ULNRC-04990, Annual Environmental Operating Report

Annual Environmental Operating Report

ML041330469
Person / Time
Site:	Callaway
Issue date:	04/27/2004
From:	Keith Young AmerenUE, Union Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-04990
Download: ML041330469 (46)

Text

Union Electric One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166-6149 314.621.3222 April 27, 2004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop PI1-137 Washington, DC 20555-0001 W~Amereil(IF Ladies and Gentlemen:

ULNRC-04990 DOCKE T NUMBER 50-483 CALLAWAY PLANT UNIT I UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 2003 ANNUAL ENVIRONMENTAL OPERATING REPORT Please find enclosed the 2003 Annual Environmental Operating Report for the Callaway Plant. This report is submitted in accordance with Section 5.6.2 of the Technical Specification and Appendix B to the Callaway Plant Operating License.

Very truly yours, Keith D. Young Manager, Regulatory Affairs DJW/jdg Enclosure a subsidiary ofAmeren Corporation

ULNRC-04990 April 27, 2004 Page 2 cc: U. S. Nuclear Regulatory Commission (Original and I copy)

Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)

Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102 Mr. Gerhard K. Samide ANI Account Engineer Town Center, Suite 3005 29 S. Main St.

West Hartford, CT 06107-2445 Regional Administrator Department of Natural Resources Central Regional Office P.O. Box 176 J efferson City, MO 65102-0176

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2003 Callaway Plant Radioactive Effluent Release Report wameren UF Docket In. 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

.9 6.3 Major Changes to Radwaste Treatment Systems

.9 6.4 Land Use Census Changes.10 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 7.0 Meteorological Data.11 8.0 Assessment of Doses.12 8.1 Dose at the Site Boundary from Gaseous Effluents.12 8.2 Dose to the Member of the Public.12 8.3 Total Dose Due to the Uranium Fuel Cycle.13 8.4 Dose Due to Liquid Effluents.13 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 2003.

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 from the Callaway Plant during the period from January 1, 2003 to December 31, 2003 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.

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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/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:

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/yr to 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 (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.

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. Composite samples were analyzed for Sr-89, Sr-90, Fe-55, and transuranic 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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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 ofbatch releases:

Total time period for batch releases:

Maximum time period for batch releases:

Average time period for batch releases:

Minimum time period forbatch releases:

Average Missouri River flow during periods of effluent release to the river1 :

Minutes Minutes Minutes Minutes ftl/sec JAN-JUN 76 34,684 624 456 405 47,970 JUL-DEC 68 32,336 1962 476 296 45,571 GASEOUS UNITS Number ofbatch 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 30 19,288 7,243 643 22 JUL - DEC 29 6,826 3,737 235 35

' E-mail, S. Ternes, United States Department of the Interior -Geological Survey-Water Resources Division dated January 13, 2004 2.5 Abnormal Releases LIQUID Number of releases: 0 Total Activity released: 0 GASEOUS Number of releases: I Total Activity released: 1.31 e-02 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 I A and 1 B. During 2003, 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 2003, there was no continuous release of liquid effluent from the plant.

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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 for waste 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 In 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.

formation 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 On April 10, 1998, during a refueling outage, radioactivity was detected in the Auxiliary Boiler feed water system. The boilerwas flushed 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 mispositioned 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 higherthan 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 current safety evaluation forthe Aux. Boiler was evaluated in early 2004. During the review, it was determined that several radionuclides were not included in the safety evaluation. A revision to the safety evaluation is being evaluated at this time (CAR 200400644). Despite having radionuclides present in the Auxiliary Boiler that were not listed in the current evaluation, it is still concluded that releases from the Auxiliary Boiler are well below regulatory limits.

The Auxiliary Boiler was operated intermittently during 2003. The maximum total body dose to a 7

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6.0 Related Information Member of the Public from these releases was 3.72 E-05 mrem during 2003. This is negligible compared to the quarterly and annual effluent control limits. The activity released from the Auxiliary Boiler during 2003 is included in Tables 1A, 1B, 5, 6 and 7.

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6.0 Related Information 6.2 Changes to the Offsite Dose Calculation Manual Changes were made to the Callaway Offsite Dose Calculation Manual (ODCM - Callaway plant procedureAPA-ZZ-01 003) and the Final Safety Analysis Report -Standard Plant (FSAR

- SP) Chapter 16.11 (Offsite Dose Calculation Manual - Radiological Effluent Controls) in 2003. The ODCM was revised on June 17th to add a liquid Ingestion Dose Commitment factor for Pr-144 (CAR 200303251).

In addition, the Farmer's residence ( Critical Receptor) was also updated to a location directly across the street from the Nearest Resident. For conservatism and ease in calculation, Table 6.1 and 6.2 were revised making the distances and dispersion parameters for the Critical Receptor and the Nearest Resident the same.

The ODCM was also revised by removing QA Dept. review requirements for all changes to the ODCM (CAR 200304509).

Callaway RFR 22046 Revision A allowed the addition of depleted or natural soluble zinc to the Callaway primary system to reduce radiation fields in out-of-core piping and components. As a result of zinc addition to the RCS, increased production of Zn -65 required revision of the Callaway REMP program (CAR 200303604). FSAR Change Notice 03 - 020 revised FSAR Tables 16.11-8/9 by adding lower limits of detection and reporting levels for Zn-65 as perthe NRC Radiological Assessment Branch Technical Position, Rev 1, November 1979, "An Acceptable Radiological Environmental Monitoring Program".

FSAR - SP CN 03-045/046 revised the requirements listed in FSAR - SP Table 16.11-5 "Radioactive Gaseous Effluent Monitoring Instrumentation" by clarifying required actions when the Minimum Channels Operable requirement for Containment Purge System Noble Gas Activity Monitors are not met during COREALTERATIONS or movement of irradiated fuel within the containment (CAR 200305729).

