ML021480210
| ML021480210 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/13/2002 |
| From: | Mccloskey P FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| DSC-02-00046 | |
| Download: ML021480210 (95) | |
Text
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2001 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ioniz ing radiation were recognized and efforts were made to establish radiation protection standards.
The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recommendations have been given legislative authority through publication in the Code of Fed eral Regulations (CFR) by the Nuclear Regulatory Commission (NRC).
The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA principle ap plies to reducing radiation dose both to the individual working at Davis-Besse and to the general public. "Reasonably achievable" means that exposure reduction is based on sound economic de cisions and operating practices. By practicing ALARA, Davis-Besse minimizes health risk and environmental detriment and ensures that doses are maintained well below regulatory limits.
Sources of Radioactivity Released During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The three types of radioactive material released are noble gases, io dine and particulates, and tritium.
The noble gas fission products in the primary coolant are given off as a gas when the coolant is depressurized. These gases are then collected by a system designed for gas collection and stored for radioactive decay prior to release.
Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if neces sary, prior to release.
Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive.
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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xenon-133 and xenon-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive no ble gases released. They are readily dispersed in the atmosphere.
Iodine and Particulates Annual releases of radioisotopes of iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys tems, minimize their discharge. The predominant radioiodine released is iodine-131 with a half life of approximately eight days. The main contribution of radioactive iodine to human dose is to the thyroid gland, where the body concentrates iodine.
The principal radioactive particulates released are fission products (e.g., cesium-134 and cesium 137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesium and cobalt con tribute to internal radiation exposure of tissues such as the muscle, liver, and intestines. These particulates are also a source of external radiation exposure if deposited on the ground.
Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neu tron interaction with deuterium (also a hydrogen isotope) present in the water and with the boron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or inhaled it is dispersed throughout the body until eliminated.
Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environment is minimal and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance pro grams for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.
The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which allow radioactivity in gases to decay prior to release via the station vent.
Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits.
These instruments provide a continuous indication of the radioactivity present. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded. If a monitor alarms, a release from a tank is automati cally stopped.
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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report All wastes are sampled prior to release and analyzed in a laboratory to identify the specific con centrations of radionuclides being released. Sampling and analysis provide a more sensitive and precise method of determining effluent composition than with monitoring instruments alone.
A meteorological tower is located in the southwest sector of the Station. It is linked to computers which record the meteorological data. Coupled with the effluent release data, the meteorological data are used to czaculate the dose to the public.
Beyond the plant, devices maintained in conjunction with the Radiological Environmental Monitoring Program constantly sample the air in the surrounding environment. Frequent sam ples of other environmental media, such as water and vegetation, are also taken to determine if buildup of deposited radioactive material has occurred in the area.
Exposure Pathways Radiological exposure pathways define the methods by which people may become exposed to ra dioactive material. The major pathways of concern are those which could cause the highest cal culated radiation dose. These projected pathways are determined from the type and amount of radioactive material released, the environmental transport mechanism, and the use of the envi ronment. The environmental transport mechanism includes consideration of physical factors, such as the hydrological (water) and meteorological (weather) characteristics of the area. An An nual average on the water flow, wind speed, and wind direction are used to evaluate how the ra dionuclides will be distributed in an area for gaseous or liquid releases. An important factor in evaluating the exposure pathways is the use of the environment. Many factors are considered such as dietary intake of residents, recreational use of the area, and the locations of homes and farms in the area.
The external and internal exposure pathways considered are shown in Figure 30. The release of radioactive gaseous effluents involves pathways such as external whole body exposure, deposi tion of radioactive material on plants, deposition on soil, inhalation by animals destined for hu man consumption, and inhalation by humans. The release of radioactive material in liquid efflu ents involves pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline while swimming.
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Ill j LLI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 29: The exposure pathways shown here are monitored through the Radiological Environmental Monitoring Program (REMP) and are considered when calculating doses to the public.
Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure route that will provide, for a specific radionu clide, the greatest dose to a population, or to a specific group of the population called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.
Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to ra diation involves the exposure of all organs. Most background exposures are of this form. Both non-radioactive and radioactive elements can enter the body through inhalation or. ingestion.
When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue.
The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the organ. Some ra dionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time.
The dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous release. The dose due to radioactive material released in gaseous effluents is calcu-85
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report lated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the average weather conditions at the time of the release, the locations of expo sure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inha lation, food consumption). The dose due to radioactive material released in liquid effluents is calculated using factors such as the total volume of liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming fac tors). These calculations produce a conservative estimation of the dose.
Results The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period from January 1, 2001 through December 31,2001.
"* Summation of the quantities of radioactive material released in gaseous and liquid effluents (Tables 17-21)
"* Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites (Table 22)
"* A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluent was:
Liquid Effluents:
- 7.75E-02 mrem, whole body
- 8.03E-02 mrem, thyroid Gaseous Effluents:
Noble Gas:
- 2.71E-04 mrad, whole body
e, 1.99E-03 mrem, whole body
- 2.54E-03 mrem, thyroid These doses are an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.
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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmnental Operating Report Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathways include the auxiliary feed pump turbine exhausts, the main steam safety valve system and the atmospheric vent valve system, steam packing exhaust and main feed water. For liquid effluents, the additional pathways include the Turbine Building drains via the settling ba sins. Releases via these pathways are included in the normal release tables in this report.
Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
Noble gases:
"* Released at a rate equal to or less than 500 mremn TEDE per year. (Note: the total dose due to these releases is also limited to 50 rnlrem in any calendar year.)
"* Released at a rate such that the total dose to the skin will be less than or equal to 3000 mrem in a year.
Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
e Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.
In accordance with IOCFR50, Appendix I, See. JIB. 1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year.
In accordance with 10CFR50, Appendix I, Sec. IC, dose to a member of the public from Iodine 131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gase ous effluents released to areas at and beyond the site boundary shall be limited to the following:
- Less than or equal to 15 total mrem to any organ in any calendar year.
Liquid Effluents In accordance with 10CFR50, Appendix I, See IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to accumulated doses of:
- Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ in any calendar year.
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Davis-Besse Nuclear Power Station 2001 Amnual Radiological Environmental Operating Report Effluent Concentration Limits The Effluent Concentration Limits (ECs) for liquid and gaseous effluents at and beyond the site boundary are listed in 10CFR20, Appendix B, Table II, Column 2, with the most restrictive EC being used in all cases. For dissolved and entrained gases the EC of 2.0E.-04 uCi/ml is applied.
This EC is based on the Xe-I 35 DAC of IE-05 uCi/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.
Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activa tion products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radio activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.
Measurements of Total Activity Fission and Activation Gases:
These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel flasks, or glass vials and are counted on a germanium detector for principal gamma emitters. Radionuclides that are detected are quantified via gamma spectroscopy.
Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation.
Iodine Iodine is collected on a charcoal cartridge filter and counted on a germanium detector. Specific quantification of each iodine radionuclide is via gamma spectroscopy.
Particulates Particulates are collected on filter paper and counted on a germanium detector. Specific quantifi cation of each radionuclide present on the filter paper is via gamma spectroscopy.
Liquid Effluents Liquid effluents are collected in a marinelli beaker and counted on a germanium detector. Quan tification of each gamma-emitting radionuclide present in liquid samples is via gamma spectros copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system.
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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Batch Releases Liquid from 1/1/01 through 12/31/01
- 1. Number of batch releases:
- 2. Total time period for the batch releases:
- 3. Maximum time period for a batch release:
- 4. Minimum time period for a batch release:
- 5. Average time period for a batch release:
Gaseous from 1/1/01 through 12/31/01
- 1. Number of batch releases:
- 2. Total time period for the batch releases:
- 3. Maximum time period for a batch release:
- 4. Minimum time period for a batch release:
- 5. Average time period for batch release:
51 85.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 133 minutes 81 minutes 100.6 minutes 6
61.92 hours0.00106 days <br />0.0256 hours <br />1.521164e-4 weeks <br />3.5006e-5 months <br /> 2473 minutes 172 minutes 619.2 minutes Abnormal Releases Total 2001 activity due to Abnormal Releases 0.0 Total 2001 Dose due to Abnormal Releases is 0.OOE+00 mRem Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent of limits, for January 1, 2001 through December 31, 2001.
PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1, 2001-December 31,2001 (gaseous)
Noble gases (gamma) 2.71E-04 mrad 10 mrad 2.71E-03 Noble gases (beta) 6.56E-04 mrad 20 mrad 3.28E-03 1-131, tritium and particulates 1.99E-03 mrem 15 mrem 1.33E-02 Report Period: January 1, 2001 - December 31, 2001 (liquid)
Total body 7.75E-02 mrem 3 mrem 2.58E+00 Organ 8.03E-02 mrem 10 mrem 8.03E-01 89 V
2--LLI-
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Sources of Input Data
- Water Usage: Survey of Water Treatment Plants (DSR-95-00347)
- 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating Report entitled, "Evaluation of Compliance with Appendix I to I OCFR50: Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricul tural Statistics and Livestock Marketing Account", the Agricultural Ministry of Ontario report entitled "Agricultural Statistics for Ontario, Publication 21, 1980",
the Michigan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981", and the Ohio Crop Reporting Service report entitled "Ohio Agri cultural Statistics, 1981".
- Gaseous and liquid source terms: Tables 17 through 21 of this report.
- Location of the nearest individuals and pathways by sector within 5 miles, see Land Use Census Section of the report.
- Population of the 50-mile Radius of Davis-Besse (DSR-95-00398).
Dose to Public Due to Activities Inside the Site Boundary In accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes an as sessment of radiation doses from radioactivity released in liquid and gaseous effluents to mem bers of the public due to activities inside the site boundary.
In special instances, members of the public are permitted access to the Radiologically Restricted Area within the Davis-Besse Station. Tours for the public are conducted with the assurance that no individual will receive any appreciable dose due to radioactivity released in gaseous or liquid effluents (i.e., not more than a small fraction of the 40 CFR190 standards.)
The Wellness Center, Pavilion, Training Center pond and the forebay/canal area located inside DBNPS Owner Controlled Area are accessible to members of the public. The Pavilion is acces sible to the public for social activities. The Training Center pond, forebay/canal area allows the member of the public to fish on site under a "catch-an-release" program; therefore the fish path way is not considered applicable. Considering the frequency and duration of the visits, the re sultant dose would be a small fraction of the calculated maximum site boundary dose. For pur poses of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:
e Exposure time for maximally-exposed visitors is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (I hr/day, 5 day/ week, 50 wk/yr)
"* Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).
" For direct "shine" from the Independent Spent Fuel Storage Installation (ISFSI),
default use of the maximum dose rate for a completed (full) ISFSI, and a distance of 950 feet.
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1l
- 1 [
Davis-Besse Nuclear Power Station 2001 Arnnual Radiological Environmental Operating Report The equations in the ODCM may be used for calculating the potential dose to a member of the public for activities inside the site boundary. Based on these assumptions, this dose would be at least a factor of 35 less than the maximum site boundary air dose, as calculated in the ODCM.
Nowhere onsite are areas accessible to the public where exposure to liquid effluents could occur.
Therefore, the modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.
Inoperable Radioactive Effluent Monitoring Equipment There were no radioactive effluent monitoring equipment required to be operable that was in operable for greater than 30 days during the reporting period.
Changes to the ODCM and PCP There were two alterations to the OCDM, Revision 14.0 and Rev. 15.0. The Process Control Program (PCP) had no changes in the reporting period.
Borated Water Storage Tank Radionuclide Concentration During the Reporting Period of 2001, the BWST tank concentration did not exceed the ODCM specification of Section 2.2.4. The sum of the limiting fraction of nuclides, a unitless number between 0 and 1, the BWST tank did not exceed the limit of 1. Of the ten samples taken for the reporting period of 2001, all samples analyzed for the sum of the limiting fractions of nuclides reported were <0.05.
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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents - Sulmantion of All Releases Type Fission and Activation Gases Total Release
.Average Release Rate for Perioda Percent of ODCM Limits lodines Total Iodines (1-131)
Average Release Rate for Period!
Percent of ODCM Limits Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period' Percent of ODCM Limits Unit 1st Qtr 2001 2nd Qtr 3rd Qtr 2001 2001 4th Qtr 2001 Ci 3.33E+00 3.09E+00 2.75E+00 5.93E+00 ptCi/sec 4.22E-01 3.93E-01 3.49E-01 7.52E-01 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Ci 5.24E-06 2.97E-05 5.66E+00 1.13E-04
ýtCiisec 6.65E-07 3.77E-06 7.18E-06 1.43E-05 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Ci 0.OOE+00 0.00E0-0 O.OOE+00 7.33E-07 ptCilsec O.OOE+L00 0.00E+00 0.OOE+00 9.30E-08 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Gross Alpha Activity Tritium Total Release Average Release Rate for Period&
Percent of ODCM Limits Ci O.OOE+00 O.OOE+00 0.00E+00 O.OOE-00 Ci 1.02E+01 7.33E+00 5.62E+00 4.78E+00 OCi/sec 1.29E.00 9.21E-01 7.12E-01 6.07E-0I See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination 2.5E+01 2.5E+01 a The average release rate is taken over the entire quarter. It is NOT averaged over the time period of the releases.
92 Est. Total
% Error 2.5E+01 2.5E+01 2.5E+0-1
E
-a J
11_
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases Batch Modea Unit Nuclide Fission Gases Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 I st Qtr 2001 2nd Qtr 2001 3rd Qtr 2001 4th Qtr 2001 Ci LLDb LLD LLD LLD LLD LID LLD LLD Total for Period:
N/A lodines LLDb LLD LLD LLD LLD LLD LLD LLD N/A LLDb LLD LID LLD LLD LLD LLD LLD N/A LLDb LLD LLD LLD LLD LLD LLD LLD N/A Ci 1-131 1-132 1-133 1-135 Total for Period:
Particulates and Tritium H-3 Sr-89
'Sr-90 Cs-134 Cs-137 Ba-140 Co-58 Total for Period:
9.6511-03 8.69E-03 1.1OE-02 6.35E-03 93 LLD LLD LLD LLD N/A LLD LLD LLD LLD N/A LLD LLD LLD LLD N/A Ci LLD LLD LLD LLD N/A 9.65E-03 LLD LID LLD LLD LLD LLD 8.69E-03 LLD LLD LLD LLD LLD LLD 1 °10E-02 LLD LLD LLD LLD LLD LLD 6.351E-03 LLD LLD LLD LLD LLD LLD
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 (Continued)
Gaseous Effluents - Ground Level Releases Continuous Modec Nuclide Fission Gases Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Unit lstQtr 2001 2nd Qtr 2001 3rd Qtr 2001 Ci LLDb LLD LLD LLD LLD LLD LID LLD N/A Total for Period:
LLDb LLD LLD LLD LLD LLD LLD LLD N/A LLDb LLD LLD LLD LLD LLD LLD LID N/A Ci 1-131 1-133 1-135 Total for Period:
Particulates and Tritium H-3 Sr-89 Sr-90 Cs-134 Cs-137 Ba-140 Total for Period:
1.1IE-02 1.13E-02 1.88E-02 2.34M-02 94 4th Qtr 2001 lodines LID LLD LLD LLD LID LID LLD LLD N/A LLD LLD LLD N/A LLD LLD LLD N/A LLD LID LLD N/A Ci LID LLD LLD N/A 1.11 E-02 LLD LLD LLD LLD LLD
IEl
_ 11 -l t Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 (Continued)
Gaseous Effluents - Ground Level Releases Continuous and Batch Mode Ar-41:
Kr-85:
Kr-85m:
Kr-87:
Kr-88:
Xe-13 Ir:
Xe-133:
Xe-133m:
Xe-135:
Xe-135m:
Xe-138:
1-131:
1-133:
1-135:
Mn-54 Fe-59:
Co-58:
Co-60:
Zn-65:
Mo-99:
Cs-134:
Cs-137:
Ce-141:
Ce-144:
Ba-140:
La-140:
Sr-89:
Sr-90:
<2.2E-08
<6.213-06
<2.0E-08
<3.4E-08
<4.013-08
<9.0E-08
<4.6E-08
<1.6E-07
<1.9E-08
<4.0E-07
<2.5E-07
<1.0E-07
<2.11E-08
<2.113-08
<2.OE-08
<4.013-08
<3.0E-08
<2.0E-08
<4.0E-08
<2.0E-07
<2.113-08
<3.013-08
<3.0E-08
<1.2E-07
<7.0E-08
<3.0E-08
<5.0E-08
<6.0E-09 iCimrnI pCi/ml
- Ci/ml pCi/fil iCi/ml gCi/nl pCi/ml
ýCi/mnl ACi/ml gCi/nml gCi/nm pCi/mi jiCi/nil i+/-Ci/ml gCiiml gCi/nil gCi/mi RCi/mI pCi/nml gtCi/rnl pCi/rnl j~i/n-l pCi/ml pCi/mi pCi/nil gCi/nil pCi/rm a
Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release are listed as batch releases.
b These radionuclides were not identified in concentrations above the lower limit of detection (LLD).
c Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases.
95
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Unit 2001 2001 2001 2001 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133mn Xe-135 Xe-135m Xe-138 Xe-131m Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci LLD 1.06E-01 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.74E-02 LLD LLD LLD LLD Ci LLD LLD LLD 2.05E-01 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.54E-01 LLD LLD LLD 7.24E-01 LLD LLD LLD LLD 4.10E-02 Total for Period:
1.06E-01 1.74E-02 2.05E-01 1.12E+00
- Iodines 1-131 1-132 1-133 1-135 Total for Period:
- Particulates H-3 Total for Period:
Ci Ci Ci LLD LLD LLD Ci LLD LLD LLD LLD LLD Ci LWD LLD Ci 1.21E-03 5.85E-04 Ci 1.21E-03 5.85E-04 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.06E-02 4.65E-03 3.06E 4.65E-03
- Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Sta tion Vent) 96 Nuclide Fission Gases
rt 1
nI _LI _
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 19 (Continued)
Gaseous Effluents - Mixed Mode Releases Continuous Mode Unit 1st Qtr 2001 2nd Qtr 2000 3rd Qtr 2000 4th Qtr 2000 Fission Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci LLD LLD LLD LLD LLD 2.88E+00 LLD 3.39E-01 LLD LLD LLD LLD LLD LLD LLD 2.65E+00 LLD 4.23E-01 LLD LLD LLD LLD LLD LLD LLD 1.84+00 LLD 7.11 E-01 LLD LLD LLD LLD LLD LLD LLD 4.57E+00 LLD 2.40E-01 LLD LLD Total for Period:
3.22E+00 3.07+00 2.55E+00 4.8 IE+00 lodines 1-131 1-133 1-135 1-132 Ci Ci Ci Ci Total for Period:
5.24E-06 LLD LLD LLD 5.24E-6 3.32E-05 1.11 E-04 2.62E-04 Particulates and Tritium H-3 Sr.89b.0 Sr-90b6*
Cs-134 Cs-137 Ba-140 Co-58 La-140 Co-60 Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.02E+01 LLD LLD LLD LLD LLD LLD LLD LLD Total for Period:
1.02E+01 7.31E E+00 5,56E+00 4.75E+00 97 Nuclide 2.97E-05 3.52E-06 LLD LLD 5.66E-05 5.39E-05 LLD LLD 1.13E-04 1.49E-04 LLD LLD 7.3 1E-÷-00 LLD LLD LLD LLD LLD LLD LLD LLD 5.56E+00 LLD LLD.
