ML051220447

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Radioactive Effluent Release Report
ML051220447
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/19/2005
From: Bradley S, Curtis J, Floyd E
TXU Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2009-0260
Download: ML051220447 (48)
v • d • e


Text

COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2004 - December 31, 2004 Prepared By: Date: _______

E. T. Floyd Radiation Protection Technician Reviewed By: C Date: /iX Scott E. Bradley Health Physics Supefvisor Approved By: Date: C___ 6

/ J. R. Curtis Radiation Protection Manager

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 Instrumen tation 6.2 Changes to the Offsite Dose Calculation Manual 6.3 New Locations for Dose Calculations or Environmental MonLitoring 6.4 Liquid Holdup and Gas Storage Tanks 6.5 Noncompliance with Radiological Effluent Control Requi rements 6.6 Resin Releases to the LVW Pond 6.7 Chanqes to the Liquid, Gaseous, and Solid Waste Tr eatment Systems 6.8 Meteorological Monitoring Program 6.9 Assessment of Doses i

TABLE OF CONTENTS 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary -2004 7.2 Abnormal Batch Liquid and Gaseous Release Summary -2004 7.3 Gaseous Effluents--Summation of All Releases -2004 7.4 Gaseous Effluents--Ground Level Releases -2004 7.5 Liquid Effluents--Summation of All Releases -2004 7.6 Liquid Effluents -2004 7.7 Doses From Liquid Effluents -2004 7.8 Doses From Gaseous Effluents -2004; Noble Gas Air Dose 7.9 Doses From Gaseous Effluents -2004; Site Iodines, Particulates and Tritium Dose, Adult Age Group 7.10 Doses From Gaseous Effluents -2004; Site Iodines, Particulates and Tritium Dose, Teen Age Group 7.11 Doses From Gaseous Effluents -2004; Site Iodines, Particulates and Tritium Dose, Child Age Group 7.12 Doses From Gaseous Effluents -2004; Site Iodines, Particulates and Tritium Dose, Infant Age Group 7.13 Solid Waste and Irradiated Fuel Shipments -2004 8.0 ATTACHMENTS 8.1 Joint Frequency Tables for 2004 8.2 Offsite Dose Calculation Manual for TXU Electric Comanche Peak Steam Electric Station Units 1 and 2, Revision 22.

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ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPSES Comanche Peak Steam Electric Station 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 iii

1.0 INTRODUCTION

This Radioactive Effluent Release Report, for Comanche Peak Steam Electric Station 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, 2004, through December 31, 2004.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2004 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).

A summation of all the radioactive gaseous releases to the environment during 2004 produced the following results:

The total gaseous tritium activity released from the site for 2004 was 40.5 Curies which is a decrease from the 49.1 Curies in 2003. 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 (ie, 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 2004 was 5.62 Curies. This is a slight increase from the 1.48 Curies released in 2003.
  • The total gaseous particulate activity released for 2004 was 0.00 Curies, as was reported in 2003 also.
  • The gross alpha released has continued at 0.00 Curies for 2004 matching the performance of the previous eight years.

The iodine released was also 0.00 Curies for 2004.

  • The calculated gamma air dose from the site due to noble gases released during 2004 is 4.10E-03 mrad. This is an increase from 2003 which calculated out as 9.09E-04 mrad; the 2004 value represents only 0.021% of the annual limit for each reactor unit.
  • The calculated beta air dose from the site due to noble gases released during 2004 is 1.63E-03 mrad which is an increase from 2003 which calculated out as 3.99E-04 mrad; however, this represents only 0.004% of the annual limit.
  • The total whole body dose from the site due to gaseous radioactivity released based on I-131, I-133, H-3(tritium), and particulate nuclides for 2004 calculated out to be 0.039 mrem. This value is a decrease from the 1

2003 whole body dose of 0.047 mrem.

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

A summation of all the radioactive liquid releases to the environment during 2004 produced the following results:

  • The total number of Curies of radioactive nuclides released from the site in liquid effluents in 2004 was 1080.02 Curies, down from 1430.07 Curies in 2003.
  • Of the total Curies released from the site, tritium accounted for 1080.0 Curies while all other nuclides released accounted for only 0.02 Curies. The total curies of tritium released is down from the 2003 total of 1430.0 Curies. Tritium production is dependent on fuel type, power production and core power history.
  • The total whole body dose from the site due to liquid effluents calculated out at 1.05E-01 mrem which is only 1.75% of the annual limit for each unit. Tritium accounts for >99% of the calculated total whole body dose with the Squaw Creek Reservoir (SCR) tritium concentration being the controlling factor. The SCR tritium concentration for 2004 averaged 11,094 pCi/l which is statistically constant with 2003 which averaged 11,475 pCi/l.
  • The 2004 average SCR tritium concentration of 11,094 pCi/l is 36.98% of the reporting limit of 30,000 pCi/l.

The CPSES meteorological system achieved a 97.1% 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 also achieved a >90%

recoverable data rate for 2004.

There are no ODCM noncompliance related issues discussed in this annual report.

During 2004 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

There were two revisions to the ODCM approved and/or implemented in 2004. Details are discussed in section 6.2 of this report. I For 2004, the total volume of solid radwaste buried was 34.0 cubic meters and the total radioactivity buried was 474 curies.

The majority of the buried solid waste volume comes from dry active waste at 28.7 cubic meters. Also, spent resins and filters were responsible for >99% of all the total radioactivity buried.

