15June 6, 20130000000S0000000000013.1 LIQUID EFFLUENTS 13.1.4DNC 13.1.4Liquid Holdup TanksThe quantity of radioactivity contained in unprotected outdoor liquid storagetanks 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 nearestpotable water supply and surface water supply in an UNRESTRICTED AREA,excluding tritium and dissolved or entrained gases.APPLICABILITY:

At all times.ACTIONSIVERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.4.1 Sample and analyze radioactive liquid located in 31 days duringunprotected outdoor liquid storage tanks for level of addition ofradioactivity.

radioactive liquidto the tanks13.1.4-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.4Revision 15June 6, 201313.1 LIQUID EFFLUENTS 13.1.4 Liquid Holdup TanksBASESThe tanks listed in this Normal Condition include outdoor tanks that are not surrounded byliners, dikes or walls capable of holding the tank contents and do not have tank overflows andsurrounding area drains connected to the radwaste treatment system.Technical Specification 5.5.10.c requires a program to ensure that the material contained in the specified tanks provides assurance that, in the ej 0ofauncontrolled release of any such tank's contents, the resulting concentr ti'b ould)e lessthan the limits of 10 CFR 20, Appendix B Table II, Column 2 at the n st p' abJ0'&ater supply and the nearest surface water supply in an UNRESTRECT A .* quantities shall be determined in accordance with Standard Review Plan, S.ct .7X"ý'Postulated Radioactive Release due to Tank Failures."

,>00000000000000000000000000000000<N13.1.4-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.1Revision 15June 6, 201313.2.1DNC 13.2.1Gaseous Effluents Dose RateThe dose rate due to radioactive materials released in gaseous effluents from thesite 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 andb. For 1-131, 1-133, tritium and for all radionuclides in particulate form with half-lives > 8 days, < 1500 mrem/yr to any organ.0000SSSSSSSSSSSSSSSSSSS0SSSSSSSAPPLICABILITY:

At all times.ACTIONS/2NON-CONFORMANCE

,TIONiA. The dose rate(s) at orbeyond the SITEBOUNDARY due toradioactive gaseouseffluents exceeds limits.Immediately B. CONTINGENCY MEASURESORRESTORATION" not met.fr'1~ll ea CRAB.2 Explain in the nextRadioactive EffluentRelease Report why theCONTINGENCY MEASUREwas not met in a timelymanner.In accordance withCorrective ActionProgramIn accordance withRadioactive EffluentRelease Report13.2.1 -1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.1Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.1.1 The dose rate due to noble gases in gaseous In accordance witheffluents shall be determined to be within the Table 13.2.1-1above limits in accordance with the methodology and parameters in the ODCM.DVR 13.2.1.2The dose rate due to 1-131, 1-133, tritium and allradionuclides in particulate form with half-lives

> 8 days in gaseous effluents shall be determine;V to be within the above limits in accordance withmethodology and parameters in the ODCM byobtaining representative samples and erfanalyses in accordance with the samp in danalysis proaram specified in Table 13. .1ccor .ce with> e13. 1-10000000000000000000000000000000000000000000013.2.1 -2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.1Revision 15June 6, 2013Table 13.2.1-1 (Page 1 of 2)Radioactive Gaseous Waste Sampling and AnalysisGASEOUS RELEASETYPETYPE OFACTIVITYANALYSISSAMPLETYPESAMPLEFREQUENCY MINIMUMANALYSISFREQUENCY LOWER LIMIT OFDETECTION (LLD)(a)00S0000000001. Waste Gas StorageTank and Chemical Principal Gamma Graband Volume Control Emitters (b) SampleSystem Holdup Tank2. Containment Purge Principal Gamma GrabEmitters (b) Sample3. Auxiliary Building Principal Gamma Graband Containment Emitters (b) SampleBuilding VentSilica Gel,a. H-3 GrabSampleCharcoalb. 1-131Sample Each Tank (d)Each Purge (d)31 days ,-1 x 10-4 Ci/ml1 x 10-4 iCi/ml1 x 10 ACi/ml31 days1 x 106 pCi/mI7 days3 x 10-12 ACi/mlPrincipal Gammac. Emitters (b)(1-131, Others)(c)7 days1 x 10"" jiCi/mld. GrossContinuous (c)31 days1 x 10" 11Ci/mle.Continuous (c)92 days1 x 10.1, .Ci/mlContinuous (c)Continuous (c)1 x 10 p.Ci/ml13.2.1 -3 KEWAUNEE POWER STATION ODCM 13.2.1 UOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Table 13.2.1-1 (Page 2 of 2)Radioactive Gaseous Waste Sampling and Analysis(a) The LLD is defined, for purposes of these DNC's, as the smallest concentration of radioactive material in a sample that 0will yield a net count, above system background, that will be detected with 95% probability with only 5% probability offalsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

004.66

SbLLD = E*V2.22 x 106"Y* exp(-Aut)

OWhere:LLD is the a orio lower limit of detection as defined above, as g.Ci per unit ma lume,S Sb is the standard deviation of the background counting rate or of the counti ate o a ample as appropriate, as counts per minute,* E is the counting efficiency, as counts per disintegration, SVis thesample size in units of mass or volume, y-' 02.22 x 106 is the number of disintegrations per minute per micro O* Y is the fractional radiochemical yield, when applicable,

X. is the radioactive decay constant for the particular radi did/,ndAt for plant effluents is the elapsed time between the mid sa collection and time of counting.

Typical values of E, V, Y, and At should be used i ICUIt should be recognized that the LLD is defined a n(b e the fact) limit representing the capability of ameasurement system and not as an a osteri aft r the it for a particular measurement.

(b) The principal gamma emitters for whic LL r quirement applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-13 , d 13 aseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65,Mo-99, Cs-134, Cs-137, Ce-141, an 4for rticulate emissions.

This list does not mean that only thesenuclides are to be a ks that are identifiable, together with those of the above nuclides, shall also be analyzed and rt ithe ioactive Effluent Release Report pursuant to ODCM 15.2.(c) The ratio of the sample fi e sampled flow stream flow rate shall be known (based on sampler andventilation system meas ices or periodic flow estimates) for the time period covered by each dose ordose rate calc5dan e in rdance with ODCM DNC 13.2.1,13.2.2, and 13.2.3. 0(d) Complete p /" lease.00000000O13.2.1 -4 0OO0 W KEWAUNEE POWER STATION ODCM 13.2.1* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 2013* BASES0* 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 orequal 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 1500mrem/yr.

These dose rate limits provide additional assurance that radioactive material discharged ingaseous 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 inAppendix B, Table 2, Column 1 of 10 CFR 20. For MEMBERS OF THE P ho may at times be* within the SITE BOUNDARY, the occupancy of that MEMBER OF P IC will usually be* sufficiently low to compensate for any increase in the atmospheric si c above that for theSITE BOUNDARY.

The required detection capabilities for radioactive materials in samples are tabulated interms of the lower limits of detection (LLDs). Detailed disc n , and other detection limitscan be found in HASL Procedures Manual, HASL-30 r ed ually), Currie, L.A., "Limits for* Qualitative Detection and Quantitative Determination

-plia adiochemistry,"

Anal. Chem. 40,~ ~586-93Rihil(1968),HafrandcopnHartwell,ReorJ.K, "DetectionAHS_1 J~~'l95Limits afxR i al Counting Techniques,"

AtlanticRichfield Hanford Company Report ARH-SA-215 e 5)10S*0SSS0* 13.2.1 -5SSS KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.2Revision 15June 6, 201313.2.2Gaseous Effluent Dose -Noble GasDNC 13.2.2The air dose due to noble gases released in gaseous effluents from thefacility to areas at or beyond the SITE BOUNDARY (Plant Drawing A-408)shall be limited to the following:

a. < 5 mrad for gamma radiation and < 10 mrad for beta radiation during any calendar

quarter, andb. < 10 mrad for gamma radiation and < 20 mrad for beta radiation during any calendar year.APPLICABILITY:

At all times.6i/?>ACTIONS000000000000000000000000000000000006613.2.2- 1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.2Revision 15June 6, 2013S00S00000000000000000ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Calculated dose to aMEMBER OF THEPUBLIC from the releaseof radioactive materials inliquid effluents exceeds 2times the limits.B.1 Calculate the annual dose toa MEMBER OF THEPUBLIC which includescontributions from directradiation from the facility(including outside storagetanks, etc.).Immediately ANDlyB.2 Verify that the limits of DN13.4 have not beenexceeded.

1-C. CONTINGENCY MEASURE B.2 andAssociated RESTORATION TIME notmet.30 days(corrective action(s)

W be taken to preventrecurrence of exceeding the limits of DNC 13.4and the schedule forachieving conformance, (2) An analysis thatestimates the dose to aMEMBER OF THEPUBLIC from uraniumfuel cycle sources,including all effluentpathways and directradiation, for thecalendar year thatincludes the release(s),

and(3) Describes the levels ofradiation andconcentrations ofradioactive materialinvolved and the causeof the exposure levels orconcentrations.

13.2.2-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.2Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.2.1 Determine cumulative dose contributions for the 31 dayscurrent calendar quarter and current calendar year inaccordance with the methodology and parameters inthe ODCM.000000000000000000000000000000000000000000013.2.2-3

KEWAUNEE POWER STATION ODCM 13.2.2* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013* BASES* This DNC is provided to implement the requirements of Sections II.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 SectionIII.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 00 for c lating the* doses due to the actual release rates of radioactive noble gases in gasu areconsistent with the methodology provided in Regulatory Guide 1.10 lptab f Annual0 Doses to Man from Routine Releases of Reactor Effluents for the of ,yluating

Compliance with 10 CFR Part 50, Appendix I," Revision 1, Oct a egulatory Guide1.111, "Methods for Estimating Atmospheric Transport and i ersi o seous Effluents inRoutine Releases from Light-Water Cooled Reactors,"

Re s 1, JI 1977. The ODCM* equations provided for determining the air doses at an dyo E BOUNDARY arebased upon the historical average atmospheric condi s.S"00* 13.2.2-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.3Revision 15June 6, 201313.2.3Gaseous Effluent Dose -Iodine, Tritium and Particulate DNC 13.2.3The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, andall radionuclides in particulate form with half-lives

> 8 days, in gaseouseffluents, released to areas at or beyond the SITE BOUNDARY (PlantDrawing A-408) shall be limited to the following:

a. < 7.5 mrem to any organ during any calendar

quarter, andb. < 15 mrem to any organ during any calendarAPPLICABILITY:

At all times.ACTIONS ,zNON-CONFORMANCE CONTINGENCY A RESTORATION TIMEA. The calculated dose from A.1 Prep an o the 30 daysthe release of 1-131, 1-133, NRC, o NC 15.3,tritium, and radionuclides t thatin particulate form with he cause(s)half-lives

> 8 days eeding the limit(s)released in gaseous nd;effluents at or beyond the < (2 efines the corrective SITE BOUNDARY actions that have beenexceeds limits. i'X) taken to reduce thereleases and theproposed corrective actions to be taken toassure that subsequent releases will be incompliance with DNC13.2.3.000SS0S0SSSSSSSSS0SSSSSSSSSSSSSSSSSSSSSSSSSS13.2.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.3Revision 15June 6, 2013S0000000000000S00000ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Calculated dose to aMEMBER OF THEPUBLIC from the releaseof radioactive materials inliquid effluents exceeds 2times the limits.B.1 Calculate the annual dose toa MEMBER OF THEPUBLIC which includescontributions from directradiation from the facility(including outside storagetanks, etc.).Immediately ANDB.2 Verify that the limits of Dh13.4 have not been,,.-.

exceeded.

yC. CONTINGENCY MEASURE B.2 andAssociated RESTORATION TIME notmet.30 days>1 5.3,!(efined1)(4), ofkSUREthe\T rrective action(s)

"ý be taken to prevent/ _currence of exceeding the limits of DNC 13.4and the schedule forachieving conformance, (2) An analysis thatestimates the dose to aMEMBER OF THEPUBLIC from uraniumfuel cycle sources,including all effluentpathways and directradiation, for thecalendar year thatincludes the release(s),

and(3) Describes the levels ofradiation andconcentrations ofradioactive materialinvolved and the causeof the exposure levels orconcentrations.

Ic13.2.3-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.3Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION DVR 13.2.3.1 Determine cumulative dose contributions for thecurrent calendar quarter and current calendar yearfor 1-131, 1-133, tritium, and radionuclides inparticulate form with half-lives

> 8 days in accordance with the methodology and parameters in the ODCM.31 days00000000000000SS0000000000000000000S0000S00013.2.3-3 00* KEWAUNEE POWER STATION ODCM 13.2.3OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013*BASES*This DNC is provided to implement the requirements of Sections II.C, III.A and IV.A of AppendixI1, 10 CFR Part 50. The DNC's are the guides set forth in Section II.C of Appendix I. Thecontingency 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 4BER OF THEPUBLIC through appropriate pathways is unlikely to be substantially

.6 ated. TheODCM calculational methodology and parameters for calculating the due the actual* release rates of the subject materials are consistent with the tho'qg/,g rovided inRegulatory Guide 1.109, "Calculation of Annual Doses to ma rou Releases ofReactor Effluents for the Purpose of Evaluating Compliance with P 50, Appendix I,"Revision 1, October 1977 and Regulatory Guide 1.111, W ating Atmospheric Transport and Dispersion of Gaseous Effluents in RoutineK lease fi Light-Water-Cooled Reactors,"

Revision 1, July 1977.These equations also provide for determining the d based upon the historical average atmospheric conditions.

The release r itib iodine-131, iodine-I33, tritium,*I and radionuclides in particulate form with half-lis

,srt'n 8 days are dependent upon theexisting radionuclide pathways to man in a beyond the SITE BOUNDARY.

Thepathways that were examined in the o-l) ern hese calculations were: 1) individual

inhalation of airborne radionuclides,

2) radionuclides onto green leafy vegetation with subsequent consumption by ,3 osition onto grassy areas where milk animals andmeat producing animals graze w' o l ,inof the milk and meat by man, and 4) deposition on the ground with subsequen e o an.00-000000000*13.2.3-4 00 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.4Revision 15June 6, 201313.2.4GASEOUS RADWASTE TREATMENT SYSTEMDNC 13.2.4APPLICABILITY:

The GASEOUS RADWASTE TREATMENT SYSTEM and theVENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduceradioactive materials in gaseous waste prior to their discharge when theprojected gaseous effluent air doses due to gaseous effluent releases toareas at and beyond the SITE BOUNDARY (Plant Drawing A-408) wouldbe:a. > 0.2 mrad for gamma radiation; orb. > 0.4 mrad for beta radiation; orc. > 0.3 mrem to any organ in 31 dayTreatment System only)At all times, except for the parts of the sservice.

Výf~haustnently out ofACTIONSNON-CONFORMANCE kTION00000000000000000000000000000000000000000000A. Radioactive gaseouswaste is being discharged without treatment.

ANDProjected dosesgaseous effluentfacility, at and_SITE B O,exceed Vdsubmit to thepusant to DNC 15.3,cial Report thatdes the following:

(1tion of whygaseous radwaste wasbeing discharged withouttreatment, (2) Identification of anynon-functional Iinoperable equipment orsubsystems and thereason for thenon-functional/

inoperability, (3) ACTION(s) taken torestore thenon-functional

/inoperable equipment toFUNCTIONAL

/OPERABLE status, and(4) Summary description ofACTION(s) taken toprevent a recurrence.

30 days13.2.4-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.4Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION 00000000000000000000000000000000000DVR 13.2.4.1Project the doses due to gaseous effluents from eachfacility at and beyond the SITE BOUNDARY inaccordance with the methodology and parameters inthe ODCM.31 days13.2.4-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.4Revision 15June 6, 2013BASESThe requirement that the appropriate portions of these systems be used, whenspecified, provides reasonable assurance that the releases of radioactive materials ingaseous effluents will be kept "as low as is reasonably achievable."

This DNC implements the requirements of 10 CFR 50.36a, General Design Criterion 60of Appendix A to 10 CFR Part 50, and the design objectives given in section II.D ofAppendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of thespecified as a suitable fraction of the dose design objectives set foqand II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

/.>were0000000000000000000000000000000000000000000013.2.4-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.5Revision 15June 6, 201313.2 GASEOUS EFFLUENTS 13.2.5Gas Storage TanksDNC 13.2,5The radioactivity contained in each gas storage tank shall be limited to< 52,000 Curies of noble gas. (Considered as Xe-1 33)APPLICABILITY:

At all times, except when the tank is taken permanently out of service.I0000000000000000000000000000000ACTIONSAA. Level of radioactivity exceeds the limits.Immediately 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months s13.2.5-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.5Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION DVR 13.2.5.1 Verify quantity of radioactive material contained ineach gas storage tank is 5 52,000 curies of noblegases (considered as Xe-133).31 daysANDVtreg', red to beýp-oyfed if thenjas recentactor CoolantSystem specificactivity DOSEEQUIVALENT 1-131 is< 1.0 pCi/gmOnce per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months swhen radioactive materials are00000000000000000000000000000000000000000000being added to thetank13.2.5-2

KEWAUNEE POWER STATION ODCM 13.2.5OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013*BASESThis verification implements the requirement of Technical Specification 5.5.10.b.

whichrequires a program to ensure that the quantity of radioactivity contained in each gas storagetank and fed into the offgas treatment system is less than the amount that would result in awhole body exposure of > 0.5 rem to any individual in an UNRESTRICTED AREA, in the01 event of an uncontrolled release of the tanks contents.

Contents of the tank quantities shall*1 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 decaytank is taken to be the maximum amount that could accumulate from opera' claddingdefects in 1 percent of the fuel elements.

This is at least ten times the ex. ed nber ofdefective fuel elements.

The maximum activity is obtained by assumin e le es,xenon and krypton, are accumulated with no release over a full cor _ le tank inventory is calculated assuming nuclide decay, degassing of r to ,'olant withletdown at the maximum rate, and periodic purging to the gas .maximuminventory for each nuclide during the degas and PURGE cy s iI lendix D,*Table D.7-1. (reference 1)0 The resultant dose consequence for this accident is .re ho dy at the SITE* BOUNDARY.

Summing the activities in USAR Ta 1",(re fnce 4) results in 42,792.74 curies. Using the noble gas dose conversion fa ained in USAR Table D.8-1(reference

5) referenced to Xe-1 33 results in a n;- onf 52,000 curies whenconsidered as Xe-133. Kewaunee Power nidoes t have a calculation correcting thewaste gas decay tank activity to a SITE U AR'6nsequence of < 0.5 rem, therefore bylimiting the activity in a waste gas de -hich results in 0.1 rem at the SITE* BOUNDARY, the 0.5 rem limit will eded.DVR 13.2.5 frequency is modi no at restricts performing the verification when* additions are made to a ta y e reactor coolant system DOSE EQUIVALENT Iodine 131 (DEI-131) acti s ater an 1.0 gCi/gm (microcurie per gram). A calculation has shown that when a fuel assumption is used the resultant RCS DOSEEQUIVALENT XE-R3 ac Id be 595 .tCi/gm (reference 2). Engineering experience is*that with 1.0 [lCi/gn 1-13 CS activity, the associated DEX-133 activity is approximately 200 laCi/gm.

w an ption of 1% failed fuel calculations results are 595 gCi/gmDEX-1 33, ana consequences calculation also yields a 0.1 rem whole body at theSITE BOUND b Iculation then a gas decay tank on fill cannot exceed the activitylimits of this req _frnt and the once per 31 day frequency is adequate.

Reference

1. USAR Section 14.2.3, Accidental Release-Waste Gas2. Calculation C1 1833, Kewaunee Power Station RCS Specific Activity Dose Equivalent

) Xenon -133 Indicator

3. Calculation CN-CRA-99-46, Revision 3, Kewaunee GDT Rupture and VCT RuptureRadiation 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 1*13.2.5-3000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 15June 6, 201313.3 INSTRUMENTATION 13.3.1Radioactive Liquid Effluent Monitoring Instrumentation DNC 13.3.1The radioactive liquid effluent monitoring instrumentation channels shownin Table 13.3.1-1 shall be FUNCTIONAL with:a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1are not exceeded.

APPLICABILITY:

During release via the monitored pathway.ACTIONS--------------------------------------------------------------

A. Liquid effluent monitoring instrumentation channelalarm/trip setpoint lessconservative than required.

Immediately 000000000000000000000000S000S000000000000000the channelImmediately

.3 Change the setpoint so itis acceptably conservative.

Immediately 13.3.1 -1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 15June 6, 201300000000S00000S0000000000ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. One or more required B.1 Restore non-functional 30 dayschannels non-functional, channel(s) to FUNCTIONAL status.C. Liquid Radwaste Effluent

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

Line (R-18) non-functional Prior to initiating an effluentprior to or during effluent

release, complete sections

>releases.

C.1.1 and C.1.2C.1.1 Analyze at least 2 rto initiating aindependent sam in leaseaccordance WjANDC.1.2 T~nq *ul ti ION will be[1]y at least 2arate technically

< ,quied members of thef ility staff.Independently verify the Prior to initiating arelease rate calculations and releasedischarge line valving.ORC.2 Suspend release of Immediately radioactive effluents via thispathway13.3.1-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 15June 6, 2013ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMED. Steam Generator Effluent D.1 Collect and analyze grab At least once everyLine (R-19) non-functional samples for gross 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months withprior to or during effluent radioactivity (beta or gamma) identified primary toreleases at a lower limit of detection of secondary leakageat least 1 x 10-6 RCi/mI. (with secondary sideac ix 10-sMI .At st once ak when noindication of primaryto secondary leakage;Failu o mpt ampling andan is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after theSni decared non-functional s ol of this DNC.E. ollect and analyze grabE. Service Water S en- samples for gross radioactivity Once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sEffluent Line (R-2 (beta or gamma) at a lower limit of16) non-fun"al detection of at least 1 x 10-6prior to ri laCi/ml.efflue r__000000000000000000000000000000000000000000013.3.1 -3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 15June 6, 2013000S0000000S00NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEF. CONTINGENCY F.1 Initiate a CR In accordance withMEASURES Corrective ActionOR AND ProgramRESTORATION TIME of A,B, C, D or Enot met. F.2 Explain in the next In accordance withRadioactive Effluent R e EffluentRelease Report why the easeportCONTINGENY MEASUREwas not met in a timely < VERIFICATION REQUIREMENTS

-- ---.--.-.--------------------.------

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

Refer to Table 13.3.1-1 to determine which DVRs appl re c on.VERIFICATION FREQUENCY DVR 13.3.1.1 Perform 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sDVR 13.3.1.2 Perform K. Prior to releaseDVR 13.3.1.3

,,erfor 0 CE CHECK. 31 daysDVR 13.3.1. e rm CHANNEL FUNCTIONAL TEST 92 daysDVR 13.3.1.5 Perform CHANNEL CALIBRATION.

18 months13.3.1-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 15June 6, 2013Table 13.3.1-1Radioactive Liquid Effluent Monitoring Instrumentation

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REQUIREDCHANNELSPERINSTRUMENT INSTRUMENT VERIFICATION REQUIREMENTS

------ -----------

..............

1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination ofReleasea. Liquid Radwaste Effluent Line (R-18)b. Steam Generator Blowdown EffluentLine (R-19)2.Gross Beta or Gamma Radioactivity Monitors Providing Alarm but notProviding Automatic Termination ofReleasea. Service Water System E tye(Component Coolingb. Service r., e ffluent Line ling R-16)1 ....... .. ..L6R/t .1.21.3.1.43.3.1.5DVR 13.3.1.1DVR 13.3.1.3DVR 13.3.1.4DVR 13.3.1.500000000000000000000000000000000000000000000DVRDVRDVRDVRDVRDVRDVRDVR13.3.1.113.3.1.313.3.1.413.3.1.513.3.1.113.3.1.313.3.1.413.3.1.513.3.1-5

KEWAUNEE POWER STATION ODCM 13.3.1* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013*BASES0*The radioactive liquid effluent instrumentation, required FUNCTIONAL by this DNC, isprovided 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 priorto 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 to10 CFR Part 50.N*00000000000000O 13.3.1-600 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 15June 6, 201313.3 INSTRUMENTATION 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DNC 13.3.2The radioactive gaseous effluent monitoring instrumentation channelsshown in Table 13.3.2-1 shall be FUNCTIONAL with:a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.2.1 arenot exceeded.

APPLICABILITY:

During release via the monitored pathway.IACTIONS-..-----------.-.-------.----------------------

NOTE- -----Separate NON-CONFORMANCE entry is allowed for each channel.............

NON-CONFORMANCE CONTINGENCY A ES RESTORATION TIMEA. Gaseous effluent A.1 Suspen as Immediately monitoring instrumentation radio vechannel alarm/trip setpoint efflue re by theless conservative than d 1.required.

K 20< D retlchannel Immediately

-functional.

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

B. Less than ;he-inimum B.1 Restore non-functional 30 days.number of channels channel(s) toFUNCTIONAL.

FUNCTIONAL status.0000000000000000000000000000000000000000000013.3.2-1 S0000S0000000000S0KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 15June 6, 2013ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEC. Noble Gas Activity effluentmonitoring for the WasteGas Holdup System andChemical and VolumeControl System HoldupTanks non-functional priorto or during releases-NOTE -----.-.--.....

Prior to initiating aneffluent

release, completesections C.1.1 and C.1.2.Prior to initiating areleaseC.1.1 Analyze at least 2independent samples inaccordance with Table13.2.1-1.

<ANDC.. 1.2 ------NOTEVerification, be performbPrior to initiating areleaseiendently verify the5e rate calculations Iischarge line valving.NC.2 Suspend release ofradioactive effluents viathis pathwayImmediately D. Noble Gas Activity effluentmonitoring for the Auxiliary Building Ventilation Systemand the Condenser Evacuation Systemnon-functional prior to orduring releasesD.1Take grab samples.12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sANDANDD.2Once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sthereafter 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time ofsampling completion Analyze samples forgross activity.

13.3.2-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 15June 6, 2013NON-CONFORMANCE I CONTINGENCY MEASURES RESTORATION TIMEE. Noble Gas Activity effluentmonitoring for theContainment PurgeSystem, 2" line and 36"duct (auto-isolation) non-functional prior to orduring releasesE.1 Suspend PURGING ofRadioactive effluents viathis pathway.Immediately

+F. Sampler Flow rateMeasuring Devices (for theAuxiliary BuildingVentilation or Containment Building Ventilation Sampler) non-functional prior to or during releasesF. 1 Estimate the flow rate forthe non-functional channel(s).

<<per 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sifterG. Radioiodine and Particulate Samplers (for theAuxiliary BuildingVentilation or Containment Building Ventilation system) non-functional prior to or during releases

/G.112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months s00SSSSSSSSSSSSSSSSSSSSSS0SSSSSSSSSSSSSSSSSSSx,H. CONTINGENCY MEASURESInitiate a CRORRESTOFC, D, E,(not met.ANDB,In accordance withCorrective ActionProgramIn accordance withRadioactive EffluentRelease ReportH.2 Explain in the nextRadioactive EffluentRelease Report why theCONTINGENCY MEASURE was not met ina timely manner.13.3.2-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 15June 6, 2013VERIFICATION REQUIREMENTS 0000000000000000000000000000VERIFICATION FREQUENCY DVR 13.3.2.1 Perform CHANNEL CHECK. Prior to releaseDVR 13.3.2.2 Perform CHANNEL CHECK. 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sDVR 13.3.2.3 Perform CHANNEL CHECK. aysDVR 13.3.2.4 Perform SOURCE CHECK. nKior to releaseDVR 13.3.2.5 Perform SOURCE CHECK. 31 daysDVR 13.3.2.6 Perform CHANNEL FU L T. 92 days1L ATION. 18 months13.3.2-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 15June 6, 2013Table 13.3.2-1Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT REQUIRED NON- VERIFICATION CHANNELS PER CONFORMANCE REQUIREMENTS INSTRUMENT

1. Waste Gas Holdup SystemDVR 13.3.2.1DVR 13.3.2.4DVR 13.3.2.6DVR 13.3.2.7a. Noble Gas Activity Monitor(R-13 or R-14)IC2. Condenser Evacuation Systema. Noble Gas Activity (R-15)3. Auxiliary Building Venta. Noble Gas Activity Monitor(R-13 or R-14)IDVR 13.3.2.2DVR 13.3.2.5DVR 13.3.2.6DVR 13.3.2.7b. Radioiodine andParticulate Sampler(R-13 or R-14)G DVR 13.3.2.3F DVR 13.3.2.2S0SS0SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSc. Sample Flow-Rate Monitor(R-13 or R-14)DVR 13.3.2.6DVR 13.3.2.74. Containment Buildinga. Radioiodine andParticulate (R-21) 1111GDVR 133.2.31Fb.DVR 13.3.2.2DVR 13.3.2.6DVR 13.3.2.75. Containment Purge 2" linea. Noble Gas Activity Monitor(R-13 or R-14)1 EDVR 13.3.2.2DVR 13.3.2.5DVR 13.3.2.6DVR 13.3.2.76. Containment Purge 36" line DVR 13.3.2.2DVR 13.3.2.4a. Noble Gas Activity Monitor 1 E DVR 13.3.2.6(R-12 or R-21) DVR 13.3.2.713.3.2-5

KEWAUNEE POWER STATION ODCM 13.3.2* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013* 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.

Thealarm/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 50.10S0S*S-S.S.K24S* ,-S_**SSSSSSSSO 13.3.2-6SSS 00KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.4 RADIOACTIVE EFFLUENTS TOTAL DOSEODCM 13.4.1Revision 15June 6, 201313.4.1Radioactive Effluents Total DoseDNC 13.4.1The annual (calendar year) dose or dose commitment to any MEMBER OFTHE PUBLIC due to releases of radioactivity and to radiation from uraniumfuel cycle sources shall be limited to < 25 mrem to the total body or anyorgan, except the thyroid, which shall be limited to < 75 mrem.APPLICABILITY:

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES)TION-I-A. Estimated dose or dosecommitment due to directradiation and the releaseof radioactive materials inliquid or gaseous effluents exceeds the limits.A. 1 Verify the condition in doses exceeding limits has beenAr1oIliatelyB. CONTINGENCY MEASURES A.1 andRESTORATION TIME notmet.(lemented with theting.0S0S0S00S00SSSS0SSSSSSSSSS0SSSS0SSSSS(30 daysSubmit a Special Report,pursuant to DNC 15.3,including a request for avariance in accordance withthe provisions of 40 CFR190. This submission isconsidered a timely request,and a variance is granteduntil staff ACTION on therequest is complete.

13.4.1 -1 S00000S0S000S0S0S000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.4.1Revision 15June 6, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.4.1.1 Cumulative dose contributions from liquid and 12 monthsgaseous 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 themethodology and parameters in the ODCM.DVR 13.4.1.2Cumulative dose contributions from direct radiation from the facility shall be determined in accordance with the methodology and parameters in the ODC)4This requirement is applicable only under condjt,set forth in ODCM DNC 13.4.1I.A.

II((v(13.4.1 -2 OOKEWAUNEE POWER STATION ODCM 13.4.1 OOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013BASES0This 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 andsubmittal 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 Odose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if thefacility remains within twice the dose design objectives of Appendix I, and if direct radiation Idoses from the facility are kept small. OThe Special Report will describe a course of ACTION that should resulteth tion of theannual dose to a MEMBER OF THE PUBLIC to within the 40 CF R r/ li ' s. For the 5purposes of the Special Report, it may be assumed that the dose eme MEMBEROF THE PUBLIC from other uranium fuel cycle sources is ne h Ie dose to any OMEMBER OF THE PUBLIC is estimated to exceed the requi ,FR Part 190, the SSpecial Report with a request for a variance (provided rele nditions resulting inviolation of 40 CFR Part 190 have not already beelnc cted in accordance with the Oprovisions of 40 CFR 190.11 and 10 CFR 20.2203, on*'d be a timely request and 0fulfills the requirements of 40 CFR Part 190 until NR TI is completed.

The varianceonly relates to the limits of 40 CFR Part 190, n pply in any way to the other Orequirements for dose limitation of 10 CFR Pa 0 ssed in ODCM Normal Condition 013.3.1 and 13.4.1. An individual is not co si a MBER OF THE PUBLIC during anyperiod in which he/she is engaged in ca ut that is part of the nuclear fuelOcycle. .,,'...,Z-._.

-00"0000000000000013.4.1 -3 O000 0S0000000000000000000000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.5.1Revision 15June 6, 201313.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.1 Monitoring ProgramThis Kewaunee Program is established by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and implemented by approved station procedures.

Thisprogram is required by Technical Specification 5.5.1 .a, ODCM.The radiological environmental monitoring program required by this DNC providesrepresentative measurements of radiation and of radioactive materials in thpathways and for those radionuclides that lead to the highest potential ra on eMEMBERS OF THE PUBLIC resulting from the station operation.

This r ng IimplementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and ther 5 pradiological effluent monitoring program by verifying that the meas I ncradioactive materials and levels of radiation are not higher tha eo beeffluent measurements and the modeling of the environmenc xpo ewayseforflns moesoun roeram is a rovid the moe iof he envion me wranysPosition on Environmental Monitoring.

R l iasSuresures ofgrams the3tions ofisis of theGuidance(Zz;,13.5.1 -1 00KEWAUNEE POWER STATION ODCM 13.5.2 *OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 201313.5 RADIOLOGICAL ENVIRONMENTAL MONITORING.

13.5.2 Land Use Census Program OThis Kewaunee Land Use Census Program is implemented by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and Land Use Census Programprocedure.

OBASES O0This DNC is provided to ensure that changes in the use of areas at and bey SITE 0BOUNDARY are identified and that modifications to the radiological envir enta onitoring program are made if required by the results of this census. Thest in n fro the door-to-door survey, from aerial survey or from consulting with local agricu r shall beused. This census satisfies the requirements of Section IV.B.3 of A I , CFR Part 50. ORestricting the census to gardens of greater than 50 m2 provid C t significant exposure pathways via leafy vegetables will be identified an o e a garden of thissize is the minimum required to produce the quantity (26 W/ rfy vegetables assumed 0in Regulatory Guide 1.109 for consumption by a child.Tdee is minimum garden size, dthe following assumptions were made: (1) 20% of the rd as ed for growing broad leafvegetation (i.e., similar to lettuce and cabbage),

a eg on yield of 2 kg/M2.0 00-00000000S013.5.2-1 00O0 0000000000000000000000SKEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.5.3Revision 15June 6, 201313.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.3 Interlaboratory Comparison ProgramThis Kewaunee Interlaboratory Comparison Program is implemented by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and approved station procedures.

BASESThe requirement for participation in an approved Interlaboratory Comparison Program isprovided to ensure that independent checks on the precision and accuracymeasurements of radioactive material in environmental sample matrices perfo d cof the quality assurance program for environmental monitoring (develop~l gthuicRegulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guid v Ap1975) in order to demonstrate that the results are valid for the pur ps e i IV.B.;Appendix I to 10 CFR Part 50.as partlance in13.5.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 14.1Revision 15June 6, 201314.0 DESIGN FEATURES14.1 GASEOUS AND LIQUID EFFLUENT RELEASE POINTS14.1.1Plant drawing A-408, "Radiological Survey Site Map" depicts the site area byillustrating the SITE BOUNDARY and the restricted areas. Plant drawing A-449,"Plan of Plant Area, Fence, Lighting, and CCTV Support Structure" shows thelayout of the site buildings.

MEMBERS OF THE PUBLIC are restricted from accessto all areas of the Owner Controlled Area (OCA).14.1.2 Figure 14.1-1 presents the locations of radioactive effluentplant. The plant drawings referenced above are not includeqbut can be found in the plant drawing system.0000000S000000S0000S000000000000000000000014.1 -1 KEWAUNEE POWER STATION ODCM 14.1OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013FIGURE 14.1-1-----~--~ --. --. -_ _ _ _ _ _ _---------.----

KEWAUNEE_ _ -- 4--"'C I~. (N~- A ~-,'.~ ~;,LA Z UVWCWIAMc LECGJEA Cr7NIAWENjT BUw.iNr.*VZNT ELEVATION 775'B = AUXI-IMAY WJl*L4NIC EN1CLEVATIM~

WE'C 7ErrULErT L10110 -ISLEP1tG.IE ft-z-VAIICN S-W414.1 -2 00KEWAUNEE POWER STATION ODCM 15.1OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013015.0 ADMINISTRATIVE CONTROLS15.1 Major Changes to Radioactive Waste Systems(')

0Licensee 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 inwhich the evaluation was reviewed by FSRC. The discussion of each change shall contain:a. A summary of the evaluation that led to the determination that the change could bemade in accordance with 10 CFR Part 50.59,b. Sufficient information to totally support the reason for the n irn benefit ofadditional or supplemental information,

c. A description of the equipment, components and in ed and theinterfaces with other plant systems,d An evaluation of the change, which shows p e leases of radioactive materials in liquid and gaseous effluents d/ .ua n of solid waste that differfrom those previously predicted in p i " tion and amendments thereto,-0e. An evaluation of the change, whic xpected maximum exposures toindividuals in the UNRESTRI A1d to the general population that differfrom those previously esti se application and amendments thereto,f. A comparison of th d ases of radioactive materials in liquid and 0gaseous effluen o, aste to the actual releases for the period in whichthe changes o mg. An estimate posure to plant operating personnel as a result of the change, 0and0h. fact that the change was reviewed and found acceptable byChanges shall become effective upon review and acceptance by the FSRC.0000000(')Licensees may choose to submit the information called for in this requirement as part of the 0periodic USAR update. 115.1 -1I W KEWAUNEE POWER STATION ODCM 15.2* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013*15.0 ADMINISTRATIVE CONTROLS15.2 Radioactive Effluent Release Report0*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 solidwaste released from the facility following the format of Regulatory Guide 1.21,*"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases 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 colle r the reviousyear. This annual summary may be either in the form n -our listingon magnetic tape of wind speed, wind direction, atmr st b'rity, andprecipitation (if measured),

or in the form of join e d' ution of windspeed, wind direction, and atmospheric stabil* In Ii o mission with the*Radioactive Effluent Release Report, the Ii has e option of retaining thissummary of required meteorological data se that shall be provided tothe NRC upon request.es(7 rc. An assessment of the radiation d es radioactive liquid and gaseouseffluents released from the facilit .revious calendar year.d. An assessment of radiat' d kely most exposed MEMBER OF THEPUBLIC from facility r a nearby uranium fuel cycle sources,including doses fro ri uent pathways and direct radiation, the previouscalendar year to s r ce with 40 CFR Part 190, Environmental Radiation Pro for Nuclear Power Operation.

All assun1ti ed in making these assessments, i.e., specific

activity, exposure

location, shall be included in these reports.

The assessment of r tion s hall be performed in accordance with the methodology andSsi e OFFSITE DOSE CALCULATION MANUAL (ODCM).00000000*15.2- 1000 OKEWAUNEE POWER STATION ODCM 15.2 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20130e. The report shall include a summary of the quantities of radioactive liquid andgaseous effluents and solid waste released from the facility.

The material Iprovided shall be consistent with the objectives outlined in the ODCM and thePCP, and in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix Ito 10 CFR Part 50.0f. A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during thereporting period. 0g. Any changes made during the reporting period to the PROC NTROLPROGRAM (PCP) and to the OFFSITE DOSE CALCULAT 0MANUAL (ODCM), as well as a listing of new locations s calcations and/or environmental monitoring identified by te laai ne toDNC 13.5.2. , ,-/>15.2-2000000000*"00000000015.2-2 0O000 000S00000000000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 15.3Revision 15June 6, 201315.0 ADMINISTRATIVE CONTROLS15.3 Special ReportsSpecial reports may be required covering inspections, tests, and maintenance activities.

Thesespecial reports are determined on an individual basis. Their preparation and submittal aredesignated in the ODCM Contingency Measures for each Normal Condition.

Special reports shall be submitted to the Director of the NRC Regional Office listed in AppendixD, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enfnt, U.S.Nuclear Regulatory Commission, Washington D.C. 20555 within the time iod s ified foreach report.These Special Report(s) are in lieu of a Licensee Event Report15.3-1 Kewaunee Power StationOffsite Dose Calculation Manual000000000000000000000000000000000000000000 S KEWAUNEE POWER STATION ODCM 1.0* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013* 1.0 LIQUID EFFLUENTS METHODOLOGY 01.1 Radiation Monitoring Instrumentation and ControlsThe liquid effluent monitoring instrumentation and controls installed at Kewaunee forcontrolling 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 liquidradwaste effluent line, R-19 on the Steam Generator blowdown.

2) Alarm (only) -R-20 and R-16 provide alarm function Service Water* discharges.

3) Composite Samples -Samples are collected w y team generator blowdown and analyzed by gamma spectroscop pie e collected weeklyfrom the Turbine Building Sump and anal spectroscopy.

Theweekly samples are composited for montl. ritiu nt oss alpha analyses andfor quarterly Sr-89, Sr-90, and Fe- 5ayses.)During periods of identified primary-to-secondary leakage (with e e activity

> 1.OE-05 pCi/ml),grab samples from the Turbine B in M e collected daily and analyzedby gamma spectroscopy.

Thes composited for monthly tritium and* gross alpha analyses and for a r , Sr-90, and Fe-55 analyses.

4) Liquid Tank quid tanks are located inside the Auxiliary Building and contai e be--onfinement systems and drains to preventdirect, unmonitore renvironment.

A liquid radioactive waste flowdiagram with th pll a associated radiation monitoring instrumentation andcontrols is pre t SF re 1.1.2 Liquid Effluent Monitor D inationPer the re " ts of Technical Specification 5.5.3.b and ODCM NormalConditicKE1i3.3.,

la' setpoints shall be established for the liquid effluent monitoring instru e on t ensure that the release concentration limits of ODCM NormalCo n1 re met (i.e., the concentration of radioactive material released in liquidefL UNRESTRICTED AREA shall be limited to ten times the concentrations spe led 1 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and2.0E- i/ml for dissolved or entrained noble gases). The following equation1 must besatisified to meet the liquid effluent restrictions:

00 <IOxC(F+f)

(1.0f'Adapted from NUREG-01 33 to include the application of 10 times the Effluent Concentration (EC) of 10 CFR 20,* Appendix B, Table 2, Column 2.1.0-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALwhere:ODCM 1.0Revision 15June 6, 201310xC = ten times the effluent concentration limit of 10 CFR 20, Appendix B, Table 2,Column 2, in pCi/ml. For dissolved and entrained noble gases equals2x10- 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; thesetpoint, which is inversely proportional to the volumetric flow of the effluent lineand proportional to the volumetric flow of the dilution stream plus the effluentstream, represents a value which, if exceeded, would concentrations exceeding the limits of ODCM Normal Condition 113.I .,f = the flow rate at the radiation monitor locationsame units as F, below.time, but in theF = the dilution water flow rate asunit time.[Note that if no dilution iscompared to (f), then(,kýrelease point, in volume perC. Also, note that when (F) is large06000S00000000S00000S00000000S000SSSSS01.2.1 Liquid Effluent Monitors Steam Generator Blowdown and Service Water)The setpoidetermir,4 effluent monitors at the Kewaunee Power Station areI equations:

SP : CWX-CEi xSENi)+bkg Ci xRRlOx EC,(1.2)SP= alarm setpoint corresponding to the maximum allowable releaserate (cpm)Ci = the concentration of radionuclide "i" in the liquid effluent (pCi), toinclude gamma emitters only10xECi = ten times the EC value corresponding to radionuclide

'"T from10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml)1.0-2 000000000000KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013SENi = the sensitivity value to which the monitor is calibrated forradionuclide "iT (cpm per pCi/ml).

The default calibration valuefrom Table 1.1 may be used for gamma emitting radionuclides inlieu of nuclide specific values.CW = the circulating water flow rate (dilution water flow) at the time ofrelease (gal/min)

RR = the liquid effluent release rate (gal/min) bkg = the background of the monitor (cpm)The radioactivity monitor setpoint equation (1.2) remai "yv~l during outageswhen the circulating water dilution is at its lowest. Red on o e waste streamflow (RR) may be necessary during these periods t94n the d harge criteria.

At its lowest value, CW will equal RR and equati'1 pto the following equation:

SP _< b (C1 3b' k (1:3)( E.1.2.2 Conservative Default ValuesNon-gamma emitting ra " 3, Fe-55, Sr-89/90) are not detected bythe effluent monitor a not directly included in the above setpointequation.

These n a ionuclides can, however, contribute a sizablefraction of the toa it (re to Appendix C). The method specified belowfor establishin fa se "nts provides conservatism to account for these non-gamma emitte en es that the setpoint meets the requirements of ODCMNormal nKJ.x*including all radionuclides.

Refer to Appendix C forfurther ,in.Conse 'v arm setpoints have been determined through the use of generic,ul ers. Table 1.1 summarizes all current default values in use forThey are based upon the following:

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

where:EC= ciCi(ECO)(1.4)1.0-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 15June 6, 2013b) substitution of the lowest operational circulating water flow, in gal/min; and,c) substitution of the highest effluent release rate, in gal/min,d) substitution of the default monitor sensitivity.

The default setpoint equation is provided below:SP < ECe xlOxSENxCW

+bkgRR(1.5)1.3 LiquidEffluent Concentration Limits -10 CFR 20ODCM Normal Condition 13.1.1 limits the concentration oJ-hdi ive aterial in liquideffluents (after dilution in the Circulating Water Syst to ten times theconcentrations as specified in 10 CFR 20, Appen .a 27, p _, Column 2 forradionuclides other than noble gases. Noble gase J diluted concentration of 2E-04 pCi/ml. Release rates are controlled a adia itor alarm setpoints areestablished to ensure that these concentratio re n exceeded.

In the event anyliquid release results in an alarm setpoint

-g c an evaluation of compliance with the concentration limits of ODCM No I 13.1.1 may be performed usingthe following equation:

where:'(C1 CW)] l (1.6)Ci c ai of radionuclide "i" in the undiluted liquid effluentI )10xECi n ti es the EC value corresponding to radionuclide "i" from10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml),= 2E-04 pCi/ml for dissolved or entrained noble gasesRI- the liquid effluent release rate (gal/min)

CW- the circulating water flow rate (dilution water flow) at the time of0000000000000000000000000000000000000000tne reiease (gai/min) 1.0-4 KEWAUNEE POWER STATION ODCM 1.0* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013*P 1.4 Liquid Effluent Dose Calculation

-10 CFR 50O* 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 PowerStation to:0 during any calendar quarter;* < 1.5 mrem to total bodyS:5 5.0 mrem to any organ0 during any calendar year;* < 3.0 mrem to total body:5. 10.0 mrem to any organ.Per Verification Requirement 13.1.2.1, the follo calc tio al methods may be usedO for determining the dose or dose commitme e e id radioactive effluents from0 Kewaunee.

SO Do l "~~167E -

D.= CW Aj°) (1.7)0 where:0 D. e commitment to organ "o", including total bodySAo te- d ingestion dose commitment factor to the total body or, ny organ "o" for radionuclide "i" (mrem/hr per pCi/ml) (Table 1.2)= \ verage concentration of radionuclide "i", in undiluted liquid*effluent representative of the volume VOL (pCi/ml)0 V = volume of liquid effluent released (gal)SCW average circulating water discharge rate during release period(gal/min) 01.67E-02

= conversion factor (hr/min)0000O ~1.0- 50000 KEWAUNEE POWER STATION ODCM 1.0 UOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013The site-related ingestion doses/dose commitment factors (Ai,) are presented inTable 1.2 and have been derived in accordance with guidance of NUREG-0133 by theequation:

0A1o = 1. 14E + 05[(UW + D,,) + (UFx BFi)]DFi (1.8)where: 0Al = composite dose parameter for the total body or critical organ "o" ofan adult for radionuclide "i", for the fish ingestion and water 0consumption pathways (mrem/hr per pCi/ml)1.14E+05

= conversion factor (pCi/pCi x ml/kg -hr/y r0Uw = adult water consumption (730 kg/D= dilution factor from the near f it 4mile of the releasepoint to the nearest pot w e for the adult waterconsumption (84 2, UF " adult fish consumptk (2 d/y"BF1 = bioaccumulati a nuclide "i" in fish from Table 1.3(pCi/kg per DF1 = dose ye on or for radionuclide "iT for adults in pre-sele'e , ,n from Table E-11 of Regulatory Guide 1.109,1 a REG 0172, 1977 (mrem/pCi) 0The radionuclides-i n periodic dose assessment per the requirements ofODCM Normal n nt and Verification Requirement 13.1.2.1 are those asidentified by .spet ral analysis of the liquid waste samples collected andanalyzed per ifotn Requirement 13.1.1.1, Table 13.1.1-1.

s re. iring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added toth at a frequency consistent with the required minimum analysisfr Table 13.1.1-1.

In -)lie e individual radionuclide dose assessment as presented above, the following simplified dose calculational equation may be used for demonstrating compliance with Othe dose limits of ODCM Normal Condition 13.1.2. (Refer to Appendix A for thederivation and justification for this simplified method.)0002Adapted from the Kewaunee Final Environmental Statement,Section V.1.0-6 0 KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013* Total Body* DDb= 9.67E+ 03xVOLx C (1.9)CWMaximum OrganD.a= 1.18E+04xVOL xC, (1.10)* cwwhere:Ci = average concentration of radionuclid i ndiluted liquideffluent representative of the volume C./mi* VOL = volume of liquid effluent released 1)CW = average circulating water /ring release period* (gal/min)

Dt= conservatively evalua t I ose (mrem)Dmax = conservatively t um organ dose (mrem)9.67E+03

= product ofi r-to nute conversion factor (hr/min) and theconse e t tal dose conversion factor (Cs-1 34, total body--5.79 5 per ICi/ml)1.18E+04 d 0 hour-to-minute conversion factor (hr/min) and thea maximum organ dose conversion factor (Cs-134,* mrem/hr per pCi/ml)1.5 Liquid Effluent Dos 0 nsODCM mal d-ion 13.1.3 requires that the liquid radioactive waste processinged reduce the radioactive material levels in the liquid waste prior to5 relZse -31 day projected doses exceed:* 0. m to the total body, or0 0.2 mrem to any organ.*The applicable liquid waste streams and processing systems are as delineated inFigure 1.000~1.0-70000 06KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Dose projections are made at least once per 31 days by the following equations:

Dtbp= DDb(31 +d) (1.11)0Dnmp = + d) (1.12)where: 0Dtp= the total body dose projection for current 31 day period (mrem)Dt= the total body dose to date for current 31 da *d as determined by equation (1.7) or (1.9) (mrem)Dmaxp = the maximum organ dose projection fo o ren period (mrem)Dmax = the maximum organ dose to d 31 day period asdetermined by equation (1.7) od = the number of days to dat r en day period31 = the number of days in a y pod1.6 Onsite Disposal of Low-Level Radioactively o

StreamsDuring the normal operation ww n the potential exists for in-plant processstreams, which are not nol ly d_ etie to become contaminated with very lowlevels of radioactive mat

T aste streams are normally separated from theradioactive streams.

e ue mainly to infrequent, minor system leaks, andanticipated operation (c nc , the potential exists for these systems to becomeslightly contamin

.A e dnee, the secondary system demineralizer resins, theservice water P ea en em sludges, the make-up water system resins, and thesewage trea t sludges are waste streams that have the potential to becomecontaminate dt low levels. During the yearly testing of a batch of pre-treatment sludge, as d proximately 15,000 cubic feet of sludge had been contaminated with *nd-60.0 radation doses to MEMBERS OF THE PUBLIC from these onsite disposalm a well below 1 mrem per year. This dose is in keeping with the guidelines ofthe N Council on Radiation Protection (NCRP) in their Report No. 91, in which theNCRP established a "negligible individual risk level" at a dose rate of 1 mrem per year. 0It is for these type wastes that the NRC acknowledged in Information Notice No. 83-05and 88-22 that the levels of radioactive material are so low that control and disposal as aradwaste are not warranted.

The potential risks to man are negligible and the disposalcosts as a radwaste are unwarranted and costly.1001.0-80000 KEWAUNEE POWER STATION ODCM 1.0* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013This waste material will be monitored and evaluated prior to disposal to ensure itsradioactive material content is negligible.

It shall then be disposed of in a normalconventional 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,

I only service water pretreatment (SWPT) facility lagoon sludge and sewage treatment

plant sludge have been approved for disposal by land spreading.

00-*00-0-000*0000* 1.0-9 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 15June 6, 20134 = Sample/Monitor

= Isolation Devise(Damper or Valve)--= Auto Isolation

=This Flow Path shal onlybe used If orolected doescomply with ODCM O anTni Slpe~iticatlon (CA%1074)

Graphice No. CS73s.ODCM FIGURE 1LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM1.0-10 000000000000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 15June 6, 2013Table 1.1Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value* Units CommentsECe calculated 1.0E-06**

PCi/mI Calculate for each batch to be releaseddN/A PCi/mI Taken from gamma spectral analysisC measured NIof liquid effluentTaken from 10 CFR 20, Appendix B,EC1 as determined N/A pCi/mI Table 2, Col. 2Sensitivity (SEN)R-18 as determined 1.0E+08 Rad effluR-19 as determined 1.0E+08 cpm per S ra blowdownR-20 as determined 1.0E+08 pCi/ml rvi component coolingR-16 as determined 9.8E+07 aer -containment fan coolingr g Water System default =CW as determined 2.58E+05 gp te , single CW pumpRelease Rate(RR)R-1 8 as determined 8.OE+01 Determined prior to release; release ratecan be adjusted for requirement compliance R-1 9 as determined

2. Steam Generator A and B combinedR-20 as determined 5 + Service Water -component coolingR-16 as determined Service Water -Containment fan coolingBackground (bkg) <R-18 as determi .0 3 cpm Nominal values only; actual valuesR-19 as deter e + 01 may be used in lieu of these reference R-20 as de e .O-+01 valuesR-16 as x 8.0E+01Setpoint*

(SP) R-18 culat 5.OOE+05+bkg cpm Default alarm setpoints; moreS C5.E+05+bkg conservative values may be used asR-20 cu1 ul-aated 5.16E+04+bkg deem appropriate and desirable forR-16 ulated 1.68E+05+bkg assuring regulatory compliance and formaintaining releases ALARA.Setpoint*

(SP) with no Circulating Water System flow, CW=0R-18 calculated 6.25E+04+bkg For outages with no Circulating WaterR-19 calculated 2.50E+04+bkg cpm System flow (CW=0) and a dilution flowR-20 calculated 1.OOE+03+bkg as provided by the Service WaterR-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 thoseradiation monitors in accordance with CAP 37265 and DCR 26981.1.0-11 0KEWAUNEE POWER STATION ODCM 1.0 0OFFSITE DOSE CALCULATION MANUAL Revision 15Table 1.2 (Page 1 of 2) June6, 2013Site Related Ingestion Dose Commitment Factors(mrem/hr per uCi/ml)Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 -3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 0C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2P-32 1.39E+6 8.62E+4 5.36E+4 --1.56E+5Cr-51 --1.28E+O 7.63E-1 2.81 E-1 1.69E+0 3.21 E+2 0Mn-54 -4.38E+3 8.36E+2 -1.30E+3 1.34E+4Mn-56 -1.1OE+2 1.96E+1 -1.40E+2 3.52E+3Fe-55 6.61 E+2 4.57E+2 1.06E+2 ..2 ..... -.+.22. 2.62E+2Fe-59 1.04E+3 2.45E+3 9.40E+2 --8.17E+3Co-57 2.11E+1 3.51E+1 -.5.36E+2Co-58 8.99E+1 2.02E+2 -1.82E+3Co-60 2.58E+2 5.70E+2 -4.85E+3Ni-63 3.13E+4 2.17E+3 1.05E+3 -. -._ 4.52E+2Ni-65 1.27E+2 1.65E+1 7.52E+0 --4.18E+2Cu-64 1.01E+1 4.72E+0 -8.57E+2Zn-65 2.32E+4 7.38E+4 3.33E+4 -9 .4 -4.65E+4Zn-69 4.93E+1 9.43E+1 6.56E+0 E+1 -1.42E+1Br-82 -2.27E+3 -2.61 E+3 0Br-83 -4.05 -5.83E+ 1Br-84 4.12E-4Br-85 --' -+0-Rb-86 -1.01 E+5 4.7 .... .. 1.99E+4Rb-88 -2.90 _.W 4.00E-9Rb-89 -1. 9,4 2 1".ý 2 2.............--

.-.-.--.-------

Sr-89 2.24E+4 -6 +2 3.60E+3Sr-90 5.52E+5,-"

5E+5 _ _ ---1.59E+4Sr-91 4.13E-, 1.67E+1 -.-1.97E+3Sr-92 1.57 6.77E+0 3.10E+3... ....... ........................

.......................................

.....................................

..................

Sr-92_0 1.5.E-2 --621E+ 5Y-91m 2.14E-4 ---1.62E-2YIII1zz:zI

+ 2.2E- 4.72E+3Y-9 150E-3 _--- 9.OOE+20Y -9;" ----- -_-5 ()E ': ...................................

........ ........

-. .. .............

..........................

9. 0 E+-- --2Z" 1E ... .... .. .. ........ 5.87E-2 1.36E-1 2.75E+2Zr-97 1.49E-2 3.01E-3 1.38E-3 4.55E-3 9.34E+2Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 5Nb-97 3.75E+0 9.48E-1 3.46E-1 -1.11E+0 3.50E+3Mo-99 -1.07E+2 2.04E+1 -2.43E+2 2.49E+2Tc-99m 9.11E-3 2.58E-2 3.28E-1 -3.91E-1 1.26E-2 1.52E+1 0Tc-101 9.37E-3 1.35E-2 1.32E-1 -2.43E-1 6.90E-3 -0Ru-103 4.61E+0 1.99E+0 -1.76E+1 5.39E+2Ru-105 3.84E-1 1.52E-1 -4.96E+0 2.35E+2Ru-106 6.86E+1 8.68E+0 -1.32E+2 4.44E+3Rh-103m ----...0Rh-106 -- --1.0-12 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 1.2 (Page 2 of 2)Site Related Ingestion Dose Commitment Factors(mrem/hr oer uCi/ml)ODCM 1.0Revision 15June 6, 201300S0000000000000S00SS00000Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI10Ag0m. 1.04E+O 9.62E-1 5.71 E- -1.89E+0 .-3.92E+2Sb-124 9.48E+0 1.79E-1 3.76E+O 2.30E-2 -7.38E+0 2.69E+2Sb-125 6.06E+0 6.77E-2 1.44E+O 6.16E-3 -4.67E+0 6.67E+1Te-125m 2.57E+3 9.31E+2 3.44E+2 7.73E+2 1.04E+4 1.03E+4Te-127m 6.49E+3 2.32E+3 7.911E+2 1.66E+3 2.64E+4 -2.18E+4Te-127 1.05E+2 3.79E+1 2.28E+1 7.81E+1 4.29E+2 8.32E+3Te-129m 1.10E+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 5.55E+4Te-129 3.OIE+1 1.13E+1 7.33E+O 2.31E+1 1.27E+2 2.27E+1Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+41.89E+. 7.89E+8 5.96E+O 1.55E+- 8.27E+--

2.67E+O...........

....!.3. 1 ..............

-.... 1...........E....+.2"....

.2 2 E + ..1,2.6...

2... 7 0 +4.(. 5. .9 + 1Te-132 _2.42E+3 1.56E+3 1,47E+3 1.73E+3 1.50 7.39E+41-130 2.79E+1 8.23E+1 3.25E+1 6.97E+3 1.2 2 -70E1..... 1 .13.2. ...........

...49_E+0.......00E.1....7..0......+.-......7..E+2.3.76

.+..1-1.3....

1.54E+2 2.20E+2 1,26E+2 7.20E+4 5.79E+-1-132 7.49E+O 2.00E+1 7.01 E+ 70 1 E+2 3.76E+O1-133 5.24E+1 9.11E+1 2.78E+1 1.34Et4 \2,59E 8.19E+1T-14 3.91 E+0 1.06E+1 3.80E+0 1.84 9 96-31-135 1.63E+1 4.28E+1 1.58E+1 2. +6 +i--1 -4.83E+1Cs-134 2.98E+5 7.09E+5 5.79E+5 9E+5 7.61E+4 1.24E+4Cs-136 3.12E+4 1.23E+5 8.86E+4 -.85E+4 9.39E+3 1.40E+4Cs-.37 3.82E+5 5.22E+5 3.42E+ --1.77E+5 5.89E+4 1.01E+4Cs-138 2.64E+2 5.22E+2 2. 3.84E+2 3.79E+1 2.23E-3Ba-139 1.02E+O 7.30E-4 O -6.83E-4 4.14E-4 1.82E+0.....................................................

... .. ... .......Ba-..140"

........2...,5E.+

2 ... .26___ 9E- ..... -..9,.1.6,.E-2_..

1.54 E-1 ..4., 4.2..E+2.

..Ba-141 4.98E-1 3.76E- 6 _____3.50E-4 2.13E-4 ....-....Ba-142 2.25E-1 2.31 -1.95E-4 1.31E-4La-.40 1.52E-1 7" 2 -5.63E+3La-142 7.79E-3 .3 54V-.,b ,2E-4 --2.59E+1Ce-141 3.17E-2._

-2 2.43E-3 -9.95E-3 -8.195+1Ce-143 5.58E-3 _1 0 4.57E-4 -1.82E-3 -1.54E+2Ce-144 16 0 0 -1 8.87E-2 -O4.1E-1 -5.58E+2Pr-143 E -i 2.77E-2 -1.30E-1 -2.45E+3Pr-144 1. -- .61E-4 931E-5 -4.29E-4 ..........

.- ........Nd-147 .9E- 4.42E-1 2.65E-2 -9,1E-3 -2.12E+3.W........

..........

...5E.................

.8.1.O.......

Np29 2.97E-2 2.92E-3 1.61 E-3 -9. 1OE-3 -5.98E+21.0-13 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 1.3Bioaccumulation Factors (BFi)(pCi/kg per pCi/liter)*

ODCM 1.0Revision 15June 6, 2013Element Freshwater FishH 9.OE-01C 4.6E+03Na ...0E+02P 3.OE+03Cr 2.OE+02Mn 4.OE+02Fe I .OE+02......Cu....................5..

..r.........

.................................

.........

......................

................

.... ._! .. .... .... .............

...........

.. ...........

.. .! -...E.............

.. ..........................................

C u...............................

....................

.......................

.............

.5...........O E .... ...................................................

..... .........

.... ...................-

-.... ........

.. ....................

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

.........................

.............

--................

..... ............

r< 0.. .........

..... ..... ...... ...... ..c ... ..... ..........

................

.......Sr..... .........

I.5_0 ..................

Zr 00-------Nb E-+04Mo L> OE+01..T....c..............

.. .. ... ., E +O.................

..........

.... ..... ... .... .............

........................

.. .-, -, : ...............

........ ..... .. ...................

...: ::: : :: :::: ::: ::: : : : : : : : :::,EO.....

........ .........

....... .. ............

......--

..........

I..... ... ........

.Ru I.OE+00S.............. r...............

... ............

..............

....... ....... ..-- -.... ..........

4O E 0...RQ.. ..........

1.5E+012.3E+00Ba 4.OE+02.~~~ ..........

La 2.5E+01-------Ce 1.OE+00Nd 2.5E+01W 1.2E+03II6660000000000000000000000000000003/4!Np 1.OE+01* Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which is adapted from NUREG/CR-1336 and silver and antimony which are taken fromUCRL 50564, Rev. 1, October 1972.1.0-14 U KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20132.0 Gaseous Effluents Methodology

2.1 Radiation Monitoring Instrumentation and ControlsThe gaseous effluent monitoring instrumentation and controls at Kewaunee for controlling andO monitoring normal radioactive material releases in accordance with 10 CFR 50, Appendix A, Criteria 60and 64, are summarized as follows:O 2.1.1 Waste Gas Holdup SystemO The vent header gases are collected by the Waste Gas Holdup System. Gases may be recycledO to provide cover gas for the Chemical and Volume Control System Hold-Up Tanks(CVCS HUTs) or held in the Waste Gas Decay Tanks (WGDTs y prior to release.Waste Gas Decay Tanks are batch released after sampling analy .The tanks areO discharged via the Auxiliary Building vent. R-13 and/or R-14 oil b as monitoring and* automatic isolation.

In some cases, the gas in the CVC HUTs will not be lely depressurized to theWGDTs. CVCs HUTs will be isolated and discha Building Vent. R-13and/or R-14 provide noble gas monitoring, and at ad i istrative controls are required in* lieu of automatic isolation.

During a planned release, the administra 0 (s de the presence of an operator in theO Aux Building if R-13/R-14 levels are b ow .If levels are above 5,000 but below10,000 cpm, an operator will b the valve MG(R)-519A, B, or C area,in communication with the Control ,a be directed to manually shut the valve if levels* exceed 10,000 cpm.2.1.2 Condenser Evacuation S!The air ejector disch \-- it by R-15. Releases from this system are normally via theAuxiliary Building n ere~0 itored by R-13 and/or R-14.0 2.1.3 Containment PurO Contain t e ventilation is via the containment stack for the 36-inch RBV system butvia th u il' ing stack for the 2-inch vent and mini-purge blower system. The stackradiati ing system consists of:O oble gas activity monitor providing alarm and automatic termination of release(R-12 and R-21),O

an iodine sampler, and0

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.

2.0-1 00KEWAUNEE POWER STATION ODCM 2.0 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20132.1.4 Auxiliary Building VentThe Auxiliary Building vent receives discharges from the waste gas holdup system, condenser evacuation system, fuel storage area ventilation, Auxiliary Building radwaste processing areaventilation, 2-inch containment pressure relief purge/vent system, and Auxiliary Building generalarea. All effluents pass through the R-13 and/or R-14 channels which contain:* a noble gas monitor* an iodine sampler, and 0" a particulate sampler.

zThe noble gas monitor provides auto isolation of any waste gay tan elease and divertsother releases through the special ventilation system. Effi f are determined byinstalled flow measurement equipment or as a function of f , ati n curves).

Sampler 0flow rates are determined by flow rate instrumentation.

> 72.1.5 Containment Mini-PurgeNent System 0Slight pressure buildup in containment is a rri ev resulting from normal operation ofthe plant. Prior to exceeding 2 psig in con ,hi~xcess pressure is vented off. Air fromcontainment is routed to the Auxiliary B E system, via the post-LOCA hydrogenrecombiner piping and then out througl ia Building vent stack. The system is alsodesigned to allow a continuous su f resh to be introduced into containment via a mini-blower to purge gases. An alar t Building vent stack monitor (R-13 or R-14) orthe containment building ai o ivity monitors (R-11, R-12) provides automatic isolation.

2.1.6 Non-routine

Discharg, sPeriodically, noni reac s are made in the Auxiliary and Containment buildings thatmight allow the' fthe atmosphere, which contains some levels of radioactivity.

Thesebreaches irudeid not limited to, opening the Containment equipment hatch duringoutages, ho c walls or ceilings to allow for moving equipment in or out of theRadiol, y d Areas (RCAs). All efforts to maintain these areas at negative pressurewill b 0egative pressure cannot be maintained (i.e., more exhaust than supply fanvolume , E supply ventilation to the area must be secured.

Criteria for determining if andwhen a r occurs from these areas is provided in implementing procedures.

As possible, the effects of these possible releases shall be evaluated beforehand.

Any actual releases shallbe documented and included in the monthly, quarterly and annual reports as appropriate.

0A gaseous radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 2.20S002.0-20000 W KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013* 2.2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Containment and Auxiliary Building Vent MonitorPer the requirements of ODCM Normal Condition 13.3.2, alarm setpoints shall be established 01 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 tothe 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:FRACtb= [4.72E + 02 x X/Q x VFx E (Ci x K 500 (2.1)FRAC~, = [4.72E+02xX/QxVFx (Cix(Li +1.1M,))]

3000 (2.2)where:FRACtb fraction of the allowable relea total body based on the= tal bodyski based o hidentified radionuclide concenions an t release flow rateFRACskin fraction of the allowab el e on the identified radionuclide concentrati t release flow rate*./Q = annual average t a dispersion for direct exposure to noble* gas at the co ir IT OUNDARY location (sec/mi3, from Table 2.3)* VF = ventilati n4// ) rate for the applicable release point and monitorO (ft3llrn rolmNTe 2.2)Q iopf noble gas radionuclide "i" as determined by radioanalysis e (,Ci/cm3)Ki I .body dose conversion factor for noble gas radionuclioe "i"*m /yr per jiCi/m3, from Table 2.1)0Li beta skin dose conversion factor for noble gas radionuclide "i"(mrem/yr per giCi/m3, from Table 2. 1)Mi gamma air dose conversion factor for noble gas radionuclide "i'(mrad/yr per gCi/m3, from Table 2.1)1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 4.72E+02

= conversion factor (cm3/ft3 x min/sec)0*500 = total body dose rate limit (mrem/yr)

3000 = skin dose rate limit (mrem/yr) 2.0-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpointfor the Containment and Auxiliary Building vent monitors at Kewaunee may be calculated:

SP = [ (Ci x SENO ) FRAC]+ bkg(2.3)where:SP= alarm setpoint corresponding to the maximum allowable release rate(cpm)SENi = the sensitivity value to which the monitor is ca ed for radionuclide "i"(cpm per jiCi/cm3), use the default value fr Ta 2.2 if radionuclide specific sensitivities are not available bkg = background of the monitor (cpm)2.2.2 Conservative Default ValuesA conservative alarm setpoint can be estab e , Ii of the individual radionuclide evaluation based on the grab sample analysis 4 elid- a potential of periodically having toadjust the setpoint to reflect minor changes in ucl* distribution and variations in releaseflow rate. The alarm setpoint may be co ti y rmined by the default values presented in Table 2.2. These values are based u n Na) substitution of the maxim e lat' w rate,b) substitution of a radj cli distribution 1 comprised of 95% Xe-133, 2% Xe-135, 1%Xe-133m, 1% Kr- nd 0 -5; and,c) application tive multiplier of 0.5 to conservatively assure that anysimultaneo el es not exceed the maximum allowable release rate.For ' r uie distribution, the alarm setpoint based on the total body dose rate ism r I an the corresponding setpoint based on the skin dose rate. The resulting co ti, default setpoints are presented in Table 2.2.0000000S000000SSSSS000S00000S0S00SAdopted from ANSI N237-1976/ANS-1 8.1, Source Term Specifications, Table 6.2.0-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 20132.3Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 200000SS000002.3.1 SITE BOUNDARY Dose Rate -Noble Gases.ODCM Normal Condition 13.2.1.a limits the dose rate at the SITE BOUNDARY due to noble gasreleases to < 500 mrem/yr to the total body, and < 3000 mrem/yr to the skin. Radiation monitoralarm setpoints are established to ensure that these release limits are not exceeded.

In theevent any gaseous releases from the station results in the alarm setpoints being exceeded, anevaluation of the UNRESTRICTED AREA dose rate resulting from the release may beperformed using the following equations:

Db=XIQX I(KxQijandr, = /Qxj(Li +1.1tvtotal bodvý ir(2.4)(2.5)where:D tbD.nrem/yr)QiK,-p6spheiFic dispersion for direct exposure to noble gas at the controlling BOUNDARY (sec/m3, from Table 2.3)-average release rate of radionuclide "i" over the release period underS evaluation (gCi/sec)

-total body dose conversion factor for noble gas radionuclide "i"(mrem/yr per gCi/mi3, from Table 2.1)beta skin dose conversion factor for noble gas radionuclide "i"(mrem/yr per giCi/m3, from Table 2.1)gamma air dose conversion factor for noble gas radionuclide "i" (mradlyrper IaCi/m3, from Table 2.1)mrem skin dose per mrad gamma air dose (mrem/mrad)

Mi1.12.0-5 06KEWAUNEE POWER STATION ODCM 2.0 0OFFSITE DOSE CALCULATION MANUAL Revision 15 6June 6, 2013Actual meteorological conditions concurrent with the release period or the default, annualaverage dispersion parameters as presented in Table 2.3 may be used for evaluating thegaseous effluent dose rate.2.3.2 SITE BOUNDARY Dose Rate -Radioiodine and Particulates SODCM 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 tothe 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. Thefollowing equation may be used for the dose rate evaluation:

D.X/Q x ZRXQj (2.6)0-0where:D. = average organ dose rat ve e s ling time period (mrem/yr) 0x/Q = atmospheric disp o controlling SITE BOUNDARY for theinhalation pathwa rom Table 2.3)R= dose par e r nuclide "", (mrem/yr per jiCi/m3) for the child Table 2.6C~j/ 0Qi el e rate over the appropriate sampling period and analysisfre/enc y~r radionuclide "i", 1-131, 1-133, tritium or other radionuclide inulate form with half-life greater than 8 days (gCi/sec)

By sub .0 rem/yr for D'o solving forQi, an allowable release rate for 1-131 can bedeter e s on the annual average meteorological dispersion (see Table 2.3) and themost Itwi

pathway, age group and organ (inhalation

pathway, child thyroid -0Ri = 1.62 mremlyr per igCi/m3) the allowable release rate for 1-131 is 6.43 jiCi/sec.

Anadded conservatism factor of 0.25 has been included in this calculation to account for any 0potential dose contribution from other radioactive particulate material.

For a 7-day period, whichis the nominal sampling and analysis frequency for 1-131, the cumulative allowable release is3.9 Ci. Therefore, as long as the 1-131 releases in any 7-day period do not exceed 3.9 Ci, noadditional analyses are needed to verify compliance with the ODCM Normal Condition 13.2.1.b 5limits on allowable release rate.0S002.0-6000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 20132.4Gaseous Effluent Dose Calculations

-10 CFR 5000SS00S0S00000000S02.4.1 UNRESTRICTED AREA Dose -Noble GasesODCM Normal Condition 13.2.2 requires a periodic assessment of releases of noble gases toevaluate compliance with the quarterly dose limits of (< 5 mrad, gamma-air and < 10 mrad,beta-air) and the calendar year limits (5 10 mrad, gamma-air and < 20 mrad, beta-air).

Thefollowing equations may be used to calculate the gamma-air and beta-air doses:D-, = 3.17E -08x /Q x I(M X Qi)and(2.7)(2.8)D,6 = 3.17E- 08 x 7/Q x I (Ni x Qi)where:= air dose due to gamma= air dose due tole gas radionuclides (mrad))ble gas radionuclides (mrad)Iling SITE BOUNDARY (sec/m3, fromx/QQigas radionuclide "i" over the period of interest-atdue to gamma emissions from noble gas radionuclide "i"W /iCi/m3 from Table 2.1)factor due to beta emissions from noble gas radionuclide "i"per giCi/m3, Table 2.1)Ni3.1conversion factor (yr/sec)In lieu of~j..!ndividual noble gas radionuclide dose assessment as presented above, thefollowing simplified dose calculational equation may be used for verifying compliance with thedose limits of ODCM Normal Condition 13.2.2. (Refer to Appendix B for the derivation andjustification for this simplified method.)Dy= 3.17E-08XX/QxMCfxzQ, 0.50(2.9)andDt = 3.17E- 08 xX/Q xNetr x E Qi0.50(2.10)2.0-7 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013where:MeffNeff0.50= 5.3E+02 effective gamma-air dose factor (mrad/yr per jiCi/m3)= 1.1 E+03 effective beta-air dose factor (mrad/yr per igCi/m3)= conservatism factor2.4.2Actual meteorological conditions concurrent with the release period or the default, annualaverage dispersion parameters as presented in Table 2.3, may be used for the evaluation of thegamma-air and beta-air doses.UNRESTRICTED AREA Dose -Radioiodine and Particulates Per the requirements of ODCM Normal Condition 13.2.3 p 1 sessment shall beperformed to evaluate compliance with the quarterly dose .5 1m) and calendar yearlimit (_< 15 mrem) to any organ. The following equatio bs o evaluate the maximumorgan dose due to releases of 1-131, 1-133, tritium pa Itwith half-lives greater than8 days:D.op =3.17E -08 x W x SFp x -(%1 X (2.11)where:Daop = dose or d c mi for age group "a" to organ "o", including thetotal boiyiA "p" from 1-131, 1-133, tritium and radionuclides inPart'Iaeo with half-life greater than eight days (mrem)W = ric/ spersion parameter to the controlling location(s) ase.fi able 2.3X!Q = ospheric dispersion for inhalation pathway and H-3 dose contribution I her pathways (sec/m3)D/Q / .tmospheric deposition for vegetation, milk and ground plane exposurepathways (I/mr)Ri dose factor for radionuclide "i", (mrem/yr per gCi/m3) or (M2 -mrem/yr perpCi/sec) from Table 2.4 through 2.15 for each age group "a" and theapplicable pathway "p" as identified in Table 2.3. Values for R1 werederived in accordance with the methods described in NUREG-0133.

0000000000000000000000000000000000000000000Qi= cumulative release over the period of interest for radionuclide "i" -- 1-131or radioactive material in particulate form with half-life greater than 8 days(RCi).2.0-8

KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20130SFP seasonal correction factor to account for the fraction of the period that theapplicable exposure pathway does exist.1) For milk and vegetation exposure pathways:

S# of months in the period that grazing occurs*total # of months in period= 0.5 for annual calculations

2) For inhalation and ground plane expo epways: = 1.0In lieu of the individual radionuclide (1-131 and particulates se e ent as presented above, the following simplified dose calculational equation r bse verifying compliance 0 with the dose limits of ODCM Normal Condition 13.2.3. \V'77,*D. = 3.17E -08x WxSFpx Ri-131 Q (2.12)where:Dmax maximum organ eRI-13 = 1-131 dose p tor thyroid for the identified controlling pathwayS 1.05E+, dose parameter with the grass-cow-milk pathway nrem/yr per gCi/sec)The ground plane ex e d i lation pathways need not be considered when the above-simplified calculati m ho used because of the overall negligible contribution of thesepathways to th o, oid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and the ground plane exposure pathway may represent a higher dosecontribution an ei vegetation or grass-cow-milk pathway.

However, use of the 1-131thyroid for all radionuclides will maximize the organ dose calculation, especially considki tb]a ther radionuclide has a higher dose parameter for any organ via any* pathwa 31 for the thyroid via the grass-cow-milk pathway.The locatitoof exposure pathways and the maximum organ dose calculation may be based onthe available pathways in the surrounding environment of Kewaunee as identified by the annual0land-use census. Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2.3.20000*2.0- 900 SOKEWAUNEE POWER STATION ODCM 2.0 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20132.5 Gaseous Effluent Dose Projection 0ODCM Normal Condition 13.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM beused to reduce radioactive material levels prior to discharge when projected doses exceed one-half theannual design objective rate in any 31 days, i.e., exceeding:

0* 0.2 mrad, gamma air,* 0.4 mrad, beta air, or0 0.3 mrem, maximum organ. 0The applicable gaseous release sources and processing systems are atei Figure 2.Dose projections are performed at least once per 31 days by the fo i ns:Dp = Dy x (31÷ d) (2.13)D.p= Dp x(31d) (2.14)D.,v= D. x(31 d) (2.15)where:D-p gamma ai tion for current 31 day period (mrad) SD- ga a do to date for current 31 day period as determined by;ttb6{2.7 r (2.9) (mrad)DI~ppair d se projection for current 31 day period (mrad)Dp \.8 air dose to date for current 31 day period as determined by equation 02~.8) or (2.10) (mrad)Dmaxp maximum organ dose projection for current 31 day period (mrem)Dmax maximum organ dose to date for current 31 day period as determined byequation (2.11) or (2.12) (mrem)d number of days to date in current 31 day period31 number of days in a 31 day period S2SSS2.0- 10SSS 0* KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20132.6 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 may0be 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 (TLDmeasurements) 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 OilDuring plant operation, radioactively contaminated oils are generate m V eces of equipment operating in the plant. The largest source of contaminated oil is th a co t pump lubricating oil, which is periodically changed for preventive maintenance re Part 20 allowslicensees-to incinerate radioactively contaminated oils on sit vi e total radioactive effluents from the facility conform to the requirements of 1 Par ppendix 1.Radioactively contaminated oil, which is designate r i ne n, will be collected in containers, which are uniquely serialized such that the conten c ide5Ofied and tracked.

Each container will* be sampled and analyzed for radioactivity.

oto'NAi centrations will be recorded for eachcontainer.

The heating boiler will be utilized to in t rah actively contaminated oil collected on site. Agaseous radwaste effluent dose c c rescribed in Section 2.3 of the ODCM, will beperformed to ensure that the limit ab d by ODCM Normal Condition 13.2.1, 13.2.2 and 13.2.3are not exceeded.

Release of assumed to occur at the time the contaminated oil istransferred into the heating b il s ge tank and will be accounted for using established plant*procedures.

This will be v o n ed release from the fuel oil storage tank vent, fill piping, orfrom the boiler exhaust sFige 3 for a description of the heating boiler fuel oil system.2.8 Total Do eThe purpose/

i," sis to describe the method used to calculate the cumulative dose0 contributions 1A d gaseous effluents in accordance with KPS Technical Specifications fortotal dose. m od can also be used to demonstrate compliance with the Environmental Protection Agen ) 40CFR190, "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*1 public. With the calculated doses from the releases of radioactive materials in liquid or gaseouseffluents 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 directradiation contributions from the facility, from outside storage areas and from all real pathways) is limited I*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.0*2.0- 11000 00KEWAUNEE POWER STATION ODCM 2.0 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013If required, the total dose to a MEMBER OF THE PUBLIC will be calculated for all significant effluentrelease points for all real pathways including direct radiation.

Effluent releases from Point BeachNuclear Plant must also be considered due to its proximity.

Calculations will be based on the equations in Sections 1.4, 2.4.1, and 2.4.2, with the exception that usage factors and other site specificparameters 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 areasaccessible to the general public at the location of maximum direct radiation.

It is recognized that byincluding the results from the environmental TLDs into the sum of total dose component, the directradiation dose may be overestimated.

The TLD measurements may include the exposure from noblegases, ground plane deposition, and shoreline deposition, which have al een included in thesummation of the significant dose pathways to the general public. How this nservative methodcan be used, if required, as well as any other method for estimatin hi\ 4rc)rpcdiation dose fromcontained radioactive sources within the facility.

The mel u orporate the directradiation component into total dose estimates will be outlined when r I s are reported.

