ML12128A194

From kanterella
Jump to navigation Jump to search
Enclosure 1 to TXX-12061, 2011 Radioactive Effluent Release Report
ML12128A194
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/04/2012
From: Valentine D
Luminant Generation Co, Luminant Power
To:
Office of Nuclear Reactor Regulation
References
CP-201200347, TXX-12061
Download: ML12128A194 (49)
v • d • e


Text

Enclosure 1 to TXX-12061 2011 Radioactive Effluent Release Report

I D 2011 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2011 - December 31, 2011 Prepared By: David Valentine Date 4/4/12 Reviewed By: Jim Stevens Date 4/4/12 Approved By: Bill Moore Date 4/4/12 Page 1 of 48

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 METEROLOGICAL DATA 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 48

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 Site Liquid and Gaseous Batch Release Summary 9.2 Site Abnormal Batch Liquid and Gaseous Release Summary 9.3 Site Gaseous Effluents-Summation of All Releases 9.4 Site Gaseous Effluents-Ground Level Releases 9.5 Site Liquid Effluents Summation of All Releases 9.6 Site Liquid Effluents 9.7 Dose Due to Liquid Releases-Site 9.8 Dose Due to Gaseous Releases-Site 9.9 Dose Due to Radioiodines, Tritium, and Particulates in Gaseous Releases-Site 9.10 Solid Waste and Irradiated Fuel Shipments 9.11 Meteorological Joint Frequency Tables 10.0 ATTACHMENTS 10.1 Meteorological Joint Frequency Distribution Tables 10.2 Carbon 14 Supplemental Information Page 3 of 48

ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPNPP Comanche Peak Nuclear Power Plant ECL Effluent Concentration Limit IFSFI Independent Spent Fuel Storage Installation LDCR Licensing Document Change Request LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks pCi Picocurie REC Radiological Effluent Control SORC Station Operations Review Committee uCi Microcurie WMT Waste Monitor Tanks WWHT Waste Water Holdup Tanks Page 4 of 48

1.0 Introduction This Radioactive Effluent Release Report, for Comanche Peak Nuclear Power Plant 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, 2011, through December 31, 2011.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2011 was conducted as described in the following report. The results of the monitoring program indicate the 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, the improvements in the mitigation of other isotopes have made C- 14 more prominent.

Attachment 10.2 on page 46 provides more detail about C-14.

Gaseous Effluents:

A summary of all the radioactive gaseous releases to the environment during 2011:

Gaseous Waste 2011 2010 Comments Tritium 48.12 Ci 43.21 Ci 1 C-14 Activity 23.32 Ci 25.48 Ci 2 Total Fission and Activation Activity 3.73 Ci 3.89 Ci Total Particulate Activity 0 Ci 0 Ci 3 Gross Alpha Activity 0 Ci 0 Ci 3 Iodine Activity 0 Ci 0 Ci 3 Calculated Gamma Air Dose 6.21E-5 mRad 4.15E-4 mRad Calculated Beta Air Dose 7.54E-5 mRad 8.5 1E-4 mRad Total Whole body dose 0.1 lmRem 0.11 mRem 4 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 is related to the type of fuel used (i.e., 18-month fuel) the core life and power output and number of core cycles.

2. Because the industry as a whole has minimized effluents, C-14 is now a principle isotope. The majority of the gaseous activity and 'dose increase is from the addition of C- 14.
3. No alpha, iodine or particulate activity was released.

Page 5 of 48

4. Despite the inclusion of C-14, total whole body dose is very low (0.44% of Technical Specification).

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 significant fuel defects during 2011. There were 2 refueling outages and 3 other unplanned outages. Despite the higher than normal number of outages, most of the released activity and associated dose was significantly lower in 2011 versus 2010.

Liquid Effluents:

A summary of all the radioactive liquid releases to the environment during 2011:

Liquid Waste 2011 2010 Comments Total Activity (excluding tritium) 6.5 6mCi 16.4 mCi 1 Tritium Activity 2790 Ci 1340 Ci 2 Total Whole Body Dose 0.149 mRem 0.155 mRem 1 Total Volume Released 1,155,673 Gal 28,005,284 Gal 3 Comments

1. The increased activity and dose in 2010 was due to issues with the liquid waste processing equipment from March to June. Changes in media and processing equipment repairs solved the problem and restored processing efficiency as can be seen by the decrease in 2011 totals.
2. The increased tritium activity for 2011 is attributed to waste water processing for 2 refueling outages.

3 Explanation for the larger than normal total volume released during 2010: CPNPP processes many millions of gallons of non-radioactive water each year from the secondary portion of the plant. Water plant waste, turbine building sumps and other sources all contribute to these totals. This waste water is processed through the low volume waste (LVW) system which then discharges to Squaw Creek Reservoir. A monthly composite sample from the LVW is analyzed quarterly for activity. Normally, this waste water does not contain any radionuclides.

However, in late 2009, the Unit 2 refueling water storage tank (RWST) overflowed into the turbine building sumps. Initially this water was diverted to the waste processing system. Once.

the 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 LVW. The first quarter LVW composite sample tested positive for tritium (a small amount above background). Consequently, the volume discharged from the LVW had to be accounted for as liquid waste.

Because the LVW 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., For 2011, the volume returned to normal values.

Page 6 of 48

Meteorological Data The CPNPP meteorological system achieved a greater than 90% 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 2011 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

ODCM Changes There were 2 changes made to the ODCM. These changes are referenced in section 8.2 Solid Waste Summary of the solid waste production Total Waste 2011 2010  % Error Shipped (m3) 667 476 25%

Shipped (Ci) 0.215 18.9 25%

Buried (m3) 70.7 65.6 25%

Buried (Ci) 0.149 18.9 25%

Comments CPNPP disposed four containers of Class A resins in 2010 and a typical quantity of dry active waste. The impact of this resin disposal disproportionally increased the activity disposal with respect to 2011. In addition, during 2011, several containers of legacy dry activity waste were disposed of which resulted in greater volume during the year.

