ML021230023

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2001 Annual Radioactive Effluent Release Report
ML021230023
Person / Time
Site: Callaway Ameren icon.png
Issue date: 04/25/2002
From: Blosser J
AmerenUE
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-4647
Download: ML021230023 (44)
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Text

One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166-6149 314.621.3222 April 25, 2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20556 ULNRC-4647 Gentlemen:

W"Ameren LIE DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY CALLAWAY PLANT FACILITY OPERATING LICENSE NPF-30 2001 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Please find enclosed the 2001 Annual Radioactive Effluent Release Report for the Callaway Plant. This report is submitted in accordance with section 5.6.3 of the Technical Specification.

Very truly yours, o

John D. Blosser Manager, Corporate Nuclear Services BFH/jdg Enclosure

by a subsidiary of Ameren Corporation Union Electric

cc:

M. H. Fletcher Professional Nuclear Consulting, Inc.

19041 Raines Drive

Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack Donohew (2)-

OPEN BY ADDRESSEE ONLY Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop OWFN 7E1 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Regional Administrator Department of Natural Resources Central Regional Office P.

0. Box 176 Jefferson City, MO 65102-0176 Mr. Gerhard K. Samide ANI Account Engineer Town Center, Suite 3005 29 S. Main St.

West Hartford, CT 06107-2445

2001 Callaway Plant Radioactive Effluent Release Report ESE WAmeren UF Docket no. 50-483 ENE MET

\\ TOWER

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Table of Contents 1.0 Introduction......................................................................................................................

1 2.0 Supplemental Information............................................................................................

2 2.1 R egulatory L im its...............................................................................................................

2 2.2 A verage E nergy....................................................................................................................

3 2.3 Measurements and Approximations of TOTAL RADIOACTIVITY........................... 3 2.4 B atch R eleases.....................................................................................................................

4 2.5 A bnorm al R eleases..............................................................................................................

4 3.0 Summary of Gaseous Radioactive Effluents.....................................................................

5 4.0 Summary of Liquid Radioactive Effluents........................................................................

6 5.0 Solid W astes..........................................................................................................................

7 6.0 Related Information.............................................................................................................

7 6.1 Unplanned Releases...................................................................................................

7 6.2 Changes to the Offsite Dose Calculation Manual.......................................................... 8 6.3 Major Changes to Radwaste Treatment Systems............................................................ 8 6.4 Land Use Census Changes.............................................................................................

8 6.5 Inoperability of Effluent Monitoring Instrumentation.................................................. 8 6.6 Instances of Liquid Holdup Tanks or Waste Gas Decay Tanks Exceeding Technical Specification Limits...................................................................................................

8 7.0 M eteorological Data.............................................................................................................

9 8.0 Assessment of Doses..........................................................................................................

10 8.1 Dose at the Site Boundary from Gaseous Effluents..................................................... 10 8.2 Dose to the Member of the Public...............................................................................

10 8.3 Total Dose Due to the Uranium Fuel Cycle................................................................ 10 8.4 Dose Due to Liquid Effluents...................................................................................... 11 List of Tables 1A Annual Summation of Gaseous Releases 1B 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 2001. It is submitted in accordance with Section 5.63 of the Callaway Plant Technical Specifications.

A summary of radioactivity released in liquid and gaseous effluents and solid waste shippedfrom the Callaway Plant during the periodfrom January 1, 2001 to December 31, 2001 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

Suplemental 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.

Radioiodine, Tritium, And Particulates The dose rate due to Iodine-131 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 Iodine-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 to 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/mI 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 mrern 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.

2.0

Suplemental Information Continued 2.2 Average Energy This requirement is not applicable to the Callaway Plant radiological effluent monitoring program since the release rate limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture.

2.3 Measurements and Approximations of Total Radioactivity Radionuclide concentrations in liquid and gaseous effluents were obtained by effluent sampling and radiological analysis in accordance with the requirements of Final Safety Analysis Report Table 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-5 5, and transuranic nuclides by an independent 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.

3 2.0

Suplemen tat 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 Missouri River flow during periods of effluent release to the river1 UNITS Minutes Minutes Minutes Minutes ft3/sec JAN-JUN 121 51,064 738 422 166 113,895 JUL-DEC 105 45,696 650 435 228 60,934 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:

UNITS Minutes Minutes Minutes Minutes JAN - JUN 28 23,136 11,908 826 11 JUL - DEC 34 4,318 1,379 127 15

'E-mail, S. Ternes, United States Department of the Interior - Geological Survey - Water Resources Division dated January 3, 2002 2.5 Abnormal Releases UQUID Number of releases: 0 Total Activity released: 0 GASEOUS Number of releases: 1 Total Activity released: 4.91 E-2 curies 4

2.0 GASEOUS

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 2001, 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.

5

4.0 Summary ofLiquid Radioactive Effluents The quantity of radioactive material released in liquid effluents during the year is summarized in Tables 2A and 2B. During 2001, there was no continuous release of liquid effluent from the plant.

Liquid effluents from the plant are continuously monitored. Shown is a liquid monitor shielded by lead to increase its sensitivity for sampling discharged water.

6

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 60 Related for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration of each nuclide listed in Table 3 was determined as the product of the fractional abundance and the total curies shipped. Those nuclides which comprise at least 1% of the total activity for a particular waste type are presented in Table 3.

nformation 6.1 Unplanned Releases Unplanned releases are:

1) Inadvertent or accidental releases of radioactive material.
2) Releases of radioactive material via normal pathways without a release permit, proper authorization, or proper sampling and analysis.
3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.

