CPSES-200600870, (Cpses), Transmittal of Year 2005 Radioactive Effluent Release Report
| ML061220666 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/28/2006 |
| From: | Madden F TXU Generation Co, LP, TXU Power |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CPSES-200600870, TXX-06080, FOIA/PA-2009-0260 | |
| Download: ML061220666 (50) | |
Text
TXU 4act Power TXU Powe Comancpe Peak Steam Electric Stabon P.O. Box 1002 (E01)
Glen Rosei TX 76043 Tel: 254 897 5209 Fax: 254 897 6652 mke.blevins~tu.con Mike Mevins Senior Vice President &
Chief Ntxuear Officer Ref: #I OCFR50.36(a)(2)
CPSES-200600870 Log # TXX-06080 File # RP-09 April 28, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF YEAR 2005 RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:
In accordance with Section 5.6.3 of the CPSES Unit 1 and 2 Technical Specifications (Appendix A to License Nos. NPF-87 and NPF-89) and Section 6.9.1.4 of the CPSES Offsite Dose Calculation Manual (ODCM), enclosed is the Radioactive Effluent Release Report which covers the reporting period from January 1, 2005 through December 31, 2005.
The tabular summaries of radioactive liquid and gaseous releases are provided in the format defined in Appendix B of Regulatory Guide 1.21, Rev. 1, dated June, 1974.
During this reporting period there were no changes to the CPSES ODCM.
If there are any questions regarding this report, contact Bob Kidwell at (254) 897-5310 or Scott Bradley at (254) 897-5495.
Aoo'8 q0c A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek
TXX-06080 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units I and 2.
Sincerely, TXU Generation Company LP By:
TXU Generation Management Company LLC Its General Partner Mike Blevins By:
2I22?2L W. Madden Director, Regulatory Affairs RJK Enclosure c -
B. S. Mallett, Region IV w/encl M. C. Thadani, NRR (clo)
Resident Inspectors, CPSES (clo)
2005 Report
COMAXCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2005 -
December Prepared By:
Reviewed By:
Approved By:
E. T. Floyd Radiation Protection Technician Scott E. Bradd Health Physics Su risor J. R. Curtis Radiation Protection Manager 31, 2005 Date:
_ /_/- 66 Date:
7 /.
Date:
TABLE OF CONTENTS ACRONYYMS 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 i
TABLE OF CONTENTS 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary -2005 7.2 Abnormal Batch Liquid and Gaseous Release Summary -2005 7.3 Gaseous Effluents--Summation of All Releases -2005 7.4 Gaseous Effluents--Ground Level Releases -2005 7.5 Liquid Effluents--Summation of All Releases -2005 7.6 Liquid Effluents -2005 7.7 Doses From Liquid Effluents -2005 7.8 Doses From Gaseous Effluents -2005; Noble Gas Air Dose 7.9 Doses From Gaseous Effluents -2005; Site Iodines, Particulates and Tritium Dose, Adult Age Group 7.10 Doses From Gaseous Effluents -2005; Site Iodines, Particulates and Tritium Dose, Teen Age Group 7.11 Doses From Gaseous Effluents -2005; Site Iodines, Particulates and Tritium Dose, Child Age Group 7.12 Doses From Gaseous Effluents -2005; Site Iodines, Particulates and Tritium Dose, Infant Age Group 7.13 Solid Waste and Irradiated Fuel Shipments -2005 8.0 ATTACHMENTS 8.1 Joint Frequency Tables for 2005 ii
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, 2005, through December 31, 2005.
1.1 Executive Summary The radioactive effluent monitoring program for the year 2005 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 2005 produced the following results:
The total gaseous tritium activity released from the site for 2005 was 38.3 Curies which is a decrease from the 40.5 Curies in 2004. The major contributor to gaseous tritium activity is evaporation from the spent fuel pools. Factors contributing to the tritium activity in the pools is related to the type of fuel used (i.e., 18-month fuel) the core life and power output and number of core cycles.
The total gaseous fission and activation activity (Noble gas) released from the site in 2005 was 845.0 Curies. This is an increase from the 5.62 Curies released in 2004. This increase was due to leaking fuel elements from Unit 1 reactor.
The total gaseous particulate activity released for 2005 was 1.20e-06 Curies, due to leaking fuel elements from Unit 1 reactor.
The gross alpha released has continued at 0.00 Curies for 2005 matching the performance of the previous nine years.
Iodine was released at a value of 2.48e-04 Curies for 2005 due to the leaking fuel elements from Unit 1 reactor.
The calculated gamma air dose from the site due to noble gases released during 2005 is 4.09e-02 mrad. This is an increase from 2004 which calculated out as 4.10e-03 mrad; the 2005 value represents only 0.205% of the annual limit for each reactor unit.
The calculated beta air dose from the site due to noble gases released during 2005 is 1.02e-01 mrad which is an increase from 2004 which calculated out as 1.63e-03 mrad; however, this represents only 0.255% of the annual limit for each reactor unit.
1
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 2005 calculated out to be 0.037 mrem.
This value is a decrease from the 2004 whole body dose of 0.039 mrem.
CPSES is well below all applicable limits for gaseous releases.
- A summation of all the radioactive liquid releases to the environment during 2005 produced the following results:
The total number of Curies of radioactive nuclides released from the site in liquid effluents in 2005 was 1480.02 Curies, up from 1080.02 Curies in 2004.
Of the total Curies released from the site, tritium accounted for 1480.0 Curies while all other nuclides released accounted for only 0.02 Curies.