Over the past three years, CPNPP has only had access to a Class A radioactive waste disposal site. Class A waste represents the vast majority of volume but very little of the activity disposed of as radioactive waste resulting from operations and maintenance. Once the Texas waste disposal facility becomes available, the disposal activity is expected to spike high due to disposal of waste in storage and then return to normal.

Page 7 of 48

Groundwater Tritium CR-2011-003303, CR 2011-010251 and CR-2011-009873 documented some positive indications of tritium in the seepage sump near the water treatment plant and in the LVW Pond A Leachate. All of these samples were well below the state reportable criteria of 20,000 pCi/L. Because Squaw Creek Reservoir (SCR) water contains a low background concentration of tritium, SCR water used in the plant will contain similar concentrations.

See section 8.8 for details.

Conclusion Overall, 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 8 of 48

1.2 Historical Trend Graphs Total Gaseous Fission and Activation Activity Released from CPNPP AmM 996.9 1cX00.00 228.0O 148.00 100.00 25.20 13.90 S10.00 5.82 SM 3.89 3.73 2.60 1.60 1.60 1.30 14 1.00 1.30-0.10 1996 1997 1998 1999 2000 2001 2002 2003 2004 200 06 2007 200820120W0 2010 2011 Year Total Gaseous Titium Released from CPNPP 90.00 80.00 77.*

70.00 61.27 600.00 "1 8'.t0 55.80 56

___________ 49.10 0 o 50.00 A 43.90 43.60 40.00 0

296 20.00.

10.00.

0.00 4 196 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year Page 9 of 48

Total Whole Body Dose due to Gaseous Activity released from CPNPP 012 0.11 0.11 0.11 0.10 0.09 0.06 0.06 _ 0.06 0.05 0.05 0.0-4 000 0.04 0.02 199 197 INS 19 2000 2M1 2002 2003 2004 200 2006 2007 20 2009Y 2010 2011 Yeaw Total Volume Liquid Effluents Released from CPNPP 1OXWXX]

i I 10~DXX]

Year Page 10 of 48

Total Activity (Excluding H3) Released In Liquid Effluents from CPNPP 430000 00227.90 232.10 U

293.00 124.80 110.0 11.90 108.70 100.00 50.00 17.60 21.60 15.00 6 00 "- r-5.A8 7.60 M 3.75 6.4 6 0.00 M"AL.

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year Total Curies of Titium Released in Liquid Effluents from CPNPP 2790 36M 1500 1550 1520 V0 1223 134 669 532 0

1996 1997 1998 1999 2000 2001 2002 20M3 2004 2005 2006 2007 2006 2009 2010 2011 Year Page 11 of 48

TotalWhole BodyDose Due to Liquid Effluents Released from CPNPP 0.16 0.15 0.149 0.14 3 0.13 0.12 0.11 0.11 0.11

.10 __

0______ 0.10 0.10 0.10 0.09 0.09 0.08 0.06 0.04 0.W 0.02 1996 1997 1998 1999 2000 2031 2002 2033 2004 2035 2006 2037 26 2009 2010 2011 Yeor Total Volume of Solid Radwaste Buried from CPNPP 2W.00 180.00 10.00 160M.0 140.00 120.00 100.00 90.20 80.00 470.7 60.03 65&mmm56 M.U 4o.1 40.00 20.00 m .... 27.1M 1920 3I 2 18.70 m 19.30 160 21.1lf 0.00 Im 1996 1997 Il m I mI 1998 1999 2000 2001 20M2 2003 I

2004 2005 2006 2o07 I II 28 2009 2010 I

2011 Year Page 12 of 48

Total Curies of Solid Radwaste Burled from CPNPP 1800 1800 1400 1~00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2EX8 2009 2010 2011 Year Page 13 of 48 I

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.

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.OE-4 gCi/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 Page 14 of 48
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 LVW Pond Resin Inventory The quantity of radioactive material contained in resins transferred to the LVW pond shall be limited by the following expression:

(264/V)

  • Xj Aj/Cj < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:

Aj = pond inventory limit for a single radionuclide j (Curies),

C3 = 10CFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (jtCi/ml),

V = volume of resins in the pond (gallons), and 264 = conversion factor ([tCi/Ci per ml/gal) 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 75 mRem.

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 gCi/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.

Page 15 of 48

2.3.1 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. 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 and Fe-55 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 prior to release. 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 and Fe-55 by a contract laboratory.

2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release using gamma spectroscopy. 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 gamma emitting radionuclides 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 for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for 1-131 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.

Page 16 of 48

C-i14 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 10.2 on page 46 for more information on C-14.

2.4 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 9.1.

2.5 Abnormal or Unplanned Releases Abnormal releases are defined as the unintended discharge of a volume of liquid or airborne radioactivity to the environment. There was 1 normal (monitored) unplanned gaseous effluent releases during .2011 and is summarized in section 8.5.1. There were no abnormal unplanned liquid or gaseous releases during 2011. Table 9.2 summarizes the abnormal and unplanned releases.

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.

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 radioiodines and particulates, for the pathways Page 17 of 48

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 2011 were any of these limits exceeded, therefore no evaluations are required.

6.5 Dose to a MEMBER OF THE PUBLIC From Activities Inside the Site Boundary Three activities are considered in this evaluation: fishing on Squaw Creek Reservoir, recreation activitie's at the CPNPP employee recreational area and site tours through the CPNPP Visitors Center.

The highest dose occurred in the evaluation for fishing, resulting in a dose of 3.69E-03 mRem/yr.

The dose to a MEMBER OF THE PUBLIC (fisherman) on Squaw Creek Reservoir was calculated based on 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 dose is calculated at the point of circ water discharge into the reservoir.

