ML14126A088: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 76: | Line 76: | ||
__ 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 and cumulative quarterly and annual doses. The ODCM methodology is acceptable for use in demonstrating compliance with 10 CFR 20.1301/1302; 10 CFR 50, Appendix I; and 40 CFR 190.Page 4 of 35 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 S S S S S S S S S 0 0 0 S S S 0 S S S S 0 S 0 S S S S 0 0 0 0 0 0 0 0 0 S S S S S 0 0 0 0 S 0 0 2.0 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. The auxiliary 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. | __ 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 and cumulative quarterly and annual doses. The ODCM methodology is acceptable for use in demonstrating compliance with 10 CFR 20.1301/1302; 10 CFR 50, Appendix I; and 40 CFR 190.Page 4 of 35 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 S S S S S S S S S 0 0 0 S S S 0 S S S S 0 S 0 S S S S 0 0 0 0 0 0 0 0 0 S S S S S 0 0 0 0 S 0 0 2.0 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. The auxiliary 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 releases are 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: Analysis LLD (gCi/ml)Gaseous Gamma Emitters Iodine 131 Particulate Gamma Emitters Particulate Gross Alpha Strontium 89, 90 Noble Gases, Gross Beta or Gamma 1.OOE-04 3.OOE- 12 1.OOE- 1I L.OOE- 1I L.OOE- 11 1.OOE-06 The nominal "a priori" LLD values are shown below.Isotope a priori LLD (jtCi/ml)a. Gaseous emissions: | Batch releases are 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: Analysis LLD (gCi/ml)Gaseous Gamma Emitters Iodine 131 Particulate Gamma Emitters Particulate Gross Alpha Strontium 89, 90 Noble Gases, Gross Beta or Gamma 1.OOE-04 3.OOE- 12 1.OOE- 1I L.OOE- 1I L.OOE- 11 1.OOE-06 The nominal "a priori" LLD values are shown below.Isotope a priori LLD (jtCi/ml)a. Gaseous emissions: | ||
Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 5.61 E-08 1.02E-07 6.68E-08 2.75E-07 2.99E-08 1.13E-07 Page 5 of 35 | Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 5.61 E-08 1.02E-07 6.68E-08 2.75E-07 2.99E-08 1.13E-07 Page 5 of 35 | ||
: b. Particulate emissions: | : b. Particulate emissions: | ||
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 1.11E-13 2.27E-13 2.28E-13 3.57E-13 1.68E-13 2.73E-13 4.69E- 13 1.68E-13 2.08E-13 1.24E-12 c. Other identifiable gamma emitters: Ar-41 Kr-85 Kr-85m Kr-89 Xe-127 Xe-131m Xe-135m Xe-137 1-131 3.97E-10 8.63E-05 4.62E-08 2.04E-06 4.20E-08 1.82E-06 1.90E-08 2.88E-07 1.32E-13 0 0 0 0 0 S 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S 0 0 S S S S S S S S 0 S 0 d. Composite particulate samples: Sr-89 1.OOE-14 Sr-90 1.00E- 14 Gross Alpha 1.OOE-14 These "a priori" LLDs represent the capabilities of the counting systems in use, not an after the fact "a posteriori" limit for a particular measurement. | Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 1.11E-13 2.27E-13 2.28E-13 3.57E-13 1.68E-13 2.73E-13 4.69E- 13 1.68E-13 2.08E-13 1.24E-12 c. Other identifiable gamma emitters: Ar-41 Kr-85 Kr-85m Kr-89 Xe-127 Xe-131m Xe-135m Xe-137 1-131 3.97E-10 8.63E-05 4.62E-08 2.04E-06 4.20E-08 1.82E-06 1.90E-08 2.88E-07 1.32E-13 0 0 0 0 0 S 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S 0 0 S S S S S S S S 0 S 0 d. Composite particulate samples: Sr-89 1.OOE-14 Sr-90 1.00E- 14 Gross Alpha 1.OOE-14 These "a priori" LLDs represent the capabilities of the counting systems in use, not an after the fact "a posteriori" limit for a particular measurement. | ||
| Line 176: | Line 176: | ||
==11.0 INTRODUCTION== | ==11.0 INTRODUCTION== | ||
The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent Controls, includes: | The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent Controls, includes: | ||
(1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively. | (1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively. | ||
Part II, Calculational Methodologies: | Part II, Calculational Methodologies: | ||
| Line 290: | Line 290: | ||
This is at least ten times the ex. ed nber of defective fuel elements. | This is at least ten times the ex. ed nber of defective 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 with letdown at the maximum rate, and periodic purging to the gas .maximum inventory 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. | 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 with letdown at the maximum rate, and periodic purging to the gas .maximum inventory 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 | 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 when considered as Xe-133. Kewaunee Power nidoes t have a calculation correcting the waste gas decay tank activity to a SITE U AR'6nsequence of < 0.5 rem, therefore by limiting 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 DOSE EQUIVALENT 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/gm DEX-1 33, ana consequences calculation also yields a 0.1 rem whole body at the SITE BOUND b Iculation then a gas decay tank on fill cannot exceed the activity limits of this req _frnt and the once per 31 day frequency is adequate.Reference 1. USAR Section 14.2.3, Accidental Release-Waste Gas 2. Calculation C1 1833, Kewaunee Power Station RCS Specific Activity Dose Equivalent | : 5) referenced to Xe-1 33 results in a n;- onf 52,000 curies when considered as Xe-133. Kewaunee Power nidoes t have a calculation correcting the waste gas decay tank activity to a SITE U AR'6nsequence of < 0.5 rem, therefore by limiting 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 DOSE EQUIVALENT 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/gm DEX-1 33, ana consequences calculation also yields a 0.1 rem whole body at the SITE BOUND b Iculation then a gas decay tank on fill cannot exceed the activity limits of this req _frnt and the once per 31 day frequency is adequate.Reference 1. USAR Section 14.2.3, Accidental Release-Waste Gas 2. 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 Rupture Radiation Dose Analysis for the 7.4% Power Uprate Program.4. USAR Table D.7-1 Inventory of Gas Decay Tank After Shutdown and Degassing of*the RCS (Based on 1 percent of Fuel Defects)5. USAR Table D.8-1, Nuclide Parameters 1*13.2.5- 3 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 13.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DNC 13.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 13.3.1-1 shall be FUNCTIONAL with: a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1 are not exceeded.APPLICABILITY: | *) Xenon -133 Indicator* 3. Calculation CN-CRA-99-46, Revision 3, Kewaunee GDT Rupture and VCT Rupture Radiation Dose Analysis for the 7.4% Power Uprate Program.4. USAR Table D.7-1 Inventory of Gas Decay Tank After Shutdown and Degassing of*the RCS (Based on 1 percent of Fuel Defects)5. USAR Table D.8-1, Nuclide Parameters 1*13.2.5- 3 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 13.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DNC 13.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 13.3.1-1 shall be FUNCTIONAL with: a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1 are not exceeded.APPLICABILITY: | ||
| Line 362: | Line 362: | ||
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 prevent direct, unmonitore renvironment. | 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 prevent direct, unmonitore renvironment. | ||
A liquid radioactive waste flow diagram with th pll a associated radiation monitoring instrumentation and controls is pre t SF re 1.1.2 Liquid Effluent Monitor D ination Per the re " ts of Technical Specification 5.5.3.b and ODCM Normal ConditicKE1i3.3., la' setpoints shall be established for the liquid effluent monitoring instru e on t ensure that the release concentration limits of ODCM Normal Co n1 re met (i.e., the concentration of radioactive material released in liquid efL UNRESTRICTED AREA shall be limited to ten times the concentrations spe led 1 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and 2.0E- i/ml for dissolved or entrained noble gases). The following equation 1 must be satisified to meet the liquid effluent restrictions: | A liquid radioactive waste flow diagram with th pll a associated radiation monitoring instrumentation and controls is pre t SF re 1.1.2 Liquid Effluent Monitor D ination Per the re " ts of Technical Specification 5.5.3.b and ODCM Normal ConditicKE1i3.3., la' setpoints shall be established for the liquid effluent monitoring instru e on t ensure that the release concentration limits of ODCM Normal Co n1 re met (i.e., the concentration of radioactive material released in liquid efL UNRESTRICTED AREA shall be limited to ten times the concentrations spe led 1 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and 2.0E- i/ml for dissolved or entrained noble gases). The following equation 1 must be satisified to meet the liquid effluent restrictions: | ||
00 <IOxC(F+f) | 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 STATION OFFSITE DOSE CALCULATION MANUAL where: ODCM 1.0 Revision 15 June 6, 2013 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- pCi/ml.c = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would concentrations exceeding the limits of ODCM Normal Condition 113.I ., f = the flow rate at the radiation monitor location same units as F, below.time, but in the F = the dilution water flow rate as unit time.[Note that if no dilution is compared to (f), then(,kýrelease point, in volume per C. Also, note that when (F) is large 0 6 0 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 S S S S S 0 1.2.1 Liquid Effluent Monitors Steam Generator Blowdown and Service Water)The setpoi determir,4 effluent monitors at the Kewaunee Power Station are I equations: | (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 STATION OFFSITE DOSE CALCULATION MANUAL where: ODCM 1.0 Revision 15 June 6, 2013 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- pCi/ml.c = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would concentrations exceeding the limits of ODCM Normal Condition 113.I ., f = the flow rate at the radiation monitor location same units as F, below.time, but in the F = the dilution water flow rate as unit time.[Note that if no dilution is compared to (f), then(,kýrelease point, in volume per C. Also, note that when (F) is large 0 6 0 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 S S S S S 0 1.2.1 Liquid Effluent Monitors Steam Generator Blowdown and Service Water)The setpoi determir,4 effluent monitors at the Kewaunee Power Station are I equations: | ||
SP : CWX-CEi xSENi)+bkg Ci xRR lOx EC, (1.2)SP= alarm setpoint corresponding to the maximum allowable release rate (cpm)Ci = the concentration of radionuclide "i" in the liquid effluent (pCi), to include gamma emitters only 10xECi = ten times the EC value corresponding to radionuclide | SP : CWX-CEi xSENi)+bkg Ci xRR lOx EC, (1.2)SP= alarm setpoint corresponding to the maximum allowable release rate (cpm)Ci = the concentration of radionuclide "i" in the liquid effluent (pCi), to include gamma emitters only 10xECi = ten times the EC value corresponding to radionuclide | ||
| Line 380: | Line 380: | ||
0 0-*0 0-0-0 0 0*0 0 0 0* 1.0-9 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 4 = Sample/Monitor | 0 0-*0 0-0-0 0 0*0 0 0 0* 1.0-9 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 4 = Sample/Monitor | ||
= Isolation Devise (Damper or Valve)--= Auto Isolation=This Flow Path shal onlybe used If orolected does comply with ODCM O anTni Slpe~iticatlon (CA%1074)Graphice No. CS73s.ODCM FIGURE 1 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM 1.0-10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 Table 1.1 Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value* Units Comments ECe calculated 1.0E-06** | = Isolation Devise (Damper or Valve)--= Auto Isolation=This Flow Path shal onlybe used If orolected does comply with ODCM O anTni Slpe~iticatlon (CA%1074)Graphice No. CS73s.ODCM FIGURE 1 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM 1.0-10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 Table 1.1 Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value* Units Comments ECe calculated 1.0E-06** | ||
PCi/mI Calculate for each batch to be released dN/A PCi/mI Taken from gamma spectral analysis C measured NIof liquid effluent Taken from 10 CFR 20, Appendix B, EC 1 as determined N/A pCi/mI Table 2, Col. 2 Sensitivity (SEN)R-18 as determined 1.0E+08 Rad efflu R-19 as determined 1.0E+08 cpm per S ra blowdown R-20 as determined 1.0E+08 pCi/ml rvi component cooling R-16 as determined 9.8E+07 aer -containment fan cooling r g Water System default =CW as determined 2.58E+05 gp te , single CW pump Release Rate (RR)R-1 8 as determined 8.OE+01 Determined prior to release; release rate can be adjusted for requirement compliance R-1 9 as determined | PCi/mI Calculate for each batch to be released dN/A PCi/mI Taken from gamma spectral analysis C measured NIof liquid effluent Taken from 10 CFR 20, Appendix B, EC 1 as determined N/A pCi/mI Table 2, Col. 2 Sensitivity (SEN)R-18 as determined 1.0E+08 Rad efflu R-19 as determined 1.0E+08 cpm per S ra blowdown R-20 as determined 1.0E+08 pCi/ml rvi component cooling R-16 as determined 9.8E+07 aer -containment fan cooling r g Water System default =CW as determined 2.58E+05 gp te , single CW pump Release Rate (RR)R-1 8 as determined 8.OE+01 Determined prior to release; release rate can be adjusted for requirement compliance R-1 9 as determined | ||
: 2. Steam Generator A and B combined R-20 as determined 5 + Service Water -component cooling R-16 as determined Service Water -Containment fan cooling Background (bkg) <R-18 as determi .0 3 cpm Nominal values only; actual values R-19 as deter e + 01 may be used in lieu of these reference R-20 as de e .O-+01 values R-16 as x 8.0E+01 Setpoint* (SP) R-18 culat 5.OOE+05+bkg cpm Default alarm setpoints; more S C5.E+05+bkg conservative values may be used as R-20 cu1 ul-aated 5.16E+04+bkg deem appropriate and desirable for R-16 ulated 1.68E+05+bkg assuring regulatory compliance and for maintaining releases ALARA.Setpoint* (SP) with no Circulating Water System flow, CW=0 R-18 calculated 6.25E+04+bkg For outages with no Circulating Water R-19 calculated 2.50E+04+bkg cpm System flow (CW=0) and a dilution flow R-20 calculated 1.OOE+03+bkg as provided by the Service Water R-16 calculated 3.26E+03+bkg system of 5,000 gpm total.**** Refer to Calculation | : 2. Steam Generator A and B combined R-20 as determined 5 + Service Water -component cooling R-16 as determined Service Water -Containment fan cooling Background (bkg) <R-18 as determi .0 3 cpm Nominal values only; actual values R-19 as deter e + 01 may be used in lieu of these reference R-20 as de e .O-+01 values R-16 as x 8.0E+01 Setpoint* (SP) R-18 culat 5.OOE+05+bkg cpm Default alarm setpoints; more S C5.E+05+bkg conservative values may be used as R-20 cu1 ul-aated 5.16E+04+bkg deem appropriate and desirable for R-16 ulated 1.68E+05+bkg assuring regulatory compliance and for maintaining releases ALARA.Setpoint* (SP) with no Circulating Water System flow, CW=0 R-18 calculated 6.25E+04+bkg For outages with no Circulating Water R-19 calculated 2.50E+04+bkg cpm System flow (CW=0) and a dilution flow R-20 calculated 1.OOE+03+bkg as provided by the Service Water R-16 calculated 3.26E+03+bkg system of 5,000 gpm total.**** Refer to Calculation | ||
# C1 0690 for the default setpoint calculation. | # C1 0690 for the default setpoint calculation. | ||
| Line 386: | Line 386: | ||
* SW flow is based on N-SW-02 Operating Parameters and Service Water Pump Flow Curves.* The default alarm setpoints for R-18 and R-19 are based upon the linear calibration range of those radiation monitors in accordance with CAP 37265 and DCR 26981.1.0-11 0 KEWAUNEE POWER STATION ODCM 1.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 Table 1.2 (Page 1 of 2) June6, 2013 Site Related Ingestion Dose Commitment Factors (mrem/hr per uCi/ml)Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 -3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 0 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 P-32 1.39E+6 8.62E+4 5.36E+4 --1.56E+5 Cr-51 --1.28E+O 7.63E-1 2.81 E-1 1.69E+0 3.21 E+2 0 Mn-54 -4.38E+3 8.36E+2 -1.30E+3 1.34E+4 Mn-56 -1.1OE+2 1.96E+1 -1.40E+2 3.52E+3 Fe-55 6.61 E+2 4.57E+2 1.06E+2 ..2 ..... -.+.22. 2.62E+2 Fe-59 1.04E+3 2.45E+3 9.40E+2 --8.17E+3 Co-57 2.11E+1 3.51E+1 -.5.36E+2 Co-58 8.99E+1 2.02E+2 -1.82E+3 Co-60 2.58E+2 5.70E+2 -4.85E+3 Ni-63 3.13E+4 2.17E+3 1.05E+3 -. -._ 4.52E+2 Ni-65 1.27E+2 1.65E+1 7.52E+0 --4.18E+2 Cu-64 1.01E+1 4.72E+0 -8.57E+2 Zn-65 2.32E+4 7.38E+4 3.33E+4 -9 .4 -4.65E+4 Zn-69 4.93E+1 9.43E+1 6.56E+0 E+1 -1.42E+1 Br-82 -2.27E+3 -2.61 E+3 0 Br-83 -4.05 -5.83E+ 1 Br-84 4.12E-4 Br-85 --' -+0-Rb-86 -1.01 E+5 4.7 .... .. 1.99E+4 Rb-88 -2.90 _.W 4.00E-9 Rb-89 -1. 9,4 2 1".ý 2 2.............-- | * SW flow is based on N-SW-02 Operating Parameters and Service Water Pump Flow Curves.* The default alarm setpoints for R-18 and R-19 are based upon the linear calibration range of those radiation monitors in accordance with CAP 37265 and DCR 26981.1.0-11 0 KEWAUNEE POWER STATION ODCM 1.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 Table 1.2 (Page 1 of 2) June6, 2013 Site Related Ingestion Dose Commitment Factors (mrem/hr per uCi/ml)Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 -3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 0 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 P-32 1.39E+6 8.62E+4 5.36E+4 --1.56E+5 Cr-51 --1.28E+O 7.63E-1 2.81 E-1 1.69E+0 3.21 E+2 0 Mn-54 -4.38E+3 8.36E+2 -1.30E+3 1.34E+4 Mn-56 -1.1OE+2 1.96E+1 -1.40E+2 3.52E+3 Fe-55 6.61 E+2 4.57E+2 1.06E+2 ..2 ..... -.+.22. 2.62E+2 Fe-59 1.04E+3 2.45E+3 9.40E+2 --8.17E+3 Co-57 2.11E+1 3.51E+1 -.5.36E+2 Co-58 8.99E+1 2.02E+2 -1.82E+3 Co-60 2.58E+2 5.70E+2 -4.85E+3 Ni-63 3.13E+4 2.17E+3 1.05E+3 -. -._ 4.52E+2 Ni-65 1.27E+2 1.65E+1 7.52E+0 --4.18E+2 Cu-64 1.01E+1 4.72E+0 -8.57E+2 Zn-65 2.32E+4 7.38E+4 3.33E+4 -9 .4 -4.65E+4 Zn-69 4.93E+1 9.43E+1 6.56E+0 E+1 -1.42E+1 Br-82 -2.27E+3 -2.61 E+3 0 Br-83 -4.05 -5.83E+ 1 Br-84 4.12E-4 Br-85 --' -+0-Rb-86 -1.01 E+5 4.7 .... .. 1.99E+4 Rb-88 -2.90 _.W 4.00E-9 Rb-89 -1. 9,4 2 1".ý 2 2.............-- | ||
.-.-.--.------- | .-.-.--.------- | ||
Sr-89 2.24E+4 -6 +2 3.60E+3 Sr-90 5.52E+5,-" 5E+5 _ _ ---1.59E+4 Sr-91 4.13E-, 1.67E+1 -.-1.97E+3 Sr-92 1.57 6.77E+0 3.10E+3... ....... ........................ | Sr-89 2.24E+4 -6 +2 3.60E+3 Sr-90 5.52E+5,-" 5E+5 _ _ ---1.59E+4 Sr-91 4.13E-, 1.67E+1 -.-1.97E+3 Sr-92 1.57 6.77E+0 3.10E+3... ....... ........................ | ||
:....................................... | :....................................... | ||
:..................................... | :..................................... | ||
.................. | .................. | ||
| Line 393: | Line 393: | ||
+ 2.2E- 4.72E+3 Y-9 150E-3 _--- 9.OOE+20 Y -9;" ----- -_-5 ()E ': ................................... | + 2.2E- 4.72E+3 Y-9 150E-3 _--- 9.OOE+20 Y -9;" ----- -_-5 ()E ': ................................... | ||
........ ........ -. .. ............. | ........ ........ -. .. ............. | ||
.......................... | .......................... | ||
: 9. 0 E+-- --2 Z" 1E ... .... .. .. ........ 5.87E-2 1.36E-1 2.75E+2 Zr-97 1.49E-2 3.01E-3 1.38E-3 4.55E-3 9.34E+2 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 5 Nb-97 3.75E+0 9.48E-1 3.46E-1 -1.11E+0 3.50E+3 Mo-99 -1.07E+2 2.04E+1 -2.43E+2 2.49E+2 Tc-99m 9.11E-3 2.58E-2 3.28E-1 -3.91E-1 1.26E-2 1.52E+1 0 Tc-101 9.37E-3 1.35E-2 1.32E-1 -2.43E-1 6.90E-3 -0 Ru-103 4.61E+0 1.99E+0 -1.76E+1 5.39E+2 Ru-105 3.84E-1 1.52E-1 -4.96E+0 2.35E+2 Ru-106 6.86E+1 8.68E+0 -1.32E+2 4.44E+3 Rh-103m ----...0 Rh-106 -- --1.0-12 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 1.2 (Page 2 of 2)Site Related Ingestion Dose Commitment Factors (mrem/hr oer uCi/ml)ODCM 1.0 Revision 15 June 6, 2013 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S S 0 0 0 0 0 Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 10Ag0m. 1.04E+O 9.62E-1 5.71 E- -1.89E+0 .-3.92E+2 Sb-124 9.48E+0 1.79E-1 3.76E+O 2.30E-2 -7.38E+0 2.69E+2 Sb-125 6.06E+0 6.77E-2 1.44E+O 6.16E-3 -4.67E+0 6.67E+1 Te-125m 2.57E+3 9.31E+2 3.44E+2 7.73E+2 1.04E+4 1.03E+4 Te-127m 6.49E+3 2.32E+3 7.911E+2 1.66E+3 2.64E+4 -2.18E+4 Te-127 1.05E+2 3.79E+1 2.28E+1 7.81E+1 4.29E+2 8.32E+3 Te-129m 1.10E+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 5.55E+4 Te-129 3.OIE+1 1.13E+1 7.33E+O 2.31E+1 1.27E+2 2.27E+1 Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+41.89E+. 7.89E+8 5.96E+O 1.55E+- 8.27E+-- 2.67E+O........... | : 9. 0 E+-- --2 Z" 1E ... .... .. .. ........ 5.87E-2 1.36E-1 2.75E+2 Zr-97 1.49E-2 3.01E-3 1.38E-3 4.55E-3 9.34E+2 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 5 Nb-97 3.75E+0 9.48E-1 3.46E-1 -1.11E+0 3.50E+3 Mo-99 -1.07E+2 2.04E+1 -2.43E+2 2.49E+2 Tc-99m 9.11E-3 2.58E-2 3.28E-1 -3.91E-1 1.26E-2 1.52E+1 0 Tc-101 9.37E-3 1.35E-2 1.32E-1 -2.43E-1 6.90E-3 -0 Ru-103 4.61E+0 1.99E+0 -1.76E+1 5.39E+2 Ru-105 3.84E-1 1.52E-1 -4.96E+0 2.35E+2 Ru-106 6.86E+1 8.68E+0 -1.32E+2 4.44E+3 Rh-103m ----...0 Rh-106 -- --1.0-12 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 1.2 (Page 2 of 2)Site Related Ingestion Dose Commitment Factors (mrem/hr oer uCi/ml)ODCM 1.0 Revision 15 June 6, 2013 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S S 0 0 0 0 0 Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 10Ag0m. 1.04E+O 9.62E-1 5.71 E- -1.89E+0 .-3.92E+2 Sb-124 9.48E+0 1.79E-1 3.76E+O 2.30E-2 -7.38E+0 2.69E+2 Sb-125 6.06E+0 6.77E-2 1.44E+O 6.16E-3 -4.67E+0 6.67E+1 Te-125m 2.57E+3 9.31E+2 3.44E+2 7.73E+2 1.04E+4 1.03E+4 Te-127m 6.49E+3 2.32E+3 7.911E+2 1.66E+3 2.64E+4 -2.18E+4 Te-127 1.05E+2 3.79E+1 2.28E+1 7.81E+1 4.29E+2 8.32E+3 Te-129m 1.10E+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 5.55E+4 Te-129 3.OIE+1 1.13E+1 7.33E+O 2.31E+1 1.27E+2 2.27E+1 Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+41.89E+. 7.89E+8 5.96E+O 1.55E+- 8.27E+-- 2.67E+O........... | ||
....!.3. 1 .............. | ....!.3. 1 .............. | ||
| Line 513: | Line 513: | ||
9.20E+2 Co-58 2.07E+3 --<-13 -"9.52E+4 2.78E+3 Co-60 -1.51E+4 -I Z2 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 --3.' +5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 --, 6E+3 3.67E+4 1.27E-1 Cu-64 -2.03E+0 -.4 4 11 E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 -, 4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 -0 2 1.58E+3 2.85E+2 6.46E-3 Br-82 --_,_____-- | 9.20E+2 Co-58 2.07E+3 --<-13 -"9.52E+4 2.78E+3 Co-60 -1.51E+4 -I Z2 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 --3.' +5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 --, 6E+3 3.67E+4 1.27E-1 Cu-64 -2.03E+0 -.4 4 11 E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 -, 4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 -0 2 1.58E+3 2.85E+2 6.46E-3 Br-82 --_,_____-- | ||
1.82E+4 Br-83 ---_____,V_,__-"-- | 1.82E+4 Br-83 ---_____,V_,__-"-- | ||
3.44E+2 Br-84 -__,__ -4.33E+2 Br-85 --, 1.83E+1 Rb-86 -1.77E+4 8.40E+4 Rb-88 -2.92E-5 2.72E+2 Rb-89 -+2_-,,_ -3.38E-7 2.33E+2 Sr-89 4.34E+5 --2.42E+6 3.71 E+5 1.25E+4 Sr-90 1.0 ---1.65E+7 7.65E+5 6.68E+6 Sr-91 -OEE+ 6.07E+4 2.59E+5 3.51 E+O Sr-92 9 ---2.74E+4 1.19E+5 4.06E-1 Y-90 '" BEt ---2.93E+5 5.59E+5 8.00E+1 Y-91 m 3. ---3.20E+3 3.02E+1 1.42E-2 Y-91 6.61 E+5 --2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 ---2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 ---8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-97 1.38E+2 2.72E+1 -4.12E+1 1.30E+5 6.30E+5 1.26E+1 Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51 E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 -9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 -1.69E+2 -4.11 E+2 1.54E+5 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 -5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 -1.52E-3 6.67E+2 8.72E-7 8.24E-4 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.5 (Page 2 of 2)R, Inhalation Pathway Dose Factors -TEEN (mrem/yr per pCi/rn 3)ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.1OE+3 -7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-105 1.125+0 ---1.41E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m ---Rh-1 06 --Ag-11Orn 1.38E+4 1.31E+4 -2.50E+4 6.75E+6< .73 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E, \V 98E4 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.7,,4 W)6 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 -5. + 7,,, 4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 -+,,.59E+5 2.18E+3 Te-127 2.01E+O 9.12E-1 1.42E+0 7.28E+,/ 1. + 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19,:*\ X1.98F6 4.05E+5 2.25E+3 Te-129 7.10E-2 3.38E-2 5.18E-2 2 -.+3 1.62E+3 1.76E-2 Te-131m 9.84E+1 6.01E+1 7.25E+1 48E+5 6.21 E+5 4.02E+1 Te-131 1.58E-2 8.32E-3 1.24E-2.-,- | 3.44E+2 Br-84 -__,__ -4.33E+2 Br-85 --, 1.83E+1 Rb-86 -1.77E+4 8.40E+4 Rb-88 -2.92E-5 2.72E+2 Rb-89 -+2_-,,_ -3.38E-7 2.33E+2 Sr-89 4.34E+5 --2.42E+6 3.71 E+5 1.25E+4 Sr-90 1.0 ---1.65E+7 7.65E+5 6.68E+6 Sr-91 -OEE+ 6.07E+4 2.59E+5 3.51 E+O Sr-92 9 ---2.74E+4 1.19E+5 4.06E-1 Y-90 '" BEt ---2.93E+5 5.59E+5 8.00E+1 Y-91 m 3. ---3.20E+3 3.02E+1 1.42E-2 Y-91 6.61 E+5 --2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 ---2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 ---8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-97 1.38E+2 2.72E+1 -4.12E+1 1.30E+5 6.30E+5 1.26E+1 Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51 E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 -9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 -1.69E+2 -4.11 E+2 1.54E+5 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 -5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 -1.52E-3 6.67E+2 8.72E-7 8.24E-4 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.5 (Page 2 of 2)R, Inhalation Pathway Dose Factors -TEEN (mrem/yr per pCi/rn 3)ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.1OE+3 -7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-105 1.125+0 ---1.41E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m ---Rh-1 06 --Ag-11Orn 1.38E+4 1.31E+4 -2.50E+4 6.75E+6< .73 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E, \V 98E4 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.7,,4 W)6 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 -5. + 7,,, 4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 -+,,.59E+5 2.18E+3 Te-127 2.01E+O 9.12E-1 1.42E+0 7.28E+,/ 1. + 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19,:*\ X1.98F6 4.05E+5 2.25E+3 Te-129 7.10E-2 3.38E-2 5.18E-2 2 -.+3 1.62E+3 1.76E-2 Te-131m 9.84E+1 6.01E+1 7.25E+1 48E+5 6.21 E+5 4.02E+1 Te-131 1.58E-2 8.32E-3 1.24E-2.-,- | ||
:S. 2 /,2.34E+3 1.51E+1 5.04E-3 Te-132 3.60E+2 2.90E+2 2.46E-ýZ ý 4.49E+5 4.63E+5 2.19E+2 1-130 6.24E+3 1.79E+4 12 +F 2.7 +4 -9.12E+3 7.17E+3 1-131 3.54E+4 4.91E+4 ,,64'7 E44 5+4 -6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3- \",ft -1.27E+3 1.58E+3 1-133 1.22E+4 2.05E, 2. %ý+6 3.59E+4 -1.03E+4 6.22E+3 1-134 8.88E+2 2.32"3 / ).9.5 14 3.66E+3 -2.04E+1 8.40E+2 1-135 3.70E+3 .68X +5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 5.02E+5 1 .+- 3.75E+5 1.46E+5 9.76E+3 5.49E+5 CS-1 36 5.15E+A +5 -1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 &.44E+5 -3.04E+5 .1.21E+5 8.48E+3 3.11E+5 Cs-138 4.ffg +2 5 +2 -6.62E+2 7.87E+1 2.70E-1 4.46E+2 Ba-139 , iZ\-0 44E-4 -8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5 ..70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 ., 1 1.06E-4 -9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ba-142 2 3.70E-5 -3.14E-5 1.91E+3 -2.27E-3 La-140 4. 9E+2 2.36E+2 -2.14E+5 4.87E+5 6.26E+1 La-142 9.60E-1 4.25E-1 --1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-143 2.66E+2 1.94E+2 -8.64E+1 1.30E+5 2.55E+5 2.16E+1 Ce-144 4.89E+6 2.02E+6 -1.21 E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31 E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 -1.01E-2 1.75E+3 2.35E-4 2.18E-3 Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+O -4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 -1.OOE+2 6.49E+4 1.32E+5 1.77E+1 2.0-21 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.6 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -CHILD (mrem/yr per pCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 P-32 2.60E+6 1.14E+5 ---4.22E+4 9.88E+4 Cr-51 -8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 -4.29E+4 -1.OOE+4 1.58E+6 2.29.ii .51E+3 Mn-56 -1.66E+0 -1.67E+0 1.31E+4 1.2X+5 .7+2E-1 Fe-55 4.74E+4 2.52E+4 --1.11E+5Fe-5 I 3.34E 7E+3 Fe-59 2.07E+4 3.34E+4 --.+.27E+7E | :S. 2 /,2.34E+3 1.51E+1 5.04E-3 Te-132 3.60E+2 2.90E+2 2.46E-ýZ ý 4.49E+5 4.63E+5 2.19E+2 1-130 6.24E+3 1.79E+4 12 +F 2.7 +4 -9.12E+3 7.17E+3 1-131 3.54E+4 4.91E+4 ,,64'7 E44 5+4 -6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3- \",ft -1.27E+3 1.58E+3 1-133 1.22E+4 2.05E, 2. %ý+6 3.59E+4 -1.03E+4 6.22E+3 1-134 8.88E+2 2.32"3 / ).9.5 14 3.66E+3 -2.04E+1 8.40E+2 1-135 3.70E+3 .68X +5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 5.02E+5 1 .+- 3.75E+5 1.46E+5 9.76E+3 5.49E+5 CS-1 36 5.15E+A +5 -1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 &.44E+5 -3.04E+5 .1.21E+5 8.48E+3 3.11E+5 Cs-138 4.ffg +2 5 +2 -6.62E+2 7.87E+1 2.70E-1 4.46E+2 Ba-139 , iZ\-0 44E-4 -8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5 ..70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 ., 1 1.06E-4 -9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ba-142 2 3.70E-5 -3.14E-5 1.91E+3 -2.27E-3 La-140 4. 9E+2 2.36E+2 -2.14E+5 4.87E+5 6.26E+1 La-142 9.60E-1 4.25E-1 --1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-143 2.66E+2 1.94E+2 -8.64E+1 1.30E+5 2.55E+5 2.16E+1 Ce-144 4.89E+6 2.02E+6 -1.21 E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31 E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 -1.01E-2 1.75E+3 2.35E-4 2.18E-3 Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+O -4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 -1.OOE+2 6.49E+4 1.32E+5 1.77E+1 2.0-21 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.6 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -CHILD (mrem/yr per pCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 P-32 2.60E+6 1.14E+5 ---4.22E+4 9.88E+4 Cr-51 -8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 -4.29E+4 -1.OOE+4 1.58E+6 2.29.ii .51E+3 Mn-56 -1.66E+0 -1.67E+0 1.31E+4 1.2X+5 .7+2E-1 Fe-55 4.74E+4 2.52E+4 --1.11E+5Fe-5 I 3.34E 7E+3 Fe-59 2.07E+4 3.34E+4 --.+.27E+7E | ||
.+ .67E+4 Co-57 -9.03E+2 --5.07F , +- .2F,,0 1.07E+3 Co-58 -1.73- ',W43163 Co-60 -1.31E+4 E+6 .692E+4 2.26E+4 Ni-63 8.21 E+5 4.63E+4 -Z. -,18 , '6.33E+3 E.+ 32.80E+4 Ni-65 2.99E+0 2.96E-1 -< 18 8.40E+4 1.64E-1 Cu-64 -1.99E+0 -.-9.,+3 3.67E+4 1.07E+0 Zn-65 4.26E+4 1.13E+5. 4;5E+5 1.63E+4 7.03E+4 Zn-69 6.70E-2 9.66E-2-E 1.42E+3 1.02E+4 8.92E-3 Br-82 --____- 2.09E+4 Br-83 -___,/____ | .+ .67E+4 Co-57 -9.03E+2 --5.07F , +- .2F,,0 1.07E+3 Co-58 -1.73- ',W43163 Co-60 -1.31E+4 E+6 .692E+4 2.26E+4 Ni-63 8.21 E+5 4.63E+4 -Z. -,18 , '6.33E+3 E.+ 32.80E+4 Ni-65 2.99E+0 2.96E-1 -< 18 8.40E+4 1.64E-1 Cu-64 -1.99E+0 -.-9.,+3 3.67E+4 1.07E+0 Zn-65 4.26E+4 1.13E+5. 4;5E+5 1.63E+4 7.03E+4 Zn-69 6.70E-2 9.66E-2-E 1.42E+3 1.02E+4 8.92E-3 Br-82 --____- 2.09E+4 Br-83 -___,/____ | ||
| Line 588: | Line 588: | ||
In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Page 2 application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that either disposal method was acceptable provided:-if the material is to be left in the lagoon, it would be capped in accordance with Wisconsin State statutes. | In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Page 2 application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that either disposal method was acceptable provided:-if the material is to be left in the lagoon, it would be capped in accordance with Wisconsin State statutes. | ||
XZN-if the on site landspreading option is utilized, the material would disking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading performance standards. | XZN-if the on site landspreading option is utilized, the material would disking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading performance standards. | ||
Should there be any additional qu member of my siaff.Sincerely, C. A. Schrock Manager -Nuclear Engineering Pq(bctional and ,free to contact a LICXDJMN492 0 S S 0 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 DJIrjms Attach.cc -.US NRC -Mr. Patrick D-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 ATTACHMENT I To 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Letter from K. H. Evers (WPSC) to Document Dated (NRC)'1 D-5 S KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page I 0 0 References | Should there be any additional qu member of my siaff.Sincerely, C. A. Schrock Manager -Nuclear Engineering Pq(bctional and ,free to contact a LICXDJMN492 0 S S 0 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 DJIrjms Attach.cc -.US NRC -Mr. Patrick D-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 ATTACHMENT I To 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Letter from K. H. Evers (WPSC) to Document Dated (NRC)'1 D-5 S KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page I 0 0 References | ||
: 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989.NRC Question #1 On page 4 of your submittal, the average input to the Sewage'System is approximately 11,000 gallons per day. In the FA Statement, this system is to be operated below its desi of gallons per day. Discuss this deviation from the d cap d provide information to justify the higher output for thi te WPSC Response The original Sewage Treatment S th a Kewamee Nuclear Power Plant (KNPP) was rp 1a19 a higher capacity system. The original system was I .. work force of around [50 people.It was a limited capa ,/ ae c il ent system which included the onsite lagoon for additi '4< c ause of this limited capacity and more stringent con s steeffluent to Lake Michigan, an aerobic digester system wasi which has a higher capacity, and uses current techno input volume to the Sewage Treatment System used in the Septir 12. 1989 application was 11,000 gallons per day. This value was based on past operating data. The increase in influent from the original design basis included in the Final Environmental Statement is due mainly to an increase in the number of individuals and facilities (e.g., training and simulator building) located onsite. Design changes to the system were required to accommodate these new facilities. | : 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989.NRC Question #1 On page 4 of your submittal, the average input to the Sewage'System is approximately 11,000 gallons per day. In the FA Statement, this system is to be operated below its desi of gallons per day. Discuss this deviation from the d cap d provide information to justify the higher output for thi te WPSC Response The original Sewage Treatment S th a Kewamee Nuclear Power Plant (KNPP) was rp 1a19 a higher capacity system. The original system was I .. work force of around [50 people.It was a limited capa ,/ ae c il ent system which included the onsite lagoon for additi '4< c ause of this limited capacity and more stringent con s steeffluent to Lake Michigan, an aerobic digester system wasi which has a higher capacity, and uses current techno input volume to the Sewage Treatment System used in the Septir 12. 1989 application was 11,000 gallons per day. This value was based on past operating data. The increase in influent from the original design basis included in the Final Environmental Statement is due mainly to an increase in the number of individuals and facilities (e.g., training and simulator building) located onsite. Design changes to the system were required to accommodate these new facilities. | ||
D 0 0 D-60 0 0 0 O KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 O 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. This O increase has no significant effect on the dose modeling. (Refer to the response O to NRC Question #2, below.)O NRC Question #2 Provide information regarding how the disposal plan assur a an* dose to any exposed individual will be kept below 1WPSC Response n#a cocnrto 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 | D 0 0 D-60 0 0 0 O KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 O 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. This O increase has no significant effect on the dose modeling. (Refer to the response O to NRC Question #2, below.)O NRC Question #2 Provide information regarding how the disposal plan assur a an* dose to any exposed individual will be kept below 1WPSC Response n#a cocnrto 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 | ||
| Line 652: | Line 652: | ||
These waste streams are normally ratmd from the radioactive streams. However, due mainly to infrequent, minor syvtem leaks, and anticipated operational occurrences, the potential exists for these systems to become slightly contaminated. | These waste streams are normally ratmd from the radioactive streams. However, due mainly to infrequent, minor syvtem leaks, and anticipated operational occurrences, the potential exists for these systems to become slightly contaminated. | ||
At Kewaunee, the Oecondary system demineralizer resins, the survice water pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels.0 0 0D-19 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-2 -During the yearly testing of a batch of pre-treatment sludge, it was found that approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.3.0 PROPOSED DISPOSAL METHOD WPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsite pursuant to 10 CFR 20.302. The sludge is currently contained in an onsite lagoon at the KNPP sewage treatment facility. | At Kewaunee, the Oecondary system demineralizer resins, the survice water pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels.0 0 0D-19 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-2 -During the yearly testing of a batch of pre-treatment sludge, it was found that approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.3.0 PROPOSED DISPOSAL METHOD WPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsite pursuant to 10 CFR 20.302. The sludge is currently contained in an onsite lagoon at the KNPP sewage treatment facility. | ||
The disposal of the sludge will ha hv l~ndI 2nnliratinn tn an araa lncat~d nnsiti@ at K(NPP_ as shown in Figure 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 I is 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 less years. T7 I Nucl ide Co-60 Cs-137 4.0 RADIOLOGICAL IMPACTS 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 The licensee has evaluated the fol in entT11exposura pathways to members of the general public fr he akbkuclides in the sludge: (1)external exposure caused by gr nsh froifr.,he disposal site; (2) internal exposure from inhalation of jed ionuclides; and (3) internal exposure from ingesti ng gr t0\- Pt staff has reviewed the licensee's calculatlonal methods andbsu Ion finds that they are consistent with NRC Regulatory Guide I1 culati n of Annual Doses to Man from Routine Releases of Reactor E eh or the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,,e n 1, October 1977. The staff finds the assessment method g- acg abye.Table 2 listý do ulated by the licensee for the maximally exposed member of t epu on a total activity of 0.170 mCi disposed of In the current yea .. as the cumulative impact of similar disposals during subsequent years. any repetitive disposals, the licensee must reapply to the NRC when a r ular disposal would exceed the. following boundary conditions: | The disposal of the sludge will ha hv l~ndI 2nnliratinn tn an araa lncat~d nnsiti@ at K(NPP_ as shown in Figure 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 I is 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 less years. T7 I Nucl ide Co-60 Cs-137 4.0 RADIOLOGICAL IMPACTS 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 The licensee has evaluated the fol in entT11exposura pathways to members of the general public fr he akbkuclides in the sludge: (1)external exposure caused by gr nsh froifr.,he disposal site; (2) internal exposure from inhalation of jed ionuclides; and (3) internal exposure from ingesti ng gr t0\- Pt staff has reviewed the licensee's calculatlonal methods andbsu Ion finds that they are consistent with NRC Regulatory Guide I1 culati n of Annual Doses to Man from Routine Releases of Reactor E eh or the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,,e n 1, October 1977. The staff finds the assessment method g- acg abye.Table 2 listý do ulated by the licensee for the maximally exposed member of t epu on a total activity of 0.170 mCi disposed of In the current yea .. as the cumulative impact of similar disposals during subsequent years. any repetitive disposals, the licensee must reapply to the NRC when a r ular disposal would exceed the. following boundary conditions: | ||
(1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.D-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-3-IAHLLZ Pathway Whole Body Dose Received by Maximally Exposed Individual (mremrvear) 0.034 0.008 0.007 Groundshine Inhalation Groundwater Ingestion TOTAL 0T.04 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 As shown in Table 2, the annual dose is expected to be on the 0.1 mrem or less. Such a dose is a small fraction of the 300 annually by members of the general public from sources of natu radiation. | (1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.D-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-3-IAHLLZ Pathway Whole Body Dose Received by Maximally Exposed Individual (mremrvear) 0.034 0.008 0.007 Groundshine Inhalation Groundwater Ingestion TOTAL 0T.04 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 As shown in Table 2, the annual dose is expected to be on the 0.1 mrem or less. Such a dose is a small fraction of the 300 annually by members of the general public from sources of natu radiation. | ||
The guidelines used by the NRC staff for onsite disposal are presented in Table 3, along with the staff's guideline has been satisfied. | The guidelines used by the NRC staff for onsite disposal are presented in Table 3, along with the staff's guideline has been satisfied. | ||
| Line 672: | Line 672: | ||
By letter dated June 23, 1994, as supplemented June 29, 1994, equ ed approval to use another onsite area for the disposal of ste sludge In addition to the location approved by the WR staff has completed its review of your request and f t roposal meets the radiological boundary conditions approv Il Ju 11. 1992, Safety Evaluation! | By letter dated June 23, 1994, as supplemented June 29, 1994, equ ed approval to use another onsite area for the disposal of ste sludge In addition to the location approved by the WR staff has completed its review of your request and f t roposal meets the radiological boundary conditions approv Il Ju 11. 1992, Safety Evaluation! | ||
and is therefore acceptable,. | and is therefore acceptable,. | ||
ta finds that your proposal is in accordance with 1o0 CFR 20 2 r aced 20.302 on This approval Is granted provided that t e ety Evaluation is permanently incorporated Into your Offsi cu ation Manual (01CM) as* an Appendix, and that future modif sot commitments are reported 4>S/-Richard | ta finds that your proposal is in accordance with 1o0 CFR 20 2 r aced 20.302 on This approval Is granted provided that t e ety Evaluation is permanently incorporated Into your Offsi cu ation Manual (01CM) as* an Appendix, and that future modif sot commitments are reported 4>S/-Richard | ||
: 3. Laufer, Acting Project Manager* Directorate 111-3\K 0Division of Reactor Projects III/IV*) Office of Nuclear Reactor Regulation | : 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~ | *Docket No 5 5* ~Enclo ei.-x* ~~~SafetA~Wl~ | ||
| Line 708: | Line 708: | ||
By letter dated October 17, 1995. as supplemented a6 r 5, you requested approval for the onsite disposal o con 1 treatment sludge In accordance with 10 CFR 20.2002. This ln to a previous disposal request that wa approved ca 17, 1992.The staff has completed Its review s that your proposal mets the radiological bound ad In the June 17.1992, Safety Evaluation, and Is theref.This approval is granted provided safety evaluation Is penmantly incorporated Into y culation Manual (000m) as an Appendix, and that future as comitments are reported to the NRC.Richard J.LweProject Manager Project Directorate 111-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Enclosur etY Evaluation cc: See next page NIRC to WPSC LJT 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 T A HMC (MO&E)M W Seitz (WPL)Lftq Nilbmn (AJFC D A BoilM 06 DEDayDI K H Rvm XNP M L Marchi D2 I X Jubin ('NSRAC)R P P"N(3)C A Sabiuck 3W?CS Simolr X"N C R Stelahu* D2 CA SmwStnzy s F Woz" D2 B Domnck NP (Corn)D-30 0 0* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 Hr. M. L. ,archi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 0 cc: Foley A Lardner Attention: | By letter dated October 17, 1995. as supplemented a6 r 5, you requested approval for the onsite disposal o con 1 treatment sludge In accordance with 10 CFR 20.2002. This ln to a previous disposal request that wa approved ca 17, 1992.The staff has completed Its review s that your proposal mets the radiological bound ad In the June 17.1992, Safety Evaluation, and Is theref.This approval is granted provided safety evaluation Is penmantly incorporated Into y culation Manual (000m) as an Appendix, and that future as comitments are reported to the NRC.Richard J.LweProject Manager Project Directorate 111-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Enclosur etY Evaluation cc: See next page NIRC to WPSC LJT 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 T A HMC (MO&E)M W Seitz (WPL)Lftq Nilbmn (AJFC D A BoilM 06 DEDayDI K H Rvm XNP M L Marchi D2 I X Jubin ('NSRAC)R P P"N(3)C A Sabiuck 3W?CS Simolr X"N C R Stelahu* D2 CA SmwStnzy s F Woz" D2 B Domnck NP (Corn)D-30 0 0* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 Hr. M. L. ,archi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 0 cc: Foley A Lardner Attention: | ||
1r. Bradley 0. Jackson*One South Pinckney Street P. 0. Box 1497 H Madison, Wisconsin 53701-1497 Chairman Town of Carlton Route I Kewaunee, Wisconsin 54216*Mr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse | 1r. Bradley 0. Jackson*One South Pinckney Street P. 0. Box 1497 H Madison, Wisconsin 53701-1497 Chairman Town of Carlton Route I Kewaunee, Wisconsin 54216*Mr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse | ||
*Kewaunee, Wisconsin 54216* Chairman Public Service Commisslon of* Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702* Attorney General 114 East, State Capitol* Madison, Wisconsin "702 U. S. Nuclear Regulatory Comisst-Resident Inspectors Office.Route 0l, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator I U. S. Nuclear Regula C rs'801 Warrenville Road* Lisle, Illinois 2 Mr. Robert S. ln Chief Enginer ic I missi on P. 0. 00 /85..-MadisonA m 53707*0 0 0 0 0 0 0 0 0 D-3 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 UNITED STATES NUCLEAR REGULATORY COMMISSION WAgNINGTON, D..0 206SO-M SAFM EVALUATION fLY THE OfF CF NiLEAR REACTOb REC.LATIOM RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELYO cONTAmINATED SEvAGE TREATmENT SLwUGE AT THE KEVAINEE NMLEAR POWER PLANT WISCONSIN PUBLIC SERVICE CORPORATION MADISON GAS AND ELECTRIC COMPANV DOCKET HO. SC-305 By lettero ated October 17, 1995, as imaplwtwt n V 1 Wisconsin Public Service Co rtio Tic approval for the onsite disposal of contaminated s i sl t previous disposal request that was approved by the , O 2.0 In a letter dated September | *Kewaunee, Wisconsin 54216* Chairman Public Service Commisslon of* Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702* Attorney General 114 East, State Capitol* Madison, Wisconsin "702 U. S. Nuclear Regulatory Comisst-Resident Inspectors Office.Route 0l, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator I U. S. Nuclear Regula C rs'801 Warrenville Road* Lisle, Illinois 2 Mr. Robert S. ln Chief Enginer ic I missi on P. 0. 00 /85..-MadisonA m 53707*0 0 0 0 0 0 0 0 0 D-3 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 UNITED STATES NUCLEAR REGULATORY COMMISSION WAgNINGTON, D..0 206SO-M SAFM EVALUATION fLY THE OfF CF NiLEAR REACTOb REC.LATIOM RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELYO cONTAmINATED SEvAGE TREATmENT SLwUGE AT THE KEVAINEE NMLEAR POWER PLANT WISCONSIN PUBLIC SERVICE CORPORATION MADISON GAS AND ELECTRIC COMPANV DOCKET HO. SC-305 By lettero ated October 17, 1995, as imaplwtwt n V 1 Wisconsin Public Service Co rtio Tic approval for the onsite disposal of contaminated s i sl t previous disposal request that was approved by the , O 2.0 In a letter dated September | ||
: 12. ]ýJ t requested authorization for the alternate disposal of very- lIs tive material. | : 12. ]ýJ t requested authorization for the alternate disposal of very- lIs tive material. | ||
In a Safety Evaluation (SE) dated June 1approved the licensee's request pursuant to 10 CFR 20.302 10 for tiI disposal of 100 cubic feet of contaminat t l I l application at the Kewaunee Nuclear Power Plant (X 'i The SE imposed the following boundary conditions: | In a Safety Evaluation (SE) dated June 1approved the licensee's request pursuant to 10 CFR 20.302 10 for tiI disposal of 100 cubic feet of contaminat t l I l application at the Kewaunee Nuclear Power Plant (X 'i The SE imposed the following boundary conditions: | ||
| Line 764: | Line 764: | ||
==11.0 INTRODUCTION== | ==11.0 INTRODUCTION== | ||
The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent Controls, includes: | The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent Controls, includes: | ||
(1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively. | (1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively. | ||
Part II, Calculational Methodologies: | Part II, Calculational Methodologies: | ||
| Line 883: | Line 883: | ||
This is at least ten times the expected number of* defective 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 decay tank inventory is calculated assuming nuclide decay, degassing of the reactor coolant with*letdown at the maximum rate, and periodic purging to the gas decay tank. The maximum inventory for each nuclide during the degas and PURGE cycle is given in Appendix D,*Table D.7-1. (reference 1)The resultant dose consequence for this accident is 0.1 rem whole body at the SITE* BOUNDARY. | 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 decay tank inventory is calculated assuming nuclide decay, degassing of the reactor coolant with*letdown at the maximum rate, and periodic purging to the gas decay tank. The maximum inventory for each nuclide during the degas and PURGE cycle is given in Appendix D,*Table D.7-1. (reference 1)The resultant dose consequence for this accident is 0.1 rem whole body at the SITE* BOUNDARY. | ||
Summing the activities in USAR Table D.7-1 (reference | 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 | : 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 when considered as Xe-133. Kewaunee Power Station does not have a calculation correcting the*waste gas decay tank activity to a SITE BOUNDARY consequence of < 0.5 rem, therefore by limiting the activity in a waste gas decay tank to that which results in 0.1 rem at the SITE*BOUNDARY, the 0.5 rem limit will not be exceeded.DVR 13.2.5 frequency is modified by a note that restricts performing the verification when*additions are made to a tank to only when the reactor coolant system DOSE EQUIVALENT | : 5) referenced to Xe-133 results in a curie content of 52,000 curies when considered as Xe-133. Kewaunee Power Station does not have a calculation correcting the*waste gas decay tank activity to a SITE BOUNDARY consequence of < 0.5 rem, therefore by limiting the activity in a waste gas decay tank to that which results in 0.1 rem at the SITE*BOUNDARY, the 0.5 rem limit will not be exceeded.DVR 13.2.5 frequency is modified by a note that restricts performing the verification when*additions are made to a tank to only when the reactor coolant system DOSE EQUIVALENT | ||
* Iodine 131 (DEI-131) activity is greater than 1.0 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 | * 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 | ||
| Line 958: | Line 958: | ||
* specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and 2.OE-04 p Ci/ml for dissolved or entrained noble gases). The following equation 1 must be satisified | * specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and 2.OE-04 p Ci/ml for dissolved or entrained noble gases). The following equation 1 must be satisified | ||
*to meet the liquid effluent restrictions: | *to meet the liquid effluent restrictions: | ||
c< 1OxC(F+f) | c< 1OxC(F+f) | ||
(1.1)0f 0 0 0 0 0 0* 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 1.0-1 0 0 0 0 KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 where: 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 2x10-4 pCi/ml.C = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity 0 concentration in the effluent line prior to dilution and subsequent release; the 0 setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of ODCM Normal Condition 13.1.1. 0 0 f = the flow rate at the radiation monitor location in volume per unit time, but in the 0 same units as F, below.0 F = the dilution water flow rate as measured prior to the release point, in volume per unit time.[Note that if no dilution is provided, c < C. Also, note that when (F) is large compared to (f), then (F + f) = F.]0 1.2.1 Liquid Effluent Monitors (Radwaste and Service Water)The setpoints for the liquid effluent monitors at the Kewaunee Power Station are determined by the following equations: | (1.1)0f 0 0 0 0 0 0* 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 1.0-1 0 0 0 0 KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 where: 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 2x10-4 pCi/ml.C = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity 0 concentration in the effluent line prior to dilution and subsequent release; the 0 setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of ODCM Normal Condition 13.1.1. 0 0 f = the flow rate at the radiation monitor location in volume per unit time, but in the 0 same units as F, below.0 F = the dilution water flow rate as measured prior to the release point, in volume per unit time.[Note that if no dilution is provided, c < C. Also, note that when (F) is large compared to (f), then (F + f) = F.]0 1.2.1 Liquid Effluent Monitors (Radwaste and Service Water)The setpoints for the liquid effluent monitors at the Kewaunee Power Station are determined by the following equations: | ||
0 SSW xSENi)SP < +bkg (1.2)C, x RR Zi0xEC0 where: 0 SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)C = the concentration of radionuclide "i" in the liquid effluent (pCi), to include gamma emitters only 10xECi= ten times the EC value corresponding to radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml) 0 1.0-2 0 0 0 0 0 O O KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 O SENi the sensitivity value to which the monitor is calibrated for O radionuclide "i" (cpm per pCi/ml). The default calibration value from Table 1.1 may be used for gamma emitting radionuclides in lieu of nuclide specific values.O SW = the service water flow rate (dilution water flow) at the time of release (gal/min)0 O 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 periods when the service water dilution is at its lowest. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.At its lowest value, SW will equal RR and equation (1.2) reverts to the following 0 equation: 0 X(C 1 xSEN.)O SP ' bkg (1.3)Z (IOx ECO)0 1.2.2 Conservative Default Values Non-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) are not detected by the effluent monitor and, therefore, are not directly included in the above setpoint 0equation. | 0 SSW xSENi)SP < +bkg (1.2)C, x RR Zi0xEC0 where: 0 SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)C = the concentration of radionuclide "i" in the liquid effluent (pCi), to include gamma emitters only 10xECi= ten times the EC value corresponding to radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml) 0 1.0-2 0 0 0 0 0 O O KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 O SENi the sensitivity value to which the monitor is calibrated for O radionuclide "i" (cpm per pCi/ml). The default calibration value from Table 1.1 may be used for gamma emitting radionuclides in lieu of nuclide specific values.O SW = the service water flow rate (dilution water flow) at the time of release (gal/min)0 O 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 periods when the service water dilution is at its lowest. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.At its lowest value, SW will equal RR and equation (1.2) reverts to the following 0 equation: 0 X(C 1 xSEN.)O SP ' bkg (1.3)Z (IOx ECO)0 1.2.2 Conservative Default Values Non-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) are not detected by the effluent monitor and, therefore, are not directly included in the above setpoint 0equation. | ||
| Line 1,072: | Line 1,072: | ||
of Effective EC (ECe)2000 2001 2002 Nuclide EC (IiCi/ml) | of Effective EC (ECe)2000 2001 2002 Nuclide EC (IiCi/ml) | ||
T Release (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+00 Cr-51 5.OOE-04 1.44E-03 2.89E+00 6.85E-04 8.26E-04 1.65E+00 4.83E-04 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 3.00E-05 1.49E-04 4.97E+00 I. 18E-03 3.30E-04 1.1OE+01 3.22E-03 6.41 E-05 2.14E+00 9.83E-04 Fe-55 1.00E-04 4.81E-02 4.81E+02 1.14E-01 4.85E-02 4.85E+02 1.42E-01 3.69E-02 3.69E+02 1.70E-01 Co-57 6.OOE-05 0.OOE+00 0.OOE+00 0.OOE+00 2.42E-05 4.03E-01 1.18E-04 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 2.OOE-05 8.07E-03 4.04E+02 9.59E-02 4.09E-03 2.05E+02 5.99E-02 4.94E-03 2.47E+02 1.14E-01 Fe-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-03 Co-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-01 Br-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+00 Sr-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-02 Sr-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-02 Zr-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-03 Nb-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-03 Ag-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-01 Sn-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-03 Sb-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-03 Sb-125 3.OOE-05 4.86E-03 1.62E+02 3.85E-02 1.02E-03 3.41E+01 9.99E-03 2.46E-03 8.18E+01 3.76E-02 1-132 1.00E-04 0.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+00 1-133 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+00 1-135 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+00 Cs-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-03 Total 7.46E-02 4.21E+03 1.00E+00 6.34E-02 3.42E+03 1.00E+00 5.06E-02 2.17E+03 1.00E+00 Non-Gamma Fraction * : 0.23 _ _ _ _ _ 0.30 _ _ _ _, 0.29 Gamma Fraction _ _ _,_ 0.77 ,: _,_ _,_ 0.70 ,: ,: ,: 0.71 EC, (pCi/ml, total) 1.77E-05 1.86E-05 2.33E-05 ECe (pCi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06 C-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 APPENDIX D On-site Disposal of Low-Level Radioactively Contaminated Waste Streams D-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 Appendix D consists of hard copies of the following reference documents: | T Release (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+00 Cr-51 5.OOE-04 1.44E-03 2.89E+00 6.85E-04 8.26E-04 1.65E+00 4.83E-04 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 3.00E-05 1.49E-04 4.97E+00 I. 18E-03 3.30E-04 1.1OE+01 3.22E-03 6.41 E-05 2.14E+00 9.83E-04 Fe-55 1.00E-04 4.81E-02 4.81E+02 1.14E-01 4.85E-02 4.85E+02 1.42E-01 3.69E-02 3.69E+02 1.70E-01 Co-57 6.OOE-05 0.OOE+00 0.OOE+00 0.OOE+00 2.42E-05 4.03E-01 1.18E-04 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 2.OOE-05 8.07E-03 4.04E+02 9.59E-02 4.09E-03 2.05E+02 5.99E-02 4.94E-03 2.47E+02 1.14E-01 Fe-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-03 Co-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-01 Br-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+00 Sr-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-02 Sr-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-02 Zr-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-03 Nb-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-03 Ag-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-01 Sn-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-03 Sb-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-03 Sb-125 3.OOE-05 4.86E-03 1.62E+02 3.85E-02 1.02E-03 3.41E+01 9.99E-03 2.46E-03 8.18E+01 3.76E-02 1-132 1.00E-04 0.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+00 1-133 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+00 1-135 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+00 Cs-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-03 Total 7.46E-02 4.21E+03 1.00E+00 6.34E-02 3.42E+03 1.00E+00 5.06E-02 2.17E+03 1.00E+00 Non-Gamma Fraction * : 0.23 _ _ _ _ _ 0.30 _ _ _ _, 0.29 Gamma Fraction _ _ _,_ 0.77 ,: _,_ _,_ 0.70 ,: ,: ,: 0.71 EC, (pCi/ml, total) 1.77E-05 1.86E-05 2.33E-05 ECe (pCi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06 C-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 APPENDIX D On-site Disposal of Low-Level Radioactively Contaminated Waste Streams D-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 Appendix D consists of hard copies of the following reference documents: | ||
DESCRIPTION | DESCRIPTION | ||
[ DATE DOCKET NUMBER Operating License DPR-43 Kewaunee Nuclear Power Plant October 17, 1991 NRC-9 1-148 Disposal of Low Level Radioactive 50-305 Material Proposed Disposal of Low Level Radioactive Waste Sludge Onsite at the June 17, 1992 K92-119 Kewaunee Nuclear Power Plant 50-305 (TAC No. M75047)Safety Evaluation For An Amendment To An Approved 10 CFR 20.302 Application September 14, 1994 K-94-195 For The Kewaunee Nuclear Plant 50-305 (TAC No. M89719)Alternate Disposal Of Contaminated Sewage Treatment Plant Sludge In November 13, 1995 K-95-172 Accordance With 10 CFR 20.2002 50-305 (TAC No. M93844)Onsite Disposal Of Contaminated Sludge K-97-64 Pursuant To 10 CFR 20.2002 April 9, 1997 50-305 (TAC No. M9741 1) 1 1 _1_0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Adapted from N D-2 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 WPSC ( 414) 433.1598 TELECOPIER (414) 433-5544 00 WISCONSIN PUDUIC SERVICE CORPOSUATIONd 61- %.artn AcarýS 0 PO Sax 19002 a Green Bav. W1 5d3C7-GC02 INRC 91-/14 EASYLINK 628S '993 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 bce -K M Badow, MGE N E Boys, WPL Larry Nielsen, ANFC D R Berg KNP D A Bollom 06 R E Drshtim KNP K H Evers 02 M L Marchi KNP D L Masank KNP I N Morrison D2 I R Mueller D2 D S Nf,,hqplk KNP L A Nuitls D2 (NSRAc)R P Pulec D2 I S Richmond D2 D J Ristau D2 D I Roon KNP.-7 T- /,6J A J Ruege D2 C A Schrock KNIP C S Smoker KNP C R Steinhardt D2 I I Wallsace KNP K H Weinhauer KNP S F Womiak D2 QA Vault KNP October 17, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: | [ DATE DOCKET NUMBER Operating License DPR-43 Kewaunee Nuclear Power Plant October 17, 1991 NRC-9 1-148 Disposal of Low Level Radioactive 50-305 Material Proposed Disposal of Low Level Radioactive Waste Sludge Onsite at the June 17, 1992 K92-119 Kewaunee Nuclear Power Plant 50-305 (TAC No. M75047)Safety Evaluation For An Amendment To An Approved 10 CFR 20.302 Application September 14, 1994 K-94-195 For The Kewaunee Nuclear Plant 50-305 (TAC No. M89719)Alternate Disposal Of Contaminated Sewage Treatment Plant Sludge In November 13, 1995 K-95-172 Accordance With 10 CFR 20.2002 50-305 (TAC No. M93844)Onsite Disposal Of Contaminated Sludge K-97-64 Pursuant To 10 CFR 20.2002 April 9, 1997 50-305 (TAC No. M9741 1) 1 1 _1_0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Adapted from N D-2 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 WPSC ( 414) 433.1598 TELECOPIER (414) 433-5544 00 WISCONSIN PUDUIC SERVICE CORPOSUATIONd 61- %.artn AcarýS 0 PO Sax 19002 a Green Bav. W1 5d3C7-GC02 INRC 91-/14 EASYLINK 628S '993 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 bce -K M Badow, MGE N E Boys, WPL Larry Nielsen, ANFC D R Berg KNP D A Bollom 06 R E Drshtim KNP K H Evers 02 M L Marchi KNP D L Masank KNP I N Morrison D2 I R Mueller D2 D S Nf,,hqplk KNP L A Nuitls D2 (NSRAc)R P Pulec D2 I S Richmond D2 D J Ristau D2 D I Roon KNP.-7 T- /,6J A J Ruege D2 C A Schrock KNIP C S Smoker KNP C R Steinhardt D2 I I Wallsace KNP K H Weinhauer KNP S F Womiak D2 QA Vault KNP October 17, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: | ||
Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Diwsosal of Low Level Radioactive Material | Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Diwsosal of Low Level Radioactive Material | ||
| Line 1,080: | Line 1,080: | ||
WPSC requested the State of Wisconsin Department of Natural Resources (WDNR) to review the disposal options for the service water pretreatment lagoon sludges. In reference 3, the WDNR completed a review of the most appropriate on site disposal methods for the slightly contaminated service water pretreatment lagoon sludges' The two proposed methods that the WDNR evaluated included in-situ capping of the sludge in the wastewater treatment lagoon and on site landspreading. | WPSC requested the State of Wisconsin Department of Natural Resources (WDNR) to review the disposal options for the service water pretreatment lagoon sludges. In reference 3, the WDNR completed a review of the most appropriate on site disposal methods for the slightly contaminated service water pretreatment lagoon sludges' The two proposed methods that the WDNR evaluated included in-situ capping of the sludge in the wastewater treatment lagoon and on site landspreading. | ||
In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Page 2 application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that either disposal method was acceptable provided:-if the material is to be left in the lagoon, it would be capped in accordance with Wisconsin State statutes.-if the on site landspreading option is utilized, the material would be spread by either disking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading requirements which include locational and performance standards. | In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Page 2 application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that either disposal method was acceptable provided:-if the material is to be left in the lagoon, it would be capped in accordance with Wisconsin State statutes.-if the on site landspreading option is utilized, the material would be spread by either disking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading requirements which include locational and performance standards. | ||
Should there be any additional questions please feel free to contact a member of my siaff.Sincerely, c~c( Z.'A.L C. A. Schrock Manager -Nuclear Engineering DJM/jms Attach.6 0 0 0 0 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S cc -.US NRC -Region 1l Mr. Patrick Castleman, US NRC D-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 ATTACHMENT I To 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Letter from K. H. Evers (WPSC) to Document Control Desk (NRC)Dated October 17, 1991 D-5 S KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 1 References | Should there be any additional questions please feel free to contact a member of my siaff.Sincerely, c~c( Z.'A.L C. A. Schrock Manager -Nuclear Engineering DJM/jms Attach.6 0 0 0 0 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S cc -.US NRC -Region 1l Mr. Patrick Castleman, US NRC D-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 ATTACHMENT I To 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Letter from K. H. Evers (WPSC) to Document Control Desk (NRC)Dated October 17, 1991 D-5 S KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 1 References | ||
: 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989. 0 NRC Question #1 On page 4 of your submittal, the average input to the Sewage Treatment System is approximately 11,000 gallons per day. In the Final Environmental Statement, this system is to be operated below its design capacity of 9,000 gallons per day. Discuss this deviation from the design capacity, and provide information to justify the higher output for this system.WPSC Response The original Sewage Treatment System installed at the Kewaunee Nuclear Power Plant (KNPP) was replaced in 1986 with a higher capacity system. The original system was designed for an onsite work force of around 150 people.It was a limited capacity aerobic treatment system which included the onsite lagoon for additional retention. | : 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989. 0 NRC Question #1 On page 4 of your submittal, the average input to the Sewage Treatment System is approximately 11,000 gallons per day. In the Final Environmental Statement, this system is to be operated below its design capacity of 9,000 gallons per day. Discuss this deviation from the design capacity, and provide information to justify the higher output for this system.WPSC Response The original Sewage Treatment System installed at the Kewaunee Nuclear Power Plant (KNPP) was replaced in 1986 with a higher capacity system. The original system was designed for an onsite work force of around 150 people.It was a limited capacity aerobic treatment system which included the onsite lagoon for additional retention. | ||
Because of this limited capacity and more stringent conditions on system effluent to Lake Michigan, an aerobic digester system was installed, which has a higher capacity, and uses current technology. | Because of this limited capacity and more stringent conditions on system effluent to Lake Michigan, an aerobic digester system was installed, which has a higher capacity, and uses current technology. | ||
| Line 1,091: | Line 1,091: | ||
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. | This LLD ensures the identification of*any contaminated materials at a fraction of the allowable concentration limits*for the alternative disposal.The results of these analyses will be used to ensure that any detectable levels* of radioactive material are within the limits for alternative disposal. | ||
Any materials with levels of radioactive material above the concentration limits D 0 0*D-7 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 3 (and of plant origin) will be treated as a radioactive waste and appropriately controlled. | Any materials with levels of radioactive material above the concentration limits D 0 0*D-7 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 3 (and of plant origin) will be treated as a radioactive waste and appropriately controlled. | ||
0 Records will be maintained to ensure that the cumulative disposal of any contaminated materials are maintained within the bounds of the evaluation. | 0 Records will be maintained to ensure that the cumulative disposal of any contaminated materials are maintained within the bounds of the evaluation. | ||
[n 0 addition to a comparison of the individual radionuclide concentration limits, a record of the total amount of radioactive material disposed of will be maintained. | [n 0 addition to a comparison of the individual radionuclide concentration limits, a record of the total amount of radioactive material disposed of will be maintained. | ||
Cumulative totals will be maintained to ensure that the total activity does not exceed the quantity assumed in the derivation of the limits.In developing the concentration limits presented in Table I of reference 1, it was assumed the total annual design basis volume of 27,000 ft 3 would be contaminated at the derived limit. The dose commitment from each radionuclide was individually evaluated as if it were the only radioactive material present. To determine if a mixture of radionuclides meets the limit, the sum-of-the-fractions rule should be applied (i.e., the sum of each radionuclide's concentration divided by its limiting concentration must be less than one)..The concentration limits of Table I of reference I also have an implied total activity limit. This limit is determined by multiplying the individual radionuclide concentration limit by the total estimated waste volume of 27,000 ft 3.These total activity limits are presented in Table A of this response, for each radionuclide individually. | Cumulative totals will be maintained to ensure that the total activity does not exceed the quantity assumed in the derivation of the limits.In developing the concentration limits presented in Table I of reference 1, it was assumed the total annual design basis volume of 27,000 ft 3 would be contaminated at the derived limit. The dose commitment from each radionuclide was individually evaluated as if it were the only radioactive material present. To determine if a mixture of radionuclides meets the limit, the sum-of-the-fractions rule should be applied (i.e., the sum of each radionuclide's concentration divided by its limiting concentration must be less than one)..The concentration limits of Table I of reference I also have an implied total activity limit. This limit is determined by multiplying the individual radionuclide concentration limit by the total estimated waste volume of 27,000 ft 3.These total activity limits are presented in Table A of this response, for each radionuclide individually. | ||
| Line 1,159: | Line 1,159: | ||
At Kewaunee, the tecondary system demineralizer resins, the service water pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels.0 0 0 0 0 D-I 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013-2-0 During the yearly testing of a batch of pre-treatment sludge, it was found that approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.3.0 PROPOSED DISPOSAL METHOD WPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsite pursuant to 10 CFR 20.302. The sludge is currently contained in an onsite lagoon at the KNPP sewage treatment facility. | At Kewaunee, the tecondary system demineralizer resins, the service water pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels.0 0 0 0 0 D-I 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013-2-0 During the yearly testing of a batch of pre-treatment sludge, it was found that approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.3.0 PROPOSED DISPOSAL METHOD WPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsite pursuant to 10 CFR 20.302. The sludge is currently contained in an onsite lagoon at the KNPP sewage treatment facility. | ||
The disposal of the sludge will be by land application to an area located onsite at KNPP, as shown in Figure 1. 7he area will be periodically plowed to a depth of 6 inches.Table I lists the principal nuclides identified in the sludge. The activity is based on measurements made in 1989. The radionuclide half-lives, which are dominated by 30-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (reference 6), which apply to radionuclides with half-lives less than 35 y e a r s .T Nuclide Total Activity (mCil Co-60 0.076 Cs-137 0.094 0.170 0 4,0 RADIOLOGICAL tMPACTS The licensee has evaluated the following potential exposure pathways to members of the general public from the radionuclides in the sludge: (1)external exposure caused by groundshlne from the disposal site; (2) internal exposure from inhalation of re-suspended radionuclides; and (3) internal exposure from ingesting ground water. The staff has reviewed the licensee's calculatlonal methods and assumptions and finds that they are consistent with NRC Regulatory Guide 1,109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977. The staff finds the assessment methodology acceptable. | The disposal of the sludge will be by land application to an area located onsite at KNPP, as shown in Figure 1. 7he area will be periodically plowed to a depth of 6 inches.Table I lists the principal nuclides identified in the sludge. The activity is based on measurements made in 1989. The radionuclide half-lives, which are dominated by 30-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (reference 6), which apply to radionuclides with half-lives less than 35 y e a r s .T Nuclide Total Activity (mCil Co-60 0.076 Cs-137 0.094 0.170 0 4,0 RADIOLOGICAL tMPACTS The licensee has evaluated the following potential exposure pathways to members of the general public from the radionuclides in the sludge: (1)external exposure caused by groundshlne from the disposal site; (2) internal exposure from inhalation of re-suspended radionuclides; and (3) internal exposure from ingesting ground water. The staff has reviewed the licensee's calculatlonal methods and assumptions and finds that they are consistent with NRC Regulatory Guide 1,109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977. The staff finds the assessment methodology acceptable. | ||
Table 2 lists the doses calculated by the licensee for the maximally exposed member of the public based on a total activity of 0.170 Wi disposed of in the current year, as well as the cumulative Impact of similar disposals during subsequent years. For any repetitive disposals, the licensee must reapply to the NRC when a particular disposal would exceed the following boundary conditions: | Table 2 lists the doses calculated by the licensee for the maximally exposed member of the public based on a total activity of 0.170 Wi disposed of in the current year, as well as the cumulative Impact of similar disposals during subsequent years. For any repetitive disposals, the licensee must reapply to the NRC when a particular disposal would exceed the following boundary conditions: | ||
(1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.0 0 0 0 0 0 D-20 0 0 0 | (1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.0 0 0 0 0 0 D-20 0 0 0 | ||
* KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0*~ -3 Whole Body Dose Received by Maximally Exposed Individual Pathway (mrem/vear) | * KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0*~ -3 Whole Body Dose Received by Maximally Exposed Individual Pathway (mrem/vear) | ||
| Line 1,171: | Line 1,171: | ||
Principal Contributor: | Principal Contributor: | ||
J. Minns Date: June 17. 1992 D-23 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013-6-Figure I Kewaunee Nuclear Power Plant Site Area Map 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D-24 | J. Minns Date: June 17. 1992 D-23 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013-6-Figure I Kewaunee Nuclear Power Plant Site Area Map 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D-24 | ||
* KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013+ ,#A UNrTED STATES9/14 REGULATORY COMMMISlON O | * KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013+ ,#A UNrTED STATES9/14 REGULATORY COMMMISlON O | ||
: 14. 1994.Mr. C. A. Schrock Manager -Nuclear Engineering Wisconsin Public Service Corporation Post Office Box 19002*Green Bay, 1I 54307-9002 | : 14. 1994.Mr. C. A. Schrock Manager -Nuclear Engineering Wisconsin Public Service Corporation Post Office Box 19002*Green Bay, 1I 54307-9002 | ||
| Line 1,179: | Line 1,179: | ||
==Dear Mr. Schrock:== | ==Dear Mr. Schrock:== | ||
By letter dated June 23, 1994, as supplemented June 29, 1994, you requested approval to use another onsite area for the disposal of contaminated waste sludge In addition to the location approved by the NRC on June 17, 1992. The staff has completed its review of your request and finds that your proposal meets the radiological boundary conditions approved In the June 17. 1992.*Safety Evaluation, and Is therefore acceptable. | By letter dated June 23, 1994, as supplemented June 29, 1994, you requested approval to use another onsite area for the disposal of contaminated waste sludge In addition to the location approved by the NRC on June 17, 1992. The staff has completed its review of your request and finds that your proposal meets the radiological boundary conditions approved In the June 17. 1992.*Safety Evaluation, and Is therefore acceptable. | ||
The staff also finds that your proposal is in accordance with 10 CFR 20.2002 which replaced 20.302 on*January 1, 1994.This approval is granted provided that the enclosed Safety Evaluation is permanently Incorporated Into your Offsite Dose Calculation Manual (O0CM) as 0 an Appendix, and that future modifications of these comitments are reported* to the NRC.*Sincerely,*Richard J. Laufer, Acting Project Manager*Project Directorate | The staff also finds that your proposal is in accordance with 10 CFR 20.2002 which replaced 20.302 on*January 1, 1994.This approval is granted provided that the enclosed Safety Evaluation is permanently Incorporated Into your Offsite Dose Calculation Manual (O0CM) as 0 an Appendix, and that future modifications of these comitments are reported* to the NRC.*Sincerely,*Richard J. Laufer, Acting Project Manager*Project Directorate | ||
[11-3 Division of Reactor Projects Ill/IV*Office of Nuclear Reactor Regulation | [11-3 Division of Reactor Projects Ill/IV*Office of Nuclear Reactor Regulation | ||
* Docket No. 50-3os | * Docket No. 50-3os | ||
| Line 1,200: | Line 1,200: | ||
locatioit will meet all the radiological boundary conditions contained in the SE for the 10 CFR 20.302 application approved on June 17, 1992. Additionally, the licensee has stated that this additional disposal site will meet all O 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 and performance standards that were required at the original disposal site.O O O O D-27 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 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 the radiological boundary conditions approved In the June 17, 1992, SE and Is therefore acceptable. | locatioit will meet all the radiological boundary conditions contained in the SE for the 10 CFR 20.302 application approved on June 17, 1992. Additionally, the licensee has stated that this additional disposal site will meet all O 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 and performance standards that were required at the original disposal site.O O O O D-27 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 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 the radiological boundary conditions approved In the June 17, 1992, SE and Is therefore acceptable. | ||
The staff also finds that your proposal is In accordance 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 20.302 application, the licensee Is required to permanently Incorporate this modification into the Offsite Dose Calculation Manual as an Appendix, and that future modification of this comitment be reported to the NRC.Principal Contributor: | The staff also finds that your proposal is In accordance 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 20.302 application, the licensee Is required to permanently Incorporate this modification into the Offsite Dose Calculation Manual as an Appendix, and that future modification of this comitment be reported to the NRC.Principal Contributor: | ||
S. [lementowicz Date: September | S. [lementowicz Date: September | ||
: 14. 1994 | : 14. 1994 | ||
| Line 1,224: | Line 1,224: | ||
In a Safety Evaluation (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 wasta sludge by land application at the Kewaunee Nuclear Power Plant (KNPP) location. | In a Safety Evaluation (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 wasta sludge by land application at the Kewaunee Nuclear Power Plant (KNPP) location. | ||
The SE imposed the following boundary conditions: | The SE imposed the following boundary conditions: | ||
: 1. The annual disposal must be less than a total activity of 0.2 MCI.2. The whole body dose to the hypothetical maximally exposed Individual must be less than 0.1 | : 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 boundary conditions of the previously approved disposal.3.0 *YALUAI.WI The 1 icensee has proposed to dispose of approximately 5000 gallons (800 cubic O feet) of sewage sludge similar to the material approved for disposal in the SE dated June 17, 1992. The principal radlonuclides identified In the waste sludge and their activity based on measurements In Nay 19,9 are: Co-58, D 0 0 S D-32 O O 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 O 0.0009 ict; Co-60, 0.0008 mCi; and Cr-51, 0.0006 mCI. The total combined activity is 0.0023 noi. This activity is well below the boundary value of 0.2 mCi. Additionally, Cr-Il with It short half-life (27.7 day) will have O undergone significant decay from Its Initial value of 0.0006 mCi.* The licensee has committed that the now disposal will met all the radiological boundary conditions, on a cumulative basis, contained In the SE for the 10 CFR 20.M02 application approved on June 17, 1992. Additionally, the licensee has stated that all applicable permits for this disposal have been obtained from the Wisconsin Department of Natural Resources. | : 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 boundary conditions of the previously approved disposal.3.0 *YALUAI.WI The 1 icensee has proposed to dispose of approximately 5000 gallons (800 cubic O feet) of sewage sludge similar to the material approved for disposal in the SE dated June 17, 1992. The principal radlonuclides identified In the waste sludge and their activity based on measurements In Nay 19,9 are: Co-58, D 0 0 S D-32 O O 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 O 0.0009 ict; Co-60, 0.0008 mCi; and Cr-51, 0.0006 mCI. The total combined activity is 0.0023 noi. This activity is well below the boundary value of 0.2 mCi. Additionally, Cr-Il with It short half-life (27.7 day) will have O undergone significant decay from Its Initial value of 0.0006 mCi.* The licensee has committed that the now disposal will met all the radiological boundary conditions, on a cumulative basis, contained In the SE for the 10 CFR 20.M02 application approved on June 17, 1992. Additionally, the licensee has stated that all applicable permits for this disposal have been obtained from the Wisconsin Department of Natural Resources. | ||
O | O | ||
| Line 1,874: | Line 1,874: | ||
Guests: J Stafford, Chairperson | Guests: J Stafford, Chairperson | ||
-Director Safety and Licensing (1)JD Helbing, Supervisor | -Director Safety and Licensing (1)JD Helbing, Supervisor | ||
-Maintenance (1)JM Hale, Manager -RP/Chem (1)ME Aulik, Manager -Engineering | -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 III MW Grapentine, Electrical Maintenance Supervisor DA Jeanquart, Mechanical Maintenance Supervisor WG Swanson, Decommissioning Team-Ops MD Townsend, Hughes Associates | ()B McMahon, Manager -Operations (1)JM Schuh, Administrative Assistant -Decommissioning TS Wattleworth, Engineer III MW Grapentine, Electrical Maintenance Supervisor DA Jeanquart, Mechanical Maintenance Supervisor WG Swanson, Decommissioning Team-Ops MD 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 Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-078 Design Change (DC)Presenter: | -Fire Protection RG Krsek, NRC (1) Indicates Chairperson and Members required for quorum per LI-AA-600.(alt) Alternate Member (nv) Non-Voting Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-078 Design Change (DC)Presenter: | ||
| Line 1,906: | Line 1,906: | ||
Presenters: | Presenters: | ||
Guests: J Stafford, Chairperson | 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 | -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 Manager WG Swanson, Decommissioning Ops J Gadzala, Decommissioning R Edwards, USNR T Hanna, Supervisor Engineering (1) Indicates Chairperson and Members required for quorum per LI-AA-600.(alt) Alternate Member (nv) Non-Voting Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-112 Licensing Amendment Request (LAR)Presenter: | (!)SA Smidel, Administrative Assistant -Plant Manager WG Swanson, Decommissioning Ops J Gadzala, Decommissioning R Edwards, USNR T Hanna, Supervisor Engineering (1) Indicates Chairperson and Members required for quorum per LI-AA-600.(alt) Alternate Member (nv) Non-Voting Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-112 Licensing Amendment Request (LAR)Presenter: | ||
Gadzala Approved 1) LAR 256- PDTS, Supplement 2 By application dated May 29, 2013, Dominion Energy Kewaunee, Inc. (DEK), requested an amendment to Facility Operating License Number DPR-43 for Kewaunee Power Station (KPS). The proposed amendment would revise the Operating License and revise the associated Technical Specifications (TS) to Permanently Defueled Technical Specifications (PDTS). Supplement I to the application was submitted on October 15, 2013.Include within the changes proposed in the application was deletion of the cyber security provisions contained in License Condition 2.C.(4). This proposal was based on the requirements of 10 CFR 73.54. regarding cyber security, no longer applying FSRC Minutes Kewaunee Plant 12/19/13 Meeting No. 13-048 to KPS. However, the NRC staff recently verbally informed DEK that 10 CFR 73.54 continues to apply to facilities that were previously licensed to operate on the November 23, 2009 mandated date for that rule.In response to the staff's comments, DEK is revising the originally proposed amendment. | Gadzala Approved 1) LAR 256- PDTS, Supplement 2 By application dated May 29, 2013, Dominion Energy Kewaunee, Inc. (DEK), requested an amendment to Facility Operating License Number DPR-43 for Kewaunee Power Station (KPS). The proposed amendment would revise the Operating License and revise the associated Technical Specifications (TS) to Permanently Defueled Technical Specifications (PDTS). Supplement I to the application was submitted on October 15, 2013.Include within the changes proposed in the application was deletion of the cyber security provisions contained in License Condition 2.C.(4). This proposal was based on the requirements of 10 CFR 73.54. regarding cyber security, no longer applying FSRC Minutes Kewaunee Plant 12/19/13 Meeting No. 13-048 to KPS. However, the NRC staff recently verbally informed DEK that 10 CFR 73.54 continues to apply to facilities that were previously licensed to operate on the November 23, 2009 mandated date for that rule.In response to the staff's comments, DEK is revising the originally proposed amendment. | ||
Revision as of 09:07, 28 April 2019
| 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) | |
Text
Dominion Energy Kewaunee, Inc.N490 Hwy 42, Kewaunee, WI 54216 Web Address: www.dom.com APR 2 9 2014 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Serial No.14-149 LIC/NW/R0 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATION 2013 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Kewaunee Power Station (KPS) 2013 Annual Radioactive Effluent Release Report for January through December 2013. This report is submitted to meet the requirements of KPS Technical Specification 5.6.2 and 10 CFR 50.36a(a)(2).
If you have questions or require additional information, please feel free to contact Mr.Richard Repshas at 920-388-8217.
Very truly yours, Jeffrey T. Stafford Director Safety and Licensing, Kewaunee Power Station Commitments made by this letter: NONE Serial No.14-149 Page 2 of 2 cc: Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. Christopher Gratton Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D15 11555 Rockville Pike Rockville, MD 20852-2738 Mr. W. C. Huffman Jr.Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D15 11555 Rockville Pike Rockville, MD 20852-2738 Mr. W. A. Nestel Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339 Mr. Don Hendrikse WI Division of Public Health Radiation Protection Section Room 150 Madison, WI 53701-2659 Ms. Deborah Russo American Nuclear Insurers 95 Glastonbury Blvd.Glastonbury, CT 06033 0 0 S 0 0 S 0 0 0 0 0 S S S S 0 S S 0 S 0 S iADominion 2013 Annual Radioactive Effluent Release Report Kewaunee Power Station Dominion Energy Kewaunee, Inc.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 ,0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 DOCKET 50-305 KEWAUNEE POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1 -December 31, 2013 S 0 0 S S S S 0 0 0 S 0 S S S This page intentionally left blank 5 S 0 S S S S 0 S 0 0 S S S S S S S 0 S S S S S
- Table of Contents* Section Description 0.0 Sum m ary ......................................................................................................
3 1.0 Introduction....................................
................
