ML091280374

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Radioactive Effluent Release Report, January 1, 2008 - December 31, 2008
ML091280374
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/09/2009
From: Valentine D
Luminant Generation Co, Luminant Power
To:
Office of Nuclear Reactor Regulation
References
CP-200900615, TXX-09066, FOIA/PA-2009-0260
Download: ML091280374 (45)
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Text

ENCLOSURE 1 TO TXX-09066 2008 Radioactive Effluent Release Report

2008 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2008 - December 31, 2008 Prepared By: David Valentine __Date: 4/09/08.

Reviewed By: Randy Walsh Date: 4/15/08 Approved By: Terry Marsh Date: 4/20/08

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 6.10 Groundwater Tritium Monitoring Program Page 2 of 44

TABLE OF CONTENTS (cont) 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 Meteorological Joint Frequency Tables Page 3 of 44

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 pCi Picocurie REC Radiological Effluent Control SORC Station Operations Review Committee uCi Microcurie WMT Waste Monitor Tanks WWHT Waste Water Holdup Tanks Page 4 of 44

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, 2008, through December 31, 2008.

1.1 Executive Summary The radioactive effluent monitoring program for the year 2008 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).

Gaseous Effluents:

A summary of all the radioactive gaseous releases to the environment during 2008 Gaseous Waste 2008 ' 2007 Comments Tritium Activity 61.27 Ci 55.9 1 Total Fission And Activation Activity 996.9 Ci 13.9 2 Total Particulate Activity * ' 8.44E-05 Ci 1..9E-06 2 Gross Alpha Activity 0 Ci 0 Ci 3 Iodine Activity 1.41E-04 Ci 0 Ci 2 Calculated Gamma Air Dose 3.93E-02 mRad 1.53E-3 mRad 2 Calculated Beta Air Dose 0.112 mRad 2.068E-3 mRad. 2 Total Whole body dose 0.0868 mRem 0.0785 mRem 4 Comments:

1 The major contributor to gaseous tritium activity is evaporation 'from the spent fuel pools. Factors contributing to the tritium activity in the pools is related to the type of fuel used (i.e., 18-month fuel) the core life and power output and number of core cycles.

2 The majority of the gaseous activity and 100% of the Iodine activity was released in the first 2 quarters of the year as a result of 2RF10 with fuel defects.

3 No alpha activity was released.

4 Whole body dose was still very low (0.29% of Technical Specification).

Overall the gaseous radioactivity releases from CPNPP are well controlled and maintained ALARA.

CPNPP is well below all applicable limits for gaseous releases.

Page 5 of 44

Liquid Effluents:

A summary of all the radioactive liquid releases to the environment during 2008:

Liquid Waste 2008 2007 Comments Total Activity (excluding tritium) 15.2 mCi 7.6 mCi 1 Tritium Activity 2426 Ci 532 Ci 2,3 Total Whole Body Dose 0.127 mRem 0.137 mRem n/a Comments /.

1 CPNPP had 2 refueling outages during 2008. Despite the fuel defects on Unit 2 at 2RF10, the site managed to limit the total activity (excluding tritium) to 15 mCi.

2 A combination of factors resulted in the large increase of tritium released during 2008 as described in Note 3. During 2007, an unusually low amount of tritium was released. Averaging the tritium from 2007 and 2008 results in a more "normal" value of 1479 Ci.

3 In preparation for 2RF10, 22 PET tanks were processed during the first quarter of 2008. Much of this waste water was due to U2 end of cycle dilutions and contained higher concentrations of tritium. Unit 1 tritium concentrations were at the highest level for the cycle. Lastly, with the use of IFBA (Integral Fuel Burnable Absorber) fuel, additional tritiated waste water was produced from initial borations and subsequent dilutions. The combination of all of these factors resulted in a much larger than usual total tritium release for 2008.

Meteorological Data The CPNPP meteorological system achieved a 98.0% recoverable data rate for the joint frequency parameters required by Regulatory Guide 1.23 for wind speed, wind direction and delta temperature.

Monitors OOS > 30 Days During 2008 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.

ODCM Changes There was one revision to the ODCM in 2008.Revis'ion 28 (9/11/08): LDCR-OD-2007-1 (EVAL-2006-003080-05) (JDS) - Revised the definition of rated thermal power to reflect a 4.5% increase on Units 1 and 2 as issued by the. NRC in Amendment 146 to the Operating Licenses and Technical Specifications.

Page 6 of 44

Solid Waste Summary of the solid waste production Total Waste 2008 2007  % Error Comments Shipped (m3) 362 1410 25% 1 Shipped (Ci) 383 652 '25% 2 Buried (m3) 40.6 180 25% 1 Buried (Ci) 559 475 25% 2 Comments 1 The majority of the volume was from dry active waste. The large. volume in 2007 was from the steam generator replacement outage.

2 The majority of the activity came from resins and filters.

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).

Groundwater Tritium A positive indication (2186 pCi/L) for tritium was found in the artesian basin near the water plant.

The source of the tritium was determined to be from the Squaw Creek Lake (approximate tritium concentration of 11,000 pCi/L). The basin discharges back to the lake. This concentration was well below the state reportable criteria of 20,000 pCi/L. This issue is tracked in our corrective action program.

