ML021480210

Part 2 of 2, Ltr Forwarding Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report (AREOR)

ML021480210
Person / Time
Site:	Davis Besse
Issue date:	05/13/2002
From:	Mccloskey P FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Material Safety and Safeguards
References
DSC-02-00046
Download: ML021480210 (95)

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Radioactive Effluent Release Report January 1 through December 31, 2001 Protection Standards Soon after the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazards of ioniz ing radiation were recognized and efforts were made to establish radiation protection standards.

The primary source of recommendations for radiation protection standards within the United States is the National Council on Radiation Protection and Measurement (NCRP). Many of these recommendations have been given legislative authority through publication in the Code of Fed eral Regulations (CFR) by the Nuclear Regulatory Commission (NRC).

The main objective in the control of radiation is to ensure that any dose is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA principle ap plies to reducing radiation dose both to the individual working at Davis-Besse and to the general public. "Reasonably achievable" means that exposure reduction is based on sound economic de cisions and operating practices. By practicing ALARA, Davis-Besse minimizes health risk and environmental detriment and ensures that doses are maintained well below regulatory limits.

Sources of Radioactivity Released During the normal operation of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small amounts of radioactive fission products and trace amounts of the component and structure surfaces which have been activated are present in the primary coolant water. The three types of radioactive material released are noble gases, io dine and particulates, and tritium.

The noble gas fission products in the primary coolant are given off as a gas when the coolant is depressurized. These gases are then collected by a system designed for gas collection and stored for radioactive decay prior to release.

Small releases of radioactivity in liquids may occur from valves, piping or equipment associated with the primary coolant system. These liquids are collected through a series of floor and equipment drains and sumps. All liquids of this nature are monitored and processed, if neces sary, prior to release.

Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as xenon and krypton. Noble gases are biologically and chemically nonreactive.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report They do not concentrate in humans or other organisms. They contribute to human radiation dose by being an external source of radiation exposure to the body. Xenon-133 and xenon-135, with half-lives of approximately five days and nine hours, respectively, are the major radioactive no ble gases released. They are readily dispersed in the atmosphere.

Iodine and Particulates Annual releases of radioisotopes of iodine, and those particulates with half-lives greater than 8 days, in gaseous and liquid effluents are small. Factors such as their high chemical reactivity and solubility in water, combined with the high efficiency of gaseous and liquid processing sys tems, minimize their discharge. The predominant radioiodine released is iodine-131 with a half life of approximately eight days. The main contribution of radioactive iodine to human dose is to the thyroid gland, where the body concentrates iodine.

The principal radioactive particulates released are fission products (e.g., cesium-134 and cesium 137) and activation products (e.g., cobalt-58 and cobalt-60). Radioactive cesium and cobalt con tribute to internal radiation exposure of tissues such as the muscle, liver, and intestines. These particulates are also a source of external radiation exposure if deposited on the ground.

Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid effluents. It is also present in gaseous effluents. Tritium is produced in the reactor coolant as a result of neu tron interaction with deuterium (also a hydrogen isotope) present in the water and with the boron in the primary coolant. When tritium, in the form of water or water vapor, is ingested or inhaled it is dispersed throughout the body until eliminated.

Processing and Monitoring Effluents are strictly controlled to ensure radioactivity released to the environment is minimal and does not exceed regulatory limits. Effluent control includes the operation of monitoring systems, in-plant and environmental sampling and analyses programs, quality assurance pro grams for effluent and environmental programs, and procedures covering all aspects of effluent and environmental monitoring.

The radioactive waste treatment systems at Davis-Besse are designed to collect and process the liquid and gaseous wastes which contain radioactivity. For example, the Waste Gas Decay Tanks are holding tanks which allow radioactivity in gases to decay prior to release via the station vent.

Radioactivity monitoring systems are used to ensure that all releases are below regulatory limits.

These instruments provide a continuous indication of the radioactivity present. Each instrument is equipped with alarms and indicators in the control room. The alarm setpoints are low enough to ensure the limits will not be exceeded. If a monitor alarms, a release from a tank is automati cally stopped.

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Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental the specific con All wastes are sampled prior to release and analyzed in a laboratory to identify analysis provide a more sensitive and centrations of radionuclides being released. Sampling and monitoring instruments alone.

precise method of determining effluent composition than with Station. It is linked to computers A meteorological tower is located in the southwest sector of the release data, the meteorological which record the meteorological data. Coupled with the effluent data are used to czaculate the dose to the public.

Radiological Environmental Beyond the plant, devices maintained in conjunction with the Frequent sam Monitoring Program constantly sample the air in the surrounding environment.

are also taken to determine if ples of other environmental media, such as water and vegetation, buildup of deposited radioactive material has occurred in the area.

Exposure Pathways become exposed to ra Radiological exposure pathways define the methods by which people may cause the highest cal dioactive material. The major pathways of concern are those which could from the type and amount of culated radiation dose. These projected pathways are determined and the use of the envi radioactive material released, the environmental transport mechanism, ronment. The environmental transport mechanism includes consideration of physical factors, of the area. An An such as the hydrological (water) and meteorological (weather) characteristics evaluate how the ra nual average on the water flow, wind speed, and wind direction are used to important factor in dionuclides will be distributed in an area for gaseous or liquid releases. An are considered evaluating the exposure pathways is the use of the environment. Many factors and the locations of homes and such as dietary intake of residents, recreational use of the area, farms in the area.

30. The release of The external and internal exposure pathways considered are shown in Figure exposure, deposi radioactive gaseous effluents involves pathways such as external whole body destined for hu tion of radioactive material on plants, deposition on soil, inhalation by animals material in liquid efflu man consumption, and inhalation by humans. The release of radioactive from the ents involves pathways such as drinking water, fish consumption, and direct exposure lake at the shoreline while swimming.

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Ill j LLI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 29: The exposure pathways shown here are monitored through the Radiological Environmental Monitoring Program (REMP) and are considered when calculating doses to the public.

Although radionuclides can reach humans by many different pathways, some result in more dose than others. The critical pathway is the exposure route that will provide, for a specific radionu clide, the greatest dose to a population, or to a specific group of the population called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, or other cultural factors. The dose may be delivered to the whole body or to a specific organ. The organ receiving the greatest fraction of the dose is called the critical organ.

Dose Assessment Dose is the energy deposited by radiation in an exposed individual. Whole body exposure to ra diation involves the exposure of all organs. Most background exposures are of this form. Both non-radioactive and radioactive elements can enter the body through inhalation or. ingestion.

When they do, they are usually not distributed evenly. For example, iodine concentrates in the thyroid gland, cesium collects in muscle and liver tissue, and strontium collects in bone tissue.

The total dose to organs from a given radionuclide depends on the amount of radioactive material present in the organ and the amount of time that the radionuclide remains in the organ. Some ra dionuclides remain for very short times due to their rapid radioactive decay and/or elimination rate from the body, while other radionuclides may remain in the body for longer periods of time.

The dose to the general public in the area surrounding Davis-Besse is calculated for each liquid or gaseous release. The dose due to radioactive material released in gaseous effluents is calcu-85

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report lated using factors such as the amount of radioactive material released, the concentration beyond the site boundary, the average weather conditions at the time of the release, the locations of expo sure pathways (cow milk, goat milk, vegetable gardens and residences), and usage factors (inha lation, food consumption). The dose due to radioactive material released in liquid effluents is calculated using factors such as the total volume of liquid, the total volume of dilution water, near field dilution, and usage factors (water and fish consumption, shoreline and swimming fac tors). These calculations produce a conservative estimation of the dose.

Results The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period from January 1, 2001 through December 31,2001.

"* Summation of the quantities of radioactive material released in gaseous and liquid effluents (Tables 17-21)

"* Summation of the quantities of radioactive material contained in solid waste packaged and shipped for offsite disposal at federally approved sites (Table 22)

"* A listing of all radioactive effluent monitoring instrumentation required by the Offsite Dose Calculation Manual, but which were inoperable for more than 30 days During this reporting period, the estimated maximum individual offsite dose due to radioactivity released in effluent was:

Liquid Effluents:

• 7.75E-02 mrem, whole body

• 8.03E-02 mrem, thyroid Gaseous Effluents:

Noble Gas:

• 2.71E-04 mrad, whole body

• 9.27E-04 mrad, skin Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days:

e, 1.99E-03 mrem, whole body

• 2.54E-03 mrem, thyroid These doses are an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmnental Operating Report Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathways include the auxiliary feed pump turbine exhausts, the main steam safety valve system and the atmospheric vent valve system, steam packing exhaust and main feed water. For liquid effluents, the additional pathways include the Turbine Building drains via the settling ba sins. Releases via these pathways are included in the normal release tables in this report.

Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

Noble gases:

"* Released at a rate equal to or less than 500 mremn TEDE per year. (Note: the total dose due to these releases is also limited to 50 rnlrem in any calendar year.)

"* Released at a rate such that the total dose to the skin will be less than or equal to 3000 mrem in a year.

Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

e Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.

In accordance with IOCFR50, Appendix I, See. JIB. 1, air dose due to radioactivity released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:

• Less than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year.

In accordance with 10CFR50, Appendix I, Sec. IC, dose to a member of the public from Iodine 131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gase ous effluents released to areas at and beyond the site boundary shall be limited to the following:

• Less than or equal to 15 total mrem to any organ in any calendar year.

Liquid Effluents In accordance with 10CFR50, Appendix I, See IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to accumulated doses of:

• Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ in any calendar year.

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Davis-Besse Nuclear Power Station 2001 Amnual Radiological Environmental Operating Report Effluent Concentration Limits The Effluent Concentration Limits (ECs) for liquid and gaseous effluents at and beyond the site boundary are listed in 10CFR20, Appendix B, Table II, Column 2, with the most restrictive EC being used in all cases. For dissolved and entrained gases the EC of 2.0E.-04 uCi/ml is applied.

This EC is based on the Xe-I 35 DAC of IE-05 uCi/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.

Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activa tion products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radio activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" are not applicable.

Measurements of Total Activity Fission and Activation Gases:

These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel flasks, or glass vials and are counted on a germanium detector for principal gamma emitters. Radionuclides that are detected are quantified via gamma spectroscopy.

Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation.

Iodine Iodine is collected on a charcoal cartridge filter and counted on a germanium detector. Specific quantification of each iodine radionuclide is via gamma spectroscopy.

Particulates Particulates are collected on filter paper and counted on a germanium detector. Specific quantifi cation of each radionuclide present on the filter paper is via gamma spectroscopy.

Liquid Effluents Liquid effluents are collected in a marinelli beaker and counted on a germanium detector. Quan tification of each gamma-emitting radionuclide present in liquid samples is via gamma spectros copy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system.

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V 2--LLI-Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Batch Releases Liquid from 1/1/01 through 12/31/01

1. Number of batch releases: 51

2. Total time period for the batch releases: 85.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

3. Maximum time period for a batch release: 133 minutes

4. Minimum time period for a batch release: 81 minutes

5. Average time period for a batch release: 100.6 minutes Gaseous from 1/1/01 through 12/31/01

1. Number of batch releases: 6

2. Total time period for the batch releases: 61.92 hours0.00106 days <br />0.0256 hours <br />1.521164e-4 weeks <br />3.5006e-5 months <br />

3. Maximum time period for a batch release: 2473 minutes

4. Minimum time period for a batch release: 172 minutes

5. Average time period for batch release: 619.2 minutes Abnormal Releases Total 2001 activity due to Abnormal Releases 0.0 Total 2001 Dose due to Abnormal Releases is 0.OOE+00 mRem Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent of limits, for January 1, 2001 through December 31, 2001.

PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1, 2001- December 31,2001 (gaseous)

Noble gases (gamma) 2.71E-04 mrad 10 mrad 2.71E-03 Noble gases (beta) 6.56E-04 mrad 20 mrad 3.28E-03 1-131, tritium and particulates 1.99E-03 mrem 15 mrem 1.33E-02 Report Period: January 1, 2001 - December 31, 2001 (liquid)

Total body 7.75E-02 mrem 3 mrem 2.58E+00 Organ 8.03E-02 mrem 10 mrem 8.03E-01 89

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Sources of Input Data

• Water Usage: Survey of Water Treatment Plants (DSR-95-00347)

• 0-50 mile meat, milk, vegetable production, and population data was taken from 1982 Annual Environmental Operating Report entitled, "Evaluation of Compliance with Appendix I to I OCFR50: Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982". This evaluation was based on the 1980 Census, the Agricultural Ministry of Ontario 1980 report entitled "Agricul tural Statistics and Livestock Marketing Account", the Agricultural Ministry of Ontario report entitled "Agricultural Statistics for Ontario, Publication 21, 1980",

the Michigan Department of Agriculture report entitled "Michigan Agricultural Statistics, 1981", and the Ohio Crop Reporting Service report entitled "Ohio Agri cultural Statistics, 1981".

• Gaseous and liquid source terms: Tables 17 through 21 of this report.

• Location of the nearest individuals and pathways by sector within 5 miles, see Land Use Census Section of the report.

• Population of the 50-mile Radius of Davis-Besse (DSR-95-00398).

Dose to Public Due to Activities Inside the Site Boundary In accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes an as sessment of radiation doses from radioactivity released in liquid and gaseous effluents to mem bers of the public due to activities inside the site boundary.

In special instances, members of the public are permitted access to the Radiologically Restricted Area within the Davis-Besse Station. Tours for the public are conducted with the assurance that no individual will receive any appreciable dose due to radioactivity released in gaseous or liquid effluents (i.e., not more than a small fraction of the 40 CFR190 standards.)

The Wellness Center, Pavilion, Training Center pond and the forebay/canal area located inside DBNPS Owner Controlled Area are accessible to members of the public. The Pavilion is acces sible to the public for social activities. The Training Center pond, forebay/canal area allows the member of the public to fish on site under a "catch-an-release" program; therefore the fish path way is not considered applicable. Considering the frequency and duration of the visits, the re sultant dose would be a small fraction of the calculated maximum site boundary dose. For pur poses of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:

e Exposure time for maximally-exposed visitors is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (I hr/day, 5 day/ week, 50 wk/yr)

"* Annual average meteorological dispersion (conservative, default use of maximum site boundary dispersion).

" For direct "shine" from the Independent Spent Fuel Storage Installation (ISFSI),

default use of the maximum dose rate for a completed (full) ISFSI, and a distance of 950 feet.

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1l - 1 [

Davis-Besse Nuclear Power Station 2001 Arnnual Radiological Environmental Operating Report The equations in the ODCM may be used for calculating the potential dose to a member of the public for activities inside the site boundary. Based on these assumptions, this dose would be at least a factor of 35 less than the maximum site boundary air dose, as calculated in the ODCM.

Nowhere onsite are areas accessible to the public where exposure to liquid effluents could occur.

Therefore, the modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.