3 1.1 Effluent D ose Lim its .....................................................................................
3 2.0 G aseous Effl uents .........................................................................................
5 2.1 Lower Limits of Detection (LLD) for Gaseous Effluents
............................
5 2.2 Gaseous Batch Release Statistics
.................................................................
7 2.3 Gaseous Effl uent Data ...................................................................................
7 Table 2.1 Gaseous Effluents
-Summation of all Releases ...........................
8 Table 2.2 Gaseous Effluent -Continuous Mode .....................
9 Table 2.3 Gaseous Release -Batch Mode .................................................
10 Table 2.4 Dose from Gaseous Effluents
.....................................................
11 2.4 Estimation of Carbon-14 in Gaseous Releases ..................................
13 3.0 Liquid Effluents
........................................................................................
14 3.1 Lower Limits of Detection (LLD) for Liquid Effluents
...............................
14 3.2 Liquid Batch Release Statistics
...................................................................
16 3.3 Liquid Effluent Data .......................................
16 Table 3.1 Liquid Effluents
-Summation of all Releases ............................
17 Table 3.2 Liquid Effluents
-Batch Mode ...................................................
18 Table 3.3 Liquid Effluents
-Continuous Mode ..........................................
19 Table 3.4 Dose from Liquid Effluents
.......................................................
20 3.4 Ground Water Monitoring
..........................................................................
22 4.0 U nplanned Releases ...................................................................................
24 5.0 M eteorological D ata ..................................................................................
24 6.0 Solid W aste D isposal ................................................................................
24 Table 6.1 Solid Waste and Irradiated Fuel Shipments
...............................
25 7.0 Program Revisions
.....................................................................................
33 8.0 Reportable Occurrences
..............................................................................
35 Appendix A Meteorological Data Appendix B KPS Offsite Dose Calculation Manual (ODCM), Rev. 15 Appendix C KPS Offsite Dose Calculation Manual (ODCM), Rev. 16 Appendix D KPS Radiological Environmental Monitoring manual (REMM), Rev. 20 Appendix E Documentation for Major Changes to Radioactive Waste Treatment Systems P 0* ae2o3 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0*t 0.0
SUMMARY
On 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 the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).
Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the*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 were well below regulatory limits. For individual effluent streams, the quarterly limit most closely approached was:* GASEOUS: Ingestion Pathway-Organ Total Body* Quarterly Limit (mRem) 7.5 nd Actual Dose (mRem) 5.42E-04 (2 Quarter)* % of Specification 7.23E-03* LIQUID: Ingestion Pathway-Organ GI-LLI* Quarterly Limit (mRem) 5.0 Actual Dose (mRem) 5.03E-03 (2 nd Quarter)% of Limit 1.OIE-01* SOLID: No upper limit for solid radioactive waste applies.Cubic Meters Shipped 3.19E+01 m 3 (1.31E+03 ft 3)*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 data from all effluent releases made from January 1 -December 31, 2013. The report contains summaries of the gaseous and liquid releases made to the environment including the quantity, characterization, time St duration and calculated radiation dose at the site boundary resulting from these releases.
The report also includes a summation of solid radioactive waste disposal, revisions to the Process Control Program and the Offsite Dose Calculation Manual, and addresses the cumulative meteorological data.Values indicated as 0 (zero) in this report refer to actual values less than the detection limits. A table* of these less than detectable (LLD) values is identified in sections 2.1 and 3.1.*t 1.1 Effluent Dose Limits Specifications 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 and cumulative quarterly and annual doses. The ODCM methodology is acceptable for use in demonstrating compliance with 10 CFR 20.1301/1302; 10 CFR 50, Appendix I; and 40 CFR 190.Page 4 of 35 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 S S S S S S S S S 0 0 0 S S S 0 S S S S 0 S 0 S S S S 0 0 0 0 0 0 0 0 0 S S S S S 0 0 0 0 S 0 0 2.0 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. The auxiliary 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 releases are 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: Analysis LLD (gCi/ml)Gaseous Gamma Emitters Iodine 131 Particulate Gamma Emitters Particulate Gross Alpha Strontium 89, 90 Noble Gases, Gross Beta or Gamma 1.OOE-04 3.OOE- 12 1.OOE- 1I L.OOE- 1I L.OOE- 11 1.OOE-06 The nominal "a priori" LLD values are shown below.Isotope a priori LLD (jtCi/ml)a. Gaseous emissions:
Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-138 5.61 E-08 1.02E-07 6.68E-08 2.75E-07 2.99E-08 1.13E-07 Page 5 of 35
- b. Particulate emissions:
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 1.11E-13 2.27E-13 2.28E-13 3.57E-13 1.68E-13 2.73E-13 4.69E- 13 1.68E-13 2.08E-13 1.24E-12 c. Other identifiable gamma emitters: Ar-41 Kr-85 Kr-85m Kr-89 Xe-127 Xe-131m Xe-135m Xe-137 1-131 3.97E-10 8.63E-05 4.62E-08 2.04E-06 4.20E-08 1.82E-06 1.90E-08 2.88E-07 1.32E-13 0 0 0 0 0 S 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S 0 0 S S S S S S S S 0 S 0 d. Composite particulate samples: Sr-89 1.OOE-14 Sr-90 1.00E- 14 Gross Alpha 1.OOE-14 These "a priori" LLDs represent the capabilities of the counting systems in use, not an after the fact "a posteriori" limit for a particular measurement.
Page 6 of 35 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 S S S 0 S 0 S 0 0 S 0 0 2.2 Gaseous Batch Release Statistics The following is a summation of all gaseous batch releases made during 2013.Number of batch releases .................................
27 Total time for all batch releases (min) ...............
2490.0 Maximum time for a batch release (min) ...........
1440.0 Average time for a batch release (min) ...................
92.1 Minimum time for a batch release (min) .................
16.0 2.3 Gaseous Effluent Data Table 2.1 presents a quarterly summation of the total activity released and average release rates of gaseous effluents.
Table 2.2 lists the quarterly sums of individual gaseous radionuclide released by continuous mode. Table 2.3 lists the quarterly sums of individual gaseous radionuclide released by batch mode. Table 2.4 presents the dose limits for gaseous effluents, and the calculated doses this year from gaseous effluents.
Page 7 of 35 Table 2.1 Gaseous Effluents
-Summation of all Releases Fission and Activation Gases Total Activity Released (Ci)Average Release Rate (ItCi/sec) 1 st Quarter O.OOE+00 O.OOE+00 2nd Quarter 1.79E-02 2.27E-03 3rd Quarter O.OOE+00 O.OOE+00 4th Quarter Total O.OOE+00 O.OOE+00 1.79E-02 5.67E-04 lodines Total Activity Released (Ci)Average Release Rate (gtCi/sec)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Particulates Total Activity Released (Ci)Average Release Rate (jtCi/sec)
O.OOE+00 O.OOE+00 6.84E-06 8.68E-07 O.OOE+00 O.OOE+00 2.8 1E-05 3.564E-06 3.49E-05 1.11 E-06 Tritium 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total Activity Released (Ci)Average Release Rate (ptCi/sec)
Gross Alpha Released (Ci)8.54E+00 1.08E+00 2.05E+01 2.60E+00 1.32E+01 1.67E+00 7.95E+00 1.01E+00 5.02E+01 1.59E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Carbon-14 Total Annual Activity Released (Ci)2.41E+00 Page 8 of 35 0 0 S S 0 0 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 Table 2.2 Gaseous Effluents
-Ground Level -Nuclides Released (Ci)Continuous Mode 1 st Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Fission Gases Total O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Iodines Total Particulates Co-58 Nb-95 Cs-137 m Total Gross Alpha Tritium O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.54E+00 5.84E-06 1.OOE-06 O.OOE+00 6.84E-06 O.OOE+00 5.57E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.32E+01 O.OOE+00 O.OOE+00 2.8 1E-05 2.8 1E-05 5.84E-06 1.OOE-06 2.8 1E-05 3.49E-05 O.OOE+00 O.OOE+00 7.95E+00 3.52E+01 0 0 0 0 0 0 0 0 0 (1) Cs- 137 isotope was in contaminated oil that was transferred to the heating boiler for disposal as part of the continuous release process.Page 9 of 35 0 0 0 0 Table 2.3 Gaseous Effluents
-Ground Level -Nuclides Released (Ci)Batch Mode 1 st Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Fission Gases Xe-133 Xe-133m Total lodines Total Particulates Total Tritium O.OOE+00 O.OOE+00 O.OOE+00 1.78E-02 3.77E-05 1.78E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.78E-02 3.77E-05 1.78E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.68E-03 O.OOE+00 O.OOE+00 1.49E+01 O.OOE+00 O.OOE+00 2.83E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.49E+01 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Gross Alpha O.OOE+00 O.OOE+00 Page 10 of 35 0 0 S 0 0 0 S 0 0 0 S 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 Table 2.4 Dose from Gaseous Effluents The offsite dose limits from radioactive materials in gaseous effluents are specified in Section 13.2.2 and 13.2.3 of the Kewaunee ODCM and can be summarized as follows: Limit Quarterly Annual Air Dose Gamma 5.0 mrad 10.0 mrad Air Dose Beta 10.0 mrad 20.0 mrad Organ 7.5 mrem 15.0 mrem The 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 Kewaunee ODCM. Calculated offsite doses versus quarterly and annual limits are shown below: 1 st Qtr 1. Gamma- Air Dose Specification (mrad)Actual Dose (mrad)% of Specification
- 2. Beta- Air Dose Specification (mrad)Actual Dose (mrad)% of Specification
- 3. Organ Dose Specification (mrem)Total Body Actual Dose (mrem)% of Specification Bone Actual Dose (mrem)% of Specification 5.OOE+00 0.OOE+00 0.OOE+00 1.00E+01 0.OOE+00 0.OOE+00 7.50E+00 2.26E-04 3.01E-03 0.00E+00 0.OOE+00 2nd Qtr 5.OOE+00 1.49E-07 2.98E-06 1.00E+01 4.43E-07 4.43E-06 7.50E+00 5.42E-04 7.23E-03 1.40E-07 1.86E-06 3rd Qtr 5.OOE+00 0.OOE+00 0.OOE+00 1.00E+01 0.OOE+00 0.OOE+00 4th Qtr 5.OOE+00 0.OOE+00 0.OOE+00 1.00E+01 0.OOE+00 0.OOE+00 Annual 1.00E+01 1.49E-07 1.49E-06 2.OOE+01 4.43E-07 2.22E-06 7.50E+00 7.50E+00 1.50E+01 3.48E-04 4.64E-03 0.OOE+00 0.OOE+00 2. 1OE-04 2.8 1E-03 5.99E-05 7.99E-04 1.33E-03 8.85E-03 6.01E-05 4.01 E-04 Page 11 of 35 Table 2.4 (continued)
Dose from Gaseous Effluents 1 st Qtr 2nd Qtr 3rd Q tr Liver Actual Dose (mrem)% of Specification Thyroid Actual Dose (mrem)% of Specification Kidney Actual Dose (mrem)% of Specification Lung Actual Dose (mrem)% of Specification GI-LLI Actual Dose (mrem)% of Specification 2.26E-04 3.01E-03 2.26E-04 3.01E-03 2.26E-04 3.01E-03 2.26E-04 3.01E-03 2.26E-04 3.01E-03 5.42E-04 7.23E-03 5.42E-04 7.23E-03 5.42E-04 7.23E-03 5.42E-04 7.23E-03 5.42E-04 7.23E-03 3.48E-04 4.64E-03 3.48E-04 4.64E-03 3.48E-04 4.64E-03 4th Qtr 2.11 E-04 2.81E-03 Annual 1.33E-03 8.85E-03 2. 1OE-04 1.33E-03 2.8 1E-03 8.85E-03 2.11E-04 2.8 1E-03 3.48E-04 2.1OE-04 4.64E-03 2.8 1E-03 1.33E-03 8.85E-03 1.33E-03 8.85E-03 1.33E-03 8.85E-03 3.48E-04 4.64E-03 2.1OE-04 2.8 1E-03 6 0 6 0 0 0 0 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 Page 12 of 35 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.4 Estimation of Carbon-14 in Gaseous Releases Per Nuclear Engineering in Innsbrook the Cycle 31 flux values are bounding and conservative and can be 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 CO 2.The highest estimated C-14 doses at the highest X/Q for ingestion and inhalation receptor (one mile west) were: 1.94E-01 mrem (2012 value) x 0.3837 = 7.44E-02 mrem as Child Bone Dose 3.88E-02 mrem (2012 value) x 0.3837 = 1.49E-02 mrem as Child Whole Body Page 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 is sampled prior to release and analyzed for gamma emitters and tritium. A fraction of each sample is retained for a monthly proportional composite which is then analyzed for Gross Alpha, Strontium 89, Strontium 90, Iron 55 and Nickel 63.The LLD's for liquid batch release radio-analyses, as listed in Table 13.1.1-1 of the Kewaunee ODCM are: Analysis Principal Gamma Emitters Iodine 131 Tritium Gross Alpha Strontium 89, 90 Iron 55 LLD (VCi/ml)1.00 E-06 1.00 E-06 1.00 E-05 5.00 E-07 5.00 E-08 1.00 E-06 The actual obtained "a priori" LLD values for batch releases are shown below.Isotope Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 1-131 H-3 Sr-89 Sr-90 Gross Alpha Fe-55 Ni-63 1 st Quarter 1.33E-07 2.22E-07 1.31E-07 1.33E-07 4.42E-08 9.40E-07 1.03E-07 9.5 1E-08 1.04E-07 3.09E-07 9.29E-08 2.69E-06 L.O1E-08 7.36E-09 7.84E-09 6.76E-07 1.22E-07 2nd Quarter 1.33E-07 3.92E-08 1.31E-07 2.34E-08 4.42E-08 6.98E-07 1.35E-08 9.5 1E-08 9.42E-08 5.43E-07 9.28E-08 3.16E-06 3.48E-08 6.94E-09 8.74E-09 7.77E-07 1.36E-07 3rd Quarter 1.75E-08 2.22E-07 9.73E-08 2.34E-08 4.42E-08 1.23E-07 1.03E-07 9.5 1E-08 1.04E-07 5.43E-07 9.28E-08 3.1OE-06 9.57E-09 7.12E-09 1.13E-08 7.87E-07 1.19E-07 4th Quarter 9.53E-08 3.78E-08 1.65E-08 2.05E-07 4.26E-08 8.99E-07 1.18E-07 1.22E-07 1.24E-07 3.54E-07 7.42E-08 3.OOE-06 NA NA NA NA NA Average a priori LLD (pCi/ml)9.47E-08 1.30E-07 9.40E-08 9.62E-08 4.38E-08 6.65E-07 8.44E-08 1.02E-07 1.07E-07 4.37E-07 8.82E-08 2.99E-06 1.82E-08 7.14E-09 9.29E-09 7.47E-07 1.26E-07 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 14 of 35 0 0 0 S 0 0 0 S 0 0 0 S 0 0 0 S 0 0 S 0 S S S 0 Continuous liquid releases are grab-sampled weekly and analyzed for principal gamma emitters.
A fraction of each weekly sample is retained for a monthly proportional composite which is then analyzed for Gross Alpha, Strontium 89, Strontium 90, Iron 55 and Nickel 63.The LLD's for liquid continuous release radioanalyses, as listed in Table 13.1.1-1 of the Kewaunee ODCM are: Analysis LLD (gtCi/ml)Principal Gamma Emitters Iodine 131 Tritium Gross Alpha Strontium 89, 90 Iron 55 5.00 E-07 1.00 E-06 1.00 E-05 5.00 E-07 5.00 E-08 1.00 E-06 The actual obtained "a priori" LLD values for continuous releases are shown below.Isotope Mn-54 Fe-59 Co-58 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce- 141 Ce- 144 1-131 H-3 Sr-89 Sr-90 Gross Alpha Fe-55 Ni-63 1 st Quarter 1.38E-08 1.80E-08 1.08E-08 1.38E-08 2.94E-08 9.03E-08 9.02E-09 9.94E-09 1.73E-08 7.94E-08 1.01E-08 2.69E-07 8.70E-09 5.69E-09 4.37E-09 6.80E-07 1.17E-07 2nd Quarter 1.52E-08 2.47E-08 1.14E-08 1.1 8E-08 1.49E-08 1.05E-07 9.91 E-09 9.26E-09 1.77E-08 8.38E-08 8.48E-09 3.16E-06 3.71E-08 7.83E-09 4.94E-09 7.91 E-07 1.15E-07 3rd Quarter 1.28E-08 1.99E-08 1.25E-08 1.55E-08 2.43E-08 7.78E-08 1.22E-08 1.17E-08 1.77E-08 6.76E-08 1.13E-08 3.1OE-06 6.32E-09 7.48E-07 1.16E-07 9.29E-09 6.50E-09 4th Quarter 4.39E-09 2.47E-08 1.20E-08 1.38E-08 2.61E-08 8.24E-08 9.48E-09 1.33E-08 1.68E-08 2.36E-08 9.36E-09 3.OOE-06 1.08E-08 6.29E-09 4.71E-09 6.76E-07 1.24E-07 Average a priori LLD (jiCi/ml)1.1 5E-08 2.18E-08 1.17E-08 1.37E-08 2.37E-08 8.89E-08 1.02E-08 1.11E-08 1.74E-08 6.36E-08 9.81 E-09 2.38E-06 1.57E-08 1.92E-07 3.25E-08 5.39E-07 9.06E-08 Page 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 ..................................
46 Total time for all batch releases (min) .............
33,000 Maximum time for a batch release (min) ...........
2,020 Minimum time for a batch release (min) ............
30 Average time for a batch release (min) ..................
718 3.3 Liquid Effluent Data The following Table 3.1 presents a quarterly summation of the total activity released and average concentration for all liquid effluents.
It also presents the gross alpha activity released, volume of waste released and volume of dilution water used. Table 3.2 contains the quantity of the individual isotopes released 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 from liquid effluents for each quarter and the calculated doses this year from liquid effluents.
Page 16 of 35 S 0 S 0 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 0 0 0 S S S S 0 0 S 0 0 S 0 0 S S S 0 Table 3.1 Liquid Effluents
-Summation of all Releases 1 st Qtr Fission and Activation Products Total Release (Ci)Average Concentration (gCi/ml)Tritium Total Release (Ci)Average Concentration (jICi/ml)% of Tech. Spec.Limit(3.OE-3 ptCi/ml)Dissolved and Entrained Gases Total Release (Ci)Average Concentration (jiCi/ml)% of Tech. Spec.Limit(2.OE-4 gaCi/ml)Gross Alpha Activity Total Release (Ci)Volume of Waste Released Total (liters)Volume of Dilution Water Total (liters)9.16E-04 5.71E-12 4.62E+01 2.88E-07 9.60E-03 0.OOE+00 0.OOE+00 0.OOE+00 2nd Qtr 1.12E-02 1.0LE-10 1.85E+02 1.67E-06 5.57E-02 7.67E-05 6.92E-13 3.46E-07 3rd Qtr 3.80E-03 3.47E-1 1 5.12E+01 4.68E-07 1.56E-02 0.OOE+00 0.OOE+00 0.OOE+00 4th Qtr O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total 1.59E-02 4.17E-11 2.82E+02 7.39E-07 2.46E-02 7.67E-05 2.OOE-13 1.OOE-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.49E+07 1.26E+07 6.12E+06 3.39E+06 4.70E+07 1.60E+ 1I 1.I11E+11 I .09E+1 I 2.14E+/-09 3.82E+11I Page 17 of 35 Table 3.2 Liquid Effluents
-Nuclides Batch Mode Released (Ci)I st Qtr 2nd Qtr 3rd Qtr 4th Qtr* Total Fission and Activation Products Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-63 Nb-95 Ag-I 10m Sn-I 17m Sb- 124 Sb- 125 Total Release O.OOE+00 4.81E-04 O.OOE+00 2.72E-05 1.58E-05 3.04E-04 O.OOE+00 3.65E-05 3.81 E-06 O.OOE+00 4.74E-05 9.16E-04 1.77E-04 2.38E-03 3.69E-05 2.87E-04 3.38E-03 4.01E-03 9.62E-05 5.3 1E-04 O.OOE+00 1.78E-05 3.19E-04 1.12E-02 O.OOE+00 2.22E-03 O.OOE+00 1.36E-04 7.72E-05 3.64E-04 O.OOE+00 1.60E-04 O.OOE+00 1.19E-04 7.16E-04 3.80E-03 NA NA NA NA NA NA NA NA NA NA NA NA 1.77E-04 5.08E-03 3.69E-05 4.50E-04 3.47E-03 4.68E-03 9.62E-05 7.28E-04 3.81 E-06 1.37E-04 1.08E-03 1.59E-02 0 S S S S S S S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 S S S S S S 0 Dissolved and Entrained Gases Xe-133 Total Release O.OOE+00 7.67E-05 O.OOE+00 7.67E-05 O.OOE+00 O.OOE+00 NA NA 7.67E-05 7.67E-05 Tritium Total Release 4.62E+01 1.85E+02 5.12E+01 NA 2.82E+2 Gross Alpha Activity Total Release O.OOE+00 O.OOE+00 O.OOE+00 NA O.OOE+00*There were no batch releases in the 4 th quarter.Page 18 of 35 Table 3.3 Liquid Effluents
-Nuclides Released (Ci)Continuous Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total Fission and Activation Products Total Release O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Dissolved and Entrained Gases Total Release O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Tritium Total Release 1.51E-02 6.44E-03 O.OOE+00 O.OOE+00 2.15E-02 S S S S S S S S S S S S S S S S S S S S S S S Gross Alpha Activity Total Release O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Page 19 of 35 Table 3.4 Dose from Liquid Effluents The dose to a member of the public from total liquid radioactive releases for each quarter was below the Kewaunee ODCM limits of 1.5 mrem to the total body and less than or equal to 5 mrem to any organ. Additionally, the dose to a member of the public from total liquid radioactive releases for the year was below the Kewaunee ODCM limits of 3 mrem to the total body and less than or equal to 10 mrem 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 the isotopes released exceed the concentrations specified in Appendix B. The following offsite doses were calculated using equation 1.7 from the Kewaunee ODCM.1st Qtr Total Body Specification (mrem)Actual Dose (mrem)% of Specification Orizans Specification (mrem)Bone Actual Dose (mrem)% of Specification Liver Actual Dose (mrem)% of Specification Thyroid Actual Dose (mrem)% of Specification Kidney Actual Dose (mrem)% of Specification 2nd Qtr 1.50E+00 1.49E-03 9.95E-02 3rd Qtr 1.50E+00 3.87E-04 2.58E-02 4th Qtr 1.50E+00 0.OOE+00 0.OOE+00 Annual 3.OOE+00 2.22E-03 7.41E-02 1.50E+00 3.44E-04 2.30E-02 5.OOE+00 2.17E-04 4.35E-03 3.55E-04 7.11 E-03 3.36E-04 6.72E-03 3.36E-04 6.72E-03 S 0 0 S 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 5.OOE+00 5.OOE+00 5.OOE+00 1.OOE+01 2.80E-03 5.60E-02 1.60E-03 3.20E-02 1.35E-03 2.69E-02 1.35E-03 2.71 E-02 2.83E-04 0.OOE+00 3.30E-03 5.66E-03 0.OOE+00 3.30E-02 4.12E-04 8.24E-03 0.OOE+00 0.OOE+00 2.37E-03 2.37E-02 3.72E-04 O.OOE+00 2.05E-03 7.43E-03 0.OOE+00 2.05E-02 3.72E-04 7.43E-03 0.OOE+00 0.OOE+00 2.06E-03 2.06E-02 Page 20 of 35 0 0 0 0 0 0 S 0 S 0 0 0 0 S 0 S 0 0 S 0 0 0 Table 3.4 (continued)
Dose from Liquid Effluents 1 st Qtr Lung Actual Dose (mrem)% of Specification GI-LLI Actual Dose (mrem)% of Specification 3.39E-04 6.77E-03 3.45E-04 6.90E-03 2nd Qtr 1.36E-03 2.72E-02 5.03E-03 1.01E-01 3rd Qtr 4th Qtr Annual 3.84E-04 O.OOE+00 2.08E-03 7.69E-03 O.OOE+00 2.08E-02 4.05E-04 8.1OE-03 O.OOE+00 O.OOE+00 5.78E-03 5.78E-02 Page 21 of 35
3.4 Ground
Water Monitoring Sample Point Tritium Total Gamma Activity Sample Date pCi/L iRCi/mI AB-707 03/26/13 2194 None Detected 04/24/13 1149 (1)05/29/13 1038 None Detected 07/02/13 1917 None Detected 07/25/13 1802 None Detected 08/29/13 1219 None Detected 09/06/13 1429 None Detected 01/04/14 (2) 1204 None Detected AB-708 03/26/13 1181 None Detected 07/02/13 1036 None Detected 09/06/13 953 None Detected 01/04/14 (2) 856 None Detected AB-709 03/26/13 575 None Detected 07/03/13 463 None Detected 09/11/13 548 None Detected 01/10/14 (2) 904 None Detected AB-710 03/26/13 985 None Detected 07/03/13 966 None Detected 09/06/13 809 None Detected 01/04/14 (2) 877 None Detected AB-711 03/25/13 978 None Detected 07/03/13 952 None Detected 09/06/13 805 None Detected 01/04/14 (2) 1060 None Detected AB-712 03/25/13 <241 None Detected 07/03/13 251 None Detected 09/11/13 554 None Detected 01/10/14 (2) 419 None Detected AB-715 03/25/13 624 None Detected 07/03/13 1623 None Detected 09/11/13 759 None Detected 01/04/14 (2) 553 None Detected 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 22 of 35 S 0 S S 0 0 0 S S S 0 0 0 S 0 0 0 S 0 0 S 0 0 S 0 0 0 Sample Point Tritium Total Gamma Activity Sample Date pCi/L ttCi/ml AB-717 03/26/13 <241 None Detected 07/03/13 <239 None Detected 09/12/13 <280 None Detected 01/10/14 (2) <253 None Detected MW-701 03/26/13 <241 None Detected 07/03/13 <219 None Detected 09/11 / 13 <240 None Detected MW-702 03/26/13 <241 None Detected 07/02/13 <219 None Detected 09/11/13 <240 None Detected MW-703 04/01/13 <241 None Detected 07/02/13 <219 None Detected 09/11/13 <240 None Detected MW-704 04/01/13 <241 None Detected 07/02/13 <219 None Detected 09/11/13 <240 None Detected MW-705 03/26/13 <241 None Detected 07/03/13 <219 None Detected 09/12/13 <240 None Detected MW-706 03/26/13 <241 None Detected 07/03/13 <219 None Detected 09/12/13 <240 None Detected (1) The sample at location AB-707 on 4/24/13 was an additional sample for tritium -the sample was not 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 4 th quarter in January 2014. Wells MW701, MW702, MW703, MW704, MW705, and MW706 were not sampled for 4 th quarter 2013. Condition Report 538443 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 Power Station during the report period.5.0 METEOROLOGICAL DATA See Appendix A for missing meteorological data and the joint frequency distribution tables for the report period.6.0 SOLID WASTE DISPOSAL Table 6.1 is a summation of solid radioactive waste shipped during 2013. Presented are the types of waste, major nuclide composition, disposition of the waste and shipping containers used. Table 6.1 also contains the radionuclide content (curies) and percent abundance for each type of waste.6 0 6 0 0 0 6 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 24 of 35 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 S 0 S 0 0 0 0 0 0 S 0 S Table 6.1 Solid Waste and Irradiated Fuel Shipments A. Solid Radioactive Waste Shipped Off-Site for Burial or Disposal 1. Type of Waste with Estimate of Major Nuclide Composition Resins, Filters, and Volume Curies Shipped Evaporator Bottoms Waste Class f 3 m 3 Curies A 1.94E+02 5.49E+00 1.30E+O 1 B 1.63E+02 4.62E+00 1.45E+02 C O.00E+00 0.OOE+00 0.OOE+00 All 3.57E+02 1.01E+01 1.58E+02 Estimate of Major Nuclides for Resins, Filters, and Evaporator Bottoms: Class A Nuclide H-3 C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-59 Ni-63 Sr-90 Nb-95 Ag-li0m Sb-125 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Nuclide% Abundance 0.020 0.069 2.420 8.150 0.340 3.118 13.253 0.789 71.013 0.003 0.024 0.012 0.558 0.159 0.068 0.000 0.000 0.004% Abundance 0.020 0.048 0.879 Curies 2.56E-03 8.94E-03 3.14E-01 1.06E+00 4.42E-02 4.05E-01 1.72E+00 1.02E-01 9.22E+00 4.15E-04 3.15E-03 1.61E-03 7.25E-02 2.06E-02 8.81E-03 5.96E-06 1.97E-06 4.76E-04 Curies 2.89E-02 6.96E-02 1.28E+00 Class B H-3 C-14 Mn-54 Page 25 of 35 0 0 0 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments Fe-55 5.942 8.62E+00 Co-57 0.457 6.63E-01 Co-58 6.442 9.35E+00 Co-60 7.737 1.12E+O1 Ni-59 0.635 9.21E-01 Ni-63 77.073 1.12E+02 Zn-65 0.080 1.16E-01 Sr-89 0.001 9.06E-04 Sr-90 0.004 5.29E-03 Sb-125 0.406 5.89E-01 Cs-137 0.208 3.02E-01 Ce-144 0.063 9.14E-02 Pu-238 0.000 2.67E-05 Pu-239 0.000 1.79E-05 Pu-241 0.005 6.82E-03 Am-241 0.000 8.73E-06 Cm-243 0.000 8.78E-06 Class All Nuclide % Abundance Curies H-3 0.020 3.15E-02 C-14 0.050 7.85E-02 Mn-54 1.006 1.59E+00 Fe-55 6.124 9.68E+00 Co-57 0.447 7.07E-01 Co-58 6.169 9.75E+00 Co-60 8.190 1.29E+01 Ni-59 0.647 1.02E+00 Ni-63 76.575 1.21E+02 Zn-65 0.073 1.16E-01 Sr-89 0.001 9.06E-04 Sr-90 0.004 5.70E-03 Nb-95 0.002 3.15E-03 Ag-110m 0.001 1.61E-03 Sb-125 0.419 6.62E-01 Cs-137 0.204 3.22E-01 Ce-144 0.063 1.00E-01 Pu-238 0.000 3.26E-05 Pu-239 0.000 1.98E-05 Pu-241 0.005 7.30E-03 Am-241 0.000 8.73E-06 Cm-243 0.000 8.78E-06 0 6 Page 26 of 35 6 6 0 0 0 0 0 0 S 0 0 S 0 0 0 0 S 0 0 S 0 0 S 0 0 0 0 S S 0 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments Dry Active Waste Volume Curies Shipped Waste Class fW 3 m 3 Curies A 5.OOE+02 1.42E+01 1.34E-01 B 0.OOE+00 0.OOE+00 0.OOE+00 C 0.OOE+00 0.OOE+00 O.00E+00 All 5.00E+02 1.42E+01 1.34E-01 Estimate of Major Nuclides for Dry Active Waste: Class A Nuclide H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Zr-95 Nb-95 Tc-99 Ag-i 1Oim Sn- 113 Sb- 125 Cs-137 Ce-144 Nuclide% Abundance 0.477 5.063 0.823 12.306 0.384 0.231 54.749 3.087 10.045 0.089 4.043 7.488 0.579 0.024 0.139 0.265 0.137 0.070% Abundance 0.477 5.063 0.823 12.306 0.384 0.231 54.749 3.087 10.045 0.089 Curies 6.38E-04 6.76E-03 1.1OE-03 1.64E-02 5.14E-04 3.08E-04 7.32E-02 4.12E-03 1.34E-02 1.18E-04 5.40E-03 1.00E-02 7.74E-04 3.25E-05 1.86E-04 3.55E-04 1.84E-04 9.34E-05 Curies 6.38E-04 6.76E-03 1.1OE-03 1.64E-02 5.14E-04 3.08E-04 7.32E-02 4.12E-03 1.34E-02 1.1 8E-04 Class All H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Page 27 of 35 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments Zr-95 Nb-95 Tc-99 Ag-1 10m Sn- 113 Sb- 125 Cs-137 Ce-144 4.043 7.488 0.579 0.024 0.139 0.265 0.137 0.070 5.40E-03 1.00E-02 7.74E-04 3.25E-05 1.86E-04 3.55E-04 1.84E-04 9.34E-05 Irradiated Components Volume Curies Shipped Waste Class fW 3 m 3 Curies A 0.OOE+00 0.OOE+00 0.OOE+00 B 0.OOE+00 0.OOE+00 0.OOE+00 C 0.OOE+00 0.OOE+00 0.OOE+00 All O.OOE+00 0.OOE+00 0.OOE+00 Estimate of Major Nuclides for Irradiated Components:
Nuclide % Abundance Curies None NA NA Other Waste (DAW-Asbestos)
Volume Curies Shipped Waste Class W 3 m 3 Curies A 2.70E+02 7.65E+00 2.89E-04 B 0.OOE+00 0.OOE+00 0.OOE+00 C 0.OOE+00 0.O0E+00 0.OOE+00 All 2.70E+02 7.65E+00 2.89E-04 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Estimate of Major Nuclides for Other Waste: Class A Nuclide % Abundance H-3 0.448 Cr-51 5.629 Mn-54 0.785 Fe-55 11.610 Fe-59 0.403 Page 28 of 35 Curies 1.30E-06 1.63E-05 2.27E-06 3.36E-05 1.16E-06 0 0 S 0 0 0 0 S 0 S 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments Co-57 Co-58 Co-60 Ni-63 Zn-65 Zr-95 Nb-95 Tc-99 Ag-ll0m Sn- 113 Sb-125 Cs-137 Ce-144 Class All Nuclide H-3 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Zr-95 Nb-95 Tc-99 Ag-li0m Sn-ill3 Sb-125 Cs-137 Ce- 144 0.221 55.173 2.905 9.427 0.085 4.103 8.061 0.543 0.023 0.137 0.250 0.129 0.067% Abundance 0.448 5.629 0.785 11.610 0.403 0.221 55.173 2.905 9.427 0.085 4.103 8.061 0.543 0.023 0.137 0.250 0.129 0.067 6.39E-07 1.60E-04 8.40E-06 2.73E-05 2.46E-07 1.1 9E-05 2.33E-05 1.57E-06 6.74E-08 3.95E-07 7.24E-07 3.73E-07 1.93E-07 Curies 1.30E-06 1.63E-05 2.27E-06 3.36E-05 1.16E-06 6.39E-07 1.60E-04 8.40E-06 2.73E-05 2.46E-07 1.19E-05 2.33E-05 1.57E-06 6.74E-08 3.95E-07 7.24E-07 3.73E-07 1.93E-07 Sum of All Low-Level Volume Curies Shipped Waste Volume CuriesShipped Waste Class ft 3 m 3 Curies A 9.64E+02 2.73E+01 1.31E+01 B 1.63E+02 4.62E+00 1.45E+02 C 0.OOE+00 0.OOE+00 0.OOE+00 All 1.13E+03 3.19E+01 1.58E+02 Page 29 of 35 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments Estimate of Major Nuclides for All Low-Level Waste: Class A Nuclide H-3 C-14 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-59 Ni-63 Zn-65 Sr-90 Zr-95 Nb-95 Tc-99 Ag- I10m Sn-l 13 Sb-125 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Nuclide% Abundance 0.024 0.068 0.052 2.404 8.192 0.004 0.339 3.645 13.149 0.781 70.391 0.001 0.003 0.041 0.100 0.006 0.013 0.001 0.555 0.159 0.068 0.000 0.000 0.004% Abundance 0.020 0.048 0.879 5.942 0.457 6.442 7.737 0.635 77.073 0.080 0.001 0.004 Curies 3.20E-03 8.94E-03 6.78E-03 3.16E-01 1.08E+00 5.15E-04 4.45E-02 4.78E-01 1.73E+00 1.02E-01 9.24E+00 1.19E-04 4.15E-04 5.41E-03 1.32E-02 7.75E-04 1.64E-03 1.86E-04 7.28E-02 2.08E-02 8.91E-03 5.96E-06 1.97E-06 4.76E-04 Curies 2.89E-02 6.96E-02 1.28E+00 8.62E+00 6.63E-01 9.35E+00 1.12E+01 9.21 E-01 1.12E+02 1.16E-01 9.06E-04 5.29E-03 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Class B H-3 C-14 Mn-54 Fe-55 Co-57 Co-58 Co-60 Ni-59 Ni-63 Zn-65 Sr-89 Sr-90 Page 30 of 35 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S S S 0 0 0 0 0 S 0 0 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments Class All Sb-125 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-243 Nuclide H-3 C-14 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-59 Ni-63 Zn-65 Sr-89 Sr-90 Zr-95 Nb-95 Tc-99 Ag-110m Sn-l13 Sb-125 Cs-137 Ce-144 Pu-238 Pu-239 Pu-241 Am-241 Cm-243 0.406 0.208 0.063 0.000 0.000 0.005 0.000 0.000% Abundance 0.020 0.050 0.004 1.006 6.129 0.000 0.447 6.210 8.186 0.647 76.519 0.073 0.001 0.004 0.003 0.008 0.000 0.001 0.000 0.419 0.204 0.063 0.000 0.000 0.005 0.000 0.000 5.89E-01 3.02E-01 9.14E-02 2.67E-05 1.79E-05 6.82E-03 8.73E-06 8.78E-06 Curies 3.2 1E-02 7.85E-02 6.78E-03 1.59E+00 9.70E+00 5.15 E-04 7.08E-01 9.82E+00 1.30E+01 1.02E+00 1.21E+02 1.16E-01 9.06E-04 5.70E-03 5.41E-03 1.32E-02 7.75E-04 1.64E-03 1.86E-04 6.62E-01 3.23E-01 1.OOE-01 3.26E-05 1.98E-05 7.30E-03 8.73E-06 8.78E-06 Page 31 of 35 Table 6.1 (continued)
Solid Waste and Irradiated Fuel Shipments 2. Solid Waste Disposition Number of Shipments 3 2 Mode of Transportation Hittman Transport Hittman Transport Destination Energy Solutions, LLC Studsvik Processing Facility, LLC B. Irradiated Fuel Shipments Number of Shipments None Mode of Transportation NA Destination NA No irradiated fuel shipments were made from the Kewaunee Power Station during 2013.Page 32 of 35 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0* 7.0 PROGRAM REVISIONS 0 In accordance with Technical Specification 5.6.2, the revisions to the Process Control Program, Offsite Dose Calculation Manual, Radiological Environmental Monitoring Program and radioactive waste 0 treatment systems are listed below.7.1 Process Control Program There were no revisions made to the Process Control Program.0* 7.2 Offsite Dose Calculation Manual The Kewaunee Power Station Offsite Dose Calculation Manual (ODCM) was revised twice during this 0report 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 Manual SThe 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 Systems The 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 for the 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 System S*On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently
- cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the 0certification 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 the reactor or emplace or retain fuel in the reactor vessel, as specified in 10 CFR 50.82(a)(2).
0 0 0 S*Page 33 of 35 S 0 0 0 0 Steam Generator Blowdown Treatment System Being 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 no longer performs a function or provides support for decommissioning, except as follows: One train is being maintained available to support draining and processing waste water for systems located in the auxiliary building.Reactor Building Ventilation System Being that the reactor is defueled, and the RCS and associated systems are no longer in operation; the Reactor Building Ventilation (RBV) System no longer performs prevention or mitigating function or provides support for decommissioning.
Waste Gaseous System The 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 the abandonment of the RCS and CVCS systems the waste gas decay tanks and associated piping were discharged and vented to atmosphere.
No new gases will be produced as the CVCS was drained and vented and the reactor vessel has been defueled.Chemical and Volume Control System Being that the reactor is defueled, and the RCS and associated systems are no longer in operation; 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 of radioactive 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 the auxiliary building.
There will no longer be any releases of radioactive material or any further exposures to individuals in the UNRESTRICTED AREA and to the general population from the 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 waste treatment 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 the radioactive waste treatment systems.0 0 Page 34 of 350 0 0 0 0* 8.0 REPORTABLE OCCURRENCES S* 8.1 Condition Report 516118, ODCM Channel Checks Not Performed for R-12 and R-21 On 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify the monitor is functional.
This performance check was not performed as required placing the monitors in a nonconforming condition.
Upon discovery of the missed 0 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 of discovery 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, Shutdown Bases statement excerpt from the ODCM related to gaseous effluent instrumentation:
- "The radioactive gaseous effluent instrumentation, required FUNCTIONAL by this DNC, is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents."* The plant had been permanently shut down on 5/7/2013 and certified defueled on 5/15/2013.
The Main Steam 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'0 0 0 S 0 0 0 0 0 0 0*Page 35 of 35 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 S* Appendix A 0 0* Kewaunee Power Station 0 S* 2013 Meteorological Data 0 Missing Data 0 0 First Quarter: 17.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> SSecond Quarter: 5.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />s* Third Quarter: 1.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> SFourth Quarter: 47.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> S S*Note: A total of 72.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of data is missing or otherwise* unavailable.
This represents the availability of 99.18% of the Sdata for the year.S* is urer 77 or* eodQate:52 or S hr ure:15 or 0 orhQatr 75 or 0 0* oe oa f7.0husofdt smsigo tews 0 nvial.Ti ersnsth viaiiyo 91%o h* aafr h er 0 S APPENDIX A Kewaunee Power Station 2013 Meteorological Data First Ouarter 2013 Stability Class A Wind Speed Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4-7 7.25 3 12.25 2.5 6.25 1 0 1.25 2.25 2.25 6 2.75 7.5 9.5 12 18.5 94.25 8-12 13 9.75 17.5 3 6.75 4 0 8 7.25 2.25 4.75 16.75 55.5 39.5 21.25 28.75 238 13-18 21.25 15.75 10.25 5.25 10.25 13 20.75 6.5 0 0 0 4.25 21 24.75 7.25 9.75 170 0 9.25 0 0 3 0 1 0 0 0 0 0.25 6.5 0 1 0 21 0 0 0 0 0.25 0.25 0 0 0 0 0 0 0 0 0 0 0.5 41.5 37.75 40 10.75 26.5 18.25 21.75 15.75 9.5 4.5 10.75 24 90.5 73.75 41.5 57 523.75 19-24 >24 TOTAL 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 Stability Class B Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0 0 0 0 0 0 0 0 0 0 0 0.25 0 0 0 0.25 4-7 1.75 0.5 3 0 0.5 1.25 0 0.75 1.5 1.75 1 2.25 4 3.5 1.5 1.75 25 8-12 5.5 1 0 0.25 1 0 0 0 15.5 7.5 3.25 1.75 7.5 10 7 8 68.25 13-18 6.75 3.25 1.5 2 3.5 0 0.5 0 6 0 0.25 0.5 9.5 2.25 2 2.25 40.25 19-24 >24 TOTAL 0 12.75 1 0 0 0 0.5 1.25 0.75 0 0 0 0 0 0 0 16.25 0 3.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.25 14 20.75 5.5 2.25 5 1.25 1 2 23.75 9.25 4.5 4.5 21.25 15.75 10.5 12 153.25 Page A2 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data 0 S 0 0 0 0 0 0 S 0 0 0 0 0 S Stability Class C Wind Direction CALM N 0 NNE 0 NE 0 ENE 0' E 0 ESE 0 SE 0 SSE 0 S 0 SSW 0 SW 0 WSW 0 W 0 WNW 0.NW 0 NNW 0 TOTAL 0 Stability Class D Wind Direction CALM N 0 NNE 0 NE 0 ENE 0 E 0 ESE 0 SE 0 SSE 0 S 0 SSW 0 SW 0 WSW 0 W 0 WNW 0 NW 0 NNW 0 TOTAL 0 Wind Speed 1-3 0 0 0 0 0 0 0 0 0 0 0 0.75 0.25 0 0.75 0 1.75 4-7 1.5 1.25 1.75 0.25 0.5 0.25 0 0.25 0.25 1.25 13 3.5 2.25 3 3.25 4.25 36.5 8-12 6 0.5 2 1.75 0.25 0 0 1 1.75 6.5 3.5 4.5 15 24 6.5 5.5 78.75 13-18 16.75 5 1.5 0 0.5 0 0 1 0 0 0.75 2 6 3.25 5.25 0 42 19-24 0 5.75 2.5 0 0 0 1 0 2.25 0 0 0.25 0 1 0 0 12.75>24 0 1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.25 TOTAL 24.25 13.75 7.75 2 1.25 0.25 1 2.25 4.25 7.75 17.25 11 23.5 31.25 15.75 9.75 173 Wind Speed 1-3 1.5 0 0 0 1 1.75 0.25 0.75 0.5 1.5 2.25 2.5 0.75 0.5 1.25 1.5 16 4-7 7.25 2.25 2.25 2.75 0.5 1.25 3 6.25 12.5 29 9.75 20.25 22.5 11.75 12.25 11.75 155.25 8-12 28.5 4.75 0 0.25 1.25 1.75 2 5.25 10.25 8.75 10.5 12.25 22 56.5 27 24.75 215.75 13-18 27.5 5.25 0 0 1.5 0 4.5 17 7.25 1.75 8 8.75 14.25 5 12.75 11.5 125 19-24 0 0 0 0 0 0 2.75 11.75 2.75 0 0 1.25 2.75 4.75 0.25 0 26.25>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 64.75 12.25 2.25 3 4.25 4.75 12.5 41 33.25 41 30.5 45 62.25 78.5 53.5 49.5 538.25 Page A3 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class E Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0.25 0 0 0.25 0.25 0.75 0.25 3.5 4 2.5 2.75 2 1 0.5 0.25 18.25 4-7 5.75 1.75 1 1 1 1 2.75 4.5 8.25 26.5 19.75 12 11.75 22 18.75 16 153.75 8-12 10 0.5 0 0 0.5 0.5 0.25 4.25 6.5 22 20.5 11.25 18.25 23.5 16 20.25 154.25 13-18 2.5 0 0 0 0 0 1.25 3 2.25 0.25 1.5 5.5 9.5 0.25 3.5 3.75 33.25 19-24 0 0 0 0 0 0 0 0.75 0 0 0.5 1.75 0.25 0.25 0 0 3.5>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 18.25 2.5 1 1 1.75 1.75 5 12.75 20.5 52.75 44.75 33.25 41.75 47 38.75 40.25 363 0 6 0 S 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 Stability Class F Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0.25 0 0.25 0 0.5 0.25 0 0.25 0.5 3 2.75 3.5 5.25 1.5 1.25 0.75 20 4-7 0.75 0 0.25 0.25 0.25 1.25 2.25 3.75 5.25 10.5 16.25 12 15 25.5 17.5 7.75 118.5 8-12 0.75 0 0 0 0 1.25 4.75 4.75 1.5 1.5 2.25 5.25 10.75 12.25 5.75 1.5 52.25 13-18 0 0 0 0 0 0 2 0.5 0 0 0.75 0 0 0 0 0 3.25 19-24 >24 TOTAL 1.75 0 0.5 0.25 0.75 2.75 9 9.25 7.25 15 22 20.75 31 39.25 24.5 10 194 0 0 0 Page A4 of A 17 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class G Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 1.5 1 0 0.25 0 0.25 0.25 0 0 1.75 3 5.75 4 1 1.25 1.5 21.5 4-7 4 0 0 0 0 0 0 0.75 1.5 5.5 15.5 25.25 27 39.25 32 13.75 164.5 8-12 0 0 0 0 0 0 0 0.25 0 0 0.25 0.75 1.5 0 7.5 0 10.25 13-18 0 0 0 0 0 0 0 0 0 0 0.75 0 0 0 0 0 0.75 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 5.5 1 0 0.25 0 0.25 0.25 1 1.5 7.25 19.5 31.75 32.5 40.25 40.75 15.25 197 Page A5 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Second Ouarter 2013 Stability Class A Wind Speed Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0 0 0 0 0 0 0.25 0 0 0 0 0 0 0 0 0.25 4-7 5.75 9.5 7.75 7 5.5 4 3.5 2 1 3 2.75 3.75 1.75 6 5.5 3.75 72.5 8-12 12.5 61.25 25.75 11.5 7.25 3 6.5 8.5 10.25 6.5 2.25 4.75 23.25 29.25 23 12.25 247.75 13-18 14.75 55.25 4.25 12.75 1 0 0 14 8 0.25 1 3.25 7.25 5.5 11.5 7.25 146 19-24 0 18 0.25 4.5 0 0 0 9.25 2 0 0 1.75 2.25 0 0 0.5 38.5>24 0 1.75 0 0 0 0 0 2 0.25 0 0 0 0 0 0 0 4 TOTAL 33 145.75 38 35.75 13.75 7 10 36 21.5 9.75 6 13.5 34.5 40.75 40 23.75 509 6 6 6 6 0 6 6 0 S 0 0 0 o 0 S S 0 0 0 0 o S 0 S 0 o o o o 0 o o o 0 S o 0 0 0 0 Stability Class B Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0 0 0 0 0 0 0 0.25 0 0 0 0 0 0 0 0.25 4-7 2.75 4 3.25 1.25 0.5 1.25 0 0.5 1.25 2.5 0 0.25 0.5 0.75 2.75 1.75 23.25 8-12 3 13.5 2.5 1.5 2.75 0.25 0.75 1.5 2.25 3 0.5 1 1.25 7 2.25 0.5 43.5 13-18 2.75 11.5 6 0.5 2 0 0 4.5 3.75 0.25 0 0 0 1.25 3 0.5 36 19-24 >24 TOTAL 0.75 3 0 0 0 0 0 0.25 0.25 0 0.75 0.25 0 0 0 0 5.25 0 2.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.75 9.25 34.75 11.75 3.25 5.25 1.5 0.75 6.75 7.75 5.75 1.25 1.5 1.75 9 8 2.75 111 Page A6 of A17 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class C Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0 0.25 0 0 0 0.25 0 0 0 0 0 0 0 0 0 0.5 4-7 2.25 2.75 6 3.5 6.25 1 0.25 1 0.25 1.5 0 0.25 0.25 0.25 4.5 1.5 31.5 8-12 5.5 11.75 6.5 1.5 1 0.25 3.5 0.5 3.25 1.25 0.75 0.75 2 6.5 1.25 2 48.25 13-18 2 8.5 0 0 0 0.5 0 1 2.75 0 0.5 0 0.75 2.25 3.5 0.25 22 19-24 0 5 0 0 0 0 0 1 0.5 0 0.5 0 0 0 0 0 7>24 0 5.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.75 TOTAL 9.75 33.75 12.75 5 7.25 1.75 4 3.5 6.75 2.75 1.75 1 3 9 9.25 3.75 115 Stability Class D Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0.25 0.25 0.75 3.5 2 1 1 0.25 0.25 0.25 1 1.25 0.25 0.75 0 0.25 13 4-7 3.75 14.25 17.25 12.5 4.5 2.25 2.5 3 3.25 8.75 2 3.25 3 4 7.75 3.25 95.25 8-12 7 39.5 6 3.25 0 1.25 4.25 10 7.75 8 1.75 2 4.25 9.75 7.25 4 116 13-18 1.75 24.25 0.25 0.25 0 0.25 3 3.5 6 0.75 5.75 0.5 0 2.25 7.75 1.75 58 19-24 0 1 0 0 0 0 0.75 2.25 0 0 0.5 0 0 0 0 0 4.5>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 12.75 79.25 24.25 19.5 6.5 4.75 11.5 19 17.25 17.75 11 7 7.5 16.75 22.75 9.25 286.75 Page A7 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class E Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 1.75 3.75 6.25 5.5 2.75 3.25 1.5 1.75 3.5 2.25 2.75 3.5 0.75 2.25 1.75 2.75 46 4-7 11 33 28.75 10 6.75 5 4.75 11.5 13 19.75 6.5 6.25 8 5.25 5.75 7.25 182.5 8-12 7.5 32.25 4.25 2.75 0.75 0 1.5 6.5 16.25 11 1.75 1.75 2.75 1.75 0 8.25 99 13-18 0.5 17 0 0 0 0 0.75 2.5 3.5 0.25 2.25 1.75 0.25 0.75 1 0.25 30.75 19-24 >24 TOTAL 0 0 0 0 0 0 0 0.75 0 0 0 0 0 0 0 0 0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 20.75 86 39.25 18.25 10.25, 8.25 8.5 23 36.25 33.25 13.25 13.25 11.75 10 8.5 18.5 359 Stability Class F Wind Direction 0 0 0 0 0 S 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 1.75 1.5 5.75 3.5 5.25 3 3.5 3.75 3.75 7.75 4.5 3.75 2 1.5 2.25 0.75 54.25 4-7 15.25 16 13.5 4.25 3 3.25 4.75 15 20 24.75 7.75 6.75 7.75 7.5 2.75 18.5 170.75 8-12 6.5 13.25 3.25 0 0 0 0.25 13.25 10.5 4.5 2.25 0.5 0 3.5 0.5 1.75 60 13-18 0 4.25 0 0 0 0 0 1.25 0.75 0 0 0 0 0.5 0 0 6.75 23.5 35 22.5 7.75 8.25 6.25 8.5 33.25 35 37 14.5 11 9.75 13 5.5 21 291.75 19-24 >24 TOTAL Page A8 of A17 0 0 0 0 0 S 0 0 0 0 0 0 S 0 0.0 0 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class G Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0.25 0.25 0.25 0 0 0.25 0 0 0 0.25 0 0.25 0 0 0 0 1.5 1-3 6.75 7.75 6.5 6.25 6 4.5 6.25 4.5 9 12.5 13.75 12 5.75 6.25 11 9.25 128 4-7 5.5 7 16 6.25 2.75 6 14.75 64.75 55.75 19.25 14 20 13.25 8.75 5.25 6 265.25 8-12 0.25 6.75 7.25 0 0 1 1.25 32.75 39.25 1 1 0.5 3.5 3.25 0.5 1 99.25 13-18 0 4.25 0 0 0 0 0.25 4.75 2.25 0.25 0 0 0 0.25 0 0 12 19-24 0 0 0 0 0 0 0 0.25 0 0 0 0 0 0 0 0 0.25>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 12.75 26 30 12.5 8.75 11.75 22.5 107 106.25 33.25 28.75 32.75 22.5 18.5 16.75 16.25 506.25 Page A9 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Third Ouarter 2013 Stability Class A Wind Speed Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0.5 0.25 0 1.75 0.75 0.5 1.25 0.75 0.25 0 0.25 1 0.75 1 0.75 0.25 10 4-7 7.75 13.75 17.25 8.5 68 3.5 14.5 8.25 4 4.75 9 7.75 11.25 16.25 9.75 15.5 219.75 8-12 10.5 39 5.5 0.5 22 0.25 6 12.25 9.75 5.75 7.25 9.5 8.25 13.25 13.75 11.25 174.75 13-18 2.25 7 0 1.75 0 0 0 8.5 3 0 0 4 0.5 0.25 0 0.25 27.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 21 60 ,22.75 12.5 90.75 4.25 21.75 29.75 17 10.5 16.5 22.25 20.75 30.75 24.25 27.25 432 19-24 >24 TOTAL 6 6 6 6 6 6 6 0 6 0 6 0 S 0 S 0 0 S 0 0 0 0 0 0 0 Stability Class B Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 1 0 0.25 0 1.25 0.25 1 0 0 0 0 0 0 0.25 0.25 4.25 4-7 0.5 4 3.75 6 19.25 1.25 1.25 1.75 0.25 1 1.75 2.25 3.25 5 1.75 1.75 54.75 8-12 2.5 5.25 0 0 8.25 0 0.5 1.25 5.75 2 0.5 1 1 1.75 1.5 1.5 32.75 13-18 0.5 1.25 0 0 0 0 0 2 0.25 0 0 0.5 0.25 0 0 0 4.75 0 0.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.25 3.5 11.75 3.75 6.25 27.5 2.5 2 6 6.25 3 2.25 3.75 4.5 6.75 3.5 3.5 96.75 19-24 >24 TOTAL Page A10 of A17 Kewaunee Power S S 0 0 0 S 0 0 0 0 0 0 0 S 0 0 APPENDIX A Station 2013 Meteorological Data Wind Speed Stability Class C Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0.25 0.75 0.25 0 0.75 2.5 1 1 0.25 0.25 0 0 0 0 0.25 0 7.25 4-7 0.75 3 2.25 4.25 5 3 7.75 3 1.25 2.25 0.75 0.75 1 2.75.2.75 1.75 42.25 8-12 6.25 5.75 0 1.75 9.75 0.75 1.5 7.75 3.75 0.25 0.5 0.75 0 1.2S 0.25 2 42.25 13-18 0.25 0 0 0.25 1.25 0 0 1.75 1.25 0 0 0.5 0 0.25 0 0 5.5 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0.25 0 0 0.25>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 7.5 9.5 2.5 6.25 16.75 6.25 10.25 13.5 6.5 2.75 1.25 2 1 4.5 3.25 3.75 97.5 Stability Class D Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0.5 0.5 1 2.25 1.25 2.25 1.5 3.25 1.5 I 3.25 3.25 1.75 2.5 0.5 1 27.25 4-7 6.75 6 4.75 2.75 5.5 3.5 14 10.75 6.5 11 3.5 4 3 5.5 4.25 7.5 99.25 8-12 5.5 11.75 0 0.25 2.75 40.25 0.75 17 15 3 0.5 0.75 2 1 1.5 4.25 106.25 13-18 0.25 1.5 0 0.25 0.25 0 0 0.75 0.5 0 0 2.25 1.25 0 0.5 0 7.5 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 13 19.75 5.75 5.5 9.75 46 16.25 31.75 23.5 15 7.25 10.25 8 9 6.75 12.75 240.25 Page All of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class E Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 1.75 1.5 2 2 2.5 0.5 2 5.75 5 4 3.5 1.75 1.25 0.75 1.25 1.5 37 4-7 7 7.25 4.75 3.5 3 6 8.5 19.25 25.5 33.75 11.25 6 6.75 4.25 7.25 12.5 166.5 8-12 2 5.75 0.25 0 0 77.25 7.75 25.5 21.75 8.5 2.75 5.25 3.5 1.5 0.5 12.25 174.5 13-18 0 0.25 0 0 0 0 0 10.5 3.75 0 0 0 0 0 0 0.25 14.75 0 0 0 0 0 0 0 0 0.75 0 0 0 0 0 0 0 0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.75 14.75 7 5.5 5.5 83.75 18.25 61 56.75 46.25 17.5 13 11.5 6.5 9 26.5 393.5 19-24 >24 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Stability Class F Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 2.5 1.5 2 1.5 1.5 0.5 1.5 2 9 11.5 4.5 5 2.5 2 1.5 3 52 4-7 6.5 1.25 4.75 6 1.25 0.75 2.25 10 26 25 8.75 11 7.25 10.5 4.75 8.25 134.25 8-12 0.25 0 0 0 0 0 101.25 4.5 9 0.75 0.5 3.75 0.75 0 0 2.25 123 13-18 0 0 0 0 0 0 0 6.25 2 0 0 0 0 0 0 0 8.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9.25 2.75 6.75 7.5 2.75 1.25 105 22.75 46 37.25 13.75 19.75 10.5 12.5 6.25 13.5 317.5 19-24 >24 TOTAL Page A12 of A17 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class G Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0.25 0 0.25 0.5 0.25 0 0 0 0 0 0 0.25 0 0.25 0.5 2.25 1-3 10.75 2.5 1.25 1.25 0.75 3.5 5.5 7.25 12.75 13.75 21 49 28 15 13.5 17 202.75 4-7 3 0.75 0.25 0 0 1.25 5 30.25 46 25.25 27.25 32.5 48.25 33.5 23.25 17 293.5 8-12 0 0 0 0 0 0 13.25 96 16.75 0.25 0.25 0 0 0 0 0 126.5 13-18 0 0 0 0 0 0 0 3.25 0.75 0 0 0 0 0 0 0 4 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 13.75 3.5 1.5 1.5 1.25 5 23.75 136.75 76.25 39.25 48.5 81.5 76.5 48.5 37 34.5 629 Page A13 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Fourth Ouarter 2013 Stability Class A Wind Speed Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0.25 0.25 0 0.75 1.5 0 0 0 0.25 0.25 0.5 0.5 0.75 1.25 0 6.25 4-7 8.75 2.5 2 2 6 2 4.25 2.75 6.25 13 13.25 17.75 21.5 9 8.75 16 135.75 8-12 33.75 8.75 5.5 0.75 7 10.75 3.25 7 16 5.75 11 15.5 51.5 43.5 17 21.5 258.5 13-18 8.25 13.75 8.25 6.5 10.25 4.5 0 6 10.25 0 13.5 4.5 22.25 9.75 13 16 146.75 19-24 >24 TOTAL 0 6.25 0 0 0 0 0 13.25 8 0 2 0 0.25 1 0 0 30.75 0 0 0 0 0 0 0 0.5 0 0 0 0 0 0 0 0 0.5 50.75 31.5 16 9.25 24 18.75 7.5 29.5 40.5 19 40 38.25 96 64 40 53.5 578.5 0 0 6 0 6 0 S 0 0 S 0 0 0 S S 0 0 S 0 S S S S S S 0 S 0 S Stability Class B Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0 0 0 0.25 0.75 0.25 0 0 0 0 0 0 0 0 0.25 0.25 1.75 4-7 0.75 0 0.25 0 1 2 0.25 0 1 1.25 6.25 10.25 8 3.25 3 6.5 43.75 8-12 4.25 1.75 0.5 0.25 0 2 0 0 5 7.75 5 10.5 16.75 16 3 7 79.75 13-18 3 1 0 0 1.25 0 0 0.25 0.25 1 2 3.75 3.5 2 0.75 4.25 23 19-24 >24 TOTAL 0 0.75 0 0 0 0 0 1 1 0 0 0 3.5 0 0.25 0 6.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 3.5 0.75 0.5 3 4.25 0.25 1.25 7.25 10 13.25 24.5 31.75 21.25 7.25 18 154.75 Page A14 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 Stability Class C Wind Direction CALM N 0 NNE 0 NE 0 ENE 0 E 0 ESE 0 SE 0 SSE 0 S 0 SSW 0 SW 0 WSW 0 W 0 WNW 0 NW 0 NNW 0 TOTAL 0 Stability Class D Wind Direction CALM N 0 NNE 0 NE 0 ENE 0 E 0 ESE 0 SE 0 SSE 0 S 0 SSW 0 SW 0 WSW 0 W 0 WNW 0 NW 0 NNW 0 TOTAL 0 Wind Speed 1-3 0 0 0 0 0.5 0.25 0 0 0 0.5 0.25 1.75 0.75 0.5 0.75 1 6.25 4-7 0.25 0.25 0.5 0 0.25 2.75 0.5 0.75 0.75 4 3.5 6.5 7.25 4.25 4.5 4 40 8-12 6 1.75 0 0.75 0.25 0.75 1.25 0.75 2.25 3 1.5 5.5 8.25 12 4.25 8.5 56.75 13-18 2.25 0.75 0 0 0 0.25 0 0.5 2.75 0 4.25 2.75 4.5 1.25 0.5 3.5 23.25 19-24 0 0.25 0 0 0 0.25 0 0.75 0 0 0 0 0.5 0 0 0 1.75>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 8.5 3 0.5 0.75 1 4.25 1.75 2.75 5.75 7.5 9.5 16.5 21.25 18 10 17 128 Wind Speed 1-3 0.25 0.25 0 0 0.25 1.25 0 0 0 0 1.25 1.75 1.75 1.75 1.5 0.5 10.5 4-7 3.75 0.5 0.75 2.75 5 3.5 3.25 2.5 4 13.75 8.75 14.25 18 27.5 12.5 15.5 136.25 8-12 1.5 8.75 0.5 4.75 3.25 4 2.5 7.5 9.5 17 4.25 10 38.75 25.25 12.5 23.25 173.25 13-18 6 4.25 1.25 0 0 1.5 6.25 6 12.25 1.25 4.25 2 13 5.25 4 10 77.25 19-24 0 1.5 0 0 0 0.25 1.25 1.5 7 0 0.5 1.25 0 0 0 0 13.25>24 0 0.5 0 0 0 0 0 0.5 1.5 0 0 0 0 0 0 0 2.5 TOTAL 11.5 15.75 2.5 7.5 8.5 10.5 13.25 18 34.25 32 19 29.25 71.5 59.75 30.5 49.25 413 Page A15 of A17 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class E Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 0.75 1 0.75 0.5 1 0.75 0.75 1.5 0.25 0 2 4.5 4.5 3.5 2.25 1.75 25.75 4-7 6.5 1.25 0 1.75 3 0.75 2 11.75 11.25 23.5 15.75 22.5 33.25 29.25 7.25 6.25 176 8-12 2.75 3.5 0 0.25 3.75 0.5 1.5 10.25 15.25 7.25 15.75 22.25 22.75 21.5 8 9.75 145 13-18 2 5.5 0 0 0 0 0 0.5 1.75 0 5.75 4.75 3 3.25 0 3 29.5 19-24 >24 TOTAL 0 1.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12 12.75 0.75 2.5 7.75 2 4.25 24 28.5 30.75 39.25 54 63.5 57.5 17.5 20.75 377.75 Stability Class F Wind Direction 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 3.25 2.75 1.5 2.25 1 1 1.5 0.75 0.75 2 1.75 4 1.25 1 7.75 5 37.5 4-7 4.75 1.75 3.25 0.5 0.75 3.75 1.25 5 8.5 18 8.5 18.5 21.75 21 13.25 12.5 143 8-12 0 1.5 0 0.5 1.25 1.75 1.25 11.25 4.5 0.25 0.5 5.5 7.75 11.25 2.75 6.5 56.5 13-18 0 1.25 0 0 0 0 0 0 1.25 0 0 0 0 0 0 0 2.5 19-24 >24 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 7.25 4.75 3.25 3 6.5 4 17 15 20.25 10.75 28 30.75 33.25 23.75 24 239.5 Page A16 of A17 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 APPENDIX A Kewaunee Power Station 2013 Meteorological Data Stability Class G Wind Direction Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-3 5 3.5 3 1.25 1.5 2 1.25 3 4.5 6.25 4 10.5 6.75 4.25 3.75 5 65.5 4-7 6.75 0.75 4 1.75 0.75 2.5 1.5 8.75 10 9.75 10 50.5 33.5 32.75 11.75 3.75 188.75 8-12 0 0 0 0.25 0.75 0.75 0.5 2.25 0.25 0 0 0 0.5 0.5 8.25 0.75 14.75 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 11.75 4.25 7 3.25 3 5.25 3.25 14 14.75 16 14 61 40.75 37.5 23.75 9.5 269 Page A17 of A17 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 This page intentionally left blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0* Appendix B 0* Kewaunee Power Station 0 O* Offsite Dose Calculation 0 aul(DM* aul(DM 0* Revision 15 0 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 This page intentionally left blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0o 0 0 0 0 S Dominion Energy Kewaunee, Inc.Kewaunee Power Station OFFSITE DOSE CALCU MANUAL (OD1 15 Approved Approved By: Reviewed By: Approved By: I James M. Hale-Radiological Protection and Chemistry 06-04-2013 Date Richard P. Repshas Manager -Regulatory Affairs Jeffrey T. Stafford Facility Safety Review Committee A. J. Jordan Site Vice President 06-04-2013 Date 06-04-2013 Date 06-06-2013 Date KEWAUNEE POWER STATION ODCM TOC W OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 0 TABLE OF CONTENTS PAGE 0 PART I -RADIOLOGICAL EFFLUENT CONTROLS NORMAL CONDITIONS AND BASES
11.0 INTRODUCTION
11.0-1 12.0 (Not Used)S 13.0 USE AND APPLICATION 13.0.1 Definitions 13.0.1-1 13.0.2 Logical Connectors 13.0.2-1 13.0.3 Restoration Times 13.0.3-1 13.0.4 Frequency 13.0.4-1 13.0.5 ODCM Normal Condition (DNC) Applicability 13.0.5-1 13.0.6 ODCM Verification Requirement (DVR) 13.0.6-1 13.1 RADIOACTIVE LIQUID EFFLUENTS5 13.1.1 Liquid Effluents Concentration 13.1.1-1 13.1.2 Liquid Effluents Dose 13.1.2-1 13.1.3 Liquid Radwaste Treatme 13.1.3-1 13.1.4 Liquid Holdup Tanks 13.1.4-1-0 13.2 RADIOACTIVE GAS S F NTS 13.2.1 Gaseous Eff! 13.2.1-1 5 13.2.2 Gaseous E s oble Gas 13.2.2-1 13.2.3 Gaseou Dose- Iodine and Particulate 13.2.3-1 13.2.4 Gaseous Treatment System 13.2.4-1 0 13.2.5 GGas rage nks 13.2.5-1 13.3 IN R ION 13.3.1 R tive Liquid Effluent Monitoring Instrumentation 13.3.1-1 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-1 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 0 13.4.1 Radioactive Effluents Total Dose 13.4.1-10 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM TOC Revision 15 June 6, 2013 13.5 13.5.1 13.5.2 13.5.3 14.0 14.1 15.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PAGE 13.5.1-1 13.5.2-1 13.5.3-1 Monitoring Program Land Use Census Interlaboratory Comparison Program DESIGN FEATURES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Gaseous and Liquid Effluent Release Points ADMINISTRATIVE CONTROLS Major Changes to Radwaste Treatment Systems Radioactive Effluent Release Report Special Reports <<14.1-1 15.1-1 15.2-1 15.3-1 15.1 15.2 15.3 iii 0 0 KEWAUNEE POWER STATION ODCM TOC 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 PART II CALCULATIONAL METHODOLOGIES PAGE 1.0 LIQUID EFFLUENT METHODOLOGY
1.1 Radiation
Monitoring Instrumentation and Controls 1.0-1 1.2 Liquid Effluent Monitor Setpoint Determination 1.0-1 1.3 Liquid Effluent Concentration Limits -10CFR 20 1.0-4 1.4 Liquid Effluent Dose Calculation
-10 CFR 50 1.0-5 1.5 Liquid Effluent Dose Projections 1.0-7 0 1.6 Onsite Disposal of Low-Level Radioactively Contaminated e ams 1.0-8 2.0 GASEOUS EFFLUENT METHODOLOGIES, -2.1 Radiation Monitoring Instrumentation and Controls 2.0-1 2.2 Gaseous Effluent Monitor Setpoint Determinati 2.0-3 2.3 Gaseous Effluent Instantaneous Dose Rate culatio -"0 CFR 20 2.0-5 2.4 Gaseous Effluent Dose Calculations
-1 MytR 2.0-7 2.5 Gaseous Effluent Dose Projection 2.0-10 2.6 Environmental Radiation Protection R 190 2.0-11 2.7 Incineration of Radioactively Conpa 2.0-11 2.8 Total Dose 2.0-11 0 APPENDICES Appendix A Technical Basis fofe e e Factors -Liquid Radioactive Effluents
....... A-1 Table A-1 ACo butions Fish and Drinking Water Pathways ..... A-5 Table A-2 u i Total Body Dose Assessment
.............................
A-6 0 Appendix B Technica r Effective Dose Factors -Gaseous Radioactive Effluents
.. B-1 Tabl B-1 e e Dose Factors -Noble Gases ........................................
B-5 0 Appendix C a onservative, Default Effective EC Value for Liquid Effluents
....C-1 1 alculation of Effective EC (ECe) ...........................................
C-4 Appendix D 0 isposal of Low-Level Radioactively Contaminated Waste Streams ..... D-1 0 0 S S 0 S 0 S'V 0 S 0 S S 0* KEWAUNEE POWER STATION ODCM TOC OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 0 LIST OF TABLES PAGE 0l PART I -RADIOLOGICAL EFFLUENT CONTROLS 13.1.1-1 Radioactive Liquid Waste Sampling and Analysis 13.1.1-3 13.2.1-1 Radioactive Gaseous Waste Sampling and Analysis 13.2.1-3 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-5 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-5*PART II CALCULATIONAL METHODOLOGIES
" 12STREAEINETODOECMI1.1 PARAMETERS FOR LIQUID ALARM SETPOIN IONS 1.0-11~1.2 SITE RELATED INGESTION DOSE COMMI -IIT FA," \ ORS 1.0-12 1.3 BIOACCUMULATION FACTORS 1.0-14* 2.1 DOSE FACTORS FOR NOBLE GA 2.0-15 2.2 PARAMETERS FOR GASEOUS NT DETERMINATIONS 2.0-16 2.3 CONTROLLING LOCATION AND ATMOSPHERIC DISPERSION FOR DOSE L S 2.0-17 2.4 R 1 INHALATION Y FACTORS-ADULT 2.0-18 2.5 R 1 INHALATION PA D D FACTORS-TEEN 2.0-20* 2.6 R 1 INHALATIO
-SE FACTORS-CHILD 2.0-22 2.7 Ra INHALA _W AY DOSE FACTORS-INFANT 2.0-24* 2.8 R VEGETA, HWAY DOSE FACTORS-ADULT 2.0-26*2.9 R 1 VE TIO )PATHWAY DOSE FACTORS-TEEN 2.0-28 O 2.10 PATHWAY DOSE FACTORS-CHILD 2.0-30 2.11 AS COW-MILK PATHWAY DOSE FACTORS-ADULT 2.0-32 2.12 Ri G S-COW-MILK PATHWAY DOSE FACTORS-TEEN 2.0-34 2.13 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-CHILD 2.0-36* 2.14 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-INFANT 2.0-38 2.15 Ri GROUND PLANE PATHWAY DOSE FACTORS 2.0-40 0 0 0 0 0e KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM TOC Revision 15 June 6, 2013 0 0 0 0 LIST OF FIGURES PART I -RADIOLOGICAL EFFLUENT CONTROLS PAGE 14.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENT PART II CALCULATIONAL METHODOLOGIES 14.1-2 1 2 3 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGR SIMPLIFIED HEATING BOILER FUEL OIL PIPIKO;Sý1.0-10 2.0-13 2.0-14 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 vi 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0'0 Kewaunee Power Station Offsite Dose Calculation Manual KEWAUNEE POWER STATION ODCM 11.0 V OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013
11.0 INTRODUCTION
The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent Controls, includes:
(1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively.
Part II, Calculational Methodologies:
provides the methodology to man h ula radiation dose rates and doses to individual persons in UNRESTRICTED ARI t -outine release of gaseous and liquid effluents.
Long term cumulative effe su I.calculated through computer programs employing approved methodologyg -time meteorology in the case of gaseous effluents.
Other compu rog utilized to routinely estimate the doses due to radioactivity in liquid effluents.
I calculations are performed when computerized calculations are not ava e.The methodology stated in this manual is acce se emonstrating compliance with 1OCFR20.1302; 10CFR50, Appendix I; and 40 1 More conservative calculational method /"r, ions (e.g., location and/or exposure pathways) expected to yield higher co ed an appropriate for the maximally exposed person may be assumed in the dose a .The ODCM will be maintained a ion use as a reference guide and training document of accepted methodologies ti .Changes will be made to the ODCM calculational methodologies and para rns is ed necessary to assure reasonable conservatism in keeping with the p nc ,1'Oe CFR50.36a and Appendix I for demonstrating radioactive effluents are ALARA. \11.1 Change Pr s> 0 Instructions f the responsibilities and requirements for revision and control of both the ODCM and th e D) .OGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) are located in approv d-_ation procedure for Revision and Control of the REMM and ODCM.0 0 0 0 0 0 6 6 11.0- 1 0 6 6 0 W KEWAUNEE POWER STATION ODCM 13.0.1* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 S 13.0 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 the Radiological Effluent Controls Normal Conditions and Bases and the Calculational
- Methodologies.
------------
---- -----------------------
- Term Definition ACTION Action shall be that part of a Normal Conditi h Q ibes remedial measures required under design iti CHANNEL CHECK CHANNEL CHECK is a qualita 'e ion of acceptable FUNCTIONALITY by observa; I f c! nnel behavior during operation.
This determinat' where possible, comparison of the channel ic n other indications derived from 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 to CANLverify that it i including alarm and/or trip initiating el ~ CHANNEL action. CALIBRATION CHANN IB ION consists of the adjustment of channel o O such that it responds with acceptable range and aq ac k h values of the parameter that the channel monitors.shall encompass the entire channel, including alarm and/or tE* shall be deemed to include the CHANNEL FUNCTIONAL
- ) FUNCTIONAL/
- FUNCTIONA fined in the Technical Requirements Manual* GASEOUS A GASEOUS RADWASTE TREATMENT SYSTEM is any system RADWASTE designed and installed to reduce radioactive gaseous effluents by TREATMENT collecting off-gases from the primary system and providing for delay or SYSTEM holdup for the purpose of reducing the total radioactivity released to the environment.
MEMBER(S)
OF THE MEMBER(S)
OF THE PUBLIC means any individual except when that* PUBLIC individual is receiving an OCCUPATIONAL DOSE.1 S S S*13.0.1 -1 S S S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.1 Revision 15 June 6, 2013 OCCUPATIONAL DOSE OFFSITE DOSE CALCULATION MANUAL ODCM NORMAL CONDITIONS (DNC)OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. OCCUPATIONAL DOSE does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75, from voluntary participation in medical research programs, or as a MEMBER OF THE PUBLIC.The OFFSITE DOSE CALCULATION MANUAL shall tain the current methodology and parameters used in the of offsite doses due to radioactive gaseous and liquid effl in th calculation of gaseous and liquid effluent mo ing\ ,lprr p setpoints, in the conduct of the Radiologic nv' m~al Monitoring Program. Shall also contain the Radioactiv enlgontrols and Radiological Environmental Operatin .e Effluent Release Reports required by TS 5. and ...Specify minimum requirement e s'b ,dfe operation of the facility.
The Contingency Me re soclfed with a DNC state Nonconformances that ty lyecrSehe ways in which the requirements of the DN ca Specified with each stated Nonconforma o ngency Measures and Restoration Time(s).Verification r requirements relating to test, calibration, or inspecti o as e that the necessary FUNCTIONALITY of systems ýd po ts are maintained, that facility operation will be maint in current licensing basis, and that the ODCM No n in NC) for operation will be met.CESS CONTROL PROGRAM shall contain the current sampling, analyses, tests, and determinations to be made to ensl t at the processing and packaging of solid radioactive wastes, as on demonstrated processing of actual or simulated wet solid es, will be accomplished in such a way as to ensure compliance)with 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71, Federal and State regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste.Licensee initiated changes to the PCP, which was approved by the Commission prior to implementation:
- 1. Shall be documented and records of reviews performed shall be retained as required by the quality assurance program. The documentation shall contain: a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s).
- b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Shall become effective upon review and acceptance by the FSRC.0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 0 ODCM VERIFICATION REQUIREMENTS (DVR)PROCESS CONTROL PROGRAM 13.0.1-2 U KEWAUNEE POWER STATION ODCM 13.0.1 O OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 O PUBLIC DOSE PUBLIC DOSE means the dose received by a MEMBER OF THE PUBLIC from exposure to radiation or to radioactive material released by a licensee, or to any other source of radiation under the control of a O licensee.
PUBLIC DOSE does not include OCCUPATIONAL DOSE or O doses received from background radiation, from any medical administration 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 or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such r that replacement air or gas is required to purify the co i eme .RADIOLOGICAL The REMM shall contain the current method y d .._, leters used ENVIRONMENTAL in the conduct of the radiological environme to program.O MONITORING MANUAL (REMM) <e b tld O SITE BOUNDARY The SITE BOUNDARY shall b t I* which the land is neither owned, leased, nor otl o ed by the licensee.O SOURCE CHECK A SOURCE CHECK sh e tive assessment of channel response 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 SITE AREA BOUND, ee which is not controlled by the licensee for purpos2es ec of individuals from exposure to radiation and radi .s, or any area within the SITE BOUNDARY used fo si tal rters or for industrial, commercial, institutional, creational purposes. (See Plant Drawing A-408)VENTILATION T INEXHAUST TREATMENT SYSTEM is any system O 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 of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.
Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature atmospheric cleanup systems (i.e., Auxiliary Building special ventilation, Shield Building ventilation, spent fuel pool ventilation) are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, O concentration or other operating condition, in such a manner that O 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 STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.2 Revision 15 June 6, 2013 0 0 0 0 0 13.0 USE AND APPLICATION 13.0.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.0.2-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.3 Revision 15 June 6, 2013 13.0 USE AND APPLICATION 13.0.3 Restoration Times Restoration Times are the same as Completion Times as discussed in Section 1.3 of the Technical Specifications and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.0 S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S When "Immediately" is used as a Restoration Time, the Contingency Measure should be pursued without delay in a controlled manner.13.0.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.4 Revision 15 June 6, 2013 13.0 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 Bases 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 13.0.4-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.5 Revision 15 June 6, 2013 13.0 USE AND APPLICATION 13.0.5 ODCM Normal Condition (DNC) Applicability 0 0 0 S 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 0 0 DNC 13.0.5.1 DNCs shall be met during the specified conditions in the Applicability.
DNC 13.0.5.2 Upon discovery of a failure to meet the DNC, the Contingency Measures of the associated Nonconformance shall be met, except as provided in DNC 13.0.5.4.DNC 13.0.5.3 When it is discovered that a DNC has not been met and the associated contingency measures are not satisfied within the specified r" n time (or an associated contingency measure is not provided), the e men bject to the DNC is in a nonconforming condition.
In this situati2V, a pri actions shall be taken as necessary to provide assurance of in lant operations.
In addition a Condition Report shall be i an sessment of reasonable assurance of safety shall be conduc t consid for this 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 mar If this assessment c ud at sa ety is sufficiently assured, the facility may continue to operat il roi'i corrective action is taken.DNC 13.0.5.4 Equipment r ice or declared nonfunctional to comply with Contingen e res y be returned to service under administrative control solely to required to demonstrate its FUNCTIONALITY or the FUN QTIO f other equipment.
This is an exception to DNC 13.0.5.2 for the e to service under administrative control to perform the testing ir onstrate FUNCTIONALITY.
I 13.0.5-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.6 Revision 15 June 6, 2013 13.0 USE AND APPLICATION 13.0.6 ODCM VERIFICATION REQUIREMENTS (DVR) Applicability DVR 13.0.6.1 DVR 13.0.6.2 DVR 13.0.6.3 DVRs shall be met during the specified conditions in the Applicability for individual DNCs, unless otherwise stated in the DVR. Failure to meet a DVR, whether such failure is experienced during the performance of the DVR or between performances of the DVR, shall be failure to meet the DNC. Failure to perform a DVR within the specified Frequency shall be failure to meet the DNC except as provided in DVR 13.0.6.3.
DVR's do not have to be performed on nonfunctional equipment or variables outside specified Ii Each Verification Requirement shall be performed withi Pee cifie) time interval 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 t 9 4 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 a timely fashion and in accordance ,ro res.Actions should be taken to resto' nce with the DNCs / DVRs in a timely fashion. /-I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.0.6-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration ODCM 13.1.1 Revision 15 June 6, 2013 DNC 13.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure 14.1-1) shall be limited to: a. 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases;and b. 2 x 104 pCi/mI total activity concentration for dissolved or entrained noble gases.APPLICABILITY:
During release via the monitored pathway.ACTIONS 6 9/>0 0 0 0 0 S 0 0 S 0 0 S i NON-CONFORMANCE CONTINGENCY ME TION A. Concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeds limits.Immediately B. CONTINGEN MEASURES OR RESTORATI, not met.eaCR In accordance with Corrective Action Program AND B.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.In accordance with Radioactive Effluent Release Report (__________________________________
1 ______________________________________
.1 ____________________
13.1.1 -1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.1 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY+DVR 13.1.1.1 Perform radioactive liquid waste sampling and activity analysis.In accordance with Table 13.1.1-1---- ----- -----.-..-.-.-
..----------
NOTE --.......-----------
-In this DVR the results of DVR 13.1.1.1 shall be used in accord;with the methodology and parameters of the ODCM.ance with 1.1-1 DVR 13.1.1.2 Verify the results of the DVR 13.1.1.1 assure that the concentrations at the I are maintained within the limits of DOI 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.1-2 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 S S 0 0 0 S 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.1 Revision 15 June 6, 2013 Table 13.1.1-1 (Page 1 of 2)Radioactive Liquid Waste Sampling and Analysis LIQUID RELEASE TYPE 1. Batch Waste Release Tanks (b)2. Continuous Releases (e)(SG Blowdown)(TB Sump)TYPE OF ACTIVITY ANALYSIS MINIMUM SAMPLE ANALYSIS FREQUENCY FREQUENCY LOWER LIMIT OF DETECTION (LLD)(a)SAMPLE TYPE a. Principal Gamma Emitters(c)
- b. 1-131 Dissolved and c. Entrained Gases (gamma emitters)d. H-3 e. Gross Alpha f. Sr-89 g. Sr-90 h. Fe-55 Grab Sample Each Batch (g)Grab Sample Each Batch (g)Grab Sample Each Batclh,(qg Composite (d)Composite (d)31 days 31 days 92 days 92 days 92 days h Batch (g)Each Batch (g)1 x 10-6 ICi/ml 1 x 10-4 ACi/ml 1 x 10-5 PCi/mI 1 x 105 PCi/mI 5 x 10:7 liCilml 5 x 10.8 gCi/ml 5 x 10.8 AiCi/ml 1 x 106 AICi/ml 5 x 10U jiCi/ml 1 x 108 i+/-Ci/ml 1 x 10" pCi/ml 1 x 107 , Cic/ml 5 x 10-7 gCi/ml 5 x 10e liCi/ml 5 x 108 AiCi/ml I x 10-6 ACi/ml a.Grab Sample 7 days 7 days Grab Sample 7 days 7 days'-NDbsoted and trained Gases Grab Sample 7 days 7 days mma 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 0 KEWAUNEE POWER STATION ODCM 13.1.1 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Table 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 S will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
4.66
- Sb LLD = E*V*2.22 x 10 6*Y* exp(-&AA0 Where:* LLD is the a Prori lower limit of detection as defined above, as RCi per uni ss v 0 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 10 6 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 a measurement 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 be isolated, and then thoroughly mixedo<ass frepr ntative sampling.(c) The principal gamma emitters h L.l 6 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 are to be considered.
Other 9s that are identified, together with those of the above nuclides, shall also be analyzed 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 has an 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.0 0 0 0 0 0 0 0 13.1.1 -4 01 0 0 0 0* KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013*BASES 0This DNC is provided to ensure that the concentration of radioactive materials released in liquid waste*effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the*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 for dissolved 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 in terms 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 for Qualitative 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 19 0 0 0* K 0 0 0-0 0 0;0 0 0 0 0*13.1.1 -5 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.2 Revision 15 June 6, 2013 0 0 0 0 0 0 13.1.2 DNC 13.1.2 Liquid Effluents Dose The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials released in liquid effluents released to UNRESTRICTED AREAS shall be limited to: a. < 1.5 mrem to the total body and < 5 mrem to any organ during any calendar quarter; and b. < 3 mrem to the total body and < 10 mrem to any organ during any calendar year.APPLICABILITY:
At all times.ACTIONS Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents to UNRESTRICTED AREAS exceeds limits.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.2- 1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.2 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 S 0 0 0 0 S S 0 0 0 0 S 0 0 0 0 0 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents exceeds 2 times the limits.B.1 Calculate the annual dose to a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the facility (including outside storage tanks, etc.).Immediately AND B.2 Verify that the limits of DN 13.4 have not been exceeded.C. CONTINGENCY MEASURE B.2 and Associated RESTORATION TIME not met.30 days C90 N,01 5. 3,ý'~sefefi ned r. (a)(4), of MEASURE dclude the e rrective action(s)be taken to prevent"/ currence of exceeding the limits of DNC 13.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.
