NG-18-0090, Calculation No. NEE-323-CALC-004, Revised Liquid Radiological EALs Per NEI 99-01

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Calculation No. NEE-323-CALC-004, Revised Liquid Radiological EALs Per NEI 99-01
ML18212A234
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 12/12/2017
From:
NextEra Energy Duane Arnold
To:
Office of New Reactors
References
NG-18-0090 NEE-323-CALC-004
Download: ML18212A234 (42)
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{{#Wiki_filter:CALC NO. NEE-323-CALC-004 I ENERCON CALCULATION COVER i SHEET REV. 00 Excellence-Every p roject. Eve ry doy. PAGE NO. 1 of 23 Revised Liquid Radiological EALs per N EI 99-Client: Duane Arnold Energy Center Title: 01 Project Identifier: NEE-323 Item Cover Sheet Items Yes No 1 Does this calculat ion contain any open assumptions , includi ng preliminary D [81 information , that requ ire confirmation? (If YES, ident ify the assumptions .) 2 Does this ca lcula tion serve as an " Alternate Calculation "? (If YES , identify the design D [81 verified calcu latio n.) Design Verified Calculation No. --3 Does this calculation supe r sede an existing Calculation? (If YES , identify the design D [81 verified calculation .) Superseded Calculation No. --Scope of Revision: Initial Issue Revision Impact on Results: Initial Issue Study Calculation D Final Calculation Safety-Related D Non-Safety-Related (Print Nam e and Sign) Originator: Jay Bhatt Date: 12/12/17 Design Verifier 1 (Reviewer if NSR): Ryan Skaggs Date: 12/12/17 Approver: Zachary Rose Date: 12/12/17 Note 1: For non-safety-re l ated calculation , design verification can be substituted by review. ENERCON CALCULATION CAL C NO. N EE-3 23-CAL C-00 4 I, bcellen~-Evtry proJ<<t. Every day. REVISION STATUS SHEET REV. 00 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 00 12/12/17 Ini tial I ssu e PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION A ll 00 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO.O F REVISION ATTACHMENT NO.OF REVISION PAGES NO. NO. PAGES NO. A 12 00 1 4 0 2 3 0 Page 2 o f 23 ENERCON TABLE OF CONTENTS Exctllence-F:vtry p r ojtct. Every day. Section 1.0 Purpose and Scope 2.0 Summary of Results and Conclusions 3.0 References 4.0 Assumptions 5.0 Design Inputs 6.0 Methodology 7.0 Calculations 8.0 Computer Software 9.0 Impact Assessment List of Attachments Attachment 1 -Calculation Preparation Checklist Attachment 2 -Monitor Efficiency Page 3 of 23 CALC NO. NEE-323-CALC-004 REV. 00 Page No. 4 4 5 5 6 8 15 23 23 # of Pages 4 3 I ENERCON &ctllenc e-Evtry projtct. Every day. N EE-323-CALC-004 CALC Revised Liquid Radiological EALs NO. f---------------------l per NEI 99-01 REV. 00 1.0 Purpose and Scope The Duane Arnold Energy Center is implementing the guidance of Revision 6 to NEI 99-01, "Development of Emergency Action Levels for Non-Passive Reactors ," which is the industry-developed methodology for emergency classification for the current operating fleet. Changes to the definitions of the condition for entry into the Emergency Action Level (EAL) RA 1 result in the development of a new entry threshold value for this EAL. This calculation determines the liquid radiation monitor readings that correspond to the new EAL thresholds for the release of liquid radioactivity resulting in offsite dose greater than 10 mrem Total Effective Dose Equivalent (TEDE) or 50 mrem thyroid Committed Dose Equivalent (COE) for one hour of exposure. 2.0 Summary of Results and Conclusions A spreadsheet was used to calculate the monitor counts per second (cps) reading necessary to reach offsite dose of 10 mrem TEDE or 50 mrem child thyroid organ dose as described in Section 7.0. The output from that spreadsheet is seen below. Tabl e 1-Monit o r R e s po nse for Liquid Radiol og i ca l EAL Thresholds Rad Monitor Equip. Modes 1,2,3 Modes 4, 5 ID 2 Hour Decay 36 Hour Decay cps cps 10 mrem SOmrem 10 mrem SOmrem TEDE Thyroid TEDE Thyroid General Service Water (GSW) RE-4767 2 3 , 200 49,100 10,400 14 , 000 Residual Heat Removal Service RE-1997 16,000 33,800 7,200 9,650 Water (RHRSW)/Essential Service I Water(ESW) RHRSW Dilution Line R E-4268 24,200 51 , 300 10 , 900 14 , 650 For a given scenario , the threshold is always met for the TEDE dose before it is met for the organ dose. The recommended RA 1 Liquid EALs are: Page 4 of 23 NEE-323-CALC-004 I ENERCON CALC Revised Liquid Rad i ological EALs NO. t------------------; per NEI 99-01 &cellenc~Every project. Every day. REV. 00 Table 2 -Recommen ded RA 1 Liqu id EALs Rad Monitor Equip. Modes 1,2,3 Modes 4, 5 cps cps GSW RE-4767 2.32E+4 1.04E+4 RHRSW/ESW RE-1997 1.60E+4 7.20E+3 RHRSW Dilution Line RE-4268 2.42E+4 1.09E+4 3.0 References 3.1 DAEC Offsite Dose Assessment Manual (ODAM), Rev. 37. 3.2 Federal Guidance Report No. 12 , External Exposure to Radionuclides in Air , Water , and Soil , 1993. 3.3 Code of Federal Regulations, 1 OCFR20 , January 2013. 3.4 NUREG-1940 , RASCAL 4: Description of Models and Methods , United States Nuclear Regulatory Commission , Office of Nuclear Security and Incident Response , 2012. 3.5 American National Standard Institute (ANSI/ANS). 1999. " Radioactive Source Term for Normal Operation of Light-Water Reactors," ANSI/ANS-18.1-1999, American Nuclear Society , La Grange Park , IL. 3.6 Plant Chemistry Procedure PCP 8.7 , Alarm Setpoints for Liquid Rad. Monitors. 3.7 NEI 99-01 , " Development of Emergency Action Levels for Non-Passive Reactors", Rev. 6. 4.0 Assumptions 4.1 For the calculation determining the RA 1 EAL for Reactor Modes 1 , 2 and 3 , the source is assumed to have decayed for 2 hours before reaching the receptor. This decay time is appropriate to produce best estimate results for liquid effluent thresholds for the corresponding Reactor Modes. 4.2 For the calculation determining the RA1 EAL for Reactor Modes 4 and 5 , the source is assumed to have decayed for 36 hours before reaching the receptor. This decay time is appropriate to produce best estimate results for liquid effluent thresholds for the corresponding Reactor Modes. 4.3 Per the ODAM , a mixing ratio of 5 is assumed when the effluent mixes with the water in the river. This correlates to a dilution ratio of 1/5 = 0.2. While the ODAM Page 5 of 23 ENERCON Excellena-Every projecc. Every day. CALC Revised Liquid Radiological EALs NO. N EE-323-CALC-004 per NEI 99-01 1------------------< REV. 00 Section 2.3 states that a dilution factor of 10 can be used for drinking water, using a mixing ratio of 5 is appropriate for determining the EAL thresholds. 5.0 Design Inputs 5.1 Data for each of the Service Water Radiation monitors, taken from ODAM Table 1-2 and Attachment 2, is presented here: Table 3 -Service Water Radiation Monitor Design Inputs Rad Monitor Equip. Range Efficiency Efficiency ID cps/µci/ml Source Document cps GSW RE-4767 0.1-10 6 2.19E+06 Attachment 2 RHRSW/ESW RE-1997 0.1-10 6 1.51E+06 Attachment 2 RHRSW Dilution Line* RE-4268 0.1-10 6 2.29E+06 Attachment 2 *RE-4268 wa s previously kn own as the RHRSW Rupture Disk Page 6 of 23 CALC N EE-323-CALC-004 ENERCON Revised Liquid Radiological EALs NO. &cellence-Every project. E v ery day. per NEI 99-01 REV. 00 5.2 The isotopic mixtu r e and half-lives used in this calculation are taken or developed from NUREG-1940 Table 1-2 and Table A-4. Table 4 -Isotopic Mi x ture and H a lf-li v e s Isotope BWR Coolant Half-life Isotope BWR Coolant Half-life Concentration (hr) Concentration (hr) (Cilg) (Cilg) Ag-110m 1.00E-12 6.00E+03 Na-24 2.00E-09 1.50E+01 Ba-140 4.00E-10 3.05E+02 Np-239 8.00E-09 5.66E+01 Ce-141 3.00E-11 7.80E+02 P-32 4.00E-11 5.83E+02 Ce-144* 3.00E-12 6.82E+03 Rb-89 5.00E-09 2.54E-01 Co-58 1.00E-10 1.70E+03 Ru-103 2.00E-11 9.43E+02 Co-60 2.00E-10 4.61 E+04 Ru-106 3.00E-12 8.83E+03 Cr-51 3.00E-09 6.65E+02 Sr-89 1.00E-10 1.21E+03 Cs-134 3.00E-11 1.81E+04 Sr-90 7.00E-12 2.54E+05 Cs-136 2.00E-11 3.14E+02 Sr-91 4.00E-09 9.50E+OO Cs-137* 8.00E-11 2.64E+05 Sr-92 1.00E-08 2.71 E+OO Cs-138 1.00E-08 5.38E-01 Te-129m 4.00E-11 8.06E+02 Cu-64 3.00E-09 1.27E+01 Te-131m 1.00E-10 3.00E+01 Fe-59 3.00E-11 1.07E+03 Te-132 1.00E-11 7.82E+01 1-131 2.20E-09 1.93E+02 W-187 3.00E-10 2.39E+01 1-132 2.20E-08 2.29E+OO Y-91 4.00E-11 1.40E+03 1-133 1.50E-08 2.08E+01 Y-92 6.00E-09 3.55E+OO 1-134 4.30E-08 8.76E-0 1 Y-93 4.00E-09 1.01E+01 1-135 2.20E-08 6.60E+OO Zn-65 1.00E-10 5.86E+03 Mn-54 3.50E-11 7.51E+03 Zr-95 8.00E-12 1.54E+03 Mn-56 2.50E-08 2.57E+OO Fe-55 1.00E-09 2.37E+04 Mo-99 2.00E-09 6.60E+01 H-3 1.00E-08 1.08E+05 Ni-63 1.00E-12 8.40E+05 5.3 Dose Coefficient from Water Immersion/ Annual Limit for Intake (ALI) The dose coefficient for water immersion for each isotope are from Table 111.2 of FGR12. The Annual Limit for Intake (ALI), which represents the number of microcuries that would have to be ingested to cause a dose of 5 rem to an occupationally exposed worke r is taken from 1 OCFR20, Appendix B, Table 1 Column One. Page 7 of 23 I ENERCON Excellence-Every project Every day. Isotope FGR 12 Svm 3 / Bq s Ag-110m 2.94E-16 Ba-140 l.87E-17 Ce-141 7.62E-18 Ce-144 l.91E-18 Co-58 l.03E-16 Co-60 2.74E-16 Cr-51 3.30E-18 Cs-134 l.64E-16 Cs-136 2.31E-16 Cs-137 l.49E-20 Cs-138 2.62E-16 Cu-64 l.98E-17 Fe-59 l.29E-16 1-131 3.98E-17 1-132 2.43E-16 1-133 6.39E-17 1-134 2.82E-16 1-135 l.73E-16 Mn-54 8.88E-17 Mn-56 l.86E-16 Mo-99 l.58E-17 N EE-323-CALC-004 CALC Revised Liquid Radiological EALs NO. f------------------l per NEI 99-01 REV. 00 Ta bl e 5-FGR 12 and ALI ALI Isotope FGR 12 ALI µCi Sv m 3 / Bq s µCi 5.00E+02 Na-24 4.73E-16 4.00E+03 6.00E+02 Np-239 l.70E-17 2.00E+03 2.00E+03 P-32 l.90E-19 6.00E+02 3.00E+02 Rb-89 2.30E-16 6.00E+04 2.00E+03 Ru-103 4.89E-1 7 2.00E+03 2.00E+02 Ru-106 2.24E-17 2.00E+02 4.00E+04 Sr-89 l.49E-19 5.00E+02 7.00E+Ol Sr-90 l.46E-20 4.00E+Ol 4.00E+02 Sr-91 7.48E-17 2.00E+03 l.OOE+02 Sr-92 l.47E-16 3.00E+03