The total curies of tritium released is up from the 2004 total of 1080.0 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 1.08E-01 mrem which is only 1.80% 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 2005 averaged 13,300 pCi/l which is statistically consistent with 2004 which averaged 11,094 pCi/l.
- The 2005 average SCR tritium concentration of 13,300 pCi/l is 44.33% of the reporting limit of 30,000 pCi/l.
The CPSES meteorological system achieved an 87.3% 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 approximately 87.0% recoverable data rate for 2005. The program goal is > 90%
recovery. See section 6.8 for further explanation.
There are no ODCM noncompliance related issues discussed in this annual report.
During 2005 there were no Technical Specification/ODCM effluent radiation monitors out of service for >30 days.
There were no revisions to the ODCM approved and/or implemented in 2005.
2
For 2005, the total volume of solid radwaste buried decreased to 19.3 cubic meters from 34.0 cubic meters last year and the total radioactivity buried decreased to 249 curies from 474 curies in 2004. The majority of the buried solid waste volume comes from dry active waste at 13.9 cubic meters.
Also, spent resins and filters were responsible for >98% of all the total radioactivity buried.
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.
- 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 2005.
3
- 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.
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 E
a)
E 0
0 1.20E-01 1.OOE-01 8.OOE-02 6.OOE-02 4.OOE-02
- 2. 00E-02 oi 1995
- 1996 a 1997 r 1998 E 1999 Eo 2000
- 2001 n 2002
- 2003
- 2004 E 2005 O.OOE+00 Yearly Dose Totals Total Gaseous Fission and Activation Activity Released from CPSES U) 0)
0 l o 1996
- m 1997, En 1998 r-1 999
- 2000 E 2001
- 2002 a 2003
- 2004
- 2005 Yearly Activity Totals 5
Total Gaseous Tritium Activity Released from CPSES 100 80 Un a@
60 40 El 1995 m 1996 n 1997 n 1998 i I 1999 Ei 2000
- 2001l o 2002
- 2003
- 2004 Ei 2005 20 0
Yearly Activity Totals Total Whole Body Dose Due to Liquid Effluents Released from CPSES 1.20E-01 1.OOE-01 8.OOE-02 6.OOE-02
- 4. OOE-02 E
z2 E
- 1996 El 1997 Elo 1998
- 1999 El 2000
- 2001 El 2002
- 2003
- 2004 i la 2005 2.OOE-02 O.OOE+00 Yearly Dose Totals 6
Total Curies of Tritium Released in Liquid Effluents from CPSES
- z 1995 2000
-- 777777-1996 El 1997 1500
=n 1998
- 1999E 10, El 2000 50)
-*2001 0
2003 Yearly Totals ra 2005 Squaw Creek Reservoir Average Tritium Concentration Eu 1995 30000 1996 25000 ri.1997 nn1998 20000
- 1999 O 15000 2
^ ::;
- s u:
- 0XSVf ;;
- fEiVA ;
l 2000 10000
- 2001 5000 3;
2002 Yearly Average Concentration
- 2004 Eo 2005 7
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
- a.
During any calendar quarter:
Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b.
During any calendar year:
Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.1.2 Iodine-131, Iodine-133.
Tritium and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem/yr to any organ.
The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:
- a.
During any calendar quarter:
Less than or equal to 7.5 mrems to any organ, and
- b.
During any calendar year:
Less than or equal to 15 mrems to any organ.
8
2.1.3 Licquid 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 pCi/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 AJ/CJ < 1.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:
Aj
=
pond inventory limit for a
single radionuclide j (Curies),
Ci
=
10CFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (ACi/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 Licquid 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 iCi/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 10
effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.
For batch releases of powdex resin to the LVW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release.
Composite samples were analyzed quarterly, for Sr-89 and Sr-90, by a contract laboratory.
For continuous releases to the Circulating Water Discharge from the LVW pond, daily grab samples were obtained over the period of pond discharge.
These samples were composited and analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques.
Composite samples were also analyzed for tritium and gross alpha radioactivity using liquid scintillation and gas flow proportional counting techniques, respectively.
Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory.
2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release.
For releases from Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy.
For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release with the exception of Containment vents made as a precursor to a Containment purge.
In these cases, samples collected and analyzed as a prerequisite to the vent were used to estimate total radioactivity released during the subsequent purge.
The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.
For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively.
Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters.
The radioiodine adsorbers and particulate filters were analyzed weekly for I-131 and gamma emitting radionuclides using gamma spectroscopy.
Results of the noble gas and tritium grab samples, radioiodine adsorber and 11
particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode.
Monthly composites of particulate filters were analyzed for gross alpha activity, in the onsite laboratory using the gas flow proportional counting technique.
Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by a contract laboratory.
2.4 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 7.1.
2.5 Abnormal or Unplanned Releases Abnormal releases are defined as the unintended discharge of a volume of liquid or airborne radioactivity to the environment.
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 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 7.13.
12
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 were no revisions to the ODCM approved and/or implemented. A complete copy of the ODCM is not required to be submitted with this report.
6.3 New Locations for Dose Calculations or Environmental Monitoring ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations and/or environmental monitoring, identified by the Land Use Census, to be included in the Radioactive Effluent Release Report.
Based on the 2005 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 2005 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.
13
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 Liquid 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 regarding the failure to meet the requirements of the Radiological Effluent Controls either from the ODCM or CPSES programs and procedures.
6.6 Resin Releases to the LVW Pond A total of 486 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 2005 totals 6.68E-04 Curies, consisting of Co-58, Co-60, 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.