A positive indication (8380 pCi/L) for tritium was also found in Waste Monitoring Basin C liner leachate. This water is contained within the double liner system of basin C; therefore, this incident does not confirm a leak from Basin C, but does suggest a leak in the primary liner of Basin C. Plans have been made to inspect and repair all basin liners. This issue is also tracked in our corrective action program.

See section 6.10 for the details.

Page 7 of 44

1.2 Historical Trend Graphs Total Gaseous Fission and Activation Activity Released from CPNPP 996.9 1000.00 100.00 0

0 S 10.00 I).

(U-0 0

I'-

1.00 0.10 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Total Gaseous Tritium Released from CPNPP 90.00 70.00 60.00 d

C 50.00 0

, 30.00 20.00 10.00 0.00 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Page 8 of 44

Total Whole Body Dose due to Gaseous Activity released from CPNPP 0.12 0.06 0) 0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Total Volume Liquid Effluents Released from CPNPP 1800000 1600000 1400000 1200000 S1000000 E

.2 800000 0

600000 400000 200000 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Page 9 of 44

Total Activity (Excluding H3) Released in Liquid Effluents from CPNPP 400.00 358.00 350.00 300.00 250.00 227.90 232.10 S200.00-100 144.00 150.00

  • ""17.60 21.60 5.8 76 1 0 0.00 - -E 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Total Curies of Tritium Released in Liquid Effluents from CPNPP 3000 2500

... 2000 1500 DI 1000 500 0~

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Page 10 of 44

Total Whole Body Dose Due to Liquid Effluents Released from CPNPP 0.08 0

0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Total Volume of Solid Radwaste Buried from CPNPP 200.00 180.00 180.00 160.00 140.00 120.00 E,

100.00 90.20 902 E

-2 80.00 0

60.00 z 40.6 400--

40.00 ': 2 .079034.00 T

20.00 4.19.20 1. 18.70 19.30 16.90 o~oo4-1 I-1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year Page 11 of 44

Total Curies of Solid Radwaste Buried from CPNPP

  • 1800-1620 1400-1200 116 S1000-S800-60011 474, 475 400 369 255 249 200 190 Year Page 12 of 44

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 15t mrems to any organ.

.2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 ptCi/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 Page 13 of 44
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) Aj/Cj < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:

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

C1 = 10CFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (jiCi/ml),

V = volume of resins in the pond (gallons), and 264 = conversion factor (jiCi/Ci per ml/gal) 2.1.5 Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 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 ptCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.

2.3 Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-1 and 4.11-2, respectively, of the CPNPP ODCM.

Page 14 of 44

2.3.1 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for the Primary Effluent Tanks (PET), Waste Monitor Tanks (WMT), Laundry Holdup and Monitor Tanks (LHMT) and Waste Water Holdup Tanks (WWHT). Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation, and gas flow proportional counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory. The, results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.

For batch releases of powdex resin to the LVW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite samples were analyzed quarterly, for Sr-89 and Sr-90, by a contract laboratory.

For continuous releases to the Circulating Water Discharge from the LVW pond, daily grab samples were obtained over the period of pond discharge. These samples were composited and analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques.. Composite samples were also analyzed for tritium and gross alpha radioactivity using liquid scintillation and gas flow proportional counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory.

2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For releases from Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.

For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed 'Weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for 1-131 and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode.

Monthly composites of particulate filters were analyzed for gross alpha activity, in the onsite laboratory using the gas flow proportional counting technique. Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by a contract laboratory.

Page 15 of 44

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 or unplanned liquid or gaseous effluent releases occurred during 2008. Table 7.2 summarizes the abnormal and unplanned releases.

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.

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 28. A complete copy of the ODCM, with change bars, will be provided as a separate Enclosure to the letter transmitting this report. The change revised the definition of rated thermal power to reflect a 4.5% increase on Units 1 and 2 as issued by the NRC in Amendment 146 to the Operating Licenses and Technical Specifications.

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 Page 16 of 44

Effluent Release Report. Based on the 2008 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 2008 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.

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 No normal, unplanned gaseous effluent releases occurred during 2008.

6.5.2 Abnormal, Unplanned Gaseous Effluent Release No abnormal, unplanned gaseous effluent releases occurred during 2008.

6.5.3 Abnormal. Unplanned Liquid Effluent Releases No abnormal, unplanned liquid effluent releases occurred during 2008.

6.6 Resin Releases to the LVW Pond A total of 277 ft3 of powdex resin was transferred to the LVW pond during the period covered by this report. The cumulative activity deposited in the LVW pond since operations began through the end of 2008 is 1.16E-03 Curies, consisting of Co-58, Co-60, Cs-134, Cs-137, 1-131 and Sb-125.

6.7 Chan2es 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 Page 17 of 44

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 2008, is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 8.1. During 2008, 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 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.

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 2008 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 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 Page 18 of 44

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.

6.10 Groundwater Tritium monitoring Program Samples of perched groundwater are taken quarterly in accordance with the site groundwater tritium monitoring program. During the first quarter of 2008, a sample from the Water Production Plant artesian basin (storm drain) had a positive value for tritium of 2.18E-6 uCi/cc (2186. pCi/L).

This value was well below state reportable limit of 20,000 pCi/L. The source of the tritium was from Squaw Creek Lake water (tritium concentration approximately 11,000 pCi/L) from a small leak in the water treatment system. Subsequent samples were taken to monitor for degrading conditions. Since this basin is part of the groundwater tritium monitoring program, the event was put into the corrective action program for tracking. The basin discharges back to Squaw Creek Lake.

