ML081260348

Radioactive Effluent Release Report

ML081260348
Person / Time
Site:	Comanche Peak
Issue date:	04/10/2008
From:	Rebstock D, Walsh R Luminant Power
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2009-0260
Download: ML081260348 (51)

Text

2007 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2007 - December 31, 2007 Prepared By: Don Rebstock/Randy Walsh Date: 4/10/08 Reviewed By: David Valentine/Scott Bradley Date: 4/28/08 Approved By: Terry Marsh Date: 4/28/08

TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS

1.0 INTRODUCTION

1.1 Executive Summary 1.2 General 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 RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to the Offsite Dose Calculation Manual 6.3 New Locations for Dose Calculations or Environmental Monitoring 6.4 Liquid Holdup and Gas Storage Tanks 6.5 Noncompliance with Radiological Effluent Control Requirements 6.6 Resin Releases to the LVW Pond 6.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems 6.8 Meteorological Monitoring Program 6.9 Assessment of Doses ii

TABLE OF CONTENTS 7.0 TABLES 7.1 Site Liquid and Gaseous Batch Release Summary 7.2 Site Abnormal Batch Liquid and Gaseous Release Summary 7.3 Site Gaseous Effluents-Summation of All Releases 7.4 Site Gaseous Effluents-Ground Level Releases 7.5 Site Liquid Effluents Summation of All Releases 7.6 Site Liquid Effluents 7.7 Doses Due to Liquid Releases-Site 7.8 Doses Due to Gaseous Releases-Site 7.9 Doses Due to Radioiodines, Tritium, and Particulates in Gaseous Releases-Site 7.10 Solid Waste and Irradiated Fuel Shipments 8.0 ATTACHMENTS 8.1 Joint Frequency Tables iii

ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPNPP Comanche. Peak Nuclear Power Plant ECL Effluent Concentration Limit LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks REC Radiological Effluent Control SORC Station Operations Review Committee WMT Waste Monitor Tanks, WWHT Waste Water Holdup Tanks 4

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, 2007, through December 31, 2007.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2007 was conducted as described in the following report. The results of the monitoring program indicate the continued effort toý maintain the release of radioactive effluents to the environment as low as reasonably achievable (ALARA).

A summation of all the radioactive gaseous releases to the environment during 2007 produced the following results:

" The total gaseous tritium activity released from the site for 2007 was 55.9 Curies which is an increase from the 47.4 Curies in 2006. 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.

" The total gaseous fission and activation activity (Noble gas) released from the site in 2007 was 13.9 Curies. This is a decrease from the 148.0 Curies released in 2006. In early 2007 during IRFI2, the PRT gas space was evacuated via an eduction method to the Waste Gas system. In the past, the PRT gas space was 'equalized" to the Waste Gas system prior to venting to the Containment Atmosphere.

As demonstrated by the 2007 total gaseous fission and activation activity, the PRT eduction method has significantly reduced the' amount of radioactive gas released to the environment:

N The total gaseous particulate activity released for 2007 was 1.912E-06 Curies.

0 The gross alpha released has continued at 0.00 Curies for 2007 matching the performance of the previous 11 years.

E Iodine was released at a value of 0.0 Curies for 2007.

0 The calculated gamma air dose from the site due to noble gases released during 2007 is 1.53E-03 mrad. This is a decrease from 2006 which was 7.21E-03 mrad; the 2007 value represents only 0.008% of the annual limit for each reactor unit. This decrease is a direct result of less total gaseous fission and activation activity released in 2007.

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" The calculated beta air dose from the site due to noble gases released during 2007 is 2.068E-03 mrad which is an increase from 2006 which was 1.76E-03 mrad; however, this represents only 0.005% of the annual limit for each unit.

" The total whole body dose from the site due to gaseous radioactivity released based on 1-131, 1-133, H-3(tritium), and particulate nuclides for 2007 was 0.0785 mrem. This value is an increase from the 2006 whole body dose of 0.046 mrem.

" Overall the gaseous radioactivity releases from CPNPP are well controlled and maintained ALARA. CPNPP is well below all applicable limits for gaseous releases.

" A summation of all the radioactive liquid releases to the environment-during 2007 produced the following results:

" The total number of Curies of radioactive nuclides released from the site in liquid effluents in 2007 was 532.06 Curies, down from 1520.54 Curies in 2006.

Of the total Curies released from the site, tritium accounted for 532.00 Curies while *all other nuclides released accounted for only 0.06 Curies-. The total curies of tritium released are down from the 2006 total of. 1520.0 Curies. This reduction was due mainly to lowered RCS tritium concentrations in both units for much of 2007. RCS tritium concentrations slowly increase to equilibrium during the first half of the fuel cycle. This is followed by a decrease, in concentration as RCS dilution overtakes tritium production. Unit 2; refueled late in 2006 and Unit 1 was shutdown for almost 2 months in early 2007 for IR12 (steam generator replacement). The combination'of the timing of these two events resulted in a lower combined 2007 RCS tritium concentration for much of the year. Since most of the liquid effluents were released during the first part of the year, the annual effluent tritium concentration was unusually low.

The total whole body dose from the site due to liquid effluents was 1.368E-01 mrem, which is only 2.28% of the annual limit for each unit. Tritium accounts for >99% of the calculated total whole body dose. '

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The CPNPP meteorological system achieved a 98.1% recoverable data rate for the joint frequency parameters required by Regulatory Guide 1.23 for wind speed, wind direction and delta temperature.

All other parameters achieved an average of 94.0% recoverable data rate for 2007.

During 2007 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

There was one revision to the ODCM. approved and/or implemented in 2007. Refer to' section 6.2 for an explanation of the revision.

For 2007, the total volume of solid radwaste buried increased to 180 cubic 'meters from 16.9 cubic meters last year and the total radioactivity' buried increased to 475 curies from 369 curies in 2006. This increase was due to steam generator replacement during 1R12. The bulk of the buried solid waste volume comes from dry active waste at 177 cubic meters. Also, spent resins and filters were responsible for >99% of the entire total radioactivity buried.