  • 3.00E+04 Te-129m 3.39E-18 5.00E+02 l.OOE+04 Te-131m l.52E-16 6.00E+02 8.00E+02 Te-132 2.28E-17 7.00E+02 9.00E+Ol W-187 4.97E-17 2.00E+03 9.00E+03 Y-91 S.44E-19 6.00E+02 5.00E+02 Y-92 2.81E-17 3.00E+03 3.00E+04 Y-93 l.03E-17 l.OOE+03 3.00E+03 Zn-65 6.29E-17 4.00E+02 2.00E+03 Zr-95 7.82E-17 l.OOE+03 5.00E+03 Fe-55 O.OOE+OO 9.00E+03 l.OOE+03 H-3 0.00E+OO 8.00E+04 Ni-63 0.00E+OO 9.00E+03 5.4 Dose transfer fac t ors for radionuclides in effluent water for a child through the potable water pathway are taken from ODAM Appendix C , and shown in Table 9. 6.0 Methodology 6.1 General Approach With a given mixture of radionuclides , the dose received by an individual offsite is a function of the gross activity present in the liquid mixture. The resultant dose received by an offsite receptor is dependent not only on the gross radioactivity levels of the effluent but also upon the isotopic mixture present in the Page 8 of 23 NEE-323-CALC-004 ENERCON CALC Revised Liquid Rad i ological EALs NO. 1-------------------<

per NEI 99-01 &cellenc~Every project Ev,ry day. REV. 00 liquid. This calculation predicts the relative contribution of each radionuclide to the gross radiation monitored by the liquid effluent monitor. For a liquid release , the only phenomenon affecting the mixture is radioactive decay. With the mixture known , a given gross output reading (cps) from a liquid effluent radiation monitor can be scaled to determine the concentration of each isotope present in the liquid effluent. The calculation then uses liquid dilution factors as described in the Offsite Dose Assessment Manual to determine the resultant concentration of radionuclides to which an individual offsite would be exposed. Dose conversion factors are used to determine the dose (mrem) to an individual offsite due to their exposure to the liquid mixture of radionuclides. With the given radionuclide mixture and dilution factors understood , an iterative process can be used to relate the liquid effluent monitor reading to a target offsite dose. Two types of radiation dose are calculated:

  • Thyroid COE or Committed Dose Equivalent is the radiation dose to the thyroid due to an uptake of radioactive material.

In this case, the uptake is limited to ingestion of radioactive material present in river water.

  • TEDE or Total Effective Dose Equivalent is the summation of the Effective Dose Equivalent (EDE) and the Committed Effective Dose Equivalent (CEDE): TEDE = EDE+ CEDE.
  • EDE is the dose due to an individual being directly exposed (by submersion) to the radiation present in the liquid release. For this scenario , the individual is not actually immersed in the liquid , but boating above it so a correction factor is applied.
  • CEDE is the sum of the COE for each organ of the body with weighting factors applied for each organ. 6.2 Scenario The ODAM described dose pathways focus on long term ingestion of radionuclides through various food pathways.

This is in sharp contrast to the NEI thresholds which limit the exposure to one hour. To meet the prescribed one hour exposure scenario , the following scenario will be used:

  • An adult and a child are fishing from a boat on the Cedar River downstream of the facility.

While they are there , a radioactive liquid release from the facility curs. The release lasts one hour.

  • During that time frame each of the individuals ingests 500 milliliters of river water.
  • The individuals leave the area one hour after the start of the exposure when they heed the announcement from the ERO siren system. The pathways thus indicated are drinking water and boating. Page 9 of 23 ENERCON txcellena-Every proj~ct Every day. N EE-323-CALC-004 CALC Revised Liquid Radiolog i cal EALs NO. 1-----------------< per NEI 99-01 REV. 00 6.3 Radioactive Source The gross radioactive concentration is converted from cps to µCi/ml using the monitor efficiencies from Design Input 5.1. For example , the gross radioactive concentration in the GSW system with an indication of 10000 cps from the GSW Rad. Monitor is calculated as follows: 10000 1 µCi/ml 4.57E-03 µCi/ml 2.19E+06 With the total concentration of the effluent known , given a mixture of isotopes where the relative amount of each isotope is known , the isotopic mixture in the effluent can be determined.

The isotopic mixture and half-lives used in this calculation come from Design Input 5.2. In order to determine the radiation dose to the receptor , the concentrations affecting the receptor must be known. For Plant Modes 1 , 2 , and 3 , a source decay time of two hours is assumed to account for transit time (Assumption 4.1 ). For Plant Modes 4 and 5, a source decay time of 36 hours is assumed (Assumption 4.2). The NUREG-1940 source is decayed using Design Input 5.2. The Ag-11 Om computation is displayed (indicated as row 7) as an example: Page 10 of 23 CALC N EE-323-CALC-0 04 ENERCON Revised Liqu i d Radiological EALs NO. &cellena-Ev,ry projtcr. Every day. per NEI 99-01 REV. 00 Table 6 -So urce Decay NUREG-1940 Half-life l ambda Cone. Cone. Isotope Concentration hr hrs-1 2 Hr 36 Hr Ci/g Decay Decay A B C D E F Ag-llOm l.OOE-12 6.00E+03 =(LN(2))/C7 = B7*(EXP(-D7*2)) = B7*(EXP(-D7*36)) Ag-llOm l.OOE-12 6.00E+03 l.16E-04 l.OOE-12 9.96E-13 Ba-140 4.00E-10 3.05E+02 2.27E-03 3.98E-10 3.69E-10 Ce-141 3.00E-11 7.80 E+0 2 8.89E-04 2.99E-11 2.91E-11 Ce-144* 3.00E-12 6.82E+03 1.02E-04 3.00E-12 2.99E-12 Co-58 l.OOE-10 l.70E+03 4.08E-04 9.99E-11 9.85E-11 Co-60 2.00E-10 4.61E+04 l.SOE-05 2.00E-10 2.00E-10 Cr-51 3.00E-09 6.65E+02 l.04E-03 2.9 9E-09 2.8 9E-09 Cs-134 3.00E-11 l.81E+04 3.84E-05 3.00E-11 3.00E-11 Cs-136 2.00E-11 3.14E+02 2.2 0E-03 l.99E-11 l.85E-11 Cs-137* 8.00E-11 2.64E+OS 2.63E-06 8.00E-11 8.00E-11 Cs-138 l.OOE-08 5.38E-01 l.2 9E+OO 7.59E-10 6.9 5E-2 9 Cu-64 3.00E-09 l.27E+Ol S.46E-0 2 2.69E-09 4.20E-10 Fe-59 3.00E-11 1.07E+0 3 6.49E-04 3.0 0E-11 2.93 E-11 1-131 2.20E-09 l.93E+02 3.59E-03 2.18E-09 l.93E-09 1-132 2.20E-0 8 2.29E+OO 3.02E-01 l.20E-08 4.16E-13 1-133 l.SOE-0 8 2.08E+Ol 3.33E-02 1.40E-08 4.52E-09 1-134 4.30E-08 8.76E-01 7.91E-01 8.83E-09 l.83E-20 1-135 2.20E-08 6.60E+OO l.OSE-01 1.78E-08 5.02E-10 Mn-54 3.SOE-11 7.5 1E+03 9.23E-05 3.SOE-11 3.49E-11 Mn-56 2.SOE-08 2.57E+OO 2.70E-01 1.46E-08 1.SlE-12 Mo-99 2.00E-09 6.60E+Ol l.OSE-02 l.96E-09 l.3 7E-09 Na-24 2.00E-09 1.SOE+Ol 4.62E-02 1.82E-09 3.79E-1 0 Np-239 8.00E-09 5.66E+Ol l.22E-0 2 7.81E-09 5.lSE-09 P-32 4.00E-11 5.83E+02 l.19E-03 3.99E-11 3.8 3E-11 Rb-89 5.00E-09 2.54E-01 2.72E+OO 2.lSE-11 l.26E-51 Ru-103 2.00E-11 9.43E+02 7.35E-04 2.00E-11 l.95E-11 Ru-106 3.00 E-12 8.8 3E+0 3 7.85E-05 3.00E-12 2.99E-12 Sr-89 l.OOE-10 l.21E+03 5.72E-04 9.99E-11 9.80E-11 Sr-9 0 7.00E-1 2 2.54E+05 2.72 E-06 7.00E-12 7.00E-1 2 Sr-91 4.00E-09 9.SOE+OO 7.29E-02 3.46E-09 2.90E-10 Sr-92 l.OOE-08 2.71E+OO 2.56E-01 6.00E-09 l.Ol E-12 Te-129m 4.00E-11 8.06E+02 8.60E-04 3.99E-11 3.88E-11 Te-131m l.OOE-10 3.00E+Ol 2.31E-0 2 9.SSE-11 4.35 E-11 Te-132 l.OOE-11 7.82E+Ol 8.86E-03 9.82E-12 7.27E-12 W-187 3.00E-10 2.39E+Ol 2.9 0E-02 2.8 3E-10 l.06E-10 Y-91 4.00E-11 1.40E+03 4.94E-04 4.00E-11 3.93E-11 Y-92 6.00E-09 3.SSE+OO 1.95E-01 4.06E-09 5.34E-12 Y-93 4.00E-09 l.OlE+Ol 6.86E-02 3.49E-09 3.38E-10 Zn-6 5 l.OOE-10 S.86E+03 l.18E-04 1.00E-10 9.96E-11 Zr-95 8.00E-12 1.54E+03 4.SlE-04 7.99E-12 7.87E-12 Fe-55 l.OOE-09 2.3 7E+04 2.93E-05 l.OOE-09 9.99E-10 H-3 l.OOE-08 1.08E+OS 6.40E-06 l.OOE-08 l.OOE-08 Ni-63 l.OOE-12 8.40E+OS 8.25E-07 l.OOE-12 l.OOE-12 Page 11 of 23 ENERCON N EE-323-CALC-004 CALC Revised Liquid Radiological EALs NO. r-----------------1 per NEI 99-01 txct!llenct!-Every project. Every day. REV. 00 6.4 TEDE Dose To determine the TEDE dose for a one hour exposure , two components are considered. 1. Direct exposure to the radioactive water present in the river is considered , commonly described as Effective Dose Equivalent (EDE). 2. Committed Effective Dose Equivalent (CEDE) is considered , which is the dose mitment due to the ingestion or inhalation of a mixture of radioactive material. 6.4.1 EDE Immersion dose is calculated with guidance provided in Federal Guidance Report 12 (FGR12). With the isotopic concentration at the receptor known (Table 6), the dose (mrem) at the receptor can be calculated