13.1.2-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.2 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION DVR 13.1.2.1 Determine cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year in accordance with the methodology and parameters in the ODCM.31 days 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.2-3 KEWAUNEE POWER STATION ODCM 13.1.2* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 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. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive
- material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be 0shown 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 of radioactive materials in liquid effluents are consistent with the meth og in* Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Ies of Reactor Effluents for the Purpose of Evaluating Compliance i 0, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Esf in ispersion of Effluents from Accidental and Routine Reactor Releases f urp e of Implementing
- D Appendix I," April 1977.0*.0 0 0 0 0 0 0 0 0 0*13.1.2-4 0 0 0e KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.3 Revision 15 June 6, 2013 13.1.3 DNC 13.1.3 Liquid Radwaste Treatment System The Liquid Radwaste Treatment System, as described in the ODCM, shall be used to reduce the radioactive material in liquid wastes prior to their discharge when the projected dose, due to the liquid effluent, to UNRESTRICTED AREAS would exceed in a 31 day period: a. > 0.06 mrem to the total body; or b. > 0.2 mrem to any organ.APPLICABILITY:
At all1 times, except for the parts of the system taken service.ACTIONS of I A. Radioactive liquid waste being discharged without treatment and in excess of the above limits.30 daysion of why adwaste was ein ischarged without\\eatment, identification
/f fany non-functional/
inoperable equipment or subsystems, and the reason for the non-functional
/ inoperability, (2) ACTION(s) taken to restore the non-functional
/ inoperable equipment to FUNCTIONAL I OPERABLE status, and (3) Summary description of ACTION(s) taken to 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 6 S 6 6 prevent a recurrence.
13.1.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.3 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 DVR 13.1.3.1 Project the doses due to liquid effluents from the facility to UNRESTRICTED AREAS in accordance with the methodology and parameters specified in the ODCM.31 days I 13.1.3-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.3 Revision 15 June 6, 2013 BASES The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This DNC implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectivess1 n Section II.A of Appendix 1, 10 CFR Part 50, for liquid effluents.
r llz\0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.3-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.4 Revision 15 June 6, 2013 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 13.1 LIQUID EFFLUENTS 13.1.4 DNC 13.1.4 Liquid Holdup Tanks The quantity of radioactivity contained in unprotected outdoor liquid storage tanks shall be limited to less than the amount that would result in concentrations less than the limits in 10 CFR20, Appendix B, Table II, Column 2, at the nearest potable water supply and surface water supply in an UNRESTRICTED AREA, excluding tritium and dissolved or entrained gases.APPLICABILITY:
At all times.ACTIONS I VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.4.1 Sample and analyze radioactive liquid located in 31 days during unprotected outdoor liquid storage tanks for level of addition of radioactivity.
radioactive liquid to the tanks 13.1.4-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.4 Revision 15 June 6, 2013 13.1 LIQUID EFFLUENTS 13.1.4 Liquid Holdup Tanks BASES The tanks listed in this Normal Condition include outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the radwaste treatment system.Technical Specification 5.5.10.c requires a program to ensure that the material contained in the specified tanks provides assurance that, in the ej 0ofa uncontrolled release of any such tank's contents, the resulting concentr ti'b ould)e less than 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." ,>0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0<N 13.1.4-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.1 Revision 15 June 6, 2013 13.2.1 DNC 13.2.1 Gaseous Effluents Dose Rate The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. For noble gases, < 500 mrem/yr to the total body and< 3000 mrem/yr to the skin and b. For 1-131, 1-133, tritium and for all radionuclides in particulate form with half-lives > 8 days, < 1500 mrem/yr to any organ.0 0 0 0 S S S S S S S S S S S S S S S S S S S 0 S S S S S S S APPLICABILITY:
At all times.ACTIONS/2 NON-CONFORMANCE ,TION i A. The dose rate(s) at or beyond the SITE BOUNDARY due to radioactive gaseous effluents exceeds limits.Immediately B. CONTINGENCY MEASURES OR RESTORATION" not met.fr'1~ll ea CR A B.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.In accordance with Corrective Action Program In accordance with Radioactive Effluent Release Report 13.2.1 -1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.1 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.1.1 The dose rate due to noble gases in gaseous In accordance with effluents shall be determined to be within the Table 13.2.1-1 above 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 radionuclides in particulate form with half-lives
> 8 days in gaseous effluents shall be determine;V to be within the above limits in accordance with methodology and parameters in the ODCM by obtaining representative samples and erf analyses in accordance with the samp in d analysis proaram specified in Table 13. .1 ccor .ce with> e13. 1-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.1 -2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.1 Revision 15 June 6, 2013 Table 13.2.1-1 (Page 1 of 2)Radioactive Gaseous Waste Sampling and Analysis GASEOUS RELEASE TYPE TYPE OF ACTIVITY ANALYSIS SAMPLE TYPE SAMPLE FREQUENCY MINIMUM ANALYSIS FREQUENCY LOWER LIMIT OF DETECTION (LLD)(a)0 0 S 0 0 0 0 0 0 0 0 0 1. Waste Gas Storage Tank and Chemical Principal Gamma Grab and Volume Control Emitters (b) Sample System Holdup Tank 2. Containment Purge Principal Gamma Grab Emitters (b) Sample 3. Auxiliary Building Principal Gamma Grab and Containment Emitters (b) Sample Building Vent Silica Gel, a. H-3 Grab Sample Charcoal b. 1-131Sample Each Tank (d)Each Purge (d)31 days ,-1 x 10-4 Ci/ml 1 x 10-4 iCi/ml 1 x 10 ACi/ml 31 days 1 x 106 pCi/mI 7 days 3 x 10-12 ACi/ml Principal Gamma c. Emitters (b)(1-131, Others)(c)7 days 1 x 10"" jiCi/ml d. Gross Continuous (c)31 days 1 x 10" 11Ci/ml e.Continuous (c)92 days 1 x 10.1, .Ci/ml Continuous (c)Continuous (c)1 x 10 p.Ci/ml 13.2.1 -3 KEWAUNEE POWER STATION ODCM 13.2.1 U OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Table 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 0 will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
0 0 4.66
- Sb LLD = E*V2.22 x 106"Y* exp(-Aut)
O Where: 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-' 0 2.22 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/,nd At 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 ICU It should be recognized that the LLD is defined a n(b e the fact) limit representing the capability of a measurement 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 these nuclides 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 and ventilation system meas ices or periodic flow estimates) for the time period covered by each dose or dose rate calc 5 dan e in rdance with ODCM DNC 13.2.1,13.2.2, and 13.2.3. 0 (d) Complete p /" lease.0 0 0 0 0 0 0 0 O 13.2.1 -4 0 O O 0 W KEWAUNEE POWER STATION ODCM 13.2.1* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 2013* BASES 0* This DNC is provided to ensure that the dose rates at any time to a MEMBER OF THE PUBLIC at or* beyond the SITE BOUNDARY are less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin. This also restricts releases, at all times, for the corresponding
- thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/yr. These dose rate limits provide additional assurance that radioactive material discharged in gaseous effluents will be maintained ALARA, and coupled with the requirements of ODCM DNC 13.2.2, ensure that the exposures of MEMBERS OF THE PUBLIC in an UNRESTRICTED AREA, either within* or outside the SITE BOUNDARY, will not exceed the annual average concentrations specified in Appendix B, Table 2, Column 1 of 10 CFR 20. For MEMBERS OF THE 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 the SITE BOUNDARY.The required detection capabilities for radioactive materials in samples are tabulated in terms of the lower limits of detection (LLDs). Detailed disc n , and other detection limits can 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," Atlantic Richfield Hanford Company Report ARH-SA-215 e 5)1 0 S*0 S S S 0* 13.2.1 -5 S S S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.2 Revision 15 June 6, 2013 13.2.2 Gaseous Effluent Dose -Noble Gas DNC 13.2.2 The air dose due to noble gases released in gaseous effluents from the facility 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, and b. < 10 mrad for gamma radiation and < 20 mrad for beta radiation during any calendar year.APPLICABILITY:
At all times.6i/?>ACTIONS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 6 13.2.2- 1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.2 Revision 15 June 6, 2013 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents exceeds 2 times the limits.B.1 Calculate the annual dose to a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the facility (including outside storage tanks, etc.).Immediately AND ly B.2 Verify that the limits of DN 13.4 have not been exceeded.1-C. CONTINGENCY MEASURE B.2 and Associated RESTORATION TIME not met.30 days (corrective action(s)W be taken to prevent recurrence of exceeding the limits of DNC 13.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.
13.2.2-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.2 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.2.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.2-3
- KEWAUNEE POWER STATION ODCM 13.2.2* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 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 Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational
- procedures based on models and data such that the actual exposure of a MEMBER OF THE* PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
- The dose calculation methodology and parameters established in the 00 for c lating the* doses due to the actual release rates of radioactive noble gases in gasu are consistent with the methodology provided in Regulatory Guide 1.10 lptab f Annual 0 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 Guide 1.111, "Methods for Estimating Atmospheric Transport and i ersi o seous Effluents in Routine 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 are based upon the historical average atmospheric condi s.S" 0 0* 13.2.2-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.3 Revision 15 June 6, 2013 13.2.3 Gaseous Effluent Dose -Iodine, Tritium and Particulate DNC 13.2.3 The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives
> 8 days, in gaseous effluents, released to areas at or beyond the SITE BOUNDARY (Plant Drawing A-408) shall be limited to the following:
- a. < 7.5 mrem to any organ during any calendar quarter, and b. < 15 mrem to any organ during any calendar APPLICABILITY:
At all times.ACTIONS ,z NON-CONFORMANCE CONTINGENCY A RESTORATION TIME A. The calculated dose from A.1 Prep an o the 30 days the release of 1-131, 1-133, NRC, o NC 15.3, tritium, and radionuclides t that in 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 been exceeds limits. i'X) taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DNC 13.2.3.0 0 0 S S 0 S 0 S S S S S S S S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S 13.2.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.3 Revision 15 June 6, 2013 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a MEMBER OF THE PUBLIC from the release of radioactive materials in liquid effluents exceeds 2 times the limits.B.1 Calculate the annual dose to a MEMBER OF THE PUBLIC which includes contributions from direct radiation from the facility (including outside storage tanks, etc.).Immediately AND B.2 Verify that the limits of Dh 13.4 have not been,,.-.exceeded.y C. CONTINGENCY MEASURE B.2 and Associated RESTORATION TIME not met.30 days>1 5.3,!(efined 1)(4), of kSURE the\T rrective action(s);"ý be taken to prevent/ _currence of exceeding the limits of DNC 13.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.
Ic 13.2.3-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.3 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION DVR 13.2.3.1 Determine cumulative dose contributions for the current calendar quarter and current calendar year for 1-131, 1-133, tritium, and radionuclides in particulate form with half-lives
> 8 days in accordance with the methodology and parameters in the ODCM.31 days 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 13.2.3-3 0 0* KEWAUNEE POWER STATION ODCM 13.2.3 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013*BASES*This DNC is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I1, 10 CFR Part 50. The DNC's are the guides set forth in Section II.C of Appendix I. The contingency measures provide the required operating flexibility and at the same time implement*the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive
- materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the DVR's implement the requirements in Section*III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational
- procedures based on models and data, such that the actual exposure of a 4BER OF THE PUBLIC through appropriate pathways is unlikely to be substantially
.6 ated. The ODCM calculational methodology and parameters for calculating the due the actual* release rates of the subject materials are consistent with the tho'qg/,g rovided in Regulatory Guide 1.109, "Calculation of Annual Doses to ma rou Releases of Reactor 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 the existing radionuclide pathways to man in a beyond the SITE BOUNDARY.
The pathways 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 and meat producing animals graze w' o l ,inof the milk and meat by man, and 4) deposition on the ground with subsequen e o an.0 0-0 0 0 0 0 0 0 0 0*13.2.3-4 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.4 Revision 15 June 6, 2013 13.2.4 GASEOUS RADWASTE TREATMENT SYSTEM DNC 13.2.4 APPLICABILITY:
The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (Plant Drawing A-408) would be: a. > 0.2 mrad for gamma radiation; or b. > 0.4 mrad for beta radiation; or c. > 0.3 mrem to any organ in 31 day Treatment System only)At all times, except for the parts of the s service. Výf~haust nently out of ACTIONS NON-CONFORMANCE kTION 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A. Radioactive gaseous waste is being discharged without treatment.
AND Projected doses gaseous effluent facility, at and_SITE B O, exceed V dsubmit to the pusant to DNC 15.3, cial Report that des the following:
(1tion of why gaseous radwaste was being discharged without treatment, (2) Identification of any non-functional I inoperable equipment or subsystems and the reason for the non-functional/
inoperability, (3) ACTION(s) taken to restore the non-functional
/inoperable equipment to FUNCTIONAL
/OPERABLE status, and (4) Summary description of ACTION(s) taken to prevent a recurrence.
30 days 13.2.4-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.4 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 DVR 13.2.4.1 Project the doses due to gaseous effluents from each facility at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.31 days 13.2.4-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.4 Revision 15 June 6, 2013 BASES The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This DNC implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the specified as a suitable fraction of the dose design objectives set foq and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.
/.>were 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.4-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.5 Revision 15 June 6, 2013 13.2 GASEOUS EFFLUENTS 13.2.5 Gas Storage Tanks DNC 13.2,5 The radioactivity contained in each gas storage tank shall be limited to< 52,000 Curies of noble gas. (Considered as Xe-1 33)APPLICABILITY:
At all times, except when the tank is taken permanently out of service.I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ACTIONS AA. Level of radioactivity exceeds the limits.Immediately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 13.2.5-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.5 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION DVR 13.2.5.1 Verify quantity of radioactive material contained in each gas storage tank is 5 52,000 curies of noble gases (considered as Xe-133).31 days AND Vtreg', red to beýp-oyfed if the njas recent actor Coolant System specific activity DOSE EQUIVALENT 1-131 is< 1.0 pCi/gm Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 being added to the tank 13.2.5-2
- KEWAUNEE POWER STATION ODCM 13.2.5 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013*BASES This verification implements the requirement of Technical Specification 5.5.10.b.
which requires a program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of > 0.5 rem to any individual in an UNRESTRICTED AREA, in the 01 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 decay tank is taken to be the maximum amount that could accumulate from opera' cladding defects in 1 percent of the fuel elements.
This is at least ten times the ex. ed nber of defective 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 with letdown at the maximum rate, and periodic purging to the gas .maximum inventory 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 when considered as Xe-133. Kewaunee Power nidoes t have a calculation correcting the waste gas decay tank activity to a SITE U AR'6nsequence of < 0.5 rem, therefore by limiting 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 DOSE EQUIVALENT 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/gm DEX-1 33, ana consequences calculation also yields a 0.1 rem whole body at the SITE BOUND b Iculation then a gas decay tank on fill cannot exceed the activity limits of this req _frnt and the once per 31 day frequency is adequate.Reference 1. USAR Section 14.2.3, Accidental Release-Waste Gas 2. 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 Rupture Radiation Dose Analysis for the 7.4% Power Uprate Program.4. USAR Table D.7-1 Inventory of Gas Decay Tank After Shutdown and Degassing of*the RCS (Based on 1 percent of Fuel Defects)5. USAR Table D.8-1, Nuclide Parameters 1*13.2.5- 3 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 13.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation DNC 13.3.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 13.3.1-1 shall be FUNCTIONAL with: a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1 are not exceeded.APPLICABILITY:
During release via the monitored pathway.ACTIONS--------------------------------------------------------------
A. Liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required.Immediately 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 the channel Immediately
.3 Change the setpoint so it is acceptably conservative.
Immediately 13.3.1 -1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. One or more required B.1 Restore non-functional 30 days channels non-functional, channel(s) to FUNCTIONAL status.C. Liquid Radwaste Effluent ----NOTE ----------------
Line (R-18) non-functional Prior to initiating an effluent prior to or during effluent release, complete sections >releases.
C.1.1 and C.1.2 C.1.1 Analyze at least 2 rto initiating a independent sam in lease accordance Wj AND C.1.2 T~nq *ul ti ION will be[1]y at least 2 arate technically
< ,quied members of the f ility staff.Independently verify the Prior to initiating a release rate calculations and release discharge line valving.OR C.2 Suspend release of Immediately radioactive effluents via this pathway 13.3.1-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME D. Steam Generator Effluent D.1 Collect and analyze grab At least once every Line (R-19) non-functional samples for gross 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with prior to or during effluent radioactivity (beta or gamma) identified primary to releases at a lower limit of detection of secondary leakage at least 1 x 10-6 RCi/mI. (with secondary side ac ix 10-s MI .At st once a k when no indication of primary to secondary leakage;Failu o mpt ampling and an is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the Sni decared non-functional s ol of this DNC.E. ollect and analyze grab E. Service Water S en- samples for gross radioactivity Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Effluent Line (R-2 (beta or gamma) at a lower limit of 16) non-fun"al detection of at least 1 x 10-6 prior to ri laCi/ml.efflue r__0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.1 -3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 0 0 0 S 0 0 0 0 0 0 0 S 0 0 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME F. CONTINGENCY F.1 Initiate a CR In accordance with MEASURES Corrective Action OR AND Program RESTORATION TIME of A, B, C, D or E not met. F.2 Explain in the next In accordance with Radioactive Effluent R e Effluent Release Report why the easeport CONTINGENY MEASURE was 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DVR 13.3.1.2 Perform K. Prior to release DVR 13.3.1.3 ,,erfor 0 CE CHECK. 31 days DVR 13.3.1. e rm CHANNEL FUNCTIONAL TEST 92 days DVR 13.3.1.5 Perform CHANNEL CALIBRATION.
18 months 13.3.1-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 15 June 6, 2013 Table 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation
........ ... .................
..................
.............................................
..............................................................................
....... ................
........ ............
..............
...... ... ... .......................
REQUIRED CHANNELS PER INSTRUMENT INSTRUMENT VERIFICATION REQUIREMENTS
------ -----------
..............
------1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluent Line (R-18)b. Steam Generator Blowdown Effluent Line (R-19)2.Gross Beta or Gamma Radioactivity Monitors Providing Alarm but not Providing Automatic Termination of Release a. Service Water System E tye (Component Cooling b. Service r., e ffluent Line ling R-16)1 ....... .. ..L6R/t .1.21.3.1.4 3.3.1.5 DVR 13.3.1.1 DVR 13.3.1.3 DVR 13.3.1.4 DVR 13.3.1.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 DVR DVR DVR DVR DVR DVR DVR DVR 13.3.1.1 13.3.1.3 13.3.1.4 13.3.1.5 13.3.1.1 13.3.1.3 13.3.1.4 13.3.1.5 13.3.1-5
- KEWAUNEE POWER STATION ODCM 13.3.1* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013*BASES 0*The radioactive liquid effluent instrumentation, required FUNCTIONAL by this DNC, is provided to monitor and control, as applicable, the releases of radioactive materials in*liquid effluents during actual or potential releases of liquid effluent.
The alarm/trip
- setpoints for these instruments shall be calculated and adjusted in accordance with*methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten (10) times the values 10 CFR Part 20, Appendix B, Table 2, Column 2.*The FUNCTIONALITY and use of this instrumentation is consistent with the appropriate
- requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.N*0 0 0 0 0 0 0 0 0 0 0 0 0 0 O 13.3.1-6 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 15 June 6, 2013 13.3 INSTRUMENTATION 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DNC 13.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 13.3.2-1 shall be FUNCTIONAL with: a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.2.1 are not exceeded.APPLICABILITY:
During release via the monitored pathway.I ACTIONS-..-----------.-.-------.----------------------
NOTE- -----Separate NON-CONFORMANCE entry is allowed for each channel.............
NON-CONFORMANCE CONTINGENCY A ES RESTORATION TIME A. Gaseous effluent A.1 Suspen as Immediately monitoring instrumentation radio ve channel alarm/trip setpoint efflue re by the less conservative than d 1.required.
K 2 0< 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) to FUNCTIONAL.
FUNCTIONAL status.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.2-1 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 15 June 6, 2013 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. Noble Gas Activity effluent monitoring for the Waste Gas Holdup System and Chemical and Volume Control System Holdup Tanks non-functional prior to or during releases-NOTE -----.-.--.....
Prior to initiating an effluent release, complete sections C.1.1 and C.1.2.Prior to initiating a release C.1.1 Analyze at least 2 independent samples in accordance with Table 13.2.1-1.
<AND C.. 1.2 ------NOTE Verification, be performb Prior to initiating a release iendently verify the 5e rate calculations Iischarge line valving.N C.2 Suspend release of radioactive effluents via this pathway Immediately D. Noble Gas Activity effluent monitoring for the Auxiliary Building Ventilation System and the Condenser Evacuation System non-functional prior to or during releases D.1 Take grab samples.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND AND D.2 Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of sampling completion Analyze samples for gross activity.13.3.2-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 15 June 6, 2013 NON-CONFORMANCE I CONTINGENCY MEASURES RESTORATION TIME E. Noble Gas Activity effluent monitoring for the Containment Purge System, 2" line and 36" duct (auto-isolation) non-functional prior to or during releases E.1 Suspend PURGING of Radioactive effluents via this pathway.Immediately
+F. Sampler Flow rate Measuring Devices (for the Auxiliary Building Ventilation or Containment Building Ventilation Sampler) non-functional prior to or during releases F. 1 Estimate the flow rate for the non-functional channel(s).
<<per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ifter G. Radioiodine and Particulate Samplers (for the Auxiliary Building Ventilation or Containment Building Ventilation system) non-functional prior to or during releases /G.1 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0 0 S S S S S S S S S S S S S S S S S S S S S S 0 S S S S S S S S S S S S S S S S S S S x, H. CONTINGENCY MEASURES Initiate a CR OR RESTOF C, D, E,(not met.AND B, In accordance with Corrective Action Program In accordance with Radioactive Effluent Release Report H.2 Explain in the next Radioactive Effluent Release Report why the CONTINGENCY MEASURE was not met in a timely manner.13.3.2-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 VERIFICATION FREQUENCY DVR 13.3.2.1 Perform CHANNEL CHECK. Prior to release DVR 13.3.2.2 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DVR 13.3.2.3 Perform CHANNEL CHECK. ays DVR 13.3.2.4 Perform SOURCE CHECK. nKior to release DVR 13.3.2.5 Perform SOURCE CHECK. 31 days DVR 13.3.2.6 Perform CHANNEL FU L T. 92 days 1L ATION. 18 months 13.3.2-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 15 June 6, 2013 Table 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT REQUIRED NON- VERIFICATION CHANNELS PER CONFORMANCE REQUIREMENTS INSTRUMENT
- 1. Waste Gas Holdup System DVR 13.3.2.1 DVR 13.3.2.4 DVR 13.3.2.6 DVR 13.3.2.7 a. Noble Gas Activity Monitor (R-13 or R-14)I C 2. Condenser Evacuation System a. Noble Gas Activity (R-15)3. Auxiliary Building Vent a. Noble Gas Activity Monitor (R-13 or R-14)I DVR 13.3.2.2 DVR 13.3.2.5 DVR 13.3.2.6 DVR 13.3.2.7 b. Radioiodine and Particulate Sampler (R-13 or R-14)G DVR 13.3.2.3 F DVR 13.3.2.2 S 0 S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S c. Sample Flow-Rate Monitor (R-13 or R-14)DVR 13.3.2.6 DVR 13.3.2.7 4. Containment Building a. Radioiodine and Particulate (R-21) 111 1 G DVR 133.2.3 1 F b.DVR 13.3.2.2 DVR 13.3.2.6 DVR 13.3.2.7 5. Containment Purge 2" line a. Noble Gas Activity Monitor (R-13 or R-14)1 E DVR 13.3.2.2 DVR 13.3.2.5 DVR 13.3.2.6 DVR 13.3.2.7 6. Containment Purge 36" line DVR 13.3.2.2 DVR 13.3.2.4 a. Noble Gas Activity Monitor 1 E DVR 13.3.2.6 (R-12 or R-21) DVR 13.3.2.7 13.3.2-5
- KEWAUNEE POWER STATION ODCM 13.3.2* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 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.
The alarm/trip will occur prior to exceeding the dose rate limits of ODCM DNC 13.2.1. The* FUNCTIONALITY and use of this instrumentation is consistent with the requirements of* General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.1 0 S 0 S*S-S.S.K24 S* ,-S_**S S S S S S S S O 13.3.2-6 S S S 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE ODCM 13.4.1 Revision 15 June 6, 2013 13.4.1 Radioactive Effluents Total Dose DNC 13.4.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrem to the total body or any organ, except the thyroid, which shall be limited to < 75 mrem.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES)TION-I-A. Estimated dose or dose commitment due to direct radiation and the release of radioactive materials in liquid or gaseous effluents exceeds the limits.A. 1 Verify the condition in doses exceeding limits has beenAr1o Iliately B. CONTINGENCY MEASURES A.1 and RESTORATION TIME not met.(lemented with the ting.0 S 0 S 0 S 0 0 S 0 0 S S S S 0 S S S S S S S S S S 0 S S S S 0 S S S S S (30 days Submit a Special Report, pursuant to DNC 15.3, including a request for a variance in accordance with the provisions of 40 CFR 190. This submission is considered a timely request, and a variance is granted until staff ACTION on the request is complete.13.4.1 -1 S 0 0 0 0 0 S 0 S 0 0 0 S 0 S 0 S 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.4.1 Revision 15 June 6, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.4.1.1 Cumulative dose contributions from liquid and 12 months gaseous effluents shall be determined in accordance with VERIFICATION REQUIREMENTS 13.1.2.1, 13.2.2.1, and 13.2.3.1 in accordance with the methodology and parameters in the ODCM.DVR 13.4.1.2 Cumulative dose contributions from direct radiation from the facility shall be determined in accordance with the methodology and parameters in the ODC)4 This requirement is applicable only under condjt, set forth in ODCM DNC 13.4.1I.A.
I I ((v (13.4.1 -2 O O KEWAUNEE POWER STATION ODCM 13.4.1 O OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 BASES 0 This normal condition is provided to meet the dose limitations of 40 CFR Part 190 that have *been incorporated into 10 CFR Part 20 by 46 FR 18525. The DNC requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. It is highly unlikely that the resultant O dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the facility remains within twice the dose design objectives of Appendix I, and if direct radiation I doses from the facility are kept small. O The Special Report will describe a course of ACTION that should resulteth tion of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CF R r/ li ' s. For the 5 purposes of the Special Report, it may be assumed that the dose eme MEMBER OF THE PUBLIC from other uranium fuel cycle sources is ne h Ie dose to any O MEMBER OF THE PUBLIC is estimated to exceed the requi ,FR Part 190, the S Special Report with a request for a variance (provided rele nditions resulting in violation of 40 CFR Part 190 have not already beelnc cted in accordance with the O provisions of 40 CFR 190.11 and 10 CFR 20.2203, on*'d be a timely request and 0 fulfills the requirements of 40 CFR Part 190 until NR TI is completed.
The variance only relates to the limits of 40 CFR Part 190, n pply in any way to the other O requirements for dose limitation of 10 CFR Pa 0 ssed in ODCM Normal Condition 0 13.3.1 and 13.4.1. An individual is not co si a MBER OF THE PUBLIC during any period in which he/she is engaged in ca ut that is part of the nuclear fuelO cycle. .,,'...,Z-._.
-0 0"0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.4.1 -3 O 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.5.1 Revision 15 June 6, 2013 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.1 Monitoring Program This Kewaunee Program is established by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and implemented by approved station procedures.
This program is required by Technical Specification 5.5.1 .a, ODCM.The radiological environmental monitoring program required by this DNC provides representative measurements of radiation and of radioactive materials in th pathways and for those radionuclides that lead to the highest potential ra on e MEMBERS OF THE PUBLIC resulting from the station operation.
This r ng I implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and ther 5 p radiological effluent monitoring program by verifying that the meas I nc radioactive materials and levels of radiation are not higher tha eo be effluent measurements and the modeling of the environmenc xpo ewayse forflns moesoun roeram is a rovid the moe iof he envion me wranys Position on Environmental Monitoring.
R l i asSure sures of gram s the 3tions of isis of the Guidance (Zz;, 13.5.1 -1 0 0 KEWAUNEE POWER STATION ODCM 13.5.2 *OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING.
13.5.2 Land Use Census Program O This Kewaunee Land Use Census Program is implemented by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and Land Use Census Program procedure.
O BASES O 0 This DNC is provided to ensure that changes in the use of areas at and bey SITE 0 BOUNDARY 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 be used. This census satisfies the requirements of Section IV.B.3 of A I , CFR Part 50. O Restricting the census to gardens of greater than 50 m 2 provid C t significant exposure pathways via leafy vegetables will be identified an o e a garden of this size is the minimum required to produce the quantity (26 W/ rfy vegetables assumed 0 in Regulatory Guide 1.109 for consumption by a child.Tdee is minimum garden size, d the following assumptions were made: (1) 20% of the rd as ed for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), a eg on yield of 2 kg/M 2.0 0 0-0 0 0 0 0 0 0 0 S 0 13.5.2-1 0 0 O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.5.3 Revision 15 June 6, 2013 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.3 Interlaboratory Comparison Program This Kewaunee Interlaboratory Comparison Program is implemented by the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) and approved station procedures.
BASES The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy measurements of radioactive material in environmental sample matrices perfo d c of the quality assurance program for environmental monitoring (develop~l gthuic Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guid v Ap 1975) 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 part lance in 13.5.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 14.1 Revision 15 June 6, 2013 14.0 DESIGN FEATURES 14.1 GASEOUS AND LIQUID EFFLUENT RELEASE POINTS 14.1.1 Plant drawing A-408, "Radiological Survey Site Map" depicts the site area by illustrating the SITE BOUNDARY and the restricted areas. Plant drawing A-449,"Plan of Plant Area, Fence, Lighting, and CCTV Support Structure" shows the layout of the site buildings.
MEMBERS OF THE PUBLIC are restricted from access to all areas of the Owner Controlled Area (OCA).14.1.2 Figure 14.1-1 presents the locations of radioactive effluent plant. The plant drawings referenced above are not includeq but can be found in the plant drawing system.0 0 0 0 0 0 0 S 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 14.1 -1 KEWAUNEE POWER STATION ODCM 14.1 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 FIGURE 14.1-1-----~--~ --. --. -_ _ _ _ _ _ _---------.----
KEWAUNEE_ _ -- 4--"'C I~. (N~- A ~-,'.~ ~;, LA Z UVWCWIAM c LECGJE A Cr7NIAWENjT BUw.iNr.*VZNT ELEVATION 775'B = AUXI-IMAY WJl*L4NIC EN1 CLEVATIM~
WE'C 7ErrULErT L10110 -ISLEP1tG.IE ft-z-VAIICN S-W4 14.1 -2 0 0 KEWAUNEE POWER STATION ODCM 15.1 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 15.0 ADMINISTRATIVE CONTROLS 15.1 Major Changes to Radioactive Waste Systems(')
0 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 Part 50.59, b. Sufficient information to totally support the reason for the n irn benefit of additional or supplemental information, c. A description of the equipment, components and in ed and the interfaces 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 differ from those previously predicted in p i " tion and amendments thereto,-0 e. An evaluation of the change, whic xpected maximum exposures to individuals in the UNRESTRI A1d to the general population that differ from those previously esti se application and amendments thereto, f. A comparison of th d ases of radioactive materials in liquid and 0 gaseous effluen o, aste to the actual releases for the period in which the changes o m g. An estimate posure to plant operating personnel as a result of the change, 0 and 0 h. fact that the change was reviewed and found acceptable by Changes shall become effective upon review and acceptance by the FSRC.0 0 0 0 0 0 0 (')Licensees may choose to submit the information called for in this requirement as part of the 0 periodic USAR update. 1 15.1 -1I W KEWAUNEE POWER STATION ODCM 15.2* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013*15.0 ADMINISTRATIVE CONTROLS 15.2 Radioactive Effluent Release Report 0*The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include: a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility following the format of Regulatory Guide 1.21,*"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974.-b. An annual summary of hourly meteorological data colle r the revious year. This annual summary may be either in the form n -our listing on magnetic tape of wind speed, wind direction, atmr st b'rity, and precipitation (if measured), or in the form of join e d' ution of wind speed, wind direction, and atmospheric stabil* In Ii o mission with the*Radioactive Effluent Release Report, the Ii has e option of retaining this summary of required meteorological data se that shall be provided to the NRC upon request.es(7 r c. An assessment of the radiation d es radioactive liquid and gaseous effluents released from the facilit .revious calendar year.d. An assessment of radiat' d kely most exposed MEMBER OF THE PUBLIC from facility r a nearby uranium fuel cycle sources, including doses fro ri uent pathways and direct radiation, the previous calendar 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 and Ssi e OFFSITE DOSE CALCULATION MANUAL (ODCM).0 0 0 0 0 0 0 0*15.2- 1 0 0 0 O KEWAUNEE POWER STATION ODCM 15.2 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 e. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility.
The material I provided shall be consistent with the objectives outlined in the ODCM and the PCP, and in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.0 f. A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. 0 g. Any changes made during the reporting period to the PROC NTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULAT 0 MANUAL (ODCM), as well as a listing of new locations s calcations and/or environmental monitoring identified by te laai ne to DNC 13.5.2. , ,-/>15.2-20 00 0 0 0 0 0 0*"0 0 0 0 0 0 0 0 0 15.2-2 0O 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 15.3 Revision 15 June 6, 2013 15.0 ADMINISTRATIVE CONTROLS 15.3 Special Reports Special reports may be required covering inspections, tests, and maintenance activities.
These special reports are determined on an individual basis. Their preparation and submittal are designated in the ODCM Contingency Measures for each Normal Condition.
Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix D, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enfnt, U.S.Nuclear Regulatory Commission, Washington D.C. 20555 within the time iod s ified for each report.These Special Report(s) are in lieu of a Licensee Event Report 15.3-1 Kewaunee Power Station Offsite Dose Calculation Manual 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S KEWAUNEE POWER STATION ODCM 1.0* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013* 1.0 LIQUID EFFLUENTS METHODOLOGY 0 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls installed at Kewaunee for controlling and monitoring normal radioactive material releases in accordance with 10* CFR 50, Appendix A, Criteria 60 and 64, are summarized as follows: 1) Alarm (and Automatic Termination)
-R-18 provides this function on the liquid radwaste effluent line, R-19 on the Steam Generator blowdown.2) Alarm (only) -R-20 and R-16 provide alarm function Service Water* discharges.
- 3) Composite Samples -Samples are collected w y team generator blowdown and analyzed by gamma spectroscop pie e collected weekly from the Turbine Building Sump and anal spectroscopy.
The weekly samples are composited for montl. ritiu nt oss alpha analyses and for 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 analyzed by 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 prevent direct, unmonitore renvironment.
A liquid radioactive waste flow diagram with th pll a associated radiation monitoring instrumentation and controls is pre t SF re 1.1.2 Liquid Effluent Monitor D ination Per the re " ts of Technical Specification 5.5.3.b and ODCM Normal ConditicKE1i3.3., la' setpoints shall be established for the liquid effluent monitoring instru e on t ensure that the release concentration limits of ODCM Normal Co n1 re met (i.e., the concentration of radioactive material released in liquid efL UNRESTRICTED AREA shall be limited to ten times the concentrations spe led 1 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and 2.0E- i/ml for dissolved or entrained noble gases). The following equation 1 must be satisified 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 STATION OFFSITE DOSE CALCULATION MANUAL where: ODCM 1.0 Revision 15 June 6, 2013 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- pCi/ml.c = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would concentrations exceeding the limits of ODCM Normal Condition 113.I ., f = the flow rate at the radiation monitor location same units as F, below.time, but in the F = the dilution water flow rate as unit time.[Note that if no dilution is compared to (f), then(,kýrelease point, in volume per C. Also, note that when (F) is large 0 6 0 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 S 0 0 0 S S S S S 0 1.2.1 Liquid Effluent Monitors Steam Generator Blowdown and Service Water)The setpoi determir,4 effluent monitors at the Kewaunee Power Station are I equations:
SP : CWX-CEi xSENi)+bkg Ci xRR lOx EC, (1.2)SP= alarm setpoint corresponding to the maximum allowable release rate (cpm)Ci = the concentration of radionuclide "i" in the liquid effluent (pCi), to include gamma emitters only 10xECi = ten times the EC value corresponding to radionuclide
'"T from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml)1.0-2 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 SENi = the sensitivity value to which the monitor is calibrated for radionuclide "iT (cpm per pCi/ml). The default calibration value from Table 1.1 may be used for gamma emitting radionuclides in lieu of nuclide specific values.CW = the circulating water flow rate (dilution water flow) at the time of release (gal/min)RR = the liquid effluent release rate (gal/min)bkg = the background of the monitor (cpm)The radioactivity monitor setpoint equation (1.2) remai "yv~l during outages when the circulating water dilution is at its lowest. Red on o e waste stream flow (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 Values Non-gamma emitting ra " 3, Fe-55, Sr-89/90) are not detected by the effluent monitor a not directly included in the above setpoint equation.
These n a ionuclides can, however, contribute a sizable fraction of the toa it (re to Appendix C). The method specified below for establishin fa se "nts provides conservatism to account for these non-gamma emitte en es that the setpoint meets the requirements of ODCM Normal nKJ.x*including all radionuclides.
Refer to Appendix C for further ,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 for They are based upon the following:
substitution of the default effective EC (ECe) value of 1.OE-06 pCi/ml (refer to Appendix C for justification), where: EC= ci Ci (ECO)(1.4)1.0-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 b) 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
+bkg RR (1.5)1.3 Liquid Effluent Concentration Limits -10 CFR 20 ODCM Normal Condition 13.1.1 limits the concentration oJ-hdi ive aterial in liquid effluents (after dilution in the Circulating Water Syst to ten times the concentrations as specified in 10 CFR 20, Appen .a 27, p _, Column 2 for radionuclides other than noble gases. Noble gase J diluted concentration of 2E-04 pCi/ml. Release rates are controlled a adia itor alarm setpoints are established to ensure that these concentratio re n exceeded.
In the event any liquid 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 using the following equation: where: '(C1 CW)] l (1.6)Ci c ai of radionuclide "i" in the undiluted liquid effluent I )10xECi n ti es the EC value corresponding to radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml),= 2E-04 pCi/ml for dissolved or entrained noble gases RI- the liquid effluent release rate (gal/min)CW- the circulating water flow rate (dilution water flow) at the time of 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 tne reiease (gai/min)1.0-4 KEWAUNEE POWER STATION ODCM 1.0* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013*P 1.4 Liquid Effluent Dose Calculation
-10 CFR 50 O* ODCM Normal Condition 13.1.2 limits the dose or dose commitment to MEMBERS OF* THE PUBLIC from radioactive materials in liquid effluents from the Kewaunee Power Station to: 0 during any calendar quarter;* < 1.5 mrem to total body S:5 5.0 mrem to any organ 0 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 used O for determining the dose or dose commitme e e id radioactive effluents from 0 Kewaunee.S O Do l "~~167E -D.= CW Aj°) (1.7)0 where: 0 D. e commitment to organ "o", including total body SAo 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)0 1.67E-02 = conversion factor (hr/min)0 0 0 0 O ~1.0- 5 0 0 0 0 KEWAUNEE POWER STATION ODCM 1.0 U OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 The site-related ingestion doses/dose commitment factors (Ai,) are presented in Table 1.2 and have been derived in accordance with guidance of NUREG-0133 by the equation: 0 A 1 o = 1. 14E + 05[(UW + D,,) + (UFx BFi)]DFi (1.8)where: 0 Al = composite dose parameter for the total body or critical organ "o" of an adult for radionuclide "i", for the fish ingestion and water 0 consumption pathways (mrem/hr per pCi/ml)1.14E+05 = conversion factor (pCi/pCi x ml/kg -hr/y r0 Uw = adult water consumption (730 kg/D= dilution factor from the near f it 4mile of the release point to the nearest pot w e for the adult water consumption (84 2, UF " adult fish consumptk (2 d/y" BF 1 = bioaccumulati a nuclide "i" in fish from Table 1.3 (pCi/kg per DF 1 = 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) 0 The radionuclides-i n periodic dose assessment per the requirements of ODCM Normal n nt and Verification Requirement 13.1.2.1 are those as identified by .spet ral analysis of the liquid waste samples collected and analyzed 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 to th at a frequency consistent with the required minimum analysis fr 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 O the dose limits of ODCM Normal Condition 13.1.2. (Refer to Appendix A for the derivation and justification for this simplified method.)0 0 0 2Adapted from the Kewaunee Final Environmental Statement,Section V.1.0-6 0 KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013* Total Body* DDb= 9.67E+ 03xVOLx C (1.9)CW Maximum Organ D.a= 1.18E+04xVOL xC, (1.10)* cw where: Ci = average concentration of radionuclid i ndiluted liquid effluent 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 the conse 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 the a maximum organ dose conversion factor (Cs-134,* mrem/hr per pCi/ml)1.5 Liquid Effluent Dos 0 ns ODCM mal d-ion 13.1.3 requires that the liquid radioactive waste processinged reduce the radioactive material levels in the liquid waste prior to 5 relZse -31 day projected doses exceed:* 0. m to the total body, or 0 0.2 mrem to any organ.*The applicable liquid waste streams and processing systems are as delineated in Figure 1.0 0 0~1.0-7 0 0 0 0 0 6 KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Dose projections are made at least once per 31 days by the following equations:
Dtbp= DDb(31 +d) (1.11)0 Dnmp = + d) (1.12)where: 0 Dtp= 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 as determined by equation (1.7) o d = the number of days to dat r en day period 31 = the number of days in a y pod 1.6 Onsite Disposal of Low-Level Radioactively o Streams During the normal operation ww n the potential exists for in-plant process streams, which are not nol ly d_ etie to become contaminated with very low levels of radioactive mat
- T aste streams are normally separated from the radioactive streams. e ue mainly to infrequent, minor system leaks, and anticipated operation (c nc , the potential exists for these systems to become slightly contamin .A e dnee, the secondary system demineralizer resins, the service water P ea en em sludges, the make-up water system resins, and the sewage trea t sludges are waste streams that have the potential to become contaminate 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 disposal m a well below 1 mrem per year. This dose is in keeping with the guidelines of the N Council on Radiation Protection (NCRP) in their Report No. 91, in which the NCRP established a "negligible individual risk level" at a dose rate of 1 mrem per year. 0 It is for these type wastes that the NRC acknowledged in Information Notice No. 83-05 and 88-22 that the levels of radioactive material are so low that control and disposal as a radwaste are not warranted.
The potential risks to man are negligible and the disposal costs as a radwaste are unwarranted and costly.1 0 0 1.0-8 0 0 0 0 KEWAUNEE POWER STATION ODCM 1.0* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 This waste material will be monitored and evaluated prior to disposal to ensure its radioactive material content is negligible.
It shall then be disposed of in a normal conventional manner with records being maintained of all materials disposed of using*these methods.Approvals for specific alternate disposal methods are listed in Appendix D. Currently,*I only service water pretreatment (SWPT) facility lagoon sludge and sewage treatment*plant sludge have been approved for disposal by land spreading.
0 0-*0 0-0-0 0 0*0 0 0 0* 1.0-9 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 4 = Sample/Monitor
= Isolation Devise (Damper or Valve)--= Auto Isolation=This Flow Path shal onlybe used If orolected does comply with ODCM O anTni Slpe~iticatlon (CA%1074)Graphice No. CS73s.ODCM FIGURE 1 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM 1.0-10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 15 June 6, 2013 Table 1.1 Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value* Units Comments ECe calculated 1.0E-06**
PCi/mI Calculate for each batch to be released dN/A PCi/mI Taken from gamma spectral analysis C measured NIof liquid effluent Taken from 10 CFR 20, Appendix B, EC 1 as determined N/A pCi/mI Table 2, Col. 2 Sensitivity (SEN)R-18 as determined 1.0E+08 Rad efflu R-19 as determined 1.0E+08 cpm per S ra blowdown R-20 as determined 1.0E+08 pCi/ml rvi component cooling R-16 as determined 9.8E+07 aer -containment fan cooling r g Water System default =CW as determined 2.58E+05 gp te , single CW pump Release Rate (RR)R-1 8 as determined 8.OE+01 Determined prior to release; release rate can be adjusted for requirement compliance R-1 9 as determined
- 2. Steam Generator A and B combined R-20 as determined 5 + Service Water -component cooling R-16 as determined Service Water -Containment fan cooling Background (bkg) <R-18 as determi .0 3 cpm Nominal values only; actual values R-19 as deter e + 01 may be used in lieu of these reference R-20 as de e .O-+01 values R-16 as x 8.0E+01 Setpoint* (SP) R-18 culat 5.OOE+05+bkg cpm Default alarm setpoints; more S C5.E+05+bkg conservative values may be used as R-20 cu1 ul-aated 5.16E+04+bkg deem appropriate and desirable for R-16 ulated 1.68E+05+bkg assuring regulatory compliance and for maintaining releases ALARA.Setpoint* (SP) with no Circulating Water System flow, CW=0 R-18 calculated 6.25E+04+bkg For outages with no Circulating Water R-19 calculated 2.50E+04+bkg cpm System flow (CW=0) and a dilution flow R-20 calculated 1.OOE+03+bkg as provided by the Service Water R-16 calculated 3.26E+03+bkg system of 5,000 gpm total.**** Refer to Calculation
- C1 0690 for the default setpoint calculation.
- Refer to Appendix C for derivation
- SW flow is based on N-SW-02 Operating Parameters and Service Water Pump Flow Curves.* The default alarm setpoints for R-18 and R-19 are based upon the linear calibration range of those radiation monitors in accordance with CAP 37265 and DCR 26981.1.0-11 0 KEWAUNEE POWER STATION ODCM 1.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 Table 1.2 (Page 1 of 2) June6, 2013 Site Related Ingestion Dose Commitment Factors (mrem/hr per uCi/ml)Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 -3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 0 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 P-32 1.39E+6 8.62E+4 5.36E+4 --1.56E+5 Cr-51 --1.28E+O 7.63E-1 2.81 E-1 1.69E+0 3.21 E+2 0 Mn-54 -4.38E+3 8.36E+2 -1.30E+3 1.34E+4 Mn-56 -1.1OE+2 1.96E+1 -1.40E+2 3.52E+3 Fe-55 6.61 E+2 4.57E+2 1.06E+2 ..2 ..... -.+.22. 2.62E+2 Fe-59 1.04E+3 2.45E+3 9.40E+2 --8.17E+3 Co-57 2.11E+1 3.51E+1 -.5.36E+2 Co-58 8.99E+1 2.02E+2 -1.82E+3 Co-60 2.58E+2 5.70E+2 -4.85E+3 Ni-63 3.13E+4 2.17E+3 1.05E+3 -. -._ 4.52E+2 Ni-65 1.27E+2 1.65E+1 7.52E+0 --4.18E+2 Cu-64 1.01E+1 4.72E+0 -8.57E+2 Zn-65 2.32E+4 7.38E+4 3.33E+4 -9 .4 -4.65E+4 Zn-69 4.93E+1 9.43E+1 6.56E+0 E+1 -1.42E+1 Br-82 -2.27E+3 -2.61 E+3 0 Br-83 -4.05 -5.83E+ 1 Br-84 4.12E-4 Br-85 --' -+0-Rb-86 -1.01 E+5 4.7 .... .. 1.99E+4 Rb-88 -2.90 _.W 4.00E-9 Rb-89 -1. 9,4 2 1".ý 2 2.............--
.-.-.--.-------
Sr-89 2.24E+4 -6 +2 3.60E+3 Sr-90 5.52E+5,-" 5E+5 _ _ ---1.59E+4 Sr-91 4.13E-, 1.67E+1 -.-1.97E+3 Sr-92 1.57 6.77E+0 3.10E+3... ....... ........................
- .......................................
- .....................................
..................
Sr-92_0 1.5.E-2 --621E+ 5 Y-91m 2.14E-4 ---1.62E-2 YIII1zz:zI
+ 2.2E- 4.72E+3 Y-9 150E-3 _--- 9.OOE+20 Y -9;" ----- -_-5 ()E ': ...................................
........ ........ -. .. .............
..........................
- 9. 0 E+-- --2 Z" 1E ... .... .. .. ........ 5.87E-2 1.36E-1 2.75E+2 Zr-97 1.49E-2 3.01E-3 1.38E-3 4.55E-3 9.34E+2 Nb-95 4.47E+2 2.49E+2 1.34E+2 2.46E+2 1.51E+6 5 Nb-97 3.75E+0 9.48E-1 3.46E-1 -1.11E+0 3.50E+3 Mo-99 -1.07E+2 2.04E+1 -2.43E+2 2.49E+2 Tc-99m 9.11E-3 2.58E-2 3.28E-1 -3.91E-1 1.26E-2 1.52E+1 0 Tc-101 9.37E-3 1.35E-2 1.32E-1 -2.43E-1 6.90E-3 -0 Ru-103 4.61E+0 1.99E+0 -1.76E+1 5.39E+2 Ru-105 3.84E-1 1.52E-1 -4.96E+0 2.35E+2 Ru-106 6.86E+1 8.68E+0 -1.32E+2 4.44E+3 Rh-103m ----...0 Rh-106 -- --1.0-12 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 1.2 (Page 2 of 2)Site Related Ingestion Dose Commitment Factors (mrem/hr oer uCi/ml)ODCM 1.0 Revision 15 June 6, 2013 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S S 0 0 0 0 0 Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 10Ag0m. 1.04E+O 9.62E-1 5.71 E- -1.89E+0 .-3.92E+2 Sb-124 9.48E+0 1.79E-1 3.76E+O 2.30E-2 -7.38E+0 2.69E+2 Sb-125 6.06E+0 6.77E-2 1.44E+O 6.16E-3 -4.67E+0 6.67E+1 Te-125m 2.57E+3 9.31E+2 3.44E+2 7.73E+2 1.04E+4 1.03E+4 Te-127m 6.49E+3 2.32E+3 7.911E+2 1.66E+3 2.64E+4 -2.18E+4 Te-127 1.05E+2 3.79E+1 2.28E+1 7.81E+1 4.29E+2 8.32E+3 Te-129m 1.10E+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 5.55E+4 Te-129 3.OIE+1 1.13E+1 7.33E+O 2.31E+1 1.27E+2 2.27E+1 Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+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 + 1 Te-132 _2.42E+3 1.56E+3 1,47E+3 1.73E+3 1.50 7.39E+4 1-130 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+O 1-133 5.24E+1 9.11E+1 2.78E+1 1.34Et4 \2,59E 8.19E+1 T-14 3.91 E+0 1.06E+1 3.80E+0 1.84 9 96-3 1-135 1.63E+1 4.28E+1 1.58E+1 2. +6 +i--1 -4.83E+1 Cs-134 2.98E+5 7.09E+5 5.79E+5 9E+5 7.61E+4 1.24E+4 Cs-136 3.12E+4 1.23E+5 8.86E+4 -.85E+4 9.39E+3 1.40E+4 Cs-.37 3.82E+5 5.22E+5 3.42E+ --1.77E+5 5.89E+4 1.01E+4 Cs-138 2.64E+2 5.22E+2 2. 3.84E+2 3.79E+1 2.23E-3 Ba-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-4 La-.40 1.52E-1 7" 2 -5.63E+3 La-142 7.79E-3 .3 54V-.,b ,2E-4 --2.59E+1 Ce-141 3.17E-2._
-2 2.43E-3 -9.95E-3 -8.195+1 Ce-143 5.58E-3 _1 0 4.57E-4 -1.82E-3 -1.54E+2 Ce-144 16 0 0 -1 8.87E-2 -O4.1E-1 -5.58E+2 Pr-143 E -i 2.77E-2 -1.30E-1 -2.45E+3 Pr-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+2 1.0-13 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 1.3 Bioaccumulation Factors (BFi)(pCi/kg per pCi/liter)*
ODCM 1.0 Revision 15 June 6, 2013 Element Freshwater Fish H 9.OE-01 C 4.6E+03 Na ...0E+02 P 3.OE+03 Cr 2.OE+02 Mn 4.OE+02 Fe I .OE+02......Cu....................5..
..r.........
.................................
......... ......................
................
.... ._! .. .... .... .............
...........
.. ...........
.. ...........
.. .! -...E.............
.. ..........................................
C u...............................
....................
.......................
.............
.5...........O E .... ...................................................
..... .........
.... ...................-
-.... ........ .. ....................
... .2.. ................................
.........................
.............
.............
.............
--................
..... ............
r< 0.. .........
..... ..... ...... ...... ..c ... ..... ..........
................
.......Sr..... .........
I.5_0 ..................
Zr 00-------Nb E-+04 Mo L> OE+01..T....c..............
.. .. ... ., E +O.................
..........
.... ..... ... .... .............
........................
.. .-, -, : ...............
........ ..... .. ...................
...: ::: : :: :::: ::: ::: : : : : : : : :::,EO.....
........ .........
....... .. ............
......-- ..........I..... ... ........ .Ru I.OE+00 S.............. r...............
... ............
..............
....... ....... ..-- -.... ..........
4O E 0...RQ.. ..........
1.5E+01 2.3E+00 Ba 4.OE+02.~~~ ..........
La 2.5E+01-------Ce 1.OE+00 Nd 2.5E+01 W 1.2E+03 I I 6 6 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 03/4!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 from UCRL 50564, Rev. 1, October 1972.1.0-14 U KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 2.0 Gaseous Effluents Methodology
- 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Kewaunee for controlling and O monitoring normal radioactive material releases in accordance with 10 CFR 50, Appendix A, Criteria 60 and 64, are summarized as follows: O 2.1.1 Waste Gas Holdup System O The vent header gases are collected by the Waste Gas Holdup System. Gases may be recycled O 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 are O 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 the WGDTs. CVCs HUTs will be isolated and discha Building Vent. R-13 and/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 the O Aux Building if R-13/R-14 levels are b ow .If levels are above 5,000 but below 10,000 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 the Auxiliary Building n ere~0 itored by R-13 and/or R-14.0 2.1.3 Containment Pur O Contain t e ventilation is via the containment stack for the 36-inch RBV system but via th u il' ing stack for the 2-inch vent and mini-purge blower system. The stack radiati 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, and 0
- 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 0 0 KEWAUNEE POWER STATION ODCM 2.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 2.1.4 Auxiliary Building Vent The Auxiliary Building vent receives discharges from the waste gas holdup system, condenser evacuation system, fuel storage area ventilation, Auxiliary Building radwaste processing area ventilation, 2-inch containment pressure relief purge/vent system, and Auxiliary Building general area. 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. z The noble gas monitor provides auto isolation of any waste gay tan elease and diverts other releases through the special ventilation system. Effi f are determined by installed flow measurement equipment or as a function of f , ati n curves). Sampler 0 flow rates are determined by flow rate instrumentation.
> 7 2.1.5 Containment Mini-PurgeNent System 0 Slight pressure buildup in containment is a rri ev resulting from normal operation of the plant. Prior to exceeding 2 psig in con ,hi~xcess pressure is vented off. Air from containment is routed to the Auxiliary B E system, via the post-LOCA hydrogen recombiner piping and then out througl ia Building vent stack. The system is also designed 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) or the containment building ai o ivity monitors (R-11, R-12) provides automatic isolation.
2.1.6 Non-routine Discharg, s Periodically, noni reac s are made in the Auxiliary and Containment buildings that might allow the' fthe atmosphere, which contains some levels of radioactivity.
These breaches irudeid not limited to, opening the Containment equipment hatch during outages, ho c walls or ceilings to allow for moving equipment in or out of the Radiol, y d Areas (RCAs). All efforts to maintain these areas at negative pressure will b 0egative pressure cannot be maintained (i.e., more exhaust than supply fan volume , E supply ventilation to the area must be secured. Criteria for determining if and when 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 shall be documented and included in the monthly, quarterly and annual reports as appropriate.
0 A gaseous radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 2.2 0 S 0 0 2.0-20 0 0 0 W KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013* 2.2 Gaseous Effluent Monitor Setpoint Determination
2.2.1 Containment
and Auxiliary Building Vent Monitor Per the requirements of ODCM Normal Condition 13.3.2, alarm setpoints shall be established 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 to the total body or 3000 mrem/year to the skin. Based on a grab sample analysis of the*applicable release (i.e., grab sample of the Containment vent or Auxiliary Building vent), the*radiation monitoring alarm setpoints may be established by the following calculational method: FRACtb= [4.72E + 02 x X/Q x VFx E (Ci x K 500 (2.1)FRAC~, = [4.72E+02xX/QxVFx (C i x(Li +1.1M,))]
3000 (2.2)where: FRACtb fraction of the allowable relea total body based on the= tal bodyski based o h identified radionuclide concenions an t release flow rate FRACskin 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/mi 3 , from Table 2.3)* VF = ventilati n4// ) rate for the applicable release point and monitor O (ft 3 llrn rolmNTe 2.2)Q iopf noble gas radionuclide "i" as determined by radioanalysis e (,Ci/cm 3)Ki I .body dose conversion factor for noble gas radionuclioe "i"*m /yr per jiCi/m 3 , from Table 2.1)0 Li 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/m 3 , from Table 2.1)1.1 = mrem skin dose per mrad gamma air dose (mrem/mrad) 4.72E+02 = conversion factor (cm 3/ft 3 x min/sec)0*500 = total body dose rate limit (mrem/yr)*3000 = skin dose rate limit (mrem/yr)2.0-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoint for 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/cm 3), 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 Values A 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 to adjust the setpoint to reflect minor changes in ucl* distribution and variations in release flow 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 N a) 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 any simultaneo el es not exceed the maximum allowable release rate.For ' r uie distribution, the alarm setpoint based on the total body dose rate is m r I an the corresponding setpoint based on the skin dose rate. The resulting co ti, default setpoints are presented in Table 2.2.0 0 0 0 0 0 0 S 0 0 0 0 0 0 S S S S S 0 0 0 S 0 0 0 0 0 S 0 S 0 0 S Adopted from ANSI N237-1976/ANS-1 8.1, Source Term Specifications, Table 6.2.0-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations
-10 CFR 20 0 0 0 0 S S 0 0 0 0 0 2.3.1 SITE BOUNDARY Dose Rate -Noble Gases.ODCM Normal Condition 13.2.1.a limits the dose rate at the SITE BOUNDARY due to noble gas releases to < 500 mrem/yr to the total body, and < 3000 mrem/yr to the skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.
In the event any gaseous releases from the station results in the alarm setpoints being exceeded, an evaluation of the UNRESTRICTED AREA dose rate resulting from the release may be performed using the following equations:
Db=XIQX I(KxQij and r, = /Qxj(Li +1.1tv total bodvý ir (2.4)(2.5)where: D tb D.nrem/yr)Qi K,-p6spheiFic dispersion for direct exposure to noble gas at the controlling BOUNDARY (sec/m 3 , from Table 2.3)-average release rate of radionuclide "i" over the release period under S evaluation (gCi/sec)-total body dose conversion factor for noble gas radionuclide "i" (mrem/yr per gCi/mi 3 , from Table 2.1)beta skin dose conversion factor for noble gas radionuclide "i" (mrem/yr per giCi/m 3 , from Table 2.1)gamma air dose conversion factor for noble gas radionuclide "i" (mradlyr per IaCi/m 3 , from Table 2.1)mrem skin dose per mrad gamma air dose (mrem/mrad)
Mi 1.1 2.0-5 0 6 KEWAUNEE POWER STATION ODCM 2.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 6 June 6, 2013 Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2.3 may be used for evaluating the gaseous effluent dose rate.2.3.2 SITE BOUNDARY Dose Rate -Radioiodine and Particulates S ODCM Normal Condition 13.2.1.b limits the dose rate to < 1500 mrem/yr to any organ for 1-131, 1-133, tritium and particulates with half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period for continuous releases (e.g., nominally once per 7 days)and for batch releases on the time period over which any batch release is to occur. The following equation may be used for the dose rate evaluation:
D.X/Q x ZRXQj (2.6)0-0 where: D. = average organ dose rat ve e s ling time period (mrem/yr) 0 x/Q = atmospheric disp o controlling SITE BOUNDARY for the inhalation pathwa rom Table 2.3)R= dose par e r nuclide "", (mrem/yr per jiCi/m 3) for the childTable 2.6 C~j/ 0 Qi el e rate over the appropriate sampling period and analysis fre/enc y~r radionuclide "i", 1-131, 1-133, tritium or other radionuclide in ulate 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 be deter e s on the annual average meteorological dispersion (see Table 2.3) and the most Itwi pathway, age group and organ (inhalation pathway, child thyroid -0 Ri = 1.62 mremlyr per igCi/m 3) the allowable release rate for 1-131 is 6.43 jiCi/sec.
An added conservatism factor of 0.25 has been included in this calculation to account for any 0 potential dose contribution from other radioactive particulate material.
For a 7-day period, which is the nominal sampling and analysis frequency for 1-131, the cumulative allowable release is 3.9 Ci. Therefore, as long as the 1-131 releases in any 7-day period do not exceed 3.9 Ci, no additional analyses are needed to verify compliance with the ODCM Normal Condition 13.2.1.b 5 limits on allowable release rate.0 S 0 0 2.0-6 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 2.4 Gaseous Effluent Dose Calculations
-10 CFR 50 0 0 S S 0 0 S 0 S 0 0 0 0 0 0 0 0 S 0 2.4.1 UNRESTRICTED AREA Dose -Noble Gases ODCM Normal Condition 13.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of (< 5 mrad, gamma-air and < 10 mrad, beta-air) and the calendar year limits (5 10 mrad, gamma-air and < 20 mrad, beta-air).
The following 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 to le gas radionuclides (mrad))ble gas radionuclides (mrad)Iling SITE BOUNDARY (sec/m 3 , from x/Q Qi gas 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/m 3 , Table 2.1)Ni 3.1 conversion factor (yr/sec)In lieu of~j..!ndividual noble gas radionuclide 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 13.2.2. (Refer to Appendix B for the derivation and justification for this simplified method.)Dy= 3.1 7 E-0 8 XX/QxMCfxzQ, 0.50 (2.9)and Dt = 3.17E- 08 xX/Q xNetr x E Qi 0.50 (2.10)2.0-7 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 where: Meff Neff 0.50= 5.3E+02 effective gamma-air dose factor (mrad/yr per jiCi/m 3)= 1.1 E+03 effective beta-air dose factor (mrad/yr per igCi/m 3)= conservatism factor 2.4.2 Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2.3, may be used for the evaluation of the gamma-air and beta-air doses.UNRESTRICTED AREA Dose -Radioiodine and Particulates Per the requirements of ODCM Normal Condition 13.2.3 p 1 sessment shall be performed to evaluate compliance with the quarterly dose .5 1m) and calendar year limit (_< 15 mrem) to any organ. The following equatio bs o evaluate the maximum organ dose due to releases of 1-131, 1-133, tritium pa Itwith half-lives greater than 8 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 the total boiyiA "p" from 1-131, 1-133, tritium and radionuclides in Part'Iaeo with half-life greater than eight days (mrem)W = ric/ spersion parameter to the controlling location(s) as e.fi able 2.3 X!Q = ospheric dispersion for inhalation pathway and H-3 dose contribution I her pathways (sec/m 3)D/Q / .tmospheric deposition for vegetation, milk and ground plane exposure pathways (I/mr)Ri dose factor for radionuclide "i", (mrem/yr per gCi/m 3) or (M 2 -mrem/yr per pCi/sec) from Table 2.4 through 2.15 for each age group "a" and the applicable pathway "p" as identified in Table 2.3. Values for R 1 were derived in accordance with the methods described in NUREG-0133.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Qi= cumulative release over the period of interest for radionuclide "i" -- 1-131 or radioactive material in particulate form with half-life greater than 8 days (RCi).2.0-8
- KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 SFP seasonal correction factor to account for the fraction of the period that the applicable exposure pathway does exist.1) For milk and vegetation exposure pathways: 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: = 1.0 In 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 e RI-13 = 1-131 dose p tor thyroid for the identified controlling pathway S 1.05E+, dose parameter with the grass-cow-milk pathwaynrem/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 these pathways 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 dose contribution an ei vegetation or grass-cow-milk pathway. However, use of the 1-131 thyroid 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 on the available pathways in the surrounding environment of Kewaunee as identified by the annual 0land-use census. Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2.3.2 0 0 0 0*2.0- 9 0 0 S O KEWAUNEE POWER STATION ODCM 2.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 2.5 Gaseous Effluent Dose Projection 0 ODCM Normal Condition 13.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses exceed one-half the annual design objective rate in any 31 days, i.e., exceeding:
0* 0.2 mrad, gamma air,* 0.4 mrad, beta air, or 0 0.3 mrem, maximum organ. 0 The 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) S D- 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 0 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 period 31 number of days in a 31 day period S 2 S S S 2.0- 10 S S S 0* KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 2.6 Environmental Radiation Protection Standards 40 CFR 190*For the purpose of implementing ODCM Normal Condition 13.4.1 on the EPA environmental radiation protection standard and Technical Specification 5.6.2 on reporting requirements, dose calculations may 0be performed using the above equations with the substitution of average or actual meteorological parameters for the period of interest and actual applicable pathways.
Any exposure attributable to on-site sources will be evaluated based on the results of the environmental monitoring program (TLD measurements) or by calculational methods. NUREG-0543 describes acceptable methods for*demonstrating compliance with 40 CFR Part 190 when radioactive effluents exceed the Appendix I*portion of the specifications.
- 2.7 Incineration of Radioactively Contaminated Oil During plant operation, radioactively contaminated oils are 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 allows licensees-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 each container.
The heating boiler will be utilized to in t rah actively contaminated oil collected on site. A gaseous radwaste effluent dose c c rescribed in Section 2.3 of the ODCM, will be performed to ensure that the limit ab d by ODCM Normal Condition 13.2.1, 13.2.2 and 13.2.3 are not exceeded.
Release of assumed to occur at the time the contaminated oil is transferred 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, or from the boiler exhaust sFige 3 for a description of the heating boiler fuel oil system.2.8 Total Do e The purpose/ i," sis to describe the method used to calculate the cumulative dose 0 contributions 1 A d gaseous effluents in accordance with KPS Technical Specifications for total 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 gaseous effluents exceeding twice the limits outlined in ODCM DNC 13.1.2, 13.2.2, and 13.2.3, a special*! analysis shall be performed.
The purpose of this analysis is to demonstrate if the total dose to any*MEMBER OF THE PUBLIC (real individual) from all uranium fuel cycle sources (including direct radiation contributions from the 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- 11 0 0 0 0 0 KEWAUNEE POWER STATION ODCM 2.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 If required, the total dose to a MEMBER OF THE PUBLIC will be calculated for all significant effluent release points for all real pathways including direct radiation.
Effluent releases from Point Beach Nuclear Plant must also be considered due to its proximity.
Calculations will be based on the equations in Sections 1.4, 2.4.1, and 2.4.2, with the exception that usage factors and other site specific parameters may be modified using more realistic assumptions, where appropriate.
The direct radiation component from the facility can be determined using environmental TLD results.These results will be corrected for natural background and for actual occupancy time of any areas accessible to the general public at the location of maximum direct radiation.
It is recognized that by including the results from the environmental TLDs into the sum of total dose component, the direct radiation dose may be overestimated.
The TLD measurements may include the exposure from noble gases, ground plane deposition, and shoreline deposition, which have al een included in the summation of the significant dose pathways to the general public. How this nservative method can be used, if required, as well as any other method for estimatin hi\ 4rc)rpcdiation dose from contained radioactive sources within the facility.
The mel u orporate the direct radiation 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 and parameters to assess the real dose to any MEMBER OF UBLI--0 0 0 0 0 0 2.0- 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 Auxliajy Buding VentStock (~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. CS75M3 ODCM FIGURE 2 GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM 2.0-13 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 Figure 3 Simplified Heating Boiler Fuel Oil Piping System Heating Boger Fuel OU Storage Tank heating boller 30,000 Gallons fuel all pumps 2.0-14 0000000000000000000000000000000000000000000o 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0 0 0 0 0 0 0 0 S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 Table 2.1 Dose Factors for Noble Gases Total Body Dose Skin Dose Factor Gamma Air Dose Beta Air Dose Factor Ki L, (mremlyr per Factor M, Factor N, Radionuclide (mrem/yr per IJCilm 3) (mradlyr per (mradlyr per PCI/m 3) pCilm 3) PCilm 3)Kr-83m 7.56E-02 1.93E+01 ,88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1. E+03 Kr-85 1.61E+01 1.34E+03 1.72E+Of / 195E+03 Kr-87 5.92E+03 9.73E+03 __1.03E+04 Kr-88 1.47E+04 2.37E+03 1. + 2.93E+03 Kr-89 1.66E+04 1.01E+04 .7 +04 1.06E+04 Kr-90 1.56E+04 7.29E+04 L .63E+04 7.83E+03 Xe-1 31 m 9.15E+01 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9 3.27E+02 1.48E+03 Xe-133 2.94E+02 0! 02 3.53E+02 1.05E+03 Xe-135m 3.12E6 3.36E+03 7.39E+02 Xe-135 1 N .86E+03 1 .92E+03 2.46E+03 Xe- 137 ,N2ý 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.88 -03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 2.0-15 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.2 Parameters for Gaseous Alarm Setpoint Determinations ODCM 2.0 Revision 15 June 6, 2013 Parameter Actual Value Default Value* Units Comments Y]Q calculated 3.6E-06 sec/in 3 Licensing technical specification
!_acad 3E6s/ value Containment
-normal plus VF fan curves 26,000 cfm purge modes 54,000 Auxiliary Building -normal QC measured N/A pCi/m3 <<VV nuclide mrem/yr per Ki specific N/A _JCi/m3 _____ _2.1 m ~nuclide mrem/yr" perVa /Li nddeN/A firi/yr per s fr Table 2.1 Mi nuclide N/A mrem/y er from Table 2.1 Sensitivity**" s fi (SEN)R-12 2.32E+07 m Containment R-21 as determined 2.32E+07 Containment R-13 2.32E+07 Auxiliary Building R-14 2.32E+07/Z Auxiliary Building Background (bkg)R-12 as determined 4 Nominal values only; actual R-21 adeemndvalues may be used in lieu of R-13 E0 these reference values.R-14 ___Setpoint* (SP) Default alarm setpoints; more R-12 calc d 2.8E+05+bkg conservative values may be R-21 Ia 2.8E+05+bkg cpm used as deemed appropriate R-13 a 1.3E+05+bkg and desirable for ensuring R-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.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-16 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 S S 0 0 0 0 KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Table 2.3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations Atmospheric Dispersion ODCM Normal Condition Location Pathways x/Q (seclm 3) D/Q (/lm 2)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. 0C Site Boundary Gamma Air 4- N7A 13.2.2 (0.81 mile, NNW) Beta Air _"___"___,__NI Residence/dairy Inhalation, 13.2.3 (1.3 mile S) Vegetation, Mil X 1.86E-09 2.0-17 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.4 (Page 1 of 2)Ri Inhalation Pathway Dose Factors- ADULT (mrem/yr per pCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 P-32 1.32E+6 7.71 E+4 8-Wo4-+4 5.01 E+4 Cr-51 --5.95E+1 2.28E+1 1.44 E+4/ /3.3_ 3 1.OOE+2 Mn-54 -3.96E+4 -9.84E+3 1.40E,6X ,.74E 6.30E+3 Mn-56 -1.24E+0 -1.30E+0 9.4,4 3 ."? 4 1.83E-1 Fe-55 2.46E+4 1.70E+4 --7.!ýX +, ,05E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 --.-Q .88E+5 1.06E+4 Co-57 -6.92E+2 --3.XX+)V 3.14E+4 6.71E+2 Co-58 -1.58E+3 --9.28) 5 1.06E+5 2.07E+3 0o-60 -1.15E+4 --+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 -.8E+5 1.34E+4 1.45E+4 Ni-65 1.54E+0 2.10E-1 -/,"5.60E+3 1.23E+4 9.12E-2 Cu-64 -1.46E+0 -6.78E+3 4.90E+4 6.15E-1 Zn-65 3.24E+4 1.03E+5 -.9 +4 8.64E+5 5.34E+4 4.66E+4 Zn-69 3.38E-2 6.51E-2 -.E-2 9.20E+2 1.63E+1 4.52E-3 Br-82 -1.04E+4 1.35E+4 Br-83___,,__" -<1 2.32E+2 2.41 E+2 Br-84 1.64E-3 3.13E+2 Br-85 -_ ,,-,_,__ .-1.28E+1 Rb-86 -______,,/-1.66E+4 5.90E+4 Rb-88 -2 3.34E-9 1.93E+2 Rb-89 -g2_+2 1.70E+2 Sr-89 _____1.40E+6 3.50E+5 8.72E+3 Sr-90 9.60E+6 7.22E+5 6.1OE+6 Sr-91 ______9___,___3.65E+4 1.91E+5 2.50E+0 Sr-92_,_.__-_)
-_1.65E+4 4.30E+4 2.91 E-1 Y-90 2.,2_,_W 1.70E+5 5.06E+5 5.61E+1 Y-91 r 2._611r=-
11.92E+3 1.33E+0 1.02E-2 Y-91 4.62E+5 1.70E+6 3.85E+5 1.24E+4 Y-92 1.03E+1 1.57E+4 7.35E+4 3.02E-1 Y-93 9.44E+1 4.85E+4 4.22E+5 2.61 E+0 Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 2.33E+4 Zr-97 9.68E+1 1.96E+1 -2.97E+1 7.87E+4 5.23E+5 9.04E+0 Nb-95 1.41 E+4 7.82E+3 -7.74E+3 5.05E+5 1.04E+5 4.21E+3 Nb-97 2.22E-1 5.62E-2 -6.54E-2 2.40E+3 2.42E+2 2.05E-2 Mo-99 -1.21 E+2 -2.91E+2 9.12E+4 2.48E+5 2.30E+1 Tc-99m 1.03E-3 2.91 E-3 -4.42E-2 7.64E+2 4.16E+3 3.70E-2 Tc-101 4.18E-5 6.02E-5 -1.08E-3 3.99E+2 -5.90E-4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.4 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -ADULT (mrem/yr per pCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.53E+3 -5.83E+3 5.05E+5 1.10E+5 6.58E+2 Ru-105 7.90E-1 --1.02E+0 1.1OE+4 4.82E+4 3.11E-1 Ru-106 6.91E+4 --1.34E+5 9.36E+6 9.12E+5 8.72E+3 Rh-103m --Rh-106 -Ag-110m 1.08E+4 1.OOE+4 1.97E+4 4.63E+6 /.+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 -2.48E+6 4.061ý5 1.24E+4 Sb-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+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 .6 /.50E+5 1.57E+3 Te-127 1.40E+0 6.42E-1 1.06E+0 5.10 E+0 .5.74E+4 3.10E-1 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.661 +'X 1.1 O+6v 3.83E+5 1.58E+3 Te-129 4.98E-2 2.39E-2 3.90E-2 1.W-1 N J.9.X_+3 1.57E+2 1.24E-2 Te-131m 6.99E+1 4.36E+1 5.50E+1 .Ey;> 'IAE+5 5.56E+5 2.90E+1 Te-131 1.11E-2 5.95E-3 9.36E-3 r54. W2 / 1.39E+3 1.84E+1 3.59E-3 Te-132 2.60E+2 2.15E+2 1.90E+;" 1, 2.88E+5 5.1OE+5 1.62E+2 1-130 4.58E+3 1.34E+4 0 7.69E+3 5.28E+3 1-131 2.52E+4 3.58E+4 1 tR-)7 , +4 -6.28E+3 2.05E+4 1-132 1.16E+3 3.26E+3 14 , 18E+3 -4.06E+2 1.16E+3 1-133 8.64E+3 1.48E+4 / + 2.58E+4 -8.88E+3 4.52E+3 1-134 6.44E+2 1.73_, /4.9"e4 2.75E+3 -1.01E+0 6.15E+2 1-135 2.68E+3 6.98 , 44.4 5 1.11E+4 -5.25E+3 2.57E+3 Cs-134 3.73E+5 ,8" tb,\,ZZ 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 .4_4-5 " _ 8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+ + 5 -2.22E+5 7.52E+4 8.40E+3 4.28E+5 Cs-138 3.31+2 ""6 +2 4.80E+2 4.86E+1 1.86E-3 3.24E+2 Ba-139 9.36 ý. 6E-4 6.22E-4 3.76E+3 8.96E+2 2.74E-2 Ba-140 .,E , OE+I 1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ba-141 7.53E-5 7.OOE-5 1.94E+3 1.16E-7 3.36E-3 Ba-142 .63 2.70E-5 2.29E-5 1.19E+3 -1.66E-3 La-140 3 +2 1.74E+2 1.36E+5 4.58E+5 4.58E+1 La-142 6.83E-1 3.1OE-1 6.33E+3 2.11E+3 7.72E-2 Ce-141 1.99E+4 1.35E+4 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-143 1.86E+2 1.38E+2 6.08E+1 7.98E+4 2.26E+5 1.53E+1 Ce-144 3.43E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Pr-144 3.01E-2 1.25E-2 7.05E-3 1.02E+3 2.15E-8 1.53E-3 Nd-147 5.27E+3 6.10E+3 -3.56E+3 2.21E+5 1.73E+5 3.65E+2 W-187 8.48E+0 7.08E+0 -2.90E+4 1.55E+5 2.48E+0 Np-239 2.30E+2 2.26E+1 -7.00E+1 3.76E+4 1.19E+5 1.24E+1 2.0-19 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.5 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -TEEN (mrem/yr per pCi/rn 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 Na-24 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 P-32 1.89E+6 1.1OE+5 --9.28E+4 7.16E+4 Cr -7.50E+1 3.07E+1 2.1OE+4 3 1.35E+2 Mn-54 -5.11E+4 -1.27E+4 1.98E+6 ..68E+4N 8.40E+3 Mn-56 -1.70E+0 -1.79E+0 1.52E+4 E+ 2.52E-1 Fe-55 3.34E+4 2.38E+4 --5.54E+3 Fe-59 1.59E+4 3.70E+4 --1.53 1. +5 1.43E+4 Co-57 -6.92E+2 --
9.20E+2 Co-58 2.07E+3 --<-13 -"9.52E+4 2.78E+3 Co-60 -1.51E+4 -I Z2 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 --3.' +5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 --, 6E+3 3.67E+4 1.27E-1 Cu-64 -2.03E+0 -.4 4 11 E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 -, 4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 -0 2 1.58E+3 2.85E+2 6.46E-3 Br-82 --_,_____--
1.82E+4 Br-83 ---_____,V_,__-"--
3.44E+2 Br-84 -__,__ -4.33E+2 Br-85 --, 1.83E+1 Rb-86 -1.77E+4 8.40E+4 Rb-88 -2.92E-5 2.72E+2 Rb-89 -+2_-,,_ -3.38E-7 2.33E+2 Sr-89 4.34E+5 --2.42E+6 3.71 E+5 1.25E+4 Sr-90 1.0 ---1.65E+7 7.65E+5 6.68E+6 Sr-91 -OEE+ 6.07E+4 2.59E+5 3.51 E+O Sr-92 9 ---2.74E+4 1.19E+5 4.06E-1 Y-90 '" BEt ---2.93E+5 5.59E+5 8.00E+1 Y-91 m 3. ---3.20E+3 3.02E+1 1.42E-2 Y-91 6.61 E+5 --2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 ---2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 ---8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-97 1.38E+2 2.72E+1 -4.12E+1 1.30E+5 6.30E+5 1.26E+1 Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51 E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 -9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 -1.69E+2 -4.11 E+2 1.54E+5 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 -5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 -1.52E-3 6.67E+2 8.72E-7 8.24E-4 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.5 (Page 2 of 2)R, Inhalation Pathway Dose Factors -TEEN (mrem/yr per pCi/rn 3)ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.1OE+3 -7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-105 1.125+0 ---1.41E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m ---Rh-1 06 --Ag-11Orn 1.38E+4 1.31E+4 -2.50E+4 6.75E+6< .73 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E, \V 98E4 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.7,,4 W)6 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 -5. + 7,,, 4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 -+,,.59E+5 2.18E+3 Te-127 2.01E+O 9.12E-1 1.42E+0 7.28E+,/ 1. + 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19,:*\ X1.98F6 4.05E+5 2.25E+3 Te-129 7.10E-2 3.38E-2 5.18E-2 2 -.+3 1.62E+3 1.76E-2 Te-131m 9.84E+1 6.01E+1 7.25E+1 48E+5 6.21 E+5 4.02E+1 Te-131 1.58E-2 8.32E-3 1.24E-2.-,-
- S. 2 /,2.34E+3 1.51E+1 5.04E-3 Te-132 3.60E+2 2.90E+2 2.46E-ýZ ý 4.49E+5 4.63E+5 2.19E+2 1-130 6.24E+3 1.79E+4 12 +F 2.7 +4 -9.12E+3 7.17E+3 1-131 3.54E+4 4.91E+4 ,,64'7 E44 5+4 -6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3- \",ft -1.27E+3 1.58E+3 1-133 1.22E+4 2.05E, 2. %ý+6 3.59E+4 -1.03E+4 6.22E+3 1-134 8.88E+2 2.32"3 / ).9.5 14 3.66E+3 -2.04E+1 8.40E+2 1-135 3.70E+3 .68X +5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 5.02E+5 1 .+- 3.75E+5 1.46E+5 9.76E+3 5.49E+5 CS-1 36 5.15E+A +5 -1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 &.44E+5 -3.04E+5 .1.21E+5 8.48E+3 3.11E+5 Cs-138 4.ffg +2 5 +2 -6.62E+2 7.87E+1 2.70E-1 4.46E+2 Ba-139 , iZ\-0 44E-4 -8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5 ..70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 ., 1 1.06E-4 -9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ba-142 2 3.70E-5 -3.14E-5 1.91E+3 -2.27E-3 La-140 4. 9E+2 2.36E+2 -2.14E+5 4.87E+5 6.26E+1 La-142 9.60E-1 4.25E-1 --1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-143 2.66E+2 1.94E+2 -8.64E+1 1.30E+5 2.55E+5 2.16E+1 Ce-144 4.89E+6 2.02E+6 -1.21 E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31 E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 -1.01E-2 1.75E+3 2.35E-4 2.18E-3 Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+O -4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 -1.OOE+2 6.49E+4 1.32E+5 1.77E+1 2.0-21 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.6 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -CHILD (mrem/yr per pCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 P-32 2.60E+6 1.14E+5 ---4.22E+4 9.88E+4 Cr-51 -8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 -4.29E+4 -1.OOE+4 1.58E+6 2.29.ii .51E+3 Mn-56 -1.66E+0 -1.67E+0 1.31E+4 1.2X+5 .7+2E-1 Fe-55 4.74E+4 2.52E+4 --1.11E+5Fe-5 I 3.34E 7E+3 Fe-59 2.07E+4 3.34E+4 --.+.27E+7E
.+ .67E+4 Co-57 -9.03E+2 --5.07F , +- .2F,,0 1.07E+3 Co-58 -1.73- ',W43163 Co-60 -1.31E+4 E+6 .692E+4 2.26E+4 Ni-63 8.21 E+5 4.63E+4 -Z. -,18 , '6.33E+3 E.+ 32.80E+4 Ni-65 2.99E+0 2.96E-1 -< 18 8.40E+4 1.64E-1 Cu-64 -1.99E+0 -.-9.,+3 3.67E+4 1.07E+0 Zn-65 4.26E+4 1.13E+5. 4;5E+5 1.63E+4 7.03E+4 Zn-69 6.70E-2 9.66E-2-E 1.42E+3 1.02E+4 8.92E-3 Br-82 --____- 2.09E+4 Br-83 -___,/____
4.74E+2 Br-84 -__,._,, 5.48E+2 Br-85 -2.53E+1 Rb--86 -7.99E+3 1.14E+5 R__-88 _ 2E -1.72E+1 3.66E+2 Rb-89
--1.89E+0 2.90E+2 Sr-89 5.99F-+5 --2.16E+6 1.67E+5 1.72E+4 Sr-90 1.0 ---1.48E+7 3.43E+5 6.44E+6 Sr-91 E+- -5.33E+4 1.74E+5 4.59E+0 Sr-92 --- _ 2.40E+4 2.42E+5 5.25E-1 Y-90 11 o ---2.62E+5 2.68E+5 1.11E+2 Y-91m 5. --2.81E+3 1.72E+3 1.84E-2 Y-91 9.14E+5 ---2.63E+6 1.84E+5 2.44E+4 Y-92 2.04E+1 ---2.39E+4 2.39E+5 5.81 E-1 Y-93 1.86E+2 ---7.44E+4 3.89E+5 5.11E+0 Zr-95 1.90E+5 4.18E+4 -5.96E+4 2.23E+6 6.11E+4 3.70E+4 Zr-97 1.88E+2 2.72E+1 -3.89E+1 1.13E+5 3.51E+5 1.60E+1 Nb-95 2.35E+4 9.18E+3 -8.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-97 4.29E-1 7.70E-2 -8.55E-2 3.42E+3 2.78E+4 3.60E-2 Mo-99 -1.72E+2 -3.92E+2 1.35E+5 1.27E+5 4.26E+1 Tc-99m 1.78E-3 3.48E-3 -5.07E-2 9.51E+2 4.81E+3 5.77E-2 Tc-101 8.1OE-5 8.51E-5 -1.45E-3 5.85E+2 1.63E+1 1.08E-3 2.0-22 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 0 6 0 0 0 S 0 0 0 0 0 0 S 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.6 (Page 2 of 2)R, Inhalation Pathway Dose Factors -CHILD (mrem/yr per JACi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.79E+3 --7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-105 1.53E+0 --1.34E+O 1.59E+4 9.95E+4 5.55E-1 Ru-106 1.36E+5 --1.84E+5 1.43E+7 4.29E+5 1.69E+4 Rh-103m --..Rh-106 -.....- -Ag-l10m 1.69E+4 1.14E+4- 2.12E+4 5.48E+6 1.0 14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -3.24E+6 +,655 20E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 -2.32E+6/ .03E4+4, 7E+4 Te-125m 6.73E+3 2.33E+3 1.92E+3 -4.77E-g 30A+ .14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.4 .-N 3.02E+3 Te-127 2.77E+0 9.51E-1 1.96E+0 7.07E+O0@
\ +4 6.11E-1 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4, ,E+6 )1.8'2E+5 3.04E+3 Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-/ 2.55E+4 2.38E-2 Te-131m 1.34E+2 5.92E+1 9.77E+1 4.0015<2 ,61Y 3.08E+5 5.07E+1 Te-131 2.17E-2 8.44E-3 1.70E-2 _ 2. +3 1.33E+3 6.59E-3 Te-132 4.81E+2 2.72E+2 3.17E+2 .7 E+5 1.38E+5 2.63E+2 1-130 8.18E+3 1.64E+4 1.85E+6 + 5.11E+3 8.44E+3 1-131 4.81 E+4 4.81 E+4 16 7. -2.84E+3 2.73E+4 1-132 2.12E+3 4.07E+3,1.l
+ +3 3.20E+3 1.88E+3 1-133 1.66E+4 2.03E+4 ,,ý.8WE 3. E+4 5.48E+3 7.70E+3 1-134 1.17E+3 5El 3.30E+3 9.55E+2 9.95E+2 1-135 4.92E+3 8.73 +\442F_% 1.34E+4 -4.44E+3 4.14E+3 Cs-134 6.51E+5 1 t't 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 <.1F-1 9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+'.2,.
