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{{Adams
#REDIRECT [[CP-201700255, Comanche Peak, Units 1 and 2, Transmittal of Year 2016 Radioactive Effluent Release Report]]
| number = ML17124A376
| issue date = 04/27/2017
| title = Comanche Peak, Units 1 and 2, Transmittal of Year 2016 Radioactive Effluent Release Report
| author name = McCool T P
| author affiliation = Luminant Power, TXU Energy, Vistra Operations Company, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000445, 05000446
| license number =
| contact person =
| case reference number = CP-201700255, TXX-17043
| document type = Environmental Monitoring Report, Letter
| page count = 61
}}
 
=Text=
{{#Wiki_filter:CP-201700255 TXX-17043 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 4/27/2017 ENERGY I 'f* energy Luminant
 
==SUBJECT:==
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 Thomas P. McCool Site Vice President Luminant P.O. Box 1002 6322 North FM 56 Glen Rose, TX 76043 0 254.897.6042 m 817.776.0308 Ref 10 CFR 50.36a Tech Spec 5.6.3 TRANSMITIAL OF YEAR 2016 RADIOACTIVE EFLUENT RELEASE REPORT
 
==Dear Sir or Madam:==
In accordance with Comanche Peak Nuclear Power Plant 1 Units1 and 2 Technical Specifications (TS) 5.6.3 and Section 6.9.1.4 of the Comanche Peak Offsite Dose Calculation Manual (ODCM), enclosed is the Radioactive Effluent Release Report which covers the reporting period from January 1, 2016 through December 31, 2016. The tabular summaries of radioactive liquid and gaseous releases are provided in the format defined in Appendix B of Regulatory Guide 1.21, Rev. 1, dated June, 1974. During this reporting period there were no revisions to the ODCM. If there are any questions regarding this report, please contact Steve Dixon at (254) 897-5482 or Kerry Cooper at (254) 897-0462.
1 TEX Operations Company LLC and Comanche Peak Company LLC are the current NRC licensees.
On December 14, 2016, License Amendment Request 16-003 (ML16351A200) submitted an administrative change to change the licensee name "TEX Operations Company LLC" to "Vistra Operations Company LLC". 1601 BRYAN STREET DALLAS, TEXAS 75201 0 214-812-4600 VISTRAENERGY.COM 
-, TXX-17043 Page 2 of 2 Sincerely, Th:#-6 Enclosure
: 1. Comanche Peak 2016 Radioactive Effluent Release Report c -K. M. Kennedy, Region IV M. Watford, NRR Resident Inspectors, Comanche Peak Enclosure 1 Comanche Peak 2016 Radioactive Effluent Release Report 
 
CPNPP_)
* _ <_ l . . . ; _. . : .. * . * . . . : . ; Prepared By: * ... f, ,._. 1 ,.. ... .. "' .'l< ** "' ' 2016 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2016 -December 31, 2016 Donald Rebstock Reviewed By: David Valentine Date: 4/23/17 Date: 4/23/17 Date: 4/23/ 17 Approved By (Print/Signature):
___ _ Pa e 1 of 58 TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS
 
==1.0 INTRODUCTION==
 
1.1 Executive Summary 1.2 Historical Trend Graphs 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Measurements and Approximations of Total Radioactivity 2.4 Batch Releases 2.5 Abnormal or Unplanned Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 RADIOLOGICAL IMPACT ON MAN 6.1 Dose Due to Liquid Effluents 6.2 Dose Due to Gaseous Effluents 6.3 Dose Due to Radioiodines, Tritium, and Particulates 6.4 40CFR190 Dose Evaluation 6.5 Dose to a MEMBER OF THE PUBLIC from Activities inside the Site Boundary 7.0 METEROLOGICALDATA 7.1 Meteorological Monitoring Program 8.0 RELATED INFORMATION 8 .1 Operability of Liquid and Gaseous Monitoring Instrumentation 8.2 Changes to the Offsite Dose Calculation Manual Page 2 of 58 TABLE OF CONTENTS 8.3 New Locations for Dose Calculations or Environmental Monitoring 8.4 Liquid Holdup and Gas Storage Tanks 8.5 Noncompliance with Radiological Effluent Control Requirements 8.6 Resin Releases to the LVW Pond 8.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems 8.8 Groundwater Tritium Monitoring Program 9.0 TABLES 9 .1 Liquid and Gaseous Batch Release Summary 9 .2 Abnormal Batch Liquid and Gaseous Release Summary 9.3 Gaseous Effluents-Summation of All Releases 9 .4 Gaseous Effluents-Ground Level Releases 9 .5 Liquid Effluents Summation of All Releases 9.6 Liquid Effluents
: 9. 7 Dose to a member of the public due to Liquid Releases 9.8 Dose Due to Gaseous Releases 9.9 Dose to a Member of the Public Due to Radioiodines, Particulates, Tritium, and C-14 in Gaseous Releases 9 .10 Solid Waste and Irradiated Fuel Shipments 10.0 ATTACHMENTS 10.1 Meteorological Joint Frequency Distribution Tables 10.2 Atmospheric Dispersion (X/Q) and Deposition (D/Q) Calculation Methodology Discussion 10.3 Carbon 14 Supplemental Information Page 3 of 58 CFR CPNPP ECL IFS FI LDCR LHMT LVW ODCM PET pCi REC SORC uCi WMT WWHT ACRONYMS AND ABBREVIATIONS Code of Federal Regulations Comanche Peak Nuclear Power Plant Effluent Concentration Limit Independent Spent Fuel Storage Installation Licensing Document Change Request Laundry Holdup and Monitor Tanks Low Volume Waste Offsite Dose Calculation Manual Primary Effluent Tanks Pico-Curie Radiological Effluent Control Station Operations Review Committee Micro-Curie Waste Monitor Tanks Waste Water Holdup Tanks Page 4 of 58 1.0 Introduction This Radioactive Effluent Release Report, for Comanche Peak Nuclear Power Plant (CPNPP) Unit 1 and Unit 2, is submitted as required by Technical Specification 5.6.3 and Offsite Dose Calculation Manual (ODCM) Administrative Control 6.9.1.4 for the period January 1, 2016, through December 31, 2016. Data in this report were calculated in accordance with the CPNPP ODCM using the Canberra OpenEMS software.
1.1 Executive Summary The radioactive effluent monitoring program for 2016 was conducted as described in the following report. Results of the monitoring program indicate continued effort to maintain the release of radioactive effluents to the environment as low as reasonably achievable (ALARA). In June 2009, the NRC provided revised guidance in Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 2, establishing an updated approach for identifying principal radionuclides.
Because the overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations, Carbon-14 (C-14) now qualifies as a "principal radionuclide" (anything greater than one percent of overall radioactivity in effluents) under federal regulations at many plants. In other words, C-14 has not increased and C-14 is not a new nuclear plant emission.
Rather, improvements in the mitigation of other isotopes have made C-14 more prominent.
Attachment 10.3 provides more detail about C-14. Page 5 of 58 1.1 Executive Summary (continued)
Gaseous Effluents:
Two year summary of all the radioactive gaseous releases to the environment:
Gaseous Waste 2015 2016 Comments Tritium (Ci) 38.2 35.3 1 C-14 (Ci) 25.3 25.9 2 Total Fission and Activation Products (Ci) 0.55 0.43 Total Particulate (Ci) 0 0 3 Gross Alpha (Ci) 0 0 3 Iodine (Ci) 0 0 3 Calculated Gamma Air Dose (mRad) 3.71E-04 3.72E-04 Calculated Beta Air Dose (mRad) 1.62E-04 1.41E-04 Total Body Dose (mRem) 0.10 0.10 Comments:
: 1. The major contributor to gaseous tritium activity is evaporation from the spent fuel pools. Factors contributing to the tritium activity in the pools are related to the type of fuel used (i.e., 18-month fuel) the core life, power output, and number of core cycles. The small decrease from 2015 to 2016 is within the historical statistical variation.
: 2. C-14 activity released from the site is estimated using reactor power in accordance with EPRI document "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents".
: 3. No particulate, Iodine, or alpha activity was released.
Overall the gaseous radioactivity releases from CPNPP are well controlled and maintained ALARA. CPNPP is well below all applicable limits for gaseous releases.