Dose Where 1= concentration of radionuclide i present in the water at the receptor (µCi/ mP each isotope present in the liquid release factor from FGR12 for converting the liquid concentration to effective dose equivalent from Design Input 5.3 (mrem ml/ sec µCi) The dose coefficients in Design Input 5.3 from FGR12 relate the radioactive concentration of a liquid to the dose received by a person who is immersed in the liquid. FGR 12 also provides this statement about the relationship between immersion dose and dose received while boating: Exposure during boating activities T he do se coeffici ents for i mme rs ion i n cont a min a t e d w a ter in T a ble 111.2 a ss um e immer s ion in an in fi n it e pool and , t h us, a r e a ppropri a t e for e x po s ure while s wimming. E x tern a l e x po s ure to con ta min a t e d wat er can al s o occ ur durin g bo ati n g act i viti es. Fo r photon ex posur e, a do s ere d u ct i on factor o f 0.5 during bo at in g a c t i v it i es is a re as o na b l e v a lue th a t is unli k ely to und eres timat e ext e rnal dos e equiv a l e nt s. 6.4.2 CEDE To calculate the Committed Effective Dose Equivalent due to the consumption of contaminated water , the ALI values from Design Input 5.3 are used. The first column of Page 12 of 23 I ENERCON NEE-323-CALC-004 CALC Revised Liqu i d Radiological EALs NO. ____________ ____, &cellenc~Every projecc. Evtry day. per NEI 99-01 REV. 00 the table lists the ALI for each isotope. The ALI value is the Annual Limit for Intake and represents the number of microcuries that would have to be ingested to cause a dose of 5 rem to an occupationally exposed worker. Following the conversion of the ALI values to units of " mrem pe r µCi" the following equation can be used to determine radiation dose due to ingestion of a liquid mixture of radioisotopes.

Where v= concentration of the radionuclide i present in the water at the receptor (µCi/ml) each isotope present in the gaseous release factor converting the gas concentration to effective dose equivalent (mrem/µCi) volume of water ingested (ml) 1 OCFR20 includes a statement regarding the use of Table 1 Column One values for members of the public: ... a fa c t or o f 2 t o adju st th e o cc up at ional v a l u e s (derived fo r a du lts) s o t h a t th e y are a ppl i cable to o t her age group s. Spreadsheets are used in section 7.1 to calculate EDE and CEDE from all of the isotopes in the m i xture. 6.5 Organ dose Methods to calculate Organ Dose are taken from ODAM section 2.6 titled " Accumulated Personal Maximum Dose". The guidance is provided here: Page 13 of 23 ENERCON CALC Revised Liqu i d Radiological EALs NO. NEE-323-CALC-004 t-----------------; Excellence-Every p r ojec r. E v ery day. per NEI 99-01 REV. 00 where AD arJ; = Da 11 = L A Da nt .t; the dose commitment (mrem) to organ n of age group a due to the i sotopes identified in analysis k , where the analyses are those required by Tab l e 7.1-2. Thus the contribution t o the dose from gamma emitters become available on a batch basis for batch releases and on a weekly basiis for continuous r eleases. Similarly the contributions from H-3 is available on a monthly basis and the contributions from Fe-55, Sr-89, and Sr-90 become available on a quarterly basis. D a11 = the dose commitment duning the quarter-to-date to organ n , i ncl uding whole body , of the maximally exposed person i n age group a (mrem) ~a ni =transfer factor rela t ing a un i t release of rad i onudide i ,(Ci) i n a unit stream flow (gal/m in) to dose commitment to organ n, or who l e body , of an exposed person in [m.rem ga l]* age group a Ci min

  • via env i ronmen t al pathway e. C , 1: = the concentration of rad i onuclide i in the undi l uted liquid waste represented by sample k to be d i scharged (µCi/ml) A ft = duration of radioact i ve release represented by sample k which occurs within time boundaries TB and T E and during which concentration C"' and flows F1 k and F2k ex i s t. (min.) 3. 785
  • 10*1 = convers ion constant (3785 ml/ga l* 1 o-t' C i/µC i) F 1 1 = flow in the radioactive was t e release li ne (gaVm i nf re presen t ed by samp l e k. F 2t., = flow into which radioactive release rep resented by sample .k is mixed in the river at the po i nt of exposu re or withd rawa l o f wat er for use (same units as Fh)* For this calculation ,
  • ilt k is set to 60 minutes
  • F11<1 2ke is 0.2 per Assumption 4.3. Page 14 of 23 ENERCON NEE-323-CALC-004 CALC Revised Liquid Radiological EALs NO. 1---------

i

&cellence-Ev~ry project. E v ery day. per NEI 99-01 REV. 00

  • A ea ni values are taken from ODAM Appendix C (Design Input 5.4)
  • Based on the scenario , only the child thyroid organ is considered , as this bounds the adult , and is used in Iowa as the basis for Protective Action Guidelines.
  • Based on the scenario , only the drinking water pathway is considered. Spreadsheets are used in sect i on 7.2 to calculate COE-Thyroid from all of the isotopes in the mixture. 7 .0 Calculation 7 .1 TEDE Dose A Microsoft Excel spreadsheet uses an iterative process to determine the cps output r eadings from each of the three monitors that correspond to a TEDE Dose of 10 mrem. Sections of the spreadsheet are presented here. This is the spreadsheet for the RHRSW/ESW Monitor. "' cu -..c n, *-... n, > Ingestio n Dose: 8.24 mrem + Boati n g Dose: 1.79 mrem Resu'ltant To t al mRem: 10.0 mr e m M o nit o r: RH RSW/ES W R M 1997 FGR~ Units I 3.70E+15 I Conversion Factor: r<iRl.2 Bonin&/l m'."er s ion Re d u ct ion F acto r:~ !c ps Mon it or c[s:! 16 , 000 Mon it or E ff iciency: ! I m 1.5 1E+'6 10 CFR20lngesti on AgeCo ru ider.o t ion F acto r:~ UC: i/m l Volu m e Consumed:! 500 !m l Decay Hrs:! 2 Dilution Fact o r: ! 0.20 R es ul ta n t Ri ve r Ga m ma Co n cent r at i o n fo r t h e G i ve n CPS R ea din g: 1E+0 6~ = 2.llE-03 lµC i/m l l6000 1~ I lµC i/m l 0.20 The mrem values seen above are calculated in the spreadsheet on the following pages. As can be seen above , the dilution factor (0.20) is included in the efficiency equation to account for the fact that the concentration in the river will be only 20% of the concentration seen by the effluent radiat i on monitor per Assumption 4.3. Page 15 of 23 N EE-323-CALC-004 ENERCON CALC Revised Liquid Radiological EALs NO. I------------

< per NEI 99-01 t x c~lle n~Every pro j e ct E v er y da y. REV. 00 7.1.1 Boating Dose The concentrations for the individual isotopes are scaled to the gross concentration determined above. In this case , the value is 2.12E-03 µCi/ml. The value of 2.12E-03 is calculated based on the monitor cps reading entered by the spreadsheet user. Through an iterative process , the user enters the monitor cps necessary to determine the desired resultant total dose (in mrem). The dose coefficien t for water immersion for each isotope in column Bin Table 7 is taken from Design Input 5.3. FGR 12 d i splays dose factors in the SI units of SV m 3/ bq sec. Traditional units of mrem ml/sec µCi sec are desired. FGR 12: 1 !i,lJ. lE+O S mR em 1 1*i-1E+0 6 ml f+ 3.7 0E+15 m Re m ml 1*i-sec !i,lJ. 2.7E-11 f+ 1E+0 6 µCi sec µC i The conversion factor from SV m 3/bq sec to mrem cm 3/µCi sec is 3. 70E+15. The decayed mixture from column E is taken from Table 6. Note that the concentration values present in the (starting) mixture do not affect the result. It is the ratios of the isotopes to the gross concentration (Section 7.1 -Column G) in the mixture that are needed. Per Section 6.4.1, a 0.5 dose-reduction factor is applied in Column I. For illustrative purposes , for the isotope AG-11 Om , the cell formulas are displayed. Tabl e 7 -Boat i ng Dose D ec ay e d F G R 1 2: FGR12 M ix Ri v e r Im mers i o n Boat in g SV m 3 Unit s mr e m m l µC i mr e m mr em b sec Conv. Ci sec ml Fra c tion C i/ml Sec H r 2.94E-16 3.70E+15 l.09E+O T ab l e 6 =E2/ =F2*2.12E-3 =D2*G2 =H 2*3600 l.1 7E-7

  • 0.5 A g-llOm 2.94 E-1 6 3.70E+15 l.09E+O l.OOE-12 0.00% l.81E-8 l.97E-8 3.54E-5 Ba-140 l.87E-1 7 3.70E+15 6.92E-2 3.98E-10 0.34% 7.20E-6 4.98E-7 8.97E-4 Ce-141 7.62E-1 8 3.70E+l5 2.82E-2 2.99E-11 0.03% 5.41E-7 1.53E-8 2.75E-5 Ce-144* l.91E-1 8 3.70E+15 7.07E-3 3.00E-12 0.00% 5.42E-8 3.83E-10 6.90E-7 Co-58 l.03E-16 3.70E+15 3.81E-1 9.99E-11 0.09% l.81E-6 6.88E-7 l.24E-3 C o-60 2.74E-1 6 3.70E+15 l.OlE+O 2.00E-10 0.1 7% 3.62E-6 3.67E-6 6.60E-3 C r-51 3.30E-1 8 3.70E+15 l.22E-2 2.99E-09 2.55% 5.41E-5 6.61E-7 l.1 9E-3 C s-134 l.64 E-16 3.70E+15 6.07E-1 3.00E-11 0.03% 5.42E-7 3.29E-7 5.92E-4 Cs-136 2.3 1 E-16 3.70E+l5 8.SSE-1 l.99E-11 0.02% 3.60E-7 3.08E-7 5.54E-4 Cs-1 37* 1.49E-20 3.70E+15 5.SlE-5 8.00E-11 0.07% l.45E-6 7.97E-11 1.44E-7 Cs-138 2.62E-16 3.70E+15 9.69E-1 7.59E-10 0.65% l.3 7 E-5 l.33E-5 2.39E-2 C u-64 l.98E-1 7 3.70E+15 7.33E-2 2.69E-09 2.29% 4.86E-5 3.56E-6 6.41E-3 F e-59 l.29E-1 6 3.70E+1 5 4.77 E-1 3.00E-11 0.03% 5.42E-7 2.59E-7 4.65E-4 1-1 31 3.98E-1 7 3.70E+15 l.4 7 E-1 2.1 8 E-09 1.86% 3.95E-5 5.82E-6 l.OSE-2 1-132 2.43E-1 6 3.70E+15 8.99E-1 l.20E-08 10.26% 2.17E-4 l.95E-4 3.52E-1 1-1 33 6.39E-17 3.70E+15 2.36E-1 l.40E-08 11.97% 2.54E-4 6.00E-5 l.08E-1 1-1 34 2.82E-16 3.70E+15 l.04E+O 8.83E-09 7.54% l.60E-4 l.67E-4 3.00E-1 1-1 35 l.73E-16 3.70E+15 6.40E-1 l.78E-08 15.21% 3.22E-4 2.06E-4 3.71E-1 Mn-54 8.88 E-1 7 3.70E+15 3.29E-1 3.SOE-11 0.03% 6.33E-7 2.08E-7 3.74E-4 Page 16 of 23 ENERCON NEE-323-CALC

