ML031430504
| ML031430504 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/30/2003 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| -nr | |
| Download: ML031430504 (94) | |
Text
Radioactive Effluent Release Report
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2002 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 inert.
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Davis-Besse Nuclear Power Station 2002 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 intemal 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 that contain radioactivity. For example, the Waste Gas Decay Tanks 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 alarns 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 2002 Annual Radiological Environnental 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 that record the meteorological data.- Coupled with the effluent release data, the'meteorological data are used to calculate the dose to the public.
Beyond the plant, devices' maintained in conjunction with the Radiological Environmental Monitoring Program continuously 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 extemal and internal exposure pathways considered are shown in Figure 29. The release of radioactive gaseous effluents involves pathways such as extemal wh'ole 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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Davis-Besse Nuclear Power Station 2002 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 2002 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, 2002 through December 31, 2002.
- 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:
- 1.00E-02 mrem, whole body
- 2.17E-01 mrem, gastro-intestinalAower large intestine Gaseous Effluents:
Noble Gas:
- 9.04E-06 mrad, whole body
- 5.70E-04 mrem, whole body
- 5.70E-04 mrem, lung 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 2002 Annual Radiological Environmental 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 mrem TEDE per year. (Note: the total dose due to these releases is also limited to 50 mrem 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:
o 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 OCFR50, Appendix I, Sec. IIB. 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 IOCFR50, 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 IOCFR50, Appendix I, Sec 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:
o 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 2002 Annual 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.OE-04 uCi/ml is applied.
This EC is based on the Xe-135 DAC of E-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 2002 Annual Radiological Environmental Operating Report Batch Releases Liquid from 1/1/02 through 12/31/02
- 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 1/1/02 through 12/31/02
- 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:
48 104.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 300 minutes 58 minutes 124.8 minutes 7
67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> 1440 minutes 33 minutes 802 minutes Abnormal Releases Total 2002 activity due to Abnormal Releases 0.0 E+00 Ci Total 2002 Dose due to Abnormal Releases is 0.00E+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, 2002 through December 31, 2002.
I I
PERCENT OF I SPECIFICATION I ANNUAL DOSE I LIMIT UME T Report Period: January 1, 2002-Dece ber 31, 2002 (gaseous)
I Noble gases (gamma) 9.04E-06 mrad 10 mrad 9.04E-05 I Noble gases (beta) 5.99E-05 mrad 20 mrad 3.OOE-04 I 1-13 1, tritium and particulates 5.70E-04 mrem 15 mrem 3.80E-03 Report Period: January 1, 2002 - Dece ber 31, 2002 (liquid)
I Total body 1.00E-02 mrem 3 mrem I 6.67E-01
_- Organ _t2.17E-01 mrem I10 mrem I 2.17E+00 89
Davis-Besse Nuclear Power Station 2002 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 10CFR50: 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:
- 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 /> (1 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.
90
Davis-Besse Nuclear Power Station 2002 Annual 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 was one alteration to the OCDM, Revision 16.0. There were no changes to the Process Control Program (PCP) during this reporting period.
Borated Water Storage Tank Radionuclide Concentrations During the Reporting Period of 2002, the BWST tank concentration did not exceed the ODCM Section 2.2.4 sum of the limiting fraction of nuclides. This is a unitless number between 0 and 1, and the BWST did not exceed the limit of 1.
91
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents - Sum tion of All Releases Type Unit 1st Qtr 2002 Fisslon and Activation Gases Total Release Average Release Rate for Period Percent of ODCM Limits lodines Total lodines (1-131)
Average Release Rate for Period Percent of ODCM Limits 2nd Qtr 3rd Qtr 4th Qtr 2002-2002 2002 Ci 1.74E+02 0.OOE+00 6.20E-02 0.00E+00 pCilsec 2.21 E+01 0.OOE+00 7.86E-03 0.OOE+00 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Ci 2.54E-03 1.30E-05 O.OOE+00 O.OOE+00
.CI/sec 3.22E-04 1.66E-06 O.OOE+00 0.00E+00 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination Particulates Particulates with half-lives greater than 8 days Average Release Rate for Period Percent of ODCM Limits ci 6.31 E-03 0.OOE+00 0.OOE+00 0.OOE+00
-CVsec I
8.OOE-04 0.OOE+00 O.OOE+00 0.OOE+00 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpolnt Determination Gross Aloha Activitv ci
-O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Tritium Total Release Average Release Rate for Period Percent of ODCM Limits Ci 1.59E+01 2.66E+01 1.49E+01 1.18E+01 CI/Vsec 2.02E+00 3.39E+00 1.85E+00 1.39E+00 See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Setpoint Determination 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+01 2.5E+01
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases Batch Modea Unit Fission Gases 1st Qtr 2002 2nd Qtr 3rd Qtr 2002 2002 4th Qtr 2002 ci LLDb LLD LLD LLD LLD LLD LLD LLD Total for Period:
N/A LLDb LLD LLD LLD LLD LLD LLD LLD N/A LLDb LLD LLD LLD LLD LLD LLD LLD N/A UInb LLD LLD LLD LLD Ln LID LLD N/A Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Total for Period:
Particulates and Tritium H-3 Sr-89 Sr-90 Cs-134 Cs-137 Ba-140 Co-58 Total for Period:
6.15E-03 LLD 93 Nuclide Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 lodines I-131 1-132 1-133 1-135 N/A ci N/A N/A N/A 6.15E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LW LLD LLD LLD LLD LLD LLD LLD LLD
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 18 (Continued)
Gaseous Effluents - Ground Level Releases Continuous Modec Nuclide Unit Fission Gases 1st Qtr 2002 2nd Qtr 2002 3rd Qtr 2002 ci Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Total for Period:
Iodines 11Db LLD LLD LLD LLD LLD LLD LLD N/A LLD LLD LLD LLD LLD LLD LLD N/A LWb LLD LLD LLD LLD LLD LLD LLD N/A ci 1-131 1-133 I-135 Total for Period:
Particulates and Tritium H-3 Sr-89 Sr-90 Cs-134 Cs-137 Ba-140 Total for Period:
8.46E-03 N/A 94 4th Qtr 2002 LLD LLD LLD LLD LLD LID LLD LLD N/A LLD LLD LLD LLD LLD N/A N/A LLD LLD LLD N/A ci LWD LLD LWD N/A 8.46E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LD LLD LLD LLD LLD LLD LD LLD LLD LLD LLD LLD N/A N/A
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 18 (Continued)
Gaseous Effluents - Ground Level Releases Continuous and Batch Mode Ar-4:
Kr-85:
Kr-85m:
Kr-87:
Kr-88:
Xe-131m:
Xe-133:
Xe-133m:
Xe-135:
Xe-135m:
Xe-138:
1-131:
I-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
<6.2E-06
<2.OE-08
<3.4E-08
<4.OE-08
<9.OE-08
<4.6E-08
<1.6E-07
<1.9E-08
<4.OE-07
<2.5E-07
<I.OE-07
<2.1E-08
<2.lE-08
<2.OE-08
<4.OE-08
<3.OE-08
<2.OE-08
<4.OE-08
<2.0E-07
<2.1E-08
<3.OE-08
<3.OE-08
<1.2E-07
<7.OE-08
<3.OE-08
<5.OE-08
<6.OE-09 I.Ci/ml jiCi/mi j.tCi/nml JlCi/nil pACi/mi pci/mi pci/mi 11Ci/mi A+/-Ci/mI P'Ci/mi pLCi/mi 11Ci/ml j.Ci/mi ILCi/mi pCi/mi pLCi/mi pLCi/mt pLCi/mi pLCi/mi pCi/mi i.Ci/ml IpCi/mi pCi/mI pCi/mi pLCi/mi pCi/mi pCi/mi piCi/mi 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 2002 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Unit 2002 2002 2002 2002 Fission Gases Ci LLD Ci 8.71E+00 Ci LLD Ci LLD Ci LLD Ci 4.80E+01 Ci 4.47E-01 Ci 4.03E-01 Ci LLD Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LD Ci 9.18E-01 LLD LLD 6.20E-02 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 5.84E+01 N/A Total for Period:
I-131 I-132 1-133 I-135 Ci LLD Ci LLD Ci LLD Ci LLD LLD LLD LLD LLD 6.20E-02 N/A LLD LLD LLD LLD LLD LLD LLD LLD Total for Period:
Ci 5.07E-01 N/A 2.15E-04 N/A
- Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Sta-tion Vent) 96 Nuclide Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Xe-131m Ci N/A N/A N/A N/A
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 19 (Continued)
Gaseous Effluents - Mixed Mode Releases Continuous Mode Nuclide Fission Gases Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Unit Ci Ci Ci ci ci ci Ci Ci Ci Ci 1st Qtr 2002 LLD LLD LLD LLD LLD 1.09E+02 LLD 7A2E+00 LLD LLD 2nd Qtr 2002 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3rd Qtr 2002 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Total for PeriGd:
1.16E+02 N/A lodines 1-131 1-133 1-135 1-132 Ci ci Ci Ci 2.54E-03 3.56E-04 LLD 7.94E-04 1.30E-05 LLD LLD LLD Total for Period:
3.69E-03 1.30E-05 N/A Particulates and Tritium H-3 Sr-89b,c Sr_9Ob.c Cs-134 Cs-137 Ba-140 Co-58 La-140 Co-60 Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.54E+01 LLD LLD LLD LLD LLD LLD LLD LLD Total for Period:
1.54E+01 2.66E+01 1.46E+01 1.18E+01 97 4th Qtr 2002 LLD LLD LLD LLD LWi LLD LLD LLD LLD LLD N/A N/A LLD LLD LLD LLD LLD LLD LLD LLD N/A 2.66E+01 LLD LLD LLD LLD LLD LLD LLD LLD 1.46E+01 LLD LLD LLD LLD LLD LLD LLD LLD 1.18E+O1 LLD LLD LLD LLD LLD LLD LLD LLD
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 19 (Continued)
Gaseous Effluents - Mixed Mode Releases Continuous Mode'
<2.9E-08
<3.3E-06
<1.3E-08
<6.OE-08
<6.OE-08
<4.4E-07
<7.2E-08
<I.lE-08
<5.9E-06
<2.0E-05
<3.9E-10
<2.6E-14
<3.OE-14
<3.OE-14
<2.5E-14
<1.OE-13
<1.8E-14
<1.6E-14
<1.3E-14
<1.2E-13
<1.2E-14
<4.OE-14
<1.OE-14
<9.3E-16
<3.1E-16 Batch Mode' j.Cilml jiCi/mi p.Ciiml liCi/mi jiCi/mi tLiCiml piCim1 ptCiIml 11Cirni IlCi/ml pCi/mi jiCi/mi l.CiIml jiiml j.Ci/ml
.LCiImi
.tCi/rnl tCiIml jtiIml
.tCiIml I.Ci/ml Pci/mi JACi/ml Kr-87 Kr-88 Xe-135 Xe-135m Xe-138 Ar-41 Kr-85 Xe-133 Xe-133m
<4.5E-06
<6.6E-06
<1.4E-05
<2.1E-06
<2.8E-05
<1.8E-06
<1.2E-06
<2.4E-06
<I.OE-05 j.Ci/ml p.CiIml
.lCi/ml 3.Ci/ml AiCi/ml jAci/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 composite sample for continuous mode.
c Analysis not required for batch release.
98 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133m Xe-135 Xe-135m Xe-138 I-135' Mn-54' Fe-59c Co-58c Co-60c Zn-65c Mo-99' Cs-134' Cs-137' Ce-141' Ce-144' Ba-140' La-140' Sr-89bc Sr-9Obc
Davis-Besse Nuclear Power Station 2002 Annual Radiological Envirornmental Operating Report Table 20 Liquid Effluents - Summation of All Releases Type FLssion and Activation Products Total Release (without Tritium, Gases, Alpha)
Average Diluted Concentration During Period' Percent of ODCM Limits Percent of 10CFR20 Limit Tritium Total Release Average Diluted Concentration During Period' Percent of IOCFR20 Limit Dissolved and Entrained Gases Total Release Average Diluted Concentration During Period' Percent of IOCFR20 Limit Gross Alpha Total Release Volume of Waste Released (prior to dilution)
Batch Continuous Volume of Dilution Water Batch Continuous Total Volume of Water Released Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2002 2002 2002 2002
% Error Ci 1.66E-01 6.31E-03 4.74E-02 3.63E-03 2.0E+01 iCUml 1.68E-08 9.302-10 5.992-09 6.17E-10 See Supplement information in ODCM Release Limits Sec-tion 1.28E-01 7.43E-03 4.73E-02 8.092-03 Ci 3.06E+02 5.85E+01 3.33E+00 1.61E+01 liCi/ml 3.09E-05 8.61E-06 4.20E-07 2.74E-06 3.09E+00 8.61E-01 4.20E-02 2.74E-01 Ci 3.20E+00 7.28E-03 0.00E+00 5.87E-04 CiCVml 3.23E-07 1.072-09 0.00E+00 9.99E-I I 1.62E-01 5.36E-04 0.OOE+00 5.00E-05 Ci 0.002+00 0.002+00 5.042-04 2.1 E-04 liter 1.03E+06 3.46E+05 2.31E+05 2.47E+05 liter 5.59E+07 1.28E+08 1.43E+08 5.35E+07 liter liter liter 3.15E+08 8.92E+07 1.15E+08 6.81E+07 9.47E+09 6.45E+09 7.52E+09 5.70E+09 9.85E+09 6.66E+09 7.772+09 5.82E+09 2.0E+01 2.0E+01 2.0E+01 2.02+01 2.02+01 2.0E+01 2.0E+01
' 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
Davis-Besse Nuclear Power Station 2002 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. I Sr-90a I Fe-55 Cr-51 I-131 I-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 ICi 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 1st Qtr 2002 1.13E-01 7.18E-03 1.11E-02 6.64E-04 1.97E-04 3.84E-04 LLD LD 8.30E-03 7.26E-03 8.24E-04 LLD 9.07E-06 LLD 8.27E-05 LID 1.26E-04 1.67E-03 2.36E-04 LLD 3.60E-04 7.75E-03 3.73E-03 LLD 3.82E-04 LLD 7.56E-04 LLD 2.53E-05 3.48E-04 LLD 3.88E-04 LLD 9.59E-04 LLD LLD 2 nd Qtr 2002 4.95E-03 1.91E-04 2.36E-04 1.26E-04 3.86E-05 9.65E-05 LLD LLD 5.29E-04 LID LLD LLD LLD LLD LLD LID LLD 3.53E-05 LLD LD 2.1 IE-05 6.54E-05 2.65E-05 LLD LD LID LLD LLD 7.73E-06 LLD LLD LLD LD LLD)
LID LLD 3rd Qtr 2002 3.06E-02 4.22E-03 1.59E-03 6.45E-03 7.92E-06 1.20E-04 LLD LLD 2.88E-03 LD LD LLD LLD LD LLD 4.63E-06 LLD 8.9 1E-05 4.3 1 E-05 LLD 2.1 IE-04 4.74E-04 2.82E-04 LLD LLD)
LLD 3.94E-04 LI-D LD 2.06E-5 LLD LD LD LD LLD LLD 4th Qtr 2002 9.21E-04 2.80E-04 9.25E-04 1.1 lE-04 8.82E-06 1.56E-04 LLD LLD 1.21E-03 LID LID 2.OOE-05 LLD LLD LLD LLD LD LLD LID 1.57E-05 LI-D LD LLD)
LD LILD LD LD LD LD LLD LLD LLD LLD LID LID Total for Period:
ci 1.66E-01 6.31E-03 4.74E-02 3.63E-03 100
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclides Released Batch Releases Nuclide Tritium Dissolved and Entrained Gases Kr-85m Kr-85 Xe-131m Xe-133 Xe-135 Xe-133m I -135 Total for Period:
Unit ci ci ci Ci ci ci ci ci Ci 1st Qtr 2002 2nd Qtr 2002 3rd Qtr 2002 4th Qtr 2002 3.06E+02 5.85E+01 3.33E+00 1.61E+01 T T _a 2.55E-02 4.59E-02 3.1 OE+00 1.64E-03 2.42E-02 LLD Iuna 6.99E-03 2.18E-04 7.23E-05 LLD LLD LLD TT Da LLD
.LD LLD LLD UTD LLD 3.09E+02 5.85E+01 3.33E+00 1T;Da 5.87E-04 LLD LID LLD LTTD LLD 1.61E+01 101
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 21 (continued)
Liquid Effluents - Nuclides Released Continuous Releases Nuclide Unit 1st Qtr 2002
.. 2nd Qtr 2002 3rd Qtr 2002 4th Qtr 2002 Fission and Activation Products Cr-51 Fe-59 Co-58 Co-60 Zn-65 Sr_89ab Sr_90a,b Nb-95 Zr-95 Mo-99 Tc-99m I-131 Cs-134 Cs-137 Ba-140ALa-140 Ce-141 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci ci
,.,_Da LLD LLD LD ILD LLD LLD LL-D LLD LID LD
.LD
.LD IID L:ID N/A_
2.24E-01 T 1.Da T a 1LD LID LID LID ULD LID UID TL.I.