During the spring of. 2007, the Chemistry Department acquired responsibility for the Radioactive Effluents Program from the Radiation Protection Department. During this time, the existing radioactive effluents software program (RETDAS) was replaced by the OpenEMS software program.

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).

Information pertaining to the following items is included in this report:

• A summary of the quantities of radioactive liquid and gaseous effluents released from CPNPP during the reporting period in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

• A summary of solid waste shipped from CPNPP in the format shown in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974, supplemented with three additional categories:

class of waste (per 10CFR61), type. of container (Strong Tight, HIC) and shipped and buried volumes and curies.

• An explanation of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days.

" ODCM changes during 2007. A copy of the ODCM will be sent along with this report.

" A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use 7

Census.

" A description of the events leading to liquid holdup tanks or gas storage tanks exceeding Technical Specification limits.

" A list and description of abnormal releases of radioactiye material from the site to unrestricted areas.

" A description of secondary resin releases to the LVW Pond.

" A description of major changes to radioactive waste treatment systems (liquid, gaseous and solid).

• An assessment of radiation doses due to the radioactive liquid and gaseous effluents released from CPNPP Unit 1 and Unit 2 in 2007.

• An assessment of radiation doses to the likely, most exposed MEMBER OF THE PUBLIC from CPNPP releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation,., for the reportinhg period,' to show conformance with 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

• An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the Site Boundary.

• Onsite perched groundwater wells were sampled in accordance with ENV-323, Tritium Groundwater Monitoring Program, with no tritium or any other radioactive nuclides detected in 2007.

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1.2 General Trend Graphs Total Whole Body Dose Due to Liquid Effluents Released from CPSES 0.16 0.14 0.12 0.11 0 .11 0.11 010 0 0.10 0.09 0.10 01 - 010 0.10 - 09909 0.0" -

0.09 0.08 E 0.08 0) 0.06 0.04 0.02 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year Total Whole Body Dose due to Gaseous Activity released from CPSES 0.12 0.10 0.08 E 0.06 0) 0.04 0.02 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year 9

Total Activity (Excluding H3) Released in Liquid Effluents from CPSES 400.00 358.00 350.00 300.00 250.00 227.90 232.10 U

E 200.00  : --

144.00 150.00 1- --

124.80 100.0011.0[] 110i.r 50.00 L .V

[1 t fI 17.60 21.60 0.00, ,

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year Total Gaseous Fission and Activation Activity Released from CPSES 1000.00 100.00 d

0 L) 0 10.00 0

(.9 0

I.-

1.00 0.10 1996 1997 1998 1999, 2000 2001 2002 2003 2004 2005 2006 2007 Year 10

Total Curies of Tritium Released in Liquid Effluents from CPSES 1800 1600 1550 1520 1455 -:*. 11 1430 13-1480 -

• '- *,* ;1391 1400-____ _

1223 1200 -,

C 1080 1o 98 986 a91000 931 2 0 0 0 0 0

800 - _ _

S 669 600 400__ __

Gaseous Tiu Rls fro CP532 Yea 200__ _ _

0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year Total Gaseous Tritium Released from CPSES 90.00 80.00 70.00 60.00 C-,

0 50.00 0

40.00 0

30.00 20.00 10.00 0.00 1996 1997 1998 1999 2000 2001 2002 2003 ' 2004 2005 2006 2007 Year 11

Total Volume Liquid Effluents Released from CPSES 1800000 1600000 1489742 1400000 1368826 1174134 1200000 S 1098400  !)

1057939 1000000 909767 969860 0)871352 909767 EA 800000 4 _762800 0 700793 638000 600000 400000 200000 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year Total Curies of Solid Radwaste Buried from CPSES 1800 1620 1600 1400 1200 1.150 S1000 .- ________________________

800 600 . 552 ..... .. . -- -- "

A474 475

. . . .36 1 - 3 69 4 00 .

255 249 200 90 -- - 49 - - 135---

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year 12

Total Volume of Solid Radwaste Buried from CPSES 200.00 180.00 160.00 +-

140.00 4 120.00 E

S100.009.2 uuuu 90.20 S80.00 0

60.00 52.20 40.00 34;00 27.10 27.90 1590 200 119070 19.30 16.90 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 Year 13

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 mrems/yr to the whole body and less than or equal to 3000 mrems/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 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads 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 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

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2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 gCi/ml total activity.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems 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:

(2 64/V) Yj ij/Cj < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:

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

C. = 10CFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (WCi/ml),

V = volume of resins in the pond (gallons), and 264 = conversion factor (gCi/Ci per ml/gal) 15

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 mrems to the whole body or any organ,.

except the thyroid, which shall be limited, to,.less than or equal to 75 mrems.

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.

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 16

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 with the exception of Containment vents made as a precursor to a Containment purge. In these cases, samples collected and analyzed as *a prerequisite to the vent were used to estimate total radioactivity released during' the subsequent purge. 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 17

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.

2.4 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 7.1.

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. One normal, unplanned gaseous effluent release and one abnormal, unplanned gaseous effluent release occurred during 2007. Refer to section 6.5.1 and 6.5.2 for a detailed description of these events. No abnormal or unplanned liquid effluent releases occurred during 2007. Table 7.2 summarizes the abnormal and unplanned releases.

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3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 7.3 and 7.4. 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 7.5 and 7.6.

5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Table 7.10.

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6.0 RELATED INFORMATION 6.1 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.

6.2 Changes to the Offsite Dose Calculation Manual During the period covered by this report, there was one revision to the ODCM approved and/or implemented. The revision number is 27. A complete copy of the ODCM, with change bars, will be provided as a separate Enclosure to the letter transmitting this report.

6.3 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 2007 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 2007 Land Use Census.

6.4 Liquid Holdup and Gas Storage Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading to liquid holdup or gas storage tanks exceeding the limits required to be established by Technical Specification 5.5.12. Technical Requirements Manual 13.10.33 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten curies, excluding tritium and dissolved or entrained noble gases.