-004 CALC Revis e d Li quid Ra di ologi c al EALs NO. 1--------------

' &c~llenc~-Evt.ry proj~c. E very da y. per NEI 99-01 REV. 00 Deca y ed FGR 1 2: FGR12 Mi x R iv er I mm e rsion Boa t ing SVm3 Unit s mr em ml µC i mrem m rem b sec Conv. Ci sec ml F r ac t io n C i/ml Sec H r Mn-56 l.86E-16 3.70E+15 6.88E-1 1.46E-08 12.43% 2.63E-4 1.81E-4 3.26E-1 Mo-99 1.58E-17 3.70E+15 5.85E-2 1.96E-09 1.67% 3.54E-5 2.07E-6 3.73E-3 N a-24 4.73 E-16 3.70E+15 1.75E+O 1.82E-09 1.56% 3.30E-5 5.77E-5 1.0 4E-1 N p-239 1.70E-17 3.70 E+15 6.29E-2 7.8 1E-09 6.66% 1.41E-4 8.88E-6 1.60E-2 P-32 1.90E-19 3.70E+15 7.03E-4 3.99E-11 0.03% 7.22E-7 5.07 E-10 9.13E-7 Rb-89 2.30E-1 6 3.70E+15 8.SlE-1 2.l SE-11 0.02% 3.89E-7 3.3 1E-7 5.95E-4 Ru-10 3 4.89E-17 3.70E+1 5 1.81E-1 2.00E-11 0.02% 3.6 1 E-7 6.53E-8 1.18E-4 Ru-106 2.24E-17 3.70E+1 5 8.29E-2 3.00E-12 0.00% 5.42E-8 4.49E-9 8.09E-6 Sr-89 1.49E-19 3.70E+15 5.SlE-4 9.99E-11 0.09% 1.81E-6 9.96E-10 1.79E-6 Sr-90 1.46E-20 3.70E+15 5.40E-S 7.00E-12 0.01% 1.27E-7 6.84E-12 1.23E-8 Sr-9 1 7.4 8E-17 3.70E+l5 2.77E-1 3.46E-09 2.95% 6.25E-5 1.73E-5 3.llE-2 Sr-92 1.47E-16 3.7 0E+15 5.44E-1 6.00 E-09 5.12% 1.08E-4 5.90E-5 1.0 6E-1 T e-129m 3.39E-18 3.70E+15 1.25E-2 3.99E-11 0.03% 7.22E-7 9.06E-9 1.63E-5 T e-131m 1.52E-16 3.70E+15 5.62E-1 9.SSE-11 0.08% l.7 3 E-6 9.71E-7 1.75E-3 T e-132 2.28E-17 3.70E+15 8.44E-2 9.82 E-12 0.01% 1.78E-7 1.SOE-8 2.70E-5 W-187 4.97E-17 3.70E+15 l.84E-1 2.83E-10 0.24% 5.12E-6 9.41E-7 1.6 9E-3 Y-91 5.44E-19 3.70E+l5 2.0lE-3 4.00E-11 0.03% 7.23E-7 1.45E-9 2.62E-6 Y-92 2.8 1E-17 3.70E+15 1.04E-1 4.06E-09 3.46% 7.34 E-5 7.63E-6 l.37E-2 Y-93 1.0 3E-1 7 3.7 0E+15 3.81E-2 3.49E-09 2.98% 6.3 1E-5 2.40E-6 4.33E-3 Zn-65 6.29E-17 3.70E+l 5 2.33 E-1 1.00E-10 0.09% 1.81E-6 4.21E-7 7.57E-4 Zr-95 7.82E-17 3.70E+15 2.89E-1 7.9 9E-12 0.01% 1.45E-7 4.18E-8 7.53E-5 Fe-55 O.O OE+OO 3.70E+l5 O.OOE+O 1.00E-09 0.85% 1.81E-5 O.OOE+O O.OOE+O H-3 O.OOE+OO 3.70E+l 5 O.OOE+O 1.0 0E-08 8.53% 1.81E-4 O.OOE+O O.OOE+O Ni-63 O.OOE+OO 3.70E+1 5 O.OOE+O 1.00E-12 0.00% 1.81E-8 O.OOE+O O.OOE+O l.17E-7 100.00% 2.12E-3 9.97E-4 1.7 9 2.12E-3 mr e m 7.1.2 Ingestion Dose I ngestio n dose is calc u lated in the section of th e spreadsheet seen below. ALis (umn D) from Design Input 5.3 are converted to mrem/µCi factors (co lumn E) as shown in the example below for Co-60 wh i ch has an ALI of 200 µC i: 5 ffiffi 100 0 mr em 2 5 m R em 2E+0 2 µC i 1 µC i The resul t ant dose (i n mrem) caused by ingesting 500 ml of the liquid is calculated per Section 6.4.2. The decayed mixtu r e from colu m n F is tak e n from Tabl e 6. An example demons tr ati n g dose caused by drinking 500 ml of wat er containing cobalt-60 with a c oncentra ti on of 0.001 µCi/ml: Page 17 o f 2 3 CALC NEE-323-CALC-004 J.I ENERCON Revised Liquid Radiological EALs NO. &cellence-Every projecr. Every day. per NEI 99-01 REV. 00 2 5 mr e m 0.001 500 RH 12.5 mrem ------i---+----+---+----+---