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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 CPSES 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 CPSES 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.
  • Changes to the ODCM in the form of a complete, legible copy of the entire ODCM.
  • A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use 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 radioactive 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 CPSES Unit 1 and Unit 2 in 2004.
  • An assessment of radiation doses to the likely, most exposed MEMBER OF THE PUBLIC from CPSES releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the reporting 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.

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1.2 General Trend Graphs

  • Total Whole Body Dose due to Gaseous Activity Released from CPSES
  • Total Gaseous Fission and Activation Activity Released from CPSES
  • Total Whole Body Dose due to Liquid Effluents Released from CPSES
  • Total Curies of Tritium Released in Liquid Effluents from CPSES
  • Squaw Creek Reservoir Average Tritium Concentration 4

Total Whole Body Dose due to Gaseous Activity Released from CPSES

  • 1995 1 1996 14OOE-0 1997 8.OOE-02 26.OOE-02 4U1999 U,4.OOE-02 200

'8 2.OOE-02 *2001

  • 2002 0.ealE+00 D 2003 Yearly Dose Totals *2004 Total Gaseous Fission and Activation Activity Released from CPSES 250
  • 1995 m*1996 200 031997 U) 150 - 1998 0

o 100 m20 50 U 2001 0 2002 l* 2003 Yearly Activity Totals m2004 5

col

Total Gaseous Tritium Activity Released from CPSES 100

  • 1995 U 1996 80 021997 "0 60 01998 0

m 1999 20 U12001

  • 2002
  • 2003 Yearly Activity Totals
  • 2004 Total Whole Body Dose Due to Liquid Effluents Released from CPSES 1.20E-01 U 1995 1.OOE-0 D 1996 0 1997 8.OOE-02 031998 6.OOE-02 l 1999 4.OOE-02 2000 2.OOE-02 U 2001
  • 2002 O.OOE+00 I I
  • 2003 Yearly Dose Totals 2004 6

Total Curies of Tritium Released in Liquid Effluents from CPSES 2000 U1995 U 1996 1500 031997 01998 1000 I 1999 U2000 500 2001 Y 2002 0 *2003 Yearly Totals *2004 Squaw Creek Reservoir Average Tritium Concentration 30000 1995 a

25000 I 1996 0 1997 20000 03 1998 15000 U1999 0.

10000 - 2000 5000 - 2001 0 U20-02 0*2003 Yearly Average Concentration 2004 7

Co3

2.0 SUPPLEMENTAL INFORMATION 2.1 ReQulatorv 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.OE-4 gCi/ml total activity.

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

a. During any calendar quarter to less than or equal to 1.5 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:

(264/V) EJ Ai/Ci < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:

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

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

V = volume of resins in the pond (gallons), and 264 = conversion factor (gCi/Ci per ml/gal) 9

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 Licnuid 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 pCi/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 CPSES 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 in liquid effluent releases was determined from the 10

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 I-131 and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and 11

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.

No abnormal effluent releases occurred during the period covered by this report.

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 LIOUID 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 7.13.

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6.0 RELATED INFORMATION 6.1 Operabilitv of Liquid and Gaseous MonitorinQ 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 were two revisions to the ODCM approved and/or implemented.

Revision 21 was issued and became effective on March 23, 2004.

This revision clarified and removed ODCM applicability versus the use and applicability of the CPSES Technical Specifications upon implementation of License Amendment No. 109. This license Amendment no longer allows the use of a general exception statement to Technical Specification LCO 3.0.4 in the ODCM.

This revision removed all the exception statements from the ODCM or marked the areas affected as N/A where required.

Revision 22 was issued and became effective on December 12, 2004. This revision implemented the name change of TXU Energy to TXU Power in all appropriate places. This revision removed a note on a future 'rated thermal power' upgrade which was implemented during the last Unit-i refueling outage.

Revision 22 also corrected typographical errors for: a missing summation symbol, removed an 'or equal to' sign, placed the symbol 'DF' in the denominator of an equation, explained the units involved in equation 1-11, corrected the numerical value of the transfer coefficient and added the missing multiplier for the time of exposure to the equation, removed an extra subscript 'I' involved in the equation, removed an extra 'I' from equation 2-15, corrected the designation of the meteorological expression of stability class 'j', changed the term 'K' to terrain correction factor, changed the units of

'Mi' and 'Ni' to mRad/yr and added a footnote to Table 4.11-1 that was inadvertently omitted during revision 20.

None of the changes made in revision 21 or 22 had any effect on actual data, calculations or releases covered by the ODCM. They were all editorial in nature. A complete copy of the ODCM Revision 22 is included in this report in Attachment 8.2 13

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 2004 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 CPSES were included in the 2004 Land Use Census.

6.4 Liquid Holdup and Gas Storaae 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.

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 CPSES ODCM and/or issues that did not comply with associated Administrative Controls and that failed to meet CPSES expectations regarding Station Radioactive Effluent Controls. Detailed documentation concerning evaluations of these events and corrective actions is maintained onsite.

6.5.1 Abnormal or Unplanned Gaseous and Liguid Releases There were no abnormal or unplanned gaseous or liquid releases during this reporting period.

6.5.2 ODCM Expectations and Controls During the time period of this report there were no issues reguarding the failure to meet the requirements of the Radiological Effluent Controls either from the ODCM or CPSES programs and procedures.

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6.6 Resin Releases to the LVW Pond A total of 338 ft5 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 now totals 6.60E-04 Curies, consisting of Cs-134, Cs-137 and Sb-125.

