CP-201100563, Transmittal of Year 2010 Radioactive Effluent Release Report

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Transmittal of Year 2010 Radioactive Effluent Release Report
ML11116A058
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/20/2011
From: Flores R, Madden F
Luminant Generation Co, Luminant Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201100563, TXX-11047
Download: ML11116A058 (49)
v • d • e


Text

Luminant Rafael Flores Senior Vice President

& Chief Nuclear Officer Rafael.flores@Luminant.com Luminant Power P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201100563 Log# TXX-11047 Ref. #

Tech. Spec. 5.6.3 April 20, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF YEAR 2010 RADIOACTIVE EFFLUENT RELEASE REPORT

Dear Sir or Madam:

In accordance with Comanche Peak Nuclear Power Plant Unit 1 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, 2010 through December 31, 2010.

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 Bill Moore at (254) 897-8222.

Sincerely, Luminant Generation Company LLC Rafael Flores By:

Area W. Madden Director, Oversight & Regulatory Affairs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance UB~/8 Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre South Texas Project
  • Wolf Creek

U. S. Nuclear Regulatory Commission TXX-11047 Page 2 04/20/2011 Enclosures 2010 Radiological Effluent Release Report c -

E. E. Collins, Region IV B. Singal, NRR Resident Inspectors, Comanche Peak

CPNPP CoacePa ula oe ln 2010 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2010 - December 31, 2010 Prepared By:

David Valentine Reviewed By:

Jim Stevens Approved By:

Bill Moore Date:

3/28/11 Date:

3/28/11 Date:

3/28/11 Page 1 of 47

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 40CFR 190 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 47

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 47

ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPNPP Comanche Peak Nuclear Power Plant ECL Effluent Concentration Limit 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 47

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, 2010, through December 31, 2010.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2010 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. 0.2 on page 46 provides more detail about C-14.

Gaseous Effluents:

A summary of all the radioactive gaseous releases to the environment during 2010:

Gaseous Waste 2010 2009 Comments Tritium 43.21 Ci 56.2 Ci 1

C-14 Activity 25.48 Ci N/A 2

Total Fission and Activation Activity 3.89 Ci 5.08 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 4.18E-2 mRad 4.79E-4 mRad Calculated Beta Air Dose 8.51 E-4 mRad 1.10e-3 mRad Total Whole body dose 0.11 mRem 0.0789 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 47

4. Despite the inclusion of C-14, total whole body dose is very low (0.71% 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. Because neither unit had fuel defects during 2010, most of the released activity and associated dose was significantly lower than those during 2009.

Liquid Effluents:

A summary of all the radioactive liquid releases to the environment during 2010-Liquid Waste 2010 2009 Comments Total Activity (excluding tritium) 16.4 mCi 3.75 mCi 1

Tritium Activity 1340 Ci 1623 Ci Total Whole Body Dose 0.155 mRem 0.129 mRem 1

Total Volume Released 28,005,284 Gal 955,350,066 Gal 2

Comments

1. The increase in activity and dose in 2010 was due to issues with the liquid waste processing equipment from March to June. Changes in media and processing methodology solved the problem and restored processing efficiency. Despite this, total liquid waste released in 2010 was very low.

2 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 discharge to Squaw Creek Reservoir. A monthly composite sample of from the LVW is analyzed quarterly for activity. Normally, this waste water does not contain any radionuclides.

However, in late 2009, the 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.

Page 6 of 47

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. The individual percent recoveries are listed below:

Meteorological Data Recovery Channel

% Recovery Wind Speed 98.7 Wind Direction 99.0 Delta Temperature A 95.4 Delta Temperature B 95.4 Monitors OOS > 30 Days During 2010 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

ODCM Changes There were no changes to the ODCM in 2010. The changes to implement C-14 dose calculations will be part of the 2011 report.

Solid Waste Summary of the solid waste production Total Waste 2010 2009

% Error Shipped (m3) 476 168 25%

Shipped (Ci) 18.9

.175 25%

Buried (m3) 65.6 28.5 25%

Buried (Ci) 18.9 2.34 25%

Comments The reason for the fluctuation in waste volume and activity has two elements including outage timing and the formation of the Texas Low Level Waste Compact Commission. These outage dates combined with the formation of the Texas Compact Commission in the April/May time frame of 2009 that effectively suspended all waste shipments pending approval of an export permit. The waste export permit was approved in September 2009 allowing waste to be shipped. As a result, shipment of waste generated during the late spring and summer of 2009 leading up to 2RF 11 and waste from 2RF1 1 was not started until very late in 2009 continuing into 2010. This accounts for the majority of the waste volume change observed (see table 9.10, item b).