LLD LLD LLD LLD LLD LLD 4.75E+00 LLD LLD LLD LLD LLD 7.33E-07 LLD LLD
Da-,,is-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating ReLport Table 19 (Continued)
Gaseous Effluents - Mixed Mode Releases Continuous Mode' Ar-41 Kr-85 K~r-85m Kr-87 Kr-88 Xe-131m, Xe-133m.
Xe-135 Xe-135m.
Xe-I 38 1-135' Mn-54c Fe-59c Co-58c Co-60c Zn-65 Mo-99c Cs-i34' Cs¶37c Ce-14 I' Ce-144c Ba-140C La-14O Sr-89b'r Sr-9ObC Kr-87 Kr-88 Xe-i 35 Xe-13 5m Xe-138 Ar-41 Kr-85 Xe-133 Xe-133m,
<2.9E-08
<3.3E-06
<1 313-08
<6.OE-08
<6.OE-O8
<4.4E-07
<7.2E-08
<I IE-08
<5.9E-06
<z.OE-O5
<3.9E-10
<2.6E-14
<3.013-14
<3.OE-14
<2.5E-14
<I.OE-13
<1.8E-14
<1,613-14
<1.3E-14
<1.2E-13
<1.2E-14
<4.013-14
<1.O13-14
<9.3E-16
<3. 1E-1 6 Batch Modes
<4.SE-06
<6.6E-06
<1.E-O5
<2.lE-06
<2.813-05
<1.8E-06
<1.2E-06
<2.4B-06
<1.OE-05 RCi/mid VCi/nil pCi/mil g.Ci/mI gCi/miA 9+/-Ci/nil pLci/mi LLCi/ml a
These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is listed.
b Quarterly corrposite sample for continuous mode.
c Analysis not required for batch release.
98 P.Ci/nl pCi/mid liCi/mni tiLCi/m1.
p;Xi/nil p~Ci/ml JlCi/mfl jliCi/nml gCi/mi pCi/nil gCi/mid 9Ci/mi pCi/miA pCi/ni]
pCi/min ICimln) pCi/mi PCi/mi pCi/nil ACi/mi piCi/nil PCi/mi pCi/nil
EI
] -11 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Liquid Effluents -
Table 20 Summation of All Releases Type Fission and Activation Products Total Release (without Tritium, Gases, Alpha)
Average Diluted Concentration During Period' Percent of ODCM Limits Percent of IOCFR20 Limit Tritium Total Release Average Diluted Concentration During Period&
Percent of 10CFR20 Limit Dissolved and Entrained Gases Total Release Average Diluted Concentration During Perioda Percent of IOCFR20 Limit Gross Alpha Total Release Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2001 2001 2001 2001
% Error Ci 3.37E-03 1.08E-03 1.20E-03 jCi/ml 3.24E-10 1.0113-10 9.75E-11 5.55E-04 2.0E+01 5.18E-!1 See Supplement information in ODCM Release Limits Sec tion 2.16E-03 1.61 E-03 1.65E-03 3.26E-03 Ci jPCi/ml 1.65E+02 1.58E-05 1.36E+02 1.27E-05 1.29E+02 1.05E-05 1.361+02 1.27E-05 2.OE+01 1.58E+00 1.27E+00 1.051+00 1.27E+0 Ci pCi/ml 1.39E-05 1.33E-12 4.68E-04 4.36E-1 1 5.46E-05 4.441-12 1.99E-03 1.86E-10 2.0E+01 6.67E-07 2.18E-05 2.221-06 9.301-05 Ci 0.00E+00 0.00E+00 0.00t+00 4.61E-03 2.0E+01 Volume of Waste Released (prior to dilution)
Batch Continuous Volume of Dilution Water Batch Continuous Total Volume of Water Released liter 3.45E+05 liter 9.05E+07 liter liter liter 1.01E+08 1.02E+1 0 1.04E+i 0
' Tritium and alpha are found in both continuous and batch releases. Average diluted concentrations are based on total volume of water released during the quarter. Fission and Activation products and Dissolved and Entrained Gases are normally only detected in batch releases.
99 3.42E+05 8.04E+07 1,01 E+08 1.06E+10 1.07E+10 3.73E+05 7.97E+07 1.10E1+08 1.21 E+ 10 1.23E+10 3.96E+05 1.02E+08
- 1. 17E+08 1.05E+10 1.07E+10 2.0E+01 2.OE+01 2.0E+01 2.0E+01
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 Liquid Effluents - Nuclides Released Batch Releases Nuclide Fission and Activation Products Co-58 Co-60 Ag-110m Sb-125 Cs-134 Cs-137 Sr_89a, b Sr.90, b Fe-55 Cr-51 1-131 1-132 1-133 Te-132 Tc-99m Sb-124 Sn-113 Ru-103 Mn-54 Np-239 Co-57 Nb-95 Zr-95 Se-75 Fe-59 Zn-65 Ce-144 Na-24 Zr-97 Ce-141 Nb-97 La-140 Ba-140 Ru-106 Ba-139 Mo-99 Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1 st Qtr 2001 6.40E-05 7.42E-05 5.55E-04 2.36E-03 6.90E-06 1.32E-05 LLD LLD 1.97E-04 7.11E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 2.53E-05 LLD LLD LLD LLD LLD LLD LLD 2 nd Qtr 2001 3.95E-05 1.37E-04 3.84E-04 4.67E-04 LLD LLD LLD LLD LLD LLD 4.44E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 7.73E-06 LLD LLD LLD LLD LLD LID LLD 3rd Qtr 2001 1.24E-04 1.28E-04 7.96E-04 LLD LLD 8.17E-07 LLD LLD 1 32E-04 LLD 1.88E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 4th Qtr 2001 1.34E-03 1.80E-05 7.52E-05 LLD LLD 4.23E-07 LLD LLD 1.15E-04 LLD 3.12E-04 LLD 2.OOE-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.43E-06 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Total for Period:
Ci 3.37E-03 1.08E-03 1.20E-03 5.55E-04 100
rn 11 111 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclides Released Batch Releases Nuclide Tritium Unit Ci 1 st Qtr 2nd Qtr 2001 2001 3rd Qtr 2001 4th Qtr 2001 1.65E+02 1.36E+02 1.29E+02 1.36E+2 Dissolved and Entrained Gases Kr-85m Kr-85 Xe-131m Xe-133 Xe-135 Xe-133m 1-135 Ci Ci Ci Ci Ci Ci Ci Ci Total for Period:
LLDa LLD LLD 1.39E-05 LLD LLD LLD LLDa LLD LLD 4.68E-04 LLD LLD LLD LLDa LLD LLD 5.38E-05 8.69E-07 LLD LLD LIDa LLD LLD 1.94E-03 4.68E-05 LLD LLD 1.39E-05 4.68E-04 5.47E-05 1.99E-03 101
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclides Released Continuous Releases Nuclide Unit Fission and Activation Products Cr-51 Fe-59 Co-58 Co-60 Zn-65 Sr.89B"b Srt90ab Nb-95 Zr-95 Mo-99 Tc-99m 1-131 Cs-134 Cs-137 Ba-140/La-140 Ce-141 Total for Period:
Tritium Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci NI/A 2nd Qtr 2001 I st Qtr 2001 LLDa LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3rd tr
'nil vrr 3rd Qtr 420 0tr 2001 2001 LLDV LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LID LID LLD N/A 2.37E-01 1.29E-01 2.97E-01 9.45E-02 Dissolved and Entrained Gases Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 Total for Period:
LLDa LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD N/A Ci Ci Ci Ci Ci Ci LLD LLD LLD LLD LLD N/A LID LLD LLD LLD LLD N/A LLD LLD LLD LLD LLD N/A LLD LLD LLD LLD LLD N/A 102 LLDa LLD LLD LLD LLD LLD LLD LLD LID LLD LLD LLD LLD LLD LLD LLD N/A
El
- _ILLJ Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclides Releaseda Na-24 Cr-51 Mn-54 Fe-55b Fe-59 Co-57 Co-58 Co-60 Zn-65 Se-75 Sr-89b Sr-90b Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Ru-103 Ag-110m Sn-i 13
<2.OE-08
<1.7E-07
<2.1E-08
<7.OE-07
<4.2E-08
<1.6E-08
<1.9E-08
<2.5E-08
<5.2E-08
<2.4E-08
<3.OE-08
<8.OE-09
<4.OE-08
<2.SE-08
<2.IE-08
<1.6E-07
<1.8E-08
<2.2E-08
<2.5E-08
<2.8E-08 pCi/mI tCi/ml pCi/ml pCi/ml PCi/mi pCi/ml gCi/ml IpCi/mi
- .tCi/mi pCi/mi pCi/mi pCi/ml pCi/ml pCi/ml pCi/ml pCi/ml PCi/mi pCi/ml pCi/ml pCi/ml Sb-124 Sb-125 Te-132 Ce-141 Ce-144 Cs-134 Ce-136 Cs-137 Ba-140 La-140 Np-239 1-131 1-132 1-133 1-135 Kr-85 Xe-131 Xe-133 Xe-133m Xe-135
<1.OE-08
<1.7E-08
<1.8E-08
<3,0E-08
<1.7E-07
<2.IE-08
<2.8E-08
<2.7E-08
<7.OE-08
<3.OE-08
<1.2E-07
<2.5E-08
<1.OE-08
<2.1E-08
<1.7E-07
<6.2E-06
<7.7E-07
<4.6E-08
<1.6E-07
<1.9E-08 pCi/ml pCi/ml pCi/ml pCi/ml pCi/ml pCi/ml PCi/ml pCi/mi pCi/mI pCi/ml gCi/mi aCi/mi pCi/ml gCi/mi ptCii/ml gCi/mi tCi/ml pCi/mi PCi/ml RCi/mi 2 These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is used for each radionuclide. LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.
b Quarterly composite sample 103
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 22 Solid Waste and Irradiated Fuel Shipments A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) r T
y'...i i2-montfl rL. ZUWI I T..4-12-monm Error. %
- 1. Type of Waste
- a. Spent resins, filter sludges, mn 3
5.45E+00 2.5E+01 evaporator bottoms, etc.
Ci 2.03E+02 2.5E+01
- b. Dry compressible waste, rn3 1.02E+02 2.5E+01 contaminated equip., etc.
Ci 3.85E+00 2.5E+01
- c.
Irradiated components, mn 3
control rods, etc.
Ci N/A N/A
- d. Others: dewatered primary mn 3
9.10E-02 2.5E+01 system cartridge filters Ci 1.44E-02 2.5E+01
- a. Spent Resins
- b. Dry compressible waste, contaminated equipment, etc.
- e. None
- d. Cartridge filters Fe" Co60 Ni63 Cs134 Cs137 Fe"'
Co60 Ni63 Co58 Fe" Co 58 Ni 63 Agli°m Zr95 Co06 C14 Percent (%)
2.78E+00 7.71E+00 2.93E+01 4.76E+00 5.38E+02 6.38E+01 1.75E+01 3.59E+00 6.54E+00 2.OOE+00 2.63E+01 5.26E+01 5.06E+00 2.36E+00 1.49E+00 5.37E+00 1.96E+00 Est. Total Error, %
2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+0l 2.50E+01 2.50E+01 104
- 2. Estimate of major nuclide composition tby type of waste;
El H1XLL Dav is-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 22 (continued)
Solid Waste and Irradiated Fuel Shipments
- 3. Solid Waste Disposition Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Volume disposed Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Volume disposed Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Volume disposed Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Volume disposed Number of Shipments Mode of Transportation Destination Type of Container (Container Volume)
Volume shipped for processing Volume disposed B. IRRADIATED FUEL SHIPMENTS 2
Truck STUDSVIK Processing Facility, Erwin TN For processing then disposal at Barnwell S.C.
High Integrity Container (3.75 m3) 7.5 mn 3
0.64m 3 4
Truck US Ecology, Oak Ridge, TN for processing then disposal at Envirocare of Utah Metal boxes (36.3 m 3) 194.05 mn 3
39.96 M 3
1 Truck ATG Inc. Richland Washington for processing then disposal at Envirocare of Utah or Bamwell S.C.
Metal Boxes (2.6 m3) 8.15 m3 Processing not complete in 2001 Est. 0.82 n3 1
Truck ATG Inc, Oak Ridge Tenn. for processing then disposal at Barnwell S.C.
High Integrity Container (5.72m3) 5.72 mn 3
5.72 rn3 9
Truck ALARON Corp., Wampami Pa. For processing then Disposal at Envirocare of Utah.
Metal Boxes (73.42 mn
- 3) 259.83 m 3 (spent fuel racks)
Processing not complete in 2001 Est. 61.28 in3 105
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 23 Doses Due to Gaseous Releases for January through December 2001 Maximum Individual Dose Due to 1-131, 1H-3 and Particulates with Half-Lives Greater than 8 days.
Whole Body Dose 1.99E-03 mrem Significant Organ Dose 2.54E-03 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 2.71E-04 mrad Skin Dose 9.27E-04 mrad Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.
Total Integrated Population Dose 7.02E-03 person-rem Average Dose to Individual in Population 3.21E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 5.03E-04 person-rem Average Dose to Individual in Population 2.30E-07 mrem 106
El I
is ALI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 2001 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose Population Dose Total Integrated Population Dose Average Dose to Individual 7.75E-02 mnrem 8.03E-02 mremr 7.31E-01 person-rem 3.35E-04 mrern 107
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 25 Annual Dose to The Most Exposed (from all pathways) Member of The Public 2001 ANNUAL DOSE 40CFRI90 LIMIT PERCENT OF (mrem)
(mrem)
LIMIT Whole Body Dose*
Noble Gas 2.98E-04 Iodine, Tritium, Particulates 1.99E-03 Liquid 7.75E-02 Total Whole Body Dose 7.98E-02 25 3.19E-01 Thyroid Dose Iodine, Tritium, Particulates 8.28E-02 75 1.1 OE-01 Skin Dose Noble Gas 1.02E-03 25 4.08E-03 Significant Organ Dose 8.28E-02 25 3.31E-01 (Thyroid)
Meteorological Data Meteorological data on 3Y inch microdisk for January through December 31, 2001, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555.
- Direct radiation from the facility is not distinguishable from natural background and is, therefore, not included in this compilation.
108
Land Use Census
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information neces sary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use Cen sus is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. The Land Use Census identifies gaseous pathways by which radioactive mate rial may reach the general population around Davis-Besse. The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these programs are as cur rent as possible. The pathways of concern are listed below:
"* Inhalation Pathway - Internal exposure as a result of breathing radionuclides car ried in the air.
"* Ground Exposure Pathway - External exposure from radionuelides deposited on the ground Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.
Vegetation Pathway - Internal exposure as a result of eating vegetables, fi-uit, etc.
which have a build up of deposited radioactive material or which have absorbed ra dionuclides through the soil.
" Milk Pathway - Internal exposure as a result of drinking milk, which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides.
Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each meteorological sector within a five mile radius of Davis-Besse.
The siurveillance portion of the 2001 Land Use Census was performed during the month of August. In order to gather as much information as possible, the locations of residences, dairy cows, dairy goats, and vegetable gardens were recorded. The residences, vegetable gardens, and milk animals are used in the dose assessment program. The gardens must be at least 500 square feet in size, with at least 20% of the vegetables being broadleaf plants (such as lettuce and cab bage).
Each residence is tabulated as being an inhalation pathway, as well as ground and plume expo sure pathways. Each garden is tabulated as a vegetation pathway.
109
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi nute series of the relevant quadrangles) which has been divided into 16 equal sectors corre sponding to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the vent at Davis-Besse.
Results The following changes in the pathways were recorded in the 2001 census:
"* S Sector - A garden at 5830 meters replaced a garden at 4960 meters
"* SW Sector - The garden at 5400 meters was replaced by a garden at 5180 meters.
"* WSW Sector - The garden at 4270 meters was replaced with a garden at 7430 meters.
"* SE Sector - a residence at 8000 meters was added.
"* SW Sector - the former closest residence was replaced with a residence at 1070 meters.
The critical receptor identified by the 2001 Land Use Census is a garden in the W sector at 1610 meters from Davis-Besse.
The detailed list in Table 26 was used to update the database of the effluent dispersion model used in dose calculations. Table 26 is divided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector.
Table 27 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the' methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in cal culating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.
110
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 31: Land Use Census Map ill cot z
0 w
(0 z
w U)
U,,
LU in 5:D 4h 0 w 0 z 0
2 0
LI 2 w 0
5 0
-j 0
I
.PdFi Radioactive Effluent Release Report
Davis-Besse Nuclear Power Station 2001. Annual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2001 Sector Distance from Station (meters)
Closest Pathways N
880 Inhalation Ground Exposure Plume Exposure NNE 880 Inhalation Ground Exposure Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure ENE,, E, ESE N/A Located over Lake Erie SE**
8000 Inhalation Ground Exposure Plume Exposure SSE 2860 Vegetation SSE 1970 Inhalation Ground Exposure Plume Exposure S**
5830 Vegetation S
1030 Inhalation Ground Exposure Plume Exposure SSW 2350 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SW**
5180 Vegetation SW**
1070 Inhalation Ground Exposure Plume Exposure
"**Changes since 2000 112
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 26 (continued)
Closest Exposure Pathways Present in 2001 Sector WSW WSW**
W W
Distance from Station (meters) 1540 7430 980 1610 1750 WNMT NW NW 1490 2300 1270 NNW Closest Pathways Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure
- Changes since 2000 113 RL
- -ý
-I-LL-
Davis-Besse Nuclear Power Station 2001 Annual Radiological Envirornmental Operating Report Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)
Parameters CRITICAL PATHWAY Inhalation Inhalation Inhalation Inhalation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Inhalation Vegetation Inhalation AGE GROUP Child Child Child Child Child Child Child Child Child Child Child Child Child X/Q (SEC/M
- 3) 9.15E-07 1.24E-06 1.26E-06 D/Q (M_)
8.40E-09 1.44E-08 1.58E-08 3.43E-8 1.45E-10 6.91E-08 2.90E-08 5.90E-08 3.85E-08 3.40E-08 2.77E-07 1.46E-07 6.98 E-08 2.41E-07 8.13E-10 1.67E-10 1.03E-09 3.40E-10 1.80E-10 4.37E-09 1.72E-09 5.79E-10 1.73E-09
- Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present.
