ML061290525
| ML061290525 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/2005 |
| From: | AmerenUE |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML061290525 (47) | |
Text
-q -;
-
a 2005 Callaway Plant Radioactive Effluent Release Report E
wamew,, UF Sm Docket r -. 50-483
Table of Contents Introduction 1.0 Introduction
... 1 2.0 Supplemental Information....
2 2.1 Regulatory Limits
.2 2.2 Average Energy..........
2 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
.9 6.3 Major Changes to Radwaste Treatment Systems
.9 6.4 Land Use Census Changes...........................................................................9......9 6.5 Inoperability of Effluent Monitoring Instrumentation.10 6.6 Instances of Liquid Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits......................
10 7.3 M eteorological Data.............................................................................................
11 8.0 Assessment of Doses.13 8.1 Dose at the Site Boundary from Gaseous Effluents.13 8.2 Dose to the Member of the Public.13 8.3 Total Dose Due to the Uranium Fuel Cycle...................................
14 8.4 Dose Due to Liquid Effluents.14 List of Tables 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 This report describes the Union Electric Co.
Callaway Plant radioactive effluent releases for 2005.
It is submitted in accordance with Section 5.6.3 of the Callaway Plant Technical Specifications.
A summary of radioactivity released in liquid and gaseous effluents and solid waste shipped and/or buried from the Callaway Plant during the period from January 1, 2005 to December 31, 2005 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.
I
2.0 Supplemental Information 2.1 Regulatory Umits The Radiological Effluent Control (REC) limits W
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/yr to 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:
ID
- 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-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight D
(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 otherthan 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 quarterto 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, exceptthe thyroid, which shall be limited to less than or equal to 75 mrem.
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.
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2.0 Supplemental Information Continued 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 ReportTable 16.11-1 and Table 16.11-4.
Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Liquid composite samples were analyzed for Sr-89, Sr-90, Fe-55, Ni-63, and transuranic nuclides by Environmental Inc. -
Midwest Laboratory. Gaseous composite samples were analyzed for Sr-89 and Sr-90 nuclides by Environmental Inc. -Midwest Laboratory. 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.
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V 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 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 Missoui River flow during periods of effluentrelease to theriver1 :
UNITS Minutes Minutes Minutes Minutes ft3/sec JAN-JUN 55 28,940 3,067 526 362 89,155 JUL-DEC 73 30,134 719 413 98 45,023 GASEOUS UNITS Number of batch releases:
Total time period for batch releases:
Maximum time period forbatch releases:
Average time period for batch releases:
Minimum time period for batch releases:
Minutes Minutes Minutes Minutes JAN - JUN 32 4,580 1,741 143 28 JUL-DEC 25 17,493 1,816 700 30
' E-mail, S. Temes, United States Department of the Interior -Geological Survey -Water Resources Divisionrdated January 30,2006 2.5 Abnormal Releases LIQUID D
Number of releases: 1 Total Activity released: 928 microCuries GASEOUS Number of releases: 1 Total Activity released: 23.4 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 1A and 1 B. During 2005, 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 2005, there was no continuous release of liquid effluent from the plant.
Liquid effluents from the plant are continuously monitored.
Shown is a liquid radiation monitor shielded by lead to increase its sensitivity for sampling discharged water.
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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 processors 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 II
- of each nuclide listed in Table 3 was determined
- as the product of the fractional abundance and the total curies buried. 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:
I
- 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 P0 significant deviation from the requirements of the release permit.
Auxiliary Boller Contamination
° On April 10, 1998, during a refueling outage, radioactivity was detected in the Auxiliary Boiler feed water system. The boilerwasflushed and cleaned several times in an attempt to decontaminate the unit. Small amounts of D
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.
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 the Auxiliary Boiler would not pose any significant safety or environmental concern.
The Auxiliary Boiler was operated intermittently during 2005. The maximum total body dose to a Member of the Public from these releases was 4.11 E-05 mrem during 2005. This is negligible compared to the quarterly and annual effluent control limits. The activity released from the Auxiliary Boiler during 2005 is included in Tables 1A, 18, 5,6and 7.
An investigation was performed to locate the source of the contamination. No mispositioned valves or leaks were identified. The results of 7
6.0 Related Information 6.1 Unplanned Releases (continued)
Intermittent Releases from the Cooling Tower (NRC Information Notice 2004-05)
Durirng investigation of NRC Information Notice 2004-05, sample results revealed intermittent levels of tritium in the cooling tower basin (CAR 200403826). It was determined that the tritium found in cooling tower samples was a result of recirculation of liquid effluents (CAR 200403826).
An evaluation of the dose impact was performed assuming releases from the cooling tower were elevated. The total activity released from the cooling tower in 2005 was determined to be 23.4 Curies of tritium. The total dose to the W
Member of the Public was calculated to be 3.28E-03 mrem.
Discharge Line Leak In January2005, it was identified that the plant discharge line had ruptured in a field on Union Electric property nearthe Missouri River. The rupture occurred near a cement crossing created to facilitate movement of replacement Steam Generators. The total activity released in the vicinity of the break was determined to be 928 microCuries (CAR 200500214).
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6.0 Related Information 6.2 Changes to the Offsite Dose Calculation Manual Changes to APA-ZZ-01 003 Minor changes were made in 2005 toAPA-ZZ-01 003, the Callaway Offsite Dose Calculation Manual (ODCM).
Section 5.1 of APA-ZZ-01003 was revised to remove an invalid requirement that a REMP contract lab performing direct radiation analyses is required to participate in the Environmental Measurements Laboratory QualityAssessment Program or equivalent.
Additional guidance on REMP contract lab participation in Interlaboratory Comparisons was also added to section 5.1 (CAR 200500891).
Reference to.Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment, was added to provide supporting documentation for contract lab Interlaboratory Comparison requirements (CAR 200500891).
Health Physics Calculation HPCI 87-10, Methodology for Calculating the Response of Gross Nal(TI) Monitors to Liquid Effluent Streams, was revised to add normalization and standardization factors to the Effluent Management System software for radionuclides listed in Table 2.1 that were not included in the original calculation (CAR 200501509).
Section 4.1.3.1.4 was added to describe direct radiation dose from the newly constructed Old Steam Generator Storage Facility to a Member of the Public.
Section 4.1.2 was revised to describe the sources of direct radiation from "outside storage tanks" to "storage of radioactive material".