6.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems In accordance with the CPSES 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 2004, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 8.1.

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 Table 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 Tables 7.9 through 7.12.

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 2004 were any of these limits exceeded, therefore no evaluations are required.

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 CPSES employee recreational area and site tours through the CPSES 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 CPSES 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 CPSES Visitors Center was calculated based on two visits per year, thirty minutes each visit. Pathways included in the calculation were gaseous inhalation and submersion.

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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 BATCH LIOUID AND GASEOUS RELEASE

SUMMARY

- 2004 Ouarter 1 Ouarter 2 Ouarter 3 Ouarter 4 E

A'.

"LJJ'U.U4 A n-

~~Lazu

~.L.L Ai I 'I sSPe Ou~

Number of Batch Releases 1.50E+01 9.OOE+00 7.OOE+00 1.20E+01 Total Time Period for Batch Releases (min) 4.57E+03 2.90E+03 2.19E+03 3.16E+03 Maximum Time Period for a Batch Release (min) 3.56E+02 3.65E+02 3.54E+02 3.43E+02 Average Time Period for a Batch Release (min) 3.05E+02 3.22E+02 3.12E+02 2.63E+02 Minimum Time Period for a Batch Release (min) 2.47E+02 2.73E+02 2.83E+02 8.OOE+00 Average Stream Flow During Periods of Release (ft3 /s) N/A N/A N/A N/A B. Gaseous Releases All Sources Number of Batch Releases 5.lOE+01 3.40E+01 4.30E+01 4.30E+01 Total Time Period for Batch Releases (min) 1.89E+04 1.43E+04 1.51E+04 1.78E+04 Maximum Time Period for a Batch Release (min) 7.26E+02 2.OOE+03 4.21E+02 1.78E+03 Average Time Period for a Batch Release (min) 3.70E+02 4.20E+02 3.51E+02 4.13E+02 Minimum Time Period for a Batch Release (min) 1.95E+02 2.33E+02 2.31E+02 2.21E+02 T-1

TABLE 7.2 ABNORMAL BATCH LIOUID AND GASEOUS RELEASE

SUMMARY

- 2004 Ouarter 1 Quarter 2 Ouarter 3 Ouarter 4 A. Licuids Number of Releases 0 0 0 0 Total Activity Released, Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 B. Gases Number of Releases 0 0 0 0 Total Activity Released, Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 T-2

TABLE 7.3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES - 2004 Quarter Quarter l Quarter l Quarter ESt.Total 1 Fission and Error, %

A. Fission and Activation Gases

1. Total release (site) Ci 9.03E-01 2.22E-01 3.85E+00 6.53E-01 2.35E+01
2. Average release rate for pci/sec 1.15E-01 2.83E-02 4.84E-01 8.22E-02 period (site)
3. Percent of ODCM REC 5.74E-05 2.79E-05 6.42E-04 3.73E-05 limit (Dose Rate 500 mrem/yr/site)
4. Percent of ODCM REC 9.41E-05 3.71E-05 8.12E-04 6.06E-05 limit (Skin Dose Rate 3000 mrem/yr/site)

B. Iodines

1. Total Iodine-131 (site) Ci O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 1.43E+01
2. Average release rate for pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 perio d(site)
3. Percent of ODCM REC 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 limit (organ Dose Rate 1500 mrem/yr/site)

C. Particulates

1. Particulates with half Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.13E+01 lives > 8 days (site)
2. Average release rate for pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 perio (site) _
3. Percent of ODCM REC 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 limit (organ Dose Rate 1500 mrem/yr/site)
4. Gross alpha Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 radioactivity (site)

D. Tritium

1. Total release (site) Ci l_5.12E+00 1.15E+01 1.41E+01 9.73E+00jl 2.38E+01
1. 6E 0 1. E 0 1 .21.0 Av r g re e s rat Average release rate for pCi/sec 6.51E-01 1. 46E+00 1. 78E+00 1.22E+00 period (site)
3. Percent of ODCM REC  % 3.28E-02 7.35E-02 9.05E-02 6.25E-02 limit (organ Dose 7.5 mrem/qtr/unit) _ _ _ _ __

T-3

TABLE 7.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES--2004 Continuous Mode

[ Nuclides Released from the site Units 1

Quarter 11 Quarter 2 1 TQuarter 3

Quarter Qu 4 A. Fission and Activation Gases l None I Ci I O.OOE+OO I O.OOE+OO I O.OOE+OO l O.OOE+OO l None I Ci I O. OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I None I ci I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO l Total for period I Ci I O.OOE+OO j O.OOE+OO IO.OOE+OO I O.OOE+OO B. iodines I None I Ci IO.OOE+OO IO.OOE+OO I O.OOE+OO IO.OOE+OO Total for period ci O.OOE+OO O.OOE+OO O.OOE+OOJ O.OOE+OO C. Particulates-Halflife >= 8 Days None Ci IO.OOE+OO IO.OOE+OO O.OOE+OOI O.OOE+OO I Total for period ci O.OOE+OO I O.OOE+OO IO.OOE+OO I O.OOE+OO I D. Tritium H-3 I Ci I4.98E+00 I1.14E+01 I1.34E+01 9.72E+OQI]

Total for period [ Ci l_4.98E+00 I 1.14E+01 I 1.34E+01 I 9.72E+OOl T-4

TABLE 7.4 (con't.)