Neither unit had fuel defects during the year of this report. Page 6 of 58 1.1 Executive Summary (continued)
Liquid Effluents:
Two year summary of all the radioactive liquid releases to the environment:
Liquid Waste 2015 2016 Comments Total Activity Excluding Tritium (Ci) l.83E-03 l.92E-03 Tritium Activity (Ci) 1950 1390 1 Total Body Dose (mRem) 0.19 0.16 Total Volume Released (Gallons) 665,178 678,996 Comments:
: 1. Tritium released values can vary significantly from year to year based on a couple of factors. First, reactor coolant tritium production changes based on fuel bumup characteristics.
Tritium activity increases following reactor startup, then plateaus mid-cycle, and begins to decline towards the end of cycle. Second, the tritium released value is dependent upon on how many outages there were during a calendar year. More liquid waste is processed and released during unit outages. Meteorological Data During 2016, the CPNPP meteorological system achieved a greater than 97% mean recoverable data rate for the joint frequency parameters required by Regulatory Guide 1.23 for wind speed, wind direction and delta temperature.
See section 7 .1 for the actual recovery percentages.
Monitors OOS > 30 Days During 2016, there were no Technical Specification/ODCM effluent radiation monitors out of service for> 30 days. ODCM Changes No changes were made to the ODCM during 2016. Page 7 of 58 1.1 Executive Summary (continued)
Solid Waste Two year summary of the solid waste production:
Total Waste 2015 2016 % Error Shipped (mj) 316 261 25% Shipped (Ci) 52.1 45.6 25% Buried (mj) 44.5 30.0 25% Buried (Ci) 52.1 45.6 25% Comments:
Solid waste shipments and burials have generally trended downward over the past 5 years due to solid waste reduction measures.
2016 was a single outage year which led to less solid waste shipped and buried, consistent with single outage years. Page 8 of 58 Groundwater Tritium Sentinel Well location CP-A near the Water Plant and Monitor Well 11 (which is directly down gradient from CP-A) continued showing intermittent positive results for tritium. The positive results were from a leak in the filtered water storage tank (FWST) and from a leak in piping from the Low Volume Waste (L VW) Pond to the Water Treatment Waste Sump. The FWST leak was repaired mid-2016 and the L VW leak was repaired in January of 2017. See section 8.8 for details. Conclusion During 2016, the radioactive effluent monitoring program has been conducted in an appropriate manner to ensure the activity released and associated dose to the public has been maintained as low as reasonably achievable (ALARA). Page 9 of 58 1.2 Historical Trend Graphs Total Gaseous Fission and Activation Activity Released 10 9 8 7 &#xa3; <.) 6 c: 0 0 (/) 5 ::J 0 Cl> (/) cu 4 3.89 ---C) --* {:!. 3 1.27 0.88 1 -0.55 n 0.49 0.43 0 11 11 II 2010 2011 2012 2013 2014 2015 2016 Year Year Total Gaseous Fission and Activation Activi Released Comments 2010 Higher gas activity released from the site due to fuel leaks occurring between 2004 and 2008. 2011 Higher gas activity released from the site due to fuel leaks occurring between 2004 and 2008. Another fuel leak occurred in 2011. 2012 Lower as activity released from the site due to recovery from revious fuel leaks. Page 10 of 58 Total Gaseous Tritium Released 100 90 80 70 -Q_ cj 60 c 0 51.6 0 AA 1 -(") 5 0 ::c -(/) 43.2 :::J -""" 0 40 -35.8 Q) -35.3 (/) --ell (!) 30.1 30 --20 --10 --0 2010 2011 2012 2013 2014 2015 2016 Year Year Total Gaseous Tritium Released Comments NIA The major contributor to gaseous tritium activity is evaporation from the spent fuel pools. Factors contributing to the tritium activity in the pools is related to the type of fuel used (i.e., 18-month fuel) the core life, power output , and number of core cycles. Page 11 of 58 Tota l Body Dose due to Gaseo u s Act i v i ty Released 0.2 0.18 0.16 0.1 4 'E 0.1 2 0.11 0.11 Q) --a:: 0.10 0.10 .&sect;. 0.1 -n *n U.Ul:I U.Ul:I -Q) --UI 0 0 0.08 --0.0 6 --0.04 --0.0 2 --0 2 010 2011 201 2 2 013 2014 2 015 2 016 Year Total Bod y Do s e due to Gaseous A ctivity Rel e a se d Comment s Year 2 010 D es p i te t h e inclu s io n of C-14 , tot al who l e bod y do se i s very low (0. 71 % of T ec hni cal Sp ecifica t io n). 2 01 2 Th e r e was a mid-cycle out age dur ing 2 01 2 th at re quir ed d egassi n g o f th e R CS in additio n to a pl a nn e d re fu e ling out age r es ulting i n s li g htl y h ig h e r tot al b o d y do se for 2 01 2. Page 12 of 58 100 , 000,000 10,000 , 000 1 , 000 , 000 100,000 iii Q. Q) 10 , 000 E ::J ;g 1,000 100 10 Year 2010 2012 Total Volume Liquid Effluents Released 28,005,284 18,733,509
---1,155,673 "n7 oo" 929,987 "470 "7R nn" ------2010 2011 2012 -2013 Year 2014 2015 Total Body Dose due to Gaseous Activity Released Comments ->---------2016 CPNPP processes many millions of gallons of non-radioactive water each year from th e secondary portion of the plant. Water plant waste , turbine building sumps and other source s all contribute to these total s. This waste water is processed through the low volume waste (L VW) system which then discharged to Squaw Creek Reservoir.
A monthly composite sample of from the L VW is analyzed quarterly for activity.
Normally, this waste water does not contain any radionuclides.
Howe v er , in late 2009 , the refueling water storage tank (RWST) overflowed into th e turbine building sumps. Initially this water was diverted to the waste processing system. Once th e cleanup was complete, the turbine building sump was directed back to the LVW system. A small amount of tritium remained in the turbine building sumps and was sent to the L VW. The first quarter L VW composite sample tested positive for tritium (a small amount above background). Consequently , the volume discharged from the L VW had to be accounted for as liquid waste. Because the L VW sample is a quarterly composite , the volume processed as liquid waste for the first quarter (and for the year) is 20 times larger than normal. Analysis of the 2nd quarter L VW composite indicated a small concentration of tritium. Consequently , the volume discharged from the L VW had to be accounted for as radioactive liquid waste for that quarter resulting in a much larger than normal total annual liquid waste volume. Page 13 of 58 30 25 20 0 E 15 > :;::::; 0 10 0 Y ear 2 010 2 01 2 16.40 -2010 T ot al Activity (Exc lu ding Tritium) R e leased i n Liquid Effluents 13.80 -6.56 2 011 2 01 2 3.47 n 2013 Year 1.83 0.86 II r---i 2014 2015 Total Acti v ity (E x cludine; H3) Released in Liouid Effluents Comment s 1.92 n 2 016 Th e i ncrease in a c ti v i ty in 2 0 1 0 was du e t o iss u es w it h the liquid waste pro cessing e quipm ent fr om M arch to Jun e. Cha n ge s in me d ia and p rocess in g m e t ho dolo gy so l ve d th e probl em and r estored p rocess i ng ef fici e n cy. D es p i t e thi s, t o tal liquid was t e re l ease d in 2010 was ve ry lo w. Th e i ncrease d a cti v i ty fo r 2 01 2 is a ttribut ed t o was t e water pro cess in g for 1 re fu eling o ut age, 1 for c e d out age , a nd d ry ca s k st ora ge o p era t i on s. Page 14 o f 58 Total Curies of Tritium Released in Liquid Effluents 0 -: 3000+------------------------------------------<
u 2790 c 0 0 ('I) ::i::: "C 2430 2080 ::I 2000 +---------! C" 1950 :::i 1000 Year All 1340 -2010 2011 2012 919 2013 Year 2014 2015 Total Curies of Tritium Released in Liquid Effluents Comments 1390 -2 016 Tritium released values can vary significantly from year to year based on a couple of factors. First, reactor coolant tritium production changes based on fuel burnup characteristics. Tritium activity increases following reactor startup, then plateaus cycle, and begins to decline towards the end of cycle. Second, the tritium released value is dependent upon on how many outages there were during a calendar year. More liquid waste is processed and released during unit outages. Page 15 of 58 0.4 0.35 0.3 0.2 5 'E Q) 0:: .s 0.2 Q) fl) 0 Cl 0.15 0.1 -0.05 -0 Year N I A 0.15 2010 Tota l Body Dose Due to Liqu i d Effluents Released 0.17 -0.15 2011 2012 0.17 -2013 Year 0.18 -2014 n *n -2 0 15 Total Bod Dose Due to Li uid Effluents Released Comments No comm e nts Page 16 of 58 0.16 ----2016 700 600 500 400 Ill Q) -.::: ::I 0 300 200 100 0 Year 2013 2014 18.9 II 0.1 2010 2011 Total Curies of Solid Radwaste Buried 3.0 2012 235.0 -2013 Year 608.0 -2014 Total Curies of Solid Radwaste Buried Comments 52.1 45.6 n n 2015 2016 In 2013 CPNPP shipped and buried significantly more Class Band C waste to the compact disposal facility in Andrews, Texas. This waste has a very high specific activity with respect to Class A waste. In 2012 , CPNPP only disposed of Class A waste and consequently the activity was very low with respect to 2013 values. The buried volume in both years are similar since Class Band C wastes are in packages of 120 cubic feet , or about 3 cubic meters , and consequently , the impact on the overall waste volume is minimal. In 2014 CPNPP continued to ship and bury stored Class B and Class C wastes at the compact disposal facility in Andrews , Texas. In advance of the compliance date for 10 CFR 37, waste containers with the highest radioactivity, particularly those exceeding category two quantities , were chosen to be shipped. In 2013 , CPNPP had just began shipments to the new Andrews, Texas disposal facility and the waste containers chos e n for shipment represented lower total activity to allow the staff to become familiar with the new procedure processes required by the new facility.