Inoperable Radioactive Effluent Monitoring Equipment There were no radioactive effluent monitoring equipment required to be operable that was in operable for greater than 30 days during the reporting period.

Changes to the ODCM and PCP There were two alterations to the OCDM, Revision 14.0 and Rev. 15.0. The Process Control Program (PCP) had no changes in the reporting period.

Borated Water Storage Tank Radionuclide Concentration During the Reporting Period of 2001, the BWST tank concentration did not exceed the ODCM specification of Section 2.2.4. The sum of the limiting fraction of nuclides, a unitless number between 0 and 1, the BWST tank did not exceed the limit of 1. Of the ten samples taken for the reporting period of 2001, all samples analyzed for the sum of the limiting fractions of nuclides reported were <0.05.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 17 Gaseous Effluents - Sulmantion of All Releases Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total

% Error Type 2001 2001 2001 2001 Fission and Activation Gases 2.5E+01 Total Release Ci 3.33E+00 3.09E+00 2.75E+00 5.93E+00

.Average Release Rate for Perioda ptCi/sec 4.22E-01 3.93E-01 3.49E-01 7.52E-01 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination lodines 2.5E+01 Ci 5.24E-06 2.97E-05 5.66E+00 1.13E-04 Total Iodines (1-131)

ýtCiisec 6.65E-07 3.77E-06 7.18E-06 1.43E-05 Average Release Rate for Period!

Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Particulates 2.5E+0-1 Ci 0.OOE+00 0.00E0-0 O.OOE+00 7.33E-07 Particulates with half-lives greater than 8 days Average Release Rate for Period' ptCilsec O.OOE+L00 0.00E+00 0.OOE+00 9.30E-08 Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination Ci O.OOE+00 O.OOE+00 0.00E+00 O.OOE-00 2.5E+01 Gross Alpha Activity Tritium 2.5E+01 Total Release Ci 1.02E+01 7.33E+00 5.62E+00 4.78E+00 OCi/sec 1.29E.00 9.21E-01 7.12E-01 6.07E-0I Average Release Rate for Period&

Percent of ODCM Limits See Supplemental Information in ODCM Release Limits Section 3.3, Gaseous Effluent Monitor Setpoint Determination a The average release rate is taken over the entire quarter. It is NOT averaged over the time period of the releases.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 Gaseous Effluents - Ground Level Releases Batch Modea Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2001 2001 2001 2001 Fission Gases Ci Kr-85 LLDb LLDb LLDb LLDb Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LID LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe-135 LID LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A lodines Ci 1-131 LLD LLD LLD LLD 1-132 LLD LLD LLD LLD 1-133 LLD LLD LLD LLD 1-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A Particulates and Tritium Ci H-3 9.65E-03 8.69E-03 1°10E-02 6.351E-03 Sr-89 LLD LLD LLD LLD

'Sr-90 LID LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba-140 LLD LLD LLD LLD Co-58 LLD LLD LLD LLD Total for Period: 9.6511-03 8.69E-03 1.1OE-02 6.35E-03 93

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Table 18 (Continued)

Gaseous Effluents - Ground Level Releases Continuous Modec 3rd 4th 2001Qtr lstQtr 2001 2nd Qtr 2001 2001Qtr Nuclide Unit Fission Gases Ci LLDb LLDb LLDb LID Kr-85 LLD LLD LLD LLD Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LID LLD Xe-133 LLD LLD LID LLD Xe-135 LLD LLD LLD LID Xe-135m LLD LID LLD LLD Xe-138 N/A N/A N/A N/A Total for Period:

lodines Ci LLD LLD LLD LID 1-131 LLD LID LLD LLD 1-133 LLD LLD LLD LLD 1-135 N/A N/A N/A N/A Total for Period:

Particulates and Tritium Ci 1.11 E-02 1. I3E-02 1.88E-02 2.34E-02 H-3 LLD LLD LLD LLD Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba-140 1.1IE-02 1.13E-02 1.88E-02 2.34M-02 Total for Period:

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IEl _ 11 -l t Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 18 (Continued)

Gaseous Effluents - Ground Level Releases Continuous and Batch Mode Ar-41: <2.2E-08 iCimrnI Kr-85: <6.213-06 pCi/ml Kr-85m: <2.0E-08 *Ci/ml pCi/fil Kr-87: <3.4E-08 Kr-88: <4.013-08 iCi/ml gCi/nl Xe-13 Ir: <9.0E-08 pCi/ml Xe-133: <4.6E-08

ýCi/mnl ACi/ml Xe-133m: <1.6E-07 Xe-135: <1.9E-08 gCi/nml Xe-135m: <4.0E-07 Xe-138: <2.5E-07 gCi/nm 1-131: <1.0E-07 pCi/mi 1-133: <2.11E-08 jiCi/nil 1-135: <2.113-08 i+/-Ci/ml Mn-54 <2.OE-08 gCiiml gCi/nil Fe-59: <4.013-08 gCi/mi Co-58: <3.0E-08 RCi/mI Co-60: <2.0E-08 Zn-65: <4.0E-08 pCi/nml Mo-99: <2.0E-07 gtCi/rnl Cs-134: <2.113-08 pCi/rnl Cs-137: <3.013-08 j~i/n-l pCi/ml Ce-141: <3.0E-08 pCi/mi Ce-144: <1.2E-07 Ba-140: <7.0E-08 La-140: <3.0E-08 pCi/nil Sr-89: <5.0E-08 gCi/nil Sr-90: <6.0E-09 pCi/rm a Auxiliary Feed Pump Turbine Exhaust, Main Steam Safety Valves, and Auxiliary Boiler Outage Release are listed as batch releases.

b These radionuclides were not identified in concentrations above the lower limit of detection (LLD).

c Atmospheric Vent Valve weepage and Steam Packing Exhaust are continuous releases.

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 19 Gaseous Effluents - Mixed Mode Releases Batch Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Unit 2001 2001 2001 2001 Nuclide Fission Gases Ar-41 Ci LLD LLD LLD LLD Ci 1.06E-01 LLD 2.05E-01 3.54E-01 Kr-85 Ci LLD LLD LLD LLD Kr-85m Ci LLD LLD LLD LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD 1.74E-02 LLD 7.24E-01 Xe-133 Ci LLD LLD LLD LLD Xe-133mn Ci LLD LLD LLD LLD Xe-135 Ci LLD LLD LLD LLD Xe-135m Ci LLD LLD LLD LLD Xe-138 LLD 4.10E-02 Xe-131m Ci LLD LLD 1.06E-01 1.74E-02 2.05E-01 1.12E+00 Total for Period:

• Iodines 1-131 Ci LLD LLD LLD LLD Ci LLD LLD LLD LLD 1-132 Ci LLD LLD LLD LLD 1-133 LLD LLD LLD 1-135 Ci LLD LLD LLD Total for Period: Ci LWD LLD

• Particulates H-3 Ci 1.21E-03 5.85E-04 3.06E-02 4.65E-03 Ci 1.21E-03 5.85E-04 3.06E 4.65E-03 Total for Period:

• Release of iodines and particulates are quantified in Mixed Mode Releases, Continuous Mode (Unit Sta tion Vent) 96

rt 1 nI _LI _I Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 19 (Continued)

Gaseous Effluents - Mixed Mode Releases Continuous Mode 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2001 2000 2000 2000 Fission Gases Ar-41 Ci LLD LLD LLD LLD Kr-85 Ci LLD LLD LLD LLD Kr-85m Ci LLD LLD LLD LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD LLD LLD LLD Xe-133 Ci 2.88E+00 2.65E+00 1.84+00 4.57E+00 Xe- 133m Ci LLD LLD LLD LLD Xe-135 Ci 3.39E-01 4.23E-01 7.11 E-01 2.40E-01 Xe-135m Ci LLD LLD LLD LLD Xe-138 Ci LLD LLD LLD LLD Total for Period: 3.22E+00 3.07+00 2.55E+00 4.8 IE+00 lodines 1-131 Ci 5.24E-06 2.97E-05 5.66E-05 1.13E-04 1-133 Ci LLD 3.52E-06 5.39E-05 1.49E-04 1-135 Ci LLD LLD LLD LLD 1-132 Ci LLD LLD LLD LLD Total for Period: 5.24E-6 3.32E-05 1.11 E-04 2.62E-04 Particulates and Tritium H-3 Ci 1.02E+01 7.3 1E-÷-00 5.56E+00 4.75E+00 Sr.89b.0 Ci LLD LLD LLD LLD Sr-90b6* Ci LLD LLD LLD. LLD Cs- 134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LLD Ba-140 Ci LLD LLD LLD LLD Co-58 Ci LLD LLD LLD 7.33E-07 La-140 Ci LLD LLD LLD LLD Co-60 Ci LLD LLD LLD LLD Total for Period: 1.02E+01 7.31EE+00 5,56E+00 4.75E+00 97

ReLport Da-,,is-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Table 19 (Continued)

Gaseous Effluents - Mixed Mode Releases Batch Modes Continuous Mode'

<2.9E-08 P.Ci/nl Kr-87 <4.SE-06 RCi/mid Ar-41 <6.6E-06 VCi/nil Kr-85 <3.3E-06 pCi/mid Kr-88 Xe-i 35 <1 .E-O5 pCi/mil K~r-85m <1 313-08 liCi/mni

<6.OE-08 tiLCi/m1. Xe- 13 5m <2.lE-06 Kr-87 g.Ci/mI

<6.OE-O8 p;Xi/nil Xe-138 <2.813-05 Kr-88 <1 .8E-06 gCi/miA Xe-131m, <4.4E-07 Ar-41 p~Ci/ml Kr-85 <1 .2E-06 9+/-Ci/nil Xe- 133m. <7.2E-08 JlCi/mfl Xe-133 <2.4B-06 pLci/mi Xe-135 <I IE-08 jliCi/nml Xe-133m, <1 .OE-05 LLCi/ml Xe-135m. <5.9E-06 gCi/mi Xe-I 38 <z.OE-O5 pCi/nil 1-135' <3.9E-10 gCi/mid Mn-54c <2.6E-14

<3.013-14 9Ci/mi Fe-59c pCi/miA Co-58c <3.OE-14 pCi/ni]

Co-60c <2.5E-14 pCi/min Zn-65 <I.OE-13 ICimln)

Mo-99c <1 .8E-14

<1,613-14 pCi/mi Cs-i34' PCi/mi Cs¶37c <1 .3E-14 Ce-14 I' <1.2E-13 pCi/nil Ce-144c <1 .2E-14 ACi/mi Ba-140C <4.013-14 piCi/nil La-14O <1.O13-14 Sr-89b'r <9.3E-16 PCi/mi Sr-9ObC <3. 1E-1 6 pCi/nil a These radionuclides were not identified in every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is listed.

b Quarterly corrposite sample for continuous mode.

c Analysis not required for batch release.

98

EI -- ] -11 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 20 Liquid Effluents - Summation of All Releases Type Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total 2001 2001 2001 2001  % Error Fission and Activation Products Total Release (without Tritium, Ci 3.37E-03 1.08E-03 1.20E-03 5.55E-04 2.0E+01 Gases, Alpha)

Average Diluted Concentration jCi/ml 3.24E-10 1.0113-10 9.75E-11 5.18E-!1 During Period' Percent of ODCM Limits  % See Supplement information in ODCM Release Limits Sec tion Percent of IOCFR20 Limit  % 2.16E-03 1.61 E-03 1.65E-03 3.26E-03 Tritium Total Release Ci 1.65E+02 1.36E+02 1.29E+02 1.361+02 2.OE+01 Average Diluted Concentration jPCi/ml 1.58E-05 1.27E-05 1.05E-05 1.27E-05 During Period&

Percent of 10CFR20 Limit  % 1.58E+00 1.27E+00 1.051+00 1.27E+0 Dissolved and Entrained Gases Total Release Ci 1.39E-05 4.68E-04 5.46E-05 1.99E-03 2.0E+01 Average Diluted Concentration pCi/ml 1.33E-12 4.36E-1 1 4.441-12 1.86E-10 During Perioda Percent of IOCFR20 Limit  % 6.67E-07 2.18E-05 2.221-06 9.301-05 Gross Alpha Total Release Ci 0.00E+00 0.00E+00 0.00t+00 4.61E-03 2.0E+01 Volume of Waste Released (prior to dilution)

Batch liter 3.45E+05 3.42E+05 3.73E+05 3.96E+05 2.0E+01 Continuous liter 9.05E+07 8.04E+07 7.97E+07 1.02E+08 2.OE+01 Volume of Dilution Water Batch liter 1.01E+08 1,01 E+08 1.10E1+08 1.17E+08 2.0E+01 Continuous liter 1.02E+1 0 1.06E+10 1.21 E+ 10 1.05E+10 2.0E+01 Total Volume of Water Released liter 1.04E+i 0 1.07E+10 1.23E+10 1.07E+10

' 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

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Table 21 Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2 nd Qtr 3rd Qtr 4th Qtr 2001 2001 2001 2001 Nuclide Unit Fission and Activation Products 1.24E-04 Ci 6.40E-05 3.95E-05 1.34E-03 Co-58 1.37E-04 1.28E-04 1.80E-05 Ci 7.42E-05 Co-60 3.84E-04 7.96E-04 7.52E-05 Ci 5.55E-04 Ag-110m 4.67E-04 LLD LLD Ci 2.36E-03 Sb-125 LLD LLD LLD Ci 6.90E-06 Cs-134 LLD 8.17E-07 4.23E-07 Ci 1.32E-05 Cs-137 LLD LLD LLD Ci LLD Sr_89a, b LLD LLD LLD LLD Ci Sr.90, b 1.97E-04 LLD 1 32E-04 1.15E-04 Ci LLD Fe-55 7.11E-05 LLD LLD Cr-51 Ci 3.12E-04 LLD 4.44E-05 1.88E-05 1-131 Ci LLD LLD LLD LLD 1-132 Ci 2.OOE-05 LLD LLD LLD 1-133 Ci LLD LLD Ci LLD LLD Te-132 LLD LLD LLD Ci LLD Tc-99m LLD LLD LLD Ci LLD Sb-124 LLD LLD LLD Ci LLD Sn- 113 LLD LLD LLD Ci LLD Ru-103 LLD LLD LLD Ci LLD Mn-54 LLD LLD LLD Ci LLD Np-239 LLD LLD LLD Ci LLD Co-57 LLD LLD LLD Ci LLD Nb-95 LLD LLD 1.43E-06 Ci LLD Zr-95 LLD LLD LLD Ci LLD Se-75 LLD LLD LLD Ci LLD Fe-59 LLD LLD LLD Ci LLD Zn-65 LLD LLD LLD Ci LLD Ce-144 LLD LLD LLD Ci LLD Na-24 7.73E-06 LLD LLD Ci 2.53E-05 Zr-97 LLD LLD LLD Ci LLD Ce-141 LLD LLD LLD Ci LLD Nb-97 LLD LLD LLD Ci LLD La-140 LLD LLD LLD Ci LLD Ba-140 LLD LLD LLD Ci LLD Ru-106 LID LLD LLD Ci LLD Ba-139 LLD LLD LLD Ci LLD Mo-99 Ci 3.37E-03 1.08E-03 1.20E-03 5.55E-04 Total for Period:

100

rn 11111 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Released Batch Releases 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Nuclide Unit 2001 2001 2001 2001 Tritium Ci 1.65E+02 1.36E+02 1.29E+02 1.36E+2 Dissolved and Entrained Gases Kr-85m Ci LLDa LLDa LLDa LIDa Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci 1.39E-05 4.68E-04 5.38E-05 1.94E-03 Xe-135 Ci LLD LLD 8.69E-07 4.68E-05 Xe-133m Ci LLD LLD LLD LLD 1-135 Ci LLD LLD LLD LLD Total for Period: Ci 1.39E-05 4.68E-04 5.47E-05 1.99E-03 101

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Table 21 (continued)

Liquid Effluents - Nuclides Released Continuous Releases 3rd tr 'nil vrr I st Qtr 2nd Qtr 3rd 0tr 2001 2001 2001Qtr 420 2001 Nuclide Unit Fission and Activation Products Ci LLDa LLDa LLDV LLDa Cr-51 LLD LLD LLD Ci LLD Fe-59 LLD LLD LLD Ci LLD Co-58 LLD LLD LLD Ci LLD Co-60 LLD LLD LLD Ci LLD Zn-65 LLD LLD LLD Ci LLD Sr.89B"b LLD LLD LLD Ci LLD Srt90ab LLD LLD Ci LLD LLD Nb-95 LID LLD LLD Ci LLD Zr-95 LLD LLD LLD Ci LLD Mo-99 LLD LLD LLD Ci LLD Tc-99m LLD LLD LLD Ci LLD 1-131 LLD LLD LLD Ci LLD Cs-134 LLD LID LLD Ci LLD Cs-137 LLD LID LLD Ci LLD Ba-140/La-140 LLD LLD LLD Ci LLD Ce-141 N/A N/A N/A Total for Period: NI/A Tritium Ci 2.37E-01 1.29E-01 2.97E-01 9.45E-02 Dissolved and Entrained Gases Kr-85 Ci LLD LID LLD LLD LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD LLD Xe-133 Ci LLD LLD LLD LLD Xe-133m Ci LLD LLD LLD LLD Xe-135 Ci N/A N/A N/A N/A Total for Period: Ci 102

El - _ILLJ Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 21 (continued)

Liquid Effluents - Nuclides Releaseda Na-24 <2.OE-08 pCi/mI Sb-124 <1.OE-08 pCi/ml Cr-51 <1.7E-07 tCi/ml Sb-125 <1.7E-08 pCi/ml Mn-54 <2.1E-08 pCi/ml Te- 132 <1.8E-08 pCi/ml Fe-55b <7.OE-07 pCi/ml Ce-141 <3,0E-08 pCi/ml Fe-59 <4.2E-08 PCi/mi Ce-144 <1.7E-07 pCi/ml Co-57 <1.6E-08 pCi/ml Cs-134 <2.IE-08 pCi/ml Co-58 <1.9E-08 gCi/ml Ce-136 <2.8E-08 PCi/ml Co-60 <2.5E-08 IpCi/mi Cs-137 <2.7E-08 pCi/mi Zn-65 <5.2E-08  ;.tCi/mi Ba-140 <7.OE-08 pCi/mI Se-75 <2.4E-08 pCi/mi La-140 <3.OE-08 pCi/ml Sr-89b <3.OE-08 pCi/mi Np-239 <1.2E-07 gCi/mi pCi/ml Sr-90b <8.OE-09 1-131 <2.5E-08 aCi/mi Zr-95 <4.OE-08 pCi/ml 1-132 <1.OE-08 pCi/ml Zr-97 <2.SE-08 pCi/ml 1-133 <2.1E-08 gCi/mi Nb-95 <2.IE-08 pCi/ml 1-135 <1.7E-07 ptCii/ml Mo-99 <1.6E-07 pCi/ml Kr-85 <6.2E-06 gCi/mi Tc-99m <1.8E-08 PCi/mi Xe-131 <7.7E-07 tCi/ml Ru-103 <2.2E-08 pCi/ml Xe-133 <4.6E-08 pCi/mi Ag- 110m <2.5E-08 pCi/ml Xe-133m <1.6E-07 PCi/ml Sn-i 13 <2.8E-08 pCi/ml Xe-135 <1.9E-08 RCi/mi 2 These radionuclides were not identified every quarter in concentrations above the lower limit of detection (LLD). The largest LLD value is used for each radionuclide. LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.

b Quarterly composite sample 103

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Table 22 Solid Waste and Irradiated Fuel Shipments irradiated fuel)

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not r i2-montfl

- - .. T rL. ZUWI y'...i 12-monm Error. %

I T..4-

1. Type of Waste __ _......_

mn 3 5.45E+00 2.5E+01

a. Spent resins, filter sludges, 2.5E+01 evaporator bottoms, etc. Ci 2.03E+02 rn3 1.02E+02 2.5E+01

b. Dry compressible waste, Ci 3.85E+00 2.5E+01 contaminated equip., etc.

3

c. Irradiated components, mn Ci N/A N/A control rods, etc.

mn 3 9.10E-02 2.5E+01

d. Others: dewatered primary Ci 1.44E-02 2.5E+01 system cartridge filters

2. Estimate of major nuclide composition tby type of waste; Est. Total Error, %

Percent (%)

2.78E+00 2.50E+01 Fe"

a. Spent Resins 7.71E+00 2.50E+01 Co 60 2.93E+01 2.50E+01 Ni63 4.76E+00 2.50E+01 Cs134 5.38E+02 2.50E+01 Cs137

b. Dry compressible waste, contaminated 6.38E+01 2.50E+01 equipment, etc. Fe"' 2.50E+01 Co60 1.75E+01 3.59E+00 2.50E+01 6.54E+00 2.50E+01 Ni63 2.OOE+00 2.50E+01 Co58

e. None 2.63E+01 2.50E+01 Fe"

d. Cartridge filters 5.26E+01 2.50E+01 Co 58 63 5.06E+00 2.50E+01 Ni 2.36E+00 2.50E+01 Agli°m Zr95 1.49E+00 2.50E+0l 5.37E+00 2.50E+01 Co06 14 C 1.96E+00 2.50E+01 104

El H1XLL Dav is-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 22 (continued)

Solid Waste and Irradiated Fuel Shipments

3. Solid Waste Disposition Number of Shipments: 2 Mode of Transportation: Truck Destination: STUDSVIK Processing Facility, Erwin TN For processing then disposal at Barnwell S.C.

Type of Container (Container Volume): High Integrity Container (3.75 m3)

Volume shipped for processing 3 7.5 mn Volume disposed 0.64m 3 Number of Shipments: 4 Mode of Transportation: Truck Destination: US Ecology, Oak Ridge, TN for processing then disposal at Envirocare of Utah Type of Container (Container Volume): Metal boxes (36.3 m 3)

Volume shipped for processing 3 194.05 mn3 Volume disposed 39.96 M Number of Shipments: 1 Mode of Transportation: Truck Destination: ATG Inc. Richland Washington for processing then disposal at Envirocare of Utah or Bamwell S.C.

Type of Container (Container Volume): Metal Boxes (2.6 m3)

Volume shipped for processing 8.15 m3 Volume disposed Processing not complete in 2001 Est. 0.82 n 3 Number of Shipments: 1 Mode of Transportation: Truck Destination: ATG Inc, Oak Ridge Tenn. for processing then disposal at Barnwell S.C.

Type of Container (Container Volume): High Integrity Container (5.72m3)

Volume shipped for processing 5.72 mn3 Volume disposed 5.72 rn3 Number of Shipments 9 Mode of Transportation Truck Destination ALARON Corp., Wampami Pa. For processing then Disposal at Envirocare of Utah.

Type of Container (Container Volume) Metal Boxes (73.42 mn 3)

Volume shipped for processing 259.83 m3 (spent fuel racks)

Volume disposed Processing not complete in 2001 Est. 61.28 in 3 B. IRRADIATED FUEL SHIPMENTS 105

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Table 23 Doses Due to Gaseous Releases for January through December 2001 Maximum Individual Dose Due to 1-131, 1H-3 and Particulates with Half-Lives Greater than 8 days.

Whole Body Dose 1.99E-03 mrem Significant Organ Dose 2.54E-03 mrem Maximum Individual Dose Due to Noble Gas Whole Body Dose 2.71E-04 mrad Skin Dose 9.27E-04 mrad Population Dose Due to 1-131, H-3 and Particulates with Half-Lives Greater than 8 days.

Total Integrated Population Dose 7.02E-03 person-rem Average Dose to Individual in Population 3.21E-06 mrem Population Dose Due to Noble Gas Total Integrated Population Dose 5.03E-04 person-rem Average Dose to Individual in Population 2.30E-07 mrem 106

El I is ALI Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 24 Doses Due to Liquid Releases for January through December 2001 Maximum Individual Whole Body Dose 7.75E-02 mnrem Maximum Individual Significant Organ Dose 8.03E-02 mremr Population Dose Total Integrated Population Dose 7.31E-01 person-rem Average Dose to Individual 3.35E-04 mrern 107

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Table 25 Annual Dose to The Most Exposed (from all pathways) Member of The Public 2001 ANNUAL DOSE 40CFRI90 LIMIT PERCENT OF (mrem) (mrem) LIMIT Whole Body Dose*

Noble Gas 2.98E-04 Iodine, Tritium, Particulates 1.99E-03 Liquid 7.75E-02 Total Whole Body Dose 7.98E-02 25 3.19E-01 Thyroid Dose Iodine, Tritium, Particulates 8.28E-02 75 1.1 OE-01 Skin Dose Noble Gas 1.02E-03 25 4.08E-03 Significant Organ Dose 8.28E-02 25 3.31E-01 (Thyroid)

Meteorological Data Meteorological data on 3Y inch microdisk for January through December 31, 2001, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555.

not

• Direct radiation from the facility is not distinguishable from natural background and is, therefore, included in this compilation.

108

Land Use Census Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Land Use Census Program Design Each year a Land Use Census is conducted by Davis-Besse in order to update information neces sary to estimate radiation dose to the general public and to determine if any modifications are necessary to the Radiological Environmental Monitoring Program (REMP). The Land Use Cen sus is required by Title 10 of the Code of Federal Regulations, Part 50, Appendix I and Davis Besse Nuclear Power Station Offsite Dose Calculation Manual, Section 5, Assessment of Land Use Census Data. The Land Use Census identifies gaseous pathways by which radioactive mate rial may reach the general population around Davis-Besse. The information gathered during the Land Use Census for dose assessment and input into the REMP ensure these programs are as cur rent as possible. The pathways of concern are listed below:

"* Inhalation Pathway - Internal exposure as a result of breathing radionuclides car ried in the air.

"* Ground Exposure Pathway - External exposure from radionuelides deposited on the ground

" Plume Exposure Pathway - External exposure directly from a plume or cloud of radioactive material.

" Vegetation Pathway - Internal exposure as a result of eating vegetables, fi-uit, etc.

which have a build up of deposited radioactive material or which have absorbed ra dionuclides through the soil.

" Milk Pathway - Internal exposure as a result of drinking milk, which may contain radioactive material as a result of a cow or goat grazing on a pasture contaminated by radionuclides.

Methodology The Land Use Census consists of recording and mapping the locations of the closest residences, dairy cattle and goats, and broad leaf vegetable gardens (greater than 500 square feet) in each meteorological sector within a five mile radius of Davis-Besse.

The siurveillance portion of the 2001 Land Use Census was performed during the month of August. In order to gather as much information as possible, the locations of residences, dairy cows, dairy goats, and vegetable gardens were recorded. The residences, vegetable gardens, and milk animals are used in the dose assessment program. The gardens must be at least 500 square feet in size, with at least 20% of the vegetables being broadleaf plants (such as lettuce and cab bage).

Each residence is tabulated as being an inhalation pathway, as well as ground and plume expo sure pathways. Each garden is tabulated as a vegetation pathway.

109

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report All of the locations identified are plotted on a map (based on the U.S. Geological Survey 7.5 mi nute series of the relevant quadrangles) which has been divided into 16 equal sectors corre sponding to the 16 cardinal compass points (Figure 31). The closest residence, milk animal, and vegetable garden in each sector are determined by measuring the distance from each to the vent at Davis-Besse.

Results The following changes in the pathways were recorded in the 2001 census:

"* S Sector - A garden at 5830 meters replaced a garden at 4960 meters

"* SW Sector - The garden at 5400 meters was replaced by a garden at 5180 meters.

"* WSW Sector - The garden at 4270 meters was replaced with a garden at 7430 meters.

"* SE Sector - a residence at 8000 meters was added.

"* SW Sector - the former closest residence was replaced with a residence at 1070 meters.

The critical receptor identified by the 2001 Land Use Census is a garden in the W sector at 1610 meters from Davis-Besse.

The detailed list in Table 26 was used to update the database of the effluent dispersion model used in dose calculations. Table 26 is divided by sectors and lists the distance (in meters) of the closest pathway in each meteorological sector.

Table 27 provided information on pathways, critical age group, atmospheric dispersion (X/Q) and deposition (D/Q) parameters for each sector. This information is used to update the Offsite Dose Calculation Manual (ODCM). The ODCM describes the' methodology and parameters used in calculating offsite doses from radioactivity released in liquid and gaseous effluents and in cal culating liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints.