The dose to a MEMBER OF THE PUBLIC engaged in recreational activities at the CPNPP employee recreational park was calculated based on one visit a week, five hours each day, six months per year. Pathways included in the calculation were gaseous inhalation, submersion and ground plane.

The dose to a MEMBER OF THE PUBLIC during site tours through the CPNPP Visitors Center was calculated based on two visits per year, thirty minutes each visit. Pathways included in the calculation were gaseous inhalation and submersion.

Due to increased security, routine fishing on Squaw Creek Reservoir and visitation by the public on-site has been significantly restricted. The calculations are still valid and included in the event security access restrictions are ever returned to previous conditions and controls.

All calculations were performed in accordance with the methodology and parameters in the ODCM.

Page 18 of 48

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 2011, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 10. During 2011, the goal of >90%

joint data recovery was met. The individual percent recoveries are listed below:

Meteorological Data Recoverv Channel  % Recovery Wind Speed 99.8 Wind Direction 99.7 Delta Temperature A 98.4 Delta Temperature B 99.8 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 the period covered by this report, there were no instances where these instruments were' inoperable for more than thirty days.

8.2 Changes to the Offsite Dose Calculation Manual During the period covered by this report, there were 2 revisions to the ODCM:

REVISION 31 LDCR-OD-20 11-1 (EV-CR-2010-010410-37) (SCD):

Dose limits at the site boundary require monitoring to demonstrate compliance with the limits of 10 CFR 72 as a result of direct radiation exposure emitted by the facility. The limits for the ISFSI are the same as the existing limits specified by 10 CFR 50 and therefore there are no changes to the monitoring criteria outlined in the ODCM.

REVISION 32 LDCR-OD-2010-1 (EV-CR-2010-011250-1) (SCD):

Revised the ODCM to incorporate the Carbon-14 isotope dose considerations into the CPNPP Radioactive Effluent Release Report in accordance with the new revision 2 of REGULATORY GUIDE 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste" This change is applicable to Units 1 and 2.

Page 19 of 48

8.3 New Locations for Dose Calculations or Environmental Monitorin2 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 2011 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 2011 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.

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 Normal. Unplanned Gaseous Release There was one normal, unplanned gaseous effluent releases occurred during 2011 documented by CR-2011-001885. RCS leakage from the Unit I charging system degassed and caused an increasing trend on PVG-384 plant stack A radiation monitor. A plant stack A gas sample indicated the presence of Xe-135 and Ar-41. A release permit was created to account for this monitored gas release.

8.5.2 Abnormal, Unplanned Gaseous Effluent Release No abnormal, unplanned gaseous effluent releases occurred during 2011.

8.5.3 Abnormal. Unplanned Liquid Effluent Releases No abnormal, unplanned liquid effluent releases occurred during 2011.

Page 20 of 48

8.6 Resin Releases to the LVW Pond A total of 927 ft3 of powdex resin was transferred to. the LVW pond during the period covered by this report. The cumulative activity deposited in the LVW pond since operations began through the end of 2011 is 2.14E-3 Curies, consisting of Co-58, Co-60, Cs-1 34, Cs-137, 1-131, 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.

For the reporting period of this report, no changes to the Radwaste Treatment Systems occurred that meet the reporting criteria of the Process Control Program.

Page 21 of 48

8.8 Groundwater Tritium monitoring Pro2ram Seepage Sump Samples of perched groundwater are taken quarterly in accordance with the site groundwater tritium monitoring program. During 2011, samples from the Water Production Plant seepage sump (storm drain) had positive values for tritium as listed in the table below. The source of the tritium is from a small leak of Squaw Creek Reservoir (SQR) water that feeds the water plant. Because CPNPP discharges its effluents into Squaw Creek Reservoir, there is always a low level background concentration of tritium in the reservoir water. Essentially the seepage sump is discharging diluted Squaw Creek. Reservoir water back to Squaw Creek Reservoir.

Basin A Variations in the tritium values from the Pond A Leachate are thought to come from pockets of water trapped in between the inner and outer liner by many inches of lake sediment resting on top of the liner. These pockets of water are from basin water previously transferred to the space between the liners to test for liner repair work effectiveness. Work is in progress to remove this sediment from the pond. As the sediment is removed, pockets of residual basin water are reintroduced into the Leachate sample.

Basin A only receives Surface Water Treatment System wastewater; therefore, there is a high level of confidence the source of the tritium is Squaw Creek Reservoir water. Also, there is no indication of a release from the secondary liner, since tritium was not detected in down gradient monitoring wells.

In both of these cases, the tritium concentrations are well below the state reportable limit of 20,000 pCi/L. The source of the tritium is from SQR.

This has been documented in CR-2011-003303, CR 2011-010251 and CR-2011-009873.

Tritium Results in pCi/L Pond A Date Seepage Sump Leachate Mar-11 9300 11300 Jun-11 10400 2050 Sep-11 Dry (no Sample) 12100 Dec-11 5030 2260 Page 22 of 48

SECTION 9.0 EFFLUENT TABLES Page 23 of 48

Table 9.1 Site Liquid and Gaseous Batch Release Summary (2011)

A. Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual

1. Number of batch releases 15 15 19 12 61
2. Total time period for Batch. releases (Minutes) 4.69E+03 4.46E+03 5.93E+03 3.76E+03 1.88E+04
3. Maximum time period for a batch release ( Minutes) 3.45E+02 3.30E+02 3.40E+02 3.40E+02 3.45E+02
4. Average time period for a batch release (Minutes) 3.13E+02 2.97E+02 3.12E+02 3.13E+02 3.09E+02
5. Minimum time period for a batch release (Minutes) 2.90E+02 2.39E+02 2.60E+02 2.82E+02 2.39E+02
6. Average stream flow during periods of release of (GPM ) 6.35E+04 7.99E+04 4.91E+04 7.14E+04 2.64E+05 liquid Effluent into a flowing stream B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual
1. Number of batch releases 27 29 28 34 118
2. Total time period for batch releases (Minutes) 9.73E+03 1.16E+04 9.57E+03 1.30E+04 4.39E+04
3. Maximum time period for a batch release (Minutes) 4.46E+02 2.10E+03 4.11E+02 1.06E+03 2.10E+03
4. Average time period for a batch release (Minutes) 3.60E+02 4.OOE+02 3.42E+02 3.82E+02 3.72E+02
5. Minimum time period for a batch release (Minutes) 2.31E+02 1.72E+02 1.82E+02 5.10E+01 5.10E+01 Page 24 of 48

