ML051300221
| ML051300221 | |
| Person / Time | |
|---|---|
| Site: | Callaway  (NPF-030) |
| Issue date: | 12/31/2004 |
| From: | AmerenUE, Union Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-05140 | |
| Download: ML051300221 (50) | |
Text
2004 Callaway Plant Radioactive Effluent Release Report
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I I I WAmeren UE Docket no. 50-483
Table of Contents 1.0 Introduction....................................
1 2.0 Supplemental Information...................................
2 2.1 Regulatory Limits
.2 2.2 Average Energy
.3 2.3 Measurements and Approximations of TOTAL RADIOACTIVITY
.3 2.4 Batch Releases
.4 2.5 Abnormal Releases
.4 3.0 Summary of Gaseous Radioactive Effluents................................... 5 4.0 Summary of Liquid Radioactive Effluents................................... 6 5.0 Solid Wastes....
7.......................
6.0 Related Information....................................
7 6.1 Unplanned Releases
.7 6.2 Changes to the Offsite Dose Calculation Manual.10 6.3 Major Changes to Radwaste Treatment Systems.11 6.4 Land Use Census Changes.11 6.5 Inoperability of Effluent Monitoring Instrumentation.11 6.6 Instances of Liquid Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits............................................... 12 7.0 Meteorological Data 13 8.0 Assessment of Doses..........................................
16 8.1 Dose at the Site Boundary from Gaseous Effluents...........................................
16 8.2 Dose to the Member of the Public...............................................
16 8.3 Total Dose Due to the Uranium Fuel Cycle............................................... 17 8.4 Dose Due to Liquid Effluents............................................... 17 List of Table 1A Annual Summation of Gaseous Releases 1 B Annual Airborne Continuous and Batch Releases 2A Annual Summation of Liquid Releases 2B Annual Liquid Continuous and Batch Releases 3
Solid Waste and Irradiated Fuel Shipments 4
Cumulative Joint Frequency Distributions 5
Dose at the SITE BOUNDARY and Nearest Resident 6
Dose to the Member of the Public from Activities within the SITE BOUNDARY 7
Total Dose Due to the Uranium Fuel Cycle 8
Dose Due to Liquid Effluents i
1.0 Introduction 1.0 Introduction This report describes the Union Electric Co.
Cal/away Plant radioactive effluent releases for 2004. It is submitted in accordance with Section 5.6.3 of the Cal/away Plant Technical Specifications.
A summary of radioactivity released in liquid and gaseous effluents and solid waste shipped from the Callaway Plant during the period from January 1, 2004 to December 31, 2004 is presented.
All liquid and gaseous effluents discharged during this reporting period complied with federal regulations and the limits in the Offsite Dose Calculation Manual (ODCM). Any exceptions are noted in this report.
1
2.0 Supplemental Information 2.1 Regulatory Limits The Radiological Effluent Control (REC) limits applicable to the release of radioactive material in liquid and gaseous effluents are provided below.
Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem/yrto the total body and less than or equal to 3000 mrem/yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
Radiolodine, Tritium, And Particulates The dose rate due to lodine-1 31 and 133, tritium and all radionuclides in particulate form with half-lives greater than eight (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/yrto any organ.
The dose to a Member of the Public from lodine-1 31 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
Liquid Effluent The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in Appendix B, Table 2, Column 2 of 1 OCFR20 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 microcuries/ml total activity.
The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
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2.0 Supplemental Information Continued 2.0 Supplemental Information Continued 2.2 Average Energy This requirement is not applicable to the Callaway Plant radiological effluent monitoring program since the release rate limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture.
2.3 Measurements and Approximations of Total Radioactivity Radionuclide concentrations in liquid and gaseous effluents were obtained by effluent sampling and radiological analysis in accordance with the requirements of Final SafetyAnalysis Report-SP Tables 16.11-1 and 16.11-4.
Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, Fe-55, and transuranic nuclides by an independent laboratory. In the second quarter of 2004, analysis of Ni-63 was also included based on previous 10 CFR 61 analyses. Tritium and gross alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively.
The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.
Pictured is a gamma ray detector inside a graded shield.
Positioned on top of the detector (blue box) is a sample holder used to precisely position samples of various geometries.
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2.0 Supplemental Information Continued 2.0 Supplemental Information Continued 2.4 Batch Releases Summary information relating to batch releases of gaseous and liquid effluents to the environment from the Callaway Plant during this year is presented below.
LIQUID UNITS Number of batch releases:
Total time period for batch releases:
Maximum time period for batch releases:
Average time period for batch releases:
Minimum time period for batch releases:
Average Missouri River flow during periods of effluent release to the river1 :
Minutes Minutes Minutes Minutes ft3/sec JAN-JUN 77 38,417 2,182 499 255 77,919 JUL-DEC 107 46,184 505 432 337 65,561 GASEOUS UNITS Number of batch releases:
Total time period for batch releases:
Maximum time period for batch releases:
Average time period for batch releases:
Minimum time period for batch releases:
Minutes Minutes Minutes Minutes JAN -JUN 32 11,078 4,023 346 6
JUL - DEC 27 2,010 365 74 29 I E-mail, S. Ternes, United States Department of the Interior - Geological Survey -Water Resources Division dated January 14,2005.
2.5 Abnormal Releases LIQUID Numberof releases: 1 Total Activity released: 1.29E-03 Curies GASEOUS Number of releases: 7 Total Activity released: 17.1 Curies 4
3.0 Summary of Gaseous Radioactive Effluents The quantity of radioactive material released in gaseous effluents during the-year is summarized in Tables IA and lB. During 2004, all gaseous effluents were considered as ground level releases.
Gaseous effluents from the plant are continuously monitored.
Instrumentation provides on-line and grab sampling for iodine, particulates and noble gas.
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4.0 Summary of Liquid Radioactive Effluents The quantity of radioactive material released in liquid effluents during the year is summarized in Tables 2Aand 2B. During 2004, there was no continuous release of liquid effluent from the plant.
Liquid effluents from the plant are continuously monitored.
Shown is a liquid monitor shielded by lead to increase its sensi-tivity for sampling discharged water.
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5.0 S olid W astes 5.0 Solid Wastes The quantities of radioactive material released in shipments of solid waste for burial and irradiated fuel transported from the site during the year are summarized in Table 3. The total quantity and radioactivity reported in Table 3 for each waste type was forwaste buried and includes wastes buried by waste reprocesses after volume reduction. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration 6.0 Related I of each nuclide listed in Table 3 was determined
- as the product of the fractional abundance and the
- total curies shipped. Those nuclides which comprise at least 1% of the total activity for a
- particular waste type are presented in Table 3.
nformation 6.1 Unplanned Releases Unplanned releases are:
- 1) Inadvertent or accidental releases of radioactive material.
- 2) Releases of radioactive material via normal pathways without a release permit, proper authorization, or proper sampling and analysis.
- 3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.
Auxiliary Boiler Contamination OnApril 10, 1998, during a refueling outage, radioactivity was detected in the Auxiliary Boiler feed watersystem. The boilerwasflushed and cleaned several times in an attempt to decontaminate the unit. Small amounts of contamination remained in the sludge. During subsequent operation of the boiler small amounts of contamination leached from the sludge and were detected in the boiler water.
An investigation was performed to locate the source of the contamination. No miss-positioned valves or leaks were identified. The results of sampling different system components were inconclusive, but may indicate a small leak in the SLWE heat exchanger. During refueling operations, the concentration of radioactive nuclides in the SLWE system can be a factor of 1000 times higher than normal operations. The size of the leak may be small enough to only be recognized when these high concentrations are present. Increased monitoring was initiated in an attempt to identify the source of the contamination.
No additional contamination was identified.
A I OCFR50.59 evaluation concluded that the resulting dose to a Member of the Public from the release of radioactive material to the environment would be a small fraction of the regulatory dose limits. Therefore, continued operation of theAuxiliary Boiler would not pose any significant safety or environmental concern.
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6.0 Related Information The Auxiliary Boiler was operated intermittently during 2004. The maximum total body dose to a Member of the Public from these releases was 4.85E-05 mrem during 2004. This is negligible compared to the quarterly and annual effluent control limits. The total activity released from theAuxiliary Boiler in 2004 was 1.24E-01 Curies.
Containment Equipment Hatch Air samples taken outside of the Containment Equipment hatch during RF012 indicated reactor produced isotopes (CAR 200207059).
Releases of radioactivity from the Containment Equipment hatch in 2004 (RFO13) were quantified and are included in this report.