Section 4.1.3.1.2 was revised to describe direct dose calculations in support of Modification 03-1008, Equipment Hatch Platform and Missile Shield Modification.
Reference to Health Physics Calculation 06-01, Equipment Hatch Platform and Missile Shield Modification Direct Dose Calculation to the Member of the Public, was added to reference direct dose calculation to the Member of the Public from Modification 03-1008.
Section 4.1.3.1.3 was revised to describe direct dose calculations from the Radwaste Yard RAM storage and Stores II.
Changes to FSAR-SP Chapter 16.11 No changes were made in 2005 to the Final Safety Analysis Report - Standard Plant Chapter 16.11, Offsite Dose Calculation Manual - Radioactive Effluent Controls (ODCM-RECs).
6.3 Major Changes to Radwaste Systems During 2005, there were no major plant changes to Radwaste systems.
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.
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6.0 Related Information 6.5 Inoperability of Effluent Monitoring Instrumentation During 2005 all effluent monitoring instrumentation was OPERABLE within limits specified in ODCM-REC sections 16.11.1.3 and 16.11.2.4.
One related exception in 2005 was failure of Primary Met Tower 60-1 Om Delta-T instrumentation (CAR 200503749), later described in section 7.0, Meteorological Data.
6.6 Instances of Liquld Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical, Specification Limits All liquid tanks and waste gas decay tanks were within limits specified in ODCM-REC sections 16.11.1 and 16.11.2 during the reporting period.
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7.0 Meteorological Data The on-site meteorological data for 2005 is presented in Table 4. 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.
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.
Valid data recovery for 2005 was greater than 90% for all required parameters. Specific valid recovery rates for the year are listed as follows:
60mWS 6OmWD 60m sigma-theta 60m-1 Om delta-T 1OmWS 1OmWD 1 Om sigma-theta 10mT 99.7%
99.7%
99.2%
92.9%
99.9%
99.9%
99.9%
99.9%
S Mercury Wetted Relay Failure an 604lOim Delta-T Channel The biggest problem encountered during 2005 affecting valid data capture was a mercury wetted relay failure on the Primary Met Tower 60-1 Om delta-T channel (CAR 200503749). In late May an unusual lapse rate pattern was noted by the contract meteorologist in his review of the 15 min averaged data. Inspection of the 5 sec data values forthe channel by the system engineer showed that although the 60-1 Om delta-T data were showing reasonable diumal patterns, the raw data appeared to be filtered or damped (lower than normal standard deviations). The data anomaly was visible in the real time 5 sec data, but rather hidden in the 15 minute and hourly averages.
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.
Engineering's initial investigation determined that the meteorological instruments were functioning normally, and the problem appeared to be a communication problem with the plant computer. Job 05105573 troubleshot and corrected the communication problem. The cause was attributed to a mercury wetted relay not making good contact on the analog-to-digital (AW D) input card for the plant computer. The input cards were removed and mechanically agitated to recoat the contacts with mercury.
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7.0 Meteorological Data (continued)
Plant Computer and Communications Link Failures Plant computer problems resulted in the loss of data several times during the year, but the data losses were quite minimal.
Occasionally the system showed spikes (usually "open" channel values) in the raw 5 sec data. These were attributed to communications link failures due to the momentary or short term power failures (and switching to backup power). The system engineer provided a listing of these occurrences to the meteorologist and any affected data averages were invalidated.
Evaluation of Primary Met Tower Anchors As part of modification MP 04-1 020A to upgrade Callaway's meteorological monitoring system, Engineering contracted with Tower Systems, Inc. to perform an inspection of the Primary Met Tower structure and anchors. The purpose of this inspection was to verify the long term structural reliability of the tower and its anchors if it is to be retrofit with new instrumentation and elevators.
This inspection was performed on 12/5/05 by Job 05110411/500. The initial results of the inspection indicated that there was some degradation of the anchor rods near the concrete slabs in which they were embedded. The anchors were replaced on March 18,2006.
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8.0 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 LD all airborne effluents released from the Callaway Plant during 2005, the annual dose to the maximum exposed individual was less than 1 % of the Radiological Effluent Control Limits presented in Section 2.1 of this report.
For all liquid effluents, the annual dose to the maximum exposed individual was less than 1.0%
of the Radiological Effluent Control Limits presented in Section 2.1 of this report.
O:
8.1 Dose at the Site Boundary from Gaseous Effluents The dose at the Site Boundary was due to I
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 I 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 2005 is presented in Table 5.
8.2 Dose to the Member of the Public D
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 Memberofthe Publicwithin the Site Boundary, and the Nearest Resident were each evaluated.
Dose at the Nearest Resident 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 conditionsforthe 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 2005 are presented in Table 5.
Dose to the Member of the Public from Activites wAthin 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.
1 -.4
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) wras the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence. Itwas conservativelyassumed that each food ingestion pathway exists at his residence and that the adult is the critical age group.
The total dose from the Uranium Fuel Cycle is presented in Table 7.
8.4 Dose Due to Uquid Effluents Dose due to liquid effluents includes contributions from the maximum exposed individual's consumption of fish and recreational ID activities. An adult was considered the maximum exposed individual in this assessment.
It is conservatively assumed that the hypothetical maximum exposed individual obtained his entire annual fish intake from near V
the plant discharge.
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Table 1A Semiannual Summation of Gaseous Releases All Airborne Effluents TABLE 1A SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2,2005 FIRST SECOND EST TOTAL TYPE OF EFLtUENT UNITS QUARTER QUARTER ERROR % (a)
A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 9.13E+00 2.59E+00 20 l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.17E+00 3.29E-01
- 3. PERCENT OF TECH SPEC LIMIT N/A.