Auxiliary Boiler Contamination On April 10, 1998, radioactivity was detected in the Auxiliary Boiler feed water system. The plant was performing a refueling outage during this time. The boiler was 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 miss-positioned valves or leaks were identified. The results of sampling different system components were inconclusive, but may indicate a small leak in the SLWE heat exchanger. During refueling operations, the concentration of radioactive nuclides in the SLWE system can be a factor of 1000 higher then 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 10CFR50.59 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.

7 5.0

Related Information The Auxiliary Boiler was operated intermittently during 2001. The maximum total body dose to a Member of the Public from these releases was 2.6 E-04 mrem during 2001. This is negligible compared to the quarterly and annual effluent control limits. The activity released from the Auxiliary Boiler during 2001 is included in Tables lA, IB, 5, 6 and 7.

6.2 Changes to the Offsite Dose Calculation Manual No changes were made to the Callaway Offsite Dose Calculation Manual (plant procedure APA-ZZ-0 1003) during 2001.

6.3 Major Changes to Radwaste Treatment Systems During 2001, there were no major plant modifications to the gaseous, solid or liquid radwaste treatment systems.

The following minor modification was made to the liquid radwaste system during 2001.

Temporary Modification 0 1-0009 was installed to provide a NUKEM ultrafiltration and demineralization skid to process liquid wastewater. This skid allows processing of plant wastewater, while removing solids using filtration and demineralization.

The NUKEM skid interfaces with Liquid Radwaste, Service Air and Reactor Makeup Water systems. Existing plant piping connections allow wastewater from the Boron Recycle System to be processed.

Because the wastewater continues to be collected in the Discharge Monitor Tanks and sampled prior to discharge, this change was not considered a major change. This modification was approved by ORC on 9/

13/01 via meeting number 1823.

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 2001 all effluent monitoring instrumentation was OPERABLE within the limits specified in Radioactive Effluent Controls 16.11.1.3 and 16.11.2.4.

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.

60

7.0 M eteo rological Data The on-site meteorological data for this reporting period is presented in Table 4. 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 2001 was greater than 90% for all required parameters.

A variation was discovered in the Primary Tower 10 meter wind speed data. The evening Primary Tower wind speed indicated consistently higher then the Sec ondary Tower 10 meter data. The cause for the variation was determined to be an electrical interference from the tower strobe light.

The affected data points were invalidated and substituted with secondary tower data. Primary Tower 60 and 90 meter wind speed data was also affected to a smaller extent. No affected values were not used to substitute for any 10 meter wind speed data used to calculate dose.

The percent of good data for the 10 meter wind speed for 2001 approached 100% after corrections. Plant Corrective Action Document 200202583 provides the details on this event.

Pictured is the Secondary Meteological Tower. This station obtains measurements at a height of 10 meters, and On 9/2/01 the Primary Met Tower 60 meter wind speed provides backup data for the Primary Meteological Tower instrument anemometer was discovered to be damaged.

readings at 10, 60 and 90 meters.

Special Report 2001-004 was submitted to the NRC after it was determined the instrument was inoperable for greater then seven days. Plant Corrective Action A meteorologist was consulted to determine possible Document 200105528 provides the details of this event.

solutions to this problem.

Plant Corrective Action Document 200206313 evalu ated damage that was discovered on the Primary Met Tower 10 and 90 meter wind speed instruments. The 90 meter instrument had heat tracing wire rubbing on the anemometer. The 10 meter instrument was missing a cup.

Based on the type of damage to these instruments it was determined a large predatory bird was causing the prob lems.

9

Assessment of Doses Assessment of doses to the maximum exposed individual from gaseous and liquid effluents released was performed in accordance with the ODCM as described in the following sections. For all effluents released from the Callaway Plant during this year, the annual dose to the maximum exposed individual was less than 1% of the Radiological Effluent Control Limits presented in Section 2.1 of this report.

8.1 Dose at the Site Boundary from Gaseous Effluents The dose at the Site Boundary was due to plume exposure from noble gases, ground plane exposure, and inhalation. It was conservatively assumed that a hypothetical maximum exposed individual was present at the Site Boundary location with the most limiting atmospheric dispersion (based on actual meteorological conditions for the year). Dose was conservatively calculated using a child as the critical age group.

The dose from gaseous effluents at the Site Boundary for 2001 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 for the 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 2001 are presented in Table 5.

Dose To The Member Of The Public From Activities Within The Site Boundaiy 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.

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.

10 8.0

Assessment of Doses Continued The total dose to the Member of the Public (Table 7) was the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence. It was conservatively assumed that each food ingestion pathway exists at his residence and that the 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.

11 8.0

Table 1A Semiannual Summation of Gaseous Releases AllAirborne Effluents QUARTERS 1 AND 2,2001 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CURIES 2.07E+02 4.04E+01 20
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.66E+01 5.14E+00
3. PERCENT OF TECH SPEC LIMIT N/A N/A B. RADIOIODINES
1. TOTAL IODINE-131 CURIES 2.39E-06 4.7 1E-05 23
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.07E-07 5.99E-06
3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES
1. PARTICULATE (HALF-LIVES > 8 DAYS)

CURIES 2.66E-07 1.06E-04 30

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.42E-08 1.35E-05
3. PERCENT OF TECH SPEC LIMIT N/A N/A
4. GROSS ALPHA RADIOACTIVITY CURIES 7.69E-08 3.65E-08 D. TRITIUM

[1. TOTAL RELEASE CURIES 1.96E+01 1.82E+01 14

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.52E+00 I 2.32E+00
3. PERCENT OF TECH SPEC LIMIT N/A N/A (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 1 of 2 12

Semiannual Summation of Gaseous Releases AllAirborne Effluents QUARTERS 3 AND 4,2001 Continued THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CURIES 2.63E+00 9.1 IE-01 20
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 3.30E-01 1.15E-01
3. PERCENT OF TECH SPEC LIMIT N/A N/A B. RADIOIODINES
1. TOTAL IODINE-131 CURIES 5.48E-08 2.73E-07 23
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 6.89E-09 3.43E-08
3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES
1. PARTICULATE (HALF-LIVES > 8 DAYS)