=-------For an occupationally exposed worker , drinking those 500 millilite r s of water contaminated with Co-60 would result in a dose of 12.5 mrem. Per Section 6.4.2 , this is multiplied by 2 , generating 25 mrem. Note that there are three hard-to-detect isotopes (HTDs) present in the mixture: Fe-55 , H-3 and Ni-63. Because they do not emit gamma rays , they are not detected by the service water radiation monitor. Therefore , they are effectively removed from the gross gamma calculation calibrating the monitor response (Columns H , I , and J). The HTDs are then scaled back into the calculation of the applied dose. For illustrative purposes , for the isotope Ag-1 1 0m , the cell formulas are displayed. The decayed mixture from column Fis taken from Table 6. Column M contains the multiplier for the 500 ml volume consumed and the 2x multiplier factor for members of the public. T a bl e 8-Ing e sti o n Dose Ga mm a Gamma 10CFR20 mrem Ci C i G amm a .b!Q .b!Q ALI Ci ml Fr ac t io n ml Fra c ti o n ml ml Fra c ti o n =1/ Table 6 =F2*1.17E-7 =H 2/ =12*2.12E-3 =J2 =K2/ 5.00E+02 (D2/SOOO) =F2 l.06E-7 2.32E-3 Ag-llOm 5.00E+02 1.00E+l 1.00E-12 0.0% 1.00E-12 0.0% 1.99E-8 1.99E-8 0.0% Ba-140 6.00E+02 8.33E+O 3.98E-10 0.3% 3.98E-10 0.4% 7.95E-6 7.95E-6 0.3% Ce-14 1 2.00E+03 2.SOE+O 2.99E-11 0.0% 2.99E-11 0.0% 5.98E-7 5.98E-7 0.0% Ce-144* 3.00E+02 1.67E+l 3.00E-12 0.0% 3.00E-12 0.0% 5.98E-8 5.98E-8 0.0% Co-58 1.00E+03 5.00E+O 9.99E-11 0.1% 9.99E-11 0.1% 1.99E-6 1.99E-6 0.1% Co-60 2.00E+02 2.SOE+l 2.00E-1 0 0.2% 2.00E-10 0.2% 3.99E-6 3.99E-6 0.2% Cr-5 1 4.00E+04 1.25E-1 2.99E-09 2.6% 2.99E-9 2.8% 5.97E-5 5.97E-5 2.6% Cs-134 7.00E+Ol 7.14E+l 3.00E-11 0.0% 3.00E-11 0.0% S.99E-7 5.99E-7 0.0% Cs-136 4.00E+02 1.25E+l 1.99E-1 1 0.0% 1.99E-11 0.0% 3.97E-7 3.97E-7 0.0% Cs-137* 1.00E+02 5.00E+l 8.00E-11 0.1% 8.00E-11 0.1% 1.60E-6 1.60E-6 0.1% Cs-138 3.00E+04 1.67E-1 7.59E-10 0.6% 7.59E-1 0 0.7% 1.SlE-5 1.SlE-5 0.7% Cu-6 4 1.00E+04 5.00E-1 2.69E-09 2.3% 2.69E-9 2.5% 5.3 7 E-5 5.3 7E-5 2.3% Fe-59 8.00E+02 6.25E+O 3.00E-11 0.0% 3.00E-11 0.0% 5.98E-7 5.98E-7 0.0% 1-13 1 9.00E+Ol 5.56E+l 2.18E-09 1.9% 2.18E-9 2.1% 4.36E-5 4.36E-5 1.9% 1-13 2 9.00E+03 5.56E-1 1.20E-08 10.3% 1.20E-8 11.3% 2.4 0E-4 2.40E-4 1 0.3% 1-133 5.00E+02 1.00E+l 1.40E-08 12.0% 1.40E-8 13.2% 2.80E-4 2.BOE-4 12.1% 1-134 3.00E+04 1.67E-1 8.83E-09 7.5% 8.83E-9 8.3% 1.7 6E-4 1.76E-4 7.6% 1-13 5 3.00E+03 1.67E+O 1.78E-08 15.2% 1.78E-8 1 6.8% 3.56E-4 3.56E-4 15.3% Mn-5 4 2.00E+03 2.SOE+O 3.SOE-11 0.0% 3.SOE-11 0.0% 6.98E-7 6.98E-7 0.0% Mn-56 5.00E+03 1.00E+O 1.46E-08 12.4% 1.46E-8 13.7% 2.91E-4 2.91E-4 12.5% Mo-99 1.00E+03 5.00E+O 1.96E-09 1.7% 1.96E-9 1.8% 3.91E-5 3.91E-5 1.7% N a-24 4.00E+03 1.2SE+O 1.82E-09 1.6% 1.82E-9 1.7% 3.64E-5 3.64E-5 1.6% Np-239 2.00E+03 2.SOE+O 7.81E-09 6.7% 7.81E-9 7.4% 1.56E-4 1.56E-4 6.7% P-3 2 6.00E+02 8.33E+O 3.99E-11 0.0% 3.99E-11 0.0% 7.96E-7 7.96E-7 0.0% Rb-89 6.00E+04 8.33 E-2 2.lSE-11 0.0% 2.lSE-11 0.0% 4.29E-7 4.29E-7 0.0% Page 18 of 23 mrem =K2*E2 *2*soo 1.99E-04 6.62E-02 1.49E-0 3 9.97E-04 9.9 7 E-03 9.98E-02 7.47E-0 3 4.28E-02 4.97E-03 7.98E-02 2.52E-03 2.68E-02 3.74E-03 2.42E+OO 1.33E-01 2.8 0E+OO 2.94E-02 5.93E-01 1.75E-03 2.9 1E-0 1 1.95E-0 1 4.SSE-0 2 3.89E-01 6.64E-0 3 3.5 7E-05 ENERCON Exc~llenc~Evt.ry p ro j<<.r. E very d ay. 10CFR 2 0 ALI Ru-103 2.00E+03 Ru-106 2.00E+02 Sr-89 5.00E+02 Sr-90 4.00E+Ol Sr-91 2.00E+03 Sr-92 3.00E+03 Te-129m 5.00E+02 Te-131m 6.00E+02 Te-132 7.00E+02 W-18 7 2.00E+03 Y-91 6.00E+02 Y-92 3.00E+03 Y-93 l.OOE+03 Zn-65 4.00E+02 Zr-95 1.00E+03 Fe-55 9.00E+03 H-3 8.00E+04 Ni-63 9.00E+03 N EE-323-CALC-004 CALC Revised Liqu id Radiological EALs NO. t--------------------i per NEI 99-01 REV. 00 Ga mma Gamma mrem Ci Ci Gamma 1dQ 1dQ Ci ml Fraction ml Fract i on ml ml Fraction 2.SOE+O 2.00E-11 0.0% 2.0 0E-11 0.0% 3.98 E-7 3.98E-7 0.0% 2.SOE+l 3.00 E-12 0.0% 3.00E-12 0.0% 5.99E-8 5.99E-8 0.0% 1.00E+l 9.99 E-11 0.1% 9.99E-11 0.1% 1.99E-6 1.99E-6 0.1% 1.25E+2 7.00E-12 0.0% 7.00E-12 0.0% 1.40E-7 1.40 E-7 0.0% 2.SOE+O 3.46E-09 2.9% 3.46E-9 3.3% 6.90E-5 6.90E-5 3.0% 1.67E+O 6.00E-09 5.1% 6.00E-9 5.6% 1.20E-4 l.20E-4 5.2% 1.00E+l 3.99E-11 0.0% 3.99E-11 0.0% 7.97E-7 7.97E-7 0.0% 8.33E+O 9.SSE-11 0.1% 9.SSE-11 0.1% 1.91E-6 1.91E-6 0.1% 7.14E+O 9.82E-12 0.0% 9.82E-12 0.0% 1.9 6 E-7 1.9 6E-7 0.0% 2.SOE+O 2.83E-10 0.2% 2.83E-10 0.3% 5.65E-6 5.65E-6 0.2% 8.33E+O 4.00E-11 0.0% 4.00 E-11 0.0% 7.97E-7 7.97E-7 0.0% 1.6 7E+O 4.06E-09 3.5% 4.06E-9 3.8% 8.lOE-5 8.lOE-5 3.5% 5.00E+O 3.49 E-0 9 3.0% 3.49E-9 3.3% 6.96E-5 6.96E-5 3.0% 1.25E+1 1.00E-10 0.1% 1.00E-10 0.1% 1.99E-6 1.9 9E-6 0.1% 5.00E+O 7.99E-12 0.0% 7.99E-1 2 0.0% 1.59E-7 1.5 9E-7 0.0% 5.56E-1 1.00E-09 0.9% 1.81E-5 0.8% 6.25E-2 1.00E-08 8.5% 1.81E-4 7.8% 5.56E-1 1.00E-12 0.0% 1.81E-8 0.0% 1.17E-7 100% 1.06E-07 100.0% 2.12E-3 2.3 2E-3 100.0% 2.12E-3 The initial HTD value is scaled to the total value of the gammas present. Using those ratios, the new HTD concentrations are determined by multiplying the ratios by the revised sum of the gamma emitters. Hard-to-Detect Determination Concl z:gammas z:gammas Conc2 HTD Ci Ci Ratio HTD 1dQ 1dQ ml ml ml ml Fe-55 l.OOE-9 l.17E-07 8.53E-3 Fe-55 2.12E-3 l.81E-5 H-3 l.OOE-8 l.17E-07 8.53E-2 H-3 2.12E-3 l.81E-4 Ni-63 l.OOE-12 l.17E-07 8.53E-6 Ni-63 2.12E-3 l.81E-8 7.2 Organ Dose The organ dose calculation is similar to the TEDE calculation above in that it uses a spreadsheet to determine the monitor cps reading necessary to reach the EAL threshold. The calculation is also similar in that it uses liquid concentrations and dose conversion factors to determine dose. The first part of the spreadsheet is presented here showing the gross concentration developed from section 6.5. Page 19 of 23 mrem 9.96E-04 1.SOE-03 1.99E-02 1.75E-02 1.72E-01 1.99E-01 7.97E-03 1.59E-02 1.40E-03 1.41E-02 6.64E-03 l.35 E-01 3.48E-01 2.49E-02 7.97E-04 1.00E-02 1.13E-02 1.00E-05 8.24 mrem NEE-323-CALC-004 ENERCON CALC Revised Liquid Radiological EALs NO. 1--------------- p er NEI 99-01 "' a.. -.a ra *-I.. ra > Excellt!nc~fvery projecr. Eve,y day. REV. Ch i ld T h yroid: 5-0.0 mRem Monitor: RHRSW/ESW R M1997 2 I ODAM Conversion Factor: 13. 785E-03 I Dec.y H ours!._ _ __._ Monito r*CPS:! 33,800 !c: ps ._ _____ _. EKposure Time (Mins.):~ Monito r Effi ci en cy:! 1.51E+6 !c ps L....:......J uCi/ml Di l'ution Factor:-, -0.-2 0--! ComblnlngFactor: ! 2.2 71E-01 ! Resultan t Gamma Concentration for the G iv en CPS Reading : 3 3800 1~ I I uCi/ml I 0.20 l.51E+06 Efi5 = 4.48E--03 I u<:i/m l 00 The dose value seen above is calculated in the spreadsheet on the following pages. As can be seen above , the dilution factor (0.20) is included in the efficiency equation to account for the fact that the concentration in the river will be only 20% of the concentration seen by the effluent rad monitor per Assumption 4.3. The concentrations for the individual isotopes are scaled to the gross concentration determined above. In this case , the value is 4.48E-03 µCi/ml. This value is calculated based on the monitor cps reading entered by the spreadsheet user. Through an iterative process , the user enters the monitor cps necessary to determine the desired resultant total dose (in mrem). Resultant river concentrations are presented in the section of the spreadsheet seen on the next page. In this spreadsheet , all of the isotopes present in Appendix C of the ODAM (Design Input 5.4) are included. In many instances , there is no corresponding isotope available from the NUREG-1940 reference. The entire list was included to simplify the spreadsheet calculation. The decayed mixture is taken from Table 6. Note that the concentration values present in the (starting) mixture do not affect the result. It is the ratios of the isotopes to the gross concentration in the mixture that are needed. These fractions are calculated in the same way as section 7.1. As in section 7.1.2 , HTDs present in the mixture (Fe-55 , H-3 , and Ni-63) are removed from the gross gamma calculation and then scaled back into the calculation of the applied dose (see below for scaling). Page 20 of 23 NEE-323-CAlC-004 ENERCON CALC Revised Liquid Radiological EALs NO. 1-------------------1 per NEI 99-01 £xcellena-Every p r oject. Every day. REV. 00 The ODAM Appendix C dose transfer factors for the thyroid (Design Input 5.4) are displayed on the second to last column from the right. Using ODAM calculation methods described in section 6.5 , the H-3 dose component of the child thyroid pathway is calculated individu ally here as an example: 3.82E-04 µCi/ml

  • 2.97E+01 mrem gal/ Ci min
  • 3.785E-03 ml Ci/gal µCi
  • 60 min = 2.58E-03 mrem Where 3.785E-03 is the conversion factor from the ODAM. 2.97E+01 is the H-3 dose transfer factor for the thyroid (Design Input 5.4). 3.82E-04 is the concentration of H-3 in the river corresponding to the monitor reading developed from Table 6 (see below for scaling).