+5 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-138 6.3?,AF + 2 0X "+ -6.22E+2 6.81 E+ 1 2.70E+2 5.55E+2 Ba-139 1.84IN 9. E-4 8.62E-4 5.77E+3 5.77E+4 5.37E-2 Ba-140 ý,Q E+ A-,4E+1 -2.11E+1 1.74E+6 1.02E+5 4.33E+3 Ba-1441 9E-4 -9.47E-5 2.92E+3 2.75E+2 6.36E-3 Ba-142 QOF. 3.60E-5 -2.91 E-5 1.64E+3 2.74E-0 2.79E-3 La-140 6. 4-+2 2.25E+2 -- 1.83E+5 2.26E+5 7.55E+1 La-142 1.30E+0 4.11E-1 -8.70E+3 7.59E+4 1.29E-1 Ce-141 3.92E+4 1.95E+4 -8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-143 3.66E+2 1.99E+2 -8.36E+1 1.15E+5 1.27E+5 2.87E+1 Ce-144 6.77E+6 2.12E+6 -1.171E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 -3.OOE+3 4.33E+5 9.73E+4 9.14E+2 Pr-144 5.96E-2 1.85E-2 -9.77E-3 1.57E+3 1.97E+2 3.OOE-3 Nd-147 1.08E+4 8.73E+3 -4.81 E+3 3.28E+5 8.21E+4 6.81 E+2 W-187 1.63E+1 9.66E+0 -4.11E+4 9.1OE+4 4.33E+0 Np-239 4.66E+2 3.34E+1 -9.73E+1 5.81 E+4 6.40E+4 2.35E+1 2.0-23 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.7 (Page 1 of 2)R 1 Inhalation Pathway Dose Factors -INFANT (mrem/yr per igCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 Na-24 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 P-32 2.03E+6 1.12E+5 ---1.61E+4 7.74E+4 Cr-51 --5.75E+1 1.32E+1 1.28E+4 3.57E+2, 8.95E+1 Mn-54 -2.53E+4 -4.98E+3 1.OOE+6 7.0W,,3-'1 98E+3 Mn-56 -1.54E+0 -1.10E+0 1.25E+4 7 +,;4 1E-1 Fe-55 1.97E+4 1.17E+4 --8.69E+4/X.091!3, 3E+3 Fe-59 1.36E+4 2.35E+4 -1.02E-+,6<
2,, + 4,* .48E+3 Co-57 -6.51 E+2 -- 3.7 5 6W !6.41 E+2 Co-58 -1.22E+3 --/S-& 74182 Co-60 -8.02E+3 -- IE+6 .19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 -- //2. .2.42E+3 1.16E+4 Ni-65 2.39E+0 2.84E-1 -(< V.12P 5.01E+4 1.23E-1 Cu-64 1.88E+0 -9. +3 1.50E+4 7.74E-1 Zn-65 1.93E+4 6.26E+4 -.2 V,47E+5 5.14E+4 3.11E+4 Zn-69 5.39E-2 9.67E-2 -1.47E+3 1.32E+4 7.18E-3 Br-82 ----- -.1.33E+4 Br-83_ _,__,,,___
_ --3.81E+2 Br-85 --//- --2.04E+1 Rb-86 -1.90 + --3.04E+3 8.82E+4 Rb-88 5 5 3.39E+2 2.87E+2 Rb-89 -.., --6.82E+1 2.06E+2 Sr-89 3.98E+5 -2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09+7 -1.12E+7 1.31E+5 2.59E+6 Sr-91 9.56)S! --5.26E+4 7.34E+4 3.46E+0 S-2 " 3 --2.38E+4 1.40E+5 3.91 E- 1 Y-90 --2.69E+5 1.04E+5 8.82E+1 Y-91m .7F ---2.79E+3 2.35E+3 1.39E-2 Y-91 5. + ---2.45E+6 7.03E+4 1.57E+4 Y-92 1.64E+1 ---2.45E+4 1.27E+5 4.61E-1 Y-93 1.50E+2 ---7.64E+4 1.67E+5 4.07E+0 Zr-95 1.15E+5 2.79E+4 -3.11E+4 1.75E+6 2.17E+4 2.03E+4 Zr-97 1.50E+2 2.56E+1 -2.59E+1 1.10E+5 1.40E+5 1.17E+1 Nb-95 1.57E+4 6.43E+3 -4.72E+3 4.79E+5 1.27E+4 3.78E+3 Nb-97 3.42E-1 7.29E-2 -5.70E-2 3.32E+3 2.69E+4 2.63E-2 Mo-99 -1.65E+2 -2.65E+2 1.35E+5 4.87E+4 3.23E+1 Tc-99m 1.40E-3 2.88E-3 -3.11E-2 8.11E+2 2.03E+3 3.72E-2 Tc-101 6.51E-5 8.23E-5 -9.79E-4 5.84E+2 8.44E+2 8.12E-4 S 0 0 6 6 0 0 6 0 0 6 0 0 0D 0 0 0 0 0 0 0 0 0 0 0 0 6 6 0 0 6 6 6 0 6 6 6 2.0-24 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.7 (Page 2 of 2)R, Inhalation Pathway Dose Factors -INFANT (mrem/yr per lCi/m 3)ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.02E+3 --4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-105 1.22E+0 -8.99E-1 1.57E+4 4.84E+4 4.10E-1 Ru-106 8.68E+4 -1.07E+5 1.16E+7 1.64E+5 1.09E+4 Rh-103m Rh-106 ---Ag-110m 9.98E+3 7.22E+3 -1.09E+4 3.67E+6 3.3064-1 OOE+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -2.65E+6 5 +4 1JOE+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 -1A9E+4 Te-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+3 Te-127 2.23E+O 9.53E-1 1.85E+O 4.86E+O +4 4.89E-1 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 ^,UE+6 .90E+4 2.23E+3 Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-X1 3. + 2.63E+4 1.88E-2 Te-131m 1.07E+2 5.50E+1 8.93E+1 2.65C2 ."9r 1.19E+5 3.63E+1 Te-131 1.74E-2 8.22E-3' 1.58E-2 -2.)+3 8.22E+3 5.OOE-3 Te-132 3.72E+2 2.37E+2 2.79E+2 .0J,- 0E+5 4.41E+4 1.76E+2 1-130 6.36E+3 1.39E+4 1.60E+6 1.+ 1.99E+3 5.57E+3 1-131 3.79E+4 4.44E+4 1.4 5. -1.06E+3 1.96E+4 1-132 1.69E+3 3.54E+3 1.4+Y ,3 -1.90E+3 1.26E+3 1-133 1.32E+4 1.92E+4 .5ý 2.2-4E+4 -2.16E+3 5.60E+3 1-134 9.21E+2 1.88E+/ 2.09E+3 -1.29E+3 6.65E+2 1-135 3.86E+3 7.60.- "+N 6 8.47E+3 -1.83E+3 2.77E+3 Cs-134 3.96E+5 7 tL 1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 ."5" -5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5" ,.V 1+5 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-138 5.0.+2 1 4.1OE+2 6.54E+1 8.76E+2 3.98E+2 Ba-139 1.48E, 9. E-4 5.92E-4 5.95E+3 5.1OE+4 4.30E-2 Ba-140 E _,E+, E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ba-11 Lý 1.08E-4 -6.50E-5 2.97E+3 4.75E+3 4.97E-3 Ba-142 3. '98 3.30E-5 -1.90E-5 1.55E+3 6.93E+2 1.96E-3 La-140 5.+ý2 2.OOE+2 -1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+0 3.77E-1 -8.22E+3 5.95E+4 9.04E-2 Ce-141 2.77E+4 1.67E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-143 2.93E+2 1.93E+2 -5.64E+1 1.16E+5 4.97E+4 2.21 E+1 Ce-144 3.19E+6 1.21E+6 -5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 -1.97E+3 4.33E+5 3.72E+4 6.99E+2 Pr-144 4.79E-2 1.85E-2 -6.72E-3 1.61 E+3 4.28E+3 2.41 E-3 Nd-147 7.94E+3 8.13E+3 -3.15E+3 3.22E+5 3.12E+4 5.OOE+2 W-187 1.30E+1 9.02E+O 3.96E+4 3.56E+4 3.12E+0 Np-239 3.71E+2 3.32E+1 -6.62E+1 5.95E+4 2.49E+4 1.88E+1 2.0-25 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 Table 2.8 (Page 1 of 2)Ri Vegetation Pathway Dose Factors -ADULT (mrem/yr per gCi/m 3) for H-3 and C-14 (m 2 x mrem/yr gCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 P-32 11.40E+9 8.73E+7 ---11.58E+8 5.42E+7 Cr-51 -2.79E+4 1.03E+4 6.19E+4 1.17E+7 .4.66E+4 Mn-54 -3.11E+8 -9.27E+7 -9.54r .-- "4E+7 Mn-56 -1.61E+1 -2.04E+1 -5.12 E+0 Fe-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+7 Co-58 -3.09E+7 -, .2W8 6.92E+7 Co-60 -1.67E+8 --I 4+ .9+Ni-63 1.04E+10 7.21E+8 ---.50E+8 3.49E+8 Ni-65 6.15E+1 7.99E+0 -2.03E+2 3.65E+0 Cu-64 -9.27E+3 -2,34/, 7.90E+5 4.35E+3 Zn-65 3.17E+8 1.01E+9 -6.36E+8 4.56E+8 Zn-69 8.75E-6 1.67E-5 -- -2.51E-6 1.16E-6 Br-82 -- 1.73E+6 1.51E+6 Br-83 -4.63E+O 3.21 E+0 Br-84 --Br-85 -Rb-86 -2.1 4.32E+7 1.02E+8 Rb-88 -____Rb-89 <//Sr-89 9.96E+9+/-2<
--" 1.60E+9 2.86E+8 Sr-90 6.05R+11 ---1.75E+10 1.48E+11 Sr-91 3.20 ----1.52E+6 1.29E+4 Sr --8.46E+3 1.85E+1 Y-90 ---1.41 E+8 3.56E+2 Y-91 m "56-3 EA , -/- 1.71 E-8 -Y-91 5. 36 -- --2.82E+9 1.37E+5 Y-92 9.01E-1 -- -1.58E+4 2.63E-2 Y-93 1.74E+2 -- --5.52E+6 4.80E+O Zr-95 1.19E+6 3.81E+5 -5.97E+5 -1.21E+9 2.58E+5 Zr-97 3.33E+2 6.73E+1 -1.02E+2 -2.08E+7 3.08E+1 Nb-95 1.42E+5 7.91E+4 -7.81 E+4 -4.80E+8 4.25E+4 Nb-97 2.90E-6 7.34E-7 -8.56E-7 -2.71 E-3 2.68E-7 Mo-99 -6.25E+6 -1.41E+7 -1.45E+7 1.19E+6 Tc-99m 3.06E+0 8.66E+0 -1.32E+2 4.24E+0 5.12E+3 1.1OE+2 Tc-101 .- I. --0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 6 6 6 6 I 6 I I 2.0-26 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0!0 0 0O 0 0[0 0 0 Table 2.8 (Page 2 of 2)R, Vegetation Pathway Dose Factors -ADULT (mrem/yr per giCi/m 3) for H-3 and C-14 (M 2 x mrem/yr for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 4.80E+6 -1.83E+7 -5.61E+8 2.07E+6 Ru-105 5.39E+1 -6.96E+2 -3.30E+4 2.13E+1 Ru-106 1.93E+8 -3.72E+8 -1.25E+10 2.44E+7 Rh-103m Rh-106 -Ag-110m 1.06E+7 9.76E+6 -1.92E+7 -4k80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 219 W9 49 1 E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 1.05E+8, .,QE:I- Z5E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -3.W+8"ý 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -N 7E 4.26E+7 Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 -.5 1.25E+3 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9, -.2 E+9 4.03E+7 Te-129 6.65E-4 2.50E-4 5.10E-4 2.79E-, , .02E-4 1.62E-4 Te-131m 9.12E+5 4.46E+5 7.06E+5 4.5216 4.43E+7 3.72E+5 Te-131 -_-, -'_.Te-132 4.29E+6 2.77E+6 3.06E+6 .6 1.31E+8 2.60E+6 1-130 3.96E+5 1.17E+6 9.90E+7_ 2 + I 1.01E+6 4.61E+5 1-131 8.09E+7 1.16E+8 3.79,- 1. -4 3.05E+7 6.63E+7 1-132 5.74E+1 1.54E+2 5.3 +3) +2 -2.89E+1 5.38E+1 1-133 2.12E+6 3.69E+6 215:i2 6. 4E+6 -3.31E+6 1.12E+6 1-134 1.06E-4 2.88E/5./
-4.59E-4 -2.51E-7 1.03E-4 1-135 4.08E+4 1.07 .+ 4E 1.71E+5 -1.21E+5 3.94E+4 Cs-134 4.66E+9 ;m' -, \ -3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4.20E+7 ,jNH,8 -9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-138'17
... ... 6.3, 8- -2.95E+9 9.81E+8 1.68E+8 5.70E+9 Ba-139 , E-K, -1.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-1 4t; 1.62E+5 -5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ba-141 -I-L Ba-142 ----La-140 1.97E+3 9.92E+2 -7.28E+7 2.62E+2 La-142 1.40E-4 6.35E-5 --4.64E-1 1.58E-5 Ce-141 1.96E+5 1.33E+5 -6.17E+4 -5.08E+8 1.51E+4 Ce-143 1.00E+3 7.42E+5 -3.26E+2 -2.77E+7 8.21E+1 Ce-144 3.29E+7 1.38E+7 -8.16E+6 -1.11E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 -1.47E+4 -2.78E+8 3.14E+3 Pr-144 .....Nd-147 3.34E+4 3.86E+4 -2.25E+4 -1.85E+8 2.31 E+3 W-187 3.82E+4 3.19E+4 ---1.05E+7 1.12E+4 Np-239 1.42E+3 1.40E+2 -4.37E+2 -12.87E+7 7.72E+1 2.0-27 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.9 (Page 1 of 2)Ri Vegetation Pathway Dose Factors -TEEN (mrem/yr per gCi/m 3) for H-3 and C-14 (M 2 x mrem/yr i4Ci/sec) for others ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 P-32 1.61E+9 9.96E+7 -1.35E+8 6.23E+7 Cr-51 -3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 -4.52E+8 -1.35E+8 -9.27E, 2 ,97E+7 Mn-56 -1.45E+1 -1.83E+1 -9.54f2 8E+0 Fe-55 3.25E+8 2.31 E+8 --1.46E+8 9.*4k 5)18E+7 Fe-59 1.81E+8 4.22E+8 --1.33E+ .9 + , \ .63E+8 Co-57 -1.79E+7- -,+> 3.00E+7 Co-58 -4.38E+7 -" 1.01E+8 Co-60 -2.49E+8,_
-_._2_ 2 +9 5.60E+8 Ni-63 1.61E+10 1.13E+9 ---.81E+8 5.45E+8 Ni-65 5.73E+1 7.32E+0 --+ ,,/, /3.97E+2 3.33E+O Cu-64 -8.40E+3 -2.12 6.51 E+5 3.95E+3 Zn-65 4.24E+8 1.47E+9 -, +S, 6.23E+8 6.86E+8 Zn-69 8.19E-6 1.56E 2.88E-5 1.09E-6 Br-82 -1.33E+6 Br-839 1E 3.01 E+0 Br-84 7 _Br-85 29, -Rb-86 --.73E#414.05E+7 1.28E+8 Rb-88 --_0,/" Rb-89 -Sr-89 1.51E+210<-'-
1.80E+9 4.33E+8 Sr-90 7.511E+11 1.85E+1 1 Sr-91 2.991E6 4 1.36E+6 1.19E+4 Sr-92 3.,M9+2 E 1.01E+4 1.69E+1 Y-90 1.924E+4\
12 ---1.0E+8 3.34E+2 Y-91 m , ...2.56E-7 -Y-91 3.23E+9 2.11 E+/-5 Y-92 8.47E-1 6.6 2.32E+4 2.45E-2 Y-93 1.63E+2 ...4.98E+6 4.47E+0 Zr-95 1.74E+6 5.49E+5 -8.07E+5 -1.27E+9 3.78E+5 Zr-97 3.09E+2 6.11E+1 -9.26E+1 -1.65E+7 2.81E+1 Nb-95 1.92E+5 1.06E+5 -1.03E+5 -4.55E+8 5.86E+4 Nb-97 2.69E-6 6.67E-7 7.80E-7 -1.59E-2 2.44E-7 Mo-99 -5.74E+6 -1.31E+7 -1.03E+7 1.09E+6 Tc-99m 2.70E+0 7.54E+0 -1.12E+2 4.19E+0 4.95E+3 9.77E+1 Tc-101 -...... -0 0 0 0 0 0 0 0 0 0 6 S 6 S 6 6 6 6 0 6I 6I 6I 6I SI 0I SI SI SI 2.0-28 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0[.I KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.9 (Page 2 of 2)Ri Vegetation Pathway Dose Factors -TEEN (mren/v ,~ i~/ for H-3 and C-14 (i 2 x mrmm/vr Iu for nthers ODCM 2.0 Revision 15 June 6, 2013%. .......I re p rf... ................
"- ... 1 ..........
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 6.87E+6 -2.42E+7 -5.74E+8 2.94E+6 Ru-105 5.00E+1 -6.31E+2 -4.04E+4 1.94E+1 Ru-106 3.09E+8 -5.97E+8 -1.48E+10 3.90E+7 Rh-103m --Rh-106 ---Ag-110m 1.52E+7 1.44E+7 -2.74E+7 -4.04E 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 -1.35E+8 3.13j '%'03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 -1.88E+8 1.W+9 OOE+7 Te-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+7 Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4- .,,.... .19 1.17E+3 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 +9 5.81E+7 Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E 3.40E-3 1.51E-4 Te-1 31 m 8.44E+5 4.05E+5 6.09E+5 4.22V,12 3.25E+7 3.38E+55 Te-131 -_ __- I --< ,_ ",_-Te-132 3.90E+6 2.47E+6 2.60E+6 .. -7.82E+7 2.32E+6 1-130 3.54E+5 1.02E+6 8.35E+7 .7.87E+5 4.09E+5 1-131 7.70E+7 1.08E+8 3.14E+10 -2.13E+7 5.79E+7 1-132 5.18E+1 1.36E+2 4.5 -.4EK 5.91E+1 4.87E+1 1-133 1.97E+6 3.34E+6 E+ +6 2.53E+6 1.02E+6 1-134 9.59E-5 2.54E-4 ./X-2I-4 -3.35E-6 9.13E-5 1-135 3.68E+4 9.48E+Xl 1.50E+5 1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+-",6 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1,41,Et \ 9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-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-4 Ba-140 1.38&, 1.60E+5 -5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ba-141 "_ _....Ba-142 OE -La-140 8.84E+2 -5.08E+7 2.35E+2 La-142 1.e-4 5.69E-5 --1.73E+0 1.42E-5 Ce-141 2.82E+5 1.88E+5 -8.86E+4 -5.38E+8 2.16E+4 Ce-143 9.37E+2 6.82E+5 -3.06E+2 -2.05E+7 7.62E+1 Ce-144 5.27E+7 2.18E+7 -1.30E+7 1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 -1.65E+4 2.34E+8 3.55E+3 Pr-144 ...Nd-147 3.63E+4 3.94E+4 -2.32E+4 -1.42E+8 2.36E+3 W-187 3.55E+4 2.90E+4 --7.84E+6 1.02E+4 Np-239 1.38E+3 1.30E+2 -4.09E+2 12.1OE+7 7.24E+1 2.0-29 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.10 (Page 1 of 2)R 1 Vegetation Pathway Dose Factors -CHILD (mrem/yr per pCi/m 3) for H-3 and C-14 (m 2 x mrem/yr giCi/sec) for others ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 Na-24 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 P-32 3.37E+9 1.58E+8 ---9.30E+7 1.30E+8 Cr-51 --6.54E+4 1.79E+4 1.19E+5 6.25E+f--,,1.18E+5 Mn-54 -6.61E+8 -1.85E+8 -5.550,+6 -.,N6E+8 Mn-56 -1.90E+1 -2.29E+1 -2. 4 E+0 Fe-55 8.OOE+8 4.24E+8 --2.40E+8.6+
1,S1E+8 Fe-59 4.01E+8 6.49E+8 --1.88E+ +8-\ 9.23E+8 Co-57 -2.99E+7 --. E, 6.04E+7 o-58 -6 Co-60 -3.78E+8 --2-1OE+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 --.42E+8 1.34E+9 Ni-65 1.05E+2 9.89E+0 -I -1.21E+3 5.77E+0 Cu-64 -1.11E+4 -Z- -5.20E+5 6.69E+3 Zn-65 8.12E+8 2.16E+9 -.36 3.80E+8 1.35E+9 Zn-69 1.51E-5 2.18E-5 --5 -1.38E-3 2.02E-6 Br-82 ---,2.91 -+- 2.04E+6 Br-83 .9+ -< / =:,7-1 5.55E+0 Br-84 1 12 E Br-85 -,/> -Rb-86 4.5 9 E+ 2.78E+8 Rb-89 Sr-89 3.59E*101 1.39E+9 1.03E*9 Sr-90
-" 1.67E+10 3.15E+1 1 Sr-91 5.,5ijEW ) -1.21 E+6 2.08E+4 Sr-92 +2 1.38E+4 2.92E+1 Y-90 ----6.56E+7 6.17E+2 Y-91m 99E ---1.95E-5 -Y-91 1.8 .... 2.49E+9 5.01E+5 Y-92 1.56E+0 .... 4.51 E+4 4.46E-2 Y-93 3.01 E+2 .... 4.48E+6 8.25E+0 Zr-95 3.90E+6 8.58E+5 -1.23E+6 -8.95E+8 7.64E+5 Zr-97 5.64E+2 8.15E+1 -1.17E+2 -1.23E+7 4.81E+1 Nb-95 4.1OE+5 1.59E+5 -1.50E+5 -2.95E+8 1.14E+5 Nb-97 4.90E-6 8.85E-7 -9.82E-7 -2.73E-1 4.13E-7 Mo-99 -7.83E+6 -1.67E+7 -6.48E+6 1.94E+6 Tc-99m 4.65E+0 9.12E+0 -1.33E+2 4.63E+0 5.19E+3 1.51E+2 Tc-101 ......0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-30 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 Table 2.10 (Page 2 of 2)R1 Vegetation Pathway Dose Factors -CHILD (mrem/yr per g.Ci/m 3) for H-3 and C-14 (M 2 x mrem/yr jiCi/sec) for others 0 0 0 0 0 I.0 0 0 0 S 0 0 0 0 S 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.55E+7 -3.89E+7 -3.99E+8 5.94E+6 Ru-105 9.17E+1 -8.06E+2 -5.98E+4 3.33E+1 Ru-106 7.45E+8 -1.01E+9 -1.16E+10 9.30E+7 Rh-103m -Rh-106 -Ag-110m 3.22E+7 2.17E+7 4.05E+7 -2.58 ,1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 -1.96E+8 2.0+9 23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 -2.78E+8 1 .05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 -3. +VV 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 X-07TE " 1.57E+8 Te-127 1.00E+4 2.70E+3 6.93E+3 2.85E+4 -2.15E+3 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 0"1.'E+9 1.33E+8 Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E--,3
.1 7E-2 2.74E-4 Te-131m 1.54E+6 5.33E+5 1.1OE+6 5.1W6 2.16E+7 5.68E+5 Te-131 --_ __ ________ _-___-Te-132 6.98E+6 3.09E+6 4.50E+6/-E
-3.11_E+7 3.73E+6 1-130 6.21E+5 1.26E+6 1.38E+8 -5.87E+5 6.47E+5 1-131 1.43E+8 1.44E+8 4.7r" .361.28E+7 8.18E+7 1-132 9.20E+1 1.69E+2 7 +, 2W+2 -1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 M 5 ZlOE+6 -1.79E+6 1.68E+6 1-134 1.70E-4 3.16E-4/ 7.- 4.84E-4 -2.1OE-4 1.46E-4 1-135 6.54E+4 1.18E-6 /0,4 +- 1.81E+5 -8.98E+4 5.57E+4 Cs-134 1.60E+10 2,=tX- 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 4. 1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+1 10 -7.46E+9 2.68E+9 1.43E+8 3.38E+9 Cs-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+7 Ba- 141 (-/-Ba- ..La-140 3 1.13E+3 --3.15E+7 3.81E+2 La-142 2.32E-4 7.40E-5 --1.47E+1 2.32E-5 Ce-141 6.35E+5 3.26E+5 -1.43E+5 -4.07E+8 4.84E+4 Ce-143 1.73E+3 9.36E+5 -3.93E+2 -1.37E+7 1.36E+2 Ce-144 1.27E+8 3.98E+7 -2.21E+7 -1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 -2.41E+4 -1.60E+8 7.37E+3 Pr-144 ..... --Nd-147 7.16E+4 5.80E+4 -3.18E+4 -9.18E+7 4.49E+3 W-187 6.47E+4 3.83E+4 -- 1-5.38E+6 1.72E+4 Np-239 2.55E+3 1.83E+2 -5.30E+2 1- 1.36E+7 1.29E+2 2.0-31 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.11 (Page 1 of 2)R, Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per pCi/m 3) for H-3 and C-14 (M 2 x mrem/yr gCi/sec) for others ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 --1.92E+9 6.60E+8 Cr-51 --1.71E+4 6.30E+3 3.80E+4 7.20E++++2.86E+4 Mn-54 -8.40E+6 -2.50E+6 -2.5 T '.0OE+6 Mn-56 -4.23E-3 -5.38E-3 -7.'OE-4 Fe-55 2.51 E+7 1.73E+7 -9.67E+6 / .95 .4E+6 Fe-59 2.98E+7 7.OOE+7 -1.95E4< 2,,lE+.k s.68E+7 Co-57 -1.28E+6 -! -.5 2.13E+6 Co-58 -4.72E+6 , 1.06E+7 Co-60 -1.64E+7 -- -.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 -.-+9.73E+7 2.26E+8 Ni-65 3.70E-1 4.81E-2 -1.22E+0 2.19E-2 Cu-64 -2.41E+4 --8V', 2.05E+6 1.13E+4 Zn-65 1.37E+9 4.36E+9 -.9_2.75E+9 1.97E+9 Zn-69 -_____ _____Br-82 ---, -3.72E+7 3.25E+7 Br-83 .-1.49E-1' 1.03E-1 Br-84 --/"/Rb-86 -2.59 + 5.11E+8 1.21E+9 Rb-88 -Rb-89 Sr-89 1.45E+9 --2.33E+8 4.16E+7 Sr-90 4.68 +10 1.35E+9 1.15E+10 Sr-91 3.13 -, --1.49E+5 1.27E+3 Sr --9.68E+0 2.11E-2 Y --7.50E+5 1.90E+0 Y-91m ,/ -Y-91 8. 3 --4.73E+6 2.30E+2 Y-92 5.42E-5 --9.49E-1 1.58E-6 Y-93 2.33E-1 ---7.39E+3 6.43E-3 Zr-95 9.46E+2 3.03E+2 -4.76E+2 -9.62E+5 2.05E+2 Zr-97 4.26E-1 8.59E-2 -1.30E-1 -2.66E+4 3.93E-2 Nb-95 8.25E+4 4.59E+4 -4.54E+4 -2.79E+8 2.47E+4 Nb-97 -----5.47E-9 -Mo-99 -2.52E+7 -5.72E+7 -5.85E+7 4.80E+6 Tc-99m 3.25E+0 9.19E+0 -1.40E+2 4.50E+0 5.44E+3 1.17E+2 Tc-101 -------0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0I 0 0I 0I 01 2.0-32 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0;0 0 S i 0 0 0 0 0 0 Table 2.11 (Page 2 of 2)R, Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per giCi/m 3) for H-3 and C-14 (M 2 x mrem/yr p.Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.02E+3 --3.89E+3 -1.19E+5 4.39E+2 Ru-105 8.57E-4 --1.11E-2 -5.24E-1 3.38E-4 Ru-106 2.04E+4 --3.94E+4 -1.32E+6 2.58E+3 Rh-103m ---Rh-106 --,,-.,,--Ag-110m 5.83E+7 5.39E+7 -1.06E+8 2.20,,1" 20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 -2.OOE+7 7,31,8 t.)2E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 -1.58E+7 , 5E 6E6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -<6.% +7N, P2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 Y64 5.58E+6 Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 -+4 1.45E+2 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8,,--X04F+8 9.57E+6 Te-129 -,--,___Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79, 1.75E+7 1.47E+5 Te-131 -_,,-,,_ __.4__ ___,,_Te-132 2.39E+6 1.55E+6 1.71E+6 .4 -7.32E+7 1.45E+6 1-130 4.26E+5 1.26E+6 1.07E+8 0+ -1.08E+6 4.96E+5 1-131 2.96E+8 4.24E+8 1.390,,1 7. 1.12E+8 2.43E+8 1-132 1.64E-1 4.37E-1 1.51+ 8.22E-2 1.53E-1 1-133 3.97E+6 6.90E+6 , 1 .OE+7 6.20E+6 2.1OE+6 1-134 --_______1-135 1.39E+4 3.63E+ 4_ ýý0E 5.83E+4 -4.1OE+4 1.34E+4 Cs-134 5.65E+9 1. 343-TA4 4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 + -5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 .3.43E+9 1.14E+9 1.95E+8 6.61E+9 Cs-1 38!)+ -- -Ba-139 4.- -8.34E-8 1.38E-9 Ba-140 +t .4 1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-141 _ -, ...Ba-142 .... --La-140 4. 0 2.26E+0 --1.66E+5 5.97E-1 La-142 --3.03E-8 -Ce-141 4.84E+3 3.27E+3 1.52E+3 -1.25E+7 3.71E+2 Ce-143 4.19E+1 3.09E+4 1.36E+1 -1.166E+6 3.42E+0 Ce-144 3.58E+5 1.50E+5 -8.87E+4 -1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 3.68E+1 -_6.96E+5 7.88E+0 Pr-144 -....Nd-147 9.42E+1 1.09E+2 6.37E+1 5.23E+5 6.52E+0 W-187 6.56E+3 5.48E+3 --1.80E+6 1.92E+3 Np-239 3.66E+0 3.60E-1 -1.12E+0 -7.39E+4 1.98E-1 2.0-33 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.12 (Page 1 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -TEEN (mrem/yr per gCi/m 3) for H-3 and C-14 (m 2 x mrem/yr laCi/sec) for others ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 P-32 3.15E+10 1.95E+9 ---2.65E+9 1.22E+9 Cr-51 -2.78E+4 1.1OE+4 7.13E+4 5.OOE+4 Mn-54 -1.40E+7 -4.17E+6 -2.87,2ý1ý
,.8E+6 Mn-56 -7.51 E-3 -9.50E-3 -4,W1 1 VE-3 Fe-55 4.45E+7 3.16E+7 -2.OOE+7 Y.37-E 6E+6 Fe-59 5.20E+7 1.21E+8 --3.82E+ 2.,+8\ 4.68E+7 Co-57 -2.25E+6 ---9W 3.76E+Co-58 -7.95E+6 -8 1.83E+7 Co-60 -2.78E+7 -.6 E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 -, 1.33E+8 4.01E+8 Ni-65 6.78E-1 8.66E-2 -4.70E+0 3.94E-2 Cu-64 -4.29E+4 -1 + -3.33E+6 12.02E+4 Zn-65 2.11E+9 7.31E+9 -.68 1 OE+9 3.41E+9 Zn-69 ---Br-82 ---5.64E+-r8 --< 1.91E-1 Rb-86 -4.73__- -7.OOE+8 2.22E+9 Rb-88 -_ /,',,-/..Sr-89 2.67E+9 -" -3.18E+8 7.66E+7 Sr-90 6.61F__ 10- ---1.86E+9 1.63E+10 Sr-91 5.75E- --2.61 E+5 2.29E+3 Sr-92 8, -- -2.28E+1 3.81 E-2 Y-90 -1.07E+6 3.50E+0 Y-91m M Y-91 --6.48E+6 4.24E+2 Y-92 1.OOE-4 .... 2.75E+0 2.90E-6 Y-93 4.30E-1 ----1.31E+4 1.18E-2 Zr-95 1.65E+3 5.22E+2 -7.67E+2 -1.20E+6 3.59E+2 Zr-97 7.75E-1 1.53E-1 -2.32E-1 -4.15E+4 7.06E-2 Nb-95 1.41 E+5 7.80E+4 -7.57E+4 -3.34E+8 4.30E+4 Nb-97 -6.34E-8 -Mo-99 -4.56E+7 -1.04E+8 -8.16E+7 8.69E+6 Tc-99m 5.64E+0 1.57E+1 -2.34E+2 8.73E+0 1.03E+4 2.04E+2 Tc-101 -I- I- ---0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 S S 0 0 0 0 6 0 0 6 6 0 0 0 0 0 0 0 0 I I 2.0-34 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table 2.12 (Page 2 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -TEEN (mrem/yr per gICi/m 3) for H-3 and C-14 (M 2 x mrem/yr giCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.81E+3 -6.40E+3 -1.52E+5 7.75E+2 Ru-105 1.57E-3 -1.97E-2 -1.26E+0 6.08E-4 Ru-106 3.75E+4 -7.23E+4 -1.80E+6 4.73E+3 Rh-103m --Rh-106 -...Ag-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+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 -3.21E+7/ ..84Li, .54E+6 Te-125m 3.OOE+7 1.08E+7 8.39E+6 -40E+'ý," 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -.10 1.OOE+7 Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 _ _+4 2.68E+2 Te-129m 1.11E+8 4.1OE+7 3.57E+7 4.62E+O,'
4.i5E+8 1.75E+7 Te-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+5 Te-131 -W --,___,, Te-132 4.28E+6 2.71 E+6 2.86E+6 6 + 8.58E+7 2.55E+6 1-130 7.49E+5 2.17E+6 1.77E+8 \ý -1.67E+6 8.66E+5 1-131 5.38E+8 7.53E+8 2."1 .+E9 -1.49E+8 4.04E+8 1-132 2.90E-1 7.59E-1 E E+. 9- 3.31E-1 2.72E-1 1-133 7.24E+6 1.23E+7 -.9 15E+7 9.30E+6 3.75E+6 1-134 -/,/ -_ N__ -I-1-135 2.47E+4 6.35 +
- 1.O0E+5 7.03E+4 2.35E+4 Cs-134 9.81E+9 0 7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 t.7 5 F_ -9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+1 1 .+10 -6.06E+9 2.35E+9 2.53E+8 6.20E+9 CS-1 38 -\,:>Ba-1 39 8.69eh ---7.75E-7 2.53E-9 Ba-140 -+ E+4 2.02E+4 4.OOE+4 7.49E+7 3.13E+6 Ba-141 _ _ _ _ _ __._ _ __-Ba-142 La-140 .0 3.96E+0 -- 2.27E+5 1.05E+0 La-142 ---2.23E-7 -Ce-141 8.87E+3 5.92E+3 -2.79E+3 -1.69E+7 6.81E+2 Ce-143 7.69E+1 5.60E+4 -2.51 E+I -1.68E+6 6.25E+0 Ce-144 6.58E+5 2.72E+5 -1.63E+5 -1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -6.77E+1 -9.61E+5 1.45E+1 Pr-144 -----Nd-147 1.81E+2 1.97E+2 1.16E+2 -7.11E+5 1.18E+1 W-187 1.20E+4 9.78E+3 --2.65E+6 3.43E+3 Np-239 6.99E+0 6.59E-1 -2.07E+0 1.06E+5 3.66E-1 2.0-35 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.13 (Page 1 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per RiCi/m 3) for H-3 and C-14 (M 2 x mrem/yr giCi/sec) for others ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 P-32 7.77E+10 3.64E+9 -2.15E+9 3.OOE+9 Cr-51 --5.66E+4 1.55E+4 1.03E+5 5.41E+, 1.02E+5 Mn-54 -2.09E+7 -5.87E+6 -1.7%+ý , 8E+6 Mn-56 -1.31 E-2 -1.58E-2 -,1 9 0 2WE-3 Fe-55 1.12E+8 5.93E+7 -3.35E+7 ,.10_ X,94E*7 Fe-59 1.20E+8 1.95E+8 -5.65E+i 2. +8\ .71E+7 Co-57 -3.84E+6 -5,,j- 4 7.77E+6 Co-58 -1.21E+7 --,, ,, 7 3.72E+7 Co-60 -4.32E+7 -,.E+8 I1.27E+8 Ni-63 2.96E+10 1.59E+9 --1.07E+8 1.01E+9 Ni-65 1.66E+0 1.56E-1 -1.91E+1 9.11E-2 Cu-64 -7.55E+4 -I + -3.54E+6 4.56E+4 Zn-65 4.13E+9 1.10E+10 -.94' 1.93E+9 6.85E+9 Zn-69 --)2.14E-9 Br-82 ---__,,_) __._. _-_ _/,_' 1.15E+8 Br-,3 -4.69E-1 Br-84 -- ,/ \<Br-85 --Rb-86 -8.77_E+_5.64E+8 5.39E+9 Rb-88 _ -/_Sr-89 6.62E+9 -\-2.56E+8 1.89E+8 Sr-90 1.12F_ 11 --,1.51E+9 2.83E+10 Sr-91 1.41 ---3.12E+5 5.33E+3 Sr-92 4.14E+1 8.76E-2 Y-90-- ---9.15E+5 8.61E+0 Y-91 m Y-91 3. 4 5.21E+6 1.04E+3 Y-92 2.46E-4 -7.1OE+0 7.03E-6 Y-93 1.06E+0 -1.57E+4 2.90E-2 Zr-95 3.84E+3 8.45E+2 -1.21 E+3 -8.81 E+5 7.52E+2 Zr-97 1.89E+O 2.72E-1 -3.91E-1 -4.13E+4 1.61E-1 Nb-95 3.18E+5 1.24E+5 -1.16E+5 -2.29E+8 8.84E+4 Nb-97 ---1.45E-6 -Mo-99 -8.29E+7 -1.77E+8 -6.86E+7 2.05E+7 Tc-99m 1.29E+1 2.54E+1 -3.68E+2 1.29E+1 1.44E+4 4.20E+2 Tc-101 ------0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S S S S S S S S S 6 6 6 2.0-36 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 S 0 0 S S 0 0 0 S 0 S 0 0 S 0 0 0 0 0 0 0 Table 2.13 (Page 2 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per glCi/m 3) for H-3 and C-14 (mi x mrem/yr iiCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 4.29E+3 --1.08E+4 -1.11E+5 1.65E+3 Ru-105 3.82E-3 --3.36E-2 -2.49E+0 1.39E-3 Ru-106 9.24E+4 --1.25E+5 -1.44E+6 1.15E+4 Rh-103m ---Rh-106 -1 "--"__ _-Ag-110m 2.09E+8 1.41E+8 -2.63E+8 -1.9+ 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 -6.03E+7 6M+8 11.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 -4.85E+ 62.0"/ .82E+7 Te-125m 7.38E+7 2.OOE+7 2.07E+7 -- << ,2E+'V 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -- .6 8 2.47E+7 Te-127 3.06E+3 8.25E+2 2.12E+3 8.71E+3 +5 6.56E+2 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+ 3."32E+8 4.23E+7 Te-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+5 Te- 131r Te-132 1.02E+7 4.52E+6 6.58E+64 -4.55E+7 5.46E+6 1-130 1.75E+6 3.54E+6 3.90E+8 -'ýfý2 1.66E+6 1.82E+6 1-131 1.30E+9 1.31E+9 4. -1.17E+8 7.46E+8 1-132 6.86E-1 1.26E+0 EJ-- 4.Z"E+0 1.48E+0 5.80E-1 1-133 1.76E+7 2.18E+7 .9 .63E+7 8.77E+6 8.23E+6 1-134 --5//5 /.+NN -" 135 5.84E+4 1.05 + \ .30j-6 1.61E+5 8.OOE+4 4.97E+4 Cs-134 2.26E+10 3" 0 1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs-136 1.OOE+9 .6 v 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10<. ,jlb+10 -1.01E+10 3.62E+9 1.93E+8 4.55E+9 Cs-1 38 ,),_.Ba-139 2.14N ---1.23E-5 6.19E-9 Ba-140 +, E+5 -3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ba-141 ___.. __-_ _-_-Ba-142---La-140 1. 1- 6.74E+0 -1.88E+5 2.27E+0 La-142 ---2.51E-6 -Ce-141 2.19E+4 1.09E+4 -4.78E+3 -1.36E+7 1.62E+3 Ce-143 1.89E+2 1.02E+5 -4.29E+1 -1.50E+6 1.48E+1 Ce-144 1.62E+6 5.09E+5 -2.82E+5 -1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 -1.17E+2 -7.80E+5 3.59E+1 Pr.-144 --Nd-147 4.45E+2 3.60E+2 -1.98E+2 -5.71E+5 2.79E+1 W-187 2.91E+4 1.72E+4 -2.42E+6 7.73E+3 Np-239 1.72E+1 1.23E+0 -3.57E+0 -9.14E+4 8.68E-1 2.0-37 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.14 (Page 1 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -INFANT (mrem/yr per ,iCi/m 3) for H-3 and C-14 (m 2 x mrem/yr giCi/sec) for others ODCM 2.0 Revision 15 June 6, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 Na-24 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 P-32 1.60E+11 9.42E+9 --2.17E+9 6.21E+9 Cr-51 -1.05E+5 2.30E+4 2.05E+5 4.71E+-,--
1.61E+5 Mn-54 -3.89E+7 -8.63E+6 -1.4 7 83E+6 Mn-56 -3.21E-2 -2.76E-2 -0 !3E3 Fe-55 1.35E+8 8.72E+7 4.27 E*7 ,.11K, 3E+7 Fe-59 2.25E+8 3.93E+8 1.16E+&I<r 1,8t+ 81.55E+8 Co-57 -8.95E+6 -,,,-, 5 1.46E+7 Co-58 2.43E+7 +7 -6.06E+7 Co-60 -8.81 E+7 E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 -1.07E+8 1.21E+9 Ni-65 3.51E+0 3.97E-1 --3.02E+1 1.81E-1 Cu-64 -1.88E+5 -3.85E+6 8.69E+4 Zn-65 5.55E+9 1.90E+10 -.23 1.61E+10 8.78E+9 Zn-69 -- 7.36E-9 Br-82 -_/__ -1.94E+8 Br-83 <<
Br-84//. , Br-85 -,, Rb-86 -2.22 1,+A , 5.69E+8 1.10E+10 Rb-88_ --, /Rb-89 -_, / _Sr-89 1.26E+107
-2.59E+8 3.61E+8 Sr-90 1.22-.11 -1.52E+9 3.10E+10 Sr-91 2.94Eft -3.48E+5 1.06E+4 Sr-92 r,85L _. ,, 5.01E+1 1.73E-1 Y-90 9.39E+5 1.82E+1 Y-9lm Y-91 7.3_-_ 5.26E+6 1.95E+3 Y-92 5.22E-4 9.97E+0 1.47E-5 Y-93 2.25E+0 -1.78E+4 6.13E-2 Zr-95 6.83E+3 1.66E+3 1.79E+3 -8.28E+5 1.18E+3 Zr-97 3.99E+0 6.85E-1 6.91E-1 -4.37E+4 3.13E-1 Nb-95 5.93E+5 2.44E+5 1.75E+5 -2.06E+8 1.41E+5 Nb-97 -3.70E-6 -Mo-99 -2.12E+8 3.17E+8 6.98E+7 4.13E+7 Tc-99m 2.69E+1 5.55E+1 5.97E+2 2.90E+1 1.61E+4 7.15E+2 Tc-101 S 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 6 0 0 2.0-38 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 S 0 S 0 S 0 0 0 0 0 0 0 0 0 S 0 Table 2.14 (Page 2 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -INFANT (mrem/yr per igCi/m 3) for H-3 and C-14 (mi x mrem/yr gCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung I-LLI T.Body Ru-103 8.69E+3 --1.81E+4 -1.06E+5 2.91E+3 Ru-105 8.06E-3 --5.92E-2 -3.21E+0 2.71E-3 Ru-106 1.90E+5 --2.25E+5 -1.44E+6 2.38E+4 Rh-103m --- -Rh-106 ......Ag-110m 3.86E+8 2.82E+8 4.03E+8 -1 1_ I +N 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 -1.31E+8 ,6.4kE+8 '.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 -9.38E+,, /'1..9" 8,,- /.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 -_- 8E, 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 1.7,8 5.1OE+7 Te-127 6.50E+3 2.18E+3 5.29E+3 1.59E+4 , -.E+5 1.40E+3 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 S334E+8 8.62E+7 Te-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+6 Te-131 -Te-132 2.1OE+7 1.04E+7 1.54E+7 _.____E-_
3.85E+7 9.72E+6 1-130 3.60E+6 7.92E+6 8.88E+8 3 -1.70E+6 3.18E+6 1-131 2.72E+9 3.21E+9 1.0 3 1.15E+8 1.41E+9 1-132 1.42E+O 2.89E+0 .+0 -2.34E+0 1.03E+O 1-133 3.72E+7 5.41E+7 .8 .6E+7 -9.16E+6 1.58E+7 1-134 --1-135 1.21E+5 2.41 + .16 2.69E+5 8.74E+4 8.80E+4 Cs-134 3.65E+10 6. 1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5 E -Y"/ 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+1 01_O 10 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Cs-1 38 -I-Ba-139 4.55 2.88E-5 1.32E-8 B~a-140 + .E+5 -5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ba-142 La-140 1.59E+1 --1.87E+5 4.09E+0 La-142 ...5.21 E-6 -Ce-141 4.33E+4 2.64E+4 -8.15E+3 -1.37E+7 3.11E+3 Ce-143 4.OOE+2 2.65E+5 -7.72E+1 -1.55E+6 3.02E+1 Ce-144 2.33E+6 9.52E+5 -3.85E+5 -1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 -2.08E+2 -7.89E+5 7.41E+1 Pr-144 ..Nd-147 8.82E+2 9.06E+2 -3.49E+2 -5.74E+5 5.55E+1 W-187 6.12E+4 4.26E+4 --2.50E+6 1.47E+4 Np-239 3.64E+1 3.25E+0 -6.49E+0 -9.40E+4 1.84E+0 2.0-39 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.15 (Page 1 of 2)R, Ground Plane Pathway Dose Factors (M 2 x mrem/yr per pCi/sec)ODCM 2.0 Revision 15 June 6, 2013 Nuclide Any Organ H-3 C-14 Na-24 1.21E+7 P-32 Cr-51 4.68E+6 Mn-54 1.34E+9 Mn-56 9.05E+5 Fe-55 Fe-59 2.75E+8 Co-57 4.37E+8 Co-58 3.82E+8 Co-60 2.16E+1 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-82 4. [Br-83 +Br-84 2 +E+5>8.98E+6 Rb,88 3.29E+4 ,8 1.21 E+5 Sr-8\' .2.16E+4 2.19E+67.77E+54.48E+3* 1.01E+5 Akg1 1.08E+6 Y-92 1.80E+5 Y-93 1.85E+5 Zr-95 2.48E+8 Zr-97 2.94E+6 Nb-95 1.36E+8 Nb-97 2.28E+6 Mo-99 4.05E+6 Tc-99m 1.83E+5 Tc-101 2.04E+4 Ru-103 1.09E+8 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 0 S 6 6 6 6 6 6 6 6 2.0-40 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.15 (Page 2 of 2)Ri Ground Plane Pathway Dose Factors (M 2 x mrem/yr per liCi/sec)ODCM 2.0 Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Any Organ Ru-105 6.36E+5 Ru-106 4.21E+8 Rh-103m Rh-106 Ag-110m 3.47E+9 Sb-124 2.87E+9 Sb-125 6.49E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-127 3.00E+3 Te-129m 2.00E+7 Te-129 2.60E+4 Te-131 m Te- 131 Te-132 1-130 1-131 Y 1-132 1-133 < <6 1-134 .9E+5 1-135 \\,2.56E+6 Cs-134 / 6.75E+9 Cs-136 -1.49E+8 C1.04E+10 Cs19= 3.59E+5 R_-_13_X__1.06E+5
_.e'kX4 2.05E+74. 18E+4 La4O 1.91 E+7"Ld-142 7.36E+5 Ce-141 1.36E+7 Ce-143 2.32E+6 Ce-144 6.95E+7 Pr-143 Pr-144 1.83E+3 Nd-147 8.40E+6 W-187 2.36E+6 Np-239 1.71_E+6 2.0-41 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 15 June 6, 2013 APPENDIX A TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -LIQUID RADIOACTIVE EFFLUENTS 6 6 0 S 0 0 0 0 0 S 0 S S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S 0 S A-1 KEWAUNEE POWER STATION ODCM App-A* OFFSITE DOSE CALCULATION MANUAL Revision 15 O June 6, 2013 0 Technical Basis for Effective Dose Factors -Liquid Effluent Releases To verify that the current approach to determining environmental doses using a simplified method has remained consistent since the previous analysis (performed using effluent data from 1981-1983), a similar evaluation was performed using the liquid effluent release data from* 2000-2002.
From the effluent data, the dose contribution of the radionuclide mixture can be O obtained to provide a simplified method of determining compliance with the dose limits of ODCM Normal Condition 13.1.2. For the radionuclide distribution of nts from the Kewaunee 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 a function of the Cs-134 and Fe-55 releases.
The radionuclides, Fe- Sr-90, and Cs-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 of Table A-I were calculated using the total curies released batch d ontinuous releases as reported in the Annual Radioactive Effluent Release R >r gh o by the appropriate dose factors.* Tritium is not included in the limited analysis e ss, for liquid releases, because the potential dose resulting from normal facility s negligible.
From 2000-2002, the maximum 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 is essentially unrelated to radwaste se op tion.*For purposes of simpli o of the dose calculational process, it is conservative to identify a controlling, d cant radionuclide and limit the calculational process to the use O 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 the O maximum organ dose. Only the reactor-generated radionuclide Nb-95 has a higher dose conversion factor (1.51E+06 mrem/hr per g.tCi/ml, GI-LLI). However, since Nb-95 releases are typically less than 5% of the total releases, it is conservative to use the Cs-134 factor. By this approach, the maximum organ dose will be routinely overestimated.
For 2000, using this* simplified conservative method (CW value of 2.OOE+05 gpm) would overestimate the maximum organ dose as reported in the Annual Radioactive Effluent Release Report by a factor of 234; for O 2001, the conservatism is a factor of 109; and for 2002, a factor of 730. This comparison is O shown in Table A-2.0 A-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 15 June 6, 2013 For 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 this simplified conservative dose calculational method would overestimate the total body dose by a factor of 253; for 2001, the conservatism is a factor of 105; and for 2002, a factor of 601.For evaluating compliance with the dose limits of ODCM Normal Condition 13.1.2 the following simplified equations may be used: Total Body where: Dtb Acs- 134,TB VOL CW 1.67E-02 I1.67E -02 x VOL Dtb = X Acs -134, TB X Ci= dose to the total body (mrem) K= 5.79E+05, total body ingestion dose co)rsZin RCi/ml) ,,* 1)(mrem/hr per 0 0 0 0 0 S 0 0 0 0 S 0 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I 6= total concentration of all= average circulating d616,Ci/ml) rate during release period (gal/min)lose conversion factor, the equation simplifies conversion Substituting the value to: (A.2)CW 1.67E -02 x VOL x Ac, -134. L X EC CW= maximum organ dose (mrem)(A.3)where: Dmax Acs-134,L
= 7.09E+05, liver ingestion dose conversion factor for Cs-134 (m~rem/hr per tCi/ml)A-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 15 June 6, 2013 Substituting 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 more limiting dose (compared with the maximum organ dose) for demonstrating compliance with ODCM Normal Condition 13.1.2.A-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 15 June 6, 2013 Table A-1 Adult Dose Contributions 2000___ Fish and Drinking Water Pathways__________
2000 _________
2001 2002 Radio- Release TB GI-LLI Liver Release TB GI-LLI Liver R e TB GI-LLI Liver nuclide (CG) Dose Dose Dose (Ci) Dose Dose Do Dose Dose Dose Frac. 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>____ 02 Co-58 8.07E- 0.01 0.03 *4.09E- 0.01 4.94E- 0.05 0.02 0.02 03 03 !/5 03 Fe-59 2.77E- 2.44E- 0.01 0.02 04 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 0.03 0___03 0.02 0.04 00103 Br-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- 0.91 04 _&404 Cs-137 3.70E- 0.75 0 2.74E- 0.68 0.01 0.85 3.04E- 0.05 0.08 104 04 0.68 0.01 0.85 06* Less than 0.01 N/D = not detected A-5 0090*....e..eee0eeee0eoo..e..e.....@.oee00e0e KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 15 June 6, 2013 0 0 S 0 S 0 0 0!0 0 I ,0 Table A-2 Adult Liver and Total Body Dose Assessment Dose Via the Simplified Method Versus the Actual Calculated Dose 2000 2001 2000 2001 I 4 Simplified Liver Dose (mRem)* I. 16E+00 9.87E-0 I Simplified Liver Dose (mRem)*1. 16E+00 9.87E-01 Actual Liver Dose (mRem)**4.97E-03 9.02E-03 Simplified divided by Actual 234 109 Simplified 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 STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 15 June 6, 2013 0 0 0 0 0 0 APPENDIX B TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -GASEOUS RADIOACTIVE EFFLUENTS 0, 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 0 6 0 0 0 B-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 15 June 6, 2013 APPENDIX B Technical Basis for Effective Dose Factors -Gaseous Radioactive Effluents Overview 0 0 0 0 0 0 0 SO 0:0 re The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose ctors, which are radionuclide 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 dose in the environment (i.e., instead of having to perform individual radi lid s alyses only a 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 while eliminating the need for a detailed calculational technique.
Determination of Effective Dose Factors~~tions Effective 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 gases released e de gmaeisosfo l ol ae= the total radionucl or due to gamma emissions from each noble gas of noble gas radionuclide "i" relative to the total noble f.(L + 1.1 M)eff = Z [(Li + 1.1 Ml )x fi](B.2)where: (L + 1.1 M)eff =(Li + 1.1 M 1) =the effective skin dose factor due to beta and gamma emissions from all noble gases released the skin dose factor due to beta and gamma emissions from each noble gas radionuclide "i" released Meff= I (IvL.xfi)(13.3)B-2 0 0 KEWAUNEE POWER STATION ODCM App-B 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 where: 0 Meff = the effective air dose factor due to gamma emissions from all noble gases released Mi the air dose factor due to gamma emissions from each noble gas radionuclide "i" released Neff =E (Nixfi) (B.4)where: Neff the effective air dose factor due to beta emissions from a o gase eleased Ni the air dose factor due to beta emissions from eac g9 adionuclide "i" released " "s r Normally, it would be expected that past radioactive fi d would be used for the determination of the effective dose factors. Howev en b s releases from Kewaunee have been maintained to such negligible quantities tha he t variability in the data makes any meaningful evaluations difficult.
For the y 2 1 and 2002, the total noble gas releases have been limited to 2.54E-04 Ci for Ci for 2001, and 1.91E-02 Ci for 2002. Therefore, in order to provide a re le 's r the derivation of the effective noble gas dose factors, the primary coolant rce rm ANSI N237-1976/ANS-18.1, "Source Term Specifications," has been use s s a typical distribution.
The effective dose factors as derived are presented in le,-Application,0 To provide an addition e of conservatism, a factor of 0.50 is introduced into the dose calculational proces whe ' ctive dose transfer factor is used. This conservatism provides additional surance" tthe aluation of doses by the use of a single effective factor will not significantly stii , , actual doses in the environment.
For with the dose limits of ODCM Normal Condition 13.2.2, the following simpli i dequations may be used: 3.17E-08 DO -(B.5)0.50 0 DO = 3.1 7 E-08 xX/QxNeffx-Qi (B.6) 0 0.50 B-3 0 S S 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 15 June 6, 2013 where: 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/m 3)0 0 S 0 S 0 0 0 0 0 0 0 Meff = 5.3E+02, effective gamma-air dose factor (mrad/yr per Neff = 1. IE+03, effective beta-air dose factor (mrad/yr per g9 3.17E-08 =conversion factor (yr/sec)0.50= conservat Combining the constants ism factor to account for the (thfie effluent data the 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 the adio ive effluent releases, particularly during periods of computer ose assessment may be unavailable.
Dose assessments using the pendent calculation are performed at least annually for preparation of Reports. Comparisons can be performed at this time to assure that the factors does not substantially underestimate actual doses.The effective dose malfunction the Radioýuse of the B-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 15 June 6, 2013 Table B-1 Effective Dose Factors -Noble Gases Total Body Effective Skin Effective Dose Factor Dose Factor Ke1w (L+1.1 M)eff Radionuclide fi (mrem/yr per gCi/mr 3) (mrem/yr per gCi/mr 3)Noble Gases -Total Body and Skin Kr-85 0.01 -- 1.4E+01 Kr-88 0.01 1.5E+02 1.9E+02(ýXe-133m 0.01 2.5E+00 1.Xe-133 0.9 3.OE+02 +02 Xe-135 0.02 3.6E+O, /01Eb(TOTAL 4.8E+02 <9 02 Noble Gases -Air Gamma ti Beta Air Effective Dose Dose Factor Radionuclide fi ( / er i/m3) (mrad/yr per pCi/mr 3)Kr-85 2.OE+01 Kr-88 0.01 4ýý 2.9E+01 Xe-133m 0.0 .$ +00 1.5E+01 Xe-133 /
1.0E+03 Te-135 1..1) 3.8E+01 4.9E+01 TOTAL 15.3F-+02 1I.1E+03 S S S S S S S S S S q'4, S S S S S S S S S S S S S S S S S S S S S S S S S S S B-5 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-C Revision 15 June 6, 2013 0 0 0!0 0 0 0 0 0 0 0 0 S S S S S S S S S S'0 APPENDIX C EVALUATION OF CONSERVATIVE, DEFAULT EFFECTIVE EC VALUE FOR LIQUID EFFLUENTS C-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-C Revision 15 June 6, 2013 Appendix C Evaluation of Conservative, Default Effective EC Value for Liquid Effluents In accordance with the requirements of ODCM Normal Condition 13.3.1 the radioactive liquid effluent monitors shall be FUNCTIONAL with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed 10 times the value of 10 CFR 20, AP.4endix B, Table 2, Column 2 for all radionuclides other gases and a value 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.I In order to limit the need for routinely having to reestablish changing radionuclide distributions, a default alarm setpoif setpoint can be conservatively based on an evaluatio yI liquid effluents from Kewaunee and the ECe value for 16'6ts as a function of 6lished. This default lide distribution of the The effective EC value for a where: radionuclide distri on ulated by the equation: E-- (C.1)alue for a mixture of radionuclide (gCi/ml)of radionuclide "i" in the mixture 20, Appendix B, Table 2, Column 2 EC value for radionuclide "i" 6 0 S S 0 0 0 6 6 0 0 0 a 6D SD 6D 0D 0D 0D 0D 0D 0D 0D 0 0D 0D 0 0D 0D 0D 0I 0D 0 0 0I 0D 0I 6 S 0 0 EC, Ci ECQ-an Based on the above equation and the radionuclide distribution in the effluents for past years from Kewaunee, an ECe value can be determined.
Effluent release data from 2000-2002 was used to generate the results presented in Table C-1. The most limiting effective EC (for gamma emitting radionuclides) was for the calendar year 2001, with a calculated value of 5.98E-06 itCi/ml. For conservatism in establishing the alarm setpoints, a default effective EC value of 1.OE-06 gtCi/ml was 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 EC C-2 0 0* 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 the alarm setpoint for release rate evaluations.
Examining releases over the years 2000-2002, the average, diluted H-3 contribution to its limiting concentration (i.e., fraction of concentration
- limit -10 x EC) in liquid effluents was 0.004%. This contribution is not expected to change 0significantly over time, since the concentration of H-3 in effluents can be expected to remain fairly consistent in effluent releases regardless of fuel conditions, activation product releases, and waste processing.
Based on relative abundances, other non-gamma emitting radionucl Sr-89/90)contributed up to 30% of the concentration limit (30% for CY 2001 le to assume that the abundances of these non-gammas will remain the same reer fission and/or activation products under varying conditions.
Therefore, un I f elevated effluent radionuclide levels, the gamma-emitting radionuclides ed to be the main contributors 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 limiting conditions of the liquid effluent concentr o" -gamma-emitting radionuclides.
The factor of six (6) conservatism in the etermination (discussed above) provides*adequate consideration for the c gib from non-gamma emitting radionuclides, and provides 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 no installed radiation mon ing the default effective EC value of 1.OE-06 jiCi/ml for increased monitori is con ewith the ODCM methodology if an installed radiation monitor 0 was available.
0 0 0 0 0 0 0 0 0*0 0 0 KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Table C-1 Calculation of Effective EC (ECe)_ _ _ 2000 2001 __________
2002 Nuclide 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+00 Cr-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+00 Mn-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-04 Fe-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-01 Co-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+00 Co-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-01 Fe-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-03 Co-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-01 Br-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+00 Sr-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-02 Sr-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-02 Zr-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-03 Nb-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-03 Ag-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-01 Sn-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-03 Sb-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-03 Sb-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-02 1-132 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+00 1-133 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+00 1-135 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+00 Cs-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-03 Total 7.4Z 4. 03 1.00E+00 6.34E-02 3.42E+03 1.00E+00 5.06E-02 2.17E+03 1.00E+00 Non-Gamma Fraction 0.23 _ _ _ _0.30 0._ _0"29 Gamma Fraction 0.77 _ i _ 0.70 i _ i 0.71 ECe (JLCi/ml, total) I.77E- 1.86E-05 2.33E-05 ECe (ICi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06 C-4 0000000 0 0 00 00 0 0 0 00 00 0 0 0 00 00 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX D On-site Disposal of Low-Level Radioactively Contaminated Waste Streams D-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Appendix D consists of hard copies of the following reference documents:
DESCRIPTION DATE IDOCKET NUMBER Operating License DPR-43 Kewaunee Nuclear Power Plant Disposal of Low Level Radioactive Material October 17, 1991 NRC-91-148 50-305 Proposed Disposal of Low Level Radioactive Waste Sludge Onsite at the Kewaunee Nuclear Power Plant (TAC No. M75047)Safety Evaluation For An Amendment To An Approved 10 CFR 20.302 Application For The Kewaunee Nuclear Plant (TAC No. M89719)11 I Alternate Disposal Of Contaminated Sewage Treatment Plant Sludge In Accordance With 10 CFR 20.2002 (TAC No. M93844)11 0 0 0 0 0 0 0 0 0 0 0 0 0, 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Onsite Disposal Of Contaminated Pursuant To 10 CFR 20.2002 (TAC No. M97411)I Adapte D-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 WPSC 1414) 433. 1598 TELECOPIER (414: 433-5544 0.WI9CONSIU PUBUC SRIMCE COMPORATION
.-0F1 %ore-%Acar-s
- P0 Box IS02 a GeeerkBav.
W' 5d3C7-CO02 AtR 91-/4 tg EASYLINK 628S1993 bce- KM NE LarT DR DA RE KH ML DL I Lp m I 01noNV. Wui J N MorTison D2 A J Ruege D2 Boys, WPL I R Mueller D2 C A Schrock KNP Nielsen, ANFC D S Nalelka KNP C S Smoker KNP Berg KNP L A Nuthals D2 (NSRAC) C R Seinhaid D2 Bollom G6 R P Pulec D2 J I Wallace KNP Dratwim NiCJP J SRichmond D2 K KH Wihe Evers D2 D JRistau D2 S FWo, 12 \Marchi KNP D J Ro ponKJP Q,, QAVa M 4 P \M~asarile KNP-07K P w October 17, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
Docket 50-305 Operating 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, 1989 2) '- , s to K.H.Evers dated February 13, 1990 3 t m L.Sridhazon (W`DNR) to M.Vandenbusch dated June 13. 1991 In referen purs t t the regulation of 10 CFR 20.302, Wisconsin Public Service Corpo C) uested authorization for the alternative disposal of very-low-level radi the Kewaunee Nuclear Power Plant. In reference 2, the US NRC idenc4 .)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 review the disposal options for the service water pretreatment lagoon sludges. In reference 3, the WDNR completed a review of the most appropriate on site disposal methods for the slightly contaminated service water pretreatment lagoon studges. The two proposed methods that the WDNR evaluated included in-situ capping of the sludge in the wastewater treatment lagoon and on site landspreading.
In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Page 2 application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that either disposal method was acceptable provided:-if the material is to be left in the lagoon, it would be capped in accordance with Wisconsin State statutes.
XZN-if the on site landspreading option is utilized, the material would disking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading performance standards.
Should there be any additional qu member of my siaff.Sincerely, C. A. Schrock Manager -Nuclear Engineering Pq(bctional and ,free to contact a LICXDJMN492 0 S S 0 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 DJIrjms Attach.cc -.US NRC -Mr. Patrick D-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 ATTACHMENT I To 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Letter from K. H. Evers (WPSC) to Document Dated (NRC)'1 D-5 S KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page I 0 0 References
- 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989.NRC Question #1 On page 4 of your submittal, the average input to the Sewage'System is approximately 11,000 gallons per day. In the FA Statement, this system is to be operated below its desi of gallons per day. Discuss this deviation from the d cap d provide information to justify the higher output for thi te WPSC Response The original Sewage Treatment S th a Kewamee Nuclear Power Plant (KNPP) was rp 1a19 a higher capacity system. The original system was I .. work force of around [50 people.It was a limited capa ,/ ae c il ent system which included the onsite lagoon for additi '4< c ause of this limited capacity and more stringent con s steeffluent to Lake Michigan, an aerobic digester system wasi which has a higher capacity, and uses current techno input volume to the Sewage Treatment System used in the Septir 12. 1989 application was 11,000 gallons per day. This value was based on past operating data. The increase in influent from the original design basis included in the Final Environmental Statement is due mainly to an increase in the number of individuals and facilities (e.g., training and simulator building) located onsite. Design changes to the system were required to accommodate these new facilities.
D 0 0 D-60 0 0 0 O KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 O 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. This O increase has no significant effect on the dose modeling. (Refer to the response O to NRC Question #2, below.)O NRC Question #2 Provide information regarding how the disposal plan assur a an* dose to any exposed individual will be kept below 1WPSC Response n#a cocnrto 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 of any slightly ed materials from KNPP are within the bounds of the O evaluat .m each of the waste streams will be collected and an am spectroscopy prior to release for disposal.
A system 1 e f'etection (LLD) of 5F.A7 ptCi/ml for the principal gamma Oemi ionucides will be required.
This LLD ensures the identification of any contaminated materials at a fraction of the allowable concentration limits.O for the alternative disposal.o The results of these analyses will be used to ensure that any detectable levels 0of radioactive material are within the limits for alternative disposal.
Any materials with levels of radioactive material above the concentration limits 0 0* -O 0 0 KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 3 (and of plant origin) will be treated as a radioactive waste and appropriately controlled.
0 Records will be maintained to ensure that the cumulative disposal of any contaminated materials are maintained within the bounds of the _.ev IZ n addition to a comparison of the individual radionuclide concen 'l record of the total amount of radioactive material disposed wi maintained.
Cumulative totals will be maintained to e .te activity does not exceed the quantity assumed in enivati o e limits.In developing the concentration limits pres, , of reference 1, it was assumed the total annual design s v ,000 ft0 would be contaminated at the derived limit mitment from each radionuclide 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 each radionuclide's c by its limiting concentration must be less than one). 0 e0*The tio mits of Table I of reference 1 also have an implied total activity li, t. imit is determined by multiplying the individual radionuclide con limit by the total estimated waste volume of 27,000 ft 3.These total activity limits are presented in Table A of this response, for each radionuclide individually.
For a mixture of radionuclides, a total annual activity limit may be determined by normalizing the concentrations so that the sum-of-the-fractions for the mixture equals one (1). These resultant adjusted concentrations may be multiplied by the 27,000 ft waste volume to determine the corresponding total activity limit of the mixture.0 0 D-8 0 0 0 O 0* KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 15 O June 6, 2013 O Document Control Desk O October 17, 1991 O Attachment I, Page 4 0 O A Disposal Log will be maintained on a calendar year basis for all disposals of O any very-low-level radioactive materials.
The log will contain as a minimum* the following information:
O
- Disposal location*
- Description of waste-Shipment/disposal date O Waste volume O
- Radionucide concentrations (gamma emitt*
- Year-to-date radionuclide activity.-Year-to-date waste volume*Inaddition to the above Disposat Log, be kept for each O individual disposal.
This file " a3 inimum, the following O information:
- *- Waste identif-Sample ganm y results O Idetif Iuc* ncentrations and total activity* NRC QU 3B, Section A of your submittal, 'Radiation Exposure During 0 Trans y adding the cumulative dose to the exposed population per O reactor year for both the transportation worker and the general public O (onlookers along route).O O WPSC Response* The potential exposure to the general public (onlookers along route) is O 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 assumed 0 O -o 0 0 6 KEWAUNEE POWER STATION ODCM App-D 6 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 5 0 population density along route and vehicular speed. For a conservative evaluation of the potential exposure to the general public from the transport of the KNPP waste, a population density of 610 persons/mi 2 was assumed. This 0 value is conservative for the KNPP site area where the average aon density is less than 53 persons/mi 2.A transport distance of mmiles assumed. The IMPACTS-BRC modeling assumes five o ot 'erial are transported per shipment.
For the assumed KNPP s shipment weight translates into a total of 167 s ens a. With a vehicular speed of 20 miles per hour, the pulaon exposure--
time is 375 person-hours per year. At th 'a6 on limits established for 0 the alternative disposal, the potend n ' during transport will be less than 0.01 person-rem..per
^ _odeling of the exposure to the0 transport worker, the Iel )) assumes two drivers per vehicle.As presented in the S m 989 submitL, the maximum dose to the 0 driver is less th (<0.001 remlyr). Therefore, the total collective 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 the0 Po ess than 0.02 person-rem (0.002 person-rem
+ 0.01 person-rem
< 0. on-rem). O For the disposal of the existing 15,000 ft 3 of contaminated sludges, the population dose due to the transportation of the waste is calculated to be 0.0002 person-rem.
The estimated collective exposure to the transport worker O is 0.00007 person-rem.
The total collective dose due to transport of the waste 0 is 0.00027 person-rem.
0 D-lO 0 0 0 0 S O KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 Document Control Desk*October 17, 1991*Attachment I, Page 6 0 Additional Potential Disposal Method*The Wisconsin Department of Natural Resources has requested Wisconsin* Public Service to examine the feasibility of land application of the lagoon* sludges in lieu of 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 ion be included in the alternative disposal methods which was be acceptable in our September 12, 1989 submittal.
The potential pathways of exposure as eval 12, 1989 submittal conservatively bound any of exposure that would result from onsite land spreading of e.-A hment A to this response provides 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 During Transportu an on Exposure to Landfill Operator,'
appropriately ch y ntial exposure to workers involved with the land s 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 STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 7 6 Table A Radionuclide Quantity Limits for Alternative Disposal Limiting Limiting Annual Nuclide Concentration Qnti ("Ci/mi)H-3 9.65E-04 C-14 4.55E-05 48 Cr-51 3.13E-04 .2394 Mn-54 1. 14E-05 0.0087 Fe-55 l-.W0 7.6500 Fe-59 7. 0.0060 CO-58 .0.0089 Co-60 0.0029 Ni-63 E 7.6500 Sr-9 / 2.6393 Zr-q -06 0.0048 1.23E-05 0.0094 M6.73E-05 0.05 15 To- 2.70E-04 0.2066 2.5013-06 0.0019 2.68E-05 0.0205-134 6.161-06 0.0047 s-137 1.71E-05 0.0131 Ba-140 5.52E-05 0.0422 La-140 4.17E-06 0.0032 Transuranics.TRU (T1/2A > 5 yrs) 8.91E-05 0.0682 Pu-241 2.85E-03 2.1803 Cm-242 1.00E-02 7.6500 Assumes annual quantity of KNPP wastes is 27,000 ft 3 or 7.65E8 mls.S 0 6 S S S 6 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D-12 S S* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 0 Document Control Desk* October 17, 1991*Attachment 1, Page 8 0*Appendix A*Evaluation of Onsite Land Application for* Alternative Disposal of Very-Low-Level Contaminated Materials Overview Land spreading of lagoon sludges onsite at the Kewaunee Nuclear P P n recommended by personnel from the Wisconsin Department of N , (DNR) as a desirable alternative to the use of the Kewaunee County r This method of disposal is also a recommended practice for dispo0 age itment facility sludges.Therefore, WPS requests that this disposal meth i options available for the alternative disposal of very-low-level rad" n ted materials from KNPP.Description of Disposal Method The disposal of KNPP sludges y beneficial land application to a dedicated disposal area located onsite at a Nuclear Power Plant. Typical methods of land 0spreading 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 of Wiscon 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 for human 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 as D D-1 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D S OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 9 performed previously.
In addition, other limitations as applied to land application by the State of Wisconsin Department of Natural Resources will bI followed (e.g., control of runoff/erosion, proximity to wells/residences/surface water, etc.).Applicable Pathways of Exposure 4 The pathways of exposure applicable for land spreading are not d fo tm f the pathways evaluated for the disposal methods at the Kewa filor the Green Bay Metropolitan Sewerage District facilities.
The o pathways are discussed below: 0 Direct Exposure to WorkersS Any potential exposures to wo 0 removal, transport and land S spreading of the sludges are d by the evaluation of the exposure to the trans September 12, 1989 submittal.
The transport worker h In o be exposed for 460 hours0.00532 days <br />0.128 hours <br />7.60582e-4 weeks <br />1.7503e-4 months <br /> per year at one (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 the lagoon es w .reno longer than a three week period per year (i.e., 12 0 The p exposure to a worker onsite after land spreading, has been estimated at no more that 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year. Such an individual would be involved in land maintenance activities, such as plowing and mowing. As modeled in the September 12, 1989 submittal, an exposure of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year to the landfill operator has been assumed. For this exposure, the KNPP materials are mixed with other landfill waste: a 1:13 mixing of KNPP materials to other waste is assumed. This mixing is not significantly different from the type of mixing that will occur in the field with the sludges being D D-14 0 S 0 0* KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 2013 0 Document Control Desk October 17, 1991* Attachment 1, Page 10 o* 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 I Smmrem per year dose to the transport worker as evaluated in the S ber "" 1989 submittal.
- Post Disposal Exposure -Intruder Scenario 0* The IMPACTS-BRC model, as applied to the 0 P waste, assumes a loss of institutional controls 10 years af f ite (See Appendix B of the September 12, 1989 submittal).
An in med to reside in a house built on the disposal area. This indi irect exposure (from the uncovered waste), an inhalation exposu ion), and an ingestion exposure (from growing % of his food cigproeit is assumed that the waste is mixed 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.
- 0 0 D-15 0 0 0 KEWAUNEE POWER STATION ODCM App-D S OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 Document Control Desk October 17, 1991 Attachment I, Page 11 0 Post Disposal -Intruder Well 0 The intruder well pathway for onsite land disposal is essentially the same as the intruder 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/$ locating the well at the disposal site edge in "downstreamn flow" di i s the calculated hypothetical dose. (Additional discussion presented in NUREG/CR-3585, Volume 2). o The potential dose for the intruder well 0dspreading disposal would be 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-site land 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 S contam' te D 0 S S S 0 0 0 0 D-16 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON.
D.C.K ~-6r)q June 17, 1992 Docket No. 50-305 S 0 0 0 0 0 0 S 0 0 S 0 0 0 S Mr. C. A. Schrock Manager -Nuclear Engineering Wisconsin Public Service.Corporation P. 0. Box 19002 Green Bay, Wisconsin 54037-9002
Dear Mr. Schrock:
SUBJECT:
PROPOSED DISPOSAL OF LOW LEVEL RADIOACV TJDGE ONSITE AT THE KEWAUNEE NUCLEAR POWER PLANT (TA Ml7 By letters dated September 12, 1989, and )A, you submitted a request pursuant to 10 CFR 20.302 for th po0sa4 o 4ipste sludge onsite at the Kewaunee Nuclear Power Plant. We h cc q d.lur review of the request and find your procedures, including doc tments, to be acceptable.
This approval is granted provide a he sdsafety evaluation is permanently incorporated into y 0 se Calculation Manual (ODCM) as an Appendix, and that future pd f these commitments are reported to the NRC.Issuance of this safety v onpletes all effort on TAC No. M75047.O /Sincerely, Allen G. Hansen, Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page NRMC LETF'R E)ISTRIBUfloN T A Hanson (MG&E)J D Loock (WPL)Larry Nielsen (ANFC)J L Belaht (NSRAC)D A Bollom 06 K H Evers KNP J P Giesler D2 M L Marchi KNP D L Masarik KNP R P Pulac D2 (2)D J Rlisiu D2 A I Ruege D2 C A Schrock D2 C R D2 T J Webb KNP S F Womiak D2 QA Vault KNP D-17 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: David Baker. Esquire Foley and Lardner P.O. Box 2193 Orlando, Florida 32082 Glen Kunesh, Chairman Town of Carlton Route I Kewaunee, Wisconsin 54216 Mr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse Kewaunee, Wisconsin
.54216 Chairman Public Service Commission of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U.S. Nuclear Regulatory Counlsson Resident Inspectors Office Route #1, Box 999 Kewaunee, Wisconsin 54216 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0.0 0 S 0 0 0 0 Regional Administrator
-Region III U.S. Nuclear Regulatory Commissio 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Robert S. Cullen Chief Engineer Wisconsin Public Serv P.O. Box 7854 Madison, Wisconsi, 5 ion D-18 W KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6,2013* ~UNITD STATES NUCLEAR 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 COMPANY MADISON GAS AND ELECTRIC COM4PANY 0e DOCKET NO, 50-305
1.0 INTRODUCTION
In reference 1, Wisconsin Public Service ( ested approval pursuant to Section 20.302 of Title 10 of the e e Regulations (CFR) for the disposal of licensed material n r us onsidered in the Kewaunee Final Environmental Statement (F a ec r 1972. Additional related material from the licensee, fro at sconsin, and from the staff are contained in references 2 The WPSC request contains a detai the licensed material (i.e.. contaminated sludge) sub' t is FR 20.302 request, based on radioactivity absorbed from I ' of licensed material.
The S15,000 cubic feet of contam ed dge identified in the request contains a total radionuclide inven of I i of Cesium-137 and Cobalt-60.
In its submittal, the ad ;ed specific Information requested in accordance with 10 I .0 ovided a detailed description of the licensed material, oro ly yzd and evaluated the information pertinent to the effects t ironment nf the proposed disposal of licensed material, and c t o follow specific procedures to minimize the risk of unexpected xpos 2.0 OE 0 h Durin t a operation of Kewaunee, the potential exists for in-plant proce e which are not normally radioactive to become contaminated with ver evels of radioactive materials.
These waste streams are normally ratmd from the radioactive streams. However, due mainly to infrequent, minor syvtem leaks, and anticipated operational occurrences, the potential exists for these systems to become slightly contaminated.
At Kewaunee, the Oecondary system demineralizer resins, the survice water pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels.0 0 0D-19 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-2 -During the yearly testing of a batch of pre-treatment sludge, it was found that approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.3.0 PROPOSED DISPOSAL METHOD WPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsite pursuant to 10 CFR 20.302. The sludge is currently contained in an onsite lagoon at the KNPP sewage treatment facility.
The disposal of the sludge will ha hv l~ndI 2nnliratinn tn an araa lncat~d nnsiti@ at K(NPP_ as shown in Figure 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 I is 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 less years. T7 I Nucl ide Co-60 Cs-137 4.0 RADIOLOGICAL IMPACTS 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 The licensee has evaluated the fol in entT11exposura pathways to members of the general public fr he akbkuclides in the sludge: (1)external exposure caused by gr nsh froifr.,he disposal site; (2) internal exposure from inhalation of jed ionuclides; and (3) internal exposure from ingesti ng gr t0\- Pt staff has reviewed the licensee's calculatlonal methods andbsu Ion finds that they are consistent with NRC Regulatory Guide I1 culati n of Annual Doses to Man from Routine Releases of Reactor E eh or the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,,e n 1, October 1977. The staff finds the assessment method g- acg abye.Table 2 listý do ulated by the licensee for the maximally exposed member of t epu on a total activity of 0.170 mCi disposed of In the current yea .. as the cumulative impact of similar disposals during subsequent years. any repetitive disposals, the licensee must reapply to the NRC when a r ular disposal would exceed the. following boundary conditions:
(1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.D-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-3-IAHLLZ Pathway Whole Body Dose Received by Maximally Exposed Individual (mremrvear) 0.034 0.008 0.007 Groundshine Inhalation Groundwater Ingestion TOTAL 0T.04 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 As shown in Table 2, the annual dose is expected to be on the 0.1 mrem or less. Such a dose is a small fraction of the 300 annually by members of the general public from sources of natu radiation.
The guidelines used by the NRC staff for onsite disposal are presented in Table 3, along with the staff's guideline has been satisfied.
The licensee's procedures and commitments as docu ed th acceptable, provided that they are permanently Inc ed licensee's Offslte Dose Calculation Manual (OcsZas AA ruture modifications be reported to NRC In a rdr he change protocol.ial ,\ ittal are Xo the ix, and that applicable ODCH Based on the above findings, the sta dispose of the low level radioactive described In the WPSC letter dateJSi State of Wisconsin has also appeVd=4ii6see's proposal to nsite in the manner 71989, to be acceptable.
lures (reference 5).The (D-21 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-4 -TABtLE3 20.302 Guideline for Onsite Disoosal 1. The radioactive material should be disposed of in a manner that It is unlikely that the material would be recycled.Staff's Evaluation
- 1. Due to the nature of the disposed material,,recycling to the general 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 general public or a non-occupationally exposed worker) from the probable pathways of exposure to the disposed J A material should be less than 1 mrem/year.
- 3. Doses to the total body and any 3. Because t riN al ill be body organ of an inadvertent land-spread te s c iders the intruder from the probable pathways maximally os in al of exposure should be less than scenario add the 5 nreminyear..
intru 10 4. Doses to the total body and any 4. v c ing were to occur body 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 not site 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-22 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-5-0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (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 For Additional 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 e 1991.(5) Letter from L. Sridharon of the State of Wisconsin Departm Nat Resources to M. Vandenbusch of WPSC, dated June 13, 1 (6) E. F. Branagan Jr. and F. J. Congel. 'Disposal of am Inna Radioactive Wastes from Nuclear Power Plants, se)t',~at e Health Physics Society's midyear Symposium on Health s rations In DecontaiiinationfOecommissfontng.
OF.00I3IIxvllle bF (CONF-86O203).
Principal Contributor:
J. Minns Date: June 17. 1992 D-23 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-6-Figure 1 Kewaunee Nuclear Power Plant Site Area Hap 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D-24 KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 2013 0*
UNITED STATES 9/21/94:1 =NUCLEAR REGULATORY COMMISSION WASHN1GT10N, D.C. UM&OM September 14., 1994 M Hr. C. A. Schrock Manager -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 CVR APPLICATION FOR THE KEWAUNEE NUCLEAR PLANT (TAC NO. 14897
Dear Mr. Schrock:
By letter dated June 23, 1994, as supplemented June 29, 1994, equ ed approval to use another onsite area for the disposal of ste sludge In addition to the location approved by the WR staff has completed its review of your request and f t roposal meets the radiological boundary conditions approv Il Ju 11. 1992, Safety Evaluation!
and is therefore acceptable,.
ta finds that your proposal is in accordance with 1o0 CFR 20 2 r aced 20.302 on This approval Is granted provided that t e ety Evaluation is permanently incorporated Into your Offsi cu ation Manual (01CM) as* an Appendix, and that future modif sot commitments are reported 4>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/encl see next page ST 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 DNP D A 1eUam 1 JN Uf DI TJWd" DIU Cob XNP L A Nb 013RAC) $ F Wandek D2 K B Sven Kp RPPuh1D2M(z QA Vlt KNP 1) P Gimler C A Sh*D2 4) D-25* P4f) ~0)0) 0 0 KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 0 Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: Foley & Lardner Attention:
Mr. Bradley D. Jackson One South Pinckney Street P. 0. Box 1497 Madison, Wisconsin 53701-1497 Chairman Town of Carlton Route 1 Kewaunee.
Wisconsin 54216 Mr. Harold Reckelberg, Chairman Kewaunee County Board Kevaunee County Courthouse 0 Kewaunee, Wisconsin 54216 Chairman Public Service Comission of 0 Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 Attorney General 114 East, State Capitol N-'Madison, Wisconsin 53702 U. S. Nuclear Regulator'y Commiission Resident Inspectors Office Route 01, Box 999 -Kewaunee, Wisconsin 54216 Regional Administrator
-U. S. Nuclear Reuloa 801 Warrenville Rad Lisle. Illinois 60 0 Mr. Robert S. C 11.e0 nChief Engineer e Wisconsin iPOJd c ice tssion P. o. Boxiaw Madison, 07 D-26 0 0!0 0 0 0 0 0 D-26 S 0 0 0 w KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 UNITED STATES NUCLEAR REGULATORY COMMISSION eWAMINGTON.
D.C. =4WM SSAFETY 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 COMPANY DOCKET NO. 50-305 1.0 l.0 TOCTIo By letter dated June 23, 1994, and as suppl on 29. 1994, Wisconsin Public Service Corporation (the licens sed val to use another onsite area for the disposal of cont a dge in addition to the.. location approved by the NRC on June 2.0 EVALUATION-A Safety Evaluation (SE) ai
- approved the licensee's request pursuant to 10 CFR 20.302 s sal of 15,000 cubic feet of contaminated waste slud yIcatlon at the Kewaunee Nuclear Power Plant (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 Iagoon at t1i4OlPP treatment facility.
In 1993, approximately 7500 cubic feet of the o 1 5,000 cubic feet of contaminated sludge was spread on that locato 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 will meet all the radiological boundary conditions contained in the SE for the 10 CFR 20.30Z application approved on June 17, 1992. Additionally.
the licensee has stated that this additional disposal site will meet all 0 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.0 0 0 D-2 S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 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 the radiological boundary conditions a pproved In the June 17, 1992, SE and is therefore acceptable.
The staff also finds that your proposal is in accordance with 10 CFR 20.2002 which replaced 20.302 on January 1. 1994.As stated In the NRC's June 17, 1992, approval of the licensee's 10 CFR 20.302 application, the licensee Is required to permanently Incorporate this modification 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 Hap 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D-28 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013-----------------
---t------ --------------------------
1~D-29 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 K-?5-l/,,2.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DA.. S.CWI November 13, 1995 Mr. M. L. tarchi Manager -Nuclear Business Group Wisconsin Public Service Corporation Post Office Box 19002 Green Say, III 4307-9002
SUBJECT:
ALTERNTE DISPOSAL OF CONTAINATED SEVAME TREATKf A 'CCOIWANCE VITH 10 CFR 20.2002 (TAC NO. N93844)
Dear 4r. ardchi:
By letter dated October 17, 1995. as supplemented a6 r 5, you requested approval for the onsite disposal o con 1 treatment sludge In accordance with 10 CFR 20.2002. This ln to a previous disposal request that wa approved ca 17, 1992.The staff has completed Its review s that your proposal mets the radiological bound ad In the June 17.1992, Safety Evaluation, and Is theref.This approval is granted provided safety evaluation Is penmantly incorporated Into y culation Manual (000m) as an Appendix, and that future as comitments are reported to the NRC.Richard J.LweProject Manager Project Directorate 111-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Enclosur etY Evaluation cc: See next page NIRC to WPSC LJT 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 T A HMC (MO&E)M W Seitz (WPL)Lftq Nilbmn (AJFC D A BoilM 06 DEDayDI K H Rvm XNP M L Marchi D2 I X Jubin ('NSRAC)R P P"N(3)C A Sabiuck 3W?CS Simolr X"N C R Stelahu* D2 CA SmwStnzy s F Woz" D2 B Domnck NP (Corn)D-30 0 0* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 15*June 6, 2013 Hr. M. L. ,archi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 0 cc: Foley A Lardner Attention:
1r. Bradley 0. Jackson*One South Pinckney Street P. 0. Box 1497 H Madison, Wisconsin 53701-1497 Chairman Town of Carlton Route I Kewaunee, Wisconsin 54216*Mr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse
- Kewaunee, Wisconsin 54216* Chairman Public Service Commisslon of* Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702* Attorney General 114 East, State Capitol* Madison, Wisconsin "702 U. S. Nuclear Regulatory Comisst-Resident Inspectors Office.Route 0l, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator I U. S. Nuclear Regula C rs'801 Warrenville Road* Lisle, Illinois 2 Mr. Robert S. ln Chief Enginer ic I missi on P. 0. 00 /85..-MadisonA m 53707*0 0 0 0 0 0 0 0 0 D-3 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 UNITED STATES NUCLEAR REGULATORY COMMISSION WAgNINGTON, D..0 206SO-M SAFM EVALUATION fLY THE OfF CF NiLEAR REACTOb REC.LATIOM RELATING TO ONSITE DISPOSAL OF LOW-LEVEL RADIOACTIVELYO cONTAmINATED SEvAGE TREATmENT SLwUGE AT THE KEVAINEE NMLEAR POWER PLANT WISCONSIN PUBLIC SERVICE CORPORATION MADISON GAS AND ELECTRIC COMPANV DOCKET HO. SC-305 By lettero ated October 17, 1995, as imaplwtwt n V 1 Wisconsin Public Service Co rtio Tic approval for the onsite disposal of contaminated s i sl t previous disposal request that was approved by the , O 2.0 In a letter dated September
- 12. ]ýJ t requested authorization for the alternate disposal of very- lIs tive material.