CURIES 9.73E-05 1.46E-04 30

2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.22E-05 1.83E-05
3. PERCENT OF TECH SPEC LIMIT N/A N/A
4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 4.74E-08 D. TRITIUM
1. TOTAL RELEASE CURIES 1.47E+01 1.07E+01 14
2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.85E+00 1.35E+00
3. PERCENT OF TECH SPEC LIMIT N/A IN/A (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 2 of 2 Table ]A

SemiannualAirborne Continuous and Batch Releases, Ground Level Releases Fission Gases, Jodines, and Particulates QUARTERS 1 AND 2,2001 CONTINUOUS RELEASES I BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER I. FISSION GASES XE-133 CURIES 1.89E+02 3.63E+01 2.63E-01 1.78E+00 AR-41 CURIES 2.29E-01 0.OOE+00 3.91E-02 1.77E-01 XE-135 CURIES 8.92E+00 1.26E+00 4.59E-03 5.02E-02 KR-85 CURIES 0.OOE+00 0.OOE+00 4.88E-01 2.60E-01 XE-133M CURIES 2.30E+00 6.18E-01 7.60E-04 1.41E-02 XE-13 IM CURIES 8.05E-01 0.OOE+00 1.89E-03 0.OOE+00 KR-85M CURIES 1.53E+00 0.OOE+00 6.48E-05 4.44E-03 KR-87 CURIES 7.79E-01 0.OOE+00 0.OOE+00 0.OOE+00 KR-88 CURIES 2.25E+00 0.OOE+00 0.OOE+00 0.OOE+00 XE-135M CURIES 3.35E-01 0.OOE+00 2.75E-07 0.00E+00 XE-138 CURIES 4.04E-01 0.OOE+00 0.OOE+00 0.00E+00 TOTAL FOR PERIOD CURIES 2.06E+02 3.82E+01 7.97E-01 2.28E+00

2. IODINES 1-131 CURIES 1.28E-06 4.71E-05 1.10E-06 0.00E+00 1-132 CURIES O.OOE+00 3.20E-05 2.56E-07 0.OOE+00 1-133 CURIES 0.OOE+00 2.27E-06 9.01E-07 0.OOE+00 1-135 CURIES 0.OOE+00 0.OOE+00 5.21E-07 0.OOE+00 TOTAL FOR PERIOD CURIES 1.28E-06 8.13E-05 2.78E-06 0.OOE+00
3. PARTICULATES CS-134 CURIES 0.OOE+00 8.53E-08 1.03E-07 4.08E-06 CS-137 CURIES 0.OOE+00 4.75E-07 1.63E-07 2.93E-05 CO-60 CURIES 0.OOE+00 0.OOE+00 0.00E+00 7.OOE-05 CO-58 CURIES 0.OOE+00 2.15E-06 O.OOE+00 0.OOE+00 SB-125 CURIES 0.OOE+00 O.OOE+00 0.00E+00 4.70E-08 ALPHA CURIES 7.69E-08 3.65E-08 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 7.69E-08 2.75E-06 2.66E-07 1.03E-04
4. TRITIUM H-3 CURIES 1.95E+01 1.78E-i01 1.10E-01 4.65E-01 Page 1 of 2 14 Table 1B

SemiannualAirborne Continuous and Batch Releases, Ground Level Releases Fission Gases, lodines, and Particulates QUARTERS 3 AND 4,2001 CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. FISSION GASES XE-133 CURIES 0.OOE+00 7.76E-02 8.54E-02 1.85E-01 AR-41 CURIES 0.OOE+00 0.OOE+00 3.59E-02 5.23E-02 XE-135 CURIES 0.OOE+00 0.OOE+00 1.01E-03 1.27E-03 KR-85 CURIES 0.00E+00 0.OOE+00 1.73E+00 0.OOE+00 XE-133M CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.73E-04 XE-131M CURIES 0.OOE+00 6.70E-02 3.33E-04 0.OOE+00 KR-85M CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KR-87 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 KR-88 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 XE-135M CURIES 0.OOE+00 0.OOE+00 0.OOE+00 6.28E-06 XE-138 CURIES 7.79E-0t 5.28E-01 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 7.79E-0I 6.72E-01 1.85E+00 2.39E-01
2. IODINES 1-131 CURIES 5.48E-08 2.73E-07 0.OOE+00 0.OOE+00 1-132 CURIES 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1-133 CURIES 0.OOE+00 2.52E-07 0.00E+00 0.OOE+00 1-135 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 5.48E-08 5.25E-07 0.OOE+00 0.OOE+00
3. PARTICULATES CS-134 CURIES 0.OOE+00 4.53E-07 0.OOE+00 2.41E-06 CS-137 CURIES 2.28E-07 5.07E-06 0.OOE+00 4.82E-06 CO-60 CURIES 0.00E+00 0.OOE+00 1.62E-06 1.29E-05 CO-58 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SB-125 CURIES 9.21E-05 1.17E-04 3.07E-07 0.OOE+00 CR-51 CURIES 2.68E-06 2.05E-06 O.OOE+00 0.OOE+00 SB-124 CURIES 3.54E-07 3.65E-07 0.OOE+00 O.OOE+00 ALPHA CURIES 0.OOE+00 4.74E-08 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 9.53E-05 1.25E-04 1.93E-06 2.02E-05
4. TRITIUM H-3 CURIES 1.38E+01 1.OOE+01 7 9.31E-01 6.97E-01 Page 2 of 2 15 Table 1B