14
6.8 Meteorological Monitoring Program In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 2005, is retained onsite.
This data is available for review by the NRC upon request.
Joint Frequency Tables are included in.1.
During 2005, the goal of >90% joint data recovery was not met.
The meteorological computer failed on August 1, 2005. It remained undiscovered until September 7, 2005. The problem was traced to a printer problem. As an interim corrective action, a sign has been placed on the printer to warn people using the computer system to avoid the same print error.
This compensatory measure has been effective in preventing a reoccurrence of the condition. Alternative meteorological data sources were available on site during this time frame.
Historical and current meteorological data was available if it had been needed to meet emergency planning needs. The strip-chart recorders and the ERF computer systems both had data during this timeframe but the data can not be sent to the meteorological computer and is therefore not considered as being recoverable, resulting in an 87.3% joint data recovery rate.
Long term solutions to address the problem are being planned in the CPSES Corrective Action Program (SMF-2006-000489).
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.
15
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 2005 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.
16
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.
17
SECTION 7.0 TABLES
Table 7.1 BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
2005 Ouarter 1 Quarter 2 Ouarter 3 Ouarter 4 A. Liauid Releases All Sources Number of Batch Releases 1.80E+01 1.00E+01 1.50E+01 1.00E+01 Total Time Period for Batch Releases (min) 5.43E+03 3.20E+03 4.88E+03 3.20E+03 Maximum Time Period for a Batch Release (min) 3.33E+02 3.45E+02 3.55E+02 3.52E+02 Average Time Period for a Batch Release (min) 3.02E+02 3.20E+02 3.25E+02 3.20E+02 Minimum Time Period for a Batch Release (min) 2.55E+02 2.96E+02 2.85E+02 2.80E+02 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 4.30E+01 3.30E+01 3.30E+01 3.50E+01 Total Time Period for Batch Releases (min) 1.60E+04 1.31E+04 1.23E+04 1.42E+04 Maximum Time Period for a Batch Release (min) 8.13E+02 9.90E+02 4.44E+02 1.44E+03 Average Time Period for a Batch Release (min) 3.71E+02 3.98E+02 3.73E+02 4.04E+02 Minimum Time Period for a Batch Release (min) 1.37E+02 2.98E+02 2.67E+02 1.79E+02 T-1
TABLE 7.2 ABNORMAL BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
2005 Ouarter 1 Quarter 2 Quarter 3 Quarter 4 A. Liquids Number of Releases 0
0 0
0 Total Activity Released, Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 B. Gases Number of Releases 0
0 0
0 Total Activity Released, Ci 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 T-2
TABLE 7.3 GASEOUTS EFF.LUENTS--SUMMATTON OF AT.L RPETASE 2005 Units Qrer Quarter Quarter I Quarter Est.Total L
1 2
3 l
4 1 Error, %
A.
Fission and Activation Gases
- 1. Total release (site)
Ci 1.11E+01 4.08E+01 1.30E+02 6.63E+02 2.35E+01
- 2. Average release rate for pCi/sec 1.42E+00 5.18E+00 1.64E+01 8.34E+01 period (site)
B. lodines
- 1. Total Iodine-131 (site)
Ci 0.OOE+00 0.OOE+00 0.OOE+00 1.82E-04 1.43E+01
- 2. Average release rate for pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 2.29E-05 period (site)
- 3. Percent of ODCM REC O.OOE+00 O.OOE+00 0.OOE+00 1.46E-02 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 0.OOE+00 period (site)
- 0. OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 limit (organ Dose Rate 1500 mrem/yr/site)
- 4. Gross alpha Ci 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 radioactivity (site)
D. Tritium
- 1. Total release (site)
Ci 7.60E+00 l_8.OOE+00 7.11E+00 lI1.56E+01 2.38E+01
- 2. Average release rate for peri od (si te) pCi/sec 9.78E-01 l1. 02 E+00
- 8. 95SE-01
- 1. 96E+00
4.87E-02 1.02E-01 9.01E-02 2.79E+00 limit (Organ Dose 7.5 mrem/qtr/unit)
T-3
TABLE 7.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES--2005 continuous Mode Nuclides Released Units T Quarter l Quarter l Quarter I Quarter from the site j
1 2
3_
4 A. Fission and Activation Gases
[ Xe-131M I
Ci I O.OOE+00 I O.OOE+00 I O.OOE+00 I O.OOE+00 l
[ Xe-133 I
ci T 8.87E+00 I 3.29E+01 I 1.22E+02 I 2.32E+01 I
[ Xe-135 I Ci I
O.OOE+00 I 8.68E-01 I 3.19E-01 I O.OOE+OO I Total for period I ci I8.87E+00 [
3.38E+01 I 1.22E+02 J 2.32E+01 B. Iodines 1 I-131 I
Ci I
O.OOE+00 I O.OOE+00 I O.OOE+00 I 1.82E-04 l l
I-133 Ci l O.OOE+00 I O.OOE+00 [ O.OOE+00 I 6.61E-05 I
Total for period I
Ci I O.OOE+00 I O.OOE+00 I O.OOE+00 I 2.48E-04 I C. Particulates-Halflife >= 8 Days I
None I
ci I O.OOE+OO I O.OOE+00 I O.OOE+00 I O.OOE+00 l
Total for period I Ci IO.OOE+00 J O.OOE+00 I O.OOE+00 I O.OOE+00 D. Tritium I
H-3 I
Ci l7.52E+00 7.96E+00 I7.08E+00 I1.53E+01 Il Total for period [ Ci I 7.52E+00 I 7.96E+00 I 7.08E+00 I 1.53E+01 T-4
TABLE 7.4 (con't.)
fth2CMfTTQ L
TLrT-NT'r C- -DArTTh1Th T.MMtT.