Therefore, the total dose will be determined based on m tic site specific data andparameters to assess the real dose to any MEMBER OF UBLI--0000002.0- 00 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013AuxliajyBudingVentStock

(~Nb~re shield building ventilation and special ventilation are ESF systems and are not part of the= Sample/Monitor p = Pre normal effluent processing system. They are Included for completeness only.= Isolation Devise h = HEPA !, The containment air sampler (R 1I and radiation monitor (R12) can also be aligned as needed(Damper or Valve) = rc ) for sampling containment vent.c = Charcoal Iter= 3 Was Valve= Auto Isolation Graphics No. CS75M3ODCM FIGURE 2GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM2.0-13 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013Figure 3Simplified Heating Boiler Fuel Oil Piping SystemHeating Boger Fuel OU Storage Tank heating boller30,000 Gallons fuel all pumps2.0-140000000000000000000000000000000000000000000o 000S0000000000000000,0000000000SKEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013Table 2.1Dose Factors for Noble GasesTotal Body Dose Skin Dose Factor Gamma Air Dose Beta Air DoseFactor Ki L, (mremlyr per Factor M, Factor N,Radionuclide (mrem/yr per IJCilm3) (mradlyr per (mradlyr perPCI/m3) pCilm3) PCilm3)Kr-83m 7.56E-02 1.93E+01

,88E+02Kr-85m 1.17E+03 1.46E+03 1.23E+03

1. E+03Kr-85 1.61E+01 1.34E+03 1.72E+Of

/ 195E+03Kr-87 5.92E+03 9.73E+03

__1.03E+04 Kr-88 1.47E+04 2.37E+03

1. + 2.93E+03Kr-89 1.66E+04 1.01E+04

.7 +04 1.06E+04Kr-90 1.56E+04 7.29E+04 L .63E+04 7.83E+03Xe-1 31 m 9.15E+01 1.56E+02 1.11E+03Xe-133m 2.51E+02 9 3.27E+02 1.48E+03Xe-133 2.94E+02 0! 02 3.53E+02 1.05E+03Xe-135m 3.12E6 3.36E+03 7.39E+02Xe-135 1 N .86E+03 1 .92E+03 2.46E+03Xe- 137 ,N2ý 1.22E+04 1.51E+03 1.27E+04Xe-138 8.88 -03 4.13E+03 9.21E+03 4.75E+03Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+032.0-15 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.2Parameters for Gaseous Alarm Setpoint Determinations ODCM 2.0Revision 15June 6, 2013Parameter Actual Value Default Value* Units CommentsY]Q calculated 3.6E-06 sec/in3 Licensing technical specification

!_acad 3E6s/ valueContainment

-normal plusVF fan curves 26,000 cfm purge modes54,000 Auxiliary Building

-normal QC measured N/A pCi/m3 <<VVnuclide mrem/yr perKi specific N/A _JCi/m3 _____ _2.1m ~nuclide mrem/yr" perVa /Li nddeN/A firi/yr per s fr Table 2.1Mi nuclide N/A mrem/y er from Table 2.1Sensitivity**"

s fi(SEN)R-12 2.32E+07 m Containment R-21 as determined 2.32E+07 Containment R-13 2.32E+07 Auxiliary BuildingR-14 2.32E+07/Z Auxiliary BuildingBackground (bkg)R-12 as determined 4 Nominal values only; actualR-21 adeemndvalues may be used in lieu ofR-13 E0 these reference values.R-14 ___Setpoint*

(SP) Default alarm setpoints; moreR-12 calc d 2.8E+05+bkg conservative values may beR-21 Ia 2.8E+05+bkg cpm used as deemed appropriate R-13 a 1.3E+05+bkg and desirable for ensuringR-14 d 1.3E+05+bkg regulatory compliance and for_ in_ _maintaining releases ALARA.* Refer to Calculation

C10690 for the default setpoint calculation.

Conservatively based on Xe-133 sensitivity.

000000000000000000000000000000000000000000002.0-16 000000S000000000SS0000KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Table 2.3Controlling Locations, Pathways andAtmospheric Dispersion for Dose Calculations Atmospheric Dispersion ODCM NormalCondition Location Pathways x/Q (seclm3) D/Q (/lm2)13.2.1 .a Site Boundary Noble gases 7.44E-07 N/A(0.81 mile, NNW) Direct exposure

,___________-_

13.21.b Site Boundary Inhalation, (0.81 mile, NNW) Ground Plane 7. 0CSite Boundary Gamma Air 4- N7A13.2.2 (0.81 mile, NNW) Beta Air _"___"___,__NI Residence/dairy Inhalation, 13.2.3 (1.3 mile S) Vegetation, Mil X 1.86E-092.0-17 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.4 (Page 1 of 2)Ri Inhalation Pathway Dose Factors-ADULT(mrem/yr per pCi/m3)ODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4P-32 1.32E+6 7.71 E+4 8-Wo4-+4 5.01 E+4Cr-51 --5.95E+1 2.28E+1 1.44 E+4/ /3.3_ 3 1.OOE+2Mn-54 -3.96E+4 -9.84E+3 1.40E,6X

,.74E 6.30E+3Mn-56 -1.24E+0 -1.30E+0 9.4,4 3 ."? 4 1.83E-1Fe-55 2.46E+4 1.70E+4 --7.!ýX +, ,05E+3 3.94E+3Fe-59 1.18E+4 2.78E+4 --.-Q .88E+5 1.06E+4Co-57 -6.92E+2 --3.XX+)V 3.14E+4 6.71E+2Co-58 -1.58E+3 --9.28) 5 1.06E+5 2.07E+30o-60 -1.15E+4 --+6 2.85E+5 1.48E+4Ni-63 4.32E+5 3.14E+4 -.8E+5 1.34E+4 1.45E+4Ni-65 1.54E+0 2.10E-1 -/,"5.60E+3 1.23E+4 9.12E-2Cu-64 -1.46E+0 -6.78E+3 4.90E+4 6.15E-1Zn-65 3.24E+4 1.03E+5 -.9 +4 8.64E+5 5.34E+4 4.66E+4Zn-69 3.38E-2 6.51E-2 -.E-2 9.20E+2 1.63E+1 4.52E-3Br-82 -1.04E+4 1.35E+4Br-83___,,__"

-<1 2.32E+2 2.41 E+2Br-84 1.64E-3 3.13E+2Br-85 -_ ,,-,_,__

.-1.28E+1Rb-86 -______,,/-1.66E+4 5.90E+4Rb-88 -2 3.34E-9 1.93E+2Rb-89 -g2_+2 1.70E+2Sr-89 _____1.40E+6 3.50E+5 8.72E+3Sr-90 9.60E+6 7.22E+5 6.1OE+6Sr-91 ______9___,___3.65E+4 1.91E+5 2.50E+0Sr-92_,_.__-_)

-_1.65E+4 4.30E+4 2.91 E-1Y-90 2.,2_,_W 1.70E+5 5.06E+5 5.61E+1Y-91 r 2._611r=-

11.92E+3 1.33E+0 1.02E-2Y-91 4.62E+5 1.70E+6 3.85E+5 1.24E+4Y-92 1.03E+1 1.57E+4 7.35E+4 3.02E-1Y-93 9.44E+1 4.85E+4 4.22E+5 2.61 E+0Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 2.33E+4Zr-97 9.68E+1 1.96E+1 -2.97E+1 7.87E+4 5.23E+5 9.04E+0Nb-95 1.41 E+4 7.82E+3 -7.74E+3 5.05E+5 1.04E+5 4.21E+3Nb-97 2.22E-1 5.62E-2 -6.54E-2 2.40E+3 2.42E+2 2.05E-2Mo-99 -1.21 E+2 -2.91E+2 9.12E+4 2.48E+5 2.30E+1Tc-99m 1.03E-3 2.91 E-3 -4.42E-2 7.64E+2 4.16E+3 3.70E-2Tc-101 4.18E-5 6.02E-5 -1.08E-3 3.99E+2 -5.90E-4000000000000000000000000000000000000000000002.0-18 0000000000000000000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.4 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -ADULT(mrem/yr per pCi/m3)ODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.53E+3 -5.83E+3 5.05E+5 1.10E+5 6.58E+2Ru-105 7.90E-1 --1.02E+0 1.1OE+4 4.82E+4 3.11E-1Ru-106 6.91E+4 --1.34E+5 9.36E+6 9.12E+5 8.72E+3Rh-103m --Rh-106 -Ag-110m 1.08E+4 1.OOE+4 1.97E+4 4.63E+6 /.+5 5.94E+3Sb-124 3.12E+4 5.89E+2 7.55E+1 -2.48E+6 4.061ý5 1.24E+4Sb-125 5.34E+4 5.95E+2 5.40E+1 -1.74 Q 01,95 1.26E+4.Te-1 25m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3 +5; PZYý+4 4.67E+2Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 .6 /.50E+5 1.57E+3Te-127 1.40E+0 6.42E-1 1.06E+0 5.10 E+0 .5.74E+4 3.10E-1Te-129m 9.76E+3 4.67E+3 3.44E+3 3.661 +'X 1.1 O+6v 3.83E+5 1.58E+3Te-129 4.98E-2 2.39E-2 3.90E-2 1.W-1 N J.9.X_+3 1.57E+2 1.24E-2Te-131m 6.99E+1 4.36E+1 5.50E+1 .Ey;> 'IAE+5 5.56E+5 2.90E+1Te-131 1.11E-2 5.95E-3 9.36E-3 r54. W2 / 1.39E+3 1.84E+1 3.59E-3Te-132 2.60E+2 2.15E+2 1.90E+;"

1, 2.88E+5 5.1OE+5 1.62E+21-130 4.58E+3 1.34E+4 0 7.69E+3 5.28E+31-131 2.52E+4 3.58E+4 1 tR-)7 , +4 -6.28E+3 2.05E+41-132 1.16E+3 3.26E+3 14 , 18E+3 -4.06E+2 1.16E+31-133 8.64E+3 1.48E+4 / + 2.58E+4 -8.88E+3 4.52E+31-134 6.44E+2 1.73_, /4.9"e4 2.75E+3 -1.01E+0 6.15E+21-135 2.68E+3 6.98 , 44.4 5 1.11E+4 -5.25E+3 2.57E+3Cs-134 3.73E+5 ,8" tb,\,ZZ 2.87E+5 9.76E+4 1.04E+4 7.28E+5Cs-136 3.90E+4 .4_4-5 " _ 8.56E+4 1.20E+4 1.17E+4 1.10E+5Cs-137 4.78E+ + 5 -2.22E+5 7.52E+4 8.40E+3 4.28E+5Cs-138 3.31+2 ""6 +2 4.80E+2 4.86E+1 1.86E-3 3.24E+2Ba-139 9.36 ý. 6E-4 6.22E-4 3.76E+3 8.96E+2 2.74E-2Ba-140 .,E , OE+I 1.67E+1 1.27E+6 2.18E+5 2.57E+3Ba-141 7.53E-5 7.OOE-5 1.94E+3 1.16E-7 3.36E-3Ba-142 .63 2.70E-5 2.29E-5 1.19E+3 -1.66E-3La-140 3 +2 1.74E+2 1.36E+5 4.58E+5 4.58E+1La-142 6.83E-1 3.1OE-1 6.33E+3 2.11E+3 7.72E-2Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3Ce-143 1.86E+2 1.38E+2 6.08E+1 7.98E+4 2.26E+5 1.53E+1Ce-144 3.43E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.OOE+5 4.64E+2Pr-144 3.01E-2 1.25E-2 7.05E-3 1.02E+3 2.15E-8 1.53E-3Nd-147 5.27E+3 6.10E+3 -3.56E+3 2.21E+5 1.73E+5 3.65E+2W-187 8.48E+0 7.08E+0 -2.90E+4 1.55E+5 2.48E+0Np-239 2.30E+2 2.26E+1 -7.00E+1 3.76E+4 1.19E+5 1.24E+12.0-19 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.5 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -TEEN(mrem/yr per pCi/rn3)ODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3Na-24 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4P-32 1.89E+6 1.1OE+5 --9.28E+4 7.16E+4Cr -7.50E+1 3.07E+1 2.1OE+4 3 1.35E+2Mn-54 -5.11E+4 -1.27E+4 1.98E+6 ..68E+4N 8.40E+3Mn-56 -1.70E+0 -1.79E+0 1.52E+4 E+ 2.52E-1Fe-55 3.34E+4 2.38E+4 --5.54E+3Fe-59 1.59E+4 3.70E+4 --1.53 1. +5 1.43E+4Co-57 -6.92E+2 --

9.20E+2Co-58 2.07E+3 --<-13 -"9.52E+4 2.78E+3Co-60 -1.51E+4 -I Z2 2.59E+5 1.98E+4Ni-63 5.80E+5 4.34E+4 --3.' +5 1.42E+4 1.98E+4Ni-65 2.18E+0 2.93E-1 --, 6E+3 3.67E+4 1.27E-1Cu-64 -2.03E+0 -.4 4 11 E+4 6.14E+4 8.48E-1Zn-65 3.86E+4 1.34E+5 -, 4 1.24E+6 4.66E+4 6.24E+4Zn-69 4.83E-2 9.20E-2 -0 2 1.58E+3 2.85E+2 6.46E-3Br-82 --_,_____--

1.82E+4Br-83 ---_____,V_,__-"--

3.44E+2Br-84 -__,__ -4.33E+2Br-85 --, 1.83E+1Rb-86 -1.77E+4 8.40E+4Rb-88 -2.92E-5 2.72E+2Rb-89 -+2_-,,_ -3.38E-7 2.33E+2Sr-89 4.34E+5 --2.42E+6 3.71 E+5 1.25E+4Sr-90 1.0 ---1.65E+7 7.65E+5 6.68E+6Sr-91 -OEE+ 6.07E+4 2.59E+5 3.51 E+OSr-92 9 ---2.74E+4 1.19E+5 4.06E-1Y-90 '" BEt ---2.93E+5 5.59E+5 8.00E+1Y-91 m 3. ---3.20E+3 3.02E+1 1.42E-2Y-91 6.61 E+5 --2.94E+6 4.09E+5 1.77E+4Y-92 1.47E+1 ---2.68E+4 1.65E+5 4.29E-1Y-93 1.35E+2 ---8.32E+4 5.79E+5 3.72E+0Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4Zr-97 1.38E+2 2.72E+1 -4.12E+1 1.30E+5 6.30E+5 1.26E+1Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51 E+5 9.68E+4 5.66E+3Nb-97 3.14E-1 7.78E-2 -9.12E-2 3.93E+3 2.17E+3 2.84E-2Mo-99 -1.69E+2 -4.11 E+2 1.54E+5 2.69E+5 3.22E+1Tc-99m 1.38E-3 3.86E-3 -5.76E-2 1.15E+3 6.13E+3 4.99E-2Tc-101 5.92E-5 8.40E-5 -1.52E-3 6.67E+2 8.72E-7 8.24E-400600000000000000000000000000000000000002.0-20 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.5 (Page 2 of 2)R, Inhalation Pathway Dose Factors -TEEN(mrem/yr per pCi/rn3)ODCM 2.0Revision 15June 6, 201300000000000000000000Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 2.1OE+3 -7.43E+3 7.83E+5 1.09E+5 8.96E+2Ru-105 1.125+0 ---1.41E+0 1.82E+4 9.04E+4 4.34E-1Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4Rh-103m ---Rh-1 06 --Ag-11Orn 1.38E+4 1.31E+4 -2.50E+4 6.75E+6<

.73 7.99E+3Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E, \V 98E4 1.68E+4Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.7,,4 W)6 1.72E+4Te-125m 4.88E+3 2.24E+3 1.40E+3 -5. + 7,,, 4 6.67E+2Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 -+,,.59E+5 2.18E+3Te-127 2.01E+O 9.12E-1 1.42E+0 7.28E+,/

1. + 8.08E+4 4.42E-1Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19,:*\

X1.98F6 4.05E+5 2.25E+3Te-129 7.10E-2 3.38E-2 5.18E-2 2 -.+3 1.62E+3 1.76E-2Te-131m 9.84E+1 6.01E+1 7.25E+1 48E+5 6.21 E+5 4.02E+1Te-131 1.58E-2 8.32E-3 1.24E-2.-,-

S. 2 /,2.34E+3 1.51E+1 5.04E-3Te-132 3.60E+2 2.90E+2 2.46E-ýZ

ý 4.49E+5 4.63E+5 2.19E+21-130 6.24E+3 1.79E+4 12 +F 2.7 +4 -9.12E+3 7.17E+31-131 3.54E+4 4.91E+4 ,,64'7 E44 5+4 -6.49E+3 2.64E+41-132 1.59E+3 4.38E+3-

\",ft

-1.27E+3 1.58E+31-133 1.22E+4 2.05E, 2. %ý+6 3.59E+4 -1.03E+4 6.22E+31-134 8.88E+2 2.32"3 / ).9.5 14 3.66E+3 -2.04E+1 8.40E+21-135 3.70E+3 .68X +5 1.49E+4 -6.95E+3 3.49E+3Cs-134 5.02E+5 1 .+- 3.75E+5 1.46E+5 9.76E+3 5.49E+5CS-1 36 5.15E+A +5 -1.10E+5 1.78E+4 1.09E+4 1.37E+5Cs-137 6.70E+5 &.44E+5 -3.04E+5 .1.21E+5 8.48E+3 3.11E+5Cs-138 4.ffg +2 5 +2 -6.62E+2 7.87E+1 2.70E-1 4.46E+2Ba-139 , iZ\-0 44E-4 -8.88E-4 6.46E+3 6.45E+3 3.90E-2Ba-140 5 ..70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3Ba-141 ., 1 1.06E-4 -9.84E-5 3.29E+3 7.46E-4 4.74E-3Ba-142 2 3.70E-5 -3.14E-5 1.91E+3 -2.27E-3La-140 4. 9E+2 2.36E+2 -2.14E+5 4.87E+5 6.26E+1La-142 9.60E-1 4.25E-1 --1.02E+4 1.20E+4 1.06E-1Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3Ce-143 2.66E+2 1.94E+2 -8.64E+1 1.30E+5 2.55E+5 2.16E+1Ce-144 4.89E+6 2.02E+6 -1.21 E+6 1.34E+7 8.64E+5 2.62E+5Pr-143 1.34E+4 5.31 E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2Pr-144 4.30E-2 1.76E-2 -1.01E-2 1.75E+3 2.35E-4 2.18E-3Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2W-187 1.20E+1 9.76E+O -4.74E+4 1.77E+5 3.43E+0Np-239 3.38E+2 3.19E+1 -1.OOE+2 6.49E+4 1.32E+5 1.77E+12.0-21 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.6 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -CHILD(mrem/yr per pCi/m3)ODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4P-32 2.60E+6 1.14E+5 ---4.22E+4 9.88E+4Cr-51 -8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2Mn-54 -4.29E+4 -1.OOE+4 1.58E+6 2.29.ii .51E+3Mn-56 -1.66E+0 -1.67E+0 1.31E+4 1.2X+5 .7+2E-1Fe-55 4.74E+4 2.52E+4 --1.11E+5Fe-5 I 3.34E 7E+3Fe-59 2.07E+4 3.34E+4 --.+.27E+7E

.+ .67E+4Co-57 -9.03E+2 --5.07F , +- .2F,,0 1.07E+3Co-58 -1.73- ',W43163Co-60 -1.31E+4 E+6 .692E+4 2.26E+4Ni-63 8.21 E+5 4.63E+4 -Z. -,18 , '6.33E+3 E.+ 32.80E+4Ni-65 2.99E+0 2.96E-1 -< 18 8.40E+4 1.64E-1Cu-64 -1.99E+0 -.-9.,+3 3.67E+4 1.07E+0Zn-65 4.26E+4 1.13E+5.

4;5E+5 1.63E+4 7.03E+4Zn-69 6.70E-2 9.66E-2-E 1.42E+3 1.02E+4 8.92E-3Br-82 --____- 2.09E+4Br-83 -___,/____

4.74E+2Br-84 -__,._,, 5.48E+2Br-85 -2.53E+1Rb--86 -7.99E+3 1.14E+5R__-88 _ 2E -1.72E+1 3.66E+2Rb-89

--1.89E+0 2.90E+2Sr-89 5.99F-+5

--2.16E+6 1.67E+5 1.72E+4Sr-90 1.0 ---1.48E+7 3.43E+5 6.44E+6Sr-91 E+- -5.33E+4 1.74E+5 4.59E+0Sr-92 --- _ 2.40E+4 2.42E+5 5.25E-1Y-90 11 o ---2.62E+5 2.68E+5 1.11E+2Y-91m 5. --2.81E+3 1.72E+3 1.84E-2Y-91 9.14E+5 ---2.63E+6 1.84E+5 2.44E+4Y-92 2.04E+1 ---2.39E+4 2.39E+5 5.81 E-1Y-93 1.86E+2 ---7.44E+4 3.89E+5 5.11E+0Zr-95 1.90E+5 4.18E+4 -5.96E+4 2.23E+6 6.11E+4 3.70E+4Zr-97 1.88E+2 2.72E+1 -3.89E+1 1.13E+5 3.51E+5 1.60E+1Nb-95 2.35E+4 9.18E+3 -8.62E+3 6.14E+5 3.70E+4 6.55E+3Nb-97 4.29E-1 7.70E-2 -8.55E-2 3.42E+3 2.78E+4 3.60E-2Mo-99 -1.72E+2 -3.92E+2 1.35E+5 1.27E+5 4.26E+1Tc-99m 1.78E-3 3.48E-3 -5.07E-2 9.51E+2 4.81E+3 5.77E-2Tc-101 8.1OE-5 8.51E-5 -1.45E-3 5.85E+2 1.63E+1 1.08E-32.0-22SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS006 000S000000S00KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.6 (Page 2 of 2)R, Inhalation Pathway Dose Factors -CHILD(mrem/yr per JACi/m3)ODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 2.79E+3 --7.03E+3 6.62E+5 4.48E+4 1.07E+3Ru-105 1.53E+0 --1.34E+O 1.59E+4 9.95E+4 5.55E-1Ru-106 1.36E+5 --1.84E+5 1.43E+7 4.29E+5 1.69E+4Rh-103m --..Rh-106 -.....- -Ag-l10m 1.69E+4 1.14E+4-2.12E+4 5.48E+6 1.0 14E+3Sb-124 5.74E+4 7.40E+2 1.26E+2 -3.24E+6 +,655 20E+4Sb-125 9.84E+4 7.59E+2 9.10E+1 -2.32E+6/

.03E4+4, 7E+4Te-125m 6.73E+3 2.33E+3 1.92E+3 -4.77E-g 30A+ .14E+2Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.4 .-N 3.02E+3Te-127 2.77E+0 9.51E-1 1.96E+0 7.07E+O0@

\ +4 6.11E-1Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4,

,E+6 )1.8'2E+5 3.04E+3Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-/ 2.55E+4 2.38E-2Te-131m 1.34E+2 5.92E+1 9.77E+1 4.0015<2

,61Y 3.08E+5 5.07E+1Te-131 2.17E-2 8.44E-3 1.70E-2 _ 2. +3 1.33E+3 6.59E-3Te-132 4.81E+2 2.72E+2 3.17E+2 .7 E+5 1.38E+5 2.63E+21-130 8.18E+3 1.64E+4 1.85E+6 + 5.11E+3 8.44E+31-131 4.81 E+4 4.81 E+4 16 7. -2.84E+3 2.73E+41-132 2.12E+3 4.07E+3,1.l

+ +3 3.20E+3 1.88E+31-133 1.66E+4 2.03E+4 ,,ý.8WE 3. E+4 5.48E+3 7.70E+31-134 1.17E+3 5El 3.30E+3 9.55E+2 9.95E+21-135 4.92E+3 8.73 +\442F_%

1.34E+4 -4.44E+3 4.14E+3Cs-134 6.51E+5 1 t't 3.30E+5 1.21E+5 3.85E+3 2.25E+5Cs-136 6.51E+4 <.1F-1 9.55E+4 1.45E+4 4.18E+3 1.16E+5Cs-137 9.07E+'.2,.

+5 2.82E+5 1.04E+5 3.62E+3 1.28E+5Cs-138 6.3?,AF + 2 0X "+ -6.22E+2 6.81 E+ 1 2.70E+2 5.55E+2Ba-139 1.84IN 9. E-4 8.62E-4 5.77E+3 5.77E+4 5.37E-2Ba-140 ý,Q E+ A-,4E+1 -2.11E+1 1.74E+6 1.02E+5 4.33E+3Ba-1441 9E-4 -9.47E-5 2.92E+3 2.75E+2 6.36E-3Ba-142 QOF. 3.60E-5 -2.91 E-5 1.64E+3 2.74E-0 2.79E-3La-140 6. 4-+2 2.25E+2 -- 1.83E+5 2.26E+5 7.55E+1La-142 1.30E+0 4.11E-1 -8.70E+3 7.59E+4 1.29E-1Ce-141 3.92E+4 1.95E+4 -8.55E+3 5.44E+5 5.66E+4 2.90E+3Ce-143 3.66E+2 1.99E+2 -8.36E+1 1.15E+5 1.27E+5 2.87E+1Ce-144 6.77E+6 2.12E+6 -1.171E+6 1.20E+7 3.89E+5 3.61E+5Pr-143 1.85E+4 5.55E+3 -3.OOE+3 4.33E+5 9.73E+4 9.14E+2Pr-144 5.96E-2 1.85E-2 -9.77E-3 1.57E+3 1.97E+2 3.OOE-3Nd-147 1.08E+4 8.73E+3 -4.81 E+3 3.28E+5 8.21E+4 6.81 E+2W-187 1.63E+1 9.66E+0 -4.11E+4 9.1OE+4 4.33E+0Np-239 4.66E+2 3.34E+1 -9.73E+1 5.81 E+4 6.40E+4 2.35E+12.0-23 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.7 (Page 1 of 2)R1 Inhalation Pathway Dose Factors -INFANT(mrem/yr per igCi/m3)ODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3Na-24 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4P-32 2.03E+6 1.12E+5 ---1.61E+4 7.74E+4Cr-51 --5.75E+1 1.32E+1 1.28E+4 3.57E+2, 8.95E+1Mn-54 -2.53E+4 -4.98E+3 1.OOE+6 7.0W,,3-'1 98E+3Mn-56 -1.54E+0 -1.10E+0 1.25E+4 7 +,;4 1E-1Fe-55 1.97E+4 1.17E+4 --8.69E+4/X.091!3, 3E+3Fe-59 1.36E+4 2.35E+4 -1.02E-+,6<

2,, + 4,* .48E+3Co-57 -6.51 E+2 -- 3.7 5 6W !6.41 E+2Co-58 -1.22E+3 --/S-& 74182Co-60 -8.02E+3 -- IE+6 .19E+4 1.18E+4Ni-63 3.39E+5 2.04E+4 -- //2. .2.42E+3 1.16E+4Ni-65 2.39E+0 2.84E-1 -(< V.12P 5.01E+4 1.23E-1Cu-64 1.88E+0 -9. +3 1.50E+4 7.74E-1Zn-65 1.93E+4 6.26E+4 -.2 V,47E+5 5.14E+4 3.11E+4Zn-69 5.39E-2 9.67E-2 -1.47E+3 1.32E+4 7.18E-3Br-82 ----- -.1.33E+4Br-83_ _,__,,,___

_ --3.81E+2Br-85 --//- --2.04E+1Rb-86 -1.90 + --3.04E+3 8.82E+4Rb-88 5 5 3.39E+2 2.87E+2Rb-89 -.., --6.82E+1 2.06E+2Sr-89 3.98E+5 -2.03E+6 6.40E+4 1.14E+4Sr-90 4.09+7 -1.12E+7 1.31E+5 2.59E+6Sr-91 9.56)S! --5.26E+4 7.34E+4 3.46E+0S-2 " 3 --2.38E+4 1.40E+5 3.91 E- 1Y-90 --2.69E+5 1.04E+5 8.82E+1Y-91m .7F ---2.79E+3 2.35E+3 1.39E-2Y-91 5. + ---2.45E+6 7.03E+4 1.57E+4Y-92 1.64E+1 ---2.45E+4 1.27E+5 4.61E-1Y-93 1.50E+2 ---7.64E+4 1.67E+5 4.07E+0Zr-95 1.15E+5 2.79E+4 -3.11E+4 1.75E+6 2.17E+4 2.03E+4Zr-97 1.50E+2 2.56E+1 -2.59E+1 1.10E+5 1.40E+5 1.17E+1Nb-95 1.57E+4 6.43E+3 -4.72E+3 4.79E+5 1.27E+4 3.78E+3Nb-97 3.42E-1 7.29E-2 -5.70E-2 3.32E+3 2.69E+4 2.63E-2Mo-99 -1.65E+2 -2.65E+2 1.35E+5 4.87E+4 3.23E+1Tc-99m 1.40E-3 2.88E-3 -3.11E-2 8.11E+2 2.03E+3 3.72E-2Tc-101 6.51E-5 8.23E-5 -9.79E-4 5.84E+2 8.44E+2 8.12E-4S0066006006000D000000000000660066606662.0-24 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.7 (Page 2 of 2)R, Inhalation Pathway Dose Factors -INFANT(mrem/yr per lCi/m3)ODCM 2.0Revision 15June 6, 201300000S0000000000000Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 2.02E+3 --4.24E+3 5.52E+5 1.61E+4 6.79E+2Ru-105 1.22E+0 -8.99E-1 1.57E+4 4.84E+4 4.10E-1Ru-106 8.68E+4 -1.07E+5 1.16E+7 1.64E+5 1.09E+4Rh-103mRh-106 ---Ag-110m 9.98E+3 7.22E+3 -1.09E+4 3.67E+6 3.3064-1 OOE+3Sb-124 3.79E+4 5.56E+2 1.01E+2 -2.65E+6 5 +4 1JOE+4Sb-125 5.17E+4 4.77E+2 6.23E+1 -

1A9E+4Te-125m 4.76E+3 1.99E+3 1.62E+3 -4.47E-$ 15*+.,4t.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31 .3 V, 2.07E+3Te-127 2.23E+O 9.53E-1 1.85E+O 4.86E+O +4 4.89E-1Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 ^,UE+6 .90E+4 2.23E+3Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-X1

3. + 2.63E+4 1.88E-2Te-131m 1.07E+2 5.50E+1 8.93E+1 2.65C2 ."9r 1.19E+5 3.63E+1Te-131 1.74E-2 8.22E-3' 1.58E-2 -2.)+3 8.22E+3 5.OOE-3Te-132 3.72E+2 2.37E+2 2.79E+2 .0J,- 0E+5 4.41E+4 1.76E+21-130 6.36E+3 1.39E+4 1.60E+6 1.+ 1.99E+3 5.57E+31-131 3.79E+4 4.44E+4 1.4 5. -1.06E+3 1.96E+41-132 1.69E+3 3.54E+3 1.4+Y ,3 -1.90E+3 1.26E+31-133 1.32E+4 1.92E+4 .5ý 2.2-4E+4

-2.16E+3 5.60E+31-134 9.21E+2 1.88E+/ 2.09E+3 -1.29E+3 6.65E+21-135 3.86E+3 7.60.- "+N 6 8.47E+3 -1.83E+3 2.77E+3Cs-134 3.96E+5 7 tL 1.90E+5 7.97E+4 1.33E+3 7.45E+4Cs-136 4.83E+4 ."5" -5.64E+4 1.18E+4 1.43E+3 5.29E+4Cs-137 5.49E+5"

,.V 1+5 1.72E+5 7.13E+4 1.33E+3 4.55E+4Cs-138 5.0.+2 1 4.1OE+2 6.54E+1 8.76E+2 3.98E+2Ba-139 1.48E, 9. E-4 5.92E-4 5.95E+3 5.1OE+4 4.30E-2Ba-140 E _,E+, E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3Ba-11 Lý 1.08E-4 -6.50E-5 2.97E+3 4.75E+3 4.97E-3Ba-142 3. '98 3.30E-5 -1.90E-5 1.55E+3 6.93E+2 1.96E-3La-140 5.+ý2 2.OOE+2 -1.68E+5 8.48E+4 5.15E+1La-142 1.03E+0 3.77E-1 -8.22E+3 5.95E+4 9.04E-2Ce-141 2.77E+4 1.67E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3Ce-143 2.93E+2 1.93E+2 -5.64E+1 1.16E+5 4.97E+4 2.21 E+1Ce-144 3.19E+6 1.21E+6 -5.38E+5 9.84E+6 1.48E+5 1.76E+5Pr-143 1.40E+4 5.24E+3 -1.97E+3 4.33E+5 3.72E+4 6.99E+2Pr-144 4.79E-2 1.85E-2 -6.72E-3 1.61 E+3 4.28E+3 2.41 E-3Nd-147 7.94E+3 8.13E+3 -3.15E+3 3.22E+5 3.12E+4 5.OOE+2W-187 1.30E+1 9.02E+O 3.96E+4 3.56E+4 3.12E+0Np-239 3.71E+2 3.32E+1 -6.62E+1 5.95E+4 2.49E+4 1.88E+12.0-25 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013Table 2.8 (Page 1 of 2)Ri Vegetation Pathway Dose Factors -ADULT(mrem/yr per gCi/m3) for H-3 and C-14 (m2 x mrem/yr gCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5P-32 11.40E+9 8.73E+7 ---11.58E+8 5.42E+7Cr-51 -2.79E+4 1.03E+4 6.19E+4 1.17E+7 .4.66E+4Mn-54 -3.11E+8 -9.27E+7 -9.54r .-- "4E+7Mn-56 -1.61E+1 -2.04E+1 -5.12 E+0Fe-55 2.09E+8 1.45E+8 --8.06E+7 9E+ Fe-59 1.27E+8 2.99E+8 --8.35E+Z W +8 N<4.14E+8 Co-57 -1.17E+7 ---1.95E+7Co-58 -3.09E+7 -, .2W8 6.92E+7Co-60 -1.67E+8 --I 4+ .9+Ni-63 1.04E+10 7.21E+8 ---.50E+8 3.49E+8Ni-65 6.15E+1 7.99E+0 -2.03E+2 3.65E+0Cu-64 -9.27E+3 -2,34/, 7.90E+5 4.35E+3Zn-65 3.17E+8 1.01E+9 -6.36E+8 4.56E+8Zn-69 8.75E-6 1.67E-5 -- -2.51E-6 1.16E-6Br-82 -- 1.73E+6 1.51E+6Br-83 -4.63E+O 3.21 E+0Br-84 --Br-85 -Rb-86 -2.1 4.32E+7 1.02E+8Rb-88 -____Rb-89 <//Sr-89 9.96E+9+/-2<

--" 1.60E+9 2.86E+8Sr-90 6.05R+11

---1.75E+10 1.48E+11Sr-91 3.20 ----1.52E+6 1.29E+4Sr --8.46E+3 1.85E+1Y-90 ---1.41 E+8 3.56E+2Y-91 m "56-3 EA , -/- 1.71 E-8 -Y-91 5. 36 -- --2.82E+9 1.37E+5Y-92 9.01E-1 -- -1.58E+4 2.63E-2Y-93 1.74E+2 -- --5.52E+6 4.80E+OZr-95 1.19E+6 3.81E+5 -5.97E+5 -1.21E+9 2.58E+5Zr-97 3.33E+2 6.73E+1 -1.02E+2 -2.08E+7 3.08E+1Nb-95 1.42E+5 7.91E+4 -7.81 E+4 -4.80E+8 4.25E+4Nb-97 2.90E-6 7.34E-7 -8.56E-7 -2.71 E-3 2.68E-7Mo-99 -6.25E+6 -1.41E+7 -1.45E+7 1.19E+6Tc-99m 3.06E+0 8.66E+0 -1.32E+2 4.24E+0 5.12E+3 1.1OE+2Tc-101 .- I. --00000000000000000000000S006666I6II2.0-26 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 20130000000000!000O00[000Table 2.8 (Page 2 of 2)R, Vegetation Pathway Dose Factors -ADULT(mrem/yr per giCi/m3) for H-3 and C-14 (M2 x mrem/yr for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 4.80E+6 -1.83E+7 -5.61E+8 2.07E+6Ru-105 5.39E+1 -6.96E+2 -3.30E+4 2.13E+1Ru-106 1.93E+8 -3.72E+8 -1.25E+10 2.44E+7Rh-103mRh-106 -Ag-110m 1.06E+7 9.76E+6 -1.92E+7 -

4k80E+6Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 219 W9 49 1 E+7Sb-125 1.36E+8 1.52E+6 1.39E+5 1.05E+8,

.,QE:I- Z5E+7Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -3.W+8"ý 1.29E+7Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -N 7E 4.26E+7Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 -.5 1.25E+3Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9,

-.2 E+9 4.03E+7Te-129 6.65E-4 2.50E-4 5.10E-4 2.79E-, , .02E-4 1.62E-4Te-131m 9.12E+5 4.46E+5 7.06E+5 4.5216 4.43E+7 3.72E+5Te-131 -_-, -'_.Te-132 4.29E+6 2.77E+6 3.06E+6 .6 1.31E+8 2.60E+61-130 3.96E+5 1.17E+6 9.90E+7_

2 + I 1.01E+6 4.61E+51-131 8.09E+7 1.16E+8 3.79,- 1. -4 3.05E+7 6.63E+71-132 5.74E+1 1.54E+2 5.3 +3) +2 -2.89E+1 5.38E+11-133 2.12E+6 3.69E+6 215:i2 6. 4E+6 -3.31E+6 1.12E+61-134 1.06E-4 2.88E/5./

-4.59E-4 -2.51E-7 1.03E-41-135 4.08E+4 1.07 .+ 4E 1.71E+5 -1.21E+5 3.94E+4Cs-134 4.66E+9 ;m' -, \ -3.59E+9 1.19E+9 1.94E+8 9.07E+9Cs-136 4.20E+7 ,jNH,8 -9.24E+7 1.27E+7 1.89E+7 1.19E+8Cs-138'17

... ... 6.3, 8- -2.95E+9 9.81E+8 1.68E+8 5.70E+9Ba-139 , E-K, -1.96E-5 1.19E-5 5.23E-2 8.64E-4Ba-1 4t; 1.62E+5 -5.49E+4 9.25E+4 2.65E+8 8.43E+6Ba-141 -I-LBa-142 ----La-140 1.97E+3 9.92E+2 -7.28E+7 2.62E+2La-142 1.40E-4 6.35E-5 --4.64E-1 1.58E-5Ce-141 1.96E+5 1.33E+5 -6.17E+4 -5.08E+8 1.51E+4Ce-143 1.00E+3 7.42E+5 -3.26E+2 -2.77E+7 8.21E+1Ce-144 3.29E+7 1.38E+7 -8.16E+6 -1.11E+10 1.77E+6Pr-143 6.34E+4 2.54E+4 -1.47E+4 -2.78E+8 3.14E+3Pr-144 .....Nd-147 3.34E+4 3.86E+4 -2.25E+4 -1.85E+8 2.31 E+3W-187 3.82E+4 3.19E+4 ---1.05E+7 1.12E+4Np-239 1.42E+3 1.40E+2 -4.37E+2 -12.87E+7 7.72E+12.0-27 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.9 (Page 1 of 2)Ri Vegetation Pathway Dose Factors -TEEN(mrem/yr per gCi/m3) for H-3 and C-14 (M2x mrem/yr i4Ci/sec) for othersODCM 2.0Revision 15June 6, 20130000000Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5P-32 1.61E+9 9.96E+7 -1.35E+8 6.23E+7Cr-51 -3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4Mn-54 -4.52E+8 -1.35E+8 -9.27E, 2 ,97E+7Mn-56 -1.45E+1 -1.83E+1 -9.54f2 8E+0Fe-55 3.25E+8 2.31 E+8 --1.46E+8 9.*4k 5)18E+7Fe-59 1.81E+8 4.22E+8 --1.33E+ .9 + , \ .63E+8Co-57 -1.79E+7-

-,+> 3.00E+7Co-58 -4.38E+7

-" 1.01E+8Co-60 -2.49E+8,_

-_._2_ 2 +9 5.60E+8Ni-63 1.61E+10 1.13E+9 ---.81E+8 5.45E+8Ni-65 5.73E+1 7.32E+0 --+ ,,/, /3.97E+2 3.33E+OCu-64 -8.40E+3 -2.12 6.51 E+5 3.95E+3Zn-65 4.24E+8 1.47E+9 -, +S, 6.23E+8 6.86E+8Zn-69 8.19E-6 1.56E 2.88E-5 1.09E-6Br-82 -1.33E+6Br-839 1E 3.01 E+0Br-84 7 _Br-85 29, -Rb-86 --.73E#414.05E+7 1.28E+8Rb-88 --_0,/"Rb-89 -Sr-89 1.51E+210<-'-

1.80E+9 4.33E+8Sr-90 7.511E+11 1.85E+1 1Sr-91 2.991E6 4 1.36E+6 1.19E+4Sr-92 3.,M9+2 E 1.01E+4 1.69E+1Y-90 1.924E+4\

12 ---1.0E+8 3.34E+2Y-91 m , ...2.56E-7 -Y-91 3.23E+9 2.11 E+/-5Y-92 8.47E-1 6.6 2.32E+4 2.45E-2Y-93 1.63E+2 ...4.98E+6 4.47E+0Zr-95 1.74E+6 5.49E+5 -8.07E+5

-1.27E+9 3.78E+5Zr-97 3.09E+2 6.11E+1 -9.26E+1

-1.65E+7 2.81E+1Nb-95 1.92E+5 1.06E+5 -1.03E+5

-4.55E+8 5.86E+4Nb-97 2.69E-6 6.67E-7 7.80E-7 -1.59E-2 2.44E-7Mo-99 -5.74E+6 -1.31E+7 -1.03E+7 1.09E+6Tc-99m 2.70E+0 7.54E+0 -1.12E+2 4.19E+0 4.95E+3 9.77E+1Tc-101 -...... -00000000006S6S666606I6I6I6ISI0ISISISI2.0-28 00000000000S000[.IKEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.9 (Page 2 of 2)Ri Vegetation Pathway Dose Factors -TEEN(mren/v ,~ i~/ for H-3 and C-14 (i2x mrmm/vr Iu for nthersODCM 2.0Revision 15June 6, 2013%. .......I re p rf... ................

"- ... 1 ..........

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 6.87E+6 -2.42E+7 -5.74E+8 2.94E+6Ru-105 5.00E+1 -6.31E+2 -4.04E+4 1.94E+1Ru-106 3.09E+8 -5.97E+8 -1.48E+10 3.90E+7Rh-103m --Rh-106 ---Ag-110m 1.52E+7 1.44E+7 -2.74E+7 -4.04E 8.74E+6Sb-124 1.55E+8 2.85E+6 3.51E+5 -1.35E+8 3.13j '%'03E+7Sb-125 2.14E+8 2.34E+6 2.04E+5 -1.88E+8 1.W+9 OOE+7Te-125m 1.48E+8 5.34E+7 4.14E+7 --.3 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -6.56E+7Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4-

.,,.... .19 1.17E+3Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 +9 5.81E+7Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E 3.40E-3 1.51E-4Te-1 31 m 8.44E+5 4.05E+5 6.09E+5 4.22V,12 3.25E+7 3.38E+55Te-131 -_ __- I --< ,_ ",_-Te-132 3.90E+6 2.47E+6 2.60E+6 .. -7.82E+7 2.32E+61-130 3.54E+5 1.02E+6 8.35E+7 .7.87E+5 4.09E+51-131 7.70E+7 1.08E+8 3.14E+10

-2.13E+7 5.79E+71-132 5.18E+1 1.36E+2 4.5 -.4EK 5.91E+1 4.87E+11-133 1.97E+6 3.34E+6 E+ +6 2.53E+6 1.02E+61-134 9.59E-5 2.54E-4 ./X-2I-4

-3.35E-6 9.13E-51-135 3.68E+4 9.48E+Xl 1.50E+5 1.05E+5 3.52E+4Cs-134 7.09E+9 1.67E+-",6 5.30E+9 2.02E+9 2.08E+8 7.74E+9Cs-136 4.29E+7 1,41,Et \ 9.19E+7 1.45E+7 1.36E+7 1.13E+8Cs-137 1.01E+10

.1 45 VA"0 4.59E+9 1.78E+9 1.92E+8 4.69E+9-S ,< .... -Ba-139 2.779-2 5 -1.84E-5 1.34E-5 2.47E-1 8.08E-4Ba-140 1.38&, 1.60E+5 -5.75E+4 1.14E+5 2.13E+8 8.91E+6Ba-141 "_ _....Ba-142 OE -La-140 8.84E+2 -5.08E+7 2.35E+2La-142 1.e-4 5.69E-5 --1.73E+0 1.42E-5Ce-141 2.82E+5 1.88E+5 -8.86E+4 -5.38E+8 2.16E+4Ce-143 9.37E+2 6.82E+5 -3.06E+2 -2.05E+7 7.62E+1Ce-144 5.27E+7 2.18E+7 -1.30E+7 1.33E+10 2.83E+6Pr-143 7.12E+4 2.84E+4 -1.65E+4 2.34E+8 3.55E+3Pr-144 ...Nd-147 3.63E+4 3.94E+4 -2.32E+4 -1.42E+8 2.36E+3W-187 3.55E+4 2.90E+4 --7.84E+6 1.02E+4Np-239 1.38E+3 1.30E+2 -4.09E+2 12.1OE+7 7.24E+12.0-29 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.10 (Page 1 of 2)R1 Vegetation Pathway Dose Factors -CHILD(mrem/yr per pCi/m3) for H-3 and C-14 (m2x mrem/yr giCi/sec) for othersODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5Na-24 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5P-32 3.37E+9 1.58E+8 ---9.30E+7 1.30E+8Cr-51 --6.54E+4 1.79E+4 1.19E+5 6.25E+f--,,1.18E+5 Mn-54 -6.61E+8 -1.85E+8 -5.550,+6

-.,N6E+8Mn-56 -1.90E+1 -2.29E+1 -2. 4 E+0Fe-55 8.OOE+8 4.24E+8 --2.40E+8.6+

1,S1E+8Fe-59 4.01E+8 6.49E+8 --1.88E+ +8-\ 9.23E+8Co-57 -2.99E+7 --. E, 6.04E+7o-58 -6Co-60 -3.78E+8 --2-1OE+9 1.12E+9Ni-63 3.95E+10 2.11E+9 --.42E+8 1.34E+9Ni-65 1.05E+2 9.89E+0 -I -1.21E+3 5.77E+0Cu-64 -1.11E+4 -Z- -5.20E+5 6.69E+3Zn-65 8.12E+8 2.16E+9 -.36 3.80E+8 1.35E+9Zn-69 1.51E-5 2.18E-5 --5 -1.38E-3 2.02E-6Br-82 ---,2.91 -+- 2.04E+6Br-83 .9+ -< / =:,7-1 5.55E+0Br-84 1 12 EBr-85 -,/> -Rb-86 4.5 9 E+ 2.78E+8Rb-89Sr-89 3.59E*101 1.39E+9 1.03E*9Sr-90

-" 1.67E+10 3.15E+1 1Sr-91 5.,5ijEW

) -1.21 E+6 2.08E+4Sr-92 +2 1.38E+4 2.92E+1Y-90 ----6.56E+7 6.17E+2Y-91m 99E ---1.95E-5 -Y-91 1.8 .... 2.49E+9 5.01E+5Y-92 1.56E+0 .... 4.51 E+4 4.46E-2Y-93 3.01 E+2 .... 4.48E+6 8.25E+0Zr-95 3.90E+6 8.58E+5 -1.23E+6 -8.95E+8 7.64E+5Zr-97 5.64E+2 8.15E+1 -1.17E+2 -1.23E+7 4.81E+1Nb-95 4.1OE+5 1.59E+5 -1.50E+5 -2.95E+8 1.14E+5Nb-97 4.90E-6 8.85E-7 -9.82E-7 -2.73E-1 4.13E-7Mo-99 -7.83E+6 -1.67E+7 -6.48E+6 1.94E+6Tc-99m 4.65E+0 9.12E+0 -1.33E+2 4.63E+0 5.19E+3 1.51E+2Tc-101 ......000000000000000000000000000000000000000002.0-30 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013Table 2.10 (Page 2 of 2)R1 Vegetation Pathway Dose Factors -CHILD(mrem/yr per g.Ci/m3) for H-3 and C-14 (M2x mrem/yr jiCi/sec) for others00000I.0000S0000S00Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.55E+7 -3.89E+7 -3.99E+8 5.94E+6Ru-105 9.17E+1 -8.06E+2 -5.98E+4 3.33E+1Ru-106 7.45E+8 -1.01E+9 -1.16E+10 9.30E+7Rh-103m -Rh-106 -Ag-110m 3.22E+7 2.17E+7 4.05E+7 -2.58 ,1.74E+7Sb-124 3.52E+8 4.57E+6 7.78E+5 -1.96E+8 2.0+9 23E+8Sb-125 4.99E+8 3.85E+6 4.62E+5 -2.78E+8 1 .05E+8Te-125m 3.51E+8 9.50E+7 9.84E+7 -3. +VV 4.67E+7Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 X-07TE " 1.57E+8Te-127 1.00E+4 2.70E+3 6.93E+3 2.85E+4 -2.15E+3Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 0"1.'E+9 1.33E+8Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E--,3

.1 7E-2 2.74E-4Te-131m 1.54E+6 5.33E+5 1.1OE+6 5.1W6 2.16E+7 5.68E+5Te-131 --_ __ ________

_-___-Te-132 6.98E+6 3.09E+6 4.50E+6/-E

-3.11_E+7 3.73E+61-130 6.21E+5 1.26E+6 1.38E+8 -5.87E+5 6.47E+51-131 1.43E+8 1.44E+8 4.7r" .361.28E+7 8.18E+71-132 9.20E+1 1.69E+2 7 +, 2W+2 -1.99E+2 7.77E+11-133 3.59E+6 4.44E+6 M 5 ZlOE+6 -1.79E+6 1.68E+61-134 1.70E-4 3.16E-4/

7.- 4.84E-4 -2.1OE-4 1.46E-41-135 6.54E+4 1.18E-6 /0,4 +- 1.81E+5 -8.98E+4 5.57E+4Cs-134 1.60E+10 2,=tX- 8.14E+9 2.92E+9 1.42E+8 5.54E+9Cs-136 8.06E+7 4. 1.18E+8 1.76E+7 7.79E+6 1.43E+8Cs-137 2.39E+1 10 -7.46E+9 2.68E+9 1.43E+8 3.38E+9Cs-1 38 -\ X Ný --Ba-139 5.1 :L. NV 6-5 -2.38E-5 1.61E-5 2.95E+O 1.48E-3

_.3E+5 -7.90E+4 1.45E+5 1.40E+8 1.62E+7Ba- 141 (-/-Ba- ..La-140 3 1.13E+3 --3.15E+7 3.81E+2La-142 2.32E-4 7.40E-5 --1.47E+1 2.32E-5Ce-141 6.35E+5 3.26E+5 -1.43E+5 -4.07E+8 4.84E+4Ce-143 1.73E+3 9.36E+5 -3.93E+2 -1.37E+7 1.36E+2Ce-144 1.27E+8 3.98E+7 -2.21E+7 -1.04E+10 6.78E+6Pr-143 1.48E+5 4.46E+4 -2.41E+4 -1.60E+8 7.37E+3Pr-144 ..... --Nd-147 7.16E+4 5.80E+4 -3.18E+4 -9.18E+7 4.49E+3W-187 6.47E+4 3.83E+4 -- 1-5.38E+6 1.72E+4Np-239 2.55E+3 1.83E+2 -5.30E+2 1- 1.36E+7 1.29E+22.0-31 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.11 (Page 1 of 2)R, Grass-Cow-Milk Pathway Dose Factors -ADULT(mrem/yr per pCi/m3) for H-3 and C-14 (M2x mrem/yr gCi/sec) for othersODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6P-32 1.71E+10 1.06E+9 --1.92E+9 6.60E+8Cr-51 --1.71E+4 6.30E+3 3.80E+4 7.20E++++2.86E+4 Mn-54 -8.40E+6 -2.50E+6 -2.5 T '.0OE+6Mn-56 -4.23E-3 -5.38E-3 -7.'OE-4Fe-55 2.51 E+7 1.73E+7 -9.67E+6 / .95 .4E+6Fe-59 2.98E+7 7.OOE+7 -1.95E4< 2,,lE+.k s.68E+7Co-57 -1.28E+6 -! -.5 2.13E+6Co-58 -4.72E+6

, 1.06E+7Co-60 -1.64E+7 -- -.08E+8 3.62E+7Ni-63 6.73E+9 4.66E+8 -.-+9.73E+7 2.26E+8Ni-65 3.70E-1 4.81E-2 -1.22E+0 2.19E-2Cu-64 -2.41E+4 --8V', 2.05E+6 1.13E+4Zn-65 1.37E+9 4.36E+9 -.9_2.75E+9 1.97E+9Zn-69 -_____ _____Br-82 ---, -3.72E+7 3.25E+7Br-83 .-1.49E-1' 1.03E-1Br-84 --/"/Rb-86 -2.59 + 5.11E+8 1.21E+9Rb-88 -Rb-89Sr-89 1.45E+9 --2.33E+8 4.16E+7Sr-90 4.68 +10 1.35E+9 1.15E+10Sr-91 3.13 -, --1.49E+5 1.27E+3Sr --9.68E+0 2.11E-2Y --7.50E+5 1.90E+0Y-91m ,/ -Y-91 8. 3 --4.73E+6 2.30E+2Y-92 5.42E-5 --9.49E-1 1.58E-6Y-93 2.33E-1 ---7.39E+3 6.43E-3Zr-95 9.46E+2 3.03E+2 -4.76E+2 -9.62E+5 2.05E+2Zr-97 4.26E-1 8.59E-2 -1.30E-1 -2.66E+4 3.93E-2Nb-95 8.25E+4 4.59E+4 -4.54E+4 -2.79E+8 2.47E+4Nb-97 -----5.47E-9 -Mo-99 -2.52E+7 -5.72E+7 -5.85E+7 4.80E+6Tc-99m 3.25E+0 9.19E+0 -1.40E+2 4.50E+0 5.44E+3 1.17E+2Tc-101 -------000000000000000000I00I0I012.0-32 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013000000;00Si000000Table 2.11 (Page 2 of 2)R, Grass-Cow-Milk Pathway Dose Factors -ADULT(mrem/yr per giCi/m3) for H-3 and C-14 (M2 x mrem/yr p.Ci/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.02E+3 --3.89E+3 -1.19E+5 4.39E+2Ru-105 8.57E-4 --1.11E-2 -5.24E-1 3.38E-4Ru-106 2.04E+4 --3.94E+4 -1.32E+6 2.58E+3Rh-103m ---Rh-106 --,,-.,,--Ag-110m 5.83E+7 5.39E+7 -1.06E+8 2.20,,1" 20E+7Sb-124 2.57E+7 4.86E+5 6.24E+4 -2.OOE+7 7,31,8 t.)2E+7Sb-125 2.04E+7 2.28E+5 2.08E+4 -1.58E+7 , 5E 6E6Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -<6.% +7N, P2.18E+6Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 Y64 5.58E+6Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 -+4 1.45E+2Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8,,--X04F+8 9.57E+6Te-129 -,--,___Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79, 1.75E+7 1.47E+5Te-131 -_,,-,,_ __.4__ ___,,_Te-132 2.39E+6 1.55E+6 1.71E+6 .4 -7.32E+7 1.45E+61-130 4.26E+5 1.26E+6 1.07E+8 0+ -1.08E+6 4.96E+51-131 2.96E+8 4.24E+8 1.390,,1

7. 1.12E+8 2.43E+81-132 1.64E-1 4.37E-1 1.51+ 8.22E-2 1.53E-11-133 3.97E+6 6.90E+6 , 1 .OE+7 6.20E+6 2.1OE+61-134 --_______1-135 1.39E+4 3.63E+ 4_ ýý0E 5.83E+4 -4.1OE+4 1.34E+4Cs-134 5.65E+9 1. 343-TA4 4.35E+9 1.44E+9 2.35E+8 1.10E+10Cs-136 2.61E+8 + -5.74E+8 7.87E+7 1.17E+8 7.42E+8Cs-137 7.38E+9 .3.43E+9 1.14E+9 1.95E+8 6.61E+9Cs-1 38!)+ -- -Ba-139 4.- -8.34E-8 1.38E-9Ba-140 +t .4 1.15E+4 1.93E+4 5.54E+7 1.76E+6Ba-141 _ -, ...Ba-142 .... --La-140 4. 0 2.26E+0 --1.66E+5 5.97E-1La-142 --3.03E-8 -Ce-141 4.84E+3 3.27E+3 1.52E+3 -1.25E+7 3.71E+2Ce-143 4.19E+1 3.09E+4 1.36E+1 -1.166E+6 3.42E+0Ce-144 3.58E+5 1.50E+5 -8.87E+4

-1.21E+8 1.92E+4Pr-143 1.59E+2 6.37E+1 3.68E+1 -_6.96E+5 7.88E+0Pr-144 -....Nd-147 9.42E+1 1.09E+2 6.37E+1 5.23E+5 6.52E+0W-187 6.56E+3 5.48E+3 --1.80E+6 1.92E+3Np-239 3.66E+0 3.60E-1 -1.12E+0

-7.39E+4 1.98E-12.0-33 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.12 (Page 1 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -TEEN(mrem/yr per gCi/m3) for H-3 and C-14 (m2x mrem/yr laCi/sec) for othersODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6P-32 3.15E+10 1.95E+9 ---2.65E+9 1.22E+9Cr-51 -2.78E+4 1.1OE+4 7.13E+4 5.OOE+4Mn-54 -1.40E+7 -4.17E+6 -2.87,2ý1ý

,.8E+6Mn-56 -7.51 E-3 -9.50E-3 -4,W1 1 VE-3Fe-55 4.45E+7 3.16E+7 -2.OOE+7 Y.37-E 6E+6Fe-59 5.20E+7 1.21E+8 --3.82E+ 2.,+8\ 4.68E+7Co-57 -2.25E+6 ---9W 3.76E+Co-58 -7.95E+6

-8 1.83E+7Co-60 -2.78E+7 -.6 E+8 6.26E+7Ni-63 1.18E+10 8.35E+8 -, 1.33E+8 4.01E+8Ni-65 6.78E-1 8.66E-2 -4.70E+0 3.94E-2Cu-64 -4.29E+4 -1 + -3.33E+6 12.02E+4Zn-65 2.11E+9 7.31E+9 -.68 1 OE+9 3.41E+9Zn-69 ---Br-82 ---5.64E+-r8 --< 1.91E-1Rb-86 -4.73__- -7.OOE+8 2.22E+9Rb-88 -_ /,',,-/..Sr-89 2.67E+9 -" -3.18E+8 7.66E+7Sr-90 6.61F__ 10- ---1.86E+9 1.63E+10Sr-91 5.75E- --2.61 E+5 2.29E+3Sr-92 8, -- -2.28E+1 3.81 E-2Y-90 -1.07E+6 3.50E+0Y-91m MY-91 --6.48E+6 4.24E+2Y-92 1.OOE-4 .... 2.75E+0 2.90E-6Y-93 4.30E-1 ----1.31E+4 1.18E-2Zr-95 1.65E+3 5.22E+2 -7.67E+2 -1.20E+6 3.59E+2Zr-97 7.75E-1 1.53E-1 -2.32E-1 -4.15E+4 7.06E-2Nb-95 1.41 E+5 7.80E+4 -7.57E+4 -3.34E+8 4.30E+4Nb-97 -6.34E-8 -Mo-99 -4.56E+7 -1.04E+8 -8.16E+7 8.69E+6Tc-99m 5.64E+0 1.57E+1 -2.34E+2 8.73E+0 1.03E+4 2.04E+2Tc-101 -I- I- ---00000000000000S000SS00006006600000000II2.0-34 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 20130000000000000000000000Table 2.12 (Page 2 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -TEEN(mrem/yr per gICi/m3) for H-3 and C-14 (M2x mrem/yr giCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.81E+3 -6.40E+3 -1.52E+5 7.75E+2Ru-105 1.57E-3 -1.97E-2 -1.26E+0 6.08E-4Ru-106 3.75E+4 -7.23E+4 -1.80E+6 4.73E+3Rh-103m --Rh-106 -...Ag-11Orn 9.63E+7 9.11E+7 1.74E+8 -2.5 'T§.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 -4.01E+7 9,.W+8 179E+7Sb-125 3.65E+7 3.99E+5 3.49E+4 -3.21E+7/

..84Li, .54E+6Te-125m 3.OOE+7 1.08E+7 8.39E+6 -40E+'ý,"

4.02E+6Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -.10 1.OOE+7Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 _ _+4 2.68E+2Te-129m 1.11E+8 4.1OE+7 3.57E+7 4.62E+O,'

4.i5E+8 1.75E+7Te-129 -- 1.67W 7N_ /2.18E-9

-Te-131m 6.57E+5 3.15E+5 4.74E+5 3.2#1 +6,;? \ 2.53E+7 2.63E+5Te-131 -W --,___,,Te-132 4.28E+6 2.71 E+6 2.86E+6 6 + 8.58E+7 2.55E+61-130 7.49E+5 2.17E+6 1.77E+8 \ý -1.67E+6 8.66E+51-131 5.38E+8 7.53E+8 2."1 .+E9 -1.49E+8 4.04E+81-132 2.90E-1 7.59E-1 E E+. 9- 3.31E-1 2.72E-11-133 7.24E+6 1.23E+7 -.9 15E+7 9.30E+6 3.75E+61-134 -/,/ -_ N__ -I-1-135 2.47E+4 6.35 +

1.O0E+5 7.03E+4 2.35E+4Cs-134 9.81E+9 0 7.34E+9 2.80E+9 2.87E+8 1.07E+10Cs-136 4.45E+8 t.7 5 F_ -9.53E+8 1.50E+8 1.41E+8 1.18E+9Cs-137 1.34E+1 1 .+10 -6.06E+9 2.35E+9 2.53E+8 6.20E+9CS-1 38 -\,:>Ba-1 39 8.69eh ---7.75E-7 2.53E-9Ba-140 -+ E+4 2.02E+4 4.OOE+4 7.49E+7 3.13E+6Ba-141 _ _ _ _ _ __._ _ __-Ba-142La-140 .0 3.96E+0 -- 2.27E+5 1.05E+0La-142 ---2.23E-7 -Ce-141 8.87E+3 5.92E+3 -2.79E+3 -1.69E+7 6.81E+2Ce-143 7.69E+1 5.60E+4 -2.51 E+I -1.68E+6 6.25E+0Ce-144 6.58E+5 2.72E+5 -1.63E+5 -1.66E+8 3.54E+4Pr-143 2.92E+2 1.17E+2 -6.77E+1 -9.61E+5 1.45E+1Pr-144 -----Nd-147 1.81E+2 1.97E+2 1.16E+2 -7.11E+5 1.18E+1W-187 1.20E+4 9.78E+3 --2.65E+6 3.43E+3Np-239 6.99E+0 6.59E-1 -2.07E+0 1.06E+5 3.66E-12.0-35 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.13 (Page 1 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -CHILD(mrem/yr per RiCi/m3) for H-3 and C-14 (M2x mrem/yr giCi/sec) for othersODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6P-32 7.77E+10 3.64E+9 -2.15E+9 3.OOE+9Cr-51 --5.66E+4 1.55E+4 1.03E+5 5.41E+, 1.02E+5Mn-54 -2.09E+7 -5.87E+6 -1.7%+ý , 8E+6Mn-56 -1.31 E-2 -1.58E-2 -,1 9 0 2WE-3Fe-55 1.12E+8 5.93E+7 -3.35E+7 ,.10_ X,94E*7Fe-59 1.20E+8 1.95E+8 -5.65E+i 2. +8\ .71E+7Co-57 -3.84E+6 -5,,j- 4 7.77E+6Co-58 -1.21E+7 --,, ,, 7 3.72E+7Co-60 -4.32E+7 -,.E+8 I1.27E+8Ni-63 2.96E+10 1.59E+9 --1.07E+8 1.01E+9Ni-65 1.66E+0 1.56E-1 -1.91E+1 9.11E-2Cu-64 -7.55E+4 -I + -3.54E+6 4.56E+4Zn-65 4.13E+9 1.10E+10

-.94' 1.93E+9 6.85E+9Zn-69 --)2.14E-9 Br-82 ---__,,_) __._. _-_ _/,_' 1.15E+8Br-,3 -4.69E-1Br-84 -- ,/ \<Br-85 --Rb-86 -8.77_E+_5.64E+8 5.39E+9Rb-88 _ -/_Sr-89 6.62E+9 -\-2.56E+8 1.89E+8Sr-90 1.12F_ 11 --,1.51E+9 2.83E+10Sr-91 1.41 ---3.12E+5 5.33E+3Sr-92 4.14E+1 8.76E-2Y-90-- ---9.15E+5 8.61E+0Y-91 mY-91 3. 4 5.21E+6 1.04E+3Y-92 2.46E-4 -7.1OE+0 7.03E-6Y-93 1.06E+0 -1.57E+4 2.90E-2Zr-95 3.84E+3 8.45E+2 -1.21 E+3 -8.81 E+5 7.52E+2Zr-97 1.89E+O 2.72E-1 -3.91E-1 -4.13E+4 1.61E-1Nb-95 3.18E+5 1.24E+5 -1.16E+5 -2.29E+8 8.84E+4Nb-97 ---1.45E-6 -Mo-99 -8.29E+7 -1.77E+8 -6.86E+7 2.05E+7Tc-99m 1.29E+1 2.54E+1 -3.68E+2 1.29E+1 1.44E+4 4.20E+2Tc-101 ------000000000000000000000000000S00SSSSSSSSS6662.0-36 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 2013S00SS000S0S00S0000000Table 2.13 (Page 2 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -CHILD(mrem/yr per glCi/m3) for H-3 and C-14 (mi x mrem/yr iiCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 4.29E+3 --1.08E+4 -1.11E+5 1.65E+3Ru-105 3.82E-3 --3.36E-2 -2.49E+0 1.39E-3Ru-106 9.24E+4 --1.25E+5 -1.44E+6 1.15E+4Rh-103m ---Rh-106 -1 "--"__ _-Ag-110m 2.09E+8 1.41E+8 -2.63E+8 -1.9+ 1.13E+8Sb-124 1.09E+8 1.41E+8 2.40E+5 -6.03E+7 6M+8 11.81E+7Sb-125 8.70E+7 1.41E+6 8.06E+4 -4.85E+ 62.0"/ .82E+7Te-125m 7.38E+7 2.OOE+7 2.07E+7 -- << ,2E+'V 9.84E+6Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -- .6 8 2.47E+7Te-127 3.06E+3 8.25E+2 2.12E+3 8.71E+3 +5 6.56E+2Te-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+ 3."32E+8 4.23E+7Te-129 --2.87F_ -6.12E-8 -Te-1 31 m 1.60E+6 5.53E+5 1. 14E+6 5. W+6,/ 2.24E+7 5.89E+5Te- 131rTe-132 1.02E+7 4.52E+6 6.58E+64

-4.55E+7 5.46E+61-130 1.75E+6 3.54E+6 3.90E+8 -'ýfý2 1.66E+6 1.82E+61-131 1.30E+9 1.31E+9 4. -1.17E+8 7.46E+81-132 6.86E-1 1.26E+0 EJ-- 4.Z"E+0 1.48E+0 5.80E-11-133 1.76E+7 2.18E+7 .9 .63E+7 8.77E+6 8.23E+61-134 --5//5 /.+NN -" 135 5.84E+4 1.05 + \ .30j-6 1.61E+5 8.OOE+4 4.97E+4Cs-134 2.26E+10 3" 0 1.15E+10 4.13E+9 2.OOE+8 7.83E+9Cs-136 1.OOE+9 .6 v 1.47E+9 2.19E+8 9.70E+7 1.79E+9Cs-137 3.22E+10<.

,jlb+10 -1.01E+10 3.62E+9 1.93E+8 4.55E+9Cs-1 38 ,),_.Ba-139 2.14N ---1.23E-5 6.19E-9Ba-140 +, E+5 -3.34E+4 6.12E+4 5.94E+7 6.84E+6Ba-141 ___.. __-_ _-_-Ba-142---

La-140 1. 1- 6.74E+0 -1.88E+5 2.27E+0La-142 ---2.51E-6 -Ce-141 2.19E+4 1.09E+4 -4.78E+3 -1.36E+7 1.62E+3Ce-143 1.89E+2 1.02E+5 -4.29E+1 -1.50E+6 1.48E+1Ce-144 1.62E+6 5.09E+5 -2.82E+5 -1.33E+8 8.66E+4Pr-143 7.23E+2 2.17E+2 -1.17E+2 -7.80E+5 3.59E+1Pr.-144 --Nd-147 4.45E+2 3.60E+2 -1.98E+2 -5.71E+5 2.79E+1W-187 2.91E+4 1.72E+4 -2.42E+6 7.73E+3Np-239 1.72E+1 1.23E+0 -3.57E+0

-9.14E+4 8.68E-12.0-37 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.14 (Page 1 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -INFANT(mrem/yr per ,iCi/m3) for H-3 and C-14 (m2x mrem/yr giCi/sec) for othersODCM 2.0Revision 15June 6, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5Na-24 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7P-32 1.60E+11 9.42E+9 --2.17E+9 6.21E+9Cr-51 -1.05E+5 2.30E+4 2.05E+5 4.71E+-,--

1.61E+5Mn-54 -3.89E+7 -8.63E+6 -1.4 7 83E+6Mn-56 -3.21E-2 -2.76E-2 -0 !3E3Fe-55 1.35E+8 8.72E+7 4.27 E*7 ,.11K, 3E+7Fe-59 2.25E+8 3.93E+8 1.16E+&I<r 1,8t+ 81.55E+8Co-57 -8.95E+6 -,,,-, 5 1.46E+7Co-58 2.43E+7 +7 -6.06E+7Co-60 -8.81 E+7 E+8 2.08E+8Ni-63 3.49E+10 2.16E+9 -1.07E+8 1.21E+9Ni-65 3.51E+0 3.97E-1 --3.02E+1 1.81E-1Cu-64 -1.88E+5 -3.85E+6 8.69E+4Zn-65 5.55E+9 1.90E+10

-.23 1.61E+10 8.78E+9Zn-69 -- 7.36E-9Br-82 -_/__ -1.94E+8Br-83 <<

Br-84//.

,Br-85 -,,Rb-86 -2.22 1,+A , 5.69E+8 1.10E+10Rb-88_ --, /Rb-89 -_, / _Sr-89 1.26E+107

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

-1.52E+9 3.10E+10Sr-91 2.94Eft -3.48E+5 1.06E+4Sr-92 r,85L _. ,, 5.01E+1 1.73E-1Y-90 9.39E+5 1.82E+1Y-9lm Y-91 7.3_-_ 5.26E+6 1.95E+3Y-92 5.22E-4 9.97E+0 1.47E-5Y-93 2.25E+0 -1.78E+4 6.13E-2Zr-95 6.83E+3 1.66E+3 1.79E+3 -8.28E+5 1.18E+3Zr-97 3.99E+0 6.85E-1 6.91E-1 -4.37E+4 3.13E-1Nb-95 5.93E+5 2.44E+5 1.75E+5 -2.06E+8 1.41E+5Nb-97 -3.70E-6 -Mo-99 -2.12E+8 3.17E+8 6.98E+7 4.13E+7Tc-99m 2.69E+1 5.55E+1 5.97E+2 2.90E+1 1.61E+4 7.15E+2Tc-101S0S0000000000000S00000000000000S00S06002.0-38 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 15June 6, 201300000S0S0S000000000S0Table 2.14 (Page 2 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -INFANT(mrem/yr per igCi/m3) for H-3 and C-14 (mi x mrem/yr gCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung I-LLI T.BodyRu-103 8.69E+3 --1.81E+4 -1.06E+5 2.91E+3Ru-105 8.06E-3 --5.92E-2 -3.21E+0 2.71E-3Ru-106 1.90E+5 --2.25E+5 -1.44E+6 2.38E+4Rh-103m --- -Rh-106 ......Ag-110m 3.86E+8 2.82E+8 4.03E+8 -1 1_ I +N 1.86E+8Sb-124 2.09E+8 3.08E+6 5.56E+5 -1.31E+8 ,6.4kE+8

'.49E+7Sb-125 1.49E+8 1.45E+6 1.87E+5 -9.38E+,,

/'1..9" 8,,- /.07E+7Te-125m 1.51E+8 5.04E+7 5.07E+7 -_- 8E, 2.04E+7Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1.7,8 5.1OE+7Te-127 6.50E+3 2.18E+3 5.29E+3 1.59E+4 , -.E+5 1.40E+3Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 S334E+8 8.62E+7Te-129 2.08E-9 -1.75E-9 5.18 7- 1.66E-7 -Te-131m 3.38E+6 1.36E+6 2.76E+6 9.3a +6 -2.29E+7 1.12E+6Te-131 -Te-132 2.1OE+7 1.04E+7 1.54E+7 _.____E-_

3.85E+7 9.72E+61-130 3.60E+6 7.92E+6 8.88E+8 3 -1.70E+6 3.18E+61-131 2.72E+9 3.21E+9 1.0 3 1.15E+8 1.41E+91-132 1.42E+O 2.89E+0 .+0 -2.34E+0 1.03E+O1-133 3.72E+7 5.41E+7 .8 .6E+7 -9.16E+6 1.58E+71-134 - 135 1.21E+5 2.41 + .16 2.69E+5 8.74E+4 8.80E+4Cs-134 3.65E+10

6. 1.75E+10 7.18E+9 1.85E+8 6.87E+9Cs-136 1.96E+9 5 E -Y"/ 2.30E+9 4.70E+8 8.76E+7 2.15E+9Cs-137 5.15E+1 01_O 10 1.62E+10 6.55E+9 1.88E+8 4.27E+9Cs-1 38 -I-Ba-139 4.55 2.88E-5 1.32E-8B~a-140 + .E+5 -5.73E+4 1.48E+5 5.92E+7 1.24E+7Ba-142 La-140 1.59E+1 --1.87E+5 4.09E+0La-142 ...5.21 E-6 -Ce-141 4.33E+4 2.64E+4 -8.15E+3 -1.37E+7 3.11E+3Ce-143 4.OOE+2 2.65E+5 -7.72E+1 -1.55E+6 3.02E+1Ce-144 2.33E+6 9.52E+5 -3.85E+5 -1.33E+8 1.30E+5Pr-143 1.49E+3 5.59E+2 -2.08E+2 -7.89E+5 7.41E+1Pr-144 ..Nd-147 8.82E+2 9.06E+2 -3.49E+2 -5.74E+5 5.55E+1W-187 6.12E+4 4.26E+4 --2.50E+6 1.47E+4Np-239 3.64E+1 3.25E+0 -6.49E+0 -9.40E+4 1.84E+02.0-39 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.15 (Page 1 of 2)R, Ground Plane Pathway Dose Factors(M2x mrem/yr per pCi/sec)ODCM 2.0Revision 15June 6, 2013Nuclide Any OrganH-3C-14Na-24 1.21E+7P-32Cr-51 4.68E+6Mn-54 1.34E+9Mn-56 9.05E+5Fe-55Fe-59 2.75E+8Co-57 4.37E+8Co-58 3.82E+8Co-60 2.16E+1Ni-63Ni-65Cu-64Zn-65Zn-69Br-82 4. [Br-83 +Br-84 2 +E+5>8.98E+6Rb,88 3.29E+4,8 1.21 E+5Sr-8\' .2.16E+42.19E+67.77E+54.48E+3* 1.01E+5Akg1 1.08E+6Y-92 1.80E+5Y-93 1.85E+5Zr-95 2.48E+8Zr-97 2.94E+6Nb-95 1.36E+8Nb-97 2.28E+6Mo-99 4.05E+6Tc-99m 1.83E+5Tc-101 2.04E+4Ru-103 1.09E+800000000S00000000000000000060S666666662.0-40 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.15 (Page 2 of 2)Ri Ground Plane Pathway Dose Factors(M2x mrem/yr per liCi/sec)

ODCM 2.0Revision 15June 6, 20130000000000000000000S0000000000000Nuclide Any OrganRu-105 6.36E+5Ru-106 4.21E+8Rh-103mRh-106Ag-110m 3.47E+9Sb-124 2.87E+9Sb-125 6.49E+9Te-125m 1.55E+6Te-127m 9.17E+4Te-127 3.00E+3Te-129m 2.00E+7Te-129 2.60E+4Te-131 mTe- 131Te-1321-1301-131 Y1-1321-133 < <61-134 .9E+51-135 \\,2.56E+6 Cs-134 / 6.75E+9Cs-136 -1.49E+8C1.04E+10 Cs19= 3.59E+5R_-_13_X__1.06E+5

_.e'kX4 2.05E+74. 18E+4La4O 1.91 E+7"Ld-142 7.36E+5Ce-141 1.36E+7Ce-143 2.32E+6Ce-144 6.95E+7Pr-143Pr-144 1.83E+3Nd-147 8.40E+6W-187 2.36E+6Np-239 1.71_E+62.0-41 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-ARevision 15June 6, 2013APPENDIX ATECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -LIQUID RADIOACTIVE EFFLUENTS 660S00000S0SSS0SSSSSSSSSSSSSSSSSSSSSSSSS0SA-1 KEWAUNEE POWER STATION ODCM App-A* OFFSITE DOSE CALCULATION MANUAL Revision 15O June 6, 20130Technical Basis for Effective Dose Factors -Liquid Effluent ReleasesTo verify that the current approach to determining environmental doses using a simplified method has remained consistent since the previous analysis (performed using effluent data from1981-1983),

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 beO obtained to provide a simplified method of determining compliance with the dose limits ofODCM Normal Condition 13.1.2. For the radionuclide distribution of nts from theKewaunee Power Station, the controlling organ is either the GI-LLI or th er. calculated GI-LLI dose is almost exclusively dictated by the Nb-95 releases;

t Iidos s mostly afunction of the Cs-134 and Fe-55 releases.

The radionuclides, Fe- Sr-90, andCs-137 contribute essentially all of the calculated total body dose I this evaluation

are presented in Table A-I. The individual nuclide dosess e comparisons ofTable A-I were calculated using the total curies released batch d ontinuous releases asreported in the Annual Radioactive Effluent Release R >r gh o by the appropriate dosefactors.* Tritium is not included in the limited analysis e ss, for liquid releases, because thepotential dose resulting from normal facility s negligible.

From 2000-2002, themaximum tritium release from the Kewa ow "ion to Lake Michigan was 270 curies.O The calculated total body dose from 1 a 1.36E-02 mrem/yr via the fish ingestion O and drinking water pathways.

This u of the design objective dose of 3 mrem/yr.Furthermore, the release of triti is ion of operating time and power level and isessentially unrelated to radwaste se op tion.*For purposes of simpli o of the dose calculational

process, it is conservative toidentify a controlling, d cant radionuclide and limit the calculational process to the useO of the dose convers~

.n fac 0 is nuclide.

Multiplication of the total release (i.e., cumulative

activity for all rioi li by this dose conversion factor provides for a dose calculational method that i.. .ifie also being conservative.

O While not presen i e 2000-2002 liquid effluent

releases, it still remains conservative to use* the Cs-134 dose conversion factor (7.09E+05 mrem/hr per g.tCi/ml, liver) to evaluate theO maximum organ dose. Only the reactor-generated radionuclide Nb-95 has a higher doseconversion factor (1.51E+06 mrem/hr per g.tCi/ml, GI-LLI).

However, since Nb-95 releases aretypically less than 5% of the total releases, it is conservative to use the Cs-134 factor. By thisapproach, 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 maximumorgan dose as reported in the Annual Radioactive Effluent Release Report by a factor of 234; forO 2001, the conservatism is a factor of 109; and for 2002, a factor of 730. This comparison isO shown in Table A-2.0A-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-ARevision 15June 6, 2013For the total body calculation, the Cs-I134 dose factor (5.79E+05 mrem/hr per ItCi/ml, total body)is again used since it is higher than the identified dominant nuclides.

For 2000, using thissimplified conservative dose calculational method would overestimate the total body dose by afactor 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 thefollowing simplified equations may be used:Total Bodywhere:DtbAcs- 134,TBVOLCW1.67E-02I1.67E -02 x VOLDtb = X Acs -134, TB X Ci= dose to the total body (mrem) K= 5.79E+05, total body ingestion dose co)rsZinRCi/ml) ,,* 1)(mrem/hr per00000S0000S000S00S000000000000000000I6= total concentration of all= average circulating d616,Ci/ml) rate during release period (gal/min) lose conversion factor, the equation simplifies conversion Substituting the valueto:(A.2)CW1.67E -02 x VOL x Ac, -134. L X ECCW= maximum organ dose (mrem)(A.3)where:DmaxAcs-134,L

= 7.09E+05, liver ingestion dose conversion factor for Cs-134 (m~rem/hr pertCi/ml)A-3 00000000000000SS000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-ARevision 15June 6, 2013Substituting the value for Acs-134,Liver the equation simplifies to:D. =a1.18E+04xVOLXC CW(A.4)Only the total body dose need be evaluated by this simplified method since it represents the morelimiting dose (compared with the maximum organ dose) for demonstrating compliance withODCM Normal Condition 13.1.2.A-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-ARevision 15June 6, 2013Table A-1Adult Dose Contributions 2000___ Fish and Drinking Water Pathways__________

2000 _________

2001 2002Radio- Release TB GI-LLI Liver Release TB GI-LLI Liver R e TB GI-LLI Livernuclide (CG) Dose Dose Dose (Ci) Dose Dose Do Dose Dose DoseFrac. Frac. Frac. Frae. Frac. C. < Frac. Frac. Frac.Fe-55 4.81E- 0.03 0.02 0.10 4.85E- 0.04 0.03 01 0.19 0.02 0.84____02 02___ /I>____ 02Co-58 8.07E- 0.01 0.03 *4.09E- 0.01 4.94E- 0.05 0.02 0.0203 03 !/5 03Fe-59 2.77E- 2.44E- 0.01 0.0204 04G0.010.00 C60 47E-4.31E-/

2.07E-Co-60 4.71E- 0.02 0.04 0.01 0.01 0.06 0.02 0.030___03 0.02 0.04 00103Br-82 4.94E- 0.01 N/1)04 0.1 _*N/Sr-90 2.25E- 0.18 0.01 0.25 0.01 9.76E- 0.63 *__ __ _ 04 _ _ _ 05 _ _ _ _ ____Nb-95 3.41EE- -0.89 2 2.45E- 0.9104 _&404Cs-137 3.70E- 0.75 0 2.74E- 0.68 0.01 0.85 3.04E- 0.05 0.08104 04 0.68 0.01 0.85 06* Less than 0.01N/D = not detectedA-50090*....e..eee0eeee0eoo..e..e.....@.oee00e0e KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-ARevision 15June 6, 201300S0S000!00I,0Table A-2Adult Liver and Total Body Dose Assessment Dose Via the Simplified Method Versus the Actual Calculated Dose200020012000 2001I 4Simplified Liver Dose (mRem)* I. 16E+00 9.87E-0 ISimplified Liver Dose (mRem)*1. 16E+009.87E-01Actual Liver Dose (mRem)**4.97E-039.02E-03Simplified divided by Actual234109Simplified Total Body Dose(mRem) *Actual Total Body Dose (mRem)* Assuming 2.OOE+05 gpm circulating water flow** From the Annual Radioactive Effluent Release Re(()A-6 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 15June 6, 2013000000APPENDIX BTECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -GASEOUS RADIOACTIVE EFFLUENTS 0,0000000000000000000606000B-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 15June 6, 2013APPENDIX BTechnical Basis for Effective Dose Factors -Gaseous Radioactive Effluents Overview0000000SO0:0reThe evaluation of doses due to releases of radioactive material to the atmosphere can besimplified by the use of effective dose transfer factors instead of using dose ctors, which areradionuclide specific.