Table 2A Semiannual Summation of Liquid Releases All Liquid Effluents QUARTERS I AND 2,2001 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA]

CURIES 1.92E-03 6.44E-03 20

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.13E-09 1.42E-08
3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
1. TOTAL RELEASE CURIES 7.54E+02 8.97E+01 14
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.62E-03 1.98E-04
3. PERCENT OF APPLICABLE LIMIT N/A N/A C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE CURIES 2.46E+00 1.29E-01 27
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.30E-06 2.85E-07 D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE CURIES O.OOE+00 0.OOE+00 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) [GAL 5.82E+06 I 4.89E+06 10 F. VOLUME OF DILUTION WATER USED IGAL
1. 17E+08 I1.15E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 1 of 2 16

Table 2A Semiannual Summation ofLiquid Releases All Liquid Effluents QUARTERS 3 AND 4,2001 THIRD FORH EST TOTAL TYPE OF EFFLUENT QUARTER QUARTER ERROR % (a)

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE [NOT INCLUDING TRITIUM, GASES, ALPHA]

CURIES 1.32E-03 3.12E-03 20

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.94E-09 6.57E-09
3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
1. TOTAL RELEASE CURIES 4.05E+01 1.02E+02 t4
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.01E-05 2.15E-04
3. PERCENT OF APPLICABLE LIMIT N/A N/A C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE CURIES 2.05E-06 4.88E-04 27
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.57E-12 1.03E-09 D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE CURIES 0.OOE+00 0.OOE+00 29 E. WASTE VOLUME RELEASED (PRE-DILUTION)

GAL 4.9 1 E+06 4.77E+06 10 F. VOLUME OF DILUTION WATER USED GAL I.14E+08 1.21E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6, 1988 Page 2 of 2 17

Semiannual Liquid Continuous & Batch Releases Totals for Each Nuclide Released QUARTERS 1 AND 2,2001 CONTINUOUS RELEASES I BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER

1. ALL NUCLIDES CS-134 CURIES 0.OOE+00 0.OOE+00 4.29E-04 4.91E-04 CS-137 CURIES 0.OOE+00 0.OOE+00 1.11E-03 1.31E-03 H-3 CURIES 0.00E+00 0.OOE+00 7.54E+02 8.97E+01 CO-60 CURIES 0.00E+00 0.OOE+00 2.96E-04 9.59E-04 XE-133 CURIES 0.OOE+00 0.OOE+00 2.39E+00 1.24E-01 XE-131M CURIES 0.OOE+00 0.OOE+00 4.31E-02 5.01E-03 1-131 CURIES 0.OOE+00 0.OOE+00 2.28E-05 1.03E-04 MN-54 CURIES 0.OOE+00 0.OOE+00 1.34E-05 1.42E-04 XE-133M CURIES 0.OOE+00 0.OOE+00 1.11E-02 3.32E-04 XE-135 CURIES 0.OOE+00 0.OOE+00 1.59E-04 1.99E-05 1-133 CURIES 0.00E+00 0.OOE+00 2.65E-06 0.OOE+00 KR-85 CURIES 0.00E+00 O.OOE+00 1.35E-02 0.OOE+00 CS-136 CURIES 0.OOE+00 0.OOE+00 8.60E-06 0.OOE+00 CO-58 CURIES 0.OOE+00 0.OOE+00 2.43E-05 2.67E-03 CO-57 CURIES 0.00E+00 0.OOE+00 8.09E-06 0.OOE+00 BA-140 CURIES 0.OOE+00 0.OOE+00 7.20E-06 0.OOE+00 NB-95 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 3.22E-04 ZR-95 CURIES 0.00E+00 0.OOE+00 0.OOE+00 1.90E-04 CR-51 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.78E-04 FE-59 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.73E-05 BA-139 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 2.25E-05 SN-113 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 2.84E-06 BE-7 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 3.25E-05 KR-85M CURIES 0.OOE+00 0.OOE+00 0.00E+00 2.66E-06 TOTALS FOR PERIOD CURIES 0.00E+00 0.OOE+00 7.56E+02 8.98E+01 Page 1 of 2 18 Table 2B

Semiannual Liquid Continuous & Batch Releases Totals for Each Nuclide Released QUARTERS 3 AND 4,2001 CONTINUOUS RELEASES IBATCH RELEASES jTHIRD IFOURTH jTHIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER_

1. ALL NUCLIDES CS-134 CURIES O.OOE+00 O.OOE+O0 2.71E-04 3.67E-04 CS-137 CURIES O.OOE+00 O.00E+00 6.75E-04 7.67E-04 H-3 CURIES 0.OOE+00 O.OOE+O0 4.05E+01 1.02E+02 CO-60 CURIES 0.OOE+00 0.OOE+00 1.41E-04 2.73E-05 XE-133 CURIES O.OOE+00 0.OOE+00 O.00E+00 4.84E-04 XE-13 IM CURIES O.OOE-i00 O.OOE+00 O.OOE+00 0.OOE+00 1-131 CURIES 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 MN-54 CURIES O.OOE+00 0.OOE+00 3.56E-06 0.OOE+00 XE-133M CURIES O.OOE+00 0.OOE+00 0.00E+00 0.OOE+0O XE-135 CURIES 0.OOE+00 0.OOE+00 2.05E-06 0.OOE+0O 1-133 CURIES O.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+0O KR-85 CURIES 0.OOE+00 0.00E+O0 0.OOE+00 0.OOE+00 CS-136 CURIES O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 CURIES 0.OOE+00 O.OOE+00 1.80E-04 6.04E-06 CO-57 CURIES O.OOE+00 O.OOE+O0 O.00E+00 0.OOE+00 BA-140 CURIES O.OOE+00 O.OOE+0O O.OOE-i00 0.OOE+0O NB-95 CURIES 0.OOE+00 O.OOE+/-O0 O.OOE+00 1.04E-05 ZR-95 CURIES 0.OOE+O0 0.OOE+O0 O.OOE+00 3.60E-06 CR-5i CURIES 0.OOE+00 0.OOE+00 O.OOE+/-00 0.OOE+00 FE-59 CURIES 0.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+0O BA-139 CURIES 0.OOE+00 O.OOE+00 O.OOE÷00 0.OOE+00 SN-113 CURIES O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 BE-7 CURIES 0.OOE+00 O.OOE+O0 O.OOE+00 0.OOE+0O KR-85M CURIES O.OOE+O0 O.OOE+00 0.OOE+O0 0.OOE+0O TC-99M CURIES 0.OOE+00 O.OOE+00 2.40E-06 0.OOE+00 CE-144 CURIES 0.OOE+00 0.OOE+0O 1.35E-05 0.OOE+O0 PR-144 CURIES O.OOE+00 0.OOE-i-0 1.35E-05 0.OOE+0O RU-106 CURIES O.OOE-i00 O.OOE+00 1.98E-05 0.OOE+00 SB-125 CURIES O.OOE+00 O.OOE+OO 0.OOE+00 1.94E-03 XE-135M CURIES O.OOE+00 O.OOE+00 O.OOE+00 4.25E-06 TOTALS FOR PERIOD CURIES --