The total amount of activity released from the Containment Equipment hatch was approximately 13.9 Curies, primarily consisting of Noble gases.
The maximum total body dose to a Member of the Public from these releases was 2.65E-04 mrem during 2004. This is negligible compared to the quarterly and annual effluent control limits.
The activity released from the Containment Equipment hatch during 2004 is included in Tables 1A, 1B, 5,6, and 7.
Auxiliary Boiler Operated w/o Release Permit On 1/27/04, the Auxiliary Boiler was started prior to release permit generation (CAR 200400644). Control room procedures require release permit generation priorto operation.
Approximately 30 minutes after operation began, the Count Room technicians were notified and a release permit was generated. The total activity released during this release was 1.82E-03 Curies and the Total Body dose to a Member of the Public was 3.28E-07 mrem. As expected, the activity and dose from this release was well below regulatory limits.
To prevent reoccurence, Radiation Protection procedures were revised to provide a continuously open Auxiliary Boiler release permit to allow the Callaway Operations staff increased operating flexibility.
Antimony-122 In Liquid Effluents Antimony-1 22 (Sb-1 22) was discovered in liquid effluent release permits during Health Physicist review (CAR 200409000). Sb-1 22 was initially discovered in reactor coolant samples and added to the effluent release library based on the comparison. Afterthe radionuclide was added to the release library, an interference with Cs-1 34 at the 564 keV energy was noticed. All of the liquid release permits from 2004 were evaluated for Sb-122. The evaluation revealed 10 batch liquid release permits where Sb-1 22 was present. The affected release permits were revised to account for Sb-122.
Sb-1 22 was also added to Table 2.1, Ingestion Dose Commitment Factor (AIT) forAdultAge Group, of APA-ZZ-01 003, CallawayODCM. The total amount of Sb-1 22 activity released in liquid effluents was 1.29E-03 Curies. The dose from Sb-122 was well below 1 % of the total dose from liquid effluents in 2004.
'A' Mixed Bed Demineralizer Flush On 4/6/04, the control room commenced a flush of 'A' Mixed Bed Demineralizer in accordance with plant procedures. Shortly after the flush began, the Auxiliary Building ventilation exhaust particulate monitorr GL-RE-60 alarmed in the control room (CAR 200402553). Trends on GL-RE-60 indicated a step increase in activity. As a result of the alarm, the control room decided to secure the flush of 'A' Mixed Bed Demineralizer.
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_6.0 Related Information After the flush was secured, control room operators noticed decreasing level in the Volume Control Tank (VCT). Control room personnel commenced plant procedures for excessive reactor coolant system leakage and eventually determined that the leakage was from BG-V-0237 to the DRW sumps.
As a result of the leaking valve, trends on the unit vent noble gas monitor GT-RE-21 B indicated a "spike" of activity was released from the unit vent. The total activity released during this time was approximately 1.25 Curies. The total dose to the Member of the Public was approximately 7.89E-05 mrem.
Pressurizer Degas Relief Lift Intermittent Releases from the Cooling Tower (NRC Information Notice 2004-05)
During investigation of NRC Information Notice 2004-05, sample results revealed intermittent levels of tritium in the cooling tower basin (CAR 200403826). An investigation revealed that detectable triturm in the cooling tower was a result of recirculation of plant liquid effluents (CAR 200403826).
An evaluation of the dose impact was per-formed, assuming releases from the cooling tower were elevated. The total activity released from the cooling tower was determined to be 0.25 Curies of tritum. The total dose to the Member of the Public was calculated to be 3.50E-05 mrem.
On 2/5/04, during a pressurizer purge to the Volume Control Tank, relief valve SJ-V-081 3 lifted sending liquid and gas to the CRW sump. As a result, the Unit Vent noble gas readings increased (CAR 200400941).
As for corrective actions, the valve was replaced and the setpoint raised to 100 psig as per RFR 18134 Rev. B. The total activity released during the evolution was approximately 1.47 Curies. The total dose to the member of the publicfrom this release was 6.17E-05 mrem.
Boron Thermal Regeneration System Vent Valve Failure During fill and venting operations of the BTRS system on 1/24/04, vent valve BG-V-0395 failed in the open position (CAR 200400575). As a result, an increase was seen on the Unit Vent noble gas monitor.
The release of noble gas activity was quantified and determined to be approximately 108 milliCuries. The total dose to the member of the public from this release was 8.98E-05 mrem.
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6.0 Related Information
- 6.0 Related Information 6.2 Changes to the Offsite Dose Calculation Manual Changes were made to the Callaway Offsite Dose Calculation Manual (plant procedureAPA-ZZ-01 003) during 2004. Revision 15 of APA-ZZ-01003 was approved in December of 2004 and included the following changes.
- 1. References to FSAR-SP Chapter 16.11 Offsite Dose Calculation Manual -
Radioactive Effluent Controls were standardized.
Several changes were also made to FSAR-SP Chapter 16.11, Offsite Dose Calculation Manual - Radioactive Effluent Controls (ODCM - RECS) located in FSAR - SP Chapter 16.11.
FSAR Change Notice 04-032 revised FSAR-SP Chapter 16.11.5.1 to state that sample locations for the Callaway REMP are calculated from the midpoint between the two reactors for consistency with FSAR-SA Chapter 2.1.1.1.
FSAR-SP Change Notice 04-057 corrected a typo introduced in FSAR-SP Section 16.11.2.2.2 (CAR 200407044).
FSAR-SP Change Notice 02-034 changed the description of the Gaseous Radwaste Hydrogen/Oxygen Analyzer System to reflect the replacement system to be installed per Callaway Plant Modification 98-1032.
- 2.
Ni-63 and Sb-1 22 were added to Table 2.1 (Site specific Ingestion Dose Commitment Factors (A1T) for theAdultAge Group) based on 10 CFR 61 analysis results. Ni-63 was included in the second quarter compositeresults. Sb-122was evaluated in all of the permits for 2004 and added as necessary (CAR 200409000).
- 3.
In addition, the Ingestion Dose Commitment Factors (AT) listed in Table 2.1 were all consolidated in HPCI 04-06, Revision 1, due to minor differences in rounding found in previous calculations..
- 4.
References to Callaway processing of the Radiological Environmental Monitoring Program direct radiation monitors (TLDs) were removed. Processing of REMP TLDs will be performed by a contract lab beginning in 2005.
- 5. Added a 0.95 conservatism factor in the setpoint calculation for the liquid effluent release monitor. This is based on guidance from section 4.4.1 of NUREG 0133, U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants" which states the alarm and trip setpoints for each instrument listed in Table 3.3-11 should be provided and correspond to a value(s) which represents a safe margin of assurance that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded.
- 6. Additional administrative corrections.
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-1 6.0 Related Inform ation 6.0 Related Information 6.3 Major Changes to Radwaste Systems During 2004, the following plant modifications to Radwaste Systems were implemented:
Installation of theAdvanced Liquid Processing System (ALPS) as per MP 01-1001 was completed and fully operational in early January following field testing completed in accordance with ETP-HB-03002 (ALPS Startup Testing).
ALPS replaces the temporary NUKEM processing skid and utlizes charcoal filters and demineralizers to remove ionic impurities and suspended solids.
Modification MP 01-1001 also included installation of vacuum breakers, vent valves, and overflow check valves on the SLW Monitor Tanks to allow a direct vent path to the Radwaste HVAC Exhaust as opposed to the tank rooms. Vacuum breakers and vent valves preclude developing a significant vacuum and positive pressure, respectively, during normal operation.
Modification MP 01-1 001 also included various Radwaste piping modifications to allow ALPS to process from the Recycle Holdup Tanks, Laundry and Hot Shower Tanks, Waste Holdup Tanks, and the Floor Drain Tanks.
The following minor modification was made to the gaseous radwaste system during 2004.
Modification MP 98-1032 installed new analyzers in the "A" GasAnalyzer rackwhich is used to monitor performance of the "A" Waste Gas Recombiner. It also installed piping to allow the analyzers to be purged with N2 when not in use.
6.4 Land Use Census Changes No changes were identified that required a change to the location of the nearest resident yielding the highest calculated dose commitment.
6.5 Inoperability of Effluent Monitoring Instrumentation In 2004. all effluent instrumentation was OPERABLE within the limits specified in the Offsite Dose Calculation Manual -
Radioactive Effluent Controls section of FSAR-SP 16.11.1.3 and16.11.2.4 exceptfor the following instances.