LID N/A LD LID LD LD LLD LD LD
-LD LID LD LID LLD
.LD N/A LD IDa LD LD LID LLD LID LID LID LLD LD LD ILD LID N/A LLD Dissolved and Entrained Gases Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 Total for Period:
Total for Period:
Tritium Ci Ci Ci Ci Ci LLD LID LD LLD LD N/A LTD LD LID LD LD N/A ci LD LD LD LID LD N/A LD LD LD LD LD N/A 102
Davis-Besse Nuclear Power Station 2002 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-113
<2.OE-08
<1.7E-07
<2. lE-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
<2.5E-08
<2. E-08
<1.6E-07
<1.8E-08
<2.2E-08
<2.5E-08
<2.8E-08 pci/mi jtCi/ml pLCi/mi pci/mi pciIml pci/mi jii pci/mi JtCi/mi j.Ci/ml pci/mi AiCi/ml pci/mi jRCi/ml pciIml pci/mi pCi/mi PLCi/mi pi/imi 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 I-135 Kr-85 Xe-131 Xe-133 Xe-133m Xe-135
<1.OE-08
<1.7E-08
<1.8E-08
<3.OE-08
<1.7E-07
<2.lE-08
<2.8E-08
<2.7E-08
<7.OE-08
<3.OE-08
<1.2E-07
<2.5E-08
<1.OE-08
<2.lE-08
<1.7E-07
<6.2E-06
<7.7E-07
<4.6E-08
<1.6E-07
<1.9E-08 pcifml j.CiIml pci/mi j+/-CiImi pLci/mi pci/mi pci/mi jiCi/mi pici/ml jiCi/mi pci/mi pci/mi jtCiIml jiCi/mi jiCi/mI j+/-CiImi jiCi/mi liCi/mi pci/mi pci/mi a 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 2002 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) 12-month Est. Total
- 1. Tpe of Waste Unit Period Error, %
- a. Spent resins, filter sludges, M3 3.41E+01 2.5E+01 evaporator bottoms, etc.
Ci 2.4E+02 2.5E+01
- b. Dry compressible waste, M3 1.6E+03 2.5E+01 contaminated equip., etc.
Ci 4.5E+00 2.5E+01
- c. Irradiated components, mi3 control rods, etc.
Ci N/A N/A
- d. Others: dewatered primary Ml 4.4E+00 2.5E+01 system cartridge filters Ci 1.3E+01 2.5E+01
- 2. Estimate of major nuclide composition (by type of waste)
- a. Spent Resins
- b. Dry compressible waste, contaminated equipment, etc.
- c.
None
- d. Cartridge filters Cs'3 7 Ni 6 3 Co6 0
.CS134 Fe 55 co5 8 c14 Sr90 IH3.
H Fe55 Co6 0 Cs,3 7 C14 Ni6 3 Co5 8 H3 Cs'34 Fe55 C60 Co~
Ni6 3 c14 HI Cs'37 Percent (%)
4.94E+0 1 3.60E+0 1 5.69E+00 3.1 5E+0 1 2.33E+00 1.54E+00 1.25E+00 1.30E-01 1.30E-01 4.94E+01 1.56E+01 7.35E+00 6.58E+00 5.83E+00 5.27E+00 3.40E+00 2.02E+00 5.20E+01 1.91E+01 1.1 8E+0 1 3.26E+00 2.06E+00 1.37E+00 1.35E+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+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+01 104
Davis-Besse Nuclear Power Station 2002 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 3
Truck Bamwell, SC 3 resin/filter media HIC 44 m 3 44 m3 7
Truck GTS Duratek, Oak Ridge, TN for processing then disposal at Envirocare of Utah or Barnwell S.C.
Metal boxes (36.3 m3 )
326.25m3 54.4 m3 4
Truck Alaron, Wampum, PA for processing then disposal at Envirocare of Utah Oversize boxes on lowboy trailers (73.405 m3) 293.62m3 69.09 m3 1
Truck AERC, Oak Ridge Tenn. for processing then disposal at Envirocare of Utah Metal liners (4.82m3) 19.28m3 16.85 m3 22 Truck AERC, Oak Ridge Tenn. for processing then disposal at Envirocare of Utah Metal boxes (36.3 m3, 2.72 m3, or 3.12 m3 )
1160 m3 193.33 m3 105
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 22 (continued)
Solid Waste and Irradiated Fuel Shipments Number of Shipments:
Mode of Transportation:
Destination:
Type of Container (Container Volume):
Volume shipped for processing Volume disposed 4
Truck Studsvick Erwin, TN. for processing then disposal at Envirocare of Utah Metal liners (5.72m3 or 3.75m3) 18.94m3 2.2m3 B. IRRADIATED FUEL SHIPMENTS There were no shipments of irradiated fuel.
106
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 23 Doses Due to Gaseous Releases for January through December 2002 Maximum Individual Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.
Whole Body Dose 5.70E-04 mrem Significant Organ Dose 5.70E-04 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 9.04E-06 mrad Skin Dose 5.99E-05 mrad Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.
Total Integrated Population Dose 1.58E-02 person-rem Average Dose to Individual in Population 7.25E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 4.83E-03 person-rem Average Dose to Individual in Population 2.21E-06 mrem 107
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 2002 Maximum Individual Whole Body Dose Maximum Individual Significant Organ Dose Population Dose Total Integrated Population Dose Average Dose to Individual 1.00E-02 mrem 2.17E-01 mrem 8.78E-01 person-rem 4.02E-04 mrem 108
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 25 Annual Dose to The Most Exposed (from all pathways) Member of The Public 2002 ANNUAL DOSE 40CFR190 LIMIT PERCENT OF (mrem)
(mrem)
LIMIT Whole Body Dose*
Noble Gas 9.94E-06 Iodine, Tritium, Particulates 5.70E-04 Liquid 1.OOE-02 Total Whole Body Dose 1.06E-02 25 4.24E-02 Thyroid Dose Iodine, Tritium, Particulates 3.21E-03 75 4.28E-03 Skin Dose Noble Gas 7.58E-05 25 2.40E-04 Significant Organ Dose (Gastro-2.17E-01 25 8.68E-01 intestinaVlower large intestines)
Meteorological Data Meteorological data on 31/2 inch microdisk for January through December 31, 2002, 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.
109
Davis-Besse Nuclear Power Station 2002 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, 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 - Intemal exposure as a result of breathing radionuclides car-ried in the air.
Ground Exposure Pathway - Extemal exposure from radionuclides deposited on the ground Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.
Vegetation Pathway - Intemal exposure as a result of eating vegetables, fruit, 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 surveillance portion of the 2002 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.
110
Davis-Besse Nuclear Power Station 2002 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 Sta-tion Vent at Davis-Besse.
Results The following changes in the pathways were recorded in the 2002 census:
S Sector - A garden at 4960 meters replaced a garden at 4230 meters SW Sector - No gardens were reported in this sector in 2002 WSW Sector - The garden at 7430 meters was replaced with a garden at 7770 meters.
- NW Sector - No gardens were reported in this sector in 2002.
The critical receptor identified by the 2002 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.
111
DAVIS-BESSE NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PRIMARY PATHWAYS WITHIN A 5 MILE RADIUS WNW W
J1 WSW To Dvis-Besse Within Sector a
RESIDENCE l
49 VEGETABLE GARDEN T
SSW I
CAMP PE~RYV x 0 I) bI II ~
-Il
-0
( D N) r-D c
()
0fD 0
D F-0 Is SE
-i-.
II---
IIj II~~
WESER R
.2O_.
wr i
coi
° 0,,
0 vt 7tf cr ws
!!1 cr 2:
f fffffffff J
fSS
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2002 Distance from Station (meters)
C 880 In G
Pi 880 900 losest Pathways nhalation round Exposure
'ume Exposure Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure ENE, E, ESE SE N/A 8000 SSE SSE 2860 1970 4230 S
SSW 1030 2350 SSW 980 SW 1070 Located over Lake Erie Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure
- changed since 2001 113 Sector N
NNE NE
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2002 Distance from Station (meters)
Closest Pathways Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Vegetation Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure Inhalation Ground Exposure Plume Exposure
- Changed since 2001 114 Sector WSW WSW**
1540 7770 w
980 W
1610 WNW 1750 NW 1490 NNW 1270
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)
Parameters SECTOR METERS CRITICAL AGE X/Q D/Q PATHWAY GROUP (SEC/M3)
(M2)
N 880 Inhalation Child 9.15E-07 8.40E-09 NNE 880 Inhalation Child 1.24E-06 1.44E-08 NE 900 Inhalation Child 1.26E-06 1.58E-08 ENE*
E*
ESE*
SE 8000 Inhalation Child 3.43E-08 1.45E-10 SSE 2860 Vegetation Child 6.91E-08 8.13E-10 S**
4230 Vegetation Child 3.71E-08 3.09E-10 SSW 2350 Vegetation Child 5.90E-08 1.03E-09 SW 1070 Inhalation Child 2.86E-07 5.23E-09 WSW**
7770 Vegetation Child 3.25E-08 1.64E-10 W
1610 Vegetation Child 2.77E-07 4.37E-09 WNW 1750 Inhalation Child 1.46E-07 1.72E-09 NW 1490 Inhalation Child 1.43E-07 1.35E-09 NNW 1270 Inhalation Child 2.41E-07 1.73E-09
- Since these sectors are located over marsh areas and Lake Erie, no ingestion pathways are present.
- Changed since 2001 115
Non-Radiological Environmental Programs
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental 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, Industial 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.
116
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental 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 100m free-standing tower located about 3,000 feet SSW of the cooling tower, and an auxiliary lOm foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The lOOm tower has primary and backup instruments for wind speed and wind direction at lOOm and 75m. The lOOm tower also measures differential temperature (delta Ts): 100-lOm and 75-lOm. The lOm tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the lOm 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 lOm) to measure temperature, wind speed, and wind direction. During 2002, annual data recoveries for all required instruments were 98.9 percent. Minor losses of data occurred during routine instru-ment 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 117
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating 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 2002.
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 pattems as they relate to defined past climatological wind pattems reported in Davis-Besse's Updated Safety Analysis Report. The maximum measured sustained wind speeds for 2002 occurred on March 9, when they were measured at 55.98 mph at the 100m level, 52.27 mph at the 75m level, and 39.02mph at the lOm level.
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.
118
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2002 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 was 51.29°F.
The maximum temperature was 92.67°F on July 2 with a minimum temperature of 6.74°F on March 4. Yearly average differential temperatures were -0.21°F (lOOm), and 0.08°F (75m). Maximum differen-tial temperatures for 100m and 75m levels were 7.99°F on Octoberber 10, (lOOm), and 7.99°F on October 10, (75m). Minimum differential temperatures for 100m and 75m levels were -3.31°F on October 19, (lOOm) and -2.47°F on April 26, (75m). Differential temperatures are a meas-urement of atmospheric stability and used to calculate radioactive plume dispersions 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 2002 are provided in Table 29. These data are measured at the 10 meter level. The average dew point temperature was 42.08°F with a maximum dew point temperature of 75.20TF on July 28. Please note that dew point temperatures above 75°F 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 32°F is frost point) temperature was 3.40°F on March 4. Average relative humidity is 73.52 percent for the year. The maximum relative humidity was 100.00 percent on August 23. The minimum relative humidity was 14.52 on April 16. It is possible to have rela-tive humidity above 100 percent, which is known as supersaturation. Conditions for supersatu-ration have been met a few times at Davis-Besse due to its close proximity to Lake Erie, and the evaporative pool of moisture available from such a large body of water.
Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 2002 are given in Table 29. To-tal precipitation for the year was 29.26 inches. The maximum daily precipitation total was 1.61 inches in January. The minimum was 0.36 inches recorded in December. 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.
119
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report 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 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.
120
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2002 z
IOOm Wind Speed 94.35 98.66 93.68 99.72 100 100 100 77.69 100 100 100 100 96.96 lOOM Wind Direction 100 100 100 91.25 100 100 100 98.79 100 100 100 100 99.18 O
75M Wind speed 94.49 95.83 79.44 99.72 100 100 100 98.79 100 100 100 100 97.34 0
75M Wind Direction 100 100 100 99.72 100 100 100 98.79 100 100 100 100 99.87 IOM Wind Speed 97.72 97.62 96.10 99.72 100 100 100 98.79 100 100 100 100 99.17 CD v
lOM Wind Direction 100 100 100 99.72 100 100 100 98.79 100 100 100 100 99.87 CD P.
0 lOM Ambient Air Temp 100 100 100 99.72 100 100 100 77.15 100 100 100 100 98.04 0
IOM Dew Point Temp 100 100 100 99.72 100 100 100 98.79 100 100 100 100 99.87 O
DeltaT(IOOM-1OM) 100 100 100 99.72 100 100 100 77.15 100 100 100 100 98.04 Delta T (75M-IOM) 100 100 100 99.72 100 100 100 77.15 100 100 100 100 98.04 f
pz Joint IOOM Winds and DeltaT(IOOM-IOM) 94.35 98.66 93.68 91.25 100 100 100 77.15 100 100 100 100 96.22 x
CD Joint 75M Winds and tO)
DeltaT(IOOM-IOM) 94.49 95.83 79.44 99.72 100 100 100 77.15 100 100 100 100 95.50 00 o
Joint lOM Winds and 0
Delta T(75M-IOM) 97.72 97.62 96.10 99.72 100 100 100 77.15 100 100 100 100 97.33 to CD r
- all data for individual months expressed as percent of time instrument was operable during the month, divided by the maximum number of hours in O
0 that month that the instrument could be operable. Values for annual data recoveries equals the percent of time instrument was operable during the C l year. divided by the number of hours in the year that the instrument was operable.