Analysis of the fourth quarter ground monitoring conducted on 11/06/08 also indicated the presence of tritium in Waste Monitoring Basin C liner leachate at a concentration of 8380 pCi/L.

This water is contained within the double liner system of basin C; therefore, this incident does not confirm a leak from Basin C, but does suggest a leak in the primary liner of Basin C. A sample was collected on 11/17/08 from downgradient well #19 (located east of switchyard) and no tritium was detected, suggesting no release from secondary liner of Basin C. A vendor inspected the WMS liners, including Basin C, on 12/17/08 and indicated the integrity of liners appear to be in good condition. A scope of work for liner leak detection has been received from the contractor and a PIF is in preparation for funding both the leak detection work, as well as anticipated repairs.

Man. Act. 08-3781-03 and 04 have been issued to process and leak detect/repair, respectively.

6.11 Nonroutine planned release There was one nonroutine planned release. During the U2 refueling outage, fuel defects along with a minor steam generator manufacturing imperfection resulted in positive activity in the steam generators. Prior to opening the steam relief valves, the quantity of steam was estimated and a permit was generated to account for the steam release.

Page 19 of 44

SECTION 7.0 TABLES Page 20 of 44

Table 7.1 Site Liquid and Gaseous Batch Release Summary (2008)

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

1. Number of batch releases 22 13 14 12 61
2. Total time period for Batch releases (Minutes) 7.616E+03 4.504E+03 4.708E+03 3.837E+03 2.067E+04
3. Maximum time period for a batch release Minutes ) 4. 100E+02 4.020E+02 4.OOOE+02 3.620E+02 4. 100E+02
4. Average time period for a batch release (Minutes ) 3.462E+02 3.465E+02 3.363E+02 3.198E+02 3.388E+02
5. Minimum time period for a batch release (Minutes) 2.150E+02 3.080E+02 3.OOOE+02 2.390E+02 2.150E+02
6. Average stream flow during periods of release of liquid Effluent into a flowing stream (GPM) 8.937E+04 6.304E+04 6.376E+04 5.212E+04 2.683E+05 B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals
1. Number of batch releases 39 35 44 31 149
2. Total time period for batch releases ( Minutes ) 1.380E+04 1.480E+04 1.532E+04 1.264E+04 5.657E+04
3. Maximum time period for a batch release ( Minutes ) 5.890E+02 2.071E+03 4.560E+02 1.510E+03 2.071E+03
4. Average time period for a batch release ( Minutes ) 3.538E+02 4.230E+02 3.482E+02 4.078E+02 3.796E+02
5. Minimum time period for a batch release (Minutes) 1.350E+02 3.030E+02 1.890E+02 2.570E+02 1.350E+02 Page 21 of 44

Table 7.2 Site Abnormal Liquid and Gaseous Batch Release Summary (2008)

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

1. Number of batch releases  : 0 0 0 0 0
2. Total time period for Batch releases ( Minutes) O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00
3. Maximum time period for a batch release ( Minutes ) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00
4. Average time period for a batch release ( Minutes ) 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
5. Minimum time period for a batch release (Minutes ) 0.000E+00 0.OOOE+00 0.000E+00 O.000E+00 0.OOOE+00
6. Total Activity for all releases ( Curies) 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 B. Gaseous Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Totals
1. Number of batch releases  : 0 0 0 0 0
2. Total time period for batch releases (Minutes )  : 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
3. Maximum time period for a batch release (Minutes )  : 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
4. Average time period for a batch release (Minutes )  : 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00
5. Minimum time period for a batch release ( Minutes ) : 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00
6. Total Activity for all releases ( Curies )  : 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Page 22 of 44

Table 7.3 Site Gaseous Effluents - Summation of All Releases (2008)

Type of Effluent Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year A. Fission and Activation Gases

1. Total Release Curies
  • 5.050E+02 4.916E+02 2.092E-01 9.600E-02 9.969E+02
2. Average Release rate for period uCi/sec
  • 6.405E+01 6.236E+01 2.653E-02 1.218E-02 1.264E+02
3. Percent of Applicable Limit B. Radioiodines
1. Total Iodine-131 Curies 8.186E-05 5.861E-05 0.OOOE+00 0.OOOE+00 1.405E-04
2. Average Release rate for period uCi/sec 1.038E-05 7.434E-06 O.OOOE+00 0.OOOE+00 1.782E-05
3. Percent of Applicable Limit C. Particulates
1. Particulates ( Half-Lives > 8 Days Curies 1.231IE-05 O.OOOE+00 4.396E-06 6.776E-05 8.446E-05
2. Average Release rate for period uCi/sec 1.561E-06 O.OOOE+00 5.575E-07 8.594E-06 1.07 1E-05
3. Percent of Applicable Limit D. Tritium
1. Total Release Curies 9.549E+00 2.049E+01 1.715E+01 1.409E+01 6.127E+01
2. Average Release rate for period uCi/sec 1.2 11E+00 2.598E+00 2.175E+00 1.787E+00 7.772E+00
3. Percent of Applicable Limit E. Gross Alpha
1. Total Release 0.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+0O O.OOOE+00 O.OOOE+00
2. Average Release rate for period O.OOOE+00
  • Applicablelimits are expressed in terms of dose. Estimated total error for all values is <1.0%