FSAR - SP CN 03-050 revised section 16.11.1.3 and Tables 16.11-2 and 16.11-3 to allow either the cooling tower blowdown flow or bypass flow instrumentation to be used for dilution flow indication, instead of requiring that both instruments be operable for combined flow measurement (as long as dilution path used is for operable instrument).

This change was approved on 1/1 4/04 and in response to problems experienced in 2003 with the cooling tower blowdown flow transmitter FEDB1101 (CAR 200306808).

The problems with Cooling Tower Blowdown flow transmitter FEDB1101 are described in section 6.5 of this report under Inoperablity of Effluent Monitor Instrumentation.

Major Changes to Radwaste Systems During 2003, there were two major plant modifications to Radwaste systems:

1. Design Modification 01 -1001 installed the Duratek -Advanced Liquid Processing System (ALPS) capable of processing fluid from floor drains, equipment drains, and RCS letdown.

This modification replaces the temporary filtration skid, i.e. Nukem Skid, which utilized a modular design and included ultra-filtration membranes followed by demineralizers.

Design Modification 01-1 001 also removed a significant portion of Radwaste Volume Reduction (RVR) system to accomodate installation of the new ALPS system. The RVR system was used to process evaporator bottoms and is no longer needed due to the pending retirement of the evaporators. ALPS operation began on January 12,2004.

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6.0 Related Information

2. Design Modification 98-1032 replaced antiquated H}O2 analyzers with Orbisphere model 3636 analyzer systems. The previous H) 02 analyzers were obsolete, thus spare parts were not readily available. The new Orbisphere analyzers will perform the same function as the existing analyzers.

The following minor modification was made to the gaseous radwaste system during 2003.

Modification Package 99 - 2003 removed the drum labeling and inspection station from service.

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 During 2003 all effluent monitoring instrumentation was OPERABLE within the limits specified in Radioactive Effluent Controls 16.11.1.3 and 16.11.2.4 with one exception being the Cooling Tower Blowdown flow transmitter FEDB1101.

CAR 200306808 was written on 8/23/03 by the Shift Engineer requesting a Operability Determination after FEDBII01 was declared inoperable. Radiological Effluent Controls 16.11.1.3 allows liquid effluent discharges to continue for up to 30 days provided that flow rates are estimated every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during discharge. Liquid effluent discharges continued based on the development of a graph which allowed operators to measure Cooling Tower Blowdown flow based on valve position.

An investigation of the blowdown flow transmitter condition indicated power supply failure, poor cable connections, transducer housing leakage in the pipe spool, as well as drastic corrosion. The cause was determined to be from age and environmental conditions.

Part unavailability caused repairs to exceed 30 days. Additional maintenance, replacement of the spoolpiece and/or transducer, is scheduled during Refuel 13.

It is important to note that although Callaway Plant did not meet the full operability requirements of the FSAR for this equipment, dilution flow was always positively monitored with installed instrumentation (Bypass flow transmitter) during liquid effluent releases As mentioned in Section 6.3, FSAR - SP CN 03 -050 revised the liquid effluent dilution flow indication operability requirements.

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.

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7.0 Meteorological Data The on-site meteorological data for 2003 is presented in Table 4. All meteorological data was reviewed, analyzed, and validated by a boundary layer meteorologist.

The data is 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 2003 was 90% or greaterforall required parameters. During January and February 2003, the Primary METtower 1Oim wind direction data was offset when the crossarm adaptor collar for the anemometerwas inadvertantly rotated on the crossarm following calibrations in late 2002. The problem was discovered when a distinct offset was observed in the data from the primary 10 m wind direction when compared to the other 3 directional channels (CAR 200300533). Discriminatory differential analysis, using all directional data obtained during well-mixed daytime periods of neutral stability, confirmed the offset to be a constant value of approximately 46 degrees. The primary 1 Om wind direction data was subsequently corrected before dispersion calculations were performed.

The precipitation gauge did not operate prop-Pictured is the Secondary Meteological erly for several months during 2003. Auxiliary Tower. This station obtains measurements at a hourly precipitation data was acquired from the height of 10 meters, and provides backup data Prairie Fork Conservation area to aid in data for the Primary Meteological Tower readings at assessments during these periods.

10, 60 and 90 meters.

Other problems with the 2003 data were inter-mittent, of limited duration, or affected secondary 90 m data levels. These included a continued (but decreased) problem with upper level wind speed data, most likely affected by large birds perching on the anemometers (similar bird problems were encountered in 2001 and 2002 - CARs 200105528 and 200205532), precipitation events which affected the 60 m input data to the 60 - 10 m delta -temperature, as well as some drift ob-served in dew point data. All affected data was either invalidated or corrected at the 15 minute level before inclusion in the hourly averages for dispersion and dose modeling.

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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 all airborne effluents released from the Callaway Plant during 2003, 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 2.5%

of the Radiological Effluent Control Limits presented in Section 2.1 of this report. Liquid radwaste processing equipment performance problems and fuel defects contributed to increased cesium concentrations in liquid effluent and subsequent higherTotal Body dose (CAR 200309297). CARs 200400200 and 200401501 were written in an effort to to reduce liquid effluent dose.

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 2003 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 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 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 2003 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, 12

8.0 Assessment of Doses Continued 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.

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. Itwas conservatively assumed 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 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 that the hypothetical maximum exposed individual obtained his entire annual fish intake from near the plant discharge.