N/A B. RADIOQODINES
- 1. TOTAL IODINE-131 CURIES 0.OOE+00 4.55E-08 23
- 2. AVERAGE RELEASE RATE FOR PERIOD uCYSEC 0.ooE+00 5.79E-09
- 3. PERCENT OF TECH SPEC LIMIT S
l NJA N/A C. PARTICULATES
- 1. PARTULATE (HALF-LIVES > 8 DAYS)
CURIES 2.3 iE-05 3.17E-05 30k]
2 AVERAGE RELEASE RATE FOR PERIOD uCiSEC 2.96E-46 4.04E-06 3 PERCENT OFMTECH SPEC IMIT N
M/A NJA 4 GROSS ALPHA RADIOACTIVITY CURIES 1.25E-07 2.07E-07 D. TRMUM i TOTAL RELEASE CURIES l6.TVEO 7.34h+00 l
1 i4
- 12. AVERAGE RELASE RATE FOR PERIOD uCiYSEC 1 8.62E-01 9.34E-01
- 3. PERCENT OF TECH SPEC LIMIT
[_%
N/A N/A (a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page I of I tI
Table 1A Semiannual Summation of Gaseous Releases All Airborne Effluents TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS Continued QUARTERS 3 AND 4,2005 THIRD l FOURTH l EST TOTAL TYPE OF EFFLUENT I UNITS I QUARTER IQUARTER I ERROR % (a) I A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 1.95E+01 3.33E+00 20
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.45E+00 4.19E-01
- 3. PERCENT OF TECH SPEC LIMIT
%_N/A N/A J
B. RADIOIODINES
- 1. TOTAL IODINE-13 1 CURIES 3.94E-08 5.81E-08 23
- 2. AVERAGE RELEASE RATE FOR PERIOD UCiSEC 4.96E-09 7.31E-09
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES > 8 DAYS)
CURIES 1.14E-05 5.45E-05 30Il 2-AVERAGE RELEASE RATE FOR PERIOD U-irSEC 1.43E-06 6.86E-06
- 3. PERCENT OF TECH SPEC L1aT JoMIlA NfA 4 GROSS ALPHA RADIOACIVTY CURIES L.98P-07 5.48 07 D. TRITIUM
- 1. TOTAL RELEASE CURIES 9.L7E+0
&94E+0 1
14
- 12. AVERAGE RELEASE RATE FOR PERIOD uCiISEC I 1. LSE00 1.13B+00 I 3. PERCENT OF TECH SPEC LIMIT I
INIA IN/A (a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page 1 of I in-
Table lB 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 1 AND 2,2005 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLCDE UNTTS QUARTER QUARTER QUARTER QUARTER
- 1. FISSION GASES AR-41 CURIES 2.94E-02 1.09E-01 9.45E-02 4.35E-02 XE-133 CURIES 2.85E-01 9.992-01 1.96E-03 1.87E-03 XE-135 CURIES 1.25E-01 4.00E-01 2.96E-05 2.92E-05 KR45 CURIES 0.002+00 0.00E+00 4.11E+00 0.00E2+00 KR-85M CURIES 1.33E-02 4.952-02 0.OOE+00 0.00E+00 KR-87 CURIES 3.07E-02 1.15E-01 0.00E+00 O.OOE+00 KR-nS CURIES 3.822-02 1.422-01 0.00E+00 0.00E2+00 XE-U5M RES 5.31E-02 1.08E-01 0.OOE+00 0.00E+00 XE-Ut.
CURIES 1.752+00 1.33E-01 0.OOE+00 0.002+00 XE-13LM CURIES 2.61E+00 4.892-01 0.002+00 0.00E+00 TOTALFOR PERIOD CURIES 4.93E+00 2.554+00 4.202+00 4.542-02
- 2. [ODINES 1-133 CURIES 5.62E-08 0.00fi400 2.89E-08 3.37E-09 R-132 CUS 1.772-05 4.5-E+08 1.33E-08 0 3.3E20 1A3M CURJES 0.002+00 4.55-08 0 02E+00 0.002+00
-1AL FRR DES J
1.78E-05 4.50-0 J
4.23E3-08 3.37E-09 S. PARTMULATES 99 CUIES 0.00E+00 0.0013+00 7.052-07 2.452-07 TC-99M CURIES 0.00E+00 0Q00+00 7.052-07 2.452-07 CS-134 CURIES 0.002+00 0.002+00 4.96E-06 1.42E-06 CS-137 CURIES 5.172-08 0.00E+O0 4.93E-06 1.22E-06 CO-60 CURJES 0.00E+00 0.00E+00 7.292-06 1.72E-05 CE, 141 CURIES 0.002+00 0.002+00 1.29f-06 4.49E-07 CO-Se CURIES 0.00+00 0.00+00 3.122-06 1.09E-06 SB-125 CURIES 0.002+00 2.80E-07 0.002+0 O.OOE+00 CD-109 CURIES 0.002+00 9.63E-06 0.002+0 0.00+00 CE-144 CURIES 0.00E+00 0.0OE+00 0.00E+00 5.86E-09 PR-144 CURIES 0.002+00 O.OOE+00 0.00+00 5.86E-09 TE-132 CURIES 0.002+00 0.002+00 O.OOE+00 1.06E-09 AL!PHA CURIES 1.25E-07 2.072-07 0.002+00 0.00E+00 TOTAL FOR PERIOD CURIES 1.76E-07 1.01E-05 2.30E-05 2.18E-05 Page 1 of 2 17
Table IB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE lB (continued)
SEMWANNUAL ARBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES. IODINES, AND PARTICULATES QUARTERS 1 AND 2,2005 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLDE UNITS QUARTER QUARTER QUARTER QUARTER
- 4. TRITIUM rH-3 CURIES 5.66E F00 6.99E+00 l 1.04E+00 3.55E-01 l
Page 2 of 2 18 I
0 Table IB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE lB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 3 AND 4,2005 I CONTINUOUS RELEASES BATCH RELEASES I
ITHID F OURTH THIRD IFU lNUCLIDE IUNITS QUARTER I
QQUARTER I QUARTER