GASEOUS EFFLUENTS--GROUND LEVEL RELEASES--2004 Batch Mode Nuclides Released Quarter Quarter 3uarterQuarter from the site Units 1 2 3 4 A. Fission and Activation Gases Ar-41 Ci 2.48E-01 1.48E-01 3.57E+00 1.78E-01 Kr-85 Ci 5.93E-02 8.88E-03 1.28E-01 9.94E-02 Kr-85M Ci 1.01E-06 5.38E-06 O.OOE+00 O.OOE+OO Kr-87 Ci O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+OO Kr-88 Ci O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+OO Xe-131M Ci O.OOE+00 O.OOE+00 O.OOE+00 3.40E-03 Xe-133 Ci 4.71E-01 5.80E-02 1.45E-01 3.71E-01 Xe-133M ci 1.75E-04 1.35E-03 O.OOE+00 1.75E-03 Xe-135 Ci 1.24E-01 6.51E-03 O.OOE+00 3.23E-04 Xe-135M Ci 3.62E-05 2.30E-04 O.OOE+00 O.OOE+00 Xe-138 ci 3.27E-04 O.OOE+00 O.OOE+00 O.OOE+00 Total for period ci 9.03E-01 I2.23E-01_j3.84E+00 I6.54E-01 B. lodines I None I ci IO.OOE+00 I O.OOE+OO IO.OOE+00 I O.OOE+OO

.I Total for period I Ci I O.OOE+00 I O.OOE+00 I O.OOE+00 I O.OOE+00ll C. Particulates-Halflife >= 8 Days None I Ci IO.OOE+OO I O.OOE+00 IO.OOE+OO I O.OOE+00 I Total for period I Ci I O.OOE+00 _ O.OOE+00_ O.OOE+00 O.OOE+O0 D. Tritium I H-3 I ci I1.31E-01 I1.94E-02 I7.OOE-01  ! 1.27E-02 Total for period I Ci I 1.31E-01 I 1.94E-02 I 7.OOE-01 I 1.27E-02 T-5

TABLE 7.5 LIOUID EFFLUENTS--SUMMATION OF ALL RELEASES - 2004 Quarter Quarter l Quarter l Quarter Est.Total

___- 1 2 3 4 J Error, %

A. Fission and Activation Products

1. Total release (not Ci 6.82E-03 3.09E-03 5.24E-03 2.54E-03 3.03E+01 including tritiumz gases, alpha) (site)
2. Average diluted PCi/ml 5.07E-10 6.78E-11 6.39E-10 2.37E-10 concentration during period (site)
3. Percent of ODCM REC  % 2.34E-04 4.80E-05 5.23E-04 1.02E-04 limit (Z diluted conc/10*ECL)

B. Tritium

1. Total release (site) Ci 5.30E+02 2.42E+02 7.25E+01 2.35E+02 1.34E+01
2. Average diluted PCi/ml 3.94E-05 5.32E-06 8.84E-06 2.19E-05 concentration during period (site)
3. Percent of ODCM REC 3.94E-01 5.32E-02 8.84E-02 2.19E-01 limit (diluted conc/lE-02 pCi/ml)

C. Dissolved and Entrained Gases

1. Total release (site) Ci 6.04E-04 7.83E-05 1.80E-05 8.98E-05 1.16E+01
2. Average diluted 1Ci/ml 4.49E-05 1.72E-12 2.20E-12 8.35E-12 concentration during 0 I 2 II period (site) _ _ ____
3. Percent of ODCM REC 2.25E-05 8.60E-07 1.10E-06 4.18E-06 limit (diluted conc/2.OE-04 pCi/ml D. Gross Alpha Radioactivity
1. Total release (site) Ci JO.OOE+00 lQO.OOE+00 O.OOE+00 O.OOE+00 dO.0E+00 volume of waste released (prior to dilution)

(site) n volume dilution of water used during period (Note 1)(site)

Note 1: The dilution volume reported is the total dilution volume during periods when effluent releases were occurring. The additional dilution volume available when there are no effluent releases occurring is not included.

T-6

TABLE 7.6 LIQUID EFFLUENTS--2 004 Continuous Mode l Nuclides Released Units l Quarter Quarter l Quarter Quarter ]

A. Fission and Activation Products l None i C O.OOE+00 ]I O. OOE+00 O.OOE+O0 0.OOE+0O Total for period llj 0.OOE+O l.OOE+O 0.OOE+00 O.OOE+O0 B. Tritium _ _ _ __ __ __ _

None Ci ll O.OOE+OO ]I O.OOE+OO 1 O.OOE+OO O.OOE+OO Total for period j Ci l O.OOE+OO EO.OOE+OO l O.OOE+OO lO.OOE+00 C. Dissolved and Entrained Gases None I Ci l O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+00 Total for period J Ci O.OOE+00 J O.OOE+00 O.OOE+00 O.OOE+0O D.

l Gross Alpha Radioactivity None Total for period l

ll Ci Ci llO.OOE+O0 llO.OOE+OO O.OOE+00 _O.OOE+O0 I O.OoE+oo ]IO.OOE+OO 0 O.OOE+0O !