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Table 1A Semiannual Summation of Gaseous Releases All Airborne Effluents TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS I AND 2 2003 I

I T FIRST 1 SECOND I EST TOTAL TYPE OF EFFLUENT I UNITS I QUARTER QUARTER I ERROR% (a) I A. FISSION AND ACTIVATION GASES 1.TOTAL RELEASE CURIES 2.60E+01 1.13E+00 20

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.35E+00 1.44E-01

3. PERCENT OF TECH SPEC LIMIT N/A N/A B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 1.63E-06 0.OOE+00 23

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.10-07 0.00E+00

3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES

1. PARTICULATE (HALF-LIVES > 8 DAYS)

CURIES 8.72E-05 2.22E-05 30

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.12E-05 2.82E-06

3. PERCENT OF TECH SPEC LIMIT N/A N/A

4. GROSS ALPHA RADIOACTIVITY CURIES 1.83E-07 2.28E-07 D. TRITIUM l.TOTAL RELEASE CURIES l1.16E+01 14.44E+01 l

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12. AVERAGE RELEASE RATE FOR PERIOD I uCi/SEC I 1.49E+300 I 1.84E+00 I

13. PERCENT OF TECH SPEC LIMIT I %

I N/A I N/A I

(a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page I of 1 14

Table IA Semiannual Summation of Gaseous Releases All Airborne Effluents Continued TABLE IA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 3 AND 4.2003 THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION GASES 1.TOTAL RELEASE CURIES S.08E+00 1.68E+01 20

2. AVERAGE RELEASE RATE FOR PERIOD UCV/SEC 6.39E-01 2.12E+00

3. PERCENT OF TECH SPEC LIMIT l %

N/A j N/A B. RADIOIODINES I.TOTALIODINE-131 CURIES l 0.OOE+00 4.47E-07 23

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC l 0.OOE+00 5.62E-08

3. PERCENT OF TECH SPEC LIMIT l

l N/A l_N/A J

C. PARTICULATES I.PARTICULATE (HALF-LIVES > 8 DAYS)

CURIES 5.13E-07 1.28E-05 30

2. AVERAGE RELEASE RATE FOR PERIOD uCVSEC l 6.45E-08 1.6IE-06 j

3. PERCENT OF TECH SPEC LIMIT l

l N/A N/A

4. GROSS ALPHA RADIOACTIVITY CURIES l 7.89E-0S 1.69E-07 J

D. TRITIUM

1. TOTAL RELEASE CURIES 1.24E+01 1.08E+01 14

12. AVERAGE RELEASE RATE FOR PERIOD I UCi/SEC I 1.56E+00 I 1.36E+00 I

3. PERCENT OF TECH SPEC LIMIT N/A N/A (a) Safety Analysis Calculation 87-063-00. January 6, 1988 Page I of I 15-

Table 1B 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 I AND 2.2003 I CONTINUOUS RELEASES I

BATCH RELEASES I

1 FIRST SECOND FIRST SECOND lNUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER I. FISSION GASES AR-41 CURIES 0.00E+00 0.00E+00 2.11 E-01 5.58E-02 XE-133 CURIES 1.04E+01 1.0613+00 IA.I-E+01 1.47E-02 XE-135 CURIES 3.03E-01 0.00E+00 2.55E-02 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 2.07E-01 0.00E+00 XE-133M CURIES 4.01E-01 0.001E+00 1.15E-01 1.971E-09 XE-138 CURIES 1.5913-01 0.00E+00 1.44E-04 0.00E+ 00 XE-135M CURIES 0.0013+00 0.00E+00 2.2013-04 0.00E+00 KR-85M CURIES 0.0013+00 0.0013+00 9.5313-05 0.OOE:00 KR-85 CURIES 0.00E+00 0.OOE+00 1.1513-01 0.OOE+00 TOTAL FOR PERIOD CURIES 1.1313+01 1.06E+00 1.48E+01 7.0513-02

2. IODINES 1-131 CURIES 6.26E-08 0.0013+00 1.57E-06 l 0.00E+00 TOTAL FOR PERIOD CURIES 6.26E3-0S 0.00E+00 l1157E3-06 l.0E0

3. PARTICULATES SB-125 CURIES 3.90106 4.01E-06 0.00E+00 0.00E+00 CO-60 CURIES 3.30E-07 5.79E-07 8.08E-05 1.67E-05 CS-137 CURIES 7.95E-07 7.54E-07 3.7013-07 1.52E-07 CO-57 CURIES 5.1213-08 0.0013+00 0.00E+00 0.003E+00 CE-144 CURIES 0.0013+00 0.00E+00 1.4413-08 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 5.3413-07 0.00E1+00 ZR-95 CURIES 0.0013+00 0.00E+00 3.73E-07 0.0013+00 CO-S8 CURIES 0.00E+00 0.0013+00 0.0013+00 2.0213-09 ALPHA CURIES 1.83E-07 2.2813-07 0.0013+00 0.OOE+00 TOTAL FOR PERIOD CURIES 5.26E-06 5.5713-06 8.21 E-05 1.691E-05

4. TRITIUM lH-3 CURIES 1.09E1+01 1.44E+01 6.63E-01 7.8913-02 Page I of I 16

Table 1B 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 4,2003 CONTINUOUS RELEASES I BATCH RELEASES I

THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. FISSION GASES AR-41 CURIES 0.002+00 0.00E+00 3.94E-02 4.82E-01 XE-133 CURIES 1.782-01 1.09E+01 1.19E-02 2.19E-01 XE-135 CURIES 0.00E+00 1.07E-01 0.00E+00 4.60E-03 XE-131M CURIES 4.63E+00 4.97E+00 0.00E+00 1.76E-04 XE-133M CURIES 0.00E+00 1.074-02 0.OOE+00 0.OOE+00 XE-138 CURIES 0.OOE+00 0.00E+00 2.822-04 0.00E+00 XE-135M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-85M CURIES 0.00E+00 1.29E-03 0.00E+00 0.00E+00 KR-85 CURIES 0.00E+00 0.00E+00 2.284-01 7.95E-02 KR-88 CURIES 0.00E+00 2.47E-02 0.00E+00 0.00E+00 KR-87 CURIES 0.OOE+00 0.00E+00 0.00E+00 3.72E-05 TOTAL FOR PERIOD CURIES 4.80E+00 1.60E+01 2.80E-01 7.854-01