These effective

factors, which can be based On.,pe',adionuclide distributions of releases, can be applied to the total radioactivity released t oroxi "te the dosein the environment (i.e., instead of having to perform individual radi lid s alyses onlya single multiplication (Kefr, Meff or Neff)times the total quantity of di ive'liuaerialsreleased would be needed).

This approach provides a reasonable es ,t th tual dose whileeliminating the need for a detailed calculational technique.

Determination of Effective Dose Factors~~tionsEffective dose transfer factors are calculated by t I as:Keff i(13.1)where:Ier theleffective total h e -or due to gamma emissions from all noble gasesreleased e de gmaeisosfo l ol ae= the totalradionucl or due to gamma emissions from each noble gasof noble gas radionuclide "i" relative to the total noblef.(L + 1.1 M)eff = Z [(Li + 1.1 Ml )x fi](B.2)where:(L + 1.1 M)eff =(Li + 1.1 M1) =the effective skin dose factor due to beta and gamma emissions from all noblegases releasedthe skin dose factor due to beta and gamma emissions from each noble gasradionuclide "i" releasedMeff= I (IvL.xfi)

(13.3)B-2 00KEWAUNEE POWER STATION ODCM App-B 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013where:0Meff = the effective air dose factor due to gamma emissions from all noble gases releasedMi the air dose factor due to gamma emissions from each noble gas radionuclide "i"releasedNeff =E (Nixfi) (B.4)where:Neff the effective air dose factor due to beta emissions from a o gase eleasedNi the air dose factor due to beta emissions from eac g9 adionuclide "i"released

" "s rNormally, it would be expected that past radioactive fi d would be used for thedetermination of the effective dose factors.

Howev en b s releases from Kewauneehave been maintained to such negligible quantities tha he t variability in the data makesany meaningful evaluations difficult.

For the y 2 1 and 2002, the total noble gasreleases have been limited to 2.54E-04 Ci for Ci for 2001, and 1.91E-02 Ci for2002. Therefore, in order to provide a re le 's r the derivation of the effective noblegas dose factors, the primary coolant rce rm ANSI N237-1976/ANS-18.1, "SourceTerm Specifications,"

has been use s s a typical distribution.

The effective dosefactors as derived are presented in le,-Application,0 To provide an addition e of conservatism, a factor of 0.50 is introduced into the dosecalculational proces whe ' ctive dose transfer factor is used. This conservatism providesadditional surance" tthe aluation of doses by the use of a single effective factor will notsignificantly stii , , actual doses in the environment.

For with the dose limits of ODCM Normal Condition 13.2.2, thefollowing simpli i dequations may be used:3.17E-08DO -

(B.5)0.500DO = 3.17E-08 xX/QxNeffx-Qi (B.6) 00.50B-3 0SS 0000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 15June 6, 2013where: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)= atmospheric dispersion to the controlling SITE BOUNDARY (sec/m3)00S0S0000000Meff = 5.3E+02, effective gamma-air dose factor (mrad/yr perNeff = 1. IE+03, effective beta-air dose factor (mrad/yr per g93.17E-08

=conversion factor (yr/sec)0.50= conservat Combining the constants ism factor to account for the (thfie effluent datathe dose calculational I plify to:Dy = 3.5 5 x (B.7)fi 7 5X /QxzQi (B.8))rý e d on a very limited basis for the purpose of facilitating theadio ive effluent

releases, particularly during periods of computerose assessment may be unavailable.

Dose assessments using thependent calculation are performed at least annually for preparation ofReports.

Comparisons can be performed at this time to assure that thefactors does not substantially underestimate actual doses.The effective dosemalfunction the Radioýuse of theB-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 15June 6, 2013Table B-1Effective Dose Factors -Noble GasesTotal Body Effective Skin Effective Dose Factor Dose FactorKe1w (L+1.1 M)effRadionuclide fi (mrem/yr per gCi/mr3) (mrem/yr per gCi/mr3)Noble Gases -Total Body and SkinKr-85 0.01 -- 1.4E+01Kr-88 0.01 1.5E+02 1.9E+02(ý Xe-133m 0.01 2.5E+00 1.Xe-133 0.9 3.OE+02 +02Xe-135 0.02 3.6E+O, /01Eb(TOTAL 4.8E+02 <9 02Noble Gases -AirGamma ti Beta Air Effective Dose Dose FactorRadionuclide fi ( / er i/m3) (mrad/yr per pCi/mr3)Kr-85 2.OE+01Kr-88 0.01 4ýý 2.9E+01Xe-133m 0.0 .$ +00 1.5E+01Xe-133 /

1.0E+03Te-135 1..1) 3.8E+01 4.9E+01TOTAL 15.3F-+02 1I.1E+03SSSSSSSSSSq'4,SSSSSSSSSSSSSSSSSSSSSSSSSSSB-5 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-CRevision 15June 6, 2013000!000000000SSSSSSSSSS'0APPENDIX CEVALUATION OF CONSERVATIVE, DEFAULT EFFECTIVE EC VALUEFOR LIQUID EFFLUENTS C-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-CRevision 15June 6, 2013Appendix CEvaluation of Conservative, Default Effective EC Valuefor Liquid Effluents In accordance with the requirements of ODCM Normal Condition 13.3.1 the radioactive liquideffluent monitors shall be FUNCTIONAL with alarm setpoints established to ensure that theconcentration of radioactive material at the discharge point does not exceed 10 times the value of10 CFR 20, AP.4endix B, Table 2, Column 2 for all radionuclides other gases and avalue of 2E10 pACi/ml for noble gases. The determination of a wable concentration and corresponding alarm setpoint is a function of tn 2rdiiua /adionuclide distribution and corresponding EC values.IIn order to limit the need for routinely having to reestablish changing radionuclide distributions, a default alarm setpoifsetpoint can be conservatively based on an evaluatio yIliquid effluents from Kewaunee and the ECe value for 16'6ts as a function of6lished.

This defaultlide distribution of theThe effective EC value for awhere:radionuclide distri on ulated by the equation:

E-- (C.1)alue for a mixture of radionuclide (gCi/ml)of radionuclide "i" in the mixture20, Appendix B, Table 2, Column 2 EC value for radionuclide "i"60SS00066000a6DSD6D0D0D0D0D0D0D0D00D0D00D0D0D0I0D000I0D0I6S00EC,CiECQ-anBased on the above equation and the radionuclide distribution in the effluents for past years fromKewaunee, an ECe value can be determined.

Effluent release data from 2000-2002 was used togenerate the results presented in Table C-1. The most limiting effective EC (for gamma emittingradionuclides) was for the calendar year 2001, with a calculated value of 5.98E-06 itCi/ml.

Forconservatism in establishing the alarm setpoints, a default effective EC value of 1.OE-06 gtCi/mlwas selected.

The overall conservatism of this value is reaffirmed for future releases considering that 1.OE-06 tCi/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 ECC-2 00* KEWAUNEE POWER STATION ODCM App-C* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013*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 thealarm setpoint for release rate evaluations.

Examining releases over the years 2000-2002, theaverage, 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 change0significantly over time, since the concentration of H-3 in effluents can be expected to remainfairly consistent in effluent releases regardless of fuel conditions, activation product releases, andwaste processing.

Based on relative abundances, other non-gamma emitting radionucl Sr-89/90) contributed up to 30% of the concentration limit (30% for CY 2001 le to assumethat the abundances of these non-gammas will remain the same reer fission and/oractivation products under varying conditions.

Therefore, un I f elevated effluentradionuclide levels, the gamma-emitting radionuclides ed to be the maincontributors to limiting conditions on liquid eflent cokntr s established in Technical Specification 5.5.3.b and ODCM Normal Condition 1 1 te including the non-gammas (excluding tritium) in the evaluation results in a hi C value.*Therefore, under conditions of elevated efflu e , the main contributor to the limitingconditions of the liquid effluent concentr o" -gamma-emitting radionuclides.

Thefactor of six (6) conservatism in the etermination (discussed above) provides*adequate consideration for the c gib from non-gamma emitting radionuclides, andprovides a conservative basis for ab 'in alarm setpoint consistent with the requirements of Technical Specification 5.5. Normal Condition 13.1.1.The Heating Boiler Blo d T bine Building Sump are discharged to the lake with noinstalled radiation mon ing the default effective EC value of 1.OE-06 jiCi/ml forincreased monitori is con ewith the ODCM methodology if an installed radiation monitor0 was available.

000000000*000 KEWAUNEE POWER STATION ODCM App-COFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Table C-1Calculation of Effective EC (ECe)_ _ _ 2000 2001 __________

2002Nuclide EC (jiCi/ml)

_ Release (Ci) C,/ECi Frac. Release (CQ) Ci/ECi ac. Release (Q) CIEC, Frac.Na-24 5.OOE-05 1.03E-03 2.06E+01 4.89E-03 2.18E-04 4.35E+0 .-03 0.00E+00 0.OOE+00 0.OOE+00Cr-5 1 5.OOE-04 1.44E-03 2.89E+00 6.85E-04 8.26E-04 1.65 .8 -0.OOE+00 0 OOE+00 0 OOE+00Mn-54 3.OOE-05 1.49E-04 4.97E+00 1.18E-03 3.30E-04 1.10 6.4 1 E-05 2.14E+00 9.83E-04Fe-55 1.00E-04 4.81E-02 4.81E+02

1. 14E-01 4.85E-02 E-01 3.69E-02 3.69E+02 1.70E-01Co-57 6.00E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.42E-05 4.03E- 18E-04 0.OOE+00 0.00E+00 0.OOE+00Co-58 2.00E-05 8.07E-03 4.04E+02 9.59E-02 4.09E-0 , ,,5E+ 5.99E-02 4.94E-03 2.47E+02 1.14E-01Fe-59 1.00E-05 2.77E-04 2.77E+0I 6.57E-03 2.44 4 .1 7.14E-03 1.65E-04 1.65E+01 7.61E-03Co-60 3.OOE-06 4.71E-03 1.57E+03 3.73E-01 4.31 1 +03 4.21E-01 2.07E-03 6.89E+02 3.17E-01Br-82 4.OOE-05 4.94E-04 1.23E+01 2.93E 03 -,9E+00 1.05E-03 0.OOE+00 0.OOE+00 0.OOE+00Sr-89 8.OOE-06 3.42E-04 4.27E+01 I .1IE-02 2.5 -3.24E+01 9.48E-03 5.98E-04 7.48E+01 3.44E-02Sr-90 5.OOE-07 2.25E-04 4.50E+02 1.07E- -0 5.OOE+02 1.46E-0I 9.76E-05 1.95E+02 8.98E-02Zr-95 2.OOE-05 1.16E-04 5.79E+00 1.3 7. -3.59E+00 1.05E-03 5.24E-05 2.62E+00 1.20E-03Nb-95 3.00E-05 3.41E-04 1.14E+01

2. -0 E-04 7.95E+00 2.33E-03 2.45E-04 8.17E+00 3.76E-03Ag-ll10m 6.00E-06 2.85E-03 4.74E+02 .135, , 1. 3E-03 2.72E+02 7.97E-02 2.86E-03 4.76E+02 2.19E-01Sn-1 13 3.OOE-05 9.65E-05 3.22E+0 7. 5.08E-05 1.69E+00 4.95E-04 7.06E-05 2.35E+00 1.08E-03Sb-124 7.00E-06 5.61E-04 8.01 E+0 OE- 1.81E-04 2.59E+01 7.59E-03 4.34E-05 6.20E+00 2.85E-03Sb-125 3.OOE-05 4.86E-03

1. 2 1.02E-03 3.41E+01 9.99E-03 2.46E-03 8.18E+01 3.76E-021-132 1.00E-04 0.OOE+00 E 0. +00 7.75E-08 7.75E-04 2.27E-07 0.OOE+00 0.OOE+00 0.OOE+001-133 7.OOE-06 6.16E-04

.8 1 2.09E-02 6.32E-04 9.03E+01 2.65E-02 0.00E+00 0.OOE+00 0.OOE+001-135 3.OOE-05 0.OOE+00 0.OOE+00 4.61E-05 1.54E+00 4.50E-04 0.OOE+00 0.OOE+00 0.OOE+00Cs-137 1.00E-06 3.70E-0 3.7 0 8.78E-02 2.74E-04 2.74E+02 8.02E-02 3.04E-06 3.04E+00 1.40E-03Total 7.4Z 4. 03 1.00E+00 6.34E-02 3.42E+03 1.00E+00 5.06E-02 2.17E+03 1.00E+00Non-Gamma Fraction 0.23 _ _ _ _0.30 0._ _0"29Gamma Fraction 0.77 _ i _ 0.70 i _ i 0.71ECe (JLCi/ml, total) I.77E- 1.86E-05 2.33E-05ECe (ICi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06C-40000000 0 0 00 00 0 0 0 00 00 0 0 0 00 00 0 0 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 201300000000000000000000000APPENDIX DOn-site Disposal of Low-Level Radioactively Contaminated Waste StreamsD-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013Appendix D consists of hard copies of the following reference documents:

DESCRIPTION DATE IDOCKET NUMBEROperating License DPR-43Kewaunee Nuclear Power PlantDisposal of Low Level Radioactive MaterialOctober 17, 1991NRC-91-148 50-305Proposed Disposal of Low LevelRadioactive Waste Sludge Onsite at theKewaunee Nuclear Power Plant(TAC No. M75047)Safety Evaluation For An Amendment ToAn Approved 10 CFR 20.302 Application For The Kewaunee Nuclear Plant(TAC No. M89719)11IAlternate Disposal Of Contaminated Sewage Treatment Plant Sludge InAccordance With 10 CFR 20.2002(TAC No. M93844)110000000000000,000000000000000000000000000000Onsite Disposal Of Contaminated Pursuant To 10 CFR 20.2002(TAC No. M97411)IAdapteD-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013000S0000000000000WPSC 1414) 433. 1598TELECOPIER (414: 433-55440.WI9CONSIU PUBUC SRIMCE COMPORATION

.-0F1 %ore-%Acar-s

P0 Box IS02 a GeeerkBav.

W' 5d3C7-CO02 AtR 91-/4tgEASYLINK 628S1993bce- KMNELarTDRDAREKHMLDLI Lp m I 01noNV. Wui J N MorTison D2 A J Ruege D2Boys, WPL I R Mueller D2 C A Schrock KNPNielsen, ANFC D S Nalelka KNP C S Smoker KNPBerg KNP L A Nuthals D2 (NSRAC) C R Seinhaid D2Bollom G6 R P Pulec D2 J I Wallace KNPDratwim NiCJP J SRichmond D2 K KH WiheEvers D2 D JRistau D2 S FWo, 12 \Marchi KNP D J Ro ponKJP Q,, QAVa M 4 P \M~asarile KNP-07K P wOctober 17, 1991U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, D.C. 20555Gentlemen:

Docket 50-305Operating License DPR-43 //Kewaunee Nuclear Power Plant -...Dis~goa of Lw Level Radioate afi]

References:

1) Letter fr .erg o ment Control Desk dated September 12, 19892) '- , s to K.H.Evers dated February 13, 19903 t m L.Sridhazon (W`DNR) to M.Vandenbusch dated June 13. 1991In referen purs t t the regulation of 10 CFR 20.302, Wisconsin Public ServiceCorpo C) uested authorization for the alternative disposal of very-low-level radi the Kewaunee Nuclear Power Plant. In reference 2, the US NRCidenc4 .)dtt nal questions that needed to be addressed in order to complete their review.AttacRen

,I vides our response to the questions.

WPSC requested the State of Wisconsin Department of Natural Resources (WDNR) to reviewthe disposal options for the service water pretreatment lagoon sludges.

In reference 3, theWDNR completed a review of the most appropriate on site disposal methods for the slightlycontaminated service water pretreatment lagoon studges.

The two proposed methods that theWDNR evaluated included in-situ capping of the sludge in the wastewater treatment lagoon andon site landspreading.

In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013Document Control DeskOctober 17, 1991Page 2application which is our preferred disposal method. WPSC does not intend to utilize the in-situcapping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed thateither 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.

XZN-if the on site landspreading option is utilized, the material woulddisking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading performance standards.

Should there be any additional qumember of my siaff.Sincerely, C. A. SchrockManager -Nuclear Engineering Pq(bctional and,free to contact aLICXDJMN492 0SS00000000S0S000000000S0000DJIrjmsAttach.cc -.US NRC -Mr. PatrickD-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013ATTACHMENT ITo0000000000000000000000000000Letter from K. H. Evers (WPSC) to DocumentDated(NRC)'1D-5 SKEWAUNEE POWER STATION ODCM App-D 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Document Control DeskOctober 17, 1991Attachment 1, Page I00References

1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989.NRC Question

1On page 4 of your submittal, the average input to the Sewage'System is approximately 11,000 gallons per day. In the FAStatement, this system is to be operated below its desi ofgallons per day. Discuss this deviation from the d cap d provideinformation to justify the higher output for thi teWPSC ResponseThe original Sewage Treatment S th a Kewamee NuclearPower Plant (KNPP) was rp 1a19 a higher capacity system. Theoriginal system was I .. work force of around [50 people.It was a limited capa ,/ ae c il ent system which included the onsitelagoon for additi '4< c ause of this limited capacity and morestringent con s steeffluent to Lake Michigan, an aerobic digestersystem wasi which has a higher capacity, and uses currenttechnoinput volume to the Sewage Treatment System used in theSeptir 12. 1989 application was 11,000 gallons per day. This value wasbased on past operating data. The increase in influent from the original designbasis included in the Final Environmental Statement is due mainly to anincrease in the number of individuals and facilities (e.g., training andsimulator building) located onsite. Design changes to the system wererequired to accommodate these new facilities.

D00D-60000 O KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Document Control DeskOctober 17, 1991O Attachment 1, Page 2@The current volumes of sewage sludge were used as the basis for the potential O dose analysis and corresponding radionuclide concentration limits. ThisO increase has no significant effect on the dose modeling.

(Refer to the responseO to NRC Question

2, below.)O NRC Question

2Provide information regarding how the disposal plan assur a an* dose to any exposed individual will be kept below 1WPSC Response n#acocnrto iiswsbsdo RcmueThe dose pathway modeling used for de i e active material*IMPACTS-BRC was used as the cai g the potential doses from*the alternative disposal me ug includes reasonable

conservative exposure os for the various disposal methods.Administrative i blished to ensure that the actual disposal ofany slightly ed materials from KNPP are within the bounds of theO evaluat .m each of the waste streams will be collected andan am spectroscopy prior to release for disposal.

A system1 e f'etection (LLD) of 5F.A7 ptCi/ml for the principal gammaOemi ionucides will be required.

This LLD ensures the identification ofany contaminated materials at a fraction of the allowable concentration limits.O for the alternative disposal.

oThe results of these analyses will be used to ensure that any detectable levels0of radioactive material are within the limits for alternative disposal.

Anymaterials with levels of radioactive material above the concentration limits00* -O0 0KEWAUNEE POWER STATION ODCM App-D 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Document Control DeskOctober 17, 1991Attachment 1, Page 3(and of plant origin) will be treated as a radioactive waste and appropriately controlled.

0Records will be maintained to ensure that the cumulative disposal of anycontaminated materials are maintained within the bounds of the _.ev IZ naddition to a comparison of the individual radionuclide concen 'l record of the total amount of radioactive material disposed wimaintained.

Cumulative totals will be maintained to e .teactivity does not exceed the quantity assumed in enivati o e limits.In developing the concentration limits pres, , of reference 1, itwas assumed the total annual design s v ,000 ft0 would becontaminated at the derived limit mitment from eachradionuclide was individually u were the only radioactive material present.

To det9ine mixture of radionuclides meets the limit,the sum-of-the-fractiot ou applied (i.e., the sum of eachradionuclide's c by its limiting concentration must be lessthan one). 0e0*The tio mits of Table I of reference 1 also have an implied total activityli, t. imit is determined by multiplying the individual radionuclide con limit by the total estimated waste volume of 27,000 ft3.These totalactivity limits are presented in Table A of this response, for each radionuclide individually.

For a mixture of radionuclides, a total annual activity limit may bedetermined by normalizing the concentrations so that the sum-of-the-fractions for themixture equals one (1). These resultant adjusted concentrations may be multiplied bythe 27,000 ft waste volume to determine the corresponding total activity limit of themixture.00D-8000 O0* KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 15O June 6, 2013O Document Control DeskO October 17, 1991O Attachment I, Page 40O A Disposal Log will be maintained on a calendar year basis for all disposals ofO any very-low-level radioactive materials.

The log will contain as a minimum* the following information:

O

Disposal location*

Description of waste-Shipment/disposal dateO Waste volumeO

Radionucide concentrations (gamma emitt*

Year-to-date radionuclide activity.

-Year-to-date waste volume*Inaddition to the above Disposat Log, be kept for eachO individual disposal.

This file " a3 inimum, the following O information:

*- Waste identif-Sample ganm y resultsO Idetif Iuc* ncentrations and total activity* NRC QU 3B, Section A of your submittal,

'Radiation Exposure During0Trans y adding the cumulative dose to the exposed population perO reactor year for both the transportation worker and the general publicO (onlookers along route).OO WPSC Response* The potential exposure to the general public (onlookers along route) isO imodeled by the IMPACTS-BRC code. As addressed in NUREG/CR-3585, O this modeling is based on an integration of the source strength, an assumed0O -o0 06KEWAUNEE POWER STATION ODCM App-D 6OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Document Control DeskOctober 17, 1991Attachment 1, Page 50population density along route and vehicular speed. For a conservative evaluation of the potential exposure to the general public from the transport ofthe KNPP waste, a population density of 610 persons/mi 2 was assumed.

This 0value is conservative for the KNPP site area where the average aondensity is less than 53 persons/mi 2.A transport distance of mmilesassumed.

The IMPACTS-BRC modeling assumes five o ot 'erial aretransported per shipment.

For the assumed KNPP sshipment weight translates into a total of 167 s ens a. With avehicular speed of 20 miles per hour, the pulaon exposure--

time is 375 person-hours per year. At th 'a6 on limits established for 0the alternative

disposal, the potend n ' during transport will beless than 0.01 person-rem..per

^ _odeling of the exposure to the0transport worker, the Iel )) assumes two drivers per vehicle.As presented in the S m 989 submitL, the maximum dose to the 0driver is less th (<0.001 remlyr).

Therefore, the totalcollective do sr workers will be twice the individual dosei.e.,

less than 0. r -rem. Including the population dose of <0.01 person-rem th tlcollective dose to both the transport workers and the0Po ess than 0.02 person-rem (0.002 person-rem

+ 0.01 person-rem

< 0. on-rem).

OFor the disposal of the existing 15,000 ft3 of contaminated

sludges, thepopulation dose due to the transportation of the waste is calculated to be0.0002 person-rem.

The estimated collective exposure to the transport worker Ois 0.00007 person-rem.

The total collective dose due to transport of the waste 0is 0.00027 person-rem.

0D-lO 0000 SO KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20130 Document Control Desk*October 17, 1991*Attachment I, Page 60Additional 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 disposal in the Kewaunee County Landfill.

Land pcation* is also an option for the disposal of the sewage sludges.

Theref -- WP*requests that the option for onsite disposal at the KNPP site I.a ionbe included in the alternative disposal methods which was beacceptable in our September 12, 1989 submittal.

The potential pathways of exposure as eval 12, 1989submittal conservatively bound any of exposure that wouldresult from onsite land spreading of e.-A hment A to this responseprovides an overview of the method. Also, thepathways of exposure app , bite land application are evaluated; and a comparison to t llin thways and radionuclide concentrations

as presented in tN 1989 submittal are discussed.

From a.modeling s e two exposure scenarios, "Radiation Exposure DuringTransportu an on Exposure to Landfill Operator,'

appropriately ch y ntial exposure to workers involved with the lands Iwaste. The other post-disposal exposure scenarios, "Intruder See c " ntruder Well", and "Exposed Waste Scenario,"

as described in*NUREGICR-3585 (and as discussed in Appendix C of the submittal) reasonably bound any potential exposures from either ground waste migration 0or 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.D-11 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013Document Control DeskOctober 17, 1991Attachment 1, Page 76Table ARadionuclide Quantity Limitsfor Alternative DisposalLimitingLimiting AnnualNuclide Concentration Qnti("Ci/mi)H-3 9.65E-04C-14 4.55E-05 48Cr-51 3.13E-04

.2394Mn-54 1. 14E-05 0.0087Fe-55 l-.W0 7.6500Fe-59 7. 0.0060CO-58 .0.0089Co-60 0.0029Ni-63 E 7.6500Sr-9 / 2.6393Zr-q -06 0.00481.23E-05 0.0094M6.73E-05 0.05 15To- 2.70E-04 0.20662.5013-06 0.00192.68E-05 0.0205-134 6.161-06 0.0047s-137 1.71E-05 0.0131Ba-140 5.52E-05 0.0422La-140 4.17E-06

0.0 032Transuranics

.TRU (T1/2A > 5 yrs) 8.91E-05 0.0682Pu-241 2.85E-03 2.1803Cm-242 1.00E-02 7.6500Assumes annual quantity of KNPP wastes is 27,000 ft3 or7.65E8 mls.S06SSS6S00000000000000D-12 SS* KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 20130Document Control Desk* October 17, 1991*Attachment 1, Page 80*Appendix A*Evaluation of Onsite Land Application for* Alternative Disposal of Very-Low-Level Contaminated Materials OverviewLand spreading of lagoon sludges onsite at the Kewaunee Nuclear P P nrecommended by personnel from the Wisconsin Department of N , (DNR) asa desirable alternative to the use of the Kewaunee County r This methodof disposal is also a recommended practice for dispo0 age itment facility sludges.Therefore, WPS requests that this disposal meth i options available forthe alternative disposal of very-low-level rad" n ted materials from KNPP.Description of Disposal MethodThe disposal of KNPP sludges y beneficial land application to a dedicated disposal area located onsite at a Nuclear Power Plant. Typical methods of land0spreading will be employ es. will be loaded onto appropriate vehicles (e.g.,tanker truck, sludge de. , etc., applied to the dedicated disposal area. The dedicated 0 disposal area will cally plowed to a depth of 6 inches.Onsite eatment and sewage sludges are allowed by EPA and State ofWiscon eat of Natural Resources with the criteria and limits for land spreading being speci y 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 are grazed forhuman 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 be 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 hectare will be applied to the dedicated disposal site. This*limit will ensure that any land application will not exceed the bounds of the dose analysis asDD-1000 0KEWAUNEE POWER STATION ODCM App-D SOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Document Control DeskOctober 17, 1991Attachment 1, Page 9performed previously.

In addition, other limitations as applied to land application by theState of Wisconsin Department of Natural Resources will bI followed (e.g., control ofrunoff/erosion, proximity to wells/residences/surface water, etc.).Applicable Pathways of Exposure 4The pathways of exposure applicable for land spreading are not d fo tm fthe pathways evaluated for the disposal methods at the Kewa filor theGreen Bay Metropolitan Sewerage District facilities.

The o pathways arediscussed below: 0Direct Exposure to WorkersSAny potential exposures to wo 0 removal, transport and land Sspreading of the sludges are d by the evaluation of theexposure to the trans September 12, 1989 submittal.

Thetransport worker h In o be exposed for 460 hours0.00532 days 0.128 hours 7.60582e-4 weeks 1.7503e-4 months per year atone (1) meter f un e, te. For the land spreading of these wastes,it is estimn. total exposure time for the removal and disposal of thelagoon es w .reno longer than a three week period per year (i.e.,12 0The p exposure to a worker onsite after land spreading, has beenestimated 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 beinvolved in land maintenance activities, such as plowing and mowing. Asmodeled in the September 12, 1989 submittal, an exposure of 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months peryear to the landfill operator has been assumed.

For this exposure, the KNPPmaterials are mixed with other landfill waste: a 1:13 mixing of KNPPmaterials to other waste is assumed.

This mixing is not significantly different from the type of mixing that will occur in the field with the sludges beingDD-14 0S0 0* KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 20130Document Control DeskOctober 17, 1991* Attachment 1, Page 10o* 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 e ISmmrem per year dose to the transport worker as evaluated in the S ber "" 1989 submittal.

Post Disposal Exposure

-Intruder Scenario0* The IMPACTS-BRC model, as applied to the 0 P waste, assumes aloss of institutional controls 10 years af f ite (See Appendix B of theSeptember 12, 1989 submittal).

An in med to reside in a house builton the disposal area. This indi irect exposure (from the uncovered waste), an inhalation exposu ion), and an ingestion exposure (fromgrowing % of his food cigproeit is assumed that the waste ismixed at a ratio of th ils during the resident's construction process.Applicati udge )ncentrations even though the less restrictive Non-Agricultural

4 Ii concentrations are applicable since a "dedicated land* disl be used (i.c., no crops will be grown on the disposal site).* Therefeprovided 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*t 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 1 bounds this exposure pathway for the on-site land spreading.

00 D-150 00KEWAUNEE POWER STATION ODCM App-D SOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013Document Control DeskOctober 17, 1991Attachment I, Page 110Post Disposal

-Intruder Well0The intruder well pathway for onsite land disposal is essentially the same as theintruder well pathway as evaluated by the IMPACTS-BRC model.. i rvatively assumed that the well is located at the edge of the disposal sit >44e/$ locatingthe well at the disposal site edge in "downstreamn flow" di i s thecalculated hypothetical dose. (Additional discussion presented inNUREG/CR-3585, Volume 2). oThe potential dose for the intruder well 0dspreading disposal wouldbe less than 0.001 mrem per year. as presented in the September 12,1989 submittal reasonably boun y well water exposure pathway.In summary, the mod f scenarios, as presented in the September 12, 1989 submittal, s the hypothetically exposures for the on-siteland spreading.

I is it ikely that any individual, either on-site or off-site, will receive a do of I mrem per year from the disposal of the slightly Scontam' teD0SSS0000D-16000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013UNITED STATESNUCLEAR REGULATORY COMMISSION WASHINGTON.

D.C.K ~-6r)qJune 17, 1992Docket No.50-305S000000S00S000SMr. C. A. SchrockManager -Nuclear Engineering Wisconsin Public Service.Corporation P. 0. Box 19002Green Bay, Wisconsin 54037-9002

Dear Mr. Schrock:

SUBJECT:

PROPOSED DISPOSAL OF LOW LEVEL RADIOACV TJDGE ONSITE ATTHE KEWAUNEE NUCLEAR POWER PLANT (TA Ml7By letters dated September 12, 1989, and )A, you submitted arequest pursuant to 10 CFR 20.302 for th po0sa4 o 4ipste sludge onsite atthe Kewaunee Nuclear Power Plant. We h cc q d.lur review of the requestand find your procedures, including doc tments, to be acceptable.

This approval is granted provide a he sdsafety evaluation ispermanently incorporated into y 0 se Calculation Manual (ODCM) asan Appendix, and that future pd f these commitments are reportedto the NRC.Issuance of this safety v onpletes all effort on TAC No. M75047.O /Sincerely, Allen G. Hansen, Project ManagerProject Directorate 111-3Division of Reactor Projects III/IV/VOffice of Nuclear Reactor Regulation

Enclosure:

As statedcc w/enclosure:

See next pageNRMC LETF'R E)ISTRIBUfloN T A Hanson (MG&E)J D Loock (WPL)Larry Nielsen (ANFC)J L Belaht (NSRAC)D A Bollom 06K H Evers KNPJ P Giesler D2M L Marchi KNPD L Masarik KNPR P Pulac D2 (2)D J Rlisiu D2A I Ruege D2C A Schrock D2C R D2T J Webb KNPS F Womiak D2QA Vault KNPD-17 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013Wisconsin Public Service Corporation Kewaunee Nuclear Power Plantcc:David Baker. EsquireFoley and LardnerP.O. Box 2193Orlando, Florida 32082Glen Kunesh, ChairmanTown of CarltonRoute IKewaunee, Wisconsin 54216Mr. Harold Reckelberg, ChairmanKewaunee County BoardKewaunee County Courthouse

Kewaunee, Wisconsin

.54216ChairmanPublic Service Commission of Wisconsin Hill Farms State Office BuildingMadison, Wisconsin 53702Attorney General114 East, State CapitolMadison, Wisconsin 53702U.S. Nuclear Regulatory Counlsson Resident Inspectors OfficeRoute #1, Box 999Kewaunee, Wisconsin 542160S000S000000000.00S0000Regional Administrator

-Region IIIU.S. Nuclear Regulatory Commissio 799 Roosevelt RoadGlen Ellyn, Illinois 60137Mr. Robert S. CullenChief EngineerWisconsin Public ServP.O. Box 7854Madison,

Wisconsi, 5ionD-18 W KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6,2013* ~UNITD STATESNUCLEAR REGULATORY COMMISSION WASHINGTON.

D.C. 2* SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELY

CONTAMINATED WASTE SLUDGE*AT THE KEWAUNEE NUCLEAR POWER PLANT* WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANYMADISON GAS AND ELECTRIC COM4PANY0e DOCKET NO, 50-30

51.0 INTRODUCTION

In reference 1, Wisconsin Public Service

( ested approvalpursuant to Section 20.302 of Title 10 of the e e Regulations (CFR) for the disposal of licensed material n r us onsidered in theKewaunee Final Environmental Statement (F a ec r 1972. Additional related material from the licensee, fro at sconsin, and from thestaff are contained in references 2The WPSC request contains a detai the licensed material(i.e.. contaminated sludge) sub' t is FR 20.302 request, based onradioactivity absorbed from I ' of licensed material.

TheS15,000 cubic feet of contam ed dge identified in the request contains atotal radionuclide inven of I i of Cesium-137 and Cobalt-60.

In its submittal, the ad ;ed specific Information requested inaccordance with 10 I .0 ovided a detailed description of thelicensed

material, oro ly yzd and evaluated the information pertinent to the effects t ironment nf the proposed disposal of licensedmaterial, and c t o follow specific procedures to minimize the risk ofunexpected xpos2.0 OE 0 hDurin t a operation of Kewaunee, the potential exists for in-plantproce e which are not normally radioactive to become contaminated with ver evels of radioactive materials.

These waste streams arenormally ratmd from the radioactive streams.

However, due mainly toinfrequent, minor syvtem leaks, and anticipated operational occurrences, thepotential exists for these systems to become slightly contaminated.

AtKewaunee, the Oecondary system demineralizer resins, the survice water pre-treatment system sludges, the make-up water system resins, and the sewagetreatment plant sludges are waste streams that have the potential to becomecontaminated at very low levels.000D-19 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-2 -During the yearly testing of a batch of pre-treatment sludge, it was foundthat approximately 15,000 cubic feet of sludge had been contaminated withCs-137 and Co-60.3.0 PROPOSED DISPOSAL METHODWPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsitepursuant to 10 CFR 20.302. The sludge is currently contained in an onsitelagoon at the KNPP sewage treatment facility.

The disposal of the sludge willha hv l~ndI 2nnliratinn tn an araa lncat~d nnsiti@ at K(NPP_ as shown inFigure 1. The area will be periodically plowed to a depth of 6 inches.Table I lists the principal nuclides identified in the sludge. The ac Iis based on measurements made in 1989. The radionuclide half-lives.~ dominated by 30-year Cs-137, meet the staff's 10 CFR 20.302 guidel, ¶ .N-(reference 6), which apply to radionuclides with half-lives lessyears. T7 INucl ideCo-60Cs-1374.0 RADIOLOGICAL IMPACTS00000000000S000000000000000S000The licensee has evaluated the fol in entT11exposura pathways tomembers of the general public fr he akbkuclides in the sludge: (1)external exposure caused by gr nsh froifr.,he disposal site; (2) internalexposure from inhalation of jed ionuclides; and (3) internalexposure from ingesti ng gr t0\- Pt staff has reviewed the licensee's calculatlonal methods andbsu Ion finds that they are consistent withNRC Regulatory Guide I1 culati n of Annual Doses to Man from RoutineReleases of Reactor E eh or the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I,,e n 1, October 1977. The staff finds theassessment method g- acg abye.Table 2 listý do ulated by the licensee for the maximally exposedmember of t epu on a total activity of 0.170 mCi disposed of In thecurrent yea .. as the cumulative impact of similar disposals duringsubsequent years. any repetitive disposals, the licensee must reapply tothe NRC when a r ular disposal would exceed the. following boundaryconditions:

(1) the annual disposal must be less than a total activity of 0.2mCi; (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 siteas described in Figure 1.D-20 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-3-IAHLLZPathwayWhole Body Dose Received byMaximally Exposed Individual (mremrvear) 0.0340.0080.007Groundshine Inhalation Groundwater Ingestion TOTAL0T.0400000000000S000As shown in Table 2, the annual dose is expected to be on the0.1 mrem or less. Such a dose is a small fraction of the 300annually by members of the general public from sources of naturadiation.

The guidelines used by the NRC staff for onsite disposalare presented in Table 3, along with the staff's guideline has been satisfied.

The licensee's procedures and commitments as docu ed thacceptable, provided that they are permanently Inc edlicensee's Offslte Dose Calculation Manual (OcsZas AAruture modifications be reported to NRC In a rdr hechange protocol.

ial,\ ittal areXo theix, and thatapplicable ODCHBased on the above findings, the stadispose of the low level radioactive described In the WPSC letter dateJSiState of Wisconsin has also appeVd=4ii6see's proposal tonsite in the manner71989, to be acceptable.

lures (reference 5).The(D-21 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-4 -TABtLE320.302 Guideline for Onsite Disoosal1. The radioactive material shouldbe disposed of in a manner that Itis unlikely that the material wouldbe recycled.

Staff's Evaluation

1. Due to the nature of thedisposed material,,recycling to thegeneral public is not considered likely.2. Doses to the total body and any 2. This guideline is addressed body organ of a maximally exposed Table 2.Individual (a member of the generalpublic or a non-occupationally exposed worker) from the probablepathways of exposure to the disposed J Amaterial should be less than1 mrem/year.

3. Doses to the total body and any 3. Because t riN al ill bebody organ of an inadvertent land-spread te s c iders theintruder from the probable pathways maximally os in alof exposure should be less than scenario add the5 nreminyear..

intru 104. Doses to the total body and any 4. v c ing were to occurbody organ of an individual from T eas from regulatory assumed recycling of the disposed rol, ose to the maximally material at the time the disposal e e r of the public is notsite is released from regulatory 1to exceed mrem/year, control from all likely pathways

> ased on the exposure scenarios exposure should be less than I sidered in this analysis.

D-2200000000000000000000000000000000000000000000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-5-0000000000000000000000(1) WPSC letter from K. H. Evers to NRC Document Control Desk, September 12,1989.(2) Memorandum from L. J. Cunningham, DREP, to J. N. Hannon, "Request ForAdditional Information,"

December 11, 1989.(3) NRC letter from H. J. Davis to K. H. Evers of WPSC dated February 1(4) WPSC letter from K. H. Evers to NRC Document Control Desk, Oc e1991.(5) Letter from L. Sridharon of the State of Wisconsin Departm NatResources to M. Vandenbusch of WPSC, dated June 13, 1(6) E. F. Branagan Jr. and F. J. Congel. 'Disposal of am InnaRadioactive Wastes from Nuclear Power Plants, se)t',~at e HealthPhysics Society's midyear Symposium on Health s rations InDecontaiiinationfOecommissfontng.

OF.00I3IIxvllle bF (CONF-86O203).

Principal Contributor:

J. MinnsDate: June 17. 1992D-23 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-6-Figure 1Kewaunee Nuclear Power Plant Site Area Hap00000000000000000000000000000000000000000000D-24 KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 20130*

UNITED STATES 9/21/94:1 =NUCLEAR REGULATORY COMMISSION WASHN1GT10N, D.C. UM&OMSeptember 14., 1994M Hr. C. A. SchrockManager -Nuclear Engineering Wisconsin Public Service Corporation Post Office Box 19002*) Green Bay, WI 54307-9002

SUBJECT:

SAFETY EVALUATION FOR AN AMEND14ENT 7O AN APPROVED 10 CVRAPPLICATION FOR THE KEWAUNEE NUCLEAR PLANT (TAC NO. 14897

Dear Mr. Schrock:

By letter dated June 23, 1994, as supplemented June 29, 1994, equ edapproval to use another onsite area for the disposal of stesludge In addition to the location approved by the WRstaff has completed its review of your request and f t roposalmeets the radiological boundary conditions approv Il Ju 11. 1992,Safety Evaluation!

and is therefore acceptable,.

ta finds thatyour proposal is in accordance with 1o0 CFR 20 2 r aced 20.302 onThis approval Is granted provided that t e ety Evaluation ispermanently incorporated Into your Offsi cu ation Manual (01CM) as* an Appendix, and that future modif sot commitments are reported4>S/-Richard

3. Laufer, Acting Project Manager*

Directorate 111-3\K 0Division of Reactor Projects III/IV*) Office of Nuclear Reactor Regulation

Docket No 5 5* ~Enclo ei.-x* ~~~SafetA~Wl~

cc W/enclsee next pageST A Hme (MUdJ, K A msM CS Smaetw I"hi w S eiz (W F ) M L b b nM d a & C Ax S ks b w D 2* IA"j NW.. (ANC D L MAma VMW CA Saniuia DNPD A 1eUam 1 JN Uf DI TJWd" DIU Cob XNP L A Nb 013RAC) $ F Wandek D2K B Sven Kp RPPuh1D2M(z QA Vlt KNP1) P Gimler C A Sh*D24) D-25* P4f) ~0)0) 00KEWAUNEE POWER STATION ODCM App-D 0OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 20130Wisconsin Public Service Corporation Kewaunee Nuclear Power Plantcc:Foley & LardnerAttention:

Mr. Bradley D. JacksonOne South Pinckney StreetP. 0. Box 1497Madison, Wisconsin 53701-1497 ChairmanTown of CarltonRoute 1Kewaunee.

Wisconsin 54216Mr. Harold Reckelberg, ChairmanKewaunee County BoardKevaunee County Courthouse 0Kewaunee, Wisconsin 54216ChairmanPublic Service Comission of 0Wisconsin Hill Farms State Office BuildingMadison, Wisconsin 53702Attorney General114 East, State Capitol N-'Madison, Wisconsin 53702U. S. Nuclear Regulator'y Commiission Resident Inspectors OfficeRoute 01, Box 999 -Kewaunee, Wisconsin 54216Regional Administrator

-U. S. Nuclear Reuloa801 Warrenville RadLisle. Illinois 60 0Mr. Robert S. C 11.e0nChief Engineer eWisconsin iPOJd c ice tssionP. o. BoxiawMadison, 07D-2600!000000D-26 S000 w KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013UNITED STATESNUCLEAR REGULATORY COMMISSION eWAMINGTON.

D.C. =4WMSSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELY SCONTANINATED WASTE SLUDGE*) AT THE KEMAUNEE NUCLEAR POWER PLANT* WISCONSIN PU-LIC SERVICE CORPORATIN

WISCON1SIN POWER AND LIGHT COMPANYDOCKET NO. 50-3051.0 l.0 TOCTIoBy letter dated June 23, 1994, and as suppl on 29. 1994, Wisconsin Public Service Corporation (the licens sed val to use anotheronsite area for the disposal of cont a dge in addition to the.. location approved by the NRC on June2.0 EVALUATION-A Safety Evaluation (SE) ai

approved the licensee's requestpursuant to 10 CFR 20.302 s sal of 15,000 cubic feet ofcontaminated waste slud yIcatlon at the Kewaunee Nuclear PowerPlant (KNPP) at a specl t tion. The SE imposed the following

boundary conditions*

1. The a I sa st be less than a. total activity of 0.2 mCi.2. The a dose to the hypothetical maximally exposed Individual Ust 5 0. 1 mrea/year.

i I must be the same site.0 The I 4nated In the SE was an unused area adjacent to the onsite Iagoonat t1i4OlPP treatment facility.

In 1993, approximately 7500 cubic feetof the o 1 5,000 cubic feet of contaminated sludge was spread on thatlocato l e licensee has now proposed to dispose of the remaining contaminated sludge at another onsite location northwest of the plant (see*Attachment).

The licensee has comitted that the new disposal.

location willmeet all the radiological boundary conditions contained in the SE for the10 CFR 20.30Z application approved on June 17, 1992. Additionally.

thelicensee has stated that this additional disposal site will meet all0 applicable Wisconsin Department of Natural Resources (IIONR) application requirements (i.e., sludge application rate and frequency of spreading rate).in addition to WONR landspreading requirements regarding location and*performance standards that were required at the original disposal site.000D-2S KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-2-

3.0 CONCLUSION

The staff finds the licensee's proposal to dispose of the low-level radioactive waste sludge in the additional onsite location to be within theradiological boundary conditions a pproved In the June 17, 1992, SE and istherefore acceptable.

The staff also finds that your proposal is inaccordance 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 20.302application, the licensee Is required to permanently Incorporate thismodification Into the OffsIte Dose Calculation Manual as an Appendix, future modification of this comitment be reported to the HRC.Principal Contributor:

S. Klementovicz

Attachment:

KMPP Site Area Hap00000000000000000000000000000D-28 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013-----------------

---t------ --------------------------

1~D-29 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013K-?5-l/,,2.

UNITED STATESNUCLEAR REGULATORY COMMISSION WASHINGTON, DA.. S.CWINovember 13, 1995Mr. M. L. tarchiManager -Nuclear Business GroupWisconsin Public Service Corporation Post Office Box 19002Green Say, III 4307-9002

SUBJECT:

ALTERNTE DISPOSAL OF CONTAINATED SEVAME TREATKfA 'CCOIWANCE VITH 10 CFR 20.2002 (TAC NO. N93844)

Dear 4r. ardchi:

By letter dated October 17, 1995. as supplemented a6 r 5, yourequested approval for the onsite disposal o con 1 treatment sludge In accordance with 10 CFR 20.2002.

This ln to aprevious disposal request that wa approved ca 17, 1992.The staff has completed Its review s that yourproposal mets the radiological bound ad In the June 17.1992, Safety Evaluation, and Is theref.This approval is granted provided safety evaluation Ispenmantly incorporated Into y culation Manual (000m) as anAppendix, and that future as comitments are reported tothe NRC.Richard J.LweProject ManagerProject Directorate 111-3Division of Reactor Projects III/IVOffice of Nuclear Reactor Regulation Enclosur etY Evaluation cc: See next pageNIRC to WPSC LJT 000S0000000000000S0000T A HMC (MO&E)M W Seitz (WPL)Lftq Nilbmn (AJFCD A BoilM 06DEDayDIK H Rvm XNPM L Marchi D2I X Jubin ('NSRAC)R P P"N(3)C A Sabiuck 3W?CS Simolr X"NC R Stelahu*

D2CA SmwStnzy s F Woz" D2B Domnck NP (Corn)D-30 00* KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013Hr. M. L. ,archiWisconsin Public Service Corporation Kewaunee Nuclear Power Plant0cc:Foley A LardnerAttention:

1r. Bradley 0. Jackson*One South Pinckney StreetP. 0. Box 1497H Madison, Wisconsin 53701-1497 ChairmanTown of CarltonRoute IKewaunee, Wisconsin 54216*Mr. Harold Reckelberg, ChairmanKewaunee County BoardKewaunee County Courthouse

Kewaunee, Wisconsin 54216* ChairmanPublic Service Commisslon of* Wisconsin Hill Farms State Office BuildingMadison, Wisconsin 53702* Attorney General114 East, State Capitol* Madison, Wisconsin "702U. S. Nuclear Regulatory Comisst-Resident Inspectors Office.Route 0l, Box 999Kewaunee, Wisconsin 54216Regional Administrator IU. S. Nuclear Regula C rs'801 Warrenville Road* Lisle, Illinois 2Mr. Robert S. lnChief Enginer ic I missi onP. 0. 00 /85..-MadisonA m 53707*000000000D-3000 0KEWAUNEE POWER STATION ODCM App-D OOFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013UNITED STATESNUCLEAR REGULATORY COMMISSION WAgNINGTON, D..0 206SO-MSAFM EVALUATION fLY THE OfF CF NiLEAR REACTOb REC.LATIOM RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELYO cONTAmINATED SEvAGE TREATmENT SLwUGEAT THE KEVAINEE NMLEAR POWER PLANTWISCONSIN PUBLIC SERVICE CORPORATION MADISON GAS AND ELECTRIC COMPANVDOCKET HO. SC-305By lettero ated October 17, 1995, as imaplwtwt n V 1Wisconsin Public Service Co rtio Tic approval for theonsite disposal of contaminated s i sl t previous disposalrequest that was approved by the , O2.0In a letter dated September

12. ]ýJ t requested authorization forthe alternate disposal of very- lIs tive material.

In a SafetyEvaluation (SE) dated June 1approved the licensee's requestpursuant to 10 CFR 20.302 10 for tiI disposal of 100cubic feet of contaminat t l I l application at the KewauneeNuclear Power Plant (X 'i The SE imposed the following boundaryconditions:

1. The an u I & = t be less than a total activity of 0.2 ,,.2. The who se to the hypothetical maximally exposed Individual

" be t 0.1 mrem/year.

a must be at the same its.The e%. lleted the disposal of the contaminated waste sludge discussed in the 17, 1992. The licensee is now requesting authorization to disposd -ditiot al contaminated waste sludge within the boundaryconditions of the previously approved disposal.

3.0 EVALUATION

The licensee has proposed to dispose of approximately 6000 gallons (800 cubicfeet) of sewage sludge similar to the material approved for disposal in the SEdated June 17, 1992. The principal radionuclides identified in the wastesludge and their activity based on measurements In Mqa, 1995 are: Co-58,OOOOD-32 OOOO 0* KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 20130* 00.0009 mCI; Co-60, 0.0008 mCi; and Cr-51, 0.0006 .CI. The total combined* activity Is 0.0023 .CI. This activity Is well below the boundary value of0.2 ;Ci. Additionally, Cr-51 with it short half-life (27.7 day) will haveundergone significant decay from Its Initial value of 0.0005 @Ci.* The licensee has committed that the new disposal will met all theradiological boundary conditions, on a cumalative basis, contained In the SEfor the 10 CrR 20.302 application approved on June 17, 1902. Additionally, the licensee has stated that all applicable pendts for this disposal havebeen obtained from the Wisconsin Department of Natural Resources.

4.0 CNLSOThe staff finds the licensee's proposal to dispose of the low-leyradioactive waste sludge pursuant to 10 CFR 20.2002, on the lic e' te(see AttacNment),

Is within the radiological boundary conditions e* the June 17, 1992, SER and Is therefore acceptable.

The licensee is required to permanently Incorporate this iflca o theOffsite Dose Calculation fanual as an Appendix, and t .that twe* modifications of these commitmets are reported to P* Principal Contributor:

S. klementowicz 0 Date: November 13, 1995*

Attachment:

KNPP Site Area Nap0I0S 00ccO00000000*S -300 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013---------------------

4D-34 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 20130000000000000UNrTED STATESNUCLEAR REGULATORY COMMISSION WASHINGTON.

D.O. "6864MApril 9, 1997Mr. M. L. tarchiManager -Nuclear Business GroupWisconsin Public Service Corporation Post Office Box 19002Green Bay, WE 54307-9002

SUBJECT:

ONSITE DISPOSAL OF CONTAHINATED SLUDGE PURSUANT TO 10(TAC NO. 197411)

Dear Mr. Harchi:

By letter dated D~eener 10. 1996, you requested that .uRegulatory Commission (NRC) review the applicability 120.2002) application approved on June 17, 1992, for nal sposals of asimilar nature.The staff has completed its review of your requ ag s with yourdetermination that the 10 CFR 20.203 appli on disposal of sludgecontaminated with licensed radioactive ma a £-;iapproved onJune 17, 1992,. contains bounding conditio able for aconsite disposals of a similar nature. Safety Evaluation isenclosed..

ihard .Project ManagerProject Directorate 111-3NDivision of Reactor Projects III/[VOffice of Nuclear Reactor Regulation DocketEnclosl Evaluation cc: See n--ý epar n W419 1 "mmT A Mama. (MG&Z)mwseitg(mp H D Oww (9t)~D A Bob=. 06D E Day DIK f Evene KNpR P M.w KNlp M3C A Srchk IXNpC 3 Snx*w X"C R SbcWxu* D23 F Womoikk D2=0=3iCkMRPAedw1w XNP(C-WUSAR)

D-35 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013Mr. H. L. MarchiWisconsin Public Service Corporation cc:Foley & LardnerAttention:

Hr. Bradley 0. JacksonOne South Pinckney StreetP. 0. Box 1497Madison, Wisconsin 53701-1497 Kewaunee Nuclear Power PlantChairmanTown of CarltonRoute IKewaunee, Wiscpnsin 54216Hr. Harold Reckelberg, ChairmanKewaunee County BoardKewaunee County Courthouse

Kewaunee, Wisconsin 54216ChairmanWisconsin Public Service Commission 610 N. Whitney WayMadison, Wisconsin 53705-2729 Attorney General114 East, State CapitolMadison, Wisconsin 53702U. S. Nuclear Regulatory Commission Resident Inspectors OfficeRoute fl, Box 999Kewaunee, Wisconsin 54216 /66S6S0000000SS0S0S0000000Regional Administrator

-RegiiU. S. Nuclear Regulatory 801 Warrenvflle Road'Lisle, Illinois 60532-Mr. Rbbert S.- CullenChief EngineerWisconsin Public vce610 N. Whitneyjta

Madison, Wisý iVcIonD-36 KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15June 6, 2013SNUCLEAR REGULATORY COMMISSION 0* SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATING TO ONSITE DISPOSAL OF CONTAMINATED SLUDGE*AT THE KEWLAUNEr NCLEAft POWER PLANT*WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANYMADISON GAS AND ELECTRIC COMPANY* DOCKEt NO,. 50-305.*1.0 CNTlOUCthe By letter dated December 1 0. 1996, Wisconsin Public S em C an (thelicensee) requested that the U.S. Nuclear Regulator sion RC) reviewits determination that NRC approval, pursuant toMF for theonsite disposal of contaminated sludge at the un UCI -Power Plant.(KNPP) Is not required, provided such disposals within thelimits and bounding conditions approvedy R I une 17, 1992,Safety Evaluation (SE).* 2.0 RACKGROUN-In a leftter dated September 12, 1 t cese requested authorization forthe alternate disposal of slud c th licensed radioactive material.

In an SE dated Ju 0 the NRC approved the licensee's request pursuant to 10 CR .0 CFR 20.2002) for the disposal of15,000 cubic feet of cont s ludge by land application at the KNPP*location.

The SE imoitions as follows:1 1, The annua s WN be less than a total activity of 0.2 MCi1:2. The who0 to the hypothetical maximally exposed Individual mu be h .torem/year; and3.$,T s st be at the same site.The SE that for any repetitive disposals, the licensee must* reapply as.he.C when a particular disposal would exceed the boundaryconditions 03.0 ELUATIONThe licensee has determined that NRC approval for future onsite disposals ofsludge contaminated with licensed radioactive material is not requiredprovided 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 impleaents the guidance contained in NRC Information 00)4)S)0)D3 KEWAUNEE POWER STATION ODCM App-D wOFFSITE DOSE CALCULATION MANUAL Revision 15 0June 6, 20130-2-0Notice 8B-22. Specifically, the licensee's procedure will require theanalysis of sludge samples using a detection system design and operating characteristics that yield a lower limit of detection for Co-58, Co-GO,Cs-134, and Cs-137 consistent with measurements of environmental saumples.

Thelicensee has provided a site map (attached) that specifies the acceptable onsite disposal areas for the contaminated sludge.

4.0 CONCLUSION

0The staff agrees with the licensee's determination that additional onstte,-..

disposals of contaminated sludge, which are conducted within the boundij4" N\limits and conditions contained in the June 17, 1992, SE and within th specified in the attached site map, do not require specific NRC a \ )uThe licensee should permanently incorporate this Safety Evaluat In heOffsite Dose Calculation Manual as an Appendix.

Principal Contributor:

S. Kiementowicz Date." April 9. 1.997

Attachment:

KNPP Site Map.30000*0-0S0S0000000D-38 00S0 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 15June 6, 2013It**D-39 0000000000000000000Thi pge ntntinaly ef blnk00Thi pae ntetinaly lftblak000000000000000000000 SS0SSSS0oOffsitenDose Caclto0* Revision 16* ~December 5, 2013SSSSSSSSSSSSSSSS 0000000000000000000Thi pge ntntinaly ef blnk00Thi pae ntetinaly lftblak000000000000000000000 000S000000000S00000000Dominion Energy Kewaunee, Inc.Kewaunee Power StationOFFSITE DOSE CALCULATION MANUAL (ODCM)Revision 16DATE: December 5, 2013Approved By:Approved By:Reviewed By:Approved By:James M. HaleManager -Radiological Protection and Chemistry Richard P. RepshasManager -Regulatory AffairsJeffrey T. StaffordFacility Safety Review Committee 12/04/2013 Date12/04/2013 Date12/05/2013 Date12/05/2013 DateA. J. JordanSite Vice President KEWAUNEE POWER STATION ODCM TOC wOFFSITE DOSE CALCULATION MANUAL Revision 16 0December 5, 20130TABLE OF CONTENTS PAGE0PART I -RADIOLOGICAL EFFLUENT CONTROLS NORMAL CONDITIONS AND BASES

11.0 INTRODUCTION

11.0-112.0 (Not Used)13.0 USE AND APPLICATION 13.0.1 Definitions 13.0.1-113.0.2 Logical Connectors 13.0.2-113.0.3 Restoration Times 13.0.3-113.0.4 Frequency 13.0.4-113.0.5 ODCM Normal Condition (DNC) Applicability 13.0.5-113.0.6 ODCM Verification Requirement (DVR) 13.0.6-113.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration 13.1.1-113.1.2 Liquid Effluents Dose 13.1.2-113.1.3 Liquid Radwaste Treatment System 13.1.3-113.1.4 Liquid Holdup Tanks 13.1.4-1013.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.1 Gaseous Effluents Dose Rate 13.2.1-113.2.2 Gaseous Effluents Dose -Noble Gas 13.2.2-113.2.3 Gaseous Effluents Dose -Iodine and Particulate 13.2.3-113.2.4 Gaseous Radwaste Treatment System 13.2.4-113.2.5 Gas Storage Tanks 13.2.5-113.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-113.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3. 2-113.4 RADIOACTIVE EFFLUENTS TOTAL DOSE13.4.1 Radioactive Effluents Total Dose 13.4.1-10ii KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM TOCRevision 16December 5, 2013000000000000000000000013.513.5.113.5.213.5.314.014.1RADIOLOGICAL ENVIRONMENTAL MONITORING Monitoring ProgramLand Use CensusInterlaboratory Comparison ProgramDESIGN FEATURESGaseous and Liquid Effluent Release PointsADMINISTRATIVE CONTROLSMajor Changes to Radwaste Treatment SystemsRadioactive Effluent Release ReportSpecial ReportsPAGE13.5.1-113.5.2-113.5.3-114.1-115.015.115.215.315.1-115.2-115.3-1iii KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM TOCRevision 16December 5, 2013PART II CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENT METHODOLOGY 00SPAGE1.11.21.31.41.51.6Radiation Monitoring Instrumentation and Controls 1.0-1Liquid Effluent Monitor Setpoint Determination 1.0-1Liquid Effluent Concentration Limits -10CFR 20 1.0-4Liquid Effluent Dose Calculation

-10 CFR 50 1.0-5Liquid Effluent Dose Projections 1.0-7Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams 1.0-82.0 GASEOUS EFFLUENT METHODOLOGIES 2.12.22.32.42.52.62.72.8Radiation Monitoring Instrumentation and ControlsGaseous Effluent Monitor Setpoint Determination Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 20Gaseous Effluent Dose Calculations

-10 CFR 50Gaseous Effluent Dose Projection Environmental Radiation Protection Standards 40 CFR 190Incineration of Radioactively Contaminated OilTotal Dose2.0-12.0-32.0-52.0-72.0-102.0-112.0-112.0-110APPENDICES Appendix A (Not Used) ...................................................................................................

A-1 IAppendix BAppendix CTechnical Basis for Effective Dose Factors -Gaseous Radioactive Effluents

.. B-1Table B-1 Effective Dose Factors -Noble Gases ...................................

B-5Evaluation of Conservative, Default Effective EC Value for Liquid Effluents

.... C-1Table C-1 Calculation of Effective EC (ECe) ............................................

C-4Appendix D Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams ..... D-100000000000000000iv

KEWAUNEE POWER STATION ODCM TOCOFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013SLIST OF TABLES PAGE0PART I -RADIOLOGICAL EFFLUENT CONTROLS13.1.1-1 Radioactive Liquid Waste Sampling and Analysis 13.1.1-313.2.1-1 Radioactive Gaseous Waste Sampling and Analysis 13.2.1-313.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-513.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-5*PART II CALCULATIONAL METHODOLOGIES 01.1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATIONS 1.0-101.2 SITE RELATED INGESTION DOSE COMMITMENT FACTORS 1.0-121.3 BIOACCUMULATION FACTORS 1.0-142.1 DOSE FACTORS FOR NOBLE GASES 2.0-152.2 PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATIONS 2.0-162.3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS 2.0-172.4 R1 INHALATION PATHWAY DOSE FACTORS-ADULT 2.0-182.5 Ri INHALATION PATHWAY DOSE FACTORS-TEEN 2.0-202.6 Ri INHALATION PATHWAY DOSE FACTORS-CHILD 2.0-222.7 Ri INHALATION PATHWAY DOSE FACTORS-INFANT 2.0-242.8 Ri VEGETATION PATHWAY DOSE FACTORS-ADULT 2.0-262.9 Ri VEGETATION PATHWAY DOSE FACTORS-TEEN 2.0-282.10 R, VEGETATION PATHWAY DOSE FACTORS-CHILD 2.0-302.11 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-ADULT 2.0-322.12 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-TEEN 2.0-342.13 R1 GRASS-COW-MILK PATHWAY DOSE FACTORS-CHILD 2.0-362.14 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-INFANT 2.0-38* 2.15 Ri GROUND PLANE PATHWAY DOSE FACTORS 2.0-4000000000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM TOCRevision 16December 5, 2013LIST OF FIGURESPART I -RADIOLOGICAL EFFLUENT CONTROLSPAGE00000S014.1-1MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENT14.1-2PART II CALCULATIONAL METHODOLOGIES 123LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAMGASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAMSIMPLIFIED HEATING BOILER FUEL OIL PIPING SYSTEM1.0-92.0-132.0-140000000000000000000000000000Vi Kewaunee Power StationOffsite Dose Calculation ManualPART I -RADIOACTIVE EFFLUENT CONTROLS000000000000000000000000000 00KEWAUNEE POWER STATION ODCM 11.0 0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130

11.0 INTRODUCTION

The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established andmaintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of twoparts: Radiological Effluent

Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent

Controls, includes:

(1) The Radioactive Effluent ControlSpecifications (RECS) and Radiological Environmental Monitoring Programs (REMP) requiredby Technical Specification 5.5.1 and (2) descriptions of the information that should be includedin the Annual Radiological Environmental Operating and Radioactive Effluent Release Reportsrequired by Technical Specifications 5.6.1 and 5.6.2 respectively.

Part II, Calculational Methodologies:

provides the methodology to manually calculate radiation dose rates and doses to individual persons in UNRESTRICTED AREAS due to the routinerelease of gaseous and liquid effluents.

Long term cumulative effects are usually calculated 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 areperformed when computerized calculations are not available.

The methodology stated in this manual is acceptable for use in demonstrating compliance with10CFR20.1302;

10CFR50, Appendix I; and 40CFR190.

0More conservative calculational methods and/or conditions (e.g., location and/or exposurepathways) expected to yield higher computed doses than appropriate for the maximally exposedperson may be assumed in the dose evaluations.

The ODCM will be maintained at the station for use as a reference guide and training documentof accepted methodologies and calculations.

Changes will be made to the ODCM calculational methodologies and parameters as is deemed necessary to assure reasonable conservatism inkeeping with the principles of 10CFR50.36a and Appendix I for demonstrating radioactive effluents are ALARA.11.1 Change Process0Instructions for defining the responsibilities and requirements for revision and control of both theODCM and the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) arelocated in approved station procedure for Revision and Control of the REMM and ODCM.0000000011.0-1 1000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.1Revision 16December 5, 201313.0 USE AND APPLICATION 00000000000000000013.0.1 Definitions IlL I f'%"Ir" lr"--------

I-l-- JJIl-----------------------------------------------------

Terms defined in both Kewaunee Technical Specifications and the OFFSITE DOSECALCULATION MANUAL appear in capitalized type and are applicable throughout theRadiological Effluent Controls Normal Conditions and Bases and the Calculational Methodologies.

TermACTIONCHANNEL CHECKCHANNELFUNCTIONAL TESTCHANNELCALIBRATION FUNCTIONAL/

FUNCTIONALITY GASEOUSRADWASTETREATMENT SYSTEMMEMBER(S)

OF THEPUBLICDefinition Action shall be that part of a Normal Condition which prescribes remedial measures required under designated conditions.

CHANNEL CHECK is a qualitative determination of acceptable FUNCTIONALITY by observation of channel behavior duringoperation.

This determination shall include, where possible, comparison of the channel indication with other indications derivedfrom independent channels measuring the same variable.

A CHANNEL FUNCTIONAL TEST consists of injecting a simulated signal into the channel as close to the primary sensor as practicable toverify that it is FUNCTIONAL, including alarm and/or trip initiating action.CHANNEL CALIBRATION consists of the adjustment of channeloutput as necessary, such that it responds with acceptable range andaccuracy to known values of the parameter that the channel monitors.

Calibration shall encompass the entire channel, including alarm and/ortrip, and shall be deemed to include the CHANNEL FUNCTIONAL TEST.As defined in the Technical Requirements ManualA GASEOUS RADWASTE TREATMENT SYSTEM is any systemdesigned and installed to reduce radioactive gaseous effluents bycollecting off-gases from the primary system and providing for delay orholdup for the purpose of reducing the total radioactivity released tothe environment.

MEMBER(S)

OF THE PUBLIC means any individual except when thatindividual is receiving an OCCUPATIONAL DOSE.13.0.1 -10000000000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.1Revision 16December 5, 2013OCCUPATIONAL DOSEOFFSITE DOSECALCULATION MANUALODCM NORMALCONDITIONS (DNC)ODCMVERIFICATION REQUIREMENTS (DVR)PROCESSCONTROLPROGRAMOCCUPATIONAL DOSE means the dose received by an individual inthe course of employment in which the individual's assigned dutiesinvolve exposure to radiation or to radioactive material from licensedand unlicensed sources of radiation, whether in the possession of thelicensee or other person. OCCUPATIONAL DOSE does not includedoses received from background radiation, from any medicaladministration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75,from voluntary participation in medical research

programs, or as aMEMBER OF THE PUBLIC.The OFFSITE DOSE CALCULATION MANUAL shall contain thecurrent methodology and parameters used in the calculation of offsitedoses due to radioactive gaseous and liquid effluents, in thecalculation of gaseous and liquid effluent monitoring alarm/trip setpoints, in the conduct of the Radiological Environmental Monitoring Program.

Shall also contain the Radioactive Effluent Controls andRadiological Environmental Operating and Radioactive EffluentRelease Reports required by TS 5.6.1 and TS 5.6.2.Specify minimum requirements for ensuring safe operation of thefacility.

The Contingency Measures associated with a DNC stateNonconformances that typically describe the ways in which therequirements of the DNC can fail to be met. Specified with eachstated Nonconformance are Contingency Measures and Restoration Time(s).Verification requirements are requirements relating to test, calibration, or inspection to assure that the necessary FUNCTIONALITY ofsystems and components are maintained, that facility operation will bemaintained within the current licensing basis, and that the ODCMNormal Condition (DNC) for operation will be met.The PROCESS CONTROL PROGRAM shall contain the currentformulae,

sampling, analyses, tests, and determinations to be made toensure that the processing and packaging of solid radioactive wastes,based on demonstrated processing of actual or simulated wet solidwastes, 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 andState regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste.Licensee initiated changes to the PCP, which was approved by theCommission prior to implementation:

1. Shall be documented and records of reviews performed shall beretained as required by the quality assurance program.

Thedocumentation shall contain:a. Sufficient information to support the change together with theappropriate analyses or evaluations justifying the change(s).

b. A determination that the change will maintain the overallconformance of the solidified waste product to existingrequirements of Federal, State, or other applicable regulations.

2. Shall become effective upon review and acceptance by the FSRC.SSS0SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS13.0.1-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.1Revision 16December 5, 2013000S0000000000000000000000PUBLIC DOSEPURGE -PURGINGRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)SITE BOUNDARYSOURCE CHECKUNRESTRICTED AREAVENTILATION EXHAUSTTREATMENT SYSTEMVENTINGPUBLIC DOSE means the dose received by a MEMBER OF THEPUBLIC from exposure to radiation or to radioactive material releasedby a licensee, or to any other source of radiation under the control of alicensee.

PUBLIC DOSE does not include OCCUPATIONAL DOSE ordoses received from background radiation, from any medicaladministration 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 or PURGING is the controlled process of discharging air orgas from a confinement to maintain temperature,

pressure, humidity, concentration or other operating condition, in such a manner thatreplacement air or gas is required to purify the confinement.

The REMM shall contain the current methodology and parameters usedin the conduct of the radiological environmental monitoring program.The SITE BOUNDARY shall be that line beyond which the land isneither owned, leased, nor otherwise controlled by the licensee.

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

An UNRESTRICTED AREA shall be any area at or beyond the SITEBOUNDARY, access to which is not controlled by the licensee forpurposes of protection of individuals from exposure to radiation andradioactive materials, or any area within the SITE BOUNDARY usedfor residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

(See Plant Drawing A-408)A VENTILATION EXHAUST TREATMENT SYSTEM is any systemdesigned and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or ventexhaust gases through charcoal andlor HEPA filters for the purpose ofremoving iodines or particulates from the gaseous exhaust streamprior to the release to the environment.

Such a system is notconsidered to have any effect on noble gas effluents.

Engineered Safety Feature atmospheric cleanup systems (i.e., Auxiliary Buildingspecial ventilation, Shield Building ventilation, spent fuel poolventilation) are not considered to be VENTILATION EXHAUSTTREATMENT SYSTEM components.

VENTING is the controlled process of discharging air or gas from aconfinement to maintain temperature,

pressure, humidity, concentration or other operating condition, in such a manner thatreplacement 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 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.2Revision 16December 5, 201313.0 USE AND APPLICATION 13.0.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and areapplicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.000000000000000000000000000000000000*000000013.0.2-1 0000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.3Revision 16December 5, 201313.0 USE AND APPLICATION 13.0.3 Restoration TimesRestoration Times are the same as Completion Times as discussed in Section 1.3 of theTechnical Specifications and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.When "Immediately" is used as a Restoration Time, the Contingency Measure should bepursued without delay in a controlled manner.00000000000000000000000000000013.0.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.0 USE AND APPLICATION 13.0.4 Frequency ODCM 13.0.4Revision 16December 5, 2013Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases00000000000000000000000000000000000000013.0.4-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.5Revision 16December 5, 201313.0 USE AND APPLICATION 13.0.5 ODCM Normal Condition (DNC) Applicability DNC 13.0.5.1 DNCs shall be met during the specified conditions in the Applicability.

DNC 13.0.5.2DNC 13.0.5.3Upon discovery of a failure to meet the DNC, the Contingency Measures of theassociated Nonconformance shall be met, except as provided in DNC 13.0.5.4.

When it is discovered that a DNC has not been met and the associated contingency measures are not satisfied within the specified restoration time (oran associated contingency measure is not provided),

the equipment subject tothe DNC is in a nonconforming condition.

In this situation, appropriate actionsshall be taken as necessary to provide assurance of continued safe plantoperations.

In addition a Condition Report shall be initiated and assessment ofreasonable assurance of safety shall be conducted.

Items to be considered forthis assessment include the following:

Availability of redundant or backup equipment;

Compensatory

measures, including limited administrative controls;

Safety function and events protected against;* Probability of needing the safety function; and* Conservatism and margins.If this assessment concludes that safety is sufficiently

assured, the facility maycontinue to operate while prompt corrective action is taken.Equipment removed from service or declared nonfunctional to comply withContingency Measures may be returned to service under administrative controlsolely to perform testing required to demonstrate its FUNCTIONALITY or theFUNCTIONALITY of other equipment.

This is an exception to DNC 13.0.5.2 forthe system returned to service under administrative control to perform the testingrequired to demonstrate FUNCTIONALITY.

00S0S0S0SSSSSSSSSSSSSSSDNC 13.0.5.413.0.5-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.0.6Revision 16December 5, 201313.0 USE AND APPLICATION 13.0.6 ODCM VERIFICATION REQUIREMENTS (DVR) Applicability DVR 13.0.6.1DVR 13.0.6.2DVR 13.0.6.3DVRs shall be met during the specified conditions in the Applicability forindividual DNCs, unless otherwise stated in the DVR. Failure to meet a DVR,whether such failure is experienced during the performance of the DVR orbetween performances of the DVR, shall be failure to meet the DNC. Failure toperform a DVR within the specified Frequency shall be failure to meet theDNC except as provided in DVR 13.0.6.3.

DVR's do not have to be performed on nonfunctional equipment or variables outside specified limitsEach Verification Requirement shall be performed within the specified timeinterval with a maximum allowable extension not to exceed 25% of the specified DVR frequency.

When it is discovered that a DVR frequency (including the 1.25 times extension) has not been met, the equipment subject to the DVR is in a nonconforming condition.

In this situation, a Condition Report shall be initiated and, if indicated, determination to evaluate the impact on plant safety shall be performed in atimely fashion and in accordance with plant procedures.

Actions should be taken to restore conformance with the DNCs / DVRs in atimely fashion.00S00S0000000000000000000000000000000000013.0.6-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration ODCM 13.1.1Revision 16December 5, 2013DNC 13.1.1The concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS (Figure 14.1-1) shall be limited to:00000000000000a. 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table2, Column 2 for radionuclides other than dissolved or entrained noble gases;andb. 2 x 10 4pCi/ml total activity concentration for dissolved or entrained noblegases.APPLICABILITY:

During release via the monitored pathway.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. 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 ProgramRESTORATION TIME ANDnot met.B.2 Explain in the next Radioactive In accordance Effluent Release Report why with Radioactive the CONTINGENCY Effluent ReleaseMEASURE was not met in a Reporttimely manner.13.1.1 -1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.1Revision 16December 5, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.1.1 Perform radioactive liquid waste sampling and activity In accordance withanalysis.

Table 13.1.1-1----------

NOTE------.-.................

In accordance withIn this DVR the results of DVR 13.1.1.1 shall be used in accordance Table 13.1.1-1with the methodology and parameters of the ODCM.DVR 13.1.1.2 Verify the results of the DVR 13.1.1.1 analyses toassure that the concentrations at the point of releaseare maintained within the limits of DNC 13.1.1.000000000000000000000000000000013.1.1-2 00000000SS00000000S0KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.1Revision 16December 5, 2013Table 13.1.1-1 (Page 1 of 2)Radioactive Liquid Waste Sampling and AnalysisLIQUID RELEASETYPE1. Batch Waste ReleaseTanks (b)TYPE OFACTIVITY SAMPLE TYPEANALYSISSAMPLEFREQUENCY

a. Principal GammaEmitters(c)

b. 1-131Dissolved andc. Entrained Gases(gamma emitters)

d. H-3e. Gross Alphaf. Sr-89g. Sr-90h. Fe-55Grab Sample Each Batch (g)Grab Sample Each Batch (g)Grab Sample Each Batch (g)MINIMUMANALYSISFREQUENCY Each Batch (g)Each Batch (g)31 days31 days31 days92 days92 days92 daysLOWER LIMIT OFDETECTION (LLD)(a)1 x 1V ACi/mlI x 10e giCi/ml1 x 1V"s pCi/mI1 x 105 ACi/ml5 x 10.' ACi/ml5 x 10.8 ACi/ml5 x 10.8 gCilml1 x 10-6 ACi/mlComposite (d)Composite (d)Composite (d)Composite (d)Composite (d)Each Batch (g)Each Batch (g)Each Batch (g)Each Batch (g)Each Batch (g)2. Continuous Releases (e)(TB Sump)Principal GammaEmitters (c)b. 1-131Dissolved andc. Entrained Gases(gamma emitters)

d. H-3e. Gross Alphaf. Sr-89g. Sr-90h. Fe-55Grab SampleGrab SampleGrab SampleGrab SampleComposite (f)Composite (t)Composite (1)Composite (f)7 days7 days7 days7 days7 days7 days7 days7 days7 days7 days7 days31 days(o31 days()92 days(f92 days()92 days(f5 x 10r pCi/mI1 x 106 pCi/ml1 x 10S pCi/ml1 x 10.8 iCi/ml5 x 10.7 p.Ci/ml5 x 10.8 pCi/ml5 x 10.8 pCi/ml1 x 10i ACi/mI13.1.1-3 KEWAUNEE POWER STATION ODCM 13.1.1OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Table 13.1.1-1 (Page 2 of 2)Radioactive Liquid Waste Sampling and Analysis(a) The LLD is defined, for purposes of these DNC's, as the smallest concentration of radioactive material in a sample thatwill yield a net count, above system background, that will be detected with 95% probability with only 5% probability offalsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

4.66

SbLLD = EV*2.22 x 106*Y* exp(-A4OWhere:* LLD is the a Priori lower limit of detection as defined above, as gICi per unit mass or volume,s 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, S" 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, and0 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.

It should be recognized that the LLD is defined as an a griori (before the fact) limit representing the capability of ameasurement 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 beisolated, and then thoroughly mixed to assure representative sampling.

5(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-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides areto be considered.

Other gamma peaks that are identified, together with those of the above nuclides, shall also beanalyzed and reported in the Radioactive Effluent Release Report pursuant to DNC 15.2.(d) A composite sample is one in which the quantity of liquid sampled is -proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(e) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that hasan input flow during the continuous release.(f) As a minimum, the monthly and quarterly composite samples shall be compromised of weekly grab samples.(g) Complete prior to each release.1SSSSSS13.1.1 -4SSS

KEWAUNEE POWER STATION ODCM 13.1.1OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013*) BASES0This DNC is provided to ensure that the concentration of radioactive materials released in liquid waste*t effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that thelevels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures

within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE*PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population.

The concentration limit fordissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling

0) 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 interms 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).100000000000000000000013.1.1 -5000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.2Revision 16December 5, 201313.1.2DNC 13.1.2Liquid Effluents DoseThe dose or dose commitment to a MEMBER OF THE PUBLIC fromradioactive materials released in liquid effluents released toUNRESTRICTED AREAS shall be limited to:0a. < 1.5 mrem to the total body and < 5 mrem to any organ during anycalendar quarter; andb. < 3 mrem to the total body and < 10 mrem to any organ during anycalendar year.APPLICABILITY:

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Calculated dose to a A.1 Prepare and submit to the 30 daysMEMBER OF THE NRC, pursuant to DNC 15.3,PUBLIC from the release a Special Report thatof radioactive materials in (1) Identifies the cause(s)liquid effluents to for exceeding the limit(s)UNRESTRICTED AREAS and;exceeds limits. (2) Defines the corrective actions that have beentaken to reduce thereleases and theproposed corrective actions to be taken toassure that subsequent releases will be incompliance with DNC13.1.2.00000S00000000000000000000000000013.1.2-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.2Revision 16December 5, 20130000000000S0SACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THEPUBLIC from the release PUBLIC which includesof radioactive materials in contributions from directliquid effluents exceeds 2 radiation from the facilitytimes the limits. (including outside storagetanks, etc.).ANDImmediately B.2 Verify that the limits of DNC13.4 have not beenexceeded.

C. CONTINGENCY C.1 Prepare and submit to the 30 daysMEASURE B.2 and NRC, pursuant to DNC 15.3,Associated a Special Report, as definedRESTORATION TIME not in 10 CFR 20.2203 (a)(4), ofmet. CONTINGENCY MEASUREA.1 shall also include thefollowing:

(1) The corrective action(s) to be taken to preventrecurrence of exceeding the limits of DNC 13.4and the schedule forachieving conformance, (2) An analysis thatestimates the dose to aMEMBER OF THEPUBLIC from uraniumfuel cycle sources,including all effluentpathways and directradiation, for thecalendar year thatincludes the release(s),

and(3) Describes the levels ofradiation andconcentrations ofradioactive materialinvolved and the causeof the exposure levels orconcentrations.

13.1.2-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.2Revision 16December 5, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.2.1 Determine cumulative dose contributions from liquid 31 dayseffluents for the current calendar quarter and thecurrent calendar year in accordance with themethodology and parameters in the ODCM.00000000000000000000000000000000000000013.1.2-3 S* KEWAUNEE POWER STATION ODCM 13.1.2OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013*BASESThis DNC is provided to implement the requirements of Sections lI.A, III.A and IV.A of AppendixS1, 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 therequirements in Section III.A of Appendix I that conformance with the guides of Appendix I be5) 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 inRegulatory 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 ofEffluents from Accidental and Routine Reactor Releases for the Purpose of Implementing

Appendix I," April 1977.1SSSSSSS0SSSSSSSSSSS~13.1.2-4 SSS KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.3Revision 16December 5, 201313.1.3DNC 13.1.3Liquid Radwaste Treatment SystemThe Liquid Radwaste Treatment System, as described in the ODCM, shallbe used to reduce the radioactive material in liquid wastes prior to theirdischarge when the projected dose, due to the liquid effluent, toUNRESTRICTED AREAS would exceed in a 31 day period:a. > 0.06 mrem to the total body; orb. > 0.2 mrem to any organ.APPLICABILITY:

At all times, except for the parts of the system taken permanently out ofservice.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Radioactive liquid waste A.1 Prepare and submit to the 30 daysbeing discharged without NRC, pursuant to DNC 15.3,treatment and in excess of a Special Report thatthe above limits, includes:

(1) An explanation of whyliquid radwaste wasbeing discharged withouttreatment, identification of any non-functional

/inoperable equipment orsubsystems, and thereason for the non-functional

/ inoperability, (2) ACTION(s) taken torestore the non-functional

/ inoperable equipment toFUNCTIONAL IOPERABLE status, and(3) Summary description ofACTION(s) taken toprevent a recurrence.

00000000000000000000000000000000013.1.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.3Revision 16December 5, 2013VERIFICATION REQUIREMENTS SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSVERIFICATION FREQUENCY DVR 13.1.3.1 Project the doses due to liquid effluents from the 31 daysfacility to UNRESTRICTED AREAS in accordance withthe methodology and parameters specified in theODCM.13.1.3-2 KEWAUNEE POWER STATION ODCM 13.1.3 wOFFSITE DOSE CALCULATION MANUAL Revision 16 0December 5, 2013BASES0The requirement that the appropriate portions of this system be used, when specified, providesassurance that the releases of radioactive materials in liquid effluents will be kept "as low as isreasonably achievable."