Technical Requirements Manual 13.10.32 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 curies of noble gases (considered as Xe-133 equivalent). These limits were not exceeded during the period covered by this report.

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6.5 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.

6.5.1 Normal, Unplanned Gaseous Release A normal, unplanned gaseous effluent release occurred on 2/12/07 and originated from Waste Gas Decay Tank X-03. While performing normal Waste Gas System operations, 654 ft 3 gas. Volume leaked from GDT 3 via a body to bonnet leak on inlet valve XGH-7820C.

Fasteners on this valve were later. found to be loose.

This normal, unplanned gaseous effluent release was documented in release permit number 2007-027 and Smart Form number.2007-000468.

6.5.2 Abnormal, Unplanned Gaseous Effluent Release An abnormal, unplanned gaseous effluent release occurred on 4/14/07 during 'the 1RF12 Containment Integrated Leak Rate Test (ILRT) and originated from the Unit 1 emergency airlock inner door boundary (outer door was open). The leakage was found in room 1-111 by the ILRT team. This room is not ventilated by the primary plant ventilation system and is therefore an unmonitored unplanned release. An analysis was performed that determined the leakage through the emergency airlock inner boundary while at full ILRT test pressure (about 50 psig) was approximately 0.0314 weight %/day which is equivalent to about 78,000 SCCM or 2.75 SCFM. Pressurization for the ILRT started on 4/14/07 at .00:40 hours and the leak was discovered/stopped at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br /> the same day. This abnormal, unplanned gaseous effluent release was documented in release permit number 2007-064 and Smart Form number 2007-001327.

6.5.3 Abnormal, Unplanned Liquid Effluent Releases No abnormal or unplanned liquid effluent releases occurred during 2007.

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6.6 Resin Releases to the LVW Pond A total of 172 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 2007 is 1.18E-03 Curies, consisting of Co-58, Co-60, Cs-134, Cs-137, 1-131 and Sb-125.

6.7 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.

6.8 Meteorological Monitoring Program In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 2007, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 8.1. During 2007, the goal of >90% joint data recovery was met.

6.9 Assessment of Doses 6.9.1 Doses Due to Liquid Effluents The doses 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 7.7.

6.9.2 Doses 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 7.8.

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6.9.3 Dose Due to Radioiodines, Tritium and Particulates The doses 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 ODCM.

The results of the calculations are summarized on a quarterly and annual basis in Table 7.9.

6.9.4 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 doses exceed two times the applicable quarterly or annual dose limits. At no time during 2007 were any of these limits exceeded, therefore no evaluations are required.

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6.9.5 Doses 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 1.27E-4 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 doses are calculated at the point of circwater discharge into the lake.

/

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.

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SECTION 7.0 TABLES

Table 7.1 Site Liquid and Gaseous Batch Release Summary (2007) 1st 2nd 3rd 4th Year A. Liquid Releases Units Quarter Quarter Quarter Quarter Totals Number of batch releases 15 10 4 5 34 Total time period for Batch releases ( Minutes): 5.095E+03 3.300E+03 1.270E+03 1.513E+03 1.118E+04 Maximum time period for a batch release ( Minutes): 3.850E+02 4.300E+02 3.300E+02 3.230E+02 4.300E+02 Average time period for a batch release ( Minutes): 3.397E+02 3.300E+02 3.175E+02 3.026E+02 3.288E+02 Minimum time period for a batch release ( Minutes ) : 3.OOOE+02 2.450E+02 2.900E+02 2.800E+02 2.450E+02 Average stream flow (GPM ) 5.537e+04 4.531E+04 1.788E+04 2.021E+04 1.388E+05 1st 2nd 3rd 4th Year B. Gaseous Releases Units Quarter Quarter Quarter Quarter Totals Number of batch releases 31 34 32 35 132 Total time period for batch. releases ( Minutes): 1.113E+04 1.362E+04 1.169E+04 1.234E+04 4.878E+04 Maximum time period for a batch release ( Minutes): 4.540E+02 1.320E+03 3.990E+02 4.110E+02 1.320E+03 Average time period for a batch release ( Minutes): 3.589E+02 4.007E+02 3.653E+02 3.526E+02 3.696E+02 Minimum time period for a batch release ( Minutes): 1.820E+02 2.800E+02 3.260E+02 2.730E+02 1.820E+02 T-1

Table 7.2 Site Abnormal Batch Liauid and Gaseous Release Summary (20071 Site Abnormal Batch 1ST 2ND 3RD 4TH Year A. Liquid Releases Units Quarter Quarter Quarter Quarter Totals Number of Releases 0 0 0 0 Total Time For All Releases (Minutes): O.OOOE+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 Maximum Time For A Release (Minutes): O.OOOE+00 0.OOOE+00 0.000E+00 O.OOOE+00 Average Time For A Release (Minutes): O.OOOE+00 0.OOOE+00 0.000E+00 O.OOOE+0O Minimum Time For A Release (Minutes): O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Total activity for all releases (Curies O.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 1ST 2ND 3RD 4TH Year B. Gaseous Releases Units Quarter 1 Quarter Quarter Quarter Totals Number of Releases 1 0 0 2 Total Time For All Releases (Minutes): 3.OOOE+02 1.320E+03 O.OOOE+00 0.OOOE+00 1.620E+03 Maximum Time For A Release (Minutes): 3.OOOE+02 1.320E+03 0.OOOE+00 0.OOOE+00 1.320E+03 Average Time For A Release (Minutes): 3.OOOE+02 1.320E+03 0.OOOE+00 0.OOOE+00 8.100E+02 Minimum Time For A Release (Minutes): 3.OOOE+02 1.320E+03 O.OOOE+00 0.OOOE+00 3.OOOE+02 Total activity for all releases ( Curies ) 3.757E-01 7.843E-07 0.OOOE+00 0.OOOE+00 3.757E-01 T-2