0
=-
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV 100M WIND Max Speed (mph) 37.23 42.97 55.48 46.81 34.62 36.04 26.61 32.25 31.28 35.75 38.58 Date of Max Speed 01/09 02/01 03/09 04/28 05/09 06/05 07/10 08/02 09/10 10/18 11/29 Min Speed (mph) 2.31 0.05 1.37 1.73 3.67 2.46 2.43 2.41 1.05 0.71 3.34 Date of Min Speed 01/19 02/26 03/20 04/04 05/26 06/08 07/07 08/02 09/09 10/10 11/21 Ave Wind Speed 19.63 20.65 19.70 17.35 17.00 13.43 12.91 13.57 13.21 14.98 19.26 75M WIND Max Speed (mph) 34.14 40.70 52.27 44.67 33.13 33.49 24.86 28.56 30.05 33.10 37.21 Date of Max Speed 01/09 02101 03/09 04/28 05/09 06/05 07/11 08/02 09/11 10/04 11/22 Min Speed (mph) 1.51 2.12 2.06 1.42 3.61 2.44 1.84 1.40 0.72 0.75 3.31 Dateof Min Speed 01/19 02/22 03/29 04/04 05/26 06/29 07/14 08/26 09/25 10/10 11/21 Ave Wind Speed 17.76 19.14 18.58 15.96 15.65 12.39 11.80 12.23 12.13 13.94 17.83 IOM WIND Max Speed (mph) 26.37 31.72 41.22 33.66 24.79 23.51 21.22 20.59 20.42 26.66 28.53 Date of Max Speed 01/04 02/01 03/09 04/28 05/09 06/05 07/05 08/06 09/10 10/30 11/22 Min Speed (mph) 0.88 2.00 1.49 1.35 1.71 1.55 1.44 0.45 1.36 0.86 1.80 Date of Min Speed 01/19 02/23 03/12 04/04 05/11 06/08 07/19 08/26 09/25 10/12 11/05 Ave Wind Speed 11.00 12.49 12.43 10.94 9.82 7.75 7.75 7.78 6.63 8.83 11.71 DEC 2002 33.94 55.48 12/19 03/09 1.75 0.05 12/04 02/26 18.75 16.07 31.06 52.27 12/19 03/09 1.72 0.72 12/04 09/25 17.22 15.29 24.48 41.22 12/02 03/09 0.80 0.45 12/10 08/26 11.09 9.79 I
0 C/D 1
0 CD CD" 0
8
-t 0
A fq x
0 a
t'Q p
CD p
cn Q,
81 t-C)
C) t-l Sc.
to0(b zc0 0
C 0
ItJ 0
m 3
1 -
8 r
to
It z
ct JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2002 10M AMBIENT TEMP 0
Max (F) 59.03 58.44 68.51 84.50 84.03 88.08 92.67 90.85 89.23 82.85 66.22 53.43 92.67 Date of Max 01/28 02/25 03/08 04/18 05/31 06/30 07/02 08/01 09/10 10/01 11/10 12/31 07/02 (D
_3 Min (F) 15.78 16.14 6.74 30.85 36.23 54.39 63.82 60.35 46.51 32.79 22.67 8.09 6.74 C
Date of Min 01/03 02/28 03/04 04/07 05/19 06/03 07/13 08/09 09/23 10/31 11/28 12.04 03/04
-A t
Ave Temp 33.25 33.60 35.37 50.35 55.22 70.70 76.27 74.60 68.51 52.19 40.00 29.93 51.29
° D
IOM DEW POINT UQ.
TEMP Mean (F) 26.74 25.47 28.29 40.72 44.57 58.98 62.70 62.41 56.87 41.49 31.91 24.09 42.08 c
Max (F) 48.12 48.60 52.91 65.47 65.91 71.65 75.20 73.83 70.46 67.91 58.26 49.66 75.20
- 3 Date of Max 01/29 02/20 03/09 04/15 05/09 06.22 07/28 08/04 09/20 10/04 11/10 12/31 07/28 o
Min (F) 11.78 3.51 3.40 19.94 25.35 43.35 46.13 48.92 39.72 24.99 13.10 5.34 3.40 Date of Min 01/01 02/04 03/04 04/06 05/03 06/02 07/11 08/06 09/24 10/14 11/27 12/04 03/04 CD PRECIPITATION I
Total (inches) 3.45 1.38 2.63 4.59 3.77 1.52 2.88 2.49 1.21 1.62 1.89 1.83 29.26 o
Max. in One Day 1.61 0.63 0.77 0.84 0.88 0.45 0.87 0.80 0.62 0.92 0.73 0.36 1.61 i-i Date 01/31 02/10 03/26 04/16 05/12 06/03 07/29 08/22 09/14 10/28 11/10 12/31 01/31 0
O x
O
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Figure 32 Wind Rose Annual Average lOOM WIND SPEED (MPH)
DIRECTION FREOUENCY (1 DAVIS-BESSE ANNUAL 2002 1OOM -LEVEL 124-E
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M N
WIND SPEED (MPH)
DIRECTION FREGUENCY X}
S DAVIS-BESSE ANNUAL 2002 75M LEVEL 125 w
E
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Figure 34 Wind Rose Annual Average lOM N
Q2222929SW: WINO SPEED (MPH)
DIRECTION FREQUENCY X)
DAV IS-BESSE ANNUAL 2002 IOM LEVEL 126 w
E
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 30 Joint Frequency Distribution by Stability Class DAVIC 88 DVIO4WAL COPLIAIC UNIlT -
- *-*3-JAN-03 TIME Or DAY, 041.16 PAJI:
JD VEsION 77-1.0
.DAVIS-SSUZ 75-10 DS. NO ACKUP.
DATA PIIOD EIAMINSO 1/
1/
2 -
12/
1/
2 SITE IDITIFltE 2
AMAL STAIILlT ClJaS A
STASILIT BZED ll DLTA RT IN 2S0.0 AND 35.0 FEET WIND MASURZD AT 35.0 rUT MIND TUSuOw AT:
1.00 MU JOINwT RYzJI DI w1rIom or wIEW spEzD A DIECTIrN IN mos AT 35.00 E ET SPED IMPEl Cum 1.01-3.69 0
3.50- 7.49 3
7.50.12.49 2
12.50-18.49 0
18.50-24.49 0
- 24.49 0
N MME us on S
S St SE S
SSW gmN N
0 0
0 0
1 0
0 0
0 2 0 0
0 0
0 0
0 0
0 0
0 0
w MM w
OTAL 0
0 0
0 a
a 0
0 0
1 1
0 0
0 0
1 0
a 0
0 2
0 a
0 0
1 0
1 0
0 a
0 0
0 0
0 SOTAL 6
2 1
1 1
1 0
0 0
0 0
1 2
3 1
0 19 ETAILITY CLASS 8
ETASILITE S D Cla TA T S3115 250.0 AD 35.0 FEs WIND MAID AT:
S.
VT XlD TImSSOL AT:
1.00 M
JOINT rSSWlCT DIBtI I
0F WIND SPEED AND DIRECTION I HOMS AT 315.00 FET oPSn N
WIE HE z
SEE SE SEE S
saw S"
WV N
MN W
MM TOTAL CMX 1.01-
.49 0
3.50- 7.49 4
7.50-12.49 9
12.50.18.49 1
16.50-4.49 0
a24.49 0
0 0
0 0
6 0
0 0
a 1
0 2
3 1
0 1
I 3
0 0
0 0
0 0
0 0
0 0
0 o
0 1
2 O
0 2
12 0
0 0
1 0
0 0
0 0
0 0
0 0
0 0
0 1
O S
2 1 4
2 0
0 11 51 3
0 2
0 1
1 21 0
1 1
0 2
0 0
0 0
0 0
TOTAL 16 7
1 11 S
I 0
0 3
1S 7
3 3
1 4
17 95 127 PACE 91 7
4 5
2 0
(MM')
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 30 (continued)
Joint Frequency Distribution by Stability Class ISSSSE ClVIROHTAL CIPLIANCE LWT -..
- *-11-JAN-03 TIME OF DAY, 0s,41.56 PROGRAM. JD
- VESION, 77-1.0 DAVIS-SSSS 75-10 DI. NO MACKUP DATA PERIOD XAmINEC:
if 1/
2 12/
31/
2 SITS IDNDITIrlER 2
aJAL STUILITY CLASS C
STABILITY ASED OM. DELTA T REIWEN 250.0 AND 35.0 rT MIND MEASURED AT.
35.0 FET MIND TIUSMOLD AT.
1.00 MPH JOiNt ruD=cT DJSSIIIUSJON OF IND PSD AND DIRECTION I NEURS AT 3S.00 rCT SPED IMPE)
So SW WSW u
VW uw UW TOTAL CALM 0
1.01.
.49 0
1 0
0 0
0 0
0 0
0 0
0 0
0 0
1 2
3.50. 7.49 12 11 I
0 0
0 1
0 6
5 4
5 1
0 7
5 So 7.50.12.49 10 6
7 12 a
1 0
1 a
12 23 11 2
1 17 IS 134 12.SO-IS.49 4
s S
9 2
0 0
0 0
7 16 iS S
S 10 5
92 13.50-24.49 0
0 a
0 a
0 0
0 1
a a
2 3
4 26
.24.49 0
0 0
0 0
0 0
0 0
2 0
0 0
5 TOsaL 26 24 16 21 10 1
1 1
14 24 44 45 1
3 37 30 320 STILITY CLA D
STAILITT DAD O.
DELTA T
%ETKZ3 250.0 AND 35.0 m
WIND MEASURED AT, 35.0 Es MIND TNSSWWLD AT, 1.00 MPH JOIWI IUSU%M= DISRIW SIV OF WIND SPEED AND VIR=IOI I" NOURS AT 35.00 PSET SUD Y
S ME gm 5
soW S
WW v
mw NM SW TOTAL 1.01. 3.49 0
2 3
1 1
I G
11 a
6 3
4 4
2 2
1 SY 3.50- 7.49 27 4S 55 39 as 50 31 32 41 72 as 51 41 39 29 24 794 7.50-12.49 45 112 207 A80 133 41 14 22 IS 144 ISs 341 303 fi 91 52 1593 12.50-19.49 27 94 130 75 4
3 2
2 4
82 224 213 99 71 a5 SI 1227 1I.50.24.49 12 37 52 23 a
0 0
0 3
6 95 140 26 16 1S 28 441
.24.49 4
4 2
0 0
0 0
0 0
0 14 32
- S 1
2 4
49 TOTAL 145 296 450 371 295 95 53 67 93 310 577 551 270 198 227 197 4203 128 PACE 92 IMP)
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 30 (continued)
Joint Frequency Distribution by Stability Class
.... DAVIS-8SS SNVIRONKO4V AL COMPLIANC 1313 o -JAN-03 TIME OF AXY 46.41,S6 POaAt: JD
- VZSIOM, 177
.0 DAVIS-BSESS 75-10 N
S P.-.-.
DATA PIOD EXAMINED, 1/
1/
2 12/
31/
2 A3NWAL...
STABILITY CLASS C
STABILITY AC8D ONH 02.TA T RUTEE 250.0 AND IS.0 EET MIND KWAZUUD AT, 3S.0 FrEs WIND TZSLD T
AT 1.00 M4PH
.o0w? rFREguD DSTatSloH or mIND SPEED AND DCCrioH IN NOURS AT 3s.oo rZ S, m CPN)
CAIM N
NM Ne NM F
aW N
Mm TOTAL 1.01-
.49 2
4 4
11 17 22 17 29 24 20 14 7
4 3
4 190 3.50- 7.49 14 7
16 71 110 90 94 62 122 255 124 45 44 23 13 19 1157 7.SO-12.49 14 11 14 22 53 3S 3
30 92 244 219 116 71 45 22 11 1009 12.50-l.49 1
it 4
2 4
1 0
2 1S S1 t29 62 13 4
1 2
324 13.50-24.49 I
1 4
1 3
0 0
0 2
0 26 1S 0
4 2
0 61
.24.49 0
2 0
0 0
0 0
0 0
0 2
5 0
0 1
0 10 SToAL 34 3
42 107 107 156 119 123 255 Sa0 si1 270 153 00 59 36 2762 STABILITY CLASS F
SrAalLI?T 3A2D Out DELTA T 3
M 250.0 AND 3S.0 FEEs WIND ASVE A?S 3S.0 FEM?
mND T1 LDZSND A?S 1.00 M JOtII PSgI Y DIMISWTIOH or WIND 3922D AND DsCTioN I1 IN IMS AT 35.00 n BPn=
3MPH)
CALM N
NM us D
1.01-3.49 4
3.50- 7.49 0
7.50-12.49 2
12.5010.49 0
10.50-24.40 0
.24.49 0
2 S
53W SW m W v
RU NW RU TOTAL 2
3 3
5 9
21 40 44 43 30 17 5
4 1
0 7
25 48 39 36 73 96 74 55 31 13 0
2 2
12 2
1 2
S 24 4
3 3
2 0
a 0
0 0
1 0
0 0
0 0
0 a
0O a
0 0
0 a
0 0
0 0
0 0
1 0
0 0
0 0
0 a
0 0
0 0
0 0
I 3
1 246 2
1 501 1
1 63 0
0 1
a 0
1 0
0 0
TOTAL 3
3 5
12 42 59 52 16 122 170 log 75 40 20 3
020 129 PAGE 3
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report
-Table 30 (continued)
Joint Frequency Distribution by Stability Class
.... DAVIS-SSSEC UIVIRNWAL COMPLIANC UIT
- PR3AN: JFD VESSION 771.0 DAVIS4ISS is-o10 VT. to sACKu DATA P9OD XAMIq3Ds A/
I/
2 -
12/
1f 2
AXOfiJAL sTABILITY CASS G
STABILITY ASED ON DLTAT S
- TKH 250.0 AO 5.0 FET MIND EASUED AT, 35.0 8 T YS3ND TLSND AT.
1.00 MPH
.0IW1T PUEfCT DISMI MIN OF WIND SPEED AND DICSIOM IN 3US AT 35.00 EST SPED IMPH)
N n
NE cIE 1
0 3.50- 7.49 0
0 7.50-12.4%
0 0
12.50-16.49 0
0 1.50.24.49 0
0
.24.49 0
0 15JAN-0 TIMS o DAY 06,43.56 PAGE 94 SIT! 10m4T191E1 2
mw W
1N TOTAL 2
a 0
3 4
9 12 31 37 27 13 0
2 6
12 3
9 20 42 41 a
0 0
4 4
0 1
1 0
1 0
0 0
0 0
0 0
0 0
0 1
0 0
0 a
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
6 2
0 1
144 6
0 0
0 149 0
0 0
0 11 0
0 0
0 1
0 0
0 0
0 0
0 a
0 0
TOMAL 0
0 0
2 11 20 11 22 52 79 99 22 12 2
0 1
307 STABILITY CLASS ALL STABILITY UD OK. DSLTA T SWZN1 250.0 AND 2S.0 FICT WIND ISASURZO AT.
S.0 PUT WIND TISNLD AT, 1.00 M JOIYS rEsauaT DIImIIoSI or JIN SPED AND DIaICToY IN 93uS AT 3s.0 0 EST SPD KPH)
N ml ME mm g SE 33
-SE 1
Isw SOW N
IN Mm TOTAL CALM 4
1.01-3.49 I
10 IS 2
37 52 100 107 111 14 41 24 12 8
8 642 3.50- 7.49 62 72 72 169 226 208 1g 19 263 472 32 194 143 77 S2 54 2689 7.50-12.49 103 130 230 219 213 94 23 56 143 439 407 273 179 11 134 120 2070 12.50-
.49 43 113 144 9
76 4
3 4
21 ISI 372 261 126 s0 117 66 1681 19.50.24.49 IS 31 56 24 11 0
0 0
S 6
122 16S 35 24 20 32 SS3
,24.49 4
4 3
0 0
0 0
0 0
0 16 43 7
1 3
4 17 TDTAL 233 369 515 525 554 23 246 299 SI2 1176 1319 967 S16 312 334 254 S26 130
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 30 (continued)
Joint Frequency Distribution by Stability Class
- --.... DAVIS-SESSS NVIRONMENTAL COMPLIANCE UNIT *-'
.18-JAM-03 TiS or DAY, 041.56 PROR AM JrD
- VUSI0W, 77-1.0 DAVR8.*SS 7-10 OT NO ACl.P.
DATA PIOD EXAMIND.
i/
1/
2 -
12/
31/
STABILITY R0SD ON, DELTA T WIND MEASURED ATs 35.0 FMT MIND THImSND AT.
1.00 MPH SITS IDIDlIIFKR 2
.-- ANUAL SEMEN 250.0 AND 3S.0 FT TOTAL NIMBE o OSSRVATIOWSs 8760 TOTAL mull or VALID OU;SZVATIONS:
8526 7DTAL. hU OF MI1SING OSVATIWSt 234 PRCW DATA REWVZT FM THIS PIO.
97.1 '
MUWI WIND 3P550 rOR THIS P5310 9.80 PH TOTAL l1n OF OBSnVATIOS WITH ACKP DATA, A.