2. IODINES 1-131 CURIES 0.002+00 2.75E-07 0.00E+00 1.72E-07 1-133 CURIES 0.00E+00 0.00E+00 0.OOE+00 6.59E-08 1-132 CURIES 0.00E+00 0.00E+00 0.00E+00 1j.6 5 E408 TOTAL FOR PERIOD CURIES 0.00E+00 2.75E-07 0.00E+00 2.55E-07

3. PARTICULATES SB-125 CURIES 4.90-07 1.02E-06 0.00E+00 0.OOE+00 CO-60 CURIES 0.00E+00 2.18E-07 2.234-08 1.122-05 CS-137 CURIES 0.00E+00 2.91E-07 0.00E+00 2.68E-08 CO-57 CURIES 0.002+00 0.002+00 0.00E+00 0.00E+00 CE-144 CURIES 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00Q+00 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 CO-58 CURIES 0.00E+00 0.00E+00 0.002+00 0.00E+00 CS-134 CURIES O.OOE+00 0.00E2+00 0.00E+00 1.39E-08 CS-136 CURIES 0.00E+00 0.00E+00 0.00E+00 4.47E-09 ALPHA CURIES 7.89E-08 1.69E-07 0.00E+00 0.002+00 TOTAL FOR PERIOD CURIES 5.69E-07 1.704-06 2.23E-08 1.13E-05

4. TRITIUM lH-3 CURIES 1.23E+01 1.06E+01 I 3.914-02

.2A7E-01 Page I of I 17

Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS I AND 2,2003 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE INOT INCLUDING TRITIUM. GASES, ALPHA]

CURIES 2.36E-02 6.63E-02 20

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCiIML 5.43E-08 1.8 IE-07

3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM

1. TOTAL RELEASE CURIES 1.91E+02 1.89E+02 14 1

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.42E-04 S.15E-04

3. PERCENT OF APPLICABLE LIMIT N/A N/A C. DISSOLVED AND ENTRAINED GASES I. TOTAL RELEASE CURIES l2.91E-01 I

8.29E-02 27

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.72E-07 2.26E-07 D. GROSS ALPHA RADIOACTIVITY I 1. TOTAL RELEASE CURIES 1.43E-03 0.00E+00 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) lGAL I 3.82E+06 13.25E+06 10 IF. VOLUME OF DILUTION WATER USED I GAL I.IIE+08 9.37E+07 1

10 1

(a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page 1 of I 18

Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4.2003 THIRD FOURTH ESTTOTAL TYPE OF EFFLUENT UNITS I QUARTER IQUARTER ERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS I. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA]

CURIES 3.18E-02 2.18E-02 20

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.02E-07 5.28E-08

3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM

1. TOTAL RELEASE CURIES 1.10E+02 4.46E+02 14u 1

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uC/ML 3.52E-04 1.08E-03

3. PERCENT OF APPLICABLE LIMIT

%NA N/A C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 2.23E-04 1.98E-01 27

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uC7.17E-0 4.79E-07 D. GROSS ALPHA RADIOACTIVrrY I.TOTALRELEASE CURIES I 1.02E-03 1.93E-04 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) I GAL I 2.97E+06 I3.36E+06 10 F. VOLUME OF DILUTION WATER USED lGAL I 7.94E+07 I 1.06E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6. 1988 Page 1 of I

.4 n I 1

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 2,2003 I CONTINUOUS RELEASES I BATCH RELEASES I

I FIRST l SECOND FIRST lSECOND NUCLIDE I UNITS I QUARTER I QUARTER IQUARTER I QUARTER

1. ALL NUCLIDES ALPHA CURIES 0.00E+00 0.00E+00 1.43E-03 0.OOE+00 CO-58 CURIES O.OOE+00 0.00E+00 6.97E-03 2.42E-02 CO-60 CURIES 0.OOE+00 0.OOE+00 8.17E-04 1.25E-03 CS-134 CURIES O.OOE+00 0.00E+00 1.99E-04 5.99E-04 CS-137 CURIES 0.00E+00 0.OOE+00 6.90E-04 1.95E-03 H-3 CURIES 0.OOE+00 0.00E+00 1.91E+02 1.89E+02 SB-125 CURIES 0.00E+00 0.OOE+00 1.39E-02 3.39E-02 SB-124 CURIES 0.001E+00 0.OOE+00 7.40E-05 1.95E-03 CR-51 CURIES 0.00E+00 0.00E+00 1.80E-04 1.30E-03 XE-133 CURIES 0.00E+00 0.00E+00 2.84E-01 8.19E-02 MN-S4 CURIES 0.OOE+00 0.00E+00 8.80E-06 0.00E-+00 XE-135M CURIES 0.OOE+00 0.00E+00 3.20E-06 0.OOE+00 NB-95 CURIES 0.00E+00 0.00E+00 1.03E-05 0.OOE+00 XE-135 CURIES 0.00E+00 0.OOE+00 1.24E-06 O.OOE+00 KR-87 CURIES 0.OOE+00 0.00E+00 3.52E-06 0.00E+00 I-131 CURIES 0.00E+00 0.00E+00 2-53E-04 3.53E-04 XE-131M CURIES O.OOE+00 0.OOE+00 6.21E-03 9.33E-04 CO-57 CURIES O.OOE+00 0.00E+00 1.89E-05 3.09E-05 XE-133M CURIES 0.00E+00 0.OOE+00 1.28E-03 1.18E-04 1-132 CURIES 0.00E+00 0.00E+00 2.27E-04 2.54E-04 TE-132 CURIES 0.OOE+00 0.OOE+00 2.25E-04 1.94E-04 ZR-95 CURIES 0.00E+00 0.OOE+00 0.OOE+00 1.52E-04 NA-24 CURIES 0.00E+00 O.OOE+00 0.OOE+00 3.04E-05 AG-110M CURIES O.OOE+00 0.00E+00 0.00E+00 5.52E-05 TOTALS FOR PERIOD CURIES 0.OOE+00 0.OOE+00 I.92E+02 1.89E+02 Page I of I 2i0