- Changes since 2000 114 SECTOR N
NNE NE ENE*
E*
ESE*
SE**
SSE S**
SSW SW**
WSW`**
W WNW NW NNW METERS 880 880 900 8000 2860 5830 2350 5180 7430 1610 1750 2300 1270
7 Non-Radiological Environmental Programs
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environrmental Operating Report Non-Radiological Environmental Programs Meteorological Monitoring The Meteorological Monitoring Program at Davis-Besse is required by the Nuclear Regulatory Commission (NRC) as part of the program for evaluating the effects of routine operation of nu clear power stations on the surrounding environment. Both NRC regulations and the Davis Besse Technical Requirements Manual provide guidelines for the Meteorological Monitoring Program. These guidelines ensure that Davis-Besse has the proper equipment, in good working order, to support the many programs utilizing meteorological data.
Meteorological observations at Davis-Besse began in October 1968. The Meteorological Moni toring Program at Davis-Besse has an extensive record of data with which to perform clima tological studies which are used to determine whether Davis-Besse has had any impact upon the local climate. After extensive statistical comparative research the meteorological personnel have found no impact upon local climate or short-term weather patterns.
The Meteorological Monitoring Program also provides data that can be used by many other groups and programs: Radiological Environmental Monitoring Program, The Emergency Prepar edness Program, The Chemistry Unit, and groups such as Plant Operations, Plant Security, Mate rials Management, Industrial Safety Program, plant personnel and members of the surrounding community.
The Radiological Environmental Monitoring Program uses meteorological data to aid in evalu ating the radiological impact, if any, of radioactivity released in Station effluents. The meteoro logical data is used to evaluate radiological environmental monitoring sites to assure the program is as current as possible. The Emergency Preparedness Program uses meteorological data to cal culate emergency dose scenarios for emergency drills and exercises and uses weather data to plan evacuations or station isolation during adverse weather. The Chemistry Unit uses meteorological data for chemical spill response activities, marsh management studies, and wastewater discharge flow calculations. Plant Operations uses meteorological data for cooling tower efficiency calcu lations, forebay water level availability and plant work which needs certain environmental con ditions to be met before work begins. Plant Security utilizes weather data in their routine plan ning and activities. Materials Management plans certain plant shipments around adverse weather conditions to avoid high winds and precipitation, which would cause delays in material deliveries and safety concerns. industrial Safety uses weather and climatological data to advise personnel of unsafe working conditions due to environmental conditions, providing a safer place to work.
Legal Affairs uses climatological data for their investigation into adverse weather accidents to the plant and personnel.
115
11 Davis-Besse Nuclear Power Station 2001 Anuial Radiological Enviromnental Operating Report On-site Meteorological Monitoring
System Description
At Davis-Besse there are two meteorological systems, a primary and a backup. They are both housed in separate environmentally controlled buildings with independent power supplies. Both primary and backup systems have been analyzed to be "statistically identical" to the other so if one system fails the other can take its place. The instrumentation of each system follows:
PRIMARY BACKUP 100 Meter Wind Speed 100 Meter Wind Speed 75 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 100 Meter Wind Direction 75 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 100 Meter Delta Temperature 75 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Ambient Temperature 10 Meter Dew Point 10 Meter Solar Incidence Precipitation Meteorological Instrumentation The meteorological system consists of one monitoring site located at an elevation of 577 feet above mean sea level (IGLD 1955)*, a l00m free-standing tower located about 3,000 feet SSW of the cooling tower, and an auxiliary l0m foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The l00m tower has primary and backup instruments for wind speed and wind direction at 100m and 75m. The l00m tower also measures differential temperature (delta Ts): 100-10m and 75-10m. The i0m tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 10m tower.
According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a mini mum of five instruments are required to be operable at the two lower levels (75m and 10m) to measure temperature, wind speed, and wind direction. During 2001, annual data recoveries for all required instruments were 99.27 percent. Minor losses of data occurred during routine in strument maintenance, calibration, and data validation.
Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are performed by in-house facilities and by an outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations and plant specifications.
- International Great Lakes Data - 1955 116
Davis-Besse Nuclear Power Station 2001 Anuial Radiological Environmental Operaiing Report Meteorological Data Handling and Reduction Each meteorological system, primary and backup, have two Campbell Scientific Dataloggers (model 21XL) assigned to them. The primary system has a first datalogger to communicate 900 second averages to the control room via a Digital Alpha computer system. This is a dedicated line. If a failure occurs at any point between the primary meteorological system and the control room the control room can utilize the second data logger in the primary shelter. Each datalogger has its own dedicated communication link with battery backup. The backup meteorological sys tem is designed the same as the primary; so to lose all meteorological data the primary and backup meteorological systems would have to lose all four dataloggers. However, this would be difficult since each is powered by a different power supply and equipped with lightning and surge protection, plus four independent communication lines and datalogger battery backup.
The data from the primary and backup meteorological systems are stored in a 30-day circular storage module with permanent storage held by the Digital Alpha computer. Data goes back to 1988 in this format and to 1968 in both digital and hardcopy formats. All data points are scruti nized every 900 seconds by meteorological statistics programs running continuously. These are then reviewed by meteorological personnel daily for validity based on actual weather conditions.
A monthly review is performed using 21 NRC computer codes, which statistically analyze all data points for their availability and validity. If questionable data on the primary system can not be corroborated by the backup system, the data in question is eliminated and not incorporated into the final database. All validated data is then documented and stored on hard copy and in digital format for a permanent record of meteorological conditions.
Meteorological Data Summaries This section contains Tables 28-30, which summarize meteorological data collected from the on site monitoring program in 2001.
Wind Speed and Wind Direction Wind sector graphics represent the frequency of wind direction by sector and the wind speed in mph by sector. This data is used by the NRC to better understand local wind patterns as they relate to defined past climatological wind patterns reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speeds for 2001 were 51.03 mph for the 100m level on April 12, 45.85 mph for the 75m level on October 25, and 39.02mph for the 10m level on April 12.
Figures 32-34 give an annual sector graphic of average wind speed and percent frequency by di rection measured at the three monitoring levels. Each wind sector graphic has two radial bars.
The darker bar represents the percent of time the wind blew from that direction. The hatched bar represents the average wind speed from that direction. Wind direction sectors are classified us ing Pasquill Stabilities. Percent calms (less than or equal to 1.0 mph) are shown in the middle of the wind sector graphic.
117
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2001 are given in Table 29.
These data are measured at the 10m level; with differential temperatures taken from 100m and 75m levels. The yearly average ambient temperature for 2001 was 51.86 0F. The maximum temperature was 92.28°F on August 8 with the minimum temperature of 4.78°F on January 02.
Yearly average differential temperatures were -0.21°F (100m), and -0.07°F (75m). Maximum differential temperatures for 100m and 75m levels were 7.990F on December 11, (100m), and 7.99°F on November 11, (75m). Minimum differential temperatures for 100m and 75m levels were -4.0G0F on September 8, (100m) and -2.86'F on April 18, (75m). Differential tempera tures are a measurement of atmospheric stability and used to calculate radioactive plume disper sions based on Gaussian Plume Models of continuous effluent releases.
Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point and humidity temperatures for 2001 are provided in Table 29. These data are measured at the 10 meter level. The average dew point temperature was 43.05'F with a maximum dew point temperature of 77.10°F on July 23. Please note that dew point temperatures above 75WF are highly suspect and are possibly due to calm winds and high solar heating allowing the aspirated dew point processor to retain heat. The minimum dew point (dew point under 32WF is frost point) temperature was 3.76"F on January 9. Average rela tive humidity is 73.52 percent for the year. The maximum relative humidity was 100.00 percent on November 11. The minimum relative humidity was 27.11 on May 4. It is possible to have relative humidity above 100 percent, which is known as supersaturation.
Conditions for super saturation have been met a few times at Davis-Besse due to its close proximity to Lake Erie and the evaporative pool of moisture available by such a large body of water.
Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 2001 are given in Table 29. To tal precipitation for the year was 22.91 inches. The maximum daily precipitation total was 1.34 inches in September. The minimum was 0.19 inches recorded in January. It is likely that pre cipitation totals recorded in colder months are somewhat less than actual due to snow/sleet blowing across the collection unit rather than accumulating in the gauge.
Lake Breeze and Lake Level Monitoring Lake Breeze is monitored at Davis-Besse because of its potential to cause major atmospheric/
dispersion problems during an unlikely radioactive release. A lake breeze event occurs during the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation, which draws air from the water to the land during the daytime, creating a "Lake Breeze" effect. This event could be problematic if a release were to occur because diffusion would be slow thus cre ating an adverse atmosphere to the surrounding site.
Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi nate high or low lake level information. This data is critical in the running of the plant due to the 118
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report large amounts of water needed to cool plant components. If water levels get too low the plant operators can take measures for the safe shutdown of the plant. Since Lake Erie is the shallowest of the Great Lakes, it is not uncommon for a plus or minus five feet lake level fluctuation to oc cur within an eight to ten hour period, High water levels also effect the plant due to emergency transportation and evacuation pathways.
119
10Gm Wind Speed 100M Wind Direction 75M Wind speed 75M Wind Direction 1GM Wind Speed I OM Wind Direction 10M Ambient Air Temp 10M Dew Point Temp Delta T (1OOM-IOM)
Delta T (75M-lOM)
Joint 10GM Winds and C3 Delta T (100M-1OM)
Joint 75M Winds and Delta T (IOOM-IOM)
Joint 1GM Winds and Delta T (75M-10M)
JAN 100 100 100 100 100 100 100 100 100 l00 100 100 100 FEB 94.20 100 100 100 100 100 100 100 100 100 MAR 100 100 100 100 100 100 100 100 100 100 APR 99.17 99.17 99.17 99.17 99.17 99.17 99.17 99.17 99.17 99.17 MAY 100 100 100 100 100 100 100 100 100 100 94.20 100 99.17 100 100 100 100 99.1.7 100 JUN 100 100 100 100 100 100 too 100 100 100 JUL 100 100 100 100 100 100 99.87 100 99.87 99.87 AUG 100 100 100 100 100 100 98.92 100 98.92 98.92 100 99.87 98.92 100 99.87 98.92 100 99.17 100 100 99.87 98.92 SEP 100 100 100 100 100 100 100 100 100 100 OCT 96.64 100 96.91 100 97.18 100 88.31 99.73 88.17 88.17 NOV DEC 100 100 100 100 100 100 100 100 100 100 99.73 99.73 99.73 99.73 99.73 99.73 99.73 99.73 99.73 99.73 2001 99.18 99.91 99.65 99.91 99.67 99.91 98.81 99.89 98.80 98.80 100 87.23 100 99.73 98.28 100 87.37 100 99.73 98.73 100 87.37 100 99.73 98.76
- all data for individual months expressed as percent of time instrument was operable during the month, divided by the rnaxiimiin number of hours in that month that the instrument could be operable. Values for annual data recoveries equals the percent of time instrument was operable during the year, divided by the number of hours in the year that the instrument was operable.
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100M WIND Max Speed (mph) 33.83 48.50 41.33 51.03 34.01 38.54 25.32 25.62 32.99 48,35 Date of Max Speed 01/03 02/25 03/06 04/12 05/04 06/12 07/26 08/16 09/24 10/25 Min Speed (mph) 1.33 2.80 2.12 2.46 2.38 1.44 1.42 1.53 0.81 2.13 Date of Min Speed 01./12 02/13 03/29 04/30 05/17 06/08 07/30 08/10 09/30 10/21 Ave WindSpeed 17.42 18.01 16.88 18.13 15.38 12.44 1.2.73 1.2.63 15.13 19.73 75M WIND Max Speed (mph) 31.90 44.76 39.08 42.93 32.17 35.25 23.17 23.99 31.75 45.85 Date of Max Speed 01/03 02/25 03/06 04/12 05/21 06/12 07/01 08/1.6 09/24 10/25 Min Speed (mph) 1.94 2.53 1.32 1.96 2.87 1.47 1.65 1.41 1.35 1.94 Date of Min Speed 01/12 02/13 03/19 04/30 05/18 06/08 07/13 08/10 09/15 1.0/21 Ave Wind Speed 15.80 16.18 15.45 16.54 14.03 11.52 11.88 11.56 13.82 17.99 10M WIND Max Speed (mph) 23.44 34.71 29.43 39.02 24.70 22.67 18.83 19.23 22.68 36.02 Date of Max Speed 01/03 02/25 03/06 04/12 05/21 06/12 07/26 08/31 09/24 10/25 MinSpeed(mph) 0.98 2.16 0.48 1.05 1.13 1.34 1.39 1.01 1.18 1.57 Date of Min Speed 01/12 02/13 03/19 04/01 05/18 6/05 07/31 08/01 09/15 10/21 Ave Wind Speed 10.08 10.70 10.97 10.82 8.48 7.00 7.68 7.99 8.49 10.66 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2001 40,15 11/24 2.56 11/07 18.33 38.02 11/24 2.77 11/26 16.89 35.89 51.03 12/14 04/12 1.46 0.81 12/11 09130 1.8.06 16.25 34.49 45.85 12/14 10/25 1.43 1.32 12/11 03/19 16.55 14.83 28.13 25.86 39.02 1.1/25 1.2/14 04/12 1.60 1.60 0.48 11/11 12/17 03/19 9.73 10.91 9/36 I-.
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JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2001 1 OM AMBIENT TEMP Max(F) 45.78 59.70 52.54 79.37 84.25 90.35 91.15 92.28 87,75 79.8 68.13 Date of Max 01/30 02/09 03/22 04/23 05/04 06/15 07/24 08/08 09/07 10/03 11/01 Min (F) 4.78 14.73 12.83 29.71 47.94 47.60 56.43 41.21 41.94 34.19 30.55 Date of Min 01/02 02/18 03/26 04/17 05/23 06/04 07/02 08/23 09/25 10/28 11/12 AveTemp 26.93 30.83 34.26 51.09 61.52 69.38 72.97 73.34 62.90 53.21 48.16 IOM DEW POINT TI'EMP Mean (F) 24.55 24.83 26.83 40.68 49.72 57.68 60.99 63.51 53.11 43.42 38.79 Max (F) 46.48 51.99 46.48 63.77 67.25 70.60 77.10 76.34 71.53 64.60 58.84 Date of Max 01/30 02/09 03/12 04/11 05/17 06.14 07/23 08/09 09/07 10/13 11/02 Min(F) 3.76 4.56 7.30 20.73 31.13 43.19 40.10 46.91 37.88 24.21 25.05 Date of Min 01/09 02/21 03/26 04/17 05/13 06/01 07/06 08/14 09/26 10/28 11/20 67.87 92.28 12/05 08/08 11.08 4.78 12/30 01/02 36.86 51.86 31.25 43.05 52.64 77.10 12/04 07/23 7.58 3.76 12/30 01/09 PRECIPITATION Total (inches) 0.58 1.93 0.70 1.57 3.20 1.41 2.27 2.89 3.61 0.80 1.78 2.17 22.91 Max.inOneDay 0.19 0.54 0.22 0.54 0.45 0.38 0.93 1.13 1.34 0.36 0.45 0,91 1,34 Date 01/30 02/09 03/12 04/06 05/1.5 06/02 07/25 08/22 09/09 10/24 11/29 12/14 09/09 I-0 ct)
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Davis-Besse Nluclear Power Station 2001 Anmual Radiological Environmental Operating Report Figure 32 Wind Rose Annual Average 100M E
WIND SPEED (MPH)
DIRECTION FREQUENCY W%)
DAVIS-BESSE ANNUAL 2001 100M LEVEL 123 w
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M N
WIND SPEED (MPH)
DIRECTION FREQUENCY
(%W DAVIS-BESSE ANNUAL 2001 75M LEVEL 124 11 w
-i E
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 34 Wind Rose Annual Average IOM
!WIND SPEED (MPH)
S DIRECTION FREQUENCY (W)
DAVIS-BESSE ANNUAL 2001 ION LEVEL 125 W
E
Da\\'is-Bcsse Nuiclear Polwer Station 2001 Annual Radiolo-ical Environmnental Oper-ating Report Table 30 Joint Frequency Distribution by Stability Class DAVIS-BESSE FNV DUNENTAL C¶2MPLIA35ZE.tnIT..
- JA14 02 PACE 9L TIKE OF' DAY:
05:54:59 PROGRXMs JPD VEMSAN:~J F77-1.0 DAVIS-BESSE 75-10 DT, 140 11AMP SITE IDEETIFIER:
I DATA PERIOD EXAM4INED:
/
1 1/
1 AMIUAL STAB LTUT CMASS A
STA2ILrTY BARED ON, DELTA T PETWEIX 2S0.0 AND 55.0 FEE WIND MtE.KSUME XTý 35.0 FEET WIND "M&SH=L AT-1.003 "4H
,JOINT 211EDUENCY DI)XVI'IBUTIDN OF WIND SPEED AND DIRECTON IN "OSUES AT 35.00 F=T SPEED tMPAJ N
NNlE WE Ex.-
51 SE ESr S
SSW4 514 WSW1 v
WN4 NK bam8 TOTAL CI.LN 1.01-3.49 1
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TOTAL 17 4
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28 19 97 STASBILITY CLASS a
SrTAEILITY BASED MV DELTA T BET¶4E835 250.C AND 35.0 FEET SiLIOD 4'.SASSIS.
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XT. 1.00 8492 JOINT FREEIUENCy DISTEIWUTON 0p WIND SPEED MM DIPXCSIOS4 IN HOMSE KA 35.00 FEET S PEED
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1 1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 30 (continued)
Joint Frequency Distribution by Stability Class
... DAVIS-BEESE ENVIRONHNTA1, COMPLIANCE UNIT...
- P5OG8M6, JM1 VERSXOHý F77-1.0 DAVIS-BESSE 75-10 DT.
NO BACKUP........
DATA PERIOD EXAMINED, I/
1/
I -
12/
31/
CALM 24-JkN-02 53M6 OF DAY.
05.S4ý59 SITE IETIFIER, I PAGE 53
... ANNUA STABILITY CLASS X
STABILITY BASED ON, DLTA T BETTIERi 250.0 AND 35.0 FEET WIND MEASURRI)
AT:
35.0 FEET WINXD THRESHOLD ATM 1.00 MP JOINT PFEQUENCY DISTRIBUTION OF WIND SP0EE AND ASODIRECTON IN HOURS AT 3S.00 FEET U
NM NO EnE C
m Sw WSW I
t" sW MW TOTAL 1
1.01-3.49 2
3 4
6 7
19 26 37 36 30 22 14 a
7 5
3 239 3.50- 7.49 121 13 18 49 89 105 81 83 132 1$5 165 92 72 43 14 a
u160 7.S0-12.49 5
13 IB s0 6t 42 2&
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2 7
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T*IAL 22 32 47 112 364 168 Z42 165 218 483 464 271 I18 98 57 36 2680 STAMXLrT'. CLASS F
STABILITY WASED ON: DELTA T BETWEEN 250.0 AND 35.0 mET WIND ME45138 AT, 3S.0 FEET WIND THESHOLD AT.
1.00 ME9 JOINT FRSOEU= DIE"81M014 OF #IND SPE.D AND DIPCION IN HOURS AT 35.00 FEET SPEED N
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WNW NW WN1 TOTAL CALM 2
1.01-3.49 1
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1 216 3.50- 7.49 1
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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Land and Wetlands Management The Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, makes up 733 acres of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by Toledo Edison and jointly managed by the U.S. Fish and Wild life Service and Toledo Edison. Navarre Marsh is divided into three pools. The pools are sepa rated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison is re sponsible for the maintenance and repair of the dikes and controlling the water levels in each of the pools.