Page 23 of 44

2008 Table 7.4 Site Gaseous Effluents - Ground Level Releases (2008)

Reactor Unit: Site Continuous Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Xe-133m Curies 6.313E+00 7.193E+00 0.000E+00 O.OOOE+00 1.351E+01 Xe-133 Curies 4.759E+02 4.805E+02 O.OOOE+00 O.OOOE+00 9.564E+02 Xe-135 Curies 7.770E+00 3.783E+00 O.OOOE+00 O.OOOE+00 1.155E+01 Total For Period Curies 4.900E+02 4.915E+02 O.OOOE+00 O.OOOE+00 9.815E+02 lodines 1-131 Curies 1.468E-05 5.769E-05 O.OOOE+00 O.OOOE+00 7.238E-05 Total For Period Curies 1.468E-05 5.769E-05 O.OOOE+00 0.000E+00 7.238E-05 Particulates Co-58 Curies O.OOOE+00 O.OOOE+00 4.396E-06 6.776E-05 ,7.215E-05 Total For Period Curies O.OOOE+00 O.OOOE+00 4.396E-06 6.776E-05 7.215E-05 Tritium H-3 Curies 9.476E+00 2.047E+01 1.714E+01 1.407E+61 6.115E+01 Gross Alpha No Nuclides Found N/A N/A N/A N/A Page 24 of 44

2008 Table 7.4 (cont.)

Site Gaseous Effluents - Ground Level Releases (2008)

Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Gases Ar-41 Curies 1.953E-01 1.247E-01 1.858E-01 9.533E-02

  • 6.012E-01 Kr-85m Curies 6.613E-03 0.OOOE+00 2.563E-05 0.OOOE+O0 6.639E-03 Kr-85 Curies 8.753E-01 2.041E-02 1.080E-02 4.447E-04 9.069E-01 Kr-88 Curies 0.OOOE+00 0.000E+00 4.353E-06 0.OOOE+OO 4.353E-06 Xe-131m Curies 1.649E-01 2.143E-04 O.000E+00 0.OOOE+OO 1.651E-01 Xe-133m Curies 2.043E-01 2.998E-06 2.996E-04 2.50 1E-06 2.046E-01 Xe-133 Curies 1.305E+01 5.850E-03 8.986E-03 2.255E-04 1.306E+01 Xe-135m Curies O.OOOE+00 0.000E+00 1.068E-04 0.OOOE+O0 1.068E:04 Xe-135 Curies 4.445E-01 0.000E+00 3.191E-03 0.OOOE+O0 4.477E-01 Total For Period Curies 1.494E+01 1.512E-01 2.092E-01 9.600E-02 1.539E+01 lodines 1-131 Curies 6.718E-05 9.125E-07 0.000E+00 0.OOOE+0O 6.809E-05 1-133 Curies 4.268E-05 0.OOOE+00 0.OOOE+00 0.OOOE+0O 4.268E-05 Total For Period Curies 1.099E-04 9.125E-07 0.000E+00 0.OOOE+00 1. 108E-04

)

Particulates Curies Cs- 134 1.23 IE-05 O:OOOE+00 0.OOOE+00 O.OOOE+00 1.231E-05 Total For Period Curies 1.231E-05 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.231E-05 Tritium H-3 Curies 7.285E-02 1.564E-02 1.339E-02 1.979E-02 9.270E-02 Gross Alpha No Nuclides Found Curies N/A N/A N/A N/A

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

Page 25 of 44

Table 7.5 Site Liquid Effluents - Summation Of All Releases (2008)

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

1. Total Release (not including tritium, gases, alpha) Curies 1.753E-03 8.541E-03 3.947E-03 9.165E-04 1.516E-02
2. Average diluted concentration during period uCi/ml 7.271 E- 11 5.074E- 10 2.316E-10 6.542E- I1 8.771E-10
3. Percent of Applicable Limit  % 0.000022 0.000399 0.000020 0.000026 B. Tritium
1. Total Release Curies 1.735E+03 2.435E+02 2.867E+02 1.608E+02 2.426E+03
2. Average diluted Concentration during period uCi/ml 7.197E-05 1.446E-05 1.682E-05 1.148E-05 1.147E-04
3. Percent of Applicable Limit  % 0.7197 0.1446 0.1682 0.1148 C. Dissolved and Entrained Gases
1. Total Release Curies 1.723E+00 6.527E-01 2.678E-02 2.092E-02 2.423E+00
2. Average diluted Concentration during period uCi/ml 7.149E-08 3.877E-08 1.571E-09 1.493E-09 1.133E-07
3. Percent of Applicable Limit 0.036 0.019 0.001 0.001 D: Gross Alpha Radioactivity
1. Total Release 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 1.619E+06 9.699E+05 1.070E+06 8.957E+05 4.555E+06 F. Volume of Dilution Water Used Liters 2.410E+10 1.683E+10 1.704E+10 1.401E+10 7.199E+ 10 Estimated total error for all values is <1.0%

Page 26 of 44

Table 7.6 Site Liquid Effluents (2008)