In a Safety Evaluation (SE) dated June 1approved the licensee's request pursuant to 10 CFR 20.302 10 for tiI disposal of 100 cubic feet of contaminat t l I l application at the Kewaunee Nuclear Power Plant (X 'i The SE imposed the following boundary conditions:
- 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 boundary conditions of the previously approved disposal.3.0 EVALUATION The licensee has proposed to dispose of approximately 6000 gallons (800 cubic feet) of sewage sludge similar to the material approved for disposal in the SE dated June 17, 1992. The principal radionuclides identified in the waste sludge and their activity based on measurements In Mqa, 1995 are: Co-58, O O O O D-32 O O O O 0* KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 15* June 6, 2013 0* 0 0.0009 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 of 0.2 ;Ci. Additionally, Cr-51 with it short half-life (27.7 day) will have undergone significant decay from Its Initial value of 0.0005 @Ci.* The licensee has committed that the new disposal will met all the radiological boundary conditions, on a cumalative basis, contained In the SE for the 10 CrR 20.302 application approved on June 17, 1902. Additionally, the licensee has stated that all applicable pendts for this disposal have been obtained from the Wisconsin Department of Natural Resources.
- 4.0 CNLSO The staff finds the licensee's proposal to dispose of the low-ley radioactive 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 the Offsite 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 Nap 0 I 0 S 0 0 ccO 0 0 0 0 0 0 0 0*S -3 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013---------------------
4 D-34 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 UNrTED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON.
D.O. "6864M April 9, 1997 Mr. M. L. tarchi Manager -Nuclear Business Group Wisconsin Public Service Corporation Post Office Box 19002 Green 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 .u Regulatory Commission (NRC) review the applicability 1 20.2002) application approved on June 17, 1992, for nal sposals of a similar nature.The staff has completed its review of your requ ag s with your determination that the 10 CFR 20.203 appli on disposal of sludge contaminated with licensed radioactive ma a £-;iapproved on June 17, 1992,. contains bounding conditio able for ac onsite disposals of a similar nature. Safety Evaluation is enclosed..
ihard .Project Manager Project Directorate 111-3 NDivision of Reactor Projects III/[V Office of Nuclear Reactor Regulation Docket Enclosl Evaluation cc: See n--ý e par n W419 1 "mm T A Mama. (MG&Z)mwseitg(mp H D Oww (9t)~D A Bob=. 06 D E Day DI K f Evene KNp R P M.w KNlp M3 C A Srchk IXNp C 3 Snx*w X" C R SbcWxu* D2 3 F Womoikk D2=0=3iCkMRPAedw1w XNP (C-WUSAR)D-35 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 Mr. H. L. Marchi Wisconsin Public Service Corporation cc: Foley & Lardner Attention:
Hr. Bradley 0. Jackson One South Pinckney Street P. 0. Box 1497 Madison, Wisconsin 53701-1497 Kewaunee Nuclear Power Plant Chairman Town of Carlton Route I Kewaunee, Wiscpnsin 54216 Hr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse Kewaunee, Wisconsin 54216 Chairman Wisconsin Public Service Commission 610 N. Whitney Way Madison, Wisconsin 53705-2729 Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U. S. Nuclear Regulatory Commission Resident Inspectors Office Route fl, Box 999 Kewaunee, Wisconsin 54216 /6 6 S 6 S 0 0 0 0 0 0 0 S S 0 S 0 S 0 0 0 0 0 0 0 Regional Administrator
-Regii U. S. Nuclear Regulatory 801 Warrenvflle Road'Lisle, Illinois 60532-Mr. Rbbert S.- Cullen Chief Engineer Wisconsin Public vce 610 N. Whitneyjta Madison, Wisý iVc Ion D-36 KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 15 June 6, 2013 SNUCLEAR 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 COMPANY MADISON GAS AND ELECTRIC COMPANY* DOCKEt NO,. 50-305.*1.0 CNTlOUCthe By letter dated December 1 0. 1996, Wisconsin Public S em C an (the licensee) requested that the U.S. Nuclear Regulator sion RC) review its determination that NRC approval, pursuant toMF for the onsite disposal of contaminated sludge at the un UCI -Power Plant.(KNPP) Is not required, provided such disposals within the limits 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 for the 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 of 15,000 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; and 3.$,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 boundary conditions 03.0 ELUATION The licensee has determined that NRC approval for future onsite disposals of sludge contaminated with licensed radioactive material is not required provided the disposals comply with the limits and conditions of the SE issued*on June 17, 1992. The licensee has also developed a sludge sampling and*analysis procedure that impleaents the guidance contained in NRC Information 0 0)4)S)0)D3 KEWAUNEE POWER STATION ODCM App-D w OFFSITE DOSE CALCULATION MANUAL Revision 15 0 June 6, 2013 0-2-0 Notice 8B-22. Specifically, the licensee's procedure will require the analysis 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.
The licensee has provided a site map (attached) that specifies the acceptable onsite disposal areas for the contaminated sludge.
4.0 CONCLUSION
0 The 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 \ )u The licensee should permanently incorporate this Safety Evaluat In he Offsite Dose Calculation Manual as an Appendix.Principal Contributor:
S. Kiementowicz Date." April 9. 1.997
Attachment:
KNPP Site Map.3 0 0 0 0*0-0 S 0 S 0 0 0 0 0 0 0 D-38 0 0 S 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 15 June 6, 2013 I t**D-39 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Thi pge ntntinaly ef blnk0 0 Thi pae ntetinaly lftblak0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S S 0 S S S S 0 o OffsitenDose Caclto 0* Revision 16* ~December 5, 2013 S S S S S S S S S S S S S S S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Thi pge ntntinaly ef blnk0 0 Thi pae ntetinaly lftblak0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 Dominion Energy Kewaunee, Inc.Kewaunee Power Station OFFSITE DOSE CALCULATION MANUAL (ODCM)Revision 16 DATE: December 5, 2013 Approved By: Approved By: Reviewed By: Approved By: James M. Hale Manager -Radiological Protection and Chemistry Richard P. Repshas Manager -Regulatory Affairs Jeffrey T. Stafford Facility Safety Review Committee 12/04/2013 Date 12/04/2013 Date 12/05/2013 Date 12/05/2013 Date A. J. Jordan Site Vice President KEWAUNEE POWER STATION ODCM TOC w OFFSITE DOSE CALCULATION MANUAL Revision 16 0 December 5, 2013 0 TABLE OF CONTENTS PAGE 0 PART I -RADIOLOGICAL EFFLUENT CONTROLS NORMAL CONDITIONS AND BASES
11.0 INTRODUCTION
11.0-1 12.0 (Not Used)13.0 USE AND APPLICATION 13.0.1 Definitions 13.0.1-1 13.0.2 Logical Connectors 13.0.2-1 13.0.3 Restoration Times 13.0.3-1 13.0.4 Frequency 13.0.4-1 13.0.5 ODCM Normal Condition (DNC) Applicability 13.0.5-1 13.0.6 ODCM Verification Requirement (DVR) 13.0.6-1 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration 13.1.1-1 13.1.2 Liquid Effluents Dose 13.1.2-1 13.1.3 Liquid Radwaste Treatment System 13.1.3-1 13.1.4 Liquid Holdup Tanks 13.1.4-1 0 13.2 RADIOACTIVE GASEOUS EFFLUENTS 13.2.1 Gaseous Effluents Dose Rate 13.2.1-1 13.2.2 Gaseous Effluents Dose -Noble Gas 13.2.2-1 13.2.3 Gaseous Effluents Dose -Iodine and Particulate 13.2.3-1 13.2.4 Gaseous Radwaste Treatment System 13.2.4-1 13.2.5 Gas Storage Tanks 13.2.5-1 13.3 INSTRUMENTATION 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-1 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3. 2-1 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE 13.4.1 Radioactive Effluents Total Dose 13.4.1-1 0 ii KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM TOC Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.5 13.5.1 13.5.2 13.5.3 14.0 14.1 RADIOLOGICAL ENVIRONMENTAL MONITORING Monitoring Program Land Use Census Interlaboratory Comparison Program DESIGN FEATURES Gaseous and Liquid Effluent Release Points ADMINISTRATIVE CONTROLS Major Changes to Radwaste Treatment Systems Radioactive Effluent Release Report Special Reports PAGE 13.5.1-1 13.5.2-1 13.5.3-1 14.1-1 15.0 15.1 15.2 15.3 15.1-1 15.2-1 15.3-1 iii KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM TOC Revision 16 December 5, 2013 PART II CALCULATIONAL METHODOLOGIES
1.0 LIQUID
EFFLUENT METHODOLOGY 0 0 S PAGE 1.1 1.2 1.3 1.4 1.5 1.6 Radiation Monitoring Instrumentation and Controls 1.0-1 Liquid Effluent Monitor Setpoint Determination 1.0-1 Liquid Effluent Concentration Limits -10CFR 20 1.0-4 Liquid Effluent Dose Calculation
-10 CFR 50 1.0-5 Liquid Effluent Dose Projections 1.0-7 Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams 1.0-8 2.0 GASEOUS EFFLUENT METHODOLOGIES 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 Radiation Monitoring Instrumentation and Controls Gaseous Effluent Monitor Setpoint Determination Gaseous Effluent Instantaneous Dose Rate Calculations
-10 CFR 20 Gaseous Effluent Dose Calculations
-10 CFR 50 Gaseous Effluent Dose Projection Environmental Radiation Protection Standards 40 CFR 190 Incineration of Radioactively Contaminated Oil Total Dose 2.0-1 2.0-3 2.0-5 2.0-7 2.0-10 2.0-11 2.0-11 2.0-11 0 APPENDICES Appendix A (Not Used) ...................................................................................................
A-1 I Appendix B Appendix C Technical Basis for Effective Dose Factors -Gaseous Radioactive Effluents
.. B-1 Table B-1 Effective Dose Factors -Noble Gases ...................................
B-5 Evaluation of Conservative, Default Effective EC Value for Liquid Effluents
.... C-1 Table C-1 Calculation of Effective EC (ECe) ............................................
C-4 Appendix D Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams ..... D-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 iv
- KEWAUNEE POWER STATION ODCM TOC OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013 S LIST OF TABLES PAGE 0PART I -RADIOLOGICAL EFFLUENT CONTROLS 13.1.1-1 Radioactive Liquid Waste Sampling and Analysis 13.1.1-3 13.2.1-1 Radioactive Gaseous Waste Sampling and Analysis 13.2.1-3 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 13.3.1-5 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 13.3.2-5*PART II CALCULATIONAL METHODOLOGIES 0 1.1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATIONS 1.0-10 1.2 SITE RELATED INGESTION DOSE COMMITMENT FACTORS 1.0-12 1.3 BIOACCUMULATION FACTORS 1.0-14 2.1 DOSE FACTORS FOR NOBLE GASES 2.0-15 2.2 PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATIONS 2.0-16 2.3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS 2.0-17 2.4 R 1 INHALATION PATHWAY DOSE FACTORS-ADULT 2.0-18 2.5 Ri INHALATION PATHWAY DOSE FACTORS-TEEN 2.0-20 2.6 Ri INHALATION PATHWAY DOSE FACTORS-CHILD 2.0-22 2.7 Ri INHALATION PATHWAY DOSE FACTORS-INFANT 2.0-24 2.8 Ri VEGETATION PATHWAY DOSE FACTORS-ADULT 2.0-26 2.9 Ri VEGETATION PATHWAY DOSE FACTORS-TEEN 2.0-28 2.10 R, VEGETATION PATHWAY DOSE FACTORS-CHILD 2.0-30 2.11 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-ADULT 2.0-32 2.12 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-TEEN 2.0-34 2.13 R1 GRASS-COW-MILK PATHWAY DOSE FACTORS-CHILD 2.0-36 2.14 Ri GRASS-COW-MILK PATHWAY DOSE FACTORS-INFANT 2.0-38* 2.15 Ri GROUND PLANE PATHWAY DOSE FACTORS 2.0-40 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM TOC Revision 16 December 5, 2013 LIST OF FIGURES PART I -RADIOLOGICAL EFFLUENT CONTROLS PAGE 0 0 0 0 0 S 0 14.1-1 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENT 14.1-2 PART II CALCULATIONAL METHODOLOGIES 1 2 3 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM SIMPLIFIED HEATING BOILER FUEL OIL PIPING SYSTEM 1.0-9 2.0-13 2.0-14 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Vi Kewaunee Power Station Offsite Dose Calculation Manual PART I -RADIOACTIVE EFFLUENT CONTROLS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION ODCM 11.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0
11.0 INTRODUCTION
The Kewaunee OFFSITE DOSE CALCULATION MANUAL (ODCM) is established and maintained pursuant to Technical Specifications Section 5.5.1. The ODCM consists of two parts: Radiological Effluent Controls, Part I, and Calculational Methodologies, Part I1.Part I, Radiological Effluent Controls, includes:
(1) The Radioactive Effluent Control Specifications (RECS) and Radiological Environmental Monitoring Programs (REMP) required by Technical Specification 5.5.1 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by Technical Specifications 5.6.1 and 5.6.2 respectively.
Part II, Calculational Methodologies:
provides the methodology to manually calculate radiation dose rates and doses to individual persons in UNRESTRICTED AREAS due to the routine release of gaseous and liquid effluents.
Long term 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 are performed when computerized calculations are not available.
The methodology stated in this manual is acceptable for use in demonstrating compliance with 10CFR20.1302; 10CFR50, Appendix I; and 40CFR190.0 More conservative calculational methods and/or conditions (e.g., location and/or exposure pathways) expected to yield higher computed doses than appropriate for the maximally exposed person may be assumed in the dose evaluations.
The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations.
Changes will be made to the ODCM calculational methodologies and parameters as is deemed necessary to assure reasonable conservatism in keeping with the principles of 10CFR50.36a and Appendix I for demonstrating radioactive effluents are ALARA.11.1 Change Process 0 Instructions for defining the responsibilities and requirements for revision and control of both the ODCM and the RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM) are located in approved station procedure for Revision and Control of the REMM and ODCM.0 0 0 0 0 0 0 0 11.0-1 1 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.1 Revision 16 December 5, 2013 13.0 USE AND APPLICATION 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.0.1 Definitions IlL I f'%"Ir" lr"-------- ----------
I-l-- J JIl-----------------------------------------------------
Terms defined in both Kewaunee Technical Specifications and the OFFSITE DOSE CALCULATION MANUAL appear in capitalized type and are applicable throughout the Radiological Effluent Controls Normal Conditions and Bases and the Calculational Methodologies.
Term ACTION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION FUNCTIONAL/
FUNCTIONALITY GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S)
OF THE PUBLIC Definition 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 during operation.
This determination shall include, where possible, comparison of the channel indication with other indications derived from 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 to verify that it is FUNCTIONAL, including alarm and/or trip initiating action.CHANNEL CALIBRATION consists of the adjustment of channel output as necessary, such that it responds with acceptable range and accuracy to known values of the parameter that the channel monitors.Calibration shall encompass the entire channel, including alarm and/or trip, and shall be deemed to include the CHANNEL FUNCTIONAL TEST.As defined in the Technical Requirements Manual A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity released to the environment.
MEMBER(S)
OF THE PUBLIC means any individual except when that individual is receiving an OCCUPATIONAL DOSE.13.0.1 -1 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.1 Revision 16 December 5, 2013 OCCUPATIONAL DOSE OFFSITE DOSE CALCULATION MANUAL ODCM NORMAL CONDITIONS (DNC)ODCM VERIFICATION REQUIREMENTS (DVR)PROCESS CONTROL PROGRAM OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. OCCUPATIONAL DOSE does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75, from voluntary participation in medical research programs, or as a MEMBER OF THE PUBLIC.The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation 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 and Radiological Environmental Operating and Radioactive Effluent Release Reports required by TS 5.6.1 and TS 5.6.2.Specify minimum requirements for ensuring safe operation of the facility.
The Contingency Measures associated with a DNC state Nonconformances that typically describe the ways in which the requirements of the DNC can fail to be met. Specified with each stated Nonconformance are Contingency Measures and Restoration Time(s).Verification requirements are requirements relating to test, calibration, or inspection to assure that the necessary FUNCTIONALITY of systems and components are maintained, that facility operation will be maintained within the current licensing basis, and that the ODCM Normal Condition (DNC) for operation will be met.The PROCESS CONTROL PROGRAM shall contain the current formulae, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes, based on demonstrated processing of actual or simulated wet solid wastes, will be accomplished in such a way as to ensure compliance with 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71, Federal and State regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste.Licensee initiated changes to the PCP, which was approved by the Commission prior to implementation:
- 1. Shall be documented and records of reviews performed shall be retained as required by the quality assurance program. The documentation shall contain: a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s).
- b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Shall become effective upon review and acceptance by the FSRC.S S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 13.0.1-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.1 Revision 16 December 5, 2013 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 PUBLIC DOSE PURGE -PURGING RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)SITE BOUNDARY SOURCE CHECK UNRESTRICTED AREA VENTILATION EXHAUST TREATMENT SYSTEM VENTING PUBLIC DOSE means the dose received by a MEMBER OF THE PUBLIC from exposure to radiation or to radioactive material released by a licensee, or to any other source of radiation under the control of a licensee.
PUBLIC DOSE does not include OCCUPATIONAL DOSE or doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10 CFR 35.75, or from voluntary participation in medical research programs.PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
The REMM shall contain the current methodology and parameters used in the conduct of the radiological environmental monitoring program.The SITE BOUNDARY shall be that line beyond which the land is neither owned, leased, nor otherwise controlled by the licensee.A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. (See Plant Drawing A-408)A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal andlor HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.
Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature atmospheric cleanup systems (i.e., Auxiliary Building special ventilation, Shield Building ventilation, spent fuel pool ventilation) are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting.Vent, used in system names, does not imply a VENTING process.13.0.1-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.2 Revision 16 December 5, 2013 13.0 USE AND APPLICATION 13.0.2 Logical Connectors Logical Connectors are discussed in Section 1.2 of the Technical Specifications and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0*0 0 0 0 0 0 0 13.0.2-1 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.3 Revision 16 December 5, 2013 13.0 USE AND APPLICATION 13.0.3 Restoration Times Restoration Times are the same as Completion Times as discussed in Section 1.3 of the Technical Specifications and are applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases.When "Immediately" is used as a Restoration Time, the Contingency Measure should be pursued without delay in a controlled manner.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.0.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.0 USE AND APPLICATION 13.0.4 Frequency ODCM 13.0.4 Revision 16 December 5, 2013 Frequency is discussed in Section 1.4 of the Technical Specifications and is applicable throughout the OFFSITE DOSE CALCULATION MANUAL and Bases 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.0.4-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.5 Revision 16 December 5, 2013 13.0 USE AND APPLICATION 13.0.5 ODCM Normal Condition (DNC) Applicability DNC 13.0.5.1 DNCs shall be met during the specified conditions in the Applicability.
DNC 13.0.5.2 DNC 13.0.5.3 Upon discovery of a failure to meet the DNC, the Contingency Measures of the associated Nonconformance shall be met, except as provided in DNC 13.0.5.4.When it is discovered that a DNC has not been met and the associated contingency measures are not satisfied within the specified restoration time (or an associated contingency measure is not provided), the equipment subject to the DNC is in a nonconforming condition.
In this situation, appropriate actions shall be taken as necessary to provide assurance of continued safe plant operations.
In addition a Condition Report shall be initiated and assessment of reasonable assurance of safety shall be conducted.
Items to be considered for this assessment include the following:
- Availability of redundant or backup equipment;
- Compensatory measures, including limited administrative controls;* 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 may continue to operate while prompt corrective action is taken.Equipment removed from service or declared nonfunctional to comply with Contingency Measures may be returned to service under administrative control solely to perform testing required to demonstrate its FUNCTIONALITY or the FUNCTIONALITY of other equipment.
This is an exception to DNC 13.0.5.2 for the system returned to service under administrative control to perform the testing required to demonstrate FUNCTIONALITY.
0 0 S 0 S 0 S 0 S S S S S S S S S S S S S S S DNC 13.0.5.4 13.0.5-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.0.6 Revision 16 December 5, 2013 13.0 USE AND APPLICATION 13.0.6 ODCM VERIFICATION REQUIREMENTS (DVR) Applicability DVR 13.0.6.1 DVR 13.0.6.2 DVR 13.0.6.3 DVRs shall be met during the specified conditions in the Applicability for individual DNCs, unless otherwise stated in the DVR. Failure to meet a DVR, whether such failure is experienced during the performance of the DVR or between performances of the DVR, shall be failure to meet the DNC. Failure to perform a DVR within the specified Frequency shall be failure to meet the DNC except as provided in DVR 13.0.6.3.
DVR's do not have to be performed on nonfunctional equipment or variables outside specified limits Each Verification Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified DVR frequency.
When it is discovered that a DVR frequency (including the 1.25 times extension) has not been met, the equipment subject to the DVR is in a nonconforming condition.
In this situation, a Condition Report shall be initiated and, if indicated, determination to evaluate the impact on plant safety shall be performed in a timely fashion and in accordance with plant procedures.
Actions should be taken to restore conformance with the DNCs / DVRs in a timely fashion.0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.0.6-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.1 RADIOACTIVE LIQUID EFFLUENTS 13.1.1 Liquid Effluents Concentration ODCM 13.1.1 Revision 16 December 5, 2013 DNC 13.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (Figure 14.1-1) shall be limited to: 0 0 0 0 0 0 0 0 0 0 0 0 0 0 a. 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases;and b. 2 x 10 4pCi/ml total activity concentration for dissolved or entrained noble gases.APPLICABILITY:
During release via the monitored pathway.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Concentration of A.1 Initiate ACTION to restore Immediately radioactive material concentration to within limits.released in liquid effluents to UNRESTRICTED AREAS exceeds limits.B. CONTINGENCY B.1 Initiate a CR In accordance MEASURES with Corrective OR Action Program RESTORATION TIME AND not met.B.2 Explain in the next Radioactive In accordance Effluent Release Report why with Radioactive the CONTINGENCY Effluent Release MEASURE was not met in a Report timely manner.13.1.1 -1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.1 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.1.1 Perform radioactive liquid waste sampling and activity In accordance with analysis.
Table 13.1.1-1----------
NOTE------.-.................
In accordance with In this DVR the results of DVR 13.1.1.1 shall be used in accordance Table 13.1.1-1 with the methodology and parameters of the ODCM.DVR 13.1.1.2 Verify the results of the DVR 13.1.1.1 analyses to assure that the concentrations at the point of release are maintained within the limits of DNC 13.1.1.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.1-2 0 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 0 S 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.1 Revision 16 December 5, 2013 Table 13.1.1-1 (Page 1 of 2)Radioactive Liquid Waste Sampling and Analysis LIQUID RELEASE TYPE 1. Batch Waste Release Tanks (b)TYPE OF ACTIVITY SAMPLE TYPE ANALYSIS SAMPLE FREQUENCY a. Principal Gamma Emitters(c)
- b. 1-131 Dissolved and c. Entrained Gases (gamma emitters)d. H-3 e. Gross Alpha f. Sr-89 g. Sr-90 h. Fe-55 Grab Sample Each Batch (g)Grab Sample Each Batch (g)Grab Sample Each Batch (g)MINIMUM ANALYSIS FREQUENCY Each Batch (g)Each Batch (g)31 days 31 days 31 days 92 days 92 days 92 days LOWER LIMIT OF DETECTION (LLD)(a)1 x 1V ACi/ml I x 10e giCi/ml 1 x 1V"s pCi/mI 1 x 105 ACi/ml 5 x 10.' ACi/ml 5 x 10.8 ACi/ml 5 x 10.8 gCilml 1 x 10-6 ACi/ml Composite (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 Gamma Emitters (c)b. 1-131 Dissolved and c. Entrained Gases (gamma emitters)d. H-3 e. Gross Alpha f. Sr-89 g. Sr-90 h. Fe-55 Grab Sample Grab Sample Grab Sample Grab Sample Composite (f)Composite (t)Composite (1)Composite (f)7 days 7 days 7 days 7 days 7 days 7 days 7 days 7 days 7 days 7 days 7 days 31 days(o 31 days()92 days(f 92 days()92 days(f 5 x 10r pCi/mI 1 x 106 pCi/ml 1 x 10S pCi/ml 1 x 10.8 iCi/ml 5 x 10.7 p.Ci/ml 5 x 10.8 pCi/ml 5 x 10.8 pCi/ml 1 x 10i ACi/mI 13.1.1-3 KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Table 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 will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
4.66
- Sb LLD = EV*2.22 x 10 6*Y* exp(-A4O Where:* 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, and 0 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 a measurement system and not as an a posteriori (after the fact) limit for a particular measurement..(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
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 are to be considered.
Other gamma peaks that are identified, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to DNC 15.2.(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 has an input flow during the continuous release.(f) As a minimum, the monthly and quarterly composite samples shall be compromised of weekly grab samples.(g) Complete prior to each release.1 S S S S S S 13.1.1 -4 S S S
- KEWAUNEE POWER STATION ODCM 13.1.1 OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013*) BASES 0This 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 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures* within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE*PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the population.
The concentration limit for dissolved 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 in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits* can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for*Qualitative Detection and Quantitative Determination
-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic*Richfield Hanford Company Report ARH-SA-215 (June 1975).1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 013.1.1 -5 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.2 Revision 16 December 5, 2013 13.1.2 DNC 13.1.2 Liquid Effluents Dose The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials released in liquid effluents released to UNRESTRICTED AREAS shall be limited to: 0 a. < 1.5 mrem to the total body and < 5 mrem to any organ during any calendar quarter; and b. < 3 mrem to the total body and < 10 mrem to any organ during any calendar year.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Calculated dose to a A.1 Prepare and submit to the 30 days MEMBER OF THE NRC, pursuant to DNC 15.3, PUBLIC from the release a Special Report that of 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 been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DNC 13.1.2.0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.2-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.2 Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 S 0 S ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the facility times the limits. (including outside storage tanks, etc.).AND Immediately B.2 Verify that the limits of DNC 13.4 have not been exceeded.C. CONTINGENCY C.1 Prepare and submit to the 30 days MEASURE B.2 and NRC, pursuant to DNC 15.3, Associated a Special Report, as defined RESTORATION TIME not in 10 CFR 20.2203 (a)(4), of met. CONTINGENCY MEASURE A.1 shall also include the following:
(1) The corrective action(s)to be taken to prevent recurrence of exceeding the limits of DNC 13.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.
13.1.2-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.2 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.2.1 Determine cumulative dose contributions from liquid 31 days effluents for the current calendar quarter and the current calendar year in accordance with the methodology and parameters in the ODCM.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.2-3 S* KEWAUNEE POWER STATION ODCM 13.1.2 OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013*BASES This DNC is provided to implement the requirements of Sections lI.A, III.A and IV.A of Appendix S1, 10 CFR 50. The DNC implements the guides set forth in Section II.A of Appendix I. The*ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive
- material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably
- achievable." The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be 5) shown by calculational procedures based on models and data, such that the actual exposure of*a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
- The equations specified in the ODCM for calculating the doses due to the actual release rates of*radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of*Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"*Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing
- Appendix I," April 1977.1 S S S S S S S 0 S S S S S S S S S S S~13.1.2-4 S S S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.1 RADIOACTIVE LIQUID EFFLUENTS ODCM 13.1.3 Revision 16 December 5, 2013 13.1.3 DNC 13.1.3 Liquid Radwaste Treatment System The Liquid Radwaste Treatment System, as described in the ODCM, shall be used to reduce the radioactive material in liquid wastes prior to their discharge when the projected dose, due to the liquid effluent, to UNRESTRICTED AREAS would exceed in a 31 day period: a. > 0.06 mrem to the total body; or b. > 0.2 mrem to any organ.APPLICABILITY:
At all times, except for the parts of the system taken permanently out of service.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Radioactive liquid waste A.1 Prepare and submit to the 30 days being discharged without NRC, pursuant to DNC 15.3, treatment and in excess of a Special Report that the above limits, includes: (1) An explanation of why liquid radwaste was being discharged without treatment, identification of any non-functional
/inoperable equipment or subsystems, and the reason for the non-functional
/ inoperability, (2) ACTION(s) taken to restore the non-functional
/ inoperable equipment to FUNCTIONAL I OPERABLE status, and (3) Summary description of ACTION(s) taken to prevent a recurrence.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.3 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S VERIFICATION FREQUENCY DVR 13.1.3.1 Project the doses due to liquid effluents from the 31 days facility to UNRESTRICTED AREAS in accordance with the methodology and parameters specified in the ODCM.13.1.3-2 KEWAUNEE POWER STATION ODCM 13.1.3 w OFFSITE DOSE CALCULATION MANUAL Revision 16 0 December 5, 2013 BASES 0 The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This DNC implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section Il.A of Appendix 1, 10 CFR Part 50, for liquid effluents.
1 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1.3-30 0 0 0 S 0 S S S 0 0 0 S 0 0 0 0 0 0 S S 0 0 S 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.1.4 Revision 16 December 5, 2013 13.1 LIQUID EFFLUENTS 13.1.4 DNC 13.1.4 Liquid Holdup Tanks The quantity of radioactivity contained in unprotected outdoor liquid storage tanks shall be limited to less than the amount that would result in concentrations less than the limits in 10 CFR20, Appendix B, Table II, Column 2, at the nearest potable water supply and surface water supply in an UNRESTRICTED AREA, excluding tritium and dissolved or entrained gases.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits in any radioactive material.listed tank.AND A.2 Initiate measures to reduce 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> content to within the limits.AND A.3 Describe the events leading to Prior to submittal of the condition in the next Radioactive Radioactive Effluent Release Effluent Release Report. Report VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.1.4.1 Sample and analyze radioactive liquid located in 31 days during unprotected outdoor liquid storage tanks for level of addition of radioactivity.
radioactive liquid to the tanks 0 S S S 0 S S S S 13.1.4-1 0 S KEWAUNEE POWER STATION ODCM 13.1.4 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 13.1 LIQUID EFFLUENTS 13.1.4 Liquid Holdup Tanks 0 BASES 0 The tanks listed in this Normal Condition include outdoor tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents and do not have tank overflows and surrounding area drains connected to the radwaste treatment system.Technical 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 an uncontrolled release of any such tank's contents, the resulting concentration would be less than the limits of 10 CFR 20, Appendix B Table II, Column 2 at the nearest potable water supply and the nearest surface water supply in an UNRESTRECTED AREA. Tank quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures." 1 S S S S S S 0 S S S S S S S 0 0 S S S S S S 13.1.4-2 2 S S S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.1 Revision 16 December 5, 2013 13.2.1 Gaseous Effluents Dose Rate DNC 13.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
S 0 0 0 0 0 S 0 0 0 0 0 0 0 a. For noble gases, < 500 mrem/yr to the total body and< 3000 mrem/yr to the skin and b. For 1-131, 1-133, tritium and for all radionuclides in particulate form with half-lives > 8 days, < 1500 mrem/yr to any organ.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. The dose rate(s) at or A.1 Restore the release rate to Immediately beynd the SITE within the limit.BUOUNDARY due to radioactive gaseous effluents exceeds limits.B. CONTINGENCY B.1 Initiate a CR In accordance with MEASURES Corrective Action OR Program RESTORATION TIME AND not met.B.2 Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report CONTINGENCY MEASURE was not met in a timely manner.13.2.1 -1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL VERIFICATION REQUIREMENTS ODCM 13.2.1 Revision 16 December 5, 2013 VERIFICATION FREQUENCY DVR 13.2.1.1 The dose rate due to noble gases in gaseous In accordance with effluents shall be determined to be within the Table 13.2.1-1 above 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 with radionuclides 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 the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 13.2.1-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.1-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.1 Revision 16 December 5, 2013 Table 13.2.1-1 (Page 1 of 2)Radioactive Gaseous Waste Sampling and Analysis GASEOUS RELEASE TYPE TYPE OF ACTIVITY ANALYSIS SAMPLE TYPE SAMPLE FREQUENCY MINIMUM ANALYSIS FREQUENCY LOWER LIMIT OF DETECTION (LLD)(a)0 S 0 S 0 0 S 0 0 0 1. Waste Gas Storage Tank and Chemical and Volume Control System Holdup Tank 2. Containment Purge 3. Auxiliary Building and Containment Building Vent Principal Gamma Emitters (b)Principal Gamma Emitters (b)Principal Gamma Emitters (b)H-3 Grab Sample a.Grab Sample Grab Sample Silica Gel, Grab Sample Charcoal Sample Particulate Sample b. 1-131 Principal Gamma C. Emitters (b)(1-131, Others)Each Tank (d)Each Purge (d)31 days 31 days Continuous (c)Continuous (c)Continuous (c)Continuous (c)Continuous (c)Each Tank (d)Each Purge (d)31 days 31 days 7 days 7 days 31 days 92 days Continuous (c)1 x 10, 4ACi/ml 1 X 10-4 gCi/ml 1 x 10-4 Ci/ml 1 x 10 pCi/mI 3 x 10.12 iACi/ml 1 x 10.11 A.Ci/ml 1 x 10" l.Ci/ml 1 x 1011 o Ci/ml 1 x 10e8 gCi/ml Composite d. Gross Alpha Particulate Sample Composite e. Sr-89, Sr-90 Particulate Sample S S 0 S S S S S S S S 0 S S S S Noble Gases f. Gross Beta or Gamma Noble Gas Monitor 13.2.1 -3 0 KEWAUNEE POWER STATION ODCM 13.2.1 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Table 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 will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
LLD = 4.66
- Sb Where: EV*2.22 x 10 6"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 a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.(b) The principal gamma emitters for which the LLD requirement applies exclusively are the following radionuclides:
Kr- 0 87, 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 these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to ODCM 15.2.(c) The ratio of the sample flow rate to the sampled flow stream flow rate shall be known (based on sampler and ventilation system flow measuring devices or periodic flow estimates) for the time period covered by each dose or dose rate calculation made in accordance with ODCM DNC 13.2.1, 13.2.2, and 13.2.3.0 (d) Complete prior to each release.1 0 0 0 0 0 0 0 13.2.1 -4 01 0 0 0 KEWAUNEE POWER STATION ODCM 13.2.1 O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013* BASES O* This DNC is provided to ensure that the dose rates at any time to a MEMBER OF THE PUBLIC at or O beyond the SITE BOUNDARY are less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin. This also restricts releases, at all times, for the corresponding O thyroid dose rate above background to a child via the inhalation pathway to less than or equalto 1500 mrem/yr. These dose rate limits provide additioral assurance that radioactive material discharged in gaseous effluents will be maintained ALARA, and coupled with the requirements of ODCM DNC 13.2.2, ensure that the exposures of MEMBERS OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, will not exceed the annual average concentrations specified in Appendix B, Table 2, Column 1 of 10 CFR 20. For MEMBERS OF THE PUBLIC who may at times be 1 within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits* can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for* Qualitative Detection and Quantitative Determination
-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic O Richfield Hanford Company Report ARH-SA-215 (June 1975).0 0!0 0 0!0 0 0 0 0 0 0 0!0 0!0* 13.2.1- 5 0 O 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.2 Revision 16 December 5, 2013 13.2.2 Gaseous Effluent Dose -Noble Gas DNC 13.2.2 The air dose due to noble gases released in gaseous effluents from the facility 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, and b. < 10 mrad for gamma radiation and < 20 mrad for beta radiation during any calendar year.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. The calculated air dose at A.1 Prepare and submit to the 30 days or beyond the SITE NRC, pursuant to DNC 15.3, BOUNDARY due to noble gases released in gaseous a Special Report that effluents exceeds limits. (1) Identifies the cause(s)for exceeding the limit(s)and;(2) Defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DNC 13.2.2.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.2-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.2 Revision 16 December 5, 2013 S S 0 S 0 0 0 0 0 0 0 0 S 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the facility times the limits. (including outside storage tanks, etc.).AND Immediately B.2 Verify that the limits of DNC 13.4 have not been exceeded.C. CONTINGENCY C.1 Prepare and submit to the 30 days MEASURE B.2 and NRC, pursuant to DNC 15.3, Associated a Special Report, as defined RESTORATION TIME not in 10 CFR 20.2203 (a)(4), of CONTINGENCY MEASURE met. A.1 shall also include the following:
(1) The corrective action(s)to be taken to prevent recurrence of exceeding the limits of DNC 13.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.
13.2.2-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.2 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.2.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.2-3 W KEWAUNEE POWER STATION ODCM 13.2.2* OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013*BASES This DNC is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix 1 , 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 Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational
- procedures based on models and data such that the actual exposure of a MEMBER OF THE*PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
- The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating
- Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM*1 equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0*13.2.2-4 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.3 Revision 16 December 5, 2013 13.2.3 Gaseous Effluent Dose -Iodine, Tritium and Particulate DNC 13.2.3 The dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives
> 8 days, in gaseous effluents, released to areas at or beyond the SITE BOUNDARY (Plant Drawing A-408) shall be limited to the following:
- a. < 7.5 mrem to any organ during any calendar quarter, and b. < 15 mrem to any organ during any calendar year.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. The calculated dose from A.1 Prepare and submit to the 30 days the release of 1-131, 1-133, NRC, pursuant to DNC 15.3, tritium, and radionuclides a Special Report that in 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 been exceeds limits, taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with DNC 13.2.3.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.3-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.3 Revision 16 December 5, 2013 0 0 S 0 0 0 0 0 0 S 0 0 0 0 S 0 0 S 0 0 0 0 0 0 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Calculated dose to a B.1 Calculate the annual dose to Immediately MEMBER OF THE a MEMBER OF THE PUBLIC from the release PUBLIC which includes of radioactive materials in contributions from direct liquid effluents exceeds 2 radiation from the facility times the limits. (including outside storage tanks, etc.).AND B.2 Verify that the limits of DNC Immediately 13.4 have not been exceeded.C. CONTINGENCY C.1 Prepare and submit to the 30 days MEASURE B.2 and NRC, pursuant to DNC 15.3, Associated a Special Report, as defined RESTORATION TIME not in 10 CFR 20.2203 (a)(4), of CONTINGENCY MEASURE met. A.1 shall also include the following:
(1) The corrective action(s)to be taken to prevent recurrence of exceeding the limits of DNC 13.4 and the schedule for achieving conformance, (2) An analysis that estimates the dose to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s), and (3) Describes the levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations.
13.2.3-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL VERIFICATION REQUIREMENTS ODCM 13.2.3 Revision 16 December 5, 2013 VERIFICATION FREQUENCY DVR 13.2.3.1 Determine cumulative dose contributions for the 31 days current calendar quarter and current calendar year for 1-131, 1-133, tritium, and radionuclides in particulate form with half-lives
> 8 days in accordance with the methodology and parameters in the ODCM.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.3-3 0* KEWAUNEE POWER STATION ODCM 13.2.3* OFFSITE DOSE CALCULATION MANUAL Revision 16* December 5, 2013* BASES This DNC is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix* I, 10 CFR Part 50. The DNC's are the guides set forth in Section II.C of Appendix I. The contingency measures provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive
- materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably
- 1 achievable."* The ODCM calculational methods specified in the DVR's implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational
- procedures based on models and data, such that the actual exposure of a MEMBER OF THE* PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methodology and parameters for calculating the doses due to the actual* release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"* Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate limitations for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the* existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY.
The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation 0 with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0* 13.2.3- 4 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.2 RADIOACTIVE GASEOUS EFFLUENTS ODCM 13.2.4 Revision 16 December 5, 2013 13.2.4 GASEOUS RADWASTE TREATMENT SYSTEM DNC 13.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (Plant Drawing A-408) would be: 0 0 a. > 0.2 mrad for gamma radiation; or b. > 0.4 mrad for beta radiation; or c. > 0.3 mrem to any organ in 31 day period. (Ventilation Exhaust Treatment System only)At all times, except for the parts of the system taken permanently out of service.APPLICABILITY:
ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Radioactive gaseous A. 1 Prepare and submit to the 30 days waste is being discharged NRC, pursuant to DNC 15.3, without treatment, a Special Report that AND includes the following:
(1) Explanation of why Projected doses due to the gaseous radwaste was gaseous effluent, from the being discharged without facility, at and beyond the treatment, SITE BOUNDARY would (2) Identification of any exceed limits, non-functional I inoperable equipment or subsystems and the reason for the non-functional I inoperability, (3) ACTION(s) taken to restore the non-functional I inoperable equipment to FUNCTIONAL
/OPERABLE status, and (4) Summary description of ACTION(s) taken to prevent a recurrence.
13.2.4-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.4 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 VERIFICATION FREQUENCY DVR 13.2.4.1 Project the doses due to gaseous effluents from each 31 days facility at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.13.2.4-2 0 KEWAUNEE POWER STATION ODCM 13.2.4 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 BASES 0 The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." 0 This DNC implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B1 and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.4 -3 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.5 Revision 16 December 5, 2013 13.2 GASEOUS EFFLUENTS 0 0 0 0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 S 0 13.2.5 DNC 13.2.5 Gas Storage Tanks The radioactivity contained in each gas storage tank shall be limited to 5 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.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Level of radioactivity A.1 Suspend addition of Immediately exceeds the limits, radioactive material.AND A.2 Reduce tank contents to within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the limits.13.2.5-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.2.5 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.2.5.1 Verify quantity of radioactive material contained in 31 days each gas storage tank is < 52,000 curies of noble gases (considered as Xe-1 33). AND.--------
NOTE------
Not required to be performed if the most recent Reactor Coolant System specific activity DOSE EQUIVALENT 1-131 is< 1.0 pCi/gm Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.2.5-2 W KEWAUNEE POWER STATION ODCM 13.2.5* OFFSITE DOSE CALCULATION MANUAL Revision 16*! December 5, 2013*BASES This verification implements the requirement of Technical Specification 5.5.1 0.b. which requires a program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the offgas treatment system is less than the amount that would result in a*whole body exposure of > 0.5 rem to any individual in an UNRESTRICTED AREA, in the event of an uncontrolled release of the tanks contents.
Contents of the tank quantities shall*be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5,"Postulated Radioactive Release due to Waste Gas System Leak or Failure." 0Radiological analysis for a waste gas decay tank rupture assumes the activity in a gas decay tank is taken to be the maximum amount that could accumulate from operation with cladding 0 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 decay tank inventory is calculated assuming nuclide decay, degassing of the reactor coolant with*letdown at the maximum rate, and periodic purging to the gas decay tank. The maximum inventory for each nuclide during the degas and PURGE cycle is given in Appendix D,*Table D.7-1. (reference 1)The resultant dose consequence for this accident is 0.1 rem whole body at the SITE* BOUNDARY.
Summing the activities in USAR Table D.7-1 (reference
- 4) results in 42,792.74*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 when considered as Xe-133. Kewaunee Power Station does not have a calculation correcting the*waste gas decay tank activity to a SITE BOUNDARY consequence of < 0.5 rem, therefore by limiting the activity in a waste gas decay tank to that which results in 0.1 rem at the SITE*BOUNDARY, the 0.5 rem limit will not be exceeded.DVR 13.2.5 frequency is modified by a note that restricts performing the verification when*additions are made to a tank to only when the reactor coolant system DOSE EQUIVALENT
- Iodine 131 (DEI-131) activity is greater than 1.0 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/gm DEX-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 Gas 2. 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 Rupture Radiation Dose Analysis for the 7.4% Power Uprate Program.4. USAR Table D.7-1 Inventory of Gas Decay Tank After Shutdown and Degassing of*the RCS (Based on 1 percent of Fuel Defects)* 5. USAR Table D.8-1, Nuclide Parameters
- 13.2.5-3 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 16 December 5, 2013 13.3 INSTRUMENTATION 13.3.1 DNC 13.3.1 Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent monitoring instrumentation channels shown in Table 13.3.1-1 shall be FUNCTIONAL with: a. The minimum FUNCTIONAL channel(s) in service.b. The alarm/trip setpoints set to ensure that the limits of DNC 13.1.1 are not exceeded.APPLICABILITY:
During release via the monitored pathway.ACTIONS-..--.....
----------------
NOTE ---------------------
Separate NON-CONFORMANCE entry is allowed for each channel.NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Liquid effluent monitoring A.1 Suspend the release of Immediately instrumentation channel radioactive liquid effluents alarm/trip setpoint less monitored by the affected conservative than required.
channel.OR A.2 Declare the channel Immediately non-functional.
OR A.3 Change the setpoint so it Immediately is acceptably conservative.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.1 -1 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 16 December 5, 2013 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. One or more required B.1 Restore non-functional 30 days channels non-functional, channel(s) to FUNCTIONAL status.C. Liquid Radwaste Effluent Line (R-18) non-functional Prior to initiating an effluent prior to or during effluent release, complete sections releases.
C.1.1 and C.1.2 C.1.1 Analyze at least 2 Prior to initiating a independent samples in release accordance with Table 13.1.1-1.AND C.1.2 -----NOTE----Verification ACTION will be performed by at least 2 separate technically qualified members of the facility staff.Independently verify the Prior to initiating a release rate calculations and release discharge line valving.OR C.2 Suspend release of Immediately radioactive effluents via this pathway 13.3.1-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 16 December 5, 2013 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME----------------
NOTE---- --Failure to complete sampling and analysis prior to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the monitor is declared non-functional is a violation of this DNC.D.1 Collect and analyze grab D. Service Water System samples for gross radioactivity Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Effluent Line (R-20) non- (beta or gamma) at a lower limit of functional prior to or detection of at least 1 x 10-6 during effluent releases jiCi/ml.E. CONTINGENCY E.1 Initiate a CR In accordance with MEASURES Corrective Action OR Program RESTORATION TIME of AND A, B, C, or D not met.E.2 Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report CONTINGENY MEASURE was not met in a timely manner.I 0 0 0 S S S S S S S S S S S S S S 0 S 0 S S S S S S S S S S S S S S S S S S S 13.3.1 -3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS
NOTE----------------------
Refer to Table 13.3.1-1 to determine which DVRs apply for each function.-- ---- --------------
VERIFICATION FREQUENCY DVR 13.3.1.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DVR 13.3.1.2 Perform SOURCE CHECK. Prior to release DVR 13.3.1.3 Perform SOURCE CHECK. 31 days DVR 13.3.1.4 Perform CHANNEL FUNCTIONAL TEST 92 days DVR 13.3.1.5 Perform CHANNEL CALIBRATION.
18 months 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 13.3.1-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.1 Revision 16 December 5, 2013 Table 13.3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation REQUIRED CHANNELS PER VERIFICATION INSTRUMENT INSTRUMENT REQUIREMENTS
- 1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release a. Liquid Radwaste Effluent Line (R-18) 1 DVR 13.3.1.1 DVR 13.3.1.2 DVR 13.3.1.4 DVR 13.3.1.5 2. Gross Beta or Gamma Radioactivity Monitors Providing Alarm but not Providing Automatic Termination of Release DVR 13.3.1.1 a. Service Water System Effluent Line 1 DVR 13.3.1.3 (R-20) DVR 13.3.1.4 DVR 13.3.1.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.1 -5 0* KEWAUNEE POWER STATION ODCM 13.3.1 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013*BASES 0*The radioactive liquid effluent instrumentation, required FUNCTIONAL by this DNC, is provided to monitor and control, as applicable, the releases of radioactive materials in*liquid effluents during actual or potential releases of liquid effluent.
The alarm/trip
- setpoints for these instruments shall be calculated and adjusted in accordance with*methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten (10) times the values 10 CFR Part 20, Appendix B, Table 2, Column 2.*The FUNCTIONALITY and use of this instrumentation is consistent with the appropriate
- requirements of General Design Criteria 60, 63 and 64 of Appendix A to~10 CFR Part 50.*0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0*13.3.1 -6 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 16 December 5, 2013 13.3 INSTRUMENTATION 13.3.2 Radioactive Gaseous Effluent Monitoring Instrumentation DNC 13.3.2 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 13.3.2-1 shall be 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 are 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 TIME A. Gaseous effluent A.1 Suspend the release of Immediately monitoring instrumentation radioactive gaseous channel alarm/trip setpoint effluents monitored by the less conservative than affected channel.required.OR A.2 Declare the channel Immediately non-functional.
OR A.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) to FUNCTIONAL.
FUNCTIONAL status.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.2-1
.0 0 S S 0 0 0 0 0 0 0 0 0 S 0 S S 0 0 S 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 16 December 5, 2013 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. Noble Gas Activity effluent NOTE ------Prior to initiating a monitoring for the Waste Prior to initiating an release Gas Holdup System and effluent release, complete Chemical and Volume sections C.1.1 and C.1.2.Control System Holdup Tanks non-functional prior to or during releases C.1.1 Analyze at least 2 independent samples in accordance with Table 13.2.1-1.AND C. 1.2 ------NOTE ----------------
Verification ACTION will Prior to initiating a be performed by at least 2 release technically qualified members of the facility staff.Independently verify the release rate calculations and discharge line valving.OR C.2 Suspend release of Immediately radioactive effluents via this pathway D. Noble Gas Activity effluent D.1 Take grab samples. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> monitoring for the Auxiliary Building Ventilation System AND and the Condenser Evacuation System Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> non-functional prior to or thereafter during releases AND D.2 Analyze samples for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of gross activity, sampling completion 13.3.2-2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 16 December 5, 2013 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME E. Noble Gas Activity effluent E.1 Suspend PURGING of Immediately monitoring for the Radioactive effluents via Containment Purge this pathway.System, 2" line and 36" duct (auto-isolation) non-functional prior to or during releases F. Sampler Flow rate F. 1 Estimate the flow rate for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Measuring Devices (for the the non-functional Auxiliary Building channel(s).
AND Ventilation or Containment Building Ventilation Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Sampler) non-functional thereafter prior to or during releases G. Radioiodine and Particulate G.1 Continuously collect 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Samplers (for the samples using auxiliary Auxiliary Building sampling equipment as required in Ventilation or Containment Table 13.2.1-1.Building Ventilation system) non-functional prior to or during releases H. CONTINGENCY H.1 Initiate a CR In accordance with MEASURES Corrective Action OR Program RESTORATION TIME A, B, AND C, D, E, F, orG not met.H.2 Explain in the next In accordance with Radioactive Effluent Radioactive Effluent Release Report why the Release Report CONTINGENCY MEASURE was not met in a timely manner..0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 S 0 0 0 S 0 S 13.3.2-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.3.2.1 Perform CHANNEL CHECK. Prior to release DVR 13.3.2.2 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DVR 13.3.2.3 Perform CHANNEL CHECK. 7 days DVR 13.3.2.4 Perform SOURCE CHECK. Prior to release DVR 13.3.2.5 Perform SOURCE CHECK. 31 days DVR 13.3.2.6 Perform CHANNEL FUNCTIONAL TEST. 92 days DVR 13.3.2.7 Perform CHANNEL CALIBRATION.
18 months 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.2-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.3.2 Revision 16 December 5, 2013 0I 0I 0 0 0 Table 13.3.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT REQUIRED NON- VERIFICATION CHANNELS PER CONFORMANCE REQUIREMENTS INSTRUMENT
- 1. Waste Gas Holdup System DVR 13.3.2.1 DVR 13.3.2.4 a. Noble Gas Activity Monitor 1 C DVR 13.3.2.6 (R-13 or R-14) DVR 13.3.2.7 2. Condenser Evacuation System DVR 13.3.2.2 DVR 13.3.2.5 a. Noble Gas Activity (R-15) 1 D DVR 13.3.2.6 DVR 13.3.2.7 3. Auxiliary Building Vent a. Noble Gas Activity Monitor 1 D DVR 13.3.2.2 (R-13 or R-14) DVR 13.3.2.5 DVR 13.3.2.6 DVR 13.3.2.7 b. Radioiodine and 1 G DVR 13.3.2.3 Particulate Sampler (R-13 or R-14)1 F DVR 13.3.2.2 c. Sample Flow-Rate Monitor DVR 13.3.2.6 (R-13 or R-14) DVR 13.3.2.7 4. Containment Building Vent a. Radioiodine and 1 G DVR 13.3.2.3 Particulate Sampler (R-21)1 F DVR 13.3.2.2 b. Sample Flow-Rate Monitor DVR 13.3.2.6 (R-21) DVR 13.3.2.7 5. Containment Purge 2" line DVR 13.3.2.2 a. Noble Gas Activity Monitor 1 E DVR 13.3.2.5 (R-13 or R-14) DVR 13.3.2.6 DVR 13.3.2.7 6. Containment Purge 36" line DVR 13.3.2.2 DVR 13.3.2.4 a. Noble Gas Activity Monitor E DVR 13.3.2.6 (R-12 or R-21) DVR 13.3.2.7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.3.2-5 S* KEWAUNEE POWER STATION ODCM 13.3.2 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 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 in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm/trip will occur prior to exceeding the dose rate limits of ODCM DNC 13.2.1. The*FUNCTIONALITY and use of this instrumentation is consistent with the requirements of*General Design criteria 60, 63 and 64 in Appendix A to 10 CFR Part 50.1 0 0 S 0 S S S S S S S S S S S S S S S S S S SO S S S S*13.3.2 -6 S 0 S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL 13.4 RADIOACTIVE EFFLUENTS TOTAL DOSE ODCM 13.4.1 Revision 16 December 5, 2013 13.4.1 Radioactive Effluents Total Dose DNC 13.4.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrem to the total body or any organ, except the thyroid, which shall be limited to < 75 mrem.APPLICABILITY:
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Estimated dose or dose A.1 Verify the condition resulting Immediately commitment due to direct in doses exceeding these radiation and the release limits has been corrected.
of radioactive materials in liquid or gaseous effluents exceeds the limits.B. CONTINGENCY B.1 ---------NOTE ----MEASURES A.1 and This is the Special Report RESTORATION TIME not required by DNC 13.1.2, met. 13.2.2, or 13.2.3 supplemented with the following.
30 days Submit a Special Report, pursuant to DNC 15.3, including a request for a variance in accordance with the provisions of 40 CFR 190. This submission is considered a timely request, and a variance is granted until staff ACTION on the._ request is complete.0 0 0 0 6 0 6 0 0 0 0 0 0 0 S S S 0 S S S 0 S S S S S S S S S S S S S S S S S S S S 0 S 13.4.1 -1 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 13.4.1 Revision 16 December 5, 2013 VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY DVR 13.4.1.1 Cumulative dose contributions from liquid and 12 months gaseous effluents shall be determined in accordance with VERIFICATION REQUIREMENTS 13.1.2.1, 13.2.2.1, and 13.2.3.1 in accordance with the methodology and parameters in the ODCM.DVR 13.4.1.2 Cumulative dose contributions from direct radiation 12 months from the 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 13.4.1 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 6 BASES S This normal condition is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The DNC requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive 0 effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the facility remains within twice the dose design objectives of Appendix I, and if direct radiation 0 doses from the facility are kept small.The Special Report will describe a course of ACTION that should result in the limitation of the 0 annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible.
If the dose to any 0 MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff ACTION is completed.
The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM Normal Condition 5 13.3.1 and 13.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.4.1-3 3 0 0 0 0* KEWAUNEE POWER STATION ODCM 13.5.1 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0* 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING
- I 13.5.1 Monitoring Program This 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.0 The radiological environmental monitoring program required by this DNC provides 0representative measurements of radiation and of radioactive materials in those exposure*pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.
This monitoring program*implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the 0effluent 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.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 013.5.1 -1 0 KEWAUNEE POWER STATION ODCM 13.5.2 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING 13.5.2 Land Use Census Program S This Kewaunee Land Use Census Program is implemented by the RADIOLOGICAL 0 ENVIRONMENTAL MONITORING MANUAL (REMM) and Land Use Census Program procedure.
BASES 0 0 This DNC is provided to ensure that changes in the use of areas at and beyond the SITE 0 BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/M 2.0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.5.2-1 0 0 0 0 S S* KEWAUNEE POWER STATION ODCM 13.5.3 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013*13.5 RADIOLOGICAL ENVIRONMENTAL MONITORING
- 13.5.3 Interlaboratory Comparison Program This Kewaunee Interlaboratory Comparison Program is implemented by the RADIOLOGICAL
- ENVIRONMENTAL MONITORING MANUAL (REMM) and approved station procedures.
BASES 0 The requirement for participation in an approved Interlaboratory Comparison Program is 0provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring (developed using the guidance in*Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April*1975) in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.5.3-1 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 14.1 Revision 16 December 5, 2013 14.0 DESIGN FEATURES 14.1 GASEOUS AND LIQUID EFFLUENT RELEASE POINTS 14.1.1 Plant drawing A-408, "Radiological Survey Site Map" depicts the site area by illustrating the SITE BOUNDARY and the restricted areas. Plant drawing A-449,"Plan of Plant Area, Fence, Lighting, and CCTV Support Structure" shows the layout of the site buildings.
MEMBERS OF THE PUBLIC are restricted from access to all areas of the Owner Controlled Area (OCA).14.1.2 Figure 14.1-1 presents the locations of radioactive effluent release points at the plant. The plant drawings referenced above are not included as part of the ODCM but can be found in the plant drawing system.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 14.1 -1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 14.1 Revision 16 December 5, 2013 FIGURE 14.1-1 KE4ýAUNHI COUNTYt XAL f"Sl LalrA 1W W A CaNTAINUEN1 -L~L*4~VENT LEAATIDS 7T5'3 AUiXLARY But)I',% VENT ELEVaTIMv4 675*-EFFLIJENr J0JD 0DiS~iroE ELF-ADiON 580, 14.1 -2 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 15.1 Revision 16 December 5, 2013 15.0 ADMINISTRATIVE CONTROLS 15.1 Major Changes to Radioactive Waste Systems(1)Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid)shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by 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 Part 50.59, b. Sufficient information to totally support the reason for the change without benefit of additional or supplemental information, c. A description of the equipment, components and processes involved and the interfaces with other plant systems, d An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto, e. An evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto, f. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change, and h. Documentation of the fact that the change was reviewed and found acceptable by the FSRC.Changes shall become effective upon review and acceptance by the FSRC.0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (')Licensees may choose to submit the information called for in this requirement as part of the periodic USAR update.15.1 -1 0 0* KEWAUNEE POWER STATION ODCM 15.2 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 S*15.0 ADMINISTRATIVE CONTROLS* 15.2 Radioactive Effluent Release Report 0*The Radioactive Effluent Release Report to be submitted by May 1 of each year shall include: a. A summary of the quantities of radioactive liquid and gaseous effluents and solid*waste released from the facility following the format of Regulatory Guide 1.21,*"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974.b. An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing*on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind*speed, wind direction, and atmospheric stability.
In lieu of submission with the*Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data onsite in a file that shall be provided to*the NRC upon request.0 c. An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the facility during the previous calendar year.0 d. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from facility releases and other nearby uranium fuel cycle sources, 01 including doses from primary effluent pathways and direct radiation, the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
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).1 0 0 0 0 0 S 0 0 0 0* 15.2-1 0 0 0 S 0 KEWAUNEE POWER STATION ODCM 15.2 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 e. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility.
The material 0 provided shall be consistent with the objectives outlined in the ODCM and the PCP, and in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.f. A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.g. Any changes made during the reporting period to the PROCESS CONTROL S PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to DNC 13.5.2.0 0 S 0 0 0 S 0 0 S 0 S S 0 0 0 S S S S 0 0 0 0 15.2-2 0 0 0 0
-KEWAUNEE POWER STATION ODCM 15.3* OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013 015.0 ADMINISTRATIVE CONTROLS 0 15.3 Special Reports 0 Special reports may be required covering inspections, tests, and maintenance activities.
These special reports are determined on an individual basis. Their preparation and submittal are*designated in the ODCM Contingency Measures for each Normal Condition.
Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix*D, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S.Nuclear Regulatory Commission, Washington D.C. 20555 within the time period specified for each report.*These Special Report(s) are in lieu of a Licensee Event Report 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 015.3- 1 0 0 0 Kewaunee Power Station Offsite Dose Calculation Manual PART II -CALCULATIONAL METHODOLOGIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0
- KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0*1.0 LIQUID EFFLUENTS METHODOLOGY
1.1 Radiation
Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls installed at Kewaunee for 0controlling and monitoring normal radioactive material releases in accordance with 10*CFR 50, Appendix A, Criteria 60 and 64, are summarized as follows:*1) Alarm (and Automatic Termination)
-R-18 provides this function on the liquid radwaste effluent line.2) Alarm (only) -R-20 provides this function for the Service Water discharges.
0 3) Composite Samples -Samples are collected weekly from the Turbine Building Sump and analyzed by gamma spectroscopy.
The weekly samples are*composited for monthly tritium and gross alpha analyses and for quarterly Sr-89,*Sr-90, and Fe-55 analyses.* 4) Liquid Tank Controls -All radioactive liquid tanks are located inside the Auxiliary Building and contain the suitable confinement systems and drains to prevent direct, unmonitored release to the environment.
A liquid radioactive waste flow*diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 1.* 1.2 Liquid Effluent Monitor Setpoint Determination
- Per the requirements of Technical Specification 5.5.3.b and ODCM Normal*Condition 13.3.1, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of ODCM Normal Condition 13.1.1 are met (i.e., the concentration of radioactive material released in liquid*effluents to UNRESTRICTED AREA shall be limited to ten times the concentrations
- specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides and 2.OE-04 p Ci/ml for dissolved or entrained noble gases). The following equation 1 must be satisified
- to meet the liquid effluent restrictions:
c< 1OxC(F+f)
(1.1)0f 0 0 0 0 0 0* 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 1.0-1 0 0 0 0 KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 where: 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 2x10-4 pCi/ml.C = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity 0 concentration in the effluent line prior to dilution and subsequent release; the 0 setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of ODCM Normal Condition 13.1.1. 0 0 f = the flow rate at the radiation monitor location in volume per unit time, but in the 0 same units as F, below.0 F = the dilution water flow rate as measured prior to the release point, in volume per unit time.[Note that if no dilution is provided, c < C. Also, note that when (F) is large compared to (f), then (F + f) = F.]0 1.2.1 Liquid Effluent Monitors (Radwaste and Service Water)The setpoints for the liquid effluent monitors at the Kewaunee Power Station are determined by the following equations:
0 SSW xSENi)SP < +bkg (1.2)C, x RR Zi0xEC0 where: 0 SP = alarm setpoint corresponding to the maximum allowable release rate (cpm)C = the concentration of radionuclide "i" in the liquid effluent (pCi), to include gamma emitters only 10xECi= ten times the EC value corresponding to radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml) 0 1.0-2 0 0 0 0 0 O O KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 O SENi the sensitivity value to which the monitor is calibrated for O radionuclide "i" (cpm per pCi/ml). The default calibration value from Table 1.1 may be used for gamma emitting radionuclides in lieu of nuclide specific values.O SW = the service water flow rate (dilution water flow) at the time of release (gal/min)0 O 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 periods when the service water dilution is at its lowest. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.At its lowest value, SW will equal RR and equation (1.2) reverts to the following 0 equation: 0 X(C 1 xSEN.)O SP ' bkg (1.3)Z (IOx ECO)0 1.2.2 Conservative Default Values Non-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) are not detected by the effluent monitor and, therefore, are not directly included in the above setpoint 0equation.
These non-gamma radionuclides can, however, contribute a sizable fraction of the total EC limit (refer to Appendix C). The method specified below for establishing default setpoints provides conservatism to account for these non-gamma emitters and ensures that the setpoint meets the requirements of ODCM O 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 for Kewaunee.
They are based upon the following:
0 O a) substitution of the default effective EC (ECe) value of 1.OE-06 pCi /ml (refer to Appendix C for justification), 0 O where: OECe -CI (1.4)(ECi)0 O ~1.0- 3 0 0 0 0 O KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 b) 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.
0 The default setpoint equation is provided below: sp! ECex SENxSW +bkg (1.5)RR 1.3 Liquid Effluent Concentration Limits -10 CFR 20 0 0 ODCM Normal Condition 13.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Service Water System) to less than ten times the concentrations as specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2E-04 pCi/ml. Release rates are controlled and radiation monitor alarm setpoints are established to ensure that these concentration limits are not exceeded.
In the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of ODCM Normal Condition 13.1.1 may be performed using the following equation: where: 0 0-[(C, +(IOxEC,))x(RR+SW)]<
1 (1.6)C 1 = concentration of radionuclide "i" in the undiluted liquid effluent (pCi/ml)0 10xECj = ten times the EC value corresponding to radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 2 (pCi/ml)0= 2E-04 pCi/ml for dissolved or entrained noble gases RR = the liquid effluent release rate (gal/min)SW = the service water flow rate (dilution water flow) at the time of the 0 release (gal/min)1 0 0 0 1.0-4 0 0 0 0 0
- KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0* 1.4 Liquid Effluent Dose Calculation
-10 CFR 50* ODCM Normal Condition 13.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from the Kewaunee Power Station to: 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.0 Per Verification Requirement 13.1.2.1, the following calculational methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from 0Kewaunee.
D0 1.67E-02x VOL= 0 -x-'Z(C, x A 1 o) (1.7)SW 0 where: 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)0 0 0 0 0 01.0- 5 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 16 December 5, 2013 The site-related ingestion doses/dose commitment factors (Ai,) are presented in Table 1.2 and have been derived in accordance with guidance of NUREG-0133 by the equation: Ai. = 1.14E+ 05[(UI +D,,)+(UF x BF;)]DF, (1.8)where: A 1 o= composite dose parameter for the total body or critical organ "o" of an adult for radionuclide "i", for the fish ingestion and water consumption pathways (mrem/hr per pCi/ml)1.14E+05 = conversion factor (pCi/pCi x ml/kg -hr/yr)U, = adult water consumption (730 kg/yr)D= dilution factor from the near field area within % mile of the release point to the nearest potable water intake for the adult water consumption (842, unitless)UF adult fish consumption (21 kg/yr)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 of ODCM Normal Condition 13.1.2 and Verification Requirement 13.1.2.1 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per Verification Requirement 13.1.1.1, Table 13.1.1-1.Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Table 13.1.1-1.2Adapted from the Kewaunee Final Environmental Statement,Section V.1.0-6 S 0 0 0 0 0 S 0 0 S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 0* KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0* 1.5 Liquid Effluent Dose Projections ODCM Normal Condition 13.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to e5 release when the 31 day projected doses exceed: 0* ,* 0.06 mrem to the total body, or 0l .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 period S 31 = the number of days in a 31 day period 0 S 0 0 0 0 S 0 0l 1.0-7 0 0 S S S S KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 1.6 Onsite Disposal of Low-Level Radioactively Contaminated Waste Streams During the normal operation of Kewaunee, the potential exists for in-plant process streams, which are not normally radioactive to become contaminated with very low levels of radioactive materials.
These waste streams are normally separated from the radioactive streams. However, due mainly to infrequent, minor system leaks, and anticipated operation occurrences, the potential exists for these systems to become slightly contaminated.
At Kewaunee, the secondary system demineralizer resins, the service water pretreatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels. During the yearly testing of a batch of pre-treatment S sludge, it was found approximately 15,000 cubic feet of sludge had been contaminated 5 with Cs-137 and Co-60.The potential radiation doses to MEMBERS OF THE PUBLIC from these onsite disposal methods are well below 1 mrem per year. This dose is in keeping with the guidelines of the National Council on Radiation Protection (NCRP) in their Report No. 91, in which the NCRP established a "negligible individual risk level" at a dose rate of 1 mrem per year.It is for these type wastes that the NRC acknowledged in Information Notice No. 83-05 and 88-22 that the levels of radioactive material are so low that control and disposal as a radwaste are not warranted.
The potential risks to man are negligible and the disposal S costs as a radwaste are unwarranted and costly. 5 This waste material will be monitored and evaluated prior to disposal to ensure its S radioactive material content is negligible.
It shall then be disposed of in a normal 5 conventional manner with records being maintained of all materials disposed of using these methods.S Approvals for specific alternate disposal methods are listed in Appendix D. Currently, only service water pretreatment (SWPT) facility lagoon sludge and sewage treatment plant sludge have been approved for disposal by land spreading.
1 S S S 0 0 S 1.0-8 8 S S S S S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 16 December 5, 2013 Legend= = San4AofMonitot
= (Isol&=o Devoe=(Damper or Valve)-= Auto Isolation=.... This Flow Pah a on abe usHd floeted s CooMty with ODCM and'rectrncal S lfl caton (CAB1074)ODCM FIGURE 1 LIQUID RADIOACTIVE EFFLUENT FLOW DIAGRAM Graphic, No. CS7537 1.0-9 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 16 December 5, 2013 Table 1.1 Parameters for Liquid Alarm Setpoint Determinations Parameter Actual Value Default Value Units Comments ECe** calculated 1.OE-06 PCi/ml Calculate for each batch to be released dN/A pCi/mI Taken from gamma spectral analysis C measured N/of liquid effluent Taken from 10 CFR 20, Appendix B, EC 1 as determined N/A pCi/mI Table 2, Col. 2 Sensitivity (SEN)R-18 as determined 1.OE+08 cpm per Radwaste effluent R-20 as determined 1.OE+08 pCi/ml Service Water Release Rate (RR)R-18 as determined 8.OE+01 Determined prior to release; release rate can be adjusted for ODCM limit gpm compliance R-20*** as determined 8.OE+02 Service Water Background (bkg) Nominal values only; actual values R-18 as determined 2.OE+03 cpm may be used in lieu of these reference R-20 as determined 6.OE+01 values Setpoint* (SP)R-18**** calculated 6.25E+04+bkg cpm Default alarm setpoints; more R-20 calculated 1.OOE+03+bkg conservative values may be used as deem appropriate and desirable for assuring regulatory compliance and for maintaining 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 the radiation monitor in accordance with CAP 37265 and DCR 26981 (5.OOE+05+bkg cpm).S 0 S 0 S S 0 S S S S S S S S S 0 S 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S S 1.0-10 0 0 S 0 0 S 0 0 S 0 0 0 S S 0 0 0 S 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OD(OFFSITE DOSE CALCULATION MANUAL Rev Dec Table 1.2 (Page 1 of 2)Site Related Ingestion Dose Commitment Factors (mrem/hr oer uCi/ml)3M 1.0 ision 16 ember 5, 2013 Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 -3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 3.30E-1 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 4.09E+2 P-32 1.39E+6 8.62E+4 5.36E+4 -1.56E+5 Cr-51 -1.28E+0 7.63E-1 2.81 E-1 1.69E+0 3.21E+2 Mn-54 -4.38E+3 8.36E+2 -1.30E+3 1.34E+4 Mn-56 -1.10E+2 1.96E+1 -1.40E+2 3.52E+3 Fe-55 6.61E+2 4.57E+2 1.06E+2 -2.55E+2 2.62E+2 Fe-59 1.04E+3 2.45E+3 9.40E+2 -6.85E+2 8.17E+3 Co-57 -2.11E+1 3.51E+1 -5.36E+2 Co-58 -8.99E+1 2.02E+2 -1.82E+3 Co-60 -2.58E+2 5.70E+2 -4.85E+3 Ni-63 3.13E+4 2.17E+3 1.05E+3 -4.52E+2 Ni-65 1.27E+2 1.65E+1 Cu-64 1.01E+1 Zn-65 2.32E+4 7.38E+4 Zn-69 4.93E+1 9.43E+1 Br-82 --7.52E+0 --4.18E+2 4.72E+0 -2.53E+1 -8.57E+2 3.33E+4 -4.93E+4 -4.65E+4 6.56E+0 -6.13E+1 -1.42E+1 2.27E+3 --2.61 E+3 4.05E+1 --5.83E+1 Br-83 Br-84 5.24E+1 -4.12E-4 Br-85 2.15E+0 --Rb-86 1 .1E+5 4.71 E+4 -1.99E+4 Rb-88 2.90E+2 1.54E+2 -4.OOE-9 Rb-89 1.92E+2 1.35E+2 -Sr-89 2.24E+4 6.44E+2 -3.60E+3 Sr-90 5.52E+5 1.35E+5 -1.59E+4 Sr-91 4.13E+2 1.67E+1 1.97E+3 Sr-92 1.57E+2 6.77E+0 -3.1OE+3 Y-90 5.85E-1 1.57E-2 -6.21E+3 Y-91m 5.53E-3 2.14E-4 -1.62E-2 Y-91 8.58E+0 2.29E-1 -4.72E+3 Y-92 5.14E-2 1.50E-3 -9.OOE+2 Y-93 1.63E-1 4.50E-3 --5.17E+3 Zr-95 2.70E-1 8.67E-2 5.87E-2 -1 36E-1 2.75E+2 Zr-97 1.49E-2 3.01E-3 1.38E-3 -4.55E-3 9.34E+2 Nb-95 4.47E+2 2.49E+2 1.34E+2 -2.46E+2 1.51E+6 Nb-97 3.75E+0 9.48E-1 3.46E-1 -1.11E+O 3.50E+3_Mo-99 -1.07E+2 2.04E+1 -2.43E+2 2.49E+2 Tc-99m 9.11E-3 2.58E-2 3.28E-1 -3.91E-1 1.26E-2 1.52E+1 Tc-101 9.37E-3 1.35E-2 1.32E-1 -2.43E-1 6.90E-3 Ru-103 4.61E+O 1.99E+0 -1.76E+1 5.39E+2 Ru-105 3.84E-1 1.52E-1 -4.96E+O 2.35E+2 Ru-106 6.86E+1 8.68E+0 -1.32E+2 4.44E+3 Rh-103m ......- -...Rh-106 --1.0-11 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 1.0 Revision 16 December 5, 2013 Table 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-LLI Ag-110m 1.04E+0 9.62E-1 5.71E-1 -1.89E+0 -3.92E+2 Sb-124 9.48E+O 1.79E-1 3.76E+0 2.30E-2 7.38E+O 2.69E+2 Sb-125 6.06E+0 6.77E-2 1.44E+0 6.16E-3 4.67E+0 6.67E+1 Te-125m 2.57E+3 9.31 E+2 3.44E+2 7.73E+2 1.04E+4 -.1.03E+4 Te-127m 6.49E+3 2.32E+3 7.91 E+2 1.66E+3 2.64E+4 -2.18E+4 Te-127 1.05E+2 3.79E+1 2.28E+1 7.81 E+1 4.29E+2 -8.32E+3 Te-129m 1.1OE+4 4.11E+3 1.74E+3 3.79E+3 4.60E+4 -5.55E+4 Te-129 3.01E+1 1.13E+1 7.33E+0 2.31E+1 1.27E+2 -2.27E+1 Te-131m 1.66E+3 8.11E+2 6.76E+2 1.28E+3 8.22E+3 8.05E+4 Te-131 1.89E+1 7.89E+0 5.96E+0 1.55E+1 8.27E+1 2.67E+0 Te-132 2.42E+3 1.56E+3 1.47E+3 1.73E+3 1.50E+4 7.39E+4 1-130 2.79E+1 8.23E+1 3.25E+1 6.97E+3 1.28E+2 7.08E+1 1-131 1.54E+2 2.20E+2 1.26E+2 7.20E+4 3.76E+2 5.79E+1 1-132 7.49E+0 2.00E+1 7.01E+0 7.01E+2 3.19E+1 3.76E+0 1-133 5.24E+1 9.11E+1 2.78E+1 1.34E+4 1.59E+2 8.19E+1 1-134 3.91E+0 1.06E+1 3.80E+0 1.84E+2 1.69E+1 9.26E-3 1-135 1.63E+1 4.28E+1 1.58E+1 2.82E+3 6.86E+1 4.83E+ 1 Cs-134 2.98E+5 7.09E+5 5.79E+5 -2.29E+5 7.61E+4 1.24E+4 Cs-136 3.12E+4 1.23E+5 8.86E+4 -6.85E+4 9.39E+3 1.40E+4 Cs-137 3.82E+5 5.22E+5 3.42E+5 -1.77E+5 5.89E+4 1.01 E+4 Cs-138 2.64E+2 5.22E+2 2.59E+2 -3.84E+2 3.79E+1 2.23E-3 Ba-139 1.02E+0 7.30E-4 3.00E-2 -6.83E-4 4.14E-4 1.82E+0 Ba-140 2.15E+2 2.69E-1 1.41E+1 -9.16E-2 1.54E-1 4.42E+2 Ba-141 4.98E-1 3.76E-4 1.68E-2 -3.50E-4 2 13E-4 -Ba-142 2.25E-1 2.31 E-4 1.42E-2 -1.95E-4 .31 E-4 La-140 1.52E-1 7.67E-2 2.03E-2 --5.63E+3 La-142 7.79E-3 3.54E-3 8.82E-4 --2.59E+1 Ce-141 3.17E-2 2.14E-2 2.43E-3 -9.95E-3 8.19E+1 Ce-143 5.58E-3 4.13E+0 4.57E-4 -1.82E-3 f 1.54E+2 Ce-144 1.65E+0 6.90E-1 8.87E-2 -4.10E-1 .5.58E+2 Pr-143 5.60E-1 2.25E-1 2.77E-2 -1.30E-1 2.45E+3 Pr-144 1.83E-3 7.61E-4 9.31E-5 -4.29E-4 Nd-147 3.83E-1 4.42E-1 2.65E-2 -2.59E-1. 2.12E+3 W-187 2.96E+2 2.47E+2 8.65E+1 --8.10E+4 Np-239 2.97E-2 2.92E-3 1.61E-3 -9.10E-3 -5.98E+2 0 0 S 0 0 S 0 S 0 S 0 0 S 0 S 0 S S S 0 S S S 0 1.0-12
- KEWAUNEE POWER STATION ODCM 1.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013*Table 1.3*Bioaccumulation Factors (BFi)(pCi/kg per pCi/liter)*
Element Freshwater Fish H 9.OE-01 SC 4.6E+03 Na 1.OE+02 P 3.OE+03 Cr 2.OE+02 Mn 4.0E+02 Fe 1.OE+02 Co 5.OE+01* Ni 1.0E+02 Cu 5.OE+01 Zn 2.OE+03 Br 4.2E+02 Rb 2.OE+03 Sr 3.OE+01 Y 2.5E+01 Zr 3.3E+00*Nb 3.OE+04 Mo 1.OE+01 Tc 1.5E+01 Ru 1.OE+01 Rh 1.0E+01 Ag 2.3E+00 Sb 1.0E+00 Te 4.OE+02 I 1.5E+01 Cs 2.0E+03 Ba 4.OE+00 La 2.5E+01 Ce 1.OE+00 Pr 2.5E+01 Nd 2.5E+01 W 1.2E+03 S1Np.0E+01 0 Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which is adapted from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564,*Rev. 1, October 1972.0 0 0 0 S*1.0- 13 0 0 0 0 0 KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 20130 2.0 Gaseous Effluents Methodology S 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Kewaunee for controlling and monitoring normal radioactive material releases in accordance with 10 CFR 50, Appendix A, Criteria 60 and 64, are summarized as follows: 2.1.1 Waste Gas Holdup System The vent header gases are collected by the Waste Gas Holdup System. Gases may be recycled to provide cover gas for the 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 0 discharged via the Auxiliary Building vent. R-13 and/or R-14.provide noble gas monitoring and automatic isolation.
In some cases, the gas in the CVC HUTs will not be able to be completely depressurized to the 5 WGDTs. CVCs HUTs will be isolated and discharged via the Auxiliary Building Vent. R-13 and/or R-14 provide noble gas monitoring, and additional administrative controls are required in lieu of automatic isolation.
During a planned release, the administrative controls include the presence of an operator in the Aux Building if R-13/R-14 levels are below 5,000 cpm. If levels are above 5,000 but below 10,000 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 levels exceed 10,000 cpm. 5 2.1.2 Condenser Evacuation System 0 S The air ejector discharge is monitored by R-15. Releases from this system are normally via the Auxiliary Building vent and are monitored by R-13 and/or R-14.0 2.1.3 Containment Purge Containment purge and ventilation is via the containment stack for the 36-inch RBV system but 5 via the auxiliary building stack for the 2-inch vent and mini-purge blower system. The stack radiation 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.
2 S S 2.0-1 S S S S 0* KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013*2.1.4 Auxiliary Building Vent SI The Auxiliary Building vent receives discharges from the waste gas holdup system, condenser evacuation system, fuel storage area ventilation, Auxiliary Building radwaste processing area ventilation, 2-inch containment pressure relief purge/vent system, and Auxiliary Building general* area. All effluents pass through the R-13 and/or R-14 channels which contain: 0 a noble gas monitor 0 5* an iodine sampler, and 0 .a particulate sampler.The noble gas monitor provides auto isolation of any waste gas decay tank release and diverts 0 other releases through the special ventilation system. Effluent flow rates are determined by installed flow measurement equipment or as a function of fan operation (fan curves). Sampler flow rates are determined by flow rate instrumentation.
2.1.5 Containment
Mini-PurgeNent SystemSlight pressure buildup in containment is a recurring event resulting from normal operation of the plant. Prior to exceeding 2 psig in containment, this excess pressure is vented off. Air from containment is routed to the Auxiliary Building ventilation system, via the post-LOCA hydrogen*recombiner piping and then out through the Auxiliary Building vent stack. The system is also 5designed 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 S Periodically, non-routine breaches are made in the Auxiliary and Containment buildings that might allow the release of the atmosphere, which contains some levels of radioactivity.
These*breaches include, but are not limited to, opening the Containment equipment hatch during outages, holes cut in walls or ceilings to allow for moving equipment in or out of the Radiologically Controlled Areas (RCAs). All efforts to maintain these areas at negative pressure Swill be made. IF negative pressure cannot be maintained (i.e., more exhaust than supply fan volume), THEN supply ventilation to the area must be secured. Criteria for determining if and when a release occurs from these areas is provided in implementing procedures.
As possible, S! the effects of these possible releases shall be evaluated beforehand.
Any actual releases shall be documented and included in the monthly, quarterly and annual reports as appropriate.
SA gaseous radioactive waste flow diagram with the applicable, associated radiation monitoring 5 instrumentation and controls is presented as Figure 2.2 S 0 S S*2.0-2 S 0 S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 2.2 Gaseous Effluent Monitor Setpoint Determination
2.2.1 Containment
and Auxiliary Building Vent Monitor Per the requirements of ODCM Normal Condition 13.3.2, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed corresponding dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin. Based on a grab sample analysis of the applicable release (i.e., grab sample of the Containment vent or Auxiliary Building vent), the radiation monitoring alarm setpoints may be established by the following calculational method: 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: FRACtb FRACski.x/Q VF Ci Ki Li Mi 1.1 4.72E+02 500 3000= fraction of the allowable release rate for the total body based on the identified 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 rate annual average meteorological dispersion for direct exposure to noble gas at the controlling SITE BOUNDARY location (sec/m 3 , from Table 2.3)= ventilation system flow rate for the applicable release point and monitor (ft 3/min, from Table 2.2)= concentration of noble gas radionuclide
'"T as determined by radioanalysis of grab sample (pCi/cm 3)= total body dose conversion factor for noble gas radionuclide
'T'(mrem/yr per pCi/m 3 , from Table 2.1)= beta skin dose conversion factor for noble gas radionuclide
'"T (mrem/yr per [tCi/m 3 , from Table 2.1)= gamma air dose conversion factor for noble gas radionuclide
'"T (mrad/yr per ljCi/m 3 , from Table 2.1)= mrem skin dose per mrad gamma air dose (mrem/mrad)
= conversion factor (cm 3/ft 3 x min/sec)= total body dose rate limit (mrem/yr)= skin dose rate limit (mrem/yr)2.0-3 0 0 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoint for the Containment and Auxiliary Building vent monitors at Kewaunee may be calculated:
SP= [I (C X SENi) -FRAC]+ bkg (2.3)where: SP SENi bkg= 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/cm 3), 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 Values A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2.2. These values are based upon: a) substitution of the maximum ventilation flow rate, 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 any simultaneous releases do not exceed the maximum allowable release rate.For this radionuclide distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table 2.2.'Adopted from ANSI N237-1976/ANS-18.1, Source Term Specifications, Table 6.2.0-4 0 0 KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations
-10 CFR 20 0 2.3.1 SITE BOUNDARY Dose Rate -Noble Gases.ODCM Normal Condition 13.2.1.a limits the dose rate at the SITE BOUNDARY due to noble gas releases to _< 500 mrem/yr to the total body, and < 3000 mrem/yr to the skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.
In the event any gaseous releases from the station results in the alarm setpoints being exceeded, an evaluation of the UNRESTRICTED AREA dose rate resulting from the release may be performed using the following equations:
Dtb =x/Qx- KixQi (2.4)0 and Dý=X/Qx (Li +1.1M,)X(i, (2.5)0 where: 0 D tb total body dose rate (mrem/yr) 0 0 Ds skin dose rate (mrem/yr)0 x/Q atmospheric dispersion for direct exposure to noble gas at the controlling 0 SITE BOUNDARY (sec/m 3 , from Table 2.3)0 Q= average release rate of radionuclide
'i" over the release period under evaluation (gCi/sec)K, total body dose conversion factor for noble gas radionuclide "r'(mrem/yr per gCi/m 3 , from Table 2.1)Li beta skin dose conversion factor for noble gas radionuclide
'i" (mrem/yr per gCi/m 3 , from Table 2.1)Mi gamma air dose conversion factor for noble gas radionuclide
'"T (mrad/yr per jICi/m 3 , from Table 2.1) 0 1.1 mrem skin dose per mrad gamma air dose (mrem/mrad) 0 0 2.0-50 0 0 0 KEWAUNEE POWER STATION ODCM 2.0* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2.3 may be used for evaluating the 0 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 to the sampling and analysis time period for continuous releases (e.g., nominally once per 7 days)and for batch releases on the time period over which any batch release is to occur. The following equation may be used for the dose rate evaluation:
- Do=X/Qx (2.6)0where: 0 D = average organ dose rate over the sampling time period (mrem/yr)*x/Q atmospheric dispersion to the controlling SITE BOUNDARY for the inhalation pathway (sec/m 3 , from Table 2.3)Ri= dose parameter for radionuclide "i", (mrem/yr per jiCi/m 3) for the child inhalation pathway from Table 2.6 0 Q= average release rate over the appropriate sampling period and analysis frequency 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 forQ 1 , an allowable release rate for 1-131 can be*determined.
Based on the annual average meteorological dispersion (see Table 2.3) and the most limiting potential pathway, age group and organ (inhalation pathway, child thyroid -Ri = 1.62E+07 mrem/yr per gCi/m 3) the allowable release rate for 1-131 is 6.43 RCi/sec. An 0 added conservatism factor of 0.25 has been included in this calculation to account for any potential dose contribution from other radioactive particulate material.