This DNC implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 ofAppendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to10 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 inSection Il.A of Appendix 1, 10 CFR Part 50, for liquid effluents.

10S0000000000000000000000013.1.3-30 000 S0SSS000S000000SS00S0KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.1.4Revision 16December 5, 201313.1 LIQUID EFFLUENTS 13.1.4DNC 13.1.4Liquid Holdup TanksThe quantity of radioactivity contained in unprotected outdoor liquid storagetanks 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 nearestpotable water supply and surface water supply in an UNRESTRICTED AREA,excluding tritium and dissolved or entrained gases.APPLICABILITY:

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.

listed tank.ANDA.2 Initiate measures to reduce 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months scontent to within the limits.ANDA.3 Describe the events leading to Prior to submittal ofthe condition in the next Radioactive Radioactive Effluent Release Effluent ReleaseReport. ReportVERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.4.1 Sample and analyze radioactive liquid located in 31 days duringunprotected outdoor liquid storage tanks for level of addition ofradioactivity.

radioactive liquidto the tanks0SSS0SSSS13.1.4-1 0SKEWAUNEE POWER STATION ODCM 13.1.4 0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 201313.1 LIQUID EFFLUENTS 13.1.4 Liquid Holdup Tanks 0BASES0The tanks listed in this Normal Condition include outdoor tanks that are not surrounded byliners, dikes or walls capable of holding the tank contents and do not have tank overflows andsurrounding area drains connected to the radwaste treatment system.Technical Specification 5.5.1 0.c requires a program to ensure that the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of anuncontrolled release of any such tank's contents, the resulting concentration would be lessthan the limits of 10 CFR 20, Appendix B Table II, Column 2 at the nearest potable watersupply 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."

1SSSSSS0SSSSSSS00SSSSSS13.1.4-2 2SSS KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.1Revision 16December 5, 201313.2.1Gaseous Effluents Dose RateDNC 13.2.1The dose rate due to radioactive materials released in gaseous effluents from thesite to areas at and beyond the SITE BOUNDARY shall be limited to the following:

S00000S0000000a. For noble gases, < 500 mrem/yr to the total body and< 3000 mrem/yr to the skin andb. 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.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. The dose rate(s) at or A.1 Restore the release rate to Immediately beynd the SITE within the limit.BUOUNDARY due toradioactive gaseouseffluents exceeds limits.B. CONTINGENCY B.1 Initiate a CR In accordance withMEASURES Corrective ActionOR ProgramRESTORATION TIME ANDnot met.B.2 Explain in the next In accordance withRadioactive Effluent Radioactive EffluentRelease Report why the Release ReportCONTINGENCY MEASUREwas not met in a timelymanner.13.2.1 -1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALVERIFICATION REQUIREMENTS ODCM 13.2.1Revision 16December 5, 2013VERIFICATION FREQUENCY DVR 13.2.1.1 The dose rate due to noble gases in gaseous In accordance witheffluents shall be determined to be within the Table 13.2.1-1above limits in accordance with the methodology and parameters in the ODCM.DVR 13.2.1.2 The dose rate due to 1-131, 1-133, tritium and all In accordance withradionuclides in particulate form with half-lives Table 13.2.1-1> 8 days in gaseous effluents shall be determined to be within the above limits in accordance with themethodology and parameters in the ODCM byobtaining representative samples and performing analyses in accordance with the sampling andanalysis program specified in Table 13.2.1-10000000000000000S00S00S0000000000000013.2.1-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.1Revision 16December 5, 2013Table 13.2.1-1 (Page 1 of 2)Radioactive Gaseous Waste Sampling and AnalysisGASEOUS RELEASETYPETYPE OFACTIVITYANALYSISSAMPLETYPESAMPLEFREQUENCY MINIMUMANALYSISFREQUENCY LOWER LIMIT OFDETECTION (LLD)(a)0S0S00S0001. Waste Gas StorageTank and Chemicaland Volume ControlSystem Holdup Tank2. Containment Purge3. Auxiliary Buildingand Containment Building VentPrincipal GammaEmitters (b)Principal GammaEmitters (b)Principal GammaEmitters (b)H-3GrabSamplea.GrabSampleGrabSampleSilica Gel,GrabSampleCharcoalSampleParticulate Sampleb. 1-131Principal GammaC. Emitters (b)(1-131, Others)Each Tank (d)Each Purge (d)31 days31 daysContinuous (c)Continuous (c)Continuous (c)Continuous (c)Continuous (c)Each Tank (d)Each Purge (d)31 days31 days7 days7 days31 days92 daysContinuous (c)1 x 10, 4ACi/ml1 X 10-4 gCi/ml1 x 10-4 Ci/ml1 x 10 pCi/mI3 x 10.12 iACi/ml1 x 10.11 A.Ci/ml1 x 10" l.Ci/ml1 x 1011 o Ci/ml1 x 10e8 gCi/mlComposite

d. Gross Alpha Particulate SampleComposite

e. Sr-89, Sr-90 Particulate SampleSS0SSSSSSSS0SSSSNoble Gasesf. Gross Beta orGammaNoble GasMonitor13.2.1 -3 0KEWAUNEE POWER STATION ODCM 13.2.1OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Table 13.2.1-1 (Page 2 of 2)Radioactive Gaseous Waste Sampling and Analysis(a) The LLD is defined, for purposes of these DNC's, as the smallest concentration of radioactive material in a sample thatwill yield a net count, above system background, that will be detected with 95% probability with only 5% probability offalsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:

LLD = 4.66

SbWhere: EV*2.22 x 106"Y* exp(-A0t)

Where: 0 LLD is the a priori lower limit of detection as defined above, as pCi per unit mass or volume,0 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, 0 V is the sample size in units of mass or volume,* 2.22 x 106 is the number of disintegrations per minute per microcurie, 0* Y is the fractional radiochemical yield, when applicable,

? X 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.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of ameasurement 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- 087, Kr-88, Xe-133, Xe-1 33m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65,Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.

This list does not mean that only thesenuclides 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 andventilation system flow measuring devices or periodic flow estimates) for the time period covered by each dose ordose rate calculation made in accordance with ODCM DNC 13.2.1, 13.2.2, and 13.2.3.0(d) Complete prior to each release.1000000013.2.1 -4 01000 KEWAUNEE POWER STATION ODCM 13.2.1O OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013* BASESO* This DNC is provided to ensure that the dose rates at any time to a MEMBER OF THE PUBLIC at orO beyond the SITE BOUNDARY are less than or equal to 500 mrem/yr to the total body and less than orequal to 3000 mrem/yr to the skin. This also restricts

releases, at all times, for the corresponding O thyroid dose rate above background to a child via the inhalation pathway to less than or equalto 1500mrem/yr.

These dose rate limits provide additioral assurance that radioactive material discharged ingaseous 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 withinor outside the SITE BOUNDARY, will not exceed the annual average concentrations specified inAppendix B, Table 2, Column 1 of 10 CFR 20. For MEMBERS OF THE PUBLIC who may at times be1 within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually besufficiently low to compensate for any increase in the atmospheric diffusion factor above that for theSITE BOUNDARY.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated interms 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,"

AtlanticO Richfield Hanford Company Report ARH-SA-215 (June 1975).00!000!00000000!00!0* 13.2.1- 50O0 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.2Revision 16December 5, 201313.2.2Gaseous Effluent Dose -Noble GasDNC 13.2.2The air dose due to noble gases released in gaseous effluents from thefacility to areas at or beyond the SITE BOUNDARY (Plant Drawing A-408)shall be limited to the following:

a. < 5 mrad for gamma radiation and < 10 mrad for beta radiation during any carendar

quarter, andb. < 10 mrad for gamma radiation and < 20 mrad for beta radiation during any calendar year.APPLICABILITY:

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. The calculated air dose at A.1 Prepare and submit to the 30 daysor beyond the SITE NRC, pursuant to DNC 15.3,BOUNDARY due to noblegases released in gaseous a Special Report thateffluents exceeds limits. (1) Identifies the cause(s)for exceeding the limit(s)and;(2) Defines the corrective actions that have beentaken to reduce thereleases and theproposed corrective actions to be taken toassure that subsequent releases will be incompliance with DNC13.2.2.0000000000000000000000000000000000000013.2.2-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.2Revision 16December 5, 2013SS0S00000000S00ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THEPUBLIC from the release PUBLIC which includesof radioactive materials in contributions from directliquid effluents exceeds 2 radiation from the facilitytimes the limits. (including outside storagetanks, etc.).ANDImmediately B.2 Verify that the limits of DNC13.4 have not beenexceeded.

C. CONTINGENCY C.1 Prepare and submit to the 30 daysMEASURE B.2 and NRC, pursuant to DNC 15.3,Associated a Special Report, as definedRESTORATION TIME not in 10 CFR 20.2203 (a)(4), ofCONTINGENCY MEASUREmet. A.1 shall also include thefollowing:

(1) The corrective action(s) to be taken to preventrecurrence of exceeding the limits of DNC 13.4and the schedule forachieving conformance, (2) An analysis thatestimates the dose to aMEMBER OF THEPUBLIC from uraniumfuel cycle sources,including all effluentpathways and directradiation, for thecalendar year thatincludes the release(s),

and(3) Describes the levels ofradiation andconcentrations ofradioactive materialinvolved and the causeof the exposure levels orconcentrations.

13.2.2-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.2Revision 16December 5, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.2.1 Determine cumulative dose contributions for the 31 dayscurrent calendar quarter and current calendar year inaccordance with the methodology and parameters inthe ODCM.0000000000000000000000000000000000000000000013.2.2-3 W KEWAUNEE POWER STATION ODCM 13.2.2* OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013*BASESThis DNC is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix1 , 10 CFR Part 50. The DNC implements the guides set forth in Section II.B of Appendix I. The*I 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

D material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably

achievable."

The VERIFICATION REQUIREMENTS implement the requirements in SectionIII.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 thedoses due to the actual release rates of radioactive noble gases in gaseous effluents areconsistent with the methodology provided in Regulatory Guide 1.109, "Calculation of AnnualDoses 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 Guide1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents inRoutine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM*1 equations provided for determining the air doses at and beyond the SITE BOUNDARY arebased upon the historical average atmospheric conditions.

00S000000000000000*13.2.2-4 000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.3Revision 16December 5, 201313.2.3Gaseous Effluent Dose -Iodine, Tritium and Particulate DNC 13.2.3The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, andall radionuclides in particulate form with half-lives

> 8 days, in gaseouseffluents, released to areas at or beyond the SITE BOUNDARY (PlantDrawing A-408) shall be limited to the following:

a. < 7.5 mrem to any organ during any calendar

quarter, andb. < 15 mrem to any organ during any calendar year.APPLICABILITY:

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. The calculated dose from A.1 Prepare and submit to the 30 daysthe release of 1-131, 1-133, NRC, pursuant to DNC 15.3,tritium, and radionuclides a Special Report thatin particulate form with (1) Identifies the cause(s)half-lives

> 8 days for exceeding the limit(s)released in gaseous and;effluents at or beyond the (2) Defines the corrective SITE BOUNDARY actions that have beenexceeds limits, taken to reduce thereleases and theproposed corrective actions to be taken toassure that subsequent releases will be incompliance with DNC13.2.3.0000000000000000000000000000000000000000000013.2.3-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.3Revision 16December 5, 201300S000000S0000S00S00000000ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THEPUBLIC from the release PUBLIC which includesof radioactive materials in contributions from directliquid effluents exceeds 2 radiation from the facilitytimes the limits. (including outside storagetanks, etc.).ANDB.2 Verify that the limits of DNC Immediately 13.4 have not beenexceeded.

C. CONTINGENCY C.1 Prepare and submit to the 30 daysMEASURE B.2 and NRC, pursuant to DNC 15.3,Associated a Special Report, as definedRESTORATION TIME not in 10 CFR 20.2203 (a)(4), ofCONTINGENCY MEASUREmet. A.1 shall also include thefollowing:

(1) The corrective action(s) to be taken to preventrecurrence of exceeding the limits of DNC 13.4and the schedule forachieving conformance, (2) An analysis thatestimates the dose to aMEMBER OF THEPUBLIC from uraniumfuel cycle sources,including all effluentpathways and directradiation, for thecalendar year thatincludes the release(s),

and(3) Describes the levels ofradiation andconcentrations ofradioactive materialinvolved and the causeof the exposure levels orconcentrations.

13.2.3-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALVERIFICATION REQUIREMENTS ODCM 13.2.3Revision 16December 5, 2013VERIFICATION FREQUENCY DVR 13.2.3.1 Determine cumulative dose contributions for the 31 dayscurrent calendar quarter and current calendar yearfor 1-131, 1-133, tritium, and radionuclides inparticulate form with half-lives

> 8 days in accordance with the methodology and parameters in the ODCM.0000000000000000000000000000000000000000000013.2.3-3 0* KEWAUNEE POWER STATION ODCM 13.2.3* OFFSITE DOSE CALCULATION MANUAL Revision 16* December 5, 2013* BASESThis DNC is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix* I, 10 CFR Part 50. The DNC's are the guides set forth in Section II.C of Appendix I. Thecontingency 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

1 achievable."

The ODCM calculational methods specified in the DVR's implement the requirements in SectionIII.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.

TheODCM calculational methodology and parameters for calculating the doses due to the actual* release rates of the subject materials are consistent with the methodology provided inRegulatory Guide 1.109, "Calculation of Annual Doses to man from Routine Releases ofReactor 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.

Thepathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation 0 with subsequent consumption by man, 3) deposition onto grassy areas where milk animals andmeat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.000000000000000* 13.2.3- 4000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.4Revision 16December 5, 201313.2.4GASEOUS RADWASTE TREATMENT SYSTEMDNC 13.2.4The GASEOUS RADWASTE TREATMENT SYSTEM and theVENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduceradioactive materials in gaseous waste prior to their discharge when theprojected gaseous effluent air doses due to gaseous effluent releases toareas at and beyond the SITE BOUNDARY (Plant Drawing A-408) wouldbe:00a. > 0.2 mrad for gamma radiation; orb. > 0.4 mrad for beta radiation; orc. > 0.3 mrem to any organ in 31 day period. (Ventilation ExhaustTreatment System only)At all times, except for the parts of the system taken permanently out ofservice.APPLICABILITY:

ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Radioactive gaseous A. 1 Prepare and submit to the 30 dayswaste is being discharged NRC, pursuant to DNC 15.3,without treatment, a Special Report thatAND includes the following:

(1) Explanation of whyProjected doses due to the gaseous radwaste wasgaseous effluent, from the being discharged withoutfacility, at and beyond the treatment, SITE BOUNDARY would (2) Identification of anyexceed limits, non-functional Iinoperable equipment orsubsystems and thereason for thenon-functional Iinoperability, (3) ACTION(s) taken torestore thenon-functional Iinoperable equipment toFUNCTIONAL

/OPERABLE status, and(4) Summary description ofACTION(s) taken toprevent a recurrence.

13.2.4-1000000000000000000000000000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.4Revision 16December 5, 2013VERIFICATION REQUIREMENTS S000000000000000S0000VERIFICATION FREQUENCY DVR 13.2.4.1 Project the doses due to gaseous effluents from each 31 daysfacility at and beyond the SITE BOUNDARY inaccordance with the methodology and parameters inthe ODCM.13.2.4-2 0KEWAUNEE POWER STATION ODCM 13.2.4OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013BASES 0The requirement that the appropriate portions of these systems be used, whenspecified, provides reasonable assurance that the releases of radioactive materials ingaseous effluents will be kept "as low as is reasonably achievable."

0This DNC implements the requirements of 10 CFR 50.36a, General Design Criterion 60of Appendix A to 10 CFR Part 50, and the design objectives given in section II.D ofAppendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the systems werespecified as a suitable fraction of the dose design objectives set forth in Sections II.B1and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

000000000000000000000000013.2.4 -3000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.5Revision 16December 5, 201313.2 GASEOUS EFFLUENTS 0000S0000000S0000000S013.2.5DNC 13.2.5Gas Storage TanksThe radioactivity contained in each gas storage tank shall be limited to5 52,000 Curies of noble gas. (Considered as Xe-1 33)APPLICABILITY:

At all times, except when the tank is taken permanently out of service.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits, radioactive material.

ANDA.2 Reduce tank contents to within 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months sthe limits.13.2.5-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.2.5Revision 16December 5, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.5.1 Verify quantity of radioactive material contained in 31 dayseach gas storage tank is < 52,000 curies of noblegases (considered as Xe-1 33). AND.--------

NOTE------

Not required to beperformed if themost recentReactor CoolantSystem specificactivity DOSEEQUIVALENT 1-131 is< 1.0 pCi/gmOnce per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months swhen radioactive materials arebeing added to thetank0000000000000000000000000000000000000000013.2.5-2 W KEWAUNEE POWER STATION ODCM 13.2.5* OFFSITE DOSE CALCULATION MANUAL Revision 16*! December 5, 2013*BASESThis verification implements the requirement of Technical Specification 5.5.1 0.b. whichrequires a program to ensure that the quantity of radioactivity contained in each gas storagetank 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 theevent 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."

0Radiological analysis for a waste gas decay tank rupture assumes the activity in a gas decaytank is taken to be the maximum amount that could accumulate from operation with cladding0 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,xenon and krypton, are accumulated with no release over a full core cycle. The gas decaytank 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 maximuminventory 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

l 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 whenconsidered 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 bylimiting 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 gCi/gm (microcurie per gram). A calculation has shown that when a 1% failed fuel assumption is used the resultant RCS DOSE*I EQUIVALENT XE-133 activity would be 595 jiCi/gm (reference 2). Engineering experience is*that with 1.0 iCi/gm DEl-1 31 RCS activity, the associated DEX-1 33 activity is approximately

200 gCi/gm. If with an assumption of 1% failed fuel calculations results are 595 AiCi/gmDEX-133, 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 Gas2. Calculation Cl 1833, Kewaunee Power Station RCS Specific Activity Dose Equivalent

Xenon -133 Indicator

3. Calculation CN-CRA-99-46, Revision 3, Kewaunee GDT Rupture and VCT RuptureRadiation 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

13.2.5-3000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 16December 5, 201313.3 INSTRUMENTATION 13.3.1DNC 13.3.1Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent monitoring instrumentation channels shownin Table 13.3.1-1 shall be FUNCTIONAL with:a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1are not exceeded.

APPLICABILITY:

During release via the monitored pathway.ACTIONS-..--.....

----------------

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

Separate NON-CONFORMANCE entry is allowed for each channel.NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Liquid effluent monitoring A.1 Suspend the release of Immediately instrumentation channel radioactive liquid effluents alarm/trip setpoint less monitored by the affectedconservative than required.

channel.ORA.2 Declare the channel Immediately non-functional.

ORA.3 Change the setpoint so it Immediately is acceptably conservative.

0000000000000000000000000000000000000000013.3.1 -1 000000S0000000000000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 16December 5, 2013ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. One or more required B.1 Restore non-functional 30 dayschannels non-functional, channel(s) to FUNCTIONAL status.C. Liquid Radwaste EffluentLine (R-18) non-functional Prior to initiating an effluentprior to or during effluent

release, complete sectionsreleases.

C.1.1 and C.1.2C.1.1 Analyze at least 2 Prior to initiating aindependent samples in releaseaccordance with Table13.1.1-1.

ANDC.1.2 -----NOTE----Verification ACTION will beperformed by at least 2separate technically qualified members of thefacility staff.Independently verify the Prior to initiating arelease rate calculations and releasedischarge line valving.ORC.2 Suspend release of Immediately radioactive effluents via thispathway13.3.1-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 16December 5, 2013ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME----------------

NOTE----

--Failure to complete sampling andanalysis prior to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after themonitor is declared non-functional is a violation of this DNC.D.1 Collect and analyze grabD. Service Water System samples for gross radioactivity Once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sEffluent Line (R-20) non- (beta or gamma) at a lower limit offunctional prior to or detection of at least 1 x 10-6during effluent releases jiCi/ml.E. CONTINGENCY E.1 Initiate a CR In accordance withMEASURES Corrective ActionOR ProgramRESTORATION TIME of ANDA, B, C, or D not met.E.2 Explain in the next In accordance withRadioactive Effluent Radioactive EffluentRelease Report why the Release ReportCONTINGENY MEASUREwas not met in a timelymanner.I000SSSSSSSSSSSSSS0S0SSSSSSSSSSSSSSSSSSS13.3.1 -3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 16December 5, 2013VERIFICATION REQUIREMENTS

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

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

-- ---- --------------

VERIFICATION FREQUENCY DVR 13.3.1.1 Perform CHANNEL CHECK. 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sDVR 13.3.1.2 Perform SOURCE CHECK. Prior to releaseDVR 13.3.1.3 Perform SOURCE CHECK. 31 daysDVR 13.3.1.4 Perform CHANNEL FUNCTIONAL TEST 92 daysDVR 13.3.1.5 Perform CHANNEL CALIBRATION.

18 months000000000000000,0013.3.1-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.1Revision 16December 5, 2013Table 13.3.1-1Radioactive Liquid Effluent Monitoring Instrumentation REQUIREDCHANNELSPER VERIFICATION INSTRUMENT INSTRUMENT REQUIREMENTS

1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination ofReleasea. Liquid Radwaste Effluent Line (R-18) 1 DVR 13.3.1.1DVR 13.3.1.2DVR 13.3.1.4DVR 13.3.1.52. Gross Beta or Gamma Radioactivity Monitors Providing Alarm but notProviding Automatic Termination ofReleaseDVR 13.3.1.1a. Service Water System Effluent Line 1 DVR 13.3.1.3(R-20) DVR 13.3.1.4DVR 13.3.1.5000000000000000000000000000000000000000000013.3.1 -5 0* KEWAUNEE POWER STATION ODCM 13.3.1OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013*BASES0*The radioactive liquid effluent instrumentation, required FUNCTIONAL by this DNC, isprovided 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 priorto 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.*000000000000000000000000*13.3.1 -6000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 16December 5, 201313.3 INSTRUMENTATION 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DNC 13.3.2The radioactive gaseous effluent monitoring instrumentation channelsshown in Table 13.3.2-1 shall be FUIOAL with:a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.2.1 arenot exceeded.

APPLICABILITY:

During release via the monitored pathway.ACTIONS----------------

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

Separate NON-CONFORMANCE entry is allowed for each channel.NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Gaseous effluent A.1 Suspend the release of Immediately monitoring instrumentation radioactive gaseouschannel alarm/trip setpoint effluents monitored by theless conservative than affected channel.required.

ORA.2 Declare the channel Immediately non-functional.

ORA.3 Change the setpoint so it Immediately is acceptably conservative.

B. Less than the minimum B.1 Restore non-functional 30 days.number of channels channel(s) toFUNCTIONAL.

FUNCTIONAL status.000000000000000000000000000000000013.3.2-1

.00SS000000000S0SS00S0000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 16December 5, 2013ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEC. Noble Gas Activity effluent NOTE ------Prior to initiating amonitoring for the Waste Prior to initiating an releaseGas Holdup System and effluent

release, completeChemical and Volume sections C.1.1 and C.1.2.Control System HoldupTanks non-functional priorto or during releases C.1.1 Analyze at least 2independent samples inaccordance with Table13.2.1-1.

ANDC. 1.2 ------NOTE ----------------

Verification ACTION will Prior to initiating abe performed by at least 2 releasetechnically qualified members of the facilitystaff.Independently verify therelease rate calculations and discharge line valving.ORC.2 Suspend release of Immediately radioactive effluents viathis pathwayD. Noble Gas Activity effluent D.1 Take grab samples.

12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months smonitoring for the Auxiliary Building Ventilation System ANDand the Condenser Evacuation System Once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months snon-functional prior to or thereafter during releasesANDD.2 Analyze samples for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from time ofgross activity, sampling completion 13.3.2-2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 16December 5, 2013NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEE. Noble Gas Activity effluent E.1 Suspend PURGING of Immediately monitoring for the Radioactive effluents viaContainment Purge this pathway.System, 2" line and 36"duct (auto-isolation) non-functional prior to orduring releasesF. Sampler Flow rate F. 1 Estimate the flow rate for 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sMeasuring Devices (for the the non-functional Auxiliary Building channel(s).

ANDVentilation or Containment Building Ventilation Once per 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sSampler) non-functional thereafter prior to or during releasesG. Radioiodine and Particulate G.1 Continuously collect 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sSamplers (for the samples using auxiliary Auxiliary Building sampling equipment asrequired inVentilation or Containment Table 13.2.1-1.

Building Ventilation system) non-functional prior to or during releasesH. CONTINGENCY H.1 Initiate a CR In accordance withMEASURES Corrective ActionOR ProgramRESTORATION TIME A, B, ANDC, D, E, F, orGnot met.H.2 Explain in the next In accordance withRadioactive Effluent Radioactive EffluentRelease Report why the Release ReportCONTINGENCY MEASURE was not met ina timely manner..0000000S0000000S0000000000000S000S000S000S0S13.3.2-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 16December 5, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.3.2.1 Perform CHANNEL CHECK. Prior to releaseDVR 13.3.2.2 Perform CHANNEL CHECK. 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sDVR 13.3.2.3 Perform CHANNEL CHECK. 7 daysDVR 13.3.2.4 Perform SOURCE CHECK. Prior to releaseDVR 13.3.2.5 Perform SOURCE CHECK. 31 daysDVR 13.3.2.6 Perform CHANNEL FUNCTIONAL TEST. 92 daysDVR 13.3.2.7 Perform CHANNEL CALIBRATION.

18 months00000000000000000000013.3.2-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.3.2Revision 16December 5, 20130I0I000Table 13.3.2-1Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT REQUIRED NON- VERIFICATION CHANNELS PER CONFORMANCE REQUIREMENTS INSTRUMENT

1. Waste Gas Holdup System DVR 13.3.2.1DVR 13.3.2.4a. Noble Gas Activity Monitor 1 C DVR 13.3.2.6(R-13 or R-14) DVR 13.3.2.72. Condenser Evacuation System DVR 13.3.2.2DVR 13.3.2.5a. Noble Gas Activity (R-15) 1 D DVR 13.3.2.6DVR 13.3.2.73. Auxiliary Building Venta. Noble Gas Activity Monitor 1 D DVR 13.3.2.2(R-13 or R-14) DVR 13.3.2.5DVR 13.3.2.6DVR 13.3.2.7b. Radioiodine and 1 G DVR 13.3.2.3Particulate Sampler(R-13 or R-14)1 F DVR 13.3.2.2c. Sample Flow-Rate Monitor DVR 13.3.2.6(R-13 or R-14) DVR 13.3.2.74. Containment Building Venta. Radioiodine and 1 G DVR 13.3.2.3Particulate Sampler(R-21)1 F DVR 13.3.2.2b. Sample Flow-Rate Monitor DVR 13.3.2.6(R-21) DVR 13.3.2.75. Containment Purge 2" lineDVR 13.3.2.2a. Noble Gas Activity Monitor 1 E DVR 13.3.2.5(R-13 or R-14) DVR 13.3.2.6DVR 13.3.2.76. Containment Purge 36" line DVR 13.3.2.2DVR 13.3.2.4a. Noble Gas Activity Monitor E DVR 13.3.2.6(R-12 or R-21) DVR 13.3.2.70000000000000000013.3.2-5 S* KEWAUNEE POWER STATION ODCM 13.3.2OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013*BASES*The radioactive gaseous effluent instrumentation, required FUNCTIONAL by this DNC,*is provided to monitor and control, as applicable, the releases of radioactive materials ingaseous effluents during actual or potential releases of gaseous effluents.

Thealarm/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 50.100S0SSSSSSSSSSSSSSSSSSSOSSSS*13.3.2 -6S0S KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL13.4 RADIOACTIVE EFFLUENTS TOTAL DOSEODCM 13.4.1Revision 16December 5, 201313.4.1Radioactive Effluents Total DoseDNC 13.4.1The annual (calendar year) dose or dose commitment to any MEMBER OFTHE PUBLIC due to releases of radioactivity and to radiation from uraniumfuel cycle sources shall be limited to < 25 mrem to the total body or anyorgan, except the thyroid, which shall be limited to < 75 mrem.APPLICABILITY:

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Estimated dose or dose A.1 Verify the condition resulting Immediately commitment due to direct in doses exceeding theseradiation and the release limits has been corrected.

of radioactive materials inliquid or gaseous effluents exceeds the limits.B. CONTINGENCY B.1 ---------

NOTE ----MEASURES A.1 and This is the Special ReportRESTORATION TIME not required by DNC 13.1.2,met. 13.2.2, or 13.2.3supplemented with thefollowing.

30 daysSubmit a Special Report,pursuant to DNC 15.3,including a request for avariance in accordance withthe provisions of 40 CFR190. This submission isconsidered a timely request,and a variance is granteduntil staff ACTION on the._ request is complete.

00006060000000SSS0SSS0SSSSSSSSSSSSSSSSSSSS0S13.4.1 -1 0S0000S00000000000000S00KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 13.4.1Revision 16December 5, 2013VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.4.1.1 Cumulative dose contributions from liquid and 12 monthsgaseous 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 themethodology and parameters in the ODCM.DVR 13.4.1.2 Cumulative dose contributions from direct radiation 12 monthsfrom the facility shall be determined in accordance with the methodology and parameters in the ODCM.This requirement is applicable only under conditions set forth in ODCM DNC 13.4.1.A.

13.4.1 -2 KEWAUNEE POWER STATION ODCM 13.4.1OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20136BASESSThis normal condition is provided to meet the dose limitations of 40 CFR Part 190 that havebeen incorporated into 10 CFR Part 20 by 46 FR 18525. The DNC requires the preparation andsubmittal of a Special Report whenever the calculated doses from plant generated radioactive 0effluents 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 thefacility remains within twice the dose design objectives of Appendix I, and if direct radiation 0doses from the facility are kept small.The Special Report will describe a course of ACTION that should result in the limitation of the 0annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For thepurposes of the Special Report, it may be assumed that the dose commitment to the MEMBEROF THE PUBLIC from other uranium fuel cycle sources is negligible.

If the dose to any 0MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, theSpecial Report with a request for a variance (provided the release conditions resulting inviolation of 40 CFR Part 190 have not already been corrected),

in accordance with theprovisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request andfulfills the requirements of 40 CFR Part 190 until NRC staff ACTION is completed.

The varianceonly relates to the limits of 40 CFR Part 190, and does not apply in any way to the otherrequirements for dose limitation of 10 CFR Part 20, as addressed in ODCM Normal Condition 513.3.1 and 13.4.1. An individual is not considered a MEMBER OF THE PUBLIC during anyperiod in which he/she is engaged in carrying out any operation that is part of the nuclear fuelcycle.1000000000000000013.4.1-3 3000 0* KEWAUNEE POWER STATION ODCM 13.5.1OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130* 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING

I 13.5.1 Monitoring ProgramThis Kewaunee Program is established by the RADIOLOGICAL ENVIRONMENTAL

MONITORING MANUAL (REMM) and implemented by approved station procedures.

This*l program is required by Technical Specification 5.5.1.a, ODCM.0The radiological environmental monitoring program required by this DNC provides0representative measurements of radiation and of radioactive materials in those exposure*pathways and for those radionuclides that lead to the highest potential radiation exposures ofMEMBERS 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 theradiological effluent monitoring program by verifying that the measurable concentrations ofradioactive materials and levels of radiation are not higher than expected on the basis of the0effluent 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.

000000000000000000000013.5.1 -10 KEWAUNEE POWER STATION ODCM 13.5.2OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013013.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.2 Land Use Census Program SThis Kewaunee Land Use Census Program is implemented by the RADIOLOGICAL 0ENVIRONMENTAL MONITORING MANUAL (REMM) and Land Use Census Programprocedure.

BASES 00This DNC is provided to ensure that changes in the use of areas at and beyond the SITE 0BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall beused. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of thissize is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumedin 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 leafvegetation (i.e., similar to lettuce and cabbage),

and (2) a vegetation yield of 2 kg/M2.01000000000000000000013.5.2-1 0000 SS* KEWAUNEE POWER STATION ODCM 13.5.3OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013*13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING

13.5.3 Interlaboratory Comparison ProgramThis Kewaunee Interlaboratory Comparison Program is implemented by the RADIOLOGICAL

ENVIRONMENTAL MONITORING MANUAL (REMM) and approved station procedures.

BASES0The requirement for participation in an approved Interlaboratory Comparison Program is0provided to ensure that independent checks on the precision and accuracy of themeasurements of radioactive material in environmental sample matrices are performed as partof 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 ofAppendix I to 10 CFR Part 50.000000000000000000000000 13.5.3-1000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 14.1Revision 16December 5, 201314.0 DESIGN FEATURES14.1 GASEOUS AND LIQUID EFFLUENT RELEASE POINTS14.1.1 Plant drawing A-408, "Radiological Survey Site Map" depicts the site area byillustrating the SITE BOUNDARY and the restricted areas. Plant drawing A-449,"Plan of Plant Area, Fence, Lighting, and CCTV Support Structure" shows thelayout of the site buildings.

MEMBERS OF THE PUBLIC are restricted from accessto all areas of the Owner Controlled Area (OCA).14.1.2 Figure 14.1-1 presents the locations of radioactive effluent release points at theplant. The plant drawings referenced above are not included as part of the ODCMbut can be found in the plant drawing system.000000000000000000000000000000000000000000014.1 -1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 14.1Revision 16December 5, 2013FIGURE 14.1-1KE4ýAUNHI COUNTYtXALf"SlLalrA 1W WA CaNTAINUEN1

-L~L*4~VENT LEAATIDS 7T5'3 AUiXLARY But)I',%

VENTELEVaTIMv4 675*-EFFLIJENr J0JD 0DiS~iroE ELF-ADiON 580,14.1 -2 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 15.1Revision 16December 5, 201315.0 ADMINISTRATIVE CONTROLS15.1 Major Changes to Radioactive Waste Systems(1)Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid)shall be reported to the Commission in the Radioactive Effluent Release Report for the period inwhich the evaluation was reviewed by FSRC. The discussion of each change shall contain:a. A summary of the evaluation that led to the determination that the change could bemade in accordance with 10 CFR Part 50.59,b. Sufficient information to totally support the reason for the change without benefit ofadditional or supplemental information,

c. A description of the equipment, components and processes involved and theinterfaces with other plant systems,d An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differfrom those previously predicted in the license application and amendments thereto,e. An evaluation of the change, which shows the expected maximum exposures toindividuals in the UNRESTRICTED AREA and to the general population that differfrom those previously estimated in the license application and amendments thereto,f. A comparison of the predicted releases of radioactive materials in liquid andgaseous effluents and in solid waste to the actual releases for the period in whichthe changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change,andh. Documentation of the fact that the change was reviewed and found acceptable bythe FSRC.Changes shall become effective upon review and acceptance by the FSRC.00000S000000000000000000000000000000000(')Licensees may choose to submit the information called for in this requirement as part of theperiodic USAR update.15.1 -1 00* KEWAUNEE POWER STATION ODCM 15.2OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013S*15.0 ADMINISTRATIVE CONTROLS* 15.2 Radioactive Effluent Release Report0*The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include:a. A summary of the quantities of radioactive liquid and gaseous effluents and solid*waste released from the facility following the format of Regulatory Guide 1.21,*"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases 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 previousyear. 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, andprecipitation (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 thissummary of required meteorological data onsite in a file that shall be provided to*the NRC upon request.0c. An assessment of the radiation doses due to the radioactive liquid and gaseouseffluents released from the facility during the previous calendar year.0d. An assessment of radiation doses to the likely most exposed MEMBER OF THEPUBLIC from facility releases and other nearby uranium fuel cycle sources,01 including doses from primary effluent pathways and direct radiation, the previouscalendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

5All 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).100000S0000* 15.2-1000 S0KEWAUNEE POWER STATION ODCM 15.2OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130e. The report shall include a summary of the quantities of radioactive liquid andgaseous effluents and solid waste released from the facility.

The material 0provided shall be consistent with the objectives outlined in the ODCM and thePCP, and in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix Ito 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 thereporting period.g. Any changes made during the reporting period to the PROCESS CONTROL SPROGRAM (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 toDNC 13.5.2.00S000S00S0SS000SSSS000015.2-2 0000

-KEWAUNEE POWER STATION ODCM 15.3* OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013015.0 ADMINISTRATIVE CONTROLS015.3 Special Reports0Special reports may be required covering inspections, tests, and maintenance activities.

Thesespecial reports are determined on an individual basis. Their preparation and submittal are*designated in the ODCM Contingency Measures for each Normal Condition.

Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix*D, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S.Nuclear Regulatory Commission, Washington D.C. 20555 within the time period specified foreach report.*These Special Report(s) are in lieu of a Licensee Event Report100000000000000000000000015.3- 1000 Kewaunee Power StationOffsite Dose Calculation ManualPART II -CALCULATIONAL METHODOLOGIES 0000000000000000000000000000000000000S000000

KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130*1.0 LIQUID EFFLUENTS METHODOLOGY 1.1 Radiation Monitoring Instrumentation and ControlsThe liquid effluent monitoring instrumentation and controls installed at Kewaunee for0controlling 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 liquidradwaste effluent line.2) Alarm (only) -R-20 provides this function for the Service Water discharges.

03) Composite Samples -Samples are collected weekly from the Turbine BuildingSump 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.

4) Liquid Tank Controls

-All radioactive liquid tanks are located inside the Auxiliary Building and contain the suitable confinement systems and drains to preventdirect, unmonitored release to the environment.

A liquid radioactive waste flow*diagram with the applicable, associated radiation monitoring instrumentation andcontrols 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 NormalCondition 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/ml for dissolved or entrained noble gases). The following equation1 must be satisified

to meet the liquid effluent restrictions:

c< 1OxC(F+f)

(1.1)0f000000* Adapted from NUREG-0133 to include the application of 10 times the Effluent Concentration (EC) of 10 CFR 20,* Appendix B, Table 2, Column 2.0 1.0-1000 0KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013where:10xC = ten times the effluent concentration limit of 10 CFR 20, Appendix B, Table 2,Column 2, in pCi/ml. For dissolved and entrained noble gases equals 2x10-4pCi/ml.C = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity 0concentration in the effluent line prior to dilution and subsequent release; the 0setpoint, which is inversely proportional to the volumetric flow of the effluent lineand proportional to the volumetric flow of the dilution stream plus the effluentstream, represents a value which, if exceeded, would result in concentrations exceeding the limits of ODCM Normal Condition 13.1.1. 00f = the flow rate at the radiation monitor location in volume per unit time, but in the 0same units as F, below.0F = the dilution water flow rate as measured prior to the release point, in volume perunit time.[Note that if no dilution is provided, c < C. Also, note that when (F) is largecompared to (f), then (F + f) = F.]01.2.1 Liquid Effluent Monitors (Radwaste and Service Water)The setpoints for the liquid effluent monitors at the Kewaunee Power Station aredetermined by the following equations:

0SSW xSENi)SP < +bkg (1.2)C, x RRZi0xEC0where:0SP = alarm setpoint corresponding to the maximum allowable releaserate (cpm)C = the concentration of radionuclide "i" in the liquid effluent (pCi), toinclude gamma emitters only10xECi= ten times the EC value corresponding to radionuclide "i" from10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml) 01.0-200000 OO KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013O SENi the sensitivity value to which the monitor is calibrated forO radionuclide "i" (cpm per pCi/ml).

The default calibration valuefrom Table 1.1 may be used for gamma emitting radionuclides inlieu of nuclide specific values.O SW = the service water flow rate (dilution water flow) at the time ofrelease (gal/min) 0O RR = the liquid effluent release rate (gal/min)

O bkg = the background of the monitor (cpm)O The radioactivity monitor setpoint equation (1.2) remains valid during periodswhen the service water dilution is at its lowest. Reduction of the waste streamflow (RR) may be necessary during these periods to meet the discharge criteria.

At its lowest value, SW will equal RR and equation (1.2) reverts to the following 0 equation:

0 X(C1 xSEN.)O SP ' bkg (1.3)Z (IOx ECO)01.2.2 Conservative Default ValuesNon-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) are not detected bythe effluent monitor and, therefore, are not directly included in the above setpoint0equation.

These non-gamma radionuclides can, however, contribute a sizablefraction of the total EC limit (refer to Appendix C). The method specified belowfor establishing default setpoints provides conservatism to account for these non-gamma emitters and ensures that the setpoint meets the requirements of ODCMO Normal Condition 13.3.1 including all radionuclides.

Refer to Appendix C for* further discussion.

0 Conservative alarm setpoints have been determined through the use of generic,default parameters.

Table 1.1 summarizes all current default values in use forKewaunee.

They are based upon the following:

0O a) substitution of the default effective EC (ECe) value of 1.OE-06 pCi /ml (referto Appendix C for justification),

0O where:OECe -CI (1.4)(ECi)0O ~1.0- 30000O KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130b) substitution of the lowest operational service water flow, in gal/min; and,c) substitution of the highest effluent release rate, in gal/min,d) substitution of the default monitor sensitivity.

0The default setpoint equation is provided below:sp! ECex SENxSW +bkg (1.5)RR1.3 Liquid Effluent Concentration Limits -10 CFR 20 00ODCM Normal Condition 13.1.1 limits the concentration of radioactive material in liquideffluents (after dilution in the Service Water System) to less than ten times theconcentrations as specified in 10 CFR 20, Appendix B, Table 2, Column 2 forradionuclides 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 areestablished to ensure that these concentration limits are not exceeded.

In the event anyliquid 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 usingthe following equation:

where: 00-[(C, +(IOxEC,))x(RR+SW)]<

1 (1.6)C1 = concentration of radionuclide "i" in the undiluted liquid effluent(pCi/ml)010xECj = ten times the EC value corresponding to radionuclide "i" from10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml)0= 2E-04 pCi/ml for dissolved or entrained noble gasesRR = the liquid effluent release rate (gal/min)

SW = the service water flow rate (dilution water flow) at the time of the 0release (gal/min) 10001.0-400000

KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130* 1.4 Liquid Effluent Dose Calculation

-10 CFR 50* ODCM Normal Condition 13.1.2 limits the dose or dose commitment to MEMBERS OFTHE PUBLIC from radioactive materials in liquid effluents from the Kewaunee PowerStation to:0 during any calendar quarter;<:5 1.5 mrem to total body*D : 5.0 mrem to any organ, during any calendar year;* : 3.0 mrem to total body10.0 mrem to any organ.0Per Verification Requirement 13.1.2.1, the following calculational methods may be usedfor determining the dose or dose commitment due to the liquid radioactive effluents from0Kewaunee.

D0 1.67E-02x VOL= 0 -x-'Z(C, x A1o) (1.7)SW0where:0 Do = dose or dose commitment to organ "o", including total body*(mrem)0 Ao = site-related ingestion dose commitment factor to the total body or*D any organ "o" for 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)SW = average service water discharge rate during release period* (gal/min) 1.67E-02

= conversion factor (hr/min)0000001.0- 500000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 16December 5, 2013The site-related ingestion doses/dose commitment factors (Ai,) are presented inTable 1.2 and have been derived in accordance with guidance of NUREG-0133 by theequation:

Ai. = 1.14E+ 05[(UI +D,,)+(UF x BF;)]DF,(1.8)where:A1o= composite dose parameter for the total body or critical organ "o" ofan adult for radionuclide "i", for the fish ingestion and waterconsumption pathways (mrem/hr per pCi/ml)1.14E+05

= conversion factor (pCi/pCi x ml/kg -hr/yr)U, = adult water consumption (730 kg/yr)D= dilution factor from the near field area within % mile of the releasepoint to the nearest potable water intake for the adult waterconsumption (842, unitless)

UF adult fish consumption (21 kg/yr)BF bioaccumulation factor for radionuclide "i" in fish from Table 1.3(pCi/kg per pCi/1)DFj 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 ofODCM Normal Condition 13.1.2 and Verification Requirement 13.1.2.1 are those asidentified by gamma spectral analysis of the liquid waste samples collected andanalyzed 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 tothe dose analysis at a frequency consistent with the required minimum analysisfrequency of Table 13.1.1-1.

2Adapted from the Kewaunee Final Environmental Statement,Section V.1.0-6S00000S00SS0SSSSSSSSSSSSSSSSSSSSSSSSSSSS0 0* KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130* 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 toe5 release when the 31 day projected doses exceed:0* ,* 0.06 mrem to the total body, or0l .0.2 mrem to any organ.The applicable liquid waste streams and processing systems are as delineated in*D Figure 1.Dose projections are made at least once per 31 days by the following equations:

0* Dtbp =Dtb(31 +d) (1.9)Dnap = Dm.., (31 -+d) (1.10)0 where:Dtbp = the total body dose projection for current 31 day period (mrem)0*Dtb = the total body dose to date for current 31 day period as determined by equation (1.7) (mrem)5Drmaxp = the maximum organ dose projection for current 31 day period (mrem)Drmax = the maximum organ dose to date for current 31 day period as*determined by equation (1.7) (mrem)*d = the number of days to date for current 31 day periodS 31 = the number of days in a 31 day period0S0000S00l 1.0-700SSS SKEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 201301.6 Onsite Disposal of Low-Level Radioactively Contaminated Waste StreamsDuring the normal operation of Kewaunee, the potential exists for in-plant processstreams, which are not normally radioactive to become contaminated with very lowlevels of radioactive materials.

These waste streams are normally separated from theradioactive streams.

However, due mainly to infrequent, minor system leaks, andanticipated operation occurrences, the potential exists for these systems to becomeslightly contaminated.

At Kewaunee, the secondary system demineralizer resins, theservice water pretreatment system sludges, the make-up water system resins, and thesewage treatment plant sludges are waste streams that have the potential to becomecontaminated at very low levels. During the yearly testing of a batch of pre-treatment Ssludge, it was found approximately 15,000 cubic feet of sludge had been contaminated 5with Cs-137 and Co-60.The potential radiation doses to MEMBERS OF THE PUBLIC from these onsite disposalmethods are well below 1 mrem per year. This dose is in keeping with the guidelines ofthe National Council on Radiation Protection (NCRP) in their Report No. 91, in which theNCRP 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. 83-05and 88-22 that the levels of radioactive material are so low that control and disposal as aradwaste are not warranted.

The potential risks to man are negligible and the disposal Scosts as a radwaste are unwarranted and costly. 5This waste material will be monitored and evaluated prior to disposal to ensure its Sradioactive material content is negligible.

It shall then be disposed of in a normal 5conventional manner with records being maintained of all materials disposed of usingthese methods.SApprovals 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.

1SSS00S1.0-8 8SSSSS KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 16December 5, 2013Legend= = San4AofMonitot

= (Isol&=o Devoe=(Damper or Valve)-= Auto Isolation

=.... This Flow Pah a on abe usHd floeted sCooMty with ODCM and'rectrncal S lfl caton (CAB1074)

ODCM FIGURE 1LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAMGraphic, No. CS75371.0-9 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 16December 5, 2013Table 1.1Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value Units CommentsECe** calculated 1.OE-06 PCi/ml Calculate for each batch to be releaseddN/A pCi/mI Taken from gamma spectral analysisC measured N/of liquid effluentTaken from 10 CFR 20, Appendix B,EC1 as determined N/A pCi/mI Table 2, Col. 2Sensitivity (SEN)R-18 as determined 1.OE+08 cpm per Radwaste effluentR-20 as determined 1.OE+08 pCi/ml Service WaterRelease Rate(RR)R-18 as determined 8.OE+01 Determined prior to release; release ratecan be adjusted for ODCM limitgpm compliance R-20*** as determined 8.OE+02 Service WaterBackground (bkg) Nominal values only; actual valuesR-18 as determined 2.OE+03 cpm may be used in lieu of these reference R-20 as determined 6.OE+01 valuesSetpoint*

(SP)R-18****

calculated 6.25E+04+bkg cpm Default alarm setpoints; moreR-20 calculated 1.OOE+03+bkg conservative values may be used asdeem appropriate and desirable forassuring regulatory compliance and formaintaining releases ALARA.* Refer to Calculation

C1 0690 Rev. 2 Addendum B for the default setpoint calculation.

- Refer to Appendix C for derivation.

Actual SW flow is determined using OP-KW-NOP-SW-001, Service Water System,Attachment B, Service Water Pump Curves.The alarm setpoint for R-1 8 cannot exceed the linear calibration range of theradiation monitor in accordance with CAP 37265 and DCR 26981 (5.OOE+05+bkg cpm).S0S0SS0SSSSSSSSS0S00S0SSSSSSSSSSSSSSSSSSSSSS1.0-10 00S00S00S000SS000S000000000KEWAUNEE POWER STATION OD(OFFSITE DOSE CALCULATION MANUAL RevDecTable 1.2 (Page 1 of 2)Site Related Ingestion Dose Commitment Factors(mrem/hr oer uCi/ml)3M 1.0ision 16ember 5, 2013Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 -3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2P-32 1.39E+6 8.62E+4 5.36E+4 -1.56E+5Cr-51 -1.28E+0 7.63E-1 2.81 E-1 1.69E+0 3.21E+2Mn-54 -4.38E+3 8.36E+2 -1.30E+3 1.34E+4Mn-56 -1.10E+2 1.96E+1 -1.40E+2 3.52E+3Fe-55 6.61E+2 4.57E+2 1.06E+2 -2.55E+2 2.62E+2Fe-59 1.04E+3 2.45E+3 9.40E+2 -6.85E+2 8.17E+3Co-57 -2.11E+1 3.51E+1 -5.36E+2Co-58 -8.99E+1 2.02E+2 -1.82E+3Co-60 -2.58E+2 5.70E+2 -4.85E+3Ni-63 3.13E+4 2.17E+3 1.05E+3 -4.52E+2Ni-65 1.27E+2 1.65E+1Cu-64 1.01E+1Zn-65 2.32E+4 7.38E+4Zn-69 4.93E+1 9.43E+1Br-82 --7.52E+0 --4.18E+24.72E+0 -2.53E+1 -8.57E+23.33E+4 -4.93E+4 -4.65E+46.56E+0 -6.13E+1 -1.42E+12.27E+3 --2.61 E+34.05E+1 --5.83E+1Br-83Br-84 5.24E+1 -4.12E-4Br-85 2.15E+0 --Rb-86 1 .1E+5 4.71 E+4 -1.99E+4Rb-88 2.90E+2 1.54E+2 -4.OOE-9Rb-89 1.92E+2 1.35E+2 -Sr-89 2.24E+4 6.44E+2 -3.60E+3Sr-90 5.52E+5 1.35E+5 -1.59E+4Sr-91 4.13E+2 1.67E+1 1.97E+3Sr-92 1.57E+2 6.77E+0 -3.1OE+3Y-90 5.85E-1 1.57E-2 -6.21E+3Y-91m 5.53E-3 2.14E-4 -1.62E-2Y-91 8.58E+0 2.29E-1 -4.72E+3Y-92 5.14E-2 1.50E-3 -9.OOE+2Y-93 1.63E-1 4.50E-3 --5.17E+3Zr-95 2.70E-1 8.67E-2 5.87E-2 -1 36E-1 2.75E+2Zr-97 1.49E-2 3.01E-3 1.38E-3 -4.55E-3 9.34E+2Nb-95 4.47E+2 2.49E+2 1.34E+2 -2.46E+2 1.51E+6Nb-97 3.75E+0 9.48E-1 3.46E-1 -1.11E+O 3.50E+3_Mo-99 -1.07E+2 2.04E+1 -2.43E+2 2.49E+2Tc-99m 9.11E-3 2.58E-2 3.28E-1 -3.91E-1 1.26E-2 1.52E+1Tc-101 9.37E-3 1.35E-2 1.32E-1 -2.43E-1 6.90E-3Ru-103 4.61E+O 1.99E+0 -1.76E+1 5.39E+2Ru-105 3.84E-1 1.52E-1 -4.96E+O 2.35E+2Ru-106 6.86E+1 8.68E+0 -1.32E+2 4.44E+3Rh-103m ......- -...Rh-106 --1.0-11 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 1.0Revision 16December 5, 2013Table 1.2 (Page 2 of 2)Site Related Ingestion Dose Commitment Factors(mrem/hr per pCi/ml)Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIAg-110m 1.04E+0 9.62E-1 5.71E-1 -1.89E+0 -3.92E+2Sb-124 9.48E+O 1.79E-1 3.76E+0 2.30E-2 7.38E+O 2.69E+2Sb-125 6.06E+0 6.77E-2 1.44E+0 6.16E-3 4.67E+0 6.67E+1Te-125m 2.57E+3 9.31 E+2 3.44E+2 7.73E+2 1.04E+4 -.1.03E+4Te-127m 6.49E+3 2.32E+3 7.91 E+2 1.66E+3 2.64E+4 -2.18E+4Te-127 1.05E+2 3.79E+1 2.28E+1 7.81 E+1 4.29E+2 -8.32E+3Te-129m 1.1OE+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 -5.55E+4Te-129 3.01E+1 1.13E+1 7.33E+0 2.31E+1 1.27E+2 -2.27E+1Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+4Te-131 1.89E+1 7.89E+0 5.96E+0 1.55E+1 8.27E+1 2.67E+0Te-132 2.42E+3 1.56E+3 1.47E+3 1.73E+3 1.50E+4 7.39E+41-130 2.79E+1 8.23E+1 3.25E+1 6.97E+3 1.28E+2 7.08E+11-131 1.54E+2 2.20E+2 1.26E+2 7.20E+4 3.76E+2 5.79E+11-132 7.49E+0 2.00E+1 7.01E+0 7.01E+2 3.19E+1 3.76E+01-133 5.24E+1 9.11E+1 2.78E+1 1.34E+4 1.59E+2 8.19E+11-134 3.91E+0 1.06E+1 3.80E+0 1.84E+2 1.69E+1 9.26E-31-135 1.63E+1 4.28E+1 1.58E+1 2.82E+3 6.86E+1 4.83E+ 1Cs-134 2.98E+5 7.09E+5 5.79E+5 -2.29E+5 7.61E+4 1.24E+4Cs-136 3.12E+4 1.23E+5 8.86E+4 -6.85E+4 9.39E+3 1.40E+4Cs-137 3.82E+5 5.22E+5 3.42E+5 -1.77E+5 5.89E+4 1.01 E+4Cs-138 2.64E+2 5.22E+2 2.59E+2 -3.84E+2 3.79E+1 2.23E-3Ba-139 1.02E+0 7.30E-4 3.00E-2 -6.83E-4 4.14E-4 1.82E+0Ba-140 2.15E+2 2.69E-1 1.41E+1 -9.16E-2 1.54E-1 4.42E+2Ba-141 4.98E-1 3.76E-4 1.68E-2 -3.50E-4 2 13E-4 -Ba-142 2.25E-1 2.31 E-4 1.42E-2 -1.95E-4 .31 E-4La-140 1.52E-1 7.67E-2 2.03E-2 --5.63E+3La-142 7.79E-3 3.54E-3 8.82E-4 --2.59E+1Ce-141 3.17E-2 2.14E-2 2.43E-3 -9.95E-3 8.19E+1Ce-143 5.58E-3 4.13E+0 4.57E-4 -1.82E-3 f 1.54E+2Ce-144 1.65E+0 6.90E-1 8.87E-2 -4.10E-1 .5.58E+2Pr-143 5.60E-1 2.25E-1 2.77E-2 -1.30E-1 2.45E+3Pr-144 1.83E-3 7.61E-4 9.31E-5 -4.29E-4Nd-147 3.83E-1 4.42E-1 2.65E-2 -2.59E-1.

2.12E+3W-187 2.96E+2 2.47E+2 8.65E+1 --8.10E+4Np-239 2.97E-2 2.92E-3 1.61E-3 -9.10E-3 -5.98E+200S00S0S0S00S0S0SSS0SSS01.0-12

KEWAUNEE POWER STATION ODCM 1.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013*Table 1.3*Bioaccumulation Factors (BFi)(pCi/kg per pCi/liter)*

Element Freshwater FishH 9.OE-01SC 4.6E+03Na 1.OE+02P 3.OE+03Cr 2.OE+02Mn 4.0E+02Fe 1.OE+02Co 5.OE+01* Ni 1.0E+02Cu 5.OE+01Zn 2.OE+03Br 4.2E+02Rb 2.OE+03Sr 3.OE+01Y 2.5E+01Zr 3.3E+00*Nb 3.OE+04Mo 1.OE+01Tc 1.5E+01Ru 1.OE+01Rh 1.0E+01Ag 2.3E+00Sb 1.0E+00Te 4.OE+02I 1.5E+01Cs 2.0E+03Ba 4.OE+00La 2.5E+01Ce 1.OE+00Pr 2.5E+01Nd 2.5E+01W 1.2E+03S1Np.0E+01 0Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which isadapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564,*Rev. 1, October 1972.0000S*1.0- 130000 0KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 201302.0 Gaseous Effluents Methodology S2.1 Radiation Monitoring Instrumentation and ControlsThe gaseous effluent monitoring instrumentation and controls at Kewaunee for controlling andmonitoring normal radioactive material releases in accordance with 10 CFR 50, Appendix A, Criteria 60and 64, are summarized as follows:2.1.1 Waste Gas Holdup SystemThe vent header gases are collected by the Waste Gas Holdup System. Gases may be recycledto provide cover gas for the Chemical and Volume Control System Hold-Up Tanks(CVCS HUTs) or held in the Waste Gas Decay Tanks (WGDTs) for decay prior to release.Waste Gas Decay Tanks are batch released after sampling and analysis.

The tanks are 0discharged via the Auxiliary Building vent. R-13 and/or R-14.provide noble gas monitoring andautomatic isolation.

In some cases, the gas in the CVC HUTs will not be able to be completely depressurized to the 5WGDTs. CVCs HUTs will be isolated and discharged via the Auxiliary Building Vent. R-13and/or R-14 provide noble gas monitoring, and additional administrative controls are required inlieu of automatic isolation.

During a planned release, the administrative controls include the presence of an operator in theAux Building if R-13/R-14 levels are below 5,000 cpm. If levels are above 5,000 but below10,000 cpm, an operator will be present at the valve MG(R)-519A, B, or C area,in communication with the Control Room, and will be directed to manually shut the valve if levelsexceed 10,000 cpm. 52.1.2 Condenser Evacuation System 0SThe air ejector discharge is monitored by R-15. Releases from this system are normally via theAuxiliary Building vent and are monitored by R-13 and/or R-14.02.1.3 Containment PurgeContainment purge and ventilation is via the containment stack for the 36-inch RBV system but 5via the auxiliary building stack for the 2-inch vent and mini-purge blower system. The stackradiation monitoring system consists of:S* a noble gas activity monitor providing alarm and automatic termination of release(R-12 and R-21),S* 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.

2SS2.0-1SSS S0* KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013*2.1.4 Auxiliary Building VentSI The Auxiliary Building vent receives discharges from the waste gas holdup system, condenser evacuation system, fuel storage area ventilation, Auxiliary Building radwaste processing areaventilation, 2-inch containment pressure relief purge/vent system, and Auxiliary Building general* area. All effluents pass through the R-13 and/or R-14 channels which contain:0 a noble gas monitor05* an iodine sampler, and0 .a particulate sampler.The noble gas monitor provides auto isolation of any waste gas decay tank release and diverts0 other releases through the special ventilation system. Effluent flow rates are determined byinstalled flow measurement equipment or as a function of fan operation (fan curves).

Samplerflow rates are determined by flow rate instrumentation.

2.1.5 Containment Mini-PurgeNent SystemSlight pressure buildup in containment is a recurring event resulting from normal operation ofthe plant. Prior to exceeding 2 psig in containment, this excess pressure is vented off. Air fromcontainment 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 also5designed 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 Non-routine Discharge Locations SPeriodically, non-routine breaches are made in the Auxiliary and Containment buildings thatmight 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 duringoutages, holes cut in walls or ceilings to allow for moving equipment in or out of theRadiologically Controlled Areas (RCAs). All efforts to maintain these areas at negative pressureSwill be made. IF negative pressure cannot be maintained (i.e., more exhaust than supply fanvolume),

THEN supply ventilation to the area must be secured.

Criteria for determining if andwhen a release occurs from these areas is provided in implementing procedures.

As possible, S! the effects of these possible releases shall be evaluated beforehand.

Any actual releases shallbe documented and included in the monthly, quarterly and annual reports as appropriate.

SA gaseous radioactive waste flow diagram with the applicable, associated radiation monitoring 5 instrumentation and controls is presented as Figure 2.2S0SS*2.0-2S0S KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 20132.2Gaseous Effluent Monitor Setpoint Determination 2.2.1 Containment and Auxiliary Building Vent MonitorPer 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 noblegases does not exceed corresponding dose rate at the SITE BOUNDARY of 500 mrem/year tothe total body or 3000 mrem/year to the skin. Based on a grab sample analysis of theapplicable release (i.e., grab sample of the Containment vent or Auxiliary Building vent), theradiation monitoring alarm setpoints may be established by the following calculational method:FRACtb = [4.72E+ 02xX/QxVFxZ(CxKi)]]+

500 (2.1)FRACAikn

= [4.72E + 02x x/Qx VF x I (Ci x (Li + 1. IM1))]+ 3000 (2.2)where:FRACtbFRACski.x/QVFCiKiLiMi1.14.72E+025003000= fraction of the allowable release rate for the total body based on theidentified radionuclide concentrations and the release flow rate= fraction of the allowable release rate for skin based on the identified radionuclide concentrations and the release flow rateannual average meteorological dispersion for direct exposure to noblegas at the controlling SITE BOUNDARY location (sec/m3, from Table 2.3)= ventilation system flow rate for the applicable release point and monitor(ft3/min, from Table 2.2)= concentration of noble gas radionuclide

'"T as determined by radioanalysis of grab sample (pCi/cm3)= total body dose conversion factor for noble gas radionuclide

'T'(mrem/yr per pCi/m3, from Table 2.1)= beta skin dose conversion factor for noble gas radionuclide

'"T(mrem/yr per [tCi/m3, from Table 2.1)= gamma air dose conversion factor for noble gas radionuclide

'"T(mrad/yr per ljCi/m3, from Table 2.1)= mrem skin dose per mrad gamma air dose (mrem/mrad)

= conversion factor (cm3/ft3 x min/sec)= total body dose rate limit (mrem/yr)

= skin dose rate limit (mrem/yr) 2.0-3000SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 201300000000000000S00000S0000000Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpointfor the Containment and Auxiliary Building vent monitors at Kewaunee may be calculated:

SP= [I (C X SENi) -FRAC]+ bkg(2.3)where:SPSENibkg= alarm setpoint corresponding to the maximum allowable release rate(cpm)= the sensitivity value to which the monitor is calibrated for radionuclide "i"(cpm per jICi/cm3), use the default value from Table 2.2 if radionuclide specific sensitivities are not available

= background of the monitor (cpm)2.2.2 Conservative Default ValuesA 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 toadjust the setpoint to reflect minor changes in radionuclide distribution and variations in releaseflow 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,b) substitution of a radionuclide distribution 1 comprised of 95% Xe-133, 2% Xe-135, 1%Xe-133m, 1% Kr-88 and 1% Kr-85; and,c) application of an administrative multiplier of 0.5 to conservatively assure that anysimultaneous releases do not exceed the maximum allowable release rate.For this radionuclide distribution, the alarm setpoint based on the total body dose rate ismore restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table 2.2.'Adopted from ANSI N237-1976/ANS-18.1, Source Term Specifications, Table 6.2.0-4 00KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 201302.3 Gaseous Effluent Instantaneous Dose Rate Calculations

-10 CFR 2002.3.1 SITE BOUNDARY Dose Rate -Noble Gases.ODCM Normal Condition 13.2.1.a limits the dose rate at the SITE BOUNDARY due to noble gasreleases to _< 500 mrem/yr to the total body, and < 3000 mrem/yr to the skin. Radiation monitoralarm setpoints are established to ensure that these release limits are not exceeded.

In theevent any gaseous releases from the station results in the alarm setpoints being exceeded, anevaluation of the UNRESTRICTED AREA dose rate resulting from the release may beperformed using the following equations:

Dtb =x/Qx- KixQi (2.4)0andDý=X/Qx (Li +1.1M,)X(i, (2.5)0where:0D tb total body dose rate (mrem/yr) 00Ds skin dose rate (mrem/yr) 0x/Q atmospheric dispersion for direct exposure to noble gas at the controlling 0SITE BOUNDARY (sec/m3, from Table 2.3)0Q= average release rate of radionuclide

'i" over the release period underevaluation (gCi/sec)

K, total body dose conversion factor for noble gas radionuclide "r'(mrem/yr per gCi/m3, from Table 2.1)Li beta skin dose conversion factor for noble gas radionuclide

'i"(mrem/yr per gCi/m3, from Table 2.1)Mi gamma air dose conversion factor for noble gas radionuclide

'"T (mrad/yrper jICi/m3, from Table 2.1) 01.1 mrem skin dose per mrad gamma air dose (mrem/mrad) 002.0-50000 KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Actual meteorological conditions concurrent with the release period or the default, annualaverage dispersion parameters as presented in Table 2.3 may be used for evaluating the0 gaseous effluent dose rate.* 2.3.2 SITE BOUNDARY Dose Rate -Radioiodine and Particulates ODCM Normal Condition 13.2.1.b limits the dose rate to < 1500 mrem/yr to any organ for 1-131,*D 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 tothe 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. Thefollowing equation may be used for the dose rate evaluation:

Do=X/Qx (2.6)0where:0D = average organ dose rate over the sampling time period (mrem/yr)

x/Q atmospheric dispersion to the controlling SITE BOUNDARY for theinhalation pathway (sec/m3, from Table 2.3)Ri= dose parameter for radionuclide "i", (mrem/yr per jiCi/m3) for the childinhalation pathway from Table 2.60Q= average release rate over the appropriate sampling period and analysisfrequency for radionuclide "i", 1-131, 1-133, tritium or other radionuclide in* particulate form with half-life greater than 8 days (jiCi/sec) 0* By substituting 1500 mrem/yr for Do solving forQ1, an allowable release rate for 1-131 can be*determined.

Based on the annual average meteorological dispersion (see Table 2.3) and themost limiting potential

pathway, age group and organ (inhalation

pathway, child thyroid -Ri = 1.62E+07 mrem/yr per gCi/m3) the allowable release rate for 1-131 is 6.43 RCi/sec.

An0 added conservatism factor of 0.25 has been included in this calculation to account for anypotential dose contribution from other radioactive particulate material.

For a 7-day period, whichis the nominal sampling and analysis frequency for 1-131, the cumulative allowable release is3.9 Ci. Therefore, as long as the 1-131 releases in any 7-day period do not exceed 3.9 Ci, no*additional analyses are needed to verify compliance with the ODCM Normal Condition 13.2.1.blimits on allowable release rate.0000*2.0-6000 0KEWAUNEE POWER STATION ODCM 2.0 0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20132.4 Gaseous Effluent Dose Calculations

-10 CFR 502.4.1 UNRESTRICTED AREA Dose -Noble GasesODCM Normal Condition 13.2.2 requires a periodic assessment of releases of noble gases toevaluate 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).

Thefollowing equations may be used to calculate the gamma-air and beta-air doses:D= 3.17E- 08x X/Q x (M, x Q) (2.7) 0and0D,= 3.17E- 08x X/Q x (N, x Q) (2.8)where:0D, air dose due to gamma emissions for noble gas radionuclides (mrad)D= air dose due to beta emissions for noble gas radionuclides (mrad)00X/Q atmospheric dispersion to the controlling SITE BOUNDARY (sec/m3, fromTable 2.3)0QI = cumulative release of noble gas radionuclide "i" over the period of interest(pCi)M= air dose factor due to gamma emissions from noble gas radionuclide "i"(mrad/yr per gCi/m3 from Table 2.1)Ni= air dose factor due to beta emissions from noble gas radionuclide "i"(mrad/yr per gCi/m3, Table 2.1) 03.17E-08

= conversion factor (yr/sec)In lieu of the individual noble gas radionuclide dose assessment as presented above, thefollowing simplified dose calculational equation may be used for verifying compliance with the 0dose limits of ODCM Normal Condition 13.2.2. (Refer to Appendix B for the derivation andjustification for this simplified method.)0D- = 3.17E- 08 (2.9)0.50and 03.17E-080 Dp = 3.50 x X/Qx Neff x I- Qi (2.10)0.5022.0- 7000 0* KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16* December 5, 2013Swhere:*Meff = 5.3E+02 effective gamma-air dose factor (mrad/yr per gCi/m3)*l Neff = 1.1 E+03 effective beta-air dose factor (mradlyr per iiCilm3)00.50 = conservatism factorActual 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 thegamma-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 beperformed to evaluate compliance with the quarterly dose limit (< 7.5 mrem) and calendar yearlimit (< 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:SDaop =3.17E- 08x W xSFpx X( xQi) (2.11)0where: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*X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution

) via other pathways (sec/m3)*D/Q = atmospheric deposition for vegetation, milk and ground plane exposure*11 pathways (lI/m)Ri= dose factor for radionuclide "i", (mrem/yr per giCi/m3) or (M2 -mrem/yr per* iCi/sec) from Table 2.4 through 2.15 for each age group "a" and theapplicable pathway "p" as identified in Table 2.3. Values for R1 were*derived in accordance with the methods described in NUREG-0133.

0Q= cumulative release over the period of interest for radionuclide "i" -- 1-131or radioactive material in particulate form with half-life greater than 8 days2SS* 2.0-8SSSS 6KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013SFp = seasonal correction factor to account for the fraction of the period that theapplicable exposure pathway does exist.1) For milk and vegetation exposure pathways:

of months in the period that grazing occurstotal # of months in period= 0.5 for annual calculations

02) For inhalation and ground plane exposure pathways:

= 1.00In 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 13.2.3.0D.. = 3.17E- 08x W xSFpxRI -

(2.12)where: 0Dmax = maximum organ dose (mrem) SSR-131 1-131 dose parameter for the thyroid for the identified controlling pathway1.05E+12, infant thyroid dose parameter with the grass-cow-milk pathwaycontrolling (M2 -mrem/yr per l.Ci/sec)

The ground plane exposure and inhalation pathways need not be considered when the above- 0simplified calculational method is used because of the overall negligible contribution of thesepathways 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 dosecontribution than either the vegetation or grass-cow-milk pathway.

However, use of the 1-131 0thyroid 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 anypathway 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 onthe available pathways in the surrounding environment of Kewaunee as identified by the annual Sland-use census. Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2.3.200002.0-900000 0* KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 201302.5 Gaseous Effluent Dose Projection 0ODCM Normal Condition 13.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM beused to reduce radioactive material levels prior to discharge when projected doses exceed one-half theSannual design objective rate in any 31 days, i.e., exceeding:

.0.2 mrad, gamma air,S.0.4 mrad, beta air, or.0.3 mrem, maximum organ.SThe 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:

Dy = D- x (31 + d) (2.13)DQp = Dp x (31 + d) (2.14)* D.= D. x (31 + d) (2.15)0where:*1 Dgamma 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)4D-p beta air dose projection for current 31 day period (mrad)Dp 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)Dmax 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 periodS31 number of days in a 31 day period20SSSD 2.0- 10SSSS 0KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013S2.6 Environmental Radiation Protection Standards 40 CFR 190SFor 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 maybe 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 (TLDmeasurements) or by calculational methods.

NUREG-0543 describes acceptable methods fordemonstrating compliance with 40 CFR Part 190 when radioactive effluents exceed the Appendix Iportion of the specifications.

2.7 Incineration of Radioactively Contaminated OilDuring 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 allowslicensees 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, 0which are uniquely serialized such that the contents can be identified and tracked.

Each container willbe sampled and analyzed for radioactivity.

The isotopic concentrations will be recorded for eachcontainer.

The heating boiler will be utilized to incinerate the radioactively contaminated oil collected on site. Agaseous radwaste effluent dose calculation, as prescribed in Section 2.3 of the ODCM, will beperformed to ensure that the limits established by ODCM Normal Condition 13.2.1, 13.2.2 and 13.2.3are not exceeded.

Release of the activity is assumed to occur at the time the contaminated oil istransferred into the heating boiler fuel oil storage tank and will be accounted for using established plantprocedures.

This will be valid for an assumed release from the fuel oil storage tank vent, fill piping, orfrom the boiler exhaust stack. See Figure 3 for a description of the heating boiler fuel oil system.2.8 Total DoseThe purpose of this section is to describe the method used to calculate the cumulative dosecontributions from liquid and gaseous effluents in accordance with KPS Technical Specifications fortotal dose. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40CFR190, "Environmental Standards for the Uranium Fuel Cycle".0Compliance 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 doseobjectives from 10CFR50, Appendix I are much lower than the 40CFR190 dose limits to the generalpublic. With the calculated doses from the releases of radioactive materials in liquid or gaseouseffluents exceeding twice the limits outlined in ODCM DNC 13.1.2, 13.2.2, and 13.2.3, a specialanalysis shall be performed.

The purpose of this analysis is to demonstrate if the total dose to any 0MEMBER OF THE PUBLIC (real individual) from all uranium fuel cycle sources (including directradiation contributions from the facility, from outside storage areas and from all real pathways) is limitedto less than or equal to 25 mrem per year to the total body or any organ, except the thyroid, which islimited to 75 mrem per year.2.0-11 00000 00* KEWAUNEE POWER STATION ODCM 2.0OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 20130If 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 BeachNuclear Plant must also be considered due to its proximity.

Calculations will be based on the equations in Sections 1.4, 2.4.1, and 2.4.2, with the exception that usage factors and other site specificparameters may be modified using more realistic assumptions, where appropriate.

0The direct radiation component from the facility can be determined using environmental TLD results.0These 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 byincluding 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 noble0gases, ground plane deposition, and shoreline deposition, which have already been included in thesummation of the significant dose pathways to the general public. However, this conservative methodcan be used, if required, as well as any other method for estimating the direct radiation dose from*contained radioactive sources within the facility.

The methodology used to incorporate the directradiation 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.000S00000000000000000~2.0- 120000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 2013AMdAiyBuiildngvaMstcdLegend= SampleiMonitor p = Prefliter

= Isolation Devise h = HEPA Filter(Damper or Valve)c = Charcoal FRlter=3 Was Valve--= Auto Isolation

The shield building ventilation and sp)clal ventilation are ESF systems and are not parl of thenormal effluent processing system. They are Included for completeness only.*. The containment air sampler (RI I and radiation monitor (R12) can also be allgned as neededfor sampling containment vent.Gra~Ile No. CS7536ODCM FIGURE 2GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM2.0-13 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 2013Figure 3Simplified Heating Boiler Fuel Oil Piping SystemHeating Boger Fuel OU Storage Tank healing boiler30,000.Gallons fuel Glo pumps2.0-14 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 2013Table 2.1Dose Factors for Noble GasesTotal Body Dose Skin Dose Factor Gamma Air Dose Beta Air DoseFactor K, L, (mremlyr per Factor M, Factor N,Radionuclide (mrem/yr per pCi/m3) (mradlyr per (mrad/yr periPCiIm3) iJCilm3) IJCiIm3)Kr-83m 7.56E-02 1.93E+01 2.88E+02Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03Kr-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+03Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03Xe-1 35m 3.12E+03 7.11E+02 3.36E+03 7.39E+02Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03S00S0000000000000000000000000000000000000002.0-15 000000000000000000000000000000000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.2Parameters for Gaseous Alarm Setpoint Determinations ODCM 2.0Revision 16December 5, 2013Parameter Actual Value Default Value* Units CommentsX/Q calculated 3.6E-06 sec/m3 Licensing technical specification valueContainment

-normal plusVfacuvs 26,000 fmpurge modes54,000 Auxiliary Building

-normaloperation C measured N/A pCi/m3K, nuclide mrem/yr per Values from Table 2.1K_____specific NIA pCi/m3nuclide mrem/yr perLi specific N/A pCilm3 Values from Table 2.1nuclide N/A mrem/yr per Values from Table 2.1M_____specific pCi/m3Sensitivity**

(SEN)R-1 2 32E+07 cpm per Containment R-21 2.32E+07 pCi/cm3 Containment R-13 2.32E+07 Auxiliary BuildingR-14 2.32E+07 Auxiliary BuildingBackground (bkg)R-12 4.OE+02 Nominal values only; actualR-21 4.0E+01 cpm values may be used in lieu ofR-13 6.OE+02 these reference values.R-14 9.OE+02Setpoint*

(SP) Default alarm setpoints; moreR-12 calculated 2.8E+05+bkg conservative values may beR-21 calculated 2.8E+05+bkg cpm used as deemed appropriate R-13 calculated 1.3E+05+bkg and desirable for ensuringR-14 calculated 1.3E+05+bkg regulatory compliance and forI_ I maintaining releases ALARA.* Refer to Calculation

C 10690 for the default setpoint calculation.

- Conservatively based on Xe-1 33 sensitivity.