- 1. FISSION GASES AR-41 CURIES 2.87E-02 O.OOE+00 1.18E-01 2.05E-02 XE-133 CURIES 2.06E+00 O.OOE+00 2.65E-03 4.16E-04 XE-135 CURIES 6.01E.:01 O.OOE+00 7.60E-05 O.OOE+00 R
CURIS 3.86E+00 0.OOE+00 1.24E+01 2.51E+00 KR-85M CUR1ES 3.22E-02 O.OOE+00 O.OOE+00 0.00+00 KR-B7 CURIES 5.65E-02 0.OOE+00 7.55E-05 0.OOE+00 KR-88 CURIES 7.58E-02 0.OOE+00 O.OOE+00 0.00E+00 XE-135M CURIES 1.31E-01 0.OOE+00 O.OOE+OO O.OOE+00 XE4138 CURIES 7.62E-02 0.00E+00 0.OOE+00 0.OOE+00 XE-131M CURIES O.OOE+00 7.72E-01 1.12E-03 2.55E-02 XE-133M CURIES 9.37E-03 0.OOE+00 0.OOE+00 O.OOE+00 TOTAL FR FERIOD CURIES 6.92E+00 7-72E-01 1.25E+01 2.55E+00
- 2. LODINES X -133 CURIES O.OOE0O0 1.00E+00 2.22-05 1 4.44E-08 1-132 CURIES 0.0E+00 O.OOE+00 1.17E-07 5.1 E7306 1-131 CURIES 0.00E4-00 0.00E+00 3.94E-08 5.81E-08 T
UrAL FRPERID CURIES 0.00-00 0.00E+00 2.24E-OS 2.84E-06
- 3. PARTICULAITS O-99 CURIES 0.00E+00 0.006+00 0.00Q+00 0.003+00 IC-99M CURIES 0.00E00 0.006400 Q.OOE+00 O.W B+00 CS-134 CURIES 0.00E+00 0.00E+00 4.10E-08 0.00E+00 CS-137 CURIES 0.OOE+00 0.1OE+00 0.OOE+00 3.89E-08 CO-60 CURIES 0.OOE+00 0.4OE+0D 8.556-07 3.49E-05 CE-141 CURIES 0.OOE+00 0.00E+0 4.606-08 O.OOE+00 CO-58 CURIES O.OOE+00 O.OOE+00 3.93E-06 1.54E-05 SB-12S CURIES 5.14E-07 4.29E-07 0.00E+C00 0.00E+O CD-1109 CURIES 0.00E+00 1.66E-06 1.04E-06 0.00Q+00 CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 PR-144 CURIES 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 TE-132 CURIES 0.00E+00 0.00+00 O.OOE+00 0.OOE+00 SB-124 CURIES 0.00E+00 0.00+00 2.92E-09 O.OOE+00 CR-51 CURIES 0.00E+00 0.00E+00 1.88E-06 1.65E-06 MN-54 CURIES O.OOE+00 0.00E+00 1.34E-07 2.40E-07 NSg-S CURIES 0.00E+00 0.00E+00 1.74E-06 1.87E-07 I
Page 1 of 2 19
Table lB Semiannual Airborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates TABLE 1B (continued)
SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 3 AND 4,2005 I CONTINUOUS RELEASES I BATCH RELEASES T
D l FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER
- 3. PARTICULATES 2R.-95 l CURIES 0.00E+00 Q.OOE+00 1.21E-06 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 0.00E+00 1.15E-08 ALPHA CURIES 1.98E-07 5.48E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 7.12E-07 2.64E-06 1.09E-05 5.24E-05
- 4. TR-ITUM IH-3 CURIES 8.47E+00
&65E+00 l 7.01-01 2.96E-01 Page 2 of 2 20
Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents TABLE 2A SEMIANNUAL SUMMATION OPLIQUID RELEASES AIL LIQUID EFFLUENTS QUARTERS 1 AN) 2, 2005 O FIRST SECOND EST TOTAL TYPE OF EFFLUENT UlS lQUARTER QUARTER ERROR % (a)
A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOT INCLUDING TRITIUM. GASES, ALPHA]
CURIES 2.53E-03 4.24E-03 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.55E-09 1.555-08
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- 1. IDTAL RELEASE CUIS 3.53E+02 5.14E+02 14
- 2. AVERAGE DILUTED CONCENATION DURING PERIOD UCi/ML 9.16E-04 1.88E-03
- 3. PERCENT OF APPLICABLE LIMIT MA N/A C. DISSOLVED AND ENTRAINED GASEoS
- 1. ITOA REESE CUIES 1 l.SME03 13.80EJ03 27 2L AVERAGE DILUTED CONCENTRATTON DURING EfRMO ftA.
iL3.89E9r 1.3913-08 D. GROSS ALPA RADIOACTIINTY I TTAL RELESE CUR0S 10.W0-M 7.14F-04 29 5WASTE VOLUM RELEASED RE-DION)
GAL 02.935+06 2.13+06 l
0 IF. VOLUME OF DILUTION WATER USED I GAL l9.88E+07 10 (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 1 of I 21
Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents TABLE 2A SEMIANNUAL SLUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4,2005 T THIRD F
FOURTH l EST TOTAL lTYPE OF EFFLUENT UNITS QUARTER l QUARTER l ERROR % (a)
A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE 1NOT INCLUDING TrTIUM, GASES, ALPHA]
CURIES 7.90E-03 4.45E-03 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.01E-08 1.45E-08
- 3. PERCENT OF APPLICABLE LIMIT 9E N/A N/A B. TITIUM TOTAL RELEASE
[CURES 3.94E+02 3.10E+01 14
- 2. AVERGE D3ITE3) 'CONCENTRATIN DURINGPERIOD aCifML 1.00E-03 l.01E-04
- 3. PERCENT OF APLCABLE LDIMT V
/A NIA C. DISSOLVED AND ENTRAINED GASES 12 AVERA(IE DILUTED CONCENTRATIONC DURING PERIOD UCUML 3.18E-08 1.41E-09 D. GROSS ALPHA RADIOACTr[VrY