0.22 PIRCSNTAOS OCCAURI OF STABILIYY CLASS3S a
C 0
3 F
a 1.11 3.75 49.30 32.40 9.62 3.60 N
NM mg DIS DISTiSSUTION OF WIND DIkECYS VS STASILITY ESE St ESE S
Sa SW uS" WN NM NMI Cum A
6 2
1 1
1 1
0 0
0 0
0 1
2 3
1 0
0 a
16 7
1 11 6
1 0
0 3
i5 7
3 3
1 4
17 0
c 26 24 1s 21 10 1
I 1
14 24 44 45 l
a 37 30 0
D 145 26 450 371 29S 9S 53 67 93 310 577 551 273 198 227 197 0
5 34 3
42 107 187 156 119 123 255 530 514 270 163 s0 59 36 1
r 6
3 5
12 42 59 62 86 122 170 108 75 40 20 6
3 1
a 0
0 0
2 13 20 11 22 52 79 9
22 12 2
0 1
2 TOTAL 233 36 515 525 554 333 246 299 539 1178 1319 967 1
312 334 284 4
131 PA5S 95
Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental 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 southwestem shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Station. The marsh is owned by FirstEnergy and jointly managed by the U.S. Fish and Wildlife Service and FirstEnergy. Navarre Marsh is divided into three pools. The pools are separated from Lake Erie and each other by a series of dikes and revetments. Davis-Besse is responsible 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 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 again in 2002, bringing the site total to nine since 1995.
Ohio has gone from a low of 4 nests in 1978 to a record of 79 nests in 2002.
Ohio's eighth Federal Junior Duck Stamp Art Contest was held at Davis-Besse. Young Ohio artists in grades K-12 submit entries in four age brackets. The contest is designed to teach con-servation through the arts and give students a chance to experience the beauty and diversity of wildlife. A total of 101 ribbons are awarded to young Ohio artists, with the state Best-of-Show 132
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report entry submitted to Washington, D.C. to compete in the national contest with other state Best-of-Show entries. The winner of this competition is 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, at age 21. 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 observed Ohio's expanding eagle population during 2002.
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, sodium aluminate and coagulant aid to pro-duce 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. Upflow clarifiers combine the conventional treatment steps of coagula-tion, flocculation, and sedimentation into a single unit. Coagulation is the process by which a chemical, 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 conglomerate particles to mass together further. Finally, during sedimentation, large conglomer-ate 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.
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Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental Operating Report RAW WATER WTAXrE STUC*TI.IR WATTET AEEDPOP AK LEt SYSTEM TO TOEWEZ WATER sysnEM T
Figure 35: At Davis-Besse, raw lake water is drawn into the water treatment plant and processed into 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 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.
Since December of 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 no longer apply.
Zebra Mussel Control Introduction The plant receives all of its water from an intake system from Lake Erie. Zebra mussels can se-134
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report 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 the Great Lakes in 1986 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders that rap-idly colonize an area by forming byssal threads that enable them to attach to solid surfaces and 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 mus-sels 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 (WWTP) Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen-erated by site personnel is treated in 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 2002 Wastewater Treatment Plant Operations All wastewater parameters were within specifications during the year 2002.
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Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report National Pollutant Discharge Elimination System (NPDES) Reporting The Ohio Environmental Protection Agency (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, suspended solids and pH are monitored under the NPDES permit. Davis-Besse 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 from Wastewater Treatment Plant Sources of Wastes: Wastewater Treatment Plant 136
Davis-Besse Nuclear Power Station 2002 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 2002 NPDES Summary During 2002, the NPDES permit was renewed by the Ohio EPA, and it will be effective for five years. A new sampling requirement with Outfall designation 004 was added to the permit, and will be used to monitor water drained from the Circulating Water System during outages. Three violations of the NPDES permit occurred during 2002. Two exceedances were measured at Out-fall 001. Total Residual Oxidant and Total Residual Chlorine were each detected above the per-mit limit once during the year. An instrument error resulted in a 9.1 pH being recorded at Outfall 002, exceeding the limit of 9.0 pH units. Corrective actions were taken to prevent reoccurrence of these exceedances.
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 137
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report (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).
In 2002, the Davis-Besse Nuclear Power Station qualified as a small quantity generator, generat-ing 2,100 pounds of hazardous waste. Davis-Besse personnel continuously strive to identify ways of reducing hazardous waste.
Non-hazardous waste disposed of in 2002 included 18,500 gallons of used oil, 800 gallons of oil filters and solid oily debris. Other non-hazardous regulated waste generated included 560 gallons of other chemicals such as microfilm process chemicals, polystyrene resins and sandblasting de-bris.
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 138
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report 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.
Annual SARA reports are submitted to local fire departments and state and local planning com-missions by March 1 for the preceding calendar year.
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-fill 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-139
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report cific regulations concerning handling, removal, environmental protection, and disposal. Also, the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concem 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.
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 bumed 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."
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Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report 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 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.
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Appendices
Davis-Besse Nuclear Power Station 2002 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, n-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, 2002 through December, 2002 142
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report APPENDIX A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly 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., mile 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.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of intemal laboratory testing is 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 NIST traceable sources. Data foar 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 Evaluation 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.
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Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report AeDendix A Interlaboratorv Comparison Proaram Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory, has participated In nterlaboratory comparison (crosscheck) programs since the formulation of its quality control program In December, 1971.
These programs are operated by agencies which supply environmental-type samples 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.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by the Environmental Resources Associates, serving as a replacement for studies studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via Intemational Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of intemal laboratory testing is 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 NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on In-house blank' samples for the past twelve months. Data for previous years available upon request. 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 Evaluation 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.
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Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report ACCEPTANCE CRITERIA FOR *SPIKED SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa Level 5 to 100 pCUliter or kg
> 100 pCiliter or kg 5 to 50 pCUliter or kg
> 50 pCiliter or kg 2 to 30 pCiliter or kg
> 30 pCUliter or kg
> 0.1 gliter or kg 20 pCitliter
> 20 pCVliter 100 pCUliter
> 100 pCUliter 4,000 pCiliter
> 4,000 pCUliter 0.1 pCUliter 0.1 pCUliter, gram, or sample 55 pCi/liter
> 55 pCUliter Gross beta Tritium Radium-226.-228 Plutonium Iodine-131, Iodine-129b Uranium-238, Nirkel63b Technetium_99b 35 pCIUter
> 35 pC i/liter 50 to 100 pCiliter
> 100 pCIliter One standard deviation for single determination 5.0 pCUliter 5% of known value 5.0 pCIliter 10% of known value 5.0 pCVliter 10% of known value 5% of known value 5.0 pCUliter 25% of known value 5.0 pCIliter 5% of known value Is = (pCiliter) =
169.85 x (known) 0 10% of known value 15% of known value 10% of known value 6.0 pCi/liter 10% of known value 6.0 pCiliter 15% of known value 10 pCUliter 10% of known value a From EPA publiation, Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
145 Analysis Gamma Emitters Strontium_89b Strontium-90b Potassium-40 Gross alpha
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Lab Code Date Concentration (pCi/L)
Analysis Laboratory Resultb STW-940 02120/02 STW-940 02/20/02 STW-942 02/20/02 STW-942 02120/02 STW-944 02120/02 STW-944 02/20/02 STW-944 02/20/02 STW-944 02/20/02 STW-944 02/20/02 STW-944 02/20/02 STW-944 02/20/02 STW-944 02/20/02 STW-951 05/22/02 STW-951 05/22/02 STW-951 05/22/02 STW-951 05/22/02 STW-952 05/22/02 STW-952 05/22/02 STW-952 05122/02 STW-952 05/22/02 STW-952 05/22102 STW-952 05/22/02 STW-953 05/22/02 STW-954 05/22/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08/21/02 STW-965 08121/02 STW-965 08/21/02 STW-966 11/20/02 STW-966 11/20/02 STW-967 11/20/02 STW-968 11/20/02 STW-968 11120/02 STW-968 11/20/02 STW-969 11/20/02 Sr-89 Sr-90 Gr. Alpha Gr. Beta Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Ra-226 Ra-228 Uranium Zn-65 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-1 34 Cs-1 37 Gr. Beta Sr-89 Sr-90 H-3 1-131 Ba-133 Co-60 Cs-134" Cs-137 Gr. Alpha Gr. Beta Ra-226 Ra-228 Sr-89 Sr-90 Uranium Zn-65 Gr. Alpha Gr. Beta H-3 Ra-226 Ra-228 Uranium 1-131 53.0 +/- 2.5 16.6 +/- 0.5 6.5 +/- 0.6 45.7 +/-3.1 25.8 1 1.5 76.9 +/-2.7 38.7 t 1.6 92.9 +/-2.7 15.3 +/- 0.7 17.5 +/- 0.4 23.8 +/- 1.1 361.0 92 23.9 +/-2.5 5.9 +/-0.5 5.6 +/- 0.9 7.6+/- 02 37.9 +/-0.7 14.5 +/-0.8 50.0 : 2.0 171.0:t 2.5 28.4 +/-4.8 32.4 +/-3.1 13900.0 +/-100.0 14.6 : 0.3 71.9 +/-2.1 23.8 +/- 1.0 62.9 +/- 1.2 219.3 +/- 10.7 74.4 +/- 0.6 26.7 +/- 0.4 5.0 +/- 0.5 6.0 +/- 0.7 28.4 +/- 1.5 36.5 t 1.1 4.1 +/-0.1 92.4 +/-2.2 9.3 +/-0.4 44.7 +/- 1.0 10100.0+/-38.7 11.6 +/- 0.1 16.0 +/- 1.4 15.5 +/- 0.5 6.0 +/- 0.4 55.3 +/- 5.0 15.9 +/-5.0 8.0 +/-5.0 48.3 +/- 5.0 28.9 +/- 5.0 73.4 +/- 5.0 42.1 +/-5.0 88.8 +/- 5.0 14.3 +/-2.2 16.9 +/-4.2 28.3 +/- 3.0 359.0 : 35.9 22.8 +/-t 5.7 6.1 +/-0.9 4.5 +/- 1.1 9.3 +/- 3.0 39.1 +/-5.0 17.1 +/-5.0 52.1 +/- 5.0 189.0 +/- 28.4 31.7 +/- 5.0 28.3 +/- 5.0 17400.0 +/-1740.0 14.7 +/- 2.0 80.0 +/- 8.0 23.3 +/-5.0 71.7 +/- 5.0 214.0t +/-10.7 58.8 +/-14.7 21.9 +/-2.2 5.0 +/- 0.8 4.7 +/-1.2 29.0 +/- 5.0 36.4 +/- 5.0 5.0 +/- 3.0 95.7 +/- 9.6 12.2 +/-5.0 47.0 t 5.0 10200.0 +/- 1020.0 12.1 +/-1.8 15.1 +/-3.8 19.2 : 3.0 6.8 +/- 2.0 46.6 - 64.0 7.2 - 24.6 0.0- 16.7 39.6 - 57.0 20.2 - 37.6 64.7 - 82.1 33.4 - 50.8 80.1 - 97.5 10.6-18.0 9.6 - 24.2 23.1 - 33.5 298.0 - 420.0 13.0 - 32.6 4.5 - 7.7 2.6 - 6.5 4.1 -14.5 30.4 - 47.8 8.4 - 25.8 43.4 - 60.8 140.0 - 238.0 23.0 - 40.4 19.6 - 37.0 14400.0 - 20400.0 11.2 - 18.2 66.4 - 93.6 14.6 - 32.0 63.0 - 80.4 195.0 - 233.0 33.5 - 84.1 132 - 30.6 3.7 - 6.3 2.7 - 6.7 20.3 - 37.7 27.7 - 45.1 0.0 - 10.2 79.4 - 112.0 3.5 - 20.9 38.3 - 55.7 8440.0- 12000.0 9.0 - 15.2 8.6 - 21.6 14.0 - 24.4 3.3 - 10.2 146 ERA Resultc Control Limits
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.
Lab Code Date S1W-970 STW-970 S1W-970 STW-970 STW-970 STW-970 STW-971 STW-971 STW-971 STW-971 Concentration (pCVL)
Analysis Laboratory Resultb 11/20/02 11/20/02 11/20102 11/20/02 11/20/02 11/20/02 11/20/02 11/20/02 11/20/02 11/20/02 Co-60 Cs-l 34 Cs-137 Gr. Beta Sr-89 Sr-90 Gr. Alpha Ra-226 Ra-228 Uranium 104.0 +/- 7.1 48.2 2.3 109.0 12.6 252.0 26.8 43.2 0.7 7.5t 0.2 74.9 +/- 1.5 8.9 +/- 0.0 15.3 +/-0.1 51.7 1.6 ERA Resultc Control Limits 104.0 +/- 5.2 55.5 t 5.0 117.0 t 5.9 288.0 +/- 49.5 47.6 +/-: 5.0 7.6 +/- 5.0 103.0 : 25.8 9.1 1.4 17.8 +/-4.5 61.7 +/- 6.2 95.0 - 113.0 46.8 - 64.2 107.0 - 127.0 244.0 - 416.0 38.9 - 56.3 0.0 - 16.2 58.4 - 148.0 6.7 - 11.5 10.1 - 25.5 51.0 - 72.4 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA) b Unless otherwise indicated, the laboratory result is given as the mean standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
a Analysis was repeated; result of reanalysis: 16114*487 pCVL e ERA acknowledged an unacceptably high percentage of failure for Cs-1 34 and questioned its own control limits.
No problems were dentified in the analysis.
147
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).
Lab Code TLD Type Date mR Measurement Known Lab Result Value 2 sigma Environmental. Inc.
CaSO4: Dy Cards 12/24/2001 CaSO4: Dy Cards 12/24/2001 CaSO4: Dy Cards 12/24/2001 CaSO4: Dy Cards 12/24/2001 CaSO4: Dy Cards 12124/2001 CaSO4: Dy Cards 12124/2001 CaSO4: Dy Cards 12/24/2001 CaSO4: Dy Cards 12/24/2001 Reader 1, #1 Reader 1, #1 Reader 1, #2 Reader 1, #2 Reader 1, #3 Reader 1, #3 Reader 1, #4 Reader 1, #4 3.98 3.98 7.07 7.07 15.9 15.9 63.61 63.61 3.71 0.12 3.38 +/- 0.09 7.89 +/- 0.18 7.64 +/- 0.25 18.62 +/- 0.40 19.58 +/- 0.12 78.24 : 1.23 79.89 +/- 2.47 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 Environmental. Inc.
CaSO4: Dy Cards 5/28/2002 CaSO4: Dy Cards 5/28/2002 CaSO4: Dy Cards 5/28/2002 CaSO4: Dy Cards 5/2812002 CaSO4: Dy Cards 5/2812002 CaSO4: Dy Cards 5/2812002 CaSO4: Dy Cards 5/2812002 CaSO4: Dy Cards 5/28/2002 Reader 1, #1 Reader 1, #1 Reader 1, #2 Reader 1, #2 Reader 1, #3 Reader 1, #3 Reader 1, #4 Reader 1, #4 4.84 4.84 8.60 8.60 19.34 19.34 77.36 77.36 4.44 0.16 4.37 +/- 0.20 9.08 f 0.14 8.76 0.16 22.14 +/- 0.27 24.03 +/- 0.30 92.77 +/- 0.58 85.25 +/- 0.37 3.39 - 629 3.39 - 6.29 6.02 -11.18 6.02 - 11.18 13.54 - 25.14 13.54 - 25.14 54.15 - 100.57 54.15 - 100.57 Environmental. Inc.
2002-2 CaSO4: Dy Cards 12113/2002 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,30 Reader 1,45a 56.73 25.21 71.61 +/-t 1.79 33.49 1.38
- Precision of the distance (cm) measurement can significantly Increase the error. The placement of the card holder could account for the error.
39.71 - 73.75 17.65 - 32.77 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 12/1312002 Reader 1,60 12/13/2002 Reader 1, 75 12/13/2002 Reader 1, 90 12/13/2002 Reader1,120 12/13/2002 Reader 1,135 12/1312002 Reader 1,150 14.18 9.08 6.30 3.55 2.80 2.28
' Control limits are based on Attachment A. Page A2 of this report.
