CP-201300487, Transmittal of Year 2012 Radioactive Effluent Release Report

Transmittal of Year 2012 Radioactive Effluent Release Report

ML13114A149
Person / Time
Site:	Comanche Peak
Issue date:	04/11/2013
From:	Madden F Luminant Generation Co, Luminant Power, Strategic Teaming & Resource Sharing (STARS)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201300487, TXX-13078
Download: ML13114A149 (51)

Text

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002

& Chief Nuclear Officer 6322 North FM 56 Rafael.flores@Luminant.com Glen Rose, TX 76043 Lumin ',,

T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201300487 Ref. #

Tech. Spec. 5.6.3 Log # TXX-13078 10CFR50.36a April 11, 2013 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 2012 RADIOACTIVE EFFLUENT RELEASE REPORT

Dear Sir or Madam:

In accordance with Comanche Peak Nuclear Power Plant Unit I 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, 2012 through December 31, 2012.

The tabular summaries of radioactive liquid and gaseous releases are provided in the format defined in Appendix B of Regulatory Guide 1.21, Rev. 1, dated June, 1974.

During this reporting period there were no revisions to the ODCM.

If there are any questions regarding this report, please contact Steve Dixon at (254) 897-5482 or Kerry Cooper at (254) 897-0462.

Sincerely, Luminant Generation Company LLC Rafael Flores By:

Fred W. Madden Director, Oversight & Regulatory Affairs A member of the STARS Alliance Callaway

• Comanche Peak Diablo Canyon

• Palo Verde

• San Onofre. South Texas Project - Wolf Creek

U. S. Nucdear Regutatory Commission TXX-13078 Page 2 04/11/2013 Enclosures

1.

2012 Radioactive Effluent Release Report c -

A. T. Howell, Region IV L. K. Gibson, NRR Resident Inspectors, Comanche Peak Comanche Peak 2012 Radioactive Effluent Release Report A

2012 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2012 - December 31, 2012 Prepared By:

David Valentine Reviewed By:

Don Rebstock Approved By:

Kerry Cooper Date 3/20/13 Date 3/20/13 Date 3/20/13 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 to a member of the public due to Liquid Releases 9.8 Dose Due to Gaseous Releases-Site 9.9 Dose to a Member of the Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases 9.10 Solid Waste and Irradiated Fuel Shipments 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, 2012, through December 31, 2012.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2012 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 2012:

Gaseous Waste 2011 2012 Comments Tritium 48.12 Ci 51.6 Ci 1

C-14 Activity 23.32 Ci 23.46 Ci 2

Total Fission and Activation Activity 3.73 Ci 1.27 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 6.2 1E-5 mRad 4.15E-04 mRad 4

Calculated Beta Air Dose 7.54E-05 mRad 3.08e-4 mRad 4

Total Whole body dose 0.10 mRem 0.11 mRem 5

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. The increase in dose is due to dry cask spent fuel storage operations.

5. 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 fuel defects during 2012.

Liquid Effluents:

A summary of all the radioactive liquid releases to the environment during 2012:

Liquid Waste 2011 2012 Comments Total Activity (excluding tritium) 6.56 mCi 13.8 mCi 1

Tritium Activity 2790 Ci 2430 Ci Total Whole Body Dose 0.149 mRem 0.171 mRem 1

Total Volume Released 1,155,673 Gal 18,733,509 Gal 2

Comments

1. The increased activity and dose for 2012 is attributed to waste water processing for 1 refueling outage, 1 forced outage, and dry cask storage operations. The slight increase in dose is consistent with the small increase in total activity released.

2. Explanation for the larger than normal total volume released during 2012: 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 quarterly composite sample from the LVW is analyzed quarterly for activity. Normally, this waste water does not contain any radionuclides.

Analysis of the Q2 LVW composite indicated a small concentration of tritium. Consequently, the volume discharged from the LVW had to be accounted for as radioactive liquid waste for that quarter resulting in a much larger than normal total annual liquid waste volume.

Page 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 2012 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

ODCM Changes There were no changes made to the ODCM during 2012.

Solid Waste Summary of the solid waste production Total Waste 2011 2012

% Error Shipped (m3) 667 230 25%

Shipped (Ci) 0.215 2.97 25%

Buried (m3) 70.7 46.8 25%

Buried (Ci) 0.149 2.98 25%

Comments The decrease in dry waste shipped was from the expiration of the Class A waste export permit (that allows the site to ship waste out of state) just prior to the U2 refueling outage. Consequently, much of the low level waste generated during the outage will not be shipped until 2013.

The increased curies were from the shipment of two containers of Class A resin. These resins contain significantly more activity than dry active waste (DAW). In 2011, only DAW was shipped.