Table 7.3 Site Gaseous Effluents - Summation Of All Releases (2007)

Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals A. Fission and Activation Gases Total Release Curies 4.569E+00 1.096E+00 1.374E+00 6.879E+00 1.392E+01 Average Release rate for period uCi/sec 5.795E-01 1.390E-01 1.743E-01 8.725E-01 1.765E+00 Percent of Applicable Limit B. Radioiodines Total Iodine-131  :

O;OOoE+oo O.OOOE+00 O.OOOE+00 0.OOOE+00 Average Release rate for period O.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 Percent of Applicable Limit C. Particulates Particulates ( Half-Lives > 8 Days) Curies O.OOOE+00 1.912E-06 0.000E+00 0.OOOE+00 1.912E-06 Average Release rate for period uCi/sec O.OOOE+00 2.425E-07 0.OOOE+00 0.OOOE+00 2.425E-07 Percent of Applicable Limit D. Tritium Total Release Curies 1.256E+01 1.279E+01 1.898E+01 1.156E+01 5.588E+01 Average Release rate for period uCi/sec 1.593E+00 1.622E+00 2.407E+00 1.467E+00 7.088E+00 Percent of Applicable Limit E. Gross Alpha Total Release 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Average Release rate for period 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00

• Applicable limits are expressed in terms of dose. Estimated total error for all values is <1.0%

T-3

Table 7.4 Site Gaseous Effluents - Ground Level Releases (2007)

Continuous Mode Nuclides Released Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Fission Gases Ar-41 Curies 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.611E-01 4.611E-01 Xe-133 Curies 2.162E+00 0.OOOE+00 O.OOOE+00 2.394E+00 4.556E+00 Total for Period Curies 2.162E+00 0.OOOE+00 O.OOOE+00 2.855E+00 5.017E+00 Iodines No Nuclides Found N/A N/A N/A N/A Particulates Cs-134 Curies 0.OOOE+00 1.912E-06 0.OOOE+00O0.OOOE+00 1.912E-06 Total for Period Curies 0.OOOE+00 1.912E-06 0.OOOE+00 0.OOOE+00 1.912E-06 Tritium H-3 Curies 1.252E+01 1.277E+01 1.895E+01 1.153E+01 5.578E+01 Gross Alpha No Nuclides Found N/A N/A N/A N/A

Table 7.4 (cont.)

Site Gaseous Effluents - Ground Level Releases (2007)

Batch Mode Nuclides Released Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Fission Gases Ar-41 Curies 1.974E-01 1.238E-01 1.322E-01 1.492E-01 6.025E-01 Kr-85m Curies 2.294E-02 O.OOOE+00 O.OOOE+00 5.045E-05 2.299E-02 Kr-85 Curies 3.301E-01 8.272E-01 1.075E-01 1.393E+00 2.658E+00 Kr-87 Curies 9.158E-03 O.OOOE+00 O.OOOE+00 O.OOOE+00 9.158E-03 Kr-88 Curies 3.265E-02 O.OOOE+00 8.604E-05 O.OOOE+00 3.274E-02 Xe-131m Curies 8.184E-03 7.788E-05 1.734E-02 3.833E-02 6.393E-02 Xe-133m Curies 2.464E-02 O.OOOE+00 2.845E-03 1.176E-02 3.925E-02 Xe-133 Curies 1.520E+00 1.447E-01 1.114E+00 2.426E+00 5.205E+00 Xe-135m Curies 1.042E-01 1.463E-04 O.OOOE+00 O.OOOE+00 1.044E-01 Xe-135 Curies 1.578E-01 4.764E-05 3.508E-04 4.567E-03 1.628E-01 Xe-138 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 4.844E-04 4.844E-04 Total for Period Curies 2.407E+00 1.096E+00 1.374E+00 4.023E+00 8.901E+00 lodines No Nuclides Found N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A Tritium H-3 Curies 3.152E-02 2.003E-02 2.581E-02 2.843E-02 5.842E-02 Gross Alpha No Nuclides Found N/A N/A N/A N/A,

Table 7.5 Site Liquid Effluents - Summation of All Releases (2007)

Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission and Activation Products Total Release(not including tritium, gases, alpha) Curies 1.097E-03 3.951E-03 1.174E-03 1.410E-03 7.631E-03 Average diluted concentration during period uCi/mL 7.495E-11 3.286E-10 2.466E-10 2.618E-10 9.119E-10 Percent of Applicable Limit  % 0.000022 0.000259 0.000022 0.000105 B. Tritium Total Release Curies 4.068E+02 7.869E+01 2.230E+01 2.417E+01 5.320E+02 Average diluted Concentration during period uCi/mL 2.780E-05 6.544E-06 4.685E-06 4.488E-06 4.351E-05 Percent of Applicable Limit  % 2.780 0.654 0.469 0.449 C. Dissolved and Entrained Gases Total Release Curies 3.847E-02 6.914E-03 1.066E-05 3.139E-03 4.853E-02 Average diluted Concentration during period uCi/mL 2.628E-09 5.749E-10 2.239E-12 5.830E-10 3.788E-09 Percent of Applicable Limit  % 0.001 0.000 0.000 0.000 D: Gross Alpha Radioactivity Total Release 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 1.095E+06 7.083E+05 2.812E+05 3.291E+05 2.414E+06 F. Volume of Dilution Water Used Liters 1.463E+10 1.202E+10 4.759E+09 5.384E+09 3.680E+10

Table 7.6 Site Liquid Effluents (2007)

Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Products No Nuclides Found N/A N/A N/A N/A Tritium H-3 Curies O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A Gross Alpha No Nuclides Found N/A N/A N/A N/A Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Products Cr-51 Curies O.OOOE+O0 2.166E-05 2.785E-05 O.OOOE+O0 4.950E-05 Mn-54 Curies O.OOOE+O0 O.OOOE+O0 O.OOOE+O0 4.643E-05 4.643E-05 Fe-55 Curies 4.928E-04 3.433E-05 O.OOOE+O0 O.OOOE+O0 5.272E-04 Co-57 Curies O.OOOE+O0 O.OOOE+O0 O.OOOE+O0 4.476E-06 4.476E-06 Co-58 Curies 8.451E-05 4.766E-04 1.298E-04 3.565E-04 1.047E-03 Co-60 Curies 5.393E-05 7.382E-05 3.005E-05 4.238E-04 5.816E-04 Zr-95 Curies O.OOOE+O0 O.OOOE+O0 O.OOOE+O0 1.681E-05 1.681E-05 Nb-95 Curies O.OOOE+O0 O.OOOE+O0 O.OOOE+O0 2.640E-05 2.640E-05 Ru-103 Curies O.OOOE+O0 O.OOOE+O0 1.144E-06 O.OOOE+O0 1.144E-06 Sb-125 Curies 4.656E-04 3.334E-03 9.849E-04 5.353E-04 5.320E-03 Ce-,144 Curies O.OOOE+O0 1.085E-05 O.OOOE+O0 O.OOOE+O0 1.085E-05 Total for Period Curies 1.097E-03 3.951E-03 1. 174E-03 1.410E-03 7.631E-03

Table 7.6 (cont.)

Site Liquid Effluents (2007)

Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Yea r.

Tritium H-3 Curies 4.068E+02 7.869E+01 2.230E+01 2.417E+01 5.320E+02 Dissolved And Entrained Gases Kr-85 Curies 9.947E-03 6.637E-03 0.OOOE+00 2.745E-03 1.933E-02 Xe-131m Curies 1.362E-03 O.OOOE+00 O.OOOE+00 O.OOOE+00 1.362E-03 Xe-133m Curies 1.889E-05 0.OOOE+00 0.066E+05 0.OOOE+00 1.889E-05 Xe-133 Curies 2.714E-02 2.767E-04 1.066E-05 3.939E-04 2.782E-02 Total for Period Curies 3.847E-02 6.914E-03 1.066E-05 3.139E-03 4.853E-02 Gross Alpha No Nuclides Found N/A N/A N/A N/A

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

Table 7.7 flnqp oses ue Duw' to Liauid Releases - Site (20071 Cumulative Doses per Quarter 0 0 Tech 1st /%of 2nd  % of 3rd /%of 4th  % of Spec Quarter Tech Quarter Tech Quarter Tech Quarter Tech Organ Limit Spec Spec Spec Spec Limit Limit Limit Limit 1.608E-05 Bone 5.OOOE+00 mRem 1.987E-06 3.974E-05 8.042E-07 1.870E-07 3.741E-06 1.581E-07 3.161E-06 GI-Lli 5.OOOE+00 m Rerm 3.148E-02 6.295E-01 3.746E-02 7.491E-01 3.721E-02 7.441E-01 3.087E-02 6.173E-01 Kidney 5.OOOE+00 mRem 3.147E-02 6.294E-01 3.744E-02 7.489E-01 3.720E-02 7.441E-01 3.067E-02 6.135E-01 Liver. 5.OOOE+00 mRem 3.147E-02 6.295E-01 3.745E-02 7.489E-01 3.720E-02 7.441E-01 3.068E-02 6.135E-01 Lung 5.OOOE+00 mRem 3.148E-02 6.297E-01 3.751E-02 7.503E-01 3.722E-02 7.445E-01 3.068E-02 6.137E-01 Thyroid 5.OOOE+00 mRem 3.147E-02 6.294E-01 3.744E-02 7.489E-01 3.720E-02 7.441E-01 3.067E-02 6.135E-01 Total Body 1.500E+00 mRem 3.147E-02 2.098E+00 3.745E-02 2.496E+00 3.720E-02 2.480E+00 3.068E-02 2.045E+00

Table 7.7 (cont.)

Doses Due to Liquid Releases - Site (2007)

Cumulative Doses per Year Tech Year to  % of Tech Receptor Limit Spec Ending Organ Limit Date Spec Limit Bone 1.OOOE+O1 mRem 3.136E-06 3.136E-05 Liquid Receptor - Adult Liq Annual Organ Dose Liver 1.OOOE-i-1 m Rem 1.368E-01 1.368E+00 Liquid Receptor - Adult Liq Annual Organ Dose Thyroid 1.00OE+01 mRem 1.368E-01 1.368E+00 Liquid Receptor - Adult Liq Annual Organ Dose Kidney 1.OOOE+O1 mRem 1.368E-01 1.368E+00 Liquid Receptor - Adult Liq Annual Organ Dose Lung 1.OOOE+O1 mRem 1.369E-01 1.369E+00 Liquid Receptor - Adult Liq Annual Organ Dose GI-Li 1.OOOE+O1 mRem 1.370E-01 1.370E+00 Liquid Receptor - Adult Liq Annual Organ Dose Total Body 3.OOOE+OO m Rem 1.368E-01 4.560E+00 Liquid Receptor - Adult Liq Annual TB Dose Bone 2.500E+01 mRem 3.136E-06 1.254E-05 Liquid Receptor - Adult 40CFR190.10 (a) Organ Liver 2.500E+01 rmRern 1'368E-01 5.472E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ Thyroid 7.500E+01 mRem 1.368E-01 1.824E-01 Liquid Receptor - Adult 40CFR190.10 (a) Thyroid Kidney 2.500E+0-1 mRem 1.368E-01 5.472E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ Lung 2.500E+01 mRem 1.369E-01 5.476E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ GI-Lli 2.500E+01 mRem 1.370E-01 5.480E-01 Liquid Receptor - Adult 40CFR190.10 (a) Organ Total Body 2.500E+01 mRem 1.368E-01 5.472E-01 Liquid Receptor - Adult 40CFR190.10 (a) TB Total Dilution Volume for 1st Quarter 1.463E+10 Total Dilution Volume for 2nd Quarter 1.202E+10 Total Dilution Volume for 3rd Quarter 4.759E+09 Total Dilution Volume for 4th Quarter 5.384E+09

Table 7.8 Doses Due to Gaseous Releases - Site (2007)