Table 9.2 Site Abnormal Liauid and Gaseous Batch Release Summary (2011)

A. Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals

1. Number of Releases 0 0 0 0 0
2. Total Time For All Releases (Minutes) 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00
3. Maximum Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
4. Average Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
5. Minimum Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+/-00 0.OOE+00
6. Total activity for all releases ( Curies ) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-40O B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals
1. Number of Releases 1 0 0 0 1
2. Total Time For All Releases (Minutes) 3.12E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.12E+02
3. Maximum Time For A Release (Minutes) 3.12E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.12E+02
4. Average Time For A Release (Minutes) 3.12E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.12E+02
5. Minimum Time For A Release (Minutes) 3.12E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.12E+02
6. Total activity for all releases ( Curies ) 2.05E-01 0.00E+00 0.OOE+00 0.OOE+00 2.05E-01 Page 25 of 48

Table 9.3 Site Gaseous Effluents - Summation of All Releases (2011 Type of Effluent Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total A. Fission And Activation Gases

1. Total Release Curies 2.86E+00 3.35E+01 3.46E-01 5.99E-01 3.73E+O1
2. Average Release rate for period uCi/sec 3.63E-01 4.24E+00 4.39E-02 7.60E-02 4.72E+00
3. Percent of Applicable Limit B. Radioiodines
1. Total Iodine- 131 Curies 2.89E-06 1.85E-06 O.OOE+00 O.OOE+00 4.74E-06
2. Average Release rate for period uCi/sec 3.67E-07 2,35E-07 O.OOE-O0 O.OOE+00 6.02E-07
3. Percent of Applicable Limit C. Particulates
1. Particulates ( Half-Lives > 8 Days) Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
3. Percent of Applicable Limit D. Tritium & C14
1. Total Release Curies 1.45E+O1 2.08E+01 2.17E+01 1.45E+01 7.14E+O1
2. Average Release rate for period uCi/sec 1.83E+00 2.65E+00 2.74E+00 1.83E+00 9.04E+00
  • g
3. Percent of Applicable Limit *g E. Gross Alpha
1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. Average Release rate for period uCi/sec 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
  • Applicable limits are expressed in terms of dose.

Estimated Total Error For All Values Reported Is < 1.0%

Page 26 of 48

2011 Table 9.4 Site Gaseous Effluents - Ground Level Releases (2011)

Continuous Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Xe-133 Curies 2.12E+00 6.19E+00 O.OOE+00 O.OOE+0O 8.32E+00 Xe-135 Curies 4.14E-01 0.OOE+O0 O.OOE+00 O.OOE+/-00 4.14E-01 Total For Period Curies 2.54E+/-00 6.19E+00 O.OOE+O0 O.OOE+/-OO 8.73E+00 lodines 1-131 Curies 2.89E-06 1.85E-06 0.OOE+00 0.OOE+00 4.74E-06 Total For Period Curies 2.89E-06 1.85E-06 0.OOE+00 0OOE+00 4.74E-06 Particulates No Nuclides Found Curies N/A N/A N/A N/A N/A Tritium & C-14 H-3 Curies 8.14E+00 1.55E+01 1.56E+01 8.76E+00 4.79E+01 C-14 Curies 1.87 1.60 1.82 1.70 7.00 Gross Alpha No Nuclides Found Curies N/A N/A N/A N/A ' N/A Page 27 of 48

2009 Table 9.4 (cont)

Site Gaseous Effluents - Ground Level Releases (2011)

Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Ar-41 Curies 2.96E-01 7.65E-02 8.11E-02 1.62EL01 6.15E-01 Kr-85m Curies O.OOE+00 1.99E-02 O.OOE+00 7.42E-04 2.07E-02 Kr-85 Curies O.OOE+00 4.52E-01 2.65E-01 3.77E-01 1.09E+00 Kr-87 Curies O.OOE+00 O.OOE+00 O.OOE+00 3.82E-04 3.82E-04 Kr-88 Curies O.OOE+00 3.08E-03 O.OOE+00 1.28E-03 4.36E-03 Xe-131m Curies O.OOE+00 3.61E-01 0.00E+00 1.44E-05 3.61E-01 Xe-133m Curies O.OOE+00 4.59E-01 O.OOE+00 1.35E-03 4.61E-01 Xe-133 Curies 1.42E-02 2.47E+01 7.30E-04 4.21 E-02 2.48E+01 Xe- 135m Curies O.OOE+00 7.66E-04 O.OOE+00 2.06E-03 2.83E-03 Xe-135 Curies 1.15E-02 1.20E+00 O.OOE+00 1.31E-02 1.23E+00 Total For Period Curies 3.22E-01 2.73E+01 3.46E-01 5.99E-01 2.85E+01 lodines No Nuclides Found Curies N/A N/A N/A N/A N/A Particulates No Nuclides Found Curies N/A N/A N/A N/A N/A Tritium H-3 Curies 8.16E-02 7.64E-02 2.39E-02 3.42E-02 2.16E-01 C-14 Curies 4.37 3.74 4.24 3.97 16.32 Gross Alpha No Nuclides Found Curies N/A N/A N/A N/A N/A

  • Zeroes in this table indicate that no radioactivity was present at detectable levels.