For a 7-day period, which is the nominal sampling and analysis frequency for 1-131, the cumulative allowable release is 3.9 Ci. Therefore, as long as the 1-131 releases in any 7-day period do not exceed 3.9 Ci, no*additional analyses are needed to verify compliance with the ODCM Normal Condition 13.2.1.b limits on allowable release rate.0 0 0 0*2.0-6 0 0 0 0 KEWAUNEE POWER STATION ODCM 2.0 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 2.4 Gaseous Effluent Dose Calculations
-10 CFR 50 2.4.1 UNRESTRICTED AREA Dose -Noble Gases ODCM Normal Condition 13.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of (< 5 mrad, gamma-air and < 10 mrad, beta-air) and the calendar year limits (< 10 mrad, gamma-air and < 20 mrad, beta-air).
The following equations may be used to calculate the gamma-air and beta-air doses: D= 3.17E- 08x X/Q x (M, x Q) (2.7) 0 and 0 D,= 3.17E- 08x X/Q x (N, x Q) (2.8)where: 0 D, air dose due to gamma emissions for noble gas radionuclides (mrad)D= air dose due to beta emissions for noble gas radionuclides (mrad)0 0 X/Q atmospheric dispersion to the controlling SITE BOUNDARY (sec/m 3 , from Table 2.3)0 QI = 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/m 3 from Table 2.1)Ni= air dose factor due to beta emissions from noble gas radionuclide "i" (mrad/yr per gCi/m 3 , Table 2.1) 0 3.17E-08 = conversion factor (yr/sec)In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculational equation may be used for verifying compliance with the 0 dose limits of ODCM Normal Condition 13.2.2. (Refer to Appendix B for the derivation and justification for this simplified method.)0 D- = 3.1 7 E- 0 8 (2.9)0.50 and 0 3.17E-080 Dp = 3.50 x X/Qx Neff x I- Qi (2.10)0.50 2 2.0- 7 0 0 0 0* KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16* December 5, 2013 S where:*Meff = 5.3E+02 effective gamma-air dose factor (mrad/yr per gCi/m 3)*l Neff = 1.1 E+03 effective beta-air dose factor (mradlyr per iiCilm 3)0 0.50 = conservatism factor Actual meteorological conditions concurrent with the release period or the default, annual*average dispersion parameters as presented in Table 2.3, may be used for the evaluation of the gamma-air and beta-air doses.2.4.2 UNRESTRICTED AREA Dose -Radioiodine and Particulates
- Per the requirements of ODCM Normal Condition 13.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit (< 7.5 mrem) and calendar year limit (< 15 mrem) to any organ. The following equation may be used to evaluate the maximum* organ dose due to releases of 1-131, 1-133, tritium and particulates with half-lives greater than*8 days: SDaop =3.17E- 08x W xSFpx X( xQi) (2.11)0 where: Daop = dose or dose commitment for age group "a" to organ "o", including the*total body, via pathway "p" from 1-131, 1-133, tritium and radionuclides in*particulate form with half-life greater than eight days (mrem)*W = atmospheric dispersion parameter to the controlling location(s) as*identified in Table 2.3*X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution
- ) via other pathways (sec/m 3)*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/m 3) or (M 2 -mrem/yr per* iCi/sec) from Table 2.4 through 2.15 for each age group "a" and the applicable pathway "p" as identified in Table 2.3. Values for R 1 were*derived in accordance with the methods described in NUREG-0133.
0 Q= cumulative release over the period of interest for radionuclide "i" -- 1-131 or radioactive material in particulate form with half-life greater than 8 days2 S S* 2.0-8 S S S S 6 KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 SFp = seasonal correction factor to account for the fraction of the period that the applicable exposure pathway does exist.1) For milk and vegetation exposure pathways:# of months in the period that grazing occurs total # of months in period= 0.5 for annual calculations 0 2) For inhalation and ground plane exposure pathways:
= 1.0 0 In lieu of the individual radionuclide (1-131 and particulates) dose assessment as presented above, the following simplified dose calculational equation may be used for verifying compliance with the dose limits of ODCM Normal Condition 13.2.3.0 D.. = 3.17E- 08x W xSFpxRI -(2.12)where: 0 Dmax = maximum organ dose (mrem) S S R-131 1-131 dose parameter for the thyroid for the identified controlling pathway 1.05E+12, infant thyroid dose parameter with the grass-cow-milk pathway controlling (M 2 -mrem/yr per l.Ci/sec)The ground plane exposure and inhalation pathways need not be considered when the above- 0 simplified calculational method is used because of the overall negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground plane exposure pathway may represent a higher dose contribution than either the vegetation or grass-cow-milk pathway. However, use of the 1-131 0 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclide has a higher dose parameter for any organ via any pathway than 1-131 for the thyroid via the grass-cow-milk pathway.The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Kewaunee as identified by the annual S land-use census. Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2.3.2 0 0 0 0 2.0-90 0 0 0 0 0* KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 2.5 Gaseous Effluent Dose Projection 0 ODCM Normal Condition 13.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses exceed one-half the Sannual 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)0 where:*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 period S 31 number of days in a 31 day period 2 0 S S SD 2.0- 10 S S S S 0 KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 S 2.6 Environmental Radiation Protection Standards 40 CFR 190 S For the purpose of implementing ODCM Normal Condition 13.4.1 on the EPA environmental radiation protection standard and Technical Specification 5.6.2 on reporting requirements, dose calculations may be performed using the above equations with the substitution of average or actual meteorological parameters for the period of interest and actual applicable pathways.
Any exposure attributable to on-site sources will be evaluated based on the results of the environmental monitoring program (TLD measurements) or by calculational methods. NUREG-0543 describes acceptable methods for demonstrating compliance with 40 CFR Part 190 when radioactive effluents exceed the Appendix I portion of the specifications.
2.7 Incineration
of Radioactively Contaminated Oil During plant operation, radioactively contaminated oils are generated from various pieces of equipment operating in the plant. The largest source of contaminated oil is the reactor coolant pump lubricating oil, which is periodically changed for preventive maintenance reasons. 10 CFR Part 20 allows licensees to incinerate radioactively contaminated oils on site provided that the total radioactive effluents from the facility conform to the requirements of 10 CFR Part 50, Appendix I.Radioactively contaminated oil, which is designated for incineration, will be collected in containers, 0 which are uniquely serialized such that the contents can be identified and tracked. Each container will be sampled and analyzed for radioactivity.
The isotopic concentrations will be recorded for each container.
The heating boiler will be utilized to incinerate the radioactively contaminated oil collected on site. A gaseous radwaste effluent dose calculation, as prescribed in Section 2.3 of the ODCM, will be performed to ensure that the limits established by ODCM Normal Condition 13.2.1, 13.2.2 and 13.2.3 are not exceeded.
Release of the activity is assumed to occur at the time the contaminated oil is transferred into the heating boiler fuel oil storage tank and will be accounted for using established plant procedures.
This will be valid for an assumed release from the fuel oil storage tank vent, fill piping, or from the boiler exhaust stack. See Figure 3 for a description of the heating boiler fuel oil system.2.8 Total Dose The purpose of this section is to describe the method used to calculate the cumulative dose contributions from liquid and gaseous effluents in accordance with KPS Technical Specifications for total dose. This method can also be used to demonstrate compliance with the Environmental Protection Agency (EPA) 40CFR190, "Environmental Standards for the Uranium Fuel Cycle".0 Compliance with the KPS Technical Specification dose objectives for the maximum individual demonstrates compliance with the EPA limits to any MEMBER OF THE PUBLIC, since the design dose objectives from 10CFR50, Appendix I are much lower than the 40CFR190 dose limits to the general public. With the calculated doses from the releases of radioactive materials in liquid or gaseous effluents exceeding twice the limits outlined in ODCM DNC 13.1.2, 13.2.2, and 13.2.3, a special analysis shall be performed.
The purpose of this analysis is to demonstrate if the total dose to any 0 MEMBER OF THE PUBLIC (real individual) from all uranium fuel cycle sources (including direct radiation contributions from the facility, from outside storage areas and from all real pathways) is limited to less than or equal to 25 mrem per year to the total body or any organ, except the thyroid, which is limited to 75 mrem per year.2.0-11 0 0 0 0 0 0 0* KEWAUNEE POWER STATION ODCM 2.0 OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5, 2013 0 If required, the total dose to a MEMBER OF THE PUBLIC will be calculated for all significant effluent*release points for all real pathways including direct radiation.
Effluent releases from Point Beach Nuclear Plant must also be considered due to its proximity.
Calculations will be based on the equations in Sections 1.4, 2.4.1, and 2.4.2, with the exception that usage factors and other site specific parameters may be modified using more realistic assumptions, where appropriate.
0 The 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 by including the results from the environmental TLDs into the sum of total dose component, the direct*radiation dose may be overestimated.
The TLD measurements may include the exposure from noble 0gases, ground plane deposition, and shoreline deposition, which have already been included in the summation of the significant dose pathways to the general public. However, this conservative method can be used, if required, as well as any other method for estimating the direct radiation dose from*contained radioactive sources within the facility.
The methodology used to incorporate the direct radiation component into total dose estimates will be outlined whenever total doses are reported.Therefore, the total dose will be determined based on the most realistic site specific data and*parameters to assess the real dose to any MEMBER OF THE PUBLIC.0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0~2.0- 12 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 AMdAiy Buiildng vaMstcd Legend= 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 the normal effluent processing system. They are Included for completeness only.*. The containment air sampler (RI I and radiation monitor (R12) can also be allgned as needed for sampling containment vent.Gra~Ile No. CS7536 ODCM FIGURE 2 GASEOUS RADIOACTIVE EFFLUENT FLOW DIAGRAM 2.0-13 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 Figure 3 Simplified Heating Boiler Fuel Oil Piping System Heating Boger Fuel OU Storage Tank healing boiler 30,000.Gallons fuel Glo pumps 2.0-14 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 Table 2.1 Dose Factors for Noble Gases Total Body Dose Skin Dose Factor Gamma Air Dose Beta Air Dose Factor K, L, (mremlyr per Factor M, Factor N, Radionuclide (mrem/yr per pCi/m 3) (mradlyr per (mrad/yr per iPCiIm 3) iJCilm 3) IJCiIm 3)Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.,03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-1 35m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-15 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.2 Parameters for Gaseous Alarm Setpoint Determinations ODCM 2.0 Revision 16 December 5, 2013 Parameter Actual Value Default Value* Units Comments X/Q calculated 3.6E-06 sec/m 3 Licensing technical specification value Containment
-normal plus Vfacuvs 26,000 fmpurge modes 54,000 Auxiliary Building -normal operation C measured N/A pCi/m 3 K, nuclide mrem/yr per Values from Table 2.1 K_____specific NIA pCi/m 3 nuclide mrem/yr per Li specific N/A pCilm 3 Values from Table 2.1 nuclide N/A mrem/yr per Values from Table 2.1 M_____specific pCi/m 3 Sensitivity**(SEN)R-1 2 32E+07 cpm per Containment R-21 2.32E+07 pCi/cm 3 Containment R-13 2.32E+07 Auxiliary Building R-14 2.32E+07 Auxiliary Building Background (bkg)R-12 4.OE+02 Nominal values only; actual R-21 4.0E+01 cpm values may be used in lieu of R-13 6.OE+02 these reference values.R-14 9.OE+02 Setpoint* (SP) Default alarm setpoints; more R-12 calculated 2.8E+05+bkg conservative values may be R-21 calculated 2.8E+05+bkg cpm used as deemed appropriate R-13 calculated 1.3E+05+bkg and desirable for ensuring R-14 calculated 1.3E+05+bkg regulatory compliance and for I_ 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 STATION OFFSITE DOSE CALCULATION MANUAL Table 2.3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations ODCM 2.0 Revision 16 December 5, 2013 Atmospheric Dispersion ODCM Normal Condition Location Pathways X/Q (sec/m 3) D/Q (lmr 2)13.2.1.a Site Boundary Noble gases 7.44E-07 N/A (0.81 mile, NNW) Direct exposure 13.2.1 .b Site Boundary Inhalation, 7.44E-07 N/A (0.81 mile, NNW) Ground Plane 13.2.2 Site Boundary Gamma Air 7.44E-07 N/A (0.81 mile, NNW) Beta Air 3 Residence/dairy Inhalation, 13.2.3 (esilne/dairy Vegetation, Milk 3.95E-08 1.86E-09 (1.3 mile SW)~ and Ground Plane 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-17 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.4 (Page 1 of 2)R 1 Inhalation Pathway Dose Factors -ADULT (mrem/yr per pCi/m 3)ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 P-32 1.32E+6 7.71E+4 -8.64E+4 5.01E+4 Cr-51 -5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 -3.96E+4 -9.84E+3 1.40E+6 7.74E+4 6.30E+3 Mn-56 -1.24E+0 -1.30E+0 9.44E+3 2.02E+4 1.83E-1 Fe-55 2.46E+4 1.70E+4 --7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 --1.02E+6 1.88E+5 1.06E+4 Co-57 -6.92E+2 --3.70E+5 3.14E+4 6.71E+2 Co-58 -1.58E+3 --9.28E+5 1.06E+5 2.07E+3 Co-60 -1.15E+4 --5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 --1.78E+5 1.34E+4 1.45E+4 Ni-65 1.54E+0 2.10E-1 --5.60E+3 1.23E+4 9.12E-2 Cu-64 -1.46E+0 -4.62E+0 6.78E+3 4.90E+4 6.15E-1 Zn-65 3.24E+4 1.03E+5 -6.90E+4 8.64E+5 5.34E+4 4.66E+4 Zn-69 3.38E-2 6.51 E-2 -4.22E-2 9.20E+2 1.63E+1 4.52E-3 Br-82 ---1.04E+4 1.35E+4 Br-83 .... 2.32E+2 2.41E+2 Br-84 .... 1.64E-3 3.13E+2 Br-85 .... 1.28E+1 Rb-86 -1.35E+5 -1.66E+4 5.90E+4 Rb-88 -3.87E+2 -3.34E-9 1.93E+2 Rb-89 -2.56E+2 --1.70E+2 Sr-89 3.04E+5 ---1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 ---9.60E+6 7.22E+5 6.1OE+6 Sr-91 6.19E+1 ---3.65E+4 1.91E+5 2.50E+0 Sr-92 6.74E+0 ---1.65E+4 4.30E+4 2.91 E-1 Y-90 2.09E+3 ---1.70E+5 5.06E+5 5.61E+1 Y-91m 2.61E-1 --1.92E+3 1.33E+0 1.02E-2 Y-91 4.62E+5 --1.70E+6 3.85E+5 1.24E+4 Y-92 1.03E+1 --1.57E+4 7.35E+4 3.02E-1 Y-93 9.44E+1 --4.85E+4 4.22E+5 2.61 E+0 Zr-95 1.07E+5 3.44E+4 -5.42E+4 1.77E+6 1.50E+5 2.33E+4 Zr-97 9.68E+1 1.96E+1 -2.97E+1 7.87E+4 5.23E+5 9.04E+0 Nb-95 1.41E+4 7.82E+3 -7.74E+3 5.05E+5 1.04E+5 4.21E+3 Nb-97 2.22E-1 5.62E-2 -6.54E-2 2.40E+3 2.42E+2 2.05E-2 Mo-99 -1.21 E+2 -2.91E+2 9.12E+4 2.48E+5 2.30E+1 Tc-99m 1.03E-3 2.91E-3 -4.42E-2 7.64E+2 4.16E+3 3.70E-2 Tc-101 4.18E-5 6.02E-5 -1.08E-3 3.99E+2 -5.90E-4 2.0-18 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.4 (Page 2 of 2)R 1 Inhalation Pathway Dose Factors -ADULT (mrem/yr per pCi/m 3)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.53E+3 5.83E+3 5.05E+5 1.1OE+5 6.58E+2 Ru-105 7.90E-1 1.02E+0 1.1OE+4 4.82E+4 3.11E-1 Ru-106 6.91E+4 -1.34E+5 9.36E+6 9.12E+5 8.72E+3 Rh-103m -Rh-106 -......Ag-110m 1.08E+4 1.OOE+4 -1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 -2.48E+6 4.06E+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 -1.74E+6 1.01E+5 1.26E+4 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-127 1.40E+0 6.42E-1 1.06E+O 5.1OE+0 6.51E+3 5.74E+4 3.1OE-1 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 Te-129 4.98E-2 2.39E-2 3.90E-2 1.87E-1 1.94E+3 1.57E+2 1.24E-2 Te-131m 6.99E+1 4.36E+1 5.50E+1 3.09E+2 1.46E+5 5.56E+5 2.90E+1 Te-131 1.11E-2 5.95E-3 9.36E-3 4.37E-2 1.39E+3 1.84E+1 3.59E-3 Te-132 2.60E+2 2.15E+2 1.90E+2 1.46E+3 2.88E+5 5.1OE+5 1.62E+2 1-130 4.58E+3 1.34E+4 1.14E+6 2.09E+4 -7.69E+3 5.28E+3 1-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -6.28E+3 2.05E+4 1-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 -4.06E+2 1.16E+3 1-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 -8.88E+3 4.52E+3 1-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 -1.01E+0 6.15E+2 1-135 2.68E+3 6.98E+3 4.48E+5 1.11E+4 -5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 -2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21E+5 -2.22E+5 7.52E+4 8.40E+3 4.28E+5 Cs-138 3.31E+2 6.21E+2 -4.80E+2 4.86E+1 1.86E-3 3.24E+2 Ba-139 9.36E-1 6.66E-4 -6.22E-4 3.76E+3 8.96E+2 2.74E-2 Ba-140 3.90E+4 4.90E+1 -1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ba-141 1.OOE-1 7.53E-5 -7.OOE-5 1.94E+3 1.16E-7 3.36E-3 Ba-142 2.63E-2 2.70E-5 -2.29E-5 1.19E+3 -1.66E-3 La-140 3.44E+2 1.74E+2 -1.36E+5 4.58E+5 4.58E+1 La-142 6.83E-1 3.1OE-1 --6.33E+3 2.11E+3 7.72E-2 Ce-141 1.99E+4 1.35E+4 -6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-143 1.86E+2 1.38E+2 -6.08E+1 7.98E+4 2.26E+5 1.53E+1 Ce-144 3.43E+6 1.43E+6 -8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 -2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Pr-144 3.01E-2 1.25E-2 -7.05E-3 1.02E+3 2.15E-8 1.53E-3 Nd-147 5.27E+3 6.1OE+3 -3.56E+3 2.21E+5 1.73E+5 3.65E+2 W-187 8.48E+O 7.08E+0 --2.90E+4 1.55E+5 2.48E+0 Np-239 2.30E+2 2.26E+1 -7.OOE+1 3.76E+4 1.19E+5 1.24E+1 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-19 S 0 0 S 0 0 0 0 S 0 0O 0 0 0 0 0 S 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.5 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -TEEN (mrem/yr per pCi/m 3)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 Na-24 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 P-32 1.89E+6 1.10E+5 --9.28E+4 7.16E+4 Cr-51 --7.50E+1 3.07E+1 2.1OE+4 3.OOE+3 1.35E+2 Mn-54 -5.11E+4 -1.27E+4 1.98E+6 6.68E+4 8.40E+3 Mn-56 -1.70E+0 -1.79E+0 1.52E+4 5.74E+4 2.52E-1 Fe-55 3.34E+4 2.38E+4 --1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 --1.53E+6 1.78E+5 1.43E+4 Co-57 -6.92E+2 --5.86E+5 3.14E+4 9.20E+2 Co-58 -2.07E+3 --1.34E+6 9.52E+4 2.78E+3 Co-60 -1.51E+4 --8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 --3.07E+5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 --9.36E+3 3.67E+4 1.27E-1 Cu-64 -2.03E+0 -6.41E+0 1.11E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 -8.64E+4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 -6.02E-2 1.58E+3 2.85E+2 6.46E-3 Br-82 ..... 1.82E+4 Br-83 ..... 3.44E+2 Br-84 ..... 4.33E+2 Br-85 ..... 1.83E+1 Rb-86 -1.90E+5 --1.77E+4 8.40E+4 Rb-88 -5.46E+2 --2.92E-5 2.72E+2 Rb-89 -3.52E+2 --3.38E-7 2.33E+2 Sr-89 4.34E+5 --2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 --1.65E+7 7.65E+5 6.68E+6 Sr-91 8.80E+1 ---6.07E+4 2.59E+5 3.51 E+0 Sr-92 9.52E+0 ---2.74E+4 1.19E+5 4.06E-1 Y-90 2.98E+3 ---2.93E+5 5.59E+5 8.00E+1 Y-91 m 3.70E-1 ---3.20E+3 3.02E+1 1.42E-2 Y-91 6.61E+5 ---2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 ---2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 ---8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 -6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-97 1.38E+2 2.72E+1 -4.12E+1 1.30E+5 6.30E+5 1.26E+1 Nb-95 1.86E+4 1.03E+4 -1.OOE+4 7.51E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 -9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 -1.69E+2 -4.11E+2 1.54E+5 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 1.52E-3 6.67E+2 8.72E-7 8.24E-4 2.0-20 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.5 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -TEEN (mrem/yr per pCi/m 3)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.1OE+3 --7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-105 1.12E+0 -1.41 E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 -1.90E+5 1.611E+7 9.60E+5 1.24E+4 Rh-1 03m ---Rh-106 ---Ag-110m 1.38E+4 1.31E+4 -2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 -2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 -5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-127 2.01E+0 9.12E-1 1.42E+0 7.28E+0 1.12E+4 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 Te-129 7.1OE-2 3.38E-2 5.18E-2 2.66E-1 3.30E+3 1.62E+3 1.76E-2 Te-131m 9.84E+1 6.01E+1 7.25E+1 4.39E+2 2.38E+5 6.21E+5 4.02E+1 Te-131 1.58E-2 8.32E-3 1.24E-2 6.18E-2 2.34E+3 1.51E+1 5.04E-3 Te-132 3.60E+2 2.90E+2 2.46E+2 1.95E+3 4.49E+5 4.63E+5 2.19E+2 1-130 6.24E+3 1.79E+4 1.49E+6 2.75E+4 -9.12E+3 7.17E+3 1-131 3.54E+4 4.91 E+4 1.46E+7 8.40E+4 -6.49E+3 2.64E+4 1-132 1.59E+3 4.38E+3 1.51 E+5 6.92E+3 -1.27E+3 1.58E+3 1-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 -1.03E+4 6.22E+3 1-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 -2.04E+1 8.40E+2 1-135 3.70E+3 9.44E+3 6.21 E+5 1.49E+4 -6.95E+3 3.49E+3 Cs-134 5.02E+5 1.13E+6 -3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 -1.1OE+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 -3.04E+5 1.21E+5 8.48E+3 3.11E+5 Cs-138 4.66E+2 8.56E+2 -6.62E+2 7.87E+1 2.70E-1 4.46E+2 Ba-139 1.34E+0 9.44E-4 -8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5.47E+4 6.70E+1 -2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 1.42E-1 1.06E-4 -9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ba-142 3.70E-2 3.70E-5 -3.14E-5 1.91E+3 -2.27E-3 La-140 4.79E+2 2.36E+2 -2.14E+5 4.87E+5 6.26E+1 La-142 9.60E-1 4.25E-1 -1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 -8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-143 2.66E+2 1.94E+2 -8.64E+1 1.30E+5 2.55E+5 2.16E+1 Ce-144 4.89E+6 2.02E+6 -1.21 E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 -3.09E+3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 -1.01E-2 1.75E+3 2.35E-4 2.18E-3 Nd-147 7.86E+3 8.56E+3 -5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+0 -4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 -1.OOE+2 6.49E+4 1.32E+5 1.77E+1 0 S S 0 0 S 0 0 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 2.0-21 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.6 (Page 1 of 2)R 1 Inhalation Pathway Dose Factors -CHILD (mrem/yr per tiCi/m 3)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body, H-3 -1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 P-32 2.60E+6 1.14E+5 --4.22E+4 9.88E+4 Cr-51 --8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 -4.29E+4 -1.OOE+4 1.58E+6 2.29E+4 9.51E+3 Mn-56 -1.66E+0 -1.67E+0 1.31E+4 1.23E+5 3.12E-1 Fe-55 4.74E+4 2.52E+4 -1.11 E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4 Co-57 -9.03E+2 -5.07E+5 1.32E+4 1.07E+3 Co-58 -1.77E+3 -1.11E+6 3.44E+4 3.16E+3 Co-60 -1.31E+4 -7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21 E+5 4.63E+4 -2.75E+5 6.33E+3 2.80E+4 Ni-65 2.99E+0 2.96E-1 -8.18E+3 8.40E+4 1.64E-1 Cu-64 -1.99E+0 -6.03E+0 9.58E+3 3.67E+4 1.07E+0 Zn-65 4.26E+4 1.13E+5 -7.14E+4 9.95E+5 1.63E+4 7.03E+4 Zn-69 6.70E-2 9.66E-2 -5.85E-2 1.42E+3 1.02E+4 8.92E-3 Br --2.09E+4 Br-83 -4.74E+2 Br-84 -15.48E+2 Br-85 --2.53E+1 Rb-86 -1.98E+5 --7.99E+3 1.14E+5 Rb-88 -5.62E+2 --1.72E+1 3.66E+2 Rb-89 -3.45E+2 --1.89E+0 2.90E+2 Sr-89 5.99E+5 ---2.16E+6 1.67E+5 1.72E+4 Sr-90 1.01 E+8 ---1.48E+7 3.43E+5 6.44E+6 Sr-91 1.21E+2 -- 5.33E+4 1.74E+5 4.59E+0 Sr-92 1.31E+1 ---2.40E+4 2.42E+5 5.25E-1 Y-90 4.11E+3 -- 2.62E+5 2.68E+5 1.11E+2 Y-91m 5.07E-1 -- 2.81E+3 1.72E+3 1.84E-2 Y-91 9.14E+5 -2.63E+6 1.84E+5 2.44E+4 Y-92 2.04E+1 -- -2.39E+4 2.39E+5 5.81E-1 Y-93 1.86E+2 --7.44E+4 3.89E+5 5.11E+0 Zr-95 1.90E+5 4.18E+4 -5.96E+4 2.23E+6 6.11E+4 3.70E+4 Zr-97 1.88E+2 2.72E+1 -3.89E+1 1.13E+5 3.51E+5 1.60E+1 Nb-95 2.35E+4 9.18E+3 -8.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-97 4.29E-1 7.70E-2 -8.55E-2 3.42E+3 2.78E+4 3.60E-2 Mo-99 -1.72E+2 -3.92E+2 1.35E+5 1.27E+5 4.26E+1 Tc-99m 1.78E-3 3.48E-3 -5.07E-2 9.51E+2 4.81E+3 5.77E-2 Tc-101 8.1OE-5 8.51E-5 -1.45E-3 5.85E+2 1.63E+1 1.08E-3 2.0-22 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.6 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -CHILD (mrem/yr per gICi/m 3)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI -T.Body Ru-103 2.79E+3 --7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-105 1.53E+0 --1.34E+0 1.59E+4 9.95E+4 5.55E-1 Ru-106 1.36E+5 --1.84E+5 1.43E+7 4.29E+5 1.69E+4 Rh-103m ---Rh-106 -Ag-110m 1.69E+4 1.14E+4 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -3.24E+6 1.64E+5 2.OOE+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 -2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1.92E+3 -4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-127 2.77E+0 9.51E-1 1.96E+0 7.07E+O 1.OOE+4 5.62E+4 6.11E-1 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-1 2.93E+3 2.55E+4 2.38E-2 Te-131m 1.34E+2 5.92E+1 9.77E+1 4.OOE+2 2.06E+5 3.08E+5 5.07E+1 Te-131 2.17E-2 8.44E-3 1.70E-2 5.88E-2 2.05E+3 1.33E+3 6.59E-3 Te-132 4.81E+2 2.72E+2 3.17E+2 1.77E+3 3.77E+5 1.38E+5 2.63E+2 1-130 8.18E+3 1.64E+4 1.85E+6 2.45E+4 -5.11E+3 8.44E+3 1-131 4.81EE+4 4.81E+4 1.62E+7 7.88E+4 -2.84E+3 2.73E+4 1-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 3.20E+3 1.88E+3 1-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 5.48E+3 7.70E+3 1-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 9.55E+2 9.95E+2 1-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 -3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 -9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 -2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-138 6.33E+2 8.40E+2 -6.22E+2 6.81E+1 2.70E+2 5.55E+2 Ba-139 1.84E+0 9.84E-4 -8.62E-4 5.77E+3 5.77E+4 5.37E-2 Ba-140 7.40E+4 6.48E+1 -2.11E+1 1.74E+6 1.02E+5 4.33E+3 Ba-141 1.96E-1 1.09E-4 -9.47E-5 2.92E+3 2.75E+2 6.36E-3 Ba-142 5.OOE-2 3.60E-5 -2.91E-5 1.64E+3 2.74E+0 2.79E-3 La-140 6.44E+2 2.25E+2 --1.83E+5 2.26E+5 7.55E+1 La-142 1.30E+0 4.11E-1 -8.70E+3 7.59E+4 1.29E-1 Ce-141 3.92E+4 1.95E+4 -8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-143 3.66E+2 1.99E+2 -8.36E+1 1.15E+5 1.27E+5 2.87E+1 Ce-144 6.77E+6 2.12E+6 -1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 -3.OOE+3 4.33E+5 9.73E+4 9.14E+2 Pr-144 5.96E-2 1.85E-2 -9.77E-3 1.57E+3 1.97E+2 3.OOE-3 Nd-147 1.08E+4 8.73E+3 -4.81E+3 3.28E+5 8.21E+4 6.81E+2 W-187 1.63E+1 9.66E+0 --4.11E+4 9.1OE+4 4.33E+0 Np-239 4.66E+2 3.34E+1 -9.73E+1 5.81 E+4 6.40E+4 2.35E+1 6 0 0 0 0 S 0 0 0 S 0 0 S 0 S S S 0 S S S S S S S S S S S S S S S S S S S S S 2.0-23 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.7 (Page 1 of 2)Ri Inhalation Pathway Dose Factors -INFANT (mrem/yr per igCilm 3)ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 Na-24 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 P-32 2.03E+6 1.12E+5 1- .61E+4 7.74E+4 Cr-51 --5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 -2.53E+4 -4.98E+3 1.OOE+6 7.06E+3 4.98E+3 Mn-56 -1.54E+0 -1.1OE+0 1.25E+4 7.17E+4 2.21E-1 Fe-55 1.97E+4 1.17E+4 --8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 1.02E+6 2.48E+4 9.48E+3 Co-57 -6.51 E+2 -3.79E+5 4.86E+3 6.41 E+2 Co-58 -1.22E+3 -7.77E+5 1.11E+4 1.82E+3 Co-60 -8.02E+3 --4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 --2.09E+5 2.42E+3 1.16E+4 Ni-65 2.39E+0 2.84E-1 --8.12E+3 5.01EE+4 1.23E-1 Cu-64 -1.88E+O -3.98E+0 9.30E+3 1.50E+4 7.74E-1 Zn-65 1.93E+4 6.26E+4 -3.25E+4 6.47E+5 5.14E+4 3.11E+4 Zn-69 5.39E-2 9.67E-2 -4.02E-2 1.47E+3 1.32E+4 7.18E-3 Br-82 --1.33E+4 Br --3.81 E+2 Br-84 -- -4.OOE+2 Br-85 ---2.04E+1 Rb-86 -1.90E+5 --3.04E+3 8.82E+4 Rb-88 -5.57E+2 --3.39E+2 2.87E+2 Rb-89 3.21E+2 -.-6.82E+1 2.06E+2 Sr-89 3.98E+5 --2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 --1.12E+7 1.31E+5 2.59E+6 Sr-91 9.56E+1 -- -5.26E+4 7.34E+4 3.46E+O Sr-92 1.05E+1 -- -2.38E+4 1.40E+5 3.91E-1 Y-90 3.29E+3 -- -2.69E+5 1.04E+5 8.82E+1 Y-91m 4.07E-1 -- -2.79E+3 2.35E+3 1.39E-2 Y-91 5.88E+5 -- -2.45E+6 7.03E+4 1.57E+4 Y-92 1.64E+1 -- -2.45E+4 1.27E+5 4.61 E-1 Y-93 1.50E+2 ---7.64E+4 1.67E+5 4.07E+0 Zr-95 1,15E+5 2.79E+4 -3.11E+4 1.75E+6 2.17E+4 2.03E+4 Zr-97 1.50E+2 2.56E+1 -2.59E+1 1.1OE+5 1.40E+5 1.17E+1 Nb-95 1.57E+4 6.43E+3 -4.72E+3 4.79E+5 1.27E+4 3.78E+3 Nb-97 3.42E-1 7.29E-2 -5.70E-2 3.32E+3 2.69E+4 2.63E-2 Mo-99 -1.65E+2 -2.65E+2 1.35E+5 4.87E+4 3.23E+1 Tc-99m 1.40E-3 2.88E-3 -3.11E-2 8.11E+2 2.03E+3 3.72E-2 Tc-101 6.51E-5 8.23E-5 -9.79E-4 5.84E+2 8.44E+2 8.12E-4 2.0-24 6 6 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.7 (Page 2 of 2)Ri Inhalation Pathway Dose Factors -INFANT (mrem/yr per giCi/m 3)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 2.02E+3 --4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-105 1.22E+0 --8.99E-1 1.57E+4 4.84E+4 4.10E-1 Ru-106 8.68E+4 --1.07E+5 1.16E+7 1.64E+5 1.09E+4 Rh-103m--
---Rh-106 -------Ag-110m 9.98E+3 7.22E+3 -1.09E+4 3.67E+6 3.30E+4 5.OOE+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -2.65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 -1.64E+6 1.47E+4 1.09E+4 Te-125m 4.76E+3 1.99E+3 1.62E+3 -4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-127 2.23E+0 9.53E-1 1.85E+0 4.86E+0 1.03E+4 2.44E+4 4.89E-1 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 Te-129 7.88E-2 3.47E-2 6.75E-2 1.75E-1 3.OOE+3 2.63E+4 1.88E-2 Te-131m 1.07E+2 5.50E+1 8.93E+1 2.65E+2 1.99E+5 1.19E+5 3.63E+1 Te-131 1.74E-2 8.22E-3 1.58E-2 3.99E-2 2.06E+3 8.22E+3 5.OOE-3 Te-132 3.72E+2 2.37E+2 2.79E+2 1.03E+3 3.40E+5 4.41E+4 1.76E+2 1-130 6.36E+3 1.39E+4 1.60E+6 1.53E+4 -1.99E+3 5.57E+3 1-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -1.06E+3 1.96E+4 1-132 1.69E+3 3.54E+3 1.69E+5 3.95E+3 -1.90E+3 1.26E+3 1-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 -2.16E+3 5.60E+3 1-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 -1.29E+3 6.65E+2 1-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 -1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 -1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 -5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 -1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-138 5.05E+2 7.81E+2 -4.1OE+2 6.54E+1 8.76E+2 3.98E+2 Ba-139 1.48E+0 9.84E-4 -5.92E-4 5.95E+3 5.1OE+4 4.30E-2 Ba-140 5.60E+4 5.60E+1 -1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ba-141 1.57E-1 1.08E-4 -6.50E-5 2.97E+3 4.75E+3 4.97E-3 Ba-142 3.98E-2 3.30E-5 -1.90E-5 1.55E+3 6.93E+2 1.96E-3 La-140 5.05E+2 2.OOE+2 -1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+0 3.77E-1 -8.22E+3 5.95E+4 9.04E-2 Ce-141 2.77E+4 1.67E+4 -5.25E+3 5.17E+5 2.16E+4 1.99E+3 Ce-143 2.93E+2 1.93E+2 -5.64E+1 1.16E+5 4.97E+4 2.21E+1 Ce-144 3.19E+6 1.21E+6 -5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 -1.97E+3 4.33E+5 3.72E+4 6.99E+2 Pr-144 4.79E-2 1.85E-2 -6.72E-3 1.61E+3 4.28E+3 2.41E-3 Nd-147 7.94E+3 8.13E+3 -3.15E+3 3.22E+5 3.12E+4 5.OOE+2 W-187 1.30E+1 9.02E+0 --3.96E+4 3.56E+4 3.12E+0 Np-239 3.71E+2 3.32E+1 -6.62E+1 5.95E+4 2.49E+4 1.88E+1 S 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-25 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 Table 2.8 (Page 1 of 2)R 1 Vegetation Pathway Dose Factors -ADULT (mrem/yr per giCi/m 3) for H-3 and C-14 (M 2 x mrem/yr lgCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 P-32 1.40E+9 8.73E+7 1 -_ 1.58E+8 5.42E+7 Cr-51 --2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Mn-54 -3.11E+8 -9.27E+7 -9.54E+8 5.94E+7 Mn-56 -1.61E+1 -2.04E+1 -5.13E+2 2.85E+0 Fe-55 2.09E+8 1.45E+8 --8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 --8.35E+7 9.96E+8 1.14E+8 Co-57 -1.17E+7 -2.97E+8 1.95E+7 Co-58 -3.09E+7 ---6.26E+8 6.92E+7 Co-60 -1.67E+8 ---3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 ---1.50E+8 3.49E+8 Ni-65 6.15E+1 7.99E+0 ---2.03E+2 3.65E+0 Cu-64 -9.27E+3 -2.34E+4 -7.90E+5 4.35E+3 Zn-65 3.17E+8 1.01E+9 -6.75E+8 -6.36E+8 4.56E+8 Zn-69 8.75E-6 1.67E-5 -1.09E-5 -2.51E-6 1.16E-6 Br-82 ---1.73E+6 1.51E+6 Br-83 -- --4.63E+0 3.21 E+0 Br-84 ..- -Br-85 ......Rb-86 -2.19E+8 ---4.32E+7 1.02E+8 Rb-88 -.....Rb-89 --....Sr-89 9.96E+9 -.. 1.60E+9 2.86E+8 Sr-90 6.05E+11 -- --1.75E+10 1.48E+11 Sr-91 3.20E+5 -- --1.52E+6 1.29E+4 Sr-92 4.27E+2 ---8.46E+3 1.85E+1 Y-90 1.33E+4 -- --1.41 E+8 3.56E+2 Y-91m 5.83E-9 ---1.71E-8 Y-91 5.13E+6 -- --2.82E+9 1.37E+5 Y-92 9.01E-1 --1.58E+4 2.63E-2 Y-93 1.74E+2 -... 5.52E+6 4.80E+0 Zr-95 1.19E+6 3.81E+5 -5.97E+5 -1.21E+9 2.58E+5 Zr-97 3.33E+2 6.73E+1 -1.02E+2 -2.08E+7 3.08E+1 Nb-95 1.42E+5 7.91E+4 -7.81E+4 -4.80E+8 4.25E+4 Nb-97 2.90E-6 7.34E-7 -8.56E-7 -2.71 E-3 2.68E-7 Mo-99 -6.25E+6 -1.41E+7 -1.45E+7 1.19E+6 Tc-99m 3.06E+0 8.66E+0 -1.32E+2 4.24E+O 5.12E+3 1.1OE+2 Tc-101 -------2.0-26 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.8 (Page 2 of 2)ODCM 2.0 Revision 16 December 5, 2013 R 1 Vegetation Pathway Dose Factors -ADULT (mrem/yr per I4Ci/m 3) for H-3 and C-14 (m 2 x mrem/yr lICi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 4.80E+6 --1.83E+7 -5.61E+8 2.07E+6 Ru-105 5.39E+1 --6.96E+2 -3.30E+4 2.13E+1 Ru-106 1.93E+8 --3.72E+8 -1.25E+10 2.44E+7 Rh-103m- --.Rh-106 ---I ---Ag-110m 1.06E+7 9.76E+6 -1.92E+7 -3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 -8.08E+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 -1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -1.17E+9 4.26E+7 Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 -4.54E+5 1.25E+3 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -1.28E+9 4.03E+7 Te-129 6.65E-4 2.50E-4 5.1OE-4 2.79E-3 -5.02E-4 1.62E-4 Te-131m 9.12E+5 4.46E+5 7.06E+5 4.52E+6 -4.43E+7 3.72E+5 Te-131 .....Te-132 4.29E+6 2.77E+6 3.06E+6 2.67E+7 -1.31E+8 2.60E+6 1-130 3.96E+5 1.17E+6 9.90E+7 1.82E+6 -1.01E+6 4.61E+5 1-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -3.05E+7 6.63E+7 1-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 -2.89E+1 5.38E+1 1-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 -3.31E+6 1.12E+6 1-134 1.06E-4 2.88E-4 5.OOE-3 4.59E-4 -2.51E-7 1.03E-4 1-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 -1.21E+5 3.94E+4 Cs-134 4.66E+9 1.11E+1 -3.59E+9 1.19E+9 1.94E+8 9.07E+9 0 Cs-136 4.20E+7 1.66E+8 -9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 -2.95E+9 9.81E+8 1.68E+8 5.70E+9 Cs-138 .....Ba-139 2.95E-2 2.1OE-5 -1.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-140 1.29E+8 1.62E+5 -5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ba-141 -....Ba-142 -....La-140 1.97E+3 9.92E+2 --7.28E+7 2.62E+2 La-142 1.40E-4 6.35E-5 --4.64E-1 1.58E-5 Ce-141 1.96E+5 1.33E+5 -6.17E+4 -5.08E+8 1.51E+4 Ce-143 1.OOE+3 7.42E+5 -3.26E+2 -2.77E+7 8.21E+1 Ce-144 3.29E+7 1.38E+7 -8.16E+6 -1.11E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 -1.47E+4 -2.78E+8 3.14E+3 Pr-144 -------Nd-147 3.34E+4 3.86E+4 -2.25E+4 -1.85E+8 2.31 E+3 W-187 3.82E+4 3.19E+4 --1.05E+7 1.12E+4 Np-239 1.42E+3 1.40E+2 -4.37E+2 -2.87E+7 7.72E+1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-27 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table 2.9 (Page 1 of 2)R 1 Vegetation Pathway Dose Factors -TEEN (mrem/yr per gCi/m 3) for H-3 and C-14 (mi x mrem/yr laCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91 E+5 2.91 E+5 2.91 E+5 2.91E+5 2.91E+5 2.91 E+5 Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 P-32 1.61E+9 9.96E+7 ---1.35E+8 6.23E+7 Cr-51 -3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 -4.52E+8 -1.35E+8 -9.27E+8 8.97E+7 Mn-56 -1.45E+1 -1.83E+1 -9.54E+2 2.58E+0 Fe-55 3.25E+8 2.31 E+8 --1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 --1.33E+8 9.98E+8 1.63E+8 Co-57 -1.79E+7 --3.34E+8 3.00E+7 Co-58 -4.38E+7 --6.04E+8 1.01E+8 Co-60 -2.49E+8 --3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 --1.81E+8 5.45E+8 Ni-65 5.73E+1 7.32E+0 --3.97E+2 3.33E+0 Cu-64 -8.40E+3 -2.12E+4 -6.51E+5 3.95E+3 Zn-65 4.24E+8 1.47E+9 -9.41 E+8 -6.23E+8 6.86E+8 Zn-69 8.19E-6 1.56E-5 -1.02E-5 -2.88E-5 1.09E-6 Br-82 -1.33E+6 Br-83 -... 3.01E+0 Br-84 ----Br-85 -- -Rb-86 -2.73E+8 -4.05E+7 1.28E+8 Rb-88 -- -Rb-89 --Sr-89 1.51E+10 ---1.80E+9 4.33E+8 Sr-90 7.51E+11 ---2.11E+10 1.85E+11 Sr-91 2.99E+5 ---1.36E+6 1.19E+4 Sr-92 3.97E+2 -1.01 E+4 1.69E+1 Y-90 1.24E+4 --1.02E+8 3.34E+2 Y-91m 5.43E-9 --2.56E-7 -Y-91 7.87E+6 --3.23E+9 2.11E+5 Y-92 8.47E-1 --2.32E+4 2.45E-2 Y-93 1.63E+2 --4.98E+6 4.47E+0 Zr-95 1.74E+6 5.49E+5 -8.07E+5 -1.27E+9 3.78E+5 Zr-97 3.09E+2 6.11E+1 -9.26E+1 -1.65E+7 2.81E+1 Nb-95 1.92E+5 1.06E+5 -1.03E+5 -4.55E+8 5.86E+4 Nb-97 2.69E-6 6.67E-7 -7.80E-7 -1.59E-2 2.44E-7 Mo-99 -5.74E+6 -1.31E+7 -1.03E+7 1.09E+6 Tc-99m 2.70E+0 7.54E+0 -1.12E+2 4.19E+0 4.95E+3 9.77E+1 Tc-101 -------2.0-28 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 Table 2.9 (Page 2 of 2)R 1 Vegetation Pathway Dose Factors -TEEN (mre /yr per gCi/m3) for H-3 and C-14 (m 2 x mrem/yr gCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 6.87E+6 -2.42E+7 -5.74E+8 2.94E+6 Ru-105 5.00E+1 -6.31E+2 -4.04E+4 1.94E+1 Ru-106 3.09E+8 -5.97E+8 -1.48E+10 3.90E+7 Rh-103m ---Rh-106 ---Ag-110m 1.52E+7 1.44E+7 -2.74E+7 4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 -1.35E+8 3.11E+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 -1.88E+8 1.66E+9 5.OOE+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 --4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -1.37E+9 6.56E+7 Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4 -4.19E+5 1.17E+3 Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 -1.38E+9 5.81E+7 Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E-3 -3.40E-3 1.51E-4 Te-131m 8.44E+5 4.05E+5 6.09E+5 4.22E+6 -3.25E+7 3.38E+5 Te-131 .....Te-132 3.90E+6 2.47E+6 2.60E+6 2.37E+7 -7.82E+7 2.32E+6 1-130 3.54E+5 1.02E+6 8.35E+7 1.58E+6 -7.87E+5 4.09E+5 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 -2.13E+7 5.79E+7 1-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 -5.91E+1 4.87E+1 1-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 -2.53E+6 1.02E+6 1-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 -3.35E-6 9.13E-5 1-135 3.68E+4 9.48E+4 6.1OE+6 1.50E+5 -1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 -5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E+8 -9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 -4.59E+9 1.78E+9 1.92E+8 4.69E+9 Cs-138 .....Ba-139 2.77E-2 1.95E-5 -1.84E-5 1.34E-5 2.47E-1 8.08E-4 Ba-140 1.38E+8 1.69E+5 -5.75E+4 1.14E+5 2.13E+8 8.91E+6 Ba-141 .- -.Ba-142 -....La-140 1.80E+3 8.84E+2 ---5.08E+7 2.35E+2 La-142 1.28E-4 5.69E-5 ---1.73E+0 1.42E-5 Ce-141 2.82E+5 1.88E+5 -8.86E+4 -5.38E+8 2.16E+4 Ce-143 9.37E+2 6.82E+5 -3.06E+2 -2.05E+7 7.62E+1 Ce-144 5.27E+7 2.18E+7 -1.30E+7 -1.33E+10 2.83E+6 Pr-143 7.12E+4 2.84E+4 -1.65E+4 -2.34E+8 3.55E+3 Pr-144 .....Nd-147 3.63E+4 3.94E+4 -2.32E+4 -1.42E+8 2.36E+3 W-187 3.55E+4 2.90E+4 --7.84E+6 1.02E+4 Np-239 1.38E+3 1.30E+2 -4.09E+2 -2.10E+7 7.24E+1 0 0 S S 0 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 2.0-29 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table 2.10 (Page 1 of 2)R, Vegetation Pathway Dose Factors -CHILD (mrem/yr per p.Ci/m 3) for H-3 and C-14 (M 2 x mrem/yr jiCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 4.01 E+3 4.01E+3 4.01 E+3 4.01E+3 4.01E+3 4.01 E+3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 Na-24 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 P-32 3.37E+9 1.58E+8 9.30E+7 .1.30E+8 Cr-51 --6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 -6.61E+8 1.85E+8 -5.55E+8 1.76E+8 Mn-56 -1.90E+1 -2.29E+1 -2.75E+3 4.28E+0 Fe-55 8.00E+8 4.24E+8 -2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 -1.88E+8 6.76E+8 3.23E+8 Co-57 -2.99E+7 --2.45E+8 6.04E+7 Co-58 -6.47E+7 --3.77E+8 1.98E+8 Co-60 -3.78E+8 --2.1OE+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 --1.42E+8 1.34E+9 Ni-65 1.05E+2 9.89E+0 ---1.21E+3 5.77E+0 Cu-64 -1.11E+4 -2.68E+4 -5.20E+5 6.69E+3 Zn-65 8.12E+8 2.16E+9 -1.36E+9 -3.80E+8 1.35E+9 Zn-69 1.51E-5 2.18E-5 -1.32E-5 -1.38E-3 2.02E-6 Br-82 ..... 2.04E+6 Br-83 -5.55E+0 Br-84 -...Br-85 .- -.Rb-86 -4.52E+8 ---2.91 E+7 2.78E+8 Rb-88 .- -.Rb-89 -....Sr-89 3.59E+10 -1.39E+9 1.03E+9 Sr-90 1.24E+12 -- --1.67E+10 3.15E+11 Sr-91 5.50E+5 -- --1.21E+6 2.08E+4 Sr-92 7.28E+2 -- --1.38E+4 2.92E+1 Y-90 2.30E+4 -- --6.56E+7 6.17E+2 Y-91 m 9.94E-9 ---1.95E-5 -Y-91 1.87E+7 -- --2.49E+9 5.01 E+5 Y-92 1.56E+0 -- --4.51 E+4 4.46E-2 Y-93 3.01E+2 ---4.48E+6 8.25E+0 Zr-95 3.90E+6 8.58E+5 -1.23E+6 -8.95E+8 7.64E+5 Zr-97 5.64E+2 8.15E+1 -1.17E+2 -1.23E+7 4.81E+1 Nb-95 4.10E+5 1.59E+5 -1.50E+5 -2.95E+8 1.14E+5 Nb-97 4.90E-6 8.85E-7 -9.82E-7 -2.73E-1 4.13E-7 Mo-99 -7.83E+6 -.1.67E+7 -6.48E+6 1.94E+6 Tc-99m 4.65E+0 9.12E+0 -1.33E+2 4.63E+0 5.19E+3 1.51E+2 Tc-101 ...... -2.0 -30 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.10 (Page 2 of 2)Ri Vegetation Pathway Dose Factors -CHILD (mrem/yr per gCi/m 3) for H-3 and C-14 (m 2 x mrem/yr gCi/sec) for others ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.55E+7 -3.89E+7 -3.99E+8 5.94E+6 Ru-105 9.17E+1 -8.06E+2 -5.98E+4 3.33E+1 Ru-106 7.45E+8 -1.01E+9 -1.16E+10 9.30E+7 Rh-103m ......Rh-106 ---Ag-110m 3.22E+7 2.17E+7 -4.05E+7 -2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 -1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 -2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 --3.38E+8 4.67E+7 Te-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -1.07E+9 1.57E+8 Te-127 1.00E+4 2.70E+3 6.93E+3 2.85E+4 -3.91E+5 2.15E+3 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -1.04E+9 1.33E+8 Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E-3 -7.17E-2 2.74E-4 Te-131m 1.54E+6 5.33E+5 1.1OE+6 5.16E+6 -2,16E+7 5.68E+5 Te-131 .......Te-132 6.98E+6 3.09E+6 4.50E+6 2.87E+7 -3.11E+7 3.73E+6 1-130 6.21E+5 1.26E+6 1.38E+8 1.88E+6 -5.87E+5 6.47E+5 1-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 -1.28E+7 8.18E+7 1-132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 -1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 -1.79E+6 1.68E+6 1-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 -2.10E-4 1.46E-4 1-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 -8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+10 -8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 -1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 -7.46E+9 2.68E+9 1.43E+8 3.38E+9 Cs-138 -...Ba-139 5.11E-2 2.73E-5 -2.38E-5 1.61E-5 2.95E+0 1.48E-3 Ba-140 2.77E+8 2.43E+5 -7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ba-141 -- --Ba-142 ----La-140 3.23E+3 1.13E+3 --3.15E+7 3.81E+2 La-142 2.32E-4 7.40E-5 ---1.47E+1 2.32E-5 Ce-141 6.35E+5 3.26E+5 -1.43E+5 -4.07E+8 4.84E+4 Ce-143 1.73E+3 9.36E+5 -3.93E+2 -1.37E+7 1.36E+2 Ce-144 1.27E+8 3.98E+7 -2.21E+7 -1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 -2.41 E+4 -1.60E+8 7.37E+3 Pr-144 -------Nd-147 7.16E+4 5.80E+4 -3.18E+4 -_ 9.18E+7 4.49E+3 W-187 6.47E+4 3.83E+4 ---5.38E+6 1.72E+4 Np-239 2.55E+3 1.83E+2 -5.30E+2 -1.36E+7 1.29E+2 0 0 S S 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-31 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S S 0 0 0 0 0 Table 2.11 (Page 1 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per gICi/m 3) for H-3 and C-14 (mi x mrem/yr jiCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 -I -1.92E+9 6.60E+8 Cr-51 --1.71 E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 -8.40E+6 -2.50E+6 -2.57E+7 1.60E+6 Mn-56 -4.23E-3 -5.38E-3 -1.35E-1 7.51 E-4 Fe-55 2.51E+7 1.73E+7 --9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.OOE+7 --1.95E+7 2.33E+8 2.68E+7 Co-57 -1.28E+6 ---3.25E+7 2.13E+6 Co-58 -4.72E+6 ---9.57E+7 1.06E+7 Co-60 -1.64E+7 --3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 --9.73E+7 2.26E+8 Ni-65 3.70E-1 4.81E-2 --1.22E+0 2.19E-2 Cu-64 -2.41E+4 -6.08E+4 -2.05E+6 1.13E+4 Zn-65 1.37E+9 4.36E+9 -2.92E+9 -2.75E+9 1.97E+9 Zn-69 -- -Br-82 -3.72E+7 3.25E+7 Br-83 -- -1.49E-1 1.03E-1 Br-84 -- -Br-85 ---Rb-86 -2.59E+9 1 -5.1E+8 1.21E+9 Rb-88 ----Rb-89 --Sr-89 1.45E+9 --2.33E+8 4.16E+7 Sr-90 4.68E+10 ---1.35E+9 1.15E+10 Sr-91 3.13E+4 --1.49E+5 1.27E+3 Sr-92 4.89E-1 -9.68E+O 2.11E-2 Y-90 7.07E+1 --7.50E+5 1.90E+0 Y-91m --Y-91 8.60E+3 --4.73E+6 2.30E+2 Y-92 5.42E-5 --9.49E-1 1.58E-6 Y-93 2.33E-1 --7.39E+3 6.43E-3 Zr-95 9.46E+2 3.03E+2 -4.76E+2 -9.62E+5 2.05E+2 Zr-97 4.26E-1 8.59E-2 -1.30E-1 -2.66E+4 3.93E-2 Nb-95 8.25E+4 4.59E+4 -4.54E+4 -2.79E+8 2.47E+4 Nb-97 -- --5.47E-9 -Mo-99 -2.52E+7 -5.72E+7 -5.85E+7 4.80E+6 Tc-99m 3.25E+O 9.19E+O -1.40E+2 4.50E+0 5.44E+3 1.17E+2 Tc-101 ----- -2.0-32 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.11 (Page 2 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -ADULT (mrem/yr per pCi/m 3) for H-3 and C-14 (M 2 x mrem/yr gCi/sec) for others ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.02E+3 -3.89E+3 -1.19E+5 4.39E+2 Ru-105 8.57E-4 -1.11E-2 -5.24E-1 3.38E-4 Ru-106 2.04E+4 -3.94E+4 -1.32E+6 2.58E+3 Rh-103m --.Rh-106 -...Ag-110m 5.83E+7 5.39E+7 1.06E+8 2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 2.OOE+7 7.31E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 1.58E+7 2.25E+8 4.86E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 -1.54E+8 5.58E+6 Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 -5.30E+4 1.45E+2 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 -3.04E+8 9.57E+6 Te-129 -....Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79E+6 -1.75E+7 1.47E+5 Te-131 --- -Te-132 2.39E+6 1.55E+6 1.71E+6 1.49E+7 -7.32E+7 1.45E+6 1-130 4.26E+5 1.26E+6 1.07E+8 1.96E+6 -1.08E+6 4.96E+5 1-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 -1.12E+8 2.43E+8 1-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 -8.22E-2 1.53E-1 1-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 -6.20E+6 2.1OE+6 1-134 ---1-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 4.1OE+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 -4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 1.03E+9 -5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 -3.43E+9 1.14E+9 1.95E+8 6.61E+9 Cs-138 ---Ba-139 4.70E-8 -8.34E-8 1.38E-9 Ba-140 2.69E+7 3.38E+4 1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-141 -- ---Ba-142 -...La-140 4.49E+0 2.26E+0 --1.66E+5 5.97E-1 La-142 --3.03E-8 -Ce-141 4.84E+3 3.27E+3 1.52E+3 -1.25E+7 3.71E+2 Ce-143 4.19E+1 3.09E+4 1.36E+1 -1.16E+6 3.42E+0 Ce-144 3.58E+5 1.50E+5 8.87E+4 -1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 3.68E+1 -6.96E+5 7.88E+0 Pr-144 ---Nd-147 9.42E+1 1.09E+2 6.37E+1 -5.23E+5 6.52E+0 W-187 6.56E+3 5.48E+3 --1.80E+6 1.92E+3 Np-239 3.66E+0 3.60E-1 -1.12E+0 -7.39E+4 1.98E-1 0 0 0 0 S S S 0 S S S S S S S S S S 0 S S 0 S S S S S S S S S S S S S S S S 2.0-33 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 0 0 0 S 0 0 0 0 0 0 0 S 0 0 0 0 S 0 Table 2.12 (Page 1 of 2)R, Grass-Cow-Milk Pathway Dose Factors -TEEN (mrem/yr per igCi/m 3) for H-3 and C-14 (m 2 x mrem/yr jiCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr-51 -2.78E+4 1.1OE+4 7.13E+4 8.40E+6 5.OOE+4 Mn-54 -1.40E+7 -4.17E+6 -2.87E+7 2.78E+6 Mn-56 -7.51E-3 -9.50E-3 -4.94E-1 1.33E-3 Fe-55 4.45E+7 3.16E+7 -2.OOE+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21 E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 -2.25E+6 --4.19E+7 3.76E+6 Co-58 -7.95E+6 --1.10E+8 1.83E+7 Co-60 -2.78E+7 --3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 --1.33E+8 4.01E+8 Ni-65 6.78E-1 8.66E-2 --4.70E+0 3.94E-2 Cu-64 -4.29E+4 -1.09E+5 -3.33E+6 2.02E+4 Zn-65 2.11E+9 7.31E+9 -4.68E+9 -3.1OE+9 3.41E+9 Zn-69 -----Br-82 -5.64E+7 Br-83 -.... , 1.91 E-1 Br-84 .--Br-85 -...Rb-86 -4.73E+9 ---7.OOE+8 2.22E+9 Rb-88 -....Rb-89 -.....Sr-89 2.67E+9 -- --3.18E+8 7.66E+7 Sr-90 6.61E+10 -- --1.86E+9 1.63E+10 Sr-91 5.75E+4 ---2.61 E+5 2.29E+3 Sr-92 8.95E-1 ---2.28E+1 3.81E-2 Y-90 1.30E+2 ---1.07E+6 3.50E+O Y-91m ....Y-91 1.58E+4 ---6.48E+6 4.24E+2 Y-92 1.OOE-4 ---2.75E+0 2.90E-6 Y-93 4.30E-1 ---1.31E+4 1.18E-2 Zr-95 1.65E+3 5.22E+2 -7.67E+2 -1.20E+6 3.59E+2 Zr-97 7.75E-1 1.53E-1 -2.32E-1 -4.15E+4 7.06E-2 Nb-95 1.41E+5 7.80E+4 -7.57E+4 -3.34E+8 4.30E+4 Nb-97 .- -6.34E-8 -Mo-99 -4.56E+7 -1.04E+8 -8.16E+7 8.69E+6 Tc-99m 5.64E+0 1.57E+1 -2.34E+2 8.73E+0 1.03E+4 2.04E+2 Tc-101 -------2.0-34 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.12 (Page 2 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -TEEN (mrem/yr per pCi/m 3) for H-3 and C-14 (M 2 x mrem/yr iiCi/sec) for others ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 1.81E+3 -6.40E+3 -1.52E+5 7.75E+2 Ru-105 1.57E-3 -1.97E-2 -1.26E+O 6.08E-4 Ru-106 3.75E+4 -7.23E+4 -1.80E+6 4.73E+3 Rh-103m ....Rh-106 ......Ag-110m 9.63E+7 9.11E+7 -1.74E+8 -2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 -4.01E+7 9.25E+8 1.79E+7 Sb-125 3.65E+7 3.99E+5 3.49E+4 -3.21E+7 2.84E+8 8.54E+6 Te-125m 3.OOE+7 1.08E+7 8.39E+6 --8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -2.1OE+8 1.OOE+7 Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 -9.61E+4 2.68E+2 Te-129m 1.11E+8 4.1OE+7 3.57E+7 4.62E+8 -4.15E+8 1.75E+7 Te-129 -1.67E-9 -2.18E-9 -Te-131m 6.57E+5 3.15E+5 4.74E+5 3.29E+6 -2.53E+7 2.63E+5 Te-131 .....Te-132 4.28E+6 2.71E+6 2.86E+6 2.60E+7 -8.58E+7 2.55E+6 1-130 7.49E+5 2.17E+6 1.77E+8 3.34E+6 -1.67E+6 8.66E+5 1-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 -1.49E+8 4.04E+8 1-132 2.90E-1 7.59E-1 2.56E+1 1.20E+O -3.31E-1 2.72E-1 1-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 -9.30E+6 3.75E+6 1-134 .....1-135 2.47E+4 6.35E+4 4.08E+6 1.OOE+5 7.03E+4 2.35E+4 Cs-134 9.81E+9 2.31E+10 -7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 -9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 -6.06E+9 2.35E+9 2.53E+8 6.20E+9 Cs-138 ---Ba-1 39 8.69E-8_ -7.75E-7 2.53E-9 Ba-140 4.85E+7 5.95E+4 -2.02E+4 4.OOE+4 7.49E+7 3.13E+6 Ba-141 -- --Ba-142 -...La-140 8.06E+0 3.96E+0 -2.27E+5 1.05E+O La-142 --2.23E-7 -Ce-141 8.87E+3 5.92E+3 -2.79E+3 -1.69E+7 6.81E+2 Ce-143 7.69E+1 5.60E+4 -2.51E+1 -1.68E+6 6.25E+0 Ce-144 6.58E+5 2.72E+5 -1.63E+5 -1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -6.77E+1 -9.61E+5 1.45E+1 Pr-144 -----Nd-147 1.81E+2 1.97E+2 -_1.16E+2
-7.11E+5 1.18E+1 W-187 1.20E+4 9.78E+3 --2.65E+6 3.43E+3 Np-239 6.99E+0 6.59E-1 -2.07E+0 -1.06E+5 3.66E-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-35 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 0 0 S 0 S 0 0 0 0 ,0'0 0 0 0 S 0 0 S 0 Table 2.13 (Page 1 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per igCi/m 3) for H-3 and C-14 (M 2 x mrem/yr gICi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 P-32 7.77E+10 3.64E+9 -2.15E+9 3.OOE+9 Cr-51 -5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn-54 -2.09E+7 -5.87E+6 -1.76E+7 5.58E+6 Mn-56 -1.31E-2 -1.58E-2 -1.90E+0 2.95E-3 Fe-55 1.12E+8 5.93E+7 -3.35E+7 1.1OE+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 -5.65E+7 2.03E+8 9.71E+7 Co-57 -3.84E+6 -3.14E+7 7.77E+6 Co-58 -1.21 E+7 -7.08E+7 3.72E+7 Co-60 -4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 1.07E+8 1.01E+9 Ni-65 1.66E+0 1.56E-1 1.91E+1 9.11E-2 Cu-64 -7.55E+4 1.82E+5 -3.54E+6 4.56E+4 Zn-65 4.13E+9 1.10E+10 16.94E+9 -1.93E+9 6.85E+9 Zn-69 -- -2.14E-9 -Br-82 -- 1.15E+8 Br-83 -4.69E-1 Br-84 -Br-85 -- --Rb-86 -8.77E+9 5.64E+8 5.39E+9 Rb-88 -- --Rb-89 ---Sr-89 6.62E+9 -2.56E+8 1.89E+8 Sr-90 1.12E+11 -1.51E+9 2.83E+10 Sr-91 1.41E+5 -3.12E+5 5.33E+3 Sr-92 2.19E+0 -4.14E+1 8.76E-2 Y-90 3.22E+2 -9.15E+5 8.61E+0 Y-91m ----Y-91 3.91 E+4 --5.21 E+6 1.04E+3 Y-92 2.46E-4 ---7.1OE+0 7.03E-6 Y-93 1.06E+0 ---1.57E+4 2.90E-2 Zr-95 3.84E+3 8.45E+2 -1.21E+3 -8.81E+5 7.52E+2 Zr-97 1.89E+0 2.72E-1 -3.91E-1 -4.13E+4 1.61E-1 Nb-95 3.18E+5 1.24E+5 -1.16E+5 -2.29E+8 8.84E+4 Nb-97 -----1.45E-6 -Mo-99 -8.29E+7 -1.77E+8 -6.86E+7 2.05E+7 Tc-99m 1.29E+1 2.54E+1 -3.68E+2 1.29E+1 1.44E+4 4.20E+2 Tc-101 .... --2.0-36 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.13 (Page 2 of 2)Ri Grass-Cow-Milk Pathway Dose Factors -CHILD (mrem/yr per giCi/M 3) for H-3 and C-14 (m 2 x mrem/yr giCi/sec) for others ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid .Kidney Fg GI-LLI T.Body Ru-103 4.29E+3 -1.08E+4 -1.11E+5 1.65E+3 Ru-105 3.82E-3 -3.36E-2 -2.49E+O 1.39E-3 Ru-106 9.24E+4 -1.25E+5 -1.44E+6 1.15E+4 Rh-103m ....Rh-106 ....Ag-110m 2.09E+8 1.41E+8 -2.63E+8 -1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 -6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 -4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.OOE+7 2.07E+7 --7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -1.68E+8 2.47E+7 Te-127 3.06E+3 8.25E+2 2.12E+3 8.71E+3 -1.20E+5 6.56E+2 Te-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+8 -3.32E+8 4.23E+7 Te-129 ---2.87E-9 -6.12E-8 -Te-131m 1.60E+6 5.53E+5 1.14E+6 5.35E+6 -2.24E+7 5.89E+5 Te-131 ....Te-132 1.02E+7 4.52E+6 6.58E+6 4.20E+7 -4.55E+7 5.46E+6 1-130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 -1.66E+6 1.82E+6 1-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 -1.17E+8 7.46E+8 1-132 6.86E-1 1.26E+0 5.85E+1 1.93E+O -1.48E+0 5.80E-1 1-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 -8.77E+6 8.23E+6 1-134 .- 135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 -8.OOE+4 4.97E+4 Cs-134 2.26E+10 3.71E+10 -1.15E+10 4.13E+9 2.OOE+8 7.83E+9 Cs-136 1.OOE+9 2.76E+9 -1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-137 3.22E+10 3.09E+10 -1.01E+10 3.62E+9 1.93E+8 4.55E+9 Cs-138 .....Ba-139 2.14E-7 .... 1.23E-5 6.19E-9 Ba-140 1.17E+8 1.03E+5 -3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ba-141 -....Ba-142 -....La-140 1.93E+1 6.74E+0 ---1.88E+5 2.27E+0 La-142 .- 2.51E-6 -Ce-141 2.19E+4 1.09E+4 -4.78E+3 -1.36E+7 1.62E+3 Ce-143 1.89E+2 1.02E+5 -4.29E+1 -1.50E+6 1.48E+1 Ce-144 1.62E+6 5.09E+5 -2.82E+5 -1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 -1.17E+2 -7.80E+5 3.59E+1 Pr-144 .....Nd-147 4.45E+2 3.60E+2 -1.98E+2 -5.71 E+5 2.79E+1 W-187 2.91E+4 1.72E+4 ---2.42E+6 7.73E+3 Np-239 1.72E+1 1.23E+0 -3.57E+O -9.14E+4 8.68E-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 2.0-37 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM 2.0 Revision 16 December 5, 2013 Table 2.14 (Page 1 of 2)R, Grass-Cow-Milk Pathway Dose Factors -INFANT (mrem/yr per gCi/m 3) for H-3 and C-14 (mi x mrem/yr laCi/sec) for others 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 -2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 Na-24 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61 E+7 1.61 E+7 P-32 1.60E+11 9.42E+9 ---2.17E+9 6.21E+9 Cr-51 -1.05E+5 2.30E+4 2.05E+5 4.71 E+6 1.61E+5 Mn-54 -3.89E+7 8.63E+6 -1.43E+7 8.83E+6 Mn-56 -3.21 E-2 2.76E-2 -2.91 E+0 5.53E-3 Fe-55 1.35E+8 8.72E+7 -4.27E+7 1.11E+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 -1.16E+8 1.88E+8 1.55E+8 Co-57 -8.95E+6 --3.05E+7 1.46E+7 Co-58 -2.43E+7 --6.05E+7 6.06E+7 Co-60 -8.81E+7 --2.1OE+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 --1.07E+8 1.21E+9 Ni-65 3.51E+0 3.97E-1 --3.02E+1 1.81E-1 Cu-64 -1.88E+5 -3.17E+5 -3.85E+6 8.69E+4 Zn-65 5.55E+9 1.90E+10 -9.23E+9 -1.61E+10 8.78E+9 Zn-69 ---7.36E-9 -Br-82 --. 1.94E+8 Br-83 --9.95E-1 Br-84 --.Br-85 -...Rb-86 -2.22E+10 --5.69E+8 1.10E+10 Rb-88 -....Rb-89 --...Sr-89 1.26E+10 -- --2.59E+8 3.61E+8 Sr-90 1.22E+11 -- --1.52E+9 3.10E+10 Sr-91 2.94E+5 -- --3.48E+5 1.06E+4 Sr-92 4.65E+0 ---5.01E+1 1.73E-1 Y-90 6.80E+2 -- --9.39E+5 1.82E+1 Y-91m -.....Y-91 7.33E+4 -- --5.26E+6 1.95E+3 Y-92 5.22E-4 -- --9.97E+0 1.47E-5 Y-93 2.25E+0 ---1.78E+4 6;13E-2 Zr-95 6.83E+3 1.66E+3 -1.79E+3 -8.28E+5 1.18E+3 Zr-97 3.99E+0 6.85E-1 -6.91E-1 -4.37E+4 3.13E-1 Nb-95 5.93E+5 2.44E+5 -1.75E+5 -2.06E+8 1.41E+5 Nb-97 .- -3.70E-6 -Mo-99 -2.12E+8 -_3.17E+8
-6.98E+7 4.13E+7 Tc-99m 2.69E+1 5.55E+1 -_ 5.97E+2 2.90E+1 1.61E+4 7.15E+2 Tc-101 -----2.0-38 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.14 (Page 2 of 2)R 1 Grass-Cow-Milk Pathway Dose Factors -INFANT (mrem/yr per jiCi/m 3) for H-3 and C-14 (M 2 x mrem/yr gCi/sec) for others ODCM 2.0 Revision 16 December 5, 2013 Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body Ru-103 8.69E+3 -1.81E+4 -1.06E+5 2.91E+3 Ru-1 05 8.06E-3 -5.92E-2 -3.21 E+0 2.71 E-3 Ru-106 1.90E+5 -2.25E+5 -1.44E+6 2.38E+4 Rh-1 03m -Rh-106 ---Ag-11Om 3.86E+8 2.82E+8 4.03E+8 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 -1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 -9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 --7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -1.70E+8 5.1OE+7 Te-127 6.50E+3 2.18E+3 5.29E+3 1.59E+4 -1.36E+5 1.40E+3 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -3.34E+8 8.62E+7 Te-129 2.08E-9 -1.75E-9 5.18E-9 -1.66E-7 -Te-131m 3.38E+6 1.36E+6 2.76E+6 9.35E+6 -2.29E+7 1.12E+6 Te-131 ------Te-132 2.1OE+7 1.04E+7 1.54E+7 6.51E+7 -3.85E+7 9.72E+6 1-130 3.60E+6 7.92E+6 8.88E+8 8.70E+6 -1.70E+6 3.18E+6 1-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -1.15E+8 1.41E+9 1-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 -2.34E+0 1.03E+0 1-133 3.72E+7 5.41 E+7 9.84E+9 6.36E+7 -9.16E+6 1.58E+7 1-134 --1.01E-9 ----1-135 1.21E+5 2.41 E+5 2.16E+7 2.69E+5 -8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 -1.75E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 -2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 -1.62E+10 6.55E+9 1.88E+8 4.27E+9 Cs-138 -------Ba-139 4.55E-7 --2.88E-5 1.32E-8 Ba-140 2.41E+8 2.41E+5 5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ba-141 --.Ba-142 -- --La-140 4.03E+1 1.59E+1 --1.87E+5 4.09E+0 La-142 ---5.21 E-6 -Ce-141 4.33E+4 2.64E+4 -8.15E+3 -1.37E+7 3.11E+3 Ce-143 4.OOE+2 2.65E+5 7.72E+1 -1.55E+6 3.02E+1 Ce-144 2.33E+6 9.52E+5 3.85E+5 -1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 2.08E+2 -7.89E+5 7.41E+1 Pr-144 -----Nd-147 8.82E+2. 9.06E+2 3.49E+2 -5.74E+5 5.55E+1 W-187 6.12E+4 4.26E+4 -2.50E+6 1.47E+4 Np-239 3.64E+1 3.25E+0 _ 6.49E+0 -9.40E+4 1.84E+0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 2.0-39 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.15 (Page 1 of 2)R 1 Ground Plane Pathway Dose Factors (M 2 x mrem/yr per IiCi/sec)ODCM 2.0 Revision 16 December 5, 2013 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0!0 0 0 Nuclide Any Organ H-3 C-14 _Na-24 1.21 E+7 P-32 _Cr-51 4.68E+6 Mn-54 1.34E+9 Mn-56 9.05E+5 Fe-55 Fe-59 2.75E+8 Co-57 4.37E+8 Co-58 3.82E+8 Co-60 2.16E+10 Ni-63 Ni-65 2.97E+5 Cu-64 6.09E+5 Zn-65 7.45E+8 Zn-69 Br-82 4.57E+7 Br-83 4.89E+3 Br-84 2.03E+5 Br-85 Rb-86 8.98E+6 Rb-88 3.29E+4 Rb-89 1.21E+5 Sr-89 2.16E+4 Sr-90 _-Sr-91 2.19E+6 Sr-92 7.77E+5 Y-90 4.48E+3 Y-91m 1.01E+5 Y-91 1.08E+6 Y-92 1.80E+5 Y-93 1.85E+5 Zr-95 2.48E+8 Zr-97 2.94E+6 Nb-95 1.36E+8 Nb-97 2.28E+6 Mo-99 4.05E+6 Tc-99m 1.83E+5 Tc-101 2.04E+4 Ru-103 1.09E+8 2.0-40 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Table 2.15 (Page 2 of 2)Ri Ground Plane Pathway Dose Factors (M 2 x mrem/yr per gCi/sec)ODCM 2.0 Revision 16 December 5, 2013 Nuclide Any Organ Ru-1 05 6.36E+5 Ru-106 4.21E+8 Rh-103m Rh-106 Ag-110rn 3.47E+9 Sb-1 24 2.87E+9 Sb-125 6.49E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-127 3.OOE+3 Te-129m 2.OOE+7 Te-129 2.60E+4 Te-131m 8.03E+6 Te-131 2.93E+4 Te-132 4.22E+6 1-130 5.53E+6 1-131 1.72E+7 1-132 1.24E+6 1-133 2.47E+6 1-134 4.49E+5 1-135 2.56E+6 Cs-134 6.75E+9 Cs-136 1.49E+8 Cs-137 1.04E+10 Cs-1 38 3.59E+5 Ba-1 39 1.06E+5 Ba-140 2.05E+7 Ba-141 4.18E+4 Ba-142 4.49E+4 La-140 1.91 E+7 La-142 7.36E+5 Ce-141 1.36E+7 Ce-143 2.32E+6 Ce-144 6.95E+7 Pr-143 Pr-144 1.83E+3 Nd-147 8.40E+6 W-187 2.36E+6 Np-239 1.71 E+6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.0-41 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-A Revision 16 December 5, 2013 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX A Content deleted. No longer being used.A-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 16 December 5, 2013 0 0 0 0 0 APPENDIX B TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS -GASEOUS RADIOACTIVE EFFLUENTS B-1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 16 December 5, 2013 APPENDIX B Technical Basis for Effective Dose Factors -Gaseous Radioactive Effluents 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors, which are radionuclide specific.
These effective factors, which can be based on typical radionuclide distributions of releases, can be applied to the total radioactivity released to approximate the dose in the environment (i.e., instead of having to perform individual radionuclide dose analyses only a single multiplication (Kerr, Meff or Neff) times the total quantity of radioactive material released would be needed). This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.
Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:
Keff = E (K X fi)(B1 (13.1)where: Keff Ki the effective total body dose factor due to gamma emissions from all noble gases released= the total body dose factor due to gamma emissions from each noble gas radionuclide "i" released the fractional abundance of noble gas radionuclide "i" relative to the total noble gas activity fi (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 noble gases released= the skin dose factor due to beta and gamma emissions from each noble gas radionuclide "i" released Meff = E(Mixfi)(B.3)B-2 KEWAUNEE POWER STATION ODCM App-B 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 where: Meff = the effective air dose factor due to gamma emissions from all noble gases released S Mi the air dose factor due to gamma emissions from each noble gas radionuclide "i" released Neff = -(Nixfi) (B.4)where: 0 Neff = the effective air dose factor due to beta emissions from all noble gases released N i the air dose factor due to beta emissions from each noble gas radionuclide "i" released Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from Kewaunee have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful evaluations difficult.
For the years of 2000, 2001 and 2002, the total noble gas releases have been limited to 2.54E-04 Ci for 2000, 1.37E-01 Ci for 2001, and 1.91E-02 Ci for 2002. Therefore, in order to provide a reasonable basis for the derivation of the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.1, "Source Term Specifications," has been used as representing a typical distribution.
The effective dose factors as derived are presented in Table B-1.0 Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used. This conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.
0 For evaluating compliance with the dose limits of ODCM Normal Condition 13.2.2, the following simplified equations may be used: 3.17E-08 Dy =-.7E-0 x X/Q x f Xo Z Qi (B.5)0.50 (Dp= 3.7 E -0 8 XX/QxNeff xzQi (B.6)0.50 0 0 0 B-3 0 0 0 0 0 0 0 0 S 0 0 0 0 S 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 16 December 5, 2013 where: 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)7IQ Meff Neff I Qi= atmospheric dispersion to the controlling SITE BOUNDARY (sec/m 3)= 5.3E+02, effective gamma-air dose factor (mrad/yr per gCi/m 3)= 1.1E+03, effective beta-air dose factor (mrad/yr per g.tCi/m 3)= 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 data Combining the constants, the dose calculational equations simplify to: D 7= 3.5E-05xX/QxlQa (B.7)0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 and ,= 7.OE-05XX/QxEQi (B.8)The effective dose factors are used on a very limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable.
Dose assessments using the detailed, radionuclide dependent calculation are performed at least annually for preparation of the Radioactive Effluent Reports. Comparisons can be performed at this time to assure that the use of the effective dose factors does not substantially underestimate actual doses.B-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-B Revision 16 December 5, 2013 Table B-1 Effective Dose Factors -Noble Gases Total Body Effective Skin Effective Dose Factor Dose Factor Keff (L+I.1 M)ef Radionuclide fi (mrem/yr per gCi/mr 3) (mrem/yr per gCi/mr 3)Noble Gases -Total Body and Skin Kr-85 0.01 -- 1.4E+01 Kr-88 0.01 1.5E+02 1.9E+02 Xe-133m 0.01 2.5E+00 1.4E+01 Xe-133 0.9 3.OE+02 6.6E+02 Xe-135 0.02 3.6E+01 7.9E+01 TOTAL 4.8E+02 9.6E+02 Noble Gases -Air Gamma Air Effective Beta Air Effective Dose Factor Dose Factor Meff Nff Radionuclide f& (mrad/yr per pCi/mr 3) (mrad/yr per gCi/m 3)Kr-85 0.01 -- 2.OE+01 Kr-88 0.01 1.5E+02 2.9E+01 Xe-133m 0.01 3.3E+00 1.5E+01 Xe- 133 0.95 3.4E+02 1.0E+03 Xe-135 0.02 3.8E+01 4.9E+01 TOTAL 5.3E+02 1.1E+03 S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 B-5 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-C Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX C EVALUATION OF CONSERVATIVE, DEFAULT EFFECTIVE EC VALUE FOR LIQUID EFFLUENTS C-1 0 0 KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 S Appendix C 0 Evaluation of Conservative, Default Effective EC Value for Liquid Effluents In accordance with the requirements of ODCM Normal Condition 13.3.1 the radioactive liquid effluent monitors shall be FUNCTIONAL with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed 10 times the value of 10 CFR 20, Appendix B, Table 2, Column 2 for all radionuclides other than noble gases and a value 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.0 In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established.
This default setpoint can be conservatively based on an evaluation of the radionuclide distribution of the liquid effluents from Kewaunee and the ECe value for this distribution.
0 The effective EC value for a radionuclide distribution can be calculated by the equation: EC. C= (C.1)-Ci ECi where: 0 ECe = an effective EC value for a mixture of radionuclide (pgCi/ml)S Ci = concentration of radionuclide "i" in the mixture ECi 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 from Kewaunee, an ECe value can be determined.
Effluent release data from 2000-2002 was used to generate the results presented in Table C-1. The most limiting effective EC (for gamma emitting radionuclides) was for the calendar year 2001, with a calculated value of 5.98E-06 ItCi/ml. For conservatism in establishing the alarm setpoints, a default effective EC value of 1.OE-06 gCi/ml was 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 EC C S C-25 S S S 0 0* KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 S* value provides a factor of six (6) conservatism based on the 2000-2002 radionuclide distribution for gamma emitters.*Being a non-gamma emitter, tritium is not detected by the effluent monitor. While tritium accounts for nearly all of the activity, it is not a significant contributor when determining the alarm setpoint for release rate evaluations.
Examining releases over the years 2000-2002, the average, diluted H-3 contribution to its limiting concentration (i.e., fraction of concentration
- limit -10 x EC) in liquid effluents was 0.004%. This contribution is not expected to change significantly over time, since the concentration of H-3 in effluents can be expected to remain fairly consistent in effluent releases regardless of fuel conditions, activation product releases, and 0waste processing.
Based on relative abundances, other non-gamma emitting radionuclides (Fe-55 and Sr-89/90)contributed up to 30% of the concentration limit (30% for CY 2001). It is reasonable to assume 0that the abundances of these non-gammas will remain the same relative to other fission and/or activation products under varying conditions.
Therefore, under conditions of elevated effluent radionuclide levels, the gamma-emitting radionuclides can be expected to be the main contributors to limiting conditions on liquid effluent concentrations, as established in Technical*Specification 5.5.3.b and ODCM Normal Condition 13.1.1. Note that including the non-gammas
- (excluding tritium) in the evaluation results in a higher effective EC value.Therefore, under conditions of elevated effluent levels, the main contributor to the limiting*conditions of the liquid effluent concentration would be the gamma-emitting radionuclides.
The factor of six (6) conservatism in the effective EC determination (discussed above) provides adequate consideration for the contribution from non-gamma emitting radionuclides, and provides a conservative basis for establishing an alarm setpoint consistent with the requirements
- of Technical Specification 5.5.3.b and ODCM Normal Condition 13.1.1.The Heating Boiler Blow Down and Turbine Building Sump are discharged to the lake with no* installed radiation monitor. Using the default effective EC value of 1.OE-06 jtCi/ml for*increased monitoring is consistent with the ODCM methodology if an installed radiation monitor was available.
0 0 0 0 0 0 0 0 0 0 0*C-3 0 0 0 KEWAUNEE POWER STATION ODCM App-C OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Table C-1 Calculation.
of Effective EC (ECe)2000 2001 2002 Nuclide EC (IiCi/ml)
T Release (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+00 Cr-51 5.OOE-04 1.44E-03 2.89E+00 6.85E-04 8.26E-04 1.65E+00 4.83E-04 0.OOE+00 0.OOE+00 0.OOE+00 Mn-54 3.00E-05 1.49E-04 4.97E+00 I. 18E-03 3.30E-04 1.1OE+01 3.22E-03 6.41 E-05 2.14E+00 9.83E-04 Fe-55 1.00E-04 4.81E-02 4.81E+02 1.14E-01 4.85E-02 4.85E+02 1.42E-01 3.69E-02 3.69E+02 1.70E-01 Co-57 6.OOE-05 0.OOE+00 0.OOE+00 0.OOE+00 2.42E-05 4.03E-01 1.18E-04 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 2.OOE-05 8.07E-03 4.04E+02 9.59E-02 4.09E-03 2.05E+02 5.99E-02 4.94E-03 2.47E+02 1.14E-01 Fe-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-03 Co-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-01 Br-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+00 Sr-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-02 Sr-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-02 Zr-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-03 Nb-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-03 Ag-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-01 Sn-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-03 Sb-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-03 Sb-125 3.OOE-05 4.86E-03 1.62E+02 3.85E-02 1.02E-03 3.41E+01 9.99E-03 2.46E-03 8.18E+01 3.76E-02 1-132 1.00E-04 0.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+00 1-133 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+00 1-135 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+00 Cs-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-03 Total 7.46E-02 4.21E+03 1.00E+00 6.34E-02 3.42E+03 1.00E+00 5.06E-02 2.17E+03 1.00E+00 Non-Gamma Fraction * : 0.23 _ _ _ _ _ 0.30 _ _ _ _, 0.29 Gamma Fraction _ _ _,_ 0.77 ,: _,_ _,_ 0.70 ,: ,: ,: 0.71 EC, (pCi/ml, total) 1.77E-05 1.86E-05 2.33E-05 ECe (pCi/ml, gammas) 8.03E-06 5.98E-06 8.44E-06 C-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 0 0 0 0 0 0 0 0 0 0 0 0 0 0.0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 APPENDIX D On-site Disposal of Low-Level Radioactively Contaminated Waste Streams D-1 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 Appendix D consists of hard copies of the following reference documents:
DESCRIPTION
[ DATE DOCKET NUMBER Operating License DPR-43 Kewaunee Nuclear Power Plant October 17, 1991 NRC-9 1-148 Disposal of Low Level Radioactive 50-305 Material Proposed Disposal of Low Level Radioactive Waste Sludge Onsite at the June 17, 1992 K92-119 Kewaunee Nuclear Power Plant 50-305 (TAC No. M75047)Safety Evaluation For An Amendment To An Approved 10 CFR 20.302 Application September 14, 1994 K-94-195 For The Kewaunee Nuclear Plant 50-305 (TAC No. M89719)Alternate Disposal Of Contaminated Sewage Treatment Plant Sludge In November 13, 1995 K-95-172 Accordance With 10 CFR 20.2002 50-305 (TAC No. M93844)Onsite Disposal Of Contaminated Sludge K-97-64 Pursuant To 10 CFR 20.2002 April 9, 1997 50-305 (TAC No. M9741 1) 1 1 _1_0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Adapted from N D-2 0 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 WPSC ( 414) 433.1598 TELECOPIER (414) 433-5544 00 WISCONSIN PUDUIC SERVICE CORPOSUATIONd 61- %.artn AcarýS 0 PO Sax 19002 a Green Bav. W1 5d3C7-GC02 INRC 91-/14 EASYLINK 628S '993 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 bce -K M Badow, MGE N E Boys, WPL Larry Nielsen, ANFC D R Berg KNP D A Bollom 06 R E Drshtim KNP K H Evers 02 M L Marchi KNP D L Masank KNP I N Morrison D2 I R Mueller D2 D S Nf,,hqplk KNP L A Nuitls D2 (NSRAc)R P Pulec D2 I S Richmond D2 D J Ristau D2 D I Roon KNP.-7 T- /,6J A J Ruege D2 C A Schrock KNIP C S Smoker KNP C R Steinhardt D2 I I Wallsace KNP K H Weinhauer KNP S F Womiak D2 QA Vault KNP October 17, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Diwsosal of Low Level Radioactive Material
References:
- 1) Letter from K.H.Evers to Document Control Desk dated September 12, 1989 2) Letter from M.Y.Davis to K.H.Evers dated February 13, 1990 3) Letter from L.Sridharon (WDNR) to M.Vandenbusch dated June 13, 1991 In reference 1, pursuant to the regulation of 10 CFR 20.302, Wisconsin Public Service Corporation (WPSC) requested authorization for the alternative disposal of very-low-level radioactive materials from the Kewaunee Nuclear Power Plant. In reference 2, the US NRC identified additional questions that needed to be addressed in order to complete their review.Attachment I provides our response to the questions.