Also, in 2010, the decision was made to dispose of 4 containers of Class A resin that had accumulated since the closure of Barnwell, SC in July 2008. These containers accounted for the majority of the activity disposed of in 2010 (see table 1, item a).

Page 7 of 47

Groundwater Tritium CR-2010-006694 documented some positive indications of tritium in the seepage Sump near the water treatment plant and in the A and C Waste Monitoring Basins. 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. The net result from these positive samples is SCR water being returned to SCR.

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 47

1.2 Historical Trend Graphs Total Gaseous Fission and Activation Activity Released from CPNPP 996.9 228.00 148.00 100.00 d25.20 0

13.90 U)

C 0

=

10.00 0

5.6 5.08 02.60 1.00 0.10 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Year 2006 2007 2008 2009 2010 Total Gaseous Tritium Released from CPNPP 90.00 80.00 70.00

-60.00 C0 50.00 UM

'A 40.00 0

0 40.0 (A

CD 30,00 20.00 10.00 0.00 58.50 I61.27 m.55....

56.2 439 43 40.50432 llll~ il ll9.60 1996 1997 1998 1999 2000 2001 2002 2003 Year 2004 2005 2006 2007 2008 2009 2010 Page 9 of 47

Total Whole Body Dose due to Gaseous Activity released from CPNPP 0.12 0.11 0.11 0.10 0.09 0.08 0.08 0.08 0.08 0.08

.0 U)

~0

.50.0 0.040 0.02 9f 9

0.00r p

i 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Total Volume Liquid Effluents Released from CPNPP 100000000 10000000 E

1000000 100000 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Page 10 of 47

Total Activity (Excluding H3) Released in Liquid Effluents from CPNPP 400.00 350.00 300.00 250.00 E

200.00 3

150,00 100.00 50.00 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Total Curies of Tritium Released in Liquid Effluents from CPNPP 3000 2500 2000 0

1500 1000 500 0

S 1623 1 4 5 5 1 5 i 1 3 9 1 4 3 1 4 8 0 1 5 2 o1O40 l~

llll l1080 986I I

1996 1997 1998 1999 2000 2001 2002 2Ye3 Year 2004 2005 2006 2007 2008 2009 2010 Page 11 of 47

Total Whole Body Dose Due to Liquid Effluents Released from CPNPP 0.16 0.15 A 4A 0.14 0.12 0,10 0.08 0

0.06 0.04 0.02 0.00 I

0.13 0.13 I U

I 0.110

.11 0.10 0.1001 o~~o_.....0i i

0.09j 0.09 II II II L!

I-II i

m m

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Total Volume of Solid Radwaste Buried from CPNPP 200.00 180.00 180.00 160.00 140.00 120.00 E

6100,00 90.20 E

80.00 0

65.6 60.00 52.20 40.0.6 40.00 34.00 27.10 27.90 28.5 200 4 0 1

019.20 1870 193*

1.(

0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Page 12 of 47

Total Curies of Solid Radwaste Buried from CPNPP 1800 1620 1600 1400 1200

..ii,,

"5800 600 55-29 47447 400 361 190 200 t49 12.34 18*9 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 Year Page 13 of 47

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 [tCi/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 47
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)

  • YXj 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),

Ci

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

V

= volume of resins in the pond (gallons), and 264

= conversion factor (jtCi/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.OE-04 ýtCi/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 47

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.

For releases from Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and 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 47

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 10.2 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. No abnormal or unplanned liquid or gaseous effluent releases occurred during 2010. 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 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 Page 17 of 47

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 2010 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 activities 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 3.47E-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 47

7.0 METEROLOGICAL DATA 7.1 Meteorolo2ical Monitoring Pro2ram In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 2010, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 10. During 2010, the goal of >90%

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

Meteorological Data Recovery Channel

% Recovery Wind Speed 98.7 Wind Direction 99.0 Delta Temperature A 95.4 Delta Temperature B 95.4 8.0 RELATED INFORMATION 8.1 Operability of Liquid and Gaseous Monitorin2 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 no revisions to the ODCM.

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 2010 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 2010 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 Page 19 of 47

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 Radiolo2ical 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 No normal, unplanned gaseous effluent releases occurred during 2010.

8.5.2 Abnormal, Unplanned Gaseous Effluent Release No abnormal, unplanned gaseous effluent releases occurred during 2010.

8.5.3 Abnormal, Unplanned Liquid Effluent Releases No abnormal, unplanned liquid effluent releases occurred during 2010.

8.6 Resin Releases to the LVW Pond A total of 364 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 2010 is 1.43E-3 Curies, consisting of Co-58, Co-60, Cs-134, 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.20 of 47

8.8 Groundwater Tritium monitorin2 Program Samples of perched groundwater are taken quarterly in accordance with the site groundwater tritium monitoring program. During 2010, samples from the Water Production Plant seepage sump (storm drain) had positive values for tritium as listed in the table below. These values are well below the state reportable limit of 20,000 pCi/L. The source of the tritium is from a small leak of Squaw Creek Reservoir 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.