Page 28 of 48

Table 9.5 Site Liquid Effluents - Summation Of All Releases (2011)

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual A. Fission And Activation Products

1. Total Release (not including tritium, gases, Curies 2.64E-04 1.79E-03 2.66E-03 1.85E-03 6.56E-03 alpha)
2. Average diluted concentration during period uCi/ml 1.73E-11 1.06E-10 1.23E-10 1.40E-10 3.86E-10
3. Percent of Applicable Limit  %

B. Tritium

1. Total Release Curies 1.14E+03 6.42E+02 7.33E+02 2.72E+02 2.79E+03
2. Average diluted concentration during period uCi/ml 7.47E-05 3.79E-05 3.39E-05 2.06E-05 1.67E-04
3. Percent of Applicable Limit  %* * * *
  • C. Dissolved and Entrained Gases
1. Total Release Curies 4.78E-03 2.45E-02 6.34E-04 4.6 1E-04 3.04E-02
2. Average diluted concentration during period uCi/ml 3.15E-10 1.45E-09 2.93E-1 1 3.49E- I1 1.83E-09
3. Percent of Applicable Limit  %* * * *
  • D: Gross Alpha Radioactivity
1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 E: Waste Vol Release (Pre-Dilution) Liters 1.10E+06 1.03E+06 1.36E+06 8.89E+05 4.38E+06 F. Volume of Dilution Water Used Liters 1.52E+10 1.69E+10 2.16E+10 1.32E+10 6.69E+10
  • Applicable limits are expressed in terms of dose.

Estimated Total Error For All Values Reported Is < 1.0%

Page 29 of 48

Table 9.6 Site Liquid Effluents (2011)

ContinuousMode Nuclides Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Fission & Activation Products No Nuclides Found Curies N/A N/A N/A N/A N/A Tritium H-3 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Dissolved And Entrained Gases No Nuclides Found Curies N/A N/A N/A N/A N/A Gross Alpha Radioactivity Curies 0 0 0 0 0 Batch Mode Nuclides Released Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Fission & Activation Products Cr-51 O.OOE+00 O.OOE+00 0.OOE+00 1.30E-04 1.30E-04 Mn-54 0.OOE+00 O.OOE+00 0.OOE+00 7.40E-06 7.40E-06 Co-57 0.OOE+00 0.OOE+00 4.07E-06 O.OOE+00 4.07E-06 Co-58 2.09E-04 1.73E-03 2.56E-03 1.62E-03 6.12E-03 Co-60 5.50E-05 3.74E-05 9.13E-05 7.30E-05 2.57E-04 Nb-95 0.OOE+00 O.OOE+00 0.OOE+00 2.02E-05 2.02E-05 Ba-139 0.OOE+00 2.58E-05 0.OOE+00 0.OOE+00 2.58E-05 Total For Period 2.64E-04 1.79E-03 2.66E-03 1.85E-03 6.56E-03 Tritium H-3 1.1 4E+03 6.42E+02 7.33E+02 2.72E+02 2.79E+03 Dissolved And Entrained Gases Kr-85m 0.OOE+00 4.3 1E-05 0.OOE+00 3.06E-06 4.62E-05 Kr-85 1.24E-03 9.35E-04 0.OOE+00 0.OOE+00 2.18E-03 Kr-88 O.OOE+00 2.92E-06 O.OOE+00 0.OOE+00 2.92E-06 Xe-131m 0.OOE+00 5.04E-04 0.OOE+00 0.OOE+00 5.04E-04 Xe-133m O.OOE+00 1.89E-04 0.OOE+00 0.OOE+00 1.89E-04 Xe-133 3.54E-03 2.27E-02 6.34E-04 4.49E-04 2.73E-02 Xe-135 0.OOE+00 1.12E-04 O.OOE+00 8.19E-06 1.20E-04 Total For Period 4.78E-03 2.45E-02 6.34E-04 4.61E-04 3.04E-02

  • Zeroes in this table indicate that no radioactivity was present at detectable levels Page 30 of 48

Table 9.7 Dose to a member of the public due to Liquid Releases (2011)

Cumulative Doses per Quarter

% of  % of

% of Tech

% of Tech Tech Tech Organ Limit Units Quarter 1 Quarter 2 Quarter 3 Spec Quarter 4 Spec Limit Spec Spec Limit Limit Limit Total Body 1.50E+00 mRem 3.26E-02 2.17E+00 3.43E-02 2.29E+00 3.85E-02 2.57E+00 4.34E-02 2.89E+00 Thyroid 5.OOE+00 mRem 3.26E-02 6.52E-01 3.43E-02 6.87E-01 3.85E-02 7.70E-01 4.34E-02 8.68E-01 Organ 5.OOE+00 miRem 3.26E-02 6.52E-01 3.43E-02 6.87E-01 3.85E-02 7.70E-01 4.34E-02 8.68E-01 Bone 5.OOE+00 mRem 0.OOE+00 O.OOE+00 1.07E-10 2.14E-09 0.OOE+00 0.OOE+00 4.OOE-08 8.01E-07 Cumulative Doses per Year Tech Year to

% of Tech Organ Spec Units Ending Receptor Limit Spec Limit Limit Date Total Body 2.50E+01 mRem 1.49E-01 5.95E-01 Liquid Receptor - Adult 40CFR190.10 (a) TB Thyroid 7.50E+01 mRem 1.49E-01 1.98E-01 Liquid Receptor - Adult 40CFR1 90.10 (a) Thyroid Organ 2.50E+01 mRem 1.49E-01 5.96E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ Bone 2.50E+01 mRem 4.01E-08 1.61E-07 Liquid Receptor - Adult 40CFR1 90.10 (a) Organ Total Body 3.OOE+00 - mRem 1.49E-01 4.96E+00 Liquid Receptor - Adult Liq Annual TB Dose Thyroid 1.00E+01 mRem 1.49E-01 1.49E+00 Liquid Receptor - Adult Liq Annual Organ Dose Organ 1.00E+01 mRem 1.49E-01 1.49E+00 Liquid Receptor - Adult Liq Annual Organ Dose Bone 1.00E+01 mRem 4.01E-08 4.01E-07 Liquid Receptor - Adult Liq Annual Organ Dose Total Dilution Volume for Quarter 1 1.52E+10 Total Dilution Volume for Quarter 2 1.69E+10 Total Dilution Volume for Quarter 3 2.16E+ 10 Total Dilution Volume for Quarter 4 1.32E+10 Organ = GI-Lii, Kidney, Liver, or Lung Page 31 of 48