Groundwater Tritium There were some positive indications of tritium in the seepage sump near the water treatment plant and in the LVW Pond A, B, and C Leachates. All of these samples were well below the state drinking water reportable criteria of 20,000 pCi/L and the environmental reportable criteria of 30,000 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 7 of 48

1.2 Historical Trend Graphs Total Gaeous Fison end AcIvao A ty A

Reisaed from CPNPP U6*

.as 1w00*

100.00 IW.

IOL 0.10 l14m0 2520 13.00 5.92 508 3*9 3.73 2.01

.0l0A.S 120?A lW I

=

M

=

=

2

=s 3

30iu R=

=0 200 11 C2M Total Gaseous Tritium Reley~d from CPNPP 90.00 80.00 70.00 60.00 Uo 50.00 S40.00 00 o

30.00 20.00 10.00 0.00 61.27 S55.80 56.2 51.6 49.10 A

43.90

~43.60432 40.50 29.60

-l- -

J

'1 199 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Year Page 8 of 48

Total Whole Body Dose due to Gaseous Activity released from CPNPP 0.121]

0 0.11 0.11 0.11 0.10 0.09 0.08 0.08

.o....g..

0.0 E 0.08 0.06 0-.0 Ce 0.06 0

0.05 0.05 0,0 0.04 0.400 0.02 0.00 0.04 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Year I

I Page 9 of 48

Total Actiht (2clduing H3) Raleged In Uqtid Efl~usnt Wor CPUPP 353.00 3ADO 2mm 232.10 m

m 110.00 1146 108.70 s_

21

.66 7.100 16 136 m

som 0Db IM 1

IMT IM 2d00 2001 20M 2003 24 In 05 3206 2007 00 00 O 211 212 Total Cud.. of Tdflum PAhmeud In ~ift E1 uerds *ova CPwpI N

I IM ¶uv IM 10m uO 2oa 202 2003 2004 2M0 3007 2W? 2am 2W D¶oMI2 Yew Page 10 of 48

Total Whole Body Dose Due to Liquid Effluents Released from CPNPP 1.00 0.90 080 0.70

?

0.60 0

, 0.50 0

0.40 0.30 0.20 0.0 0.009

,1 0.1 0.10 0.09 0.10 0.0g 0.11 0.11 0.10 0.4 01

.3 01 4

0.10 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Year Totaltm o1w 01601W Radwafte ~3uded from CPNPP 20MOD IO~

im13 i trntw un u o4tw wmrnzo9 nt mt i

aw-Year Page 11 of 48

Totel Cures of Solid Radwasta Buled forn CPNPP 1600-1620 1600-1400-1200 1150 400 2

400 255 24 100 I.

mr II ii 1=6 1997 IWS 11g 2000 0

2002 2003 2J4 2W6 2W006 T7 2004 2000 2010 2011 2012 Yeaw Page 12 of 48

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 VCi/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 13 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)

• yj 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 ([iCi/mL),

V

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

= conversion factor (gCi/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 gCi/mnL 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 14 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, Fe-55, and Ni-63 by a contract laboratory. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.

For batch releases of powdex resin to the LVW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques 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, Fe-55, and Ni-63 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 15 of 48

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 or unplanned releases are defined as the unintended discharge of a volume of liquid or airborne radioactivity to the environment. There were no abnormal (monitored) unplanned gaseous effluent releases during 2012.

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 16 of 48

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 2012 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 3.54E-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.

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

Page 17 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 2012, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 10. During 2012, the goal of >90%

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

I Meteorological Data Recovery I

Channel

% Recovery Wind Speed 99.8 Wind Direction 99.5 Delta Temperature A 99.7 Delta Temperature B 99.7 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 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 2012 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 2012 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 Page 18 of 48

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 were no normal, unplanned gaseous effluent releases occurred during 2012.

8.5.2 Abnormal, Unplanned Gaseous Effluent Release No abnormal, unplanned gaseous effluent releases occurred during 2012.

8.5.3 Abnormal, Unplanned Liquid Effluent Releases No abnormal, unplanned liquid effluent releases occurred during 2012.

Page 19 of 48

8.6 Resin Releases to the LVW Pond A total of 676 ft 3 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 2012 is 2.08e-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 1 OCFR50.59 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 48

8.8 Groundwater Tritium monitoring Program Seepage Sump Samples of perched groundwater are taken quarterly in accordance with the site groundwater tritium monitoring program. During 2012, samples from the Water Production Plant seepage sump (storm drain) had positive values for tritium as listed in the table below.

During 2012, considerable effort was made to locate the source of the seepage sump tritium and is documented in CR-2012-005813. Because CPNPP discharges its effluents into Squaw Creek Reservoir (SQR), there is always a low level background concentration of tritium in the SQR water. Essentially the seepage sump is discharging diluted Squaw Creek Reservoir water back to Squaw Creek Reservoir.