2.0-16 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.3Controlling Locations, Pathways andAtmospheric Dispersion for Dose Calculations ODCM 2.0Revision 16December 5, 2013Atmospheric Dispersion ODCM NormalCondition Location Pathways X/Q (sec/m3) D/Q (lmr2)13.2.1.a Site Boundary Noble gases 7.44E-07 N/A(0.81 mile, NNW) Direct exposure13.2.1 .b Site Boundary Inhalation, 7.44E-07 N/A(0.81 mile, NNW) Ground Plane13.2.2 Site Boundary Gamma Air 7.44E-07 N/A(0.81 mile, NNW) Beta Air3 Residence/dairy Inhalation, 13.2.3 (esilne/dairy Vegetation, Milk 3.95E-08 1.86E-09(1.3 mile SW)~ and Ground Plane00000000000S0000000000S000000000000000000002.0-17 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.4 (Page 1 of 2)R1 Inhalation Pathway Dose Factors -ADULT(mrem/yr per pCi/m3)ODCM 2.0Revision 16December 5, 2013000000000000000000000000000000000000Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4P-32 1.32E+6 7.71E+4 -8.64E+4 5.01E+4Cr-51 -5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2Mn-54 -3.96E+4 -9.84E+3 1.40E+6 7.74E+4 6.30E+3Mn-56 -1.24E+0 -1.30E+0 9.44E+3 2.02E+4 1.83E-1Fe-55 2.46E+4 1.70E+4 --7.21E+4 6.03E+3 3.94E+3Fe-59 1.18E+4 2.78E+4 --1.02E+6 1.88E+5 1.06E+4Co-57 -6.92E+2 --3.70E+5 3.14E+4 6.71E+2Co-58 -1.58E+3 --9.28E+5 1.06E+5 2.07E+3Co-60 -1.15E+4 --5.97E+6 2.85E+5 1.48E+4Ni-63 4.32E+5 3.14E+4 --1.78E+5 1.34E+4 1.45E+4Ni-65 1.54E+0 2.10E-1 --5.60E+3 1.23E+4 9.12E-2Cu-64 -1.46E+0 -4.62E+0 6.78E+3 4.90E+4 6.15E-1Zn-65 3.24E+4 1.03E+5 -6.90E+4 8.64E+5 5.34E+4 4.66E+4Zn-69 3.38E-2 6.51 E-2 -4.22E-2 9.20E+2 1.63E+1 4.52E-3Br-82 ---1.04E+4 1.35E+4Br-83 .... 2.32E+2 2.41E+2Br-84 .... 1.64E-3 3.13E+2Br-85 .... 1.28E+1Rb-86 -1.35E+5 -1.66E+4 5.90E+4Rb-88 -3.87E+2 -3.34E-9 1.93E+2Rb-89 -2.56E+2 --1.70E+2Sr-89 3.04E+5 ---1.40E+6 3.50E+5 8.72E+3Sr-90 9.92E+7 ---9.60E+6 7.22E+5 6.1OE+6Sr-91 6.19E+1 ---3.65E+4 1.91E+5 2.50E+0Sr-92 6.74E+0 ---1.65E+4 4.30E+4 2.91 E-1Y-90 2.09E+3 ---1.70E+5 5.06E+5 5.61E+1Y-91m 2.61E-1 --1.92E+3 1.33E+0 1.02E-2Y-91 4.62E+5 --1.70E+6 3.85E+5 1.24E+4Y-92 1.03E+1 --1.57E+4 7.35E+4 3.02E-1Y-93 9.44E+1 --4.85E+4 4.22E+5 2.61 E+0Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 2.33E+4Zr-97 9.68E+1 1.96E+1 -2.97E+1 7.87E+4 5.23E+5 9.04E+0Nb-95 1.41E+4 7.82E+3 -7.74E+3 5.05E+5 1.04E+5 4.21E+3Nb-97 2.22E-1 5.62E-2 -6.54E-2 2.40E+3 2.42E+2 2.05E-2Mo-99 -1.21 E+2 -2.91E+2 9.12E+4 2.48E+5 2.30E+1Tc-99m 1.03E-3 2.91E-3 -4.42E-2 7.64E+2 4.16E+3 3.70E-2Tc-101 4.18E-5 6.02E-5 -1.08E-3 3.99E+2 -5.90E-42.0-18 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.4 (Page 2 of 2)R1 Inhalation Pathway Dose Factors -ADULT(mrem/yr per pCi/m3)ODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.53E+3 5.83E+3 5.05E+5 1.1OE+5 6.58E+2Ru-105 7.90E-1 1.02E+0 1.1OE+4 4.82E+4 3.11E-1Ru-106 6.91E+4 -1.34E+5 9.36E+6 9.12E+5 8.72E+3Rh-103m -Rh-106 -......Ag-110m 1.08E+4 1.OOE+4 -1.97E+4 4.63E+6 3.02E+5 5.94E+3Sb-124 3.12E+4 5.89E+2 7.55E+1 -2.48E+6 4.06E+5 1.24E+4Sb-125 5.34E+4 5.95E+2 5.40E+1 -1.74E+6 1.01E+5 1.26E+4Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3Te-127 1.40E+0 6.42E-1 1.06E+O 5.1OE+0 6.51E+3 5.74E+4 3.1OE-1Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3Te-129 4.98E-2 2.39E-2 3.90E-2 1.87E-1 1.94E+3 1.57E+2 1.24E-2Te-131m 6.99E+1 4.36E+1 5.50E+1 3.09E+2 1.46E+5 5.56E+5 2.90E+1Te-131 1.11E-2 5.95E-3 9.36E-3 4.37E-2 1.39E+3 1.84E+1 3.59E-3Te-132 2.60E+2 2.15E+2 1.90E+2 1.46E+3 2.88E+5 5.1OE+5 1.62E+21-130 4.58E+3 1.34E+4 1.14E+6 2.09E+4 -7.69E+3 5.28E+31-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -6.28E+3 2.05E+41-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 -4.06E+2 1.16E+31-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 -8.88E+3 4.52E+31-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 -1.01E+0 6.15E+21-135 2.68E+3 6.98E+3 4.48E+5 1.11E+4 -5.25E+3 2.57E+3Cs-134 3.73E+5 8.48E+5 -2.87E+5 9.76E+4 1.04E+4 7.28E+5Cs-136 3.90E+4 1.46E+5 -8.56E+4 1.20E+4 1.17E+4 1.10E+5Cs-137 4.78E+5 6.21E+5 -2.22E+5 7.52E+4 8.40E+3 4.28E+5Cs-138 3.31E+2 6.21E+2 -4.80E+2 4.86E+1 1.86E-3 3.24E+2Ba-139 9.36E-1 6.66E-4 -6.22E-4 3.76E+3 8.96E+2 2.74E-2Ba-140 3.90E+4 4.90E+1 -1.67E+1 1.27E+6 2.18E+5 2.57E+3Ba-141 1.OOE-1 7.53E-5 -7.OOE-5 1.94E+3 1.16E-7 3.36E-3Ba-142 2.63E-2 2.70E-5 -2.29E-5 1.19E+3 -1.66E-3La-140 3.44E+2 1.74E+2 -1.36E+5 4.58E+5 4.58E+1La-142 6.83E-1 3.1OE-1 --6.33E+3 2.11E+3 7.72E-2Ce-141 1.99E+4 1.35E+4 -6.26E+3 3.62E+5 1.20E+5 1.53E+3Ce-143 1.86E+2 1.38E+2 -6.08E+1 7.98E+4 2.26E+5 1.53E+1Ce-144 3.43E+6 1.43E+6 -8.48E+5 7.78E+6 8.16E+5 1.84E+5Pr-143 9.36E+3 3.75E+3 -2.16E+3 2.81E+5 2.OOE+5 4.64E+2Pr-144 3.01E-2 1.25E-2 -7.05E-3 1.02E+3 2.15E-8 1.53E-3Nd-147 5.27E+3 6.1OE+3 -3.56E+3 2.21E+5 1.73E+5 3.65E+2W-187 8.48E+O 7.08E+0 --2.90E+4 1.55E+5 2.48E+0Np-239 2.30E+2 2.26E+1 -7.OOE+1 3.76E+4 1.19E+5 1.24E+100000S000000000000000000000000000000002.0-19 S00S0000S00O00000S0KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.5 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -TEEN(mrem/yr per pCi/m3)ODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3Na-24 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4P-32 1.89E+6 1.10E+5 --9.28E+4 7.16E+4Cr-51 --7.50E+1 3.07E+1 2.1OE+4 3.OOE+3 1.35E+2Mn-54 -5.11E+4 -1.27E+4 1.98E+6 6.68E+4 8.40E+3Mn-56 -1.70E+0 -1.79E+0 1.52E+4 5.74E+4 2.52E-1Fe-55 3.34E+4 2.38E+4 --1.24E+5 6.39E+3 5.54E+3Fe-59 1.59E+4 3.70E+4 --1.53E+6 1.78E+5 1.43E+4Co-57 -6.92E+2 --5.86E+5 3.14E+4 9.20E+2Co-58 -2.07E+3 --1.34E+6 9.52E+4 2.78E+3Co-60 -1.51E+4 --8.72E+6 2.59E+5 1.98E+4Ni-63 5.80E+5 4.34E+4 --3.07E+5 1.42E+4 1.98E+4Ni-65 2.18E+0 2.93E-1 --9.36E+3 3.67E+4 1.27E-1Cu-64 -2.03E+0 -6.41E+0 1.11E+4 6.14E+4 8.48E-1Zn-65 3.86E+4 1.34E+5 -8.64E+4 1.24E+6 4.66E+4 6.24E+4Zn-69 4.83E-2 9.20E-2 -6.02E-2 1.58E+3 2.85E+2 6.46E-3Br-82 ..... 1.82E+4Br-83 ..... 3.44E+2Br-84 ..... 4.33E+2Br-85 ..... 1.83E+1Rb-86 -1.90E+5 --1.77E+4 8.40E+4Rb-88 -5.46E+2 --2.92E-5 2.72E+2Rb-89 -3.52E+2 --3.38E-7 2.33E+2Sr-89 4.34E+5 --2.42E+6 3.71E+5 1.25E+4Sr-90 1.08E+8 --1.65E+7 7.65E+5 6.68E+6Sr-91 8.80E+1 ---6.07E+4 2.59E+5 3.51 E+0Sr-92 9.52E+0 ---2.74E+4 1.19E+5 4.06E-1Y-90 2.98E+3 ---2.93E+5 5.59E+5 8.00E+1Y-91 m 3.70E-1 ---3.20E+3 3.02E+1 1.42E-2Y-91 6.61E+5 ---2.94E+6 4.09E+5 1.77E+4Y-92 1.47E+1 ---2.68E+4 1.65E+5 4.29E-1Y-93 1.35E+2 ---8.32E+4 5.79E+5 3.72E+0Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4Zr-97 1.38E+2 2.72E+1 -4.12E+1 1.30E+5 6.30E+5 1.26E+1Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51E+5 9.68E+4 5.66E+3Nb-97 3.14E-1 7.78E-2 -9.12E-2 3.93E+3 2.17E+3 2.84E-2Mo-99 -1.69E+2 -4.11E+2 1.54E+5 2.69E+5 3.22E+1Tc-99m 1.38E-3 3.86E-3 5.76E-2 1.15E+3 6.13E+3 4.99E-2Tc-101 5.92E-5 8.40E-5 1.52E-3 6.67E+2 8.72E-7 8.24E-42.0-20 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.5 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -TEEN(mrem/yr per pCi/m3)ODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 2.1OE+3 --7.43E+3 7.83E+5 1.09E+5 8.96E+2Ru-105 1.12E+0 -1.41 E+0 1.82E+4 9.04E+4 4.34E-1Ru-106 9.84E+4 -1.90E+5 1.611E+7 9.60E+5 1.24E+4Rh-1 03m ---Rh-106 ---Ag-110m 1.38E+4 1.31E+4 -2.50E+4 6.75E+6 2.73E+5 7.99E+3Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E+6 3.98E+5 1.68E+4Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.74E+6 9.92E+4 1.72E+4Te-125m 4.88E+3 2.24E+3 1.40E+3 -5.36E+5 7.50E+4 6.67E+2Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3Te-127 2.01E+0 9.12E-1 1.42E+0 7.28E+0 1.12E+4 8.08E+4 4.42E-1Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3Te-129 7.1OE-2 3.38E-2 5.18E-2 2.66E-1 3.30E+3 1.62E+3 1.76E-2Te-131m 9.84E+1 6.01E+1 7.25E+1 4.39E+2 2.38E+5 6.21E+5 4.02E+1Te-131 1.58E-2 8.32E-3 1.24E-2 6.18E-2 2.34E+3 1.51E+1 5.04E-3Te-132 3.60E+2 2.90E+2 2.46E+2 1.95E+3 4.49E+5 4.63E+5 2.19E+21-130 6.24E+3 1.79E+4 1.49E+6 2.75E+4 -9.12E+3 7.17E+31-131 3.54E+4 4.91 E+4 1.46E+7 8.40E+4 -6.49E+3 2.64E+41-132 1.59E+3 4.38E+3 1.51 E+5 6.92E+3 -1.27E+3 1.58E+31-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 -1.03E+4 6.22E+31-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 -2.04E+1 8.40E+21-135 3.70E+3 9.44E+3 6.21 E+5 1.49E+4 -6.95E+3 3.49E+3Cs-134 5.02E+5 1.13E+6 -3.75E+5 1.46E+5 9.76E+3 5.49E+5Cs-136 5.15E+4 1.94E+5 -1.1OE+5 1.78E+4 1.09E+4 1.37E+5Cs-137 6.70E+5 8.48E+5 -3.04E+5 1.21E+5 8.48E+3 3.11E+5Cs-138 4.66E+2 8.56E+2 -6.62E+2 7.87E+1 2.70E-1 4.46E+2Ba-139 1.34E+0 9.44E-4 -8.88E-4 6.46E+3 6.45E+3 3.90E-2Ba-140 5.47E+4 6.70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3Ba-141 1.42E-1 1.06E-4 -9.84E-5 3.29E+3 7.46E-4 4.74E-3Ba-142 3.70E-2 3.70E-5 -3.14E-5 1.91E+3 -2.27E-3La-140 4.79E+2 2.36E+2 -2.14E+5 4.87E+5 6.26E+1La-142 9.60E-1 4.25E-1 -1.02E+4 1.20E+4 1.06E-1Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3Ce-143 2.66E+2 1.94E+2 -8.64E+1 1.30E+5 2.55E+5 2.16E+1Ce-144 4.89E+6 2.02E+6 -1.21 E+6 1.34E+7 8.64E+5 2.62E+5Pr-143 1.34E+4 5.31E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2Pr-144 4.30E-2 1.76E-2 -1.01E-2 1.75E+3 2.35E-4 2.18E-3Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2W-187 1.20E+1 9.76E+0 -4.74E+4 1.77E+5 3.43E+0Np-239 3.38E+2 3.19E+1 -1.OOE+2 6.49E+4 1.32E+5 1.77E+10SS00S000SSSSSSSSSSSSSSSSSSSSSSSSSSSSS2.0-21 00000S0000S0000000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.6 (Page 1 of 2)R1 Inhalation Pathway Dose Factors -CHILD(mrem/yr per tiCi/m3)ODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body,H-3 -1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4P-32 2.60E+6 1.14E+5 --4.22E+4 9.88E+4Cr-51 --8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2Mn-54 -4.29E+4 -1.OOE+4 1.58E+6 2.29E+4 9.51E+3Mn-56 -1.66E+0 -1.67E+0 1.31E+4 1.23E+5 3.12E-1Fe-55 4.74E+4 2.52E+4 -1.11 E+5 2.87E+3 7.77E+3Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4Co-57 -9.03E+2 -5.07E+5 1.32E+4 1.07E+3Co-58 -1.77E+3 -1.11E+6 3.44E+4 3.16E+3Co-60 -1.31E+4 -7.07E+6 9.62E+4 2.26E+4Ni-63 8.21 E+5 4.63E+4 -2.75E+5 6.33E+3 2.80E+4Ni-65 2.99E+0 2.96E-1 -8.18E+3 8.40E+4 1.64E-1Cu-64 -1.99E+0 -6.03E+0 9.58E+3 3.67E+4 1.07E+0Zn-65 4.26E+4 1.13E+5 -7.14E+4 9.95E+5 1.63E+4 7.03E+4Zn-69 6.70E-2 9.66E-2 -5.85E-2 1.42E+3 1.02E+4 8.92E-3Br --2.09E+4Br-83 -4.74E+2Br-84 -15.48E+2Br-85 --2.53E+1Rb-86 -1.98E+5 --7.99E+3 1.14E+5Rb-88 -5.62E+2 --1.72E+1 3.66E+2Rb-89 -3.45E+2 --1.89E+0 2.90E+2Sr-89 5.99E+5 ---2.16E+6 1.67E+5 1.72E+4Sr-90 1.01 E+8 ---1.48E+7 3.43E+5 6.44E+6Sr-91 1.21E+2 -- 5.33E+4 1.74E+5 4.59E+0Sr-92 1.31E+1 ---2.40E+4 2.42E+5 5.25E-1Y-90 4.11E+3 -- 2.62E+5 2.68E+5 1.11E+2Y-91m 5.07E-1 -- 2.81E+3 1.72E+3 1.84E-2Y-91 9.14E+5 -2.63E+6 1.84E+5 2.44E+4Y-92 2.04E+1 -- -2.39E+4 2.39E+5 5.81E-1Y-93 1.86E+2 --7.44E+4 3.89E+5 5.11E+0Zr-95 1.90E+5 4.18E+4 -5.96E+4 2.23E+6 6.11E+4 3.70E+4Zr-97 1.88E+2 2.72E+1 -3.89E+1 1.13E+5 3.51E+5 1.60E+1Nb-95 2.35E+4 9.18E+3 -8.62E+3 6.14E+5 3.70E+4 6.55E+3Nb-97 4.29E-1 7.70E-2 -8.55E-2 3.42E+3 2.78E+4 3.60E-2Mo-99 -1.72E+2 -3.92E+2 1.35E+5 1.27E+5 4.26E+1Tc-99m 1.78E-3 3.48E-3 -5.07E-2 9.51E+2 4.81E+3 5.77E-2Tc-101 8.1OE-5 8.51E-5 -1.45E-3 5.85E+2 1.63E+1 1.08E-32.0-22 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.6 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -CHILD(mrem/yr per gICi/m3)ODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI -T.BodyRu-103 2.79E+3 --7.03E+3 6.62E+5 4.48E+4 1.07E+3Ru-105 1.53E+0 --1.34E+0 1.59E+4 9.95E+4 5.55E-1Ru-106 1.36E+5 --1.84E+5 1.43E+7 4.29E+5 1.69E+4Rh-103m ---Rh-106 -Ag-110m 1.69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3Sb-124 5.74E+4 7.40E+2 1.26E+2 -3.24E+6 1.64E+5 2.OOE+4Sb-125 9.84E+4 7.59E+2 9.10E+1 -2.32E+6 4.03E+4 2.07E+4Te-125m 6.73E+3 2.33E+3 1.92E+3 -4.77E+5 3.38E+4 9.14E+2Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3Te-127 2.77E+0 9.51E-1 1.96E+0 7.07E+O 1.OOE+4 5.62E+4 6.11E-1Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-1 2.93E+3 2.55E+4 2.38E-2Te-131m 1.34E+2 5.92E+1 9.77E+1 4.OOE+2 2.06E+5 3.08E+5 5.07E+1Te-131 2.17E-2 8.44E-3 1.70E-2 5.88E-2 2.05E+3 1.33E+3 6.59E-3Te-132 4.81E+2 2.72E+2 3.17E+2 1.77E+3 3.77E+5 1.38E+5 2.63E+21-130 8.18E+3 1.64E+4 1.85E+6 2.45E+4 -5.11E+3 8.44E+31-131 4.81EE+4 4.81E+4 1.62E+7 7.88E+4 -2.84E+3 2.73E+41-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 3.20E+3 1.88E+31-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 5.48E+3 7.70E+31-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 9.55E+2 9.95E+21-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 4.44E+3 4.14E+3Cs-134 6.51E+5 1.01E+6 -3.30E+5 1.21E+5 3.85E+3 2.25E+5Cs-136 6.51E+4 1.71E+5 -9.55E+4 1.45E+4 4.18E+3 1.16E+5Cs-137 9.07E+5 8.25E+5 -2.82E+5 1.04E+5 3.62E+3 1.28E+5Cs-138 6.33E+2 8.40E+2 -6.22E+2 6.81E+1 2.70E+2 5.55E+2Ba-139 1.84E+0 9.84E-4 -8.62E-4 5.77E+3 5.77E+4 5.37E-2Ba-140 7.40E+4 6.48E+1 -2.11E+1 1.74E+6 1.02E+5 4.33E+3Ba-141 1.96E-1 1.09E-4 -9.47E-5 2.92E+3 2.75E+2 6.36E-3Ba-142 5.OOE-2 3.60E-5 -2.91E-5 1.64E+3 2.74E+0 2.79E-3La-140 6.44E+2 2.25E+2 --1.83E+5 2.26E+5 7.55E+1La-142 1.30E+0 4.11E-1 -8.70E+3 7.59E+4 1.29E-1Ce-141 3.92E+4 1.95E+4 -8.55E+3 5.44E+5 5.66E+4 2.90E+3Ce-143 3.66E+2 1.99E+2 -8.36E+1 1.15E+5 1.27E+5 2.87E+1Ce-144 6.77E+6 2.12E+6 -1.17E+6 1.20E+7 3.89E+5 3.61E+5Pr-143 1.85E+4 5.55E+3 -3.OOE+3 4.33E+5 9.73E+4 9.14E+2Pr-144 5.96E-2 1.85E-2 -9.77E-3 1.57E+3 1.97E+2 3.OOE-3Nd-147 1.08E+4 8.73E+3 -4.81E+3 3.28E+5 8.21E+4 6.81E+2W-187 1.63E+1 9.66E+0 --4.11E+4 9.1OE+4 4.33E+0Np-239 4.66E+2 3.34E+1 -9.73E+1 5.81 E+4 6.40E+4 2.35E+160000S000S00S0SSS0SSSSSSSSSSSSSSSSSSSSS2.0-23 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.7 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -INFANT(mrem/yr per igCilm3)ODCM 2.0Revision 16December 5, 20130000000000000000000000000000000000Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3Na-24 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4P-32 2.03E+6 1.12E+5 1- .61E+4 7.74E+4Cr-51 --5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1Mn-54 -2.53E+4 -4.98E+3 1.OOE+6 7.06E+3 4.98E+3Mn-56 -1.54E+0 -1.1OE+0 1.25E+4 7.17E+4 2.21E-1Fe-55 1.97E+4 1.17E+4 --8.69E+4 1.09E+3 3.33E+3Fe-59 1.36E+4 2.35E+4 1.02E+6 2.48E+4 9.48E+3Co-57 -6.51 E+2 -3.79E+5 4.86E+3 6.41 E+2Co-58 -1.22E+3 -7.77E+5 1.11E+4 1.82E+3Co-60 -8.02E+3 --4.51E+6 3.19E+4 1.18E+4Ni-63 3.39E+5 2.04E+4 --2.09E+5 2.42E+3 1.16E+4Ni-65 2.39E+0 2.84E-1 --8.12E+3 5.01EE+4 1.23E-1Cu-64 -1.88E+O -3.98E+0 9.30E+3 1.50E+4 7.74E-1Zn-65 1.93E+4 6.26E+4 -3.25E+4 6.47E+5 5.14E+4 3.11E+4Zn-69 5.39E-2 9.67E-2 -4.02E-2 1.47E+3 1.32E+4 7.18E-3Br-82 --1.33E+4Br --3.81 E+2Br-84 -- -4.OOE+2Br-85 ---2.04E+1Rb-86 -1.90E+5 --3.04E+3 8.82E+4Rb-88 -5.57E+2 --3.39E+2 2.87E+2Rb-89 3.21E+2 -.-6.82E+1 2.06E+2Sr-89 3.98E+5 --2.03E+6 6.40E+4 1.14E+4Sr-90 4.09E+7 --1.12E+7 1.31E+5 2.59E+6Sr-91 9.56E+1 -- -5.26E+4 7.34E+4 3.46E+OSr-92 1.05E+1 -- -2.38E+4 1.40E+5 3.91E-1Y-90 3.29E+3 -- -2.69E+5 1.04E+5 8.82E+1Y-91m 4.07E-1 -- -2.79E+3 2.35E+3 1.39E-2Y-91 5.88E+5 -- -2.45E+6 7.03E+4 1.57E+4Y-92 1.64E+1 -- -2.45E+4 1.27E+5 4.61 E-1Y-93 1.50E+2 ---7.64E+4 1.67E+5 4.07E+0Zr-95 1,15E+5 2.79E+4 -3.11E+4 1.75E+6 2.17E+4 2.03E+4Zr-97 1.50E+2 2.56E+1 -2.59E+1 1.1OE+5 1.40E+5 1.17E+1Nb-95 1.57E+4 6.43E+3 -4.72E+3 4.79E+5 1.27E+4 3.78E+3Nb-97 3.42E-1 7.29E-2 -5.70E-2 3.32E+3 2.69E+4 2.63E-2Mo-99 -1.65E+2 -2.65E+2 1.35E+5 4.87E+4 3.23E+1Tc-99m 1.40E-3 2.88E-3 -3.11E-2 8.11E+2 2.03E+3 3.72E-2Tc-101 6.51E-5 8.23E-5 -9.79E-4 5.84E+2 8.44E+2 8.12E-42.0-24 66KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.7 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -INFANT(mrem/yr per giCi/m3)ODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 2.02E+3 --4.24E+3 5.52E+5 1.61E+4 6.79E+2Ru-105 1.22E+0 --8.99E-1 1.57E+4 4.84E+4 4.10E-1Ru-106 8.68E+4 --1.07E+5 1.16E+7 1.64E+5 1.09E+4Rh-103m--

---Rh-106 -------Ag-110m 9.98E+3 7.22E+3 -1.09E+4 3.67E+6 3.30E+4 5.OOE+3Sb-124 3.79E+4 5.56E+2 1.01E+2 -2.65E+6 5.91E+4 1.20E+4Sb-125 5.17E+4 4.77E+2 6.23E+1 -1.64E+6 1.47E+4 1.09E+4Te-125m 4.76E+3 1.99E+3 1.62E+3 -4.47E+5 1.29E+4 6.58E+2Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3Te-127 2.23E+0 9.53E-1 1.85E+0 4.86E+0 1.03E+4 2.44E+4 4.89E-1Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-1 3.OOE+3 2.63E+4 1.88E-2Te-131m 1.07E+2 5.50E+1 8.93E+1 2.65E+2 1.99E+5 1.19E+5 3.63E+1Te-131 1.74E-2 8.22E-3 1.58E-2 3.99E-2 2.06E+3 8.22E+3 5.OOE-3Te-132 3.72E+2 2.37E+2 2.79E+2 1.03E+3 3.40E+5 4.41E+4 1.76E+21-130 6.36E+3 1.39E+4 1.60E+6 1.53E+4 -1.99E+3 5.57E+31-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -1.06E+3 1.96E+41-132 1.69E+3 3.54E+3 1.69E+5 3.95E+3 -1.90E+3 1.26E+31-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 -2.16E+3 5.60E+31-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 -1.29E+3 6.65E+21-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 -1.83E+3 2.77E+3Cs-134 3.96E+5 7.03E+5 -1.90E+5 7.97E+4 1.33E+3 7.45E+4Cs-136 4.83E+4 1.35E+5 -5.64E+4 1.18E+4 1.43E+3 5.29E+4Cs-137 5.49E+5 6.12E+5 -1.72E+5 7.13E+4 1.33E+3 4.55E+4Cs-138 5.05E+2 7.81E+2 -4.1OE+2 6.54E+1 8.76E+2 3.98E+2Ba-139 1.48E+0 9.84E-4 -5.92E-4 5.95E+3 5.1OE+4 4.30E-2Ba-140 5.60E+4 5.60E+1 -1.34E+1 1.60E+6 3.84E+4 2.90E+3Ba-141 1.57E-1 1.08E-4 -6.50E-5 2.97E+3 4.75E+3 4.97E-3Ba-142 3.98E-2 3.30E-5 -1.90E-5 1.55E+3 6.93E+2 1.96E-3La-140 5.05E+2 2.OOE+2 -1.68E+5 8.48E+4 5.15E+1La-142 1.03E+0 3.77E-1 -8.22E+3 5.95E+4 9.04E-2Ce-141 2.77E+4 1.67E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3Ce-143 2.93E+2 1.93E+2 -5.64E+1 1.16E+5 4.97E+4 2.21E+1Ce-144 3.19E+6 1.21E+6 -5.38E+5 9.84E+6 1.48E+5 1.76E+5Pr-143 1.40E+4 5.24E+3 -1.97E+3 4.33E+5 3.72E+4 6.99E+2Pr-144 4.79E-2 1.85E-2 -6.72E-3 1.61E+3 4.28E+3 2.41E-3Nd-147 7.94E+3 8.13E+3 -3.15E+3 3.22E+5 3.12E+4 5.OOE+2W-187 1.30E+1 9.02E+0 --3.96E+4 3.56E+4 3.12E+0Np-239 3.71E+2 3.32E+1 -6.62E+1 5.95E+4 2.49E+4 1.88E+1S0S000S00000000000000000000000002.0-25 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 20130000000S00000000Table 2.8 (Page 1 of 2)R1 Vegetation Pathway Dose Factors -ADULT(mrem/yr per giCi/m3) for H-3 and C-14 (M2 x mrem/yr lgCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5P-32 1.40E+9 8.73E+7 1 -_ 1.58E+8 5.42E+7Cr-51 --2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4Mn-54 -3.11E+8 -9.27E+7 -9.54E+8 5.94E+7Mn-56 -1.61E+1 -2.04E+1 -5.13E+2 2.85E+0Fe-55 2.09E+8 1.45E+8 --8.06E+7 8.29E+7 3.37E+7Fe-59 1.27E+8 2.99E+8 --8.35E+7 9.96E+8 1.14E+8Co-57 -1.17E+7 -2.97E+8 1.95E+7Co-58 -3.09E+7 ---6.26E+8 6.92E+7Co-60 -1.67E+8 ---3.14E+9 3.69E+8Ni-63 1.04E+10 7.21E+8 ---1.50E+8 3.49E+8Ni-65 6.15E+1 7.99E+0 ---2.03E+2 3.65E+0Cu-64 -9.27E+3 -2.34E+4 -7.90E+5 4.35E+3Zn-65 3.17E+8 1.01E+9 -6.75E+8 -6.36E+8 4.56E+8Zn-69 8.75E-6 1.67E-5 -1.09E-5 -2.51E-6 1.16E-6Br-82 ---1.73E+6 1.51E+6Br-83 -- --4.63E+0 3.21 E+0Br-84 ..- -Br-85 ......Rb-86 -2.19E+8 ---4.32E+7 1.02E+8Rb-88 -.....Rb-89 --....Sr-89 9.96E+9 -.. 1.60E+9 2.86E+8Sr-90 6.05E+11

-- --1.75E+10 1.48E+11Sr-91 3.20E+5 -- --1.52E+6 1.29E+4Sr-92 4.27E+2 ---8.46E+3 1.85E+1Y-90 1.33E+4 -- --1.41 E+8 3.56E+2Y-91m 5.83E-9 ---1.71E-8Y-91 5.13E+6 -- --2.82E+9 1.37E+5Y-92 9.01E-1 --1.58E+4 2.63E-2Y-93 1.74E+2 -... 5.52E+6 4.80E+0Zr-95 1.19E+6 3.81E+5 -5.97E+5 -1.21E+9 2.58E+5Zr-97 3.33E+2 6.73E+1 -1.02E+2 -2.08E+7 3.08E+1Nb-95 1.42E+5 7.91E+4 -7.81E+4 -4.80E+8 4.25E+4Nb-97 2.90E-6 7.34E-7 -8.56E-7 -2.71 E-3 2.68E-7Mo-99 -6.25E+6 -1.41E+7 -1.45E+7 1.19E+6Tc-99m 3.06E+0 8.66E+0 -1.32E+2 4.24E+O 5.12E+3 1.1OE+2Tc-101 -------2.0-26 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.8 (Page 2 of 2)ODCM 2.0Revision 16December 5, 2013R1 Vegetation Pathway Dose Factors -ADULT(mrem/yr per I4Ci/m3) for H-3 and C-14 (m2 x mrem/yr lICi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 4.80E+6 --1.83E+7 -5.61E+8 2.07E+6Ru-105 5.39E+1 --6.96E+2 -3.30E+4 2.13E+1Ru-106 1.93E+8 --3.72E+8 -1.25E+10 2.44E+7Rh-103m-

--.Rh-106 ---I ---Ag-110m 1.06E+7 9.76E+6 -1.92E+7 -3.98E+9 5.80E+6Sb-124 1.04E+8 1.96E+6 2.52E+5 -8.08E+7 2.95E+9 4.11E+7Sb-125 1.36E+8 1.52E+6 1.39E+5 -1.05E+8 1.50E+9 3.25E+7Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -3.86E+8 1.29E+7Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -1.17E+9 4.26E+7Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 -4.54E+5 1.25E+3Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -1.28E+9 4.03E+7Te-129 6.65E-4 2.50E-4 5.1OE-4 2.79E-3 -5.02E-4 1.62E-4Te-131m 9.12E+5 4.46E+5 7.06E+5 4.52E+6 -4.43E+7 3.72E+5Te-131 .....Te-132 4.29E+6 2.77E+6 3.06E+6 2.67E+7 -1.31E+8 2.60E+61-130 3.96E+5 1.17E+6 9.90E+7 1.82E+6 -1.01E+6 4.61E+51-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -3.05E+7 6.63E+71-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 -2.89E+1 5.38E+11-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 -3.31E+6 1.12E+61-134 1.06E-4 2.88E-4 5.OOE-3 4.59E-4 -2.51E-7 1.03E-41-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 -1.21E+5 3.94E+4Cs-134 4.66E+9 1.11E+1 -3.59E+9 1.19E+9 1.94E+8 9.07E+90Cs-136 4.20E+7 1.66E+8 -9.24E+7 1.27E+7 1.89E+7 1.19E+8Cs-137 6.36E+9 8.70E+9 -2.95E+9 9.81E+8 1.68E+8 5.70E+9Cs-138 .....Ba-139 2.95E-2 2.1OE-5 -1.96E-5 1.19E-5 5.23E-2 8.64E-4Ba-140 1.29E+8 1.62E+5 -5.49E+4 9.25E+4 2.65E+8 8.43E+6Ba-141 -....Ba-142 -....La-140 1.97E+3 9.92E+2 --7.28E+7 2.62E+2La-142 1.40E-4 6.35E-5 --4.64E-1 1.58E-5Ce-141 1.96E+5 1.33E+5 -6.17E+4 -5.08E+8 1.51E+4Ce-143 1.OOE+3 7.42E+5 -3.26E+2 -2.77E+7 8.21E+1Ce-144 3.29E+7 1.38E+7 -8.16E+6 -1.11E+10 1.77E+6Pr-143 6.34E+4 2.54E+4 -1.47E+4 -2.78E+8 3.14E+3Pr-144 -------Nd-147 3.34E+4 3.86E+4 -2.25E+4 -1.85E+8 2.31 E+3W-187 3.82E+4 3.19E+4 --1.05E+7 1.12E+4Np-239 1.42E+3 1.40E+2 -4.37E+2 -2.87E+7 7.72E+100000000000000000000000000000000000000002.0-27 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 201300000000000000000Table 2.9 (Page 1 of 2)R1 Vegetation Pathway Dose Factors -TEEN(mrem/yr per gCi/m3) for H-3 and C-14 (mi x mrem/yr laCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3C-14 1.45E+6 2.91 E+5 2.91 E+5 2.91 E+5 2.91E+5 2.91E+5 2.91 E+5Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5P-32 1.61E+9 9.96E+7 ---1.35E+8 6.23E+7Cr-51 -3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4Mn-54 -4.52E+8 -1.35E+8 -9.27E+8 8.97E+7Mn-56 -1.45E+1 -1.83E+1 -9.54E+2 2.58E+0Fe-55 3.25E+8 2.31 E+8 --1.46E+8 9.98E+7 5.38E+7Fe-59 1.81E+8 4.22E+8 --1.33E+8 9.98E+8 1.63E+8Co-57 -1.79E+7 --3.34E+8 3.00E+7Co-58 -4.38E+7 --6.04E+8 1.01E+8Co-60 -2.49E+8 --3.24E+9 5.60E+8Ni-63 1.61E+10 1.13E+9 --1.81E+8 5.45E+8Ni-65 5.73E+1 7.32E+0 --3.97E+2 3.33E+0Cu-64 -8.40E+3 -2.12E+4 -6.51E+5 3.95E+3Zn-65 4.24E+8 1.47E+9 -9.41 E+8 -6.23E+8 6.86E+8Zn-69 8.19E-6 1.56E-5 -1.02E-5 -2.88E-5 1.09E-6Br-82 -1.33E+6Br-83 -... 3.01E+0Br-84 ----Br-85 -- -Rb-86 -2.73E+8 -4.05E+7 1.28E+8Rb-88 -- -Rb-89 --Sr-89 1.51E+10

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

---2.11E+10 1.85E+11Sr-91 2.99E+5 ---1.36E+6 1.19E+4Sr-92 3.97E+2 -1.01 E+4 1.69E+1Y-90 1.24E+4 --1.02E+8 3.34E+2Y-91m 5.43E-9 --2.56E-7 -Y-91 7.87E+6 --3.23E+9 2.11E+5Y-92 8.47E-1 --2.32E+4 2.45E-2Y-93 1.63E+2 --4.98E+6 4.47E+0Zr-95 1.74E+6 5.49E+5 -8.07E+5 -1.27E+9 3.78E+5Zr-97 3.09E+2 6.11E+1 -9.26E+1 -1.65E+7 2.81E+1Nb-95 1.92E+5 1.06E+5 -1.03E+5 -4.55E+8 5.86E+4Nb-97 2.69E-6 6.67E-7 -7.80E-7 -1.59E-2 2.44E-7Mo-99 -5.74E+6 -1.31E+7 -1.03E+7 1.09E+6Tc-99m 2.70E+0 7.54E+0 -1.12E+2 4.19E+0 4.95E+3 9.77E+1Tc-101 -------2.0-28 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 2013Table 2.9 (Page 2 of 2)R1 Vegetation Pathway Dose Factors -TEEN(mre /yr per gCi/m3) for H-3 and C-14 (m2 x mrem/yr gCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 6.87E+6 -2.42E+7 -5.74E+8 2.94E+6Ru-105 5.00E+1 -6.31E+2 -4.04E+4 1.94E+1Ru-106 3.09E+8 -5.97E+8 -1.48E+10 3.90E+7Rh-103m ---Rh-106 ---Ag-110m 1.52E+7 1.44E+7 -2.74E+7 4.04E+9 8.74E+6Sb-124 1.55E+8 2.85E+6 3.51E+5 -1.35E+8 3.11E+9 6.03E+7Sb-125 2.14E+8 2.34E+6 2.04E+5 -1.88E+8 1.66E+9 5.OOE+7Te-125m 1.48E+8 5.34E+7 4.14E+7 --4.37E+8 1.98E+7Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -1.37E+9 6.56E+7Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4 -4.19E+5 1.17E+3Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 -1.38E+9 5.81E+7Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E-3 -3.40E-3 1.51E-4Te-131m 8.44E+5 4.05E+5 6.09E+5 4.22E+6 -3.25E+7 3.38E+5Te-131 .....Te-132 3.90E+6 2.47E+6 2.60E+6 2.37E+7 -7.82E+7 2.32E+61-130 3.54E+5 1.02E+6 8.35E+7 1.58E+6 -7.87E+5 4.09E+51-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 -2.13E+7 5.79E+71-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 -5.91E+1 4.87E+11-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 -2.53E+6 1.02E+61-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 -3.35E-6 9.13E-51-135 3.68E+4 9.48E+4 6.1OE+6 1.50E+5 -1.05E+5 3.52E+4Cs-134 7.09E+9 1.67E+10

-5.30E+9 2.02E+9 2.08E+8 7.74E+9Cs-136 4.29E+7 1.69E+8 -9.19E+7 1.45E+7 1.36E+7 1.13E+8Cs-137 1.01E+10 1.35E+10

-4.59E+9 1.78E+9 1.92E+8 4.69E+9Cs-138 .....Ba-139 2.77E-2 1.95E-5 -1.84E-5 1.34E-5 2.47E-1 8.08E-4Ba-140 1.38E+8 1.69E+5 -5.75E+4 1.14E+5 2.13E+8 8.91E+6Ba-141 .- -.Ba-142 -....La-140 1.80E+3 8.84E+2 ---5.08E+7 2.35E+2La-142 1.28E-4 5.69E-5 ---1.73E+0 1.42E-5Ce-141 2.82E+5 1.88E+5 -8.86E+4 -5.38E+8 2.16E+4Ce-143 9.37E+2 6.82E+5 -3.06E+2 -2.05E+7 7.62E+1Ce-144 5.27E+7 2.18E+7 -1.30E+7 -1.33E+10 2.83E+6Pr-143 7.12E+4 2.84E+4 -1.65E+4 -2.34E+8 3.55E+3Pr-144 .....Nd-147 3.63E+4 3.94E+4 -2.32E+4 -1.42E+8 2.36E+3W-187 3.55E+4 2.90E+4 --7.84E+6 1.02E+4Np-239 1.38E+3 1.30E+2 -4.09E+2 -2.10E+7 7.24E+100SS00SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS2.0-29 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 201300000000000000Table 2.10 (Page 1 of 2)R, Vegetation Pathway Dose Factors -CHILD(mrem/yr per p.Ci/m3) for H-3 and C-14 (M2 x mrem/yr jiCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 4.01 E+3 4.01E+3 4.01 E+3 4.01E+3 4.01E+3 4.01 E+3C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5Na-24 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5P-32 3.37E+9 1.58E+8 9.30E+7 .1.30E+8Cr-51 --6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5Mn-54 -6.61E+8 1.85E+8 -5.55E+8 1.76E+8Mn-56 -1.90E+1 -2.29E+1 -2.75E+3 4.28E+0Fe-55 8.00E+8 4.24E+8 -2.40E+8 7.86E+7 1.31E+8Fe-59 4.01E+8 6.49E+8 -1.88E+8 6.76E+8 3.23E+8Co-57 -2.99E+7 --2.45E+8 6.04E+7Co-58 -6.47E+7 --3.77E+8 1.98E+8Co-60 -3.78E+8 --2.1OE+9 1.12E+9Ni-63 3.95E+10 2.11E+9 --1.42E+8 1.34E+9Ni-65 1.05E+2 9.89E+0 ---1.21E+3 5.77E+0Cu-64 -1.11E+4 -2.68E+4 -5.20E+5 6.69E+3Zn-65 8.12E+8 2.16E+9 -1.36E+9 -3.80E+8 1.35E+9Zn-69 1.51E-5 2.18E-5 -1.32E-5 -1.38E-3 2.02E-6Br-82 ..... 2.04E+6Br-83 -5.55E+0Br-84 -...Br-85 .- -.Rb-86 -4.52E+8 ---2.91 E+7 2.78E+8Rb-88 .- -.Rb-89 -....Sr-89 3.59E+10

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

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

-6.48E+6 1.94E+6Tc-99m 4.65E+0 9.12E+0 -1.33E+2 4.63E+0 5.19E+3 1.51E+2Tc-101 ...... -2.0 -30 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.10 (Page 2 of 2)Ri Vegetation Pathway Dose Factors -CHILD(mrem/yr per gCi/m3) for H-3 and C-14 (m2x mrem/yr gCi/sec) for othersODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.55E+7 -3.89E+7 -3.99E+8 5.94E+6Ru-105 9.17E+1 -8.06E+2 -5.98E+4 3.33E+1Ru-106 7.45E+8 -1.01E+9 -1.16E+10 9.30E+7Rh-103m ......Rh-106 ---Ag-110m 3.22E+7 2.17E+7 -4.05E+7 -2.58E+9 1.74E+7Sb-124 3.52E+8 4.57E+6 7.78E+5 -1.96E+8 2.20E+9 1.23E+8Sb-125 4.99E+8 3.85E+6 4.62E+5 -2.78E+8 1.19E+9 1.05E+8Te-125m 3.51E+8 9.50E+7 9.84E+7 --3.38E+8 4.67E+7Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -1.07E+9 1.57E+8Te-127 1.00E+4 2.70E+3 6.93E+3 2.85E+4 -3.91E+5 2.15E+3Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -1.04E+9 1.33E+8Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E-3 -7.17E-2 2.74E-4Te-131m 1.54E+6 5.33E+5 1.1OE+6 5.16E+6 -2,16E+7 5.68E+5Te-131 .......Te-132 6.98E+6 3.09E+6 4.50E+6 2.87E+7 -3.11E+7 3.73E+61-130 6.21E+5 1.26E+6 1.38E+8 1.88E+6 -5.87E+5 6.47E+51-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 -1.28E+7 8.18E+71-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 -1.99E+2 7.77E+11-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 -1.79E+6 1.68E+61-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 -2.10E-4 1.46E-41-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 -8.98E+4 5.57E+4Cs-134 1.60E+10 2.63E+10

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

-7.46E+9 2.68E+9 1.43E+8 3.38E+9Cs-138 -...Ba-139 5.11E-2 2.73E-5 -2.38E-5 1.61E-5 2.95E+0 1.48E-3Ba-140 2.77E+8 2.43E+5 -7.90E+4 1.45E+5 1.40E+8 1.62E+7Ba-141 -- --Ba-142 ----La-140 3.23E+3 1.13E+3 --3.15E+7 3.81E+2La-142 2.32E-4 7.40E-5 ---1.47E+1 2.32E-5Ce-141 6.35E+5 3.26E+5 -1.43E+5 -4.07E+8 4.84E+4Ce-143 1.73E+3 9.36E+5 -3.93E+2 -1.37E+7 1.36E+2Ce-144 1.27E+8 3.98E+7 -2.21E+7 -1.04E+10 6.78E+6Pr-143 1.48E+5 4.46E+4 -2.41 E+4 -1.60E+8 7.37E+3Pr-144 -------Nd-147 7.16E+4 5.80E+4 -3.18E+4 -_ 9.18E+7 4.49E+3W-187 6.47E+4 3.83E+4 ---5.38E+6 1.72E+4Np-239 2.55E+3 1.83E+2 -5.30E+2 -1.36E+7 1.29E+200SS0S0000S000000000S0000000000000000002.0-31 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 20130S0000000000000SS00000Table 2.11 (Page 1 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -ADULT(mrem/yr per gICi/m3) for H-3 and C-14 (mi x mrem/yr jiCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6P-32 1.71E+10 1.06E+9 -I -1.92E+9 6.60E+8Cr-51 --1.71 E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4Mn-54 -8.40E+6 -2.50E+6 -2.57E+7 1.60E+6Mn-56 -4.23E-3 -5.38E-3 -1.35E-1 7.51 E-4Fe-55 2.51E+7 1.73E+7 --9.67E+6 9.95E+6 4.04E+6Fe-59 2.98E+7 7.OOE+7 --1.95E+7 2.33E+8 2.68E+7Co-57 -1.28E+6 ---3.25E+7 2.13E+6Co-58 -4.72E+6 ---9.57E+7 1.06E+7Co-60 -1.64E+7 --3.08E+8 3.62E+7Ni-63 6.73E+9 4.66E+8 --9.73E+7 2.26E+8Ni-65 3.70E-1 4.81E-2 --1.22E+0 2.19E-2Cu-64 -2.41E+4 -6.08E+4 -2.05E+6 1.13E+4Zn-65 1.37E+9 4.36E+9 -2.92E+9 -2.75E+9 1.97E+9Zn-69 -- -Br-82 -3.72E+7 3.25E+7Br-83 -- -1.49E-1 1.03E-1Br-84 -- -Br-85 ---Rb-86 -2.59E+9 1 -5.1E+8 1.21E+9Rb-88 ----Rb-89 --Sr-89 1.45E+9 --2.33E+8 4.16E+7Sr-90 4.68E+10

---1.35E+9 1.15E+10Sr-91 3.13E+4 --1.49E+5 1.27E+3Sr-92 4.89E-1 -9.68E+O 2.11E-2Y-90 7.07E+1 --7.50E+5 1.90E+0Y-91m --Y-91 8.60E+3 --4.73E+6 2.30E+2Y-92 5.42E-5 --9.49E-1 1.58E-6Y-93 2.33E-1 --7.39E+3 6.43E-3Zr-95 9.46E+2 3.03E+2 -4.76E+2 -9.62E+5 2.05E+2Zr-97 4.26E-1 8.59E-2 -1.30E-1 -2.66E+4 3.93E-2Nb-95 8.25E+4 4.59E+4 -4.54E+4 -2.79E+8 2.47E+4Nb-97 -- --5.47E-9 -Mo-99 -2.52E+7 -5.72E+7 -5.85E+7 4.80E+6Tc-99m 3.25E+O 9.19E+O -1.40E+2 4.50E+0 5.44E+3 1.17E+2Tc-101 ----- -2.0-32 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.11 (Page 2 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -ADULT(mrem/yr per pCi/m3) for H-3 and C-14 (M2x mrem/yr gCi/sec) for othersODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.02E+3 -3.89E+3 -1.19E+5 4.39E+2Ru-105 8.57E-4 -1.11E-2 -5.24E-1 3.38E-4Ru-106 2.04E+4 -3.94E+4 -1.32E+6 2.58E+3Rh-103m --.Rh-106 -...Ag-110m 5.83E+7 5.39E+7 1.06E+8 2.20E+10 3.20E+7Sb-124 2.57E+7 4.86E+5 6.24E+4 2.OOE+7 7.31E+8 1.02E+7Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -6.50E+7 2.18E+6Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -1.54E+8 5.58E+6Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 -5.30E+4 1.45E+2Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 -3.04E+8 9.57E+6Te-129 -....Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79E+6 -1.75E+7 1.47E+5Te-131 --- -Te-132 2.39E+6 1.55E+6 1.71E+6 1.49E+7 -7.32E+7 1.45E+61-130 4.26E+5 1.26E+6 1.07E+8 1.96E+6 -1.08E+6 4.96E+51-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 -1.12E+8 2.43E+81-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 -8.22E-2 1.53E-11-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 -6.20E+6 2.1OE+61-134 ---1-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 4.1OE+4 1.34E+4Cs-134 5.65E+9 1.34E+10

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

-3.43E+9 1.14E+9 1.95E+8 6.61E+9Cs-138 ---Ba-139 4.70E-8 -8.34E-8 1.38E-9Ba-140 2.69E+7 3.38E+4 1.15E+4 1.93E+4 5.54E+7 1.76E+6Ba-141 -- ---Ba-142 -...La-140 4.49E+0 2.26E+0 --1.66E+5 5.97E-1La-142 --3.03E-8 -Ce-141 4.84E+3 3.27E+3 1.52E+3 -1.25E+7 3.71E+2Ce-143 4.19E+1 3.09E+4 1.36E+1 -1.16E+6 3.42E+0Ce-144 3.58E+5 1.50E+5 8.87E+4 -1.21E+8 1.92E+4Pr-143 1.59E+2 6.37E+1 3.68E+1 -6.96E+5 7.88E+0Pr-144 ---Nd-147 9.42E+1 1.09E+2 6.37E+1 -5.23E+5 6.52E+0W-187 6.56E+3 5.48E+3 --1.80E+6 1.92E+3Np-239 3.66E+0 3.60E-1 -1.12E+0

-7.39E+4 1.98E-10000SSS0SSSSSSSSSS0SS0SSSSSSSSSSSSSSSS2.0-33 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 20130000S0000000S0000S0Table 2.12 (Page 1 of 2)R, Grass-Cow-Milk Pathway Dose Factors -TEEN(mrem/yr per igCi/m3) for H-3 and C-14 (m2 x mrem/yr jiCi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9Cr-51 -2.78E+4 1.1OE+4 7.13E+4 8.40E+6 5.OOE+4Mn-54 -1.40E+7 -4.17E+6 -2.87E+7 2.78E+6Mn-56 -7.51E-3 -9.50E-3 -4.94E-1 1.33E-3Fe-55 4.45E+7 3.16E+7 -2.OOE+7 1.37E+7 7.36E+6Fe-59 5.20E+7 1.21 E+8 3.82E+7 2.87E+8 4.68E+7Co-57 -2.25E+6 --4.19E+7 3.76E+6Co-58 -7.95E+6 --1.10E+8 1.83E+7Co-60 -2.78E+7 --3.62E+8 6.26E+7Ni-63 1.18E+10 8.35E+8 --1.33E+8 4.01E+8Ni-65 6.78E-1 8.66E-2 --4.70E+0 3.94E-2Cu-64 -4.29E+4 -1.09E+5 -3.33E+6 2.02E+4Zn-65 2.11E+9 7.31E+9 -4.68E+9 -3.1OE+9 3.41E+9Zn-69 -----Br-82 -5.64E+7Br-83 -.... , 1.91 E-1Br-84 .--Br-85 -...Rb-86 -4.73E+9 ---7.OOE+8 2.22E+9Rb-88 -....Rb-89 -.....Sr-89 2.67E+9 -- --3.18E+8 7.66E+7Sr-90 6.61E+10

-- --1.86E+9 1.63E+10Sr-91 5.75E+4 ---2.61 E+5 2.29E+3Sr-92 8.95E-1 ---2.28E+1 3.81E-2Y-90 1.30E+2 ---1.07E+6 3.50E+OY-91m ....Y-91 1.58E+4 ---6.48E+6 4.24E+2Y-92 1.OOE-4 ---2.75E+0 2.90E-6Y-93 4.30E-1 ---1.31E+4 1.18E-2Zr-95 1.65E+3 5.22E+2 -7.67E+2 -1.20E+6 3.59E+2Zr-97 7.75E-1 1.53E-1 -2.32E-1 -4.15E+4 7.06E-2Nb-95 1.41E+5 7.80E+4 -7.57E+4 -3.34E+8 4.30E+4Nb-97 .- -6.34E-8 -Mo-99 -4.56E+7 -1.04E+8 -8.16E+7 8.69E+6Tc-99m 5.64E+0 1.57E+1 -2.34E+2 8.73E+0 1.03E+4 2.04E+2Tc-101 -------2.0-34 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.12 (Page 2 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -TEEN(mrem/yr per pCi/m3) for H-3 and C-14 (M2x mrem/yr iiCi/sec) for othersODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 1.81E+3 -6.40E+3 -1.52E+5 7.75E+2Ru-105 1.57E-3 -1.97E-2 -1.26E+O 6.08E-4Ru-106 3.75E+4 -7.23E+4 -1.80E+6 4.73E+3Rh-103m ....Rh-106 ......Ag-110m 9.63E+7 9.11E+7 -1.74E+8 -2.56E+10 5.54E+7Sb-124 4.59E+7 8.46E+5 1.04E+5 -4.01E+7 9.25E+8 1.79E+7Sb-125 3.65E+7 3.99E+5 3.49E+4 -3.21E+7 2.84E+8 8.54E+6Te-125m 3.OOE+7 1.08E+7 8.39E+6 --8.86E+7 4.02E+6Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -2.1OE+8 1.OOE+7Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 -9.61E+4 2.68E+2Te-129m 1.11E+8 4.1OE+7 3.57E+7 4.62E+8 -4.15E+8 1.75E+7Te-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+5Te-131 .....Te-132 4.28E+6 2.71E+6 2.86E+6 2.60E+7 -8.58E+7 2.55E+61-130 7.49E+5 2.17E+6 1.77E+8 3.34E+6 -1.67E+6 8.66E+51-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 -1.49E+8 4.04E+81-132 2.90E-1 7.59E-1 2.56E+1 1.20E+O -3.31E-1 2.72E-11-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 -9.30E+6 3.75E+61-134 .....1-135 2.47E+4 6.35E+4 4.08E+6 1.OOE+5 7.03E+4 2.35E+4Cs-134 9.81E+9 2.31E+10

-7.34E+9 2.80E+9 2.87E+8 1.07E+10Cs-136 4.45E+8 1.75E+9 -9.53E+8 1.50E+8 1.41E+8 1.18E+9Cs-137 1.34E+10 1.78E+10

-6.06E+9 2.35E+9 2.53E+8 6.20E+9Cs-138 ---Ba-1 39 8.69E-8_

-7.75E-7 2.53E-9Ba-140 4.85E+7 5.95E+4 -2.02E+4 4.OOE+4 7.49E+7 3.13E+6Ba-141 -- --Ba-142 -...La-140 8.06E+0 3.96E+0 -2.27E+5 1.05E+OLa-142 --2.23E-7 -Ce-141 8.87E+3 5.92E+3 -2.79E+3 -1.69E+7 6.81E+2Ce-143 7.69E+1 5.60E+4 -2.51E+1 -1.68E+6 6.25E+0Ce-144 6.58E+5 2.72E+5 -1.63E+5 -1.66E+8 3.54E+4Pr-143 2.92E+2 1.17E+2 -6.77E+1 -9.61E+5 1.45E+1Pr-144 -----Nd-147 1.81E+2 1.97E+2 -_1.16E+2

-7.11E+5 1.18E+1W-187 1.20E+4 9.78E+3 --2.65E+6 3.43E+3Np-239 6.99E+0 6.59E-1 -2.07E+0 -1.06E+5 3.66E-100000000000000000000000000000000000000000002.0-35 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 201300S0S0000,0'0000S00S0Table 2.13 (Page 1 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -CHILD(mrem/yr per igCi/m3) for H-3 and C-14 (M2 x mrem/yr gICi/sec) for othersNuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6P-32 7.77E+10 3.64E+9 -2.15E+9 3.OOE+9Cr-51 -5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5Mn-54 -2.09E+7 -5.87E+6 -1.76E+7 5.58E+6Mn-56 -1.31E-2 -1.58E-2 -1.90E+0 2.95E-3Fe-55 1.12E+8 5.93E+7 -3.35E+7 1.1OE+7 1.84E+7Fe-59 1.20E+8 1.95E+8 -5.65E+7 2.03E+8 9.71E+7Co-57 -3.84E+6 -3.14E+7 7.77E+6Co-58 -1.21 E+7 -7.08E+7 3.72E+7Co-60 -4.32E+7 2.39E+8 1.27E+8Ni-63 2.96E+10 1.59E+9 1.07E+8 1.01E+9Ni-65 1.66E+0 1.56E-1 1.91E+1 9.11E-2Cu-64 -7.55E+4 1.82E+5 -3.54E+6 4.56E+4Zn-65 4.13E+9 1.10E+10 16.94E+9

-1.93E+9 6.85E+9Zn-69 -- -2.14E-9 -Br-82 -- 1.15E+8Br-83 -4.69E-1Br-84 -Br-85 -- --Rb-86 -8.77E+9 5.64E+8 5.39E+9Rb-88 -- --Rb-89 ---Sr-89 6.62E+9 -2.56E+8 1.89E+8Sr-90 1.12E+11

-1.51E+9 2.83E+10Sr-91 1.41E+5 -3.12E+5 5.33E+3Sr-92 2.19E+0 -4.14E+1 8.76E-2Y-90 3.22E+2 -9.15E+5 8.61E+0Y-91m ----Y-91 3.91 E+4 --5.21 E+6 1.04E+3Y-92 2.46E-4 ---7.1OE+0 7.03E-6Y-93 1.06E+0 ---1.57E+4 2.90E-2Zr-95 3.84E+3 8.45E+2 -1.21E+3 -8.81E+5 7.52E+2Zr-97 1.89E+0 2.72E-1 -3.91E-1 -4.13E+4 1.61E-1Nb-95 3.18E+5 1.24E+5 -1.16E+5 -2.29E+8 8.84E+4Nb-97 -----1.45E-6 -Mo-99 -8.29E+7 -1.77E+8 -6.86E+7 2.05E+7Tc-99m 1.29E+1 2.54E+1 -3.68E+2 1.29E+1 1.44E+4 4.20E+2Tc-101 .... --2.0-36 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.13 (Page 2 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -CHILD(mrem/yr per giCi/M3) for H-3 and C-14 (m2x mrem/yr giCi/sec) for othersODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid .Kidney Fg GI-LLI T.BodyRu-103 4.29E+3 -1.08E+4 -1.11E+5 1.65E+3Ru-105 3.82E-3 -3.36E-2 -2.49E+O 1.39E-3Ru-106 9.24E+4 -1.25E+5 -1.44E+6 1.15E+4Rh-103m ....Rh-106 ....Ag-110m 2.09E+8 1.41E+8 -2.63E+8 -1.68E+10 1.13E+8Sb-124 1.09E+8 1.41E+8 2.40E+5 -6.03E+7 6.79E+8 3.81E+7Sb-125 8.70E+7 1.41E+6 8.06E+4 -4.85E+7 2.08E+8 1.82E+7Te-125m 7.38E+7 2.OOE+7 2.07E+7 --7.12E+7 9.84E+6Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -1.68E+8 2.47E+7Te-127 3.06E+3 8.25E+2 2.12E+3 8.71E+3 -1.20E+5 6.56E+2Te-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+8 -3.32E+8 4.23E+7Te-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+5Te-131 ....Te-132 1.02E+7 4.52E+6 6.58E+6 4.20E+7 -4.55E+7 5.46E+61-130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 -1.66E+6 1.82E+61-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 -1.17E+8 7.46E+81-132 6.86E-1 1.26E+0 5.85E+1 1.93E+O -1.48E+0 5.80E-11-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 -8.77E+6 8.23E+61-134 .- 135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 -8.OOE+4 4.97E+4Cs-134 2.26E+10 3.71E+10

-1.15E+10 4.13E+9 2.OOE+8 7.83E+9Cs-136 1.OOE+9 2.76E+9 -1.47E+9 2.19E+8 9.70E+7 1.79E+9Cs-137 3.22E+10 3.09E+10

-1.01E+10 3.62E+9 1.93E+8 4.55E+9Cs-138 .....Ba-139 2.14E-7 .... 1.23E-5 6.19E-9Ba-140 1.17E+8 1.03E+5 -3.34E+4 6.12E+4 5.94E+7 6.84E+6Ba-141 -....Ba-142 -....La-140 1.93E+1 6.74E+0 ---1.88E+5 2.27E+0La-142 .- 2.51E-6 -Ce-141 2.19E+4 1.09E+4 -4.78E+3 -1.36E+7 1.62E+3Ce-143 1.89E+2 1.02E+5 -4.29E+1 -1.50E+6 1.48E+1Ce-144 1.62E+6 5.09E+5 -2.82E+5 -1.33E+8 8.66E+4Pr-143 7.23E+2 2.17E+2 -1.17E+2 -7.80E+5 3.59E+1Pr-144 .....Nd-147 4.45E+2 3.60E+2 -1.98E+2 -5.71 E+5 2.79E+1W-187 2.91E+4 1.72E+4 ---2.42E+6 7.73E+3Np-239 1.72E+1 1.23E+0 -3.57E+O -9.14E+4 8.68E-100000000000000000000000000000000000000S2.0-37 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM 2.0Revision 16December 5, 2013Table 2.14 (Page 1 of 2)R, Grass-Cow-Milk Pathway Dose Factors -INFANT(mrem/yr per gCi/m3) for H-3 and C-14 (mi x mrem/yr laCi/sec) for others00000000000000000000000000000000000Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyH-3 -2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5Na-24 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61 E+7 1.61 E+7P-32 1.60E+11 9.42E+9 ---2.17E+9 6.21E+9Cr-51 -1.05E+5 2.30E+4 2.05E+5 4.71 E+6 1.61E+5Mn-54 -3.89E+7 8.63E+6 -1.43E+7 8.83E+6Mn-56 -3.21 E-2 2.76E-2 -2.91 E+0 5.53E-3Fe-55 1.35E+8 8.72E+7 -4.27E+7 1.11E+7 2.33E+7Fe-59 2.25E+8 3.93E+8 -1.16E+8 1.88E+8 1.55E+8Co-57 -8.95E+6 --3.05E+7 1.46E+7Co-58 -2.43E+7 --6.05E+7 6.06E+7Co-60 -8.81E+7 --2.1OE+8 2.08E+8Ni-63 3.49E+10 2.16E+9 --1.07E+8 1.21E+9Ni-65 3.51E+0 3.97E-1 --3.02E+1 1.81E-1Cu-64 -1.88E+5 -3.17E+5 -3.85E+6 8.69E+4Zn-65 5.55E+9 1.90E+10

-9.23E+9 -1.61E+10 8.78E+9Zn-69 ---7.36E-9 -Br-82 --. 1.94E+8Br-83 --9.95E-1Br-84 --.Br-85 -...Rb-86 -2.22E+10

--5.69E+8 1.10E+10Rb-88 -....Rb-89 --...Sr-89 1.26E+10

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

-- --1.52E+9 3.10E+10Sr-91 2.94E+5 -- --3.48E+5 1.06E+4Sr-92 4.65E+0 ---5.01E+1 1.73E-1Y-90 6.80E+2 -- --9.39E+5 1.82E+1Y-91m -.....Y-91 7.33E+4 -- --5.26E+6 1.95E+3Y-92 5.22E-4 -- --9.97E+0 1.47E-5Y-93 2.25E+0 ---1.78E+4 6;13E-2Zr-95 6.83E+3 1.66E+3 -1.79E+3 -8.28E+5 1.18E+3Zr-97 3.99E+0 6.85E-1 -6.91E-1 -4.37E+4 3.13E-1Nb-95 5.93E+5 2.44E+5 -1.75E+5 -2.06E+8 1.41E+5Nb-97 .- -3.70E-6 -Mo-99 -2.12E+8 -_3.17E+8

-6.98E+7 4.13E+7Tc-99m 2.69E+1 5.55E+1 -_ 5.97E+2 2.90E+1 1.61E+4 7.15E+2Tc-101 -----2.0-38 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.14 (Page 2 of 2)R1 Grass-Cow-Milk Pathway Dose Factors -INFANT(mrem/yr per jiCi/m3) for H-3 and C-14 (M2x mrem/yr gCi/sec) for othersODCM 2.0Revision 16December 5, 2013Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.BodyRu-103 8.69E+3 -1.81E+4 -1.06E+5 2.91E+3Ru-1 05 8.06E-3 -5.92E-2 -3.21 E+0 2.71 E-3Ru-106 1.90E+5 -2.25E+5 -1.44E+6 2.38E+4Rh-1 03m -Rh-106 ---Ag-11Om 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8Sb-124 2.09E+8 3.08E+6 5.56E+5 -1.31E+8 6.46E+8 6.49E+7Sb-125 1.49E+8 1.45E+6 1.87E+5 -9.38E+7 1.99E+8 3.07E+7Te-125m 1.51E+8 5.04E+7 5.07E+7 --7.18E+7 2.04E+7Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -1.70E+8 5.1OE+7Te-127 6.50E+3 2.18E+3 5.29E+3 1.59E+4 -1.36E+5 1.40E+3Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -3.34E+8 8.62E+7Te-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+6Te-131 ------Te-132 2.1OE+7 1.04E+7 1.54E+7 6.51E+7 -3.85E+7 9.72E+61-130 3.60E+6 7.92E+6 8.88E+8 8.70E+6 -1.70E+6 3.18E+61-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -1.15E+8 1.41E+91-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 -2.34E+0 1.03E+01-133 3.72E+7 5.41 E+7 9.84E+9 6.36E+7 -9.16E+6 1.58E+71-134 --1.01E-9 ----1-135 1.21E+5 2.41 E+5 2.16E+7 2.69E+5 -8.74E+4 8.80E+4Cs-134 3.65E+10 6.80E+10

-1.75E+10 7.18E+9 1.85E+8 6.87E+9Cs-136 1.96E+9 5.77E+9 -2.30E+9 4.70E+8 8.76E+7 2.15E+9Cs-137 5.15E+10 6.02E+10

-1.62E+10 6.55E+9 1.88E+8 4.27E+9Cs-138 -------Ba-139 4.55E-7 --2.88E-5 1.32E-8Ba-140 2.41E+8 2.41E+5 5.73E+4 1.48E+5 5.92E+7 1.24E+7Ba-141 --.Ba-142 -- --La-140 4.03E+1 1.59E+1 --1.87E+5 4.09E+0La-142 ---5.21 E-6 -Ce-141 4.33E+4 2.64E+4 -8.15E+3 -1.37E+7 3.11E+3Ce-143 4.OOE+2 2.65E+5 7.72E+1 -1.55E+6 3.02E+1Ce-144 2.33E+6 9.52E+5 3.85E+5 -1.33E+8 1.30E+5Pr-143 1.49E+3 5.59E+2 2.08E+2 -7.89E+5 7.41E+1Pr-144 -----Nd-147 8.82E+2.

9.06E+2 3.49E+2 -5.74E+5 5.55E+1W-187 6.12E+4 4.26E+4 -2.50E+6 1.47E+4Np-239 3.64E+1 3.25E+0 _ 6.49E+0 -9.40E+4 1.84E+00000000000000000000000S00000S00000000002.0-39 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.15 (Page 1 of 2)R1 Ground Plane Pathway Dose Factors(M2x mrem/yr per IiCi/sec)

ODCM 2.0Revision 16December 5, 2013S00000000000000000000000000000000!000Nuclide Any OrganH-3C-14 _Na-24 1.21 E+7P-32 _Cr-51 4.68E+6Mn-54 1.34E+9Mn-56 9.05E+5Fe-55Fe-59 2.75E+8Co-57 4.37E+8Co-58 3.82E+8Co-60 2.16E+10Ni-63Ni-65 2.97E+5Cu-64 6.09E+5Zn-65 7.45E+8Zn-69Br-82 4.57E+7Br-83 4.89E+3Br-84 2.03E+5Br-85Rb-86 8.98E+6Rb-88 3.29E+4Rb-89 1.21E+5Sr-89 2.16E+4Sr-90 _-Sr-91 2.19E+6Sr-92 7.77E+5Y-90 4.48E+3Y-91m 1.01E+5Y-91 1.08E+6Y-92 1.80E+5Y-93 1.85E+5Zr-95 2.48E+8Zr-97 2.94E+6Nb-95 1.36E+8Nb-97 2.28E+6Mo-99 4.05E+6Tc-99m 1.83E+5Tc-101 2.04E+4Ru-103 1.09E+82.0-40 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALTable 2.15 (Page 2 of 2)Ri Ground Plane Pathway Dose Factors(M2x mrem/yr per gCi/sec)ODCM 2.0Revision 16December 5, 2013Nuclide Any OrganRu-1 05 6.36E+5Ru-106 4.21E+8Rh-103mRh-106Ag-110rn 3.47E+9Sb-1 24 2.87E+9Sb-125 6.49E+9Te-125m 1.55E+6Te-127m 9.17E+4Te-127 3.OOE+3Te-129m 2.OOE+7Te-129 2.60E+4Te-131m 8.03E+6Te-131 2.93E+4Te-132 4.22E+61-130 5.53E+61-131 1.72E+71-132 1.24E+61-133 2.47E+61-134 4.49E+51-135 2.56E+6Cs-134 6.75E+9Cs-136 1.49E+8Cs-137 1.04E+10Cs-1 38 3.59E+5Ba-1 39 1.06E+5Ba-140 2.05E+7Ba-141 4.18E+4Ba-142 4.49E+4La-140 1.91 E+7La-142 7.36E+5Ce-141 1.36E+7Ce-143 2.32E+6Ce-144 6.95E+7Pr-143Pr-144 1.83E+3Nd-147 8.40E+6W-187 2.36E+6Np-239 1.71 E+6000000000000000000000000000000000000000000002.0-41 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-ARevision 16December 5, 2013S0000000000000000000000000000000000APPENDIX AContent deleted.

No longer being used.A-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 16December 5, 201300000APPENDIX BTECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -GASEOUS RADIOACTIVE EFFLUENTS B-1000000000000000000000000000000000000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 16December 5, 2013APPENDIX BTechnical Basis for Effective Dose Factors -Gaseous Radioactive Effluents 000000000000000S000000000OverviewThe evaluation of doses due to releases of radioactive material to the atmosphere can besimplified by the use of effective dose transfer factors instead of using dose factors, which areradionuclide 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 dosein the environment (i.e., instead of having to perform individual radionuclide dose analyses onlya single multiplication (Kerr, Meff or Neff) times the total quantity of radioactive material releasedwould be needed).

This approach provides a reasonable estimate of the actual dose whileeliminating the need for a detailed calculational technique.

Determination of Effective Dose FactorsEffective dose transfer factors are calculated by the following equations:

Keff = E (K X fi)(B1(13.1)where:KeffKithe effective total body dose factor due to gamma emissions from all noble gasesreleased= the total body dose factor due to gamma emissions from each noble gasradionuclide "i" releasedthe fractional abundance of noble gas radionuclide "i" relative to the total noblegas activityfi(L+1.lM)eff

= E[(Li+l.1M-)Xfi]

(B.2)where:(L + 1.1 M)eff(Li + 1.1 Mi)= the effective skin dose factor due to beta and gamma emissions from all noblegases released= the skin dose factor due to beta and gamma emissions from each noble gasradionuclide "i" releasedMeff = E(Mixfi)(B.3)B-2 KEWAUNEE POWER STATION ODCM App-B 0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013where:Meff = the effective air dose factor due to gamma emissions from all noble gases releasedSMi the air dose factor due to gamma emissions from each noble gas radionuclide "i"releasedNeff = -(Nixfi)

(B.4)where:0Neff = the effective air dose factor due to beta emissions from all noble gases releasedNi the air dose factor due to beta emissions from each noble gas radionuclide "i"releasedNormally, it would be expected that past radioactive effluent data would be used for thedetermination of the effective dose factors.

However, the noble gas releases from Kewauneehave been maintained to such negligible quantities that the inherent variability in the data makesany meaningful evaluations difficult.

For the years of 2000, 2001 and 2002, the total noble gasreleases have been limited to 2.54E-04 Ci for 2000, 1.37E-01 Ci for 2001, and 1.91E-02 Ci for2002. Therefore, in order to provide a reasonable basis for the derivation of the effective noblegas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.1, "SourceTerm Specifications,"

has been used as representing a typical distribution.

The effective dosefactors as derived are presented in Table B-1.0Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dosecalculational process when the effective dose transfer factor is used. This conservatism providesadditional assurance that the evaluation of doses by the use of a single effective factor will notsignificantly underestimate any actual doses in the environment.

0For evaluating compliance with the dose limits of ODCM Normal Condition 13.2.2, thefollowing simplified equations may be used:3.17E-08Dy =-.7E-0 x X/Q x f Xo Z Qi (B.5)0.50 (Dp= 3.7E -08XX/QxNeff xzQi (B.6)0.50000B-3 0000 0000S0000S00KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 16December 5, 2013where:Dy= air dose due to gamma emissions for the cumulative release of all noble gases(mrad)DIp = air dose due to beta emissions for the cumulative release of all noble gases (mrad)7IQMeffNeffI Qi= atmospheric dispersion to the controlling SITE BOUNDARY (sec/m3)= 5.3E+02, effective gamma-air dose factor (mrad/yr per gCi/m3)= 1.1E+03, effective beta-air dose factor (mrad/yr per g.tCi/m3)= cumulative release for all noble gas radionuclides (tCi)3.17E-08

= conversion factor (yr/sec)0.50= conservatism factor to account for the variability in the effluent dataCombining the constants, the dose calculational equations simplify to:D7= 3.5E-05xX/QxlQa (B.7)0S0000000S000000000and,= 7.OE-05XX/QxEQi (B.8)The effective dose factors are used on a very limited basis for the purpose of facilitating thetimely assessment of radioactive effluent

releases, particularly during periods of computermalfunction where a detailed dose assessment may be unavailable.

Dose assessments using thedetailed, radionuclide dependent calculation are performed at least annually for preparation ofthe Radioactive Effluent Reports.

Comparisons can be performed at this time to assure that theuse of the effective dose factors does not substantially underestimate actual doses.B-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-BRevision 16December 5, 2013Table B-1Effective Dose Factors -Noble GasesTotal Body Effective Skin Effective Dose Factor Dose FactorKeff (L+I.1 M)efRadionuclide fi (mrem/yr per gCi/mr3) (mrem/yr per gCi/mr3)Noble Gases -Total Body and SkinKr-85 0.01 -- 1.4E+01Kr-88 0.01 1.5E+02 1.9E+02Xe-133m 0.01 2.5E+00 1.4E+01Xe-133 0.9 3.OE+02 6.6E+02Xe-135 0.02 3.6E+01 7.9E+01TOTAL 4.8E+02 9.6E+02Noble Gases -AirGamma Air Effective Beta Air Effective Dose Factor Dose FactorMeff NffRadionuclide f& (mrad/yr per pCi/mr3) (mrad/yr per gCi/m3)Kr-85 0.01 -- 2.OE+01Kr-88 0.01 1.5E+02 2.9E+01Xe-133m 0.01 3.3E+00 1.5E+01Xe- 133 0.95 3.4E+02 1.0E+03Xe-135 0.02 3.8E+01 4.9E+01TOTAL 5.3E+02 1.1E+03SS00000000000000000000000000000000S0000S000B-5 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-CRevision 16December 5, 20130000000000000000000000000000000000APPENDIX CEVALUATION OF CONSERVATIVE, DEFAULT EFFECTIVE EC VALUEFOR LIQUID EFFLUENTS C-1 00KEWAUNEE POWER STATION ODCM App-COFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013SAppendix C0Evaluation of Conservative, Default Effective EC Valuefor Liquid Effluents In accordance with the requirements of ODCM Normal Condition 13.3.1 the radioactive liquideffluent monitors shall be FUNCTIONAL with alarm setpoints established to ensure that theconcentration of radioactive material at the discharge point does not exceed 10 times the value of10 CFR 20, Appendix B, Table 2, Column 2 for all radionuclides other than noble gases and avalue of 2El0 pCi/ml for noble gases. The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding EC values.0In order to limit the need for routinely having to reestablish the alarm setpoints as a function ofchanging radionuclide distributions, a default alarm setpoint can be established.

This defaultsetpoint can be conservatively based on an evaluation of the radionuclide distribution of theliquid effluents from Kewaunee and the ECe value for this distribution.

0The effective EC value for a radionuclide distribution can be calculated by the equation:

EC. C= (C.1)-CiECiwhere:0ECe = an effective EC value for a mixture of radionuclide (pgCi/ml)

SCi = concentration of radionuclide "i" in the mixtureECi the 10 CFR 20, Appendix B, Table 2, Column 2 EC value for radionuclide "i"(ptCi/ml)

Based on the above equation and the radionuclide distribution in the effluents for past years fromKewaunee, an ECe value can be determined.

Effluent release data from 2000-2002 was used togenerate the results presented in Table C-1. The most limiting effective EC (for gamma emittingradionuclides) was for the calendar year 2001, with a calculated value of 5.98E-06 ItCi/ml.

Forconservatism in establishing the alarm setpoints, a default effective EC value of 1.OE-06 gCi/mlwas selected.

The overall conservatism of this value is reaffirmed for future releases considering that 1.OE-06 IaCi/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 ECCSC-25SSS 00* KEWAUNEE POWER STATION ODCM App-COFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013S* 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 tritiumaccounts for nearly all of the activity, it is not a significant contributor when determining thealarm setpoint for release rate evaluations.

Examining releases over the years 2000-2002, theaverage, 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 changesignificantly over time, since the concentration of H-3 in effluents can be expected to remainfairly consistent in effluent releases regardless of fuel conditions, activation product releases, and0waste 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 assume0that the abundances of these non-gammas will remain the same relative to other fission and/oractivation products under varying conditions.

Therefore, under conditions of elevated effluentradionuclide levels, the gamma-emitting radionuclides can be expected to be the maincontributors 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 elevated effluent levels, the main contributor to the limiting*conditions of the liquid effluent concentration would be the gamma-emitting radionuclides.

Thefactor of six (6) conservatism in the effective EC determination (discussed above) providesadequate consideration for the contribution from non-gamma emitting radionuclides, andprovides 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 jtCi/ml for*increased monitoring is consistent with the ODCM methodology if an installed radiation monitorwas available.

00000000000*C-3000 KEWAUNEE POWER STATION ODCM App-COFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Table C-1Calculation.

of Effective EC (ECe)2000 2001 2002Nuclide EC (IiCi/ml)

TRelease (Ci) Ci/ECi Frac. Release (CQ) Ci/EC, Frac. Release (Ci) C,/ECi Frac.Na-24 5.OOE-05 1.03E-03 2.06E+01 4.89E-03 2.18E-04 4.35E+00 1.27E-03 0.OOE+00 0.OOE+00 0.OOE+00Cr-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+00Mn-54 3.00E-05 1.49E-04 4.97E+00 I. 18E-03 3.30E-04 1.1OE+01 3.22E-03 6.41 E-05 2.14E+00 9.83E-04Fe-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-01Co-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+00Co-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-01Fe-59 1.00E-05 2.77E-04 2.77E+01 6.57E-03 2.44E-04 2.44E+0I 7.14E-03 1.65E-04 1.65E+01 7.61E-03Co-60 3.OOE-06 4.71E-03 1.57E+03 3.73E-01 4.31E-03 1.44E+03 4.21E-01 2.07E-03 6.89E+02 3.17E-01Br-82 4.OOE-05 4.94E-04 1.23E+01 2.93E-03 1.44E-04 3.59E+00 1.05E-03 0.OOE+00 0.00E+00 0.OOE+00Sr-89 8.00E-06 3.42E-04 4.27E+01 1.01E-02 2.59E-04 3.24E+01 9.48E-03 5.98E-04 7.48E+01 3.44E-02Sr-90 5.OOE-07 2.25E-04 4.50E+02 1.07E-01 2.50E-04 5.OOE+02 1.46E-0I 9.76E-05 1.95E+02 8.98E-02Zr-95 2.OOE-05 1.16E-04 5.79E+00 1.38E-03 7.18E-05 3.59E+00 1.05E-03 5.24E-05 2.62E+00 1.20E-03Nb-95 3.OOE-05 3.41E-04

1. 14E+O I 2.70E-03 2.39E-04 7.95E+00 2.33E-03 2.45E-04 8.17E+00 3.76E-03Ag-I 1 0m 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-01Sn-113 3.00E-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-03Sb-124 7.OOE-06 5.61E-04 8.01E+01 I 1.90E-02 1.81E-04 2.59E+01 7.59E-03 4.34E-05 6.20E+00 2.85E-03Sb-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-021-132 1.00E-04 0.OOE+00 0.OOE+00 0.OOE+00 7.75E-08 7.75E-04 2.27E-07 0.OOE+00 0.OOE+00 0.OOE+001-133 7.OOE-06 6.16E-04 8.80E+01 2.09E-02 6.32E-04 9.03E+01 2.65E-02 0.OOE+00 0.OOE+00 0.OOE+001-135 3.OOE-05 O.OOE+00 O.OOE+00 0.OOE+00 4.6 1E-05 1.54E+00 4.50E-04 0.OOE+00 0.OOE+00 0.OOE+00Cs-137 1.00E-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-03Total 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+00Non-Gamma Fraction

: 0.23 _ _ _ _ _ 0.30 _ _ _ _, 0.29Gamma Fraction

_ _ _,_ 0.77 ,: _,_ _,_ 0.70 ,: ,: ,: 0.71EC, (pCi/ml, total) 1.77E-05 1.86E-05 2.33E-05ECe (pCi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06C-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 201300000000000000.000S00000000000000,00APPENDIX DOn-site Disposal of Low-Level Radioactively Contaminated Waste StreamsD-1 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013Appendix D consists of hard copies of the following reference documents:

DESCRIPTION

[ DATE DOCKET NUMBEROperating License DPR-43Kewaunee Nuclear Power Plant October 17, 1991 NRC-9 1-148Disposal of Low Level Radioactive 50-305MaterialProposed Disposal of Low LevelRadioactive Waste Sludge Onsite at the June 17, 1992 K92-119Kewaunee Nuclear Power Plant 50-305(TAC No. M75047)Safety Evaluation For An Amendment ToAn Approved 10 CFR 20.302 Application September 14, 1994 K-94-195For The Kewaunee Nuclear Plant 50-305(TAC No. M89719)Alternate Disposal Of Contaminated Sewage Treatment Plant Sludge In November 13, 1995 K-95-172Accordance With 10 CFR 20.2002 50-305(TAC No. M93844)Onsite Disposal Of Contaminated Sludge K-97-64Pursuant To 10 CFR 20.2002 April 9, 1997 50-305(TAC No. M9741 1) 1 1 _1_000000000000000000000000000000000000000Adapted from ND-2 0000KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013WPSC ( 414) 433.1598TELECOPIER (414) 433-554400WISCONSIN PUDUIC SERVICE CORPOSUATIONd 61- %.artn AcarýS 0 PO Sax 19002 a Green Bav. W1 5d3C7-GC02 INRC 91-/14EASYLINK 628S '99300000000000000S00bce -K M Badow, MGEN E Boys, WPLLarry Nielsen, ANFCD R Berg KNPD A Bollom 06R E Drshtim KNPK H Evers 02M L Marchi KNPD L Masank KNPI N Morrison D2I R Mueller D2D S Nf,,hqplk KNPL A Nuitls D2 (NSRAc)R P Pulec D2I S Richmond D2D J Ristau D2D I Roon KNP.-7 T- /,6JA J Ruege D2C A Schrock KNIPC S Smoker KNPC R Steinhardt D2I I Wallsace KNPK H Weinhauer KNPS F Womiak D2QA Vault KNPOctober 17, 1991U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, D.C. 20555Gentlemen:

Docket 50-305Operating License DPR-43Kewaunee Nuclear Power PlantDiwsosal of Low Level Radioactive Material

References:

1) Letter from K.H.Evers to Document Control Desk dated September 12, 19892) Letter from M.Y.Davis to K.H.Evers dated February 13, 19903) Letter from L.Sridharon (WDNR) to M.Vandenbusch dated June 13, 1991In reference 1, pursuant to the regulation of 10 CFR 20.302, Wisconsin Public ServiceCorporation (WPSC) requested authorization for the alternative disposal of very-low-level radioactive materials from the Kewaunee Nuclear Power Plant. In reference 2, the US NRCidentified 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 reviewthe disposal options for the service water pretreatment lagoon sludges.

In reference 3, theWDNR completed a review of the most appropriate on site disposal methods for the slightlycontaminated service water pretreatment lagoon sludges' The two proposed methods that theWDNR evaluated included in-situ capping of the sludge in the wastewater treatment lagoon andon site landspreading.

In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013Document Control DeskOctober 17, 1991Page 2application which is our preferred disposal method. WPSC does not intend to utilize the in-situcapping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed thateither 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.

-if the on site landspreading option is utilized, the material would be spread by eitherdisking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading requirements which include locational andperformance standards.

Should there be any additional questions please feel free to contact amember of my siaff.Sincerely, c~c( Z.'A.LC. A. SchrockManager -Nuclear Engineering DJM/jmsAttach.6000000S0SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSScc -.US NRC -Region 1lMr. Patrick Castleman, US NRC D-4 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013ATTACHMENT ITo000000000000000000000000000000Letter from K. H. Evers (WPSC) to Document Control Desk (NRC)DatedOctober 17, 1991D-5 SKEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Document Control DeskOctober 17, 1991Attachment 1, Page 1References

1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989. 0NRC Question

1On 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 9,000gallons per day. Discuss this deviation from the design capacity, and provideinformation to justify the higher output for this system.WPSC ResponseThe original Sewage Treatment System installed at the Kewaunee NuclearPower Plant (KNPP) was replaced in 1986 with a higher capacity system. Theoriginal system was designed for an onsite work force of around 150 people.It was a limited capacity aerobic treatment system which included the onsitelagoon for additional retention.

Because of this limited capacity and morestringent conditions on system effluent to Lake Michigan, an aerobic digestersystem was installed, which has a higher capacity, and uses currenttechnology.

The estimated input volume to the Sewage Treatment System used in theSeptember 12, 1989 application was 11,000 gallons per day. This value wasbased on past operating data. The increase in influent from the original designbasis included in the Final Environmental Statement is due mainly to anincrease in the number of individuals and facilities (e.g., training andsimulator building) located onsite. Design changes to the system wererequired to accommodate these new facilities.

000'D-60000 00* KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130Document Control Desk*October 17, 1991Attachment 1, Page 20The current volumes of sewage sludge were used as the basis for the potential dose analysis and corresponding radionuclide concentration limits. Thisincrease has no significant effect on the dose modeling.

(Refer to the response*to NRC Question

2, below.)S*NRC Question

2* Provide information regarding how the disposal plan assures that the annual*dose to any exposed individual will be kept below 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.0Administrative 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/uCi/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.

Anymaterials with levels of radioactive material above the concentration limitsD00*D-7000 0KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Document Control DeskOctober 17, 1991Attachment 1, Page 3(and of plant origin) will be treated as a radioactive waste and appropriately controlled.

0Records will be maintained to ensure that the cumulative disposal of anycontaminated materials are maintained within the bounds of the evaluation.

[n0addition to a comparison of the individual radionuclide concentration limits, arecord of the total amount of radioactive material disposed of will bemaintained.