Buried volume in both years are similar since these values are normally associated with Class A Dry Active Waste that represents an order of magnitude more volume than Class B and Class C wastes packaged in 120 cubic feet, or about 3 cubic meter , containers.
Page 17 of 58 100 90 80 70 60 >----I/) ... 2 Q) 50 :::!!: -u :c ::I 40 0 20 0 Year 2013 2014 2016 71 66 -2010 2011 Total Volume of Solid Radwaste Buried *-2012 49 -2013 Year 39 -2014 45 -2015 Total Body Dose Due to Liquid Effluents Released Comments 30 --2016 In 2013 CPNPP shipped and buried significantly more Class B and C waste to the compact disposal facility in Andrews, Texas. This waste has a very high specific activity with respect to Class A waste. In 2012, CPNPP only disposed of Class A waste and consequently the activity was very low with respect to 2013 values. The buried volume in both years are similar since Class B and C wastes are in packages of 120 cubic feet, or about 3 cubic meters, and consequently, the impact on the overall waste volume is minimal. In 2014 CPNPP continued to ship and bury stored Class B and Class C wastes at the compact disposal facility in Andrews, Texas. In advance of the compliance date for 10 CFR 37 , waste containers with the highest radioactivity , particularly those exceeding category two quantities, were chosen to be shipped. In 2013, CPNPP had just began shipments to the new Andrews, Texas disposal facility and the waste containers chosen for shipment represented lower total activity to allow the staff to become familiar with the new procedure processes required by the new facility.
Buried volume in both years are similar since these values are normally associated with Class A Dry Active Waste that represents an order of magnitude more volume than Class B and Class C wastes packaged in 120 cubic feet, or about 3 cubic meter, containers.
Solid waste shipments and burials have generally trended downward over the past 5 years due to solid waste reduction measures.
Also, 2016 was a single outage year which led to less solid waste shipped and buried when compared to 2015. Page 18 of 58 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
2.1.1 Fission and Activation Gases (Noble Gases) 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 less than or equal to 500 mRem/yr to the whole body and less than or equal to 3000 mRem/yr to the skin. The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
: a. During any calendar quarter: Less than or equal to 5 mRad for gamma radiation and less than or equal to 10 mRad for beta radiation, and b. During any calendar year: Less than or equal to 10 mRad for gamma radiation and less than or equal to 20 mRad for beta radiation.
2.1.2 Iodine-131, Iodine-133, Tritium and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mRem/yr to any organ. The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:
: a. During any calendar quarter: Less than or equal to 7.5 mRem to any organ, and b. During any calendar year: Less than or equal to 15 mRem to any organ. Page 19 of 58 2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 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. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 &#xb5;Ci/ml total activity.
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited: a. During any calendar quarter to less than or equal to 1.5 mRem to the whole body and to less than or equal to 5 mRem to any organ, and b. During any calendar year to less than or equal to 3 mRem to the whole body and to less than or equal to 10 mRem to any organ. 2.1.4 L VW Pond Resin Inventory The quantity of radioactive material contained in resins transferred to the L VW pond shall be limited by the following expression:
(264N)
* Lj A/Cj < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day halflife, where: Aj =pond inventory limit for a single radionuclide j (Curies), Cj = 1 OCFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (&#xb5;Ci/mL), V = volume of resins in the pond (gallons), and 264 =conversion factor (&#xb5;Ci/Ci per mL/gal) This expression limits the total quantity of radioactive materials in resins discharged to the L VW Pond to a value such that the average concentration in the resins, calculated over the total volume of resins in the pond, will not exceed one times the Effluent Concentration Limits specified in 10 CFR 20, Appendix B, Table 2, Column 2. 2.1.5 Total Dose 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 less than or equal to 25 mRem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 7 5 mRem. Page 20 of 58 2.2 Effluent Concentration Limits 2.2.1 Gaseous Effluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.
2.2.2 Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 &#xb5;Ci/mL is used as the ECL for dissolved and entrained noble gases in liquid effluents.
2.3 Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-1 and 4.11-2, respectively, of the CPNPP ODCM. 2.3.1 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy.
Composite samples were analyzed monthly and quarterly for the Primary Effluent Tanks (PET), Waste Monitor Tanks (WMT), Laundry Holdup and Monitor Tanks (LHMT) and Waste Water Holdup Tanks (WWHT). Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation and gas flow proportional counting techniques, respectively.
Composite samples were analyzed quarterly for Sr-89, Sr-90, Fe-55, and Ni-63 by a contract laboratory.
The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.
For batch releases of powdex resin to the LVW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques.
Composite samples were analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory.
For continuous releases to the Circulating Water Discharge from the LVW pond, daily grab samples were obtained over the period of pond discharge.
These samples were composited and analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques.
Composite samples were also analyzed for tritium and gross alpha radioactivity using liquid scintillation and gas flow proportional counting techniques respectively.
Composite samples were analyzed quarterly for Sr-89, Sr-90, Fe-55, and Ni-63 by a contract laboratory.
Page 21 of 58 2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. Waste Gas Decay Tank samples were analyzed for gamma emitting radionuclides.
Containment Building charcoal (iodine), particulate, noble gas, and tritium grab samples were also analyzed for radioactivity prior to each release. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode. For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly. Samples were analyzed for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques.
Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for I-131 and gamma emitting radionuclides using gamma spectroscopy.
Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross alpha activity, in the onsite laboratory using the gas flow proportional counting technique.
Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by a contract laboratory.
C-14 was estimated in accordance with the methodology in the EPRI report Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents.
EPRI, Palo Alto, CA: 2010, 1021106. See attachment 10.3 on page 50 for more information on C-14. 2.4 Batch Releases A summary of information for liquid and gaseous batch releases is included in Table 9.1. 2.5 Abnormal or Unplanned Releases Abnormal or unplanned radioactive releases are defined as the unintended discharge of a volume of liquid or airborne radioactivity to the environment.
There were no abnormal or unplanned liquid or gaseous radioactive effluent releases during 2016. 3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 9.3 and 9.4. All releases of radioactive material in gaseous form are considered to be ground level releases.