CR-2012-005813 summarized the response to an INPO AFI regarding a long standing unidentified leak of tritium into a storm water collection basin. The investigation into the source of the leak revealed that it was most likely due to contaminated soil from rainout/washout from permitted gaseous releases, processed water leaks from 2000 and lake water being used on site during post construction activities. An analysis of rainwater performed in EV-CR-2010-008111-8 did not show tritium values above MDA and is not proved to be a source. The remaining two likely sources are from processed water already permitted for release to the lake. As such, they do not exceed any regulatory limits and are not considered licensed material per NEI 07-07.

Previous hydrogeology studies performed by Pastor, Behling and Wheeler LLC, showed that this perched water sits above an impermeable layer of bedrock. This prevents the migration of the tritiated perched water into the Twin Mountain Aquifer and a potential new pathway to drinking water sources but is re-routed back to Squaw Creek Lake. Groundwater monitoring wells below the perched layer have not identified any tritium above the MDA and confirm the claims of the hydrogeology study. Based on this information and the guidance in NEI 07-07, there is no requirement for notification to the NRC or local officials and no requirement for remediation as it is not considered licensed material. Continued monitoring of the catch basin will occur as part of the Groundwater Monitoring Program (STA-654) and any new sources of tritium or increase in the activity will be evaluated and remediated as necessary.

Leachate Basins A,B, & C 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.

These basins receive 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 for drinking water and 30,000 pCi/L for environmental. The source of the tritium is from SQR.

Page 21 of 48

Tritium Results in pCi/L Date Seepage Pond A Pond B Pond C Sump Leachate Leachate Leachate 13-Mar 2210

<MDA

<MDA

<MDA 13-Jun 2460 5320 2030

<MDA 15-Aug 2570 7740 OOS 1170 5-Dec 4550 17900 OOS

< MDA Page 22 of 48

SECTION 9.0 EFFLUENT TABLES Page 23 of 48

Table 9.1 Site Liouid and Gaseous Batch Release Summary (2012)

A. Liquid Releases

1. Number of batch releases

2. Total time period for Batch releases

3. Maximum time period for a batch release

4. Average time period for a batch release

5. Minimum time period for a batch release

6. Average stream flow during periods of release of liquid Effluent into a flowing stream Units Quarter I Quarter 2 Quarter 3 Quarter 4 Annual (Minutes)

(Minutes)

(Minutes)

(Minutes) 5 1.59E+03 3.30E+02 3.17E+02 3.OOE+02 9

2.83E+03 3.53E+02 3.14E+02 2.80E+02 10 3.11E+03 3.45E+02 3.11E+02 2.60E+02 23 7.19E+03 3.50E+02 3.12E+02 2.65E+02 47 1.47E+04 3.53E+02 3.13E+02 2.60E+02 (GPM )

1.78E+04 3.55E+05 4.33E+04 9.89E+04 1.22E+05 B. Gaseous Releases

1. Number of batch releases

2. Total time period for batch releases

3. Maximum time period for a batch release

4. Average time period for a batch release

5. Minimum time period for a batch release Units Quarter 1 30 (Minutes) 1.09E+04 (Minutes) 4.53E+02 (Minutes) 3.62E+02 (Minutes) 3.04E+02 Quarter 2 27 8.96E+03 3.92E+02 3.32E+02 2.41E+02 Quarter 3 30 9.47E+03 3.59E+02 3.16E+02 2.00E+02 Quarter 4 38 1.45E+04 1.15E+03 3.82E+02 1.48E+02 Annual 125 4.38E+04 1.15E+03 3.51E+02 1.48E+02 Page 24 of 48

Table 9.2 Site Abnormal Liquid and Gaseous Batch Release Summary (2012)

A. Liquid Releases

1. Number of Releases

2. Total Time For All Releases

3. Maximum Time For A Release

4. Average Time For A Release

5. Minimum Time For A Release

6. Total activity for all releases Units Quarter 1 0

(Minutes O.OOE+00 (Minutes) 0.OOE+00 (Minutes) 0.OOE+00 (Minutes O.OOE+00 (Curies) 0.OOE+00 Quarter 2 0

0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Q.OOE+00 Quarter 3 0

0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 Quarter 4 0

0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.QOE+00 Totals 0

0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 B. Gaseous Releases

1. Number of Releases

2. Total Time For All Releases

3. Maximum Time For A Release

4. Average Time For A Release

5. Minimum Time For A Release

6. Total activity for all releases Units Quarter 1 Quarter 2 Quarter 3 1

0 0

(Minutes) 0.00E+00 0.OOE+00 O.OOE+00 (Minutes) 0.OOE+00 0.00E+00 0.00E+00 (Minutes) 0.OOE+00 0.00E+00 0.OOE+00 (Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 (Curies) 0.OOE+00 O.00E+00 0.00E+00 Quarter 4 0