Table 9.8 Air Dose Due To Gaseous Releases - Site (2011)

Cumulative Doses Per Quarter Type of Tech Spec  % of Tech Quarter  % of Tech  % of Tech Quarter  % of Tech Units Quarter 1 Quarter 3 Radiation Limit Spec Limit 2 Spec Limit Spec Limit 4. Spec Limit Gamma Air 5.OOE+00 mRad 6.21E-05 1.24E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Beta Air 1.OOE+01 mRad 7.54E-05 7.54E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cumulative Doses Per Year Type of Tech Spec Year to  % of Tech Units Receptor Limit Radiation Limit Ending Date Spec Limit Gamma Air I.OOE+01 mRad 6.21E-05 6.21E-04 Gas Receptor SB -Adult NG Annual Gamma Air Dose Gamma Air I.OOE+01 mRad 6.2 1E-05 6.2 IE-04 Gas Receptor SB - Teen NG Annual Gamma Air Dose Gamma Air 1.OOE+01 mRad 6.21E-05 6.21E-04 Gas Receptor SB - Child NG Annual Gamma Air Dose Gamma Air 1.OOE+01 mRad 6.21E-05 6.21E-04 Gas Receptor SB - Infant NG Annual Gamma Air Dose Beta Air 2.OOE+01 mRad 7.54E-05 3.77E-04 Gas Receptor SB - Adult NG Annual Beta Air Dose Beta Air 2.OOE+01 mRad 7.54E-05 3.77E-04 Gas Receptor SB - Teen NG Annual Beta Air Dose Beta Air 2.OOE+01 mRad 7.54E-05 3.77E-04 Gas Receptor SB - Child NG Annual Beta Air Dose Beta Air 2.OOE+01 mRad 7.54E-05 3.77E-04 Gas Receptor SB - Infant NG Annual Beta Air Dose Page 32 of 48

Table 9.9 Dose to A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases (2011)

Cumulative Doses Per Quarter Tech Spec  % of Tech  % of Tech  % of Tech  % of Tech Organ Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Limit Spec Limit Spec Limit Spec Limit Spec Limit Total Body 7.5 mRem 2.27E-02 3.03E-01 3.14E-02 4.19E-01 3.27E-02 4.36E-01 2.25E-02 3.OOE-01 Thyroid 7.5 mRem 1.46E-02 1.95E-01 2.38E-02 3.17E-01 2.18E-02 2.91E-01 1.23E-02 1.64E-01 Organ 7.5 mRem 2.27E-02 3.03E-01 3.14E-02 4.19E-01 3.27E-02 4.36E-01 2.25E-02 3.OOE-01 Skin 7.5 mRem 6.40E-08 8.54E-07 4.10E-08 5.46E-07 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Bone 7.5 mRem 5.81E-02 7.75E-01 4.97E-02 6.62E-01 5.64E-02 7.52E-01 5.28E-02 7.04E-01 Organ = GI-Lli, Kidney, Liver, or Lung Quarterly limit values are the same for both 40CFR1 90.10 (a) and Gas Annual Organ Dose limits Cumulative Doses per Year Year to Organ Tech Spec  % of Tech Limit Units Ending Receptor Limit Spec Limit Date Total Body 25 mRem 1.09E-01 4.38E-01 Gas Receptor SB - Child 40CFR190.10 (a) TB Thyroid 75 mRem 7.26E-02 9.67E-02 Gas Receptor SB - Child 40CFRI 90.10 (a) Thyroid Organ 25 mRem 1.09E-01 4.38E-01 Gas Receptor SB - Child 40CFR190.10 (a) Organ Skin 25 mRem 1.05E-07 4.20E-07 Gas Receptor SB - Child 40CFR190.10 (a) Organ Bone 25 mRem 2.17E-01 8.68E-01 Gas Receptor SB - Child 40CFR190.10 (a) Organ Total Body 15 mRem 1.09E-01 7.30E-01 Gas Receptor SB - Child Gas Annual Organ Dose Thyroid 15 mRem 7.26E-02 4.84E-01 Gas Receptor SB - Child Gas Annual Organ Dose Organ 15 mRem 1.09E-01 7.30E-01 Gas Receptor SB - Child Gas Annual Organ Dose Skin 15 mRem 1.05E-07 7.OOE-07 Gas Receptor SB - Child Gas Annual Organ Dose Bone 15 mRem 2.17E-01 1.45E+00 Gas Receptor SB - Child Gas Annual Organ Dose Organ = GI-Lli, Kidney, Liver, or Lung Page 33 of 48

TABLE 9.10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2011 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

Shipped Shipped Buried Buried Percent

1. Type of Waste "m3 Ci m3 Ci Error
a. Spent resins/filters 0 0 0 0 N/A
b. Dry active waste 662 0.213 70.7 0.149 +/- 25%
c. Irradiated components N/A
d. Other (oil/miscellaneous liquids sent to processor for volume 5.1 1.22E-03 N/A reduction)

TOTAL 667 0.215 70.7 0.149 Note: Shipped volumes and curies are not always equal to the buried'volumes and curies since some disposal occurs outside the twelve month time period in which shipments occurred.