Cumulative Doses Per Quarter Radiation Tech Spec 1st O/oof 2nd  % of 3rd  % of 4th  % of Type Limit Quarter Tech Quarter Tech Quarter Tech Quarter Tech Spec Limit Spec Limit Spec Limit Spec Limit Beta 1.000E+01 mRad 6.177E-04 6.177E-03 2.272E-04 2.272E-03 1.923E-04 1.923E-03 1.031E-03 1.031E-02 Gamma 5.000E+00 mRad 4.588E-04 9.176E-03 1.274E-04 2.548E-03 1.705E-04 3.411E-03 7.769E-04 1.554E-02 Cumulative Doses Per Year Radiation Type Tech Spec Year to  % of Tech Receptor Limit Limit End Date Spec Limit Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor SB - Adult NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor SB - Teen NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor SB - Child NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor SB - Infant NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor MI - Adult NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor MI - Teen NG Annual Gamma Air Dose Gamma 1.000E+01 mRad 1.534E-03 1.534E-02 Gas Receptor MI - Child NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 1.534E-03 1.534E-02 Gas Receptor MI - Infant NG Annual Gamma Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor SB - Adult NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor SB - Teen NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor SB - Child NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor SB - Infant NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor MI - Adult NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor MI - Teen NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor MI - Child NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 2.068E-03 1.034E-02 Gas Receptor MI - Infant NG Annual Beta Air Dose

Table 7.9 Doses Due to Radioiodines, Tritium, and Particulates in Gaseous Releases - Site (2007)

Cumulative Doses Per Quarter 1st Quarter 0/bof T.S. 2nd Quarter 0/bof T.S. 4th Quarter 0

/b of T.S.

Organ Tech Spec Limit 3rd Quarter  % of T.S.

Limit Limit Limit Limit Bone 7.500E+00 mRem O.OOOE+00 0.OOOE+00 2.947E-04 3.929E-03 0.OOOE+0O 0.OOOE+0O 0.OOOE+00 O.OOOE+00 GI-LIi 7.500E+00 mRem 1.761E-02 2.348E-01 1.793E-02 2.391E-01 2.662E-02 3.549E-01 1.622E-02 2.162E-01 Kidney 7.500E+00 mRem 1.761E-02 2.348E-01 1.804E-02 2.406E-01 2.662E-02 3.549E-01 1.622E-02 2.162E-01 Liver 7.500E+00 mRem 1.761E-02 2.348E-01 1.829E-02 2.439E-01 2.662E-02 3.549E-01 1.622E-02 2.162E-01 3.549E-01 1.622E-02 2.162E-01 Lung 7.500E+00 mRem 1.761E-02 2.348E-01 1.797E-02 2.396E-01 2.662E-02 Skin 7.500E+00 mRem O.OOOE+00 0.OOOE+00 1.620E-05 2.160E-04 0.OOOE+O0 O.OOOE+00 0.OOOE+00 0.OOOE+00 Thyroid 7.500E+00 mRem 1.761E-02 2.348E-01 1.793E-02 2.391E-01 2.662E-02 3.549E-01 .1.622E-02 2.162E-01 Total Body 7.500E+00 mRem 1.761E-02 2.348E-01 1.802E-02 2.403E-01 2.662E-02 3.549E-01 1.622E-02 2.162E-01 Cumulative Doses per Year Organ Tech Spec Limit Year to End  % of T.S. Receptor Limit Date Total Body 2.500E+01 mRem 7.846E-02 3.138E-01 Gas Receptor SB - Child 40CFR190.10 (a) TB Total Body 2.500E+01 mRem 7.846E-02 3.138E-01 Gas Receptor MI - Child 40CFR190.10 (a) TB Thyroid 7.500E+01 mRem 7.837E-02 1.045E-01 Gas Receptor SB - Child 40CFR190.10 (a) Thyroid Thyroid 7.500E+01 mrRem 7.837E-02 1.045E-01 Gas Receptor MI - Child 40CFR190.10 (a) Thyroid Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor SB - Adult 40CFR190.10 (a) Organ Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor SB - Teen 40CFR190.10 (a) Organ Liver 2.500E+01 mRem 7.873E-02 3.149E-01 Gas Receptor SB - Child 40CFR190o.10 (a) Organ Kidney 2.500E+01 mRem 7.848E-02 3.139E-01 Gas Receptor SB - Child 40CFR190.10 (a) Organ Lung 2.500E+01 mRem 7.841E-02 3.136E-01 Gas Receptor SB - Child 40CFR190.10 (a) Organ GI-Lli 2.500E+01 m Rem 7.837E-02 3.135E-01 Gas Receptor SB - Child 40CFR190.10 (a) Organ rnRern Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor SB - Child 40CFR190.10 (a) Organ Bone 2.500E+01 mRem 2.947E-04 1.179E-03 Gas Receptor SB - Infant 40CFR190.10 (a) Organ Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor SB - Infant 40CFR190.10 (a) Organ Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor MI - Adult 40CFR190.10 (a) Organ Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor MI - Teen 40CFR190.10 (a) Organ Liver 2.500E+01 mRem 7.873E-02 3.149E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ Kidney 2.500E+01 mRem 7.848E-02 3.139E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ Lung 2.500E+01 mRem 7.841E-02 3.136E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ GI-Lli 2.500E+01 mRem 7.837E-02 3.135E-01 Gas Receptor MI - Child 40CFR190.10 (a) Organ Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor MI - Child 40CFR190.10 (a) Organ Bone 2.500E+01 mRem 2.947E-04 1.179E-03 Gas Receptor MI - Infant 40CFR190.10 (a) Organ

Table 7.9 (cont.)

Doses Due to Radioiodines, Tritium, and Particulates in Gaseous Releases - Site (2007)

Cumulative Doses per Year (cont.)