O.OOE+00 O.OOE+00 4.05E+O1I 1.02E+02 Page 2 of 2 19 Table 2B

Solid Waste & Irradiated Fuel Shipments 2001 A. SOLID WASTE BURIED (Does not include irradiated fuel)

1. Type of waste Y

I.

PERIOD JAN - JUN PERIOD JUL - DEC EST. TOTAL ERROR (%)

a.

Spent resins, filter sludges m3 11.6 15.1 evaporator bottoms, etc.

Ci 167.38 8.75

+/-25%

b. Dry compressible waste, m3 3.5 9.1 contaminated equipment, etc.

Ci 0.50 0.47

+25%

c.

Irradiated components, m3 0

0 control rods, etc.

Ci

+/--25%

d. Other m3 0

0 Ci

-+/-25%

2. Estimate of major nuclide composition (By type of waste)

PERIOD PERIOD JAN - JUN JUL - DEC Percent Percent Nuclide Abundance Curies Nuclide Abundance Curies

a.

H-3 32.64 54.63 H-3 32.64 2.86 Ni-63 22.87 38.28 Ni-63 22.87 2.00 Cs-137 17.81 29.81 Cs-137 17.81 1.56 Co-58 9.94 16.64 Co-58 9.94 0.87 Cs-134 5.68 9.51 Cs-134 5.68 0.49 Co-60 5.09 8.52 Co-60 5.09 0.45 Fe-55 4.38 7.33 Fe-55 4.38 0.38

b.

Fe-55 42.08 0.21 Fe-55 42.08 0.20 Co-58 23.65 0.12 Co-58 23.65 0.11 Ni-63 9.97 0.049 Ni-63 9.97 0.047 Co-60 7.79 0.039 Co-60 7.79 0.037 Nb-95 4.39 0.022 Nb-95 4.39 0.021 Mn-54 4.21 0.021 Mn-54 4.21 0.019 Zr-95 2.45 0.012 Zr-95 2.45 0.012 Cs-137 1.91 0.0096 Cs-137 1.91 0.0089 Cr-51 1.09 0.0055 Cr-51 1.09 0.0051 Page 1 of 2 20 Table 3 UNITS

Solid Waste & Irradiated Fuel Shipments 2001

2. Estimate of major nuclide composition (By type of waste)

Y PERIOD JAN - JUN PERIOD JUL - DEC Percent Percent Nuclide Abundance Curies Abundance Curies

c.

None

d.

None

3. Solid waste disposition Number of Mode of Class of Solid Type of Shipments Transportation Destination Waste Shipped Container 1*

Cask Duratek, Inc A

LSA 3*

Truck ATG A

LSA 5*

Cask ATG A

LSA 3*

Cask ATG B

LSA 1*

Cask ATG C

LSA 2

Cask Barnwell, S. C.

A LSA 2

Cask Barnwell, S. C.

B LSA 11 Truck Duratek, Inc A

LSA 1

Cask Duratek, Inc A

LSA 1

Truck Duratek, Inc B

LSA 1"*

_Truck DSSI A

LSA

  • Sent to waste processors for volume reduction before burial destruction Mixed waste shipment for thermal
4. Solidification agent Not used B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of Shipments Transportation Destination 0

P2ge 2 of 2 21 Table 3

Table 4 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-2001 00:00:00.00 to 31-DEC-2001 23:00:00.00 UNITS VALUES

% GOOD DATA Stability Class A-G E

99%

Total Precipitation CM.

1.19E+02 100%

10 Meter Level:

Wind Speed Meter/Sec 3.16E+00 100%

Wind Direction Degrees 1.97E+02 99%

Wind Direction Variability Degrees 1.30E+01 99%

Reference Temperature Degrees C 1.35E+01 99%

Dewpoint Degrees C 7.14E+00 98%

60 Meter Level:

Wind Speed Meter/Sec 5.76E+00 92%

Wind Direction Degrees 2.08E+02 91%

Wind Direction Variability Degrees 8.50E+00 99%

Dewpoint Degrees C NONE 0%

Temperature Difference 60 - 10 Degrees C 2.01E-01 99%

Page 1 of 15 22

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31 -DEC-2001 23:00:00.00 Stability Class: A Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