0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Totals 0

0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Page 25 of 48

Table 9.3 Site Gaseous Effluents - Summation of All Releases (2012)

Type of Effluent A. Fission And Activation Gases

1. Total Release

2. Average Release rate for period

3. Percent of Applicable Limit B. Radiolodines

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 Release

2. Average Release rate for period

3. Percent of Applicable Limit E. Gross Alpha

1. Total Release

2. Average Release rate for period Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec 5.69E-01 7.22E-02 0.OOE+O0 0.OOE+00

• .OE0 0.OOE+00 1.47E+01 1.86E+00 1.0 lE-01 1.28E-02

• .OE0 0.OOE+00 0.OOE+00 O.OOE+00 2.11E+01 2.67E+00 2.46E-01

3. 12E-02 0.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+00 2.26E+01 1.48E+00 3.53E-01 4.47E-02

• .OE0 0.OOE+00 O.OOE+00 0.OOE+00 1.68E+01 2.68E+00 Total 1.27E+00 1.61E-01 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 7.51E+01 8.64E+00 O.OOE÷00 O.OOE+Q0 0.OQE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+0O 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 26 of 48

Table 9.4 Site Gaseous Effluents - Ground Level Releases (2012)

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 8.37 14.90 16.22 11.78 51.26 C-14 Curies 1.87 1.83 1.88 1.46 7.04 Gross Alpha No Nuclides Found Curies N/A N/A N/A N/A N/A Page 27 of 48

Table 9.4 (cont)

Site Gaseous Effluents - Ground Level Releases (2012)

Batch Mode Nuclides Released Fission Gases Ar-41 Kr-85m Kr-85 Xe-131m Xe-133m Xe-133 Xe-135 Total For Period Iodines No Nuclides Found Particulates No Nuclides Found Tritium & C-14 H-3 C-14 Gross Alpha No Nuclides Found Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Total Curies Curies Curies Curies Curies Curies Curies Curies 9.46E-02 O.0OE+00 4.68E-01 O.OOE+00 O.OOE+00 6.53E-03 O.OOE+00 5.70E-01 9.38E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.96E-03 O.OOE+00 1.01E-01 N/A 1.04E-01 O.OOE+00 1.35E-01 O.OOE+00 O.OOE+00 7.OOE-03 O.OOE+00 2.46E-01 N/A 1.27E-01 5.70E-05 1.38E-01 8.36E-05 1.81E-03 7.95E-02 6.30E-03 3.53E-01 N/A 4.20E-01 5.70E-05 7.41E-01 8.36E-05 1.81E-03 1.OOE-01 6.30E-03 1.27E+00 N/A Curies N/A Curies N/A Curies 5.91E-02 Curies 4.36 Curies N/A N/A N/A N/A N/A 7.48E-02 4.26 9.05E-02 1.44E-01 3.68E-01 4.39 3.41 16.42 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 (2012)

Units Quarter Quarter Quarter Quarter Annual 1

2 3

4 A. Fission And Activation Products

1. Total Release (not including tritium, Curies 5.88E-04 2.25E-03 2.62E-03 8.37E-03 1.38E-02 gases, alpha)

2. Average diluted concentration during uCi/ml 1.25E-10 2.39E-11 2.26E-10 3.11E-10 6.86E-10 period

3. Percent of Applicable Limit B. Tritium

1. Total Release Curies 1.54E+02 5.94E+02 5.46E+02 1.14E+03 2.43E+03

2. Average diluted concentration during uCi/ml 3.27E-05 6.31E-06 4.70E-05 4.24E-05 1.28E-04 period

3. Percent of Applicable Limit C. Dissolved and Entrained Gases

1. Total Release Curies O.OOE+00 O.OOE+00 1.89E-04 1.53E-03 1.72E-03

2. Average diluted concentration during uCi/ml O.OOE+00 O.OOE+00 1.62E-11 5.67E-11 7.29E-11 period

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 3.66E+05 6.82E+07 7.31E+05 1.66E+06 7.10E+07 F. Volume of Dilution Water Used Liters 4.70E+09 9.41E+10 1.16E+10 2.69E+10 1.37E+11

• 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 (2012)

Continuous Mode Nuclides Released Units Quarter I 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 3.69E-01 O.OOE+O0 O.OOE+O0 3.69E-01 Dissolved And Entrained Gases No Nuclides Found Gross Alpha Radioactivity Curies Curies N/A N/A N/A 0

N/A N/A 0

0 0

0 Page 30 of 48

Table 9.6 (cont.)