The other positive sample was in waste monitoring basin A Leachate. This residual activity is from repairs the outer liner (CR 2008-3781). Water was intentionally transferred from the ponds to the space between the inner and outer liner in order to perform ultrasonic leak testing of the outer liner. Pond water was used because it had a lower concentration of tritium than the reservoir.

Repairs to the liners were completed and the sample results of the Pond Leachate sample points are listed below. The activity has steadily decreased during the year and was undetectable during quarter 4.

This has been documented in CR-09-000794, CR-09-001351, and CR-10-006694.

Tritium Results in pCi/L Pond A Date Seepage Sump Leachate Feb-10 2950 OOS Apr-10 6450 3620 Aug-10 2690 2900 Nov-10 5770

<mda 6.11 Nonroutine planned release There were no unplanned releases during 2010.

Page 21 of 47

SECTION 9.0 EFFLUENT TABLES Page 22 of 47

Table 9.1 Site Liquid and Gaseous Batch Release Summary (2010)

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

1. Number of batch releases 22 18 7

6 53

2. Total time period for Batch releases

( Minutes) 6.61E+03 5.70E+03 2.09E+03 1.91E+03 1.63E+04

3. Maximum time period for a batch release

( Minutes )

3.35E+02 3.39E+02 3.15E+02 3.29E+02 3.39E+02

4. Average time period for a batch release

( Minutes) 3.OOE+02 3.17E+02 2.98E+02 3.18E+02 3.08E+02

5. Minimum time period for a batch release

( Minutes) 1.20E+02 2.62E+02 2.55E+02 3.05E+02 1.20E+02

6. Average stream flow during periods of release of liquid Effluent into a flowing (GPM) 3.84E+05 7.43E+04 2.93E+04 2.46E+04 5.12E+05 stream B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual
1. Number of batch releases 33 32 26 28 119
2. Total time period for batch releases

( Minutes) 1.21E+04 1.15E+04 9.15E+03 9.76E+03 4.24E+04

3. Maximum time period for a batch release

( Minutes) 4.35E+02 1.35E+03 3.83E+02 4.30E+02 1.35E+03

4. Average time period for a batch release

( Minutes) 3.65E+02 3.58E+02 3.52E+02 3.49E+02 3.57E+02

5. Minimum time period for a batch release

( Minutes) 2.78E+02 1.08E+02 2.85E+02 2.72E+02 1.08E+02 Page 23 of 47

Table 9.2 Site Abnormal Liquid and Gaseous Batch Release Summary (2010)

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

1. Number of batch releases 0

0 0

0 0

2. Total time period for Batch releases (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
3. Maximum time period for a batch release (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
4. Average time period for a batch release (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
5. Minimum time period for a batch release (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
6. Total Activity for all releases (Curies) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals
1. Number of batch releases 0

0 0

0 0

2. Total time period for batch releases (Minutes) 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00
3. Maximum time period for a batch release (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
4. Average time period for a batch release (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00
5. Minimum time period for a batch release (Minutes) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
6. Total Activity for all releases (Curies) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Page 24 of 47

Table 9.3 Site Gaseous Effluents - Summation of All Releases (2010) 1ST 2ND 3RD 4TH Units Quarter Quarter Quarter Quarter Type of Effluent A. Fission And Activation Gases

1. Total Release
2. Average Release rate for period
3. Percent of Applicable Limit B. Radioiodines
1. Total Iodine-131
2. Average Release rate for period
3. Percent of Applicable Limit C. Particulates
1. Particulates ( Half-Lives > 8 Days)
2. Average Release rate for period
3. Percent of Applicable Limit D. Tritium & C14
1. Total H-3 Release
2. Total C-14 Release
3. Average Release rate for period
4. Percent of Applicable Limit E. Gross Alpha
1. Total Release
2. Average Release rate for period Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies Curies uCi/sec 1.20E+00 1.53E-01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.22 6.29 1.46E+00 1.52E+00 1.92E-01 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 13.06 5.72 2.38E+00 5.18E-01 6.58E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 13.33 6.74 2.55E+00 6.56E-01 8.32E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 11.60 6.73 2.33E+00
  • g Year Totals 3.89E+00 4.94E-01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 43.21 25.48 8.72E+00 Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 uCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
  • Applicable limits are expressed in terms of dose.