6 7

11 0

0 0

24 NNE 2

8 6

0 0

0 16 NE 3

9 1

0 0

0 13 ENE 1

14 10 0

0 0

25 E

5 17 10 0

0 0

32 ESE 8

35 16 0

0 0

59 SE 5

65 43 1

0 0

114 SSE 8

47 30 18 0

0 103 S

9 42 42 12 0

0 105 SSW 16 64 90 12 0

0 182 SW 5

35 50 0

4 1

95 WSW 3

21 25 7

0 0

56 W

1 27 22 9

3 0

62 WNW 3

24 33 7

0 0

67 NW 3

9 26 7

0 0

45 NNW 2

9 6

8 0

0 25 TOT 80 433 421 81 7

1 1023 Hours of Calm Data:

Hours of Invalid Data:

Table 4 6

28 Page 2 of 15

Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction 1 -JAN-2001 00:00:00.00 to 31 -DEC-2001 23:00:00.00 Stability Class: B Wind Speed at 10.00 Meter Level (MPH) 1-3 r

r T

1 T

r 4-7 8-12 13-18 19-24

>24 TOTAL N

4 9

15 0

0 0

28 NNE 3

5 0

0 0

0 8

NE 3

4 4

0 0

0 11 ENE 1

14 2

0 0

0 17 E

3 7

3 0

0 0

13 ESE 2

8 2

0 0

0 12 SE 2

14 12 0

0 0

28 SSE 2

12 9

1 0

0 24 S

4 11 14 3

0 0

32 SSW 2

21 20 4

0 0

47 SW 2

13 17 0

0 0

32 WSW 3

7 8

2 0

0 20 W

1 11 14 4

1 0

31 WNW 2

8 19 4

1 0

34 NW 1

6 9

3 0

0 19 NNW 1

8 15 5

0 0

29 TOT 36 158 163 26 2

0 385 Hours of Calm Data:

Hours of Invalid Data:

Page 3 of 15 a

Table 4 1

8

Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 23:00:00.00 Stability Class: C Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7

-r r

8-12 13-18 19-24

>24 TOTAL N

8 15 9

0 0

0 32 NNE 2

7 5

0 0

0 14 NE 2

8 2

0 0

0 12 ENE 1

8 2

0 0

0 11 E

0 9

3 0

0 0

12 ESE 4

8 11 2

0 0

25 SE 1

19 13 0

0 0

33 SSE 5

13 11 3

0 0

32 S

3 4

18 3

0 0

28 SSW 3

15 11 1

0 0

30 SW 2

13 10 1

2 0

28 WSW 2

10 6

2 0

0 20 W

3 12 14 3

0 0

32 WNW 0

11 11 2

0 0

24 NW 1

10 7

6 0

0 24 NNW 2

12 9

3 0

0 26 TOT 39 174 142 26 2

0 383 Hours of Calm Data:

Hours of Invalid Data:

1 4

Page 4 of 15 Table 4

Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 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

12 53 41 5

0 0

111 NNE 12 44 21 2

0 0

79 NE 10 29 14 0

0 0

53 ENE 6

33 25 0

0 0

64 E

5 34 19 0

0 0

58 ESE 9

32 21 0

0 0

62 SE 13 43 34 9

0 0

99 SSE 11 32 45 9

0 0

97 S

14 52 62 22 2

0 152 SSW 6

55 35 8

1 0

105 SW 14 34 28 2

0 0

78 WSW 5

34 25 12 3

2 81 W

3 41 65 31 1

0 141 WNW 5

47 53 16 1

0 122 NW 17 67 71 19 0

0 174 NNW 16 46 51 23 1

0 137 TOT 158 676 610 158 9

2 1613 Hours of Calm Data:

Hours of Invalid Data:

Page 5 of 15 26 Table 4 11 16

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31 -DEC-2001 23:00:00.00 Stability Class: E Wind Speed at 10.00 Meter Level (MPH)

T T

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

>24 TOTAL N

27 80 41 2

0 0

150 NNE 32 48 27 2

0 1

110 NE 30 87 37 0

1 0

155 ENE 13 61 32 1

0 0

107 E

8 59 41 3

0 0

111 ESE 23 87 80 9

0 0

199 SE 25 194 99 10 0

0 328 SSE 23 125 124 23 0

0 295 S

29 135 127 24 1

0 316 SSW 30 93 46 9

2 1

181 SW 21 71 21 5

1 5

124 WSW 22 89 39 7

3 4

164 W

19 107 77 5

0 0

208 WNW 19 98 51 4

0 0

172 NW 20 90 62 7

0 0

179 NNW 24 69 55 7

0 0

155 TOT 365 1493 959 118 8

11 2954 Hours of Calm Data:

Hours of Invalid Data:

Table 4 25 10 Page 6 of 15

Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 23:00:00.00 Stability Class: F Wind Speed at 10.00 Meter Level (MPH) 1-3 r

r T

1 I

F 4-7 8-12 13-18 19-24

>24 TOTAL N

19 35 12 0

0 0

66 NNE 21 42 10 0

0 0

73 NE 16 67 2

0 0

0 85 ENE 19 40 6

0 0

0 65 E

10 46 6

0 0

0 62 ESE 24 60 6

5 0

0 95 SE 31 209 22 2

0 0

264 SSE 34 167 17 1

0 0

219 S

33 133 5

1 0

0 172 SSW 17 86 8

0 0

0 111 SW 22 63 3

0 0

0 88 WSW 29 26 0

0 0

0 55 W

26 37 3

1 0

0 67 WNW 43 44 3

0 0

0 90 NW 18 33 5

0 0

0 56 NNW 24 41 8

2 0

0 75 TOT 386 1129 116 12 0

0 1643 Hours of Calm Data:

Hours of Invalid Data:

Table 4 17 12 Page 7 of 15 11

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 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 N