4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 9.5 and 9.6. 5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Table 9.10. Page 22 of 58 6.0 RADIOLOGICAL IMPACT ON MAN 6.1 Dose Due to Liquid Effluents The dose to an adult from the fish and cow-meat consumption pathways from Squaw Creek Reservoir were calculated in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in table 9.7. 6.2 Dose Due to Gaseous Effluents The air dose due to gamma emissions and the air dose due to beta emissions were calculated using the highest annual average atmospheric dispersion factor at the Site Boundary location, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 9.8. 6.3 Dose Due to Radioiodines, Tritium and Particulates The dose to an adult, teen, child, and infant from radio-iodines and particulates, for the pathways listed in Part II, Table 2.4 of the ODCM, were calculated using the highest dispersion and deposition factors, as appropriate, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 9.9. Because of pathway similarity, C-14 dose is included in this table. 6.4 40CFR190 Dose Evaluation ODCM Radiological Effluent Control 3.11.4 requires dose evaluations to demonstrate compliance with 40 CFR Part 190 only if the calculated quarterly or yearly dose exceed two times the applicable quarterly or annual dose limits. At no time during 2016 were any of these limits exceeded; therefore no evaluations are required.
Page 23 of 58 6.5 Dose to a MEMBER OF THE PUBLIC from Activities Inside the Site Boundary Dose to a MEMBER OF THE PUBLIC from activities inside the site boundary was evaluated.
The highest dose resulted from recreational fishing on Squaw Creek Reservoir.
A dose of 3 .23E-03 mRem/yr was calculated based on an individual fishing twice a week, five hours each day, six months per year. Pathways included in the calculation were gaseous inhalation and submersion.
Liquid pathways are not considered since all doses are calculated at the point of circulation water discharge into the reservoir.
This calculation was performed m accordance with the methodology and parameters in the ODCM. Page 24 of 58 7.0 METEROLOGICAL DATA 7.1 Meteorological Monitoring Program In accordance with ODCM Administrative Control 6.9 .1.4, a summary of hourly meteorological data, collected during 2016 is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment
: 10. During the year of this report, the goal of> 90% joint data recovery was met. The individual percent recoveries are listed below: Meteorolo2ical Data Recovery Channel % Recovery 10 m Wind Speed 97 .5 10 m Wind Direction 99.6 Delta Temperature A 97.5 Delta Temperature B 97.4 8.0 RELATED INFORMATION 8.1 Operability of Liquid and Gaseous Monitoring Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 require an explanation of why designated inoperable liquid and gaseous monitoring instrumentation was not restored to operable status within thirty days. During 2016, there were no instances where these instruments were inoperable for more than thirty days. 8.2 Changes to the Offsite Dose Calculation Manual (ODCM) There were no changes to the ODCM during 2016. 8.3 New Locations for Dose Calculations or Environmental Monitoring ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations and/or environmental monitoring, identified by the Land Use Census, to be included in the Radioactive Effluent Release Report. Based on the 2016 Land Use Census, no new receptor locations were identified which resulted in changes requiring a revision in current environmental sample locations.
Values for the current nearest resident, milk animal, garden, X/Q and D/Q values in all sectors surrounding CPNPP were included in the 2016 Land Use Census. 8.4 Liquid Holdup and Gas Storage Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading to liquid holdup or gas storage tanks exceeding the limits required to be established by Technical Specification 5.5.12. Technical Requirements Manual 13.10.33 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten curies, excluding tritium and dissolved or entrained noble gases. Technical Requirements Manual 13.10.32 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 curies of noble gases (considered as Xe-133 equivalent).
These limits were not exceeded during the period covered by this report. Page 25 of 58 8.5 Noncompliance with Radiological Effluent Control Requirements This section provides a listing and description of Abnormal Releases, issues that did not comply with the applicable requirements of the Radiological Effluents Controls given in Part I of the CPNPP ODCM and/or issues that did not comply with associated Administrative Controls and that failed to meet CPNPP expectations regarding Station Radioactive Effluent Controls.
Detailed documentation concerning evaluations of these events and corrective actions is maintained onsite. 8.5.1 Abnormal, Unplanned Gaseous Effluent Release No abnormal, unplanned gaseous effluent releases occurred during 2016. 8.5.2 Abnormal, Unplanned Liquid Effluent Releases No abnormal, unplanned liquid effluent releases occurred during 2016. Page 26 of 58 8.6 Resin Releases to the L VW Pond A total of 92 ft 3 of powdex resin was transferred to the L VW pond during 2016. The cumulative activity deposited in the LVW pond since operations began through the end of 2016 is 2.00e-3 Curies, consisting ofCo-58, Co-60, Cs-134, Cs-137, I-131, Sr-90 and Sb-125. 8.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems In accordance with the CPNPP Process Control Program, Section 6.2.6.2, changes to the Radwaste Treatment Systems (liquid, gaseous and solid) should be summarized and reported to the Commission in the Radioactive Effluent Release Report if the changes implemented required a 10CFR50.59 safety evaluation.
During 2016, no changes to the Rad waste Treatment Systems occurred meeting the reporting criteria of the Process Control Program. 8.8 Groundwater Tritium Monitoring Program The wells used to monitor CPNPP for tritium leaks into the ground water all had results that were less than detectable with the exception of sentinel well CP-A and MW-11 near the Water Treatment Plant. CR-2016-001459 and CR-2016-008692 documents these issues. CR-2016-001459 documents positive indications in Sentinel Groundwater Well 11 and the gradient Well CP-A is likely from percolation originating from the Filtered Water Storage Tank (FWST) X-02 leak, which contains treated Squaw Creek Reservoir (SCR) water. Because SCR water always contains low background concentrations of tritium, SCR water used in the plant will contain similar concentrations.
CP-A again had positive results for samples taken on 9/27/16 and 12/14/16.
CR-2016-008692 documents a leak in a line from the Low Volume Waste (LVW) Pond to the Water Treatment Waste Sump. Water Treatment water is produced using from SCR water and therefore contains tritium. All of these sample results were well below the state drinking water reportable criteria of 20,000 pCi/L and the environmental reportable criteria of 30,000 pCi/L. The FWST leak was repaired in mid-2016 and the monitor well results both returned to less than detectable.
The LVW line was repaired in January 2017. It is expected that the CP-A concentration will continue to decrease.
Other areas also monitored, but not considered part of the ground monitoring program include the seepage sump, and Leachate Basins A, B, and C. These sample points are actually of perched (surface) water and not indicative of ground water tritium. Previous hydro geology studies performed by Pastor, Behling and Wheeler LLC, showed that this perched water sits above an impermeable layer of bedrock. This prevents the migration of the tritiated perched water into the Twin Mountain Aquifer and a potential new pathway to drinking water sources but is re-routed back to SCR. Groundwater monitoring wells below the perched layer have not identified any tritium above the MDA and confirm the claims of the hydrogeology study. Based on this information and the guidance in NEI 07-07, there is no requirement for notification to the NRC or local officials and Page 27 of 58 no requirement for remediation as it is not considered licensed material.
Continued monitoring of these perched water sample points will occur as part of the Groundwater Monitoring Program (STA-654) and any new sources of tritium or increase in the activity will be evaluated and remediated as necessary.
Page 28 of 58 Ground Water Tritium Results (pCi/L) MW 03/25/15 06/24/15 9/22/15 11/18/15 3/24/2016 6/9/2016 9/27/2016 12/14/2016 Location 9 <665 <661 <638 <630 <597
<693 <664 <744 10 <665 <661 <638 <630 <597 <693
<664 <744 11 <665 3410(l) 2270(l) 2270(l) 1450(2) <693 <664 <744 12 <665 <661 <638 <630 <597
<693 <664 <744 14 <665 <661 <638 <630 <597
<693 <664 <744 15 DRY DRY DRY DRY DRY <693 DRY DRY 16 <665 <661 <638 <630 <597 <693
<664 <744 19 <665 <661 <638 <630 <597 <693
<664 <744 25 <665 <661 <638 <630 <597 <693
<664 <744 CP-A <665 <661 1300(l) 3250(l) 5940(l) <693 3190(2) 2100(2) CP-B <665 <661 <638 <630 <597 <693
<664 <744 CP-C <665 <661 <638 <630
<597 <693 <664 <744 (1) CR-2016-001459; SCR water leakage via Water Treatment Plant's FWST. (2) CR-2016-008692; Leak in the line from Low Volume Waste pond line to the Water Treatment Waste Sump. Page 29 of 58 Ground W ater Tritium M onitorin -==--=-==*=====:::.-:=:-
.::..-:.-=::_-:_--::--...