- 1. TOTAL RELEASE ICURIES 15.97E4 5.75E-04 29 E WASTE VOLU1iffE RELEASED (P-LUTION)
GAL 1 350B+06 12.91E+06 10 F. VOLUME OF DILUTION WATER USED GAL l.008 7.83E+O7 10 (a) Safety Analysis Calculation 87-063-00. January 6, 1988 Page 1 of I
-11
Table 2B Semiannual Liquid Continuous & Batch Releases Totals for Each Nuclide Released TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLJDE RLAE QUARTERS I AND 2,2005 CONTINUOUS RELEASES 1BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER l QUARTER
- 1. ALL NUCLIDES CO-58 CURIES 0.OOE+OO 0.OOE+00 3.49E-04 7.29E-05 CO-60 CURIES O.OOE+O0 Q.OOE+O0 3.02E-04 1.46E-04 CS-134 CURIES 0.OOE+O0 0.OOE+0O 5.07E-05 3.20E-05 CS-137 CURIES O.OOeO0 0.OOE+00 8.62E-05 8.32E-05 H-3 CURIES O.OOE+-OO
.OOE+O0 3.S3E1+02 5.14E+02 NI-63 CURIES O.OOE+00 0.OOE+00 8.OOE-04 8.54E-04 SB-125 CURIES 0.0OE+O0 0.OOE+00 9.17E-04 1.73E-03 SB-124 CURIES O.OOE+00 O.OOE+0O 1.86E-06 O.OOE+O0 CR-51 CURIES 0.OOE+00 0.OOE+OO 1.39E-05 0.OOE+O0 Rtf-103 CURIES 0I.OE+O0 O.00EE+O0 3.44E-06 0.OOE+OO XE-133 CURIES 1.O.500 O.OOE+OO 1.5E-03 3.80E-03 l-I3i CURIBS 0.OOE+130 O.OOE+00 1.36E-06 Q.OOE+OO ALPHA CURIES O.E-E+iO 0..OE+00 O.OOE+O0 7.14E-04 Nl-63 CURIES 0.00E+O0 O.OE-+OO 0.OOE+O0 1.32E-03 ITTALS FOR PERIOD CURIES 0.0E+W0 0.00E+O0 3.53E+02 5.14E+02 Page I of 1
-02
Table 2B Semiannual Liquid Continuous & Batch Releases Totals for Each Nuclide Released TABLE 2B SEM1ANNAL UQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLMDE RLEASED QUARTERS 3 AND 4,2005 CONTINUOUS RELEASES BATCH RELEASES
__ _ _ _D FOURTH THltD FOURTH NUCLIDE UNITS QUARTER QUART j
ART I QUARTER
- 1. ALL NUCLDES CO-58 CURIES 0.O0E+00 O.OOE+00 2.41E-04 2.63E-03 CO-60 CURIES
.OOE+00 0.OOE+00 4.17E-04 2.58E-04 CS-134 CURIES 0.OOE+00 0.OOE+00 5.60E-05 2.04E-04 CS-137 CURIES 0.OOE+00 0.OOE+OO 1.70E-04 2.40E-04 H-3 CURIES 0.OOE+00 0.OOE+00 3.94E+02 3.1DE+01 NI-63 CURIES O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 SB-125 CURIES
.OOE+00 0.OOE-iE00 4.57E-03 6A1E-04 SB-124 CURIES 0.OOE+00 O.OOE+00 O.OOE+00 1.33E-05 CR-51 CURIES 0.OOE+00 O.OOE+00 0.OOE+00 5.21E-05 RU-103 CURIES 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE;+00 XE-133 CURIES 0.OOE+00 0.OOE+00 1.18E-02 4.32E-04 1-131 CURIES 0.OOE+00 0.OOEe-00 1.05E-04 0.OOE+OO ALPHA CURIES O.OOE+OO
.OOE+00 5.97E-04 5.75E-04 NI-63 CURIES 0.OE+O0 0.OOE+OO 2.23E-03 2.53E-04 TE-129 CURIES 0.OOE+00 0.00E#00 4.52E-05 0.OOE+00 XE131M CURIES O.OOE+00 0.OOE+00 9.8 lE-05 0.OOE+00 KR-R5 CURIES 0.OOE-+O0 O.OOE+O0 4.83E-04 0.OOE+00 XE 133M CURIES 0.OOE+0 0.OOE+00 8.16E-05 0.OOE+00 MN-54 CURIES O.OOE+00 O1.OOE+O0 5.94E-06 0.00E+OO MO-99 CURIES
.OOOE
.OOE+00 2.93E-05 0.OOE+00 TC-99M CURIES 0.0OE+00 0.00E+O00 2.93E-05 O.OOE+00 CO-57 CURIES 0.OOE+O0 0.OE+00 3.69E-06 OOOE+O0 XE-135 CURIES
.DOE+MF 0.OOE+00 3.22E-06 1.77E-06 AM-241 CURIES 0.00W3O0 O.OOE+00 2.35E-07 1.98E-05 NP-237 CURIES O.Ol)E+'0 0.OOE+OO 4.58E-08 3.85E-06 E-127 CURIES 0.OE+00 0.OOE+00 0.OOE+0O 1.36-04 TOTALS FOR ERNOD CURtS 0ooeo
.+00 3.94E+02
- 3. 1OE+01 Pagc 1 of I 24
Table 3 Solid Waste & Irradiated Fuel Shipments 2005 V
A. SOLID WASTE BURIED (DOES NOT INCLUDE IRRAI
- 1. TYPE OF WASTE
- a. Spent resins, filter sludges evaporator bottoms, etc.
- b. Dry compressible waste, contaminated equipment, etc.
- c. Irradiated components, control rods, etc.
- d. Other (describe)
UNITS rn3 Ci m3 Ci
)IATED FUEL)
PERIOD PERIOD EST.TOTAL i
JAN - JUN JUL-DEC 1.69 0
17.78 0
38.08 6.27 6.50 0.51 0
0 0
0 0
0 0
0 ERROR (/o)
+/-25%
Ci
+/-25%
125%
Ci
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Type of Waste)
PERIOD JAN - JUN PERIOD JUL - DEC Nuclide
- a.
Fe-55 Co-58 Ni-63 Co-60 Cs-137 Nb-95 Cs-134 Zr-95 Cr-51 Mn-54 Sb-125
% Abundance 25.70 21.71 16.01 8.40 6.87 6.12 5.27 4.64 1.90 1.61 1.03 Curies 4.57 3.86 2.85 1.49 1.22 1.09 0.94 0.82 0.34 0.29 0.18
% Abundance NA NA NA NA NA NA NA NA NA NA NA Curies NA NA NA NA NA NA NA NA NA NA NA Page 1 of 2 25
Table 3 Solid Waste & Irradiated Fuel Shipments 2005 PERIOD JAN - JUN PERIOD JUL - DEC Nuclide
- b.