22 30 3

0 0

0 55 NNE 22 24 0

0 0

0 46 NE 13 13 3

0 0

0 29 ENE 8

16 3

0 0

0 27 E

3 5

0 0

0 0

8 ESE 9

14 0

0 0

0 23 SE 17 54 4

0 0

0 75 SSE 14 59 1

0 0

0 74 S

20 16 0

0 0

0 36 SSW 23 25 0

0 0

0 48 SW 15 26 0

0 0

0 41 WSW 9

4 0

0 0

0 13 W

11 7

0 0

0 0

18 WNW 24 4

0 0

0 0

28 NW 10 4

2 0

0 0

16 NNW 17 27 6

0 0

0 50 TOT 237 328 22 0

0 0

587 Hours of Calm Data:

Hours of Invalid Data:

Table 4 18 14 Page 8 of 15

Meteorological Data Continued Totals of Hours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31 -DEC-2001 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

2 3

10 3

0 0

18 NNE 1

9 8

0 0

0 18 NE 1

7 4

0 0

0 12 ENE 1

16 12 1

0 0

30 E

1 14 10 3

0 0

28 ESE 3

18 16 3

0 0

40 SE 3

33 60 3

0 0

99 SSE 4

27 51 16 7

2 107 S

7 24 33 27 9

0 100 SSW 4

25 72 52 9

0 162 SW 4

29 60 38 4

7 142 WSW 0

12 20 17 3

2 54 W

1 13 19 13 3

8 57 WNW 0

17 27 22 8

2 76 NW 1

9 16 20 6

0 52 NNW 1

6 12 7

3 0

29 TOT 34 262 430 225 52 21 1024 Hours of Calm Data:

Hours of Invalid Data:

Page 9 of 15 30 Table 4 0

33

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 23:00:00.00 Stability Class: B Wind Speed at 60.00 Meter Level (MPH) 1 T

T 1*

I r

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

>24 TOTAL N

0 3

22 3

0 0

28 NNE 2

6 2

0 0

0 10 NE 1

7 5

0 0

0 13 ENE 0

9 5

0 0

0 14 E

2 5

4 0

0 0

11 ESE 0

5 4

1 0

0 10 SE 2

10 17 0

0 0

29 SSE 1

3 15 6

1 0

26 S

1 7

13 10 2

0 33 SSW 0

8 17 11 3

1 40 SW 1

8 14 15 0

0 38 WSW 2

4 10 6

1 0

23 W

0 5

11 8

3 3

30 WNW 1

6 9

11 6

3 36 NW 1

8 8

6 2

0 25 NNW 0

5 10 8

2 0

25 TOT 14 99 166 85 20 7

391 Hours of Calm Data:

Hours of Invalid Data:

0 3

Page 10 of 15 31 Table 4

Meteorological Data Continued

.Totals of Hours at Each Wind Speed & Direction 1 -JAN-2001 00:00:00.00 to 31 -DEC-2001 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

1 8

11 2

0 0

22 NNE 1

11 8

0 0

0 20 NE 2

4 5

0 0

0 11 ENE 1

6 3

1 0

0 11 E

0 9

6 0

0 0

15 ESE 1

7 6

3 0

0 17 SE 0

7 24 4

0 0

35 SSE 2

7 11 5

2 0

27 S

2 4

9 12 4

0 31 SSW 2

4 13 9

2 0

30 SW 3

7 14 7

0 3

34 WSW 0

4 6

2 1

0 13 W

0 10 12 10 5

2 39 WNW 1

7 6

9 1

1 25 NW 1

6 9

5 8

0 29 NNW 1

8 8

3 3

0 23 TOT 18 109 151 72 26 6

382 Hours of Calm Data:

Hours of Invalid Data:

0 6

Page 11 of 15 32 Table 4

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 23:00:00.00 Stability Class: D Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 F

8-12 13-18 19-24

>24 TOTAL N

3 23 37 24 5

0 92 NNE 2

33 32 6

2 0

75 NE 3

19 20 4

0 0

46 ENE 0

19 27 16 0

0 62 E

1 24 19 12 0

0 56 ESE 2

19 31 9

0 0

61 SE 2

17 33 22 5

0 79 SSE 4

17 40 29 7

0 97 S

6 13 39 49 20 4

131 SSW 3

27 45 28 13 2

118 SW 3

26 33 32 3

1 98 WSW 2

20 14 19 11 6

72 W

3 21 28 46 25 11 134 WNW 5

24 39 47 27 10 152 NW 4

22 55 54 20 1

156 NNW 5

27 31 48 14 4

129 TOT 48 351 523 445 152 39 1558 Hours of Calm Data:

Hours of Invalid Data:

1 81 Page 12 of 15 "I

Table 4

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31-DEC-2001 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 7

49 49 4

1 112 NNE 1

8 36 32 3

0 80 NE 3

25 63 14 1

1 107 ENE 2

12 67 54 0

0 135 E

2 6

54 31 2

0 95 ESE 1

10 70 78 10 0

169 SE 2

10 91 154 18 0

275 SSE 2

14 50 112 41 14 233 S

4 15 58 169 83 14 343 SSW 3

17 56 99 21 4

200 SW 1

7 42 66 12 10 138 WSW 2

13 42 48 13 11 129 W

2 10 42 129 26 3

212 WNW 3

11 43 102 26 1

186 NW 1

15 38 99 14 2

169 NNW 1

8 40 82 11 2

144 TOT 32 188 841 1318 285 63 2727 Hours of Calm Data:

Hours of Invalid Data:

2 260 Page 13 of 15 34 Table 4

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 3 1-DEC-2001 23:00:00.00 Stability Class: F Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