Estimated Total Error For All Values Reported Is < 1.0%

Page 25 of 47

2010 Table 9.4 Site Gaseous Effluents - Ground Level Releases (2010)

Continuous Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases No Nuclides Found Curies N/A N/A N/A N/A N/A 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 & C-14 H-3 Curies 5.204 13.03 13.31 11.54 43.08 C-14 Curies 1.89 1.72 2.02 2.02 7.64 Gross Alpha No Nuclides Found Curies N/A N/A N/A N/A N/A Page 26 of 47

2010 Table 9.4 (cont)

Site Gaseous Effluents - Ground Level Releases (2010)

Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Ar-41 Curies 1.12E-01 1.09E-01 8.64E-02 1.11E-01 4.22E-01 Kr-85m Curies 0.OOE+00 1.74E-05 0.OOE+00 O.OOE+00 1.74E-05 Kr-85 Curies 1.09E+00 1.39E+00 4.29E-01 5.42E-01 3.45E+00 Xe-131m Curies O.OOE+00 1.61E-04 0.OOE+00 O.OOE+00 1.61E-04 Xe-133m Curies O.OOE+00 3.39E-04 0.00E+00 O.OOE+00 3.39E-04 Xe-133 Curies 1.35E-03 1.43E-02 3.30E-03 2.69E-03 2.16E-02 Xe-135m Curies O.OOE+00 1.50E-04 0.00E+00 O.OOE+00 1.50E-04 Xe-135 Curies O.00E+00 2.67E-03 O.OOE+00 O.OOE+00 2.67E-03 Total For Period Curies 1.20E+00 1.51E+00 5.18E-01 6.56E-01 3.89E+00 lodines No Nuclides Found N/A N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A N/A Tritium & C-14 H-3 Curies 2.54E-02 2.45E-02 2.87E-02 5.49E-02 1.34E-01 C-14 Curies 4.40 4.00 4.72 4.71 17.84 Gross Alpha No Nuclides Found N/A N/A N/A N/A N/A

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

Page 27 of 47

Table 9.5 Site Liouid Effluents - Summation Of All Releases (2010)

A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha)
2. Average diluted concentration during period
3. Percent of Applicable Limit B. Tritium
1. Total Release
2. Average diluted concentration during period
3. Percent of Applicable Limit C. Dissolved and Entrained Gases
1. Total Release
2. Average diluted concentration during period
3. Percent of Applicable Limit D: Gross Alpha Radioactivity
1. Total Release Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Curies 1.89E-03 1.38E-02 3.69E-04 3.68E-04 1.64E-02 uCi/ml Curies uCi/ml Curies uCi/ml 1.85E-11 5.49E-06 8.OOE+02 7.83E-06 7.83E-01 3.60E-03 3.52E-1 1 1.76E-05 6.91E-10 5.44E-04 2.23E+02 1.12E-05 1.12E+00 6.16E-04 3.09E-11 1.55E-05 4.71E-11 4.17E-06 6.76E+01 8.63E-06 8.63E-01 0.OOE+00 0.OOE+00 0.OOE+00 5.62E-1I1 2.25E-05 2.45E+02 3.74E-05 3.74E+00 0.OOE+00 O.OOE+00 0.OOE+00 8.13E-10 1.34E+03 6.51E-05 4.2 1E-03 6.62E-1I E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Liters 1.04E+08 1.34E+06 4.90E+05 4.32E+05 1.06E+08 Liters 1.02E+1 1 1.99E+10 7.83E+09 6.55E+09 1.36E+11

  • Applicable limits are expressed in terms of dose. -

Estimated Total Error For All Values Reported Is < 1.0%

Page 28 of 47

Continuous Mode Nuclides Released Fission & Activation Products No Nuclides Found Tritium H-3 Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity Units Curies Table 9.6 Site Liquid Effluents (2010)

Quarter 1 Quarter 2 Quarter 3 N/A N/A N/A 1.38E+00 O.OOE+00 O.OOE+00 N/A N/A N/A 0

0 0

Quarter 4 N/A 0.OOE+00 N/A 0

Annual N/A 1.38E+00 N/A 0

Page 29 of 47

Table 9.6 (cont.)

Site Liquid Effluents (2010)

Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Fission & Activation Products Cr-51 Curies O.OOE+00 3.67E-04 0.00E+00 O.OOE+00 3.67E-04 Mn-54 Curies O.00E+00 3.30E-05 1.24E-06 O.OOE+00 3.42E-05 Fe-55 Curies O.00E+00 0.OOE+00 4.85E-05 2.55E-04 3.03E-04 Fe-59 Curies O.OOE+00 1.96E-05 O.OOE+00 O.00E+00 1.96E-05 Co-57 Curies 1.17E-05 4.08E-05 O.OOE+00 0.00E+00 5.26E-05 Co-58 Curies 1.57E-03 1.22E-02 2.68E-04 9.62E-05 1.41E-02 Co-60 Curies 1.90E-04 1.13E-03 4.99E-05 1.33E-05 1.39E-03 Sr-89 Curies 0.OOE+00 0.OOE+00 8.09E-07 4.25E-06 5.06E-06 Nb-95 Curies 0.OOE+00 5.63E-06 0.OOE+00 0.00E+00 5.63E-06 Sb-125 Curies 1.20E-04 O.00E+00 0.OOE+00 0.OOE+00 1.20E-04 Cs-137 Curies 2.04E-06 O.00E+00 0.OOE+00 0.OOE+00 2.04E-06 Total For Period Curies 1.89E-03 1.38E-02 3.69E-04 3.68E-04 1.64E-02 Tritium H-3 Curies 7.98E+02 2.23E+02 6.76E+01 2.45E+02 1.33E+03 Dissolved And Entrained Gases Kr-85 Curies 2.17E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.17E-03 Xe-133 Curies 1.41E-03 6.16E-04 0.00E+00 0.OOE+00 2.03E-03 Xe-135 Curies 1.62E-05 0.OOE+00 0.OOE+00 0.00E+00 1.62E-05 Total For Period Curies 3.60E-03 6.16E-04 0.OOE+00 0.00E+00 4.21E-03 Gross Alpha Radioactivity 0

0 0

0 0

  • Zeroes in this table indicate that no radioactivity was present at detectable levels Page 30 of 47

Table 9.7 Dose to a member of the public due to Liquid Releases (2010)

Organ Total Body Bone Thyroid Kidney Lung Liver GI-Lli Cumulative Doses per Quarter

% of Tech

% of Tech Limit Units Quarter 1 Spec Limit Quarter 2 Spec Limit 1.50E+00 mRem 3.94E-02 2.63E+00 4.02E-02 2.68E+00 5.00E+00 mRern 4.64E-06 9.29E-05 1.02E-07 2.04E-06 5.OOE+00 mRem 3.94E-02 7.87E-01 4.02E-02 8.03E-01 5.OOE+00 mRem 3.94E-02 7.87E-01 4.02E-02 8.03E-01 5.OOE+00 mRem 3.94E-02 7.87E-01 4.02E-02 8.03E-01 5.00E+00 mRem 3.94E-02 7.87E-01 4.02E-02 8.04E-01 5.00E+00 mRem 3.94E-02 7.88E-01 4.03E-02 8.07E-01

% of Tech Quarter 3 Spec Limit 3.97E-02 2.64E+00 2.21E-07 4.43E-06 3.97E-02 7.93E-01 3.97E-02 7.93E-01 3.97E-02 7.93E-01 3.97E-02 7.93E-01 3.97E-02 7.93E-01

% of Tech Quarter 4 Spec Limit 3.56E-02 2.37E+00 1.24E-06 2.49E-05 3.56E-02 7.11E-01 3.56E-02 7.11E-01 3.56E-02 7.11E-01 3.56E-02 7.11E-01 3.56E-02 7.11E-01 Cumulative Doses per Year Organ Total Body Thyroid Bone Liver Kidney Lung GI-Lli Bone Liver Thyroid Kidney Lung GI-Lli Total Body Tech Spec Limit 2.50E+01 7.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 1.00E+01 1.00E+01 1.00E+01 1.00E+01 1.OOE+01 1.00E+01 3.OOE+00 Units mRem mRem mRem mRem mRem mRem mRem mRem rnRem mRem mRem mRem mRem mRem Year to Ending Date 1.55E-01 1.55E-01 6.21E-06 1.55E-01 1.55E-01 1.55E-01 1.55E-01 6.21 E-06 1.55E-01 1.55E-01 1.55E-01 1.55E-01 1.55E-01 1.55E-01

% of Tech Spec Limit 6.19E-01 2.06E-01 2.48E-05 6.19E-01 6.19E-01 6.19E-01 6.20E-01 6.21E-05 1.55E+00 1.55E+00 1.55E+00 1.55E+00 1.55E+00 5.16E+00 1.02E+l 1 1.99E+10 7.83E+09 6.55E+09 Receptor Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Liquid Receptor - Adult Limit 40CFR190.10 (a) TB 40CFR190.10 (a) Thyroid 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ Liq Annual Organ Dose Liq Annual Organ Dose Liq Annual Organ Dose Liq Annual Organ Dose Liq Annual Organ Dose Liq Annual Organ Dose Liq Annual TB Dose Total Dilution Volume for 1st Quarter Total Dilution Volume for 2nd Quarter Total Dilution Volume for 3rd Quarter Total Dilution Volume for 4th Quarter Page 31 of 47

Table 9.8 Air Dose Due To Gaseous Releases - Site (2010)