Continuous Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Fission & Activation Products No Nuclides Found N/A N/A N/A N/A Tritium H-3 Curies 0.000E+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 Radioactivity O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Fission & Activation Products Cr-51. Curies O.OOOE+00 1.561E-04 O.OOOE+00 O.OOOE+00 1.561E-04 Mn-54 Curies 4.7-25E-05 1.075E-05 0.000E+00 O.OOOE+00 5.801E-05 Fe-55 Curies 9.657E-04 7.116E-04 0.000E+00 O.OOOE+00 1.677E-03 Fe-59 Curies 0.000E+00 5.341E-06 O.OOOE+00 O.OOOE+00 5.341E-06 Co-57 Curies 1.564E-06 1.562E-05 1.929E-05 2.053E-06 3.852E-05 Co-58 Curies 1.790E-04 7.276E-03 3.691E-03 8.027E-04 1.195E-02 Co-60 Curies 3.676E-04 3.132E-04 2.367E-04 8.378E-05 1.001E-03 Zr-95 Curies O.OOOE+00 2.116E-05 O.OOOE+00 1.164E-05 3.281E-05 Nb-95 Curies O.OOOE+00 3.135E-05 O.OOOE+00 1.635E-05 4.770E-05 Sb-125 Curies 1.896E-04 O.OOOE+00 O.OOOE+00 O.OOOE+00 1.896E-04 1-133 Curies 1.124E-06 0.000E+00 O.OOOE+00 O.OOOE+00 1.124E-06 Sn- 117m Curies 7.549E-07 O.OOOE+00 O.OOOE+00 O.OOOE+00 7.549E-07 Total For Period Curies 1.753E-03 8.541E-03 3.947E-03 9.165E-04 1.516E-02 Tritium H-3 Curies 1.735E+03 2.435E+02 2.867E+02 1.608E+02 2.426E+03 Page 27 of 44

Table 7.6 (cont.)

Site Liquid Effluents (2008)

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Dissolved And Entrained Gases Kr-85m Curies 6.028E-04 O.OOOE+00 O.OOOE+00 0.000E+00 6.028E-04 Kr-85 Curies 7.966E-02 5.11 1E-02 2.660E-02 2.084E-02 1.782E-01 Kr-88 Curies 3.450E-04 O.OOOE+00 0.000E+00 O.OOOE+00 3.450E-04 Xe-131m Curies 4.432E-02, 1.964E-02 O.OOOE+00 O.OOOE+00 6.396E-02 Xe-133m Curies 1.742E-02 6.805E-03 O.OOOE+00 O.OOOE+00 2.422E-02 Xe-133 Curies 1.576E+00 5.740E-01 1.845E-04 7.325E-05 2.150E+00 Xe- 135 Curies 4.788E-03 1.1 19E-03 O.OOOE+00 O.OOOE+00 5.908E-03 Total For Period Curies 1.723E+00 6.527E-01 2.678E-02 2.092E-02 2.423E+00 Gross Alpha Radioactivity 0. 0 0 0 0

  • Zeroes in this table indicate that no radioactivity was present at detectable levels Page 28 of 44

Table 7.7 Doses to a member of the public due to Liouid Releases (2008)

Cumulative Doses Per Quarter

% of  % of  % of  % of Tech Tech Tech Tech Tech Spec Spec Spec Spec Spec Organ Limit Units Quarter 1 Limit Quarter 2 Limit Quarter 3 Limit Quarter 4 Limit Total Body 1.500E+00 mRem 2.388E-02 1.592E+00 3.049E-02 2.033E+00 3.666E-02 2.444E+00 3.603E-02 6.489E-07 Bone 5.OOOE+00 mRem 3.249E-06 6.498E-05 2.169E-06 4.338E-05 O.OOOE+00 O.OOOE+00 3.244E-08 6.489E-07 Thyroid 5.OOOE+00 mRem 2.388E-02 4.776E-01 3.048E-02 6.096E-01 3.666E-02 7.332E-01 3.603E-02 7.205E-01 Kidney 5.OOOE+00 mRem 2.388E-02 4.776E-01 3.048E-02 6.096E-01 3.666E-02 7.332E-01 3.603E-02 7.205E-01 Liver 5.OOOE+00 mRem 2.3 88E-02 4.777E-01 3.049E-02 6.097E-01 3.666E-02 7.332E-01 3.603E-02 7.205E-01 Lung 5.OOOE+00 mRem 2.389E-02 4.777E-01 3.048E-02 6.096E-01 3.666E-02 7.332E-01 3.603E-02 7.205E-01 GI-Lli 5.OOOE+00 mRem 2.390E-02 4.779E-01 3.076E-02 6.152E-01 3.669E-02 7.338E-01 3.614E-02 7.229E-01 Cumulative Doses per Year

% of Tech Year to Tech Spec Ending Spec Organ Limit Units Date Limit Receptor Limit Bone 1.000E+01 mRem 5.450E-06 5.450E-05 Liquid Receptor - Adult Liq Annual Organ Dose Liver 1.000E+01 mRem 1.271E-01 1.27 1E+00 Liquid Receptor - Adult Liq Annual Organ Dose Thyroid 1.000E+01 mRem 1.270E-01 1.270E+00 Liquid Receptor - Adult Liq Annual Organ Dose Kidney 1.0003E+01 mRem 1.270E-01 1.270E+00 Liquid Receptor - Adult Liq Annual Organ Dose Lung 1.000E+01 mRem 1.271E-01 1.27 1E+00 Liquid Receptor - Adult Liq Annual Organ Dose GI-Lli 1.000E+01 mRem 1.275E-01 1.275E+00 Liquid Receptor - Adult Liq Annual Organ Dose Total Body 3.OOOE+00 mRem 1.271E-01 4.235E+00 Liquid Receptor - Adult Liq Annual TB Dose Total Dilution Volume for Quarter 1 2.410E+10 Total Dilution Volume for Quarter 2 1.683E+10 Total Dilution Volume for Quarter 3 1.704E+10 Total Dilution Volume for Quarter 4 1.401E+10 Page 29 of 44