Organ Tech Spec Limit Year to End 0/0 of T.S. Receptor Limit Date Skin 2.500E+01 mRem 1.620E-05 6.479E-05 Gas Receptor MI - Infant 40CFR190.10 (a) Organ Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor SB - Adult Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor SB - Teen Gas Annual Organ Dose Liver 1.500E+01 mRem 7.873E-02 5.249E-01 Gas Receptor SB - Child Gas Annual Organ Dose Total Body 1.500E+01 mRem -7.846E-02 5.231E-01 Gas Receptor SB - Child Gas Annual Organ Dose Thyroid 1.500E+01 mRem 7.837E-02 5.225E-01 Gas Receptor SB - Child Gas Annual Organ Dose Kidney 1.500E+01 mRem 7.848E-02 5.232E-01 Gas Receptor SB - Child Gas Annual Organ Dose Lung 1.500E+01 mRem 7.841E-02 5.227E01 Gas Receptor SB - Child Gas Annual Organ Dose GI-Lli 1.500E+01 mRem 7.837E-02 5.225E-01 Gas Receptor SB - Child Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor SB - Child Gas Annual Organ Dose Bone 1.500E+01 mRem 2.947E-04 1.965E-03 Gas Receptor SB - Infant Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor SB - Infant Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor MI - Adult Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor MI - Teen Gas Annual Organ Dose Liver 1.500E+01 mRem 7.873E-02 5.249E-01 Gas Receptor MI - Child Gas Annual Organ Dose Total Body 1.500E+01 mRem 7.846E-02 5.231E-01 Gas Receptor MI - Child Gas Annual Organ Dose Thyroid 1.500E+01 mRem 7.837E-02 5.225E-01 Gas Receptor MI - Child Gas Annual Organ Dose Kidney 1.500E+01 mRem 7.848E-02 5.232E-01 Gas Receptor MI - Child Gas Annual Organ Dose Lung 1.500E+01 mRem 7.841E-02 5.227E-01 Gas Receptor MI - Child Gas Annual Organ Dose GI-Lli 1.500E+01 mRem 7.837E-02 5.225E-01 Gas Receptor MI - Child Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor MI - Child Gas Annual Organ Dose Bone 1.500E+01 mRem 2.947E-04 1.965E-03 Gas Receptor MI - Infant Gas Annual Organ Dose Skin 1.500E+01 mRem 1.620E-05 1.080E-04 Gas Receptor MI - Infant Gas Annual Organ Dose

TABLE 7:10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2007 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste Shipped Shipped Buried Buried Percent M3 Ci m3 Ci Error

a. Spent resins/filters 1.02E+01 6.36E+02 3.14E+00 4.73E+02 .25%

b. Dry active waste 1.40E+03 1.57E+01 1.77E+02 1.42E+00 .25%

c. Irradiated components N/A

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

TOTAL 1.41E+03 6.52E+02 1.80E+02 4.75E+02 .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.

TABLE 7.10 (Continued)

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

a. Spent resins/filters Ni-63 47.13 3.OOE+02 Fe-55 18.73 1.19E+02 Co-60 9.00 5.72E+01 CS-134 8.79 5.59E+01 CS-137 8.78 5.58E+01 Co-58 5.30 3;37E+01 Mn-54 1.26 8.04E+00 H-3 0.01 4.54E-02 C- 14 LLD Tc-99 LLD 1-129 LLD .

Other* 1.00 6.29E+00 Total 100.00 6.36E+02 Nuclides representing <1% of total shipped activity: Co-57,Ni-59, Sr-90,Sb- 122,Sb- 125,Ce- 144,Pu-238,Pu-239/240,Pu-241, Am-241,Cm-242,Cm-243/244.

TABLE 7.10 (Continued)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2007

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

b. Dry active waste Fe-55 59.88 9.38E 00 Ni-63 18.80 2.95E 00 Co-60 15.58 2.44E 00 CO-58 3.80 5.96E-01 Cs-137 0.09 1.44E-02 H-3 0.05 8.24E-03 C- 14 LLD Tc-99 LLD 1-129 LLD Other* 1.80 2.82E-01 Total 100.00 1.57E+01 Nuclides representing <1% of total shipped activity: Cr-5 1, Mn-54, Co-57, Ni-59, Sr-90, Nb-95, Zr-95, Sb-125, Cs-134, Ce-144, Pu-238, Pu-239/240, Pu-241, Am-241, Cm-242, Cm-243/244.

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

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

TABLE 7.10 (Continued)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2007

3. Solid Waste Disposition (Mode of Trans portation: Truck)

Waste Type Waste Container Number of Destination Class Type Shipments

a. Resin/filters B Poly *HIC I Studsvik Erwin, TN.

C Poly *HIC 2 Studsvik Erwin, TN.

b. Dry active waste A General Design 23 Energy Solutions Oak Ridge,TN.

General Design Energy Solutions A/B** 1 Oak Ridge,TN.

• High Integrity Container

• • One shipment included both Class A and B waste.

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation DestinatiotI 0 N/A N/A

ATTACHMENT 8.1 2007 Joint Frequency Tables

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 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 0 1 5 1 0 0 7 NNE 0 3 7 3 0 0 13 NE 0 3 6 0 0 0 9 ENE 0 3 2 0 0 0 5 E 1 2 3 0 0 0 6 ESE 0 14 16 1 0 0 31 SE 0 16 28 7 0 0 51 SSE 0 6 36 .19 1 0 62 S 0 3 26 41 2 1 73 SSW 0 1 23 22 1 0 47 SW 0 7 7 1 0 3 18 WSW 0 2 0 0 0 0 2 W 0 1 0 0 0 0 1 WNW 0 0 0 6 0 0 6 NW 0 0 1 5 1 0 7 NNW 1 0 1 7 11 4 24 VARIABLE 0 0 0 0 0 0 0 TOTAL 2 62 161 113 16 8 362 Periods of calm (hours): 0 Hours of missing data: 6