.....
--Pa e 30 of 58 """'' EXPLANATI O N e Mon i.mng w .. Loeaion Glen Rose Formrian) Q MoniloringWel l ocarim (Unwut t wred GIB\ Rose Fcnna:ion) .pu.6Ji W>ftf" left! Elenim (Ft "5l) (NM*NotMo......i) 79<J-G<oundw>lt<S.-C.......
(A MSL) Con'1>!1 lnterv31z 10 F t 1. Web Nos_ tO. 15. UI , CP..A. CP-8 * .md CP-C were not uRd 1D OOft5UVCl po1entiom<<tric surboe conlDUB for this figur. lhtse not to t.-in hydl'ilufic conMCtion with !he oflfi wens_ 2 bas<<! hydraU ic gradient at ltw Sillt. ;and thus con<<us l'NIY not bf: en consistent with !he individual eleovoltio1"150ll
.111..,..s. N I Scale in Fee.I 125 ""' S auret: C ruttd tom TXU SecticCPSES S* SGM-01. LUMINANT -C P N PP f9n23 UNWEATHERED GLEN ROSE FORMATION
*GROUNDWATER ELEVATIONS
* AUB. 29, 2010 PROJECT: 1 78fi B r. A.JD REVISK>NS: PASTOR , BEHLIN G & WHE E L E R , LL C CONSU.. TING ENGINEERS ANO SCIENTISTS SECTION 9.0 EFFLUENT TABLES Page 31 of 58 Table 9.1 Liquid and Gaseous Batch Release Summary A. Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1. Number of batch releases 8 16 6 5 35 2. Total time period for Batch releases (Minutes) 2.70E+03 5.50E+03 2.13E+03 l.68E+03 l.20E+04 3. Maximum time period for a batch release (Minutes) 3.50E+02 4.10E+02 3.80E+02 3.46E+02 4.10E+02 4. Average time period for a batch release (Minutes) 3.37E+02 3.44E+02 3.55E+02 3.36E+02 3.43E+02
: 5. Minimum time period for a batch release (Minutes) 3.15E+02 2.90E+02 3.38E+02 3.19E+02 2.90E+02 B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1. Number of batch releases 27 28 25 28 108 2. Total time period for batch releases (Minutes) 1.16E+04 l.20E+04 8.13E+03 2.19E+04 5.36E+04 3. Maximum time period for a batch release (Minutes) l.85E+03 l.92E+03 3.68E+02 l.21E+04 l.21E+04 4. Average time period for a batch release (Minutes) 4.29E+02 4.29E+02 3.25E+02 7.81E+02 4.96E+02 5. Minimum time period for a batch release (Minutes) 3.16E+02 l.67E+02 l.59E+02 2.66E+02 l.59E+02 Page 32 of 58 Table 9.2 Abnormal Liquid and Gaseous Batch Release Summary A. Liquid Abnormal Release Totals Units Quarter 1 1. Number of abnormal releases 0 2. Total activity of abnormal releases Curies O.OOE+OO B. Gas Abnormal Release Totals Units Quarter 1 1. Number of abnormal releases 0 2. Total activity of abnormal releases Curies O.OOE+OO Page 33 of 58 Quarter 2 0 O.OOE+OO Quarter 2 0 O.OOE+OO Quarter 3 0 O.OOE+OO Quarter 3 0 O.OOE+OO Quarter4 0 O.OOE+OO Quarter 4 0 O.OOE+OO Totals 0 O.OOE+OO Totals 0 O.OOE+OO Table 9.3 Gaseous Effluents
-Summation of All Releases Type of Effluent Units Quarter Quarter Quarter Quarter Total 1 2 3 4 A. Fission And Activation Gases 1. Total Release Curies 9.98E-02 1.58E-01 7.62E-02 1.00E-01 4.34E-01 2. Average Release rate for period uCi/sec 1.27E-02 2.02E-02 9.59E-03 l.26E-02 1.38E-02 3. Percent of Applicable Limit % * * * *
* B. Radioiodines
: 1. Total Iodine-131 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Percent of Applicable Limit % * * * *
* C. Particulates
: 1. Particulates ( Half-Lives
> 8 Days ) Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Average Release rate for period O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Percent of Applicable Limit % * * * *
* D. Tritium 1. H3 Release Curies 7.23E+OO 9.59E+OO 1.07E+Ol 7.75E+OO 3.53E+Ol 2. Average Release rate for period uCi/sec 9.19E-01 1.22E+OO 1.34E+OO 9.75E-01 1.1 lE+OO 3. Percent of Applicable Limit % * * * *
* D. C-14 1. C14 Release Curies 6.71E+OO 5.57E+OO 6.80E+OO 6.80E+OO 2.59E+Ol 2. Average Release rate for period uCi/sec 8.53E-01 7.09E-01 8.52E-01 8.55E-01 8.17E-01 3. Percent of Applicable Limit % * * * *
* E. Gross Alpha 1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
* Applicable limits are expressed in terms of dose. Estimated Total Error For All Values Reported Is< 1.0% Page 34 of 58 Table 9.4 Gaseous Effluents
-Ground Level Releases Continuous Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium & C-14 H-3 Curies 6.98E+OO 9.SOE+OO 1.06E+Ol 7.61E+OO 3.47E+Ol C14 C-14 Curies 2.0lE+OO 1.67E+OO 2.04E+OO 2.04E+OO 7.77E+OO Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 35 of 58 Table 9.4 (cont} Gaseous Effluents
-Ground Level Releases Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter4 Total Fission Gases Ar-41 Curies 9.98E-02 l.07E-01 7.62E-02 9.83E-02 3.81E-01 Kr-85 Curies O.OOE+OO 3.88E-02 O.OOE+OO O.OOE+OO 3.88E-02 Xe-133m Curies O.OOE+OO 8.48E-05 O.OOE+OO O.OOE+OO 8.48E-05 Xe-133 Curies O.OOE+OO 9.65E-03 9.19E-06 l.78E-03 l.14E-02 Xe-135m Curies O.OOE+OO 2.91E-05 O.OOE+OO O.OOE+OO 2.91E-05 Xe-135 Curies O.OOE+OO 2.87E-03 O.OOE+OO O.OOE+OO 2.87E-03 Total For Period Curies 9.98E-02 1.58E-01 7.62E-02 1.00E-01 4.34E-01 Iodines No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Particulates No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies 2.51E-01 9.0IE-02 5.72E-02 l.38E-01 5.36E-01 Carbon 14 C-14 Curies 4.70 3.90 4.76 4.76 18.13 Gross Alpha No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
* Zeroes in this table indicate that no radioactivity was present at detectable levels. Page 36 of 58 Table 9.5 Liquid Effluents
-Summation Of All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual A. Fission And Activation Products 1. Total Release (not including tritium, gases, Curies 7.93E-04 9.62E-04 1.13E-04 5.45E-05 1.92E-03 alpha) 2. Average diluted concentration during period uCi/ml 9.98E-11 4.79E-11 1.SOE-11 8.74E-12 4.60E-11 3. Percent of Applicable Limit % * * * *
* B. Tritium 1. Total Release Curies 2.71E+02 7.59E+02 7.78E+Ol 2.78E+02 1.39E+03 2. Average diluted concentration during period uCi/ml 3.41E-05 3.78E-05 1.04E-05 4.47E-05 3.32E-05 3. Percent of Applicable Limit % * * * *