Site Liquid Effluents (2012)

Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter Annual 1

2 3

4 Fission & Activation Products Mn-54 Curies 6.44E-06 7.97E-06 O.OOE+00 O.OOE+00 1.44E-05 Fe-55 Curies 3.28E-04 3.20E-04 7.28E-04 2.33E-03 3.71E-03 Co-57 Curies O.OOE+00 3.02E-05 6.41E-06 3.15E-06 3.98E-05 Co-58 Curies 1.94E-04 1.61E-03 3.47E-04 2.54E-03 4.69E-03 Co-60 Curies 5.14E-05 2.69E-04 1.35E-04 4.01E-05 4.96E-04 Ni-63 Curies O.OOE+00 O.OOE+00 1.38E-03 3.34E-03 4.72E-03 Nb-95 Curies 7.38E-06 O.OOE+00 O.OOE+00 O.OOE+00 7.38E-06 Sb-125 Curies O.OOE+00 9.97E-06 3.08E-05 1.20E-04 1.61E-04 Total For Period Curies 5.88E-04 2.25E-03 2.62E-03 8.37E-03 1.38E-02 Tritium H-3 Curies 1.54E+02 5.94E+02 5.46E+02 1.14E+03 2.43E+03 Dissolved And Entrained Gases Xe-133 Curies O.OOE+00 O.OOE+00 1.89E-04 1.49E-03 1.68E-03 Xe-135 Curies O.OOE+00 O.OOE+00 O.OOE+00 3.33E-05 3.33E-05 Total For Period Curies O.OOE+00 O.OOE+00 1.89E-04 1.53E-03 1.72E-03

• Zeroes in this table indicate that no radioactivity was present at detectable levels Page 31 of 48

Table 9.7 Dose to a member of the public due to Liquid Releases (2012)

Organ Total Body Thyroid Organ*

Bone Limit Units Quarter 1

Organ Total Body Thyroid Organ*

Bone Total Body Thyroid Organ*

Bone 1.50E+00 5.00E+00 5.OOE+00 5.OOE+00 Tech Spec Limit 2.50E+01 7.50E+01 2.50E+01 2.50E+01 3.OOE+00 1.OOE+01 1.00E+01 1.00E+01 mRem mRem mRem mRem 4.34E-02 4.34E-02 4.35E-02 1.19E-06 Cumulative Doses per Quarter

% of

% of Tech Quarter Tech Spec Limit 2

Spec Limit 2.90E+00 4.38E-02 2.92E+00 8.69E-01 4.38E-02 8.77E-01 8.70E-01 4.39E-02 8.77E-01 2.38E-05 9.37E-07 1.87E-05 Cumulative Doses per Year

% of Quarter Tech 3

Spec Limit 4.29E-02 2.86E+00 4.29E-02 8.58E-01 4.29E-02 8.58E-01 1.92E-04 3.85E-03 Year to Units Ending Date mRem 1.71E-01 mRem 1.71E-01 mRem 1.71E-01 mRem 6.63E-04 mRem mRem mRem mRem 0/c of Quarter Tech 4

Spec Limit 4.11E-02 2.74E+00 4.11E-02 8.21E-01 4.11E-02 8.22E-01 4.69E-04 9.37E-03 1.71E-01 1.71E-01 1.71E-01 6.63E-04 0/b of Tech Spec Limit 6.85E-01 2.28E-01 6.86E-01 2.65E-03 5.71E+00 1.71E+00 1.71E+00 6.63E-03 4.70E+09 9.41E+10 1.16E+10 2.69E+10 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 Limit 40CFR190.10 (a) TB 40CFR190.10 (a) Thyroid 40CFR190.10 (a) Organ 40CFR190.10 (a) Organ Liq Annual TB Dose Liq Annual Organ Dose Liq Annual Organ Dose Liq Annual Organ 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

• Organ = GI-Lii, Kidney, Liver, or Lung Page 32 of 48

Table 9.8 Air Dose Due To Gaseous Releases - Site (2012)

Type of Radiation Gamma Air Beta Air Tech Spec Limit 5.OOE+O0 1.00E+01 Type of Radiation Gamma Air Gamma Air Gamma Air Gamma Air Beta Air Beta Air Beta Air Beta Air Tech Spec Limit 1.00E+01 1.OOE+01 1.00E+01 1.OOE+01 2.OOE+01 2.OOE+01 2.OOE+01 Units Quarter 1 mRad 9.32E-05 mRad 1.29E-04 Year to Units Ending Date mRad 4.15E-04 mRad 4.15E-04 mRad 4.15E-04 mRad 4.15E-04 mRad 3.08E-04 mRad 3.08E-04 mRad 3.08E-04 Cumulative Doses Per Quarter

% of Tech

% of Tech Spec Limit Quarter 2 Spec Limit 1.86E-03 9.15E-05 1.83E-03 1.29E-03 3.29E-05 3.29E-04 Quarter 3 1.02E-04 6.40E-05 Cumulative Doses Per Year