148 Contro I
Umits 2001 -1 2001-1 2001 -1 2001 -1 2001-1 2001 -1 2001-1 2001 -1 2002-1 2002-1 2002-1 2002-1 2002-1 2002-1 2002-1 2002-1 2002-2 2002-2 2002-2 2002-2 2002-2 2002-2 17.37 +/-1.24 10.65 +/-1.02 6.37 +/- 0.54 4.60 +/- 0.41 2.51 +/- 0.23 2.22 +/- 0.28 9.93 - 18.43 6.36 -11.80 4.41 - 8.19 2.49 - 4.62 1.96 - 3.64 1.60 - 2.96
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-3. In-House Spike Samples Concentration (pCi/L)a Date Analysis Laboratory results 2s, n=1 b 1/7/2002 Gr. Alpha 35.33 1/7/2002 Gr. Beta 112.62 1/31/2002 Cs-1 34 29.63 1/31/2002 Cs-137 51.31 1/31/2002 Co-60 44.18 1/31/2002 Cs-134 20.15 1/31/2002 Cs-1 37 54.88 2/6/2002 Gr. Beta 1.58 2/19/2002 H-3 47607 3/8/2002 1-131 (G) 87.84 3/8/2002 1-131 82.98 3/8/2002 1-131(G) 92.75 3/8/2002 1-131 88.00 3/11/2002 1-131(G) 0.39 4/8/2002 Gr. Beta 1.43 4/5/2002 H-3 49121 4/5/2002 Cs-134 0.83 4/5/2002 Cs-137 1.29 4/8/2002 Cs-134 20.93 4/8/2002 Cs-137 51.83 4/8/2002 1-131 87.72 4/8/2002 1-131(G) 84.08 4/812002 Sr-90 62.81 4/8/2002 1-131 82.42 4/8/2002 Co-60 32.47 4/8/2002 Cs-134 30.80 4/8/2002 Cs-137 53.85 4/8/2002 1-131 (G) 79.09 4/812002 Sr-90 70.35 5/3/2002 Gr. Alpha 25.89 5/3/2002 Gr. Beta 101.19 5/11/2002 1-131(G) 0.74 7/17/2002 H-3 40856 7/17/2002 Gr. Beta 1.58
+/- 1.83
+/-2.44
+/- 4.98
+/- 7.55
+/- 7.76
+/- 5.08
+/- 8.32
+/- 0.02
- 595 t 11.47
+/- 1.20 t 12.87
+/- 1.13
+/-0.04
+/- 0.01
+/- 608
+/-0.04
+/-0.07 t 5.82
+/- 10.23
+/- 1.28
+/- 10.75
+/- 1.99
+/- 1.27
+/-5.78
+/- 3.60
+/- 7.07
+/- 7.58
+/- 2.32
+/- 1.71
+/-2.37
+/- 0.04
- 548 t 0.02 Known Control Activity umitsc 34.57 107.70 27.10 50.89 41.36 22.59 50.89 1.55 50189 85.20 85.20 85.20 85.20 0.42 1.55 46912 0.83 1.35 24.69 50.56 88.37 88.37 66.85 88.37 33.09 28.80 50.56 88.37 66.85 34.57 107.70 0.85 46179 1.55 17.29
- 51.86 96.93
-118.47 17.10
-37.10 40.89
- 60.89 31.36
-51.36 12.59
-32.59 40.89
- 60.89 0.00
-11.55 40151
+/- 60227 75.20
- 95.20 68.16
-102.24 75.20
- 95.20 68.16
-102.24 0.25
- 0.58 0.00
-11.55 37530 t 56294 0.50
- 1.16 0.81
- 1.89 14.69
- 34.69 40.56
- 60.56 70.70
- 106.04 78.37
- 98.37 53.48
- 80.22 70.70
- 106.04 23.09
- 43.09 18.80
- 38.80 40.56
- 60.56 78.37
- 98.37 53.48
- 80.22 17.29
- 51.86 96.93
- 118.47 0.51
- 1.18 36943 t 55415 0.00
- 11.55 7/17/2002 Fe-55 10463.00
+/- 126.00 12200.60 9760.48
- 14640.72 07/17/02 H-3 45779
+/- 583 46179 36943
+/- 55415 07/17/02 NI-63 17.02
+/- 1.50 17.10 10.26
- 23.94 07/22/02 Sr-90 10.22
- 0.80 9.04 0.00
- 19.04 07/23/02 Sr-90 21.43
+/- 0.97 26.55 16.55
- 36.55 08/01/02 Gr. Alpha 41.25 t 4.58 34.45 17.23
- 51.68 08/01/02 Gr. Beta 113.66 t 5.30 107.70 96.93
-118.47 08/02/02 Tc-99 16.39
+/- 0.72 14.13 2.13
-26.13 10/25/02 Fe-55 20396 t 265 22778 18222
-27334 10/25/02 Ni-63 227.18
+/- 11.60 170.80 102.48
-239.12 149 Lab Code SPW-11552 SPW-1 1552 SPMI-595 SPMI-595 SPMI-597 SPMI-597 SPMI-597 SPAP-594 SPW-599 SPMI-1446 SPW-1446 SPW-1446 SPMI-1448 SPVE-1444 SPAP-2078 SPW-2080 SPF-2082 SPF-2082 SPMI-2084 SPMI-2084 SPMI-2084 SPMI-2084 SPMI-2084 SPW-2115 SPW-2116 SPW-2116 SPW-2116 SPW-2116 SPW-2116 SPW-2019 SPW-2019 SPCH-3064 SPW-4682 SPAP-4685 W-71702S W-71702S W-71702S SPVE-4910 W-72302S W-80102S W-80102S W-80202S SPW-7188 SPW-7190 Sample Type Water Water Milk Milk Milk Milk Milk Air Filter Water Milk Water Water Milk Vegetation Air Filter Water Fish Fish Milk Milk Milk Milk Milk Water Water Water Water Water Water Water Water Charcoal Water Air Filter Water Water Water Vegetation Water Water Water Water Water Water
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-3. In-House Spike' Samples Sample Type Water Water Air Filter Water Water Water Milk Milk Fish Fish Sediment Date 10/25/02 10/25/02 10/25102 10/30/02 10/30/02 10/30/02 10/30/02 10/30/02 10/30/02 10/30/02 11/01/02 Concentration (pCiVL)
Analysis Laboratory results 2s, n=lb H-3 C-14 Gr. Beta Co-60 Cs-134 Cs-137 Cs-134 Cs-137 Cs-134 Cs-137 Sr-90 96310 t 871 42938 : 167 1.65 0.02 39.67 f 7.38 33.09 5.96 46.80 t 10.39 34.40 +/- 4.99 46.52 8.52 0.66
- 0.03 1.35 +/- 0.05 14.69 fc 0.67 Known Control Activity Umits' 90963 49661 1.53 37.05 34.11 49.90 34.11 49.91 0.68 1.33 13.45 72770 - 109156 29796 - 69525 0.00 - 11.53 27.05 - 47.05 24.11 - 44.11 39.90 - 59.90 24.11 - 44.11 39.91 - 59.91 0.41 - 0.95 0.80 - 1.86 3.45 - 23.45 Results are reported in units of pCVL, except for air filters (pC/Filter), food products, vegetation, soil, sediment (pCVg).
bResults are based on single determinations.
c Control limits are based on Attachment A, Page A2 of this report.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
150 Lab Code SPW-7192 SPW-7194 SPAP-7198 SPW-7335 SPW-7335 SPW-7335 SPMI-7336 SPMI-7336 SPF-7340 SPF-7340 SPS-8102
Davis-Besse Nuclear Power Station 2002 Annual Radiological Envirormental Operating Report TABLEA-4. In-House'Blank"Samples Lab Code Sample Type Date Concentration (pCVL)a Analysis Laboratory results (4.66a)
LLD Activityb Acceptance Criteria (4.66 n) 0.45 +/- 0.39 0.55 +/- 1.03
-0.096 +/- 0.38 1472.1 +/- 101.50
-96.5 +/- 63.40 0.17 +/- 0.31 0.15 +/- 0.22
-0.055 +/-0.19 16.13 +/- 67.39
-0.38 +/-0.34 1.29 +/- 0.36
-0.16 +/- 0.33 0.10 +/- 0.32
-0.24 +/- 0.38 3.19 +/- 1.03
-62.8 +/- 60.30
-1.72 +/- 15.63 0.71 +/- 1.37 0.31 +/-0.36 0.9 +/- 0.95 SPW-1551 SPW-1 1551 SPAP-590 SPAP-590 SPAP-590 SPAP-590 SPMI-596 SPMI-596 SPMI-596 SPMI-596 SPW-598 SPW-598 SPW-598 SPW-600 SPMI-1 447 SPVE-1 443 SPW-1 445 SPW-1445 SPW-1445 SPW-1445 SPW-1445 SPMI-1447 SPAP-2077 SPW-2079 SPF-2081 SPF-2081 SPMI-2083 SPMI-2083 SPMI-2083 SPMI-2083 SPW-21 15 SPW-2115 SPW-2115 SPW-2115 SPW-2115 SPW-2115 SPW-2018 SPW-2018 SPch-3063 SPW-4683 W-71702 W-71702 W-71802B W-71802B water water Air Filter Air Filter Air Filter Air Filter Milk Milk Milk Milk water water water water Milk Vegetation water water water water water Milk Air Filter water Fish Fish Milk Milk Milk MilkC water water water water water water water water Charcoal water water water water water 1712002 171/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002 1/31/2002
/317/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 3/8/2002 4/8/2002 4/5/2002 4/5/2002 4/5/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/8/2002 4/22/2002 4/22/2002 5/11/2002 7/17/2002 7/17/2002 7/17/2002 7/18/2002 7/18/2002 Gr. Alpha Gr. Beta Co-60 Cs-1 34 Cs-137 Gr. Beta Co-60 Cs-134 Cs-137 K-40 Co-60 Cs-1 34 Cs-1 37 H-3 1-131 (G) 1-131(G)
Co-60 Cs-134 Cs-1 37 1-131 1-131 (G) 1-131 Gr. Beta H-3 Cs-134 Cs-1 37 Cs-1 34 Cs-137 1-131 Sr-90 Co-60 Cs-134 Cs-137 1-131 1-131(G)
Sr-90 Gr. Alpha Gr. Beta 1-131(G)
H-3 Fe-55 Ni-63 Gr. Alpha Gr. Beta 0.47 1.37 1.78 3.42 2.33 0.74 3.54 3.24 3.89 2.30 3.74 3.23 138.80 7.63 0.02 2.76 2.87 4.34 0.45 6.50 0.31 0.32 134.17 7.67 9.54 2.90 3.03 0.52 0.48 1.49 2.09 3.78 0.50 3.30 0.66 0.56 1.38 8.27 129.00 33.61 2.56 0.48 1.33 1
3.2 100 100 100 3.2 10 10 10 0
10 10 10 200 20 20 10 10 10 0.5 20 0.5 3.2 200 100 100 10 10 0.5 1
10 10 10 0.5 20 1
1 3.2 9.6 200 1000 20 1
3.2 151
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-4. In-House Blank Samples Lab Code Sample Type Date Concentration (pC VL)a Analysis Laboratory results (4.66a)
LLD Activityb Acceptance Criteria (4.66 a) water water water water water Air Fifter Milk Milk water water water Fish Fish 7/23/2002 8/2/2002 1012512002 10/25/2002 10/25/2002 10/25/2002 10/30/2002 10130/2002 10/30/2002 10/30/2002 10130/2002 10130/2002 10/30/2002 Sr-90 Tc-99 Fe-55 Ni-63 H-3 Gr. Beta '
Cs-1 34 Cs-137 Co-60 Cs-134 Cs-1 37 Cs-1i34 Cs-137 0.27 0.34 978.21 11.74 146.00 0.00 5.30 4.80 3.69 5.37 3.90 4.69 11.18 0.027 +/- 0.13
-0.051 +/- 0.16 21.77 +/- 595.33 4.47 +/- 7.24
-92 +/- 65.00
-0.0024
- 0.00 1
10 1000 20 200 3.2 10 10 10 10 10 100 100
- Uquid sample results are reported In pCitLier, air filters( pCUilter). charcoal (pCVcharcoal canister), and solid samples (pCi/kg).
b The activity reported Is the net actMty result.
C Low levels of Sr-90 are sill detected In the environment. A concentration of (1-5 pCVL) In milk Is not unusual.