* C. Dissolved and Entrained Gases 1. Total Release Curies 2.82E-04 4.79E-04 O.OOE+OO 1.02E-05 7.72E-04 2. Average diluted concentration during period uCi/ml 3.56E-11 2.38E-l 1 O.OOE+OO 1.64E-12 1.85E-11 3. Percent of Applicable Limit % * * * *
* D: Gross Alpha Radioactivity
: 1. Total Release Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Average diluted concentration during period uCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E: Waste Vol Release (Pre-Dilution)
Liters 5.80E+05 1.17E+06 4.57E+05 3.61E+05 2.57E+06 F. Volume of Dilution Water Used Liters 7.94E+09 2.0lE+lO 7.51E+09 6.23E+09 4.18E+10
* Applicable limits are expressed in terms of dose. Estimated Total Error For All Values Reported Is< 1.0% Page 37 of 58 Table 9.6 Liquid Effluents Continuous Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Fission & Activation Products No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Tritium H-3 Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissolved And Entrained Gases No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Gross Alpha Radioactivity Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Fission & Activation Products Mn-54 Curies 4.80E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.80E-06 Fe-55 Curies 3.81E-04 6.72E-04 O.OOE+OO O.OOE+OO l.05E-03 Co-57 Curies O.OOE+OO O.OOE+OO 6.45E-07 O.OOE+OO 6.45E-07 Co-58 Curies 8.87E-05 2.76E-04 l.12E-04 4.78E-05 5.24E-04 Co-60 Curies 3.00E-05 l.42E-05 O.OOE+OO 6.66E-06 5.08E-05 Ni-63 Curies 2.83E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.83E-04 Nb-95 Curies 5.20E-06 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E-06 Total For Period Curies 7.93E-04 9.62E-04 l.13E-04 5.45E-05 l.92E-03 Tritium H-3 Curies 2.71E+02 7.59E+02 7.78E+Ol 2.78E+02 l.39E+03 Dissolved And Entrained Gases Kr-85 Curies 2.52E-04 2.SOE-04 O.OOE+OO O.OOE+OO 5.32E-04 Xe-133 Curies 3.07E-05 l.89E-04 O.OOE+OO l.02E-05 2.30E-04 Xe-138 Curies O.OOE+OO 1.0lE-05 O.OOE+OO O.OOE+OO l.OlE-05 Total For Period Curies 2.83E-04 4.79E-04 O.OOE+OO l.02E-05 7.72E-04 Gross Alpha Activity No Nuclides Found Curies O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicates that no radioactivity was present at detectable levels. Page 38 of 58 Organ Dose Bone Limit Percent of Limit Liver Limit Percent of Limit Total Body Limit Percent of Limit Thyroid Limit Percent of Limit Kidney Limit Percent of Limit Lung Limit Percent of Limit GI-Lli Limit Percent of Limit Table 9.7 Dose to a member of the public due to Liquid Releases Units mRem mRem % mRem mRem % mRem mRem % mRem mRem % mRem mRem % mRem mRem % mRem mRem % Quarter 1 5.36E-05 5 0.001 4.44E-02 5 0.887 4.44E-02 1.5 2.957 4.44E-02 5 0.887 4.44E-02 5 0.887 4.44E-02 5 0.887 4.44E-02 5 0.888 Quarter 2 l.97E-06 5 0 3.95E-02 5 0.791 3.95E-02 1.5 2.636 3.95E-02 5 0.791 3.95E-02 5 0.791 3.95E-02 5 0.791 3.95E-02 5 0.791 Page 39 of 58 Quarter 3 O.OOE+OO 5 0 3.75E-02 5 0.75 3.75E-02 1.5 2.5 3.75E-02 5 0.75 3.75E-02 5 0.75 3.75E-02 5 0.75 3.75E-02 5 0.75 Quarter 4 O.OOE+OO 5 0 3.42E-02 5 0.684 3.42E-02 1.5 2.281 3.42E-02 5 .0.684 3.42E-02 5 0.684 3.42E-02 5 0.684 3.42E-02 5 0.684 Annual 5.56E-05 10 0.001 1.56E-01 10 1.556 1.56E-01 3 5.187 1.56E-01 10 1.556 1.56E-01 10 1.556 1.56E-01 10 1.556 1.56E-01 10 1.556 Table 9.8 Air Dose Due To Gaseous Releases NG Dose Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gamma Air mRad 9.72E-05 1.05E-04 7.41E-05 9.57E-05 3.72E-04 Limit mRad 5 5 5 5 10 Percent of Limit % 0.002 0.002 0.001 0.002 0.004 Beta Air mRad 3.43E-05 4.65E-05 2.62E-05 3.39E-05 1.41E-04 Limit mRad 10 10 10 10 20 Percent of Limit % 0 0 0 0 0.001 NG Total Body mRem 9.24E-05 9.99E-05 7.05E-05 9. lOE-05 3.54E-04 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 0.001 0.001 0.001 0.001 0.002 NG Skin mRem l .35E-04 1.52E-04 1.03E-04 1.33E-04 5.23E-04 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 0.002 0.002 0.001 0.002 0.003 Page 40 of 58 Table 9.9 Dose to a Member of the Public Due to Radioiodines, Particulates, Tritium, and C-14 in Gaseous Releases Organ Dose Liver Limit Percent of Limit Total Body Limit Percent of Limit Thyroid Limit Percent of Limit Kidney Limit Percent of Limit Lung Limit Percent of Limit GI-Lli Limit Percent of Limit Bone Limit Percent of Limit Units mRem mRem % mRem mRem % mRem mRem % mRem mRem % mRem mRem % mRem mRem % mRem mRem % Quarter 1 2.22E-02 7.5 0.296 2.22E-02 7.5 0.296 2.22E-02 7.5 0.296 2.22E-02 7.5 0.296 2.22E-02 7.5 0.296 2.22E-02 7.5 0.296 6.25E-02 7.5 0.83 Quarter 2 2.35E-02 7.5 0.314 2.35E-02 7.5 0.314 2.35E-02 7.5 0.314 2.35E-02 7.5 0.314 2.35E-02 7.5 0.314 2.35E-02 7.5 0.314 5.19E-02 7.5 0.69 Page 41 of 58 Quarter 3 2.72E-02 7.5 0.363 2.72E-02 7.5 0.363 2.72E-02 7.5 0.363 2.72E-02 7.5 0.363 2.72E-02 7.5 0.363 2.72E-02 7.5 0.363 6.33E-02 7.5 0.84 Quarter 4 2.31E-02 7.5 0.309 2.31E-02 7.5 0.309 2.31E-02 7.5 0.309 2.31E-02 7.5 0.309 2.31E-02 7.5 0.309 2.31E-02 7.5 0.309 6.33E-02 7.5 0.84 Annual 9.60E-02 15 0.640 9.60E-02 15 0.640 9.60E-02 15 0.640 9.60E-02 15 0.640 9.60E-02 15 0.640 9.60E-02 15 0.640 2.41E-01 15 1.61 TABLE9.10 Solid Radwaste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) 1. Type of Waste Shipped Shipped Buried Buried m3 Ci m3 Ci a. Spent resins/filters 6.8E+OO 4.56E+Ol 6.80E+OO 4.56E+Ol b. Dry active waste 2.54E+02 3.69E-02 2.32E+Ol 3.68E-02 c. Irradiated components  -0--0--0-d. Other (oil/miscellaneous liquids sent to -0--0--0-processor for volume reduction)
TOTAL 2.61E+02 4.56E+Ol 3.00E+Ol 4.56E+Ol Note: Shipped volumes and curies are not always equal to the buried volumes and curies as a result of volume reducing processing, and some disposal occurs outside the twelve month time period in which shipments occurred.