O.OOE+OO l T-7

TABLE 7.6 (continued)

LIQUID EFFLUENTS--2004 Batch Mode Nuclides Released Units I Quarter 1 Quarter 2 Quarter 3 Quarter 4 A. Fission and Activation Products Co-57 Ci O.OOE+00 O.OOE+00 4.56E-06 1.51E-06 Co-58 Ci 1.44E-04 9.57E-04 8.75E-04 1.26E-04 Co-60 Ci 3.37E-04 3.51E-04 2.29E-04 1.40E-04 Cr-51 Ci 4.17E-05 3.74E-05 1.50E-04 O.OOE+00 Fe-55 Ci 8.34E-04 3.44E-04 4.29E-04 8.36E-04 Fe-59 Ci O.OOE+00 6.70E-06 O.OOE+00 O.OOE+00 In-113M Ci 3.21E-06 O.OOE+00 O.OOE+00 O.OOE+00 Mn-54 Ci 2.10E-04 4.54E-05 5.88E-05 4.31E-06 Nb-95 Ci O.OOE+00 8.77E-06 O.OOE+00 O.OOE+00 Nb-97M Ci 1.OOE-06 O.OOE+00 O.OOE+00 O.OOE+00 Ru-106 Ci 1.OOE-05 O.OOE+00 O.OOE+00 O.OOE+00 Sb-124 Ci 2.45E-05 2.68E-05 4.54E-05 O.OOE+00 Sb-125 Ci 5.21E-03 1.31E-03 3.44E-03 1.44E-03 Sb-127 Ci 1.91E-06 O.OOE+00 O.OOE+00 O.OOE+00 Sn-113 Ci 2.65E-06 O.OOE+00 O.OOE+00 O.OOE+00 W-187 Ci 2.36E-06 O.OOE+00 O.OOE+00 O.OOE+00 Zr-95 Ci O.OOE+00 O.OOE+00 3.85E-06 O.OOE+00 Zr-97 Ci 7.15E-07 O.OOE+00 O.OOE+00 O.OOE+00 Total for Period Ci l 6.82E-03 l 3.09E-03 J5.24E-03 2.55E-03 B. Tritium H-3 l Ci l 5.30E+02 l 2.42E+02 l 7.25E+01 l 2.35E+02 Total for period T ci T5.30E+02 l2.4d2E+02 l7.25E+01 l2.35E+02 C. Dissolved and Entrained Gases Xe-133 l Ci I5.75E-04 l7.83E-05 1.80E-05 l8.98E-05 Xe-133M Ci I2.78E-05 O.OOE+00 IO.OOE+00 .OOE+00 Total for period Ci 6.05E-04 7.83E-05 1.80E-05 18.98E-05 D. Gross Alpha Activity llNone l Ci lo .OOE+00 lO.OOE+00 lO.OOE+00 lO.OOE+00 Total for period Ci l O.OOE+00 l O.OOE+00 O.OOE+00 0.OOE+00 T-8

TABLE 7.7 DOSES FROM LIOUID EFFLUENTS -2004(mrem)(site)

Any Organ 5 mrem/qtr/unit -- 10 mrem/yr/unit.

Whole Body 1.5 mrem/qtr/unit -- 3 mrem/yr/unit.

Organ Bone Liver whole Thyroid Kidney Lung GI-LLI I YB Quarter 1 4.38E-06 2.74E-02 2.74E-02 2.74E-02 2.74E-02 2.75E-02 2.74E-02

% Limit 4.38E-05 2.74E-01 9.13E-01 2.74E-01 2.74E-01 2.75E-02 2.74E-01 per unit Quarter 2 2.43E-06 2.76E-02 2.76E-02 2.76E-02 2.76E-02 2.77E-02 2.78E-02

% Limit 2.43E-05 2.76E-01 9.20E-01 2.76E-01 2.76E-01 2.77E-01 2.78E-01 per unit Quarter 3 1.92E-06 2.66E-02 2.66E-02 2.66E-02 2.66E-02 2.66E-02 2.66E-02

% Limit 1.92E-05 2.66E-01 8.87E-01 2.66E-01 2.66E-01 2.66E-01 2.66E-01 per unit Quarter 4 2.99E-06 2.27E-02 2.27E-02 2.27E-02 2.27e-02 2.28E-02 2.28E-02

% Limit 2.99E-05 2.27E-01 7.57E-01 2.27E-01 2.27E-01 2.28E-01 2.28E-01 per unit I I I I I I Total 1.46E-05 1.05E-01 1.05E-01 1.05E-01 1.05E-01 1.05E-01 2004 4 I 1.05E-01

% Limit 7.30E-05 5.25E-01 1.75E+00 5.25E-01 5.25E-01 5.25E-01 5.25E-01 per unit I_ __

Theoretical Maximum Age Group - Adult Theoretical Highest Organ Dose - LUNG T-9

TABLE 7.8 DOSES FROM GASEOUS EFFLUENTS -2004 site Noble Gas Air Dose (mRad) 5 mrad gamma/qtr/unit -- 10 mrad beta/qtr/unit 10 mrad gamma/yr/Unit -- 20 mrad beta/yr/unit Air Dose (mRad) Gamma Air Beta Air Quarter 1 2.84E-04 1.81E-04

% Limit per unit 2.84E-03 9.05E-04 Quarter 2 1.47E-04 6.07E-05

% Limit per unit 1.47E-03 3.04E-04 Quarter 3 3.48E-03 1.27E-03

% Limit per unit 3.48E-02 6.35E-03 Quarter 4 1.87E-04 1.23E-04

% Limit per unit 1.87E-03 6.15E-04 Total 2004 4.10E-03 1.63E-03

% Limit per unit 2.05E-02 4.08E-03 T-10

TABLE 7.9 DOSES FROM GASEOUS EFFLUENTS -2004 Site Iodines, Particulates and Tritium Dose Adult Age Group, (mrem)