VIT.VAQrVQ-- Inn C r
rrvX
-a-nw~ -
vn
-VJ Batch Mode Nuclides Released Quarter J Quarter l Quarter J Quarter from the site Units 1
2 3
4 A. Fission and Activation Gases Ar-41 ci 2.26E-01 1.59E-01 1.69E-01 1.63E-01 Kr-85 Ci O.OOE+OO 6.11E-01 8.15E-01 8.36E-01 Kr-85M Ci 2.81E-02 O.OOE+00 O.OOE+00 1.10E+00 Kr-87 Ci 2.18E-02 O.OOE+00 O.OOE+OO O.OOE+00 Kr-88 ci 3.91E-02 O.OOE+OO O.OOE+OO O.OOE+00 Xe-131M Ci 1.02E-02 1.92E-01 1.63E-01 7.63E+00 Xe-133 Ci 1.36E+00 5.96E+OO 6.18E+00 5.65E+02 Xe-133M Ci 1.19E-03 2.64E-02 2.55E-02 1.15E+01 Xe-135 Ci 4.19E-01 2.70E-03 1.20E-03 5.37E+01 Xe-135M Ci 9.72E-02 O.OOE+00 O.OOE+00 1.97E-03 Xe-138 Ci O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 Total for period _
Cii 2.20E+00 l 6.95E+00 7.35E+00 6.40E+02 B. Iodines I
None l
Ci l O.OOE+00 l O.OOE+00 L O.OOE+00 L O.OOE+0O Total for period I Ci O.OOE+00 J O.OOE+00 l_O.OOE+00 l_O.OOE+00 C. Particulates-Halflife >= 8 Days None Ci !
O.OOE+00 ! O.OOE+00 1 O.OOE+00 l O.OOE+00 Total for period l
Ci l O.OOE+00 l O.OOE+00 l_O.OOE+00 O.OOE+00 D. Tritium l
H-3 I Ci I 8.52E-02 I 4.17E-02 I 3.79E-02 I 4.27E-01 ]
Total for period I
Ci
[ 8.52E-02 I 4.17E-02 I 3.79E-02 I 4.27E-01 I T-5
TABLE 7.5 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES -
2005 Units Quarter Quarter Quarter l Quarter l Est.Total 1
2 3
4 JError, %
A. Fission and Activation Products
- 1. Total release (not Ci 1.18E-02 4.89E-03 2.26E-03 2.71E-03 3.03E+0 including tritium, gases, alpha) (site)
- 2. Average diluted pci/ml 7.75E-10 4.42E-10 1.23E-10 2.26E-10 concentration during period (site)
B. Tritium
- 1. Total release (site)
Ci 6.80E+02 2.27E+02 3.05E+02 2.63E+02 1.34E+01
- 2. Average diluted
.Ci/ml 4.46E-05 2.05E-05 1.67E-05 2.19E-05 concentration during period (site)
C. Dissolved and Entrained Gases
- 1. Total release (site)
Ci 4.33E-01 1.63E-01 2.19E+00 4.50E-01 l 1.16E+01
- 2. Average diluted tCi/ml 2.84E-08 1.47E-08 1.20E-07 3.75E-08 concentration during period (site)
- 3. Percent of ODCM REC 1.42E-02 7.35E-03 6.OOE-02 1.88E-02 limit (diluted conc/2.OE-04 pCi/ml D. Gross Alpha Radioactivity
- 1. Total release (site)
Ci JO.OOE+00_ lO.OOE+O0_{ O.OOE+00 lO.OOE+O0OIl O.OOE+00 l E.
Volume of waste released Liters 1.24E+06 7.OOE+05 1.09E+06 7.24E+05 2.20E+00 (prior to dilution)
(site)
F. volume dilution of water Liters 1.53E+10 1.11E+10 1.83E+10 1.20E+10 1.OOE+O1 used during period (Note 1)(site)
Note 1:
The dilution volume reported is the total dilution volume during periods whenieffluent releases were occurring.
The additional dilution volume available when there are no effluent releases occurring is not included.