Percent Error +/-25% +/-25% NIA NIA +/-25% Dry active waste also includes some low-level radioactive resins, tank sediments, and filters that are handled and processed in a manner that is consistent with this waste stream. 2. Estimate of Major Nuclide Composition (by type of waste) Nuclide % Activity Abundance Ci a. Spent resins/filters H-3 37.13 l.70E+Ol Ni-63 31.52 1.44E+Ol Fe-55 17.00 7.77E+OO Co-60 12.33 5.64E+OO Cs-137d 1.58 7.22E-01 C-14 0.07 3.20E-02 Tc-99 0.01 3.12E-03 I-129 LLD Other<1 J 0.36 l.67E-01 Total 100.00 4.57E+Ol b. Dry active waste Fe-55 40.91 l.51E-02 Co-60 29.48 l.09E-02 Ni-63 18.43 6.80E-03 Co-58 5.21 l.92E-03 Mn-54 1.82 6.71E-04 Sb-125 1.07 3.93E-04 C-14 0.87 3.19E-04 H-3 LLD Tc-99 LLD I-129 LLD OtherC 1 J 2.21 8.18E-04 Total 100.00 3.69E-02 d. Other (oil/miscellaneous liquids sent to processor for volume reduction)
NIA NIA NIA (1) Nuclides representing
<1% of total shipped activity:
Cr-51, Co-57, Sr-90d, Zr-95, Nb-95, Cs-137d, and Ce-144d. Page 42 of 58 TABLE9.10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS
: 3. Solid Waste Disposition (Mode of Transportation:
Truck) Waste Type Waste Class B a. Resin/filters c b. Dry active waste A d. Other NA *High Integrity Container B. Irradiated Fuel Shipments (Disposition)
Number of Shipments 0 Mode of Transportation NIA Container Type PolyHIC* PolyHIC* General Design NA Destination NIA Page 43 of 58 Number of Shipments 1 1 4 NA Destination Waste Conrol Specialists, Andrews, TX Energy Solutions Oak Ridge, TN NA Attachment 10.1 Meteorological Joint Frequency Tables Page 44 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY A CLASS ELEVATION:
10 m WIND Wind Speed (mph) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 10 34 19 1 0 65 NNE 2 5 26 19 3 0 55 NE 5 6 9 3 0 0 23 ENE 2 13 0 0 0 0 15 E 0 4 3 0 0 0 7 ESE 2 29 26 2 0 0 59 SE 1 24 31 4 0 0 60 SSE 0 25 77 22 2 0 126 s 1 19 32 24 8 0 84 SSW 0 9 5 3 1 0 18 SW 2 3 3 0 0 0 8 WSW 2 0 0 0 0 0 2 w 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 1 2 1 0 0 4 NNW 0 5 16 27 8 3 59 VARIABLE 2 2 0 0 0 0 4 TOTAL 20 55 264 124 23 3 589 Periods of calm (hours): 1 Hours of missinq data: 3 Page 45 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP -HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY B CLASS ELEVATION:
10 m WIND Wind Speed (mph) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 13 13 12 4 0 43 NNE 2 9 13 15 3 0 42 NE 7 12 7 0 0 0 26 ENE 6 6 4 1 0 0 17 E 1 12 3 0 0 0 16 ESE 4 20 14 1 0 0 39 SE 0 18 22 9 0 0 49 SSE 0 26 46 17 2 0 91 s 1 20 64 81 16 0 182 SSW 0 8 19 6 1 0 34 SW 1 4 8 1 0 0 14 WSW 0 2 0 1 0 0 3 w 0 0 0 3 0 0 3 WNW 0 0 0 0 0 0 0 NW 0 2 6 3 2 0 13 NNW 0 13 13 20 8 5 59 VARIABLE 0 0 2 0 0 0 9 TOTAL 30 165 234 170 36 5 640 Periods of calm (hours): 1 Hours of missing data: 2 Page 46 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY c CLASS ELEVATION:
10 m WIND Wind Speed (moh) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 16 19 20 3 0 62 NNE 5 8 15 14 2 0 44 NE 10 8 7 1 0 0 21 ENE 7 12 10 1 0 0 30 E 7 13 5 0 0 0 25 ESE 1 40 15 2 0 0 58 SE 2 28 35 3 0 0 68 SSE 2 25 40 31 3 0 101 s 3 22 59 77 9 0 170 SSW 2 8 30 22 3 0 65 SW 3 7 16 6 1 0 33 WSW 2 2 6 3 0 0 13 w 1 2 4 6 0 0 13 WNW 0 1 0 1 0 0 2 NW 2 3 11 6 4 0 26 NNW 3 25 12 9 16 1 66 VARIABLE 10 0 2 0 0 0 12 TOTAL 64 215 286 202 41 1 809 Periods of calm (hours): 5 Hours of missinQ data: 6 Page 47 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY D CLASS ELEVATION:
10 m WIND Wind Speed (mph) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 19 143 227 60 2 0 451 NNE 16 99 101 21 1 0 238 NE 23 53 31 8 0 0 115 ENE 11 42 26 2 0 0 81 E 23 87 16 0 0 0 126 ESE 36 155 54 5 0 0 250 SE 34 190 214 26 0 0 464 SSE 20 138 357 238 21 0 774 s 6 78 328 224 34 5 675 SSW 8 57 80 57 12 2 216 SW 16 17 29 32 3 0 97 WSW 10 30 14 11 0 0 65 w 6 8 6 5 0 0 25 WNW 3 19 27 4 0 0 53 NW 9 39 50 23 7 0 128 NNW 8 65 164 81 6 1 335 VARIABLE 74 40 11 1 0 0 126 TOTAL 322 1260 1735 798 96 8 4219 Periods of calm (hours): 5 Hours of missinQ data: 61 Page 48 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY E CLASS ELEVATION:
10 m WIND Wind Speed (m Jh) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 59 34 1 0 0 103 NNE 4 49 25 1 0 0 79 NE 3 16 1 0 0 0 20 ENE 6 13 1 0 0 0 20 E 12 19 1 0 0 0 32 ESE 15 56 4 0 0 0 75 SE 22 321 113 1 1 0 458 SSE 13 171 189 9 1 0 383 s 15 62 66 2 0 1 146 SSW 14 46 39 10 0 0 109 SW 16 11 17 2 1 0 47 WSW 11 0 6 5 0 0 32 w 6 7 5 0 0 0 18 WNW 12 19 13 3 1 0 48 NW 29 59 29 2 0 0 119 NNW 12 30 16 1 0 0 59 VARIABLE 58 11 6 1 0 0 76 TOTAL 257 959 565 38 4 1 1824 Periods of calm (hours): 5 Hours of missing data: 45 Page 49 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY F CLASS ELEVATION:
10 m WIND Wind Speed (mph) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 2 0 0 0 0 4 NNE 0 4 1 0 0 0 5 NE 0 0 0 1 0 0 1 ENE 0 0 0 0 0 0 0 E 0 1 0 0 0 0 1 ESE 5 0 0 0 0 0 5 SE 3 28 1 0 0 0 32 SSE 11 10 7 0 0 0 28 s 12 9 14 0 0 0 35 SSW 23 19 10 1 0 0 53 SW 26 20 11 2 0 0 59 WSW 27 24 0 0 0 0 51 w 10 4 1 0 0 0 15 WNW 15 5 0 0 0 0 20 NW 12 23 2 0 0 0 37 NNW 5 5 0 0 0 0 10 VARIABLE 15 3 2 0 0 0 20 TOTAL 166 157 49 4 0 0 376 Periods of calm (hours): 1 Hours of missinq data: 13 Page 50 of 58 Reg. Guide 1.21 Joint Frequency Table \ CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY G CLASS ELEVATION:
10 m WIND Wind Speed (mph) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 0 0 0 0 1 NNE 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 1 0 0 0 0 1 SSE 0 0 0 *o 0 0 0 s 4 2 1 0 0 0 7 SSW 10 17 5 0 0 0 32 SW 14 23 5 0 0 0 42 WSW 17 21 3 0 0 0 41 w 17 4 0 0 0 0 21 WNW 9 1 0 0 0 0 10 NW 5 8 0 0 0 0 13 NNW 0 2 0 0 0 0 2 VARIABLE 6 0 0 0 0 0 6 TOTAL 83 80 14 0 0 0 177 Periods of calm (hours): 1 Hours of missinq data: 0 Page 51 of 58 Reg. Guide 1.21 Joint Frequency Table CPNPP HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2016 00:00 to 31-DEC-2016 23:59 STABILITY ALL CLASS ELEVATION:
10 m WIND Wind Speed (mph) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 36 244 327 112 10 0 729 NNE 30 174 181 70 9 0 464 NE 48 90 55 13 0 0 206 ENE 32 86 41 4 0 0 163 E 43 136 28 0 0 0 207 ESE 63 300 113 10 0 0 486 SE 62 610 416 43 1 0 1132 SSE 46 395 716 317 29 0 1503 s 42 212 564 408 67 6 1299 SSW 57 164 188 99 17 2 527 SW 78 85 89 43 5 0 300 WSW 69 89 29 20 0 0 207 w 40 25 16 14 0 0 95 WNW 39 45 40 8 1 0 133 NW 57 135 100 35. 13 0 340 NNW 28 145 221 138 48 10 590 VARIABLE 172 56 23 2 0 0 253 TOTAL 942 2991 3147 1336 200 18 8634 Periods of calm (hours): 19 Hours of missinq data: 131 Page 52 of 58 2016 Wind Rose and Stability Class Graphs 2016 N NW/ NNE NE WNW ENE*> 24 mph 19-24 mph w
* 13-18 mph E
* 8-12 mph WSW *4-7 mph ESE
* 1-3 mph SW / SE 2016 Stability Class Total Hours 5 000 4 5 00 4000 35 00 3 000 2 5 00 *Tot al Hou rs 2 000 1 5 00 1000 5 00 0 A B c D E F G Page 53 of 58 Attachment 10.2 Atmospheric Dispersion (X/Q) and Deposition (D/Q) Calculation Methodology Discussion Page 54 of 58 Introduction CR-2013-001059 evaluated the atmospheric dispersion (X/Q) and deposition (D/Q) calculation methodology and frequency as they relate to the meteorological data to ensure they are up to date. The CPNPP ODCM does not require a re-evaluation on any frequency or specific criteria for comparison.