110

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report 0

w z

0 0

z w 0 (0 2 0

U,,

LI z 2w w

U) 0 5

LU 5:D 4h 0 in -j 0

Figure 31: Land Use Census Map ill cot

I

.PdFi Radioactive Effluent Release Report

Davis-Besse Nuclear Power Station 2001. Annual Radiological Environmental Operating Report Table 26 Closest Exposure Pathways Present in 2001 Sector Distance from Station (meters) Closest Pathways N 880 Inhalation Ground Exposure Plume Exposure NNE 880 Inhalation Ground Exposure Plume Exposure NE 900 Inhalation Ground Exposure Plume Exposure ENE,, E, ESE N/A Located over Lake Erie SE** 8000 Inhalation Ground Exposure Plume Exposure SSE 2860 Vegetation SSE 1970 Inhalation Ground Exposure Plume Exposure S** 5830 Vegetation S 1030 Inhalation Ground Exposure Plume Exposure SSW 2350 Vegetation SSW 980 Inhalation Ground Exposure Plume Exposure SW** 5180 Vegetation SW** 1070 Inhalation Ground Exposure Plume Exposure

"**Changes since 2000 112

RL - -ý -I-LL-Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 26 (continued)

Closest Exposure Pathways Present in 2001 Sector Distance from Station (meters) Closest Pathways WSW 1540 Inhalation Ground Exposure Plume Exposure WSW** 7430 Vegetation W 980 Inhalation Ground Exposure Plume Exposure W 1610 Vegetation WNMT 1750 Inhalation Ground Exposure Plume Exposure NW 1490 Inhalation Ground Exposure Plume Exposure NW 2300 Vegetation NNW 1270 Inhalation Ground Exposure Plume Exposure

• • Changes since 2000 113

Davis-Besse Nuclear Power Station 2001 Annual Radiological Envirornmental Operating Report Table 27 Pathway Locations and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q)

Parameters SECTOR METERS CRITICAL AGE X/Q 3 D/Q PATHWAY GROUP (SEC/M ) (M_)

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-8 1.45E-10 SSE 2860 Vegetation Child 6.91E-08 8.13E-10 S** 5830 Vegetation Child 2.90E-08 1.67E-10 SSW 2350 Vegetation Child 5.90E-08 1.03E-09 SW** 5180 Vegetation Child 3.85E-08 3.40E-10 WSW`** 7430 Vegetation Child 3.40E-08 1.80E-10 W 1610 Vegetation Child 2.77E-07 4.37E-09 WNW 1750 Inhalation Child 1.46E-07 1.72E-09 NW 2300 Vegetation Child 6.98 E-08 5.79E-10 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.

• • Changes since 2000 114

7 Non-Radiological Environmental Programs

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environrmental Non-Radiological Environmental Programs Meteorological Monitoring by the Nuclear Regulatory The Meteorological Monitoring Program at Davis-Besse is required routine operation of nu Commission (NRC) as part of the program for evaluating the effects of regulations and the Davis clear power stations on the surrounding environment. Both NRC the Meteorological Monitoring Besse Technical Requirements Manual provide guidelines for equipment, in good working Program. These guidelines ensure that Davis-Besse has the proper data.

order, to support the many programs utilizing meteorological 1968. The Meteorological Moni Meteorological observations at Davis-Besse began in October which to perform clima toring Program at Davis-Besse has an extensive record of data with has had any impact upon the tological studies which are used to determine whether Davis-Besse meteorological personnel have local climate. After extensive statistical comparative research the found no impact upon local climate or short-term weather patterns.

be used by many other The Meteorological Monitoring Program also provides data that can The Emergency Prepar groups and programs: Radiological Environmental Monitoring Program, Plant Security, Mate edness Program, The Chemistry Unit, and groups such as Plant Operations, of the surrounding rials Management, Industrial Safety Program, plant personnel and members community.

data to aid in evalu The Radiological Environmental Monitoring Program uses meteorological The meteoro ating the radiological impact, if any, of radioactivity released in Station effluents.

the program logical data is used to evaluate radiological environmental monitoring sites to assure data to cal is as current as possible. The Emergency Preparedness Program uses meteorological weather data to plan culate emergency dose scenarios for emergency drills and exercises and uses meteorological evacuations or station isolation during adverse weather. The Chemistry Unit uses discharge data for chemical spill response activities, marsh management studies, and wastewater efficiency calcu flow calculations. Plant Operations uses meteorological data for cooling tower environmental con lations, forebay water level availability and plant work which needs certain in their routine plan ditions to be met before work begins. Plant Security utilizes weather data adverse weather ning and activities. Materials Management plans certain plant shipments around in material deliveries conditions to avoid high winds and precipitation, which would cause delays to advise personnel and safety concerns. industrial Safety uses weather and climatological data safer place to work.

of unsafe working conditions due to environmental conditions, providing a accidents to Legal Affairs uses climatological data for their investigation into adverse weather the plant and personnel.

115

11 Davis-Besse Nuclear Power Station 2001 Anuial Radiological Enviromnental Operating Report On-site Meteorological Monitoring

System Description

At Davis-Besse there are two meteorological systems, a primary and a backup. They are both housed in separate environmentally controlled buildings with independent power supplies. Both primary and backup systems have been analyzed to be "statistically identical" to the other so if one system fails the other can take its place. The instrumentation of each system follows:

PRIMARY BACKUP 100 Meter Wind Speed 100 Meter Wind Speed 75 Meter Wind Speed 75 Meter Wind Speed 10 Meter Wind Speed 10 Meter Wind Speed 100 Meter Wind Direction 100 Meter Wind Direction 75 Meter Wind Direction 75 Meter Wind Direction 10 Meter Wind Direction 10 Meter Wind Direction 100 Meter Delta Temperature 100 Meter Delta Temperature 75 Meter Delta Temperature 75 Meter Delta Temperature 10 Meter Ambient Temperature 10 Meter Ambient Temperature 10 Meter Dew Point 10 Meter Solar Incidence Precipitation Meteorological Instrumentation The meteorological system consists of one monitoring site located at an elevation of 577 feet above mean sea level (IGLD 1955)*, a l00m free-standing tower located about 3,000 feet SSW of the cooling tower, and an auxiliary l0m foot tower located 100 feet west of the 100 m tower, are used to gather the meteorological data. The l00m tower has primary and backup instruments for wind speed and wind direction at 100m and 75m. The l00m tower also measures differential temperature (delta Ts): 100-10m and 75-10m. The i0m tower has instruments for wind speed and wind direction. Precipitation is measured by a tipping bucket rain gauge located near the base of the 10m tower.

According to the Davis-Besse Nuclear Power Station Technical Requirements Manual, a mini mum of five instruments are required to be operable at the two lower levels (75m and 10m) to measure temperature, wind speed, and wind direction. During 2001, annual data recoveries for all required instruments were 99.27 percent. Minor losses of data occurred during routine in strument maintenance, calibration, and data validation.

Personnel at Davis-Besse inspect the meteorological site and instrumentation regularly. Data is reviewed daily to ensure that all communication pathways, data availability and data reliability are working as required. Tower instrumentation maintenance and semiannual calibrations are performed by in-house facilities and by an outside consulting firm. These instruments are wind tunnel tested to assure compliance with applicable regulations and plant specifications.

• International Great Lakes Data - 1955 116

Operaiing Report Davis-Besse Nuclear Power Station 2001 Anuial Radiological Environmental Meteorological Data Handling and Reduction Scientific Dataloggers Each meteorological system, primary and backup, have two Campbell to communicate 900 (model 21XL) assigned to them. The primary system has a first datalogger system. This is a dedicated second averages to the control room via a Digital Alpha computer system and the control line. If a failure occurs at any point between the primary meteorological shelter. Each datalogger room the control room can utilize the second data logger in the primary backup meteorological sys has its own dedicated communication link with battery backup. The data the primary and tem is designed the same as the primary; so to lose all meteorological However, this would be backup meteorological systems would have to lose all four dataloggers.

with lightning and surge difficult since each is powered by a different power supply and equipped battery backup.

protection, plus four independent communication lines and datalogger stored in a 30-day circular The data from the primary and backup meteorological systems are Data goes back to storage module with permanent storage held by the Digital Alpha computer.

points are scruti 1988 in this format and to 1968 in both digital and hardcopy formats. All data These are nized every 900 seconds by meteorological statistics programs running continuously.

weather conditions.

then reviewed by meteorological personnel daily for validity based on actual codes, which statistically analyze all A monthly review is performed using 21 NRC computer system can not data points for their availability and validity. If questionable data on the primary and not incorporated be corroborated by the backup system, the data in question is eliminated on hard copy and in into the final database. All validated data is then documented and stored digital format for a permanent record of meteorological conditions.

Meteorological Data Summaries from the on This section contains Tables 28-30, which summarize meteorological data collected site monitoring program in 2001.

Wind Speed and Wind Direction the wind speed in Wind sector graphics represent the frequency of wind direction by sector and as they mph by sector. This data is used by the NRC to better understand local wind patterns Updated Safety relate to defined past climatological wind patterns reported in Davis-Besse's mph for Analysis Report. The maximum measured sustained wind speeds for 2001 were 51.03 and 39.02mph for the the 100m level on April 12, 45.85 mph for the 75m level on October 25, 10m level on April 12.

by di Figures 32-34 give an annual sector graphic of average wind speed and percent frequency has two radial bars.

rection measured at the three monitoring levels. Each wind sector graphic bar The darker bar represents the percent of time the wind blew from that direction. The hatched are classified us represents the average wind speed from that direction. Wind direction sectors middle of ing Pasquill Stabilities. Percent calms (less than or equal to 1.0 mph) are shown in the the wind sector graphic.

117

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Ambient and Differential Temperatures Monthly average, minimum and maximum ambient temperatures for 2001 are given in Table 29.

These data are measured at the 10m level; with differential temperatures taken from 100m and 0

75m levels. The yearly average ambient temperature for 2001 was 51.86 F. The maximum temperature was 92.28°F on August 8 with the minimum temperature of 4.78°F on January 02.

Yearly average differential temperatures were -0.21°F (100m), and -0.07°F (75m). Maximum differential temperatures for 100m and 75m levels were 7.990 F on December 11, (100m), and 7.99°F on November 11, (75m). Minimum differential temperatures for 100m and 75m levels were -4.0G0F on September 8, (100m) and -2.86'F on April 18, (75m). Differential tempera tures are a measurement of atmospheric stability and used to calculate radioactive plume disper sions based on Gaussian Plume Models of continuous effluent releases.

Dew Point Temperatures and Relative Humidity Monthly average and extreme dew point and humidity temperatures for 2001 are provided in Table 29. These data are measured at the 10 meter level. The average dew point temperature was 43.05'F with a maximum dew point temperature of 77.10°F on July 23. Please note that dew point temperatures above 75WF are highly suspect and are possibly due to calm winds and high solar heating allowing the aspirated dew point processor to retain heat. The minimum dew point (dew point under 32WF is frost point) temperature was 3.76"F on January 9. Average rela tive humidity is 73.52 percent for the year. The maximum relative humidity was 100.00 percent on November 11. The minimum relative humidity was 27.11 on May 4. It is possible to have relative humidity above 100 percent, which is known as supersaturation. Conditions for super saturation have been met a few times at Davis-Besse due to its close proximity to Lake Erie and the evaporative pool of moisture available by such a large body of water.

Precipitation Monthly totals and extremes of precipitation at Davis-Besse for 2001 are given in Table 29. To tal precipitation for the year was 22.91 inches. The maximum daily precipitation total was 1.34 inches in September. The minimum was 0.19 inches recorded in January. It is likely that pre cipitation totals recorded in colder months are somewhat less than actual due to snow/sleet blowing across the collection unit rather than accumulating in the gauge.

Lake Breeze and Lake Level Monitoring Lake Breeze is monitored at Davis-Besse because of its potential to cause major atmospheric/

dispersion problems during an unlikely radioactive release. A lake breeze event occurs during the daytime, usually during the summer, where the land surface heats up faster than the water, and therefore reaches higher temperatures than the water. The warmer air above the land rises faster because it is less dense than the cooler air over the lake. This leads to rising air currents over the land with descending denser air over the lake. This starts a wind circulation, which draws air from the water to the land during the daytime, creating a "Lake Breeze" effect. This event could be problematic if a release were to occur because diffusion would be slow thus cre ating an adverse atmosphere to the surrounding site.

Lake and forebay levels are monitored at Davis-Besse to observe, evaluate, predict and dissemi nate high or low lake level information. This data is critical in the running of the plant due to the 118

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental too low the plant large amounts of water needed to cool plant components. If water levels get Erie is the shallowest operators can take measures for the safe shutdown of the plant. Since Lake level fluctuation to oc of the Great Lakes, it is not uncommon for a plus or minus five feet lake the plant due to emergency cur within an eight to ten hour period, High water levels also effect transportation and evacuation pathways.

119

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 99.18 2001 100 100 100 100 96.64 100 10Gm Wind Speed 100 94.20 100 99.17 100 100 100 100 99.73 99.91 100 99.17 100 100 100 100 100 100 99.73 99.65 100M Wind Direction 100 100 100 100 100 96.91 100 100 99.17 75M Wind speed 100 100 100 100 100 100 100 100 100 99.73 99.91 100 100 100 99.17 99.73 99.67 75M Wind Direction 100 100 100 100 100 97.18 100 100 99.17 1GM Wind Speed 100 100 100 100 100 100 100 100 100 99.73 99.91 100 100 100 99.17 99.73 I OM Wind Direction too 99.87 98.92 100 88.31 100 100 100 100 99.17 100 99.73 98.81 99.89 10M Ambient Air Temp 100 100 100 100 100 99.73 100 100 100 100 99.17 99.73 98.80 10M Dew Point Temp 100 100 99.87 98.92 100 88.17 100 100 100 100 99.17 99.73 Delta T (1OOM-IOM) 100 100 99.87 98.92 100 88.17 100 99.73 98.80 J l00 100 100 99.17 Delta T (75M-lOM)

Joint 10GM Winds and 0 C3 Delta T (100M-1OM) 100 94.20 100 99.17 100 100 99.87 98.92 100 87.23 100 99.73 98.28

.. + 1'Q Joint 75M Winds and 00 100 99.87 98.92 100 87.37 100 99.73 98.73 Delta T (IOOM-IOM) 100 100 100 99.1.7 100 C..

ID Joint 1GM Winds and 100 87.37 100 99.73 98.76 Delta T (75M-10M) 100 100 100 99.17 100 100 99.87 98.92

[

0 month, divided by the rnaxiimiin

• all data for individual months expressed as percent of time instrument was operable during the 0O equals the percent of time number of hours in that month that the instrument could be operable. Values for annual data recoveries was operable.

instrument was operable during the year, divided by the number of hours in the year that the instrument K1

0,/ z JUL AUG SEP OCT NOV DEC 2001 JAN FEB MAR APR MAY JUN 0 100M WIND 48.50 41.33 51.03 34.01 38.54 25.32 25.62 32.99 48,35 11/24 35.89 40,15 12/14 51.03 04/12 Max Speed (mph) 33.83 02/25 03/06 04/12 05/04 06/12 07/26 08/16 09/24 10/25 2.56 1.46 0.81 Date of Max Speed 01/03 1.42 1.53 0.81 2.13 11/07 12/11 09130 2.80 2.12 2.46 2.38 1.44 Min Speed (mph) 1.33 07/30 08/10 09/30 10/21 18.33 1.8.06 16.25 02/13 03/29 04/30 05/17 06/08 Date of Min Speed 01./12 1.2.73 1.2.63 15.13 19.73 18.01 16.88 18.13 15.38 12.44 Ave WindSpeed 17.42 38.02 34.49 45.85 A 75M WIND 44.76 39.08 42.93 32.17 35.25 23.17 23.99 31.75 45.85 11/24 12/14 10/25 CfOr Max Speed (mph) 31.90 02/25 03/06 04/12 05/21 06/12 07/01 08/1.6 09/24 10/25 2.77 1.43 1.32 444 I-.