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 4,2003 I CONTINUOUS RELEASES I BATCH RELEASES I

1 THIRD FOURTH THIRD JFOURTH INUCLIDE UNITS QUARTER QUARTER IQUARTER I QUARTER

1. ALL NUCLIDES ALPHA CURIES 0.001+00 0.0013+00 1.0213-03 1.9313-04 CO-58 CURIES 0.0013+00 0.0013+00 5.4813-03 3.24E-04 CO-60 CURIES 0.0013+00 O.OOE+OO 2.36E-03 3.64E-03 CS-134 CURIES 0.OOE+00 0.00E+O00 5.30E-04 3.5213-03 CS-137 CURIES O.OOE+00 0.OOE+00 1.89E-03 1.2513-02 H-3 CURIES 0.0013+00 0.00E+O0 1.1013+02 4.46E+02 SB-125 CURIES 0.OOE+OO0 0.00E+00 2.05E-02 1.5213-03 SB-124 CURIES 0.0013+00 0.OOE+OO 1.0813-04 0.003+00 CR-51 CURIES 0.0013+00 0.001+00 4.8313-04 O.OOE+00 XE-133 CURIES 0.OOE+O0 O.OOE+00 2.23E-04 1.88E-01 MN-54 CURIES 0.0013+00 O.OOE+00 3.17E-05 2.44E-04 XE-135M CURIES 0.0013+00 0.OOE+00 0.0013+00 0.0013+00 NB-95 CURIES 0.001+00 0.0013+00 0.0013+00 0.OOE+00 XE-135 CURIES 0.0013+00 0.OOE+OO00

.OOE+O0

.OOE+00 KR-87 CURIES 0.OOE+00 O.00E+00 O.OOE+O 0.0013+00.E+

1-131 CURIES 0.0013+00 0.00+00 1.47E-04 4.7813-05 XE-131M CURIES 0.0013+00 0.00E+00 0.0013+00 6.93E-03 CO-57 CURIES 0.0013+00 0.00E+00 1.50E-04 7.04E-06 XE-133M CURIES 0.0013+00 0.OOE+00 0.0013+00 5.5313-04 1-132 CURIES O.OOE+00 0.0013+00 0.0013+00 O.OOE+00 TE-132 CURIES 0.0013O+00 0.0013+00 O.OOE+00 0.0013+00 ZR-95 CURIES 0.00E+00 O.OOE+00 1.82E.-05 0.OOE+00 NA-24 CURIES 0.OOE+00 0.00E+00 0.0013+00 0.0013+00 AG-11OM CURIES 0.0013+00

.OOE+00 8.7513-05 0.0013+00 NP-237 CURIES 0.00E+00 0.OOE+00 1.80E-06 0.00E+00 SR-92 CURIES 0.0013+00 0.OOE+00 5.0513-06 O.OOE+00 ZN-6S CURIES 0.0013+00 0.00E+00 5.54E-06 0.00E+00 MO-99 CURIES 0.00E+00 0.OOE+00 4.1613-06 3.86E-06 TC-99M CURIES 0.OOE+00 0.0013+00 4.1613-06 3.86E-06 BE-7 CURIES 0.0013+00 0.0013+00 0.00E+00 2.3113-05 KR-85 CURIES 0.00E+00 0.00E+00 Q.OOE+00 2.4713-03 ZR-97 CURIES 0.0013+00 0.0013+00 0.0013+00 2.0613-06 TOTALS FOR PERIOD CURIES 0.0013+00 0.0013+00 1.1OE+02 4.4613+02 Page I of I 21

Table 3 Solid Waste & Irradiated Fuel Shipments 2003 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, control rods, etc.

d. Other UNITS Ci m'

ci PERIOD JAN -

JUN 0.0025 2.10E-6 11.02 0.37 0

0 0

0 PERIOD JUL DEC 2.50 64.20 5.19

2. 16E-3 0

0 0

0 EST.

TOTAL ERROR

(%)

+/-25%

+/-25%

+/-25%

+/-25%

Ci Ci

2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Tvoe of Waste)

Nuclide

a.

Ni-63 Co-60 Cs-137 Fe-55 Co-58 Cs-134 Sb-125 Mn-54 Ru-106

% Abundanc 48.60 15.50 11.79 9.56 3.74 3.19 2.41 2.05 1.64 PERIOD JAN -

JUN le Curies 1.02E-06 3.26E-07 2.48E-07 2.OOE-07 7.85E-08 6.70E-08 5.06E-08 4.31E-08 3.44E-08 PERIOD

% Abundance 48.60 15.50 11.79 9.56 3.74 3.19 2.41 2.05 1.64 JUL -

DEC Curies 31.20 9.95 7.57 6.14 2.40 2.00 1.55 1.32 1.05

b.

Fe-55 Cs-137 Ni-63 Cs-134 Co-60 Co-58 30.03 26.46 18.86 8.43 8.28 3.72 0.11 0.10 0.07 0.03 0.03 0.01 30.03 26.46 18.86 8.43 8.28 3.72 6.48E-04 5.72E-04 4.07E-04 1.82E-04 1.79E-04 8.04E-05 Pe 1 of 2 22-

Table 3 Solid Waste & Irradiated Fuel Shipments 2003

2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Type of Waste)

Cont.

PERIOD JAN -

JUN

% Abundance Curies PERIOD JUL -

DEC

% Abundance Curies Nuclide

c.

None

d.

None

3.

SOLID WASTE DISPOSITION:

Number of Mode of

'h i nma" t Trrarnsnrt' Destination Class of Solid WasteP qninpedl Type of C'ntainer 3*

2*

2*

lo*

3*

5*

Cask Cask Cask Truck Truck Truck ALARON Studsvik Studsvik Duratek, Inc.

Duratek, Inc. -

Gallaher RACE, LLC A

A B

A A

A LSA LSA LSA LSA LSA LSA Sent to waste processors for volume reduction before burial.

4.

SOLIDIFICATION AGENT2 None used.