% of Tech Spec Spec Limit 4.15E-03 4.15E-03 4.15E-03 4.15E-03 1.54E-03 1.54E-03 1.54E-03

% of Tech Spec Limit 2.03E-03 6.40E-04 Quarter 4

% of Tech Spec Limit 1.28E-04 2.57E-03 8.24E-05 8.24E-04 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 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 2.OOE+01 mRad 3.08E-04 1.54E-03 Gas Receptor SB - Infant Page 33 of 48

Table 9.9 Dose to A Member Of The Public Due To Radioiodines. Tritium, and Particulates in Gaseous Releases (2012)

Cumulative Doses Per Quarter Organ Total Body Thyroid Organ Skin Bone Tech Spec Units Limit 7.5 mRem 7.5 mRem 7.5 mRem 7.5 mRem 7.5 mRem Quarter 1 2.27E-02 1.46E-02 2.27E-02 6.40E-08 5.79E-02

% of Tech Spec Limit 3.03E-01 1.95E-01 3.03E-01 8.54E-07 7.72E-01 Quarter 2 3.28E-02 2.38E-02 3.28E-02 4.10E-08 5.66E-02

% of Tech Spec Limit 4.37E-01 3.17E-01 4.37E-01 5.46E-07 7.54E-01 Quarter 3 3.31E-02 2.18E-02 3.31E-02 O.OOE+00 5.82E-02

%/o of Tech Spec Limit 4.41E-01 2.91E-01 4.41E-01 O.OOE+00 7.77E-01 Quarter 4 2.11E-02 1.23E-02 2.11E-02 O.OOE+O0 4.53E-02

%/o of Tech Spec Limit 2.81E-01 1.64E-01 2.81E-01 O.OOE+O0 6.03E-01 Quarterly limit values are the same for both 40CFR190.10 (a) and Gas Annual Organ Dose limits Cumulative Doses per Year Organ Total Body Thyroid Organ Skin Bone Total Body Thyroid Organ Skin Bone Tech Spec Units Limit 25 75 25 25 25 15 15 15 15 15 mRem mRem mRem mRem mRem mRem mRem mRem mRem mRem Year to Ending Date 1.10E-01 7.26E-02 1.10E-01 1.05E-07 2.18E-01 1.10E-01 7.26E-02 1.10E-01 1.05E-07 2.18E-01 O/o of Tech Spec Limit 4.39E-01 9.67E-02 4.39E-01 4.20E-07 8.72E-01 7.31E-01 4.84E-01 7.31E-01 7.OOE-07 1.45E+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 Limit 40CFR190.10 (a) TB 40CFR190.10 (a) Thyroid 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 Organ = GI-LIi, Kidney, Liver, or Lung Page 34 of 48

TABLE 9.10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2012 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

Shipped Shipped Buried Buried Percent

1. Type of Waste m3 Ci M 3 Ci Error

a. Spent resins/filters

1. 17E+01 2.88E+00 1.17E+01 2.88E+00 25%

b. Dry active waste 2.18E+02 8.83E-02 3.5 1E+01 1.01E-01 25%

c. Irradiated components N/A

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

TOTAL 2.30E+02 2.97E+00 4.68E+01 2.98E+00 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 21.80 6.27E-01 H-3 20.72 5.96E-01 Cs-137 17.41 5.01E-01 Fe-55 16.44 4.73E-01 Cs-134 11.88 3.42E-01 Co-60 4.22 1.22E-01 Sb-125 2.47 7.11E-02

a. Spent resins/filters C.1 4 2.15 7.11E-02 C-14 2.15 6.19E-02 Co-58 1.68 4.83E-02 Tc-99 0.08 2.33E-03 1-129 LLD Other*

1.15 3.30E-02 I

Total 100.00 2.88E+00

• Nuclides representing <1% of total shipped activity: Be-7,Cr-51,Mn-54,Co-57,Fe-59,Zn-65,Sr-90,Zr-95,Nb-95,Ag-110m,Sn-1 13, Sb-124 Page 35 of 48

TABLE 9.10 (cont.)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2012 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 28.97 2.56E-02 Co-60 21.55 1.90E-02 Ni-63 21.54 1.90E-02 Co-58 19.93 1.76E-02 Nb-95 1.96 1.73E-03 Zr-95 1.26 1.1 E-03

b. Dry active waste Mn-54 1.13 1.00E-03 Cr-51 1.07 9.44E-04 C-14 0.20 1.78E-04 H-3 0.04 3.27E-05 Tc-99 LLD 1-129 LLD Other*

2.35 2.07E-03 Total 100.00 8.83E-02

• Nuclides representing <1% of total shipped activity: Co-57,Sn-113,Sb-125,Cs-134,Cs-137,Ce-144,Pu-238,Pu-,

Am-241,Am-243,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 N/A N/A N/A reduction)

!39/240,

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

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

Shipments Destination

a. Resin/filters A

A N/A 2

Energy Solutions, Clive UT

b. Dry active waste A

General Design N/A 3

Energy Solutions Oak Ridge, TN

d. Other N/A N/A N/A N/A N/A

• 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 N/A 0

N/A Page 36 of 48 0.1 2012 Meteorological Joint Frequency Table Page 37 of 48

B.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERMOD OF RECORD: 01-JAN-12 00:00 TO 31-DEC-12 23+/-.,.