Inoperability of Unit Vent Mid/High Range Radiation Monitor During quarterly Surveillance testing of the Unit Vent Radiation Monitor on October 22, 2004, the Mid and High Range Channel flow control circuit failed to achieve the required sample flow necessary to collect isokinetic samples (CAR 200408046). Investigation determined thatthe failure was due to improper reassembly of a filter canister located between the Mid/High Vacuum Pump discharge and the Mid and High Range Detector Chambers. The design of this filter relies upon a tapered flange between both the canister body and canister lid which compresses a sealing o-ring when coupled together using a constricting steel band. The faulty reassembly occurred on October 5,2004 when the filter was replaced and a quarterly functional test was not performed afterwards. After discovering the filter canister leakage, the canister was reassembled and a tight seal was verified with the correct flow characteristics being achieved for the Mid/High Range Unit Vent Radiation Monitor was declared Operable and returned to service.
During performance of the quarterly Surveillance on October 22, 2004, the preplanned alternate method of monitoring was instituted in accordance with plant procedures. This constituted monitoring Unit Vent releases in accordance with Emergency Plan Implementing Procedures in the event an emergency were to occur and would rely upon data supplied by field monitoring teams. This alternate method remained in effect until the problem was corrected on October 28,2004.
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6.0 Related Information 6.0 Related Information Primary Meteorological Tower 10m Termperature Inoperability On April 8,2004, with Callaway Plant in Mode 1, the Primary MetTower 10 MeterAspiratorwas determined to be inoperable. The Aspirator forces airflow past the temperature sensor and without proper airflow, temperature indication is considered inaccurate and inoperable. As a result the Primary MetTower 10 MeterTemperature Sensor RDTE5001 CA was declared Inoperable which made the FSAR required 1 Om - 60m Air Temperature Delta T instrumentation inoperable.
Further investigation indicated that aspirator operation became suspect on 3/27/04, and the date of failure was considered 3/27/04. Special Report ULNRC-04982 was initiated and sent to the NRC on April 13, 2004.
6.6 Instances of Liquid Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits All liquid tanks and waste gas decay tanks were within limits specified in Radioactive Effluent Controls 16.11.1 and 16.11.2 during the reporting period.
Primary Meteorological Tower 60m Wind Direction Inoperability On April 23,2004, Callaway Plant was informed by the contract meteorologist that there was an offset of approximately 21 degrees in the Primary Met Tower 60m wind direction instrumentation. As a result, the Primary Met Tower 60m wind direction transmitter, RDZT5000B, was delcared inoperable.
Further investigation indicated that transmitter operation became suspect on March 12,2004.
Therefore, March 12,2004, was established as the date of failure. The plant was shutdown for refueling on April 10,2004. At the time of discovery there was no fuel in the reactor (No Mode conditions). Special Report ULNRC-04992 was initiated and sent to the NRC on May 3,2004.
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7.0 Meteorological Data 7.0 Meteorological Data The on-site meteorological data for this reporting period are summarized in Table 4. All meteorological data for each day of the year were reviewed, analyzed, and validated by a boundary layer meteorologist. Data validations are performed on the 15 minute averages which are then used to create the hourly averages.
The data are presented as Cumulative Joint Frequency Distributions of wind speed and wind direction by atmospheric stability class for the 10 and 60 meter tower elevations. Valid data recovery for 2004 was greater than 90% for all required parameters except for 60-1 Om delta-T (see below). However, an additional semi-redundant 90-1 Om delta-T measurement is made by the Callaway system. The availability of the backup 90-1Om data during some of the 60-1Om data failures, provided validated delta-T data 91.6% of the time during 2004.
In addition, the decision was made in 2004 to upgrade the met system to a new datalogger based system with updated redundant instrumentation. This upgrade is scheduled for implementation this summer, and should significantly improve meteorological data quality and operability.
In 2004, Callaway experienced several unusual problems with it's met system. This resulted in an abnormally larger amount of invalidated data, especially in T and delta-T data. The problems included moisture induced interferences on temperature measurements, interference from large birds perching on wind instruments, instrument damage from birds, and failures of fan motors in the power aspirators. These are highlighted in sections below.
In April, it was discovered that the 60m WD had been misaligned by about 21 degrees during calibration re-mounting on March 12h. Analysis by the boundary layer meteorologist during well mixed conditions indicated that the offset became constant approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> later.
Pictured is the Secondary Meteological Tower. This station obtains measurements at a height of 10 meters, and provides backup data for the Primary Meteological Tower readings at 10, 60 and 90 meters.
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7.0 Meteorological Data (continued)
Consequently, data were corrected and less than one day of data were lost. As part of the corrective actions (CAR 200403284), a daily (business days) review of met data by the meteorologist was implemented. This action was designed to prevent meteorological tower problems from being undetected for long periods of time. This shift from periodic data review, to a near real-time daily statistical and graphical review of the data (commencing on May 1 st) has not only helped prevent undetected data problems, but it has provided a much more detailed and rigorous review of the data.
Some of the other significant problems encountered, and corrective actions taken, included:
PRECIPITATION INTERFERENCE on T and dT:
Moisture related interference in temperature and delta-temperature measurements were observed during periods of either precipitation or near saturated conditions (e.g., fog). A rather complete summary of the observed problems and actions taken is contained in CAR 200405482.
The interference during moist conditions was manifested by falsely indicated increases in temperature data from a few tenths to several degrees C. This resulted in significant periods where data from one or both delta-T channels were unreliable or invalid. This data was subsequently removed from the database.
CorrectiveActions: Beginning in May, there was extensive troubleshooting of the electrical and measurement system.
Troubleshooting included the tower and rack mounted components, recleaning and/or replacement of all electrical contacts, rewiring of the aspirator ground loops, replacement of aspirator cables at all three levels, replacement of aspirators, and finally replacement of the primary tower cables.
Unfortunately no artificial means to test troubleshooting efforts was available and therefore Callaway personnel were required to wait for significant weather events. As a result, mitigation of the precipitation interference was prolonged. Following installation of the primary tower cables in late September, the incidence rate of suspect data was substantially reduced.
ASPIRATOR FAILURE Effects on T and dT:
In 2004, Callaway also experienced fan failure on the power aspirators. Additional temperature and delta-T data were lost during three different periods of failed or clogged (snow) fan motors in the power aspirators. Total aspirator related dT data losses were in the 3%-4% range.
BIRD INTERFERENCE:
During 2004, Callaway continued to experience problems with large birds landing on or nextto the wind speed instruments, especially at the 60m and 90m levels. The birds were determined to be protected Great Horned owls.
CorrectiveActions: First, during periods of interference, data for each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> were carefully examined for evidence of bird interference and data was emoved from the database when interference was observed.
Second, Callaway obtained permits to trap and relocate the owls if possible. Subsequently, one large owl was trapped and removed on August 201h, however, the bird interference continued. In late September bird perches were installed at a safe distance above each anemometer level. There have been no instances of bird interference on wind measurements since that time.
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7.0 Meteorological Data (continued)
BIRD DAMAGE:
In addition to the measurement interference, the owls damaged wind speed sensors by breaking off cups on the cup assemblies and wind direction sensors by bending the vane and/or distorting the shaft. In all, approximately 8 different instrument failures appeared to be directly related to damage caused by the owls.
Corrective Actions: As mentioned above, installation of three bird perches on the tower also eliminated this problem.
PLANT COMPUTER & COMMUNICATIONS:
Nine plant computer "failovers" were identified during the year which resulted in data losses. The average data loss was less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> peroccurrenceforeach parameter. In addition, a loss of communications with the secondary tower occurred resulting in a loss of nearly six hours of secondary tower data.
ADDITIONAL METEOROLOGICAL ISSUES:
90m wind speed reduction -A documented interference is reducing the measured 90m wind speed (as determined by difference analysis with 60m shear layers) whenever the wind direction is near 45 degrees (effect maximized at 45 deg and becomes undetectable at about 22 deg and 57 deg).
Each block of 15 minute wind speed averages was examined. The 90m WS data were discarded when the error appeared to reach 0.5 m/s. It is suspected that the interference is being caused by something mounted or unique at the 90m level. The problem is well documented and will be rectified with the system upgrade.
- Precipitation Spikes - Several times in 2004, the rain gauge recorded unusually large rainfall amounts in a short periods of time (15 minutes). Inspection of the data indicated large amounts of rainfall being recorded as a result of a false reset of the totalizer count or momentary loss of communications with the plant.
Precipitation amounts were examined with daily weather maps and compared to auxiliary hourly precipitation data from the Fulton National Weather Service (NWS) coop site, the Prairie Fork automated weather station, and from the Columbia and Jefferson City NWS stations to remove the incorrect data.