A revetment is a retaining structure designed to hold water back for the purposes of erosion con trol and beach formation. Revetments are built with a gradual slope, which causes waves to dis sipate their energy when they strike their large surface area. Beach formation is encouraged through the passive deposition of sediment. A dike is a retaining structure designed to hold wa ter for the purpose of flood control and to aid in the management of wetland habitat. When used as a marsh management tool, dikes help in controlling water levels in order to maintain desired vegetation and animal species. Manipulating water levels is one of the most important marsh management techniques used in the Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, the swamp forest, and the wet meadow. Also, there exists a narrow dry beach ridge along the lakefront, with a sandbar extending out into Lake Erie. All these areas provide essential food, shelter and nesting habitat, as well as a resting area for migratory birds.
Davis-Besse personnel combine their efforts with a number of conservation agencies and organi zations. The Ottawa National Wildlife Refuge, the Ohio Department of Natural Resources (ODNR), and the Black Swamp Bird Observatory work to preserve and enhance existing habitat.
Knowledge is gained through research and is used to help educate the public about the impor tance of preserving wetlands.
With its location along two major migratory flyways, the Navarre Marsh serves as a refuge for a variety of birds in the spring and fall, giving them an area to rest and restore energy reserves be fore continuing their migration. The Black Swamp Bird Observatory, a volunteer research group, captures, bands, catalogues, and releases songbirds in the marsh during these periods.
Navarre Marsh is also home to wildlife that is typical of much of the marshland in this area, in cluding deer, fox, coyote, muskrats, mink, rabbits, groundhogs, hawks, owls, ducks, geese, her ons, snakes and turtles. For the first time in recent history, a pair of mature American Bald Ea gles chose the Navarre Marsh as their nesting site in late 1994, and fledged a healthy eaglet in July 1995. The young eagle was one of record 38 eaglets fledged in Ohio in 1995. A new nest was built in 1999-2000, and fledged a pair of eaglets in the summer of 2000. Three more eaglets were fledged at Davis-Besse in 2001, and were part of a record hatch of 104 Ohio eaglets. The state has gone from a low of 4 nests in 1978 to a record of 73 nests in 2001.
Ohio's seventh Federal Junior Duck Stamp Art Contest was held at Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 600 entries in four age brackets. The Junior Duck Stamp Art Contest was designed to teach conservation through the arts and give students a chance to experience the beauty and diversity of wildlife. A total of 101 ribbons were awarded to young Ohio artists, with the state Best-of-Show entry submitted to Washington, D.C. to compete in the 131
.I i Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report national contest with other state Best-of-Show entries. The winner of this competition will be used to make this year's Junior Duck Stamp. The 1996 Ohio Junior Duck Stamp Art Contest winner of Best-of-Show, Adam Grimm, became the youngest artist ever to win the adult Federal Duck Stamp contest. His artwork was displayed on the 2000 federal duck stamp.
Davis-Besse also hosted a Volunteer Eagle Watchers Workshop. Training was given to over 80 volunteers who will be observing Ohio's expanding eagle population during the current breeding and nesting season.
Water Treatment Plant Operation Description The Davis-Besse Nuclear Power Station draws water from Lake Erie for its water treatment plant. The lake water is treated with chlorine, lime, and other chemicals to produce high purity water, which is used by many of the Station's cooling systems.
Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which will remove debris greater than one-half inch in size. The water is then pumped to chlorine de tention tanks. Next, the water passes through one of two clarifiers. Davis-Besse uses upflow clarifiers, or precipitators, to remove sediment, organic debris, and dissolved agents from the raw water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, flocculation, and sedimentation into a single unit. Coagulation is the process by which a chemi cal, called a coagulant, is added, causing the small particles in the water to adhere to each other and form larger particles. During flocculation, the water is gently circulated, allowing these con glomerate particles to mass together further. Finally, during sedimentation, large conglomerate particles settle to the bottom of the clarifier. These processes normally require large separate tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treatment plant.
132
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report PAWWATER I
¶V~cLOFLOW spYS
.."NG TA FTOMATC*. L*
WATERWTF.
CHLpSTELVL WEATNTaJT oresos ARFIERS
- GAVtrr, CLEARWELL FEED PUMPS TANKCS FT CLEAR WELL TRANSFER PUMPS WATFP TO OEMt4ERALaEo WATER SYSTEMA Figure 35: At Davis-Besse, raw water is drawn into die water treatment plant and processed to make water for plant systems.
After the clarifier, the water goes through a flow-splitting box, which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGFs). The AVGFs contain of a 50:50 ratio of anthracite to filter sand. During this filtration process, suspended matter is removed from the water and turbidity is reduced.
After filtration, the water goes to a 32,000-gallon clearwell. The clearwell acts as a reservoir from which water can be drawn as needed for all systems, including firewater and demineralized water.
Domestic Water When Davis-Besse began operation over 20 years ago, all site domestic water was produced in the Water Treatment Facility. Operation of the domestic water treatment and distribution system, including the collection and analysis of daily samples, was reportable to the Ohio Environmental Protection Agency.
Beginning in December 1998, domestic water needs at Davis-Besse have been met by the Carroll Township Water District. Since the Station no longer produces its own domestic water, these regulatory requirements have been discontinued.
Zebra Mussel Control Introduction The plant receives all of its water from an intake system from Lake Erie. Zebra mussels can se verely impact the availability of water for plant processes. Dreissena polymorpha, commonly known as the zebra mussel, is a native European bivalve that was introduced into North 133
-1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report American waters in 1986 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders that rapidly colonize an area by forming byssal threads that enable them to attach to solid surfaces mad to each other. Because of their ability to attach in this manner, they may form layers several inches deep. This poses a problem to facilities that rely on water intakes from Lake Erie because mussels may attach to the intake structures and restrict water flow.
Zebra mussels have not caused any significant problems at Davis-Besse, but mussels have been found attached to the intake crib (the structure that allows water to be pulled in from the lake) and the first section of the intake conduit (the pipe that connects the crib to the intake canal).
Mussels have also been found on the trash racks, and the intake bay #3 walls prior to the travel ing screens. These mussels are periodically cleaned using high-pressure water. Davis-Besse uses continuous low level chlorination of the intake bays to control the mussels.
The mussel population appears to be leveling off or declining. This is likely due to the increas ing clarity of Lake Erie. As the food source for the zebra mussel declines, mussel populations decline correspondingly.
Wastewater Treatment Plant Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen erated by site personnel is treated at an onsite extended aeration package treatment facility de signed to accommodate up to 38,000 gallons per day. In the treatment process, wastewater from the various collection points around the site enters the facility through a grinder, from where it is distributed to the surge tanks of one or both of the treatment plants.
The wastewater is then pumped into aeration tanks, where it is digested by microorganisms.
Oxygen is necessary for good sewage treatment, and is provided to the microbes by blowers and diffusers. The mixture of organics, microorganisms, and decomposed wastes is called activated sludge. The treated wastewater settles in a clarifier, and the clear liquid leaves the clarifier over a weir and exits the plant through an effluent trough. The activated sludge contains the organisms necessary for continued treatment, and is pumped back to the aeration tank to digest incoming wastewater. The effluent leaving the plant is pumped to the wastewater basin (NPDES Outfall 601) where further treatment takes place.
Summary of 2001 Wastewater Treatment Plant Operations All wastewater parameters were within specifications during the year 2001.
134
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report National Pollutant Discharge Elimination System (NPDES) Reporting The OEPA has established limits on the amount of pollutants that Davis-Besse may discharge to the environment. These limits are regulated through the Station's National Pollutant Discharge Elimination System (NPDES) permit, number 21B00011.
Parameters such as chlorine, sus pended solids and pH are monitored under the NPDES permit. Toledo Edison personnel prepare the NPDES Reports and submit them to the OEPA each month.
Davis-Besse has eight sampling points described in the NPDES permit. Seven of these locations are discharge points, or outfalls, and one is a temperature monitoring location. Descriptions of these sampling points follow:
Outfall 001 Collection Box: a point representative of discharge to Lake Erie Source of Wastes: Low volume wastes (Outfalls 601 and 602), Circulating Water system blowdown and service water Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, Circulating Water pump house sumps Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh Source of Wastes: Backwash water and debris from water intake screens Outfall 004 Cooling Tower Basin Ponds: Outfall to State Route 2 Ditch Source of Wastes: Circulating Water System drain (only during system outages)
Outfall 588 Sludge Monitoring Source of Wastes: Wastewater Plant sludge shipped for offsite processing Outfall 601 Wastewater Plant Tertiary Treatment Basin: Discharge ftom Wastewater Treatment Plant Sources of Wastes: Wastewater Treatment Plant 135
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Outfall 602 Low volume wastes: Discharge from settling basins Sources of wastes: Water treatment residues, Condensate Polishing Holdup Tank decanta tion and Condensate Pit sumps Sampling Point 801 Intake Temperature: Intake water prior to cooling operation 2001 NPDES Summary During 2001, the NPDES permit was renewed by the Ohio EPA.
This permit expired on October 31, 2000, and a renewal application was submitted in May, 2000. The permit will be effective for 5 years, after which a new permit will be negotiated. A new sampling requirement with outfall designation 004 was added to the permit renewal application. This will be used to monitor water drained from the Circulating Water System during outages. Two violations of the NPDES permit occurred during 2001. The discharge limitation for Total Suspended Solids at Outfall 601 and the Total Residual Chlorine at Outfall 001 were each exceeded once.
Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are man aged and disposed of in accordance with all applicable state and federal regulations.
Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid haz ardous waste. Solid waste is defined as a solid, liquid, semi-solid, or contained gaseous material.
The major goals of RCRA are to establish a hazardous waste regulatory program to protect hu man health and the environment and to encourage the establishment of solid waste management, resource recovery, and resource conservation systems. The intent of the hazardous waste man agement program is to control hazardous wastes from the time they are generated until they are properly disposed of, commonly referred to as "cradle to grave" management. Anyone who gen erates, transports, stores, treats, or disposes of hazardous waste are subject to regulation under RCRA.
Under RCRA, there are essentially three categories of waste generators:
"* Large quantity Generators
- A facility which generates 1000 kilograms/month (2200 lbs./month) or more.
"* Small quantity Generators - A facility which generates less than 1000 kilograms/
month (2200 lbs./month).
"* Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo grams/month (220 lbs./month).
136
Davis-Besse Nuclear Power Station 2001 Arnual Radiological Enmirotnmental Operating Report In 2001, the Davis-Besse Nuclear Power Station qualified as a small quantity generator, generat ing 5,770 pounds of hazardous waste. Davis-Besse personnel also continuously strives to iden tify alternate ways of reducing hazardous waste generation.
Non-hazardous waste disposed of in 2001 included 2,250 gallons of used oil, 385 gallons of oil filters and solid oily debris. Other non-hazardous regulated waste generated included 505 gallons of other chemicals such as microfilm process chemicals and polystyrene resins.
RCRA mandates other requirements such as the use of proper storage and shipping containers, labels, manifests, reports, personnel training, a spill control plan and an accident contingency plan. These are part of the Chemical Management Program at Davis-Besse. The following are completed as part of the hazardous waste management program and RCRA regulations:
Weekly Inspections of the Chemical Waste Accumulation Areas are designated through out the site to ensure proper handling and disposal of chemical waste. These, along with the Chemical Waste Storage Area, are routinely patrolled by security personnel and in spected weekly by Environmental and Chemistry personnel. All areas used for storage or accumulation of hazardous waste are posted with warning signs and drums are color coded for easy identification of waste categories.
"* Waste Inventory Forms are placed on waste accumulation drums or provided in the ac cumulation area for employees to record the waste type and amount when chemicals are added to the drum. This ensures that incompatible wastes are not mixed and also identi fies the drum contents for proper disposal.
Other Environmental Regulating Acts Comprehensive Environmental Response, Compensation and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, or Superfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants and contaminants into the environment. Super fund establishes "reportable quantities" for several hundred hazardous materials and regulates the cleanup of abandoned hazardous waste disposal sites.
Superfund Amendment and Reauthorization Act (SARA)
Superfund was amended in October 1986 to establish new reporting programs dealing with emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized, and that adequate and timely responses are made to protect surrounding populations.
Davis-Besse conducts site-wide inspections to identify and record all hazardous products and chemicals onsite as required by SARA.
Determinations are made as to which products and chemicals are present in reportable quantities.
137
. 1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Annual SARA reports are submitted to local fire departments and state and local planning com missions by March 1 for the preceding calendar year. One additional water treatment chemical product was identified for calendar year 2001.
Toxic Substances Control Act (TSCA)
The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are intro duced into the environment, and to regulate them where necessary. This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very similar to the hazardous waste management system established under RCRA.
In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite.
PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid.
Retro-filling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the solvent to circulate in the transformer during op eration. The entire retro-fill process takes several years and will extract almost all of the PCB.
In all, Davis-Besse performed retro-filI activities on eleven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors.
These capacitors are being replaced and disposed of during scheduled maintenance activities.
Clean Air Act The Clean Air Act identifies substances that are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station Auxiliary Boiler. This boiler is used to heat the station and provide steam to plant systems when the reactor is not operating.
A report detailing the Auxiliary Boiler operation is submitted annually.
The Ohio EPA has granted an exemption from permitting our six emergency diesel engines, in cluding the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Emer gency Response Facility Diesel Generator, the Miscellaneous Diesel, and the Fire Pump Diesel.
These sources are operated infrequently to verify their reliability, and would only be used in the event of an emergency.
In response to recent "Clean Air Act Title V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined spe cific regulations concerning handling, removal, environmental protection, and disposal. Also, the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for worker protection. Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and dis posal of this waste under the Clean Air Act.
138
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the Trans portation Safety Act of 1976. These regulations are enforced by the United States Department of Transportation (DOT) and cover all aspects of transporting hazardous materials, including pack ing, handling, labeling, marking, and placarding. Before any wastes are transported off site, Davis-Besse must ensure that the wastes are identified, labeled and marked according to DOT regulations, including verification that the vehicle has appropriate placards and it is in good oper ating condition.
Other Environmental Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (USTs) are required to notify the State. This regulation was implemented in order to provided protection from tank contents leaking and causing damage to the environment.
Additional standards require leak detection systems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs.
Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and haz ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant cover alls, gloves, boots, decontamination agents, absorbent cloth, goggles and warning signs.
Waste Minimization and Recycling Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by indus tries. In some communities, MSW is burned in specially designed incinerators to produce power or is separated into waste types (such as aluminum, glass, and paper) and recycled. The vast majority of MSW is sent to landfills for disposal. As the population increases and older landfills reach their capacity, MSW disposal becomes an important economic, health, and resource issue.
The State of Ohio has addressed the issue with the State Solid Waste Management Plan, other wise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing land fills by reducing the amount of MSW produced, by reusing certain waste material, and by recy cling other wastes. This is frequently referred to as "Reduce, Reuse, and Recycle."
Davis-Besse has implemented and participated in company wide programs that emphasize the reduction, reuse, recycle approach to MSW management. An active Investment Recovery Pro gram has greatly contributed to the reduction of both hazardous and municipal waste generated by evaluating options for uses of surplus materials prior to the materials entering Davis-Besse's waste streams. Such programs include paper, cardboard, aluminum cans, used tires, and metals recycling or recovery. Paper and cardboard recycling is typically in excess of 50 tons annually.
This represents a large volume of recyclable resources, which would have otherwise been placed 139
- 1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report in a landfill. Aluminum soft drink cans are collected for the Boy Scouts of America to recycle.
Additionally, lead-acid batteries are recycled and tires are returned to the seller for proper dis posal.
Although scrap metal is not usually considered part of the MSW stream, Davis-Besse does col lect and recycle scrap metals, which are sold at current market price to a scrap dealer for resource recovery. These programs are continuously being expanded and reinforced as other components of MSW stream are targeted for reduction.
140
Davis-Besse Nuclear Power Station 200 1 Annual Radiological Environmental Operating Report APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2001 through December, 2001 141
II Davis-I3esse Nuzlear Power Station 2001 Annual R,,adiological hnvironrn'.utal Operating Report Anpendix A Inter'laboratory Cornparison Program Results Environmental, Inc., Midwest Laboratory, for'merly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.
This program was conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2.
Results of crosscheck testing with Teledyne Brown Engineering are also listed.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NqST traceable sources. Data for previous years available upon request.
Table A4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluatioh Program.
The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.
Attachment A lists acceptance criteria for "spiked" samples.
Out-of-limit results are explained directly below the result.
142
Davis-Besse Nuclear Power Station 200! AnnuaI Radiological EnvroymnentaI Operating RtpIrt 12-31-01 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/lHter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCi/liter or kg 10% of known value Strontium_90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value Potassium-40
> 0.1 g/liter or kg 5% of known value Gross alpha 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value Tritium 4,000 pCi/liter is = (pCi/liter) =
169.85 x (known)a9
> 4,000 pCi/liter 10% of known value Radium-226,-228 0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, 55 pCi/liter 6.0 pCi/liter Iodine-129b
>55 pCi/liter 10% of known valuge Uranium-238, 35 pCi/liter 6.0 pCi/liter 1
G /liter 15% of known value Nickel-6Y r
Technetium-99b 50 to 100 pCi/liter 10 pCi/liter Iron'55t
> 100 pCi/liter 10% of known value Othersb 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
143
- 1
)avis~-Be;se Nuclear Power Statioi) 2 ()I Annual~ Radiological Environmental Operating Report "Table A-1.
Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.
Concentration in pCi/Lb Lab Sample Date Control Code Type Collected Analysis Laboratory result' ERA Resultd Limits STW-897 WATER Jan, 2001 Gr. Alpha 31.9+/-2.1 STW-897 WATER Jan, 2001 Gr. Beta 25.3 +/- 2.7 STW-900 WATER Feb, 2001 1-131 27.2 +/-0.8 STW-902 WATER Feb, 2001 Ra-226 4.0 +/- 0.1 STW-902 WATER Feb, 2001 Ra-228 13.8 +/- 0.4 STW-902 WATER Feb, 2001 Uranium 17.0 +/- 0.3 STW-903 WATER Mar, 2001 H-3 17,400.0 +/-69.7 STW-917 WATER Apr, 2001 Gr. Alpha 57.4 +/-3.5 STW-917 WATER Apr, 2001 Ra-226 13.5 +/-0.4 STW-917 WATER Apr, 2001 Ra-228 10.1 +/- 0.6 STW-917 WATER Apr, 2001 Uranium 14.2 - 0.2 STW-918 WATER Apr, 2001 Co-60 27.9 +/- 1.4 STW-918 WATER Apr, 2001 Cs-134 16.0 +/-0.4 STW-918 WATER Apr, 2001 Cs-137 195.4+/-1.5 STW-918 WATER Apr, 2001 Gr. Beta 340.0+/-51.0 STW-918 WATER Apr, 2001 Sr-89 62.8 +/-5.7 STW-918 WATER Apr, 2001 Sr-90 34.2 +/- 1.6 STW-919 WATER Jun, 2001 Ba-133 37.8:+/- 1.2 STW-919 WATER Jun, 2001 Co-60 49.9 +/-0.7 STW-919 WATER Jun, 2001 Cs-134 16.0:+/- 1.4 STW-919 WATER Jun, 2001 Cs-137 208.0 +/- 1.7 STW-919 WATER Jun, 2001 Zn-65 37.8 +/-0.7 STW-920 WATER Jun, 2001 Ra-226 14.6 +/- 0.4 STW-920 WATER Jun, 2001 Ra-228 6.2 +/-i 0.2 STW-920 WATER Jun, 2001 Uranium 49.0 +/- 1.0 STW-921 WATER Jul, 2001 Sr-89 19.8 +/- 1.5 Delay in processing may have attributed to deviation.