Fe-55 Co-58 Cs-137 Ni-63 Co-60 Nb-95 Mn-54 Cs-134 Zr-95 Sb-125 Sn-1 13
% Abundance 34.98 16.38 13.03 12.26 7.77 4.51 3.85 3.77 -
2.30 0.42 0.31 Curies 2.27 1.07 0.85 0.80 0.51 0.29 0.25 0.25 0.15 0.03 0.02
% Abundance 34.98 16.38 13.03 12.26 7.77 4.51 3.85 3.77 2.30 0.42 0.31 Curies 0.178 0.084 0.066 0.063 0.040 0.023 0.020 0.019 0.012 0.002 0.002
- 3. SOLID WASTE DISPOSITION:
Number of Shipments 18*
1*
1*
1*
Mode of Transportation Truck Cask Cask Cask Destination Duratek Duratek Studsvik Studsvik Class of Solid Waste Shipped Type of Container A
LSA B
LSA A
LSA B
- Sent to waste processors for volume reduction before burial.
- 4. SOLIDIFICATION AGENT:
None used.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments 0
Mode of Transportation Destination Page2of2 z"
Table 4 Meteorological Data
-- %Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:09.02 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 IVALUES UITrS
% GOOD DATA Stability Class A-G E
93%
Total Precipitation CM.
7.40E-01 99%
10 Meter Level:
Wind Speed Meter/Sec 2.80E-00 100%
Wind Direction Degrees 2.14E+02 100%
Wind Direction Variability Degrees 1.42E+01 100%
Reference Temperature Degrees C 1.33E+01 100%
Dewpoint Degrees C 6.83E-+00 100%
60 Meter Level:
Wind Speed Meter/Sec 4.99E-+00 100%
Wind Direction Degrees 2.20E-02 100%
Wind Direction Variability Degrees 9.04E+00 99%
Dewpoint Degrees C NONE 0%
Temperature Difference 60 - 10 Degrees C 1.01E-02 93%
Page 1 of 1 27
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report DateiTime: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: A Wind Speed at 10.00 Meter Level (MPH)
I I
V I
1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
3 31 24 3
0 0
61 NNE 9
41 6
3 0
0 59 NE 6
38 11 0
0 0
55 ENE 16 40 4
0 0
0 60 E
9 27 16 2
0 0
54 ESE II 39 14 1
0 0
65 SE 22 101 17 0
0 0
140 SSE 17 i2 48 7
0 0
194 S
23 91 76 21 0
0 211 SSW 16 90 58 5
1 0
170 SW 20 88 72 3
3 0
186 WSW 12 26 21 1
0 0
60 W
8 44 29 6
0 0
87 2
35 44 13 0
0 94 NW 4
25 53 8
3 0
93 NNW 5
25 31 10 0
0 71 TOT 1_3 863 524 83 7
0 1660 D
Rours of Calm Data:
Hours of Invalid Data:
I 0
Page 1 of 7
-..,M
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 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
1 17 13 0
0 0
31 NNE 4
13 11 0
0 0
28 NE 4
14 2
0 0
0 20 ENE 4
16 5
0 0
0 25 E
1 4
7 1
0 0
13 ES 4
10 4
0 0
0 18 SE 4
t0 2
0 0
0 16 SSE 4
13 11 I
0 0
29 S
I 11 10 2
0 0
24 5SW 4
9 5
0 0
0 18 SW 4
8 6
2 0
0 20 WSW 1
14 1
1 0
0 17 W
I 13 7
0 0
21 3
21 a
5 0
0 37 NW 1
20 18 2
0 0
41 NNW 2
7 9
2 0
0 20 TOT 43 200 119 16 0
0 378 Howt of Calm Data:
Hours of Invalid Data:
0 Page 2 of 7 zu
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Eleotiic - Callaway Plant Report Date/Time: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: C Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
4 14 3
3 0
0 24 NNE 4
12 5
0 0
0 21 NE 8
16 2
0 0
0 26 ENE 4
12 5
0 0
0 21 E
0 4
10 1
0 0
15 ESE i
7 11 0
0 0
19 SE 2
14 12 0
0 0
28 SSE I
12 15 0
0 0
28 S
2 13 8
3 0
0 26 SSW 0
7 7
0 0
0 14 SW 9
9 0
1 0
21 W
5 10t 3
1 0
0 19 W
2 a
Is 2
0 0
27 WN 4
12 19 3
0 0
38 NW 3
11 19 2
1 0
36 NNW 3
12 17 4
0 0
36 TOT 45 173 160 19 2
0 399 Hours of Calm Data:
Hours of Invalid Data:
1 0
Page 3 of 7 30
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 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
22 140 104 15 1
0 282 NNE 31 155 36 2
0 0
224 NE 40 127 18 0
0 0
185 ENE 27 90 27 1
0 0
145 E
23 66 42 7
0 0
138 ESE 16 48 42 0
0 0
106 SE 15 57 81 2
0 0
155 SSE 10 69 50 6
0 0
135 S
12 25 23 8
0 0
68 SSW 6
27 21 4
0 0
58 SW 11 33 14 15 1
0 74
__W 11 28 11 10 4
0 64 W
13 25 83 14 0
0 135 19 46 71 13 1
0 150 NW 29 76 69 16 2
1 192 NNW 40 137 142 17 0
0 336 TOT
- 325 1149 834 130 9
0 2447 Hours of Calm Data:
Hours of Invalid Data:
22 0
Page 4 of 7 31
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report DatelTime: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 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
23 53 2
0 0
0 78 NNE 37 41 6
O O
O 84 NE 36 22 O
O O
O 58 ENE 35 38 4
O77 O
O 7
E 2t 43 0
71 ESE 20 44 4
0 1
O 69 SE 24 i19 4
O O
191 SSE 33 158 74 5
0 O
270 S
22
[IT 77 8
O_
224 SSW 32 56 32 2
O O
122 SW 9
1.3 0
0 O
71 WSW 32 13
-_O0 95 32 65 21 O
t I
0 118 42 68 I
0 0
0 121 NW 58 84 21 1
0 0
164 NNW 24 65 23 1
0 0
113 TOT 490 1062 356 17 1
0 1926 Hours of Calm Data:
Hours of Invalid Data:
38 0
Page 5 of 7
--t J#