Cumulative Doses Per Quarter Type of Radiation Gamma Beta Type of Radiation Gamma Gamma Gamma Gamma Beta Beta Beta Beta Tech Spec Limit 5.00 10.00 Tech Spec Limit 10 10 10 10 20 20 20 20

% of Tech Units Quarter 1 SpecL Spec Limit

% of Tech Spec Limit

% of Tech Quarter 3 Spec Limit mRad 1.11E-04 2.23E-03 1.1OE-04 2.19E-03 8.50E-05 1.70E-03 1.09E-04 2.18E-03 mRad 2.61E-04 2.61E-03 3.22E-04 3.22E-03 1.18E-04 1.18E-03 1.49E-04 1.49E-03 Cumulative Doses Per Year

% of Tech Quarter 4 Spec Limit Units Year to Ending Date mRad mRad mRad mRad mRad mRad mRad mRad 4.15E-04 4.15E-04 4.15E-04 4.15E-04 8.50E-04 8.50E-04 8.50E-04 8.50E-04

% of Tech Spec Limit 4.15E-03 4.15E-03 4.15E-03 4.15E-03 4.25E-03 4.25E-03 4.25E-03 4.25E-03 Receptor Gas Receptor SB - Adult Gas Receptor SB - Teen Gas Receptor SB - Child Gas Receptor SB - Infant Gas Receptor SB - Adult Gas Receptor SB - Teen Gas Receptor SB - Child Gas Receptor SB - Infant Limit NG Annual Gamma Air Dose NG Annual Gamma Air Dose NG Annual Gamma Air Dose NG Annual Gamma Air Dose NG Annual Beta Air Dose NG Annual Beta Air Dose NG Annual Beta Air Dose NG Annual Beta Air Dose Page 32 of 47

Table 9.9 Dose to A Member Of The Public Due To Radioiodines, Tritium, C-14. and Particulates in Gaseous Releases (2010)

Cumulative Doses Per Quarter G

K L

L T

T B

Tech Organ Spec Units Quarter 1 Limit I-Lli 7.5 mRem 1.87E-02 idney 7.5 mRem 1.87E-02 iver 7.5 mRem 1.87E-02 ung 7.5 mRem 1.87E-02 hyroid 7.5 mRem 1.87E-02 otal Body 7.5 mRem 1.87E-02 one 7.5 mRem 5.85E-02 0/b of Tech Spec Limit 2.49E-01 2.49E-01 2.49E-01 2.49E-01 2.49E-01 2.49E-01 7.80E-01 0/b of Tech Quarter 2 Spec Limit 2.86E-02 3.81E-01 2.86E-02 3.81E-01 2.86E-02 3.81E-01 2.86E-02 3.81E-01 2.86E-02 3.81E-01 2.86E-02 3.81E-01 5.32E-02 7.09E-01 Quarter 3 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 6.27E-02

% of Tech Spec Limit 4.11E-01 4.11E-01 4.11E-01 4.11E-01 4.11E-01 4.11E-01 8.36E-01

%/b of Tech Quarter 4 Spec Limit 2.84E-02 3.79E-01 2.84E-02 3.79E-01 2.84E-02 3.79E-01 2.84E-02 3.79E-01 2.84E-02 3.79E-01 2.84E-02 3.79E-01 6.26E-02 8.35E-01 Page 33 of 47

Table 9.9 (cont)

Dose to A Member Of The Public Due To Radioiodines, TritiumC-14, and Particulates in Gaseous Releases (2010)

Cumulative Doses per Year Year to

% of Tech Organ Tech Spec Limit Total Body Thyroid Liver Kidney Lung GI-Lli Bone Liver Total Body Thyroid Kidney Lung GI-Lli Bone 25 75 25 25 25 25 25 15 15 15 15 15 15 15 Units mRem mRem mRem mRem mRem mRem mnRem mRem mRem mRem mRem mRem mRem mRem Ending Date 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 2.37E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 1.07E-01 2.37E-01 Spec Spec Limit 4.26E-01 1.42E-01 4.26E-01 4.26E-01 4.26E-01 4.26E-01 9.48E-01 7.10E-01 7.10E-01 7.10E-01 7.10E-01 7.10E-01 7.10E-01 1.58E-00 Receptor Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Gas Receptor SB - Child Limit 40CFR190.10 (a) TB 40CFR190.10 (a) Thyroid 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ Gas Annual Organ Dose Gas Annual Organ Dose Gas Annual Organ Dose Gas Annual Organ Dose Gas Annual Organ Dose Gas Annual Organ Dose Gas Annual Organ Dose Page 34 of 47

TABLE 9.10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2010 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

Shipped Shipped Buried Buried Percent

1. Type of Waste W

Ci m 3 Ci Error

a. Spent resins/filters 2.33E+01 1.85E+01 2.33E+01 1.85E+01

+/-25%

b. Dry active waste 4.53E+02 4.01E-01 4.23E+01 3.91E-01

+/- 25%

c. Irradiated components N/A
d. Other (oil/miscellaneous liquids sent to processor for volume N/A reduction)

TOTAL 4.76E+02 1.89E+01 6.56+01 1.89+01

+/- 25%

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 Nuclide

% Abund.