Result of reanalysis; Sr-89, 35.3 +/- 4.4 pCi/L. Sr-90, 25.0 +/- 2.8 pCi/L.
WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Jul, 2001 Jul, 2001 Jul, 2001 Aug, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Sr-90 Gr. Alpha Gr. Beta H-3 Ra-226 Ra-228 Uranium 1-131 Gr. Alpha Ra-226 26.3:+/- 1.1 23.3+/-1.9 48.5+/-4.6 2,680.0+/-41.9 10.9 +/-0.2 9.7+/-1.1 11.2 +/-0.1 7.7 +/-0.3 82.2+/-4.0 9.5+/-1.2 45.7 +/- 11.4 16.7 +/- 5.0 28.3 +/- 3.0 4.7 +/- 0.7 14.4 +/- 3.6 20.4 +/-3.0 17,800.0+/-1,780.0 56.0 +/-14.0 17.7+/-2.7 8.1 +/-2.0 15.6 +/- 3.0 26.4 +/- 5.0 16.9 +/-5.0 186.0 +/- 9.3 343.0 +/-+_
1.7 64.1+/-5.0 33.8 +/-5.0 36.0 +/-i5.0 46.8 +/- 5.0 15.9 +/- 5.0 197.0 +/- 9.9 36.2 +/- 5.0 15.4 +/- 2.3 4.5+/-1.1 55.7 __L 5.6 31.2 +/- 5.0 25.9 +/- 5.0 17.8+/-5.0 53.0 +/- 10.0 2,730.0 +/- 356.0 10.8+/- 1.6 9.0 +/-2.2 13.1 +/- 3.0 7.7 +/-2.0 97.5 +/- 24.4 10.8 +/-_ 1.6 25.9 - 65.5 8.0- 25.4 23.1 - 33.5 3.4 - 5.9 8.2-20.6 15.2 - 25.6 14,700.0 - 20,900.0 31.8 - 80.2 13.1 - 22.3 4.6-11.6 10.4-20.8 17.7-35.1 8.2-25.6 170.0 - 202.0 252.0- 428.0 55.5 - 72.8 25.1 - 42.5 27.3-44.7 38.1 - 55.5 7.2 - 24.6 180.0 - 214.0 27.5 - 44.9 11.4-19.4 2.6-6.5 46.1 - 65.3 22.5 - 39.9 17.2-34.6 9.1 - 26.5 35.7-70.3 2,110.0 - 3,350.0 8.0- 13.6 5.1 - 12.8 7.9-18.3 4.2-11.2 55.3 - 140.0 8.0- 13.6 144 STW-921 STW-922 STW-922 STW-924 STW-931 STW-931 STW-931 STW-932 STW-933 STW-933
D )avis-f.scM Nuciiar Power Statlion 2001 Annual aRadiological Environimental Operating ReporT Table A-1.
Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.
Concentration in pCi/IT Lab Sample Date Control Code Type Collected Analysis Laboratory resultc ERA ResultW Limits STW-933 WATER Oct, 2001 Ra-228 17.0 +/- 0.8 15.6 t 3.9 8.9 - 22.4 STW-933 WATER Oct, 2001 Uranium 32.2:+/--1.4 37.2 +/- 3.7 30.7 - 43.6 STW-934 WATER Oct, 2001 Co-60 82.4+/-0.9 78.4 +/-5.0 69.7-87.1 STW-934 WATER Oct, 2001 Cs-134 52.2 +/- 1.3 54.1 +/- 5.0 45.4 - 62.8 STW-934 WATER Oct, 2001 Cs-137 39.4+/-0.6 37.9 +/- 5.0 26.3 - 43.7 STW-934 WATER Oct, 2001 Gr. Beta 166.0 +/- 7.1 192.0 +/- 28.8 142.0 - 242.0 STW-934 WATER Oct, 2001 Sr-89 12.8+/-0.8 16.7 +/-5.0 8.0- 25.4 STW-934 WATER Oct, 2001 Sr-90 6.8+/-0.7 7.7-+/-5.0
-1.0- 16.4 STW-935 WATER Oct, 2001 Gr. Alpha 63.5 +/- 2.5 64.0 +/- 16.0 36.5 - 91.5 STW-935 WATER Oct, 2001 Gr. Beta 26.0 +/-1.2 21.5 +/- 5.0 12.8-30.2 STW-938 WATER Nov, 2001 Ba-133 66.7:+/- 1.2 69.3 +/-6.9 57.5-81.1 STW-938 WATER Nov, 2001 Co-60 59.3 +/- 0.6 59.7+/- 5.0 51.0- 68.4 STW-938 WATER Nov, 2001 Cs-134 86.7+/- 1.5 93.9 -- 5.0 85.2-103.0 STW-938 WATER Nov, 2001 Cs-137 45.0 +/- 1.0 42.0 +/- 5.0 33.3 - 50.7 STW-938 WATER Nov, 2001 Zn-65 80.7+/-0.6 77.3+/-7.7 63.9-90.7 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).
b All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.
Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
"Results are presented as the known values, expected laboratory precision (1 sigma, I determination) and control limits as provided by ERA.
145
avis-Besse Nruclear Power Station 2001 Aiioal Radiologicai Fnvironmental Operating Report Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
mR Lab Known Lab result Code TLD Type Date Measurement Value
+ 2 Sigma Control Limits Teledyne Brown Engineering 2000-1 LiF-100 Chips 2000-1 LiF-100 Chips 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #1 Mar, 2000 Reader 1, #2 Mar, 2000 Reader 1, #3 17.8 35.5 62.2 14.4 +/- 0.2 32.4 +/- 0.1 61.8+/-0.9 12.46 - 23.14 24.85 - 46.15 43,54 - 80.86 Teledyne Brown Engineering 2000-2 CaSO4: Dy Cards Mar, 2000 Reader 1, #1 2000-2 CaSO4: Dy Cards Mar, 2000 Reader 1, #2 2000-2 CaSO4 : Dy Cards Mar, 2000 Reader 1, #3 Chips and cards irradiated by Teledyne Brown Engineering, 17.8 21.3 +/-0.3 12.46 - 23.14 35.5 40.1 +/- 1.9 24.85 - 46.15 62.2 69.9 +/-3.5 43.54 - 80.86 Westwood, New Jersey, in March of 2000.
12th International Intercomparison 022-1 022-1 022-1 022-1 022-1 CaSO,: Dy Cards CaSO,: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Field Field 1 Field 2 Field 3 Lab, 1 161.0 548.0 391.0 623.0 391.0 184.9 +/- 1.9 502.2 +/- 1.7 412.0 +/- 2.9 643.2+/- 2.9 442.8. 2.5 112.70 - 209.30 383.60 - 712.40 273.70 - 508.30 436.10 - 809.90 273.70 - 508.30 Environmental, Inc.
2001-1 CaSO,: Dy Cards 2001-1 CaSO: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO4: Dy Cards 2001-1 CaSO4 : Dy Cards 2001-1 CaSO4: Dy Cards 2001-1 CaSO4: Dy Cards 2001-1 CaSO,: Dy Cards Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Reader 1, #1 Reader 1, #1 Reader 1, #2 Reader 1, #2 Reader 1, #3 Reader 1, #3 Reader 1, #4 Dec, 2001 Reader 1, #4 4.0 4.0 7.1 7.1 15.9 15.9 63.6 63.6 3.7 + 0.1 3.4+/- 0.1 7.9 +0.2 7.6+/-0.3 18.6 +/- 0.4 19.6 +/- 0.1 78.2 - 1.2 79.9 t 2.5 2.79 - 5.17 2.79 - 5.17 4.95 9.19 4.95 - 9.19 11.13 - 20.67 11.13 - 20.67 44.53 - 82.69 44.53 - 82.69 146
Davis-Besse Nutchar Pow;,r Slzt:ion 2001 Annual E,
adiolonica! lnvironrnenltal Operalting Report "Table A-3. In-house "spike'"
samples.
Concentration in pCi/!L Lab Sample Date Laboratory results Known ControiF Code Type Collected Analysis 2s, n=1b Activity Limits SPAP-477 SPW-479 SPW-481 SPW-481 SPW-482 SPW-482 SPW-483 SPW-483 Sample wa.
SPW-485 SPW-485 SPW-485 SPW-485 SPAP-754 SPW-1037 SPW-1037 SPW-1224 SPW-1224 SPW-1225 SPW-1225 SPW-1272 SPW-1272 SPVE-1274 SPCH-1276 SPMI-1270 SPMI-1270 The Cs-13j SPMI-1270 SPU-2901 SPW-2161 SPU-3128 SPW-3129 Air Filter Water Water Water Water Water Water Water lost during Water Water Water Water Air Filter Water Water Water Water Water Water Water Water Vegetation Charcoal Milk Milk 7 spike is sus*
Milk Urine Water Urine Water Jan, 2001 Cs-137 Jan, 2001 H-3 Jan, 2001 Gr. Alpha Jan, 2001 Gr. Beta Jan, 2001 Gr. Alpha Jan, 2001 Gr. Beta Jan, 2001 Ra-226 Jan, 2001 Ra-228 analysis.
Jan, 2001 Co-60 Jan, 2001 Cs-134 Jan, 2001 Cs-137 Jan, 2001 Sr-90 Jan, 2001 Gr. Beta Feb, 2001 U-233/4 Feb, 2001 U-238 Feb, 2001 Ra-226 Feb, 2001 Ra-228 Feb, 2001 Gr. Alpha Feb, 2001 Gr. Beta Feb, 2001 1-131 Feb, 2001 1-131(g)
Feb, 2001 1-131(g)
Feb,2001 1-131(g)
Mar, 2001 Cs-134 Mar, 2001 Cs-137 pect; A new cesium spike has Mar, 2001 1-131(g)
Mar, 2001 H-3 Mar, 2001 Ra-228 Apr, 2001 H-3 Apr, 2001 Gr. Alpha 1.76 +/-0.02 1.68 54702.00 - 644.00 54549.00 58.08 +/- 2.79 69.14 213.83 - 3.07 220.26 51.77+/- 2.18 69.14 202.48 +/- 2.98 220.26 20.11 +/- 0.34 20.86 10.55 +/- 2.02 19.43 33.53 +/- 3.40 31.13 32.80 +/- 2.54 30.81 42.10 +/-5.60 36.00 154.34 +/- 3.49 137.66 8.53 +/- 0.02 7.88 3.74+/-0.10
.4.17 3.81 +/- 0.10 4.17 21.25 +/- 0.50 20.68 21.76 +/- 2.65 19.27 71.87+/-3.07 69.14 36.30 +/- 1.47 28.75 56.82 +/- 0.71 63.05 65.69 +/- 10.21 63.05 0.78 +/- 0.05 0.76 1.57 +/-0.05 1.58 31.89 +/-4.71 29.77 46.61 +/- 8.81 35.90 been prepared.
81.92+/- 10.80 81.95 51512.00 +/- 1369.00 50189.00 29.92+/-5.13 31.75 2065.00 +/- 408.00 2008.00 37.94 +/- 2.42 34.57 1.01 - 2.35 43639.20 - 65458.80 34.57 - 103.71 198.23 - 242.29 34.57 - 103.71 198.23 - 242.29 14.60 - 27.12 13.60 - 25.26 21.13 - 41.13 20.81 - 40.81 26.00 - 46.00 110.13 - 165.19
-2.12 - 17.88 2.50- 5.84
-7.83 - 16.17 14.48 - 26.88 13.49 - 25.05 34.57 - 103.71 18.75 - 38.75 50.44 - 75.66 53.05 - 73.05 0.45 -'1.06 0:95 - 2.21 19.77 - 39.77 25.90 - 45.90 71.95 - 91.95 40151.20 - 60226.80 22.23 - 41.28 1317.37 - 2698.63 17.29 - 51.86 147
l)avis esse Nuclear Power Stai.on 200.
Annual Radiiological Environmental Operating Report Table A-3. In-house "spike" samples.
Concentration in pCi/LU Lab Code SPW-3129 SPAP-3508 SPMI-3232 SPMI-3232 SPMI-3232 SPMI-3232 SPMI-3232 SPSO-3356 SPSO-3356 SPAP-3359 SPW-3376 SPW-3376 SPW-3376 SPW-3377 SPW-3129/1 SPW-3129/1 SPW-3129/2 SPW-3129/2 SPVE-3303 SPSO-5701 SPSO-5701 SPW-5779 SPW-5779.
SPW-5779 SPF-5781 SPF-5781 SPW-5937 SPW-59441 SPW-59441 SPAP-5703 SPW-3129/3 Sample Type Water Air Filter Milk Milk Milk Milk Milk Soil Soil Air Filter Water Water Water Water Water Water Water Water Vegetation Soil Soil Water Water Water Fish Fish Water Water Water Air Filter Water Date Collected Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 May, 2001 May, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Gr. Alpha Laboratory results ncown
.ontroi 2 s, n=lb Activity Limits Analysis Gr. Beta Gr. Beta Cs-134 Cs-137 1-131 1-131(g)
Sr-90 Co-60 Cs-137 Cs-137 Co-60 Cs-134 Sr-90 1-131 Gr. Alpha Gr. Beta Cr. Alpha Gr. Beta 1-131(g)
Co-60 Cs-137 Co-60 Cs-137 Sr-90 Co-60 Cs-137 H-3 Ra-226 Ra-228 Cs-137 117.83 +/- 2.37 0.80 +/- 0,01 32.69 +/- 6.50 44.20 +/- 9.08 48.05 +/- 0.90 55.64 +/- 11.39 143.77 +/- 3.04 18.49 +/- 0.21 18.71 +/- 0.24 1.80 +/- 0.01 48.17 +/- 4.85 37.14 +/- 3.90 159.84 +/- 3.42 68.60 +/- 2.63 37.94 +/- 2.42 117.83 t 2.37 34.42 +/- 2.14 119.99 +/- 2.45 0.81 +/- 0.03 17.42+/-0,19 16.03 +/- 0.22 250.05 +/- 18.63 178.68 +/-19.89 72.12 +/- 2.24 1.87 +/- 0,08 1.43 +/- 0.07 51177.00 +/- 631.00 36.62 +/- 1.74 41.46 +/- 6.44 1.81 +/- 0.02 35.31 +/- 3.04 109.46 0.78 33.96 35.79 56.68 56.68 136.82 19.57 16.61 1.67 45.19 33.96 136.82 85.02 34.57 109.46 34.57 109.46 0.86 19.05 16.52 233.26 175.91 68.12 1.79 1.39 50189.00 34.46 36.06 1.67 34.75 148 98.51 - 120.41
-9.22 - 10.78 23.96 - 43.96 25.79 - 45.79 45.34 - 68.02 46.68 - 66.68 109.46 - 164.18 9.57-29.57 6.61 - 26.61 1.00 - 2.34 35.19 - 55.19 23.96 - 43.96 109.46 - 164.18 68,02 - 102.02 17.29 - 51.86 98.51 - 120.41 17.29 - 51.86 98,51 - 120.41 0.51-1.20 9.05 - 29.05 6.52-26.52 209.93 - 256.59 158.32 - 193.50 54.50 - 81.74 1.07-2.51 0.83-1.95 40151.20 - 60226.80 24.12 - 44.80 25.24 - 46.88 1.00- 2.34 17.38 - 52.13
Davis-Btssc NunlInr Power Station 2001 Annual Radiological Environmental Operating Report Table A-3. In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Control:
Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3129/3 Water Jul, 2001 Gr. Beta 113.28 +/-3.65 109.46 98.51 - 120.41 SPMI-6145 Milk Jul, 2001 Cs-137 188.45 +/- 19.10 175.91 158.32 - 193.50 SPW-6604 Water Jul, 2001 Gr. Alpha 35.36 +/- 1.94 34.57 17.29 - 51.86 SPW-6604 Water Jul, 2001 Gr. Beta 112.56 +/- 2.46 108.82 97.94 - 119.70 SPW-9008 Water Oct, 2001 H-3 48285.00:+/- 606.10 50189.00 40151.20 - 60226.80 SPAP-9010 Air Filter Oct, 2001 Cs-137 1.91 +/- 0.01 1.67 1.00 - 2.34 SPW-10723 Water Dec, 2001 U-233/4 40.12 +/- 1.09 41.73 25.04 - 58.42 SPW-10723 Water Dec, 2001 U-238 40.16:+/- 1.09 41.73 29.21 - 54.25 SPAP-I1550 Air Filter Dec, 2001 Gr. Beta 1.58 +/- 0.02 1.56
-8.44 - 11.56 SPW-11757 Water Dec, 2001 Co-60 43.82 +/-3.14 41.36 31.36 - 51.36 SPW-11757 Water Dec, 2001 Cs-134 24.11+/-2.42 22.59 12.59-32.59 SPW-11757 Water Dec, 2001 Cs-137 5211+/-4.40 50.89 40.89 - 60.89 SPMI-11759 Milk Dec, 2001 Cs-134 28.03 +/- 2.64 27.10 17.10 - 37.10 SPMI-11759 Milk Dec, 2001 Cs-137 54.59 +/- 5.08 50.89 40.89 - 60.89 SPF-11761 Fish Dec, 2001 Cs-134 0.94 +/- 0.02 0.90 0.54 - 1.26 SPF-11761 Fish Dec, 2001 Cs-137 1.43:+/- 0.04 1.43 0.86-2.00 SAll results are in pCi/L, except for elemental potassium (K) in milk, which which are in pCi/Filter; and food products, which are in pCi/kg.
b Results are based on single determinations.
SControl limits are based on Attachment A, Page A2 of this report.
are in mg/L.; air filter samples, NOTE: For fish, Jello is used for the spike matrix. For vegetation, coleslaw is used for the spike matrix.
149
J)avis-Besse Nuclear Power Station 2001 Annual Radiological Environmenfal Operating Report Table A-4.
In-house "blank" samples.