Additional software checks were written and installed to detect and prevent these spikes from even entering the raw database.
- Snowfall -Amalfunctioning raingauge heater prevented normal measurement of snowfall as it fell, but recorded it as it melted. The periods of missing or false data were carefully determined and the precipitation records flagged as invalid. Likewise data were removed when the snow was melting but being recorded as falling precipitation.
This will be corrected by the meteorological system upgrade.
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8.0 Assessment of Doses 8.0 Assessment of Doses Assessment of Doses Assessment of doses to the maximum exposed individual from gaseous and liquid effluents released was performed in accordance with the ODCM as described in the following sections. For all effluents released from the Callaway Plant during this year, the annual dose to the maximum exposed individual was less than 2% of the Radiological Effluent Control Limits presented in Section 2.1 of this report.
8.1 Dose at the Site Boundary from Gaseous Effluents The dose at the Site Boundary was due to plume exposure from noble gases, ground plane exposure, and inhalation. It was conservatively assumed that a hypothetical maximum exposed individual was present at the Site Boundary location with the most limiting atmospheric dispersion (based on actual meteorological conditions forthe year). Dose was conservatively calculated using a child as the critical age group.
The dose from gaseous effluents at the Site Boundary for 2004 is presented in Table 5.
8.2 Dose to the Member of the Public The Member of the Public is considered to be a real individual, not occupationally associated with the plant, who uses portions of the plant site for recreational or other purposes not associated with plant operation. This individual's utilization of areas both inside and outside the Site Boundary was characterized for this calculation and is described in the ODCM.
To evaluate total dose from the Uranium Fuel Cycle to any Member of the Public, the critical Member of the Public within the Site Boundary, and the Nearest Resident were each evaluated.
Dose At The Nearest Residence From Gaseous Effluent The dose to the Nearest Resident was due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion. Dose was calculated at the nearest actual residence with the most limiting atmospheric dispersion (based on actual meteorological conditions forthe year). It was conservatively assumed that each ingestion pathway (meat, milk, and vegetation) existed at this location. Dose was conservatively calculated assuming the child as the critical age group.
Dose from activities within the Site Boundary was negligible and not included in this calculation.
The doses to the Nearest Resident for 2004 are presented in Table 5.
Dose To The Member Of The Public From Activities Within The Site Boundary Based on the land use within the Site Boundary, the Member of the Public with the highest dose was a farmer. Dose from farming activities within the Site Boundary was due to direct radiation exposure, plume exposure from noble gases, ground plane exposure, and inhalation. The current tenant farmer estimates spending 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working within the Site Boundary area. Dose was calculated using the adult as the critical age group.
Dose to the Member of the Public from activities within the Site Boundary is presented in Table 6.
16
8.0 Assessment of Doses Continued 8.3 Total Dose Due to the Uranium Fuel Cycle Since there are no other Uranium Fuel Cycle facilities within 8 kilometers of the Callaway Plant, the total dose to the most likely exposed Member of the Public resulted from direct radiation exposure and radioactive effluents from the Callaway Plant itself.
The total dose to the Member of the Public (Table 7) was the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence. It was conservatively assumed that each food ingestion pathway exists at his residence and that the child is the critical age group.
The total dose from the Uranium Fuel Cycle is presented in Table 7.
8.4 Dose Due to Liquid Effluents Dose due to liquid effluents includes contributions from the maximum exposed individual's consumption of fish and recreational activities. An adult was considered the maximum exposed individual in this assessment.
It is conservatively assumed thatthe hypothetical maximum exposed individual obtained his entire annual fish intake from near the plant discharge.
17
Table 1A Semiannual Summation of Gaseous Releases All Airborne Effluents TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS I AND 2,2004 I
I I FIRST I SECOND I EST TOTAL TYPE OF EFFLUENT I UNITS I QUARTER I QUARTER I ERROR % (a)
A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 3.01E+02 4.72E+02 20
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.83E+01 6.01E+01
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A B. RADIOIODINES I. TOTAL IODINE-131 CURIES 6.40E-05 2.30E-03 23
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 8.14E-06 2.93E-04
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES >8 DAYS)
CURIES 1.29E-04 3.10E1-05 30
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.64E-05 3.94E-06
- 3. PERCENT OF TECH SPEC LIMIT
%N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 14.71E-07 4.1 1E-07 D. TRITIUM I1. TOTAL RELEASE CURIES l6.09E+00 l1.31E+01 l
14 1
- 12. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 7.75E-01 I 1.67E+00
- 3. PERCENT OF TECH SPEC LIMIT
____I___IfN/A I N/A (a) Safety Analysis Calculation 87.063-00, January 6, 1988 Page 1 of I 18
Table 1A Semiannual Summation of Gaseous Releases All Airborne Effluents TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 3 AND 4,2004 O
THIRD FOURTH ESTTOTAL TYPE OF EFFLUENT lUNITS I QUARTER l QUARTER I ERROR % (a)l A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 3.09E+00 1.65E+00 20 l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.89E-01 2.08E-01
- 1. TOTAL IODINE-131 CURIES 0.003E+00 0.00E+00 231]
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 0.00E+00 O.OOE+00
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES > 8 DAYS)
CURIES 4.72E-05 9.87E-06 30
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 5.94E-06 1.24E-06
- 3. PERCENT OF TECH SPEC LIMIT g
oN/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 14.21E-07 2.24E-07 D. TRITIUM I. TOTAL RELEASE l CURIES 1.06E+01 l 8.12E+00 14
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.34E+00 1.02E+00
- 3. PERCENT OF TECH SPEC LIMIT N/A I N/A (a) Safety Analysis Calculation 87-063-00. January 6. 1988 Page 1 of I 19
Table IB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Ficcinn taqcnc Indin-c and Partit-il:tn-TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODWNES. AND PARTICULATES QUARTERS I AND 2,2004 CONTINUOUS RELEASES BATCH RELEASES I FIRST SECOND I FRST SECOND NUCLIDE UNITS QUARTER IQUARTER I QUARTER I QUARTER
- 1. FISSION GASES AR-41 CURIES O.OOE+00 0.001E+00 6.62E-02 1.177E-01 XE-133 CURIES 2.77Ei+02 4.42E+02 2.09E-01 1.53E+01 XE-135 CURIES 1.08E+01 5.25E+00 1.47E-03 4.52E-02 KR-85M CURIES 2.89E+00 4.71E-01 0.00E+00 2.76E-03 XE-135M CURIES 0.00E+00 3.76E-01 2.63E-06 0.00E+00 KR-87 CURIES 9.03E-01 1.04E-01 0.00E+00 0.00E+00 XE-131M CURIES 1.60E+00 1.711E+00 1.166E-03 1.1S5E-01 XE-133M CURIES 254E+00 5.25E+00 9.20E-04 4.54E-02 KR-88 CURIES 3.42E+00 4.54E-01 O.OOE+00 1.43E-02 ICR-85 CURIES 0.OOE+00 0.00E+00 2.10E+00 3.26E-01 XE-138 CURIES 0.00E+00 2.06E-01 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 2.99E+02 4.56E+02 2.38E+00 1.59E+01
- 2. IODINES 1-133 CURIES 0.00E+00 1.86E-05 2.17E-05 9.166E-06 I-131 CURIES 5.30E-06 1.15E-03 5.87E-05 1.15E-03 1-132 CURIES 0.00E+00 1.04E-05 5.712E-06 1.21E-04 1-135 CURIES 0.00E+00 0.00E+00 4.66E-06 0.00E+00 TOTAL FOR PERIOD CURIES 5.30E-06 1.188E-03 9.08E-05 1.28E-03
- 3. PARTICULATES CS-137 CURIES 1.05E-06 2.991-07 1.62E-05 3.86E-06 SB-125 CURIES 2.61E-06 5.54E-07 0.00E+00 0.00E+00 BA-140 CURIES 0.00E+00 0.00E+00 5.13E-07 3.57E-07 CS-134 CURIES 0.00E+00 0.00E+00 2.44E-05 1.26E-05 CS-136 CURIES 0.00E+00 0.00E+00 2.61E-06 5.64E-07 NA-24 CURIES 0.00E+00 0.00E+00 4.30E-08 0.00E+00 CO-58 CURIES 0.00E+00 5.58E-06 2.55E-07 3.79E-06 CO-60 CURIES 4.672-07 0.OOE+00 8.072-05 1.45E-06 NB-95 CURIES 0.00E+00 0.00E+00 0.00E+00 4.25E-07 CR-5 1 CURIES 0.00E+00 0.00E+00 0.00E+00 1.51 E-06 ALPHA CURIES 4.71E-07
- 4. 11E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 4.602-06 6.84E-06 1.25E-04 2.46E-05 Page I of 2 20
Table IB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE lB (continued)
SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES. IODINES. AND PARTICULATES QUARTERS I AND 2, 2004 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND INUCLIDE I UNITS QUARTER I QUARTER QUARTER l QUARTER
- 6.