STABILITY CLASS: A ELEVATION:

10 to.

Wind Directilit N

NNE NE ENE E

ESE SE SSE S

$W WSW MWV NNW Wind Speed (mph) at 10 m.

level 1-3 2

0 S

3 2

0 1

1 I

0 a

0 0

1 a

4-7 8-12 1I 9

22 26 7

20 14 13 11 3

1 0

I 2

6 22 25 14 4

2 22 25 56 55 6

1 0

0 0

0 11 13-15 19-24 13 2

8 4

1 0

1 0

o 0

4 0

10 0

32 6

31 6

0 0

0 0

0 0

0 0

0 0

0 1

7 5

>24 TOTAL o

49 0

48 0

37 0

36 0

12 o

48 0

S2 0

108 0

104 0

10 0

4 0

1 0

0 0

3 6

o 29 VARIABLE 18 5

0 0

0 0

23 Total 35 1.54 Z46 107 24 2

568 Periods of calm(hours):

1 Hours of missing data:

1 Page 38 of 48

L--_

R.G.

1.21 JOINT FRJEOUENCY TABLE T,

U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-12 00:00 TO 3J-DEC-12 23:59 STABILITY CLASS:5 ELEVATION:

10 a.

Wind Direction N

NNE NE ENE SE ESE SS gSS SW WSW W

WNW NW NN'W Wind Speed (mph) at 10 m.

level 1-3 3

1 3

6 5

3 0

0 0

1a 1

1 0

1 4-7 8-12 13-18 1.9-24

ý24 TOTAL 2

5 14 8

5 19 20 21 21 5

7 7

2 2

4 9

16 13 5

7 2

10 11 29 so 17 4

2 2

I S

15 13 6

0 0

3 44 72 10 a

0 4

It 0

3 0

0 0

0 2

7 17 S

0 0

0 3

7 37 28 23 22 12 33 36 102 161 37 12 9

6 5

17 45 VARIABLE 34 3

I a

0 a

30 Total 61 154 191 166 47 4

623 Periad

• of oslb(hours):

I Hours of missing data:

0 Page 39 of 48

11..

1.21 JOINT FREQUENCY TABLE T. U.

ELECTRIC COMPANY HOURS AT B:AC WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-12 0000 TO 31-DEC-12 23:59 STABILITY CLASSs C ELEVATION: 10 a.

Wind Speed (mph) at 10 a, level Direction N

NNT NE ENE E

ESE BE SSE S

5SW SW WSW W

Wo Nw M04w VARIABLE 1-3 4

4 i1 4

2 2

-3 0

2 0

2 0

1 0

0 0

21 4-7 7

10 10 6

25 16 2S 18 6

6 23 3

22 8-12 18 9

2 2

I 9

19 34 58 32 12 5

2 12 17 I

13-18 14 S

2 I

0 1

11 40 72 29 4

6 2

1 9

0 19-24 2

1 0

0 0

0 C

28 ii 0

0 C

C 1234 TOTAL 0

49 0

27 o

25 a

o1 9

37 49 111 173 90 24 17 36 Be I

0 0

23 Totai 56 188 234 210 56 14 758 Periods of calm(hourl):

0 Hours of missing data:

6 Page 40 of 48

31.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPED AND DIRECTION PERIOD OF RECORD: 01-JAN-12 00:00 TO 31-DEC-12 23:59 STABILITY CLASS: P ELEVATION:

1O m.

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

'24 TOTAL K

6 77 118 115 31 2

349 NNE 7

68 79 58 10 0

223 HE 8

40 51 19 L

0 119 ENE 14 27 22 3

0 o

66 E

23 72 11 1

0 0

107 ESE 20 87 55 1

0 0

a63 SE 12 134 236 39 1

a 422 SSE 6

87 399 331 59 17 699 S

7 68 2a9 61 11 736 SSW 5

36 98 67 16 0

222 SW 14 44 64 24 3

0 139 ISW to 32 25 4

3 1

75 W

5 18 7

3 0

0 33 WNW 4

25 38 16 0

4 87 NW 4

30 61 so 9

6 168 SNNW 10 32 87 1.41 24 6

300 VARIABLE 55 14 7

0 0

0 76 Total 210 891 1637 L179 318 47 4182 Periods of calm(hours):

2 Hours of miasin data:

18 Page 41 of 48

E4 G. z.21 JOINT FREQUENCY TABLE T. U. ELEcTRIC COMPANT HOURS AT EACH WIND SPEED AND DIRECTION nlIOc OF RECORD: 01-JAN-12 oo:oo TO 31-DEC-12 23:59 STABILITV CLASS: 8 ELEVATION:

1O t.