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 11 waste)
a. Spent resins/filters Nuclides representing <1% of total shipped activity: Mn-54,Co-57,Co-58,Fe-59,Zn-65,Sr-90,Nb-95,ZR-95,Ag- 110m,Sn-113,Sb-125,Ce-144,Pu-238,Pu-239/240,Am-241,Pu-241,Cm-242,Cm-243/244.

Page 34 of 48

TABLE 9.10 (cont.)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2011 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) cont

2. Estimate of Major Nuclide Composition (by type of Nuclide  % Abund. Activity waste) (Ci)

Fe-55 29.86 6.37E-02 Ni-63 22.25 4.75E-02 Co-60 19.95 4.26E-02 Co-58 19.82 4.23E-02 Nb-95, 2:11 4.50E-03 Cr-51 1.38 2.95E-03

b. Dry active waste Zr-95 1.20 2.56E-03 Mn-54 1.04 2.23E-03 C- 14 0.18 3.76E-04 H-3 0.01 1.47E-05 Tc-99 LLD 1-129 LLD Other* 2.20 4.70E-03 Total 100.00 2.13E-01
  • Nuclides representing <1% of total shipped activity: Cr-51,Mn-54,Co-57,Nb-95,ZR-95,Sb-125,Cs-134,Cs-13 7,Ce-144,Pu-238,Pu-239/240,Am-241,Cm-242,Cm-243/244.
2. Estimate of Major Nuclide Composition (by type of Nuclide  % Abund. Activity waste) (Ci)

Ni-63 43.68 5.34E-04 Fe-55 39.76 4.86E-04 Co-60 15.53 1.90E-04

d. Other H-3 LLD (oil/miscellaneous liquids sent to processor for volume C-14 LLD reduction) Tc-99 LLD 1-129 LLD . Other 1.03 1.25E-05 I Total 100.00 1.22E-03
  • Nuclides representing <1% of total shipped activity: Cr-51,Mn-54,Co-57,Nb-95,ZR-95,Sb-125,Cs-134,Cs-137,Ce-144,Pu-238,Pu-239/240,Am-241,Cm-242,Cm-243/244.

Page 35 of 48

3. Solid Waste Disposition (Mode of Transportation: Truck)

Waste Solidification Number of Class Container Type Agent(s) Shipments

a. Resin/filters N/A N/A N/A N/A N/A
b. Dry active waste A General Design N/A 10 Energy Solutions DOak Ridge, TN
d. Other A General Design N/A
  • Energy Solutions Oak Ridge, TN
  • Note: Solid Waste "Other" was included as part of a Dry Active Waste Shipment B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 36 of 48

Attachment 10.1 2010 Meteorological Joint Frequency Table Page 37 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-11 00:00 TO 31-DEC-11 23:59 STABILITY CLASS: A ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL m- - - - - - - - --- -

N 1 6 31 21 10 0 69 NNE 2 18 12 7 1 0 40 NE 2 23 7 2 0 0 34 ENE 6 12 0 0 0 0 18 E 2 13 4 0 0 0 19 ESE 0 20 39 3 0 0 62 SE 2 25 58 19 3 0 107 SSE 0 27 86 63 7 1 184 S 0 13 18 26 3 0 60 SSW 0 1 2 0 0 0 3 SW 0 0 0 0 0 0 0 WSW 1 1 0 0 0 0 2 W 0 0 0 0 0 0 0 WNW 0 0 0 0 1 0 1 NW 0 1 6 6 5 8 26 NNW 0 2 17 24 19 11 73 VARIABLE 14 7 0 0 0 0 21 Total 30 169 280 171 49 20 719 Periods of calm(hours): 0 Hours of missing data: 11 Page 38 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-I1 00:00 TO 31-DEC-11 23:59 STABILITY CLASS: B ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 6 18 6 2 0 35 NNE 6 11 9 1 0 0 27 NE 10 11 3 0 0 0 24 ENE 2 15 1 1 0 0 19 E 1 8 0 0 0 0 9 ESE 0 10 8 3 0 0 21 SE 0 12 27 14 1 0 54 SSE 1 20 33 45 14 6 119 S 1 13 35 54 35 6 144 SSW 1 7 15 6 2 2 33 SW 2 4 7 1 0 0 14 WSW 0 2 4 2 0 0 8 W 0 1 3 1 1 0 6 WNW 0 2 0 1 1 0 4 NW 1 1 4 7 3 8 24 NNW 1 5 15 8 10 8 47 VARIABLE 17 1 0 0 0 0 18 Total 46 129 182 150 69 30 606 Periods of calm(hours): 0 Hours of missing data: 0 Page 39 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-11 00:00 TO 31-DEC-11 23:59 STABILITY CLASS: C ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 6 16 13 4 0 43 NNE 2 4 12 3 1 0 22 NE 4 6 2 2 0 0 14 ENE 1 8 0 1 0 0 10 E 1 7 3 0 0 0 11 ESE 4 19 7 0 0 0 30 SE 2 8 16 9 0 0 35 SSE 2 8 24 48 15 6 103 S 2 11 38 77 52 21 201 SSW 0 5 22 38 7 3 75 SW 1 11 15 5 2 0 34 WSW 2 7 6 2 0 0 17 W 1 0 4 1 0 0 6 WNW 0 2 4 5 1 0 12 NW 1 9 7 9 5 7 38 NNW 3 5 8 21 17 11 65 VARIABLE 16 1 0 0 0 0 17 Total 46 117 184 234, 104 48 Periods of calm(hours): 1 Hours of missine data: 4 Page 40 of 48

R.G. 1.21 JOINT '*'  :' T.T.

HOURS '*:? \.¢ DIR" DECTION 1

'" VORD "*-,TAY-1I 00:00 TO 31-DEC-11 23:59 v-* Y  !TI

'. m.