2 4

26 23 0

0 55 NNE 0

4 26 7

1 0

38 NE 2

4 31 12 0

0 49 ENE 0

2 52 22 0

0 76 E

1 4

54 10 0

0 69 ESE 1

2 46 35 3

0 87 SE 0

3 52 83 5

0 143 SSE 1

8 62 100 16 1

188 S

0 3

50 97 8

0 158 SSW 0

2 45 117 20 0

184 SW 1

2 32 51 16 0

102 WSW 0

4 26 23 5

0 58 W

0 4

18 21 1

0 44 WNW 0

4 15 43 0

0 62 NW 0

2 21 48 5

0 76 NNW 1

5 15 24 5

0 50 TOT 9

57 571 716 85 1

1439 Hours of Calm Data:

Hours of Invalid Data:

1 232 Page 14 of 15 Table 4 "I

Meteorological Data Continued Totals ofHours at Each Wind Speed & Direction 1-JAN-2001 00:00:00.00 to 31 -DEC-2001 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

1 3

18 7

1 0

30 NNE 0

1 16 20 0

0 37 NE 0

2 20 9

0 0

31 ENE 0

2 24 6

0 0

32 E

0 0

16 10 0

0 26 ESE 0

0 16 8

0 0

24 SE 1

2 8

7 1

0 19 SSE 0

3 27 19 1

0 50 S

0 3

20 39 0

0 62 SSW 0

2 15 21 2

0 40 SW 0

2 3

18 12 0

35 WSW 0

3 15 14 1

0 33 W

0 0

7 5

0 0

12 WNW 0

2 9

6 0

0 17 NW 0

0 5

3 0

0 8

NNW 0

3 13 8

1 0

25 TOT 2

28 232 200 19 0

481 Hours of Calm Data:

Hours of Invalid Data:

1 137 Page 15 of 15 Table 4

Dose at the Site Boundry and to the Nearest Resident From Gaseous Effluents SITE BOUNDARY NEAREST RESIDENT LOCATION: 1.40 km SSW LOCATION: 2.90 km NNW AGE GROUP: CHILD AGE GROUP: CHILD ORGAN UNITS DOSE

% LIMIT(a)

DOSE

% L MIT:(b) ]

1. GAMMA AIR DOSE
  • MRAD 4.27E-03 0.04 2.49E-03 N/A
2. BETA AIR DOSE
  • MRAD 7.86E-03 0.04 4.58E-03 N/A
3. WHOLE BODY ***

MREM 4.11E-03 N/A 2.45E-03 N/A

4. SKIN ***

MREM 8.09E-03 N/A 4.77E-03 N/A

5. BONE **

MREM 2.94E-04 N/A 7.65E-04 0.01

6. LIVER **

MREM 1.92E-03 N/A 8.88E-03 0.06

7. TOTAL BODY **

MREM 1.92E-03 N/A 8.43E-03 0.06

8. THYROID **

MREM 1.94E-03 N/A 1.21E-02 0.08

9. KIDNEY **

MREM 1.92E-03 N/A 8.52E-03 0.06

10. LUNG **

MREM 1.94E-03 N/A 8.41E-03 0.06

11. GI-LLI **

MREM 1.92E-03 N/A 8.37E-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 1 of 1 Table 5

Table 6 Dose to the Member of the Public From Activities within the Site Boundary EFFLUENT DIRECT DIRECT TOTAL DOSE WITHIN RADIATION RADIATION DOSE THE SITE FROM THE FROM OUTSID4 FOR THE ORGAN UNITS BOUNDARY UNIT TANKS YEAR

1. SKIN MREM 2.47E-03 N/A N/A 2.47E-03
2. BONE MREM 1.25E-04 8.79E-03 1.09E-02 1.98E-02
3. LIVER MREM 7.31E-04 8.79E-03 1.09E-02 2.04E-02
4. TOTAL BODY MREM 1.94E-03 8.79E-03 1.09E-02 2.16E-02
5. THYROID MREM 7.35E-04 8.79E-03 1.09E-02 2.04E-02
6. KIDNEY MREM 7.3 1E-04 8.79E-03 1.09E-02 2.04E-02
7. LUNG MREM 7.37E-04 8.79E-03 1.09E-02 2.04E-02
8. GI-LLI MREM 7.3 1E-04 8.79E-03 1.09E-02 2.04E-02 Page 1 of 1 38

Total Dose Due to the Uranium Fuel Cycle (Member of the Public)

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

% LIMITS *

1. SKIN MREM 1.71E-03 2.47E-03 4.17E-03 0.02
2. BONE MREM 1.56E-04 1.98E-02 2.OOE-02 0.08
3. LIVER MREM 1.99E-03 2.04E-02 2.24E-02 0.09
4. TOTAL BODY MREM 2.80E-03 2.16E-02 2.44E-02 0.10
5. THYROID MREM 2.47E-03 2.04E-02 2.29E-02 0.03
6. KIDNEY MREM 1.93E-03 2.04E-02 2.24E-02 0.09
7. LUNG MREM 1.92E-03 2.04E-02 2.23E-02 0.09
8. GI-LLI MREM 1.93E-03 2.04E-02 2.24E-02 0.09
  • Annual dose limits from 40CFR 190.10(a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

Page 1 of 1 39 Table 7

Dose Due to Liquid Effluents (Member of the Public)

ORGAN UNITS DOSE LIMIT

% LIMIT

1. BONE MREM 1.89E-02 10.00 1.89E-01
2. LIVER MREM 3.26E-02 10.00 3.26E-01
3. TOTAL BODY MREM 2.39E-02 3.00 7.96E-01
4. THYROID MREM 2.26E-03 10.00 2.26E-02
5. KIDNEY MREM 1.23E-02 10.00 1.23E-01
6. LUNG MREM 5.55E-03 10.00 5.55E-02
7. GI-LLI MREM 7.78E-03 10.00 7.78E-02
  • Annual dose limits of APA-ZZ-01003, Section 9.4.1. 1.

Page 1 of 1

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