B.

IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shipments 0

Mode of Transportation Destination Pe 2 cE 2 ZA

Table 4 Meteorological Data Averages Using Hourly Averaged Data Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:21.39 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 UNITS VALUES

% GOOD DATA Stability Class A-G E

90%

Total Precipitation CM.

8.08E+01 68%

10 Meter Level:

Wind Speed Meter/Sec 2.90E+00 99%

Wind Direction Degrees 2.04E+02 97%

Wind Direction Variability Degrees 1.32E+01 99%

Reference Temperature Degrees C 1.26E+01 100%

Dewpoint Degrees C 6.34E+00 100%

60 Meter Level:

Wind Speed Meter/Sec 5.09E1+00 99%

Wind Direction Degrees 2.22E+02 99%

Wind Direction Variability Degrees 8.70E+00 99%

Dewpoint Degrees C NONE 0%

Temperature Difference 60 - 10 Degrees C 1.07E-01 90%

Page 1 of I 24

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Datef/ime: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: A Wind Speed at 10.00 Meter Level (MPH)

I 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

6 28 31 4

0 0

69 NNE 6

49 25 0

0 0

80 NE 3

30 3

0 0

0 36 ENE 5

25 2

0 0

0 32 E

7 23 4

0 0

0 34 ESE 8

24 6

2 0

0 40 SE 11 65 32 2

0 0

110 SSE 9

56 46 3

4 0

118 S

12 56 57 13 0

0 138 SSW 6

60 76 23 0

0 165 SW 4

49 41 12 0

0 106 WSW 6

21 23 3

0 0

53 W

6 25 23 3

0 0

57 WNW 2

34 37 7

0 0

80 NW 3

32 19 2

0 0

56 NNW 1

34 24 0

0 0

59 TOT 95 611 449 74 4

0 1233 Hours of Calm Data:

Hours of Invalid Data:

1 37 Page 1 of 7 ED-

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 3 1-DEC-2003 23:00:00.00 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 15 10 0

0 0

27 NNE 6

15 8

0 0

0 29 NE 2

18 4

0 0

0 24 ENE 1

14 2

0 0

0 17 E

4 8

3 0

0 0

15 ESE 0

7 4

1 0

0 12 SE 3

21 10 0

0 0

34 SSE 3

20 11 3

1 0

38 S

2

.10 8

5 0

0 25 SSW 3

16 10 3

0 0

32 SW 5

10 18 2

0 0

35 WSW 6

10 10 1

0 0

27 W

4 7

6 3

0 0

20 WNW 5

15 7

2 0

0 29 NW 1

18 11 3

1 0

34 NNW 314 15 0

0 0

32 TOT 50 218 137 23 2

0 430 Hours of Calm Data:

Hours of Invalid Data:

0 10 Page 2 of 7 26

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1 -JAN-2003 00:00:00.00 to 3 1-DEC-2003 23:00:00.00 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 19 6

1 0

0 30 NNE 7

12 13 0

0 0

32 NE 1

28 2

0 0

0 31 ENE 3

11 7

0 0

0 21 E

2 7

4 0

0 0

13 ESE 7

9 3

0 0

0 19 SE 7

12 10 0

0 0

29 SSE 3

14 8

4 0

0 29 2

10 8

3 0

0 23 SSW 4

8 1

6 0

0 19 SW 1

13 12 1

1 0

28 WSW 0

7 6

2 0

0 15 W

4 7

10 3

0 0

24 WNW 1

14 17 5

0 0

37 NW 3

19 16 0

0 0

38 NNW 3

5 8

1 1

0 18 TOT 52 195 131 26 2

0 406 Hours of Calm Data:

Hours of Invalid Data:

0 12 Page 3 of 7 27

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: D

[

Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

13 76 119 18 1

0 227 NNE 15 95 65 4

0 0

179 NE 24 111 28 4

0 0

167 ENE 25 67 48 4

0 0

144 E

15 70 50 7

0 0

142 ESE 18 58 38 6

0 0

120 SE 12 66 50 8

2 0

138 SSE 13 70 66 13 0

0 162 S

8 48 42 17 0

0 115 SSW 9

50 33 1

0 0

93 SW 11 30 20 1

0 0

62 WSW 4

28 18 0

0 0

50 W

9 39 43 1

0 0

92 WNW 11 71 84 25 0

0 191 NW 17 78 72 12 0

0 179 NNW 12 75 127 32 0

0 246 TOT 216 1032 903 153 3

0 2307 Hours of Calm Data:

Hours of Invalid Data:

6 64 Page 4 of 7 28

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: E Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

31 59 27 5

0 0

122 NNE 44 72 13 1

0 0

130 NE 46 33 2

0 0

0 81 ENE 42 31 3

0 0

0 76 E

41 52 5

2 0

0 100 ESE 39 63 15 3

1 0

121 SE 28 117 46 0

0 0

191 SSE 20 139 89 0

0 0

248 S

19 124 97 12 0

0 252 SSW 20 99 50 3

0 0

172 SW 20 64 15 0

0 0

99 WSW 28 60 19 1

0 0

108 W

22 60 22 1

0 0

105 WNW1 28 105 22 0

0 0

155 NW 39 82 42 2

0 0

165 NNW 14 50 31 4

0 0

99 TOT 481 1210 498 34 1

0 2224 Hours of Calm Data:

Hours of Invalid Data:

34 47 Page 5 of 7 9Q

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: F Wind Speed at 10.00 Meter Level (MPH)

I 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

21 17 0

0 0

0 38 NNE 36 19 0

0 0

0 55 NE 41 3

0 0

0 0

44 ENE 32 6

0 0

0 0

38 E

25 7

0 0

0 0

32 ESE 45 10 0

0 0

0 55 SE 37 110 13 0

0 0

160 SSE 34 171 18 0

0 0

223 S

24 108 2

0 0

0 134 SSW 31 45 1

0 0

0 77 SW 34 54 0

0 0

0 88 WSW 29 20 0

0 0

0 49 W

27 30 0

0 0

0 57 WNW 38 22 0

0 0

0 60 NW 23 26 0

0 0

0 49 NNW 13 22 0

0 0

0 35 TOT 490 670 34 0

0 0

1194 Hours of Calm Data:

Hours of Invalid Data:

72 43 Page 6 of 7 30

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:23.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction I-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: G Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL 32 9

0 0

0 0

41 27 3

0 0

0 0

30 21 0

0 0

0 0

21 11 0

0 0

0 0

11 14 1

0 0

0 0

15 14 0

0 0

0 0

14 18 12 0

0 0

0 30 33 46 5

0 0

0 84 26 20 0

0 0

0 46 22 4

0 0

0 0

26 24 6

0 0

0 0

30 17 2

0 0

0 0

19 5

1 0

0 0

0 6

27 2

0 0

0 0

29 NW 31 14 0

0 0

0 45 NNW 38 10 0

0 0

0 48 TOT 360 130 5

0 0

0 495 Hours of Calm Data:

Hours of Invalid Data:

Hours of Good Data:

84 25 8486 = 96.9% of Total Hours Page 7 of 7 31

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: A

[

Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

3 21 36 9

2 0

71 NNE 3

28 42 2

0 0

75 NE 3

19 14 0

0 0

36 ENE 2

17 9

0 0

0 28 E

2 20 11 0

0 0

33 ESE 4

26 8

7 0

0 45 SE 7

37 48 8

0 0

100 SSE 4

37 66 22 1

3 133 S

2 26 62 29 11 0

130 SSW 1

27 62 49 16 0

155 SW 4

22 49 38 8

6 127 WSW 1

6 21 20 4

0 52 W

4 17 23 14 2

2 62 WNW 0

15 27 31 14 4

91 NW 1

14 32 16 1

2 66 NNW 2

19 33 7

0 0

61 TOT 43 351 543 252 59 17 1265 Hours of Calm Data:

Hours of Invalid Data:

0 6

Page 1 of 7

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: B

[

• Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

2 9

13 3

0 0

27 NNE 3

14 9

5 0

0 31 NE 2

10 10 1

0 0

23 ENE 2

11 3

0 0

0 16 E

2 7

6 3

0 0

18 ESE 0

2 6

3 0

0 11 SE 0

9 16 5

0 0

30 SSE 1

12 18 6

2 1

40 S

2 6

9 6

5 0

28 SSW 2

5 11 6

3 0

27 SW 0

8 13 14 6

0 41 WSW 2

9 4

9 1

0 25 W

1 6

8 1

3 1

20 WNW 1

9 8

12 1

1 32 NW 1

7 24 7

3 1

43 NNW 0

7 13 7

0 0

27 TOT 21 131 171 88 24 4

439 Hours of Calm Data:

Hours of Invalid Data:

0 1

Page 2 of 7

-.4 -

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report DateTfime: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: C Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

3 10 13 2

0 0

28 NNE 1

9 15 3

0 0

28 NE 2

16 11 0

0 0

29 ENE 0

14 9

3 0

0 26 E

2 7

3 1

0 0

13 ESE 4

7 7

0 0

0 18 SE 4

4 12 2

0 0

22 SSE 1

15 11 4

3 0

34 S

3 3

10 6

3 0

25 SSW 0

4 6

3 4

1 18 SW 0

6 6

12 4

2 30 WSW 0

8 5

3 2

0 18 W

0 6

4 6

3 1

20 WNW 2

5 8

15 6

3 39 NW 2

11 18 13 3

1 48 NNW 1

2 11 3

0 1

18 TOT 25 127 149 76 28 9

414 Hours of Calm Data:

Hours of Invalid Data:

2 2

Page 3 of 7

54

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: D Wind Speed at 60.00 Meter Level (MPH) a a

1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

6 33 135 62 8

1 245 NNE 5

33 97 31 2

0 168 NE 14 55 84 19 2

0 174 ENE 7

44 65 29 3

0 148 E

6 38 71 21 2

0 138 ESE 4

41 39 34 5

0 123 SE 1

26 61 32 8

3 131 SSE 6

9 79 47 17 0

158 S

4 12 56 40 17 1

130 SSW 3

11 49 29 6

0 98 SW 4

13 29 20 3

0 69 WSW 3

8 17 15 3

0 46 W

1 10 32 30 14 1

88 WNW 3

16 64 65 51 16 215 NW 2

24 77 66 34 4

207 NNW 5

24 86 100 22 0

237 TOT 74 397 1041 640 197 26 2375 Hours of Calm Data:

Hours of Invalid Data:

1 1

Page 4 of 7 A-I

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: E Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

2 12 42 33 1

0 90 NNE 4

22 71 18 0

0 115 NE 7

41 56 1

0 0

105 ENE 1

26 55 1

0 0

83 E

3 26 72 4

0 2

107 ESE 3

24 90 16 2

2 137 SE 3

18 94 67 2

0 184 SSE 1

16 75 110 5

0 207 S

1 11 91 120 27 0

250 SSW 1

14 66 118 12 0

211 SW 3

13 36 60 10 0 -

122 WSW 4

14 44 40 6

0 108 W

3 13 38 53 3

2 112 WNW 2

18 57 74 5

1 157 NW 4

17 77 71 12 1

182 NNW 5

18 55 43 4

0 125 TOT 47 303 1019 829 89 8

2295 Hours of Calm Data:

Hours of Invalid Data:

5 5

Page 5 of 7

-AP%

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction I-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: F Wind Speed at 60.00 Meter Level (MIPH)

I

• I.