0 1.20E+0l 8.60E-0_
1.04E-00 I
Page 2 of 2 21
Table IB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES. AND PARTICULATES QUARTERS 3 AND 4,2004 CONTINUOUS RELEASES I
BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER
- 1. FISSION GASES AR-41 CURIES 0.00E+00 0.00E+00 4.15E-02 6.43E-02 XE-133 CURIES 3.02E+00 1.46E-01 8.79E-04 1.86E-03 XE-135 CURIES 2.87E-02 3.96E-02 1.23E-05 2.29E-05 KR-85M CURIES 0.00E+00 1.09E-02 0.00E+00 0.OOE+00 XE-135M CURIES 0.00E+00 0.003E+00 O.00E+00 0.00E+00 KR-87 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 8.20E-04 0.00E+00 XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-88 CURIES 0.00E+00 0.00E+00 0.00E+00 0.001E+00 KR-85 CURIES 0.00E+00 0.00E+00 0.00E+00 1.34E+00 XE-138 CURIES 1.42E-03 5.511E-02 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 3.0513+00 2.52E-01 4.32E-02 1.40E1+00
- 2. IODINES I-133 CURIES 9.621E-07 0.00E3+00 0.00E+00 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 0.0013+00 0.00E.+00 I-132 CURIES 0.0013+00 0.001E+00 0.001E+00 0.00E+00 I-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 9.62E-07 0.0013+00 0.00E+00 0.0013+00
- 3. PARTICULATES CS-137 CURIES 7.12E-06 1.10E-06 0.0013E+00 0.OOE+00 SB-125 CURIES 3.21E-05 7.62E-06 0.0013+00 0.00E+00 BA-140 CURIES 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 CS-134 CURIES 5.24E-07 0.00E+00 0.0013+00 0.00E+00 CS-136 CURIES 0.00E++00 0.00E+00 0.00E+00 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-60 CURIES 6.301-06 7.65E-07 1.22E3-06 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 0.00E1+00 0.00E-+00 CR-51 CURIES 0.00E+00 0.00E+00 0.0013+00 0.00E+00 MO-99 CURIES 0.00E+00 0.00E+00 3.43E-10 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 3.43E-10 0.0013+00 CE-144 CURIES 0.00E+00 0.00E+00 4.73E-09 0.00E+00 CO-57 CURIES 0.00E+00 1.04E-07 0.00E+00 0.001E+00 CE-141 CURIES 0.00E+00 1.0713-07 0.00E+00 0.00E+00 Page I of 2 22
Table I B Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE IB (continued)
SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES. IODINES. AND PARTICULATES QUARTERS 3 AND 4.2004 I CONTINUOUS RELEASES l
BATCH RELEASES I
1 THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER
- 3. PARTICULATES CS-138 CURIES 0.00E+00 O.OOE+O0 1 0.00E+00 1.74E-07 ALPHA CURIES 4.21-07 2.24E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 4.64E-05 9.92E-06 l1.23E-06 1.74E-07
- 4. TRITIUM IH-3 CURIES 1.04E+01 7.23E+00 2.29E-0 I 8.87E-0 1
Page 2 of 2 23
Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS I AND 2.2004 I
I FIRST I SECOND I ESTTOTAL TYPE OF EFFLUENT UNITS I QUARTER l QUARTER l ERROR % (a) l A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES. ALPHA]
CURIES 1.37E-02 2.93E-01 20
- 2. AVERAGE DILUTED CONCENTRATION I
DURING PERIOD uCi/ML 3.44E-08 5.83E-07
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- 1. TOTAL RELEASE CURIES 4.38E+02 1.07E+02
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.10E-03 2.12E-04
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.62E+00 I.24E+00 27
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCi/MLv I.16E-05 2.47E-06 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.l00E+00 1.03E-03 29 E. WASTE VOLUME RELEASED (PRE-DILUTION)
GAL 3.13E+06 3.76E+06 10 IF. VOLUME OF DILUTION WATER USED lGAL I.02E+08 1.29E+08 10 (a) Safety Analysis Calculation 87-063-00. January 6, 1988 Page I of I 24
Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents TABLE2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4,2004 I
I THIRD I FOURTH EST TOTAL TYPE OF EFFLUENT UNITS I QUARTER I QUARTER ERROR % (a)
A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOT INCLUDING TRMIUM. GASES, ALPHA]
CURIES 2.24E-02 L.03E-02 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.90E-08 2.11E-08
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM 1.TOTALRELEASE CURIES 1.25E+01 5.80E+01 14
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.19E-05 1.18E-04
- 3. PERCENT OF APPLICABLE LIMIT N/A JN/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.57E-05 1.55E-04 27
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.74E-11 13.17E-10 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES I 2.071-03 l2.16E-04 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) I GAL l5.28E+06 4.59E+06 10 F. VOLUME OF DILUTION WATER USED lGAL I 1.46E+08 1.25E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 1 of I 25
Table 2B Semiannual Liquid Continuous & Batch Releases Totals for Each Nuclide Released TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS I AND 2,2004 I CONTINUOUS RELEASES BATCH RELEASPS I
FIRST SECOND FIRST SECOND lNUCLIDE UNITS QUARTER
[QUARTER IQUARTER I QUARTER
- 1. ALL NUCLIDES AM-241 CURIES O.OOE+00 0.OOE+00 2.72E-05 0.003E+00 CM-242 CURIES 0.00E+00 0.OOE+00 6.39E-06 0.00E+00 CO-58 CURIES O.OOE+00 O.OOE+00 2.93E-05 5.29E-03 CO-60 CURIES O.OOE+00 0.00E+00 1.09E-03 I.05E-03 CS-134 CURIES O.OOE+00 0.OOE+00 3.58E-03 2.01E-03 CS-137 CURIES 0.00E+00 0.00E+00 6.03E-03 2.33E-03 H-3 CURIES 0.00E+00 0.00E+00 4.38E+02 1.07E+02 NP-237 CURIES 0.OOE+00 0.00E+00 2.49E-06 7.34E-08 SB-125 CURIES 0.OOE+00 0.00E+00 2.29E-03