152 W-72302 W-80202 SPW-7189 SPW-7191 SPW-7193 SPAP-7199
'SPMI-7333 SPMI-7333 SPW-7334 SPW-7334 SPW-7334 SPF-7339 SPF-7339
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-5. In-House 'Duplicate Samples Concentration (pCVL)a Lab Code Date Analysis First Result Second Result Averaged Result CF-20, 21 CF-20, 21 CF-20, 21 CF-20, 21 AP-11804, 11805 AP-11825,11826 AP-11846,11847 WW-150, 151 MI-124, 125 W-172, 173 SW-11698,11699 SW-11698, 11699 U-275. 276 LW-356, 357 LW-377, 378 SW-525, 526 SW-525, 526 DW-504, 505 MI-649, 650 DW-697, 698 DW-927, 928 W-973, 974 W-1673,1674 SWT-1395,1396 MI-1268,1269 MI-1268,1269 MI-1332,1333 Ml-1332, 1333 MI-1458, 1459 DW-10100, 10101 DW-10111, 10112 MI-1521, 1522 MI-1521, 1522 MI-1541, 1542 MI-1541, 1542 LW-1651,1652 DW-10134,10135 WW-1694,1695 SO-1715,1716 SO-1715,1716 DW-1030210303 W-1758,1759 W-1758, 1759 1/2/2002 1/2/2002 1/2/2002 1/2/2002 1/2/2002 1/2/2002 1/2/2002 1/712002 1/8/2002 1/8/2002 1/8/2002 1/8/2002 1/10/2002 1/16/2002 1/16/2002 1/30/2002 1/30/2002 1/31/2002 2/5/2002 2/6/2002 2/8/2002 2/18/2002 2/25/2002 2/26/2002 2/27/2002 2/27/2002 3/5/2002 3/5/2002 3/6/2002 3/9/2002 3/9/2002 3/11/2002 3/11/2002 3/11/2002 3/11/2002 3/14/2002 3/16/2002 3/18/2002 3/19/2002 3/19/2002 3/20/2002 3/25/2002 3125/2002 Be-7 Gr. Beta K-40 Sr-90 Be-7 Be-7 Be-7 Gr. Beta K-40 H-3 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha K-40 Gr. Beta Sr-90 Fe-55 H-3 Gr. Beta K-40 Sr-90 K-40 Sr-90 K-40 Gr. Alpha Gr. Alpha K-40 Sr-90 K-40 Sr-90 Gr. Beta Gr. Alpha Gr. Beta Cs-1 37 Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta 0.47 +/- 0.25 7.82 +/- 0.20 6.65 +/- 0.55 0.01 t 0.01 0.054 0.011 0.053 0.013 0.054 0.018 1.26 t 0.50 1332.30 +/- 158.90 153.00 +/- 68.00 2.51 +/-1.36 7.68 1.33 1.40 +/- 1.00 3.47 0.65 2.75 0.68 0.56 0.35 2.29 t 0.41 2.30 1.70 1319.40 +/- 176.70 5.10 1.20 0.69 0.29 7.29 0.97 2640.00 +/-155.00 2.96 0.59 1460.50 162.50 0.77 +/- 0.36 1503.00 t 164.00 1.35 +/- 0.38 1411.70 +/- 166.70 4.10 1.70 7.10 +/-2.00 1270.80 +/-: 103.30 1.69 0.46 1562.20 +/- 122.80 0.85 +/- 0.57 2.90 0.57 5.60 1.90 1.79 0.59 0.03 0.01 18.50 +/- 1.70 2.30 1.40 2.50 0.70 4.10 +/- 1.20 0.37 +/-0.12 7.95 +/- 0.21 6.53 +/- 0.36 0.01 *0.01 0.049 +/- 0.019 0.043
- 0.013 0.048
- 0.016 1.04
- 0.46 1271.70 +/- 151.50 148.00
- 68.00 3.71 t 1.80 8.49
- 1.43 1.10
- 1.20 2.94
- 0.61 2.84 t 0.61 0.24 +/- 0.35 2.58 +/- 0.39 3.90 t 1.40 1210.80
- 118.20 4.70 +/- 1.20 0.71 +/- 0.29 6.86 +/- 0.94 2908.00 +/- 161.00 2.29 t 0.53 1573.00 +/- 168.00 0.95 +/- 0.40 1305.00 : 168.00 1.07 t 0.40 1390.00 +/- 172.30 1.80 +/- 1.60 8.30 +/- 2.30 1369.10 +/- 121.60 2.46 t 0.49 1529.30 t 126.10 1.48 +/- 0.43 2.57 +/- 0.56 5.40 t 1.60 1.53 +/- 0.50 0.02 t 0.01 19.10 t 1.70 3.30 t 1.60 2.30 +/- 0.60 2.50 : 1.10 0.42 +/- 0.14 7.89 t 0.14 6.59 +/- 0.33 0.01 +/- 0.00 0.052 +/- 0.011 0.048 +/- 0.009 0.051 0.012 1.15 +/-0.34 1302.00 t 109.77 150.50 +/- 48.08 3.11 +/- 1.13 8.09 +/- 0.98 1.25 +/- 0.78 3.21 0.45 2.79 +/- 0.46 0.40 +/- 0.25 2.43 +/- 0.28 3.10 +/- 1.10 1265.10 +/- 106.29 4.90 +/- 0.85 0.70 +/- 0.21 7.08
- 0.68 2774.00 +/- 111.74 2.63 +/- 0.40 1516.75 +/- 116.87 0.86 +/- 0.27 1404.00 +/- 117.39 1.21 0.28 1400.85 +/- 119.87 2.95 +/- 1.17 7.70 +/-1.52 1319.95 +/- 79.78 2.07 t 0.34 1545.75
- 88.01 1.16 +/-0.36 2.74 +/- 0.40 5.50+/- 1.24 1.66 +/- 0.39 0.03 +/- 0.01 18.80 +/- 1.20 2.80 +/- 1.06 2.40 +/- 0.46 3.30 +/- 0.81 153
Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental Operating Report TABLE A-5. In-House 'Duplicate' Samples Concentration (pCi/L)'
Lab Code Date Analysis First Result Second Result Averaged Result MI-1926,1927 3/26/2002 MI-1926 1927 3/26/2002 SWU-2010, 2011 3/26/2002 DW-10376,10377 3127/2002 AP-2479, 2480 3/28/2002 DW-10395,10396 3/29/2002 LW-2181, 2182 3131/2002 LW-2181. 2182 3131/2002 CW-2437, 2438 3/31/2002 CW-2437, 2438 3/31/2002 MI-1947,1948 4/1/2002 AP-2458, 2459 4/1/2002 DW-10409, 10410 4/1/2002 MI-2052,'2053 4/3/2002 MI-2052, 2053 4/3/2002 AP-2711, 2712 4/3/2002 W-938, 939 419/2002 SS-2202, 2203 4/9/2002 SS-2202, 2203 4/9/2002 F-2307, 2308 4110/2002 DW-10476,10477 411212002 W-2244, 2245 4/15/2002 DW-10509,10510 4117/2002 SW-2690, 2691 4124/2002 S0-2903,2904 4/24/2002 SO-2903, 2904 4/24/2002 SO-2903, 2904 4/24/2002 DW-10562,10563 4/24/2002 DW-10578,10579 4/29/2002 SO-2861, 2862 4/30/2002 SO-2861, 2862 4130/2002 SL-2819, 2820 5/1/2002 SL-2819, 2820 5/1/2002 SL-2819. 2820 5/1/2002 SL-2840, 2841 5/1/2002 SL-2840. 2841 5/1/2002 SL-2840. 2841 5/1/2002 MI-2971, 2972 5/5/2002 MI-2971, 2972 5/5/2002 DW-10603,10604 5/6/2002 SS-3037, 3038 5/9/2002 MI-3124, 3125 5/13/2002 MI-3208, 3209 5/14/2002 LW-3250, 3251 5/15/2002 K-40 Sr-90 Gr. Beta Gr. Beta Be-7 Gr. Alpha Gr. Beta H-3 Gr. Beta H-3 K-40 Be-7 Gr. Alpha K-40 Sr-90 Be-7 Ni-63 Gr. Beta K-40 K-40 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Be-7 Cs-1 37 K-40 Gr. Alpha Gr. Alpha Cs-137 K-40 Be-7 Gr. Beta K-40 Be Gr. Beta K-40 K-40 Sr-90 Gr. Alpha K-40 K-40 K-40 Gr. Beta 1414.00 +/- 115.00 2.30 +/- 0.70 2.90 +/- 0.60 10.50 +/-1.30 0.064 +/- 0.023 10.20 +/- 2.10 2.98 +/-0.68
'2694.43 +/- 156.53 1.09 +/- 0.61 6456.70 +/- 229.20 1421.40 +/- 130.90 0.077 +/- 0.011 39.30 4.00 1283.70 +/- 103.20 0.81 +/-0.36 0.071 +/- 0.01 1.73 +/-0.10 5.83 +/- 1.16 5.75 +/- 0.48 2.75 +/- 0.27 5.10 +/-1.30 1.70 +/- 1.10 6.00 +/- 2.00 2.25 +/- 0.68 1.22 0.57 0.13 +/- 0.05 21.06 +/- 1.48 2.17 +/- 1.13 8.20 +/- 2.20 236A0 +/- 46.00 10191.00 +/-784.60 805.70 +/- 301.50 5566.00 +/- 124.00 5524.00 +/- 632.90 1010.00 +/-352.10 4399.00 +/-221.80 2422.80 +/-352.10 1338.90 +/- 83.44 0.83 +/- 0.47 6.30 +/- 1.70 11585.00 +/- 749.00 1329.50 +/- 103.80 1494.60 +/- 158.40 3.14 +/-0.55 1316.00 +/- 128.00 2.40 +/- 0.70 2.20 +/- 0.50 10.10 +/- 1.50 0.068 +/-0.014 14.60 +/- 2.40 1.99 +/- 0.70 2688.84 +/- 156.40 1.14 +/-0.58 6292.80 +/- 226.52 1256.80 +/- 104.20 0.081
- 0.010 35.30 +/- 3.60 1434.80 t 147.90 0.75 +/- 0.35 0.07 +/- 0.01 1.82 +/- 0.10 5.52 +/- 1.19 6.11 +/-0.51 2.49 +/- 0.32 3.90 +/- 1.60 1.60 +/- 1.00 7.30+/- 1.80 2.15 0.59 0.78 +/- 0.43 0.09 +/- 0.05 19.91 1.16 3.25+/-1.54 7.40 +/- 2.00 200.70 +/- 52.60 11025.00*941.30 860.73 +/- 164.80 5359.00+/- 122.00 5277.50 +/- 431.40 872.95 +/- 181.70 4593.00 +/- 276.00 2254.10 : 371.40 1345.80 +/- 100.90 1.65 +/- 0.46 5.50 +/- 1.60 11612.00 t 787.00 1373.00 +/- 107.40 1462.60 +/- 182.50 3.28 +/- 0.63 1365.00 +/- 86.04 2.35 0.49 2.55 0.39 10.30 +/- 0.99 0.066 +/- 0.013 12.40 t 1.59 2.48 0.49 2691.64 110.64 1.11 0.42 6374.75 161.12 1339.10 +/- 83.65 0.079 +/- 0.008 37.30 +/- 2.69 1359.25 t 90.17 0.78 : 0.25 0.07
- 0.01 1.78 0.07 5.67 0.83 5.93 0.35 2.62 0.21 4.50 1.03 1.65 0.74 6.65 +/- 1.35 2.20 0.45 1.00 0.36 0.11 0.04 20.48 0.94 2.71 0.96 7.80: 1.49 218.55 34.94 10608.00 612.71 833.22 :+/- 171.80 5462.50 +/- 86.98 5400.75 382.97 941.48 198.11 4496.00: 177.04 2338.45 t 255.89 1342.35 t 65.47 1.24
- 0.33 5.90+/-1.17 11598.50 +/-543.22 1351.25 74.68 1478.60 120.83 3.21 0.42 154
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-5. In-House"Duplicate" Samples Concentration (pCVL)'
Lab Code Date Analysis First Result Second Resuft Averaged Result CF-3292, 3293 5120/2002 MI-3376, 3377 512612002 MI-3418, 3419 5/2812002 SWT-3461, 3462 5/2812002 SO-3503, 3504 5/29/2002 S0-3503, 3504 5/29/2002 SO-3503, 3504 5/29/2002 SL-3545, 3546 6/312002 SL-3545, 3546 6/3/2002 DW-10754,10755 616/2002 SW-3777, 3778 6111/2002 SW-3m,3778 6/11/2002 MI-3798, 3799 6/11/2002 LW-3924, 3925 6/13/2002 MI-3966, 3967 6/18/2002 MI-3966, 3967 6118/2002 MI-3987, 3988 6/19/2002 MI-4095, 4096 6/25/2002 SWU-4221, 4222 6125/2002 LW-4179, 4180 6/27/2002 G-4329, 4330 7/11/2002 G-4329, 4330 7/1/2002 G-4329, 4330 7/11/2002 SL-4337, 4338 7/11/2002 SL-4337, 4338 7/1/2002 SL-4337, 4338 7/1/2002 SL4337, 4338 7/11/2002 AP-4864, 4865 7/11/2002 MI-4359, 4360 7/2/2002 AP-4569, 4570 7/2/2002 AP-4843,4844 7/2/2002 AP-4789, 4790 7/3/2002 SWU-4810, 4811 7/3/2002 MI-4548, 4549 7/9/2002 DW-4737, 4738 7/12/2002 MI-4632, 4633 7/15/2002 MI-5054, 5055 7/3012002 G-5075,5076 7/30/2002 SWU-5124, 5125 7/30/2002 G-5151, 5152 7/3112002 G-5151, 5152 7/31/2002 MI-5103, 5104 8/2/2002 LW-5434, 5435 8/5/2002 MI-5215, 5216 8/7/2002 K-40 K-40 K-40 Gr. Beta Cs-137 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Sr-90 Sr-90 K-40 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 Cs-1 37 Gr. Beta K-40 Be-7 K-40 Be-7 Be-7 Be-7 Gr. Beta K-40 1-131 K-40 K-40 Gr. Beta Gr. Beta Be-7 K-40 K-40 Gr. Beta K-40 1.33 t 0.99 1333.30 t 159.40 1423.70 t 121.30 2.65 +/- 0.54 0.17 +/-0.04 27.72 t 2.26 20.24 +/- 1.19 4436.00 +/- 90.00 4684.20 +/- 734.40 0.50 +/- 0.30 4.42 +/- 1.50 7.57+/-1.22 1433.40 +/- 124.20 3.05 t 0.59 1245.20 t 109.20 2.38 +/- 0.51 0.98 t 0.35 1256.10
- 138.20 6.89 +/- 1.97 2.37 t 0.58 1394.80 +/- 538.40 8.10 0.27 7758.20 +/- 1100.00 1480.90 +/- 223.80 32.30 +/- 14.70 5262.40 +/- 522.10 2249.00 +/- 381.90 0.085 +/- 0.009 1390.10 +/- 168.30 0.068 +/- 0.016 0.077 0.016 0.080 +/-0.013 2.40
- 0.84 1511.80 t 127.00 0.52 +/- 0.20 1198.40 t 114.10 1428.80 +/- 105.60 7.11 0.07 1.75 +/- 0.84 1.82 +/- 0.30 5.13 +/- 0.66 1415.90 +/- 70.57 2.77 t 0.35 1361.10 +/- 111.90 1.14 0.91 1090.70 143.40 1443.30 +/- 164.30 3.28 : 0.60 0.18 0.05 25.45 2.03 20.54 +/- 1.24 4281.00+/-t89.00 5242.50 884.50 0.60 0.30 2.97+/- 1.40 6.83 t 1.1 6 1401.20 96.96 3.38 0.72 1340.20 +/- 121.90 2.63 0.52 0.97 0.35 1199.00 : 128.30 5.38 +/- 1.93 2.00 0.62 1098.10 437.40 8.00 0.25 8399.80 +/- 929.30 1726.40 +/- 552.60 50.97 +/-27.10 5432.40 540.00 2989.90 +/- 509.60 0.085 +/- 0.006 1567.40 +/- 194.30 0.086 +/-0.018 0.090 +/- 0.020 0.078 +/- 0.015 2.47 +/- 0.88 1446.80 +/-t 101.80 0.49 +/- 0.29 1371.30 +/- 146.90 1344.30 +/- 106.40 6.99 +/- 0.07 1.90 t 0.78 2.05 +/- 0.32 5.72 0.70 1423.80 t 129.20 2.26 0.35 1358.30 +/- 115.80 1.23 +/- 0.67 1212.00 +/- 107.21 1433.50 +/-102.11 2.97 +/- 0.40 0.18 t 0.03 26.58 t 1.52 20.39 +/- 0.86 4358.50 63.29 4963.35 +/- 574.82 0.55 0.21 3.70 +/- 1.02 7.20 0.84 1417.30 78.78 3.21 t 0.46 1292.70 81.83 2.51 t 0.36 0.98 0.25 1227.55 +/- 94.29 6.13 t 1.38 2.19 t 0.42 1246.45 346.84 8.05 +/-0.18 8079.00 +/- 720.00 1603.65 298.10 41.64 +/- 15.42 5347.40 t 375.56 2619.45 t 318.41 0.085 +/- 0.006 1478.75 +/- 128.53 0.077 +/-0.012 0.084 t 0.013 0.079 +/- 0.010 2.43 0.61 1479.30+/- 81.38 0.51 +/-0.18 1284.85 +/- 93.00 1386.55 t 74.95 7.05 +/- 0.05 1.82 +/- 0.57 1.93 +/-0.22 5.42 +/- 0.48 1419.85 t 73.61 2.52 +/- 0.25 1359.70 +/- 80.52 155
Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental Operating Report TABLE A-5. In-House Duplicate" Samples Concentration (pCiVL)a Lab Code Date Analysis First Result Second Result Averaged Result Ml-5355, 5356 F-5413, 5414 F-5413, 5414 MI-5603, 5604 MI-5603, 5604 MI-5578, 5579 VE-5682, 5683 VE-5682, 5683 VE-5682, 5683 WW-6188,6189 SL-5724,5725 SL-5724, 5725 SL-5724, 5725 MI-5877, 5878 MI-6157, 6158 MI-6258, 6259 LW-6278, 6279 MI-6385, 6386 BS-6453, 6454 BS-6453, 6454 SO-6478, 6479 S0-6478, 6479 SO-6478, 6479 SO-6478,6479 S0-6478,6479 AP-6641, 6642 MI-6544, 6545 AP-6857, 6858 AP-6857, 6858 AP-6857, 6858 BS-6620, 6621 BS-6620, 6621 BS-6620,6621 MI-6651, 6652 G-6760, 6761 G-6760, 6761 SWU-7054,7055 U-7126, 7127 XW-7768, 7769 XW-7768, 7769 F-7148, 7149 BS-7337, 7338 BS-7337,7338 BS-7337, 7338 SO-7407, 7408 SO-7407, 7408 SO-7407,7408 8/13/2002 8/15/2002 8/15/2002 8/26/2002 8/26/2002 8/27/2002 8/28/2002 8/28/2002 8/28/2002 8/31/2002 9/3/2002 9/3/2002 9/3/2002 9/9/2002 9/19/2002 9/24/2002 9/30/2002 10/11/2002 10/1/2002 10/1/2002 10/11/2002 10/1/2002 10/1/2002 10/11/2002 10/11/2002 10/1/2002 10/2/2002 10/3/2002 10/3/2002 10/3/2002 10/7/2002 10/7/2002 10/712002 10/8/2002 10/9/2002 10/91/2002 10/10/2002 10/11/2002 10/14/2002 10/14/2002 10/15/2002 10/23/2002 10/23/2002 10/23/2002 10/29/2002 10/29/2002 10/29/2002 K-40 Gr. Beta K-40 1-131 K-40 K-40 Be-7 Gr. Beta K-40 Gr. Beta Be-7 Cs-1 37 K-40 K-40 K-40 K-40 Gr. Beta K-40 Cs-1 37 K-40 Cs-137 Gr. Alpha Gr. Beta K-40 Sr-90 Be-7 K-40 Be-7 Be-7 Be-7 Co-60 Cs-1 37 K-40 K-40 Be-7 K-40 Gr. Beta Gr. Beta Cs-137 H-3 K-40 Co-60 Cs-1 37 Gr. Beta Cs-1 37 Gr. Beta K-40 1405.00 t 165.80 2.37 +/- 0.10 1.47 0.32 0.64 0.34 1353.60 +/-83.13 1301.50 +/- 161.70 0.29 0.10 3.79 +/- 0.08 3.06 0.29 2.70 t 0.57 0.92 +/- 0.19 0.05 0.02 2.09 t 0.31 1340.70 +/- 165.00 1372.10 115.10 1328.60 : 201.00 2.15 :+/- 0.51 1297.10 +/- 168.90 0.43 :t 0.03 16.50 +/- 0.51 0.074 +/- 0.016 8.01 4.36 30.41 4.07 19.82 0.53 0.087 0.017 0.070 0.016 1331.60 125.20 0.062 0.015 0.062 0.015 0.062 t 0.015 0.090 +/- 0.020 0.62 +/- 0.04 11.38 t 0.48 1565.50 +/- 141.00 2.17 0.49 6.24 1.00 3.09 0.57 2.61 1.24 2.25 0.25 2.63 0.10 2.57 +/- 0.28 0.083 +/- 0.025 0.082
- 0.019 12.54 t 2.34 0.14 0.03 16.73 2.21 12.05 0.61 1549.30 +/- 114.40 2.55 +/- 0.10 1.73 0A3 0.52 +/- 0.36 1261.40 +/- 117.80 1381.60 +/- 111.20 0.25 +/- 0.11 3.80 +/- 0.08 3.31 +/- 0.42 2.30 +/- 0.57 1.04 0.23 0.05 +/- 0.02 2.28 +/- OA8 1168.50 t 172.50 1136.50 +/-222.70 1312.60 +/- 118.60 1.70 +/- 0.50 1310.10 +/- 128.30 0.44 +/- 0.03 16.80 +/- 0.61 0.070 +/- 0.016 7.55 +/- 4.57 33.04 +/- 4.28 20.39 t 0.58 0.094 +/- 0.020 0.080 +/-0.015 1326.50 +/- 171.60 0.071 0.015 0.071 +/- 0.015 0.071 +/- 0.015 0.11 +/- 0.02 0.63 +/- 0.03 10.78 +/- 0.52 1640.60 +/- 189.20 2.31 +/-0.34 6.61 +/-0.60 2.06 +/- 0.52 2.61 +/- 1.08 2.09 +/- 0.18 2.64 +/- 0.10 2.98 +/- 0.44 0.073 +/- 0.031 0.11 +/-0.04 12.99 +/-2.22 0.15 +/- 0.03 16.62 +/-2.27 12.27 +/- 0.81 1477.15 +/- 100.72 2.46 +/- 0.07 1.60 +/- 0.27 0.58 0.25 1307.50 +/- 72.09 1341.55 +/-98.12 0.27 +/- 0.08 3.79 0.06 3.18 +/-t 0.25 2.50 0.41 0.98 +/-0.15 0.05 +/-0.01 2.19 t0.29 1254.60 +/- 119.35 1254.30 t 125.34 1320.60
- 116.69 1.93 0.36 1303.60 +/- 106.05 0.44 0.02 16.65 +/- 0.40 0.072 0.011 7.78 3.16 31.73 2.95 20.10 0.39 0.091 +/-0.013 0.075 +/- 0.011 1329.05 t 106.21 0.066 t 0.010 0.066 +/- 0.010 0.066 0.010 0.10 +/- 0.01 0.62 0.02 11.08 0.35 1603.05 +/- 117.98 2.24 0.30 6.42 0.58 2.57 0.39 2.61 0.82 2.17 0.15 2.64 +/- 0.07 2.77 +/- 0.26 0.078 0.020 0.10 +/- 0.02 12.77 t 1.61 0.15 +/-0.02 16.67 +/- 1.58 12.16 +/-0.51 156
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-5. In-House Duplicate' Samples Concentration (pCVL)a Lab Code Date Analysis First Result Second Result Averaged Result MI-7428, 7429 pw-7621, 7622 TD-7653, 7654 SW-7569, 7570 SW-7569, 7570 SO-8010, 8011 SO-8010,8011 VE-7747, 7748 VE-7747. 7748 MI-7789, 7790 DW-8082, 8083 SW-8054, 8055 SW-8054, 8055 MI-8105, 8106 TD-8298, 8299 MI-8396, 8397 SWT-8654, 8655 AP-8783, 8784 10/29/2002 10/30/2002 10/31/2002 11/5/2002 11/5/2002 1 1/2002 117/2002 11/11/2002 11/11/2002 11/13/2002 11/29/2002 12/2/2002 12/2/2002 12/4/2002 12/5/2002 12/17/2002 12/30/2002 12/31/2002 K-40 Gr. Beta H-3 Gr. Beta K-40 Cs-137 K-40 Gr. Beta K-40 K-40 1-131 Gr. Beta K-40 K-40 H-3 K-40 Gr. Beta Be-7 1542.60 +/- 213.00 2.22 t 0.92 11122.00 +/- 387.00 15.90 +/- 1.25 14.79 +/- 1.48 0.11 0.02 6.91 : 0.54 3.59 : 0.05 3.17 :t 0.36 1319.30 +/- 167.60 0.83 t 0.24 2.60 +/- 0.46 1.44 +/- 0.14 1300.60 +/- 111.30 355.00 +/- 94.00 1409.20 +/- 117.30 1.63 +/- 0.50 0.044 +/- 0.009 1355.80 +/- 185.70 2.08 +/- 0.83 11259.00 390.00 16.24 +/- 1.27 14.79 +/- 1.48 0.11 +/-0.03 7.21 +/-0.54 3.25 +/- 0.05 3.26 +/- 0.46 1301.20 +/- 140.70 0.98 +/- 0.22 2.21 +/- 0.39 1.43 +/-0.14 1315.40 +/- 108.90 469.00 +/-99.00 1449.60 +/- 108.60 1.40 +/- 0.47 0.042 +/- 0.008 1449.20 +/- 141.29 2.15 +/-0.62 11190.50 +/- 274.71 16.07 +/- 0.89 14.79 +/- 1.05 0.11 +/- 0.02 7.06 t 0.38 3.42 t 0.03 3.22 0.29 1310.25 +/- 109.41 0.90 +/- 0.16 2.41 0.30 1.44 0.10 1308.00 t 77.86 412.00 68.26 1429.40 +/-79.93 1.51 +/- 0.34 0.043 t 0.006 Note: 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.
a Results are reported in units of pCVL, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCVg).
157
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentratio nb Lab Code Type Date Analysis Laboratory result Known Activity Control Umits' 12/01/01 Am-241 12/01/01 Co-57 12/01/01 Co-60 12/01/01 Cs-134 12/01/01 Cs-137 12/01/01 Fe-55 12/01/01 Mn-54 12/01/01 Ni-63 12/01/01 Pu-238 12/01/01 Pu-239/40 12/01/01 Sr-90 12/01/01 U-233/4 12/01/01 U-238 12/01/01 Zn-65 10/16/02 Am-241 10/16/02 Co-57 10/16/02 Co-60 10/16102 Cs-134 10/16/02 Cs-1 37 10/16/02 Fe-55 10/16/02 Mn-54 10/16/02 Ni-63 10/16/02 Pu-238 10/16/02 Pu-239/40 10/16/02 Sr-90 10/16/02 U-233/4 10/16/02 U-238 10/16/02 Zn-65 1.25 +/- 0.0 138.9 +/- 0.5 139.1 +/-0.5 25.16 :t 0.2 279.96 0.9 19.68 23.2 253.64 0.9 65.88 +/- 1.9 0.060 t 0.01 2.79 +/- 0.0 4.88 +/- 0.3 0.89 +/- 0.0 6.75 +/- 0.0 70.6 t 1.1 40.54 +/- 2.7 210.58 +/- 2.0 84.38 t 0.9 692.6 t 2.1 96.98 +/- 1.7 1714.6 :t 299.6 509.74 +/-t 3.4 890.6 +/- 22.4 34.04 +/- 6.0 68.7 t 3.7 1.5 +/-t 3.0 166.33 +/- 3.8 169.76 +/- 3.8 783.59 6.4 1.19 +/-: 0.0 143:t 14.3 141 +/- 14.1 28.5 +/- 0.3 286 +/- 28.6 9.2 +/-0.9 246 :+/- 0.2 88.3 +/- 8.8 0.0 +/-0.0 2.99 +/- 0.3 4.8 +/-0.5 0.98 +/- 0.1 7.8 : 0.8 67.3 +/- 6.7 43.5 +/- 4.4 246 +/- 24.6 87.5 +/-8.8 862 +/- 86.0 111 +/-11.1 1870+/- 187.0 546 +/-54.6 1180t +/-118.0 33.3 +/- 3.3 72.9 +/-t 7.3 0.0 +/- 0.0 229 +/- 22.9 220 fc 22.0 809 +/- 80.9 0.83 - 1.6 100.1 - 185.9 98.7 - 183.3 19.95 - 37.1 2002 - 371.8 6.44 - 12.0 1722 - 319.8 61.81 - 114.8 2.09 - 3.9 3.36 - 6.2 0.69 - 1.3 5.46 - 10.1 47.11 - 87.5 30.45 - 56.6 172.2 - 319.8 61.25 - 113.8 603.4 -1120.6 77.7 - 144.3 1309 - 2431.0 382.2 - 709.8 826 - 1534.0 23.31 - 43.3 51.03 - 94.8 160.3 - 297.7 154 - 286.0 566.3 - 1051.7
- 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 bAll results are In Bq/kg or Bq/L as requested by the Department of Energy.
C MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
Known activity below the laboratory LLD. The sample was recounted for 2000 minutes; resuit: 1 1.52 +/- 5.55 Bq /L.
eIncluded In the testing series as a false positive". No activity expected.
158 STW-939 STW-939 STW-939 STW-939 STW-939 STW-939d STW-939 STW-939 STW-939" STW-939 STW-939 STW-939 STW-939 STW-939 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 STSO-955 water water water water water water water water water water water water water water soil soil soil soil soil soil soil soil soil soil soil soil soil soil
Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental Operating Report TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)
Concentrationa Laboratory results 1.68 +/- 0.14 349.20 +/- 2.60 3.40 t 0.60 57.20 +/- 1.70 0.45 t 0.11 4.47 +/- 0.28 7.40 : 1.30 3.27 +/- 0.43 265.40 +/- 7.70 930.60 +/- 12.00 226.30 +/-: 32.70 55.00 +/- 5.50 8.30 +/-: 3.30 49.20 t 12.40 46.60 t 3.10 1401.60 +/- 9.10 613.10
- 28.10 51.60 +/-t 2.60 52.00 t 3.60 14.70 t 3.50 52.10 +/- 6.30 122.40 t 6.30 143.40 +/- 9.40 3.10 t2.20 0.90 +/- 0.80 13.50 t 2.10 350.40 +/- 6.30 940.80
- 45.60 16.90 0.70 543.40 t 24.90 0.09 t 0.05 30.10 +/-0.30 29.90 +/- 0.30 40.40 +/- 0.40 0.05 +/- 0.02 0.15 +/- 0.02 3.40 0.40 0.80 +/- 0.20 0.43 +/- 0.04 1.34 0.05 3.00 +/- 0.10 258.40 +/- 2.30 50.80 +/- 3.30 80.10 +/- 0.30 80.10 +/-0.30 3.00 *0.10 EML Resultb 1.47 347.33 3.36 56.07 0.49 4.22 7.58 2.84 375.00 1030.00 283.70 51.17 10.93 53.43 53.93 1326.67 621.67 51.10 54.37 19.10 53.76 89.30 194.77 2.23 1.32 11.23 313.67 864.33 3.54 586.28 0.09 30.52 28.23 38.53 0.06 0.19 4.83 0.61 0.53 1.30 3.04 268.67 60.20 81.43 81.43 3.04 Control Umitsc 0.79 - 1.41 0.80 - 1.20 0.80 - 1.30 0.80 - 1.22 0.74 - 1.20 0.79 - 1.20 0.69 - 1.34 0.75 - 1.33 0.58 - 1.29 0.61 - 1.43 0.78 - 2.45 0.80 - 1.38 0.65 - 2.28 0.50 - 1.34 0.78 - 1.42 0.80 - 1.25 0.80 - 1.32 0.78 - 1.32 0.76 - 1.46 0.71 - 1.30 0.67 - 2.90 0.63 - 2.35 0.71 - 1.32 0.73 - 2.02 0.61 - 1.59 0.80 - 1.44 0.80 - 1.31 0.79 - 1.39 0.69 - 1.31 0.55 - 1.21 0.70 - 2.34 0.80 - 1.26 0.80 - 1.32 0.80 - 1.35 0.67 - 1.33 0.73 - 1.26 0.53 - 1.84 0.79 - 2.10 0.73 - 1.43 0.76 - 1.36 0.79-1.41 0.80 - 1.20 0.80 - 1.30 0.80 - 1.22 0.80 - 1.22 0.79 - 1.41 159 Lab Code STW-945 STW-945 STW-945 STW-945 STW-945 STW-945 STW-945 STW-945 STW-946 STW-946 STW-946 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STSO-947 STVE-948 STVE-948 STVE-948 STVE-948 STVE-948 STVE-948d STVE-948 STAP-949 STAP-949 STAP-949 STAP-949 STAP-949 STAP-949 STAP-949 STAP-949 STAP-950 STAP-950 STW-959 STW-959 STW-959 STW-959 STW-959 STW-959 Type Water Water Water Water Water Water Water Water Water Water Water Soil Soil Soil Soil Soil Soil Soil Soil Soil Soil Soil Soil Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Water Water Water Water Water Water Date 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03101102 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 03/01/02 09/01/02 09/01/02 09(01/02 09/01/02 09/01/02 09/01/02 Analysis Am-241 Co-60 Cs-134 Cs-1 37 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta H-3 Ac-228 Am-241 BI-212 Bi-214 Cs-137 K-40 Pb-212 Pb-214 Pu-239/40 Sr-90 Th-234 Uranium Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta Am-241 Co-60 Cs-134 Cs-137 Cs-137 Am-241 I
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)'.
Concentrationb Laboratory results 3.00 0.10 258.40 2.30 50.80 3.30 80.10
- 0.30 271.90 fc 20.90 4.40 fc 0.20 2.10 t 0.10 9.70 fc 0.20 5.60 0.1 0 204.90 3.20 852.00 : 26.50 47.60 +/- 1.90 7.80 1.40 45.60 fc 1.70 48.80 4.90 819.60 16.60 705.30 31.40 48.60 3.40 51.10 +/- 5.10 20.20 0.80 38.50 0.10 58.90 +/- 0.70 2.10 0.30 1.00 0.30 11.80 fc 1.50 340.30 16.80 1646.00 fc 74.40 3.00 0.30 345.60 fc 97.80 0.20 0.01 24.90 0.60 38.00 fc 1.30 60.80 f 1.90 0.11 0.02 021 0.01 5.20 0.20 0.41 0.04 0.40 fc 0.10 0.80 0.10 EML Resultc 3.04 268.67 60.20 81.43 227.30 4.33 2.07 8.69 6.84 210.00 900.00 42.30 6.77 45.93 33.63 829.33 637.67 43.43 35.20 12.90 41.16 87.21 225 1.25 9.66 300.67 1480.00 3.43 476.26 0.19 23.00 32.50 52.20 0.12 0.21 5.56 0.47 0.29 0.87 Control Umitsd 0.79 - 1.41 0.80 - 1.20 0.80 - 1.30 0.80 - 1.22 0.78 - 2.45 0.74 - 120 0.79 - 1.20 0.69 - 1.34 0.75-1.33 0.58 - 1.29 0.61 - 1.43 0.80 - 1.38 0.65 - 228 0.50 - 1.34 0.78 - 1.42 0.80- 1.25 0.80 - 1.32 0.78 - 1.32 0.76 - 1.46 0.71 - 1.30 0.67 - 2.90 0.71 -1.32 0.73 - 2.02 0.61 - 1.59 0.80- 1.44 0.80- 1.31 0.79-1.39 0.69 - 1.31 0.55 - 1.21 0.70 -2.34 0.80 - 1.26 0.80 - 1.32 0.80 - 1.35 0.67 - 1.33 0.73 - 1.26 0.53 - 1.84 0.79 - 2.10 0.73 - 1.43 0.76 - 1.36 a Results are reported in Bq/L with the following exceptions: Air Filters (BqfFifter), Soil and Vegetation (Bq/kg).