AND the dispersion term (0.20) is not included here because it has already been included above in the concentration calculation. ODAM I sotopes H 3 C 14 NA24 P 32 CR 51 MN 54 MN 56 FE 55 FE 59 C058 C060 Nl6 3 N165 Decayed Mi x am 1.00E-08 1.82E-09 3.99E-11 2.99E-0 9 3.50E-11 1.46E-08 1.00E-09 3.00E-11 9.99E-11 2.00E-10 1.00E-12 CU 64 2.69E-09 ZN 65 1.00E-10 ZN 69 BR 83 BR 84 BR 85 RB 86 RB 88 RB 89 2.15E-11 SR89 9.99E-11 SR 90 7.00E-12 SR 9 1 3.46E-09 SR 92 6.00E-0 9 Y 90 Y 91M Y 91 4.00E-11 Mix Fraction 8.532% 0.000% 1.556% 0.034% 2.554% 0.030% 12.432% 0.853% 0.026% 0.085% 0.171% 0.001% 0.000% 2.295% 0.085% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.018% 0.085% 0.006% 2.950% 5.117% 0.000% 0.000% 0.034% Table 9-Thyroid Dose River Mix Mi x Gamma Gamma g Gamma .b!Q am Fraction ml 0.000% O.OOE+OO 0.000% O.OOE+OO l.82E-09 1.717% 7.69E-05 3.99E-11 0.038% l.68E-06 2.9 9 E-09 2.819% l.26E-04 3.SOE-11 0.033% 1.48E-0 6 1.46E-08 13.720% 6.14E-04 0.000% 3.00E-11 0.028% 1.26E-0 6 9.99E-11 0.094% 4.21E-06 2.00E-10 0.188% 8.43E-0 6 0.000% O.OOE+OO 0.000% O.OOE+OO 2.69E-09 2.532% l.13E-04 l.OOE-10 0.094% 4.21E-0 6 O.OO E+OO 0.000% O.OOE+OO O.OOE+OO 0.000% O.OOE+OO O.OOE+OO 0.000% O.OOE+OO 0.00E+OO 0.000% O.OOE+OO O.OOE+OO 0.000% O.OOE+OO O.OOE+OO 0.000% O.OOE+OO 2.lSE-11 0.020% 9.06E-07 9.99E-11 0.094% 4.21E-0 6 7.00E-12 0.007% 2.95E-07 3.4 6 E-09 3.255% l.46E-04 6.00E-09 5.6 47% 2.5 3 E-04 O.OOE+OO 0.000% O.OOE+OO O.OOE+OO 0.000% O.OOE+OO 4.00E-11 0.038% l.68E-0 6 Page 21 of 23 River River Dose Trans-Water f er Factor Thyroid Ga mma .b!Q (mrem gal} Fraction ml /Ci min) 0.00% 3.82E-4 2.97E+l 0.00% O.OOE+O 6.19E+2 1.72% 7.69E-5 4.91E+2 0.04% l.68E-6 O.OOE+O 2.82% l.26E-4 l.23E+O 0.0 3% 1.48E-6 O.OOE+O 13.72% 6.14E-4 O.OOE+O 0.00% 3.82E-5 O.OOE+O 0.0 3% l.26E-6 O.OOE+O 0.09% 4.21E-6 O.OOE+O 0.19% 8.43E-6 O.OOE+O 0.00% 3.82E-8 O.OOE+O 0.00% O.OOE+O O.OOE+O 2.53% l.13E-4 O.OOE+O 0.09% 4.21E-6 O.OOE+O 0.00% O.OOE+O O.OOE+O 0.00% O.OOE+O O.OOE+O 0.00% O.OOE+O O.OOE+O 0.00% O.OOE+O O.OOE+O 0.00% O.OOE+O O.OOE+O 0.00% O.OOE+O O.OOE+O 0.02% 9.06E-7 O.OOE+O 0.09% 4.21E-6 O.OOE+O 0.01% 2.95E-7 O.OOE+O 3.26% l.4 6 E-4 O.OOE+O 5.65% 2.53E-4 O.OOE+O 0.00% O.OOE+O O.OOE+O 0.00% O.OOE+O O.OOE+O 0.04% l.68E-6 O.OOE+O Thyroid Dose mrem 2.58E-3 O.OOE+O 8.57E-3 O.OOE+O 3.52E-5 O.OOE+O O.OOE+O O.OOE+O O.OO E+O O.OOE+O O.O O E+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O NEE-323-CALC-00 4 ENERCON CALC Revised Liquid Radio l ogical EALs NO. 1-----'--------------- p er NEI 9 9-01 &ct lle nc t-Every pro j ec t Ev er y d ay. REV. 00 Deca y ed Ri v er R i ve r Rive r Dose Tra n s-M i x Mix Mi x Mix Wa t e r f er Factor Ga m m a Gamma Thyro i d Thyroid O D AM g g Gamma .b!Q Gam m a .b!Q (mrem g a l) Dose I so t opes am Frac t ion am F raction m l Fraction ml (Ci min) mrem Y 92 4.06E-0 9 3.465% 4.06E-09 3.824% l.71E-04 3.82% l.71E-4 O.OOE+O O.OOE+O Y 93 3.4 9E-0 9 2.975% 3.49E-09 3.283% l.47E-04 3.28% l.47E-4 O.OOE+O O.OOE+O ZR 95 7.99E-1 2 0.007% 7.99E-12 0.008% 3.3 7E-07 0.01% 3.37E-7 O.OOE+O O.OOE+O ZR 97 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O N B 95 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O 0.00E+O M 099 1.96E-09 1.671% l.96E-09 1.844% 8.26E-05 1.84% 8.26E-5 O.OOE+O O.OOE+O TC99M 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% 0.00E+O O.OOE+O O.OOE+O TC 1 01 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O RU1 0 3 2.00E-11 0.017% 2.00E-11 0.019% 8.42E-07 0.02% 8.42E-7 O.OOE+O O.OOE+O R U 105 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O R U 106 3.00E-12 0.003% 3.00E-12 0.003% l.26E-07 0.00% l.26E-7 O.OOE+O O.OOE+O AG110M 1.00E-1 2 0.001% l.OOE-12 0.00 1% 4.21E-08 0.00% 4.21E-8 O.OOE+O O.OOE+O TE 125M 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O 8.09E+2 O.OOE+O TE1 27M 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O l.76E+3 O.OOE+O TE127 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O l.41E+l O.OOE+O TE 1 29M 3.99E-11 0.034% 3.99E-11 0.038% l.6 8 E-06 0.04% l.6 8E-6 3.94E+3 1.SlE-3 TE1 29 0.000% 0.00E+OO 0.000% O.OOE+OO 0.00% O.OOE+O l.44E-5 O.OOE+O T E 1 3 1 M 9.55E-1 1 0.081% 9.SSE-11 0.090% 4.02E-06 0.09% 4.02E-6 7.52E+2 6.87E-4 T E1 31 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.O OE+O O.OOE+O O.OOE+O T E1 32 9.82E-1 2 0.008% 9.82E-12 0.009% 4.14E-07 0.01% 4.14E-7 1.35E+3 l.27E-4 11 30 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O 4.32E+4 O.OOE+O I 1 31 2.1 8E-0 9 1.864% 2.18E-09 2.057% 9.21E-05 2.06% 9.21E-5 1.34E+6 2.80E+l 11 32 1.20E-0 8 10.258% l.20E-08 11.321% 5.07E-04 11.32% 5.07E-4 l.26E+l l.45E-3 11 33 1.4 0 E-0 8 11.973% l.40E-08 13.213% 5.92E-04 13.21% 5.92E-4 1.56E+S 2.lOE+l 1 134 8.83E-0 9 7.538% 8.83E-09 8.3 1 8% 3.72E-04 8.32% 3.72E-4 2.SSE-5 2.16E-9 1 135 1.78E-08 15.214% 1.7 8E-08 16.790% 7.52E-04 16.79% 7.5 2E-4 5.7 3 E+3 9.78E-1 CS 1 34 3.00E-11 0.026% 3.00E-11 0.028% 1.26E-06 0.03% l.26E-6 O.OOE+O O.OOE+O CS136 1.99E-11 0.01 7% l.99E-11 0.019% 8.39E-07 0.02% 8.39E-7 O.OOE+O O.OOE+O CS137 8.00E-11 0.068% 8.00E-11 0.0 75% 3.37E-06 0.08% 3.37E-6 O.OOE+O O.OOE+O CS 1 38 7.59E-1 0 0.64 7% 7.59E-10 0.714% 3.20E-05 0.71% 3.20E-5 O.OOE+O O.OOE+O BA139 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O BA 1 40 3.98E-10 0.340% 3.98E-10 0.375% 1.68E-05 0.37% l.68E-5 O.OOE+O O.OOE+O BA141 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O BA 1 42 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O LA140 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O LA142 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O C E1 41 2.99E-11 0.026% 2.99 E-11 0.028% l.26E-06 0.03% 1.26E-6 O.OOE+O O.OOE+O CE 1 43 0.00 0% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O CE144 3.00E-12 0.003% 3.00E-12 0.003% l.26E-0 7 0.00% l.2 6 E-7 O.OOE+O O.OOE+O PR143 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O P R14 4 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O ND1 47 0.000% O.OOE+OO 0.000% O.OOE+OO 0.00% O.OOE+O O.OOE+O O.OOE+O W 1 87 2.83E-10 0.242% 2.83E-10 0.267% l.19E-05 0.27% l.19E-5 O.OOE+O O.OOE+O NP 239 7.8 1 E-0 9 6.660% 7.BlE-09 7.350% 3.29E-04 7.35% 3.29E-4 O.OOE+O O.OOE+O 1.17E-07 100.0% l.06E-0 7 100% 4.48E-03 100.00% 4.90E-3 1.55E+6 5.00E+l 4.48E-3 Page 22 o f 2 3 _I __ _ N EE-323-CALC-004 ENERCON CALC Revised Liquid Radiological EALs NO. 1-------------------l per NEI 99-01 &ettllenc~Every project. Every day. REV. 00 The HTD isotopes displayed in this spreadsheet were scaled into the results as they were in the TEDE spreadsheet. Hard to Detect Determination HTD C oncl Lg amma s Ratio HTD Lgammas Conc 2 Fe-55 l.OOE-9 l.17E-07 8.53E-3 Fe-55 4.48E-3 3.82E-5 H-3 l.OOE-8 l.17E-07 8.53E-2 H-3 4.48E-3 3.82E-4 N i-6 3 l.OOE-12 l.17E-07 8.53E-6 Ni-63 4.48E-3 3.82E-8 Spreadsheet cases are run for all three monitors at decay times of 2 hours and 36 hours in consideration of EAL entry thresholds that are mode dependent. See Section 2.0 for results. 8.0 Computer Software No computer software was used in this calculation. 9.0 Impact Assessment This calculation is based on " realistic" assumptions for the purpose of declaring EALs , rather than typical conservative "bounding" type design basis analyses. The calculation results are intended to provide order of magnitude setpoints to assist Operations and Emergency Response personnel in determining the state of the three fission product barriers in accordance with NEI 99-01 Rev. 6. Page 23 of 23 ENERCON &celfena-Every project Every day. Monitor: V, FGR12 """' I QJ Coove,s;o, Fa<to" -..c Monitor c[s: I ta *-I.. Monitor Efficiency: I ta > Volume Consumed: I CALC NEE-323-CALC-004 Appendix A NO. REV. 00 Ingestion Dose: 8.24 mrem + Boating Dose: 1.79 mrem Resultant Total mRem: 10.0 mrem GSW RIS4767 3.70E+15 FGR12 Boating/lm~ersion Redu c tion Factor: 23,200 2.19E+6 I ill uC i/ml 500 I ml 10CFR20 Ingestion 10 Age Consideration Factor: L.:___J Decay Hrs: I 2 Dilution Factor: I 0.20 Resultant River Gamma Concentration for the Given CPS Reading : 2 3 2 00 I *j:>5 I µCi/ml 2.19E+06 *f:>5 I 0.2 0 2.12E-03 I µCi/ml Page 1 of 12 ENERCON Appendix A Excellence -Every proj~cr. Every day. CALC NO. REV. NEE-323-CALC-004 00 Child Thyroid: 50.0 mRem Monitor: GSW RIS4767 V, QJ Decay Hours I 2 -ODAM Coooe,,;oo Facto<e I 3. 785E-03 .c ca Monitor CPS: I 49,100 *-I.. ca Monitor Efficiency: I 2.19E+6 I cps > uCi/ml E,posu,e Tim, (M;os.), 8 Dilution Factor: I 0.20 Combining Factor: I 2.271E-01 Resultant Gamma Concentration for the Given CPS Reading : 49100 I~ I I uCi/ml E+06 I 0.20 = 4.48E-03 I uCi/ml Page 2 of 12 ENERCON txctl/ena-Ev,ry prof<<r. Every doi Monitor: II) FGR12 un;ts I QJ Conve,s;on Facto<' -.c Monitor c[s: I ca *-Monitor Efficiency: I ca > Volume Con s umed: I CALC N EE-323-CALC-004 Appendix A NO. REV. 00 Ingestion Dose: 9.78 mrem + Boating Dose: 0.19 mrem Resultant Total mRem: 10.0 mrem GSW RIS4767 3.70E+15 FGR12 Boating/lm'.11ersion Reduction Factor: 10 , 400 2.19E+6 I ill uCi/ml 500 I ml 10CFR20 Ingestion 10 Age Consider a tion Factor: L__:___J Decay Hrs: I 36 Dilution Factor: I 0.20 Resultant River Gamma Concentration for the Given CPS Reading : 10 4 00 I *P5 I µC i/m l 2.1 9E+0 6 *P5 I 0.2 0 9.SO E-04 I µCi/m l Page 3 of 12 . ENERCON Appendix A Excellence-Every project Every day. CALC NO . REV. N EE-323-CALC-004 00 Child Thyroid: 49.9 mRem Monitor: GSW RIS4767 V) QJ Decay Hours I 36 -ODAM Coa,.,,;o" Facto" I 3. 785E-03 ..c n:s Monitor CPS: ! 14,000 *-I.. n:s Monitor Efficiency: I 2.19E+6 I cps > uCi/ml Di l ution Factor: I 0.20 Combining Facto r: I 2.271E-01 Resultant Gamma Co n centration for the Given CPS Read i ng : 14000 I *ps I I uCi/m l E+06 *P5 I 0.20 = 1.28E-03 I uCi/ml Page 4 of 12 ENERCON &cellen~-Every project Evtry day. Monitor: V) FGR12 Units I QJ Conve,slon Facto" -.c Monitor c[s: I cu *-I.. Monitor Efficiency