- 8. 18E-02 SR-90 CURIES 0.00E+00 0.OOE+00 3.20E-05 0.OOE+00 MN-54 CURIES 0.OOE+00 0.OOE+00 3.68E-05 4.79E-05 1-131 CURIES 0.OOE+00 0.OOE+00 4.71lE-04 1.58E-01 BA-140 CURIES 0.OOE+00 0.OOE+00 1.17E-05 0.OOE+00 KR-85 CURIES 0.OOE+00 0.00E+00 2.12E-01 5.38E-02 XE-131M CURIES 0.003E+00 0.OOE+00 1.36E-01 2.67E-02 XE-133 CURIES 0.00E+00 0.00E+00 4.26E+00 1.15E+00 XE-133M CURIES 0.00E+00 0.00E+00 1.42E-02 4.57E-03 ZR-95 CURIES 0.00E+00 0.OOE+00 3.54E-06 3.35E-05 CS-136 CURIES 0.OOE+00 0.00E+00 5.88E-05 0.OOE+00 SB-122 CURIES O.OOE+00 0.00E+00 1.66E-05 1.27E-03 XE-135 CURIES 0.00E+00 0.00E+00 5.19E-06 2.59E-05 CM-243 CURIES 0.00E+00 O.OOE+00 O.OOE+00 6.54E-06 FE-55 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 2.64E-02 NI-63 CURIES 0.OOE+00 0.00E+00 O.OOE+00 6.68E-03 BE-7 CURIES 0.OOE+00 0.003E+00 0.00E+00 3.71E-05 ALPHA CURIES O.OOE+00 0.00E-+00 0.00E+00 1.03E-03 CR-5I CURIES 0.003E+00 0.OOE+00 0.00E+00 2.94E-03 I-132 CURIES 0.00E+00 0.OOE+00 0.00E+00 7.87E-04 I-133 CURIES 0.00E+00 0.00E+00 0.00E+00 1.15E-03 NA-24 CURIES 0.OOE+00 0.OOE+00 0.00E+00 6.27E-05 SB-124 CURIES 0.00E+00 0.OOE+00 0.00E+00 3.80E-03 TE-132 CURIES 0.00E+00 0.OOE+00 0.00E+00 455E-04 Y-91M CURIES 0.OOE+00 0.00E+00 0.OOE+00 157E-05 NB-95 CURIES 0.OOE+00 0.OOE+00 0.00E+00 3.43E-06 AG-110M CURIES 0.0OE+00 0.OOE+00 0.OOE+00 3.84E-06 AR-41 CURIES O.OOE+00 0.OOE+00 O.OOE+00 7.66E-06 SN-113 CURIES O.OOE+00 0.00E+00 0.OOE+00 3.16E-06 NI-63 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 7.02E-05 TOTALS FOR PERIOD CURIES O.OOE+00 0.OOE+00 4.42E+02 1.08E+02 Page 1 of I 26
Table 2B Semiannual Liquid Continuous & Batch Releases Totals for Each Nuclide Released TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 3 AND 4,2004 CONTINUOUS RELEASES BATCH RELEASES t
FOURTH THIRD FOURTH NUCLIDE l UNITS QUARTER Q UARTER QUARTER l
TQUARTER
- 1. ALL NUCLIDES AM-241 CURIES 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 CM-242 CURIES 0.003E+00 0.OOE+00 0.00E+00 0.003E+00 CO-S 8 CURIES 0.00E+00 0.00E+00 7.79E-03 9.74E-04 CO-60 CURIES 0.00E+00 0.00E+00 7.33E-04 2.54E-04 CS-134 CURIES 0.00E+00 0.00E+00 9.97E-04 1.17E-04 CS-137 CURIES 0.OOE+00 0.OOE+00 1.12E-03 1.94E-04 H-3 CURIES 0.00E+00 0.00E+00 1.25E+01 5.80E+01 NP-237 CURIES 0.00E+00 0.OOE+00 4.59E-06 0.OOE+00 SB-125 CURIES 0.00E+00 0.00E-+00 7.02E-03 4.52E-03 SR-90 CURIES 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 MN-54 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1-131 CURIES 0.OOE+00 0.OOE+00 3.04E-05 0.00E+00 BA-140 CURIES 0.00E+00 0.00E+00 1.61E-05 O.OOE+00 KR-85 CURIES 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 XE-131M CURIES 0.OOE+00 O.OOE+00 0.OOE+00 1.50E-04 XE-133 CURIES 0.OOE+00 0.00E+00 0.003E+00 0.003E+00 XE-133M CURIES 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 ZR-95 CURIES 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 CS-136 CURIES 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 SB-122 CURIES 0.OOE+00 0.00E+00 9.72E-06 5.74E-06 XE-135 CURIES 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 CM-243 CURIES 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 FE-55 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 NI-63 CURIES 0.00E+00 0.OOE+00 3.1 IE-04 4.17E-03 BE-7 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ALPHA CURIES 0.00E+00 0.OOE+00 2.07E-03 2.16E-04 CR-51 CURIES 0.00E+00 0.OOE+00 1.60E-04 6.388E-05 1-132 CURIES 0.OOE+00 0.00E+00 0.00E+00 0.00E-+00 1-133 CURIES 0.003E+00 0.OOE+00 0.00E+00 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 SB-124 CURIES 0.OOE+00 0.00E+00 7.04E-05 3.79E-06 TE-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Y-91M CURIES 0.001E+00 0.OOE+00 0.00E+00 0.OOE+00 NB-95 CURIES 0.OOE+00 0.00E-+00 0.00E+00 4.61E-06 AG-110M CURIES 0.0OE+00 0.OOE+00 O.OOE+00 0.00E+00 AR-41 CURIES 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 SN-I 13 CURIES 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 NI-63 CURIES 0.OOE+00 0.OOE+00 4.08E-03 0.OOE+00 XE-135M CURIES 0.OOE+00 0.OOE+00 6.02E-06 0.OOE+00 CO-57 CURIES 0.00E+00 0.00E+00 4.68E-05 7.68E-06 MO-99 CURIES 0.00E+00 0.00E+00 0.00E+00 1.95E-06 TC-99M CURIES 0.00E+00 0.00E+00 0.00E+00 1.95E-06 TE-129 CURIES 0.00E+00 0.OOE+00 0.00E+00 3.08E-05 TOTALS FOR PERIOD CURIES 0.00E+00 0.OOE+00 1.26E+01 5.80E+01 Page I of I 4
27
Table 3 Solid Waste & Irradiated Fuel Shipments 2004 A.
SOLID WASTE BURIED (DOES NOT INCLUDE IRRADIATED FUEL)
- 1.
TYPE OF WASTE
- a. Spent resins, filter sludges, evaporator
- bottoms, etc.
- b.
Dry compressible waste, contaminated equipment, etc.
- c.
Irradiated components, UNITS Ci Ci PERIOD JAN JUN 5.86 235.00 24.36 0.33 0
0 0
0 PERIOD JUL DEC 2.88E-02 32.90 105.30 1.24 0
0 0
0 EST.
TOTAL ERROR
(%)
+/-25%
+/-25%
+/-25%
+/-25%
- d. Other etc.
Ci Ci
- 2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Type of Waste)
Nuclide
- a.
Ni-63 Fe-55 Co-60 Cs-137 Co-58 Mn-54 Cs-134 Sb-125 PERIOD JAN S Abundance 47.10 21.21 12.27 7.28 4.22 2.55 2.41 2.39 JUN Curies 109.90 49.50 28.62 16.99 9.84 5.94 5.63 5.59 PERIOD
% Abundance 28.16 1.00 2.98 19.76 24.71
<1%
22.72
<1%
JUL DEC Curies 9.29 0.33 0.98 6.52 8.15 7.49
- b.
Fe-55 Co-58 Cs-137 Ni-63 Co-60 Nb-95 Mn-54 Cs-134 Zr-95 34.98 16.38 13.03 12.26 7.77 4.51 3.85 3.77 2.30 0.11 5.OOE-02 4.OOE-02 4.OOE-02 2.50E-02 1.50E-02 0.13 1.20E-02 7.OOE-03 34.98 16.38 13.03 12.26 7.77 4.51 3.85 3.77 2.30 0.43 0.20 0.16 0.15 9.60E-02 5.60E-02 4.80E-02 4.70E-02 2.90E-02 Page 1 of 2 28
Table 3 Solid Waste & Irradiated Fuel Shipments 2004
- 2.
ESTXMATE OF MAJOR NUCLIDE COMPOSITION (by Tvye of Waste)
Cont.
PERIOD JAN -
JUN
% Abundance Curies PERIOD JUL -
% Abundance Curies Nuclide
- c.
None
- d.
None
- 3.
SOLID WASTE DISPOSITION:
Number of el, 4 m-,
t Mode of Tr.n.n.r I-Class of Solid W-nt-c'--Ae Type of t'nn to4nor i~~s~jz11UllL
-U V
X e
stxXVnva.
ssvvo
~
az lo*
1*
2*
3*
Truck Cask Cask Truck RACE, LLC Duratek Studsvik Duratek A
A B
A LSA LSA LSA LSA Sent to waste processors for volume reduction before burial.
- 4.
SOLIDIF None used.
ICATION AGENT:
B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments 0
Mode of Transportation Destination Page 2 of 2 29
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:48.72 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00
% GOOD DATA UNITS VALUES Stability Class A-G E
86%
Total Precipitation CM.