T-6
TABLE 7.6 LIOUID EFFLUENTS- -2005 Continuous Mode Nuclides Released J Units J Quarter Quarter Quarter Quarterjl A. Fission and Activation Products k
None
[l Ci ll O.OOE+O0 O.OOE+OO]I O.OOE+OO O.OOE+O0 Total for period J[
Ci O.OOE+0 I.OOE+OO O.OOE+O0 O.OOE+OO B. Tritium None I[ Ci O.OOE+OO ll OOE+OO ll O.OOE+OO II O-OOE+00 l Total for period i
O.OOE+OOO
.OOE+
C. Dissolved and Entrained Gases F
None I
ci I O.OOE+00 O.OOE+0O O.OOE.00 O.OOE+OO Total for period I
Ci O.OOE+OO l O.OOE+OO J O.OOE+OO ] O.OOE+OO D. Gross Alpha Radioactivity l None LI Ci llO.OOE+OO O.OOE+OO llO.OOE+0O 0l.OOE+OO Total for period C
OOE+OO
.OOE+0OO O.OOE+OO IJO.OOE+00 T-7
TABLE 7.6 (continued)
LIQUID EFFLUENTS--2005 Batch Mode Nuclides Released Units I Quarter 1 Quarter 2 l Quarter 3 Quarter 4 A. Fission and Activation Products As-76 Ci 2.91E-05 O.OOE+00 O.OOE+00 3.75E-05 Co-57 Ci 2.63E-06 1.85E-05 O.OOE+00 2.16E-05 Co-58 Ci 7.41E-05 3.95E-03 5.70E-04 1.36E-03 Co-60 Ci l.09E-04 4.05E-04 1.86E-04 2.45E-04 Cr-51 Ci 2.07E-04 6.47E-05 O.OOE+00 O.OOE+00 Cs-137 Ci O.OOE+00 O.OOE+00 O.OOE+00 2.63E-06 Fe-55 Ci 1.79E-03 O.OOE+00 O.OOE+00 5.35E-05 I-131 Ci O.OOE+00 O.OOE+00 O.OOE+00 9.84E-06 Mn-54 Ci O.OOE+00 1.67E-05 O.OOE+00 7.50E-06 Nb-95 Ci 6.95E-07 O.OOE+00 O.OOE+00 1.32E-05 Sb-124 Ci 4.36E-03 O.OOE+00 O.OOE+00 O.OOE+00 Sb-125 Ci 5.26E-03 4.35E-04 1.50E-03 9.66E-04 Sn-113 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.54E-06 Sr-85 Ci 1.24E-06 O.OOE+00 O.OOE+00 O.OOE+00 Y-88 Ci O.OOE+00 4.87E-06 O.OOE+00 O.OOE+00 Zr-95 Ci O.OOE+00 O.OOE+00 2.25E-06 1.10E-05 none Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 none Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Total for Period Ci 1.18E-02 4.89E-03 2.26E-03 2.71E-03 B. Tritium H-3 f
o Ci
[
6.80E+02 l 2.27E+02 l 3.05E+02 2.63E+02 Total for period Ci 6.80E+02 2.27E+02 3.05E+02 2.63E+02 C. Dissolved and Entrained Gases Kr-85 Ci 2.70E-02 1.50E-03 4.97E-02 1.22E-02 Xe-131M Ci 1.85E-02 5.87E-03 4.99E-02 1.03E-02 Xe-133 Ci 3.87E-01 1.55E-01 2.09E+00 4.19E-01 Xe-133M Ci 4.99E-04 2.39E-04 8.20E-03 6.51E-03 Xe-135 Ci 4.36E-06 O.OOE+00 1.20E-04 1.59E-03 Total for period Ci 4.33E-01 1.63E-01 2.20E+00 4.50E-01 D. Gross Alpha Activity None
) C 1
o.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Total for period l_
c;Ci o. OOE+00 l O.OOE+00 O.OOE+00 O.OOE+00 T-8
TABLE 7.7 DOSES FROM LIQUID EFFLUENTS -2005(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
_ _ _ _ _ _B o d y_
Quarter 1 9.69E-06 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02 2.08E-02
% Limit 9.69E-05 2.08E-01 6.93E-01 2.08E-01 2.08E-01 2.08E-01 2.08E-01 per unit Quarter 2 8.94E-08 2.56E-02 2.56E-02 2.56E-02 2.56E-02 2.56E-02 2.57E-02
% Limit 8.94E-07 2.56E-01 8.53E-01 2.56E-01 2.56E-01 2.56E-01 2.57E-01 per unit Quarter 3 2.84E-07 3.21E-02 3.21E-02 3.21E-02 3.21E-02 3.21E-02 3.21E-02
% Limit 2.84E-06 3.21E-01 1.07E+00 3.21E-01 3.21E-01 3.21E-01 3.21E-01 per unit Quarter 4 4.84E-06 2.96E-02 2.96E-02 2.96E-02 2.96e-02 2.96E-02 2.97E-02
% Limit 4.84E-05 2.96E-01 9.87E-01 2.96E-01 2.96E-01 2.96E-01 2.97E-01 per unit Total 1.38E-05 1.08E-01 1.08E-01 1.08E-01 1.08E-01 1.08E-01 1.08E-01 2005 5
% Limit 6.90E-05 5.40E-01 1.80E+00 5.40E-01 5.40E-01 5.40E-01 5.40E-01l per unitIII Theoretical Maximum Age Group - Adult Theoretical Highest Organ Dose -
LUNG T-9
TABLE 7.8 DOSES FROM GASEOUS EFFLUENTS -2005 Site Noble Gas Air 5 mrad gamma/qtr/unit --
10 mrad gamma/yr/unit --
Dose (mRad) 10 mrad beta/qtr/unit 20 mrad beta/yr/unit Air Dose (mRad)
Gamma Air Beta Air Quarter 1 7.96E-04 1.36E-03
% Limit per unit 7.96E-03 6.80E-03 Quarter 2 1.77E-03 4.70E-03
% Limit per unit 1.77E-02 2.35E-02 Quarter 3 4.98E-03 1.44E-02