I cu > Volume Consumed:

I Appendix A Ingestion Dose: CALC NO. REV. 8.24 NEE-323-CALC-004 00 mrem + Boating Dose: 1.79 mrem Resultant Total mRem: 10.0 mrem RHRSW/ESW RM1997 3.70E+15 FGR12 Boating/Immersion 0.50 Reduction Factor: 2 16,000 I cp s I ill 1.51E+6 10CFR20 Ingestion Age Consideration Factor: L.:._j uCi/ml 2 I 0.20 I 500 I ml Decay Hrs:!.__ Dilution Factor: .__I Resultant River Gamma Concentration for the Given CPS Readi ng: Ci/ml 16000 I *f}5 l.51E+06 *P5 I µCi/ml I 0.2 0 = 2.12E-03 I µ Page 5 of 12 I ENERCON Appendix A CALC NO. N EE-323-CALC-004 V, QJ -.c n, *-... n, > &cellence-Every project. Every day. REV. 00 Child Thyroid: 50.0 mRem Monitor: RHRSW/ESW RM1997 ODAM Conversion Factor: I 3.785E-03 Decay Hours!~ ___ 2 __ ~--------~----~ Monitor CPS: ~I ____ 33-'-,_80_0 ___ __.! cps Monitor Efficiency

I 1.51 E+6 I cps uCi/ml Dilution Factor: I 0.20 Combining Factor: I 2.271E-Ol Resultant Gamma Concentration for the Given CPS Reading: 33800 I~ I I uCi/ml i.SlE+06 I 0.20 = 4.48E-03 I uCi/ml Page 6 of 12 CALC NEE-323-CALC-004 ENERCON Appendix A NO. &:cellt!nc~-Every proj<<r. Every day. REV. 00 Ingestion Dose: 9.82 mrem + Boating Dose: 0.19 mrem Resultant Total mRem: 10.0 mrem Monitor: RHRSW/ESW RM1997 V, FGR12 un;ts I 3.70E+15 FGR12 Boat;og/lmme";"" G QJ Conmsloo Facto" Reduction Factor: -.c Monitor c[s: I 7 , 200 I cp s ca *-10CFR20 loge,t;oo 8 I.. ca Monitor Efficiency
I 1.51E+6 I ill Age Consideration Factor: > uCi/ml Decay Hrs: I 36 Volume Consumed:

I 500 I ml Dilution Factor: I 0.20 Resultant River Gamma Concentration for the Given CPS Reading: 7200 I *ps I µCi/m l l.51E+06 eps I 0.2 0 9.54E-04 I µCi/ml Page 7 of 12 I_ ENERCON Appendix A &cellenc~Every proj~r. Every day. CALC NO. REV. N EE-323-CALC-004 00 Child Thyroid: 49.9 mRem Monitor: RHRSW/ESW RM1997 V, QJ Decay Hours I 36 -ODAM Coov",;"" Facto,c I 3.785E-D3 ..c ta Monitor CPS: I 9,650 *-I,,. ta Monitor Efficiency: I I cps > 1.51E+6 uCi/ml Dilution Factor: I 0.20 Combining Factor: I 2.271E-01 Resultant Gamma Concentration for the Given CPS Reading: 9650 I~ I I uCi/ml E+06 I 0.20 = 1.28E-03 I uCi/ml Page 8 of 12 ENERCON Exullena-Every projecr. Every day. Monitor: V, FGR12 un;ts I QJ Convm;on Facto" -.c Monitor c[s: I n, *-I.. Monitor Efficiency: I n, > Volume Consumed: I CALC NEE-323-CALC-004 NO. Appendix A REV. 00 Ingestion Dose: 8.22 mrem + Boating Dose: 1.79 mrem Resultant Total mRem: 10.0 mrem RHRSW Dilution Line RM4268 3.70E+15 FGR12 Boating/lm':"ersion Reduction Factor: 24,200 2.29E+6 I ill uCi/ml 500 I ml 10CFR20 Ingestion Age Consideration Factor: L___:__J Decay Hrs: l 2 Dilution Factor: I 0.20 Resultant River Gamma Concentration for the Given CPS Reading : 24200 I *ps I µCi/ml 2.29E+06 *P5 I 0.2 0 2.llE-03 I µCi/ml Page 9 of 12 I ENERCON Appendix A CALC NO. N EE-323-CALC-004 VI a, -..c ta *-... ta > Exctllence-Every projecr. Every day. REV. 00 Child Thyroid: so.a mRem Monitor: RHRSW Dilution Line RM4268 ODAM Conversion Factor: I 3.785E-03 Decay Hours!._ ___ 2 __ __._ ________ __._ ____ __. Monitor CPS:I ._ ____ 51~,_30_0 ___ ~1 cp s Monitor Efficiency

I 2.29E+6 I cp s uCi/ml Dilution Factor: I 0.20 Combining Factor: I 2.271E-01 Resultant Gamma Concentration for the Given CPS Reading : 51300 I~ I I uCi/ml E+06 I 0.20 = 4.48E-03 I uCi/ml Page 10 of 12 CALC NEE-323-CALC-004 ENERCON Appendix A NO. f.xcttllenc

~Every p r o/ea. Eve r y d ay. REV. 00 Ingestion Dose: 9.80 mrem + Boating Dose: 0.19 mrem Resultant Total mRem: 10.0 mrem Monitor: RHRSW Dilution Line RM4268 V, FGR12 Units I Conve,s;on Facto" 3.70E+15 FGR12 Boating/lm~ersion Reduction Factor: QJ -.c Mon i tor c[s: I ra *-I-Monitor Efficiency: I ra > Volume Consumed: I 10,900 2.29E+6 I ill uCi/ml 500 I ml 10CFR20 Ingestion 10 Age Consideration Factor: L...:.___J Decay Hrs: I 36 Dilution Factor: I 0.20 Resultant River Gamma Concentration for the Given CPS Reading : 10900 I *f)5 I µCi/ml 2.29E+06 *f)5 I 0.20 9.52E-04 I µCi/ml Page 11 of 12 ENERCON Appendix A CALC NO. N EE-323-CALC-004 Excellena-Every proj~cc. Every day. REV. 00 Child Thyroid: 49.9 mRem Monitor: RHRSW Dilution Line RM4268 V, QJ Decay Hours l 36 -ODAM Coo,e,s;oo Facto" I 3.785E-D3 .c ca Monitor CPS: l 14,650 *-... ca Monitor Efficiency

l 2.29E+6 l cps > uCi/ml Dilution Factor: l 0.20 Combining Factor: l 2.271E-01 Resultant Gamma Concentration for the Given CPS Reading : 14650 I Ej,-5 I I uCi/ml 2.2 9E+0 6 Ej,-5 I 0.2 0 = 1.28 E-03 I uCi/ml Page 12 of 12 Attachment 1 CALC N EE-323-CALC-0 04 I ENERCON NO. I CALCULAT I ON PREPARAT I ON &ctllenct!-Evtry projecc. Every da y. CHECKLIST REV. 00 CHECKLIST ITEMS 1 YES NO N/A GENERAL REQUIREMENTS
1. If the cal c ulation is b ein g performed to a client procedure , i s the pro c edure being D D 1:8:1 used the latest revision? Th e calcu l ation i s being prepared to ENERCON's procedures. 2. Are the proper forms being used and are they the latest revision?

1:8:1 D D 3. Have the appropriate client review forms/checklists been completed? D D 1:8:1 The calculation is being prepared to ENERCON's procedures. 4. A re all pages properly i dentified with a cal c ulation number , ca l cu l ation revis i on and 1:8:1 D D page number cons i s t en t with the requirements of the cl i ent's procedure?

5. Is all information legible and reproducible?

1:8:1 D D 6. Is the calculation presented in a logical and orderly manner? 1:8:1 D D 7. Is there an e x isting calculat i on that should be revised or voided? D 1:8:1 D This is a new calculation to support i mp l ementing NEI 99-01 Rev. 6 8. Is it poss i ble to alter an e x isting calculation instead of prepar i ng a new calcu l ation for D 1:8:1 D t hi s situation?

9. If a n e x isting calculat i o n i s being used for design inputs , are the key des i gn inputs , assumptions and engineering judgments used in that cal c ulation val i d and do they D D 1:8:1 apply to the calcu l ation r evision bei n g performed. 10. I s t h e format of the calculation consistent with applicable procedures and 1:8:1 D D e x pectations?
11. Were des i gn inpuUoutput documents properly updated to reference th i s calculation?

0 0 1:8:1 12. Can th e calculation log i c , methodology and presentation be prope r l y understood 1:8:1 D D w i thout referring back to the originator for c l arification? OBJEC TI VE AND SC OP E 1 3. Does the ca l culation provide a clear c on c ise statement of the prob l em and objective 1:8:1 D D of the calculation?

14. Does the calcu l at i on provide a c l ear statement of qua l ity classification

? 1:8:1 D D 15. I s the reason for p erforming a n d the end use of the calcu l ation understood? 1:8:1 D D 16. Does the ca l cu l ation provide the basis for information found i n the plant's license D 1:8:1 D basis? 17. I f so , is this documented in the calculation? D D 1:8:1 18. D oes the calcu l ation provide the bas i s for information found in the pla n t's design D 1:8:1 D b asis documentation ? Page 1 of 4 Attachment 1 CALC N EE-323-CALC-004

  • ENERCON NO . CALCULATION PREPARATION

&cellence-Every pro j ecr. E v et y da y. CHECKLIST REV. 00 CHECKLIST ITEMS 1 YES NO N/A 19. If so , is this documented in the calculation? D D 0 20. Does the calculation otherwise support information found in the plant's design basis D 0 D documentation?

21. If so , is this documented in the calculation?

D D 0 22. Has the appropriate design or license basis documentation been revised , or has the D D 0 change not i ce or change request documents being prepared for subm i ttal? DESIGN INPUTS 23. Ar e design inputs clearly iden tified? 0 D D 24. Are design inputs retrievable or have they been added as attachments? 0 D D 25. If Attachments are used as design inputs or assumptions are th e Atta chme nts 0 D D traceable and veri fiable? 26. Are design inputs clearly distinguished from assumptions? 0 D D 27. Do es the calculation rely on Attachments for design inputs or assumptions? If yes , 0 D D are the attachments properly referenced in the calculat io n? 28. Are input sources (including industry codes and standards) appropriately selected 0 D D and are they consistent with the quality classification and objective of the calcu l ation? 29. Are input sources (includ i ng indu stry codes and standards) consistent with the plant's 0 D D design and license basis? 30. If applicable , do design inputs adequately address actual plant conditions? 0 D D 31. Are input values reasonable and correctly applied? 0 D D 32. Ar e design input sources approved? 0 D D 33. Does the calculation reference the latest revision of the design input source? 0 D D 34. Were all applicable plant operating modes considered? 0 D D ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective? 0 D D 36. Is adequate justification/basis for all assumptions provided?