The NRC guidance documents cited in the ODCM also do not provide any requirements for re-evaluation.
Revision 2 of Regulatory Guide 1.21, to which we are not committed, recommends that 5 years of meteorological data be used to evaluate the dispersion factors and that variation in the factors be within 10% in the non-conservative direction.
The evaluation of our meteorological data included 6 years of data and meets the criteria.
Discussion Meteorological data collected for the original FSAR, the NuBuild FSAR and historical Radiological Effluent Reports were reviewed.
The data list the predominant wind direction, as a percentage, averaged for all speeds and stability classes within the period. For periods not summarized and when the plant was operable (1990-2000) only 1990, 1995 and 1996 show the predominant wind direction to be from the SSE. This information was not included, however, since the data should include a summary of at least 5 years of data. The original dispersion and deposition factors were calculated based on meteorological data collected and summarized from 1972 through 1976 at Comanche Peak. This data show the predominant wind direction to be from the South but only slightly more than winds originating from the SSE. The historical data from 1957-1976 was included in the original FSAR for comparison and show more bias toward the southerly direction but was collected from the Dallas-Fort Worth Airport location.
Wind patterns for the DFW Airport were reviewed on the National Weather Service website for 1981-2010 and show that the prevailing wind direction remains from the South. This accounts for the slight variation in prevailing winds between historical and current data collected on site. During the New Build project for Units 3&4 and from OE 25286 the meteorological data were again summarized from 1997-2006, for Comanche Peak, and showed that the predominant wind direction shifted to the SSE. Using this data, new dispersion and deposition factors were calculated.
The new factors were less conservative when compared to the original dispersion and deposition factors at the Exclusion Area Boundary (See Reference 3). The conclusion was to continue reporting offsite exposures based on the original values. The last column of data in Table 1 is summarized for the purposes of this evaluation and includes meteorological data since the New Build evaluation through 2012. This data, like the NuBuild data, show the predominant wind direction to be from the SSE. Conclusion Although the predominant wind direction frequency changes slightly from SSE to S when comparing the NuBuild Data to the original FSAR and Historical Data, the NuBuild calculations show that dispersion and deposition factors do not increase.
Following the NuBuild evaluation, the wind direction remains the same and does not impact the calculation of the dispersion and deposition.
Using the original factors would be conservative when calculating doses to the public. CR-2017-004071 was initiated to document the evaluation of prevailing wind directions for all stability classes over the calendar year 2016. This evaluation is performed annually in accordance with Chemistry Guideline 25 to ensure the predominant wind direction has not changed based on the last 5 years of meteorological data including the current year. The 2016 predominant wind direction for the ALL stability class categories did not change when compared with the five year rolling average which includes 2016. No recalculations ofX/Q or D/Q values are required at this time. Page 55 of 58 Attachment 10.3 Carbon 14 Supplemental Information Page 56 of 58 Carbon-14 Supplemental Information Carbon-14 (C-14) is a naturally occurring isotope of carbon produced by interactions with cosmic radiation in the atmosphere with a half-life of 5730 years. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
C-14 is also produced in commercial nuclear reactors, but the amounts are much less than the amounts produced from natural formation or from weapons testing. fu June 2009, the NRC provided revised guidance in Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Ejjluents and Solid Waste, Revision 2, establishing an updated approach for identifying principal radionuclides.
Because the overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations, C-14 now qualifies as a "principal radionuclide" (anything greater than one percent of overall radioactivity in effluents) under federal regulations at many plants. fu other words, C-14 has not increased and C-14 is not a new nuclear plant emission.
Rather, the improvements in the mitigation of other isotopes have made C-14 more prominent.
The dose contribution of C-14 from liquid radioactive waste is essentially insignificant compared to that contributed by gaseous radioactive waste. Therefore the evaluation of C-14 in liquid radioactive waste is not required by the new Reg. Guide 1.21, Rev. 2. The Reg. Guide 1.21, Rev. 2 also states that the quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term production model. A recent study produced by EPRI (Estimation of Carbon-14 in Nuclear Power Plant Gaseous Ejjluents, EPRI, Palo Alto, CA: 2010, 1021106) developed a model for estimation of C-14 source production.
This model was used by CPNPP for the 2010 Radioactive Effluent Release Report. Also in the CPNPP report, the assumption that 70% of the C-14 gaseous effluent is estimated to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is estimated to be from continuous releases through the unit vents (Ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004). The C-14 released from PWR's is primarily a mix of organic carbon and carbon dioxide released from the waste gas system. The C-14 species initially produced are primarily in the organic form, such as methane. The C-14 in the primary coolant can be converted to an inorganic chemical form of primarily carbon dioxide through a chemical transformation.
Studies documented by the EPRI Report Characterization of Carbon-14 Generated by the Nuclear Power Industry, EPRI Palo Alto, CA: 1995, TR-105715, measured C-14 releases from PWRs indicating a range of 70% to 95% organic. The average value was indicated to be 80% organic with the remainder being carbon dioxide. As a result, a value of 80% organic C-14 is assumed by the CPNPP Radioactive Effluent Release Report methodology.
The public dose estimates from airborne C-14 in the CPNPP Effluent report are performed using dose models from NUREG-0133 and Regulatory Guide 1.109. The dose models and assumptions used for the dose estimates of C-14 are documented in the 2011 ODCM changes. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released during 2011 is well below the 10CFR50, Appendix I, ALARA design objective of 15 mRem/yr per unit. Page 57 of 58 Putting Radiation Dose in Context Humans are exposed to radiation every day. The majority comes from natural sources including the earth, food and water consumption, the air, the sun and outer space. A smaller fraction radiation comes from man-made source such as X-rays, nuclear medical treatments, building materials, nuclear power plants, smoke detectors and televisions.
Radiation is measured in units called millirem (mRem). One mRem is a very small amount of exposure.
On average, Americans receive 620 mRem of radiation dose every year. Approximately one-half of the dose comes from natural sources and the other half comes from medical procedures such as CAT scans. The table below can help to give some perspective to dose from various sources. Source Average Annual Dose Smoke detector in the home 0.008 mRem Live within 50 miles of a nuclear power plant 0.009mRem Live within 50 miles of a coal-fired power plant* 0.03 mRem NRC guideline for keeping radiation dose from nuclear power plants as low as 5mRem reasonablv achievable ( ALARA) Round trip flight from New York City to Los Angeles 5mRem Medical X-ray lOmRem EPA limit for dose to the public from the commercial nuclear fuel cycle 25mRem Food and water consumed throughout the course of one year 30mRem NRC limit for dose to the public from nuclear power plants lOOmRem Mammogram lOOmRem Average annual exposure for a nuclear power plant worker 120mRem Average annual exposure from background radiation 300mRem CT scan 1,000 mRem NRC's annual limit for occupational exposure 5,000mRem Cardiac catheterization or coronary angiogram 5,000mRem
*Coal is naturally radioactive.
Sources: US. Environmental Protection Agency, Health Physics Society. Page 58 of 58}}

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