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report DateTimne: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: F Wind Speed at 10.00 Meter Level (MPH)
I I-I 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
20 19 0
0 0
0 39 NNE 38 17 0
0 0
0 55 NE 24 5
0 0
0 0
29 ENE 17 2
0 0
0 0
19 B
20 6
0 0
0 0
26 ESE 29 7
0 0
0 0
36 SE 56 79 7
0 0
0 142 SSE 61 220 11 0
0 0
292 S
36 97 20 0
0 0
153 SSW 26 43 1
0 0
0 70 SW 37 40 0
0 0
0 77 WSW 34 14 1
0 0
0 49 W
39 15 0
0 0
0 54 W
34 15 0
0 0
0 49 NW 42 25 0
0 0
0 67 NNW 19 21 0
0 0
0 40 TOT 532 625 40 0
0 0
1197 Hours of Calm Data Hours of Invalid Data:
68 0
Page 6 of 7
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:10.56 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: G Wind Speed at 10.00 Meter Level (MPH)
I I
1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
49 5
0 0
0 0
54 NNE 30 1
0 0
0 0
31 NE 22 0
0 0
0 0
22 ENE 8
0 0
0 0
0 8
E 4
0 0
0 0
0 4
ESE 15 0
0 0
0 0
15 SE 19 14 3
0 0
0 36 SSE 56 85 3
0 0
0 144 S
17 13 0
0 030 SSW 35 it 0
0 0
O 46 SW 24 12 0
0 0
0 36 WSW 10 2
0 0
0 0
12 W
9 0
0 0
0 9
1WNW 5
2 0
0 0
O 17 NW 15 4
0 0
0 19 NNW 28 6
0 0
0 O
34 TOT 356 155 6
0 0
O 517 Hours of Calm Data:
Hours of Invalid Data:
Hours of Good Data:
95 0
8749 = 99.9% of Total Hours Page 7 of 7 34
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report DateJTime: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: A I _Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 19 28 5
0 0
54 NNE 3
29 14 6
0 0
52 NE 5
32 22 0
0 0
59 ENE 5
48 8
1 0
0 62 E
3 19 17 5
1 0
45 ESE 4
25 31 1
1 0
62 SE 7
78 49 1
0 0
135 SSE 4
78 75 15 7
0 179 S
7 53 89 53 13 0
215 SSW 3
53 71 32 5
3 167 SW 13 42 87 54 5
4 205 WSW 4
15 24 15 3
0 61 W
2 21 37 11 14 0
8s I
10 36 47 12 4
110 NW 2
21 25 32 14 4
98 NNW 2
20 21 15 9
1 68 TOT 67 563 634 293 84 16 1657 Hours of Calm Data:
Hours of Invalid Data:
0 4
Page 1 of 7 "10
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: B Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 9
18 2
0 0
30 NNE 2
12 6
7 0
0 27 NE 2
10 5
0 0
0 17 ENE 1
I5 9
1 0
0 26 E
0 4
8 2
0 0
14 ESE 1
6 8
0 0
0 15 SE I
7 3
1 0
0 12 SSE I
13 10 6
1 0
31 S
0 5
7 9
1 0
22 SSW 1
7 5
5 2
0 20 SW.
2 7
8 4
1 0
22 WSW 1
5 9
3 1
0 19 W
0 2
14 3
0 0
19 WNW 1
9 16 11 5
1 43 NW 1
7 18 7
6 J
40 NNW 1
3 9
5 1
0 19 TOT 16 121 1
153 66 18 2
376 Hours of Calm Data:
Hours of Invalid Data:
1 1
Page 2 of 7 36
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant ReportDate/Time: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction
. 1-JAN-2005 00:00:00.00 to 31-DEC-2005 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
1 8
7 1
2 0
19 NNE 2
7 10 1
0 0
20 NE 3
13 10 0
0 0
26 ENE 3
6 11 1
0 0
21 E
0 3
8 1
1 0
13 ESE 0
1 21_0 0
22 SE 1
4 15 5
0 0
25 SSE 0
4 17 7
0 0 28 S
0 7
10 6
3 0
26 SSW 1
2 8
6 0
0 17 SW 0
4 1
7 1
1 21 WSW 3
2
_9 i_4 1
0 19 W
3 6
5 5
7 2
28 WN6 12 12 2
41 NW 0
3 11 19 5
1 39 NNW 2
8 0
31 TOT 21 84 176 80 29 6
396 Hours of Calm Data:
Hours of Invalid Data:
0 4
Page 3 of 7
'IJ,-
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report DateTime: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: D I
-Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
5 49 117 62 7
1 241 NNE 4
73 119 20 1
0 217 NE 15 105 69 7
0 0
196 ENE 8
31 90 19 1
0 149 E
8 29 80 20 6
0 143 ESE 4
24 70 17 0
0 115 SE 1
1i 55 64 2
0 140 SSE 4
21 66 45 7
0 143 S
3 6
25 22 7
1 64 SSW 3
9 26 22 5
1 66 SW 6
12 28 18 7
12 83 WSW 2
11 19 13 10 7
62 W
I 14 12 68 21 6
121 7
17 29 65 27 7
152 NW 2
28 77 73 27 7
214 NNW 11 75 145 105 17 2
355 TOT 83 522 1027 640 145 44 2461 Hours of Calm Data:
Hours of Invalid Data:
2 6
Page 4 of 7
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 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
>24 TOTAL N
3 14 44 5
0 0
66 NNE 2
12 43 17 0
0 74 NE 3
23 37 1
0 0
64 ENE 3
20 49 11 1
0 84 E
3 15 68 14 0
0 100 ESE 2
9 56 10 0
1 78 SE 3
13 88 76 2
0 182 SSE 0
12 97 108 8
1 226 S
4 9
79 96 13 0
201 SSW 2
Is 55 85 10 0
170 SW 2
17 43 36 5
0 103 WSW 1
18 35 22 1
0 77 W
4 is 42 65 4
0 130 4
14 50 44 0
0 112 NW 3
22 87 53 2
0 167 NNW 0
21 66 40 2
0 129 TOT 39 252 939 683 48 2
1963 Hours of Calm Data:
Hours of Invalid Data:
0 1
Page 5 of 7
_q
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 23:59:59.00 Stability Class: F I
Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL
-
4 I
4 I
I N
0 7
23 7
0 0
37 NNE 2
3 26 13 0
0 44 NE 2
13 36 3
0 0
54 ENE 2
10 17 3