Cumulative totals will be maintained to ensure that the totalactivity does not exceed the quantity assumed in the derivation of the limits.In developing the concentration limits presented in Table I of reference 1, itwas assumed the total annual design basis volume of 27,000 ft3 would becontaminated at the derived limit. The dose commitment from eachradionuclide 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 eachradionuclide's concentration divided by its limiting concentration must be lessthan one)..The concentration limits of Table I of reference I also have an implied total activitylimit. This limit is determined by multiplying the individual radionuclide concentration limit by the total estimated waste volume of 27,000 ft3.These totalactivity limits are presented in Table A of this response, for each radionuclide individually.

For a mixture of radionuclides, a total annual activity limit may bedetermined by normalizing the concentrations so that the sum-of-the-fractions for themixture equals one (1). These resultant adjusted concentrations may be multiplied bythe 27,000 ft3 waste volume to determine the corresponding total activity limit of themixture.000D-8000 0* KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130*Document Control DeskOctober 17, 1991Attachment I, Page 40A Disposal Log will be maintained on a calendar year basis for all disposals ofany very-low-level radioactive materials.

The log will contain as a minimumthe following information:

Disposal location* Description of waste* Shipment/disposal 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 activity00*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).0WPSC ResponseThe potential exposure to the general public (onlookers along route) ismodeled by the IMPACTS-BRC code. As addressed in NUREG/CR-3585, this modeling is based on an integration of the source strength, an assumedD*D-9000 OKEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130Document Control Desk 0October 17, 1991Attachment I, Page 50population density along route and vehicular speed. For a conservative evaluation of the potential exposure to the general public from the transport ofthe KNPP waste, a population density of 610 persons/mi 2 was assumed.

Thisvalue is conservative for the KNPP site area where the average population density is less than 53 persons/mi 2.A transport distance of 45 miles was 0assumed.

The IMPACTS-BRC modeling assumes five (5) tons of material are 0transported per shipment.

For the assumed KNPP waste volume, thisshipment weight translates into a total of 167 shipments per year. With avehicular speed of 20 miles per hour, the resultant total population exposuretime is 375 person-hours per year. At the concentration limits established forthe alternative

disposal, the potential onlooker doses during transport will beless than 0.01 person-rem..per year. For the modeling of the exposure to thetransport worker, the IMPACTS-BRC model assumes two drivers per vehicle.

0As presented in the September 12, 1989 submittal, the maximum dose to the 0driver is less than I mrem per year (<0.001 remlyr).

Therefore, the total0collective dose to the transport workers will be twice the individual dose, i.e.,less than 0.002 person-rem.

Including the population dose of <0.01 person-rem per year, the total collective dose to both the transport workers and thepopulation is less than 0.02 person-rem (0.002 person-rem

+ 0.01 person-rem 0< 0.02 person-rem).

0For the disposal of the existing 15,000 f03 of contaminated

sludges, the Spopulation dose due to the transportation of the waste is calculated to be0.0002 person-rem.

The estimated collective exposure to the transport workeris 0.00007 person-rem.

The total collective dose due to transport of the wasteis 0.00027 person-rem.

00D-lO 5000 0* KEWAUNEE POWER STATION ODCM App-D0 OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130 Document Control Desk* October 17, 1991Attachment 1, Page 60Additional Potential Disposal Method0The Wisconsin Department of Natural Resources has requested Wisconsin 0 Public Service to examine the feasibility of land application of the lagoon* sludges in lieu of disposal 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, 1989 submittal.

00 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 spwading of the waste. Attachment A to this response0 provides an overview of the land spreading disposal method. Also, the00 pathways of exposure applicable to the onsite land application are evaluated; 0 and a comparison to the controlling pathways and radionuclide concentrations as presented in the September 12, 1989 submittal are discussed.

From amodeling 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. The other post-disposal exposure scenarios, "Intruder 0 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 0 or post-release from the Kewaunee site. In no case is there a higher potential 0 for exposure from land application than the pathways and potential exposures 0 that were used for the derivation of the limits for alternative disposal.

0Therefore, no revisions are needed to the radionuclide concentration limits0proposed in the September 12, 1989 submittal to include the option for00 D-1I0010 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALDocument Control DeskOctober 17, 1991Attachment 1, Page 7ODCM App-DRevision 16December 5, 2013Table ARadionuclide Quantity Limitsfor Alternative DisposalLimitingLimiting AnnualNuclide Concentration Quantity(pCi/ml)

(Ci)H-3 9.65E-04 0.7382C-14 4.55E-05 0.0348Cr-51 3.13E-04 0.2394Mn-54 1.14EM05 0.0087Fe-55 l-00E-02 7.6500Fe-59 7.90E-06 0.0060Co-58 1.16E-05 0.0089Co-60 3.74E-06 0.0029Ni-63 i.00E-02 7.6500Sr-90 3.45E-03 2.6393Zr-95 6.28E-06 0.0048Nb-95 1.23E-05 0.0094Mo-99 6.73E-05 0.0515Tc-99 2.70E-04 0.20661-129 2.50E-06 0.00191-131 2.68E-05 0.0205Cs- 134 6.16E-06 0.0047Cs-137 1.71E-05 0.0131Ba-140 5.52E-05 0.0422La- 140 4.17E-06

0.0 032Transuranics

.TRU (T'IA > 5 yrs) 8.91E-05 0.0682Pu-241 2.85E-03 2.1803Cm-242 1.00E-02 7.6500Assumes annual quantity of KNPP wastes is 27,000 ft3 or7.65E8 mls.S0000S00S00S000S00S0SSD-12 0* KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16SDecember 5, 20130Document Control Desk* October 17, 1991Attachment 1, Page 80 Appendix A* Evaluation of Onsite Land Application for* Alternative Disposal of Very-Low-Level Contaminated Materials 0Overview*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 he performed by beneficial land application to a dedicated

disposal area located onsite at the Kewaunee Nuclear Power Plant. Typical methods of landspreading 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.S*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 0land that covers any lands upon which food crops are grown or animals are grazed forhuman 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 of0sludge contaminants will be applied to the KNPP wastes even though the less restrictive Non-0Agricultural Land Application sludge contamination limits are allowed.

Therefore, no morethan 50 metric tons of sludge per hectare will be applied to the dedicated disposal site. Thislimit will ensure that any land application will not exceed the bounds of the dose analysis as00*D-13000 KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130Document Control DeskOctober 17, 1991Attachment 1, Page 9performed previously.

In addition, other limitations as applied to land application by theState of Wisconsin Department of Natural Resources will be followed (e.g., control ofrunoff/erosion, proximity to wells/residences/surface water, etc.).Applicable Pathways of ExposureThe pathways of exposure applicable for land spreading are not appreciably different fromthe pathways evaluated for the disposal methods at the Kewaunee County Landfill or theGreen Bay Metropolitan Sewerage District facilities.

The major exposure pathways arediscussed below:Direci Exposure to Workers 0Any potential exposures to workers involved in the removal, transport and landspreading of the sludges are reasonably bound by the evaluation of theexposure to the transport worker in the September 12, 1989 submittal.

The0transport 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 atone (1) meter from unshielded waste. For the land spreading of these wastes,it is estimated that the total exposure time for the removal and disposal of thelagoon sludges will require no longer than a three week period per year (i.e.,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 beenestimated 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 beinvolved in land maintenance activities, such as plowing and mowing. Asmodeled in the September 12, 1989 submittal, an exposure of 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months peryear to the landfill operator has been assumed.

For this exposure, the KNPPmaterials are mixed with other landfill waste: a 1:13 mixing of KNPPmaterials to other waste is assumed.

This mixing is not significantly different from the type of mixing that will occur in the field with the sludges being0D-14000

KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16*December 5,20130*Document Control Desk*-October 17, 1991Attachment 1, Page 10plowed into the soil to a depth of six (6) inches. With a land spreading of 50metric 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

% 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.0IThe onsite land application of KNPP waste will be limited by the Agricultural Land0Application sludge concentrations even though the less restrictive Non-Agricultural 0Land Application sludge concentrations are applicable since a "dedicated landSdisposal" 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 maximumsludge 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.

000D-10 KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130Document Control Desk 5October 17, 1991Attachment 1, Page 11Post Disposal

-Intruder WellThe intruder well pathway for onsite land disposal is essentially the same as theintruder 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, locatingthe well at the disposal site edge in "downstream flow" direction maximizes the 5calculated hypothetical dose. (Additional discussion of this modeling is presented in 5NUREG/CR-3585, Volume 2).SThe potential dose for the intruder well scenario for the land spreading disposal wouldbe less than 0.001 mrem per year. Tie modeling as presented in the September 12,1989 submittal reasonably bounds any hypothetical well water exposure pathway.

SIn summary, the modeling of the exposure scenarios, as presented in the September 12, 1989 submittal, conservatively bounds the hypothetically exposures for the on-siteland 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 slightlycontaminated materials.

50SSSSSSSSSSD-16 500S KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013K.1-HUNITED STATESNUCLEAR.

REGULATORY COMMISSION WASHINGTON.

D.C. 0000SS000S00June 17, 1992Docket No. 50-305Mr. C. A. SchrockManager -Nuclear Engineering Wisconsin Public Service.Corporation P. 0. Box 19002Green Bay, Wisconsin 54037-9002

Dear Mr. Schrock:

SUBJECT:

PROPOSED DISPOSAL OF LOW LEVEL RADIOACTIVE WASTE SLUDGE ONSITE ATTHE KEWAUNEE NUCLEAR POWER PLANT (TAC NO. M75047)By letters dated September 12, 1989. and October 17, 1991, you submitted arequest pursuant to 10 CFR 20.302 for the disposal of waste sludge onsite atthe Kewaunee Nuclear Power Plant. We have completed our review of the requestand find your procedures, including documented commitments, to be acceptable.

This approval is granted provided that the enclosed safety evaluation ispermanently incorporated into your Offslte Dose Calculation Manual (ODCM) asan Appendix, and that future modifications of these commitments are reportedto the NRC.Issuance of this safety evaluation completes all effort on TAC No. M75047.Sincerely, Allen G. Hansen, Project ManagerProject Directorate 111-3Division of Reactor Projects III/IV/VOffice of Nuclear Reactor Regulation

Enclosure:

As stated.cc w/enclosure:

See next pageNRC LETTER DISTRIBUTION T A Hanson (MG&E)J D Loock (WPL)Larry Nieisea (ANFC)J L Belant (NSRAC)D A Bollom G6K H Evers KNPJ P Gieslet D2M L Marchi KNPD L Mosarik KNPR P Pulec D2 (2)D J Riitau D2A I Ruege D2C A Schrock D2C Rt Swinhar D2T J Webb KNPS F Womiak D2QA Vault KNPD-17 0KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Wisconsin Public Service Corporation Kewaunee Nuclear Power Plantcc:David Baker. EsquireFoley and LardnerP.O. Box 2193Orlando, Florida 32082Glen Kunesh, ChairmanTown of CarltonRoute 1Kewaunee, Wisconsin 54216Mr. Harold Reckelberg, ChairmanKewaunee County BoardKewaunee County Courthouse

Kewaunee, Wisconsin 54216Chairman 0Public Service Commission of Wisconsin Hill Farms State Office BuildingMadison, Wisconsin 53702Attorney General114 East, State CapitolMadison, Wisconsin 53702U.S. Nuclear Regulatory Comisslon Resident Inspectors OfficeRoute 01, Box 999Kewaunee, Wisconsin 54216Regional Administrator

-Region IIIU.S. Nuclear Regulatory Commission 799 Roosevelt RoadGlen Ellyn, Illinois.

60137Mr. Robert S. CullenChief EngineerWisconsin Public Service Commission P.O. Box 7854Madison, Wisconsin 53707D00000000000D-18 0000 W KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 16* December 5, 2013NUCLEAR REGULATORY COMMISSION

WASHGON.

D.C.O SAFETY EVALUATION ft-THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELY

CONTAMINATED WASTE SLUDGE* AT THE KEWAUNEE NUCLEAR PODJER PLANTW WSCONSIN PUBLIC SERVICE CORPORATION WISCORSIN POWER AND LIGHT COMPANYMADISON GAS AND ELECTRIC COtPANY*DOCKET NO. 50-305

01.0 INTRODUCTION

In reference

.1, Wisconsin Public Service Corporation (WPSC) requested approvalpursuant to Section 20.302 of Title 10 of the Code of Federal Regulations (CFR) for the disposal of licensed material not previously considered in theKewaunee Final Environmental Statement (FES) dated December 1972. Additional 4rglated material from the licensee,,

from the State of Wisconsin, and from thestaff are contained in references 2 through 5.The WPSC request contains a detailed description of the licensed material(i.e., contaminated sludge) subject to this 10 CFR 20.302 request, based onradioactivity absorbed from liquid discharges of licensed material.

The*15,000 cubic feet of contaminated sludge identified in the request contains atotal radionuclide inventory of 0.17 mCi of Cesium-137 and Cobalt-6O.

In its submittal, the licensee addres;ed specific information requested in*accordance with 10 CFR 20.302(a),

provided a detailed description of thelicensed

material, thoroughly analyzed and evaluated the information pertinent 0to the effects on the environment nf the proposed disposal of licensedmaterial, and committed to follow specific procedures to minimize the risk of0unexpected exposures.

2.0 DESCRIPTION OF WASTE*During the normal operation of Kewaunee, the potential exists for in-plantprocess streams which are not normally radioactive to become contaminated with very low levels of radioactive materials.

These waste streams arenormally separated frqm the radioactive streams.

However, due mainly toinfrequent, minor system leaks, and anticipated operational occurrences, thepotential exists for these systems to become slightly contaminated.

AtKewaunee, the tecondary system demineralizer resins, the service water pre-treatment system sludges, the make-up water system resins, and the sewagetreatment plant sludges are waste streams that have the potential to becomecontaminated at very low levels.00000D-I000 0KEWAUNEE POWER STATION ODCM App-D 0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013-2-0During the yearly testing of a batch of pre-treatment sludge, it was foundthat approximately 15,000 cubic feet of sludge had been contaminated withCs-137 and Co-60.3.0 PROPOSED DISPOSAL METHODWPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsitepursuant to 10 CFR 20.302. The sludge is currently contained in an onsitelagoon at the KNPP sewage treatment facility.

The disposal of the sludge willbe by land application to an area located onsite at KNPP, as shown inFigure 1. 7he area will be periodically plowed to a depth of 6 inches.Table I lists the principal nuclides identified in the sludge. The activityis based on measurements made in 1989. The radionuclide half-lives, which aredominated by 30-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (reference 6), which apply to radionuclides with half-lives less than 35y e a r s .TNuclide Total Activity (mCilCo-60 0.076Cs-137 0.0940.17004,0 RADIOLOGICAL tMPACTSThe licensee has evaluated the following potential exposure pathways tomembers of the general public from the radionuclides in the sludge: (1)external exposure caused by groundshlne from the disposal site; (2) internalexposure from inhalation of re-suspended radionuclides; and (3) internalexposure from ingesting ground water. The staff has reviewed the licensee's calculatlonal methods and assumptions and finds that they are consistent withNRC Regulatory Guide 1,109, "Calculation of Annual Doses to Man from RoutineReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977. The staff finds theassessment methodology acceptable.

Table 2 lists the doses calculated by the licensee for the maximally exposedmember of the public based on a total activity of 0.170 Wi disposed of in thecurrent year, as well as the cumulative Impact of similar disposals duringsubsequent years. For any repetitive disposals, the licensee must reapply tothe NRC when a particular disposal would exceed the following boundaryconditions:

(1) the annual disposal must be less than a total activity of 0.2mCi; (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 siteas described in Figure 1.000000D-20000

KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130*~ -3Whole Body Dose Received byMaximally Exposed Individual Pathway (mrem/vear)

Groundshlne 0,034Inhalation 0.008* Groundwater Ingestion 0.007TOTALAs shown in Table 2, the annual dose Is expected to be on the order of0.1 mrem or less. Such a dose is a small fraction of the 300 mrem receivedannually by members of the general public from sources of natural background radiation.

oThe guidelines used by the NRC staff for onsite disposal of licensed materialare presented in Table 3, along with the staff's evaluation of how eachguideline has been satisfied.

0 The licensee's procedures and commitments as documented in the submittal areacceptable, provided that they are permanently incorporated Into thelicensee's Offsite Dose Calculation Manual (00CM) as an Appendix, and that* 0 Future modifications be reported to NRC In accordance with the applicable ODCMchange protocol.

Based on the above findings, the staff finds the licensee's proposal todispose of the low level radioactive waste sludge onsite in the mannerdescribed in the WPSC letter dated September 12, 1989, to be acceptable.

TheState of Wisconsin has. also approved these procedures (reference 5).0000000S0000000*) D-2I000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUAL-4 -TABLE 320.302 Guideline for onsite DisposeaODCM App-DRevision 16December 5, 2013Staff's Evaluation

1. The radioactive material shouldbe disposed of in a manner that itis unlikely that the material wouldbe recycled.

2. Doses to the total body and anybody organ of a maximally exposedindividual (a member of the generalpublic or a non-occupationally exposed worker) from the probablepathways of exposure to the disposedmaterial should be-less thanI mrem/year.

3. Doses to the total body and anybody organ of an inadvertent intruder from the probable pathwaysof exposure should be less than5 mrem/year.

4. Doses to the total body and anybody organ of an individual fromassumed recycling of the disposedmaterial at the time the disposalsite is released from regulatory control from all likely pathways ofexposure should be less than I mrem.1. Due to the nature of thedisposed

material, recycling to thegeneral public is not considered likely.2. This guideline is addressed inTable 2..3. Because the material will beland-spread, the staff considers themaximally exposed individual scenario to also address theintruder scenario.

4. Even if recycling were to occurafter release from regulatory

control, the dose to the maximally exposed memberof the public is notexpected to exceed 1 mrem/year, based on the exposure scenarios considered in this analysis.

000000SS00C0000000000000S0D-22 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013-.5-BELL&LKLZ 00000000000000S000000000(1) WPSC letter From K. H. Evers to NRC Document Control Desk, September 12,1989.(2) Memorandum from L. J. Cunningham, DREP, to J. N. Hannon, "Request ForAdditional Information,"

December 11, 1989.(3) NRC letter from M. J. Davis to K. H. Evers of WPSC dated February 13, 1990.(4) WPSC letter from K. H. Evers to NRC Document Control Desk, October 17,1991.(5) Letter from L. Sridharon of the State of Wisconsin Department of NaturalResources to N. Vandenbusch of WPSC, dated June 13, 1991.(6) E. F. Branagan Jr. and F. J. Congel. "Disposal of Contaminated Radioactive Wastes from Nuclear Power Plants, presented at the HealthPhysics Society's midyear Symposium on Health Physics Considerations inDecontaminatlon/Decommissionlng, Knoxville, TN, February 1986(CONF-850203).

Principal Contributor:

J. MinnsDate: June 17. 1992D-23 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013-6-Figure IKewaunee Nuclear Power Plant Site Area Map000000000000000000000000D-24

KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013+ ,#A UNrTED STATES9/14 REGULATORY COMMMISlON O

14. 1994.Mr. C. A. SchrockManager -Nuclear Engineering Wisconsin Public Service Corporation Post Office Box 19002*Green Bay, 1I 54307-9002

SUBJECT:

SAFETY EVALUATION FOR AN AMENDMENT TO AN APPROVED 10 CFR 20.302APPLICATION FOR THE KEWAUNEE NUCLEAR PLANT (TAC NO. 489719)

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 wastesludge In addition to the location approved by the NRC on June 17, 1992. Thestaff has completed its review of your request and finds that your proposalmeets the radiological boundary conditions approved In the June 17. 1992.*Safety Evaluation, and Is therefore acceptable.

The staff also finds thatyour 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 ispermanently Incorporated Into your Offsite Dose Calculation Manual (O0CM) as0 an Appendix, and that future modifications of these comitments are reported* to the NRC.*Sincerely,

Richard J. Laufer, Acting Project Manager*Project Directorate

[11-3Division of Reactor Projects Ill/IV*Office of Nuclear Reactor Regulation

Docket No. 50-3os

Enclosure:

Safety Evaluation cc w/enclosure:

0see next pageT TA (M"uti K A imp XJ[ CCS Sminr NPM W Siz(WPL)

ML mURDLoau7 NWam V .N D L ) ]lp C A Stauim" D2DAIaouN JN mDI T JW mbbIMD ICO b hIp L A Nlu*b MAC) 3 1 WaNk D2K H Sven KNP R P Pdw D2 (2) QA VIlt h PO D-25* PidegO KEWAUNEE POWER STATION ODCM App-DOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Wisconsin Public Service Corporation Kewaunee Nuclear Power Plantcc: 0Foley & LardnerAttention:

Mr. Bradley D. Jackson 0One South Ptnckney StreetP. 0. Box 1497 0Madison, Wisconsin 53701-1497 ChairmanTown of CarltonRoute IKewaunee.

Wisconsin 54216 0Mr. Harold Reckelberg.

Chairman "Kewaunee County BoardKewaunee County Courthouse 0Kewaunee, Wisconsin 54216ChairmanPublic Service Comilsslon of SWisconsi unHill Farms State Office BuildingMadison, Wisconsin 53702Attorney General114 East, State CapitolMadison, Wisconsin 53702U. S. Nuclear Regulatory Commission Resident Inspectors OfficeRoute 01, Box 999Kewaunee, Wisconsin 54216Regional Administrator

-Region IIIU. S. Nuclear Regulatory Commission 801 Warrenville RoadLisle. Illinois 60632-4531 0Mr. Robert S. Cullen 0Chief EngineerWisconsin Public Service Comuission P. 0. Box 7854Madison, Wisconsin 53707020)01010)D-26 010101.* 40 S KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013UN.ITD STATESNUCLEAR REGULATORY COMMISSION 0 ASHl~ rNINO ON .0 0 U UO SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION O RELATING TO ONSITE DISPOSAL OF LOW-_LEVEL RADIOACTIVELY

CoNTA[NATE TM SLUOES~AT THE KEWAUNEE NUCLEAR POWER PLANTO WISCONSIN PUBLIC SERVICE CORPORATION VISCONIN POWER AND LIGE-CONPANY O DOCKET NO, 50-305OO 1.0 !NTROIICTION By letter dated June 23, 1994, and as supplemented on June 29, 1994, Wisconsin Public Service Corporation (the licensee) requested approval to use anotheronsita area for the disposal of contaminated waste sludge in addition to thelocation approved by the NRC on June 17, 1992.2.0 EVALUATION O A Safety Evaluation (SE) dated June 17, 1992, approved the licensee's requestpursuant to 10 CFR 20.302 for the dis sal of 15,000 cubic feet ofcontaminated waste sludge by land application at the Kewaunee Nuclear PowerO 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 .Ci.2. The whole body dose to the hypothetical maximally exposed Individual

must be less than 0.1 mm/year.O 3. The disposal must be the same site.O The site designated In the SE was an unused area adjacent to the onsite lagoonat the KNPP sewage treatmant facility.

In 1993. approximately 7500 cubic feetof the original IS,000 cubic feet of contaminated sludge was spread on thatlocation.

The licensee has now proposed to dispose of the remaining contaminated sludge at another onsite location northwest of the plant (seeAttachment).

The licensee has comitted that the new disposal.

locatioit willmeet all the radiological boundary conditions contained in the SE for the10 CFR 20.302 application approved on June 17, 1992. Additionally, thelicensee has stated that this additional disposal site will meet allO applicable Wisconsin Department of Natural Resources (IMNR) application requirements (i.e., sludge application rate and frequency of spreading rate).in addition to WOUR landspreading requirements regarding location andperformance standards that were required at the original disposal site.OOOO D-27000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013-2-3.0 COmLUSION The staff finds the licensee's proposal to dispose of the low-level radioactive waste sludge in the additional onsite location to be within theradiological boundary conditions approved In the June 17, 1992, SE and Istherefore acceptable.

The staff also finds that your proposal is Inaccordance vith 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 20.302application, the licensee Is required to permanently Incorporate thismodification into the Offsite Dose Calculation Manual as an Appendix, and thatfuture modification of this comitment be reported to the NRC.Principal Contributor:

S. [lementowicz Date: September

14. 1994

Attachment:

KNPP Site Area'HapD-28S00S0000000000S00SS000S000S00SSSS 0000000000000000000000000000000000000000000o KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013--------------------- ftaj--------------------------2.D-29 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013NE@~\qUUNITED STATESNUCLEAR REGULATORY COMMISSION WAUHINGTO1, D.2O. 4November 13, 1995A'460d- / I -;t D -7S-Mr. M. L. MarchlManager -Nuclear Business GropWisconun Public Service Corporation Post Office Box 19002Green Bay. V1 54307-9002

SUBJECT:

ALTERNATE DISPOSAL OF CONTANINATED SEWAGE TREATNEIT ACCORDANCE VITH 10 CFR 20.2002 (TAC NO. N93844)PLANT SLUDGE IN

Dear Mr. Marchi:

By letter dated October 17, 1995. as supplemnted an November

3. 1995, yourequested approval for the onsite disposal of contmainated seoge treatmntsludge in accordance with 10 CFR 20.2t. This request was simlar to aprevious disposal request that was approved by the NRC on June 17, 1992.The staff has completed Its review of your request and finds that yourproposal mots 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 Ispermanently incorporated into you Offsite Dose Calculation Manual (O0CN) as anAppendix, and that future modifications of these comitments are reported tothe NRC.Sincerely, Richard J aoProject ManagerProject Directorate 111-3Division of Reactor Projects 111/IVOffice of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

Safety Evaluation cc: See next pageS0000000000S0SSS0SS00000T A li==o (MG&E)M W SUn (WPL)Lacy Nichm (ANFC)D A MGMwz 06D 6 Day DIK H Event XNPbf L Mudd D2I X Jubin (NSRAC)R P.P" XW ~(3)C A Schrock 1WPC S Smatar KWHC R Sleinhaa*

D2CA Sunkty KNP(Uc)S IF Wazd*a D2al Domnick XNP (Corn)D-30

KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013O Hr. H. L. MarchiWisconsin Public Service Corporation Kewaunee Nuclear Power Plantcc:Foley A LardnerAttention:

Mr. Bradley 0. JacksonOne South Pinckney StreetP. 0. Box 1497Madison, Wisconsin 53701-1497 ChairmanTown of CarltonO Route IKeaunee.

Wisconsin 542160 Mr. Harold Reckelberg, ChairmanO Kewaunee County BoardKewaunee County Courthouse 0 Kewaunee, Wisconsin 54216O Chal manPublic Service Commission ofWisconsin Hill Farms State Office BuildingO NMdison.

Visconsin 53702Attorney General114 East, State Capitol* Madison, Wisconsin

$3702U. S. Nuclear Regulatory Couission Resident Inspectors Office0 Route #1, Box 999Kewaunee, Wisconsin 54216Regional Administrator

-Region IIIU. S. Nuclear Regulatory Commission 801 Varrenville RoadLisle, Illinois 60532-4531 0 'Mr. Robert S. CullenO Chief EngineerWisconsin Public Service Commssion P. D. Box 7854Madison, Wisconsin 5370700000O000O D-3I000 KEWAUNEE POWER STATION ODCM App-D OOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013*A UNITED STATESNUCLEAR REGULATORY COMMISSION at WA.MI.,TON,

.o, D. =04SA~FTY EVALUATIIN, 5? ThF OFFtcE OF NUCLEAR RFACTOR RESULAIIOM RELATING TO ONSITE DISPOSAL OF LOM-LEVEL RADIOACTIVELY 0CONTANINATED SEWAGE TR.AUTHT SLUDGEAT THE KWAUNEE NUCLEAR POWER PLMNWISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANYMADISON GAS AND ELECTRIC COMPANYDOCKET NO. 50-30SO01.0 INTOMIIMBy letter dated October 17, 1995, os supplemeted on Novomber 3, 1995,Wisconsitn Public Servce Corporation (the licensee) requested approval for theonsite dtsposal of contaminated smogs sludge similar to a previous disposalrequest that was approved by the NRC on Juno 17. 1992.2.0 MACKGRMWIn a letter dated September 12, 1989, the licensee requested authorization forthe alternate disposal of very-low-level radioactive material.

In a SafetyEvaluation (SE) dated June 17, 1992, the NRC approved the licensee's requestpursuant to 10 CFR 20.302 (new 10 CFR 20.2002) for the disposal of 15,000cubic feet of contaminated wasta sludge by land application at the KewauneeNuclear Power Plant (KNPP) location.

The SE imposed the following boundaryconditions:

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

3. The disposal must be at the same site.The 1 Icensee 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 boundaryconditions of the previously approved disposal.

3.0 *YALUAI.WI The 1 icensee has proposed to dispose of approximately 5000 gallons (800 cubic Ofeet) of sewage sludge similar to the material approved for disposal in the SEdated June 17, 1992. The principal radlonuclides identified In the wastesludge and their activity based on measurements In Nay 19,9 are: Co-58,D00SD-32 OO00 KEWAUNEE POWER STATION ODCM App-DO OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130O 0.0009 ict; Co-60, 0.0008 mCi; and Cr-51, 0.0006 mCI. The total combinedactivity is 0.0023 noi. This activity is well below the boundary value of0.2 mCi. Additionally, Cr-Il with It short half-life (27.7 day) will haveO undergone significant decay from Its Initial value of 0.0006 mCi.* The licensee has committed that the now disposal will met all theradiological boundary conditions, on a cumulative basis, contained In the SEfor the 10 CFR 20.M02 application approved on June 17, 1992. Additionally, the licensee has stated that all applicable permits for this disposal havebeen obtained from the Wisconsin Department of Natural Resources.

O

4.0 CONCLUSION

O The staff finds the licensee's proposal to dispose of the lo-levelradioactive waste sludge pursuant to 10 CFR 20.2002, on the licensee's site(see Attachment),

is within the radiological boundary conditions approved inSthe June 17, 1992, SER and Is therefore acceptable.

The licensee Is required to perumantly incorporate this modification Into theOffsIte Dose Calculatien Mlanual as an Appendix, and to ensure that fturemodifications of these commitments are reported to the NRC.O Principal Contributor:

S. Klementowicz Date: Novenber 13, 1995*

Attachment:

KNPP Site Area NapD-1O0O00S0OOO000O000O D-33000 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013I........................

iD-34D-34 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013kl-? 7- Z/0000000S000UNrfED STATESNUCLEAR REGULATORY COMMISSION WASHINGTON.

D.0. Ma.4MApril 9, 1997Mr. M. L. MarchiManager -Nuclear Business GroupWisconsin Public Service Corporation Post Office Box 19002Green Bay, W[ 54307-9002

SUBJECT:

ONSITE DISPOSAL OF CONTAMINATED SLUDGE PURSUANT TO(TAC NO. M97411)10 CFR 20.2002

Dear Mr. Marchi:

By letter dated December 10, 1996, you requested that the U.S. NuclearRegulatory Conmission (NRC) review the applicability of a 10 CFR 20.203 (now20.2002) application approved on June 17, 1992, for additional disposals of asimilar nature.The staff has completed its review of your request and agrees with yourdetermination that the 10 CFR 20.203 application for onsite disposal of sludgecontaminated with licensed radioactive

material, which was approved onJune 17, 1992, contains bounding conditions that are applicable for additional onsite disposals of a similar nature. A copy of the Safety Evaluation Isenclosed.

Sincerely, Richard J. Lader, Project MlanagerProject Directorate 111-3Division of Reactor Projects III/IVOffice of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

Safety Evaluation cc: See next pagebmtn L-G m 2 mNrT A HA==i (MO&Z)M WSob (WMOD AD=?06D 9 Day DIK H Rve" ~pb(L bradic D2I1a.,g KNPQ4IRAC)

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'; F Wa* D2WD*=3iCkrRRftxheffii0 MPMO-TSAR)D-35 KEWAUNEE POWER STATION ODCM App-D UOFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013Mr. N. L. MarchiWisconsin Public Service Corporation Kewaunee Nuclear Power Plantcc: 0Foley & LardnerAttention:

Mr. Bradley D. JacksonOne South Pinckney StreetP. 0. Box 1497Madison, Wisconsin 53101-1497 ChatrmanTown of Carlton 0Route IKewaunee, Wisconsin 54216Hr. Harold Reckelberg, ChairmanKewaunee County BoardKewaunee County Courthouse

Kewaunee, Wisconsin 54216ChairmanWisconsin Public Service Commission 610 N. Whitney WayMadison, Wisconsin 53705-2729 Attorney General114 East, State CapitolMadison, Wisconsin 53702U. S. Nuclear Regulatory Commission Resident Inspectors OfficeRoute fl, Box 999Kewaunee, Wisconsin 54216Regional AWilnistrator

-Region IIIU. S. Nuclear Regulatory Comuisston 801 Warrenville Road " 0Lisle, Illinois 60532-4531 Mr. RFobert S. CullenChief EngineerWisconsin Public Service Commission 610 N. Whitney WayMadison, Wisconsin 53705-2829 0S00000000D-36 0)S00

KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 20130UNITE STATES.NUCLEAR REGULATORY COMMISSION WA5*O0GTON.

D.C,.0opSAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATING TO ONSITE DISPOSAL OF CONTAMINATED SLUDGE* AT THE KEWAUNEE NLEAR POWER PLANT* WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANYMADISON GAS ANO ELECTRICCONPANY

DOCKET NO. 50-30501 L IoBy letter dated December 10, 1996, Wisconsin Public Service Corporation (thelicensee) requested that the U.S. Nuclear Regulatory Commission (NRC) review*its determination that NRC approval, pursuant to 10 CFR 20.2002.

for theonsite disposal of contaminated sludge at the Kewaunee Nuclear.

Power Plant(KNPP) is not required, provided such disposals are conducted within thelimits and bounding conditions approved by the NRC In its June 17, 1992,* Safety Evaluation (SE).2.0 BACKGROUND In a letter dated September 12, 1989, the licensee requested authorization forthe 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 KNPPlocation.

The SE imposed boundary conditions as follows:I. 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 uris/year; and3. 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.

0 3.0 EALOA71ON The licensee has determined that NRC approval for future onsite disposals of*sludge contaminated with licensed radioactive material is not requiredprovided the disposals comply with the limits and conditions of the SE issuedon June 17, 1992. The licensee has also developed a sludge sampling andanalysis procedure that implements the guidance contained in NRC Information D* D-37000 0KEWAUNEE POWER STATION ODCM App-D 0OFFSITE DOSE CALCULATION MANUAL Revision 16December 5, 2013 0INotice 88-22. Specifically, the licensee's procedure will require theanalysis of sludge samples using a detection system design and operating chracteristics that yield a lower limit of detection for Co-58, Co-60,CS-134, and Cs-137 consistent with measurements of environmental samples.

The 0licensee has provided a site map (attached) that specifies the acceptable onsite disposal areas for the contaminated sludge.

4.0 CONCLUSION

The staff agrees with the licensee's determination that additional onsite 0disposals of contaminated sludge, which are conducted within the boundinglimits and conditions contained in the June 17, 1992,. SE and within the areasspecified in the attached site map, do not require specific NRC approval.

0The licensee should permanently Incorporate this Safety Evaluation into theOffsite Dose Calculation Manual as an Appendix.

Principal Contributor:

S. Klementowicz Date: April 9, 1997Attachpent:

KNPP Site Map0301010)0)0101010101010101010101D-38 01010101 KEWAUNEE POWER STATIONOFFSITE DOSE CALCULATION MANUALODCM App-DRevision 16December 5, 2013iIl*itD-39 00000000000000000000This page intentionally left blank 00000000000000000000000 00S00000* RdooiAlpenviromna Moiorn* RailglEnvisionmetl20itrn

October 31, 2013SSSSSSS0SSSSSSSSSS 00000000000000000000This page intentionally left blank0000000000000000000000 00000SDominion Energy Kewaunee, Inc.Kewaunee Power Station0000000S00S000000RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)Revision 20DATE: October 15,2013Approved By:Approved By:Reviewed By:Reviewed By:JM Hale /Manager -Radiological Protection and Chemistry RP Repshas/Licensing Supervisor Date:Date:Date:Date:9/30/1310/7/1310/10/1310/15/13Jeffrey T. Stafford

/Facility Safety Review Committee AJ Jordan /Site Vice President KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALREMMRevision 20October 15, 2013Table of Contents1.0 Introduction

....................................................................................................................

1-11.11.21.3Purpose ................................................................................................................

1-1Scope ...................................................................................................................

1-1Implementation

......................................................................................................

1-12.0 R EM P R equirem ents ....................................................................................................

2-12.1 O DCM 13.5 Requirements

...................................................................................

2-12.2 REM M Requirements

...........................................................................................

2-2REM M 2.2.1/2.3.1 M onitoring Program ...............................................................

2-3REM M 2.2.2/2.3.2 Land Use Census ...................................................................

2-7REMM 2.2.3/2.3.3 Interlaboratory Comparison Program ....................................

2-10REM M 2.4.1 Reporting Requirements

.................................................................

2-123.0 R EM P Im plem entation

..................................................................................................

3-13.13.23.33.43.53.6Sampling Requirements

.........................................................................................

3-1Analysis M ethodology

...........................................................................................

3-1Detection capability (LLD) Requirements

...............................................................

3-1Contracted Vendor (CV) Reporting Requirements

.................................................

3-2Quality Control Program .......................................................................................

3-3Sample Descriptions

..............................................................................................

3-30000S000S00000S00S0000000000Tables & FiguresTable 2.2.1-ATable 2.2.1-BTable 2.2.1-CTable 2.2. 1 -DTable 2.3.1-ARadiological Environmental Monitoring ProgramType and Frequency of Collection Sampling Locations, Kewaunee Power StationReporting Levels for Radioactivity Concentrations in Environmental SamplesDetection Capabilities for Environmental Sample Analysis Lower Likit ofDetection (LLD)Figure 1Figure 2Environmental Sampling LocationGround Monitoring Wells 00* KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15, 20131.0 Introduction 1.1 Purpose*The purpose ofthis document is to define the RadiologicalEnvironmental Monitoring Program (REMP) forthe 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 intendedlo serve as a tool for program administration and as a guidance document for contractors which implement the*monitoring program.1.2 ScopeThis program defines the sampling and analysis schedule which was developed to provide representative 0measurements 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 ofAppendix I to 1 OCFR Part*50 and thereby verifies that the measurable concentrations of radioactivity and levels of radiation are nothigher 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 ofthearea 0near 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

0* This document is considered, by reference, to be part of the Offsite Dose Calculation Manual. This is asrequired by KPS TS 5.5.1. The REMM is controlled as a separate document for ease ofrevision, use inthe 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.000000S*1-I000 00KEWAUNEE POWER STATION REMM 0RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15, 2013The REMP is set up to be implemented by a vendor and controlled by KPS in accordance with NuclearAdministrative Directive NAD-01.20, "Radiological Environmental Monitoring Program."

MorthlyvevL-s 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's report and raw data are checkedand 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 ControlProgram Manuals and implementing procedures shall be kept on file at KPS.Periodic reviews of monitoring data and an annual land use census will be used to develop modifications tothe existing monitoring program.

Upon approval, these modifications will be incorporated into thisdocument so that it will accurately reflect the current radiological environmental monitoring program ineffectfor 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 withtheRBlvlP.

The second section, 3.0 REMP Implementation, describes the specific requirements used to implementthe REMP.00000000000000000001-20000 0* KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15, 20132. 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 T"S to satisfy* existing regulatory requirements for RETS, and02. 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*1 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 ODCM13.5 RequirementsODCM 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 ofthe REMP. ODCM 13.5*also provides the programnatic 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, andc. Participation in an Interlaboratory Comparison Program.0The details of each requirement are described in the REMM requirements stated below.*Technical Specification 5.6.1 requires an "Annual Radiological Environmental Operating Report,"

besubmitted 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.

00000000*2-1000 0KEWAUNEE POWER STATION REMM SRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15, 20132.2 REMMRequirements SThe following REMM requirements include the procedural details that were originally located in the KPSRETS section and then relocated into Revision 6 ofthe ODCM, as discussed above. These requirements are specific to the radiological environmental monitoring program and have been relocated into thisdocument for ease of use and completeness.

The REMM requirements for the Monitoring

Program, Land Use Census, and the Interlaboratory Comparison Program include a detailed operating requirement (numbered 2.2.1, 2.2.2, and 2.2.3respectively) 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 2.4.1.0ODCM 13.0, USE AND APPLICATION, apply to both the ODCM and REMM.2SSSSSSSSSSSSSSSSSS0SSSS2-25SSS KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALRADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMREMMRevision 20October 15, 2013REMM 2.2.1APPLICABILITY:

The radiological environmental monitoring program shall be conducted asspecified in Table 2.2.1-A.At all times.0000000000000000S00ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Radiological Environmental A.1 Prepare and submit to the In accordance with theMonitoring Program not NRC in the Annual Annual Radiological conducted as specified in Radiological Environmental Environmental REMM Table 2.2.1-A.

Operating Report, a Operating Reportdescription of the reasons frequency.

for not conducting theprogram as required and theplans for preventing arecurrence.

B. Level of radioactivity in an B.1 --------NOTES------

environmental sampling

1. Only applicable if themedium at a specified radioactivity/radionuclides location exceeds the are the result of plantreporting levels of REMM effluents.

Table 2.2.1-0 when 2. For radionuclides other thanaveraged over any those in REMM Table 2.2.1-calendar quarter.

D, this report shall indicatethe methodology andOR parameters used to estimatethe potential annual dose toa MEMBER OF THEPUBLIC.2-3 KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALREMMRevision 20October 15, 2013ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEMore than one of theradionuclides in REMMTable 2.2.1-D are detectedin the environmental sampling medium andConcentration 1Reporting level 1-+Concentration 2 + .-2 1.0.Reporting level 2ORRadionuclides other thanthose in REMM Table 2.2.1-D are detected in anenvironmental samplingmedium at a specified location which are the resultof plant effluents and thepotential annual dose to aMEMBER OF THE PUBLICfrom all radionuclides is >the calendar year limits ofDNC 13.1.2, DNC 13.2.2,DNC 13.2.3Prepare and submit to theNRC, a Special Report,pursuant to DNC 15.3, that(1) Identifies the cause(s)for exceeding thelimit(s) and(2) Defines the corrective actions to be taken toreduce radioactive effluents so that thepotential annual doseto a MEMBER OF THEPUBLIC is less than thecalendar year limits ofDNC 13.1.2, DNC13.2.2, DNC 13.2.3ORB.2 -------NOTES------

1. Only applicable if theradioactivity/radionuclides are not the result of planteffluents.

2. For radionuclides otherthan those in REMMTable 2.2.1-D, this reportshall indicate themethodology andparameters used toestimate the potential annual dose to a MEMBEROF THE PUBLIC.Report and describe thecondition in the AnnualRadiological Environmental Operating Report.30 daysIn accordance with theAnnual Radiological Environmental Operating Reportfreauencv.

000S00SSSS0SSSSSSSSSSSSSSSSSSSS0SSSSSS2-4 KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALREMMRevision 20October 15, 20130000S000S0000000000S00000000000ACTIONS (continued)

NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEC. Milk or fresh leafy vegetation C.1 Identify specific alternative 30 dayssamples unavailable from locations for obtaining one or more of the sample replacement samples andlocations required by REMM add them to theTable 2.2.1-A.

Radiological Environmental Operating Program.ANDC.2 When changes in samplinglocations are permanent, then the sampling schedulein the REMM will be updatedto reflect the new routineand alternative samplinglocations.

This revision willbe submitted in the nextAnnual Radiological Environmental Operating I_ Report.VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.1 Collect and analyze radiological environmental In accordance withmonitoring samples pursuant to the requirements of REMM Table 2.2.1-REMM Table 2.2.1-A and the detection capabilities Arequired by Table 2.2.1-A.2-5 00KEWAUNEE POWER STATION REMM 0RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15,2013BASES0The radiological environmental monitoring program required by this requirement providesrepresentative measurements of radiation and of radioactive materials in those exposure pathwaysand for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THEPUBLIC resulting from the station operation.

This monitoring program implementsSection IV.B.2 ofAppendix I to 1 OCFR Part 50 and thereby supplements the radiological effluent monitoring programby verifying that the measurable concentrations of radioactive materials and levels of radiation are nothigher 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 onoperational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the 0lower limits of detection (LLDs). The LLDs required by Table 2.3.1-A are considered optimum forroutine environmental measurements in industrial laboratories.

It should be recognized that the LLDisdefined as a priori (before the fact) limit representing the capability of a measurement system and notas 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 ReportARH-SA-215 (June 1975).0I 0000000000000000002-60000 KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALRADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUSREMMRevision 20October 15, 2013REMM 2.2.2A land use census shall:a. Be conducted,

b. Identify within a distance of 8 km (5 miles) the location, in each of the10 meteorological

sectors, of the nearest milk animal and the nearestresidence, and the nearest garden > 50 m2 (500 ft2) producing broadleaf vegetation, sampling of leaf vegetation may be performed at thesite boundary in each of two different direction sectors with the highestpredicted D/Qs in lieu of the garden census. Requirements for broadleaf vegetation sampling in REMM Table 2.2.1-A item 4c shall befollowed, including analysis of control samples.APPLICABILITY:

At all times.0S0000000S000000000ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Land use census identifies A.1 Identify the new location(s)

In accordance with thelocation(s) that yields a in the next Radiological Radiological calculated dose, dose Environmental Operating Environmental commitment greater than Program.

Operating Report.the values currently beingcalculated inODCM 13.2.3.1.

2-7 00REMM 0Revision 20KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALOctober 15, 2013NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEB. Land use census identifies B.1 Add the new location(s) to 30 dayslocation(s) that yields a the Radiological calculated dose, or dose Environmental Operating commitment (via the same Program.exposure pathway) greaterthan 20% at a location from ANDwhich samples are currently being obtained in B.2 Delete the sampling In accordance withaccordance with locations(s),

excluding the Radiological REMM 2.2.1. control station location, Environmental having the lowest calculated Operating Report.dose, dose commitment(s) orD/Q value, via the sameexposure

pathway, from theRadiological Environmental Operating Program.ANDB.3 Submit in the nextRadiological Environmental Operating Reportdocumentation for a changewhich includes revisedfigures(s) and table(s)reflecting the new location(s) with information supporting the change in samplinglocations.

IVERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.2 Conduct the land use census during the growing 12 monthsseason using that information that will provide the bestresults, such as by a door-to-door survey, aerialsurvey, reporting the results of the land use census inthe Annual Radiological Environmental Operating Report, or by consulting local agriculture authorities.

00000000000000000000000000000000000000002-8 U KEWAUNEE POWER STATION REMM* RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15,2013*BASES0This requirement is provided to ensure that changes in the use of areas at and beyond the SITEBOUNDARY are identified and that modifications to the radiological environmental monitoring programare made if required by the door-to-door survey, from aerial survey or from consulting with localagricultural authorities.

This census satisfies the requirements of Section IV.B.3 of Appendix I to10CFR 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 ofthis 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, thefollowing assumptions were made:* 1. 20% of the garden was used for growing leafy vegetation (i.e., similar to lettuce and* cabbage),

and2. A vegetation yield of 2 kg/rn.00000*00000000000000S00*2-9010 KEWAUNEE POWER STATIONRADIOLOGICAL ENVIRONMENTAL MONITORING MANUALREMMRevision 20October 15, 2013RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAMREMM 2.2.3APPLICABILITY:

Analyses shall be performed on all radioactive materials, supplied as partof an Interlaboratory Comparison Program that has been approved by theCommission.

At all times.ACTIONSNON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIMEA. Analyses not performed as A.1 Report the corrective actions In accordance withrequired.

taken to prevent a recurrence the Annualto the NRC in the Annual Radiological Radiological Environmental Environmental Operating Report. Operating Report.VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.3 Report a summary of the results obtained as part of the In accordance withInterlaboratory Comparison Program in the Annual the AnnualRadiological Environmental Operating Report. Radiological Environmental Operating Report.BASESThe requirement for participation in an approved Interlaboratory Comparison Program is provided toensure 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 forenvironmental monitoring in order to demonstrate that the results are valid for the purposes of SectionIV.B.2 of Appendix I to 10CFR Part 50.S0S000S0S00S00S000SSSSSSSSSSSSSSSS2-10 00* KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15,2013* REMM2.4.1 Reporting Requirements 02.4.1 The Annual Radiological Environmental Operating Report shall include:a. Summaries, interpretations, and an analysis of trends of the results of theradiological environmental surveillance activities for the report period, including a*comparison with pre-operational

studies, with operational controls as appropriate, 0and with previous environmental surveillance

reports, and an assessment of theobserved impacts ofthe plant operation on the environment.

The reports shall asoinclude the results of land use censuses required by REMM 2.2.2.b. The results ofanalyses ofradiological environmental samples and ofenvironmental

radiation measurements taken during the period pursuant to the locations specified in the table and figures in the Radiological Environmental Monitoring Manual(REMM), as well as summarized and tabulated results of these analyses and*measurements in the format of the table in the Radiological Assessment Branch*Technical

Position, Revision 1, November 1979. In the event that some individual

results are not available for inclusion with the report, the report shall be submitted

noting and explaining the reasons for the missing results.

The missing data shall besubmitted 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 anddirections from the centerline ofone reactor; the results of licensee participation inthe Interlaboratory Comparison

Program, required by REMM 2.2.3; discussionof

all deviations from the sampling schedule of Table 2.2. 1-A; and discussion of all*analyses in which the LLD required by Table 2.3.1-A was not achievable.

Discussion KPS 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 includesummaries, interpretations, and analysis of trends of the results of the REMP for the reporting period.*The procedural details ofthis 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, alongwith TS 5.6.1, as the method for reporting deviations from the current program during the reporting period,*and require that this information be included in the Annual Radiological Environmental Operating Report.00000*2-11000 0KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15, 20133. 0 REMP Implementation The Radiological Environmental Monitoring Program for KPS is under the direction of aContracted Vendor (CV). This section describes this program, as required by REMM 2.2.1 and theprocess the CV uses to perform it.3.1 Sampling Requirements STable 2.2. 1-A identifies the various samples required by the REMP. Identified in the "available samplelocations" column in Table 2.2.1-A are the sample locations

selected, in conjunction with the vendor, tomeet 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 eachlocation and the collection frequency.

Table 2.2.1 -C identifies the location and description ofeach samplelocation.

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 theU.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 atwww.emLst.dhs.gov/publications/procman.

Updated copies will be maintained in KPS's vault.03.3 Detection Capability (LLD) Requirements The required detection capabilities for environmental sample and analysis are tabulated in terms of lowerlimits of detection (LLDs) in Table 2.3.1 -A. The LLDs required by Table 2.3.1 -A are considered optirimfor routine environmental measurements in industrial laboratories.

It should be recognized that the LLD isdefined as a priori (before the fact) limit representing the capability of a measurement system and not as anaposteriori (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 ReportARH-SA-215 (June 1975).300003-10000

KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15, 20133.4 Contracted Vendor Reporting Requirements 0*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 statusof*field collections.

One copy of the reports will be submitted within 30 to 60 days of the reporting month.0Annual ReportsSAnnual reports will be submitted in two parts. Part 1, to be submitted to the NRC, will be prepared inaccordance with NRC Regulatory Guide 4.8. It will contain an introductory statement, a summary of* results, description of the program, discussion ofthe results, and summary table. Part II ofthe 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 ofthe results.

Garnma scan datawilbe complemented by figures of representative spectra if requested by KPS. Draft copies of each annualreport 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*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 thereporting levels shown in Table 2.2. 1-D, CV to KPS column. These levels are set below the NRCrequired reporting levels (KPS to NRC column) so actions can be initiated to prevent exceeding the NRC* concentration limits.3.5 Quality Control Program*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 QCProcedures Manual. The program shall be reviewed and meet the requirements of Regulatory Guide 4.15and 1OCFR21.

All data related to quality control will be available for review by Dominion Energy*

upon reasonable prior notification.

Proprietary information will be identified so that it may be*treated accordingly.

Updated copies ofthe Quality Control Program Manual and the Quality Assurance Program Manual wibe*maintained in KPS's vault.0*3-20SS 0KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15, 20133.6 Sample Descriptions A description of each of the samples required by this program follows:Airborne Particulates 0Airborne particulates are collected at six locations (K-If; K-2, K-8, K-31, K-41, and K-43) on acontinuous basis on a 47 mm diameter membrane filter of 0.8 micron porosity at a volumetric rate ofapproximately one cubic foot per minute (CFM). The filters are changed weekly, placed in glassineprotective envelopes, and dispatched by U.S. Mail to the CV for Ganma Isotopic Analysis.

Filter samplesare analyzed weekly for gross beta activity after sufficient time (usually 3 to 5 days) has elapsed to allowdecay of Radon and Thoron daughters.

If gross beta concentration in air particulate samples are greaterthan ten (10) times the yearly mean ofthe control samples, gamma isotopic analysis shall be performed onthe individual samples.

Quarterly composites from each location receive Garmma Isotopic Analysis usirgaGermanium detector.

All identifiable gamma-emitters are quantified.

Reporting units are pCi/m3.Airborne IodineAll air samplers are equipped with charcoal traps installed behind the particulate filters for collection ofairborne 1- 131. The traps are changed once every week. Iodine- 131 is measured byGamma Isotopic Analysis.

Periphyton (Slime) or Aquatic Vegetation 0Periphyton (slime) or aquatic plant samples are collected at or near locations used for surface watersampling.

They are collected twice during the year (2nd and 3rd quarter),

if available.

The samples areanalyzed for gross beta activity and, if available in sufficient

quantity, for Sr-89, Sr-90, and by GammaIsotopic Analysis.

Reporting units are pCi/g wet weight.0FishFish are collected three times per year (second, third, and fourth quarters) near the discharge area (K- Id).Flesh is separated from the bones and analyzed for gross beta activity and byGanma Isotopic Analysis.

The bones are analyzed for gross beta activity and Sr-89 and Sr-90. Reporting units are pCi/g wet weight.Domestic MeatDomestic meat (chickens) may be collected once a year during the 3rd quarter, fromthree locations inthevicinity of the plant (K-24, K-29, and K-32). Samples may not be available every year at every locationdue to farmer preference.

At least one control and one indicator should be collected.

The flesh is analyzedfor gross alpha, gross beta, and by Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides.

Reporting units are pCi/g wet weight.03-3 00SS

KEWAUNEE POWER STATION REMM* RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20* October 15,2013Ambient Radiation

Two packets ofthermoluminescent dosimeters (CaSO4: Dy cards) are placed at twenty-two locations, six* of which are air sampling locations (K-1I K-2, K-8, K-31, K-41, and K-43), three ofwhich are milk* sampling locations (K-3, K-5, and K-39), eight of which are ISFSI area locations (K- Il through K- I s), and the remaining four locations are K -15, K- 17, K-27, and K-30. One packet is0 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 ofihemeasurement, 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 aplastic 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 background.

Maximum Error (1* standard deviation)

-60Co Gamma +/-0.2 mR or +/-3%, whichever is greater.0 The maximum spread between areas on the same dosimeter is 3.5% at I standard deviation.

S* Reporting units for TLDs are mR/91 days for quarterly TLDs and mR/exposure period for annual TLDs.* Tests for uniformity and reproducibility of TLDs as specified in ANSI N545-1981 and NRC Regulatory

Guide 4.13 are performed annually.

Well Water0One 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-lh and K-lg). All samples are analyzed for gross beta inthe totalresidue, 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-1g are also analyzed for gross alpha. Reporting units are*. pCi/I.Precipitation

A monthly cumulative sample ofprecipitation is taken at Location K- 11. This sample is analyzed for trilim* Reporting units are pCi/l.3000000* 3-4000 0KEWAUNEE POWER STATION REMM 0RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15,2013SMilkMilk samples are collected from two herds that graze within three miles of the reactor site (K-38 and K- 034); from four herds that graze between 3-7 miles ofthe reactor site (K-3, K-5, K-35, and K-39); andonefrom a dairy in Green Bay (K-42), 28.1 miles from the reactor site.The samples are collected twice per month duringthe grazing period (May through October) and monthlyfor the rest of the year. To prevent spoilage the samples are treated with preservative.

All samples areanalyzed by Gamma Isotopic Analysis and for iodine -131 immediately alter they are received at thelaboratory.

To achieve required minimum sensitivity of 0.5 pCi/l, iodine is separated on an ion exchangecolumn, precipitated as palladium iodide and beta counted.

Monthly samples and monthly composites ofsemimonthly samples are then analyzed for Sr-89 and Sr-90. Potassium and calcium are determined andthe 137Cs/gK and 90Sr/gCa ratios are calculated.

Reporting units are pCi/l except for stable potassium andcalcium, which are reported in g/LIf milk samples are not available, green leafy vegetables will be collected on a monthly basis (whenavailable) from Locations K-23A, K-23B, and K-26.GrassGrass 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- 1). The samples are analy-edfor gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamnma-emitting radionuclides.

Reporting units are pCi/g wet weight.Cattle feedOnce per year, during the first quarter when grass is not available, cattle feed (such as hay or silage) iscollected from the six dairy farms. The analyses performed are the same as for grass. Reporting units arepCVg wet weight.Vegetables and Grain0Annually, during the 3rd quarter, samples of five varieties of vegetables grown and marketed for humanconsumption are collected from K-26, depending upon the availability of samples.

If samples are notavailable from this location, samples may be obtained from any local source so there is some sample ofrecord. The location will be documented.

In addition, two varieties of grain or leafy vegetables from thehighest predicted X/Q and D/Q, ifavailable, are collected annually from the farmland owned by DominionEnergy Kewaunee (K-23 a and b) and rented to a private individual for growing crops. The analysesperformed are the same as for grass. Reporting units are pCi/g wet weight.0003-50000 S* KEWAUNEE POWER STATION REMMRADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15,20130*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 GammaIsotopic Analysis to identify and quantify gamma-emitting radionuclides.

Reporting units are pCi/g wetweight.* Soil*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- 10. 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-emittingmanmade

radionuclides.

Reporting units are pCi/g dry weight.0Surface WaterSurface 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-i14b).*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- I a, K- I b, K- I e) that pass through the reactor site andfrom the drainage pond (K- 1 k) south of the plant. The samples are taken at a point near the mouth ofeach creek and at the shore of the drainage pond. The water is analyzed for gross beta activity in:a. The total residue,b. The dissolved solids, andc. The suspended solids.*The samples are also analyzed for K-40 and by Garnma Isotopic Analysis.

Quarterly composites from all* locations are analyzed for tritium, Sr-89 and Sr-90. Reporting units are pCi/l.Bottom Sediments

Five samples ofLake Michigan bottom sediments, one at the discharge (K- I d), one from 500 feet north of*the discharge (K- 1 c), one fiom 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 ofwater.* 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 ofthe sediments (i.e., the amount ofradioactivity per unit mass ofS sediment) increases with decreasing particle size, the sampling procedure will assure collection ofvery fine*particles.

Reporting units are pCi/g dry weight.3SS*3-6SS0 0KEWAUNEE POWER STATION REMM 0RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20October 15, 20130Ground Monitoring WellsFigure 2 shows the location of 14 installed groundwater monitoring wells. The wells and location areidentified with a diamond shape in Figure 2. The wells are labeled MW (Monitoring Well) andAB (Auxiliary Building).

The Groundwater Protection Program consists ofthe 14 wells in addition to the two on-site wells already inthe REMM (K- I g and K- I h).Results of analyses and a description of any event above Reporting Levels will be included in the AnnualRadiological Environmental Operating Report for K-I g, K-lh and in the annual Radioactive EffluentRelease Report for the other 14 wells.0000000000000000000000003-70000 00000S0S0000000S0S0SS00:0Table 2.2.1-ARadiological Environmental Monitoring ProgramSampling, Exposure Pathway Minimum Available Sample Collection and Type ofAnalysis And/Or Sample Required Samples Locations b AnalysisFrequency

1. Direct Radiation' 13 Inner Ring locations K-5, K-25, K-27, See Table 2.2.1-B Gamma doseK-43, K-If, K-30,K-ll, K-I1m, K-In,K-lo, K-1p, K-1q,K-1 r, K-i s6 Outer Ring locations K-2, K-3, K-1 5,K-17, K-8, K-31, K-391 Control location K-411 Population center K-43I Special interest location K-8I Nearby resident K-272. Airborne Radioiodine 3 samples close to the site K-if, K-2, K-43, K-8, See Table 2.2.1.B Iodine (1-131) byand Particulates boundary in highest K-31 Continuous Gamma Isotopicf average X/Q sampler operation Iodine; charcoalI sample from the closest K-43 Particulates Particulates; community having the See Table 2.2.1-B gross betahighest X/Q analysise GammaI sample from a control K-41d See Table 2.2.1-B isotopic oflocation composite (bylocation) f3. Waterbome

a. Surface' I Upstream sample K-ia, K-9', K-i d Grab sample Gross Beta,1 Downstream sample K-le, K-14a, K-14b, See Table 2.2.1-B Gamma isotopicK-Ik,K-lb K-40'Composite ofgrab samples fortritium, K-40 andSr 89/90b. Ground 1-2 location likely to be K-lg, K-lhh Grab sample Gamma isotopicaffected d See Table 2.2.1-B tritium and K-40analysisGross Beta,one well forSr 89/90Rev. 20October 15, 2013Page I of 4 Table 2.2.1-ARadiological Environmental Monitoring ProgramSampling, Exposure Pathway Minimum Available Sample Collection andAnd/Or Sample Required Samples S Locations b AnalysisFrequency

c. Drinking 1-3 samples of nearest K-10, K-11, K-13, K-38 Grab sample Gross beta andwater supply See Table 2.2.1-B garmm isotopicanalysis.

Tritiumand K-40 analysisof the composite of monthly grabsamples.

'd. Sediment from I sample from K-14, K-ic, K-Id, K-ij, Grab sample Gamma isotopictshoreline downstream area with K-9 See Table 2.2.1-B analysispotential for recreational Gross Beta,value Sr 89/904. Ingestion

a. Milk Samples from milking K-5k, K-38, K-34 See Table 2.2.1-B 1-131animals in 3 locations Gamma Isotopic rwithin 5 km (if none, then3 locations between 5 to SR 89/908 km) having the highestdose potential.

I alternate location K-3, K-391 control location K-35, K-42b. Fish 3 random samplings of K-id See Table 2.2.1-B Gamma isotopiccommercially and and Gross Beta onrecreationally important edible portions, species in the vicinity of Gross Beta andthe discharge.

Sr 89/90 onbonesc. Food Products Samples of grain or leafy 2 samples K-23a, K-23b See Table 2.2.1-B Gamma isotopicTvegetables grown nearest -and one more and 1-131each of two different location if available Analysis.

offsite locations within 5miles of the plant if milksampling is not 1 sample 15-30 kmperformed.

distant if milk samplingis not performed.

K-26000S000000000000000000000Rev. 20October 15, 2013Page 2 of 4 00000000000000000000000Table 2.2.1-ARadiological Environmental Monitoring ProgramSampling, Exposure Pathway Minimum Available Sample Collection and Type ofAnalysis And/Or Sample Required Samples a Locations b AnalysisFrequency

5. Miscellaneous samplesnot identified inNUREG-0472

a. Aquatic Slime None required K-lk See Table 2.2.1-B Gross BetaK-Ia, K-I1, K-le activity and ifavailable Sr-89,K-14, K-Id Sr-90 and GammaIsotopicf K-9 (control)

b. Soil None required K-I f, K-5, K-35, K-39 GrossAlpha/Beta K-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90K-3, (control)

Gamma Isotopicf

c. Cattle feed None required K-5, K-35, K-39 Gross BetaK-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90K-3,(control)

Gamma Isotopicf

d. Grass None required K-lb, K-If, K-35, K-39 Gross BetaK-5, K-34, K-38 See Table 2.2. I-B Sr-89 and Sr-90K-3,(control)

Gamma Isotopicf

e. Domestic Meat None required K-24, K-29 GrossSee Table 2.2. 1-B Alpha/Beta K-32 (control)

Gamma Isotopicf

f. Eggs None required K-32 See Table 2.2.1-B Gross BetaK-24 Sr-89/90_Gamma Isotopicf

g. Precipitation None required K-Il See Table 2.2.1-B TritiumRev. 20October 15, 2013Page 3 of 4 0S00Table 2.2.1-ARadiological Environmental Monitoring ProgramSampling, Eqposure Pathway Minimum Available Sample Collection andAnd/Or Sample Required Samples Locations b Analysis Type of AnalysisFrequency 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 betaken from each of the "available sample locations" listed (see section 3.1). Deviations from the required samplingschedule will occur if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction ofautomatic sampling equipment and other legitimate reasons.

If specimens are unobtainable due to sampling equipment malfunction, reasonable efforts shall be made to complete corrective actions prior to the end of the next sampling period.All deviations from the sampling schedule shall be documented, as required by REMM 2.4.1.c, in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtainsamples of the media of choice at the most desired location or time. In these instances suitable alternative media andlocations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in theREMM. 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 ofthermoluminescent dosimeters (TLDs). The TLDs areCaSO4: Dy cards with 2 cards/packet and 4 dosimeters/card (four sensitive areas each for a total of eightdosimeters/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 ofanalysis or readout forTLD systems depends upon the characteristics of the specific systemused and selection is madeto 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 inaccordance with the distance and wind direction

criteria, other sites that provide valid background data may besubstituted.

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 allowfor radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearlymean 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 beattributable 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 thehydraulic gradient or recharge properties are suitable for contamination.

In the event elevated analysis are reported by CV for gamma isotopic or tritium, a review will be conducted with the optionto retest additional analysis for hard to detect isotopes or alpha emitters.

The additional test may include Fe-55, Ni-63, oralpha emitters anticipated on current plant conditions.

j. Two samples to be collected, Raw and Treatedk. K-5 is about 5.1 km, closest Milk Location available.

S00Rev. 20Page 4 of 4 October 15, 2013S0 000S0000000SS000S000Table 2.2.1-BType and Frequency of Collection Location Weekly Monthly Quarterly Semi-Annually AnnuallyK-la SW SLtK-lb SW GW SL!K-ic BSbK-ld SW Fla BSb SLOK-le SW SL!K-If AP-, Al (le TLD soK-Ig WWK-lh WWK-Ij BSbK-lk SW SL!K-lI TLDK-im TLDK-in TLDK-lo TLDK-lp TLDK-lq TLDK-Ir TLDK-is TLDK-2 AP-,AI TLDK-3 MIC GW TLD SO C~dK-5 MIC (WR TLD SO adK-8 AP-, AI TLDK-9 SWI BSb SLK-10 WWK-11 PR WWK-13 WWK-14 SWh BSb SL!K-15 TLDK-17 TLDK-23a GRN/GLVeK-23b GRN/GLVeK-24 EG DMK-25 TLDK-26 Rev. 20October 15, 2013Page 1 of 2 Table 2.2.-BType and Frequency of Collection Location Weekly Monthly Quarterly Semi-Annually AnnuallyK-27 TLDK-29 DMK-30 TLDK-31 AP&,AI TLDK-32 EG DMK-34 MIC (IV SO aK-35 MIC (V SO CFadK-38 MIC (V WW SO CFadK-39 Mil TLD (cIV SO aK-41 AP-, AI TLDK-42 MICK-43 AP8', AI TLDa. Three times a year, second (April, May, June), third (July, August, September),

and fourth(October,

November, December) quartersb. To be collected in May and Novemberc. Monthly from November through April; seminMonthly from May through Octoberd. First (January,

February, March) quarter onlye. Alternate if milk is not available f Second and third quartersg. 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 treatedCode Description Code Description Code Description Al Airborne Iodine Fl Fish SO SoilAP Airborne Particulate GR Grass SW Surface WaterBS Bottom Sediment GRN Grain TLD Thermoluminescent Dosimeter CF Cattle feed MI Milk VE Vegetables DM Domestic Meat PR Precipitation WW Well WaterEG Eggs SL Slime (ILV Green LeafyVegetables 00S000000000000S00000S0000000000000000000000Rev. 20October 15, 2013Page 2 of 2 Table 2.2.1-CSampling Locations, Kewaunee Power Station0S000S000S0000000S0DistanceCode Type' (Miles)b and LocationSectorK-I OnsitVK-la 1 0.62 N North CreekK-lb I 0.12 N Middle CreekK-Ic I 0.10 N 500' North of Condenser Discharge K-ld I 0.10 E Condenser Discharge K-le I 0.12 S South CreekK-If I 0.12 S Meteorological TowerK-lg I 0.06 W South WellK-lh I 0.12 NW North WellK-Ij. I 0.10 S 500' south of Condenser Discharge K-lk I 0.60 SW Drainage Pond, south of plantK-il I 0.13 N ISFSI Southeast K-Im I 0.15N ISFSI EastK-In I 0.16N ISFSI Northwest K-lo I 0.16N ISFSI NorthK-lp I 0.17N ISFSI Northwest K-lq I 0.16N ISFSI WestK-Ir I 0.13N ISFSI WestK-Is I 0.12 N ISFSI Southwest K-2 C 8.91 NNE WPS Operations Building in KewauneeK-3 C 5.9 N Lyle and John Siegmund Farm, N2815 Hy 42, KewauneeK-5 I 3.2 NNW Ed Paplham Farm, E4160 Old Settlers Rd, KewauneeK-8 C 4.85 WSW Saint Isadore the Farmer Church, 18424 Tisch Mills Rd, Tisch MillsGreen Bay Municipal Pumping Station, six miles east of Green BayK-9 C 11.5 NNE (sample source is Lake Michigan from Rostok Intake 2 miles northof Kewaunee)

K-10 I 1.35 NNE Turner Farm, Kewaunee SiteK-I 1 I 0.96 NW Harlan lhlenfeldt Farm, N879 Hy 42, KewauneeK-13 C 3.0 SSW Rand's General Store, Two CreeksK-14 I 2.6S Two Creeks Park, 2.5 miles south of siteK-15 C 9.25 NW Gas Substation, 1.5 miles north of Stangelville K-17 1 4.0 W Jansky's Farm, N885 Cty Tk B, KewauneeRev. 20October 15, 2013Page 1 of 2 Table 2.2.1-CSampling Locations, Kewaunee Power StationDistanceCode T Ipe_ (Miles)b and LocationSectorK-20(c) I 2.5 N Carl Struck Farm, N1596 Lakeshore Dr., KewauneeK-23a I 0.5 W 0.5 miles west of plant, Kewaunee siteK-23b I 0.6N 0.6 miles north of plant, Kewaunee siteK-24 1 5.4 N Fictum Farm, N2653 Hy 42, KewauneeK-25 1 1.9 SW Wotachek Farm, E3968 Cty Tk BB, Two RiversK-26(d) C 9.1 SSW Sandy's Vegetable Stand (8.0 miles south of"BB")K-27 I 1.53 NW Schleis Farm, E4298 Sandy Bay RdK-29 1 5.34 W Kunesh Farm, E3873 Cty Tk G, KewauneeK-30 I 0.8 N Fnd of site boundaryK-31 1 6.35 NNW E. Krok Substation, Krok RoadK-32 C 7.8 N Piggly Wiggly, 931 Marquette Dr., KewauneeK-34 I 2.7 N Leon and Vicky Struck Farm, N1549 Lakeshore Drive, KewauneeK-35(e) C 6.71 WNW Duane Ducat Farm, N1215 Sleepy Hollow, KewauneeK-36(0 I Fiala's Fish Market, 216 Milwaukee, KewauneeK-38 I 1.45 WNW Dave Sinkula Farm, N890 Town Hall Road, KewauneeK-39 1 3.46 N .Francis Wotja Farm, N1859 Lakeshore Road, KewauneeK-41 (g) C 22 NW KPS-EOF, 3060 Voyager Drive, Green BayK-42 (h) C 28.1 W Lamers Dairy Products obtain from Green Bay Markets (i)K-43 (j) 1 2.71 SSW Gary Maigatter

Property, 17333 Highway 42, Two Rivers00000000S0S00SS0000S0S00C0Ia. I = indicator; C = controlb. Distances are measured from reactor stack.c. Location removed from program in 2007d. Location K- 18 was changed because Schmidt's Food Stand went out of business.

It was replacedby 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 2007h. Location replaces K-28 as of March 2010i Lamers Dairy is actually located in Appleton.

The herds providing milk to Lamers are locatednearer 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. 20October 15, 2013Page 2 of 2 S0000000S0S00000000000Table 2.2.1-DReporting Levels for Radioactivity Concentrations in Environmental SamplesMedium Radionuclide Reporting LewisCV to IKPS J KPS to NRCbAirborne Particulate or Gases (pCi/m3)

Gross Beta I 131 (Charcoal) 0.1 0.9Cs-134 1 10Cs-137 1 20Precipitation (pCi/1) H-3 1,000 -Water (pCi/I) Gross Alpha 10Gross Beta 30 -H-3 10,000 20,000cMn-54 100 1,000Fe-59 40 400Co-58 100 1,000Co-60 30 300Zr-Nb-95 40 400Cs-134 10 30Cs-137 20 50Ba-La-140 100 200Sr-89 8d --Sr-90 8d --Zn-65 30 300Milk (pCi/I) 1-131 1.0 3Cs-134 20 60Cs-137 20 70Ba-La-140 100 300Sr-89 10 --Grass, Cattle Feed, and Vegetables (pCi/g Gross Beta 30 --wet) 1-131 0.1 0.1Cs-134 0.2 1Cs-137 0.2 2Sr-89 I --Sr-90 1Rev. 20October 15, 2013Page 1 of 2 Table 2.2.1-DReporting Levels for Radioactivity Concentrations in Environmental SamplesI Reporting LeveisMedium Radionuclide R towiCV to KPS" 1KPS to NRCbEggs (pCi/g wet) Gross Beta 30 --Cs-134 0.2 1Cs-137 0.2 2Sr-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 1.0Cs-137 (Flesh) 2 2.0Sr-89 (Bones) 2 --Sr-90 (Bones) 2 --Fish (pCVg wet) Gross Beta (Flesh, 10 -Bones)Mn-54 -30.0Fe-59 -10.0Co-58 -30.0Co-60 -10.0Cs-134 (Flesh) 1 1.0Cs-137 (Flesh) 2 2.0Sr-89 (Bones) 2 -Sr-90 (Bones) 2 -Zn-65 (Bones) -20000S00S00S00S00000000000a.b.C.d.Kacitonucdes will be monitored by tie L, V and concentrations above Me lted imiltS Will bereported to KPS.Concentrations above the listed limits will be reported to NRC as required by REMM 2.2.1 .b.For drinking water samples, this is 40CFR Part 141 value. If no drinking water pathway exists, avalue of 30,000 pCi/l may be used.The Sr-89/90 values are based on the EPA drinking water standards.

See note "f." ofTable 2.3.1-A for firther inforrnation Rev. 20October 15, 2013Page 2 of 2 Table 2.3.1-ADetection Capabilities for Environmental Sample Analysis' Lower Limit of Detection (LLD) b,cWater Airborne Fish Food Products SedimentAnalysis Particulate or Milk (pCi/1)(pCi/i) Gases (pCi/n3) (pCi/kg, wet) (pCi/kg, wet) (pCi/kg, dry)Gross Beta 4 0.01H-3 2000'Mn-54 15 130Fe-59 30 260Co-58, 60 15 130Zr-Nb-95 151-131 Ie 0.07 1 60Cs-134 15 0.05 130 15 60 150Cs-137 18 0.06 150 18 80 180Ba-La-140 15 15Zn-65 30 260Sr-89/90 r 5Rev. 20October 15, 2013Page 1 of 30000000000000000000000000000000000000000000o 0S0Table Notations for Table 2.3.1-A 00a. 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 AnnualRadiological Environment Operating Report.b. Required detection capabilities for thermnoluminescent dosimeters used for environmental mea%tantrts 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 with95% probability with only 5% probability of falsely concluding that a blank observation represents a"rear' signal.For a particular measurement system, which may include radiochemical separation:

LLD = 4.66SbE " V ' 2.22 ' Y exp(-gDt)

Where:LLD is the a prior 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 asappropriate, as counts per minute,E is the counting efficiency, as counts per disintegration, 0V 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, 07 is the radioactive decay constant for the particular radionuclide, andAt for environmental samples is the elapsed time between sample collection, or end of the samplecollection period, and time of counting, 0Typical values of E, V, Y, and At should be used in calculation.

0000Rev. 20 5Page 2 of 3 October 15, 2013000 S000000000000000000000000000STable Notations for Table 2.3.1-A (con't)It should be recognized that the LLD is defined as a (before the fact) limit representing thecapability 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 achievedunder routine conditions.

Occasionally background fluctuations, unavoidable small sample sizes, thepresence of interfering

nuclides, or other uncontrollable circumstances may render these LLDsunachievable.

In such cases, the contributing factors shall be identified and described in the AnnualRadiological Environmental Operating Report.d. If no drinking water pathway exists, a value of 3,000 pCi/1 may be used.e. LLD for drinking water samples.

If no drinking water pathway exists, the LLD of gamma isotopicanalysis may be used.E This is NOT a NUREG-0472 required value. It is based on EPA drinking water standards, which tieinto the NEI Groundwater Protection Initiative that was implemented at KPS on August 4, 2006.Rev. 20Page 3 of 3 October 15, 2013 FIGURE1lmRev. 20Page I of I October 15, 201300 FIGURE 200000000LLWC?bW W .mzmms ft"suna IT1 STS anI im SL no?.&LMCANN W MT fumy me"S aK O1WARLEGFJ~~ rUts Msa* m"N MLpL Uairi2r m no an IN s m m tllo% SU ru oC)Rev. 20October 15,2013Page 1 of I 00000S0000000000000Thi pae itenioall let ban0Thi pae itenionllylef blnk000000000000000000000 0S000Appendix EKewaunee Power StationDocumentation for Major Changes toRadioactive Waste Treatment Systems in 2013System abandonment evaluations per procedure OP-KW-DEC-SYC-00 1, System Evaluation and Categorization Attachment B -SSC Category Determination DocumentAndFSRC Review and Approval Documentation 0SSSSSSSSSSSSSS S0S0SSSSSSSSSS0SSSThis page intentionally left blank9 5SSSSSSSSSS0SSSSS*SSSS 00000S0S000000S00000000WoominIln' SSC Category Determination DocumentOPK -DCSY 0 -Atahmn B Pae1 f11.0 Doc Type: Report Revision No.: 0Sub Type: DECDocument Number (ID): SYS-07-DSERT Title: Blowdown Treatment

& Steam Generator Blowdown1.1 Brief description or reason for revision:

Not applicable for Rev 0Date: 10/09/2013 2.0 System Category (Check Appropriate):

NOTE: A SSC may be divided and have more than one category determination depending upon itsfunctional requirements.

I0] Available (Category A)Z Abandoned (Category X)Describe the assessed boundaries:

This is a partial functional abandonment of the Steam Generator Blowdown Treatment system.Parts of the system remaining available include:* Steam Generator Blowdown Tank to support Heating Boiler operation

One train of Steam Generator Blowdown Treatment Holdup/Monitor tanks/pumps willbemaintained to provide the ability to treat future waste water* SGBT Ion Exchange Pre-Filter

SGBT Ion Exchanger Post Filter BThe following instrument boundaries will be abandoned along with their respective sensing lines:P1-11172, TI-12142, TI-12143, P1-11173, TS-16232, TS-16218, DPI-11318, DPI-11325, DPI-11347, ES-19519, P1-11327, DPI-11349, ES-19521, P1-11329, T-2201S, TIS-73518, TIS-73526, P1-11898, Fl-73524, F-23070, T-22019, TIS-73519, TIS-73527, P1-11899, FI-73525, F-23071, LC-26801, DPI-11890, DPI-11892, DPI-11889, DPI-11891, FI-18354, DPI-11748, DPI-11749, P1-11887, DPI-11750, DPI-11751, P1-11888Form No. 732128 (Apr 2013)

, Dominion SSC Category Determination DocumentS.K -DCSY 0 -AtahetB Pae2o 23.0 Mark up the affected drawings using color coding to identify system category type andboundaries.

These drawings are to Include system, electrical one-line and distribution, and selectbuilding and Isometric drawings.

Related system drawings NOT Incorporated In the systemcategory require an explanation.

REFER to Step 2.7 for a list of drawings.

OPERM-203, Flow Diagram Main Aux Steam And Steam DumpAbandon:Blowdown lines from Steam Generator A, B to the Blowdown Heat Exchangers Blowdown drain lines from the MSIV's to the Steam Generator Blowdown TankOPERM-204-1, Flow Diagram Condensate

& Gland Seal SystemsAbandon:Three inch recovered condensate from the SGBT Ion Exchanger to MU-6OPERM-219, Flow Diagram Secondary Sampling SystemAbandon:Blowdown sample lines from Steam Generator A, B to secondary sampling systeminstrumentation including piping to the Sample RoomOPERM-368, Flow Diagram Steam Generator Blowdown Treatment SystemAbandon:SGBT Hold-up Tank 1A Including SGBT Hold-Up Tank 1A Transfer Pump and pipingSGBT Monitor Tank 1A including SGBT Monitor Tank 1A Transfer Pump and pipingSGBT Ion Exchanger 1ASGBT Ion Exchanger Post Filter 1ASGBT Heat Exchanger and filterAvailable:

SGBT Hold-up Tank 1B including SGBT Hold-Up Tank 18 Transfer Pump and piping.Boundary valves:BT-303A, 1.5 IN. VALVE-MANUAL-SGBT MONITOR TANK 1A DISCHARGE PUMP-DISCH BT-310, 2 IN. VALVE-MANUAL-CROSSOVER FOR SGBT HOLD-UP TANK TRANSFER PUMPSMD-4108, 1.5 IN. VALVE-MANUAL-ANAL INST PANEL TO SGBT HOLD UP TK 1BBT-131A, 2 IN. VALVE-MANUAL-SGBT HOLD-UP TANK 1A BLOWDOWN INLETBT-337A, 2 IN. VALVE-MANUAL-HOLD-UP TANK 1A MONITOR TANK RETURNBT-130, 2 IN. VALVE-MANUAL-FLASH TANK FILTER BLOWDOWN TO HOLD-UP TANKSBT-108, 2 IN. VALVE-MANUAL-SGBT FLASH TANK FILTER TO SGBT ION EXCHANGERS SGBT Monitor Tank 1B Including SGBT Monitor Tank 1B Transfer Pump and piping.Boundary valves:BT-l15A, 2 IN. VALVE-MANUAL-SGBT MONITOR TANK 1A BLOWDOWN INLETBT-210, 2 IN. VALVE-MANUAL-CROSSOVER FOR SGBT MONITOR TANK DISCHARGE PUMPSBT-203A, 1.5 IN. VALVE-MANUAL-SGBT MONITOR TANK 1A DISCHARGE PUMP-DISCH BT-230, 2 IN. VALVE-MANUAL-SGBT TO CVC MONITOR TANKSForm No. 732125 (Apr 2013)666I.I.00060000SS0100I.I.0S000000000000I.0 SDominion SSC Category Determination DocumentOPM DC-Y-0 -AtahetB Pg 4f1* SGBT Ion Exchange Pre-FilIter

) SGBT Ion Exchanger IB0) Boundary valves:BT-117B, 1.5 IN. VALVE-MANUAL-SGBT ION EXCHANGE IB TO IABT-111A, 1.5 IN. VALVE-MANUAL-SGBT ION EXCHANGER IA INLET*BT-117A, 1.5 IN. VALVE-MANUAL-SGBT ION EXCHANGE IA TO IB* DW-273, 1.5 IN. VALVE-MANUAL-DEMIN.