Date of Max Speed 01/03 1.35 1.94 11/26 12/11 03/19 2.53 1.32 1.96 2.87 1.47 1.65 1.41 Min Speed (mph) 1.94 14.83 02/13 03/19 04/30 05/18 06/08 07/13 08/10 09/15 1.0/21 16.89 16.55 Date of Min Speed 01/12 C 16.18 15.45 16.54 14.03 11.52 11.88 11.56 13.82 17.99 Ave Wind Speed 15.80 10M WIND 28.13 25.86 39.02 1.2/14 04/12 Max Speed (mph) 23.44 34.71 29.43 39.02 24.70 22.67 18.83 19.23 22.68 36.02 1.1/25 0 1.60 0.48 Date of Max Speed 01/03 02/25 03/06 04/12 05/21 06/12 07/26 08/31 09/24 10/25 1.60 0.48 1.05 1.13 1.34 1.39 1.01 1.18 1.57 11/11 12/17 03/19 MinSpeed(mph) 0.98 2.16 10.91 9/36 Date of Min Speed 01/12 02/13 03/19 04/01 05/18 6/05 07/31 08/01 09/15 10/21 9.73 cIO 0

Ave Wind Speed 10.08 10.70 10.97 10.82 8.48 7.00 7.68 7.99 8.49 10.66 0

0 C

0

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2001 0

1OM AMBIENT TEMP 45.78 59.70 52.54 79.37 84.25 90.35 91.15 92.28 87,75 79.8 68.13 67.87 92.28 Max(F) 12/05 08/08 Date of Max 01/30 02/09 03/22 04/23 05/04 06/15 07/24 08/08 09/07 10/03 11/01 11.08 4.78 Min (F) 4.78 14.73 12.83 29.71 47.94 47.60 56.43 41.21 41.94 34.19 30.55 12/30 01/02 Date of Min 01/02 02/18 03/26 04/17 05/23 06/04 07/02 08/23 09/25 10/28 11/12 51.86 36.86 ct)

AveTemp 26.93 30.83 34.26 51.09 61.52 69.38 72.97 73.34 62.90 53.21 48.16 IOM DEW POINT I-TI'EMP 0 Mean (F) 24.55 24.83 26.83 40.68 49.72 57.68 60.99 63.51 53.11 43.42 38.79 31.25 43.05 52.64 77.10 Max (F) 46.48 51.99 46.48 63.77 67.25 70.60 77.10 76.34 71.53 64.60 58.84 12/04 07/23 0 Date of Max 01/30 02/09 03/12 04/11 05/17 06.14 07/23 08/09 09/07 10/13 11/02 7.58 3.76 C),

0 Min(F) 3.76 4.56 7.30 20.73 31.13 43.19 40.10 46.91 37.88 24.21 25.05 01/09 0 12/30 Date of Min 01/09 02/21 03/26 04/17 05/13 06/01 07/06 08/14 09/26 10/28 11/20 PRECIPITATION Total (inches) 0.58 1.93 0.70 1.57 3.20 1.41 2.27 2.89 3.61 0.80 1.78 2.17 22.91 Max.inOneDay 0.19 0.54 0.22 0.54 0.45 0.38 0.93 1.13 1.34 0.36 0.45 0,91 1,34 Date 01/30 02/09 03/12 04/06 05/1.5 06/02 07/25 08/22 09/09 10/24 11/29 12/14 09/09 C)

Report Davis-Besse Nluclear Power Station 2001 Anmual Radiological Environmental Operating Figure 32 Wind Rose Annual Average 100M w E WIND SPEED (MPH)

DIRECTION FREQUENCY W%)

DAVIS-BESSE ANNUAL 2001 100M LEVEL 123

11 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Figure 33 Wind Rose Annual Average 75M N

-i w E WIND SPEED (MPH)

DIRECTION FREQUENCY (%W DAVIS-BESSE ANNUAL 2001 75M LEVEL 124

Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Figure 34 Wind Rose Annual Average IOM W E

!WIND SPEED (MPH) S DIRECTION FREQUENCY (W)

DAVIS-BESSE ANNUAL 2001 ION LEVEL 125

Da\'is-Bcsse Nuiclear Polwer Station 2001 Annual Radiolo-ical Environmnental Oper-ating Report Table 30 Joint Frequency Distribution by Stability Class

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,JOINT 211EDUENCY DI)XVI'IBUTIDN OF WIND SPEED AND DIRECTON IN "OSUES AT 35.00 F=T SPEED tMPAJ N NNlE WE Ex.- 51 SE ESr S SSW4 514 WSW1 v WN4 NK bam8 TOTAL CI.LN 1.01- 3.49 1 0 0 a 0 0 0 0 0 a G 0 0 0 0 1 3.50- 7.49 3.3 2 0 0 0 0 0 0 0 0 0 0 0 0 2 10 27 7.50-12.49 3 0 0 c 0 0 0 0 1 2 1. 1 12 5 26 12.500-28.49 0 0 0 0 0 0 a 0 0 0 3 3 1 3 34 4 27 18.50-24.49 0 2 1. 1 1 0 0 0 0 0 0 0 0 0 0 S

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11 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 30 (continued)

Joint Frequency Distribution by Stability Class

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. DAVIS-BESSE 75-10 DT. NO BACKUP........ SITE IETIFIER, I DATA PERIOD EXAMINED, I/ 1/ I - 12/ 31/

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STABILITY CLASS X STABILITY BASED ON, DLTA T BETTIERi 250.0 AND 35.0 FEET WIND MEASURRI) AT: 35.0 FEET WINXDTHRESHOLD ATM 1.00 MP JOINT PFEQUENCY DISTRIBUTION OF WIND SP0EE ASODIRECTON AND IN HOURS AT 3S.00 FEET U NM NO EnE C ESE SE SSE S m Sw WSW I t" sW MW TOTAL CALM 1 1.01- 3.49 2 3 4 6 7 19 26 37 36 30 22 14 a 7 5 3 239 3.50- 7.49 121 13 18 49 89 105 81 83 132 1$5 165 92 72 43 14 a u160 7.S0-12.49 5 13 IB s0 6t 42 2& 36 38 218 194 1.02 S2 35 36 19 986 12.50-18.49 a 2 7 7 4 2 2 8 a 41 10 50 11 13 10 a 242 18.50-24.49 4 1 0 0 0 0 0 1 4 9 10 12 5 0 2 6 48

,24.49 0 0 0 0 0 0 0 0 0 0 3 1 a 0 0 0 4 T*IAL 22 32 47 112 364 168 Z42 165 218 483 464 271 I18 98 57 36 2680 STAMXLrT'. CLASS F STABILITY WASEDON: DELTA T BETWEEN 250.0 AND 35.0 mET WIND ME45138 AT, 3S.0 FEET WIND THESHOLD AT. 1.00 ME9 JOINT FRSOEU= DIE"81M014 OF #IND SPE.D AND DIPCION IN HOURS AT 35.00 FEET SPEED N bum HE WE E ESE SE SSE S SSW SA NEW R WNW NW WN1 TOTAL CALM 2 1.01- 3.49 1 4 2 1 2 4 17 32 48 47 23 18 6 5 5 1 216 3.50- 7.49 1 0 2 7 13 25 19 44 102 I0 125 43 30 7 7 1 576 7.50-12.a9 1 0 0 0 7 10 0 7 5 8 12 21 6 7 1 5 75 12.SO-38.49 0 0 0 0 0 1 3 1 1 0 5 0 4 18.50-24.49 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 5 0

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Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Land and Wetlands Management The Navarre Marsh, which is part of the Ottawa National Wildlife Refuge, makes up 733 acres of wetlands on the southwestern shore of Lake Erie and surrounds the Davis-Besse Nuclear Power Wild Station. The marsh is owned by Toledo Edison and jointly managed by the U.S. Fish and pools are sepa life Service and Toledo Edison. Navarre Marsh is divided into three pools. The is re rated from Lake Erie and each other by a series of dikes and revetments. Toledo Edison levels in each of sponsible for the maintenance and repair of the dikes and controlling the water the pools.

con A revetment is a retaining structure designed to hold water back for the purposes of erosion trol and beach formation. Revetments are built with a gradual slope, which causes waves to dis sipate their energy when they strike their large surface area. Beach formation is encouraged through the passive deposition of sediment. A dike is a retaining structure designed to hold wa ter for the purpose of flood control and to aid in the management of wetland habitat. When used as a marsh management tool, dikes help in controlling water levels in order to maintain desired vegetation and animal species. Manipulating water levels is one of the most important marsh management techniques used in the Navarre Marsh. Three major types of wetland communities exist in Navarre Marsh, the freshwater marsh, the swamp forest, and the wet meadow. Also, there exists a narrow dry beach ridge along the lakefront, with a sandbar extending out into Lake Erie. All these areas provide essential food, shelter and nesting habitat, as well as a resting area for migratory birds.

Davis-Besse personnel combine their efforts with a number of conservation agencies and organi zations. The Ottawa National Wildlife Refuge, the Ohio Department of Natural Resources (ODNR), and the Black Swamp Bird Observatory work to preserve and enhance existing habitat.

Knowledge is gained through research and is used to help educate the public about the impor tance of preserving wetlands.

With its location along two major migratory flyways, the Navarre Marsh serves as a refuge for a variety of birds in the spring and fall, giving them an area to rest and restore energy reserves be fore continuing their migration. The Black Swamp Bird Observatory, a volunteer research group, captures, bands, catalogues, and releases songbirds in the marsh during these periods.

Navarre Marsh is also home to wildlife that is typical of much of the marshland in this area, in cluding deer, fox, coyote, muskrats, mink, rabbits, groundhogs, hawks, owls, ducks, geese, her ons, snakes and turtles. For the first time in recent history, a pair of mature American Bald Ea gles chose the Navarre Marsh as their nesting site in late 1994, and fledged a healthy eaglet in July 1995. The young eagle was one of record 38 eaglets fledged in Ohio in 1995. A new nest was built in 1999-2000, and fledged a pair of eaglets in the summer of 2000. Three more eaglets were fledged at Davis-Besse in 2001, and were part of a record hatch of 104 Ohio eaglets. The state has gone from a low of 4 nests in 1978 to a record of 73 nests in 2001.

Ohio's seventh Federal Junior Duck Stamp Art Contest was held at Davis-Besse. Young Ohio artists in grades K-12 submitted nearly 600 entries in four age brackets. The Junior Duck Stamp Art Contest was designed to teach conservation through the arts and give students a chance to experience the beauty and diversity of wildlife. A total of 101 ribbons were awarded to young Ohio artists, with the state Best-of-Show entry submitted to Washington, D.C. to compete in the 131

.Ii Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report national contest with other state Best-of-Show entries. The winner of this competition will be used to make this year's Junior Duck Stamp. The 1996 Ohio Junior Duck Stamp Art Contest winner of Best-of-Show, Adam Grimm, became the youngest artist ever to win the adult Federal Duck Stamp contest. His artwork was displayed on the 2000 federal duck stamp.

Davis-Besse also hosted a Volunteer Eagle Watchers Workshop. Training was given to over 80 volunteers who will be observing Ohio's expanding eagle population during the current breeding and nesting season.

Water Treatment Plant Operation Description The Davis-Besse Nuclear Power Station draws water from Lake Erie for its water treatment plant. The lake water is treated with chlorine, lime, and other chemicals to produce high purity water, which is used by many of the Station's cooling systems.

Treatment System Raw water from Lake Erie enters an intake structure, then passes through traveling screens which will remove debris greater than one-half inch in size. The water is then pumped to chlorine de tention tanks. Next, the water passes through one of two clarifiers. Davis-Besse uses upflow clarifiers, or precipitators, to remove sediment, organic debris, and dissolved agents from the raw water prior to filtration. Clarifiers combine the conventional treatment steps of coagulation, flocculation, and sedimentation into a single unit. Coagulation is the process by which a chemi cal, called a coagulant, is added, causing the small particles in the water to adhere to each other and form larger particles. During flocculation, the water is gently circulated, allowing these con glomerate particles to mass together further. Finally, during sedimentation, large conglomerate particles settle to the bottom of the clarifier. These processes normally require large separate tanks. However, the use of clarifiers saves both space and the manpower needed to operate the treatment plant.

132

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report PAWWATER I ¶V~cLOFLOW WEATNTaJT oresos ARFIERS GAVtrr, CLEARWELL FEED PUMPS TANKCS FT spYS .."NG TA FTOMATC*. L*

WATERWTF. CHLpSTELVL CLEAR WELL TRANSFER PUMPS WATFP TO OEMt4ERALaEo WATER SYSTEMA to make water for Figure 35: At Davis-Besse, raw water is drawn into die water treatment plant and processed plant systems.

After the clarifier, the water goes through a flow-splitting box, which equally divides the water flow to the Automatic Valveless Gravity Filters (AVGFs). The AVGFs contain of a 50:50 ratio of anthracite to filter sand. During this filtration process, suspended matter is removed from the water and turbidity is reduced.

After filtration, the water goes to a 32,000-gallon clearwell. The clearwell acts as a reservoir from which water can be drawn as needed for all systems, including firewater and demineralized water.

Domestic Water When Davis-Besse began operation over 20 years ago, all site domestic water was produced in the Water Treatment Facility. Operation of the domestic water treatment and distribution system, including the collection and analysis of daily samples, was reportable to the Ohio Environmental Protection Agency.

Beginning in December 1998, domestic water needs at Davis-Besse have been met by the Carroll Township Water District. Since the Station no longer produces its own domestic water, these regulatory requirements have been discontinued.

Zebra Mussel Control Introduction The plant receives all of its water from an intake system from Lake Erie. Zebra mussels can se verely impact the availability of water for plant processes. Dreissenapolymorpha, commonly known as the zebra mussel, is a native European bivalve that was introduced into North 133

-1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report American waters in 1986 and was discovered in Lake Erie in 1989. Zebra mussels are prolific breeders that rapidly colonize an area by forming byssal threads that enable them to attach to solid surfaces mad to each other. Because of their ability to attach in this manner, they may form layers several inches deep. This poses a problem to facilities that rely on water intakes from Lake Erie because mussels may attach to the intake structures and restrict water flow.

Zebra mussels have not caused any significant problems at Davis-Besse, but mussels have been found attached to the intake crib (the structure that allows water to be pulled in from the lake) and the first section of the intake conduit (the pipe that connects the crib to the intake canal).

Mussels have also been found on the trash racks, and the intake bay #3 walls prior to the travel ing screens. These mussels are periodically cleaned using high-pressure water. Davis-Besse uses continuous low level chlorination of the intake bays to control the mussels.

The mussel population appears to be leveling off or declining. This is likely due to the increas ing clarity of Lake Erie. As the food source for the zebra mussel declines, mussel populations decline correspondingly.