Activity waste)

(Ci)

Ni-63 41.22 7.63E+00 Fe-55 22.13 4.1OE+00 Cs-137 10.94 2.02E+00 H-3 9.42 1.74E+00

a. Spent resins/filters Co-60 7.78 1.44E+00 Cs-134 6.70 1.24E+00 C-14 0.17 3.22E-02 Tc-99 LLD 1-129 LLD Other*

1.64 3.03EE-01 Total 100.00 1.85E+01 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 35 of 47

TABLE 9.10 (cont.)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2010 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 41.18 1.65E-01 Ni-63 26.98 1.08E-01 Co-58 15.02 6.02E-02 Co-60 13.65 5.47eE-02

b. Dry active waste H-3 0.09 3.45E-04 C-14 LLD Tc-99 LLD 1-129 LLD Other*

3.08 1.24E-02 Total 100.00 4.01E-01

  • Nuclides representing <1% of total shipped activity: Cr-5 1,Mn-54,Co-57,Nb-95,ZR-95,Sb-1 25,Cs-1 34,Cs-13 239/240,Am-24 1,Cm-242,Cm-243/244.
2. Estimate of Major Nuclide Composition (by type of Nuclide

% Abund.

Activity waste)

(Ci)

d. Other (oil/miscellaneous liquids sent to processor for volume reduction)
3. Solid Waste Disposition (Mode of Transportation: Truck)

Waste Type Waste Number of Destination Class Container Type Shipments Destination

a. Resin/filters A

Type A 4Energy Solutions Clive, UT

b. Dry active waste A

General Design 7Energy Solutions Oak Ridge, TN B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 7,Ce-144,Pu-238,Pu-0 N/A N/A Page 36 of 47 0.1 2010 Meteorological Joint Frequency Table Page 37 of 47

15-MAR-11 09:39 R.G. 1.21 JOINT FREQUENCY TABLE T.

U.

ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-10 00:00 TO 31-DEC-10 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 N

1 8

21 16 5

0 51 NNE 0

4 16 3

0 0

23 NE 3

15 S

2 0

0 25 ENE 3

12 9

4 0

0 28 E

0 5

2 0

0 0

7 ESE 1

14 14 4

0 0

33 SE 0

17 42 20 0

0 79 SSE 0

20 99 47 4

0 170 S

2 18 57 45 5

1 128 SSW 2

13 22 6

0 0

43 SW 0

11 7

1 0

0 19 WSW 0

3 5

6 1

0 Is W

0 0

I 0

0 0

1 WNW 0

0 0

0 0

0 0

NW 1

0 3

is 5

0 20 mm 0

3 20 22 4

1 50 VARIABLE 17 0

0 0

0 0

17 Total 130 143 323 187 24 2

709 Periods of oalm(houre):

0 ilours of miasing data:

3 Page 38 of 47

Is-MAR-lI 09:39 R.O.

1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-10 00:00 TO 31-DEC-10 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

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

W'NW NNW 2

13 14 2

6 8

12 10 7

11 12 18 14 6

4 7

0 3

3 13 3

5 7

2 2

27 33 43 19 13 7

1 0

11 16 1

8 5

I 0

0 6

44 45 10 4

3 2

1 23 16 8

2 0

0 0

1 0

2 20 2

0 0

1 0

8 0

0 45 0

23 22 21 t0 15 45 98 124 38 23 Is 4

4 47 54 VARIABLE 12 0

0 16 Total 35 142 209 169 52 0

607 Periods of calm(hours):

Hours of missing data:

1 2

Page 39 of 47

15-MAR-11 09:39 R.0. 1.21 JOINT FREQUENCY TABLE T.

U.

ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

01-JAN-10 00:00 1TO 31-DEC-10 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

6 15 6

8 a

0 43 NNE 4

12 9

5 0

0 30 NE 7

9 5

1 0

0 22 ENE 5

6 3

2 0

0 16 E

5 9

0 0

0 0

14 ESE 2

14 7

2 0

0 25 SE 6

16 31 7

0 0

60 SSE 1

19 47 42 8

3 120 S

3 10 46 41 23 0

123 SSW 0

12 23 12 7

0 64 SW 1

11 9

7 1

0 29 WSW 3

9 10 3

1 0

26 W

2 9

2 2

1 0

16 WNW 0

6 5

3 1

1 16 NW 2

2 7

12 4

6 33 NNW 4

10 20 17 i1 8

70 VARIABLE 15 6

0 0

0 0

21 Total 66 175 230 164 65 18 718 Periods of calm(hours):

0 Hours of missing data:

I Page 40 of 47

15-MAR-I1 09:39 A,.