0 D D 37. Are any engineering judgments used? D 0 D 38. Are engineering judgments clear l y identified as such? D D 0 39. If engineering judgments are utilized as design inputs , are they reasonable and can they be quantified or substantiated by reference to site or industry standards , D D 0 eng in eering principles , physical laws or other appropriate criteria? Page 2 of 4 ENERCON fxcellence-Every projec t E v ety day. Attachment 1 CALCULATION PREPARATION CHECKLIST CHECKLIST ITEMS 1 CALC NO. REV. METHODOLOGY

40. Is t he methodology used in the calculation described or imp l ied in the p la nt's licensing basis? 41. If the methodo logy used differs from that described in the plant's licens ing basis , has the appropriate license document change notice been initiated?
42. Is the methodology used consistent with the sta ted objective?
43. Is the methodology used appropriate when considering the quality class i fication of the calculation and intended use of the results? BODY OF CALCULATION
44. Are equations used in the calculation consistent with recognized engineering practice and the plant's design and license bas i s? 45. Is there reaso nable justification provided for the us e of eq uations not in common use? 46. Are the mathematical operat i ons perfo r med properly and documented in a logica l fashion? 47. Is the math performed correctly?
48. Have adjustment facto rs , uncertainties and empirical correlations used in the analysis been correctly applied? 49. Has proper consideration been given to results that may be overly sensitive to very small changes in i nput? SOFTWARE/COMPUTER CODES 50. Are computer codes or software la nguages u sed in the preparation of the calculation?
51. Have the requirements of CSP 3.09 for use of computer codes or software languages , including ve ri fication of accuracy and applicability been met? 52. Ar e the codes properly ident ified along with source vendo r , organization , and revision level? 53. Is the computer code applicable for the analys i s being performed?
54. If applicable , does the computer model adequate l y consider actual plant conditions?
55. Are the inputs to the computer code clearly identified and consistent with the inputs and assumptions documented in the calculation?
56. Is the computer output clearly identified?
57. Does the computer output clearly ident ify the appropriat e units? Page 3 of 4 NEE-323-CALC-004 00 YES NO NIA D [8J D D D [8J [8J D D [8J D D [8J D D D D [8J [8J D D [8J D D [8J D D [8J D D D [8J D D D [8J D D [8J D D [8J D D [8J D D [8J D D [8J D D [8J
58. 59. ENERCON tx c ell e nce-E ve ry pro j e ct E v er y da y. Attachment 1 CALCULATION PREPARATION CHECKLIST CHECKLIST ITEMS 1 CALC NO. REV. Are the computer outputs reasonable when compared to the inpu ts and what was expected?

Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results? RESULTS AND CONCLUSIONS

60. Is adequate acceptance criteria specified?
61. Are the stated acceptance criteria consistent with the purpose of the calcu l ation , and intended use? 62. Are the stated acceptance criteria consistent with the plant's design basis , app li cable licensing commitments and industry codes , and standards?
63. Do the calculation results and conc lus ions meet the stated acceptance criteria?
64. Are the results represented in the prope r units with an appropriate tolerance , if applicable?
65. Are the calculation results and conclusions reasonable when considered against the stated inputs and objectives?
66. I s suffic i ent conservatism applied to the outputs and conclusions?
67. Do the calculat ion results and co ncl usions affect any other ca l cu l ations? 68. If so , have the affected calcu lation s been re vised? 69. Does the ca l culation contain any conceptual , unconfirmed or open assumptions requiring later co nfi rmat i on? 70. If so , a r e they properly identified?

DESIGN REVIEW 71. Have alternate calculation methods been used to verify calculatio n results? No , a Design Review was performed. Note: NEE-323-CALC-004 00 YES NO N/A D D [8J D D [8J [8J D D [8J D D [8J D D [8J D D [8J D D [8J D D [8J D D D [8J D D D [8J D D D D [8J D D [8J 1. Where required, provide clar ifi cation/justification for answers to the questions in the space provided below each question. An e x planation is required for any quest ion s answered as " No' or " N/A". Originator: Jay Bhatt 12/12/17 Print Name and Sign Date Page 4 of 4 NEE-323-CALC-004 Attachm e nt 2 Page 1 of 3 " 1. " 3. " 4. "-5. " 6. '-.. 7. "' 8. ""'9. ""'-10. ALARM SETPOINTS FOR LIQUID RAD MONITORS ATTACHMENT 1 PCP 8.7 Rev. 17 Page 9 of 11 Page 1 of 3 LIQUID EFFLUENT RADIOACTIVITY MONITOR SETPOINT Sample No. \ S -']\95$ / . 2. Sample Date & Time l'l-1-tS /u ~o3 / Stream/Monitor Description GS'uJ (1:;.i!'91Wi~ Rf{)-YJG;,1 V 1 Effluent Monitor Reading (cps)_---'--'1 O'--___.i[_ __ ~~---,,--'--------------Effluent Flow (gpm) 00 *. *

  • Average effluent flow during.time* represented by sample, F1 (gpm) N ./ Average dilution {discharge canal) flow duri~presented by sample , F2 (gpm) N'R Monitor calibration factor. g, (cps/µCi/ml) * '"2,1'1 e 4 v
  • Previous alarm value setpoint (cps) __ J~(o~*~$'.~c 9 jrS~V::------c---------

Fraction to apply as a safety margin , A -0.5 Setpoint = 10 x[ "i..;_K, x g x F 2 xA]+Bkg = "i..i(K 1 WEC;) F; Setpoint = sx[(lS)(S)(7)]+(4) (16)(6) Setpoint = s x[( 9.4'3 1:-> )(:2..l"t e~ )( "(( ( 11 7 . 5 L\ )( W¥Z. Setpoint= 1 o x[ (l S)(S)(?) x (l o)] +( 4) (16)(6) )C. ) 11. Setpoint = -=.54_.9_*2 ____ / Fractional Change = New value -Previous Value = ( 11 ) -( 9 ) = ( 5i 2. ) -( '?<c,5 Previous Value ( 9 ) ( 1 G 5" ) ""-... 12. Fractional Change= *-o '22~ /" Uffractional change is greater than +/-0.3, adopt a new monitor alarm setting. Continuous Monitor Hi Alarm = Setpoint 13. Monitor Hi Alarm = 7(;, 5 crs / 14. RadwasteMonitorHiAlarm=.16(11) = .16( ) = N/A cps/ 2 4 NEE-32 3-CA LC-004 Attachment 2 Page 2 of 3 1. 3. 4. 5. 6. 7. 8. 9. 10. ii. 12. 13. 14. wlo l(o32 t7~ c; ALARM SETPOINTS FOR LIQUID RAD MONITORS Rev. 17 Page 9 of 11 A TT AC HM ENT 1 Page 1 of 3 LIQUID EFFLUENT RADIOACTIVITY MONITOR SETPOINT Sample No. 1.r-If~& 2. Sample Date & Tir.pe g-zq-rs-/ 6JoZ.7 Stream/Monitor Description @n-/91) (/2.1#25"-// &sf.).) J Effluent Monitor Reading (cps)-.--.-::,3 .. : ;L.:o,.,,,_ _____________ ____ _ Effluent Flow (gpm) 99oc:>

  • Average effluent .flow during time represented by sample , F 1 (gpm)_/i:....;1/.::...'/'-'-A

_______ _ Average dilution (discharge canal) flow during time represented by sample, F2 (gpm) /V/A Monitor calibration factor, g , (cps/µCi/ml)....---,.-"""/ ,-"'5"""/__,e ..... ~-------------Previous alarm value setpoint (cps) ___ b_,_q _______________ _ Fraction to apply as a safety margin, A= 0.5 Setpoint ::::]O x[ "i..;.K, xgx Fz xA]+Bk g = "i..1 (K 1 .,.. WEC;) F; Setpoint=l O x[(l S)(S)(?) x (l O)J+( 4) (16)(6) Setpoint = sx[(lS)(&)(?)]+(4) (16)(6) /JO(!., [( -.. e.-r!)C /,:He & )( ,,;/A )] Setvoint:;:: Sx ...:..(-"'-Wfe-~--'---.--'-J('----)(--=-_;__-,v_/;4-__ ...:..) + ( /5"3 ,"i,'I ) S t . t 51P1, s< a .~ e poin = .; 6,, 1 ?J-z.-.q~h Fractional Change= New value -Previous Value= ( 11 )-( 9) = ( *~) -( !.,I'-/ ) Previous Value ( 9 ) ( h / l/ ) Fractional Change= -0* o, If fractional change is greater than +/-0.3, adopt a new monitor alarm setting. Continuous Monitor Hi Alarm = Setpoint Monitor Hi Alarm = (.p I Radwaste Monitor Hi Alarm= .'16 (11) = .16 ( ) = --'--M-~ __ cps 33 N~E-323-C A LC-004 Att ac h men t 2 ALARM SETPOINTS FOR LIQUID RAD MONITORS PCP 8.7 Rev. 17 Page 9 of 11 Pa g e 3 of 3 ATTACHMENT 1 Page 1 of 3 LIQUID EFFLUENT RADIOACTIVITY MONITOR SETPOINT 1. Sample No. I 4--~ 4-2. Sample Date & Time 2.-\4-\4-{..::io <-J 3. Stream/MonitorDescr i ption 1L~Cl...Sw/f-5W Rv..~Tl.4.ct..L: Q.\1\1\ 4"2..lo'o

4. Effluent Monitor Reading (cps)
  • o . 5. Effluent Flow (gpm) 12\_\fZ...S..J

'A'~ Az..'OO'lr=:= 1 '~-4*x)v i::-~

  • 6. Average effluent flow during time represented by sample, F 1 (gpm) N JA--V:: 7. Average dilution (discharge canal) flow during time represented by sample , F 2 (gpm) ,.} jw-8. Monitor calibrat i on factor, g, ( cps/µCi/mL)

__ '--==-v-Z:c..8._f..._<.p __ v--'-, ----------

9. Previous alarm value setpoint (cps) ____ e_~_* _~ ___ v ___________ _ 10. Fraction to apply as a safety margin, A = 0.5 S . [ 'i1K, * *.. F2 * ] etpoint = 10 x . .xg x -x A +Bkg = 'i.1 (K 1 .,. WECi) F; Setpoint==l o x[(l S)(S)(?) x (l O)] +( 4) (16)(6) Setpoint = sx[(l S)(S)(7)] + ( 4) (16)(6) "' [ ;7, &7 l-7::, 2,.2." 1 )( µ /,4-) ] Setpoint = 5 x ( )( ) + ( < t I I , 8 <o >< /VI ;4 ) ~OS v 11. Setpoint=

______ _ Fractional Change = New value -Previous Value = ( 11 ) -{ 9 ) = ( ~o7) -( 'b\,:,*~ ) Previous Value ( 9 ) ( iot.-/7 ) 12. Fractional Change= *-o, 0*7 / If fractional change is greater than +/-0.3, adopt a new monitor alarm setting., Continuous Monitor Hi Alarm = Setpoint *==t:>oLb, Si 1: c;t,... ..... '""T v" 13. Monitor Hi Alarm = 14. RadwasteMonitorHiAlarm=.16(11) = .16( ,..,jA-) = ,J /A--cps}}

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