Any Organ Dose Limit - 7.5 mrem/qtr/unit -- 15 mrem/yr/unit Organ Bone Liver Whol e Thyroi d Ki dney Lung GI-LLI Ski n Qtr-l O.OOE+00 3.26E-03 3.26E-03 3.26E-03 3.26E-03 3.26E-03 3.26E-03 1.72E-03

% Limit O.OOE+00 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 1.15E-02 per Unit _ _ _ _ __ _ _ _ _ _ _ _ _

Qtr-2 O.OOE+00 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 8.36E-04

% Limit O.OOE+00 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 5.57E-03 per Unit Qtr-3 O.OOE+00 9.00E-03 9.OOE-03 9.OOE-03 9.OOE-03 9.OOE-03 9.OOE-03 1.93E-02

% Limit O.OOE+00 6.OOE-02 6.OOE-02 6.OOE-02 6.OOE-02 6.OOE-02 6.OOE-02 1.29E-01 per Unit Qtr-4 O.OOE+00 6.19E-03 6.19E-03 6.19E-03 6.19E-03 6.19E-03 6.19E-03 1.12E-03

% Limit O.OOE+00 4.13E-02 4.13E-02 4.13E-02 4.13E-02 4.13E-02 4.13E-02 7.47E-03 per Unit I I I I I I _ _

Total O.OOE+00 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-02 2.30E-02

% Limit 0.OOE+00 8.60E-02 8.60E-02 8.60E-02 8.60E-02 8.60E-02 8.60E-02 7.67E-02 per Unit IIII T-11

TABLE 7.10 DOSES FROM GASEOUS EFFLUENTS -2004 Site Iodines, Particulates and Tritium Dose Teen Age Group, (mrem)

Any Organ Dose Limit - 7.5 mrem/qtr/unit -- 15 mrem/yr/unit Organ Bone Liver whole Thyroid Kidney Lung GI-LLI ski n Body Qtr-1 O.OOE+00 3.57E-03 3.57E-03 3.57E-03 3.57E-03 3.57E-03 3.57E-03 1.72E-03

% Limit O.OOE+00 2.38E-02 2.38E-02 2.38E-02 2.38E-02 2.38E-02 2.38E-02 1.15E-02 per Unit Qtr-2 O.OOE+00 8.OOE-03 8.00E-03 8.OOE-03 8.00E-03 8.OOE-03 8.00E-03 8.36E-04

% Limit O.OOE+00 5.33E-02 5.33E-02 5.33E-02 5.33E-02 5.33E-02 5.33E-02 5.57E-03 per Unit Qtr-3 O.OOE+00 9.86E-03 9.86E-03 9.86E-03 9.86E-03 9.86E-03 9.86E-03 1.93E-02

% Limit O.OOE+00 6.57E-02 6.57E-02 6.57E-02 6.57E-02 6.57E-02 6.57E-02 1.29E-01 per Unit Qtr-4 O.OOE+00 6.79E-03 6.79E-03 6.79E-03 6.79E-03 6.79E-03 6.79E-03 1.12E-03

% Limit O.OOE+00 4.53E-02 4.53E-02 4.53E-02 4.53E-02 4.53E-02 4.53E-02 7.47E-03 per Unit I I I I I I I Total O.OOE+00 2.82E-02 2.82E-02 2.82E-02 2.82E-02 2.82E-02 2.82E-02 2.30E-02

% Limit O.OOE+00 9.40E-02 9.40E-02 9.40E-02 9.40E-02 9.40E-02 9.40E-02 7.67E-02 per Unit IIIIII T-12

TABLE 7.11 DOSES FROM GASEOUS EFFLUENTS -2004 Site Iodines, Particulates and Tritium Dose Child Age Group, (mrem)

Any Organ Dose Limit - 7.5 mrem/qtr/unit -- 15 mrem/yr/unit Organ Bone Liver whole Thyroid Kidney Lung GI-LLI Skin Qtr-1 O.OOE+00 4.91E-03 4.91E-03 4.91E-03 4.91E-03 4.91E-03 4.91E-03 1.72E-03

% Limit O.OOE+00 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 1.15E-02 per Unit Qtr-2 O.OOE+00 1.10E-02 1.10E-02 1.10E-02 1.10E-02 1.10E-02 1.10E-02 8.36E-04

% Limit 0.OOE+00 7.33E-02 7.33E-02 7.33E-02 7.33E-02 7.33E-02 7.33E-02 5.57E-03 per Unit Qtr-3 O.OOE+00 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.98E-02

% Limit O.OOE+00 9.07E-02 9.07E-02 9.07E-02 9.07E-02 9.07E-02 9.07E-02 1.29E-01 per Unit Qtr-4 0.OOE+00 9.34E-03 9.34E-03 9.34E-03 9.34E-03 9.34E-03 9.34E-03 1.12E-03

% Limit 0.OOE+00 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 6.23E-02 7.47E-03 1_ _____ _____

per Unit I I I I I I Total 0.OOE+00 3.88E-02 3.88E-02 3.88E-02 3.88E-02 3.88E-02 3.88E-02 2.30E-02 2004 _ _ _ _ _ _ _ _ _ _ _ _ _ _

% Limit 0.OOE+00 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 7.67E-02 per Unit I I I I T-13

TABLE 7.12 DOSES FROM GASEOUS EFFLUENTS -2004 Site Iodines, Particulates and Tritium Dose Infant Age Group, (mrem)