WTR. TO SGBT ION EXCH RESIN SLUICE LINESGBT Ion Exchange Post Filter IBS Boundary valves:*BT-114A, 1.5 IN. VALVE-MANUAL-SGBT ION EXCHANGER POST FILTER lA-BYPASS BT-113A, 1.5 IN. VALVE-MANUAL-SGBT ION EXCHANGER POST FILTER lA-OUTLET Steam Generator Blowdown Tank to support Heating Boiler operation Boundary valves:BT-100A, 3 IN. VALVE-MANUAL-BLOWDOWN TANK DRAIN TO WASTE HOLD-UP TANK*BT-100B, 2 IN. VALVE-MANUAL-BLOWDOWN TANK DRAIN TO WASTE HOLD-UP TANK*1 BT-62, 6 IN. VALVE-MANUAL-STEAM GEN BLOWDOWN TANK STEAM TO COND. lB*OPERM-436; Flow Diagram Steam Generator Blowdown System*Abandon:

Steam Generator Blowdown piping from Steam Generators A, B through SGB Heat Exchangers tothe 3"drain to 24"Auxillary Building Standpipe.

SGBT Pre Filter IA, 18*SGBT Polishing Filter 1A, 1BSGBT Recovery Ion Exchangers 1A, IB*Available:

Steam Generator Blowdown Tank to support Heating Boiler operation Boundary valves:BT-4A, 1 IN. VALVE-MANUAL-STM GEN IA BLOWDOWN AT BLOWDOWN TNKBT-4B, 1 IN. VALVE-MANUAL-STM GEN lB BLOWDOWN AT BLOWDOWN TNKBT-100A, 3 IN. VALVE-MANUAL-BLOWDOWN TANK DRAIN TO WASTE HOLD-UP TANKBT-100B, 2 IN. VALVE-MANUAL-BLOWDOWN TANK DRAIN TO WASTE HOLD-UP TANK*BT-50-1, 0 IN. VALVE-MANUAL-SGBT RECOVERY ION EXCHANGER

l BT-56-1, 0 IN. VALVE-MANUAL-SGBT RECOVERY ION EXCHANGER BT-1006, 3 IN. VALVE-MANUAL-SGBT DISCHARGE TO AUX BLDG STANDPIPE

OPERM-605-2, Flow Diagram Heating SystemAvailable:

Heating Boiler Mud Drum Continuous Blowdown to Blowdown Tank0~Form No. 732125 (Apr 2013)0 SDominlon" SSC Category Determination Document0* I EC-YC001

-.tah i B ae4-f1E-256, Circuit Diagram 480V MCC 1-32D, 1-35C, 1-35F, 1-42D, 1-45C, & 1-45FAbandoned from the electrical breaker out:MCC 1-32D (C3) SGBT Hold-Up Tank 1A Transfer PumpMCC 1-32D (C4) SGBT Monitor Tank 1A Discharge PumpAvailable:

MCC 1-420 (C3) SGBT Hold-Up Tank 1B Transfer PumpMCC 1-42D (C4) SGBT Monitor Tank 1B Discharge PumpE-258, Circuit Diagram 480V MCC 1-52A, 1-52F, & 1-52BAbandoned from the electrical breaker out:MCC 1-52B (D4) Steam Generator 1A Blowdown Isolation MV lAl BT-2A/32077 E-3075, Circuit Diagram 480V MCC 1-62JAbandoned from the electrical breaker out:MCC 1-62J (2JM) Steam Generator 1B Blowdown Iso MV 1B1 BT-2B/32079 E-844, Wiring Diagram DC Auxiliary

& Emergency ACAbandoned from the electrical breaker out:BRA-104 Circuit 21, To Local Mtr Str 1-428 BT-3B/MV32080 S/G B Blowdown Isolation Valve B2BRB-104 Circuit 21, To Local Mtr Str 1-427 BT-3A/MV32078 S/G A Blowdown Isolation Valve A24.0 Evaluation (Basis for choosing category type):Purpose/Function The Steam Generator Blowdown System assists In maintaining secondary chemistry of theSteam Generators and the Main Steam System by removing contaminants.

Also, the SGBSystem provides the means to monitor SG tube integrity and has the ability to transferradioactive contaminated water from the SGs to the Steam Generator BlowdownTreatment System following a Steam Generator tube rupture.The SGB System operates in three Modes:Mode INormal operation is from plant startup to 50% power and 50% power to plant shutdown.

The water removed from the steam generators Is discharged to Lake Michigan via theAuxiliary Building standpipe.

Mode IINormal operation is from 50% to 100% power. The water removed from the SGs isprocessed through heat exchangers and filters before returning to the condenser.

Mode IIIEmergency operation, following a Steam Generator tube rupture, is to transfer theradioactive contaminated water to the SGBT System.Form No. 732125 (Apr 2013)46666I.60006S00I.000000S000I000SSS0 0* 00S0000SS000S0S00Inlet,SSC Category Determination Document0PK -E-Y-0 -Atahmn B ae5.f1The Steam Generator Blowdown Treatment System processes radioactive contaminated water. During normal plant operation, radioactive water from the Waste Disposal System isperiodically transferred to the SGBT System for processing.

In an emergency, SteamGenerator tube rupture, SGB System is aligned to Mode I1i. SGBT System pumps theradioactive water through filters and ion exchangers to remove contaminants.

When thewater is processed sufficiently, it Is discharged to Lake Michigan via the Auxiliary BuildingStandpipe.

Basis for CategoryOn February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed thecertification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii).

Therefore the 10 CFR Part 50 license no longer authorizes KPS to operatethe reactor or emplace or retain fuel in the reactor vessel, as specified in 10 CFRS0.82(a)(2).

With Irradiated fuel being stored In the SFP and the ISFSI, the reactor, RCS and secondary system are no longer in operation and have no function related to the'storage of theIrradiated fuel. Therefore, the postulated accidents involving failure or malfunction of thereactor, RCS or secondary system are no longer applicable.

The analyzed accident andoperational event applicable to KPS in the permanently shut down and defueled condition is a fuel handling accident (FHA) in the auxiliary building.

The Steam Generator Blowdown Treatment system does perform a function or providesupport for some of the following items (they are annotated for the ones that apply):1. To prevent or mitigate the consequences of a design basis accident of a permanently defueled plant.2. Fuel Handling Accident as defined In Updated Safety Analysis Report (USAR).3. For safe storage and handlingof radioactive waste or spent fuel.Supports draining and processing of systems In the Auxiliary building.

One train is beingmaintained available to support draining.

4. To support Technical Specifications, License Requirements, Design Basis, permits,regulatory requirements, insurance requirements, or other commitments.

Provide supportof the Spent Fuel Safety Management Program.Form No. 732125 (Apr 2013)

SDominion' SSC Category Determination DocumentS.I OPM DC SYC0 -tah etB Pg. f15. To support the execution of plans and programs of Kewaunee Power Station.6. Support day to day operations in the decommissioning plant.Supports Heating Boiler operations and processing of waste water. These portions arebeing maintained to support these.7. Support plant decommissioning efforts.Supports draining of systems in the Auxiliary building.

One train is being maintained available to support draining.

Regulatory ImpactUpdated Safety Analysis Report (USAR)The Steam Generator Blowdown Treatment system is mentioned in the following chapters/sections:

Section 5.3.1.1 Containment Isolation ValvesThere are two SGB System Containment vessel penetrations denoted as "tube barrier andpressurized system:"

8N and 8S. The associated SGB valves are:Inside of Containment:

BT-2A(B),

BT-2A(B)-l Outside of Containment:

BT-3A(B)Chapter 6.5 Leakage Detection And Provisions For The Primary and Auxiliary Coolant LoopsR-19 monitors the liquid phase of the secondary side of the steam generator forradiation, which would Indicate a primary-to-secondary system leak, providing backupInformation to that of the condenser air ejector gas radiation monitor.

Samples from thebottom of each of the two steam generators are mixed to a common header and thecommon sample is continuously monitored by a scintillation counter and holdup tankassembly.

Upon indication of a high-radiation level, each steam generator is individually sampled in order to determine the source. This sampling sequence is achieved by manuallyselecting the desired steam generator to be monitored and allotting sufficient time forsample equilibrium to be established (approximately I minute).

At the alarm setpoint forhigh radiation level, steam generator blowdown Is automatically Isolated.

A high radiation alarm actuated by R-19 (the steam generator blowdown monitor) or R-15(the air ejector activity monitor)

Initiates closure of the Isolation valves in the blowdownlines and sample lines.Chapter 9.4 Sampling SystemSteam generator blowdown samples can be taken either in the sample room or at thesecondary system analytical and sampling panel. Leakage and drainage resulting from thesampling operations are collected and drained to tanks in the Waste Disposal System.Form No. 732125 (Apr 2013)IIIII006606000I.000S00000S00S0000000000000 0** Domil00000000S00000000000000nionSSC Category Determination Document**K -DCSY 0 -Atahmn B Pae7. f1Section 10A.6.5 Steam Generator BlowdownTable 10A.4-5 Needed Equipment List For Blowdown Line BreakChapter 11: Waste Disposal and Radiation Protection SystemWaste from the sludge interceptor tank is pumped by the sludge Interceptor pump throughsludge Interceptor filters (4) Into the waste holdup tank. Waste from the hot samplestation and hot chemical laboratory is also drained to the waste holdup tank. Thetank's contents are pumped by the waste evaporator feed pump to the BlowdownTreatment System for processing and eventual release to the environment.

Section 11.1.2.2 Steam Generator Blowdown SystemSection 11.1.2.18 SGB Heat Exchangers Four SGB heliflow heat exchangers are used to cool normal flow blowdown from eachsteam generator to 100F. Blowdown then Is directed through a high pressure drop flowcontrol valve and then a pressure regulating valve that reduces the pressure to 40 psigprior to discharge to the Auxiliary Building Standpipe.

Section 11.1.2.19 SGBT Heat Exchanger The SGBT heat exchanger is used to cool liquid from the blowdown tank to below 120°F toallow processing through the SGBT ion exchanger.

Section 11.1.2.20 SGBT Flash Tank FiltersThe SGBT filters remove particulate matter from the fluid being pumped, prior to itspassing to the SGBT holdup tanks or ion exchangers.

The filter is constructed of stainless steel materials.

Section 11.1.2.21 SGBT Monitor TanksThe SGBT monitor tanks serve as a collection point for liqulds processed through theSGBT ion exchanger.

The contents are sampled at this point for an activity record beforedischarge through the Waste Disposal System radiation monitor to the circulating waterdischarge.

The tanks are all-welded stainless steel construction.

Section 11.1.2.22 SGBT Holdup TankThe SGBT holdup tanks serve as a collection point for cooled and filtered blowdown liquidfrom the SGB tank before processing through the SGBT Ion exchanger or for storage ofliquid wastes transferred from the waste holdup tank prior to being processed through theSGBT ion exchangers.

The tanks are of all welded stainless steel construction.

Section 11.1.2.23 SGBT Ion Exchanger Pre-Filter The SGBT ion exchanger pre-filter reduces the amount of Ion exchanger resin fouling.

Thefilter housing is constructed of stainless steel.Form No. 732125 (Apt 2013)

SDominion' SSC Category Determination DocumentI~ O KWDCS Y 0 -Atahen.6ag f1 2Section 11.1.2.24 SGBT Ion Exchangers Two flushable ion exchangers, capable of being operated in series or parallel, are provided.

Each vessel Is of all-welded stainless steel construction with a stainless steel resin retention element.Section 11.1.2.25 SGBT Ion Exchanger Post FiltersThe SGBT Ion exchanger post filters remove resin fines from the treated blowdown stream.The filter housings are constructed of stainless steel.Section 11.1.2.26 PumpsThe wetted surfaces of all pumps are stainless steel or other materials of equivalent corrosion resistance.

Section 11.1.2.27 PipingPiping carrying liquid wastes is stainless steel, while all gas piping is carbon steel. Steamgenerator blowdown piping is carbon steel to the point where this system joins the liquidwastes transferred from the waste holdup tank. Piping connections are welded, exceptwhere flanged connections are necessary to facilitate equipment maintenance.

Section 11.1.2.28 ValvesAll valves exposed to gases are carbon steel. Those exposed to liquids are stainless steel.All valves have stem leakage control.

Globe valves are Installed with flow over the seatswhen such an arrangement reduces the possibility of leakage.Isolation valves are provided to Isolate each piece of equipment for maintenance, to directthe flow of waste through the system, and to Isolate storage tanks for radioactive decay.Relief valves are provided for tanks containing radioactive wastes to preventoverpressurization by improper operation or component malfunction.

Tanks containing wastes, which are normally free of gaseous activity, are vented locally.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(1),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed thecertification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(1i).

Therefore the 10 CFR Part 50 license no longer authorizes KPS to operatethe reactor or emplace or retain fuel In the reactor vessel, as specified In 10 CFR50.82(a)(2).

The USAR will be revised to address to keep functions associated with theavailable equipment above.Form No. 732125 (Apr 2013)

SDominion SSC*Technical Specifications Reviewed all sections for applicability to Stcfollowing sections were applicable:

Section 3.4.17 Steam Generator (SG) Tube I*Applicability:

Modes, 1, 2, 3, and 4.0Section 3.6.3 Containment Isolation ValvesApplicability:

Modes, 1, 2, 3, and 4.* On February 25, 2013, DEK submitted a ceri*operations pursuant to 10 CFR 50.82(a)(1)(i cease power operation of KPS on May 7, 20certification for permanent removal of fuel50.82(a)(1)(11).

Therefore the 10 CFR Part 5S0the reactor or emplace or retain fuel in the*50.82(a)(2).

Therefore, the LCOs (and assoc*only apply in Modes 1 thru 6, are no longerOffsite Dose Calculation Manual (ODCM):* Licensee Initiated major changes to the radi*solid) shall be reported to the Commission Ithe period in which the evaluation was revishall contain:*a. A summary of the evaluation that led to t*made in accordance with 10 CFR Part 50.59b. Sufficient information to totally support t*additional or supplemental information, 0 c. A description of the equipment, componc*interfaces with other plant systems,d. An evaluation of the change, which showmaterials in liquid and gaseous effluents an*from those previously predicted in the licene. An evaluation of the change, which showIndividuals In the UNRESTRICTED AREA and*from those previously estimated in the licer*thereto,

f. A comparison of the predicted releases ofgaseous effluents and in solid waste to thethe changes are to be made;000Category Determination DocumentOP. W-ECS Y-0 -I Atahmn B ae9f1ham Generator Blowdown Treatment.

Thentegritytification of permanent cessation of power), stating that DEK has decided to permanently

'13. On May 15, 2013 the NRC docketed thefrom the reactor vessel pursuant to 10 CFR0 license no longer authorizes KPS to operatereactor vessel, as specified in 10 CFRclated Surveillance Requirements (SRs)) thatapplicable.

loactive waste systems (liquid, gaseous andn the Radioactive Effluent Release Report forewed by FSRC. The discussion of each change:he determination that the change could behe reason for the change without benefit ofents and processes involved and the's the predicted releases of radioactive d/or quantity of solid waste that differse application and amendments thereto,s the expected maximum exposures toto the general population that differnse application and amendments radioactive materials In liquid andactual releases for the period in whichForm No. 732125 (Apr 2013)

SDominion SSC Category Determination DocumentS*I OPK -E-Y *0 -. Atah etB Pae1 f1g. An estimate of the exposure to plant operating personnel as a result of the change,andh. Documentation of the fact that the change was reviewed and found acceptable by theFSRC.Changes shall become effective upon review and acceptance by the FSRC.The USAR and ODCM revisions will be revised to address requirements following cessation of power operation.

Other Related documents The EAL Technical Bases Document discusses SGB sampling, etc. in a number of places andwill require revision.

Plant ImpactNo changes are required to SSCs, procedures,

programs, processes, etc.There is no Impact on any temporary changes that are active as of 12-19-2013.

The Drawing Control Team did not Identify any outstanding drawing changes that requireddisposition as a result of system abandonment.

EAL, USAR, and ODCM will require changes as listed above in Regulatory Impact.5.0 Special conditions to support categorization(s):

None6.0 Assumptions/Open Items to be validated or dispositioned:

OPEN ITEMS: EAL, USAR, and ODCM will require changes as listed above in Regulatory Impact.7.0 Expected duration for SSC category if NOT ABANDONED:

Available SSCs In the Steam Generator Blowdown Treatment system are expected toremain available until plant demolition.

Form No. 732125 (Apt 2013)IIIIIIIII606060000I.I.S00000I0SSSSSSSSSSS0 00000000000000000000000000000000000000000' Dominion SSC Category E8.0 PREPARE and ATTACH the following documents:

Completed 10 CFR 50.59 Screening or Evaluation, if required* Proposed DUs for appropriate drawings9.0 Technical Concurrence:

)etermination Document71C ~ ~ II -Sahnn ie1 l1Type Of Review Name (Print) DateEngineering UAve Itk(/AVE IZ -12Z "3Type Of Review Name ( rint) Approval Signature DateFire Protection Type Of Review Name (Print) Appr vsignature I DateSecurity

__ _ __ _ __ _ __ _Type Of Review Name (Print) Approval~iynature DateType Of Review Name (Print) p oval Sign ure DateRadiation Protection Dole? 4. s/Type Of Review Name (Print) Appro Signature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature DateForm No. 732125 (Apr 2013)

' ominio"SSC Category Determination Document*PK -E -Y tah etBSae1 f110.0 Review and Approval:

Prepared By (Print/Sign)

Reviewed By (Screen Qual.) (Print/Sign)

Date12 1"2-DateDafe---Datea.2 -/ q-/e?DateNulear Licensi (Print/Sign)

Concurrence by DSERT Coordinator (Print/SI n)FSRC (Print/Sign),

if requiredFSRC Meeting Number:00000100.000000001000000000000000000Form No. 732125 (Apr 2013) 000000000000000sldkmhnýo SSC Category Determination DocumentOPK -DCSY 0 -Atahmn B PaeI0f21.0 Doc Type: ReportSub Type: DECDocument Number (ID): SYS-18-DSERT Title: Reactor Building Ventilation Revision No.: 0Date: 5-14-2013 1.1 Brief description or reason for revision:

Not applicable for Revision 0.2.0 System Category (Check Appropriate):

NOTE: A SSC may be divided and have more than one category determination depending upon itsfunctional requirements.

X Available (Category A)X Abandoned (Category X)Describe the assessed boundaries:

This Is a partial functional abandonment of System 18 Reactor Building Ventilation System (RBV)including the 1B, 1C, 1D Containment Fan Coil Units (CFCU), charcoal filter units, fans, heatingcoils, associated

ductwork, dampers and instrumentation except as indicated below. Thefollowing system functions shall be maintained available.

The ability to vent pressure from containment through the 2" vent to Aux Buildingexhaust.The service water system supports the Reactor Building Ventilation System CFCUs andCharcoal Filter Units fire suppression spray manifolds.

The service water system shall beisolated and drained to the RBV System including 1A CFCU though this unit could berefilled and operated as desired.Service Water supports the RBV system and shall be isolated from the containment Fan Coil Unitsas Indicated in Section 3.Service water piping to fire spray manifolds In Containment Purge Exhaust Filter housingdownstream of SW-1051 shall be Isolated.

After the charcoal is removed from the filters.Heating Steam supports the RBV System and shall be isolated from the Containment Purge VentSupply fan housing as Indicated in Section 3.Form No. 732125 (Apr 2013)

WDominion SSC Category Determination Document6* K -D C SY Att ch en 0 P g ý2The 480 volt system supports the RBV system and shall be isolated as indicated in Section 3.The instrument air system supports the RBV system. The instrument air system shall be isolatedfrom the RBV system to individual components as indicated on in Section 3.The following instrument boundaries were abandoned along with their respective sensing lines,thermo wells etc:FE-27083, P1-11405, FI-18237, P1-11403, FE-27084, F1-18238, P1-11404, P1-11406, TE-13070, TE-15128, TE-15188, TE-13071, TE-15129, TE-15130,

TE13072, TE-13074, TE-15184, TE-13168,

TE13169, TE-13170, TE-13171, TE-13172, TE-13173,

TE13073, TE-15185, TE-15186, TE-15190,

TE15191, TE-19192, TE-15080, TE-15081, DPI-11712, DPI-11713, DPI-11714, DPI-11715, DPI-11716, DPI-11717, DPS-16403, P-21100, P-21101, P-21102, P-21105, P-21117, P-21118, P-21119,P-21122, P-21132, P-21133, T-22051, T-22052, T61203, T61205, F-23061, F-23063, F-23065, F-23067 FE-27050, FE-27051, FE-27052, FE-27053, FE-27054, FE-27055, FE-27056, FE-27057, PS-16145, PS-16146, PS-16149, DPI-11407, F1-18239, F1-18240 and P1-11012The following dampers act as boundary dampers:TAV-11 Turbine Building Air Damper to RBV SystemCD-34187 Containment Fan Coil Unit B to Reactor Coolant Pump Vault Damper3.0 Mark up the affected drawings using color coding to identify system category type andboundaries.

These drawings are to include system, electrical one-line and distribution, and selectbuilding and isometric drawings.

Related system drawings NOT Incorporated in the systemcategory require an explanation.

REFER to Step 2.7 for a list of drawings.

OPERM-601 Abandon:Containment Purge and Vent Air Supply fanContainment Supply Fan Preheat CoilContainment Supply Fan Reheat CoilContainment Purge and Vent Air Supply Ductwork up to TAV-11OPERM-602 Reactor and Shield Building Ventilation Abandon:Containment Purge exhaust System including all ductwork and dampersContainment Vent Exhaust fanContainment Purge exhaust fanContainment Purge Exhaust Filter AssemblyContainment Exhaust Filter AssemblyForm No. 732125 (Apr 2013)0000000I.000000000000000000000000000000S0 0° p00S0000S000*00000000Domiflnon' SSC Category Determination Document0* I DEC SYC0 -AtahetB pg Bf2Containment Purge and Vent Air Supply from OPERM-601 through RBV-2 including allductwork and dampers upstream and downstream Containment Isolation Valves RBV-1, RBV-2, RBV-3, and RBV-4Containment Vacuum Breakers VB-1OA, VB-10B, VB-11A, and VB-11BReactor Gab & Neutron Detector Cooling Fan AReactor Gab & Neutron Detector Cooling Fan BReactor Gab & Neutron Detector Cooling ductwork and dampersContainment Fan Coil Unit BContainment Fan Coil Unit CContainment Fan Coil Unit DContainment Fan Coil Unit ductwork and dampers up to damper CD-34187.

Control Rod Drive Cooling Fan AControl Rod Drive Cooling fan BControl Rod Drive Cooling ductwork and dampersReactor Support Cooling Fan AReactor Support Cooling Fan BReactor Support Cooling Electric Heater AReactor Support Cooling Electric Heater BReactor Support Cooling ductwork and dampersContainment Dome Fan 1BContainment dome fan ductwork and heatersAvailable:

Containment Fan Coil Unit A shall remain available along with its associated ductwork tothe reactor coolant pump vault 1B, reactor building 606' and 592' elevations, CD-34187and RBV-150A.

CD-34187 shall be available to open as a check damper but the openassist shall be abandon.Containment Dome Vent Fan A will be maintained available.

OPERM-605-1 Flow Diagram Heating SteamAbandon:Containment Purge and Vent Unit Preheat and Reheat coilsHS-320 Manual Isolation to Containment Purge and Vent Unit Preheat and Reheat coils toHS-5325A, HS-5325B, HS-5321A, HS-5321B, preheat and reheat trap outlet valves, and HS-6326 Manual vacuum breaker valve.OPERM-606 Flow Diagram Air Conditioning Cooling Water pipingForm No. 732125 (Apr 2013) ominion' SSC Category Determination DocumentOPK -DCSY 0 -Atahmn B Pae4.f2Abandon:Service water piping to fire spray manifolds in Containment Purge Exhaust Filter housingdownstream of SW-1051.

After the charcoal Is removed from the filtersOPERM-403 Flow Diagram Reactor Building Vent. System Post LOCA Hydrogen ControlAbandon:2" Containment Supply BlowerReactor Building Vent System Post LOCA Hydrogen Control piping and valvesAvailable:

Vent flow path through LOCA-2B, LOCA-100B to Aux Building Exhaust up to LOCA-3B andLOCA-10B.

OPERM-213-2 Flow Diagram Station and Instrument Air SystemAbandon:IA-31120 to CV31120, SW-0904B, including positioner air to S/CV-35007 and Pos 37075on drawing OPERM-213-5 OPERM-213-5 Flow Diagram Station and Instrument Air SystemAbandon:IA-31386-1 Manual valve to LOCA-3AIA-31386-2 Manual valve to LOCA-3A/AS-19579 IA-31387 Manual Isolation to LOCA-10AIA-31388-1 Manual Isolation to LOCA-3BIA-31388-2 Manual Isolation to LOCA-3B/AS-19583 IA-31389 Manual Isolation to LOCA-1OBIA-31119 Manual Isolation to CV-31119, SW904D, Including positioner air to S/CV-35007 and Pos 37031 on drawing OPERM-213-2 IA-35007 manual Isolation to S/CV-35007 OPERM-213-8 Flow Diagram Station and Instrument Air SystemAbandon:iA-156 downstream to CD-34189, CD-34188, CD34132/RBV1SOC, CD34133/RBV15OD Including IA piping, valves, regulators and associated accumulators.

IA-108 downstream to CD-34130/RBV150A, CD-34131/RBV15OB,

CD34186, CD34187, SW-901A-1, SW-901B-1, SW-910A, SW-910B, SW-911AB, SW-914A, SW-914B including IApiping, valves, regulators and associated accumulators.

IA-131 downstream to SW-901C-1, SW-901D-1, SW-910C, SW-910D, SW-911CD, SW-914C,SW-914DIA-155 Manual Isolation to LOCA-201A IA-153 Manual Isolation to RBV-2IA-152 Manual Isolation to RBV-3IA-167 Manual Isolation to LOCA-201B Form No. 732125 (Apr 2013)000006000S0000000000000000 YDominion SSC Category Determination Document0000000S0S000S0S0S.I OPK -E*Y-0 tahetB Pg f2OPERM-213-6 Flow Diagram Station and Instrument Air SystemAbandon:IA-31340 Manual Isolation of VB-11BIA-31339 Manual Isolation of VB-11AIA-31724 Manual isolation to LOCA-IOOA IA-31125 Manual Isolation of RBV-1IA-31123 Manual Isolation of RBV-4IA-1505 Manual Isolation to RBV-5, RBV-6, RBV-7, RBV-10, RBV-20, RBV-21, TAV-12IA-1522 Manual Isolation to VB1OA, VB10B and associated accumulators and valvesIA-1550 Manual Instrument air header Isolation to manual dilution to containment IA-1630 Manual Instrument Air Isolation to Post LOCA H2 ControlOPERM-213-7 Flow Diagram Station and Instrument Air SystemAbandon:IA-34030 Manual Isolation to TAV1OIA-34034 Manual Isolation toTAV-11IA-1339 Manual Isolation to Purge Supply Unit Temperature ControlOPERM-547 Flow Diagram Service water System Containment CoolingAvailable:

Service Water piping for CFCU A through Shroud Cooling Bypass valve SW-901A-1 Abandon:1B, IC, ID Containment Fan Coil Unit coils1A, 1B,1C,1D Shroud Cooling coilsCFCU B Service Water piping and components up to but not Including SW-9OOB, SW-910A,SW-914A, SW-903B, SW-904B and SW-905B.CFCU C Service Water piping and components up to but not Including SW-900C, SW-903Cand SW-905C.CFCU D Service Water piping and components up to but not including SW-900D, SW-903D, SW-904D and SW-905D.E-257 Circuit Diagram 480 Volt MCC 1-35E & 1-45EAbandon:Breaker MCC45E-D4 to 1-105 Containment Purge and Vent Supply Fan MotorBreaker MCC35E-C5 to 1-313 Containment Purge Exhaust fanBreaker MCC35E-A3 to 1-587 Containment vent Exhaust fanE-889 Lighting panels RPB1, RPB2, RPB3, RPB4, RPBS, RPB6Abandon:Breaker RPB6-18 to 1-1079 Containment 2" Blower MotorE-235 Circuit Diagram 480V Switchgear Safeguard BusesAbandon:Breaker 15104 to 1-156 Containment FCU B MotorForm No. 732125 (Apr 2013)

SDominion SSC Category Determination DocumentI* O KWDC SYC *0 -AtahetB Pg Sf2Breaker 16105 to 1-121 Containment FCU C MotorBreaker 16104 to 1-157 Containment FCU D MotorAvailable:

Breaker 15105 to 1-120 Containment FCU A MotorE-251 Circuit Diagram 480V MCC 1-32EAbandon:Breaker MCC32E-D5 to 1-327 Reactor Vessel Support Cooling Fan ABreaker MCC32E-D4 to 1-329 Reactor Vessel Gap and Neutron Detector Cooling Fah ABreaker MCC32E-CS to 1-337 Control Rod Drive Cooling Fan ABreaker MCC32E-B5 to 1-588 Reactor Vessel Support Heater AE-252 Circuit Diagram 480V MCC 1-42EAbandon:Breaker MCC42E-A2 to 1-328 Reactor Vessel Support Cooling Fan BBreaker MCC42E-B1 to 1-330 Reactor Vessel Gap and Neutron Detector Cooling Fan BBreaker MCC42E-E5 to 1-338 Control Rod Drive Cooling Fan BBreaker MCC42E-A5 to 1-589 Reactor Vessel Support Heater BE-258 Circuit Diagram 480V 1-52A, 1-52F, 1-52BAbandon:Breaker MCC52B-G5 to 1-672, SA-7003A Hydrogen Dilution to Containment Breaker MCC52B-C2 to 1-670, LOCA 2A Post LOCA Containment VentMaintain:

Breaker MCC52B-A3 to 1-583 Containment dome Fan AE-261 Circuit Diagram 480V 1-62A, 1-52D, 1-5262, 1-62BAbandon:Breaker MCC62B-C5 to 1-673, SA-7003B Hydrogen Dilution to Containment, Breaker MCC62B-C4 to 1-671, LOCA-2B Post LOCA Containment Vent Note: The power Isto be abandoned with the valve in the open position to maintain a containment ventflow path.Breaker MCC62B-A2 to 1-584 Containment Dome Fan BE-259 Circuit Diagram 480V MCC1-62D, 1-62EAbandonBreaker MCC62E-B1 to 1-396, SW-903C MOVBreaker MCC62E-B2 to 1-397, SW-903D MOVE-260 Circuit Diagram 480V MCC 1-52C, 1-52E, 1-62CAbandon:Breaker MCC52E-G1 to 1-395, SW-903B MOVBreaker MCC52E-F5 to 1-394, SW-903A MOV Note: The power Is to be abandoned withForm No. 732125 (Apr 2013)000000000000000000000000000000000000000000

Do000* 4.0 m000000004.0vau0000000000000minloSSC Categoty Determination DocumentOP.K -DEC SY-0 -Atahet8 Pg Sf2the valve In the open position to maintain a Service Water flow path to CFCU A.ation (Basis for choosing category type):Purpose/Function The RBV System shall provide cooling and ventilation to the Containment to ensure thattemperature,

pressure, and air quality are maintained within acceptable limits to supportoperability of equipment and safety and comfort of personnel during refueling andmaintenance activities.

The RBV CFCU Subsystem shall provide Post-LOCA cooling to the Containment tocontrol temperature and pressure within design basis requirements.

The RBV CFCU Emergency Discharge Dampers shall automatically open when containment pressure exceeds 3.85 psig.The RBV Purge and Vent Subsystem four CIVs shall automatically close upon receipt ofa containment isolation signal.The Containment Vacuum Relief Subsystem shall prevent damage to the Containment vessel from negative pressure Inside the Containment.

The Reactor Gap and Neutron Detector Cooling Subsystem shall provide a pressureboundary function for the Incore Support Column and Reactor Cavity.RBV CFCUs A and B support safe shutdown following an Appendix R Fire Event in theDedicated Zone. CFCUs C and D support safe shutdown following a fire In the Alternate Zone.The RBV Post-LOCA Hydrogen Control Subsystem shall provide a means ofpreventing hydrogen concentration in containment from exceeding 3.5 percent.The RBV CFCU Subsystem shall provide cooling to the Containment general space andthe RC Pump Vaults so that the Containment environment is maintained within the limitsof acceptability to support operability of equipment required to control reactor operation.

The CRD Shroud Cooling Subsystem shall provide sufficient cooling to the CRDM duringnormal operations to support proper functioning of the components.

The Reactor Gap and Neutron Detector Cooling Subsystem shall provide sufficient Form No. 732125 (Apr 2013)

SDominlon° SSC Category Determination DocumentrS.KWDCSY 0 -Atahmn 8 Pae8 f2cooling to limit the maximum temperature of the concrete surrounding the reactor vesseland keep the neutron detectors cool during normal operations.

The Reactor Support Cooling Subsystem shall provide sufficient cooling to maintain theproper temperature profile in the reactor vessel steel at the supports, shims, shoes andsupporting steel.The Purge and Vent Subsystem shall provide comfort cooling and protection from airborneradiation for personnel entering the Containment, as well as a controlled containment exhaust air flow path.The SG Channel HeadVentilation Subsystem shall provide an air flow path and filtration to prevent condensation inside the SG heads and to control the spread of airborne contaminants.

Basis for CategoryOn February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(1),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii),

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

The basis for the abandoned category for the Reactor Building Ventilation (RBV) isdetermined by the following criteria:

The RBV is not required:

1. To prevent or mitigate the consequences of a design basis accident of a permanently defueled plant.2. To prevent or mitigate the consequences of a Fuel Handling Accident or Gas Decay Tankrupture.3. For safe storage and handling of radioactive waste or spent fuel.4. To support Technical Specifications, License Requirements, Design Basis, permits,regulatory requirements, insurance requirements, or other commitments.

Provide supportof the Spent Fuel Safety Management

Program, or radiological effluent monitoring.

5. To support the execution of plans and programs of Kewaunee Power Station.6. Support day to day operations In the decommissioning plant.7. Support plant decommissioning efforts.Regulatory ImpactForm No. 732125 (Apr 2013)000S0000000000000000000000000000000000 0000 om000000000000000000nion"TECHNICAL SPECIFICATIONS 3.6 CONTAINMENT SYSTEMSSSC Category Determination DocumentOPK -E-Y*0 -. Atahmn B .ae9f23.6.6 Containment Spray and Cooling SystemsLCO 3.6.6 Two containment spray trains and two containment cooling trains shallbe OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.SR 3.6.6.2 Operate each containment cooling train fan unit for > 15 minutes.SR 3.6.6.3 Verify each containment cooling train cooling water flow rate issufficient to remove the assumed heat load.SR 3.6.6.7 Verify each containment cooling train starts automatically on an actualor simulated actuation signal.B 3.6 CONTAINMENT SYSTEMSB 3.6.6 Containment Spray and Cooling SystemsThe Containment Spray and Containment Cooling systems provide containment atmosphere cooling to limit post accident pressure and temperature in containment to lessthan the design values. Reduction of containment pressure and the Iodine removalcapability of the spray reduces the release of fission product radioactivity fromcontainment to the environment, in the event of a Design Basis Accident (DBA), to withinlimits. The Containment Spray and Containment Cooling systems are designed to meet therequirements of USAR, General Design Criteria (GDC) 52, "Containment Heat RemovalSystems,"

GDC 58, "Inspection of Containment Pressure-Reducing Systems,"

GDC 59,"Testing of Containment Pressure-Reducing Systems Components,"

GDC 60, "Testing ofinternal Containment Spray System,"

and GDC 61, "Testing of Operational Sequence ofContainment Pressure-Reducing Systems" (Ref. 1)Containment Cooling SystemTwo trains of containment

cooling, each of sufficient capacity to supply 100% of the designcooling requirement, are provided.

Each train of two fan-coil units Is supplied with coolingwater from a separate train of service water. Each pair is connected to ductwork whichdistributes the cool air to the reactor coolant pump vaults, the ring duct above therefueling floor, the intake of the Reactor Gap and Neutron Detector Cooling Subsystem, and Various other floor levels in the Reactor Containment Vessel.The Containment Spray System and Containment Cooling System limit the temperature and pressure that could be experienced following a DBA. The limiting DBAs considered arethe loss of coolant accident (LOCA) and the main steam line break (MSLB).In MODES 1, 2, 3, and 4, a release of radioactive material to containment and an increase incontainment pressure and temperature could occur requiring the operation of thecontainment spray trains and containment cooling trains.In MODES 5 and 6, the probability and consequences of a release are reduced due to thepressure and temperature limitations of these MODES. Thus, the Containment SpraySystem and the Containment Cooling System are not required to be OPERABLE in MODES 5and 6.Form No. 732125 (Apr 2013)

' Dominion SSC Category Determination DocumentI PK-E C-Y 0 Ata chen B Pag 10o.23.6.9 Vacuum Relief ValvesLCO 3.6.9 Two vacuum relief lines shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.SR 3.6.9.1 Perform a functional test of each vacuum relief valve and verify the valve opensat a simulated containment vacuum of <0.5 psig vacuum. 18 monthsSR 3.6.9.2 Perform a CHANNEL CALIBRATION on the containment vacuum breakerdifferential pressure channels.

18 monthsB 3.6.9 Vacuum Relief ValvesThe purpose of the vacuum relief lines is to protect the containment vessel againstnegative pressure (i.e., a lower pressure inside than outside).

Excessive negative pressureinside containment can occur If there is an inadvertent actuation of containment coolingfeatures, such as the Containment Spray System. Multiple equipment failures or humanerrors are necessary to cause Inadvertent actuation of these systems.

The containment pressure vessel contains two 100% vacuum relief lines that protect the containment fromexcessive external loading.The containment was designed for an external pressure load equivalent to 0.8 psig. TheInadvertent actuation of the containment cooling features was analyzed to determine theresulting reduction In containment pressure.

The initial pressure condition used in thisanalysis was 14.7 psia (0.0 psig). This resulted in a minimum pressure Inside containment of13.917 psia (-0.783 psig), which is less than the design load.The vacuum relief valves must also perform the containment isolation function in acontainment high pressure event. For this reason, the system is designed to take the fullcontainment positive design pressure and the environmental conditions In MODES 1, 2, 3, and 4, the containment cooling features, such as the Containment SpraySystem, are required to be OPERABLE.

Excessive negative pressure inside containment could occur whenever these systems are required to be OPERABLE due to inadvertent actuation of these systems.

Therefore, the vacuum relief lines are required to be OPERABLEin MODES 1, 2, 3, and 4 to mitigate the effects of Inadvertent actuation of the Containment Spray System or Containment Cooling System.The Containment Spray System and Containment Cooling System are not required to beOPERABLE in MODES 5 and 6. Therefore, maintaining OPERABLE vacuum relief valves is notrequired in MODE 5 or 6.3.3 INSTRUMENTATION 3.3.6 Containment Purge and Vent Isolation Instrumentation LCO 3.3.6 The Containment Purge and Vent Isolation instrumentation for eachFunction in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6-1.B 3.3.6 Containment Purge and Vent Isolation Instrumentation Containment purge and vent Isolation Instrumentation closes the containment Isolation valves in the Containment Vessel Air Handling System, consisting of the Containment AirCooling and Containment Purge and Vent Systems.

This action isolates the containment atmosphere from the environment to minimize releases of radioactivity in the event of anForm No. 732125 (Apr 2013)0I.000SS000SSSSSSSSSSSSSSSSSSSSSSSSSSSSSSS 00S* 00000\000000000000000InlonSSC Category Determination DocumentePK -E -Y Atahmn B Pae1.f2accident.

The Containment Air Cooling System may be in use during reactor operation andthe Containment Purge and Vent System will be in use with the reactor shutdown3.6.3 Containment Isolation ValvesLCO 3.6.3 Each containment isolation valve shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.SR 3.6.3.1 Verify each 36 inch purge and vent isolation valve is sealed closed. 31 daysSR 3.6.3.2 Verify each 2 inch containment vent isolation valve is closed, except when the 2inch containment vent isolation valves are open for pressure control,ALARA or air quality considerations for personnel entry, or for Surveillances that requirethe valves to be open. 31 days3.6.4 Containment PressureLCO 3.6.4 Containment pressure shall be : 0.0 psig and : 2.0 psig.APPLICABILITY:

MODES 1, 2, 3, and 4.SR 3.6.4.1 Verify containment pressure Is within limits. Every 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sB 3.6.4 Containment PressureThe containment pressure is limited during normal operation to preserve the initialconditions assumed in the accident analyses for a loss of coolant accident (LOCA) or mainsteam line break (MSLB).3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be 5 120°F.APPLICABILITY; MODES 1, 2, 3, and 4.SR 3.6.5.1 Verify containment average air temperature is within limit.B3.6.5 Containment Air Temperature The containment average air temperature is limited during normal operation to preservethe initial conditions assumed In the accident analyses for a loss of coolant accident (LOCA)or main steam line break (MSLB).3.9 REFUELING OPERATIONS Verify each penetration providing direct access from the containment atmosphere to theoutside atmosphere is either closed with a manual or automatic Isolation valve, blindflange, or equivalent; or is capable of being closed by an OPERABLE Containment Purge andVent Isolation System.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii),

the 10 CFR Part 50 license will no longer authorize KPS to operate thereactor or emplace or retain fuel In the reactor vessel, as specified In 10 CFR 50.82(a)(2).

Therefore, the LCOs (and associated Surveillance Requirements (SRs)) that only apply inModes I thru 6 are no longer applicable.

Form No. 732125 (Apr 2013)

SDominion" SSC Category Determination DocumentSI OPK -EC-Y 0 -tah etB*ae1 f2TECHNICAL REQUIREMENTS MANUAL (TRM)8.6 CONTAINMENT SYSTEMS8.6.1 Containment Hydrogen Monitoring SystemTNC 8.6.1 Containment Hydrogen Monitoring System, consisting of two trains andassociated containment dome fans, shall be FUNCTIONAL.

Note:A change in operational MODES or conditions is acceptable with one or both trains of theContainment Hydrogen Monitoring System and Its associated Containment Dome Vent FanNon-Functional.

APPLICABILITY:

MODE 1 and 2.Bases:Even though the requirements for Hydrogen Monitors were taken out of TS, the systemstill needs to be available for beyond design-basis accident monitoring of containment hydrogen levels. In the event CONTINGENCY MEASURES A or B are not met, the condition will be entered into the corrective action program immediately to address why thehydrogen monitors were not restored to FUNCTIONAL status within the allotted time.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(i1),

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

Therefore, the TNC's (and associated Technical Verification Requirements (TVR's))

that onlyapply in Modes 1 thru 6, are no longer applicable.

Offslte Dose Calculation Manual (ODCM)15.1 Major Changes to Radioactive Waste SystemsLicensee Initiated major changes to the radioactive waste systems (liquid, gaseous andsolid)shall be reported to the Commission in the Radioactive Effluent Release Report for theperiod inwhich the evaluation was reviewed by FSRC. The discussion of each change shall contain:a. A summary of the evaluation that led to the determination that the change could bemade In accordance with 10 CFR Part 50.59,b. Sufficient Information to totally support the reason for the change without benefit ofadditional or supplemental Information,

c. A description of the equipment, components and processes involved and the'interfaces with other plant systems,Form No. 732125 (Apr 2013)I.I.0SSSS00000000000000000000000000000000000 0000000000000SS0SinionSSC Category Determination DocumentaPK -E-Y A ttcm n B Pae1 f2d. 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 differfrom those previously predicted in the license application and amendments thereto,e. An evaluation of the change, which shows the expected maximum exposures toindividuals in the UNRESTRICTED AREA and to the general population that differfrom those previously estimated In the license application and amendments thereto,f. A comparison of the predicted releases of radioactive materials In liquid andgaseous effluents and in solid waste to the actual releases for the period in whichthe changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change,andh. Documentation of the fact that the change was reviewed and found acceptable bythe FSRC.Changes shall become effective upon review and acceptance by the FSRC.This is a partial abandonment of RBV. The 36" Containment Purge and Vent fans will becompletely abandoned with the 36" RBV isolation valves failed closed. On February 25,2013, DEK submitted a certification of permanent cessation of power operations pursuantto 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease poweroperation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the certification forpermanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).

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

With the36" Containment Purge and Vent fans be completely abandoned with the 36" RBV Isolation valves failed closed there will be no release through this path. This change results in noincrease in maximum exposures in the UNRESTRICTED AREA, to the general population andto plant operating personnel.

Detailed information concerning the predicted releases andexposure estimates will be included In the annual Radioactive Effluent Release Report.USAR5.4 CONTAINMENT VESSEL AIR HANDLING SYSTEMThe Containment Air Cooling System is sized such that any three of the four fan-coil unitswill provide adequate heat removal capacity from the Reactor Containment Vessel duringoperation, to maintain Interior air temperatures below the maximum temperature allowable for any component and to obtain temperatures below 104°F In accessible areasduring hot standby operation.

The fan-coil units and their associated emergency discharge Form No. 732125 (Apr 2013)

SDominlon° SSC Category Determination DocumentOPK -DCSY 0 -Atahmn B ae1-f2dampers will also be utilized for emergency cooling under post-accident conditions.

Theiruse for that purpose is described in Section 6.3.The fan-coil units of the Containment Air Cooling System are utilized to distribute airadequately over equipment and around occupied spaces for ventilation service.

Operation of motors and other electrical equipment in the containment will provide heating withinthe Reactor Containment Vessel when required during shutdown.

The Containment VentSupply unit will also furnish heated makeup air under shutdown conditions.

The Purge and Ventilation System is designed to provide a reduction in the radioactivity inthe Reactor Containment Vessel air following normal full-power operation, if necessary.

Provision is made In the design of the Purge and Ventilation System for 11/2Y air changes perhour during refueling and maintenance operations.

When high airborne radioactivity levels within containment preclude a normal shutdownentry to the Reactor Containment Vessel, the initial purge will be directed to the purgefilter (particulate-absolute-carbon).

A deluge system is installed in the carbon filterassembly.

The water spray is provided from the Service Water System.When the Reactor Containment Vessel air activity has decreased sufficiently for release tothe atmosphere with particulate filtration only, the Vent and Purge Systems operating mode may be changed from purge to ventilate.

Should some Incident occur to cause the airactivity to Increase above the setpoint of the Containment System Vent Monitor, the ventand purge line valves would both be automatically closed.The Reactor Gap and Neutron Detector Cooling Subsystem limits the maximumtemperature of the concrete surrounding the reactor vessel and keeps the neutrondetectors cool.The Containment Dome Ventilation Subsystem pulls air from the Reactor Containment Vessel dome through separate fan Inlet ducts and discharges the air in the area above theoperating level of containment.

The containment fan coil units then cool the dome air andreturn it to the containment.

This process mixes the dome air and assists in the control ofthe Reactor Containment Vessel temperature during normal operation and the control ofpost-LOCA hydrogen concentration following a design basis accident.

The Reactor Support Cooling Subsystem maintains the proper temperature profile in thereactor vessel supports, shoes, shims, and supporting steel. Two 100% capacity fans drawair from the refueling floor and force the air through ductwork to each of three pairs ofreactor support plenums.The Control Rod Drive Mechanisms (CRDM) Cooling Subsystem provides CRDM cooling bydrawing air from the refueling pool area up through the CRDM enclosing shroud and upthrough three ducts connected to the CRDM shroud plenum mounted on top of the missileshield above the CRDMs.The Post-LOCA Hydrogen Control Subsystem controls the hydrogen concentration in thepost-accident containment atmosphere.

Venting and replacement of the containment atmosphere, dilution by pressurization, or a combination of both methods can be used. Ifrequired, hydrogen recombiners are brought on site5.4.2.1 Isolation ValvesThe ventilation isolation valves are included as part of the containment isolation systemsForm No. 732125 (Apr 2013)0000SS000S0S0000SS0SSSSSSSS0SSSSS0SSSSS O Dominlon" SSC Category Determination DocumentOPK -D.SY 0 -Atahmn B Pag 15of20listed in Table 5.2-3. The valves Immediately outside the Reactor Containment Vessel areconventional butterfly valves, specified to be adequately leak-tight with maximum internal0pressure on the Reactor Containment Vessel side of the valve disc. The valves inside theReactor Containment Vessel are also conventional butterfly valves, which are specified tobe adequately leak-tight with maximum internal pressure on either side of the valve disc*5.4.3 Vacuum Relief SystemVacuum relief devices or systems are provided to protect the Reactor Containment Vesselagainst excess differential pressures.

Such differential pressure conditions (vacuum) mayexist inside the containment vessel if the containment air cooling systems are operatedwith a heat removal capability in excess of the heat Inputs at any time during normal orpost-accident operations.

5.8.2.6.3 Provisions for SamplingMonitoring of the containment hydrogen concentration is accomplished by two Comsip*Model K-111 hydrogen analyzers.

As stated in Reference 7, the analyzers fulfill therequirements of Item II.F.1.6 of NUREG-0737.

The hydrogen monitors have indication inthe control room and a range of 0 percent to 10 percent by volume under positive ornegative containment pressure.

The monitors are normally kept in standby mode, butindication Is available on demand. The system Is operated from Its remote control panellocated outside the high radiation sampling room. A hydrogen sample is drawn from the0post-LOCA hydrogen control system sample ports in containment.

These ports are located0near the discharge of the containment dome fans, which permits rapid detection ofhydrogen escaping from the reactor.

The fans draw suction from the upper areas ofcontainment, which prevents the formation of a stratified atmosphere.

The fans arepowered from safeguard buses and are designed to operate In a post-LOCA environment 0*6.0 Engineered Safety Features*6.1.1*With the failure of an active component in either system, the Containment Air Cooling(CAC) System and the Internal Containment Spray (ICS) System are designed and sized so*that the remaining combined CAC and ICS equipment is able to supply the necessary post-Saccident cooling capacity to rapidly reduce the containment pressure following blowdownand cooling of the core by safety Injection.

Assuming the loss of off-site power and thesingle active failure of one Emergency Diesel Generator, one containment spray pump intandum with two containment fan coil-units on the same train, Is sufficient for5containment heat removal and depressurization.

6.3.2.2 Actuation Provisions SD During normal operation up to four fan coil units are operating and the emergency 5discharge dampers are closed. Each unit has a flow rate capacity of 44,000 cfm undernormal conditions.

During accident conditions, actuation of all four fan-coil units is by the*automatic starting sequence initiated by the Safety Injection Signal.0*6.3.2.6.4 Fan-Coil Emergency Discharge Dampers.0 Form No. 732125 (Apr 2013)S0S V aomnloWSSC Category Determination DocumentOPK -DCSY 0 -Atahmn B Pae10f2The dampers are parallel blade, pneumatically operated (air open, spring close) type.Isolation dampers are provided to prevent back flow through an inactive unit.All ductwork, damper blades, and seating surfaces are constructed of, or coated withcorrosion-resistant materials.

To ensure the Integrity of the ductwork in a post LOCAenvironment, the Containment Fan Coil Unit emergency discharge dampers and back draftdampers are tested once every operating cycle, or every 18 months.6.5.1.2.13 Service Water SystemThe containment fan-coil service water discharge radiation monitor checks thecontainment fan coils for radiation indicative of a leak from the containment atmosphere Into the service water. A small bypass flow from the common return of the fan coil units ismonitored by a scintillation detector mounted In a holdup tank assembly.

Upon indication of a high radiation level each fan coil is individually sampled to determine which unit Isleaking.14 Safety Analysis14.3.5.2.2 Input Parameters and Assumptions A series of analyses, using different break sizes and locations, was performed for the LOCAcontainment response.

Section 14.3.5.1 documents the mass and energy releases for theDEPS and DEHL breaks. The DEPS break cases were run with both minimum and maximumsafeguards.

The three minimum safeguards cases assume a diesel train failure.

Thisassumption leaves one of two containment spray pumps and two of four containment fan-coil units (CFCUs) available for containment heat removal.Table B Classification of Systems and Components

-Safeguards Fan Coil Units IReactor Building Ventilation System-Containment Purge and Vent System (Containment Isolation Valves are Class 1) 111-Containment Dome Fans I-Post-LOCA Hydrogen Control System (Containment Isolation Valves areClass I) Ill-Containment Vacuum Reilef System I-Containment Fan Coil Units (includes fans, coils, and housings)

I-CRDM Shroud Cooling System II-Reactor Gap and Neutron Detector Cooling System (excluding Class I pipingsegment in the reactor cavity) Ii-Reactor Support Cooling System IIOn February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(1),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFRForm No. 732125 (Apr 2013)0000000000S0000000S000000 0000000S000S0S00000000nlonSSC Categoty Determination Document0* W-ECS YC01 -AtahetB Pae1 f250.82(a)(1)(ii),

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

Since KPS will no longer be authorized to operate or place fuel in the reactor the functions credited In the USAR are no longer required.

The USAR will be revised to addressrequirements following cessation of power operation.

LICENSING COMMITMENTS Commitment Number: 80-001Title: Containment Purge and Vent Valve Modifications Improvement Initiative While above hot shutdown Kewaunee will seal the 36 diameter purge and vent valvesclosed and will verify the valves closed by monthly surveillance of control board Indication.

This commitment will take effect upon startup from the next refueling outage and willcontinue until such time that valve operability is shown.Commitment Number: 83-005Title: CONT. PURGE AND VENT SYSTEM OPERABILITY Installation of a 2" containment vent systemCommitment Number: 83-012Title: CONT. PURGE AND VENT SYSTEM OPERABILITY Need a procedure for Containment venting.Commitment Number: 90-143Title: GENERIC LETTER 89-13: SW BIOFOULING Commitment change evaluation was in initiated and approved to provide an alternate method for verifying continued heat exchanger performance for the CFCUs.Commitment Number: 84-009Title: RESOLUTION OF SER FOR EQReplacement of containment vacuum breakers with qualified solenoid valves.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii),

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

Since the KPS license will be modified to a possession only license, the regulatory commitments associated with the Reactor Building Ventilation System will not bemaintained.

These commitments will be dispositioned per LI-AA-110, Commitment Management.

Form No. 732125 (Apr 2013) 0Dominlow SSC Category Determination DocumentI~ OPM DC-Y-0 -e tahene ae 8oEMERGENCY PLANReviewed the Emergency Plan and the Emergency Action Level (EAL) Technical BasisDocument for classification criteria that apply in Mode DEF-Defueled.

The Emergency Plandefines Defueled as 'All reactor fuel removed from Reactor Vessel (full core off load duringrefueling or extended outage)'

Abandonment of the RBV System will not Impact theEmergency Plan as this equipment Is not listed In the EAL tables that apply to a defueledplant. None of the radiation monitoring equipment is being abandon as part of the RBVsystem categorization.

FIRE PROTECTION PROGRAM PLAN11.0 DESCRIPTION OF FIRE PROTECTION SYSTEMS AND FEATURESFire protection systems and components are designed using the guidelines of theNational Fire Protection Association (NFPA) standards (see Appendix B). The waterspray systems for the charcoal

filters, boiler fuel oil pumps and the hydrogen sealoil unit are unique and do not meet the NFPA standards.

11.4.1 Water Spray SystemsThe water spray systems for the Auxiliary Building charcoal filters (shield building, the containment purge, containment cleanup and the Control Room airconditioning ventilation units) are nonstandard;

however, they are adequate fortheir intended purpose.

The water supply is the service water system. Thesesystems have detectors that operate solenoid valves that feed water to the spraynozzles.The Fire Plan requires that if the filter fire detector is out of service a hourly firewatch is to be established.

Use of combustible

material, e.g., HEPA and charcoal

filters, dry ion exchangeresins or other combustible

supplies, In safety-related areas should he controlled.

Abandonment of the RBV system will not impact the Fire Plan. The charcoal shall beremoved from the charcoal filter unit prior to disabling the fire protection spray system tothe filters.Plant ImpactThe abandonment of the RBV system shall eliminate all Installed heating fromcontainment.

One containment fan coil unit shall remain availble for cooling anddehumidifcation if needed.Portable heaters are to be placed in containment plugged into weld receptables tomaintain containment above 40F so freezing does not occur. The following instrument loops are required to remain available to monitor containment temperture.

Forn No. 732125 (Apr 2013)60006S0SS00S000000SSSS0SSSSSSSS0SSSSSSSS 000000S0S0S0SS000S0WftminlowI SSC Categoty Determination DocumentOP, W-ECS Y 01 -AtahetB Pie1 f2TE-15189 Containment elevation 592' ambient air temperature TE-15187 Containment elevation 626' ambient air temperature New or existing procedures will need to be created or revised to provide direction formonitoring and controlling containment temperature, including the control of setpoints forthe portable heaters and operation of a dome fan to prevent stratification.

A portable dehumidifier is to be placed in containment to control humidity and reduce thepotential of mold growth. The portable dehumidifier will be used to reduce or eliminate the need to run CFCU A. The following instrument loop is to be maintained to monitorcontainment humidity.

41517 Containment humidity indicator New or exisitng procedures will need to be created or revised to control humididy Incontainmet and operation of the dehumidifier.

Althoug it is expected to be rarely if everused this should include use of the A CFCU unit as needed.There is no impact on any temporary changes that are active as of 5-9-2013.

The Drawing Control Team did not Identify any outstanding drawing changes that requireddisposition as a result of system abandonment.

This DSERT package does not Impact Spent Fuel Pool Cooling therefore does not requireFSRC approval.

5.0 Special conditions to support categorization(s):

None6.0 Assumptions/Open Items to be validated or dispositloned:

None7.0 Expected duration for SSC category if NOT ABANDONED:

The CFCU A Is expected to remain available Indefinitely to provide cooling to containment during decommissioning activities In containment.

The Containment Vent path to the aux building ventilation is expected to remain openIndefinitely to avoid pressure Increases and decreases as containment heats up and coolsdown based on ambient conditions.

Form No. 732125 (Apr 2013)

VoomnlInoe SSC Gate gory Determination Document0 -At n B PThe A Dome Fan shall be evaluated to determine if it is needed to limit stratification incontainment.

If deemed it is not required this Categorization plan will be revised toabandon the A Dome Fan.8.0 PREPARE and ATTACH the following documents:

SSCompleted 10 CFR 50.59 Screening or Evaluation, If requiredProposed DUs for appropriate drawings9.0 Technical Concurrence:

Type Of Review Name (Print) Approval Signature DateEngineering aA41o L -& ( J-/-//?Type Of Review Name (Print) Approval Signature DateFire Protection

____.___-J 1ý. .11,1Type Of Review Name (Print) Approval Signature Date 'Security iS(;A Rf 09e44Type Of Review Name (Print) '-Aproy Ig ature DateRadiation Protection DO W.--?.- /.Type Of Review Name (Print) ISign ature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature Date300000I.0000000000000000000000000000000Form No. 732125 (Apr 2013) wi-DomnInom SSC Category Determination Document0*K -DCSY-0 -Atahmn B Pae2 f2S0S000S0SS000S10.0 Review and Approval:

Prepared iy (Print/Sign)

Reviewed By (Screen Qu) (Print/Sign)

Nuclear Likrensing Print/Sign)

Concurrence by DSE (Pt/ inato r" int/Sign)

FS RC (P/nt/Sylgn),

if reql~ieý,

Date<-2 6/,3DateDateS -X) -13DateDateFSRC Meeting Number:13-0,31Form No. 732125 (Apr 2013) 00000000000SS000SS0SThis page intentionally left blank 5SS0SS00S0SSSS00SSS0SSS0

'Dominion" SSC Category Determination DocumentOPK -DCSY-0 -Atahmn B Pao1o1.0 Doc Type: ReportSub Type: DECDocument Number (ID): SYS-32B-DSERT Title: Gaseous Radioactive Waste DisposalRevision No.: 0Date: 06/07/2013 1 1.1 Brief description or reason for revision:

Not applicable for Revision 0.000SS0000000002.0 System Category (Check Appropriate):

NOTE: A SSC may be divided and have more than one category determination depending upon Itsfunctional requirements.

IEl- Available (Category A)Z Abandoned (Category X)Describe the assessed boundaries:

The WG system consists of:" Two waste gas compressor

packages,

" Four gas decay tanks," One nitrogen supply package," One hydrogen supply package," One multipoint gas analyzer,

" Associated piping, valves, and Instrumentation.

Gases processed by the WG System during normal plant operation are collected from the following sources:" Cover gas from the Chemical and Volume Control System (CVCS)," Cover gases vented to the closed cover gas system," Equipment purging (vents and reliefs),

Sampling operations,

" Automatic gas analysis for hydrogen and oxygen in cover gases.The system will be isolated from the CVCS at MG(R)-520, Hold Up Tank to Vent Header 1WG-17, Gas Decay Tanks to Holdup Tanks, and the CVCS Holdup Tank to Gas analyzer valves.The gas decay tanks and waste gas compressors will be Isolated from the plant vent at WG-36,Gas Decay Tanks to Plant Vent. The tanks will also be Isolated from various other tanks andForm No. 732125 (Apr 2013)

SDominion SSC Category Determination DocumentI .OPM DCS Y 0 -S Atahmn B Pae2osystem Interconnections at the following valves:BEF-4-1, Isolation on Vent Header Side of BEF4/CV-31277 MD(R)-401, Gas Decay Tank to Drain HeaderMG(R)-507, Reactor Coolant Drain Tank to Vent HeaderMG(R)-520 Combined Holdup Tanks to Vent HeaderISOLMG(R)-537, VCT Vent to WDS Isolation MG(R)-544, VCT Gas Space to Vent HeaderMG(R)-549 Przr Relief Tank VentIsolation MG(R)-550, Vent Header #2 to Waste Gas Analyzer Filter Inlet Isolation WG-16, Gas Decay Valve Gallery to Holdup TanksWG-200-1, Gas Decay Tank to Gas ANZR Filter Inlet Isolation WG-300, Deareated Drain Tank Vent Line to WG Manual Isolation NG-721, Nitrogen Manifold to Gas Decay TanksThe Waste Gas Analyzer will be isolated from interconnecting systems at the following valves:NG-731, Misc Gas Systems to Auto Gas AnalyzerMG(R)-561, Train B Inlet/Outlet Isolation Valves MG(R)561/MG(R)563 MG(R)-562, Train A Inlet/Outlet Isolation Valves MG(R)560/MG(R)562 MG(R)-564, WGA Cal Gas VentMG(R)-566 Grab Sample to Bottle InletMG(R)-567 Grab Sample from Bottle OutletThe system will be isolated from the electrical distribution system at the 480V Waste GasCompressor 1A and 1B supply breakers.

The system wil be Isolated from 120V AC at the supply breaker for the Waste Gas Analyzer Panel.3.0 Mark up the affected drawings using color coding to identify system category type andboundaries.

These drawings are to include system, electrical one-line and distribution, and selectbuilding and isometric drawings.

Related system drawings NOT incorporated In the systemcategory require an explanation.

REFER to Step 2.7 for a list of drawings.

Flow Diagram Chemical

& Volume Control System, OPERXK-100-37 Following valves serve as isolation boundaries:

MG(R)-516A, Hold Up Tank 1A to Gas AnalyzerMG(R)-516B, Hold Up Tank 1B to Gas AnalyzerMG(R)-516C, Hold Up Tank 1C to Gas AnalyzerMG(R)-520, Hold Up Tank to Vent Header 1WG-17, Gas Decay Tanks to Holdup TanksForm No. 732125 (Apr 2013)66666000000I.0IS0

00°000S000000S000S09SomuinlowSSC Category Determination.

DocumentSPK -E W tah etBIae3oFlow Diagram Waste Disposal System, OPERXK-100-131 Abandon the Waste Gas Analyzer with the following valves serving as isolation boundaries:

NG-731, Misc Gas Systems to Auto Gas AnalyzerMG(R)-561, Train B Inlet/Outlet Isolation Valves MG(R)561/MG(R)563 MG(R)-562, Train A Inlet/Outlet Isolation Valves MG(R)560/MG(R)562 MG(R)-564, WGA Cal Gas VentMG(R)-566 Grab Sample to Bottle InletMG(R)-567 Grab Sample from Bottle OutletFlow Diagram Waste Disposal System, OPERXK-100-132 Abandon the entire drawing with the following valves serving as boundaries:

BEF-4-1, Isolation on Vent Header Side of BEF4/CV-31277 MD(R)-401, Gas Decay Tank to Drain HeaderMG(R)-507, Reactor Coolant Drain Tank to Vent HeaderMG(R)-520 Combined Holdup Tanks to Vent HeaderISOLMG(R)-537, VCT Vent to WDS Isolation MG(R)-544, VCT Gas Space to Vent HeaderMG(R)-549 Przr Relief Tank Vent Isolation MG(R)-550, Vent Header #2 to Waste Gas Analyzer Filter Inlet Isolation WG-13A, Gas Decay Tank 1A to Plant Vent (Relief valve)WG-13B, Gas Decay Tank 1B to Plant Vent (Relief valve)WG-13C, Gas Decay Tank 1C to Plant Vent (Relief valve)WG-13D, Gas Decay Tank 1D to Plant Vent (Relief valve)WG-16, Gas Decay valve Gallery to Holdup TanksWG-36, Gas Decay Tanks to Plant VentWG-200-1, Gas Decay Tank to Gas ANZR Filter Inlet Isolation WG-300, Deareated Drain Tank Vent Line to WG Manual Isolation NG-721, Nitrogen Manifold to Gas Decay TanksFlow Diagram H2/02 Automatic Gas Analyzer, M-1725Abandon the entire drawing with the following valves serving as boundaries:

MG(R)-561, Train B Inlet/Outlet Isolation Valves MG(R)561/MG(R)563 MG(R)-562, Train A Inlet/Outlet Isolation Valves MG(R)560/MG(R)562 MG(R)-564, WGA Cal Gas VentV36SV14SV15SV16SV17SV24Circuit Diagram 480V MCC 1-35A, 1-35D, 1-45A & 1-45D, E-254Abandon:

Bus 1-35A, B6, Waste Gas Compressor 1A Motor FeedForm No. 732125 (Apr 2013)

, Donilnlon SSC Category Determination DocumentOPS. -ECS Y-0 -Atahen age 4..Circuit Diagram 480V MCC 1-62A, 1-52D, 1-5262 & 1-62B, E-261Abandon:

Bus 1-5262, A-6, Waste Gas Compressor 1B Motor FeedLighting Panels RPA7, RPA8, RPA9, RPA1O, RPA11, RPA12, E-885Abandon:

RPA8 circuit 21, Waste Gas AnalyzerThe following instrument boundaries will be abandoned along with their respective sensing lines:P1-8131, PI-8132, P1-8133, PC-16108, TI-12151, PS-16173, LT-1030, LC-1030A/F, PC-16109, TI-12152, PS-16044, LT-1032, LC-1032A/F, PT-1025, PC-1025, PC-1025A, PT-1036, PC-1036B, PT-1037, PC-1037B, PT-1038, PC-1038B, PT-1039, PC-1039B, P1-1036, P1-1037, P1-1038, P1-1025, LI-1030, Li-1032, PI-11057J 4.0 Evaluation (Basis for choosing category type):Purpose/Function The purposes of the WG System are to:* Collect gaseous radioactive waste (WG) produced by the operation of the KewauneePower Station (KPS).* Process the WG as required to permit disposal within the limits established by theapplicable regulatory guidelines.

Provide the ability to reuse waste gases as cover gases in the CVCS Holdup Tanks andDDT.Based on the above, the WG System is capable of processing all gaseous wastes generated during the continuous operation of the Reactor Coolant System (RCS) assuming claddingdefects in one percent (1 %) of the fuel rods. The WG System Is capable of handlinggaseous waste from two units.Basis for CategoryOn February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed thecertification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii).

Therefore the 10 CFR Part 50 license no longer authorizes KPS to operatethe reactor or emplace or retain fuel in the reactor vessel, as specified In 10 CFR50.82(a)(2).

The gas decay tanks contain the gases vented from the RCS, the Volume Control Tank, andthe liquid CVC Holdup Tanks. Following abandonment of the RCS and CVCS systems theWaste Gas Decay Tanks and associated piping will be discharged and vented toatmosphere.

No new gasses will be produced as the CVCS will be drained/vented and thereactor vessel has been defueled.

Form No. 732125 (Apr 2013)006I.jo00I.000000SI.I.Sl000S0000S00000 000* 0000000000000S0000000mIn'oSSC Categoty Determination DocumentOPMDC-Y-0

-Atahmn B Pag -ofBased on the above, the Waste Gas System does not perform a function or provide supportfor any of the following items:1. To prevent or mitigate the consequences of a design basis accident of a permanently defueled plant.2. Fuel Handling Accident as defined In Updated Safety Analysis Report (USAR).3. For safe storage and handling of radioactive waste or spent fuel.4. To support Technical Specifications, License Requirements, Design Basis, permits,regulatory requirements, insurance requirements, or other commitments.

Provide supportof the Spent Fuel Safety Management

Program, or radiological effluent monitoring.

5. To support the execution of plans and programs of Kewaunee Power Station.6. Support day to day operations in the decommissioning plant.7. Support plant decommissioning efforts.Regulatory ImpactThis DSERT package does not Impact Spent Fuel Pool Cooling.

This DSERT package isassociated with the accident analysis for a gas decay tank rupture per USAR section 14.2.3Accidental Release-Waste Gas. Therefore this document requires FSRC review andapproval.

Commitments:

A search of licensing commitments using the following file pathS:\KEWAUNEE\4\DATAI\LICENSING\Commitments\COMTRAKS\TRU ECOM MITM ENTS\ALLTRUE Commitments by Number, did not identify any open commitments related to theWaste Gas System. Additionally the license renewal commitments In table 15.7-1 of theUSAR were reviewed and no commitments related to the Waste Gase System wereidentified.

Commitment numbers 85-05 and 85-052 to analyze for explosive gas mixtures were closedto commitment number 94-132, which was subsequently closed to commitment number96-122. Commitment 96-122 was closed on 2/15/2001 following completion of the wastegas analyzer modification and issuance of the required operating and maintenance procedures.

Technical Specifications:

The Waste Gas System is not explicitly identified In technical specifications.

Technical Specification 5.5.3, Radioactive Effluent Controls

Program, refers to the WasteGas System. The program is required to be maintained until the issuance of the PDTS. Thisprogram provides controls for gaseous effluents.

Following abandonment of the RCS andCVCS systems the Waste Gas Decay Tanks and associated piping will be discharged andvented to atmosphere.

No new gasses will be produced as the CVC System will bedrained/vented and the reactor vessel has been defueled.

The requirement to maintainthe program does not prevent the abandonment of the Waste Gas System as the systemForm No. 732125 (Apr 2013)

SDominion" SSC Categoty Determination DocumentI* O KWDCS Y01 -Atahmn B.ae6owill be purged and vented of any radioactive gasses prior to abandonment.

The Waste Gas System is not explicitly identified in technical specifications.

Technical Specification 5.5.10, Explosive Gas and Storage Tank Radioactivity Monitoring Program,refers to the waste gas system. The program Is required to be maintained until theissuance of the PDTS. This program provides controls for potentially explosive gas mixturescontained in the Gaseous Radioactive Waste Disposal System, the quantity of radioactivity contained in gas storage tanks or fed into the offgas treatment system, and the quantity ofradioactivity contained in unprotected outdoor liquid storage tanks. The requirement tomaintain the program does not prevent the abandonment of the waste gas system as thesystem will be purged and vented of any radioactive gasses prior to abandonment.

USAR:The USAR will require revision to reflect abandonment of Waste Gas System. The system Ismentioned in the following chapters/sections:

2.7.1, Meteorological Program8.2.2.4, 480V System9.3.2.1, System Design and Operation, Component Cooling System9.6.5.1, Auxiliary Building Special Ventilation System Design Basis11.1.1.1 Control of Releases of Radioactivity to the Environment 11.1.2.3, Gas Processing 11.1.2.10, Gas Decay Tanks11.1.2.11, Waste Gas Compressors Table 11.1-2, Waste Disposal Components CodesTable 11.1-3, Component Summary DataFigure 11.1-8, Waste Gas Processing 11.2.3.5, Auxiliary Building Vent Monitors14.2 Standby Safety Features Analysis14.2.3, Accidental Release Waste GasTable B.2-1, Classification of Systems and Components H.2, Containment System evaluation, Leak PathsOffsite Dose Calculation Manual (ODCM):The ODCM will require revision to reflect abandonment of Waste Gas System. The systemis mentioned in the following chapters/sections:

2.1.1 Waste Gas Holdup System2.1.4 Auxiliary Building VentTable 13.2.1-1, Radioactive Gaseous Waste Sampling and Analysis13.2 Gaseous Effluents

-13.2.5 Gas Storage Tanks13.3 Instrumentation

-13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation Table 13.3.2-1, Radioactive Gaseous Effluent Monitoring Instrumentation Form No. 732125 (Apr 2013)I.0I.6I.06I.066I.SSI.SSSS0I.I.SSSSSI.SSSSSSS0SS 000000000000S00SS0S000, DominloWSSC Category Determination DocumentOPK -DCSY-0 -Atahmn B Pae .oThe USAR and ODCM revisions will be revised to address requirements following cessation of power operation.

Technical Requirements Manual ITRM]:Abandonment of the Waste Gas system would abandon the Waste Gas Analyzer which Isidentified In the Technical Requirements Manual section 8.3.7. The requirements of thissection are applicable whenever a Waste gas Decay Tank is inservice.

This requirement does not prevent the abandonment of the waste gas system as the system will be purgedand vented of any radioactive gasses prior to abandonment.

Additionally, no new gasseswill be produced as the CVCS will be drained/vented and the reactor vessel has beendefueled.

Plant ImpactThe FPPA will be revised to reflect the complete abandonment of the Waste Gas Systemfollowing abandonment.

In addition, the Fire Zone Summaries in the FPPA and the FireFighting Strategies books will be revised to CVC HUTs, WGDTs, and VCT as a combustible hazard. No other changes are required to SSCs, procedures,

programs, processes, etc.No additional changes are required to SSCs, procedures,

programs, processes, etc.There Is no impact on any temporary changes that are active as of 6/7/2013.

The Drawing Control Team did not identify any outstanding drawing changes that requireddisposition as a result of system abandonment.

5.0 Special conditions to support categorization(s):

RCS and CVCS system abandoned (drained/vented).

Gas Decay tanks and associated vent header piping purged and vented.6.0 Assumptions/Open Items to be validated or dispositioned:

Validate that the status of the systems and plant condition are such that conditions can notbe established for the accident analysis for a gas decay tank rupture per USAR section14.2.3 Accidental Release-Waste Gas.Form No. 732125 (Apr 2013) 09Dominionr SSC Category Determination DocumentOPK -ESY-0 -Atahmn B Pag 8-of7.0 Expected duration for SSC category if NOT ABANDONED:

N/A8.0 PREPARE and ATTACH the following documents:

Completed 10 CFR 50.59 Screening or Evaluation, if required* Proposed DUs for appropriate drawings9.0 Technical Concurrence:

Type Of Review Name (Print) Approval Signature DateEngineering

-, ., ..i 113Type Of Review Name (Print) Approval Sinature DateFire Protection

_____,,_______

___/_/__Type Of Review Name (Print) App. a na r DateSecurity

______Type Of Review Name (Print) App val S ure DateRadiation Protection DanIie J. Sha1fn -/.Type Of Review Name (Print) "ppro Signature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature DateType Of Review Name (Print) Approval Signature DateForm No. 732125 (Apr 2013)

, DominionSSC Category Determination DocumentOPK -DCSY-0 -Atahmn B Pae1 f100S00000S.0000S0000S010.0 Review and Approval:

Prepared By (Print/Sign)

Reviewed By (Screen Qual.) (Print/Sigg Nucler4icenisinglPrlnt/Sign)

OD Vks' --Concurrence by DSERT Coordinator (Print/Si n)Jeffrey Stafford

" -I_ --71,1/3DateDateDatete13DateDateFSRC (Print/Sign),

If requiredFSRC Meeting Number:/3 -0325Form No. 732125 (Apr 2013) 00S0000S0S0000S000000This page intentionally left blank00000S00000000SS000SS0 0000SS0000000SS00000S0ow-Dominlon' SSC Category Determination DocumentOP* W-EC-YC00

-AtahetB PgIof21.0 Doc Type: ReportSub Type: DECDocument Number (ID): SYS-35-DSERT Title: Chemical and Volume ControlRevision No.: 0Date: 5/6/20131.1 Brief description or reason for revision:

Not applicable for Revision 0.2.0 System Category (Check Appropriate):

NOTE: A SSC may be divided and have more than one category determination depending upon itsfunctional requirements.

I[] Available (Category A)Z Abandoned (Category X)Describe the assessed boundaries:

This is a complete functional abandonment of the Chemical And Volume Control System (CVCS),including the following components:

Letdown Heat Exchanger, Seal Water Heat Exchanger, Regenerative Heat Exchanger, Charging Pumps A, B, and C, Volume Control Tank (VCT), ChemicalMixing Tank, CVCS Mixed Bed Demineralizers A and B, CVCS Cation Bed Demineralizer, CVCSDeborating Demineralizers A and B, Boric Acid Transfer Pumps A and B, Boric Acid Storage Tanks(BAST) A and B, Boric Acid Batching Tank, Concentrates Holding Tank, Concentrates Holding TankTransfer Pumps A and B, CVCS Hold Up Tanks (HUT) A, B, and C, CVCS Monitor Tanks A and B,CVCS HUT Recirculation Pump, CVCS Monitor Tank Pumps A and B, Gas Stripper Feed Pumps Aand B, Evaporator Feed Ion Exchangers

1, #2, and #3, Evaporator Condensate Demineralizers

1and #2, the Boric Acid Evaporator

Package, Component Cooling used by the Letdown HeatExchanger and Seal Water Heat Exchanger, Instrument Air supply to control valves, Demineralized Water supplies, 480V electrical power supplies, all associated piping, instrumentation,

filters, andBoric Acid Heat Tracing.

The Excess Letdown Heat Exchanger, which directs flow to the VCT, andReactor Coolant Pumps (RXCPs),

which include seal Injection from charging and seal leakoff to theVCT, have been evaluated for abandonment in the Reactor Coolant System abandonment plan,and are not evaluated here.The Boric Acid Evaporator (BA Evap) has already been abandoned, but will be formally abandoned as a package in this plan. This will be a complete functional abandonment of the Boric AcidForm No. 732125 (Apr 2013)

SDominlon' SSC Category Determination Document0 P K -D C SY Atac ni n B Pag 2 fSEvaporator, including the following components:

Evaporator, Feed Preheater, Absorption Tower,Evaporator Condenser, Distillate Cooler, Stripping Column, Vent Condenser, Condensate ReturnTank, Condensate Return Unit Heat Exchanger, Condensate Return Pumps 1A & 2B, Distillate Pumps 1A & 1B, Boric Acid Concentrate Pumps 1A & 1B, Heating Steam, Component Cooling,Service Water, all associated piping, instrumentation,

controls, and Boric Acid Heat Tracing.The following Instrument boundaries will be abandoned along with their respective sensing linesFI-651 (18232),

FI-642 (18218),

FI-652 (18234),

PT-135 (21075),

FT-134 (23021),

FIT-116 (23112),FIT-115 (23111),

P1-136 (11126),

P1-11319, P1-11320, P1-137 (11127),

P1-138 (11128),

FI-143(18212),

FT-111 (23020),

TI-120(12072),

LT-141 (24016),

LT-112 (24015),

PT-139 (21076),

P1-152(11129),

FT-110 (23019),

FT-113 (23031),

TI-117 (12071),

P1-118 (11130),

P1-119 (11131),

FT-128(23022),

PIC-183B (11180),

PIC-183A (11181),

LT-153 (24017),

P1-11724, LT-154 (24018),

LT-156(24019),

PI-168A (11136),

PI-168B (11137),

LIT-165 (24021),

LIT-162 (24020),

P1-165 (11135),

P1-162 (11134),

PI-160A (11132),

PI-160B (11133),

FI-164 (18215),

P1-163 (11138),

FT-159 (23069),

P1-147 (11140),

Pi-146 (11139),

PI-194A (11186),

PI-194B (11187),

LT-151 (24022),

TW-150 (22021),P1-149 (11144),

P1-148 (11143),

TICA-107 (26318),

TICA-105 (26319),

LT-190 (24025),

LT-172(24024),

LT-106 (24023),

LT-196 (24038),

LT-189 (24028),

LT-171 (24027),

LT-102 (24026),

LT197(24039),

TICA-104 (26321),

TICA-103 (26320),

PI-195A (11188),

PI-195B (11189),

P1-109 (11142),P1-108 (11141),

TICA-100 (26317),

LT-101 (24061),

FT-300 (23058),

P1-11641, LT-315 (24064),

TT-304 (22022),

CE-303 (25009),

FT-307 (23059),

LT-306 (24063),

TT321 (22023),

TT-321 (54101),

PI-309 (11195),

PI-310 (11194),

PT-316 (21116),

Pl-311 (11197),

PT-21128, PI-312 (11196),

PT-21129, TI-12205, PS-16163, PS-16164, PS-16165, FI-605 (18233),

TI-604 (12077),

FI-601 (18217),

TI-600(12079).TE-126 (15056),

TE-127 (15055),

TE-150 (15119),

TE-145 (15118),

TE-140 (15057),

TE-313 (13024),TE-13181 through 13422 (242 Total Temperature Elements used for Boric Acid Heat TracingForm No. 732125 (Apr 2013)0S00SSS00S0SSSSSSSSSSSSSSSSSS0SSSSSSS0SSSS 000S0S0000000SS00000, Dominion° SSC Category Determination Document0*K -DCSY 0 -Atahmn B Pag 3 f23.0 Mark up the affected drawings using color coding to Identify system category type andboundaries.

These drawings are to include system, electrical one-line and distribution, and selectbuilding and isometric drawings.

Related system drawings NOT incorporated in the systemcategory require an explanation.

REFER to Step 2.7 for a list of drawings.

Abandon all piping, components, Instrumentation, valves, and heat tracing of System 35,Chemical And Volume Control as shown on the following drawings:

Operations Critical Drawing OPERXK-100-10, Reactor Coolant System (Revision BW)-Letdown line from Boundary Isolation Valve LD-1, Cold Leg Loop B to Letdown LineOperations Critical Drawing OPERXK-100-35, Chemical And Volume Control System (Revision AG)-Letdown Line (continued from OPERXK-IO0-10)

-Letdown Line continued on OPERXK-100-36

-RHR to CVCS Letdown piping from Boundary Isolation Valve LD-60/MV32099, RHR toCVCS Letdown Line.-RXCP Seal Leakoff line from Boundary Isolation Valve CVC-212/MV-32115, RXCP SealWater Return Isolation (continued on OPERXK-100-36).