Table 7.8 Air Doses Due To Gaseous Releases - Site (2008)

Cumulative Doses Per Quarter

% of  % of  % of  % of Tech Tech Tech Tech Tech Type of Spec Spec Spec Spec Spec Radiation Limit Units Quarter 1 Limit Quarter 2 Limit Quarter 3 Limit Quarter 4 Limit Gamma 5.0003E+00 mRad 2.013E-02 4.026E-01 1.888E-02 3.775E-01 1.8 18E-04 3.637E-03 9.278E-05 1.856E-03 Beta 1.000E+01 mRad 5.712E-02 5.712E-01 5.493E-02 5.493E-01 6.784E-05 6.784E-04 3.283E-05 3.283E-04 Cumulative Doses Per Year

% of Type of Tech Tech Radiation Spec Year to ,Spec Limit Units End Date Limit Receptor Limit Gamma 1.OOOE+01 mRad 3.928E-02 3.928E-01 Gas Receptor SB - Adult NG Annual Gamma Air Dose Gamma 1.0003E+01 mRad 3.928E-02 3.928E-01 Gas Receptor SB - Teen NG Annual Gamma Air Dose Gamma 1.0003E+01 mRad 3.928E-02 3.928E-01 Gas Receptor SB - Child NG Annual Gamma Air Dose Gamma 1.000E+01 mRad 3.928E-02 3.928E-01 Gas Receptor SB - Infant NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 3.928E-02 3.928E-01 Gas Receptor MI - Adult NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 3.928E-02 3.928E-01 Gas Receptor MI - Teen NG Annual Gamma Air Dose Gamma 1.OOOE+01 mRad 3.928E-02 3.928E-01 Gas Receptor MI - Child NG Annual Gamma Air Dose Gamma I.OOOE+01 mRad 3.928E-02 3.928E-01 Gas Receptor MI - Infant NG Annual Gamma Air Dose Beta 2.000E+01 mRad 1.121E-01 5.607E-01 Gas Receptor SB - Adult NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.121E-01 5.607E-01 Gas Receptor SB - Teen NG Annual Beta Air Dose Beta 2.OOOE+01,. mRad 1.121E-01 5.607E-01 Gas Receptor SB - Child NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.121E-01 5.607E-01 Gas Receptor SB - Infant NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.121E-01 5.607E-01 Gas Receptor MI - Adult NG Annual Beta Air Dose Beta 2.OOOE+01 mRad 1.121E-01 5.607E-01 Gas Receptor MI - Teen NG Annual Beta Air Dose Beta 2.000E+01 mRad 1.1211E-01 5.607E-01 Gas Receptor MI - Child NG Annual Beta Air Dose Beta 2.000E+01 mRad 1.121E-01 5.607E-01 Gas Receptor MI - Infant NG Annual Beta Air Dose Page 30 of 44

I Table 7.9 Doses to A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases (2008)

Cumulative Doses Per Quarter

% of  % of  % of  % of Tech Tech Tech Tech Tech Spec Spec Spec Spec Spec Organ Limit Units Quarter 1 Limit Quarter 2 Limit Quarter 3 Limit Quarter 4 Limit Skin 7.500E+00 mRem 1.062E-04 1.416E-03 1.297E-06 1.730E-05 2.067E-06 2.756E-05 3.186E-05 4.248E-04 Bone 7.500E+00 mRem 2.420E-03 3.227E-02 3.720E-04 4.961E-03 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 GI-Lli 7.500E+00 mRem 1.343E-02 1.790E-01 2.875E-02 3.833E-01 2.406E-02 3.207E-01 1.980E-02 2.640E-01 Lung 7.500E+00 mRem 1.365E-02 1.820E-01 2.873E-02 3.8311E-01 2.405E-02 3.207E-01 1.976E-02 2.635E-01 Kidney 7.500E+00 mRem 1.454E-02 1.939E-01 2.904E-02 3.872E-01 2.405E-02 3.207E-01 1.976E-02 2.634E-01 Liver 7.500E+00 mRem 1.597E-02 2.129E-01 2.892E-02 3.856E-01 2.405E-02 3.207E-01 1.976E-02 2.635E-01 Thyroid 7.500E+00 mRem 2.127E-01 2.835E+00 1.664E-01 2.219E+00 1.870E-02 2.494E-01 1.536E-02 2.048E-01 Total Body 7.500E+00 mRem 1.412E-02 1.883E-01 2.884E-02 3.845E-01 2.406E-02 3.208E-01 1.980E-02 2.641E-01 Cumulative Doses per Year