1.18E+02 98%
10 Meter Level:
Wind Speed Meter/Sec 2.95E1+00 100%
Wind Direction Degrees 2.01E+02 100%
Wind Direction Variability Degrees 1.33E+01 100%
Reference Temperature Degrees C 1.27E+01 99%
Dewpoint Degrees C 5.96E+00 81%
60 Meter Level:
Wind Speed Meter/Sec 5.18E+00 97%
Wind Direction Degrees 2.12E+02 96%
Wind Direction Variability Degrees 8.28E+00 99%
Dewpoint Degrees C NONE 0%
Temperature Difference 60 - 10 Degrees C 5.27E-02 86%
Page 1 of 1 30
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: A Wind Speed at 10.00 Meter Level (MPH)
¶ T
7 r
t 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 24 13 5
0 0
42 NNE 7
28 19 3
0 0
57 NE 7
30 14 0
0 0
51 ENE 6
22 3
0 0
0 31 E
5 16 1
0 0
0 22 ESE 5
24 5
2 0
0 36 SE 8
71 41 3
0 0
123 SSE 6
74 49 19 0
0 148 S
10 72 62 17 0
0 161 SSW 14 86 76 12 3
0 191 SW 9
63 39 4
1 0
116 WSW 8
27 15 6
0 0
56 W
10 35 49 1
0 0
95 NVNW 9
30 43 16 0
0 98 NW 6
25 30 4
0 0
65 NNW 2
22 22 8
0 0
54 TOT 112 649 481 100 4
0 1346 Hours of Calm Data:
Hours of Invalid Data:
2 0
Page 1 of 7 31
Table 4 Meteorological Data Averages Using HourlyAveraged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: B Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 20 10 1
0 0
33 NNE 6
11 12 2
0 0
31 NE 0
8 7
1 0
0 16 ENE 4
9 8
0 0
0 21 E
3 7
2 0
0 0
12 ESE 0
7 4
1 0
0 12 SE 4
16 8
0 0
0 28 SSE 5
11 11 2
2 0
31 S
9 11 16 4
0 0
40 SSW 2
14 14 9
1 0
40 SW 3
26 6
5 1
0 41 WSW 1
17 5
4 1
0 28 W
6 16 7
0 0
0 29 WNW 4
9 9
1 0
0 23 NW 5
14 4
4 0
0 27 NNW 1
20 8
1 0
0 30 TOT 55 216 131 35 5
0 442 Hours of Calm Data:
Hours of Invalid Data:
0 0
Page 2 of 7 32
Table 4 Meteorological Data Averages Using HourlyAveraged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: C Wind Speed at 10.00 Meter Level (MPH) r I
1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 16 15 0
0 0
31 NNE 3
18 13 0
0 0
34 NE 6
12 5
0 0
0 23 ENE 2
9 8
0 0
0 19 E
2 3
4 0
0 0
9 ESE 5
14 2
0 0
0 21 SE 6
11 11 0
0 0
28 SSE 0
13 8
1 0
0 22 S
2 22 12 5
0 0
41 SSW 3
13 12 0
0 0
28 SW 4
9 11 1
0 0
25 WSW 3
13 9
6 0
0 31 W
1 14 6
0 0
0 21 WNW 0
8 6
3 0
0 17 NW 1
11 20 1
0 0
33 NNW 1
17 20 2
0 0
40 TOT 39 203 162 19 0
0 423 Hours of Calm Data:
Hours of Invalid Data:
0 0
Page 3 of 7 33
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: D Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
17 120 106 15 2
0 260 NNE 20 102 80 18 1
0 221 NE 36 95 55 0
0 0
186 ENE 25 64 56 0
0 0
145 E
22 53 21 0
0 0
96 ESE 21 59 43 0
0 0
123 SE 21 84 54 2
0 0
161 SSE 14 84 80 7
2 0
187 S
17 86 86 17 2
0 208 SSW 17 55 53 25 1
0 151 SW 14 42 31 3
0 0
90 WSW 1
29 16 7
0 0
53 W
16 49 39 4
0 0
108 WNW 11 78 89 15 0
0 193 NW 20 83 69 13 0
0 185 NNW 12 71 134 38 0
0 255 TOT 284 1154 1012 164 8
0 2622 Hours of Calm Data:
Hours of Invalid Data:
10 0
Page 4 of 7 34
Table 4 Meteorological Data Averages Using HourlyAveraged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: E Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
15 78 30 0
0 0
123 NNE 24 72 7
0 0
0 103 NE 36 80 2
0 0
0 118 ENE 21 33 2
0 0
0 56 E
21 30 2
0 0
0 53 ESE 42 42 8
0 0
0 92 SE 23 135 32 1
0 0
191 SSE 25 155 97 4
0 0
281 S
35 130 115 5
0 0
285 SSW 18 82 38 3
0 0
141 SW 30 63 19 2
0 0
114 WSW 28 45 23 2
0 0
98 W
37 83 22 0
0 0
142 WNW 13 34 24 0
0 0
71 NW 37 60 24 3
0 0
124 NNW 31 67 16 1
0 0
115 TOT 436 1189 461 21 0
0 2107 Hours of Calm Data:
Hours of Invalid Data:
46 0
Page 5 of 7
.1
,
Table 4 Meteorological Data Averages Using HourlyAveraged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: F Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
21 38 0
0 0
0 59 NNE 20 20 0
0 0
0 40 NE 25 3
0 0
0 0
28 ENE 25 3
0 0
0 0
28 E
26 2
0 0
0 0
28 ESE 43 20 0
0 0
0 63 SE 33 109 6
0 0
0 148 SSE 25 172 15 0
0 0
212 S
31 89 19 0
0 0
139 SSW 40 57 0
0 0
0 97 SW 34 47 1
0 0
0 82 WSW 26 21 1
0 0
0 48 W
22 7
0 0
0 0
29 WNW 39 15 0
0 0
0 54 NW 22 11 0
0 0
0 33 NNW 32 28 0
0 0
0 60 TOT 464 642 42 0
0 0
1148 Hours of Calm Data:
Hours of Invalid Data:
64 0
Page 6 of 7 36
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 1 8-APR-2005 16:42:50.45 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: G Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
28 3
0 0
0 0
31 NNE 20 0
0 0
0 0
20 NE 24 0
0 0
0 0
24 ENE 14 0
0 0
0 0
14 E
6 1
0 0
0 0
7 ESE 15 1
0 0
0 0
16 SE 41 31 0
0 0
0 72 SSE 66 65 1
0 0
0 132 S
30 7
0 0
0 0
37 SSW 15 6
0 0
0 0
21 SW 8
5 0
0 0
0 13 WSW 6
1 0
0 0
0 7
W 14 0
0 0
0 0
14 WNW 25 3
0 0
0 0
28 NW 17 2
0 0
0 0
19 NNW 23 13 0
0 0
0 36 TOT 352 138 1
0 0
0 491 Hours of Calm Data:
Hours of Invalid Data:
Hours of Good Data:
62 0
8763 = 99.8% of Total Hours Page 7 of 7 37
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: A Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 14 16 8
2 0
42 NNE 3
15 28 8
0 0
54 NE 1
26 17 5
0 0
49 ENE 2
19 4
1 0
0 26 E
2 18 5
1 0
0 26 ESE 2
16 13 1
1 0
33 SE 0
36 58 18 1
0 113 SSE 2
38 56 36 13 0
145 S
3 41 46 39 5
2 136 SSW 3
43 69 53 11 8
187 SW 2
23 61 29 3
1 119 WSW 4
15 19 9
7 0
54 W
4 16 37 33 5
0 95 WNW 4
13 36 24 11 11 99 NW 1
11 23 18 4
1 58 NNW 1
15 17 13 7
0 53 TOT 36 359 505 296 70 23 1289 Hours of Calm Data:
Hours of Invalid Data:
0 59 Page 1 of 7 104
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: B Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 1
13-18 1
19-24
>24 TOTAL N
1 8
11 5
1 0
26 NNE 1
10 12 6
0 0
29 NE 1
7 10 6
0 0
24 ENE 1
7 7
4 0
0 19 E
1 4
3 0
0 0
8 ESE 0
4 5
3 0
0 12 SE 0
9 12 3
0 0
24 SSE 3
6 14 6
2 2
33 S
0 9
11 9
2 0
31 SSW 2
7 8
17 7
3 44 SW 0
8 20 5
3 4
40 WSW 0
8 12 4
4 0
28 W
1 7
10 6
1 0
25 WNXV 0
6 12 5
2 1
26 NW 0
9 6
4 3
2 24 NNW 0
17 14 1
1 0
33 TOT 11 126 167 84 26 12 426 Hours of Calm Data:
Hours of Invalid Data:
0 16 Page 2 of 7 39
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: C Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 9
15 7
0 0
31 NNE 3
8 16 6
0 0
33 NE 3
11 10 0
0 0
24 ENE 0
6 12 0
0 0
18 E
2 0
7 1
0 0
10 ESE 3
6 11 0
0 0
20 SE 2
7 6
4 0
0 19 SSE 0
5 10 7
0 0
22 S
0 9
16 8
5 0
38 SSW 0
8 12 9
2 0
31 SW 0
5 15 6
0 0
26 WSW 0
6 8
6 7
2 29 W
0 4
8 7
2 0
21 WNW 0
2 5
6 3
1 17 NW 0
6 11 18 1
0 36 NNW 1
6 19 9
1 0
36 TOT 14 98 181 94 21 3