Wind Speed (mph) at 'A m. level Wind Direction 1-3 '-7 8-12 13-18 19-24 >24 TOTAL N 14 y 199 121 15 0 425 NYF 11 44 101 34 0 0 190 5 36 44 11 0 0 97 ENE 9 26 25 0 0 0 60 E 12 38 13 0 0 0 63 ESE 14 89 43 10 0 0 156 SE 11 105 226 81 3 0 426 SSE 13 62 301 432 116 17 941 S 2 43 281 342 132 19 819 SSW 7 41 93 70 9 1 221 SW 10 25 39 12 0 0 86 WSW 4 20 16 4 0 0 44 W 0 9 11 8 1 0 29 WNW 3 11 45 21 3 0 83 NW 1 15 40 44 12 6 118 NNW 9 19 135 158 56 8 385 VARIABLE 56 22 2 1 0 0 81 Total 182 681 1614 1349 347 51 4224 Periods of calm(hours): 3 Hours of missing data: 10 Page 41 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-11 00:00 TO 31-DEC-I1 23:59 STABILITY CLASS: E ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 25 38 7 0 0 73 NNE 3 32 28 1 0 0 64 NE 1 8 4 1 0 0 14 ENE 0 6 2 0 0 0 8 E 10 20 0 0 0 0 30 ESE 15 65 11 0 0 0 91 SE 22 202 135 2 0 0 361 SSE 6 127 220 31 0 0 384 5 11 56 83 7 0 0 157 SSW 16 46 55 28 0 0 145 SW 9 11 33 3 0 0 56 WSW 3 13 6 1 0 0 23 W 3 13 5 1 0 0 22 WNW 8 28 19 2 0 0 57 NW 9 48 27 2 0 0 86 NNW 3 24 24 4 1 0 56 VARIABLE 55 13 3 1 0 0 72 Total 177 737 693 91 1 0 1699 Periods of calm(hours): 7 Hours of missing data: 6

'Page 42 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-11 00:00 TO 31-DEC-11 23:59 STABILITY CLASS: F ELEVATION: 10 m.

Wind Speed (mph) at' 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 0 3 0 0 0 6 NNE 0 1 3 0 0 0 4 NE 1 0 0 0 0 0 1 ENE 1 1 0 0 0 0 2 E 1 0 0 0 0 0 1 ESE 3 4 0 0 0 0 7 SE 12 46 13 0 0 0 71 SSE 18 33 13 1 0 0 65 S 17 28 10 0 0 0 55 SSW 13 23 18 0 0 0 54 SW 28 25 8 0 0 0 61 WSW 27 27 6 0 0 0 60 W 12 12 3 0 0 0 27 WNW 11 15 1 0 0 0 27 NW 11 37 4 0 0 0 52 NNW 3 1 0 0 0 0 4 VARIABLE 23 1 0 0 0 0 24 Total 184 254 82 1 0 0 521 Periods of calm(hours).: 3 Hours of missing data: 0.

Page 43 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-11 00:00 TO 31-DEC-Il 23:59 STABILITY CLASS: G ELEVATION: 10 i.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 0 0 0 0 0 2 NNE 0 0 0 0 0 0 0 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 4 1 0 0 0 5 SSE 1 1 0 0 0 0 2 S 8 3 1 0 0 0 12 SSW 14 17 4 0 0 0 35 SW 16 25 0 0 0 0 41 WSW 13 23 4 0 0 0 40 W 8 7 0 0 0 0 15 WNW 13 9 0 0 0 0 22 NW 4 20 0 0 0 0 24 NNW 1 0 0 0 0 0 1 VARIABLE 12 0 0 0 0 0 12 Total 92 109 10 0 0 0 211 Periods of calm(hours): 1 Hours of missing data: 0 Page 44 of 48

R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-11 00:00 TO 31-DEC-11 23:59 STABILITY CLASS: ALL ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 '19-24 >24 TOTAL N 30 119 305 168 31 0 653 NNE 24 110 165 46 2 0 347 NE 24 84 60 16 0 0 184 ENE 19 68 28 2 0 0 117 E 27 86 20 0 0 0 133 ESE 36 207 108 16 0 0 367 SE 49 402 476 125 7 0 1059 SSE 41 278 677 620 152 30 1798 S 41 167 466 506 222 46 1448 SSW 51 140 209 142 18 6 566 SW 66 101 102 21 2 0 292 WSW 50 93 42 9 0 0 194 W 24 42 26 11 2 0 105 WNW 35 67 69 29 6 0 206 NW 27 131 88 68 25 29 368 NNW 20 56 199 215 103 38 631 VARIABLE 193 45 5 2 0 .0 245 Total 757 2196 3045 1996 570 149 8713 Periods of calm(hours): 15 Hours of missing data: 32 Page 45 of 48

Attachment 10.2 Carbon 14 Supplemental Information Page 46 of 48

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.

In June 2009, the NRC provided revised guidance in Regulatory Guide 1.21, Measuring,Evaluatingand Reporting Radioactive Materialin 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, 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, 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 (Estimationof Carbon-i4 in Nuclear Power Plant Gaseous Effluents, 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 Characterizationof 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 47 of 48

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 0.009 mRem 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 5 mRem reasonably achievable (ALARA)

Round trip flight from New York City to Los Angeles 5 mRem Medical X-ray 10 mRem EPA limit for dose to the public from the commercial nuclear fuel cycle 25 mRem Food and water consumed throughout the course of one year 30 mRem NRC limit for dose to the public from nuclear power plants 100 mRem Mammogram 100 mRem Average annual exposure for a nuclear power plant worker 120 mRem Average annual exposure from background radiation 300 mRem CT scan 1,000 mRem NRC's annual limit for occupational exposure 5,000 mRem Cardiac catheterization or coronary angiogram 5,000 mRem

  • Coal is naturally radioactive.

Sources: U.S. EnvironmentalProtectionAgency, Health Physics Society.

Page 48 of 48

Retrieved from "https://kanterella.com/w/index.php?title=ML12128A194&oldid=2462689"