Wastewater Treatment Plant Operation The WWTP operation is supervised by an Ohio licensed Wastewater Operator. Wastewater gen erated by site personnel is treated at an onsite extended aeration package treatment facility de signed to accommodate up to 38,000 gallons per day. In the treatment process, wastewater from the various collection points around the site enters the facility through a grinder, from where it is distributed to the surge tanks of one or both of the treatment plants.

The wastewater is then pumped into aeration tanks, where it is digested by microorganisms.

Oxygen is necessary for good sewage treatment, and is provided to the microbes by blowers and diffusers. The mixture of organics, microorganisms, and decomposed wastes is called activated sludge. The treated wastewater settles in a clarifier, and the clear liquid leaves the clarifier over a weir and exits the plant through an effluent trough. The activated sludge contains the organisms necessary for continued treatment, and is pumped back to the aeration tank to digest incoming wastewater. The effluent leaving the plant is pumped to the wastewater basin (NPDES Outfall 601) where further treatment takes place.

Summary of 2001 Wastewater Treatment Plant Operations All wastewater parameters were within specifications during the year 2001.

134

Operating Report Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental National Pollutant Discharge Elimination System (NPDES) Reporting may discharge to The OEPA has established limits on the amount of pollutants that Davis-Besse Pollutant Discharge the environment. These limits are regulated through the Station's National such as chlorine, sus Elimination System (NPDES) permit, number 21B00011. Parameters permit. Toledo Edison personnel prepare pended solids and pH are monitored under the NPDES the NPDES Reports and submit them to the OEPA each month.

Seven of these locations Davis-Besse has eight sampling points described in the NPDES permit.

location. Descriptions of are discharge points, or outfalls, and one is a temperature monitoring these sampling points follow:

Outfall 001 Collection Box: a point representative of discharge to Lake Erie Water system Source of Wastes: Low volume wastes (Outfalls 601 and 602), Circulating blowdown and service water Outfall 002 Area Runoff: Discharge to Toussaint River Source of Wastes: Storm water runoff, Circulating Water pump house sumps Outfall 003 Screenwash Catch Basin: Outfall to Navarre Marsh Source of Wastes: Backwash water and debris from water intake screens Outfall 004 Cooling Tower Basin Ponds: Outfall to State Route 2 Ditch Source of Wastes: Circulating Water System drain (only during system outages)

Outfall 588 Sludge Monitoring Source of Wastes: Wastewater Plant sludge shipped for offsite processing Outfall 601 Wastewater Plant Tertiary Treatment Basin: Discharge ftom Wastewater Treatment Plant Sources of Wastes: Wastewater Treatment Plant 135

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Outfall 602 Low volume wastes: Discharge from settling basins Sources of wastes: Water treatment residues, Condensate Polishing Holdup Tank decanta tion and Condensate Pit sumps Sampling Point 801 Intake Temperature: Intake water prior to cooling operation 2001 NPDES Summary During 2001, the NPDES permit was renewed by the Ohio EPA. This permit expired on October 31, 2000, and a renewal application was submitted in May, 2000. The permit will be effective for 5 years, after which a new permit will be negotiated. A new sampling requirement with outfall designation 004 was added to the permit renewal application. This will be used to monitor water drained from the Circulating Water System during outages. Two violations of the NPDES permit occurred during 2001. The discharge limitation for Total Suspended Solids at Outfall 601 and the Total Residual Chlorine at Outfall 001 were each exceeded once.

Chemical Waste Management The Chemical Waste Management Program for hazardous and nonhazardous chemical wastes generated at the Davis-Besse Nuclear Power Station was developed to ensure wastes are man aged and disposed of in accordance with all applicable state and federal regulations.

Resource Conservation and Recovery Act The Resource Conservation and Recovery Act (RCRA) is the statute which regulates solid haz ardous waste. Solid waste is defined as a solid, liquid, semi-solid, or contained gaseous material.

The major goals of RCRA are to establish a hazardous waste regulatory program to protect hu man health and the environment and to encourage the establishment of solid waste management, resource recovery, and resource conservation systems. The intent of the hazardous waste man agement program is to control hazardous wastes from the time they are generated until they are properly disposed of, commonly referred to as "cradle to grave" management. Anyone who gen erates, transports, stores, treats, or disposes of hazardous waste are subject to regulation under RCRA.

Under RCRA, there are essentially three categories of waste generators:

"* Large quantity Generators - A facility which generates 1000 kilograms/month (2200 lbs./month) or more.

"* Small quantity Generators - A facility which generates less than 1000 kilograms/

month (2200 lbs./month).

"* Conditionally Exempt Small Quantity Generators - A facility which generates 100 kilo grams/month (220 lbs./month).

136

Davis-Besse Nuclear Power Station 2001 Arnual Radiological Enmirotnmental Operating Report In 2001, the Davis-Besse Nuclear Power Station qualified as a small quantity generator, generat ing 5,770 pounds of hazardous waste. Davis-Besse personnel also continuously strives to iden tify alternate ways of reducing hazardous waste generation.

Non-hazardous waste disposed of in 2001 included 2,250 gallons of used oil, 385 gallons of oil filters and solid oily debris. Other non-hazardous regulated waste generated included 505 gallons of other chemicals such as microfilm process chemicals and polystyrene resins.

RCRA mandates other requirements such as the use of proper storage and shipping containers, labels, manifests, reports, personnel training, a spill control plan and an accident contingency plan. These are part of the Chemical Management Program at Davis-Besse. The following are completed as part of the hazardous waste management program and RCRA regulations:

" Weekly Inspections of the Chemical Waste Accumulation Areas are designated through out the site to ensure proper handling and disposal of chemical waste. These, along with the Chemical Waste Storage Area, are routinely patrolled by security personnel and in spected weekly by Environmental and Chemistry personnel. All areas used for storage or accumulation of hazardous waste are posted with warning signs and drums are color coded for easy identification of waste categories.

"* Waste Inventory Forms are placed on waste accumulation drums or provided in the ac cumulation area for employees to record the waste type and amount when chemicals are added to the drum. This ensures that incompatible wastes are not mixed and also identi fies the drum contents for proper disposal.

Other Environmental Regulating Acts Comprehensive Environmental Response, Compensation and Liability Act The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA, or Superfund) established a federal authority and source of funding for responding to spills and other releases of hazardous materials, pollutants and contaminants into the environment. Super fund establishes "reportable quantities" for several hundred hazardous materials and regulates the cleanup of abandoned hazardous waste disposal sites.

Superfund Amendment and Reauthorization Act (SARA)

Superfund was amended in October 1986 to establish new reporting programs dealing with emergency preparedness and community right-to-know laws. As part of this program, CERCLA is enhanced by ensuring that the potential for release of hazardous substances is minimized, and that adequate and timely responses are made to protect surrounding populations.

Davis-Besse conducts site-wide inspections to identify and record all hazardous products and chemicals onsite as required by SARA. Determinations are made as to which products and chemicals are present in reportable quantities.

137

.1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Annual SARA reports are submitted to local fire departments and state and local planning com missions by March 1 for the preceding calendar year. One additional water treatment chemical product was identified for calendar year 2001.

Toxic Substances Control Act (TSCA)

The Toxic Substance Control Act (TSCA) was enacted to provide the USEPA with the authority to require testing of new chemical substances for potential health effects before they are intro duced into the environment, and to regulate them where necessary. This law would have little impact on utilities except for the fact that one family of chemicals, polychlorinated biphenyls (PCBs), has been singled out by TSCA. This has resulted in an extensive PCB management system, very similar to the hazardous waste management system established under RCRA.

In 1992, Davis-Besse completed an aggressive program that eliminated PCB transformers onsite.

PCB transformers were either changed out with non-PCB fluid transformers or retrofilled with non-PCB liquid.

Retro-filling PCB transformers involves flushing the PCB fluid out of a transformer, refilling it with PCB-leaching solvents and allowing the solvent to circulate in the transformer during op eration. The entire retro-fill process takes several years and will extract almost all of the PCB.

In all, Davis-Besse performed retro-filI activities on eleven PCB transformers between 1987 and 1992. The only remaining PCB containing equipment onsite are a limited number of capacitors.

These capacitors are being replaced and disposed of during scheduled maintenance activities.

Clean Air Act The Clean Air Act identifies substances that are considered air pollutants. Davis-Besse holds an OEPA permit to operate an Air Contaminant Source for the station Auxiliary Boiler. This boiler is used to heat the station and provide steam to plant systems when the reactor is not operating.

A report detailing the Auxiliary Boiler operation is submitted annually.

The Ohio EPA has granted an exemption from permitting our six emergency diesel engines, in cluding the Station Blackout Diesel Generator, the 2 Emergency Diesel Generators, the Emer gency Response Facility Diesel Generator, the Miscellaneous Diesel, and the Fire Pump Diesel.

These sources are operated infrequently to verify their reliability, and would only be used in the event of an emergency.

In response to recent "Clean Air Act Title V" legislation, an independent study identifying and quantifying all of the air pollution sources onsite was performed. Of particular significance is asbestos removal from renovation and demolition projects for which USEPA has outlined spe cific regulations concerning handling, removal, environmental protection, and disposal. Also, the Occupational Safety and Health Protection Administration (OSHA) strictly regulates asbestos with a concern for worker protection. Removal teams must meet medical surveillance, respirator fit tests, and training requirements prior to removing asbestos-containing material. Asbestos is not considered a hazardous waste by RCRA, but the EPA does require special handling and dis posal of this waste under the Clean Air Act.

138

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Transportation Safety Act The transportation of hazardous chemicals, including chemical waste, is regulated by the Trans portation Safety Act of 1976. These regulations are enforced by the United States Department of pack Transportation (DOT) and cover all aspects of transporting hazardous materials, including ing, handling, labeling, marking, and placarding. Before any wastes are transported off site, to DOT Davis-Besse must ensure that the wastes are identified, labeled and marked according and it is in good oper regulations, including verification that the vehicle has appropriate placards ating condition.

Other Environmental Programs Underground Storage Tanks According to RCRA, facilities with Underground Storage Tanks (USTs) are required to notify the State. This regulation was implemented in order to provided protection from tank contents leaking and causing damage to the environment. Additional standards require leak detection systems and performance standards for new tanks. At Davis-Besse two 40,000 gallon and one 8,000 gallon diesel fuel storage tanks are registered USTs.

Spill Kits Spill control equipment is maintained throughout the Station at chemical storage areas and haz ardous chemical and oil use areas. Equipment in the kits may include chemical-resistant cover alls, gloves, boots, decontamination agents, absorbent cloth, goggles and warning signs.

Waste Minimization and Recycling Municipal Solid Waste (MSW) is normal trash produced by individuals at home and by indus tries. In some communities, MSW is burned in specially designed incinerators to produce power or is separated into waste types (such as aluminum, glass, and paper) and recycled. The vast majority of MSW is sent to landfills for disposal. As the population increases and older landfills reach their capacity, MSW disposal becomes an important economic, health, and resource issue.

The State of Ohio has addressed the issue with the State Solid Waste Management Plan, other wise known as Ohio House Bill 592. The intent of the bill is to extend the life of existing land fills by reducing the amount of MSW produced, by reusing certain waste material, and by recy cling other wastes. This is frequently referred to as "Reduce, Reuse, and Recycle."

Davis-Besse has implemented and participated in company wide programs that emphasize the reduction, reuse, recycle approach to MSW management. An active Investment Recovery Pro gram has greatly contributed to the reduction of both hazardous and municipal waste generated by evaluating options for uses of surplus materials prior to the materials entering Davis-Besse's waste streams. Such programs include paper, cardboard, aluminum cans, used tires, and metals recycling or recovery. Paper and cardboard recycling is typically in excess of 50 tons annually.

This represents a large volume of recyclable resources, which would have otherwise been placed 139

1 Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report in a landfill. Aluminum soft drink cans are collected for the Boy Scouts of America to recycle.

Additionally, lead-acid batteries are recycled and tires are returned to the seller for proper dis posal.

Although scrap metal is not usually considered part of the MSW stream, Davis-Besse does col lect and recycle scrap metals, which are sold at current market price to a scrap dealer for resource recovery. These programs are continuously being expanded and reinforced as other components of MSW stream are targeted for reduction.

140

Environmental Operating Report Davis-Besse Nuclear Power Station 200 1 Annual Radiological APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2001 through December, 2001 141

II Davis-I3esse Nuzlear Power Station 2001 Annual R,,adiological hnvironrn'.utal Operating Report Anpendix A Inter'laboratory Cornparison Program Results Environmental, Inc., Midwest Laboratory, for'merly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.

This program was conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.

The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2.

Results of crosscheck testing with Teledyne Brown Engineering are also listed.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NqST traceable sources. Data for previous years available upon request.

Table A4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluatioh Program.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for "spiked" samples.

Out-of-limit results are explained directly below the result.

142

Davis-Besse Nuclear Power Station 200! AnnuaI Radiological EnvroymnentaI Operating RtpIrt 12-31-01 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES ANALYSES' LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/lHter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value 5 to 50 pCi/liter or kg 5.0 pCi/liter Strontium-89b

> 50 pCi/liter or kg 10% of known value 2 to 30 pCi/liter or kg 5.0 pCi/liter Strontium_90b

> 30 pCi/liter or kg 10% of known value

> 0.1 g/liter or kg 5% of known value Potassium-40 20 pCi/liter 5.0 pCi/liter Gross alpha

> 20 pCi/liter 25% of known value 100 pCi/liter 5.0 pCi/liter Gross beta

> 100 pCi/liter 5% of known value 4,000 pCi/liter is = (pCi/liter) =

Tritium 169.85 x (known)a9

> 4,000 pCi/liter 10% of known value 0.1 pCi/liter 15% of known value Radium-226,-228 0.1 pCi/liter, gram, or sample 10% of known value Plutonium 55 pCi/liter 6.0 pCi/liter Iodine-131,

>55 pCi/liter 10% of known valuge Iodine-129b 35 pCi/liter 6.0 pCi/liter Uranium-238, 1 G /liter 15% of known value Nickel-6Y ' r "-'

Technetium-99b 50 to 100 pCi/liter 10 pCi/liter Iron'55t > 100 pCi/liter 10% of known value Othersb 20% of known value From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

143

1

)avis~-Be;se Nuclear Power Statioi) 2 ()I Annual~Radiological Environmental Operating Report "Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.