411 Hours of Calm Data:
Hours of Invalid Data:
0 12 Page 3 of 7 An
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: I 8-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: D Wind Speed at 60.00 Meter Level (MPH)
-I 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
5 37 95 76 5
4 222 NNE 6
54 90 66 16 2
234 NE 8
47 97 31 0
0 183 ENE 5
33 72 40 0
0 150 E
8 26 42 12 0
0 88 ESE 5
24 68 25 1
0 123 SE 4
29 66 34 0
0 133 SSE 2
31 79 56 6
2 176 S
2 15 75 72 16 2
182 SSW 6
18 46 57 28 7
162 SW 3
12 37 32 11 1
96 WSW 0
5 23 19 11 2
60 W
3 30 389 4
91 WNW 3
16 71 75 25 4
194 NW 4
20 76 73 30 1
204 NNW 2
29 68 III 36 2
248 TOT 66 403 1035 817 194 31 2546 Hours of Calm Data:
Hours of Invalid Data:
1 85 Page 4 of 7 41
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: E Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 1
>24 I TOTAL N
4 20 77 47 0
0 148 NNE 4
16 57 15 0
0 92 NE 4
30 90 7
0 0
131 ENE 2
17 50 3
0 0
72 E
4 8
35 2
0 0
49 ESE 3
23 61 12 0
0 99 SE 4
20 85 60 1
1 171 SSE 1
18 86 117 4
0 226 S
1 20 69 162 14 1
267 SSW 2
13 68 95 10 2
190 SW 4
13 52 46 3
3 121 WSW 2
22 40 33 10 1
108 W
0 14 46 60 4
0 124 WNVW 1
21 29 48 2
0 101 NW 2
15 39 37 10 0
103 NNW 0
14 48 25 2
0 89 TOT 38 284 932 769 60 8
2091 Hours of Calm Data:
Hours of Invalid Data:
5 57 Page 5 of 7 42
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 18-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: F Wind Speed at 60.00 Meter Level (MPH)
.I 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 11 23 16 0
0 52 NNE 0
5 18 25 0
0 48 NE 5
16 18 5
0 0
44 ENE 6
10 9
5 0
0 30 E
3 17 20 3
0 0
43 ESE 1
17 29 7
0 0
54 SE 2
19 59 34 0
0 114 SSE 2
13 60 79 0
0 154 S
4 17 69 61 1
0 152 SSW 3
5 39 72 1
0 120 SW 1
11 44 49 2
0 107 WSW 3
16 25 15 0
0 59 W
0 12 22 8
0 0
42 WNW 1
5 14 18 0
0 38 NW 2
8 32 10 0
0 52 NNW 3
8 23 13 0
0 47 TOT 38 190 504 420 4
0 1156 Hours of Calm Data:
Hours of Invalid Data:
3 53 Page 6 of 7 43
Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report DateiTime: 18-APR-2005 16:42:51.90 Meteorological Data Totals of Hours at Each Wind Speed & Direction I-JAN-2004 00:00:00.00 to 31-DEC-2004 23:59:59.00 Stability Class: G Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 6
11 7
0 0
26 NNE 2
7 12 3
0 0
24 NE 5
9 16 2
0 0
32 ENE 1
5 27 9
0 0
42 E
4 4
10 3
0 0
21 ESE 1
13 17 2
0 0
33 SE 1
5 30 8
0 0
44 SSE 3
5 40 7
0 0
55 S
2 20 53 18 0
0 93 SSW 1
7 24 9
1 0
42 SW 0
8 9
9 0
0 26 WSW 0
6 4
3 0
0 13 W
2 7
4 2
0 0
15 WNW 2
3 11 10 0
0 26 NW 2
4 3
11 0
0 20 NNW 3
3 8
7 1
0 22 TOT 31 112 279 110 2
0 534 Hours of Calm Data:
Hours of Invalid Data:
Hours of Good Data:
0 19 8462 = 96.3% of Total Hours Page 7 of 7 AA
Table 5 Dose at the Site Boundary and to the Nearest Resident From Gaseous Effluents Table 5 DOSEATTHE SITE BOUNDARYAND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS SITE BOUNDARY LOCATION: 2.20 km NNW AGE GROUP: CHILD ORGAN UNITS DOSE
% LIMIT (a)
GAMMAAIR DOSE*
MRAD 1.29E-02 0.13 BETAAIR DOSE
- MRAD 3.03E-02 0.15 WHOLE BODY MREM 1.16E-02 N/A SKIN ***
MREM 2.49E-02 N/A BONE **
MREM 3.88E-04 N/A LIVER **
MREM 1.65E-03 N/A TOTAL BODY **
MREM 1.65E-03 N/A THYROID MREM 2.80E-03 N/A KIDNEY **
MREM 1.66E-03 N/A LUNG **
MREM 1.67E-03 N/A Gl-LLI **
MREM 1.65E-03 N/A NEAREST RESIDENT LOCATION: 2.90 km NNW AGE GROUP: CHILD DOSE
% LIMIT (b) 8.50E-03 N/A 1.99E-02 N/A 7.62E-03 N/A 1.64E-02 N/A 1.67E-03 0.01 9.27E-03 0.06 8.19E-03 0.05 2.23E-01 1.49 9.OOE-03 0.06 7.74E-03 0.05 7.71 E-03 0.05 Dose from Noble Gases only.
- Dose from Tritium, Radioiodines, and Particulates only.
- Dose from Noble Gases plus Ground Plane dose.
(a) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 10 mrad gamma air dose and 20 mrad beta air dose.
(b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 15 mrem to any organ from 1-131,1-133, H-3, and particulate radionuclides with half-lives greater than 8 days.
45
Table 6 Dose to the Member of the Public From Activities within the Site Boundary Table 6 DOSE TO THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY (MEMBER OF THE PUBLIC)
EFFLUENT DIRECT DIRECT DIRECT EFFLUENT TOTAL DOSE WITHIN RADIATION RADIATION RADIATION DOSE DOSE THE SITE FROM THE FROM OUTSIDE FROM RAM FROM FOR THE ORGAN UNITS BOUNDARY UNIT TANKS STORAGE CLG. TWR YEAR SKIN MREM 5.80E-03 N/A N/A N/A N/A 5.80E-03 BONE MREM 1.13E-04 8.79E-03 1.36E-03 1.82E-03 N/A 1.21E-02 LIVER MREM 4.77E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 TOTAL BODY MREM 3.13E-03 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.51 E-02 THYROID MREM 6.91 E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.27E-02 KIDNEY MREM 4.77E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 LUNG MREM 4.80E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 GI-LLI MREM 4.76E-04 8.79E-03 1.36E-03 1.82E-03 2.08E-05 1.25E-02 46
Table 7 Total Dose Due to the Uranium Fuel Cycle (Member of the Public)
Table 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OF THE PUBLIC)
EFFLUENT DOSE FROM DOSE AT THE ACTIVITIES RESIDENCE WITHIN SITE LOCATION BOUNDARY DOSE FROM CLG TWR H-3 TOTAL DOSE TO THE AT NEAREST MEMBER OF RESIDENCE THE PUBLIC ORGAN UNITS
% LIMITS
- SKIN MREM 1.62E-02 5.80E-03 N/A 2.20E-02 0.09 BONE MREM 5.99E-04 1.21 E-02 N/A 1.27E-02 0.05 LIVER MREM 5.32E-03 1.25E-02 1.42E-05
.1.78E-02 0.07 TOTAL BODY MREM 1.25E-02 1.51 E-02 1.42E-05 2.76E-02 0.11 THYROID MREM 7.97E-02 1.27E-02 1.42E-05 9.24E-02 0.12 KIDNEY MREM 5.24E-03 1.25E-02 1.42E-05 1.78E-02 0.07 LUNG MREM 4.78E-03 1.25E-02 1.42E-05 1.73E-02 0.07 GI-LLI MREM 4.85E-03 1.25E-02 1.42E-05 1.74E-02 0.07
'Annual dose limits from 40CFR190.1 0(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.
47
Table 8 Dose Due to Liquid Effluents (Member of the Public)
Table 8 DOSE DUE TO LIQUID EFFLUENTS (MEMBER OF THE PUBLIC) 2004 ORGAN UNITS LIMIr
% LIMIT BONE MREM 4.98E-02 10.00 4.98E-01 LIVER MREM 8.02E-02 10.00 8.02E-01 TOTAL BODY MREM 5.90E-02 3.00 1.97 THYROID MREM 8.99E-02 10.00 8.99E-01 KIDNEY MREM 2.76E-02 10.00 2.76E-01 LUNG MREM 9.81 E-03 10.00 9.81 E-02 GI-LLI MREM 3.51 E-03 10.00 3.51 E-02
- Annual dose limits of APA-ZZ01003, Section 9.4.1.1.
48