0 0
32 E
3 7
29 5
0 0
44 ESE 1
10 40 5
0 0
56 SE 1
9 74 25 0
0 109 SSE 0
15 104 74 0
0 193 S
0 14 111 51 I
0 177 SSW 0
13 666 81 0
0 160 SW 0
9 31 37 2
0 79 WSW 3
16 20 1.1 1
0 51 W
4 16 32 14
- 0 0
66 0
20 23 17 0
0 60 NW 1
16 23 9
0 0
49 NNW 0
7 25 18 0
0 50 TOT 19 185 680 373 4
0 1261 Hours of Calm Data:
Hours of Invalid Data:
2 2
Page 6 of 7 4a
Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 19-APR-2006 16:41:11.95 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2005 00:00:00.00 to 31-DEC-2005 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
0 3
8 6
0 0
17 NNE 1
7 15 4
0 0
27 NB 1
13 30 4
0 0
48 ENE 2
9 34 7
0 0
52 E
2 11 19 3
0 0
35 ESE 3
8 14 1
0 0
26 SE 0
9 15 5
0 0
29 SSE 0
11 30 21 3
0 65 S
2 12 53 11 0
0 78 SSW 0
4 41 18 0
0 63 SW 1
12 23 1I 2
10 56 WSW 0
12 20 13 0
0 45 W
1 9
10 3
0 0
23 WNW 2
6 12 3
0 0
23 NW 1
1 10 1
0 0
13 NNW 0
1 5
3 0
0 9
TOT 16 128 339 121 5
0 609 Hours of Calm Data:
Hours of Invalid Data:
Hours of Good Data:
3 0
8731 = 99.7% of Total Hours Page 7 of 7 41
Table 5 Dose at the Site Boundry and to the Nearest Resident From Gaseous Effluents TABLE 5 DOSE AT THE SITE BOUNDARY AND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS SITE BOUNDARY NEAREST RESIDENT LOCATION: 2.20 kan NNW LOCATION: 2.90 km NNW AGE GROUP: CHILD AGE GROUP: CHILD ORGAN-UNITS DOSE
% LIMIT(a)
DOSE
%LIMIT(b)
- 1. GAMMA AIR DOSE
- MRAD 1.21E-03 0.01 7.98E-04 N/A
- 2. BETA AIR DOSE
- MRAD 2.57E-03 0.01 1.69E-03 N/A
- 3. WHOLE BODY ***
MREM 1.36E-03 N/A 8.90E-04 N/A
- 4. SKcIN ***
MREM 3.32E-03 N/A 2.18E-03 N/A
- 5. BONE *'
MREM 2.14E-04 N/A 2.96E-04 0.00
- 6. LIVER **
MREM 1.36E-03 N/A 6.96E-03 0.05
- 7. TOTAL BODY **
MREM 1.35E-03 N/A 6.80E-03 0.05
- 8. THIYROID **
MREM 1.36E-03 N/A 6.79E-03 0.05
- 9. KDNEY
- MREM 1.35E-03 N/A 6.82E-03 0.05
- 10. LUNG
- MREM 1.371-03 N/A 6.79E-03 0.05
- 11. GtI-LLI**
0EM 1.35E-03 N/A 6.78E03 0.05
- Dose from Noble Gases only 0- Dose from Tritium, Radioiodines. and Particulabts only
- Dos fiom Noble Gases plus Ground Plane dose (a) Annual dose linits of Offfite Dose Calculation Manual (APA-2Z-01003) of 10 mrad garnma air dose and 20 mrad beta air dose.
(b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 15 rnrem to any organ from 1-131, 1-133, H-3 and particulate radionuclides with hatflives greater than 8 days.
I Page 1 of 1 AL-,If
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 DOSE WITHIN THE SITE ORGAN UNITS BOUNDARY DIRECT RADIATION FROM THE UNI DIRECT RADIATION FROM OUTSIDE TANKS DIRECT RADIATION FROM RAM
-STORAGE EFFLUENT DOSE FROM CLGTWR TOTAL DOSE FOR THE ffm SKIN mrem BONE mrem LIVER mrem D
TOTAL BODY(mrem)
THYROID mrem KIDNEY mrem LUNG mrem GI-LLI mrem 6.91 E-04 5.85E-05 3.67E-04 6.22E-04 3.67E-04 3.67E-04 3.70E-04 3.67E-04 N/A 8.79E-03 8.79E-03 8.79E-03 8.79E-03 8.79E-03 8.79E-03 8.79E-03 N/A 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 N/A 5.99E-03 5.99E-03 5.99E-03 5.99E-03 5.99E-03 5.99E-03 5.99E-03 N/A N/A 1.95E-03 1.95E-03 1.95E-03 1.95E-03 1.95E-03 1.95E-03 6.91 E-04 1.48E-02 1.71 E-02 1.74E-02 1.71 E-02 1.71 E-02 1.71 E-02 1.71 E-02
- Direct Rdiation dose from Stores II, OSGSF, Modification 03-1008 (Equipment Hatch Plafform and Missile Shield Modifica-tion), and from the RW storage area.
,&&a
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) v SORGAN SKIN BONE LIVER TOTAL BODY THYROID D
KIDNEY LUNG LIVER UNITS mrem mrem mrem mrem mrem mrem mrem mrem EFFLUENT DOSE AT RESIDENCE LOCATION 2.04E-03 1.76E-04 4.24E-03 4.98E-03 4.18E-03 4.19E-03 4.18E-03 4 20E-03 DOSE FROM ACTIVITIES IN SITE BOUNDARY 6.91 E-04 1.48E-02 1.71 E-02 1.74E-02 1.71 E-02 1.71 E-02 1.71 E-02 1.71 E-02 DOSE FROM CLG TWR H-3 AT NEAREST RESIDENCE N/A N/A 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 TOTAL DOSE TO THE MEMBER OF THE PUBLIC 2.73E-03 1.50E-02 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03 1.33E-03
% LIMITS
- 0.01%
0.06%
0.01%
0.01%
0.00%
0.01%
0.01%
0.01%
- Annual dose limits from 40 CFR 190.10(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.
44
Table 8 Dose Due to Liquid Effluents (Member of the Public)
TABLE 8 Dose Due To Liquid Effluents (Member of the Public) 2005 ORGAN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI UNITS DOSE LIMIT
- mrem 3.99E-03 10 mrem 6.87E-03 10 mrem 5.62E-03 3
mrem 2.42E-03 10 mrem 3.82E-03 10 mrem 2.84E-03 10 mrem 2.56E-03 10
% LIMIT 0.04%
0.07%
0.19%
0.02%
0.04%
0.03%
0.03%
F 445