WPSC requested the State of Wisconsin Department of Natural Resources (WDNR) to review the disposal options for the service water pretreatment lagoon sludges. In reference 3, the WDNR completed a review of the most appropriate on site disposal methods for the slightly contaminated service water pretreatment lagoon sludges' The two proposed methods that the WDNR evaluated included in-situ capping of the sludge in the wastewater treatment lagoon and on site landspreading.
In Attachment 1, Appendix A, WPSC evaluated the on site landspreading D-3 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Page 2 application which is our preferred disposal method. WPSC does not intend to utilize the in-situ capping of the sludge in the lagoon at this time. However, in the letter the WDNR agreed that either disposal method was acceptable provided:-if the material is to be left in the lagoon, it would be capped in accordance with Wisconsin State statutes.-if the on site landspreading option is utilized, the material would be spread by either disking into the soil or by spiking into the ground.WPSC will abide by the WDNR landspreading requirements which include locational and performance standards.
Should there be any additional questions please feel free to contact a member of my siaff.Sincerely, c~c( Z.'A.L C. A. Schrock Manager -Nuclear Engineering DJM/jms Attach.6 0 0 0 0 0 0 S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S cc -.US NRC -Region 1l Mr. Patrick Castleman, US NRC D-4 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 ATTACHMENT I To 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Letter from K. H. Evers (WPSC) to Document Control Desk (NRC)Dated October 17, 1991 D-5 S KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 1 References
- 1) Letter from K. H. Evers to Document Control Desk dated September 1, 1989. 0 NRC Question #1 On page 4 of your submittal, the average input to the Sewage Treatment System is approximately 11,000 gallons per day. In the Final Environmental Statement, this system is to be operated below its design capacity of 9,000 gallons per day. Discuss this deviation from the design capacity, and provide information to justify the higher output for this system.WPSC Response The original Sewage Treatment System installed at the Kewaunee Nuclear Power Plant (KNPP) was replaced in 1986 with a higher capacity system. The original system was designed for an onsite work force of around 150 people.It was a limited capacity aerobic treatment system which included the onsite lagoon for additional retention.
Because of this limited capacity and more stringent conditions on system effluent to Lake Michigan, an aerobic digester system was installed, which has a higher capacity, and uses current technology.
The estimated input volume to the Sewage Treatment System used in the September 12, 1989 application was 11,000 gallons per day. This value was based on past operating data. The increase in influent from the original design basis included in the Final Environmental Statement is due mainly to an increase in the number of individuals and facilities (e.g., training and simulator building) located onsite. Design changes to the system were required to accommodate these new facilities.
0 0 0'D-60 0 0 0 0 0* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0Document Control Desk*October 17, 1991 Attachment 1, Page 2 0 The current volumes of sewage sludge were used as the basis for the potential dose analysis and corresponding radionuclide concentration limits. This increase has no significant effect on the dose modeling. (Refer to the response*to NRC Question #2, below.)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.0 Administrative controls will be established to ensure that the actual disposal of*any slightly contaminated materials from KNPP are within the bounds of the*evaluation.
Samples from each of the waste streams will. be collected and*analyzed by gamma spectroscopy prior to release for disposal.
A system*lower limit of detection (LLD) of 5E-07/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.
Any materials with levels of radioactive material above the concentration limits D 0 0*D-7 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Document Control Desk October 17, 1991 Attachment 1, Page 3 (and of plant origin) will be treated as a radioactive waste and appropriately controlled.
0 Records will be maintained to ensure that the cumulative disposal of any contaminated materials are maintained within the bounds of the evaluation.
[n 0 addition to a comparison of the individual radionuclide concentration limits, a record of the total amount of radioactive material disposed of will be maintained.
Cumulative totals will be maintained to ensure that the total activity does not exceed the quantity assumed in the derivation of the limits.In developing the concentration limits presented in Table I of reference 1, it was assumed the total annual design basis volume of 27,000 ft 3 would be contaminated at the derived limit. The dose commitment from each radionuclide was individually evaluated as if it were the only radioactive material present. To determine if a mixture of radionuclides meets the limit, the sum-of-the-fractions rule should be applied (i.e., the sum of each radionuclide's concentration divided by its limiting concentration must be less than one)..The concentration limits of Table I of reference I also have an implied total activity limit. This limit is determined by multiplying the individual radionuclide concentration limit by the total estimated waste volume of 27,000 ft 3.These total activity limits are presented in Table A of this response, for each radionuclide individually.
For a mixture of radionuclides, a total annual activity limit may be determined by normalizing the concentrations so that the sum-of-the-fractions for the mixture equals one (1). These resultant adjusted concentrations may be multiplied by the 27,000 ft 3 waste volume to determine the corresponding total activity limit of the mixture.0 0 0 D-8 0 0 0 0* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0*Document Control Desk October 17, 1991 Attachment I, Page 4 0A Disposal Log will be maintained on a calendar year basis for all disposals of any very-low-level radioactive materials.
The log will contain as a minimum the following information:
- Disposal location* Description of waste* 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 activity 0 0*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 Response The potential exposure to the general public (onlookers along route) is modeled by the IMPACTS-BRC code. As addressed in NUREG/CR-3585, this modeling is based on an integration of the source strength, an assumed D*D-9 0 0 0 O KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 Document Control Desk 0 October 17, 1991 Attachment I, Page 50 population density along route and vehicular speed. For a conservative evaluation of the potential exposure to the general public from the transport of the KNPP waste, a population density of 610 persons/mi 2 was assumed. This value is conservative for the KNPP site area where the average population density is less than 53 persons/mi 2.A transport distance of 45 miles was 0 assumed. The IMPACTS-BRC modeling assumes five (5) tons of material are 0 transported per shipment.
For the assumed KNPP waste volume, this shipment weight translates into a total of 167 shipments per year. With a vehicular speed of 20 miles per hour, the resultant total population exposure time is 375 person-hours per year. At the concentration limits established for the alternative disposal, the potential onlooker doses during transport will be less than 0.01 person-rem..per year. For the modeling of the exposure to the transport worker, the IMPACTS-BRC model assumes two drivers per vehicle. 0 As presented in the September 12, 1989 submittal, the maximum dose to the 0 driver is less than I mrem per year (<0.001 remlyr). Therefore, the total 0 collective 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 the population is less than 0.02 person-rem (0.002 person-rem
+ 0.01 person-rem 0< 0.02 person-rem).
0 For the disposal of the existing 15,000 f0 3 of contaminated sludges, the S population dose due to the transportation of the waste is calculated to be 0.0002 person-rem.
The estimated collective exposure to the transport worker is 0.00007 person-rem.
The total collective dose due to transport of the waste is 0.00027 person-rem.
0 0 D-lO 5 0 0 0 0* KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 Document Control Desk* October 17, 1991 Attachment 1, Page 6 0 Additional Potential Disposal Method 0The 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.
0 0 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 response 0 provides an overview of the land spreading disposal method. Also, the 0 0 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 a modeling standpoint, the two exposure scenarios, "Radiation Exposure During* Transport' and "Radiation Exposure to Landfill Operator," appropriately
- characterize any potential exposure to workers involved with the land* spreading of the waste. 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 limits 0proposed in the September 12, 1989 submittal to include the option for 0 0 D-1I 0 0 10 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL Document Control Desk October 17, 1991 Attachment 1, Page 7 ODCM App-D Revision 16 December 5, 2013 Table A Radionuclide Quantity Limits for Alternative Disposal Limiting Limiting Annual Nuclide Concentration Quantity (pCi/ml) (Ci)H-3 9.65E-04 0.7382 C-14 4.55E-05 0.0348 Cr-51 3.13E-04 0.2394 Mn-54 1.14EM05 0.0087 Fe-55 l-00E-02 7.6500 Fe-59 7.90E-06 0.0060 Co-58 1.16E-05 0.0089 Co-60 3.74E-06 0.0029 Ni-63 i.00E-02 7.6500 Sr-90 3.45E-03 2.6393 Zr-95 6.28E-06 0.0048 Nb-95 1.23E-05 0.0094 Mo-99 6.73E-05 0.0515 Tc-99 2.70E-04 0.2066 1-129 2.50E-06 0.0019 1-131 2.68E-05 0.0205 Cs- 134 6.16E-06 0.0047 Cs-137 1.71E-05 0.0131 Ba-140 5.52E-05 0.0422 La- 140 4.17E-06 0.0032 Transuranics.TRU (T'IA > 5 yrs) 8.91E-05 0.0682 Pu-241 2.85E-03 2.1803 Cm-242 1.00E-02 7.6500 Assumes annual quantity of KNPP wastes is 27,000 ft 3 or 7.65E8 mls.S 0 0 0 0 S 0 0 S 0 0 S 0 0 0 S 0 0 S 0 S S D-12 0* KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 SDecember 5, 2013 0Document Control Desk* October 17, 1991 Attachment 1, Page 8 0 Appendix A* Evaluation of Onsite Land Application for* Alternative Disposal of Very-Low-Level Contaminated Materials 0 Overview*Land spreading of lagoon sludges onsite at the Kewaunee Nuclear Power Plant has been*recommended by personnel from the Wisconsin Department of Natural Resources (DNR) as*a desirable alternative to the use of the Kewaunee County Landfill for disposal.
This method*of disposal is also a recommended practice for disposing of sewage treatment facility sludges.*Therefore, WPS requests that this disposal method be included in the options available for*the alternative disposal of very-low-level radioactively contaminated materials from KNPP.Description of Disposal Method* The disposal of KNPP sludges will he performed by beneficial land application to a dedicated*disposal area located onsite at the Kewaunee Nuclear Power Plant. Typical methods of land spreading will be employed.
KNPP sludges will be loaded onto appropriate vehicles (e.g.,*tanker truck, sludge spreader, etc.) and applied to the dedicated disposal area. The dedicated* disposal area will be periodically plowed to a depth of 6 inches.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 for human 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 0sludge contaminants will be applied to the KNPP wastes even though the less restrictive Non-0Agricultural 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 as 0 0*D-13 0 0 0 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 Document Control Desk October 17, 1991 Attachment 1, Page 9 performed previously.
In addition, other limitations as applied to land application by the State of Wisconsin Department of Natural Resources will be followed (e.g., control of runoff/erosion, proximity to wells/residences/surface water, etc.).Applicable Pathways of Exposure The pathways of exposure applicable for land spreading are not appreciably different from the pathways evaluated for the disposal methods at the Kewaunee County Landfill or the Green Bay Metropolitan Sewerage District facilities.
The major exposure pathways are discussed below: Direci Exposure to Workers 0 Any potential exposures to workers involved in the removal, transport and land spreading of the sludges are reasonably bound by the evaluation of the exposure to the transport worker in the September 12, 1989 submittal.
The0 transport worker has been assumed to be exposed for 460 hours0.00532 days <br />0.128 hours <br />7.60582e-4 weeks <br />1.7503e-4 months <br /> per year at one (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 the lagoon sludges will require no longer than a three week period per year (i.e., 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />).The potential exposure to a worker onsite after land spreading, has been estimated at no more that 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year. Such an individual would be involved in land maintenance activities, such as plowing and mowing. As modeled in the September 12, 1989 submittal, an exposure of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year to the landfill operator has been assumed. For this exposure, the KNPP materials are mixed with other landfill waste: a 1:13 mixing of KNPP materials to other waste is assumed. This mixing is not significantly different from the type of mixing that will occur in the field with the sludges being 0 D-14 0 0 0
- KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16*December 5,2013 0*Document Control Desk*-October 17, 1991 Attachment 1, Page 10 plowed into the soil to a depth of six (6) inches. With a land spreading of 50 metric tons per hectare per year, a mixing ratio of 1:30 will be achieved.*Therefore, the resultant dose to the exposed worker would be less than the I*mrem per year dose to the transport worker as evaluated in the September 12,*1989 submittal.
- Post Disposal Exposure -Intruder Scenario* The IMPACTS-BRC model, as applied to the disposal of the KNPP waste, assumes a*loss of institutional controls 10 years after closure of the site (See Appendix B of the.September 12, 1989 submittal).
An individual is assumed to reside in a house built*on -the disposal area. This individual receives a direct exposure (from the uncovered*waste), an inhalation exposure (from resuspension), and an ingestion exposure (from*growing % 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.0 IThe onsite land application of KNPP waste will be limited by the Agricultural Land 0Application sludge concentrations even though the less restrictive Non-Agricultural 0Land Application sludge concentrations are applicable since a "dedicated land S disposal" site will be used (i.e., no crops will be grown on the disposal site).Therefore, provided the KNPP waste does not exceed the Non-Agricultural maximum sludge concentrations for heavy metal or organic chemicals, unlimited application of*waste to the dedicated land disposal site is allowed. However, to be conservative, the*land application of KNPP wastes will be limited to 5 metric tons per hectare per year.*The intruder scenario as evaluated in the September 12, 1989 submittal conservatively
- bounds this exposure pathway for the on-site land spreading.
0 0 0 D-1 0 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 Document Control Desk 5 October 17, 1991 Attachment 1, Page 11 Post Disposal -Intruder Well The intruder well pathway for onsite land disposal is essentially the same as the intruder well pathway as evaluated by the IMPACTS-BRC model. It is conservatively assumed that the well is located at the edge of the disposal site. As modeled, locating the well at the disposal site edge in "downstream flow" direction maximizes the 5 calculated hypothetical dose. (Additional discussion of this modeling is presented in 5 NUREG/CR-3585, Volume 2).S The potential dose for the intruder well scenario for the land spreading disposal would be 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. S In summary, the modeling of the exposure scenarios, as presented in the September 12, 1989 submittal, conservatively bounds the hypothetically exposures for the on-site land spreading.
In no case is it likely that any individual, either on-site or off-site, will receive a dose in excess of I mrem per year from the disposal of the slightly contaminated materials.
5 0 S S S S S S S S S S D-16 5 0 0 S KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 K.1-H UNITED STATES NUCLEAR. REGULATORY COMMISSION WASHINGTON.
D.C. 0 0 0 0 S S 0 0 0 S 0 0 June 17, 1992 Docket No. 50-305 Mr. C. A. Schrock Manager -Nuclear Engineering Wisconsin Public Service.Corporation P. 0. Box 19002 Green Bay, Wisconsin 54037-9002
Dear Mr. Schrock:
SUBJECT:
PROPOSED DISPOSAL OF LOW LEVEL RADIOACTIVE WASTE SLUDGE ONSITE AT THE KEWAUNEE NUCLEAR POWER PLANT (TAC NO. M75047)By letters dated September 12, 1989. and October 17, 1991, you submitted a request pursuant to 10 CFR 20.302 for the disposal of waste sludge onsite at the Kewaunee Nuclear Power Plant. We have completed our review of the request and find your procedures, including documented commitments, to be acceptable.
This approval is granted provided that the enclosed safety evaluation is permanently incorporated into your Offslte Dose Calculation Manual (ODCM) as an Appendix, and that future modifications of these commitments are reported to the NRC.Issuance of this safety evaluation completes all effort on TAC No. M75047.Sincerely, Allen G. Hansen, Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated.cc w/enclosure:
See next page NRC LETTER DISTRIBUTION T A Hanson (MG&E)J D Loock (WPL)Larry Nieisea (ANFC)J L Belant (NSRAC)D A Bollom G6 K H Evers KNP J P Gieslet D2 M L Marchi KNP D L Mosarik KNP R P Pulec D2 (2)D J Riitau D2 A I Ruege D2 C A Schrock D2 C Rt Swinhar D2 T J Webb KNP S F Womiak D2 QA Vault KNP D-17 0 KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: David Baker. Esquire Foley and Lardner P.O. Box 2193 Orlando, Florida 32082 Glen Kunesh, Chairman Town of Carlton Route 1 Kewaunee, Wisconsin 54216 Mr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse Kewaunee, Wisconsin 54216 Chairman 0 Public Service Commission of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U.S. Nuclear Regulatory Comisslon Resident Inspectors Office Route 01, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator
-Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois.
60137 Mr. Robert S. Cullen Chief Engineer Wisconsin Public Service Commission P.O. Box 7854 Madison, Wisconsin 53707 D 0 0 0 0 0 0 0 0 0 0 0 D-18 0 0 0 0 W KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16* December 5, 2013 NUCLEAR 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 PLANT W WSCONSIN PUBLIC SERVICE CORPORATION WISCORSIN POWER AND LIGHT COMPANY MADISON GAS AND ELECTRIC COtPANY*DOCKET NO. 50-305 0
1.0 INTRODUCTION
In reference
.1, Wisconsin Public Service Corporation (WPSC) requested approval pursuant to Section 20.302 of Title 10 of the Code of Federal Regulations (CFR) for the disposal of licensed material not previously considered in the Kewaunee Final Environmental Statement (FES) dated December 1972. Additional 4rglated material from the licensee,, from the State of Wisconsin, and from the staff 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 on radioactivity absorbed from liquid discharges of licensed material.
The*15,000 cubic feet of contaminated sludge identified in the request contains a total radionuclide inventory of 0.17 mCi of Cesium-137 and Cobalt-6O.
In its submittal, the licensee addres;ed specific information requested in*accordance with 10 CFR 20.302(a), provided a detailed description of the licensed material, thoroughly analyzed and evaluated the information pertinent 0to the effects on the environment nf the proposed disposal of licensed material, and committed to follow specific procedures to minimize the risk of 0unexpected exposures.
2.0 DESCRIPTION
OF WASTE*During the normal operation of Kewaunee, the potential exists for in-plant process streams which are not normally radioactive to become contaminated with very low levels of radioactive materials.
These waste streams are normally separated frqm the radioactive streams. However, due mainly to infrequent, minor system leaks, and anticipated operational occurrences, the potential exists for these systems to become slightly contaminated.
At Kewaunee, the tecondary system demineralizer resins, the service water pre-treatment system sludges, the make-up water system resins, and the sewage treatment plant sludges are waste streams that have the potential to become contaminated at very low levels.0 0 0 0 0 D-I 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013-2-0 During the yearly testing of a batch of pre-treatment sludge, it was found that approximately 15,000 cubic feet of sludge had been contaminated with Cs-137 and Co-60.3.0 PROPOSED DISPOSAL METHOD WPSC plans to dispose of the 15,000 cubic feet of contaminated sludge onsite pursuant to 10 CFR 20.302. The sludge is currently contained in an onsite lagoon at the KNPP sewage treatment facility.
The disposal of the sludge will be by land application to an area located onsite at KNPP, as shown in Figure 1. 7he area will be periodically plowed to a depth of 6 inches.Table I lists the principal nuclides identified in the sludge. The activity is based on measurements made in 1989. The radionuclide half-lives, which are dominated by 30-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (reference 6), which apply to radionuclides with half-lives less than 35 y e a r s .T Nuclide Total Activity (mCil Co-60 0.076 Cs-137 0.094 0.170 0 4,0 RADIOLOGICAL tMPACTS The licensee has evaluated the following potential exposure pathways to members of the general public from the radionuclides in the sludge: (1)external exposure caused by groundshlne from the disposal site; (2) internal exposure from inhalation of re-suspended radionuclides; and (3) internal exposure from ingesting ground water. The staff has reviewed the licensee's calculatlonal methods and assumptions and finds that they are consistent with NRC Regulatory Guide 1,109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977. The staff finds the assessment methodology acceptable.
Table 2 lists the doses calculated by the licensee for the maximally exposed member of the public based on a total activity of 0.170 Wi disposed of in the current year, as well as the cumulative Impact of similar disposals during subsequent years. For any repetitive disposals, the licensee must reapply to the NRC when a particular disposal would exceed the following boundary conditions:
(1) the annual disposal must be less than a total activity of 0.2 mCi; (2) the whole body dose to the hypothetical maximally exposed individual must be less than 0.1 mrem/year; and (3) the disposal must be at the same site as described in Figure 1.0 0 0 0 0 0 D-20 0 0 0
- KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0*~ -3 Whole Body Dose Received by Maximally Exposed Individual Pathway (mrem/vear)
Groundshlne 0,034 Inhalation 0.008* Groundwater Ingestion 0.007 TOTAL As shown in Table 2, the annual dose Is expected to be on the order of 0.1 mrem or less. Such a dose is a small fraction of the 300 mrem received annually by members of the general public from sources of natural background radiation.
oThe guidelines used by the NRC staff for onsite disposal of licensed material are presented in Table 3, along with the staff's evaluation of how each guideline has been satisfied.
0 The licensee's procedures and commitments as documented in the submittal are acceptable, provided that they are permanently incorporated Into the licensee's Offsite Dose Calculation Manual (00CM) as an Appendix, and that* 0 Future modifications be reported to NRC In accordance with the applicable ODCM change protocol.Based on the above findings, the staff finds the licensee's proposal to dispose of the low level radioactive waste sludge onsite in the manner described in the WPSC letter dated September 12, 1989, to be acceptable.
The State of Wisconsin has. also approved these procedures (reference 5).0 0 0 0 0 0 0 S 0 0 0 0 0 0 0*) D-2I 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL-4 -TABLE 3 20.302 Guideline for onsite Disposea ODCM App-D Revision 16 December 5, 2013 Staff's Evaluation
- 1. The radioactive material should be disposed of in a manner that it is unlikely that the material would be recycled.2. Doses to the total body and any body organ of a maximally exposed individual (a member of the general public or a non-occupationally exposed worker) from the probable pathways of exposure to the disposed material should be-less than I mrem/year.
- 3. Doses to the total body and any body organ of an inadvertent intruder from the probable pathways of exposure should be less than 5 mrem/year.
- 4. Doses to the total body and any body organ of an individual from assumed recycling of the disposed material at the time the disposal site is released from regulatory control from all likely pathways of exposure should be less than I mrem.1. Due to the nature of the disposed material, recycling to the general public is not considered likely.2. This guideline is addressed in Table 2..3. Because the material will be land-spread, the staff considers the maximally exposed individual scenario to also address the intruder scenario.4. Even if recycling were to occur after release from regulatory control, the dose to the maximally exposed memberof the public is not expected to exceed 1 mrem/year, based on the exposure scenarios considered in this analysis.0 0 0 0 0 0 S S 0 0 C 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 D-22 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013-.5-BELL&LKLZ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 (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 For Additional 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 Natural Resources 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 Health Physics Society's midyear Symposium on Health Physics Considerations in Decontaminatlon/Decommissionlng, Knoxville, TN, February 1986 (CONF-850203).
Principal Contributor:
J. Minns Date: June 17. 1992 D-23 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013-6-Figure I Kewaunee Nuclear Power Plant Site Area Map 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D-24
- KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013+ ,#A UNrTED STATES9/14 REGULATORY COMMMISlON O
- 14. 1994.Mr. C. A. Schrock Manager -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 20.302 APPLICATION 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 waste sludge In addition to the location approved by the NRC on June 17, 1992. The staff has completed its review of your request and finds that your proposal meets the radiological boundary conditions approved In the June 17. 1992.*Safety Evaluation, and Is therefore acceptable.
The staff also finds that your proposal is in accordance with 10 CFR 20.2002 which replaced 20.302 on*January 1, 1994.This approval is granted provided that the enclosed Safety Evaluation is permanently Incorporated Into your Offsite Dose Calculation Manual (O0CM) as 0 an Appendix, and that future modifications of these comitments are reported* to the NRC.*Sincerely,*Richard J. Laufer, Acting Project Manager*Project Directorate
[11-3 Division of Reactor Projects Ill/IV*Office of Nuclear Reactor Regulation
- Docket No. 50-3os
Enclosure:
Safety Evaluation cc w/enclosure:
0see next page T TA (M"uti K A imp XJ[ CCS Sminr NP M W Siz(WPL) ML mURD Loau7 NWam V .N D L ) ]lp C A Stauim" D2 DAIaouN JN mDI T JW mbbIM D ICO b hIp L A Nlu*b MAC) 3 1 WaNk D2 K H Sven KNP R P Pdw D2 (2) QA VIlt h P O D-25* PidegO KEWAUNEE POWER STATION ODCM App-D OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: 0 Foley & Lardner Attention:
Mr. Bradley D. Jackson 0 One South Ptnckney Street P. 0. Box 1497 0 Madison, Wisconsin 53701-1497 Chairman Town of Carlton Route I Kewaunee.
Wisconsin 54216 0 Mr. Harold Reckelberg.
Chairman " Kewaunee County Board Kewaunee County Courthouse 0 Kewaunee, Wisconsin 54216 Chairman Public Service Comilsslon of S Wisconsi un Hill Farms State Office Building Madison, Wisconsin 53702 Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U. S. Nuclear Regulatory Commission Resident Inspectors Office Route 01, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator
-Region III U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle. Illinois 60632-4531 0 Mr. Robert S. Cullen 0 Chief Engineer Wisconsin Public Service Comuission P. 0. Box 7854 Madison, Wisconsin 53707 02 0)01 01 0)D-26 01 01 01.* 40 S KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 UN.ITD STATES NUCLEAR REGULATORY COMMISSION 0 ASHl~ rNINO ON .0 0 U U O SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION O RELATING TO ONSITE DISPOSAL OF LOW-_LEVEL RADIOACTIVELY
- CoNTA[NATE TM SLUOE S~AT THE KEWAUNEE NUCLEAR POWER PLANT O WISCONSIN PUBLIC SERVICE CORPORATION VISCONIN POWER AND LIGE-CONPANY O DOCKET NO, 50-305 O O 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 another onsita area for the disposal of contaminated waste sludge in addition to the location approved by the NRC on June 17, 1992.2.0 EVALUATION O A Safety Evaluation (SE) dated June 17, 1992, approved the licensee's request pursuant to 10 CFR 20.302 for the dis sal of 15,000 cubic feet of contaminated waste sludge by land application at the Kewaunee Nuclear Power O 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 lagoon at the KNPP sewage treatmant facility.
In 1993. approximately 7500 cubic feet of the original IS,000 cubic feet of contaminated sludge was spread on that location.
The licensee has now proposed to dispose of the remaining contaminated sludge at another onsite location northwest of the plant (see Attachment).
The licensee has comitted that the new disposal.
locatioit will meet all the radiological boundary conditions contained in the SE for the 10 CFR 20.302 application approved on June 17, 1992. Additionally, the licensee has stated that this additional disposal site will meet all O 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 and performance standards that were required at the original disposal site.O O O O D-27 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 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 the radiological boundary conditions approved In the June 17, 1992, SE and Is therefore acceptable.
The staff also finds that your proposal is In accordance 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 20.302 application, the licensee Is required to permanently Incorporate this modification into the Offsite Dose Calculation Manual as an Appendix, and that future modification of this comitment be reported to the NRC.Principal Contributor:
S. [lementowicz Date: September
- 14. 1994
Attachment:
KNPP Site Area'Hap D-28 S 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 0 S S 0 0 0 S 0 0 0 S 0 0 S S S S 0000000000000000000000000000000000000000000o KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013--------------------- ftaj--------------------------2.D-29 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 NE@~\q U UNITED STATES NUCLEAR REGULATORY COMMISSION WAUHINGTO1, D.2O. 4 November 13, 1995 A'460d- / I -;t D -7S-Mr. M. L. Marchl Manager -Nuclear Business Grop Wisconun Public Service Corporation Post Office Box 19002 Green 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, you requested approval for the onsite disposal of contmainated seoge treatmnt sludge in accordance with 10 CFR 20.2t. This request was simlar to a previous disposal request that was approved by the NRC on June 17, 1992.The staff has completed Its review of your request and finds that your proposal 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 Is permanently incorporated into you Offsite Dose Calculation Manual (O0CN) as an Appendix, and that future modifications of these comitments are reported to the NRC.Sincerely, Richard J aoProject Manager Project Directorate 111-3 Division of Reactor Projects 111/IV Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosure:
Safety Evaluation cc: See next page S 0 0 0 0 0 0 0 0 0 0 S 0 S S S 0 S S 0 0 0 0 0 T A li==o (MG&E)M W SUn (WPL)Lacy Nichm (ANFC)D A MGMwz 06 D 6 Day DI K H Event XNP bf L Mudd D2 I X Jubin (NSRAC)R P.P" XW ~(3)C A Schrock 1WP C S Smatar KWH C R Sleinhaa*
D2 CA Sunkty KNP(Uc)S IF Wazd*a D2 al Domnick XNP (Corn)D-30
- KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 O Hr. H. L. Marchi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: Foley A Lardner Attention:
Mr. Bradley 0. Jackson One South Pinckney Street P. 0. Box 1497 Madison, Wisconsin 53701-1497 Chairman Town of Carlton O Route I Keaunee. Wisconsin 54216 0 Mr. Harold Reckelberg, Chairman O Kewaunee County Board Kewaunee County Courthouse 0 Kewaunee, Wisconsin 54216 O Chal man Public Service Commission of Wisconsin Hill Farms State Office Building O NMdison. Visconsin 53702 Attorney General 114 East, State Capitol* Madison, Wisconsin
$3702 U. S. Nuclear Regulatory Couission Resident Inspectors Office 0 Route #1, Box 999 Kewaunee, Wisconsin 54216 Regional Administrator
-Region III U. S. Nuclear Regulatory Commission 801 Varrenville Road Lisle, Illinois 60532-4531 0 'Mr. Robert S. Cullen O Chief Engineer Wisconsin Public Service Commssion P. D. Box 7854 Madison, Wisconsin 53707 0 0 0 0 0 O 0 0 0 O D-3I 0 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013*A UNITED STATES NUCLEAR REGULATORY COMMISSION at WA.MI.,TON, .o, D. =04 SA~FTY EVALUATIIN, 5? ThF OFFtcE OF NUCLEAR RFACTOR RESULAIIOM RELATING TO ONSITE DISPOSAL OF LOM-LEVEL RADIOACTIVELY 0 CONTANINATED SEWAGE TR.AUTHT SLUDGE AT THE KWAUNEE NUCLEAR POWER PLMN WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADISON GAS AND ELECTRIC COMPANY DOCKET NO.50-30S O0 1.0 INTOMIIM By letter dated October 17, 1995, os supplemeted on Novomber 3, 1995, Wisconsitn Public Servce Corporation (the licensee) requested approval for the onsite dtsposal of contaminated smogs sludge similar to a previous disposal request that was approved by the NRC on Juno 17. 1992.2.0 MACKGRMW In a letter dated September 12, 1989, the licensee requested authorization for the alternate disposal of very-low-level radioactive material.
In a Safety Evaluation (SE) dated June 17, 1992, the 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 wasta sludge by land application at the Kewaunee Nuclear Power Plant (KNPP) location.
The SE imposed the following boundary conditions:
- 1. The annual disposal must be less than a total activity of 0.2 MCI.2. The whole body dose to the hypothetical maximally exposed Individual must be less than 0.1
- 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 boundary conditions of the previously approved disposal.3.0 *YALUAI.WI The 1 icensee has proposed to dispose of approximately 5000 gallons (800 cubic O feet) of sewage sludge similar to the material approved for disposal in the SE dated June 17, 1992. The principal radlonuclides identified In the waste sludge and their activity based on measurements In Nay 19,9 are: Co-58, D 0 0 S D-32 O O 0 0 KEWAUNEE POWER STATION ODCM App-D O OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 O 0.0009 ict; Co-60, 0.0008 mCi; and Cr-51, 0.0006 mCI. The total combined activity is 0.0023 noi. This activity is well below the boundary value of 0.2 mCi. Additionally, Cr-Il with It short half-life (27.7 day) will have O undergone significant decay from Its Initial value of 0.0006 mCi.* The licensee has committed that the now disposal will met all the radiological boundary conditions, on a cumulative basis, contained In the SE for the 10 CFR 20.M02 application approved on June 17, 1992. Additionally, the licensee has stated that all applicable permits for this disposal have been obtained from the Wisconsin Department of Natural Resources.
O
4.0 CONCLUSION
O The staff finds the licensee's proposal to dispose of the lo-level radioactive waste sludge pursuant to 10 CFR 20.2002, on the licensee's site (see Attachment), is within the radiological boundary conditions approved in Sthe June 17, 1992, SER and Is therefore acceptable.
- The licensee Is required to perumantly incorporate this modification Into the OffsIte Dose Calculatien Mlanual as an Appendix, and to ensure that fture modifications of these commitments are reported to the NRC.O Principal Contributor:
S. Klementowicz Date: Novenber 13, 1995*
Attachment:
KNPP Site Area Nap D-1 O 0 O 0 0 S 0 O O O 0 0 0 O 0 0 0 O D-33 0 0 0 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 I........................
i D-34 D-34 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 kl-? 7- Z/0 0 0 0 0 0 0 S 0 0 0 UNrfED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON.
D.0. Ma.4M April 9, 1997 Mr. M. L. Marchi Manager -Nuclear Business Group Wisconsin Public Service Corporation Post Office Box 19002 Green 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. Nuclear Regulatory Conmission (NRC) review the applicability of a 10 CFR 20.203 (now 20.2002) application approved on June 17, 1992, for additional disposals of a similar nature.The staff has completed its review of your request and agrees with your determination that the 10 CFR 20.203 application for onsite disposal of sludge contaminated with licensed radioactive material, which was approved on June 17, 1992, contains bounding conditions that are applicable for additional onsite disposals of a similar nature. A copy of the Safety Evaluation Is enclosed.Sincerely, Richard J. Lader, Project Mlanager Project Directorate 111-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosure:
Safety Evaluation cc: See next page bmtn L-G m 2 mNr T A HA==i (MO&Z)M WSob (WMO D AD=?06 D 9 Day DI K H Rve" ~p b(L bradic D2 I1a.,g KNPQ4IRAC)
R P Pdg X4p (3)C A Sdwm KNP C S sawbw X" CR&AWw&D2%oauWANMk)ý-
'; F Wa* D2 WD*=3iCkrRRftxheffii0 MP MO-TSAR)D-35 KEWAUNEE POWER STATION ODCM App-D U OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 Mr. N. L. Marchi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc: 0 Foley & Lardner Attention:
Mr. Bradley D. Jackson One South Pinckney Street P. 0. Box 1497 Madison, Wisconsin 53101-1497 Chatrman Town of Carlton 0 Route I Kewaunee, Wisconsin 54216 Hr. Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse Kewaunee, Wisconsin 54216 Chairman Wisconsin Public Service Commission 610 N. Whitney Way Madison, Wisconsin 53705-2729 Attorney General 114 East, State Capitol Madison, Wisconsin 53702 U. S. Nuclear Regulatory Commission Resident Inspectors Office Route fl, Box 999 Kewaunee, Wisconsin 54216 Regional AWilnistrator
-Region III U. S. Nuclear Regulatory Comuisston 801 Warrenville Road " 0 Lisle, Illinois 60532-4531 Mr. RFobert S. Cullen Chief Engineer Wisconsin Public Service Commission 610 N. Whitney Way Madison, Wisconsin 53705-2829 0 S 0 0 0 0 0 0 0 0 D-36 0)S 0 0
- KEWAUNEE POWER STATION ODCM App-D* OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0 UNITE STATES.NUCLEAR REGULATORY COMMISSION WA5*O0GTON.
D.C,.0op SAFETY 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 COMPANY MADISON GAS ANO ELECTRICCONPANY
- DOCKET NO. 50-305 0 1 L Io By letter dated December 10, 1996, Wisconsin Public Service Corporation (the licensee) requested that the U.S. Nuclear Regulatory Commission (NRC) review*its determination that NRC approval, pursuant to 10 CFR 20.2002. for the onsite disposal of contaminated sludge at the Kewaunee Nuclear. Power Plant (KNPP) is not required, provided such disposals are conducted within the limits and bounding conditions approved by the NRC In its June 17, 1992,* Safety Evaluation (SE).
2.0 BACKGROUND
In a letter dated September 12, 1989, the licensee requested authorization for the alternate disposal of sludge contaminated with licensed radioactive
- material.
In an SE dated June 17, 1992, the NRC approved the licensee's request pursuant to 10 CFR 20.302 (new 10 CFR 20.2002) for the disposal of*15,000 cubic feet of contaminated waste sludge by land application at the KNPP location.
The SE imposed boundary conditions as follows: 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; and 3. The disposal must be at the same site.The SE also stated that for any repetitive disposals, the licensee must* reapply to the NRC when a particular disposal would exceed the .boundary conditions.
0 3.0 EALOA71ON The licensee has determined that NRC approval for future onsite disposals of*sludge contaminated with licensed radioactive material is not required provided the disposals comply with the limits and conditions of the SE issued on June 17, 1992. The licensee has also developed a sludge sampling and analysis procedure that implements the guidance contained in NRC Information D* D-37 0 0 0 0 KEWAUNEE POWER STATION ODCM App-D 0 OFFSITE DOSE CALCULATION MANUAL Revision 16 December 5, 2013 0I Notice 88-22. Specifically, the licensee's procedure will require the analysis 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 0 licensee 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 0 disposals of contaminated sludge, which are conducted within the bounding limits and conditions contained in the June 17, 1992,. SE and within the areas specified in the attached site map, do not require specific NRC approval.
0 The licensee should permanently Incorporate this Safety Evaluation into the Offsite Dose Calculation Manual as an Appendix.Principal Contributor:
S. Klementowicz Date: April 9, 1997 Attachpent:
KNPP Site Map 03 01 01 0)0)01 01 01 01 01 01 01 01 01 01 01 D-38 01 01 01 01 KEWAUNEE POWER STATION OFFSITE DOSE CALCULATION MANUAL ODCM App-D Revision 16 December 5, 2013 i Il*i t D-39 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 This page intentionally left blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0* RdooiAlpenviromna Moiorn* RailglEnvisionmetl20itrn
- October 31, 2013 S S S S S S S 0 S S S S S S S S S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 This page intentionally left blank 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S Dominion Energy Kewaunee, Inc.Kewaunee Power Station 0 0 0 0 0 0 0 S 0 0 S 0 0 0 0 0 0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL (REMM)Revision 20 DATE: October 15 ,2013 Approved By: Approved By: Reviewed By: Reviewed By: JM Hale /Manager -Radiological Protection and Chemistry RP Repshas/Licensing Supervisor Date: Date: Date: Date: 9/30/13 10/7/13 10/10/13 10/15/13 Jeffrey T. Stafford /Facility Safety Review Committee AJ Jordan /Site Vice President KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM Revision 20 October 15, 2013 Table of Contents 1.0 Introduction
....................................................................................................................
1-1 1.1 1.2 1.3 Purpose ................................................................................................................
1-1 Scope ...................................................................................................................
1-1 Implementation
......................................................................................................
1-1 2.0 R EM P R equirem ents ....................................................................................................
2-1 2.1 O DCM 13.5 Requirements
...................................................................................
2-1 2.2 REM M Requirements
...........................................................................................
2-2 REM M 2.2.1/2.3.1 M onitoring Program ...............................................................
2-3 REM M 2.2.2/2.3.2 Land Use Census ...................................................................
2-7 REMM 2.2.3/2.3.3 Interlaboratory Comparison Program ....................................
2-10 REM M 2.4.1 Reporting Requirements
.................................................................
2-12 3.0 R EM P Im plem entation ..................................................................................................
3-1 3.1 3.2 3.3 3.4 3.5 3.6 Sampling Requirements
.........................................................................................
3-1 Analysis M ethodology
...........................................................................................
3-1 Detection capability (LLD) Requirements
...............................................................
3-1 Contracted Vendor (CV) Reporting Requirements
.................................................
3-2 Quality Control Program .......................................................................................
3-3 Sample Descriptions
..............................................................................................
3-3 0 0 0 0 S 0 0 0 S 0 0 0 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 Tables & Figures Table 2.2.1-A Table 2.2.1-B Table 2.2.1-C Table 2.2. 1 -D Table 2.3.1-A Radiological Environmental Monitoring Program Type and Frequency of Collection Sampling Locations, Kewaunee Power Station Reporting Levels for Radioactivity Concentrations in Environmental Samples Detection Capabilities for Environmental Sample Analysis Lower Likit of Detection (LLD)Figure 1 Figure 2 Environmental Sampling Location Ground Monitoring Wells 0 0* KEWAUNEE POWER STATION REMM RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15, 2013 1.0 Introduction 1.1 Purpose*The purpose ofthis document is to define the RadiologicalEnvironmental Monitoring Program (REMP) for the Kewaunee Power Station (KPS). The REMP is required by ODCM 13.5.*This document is known as the Radiological Environmental Monitoring Manual (REMM) and is intendedlo serve as a tool for program administration and as a guidance document for contractors which implement the*monitoring program.1.2 Scope This program defines the sampling and analysis schedule which was developed to provide representative 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 not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.
Guidance for the development of this monitoring program is provided by the*Radiological Assessment Branch Technical Position on Environmental Monitoring.
This program has been*developed in accordance with NUREG 0472.The program will provide field and analytical data on the air, aquatic, and terrestrial radioecology 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 as required by KPS TS 5.5.1. The REMM is controlled as a separate document for ease ofrevision, use in the field and use by contractors.
This format was approved by the NRC as part of TS Amendment No. 64,*which provided Radiological Effluent Technical Specifications (RETS) for KPS.0 0 0 0 0 0 S*1-I 0 0 0 0 0 KEWAUNEE POWER STATION REMM 0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15, 2013 The REMP is set up to be implemented by a vendor and controlled by KPS in accordance with Nuclear Administrative 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 checked and approved by KPS in accordance with Surveillance Procedure SP-63-280.
All sample collection, preparation, and analysis are performed by the vendor except where noted. Surveillance Procedure SP-63-164 outlines the environmental sample collection performed by KPS. Current vendor Quality Control Program Manuals and implementing procedures shall be kept on file at KPS.Periodic reviews of monitoring data and an annual land use census will be used to develop modifications to the existing monitoring program. Upon approval, these modifications will be incorporated into this document so that it will accurately reflect the current radiological environmental monitoring program ineffect for KPS.The remainder of this document is divided into two sections.
The first section, 2.0 REMP Requirements, describes the different TS and REMM requirements associated withtheRBlvlP.
The second section, 3.0 REMP Implementation, describes the specific requirements used to implementthe REMP.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1-20 0 0 0 0* KEWAUNEE POWER STATION REMM RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15, 2013 2. 0 REMP Requirements
- KPS TS Amendment No. 104 implemented the guidance provided in Generic Letter 89-01,*'Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS)."*These changes included: 1. Incorporation of programmatic controls in the Administrative Controls section of the T"S to satisfy* existing regulatory requirements for RETS, and 0 2. Relocation of the procedural details on radioactive effluents monitoring, radiological environmental monitoring, reporting details, and other related specifications from the TS to the ODCM.*Relocating the procedural details to the ODCM allows for revising these requirements using the*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, and c. Participation in an Interlaboratory Comparison Program.0 The details of each requirement are described in the REMM requirements stated below.*Technical Specification
5.6.1 requires
an "Annual Radiological Environmental Operating Report," be submitted to the NRC each year. The specific contents of this report are detailed in*REMM 2.4.1. Additional specific reporting requirements are listed in the other REMM requirements.
0 0 0 0 0 0 0 0*2-1 0 0 0 0 KEWAUNEE POWER STATION REMM S RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15, 2013 2.2 REMMRequirements S The following REMM requirements include the procedural details that were originally located in the KPS RETS 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 this document for ease of use and completeness.
The REMM requirements for the Monitoring Program, Land Use Census, and the Interlaboratory Comparison Program include a detailed operating requirement (numbered 2.2.1, 2.2.2, and 2.2.3 respectively) and an associated verification requirement (numbered 2.3.1, 2.3.2, and 2.3.3 respectively), along with the basis for the requirement.
Reporting requirements are listed in requirement REMM 2.4.1.0 ODCM 13.0, USE AND APPLICATION, apply to both the ODCM and REMM.2 S S S S S S S S S S S S S S S S S S 0 S S S S 2-25 S S S KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REMM Revision 20 October 15, 2013 REMM 2.2.1 APPLICABILITY:
The radiological environmental monitoring program shall be conducted as specified in Table 2.2.1-A.At all times.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Radiological Environmental A.1 Prepare and submit to the In accordance with the Monitoring 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 Report description of the reasons frequency.
for not conducting the program as required and the plans for preventing a recurrence.
B. Level of radioactivity in an B.1 --------NOTES------
environmental sampling 1. Only applicable if the medium at a specified radioactivity/radionuclides location exceeds the are the result of plant reporting levels of REMM effluents.
Table 2.2.1-0 when 2. For radionuclides other than averaged over any those in REMM Table 2.2.1-calendar quarter. D, this report shall indicate the methodology and OR parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.2-3 KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM Revision 20 October 15, 2013 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME More than one of the radionuclides in REMM Table 2.2.1-D are detected in the environmental sampling medium and Concentration 1 Reporting level 1-+Concentration 2 + .-2 1.0.Reporting level 2 OR Radionuclides other than those in REMM Table 2.2.1-D are detected in an environmental sampling medium at a specified location which are the result of plant effluents and the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is >the calendar year limits of DNC 13.1.2, DNC 13.2.2, DNC 13.2.3 Prepare and submit to the NRC, a Special Report, pursuant to DNC 15.3, that (1) Identifies the cause(s)for exceeding the limit(s) and (2) Defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of DNC 13.1.2, DNC 13.2.2, DNC 13.2.3 OR B.2 -------NOTES------
- 1. Only applicable if the radioactivity/radionuclides are not the result of plant effluents.
- 2. For radionuclides other than those in REMM Table 2.2.1-D, this report shall indicate the methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC.Report and describe the condition in the Annual Radiological Environmental Operating Report.30 days In accordance with the Annual Radiological Environmental Operating Report freauencv.
0 0 0 S 0 0 S S S S 0 S S S S S S S S S S S S S S S S S S S S 0 S S S S S S 2-4 KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM Revision 20 October 15, 2013 0 0 0 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 ACTIONS (continued)
NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME C. Milk or fresh leafy vegetation C.1 Identify specific alternative 30 days samples unavailable from locations for obtaining one or more of the sample replacement samples and locations required by REMM add them to the Table 2.2.1-A. Radiological Environmental Operating Program.AND C.2 When changes in sampling locations are permanent, then the sampling schedule in the REMM will be updated to reflect the new routine and alternative sampling locations.
This revision will be submitted in the next Annual Radiological Environmental Operating I_ Report.VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.1 Collect and analyze radiological environmental In accordance with monitoring samples pursuant to the requirements of REMM Table 2.2.1-REMM Table 2.2.1-A and the detection capabilities A required by Table 2.2.1-A.2-5 0 0 KEWAUNEE POWER STATION REMM 0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15,2013 BASES 0 The radiological environmental monitoring program required by this requirement provides representative 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 THE PUBLIC resulting from the station operation.
This monitoring program implementsSection IV.B.2 of Appendix I to 1 OCFR Part 50 and thereby supplements the radiological effluent monitoring programby verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.
Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
Program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the 0 lower limits of detection (LLDs). The LLDs required by Table 2.3.1-A are considered optimum for routine environmental measurements in industrial laboratories.
It should be recognized that the LLDis defined as a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination
-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K.,"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).0 I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2-60 0 0 0 KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS REMM Revision 20 October 15, 2013 REMM 2.2.2 A land use census shall: a. Be conducted, b. Identify within a distance of 8 km (5 miles) the location, in each of the 10 meteorological sectors, of the nearest milk animal and the nearest residence, and the nearest garden > 50 m 2 (500 ft 2) producing broad leaf vegetation, sampling of leaf vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Requirements for broad leaf vegetation sampling in REMM Table 2.2.1-A item 4c shall be followed, including analysis of control samples.APPLICABILITY:
At all times.0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Land use census identifies A.1 Identify the new location(s)
In accordance with the location(s) that yields a in the next Radiological Radiological calculated dose, dose Environmental Operating Environmental commitment greater than Program. Operating Report.the values currently being calculated in ODCM 13.2.3.1.2-7 0 0 REMM 0 Revision 20 KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL October 15, 2013 NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME B. Land use census identifies B.1 Add the new location(s) to 30 days location(s) that yields a the Radiological calculated dose, or dose Environmental Operating commitment (via the same Program.exposure pathway) greater than 20% at a location from AND which samples are currently being obtained in B.2 Delete the sampling In accordance with accordance with locations(s), excluding the Radiological REMM 2.2.1. control station location, Environmental having the lowest calculated Operating Report.dose, dose commitment(s) or D/Q value, via the same exposure pathway, from the Radiological Environmental Operating Program.AND B.3 Submit in the next Radiological Environmental Operating Report documentation for a change which includes revised figures(s) and table(s)reflecting the new location(s) with information supporting the change in sampling locations.
I VERIFICATION REQUIREMENTS VERIFICATION FREQUENCY REMM 2.3.2 Conduct the land use census during the growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, reporting the results of the land use census in the Annual Radiological Environmental Operating Report, or by consulting local agriculture authorities.
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2-8 U KEWAUNEE POWER STATION REMM* RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15,2013*BASES 0 This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the door-to-door survey, from aerial survey or from consulting with local agricultural authorities.
This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50. Restricting the census to gardens of greater than 50 m 2 provides assurance that*significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in*Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:* 1. 20% of the garden was used for growing leafy vegetation (i.e., similar to lettuce and* cabbage), and 2. A vegetation yield of 2 kg/rn.0 0 0 0 0*0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0*2-9 0 10 KEWAUNEE POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL REMM Revision 20 October 15, 2013 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM REMM 2.2.3 APPLICABILITY:
Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.
At all times.ACTIONS NON-CONFORMANCE CONTINGENCY MEASURES RESTORATION TIME A. Analyses not performed as A.1 Report the corrective actions In accordance with required.
taken to prevent a recurrence the Annual to 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 with Interlaboratory Comparison Program in the Annual the Annual Radiological Environmental Operating Report. Radiological Environmental Operating Report.BASES The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.S 0 S 0 0 0 S 0 S 0 0 S 0 0 S 0 0 0 S S S S S S S S S S S S S S S S 2-10 0 0* KEWAUNEE POWER STATION REMM RADIOLOGICAL 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 the radiological 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 the observed impacts ofthe plant operation on the environment.
The reports shall aso include 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 be submitted as soon as possible in a supplementary report when applicable.
- c. A summary description of the radiological environmental monitoring program;*legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline ofone reactor; the results of licensee participation in the 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 include summaries, 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, along with 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.0 0 0 0 0*2-11 0 0 0 0 KEWAUNEE POWER STATION REMM RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15, 2013 3. 0 REMP Implementation The Radiological Environmental Monitoring Program for KPS is under the direction of a Contracted Vendor (CV). This section describes this program, as required by REMM 2.2.1 and the process the CV uses to perform it.3.1 Sampling Requirements S Table 2.2. 1-A identifies the various samples required by the REMP. Identified in the "available sample locations" column in Table 2.2.1-A are the sample locations selected, in conjunction with the vendor, to meet or exceed the REMP requirements.
Table 2.2.1 -B includes the same requirements as in Table 2.2.1 -A but presents the information in a different format by identifying the type of samples required at each location and the collection frequency.
Table 2.2.1 -C identifies the location and description ofeach sample location.
Figure 1 shows the physical location of each sample point on an area map.3.2 Analysis Methodology Analytical procedures and counting methods employed by the CV will follow those recommended by the U.S. Public Health Service publication, Radioassay Procedures for Environmental Samples, January 1967;and the U.S. Atomic Energy Commission Health and Safety Laboratory, HASL Procedures Manual (HASL-300), 1972. The manual is also available on-line at www.emLst.dhs.gov/publications/procman.
Updated copies will be maintained in KPS's vault.0 3.3 Detection Capability (LLD) Requirements The required detection capabilities for environmental sample and analysis are tabulated in terms of lower limits of detection (LLDs) in Table 2.3.1 -A. The LLDs required by Table 2.3.1 -A are considered optirim for routine environmental measurements in industrial laboratories.
It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as ana posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination
-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K.,"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).3 0 0 0 0 3-10 0 0 0
- KEWAUNEE POWER STATION REMM RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20*October 15, 2013 3.4 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 Reports S Annual reports will be submitted in two parts. Part 1, to be submitted to the NRC, will be prepared in accordance with NRC Regulatory Guide 4.8. It will contain an introductory statement, a summary of* results, description of the program, discussion 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 datawil be complemented by figures of representative spectra if requested by KPS. Draft copies of each annual report will be due 60 days after completion of the annual period. After final review of the draft document,*one photoready copy of the revised annual report will be sent to KPS for printing.Non-Routine Reports*If analyses of any samples collected show abnormally high levels of radioactivity, KPS will be notified by*telephone immediately after data becomes available.
Action Limits*The CV will report any radioactive concentrations found in the environmental samples which exceed the reporting levels shown in Table 2.2. 1-D, CV to KPS column. These levels are set below the NRC required reporting levels (KPS to NRC column) so actions can be initiated to prevent exceeding the NRC* concentration limits.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 QC Procedures Manual. The program shall be reviewed and meet the requirements of Regulatory Guide 4.15 and 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*3-2 0 S S 0 KEWAUNEE POWER STATION REMM RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15, 2013 3.6 Sample Descriptions A description of each of the samples required by this program follows: Airborne Particulates 0 Airborne particulates are collected at six locations (K-If; K-2, K-8, K-31, K-41, and K-43) on a continuous basis on a 47 mm diameter membrane filter of 0.8 micron porosity at a volumetric rate of approximately one cubic foot per minute (CFM). The filters are changed weekly, placed in glassine protective envelopes, and dispatched by U.S. Mail to the CV for Ganma Isotopic Analysis.
Filter samples are analyzed weekly for gross beta activity after sufficient time (usually 3 to 5 days) has elapsed to allow decay of Radon and Thoron daughters.
If gross beta concentration in air particulate samples are greater than ten (10) times the yearly mean ofthe control samples, gamma isotopic analysis shall be performed on the individual samples. Quarterly composites from each location receive Garmma Isotopic Analysis usirga Germanium detector.
All identifiable gamma-emitters are quantified.
Reporting units are pCi/m 3.Airborne Iodine All air samplers are equipped with charcoal traps installed behind the particulate filters for collection of airborne 1- 131. The traps are changed once every week. Iodine- 131 is measured by Gamma Isotopic Analysis.Periphyton (Slime) or Aquatic Vegetation 0 Periphyton (slime) or aquatic plant samples are collected at or near locations used for surface water sampling.
They are collected twice during the year (2nd and 3rd quarter), if available.
The samples are analyzed for gross beta activity and, if available in sufficient quantity, for Sr-89, Sr-90, and by Gamma Isotopic Analysis.
Reporting units are pCi/g wet weight.0 Fish Fish 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 by Ganma Isotopic Analysis.
The bones are analyzed for gross beta activity and Sr-89 and Sr-90. Reporting units are pCi/g wet weight.Domestic Meat Domestic meat (chickens) may be collected once a year during the 3rd quarter, fromthree locations inthe vicinity of the plant (K-24, K-29, and K-32). Samples may not be available every year at every location due to farmer preference.
At least one control and one indicator should be collected.
The flesh is analyzed for gross alpha, gross beta, and by Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides.
Reporting units are pCi/g wet weight.0 3-3 0 0 S S
- KEWAUNEE POWER STATION REMM* RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20* October 15,2013 Ambient Radiation* Two packets ofthermoluminescent dosimeters (CaSO 4: 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 is 0 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 ofihe measurement, each packet will contain two cards with four dosimeters each (four sensitive areas each for a* total of eight). For protection against moisture each set of cards is sealed in a plastic bag and placed in a plastic container.
- Each card is individually calibrated for self-irradiation and light response.
Fading is guaranteed by the* manufacturer (Teledyne Isotopes) not to exceed 20% in one year. Minimum sensitivity for the multi-area dosimeter is 0.5 mR defined as 3 times the standard deviation of the background.
Maximum Error (1* standard deviation)
-6 0 Co 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 Water 0 One gallon water samples are taken once every three months from four off-site wells, (K- 10, K- 11, K- 13, and K-38) and two on-site wells (K-lh and K-lg). All samples are analyzed for gross beta inthe total residue, K-40, tritium, and by Gamma Isotopic Analysis.
Samples from one on-site well are analyzed for* Sr-89, and Sr-90. Samples from K-lh and K-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.3 0 0 0 0 0 0* 3-4 0 0 0 0 KEWAUNEE POWER STATION REMM 0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15,2013 S Milk Milk samples are collected from two herds that graze within three miles of the reactor site (K-38 and K- 0 34); from four herds that graze between 3-7 miles ofthe reactor site (K-3, K-5, K-35, and K-39); andone from 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 monthly for the rest of the year. To prevent spoilage the samples are treated with preservative.
All samples are analyzed by Gamma Isotopic Analysis and for iodine -131 immediately alter they are received at the laboratory.
To achieve required minimum sensitivity of 0.5 pCi/l, iodine is separated on an ion exchange column, precipitated as palladium iodide and beta counted. Monthly samples and monthly composites of semimonthly samples are then analyzed for Sr-89 and Sr-90. Potassium and calcium are determined and the 1 3 7 Cs/gK and 9 0 Sr/gCa ratios are calculated.
Reporting units are pCi/l except for stable potassium and calcium, which are reported in g/L If milk samples are not available, green leafy vegetables will be collected on a monthly basis (when available) from Locations K-23A, K-23B, and K-26.Grass Grass is collected three times per year (2nd, 3rd, and 4th quarters) from the six dairy farms (K-3, K-5, K-35, K-34, K-38' and K-39) and from two on-site locations (K- lb and K- 1). The samples are analy-ed for 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 feed Once per year, during the first quarter when grass is not available, cattle feed (such as hay or silage) is collected from the six dairy farms. The analyses performed are the same as for grass. Reporting units are pCVg wet weight.Vegetables and Grain 0 Annually, during the 3rd quarter, samples of five varieties of vegetables grown and marketed for human consumption are collected from K-26, depending upon the availability of samples. If samples are not available from this location, samples may be obtained from any local source so there is some sample of record. The location will be documented.
In addition, two varieties of grain or leafy vegetables from the highest predicted X/Q and D/Q, ifavailable, are collected annually from the farmland owned by Dominion Energy Kewaunee (K-23 a and b) and rented to a private individual for growing crops. The analyses performed are the same as for grass. Reporting units are pCi/g wet weight.0 0 0 3-50 0 0 0 S* KEWAUNEE POWER STATION REMM RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15,2013 0*Quarterly samples of eggs can be taken from K-24 and K-32. At least one control and one indicator*should be collected.
The samples are analyzed for gross beta activity, for Sr-89 and Sr-90, and Gamma Isotopic Analysis to identify and quantify gamma-emitting radionuclides.
Reporting units are pCi/g wet weight.* 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 Water Surface water is sampled monthly from Lake Michigan at the KPS discharge (K-Id), two samples (north and south ends), of Two Creeks Park, 2.5 miles south of the reactor site (K- 14a, K-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 and from the drainage pond (K- 1 k) south of the plant. The samples are taken at a point near the mouth of each creek and at the shore of the drainage pond. The water is analyzed for gross beta activity in: a. The total residue, b. The dissolved solids, and c. The suspended solids.*The samples are also analyzed for K-40 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 of S sediment) increases with decreasing particle size, the sampling procedure will assure collection ofvery fine*particles.
Reporting units are pCi/g dry weight.3 S S*3-6 S S 0 0 KEWAUNEE POWER STATION REMM 0 RADIOLOGICAL ENVIRONMENTAL MONITORING MANUAL Revision 20 October 15, 2013 0 Ground Monitoring Wells Figure 2 shows the location of 14 installed groundwater monitoring wells. The wells and location are identified with a diamond shape in Figure 2. The wells are labeled MW (Monitoring Well) and AB (Auxiliary Building).
The Groundwater Protection Program consists ofthe 14 wells in addition to the two on-site wells already in the 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 Annual Radiological Environmental Operating Report for K-I g, K-lh and in the annual Radioactive Effluent Release Report for the other 14 wells.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3-70 0 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 0 S 0 S 0 S S 0 0:0 Table 2.2.1-A Radiological Environmental Monitoring Program Sampling, Exposure Pathway Minimum Available Sample Collection and Type ofAnalysis And/Or Sample Required Samples Locations b Analysis Frequency 1. Direct Radiation' 13 Inner Ring locations K-5, K-25, K-27, See Table 2.2.1-B Gamma dose K-43, K-If, K-30, K-ll, K-I1m, K-In, K-lo, K-1p, K-1 q, K-1 r, K-i s 6 Outer Ring locations K-2, K-3, K-1 5, K-17, K-8, K-31, K-39 1 Control location K-41 1 Population center K-43 I Special interest location K-8 I Nearby resident K-27 2. 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) by and Particulates boundary in highest K-31 Continuous Gamma Isotopicf average X/Q sampler operation Iodine; charcoal I sample from the closest K-43 Particulates Particulates; community having the See Table 2.2.1-B gross beta highest X/Q analysise Gamma I sample from a control K-41d See Table 2.2.1-B isotopic of location composite (by location) f 3. 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 isotopic K-Ik,K-lb K-40'Composite of grab samples for tritium, K-40 and Sr 89/90 b. Ground 1-2 location likely to be K-lg, K-lhh Grab sample Gamma isotopic affected d See Table 2.2.1-B tritium and K-40 analysis Gross Beta, one well for Sr 89/90 Rev. 20 October 15, 2013 Page I of 4 Table 2.2.1-A Radiological Environmental Monitoring Program Sampling, Exposure Pathway Minimum Available Sample Collection and And/Or Sample Required Samples S Locations b Analysis Frequency c. Drinking 1-3 samples of nearest K-10, K-11, K-13, K-38 Grab sample Gross beta and water supply See Table 2.2.1-B garmm isotopic analysis.
Tritium and K-40 analysis of the composite of monthly grab samples. 'd. Sediment from I sample from K-14, K-ic, K-Id, K-ij, Grab sample Gamma isotopic t shoreline downstream area with K-9 See Table 2.2.1-B analysis potential for recreational Gross Beta, value Sr 89/90 4. Ingestion a. Milk Samples from milking K-5k, K-38, K-34 See Table 2.2.1-B 1-131 animals in 3 locations Gamma Isotopic r within 5 km (if none, then 3 locations between 5 to SR 89/90 8 km) having the highest dose potential.
I alternate location K-3, K-39 1 control location K-35, K-42 b. Fish 3 random samplings of K-id See Table 2.2.1-B Gamma isotopic commercially and and Gross Beta on recreationally important edible portions, species in the vicinity of Gross Beta and the discharge.
Sr 89/90 on bones c. Food Products Samples of grain or leafy 2 samples K-23a, K-23b See Table 2.2.1-B Gamma isotopic T vegetables grown nearest -and one more and 1-131 each of two different location if available Analysis.offsite locations within 5 miles of the plant if milk sampling is not 1 sample 15-30 km performed.
distant if milk sampling is not performed.
K-26 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Rev. 20 October 15, 2013 Page 2 of 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Table 2.2.1-A Radiological Environmental Monitoring Program Sampling, Exposure Pathway Minimum Available Sample Collection and Type ofAnalysis And/Or Sample Required Samples a Locations b Analysis Frequency 5. Miscellaneous samples not identified in NUREG-0472
- a. Aquatic Slime None required K-lk See Table 2.2.1-B Gross Beta K-Ia, K-I1, K-le activity and if available Sr-89, K-14, K-Id Sr-90 and Gamma Isotopicf K-9 (control)b. Soil None required K-I f, K-5, K-35, K-39 Gross Alpha/Beta K-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90 K-3, (control)
Gamma Isotopicf c. Cattle feed None required K-5, K-35, K-39 Gross Beta K-34, K-38 See Table 2.2.1-B Sr-89 and Sr-90 K-3,(control)
Gamma Isotopicf d. Grass None required K-lb, K-If, K-35, K-39 Gross Beta K-5, K-34, K-38 See Table 2.2. I-B Sr-89 and Sr-90 K-3,(control)
Gamma Isotopicf e. Domestic Meat None required K-24, K-29 Gross See 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 Beta K-24 Sr-89/90_Gamma Isotopicf g. Precipitation None required K-Il See Table 2.2.1-B Tritium Rev. 20 October 15, 2013 Page 3 of 4 0 S 0 0 Table 2.2.1-A Radiological Environmental Monitoring Program Sampling, Eqposure Pathway Minimum Available Sample Collection and And/Or Sample Required Samples Locations b Analysis Type of Analysis Frequency Table Notations a. The samples listed in this column describe the minimum sampling required to meet REMP requirements.
- b. Additional details of sample locations are provided in Table 2.2.1-C and Figure 1. The REMP requires that samples to be taken from each of the "available sample locations" listed (see section 3.1). Deviations from the required sampling schedule will occur if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, reasonable efforts shall be made to complete corrective actions prior to the end of the next sampling period.All deviations from the sampling schedule shall be documented, as required by REMM 2.4.1.c, in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the REMM. The cause of the unavailability of samples for that pathway and the new location(s) for obtaining replacement samples will be identified in the Annual Radiological Environmental Operating Report.c. For the purposes of this table, each location will have 2 packets ofthermoluminescent dosimeters (TLDs). The TLDs are CaSO4: Dy cards with 2 cards/packet and 4 dosimeters/card (four sensitive areas each for a total of eight dosimeters/packet).
The NRC guidance of 40 stations is not an absolute number. The number of direct radiation monitoring stations has been reduced according to geographical limitations; e.g., Lake Michigan.
The frequency of analysis or readout forTLD systems depends upon the characteristics of the specific systemused and selection is made to obtain optimum dose information with minimal fading.d. The purpose of this sample is to obtain background information.
If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.
- e. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.f. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.g. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.
The "downstream" sample shall be taken in an area near the mixing zone.h. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
In the event elevated analysis are reported by CV for gamma isotopic or tritium, a review will be conducted with the option to retest additional analysis for hard to detect isotopes or alpha emitters.
The additional test may include Fe-55, Ni-63, or alpha emitters anticipated on current plant conditions.
- j. Two samples to be collected, Raw and Treated k. K-5 is about 5.1 km, closest Milk Location available.
S 0 0 Rev. 20 Page 4 of 4 October 15, 2013 S 0 0 0 0 S 0 0 0 0 0 0 0 S S 0 0 0 S 0 0 0 Table 2.2.1-B Type and Frequency of Collection Location Weekly Monthly Quarterly Semi-Annually Annually K-la SW SLt K-lb SW GW SL!K-ic BSb K-ld SW Fla BSb SLO K-le SW SL!K-If AP-, Al (le TLD so K-Ig WW K-lh WW K-Ij BSb K-lk SW SL!K-lI TLD K-im TLD K-in TLD K-lo TLD K-lp TLD K-lq TLD K-Ir TLD K-is TLD K-2 AP-,AI TLD K-3 MIC GW TLD SO C~d K-5 MIC (WR TLD SO ad K-8 AP-, AI TLD K-9 SWI BSb SL K-10 WW K-11 PR WW K-13 WW K-14 SWh BSb SL!K-15 TLD K-17 TLD K-23a GRN/GLVe K-23b GRN/GLVe K-24 EG DM K-25 TLD K-26 Rev. 20 October 15, 2013 Page 1 of 2 Table 2.2.-B Type and Frequency of Collection Location Weekly Monthly Quarterly Semi-Annually Annually K-27 TLD K-29 DM K-30 TLD K-31 AP&,AI TLD K-32 EG DM K-34 MIC (IV SO a K-35 MIC (V SO CFad K-38 MIC (V WW SO CFad K-39 Mil TLD (cIV SO a K-41 AP-, AI TLD K-42 MIC K-43 AP 8', AI TLD a. Three times a year, second (April, May, June), third (July, August, September), and fourth (October, November, December) quarters b. To be collected in May and November c. Monthly from November through April; seminMonthly from May through October d. First (January, February, March) quarter only e. Alternate if milk is not available f Second and third quarters g. The frequency may be increased dependent on the dust loading.h. Two water samples are collected, North (K- 14a) and South (K- 14b) of Two Creeks Rd.i. Two samples, raw and treated Code Description Code Description Code Description Al Airborne Iodine Fl Fish SO Soil AP Airborne Particulate GR Grass SW Surface Water BS Bottom Sediment GRN Grain TLD Thermoluminescent Dosimeter CF Cattle feed MI Milk VE Vegetables DM Domestic Meat PR Precipitation WW Well Water EG Eggs SL Slime (ILV Green Leafy Vegetables 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Rev. 20 October 15, 2013 Page 2 of 2 Table 2.2.1-C Sampling Locations, Kewaunee Power Station 0 S 0 0 0 S 0 0 0 S 0 0 0 0 0 0 0 S 0 Distance Code Type' (Miles)b and Location Sector K-I OnsitV K-la 1 0.62 N North Creek K-lb I 0.12 N Middle Creek K-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 Creek K-If I 0.12 S Meteorological Tower K-lg I 0.06 W South Well K-lh I 0.12 NW North Well K-Ij. I 0.10 S 500' south of Condenser Discharge K-lk I 0.60 SW Drainage Pond, south of plant K-il I 0.13 N ISFSI Southeast K-Im I 0.15N ISFSI East K-In I 0.16N ISFSI Northwest K-lo I 0.16N ISFSI North K-lp I 0.17N ISFSI Northwest K-lq I 0.16N ISFSI West K-Ir I 0.13N ISFSI West K-Is I 0.12 N ISFSI Southwest K-2 C 8.91 NNE WPS Operations Building in Kewaunee K-3 C 5.9 N Lyle and John Siegmund Farm, N2815 Hy 42, Kewaunee K-5 I 3.2 NNW Ed Paplham Farm, E4160 Old Settlers Rd, Kewaunee K-8 C 4.85 WSW Saint Isadore the Farmer Church, 18424 Tisch Mills Rd, Tisch Mills Green Bay Municipal Pumping Station, six miles east of Green Bay K-9 C 11.5 NNE (sample source is Lake Michigan from Rostok Intake 2 miles north of Kewaunee)K-10 I 1.35 NNE Turner Farm, Kewaunee Site K-I 1 I 0.96 NW Harlan lhlenfeldt Farm, N879 Hy 42, Kewaunee K-13 C 3.0 SSW Rand's General Store, Two Creeks K-14 I 2.6S Two Creeks Park, 2.5 miles south of site K-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, Kewaunee Rev. 20 October 15, 2013 Page 1 of 2 Table 2.2.1-C Sampling Locations, Kewaunee Power Station Distance Code T Ipe_ (Miles)b and Location Sector K-20(c) I 2.5 N Carl Struck Farm, N1596 Lakeshore Dr., Kewaunee K-23a I 0.5 W 0.5 miles west of plant, Kewaunee site K-23b I 0.6N 0.6 miles north of plant, Kewaunee site K-24 1 5.4 N Fictum Farm, N2653 Hy 42, Kewaunee K-25 1 1.9 SW Wotachek Farm, E3968 Cty Tk BB, Two Rivers K-26(d) C 9.1 SSW Sandy's Vegetable Stand (8.0 miles south of"BB")K-27 I 1.53 NW Schleis Farm, E4298 Sandy Bay Rd K-29 1 5.34 W Kunesh Farm, E3873 Cty Tk G, Kewaunee K-30 I 0.8 N Fnd of site boundary K-31 1 6.35 NNW E. Krok Substation, Krok Road K-32 C 7.8 N Piggly Wiggly, 931 Marquette Dr., Kewaunee K-34 I 2.7 N Leon and Vicky Struck Farm, N1549 Lakeshore Drive, Kewaunee K-35(e) C 6.71 WNW Duane Ducat Farm, N1215 Sleepy Hollow, Kewaunee K-36(0 I Fiala's Fish Market, 216 Milwaukee, Kewaunee K-38 I 1.45 WNW Dave Sinkula Farm, N890 Town Hall Road, Kewaunee K-39 1 3.46 N .Francis Wotja Farm, N1859 Lakeshore Road, Kewaunee K-41 (g) C 22 NW KPS-EOF, 3060 Voyager Drive, Green Bay K-42 (h) C 28.1 W Lamers Dairy Products obtain from Green Bay Markets (i)K-43 (j) 1 2.71 SSW Gary Maigatter Property, 17333 Highway 42, Two Rivers 0 0 0 0 0 0 0 0 S 0 S 0 0 S S 0 0 0 0 S 0 S 0 0 C 0 I a. I = indicator; C = control b. Distances are measured from reactor stack.c. Location removed from program in 2007 d. Location K- 18 was changed because Schmidt's Food Stand went out of business.
It was replaced by Bertler's Fruit Stand (K-26). Replaced with Sandy's Vegetable in 2007.e. Removed from the program in Fall of 2001, back to program in August 2008.f Removed from the program in Fall of 2001, back to program in August 2008.g. Location replaces K- 16, January of 2007 h. Location replaces K-28 as of March 2010 i Lamers Dairy is actually located in Appleton.
The herds providing milk to Lamers are located nearer to Appleton than the plant to provide adequate distance for purposes of a control location.j. K-7 moved to a nearby location and relabeled K-43, within 0-2 miles of original, August/September 2010.Rev. 20 October 15, 2013 Page 2 of 2 S 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 0 0 Table 2.2.1-D Reporting Levels for Radioactivity Concentrations in Environmental Samples Medium Radionuclide Reporting Lewis CV to IKPS J KPS to NRCb Airborne Particulate or Gases (pCi/m3) Gross Beta I 131 (Charcoal) 0.1 0.9 Cs-134 1 10 Cs-137 1 20 Precipitation (pCi/1) H-3 1,000 -Water (pCi/I) Gross Alpha 10 Gross Beta 30 -H-3 10,000 20,000c Mn-54 100 1,000 Fe-59 40 400 Co-58 100 1,000 Co-60 30 300 Zr-Nb-95 40 400 Cs-134 10 30 Cs-137 20 50 Ba-La-140 100 200 Sr-89 8 d --Sr-90 8 d --Zn-65 30 300 Milk (pCi/I) 1-131 1.0 3 Cs-134 20 60 Cs-137 20 70 Ba-La-140 100 300 Sr-89 10 --Grass, Cattle Feed, and Vegetables (pCi/g Gross Beta 30 --wet) 1-131 0.1 0.1 Cs-134 0.2 1 Cs-137 0.2 2 Sr-89 I --Sr-90 1 Rev. 20 October 15, 2013 Page 1 of 2 Table 2.2.1-D Reporting Levels for Radioactivity Concentrations in Environmental Samples I Reporting Leveis Medium Radionuclide R towi CV to KPS" 1KPS to NRCb Eggs (pCi/g wet) Gross Beta 30 --Cs-134 0.2 1 Cs-137 0.2 2 Sr-89 I --Sr-90 I --Soil, Bottom Sediments (pCi/g) Gross Beta 50 --Cs-134 5 --Cs-137 5 --Sr-89 5 --Sr-90 5 --Meat (pCi/g wet) Gross Beta (Flesh, 10 --Bones)Cs-134 (Flesh) 1.0 1.0 Cs-137 (Flesh) 2 2.0 Sr-89 (Bones) 2 --Sr-90 (Bones) 2 --Fish (pCVg wet) Gross Beta (Flesh, 10 -Bones)Mn-54 -30.0 Fe-59 -10.0 Co-58 -30.0 Co-60 -10.0 Cs-134 (Flesh) 1 1.0 Cs-137 (Flesh) 2 2.0 Sr-89 (Bones) 2 -Sr-90 (Bones) 2 -Zn-65 (Bones) -20 0 0 0 S 0 0 S 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 a.b.C.d.Kacitonucdes will be monitored by tie L, V and concentrations above Me lted imiltS Will be reported 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, a value of 30,000 pCi/l may be used.The Sr-89/90 values are based on the EPA drinking water standards.
See note "f." of Table 2.3.1-A for firther inforrnation Rev. 20 October 15, 2013 Page 2 of 2 Table 2.3.1-A Detection Capabilities for Environmental Sample Analysis'Lower Limit of Detection (LLD) b,c Water Airborne Fish Food Products Sediment Analysis Particulate or Milk (pCi/1)(pCi/i) Gases (pCi/n 3) (pCi/kg, wet) (pCi/kg, wet) (pCi/kg, dry)Gross Beta 4 0.01 H-3 2000'Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zr-Nb-95 15 1-131 Ie 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 Zn-65 30 260 Sr-89/90 r 5 Rev. 20 October 15, 2013 Page 1 of 3 0000000000000000000000000000000000000000000o 0 S 0 Table Notations for Table 2.3.1-A 0 0 a. This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environment Operating Report.b. Required detection capabilities for 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 with 95% 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 = 4.6 6 Sb E " 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 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 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, 0 7 is the radioactive decay constant for the particular radionuclide, and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting, 0 Typical values of E, V, Y, and At should be used in calculation.
0 0 0 0 Rev. 20 5 Page 2 of 3 October 15, 2013 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S Table 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 the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.d. If no drinking water pathway exists, a value of 3,000 pCi/1 may be used.e. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.E This is NOT a NUREG-0472 required value. It is based on EPA drinking water standards, which tie into the NEI Groundwater Protection Initiative that was implemented at KPS on August 4, 2006.Rev. 20 Page 3 of 3 October 15, 2013 FIGURE1lm Rev. 20 Page I of I October 15, 2013 0 0 FIGURE 2 0 0 0 0 0 0 0 0 LLWC?bW W .mzmms ft"suna IT1 STS anI im SL no?.&LMCANN W MT fumy me"S aK O1WAR LEGFJ~~ rUts Msa* m"N MLpL U airi 2r m noan IN s m m tllo% SU ru o C)Rev. 20 October 15,2013 Page 1 of I 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 Thi pae itenioall let ban 0 Thi pae itenionllylef blnk0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 Appendix E Kewaunee Power Station Documentation for Major Changes to Radioactive Waste Treatment Systems in 2013 System abandonment evaluations per procedure OP-KW-DEC-SYC-00 1, System Evaluation and Categorization Attachment B -SSC Category Determination Document And FSRC Review and Approval Documentation 0 S S S S S S S S S S S S S S S 0 S 0 S S S S S S S S S S 0 S S S This page intentionally left blank 9 5 S S S S S S S S S S 0 S S S S S*S S S S 0 0 0 0 0 S 0 S 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 WoominIln' SSC Category Determination Document OPK -DCSY 0 -Atahmn B Pae1 f1 1.0 Doc Type: Report Revision No.: 0 Sub Type: DEC Document Number (ID): SYS-07-DSERT Title: Blowdown Treatment
& Steam Generator Blowdown 1.1 Brief description or reason for revision:
Not applicable for Rev 0 Date: 10/09/2013
2.0 System
Category (Check Appropriate):
NOTE: A SSC may be divided and have more than one category determination depending upon its functional requirements.
I 0] 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 willbe maintained to provide the ability to treat future waste water* SGBT Ion Exchange Pre-Filter
- SGBT Ion Exchanger Post Filter B The 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, P1-11888 Form No. 732128 (Apr 2013)
, Dominion SSC Category Determination Document S.K -DCSY 0 -AtahetB Pae2o 2 3.0 Mark up the affected drawings using color coding to identify system category type and boundaries.
These drawings are to Include system, electrical one-line and distribution, and select building and Isometric drawings.
Related system drawings NOT Incorporated In the system category require an explanation.
REFER to Step 2.7 for a list of drawings.OPERM-203, Flow Diagram Main Aux Steam And Steam Dump Abandon: Blowdown lines from Steam Generator A, B to the Blowdown Heat Exchangers Blowdown drain lines from the MSIV's to the Steam Generator Blowdown Tank OPERM-204-1, Flow Diagram Condensate
& Gland Seal Systems Abandon: Three inch recovered condensate from the SGBT Ion Exchanger to MU-6 OPERM-219, Flow Diagram Secondary Sampling System Abandon: Blowdown sample lines from Steam Generator A, B to secondary sampling system instrumentation including piping to the Sample Room OPERM-368, Flow Diagram Steam Generator Blowdown Treatment System Abandon: SGBT Hold-up Tank 1A Including SGBT Hold-Up Tank 1A Transfer Pump and piping SGBT Monitor Tank 1A including SGBT Monitor Tank 1A Transfer Pump and piping SGBT Ion Exchanger 1A SGBT Ion Exchanger Post Filter 1A SGBT Heat Exchanger and filter Available:
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 PUMPS MD-4108, 1.5 IN. VALVE-MANUAL-ANAL INST PANEL TO SGBT HOLD UP TK 1B BT-131A, 2 IN. VALVE-MANUAL-SGBT HOLD-UP TANK 1A BLOWDOWN INLET BT-337A, 2 IN. VALVE-MANUAL-HOLD-UP TANK 1A MONITOR TANK RETURN BT-130, 2 IN. VALVE-MANUAL-FLASH TANK FILTER BLOWDOWN TO HOLD-UP TANKS BT-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 INLET BT-210, 2 IN. VALVE-MANUAL-CROSSOVER FOR SGBT MONITOR TANK DISCHARGE PUMPS BT-203A, 1.5 IN. VALVE-MANUAL-SGBT MONITOR TANK 1A DISCHARGE PUMP-DISCH BT-230, 2 IN. VALVE-MANUAL-SGBT TO CVC MONITOR TANKS Form No. 732125 (Apr 2013)6 6 6 I.I.0 0 0 6 0 0 0 0 S S 0 10 0 I.I.0 S 0 0 0 0 0 0 0 0 0 0 0 0 I.0 SDominion SSC Category Determination Document OPM DC-Y-0 -AtahetB Pg 4f1* SGBT Ion Exchange Pre-FilIter
- ) SGBT Ion Exchanger IB 0) Boundary valves: BT-117B, 1.5 IN. VALVE-MANUAL-SGBT ION EXCHANGE IB TO IA BT-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 LINE SGBT Ion Exchange Post Filter IB S 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 to the 3"drain to 24"Auxillary Building Standpipe.
- SGBT Pre Filter IA, 18*SGBT Polishing Filter 1A, 1B SGBT 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 TNK BT-4B, 1 IN. VALVE-MANUAL-STM GEN lB BLOWDOWN AT BLOWDOWN TNK 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*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 System Available:
Heating Boiler Mud Drum Continuous Blowdown to Blowdown Tank 0~Form No. 732125 (Apr 2013)0 SDominlon" SSC Category Determination Document 0* I EC-YC001 -.tah i B ae4-f1 E-256, Circuit Diagram 480V MCC 1-32D, 1-35C, 1-35F, 1-42D, 1-45C, & 1-45F Abandoned from the electrical breaker out: MCC 1-32D (C3) SGBT Hold-Up Tank 1A Transfer Pump MCC 1-32D (C4) SGBT Monitor Tank 1A Discharge Pump Available:
MCC 1-420 (C3) SGBT Hold-Up Tank 1B Transfer Pump MCC 1-42D (C4) SGBT Monitor Tank 1B Discharge Pump E-258, Circuit Diagram 480V MCC 1-52A, 1-52F, & 1-52B Abandoned 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 1-62J Abandoned 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 AC Abandoned from the electrical breaker out: BRA-104 Circuit 21, To Local Mtr Str 1-428 BT-3B/MV32080 S/G B Blowdown Isolation Valve B2 BRB-104 Circuit 21, To Local Mtr Str 1-427 BT-3A/MV32078 S/G A Blowdown Isolation Valve A2 4.0 Evaluation (Basis for choosing category type): Purpose/Function The Steam Generator Blowdown System assists In maintaining secondary chemistry of the Steam Generators and the Main Steam System by removing contaminants.
Also, the SGB System provides the means to monitor SG tube integrity and has the ability to transfer radioactive contaminated water from the SGs to the Steam Generator Blowdown Treatment System following a Steam Generator tube rupture.The SGB System operates in three Modes: Mode I Normal 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 the Auxiliary Building standpipe.
Mode II Normal operation is from 50% to 100% power. The water removed from the SGs is processed through heat exchangers and filters before returning to the condenser.
Mode III Emergency operation, following a Steam Generator tube rupture, is to transfer the radioactive contaminated water to the SGBT System.Form No. 732125 (Apr 2013)4 6 6 6 6 I.6 0 0 0 6 S 0 0 I.0 0 0 0 0 0 S 0 0 0 I 0 0 0 S S S 0 0* 0 0 S 0 0 0 0 S S 0 0 0 S 0 S 0 0 Inlet, SSC Category Determination Document 0PK -E-Y-0 -Atahmn B ae5.f1 The Steam Generator Blowdown Treatment System processes radioactive contaminated water. During normal plant operation, radioactive water from the Waste Disposal System is periodically transferred to the SGBT System for processing.
In an emergency, Steam Generator tube rupture, SGB System is aligned to Mode I1i. SGBT System pumps the radioactive water through filters and ion exchangers to remove contaminants.
When the water is processed sufficiently, it Is discharged to Lake Michigan via the Auxiliary Building Standpipe.
Basis for Category On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).
Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel in the reactor vessel, as specified in 10 CFR S0.82(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 the Irradiated fuel. Therefore, the postulated accidents involving failure or malfunction of the reactor, RCS or secondary system are no longer applicable.
The analyzed accident and operational 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 provide support 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 being maintained available to support draining.4. To support Technical Specifications, License Requirements, Design Basis, permits, regulatory requirements, insurance requirements, or other commitments.
Provide support of the Spent Fuel Safety Management Program.Form No. 732125 (Apr 2013)
SDominion' SSC Category Determination Document S.I OPM DC SYC0 -tah etB Pg. f1 5. 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 are being 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 Impact Updated Safety Analysis Report (USAR)The Steam Generator Blowdown Treatment system is mentioned in the following chapters/sections:
Section 5.3.1.1 Containment Isolation Valves There are two SGB System Containment vessel penetrations denoted as "tube barrier and pressurized 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 Loops R-19 monitors the liquid phase of the secondary side of the steam generator for radiation, which would Indicate a primary-to-secondary system leak, providing backup Information to that of the condenser air ejector gas radiation monitor. Samples from the bottom of each of the two steam generators are mixed to a common header and the common sample is continuously monitored by a scintillation counter and holdup tank assembly.
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 manually selecting the desired steam generator to be monitored and allotting sufficient time for sample equilibrium to be established (approximately I minute). At the alarm setpoint for high 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 blowdown lines and sample lines.Chapter 9.4 Sampling System Steam generator blowdown samples can be taken either in the sample room or at the secondary system analytical and sampling panel. Leakage and drainage resulting from the sampling operations are collected and drained to tanks in the Waste Disposal System.Form No. 732125 (Apr 2013)I I I I I 0 0 6 6 0 6 0 0 0 I.0 0 0 S 0 0 0 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0** Domil 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 nion SSC Category Determination Document**K -DCSY 0 -Atahmn B Pae7. f1 Section 10A.6.5 Steam Generator Blowdown Table 10A.4-5 Needed Equipment List For Blowdown Line Break Chapter 11: Waste Disposal and Radiation Protection System Waste from the sludge interceptor tank is pumped by the sludge Interceptor pump through sludge Interceptor filters (4) Into the waste holdup tank. Waste from the hot sample station and hot chemical laboratory is also drained to the waste holdup tank. The tank's contents are pumped by the waste evaporator feed pump to the Blowdown Treatment System for processing and eventual release to the environment.