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 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 0 3 9 6 2 0 20 NNE 1 7 5 7 0 0 20 NE 5 10 5 2 0 0 22 ENE 2 9 4 0 0 0 15 E 1 13 1 0 0 0 15 ESE 1 25 5 0 0 0 31 SE 5 14 18 8 0 0 45 SSE 0 20 41 27 2 0 90 s 0 6 35 40 6 0 87 SSW 0 8 17 14 4 0 43 SW 0 14 5 4 0 0 23 WSW 1 3 2 4 0 0 10 W 0 0 1 1 0 0 2 WNW 0 0 2 3 0 0 5 NW 0 4 9 8 4 2 27 NNW 0 7 11 7 14 3 42 VARIABLE 7 1 0 0 0 0 8 TOTAL 23 144 170 131 32 5 505 Periods of calm (hours): 0 Hours of missing data: 7

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO.31-DEC-07 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 0 5 18 9 4 1 37 NNE 6 11. 5 10 0 0 32 NE 11 10 4 1 0 0 26 ENE 11 17 6 1 0 0 35 E 9 10 2 0 0 .0 21 ESE 5 33 7 0 0 0 45 SE 1 16 25 7 0 0 49 SSE 3 29 37 33 3 0 105 S 2 18 59 50 6 0 135 SSW 3 17 28 5 0 0 53 SW 0 14 12 4 0 0 30 WSW 3 .13 1 1 0 1 19 W 1 3 1 3 0 0 8 WNW 0 1 9 6 1 0 17 NW 1 7 6 12 5 1 32 NNW 2 7 20 9 16 5 59 VARIABLE 19 0 0 0 0 0 19 TOTAL 77 211 240 151 35 8 722 Periods of calm (hours): 0 Hours of missing data:. 4

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 23:59 STABILITY CLASS:D 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 12 74 192 111 23 1 413 NNE 21 69 106 33 7 0 236 NE 19 44 70 9 0 0 142 ENE 25 47 47 3 0 0 122 E 28 99 26 2 0 0, 155 ESE 47 156 51 5 0 0 259 SE 21 241 338 69 5 0 674 SSE 16 145 401 209 18 0 789 S 20 100 273 142 14 0 549 SSW 7 71 71 16 1 0 166.

SW 19 50 14 10 1 0 94 WSW 15 28 4 4 1 0 52 W 10 29 15 6 2 0 62 WNW 10 19 44 11 7 2 93 NW 9 25 49 45 23 3 154 NNW 13 54 120 119 16 2 324 VARIABLE 88 34 7 1 0 0 130 TOTAL 380 1285 1828 795 118 8 4414 Periods of calm (hours): 1 Hours of missing data: 13

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 23:59 STABILITY'CLASS:E ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N ý, 3 14 10 9 0 0 36 NNE 0 32 17 2 0 0 51 NE 1 6 2 0 0 0 9 ENE 6 11 1 0 0 0 18 E 18 36 1 0 0 0 55 ESE 35 ill 10 0 0 0 156 SE 36 294 120 2 0 0 452 SSE 41 226 225 9 0 0 501 S 25 101 94 7 0 0 227 SSW 31 59 37 8 0 0 135 SW 28 24 14 6 0 0 72 WSW 17 21 5 1 0 0 44 W ii 19 9 3 0 0 42 WNW 16 30 21 1 0 0 68 NWI 10 37 31 1 0 0 79 NNW 6 14 8 4 0 0 32 VARIABLE 85 15 2 1 0. 0 103 TOTAL 369 1050 607 54 0 0 2080 Periods of calm (hours): 2 Hours of missing data: 14

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 23:59 STABILITY'CLASS:F ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 0 0 0ý 0 0 2 NNE- 0 3 2 0 0 0 5 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 5 1 0 0 0 0 6 SE. 7 50 7 0 0 0 64 SSE 16 27 2 0 0 0 45 S 18 25 6 1 0 0 50 SSW 20 18 2 0 0 0 40 SW 12 12 5 2 0 0 31 WSW 16 25 11 1 0 0 53 W 16 6 1 0 0 0 23 WNW 12 13 1 0 0 0 26 NW 21 24 7 0 0 0 52 NNW 4 1 1 0 0 0 6 VARIABLE 19 1 0 0 0 0 20 TOTAL 169 206 45 4 0 0 424 Periods of calm (hours): 1 Hours of missing data: 3

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 23:59 STABILITY CLASS:G 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 0 0 0 0 0 1 NNE 1 0 0 0 .0 0 1

ýNE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 1 0 0 0 0 0 1 ESE 1 0 0 0 0 0 1 SE 3 3 0 0 0 0 6 SSE 7 1 0 1 0 0 9 S 5 5 1 2 0 0 13 SSW 8 11 2 0 0 0 21 SW 15 17 9 0 '0 0 41 WSW 8 19 9 0 0 0 36 W 10 4 2 0 0 0 16 WNW 8 8 0 0 0. 0 16 NW 7 12 0 0 0 0 19 NNW 0 2. 0 0 0 0 2 VARIABLE 2 0 0 0 0 0 2 TOTAL 77 82 23 3 0 0 185 Periods of calm (hours): 2 Hours of missing data: 6

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC' COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-07 00:00 TO 31-DEC-07 23:59 STABILITY CLASS:ALL ELEVATION: 10 m.

Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 18 97 234 136 29 2 516 NNE 29 125 142 55 7 0 358 NE 36 73 87 12 0 0 208 ENE 44 87 60 4 0 0 195 E 59 160 33 2 0 0 254 ESE 94 340 89 6 0 0 529 SE 73 634 536 93 5 0 1341 SSE 83 454 742 298 24 0 1601 S 70 258 494 283 28 1 1134 SSW 69 185 180 65 6 0 505 SW 74 138 66 27 1 3 309 WSW 60 il1 32 11 1 1 216 W 48 62 29 13 2 0 154 WNW 46 71 77 27 8 2 231 NW 48 109 103 71 33 6 370 NNW 26 85 161 146 57 14 489 VARIABLE 220 51 9 2 0 0 282 TOTAL 1097. 3040 3074 1251 201 29 8692 Periods of calm (hours): 6 Hours of missing data: 62