-Charging Line from drawing OPERXK-100-36, to the following Boundary Isolation Valves:-CVC-11/CV-31229, Charging Line Isolation

-CVC-13, Regenerative Heat Exchanger Flow Control Bypass-CVC-15/CV-31230, Przr Auxiliary Spray Valve-RXCP Seal Injection Line and Seal Water Injection Filters By-Pass Line from OPERXK-IO0-36, to the following Boundary Isolation Valves:-CVC-204A, 1A RXCP Seal Supply Line Throttle valve-CVC-204B, 1B RXCP Seal Supply Line Throttle valveOperations Critical Drawing OPERXK-100-36, Chemical And Volume Control System (Revision BH)-Letdown line (continued from OPERXK-100-35)

-RHR to CVCS penetration from Boundary Isolation Valve RHR-211, RHR/CVC OutletIsolation

-Letdown Heat Exchanger Drain piping (hard-piped to the Sludge Interceptor Tank), up tothe following Boundary Isolation Valves:-MD(R)-270, Letdown Heat Exchanger Drain-MD(R)-271, Letdown Heat Exchanger Drain-MD(R)-272, Letdown Heat Exchanger DrainMD(R)-273, Letdown Heat Exchanger Drain-Letdown piping up to Boundary Isolation Valve LD-70, Letdown Line Sample-Letdown piping up to Boundary Isolation Valve LD-36, Boron Measuring System IsolForm No. 732125 (Apr 2013)

VDomnlon° SSC Category Determination Document3. IDE-SC-0

-Atah etB Pg .f2-*NOTE* The Boron Measuring System has previously been officially abandoned downstream of LD-36, and is therefore not considered in this abandonment plan.Letdown Line to the Volume Control Tank (VCT) from LD-14/CV-31098, LD Demin HighTemp Divert Valve-Letdown piping up to Boundary Isolation Valve LD-80, Letdown to VCT LineSample-Reactor Coolant Filter drain line piping (hard-piped to SIT), up to BoundaryIsolation Valve LD-47, Reactor Coolant Filter Drain-Letdown flow divert to CVC HUTs line from LD-27/CV-31096, VCT/Holdup TankDivert Valve (continued on OPERXK-100-37)

-Letdown piping and the VCTLetdown piping from LD-14 through the CVCS Demineralizers, and return piping todownstream of LD-14-Letdown Prefilter 1A drain line piping (hard-piped to SIT) up to Boundary Isolation Valve LD-39A, Letdown Demineralizer Prefilter 1A Drn.-Letdown Prefilter 1B drain line piping (hard-piped to SIT) up to the following Boundary Isolation Valves:-LD-39B, Letdown Demineralizer Prefilter 1B Drn-LD-39B-1, Ietdown Demlneralizer Prefilter 1B Inlet Drain-Mixed Bed Demineralizer 1A, up to the following Boundary Isolation Valves:-CVC-SlOA, 1A Mixed Bed Demineralizer Vent (hard-piped to SIT)-CVC-503A, 1A Mixed Bed DEMIN Resin Discharge Isolation (hard-piped toSpent Resin Storage Tank)LD-42A, 1A Mixed Bed Demineralizer Drain (hard-piped to SIT)-Mixed Bed Demineralizer 1B, up to the following Boundary Isolation Valves:-CVC-510B, 1B Mixed Bed Demineralizer Vent (hard-piped to SIT)-CVC-503B, 1B Mixed Bed DEMIN Resin Discharge Isolation (hard-piped toSpent Resin Storage Tank)LD-42B, 1B Mixed Bed Demineralizer Drain (hard-piped to SIT)-Cation Bed Demineralizer, up to the following Boundary Isolation Valves:-CVC-511, Cation Bed Demineralizer Vent (hard-piped to SIT)-CVC-505, Cation Bed DEMIN Resin Discharge Isolation (hard-piped toSpent Resin Storage Tank)-LD-151, Cation Bed Demineralizer Drain (hard-piped to SIT)Deborating Demineralizer 1A, up to the following Boundary Isolation Valves:-CVC-512A, 1A Deborating Demineralizer Vent (hard-piped to SIT)-CVC-507A, 1A Deborating DEMIN Resin Discharge ISOL (hard-piped to.Spent Resin Storage Tank)-CVC-553, Deborating Demineralizers Drain (hard-piped to SIT)Deborating Demineralizer 2B, up to the following Boundary Isolation Valves:-CVC-512B, 1B Deborating Demineralizer Vent (hard-piped to SIT)-CVC-507B, 1B Deborating DEMIN Resin Discharge ISOL (hard-piped toForm No. 732125 (Apr 2013)0000000000S00S00SS000000 0000 n00S0000S00000000000minlo.,SSC Category Determination DocumentOPK -D.SY 0 -Atahmn B Pae5 f2Spent Resin Storage Tank)-Flushing water supply to all Demineralizers up to Boundary Isolation Valve DW-216, Demineralized Water To Demineralizers.

Volume Control Tank (VCT) up to the following Boundary Isolation Valves:-NG-802, Nitrogen to VCT Line Isolation

-HG-302, Hydrogen to VCT Line Isolation

-CVC-50, VCT Vent to Cntmt Isol-MG(R)-534, VCT Vent to WDS Isolation

-MG(R)-540, VCT Vent to Sampling System Isol-MG(R)-531, VCT to Gas Analyzer Isol-CVC-37, Boron Measuring System Isolation

NOTE* The Boron Measuring System has previously been officially abandoned upstream of CVC-37, and is therefore not considered In this abandonment plan.Seal Water Return and Seal Water Return Bypass piping from Boundary Isolation ValveCVC-212 on OPERXK-100-35 to the VCT, up to the following Boundary Isolation Valves:-CVC-264, Seal Water Return Filter Drain (Hard-piped to SIT)-MD(R)-260, Seal Water Heat Exchanger Drain (Hard-piped to SIT)-MD(R)-261, Seal Water Heat Exchanger Drain (Hard-piped to SIT)-MD(R)-262, Seal Water Heat Exchanger Drain (Hard-piped to SIT)Charging Pumps from the VCT to Charging line (continued on OPERXK-100-35) and SealWater Injection line, Including Seal Water Injection Bypass line, (continued on OPERXK-100-35) up to the following Boundary Isolation Valves:-CVC-301/MV-32056, RWST Supply To Charging Pumps-CVC-302, RWST Emergency Suct Isol-CVC-30C, IC Charging Pump Vent (Hard-piped to Zone SV ductwork)

-CVC-30B, 1B Charging Pump Vent (Hard-piped to Zone SV ductwork)

-CVC-30A, 1A Charging Pump Vent (Hard-piped to Zone SV ductwork)

-CVC-230A, Seal Supply Line Filter 1A Drain (Hard-piped to SIT)-CVC-230B, Seal Supply Line Filter 1B Drain (Hard-piped to SIT)Reactor Makeup supply piping to the VCT and Charging Pump suction, up to the following Boundary Isolation Valves:MU-1020, Makeup Water Line isol-CVC-412, Blndr Mkup To Rfiling Water Storage Tank IsolCVC-413, Blended Makeup to Spent Fuel Pit IsolBoric Acid Supply to the Reactor Makeup piping (continued on OPERXK-100-38)

Form No. 732125 (Apr 2013)

DOF0mINIOn SSC Category Determination DocumentI P M DC-Y Atacm en B ae6*f2The following valves will be abandoned and have stem leakoff lines to the Deaerated Drains Tank (DDT). They will be abandoned up to their respective stem leakoff lineBoundary Isolation Valves:-LD-1O/CV-31099, Letdown Cont Pressure:

-LD-61, LD-10 Valve Stem Leakoff-MU-1022/CV-31095, Blender Control Rx MU Flow:-MU-1022-1, MU-1022 Valve Stem Leakoff-LD-27/CV-31096, VCT/Holdup Tank Divert ValveLD-51, LD-27 Valve Stem Leakoff-CVC-7/CV-31103, Charging Control Chg Line:-CVC-60, CVC-7 Valve Stem Leakoff-CVC-200/CV-31688, Seal Injection Filter Block Valve:-CVC-200-1, CVC-200 Valve Stem Leakoff-CVC-203B/CV-31689, Seal Injection Filter Bypass Valve:CVC-203B-1, CVC-203B Valve Stem LeakoffOperations Critical Drawing OPERXK-100-37, Chemical

& Volume Control System (Revision AH)-Abandon CVC Holdup Tank fill header up to Boundary Isolation Valve CVC-802, ReactorCoolant Drn Tank Pump Discharge

-CVC Holdup Tanks A, B, and C, Including Recirculation Pump and Gas Stripper Feed PumpsA & B, up to the following Boundary Isolation Valves:-NG-715A, Holdup Tank 1A to Vent Header Isol-MG(R)-519A, Holdup Tank 1A Vent-MG(R)-516A, Holdup Tank 1A to Gas Analyzer Isol-CVC-813A, Holdup Tank 1A Drain (Hard-piped to DDT)-NG-715B, Holdup Tank 1B to Vent Header Isol-MG(R)-S19B, Holdup Tank 1B Vent-MG(R)-S16B, Holdup Tank 1B to Gas Analyzer Isol-CVC-813B, Holdup Tank 1B Drain (Hard-piped to DDT)-NG-715C, Holdup Tank 1C to Vent Header Isol-MG(R)-519C, Holdup Tank 1C Vent-MG(R)-516C, Holdup Tank 1C to Gas Analyzer Isol-CVC-813C, Holdup Tank IC Drain (Hard-piped to DDT)Evaporator Feed Ion Exchanger

1 up to the following Boundary Isolation Valves:-CVC-855A,

1 Evap Feed Ion Exch Vent (Hard-piped to SIT)-CVC-856A,

1 Evap Feed Ion Exch Drain (Hard-piped to SIT)-CVC-857A,

1 Evap Feed Ion Exch Resin Disch (hard-piped to Spent Resin StorageTank)-DW-214A,

1 Evap Feed Ion Exch BackwashEvaporator Feed Ion Exchanger

2 up to the following Boundary Isolation Valves:Form No. 732125 (Apr 2013)66I66SSS60000000000000000000000000S 00*S00S000000S00000000000S0Dominion' SSC Category Determination Document0PK -DCSY 0 -Atahmn B*ae7 f2CVC-855B,

2 Evap Feed Ion Exch Vent (Hard-piped to SIT)CVC-856B,

2 Evap Feed Ion Exch Drain (Hard-piped to SIT)CVC-857B,

2 Evap Feed Ion Exch Resin Disch (hard-piped to Spent Resin StorageTank)DW-214B,

2 Evap Feed Ion Exch BackwashEvaporator Feed Ion Exchanger

3 up to the following Boundary Isolation Valves:CVC-859,

3 Evap Feed Ion Exch Vent (Hard-piped to SIT)CVC-861,

3 Evap Feed Ion Exch Drain (Hard-piped to SIT)-CVC-860,

3 Evap Feed Ion Exch Resin Disch (hard-piped to Spent Resin StorageTank)-DW-215, #3 Evap Feed Ion Exch BackwashBoric Acid Evap Feed Ion Exchange Filter up to Boundary Isolation Valve CVC-865, IonExchange Filter Drain (Hard-piped to SIT)Evaporator Condensate Demineralizers

1 and #2 up to the following Boundary Isolation Valves:-CVC-944A,

1 Evap Condensate Demin Vent (Hard-piped to SIT)-CVC-945A,

1 Evap Condensate Demin Resin Disch (hard-piped to Spent ResinStorage Tank)-CVC-944B,

2 Evap Condensate Demin Vent (Hard-piped to SIT)-CVC-945B,

2 Evap Condensate Demin Resin Disch (hard-piped to Spent ResinStorage Tank)-DW-219-1A, Regenerant Chemical Line Flush-DW-219-1B, Demin Water to Demineralizers Isol-CVC-936, Backwash Line Drain (Hard-piped to SIT)CVC Monitor Tanks A & B, Including Condensate Filter, and Monitor Tank Pumps A and B,up to the following Boundary Isolation Valves:-DW-151A, Demin Water to 1A Monitor Tank-DW-151B, Demin Water to 1B Monitor Tank-CVC-916, Tank Pumps DIsch to RMW Storage Tank-Monitor Tank Pumps Disch to Waste Discharge Line (continued on DrawingOPERXK-100-131)

-Abandon 2" lines from SGBT Sys & Waste Evap Dist. Filter (continued on DrawingOPERM-368) that enter CVC Monitor Tank A & B fill line.Operations Critical Drawing OPERXK-100-38, Chemical

& Volume Control System (Revision Z)Abandon Concentrates Holding Tank, Concentrates Holding Tank Heater, andConcentrates Holding Tank Transfer Pumps A and B, up to the following BoundaryIsolation Valves:-CVC-620, Boric Acid Evap to Waste Evap-CVC-637, BA Evap to Waste Concentrates TankForm No. 732125 (Apr 2013)

SDominion SSC Category Determination DocumentI OPMDCSY 1- Atacmn B Pag 8 f 2Abandon Boric Acid Batch Tank and Batching Tank Agitator, up to the following BoundaryIsolation Valves:-DW-250, Demineralized Water Supply to Batching Tank-HS-5475, Batching Tank Htg Coils Outlet To Trap-HS-5478, Batching Tank Htg Coils Outlet Trap BypassAbandon Boric Acid Storage Tanks A and B, Boric Acid Storage Tanks A and B Heaters, andBoric Acid Transfer Pumps A and B, up to the following Boundary Isolation Valves:-CI-531, Caustic Inlet for PH Adjustment

-MU-1031A, RMW to 1A Boric Acid Transfer Pump-MU-1031B, RMW to 1B Boric Acid Transfer Pump-CVC-739, Boric Acid Alternate Supply to Safety Inj Sys-SI-1A, Boric Acid Tank 1A to SI Pumps Suct Isol-SI-1B, Boric Acid Tank 1A to SI Pumps Suct IsolOperations Critical Drawing OPERXK-100-400, 15 GPM Boric Acid Evap. + Gas Stripper FlowDiagram (Revision 12T)Abandon the entire Boric Acid Evaporator

package, Including the Evaporator, Stripping Column, Absorption Tower, Evaporator Condenser, Vent Condenser, Feed Preheater, Distillate Cooler, Distillate Pumps 1A and 1B, and Boric Acid Concentrate Pumps 1A and1B, up to the following Boundary Isolation Valves:BEF-35/CV-31288, Evaporator Drain Valve (Hard-piped to Sump Tank)*NOTE* There is no manual isolation valve in the Evaporator Drain line to theSump Tank. BEF-35 needs to be failed close to serve as a Boundary Isolation Valve. As shown on Drawing E-2029, Integrated Logic Diagram Chemical

&Volume Control System, BEF-35/CV-31288 fails closed with no Instrument Air.-BEF-4-1, Vent Condenser Vent Isolation

-HS-403-1, BA Evap Vent Relief Valve Bypass-MG(R)-550, Vent Hdr #2 to WGA Filter Inlet Isol-SW-5027-1, SW to BA Evap Distillate Sample Cooler-Abandon Nitrogen Supply line to the Evaporator Condenser, including valves: NG-913/CV-31283 and NG-912/CV-31282.

Nitrogen supply line continued on drawingOPERM-216, Miscellaneous Gas Systems.-Abandon Demineralized Water Supply piping to the Vent Condenser, Evaporator Condenser, Absorption Tower, Evaporator, and Boric Acid Concentrates Pumps A& B. Demineralizer Supply lines continued on drawing OPERM-209-2, Make-UpAnd Demineralized Water SystemsOperations Critical Drawing OPERM-216, Miscellaneous Gas Systems (Revision CV)Abandon all piping downstream of Boundary Isolation Valve NG-911, Nitrogen to BA EvapAbandon all piping downstream of the following Boundary Isolation Valves:-NG-802, Nitrogen to VCT Line Isolation Form No. 732125 (Apr 2013)0000S0S00S0000000S0000000000000 00000000S0000000000S000000000DominlowSSC Category Determination DocumentOP* W-ECS YC00 -At c m n B P ag 9of2 _-HG-302, Hydrogen to VCT Line Isolation Operations Critical Drawing OPERM-209-2, Make-Up And Demineralized Water Systems (Revision P)-Abandon all piping downstream of the following Boundary Isolation Valves:-DW-140, Evap Flush Conn from Makeup Water-DW-216, Demineralized Water To Demineralizers Operations Critical Drawing OPERXK-100-44, Sampling System (Revision AT)-Abandon all piping downstream of Boundary Isolation Valve RC-438, Sample Outlet to VCTOperations Critical Drawing OPERXK-100-19, Component Cooling System (Revision AQ)-Abandon the Seal Water Heat Exchanger, Including all Component Cooling Water piping,valves, and Instrumentation up to the following Boundary Isolation Valves:-CC-200, Seal Water Heat Exchanger Inlet-CC-203, Seal Water Heat Exchanger Outlet Isolation

-Abandon the Letdown Heat Exchanger, including all Component Cooling Water piping,valves, and Instrumentation up to the following Boundary Isolation Valves:-CC-300, Letdown Heat Exchanger Inlet-CC-310, To Hi Rad Sample Hxs-CC-318, From HI Rad Sample Hxs-CC-303, Letdown Heat Exchanger Outlet*NOTE* Isolating the Component Cooling side of the Letdown Heat Exchanger alsoisolates the Component Cooling side of the Residual Heat Removal High Radiation SampleHeat Exchanger and Reactor Coolant High Radiation Sample Heat Exchanger.

TheseSample Heat Exchangers are not evaluated under this abandonment plan.Operations Critical Drawing OPERXK-100-20, Component Cooling System (revision AE)-Abandon the Boric Acid Evaporator, including all Component Cooling Water piping, valves,and Instrumentation up to the following Boundary Isolation Valves:CC-800, Main CC Supply to Boric Acid EvapCC-809, Boric Acid Evap Return Isolation Operations Critical Drawing OPERXK-100-132, Waste Disposal System (Revision AH)-Abandon all piping from Gas Stripper Boric Acid Evaporator (Vent Condenser) vent line(continued from OPERXK-100-400) up to the following Boundary Isolation Valves:-BEF-4-1, Vent Condenser Vent Isolation

-MG(R)-550, Vent Hdr #2 to WGA Filter Inlet IsolOperations Critical Drawing OPERM-368, Steam Generator Blowdown Treatment System (Revision AM)Abandon all piping downstream of the following Boundary Isolation Valves:-BT-232A, SGBT To CVC Monitor Tank 1AForm No. 732125 (Apr 2013)

' Dominion° SSC Category Determination Document6P-K -E-Y 01 -Atacnn B. Pag 10o2-BT-232B, SGBT To CVC Monitor Tank 1BOperations Critical Drawing OPERM-350, Reactor Plant Misc. Vents, Drains, & Sump Pump Piping(Revision AZ)-Abandon all piping downstream of the following Boundary Isolation Valves:-MD(R)-307A, DDT To CVC Holdup Tank A-MD(R)-307B, DDT To CVC Holdup Tank B-MD(R)-307C, DDT to CVC Holdup Tank C-Abandon all piping upstream of Boundary Isolation Valve LD-61, LD-10 Valve Stem Leakoff-Abandon all piping upstream of Boundary Isolation Valve MU-1022-1, MU-1022 ValveStem Leakoff-Abandon all piping upstream of Boundary Isolation Valve CVC-60, CVC-7 Valve StemLeakoff-Abandon all piping upstream of Boundary Isolation Valve LD-S1, LD-27 Valve Stem Leakoff-Abandon all piping upstream of Boundary Isolation Valve CVC-200-1, CVC-200 Valve StemLeakoff-Abandon all piping upstream of Boundary Isolation Valve CVC-203B-1, CVC-203B ValveStem Leakoff-Abandon the Seal Water Heat Exchanger, and all piping upstream of the following Boundary Isolation Valves:MD(R)-260, Seal Water Heat Exchanger DrainMD(R)-261, Seal Water Heat Exchanger DrainMD(R)-262, Seal Water Heat Exchanger Drain-Abandon the Letdown Heat Exchanger, and all piping upstream of the following BoundaryIsolation Valves:-MD(R)-270, Letdown Heat Exchanger DrainMD(R)-271, Letdown Heat Exchanger Drain-MD(R)-272, Letdown Heat Exchanger Drain-MD(R)-273, Letdown Heat Exchanger DrainOperations Critical Drawing OPERM-605-1, Heating System (Revision R)-Abandon all steam piping for the Boric Acid Batching Tank:-Downstream of Boundary Isolation Valve HS-475, Steam Supply to CVCS BatchingTank-Upstream of the following Boundary Isolation Valves:HS-5475, Batching Tank Htg Coils Outlet To TrapHS-5478, Batching Tank Htg Coils Outlet Trap Bypass-Abandon all steam and condensate piping for the Boric Acid Evaporator, Boric AcidEvaporator Feed Preheater, Boric Acid Evap Condensate Return Heat Exchanger, BoricAcid Evaporator Condensate Return Tank, and Condensate Return Pumps 1A and 1B:-Downstream of the following Boundary Isolation Valves:-HS-401, Boric Acid Evaporator Inlet-HS-410, BA Evap Steam Line Trap Inlet-Upstream of the following Boundary Isolation Valves:-HS-7402A, Condensate Return Pump 1A Discharge Form No. 732125 (Apr 2013)I.I.teS00S00000SS0S00000000000SSSS0S 000.0000000S0000000S000S00Dominion' SSC Category Determination Document0 K -DCS Y-0 -I Atahmn B ae1of2-HS-7402B, Condensate Return Pump 1B Discharge Operations Critical Drawing OPERM-606, Air Cond. Cooling Water Piping (Revision BY)-Abandon the Boric Acid Evaporator Condensate Return Heat Exchanger, all Service Waterpiping, and Instrumentation between the following Boundary Isolation Valves:-Downstream of SW-1256, BA Evap Cond Return Heat Exch Inlet-Upstream of SW-1257, From BA Evap Cond Return Heat ExchOperations Critical Drawing OPERXK-100-29, Safety Injection System (Revision AN)-Abandon all piping upstream of Boundary Isolation Valve CVC-412, Blndr Mkup To RflingWater Storage Tank IsolOperations Critical Drawing OPERXK-100-131, Waste Disposal System (Revision CQ)-Abandon all piping upstream of Boundary Isolation Valve CVC-920, CVC Monitor TankPump to Discharge Line-Abandon all piping upstream of Boundary Isolation Valve CVC-936, Backwash Line Drain-Abandon all piping upstream of Boundary Isolation Valve CVC-553, Deborating Demineralizers Drain.Abandon all piping upstream of Boundary Isolation Valve CVC-620, Boric Acid Evap toWaste Evap-Abandon all piping upstream of Boundary Isolation Valve CVC-802, Reactor Coolant DrnTank Pump Discharge Operations Critical Drawing E-240, 4160V & 480V Power Sources-Abandon 480V Bus 1-52 Breaker 15203, Charging Pump 1C, to loadOperations Critical Drawing E-254, Circuit Diagram 480 V MCC 1-35A, 1-35D, 1-45A & 1-45D-Abandon from the 480V Breaker to load:-480V MCC 1-35A (52), Boric Acid Evaporator Package-480V MCC 1-35A (B7), Boric Acid Evaporator Condensate Return Pump 1A-480V MCC 1-45A (57), Boric Acid Evaporator Condensate Return Pump 1B-480V MCC 1-35D (56), CVC Monitor Tank Pump 1A-480V MCC 1-45D (A6), CVC Monitor Tank 15-480V MCC 1-45D (55), Boric Acid Batching Tank AgitatorOperations Critical Drawing E-255, Circuit Diagram 480 V MCC 1-35B & 1-45B-Abandon from the 480V Breaker to load:-480V MCC 1-35B (B6), Concentrates Holding Tank Heater-480V MCC 1-35B (A7), Gas Stripper Feed Pump 1A-480V MCC 1-35B (B1), Concentrates Holding Tank Transfer Pump 1A-480V MCC 1-35B (AS), Hold Up Tank Recirculation Pump-480V MCC 1-45B (C8), Gas Stripper Feed Pump 1B-480V MCC 1-45B (B3), Concentrates Holding Tank Transfer Pump 1BOperations Critical Drawing E-258, Circuit Diagram 480V MCC 1-52A, 1-52F, & 1-52B-Abandon from the 480V Breaker to load:-480V MCC 1-52B (F4), Seal Water Leak Off Isolation MV CVC212/32115

-480V MCC 1-52B (Al), Boric Acid Tank 1A Immersion Heater 1A1-480V MCC 1-52B (B1), Volume Control Tank To Charging Pumps Isolation MVCVCl/32057 Form No. 732125 (Apr 2013)

SDominton" SSC Category Determination Document* I OPK -E -Y*0 --tah et8 Pae1 f2-480V MCC 1-52B (E5), Boric Acid Transfer Pump 1A-480V MCC 1-52B (A2), Boric Acid Tank 1B Immersion Heater 1B1Operations Critical Drawing E-259, Circuit Diagram 480V MCC 1-62D & 1-62E-Abandon from the 480V Breaker to load:-480V MCC 1-62E (A6), Charging Pump 1B-480V MCC 1-62E (H4), Boric Acid Transfer Pump 18-480V MCC 1-62E (J2), Boric Acid Tank 1B Immersion Heater 1B2-480V MCC 1-62E (Ji), Boric Acid Tank 1A Immersion Heater 1A2Operations Critical Drawing E-260, Circuit Diagram 480V MCC 1-52C, 1-52E & 1-62C-Abandon from the 480V Breaker to load:-480V MCC 1-52E (D3), Refueling Water Emergency Make-Up To Charging PumpMV CVC301/32056

-480V MCC 1-52E (F3), Emergency Boration From Boric Tank MV CVC440/32127

-480V MCC 1-52E (H4), Charging Pump 2AOperations Critical Drawing E-261, Circuit Diagram 480V MCC 1-62A, 1-52D, 1-5262 & 1-62B-Abandon from the 480V Breaker to load:-480V MCC 1-62B (DS), Residual Heat Exchanger Outlet To LTDN Line MVLD60/32099 Operations Critical Drawing OPERM-213-2, Station & Instrument Air System (Sheet 2, Revision R)-Abandon all Instrument Air piping for CVC-7/CV-31103, Charging Lihe Flow Control Valvedownstream of the following Boundary Isolation Valves:-IA-31103-1, IA'to CVC-7-IA-421, Instrument Air to CVC-7-Abandon all Nitrogen

Bottles, piping, instrumentation, and regulators for Nitrogen BackupSupply to CVC-7/CV-31103, Charging Line Flow Control Valve-Abandon all Instrument Air piping for LD-27/CV-31096, VCT/Holdup Tank Divert Valve,downstream of the following Boundary Isolation Valves:-IA-31096-1, IA to LD-27-IA-31096-2, IA to LD-27-Abandon all Instrument Air piping for LD-22/CV-31242, VCT/Deborator Divert Valve,downstream of Boundary Isolation Valve IA-31242, IA to LD-22-Abandon all Instrument Air piping for LD-6/CV-31234, Letdown Line Isolation, downstream of the following Boundary Isolation Valves:-IA-31234-1, IA to LD-6-IA-31234-2, IA to LD-6-Abandon all Instrument Air piping for LD-14/CV-31098, LD Demin High Temp Divert Valve,downstream of Boundary Isolation Valve IA-31098, IA to LD-14-Abandon all Instrument Air piping for LD-10/CV-31099, Letdown Cont Pressure, downstream of the following Boundary Isolation Valves:-IA-31099-1, IA to LD-1O-IA-31099-2, IA to LD-1O-IA-31099-3, IA to LD-10Form No. 732125 (Apr 2013)SI.006S00S000S0S0000000000000000 00S00S0000S00000000000DominionSSC Category Determination DocumentS. IOperations Critical Drawing OPERM-213-5, Station & Instrument Air System (Sheet 5, Revision AE)-Abandon all Instrument Air piping for BA Evaporator, instrumentation, and control valvesdownstream of Boundary Isolation Valve IA-1603, IA Header Isolation

-Abandon all Instrument Air piping for Concentrates Holding Tank level and temperature downstream of Boundary Isolation Valve IA-1607, IA isolation for 22021 and 24022.-Abandon all instrument Air piping for CVC-403/CV-31092, Boric Acid To Blender, CVC-406/CV-31094, BA Blender To VCT, and CVC-408/CV-31093, BA Blender To ChargingPumps, downstream of Boundary Isolation Valve IA-1430, IA Header Isolation.

-Abandon all Instrument Air piping for Boric Acid Evaporator Feed Flow Indication, downstream of Boundary Isolation Valve IA-18236, IA Isolation for 23069.-Abandon all Instrument Air piping for MU-1022/CV-31095, Reactor Makeup Water ToBlender, downstream of the following Boundary Isolation Valves:-IA-31095-1, IA to MU-1022-IA-31095-2, IA to MU-1022-Abandon all Instrument Air piping downstream of Boundary Isolation Valve IA-1407, IA toCVC-200 & 203B, for the following valves:LO-13A/CV-31685, Rx Coolant Filter Block Valve-CVC-212-1/CV-31683, Seal Water Filter Block Valve-CVC-200/CV-31688, Seal Injection Filter Block Valve-CVC-203B/CV-31689, Seal Injection Filter Bypass Valve-CVC-215B/CV-31682, Seal Water Filter Bypass Valve-LD-13B/CV-31684, Rx Coolant Filter Bypass Valve-Abandon all Instrument Air piping for CVC-832/CV-31626, Gas Stripper Feed Pumps RecircLine Control Valve, downstream of Boundary Isolation Valve IA-31626, IA to CVC-832-Abandon all Instrument piping for the Boric Acid Evaporator Control Panel downstream ofBoundary Isolation Valve IA-1429, IA To BA Evap Panel.-Abandon all instrument Air piping downstream of the following Boundary Isolation Valves:-IA-24018, IA to CVC HUT B Level-IA-24017, IA to CVC HUT A Level-IA-24020, IA to CVC Mon Tank A Level-IA-24021, IA to CVC Mon Tank B Level-IA-24061, IA to BA Batch Tank Level-IA-31105-1, IA to HS-476-IA-31105-2, IA to HS-476Operations Critical Drawing OPERM-213-6, Station & Instrument Air System (Sheet 6, Revision R)-Abandon all Instrument Air piping for CVC-712A/CV-31106, BAT Recirc Control Tank A,downstream of the following Boundary Isolation Valves:-IA-31106-1, IA to CVC-712A-IA-31106-2, IA to CVC-712A-Abandon all Instrument Air piping for CVC-712B/CV-31107, BAT Recirc Control Tank B,downstream of the following Boundary Isolation Valves:-IA-31107-1, IA to CVC-712B-IA-31107-2, IA to CVC-712BForm No. 732125 (Apr 2013)

' Dominion SSC Category Determination DocumentI .OPK -E-Y-0 -Atahm n B Pag 14 of2Operations Critical Drawing OPERM-213-8, Station & Instrument Air System (Sheet 8, Revision 1)Abandon all Instrument Air Piping, and Accumulator, downstream of Boundary Isolation Valve IA-166-1, IA to LD-4A(B)(C),

CVC-11, & CVC-15, for the following valves:-LD-4A/CV-31231, Letdown Orifice A Isolation

-LD-4B/CV-31232, Letdown Orifice B Isolation

-LD-4C/CV-31233, Letdown Orifice C Isolation

-CVC-11/CV-31229, Charging Line Isolation

-CVC-15/CV-31230, Przr Auxiliary Spray ValveAbandon all Instrument Air Piping, and Accumulator, downstream of Boundary Isolation Valve IA-147, IA to LD-2 & LD-3, for the following valves:LD-2/CV-31108, Letdown Isolation LD-3/CV-31104, Letdown Isolation 4.0 Evaluation (Basis for choosing category type):Purpose/Function The Chemical and Volume Control System:1. Adjusts the concentration of chemical neutron absorber for chemical reactivity control2. Maintains the proper water Inventory In the RCS3. Provides the required seal water flow for the reactor coolant pump shaft seals4. Processes reactor coolant letdown for reuse of boric acid5. Maintains the proper concentration of corrosion Inhibiting chemicals in the reactorcoolant, and6. Keeps the reactor coolant fission product and corrosion product activities to withindesign levels.The system is also used to fill and hydrostatically test the RCS.During normal operation, therefore, this system has provisions for supplying:

1. Hydrogen to the volume control tank2. Nitrogen as required for purging the volume control tank3. Hydrazine or pH control chemical, as required, via the chemical mixing tank to thecharging pumps suction.Additionally, reactivity control is provided by the Chemical and Volume Control Systemwhich regulates the concentration of boric acid solution neutron absorber in the ReactorCoolant System.The system Is also designed to prevent uncontrolled or Inadvertent reactivity changes,which might cause system parameters to exceed design limits.Boric Acid as a chemical shim is used in combination with Control Rods to provide controlof the reactivity changes of the core throughout the life of the core at power conditions.

This chemical shim control is used to compensate for the more slowly occurring changes Inreactivity throughout core life such as those due to fuel depletion, fission product buildupand decay, and the xenon transient associated with power level changes.Form No. 732125 (Apr 2013)S0SSS000000000000000S0 000*0DoOO0O00000O0O0000OinionlBasis for CategorySSC Category Determination Document0 K -DCS Y 0 -S tahet B Pag 15of2On May 15, 2103, the NRC docketed DEKs certification of permanent defueling of theKewaunee Power Station.

Therefore, effective Immediately, pursuant to 10 CFR50.82(a)(1)(ii),

the 10 CFR Part 50 license for KPS no longer authorizes operation of thereactor or emplacement or retention of fuel into the reactor vessel, as specified In 10 CFR50.82(a)(2).

With irradiated fuel being stored in the SFP and the ISFSI, the reactor, RCS and secondary system are no longer in operation and have no function related to the storage of theirradiated fuel. Therefore, the postulated accidents involving failure or malfunction of thereactor, RCS or secondary system are no longer applicable.

The analyzed accident andoperational event applicable to KPS in the permanently shut down and defueled condition (long term SAFSTOR condition) is a fuel handling accident (FHA) in the auxiliary building.

The Gas Decay Tank Rupture accident will not be credible following abandonment of theGaseous Waste System, scheduled to be completed in August of 2013.The basis for the abandonment category for the Chemical and Volume Control System isdetermined by screening to the following criteria:

1. To prevent or mitigate the consequences of a design basis accident of a permanently defueled plant.2. Fuel Handling Accident and Gas Decay Tank Rupture as defined in Updated safetyAnalysis Report (USAR).3. For safe storage and handling of radioactive waste or spent fuel.4. To support the technical Specifications, License Requirements, Design Basis, Permits,regulatory requirements, insurance requirements, or other commitments.

Provide supportfor safe storage of Spent Fuel and the Radiological Effluent Monitoring/Offslte DoseCalculation Manual for KPS.5. The requirements of SSCs that support the execution of plans and programs at KPS (e.g.,Security Plan, Fire Protection Plan, Emergency Management Plan, Radiation Protection Program).

Form No. 732125 (Apr 2013)

, ominion" SSC Category Determination DocumentOPMDC-Y-0

-Atahmn B Pag S1 f26. Support day to day operations in the decommissioning plant.7. Support decommissioning efforts.The Chemical and Volume Control System Is no longer required to perform/support theneeds of the above criteria and is therefore abandoned.

Regulatory ImpactUPDATED SAFETY ANALYSIS REPORT (USAR)Reviewed all sections of the USAR, and the following sections\subsections reference theChemical And Volume Control System:Chapter 1: Introduction Under Section 1.3: General Design Criteria, Subsection 1.3.5: Reactivity

Control, the CVCS isbriefly described under topic #6: Maximum Reactivity Worth of Control Rods:In addition to the reactivity control achieved by the RCC assemblies (RCCA), reactivity control Is provided by the Chemical and Volume Control System which regulates thecdncentration of boric acid solution neutron absorber in the Reactor Coolant System.The system is designed to prevent uncontrolled or inadvertent reactivity

changes, whichmight cause system parameters to exceed design limits.The chemical shim control (CVCS) is used to compensate for the more slowly occurring changes In reactivity throughout core life such as those due to fuel depletion, fissionproduct buildup and decay, and load follow.Any time that the plant Is at power, the quantity of boric acid ready for Injection alwaysexceeds that quantity required for normal cold shutdown.

Chapter 3: ReactorUnder Section 3.1: Design Bases, Subsection 3.1.2: Principal Design Criteria, the CVCS isdiscussed under topic 3.1.2.6:

Reactivity Holddown Capability:

The reactivity control systems provided are capable of making and holding the coresub-critical under accident conditions, in a timely fashion with appropriate margins forcontingencies.

Normal reactivity shutdown capability is provided within 2 secondsfollowing a trip signal by the insertion of the RCCAs with soluble poison (boric acid)injection used to compensate for the long-term xenon decay transient and for plantcooldown.

Any time that the reactor Is at power, the quantity of boric acid retained In theboric acid tanks and Refueling Water Storage Tank (RWST) Is ready for injection alwaysexceeds that required for the normal cold shutdown condition.

This quantity also exceedsthat required to bring the reactor to hot shutdown (Hot Shutdown defined as: Reactivity inAk/k is the Required Shutdown Margin in COLR (Cycle 32 requires Shutdown Margin ý: 1554Form No. 732125 (Apr 2013).00I.000000000000000000000000000000000000 0000 om0S00SS0000000000000WOWn~SSC Category Determination DocumentOPK -E-Y 0 -Atahmn B Pag 17of2pcm), Coolant Temperature

> 54001F, and = 0% fission power) and to compensate forsubsequent xenon decay.Boric acid Is pumped from the boric acid tanks by the boric acid transfer pumps to thesuction of one-of-three charging pumps, which inject boric acid into the reactor coolant.Any charging pump and any boric acid transfer pump can be operated from dieselgenerator power on loss of offsite power. Boric acid can be Injected by one pump at a ratewhich takes the reactor to hot shutdown with no rods inserted, and also compensates forxenon decay. Additional boric acid injection is employed If It is desired to bring the reactorto cold shutdown conditions.

Based on the above, the Injection of boric acid Is shown to afford backup reactivity shutdown capability, independent of the RCCAs which normally serve this function in theshort-term situation.

Shutdown for long-term and reduced-temperature conditions can beaccomplished with boric acid Injection using redundant components, thus achieving themeasure of reliability implied by the criterion.

Chapter 6: Engineered Safety FeaturesUnder Section 6.5: Leakage Detection And Provisions For The Primary And Auxiliary CoolantLoops, Subsection 6.5.1: Leakage Detection

Systems, Subsection 6.5.1.2:

Systems DesignAnd Operation, CVCS is discussed under topic 6.5.1.2.9:

Charging Pump Operation:

During normal operation charging pumps are operated as necessary to maintain Inventory In the reactor coolant system. Leakage from the reactor coolant system will cause adecrease In the pressurizer level. If the charging pump(s) are in automatic

control, anincrease in charging pump speed will occur. If the pump(s) are in manual control, adecreasing volume control tank level and/or low pressurizer level will cause an alarm toactuate.Any automatic increase in charging pump speed will try to maintain the equivalence between the letdown flow and the combined charging line flow and the flow across thereactor coolant pumps seals. If the pump(s) reach a high speed limit, an alarm Is actuated.

Also under topic 6.5.1.2.10:

Liquid Inventory:

Gross leaks might be detected by unscheduled increases in the amount of reactor coolantmakeup water, which is required to maintain the normal level In the pressurizer.

This isinherently a low precision measurement, since makeup water is also necessary for leaksfrom systems outside the containment.

Chapter 7: Instrumentation

& ControlsUnder Section 7.3: Regulating

Systems, Subsection 7.3.2: System Design, CVCS Is discussed under topic 7.3.2.5:

Pressurizer Level Control:A programmed pressurizer water level as a function of auctioneered average reactorcoolant temperature Is provided in conjunction with the programmed coolantForm No. 732125 (Apr 2013)

WDominion" SSC Category Determination Documente* -ECS Y ta h e tB Pa e1 f2temperature.

This minimizes the demands upon the Chemical and Volume Control Systemand the Waste Disposal System imposed by coolant density changes during loading andunloading.

The pressurizer water level decreases as the load is reduced from full load. Thisis the result of coolant contraction following programmed coolant temperature reduction from full power to low power. The programmed level Is designed to match as nearly aspossible the level changes resulting from the coolant temperature changes.

To permitmanual control of pressurizer level during startup and shutdown operations, the charging-pump speed can be manually regulated from the main Control Room.Under Section 7.7: Operating Control Stations, Subsection 7.7.6: Emergency ShutdownControl, Subsection 7.7.6.1:

Equipment Control Outside Control Room (specifically theDedicated Shutdown Panel), CVCS Is discussed under the following topics:7.7.6.1.2 Reactivity ControlFollowing plant shutdown to the hot shutdown condition, boric acid Is added to the RCS tomaintain sub-criticality.

For boron addition, the Chemical and Volume Control System isused. Boration requires the use of:1. Charging pumps and volume control tank with associated piping.2. Boric acid transfer pumps with tanks and associated piping.It should be noted that with the reactor held at hot shutdown conditions, boration of theplant Is not required Immediately after shutdown.

The xenon transient does not decay tothe equilibrium level until some ten to fifteen hours after shutdown, and a further periodwould elapse before the 1 percent reactivity shutdown margin provided by the full-length control rods would be cancelled.

This delay would provide ample time for emergency measures.

7.7.6.1.3 Pressurizer Pressure and Level ControlFollowing a reactor trip, the reactor coolant temperature will automatically reduce to theno-load temperature condition as dictated by the steam generator temperature conditions.

This reduction in the reactor coolant water temperature reduces the reactor volume, and ifcontinued pressure control Is to be maintained, reactor coolant makeup Is required.

The pressurizer level is controlled in normal circumstances by the CVCS. The facility forboration Is provided as described above; it is necessary only to supply water for makeup.Water may be readily obtained from normal sources such as the reactor makeup storagetanks or RWST.Under Section 7.7: Operating Control Stations, Subsection 7.7.6: Emergency ShutdownControl, Subsection 7.7.6.2:

Indication And Controls Outside Control Room, CVCS isdiscussed under the Dedicated Shutdown Panel as follows:* Controls:

Start/stop motor controls along with a selector switch are provided for Charging Pump 1C.These controls are located on the dedicated shutdown panel. The selector switch transfers control of the equipment from the Control Room to the dedicated shutdown panel. Placingthe selector switch in the local position provides an annunciator alarm in the Control Roomand will turn out the Charging Pump IC motor control Indicating lights in the Control Room.* Speed Control:Speed control for two of the charging pumps is provided locally;Form No. 732125 (Apr 2013)S0SSSSSSSSSSSSSSSSSSSS S0Dm00 0000S*000000000mb.oSSC Category Determination Document, aPM DC-Y-0 -s Atahm n B.ae1 f2Speed control for one of the charging pumps is located on the dedicated shutdown panel.0 Valve Control:Letdown orifice isolation valves (Controls mounted on the dedicated shutdown panel.Selector switch and position lamp are also provided).

The control for the charging line flow control valve is located on the dedicated shutdownpanel.Chapter 8: Electrical SystemUnder Section 8.2: Electrical System, Subsection 8.2.4: Station Blackout, CVCS is discussed under the following subsections:

8.2.4.9 Reactor Coolant Inventory The TSC diesel generator will power one of two charging pumps each having a capability ofsupplying water at the rate of 60 gpm. This will provide makeup for a total of 50 gpmreactor coolant pumps seal leakage (25 gpm per pump) and 10 gpm reactor coolant systemleakage (maximum allowed by the TS). The water supply for the pumps will be from therefueling water storage tank. Technical Specifications provide the necessary inventory forfour hours of primary make-up water.8.2.4.12 SBO Modifications An air (nitrogen) supply has been provided for RCS inventory valve CVC-7 in order toprovide control room control of the amount of charging flow to the reactor coolant loopversus the reactor coolant pump seals.Chapter 9: Auxiliary And Emergency SystemsSection 9.2: Chemical And Volume Control System, describes the design bases (section9.2.1), system design and operation, components, and control (section 9.2.2), and theSystem Design Evaluation (section 9.2.3) which addresses availability and reliability, tritiumcontrol, leakage prevention, incident

control, malfunction

analysis, galvanic corrosion, andfuel element failure detection.

Under Section 9.3: Auxiliary Coolant System, Subsection 9.3.2: System Design AndOperation, CVCS is discussed under topic 9.3.2.3:

Spent Fuel Pool Cooling System:Boron addition can be made to the spent fuel pool by use of the boric acid makeup portionof the CVCS.Also under Section 9.3, Subsection 9.3.4: System Evaluation, Subsection 9.3.4.3:

IncidentControl, Subsection 9.3.4.3.2:

Residual Heat Removal System, CVCS is discussed under topic9.3.4.3.2.1:

Low Temperature Overpressure Protection:

Overpressurization transients can result from either a mass Input or an energy Inputtransient, and typically occur when the RCS is in a water solid condition.

The LTOP designassumed as the most limiting mass input transient, an inadvertent start of one SI pump,with two RHR & RXCPs operating.

The design transients considered in the LTOP design alsoincludes a mass addition transient involving all three charging pumps injecting water intoForm No. 732125 (Apr 2013)

VDomion° SSC Category Determination Document0'I OPK -E e-Y 0 -Atah etB Pae2 f2the RCS with the letdown line isolated with two RHR & RXCPs operating.

The most limitingenergy input, i.e., thermal expansion, transient assumed an initial starting of a RXCP withan assumed secondary to primary temperature difference of 100"F, with two RHR pumpsoperating.

Chapter 11: Waste Disposal And Radiation Protection SystemUnder Section 11.1: Waste Disposal System, Subsection 11.1.1: Design Basis, Subsection 11.1.1.1:

Control of Releases of Radioactivity to the Environment, mentions the CVCSystem:The bulk of the radioactive liquids discharged from the Reactor Coolant System (RCS) areprocessed by the boron recycle portion of the Chemical and Volume Control System(CVCS).This design minimizes liquid processed by the Waste Disposal System.Under Subsection 11.1.2: System Design and Operation, CVCS Is described under topic11.1.2.1:

System

Description:

To facilitate

storage, processing and disposal, the Liquid Waste Disposal System is designedto segregate various waste streams at their point of collection Into the following categories:

" Boron recycled distillate (deaerated waste from Boric Acid Evaporator)

Miscellaneous rad waste drains (aerated waste)" Laundry and hot shower wastePart of the boron recycled distillate waste stream (deaerated waste) Is the RCS drainage, which is transferred directly to the CVCS holdup tank or waste holdup tank for processing.

Sources of this drainage include:" Reactor coolant loops" Pressurizer relief tank" Reactor coolant pump secondary seals" Excess letdown (during startup)* Accumulators

Reactor vessel flange leakoffs* Refueling cavity drains* Valve leakoffsThese liquids flow to the reactor coolant drain tank or suction of the reactor coolant draintank pumps and are discharged either directly to the CVCS holdup tanks or to the wasteholdup tank by the reactor coolant drain pumps. These pumps can also return water fromthe refueling cavity to the RWST. There is one reactor coolant drain tank with two reactdrcoolant drain tank pumps located inside of the Containment.

The remaining deaerated liquid waste originates in the CVCS charging and letdown pathsand from miscellaneous equipment drains. These liquid waste streams are collected andhandled In a closed system to minimize the hydrogen explosion hazard and prevent theescape of gaseous radioactivity.

This is accomplished by collecting deaerated waste in aclosed piping system that drains to a deaerated drain tank. The deaerated drain tank isForm No. 732125 (Apr 2013)000000000000000000000000000000000000000 wDominlon" SSC Category Determination Document00000S0S00000SS.I OPM DC SYC00 -Atcmn ae2 f2isolated from the atmosphere by diaphragm valves and diaphragm sealed Instruments.

From the tanks the deaerated waste is pumped to the CVCS holdup tanks for processing through the Boron Recovery System. The CVCS fluid is pumped from the monitor tanks tothe Waste Disposal System through flow meters and discharged in the environment.

Chapter 14: Safety AnalysisCVCS is analyzed under Section 14.1: Core And Coolant Boundary Protection

Analysis, Subsection 14.1.4: Chemical and Volume Control System Malfunction The accident analysis addresses boron dilutions during refueling,

startup, and poweroperation.

Boron.dilutions during Hot Standby, Hot Shutdown, and Cold Shutdown are notpart of the KPS licensing basis.CVCS is also mentioned under Section 14.3: Reactor Coolant System Piping Ruptures(LOCA), Subsection 14.3.2: Loss of Reactor Coolant From Small Ruptured Pipes or FromCracks In Large Pipes Which Actuates Emergency Core Cooling System, Subsection 14.3.2.1:

Identification of Causes and Accident

==

Description:==

A LOCA is defined as a rupture of the RCS piping or of any line connected to the system.Ruptures of small cross section will cause expulsion of the coolant at a rate which can beaccommodated by the charging pumps, which would maintain an operational water level Inthe pressurizer, permitting the operator to execute an orderly shutdown.

However,ruptures of small cross section in lines connected to the pressurizer steam space couldcause the steam discharge through the break to exceed the vapor generation capacity ofthe pressurizer heaters.

This situation would not allow for an orderly shutdown, eventhough an operational water level might be maintained In the pressurizer.

In either case,the coolant which would be released to the containment, contains the fission productsexisting in it.If the break is such that either pressurizer level or pressurizer pressure cannot bemaintained, depressurization of the RCS follows.

Reactor trip occurs when the pressurizer low-pressure trip setpoint is reached.

The SIS is actuated when the appropriate setpoint isreached.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(1i),

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

Since KPS will no longer be authorized to operate or place fuel in the reactor the functions credited in the USAR are no longer required.

The USAR will be revised to addressrequirements following cessation of power operation.

Technical Specifications (TS)Reviewed all sections of TS and the following section is applicable to CVCS:Form No. 732125 (Apr 2013)

Soominion" SSC Category Determination DocumentOPK -D*SY-0 -Atahmn B Pae2. f25.5.2 Primary Coolant Sources Outside Containment The System Integrity Program (SIP) provides controls to minimize leakage from thoseportions of systems outside containment that could contain highly radioactive fluids duringa serious transient or accident to levels as low as practicable.

The systems include SafetyInjection System, Chemical and Volume Control System, Containment Spray System,Miscellaneous Sumps and Drains System, Reactor Building Ventilation System, ResidualHeat Removal System, and Primary Sampling System.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7,2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii),

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

Therefore the System Integrity Program requirements are no longer applicable and theSystem Integrity Program will require revision.

Technical Requirements Manual (TRM)Reviewed all sections of the TRM, and the following section is applicable to the Chemicaland Volume Control System:8.1 REACTIVITY CONTROL SYSTEMS8.1.1 Chemical and Volume Control SystemTNC 8.1.1 The Chemical and Volume Control System shall be FUNCTIONAL consisting of EITHER:a. A flow path from the RWST or BAST via a FUNCTIONAL Chargingpump to the Reactor Coolant System (RCS);ORb. A flow path from the RWST or BAST via a FUNCTIONAL SafetyInjection Pump to the Reactor Coolant System (RCS).APPLICABILITY:

All MODES.With the reactor defueled, the plant condition is NO MODE.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(i1),

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

Since KPS will no longer be authorized to operate or place fuel in the reactor the TRMrequirements for Modes 1-6 and Refueling no longer apply.Offsite Dose Calculation Manual (ODCM)15.1 Major Changes to Radioactive Waste SystemsLicensee Initiated major changes to the radioactive waste systems (liquid, gaseous andsolid) shall be reported to the Commission In the Radioactive Effluent Release Report forForm No. 732125 (Apt 2013)0000000000000000000~0000000000000000000 PDominion SSC Category Determination Document00000S00.00000OP K -D C SY*0 -Ata hm n B Pag 23o 2the period In which the evaluation was reviewed by FSRC. The discussion of each changeshall contain:a. A summary of the evaluation that led to the determination that the change could bemade in accordance with 10 CFR Part 50.59,b. Sufficient information to totally support the reason for the change without benefit ofadditional or supplemental Information,

c. A description of the equipment, components and processes involved and theInterfaces with other plant systems,d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differfrom those previously predicted in the license application and amendments thereto,e. An evaluation of the change, which shows the expected maximum exposures toindividuals in the UNRESTRICTED AREA and to the general population that differfrom those previously estimated In the license application and amendments thereto,f. A comparison of the predicted releases of radioactive materials in liquid andgaseous effluents and in solid waste to the actual releases for the period In whichthe changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change,andh. Documentation of the fact that the change was reviewed and found acceptable by theFSRC.Changes shall become effective upon review and acceptance by the FSRC.This is a complete abandonment of CVCS. On February 25, 2013, DEK submitted acertification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7,2013. On May 15, 2013 the NRC docketed the certification for permanent removal of fuelfrom the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).

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

With the Reactor Coolant Systemabandoned and drained there will be no liquid waste created and no releases from theCVCS. With no liquid entering the CVCS and no releases from CVCS this change results inno increase in maximum exposures In the UNRESTRICTED AREA, to the general population and to plant operating personnel.

Detailed information concerning the predicted releasesand exposure estimates will be Included in the annual Radioactive Effluent Release Report.Shutdown Safety Assessment (SSA)Reviewed OU-KW-201, Shutdown Safety Assessment Checklist (Revision 13), for CVCSrequirements.

Under Attachment 1: Shutdown Safety Assessment (SSA) Checklist, theSpent Fuel Pool Cooling section requires the following:

Form No. 732125 (Apr 2013)

Woominlin" SSC Category Determination DocumentI* OPK -E-Y-0 tahetB Pg 4o II* 3. At least one non-QA SFP makeup flowpath available and Service WaterEmergency Makeup flowpath available (0-1)This requirement is addressed in detail under Attachment 7: Spent Fuel Pool Cooling:* 3. SFP Non-QA Makeup Flowpaths:

" SFP Makeup from RMST's through MU-1099 or via CVC Blender." SFP Makeup from CVC HUT.* SFP Makeup from RWSTFor RMST, RWST, and CVC HUT a usable volume of 15,120 gals shall beavailable.

The CVC HUT combined volume of 60 percent Is required.

RMST greater than 150 percent combined level, to be consistent withother requirements In this procedure.

" RWST level greater than 30 percent to be consistent with otherrequirements in this procedure.

Additionally, further requirements for makeup flow paths available that exceed acapacity of 42 gpm are specified for the following conditions:

Elevated risk on SFP Cooling" Time for SFP to reach 200OF (upon loss of normal cooling) is less than 72hours requires one alternate makeup flowpath capable of providing aminimum of 42 gpm to be protected.

Finally, under General SFP Notes, proceduralized flowpaths that meet the 42 gpmrequirement are specified:

" Makeup directly from the RMSTs via MU-1099, or makeup from the RMSTsthrough the blender in the CVC System (OP-KW-MOP-SFP-O01, OP-KW-NOP-CVC-001).

" Makeup to the SFP from CVC HUT (OP-KW-MOP-SFP-0O1, OP-KW-NOP-CVC-009).

Makeup to the SFP from RWST (OP-KW-MOP-SFP-001).

" Emergency Makeup from Service Water (OP-KW-AOP-SFP-O01, Attachment A).The SSA requirements for Spent Fuel Pool Cooling will still apply. The abandonment of theCVC System will remove the ability to satisfy all of the non-QA-1 Makeup Flowpaths to theSFP. The SFP Non-QA-1 Makeup Flowpaths being abandoned are:* SFP Makeup from the CVC Blender." SFP Makeup from CVC HUT.With these sources being abandoned, the SFP Non-QA-1 Makeup Flowpaths that willremain available are:* SFP Makeup from RMST's through MU-1099.* SFP Makeup from RWSTAttachment 1, Shutdown Safety Assessment (SSA) Checklist, requires ONE non-QA-1 SFPmakeup flowpaths available and Service Water Emergency Makeup flowpath available.

Thisrequirement will remain satisfied after abandoning the CVC System as follows:Form No. 732125 (Apr 2013)I.0I.00I.0600660000000000000000000000000000000 000o 9,.u00000000000000000000000000S000nl onSSC Category Determination DocumentOPK-aCSY 0 U- AtahetB Pae20f2* Both RMST's, and at least one Reactor Makeup Water Pump, will remain available to provide makeup through MU-1099.* The RWST, and the RWST Purification Pump, will remain available to providemakeup to the SFP.* The Service Water System will also remain available.

The requirement Is for at least one non-QA-1 SFP makeup flowpath available and ServiceWater Emergency Makeup flowpath available, and there will be two non-QA-1 SFP makeupflowpaths available.

Licensing Commitments Outstanding commitments to the regulator were reviewed.

The following was found thataffects the Chemical And Volume Control System:Commitment Number: 92-057 Commitment Made to: NRCTitle: BULLETIN 88-08: TEMP. MONITORING

Background:

ADDITIONAL INFORMATION PROVIDED TO THE NRC REGARDING BULLETIN88-08,THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS.Reference letter NRC-92-27, dated 3110192.

Also reference comtrak 92-058.Item 1 -Perform manual temperature monitoring on the Auxiliary Pressure Spray Line toenhance the ability to detect valve leakage.Item 2 -Perform a NDE of a section of pipe located adjacent to CVC-16, to demonstrate theintegrity of that line.On February 25, 2013, DEK submitted a certification of permanent cessation of poweroperations pursuant to 10 CFR 50.82(a)(1)(i),

stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR50.82(a)(1)(ii),

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

Since the KPS license will be modified to a possession only license, the regulatory commitments associated with the Chemical and Volume Control System will not bemaintained.

These commitments will be dispositioned per LI-AA-110, Commitment Management.

This package does not negatively impact the Environmental

Permits, Security Plan,REMM\ODCM, Fire Protection Plan, Health Physics Requirements or Insurance requirements.

Form No. 732125 (Apr 2013) 200minlen' SSC Category Determination DocumentOP6 W-ECS Y 1 -Atahmn B Pag 26of2Plant ImpactThere is no impact on any temporary changes that are active as of 6-4-2013.

The Drawing Control Team did not identify any outstanding drawing changes that requireddisposition as a result of system abandonment.

This DSERT package does not impact Spent Fuel Pool Cooling therefore does not requireFSRC approval.

5.0 Special conditions to support categorization(s):

None6.0 Assumptions/Open Items to be validated or dispositioned:

Validate the assumptions in this document for Spent Fuel Pool Non-QA-1 MakeupFlowpath requirements In the Shutdown Safety Assessment.

Procedure OU-KW-201, Shutdown Safety Assessment Checklist, contains the requirements.

7.0 Expected duration for SSC category if NOT ABANDONED:

N/A8.0 PREPARE and ATTACH the following documents:

09000000000Completed 10 CFR 50.59 Screening or Evaluation, if requiredProposed DUs for appropriate drawingsForm No. 732125 (Apr 2013) 0000000000000S00S0000000Dnominion" SSC Categoty Determination DocumentOPK -D*SY 0 -Atahmn B Pao 7of29.0 Technical Concurrence:

Type Of Review Name (Print)67 A DateEngineering

________

______Type Of Review Name (Print) Approval Signature DateFire Protection

_____ ___ Z *.,,,Type Of Review Name (Print) Approval Signature DateSecurity 86__144 _____ ___S 05z9_6"Type Of Review Name (Print) ISap Sn re DateRadiation Protection

-K' s', s-n 13Type Of Review Name (Print) Appr v I Signature Date10.0 Review and Approval:

Prepa(ed By (Print/Sie)/

"'Reviewed By (Screen Qual.) (Print/Signt)-

Nuclear Lice 'Ing(Print/Si.n)

/ D3Date.L/DateDateDate., l 1 =i,Concurrence by DSERT Coo dl 9tor IJAI Yca AzIFSRC (Prlnt/SIgn)',

If req-uired//

FSRC Meeting Number:13-0-31Form No. 732125 (Apr 2013)

IIIIIIIIIIII6I6I00000000000000000000 0000DOMINIONKewaunee Power StationFSRC MTG # 13-031Facility Safety Review Committee June 19,20131300 Hours0000000000000000000000ATTENDEES:

QuorumChairperson:

FSRC Coordinator:

Presenters:

Guests:SJ Yuen, Chairperson

-Director Decommissioning (I)JD Helbing, Supervisor

-Maintenance (alt)JM Hale, Manager -RP/Chem (I)JJ Madden, Manager -Component and System Engineering (I)JM Schuh, Administrative Assistant, Director Decommissioning DE Dykstra, DSERT Coordinator/Operations SM Cieslewicz, Ops-None-(1) Indicates Chairperson and Members required for quorum per LI-AA-600.

(alt) Alternate Member (nv) Non-Voting MemberThe Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted,FSRC 13-063Miscellaneous ItemPresenter:

Dykstra Approved wicomments

1) CVC documents These require FSRC review due to ODCM 15.1, Major Changes to Radioactive Waste Systems, not because it may impact Spent Fuel Pool Cooling.

Section 15.1of the ODCM states: Licensee initiated major changes to the radioactive wastesystems (liquid, gaseous and solid) shall be reported to the Commission in theRadioactive Effluent Release Report for the period in which the evaluation wasreviewed by FSRC. The discussion of each change shall contain:

a. A summary ofthe evaluation that led to the determination that the change could be made inaccordance with 10 CFR Parl 50.59, b. Sufficient information to totally support thereason for the change without benefit of additional or supplemental information,

c.

FSRC Minutes06/19/13-2-Kewaunee PlantMeeting No. 13-031A description of the equipment, components and processes involved and theinterfaces with other plant systems,

d. An evaluation of the change, which shows thepredicted releases of radioactive materials in liquid and gaseous effluents and/orquantity of solid waste that differ fi'om those previously predicted in the licenseapplication and amendments

thereto,

e. An evaluation of the change, which showsthe expected maximum exposures to individuals in the UNRESTRICTED AREAand to the general population that differ from those previously estimated in thelicense application and amendments

thereto,

f. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste tothe actual releases for the period in which the changes are to be made; g. Anestimate of the exposure to plant operating personnel as a result of the change, andh. Documentation of the fact that the change was reviewed and found acceptable bythe FSRC.Changes shall become effective upon review and acceptance by the FSRC.FSRC reviewed and discussed the documents and identified no safety issues. Thefollowing comments were made:e Page 15, list all accidents or why they were excluded.

Page 25, Under "Plant Impact" uses a date "as of 3-7-2013".

This should beupdated.The Committee recommended approval of the CVC documents with comments andfinal review of the comments by the FSRC chair.Discussion:

0000000000000000000000000000000000FSRC 13-064Miscellaneous ItemPresenter:

Dykstra Approved 0* FSRC Minutes Kewaunee Plant06/19/13 Meeting No. 13-0311) RBV documents

This item is being brought to FSRC for some major changes to Radioactive Waste*Systems.

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:

a. A summary of the evaluation that led to*the determination that the change could be made in accordance with 10 CFR Part50.59, b. Sufficient information to totally support the reason for the change without*benefit of additional or supplemental information,

c. A description of theequipment, components and processes involved and the interfaces with other plantsystems,

d. An evaluation of the change, which shows the predicted releases ofradioactive materials in liquid and gaseous effluents and/or quantity of solid waste*that differ from those previously predicted in the license application andamendments

thereto, e, An evaluation of the change, which shows the expected*maximum exposures to individuals in the UNRESTRICTED AREA and to thegeneral population that differ from those previously estimated in the licenseapplication and amendments

thereto,

f. A comparison of the predicted releases of0radioactive 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 theexposure to plant operating personnel as a result of the change, and h.Documentation of the fact that the change was reviewed and found acceptable by*the FSRC. Changes shall become effective upon review and acceptance by theFSRCDiscussion:

FSRC reviewed and discussed the documents and identified no safety issues or0 concerns.

0The Committee recommended approval of the RBV Documents.

00FSRC 13-065 Miscellaneous ItemPresenter:

Cieslewicz Approved w/comments 00000000000 S0FSRC Minutes Kewaunee Plant 006/19/13 Meeting No.13-031S1) NLAR 91 -Revise the TRM sections related to fuel movement to reflect onlythose conditions required in the permanently defueled condition.

TRM 7.0, Use and Applications

Delete the definition REFUELING OPERATION Delete the "MODES or other" from the phrase "MODES or other specified conditions" and delete the plhase "or that are part of a shutdown of theunit".* Replace the terms "unit", "operation of the unit" or "operation of the plant"with more appropriate termsTRM 8.7.8 Spent Fuel Pool Temperature

A new TRM section is being proposed to incorporate the LicenseAmendment 172 requirement to maintain the temperature of the SFP waterbelow 150'F.TRM Section 8.9 Refueling Operations

Rename Section 8.9 "Fuel Handling Operations" as a more appropriate titlein the defueled condition.

TRM 8.9.2, Fuel Handling and Manipulator Cranes* Rename TRM 8.9.2 "Spent Fuel Pool Bridge Crane" and replace "FuelHandling Crane" with "Spent Fuel Pool Bridge Crane" throughout thesection.* Change APPLICABILITY from "During REFUELING OPERATIONS" to"During movement of irradiated fuel assemblies or fuel assemblycomponents."

1* Delete requirements related to Manipulator Crane and fuel movement in thereactor.TRM 8.9.4, Radiation Monitoring During REFUELING OPERATIONS

Rename TRM 8.9.4 "Radiation Monitoring During Fuel Movement"

Change APPLICAVILITY firom "During REFUELING OPERATIONS" to"During movement of irradiated fuel assemblies or fuel assemblycomponents."

Delete requirements related to fuel movement in the reactorTRM 8.9.6, Spent Fuel Pool Sweep System is being proposed for deletion.

Functionality requirements for the Spent Fuel Pool Sweep system applyonly when irradiated fuel in the pool has decayed less than 30 days.As of June 7, 2013, all fuel on site will have decayed for greater than 30 days.Entry into any conditions that could restart the 30 day clock are prohibited by1OCFR50.82(a)(2).

SDiscussion:

FSRC reviewed and discussed the NLAR and identified no safety issues. Thefollowing action was taken by the Engineering FSRC representative:

write acondition report regarding why the deletion of the functional check of refueling SSSSS 0S000000000SS00000000000FSRC Minutes06/19/13-5-Kewaunee PlantMeeting No.13-031systems interlocks was being made since there were still interlocks on the bridge.The Committee recommended approval of NLAR 91 with comments and finalreview of the comments by the FSRC chair.

FSRC Minutes06/19/13-5-Kewaunee PlantMeeting No. 13-031The meeting adjourned at 1344.To the best of the Committee's knowledge, none of the above items required NRC approval prior toimplementation.

Submitted by:APPROVED:.

APPROVED:

J SchuhReodingSecreta.

79j3Date91A11-Si YJuen/ /FSRC Commi(tee Chaifnian cuiL ,-' DateAJ JSiteDateSSSSSSSSSSSSSSSSSSSSSSSISATTACHMENTS:

None DOMINIONKewaunee Power Station FSRC MTG # 13-035000.00000000S0000000Facility Safety Review Committee August 15, 20130958 HoursATTENDEES:

QuorumChairperson:

FSRC Coordinator:

Presenters:

Guests:J Stafford, Chairperson

-Director Safety and Licensing (1)JD Helbing, Supervisor

-Maintenance (1)JM Hale, Manager -RP/Chem (1)ME Aulik, Manager -Engineering

()B McMahon, Manager -Operations (1)JM Schuh, Administrative Assistant

-Decommissioning TS Wattleworth, Engineer IIIMW Grapentine, Electrical Maintenance Supervisor DA Jeanquart, Mechanical Maintenance Supervisor WG Swanson, Decommissioning Team-OpsMD Townsend, Hughes Associates

-Fire Protection RG Krsek, NRC(1) Indicates Chairperson and Members required for quorum per LI-AA-600.

(alt) Alternate Member (nv) Non-Voting MemberThe Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-078Design Change (DC)Presenter:

Wattleworth Approved1) DC-KW-13-01128, Discharge Structure Outfall Stop Logs and B.5.b PumpSuction PointThe Design Change (DC) will install stop logs in the discharge structure to maintainwater in the pipe and confine the remaining service water discharge to aconcentrated flow along the north sheet pile wall to assist in keeping a discharge channel open. The DC will also change the B.5.b Emergency Pump Suctionlocation to the Warm Water Pump Pit. This is being done because the plant's FSRC Minutes08/15/13-2-Kewaunee PlantMeeting No. 13-035discharge channel will begin filling with alluvial deposits from Lake Michigancurrents after the CW pumps are shut down. This has previously occurred withinweeks of stopping the CW pumps. It will also be necessary to maintain thedischarge structure and piping full for security purposes.

FSRC reviewed and discussed the design change and had the following comment:a In section 5 of CM-AA-DDC-201 remove the statement "no formal Training".

The Committee recommended approval of the procedure as modified with finalreview by the chairperson.

Discussion:

SS000S0S000S0000FSRC 13-079Miscellaneous ItemPresenter:

Grapentine Approvea4 wicomments Discussion:

1) MA-KW-EPM-039A, Linear Fire Control Panel (LFCP-1)

Inspection New procedure for the preventative maintenance and checks on the Linear FireControl Panel, LFCP-IFSRC reviewed and discussed the procedure and had the following comment:* On page 19, step 6.1.3 -the step leads you to believe that it is normal toONLY write a CR if out of acceptance.

This should be clarified.

The Committee recommended approval of the procedure as modified with finalreview by the chairperson.

FSRC 13-080Miscellaneous ItemPresenter:

Grapentine Approved wicomments Discussion:

1) MA-KW-EPM-040A, Linear Fire Control Panel (LFCP-2)

Inspection New procedure for the preventative maintenance on the Linear Fire Control Panel,LFCP-1FSRC reviewed and discussed the procedure had the following comment:* On page 26, step 6.1.3 -the step leads you to believe that it is normal toONLY write a CR if out of acceptance.

This should be clarified.

The Committee recommended approval of the procedure as modified with finalreview by the chairperson.

0SSSSSSSS0 000000S00000000000000000FSRC Minutes08/15/13-3-Kewaunee PlantMeeting No. 13-035FSRC 13-081Miscellaneous ItemPresenter:

Jeanquart Approved1) MA-KW-MPM-FP-007, Fire Hose Pressure Test, Rev. 5This procedure revision removes steps requiring performer(s) to obtain, Mark, andRecord Identification numbers on fire hoses (if not already marked/identified).

FSRC reviewed and discussed the procedure and identified no safety issues orconcerns.

Discussion:

The Committee recommended approval of the procedure.

FSRC 13-082Miscellaneous ItemPresenter:

Swanson Approved wicomments

1) Waste Gas System (32B) DSERT SSC Category Determination DocumentOP-KW-DEC-SYC-001 Attachment B. Document details total abandonment of theWaste Gas Processing System, what will be abandoned and justifies completeabandonment.

FSRC reviewed and discussed the documents and identified no safety issues. Thefollowing comments were made:* On Page 5, add "based on the above" to paragraph 3.The Committee recommended approval of the document with comments and finalreview of the comments by the FSRC chair.Discussion:

FSRC Minutes08/15/13-4-Kewaunee PlantMeeting No. 13-035The meeting adjourned at 1029.To the best of the Committee's knowledge, none of the above items required NRC approval prior toimplementation.

Submitted * ,/ Z -- v -- V,JM Schuh ,Recording Secretary APPROVED:

__/_-_- _JT StaffordFSRC Committee ChairmanDate-'-/3, ,APPROVED:

AJ Jo 1Site V eesidentDateDate0000000000000000000000000000000000000000000ATTACHMENTS:

None DOMINIONKewaunee Power Station]?.QlC MTV- f I IfAARFacility Safety Review Committee December 19, 20131002 Hours00S00000000000000000000SATTENDEES:

QuorumChairperson:

FSRC Coordinator:

Presenters:

Guests:J Stafford, Chairperson

-Director Safety and Licensing (I)BJ McMahon, Manager -Operations (1)ME Aulik, Manager -Engineering Design (1)JD Helbing, Nuclear Specialist-Maintenance

(!)SA Smidel, Administrative Assistant

-Plant ManagerWG Swanson, Decommissioning OpsJ Gadzala, Decommissioning R Edwards, USNRT Hanna, Supervisor Engineering (1) Indicates Chairperson and Members required for quorum per LI-AA-600.

(alt) Alternate Member (nv) Non-Voting MemberThe Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-112Licensing Amendment Request (LAR)Presenter:

Gadzala Approved1) LAR 256- PDTS, Supplement 2By application dated May 29, 2013, Dominion Energy Kewaunee, Inc. (DEK),requested an amendment to Facility Operating License Number DPR-43 forKewaunee Power Station (KPS). The proposed amendment would revise theOperating License and revise the associated Technical Specifications (TS) toPermanently Defueled Technical Specifications (PDTS). Supplement I to theapplication was submitted on October 15, 2013.Include within the changes proposed in the application was deletion of the cybersecurity provisions contained in License Condition 2.C.(4).

This proposal was basedon the requirements of 10 CFR 73.54. regarding cyber security, no longer applying FSRC Minutes Kewaunee Plant12/19/13 Meeting No. 13-048to KPS. However, the NRC staff recently verbally informed DEK that 10 CFR73.54 continues to apply to facilities that were previously licensed to operate on theNovember 23, 2009 mandated date for that rule.In response to the staff's comments, DEK is revising the originally proposedamendment.

The revised request retracts the original proposal to delete the eybersecurity provisions contained in License Condition 2.C.(4),

which will result in thislicense condition remaining unchanged.

Attachment 1 to this letter provides asupplement to the proposed amendment describing the revision.

Discussion:

FSRC reviewed and discussed LAR 256- PDTS supplement and identified no safetyissues or concerns.

The Committee recommended approval of LAR 256, Supplement 2.FSRC 13-113 Miscellaneous Item (NLAR)Presenter:

Gadzala Approved wicomments

1) NLAR 88- PDTS, Deletion of TRM 8.3.7, Explosive Gas Monitoring SystemThe purpose of NLAR 88 is to delete Technical Requirements Manual (TRM) 8.3.7"Explosive Gas Monitoring System" due to the permanent shutdown andabandonment of the gaseous waste system. The Explosive Gas Monitoring Systemutilizes an inline Waste Gas Analyzer (WGA) to monitor the in service Waste GsDecay Tank (WGDT) on a continuous basis to determine if the tank contains anexplosive mixture and is set to 2% oxygen by volume.With the hydrogen supply portion of the Miscellaneous Gas abandoned (hydrogen banks are permanently removed) and the Chemical and Volume Control (CVCS)and Reactor Coolant Systems (RCS) drained and vented, gaseous waste is no longerbeing produced.

The Gaseous Waste System, including WGDTs, has been purgedof radioactive and explosive gases, vented to atmosphere and abandoned.

Therefore, with no source of explosive gas the TRM requirements for the Explosive GasMonitoring System are no longer necessary.

Discussion:

FSRC asked the presenter to update the screening to add reference to Technical Specifications 5.5.10.The Committee recommended approval of this NLAR.

FSRC Minutes12/19/13FSRC 13-114 Kewaunee PlantMeeting No. 13-048Miscellaneous Item (NLAR)Presenter:

Gadzala Approved000,0'00S000000000000~01) NLAR 90, Deletion of TRM 8.7.7, Flooding Protection

-Circulating WaterPump Trip Circuitry" The purpose of NLAR 90 is to delete Technical Requirements Manual (TRM) 8.7.7"Flooding Protection-Circulating Water Pump trip Circuitry" due to thepermanent shutdown and abandonment of the Circulating Water (CW) System.With the CW system permanently shut down, flooding protection from the systemis no longer required.

FSRC reviewed and discussed the NLAR and identified no safety issues orconcerns.

Discussion:

The Committee recommended approval of this NLAR.FSRC 13-115Miscellaneous Item (NLAR)Presenter:

Gadzala Tabled1) NLAR 95, Deletion of TRM 8.3.6, Seismic Monitoring Instrumentation The purpose of NLAR 95 is to delete Technical Requirements Manual (TRM) 8.3.6Seismic Monitoring Instrumentation.

TRM 8.3.6 Bases states the seismicmonitoring instrumentation is used to provide data on seismic events in order topermit a timely determination of the need for shutting down the reactor as a result ofthe event. With the reactor permanently shut down and defueled, TRM 8.3.6"Seismic Monitoring Instrumentation" can be deleted as this function of the seismicmonitor is no longer required.

FSRC requested information regarding what administrative controls currently existto set the frequency and requirement for demonstrating fimctionality of the seismicmonitor for EAL purposes (currently contained in TVR 8.3.6.1, which is beingproposed for deletion);

and what administrative controls ensure that thesefunctionality checks remain in place.Discussion:

The Committee recommended tabling NLAR 95.FSRC 13-116Miscellaneous Item MNLAR)Presenter:

Gadzala Approved FSRC Minutes Kewaunee Plant12/19/13 Meeting No. 13-0481) NLAR 89, Deletion of TRM 8.7.5, SnubbersThe purpose of NLAR 89 is to delete Technical Requirements Manual (TRM) 8.7.5Snubbers.

TRM 8.7.5 lists the snubbers in the Snubber program and the plantMODES for which the snubbers are required to be functional.

Snubbers in theprogram are required to be functional in MODES 1,2, 3, 4, 5 and/or 6 only. Nosnubbers are required by the TRM to be functional in the defueled condition.

Consequently TRM 8.7.5 is unnecessary in the permanently defueled condition andcan be deleted.Discussion:

FSRC reviewed and discussed the NLAR and identified no safety issues orconcerns.

The Committee recommended approval of this NLAR.FSRC 13-117 Miscellaneous Item (LNLAR)Presenter:

Gadzala Approved wicomments

1) NLAR 97, Revision of TRM 8.8.3, "Emergency Diesel Generator (EDG)Ventilation Damper Control Air SupplyThe purpose of NLAR 97 is revise TRM 8.8.3, Emergency Diesel Generator (EDG)Ventilation Damper Control Air Supply, to reflect only those conditions requiredfollowing certification for permanent cessation of operations and permanent removal of fuel from the reactor vessel.TRM 8.8.3 references evaluation of EDG operability Technical Specifications (TS)3.8.1, AC Sources -Operating (Applicable in Modes 1-4) and TS 3.8.2, AC Sources-Shutdown (Applicable in Modes 5-6 and during the movement of irradiated fuelassemblies).

Following certification of permanent defueling on May 15,2013,operation of the plant or placing fuel in the reactor vessel is prohibited by 1OCFR50.82(a)(2).

This prevents entering Modes 1-6. Therefore, references to evaluating operability per TS 3.8.1 are unnecessary and can be deleted.

Since the condition

-During the movement of irradiated fuel assemblies

-can be still entered, references to evaluating operability per TS 3.8.2 remain valid.Discussion:

FSRC asked the presenter to consider the following comments:

Add reference to Technical Specifications 3.8.1 and 3.8.2 on the 10 CFR 50.59screening section BThe Committee recommended approval with comments of NLAR 97.

FSRC Minutes12/19/13-5-Kewaunee PlantMeeting No. 13-048000000000S0000S00000FSRC 13-118Operation Procedure Presenter:

McMahon Approved1) OP-KW-OSP-FP-002, Fire Pump TestUpdated procedure to framemaker standards and renumbered procedure.

Majorchanges include:" Removal of License Renewal Statement

" Added step to check the fire pump tested in run for at least 30 minutes to meetFire Plan requirements SSSAdded steps to document and track Fire Pump run timeChanged preferred method for auto start to be via opening hose station #0Updated Acceptance Criteria to be consistent with Fire PlanDiscussion:

FSRC reviewed and discussed the procedure and identified no safety issues orconcerns.

The Committee recommended approval of this procedure.

FSRC 13-1119Miscellaneous ItemPresenter:

Swanson Approved wicomments Discussion:

1) SYS-07-DSERT, Blowdown and Blowdown Treatment SystemCategorization packageS/G Blowdown and Blowdown Treatment System Categorization plan wassubmitted to FSRC because this system is an effluent processing system and perODCM chapter 15 requires a review by FSRC.FSRC asked the presenter to consider the following comments:

Remove the word solid on page 5 of 12 under item 3" Move the following statement under #3 on page 5 of 12 as justification

[Support draining of systems in the Auxiliary Building.

One train is beingmaintained available to support draining.]

" Make the following sentence specific to blowdown systems on 8 of 12. [SinceKPS will no longer be authorized to operate or place fuel in the reactor thefunctions credited in the USAR are no longer required.]

" Validate the date 3/7/13 for temporary changes FSRC Minutes12/19/13-6-Kewaunee PlantMeeting No. 13-048The Committee recommended approval with comments of SYS-07-DSERT.

FSRC 13-120Miscellaneous ItemPresenter:

Swanson Approved wiconmments Discussion:

1) SYS-45-2-DSERT, Radiation Monitoring System Categorization package forR- 11, R-12, and R-21.Categorization plan was submitted to FSRC because this system is an effluentmonitoring system and per ODCM chapter 15 requires a review by FSRC.FSRC asked the presenter to consider the following comments:

" On page 1 of 8 check the box for Abandoned

" On page 3 of 8 number 5 justify* On page 4 of 8 narrow the following statement to R- 11 and R-12 [Since KPSwill no longer be authorized to operate or place fuel in the reactor thefunctions credited in the USAR are no longer required.]

The Committee recommended approval with comments of SYS-45-2-DSERT.

000000S0000S00000000000000000000000000000 FSRC Minutes12/19/13-7-Kewaunee PlantMeeting No. 13-048The meeting adjourned at 1046.To the best of the Committee's knowledge, none of the above items required NRC approval prior toimplementation.

0000000S0000000000Submitted by: 2 2 nj QSA Sm elcRecording Secretary

,/9 1 IL-iDateAPPROVED:

APPROVED:

JT StaffordFSRC Committee Chairman04/h.LDateSite 4I9 President DateATTACHMENTS:

None This page intentionally left blankSSSS0SSSSSSSSSSSSSSSS

ML14126A088

Text

1.0 INTRODUCTION

11.0 INTRODUCTION

11.0 INTRODUCTION

References:

0.0 032Transuranics

Dear Mr. Schrock:

SUBJECT:

Enclosure:

51.0 INTRODUCTION

SUBJECT:

Dear Mr. Schrock:

3.0 CONCLUSION

Attachment:

SUBJECT:

Dear 4r. ardchi:

3.0 EVALUATION

Attachment:

SUBJECT:

Dear Mr. Harchi:

4.0 CONCLUSION

Attachment:

11.0 INTRODUCTION

11.0 INTRODUCTION

References:

0.0 032Transuranics

Dear Mr. Schrock:

SUBJECT:

Enclosure:

01.0 INTRODUCTION

SUBJECT:

Dear Mr. Schrock:

Enclosure:

Attachment:

SUBJECT:

Dear Mr. Marchi:

Enclosure:

4.0 CONCLUSION

Attachment:

SUBJECT:

Dear Mr. Marchi:

Enclosure:

4.0 CONCLUSION

1.3 Implementation

Description:

Background:

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