Any Organ Dose Limit - 7.5 mre/qtr/unit -- 15 mrem/yr/unit Organ Bone Liver whole Thyroid Kidney Lung GI-LLI skin Qtr-1 O.OOE+00 2.14E-03 2.14E-03 2.14E-03 2.14E-03 2.14E-03 2.14E-03 1.72E-03

% Limit O.OOE+00 1.43E-02 1.43E-02 1.43E-02 1.43E-02 1.43E-02 1.43E-02 1.15E-02 per Unit _____

Qtr-2 0.OOE+00 4.80E-03 4.80E-03 4.80E-03 4.80E-03 4.80E-03 4.80E-03 8.36E-04

% Limit O.OOE+00 3.20E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 3.20E-02 5.57E-03 per Unit Qtr-3 O.OOE+00 5.91E-03 5.91E-03 5.91E-03 5.91E-03 5.91E-03 5.91E-03 1.93E-02

% Limit O.OOE+00 3.94E-02 3.94E-02 3.94E-02 3.94E-02 3.94E-02 3.94E-02 1.29E-01 per Unit _

Qtr-4 O.OOE+00 4.07E-03 4.07E-03 4.07E-03 4.07E-03 4.07E-03 4.07E-03 1.12E-03

% Limit O.OOE+00 2.71E-02 2.71E-02 2.71E-02 2.71E-02 2.71E-02 2.71E-02 7.47E-03 per Unit Total O.OOE+00 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 2.30E-02

% Limit O.OOE+00 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 7.67E-02 per Unit2_

T-14

TABLE 7.13 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2004 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste shipped Shipped Buried Buried Percent m Ci m3 Ci Error
a. Spent resins/filters 2.19E+01 3.25E+02 5.31E+00 4.71E+02 +/-25%
b. Dry active waste 4.51E+02 2.91E+00 2.87E+01 3.11E+00 +/-25%
c. Irradiated components N/A
d. other N/A (oil/miscellaneous liquids sent to processor for volume reduction) l TOTAL 4.73E+02 3.28E+02 3.40E+01 4.74E+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 and filters that are handled and processed in a manner that is consistent with this waste stream.

2. Estimate of Major Nuclide Nuclide  % Abund. Activity composition (by type of waste) (Ci)
a. spent resins/filters Ni-63 40.71 1.32E+02 Fe-55 24.09 7.83E+01 Co-60 17.91 5.82E+O1 Cs-137 4.60 1.50E+01 Cs-134 3.75 1.22E+01 Mn-54 3.62 1.18E+01 Co-58 3.60 1.17E+01 H-3 0.04 1.28E-01 C-14 0.02 4.90E-02 Tc-99 LLD I-129 LLD others* 1.66 5.39E+00 TOTAL 100.00 3.25E+02
  • Nuclides representing <1% of total shipped activity: Cr-51, Co-57, Fe-59, zn-65, Sr-90, Nb-95, Zr-95, Sn-113, sb-125, Ce-144, Pu-238, Pu-239/240, Pu-241, Am-241, Cm-242, Cm-243/244 T-15

TABLE 7.13 (Continued)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2004

2. Estimate of Major Nuclide Nuclide  % Abund. Activity Composition (by type of waste) (Ci)
b. Dry active waste Fe-55 54.42 1.58E+00 Ni-63 12.87 3.75E-01 Co-60 11.64 3.39E-01 cr-51 7.40 2.15E-01 Co-58 6.16 1.79E-01 Nb-95 2.21 6.43E-02 Zr-95 2.20 6.41E-02 H-3 0.02 4.51E-04 C-14 0.03 1.02E-03 Tc-99 LLD I-129 LLD others* 3.05 8.68E-02 Total 100.00 2.91E+00
  • Nuclides representing <1% of total shipped activity: Mn-54, Co-57, Fe-59, Sn-113, sb-12 , Cs-137.
3. solid Waste Disposition (Mode of Transportation: Truck)

Waste Type Waste Container Number of Destination class Type shipments

a. Resin/filters A Poly *HIC 1 studsvik Erwin, TN.

B Poly *HIC 4 studsvik Erwin, TN.

b. Dry active waste A General 11 GTS Duratek Design oak Ridge,TN.
  • High Integrity Container B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A T-16

ATTACHMENT 8.1 Joint Frequency Tables for 2004

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 2 8 8 2 0 20 NNE 0 1 12 4 0 0 18 NE 2 6 4 0 0 0 12 ENE 0 3 3 0 0 0 6 E 1 4 3 0 0 0 8 ESE 0 13 8 0 0 0 21 SE 0 4 33 7 0 0 44 SSE 0 7 35 33 2 2 79 S 0 8 18 26 4 0 56 SSW 0 6 4 5 4 0 19 SW 0 2 2 0 0 0 4 WSW 0 0 2 0 0 0 2 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 1 1 2 5 3 3 15 NNW 0 2 11 12 2 0 27 VARIABLE 3 2 0 0 0 0 5 TOTAL 7 61 146 100 17 5 336 Periods of calm (hours): 0 Hours of missing data: 2

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 6 11 19 3 0 39 NNE 0 17 8 10 2 0 37 NE 2 13 9 1 0 0 25 ENE 5 16 5 0 0 0 26 E 0 9 3 0 0 0 12 ESE 0 12 10 0 0 0 22 SE 0 13 26 9 0 0 48 SSE 1 18 25 27 5 0 76 S 2 17 24 75 9 5 132 SSW 0 15 17 12 2 0 46 SW 0 9 14 0 0 1 24 WSW 0 6 2 4 0 0 12 W 0 0 1 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 9 11 1 1 22 NNW 0 7 12 12 3 2 36 VARIABLE 3 3 0 0 0 0 6 TOTAL 13 161 176 180 25 9 564 Periods of canlm (hours): 0 Hours of missing data: 0

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 23:59 STABILITY CLASS:C ELEVATION: 10 m.