Wind Speed (*ph) at i0 a. Level Wind Direction N

NNE EWE ESE SE S

SSW Sw WSW Ww' NW NNW 1-3 7

5 3

to 29 23 13 20 16 17 10 6

13 14 4-7 8-12 13-18 39 50 28 22 0

6 2

0 10

1.

0 21 1

0 76 5

0 174 133 2

129.

115 14 69 It9 5

48 76 11 29 22 10 23 7

0 13 5

2 17 i8 1

63 21 3

27 21 2

19-24

)24 TOTAL 0

0 99 a

0 57 0

0 13 0

0 14 0

1 33 0

0 100 0

0 338 1

0 352 1

1 208 0

0 155 1

0 78 0

0 47 0

0 30 0

0 42 0

0 100 0

0 64 r

VARIABLE 77 18 3

2 0

0 100 Total 287 790 691 57 3 -

1830 Periods of ftsm(hours):

8 Bours of miasinf Oata:

19 Page 42 of 48

RO. 1.21 JOINT FREQUENCY TABLE T. U. ELECtRIC CO1PANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-12 00:00 TO 31-DEC-12 23:59 STABILITY CLASS:, F ELEVATION:

10 m.

Wind Speed (Ctb) at 10 m.

level Wind Direction N

NE NE E

WE SS a'

&W WSW SW WNW 10 1-3 0

0 0

2 3

13 15 I8 24 26 20 12 15 10 4

4-7 8-12 13-18 19-24

)24 TOTAL aa I

1 0

0 2

63 28 22 28 21 22 9

22 2

2 2

0 0

0 1

4 10 7

25 10 S

2 2

4 v-i 0

0 2

6 80 53 47 79 59 50 25 26 6

VARIABLE 36 I

0 0

37 Total 199 236 77 0

a MG Periods of celmi(houra)t I

Hours of missing date:

F Page 43 of 48

0.0. 1.21 JOINT FREQUENCY TASLE T.

U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND) DIRECTION PERIOD OP RECORD: 01-JAN-li 00:00 TO 31-DEC-12 23:69 STASLITY CLASS: 0 ELEVATION, 10 m.

Wind Spoed (Mph) at 10 a. level Wind Direotion 1-3 4-7 8-12 13-18 19-24;

)2 TOTAL

'NE NNE MEE ES ESE SIE S

saw SW WKR KNW 0

0 0

0 0

0 I

5 9

24 15 is 16 14 15 8

a 0

0 0

0 0

1 4

2 6

14 26 2

5 8

0

• 0 0

0 0

0 0

0 0

0 C

0 0

a 0

o 0

a C

0 1

5 7

15 40 44 5I 17 20 18 VARIABLE 8

0 0

0 0

a Total 118 101 15 0

0 a

234 Periods of oulm(houra):

1 Hours or missing data:

0 Page 44 of 48

R.G. 1.21 JOINT FItEOUENCY TABLE T.

U.

ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-12 00:00 TO 31-DEC-12 23:59 STABILITY CLASS:

ALL ELEVATION:

10 a.

Wind Speed (mph) at 10 *. level Wind Direotion N

NiE NE FilE E

ESE SE SSE S

SSW Sw WSW W

WNW NW NNW L-3 19 22 27 32 45 49 58 51 51 74 74 63 43 41 36 32 4-7 8-12 13-18 19-24 141 226 160 38 120 150 78 t8 93 74 22 1

81 36 5

0 111 17 1

0 230 102 7

0 425 431 65 3

301 713 461 81 205 578 479 113 152 256 119 32 136 106 40 4

119 54 to 3

49 19 8

0 62 60 1o 0

137 106 77 14 103 151 170 41

'24 TOTAL 2

586 0

388 o

217 1

155 1

175 o

308 o

9s2 La 1632 17 1443 0

633 0

360 1

250 0

119 4

186 11 381 14 511 0

305 VARIABLE 249 42 12 2

0 Total 966 2514 3091 1723 348 69 8711 Periods of calathours):

17 Hours of missing data:

56 Page 45 of 48 0.2 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, 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-14 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-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. Environmental Protection Agency, Health Physics Society.

Page 48 of 48