Concentration in pCi/Lb Lab Sample Date Control Code Type Collected Analysis Laboratory result' ERA Resultd Limits STW-897 WATER Jan, 2001 Gr. Alpha 31.9+/-2.1 45.7 +/- 11.4 25.9 - 65.5 STW-897 WATER Jan, 2001 Gr. Beta 25.3 +/- 2.7 16.7 +/- 5.0 8.0- 25.4 STW-900 WATER Feb, 2001 1-131 27.2 +/-0.8 28.3 +/- 3.0 23.1 - 33.5 STW-902 WATER Feb, 2001 Ra-226 4.0 +/- 0.1 4.7 +/- 0.7 3.4 - 5.9 STW-902 WATER Feb, 2001 Ra-228 13.8 +/- 0.4 14.4 +/- 3.6 8.2- 20.6 STW-902 WATER Feb, 2001 Uranium 17.0 +/- 0.3 20.4 +/-3.0 15.2 - 25.6 STW-903 WATER Mar, 2001 H-3 17,400.0 +/-69.7 17,800.0+/-1,780.0 14,700.0 - 20,900.0 STW-917 WATER Apr, 2001 Gr. Alpha 57.4 +/-3.5 56.0 +/-14.0 31.8 - 80.2 STW-917 WATER Apr, 2001 Ra-226 13.5 +/-0.4 17.7+/-2.7 13.1 - 22.3 STW-917 WATER Apr, 2001 Ra-228 10.1 +/- 0.6 8.1 +/-2.0 4.6- 11.6 STW-917 WATER Apr, 2001 Uranium 14.2 - 0.2 15.6 +/- 3.0 10.4- 20.8 STW-918 WATER Apr, 2001 Co-60 27.9 +/- 1.4 26.4 +/- 5.0 17.7- 35.1 STW-918 WATER Apr, 2001 Cs-134 16.0 +/-0.4 16.9 +/-5.0 8.2- 25.6 STW-918 WATER Apr, 2001 Cs-137 195.4+/-1.5 186.0 +/- 9.3 170.0 - 202.0 STW-918 WATER Apr, 2001 Gr. Beta 340.0+/-51.0 343.0 +/-+_1.7 252.0- 428.0 STW-918 WATER Apr, 2001 Sr-89 62.8 +/-5.7 64.1+/-5.0 55.5 - 72.8 STW-918 WATER Apr, 2001 Sr-90 34.2 +/- 1.6 33.8 +/-5.0 25.1 - 42.5 STW-919 WATER Jun, 2001 Ba-133 37.8:+/- 1.2 36.0 +/-i5.0 27.3- 44.7 STW-919 WATER Jun, 2001 Co-60 49.9 +/-0.7 46.8 +/- 5.0 38.1 - 55.5 STW-919 WATER Jun, 2001 Cs-134 16.0:+/- 1.4 15.9 +/- 5.0 7.2 - 24.6 STW-919 WATER Jun, 2001 Cs-137 208.0 +/- 1.7 197.0 +/- 9.9 180.0 - 214.0 STW-919 WATER Jun, 2001 Zn-65 37.8 +/-0.7 36.2 +/- 5.0 27.5 - 44.9 STW-920 WATER Jun, 2001 Ra-226 14.6 +/- 0.4 15.4 +/- 2.3 11.4- 19.4 STW-920 WATER Jun, 2001 Ra-228 6.2 +/-i 0.2 4.5+/-1.1 2.6- 6.5 STW-920 WATER Jun, 2001 Uranium 49.0 +/- 1.0 55.7 __L5.6 46.1 - 65.3 STW-921 WATER Jul, 2001 Sr-89 19.8 +/- 1.5 31.2 +/- 5.0 22.5 - 39.9 Delay in processing may have attributed to deviation.

Result of reanalysis; Sr-89, 35.3 +/- 4.4 pCi/L. Sr-90, 25.0 +/- 2.8 pCi/L.

STW-921 WATER Jul, 2001 Sr-90 26.3:+/- 1.1 25.9 +/- 5.0 17.2- 34.6 STW-922 WATER Jul, 2001 Gr. Alpha 23.3+/-1.9 17.8+/-5.0 9.1 - 26.5 STW-922 WATER Jul, 2001 Gr. Beta 48.5+/-4.6 53.0 +/- 10.0 35.7- 70.3 STW-924 WATER Aug, 2001 H-3 2,680.0+/-41.9 2,730.0 +/- 356.0 2,110.0 - 3,350.0 STW-931 WATER Sep, 2001 Ra-226 10.9 +/-0.2 10.8+/- 1.6 8.0- 13.6 STW-931 WATER Sep, 2001 Ra-228 9.7+/-1.1 9.0 +/-2.2 5.1 - 12.8 STW-931 WATER Sep, 2001 Uranium 11.2 +/-0.1 13.1 +/- 3.0 7.9- 18.3 STW-932 WATER Oct, 2001 1-131 7.7 +/-0.3 7.7 +/-2.0 4.2- 11.2 STW-933 WATER Oct, 2001 Gr. Alpha 82.2+/-4.0 97.5 +/- 24.4 55.3 - 140.0 STW-933 WATER Oct, 2001 Ra-226 9.5+/-1.2 10.8 +/-_1.6 8.0- 13.6 144

D)avis-f.scM aRadiological Environimental Operating ReporT Nuciiar Power Statlion 2001 Annual Resource Associates (ERA)'.

Table A-1. Interlaboratory Comparison Crosscheck program, Environmental Concentration in pCi/IT Control Lab Sample Date Laboratory resultc ERA ResultW Limits Code Type Collected Analysis 17.0 +/- 0.8 15.6 t 3.9 8.9 - 22.4 STW-933 WATER Oct, 2001 Ra-228 32.2:+/--1.4 37.2 +/- 3.7 30.7 - 43.6 STW-933 WATER Oct, 2001 Uranium 82.4+/-0.9 78.4 +/-5.0 69.7- 87.1 STW-934 WATER Oct, 2001 Co-60 52.2 +/- 1.3 54.1 +/- 5.0 45.4 - 62.8 STW-934 WATER Oct, 2001 Cs-134 39.4+/-0.6 37.9 +/- 5.0 26.3 - 43.7 STW-934 WATER Oct, 2001 Cs-137 166.0 +/- 7.1 192.0 +/- 28.8 142.0 - 242.0 STW-934 WATER Oct, 2001 Gr. Beta 12.8+/-0.8 16.7 +/-5.0 8.0- 25.4 STW-934 WATER Oct, 2001 Sr-89 6.8+/-0.7 7.7-+/-5.0 -1.0- 16.4 STW-934 WATER Oct, 2001 Sr-90 63.5 +/- 2.5 64.0 +/- 16.0 36.5 - 91.5 STW-935 WATER Oct, 2001 Gr. Alpha 26.0 +/-1.2 21.5 +/- 5.0 12.8-30.2 STW-935 WATER Oct, 2001 Gr. Beta 66.7:+/- 1.2 69.3 +/-6.9 57.5- 81.1 STW-938 WATER Nov, 2001 Ba-133 59.3 +/- 0.6 59.7+/- 5.0 51.0- 68.4 STW-938 WATER Nov, 2001 Co-60 86.7+/- 1.5 93.9 --5.0 85.2- 103.0 STW-938 WATER Nov, 2001 Cs-134 45.0 +/- 1.0 42.0 +/- 5.0 33.3 - 50.7 STW-938 WATER Nov, 2001 Cs-137 80.7+/-0.6 77.3+/-7.7 63.9-90.7 STW-938 WATER Nov, 2001 Zn-65 as a participant in the environmental samples Results obtained by Environmental, Inc., Midwest Laboratory (ERA).

crosscheck program operated by Environmental Resources Associates b All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.

as the mean +/- standard deviation for three Unless otherwise indicated, the laboratory result is given determinations.

sigma, I determination)

"Results are presented as the known values, expected laboratory precision (1 and control limits as provided by ERA.

145

avis-Besse Nruclear Power Station 2001 Aiioal Radiologicai Fnvironmental Operating Report Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).

mR Lab Known Lab result Code TLD Type Date Measurement Value + 2 Sigma Control Limits Teledyne Brown Engineering Mar, 2000 Reader 1, #1 17.8 14.4 +/- 0.2 12.46 - 23.14 2000-1 LiF-100 Chips 35.5 32.4 +/- 0.1 24.85 - 46.15 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #2 62.2 61.8+/-0.9 43,54 - 80.86 2000-1 LiF-100 Chips Mar, 2000 Reader 1, #3 Teledyne Brown Engineering Reader 1, #1 17.8 21.3 +/-0.3 12.46 - 23.14 2000-2 CaSO4 : Dy Cards Mar, 2000 35.5 40.1 +/- 1.9 24.85 - 46.15 2000-2 CaSO4: Dy Cards Mar, 2000 Reader 1, #2 62.2 69.9 +/-3.5 43.54 - 80.86 2000-2 CaSO4 : Dy Cards Mar, 2000 Reader 1, #3 Westwood, New Jersey, in March of 2000.

Chips and cards irradiated by Teledyne Brown Engineering, 12th International Intercomparison 022-1 CaSO,: Dy Cards Jun, 2000 Field 161.0 184.9 +/- 1.9 112.70 - 209.30 Field 1 548.0 502.2 +/- 1.7 383.60 - 712.40 022-1 CaSO,: Dy Cards Jun, 2000 Field 2 391.0 412.0 +/- 2.9 273.70 - 508.30 022-1 CaSO 4: Dy Cards Jun, 2000 Field 3 623.0 643.2+/- 2.9 436.10 - 809.90 022-1 CaSO4 : Dy Cards Jun, 2000 Lab, 1 391.0 442.8 . 2.5 273.70 - 508.30 022-1 CaSO4 : Dy Cards Jun, 2000 Environmental, Inc.

2001-1 CaSO,: Dy Cards Dec, 2001 Reader 1, #1 4.0 3.7 + 0.1 2.79 - 5.17 Reader 1, #1 4.0 3.4+/- 0.1 2.79 - 5.17 2001-1 CaSO: Dy Cards Dec, 2001 Reader 1, #2 7.1 7.9 +0.2 4.95 9.19 2001-1 CaSO,: Dy Cards Dec, 2001 Reader 1, #2 7.1 7.6+/-0.3 4.95 - 9.19 2001-1 CaSO4 : Dy Cards Dec, 2001 Reader 1, #3 15.9 18.6 +/- 0.4 11.13 - 20.67 2001-1 CaSO4 : Dy Cards Dec, 2001 Reader 1, #3 15.9 19.6 +/- 0.1 11.13 - 20.67 2001-1 CaSO4 : Dy Cards Dec, 2001 63.6 78.2 - 1.2 44.53 - 82.69 2001-1 CaSO 4 : Dy Cards Dec, 2001 Reader 1, #4 63.6 79.9 t 2.5 44.53 - 82.69 2001-1 CaSO,: Dy Cards Dec, 2001 Reader 1, #4 146

Davis-Besse Nutchar Pow;,r Slzt:ion 2001 Annual lnvironrnenltal Operalting Report adiolonica! E, "Table A-3. In-house "spike'" samples.

Concentration in pCi/!L Lab Sample Date Laboratory results Known ControiF Code Type Collected Analysis 2s, n=1b Activity Limits SPAP-477 Air Filter Jan, 2001 Cs-137 1.76 +/-0.02 1.68 1.01 - 2.35 54702.00 - 644.00 54549.00 43639.20 - 65458.80 SPW-479 Water Jan, 2001 H-3 58.08 +/- 2.79 69.14 34.57 - 103.71 SPW-481 Water Jan, 2001 Gr. Alpha 213.83 - 3.07 220.26 198.23 - 242.29 SPW-481 Water Jan, 2001 Gr. Beta 51.77+/- 2.18 69.14 34.57 - 103.71 SPW-482 Water Jan, 2001 Gr. Alpha 202.48 +/- 2.98 220.26 198.23 - 242.29 SPW-482 Water Jan, 2001 Gr. Beta 20.11 +/- 0.34 20.86 14.60 - 27.12 SPW-483 Water Jan, 2001 Ra-226 10.55 +/- 2.02 19.43 13.60 - 25.26 SPW-483 Water Jan, 2001 Ra-228 Sample wa. lost during analysis.

33.53 +/- 3.40 31.13 21.13 - 41.13 SPW-485 Water Jan, 2001 Co-60 32.80 +/- 2.54 30.81 20.81 - 40.81 SPW-485 Water Jan, 2001 Cs-134 42.10 +/-5.60 36.00 26.00 - 46.00 SPW-485 Water Jan, 2001 Cs-137 154.34 +/- 3.49 137.66 110.13 - 165.19 SPW-485 Water Jan, 2001 Sr-90 8.53 +/- 0.02 7.88 -2.12 - 17.88 SPAP-754 Air Filter Jan, 2001 Gr. Beta 3.74+/-0.10 .4.17 2.50- 5.84 SPW-1037 Water Feb, 2001 U-233/4 3.81 +/- 0.10 4.17 -7.83 - 16.17 SPW-1037 Water Feb, 2001 U-238 21.25 +/- 0.50 20.68 14.48 - 26.88 SPW-1224 Water Feb, 2001 Ra-226 21.76 +/- 2.65 19.27 13.49 - 25.05 SPW-1224 Water Feb, 2001 Ra-228 71.87+/-3.07 69.14 34.57 - 103.71 SPW-1225 Water Feb, 2001 Gr. Alpha 36.30 +/- 1.47 28.75 18.75 - 38.75 SPW-1225 Water Feb, 2001 Gr. Beta 56.82 +/- 0.71 63.05 50.44 - 75.66 SPW-1272 Water Feb, 2001 1-131 65.69 +/- 10.21 63.05 53.05 - 73.05 SPW-1272 Water Feb, 2001 1-131(g) 0.78 +/- 0.05 0.76 0.45 -'1.06 SPVE-1274 Vegetation Feb, 2001 1-131(g) 1.57 +/-0.05 1.58 0:95 - 2.21 SPCH-1276 Charcoal Feb,2001 1-131(g) 31.89 +/-4.71 29.77 19.77 - 39.77 SPMI-1270 Milk Mar, 2001 Cs-134 46.61 +/- 8.81 35.90 25.90 - 45.90 SPMI-1270 Milk Mar, 2001 Cs-137 been prepared.

The Cs-13j7spike is sus*pect; A new cesium spike has 81.92+/- 10.80 81.95 71.95 - 91.95 SPMI-1270 Milk Mar, 2001 1-131(g) 51512.00 +/- 1369.00 50189.00 40151.20 - 60226.80 SPU-2901 Urine Mar, 2001 H-3 29.92+/-5.13 31.75 22.23 - 41.28 SPW-2161 Water Mar, 2001 Ra-228 2065.00 +/- 408.00 2008.00 1317.37 - 2698.63 SPU-3128 Urine Apr, 2001 H-3 37.94 +/- 2.42 34.57 17.29 - 51.86 SPW-3129 Water Apr, 2001 Gr. Alpha 147

l)avis esse Nuclear Power Stai.on 200. Annual Radiiological Environmental Operating Report Table A-3. In-house "spike" samples.