% Limit per unit 4.98E-02 7.20E-02 Quarter 4 3.33E-02 8.15E-02
% Limit per unit 3.33E-01 4.08E-01 F
Total 2005 4.09E-02 1.02E-01
% Limit per unit 2.05E-01 2.55E-01 T-10
TABLE 7.9 DOSES FROM GASEOUS EFFLUENTS -2005 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 whole Thyroid Kidney Lung GI-LLI skin
_ _ _ _ _ _ _ _ _ _ _B o d y Qtr-1 O.OOE+00 4.84E-03 4.84E-03 4.84E-03 4.84E-03 4.84E-03 4.84E-03 5.58E-03
% Limit O.OOE+O0 3.23E-02 3.23E-02 3.23E-02 3.23E-02 3.23E-02 3.23E-02 3.72E-02 per Unit Qtr-2 O.OOE+00 5.09E-03 5.09E-03 5.09E-03 5.09E-03 5.09E-03 5.09E-03 1.41E-02
% Limit O.OOE+00 3.39E-02 3.39E-02 3.39E-02 3.39E-02 3.39E-02 3.39E-02 9.40E-02 per Unit Qtr-3 O.OOE+O0 4.53E-03 4.53E-03 4.53E-03 4.53E-03 4.53E-03 4.53E-03 3.89E-02
% Limit O.OOE+00 3.02E-02 3.02E-02 3.02E-02 3.02E-02 3.02E-02 3.02E-02 2.59E-01 per Unit Qtr-4 7.56E-OS 1.OOE-02 9.97E-03 4.53E-02 1.O1E-02 9.90E-03 9.93E-03 2.72E-01
% Limit 5.04E-04 6.67E-02 6.65E-02 3.02E-01 6.73E-02 6.60E-02 6.62E-02 1.81E+OO per Unit Total 7.56E-05 2.45E-02 2.44E-02 5.97E-02 2.45E-02 2.44E-02 2.44E-02 3.31E-Ol
% Limit 2.52E-04 8.17E-02 8.13E-02 1.99E-01 8.17E-02 8.13E-02 8.13E-02 1.1OE+00 per Unit T-11
TABLE 7.10 DOSES FROM GASEOUS EFFLUENTS -2005 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
_ _ _B o d y Qtr-1 O.OOE+00 5.30E-03 5.30E-03 5.30E-03 5.30E-03 5.30E-03 5.30E-03 5.58E-03
% Limit O.OOE+0O 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.53E-02 3.72E-02 per Unit Qtr-2 O.OOE+O0 5.58E-03 5.58E-03 5.58E-03 5.58E-03 5.58E-03 5.58E-03 1.41E-02
% Limit O.OOE+OO 3.72E-02 3.72E-02 3.72E-02 3.72E-02 3.72E-02 3.72E-02 9.40E-02 per Unit Qtr-3 O.OOE+0O 4.96E-03 4.96E-03 4.96E-03 4.96E-03 4.96E-03 4.96E-03 3.89E-02
% Limit O.OOE+O0 3.31E-02 3.31E-02 3.31E-02 3.31E-02 3.31E-02 3.31E-02 2.59E-01 per Unit Qtr-4 1.21E-04 1.10E-02 1.09E-02 6.04E-02 1.11E-02 1.08E-02 1.09E-02 2.72E-01
% Limit 8.07E-04 7.33E-02 7.27E-02 4.03E-01 7.40E-02 7.20E-02 7.27E-02 1.81E+00 per Unit Total 1.21E-04 2.69E-02 2.68E-02 7.62E-02 2.70E-02 2.67E-02 2.67E-02 3.31E-01 2005
% Limit 4.03E-04 8.97E-02 8.93E-02 2.54E-01 9.OOE-02 8.90E-01 8.90E-01 1.10E+O per Unit T-12
TABLE 7.11 DOSES FROM GASEOUS EFFLUENTS -2005 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 I_
Body Qtr-1 O.OOE+00 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 7.30E-03 5.58E-03
% Limit O.OOE+00 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 3.72E-02 per Unit Qtr-2 O.OOE+00 7.68E-02 7.68E-02 7.68E-02 7.68E-02 7.68E-02 7.68E-02 1.41E-02
% Limit O.OOE+OO 5.12E-02 5.12E-02 5.12E-02 5.12E-02 S.12E-02 5.12E-02 9.40E-02 per Unit Qtr-3 O.OOE+00 6.83E-03 6.83E-03 6.83E-03 6.83E-03 6.83E-03 6.83E-03 3.89E-02
% Limit O.00E+OO 4.55E-02 4.55E-02 4.55E-02 4.55E-02 4.55E-02 4.55E-02 2.59E-01 per Unit Qtr-4 2.85E-04 1.52E-02 1.51E-02 1.09E-01 1.54E-02 1.49E-02 1.50E-02 2.72E-01
% Limit 1.90E-03 1.01E-01 1.01E-01 7.27E-01 1.03E-01 9.93E-02 1.OOE-01 1.81E+00 per Unit I
Total 2.85E-04 3.70E-02 3.69E-02 1.31E-01 3.72E-02 3.67E-02 3.68E-02 3.31E-01 2005
% Limit 9.50E-04 1.23E-01 1.23E-01 4.37E-01 1.24E-01 1.22E-01 1.23E-01 1.10E+00 per Unit_
T-13
TABLE 7.12 DOSES FROM GASEOUS EFFLUENTS -2005 Site Iodines, Particulates and Tritium Dose Infant 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 Body Qtr-1 0.OOE+00 3.18E-03 3.18E-03 3.18E-03 3.18E-03 3.18E-03 3.18E-03 5.58E-03
% Limit O.OOE+00 2.12E-02 2.12E-02 2.12E-02 2.12E-02 2.12E-02 2.12E-02 3.72E-02 per Unit Qtr-2 O.OOE+00 3.35E-03 3.35E-03 3.35E-03 3.35E-03 3.35E-03 3.35E-03 1.41E-02
% Limit O.OOE+00 2.23E-02 2.23E-02 2.23E-02 2.23E-02 2.23E-02 2.23E-02 9.40E-02 per Unit Qtr-3 O.OOE+00 2.98E-03 2.98E-03 2.98E-03 2.98E-03 2.98E-03 2.98E-03 3.89E-02