% of Tech Year to Tech Spec Ending Spec Organ Limit Units Date Limit Receptor Limit Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor SB - Adult Gas Annual Organ Dose Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor SB - Teen Gas Annual Organ Dose Liver 1.500E+01 mRemn 8.870E-02 5.914E-01 Gas Receptor SB - Child Gas Annual Organ Dose Total Body 1.500E+01 mRem 8.682E-02 5.788E-01 Gas Receptor SB - Child Gas Annual Organ Dose Kidney 1.500E+01 mRem 8.740E-02 5.826E-01 Gas Receptor SB - Child Gas Annual Organ Dose Lung 1.500E+01 mRem 8.620E-02 5.746E-01 Gas Receptor SB - Child Gas Annual Organ Dose GI-Lli 1.500E+01 mRem 8.603E-02 5.735E-01 Gas Receptor SB - Child Gas Annual Organ Dose Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor SB - Child Gas Annual Organ Dose Bone 1.500E+01 mRem 2.792E-03 1.861E-02 Gas Receptor SB - Infant Gas Annual Organ Dose Thyroid 1.500E+01 mRem 4.132E-01 2.754E+00 Gas Receptor SB - Infant Gas Annual Organ Dose Skin 1.500E+01 mRern 1.414E-04 9.429E-04 Gas Receptor SB - Infant Gas Annual Organ Dose Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor MI - Adult Gas Annual Organ Dose Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor MI - Teen Gas Annual Organ Dose Page 31 of 44

Table 7.9 (cont)

Doses to A Member Of The Public Due To Radioiodines, Tritium, and Particulates in Gaseous Releases (2008)

Cumulative Doses per Year (cont.)

% of Tech Year to Tech Spec Ending Spec Organ Limit Units Date Limit Receptor Limit Liver 1.500E+01 mRem 8.870E-02 5.914E-01 Gas Receptor MI - Child Gas Annual Organ Dose Total Body 1.500E+01 mRem 8.682E-02 5.788E-01 Gas Receptor MI - Child Gas Annual Organ Dose Kidney 1.500E+01 mRem 8.740E-02 5:826E-01 Gas Receptor MI - Child Gas Annual Organ Dose Lung 1.500E+01 mRem 8.620E-02 5.746E-01 Gas Receptor MI - Child Gas Annual Organ Dose GI-Lli 1.500E+01 rnRem 8.603E-02 5.735E-01 Gas Receptor MI - Child Gas Annual Organ Dose Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor MI - Child Gas Annual Organ Dose Bone 1.500E+01 mRem 2.792E-03 1.8611E-02 Gas Receptor MI - Infant Gas Annual Organ Dose Thyroid 1.500E+01 mRem 4.132E-01 2.754E+00 Gas Receptor MI - Infant Gas Annual Organ Dose Skin 1.500E+01 mRem 1.414E-04 9.429E-04 Gas Receptor MI - Infant Gas Annual Organ Dose Page-32 of 44

TABLE 7.10 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2008 A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

Shipped Shipped Buried Buried Percent

1. Type of Waste W Ci m3 Ci Error
a. Spent resins/filters 1.95E+01 3.83E+02 3.52E+00 5.43E+02 25%
b. Dry active waste 3.42E+02 3.16E-01 3.71E+01 1.52E+01 25%
c. Irradiated components N/A
d. Other (oil/miscellaneous liquids sent to processor for volume reduction) N/A TOTAL 3.62E+02 3.83E+02 4.06E+01 5.59E+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.

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

Fe-55 34.50 i*32E+02 NI-63 23.88 9.14E+01 CS-137 10.49 4.01E+01

'Co-58 9.20 3.52E+01 Co-60 8.79 3.36E+01 Cs-134 8.02 3.07E+01

a. Spent resins/filters H-3 2.23 8.52E+00 MN-54 1.77 6.77E+00 C-14 0.14 5.27E-01 Tc-99 LLD I-129 LLD Other* 0.98 *3.76E+00 Total 100.00 3.3.83E+02 Nuclides representing <1% of total shipped activity: Cr-51 ,Co-57,Fe-59,Zn-65,Sr-90,Zr-95 ,Nb-95 ,Ag- 110m,Sn- 113,Sn- 117m,Sb-122,SB- 124,Sb- 125,1-131 ,Cs- 136,Ba- 140,Ce- 144,Pu-238,Pu-239/240,Pu-241 ,Am-241 ,Cm-242,Cm-243/244.

Page 33 of 44

TABLE 7.10 (Cont)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2008

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

Fe-55 58.25 .1.84E-01 Ni-63 17.30 5.47E-02 Co-60 17.05 5.39E-02 Co-58 2.89 9.13E-03 bCR-51 1.57 4.96E-03

b. Dry active waste H-3 0.27 8.59E-04 C- 14 LLD Tc-99 LLD 1-129 LLD Other* 2.67 8.47E-03 Total 100.00 3.16E-01 Nuclides representing <1% of total shipped activity: Mn-54,Co-57,Nb-95,ZR-95,Sb- 125,Cs- 134,Cs- 137,Ce- 144,Pu-238,Pu-239/240,Am-241,Cm-242,Cm-243/244.
2. Estimate of Major Nuclide Nuclide %Abund. Activity Composition (by type of waste) (Ci)
d. Other (oil/miscellaneous liquids sent to.

processor for volume reduction)

Page 34 of 44

TABLE 7.13 (Cont)

SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2008

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

Waste Type Waste Container Type Number of Destination Class Shipments A Poly HIC* 1 Studsvik Erwin, TN

a. Resin/filters B Poly HIC* 3 Studsvik Erwin, TN C Poly HIC* 1 Studsvik Erwin, TN b- Dry active waste A General Design 5Energy Solutions Oak Ridge, TN
  • High Integrity Container B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 35 of 44

ATTACHMENT 8.1 2008 Meterological Joint Frequency Table Page 36 of 44

REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS A ELEVATION: 10m.