Section 11.1.2.2 Steam Generator Blowdown System Section 11.1.2.18 SGB Heat Exchangers Four SGB heliflow heat exchangers are used to cool normal flow blowdown from each steam generator to 100F. Blowdown then Is directed through a high pressure drop flow control valve and then a pressure regulating valve that reduces the pressure to 40 psig prior 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 to allow processing through the SGBT ion exchanger.
Section 11.1.2.20 SGBT Flash Tank Filters The SGBT filters remove particulate matter from the fluid being pumped, prior to its passing to the SGBT holdup tanks or ion exchangers.
The filter is constructed of stainless steel materials.
Section 11.1.2.21 SGBT Monitor Tanks The SGBT monitor tanks serve as a collection point for liqulds processed through the SGBT ion exchanger.
The contents are sampled at this point for an activity record before discharge through the Waste Disposal System radiation monitor to the circulating water discharge.
The tanks are all-welded stainless steel construction.
Section 11.1.2.22 SGBT Holdup Tank The SGBT holdup tanks serve as a collection point for cooled and filtered blowdown liquid from the SGB tank before processing through the SGBT Ion exchanger or for storage of liquid wastes transferred from the waste holdup tank prior to being processed through the SGBT 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. The filter housing is constructed of stainless steel.Form No. 732125 (Apt 2013)
SDominion' SSC Category Determination Document I~ O KWDCS Y 0 -Atahen.6ag f1 2 Section 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 Filters The 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 Pumps The wetted surfaces of all pumps are stainless steel or other materials of equivalent corrosion resistance.
Section 11.1.2.27 Piping Piping carrying liquid wastes is stainless steel, while all gas piping is carbon steel. Steam generator blowdown piping is carbon steel to the point where this system joins the liquid wastes transferred from the waste holdup tank. Piping connections are welded, except where flanged connections are necessary to facilitate equipment maintenance.
Section 11.1.2.28 Valves All 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 seats when such an arrangement reduces the possibility of leakage.Isolation valves are provided to Isolate each piece of equipment for maintenance, to direct the flow of waste through the system, and to Isolate storage tanks for radioactive decay.Relief valves are provided for tanks containing radioactive wastes to prevent overpressurization 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 power operations 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 the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(1i).
Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel In the reactor vessel, as specified In 10 CFR 50.82(a)(2).
The USAR will be revised to address to keep functions associated with the available equipment above.Form No. 732125 (Apr 2013)
- SDominion SSC*Technical Specifications Reviewed all sections for applicability to Stc following sections were applicable:
- Section 3.4.17 Steam Generator (SG) Tube I*Applicability:
Modes, 1, 2, 3, and 4.0 Section 3.6.3 Containment Isolation Valves Applicability:
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, 20 certification for permanent removal of fuel 50.82(a)(1)(11).
Therefore the 10 CFR Part 5S 0the 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 longer Offsite Dose Calculation Manual (ODCM):* Licensee Initiated major changes to the radi*solid) shall be reported to the Commission I the period in which the evaluation was revi shall contain:*a. A summary of the evaluation that led to t*made in accordance with 10 CFR Part 50.59 b. 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 show materials in liquid and gaseous effluents an*from those previously predicted in the licen e. An evaluation of the change, which show Individuals In the UNRESTRICTED AREA and*from those previously estimated in the licer*thereto, f. A comparison of the predicted releases of gaseous effluents and in solid waste to the the changes are to be made;0 0 0 Category Determination Document OP. W-ECS Y-0 -I Atahmn B ae9f1 ham Generator Blowdown Treatment.
The ntegrity tification of permanent cessation of power), stating that DEK has decided to permanently
'13. On May 15, 2013 the NRC docketed the from the reactor vessel pursuant to 10 CFR 0 license no longer authorizes KPS to operate reactor vessel, as specified in 10 CFR clated Surveillance Requirements (SRs)) that applicable.
loactive waste systems (liquid, gaseous and n the Radioactive Effluent Release Report for ewed by FSRC. The discussion of each change:he determination that the change could be he reason for the change without benefit of ents and processes involved and the's the predicted releases of radioactive d/or quantity of solid waste that differ se application and amendments thereto, s the expected maximum exposures to to the general population that differ nse application and amendments radioactive materials In liquid and actual releases for the period in which Form No. 732125 (Apr 2013)
SDominion SSC Category Determination Document S*I OPK -E-Y *0 -. Atah etB Pae1 f1 g. An estimate of the exposure to plant operating personnel as a result of the change, and h. Documentation of the fact that the change was reviewed and found acceptable by the FSRC.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 and will require revision.Plant Impact No 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 required disposition 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):
None 6.0 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 to remain available until plant demolition.
Form No. 732125 (Apt 2013)I I I I I I I I I 6 0 6 0 6 0 0 0 0 I.I.S 0 0 0 0 0 I 0 S S S S S S S S S S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0' Dominion SSC Category E 8.0 PREPARE and ATTACH the following documents:
- Completed 10 CFR 50.59 Screening or Evaluation, if required* Proposed DUs for appropriate drawings 9.0 Technical Concurrence:)etermination Document 71C ~ ~ II -Sahnn ie1 l1 Type Of Review Name (Print) Date Engineering UAve Itk(/AVE IZ -12Z "3 Type Of Review Name ( rint) Approval Signature Date Fire Protection Type Of Review Name (Print) Appr vsignature I Date Security __ _ __ _ __ _ __ _Type Of Review Name (Print) Approval~iynature Date Type Of Review Name (Print) p oval Sign ure Date Radiation Protection Dole? 4. s/Type Of Review Name (Print) Appro Signature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date Form No. 732125 (Apr 2013)
' ominio" SSC Category Determination Document*PK -E -Y tah etBSae1 f1 10.0 Review and Approval: Prepared By (Print/Sign)
Reviewed By (Screen Qual.) (Print/Sign)
Date 12 1"2-Date Dafe---Date a.2 -/ q-/e?Date Nulear Licensi (Print/Sign)
Concurrence by DSERT Coordinator (Print/SI n)FSRC (Print/Sign), if required FSRC Meeting Number: 0 0 0 0 0 10 0.0 0 0 0 0 0 0 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Form No. 732125 (Apr 2013) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 sldkmhnýo SSC Category Determination Document OPK -DCSY 0 -Atahmn B PaeI0f2 1.0 Doc Type: Report Sub Type: DEC Document Number (ID): SYS-18-DSERT Title: Reactor Building Ventilation Revision No.: 0 Date: 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 its functional 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, heating coils, associated ductwork, dampers and instrumentation except as indicated below. The following system functions shall be maintained available.
The ability to vent pressure from containment through the 2" vent to Aux Building exhaust.The service water system supports the Reactor Building Ventilation System CFCUs and Charcoal Filter Units fire suppression spray manifolds.
The service water system shall be isolated and drained to the RBV System including 1A CFCU though this unit could be refilled and operated as desired.Service Water supports the RBV system and shall be isolated from the containment Fan Coil Units as Indicated in Section 3.Service water piping to fire spray manifolds In Containment Purge Exhaust Filter housing downstream 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 Vent Supply fan housing as Indicated in Section 3.Form No. 732125 (Apr 2013)
WDominion SSC Category Determination Document 6* K -D C SY Att ch en 0 P g ý2 The 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 isolated from 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 P1-11012 The following dampers act as boundary dampers: TAV-11 Turbine Building Air Damper to RBV System CD-34187 Containment Fan Coil Unit B to Reactor Coolant Pump Vault Damper 3.0 Mark up the affected drawings using color coding to identify system category type and boundaries.
These drawings are to include system, electrical one-line and distribution, and select building and isometric drawings.
Related system drawings NOT Incorporated in the system category require an explanation.
REFER to Step 2.7 for a list of drawings.OPERM-601 Abandon: Containment Purge and Vent Air Supply fan Containment Supply Fan Preheat Coil Containment Supply Fan Reheat Coil Containment Purge and Vent Air Supply Ductwork up to TAV-11 OPERM-602 Reactor and Shield Building Ventilation Abandon: Containment Purge exhaust System including all ductwork and dampers Containment Vent Exhaust fan Containment Purge exhaust fan Containment Purge Exhaust Filter Assembly Containment Exhaust Filter Assembly Form No. 732125 (Apr 2013)0 0 0 0 0 0 0 I.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0° p 0 0 S 0 0 0 0 S 0 0 0*0 0 0 0 0 0 0 0 Domiflnon' SSC Category Determination Document 0* I DEC SYC0 -AtahetB pg Bf2 Containment Purge and Vent Air Supply from OPERM-601 through RBV-2 including all ductwork and dampers upstream and downstream Containment Isolation Valves RBV-1, RBV-2, RBV-3, and RBV-4 Containment Vacuum Breakers VB-1OA, VB-10B, VB-11A, and VB-11B Reactor Gab & Neutron Detector Cooling Fan A Reactor Gab & Neutron Detector Cooling Fan B Reactor Gab & Neutron Detector Cooling ductwork and dampers Containment Fan Coil Unit B Containment Fan Coil Unit C Containment Fan Coil Unit D Containment Fan Coil Unit ductwork and dampers up to damper CD-34187.Control Rod Drive Cooling Fan A Control Rod Drive Cooling fan B Control Rod Drive Cooling ductwork and dampers Reactor Support Cooling Fan A Reactor Support Cooling Fan B Reactor Support Cooling Electric Heater A Reactor Support Cooling Electric Heater B Reactor Support Cooling ductwork and dampers Containment Dome Fan 1B Containment dome fan ductwork and heaters Available:
Containment Fan Coil Unit A shall remain available along with its associated ductwork to the reactor coolant pump vault 1B, reactor building 606' and 592' elevations, CD-34187 and RBV-150A.
CD-34187 shall be available to open as a check damper but the open assist shall be abandon.Containment Dome Vent Fan A will be maintained available.
OPERM-605-1 Flow Diagram Heating Steam Abandon: Containment Purge and Vent Unit Preheat and Reheat coils HS-320 Manual Isolation to Containment Purge and Vent Unit Preheat and Reheat coils to HS-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 piping Form No. 732125 (Apr 2013) ominion' SSC Category Determination Document OPK -DCSY 0 -Atahmn B Pae4.f2 Abandon: Service water piping to fire spray manifolds in Containment Purge Exhaust Filter housing downstream of SW-1051. After the charcoal Is removed from the filters OPERM-403 Flow Diagram Reactor Building Vent. System Post LOCA Hydrogen Control Abandon: 2" Containment Supply Blower Reactor Building Vent System Post LOCA Hydrogen Control piping and valves Available:
Vent flow path through LOCA-2B, LOCA-100B to Aux Building Exhaust up to LOCA-3B and LOCA-10B.OPERM-213-2 Flow Diagram Station and Instrument Air System Abandon: IA-31120 to CV31120, SW-0904B, including positioner air to S/CV-35007 and Pos 37075 on drawing OPERM-213-5 OPERM-213-5 Flow Diagram Station and Instrument Air System Abandon: IA-31386-1 Manual valve to LOCA-3A IA-31386-2 Manual valve to LOCA-3A/AS-19579 IA-31387 Manual Isolation to LOCA-10A IA-31388-1 Manual Isolation to LOCA-3B IA-31388-2 Manual Isolation to LOCA-3B/AS-19583 IA-31389 Manual Isolation to LOCA-1OB IA-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 System Abandon: 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 IA piping, valves, regulators and associated accumulators.
IA-131 downstream to SW-901C-1, SW-901D-1, SW-910C, SW-910D, SW-911CD, SW-914C, SW-914D IA-155 Manual Isolation to LOCA-201A IA-153 Manual Isolation to RBV-2 IA-152 Manual Isolation to RBV-3 IA-167 Manual Isolation to LOCA-201B Form No. 732125 (Apr 2013)0 0 0 0 0 6 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 YDominion SSC Category Determination Document 0 0 0 0 0 0 0 S 0 S 0 0 0 S 0 S 0 S.I OPK -E*Y-0 tahetB Pg f2 OPERM-213-6 Flow Diagram Station and Instrument Air System Abandon: IA-31340 Manual Isolation of VB-11B IA-31339 Manual Isolation of VB-11A IA-31724 Manual isolation to LOCA-IOOA IA-31125 Manual Isolation of RBV-1 IA-31123 Manual Isolation of RBV-4 IA-1505 Manual Isolation to RBV-5, RBV-6, RBV-7, RBV-10, RBV-20, RBV-21, TAV-12 IA-1522 Manual Isolation to VB1OA, VB10B and associated accumulators and valves IA-1550 Manual Instrument air header Isolation to manual dilution to containment IA-1630 Manual Instrument Air Isolation to Post LOCA H2 Control OPERM-213-7 Flow Diagram Station and Instrument Air System Abandon: IA-34030 Manual Isolation to TAV1O IA-34034 Manual Isolation toTAV-11 IA-1339 Manual Isolation to Purge Supply Unit Temperature Control OPERM-547 Flow Diagram Service water System Containment Cooling Available:
Service Water piping for CFCU A through Shroud Cooling Bypass valve SW-901A-1 Abandon: 1B, IC, ID Containment Fan Coil Unit coils 1A, 1B,1C,1D Shroud Cooling coils CFCU 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-903C and 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 & 1-45E Abandon: Breaker MCC45E-D4 to 1-105 Containment Purge and Vent Supply Fan Motor Breaker MCC35E-C5 to 1-313 Containment Purge Exhaust fan Breaker MCC35E-A3 to 1-587 Containment vent Exhaust fan E-889 Lighting panels RPB1, RPB2, RPB3, RPB4, RPBS, RPB6 Abandon: Breaker RPB6-18 to 1-1079 Containment 2" Blower Motor E-235 Circuit Diagram 480V Switchgear Safeguard Buses Abandon: Breaker 15104 to 1-156 Containment FCU B Motor Form No. 732125 (Apr 2013)
SDominion SSC Category Determination Document I* O KWDC SYC *0 -AtahetB Pg Sf2 Breaker 16105 to 1-121 Containment FCU C Motor Breaker 16104 to 1-157 Containment FCU D Motor Available:
Breaker 15105 to 1-120 Containment FCU A Motor E-251 Circuit Diagram 480V MCC 1-32E Abandon: Breaker MCC32E-D5 to 1-327 Reactor Vessel Support Cooling Fan A Breaker MCC32E-D4 to 1-329 Reactor Vessel Gap and Neutron Detector Cooling Fah A Breaker MCC32E-CS to 1-337 Control Rod Drive Cooling Fan A Breaker MCC32E-B5 to 1-588 Reactor Vessel Support Heater A E-252 Circuit Diagram 480V MCC 1-42E Abandon: Breaker MCC42E-A2 to 1-328 Reactor Vessel Support Cooling Fan B Breaker MCC42E-B1 to 1-330 Reactor Vessel Gap and Neutron Detector Cooling Fan B Breaker MCC42E-E5 to 1-338 Control Rod Drive Cooling Fan B Breaker MCC42E-A5 to 1-589 Reactor Vessel Support Heater B E-258 Circuit Diagram 480V 1-52A, 1-52F, 1-52B Abandon: Breaker MCC52B-G5 to 1-672, SA-7003A Hydrogen Dilution to Containment Breaker MCC52B-C2 to 1-670, LOCA 2A Post LOCA Containment Vent Maintain: Breaker MCC52B-A3 to 1-583 Containment dome Fan A E-261 Circuit Diagram 480V 1-62A, 1-52D, 1-5262, 1-62B Abandon: 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 Is to be abandoned with the valve in the open position to maintain a containment vent flow path.Breaker MCC62B-A2 to 1-584 Containment Dome Fan B E-259 Circuit Diagram 480V MCC1-62D, 1-62E Abandon Breaker MCC62E-B1 to 1-396, SW-903C MOV Breaker MCC62E-B2 to 1-397, SW-903D MOV E-260 Circuit Diagram 480V MCC 1-52C, 1-52E, 1-62C Abandon: Breaker MCC52E-G1 to 1-395, SW-903B MOV Breaker MCC52E-F5 to 1-394, SW-903A MOV Note: The power Is to be abandoned with Form No. 732125 (Apr 2013)0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
- Do0 0 0* 4.0 m 0 0 0 0 0 0 0 0 4.0vau 0 0 0 0 0 0 0 0 0 0 0 0 0 minlo SSC Categoty Determination Document OP.K -DEC SY-0 -Atahet8 Pg Sf2 the 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 that temperature, pressure, and air quality are maintained within acceptable limits to support operability of equipment and safety and comfort of personnel during refueling and maintenance activities.
The RBV CFCU Subsystem shall provide Post-LOCA cooling to the Containment to control 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 of a 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 pressure boundary function for the Incore Support Column and Reactor Cavity.RBV CFCUs A and B support safe shutdown following an Appendix R Fire Event in the Dedicated 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 of preventing hydrogen concentration in containment from exceeding 3.5 percent.The RBV CFCU Subsystem shall provide cooling to the Containment general space and the RC Pump Vaults so that the Containment environment is maintained within the limits of acceptability to support operability of equipment required to control reactor operation.
The CRD Shroud Cooling Subsystem shall provide sufficient cooling to the CRDM during normal 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 Document rS.KWDCSY 0 -Atahmn 8 Pae8 f2 cooling to limit the maximum temperature of the concrete surrounding the reactor vessel and keep the neutron detectors cool during normal operations.
The Reactor Support Cooling Subsystem shall provide sufficient cooling to maintain the proper temperature profile in the reactor vessel steel at the supports, shims, shoes and supporting steel.The Purge and Vent Subsystem shall provide comfort cooling and protection from airborne radiation for personnel entering the Containment, as well as a controlled containment exhaust air flow path.The SG Channel Head Ventilation 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 Category On February 25, 2013, DEK submitted a certification of permanent cessation of power operations 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 CFR 50.82(a)(1)(ii), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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) is determined 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 Tank rupture.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 support of 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 Impact Form No. 732125 (Apr 2013)0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 om 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 nion" TECHNICAL SPECIFICATIONS
3.6 CONTAINMENT
SYSTEMS SSC Category Determination Document OPK -E-Y*0 -. Atahmn B .ae9f2 3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be 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 is sufficient to remove the assumed heat load.SR 3.6.6.7 Verify each containment cooling train starts automatically on an actual or simulated actuation signal.B 3.6 CONTAINMENT SYSTEMS B 3.6.6 Containment Spray and Cooling Systems The Containment Spray and Containment Cooling systems provide containment atmosphere cooling to limit post accident pressure and temperature in containment to less than the design values. Reduction of containment pressure and the Iodine removal capability of the spray reduces the release of fission product radioactivity from containment to the environment, in the event of a Design Basis Accident (DBA), to within limits. The Containment Spray and Containment Cooling systems are designed to meet the requirements of USAR, General Design Criteria (GDC) 52, "Containment Heat Removal Systems," GDC 58, "Inspection of Containment Pressure-Reducing Systems," GDC 59,"Testing of Containment Pressure-Reducing Systems Components," GDC 60, "Testing of internal Containment Spray System," and GDC 61, "Testing of Operational Sequence of Containment Pressure-Reducing Systems" (Ref. 1)Containment Cooling System Two trains of containment cooling, each of sufficient capacity to supply 100% of the design cooling requirement, are provided.
Each train of two fan-coil units Is supplied with cooling water from a separate train of service water. Each pair is connected to ductwork which distributes the cool air to the reactor coolant pump vaults, the ring duct above the refueling 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 are the 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 in containment pressure and temperature could occur requiring the operation of the containment spray trains and containment cooling trains.In MODES 5 and 6, the probability and consequences of a release are reduced due to the pressure and temperature limitations of these MODES. Thus, the Containment Spray System and the Containment Cooling System are not required to be OPERABLE in MODES 5 and 6.Form No. 732125 (Apr 2013)
' Dominion SSC Category Determination Document I PK-E C-Y 0 Ata chen B Pag 10o.2 3.6.9 Vacuum Relief Valves LCO 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 opens at a simulated containment vacuum of <0.5 psig vacuum. 18 months SR 3.6.9.2 Perform a CHANNEL CALIBRATION on the containment vacuum breaker differential pressure channels.
18 months B 3.6.9 Vacuum Relief Valves The purpose of the vacuum relief lines is to protect the containment vessel against negative pressure (i.e., a lower pressure inside than outside).
Excessive negative pressure inside containment can occur If there is an inadvertent actuation of containment cooling features, such as the Containment Spray System. Multiple equipment failures or human errors are necessary to cause Inadvertent actuation of these systems. The containment pressure vessel contains two 100% vacuum relief lines that protect the containment from excessive external loading.The containment was designed for an external pressure load equivalent to 0.8 psig. The Inadvertent actuation of the containment cooling features was analyzed to determine the resulting reduction In containment pressure.
The initial pressure condition used in this analysis was 14.7 psia (0.0 psig). This resulted in a minimum pressure Inside containment of 13.917 psia (-0.783 psig), which is less than the design load.The vacuum relief valves must also perform the containment isolation function in a containment high pressure event. For this reason, the system is designed to take the full containment positive design pressure and the environmental conditions In MODES 1, 2, 3, and 4, the containment cooling features, such as the Containment Spray System, 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 OPERABLE in 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 be OPERABLE in MODES 5 and 6. Therefore, maintaining OPERABLE vacuum relief valves is not required 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 each Function 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 Air Cooling and Containment Purge and Vent Systems. This action isolates the containment atmosphere from the environment to minimize releases of radioactivity in the event of an Form No. 732125 (Apr 2013)0 I.0 0 0 S S 0 0 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 0 S* 0 0 0 0 0\0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Inlon SSC Category Determination Document ePK -E -Y Atahmn B Pae1.f2 accident.
The Containment Air Cooling System may be in use during reactor operation and the Containment Purge and Vent System will be in use with the reactor shutdown 3.6.3 Containment Isolation Valves LCO 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 days SR 3.6.3.2 Verify each 2 inch containment vent isolation valve is closed, except when the 2 inch containment vent isolation valves are open for pressure control, ALARA or air quality considerations for personnel entry, or for Surveillances that require the valves to be open. 31 days 3.6.4 Containment Pressure LCO 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B 3.6.4 Containment Pressure The containment pressure is limited during normal operation to preserve the initial conditions assumed in the accident analyses for a loss of coolant accident (LOCA) or main steam 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 preserve the 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 the outside atmosphere is either closed with a manual or automatic Isolation valve, blind flange, or equivalent; or is capable of being closed by an OPERABLE Containment Purge and Vent Isolation System.On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 in Modes I thru 6 are no longer applicable.
Form No. 732125 (Apr 2013)
SDominion" SSC Category Determination Document SI OPK -EC-Y 0 -tah etB*ae1 f2 TECHNICAL REQUIREMENTS MANUAL (TRM)8.6 CONTAINMENT SYSTEMS 8.6.1 Containment Hydrogen Monitoring System TNC 8.6.1 Containment Hydrogen Monitoring System, consisting of two trains and associated containment dome fans, shall be FUNCTIONAL.
Note: A change in operational MODES or conditions is acceptable with one or both trains of the Containment Hydrogen Monitoring System and Its associated Containment Dome Vent Fan Non-Functional.
APPLICABILITY:
MODE 1 and 2.Bases: Even though the requirements for Hydrogen Monitors were taken out of TS, the system still 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 the hydrogen monitors were not restored to FUNCTIONAL status within the allotted time.On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(i1), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 only apply in Modes 1 thru 6, are no longer applicable.
Offslte Dose Calculation Manual (ODCM)15.1 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 Part 50.59, b. Sufficient Information to totally support the reason for the change without benefit of additional or supplemental Information, c. A description of the equipment, components and processes involved and the'interfaces with other plant systems, Form No. 732125 (Apr 2013)I.I.0 S S S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S S 0 S inion SSC Category Determination Document aPK -E-Y A ttcm n B Pae1 f2 d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto, e. An evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated In the license application and amendments thereto, f. A comparison of the predicted releases of radioactive materials In liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change, and h. Documentation of the fact that the change was reviewed and found acceptable by the 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 be completely abandoned with the 36" RBV isolation valves failed closed. On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).
Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel in the reactor vessel, as specified in 10 CFR 50.82(a)(2).
With the 36" 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 no increase in maximum exposures in the UNRESTRICTED AREA, to the general population and to plant operating personnel.
Detailed information concerning the predicted releases and exposure estimates will be included In the annual Radioactive Effluent Release Report.USAR 5.4 CONTAINMENT VESSEL AIR HANDLING SYSTEM The Containment Air Cooling System is sized such that any three of the four fan-coil units will provide adequate heat removal capacity from the Reactor Containment Vessel during operation, to maintain Interior air temperatures below the maximum temperature allowable for any component and to obtain temperatures below 104°F In accessible areas during hot standby operation.
The fan-coil units and their associated emergency discharge Form No. 732125 (Apr 2013)
SDominlon° SSC Category Determination Document OPK -DCSY 0 -Atahmn B ae1-f2 dampers will also be utilized for emergency cooling under post-accident conditions.
Their use for that purpose is described in Section 6.3.The fan-coil units of the Containment Air Cooling System are utilized to distribute air adequately over equipment and around occupied spaces for ventilation service. Operation of motors and other electrical equipment in the containment will provide heating within the Reactor Containment Vessel when required during shutdown.
The Containment Vent Supply unit will also furnish heated makeup air under shutdown conditions.
The Purge and Ventilation System is designed to provide a reduction in the radioactivity in the 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 per hour during refueling and maintenance operations.
When high airborne radioactivity levels within containment preclude a normal shutdown entry to the Reactor Containment Vessel, the initial purge will be directed to the purge filter (particulate-absolute-carbon).
A deluge system is installed in the carbon filter assembly.
The water spray is provided from the Service Water System.When the Reactor Containment Vessel air activity has decreased sufficiently for release to the 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 air activity to Increase above the setpoint of the Containment System Vent Monitor, the vent and purge line valves would both be automatically closed.The Reactor Gap and Neutron Detector Cooling Subsystem limits the maximum temperature of the concrete surrounding the reactor vessel and keeps the neutron detectors 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 the operating level of containment.
The containment fan coil units then cool the dome air and return it to the containment.
This process mixes the dome air and assists in the control of the Reactor Containment Vessel temperature during normal operation and the control of post-LOCA hydrogen concentration following a design basis accident.The Reactor Support Cooling Subsystem maintains the proper temperature profile in the reactor vessel supports, shoes, shims, and supporting steel. Two 100% capacity fans draw air from the refueling floor and force the air through ductwork to each of three pairs of reactor support plenums.The Control Rod Drive Mechanisms (CRDM) Cooling Subsystem provides CRDM cooling by drawing air from the refueling pool area up through the CRDM enclosing shroud and up through three ducts connected to the CRDM shroud plenum mounted on top of the missile shield above the CRDMs.The Post-LOCA Hydrogen Control Subsystem controls the hydrogen concentration in the post-accident containment atmosphere.
Venting and replacement of the containment atmosphere, dilution by pressurization, or a combination of both methods can be used. If required, hydrogen recombiners are brought on site 5.4.2.1 Isolation Valves The ventilation isolation valves are included as part of the containment isolation systems Form No. 732125 (Apr 2013)0 0 0 0 S S 0 0 0 S 0 S 0 0 0 0 S S 0 S S S S S S S S 0 S S S S S 0 S S S S S O Dominlon" SSC Category Determination Document OPK -D.SY 0 -Atahmn B Pag 15of2 0 listed in Table 5.2-3. The valves Immediately outside the Reactor Containment Vessel are conventional butterfly valves, specified to be adequately leak-tight with maximum internal 0pressure on the Reactor Containment Vessel side of the valve disc. The valves inside the Reactor Containment Vessel are also conventional butterfly valves, which are specified to be adequately leak-tight with maximum internal pressure on either side of the valve disc*5.4.3 Vacuum Relief System Vacuum relief devices or systems are provided to protect the Reactor Containment Vessel against excess differential pressures.
Such differential pressure conditions (vacuum) may exist inside the containment vessel if the containment air cooling systems are operated with a heat removal capability in excess of the heat Inputs at any time during normal or post-accident operations.
5.8.2.6.3 Provisions for Sampling Monitoring of the containment hydrogen concentration is accomplished by two Comsip*Model K-111 hydrogen analyzers.
As stated in Reference 7, the analyzers fulfill the requirements of Item II.F.1.6 of NUREG-0737.
The hydrogen monitors have indication in the control room and a range of 0 percent to 10 percent by volume under positive or negative containment pressure.
The monitors are normally kept in standby mode, but indication Is available on demand. The system Is operated from Its remote control panel located outside the high radiation sampling room. A hydrogen sample is drawn from the 0post-LOCA hydrogen control system sample ports in containment.
These ports are located 0near the discharge of the containment dome fans, which permits rapid detection of hydrogen escaping from the reactor. The fans draw suction from the upper areas of containment, which prevents the formation of a stratified atmosphere.
The fans are powered 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 blowdown and cooling of the core by safety Injection.
Assuming the loss of off-site power and the single active failure of one Emergency Diesel Generator, one containment spray pump in tandum with two containment fan coil-units on the same train, Is sufficient for 5containment 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 under normal 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)S 0 S V aomnloWSSC Category Determination Document OPK -DCSY 0 -Atahmn B Pae10f2 The 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 with corrosion-resistant materials.
To ensure the Integrity of the ductwork in a post LOCA environment, the Containment Fan Coil Unit emergency discharge dampers and back draft dampers are tested once every operating cycle, or every 18 months.6.5.1.2.13 Service Water System The containment fan-coil service water discharge radiation monitor checks the containment 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 is monitored 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 Is leaking.14 Safety Analysis 14.3.5.2.2 Input Parameters and Assumptions A series of analyses, using different break sizes and locations, was performed for the LOCA containment response.
Section 14.3.5.1 documents the mass and energy releases for the DEPS and DEHL breaks. The DEPS break cases were run with both minimum and maximum safeguards.
The three minimum safeguards cases assume a diesel train failure. This assumption 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 I Reactor 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 are Class 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 piping segment in the reactor cavity) Ii-Reactor Support Cooling System II On February 25, 2013, DEK submitted a certification of permanent cessation of power operations 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 CFR Form No. 732125 (Apr 2013)0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 S 0 S 0 0 0 0 0 0 0 0 nlon SSC Categoty Determination Document 0* W-ECS YC01 -AtahetB Pae1 f2 50.82(a)(1)(ii), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 address requirements following cessation of power operation.
LICENSING COMMITMENTS Commitment Number: 80-001 Title: Containment Purge and Vent Valve Modifications Improvement Initiative While above hot shutdown Kewaunee will seal the 36 diameter purge and vent valves closed 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 will continue until such time that valve operability is shown.Commitment Number: 83-005 Title: CONT. PURGE AND VENT SYSTEM OPERABILITY Installation of a 2" containment vent system Commitment Number: 83-012 Title: CONT. PURGE AND VENT SYSTEM OPERABILITY Need a procedure for Containment venting.Commitment Number: 90-143 Title: 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: 84-009 Title: RESOLUTION OF SER FOR EQ Replacement of containment vacuum breakers with qualified solenoid valves.On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 be maintained.
These commitments will be dispositioned per LI-AA-110, Commitment Management.
Form No. 732125 (Apr 2013) 0Dominlow SSC Category Determination Document I~ OPM DC-Y-0 -e tahene ae 8o EMERGENCY PLAN Reviewed the Emergency Plan and the Emergency Action Level (EAL) Technical Basis Document for classification criteria that apply in Mode DEF-Defueled.
The Emergency Plan defines Defueled as 'All reactor fuel removed from Reactor Vessel (full core off load during refueling or extended outage)' Abandonment of the RBV System will not Impact the Emergency Plan as this equipment Is not listed In the EAL tables that apply to a defueled plant. None of the radiation monitoring equipment is being abandon as part of the RBV system categorization.
11.0 DESCRIPTION
OF FIRE PROTECTION SYSTEMS AND FEATURES Fire protection systems and components are designed using the guidelines of the National Fire Protection Association (NFPA) standards (see Appendix B). The water spray systems for the charcoal filters, boiler fuel oil pumps and the hydrogen seal oil unit are unique and do not meet the NFPA standards.
11.4.1 Water Spray Systems The water spray systems for the Auxiliary Building charcoal filters (shield building, the containment purge, containment cleanup and the Control Room air conditioning ventilation units) are nonstandard; however, they are adequate for their intended purpose. The water supply is the service water system. These systems have detectors that operate solenoid valves that feed water to the spray nozzles.The Fire Plan requires that if the filter fire detector is out of service a hourly fire watch is to be established.
Use of combustible material, e.g., HEPA and charcoal filters, dry ion exchange resins 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 be removed from the charcoal filter unit prior to disabling the fire protection spray system to the filters.Plant Impact The abandonment of the RBV system shall eliminate all Installed heating from containment.
One containment fan coil unit shall remain availble for cooling and dehumidifcation if needed.Portable heaters are to be placed in containment plugged into weld receptables to maintain 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)6 0 0 0 6 S 0 S S 0 0 S 0 0 0 0 0 0 S S S S 0 S S S S S S S S 0 S S S S S S S S 0 0 0 0 0 0 S 0 S 0 S 0 S S 0 0 0 S 0 WftminlowI SSC Categoty Determination Document OP, W-ECS Y 01 -AtahetB Pie1 f2 TE-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 for monitoring and controlling containment temperature, including the control of setpoints for the 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 the potential 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 monitor containment humidity.41517 Containment humidity indicator New or exisitng procedures will need to be created or revised to control humididy In containmet and operation of the dehumidifier.
Althoug it is expected to be rarely if ever used 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 required disposition as a result of system abandonment.
This DSERT package does not Impact Spent Fuel Pool Cooling therefore does not require FSRC approval.5.0 Special conditions to support categorization(s):
None 6.0 Assumptions/Open Items to be validated or dispositloned:
None 7.0 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 open Indefinitely to avoid pressure Increases and decreases as containment heats up and cools down based on ambient conditions.
Form No. 732125 (Apr 2013)
VoomnlInoe SSC Gate gory Determination Document 0 -At n B P The A Dome Fan shall be evaluated to determine if it is needed to limit stratification in containment.
If deemed it is not required this Categorization plan will be revised to abandon the A Dome Fan.8.0 PREPARE and ATTACH the following documents:
S S Completed 10 CFR 50.59 Screening or Evaluation, If required Proposed DUs for appropriate drawings 9.0 Technical Concurrence:
Type Of Review Name (Print) Approval Signature Date Engineering aA41o L -& ( J-/-//?Type Of Review Name (Print) Approval Signature Date Fire Protection
____.___-J 1ý. .11,1 Type Of Review Name (Print) Approval Signature Date 'Security iS(;A Rf 09e44 Type Of Review Name (Print) '-Aproy Ig ature Date Radiation Protection DO W.--?.- /.Type Of Review Name (Print) ISign ature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date 3 0 0 0 0 0 I.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Form No. 732125 (Apr 2013) wi-DomnInom SSC Category Determination Document 0*K -DCSY-0 -Atahmn B Pae2 f2 S 0 S 0 0 0 S 0 S S 0 0 0 S 10.0 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/,3 Date Date S -X) -13 Date Date FSRC Meeting Number: 13-0,31 Form No. 732125 (Apr 2013) 0 0 0 0 0 0 0 0 0 0 0 S S 0 0 0 S S 0 S This page intentionally left blank 5 S S 0 S S 0 0 S 0 S S S S 0 0 S S S 0 S S S 0
'Dominion" SSC Category Determination Document OPK -DCSY-0 -Atahmn B Pao1o 1.0 Doc Type: Report Sub Type: DEC Document Number (ID): SYS-32B-DSERT Title: Gaseous Radioactive Waste Disposal Revision No.: 0 Date: 06/07/2013 1 1.1 Brief description or reason for revision:
Not applicable for Revision 0.0 0 0 S S 0 0 0 0 0 0 0 0 0 2.0 System Category (Check Appropriate):
NOTE: A SSC may be divided and have more than one category determination depending upon Its functional requirements.
I El- 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 1 WG-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 and Form No. 732125 (Apr 2013)
SDominion SSC Category Determination Document I .OPM DCS Y 0 -S Atahmn B Pae2o system 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 Header MG(R)-507, Reactor Coolant Drain Tank to Vent Header MG(R)-520 Combined Holdup Tanks to Vent Header ISOL MG(R)-537, VCT Vent to WDS Isolation MG(R)-544, VCT Gas Space to Vent Header MG(R)-549 Przr Relief Tank Vent Isolation MG(R)-550, Vent Header #2 to Waste Gas Analyzer Filter Inlet Isolation WG-16, Gas Decay Valve Gallery to Holdup Tanks WG-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 Tanks The Waste Gas Analyzer will be isolated from interconnecting systems at the following valves: NG-731, Misc Gas Systems to Auto Gas Analyzer 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 Vent MG(R)-566 Grab Sample to Bottle Inlet MG(R)-567 Grab Sample from Bottle Outlet The system will be isolated from the electrical distribution system at the 480V Waste Gas Compressor 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 and boundaries.
These drawings are to include system, electrical one-line and distribution, and select building and isometric drawings.
Related system drawings NOT incorporated In the system category 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 Analyzer MG(R)-516B, Hold Up Tank 1B to Gas Analyzer MG(R)-516C, Hold Up Tank 1C to Gas Analyzer MG(R)-520, Hold Up Tank to Vent Header 1 WG-17, Gas Decay Tanks to Holdup Tanks Form No. 732125 (Apr 2013)6 6 6 6 6 0 0 0 0 0 0 I.0 I S 0
- 0 0°0 0 0 S 0 0 0 0 0 0 S 0 0 0 S 0 9 S omuinlow SSC Category Determination.
Document SPK -E W tah etBIae3o Flow 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 Analyzer 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 Vent MG(R)-566 Grab Sample to Bottle Inlet MG(R)-567 Grab Sample from Bottle Outlet Flow 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 Header MG(R)-507, Reactor Coolant Drain Tank to Vent Header MG(R)-520 Combined Holdup Tanks to Vent Header ISOL MG(R)-537, VCT Vent to WDS Isolation MG(R)-544, VCT Gas Space to Vent Header MG(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 Tanks WG-36, Gas Decay Tanks to Plant Vent WG-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 Tanks Flow Diagram H2/02 Automatic Gas Analyzer, M-1725 Abandon 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 Vent V36 SV14 SV15 SV16 SV17 SV24 Circuit Diagram 480V MCC 1-35A, 1-35D, 1-45A & 1-45D, E-254 Abandon: Bus 1-35A, B6, Waste Gas Compressor 1A Motor Feed Form No. 732125 (Apr 2013)
, Donilnlon SSC Category Determination Document OPS. -ECS Y-0 -Atahen age 4..Circuit Diagram 480V MCC 1-62A, 1-52D, 1-5262 & 1-62B, E-261 Abandon: Bus 1-5262, A-6, Waste Gas Compressor 1B Motor Feed Lighting Panels RPA7, RPA8, RPA9, RPA1O, RPA11, RPA12, E-885 Abandon: RPA8 circuit 21, Waste Gas Analyzer The 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 Kewaunee Power Station (KPS).* Process the WG as required to permit disposal within the limits established by the applicable regulatory guidelines.
- Provide the ability to reuse waste gases as cover gases in the CVCS Holdup Tanks and DDT.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 cladding defects in one percent (1 %) of the fuel rods. The WG System Is capable of handling gaseous waste from two units.Basis for Category On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).
Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel in the reactor vessel, as specified In 10 CFR 50.82(a)(2).
The gas decay tanks contain the gases vented from the RCS, the Volume Control Tank, and the liquid CVC Holdup Tanks. Following abandonment of the RCS and CVCS systems the Waste Gas Decay Tanks and associated piping will be discharged and vented to atmosphere.
No new gasses will be produced as the CVCS will be drained/vented and the reactor vessel has been defueled.Form No. 732125 (Apr 2013)0 0 6 I.jo 0 0 I.0 0 0 0 0 0 S I.I.S l0 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0* 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 mIn'o SSC Categoty Determination Document OPMDC-Y-0
-Atahmn B Pag -of Based on the above, the Waste Gas System does not perform a function or provide support for 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 support of 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 Impact This DSERT package does not Impact Spent Fuel Pool Cooling. This DSERT package is associated with the accident analysis for a gas decay tank rupture per USAR section 14.2.3 Accidental Release-Waste Gas. Therefore this document requires FSRC review and approval.Commitments:
A search of licensing commitments using the following file path S:\KEWAUNEE\4\DATAI\LICENSING\Commitments\COMTRAKS\TRU ECOM MITM ENTS\ALL TRUE Commitments by Number, did not identify any open commitments related to the Waste Gas System. Additionally the license renewal commitments In table 15.7-1 of the USAR were reviewed and no commitments related to the Waste Gase System were identified.
Commitment numbers 85-05 and 85-052 to analyze for explosive gas mixtures were closed to commitment number 94-132, which was subsequently closed to commitment number 96-122. Commitment 96-122 was closed on 2/15/2001 following completion of the waste gas 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 Waste Gas System. The program is required to be maintained until the issuance of the PDTS. This program provides controls for gaseous effluents.
Following abandonment of the RCS and CVCS systems the Waste Gas Decay Tanks and associated piping will be discharged and vented to atmosphere.
No new gasses will be produced as the CVC System will be drained/vented and the reactor vessel has been defueled.
The requirement to maintain the program does not prevent the abandonment of the Waste Gas System as the system Form No. 732125 (Apr 2013)
SDominion" SSC Categoty Determination Document I* O KWDCS Y01 -Atahmn B.ae6o will 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 the issuance of the PDTS. This program provides controls for potentially explosive gas mixtures contained 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 of radioactivity contained in unprotected outdoor liquid storage tanks. The requirement to maintain the program does not prevent the abandonment of the waste gas system as the system 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 Is mentioned in the following chapters/sections:
2.7.1, Meteorological Program 8.2.2.4, 480V System 9.3.2.1, System Design and Operation, Component Cooling System 9.6.5.1, Auxiliary Building Special Ventilation System Design Basis 11.1.1.1 Control of Releases of Radioactivity to the Environment 11.1.2.3, Gas Processing 11.1.2.10, Gas Decay Tanks 11.1.2.11, Waste Gas Compressors Table 11.1-2, Waste Disposal Components Codes Table 11.1-3, Component Summary Data Figure 11.1-8, Waste Gas Processing 11.2.3.5, Auxiliary Building Vent Monitors 14.2 Standby Safety Features Analysis 14.2.3, Accidental Release Waste Gas Table B.2-1, Classification of Systems and Components H.2, Containment System evaluation, Leak Paths Offsite Dose Calculation Manual (ODCM): The ODCM will require revision to reflect abandonment of Waste Gas System. The system is mentioned in the following chapters/sections:
2.1.1 Waste
Gas Holdup System 2.1.4 Auxiliary Building Vent Table 13.2.1-1, Radioactive Gaseous Waste Sampling and Analysis 13.2 Gaseous Effluents
-13.2.5 Gas Storage Tanks 13.3 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.0 I.6 I.0 6 I.0 6 6 I.S S I.S S S S 0 I.I.S S S S S I.S S S S S S S 0 S S 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S S 0 S 0 0 0 , DominloW SSC Category Determination Document OPK -DCSY-0 -Atahmn B Pae .o The 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 Is identified In the Technical Requirements Manual section 8.3.7. The requirements of this section 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 purged and vented of any radioactive gasses prior to abandonment.
Additionally, no new gasses will be produced as the CVCS will be drained/vented and the reactor vessel has been defueled.Plant Impact The FPPA will be revised to reflect the complete abandonment of the Waste Gas System following abandonment.
In addition, the Fire Zone Summaries in the FPPA and the Fire Fighting 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 required disposition 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 not be established for the accident analysis for a gas decay tank rupture per USAR section 14.2.3 Accidental Release-Waste Gas.Form No. 732125 (Apr 2013) 09Dominionr SSC Category Determination Document OPK -ESY-0 -Atahmn B Pag 8-of 7.0 Expected duration for SSC category if NOT ABANDONED:
N/A 8.0 PREPARE and ATTACH the following documents:
- Completed 10 CFR 50.59 Screening or Evaluation, if required* Proposed DUs for appropriate drawings 9.0 Technical Concurrence:
Type Of Review Name (Print) Approval Signature Date Engineering
-, ., ..i 113 Type Of Review Name (Print) Approval Sinature Date Fire Protection
_____,,_______
___/_/__Type Of Review Name (Print) App. a na r Date Security ______Type Of Review Name (Print) App val S ure Date Radiation Protection DanIie J. Sha1fn -/.Type Of Review Name (Print) "ppro Signature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date Type Of Review Name (Print) Approval Signature Date Form No. 732125 (Apr 2013)
, Dominion SSC Category Determination Document OPK -DCSY-0 -Atahmn B Pae1 f1 0 0 S 0 0 0 0 0 S.0 0 0 0 S 0 0 0 0 S 0 10.0 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_ --71,1/3 Date Date Date te13 Date Date FSRC (Print/Sign), If required FSRC Meeting Number:/3 -0325 Form No. 732125 (Apr 2013) 0 0 S 0 0 0 0 S 0 S 0 0 0 0 S 0 0 0 0 0 0 This page intentionally left blank 0 0 0 0 0 S 0 0 0 0 0 0 0 0 S S 0 0 0 S S 0 0 0 0 0 S S 0 0 0 0 0 0 0 S S 0 0 0 0 0 S 0 ow-Dominlon' SSC Category Determination Document OP* W-EC-YC00 -AtahetB PgIof2 1.0 Doc Type: Report Sub Type: DEC Document Number (ID): SYS-35-DSERT Title: Chemical and Volume Control Revision No.: 0 Date: 5/6/2013 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 its functional 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), Chemical Mixing Tank, CVCS Mixed Bed Demineralizers A and B, CVCS Cation Bed Demineralizer, CVCS Deborating 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 Tank Transfer 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 A and B, Evaporator Feed Ion Exchangers
- 1, #2, and #3, Evaporator Condensate Demineralizers
- 1 and #2, the Boric Acid Evaporator Package, Component Cooling used by the Letdown Heat Exchanger and Seal Water Heat Exchanger, Instrument Air supply to control valves, Demineralized Water supplies, 480V electrical power supplies, all associated piping, instrumentation, filters, and Boric Acid Heat Tracing. The Excess Letdown Heat Exchanger, which directs flow to the VCT, and Reactor Coolant Pumps (RXCPs), which include seal Injection from charging and seal leakoff to the VCT, 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 Acid Form No. 732125 (Apr 2013)
SDominlon' SSC Category Determination Document 0 P K -D C SY Atac ni n B Pag 2 fS Evaporator, including the following components:
Evaporator, Feed Preheater, Absorption Tower, Evaporator Condenser, Distillate Cooler, Stripping Column, Vent Condenser, Condensate Return Tank, 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 lines FI-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 Tracing Form No. 732125 (Apr 2013)0 S 0 0 S S S 0 0 S 0 S S S S S S S S S S S S S S S S S S 0 S S S S S S S 0 S S S S 0 0 0 S 0 S 0 0 0 0 0 0 0 S S 0 0 0 0 0 , Dominion°SSC Category Determination Document 0*K -DCSY 0 -Atahmn B Pag 3 f2 3.0 Mark up the affected drawings using color coding to Identify system category type and boundaries.
These drawings are to include system, electrical one-line and distribution, and select building and isometric drawings.
Related system drawings NOT incorporated in the system category 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 Line Operations 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 to CVCS Letdown Line.-RXCP Seal Leakoff line from Boundary Isolation Valve CVC-212/MV-32115, RXCP Seal Water 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 valve Operations 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 Outlet Isolation-Letdown Heat Exchanger Drain piping (hard-piped to the Sludge Interceptor Tank), up to the following Boundary Isolation Valves:-MD(R)-270, Letdown Heat Exchanger Drain-MD(R)-271, Letdown Heat Exchanger Drain-MD(R)-272, Letdown Heat Exchanger Drain MD(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 Isol Form No. 732125 (Apr 2013)
VDomnlon° SSC Category Determination Document 3. 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 High Temp Divert Valve-Letdown piping up to Boundary Isolation Valve LD-80, Letdown to VCT Line Sample-Reactor Coolant Filter drain line piping (hard-piped to SIT), up to Boundary Isolation Valve LD-47, Reactor Coolant Filter Drain-Letdown flow divert to CVC HUTs line from LD-27/CV-31096, VCT/Holdup Tank Divert Valve (continued on OPERXK-100-37)
-Letdown piping and the VCT Letdown piping from LD-14 through the CVCS Demineralizers, and return piping to downstream 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 to Spent 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 to Spent 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 to Spent 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 to Form No. 732125 (Apr 2013)0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 0 S S 0 0 0 0 0 0 0 0 0 0 n 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 minlo., SSC Category Determination Document OPK -D.SY 0 -Atahmn B Pae5 f2 Spent 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 Valve CVC-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 Seal Water 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 Isol CVC-413, Blended Makeup to Spent Fuel Pit Isol Boric Acid Supply to the Reactor Makeup piping (continued on OPERXK-100-38)
Form No. 732125 (Apr 2013)
DOF0mINIOn SSC Category Determination Document I P M DC-Y Atacm en B ae6*f2 The 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 line Boundary 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 Valve LD-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 Leakoff Operations Critical Drawing OPERXK-100-37, Chemical & Volume Control System (Revision AH)-Abandon CVC Holdup Tank fill header up to Boundary Isolation Valve CVC-802, Reactor Coolant Drn Tank Pump Discharge-CVC Holdup Tanks A, B, and C, Including Recirculation Pump and Gas Stripper Feed Pumps A & 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 Storage Tank)-DW-214A, #1 Evap Feed Ion Exch Backwash Evaporator Feed Ion Exchanger
- 2 up to the following Boundary Isolation Valves: Form No. 732125 (Apr 2013)6 6 I 6 6 S S S 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0*S 0 0 S 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 S 0 Dominion'SSC Category Determination Document 0PK -DCSY 0 -Atahmn B*ae7 f2 CVC-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 Storage Tank)DW-214B, #2 Evap Feed Ion Exch Backwash Evaporator 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 Storage Tank)-DW-215, #3 Evap Feed Ion Exch Backwash Boric Acid Evap Feed Ion Exchange Filter up to Boundary Isolation Valve CVC-865, Ion Exchange 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 Resin Storage Tank)-CVC-944B, #2 Evap Condensate Demin Vent (Hard-piped to SIT)-CVC-945B, #2 Evap Condensate Demin Resin Disch (hard-piped to Spent Resin Storage 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 Drawing OPERXK-100-131)
-Abandon 2" lines from SGBT Sys & Waste Evap Dist. Filter (continued on Drawing OPERM-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, and Concentrates Holding Tank Transfer Pumps A and B, up to the following Boundary Isolation Valves:-CVC-620, Boric Acid Evap to Waste Evap-CVC-637, BA Evap to Waste Concentrates Tank Form No. 732125 (Apr 2013)
SDominion SSC Category Determination Document I OPMDCSY 1- Atacmn B Pag 8 f 2 Abandon Boric Acid Batch Tank and Batching Tank Agitator, up to the following Boundary Isolation 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 Bypass Abandon Boric Acid Storage Tanks A and B, Boric Acid Storage Tanks A and B Heaters, and Boric 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 Isol Operations Critical Drawing OPERXK-100-400, 15 GPM Boric Acid Evap. + Gas Stripper Flow Diagram (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 and 1B, 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 the Sump 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 drawing OPERM-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-Up And Demineralized Water Systems Operations Critical Drawing OPERM-216, Miscellaneous Gas Systems (Revision CV)Abandon all piping downstream of Boundary Isolation Valve NG-911, Nitrogen to BA Evap Abandon all piping downstream of the following Boundary Isolation Valves:-NG-802, Nitrogen to VCT Line Isolation Form No. 732125 (Apr 2013)0 0 0 0 S 0 S 0 0 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 Dominlow SSC Category Determination Document OP* 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 VCT Operations 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 also isolates the Component Cooling side of the Residual Heat Removal High Radiation Sample Heat Exchanger and Reactor Coolant High Radiation Sample Heat Exchanger.
These Sample 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 Evap CC-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 Isol Operations 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 1A Form No. 732125 (Apr 2013)
' Dominion° SSC Category Determination Document 6P-K -E-Y 01 -Atacnn B. Pag 10o2-BT-232B, SGBT To CVC Monitor Tank 1B Operations 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 Valve Stem Leakoff-Abandon all piping upstream of Boundary Isolation Valve CVC-60, CVC-7 Valve Stem Leakoff-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 Stem Leakoff-Abandon all piping upstream of Boundary Isolation Valve CVC-203B-1, CVC-203B Valve Stem Leakoff-Abandon the Seal Water Heat Exchanger, and all piping upstream of the following Boundary Isolation Valves: MD(R)-260, Seal Water Heat Exchanger Drain MD(R)-261, Seal Water Heat Exchanger Drain MD(R)-262, Seal Water Heat Exchanger Drain-Abandon the Letdown Heat Exchanger, and all piping upstream of the following Boundary Isolation Valves:-MD(R)-270, Letdown Heat Exchanger Drain MD(R)-271, Letdown Heat Exchanger Drain-MD(R)-272, Letdown Heat Exchanger Drain-MD(R)-273, Letdown Heat Exchanger Drain Operations 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 Batching Tank-Upstream of the following Boundary Isolation Valves: HS-5475, Batching Tank Htg Coils Outlet To Trap HS-5478, Batching Tank Htg Coils Outlet Trap Bypass-Abandon all steam and condensate piping for the Boric Acid Evaporator, Boric Acid Evaporator Feed Preheater, Boric Acid Evap Condensate Return Heat Exchanger, Boric Acid 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.te S 0 0 S 0 0 0 0 0 S S 0 S 0 0 0 0 0 0 0 0 0 0 0 S S S S 0 S 0 0 0.0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 S 0 0 0 S 0 0 Dominion'SSC Category Determination Document 0 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 Water piping, 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 Exch Operations Critical Drawing OPERXK-100-29, Safety Injection System (Revision AN)-Abandon all piping upstream of Boundary Isolation Valve CVC-412, Blndr Mkup To Rfling Water Storage Tank Isol Operations Critical Drawing OPERXK-100-131, Waste Disposal System (Revision CQ)-Abandon all piping upstream of Boundary Isolation Valve CVC-920, CVC Monitor Tank Pump 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 to Waste Evap-Abandon all piping upstream of Boundary Isolation Valve CVC-802, Reactor Coolant Drn Tank Pump Discharge Operations Critical Drawing E-240, 4160V & 480V Power Sources-Abandon 480V Bus 1-52 Breaker 15203, Charging Pump 1C, to load Operations 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 Agitator Operations 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 1B Operations 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 MV CVCl/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 1B1 Operations 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 1A2 Operations 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 Pump MV CVC301/32056
-480V MCC 1-52E (F3), Emergency Boration From Boric Tank MV CVC440/32127
-480V MCC 1-52E (H4), Charging Pump 2A Operations 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 MV LD60/32099 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 Valve downstream 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 Backup Supply 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-10 Form No. 732125 (Apr 2013)S I.0 0 6 S 0 0 S 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 Dominion SSC Category Determination Document S. I Operations Critical Drawing OPERM-213-5, Station & Instrument Air System (Sheet 5, Revision AE)-Abandon all Instrument Air piping for BA Evaporator, instrumentation, and control valves downstream 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 Charging Pumps, 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 To Blender, 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 to CVC-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 Recirc Line 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 of Boundary 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-476 Operations 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-712B Form No. 732125 (Apr 2013)
' Dominion SSC Category Determination Document I .OPK -E-Y-0 -Atahm n B Pag 14 of2 Operations 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 Valve Abandon 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 control 2. Maintains the proper water Inventory In the RCS 3. Provides the required seal water flow for the reactor coolant pump shaft seals 4. Processes reactor coolant letdown for reuse of boric acid 5. Maintains the proper concentration of corrosion Inhibiting chemicals in the reactor coolant, and 6. Keeps the reactor coolant fission product and corrosion product activities to within design 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 tank 2. Nitrogen as required for purging the volume control tank 3. Hydrazine or pH control chemical, as required, via the chemical mixing tank to the charging pumps suction.Additionally, reactivity control is provided by the Chemical and Volume Control System which regulates the concentration of boric acid solution neutron absorber in the Reactor Coolant 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 control of 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 In reactivity throughout core life such as those due to fuel depletion, fission product buildup and decay, and the xenon transient associated with power level changes.Form No. 732125 (Apr 2013)S 0 S S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0*0Do O O 0 O 0 0 0 0 0 O 0 O 0 0 0 0 O inionl Basis for Category SSC Category Determination Document 0 K -DCS Y 0 -S tahet B Pag 15of2 On May 15, 2103, the NRC docketed DEKs certification of permanent defueling of the Kewaunee Power Station. Therefore, effective Immediately, pursuant to 10 CFR 50.82(a)(1)(ii), the 10 CFR Part 50 license for KPS no longer authorizes operation of the reactor or emplacement or retention of fuel into the reactor vessel, as specified In 10 CFR 50.82(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 the irradiated fuel. Therefore, the postulated accidents involving failure or malfunction of the reactor, RCS or secondary system are no longer applicable.
The analyzed accident and operational 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 the Gaseous Waste System, scheduled to be completed in August of 2013.The basis for the abandonment category for the Chemical and Volume Control System is determined 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 safety Analysis 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 support for safe storage of Spent Fuel and the Radiological Effluent Monitoring/Offslte Dose Calculation 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 Document OPMDC-Y-0
-Atahmn B Pag S1 f2 6. 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 the needs of the above criteria and is therefore abandoned.
Regulatory Impact UPDATED SAFETY ANALYSIS REPORT (USAR)Reviewed all sections of the USAR, and the following sections\subsections reference the Chemical And Volume Control System: Chapter 1: Introduction Under Section 1.3: General Design Criteria, Subsection 1.3.5: Reactivity Control, the CVCS is briefly 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 the cdncentration of boric acid solution neutron absorber in the Reactor Coolant System.The system is designed to prevent uncontrolled or inadvertent reactivity changes, which might 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, fission product buildup and decay, and load follow.Any time that the plant Is at power, the quantity of boric acid ready for Injection always exceeds that quantity required for normal cold shutdown.Chapter 3: Reactor Under Section 3.1: Design Bases, Subsection 3.1.2: Principal Design Criteria, the CVCS is discussed under topic 3.1.2.6: Reactivity Holddown Capability:
The reactivity control systems provided are capable of making and holding the core sub-critical under accident conditions, in a timely fashion with appropriate margins for contingencies.
Normal reactivity shutdown capability is provided within 2 seconds following 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 plant cooldown.
Any time that the reactor Is at power, the quantity of boric acid retained In the boric acid tanks and Refueling Water Storage Tank (RWST) Is ready for injection always exceeds that required for the normal cold shutdown condition.
This quantity also exceeds that required to bring the reactor to hot shutdown (Hot Shutdown defined as: Reactivity in Ak/k is the Required Shutdown Margin in COLR (Cycle 32 requires Shutdown Margin ý: 1554 Form No. 732125 (Apr 2013).0 0 I.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 om 0 S 0 0 S S 0 0 0 0 0 0 0 0 0 0 0 0 0 WOWn~SSC Category Determination Document OPK -E-Y 0 -Atahmn B Pag 17of2 pcm), Coolant Temperature
> 540 0 1F, and = 0% fission power) and to compensate for subsequent xenon decay.Boric acid Is pumped from the boric acid tanks by the boric acid transfer pumps to the suction 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 diesel generator power on loss of offsite power. Boric acid can be Injected by one pump at a rate which takes the reactor to hot shutdown with no rods inserted, and also compensates for xenon decay. Additional boric acid injection is employed If It is desired to bring the reactor to 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 the short-term situation.
Shutdown for long-term and reduced-temperature conditions can be accomplished with boric acid Injection using redundant components, thus achieving the measure of reliability implied by the criterion.
Chapter 6: Engineered Safety Features Under Section 6.5: Leakage Detection And Provisions For The Primary And Auxiliary Coolant Loops, Subsection 6.5.1: Leakage Detection Systems, Subsection 6.5.1.2: Systems Design And 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 a decrease In the pressurizer level. If the charging pump(s) are in automatic control, an increase in charging pump speed will occur. If the pump(s) are in manual control, a decreasing volume control tank level and/or low pressurizer level will cause an alarm to actuate.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 the reactor 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 coolant makeup water, which is required to maintain the normal level In the pressurizer.
This is inherently a low precision measurement, since makeup water is also necessary for leaks from systems outside the containment.
Chapter 7: Instrumentation
& Controls Under 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 reactor coolant temperature Is provided in conjunction with the programmed coolant Form No. 732125 (Apr 2013)
WDominion" SSC Category Determination Document e* -ECS Y ta h e tB Pa e1 f2 temperature.
This minimizes the demands upon the Chemical and Volume Control System and the Waste Disposal System imposed by coolant density changes during loading and unloading.
The pressurizer water level decreases as the load is reduced from full load. This is 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 as possible the level changes resulting from the coolant temperature changes. To permit manual 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 Shutdown Control, Subsection 7.7.6.1: Equipment Control Outside Control Room (specifically the Dedicated Shutdown Panel), CVCS Is discussed under the following topics: 7.7.6.1.2 Reactivity Control Following plant shutdown to the hot shutdown condition, boric acid Is added to the RCS to maintain sub-criticality.
For boron addition, the Chemical and Volume Control System is used. 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 the plant Is not required Immediately after shutdown.
The xenon transient does not decay to the equilibrium level until some ten to fifteen hours after shutdown, and a further period would 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 Control Following a reactor trip, the reactor coolant temperature will automatically reduce to the no-load temperature condition as dictated by the steam generator temperature conditions.
This reduction in the reactor coolant water temperature reduces the reactor volume, and if continued pressure control Is to be maintained, reactor coolant makeup Is required.The pressurizer level is controlled in normal circumstances by the CVCS. The facility for boration 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 storage tanks or RWST.Under Section 7.7: Operating Control Stations, Subsection 7.7.6: Emergency Shutdown Control, Subsection 7.7.6.2: Indication And Controls Outside Control Room, CVCS is discussed 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. Placing the selector switch in the local position provides an annunciator alarm in the Control Room and 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)S 0 S S S S S S S S S S S S S S S S S S S S S 0Dm 0 0 0 0 0 0 S*0 0 0 0 0 0 0 0 0 mb.o SSC Category Determination Document , aPM DC-Y-0 -s Atahm n B.ae1 f2 Speed 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 shutdown panel.Chapter 8: Electrical System Under 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 of supplying water at the rate of 60 gpm. This will provide makeup for a total of 50 gpm reactor coolant pumps seal leakage (25 gpm per pump) and 10 gpm reactor coolant system leakage (maximum allowed by the TS). The water supply for the pumps will be from the refueling water storage tank. Technical Specifications provide the necessary inventory for four 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 to provide control room control of the amount of charging flow to the reactor coolant loop versus the reactor coolant pump seals.Chapter 9: Auxiliary And Emergency Systems Section 9.2: Chemical And Volume Control System, describes the design bases (section 9.2.1), system design and operation, components, and control (section 9.2.2), and the System Design Evaluation (section 9.2.3) which addresses availability and reliability, tritium control, leakage prevention, incident control, malfunction analysis, galvanic corrosion, and fuel element failure detection.
Under Section 9.3: Auxiliary Coolant System, Subsection 9.3.2: System Design And Operation, 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 portion of the CVCS.Also under Section 9.3, Subsection 9.3.4: System Evaluation, Subsection 9.3.4.3: Incident Control, Subsection 9.3.4.3.2:
Residual Heat Removal System, CVCS is discussed under topic 9.3.4.3.2.1:
Low Temperature Overpressure Protection:
Overpressurization transients can result from either a mass Input or an energy Input transient, and typically occur when the RCS is in a water solid condition.
The LTOP design assumed 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 also includes a mass addition transient involving all three charging pumps injecting water into Form No. 732125 (Apr 2013)
VDomion° SSC Category Determination Document 0'I OPK -E e-Y 0 -Atah etB Pae2 f2 the RCS with the letdown line isolated with two RHR & RXCPs operating.
The most limiting energy input, i.e., thermal expansion, transient assumed an initial starting of a RXCP with an assumed secondary to primary temperature difference of 100"F, with two RHR pumps operating.
Chapter 11: Waste Disposal And Radiation Protection System Under 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 CVC System: The bulk of the radioactive liquids discharged from the Reactor Coolant System (RCS) are processed 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 topic 11.1.2.1:
System
Description:
To facilitate storage, processing and disposal, the Liquid Waste Disposal System is designed to 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 waste Part 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 leakoffs These liquids flow to the reactor coolant drain tank or suction of the reactor coolant drain tank pumps and are discharged either directly to the CVCS holdup tanks or to the waste holdup tank by the reactor coolant drain pumps. These pumps can also return water from the refueling cavity to the RWST. There is one reactor coolant drain tank with two reactdr coolant drain tank pumps located inside of the Containment.
The remaining deaerated liquid waste originates in the CVCS charging and letdown paths and from miscellaneous equipment drains. These liquid waste streams are collected and handled In a closed system to minimize the hydrogen explosion hazard and prevent the escape of gaseous radioactivity.
This is accomplished by collecting deaerated waste in a closed piping system that drains to a deaerated drain tank. The deaerated drain tank is Form No. 732125 (Apr 2013)0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 wDominlon" SSC Category Determination Document 0 0 0 0 0 S 0 S 0 0 0 0 0 S S.I OPM DC SYC00 -Atcmn ae2 f2 isolated 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 to the Waste Disposal System through flow meters and discharged in the environment.
Chapter 14: Safety Analysis CVCS 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 power operation.
Boron.dilutions during Hot Standby, Hot Shutdown, and Cold Shutdown are not part 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 From Cracks 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 be accommodated by the charging pumps, which would maintain an operational water level In the pressurizer, permitting the operator to execute an orderly shutdown.
However, ruptures of small cross section in lines connected to the pressurizer steam space could cause the steam discharge through the break to exceed the vapor generation capacity of the pressurizer heaters. This situation would not allow for an orderly shutdown, even though 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 products existing in it.If the break is such that either pressurizer level or pressurizer pressure cannot be maintained, 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 is reached.On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(1i), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 address requirements 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 Document OPK -D*SY-0 -Atahmn B Pae2. f2 5.5.2 Primary Coolant Sources Outside Containment The System Integrity Program (SIP) provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
The systems include Safety Injection System, Chemical and Volume Control System, Containment Spray System, Miscellaneous Sumps and Drains System, Reactor Building Ventilation System, Residual Heat Removal System, and Primary Sampling System.On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7,2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 the System Integrity Program will require revision.Technical Requirements Manual (TRM)Reviewed all sections of the TRM, and the following section is applicable to the Chemical and Volume Control System: 8.1 REACTIVITY CONTROL SYSTEMS 8.1.1 Chemical and Volume Control System TNC 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 Charging pump to the Reactor Coolant System (RCS);OR b. A flow path from the RWST or BAST via a FUNCTIONAL Safety Injection 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 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. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(i1), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 TRM requirements for Modes 1-6 and Refueling no longer apply.Offsite Dose Calculation Manual (ODCM)15.1 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 Form No. 732125 (Apt 2013)0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0~0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 PDominion SSC Category Determination Document 0 0 0 0 0 S 0 0.0 0 0 0 0 OP K -D C SY*0 -Ata hm n B Pag 23o 2 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 Part 50.59, b. Sufficient information to totally support the reason for the change without benefit of additional or supplemental Information, c. A description of the equipment, components and processes involved and the Interfaces with other plant systems, d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto, e. An evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated In the license application and amendments thereto, f. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period In which the changes are to be made;g. An estimate of the exposure to plant operating personnel as a result of the change, and h. Documentation of the fact that the change was reviewed and found acceptable by the FSRC.Changes shall become effective upon review and acceptance by the FSRC.This is a complete abandonment of CVCS. On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. On May 15, 2013 the NRC docketed the certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii).
Therefore the 10 CFR Part 50 license no longer authorizes KPS to operate the reactor or emplace or retain fuel In the reactor vessel, as specified in 10 CFR 50.82(a)(2).
With the Reactor Coolant System abandoned and drained there will be no liquid waste created and no releases from the CVCS. With no liquid entering the CVCS and no releases from CVCS this change results in no increase in maximum exposures In the UNRESTRICTED AREA, to the general population and to plant operating personnel.
Detailed information concerning the predicted releases and 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 CVCS requirements.
Under Attachment 1: Shutdown Safety Assessment (SSA) Checklist, the Spent Fuel Pool Cooling section requires the following:
Form No. 732125 (Apr 2013)
Woominlin" SSC Category Determination Document I* OPK -E-Y-0 tahetB Pg 4o II* 3. At least one non-QA SFP makeup flowpath available and Service Water Emergency 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 RWST For RMST, RWST, and CVC HUT a usable volume of 15,120 gals shall be available.
- The CVC HUT combined volume of 60 percent Is required.* RMST greater than 150 percent combined level, to be consistent with other requirements In this procedure." RWST level greater than 30 percent to be consistent with other requirements in this procedure.
Additionally, further requirements for makeup flow paths available that exceed a capacity 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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> requires one alternate makeup flowpath capable of providing a minimum of 42 gpm to be protected.
Finally, under General SFP Notes, proceduralized flowpaths that meet the 42 gpm requirement are specified: " Makeup directly from the RMSTs via MU-1099, or makeup from the RMSTs through 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 the CVC System will remove the ability to satisfy all of the non-QA-1 Makeup Flowpaths to the SFP. 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 will remain available are:* SFP Makeup from RMST's through MU-1099.* SFP Makeup from RWST Attachment 1, Shutdown Safety Assessment (SSA) Checklist, requires ONE non-QA-1 SFP makeup flowpaths available and Service Water Emergency Makeup flowpath available.
This requirement will remain satisfied after abandoning the CVC System as follows: Form No. 732125 (Apr 2013)I.0 I.0 0 I.0 6 0 0 6 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0o 9,.u 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 nl on SSC Category Determination Document OPK-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 provide makeup 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 Service Water Emergency Makeup flowpath available, and there will be two non-QA-1 SFP makeup flowpaths available.
Licensing Commitments Outstanding commitments to the regulator were reviewed.
The following was found that affects the Chemical And Volume Control System: Commitment Number: 92-057 Commitment Made to: NRC Title: BULLETIN 88-08: TEMP. MONITORING
Background:
ADDITIONAL INFORMATION PROVIDED TO THE NRC REGARDING BULLETIN 88-08, 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 to enhance the ability to detect valve leakage.Item 2 -Perform a NDE of a section of pipe located adjacent to CVC-16, to demonstrate the integrity of that line.On February 25, 2013, DEK submitted a certification of permanent cessation of power operations pursuant to 10 CFR 50.82(a)(1)(i), stating that DEK has decided to permanently cease power operation of KPS on May 7, 2013. Upon docketing of the subsequent certification for permanent removal of fuel from the reactor vessel pursuant to 10 CFR 50.82(a)(1)(ii), the 10 CFR Part 50 license will no longer authorize KPS to operate the reactor 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 be maintained.
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 Document OP6 W-ECS Y 1 -Atahmn B Pag 26of2 Plant Impact There 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 required disposition as a result of system abandonment.
This DSERT package does not impact Spent Fuel Pool Cooling therefore does not require FSRC approval.5.0 Special conditions to support categorization(s):
None 6.0 Assumptions/Open Items to be validated or dispositioned:
- Validate the assumptions in this document for Spent Fuel Pool Non-QA-1 Makeup Flowpath 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/A 8.0 PREPARE and ATTACH the following documents:
0 9 0 0 0 0 0 0 0 0 0 Completed 10 CFR 50.59 Screening or Evaluation, if required Proposed DUs for appropriate drawings Form No. 732125 (Apr 2013) 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 0 0 0 0 0 0 Dnominion" SSC Categoty Determination Document OPK -D*SY 0 -Atahmn B Pao 7of2 9.0 Technical Concurrence:
Type Of Review Name (Print)6 7 A Date Engineering
________ ______Type Of Review Name (Print) Approval Signature Date Fire Protection
_____ ___ Z *.,,, Type Of Review Name (Print) Approval Signature Date Security 86__144 _____ ___S 05z9_6" Type Of Review Name (Print) ISap Sn re Date Radiation Protection -K' s', s-n 13 Type Of Review Name (Print) Appr v I Signature Date 10.0 Review and Approval: Prepa(ed By (Print/Sie)/
"'Reviewed By (Screen Qual.) (Print/Signt)-
Nuclear Lice 'Ing(Print/Si.n)
/ D3 Date.L/Date Date Date., l 1 =i, Concurrence by DSERT Coo dl 9tor I JAI Yca AzI FSRC (Prlnt/SIgn)', If req-uired//
FSRC Meeting Number: 13-0-31 Form No. 732125 (Apr 2013)
I II I II II II II 6I 6I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 DOMINION Kewaunee Power Station FSRC MTG # 13-031 Facility Safety Review Committee June 19,2013 1300 Hours 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ATTENDEES:
Quorum Chairperson:
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 Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted, FSRC 13-063 Miscellaneous Item Presenter:
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 15.1 of the ODCM states: 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 Parl 50.59, b. Sufficient information to totally support the reason for the change without benefit of additional or supplemental information, c.
FSRC Minutes 06/19/13-2-Kewaunee Plant Meeting No.13-031 A description of the equipment, components and processes involved and the interfaces with other plant systems, d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ fi'om those previously predicted in the license application and amendments thereto, e. An evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto, f. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes are to be made; g. An estimate of the exposure to plant operating personnel as a result of the change, and h. Documentation of the fact that the change was reviewed and found acceptable by the FSRC.Changes shall become effective upon review and acceptance by the FSRC.FSRC reviewed and discussed the documents and identified no safety issues. The following 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 be updated.The Committee recommended approval of the CVC documents with comments and final review of the comments by the FSRC chair.Discussion:
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 FSRC 13-064 Miscellaneous Item Presenter:
Dykstra Approved 0* FSRC Minutes Kewaunee Plant 06/19/13 Meeting No.13-031 1) 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 Part 50.59, b. Sufficient information to totally support the reason for the change without*benefit of additional or supplemental information, c. A description of the equipment, components and processes involved and the interfaces with other plant systems, d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste*that differ from those previously predicted in the license application and amendments thereto, e, An evaluation of the change, which shows the expected*maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto, f. A comparison of the predicted releases of 0radioactive materials in liquid and gaseous effluents and in solid waste to the actual*releases for the period in which the changes are to be made; g. An estimate of the exposure to plant operating personnel as a result of the change, and h.Documentation of the fact that the change was reviewed and found acceptable by*the FSRC. Changes shall become effective upon review and acceptance by the FSRC Discussion:
FSRC reviewed and discussed the documents and identified no safety issues or 0 concerns.0 The Committee recommended approval of the RBV Documents.
0 0 FSRC 13-065 Miscellaneous Item Presenter:
Cieslewicz Approved w/comments 0 0 0 0 0 0 0 0 0 0 0 S 0 FSRC Minutes Kewaunee Plant 0 06/19/13 Meeting No.13-031 S 1) NLAR 91 -Revise the TRM sections related to fuel movement to reflect only those 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 the unit".* Replace the terms "unit", "operation of the unit" or "operation of the plant" with more appropriate terms TRM 8.7.8 Spent Fuel Pool Temperature
- A new TRM section is being proposed to incorporate the License Amendment 172 requirement to maintain the temperature of the SFP water below 150'F.TRM Section 8.9 Refueling Operations
- Rename Section 8.9 "Fuel Handling Operations" as a more appropriate title in the defueled condition.
TRM 8.9.2, Fuel Handling and Manipulator Cranes* Rename TRM 8.9.2 "Spent Fuel Pool Bridge Crane" and replace "Fuel Handling Crane" with "Spent Fuel Pool Bridge Crane" throughout the section.* Change APPLICABILITY from "During REFUELING OPERATIONS" to"During movement of irradiated fuel assemblies or fuel assembly components." 1* Delete requirements related to Manipulator Crane and fuel movement in the reactor.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 assembly components."* Delete requirements related to fuel movement in the reactor TRM 8.9.6, Spent Fuel Pool Sweep System is being proposed for deletion.* Functionality requirements for the Spent Fuel Pool Sweep system apply only 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 by 1OCFR50.82(a)(2).
S Discussion:
FSRC reviewed and discussed the NLAR and identified no safety issues. The following action was taken by the Engineering FSRC representative:
write a condition report regarding why the deletion of the functional check of refueling S S S S S 0 S 0 0 0 0 0 0 0 0 0 S S 0 0 0 0 0 0 0 0 0 0 0 FSRC Minutes 06/19/13-5-Kewaunee Plant Meeting No.13-031 systems interlocks was being made since there were still interlocks on the bridge.The Committee recommended approval of NLAR 91 with comments and final review of the comments by the FSRC chair.
FSRC Minutes 06/19/13-5-Kewaunee Plant Meeting No.13-031 The meeting adjourned at 1344.To the best of the Committee's knowledge, none of the above items required NRC approval prior to implementation.
Submitted by: APPROVED:.
APPROVED: J Schuh ReodingSecreta.
79j3 Date 91A11-Si YJuen/ /FSRC Commi(tee Chaifnian cuiL ,-' Date AJ J Site Date S S S S S S S S S S S S S S S S S S S S S S S I S ATTACHMENTS:
None DOMINION Kewaunee Power Station FSRC MTG # 13-035 0 0 0.0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 Facility Safety Review Committee August 15, 2013 0958 Hours ATTENDEES:
Quorum Chairperson:
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 III MW Grapentine, Electrical Maintenance Supervisor DA Jeanquart, Mechanical Maintenance Supervisor WG Swanson, Decommissioning Team-Ops MD 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 Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-078 Design Change (DC)Presenter:
Wattleworth Approved 1) DC-KW-13-01128, Discharge Structure Outfall Stop Logs and B.5.b Pump Suction Point The Design Change (DC) will install stop logs in the discharge structure to maintain water in the pipe and confine the remaining service water discharge to a concentrated 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 Suction location to the Warm Water Pump Pit. This is being done because the plant's FSRC Minutes 08/15/13-2-Kewaunee Plant Meeting No.13-035 discharge channel will begin filling with alluvial deposits from Lake Michigan currents after the CW pumps are shut down. This has previously occurred within weeks of stopping the CW pumps. It will also be necessary to maintain the discharge 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 final review by the chairperson.
Discussion:
S S 0 0 0 S 0 S 0 0 0 S 0 0 0 0 FSRC 13-079 Miscellaneous Item Presenter:
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 Fire Control Panel, LFCP-I FSRC 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 to ONLY write a CR if out of acceptance.
This should be clarified.
The Committee recommended approval of the procedure as modified with final review by the chairperson.
FSRC 13-080 Miscellaneous Item Presenter:
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-1 FSRC 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 to ONLY write a CR if out of acceptance.
This should be clarified.
The Committee recommended approval of the procedure as modified with final review by the chairperson.
0 S S S S S S S S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 FSRC Minutes 08/15/13-3-Kewaunee Plant Meeting No.13-035 FSRC 13-081 Miscellaneous Item Presenter:
Jeanquart Approved 1) MA-KW-MPM-FP-007, Fire Hose Pressure Test, Rev. 5 This procedure revision removes steps requiring performer(s) to obtain, Mark, and Record Identification numbers on fire hoses (if not already marked/identified).
FSRC reviewed and discussed the procedure and identified no safety issues or concerns.Discussion:
The Committee recommended approval of the procedure.
FSRC 13-082 Miscellaneous Item Presenter:
Swanson Approved wicomments
- 1) Waste Gas System (32B) DSERT SSC Category Determination Document OP-KW-DEC-SYC-001 Attachment B. Document details total abandonment of the Waste Gas Processing System, what will be abandoned and justifies complete abandonment.
FSRC reviewed and discussed the documents and identified no safety issues. The following comments were made:* On Page 5, add "based on the above" to paragraph 3.The Committee recommended approval of the document with comments and final review of the comments by the FSRC chair.Discussion:
FSRC Minutes 08/15/13-4-Kewaunee Plant Meeting No.13-035 The meeting adjourned at 1029.To the best of the Committee's knowledge, none of the above items required NRC approval prior to implementation.
Submitted * ,/ Z -- v -- V, JM Schuh , Recording Secretary APPROVED:
__/_-_- _JT Stafford FSRC Committee Chairman Date-'-/3, , APPROVED: AJ Jo 1 Site V eesident Date Date 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ATTACHMENTS:
None DOMINION Kewaunee Power Station]?.QlC MTV- f I IfAAR Facility Safety Review Committee December 19, 2013 1002 Hours 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S ATTENDEES:
Quorum Chairperson:
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 Manager WG Swanson, Decommissioning Ops J Gadzala, Decommissioning R Edwards, USNR T Hanna, Supervisor Engineering (1) Indicates Chairperson and Members required for quorum per LI-AA-600.(alt) Alternate Member (nv) Non-Voting Member The Chairperson called the meeting to order and noted that quorum requirements were met.The following items were discussed and dispositioned as noted.FSRC 13-112 Licensing Amendment Request (LAR)Presenter:
Gadzala Approved 1) LAR 256- PDTS, Supplement 2 By application dated May 29, 2013, Dominion Energy Kewaunee, Inc. (DEK), requested an amendment to Facility Operating License Number DPR-43 for Kewaunee Power Station (KPS). The proposed amendment would revise the Operating License and revise the associated Technical Specifications (TS) to Permanently Defueled Technical Specifications (PDTS). Supplement I to the application was submitted on October 15, 2013.Include within the changes proposed in the application was deletion of the cyber security provisions contained in License Condition 2.C.(4). This proposal was based on the requirements of 10 CFR 73.54. regarding cyber security, no longer applying FSRC Minutes Kewaunee Plant 12/19/13 Meeting No.13-048 to KPS. However, the NRC staff recently verbally informed DEK that 10 CFR 73.54 continues to apply to facilities that were previously licensed to operate on the November 23, 2009 mandated date for that rule.In response to the staff's comments, DEK is revising the originally proposed amendment.
The revised request retracts the original proposal to delete the eyber security provisions contained in License Condition 2.C.(4), which will result in this license condition remaining unchanged.
Attachment 1 to this letter provides a supplement to the proposed amendment describing the revision.Discussion:
FSRC reviewed and discussed LAR 256- PDTS supplement and identified no safety issues 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 System The purpose of NLAR 88 is to delete Technical Requirements Manual (TRM) 8.3.7"Explosive Gas Monitoring System" due to the permanent shutdown and abandonment of the gaseous waste system. The Explosive Gas Monitoring System utilizes an inline Waste Gas Analyzer (WGA) to monitor the in service Waste Gs Decay Tank (WGDT) on a continuous basis to determine if the tank contains an explosive 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 longer being produced.
The Gaseous Waste System, including WGDTs, has been purged of radioactive and explosive gases, vented to atmosphere and abandoned.
Therefore, with no source of explosive gas the TRM requirements for the Explosive Gas Monitoring 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 Minutes 12/19/13 FSRC 13-114 Kewaunee Plant Meeting No.13-048 Miscellaneous Item (NLAR)Presenter:
Gadzala Approved 0 0 0 ,0'0 0 S 0 0 0 0 0 0 0 0 0 0 0 0~0 1) NLAR 90, Deletion of TRM 8.7.7, Flooding Protection
-Circulating Water Pump 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 the permanent shutdown and abandonment of the Circulating Water (CW) System.With the CW system permanently shut down, flooding protection from the system is no longer required.FSRC reviewed and discussed the NLAR and identified no safety issues or concerns.Discussion:
The Committee recommended approval of this NLAR.FSRC 13-115 Miscellaneous Item (NLAR)Presenter:
Gadzala Tabled 1) NLAR 95, Deletion of TRM 8.3.6, Seismic Monitoring Instrumentation The purpose of NLAR 95 is to delete Technical Requirements Manual (TRM) 8.3.6 Seismic Monitoring Instrumentation.
TRM 8.3.6 Bases states the seismic monitoring instrumentation is used to provide data on seismic events in order to permit a timely determination of the need for shutting down the reactor as a result of the event. With the reactor permanently shut down and defueled, TRM 8.3.6"Seismic Monitoring Instrumentation" can be deleted as this function of the seismic monitor is no longer required.FSRC requested information regarding what administrative controls currently exist to set the frequency and requirement for demonstrating fimctionality of the seismic monitor for EAL purposes (currently contained in TVR 8.3.6.1, which is being proposed for deletion);
and what administrative controls ensure that these functionality checks remain in place.Discussion:
The Committee recommended tabling NLAR 95.FSRC 13-116 Miscellaneous Item MNLAR)Presenter:
Gadzala Approved FSRC Minutes Kewaunee Plant 12/19/13 Meeting No.13-048 1) NLAR 89, Deletion of TRM 8.7.5, Snubbers The purpose of NLAR 89 is to delete Technical Requirements Manual (TRM) 8.7.5 Snubbers.
TRM 8.7.5 lists the snubbers in the Snubber program and the plant MODES for which the snubbers are required to be functional.
Snubbers in the program are required to be functional in MODES 1,2, 3, 4, 5 and/or 6 only. No snubbers are required by the TRM to be functional in the defueled condition.
Consequently TRM 8.7.5 is unnecessary in the permanently defueled condition and can be deleted.Discussion:
FSRC reviewed and discussed the NLAR and identified no safety issues or concerns.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 Supply The purpose of NLAR 97 is revise TRM 8.8.3, Emergency Diesel Generator (EDG)Ventilation Damper Control Air Supply, to reflect only those conditions required following 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 fuel assemblies).
Following certification of permanent defueling on May 15,2013, operation of the plant or placing fuel in the reactor vessel is prohibited by 1OCFR 50.82(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 50.59 screening section B The Committee recommended approval with comments of NLAR 97.
FSRC Minutes 12/19/13-5-Kewaunee Plant Meeting No.13-048 0 0 0 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 FSRC 13-118 Operation Procedure Presenter:
McMahon Approved 1) OP-KW-OSP-FP-002, Fire Pump Test Updated procedure to framemaker standards and renumbered procedure.
Major changes include: " Removal of License Renewal Statement" Added step to check the fire pump tested in run for at least 30 minutes to meet Fire Plan requirements S S S Added steps to document and track Fire Pump run time Changed preferred method for auto start to be via opening hose station #0 Updated Acceptance Criteria to be consistent with Fire Plan Discussion:
FSRC reviewed and discussed the procedure and identified no safety issues or concerns.The Committee recommended approval of this procedure.
FSRC 13-1119 Miscellaneous Item Presenter:
Swanson Approved wicomments Discussion:
- 1) SYS-07-DSERT, Blowdown and Blowdown Treatment System Categorization package S/G Blowdown and Blowdown Treatment System Categorization plan was submitted to FSRC because this system is an effluent processing system and per ODCM 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 being maintained available to support draining.]" Make the following sentence specific to blowdown systems on 8 of 12. [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.]" Validate the date 3/7/13 for temporary changes FSRC Minutes 12/19/13-6-Kewaunee Plant Meeting No.13-048 The Committee recommended approval with comments of SYS-07-DSERT.
FSRC 13-120 Miscellaneous Item Presenter:
Swanson Approved wiconmments Discussion:
- 1) SYS-45-2-DSERT, Radiation Monitoring System Categorization package for R- 11, R-12, and R-21.Categorization plan was submitted to FSRC because this system is an effluent monitoring 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 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 Committee recommended approval with comments of SYS-45-2-DSERT.
0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 FSRC Minutes 12/19/13-7-Kewaunee Plant Meeting No.13-048 The meeting adjourned at 1046.To the best of the Committee's knowledge, none of the above items required NRC approval prior to implementation.
0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 Submitted by: 2 2 nj Q SA Sm elc Recording Secretary ,/9 1 IL-i Date APPROVED: APPROVED: JT Stafford FSRC Committee Chairman 04/h.L Date Site 4I9 President Date ATTACHMENTS:
None This page intentionally left blank S S S S 0 S S S S S S S S S S S S S S S S