% Limit O.OOE+00 1.99E-02 1.99E-02 1.99E-02 1.99E-02 1.99E-02 1.99E-02 2.59E-01 per unit Qtr-4 5.27E-04 7.13E-03 6.78E-03 2.10E-01 7.24E-03 6.51E-03 6.53E-03 2.72E-01
% Limit 3.51E-03 4.75E-02 4.52E-02 1.40E+00 4.83E-02 4.34E-02 4.35E-02 1.81E+00 per Unit Total 5.27E-04 1.66E-02 1.63E-02 2.19E-01 1.67E-02 1.60E-02 1.60E-02 3.31E-01 2005
% Limit 1.76E-03 5.53E-02 5.43E-02 7.30E-01 5.57E-02 5.33E-02 5.33E-02 1.1OE+00 per Unit T-14
TABLE 7.13 SOLID RADWASTE AND IRRADIATED FUEL SHIPMENTS -2005 A. Solid Waste Shipped Offsite for Burial or (Not Trradiated Fuel)
Disposal
- 1. Type of Waste Shipped shipped Buried Buried Percent m
Ci m3 Ci Error
- a. Spent resins/filters 2.90E+O1 1.99E+02 5.41E+00 2.47E+02
+/-25%
- b. Dry active waste 3.77E+02 1.97E+00 1.39E+01 1.68E+00
+25%
- c. Irradiated components N/A
- d. Other N/A (oil/miscellaneous liquids sent to processor for volume reduction)
TOTAL 4.06E+02 2.0lE+02 1.93E+01 2.49E+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 Fe-55 54.14 1.08E+02 Ni-63 20.71 4.13E+01 co-60 17.65 3.52E+01 Mn-54 3.71 7.39E+00 Co-58 1.57 3.13E+00 H-3 0.32 6.46E-01 C-14 0.02 4.65E-02 Tc-99 LLD I-129 LLD others*
1.88 3.74E+00 TOTAL 100.00 1.99E+02 Nuclides representing <1% of total shipped activity: Cr-51, Co-57, Fe-59,Ni-59,Zn-65, Sr-90, Nb-95, Zr-95, Sn-113,Sb-124, Sb-125, Cs-134, Cs-137,Ce-144,Hf-181,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
-2005
- 2. Estimate of Major Nuclide Nuclide
% Abund.
Activity Composition (by type of waste)
(Ci)
- b. Dry active waste Fe-55 48.13 9.46E-01 Ni-63 21.73 4.27E-01 Co-60 16.24 3.19E-01 Cs-137 4.11 8.08E-02 Co-58 2.02 3.96E-02 H-3 5.11 1.00E-01 C-14 LLD Tc-99 LLD I-129 LLD others*
2.66 5.24E-02 Total 100.00 1.97E+00
- Nuclides representing <1% of total shipped activity: Cr-Sl, Mn-54, Co-57,Fe-59,Sr-90,Nb-95,Zr-95,Sn-113,sb-125,Cs-134, Ce-144, Pu-238, Pu-239/240, Pu-241, Am-241, Cm-242, Cm-243/244.
- 3. solid Waste Disposition (Mode of Transportation:
Truck)
Waste Type waste container Number of Destination class Type Shipments
- a. Resin/filters A
Poly *HIC 2
Studsvik Erwin, TN.
B Poly *HIC 1
Studsvik Erwin, TN.
C Poly *HIC 2
studsvik Erwin, TN.
- b. Dry active waste A
General 7
GTS Duratek Design Oak Ridge,TN.
High Integrity Container Note: one class A shipment that also included filters was shipped to Duratek and included in that total.
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation N/A Destination N/A 0
T-16
ATTACHMENT 8.1 Joint Frequency Tables for 2005
R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:
01-JAN-05 00:00 TO 31-DEC-05 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
18 18 0
3 41 NNE 0
1 2
1 3
0 7
NE 4
12 8
2 0
0 26 ENE 2
12 3
1 0
0 18 E
3 5
5 0
0 0
13 ESE 0
18 29 0
0 0
47 SE 0
11 76 6
0 0
93 SSE 1
9 74 30 6
0 120 S
1 5
50 33 5
0 94 SSW 0
2 11 16 0
0 29 SW 0
3 5
1 0
0 9
WSW 2
3 1
0 0
0 6
W 0
1 0
0 0
0 1
WNW 0
0 1
1 0
0 2
NW 0
1 4
15 5
0 25 NNW 0
2 18 17 2
8 47 VARIABLE 3
2 0
0 0
0 5
TOTAL 16 89 305 141 21 11 583 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-05 00:00 TO 31-DEC-05 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
3 10 15 9
4 3
44 NNE 1
7 6
1 2
1 18 NE 10 20 5
0 0
0 35 ENE 8
10 8
1 0
0 27 E
5 7
2 0
0 0
14 ESE 0
16 9
0 0
0 25 SE 0
14 22 4
1 0
41 SSE 1
9 31 30 4
0 75 S
0 10 37 47 5
0 99 SSW 0
10 16 14 2
0 42 SW 1
15 7
5 0
0 28 WSW 0
8 4
5 0
0 17 W
0 0
0 0
0 0
0 WNW 1
1 0
3 0
0 5
NW 0
4 6
5 4
0 19 NNW 0
19 26 14 7
5 71 VARIABLE 11 2
1 0
0 0
14 TOTAL 41 162 195 138 29 9
574 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-05 00:00 TO 31-DEC-05 23:59 STABILITY CLASS:C ELEVATION: 10 m.