1.21 JOINT FREQUENCY TABLE T.

U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-10 00:00 TO 31-DEC-10 23:59 STABILITY CLASS: D ELEVATION:

10 m.

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

)24 TOTAL N

t0 55 165 95 10 0

335 NNE 9

48 77 33 3

0 170 NE 13 40 55 15 1

0 122 ENE 8

36 31 16 1

0 92 E

8 72 20 4

1 0

105 ESE 24 135 68 4

0 0

231 SE 15 182 270 36 1

0 504 SSE 9

109 413 239 36 8

814 S

8 77 272 159 37 6

559 SSW 5

36 63 37 12 2

155 SW 12 25 Is 10 1

0 63 WSW 7

19 9

6 0

0 41 W

5 9

7 5

1 0

27 WNW 10 21 39 27 3

0 100 NW 2

22 42 78 25 9

178 NNW 6

33 104 18 25 4

330 VARIABLE 52 25 0

I 0

0 83 Total 201 944 1655 923 157 29 3909 Periods of calm(houra):

3 Hours of misslng data:

30 Page 41 of 47

15-MAR-l 09:39 R.G.

1.21 JOINT FREQUENCY TABLE T.

U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-10 00:00 TO 31-DEC-10 23t59 STABILITY CLASS: E ELEVATION:

10 m.

Wind Speed (mph) at 10 a. level Wind Direct ion N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

NW NV 1-3 4

8 4

5 7

17 25 17 15 1I 23 17 5

9 22 14 4-7 23 23 14 11 9

69 244 141 72 43 19 12 1I 32 64 21 5

6-12 29 13 13-18 0

19-?4 0

a

)24 TOTAL 0

64 0

44 4

0 0

0 22 0

I 4

160 275 122 69 19 17 10 30 45 24 2

0 0

2 19 4

3 S

0 0

0 0

0 0

0 0

1i 17 90 431 452 213 130 66 SO 31 77 136 68 4

0 3

0 6

0 3

0 9

0 VARIABLE 73 2

0 0

0 10 Total 280 817 324 66 0

2 1989 Periods of calf(hours):

4 Hours of missing dats:

I Page 42 of 47

15-MAR-1l 09:39 R.G.

1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

01-JAN-10 00:00 TO 31-DEC-10 23:59 STABILITY CLASS: F ELEVATION:

10 m.

Wind Spoed (mph) at 10 m.

lovel Wind Direotion N

WE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 1-3 2

0 0

1 0

4 11 lB 19 34 26 23 13 16 12 1

4-7 8-12 13-16 19-24

)24 TOTAL 0

2 0

0 0

7 72 40 18 22 7

12 7

10 37 2

0 0

0 0

0 14 14 7

9 2

4 0

3 9

1 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

2 3

0 1

0 11 97 79 47 65 36 39 20 29 58 5

VARIABLE 26 0

0 0

0 28 Total 206 238 64 12 0

0 520 Periods of calm(hours):

2 Hours of missing data:

0 Page 43 of 47

15-MAR-li 09:39 R.G.

1.21 JOINT FREQUENCY TABLE PAGE 7 OF T. 1). ELECTRIC CO0IPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 0I-JAM-1O 00:00 TO 31-DEC-10 23:59 STABILITY CLASS: G ELEVATION:

10 m.

Wind Speed (mph) at 10 m.

level Wind Direction NNE KE ENE E

ESE SE SSE S

SSW SW WSW w

WNW RW NNW 1-3 4-7 8-12 0

0 0

13-L8 0

19-24

)24 TOTAL 0

0 0

0 0

0 2

5 a

21 17 17 9

8 2

0 0

0 0

0 0

0 2

0 4

0 1

0 2

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 I

0 0

11 15 19 5

2 7

3 1

0 0

2 6

6 39 35 37 14 10 14 1

12 0

1 0

VARIABLE 7

0 0

0 0

0 7

Total 97 74 11 0

0 0

182 Pcriode of calm(houre):

I Hours of missing data:

0 Page 44 of 47 0.2 Carbon 14 Supplemental Information Page 45 of 47

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, 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, 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 (Estimation of Carbon-i 4 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 Characterization of Carbon-i 4 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 2010 Radioactive Effluent Release Report 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 2010 is well below the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yr per unit.

Page 46 of 47

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. Environmental Protection Agency, Health Physics Society.

Page 47 of 47

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