Lab Code SPAP-478 SPAP-478 SPAP-478 SPW-486 SPW-484 SPW-484 SPW-484 SPW-484 SPW-486 SPW-486 SPW-486 SPW-486 SPAP-755 SPW-1038 SPW-1038 SPW-1223 SPW-1223 SPW-1223 SPW-1223 SPMI-1268 SPMI-1268 SPMI-1268 SPW-1271 SPW-1271 SPW-1271 SPVE-1273 SPVE-1273 SPCH-1275 SPW-2164 SPU-3126 Sample Type AIR FILTER AIR FILTER AIR FILTER WATER WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER WATER WATER WATER WATER WATER WATER MILK MILK MILK WATER WATER WATER VEGETATION VEGETATION CHARCOAL CANISTER WATER URINE Sample Date Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Mar 2001 Apr 2001 2.0 ml. sample volume.
150 Analysis Co-60 Cs-134 Cs-137 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 Co-60 Cs-134 Cs-137 Sr-90 Gr. Beta U-238 U-238 Gr. Alpha Gr. Beta Ra-226 Ra-228 Cs-134 Cs-137 1-131(g)
Co-60 Cs-134 Cs-137 Cs-134 Cs-137 1-131(g)
< 0.02
< 642.00 0.05 +/- 0.01
-66.00 ÷335.00
<1.0
< 200.0 Concentration pCi/Lt.
Laboratory results Acceptance (4.66 Sigma)
Criteria LLD Activityb (4.66 Sigma)
< 1.12
< 100.0
< 1.66
< 100.0
- 2.46
< 100.0
< 162.00
-1.86 +/- 80.40
< 200.0
< 0.68
< 1t0
< 1.35
< 3.2
< 0.02 0.03 +/-0. 01
< 1.0
< 0.97 0.43 +/- 0.50
< 2.0
< 2.68
< 10.0
< 3.46
< 10.0
< 5.43
< 10.0
< 0.65 0.06 +/- 0.31
< 1.0
< 1.60 0.16 +/-t0.90
<3.2
< 0.03
< 1.0
< 0.00
< 1.0
< 0.46
< 1.0
< 1.50
< 3.2
< 0.02 0,03 +/- 0.01
< 1.0
< 0.95 0.45 +/- 0.49
< 2.0
< 5.86
< 10.0
< 3.02
< 10.0
< 7.46
< 20.0
< 1.06
<10.6
< 2.61
< 10.0
< 2.37
< 10.0
< 10.04
< 100.0
< 6.00
< 100.0
< 0.01
< 9.6
DavIs*l~es-se N*u.clear Power Station 2001 Annal Kadiogical Environental Operating Report "Table A-4.
In-house "blank" samples.
Concentration pCi/L[.
Laboratory results Acceptance Lab Code SPDW-3130 V
SPDW-3130 V
SPMI-3233 SPMI-3233 SPMI-3233 SPMI-3233 SPMI-3233 Low level of Sr-90 SPSO-3357 SPSO-3357 SPAP-3358 Al SPW-3375 SPW-3375 SPW-3375 SPW-3375 SPDW-3130 SPDW-3130 SPDW-3130 SPDW-3130 SPVE-3304 VE SPVE-3304 VE SPVE-3304 VE SPSO-5702 SPSO-5702 SPSO-5702 SPAP-5704 SPAP-5704 P
SPAP-5704 SPW-5780 SPW-5780 SPW-5780 Sample k '
Sample Type VATER
- ATER MILK MILK MILK MILK MILK concentration SOIL SOIL R FILTER NATER WATER WATER WATER WATER WATER WATER WATER GETATION GETATION GETATION SOIL SOIL SOIL dR FILTER JR FILTER UR FILTER WATER WATER WATER Date Aptr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 in milk (1-5 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 May 2001 May 2001 Jun 2001 Jun2001 Jun 2001 Jun 2001 Jun 2001 Jul 2001 Jul2001 Jul 2001 Jul 2001 Jul2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Activityb (4.66 Sigma) 0.04 :t 0.38
< 1.0 0.67 +/- 1.04
< 3.2
< 10.0
-0.06 -0.14
<0.5
< 20.0
-0.32 +/-_ 0.79
< 5.0 1.18 +/- 0.35
< 1.0 An alvsis LLD Gr. Alpha
< 0.54 Gr. Beta
< 1.46 Cs-137
< 2.66 1-131
< 0.26 1-131(g)
< 3.91 Sr-89
< 0.79 Sr-90 pCi/L) is not unusual.
Cs-t 34
< 14.77 Cs-137
< 11.72 Cs-137
< 0.55 Co-60
< 2.90 Cs-134
< 3.71 1-131(g)
< 0.39 Sr-90
< 0.56 Gr. Alpha
< 0.45 Gr. Beta
< 1.26 Gr. Alpha
< 0.44 Gr. Beta
< 1.46 Co-60
< 7.06 Cs-134
< 11.56 Cs-137
< 8.30 Co-60
< 12.80 Cs-134
< 13.96 Cs-137
< 8.10 Co-60
< 0.79 Cs-134
< 0.84 Cs-137
< 0.60 Co-60
< 1.86 Cs-134
< 2.46 Cs-137
< 3.77
< 100.0
< 100.0
< 100.0
< 10.0
< 10.0
< 20.0
<1.0
<1.0
<3.2
< 1.0
<3.2
<1 00.0
< 100.0
< 100.0
< I00.0
< 100.0
< 100.0
< 100.0
< 100.0
< 100.0
< 10.0
< 10.0
< 10.0 151 0.02 +/- 0.22 0.05 +/- 0.27 0.15 +/- 0.34 0.34 +/- 0.95 0.09 +/- 0.32 0.66 +/- 1.04
Davis-Bessc Nuc Lucr Power Station 2001 Anntual Radiological Fnviror..'nntal Opm-atiTg Rcport Table A-4.
In-house "blank" samples.
Concentration pCi/L".
Laboratory results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analysis LLD ActivityV (4.66 Sigma)
SPF-5782 FISH Jul2001 Co-60
< 5.64
< 100.0 SPF-5782 FISH Jul2001 Cs-134
< 7.51
< 100.0 SPW-5938 WATER Jul 2001 H-3
< 163.22
-16.21 t 85.07
< 200.0 SPW-59451 WATER Jul 2001 Ra-226
< 0.01 0.04 +/- 0.01
< 1.0 SPW-59451 WATER Jul 2001 Ra-228
< 0.77 0.70 +/- 0.44
< 2.0 SPDW-3130 WATER Jul2001 Gr. Alpha
< 0.54 0.36 +/- 0.40
< 1.0 SPDW-3130 WATER Jul.2001 Gr. Beta
< 2.27
-0.78 _i+/-1.35
< 3.2 SPMI-6146 MILK Jul2001 Sr-90
< 0.50 1.09 +/- 0.36
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPW-6605 WATER Jul2001 Gr. Beta
< 1.34 0.55 _+/- 1.01
< 3.2 SPW-9009 WATER Oct 2001 H-3
< 160.00
-56.70 +/- 76.50
< 200.0 SPAP-9011 AIR FILTER Oct 2001 Co-60
< 0.76
< 100.0 SPAP-9011 AIR FILTER Oct 2001 Cs-137
< 0.58
< 100.0 SPW-5780 WATER Oct 2001 St-90
< 0.54 0.36 +/- 0.30
< 1.0 SPW-10724 WATER Dec 2001 U-238
< 0.13 0.04 +/- 0.10
< 1.0 SPAP-11549 AIR FILTER Dec 2001 Gr. Beta
< 0.00 0.01 +/- 0.00
<3.2 SPW-11756 WATER Dec 2001 Cs-137
< 2.62
< 10.0 SPMI-11758 MILK Dec 2001 Cs-137
< 4.00
< 10.0 SPMI-11758 MILK Dec 2001 1-131(g)
< 16.57
< 20.0 SPF-11760 FISH Dec 2001 Cs-137
< 7.96
< 100.0 a Liquid sample results are reported in pCi/Liter, air filter sample results are in pCi/filter, charcoal sample results are in pCi/charcoal, and solid sample results are in pCi/kilogram.
b The activity reported is the net activity result.
152
Davis-Besse Ntcicar Powe'r S3,ation 2001 Annual Radiological Environrental Operating Report Table A-5.
In-house "duplicate" samples.
Concentration in pCi/LU Lab Codes AP-10675, 10676 AP-10803, 10804 AP-10833, 10834 WW-51, 52 M1-72, 73 MI-96, 97 U-858, 859 M1-389, 390 DW-879, 880 SWU-813, 814 141-708, 709 MI-740, 741 MI-740, 741 MI4-789, 790 DW-901, 902 SWU-1544, 1545 DW-1426, 1427 DW-1426, 1427 WW%-1476, 1477 M1-1523, 1524 M1-1523, 1524 N,1-1572, 1573 MI-1572, 1573 SW-1648, 1649 MI-1800, 1801 SW-1779, 1780 SW-1779, 1780 MI-1447, 1448 NU1-1447,1448 WW-2115, 2116 SW-1698, 1699 DW-2272, 2273 WWr-2356, 2357 AP-2812, 2813 AP-2812, 2813 LW-2217, 2218 153 Sample Date Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Analysis Be-7 Be-7 Be-7 H-3 K-40 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 1-131 K-40 K-40 Gr. Beta Gr. Beta Gr. Beta H-3 H-3 1-131 K-40 K-40 Sr-90 K-40 K-40 Gr. Alpha Gr. Beta 1-131 K-40 H-3 Gr. Beta Gr. Beta Gr. Beta Be-7 Be-7 Gr. Beta First Result 0.06 +/-+0.02 0.04:+/- 0.01 0.04 +/- 0.01 362.60 +/- 94.70 1,566.90 +/- 196.80 1,418.30 :+/- 117.80 2.17 +/- 2.47 1,489.20 +/- 141.10 2.63 +/- 0.52 2.48 + 0.58 1,179.40 +/- 103.00 0.01 +/- 0.26 1,434.00 +/- 156.50 1,584.30 +/- 158.80 4.67 +/- 1.08 3.13 +/- 0.63 2.05 +/-0.92 42.60 +/- 94.23 53.06 +/- 65.79
-0.01 +/- 0.20 1,396.00 +/- 184.80 1,499.20 +/- 113.30 1.65:+/- 0.44 297.80 +/- 67.20 1,425.80 +/- 183.30 2.22 +/- 0.73 6.28 +/- 0.74
-0.65 +/- 0.27 1,496.20 +/- 155.40 540.04 +/--111.84 6.07 +/- 1.75 2.10 +/-:0.86 1.22 +/- 0.50 0.07 +/- 0.02 0.07 +/- 0.02 1.85 +/- 0.51 Second Result 0.06 +/- 0.02 0.04 +/- 0.01 0.04 +/- 0.01 417.20 +/- 96.80 1,372.40 +/- 152.50 1,545.70 +/- 162.50 4.23 +/- 2.74 1,463.30 +/- 168.20 2.37 +/- 0.50 2.46 t 0.63 1,280.40 +/- 90.26
-0.12 +/- 0.26 1,435.00 +/- 126.10 1,390.70 +/- 136.50 5.54 +/- 1.13 2.33 +/- 0.52 2.34 +/- 0.93 131.31 +/- 95.34 53.06 +/- 93.03
-0.10 +/-0.37 1,576.00 +/- 184.90 1,326.00 +/- 118.80 1.51 +/-0.52 344.80 +/- 82.30 1,372.20 +/- 119.70 2.14 +/- 0.69 6.62 +/- 0.70 0.13 +/- 0.55 1,413.40 +/- 169.60 500.85 +/- 110.46 5.57 +/- 1.85 1.63 +/-0.83 1.32 +/- 0.47 0.05 +/- 0.01 0.05 +/- 0.01 2.23 +/- 0.55 Averaged Result 0.06 +/- 0.01 0.04 +/- 0.01 0.04 +/- 0.01 389.90 +/- 67.71 1,469.65 +/- 124.49 1,482.00 +/- 100.35 3.20 +/- 1.84 1,476.25 +/- 109.77 2.50 +/- 0.36 2.47 +/- 0.43 1,229.90 +/-68.48
-0.05 +/- 0.18 1,434.50 +/- 100.49 1,487.50 +/- 104.70 5.11 +/-0.78 2.73 +/- 0.41 2.20 +/- 0.65 86.96 +/- 67.02 53.06 +/- 56.97
-0.06 +/- 0.21 1,486.00 +/- 130.71 1,412.60 +/- 82.08 1.58+/- 0.34 321.30 +/- 53.13 1,399.00 +/- 109.46 2.18 +/- 0.50 6.45 +/- 0.51
-0.26 +/- 0.31 1,454.80 +/- 115.01 520.44 +/- 78.59 5.82 +/- 1.27 1.87 +/- 0.60 1.27 +/- 0.35 0.06 - 0.01 0.06 +/- 0.01 2.04 +/- 0.37
D1avis-Bessc Nuclear Power Station 2001 Animal R'adiological Environmental Operating Report Table A-5.
In-house "duplicate"' samples.
Concentration in pCiiLa Lab Codes AP-2833, 2834 AP-3038, 3039 AP-3038, 3039 DW-2398, 2399 LW-2467, 2468 MI-2446, 2447 AP-3017, 3018 SW-2423, 2424 BS-3103, 3104 SWU-3239, 3240 SS-3322, 3323 W-3990, 3991 BS-4347, 4348 BS-4347, 4348 MI-3364, 3365 SO-3385, 3386 SO-3385, 3386 SO-3385, 3386 CL-4068, 4069 MI-3475, 3476 Vv'XV-3545, 3546 MI-3681, 3682 SIW-3702, 3703 SW-3702, 3703 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 F-3813, 3814 G-4158, 4159 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 Sample Date Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 154 Analvsis Be-7 Be-7 Be-7 Gr. Beta Gr. Beta K-40 Be-7 K-40 Gr. Beta Gr. Beta K-40 Sr-89 K-40 K-40 K-40 Gr. Alpha Gr. Beta K-40 K-40 Gr. Beta Gr. Beta K-40 Gr. Alpha Gr. Beta Cs-137 H-3 K-40 Pu-238 Pu-239/40 Ra-226 Sr-90 K-40 Be-7 Ac-228 Bi-214 Cs-137 First Result 0.04 +/- 0.01 0.07 +/- 0.02 0.06 +/- 002 1.58 +/- 0.89 2.52 +/- 0.53 1,285.40 +/-177.10 0.05 ! 0.01 255.60 +/- 59.80 7.99 +/- 1.80 3.30 +/- 0.60 15.99 +/- 1.08 91.35 +/-18.94 3,982.40 +/- 489.60 3.26 +/- 0.45 1,325.90 +/- 160.20 6.51 +/-3.09 24.63+/-3.15 19.17 +/- 1.08 1.09 +/- 0.27 1,297.10+/-114.60 1.57 +/- 0.55 1,417.20 +/- 125.70 4.51 +/- 1.66 8.74 +/- 1.36 224.30 +/- 30.20 842.00 +/-47.00 21,117.00 +/-953.00 80.30 +/- 36.50 49.40 +/- 31.80 7,436.00 +/- 577.90 10.60 +/- 2.71 2.10+/-0.17 0.37 +/- 0.13 0.45 +/- 0.13 0.31 +/- 0.06 0.46 +/- 0.05 Second Result 0.06 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 1.81 +/- 0.88 2.42 +/- 0.53 1,376.00 +/-+ 175.90 0.05 +/- 0.01 268.40 +/- 65.40 8.17+/-1.73 4.30 +/- 0.74 15.59 +/- 1.01 85.29 +/- 23.99 3,255.80 +/- 450.10 3.98 +/- 0.49 1,453.20 +/- 163.00 9.01 +/- 3.44 28.17 +/- 3.12 17.94 +/- 0.76 1.13 +/- 0.23 1,433.60 +/- 156.60 1.36 +/- 0.53 1,496.20 +/- 124.50 3.22 +/- 1.55 7.11 +/- 1.38 205.90 +/- 43.00 860.00 +/- 48.00 21,629.00 +/- 1,357.00 59.50 +/- 22.00 41.10 +/- 19.60 9,126.00 +/- 751.90 16.80 +/- 3.22 2.30 +/- 0.26 0.41 +/- 0.14 0.52 +/- 0.14 0.41 +/- 0.06 0.47 +/-0.04 Averaged Result 0.05 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 1.69 +/- 0.63 2.47 +/- 0.37 1,330.70 +/- 124.81 0.05 +/- 0.00 262.00 +/- 44.31 8.08+/- 1.25 3.80 +/- 0.48 15.79 +/- 0.74 88.32+/- 15.28 3,619.10 +/- 332.53 3.62 +/- 0.33 1,389.55 +/- 114.27 7.76 +/- 2.31 26.40 +/- 2.22 18.56 +/- 0.66 1.11 +/-0.18 1,365.35 +/- 97.03 1.47 +/- 0.38 1,456.70 +/- 88.46 3.87 +/- 1.13 7.93 +/- 0.97 215.10 +/- 26.27 851.00 +/- 83.59 21,373.00 +/- 829.10 69.90 +/- 21.31 45.25 +/- 18.68 8,281.00 +/- 474.16 13.70 +/- 2.10 2.20.+/- 0.16 0.39 +/- 0.10 0.49 +/-+-0.10 0.36 +/-0.04 0.47 +/- 0.03
Davis.-Bi3ý,wS Ntcleair Power Station 2001 Annual Ra1diological IEnvironmcntal Operating Reporl Table A-5.
In-house "duplicate" samples.