Wind Speed mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
6 12 7
16 6
2 49 NNE 3
8 8
3 3
0 25 NE 8
15 5
5 1
0 34 ENE 11 14 12 1
0 0
38 E
2 5
3 0
0 0
10 ESE 1
20 4
0 0
0 25 SE 2
17 26 8
0 0
53 SSE 2
14 29 37 2
0 84 S
1 9
37 38 8
0 93 SSW 3
6 18 12 1
0 40 SW 1
12 10 11 0
0 34 WSW 3
4 9
10 0
0 26 W
0 4
4 0
1 0
9 WNW 0
1 2
5 4
0 12 NW 0
2 8
5 6
3 24 NNW 1
13 20 22 10 5
71 VARIABLE 17 2
1 0
0 0
20 TOTAL 61 158 203 173 42 10 647 Periods of calm (hours):
0 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-05 00:00 TO 31-DEC-05 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
8 88 146 135 16 0
393 NNE 12 60 78 31 6
2 189 NE 10 33 70 15 0
0 128 ENE 11 39 52 13 0
0 115 E
25 87 23 1
0 0
136 ESE 38 117 32 0
0 0
187 SE 26 144 192 25 1
0 388 SSE 15 73 307 228 18 1
642 S
5 54 213 172 4
0 448 SSW 7
41 37 23 1
0 109 SW 9
23 20 8
4 0
64 WSW 6
21 6
12 2
0 47 W
2 7
8 7
5 0
29 WNW 4
16 16 19 5
3 63 NW 4
22 38 36 15 5
120 NNW 7
31 73 170 46 5
332 VARIABLE 66 16 7
3 0
0 92 TOTAL 255 872 1318 898 123 16 3482 Periods of calm (hours):
6 Hours of missing data:
22
R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:
01-JAN-05 00:00 TO 31-DEC-05 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
9 13 24 2
0 0
48 NNE 3
19 22 2
0 0
46 NE 3
4 1
1 0
0 9
ENE 1
6 2
0 0
0 9
E 8
23 5
0 0
0 36 ESE 26 85 7
0 0
0 118 SE 24 188 106 1
0 0
319 SSE 21 142 166 13 0
0 342 S
14 53 81 9
1 0
158 SSW 20 29 39 11 2
0 101 SW 19 28 21 9
5 0
82 WSW 10 12 8
1 0
0 31 W
10 4
14 0
0 0
28 WNW 13 21 17 1
0 0
52 NW 9
51 47 2
0 0
109 NNW 4
27 10 6
0 0
47 VARIABLE 63 6
1 0
0 0
70 TOTAL 257 711 571 58 8
0 1605 Periods of calm (hours):
6 Hours of missing data:
8
R. G. 1.21 JOINT FREQUENCY TABLE TXU ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:
01-JAN-05 00:00 TO 31-DEC-05 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
4 1
3 0
0 0
8 NNE 0
1 1
0 0
0 2
NE 2
0 0
0 0
0 2
ENE 0
1 1
0 0
0 2
E 0
0 1
0 0
0 1
ESE 3
3 2
1 0
0 9
SE 11 34 10 0
0 0
55 SSE 15 33 7
0 0
0 55 S
23 21 14 0
0 0
58 SSW 30 22 11 3
0 0
66 SW 23 29 12 0
0 0
64 WSW 15 15 5
0 0
0 35 W
17 6
5 0
0 0
28 WNW 14 8
5 0
0 0
27 NW 20 35 10 0
0 0
65 NNW 2
6 0
0 0
0 8
VARIABLE 27 1
0 0
0 0
28 TOTAL 206 216 87 4
0 0
513 Periods of calm (hours):
7 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-05 00:00 TO 31-DEC-05 23:59 STABILITY CLASS:G ELEVATION: 10 m.
Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 0
0 0
0 0
1 NNE 0
4 0
0 0
0 4
NE 0
0 0
0 0
0 0
ENE 1
01 0
0 0
0 1
E 0
0 0
0 0
0 0
ESE 3
0 0
0 0
0 3
SE 4
8 0
0 0
0 12 SSE 7
2 0
0 0
0 9
S 11 7
1 0
0 0
19 SSW 16 4
2 0
0 0
22 SW 7
11 0
0 0
0 18 WSW 10 27 6
0 0
0 43 W
17 8
0 0
0 0
25 WNW 15 10 0
0 0
0 25 NW 17 31 1
0 0
0 49 NNW 9
3 0
0 0
0 12 VARIABLE 16 1
0 0
0 0
17 TOTAL X
134 116 10 0
0 0
260 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-05 00:00 TO 31-DEC-05 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
31 126 213 180 26 8
584 NNE 19 100 117 38 14 3
291 NE 37 84 89 23 1
0 234 ENE 35 82 78 16 0
0 211 E
43 127 39 1
0 0
210 ESE 71 259 83 1
0 0
414 SE 68 416 432 44 2
0 962 SSE 63 282 614 338 30 1
1328 S
55 159 433 300 23 0
970 SSW 76 114 134 79 6
0 409 SW 60 121 75 34 9
0 299 WSW 46 91 39 28 2
0 206 W
47 30 31 7
6 0
121 WNW 47 57 41 29 9
3 186 NW 50 146 115 66 30 8
415 NNW 23 101 147 229 65 23 588 VARIABLE 203 31 10 3
0 0
247 TOTAL 974 2326 2690 1416 223 46 7675 Periods of calm (hours):
20 Hours of missing data:
1065