WIND ODIRECTION ~ind W- Speed (mph) at 10 ni.l~evel ___

____1-3 4-7 8-12 13-18 19-24 >24 TOTAL N

NNE NE ENE

, E ESE SE

,SSE , 9 3 .12 S 1 1 2 SSW _ _ 2 2 SW WSW 1 1 W

WNW NW NNW *__

VARIABLE TOTAL 3 10 4 Periods"of calm Hoursof missing data:

Page 37 of 44

REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS B ELEVATION: 10m.

WIND DIRECTON 9Wind Speed (mph) at 0 m. leve 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N

NNE NE ENE E

ESE SE SSE S 1 SSW SW WSW W

WNW NW, NNW VARIABLE _

TOTAL 1 Periods of calm Hours of missing data:

11 Page 38 of 44

REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS C ELEVATION: 10m.

WIND D~IRECTION,: Wind Speed (mpoh), atf 0in. lev/el____

___________, _ 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N

NNE NE ENE 1 1 E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW A1 1

VARIABLE TOTAL 1 1 Periods of calm Hours of missing data:

Page 39 of 44

REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS D ELEVATION: 10m.

WINDiDIRE:T,

,Win Sped (mph) at 10 m. level1

___,_, __ 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 26 79 68 14 190 NNE 17 20 4 1. 42 NE 17 35 9 61 ENE, 19 48 4 71 E 1 56 54 1 1 113 ESE 1 71 159 48 1 280 SE. 2 46 206 202 21 477 SSE 2 51 231 400 180 35 899 S 2 57 172 174 76 5 486 SSW 4 30 60 46 1 141 SW 2 56 54 18 2 132 WSW 3 38 16 8 1V 66 W 3 41 18 9 4 1 76 WNW 3 40 36 51. 20 9 159 NW 5 46 77 141 105 18 392 NNW 1 56 147 203 97 12 516 VARIABLE TOTAL 32 667 1412 1386 524 80.

Periods of calm 2 Hours of missing data:

Page 40 of 44

REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS E ELEVATION: 10m.

.1-3 4-7 A" 13-18 1! >24 114 3 26 23 -4 4 115 NNE 1 10 4 36

-t I NE 18 1 45 ENE 38 33 1 72 E 5 178 37 1 221 ESE 8 255 241 14 518 SE 5 215 470 159 19 2 870 SSE 6 122 319 234 39 720 S 10 120 111 64 10 1 316 SSW 11 80 72 16 179 SW. 14 65 44 13 2 1 139 WSW 10 64 33 8 2 117 W 13 56 34 19 4 1 127 WNW 19 70 93 43 9 4 238 NW 8 64 55 54 21 2 204 NNW 6 48 114 50 10 4 232 VARIABLE TOTAL 119 1429 1760 704 122 15 Periods of calm 22 Hours of missing data:

Page 41 of 44

REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS F ELEVATION: 10m.

Wind Speed (m ph) at*! . level

______-_____  : 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 1 NNE NE ENE E 2 2 ESE 1 4 1 6 SE 2 7 5 14 SSE 3 13 3 19 S 8 25 18 51 SSW 7 51 8 66 SW 3 36 14 53 WSW 8 46 4 58 W 8 23 2 33 WNW 3 36 4 43

'NW 9 2 11 NNW VARIABLE TOTAL 43 253 61 Periods of calm Hours of missing data:

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REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PIERIOD OF RECORD: 1 -JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS G ELEVATION: 10m.

WIND DIRECTION _ __Wid!Sed(p)a 0~.lvl___

" - 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N

NNE NE ENE E

ESE SE SSE S

SSW 2 2 SW 7 7 WSW 6 6 W 3 3 WNW 11 NW NNW VARIABLE TOTAL 1 Periods of calm Hours,of missing data: . .

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REG. Guide 1.21 Joint Frequency Table LUMINANT HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1-JAN-2008 00:00 to 31 -DEC-2008 23:59 STABILITY CLASS ALL Stability Classes ELEVATION: 1Om.

1T3Wind Speed (mph)8-1t 10 m. level WINDDIRETIO 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 53 137 91 19 306 NNE 1 27 40 8 2 78 NE 35 61 10 106 ENE 58 81 5 144 E 6 236 91 2 1 336 ESE 10 330 401 62 1 804 SE 9 268 681 361 40 2 1361 SSE 11 186 553 643 222 35 1650 S 20 202 301 239 88 6 856 SSW 22 165 140 62 1 390 SW 19 164 112 31 4 1 331 WSW 21 155 53 16 3 248 W 24 123 54 28 8 2 239 WNW 25 147 133 94 29 13 441 NW 13 119 134 195 126 20 607 NNW 7 104 261 254 107 16 749 VARIABLE I I I TOTAL 194 2372 3233 2101 651 95 Periods of calm 24 Hours of missing data: SC 124 hrs WD 68 hrs WS 59 hrs Total Percent Recovery SC 98.6% WD 99.2% WS 99.3% Overall 98.0%

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