r I

1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

1 4

20 4

0 0

29 NNE 3

10 17 12 0

0 42 NE 5

16 34 0

0 58 ENE 2

7 40 2

0 0

51 E

2 10 29 1

0 0

42 ESE 4

is 55 12 0

0 86 SE*

1 11 56 28 0

0 96 SSE 8

18 84 93 0

0 203 S

3 9

79 54 0

0 145 SSW 2

12 68 57 1

0 140 SW 4

10 37 39 4

0 94 WSW 3

12 32 17 0

0 64 W

2 11 30 30 0

0 73 WNW 1

15 27 25 0

0 68 NW 2

8 29 31 0

0 70 NNW 2

5 12 23 0

0 42 TOT 45 173 649 431 5

0 1303 Hours of Calm Data:

Hours of Invalid Data:

4 2

Page 6 of 7 37

Table 4 Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction Union Electric - Callaway Plant Report Date/Time: 23-APR-2004 14:35:25.50 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-2003 00:00:00.00 to 31-DEC-2003 23:00:00.00 Stability Class: G Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

3 4

14 6

0 0

27 NNE 5

6 30 9

0 0

50 NE 3

14 27 3

0 0

47 ENE 2

12 19 3

0 0

36 E

4 8

24 2

0 0

38 ESE 3

11 10 1

0 0

25 SE 3

9 7

1 0

0 20 SSE 0

24 23 9

0 0

56 S

4 9

20 17 0

0 50 SSW 1

11 26 22 0

0 60 SW 5

8 12 3

0 0

28 WSW 3

11 25 6

0 0

45 W

4 7

17 1

0 0

29 WNNW 0

13 5

10 0

0 28 NW 0

9 12 11 0

0 32 NNW 2

4 6

9 0

0 21 TOT 42 160 277 113 0

0 592 Hours of Calm Data:

Hours of Invalid Data:

Hours of Good Data:

57 8700 = 993% of Total Hours Page 7 of 7 38

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 l NEAREST RESIDENT LOCATION: IA0 km SSW LOCATION: 2.90 km NNW AGE GROUP: CHILD AGE GROUP: CHILD ORGAN UNITS DOSE

% LIMIT(a)

DOSE

% LIMIT(b)

1. GAMMA AIR DOSE

• MRAD 8.87E-04 0.01 4.77E-04 N/A

2. BETA AIR DOSE

• MRAD 2.00E-03 0.01 1.07E-03 N/A

3. WHOLE BODY ***

MREM 1.14E-03 N/A 6.10E-04 N/A

4. SKIN ***

MREM 2.09E-03 N/A 1.12E-03 N/A

5. BONE **

MREM 3.68E-04 N/A 2.28E-04 0.00

6. LIVER M REM 2.1 IE-03 N/A 827E-03 0.06

7. TOTAL BODY **

MREM 2.1IE-03 N/A 8.25E-03 0.06

8. THYROID

• MREM 2.1 1E-03 N/A 8.40E-03 0.06

9. KIDNEY MREM 2.1 IE-03 N/A 8.24E-03 0.05

10. LUNG MREM 2.14E-03 N/A 8.25E-03 0.05 1

GI-LLI**

MREM 2.1 E-03 N/A 8.26E-03 0.06

• 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 halflives greater than 8 days.

Page I of I

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 EFFIUENT DIRECT DIRECT TOTAL DOSE WITHIN RADIATION RADIATION DOSE THESITE FROM THE FROM OUTSID FOR THE ORGAN UNITS BOUNDARY UNIT TANKS YEAR

1. SKIN MREM 3.95E-04 N/A N/A 3.95E-04

2. BONE MREM 9.98E-05 8.79E-03 9.21E-04 9.81 E-03

3. LIVER MREM 5.72E-04 8.79E-03 9.21E-04 1.03E-02

4. TOTAL BODY MREM 7A8E-04 8.79E-03 9.21E-04 1.05E-02

5. THYROID MREM 5.72E3-04 8.79E-03 9.2113-04 1.03E-02

6. KIDNEY MREM 5.72E-04 8.79E-03 9.21E-04 1.03E-02

7. LUNG MREM 5.77E-04 8.79E-03 9.211E-04 1.03E-02

8. GI-LLI MREM S.72E-04 8.79E-03 9.21E-04 1.03E-02 Page I of I

,4U I

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 PUBUC)

DOSE FROM TOTAL DOSE DOSE AT THE ACTIVTES TO THE RESIDENCE WITHIN SITE MEMBER OF ORGAN UNITS LOCATION BOUNDARY THE PUBLIC

% LIMITS

1. SKIN lMREM 9.24E-04 3.95E-04 l.32E-03 0.01

2. BONE MREM 2.05E-04 9.SIE-03 l1.00E-02 0.04

3. LIVER MREM 5.10E-03 1.03E-02 l.54E-02 0.06

4. TOTAL BODY NMEEM 5.51E-03 1.05E-02 1.60E-02 0.06

5. THYROID MREM 5.15E-03 1.03E-02 1.54E-02 0.02

6. KIDNEY MREM 5.09E-03 1.03E-02 1.54E-02 0.06

7. LUNG MqREM 5.IOE-03 1.03E-02 1.54E-02 0.06

8. GI-LLI MREM 5.13E-03 1.03E-02 1.54E-02 0.06

• Annual dose limits from 40CFR190.10(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

Page I of I 41

Table 8 Dose Due to Liquid Effluents (Member of the Public)

TABLE 8 DOSE DUE TO LIQUID EFFLUENTS (MEMBER OF THE PUBLIC) 2003 ORGAN UNITS DOSE LIUIT

• l

% LIMIT

1. BONE MREM 6.48E-02 10.00 6.48E-01

2. LIVER MREM 1.02E-01 10.00

.1.02E+00

3. TOTAL BODY MREM 7.22E-02 3.00 2.41E+00

4. THYROID MREM 2.19E-03 10.00 2.19E-02

5. KIDNEY hlREM 3.54E-02 10.00 3.54E-01

6. LUNG NIREM 1.29E-02 10.00 1.29E-01

7. GI-LLI MREM 4.93E-03 10.00 4.93E-02

• Annual dose limits of APA-ZZ-01003, Section 9A.4.1.

Page 1 of I 42