D The EML result listed is the mean of replicate determinations for each nuclide +/- the standard error of the mean.
c Control limits are reported by EML as the ratio of Reported Value / EML value.
160 Lab Code STW-959 STW-959 STW-959 STW-959 STW-959 STW-959 STW-959 STW-959 STW-959 STW-960 STW-960 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 STSO-961 g STVE-962 STVE-962 STVE-962 STVE-962 STVE-962 STVE-962 STVE-962 STAP-963 STAP-963 STAP-963 STAP-963 STAP-963' STAP-963h STAP-963 STAP-963' STAP-964 STAP-964 Type Water Water Water Water Water Water Water Water Water Water Water Soil Soil Soil Soil Soil Soil Soil Soil Soil Soil Soil Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Date 09/01102 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 09/01/02 Analysis Am-241 Co-60 Cs-134 Cs-137 H-3 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta Ac-228 Am-241 Bi-212 Bi-214 Cs-I 37 K-40 Pb-212 Pb-214 Pu-239/40 Sr-90 Uranium Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report d An error was found in the conversion from pCUg to Bqlkg. Corrected result: 2.84 +/- 0.59 Bq/lkg.
e Naturally-occurring radium daughters are present in the shield background, and a probable cause of the higher bias seen for isotopes of lead and bismuth.
Reporting error.The average result of the triplicate analyses was 14.1+/- 5.7 Bq/kg.
9 The analysis was repeated in duplicate; result of reanalysis, 87.05 +/- 7.64 Bqlkg.
n STAP-963, Calculations for the transuranics analyses (Am-241, Uranium, Pu-238, -239/40) were not converted to Bq/total fiter.
The data listed is the result of recalculation.
161
Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental Operating Report APPENDIX B DATA REPORTING CONVENTIONS 162
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Data Reporting 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. Sinale Measurements Each single measurement is reported as follows:
x
- 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: cL, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.
3.0. DuDlicate analyses 3.1 Individual results: For two analysis results; xl *s1 and X2 +s2 Renorted result:
x
- s; where x = (1/2) (xl + x2) and s = (1/2)JS2 3.2.
Individual results:
<LI, L2 ReDorted result: <L, where L = lower of L1 and L2 3.3.
Individual results:
x +/- s, <L Reported result:
x t s if x L; <L otherwise.
4.0. Comr,utation of Averaaes and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2.. xn are defined as follows:
1 ID X
X)2 x=-Zx s=
1 n
n-l 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 number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
163
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas 164
Davis-Besse Nuclear Power Station 2002 Annual Radiological Enviromnental Operating Report Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCim3)
Water (pCiL)
Gross alpha Gross beta lodine-1 31 b 1 x10-3 1
2.8 x Strontium-89 Strontium-90 Cesium-1 37 Barium-140 Iodine-131 Potassium-40C Gross alpha Gross beta Tritium a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
165 8,000 500 1,000 8,000 1,000 4,000 2
10 1 x 106
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report APPENDIX D REMP SAMPLING
SUMMARY
166
Davis-Besse Nuclear Power Station 2002 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, 2002 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)O Mean (F)'
Mean (F)'
Routine (Units)
Analyses" Range' Locationd Range' Range' Resuts Airbome GB 519 0.005 0.025 (311/311)
Site Boundary 0.027 (52/52) 0.025 (208/208) 0 Particulates (0.011-0.045) 0.9 mi. E (0.014-0.040)
(0.011-0.042)
(pCVm3)
Sr-89 0.001
< LLD.
< LLD 0
Sr-90 0.0008
< LLD
< LLD 0
GS 40 Be-7 0.015 0.073 (24/24)
T-2, Site Boundary 0.080 (4/4) 0.067 (16/16) 0 (0.046-0.098) 0.9 mL E (0.053-0.093)
(0.041-0.095)
K-40 0.034
< LLD
< LLD 0
Nb-95 0.0013
< LLD
< LLD 0
Zr-9S 0.0026
< LLD
< LLD 0
Ru-0.0013
< LLD
< LLD 0
103 Ru-0.0077
< LLD
< LLD 0
106 Cs-0.0011
< LLD
< LLD 0
134 Cs-0.0010
< LD
< LLD 0
137 Ce-0.0023
< LD
< LD 0
141 Ce-0.0073
< LLD
< LLD 0
144 Airbome Iodine 1-131 519 0.07
< LLD
< LLD 0
(pCVm3)
TLD (Quarterty) Gamma 295 1.0 15.5 (255/255)
T-45, Site Boundary 22.0 (4/4) 15.8 (40/40) 0 (mR191 days)
(5.7-26.1) 0.5 mL. WNW (18.5-26.1)
(9.6-21.5)
TLD (Quarterly)
Gamma 4
1.0 7.2 (4/4)
None 0
(mRt9 days)
(6.4-7.8)
(Shield)
TLD (Annual)
Gamma 85 1.0 62.2 (75/75)
T-8. Farm 95.6 (1/1) 68.0 (10/10) 0 (mR/365 days)
(36.5-95.6) 2.7 mi. WSW (50.2-82.2)
TLD (Annual)
Gamma 1
1.0 28.3 (1/1)
None 0
(mR/365 days)
(Shield) 167
Davis-Besse Nuclear Power Station 2002 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 Docket No.
50-346
- Repoting Period January-December, 2002 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLOb Mean (F)'
Mean (F)0 Mean (F)C Routine (Units)
Analyses' Range' Locationd Range' Range' Results' Milk (pCUL) 1-131 12 05 none
< LLD 0
Sr-12 1.3 none
< LLD 0
89 Sr-12 0.0 none T-24, Sandusky 1.1 (1212) 1.1 (12/12) 0 90 GS 12 21.0 m8 SE (0.7-2.3)
(0.7-2.3)
K-40 100 none T-24, Sandusky 1351 (12/12) 1351 (12/12) 0 21.0 mi. SE (1229-1517)
(1229-1517)
Cs4 7.8 134 Cs-6.4 none
< LLD 0
137 Ba-La-140 11.5 none
< LLD 0
(gL)
Ca 12 0.50 none T-24, Sandusky 0.90 (12/12) 0.90 (12/12) 0 21.0 ml. SE (0.80-0.97)
(0.80-0.97)
(gIL)
K (stable) 12 none T-24, Sandusky 1.56 (12112) 1.56 (1212) 0 21.0 mi. SE (1.42-1.75)
(1.42-1.75)
(pCIg)
Sr-90/Ca 12 none T-24, Sandusky 1.24 (12/12) 1.24 (12/12) 0 21.0 mi. SE (0.74-2.56)
(0.74-2.56)
(pCVg)
Cs-1371K 12 none
< LLD 0
Ground Water GB (TR) 8 3.5 3.8 (3/4)
T-225, residence 3.8 (3/4)
< LLD (pCUL)
(3.6-4.1) 1.55 mi. NW (3.6-4.1)
H-3 8
330 440 (1/4)
T-225, residence 440 (1/4)
< LLD 0
1.55 mi. NW Sr-8 1.2
< LLD
< LLD 0
89 Sr-8 0.7 1.2 (1/4)
T-225. residence 1.2 (1/4) 0.8 (1/4) 0 90 1.55 mi. NW GS Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15 c LLD
< LLD 0
Co-60 15
< LLD LLD 0
Zn-65 30
< LLD
< LLD 0
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
168
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Davis-Besse Nudear Power Station Ottawa, ONo Docket No.
50-346 Reporting Period January-December, 2002 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) an (F)'
Mean (F)0 Routine (Units)
Analyses Range0 Locationd Range' Range Results Edible Meat GS 4
(pCig wet)
K-40 0.10 3.05 (2t2)
T-197, residence 3.38 (1/1) 2.86 (2/2) 0 (2.71-3.38) 4.0 ml. W (2.66-3.06)
Nb-95 0.057
Zr-95 0.042
< LLD
< LLD 0
Ru-103 0.037
< LLD
< LLD 0
Ru-106 0.20
< LLD
< LLD 0
Cs-134 0.019
< LLD
< LLD 0
Cs-137 0.024
< LLD
< LLD 0
Ce-141 0.075
< LLD
< LLD 0
Ce-144 0.097
< LLD
< LLD 0
Fnits and Sr-89 3
0.003
< LLD
< LLD 0
Vegetables Sr-90 3
0.001
< LLD
< LLD 0
(pCVg wet) 1-131 3
0.022
< LLD
< LLD 0
GS 3
K-40 0.50 1.14 (2t2)
T-25, residence 1.25 (1/1) 1.D9 (111) 0 (1.03-1.25) 1.6 mi. S Nb-95 0.011
< LLD
< LLD 0
Zr-95 0.024
< LLD
< LLD 0
Cs-134 0.012
< LLD
< LLD 0
Cs-137 0.011
< LLD
< LLD 0
Ce-141 0.018
< LLD
< LLD 0
Ce-144 0.10
< LLD
< LLD 0
Broad Leal Sr-89 12 0.009
<L UD.
< LLD 0
Vegetation Sr-90 12 0.001 0.005 (7/8)
T-17, Farm 0.007 (3/3) 0.004(4/4) 0 (pCVg wet)
(0.003-0.009) 1.8 mi. SSE (0.0040.009)
(0.002-0.006) 1-131 12 0.027
< LLD
< LLD 0
GS 12 K-40 0.50 232 (8/8)
T-19, Farm 248 (4/4) 214 (4/4) 0 (1.70-281) 0.68 mi. W (2.03-Z81)
(1.82-Z41)
Nb-95 0.014
< LLD
< LLD 0
Zr-95 0.027
< LLD
< LLD 0
Cs-134 0.014
< LLD
.<L D
0 Cs-137 0.018
< LLD
< LD 0
Ce-141 0.031
<LLD
< LD 0
Ce-144 0.13 L D
< LLD 0
169
Davis-Besse Nuclear Power Station 2002 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Montoring Program Summary Name of Facility Location of Facility Davis-Besse Nuclear Power Statlon Ottawa, Ohio (County, State )
Docket No.
50-346 Reporting Period January-December, 2002 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)
Analyses' Range' Locationd Range' Range' Results Animal I GS 4
Wildlife Feed Be-7 0.24 0.33 (13)
T-31. Onsite 0.33 (111)
< LLD 0
(pCVg wet)
Roving location K-40 0.10 2.87 (3J3)
T-34, Offsite 7.09 (11) 4.29 0
(2/2)
(1.46-5.48)
Roving location (1.49-7.09)
Nb-95 0.017
< LLD
< LLD 0
Zr-95 0.044
< LLD
< LLD 0
Ru-0.021
< LLD
< LLD 0
103 Ru-0.16
< LLD
< LLD 0
106 Cs-0.023
< LLD
< LLD 0
134 Cs-0.023
< LLD
< LLD 0
137 Ce-0.031
< LLD LLD 0
141 Ce-0.15
< LLD
< LLD 0
144 Soil GS 20 (pCVg dry)
Be-7 0.40 0.88 (6112) 1.14 0.77 0
(2/2)
(418)
(0.43-T-4, Site (0.87-(0.47-1.00) 1.41)
Boundary 1.41)
K-40 0.10 11.18 (12/12) 0.8 mi. S 22.39 (2/2) 19.11 0
(4.60-23.01)
T-8, Farm (21.76-23.01)
(14.55-21.88)
Nb-95 0.084
< LLD 2.7 mi.
< LLD 0
WSW Zr-95 0.092
< LLD
< LLD 0
Ru-0.051
< LLD
< LLD 0
103 Ru-0.38
< LLD
< LLD 0
106 Cs-0.062
< LLD
< LLD 0
134 Cs-0.029 0.12 T-12, Water Treatment 0.21 0.14 137 (8/12)
(2/2)
(6/)
(0.039-019)
Plant, 23.5 mi. WNW (0.18-0.24)
(0.036-0.24) 0 Ce-0.090
< LLD
< LLD 0
141 Ce-0.22
< LWLD
<LLD 0
144 170
Davis-Besse Nuclear Power Station 2002 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.
Reponing Period 5D-346 January-December, 2002 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'
Mean (F)'
Mean (F)0 Routine (Unts)
Analyses" Range' Locationd Rangee Range' Resufts Treated GB 48 1.0 2.5 (24/24)
T-22, Carroll Twp.
2.7 2.1 0
(TR)
(12/12)
(24124)
Surface Water (1.7-3.6)
WTP, 3.0 mi. NW (1.8-3.6)
(1.3-3.5)
(pCilL)
H-3 16 330
< LLD 0
Sr-89 16 1.5
< LLD
< LLD 0
Sr-90 16 0.7
< 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-10
< LLD
< LLD 0
134 Cs-10
< LLD
< LLD 0
137 Ba-La-140 15
< LLD
< LLD 0
Untreated GB (TR) 95 1.0 2.9 (50/50)
T-3, Sie Boundary 3.3 (12112) 2.8 (4545) 0 Surface Water (1.7-6.5) 1.4 ml. ESE (1.8-6.5)
(1.7-4.9)
(pCUL)
H-3 95 330
< LLD
< LLD 0
Sr-89 20 1.2
< LLD
< LLD 0
Sr-90 20 0.8
< LLD
< LLD 0
GS 95 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-10
< LLD
< LLD 0
134 Cs-10
< LLD
< LLD 0
137 Ba-La.140 15
<LLW
<LWD 0
171
Davis-Besse Nuclear Power Station 2002 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, 2002 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F)c Mean (F)c Mean (F)C Routine (Units)
Anatyses' Rangec Locationd Rangec Range Resutts Fish GB 6
0.1 3.33 (313)
T-33, Lake Erie 3.33 (3/3) 3.00 (33) 0 (pCVg wet)
(2.90-3.73) 1.5 mi. NE (2.90-3.73)
(2.76-3.19)
GS 6
K-40 0.10 2.73 (3/3)
T-33, Lake Erie 2.73 (3'3) 2.67 (3/3) 0 (2.51 -3.12) 1.5 mL. NE (2.513.12)
(2.30-3.11)
Mn-54 0.019
< LLD
< LLD 0
Fe-59 0.131
< LLD
< LLD 0
Co-58 0.030
< LLD
< LLD 0
Co-60 0.013
<LLD LLD 0
Zn-65 0.028
<LLD
< LLD 0
Cs-0.018
< LLD
<LLD 0
134 Cs-0.018
< LLD
< LLD 0
137 Shoreline GS 8
Sediments K-40 0.10 13.38 (8/6)
T-4, Site Boundary 17.40 (2/2) 8.62 (2/2) 0 (pCVg dry)
(9.67-18.89) 0.8 mi. S (15.91-18.89)
(6.06-11.17)
Mn-54 0.038
< LLD
< LLD 0
Co-58 0.049
< LLD
< LLD 0
Co-60 0.028
< LLD
< LLD 0
Cs-0.059
<LLD
< LLD 0
134 Cs-0.024 0.056 (2/6)
T-4, Site Boundary 0.084 (1/2)
<LLD 0
137 (0.027-0.084) 0.8 mi. S GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specfied locations Is indicated In parentheses SF).
Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..
Non-routine results are those which exceed ten times the control station value.
172