Concentration in pCi/L" Lab Codes SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 BS-423.3, 4234 BS-4233, 4234 SWU-4376, 4377 DW-4449, 4450 DW-4397, 4398 MI-4114, 4115 F-4284, 4285 DW-4326, 4327 MI-4470, 4471 SW-4493, 4494 BS-4725, 4726 BS-4725, 4726 BS-4725, 4726 MI-4775, 4776 Cr-5110, 5111 G-5085, 5086 G-5085, 5086 MI-5259, 5260 MI-5259, 5260 SWU-5422, 5423 VE-5401, 5402 VE-5401, 5402 AP-5830, 5831 SW-5557, 5558 AP-5851, 5852 SW-5636, 5637 LW-5681, 5682 G-5535, 5536 G-5535, 5536 G-5535, 5536 AP-5788, 5789 155 Sample Date May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Analvsis Gr. Beta K-40 Pb-212 Ra-226 T1-208 Cs-137 K-40 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Gr. Beta K-40 Gr. Beta Co-60 Cs-137 K-40 K-40 H-3 Be-7 K-40 K-40 Sr-90 Gr. Beta Gr. Beta K-40 Be-7 Gr. Beta Be-7 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 First Result 26.65 +/- 2.63 16.35 +/--0.86 0.35 +/- 0.04 0.56 +/- 0.98 0.14 +/- 0.03 0.03 +/- 0.01 8.18 +/-0.48 2.58 +/- 0.55 2.83 +/- 0.55 9.13 +/- 1.26 1,325.90 +/- 118.80 2.23 +/- 0.32 2.60 +/- 0.97 1,514.50 +/- 116.60 4.05 +/- 1.23 112.00 +/- 24.30 3,083.10 +/- 100.10 8,143.70 +/- 640.40 1,362.20 +/- 71.80 1,173.50 +/- 129.10 0.89 +/- 0.17 5.13 +/- 0.39 1,529.70 +/-122.70 1.69 +/- 0.42 2.59 +/- 0.54 8.12:+/- 0.24 6.55 +/- 0.52 0.08 +/- 0.01 5.43 +/- 1.70 0.07 +/- 0.02 4.75 +/- 1.38 2.42 +/- 0.37 0.99 +/- 0.29 7.62 +/- 0.12 7.26 +/- 1.03 0.08 +/- 0.02 Second Result 24.68 +/- 2.52 16.05 +/- 0.82 0.43 +/- 0.05 1.03 +/- 0.31 0.17 +/- 0.03 0.03 +/- 0.02 7.80 +/- 0.58 2.94 +/- 0.58 3.74 +/- 0.65 10.20 +/- 1.34 1,394.70 +/- 133.10 2.12 +/- 0.35 1.47 +/- 0.83 1,456.80 +/- 130.90 4.64
- 1.32 84.50 +/- 8.70 3,094.80 +/- 35.30 8,083.80 +/- 225.10 1,363.90 +/-73.40 1,046.80 +/- 125.20 1.14 +/- 0.39 5.22 +/-0.70 1,406.20 _ 123.80 1.71 +/- 0.44 1.91 +/-_0.52 8.88 +/- 0.26 6.26 +/- 0.65 0.08 +/- 0.01 5.96 +/- 1.56 0.07 +/- 0,02 4.18 +/- 1.34 2.18 +/- 0.34 0.97 +/- 0.54 7.72 +/- 0.12 7.64 +/- 0.93 0.07 +/- 0.02 Averaged Result 25.67 _ 1.82 16.20 +/- 0.59 0.39 - 0.03 0.79 t 0.51 0.15 --t 0.02 0.03 - 0.01 7.99 -0.38 2.76+/-0.40 3.29 +/- 0,43 9.66 +/- 0.92 1,360.30 +/- 89.20 2.18 _t 0.24 2.04 +/- 0.64 1,485.65 +/-87.65 4.35 +/- 0.90 98.25 +/- 12.91 3,088.95 +/- 53.07 8,113.75 +/- 339.40 1,363.05 +/- 51.34 1,110.15 +/- 89.92 1.02 +/- 0,21 5.17 +/- 0.40 1,467.95 +/- 87.15 1.70 +/- 0.30 2.25 +/- 0.37 8.50 +/- Q.18 6.40 +/- 0.42 0.08 +/- 0.01 5.70 +/- 1.15 0.07 +/- 0.01 4.47 +/- 0.96 2.30 +/- 0.25 0.98 +/- 0.31 7.67 - 0.08 7.45 +/- 0.69 0.08 +/- 0.01
II Davis-Besse Nuclear Power Station 2001 Annuwa Radiolhgical Enviromierual Operating Report Table A-5.
In-house "duplicate" samples.
Concentration in pCi/L' Lab Codes AP-5872, 5873 AP-5893, 5894 AP-5809, 5810 SW-5724, 5725 SW-5724, 5725 SW-5767, 5768 LW-5920, 5921 SO-6172, 6173 SO-6172, 6173 SO-6172, 6173 MI-6353, 6354 SW-6376, 6377 VE-6424, 6425 VE-6424, 6425 MI-6445, 6446 LW-6489, 6490 MT-6533, 6534 DW-6835, 6836 MI-6693, 6694 MI-6693, 6694 WW-6952, 6953 MI-6906, 6907 VE-6973, 6974 LW-7851, 7852 MI-7001, 7002 MI-7073, 7074 LW-7145, 7146 MI-7221, 7222 MI-7221, 7222 SWU-7527, 7528 VE-7485, 7486 DW-7506, 7507 MI-7622, 7623 MI-7664, 7665 MI-7876, 7877 G-7960, 7961 Sample Date Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 200i Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 156 Analysis Be-7 Be-7 Be-7 Gr. Alpha Gr. Beta 1-131 Gr. Beta Cs-137 K-40 Sr-90 K-40 1-131 Gr. Beta K-40 K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Beta K-40 K-40 Gr. Beta K-40 K-40 Gr. Beta K-40 Sr-90 Gr. Beta K-40 Gr. Beta K-40 K-40 K-40 Be-7 First Result 0.07 _ 0.02 0.08 +/- 0.02 0.07 +/- 0.02 2.95 +/- 0.70 8.79 +/- 0.71 0.79 +/- 0.31 3.06 +/- 0.64 0.30 +/- 0.05 18.20+/- 1.08 0.03 +/- 0.01 966.35 +/- 82.28 0.58 +/- 0.16 2.52 t 0.05 3.04 +/- 0.26 1,407.40 +/- 97.10 2.61 +/- 0.57 1,498.60 +/- 113.90 2.01 +/- 0.59 1,294.30+/-118.70 1.47+/-0.42 5.49 +/- 0.69 1,613.80 +/- 218.50 4.21 +/- 0.24 2.20 +/- 0.48 1,453.80 +/- 148.10 1,217.30 +/- 80.83 2.77 +/-0.53 1,192.90 +/- 95.40 2.10 +/- 0.48 17.51 +/- 3.06 2.12 +/- 0.47 4.25 +/- 1.18 1,340.10 +/- 111.10 1,408.10 +/-102.70 1,416.40 +/-192.30 1.27 +/- 0.21 Second Result 0.08 4 0.02 0.08 +/- 0.01 0.06 +/- 0.01 2.89 +/- 0.60 8.21 +/- 0.65 0.61 -t 0.26 3.15 +/- 0.58 0.32 +/- 0.04 17.55 +/- 0.82 0.05 "-+/-
0.02 986.31 +/-91.91 0.81 +/- 0.17 2.49 +/- 0.05 3.12 +/- 0.37 1,442.20 - 189.60 2.79 +/- 0.54 1,375.50 +/- 129.60 2.36 +/- 0.63 1,417.30 +/- 176.50 1.23 +/- 0.41 5.80 +/-t 0.69 1,532.70 +/- 135.80 4.29 t 0.64 2.12 _ 0.42 1,285.30 +/- 190.50 1,218.30 +/- 99.13 3.60 +/- 0.59 1,388.90 +/- 132.70 1.72 +/- 0.47 20.36 t 3.31 2.47 +/- 0.34 4.13-+/-1.12 1,290.80 +/- 116.50 1,396.90 +/- 114.30 1,318.00 +/- 155.50 1.25 +/- 0.25 Averaged Result 0.07 +/- 0.01 0.08 +/- 0.01 0.06 +/- 0.01 2.92 +/- 0.46 8.50 +/- 0.48 0.70 +/- 0.20 3.11 +/-0.43 0.31 +/- 0.03 17.88 +/- 0.68 0.04 +/- 0.01 976.33 +/- 61.68 0.70 +/-0.12 2.51 +/- 0.03 3.08 +/- 0.23 1,424.80 +/- 106.51 2.70 +/- 0.39 1,437.05 +/- 86.27 2.19 +/- 0.43 1,355.80 106.35 1.35 +/- 0.29 5.64 +/-0.49 1,573.25 +/- 128.63 4.25 +/- 0.34 2.16 +/- 0.32 1,369.55 +/- 120.65 1,217.80 +/- 63.95 3.19 +/--0.39 1,290.90 +/- 81.72 1.91 +/- 0.34 18.93 +/- 2.25 2.30 +/- 0.29 4.19:+/-0.81 1,315.45 +/- 80.49 1,402.50 +/- 76.83 1,367.20 +/- 123.65 1.26 +/- 0.16
Davi',.-Be1se Nudiear Power Station 20) 1 Armual I.'idiological Elvironnrental Ope.ating Report Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Codes G-7960, 7961 F-8011, 8012 F-8011, 8012 F-8011, 8012 INU-8149, 8150 MI-8343, 8344 VE-8319, 8320 VE-8319, 8320 AP-9069, 9070 AP-9566, 9567 VE-8700, 8701 VE-8700, 8701 VE-8700, 8701 AP-9048, 9049 DW-8636, 8637 DW-8615, 8616 AP-9090, 9091 AP-9166, 9167 AP-9187, 9188 VE-10562, 10563 VE-10562, 10563 WW-8636, 8637 DW-8894, 8895 MI-9232, 9233 VE-9518, 9519 WW-10257, 10258 VE-10333, 10334 VE-10333, 10334 MI-10588, 10589 DW-10688, 10689 WW-10905, 10906 SS-10953, 10954 SS-10953, 10954 SS-10953, 10954 SS-10953, 10954 SS-10953, 10954 Sample Date Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Analysis K-40 Cs-137 Gr. Beta K-40 K-40 K-40 Gr. Beta K-40 Be-7 Be-7 Be-7 K-40 Sr-90 Be-7 Gr. Beta Gr. Beta Be-7 Be-7 Be-7 Be-7 K-40 Gr. Beta Gr. Beta K-40 K-40 H-3 Be-7 K-40 K-40 Gr. Beta H-3 Ac-228 Bi-214 Co-58 Co-60 Cs-137 First Result 5.21 +/-0.57 0.06 +/-0.02 3.68 +/- 0.12 3.47 +/- 0.49 1,551.70 +/- 118.00 1,550.30 +/- 170.60 3.37 - 0.10 2.14 +/- 0.46 0.07 +/- 0.02 0.08 +/- 0.02 0.24 +/- 0.10 2.03 +/- 0.24 0.01 +/- 0.00 0.07 +/- 0.01 4.74 +/- 1.06 4.65 +/-0.58 0.07 -0.01 0.08 +/- 0.02 0.07 +/- 0.01 309.90 +/- 158.80 6,407.10 +/- 620.70 5.08 +/- 1.20 4.28 +/- 0.89 1,440.70 +/- 46.60 1.91+/-0.22 755.90 +/- 10250 0.68 +/- 0.26 6.10 +/- 0.72 1,428.40 +/- 114.70 3.49 +/-0.91 233.90 +/- 90.60 1.10+/- 0.25 0.69 +/-0.08 0.21 +/- 0.05 0.93 +/- 0.06 0.13 +/- 0.03 Second Result 5.70 +/- 0.63 0.04 +/- 0.02 3.50+/- 0.11 3.38 - 0.47 1,489.90 +/- 123.60 1,368.10 +/- 126.70 3.42+/-0.11 2.24 +/- 0.37 0.07 +/- 0.01 0.09 +/- 0.03 0.19 +/- 0.10 2.03 +/- 0.21 0.01 +/-!0.00 0.07 +/- 0.00 5.08 +/- 1.21 4.28 +/- 0.54 0.07 +/- 0.01 0.08 +/- 0.02 0.05 +/- 0.01 348.30 +/- 168.10 6,057.50 +/- 660.40 4.74 +/- 1.06 3.40 +/- 0.90 1,424.80 +/- 76.40 1.97 +/- 0.39 684.70 +/- 99.90 0.99 +/- 0.26 5.83 +/- 0.72 "1,445.50 +/- 129.40 2.36 -0.76 226.30 +/- 90.20 0.91.+/-0.16 0.75 +/- 0.08 0.18 +/- 0.04 0.94 +/- 0.06 0.16 +/- 0.03 Averaged Result 5.45 +/- 0.43 C.05 +/- 0.01 3.59 +/- 0.08 3.43 +/- 0.34 1,520.80 +/- 85.44 1,459.20 +/- 106.25 3.39 +/- 0.07 2.19 +/- 0.29 0.07+/-0.01 0.09 +/- 0.02 0.22 +/-0.07 2.03 +/-- 0.16 0.01 +/- 0.00 0.07 +/- 0.01 4.91 +/- 0.80 4.47 +/- 0.40 0,07 +/- 0.01 0.08 +/- 0.01 0.06 +/- 0.01 329.10 +/- 115.62 6,232.30 +/- 453.15 4.91 +/- 0.80 3.84 +/- 0.63 1,432.75 +/- 44.75 1.94 +/- 0.22 720.30 +/- 71.57 0.84 +/- 0.18 5.97 +/- 0.51 1,436.95 +/- 86.46 2.93 +/- 0.60 230.10 +/- 63.92 1.00 +/- 0.15 0.72 +/- 0.06
- 0. 19 +/-0.03 0.93 +/- 0.04 0.14 +/- 0.02 157
Davis-P~sse Ntuclear Powe'r Station 2001 Aanuzil Radiological Environmental Operating Report Table A-5.
In-house 'duplicate" samples.
Concentration in pCi/L' Lab Codes SS-10953, 10954
$5-10953, 10954 SS-10953, 10954 SS-10953, 10954 SS-10953, 10954 MI-11033, 11034 MI-11033, 11034 AP-11888, 11889 Sample Date Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Analysis K-40 Pb-212 Pb-214 Ra-226 TI-208 K-40 Sr-90 Be-7 First Result 9.91 t+/-0.83 0.94 +/- 0.05 0.83 +/- 0.08 1.76 +/- 0.37 0.34. 0.05 1,339.80 4-128.70 1.31 -0.41 0.06 t 0.02 Second Result 8.36 +/- 0.80 0.91 +/- 0.06 0.82 +/- 0.07 1.67 +/- 0.37 0.31 +/- 0.05 1,435.80 +/--117.30 1.38 + 0.37 0.06 +/- 0.02 Averaged Result 9.13 + 0.57 0.92 +/-- 0.04 0.83 t 0.05 1.72 +/- 0.26 0.32 +/- 0.04 1,387.80 +/- 87.07 1.35 _ 0.28 0.06 +/- 0.01 Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
Results are reported in units of pCi/L, except for elemental potassium (K) in milk (mg/L), air filters (pCi/Filter),
food products and vegetation (pCi/g), soil and sediments (pCi/kg).
158 I
Davis-Bcsse Nude-ar Power Station 2001 Animal Radiological Environmnental Operating Report Table A-6.
Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentrationb Lab Sample Date MAPEP Resultd Control Code Type Collected Analysis Laboratory resultc Is, N=I Limits ST'SO-923 SOIL Jan, 2001 Am-241 0.00 - 2.60 Included as false positive. Result of analyses; < 0.8 Bq/L.
STSO-923 SOIL Jan, 2001 Co-57 100.20 +/- 3.50 103.00 +/- 10.30 72.10 - 133.90 STSO-923 SOIL Jan, 2001 Co-60 1,285.10+/-5.30 1,270.00+/- 127.00 889.00 - 1,651.00 STSO-923 SOIL Jan, 2001 Cs-134 81.10 +/- 1.80 91.10 +/- 9.11 63.77 - 118.43 STSO-923 SOIL Jan, 2001 Cs-137 1,210.60 +/- 6.60 1,240.00 +/- 124.00 868.00 - 1,612.00 STSO-923 SOIL Jan, 2001 K-40 732.60 +/- 21.20 652.00+/- 65.20 456.40 - 847.60 STSO-923 SOIL Jan, 2001 Mn-54 212.60:+/-6.70 203.00 t 20.30 142 263.90 STSO-923 SOIL Jan, 2001 Pu-238 110.70 +/- 7.20 115.00 +/- 11.50 80.50 - 149.50 STSO-923 SOIL Jan, 2001 Pu-239/40 79.60 +/-5.90 83.40 -+/- 8.34 58.38 - 108.42 STSO-923 SOIL Jan, 2001 Sr-90 159.80 +/- 9.50 209.00 +/- 20.90 146.30 - 271.70 STSO-923 SOIL Jan, 2001 U-233/4 45.00 +/- 3.90 60.00 +/- 6.00 42.00 - 78.00 STSO-923 SOIL Jan, 2001 U-238 165.60 +/- 7.40 191.00 +/- 19.10 133.70 - 248.30 STSO-923 SOIL Jan, 2001 Zn-65 428.50 +/- 10.90 382.00 +/- 38.20 267.40 - 496.60
" Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.
b All results are in Bq/kg or Bq/L as requested by the Department of Energy.
SMAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.
159
Davis-iBsse Nuclear Power Statio.. 2001 Am mai Radioiogical EnviTomnenta OpCerating Report Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)'.
Concentration b Lab Sample Date Control Code STSO-904 STSO-904 STSO-904 Possible STSO-904 STSO-904 STSO-904 STSO-904 STSO-904 STSO-904 STSO-904 STW-905 STW-905 STW-905 STW-905 STW-905 STW-905 STW-905 STW-905 STW-905 STW-906 STW-906 STAP-907 STAP-907.
STAP-907 STAP-907 STAP-907 STAP-907 STAP-907 Analvsis Laboratory result EML Result Limitsd Ac-228 Am-241 Bi-212 Type SOIL SOIL SOIL effect of shield SOIL SOIL SOIL SOIL SOIL SOIL SOIL WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER 45.600 +/- 4.000 14.400 +/- 0.500 53.200 +/- 3.100 Collected Mar, 2001 Mar, 2001 Mar, 2001 background.
Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 160 42.700 14.800 42.000 32.600 1,740.000 468.000 41.500 34.300 25.600 69.000 1.670 98.200 73.000 79.300 1.580 1.640 4.400 1.040 1.040 1,900.000 1,297.000 0.486 19.440 2.830 8.760 6.520 0.215 0.136 0.80- 1.50 0.63 - 2.64 0.45-1.23 0.78 - 1.50 0.80- 1.29 0.80- 1.37 0.74-1.36 0.76 - 1.53 0.71 - 1.33 0.61 - 3.91 0.76-1.48 0.80- 1.20 0.80 - 1.20 0.74 - 2.29 0.74-1.22 0.75 - 1.26 0.64-1,50 0.80- 1.40 0.80- 1.29 0.58 - 1.26 0.56-1.50 0.69 - 2.40 0.79 - 1.30 0.74-1.21 0.78 - 1.35 0.80- 1.36 0.66-1.35 0.69-1.29 Bi-214 Cs-137 K-40 Pb-212 Pb-214 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 H-3 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Gr. Alpha Gr. Beta Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 42.100 +/- 7.700 1,772.600 +/- 79.800 583.800 +/- 52.600 46.600 +/- 8.500 45.300 +/- 8.600 26.000 +/-0.800 55.600 +/- 2.200 2.150 +/- 0.140 97.000 +/- 0.800 70.100 +/- 4.000 76.500 +/-5.500 1.690 +/- 0.070 1.690 +/- 0.070 3.850 +/- 0.130 0.900 +/-0.050 0.880 +/- 0.050 1,724.600 +/-141.700 1,246.400 +/- 31.100 0.470 +/- 0.040 20.110 +/- 0.160 2.710 +/- 0.150 9,860 +/- 0.230 7.250 +/- 0.220 0.230 +/- 0.030 0.120 +/- 0.020
Davis-Bcss',: Nnclcr IPower StaLioni 2001 Annual Radiological Environniental Operating Report Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)'.
Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory result EML Result' Limits" STAP-907 STAP-907 STAP-907 STAP-908 STAP-908 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-926 STW-926 STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER SOIL SOIL SOIL SOIL SOIL SOIL Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sr-90 U-233/4 U-238 Gr. Alpha Gr. Beta Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 H-3 Ni-63 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta Ac-228 Am-241 Bi-212 Bi-214 Cs-137 K-40 161 7.410 +/- 0.150 0.050 +/- 0.010 0.050 +/- 0.010 2.660 +/- 0.020 2.300 +/- 0.020 6.100 +/- 0.200 3.500 +/-0.500 28.500:+/- 2.100 795.500 +/- 76,400 592.600 +/- 42.500 8.500 +/- 0.600 1,239.600 +/- 130.000 0.700 +/- 0.100 206.700 +/- 4.700 46.600 +/- 0.800 254.100 +/- 3.600 50.900 +/- 3.000 1.100 +/- 0.100 1.600 +/- 0.100 4.100 +/- 0.300 2.200 +/- 0.200 1,220.000 +/- 32.000 8,461.000 +/- 206.000 68.100 +/- 1.400 5.200 +/- 1.300 65.100 +/- 1.600 47.300 +/-4.700 659.200 +/-10.800 737.700 +/- 16.600 7.100 0.046 0.046 3.970 2.580 6.170 3.690 30.400 842.000 603.000 9.580 1,330.000 0.760 209.000 45.133 207.000 45.250 1.088 1.628 3.729 2.372 1,150.000 7,970.000 59.570 4.432 62.067 36.900 612.330 623.330 0.55 - 2.05 0.80- 1.92 0.80- 1.59 0.57-1.47 0.76-1.52 0.72-2.34 0.61-1.61 0.75-1.51 0.80- 1.37 0.78-1.43 0.67-1.49 0.52-1.23 0.76-1.48 0.80- 1.20 0.80- 1.24 0.74 - 2.29 0.70- 1.30 0.74-1.22 0.75-1.26 0.64 - 1.50 0.73-1.37 0.58-1.26 0.56-1.50 0.80- 1.50 0.63-2.64 0.45-1.23 0.78 - 1.50 0.80 - 1.29 0.80- 1.37
oI I I )1.vis-1Rc.ss, Nuc'ear Power Station 2001 Anana.m I
- EIdIio, ca1 LnVirommn)eal Opeatirng Report Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)ý.
Concentration, Lab Sample Code Type STSO-927 SOIL STSO-927 SOIL STSO-927 SOIL STSO-927 SOIL STSO-927 SOIL STVE-928 VEGETATION STVE-928 VEGETATION STVE-928 VEGETATION STVE-928 VEGETATION STVE-928 VEGETATION STVE-928 VEGETATION STVE-928 VEGETATION STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-929 AIR FILTER STAP-930 AIR FILTER STAP-930 AIR FILTER Date Collected Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001
" The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Vegetation and Water.
b Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.
' The EML result listed is the mean of replicate determinations for each nuclide+/-the standard error of the mean.
d Control limits are reported by EML as the ratio of Reported Value / EML value.
162 Analysis Pb-212 Pb-214 Pu-239/40 Sr-90 Uranium Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-r-39/40 Sr-90 Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta Laboratory result 64.700 +/- 3.800 53.700 +/- 7.700 9.300 +/- 2.900 27.400 +/- 6.300 155.600 +/- 7.800 7.000 +/- 0.300 4.300 +/- 0.800 40.200 +/- 0.900 1,184.000 +/- 2.800 1,023.000 +/-44.100 8.900 +/- 1.400 1,364.000 +/- 18.400 0.090+/-30.000 16.900 +/-0.300 11.800+/-0.200 18.300 +/- 0.300 85.400 +/- 1.300 0.051 +/-0.010 0.220 +/- 0.020 3.110 +/- 0.060 0.240 +/- 0.050 6.300 +/-0.100 13.800 t 0.100 58.330 39.670 8.948 30.596 194.230 6.915 4.308 35.300 1,030.000 898.670 11.022 1,612.800 0.088 17.500 12.950 17.100 81.150 0.071 0.229 3.481 0.222 5.362 12.770 EML Resu Control It,:
Limits" 0.74-1.36 0.76-1.53 0.71 - 1.33 0.61 - 3.91 0.62 - 1.35 0.72 - 2.34 0.61 - 1.61 0.75-1.51 0.80 - 1.37 0.78-1.43 0.67-1.49 0.52-1.23 0.69 - 2.40 0.79-1.30 0.74-1.21 0.78-1.35 0.80- 1.36 0.66-1.35 0.69-1.29 0.55 - 2.05 0.80 - 2.54 0.57-1.47 0,76-1.52
Davis-Bessý Nlucleai Pow-.r Sial.lon 200 i Annual Radioloý,.ical 1; iroriniental OperzW)g RCPOrt
.APPLNDD(.B DkTA REpORTING coNVENTIONS 163
Dav\\s-Bessc Nuckea= lower Station 2001 Annimal Radiological Environ.merntr Operating Report Data Renorting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x 4-s where:
x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L,- it is reported as: : <L, where L =.the lower limit of detection based on 4.66s uncertainty for. a background :sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xj I sI and x2 :L S2 Reported result:
x + s; where x = (1/2) (xl + x2) and s (W/2) 2 S2 3.2. Individual results:
<L 1, <L2 Reported result: <L, where L = lower of LI -and L'2 3.3. Individual results:
x : s, <L Reported result:
x -s if x>_ L; <L otherwise..
4.0... Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individue.l measurements over the period averaged; for example, an annual standard deviation would not b.
the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers xI, x2... Xn are defined as follows:
4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1.
If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to tt.45.
164
Davis-IDcsske N uclear Pc}'ver Stati.-on 20 A~iwai Ridc1logical EnvronnrCflVlT)01 OPCIuilling RCII(rl APPENDIX C Emuent Conicentration Limit of Radioactivity in Air and Water Above Natural Background in Uartstricted Areas 165
.)ais-13s.-u.~Nuciear Powe'r Station 2001 Annual Radiologi.cal I.virionmental Operating Report Table C-I Effluent Concentration Limit of Radioactivity in Air and Water Abbvc Natural Background in Unrestricted Area?
Air Water Gross Alpha Gross Beta lodine-131b IE-03 pCi/m3 I pCu/r' 2.86E-01 pCi/mr Strontium-89 Strontium -90 Cesium-137 Barium-l40 Iodine-131 Potassium.40C Gross Alpha Gross Beta Tritium 8,000 pCi/I 500 pCi/O 1,000 pCiA 8,000 pCa 1,000 pCi/I 4.0)00 pCP/
2 pCi/I 1x00* pCi/A Taken from Code of Federa Regulation Title 10, Part 20, Table II and appropriate footnotes. Concentrations may be averaged over a period not greater than one year.
b From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air grass-cow-child pathway.
A natural radionuclide.
166
-1.
Davis-l.ks.w Nuchnr Povvcr Slý,.tiojl 200 1 Armiml k,,jcjl()[ovjc,,jj ETI-vir)Ijillental Operating Rt.port APPEN'DIX D REEPAP SAMPUNG
SUMMARY
167
II Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Tabie 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Loca'ion of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio (County, State}
Docket No.
50-346 Reporting Period January-December, 2001 168 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)c Mean (Fl Mean (Ff Routine (Units)
Analyses Range' Locationc Range-^
RangeC Resultse Airbome GB 519 0.005 0.025 (3111311)
T-9, Oak Harbor 0.027 (52/52) 0.025 (208/208) 0 Particulates (0.009-0.067) 6.8 mi. SW (0.012-0.058)
(0.006-0.064)
(pCiim3)
Sr-89 0.0016
< LLD
< LLD 0
Sr-90 0.0017
< LLD
< LLD 0
GS 40 Be-7 0,015 0.069 (24/24)
T-4, Site Boundar, 0.076 (414) 0.069 (16/16) 0 (0.042-0.093) 0.8 mi. S (0.053-0.093)
(0.047-0.107)
K-40 0.039
< LLD
< LLD 0
Nb-95 0.0014
< LLD
< LLD 0
Zr-95 0.0017
< LLD
< LLD 0
Ru-103 0.0014
< LLD
< LLD 0
Ru-106 0.0102
< LLD
< LLD 0
Cs-1 34 0.0140
< LLD
< LLD 0
Cs-137 0.0011
< LLD
< LLD 0
Ce-141 0.0023
< LLD
< LLD 0
Ce-!44 0.0075
< LLD
< LLD 0
Airborne Iodine 1-131 519 0.07
< LLD
< LLD 0
(pCi/m3)
TLD (Quarterly) Gamma 340 1.0 14.4 (2941294)
T-45. Site Boundary 20,2 (414) 14,8 (46/46) 0 (mRJ91 days)
(6.4-24.1) 0.5 mL. WNW (17.4-23.2)
(9,6-19.7)
TLD (Quarterly) Gamma 4
1.0 6,7 (4/4)
None 0
(mR/91 days)
(5.9-7.1)
(Shield)
TLD (Annual)
Gamma 85 1.0 55.6 (76t76)
T-87, Site boundary 79.6 (1/1i) 58.0 (9/9) 0 (mR'365 days)
(31.1-79.6) 0.3 mi. NNW (38.6-72,6)
TLD (Annual)
Gamma 1
1.0 21.9 (111)
None 0
(mRi365 days)
(Shield)
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environinental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio (County, State)
Docket No.
Reporting Penod 50-346 January-December, 2001 Indicator Location with Highest Control Number Sample Type and Locatiions Annual Mean Locations Non Type Number of LLDb Mean (F)'
Mean (F)f Mean (F)f Routine (Units)
Analyses" Rangec Locationd Ranqec Rangec Resultse Milk (pCUi.)
1-131 12 0.4 none
< LLD 0
Sr-89 12 1.7 none
< LLD 0
Sr-90 12 1.0 none T-24, Sandusky 1.2 (5112) 1.2 (5!12) 0 21.0 mi. SE (1.1-1.4)
(1.1-1.4)
GS 12 K-40 100 none T-24, Sandusky 1378 (12112) 1378 (12/12) 0 21.0 mi. SE (1.1-1.4)
(1.1-1.4)
Cs-134 6.5 Cs-137 6.0 none
< LLD 0
Ba-La-140 9.6 none
< LLD 0
(g/L)
Ca 12 0.50 none T-24, Sandusky 0.87 (12/12) 0.87 (12-112) 0 21.0 ml. SE (0.79-1.00)
(0.79-1.00)
(gL)
K (stable) 12 0.10 none T-24, Sandusky 1.59 (12/12) 1.59 (12/12) 0 21.0 mi. SE (1,45-1.91)
(1.45-1.91)
(pCi/g)
Sr-90/Ca 12 0.00 none T-24, Sandusky 1.37 (6i12) 1.37 (6/12) 0 21.0 mi. SE (1.18-1.77)
(1.18-1.77)
(pCilg)
Cs-137/K 12 0.00 none
< LLD 0
Ground Water GB (TR) 5 3.7
< LLD
< LLD (pCi!L)
H-3 5
330 416 (1I)
T-225, residence LLD 0
1.55 mi. NW Sr-89 5
1.1
< LLD
< LLD 0
Sr-90 5
0.7
< LLD
< LLD 0
GS Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
CO-58 15
< LLD
< LLD 0
Co-60 15
< LLD
< LLD 0
Zn-65 30
Zr-95 15
< LLD
< LLD 0
Cs-134 10
< LLD
< LLD 0
Cs-137 10
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
169
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio
( County, State Docket No.
50-346 Reporting Period January-December, 2001 Indicator Location with Highest Controt Number Sampie Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)'
Mean (F)f Mean (F)c Routine (Units)
Analyses*
Range' Locationd RangeC Range' Results' Edible Meat GS 4
(pCi/g wet)
K-40 0.10 2.94 (2/2)
T-34, Offsite 3.44 (212) 3,44 (212) 0 (2.73-3.15)
Roving location (2,84-4.03)
(2.84-4.03)
Nb-95 0,032
< LLD
< LLD 0
Zr-95 0.033
< LLD LLD 0
Ru-i 03 0.032
< LLD
< LLD 0
Ru-106 0.12
< LLD
< LLD 0
Cs-137 0.013
< LLD
< LLD 0
Ce-141 0.072
< LLD
< LLD 0
Ce-144 0.093
< LLD
< LLD 0
Fruits and St-89 3
0.002
< LLD
< LLD 0
Vegetables Sr-90 3
0,001
< LLD
< LLD 0
(pCi/g wet) 1-131 3
0.017
< LLD
< LLD 0
GS 3
K-40 0.50 1.17 (2/2)
T-209, Orchard 1.34 (111) 1.34 (1/1) 0 (0.67-1.66) 18.9 mi. W Nb-95 0.011
< LLD
< LLD 0
Zr-95 0.030
< LLD
< LLD 0
Cs-137 0,010
< LLD
< LLD 0
Ce-141 0.021
< LLD
< LLD 0
Ce-144 0.077
< LLD
< LLD 0
Broad Leaf Sr-89 9
0.007
< LLD
< LLD 0
Vegetation Sr-90 9
0.004 0.008 (2/6)
T-19, Farm 0.009 (1/3)
< LLD 0
(pCi/g wet)
(0.006-0.009) 0.68 mi. W 1-131 9
0,025
< LLD
< LLD 0
GS 9
K-40 0.50 1.90 (6/6)
T-19, Farm 1.95 (3/3) 1.79 (3;3) 0 (1.48-2.20) 0.68 mi. W (1.48-2.20)
(1.64-1.89)
Nb-95 0.019
< LLD
< LLD 0
Zr-95 0.022
< LLD
< LLD 0
Cs-137 0.015
< LLD
< LLD 0
Ce-141 0.029
< LLD
< LLD 0
Ce-144 0.13
< LLD
< LLD 0
170
-1.
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio
( County, State)
Docket No.
50-346 Reporting Period January-December. 2001 171 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)C Mean (F)C Mean (F)'
Routine (Units)
Analysesa Rangec Locationd Rangec Rangec Results t
Animal I GS 5
Wildlife Feed Be-7 0.33 0.81 (1/3)
T-31, Onsite 0.81 (1/1) 0.70 (1/2) 0 (pCilg wet)
Roving location K-40 0,10 3.15 (3/3)
T-34, Offsite 8.05(1/1) 6.09 (2/2) 0 (1.11-7.01)
Roving location (4.13-8.05)
Nb-95 0.033
< LLD
< LLD 0
Zr-95 0.069
,< LLD
< LLD 0
Ru-103 0.028
< LLD LLD 0
Ru-106 0.20
< LLD
< LLD 0
Cs-137 0.019
< LLD
< LLD 0
Ce-141 0.073
< LLD
< LLD 0
Ce-144 0.19
< LLD LLD 0
Soil GS 20 (pCi/g dry)
Be-7 0.50 1.02(5/12)
T-4, Site Boundary 1.98(112) 0.92 (2/8) 0 (0.58-1.98) 0.8 mi. S (0.82-1.02)
K-40 0.10 13.35 (12112)
T-9, Oak Harbor 24.76 (2/2) 21.28 (818) 0 (4.68-23.10) 6.8 mi. SW (24.22-25.30)
(18.77-25.30)
Nb-95 0.083
< LLD
< LLD 0
Zr-95 0.11
< LLD
< LLD 0
Ru-103 0,064
< LLD
< LLD 0
Ru-106 0.38
< LLD
< LLD 0
Cs-137 0.050 0.13 (7/12)
T-12, Water Treatment 0.23(2/2) 0.18 (7/8)
(0.052-0.25)
Plant, 23.5 mi. WNW (0.20-0.26)
(0.086-0.26) 0 Ce-141 0.12
< LLD LLD 0
Ce-144 0.19
< LLD LLD 0
Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Ohio
( County, State)
Docket No.
50-346 Reporting Period January-December, 2001 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)'
Mean (F)'
Routine (Units)
Analysese Rangec Locationd Range' Rangec Resultse Treated GB (TR) 48 1.0 2.5 (24/24)
T-1 1, Port Clinton 2.7(12/12) 2.3 (24/24) 0 Surface Water (1.7-3.2)
VVTP, 9.5 mi. SE (2.1-3.5)
(1.6-3.5)
(pCVL)
H-3 16 330 593 (1/8)
T-22, Carroll Twp.
593 (1/4)
< LLD 0
WTP, 3.0 mi. NW Sr-89 16 1.7
< LLD
< LLD 0
Sr-90 16 1.0
< LLD
< LLD 0
GS 16 Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD
< LLD 0
Co-60 15
< LLD LLD 0
Zn-65 30
< LLD
< LLD 0
Zr-Nb-95 15
< LLD
< LLD 0
Cs-134 10
< LLD
< LLD 0
Cs-137 10
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
Untreated GB (TR) 95 1.0 3.1 (50/50)
T-137, Lake Erie 4.4 (7/7) 3.1 (45/45) 0 Surface Water (2.1-5.4) 7.0 mi. WNW (2.1-12.7)
(1.9-12.7)
(pCt'L)
H-3 95 330 713 (2/50)
T-3. Site Boundary 986 (1/12)
<LLD 0
330 (439-986) 1.4 mi. ESE Sr-89 20 1.6
< LLD LLD 0
Sr-90 20 0.8 1.9 (1/12)
T-3, Site Boundary 1.9 (114)
< LLD 0
1.4 mi. ESE GS 95 Mn-54 15
< LLD
< LID 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD LLD 0
Co-60 15
< LLD LLD 0
Zn-65 30
< LLD LLD 0
Zr-Nb-95 15
< LLD LLD 0
Cs-134 10
< LLD LLD 0
Cs-137 10
< LLD LLD 0
Ba-La-140 15
< LLD LLD 0
172
Davis-Bcsse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Station Ottawa, Oh;o Docket No.
50-346 Reporting Period January-December. 2001
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDO Mean (F)
Mean (F' Mean (F)'
Routine (Units)
Analysese Range.
Locationd Range' Rangeý Resultso Fish GB 6
0.1 2.97 (3/3)
T-33, Lake Erie 2.97 (313) 2.82 (3/3) 0 (pCi/g wet)
(2.70-3.12) 1.5 mi. NE (2.70-3.12)
(1.86-3.53)
GS 6
K-40 0.10 2.48(3/3)
T-35, Lake Erie 2.96 (3,3) 2.96 (3/3) 0 (1.95-3.11)
> 10mi.
(2,76-3.10)
(2.76-3.10)
Mn-54 0.013
< LLD
< LLD 0
Fe-59 0.032
< LLD
<LLD 0
Co-58 0.013
< LLD
< LLD 0
Co-60 0.014
< LLD
< LLD 0
Zn-65 0.026
< LLD
< LLD 0
Cs-134 0.014
< LLD
< LLD 0
Cs-137 0.020
< LLD
< LLD 0
Shoreline GS 8
Sediments K-40 0.10 10.80(6/6)
T-27B, Crane Creek S.P.
11.87 (2/2) 11.87 (2/2) 0 (pCi/g dry)
(8.06-12.82) 5.3 mi. WNW (10.61-13.13)
(10.61-13.13)
Mn-54 0.026
< LLD
< LLD 0
Co-58 0.028
< LLD
< LLD 0
Co-60 0.025
< LLD
< LLD 0
Cs-134 0.029
< LLD
< LLD 0
Cs-137 0.026
< LLD
< LLD 0
"GB = gross beta, GS = gamma scan.
bLLD
= nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
C Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).
Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..
e Non-routine results are those which exceed ten times the control station value.
173