Wind Speed mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 12 28 17 4 0 65 NNE 3 10 5 4 7 0 29 NE 7 21 8 6 0 1 43 ENE 8 12 4 1 0 0 25 E 3 14 1 0 0 0 18 ESE 3 20 11 1 0 0 35 SE 0 18 25 6 1 0 50 SSE 3 23 47 30 3 0 106 S 1 10 47 99 18 0 175 SSW 2 12 18 24 3 1 60 SW 1 8 13 7 1 2 32 WSW 2 7 11 7 0 0 27 W 1 1 9 1 0 0 12 WNW 0 0 3 0 1 0 4 NW 0 3 11 5 12 2 33 NNW 1 18 6 11 11 2 49 VARIABLE 29 2 1 0 0 0 32 TOTAL 68 191 248 219 61 8 795 Periods of calm (hours): 0 Hours of missing data: 0

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 10 84 155 135 28 0 412 NNE 13 57 121 66 11 0 268 NE 17 42 82 13 2 0 156 ENE 18 56 78 2 0 0 154 E 17 106 38 1 0 0 162 ESE 17 130 46 12 0 0 205 SE 15 148 282 70 5 0 520 SSE 15 95 398 281 44 2 835 5 11 70 313 283 27 3 707 SSW 12 39 66 38 6 0 161 SW 12 22 26 15 2 0 77 WSW 11 26 9 10 1 0 57 W 1 15 15 3 0 0 34 WNW 4 15 46 26 1 0 92 NW 1 30 58 66 13 0 168 NNW 10 32 83 117 50 2 294 VARIABLE 81 26 5 1 0 0 113 TOTAL 265 993 1821 1139 190 7 4415 Periods of calm (hours): 4 Hours of missing data: 19

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 6 16 32 6 0 0 60 NNE 3 24 24 0 0 0 51 NE 4 15 3 0 0 0 22 ENE 4 7 0 0 0 0 11 E 14 31 1 0 0 0 46 ESE 27 100 11 0 0 0 138 SE 20 229 172 4 0 0 425 SSE 15 156 215 6 0 0 392 S 20 61 86 4 0 0 171 SSW 18 37 51 8 0 0 114 SW 24 25 19 13 0 0 81 WSW 12 19 18 4 0 0 53 W 9 9 6 1 0 0 25 WNW 13 32 23 2 0 0 70 NW 20 63 31 1 0 0 115 NNW 6 20 18 7 0 0 51 VARIABLE 85 6 2 0 0 0 93 TOTAL 300 850 712 56 0 0 1918 Periods of calm (hours): 5 Hours of missing data: 1

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 1 0 0 0 3 NNE 0 1 2 0 0 0 3 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 1 1 0 0 0 0 2 SE 8 32 4 0 0 0 44 SSE 10 16 4 0 0 0 30 S 23 22 7 0 0 0 52 SSW 18 20 21 0 0 0 59 SW 29 17 16 0 0 0 62 WSW 18 24 7 1 0 0 50 W 17 9 5 0 0 0 31 WNW 12 10 2 0 0 0 24 NW 14 39 2 0 0 0 55 NNW 2 1 1 0 0 0 4 VARIABLE 39 0 0 0 0 0 39 TOTAL 194 192 72 1 0 0 459 Periods of calm (hours): 3 Hours of missing data: 0

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 0 4 0 0 0 0 4 SSE 2 0 0 0 0 0 2 S 2 2 1 0 0 0 5 SSW 5 14 7 0 0 0 26 SW 10 19 4 0 0 0 33 WSW 7 32 14 0 0 0 53 W 6 2 1 0 0 0 9 WNW 2 2 0 0 0 0 4 NW 7 18 2 0 0 0 27 NNW 0 1 0 0 0 0 1 VARIABLE 2 0 0 0 0 0 2 TOTAL 43 95 29 0 0 0 167 Periods of calm (hours): 1 Hours of missing data: 0

R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-04 00:00 TO 31-DEC-04 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 22 120 235 185 37 0 599 NNE 20 110 173 84 20 0 407 NE 33 97 106 20 2 1 259 ENE 37 94 90 3 0 0 224 E 37 164 46 1 0 0 248 ESE 48 277 86 13 0 0 424 SE 44 449 542 96 6 0 1137 SSE 47 315 724 377 54 4 1521 S 59 190 503 487 58 8 1305 SSW 55 143 184 87 15 1 485 SW 76 102 94 35 3 3 313 WSW 50 114 63 26 1 0 254 W 34 36 37 5 0 0 112 WNW 31 59 74 28 2 0 194 NW 43 154 115 88 29 6 435 NNW 19 81 131 159 66 6 462 VARIABLE 245 39 8 1 0 0 293 TOTAL 900 2544 3211 1695 293 29 8672 Periods of calm (hours): 13 Hours of missing data: 99

ATTACHMENT 8.2 Of f site Dose Calculation Manual For TXU Electric Comanche Peak Steam Electric Station Units 1 and 2, Revision 22.

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