Concentration in pCi/LU Lab Sample Date Laboratory results ncown .ontroi Code Type Collected Analysis 2 s, n=lb Activity Limits SPW-3129 Water Apr, 2001 Gr. Beta 117.83 +/- 2.37 109.46 98.51 - 120.41 Apr, 2001 Gr. Beta 0.80 +/- 0,01 0.78 -9.22 - 10.78 SPAP-3508 Air Filter Milk Apr, 2001 Cs-134 32.69 +/- 6.50 33.96 23.96 - 43.96 SPMI-3232 Milk Apr, 2001 Cs-137 44.20 +/- 9.08 35.79 25.79 - 45.79 SPMI-3232 Milk Apr, 2001 1-131 48.05 +/- 0.90 56.68 45.34 - 68.02 SPMI-3232 Milk Apr, 2001 1-131(g) 55.64 +/- 11.39 56.68 46.68 - 66.68 SPMI-3232 Milk Apr, 2001 Sr-90 143.77 +/- 3.04 136.82 109.46 - 164.18 SPMI-3232 SPSO-3356 Soil Apr, 2001 Co-60 18.49 +/- 0.21 19.57 9.57- 29.57 SPSO-3356 Soil Apr, 2001 Cs-137 18.71 +/- 0.24 16.61 6.61 - 26.61 Air Filter Apr, 2001 Cs-137 1.80 +/- 0.01 1.67 1.00 - 2.34 SPAP-3359 Water Apr, 2001 Co-60 48.17 +/- 4.85 45.19 35.19 - 55.19 SPW-3376 Water Apr, 2001 Cs-134 37.14 +/- 3.90 33.96 23.96 - 43.96 SPW-3376 SPW-3376 Water Apr, 2001 Sr-90 159.84 +/- 3.42 136.82 109.46 - 164.18 Water Apr, 2001 1-131 68.60 +/- 2.63 85.02 68,02 - 102.02 SPW-3377 SPW-3129/1 Water May, 2001 Gr. Alpha 37.94 +/- 2.42 34.57 17.29 - 51.86 Water May, 2001 Gr. Beta 117.83 t 2.37 109.46 98.51 - 120.41 SPW-3129/1 Water Jun, 2001 Cr. Alpha 34.42 +/- 2.14 34.57 17.29 - 51.86 SPW-3129/2 SPW-3129/2 Water Jun, 2001 Gr. Beta 119.99 +/- 2.45 109.46 98,51 - 120.41 Vegetation Jun, 2001 1-131(g) 0.81 +/- 0.03 0.86 0.51- 1.20 SPVE-3303 Soil Jul, 2001 Co-60 17.42+/-0,19 19.05 9.05 - 29.05 SPSO-5701 SPSO-5701 Soil Jul, 2001 Cs-137 16.03 +/- 0.22 16.52 6.52- 26.52 Water Jul, 2001 Co-60 250.05 +/- 18.63 233.26 209.93 - 256.59 SPW-5779 Water Jul, 2001 Cs-137 178.68 +/-19.89 175.91 158.32 - 193.50 SPW-5779.

Water Jul, 2001 Sr-90 72.12 +/- 2.24 68.12 54.50 - 81.74 SPW-5779 Fish Jul, 2001 Co-60 1.87 +/- 0,08 1.79 1.07- 2.51 SPF-5781 Fish Jul, 2001 Cs-137 1.43 +/- 0.07 1.39 0.83- 1.95 SPF-5781 Water Jul, 2001 H-3 51177.00 +/- 631.00 50189.00 40151.20 - 60226.80 SPW-5937 Water Jul, 2001 Ra-226 36.62 +/- 1.74 34.46 24.12 - 44.80 SPW-59441 Water Jul, 2001 Ra-228 41.46 +/- 6.44 36.06 25.24 - 46.88 SPW-59441 Air Filter Jul, 2001 Cs-137 1.81 +/- 0.02 1.67 1.00- 2.34 SPAP-5703 Water Jul, 2001 Gr. Alpha 35.31 +/- 3.04 34.75 17.38 - 52.13 SPW-3129/3 148

Davis-Btssc NunlInr Power Station 2001 Annual Radiological Environmental Operating Report Table A-3. In-house "spike" samples.

Concentration in pCi/La Lab Sample Date Laboratory results Known Control:

Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3129/3 Water Jul, 2001 Gr. Beta 113.28 +/-3.65 109.46 98.51 - 120.41 SPMI-6145 Milk Jul, 2001 Cs-137 188.45 +/- 19.10 175.91 158.32 - 193.50 SPW-6604 Water Jul, 2001 Gr. Alpha 35.36 +/- 1.94 34.57 17.29 - 51.86 SPW-6604 Water Jul, 2001 Gr. Beta 112.56 +/- 2.46 108.82 97.94 - 119.70 SPW-9008 Water Oct, 2001 H-3 48285.00:+/- 606.10 50189.00 40151.20 - 60226.80 SPAP-9010 Air Filter Oct, 2001 Cs-137 1.91 +/- 0.01 1.67 1.00 - 2.34 SPW-10723 Water Dec, 2001 U-233/4 40.12 +/- 1.09 41.73 25.04 - 58.42 SPW-10723 Water Dec, 2001 U-238 40.16:+/- 1.09 41.73 29.21 - 54.25 SPAP-I1550 Air Filter Dec, 2001 Gr. Beta 1.58 +/- 0.02 1.56 -8.44 - 11.56 SPW-11757 Water Dec, 2001 Co-60 43.82 +/-3.14 41.36 31.36 - 51.36 SPW-11757 Water Dec, 2001 Cs-134 24.11+/-2.42 22.59 12.59- 32.59 SPW-11757 Water Dec, 2001 Cs-137 5211+/-4.40 50.89 40.89 - 60.89 SPMI-11759 Milk Dec, 2001 Cs-134 28.03 +/- 2.64 27.10 17.10 - 37.10 SPMI-11759 Milk Dec, 2001 Cs-137 54.59 +/- 5.08 50.89 40.89 - 60.89 SPF-11761 Fish Dec, 2001 Cs-134 0.94 +/- 0.02 0.90 0.54 - 1.26 SPF-11761 Fish Dec, 2001 Cs-137 1.43:+/- 0.04 1.43 0.86- 2.00 results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, SAll which are in pCi/Filter; and food products, which are in pCi/kg.

bResults are based on single determinations.

SControl limits are based on Attachment A, Page A2 of this report.

NOTE: For fish, Jello is used for the spike matrix. For vegetation, coleslaw is used for the spike matrix.

149

J)avis-Besse Nuclear Power Station 2001 Annual Radiological Environmenfal Operating Report Table A-4. In-house "blank" samples.

Concentration pCi/Lt.

Laboratory results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)

SPAP-478 AIR FILTER Jan 2001 Co-60 < 1.12 < 100.0 SPAP-478 AIR FILTER Jan 2001 Cs-134 < 1.66 < 100.0 SPAP-478 AIR FILTER Jan 2001 Cs-137

• 2.46 < 100.0 SPW-486 WATER Jan 2001 H-3 < 162.00 -1.86 +/- 80.40 < 200.0 SPW-484 WATER Jan 2001 Gr. Alpha < 0.68 < 1t0 SPW-484 WATER Jan 2001 Gr. Beta < 1.35 < 3.2 SPW-484 WATER Jan 2001 Ra-226 < 0.02 0.03 +/-0. 01 < 1.0 SPW-484 WATER Jan 2001 Ra-228 < 0.97 0.43 +/- 0.50 < 2.0 SPW-486 WATER Jan 2001 Co-60 < 2.68 < 10.0 SPW-486 WATER Jan 2001 Cs-134 < 3.46 < 10.0 SPW-486 WATER Jan 2001 Cs-137 < 5.43 < 10.0 SPW-486 WATER Jan 2001 Sr-90 < 0.65 0.06 +/- 0.31 < 1.0 SPAP-755 AIR FILTER Jan 2001 Gr. Beta < 1.60 0.16 +/-t0.90 <3.2 SPW-1038 WATER Feb 2001 U-238 < 0.03 < 1.0 SPW-1038 WATER Feb 2001 U-238 < 0.00 < 1.0 SPW-1223 WATER Feb 2001 Gr. Alpha < 0.46 < 1.0 SPW-1223 WATER Feb 2001 Gr. Beta < 1.50 < 3.2 SPW-1223 WATER Feb 2001 Ra-226 < 0.02 0,03 +/- 0.01 < 1.0 SPW-1223 WATER Feb 2001 Ra-228 < 0.95 0.45 +/- 0.49 < 2.0 SPMI-1268 MILK Feb 2001 Cs-134 < 5.86 < 10.0 SPMI-1268 MILK Feb 2001 Cs-137 < 3.02 < 10.0 SPMI-1268 MILK Feb 2001 1-131(g) < 7.46 < 20.0 SPW-1271 WATER Feb 2001 Co-60 < 1.06 <10.6 SPW-1271 WATER Feb 2001 Cs-134 < 2.61 < 10.0 SPW-1271 WATER Feb 2001 Cs-137 < 2.37 < 10.0 SPVE-1273 VEGETATION Feb 2001 Cs-134 < 10.04 < 100.0 SPVE-1273 VEGETATION Feb 2001 Cs-137 < 6.00 < 100.0 SPCH-1275 CHARCOAL Feb 2001 1-131(g) < 0.01 < 9.6 CANISTER SPW-2164 WATER Mar 2001 Ra-226 < 0.02 0.05 +/- 0.01 <1.0 SPU-3126 URINE Apr 2001 H-3 < 642.00 -66.00 ÷335.00 < 200.0 2.0 ml. sample volume.

150

DavIs*l~es-se N*u.clear Power Station 2001 Annal Kadiogical Environental Operating Report "Table A-4. In-house "blank" samples.

Concentration pCi/L[.

Laboratory results Acceptance Lab Sample Sample k' (4.66 Sigma)

Date An alvsis LLD Activityb Code Type Gr. Alpha < 0.54 0.04 :t 0.38 < 1.0 SPDW-3130 VVATER Aptr 2001 Gr. Beta < 1.46 0.67 +/- 1.04 < 3.2 SPDW-3130 V*ATER Apr 2001 Cs-137 < 2.66 < 10.0 SPMI-3233 MILK Apr 2001 Apr 2001 1-131 < 0.26 -0.06 -0.14 <0.5 SPMI-3233 MILK

< 3.91 < 20.0 SPMI-3233 MILK Apr 2001 1-131(g)

Apr 2001 Sr-89 < 0.79 -0.32 +/-_0.79 < 5.0 SPMI-3233 MILK Sr-90 1.18 +/- 0.35 < 1.0 SPMI-3233 MILK Apr 2001 not unusual.

Low level of Sr-90 concentration in milk (1-5 pCi/L) is SOIL Apr 2001 Cs-t 34 < 14.77 < 100.0 SPSO-3357 Cs-137 < 11.72 < 100.0 SPSO-3357 SOIL Apr 2001

< 0.55 < 100.0 SPAP-3358 Al R FILTER Apr 2001 Cs-137

< 2.90 < 10.0 SPW-3375 NATER Apr 2001 Co-60

< 3.71 < 10.0 SPW-3375 WATER Apr 2001 Cs-134

< 0.39 < 20.0 SPW-3375 WATER Apr 2001 1-131(g) 0.02 +/- 0.22 0.05 +/- 0.27 <1.0 SPW-3375 WATER Apr 2001 Sr-90 < 0.56

< 0.45 0.15 +/- 0.34 <1.0 SPDW-3130 WATER May 2001 Gr. Alpha 0.34 +/- 0.95 <3.2 SPDW-3130 WATER May 2001 Gr. Beta < 1.26

< 0.44 0.09 +/- 0.32 < 1.0 SPDW-3130 WATER Jun 2001 Gr. Alpha 0.66 +/- 1.04 <3.2 SPDW-3130 WATER Jun2001 Gr. Beta < 1.46

<1 00.0 SPVE-3304 VEGETATION Jun 2001 Co-60 < 7.06

< 11.56 < 100.0 SPVE-3304 VE GETATION Jun 2001 Cs-134

< 8.30 < 100.0 SPVE-3304 VE GETATION Jun 2001 Cs-137

< 12.80 < I00.0 SPSO-5702 SOIL Jul 2001 Co-60

< 100.0 SPSO-5702 SOIL Jul2001 Cs-134 < 13.96

< 100.0 SPSO-5702 SOIL Jul 2001 Cs-137 < 8.10

< 100.0

. FILTER dR Jul 2001 Co-60 < 0.79 SPAP-5704

< 0.84 < 100.0 SPAP-5704 PJR FILTER Jul2001 Cs-134

< 100.0 UR FILTER Jul 2001 Cs-137 < 0.60 SPAP-5704

< 1.86 < 10.0 SPW-5780 WATER Jul 2001 Co-60

< 10.0 SPW-5780 WATER Jul 2001 Cs-134 < 2.46

< 10.0 WATER Jul 2001 Cs-137 < 3.77 SPW-5780 151

Davis-Bessc Nuc Lucr Power Station 2001 Anntual Radiological Fnviror..'nntal Opm-atiTg Rcport Table A-4. In-house "blank" samples.

Concentration pCi/L".

Laboratory results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD ActivityV (4.66 Sigma)

SPF-5782 FISH Jul2001 Co-60 < 5.64 < 100.0 SPF-5782 FISH Jul2001 Cs-134 < 7.51 < 100.0 SPW-5938 WATER Jul 2001 H-3 < 163.22 -16.21 t 85.07 < 200.0 SPW-59451 WATER Jul 2001 Ra-226 < 0.01 0.04 +/- 0.01 < 1.0 SPW-59451 WATER Jul 2001 Ra-228 < 0.77 0.70 +/- 0.44 < 2.0 SPDW-3130 WATER Jul2001 Gr. Alpha < 0.54 0.36 +/- 0.40 < 1.0 SPDW-3130 WATER Jul.2001 Gr. Beta < 2.27 -0.78 _i+/-1.35 < 3.2 SPMI-6146 MILK Jul2001 Sr-90 < 0.50 1.09 +/- 0.36 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-6605 WATER Jul2001 Gr. Beta < 1.34 0.55 _+/-1.01 < 3.2 SPW-9009 WATER Oct 2001 H-3 < 160.00 -56.70 +/- 76.50 < 200.0 SPAP-9011 AIR FILTER Oct 2001 Co-60 < 0.76 < 100.0 SPAP-9011 AIR FILTER Oct 2001 Cs-137 < 0.58 < 100.0 SPW-5780 WATER Oct 2001 St-90 < 0.54 0.36 +/- 0.30 < 1.0 SPW-10724 WATER Dec 2001 U-238 < 0.13 0.04 +/- 0.10 < 1.0 SPAP-11549 AIR FILTER Dec 2001 Gr. Beta < 0.00 0.01 +/- 0.00 <3.2 SPW-11756 WATER Dec 2001 Cs-137 < 2.62 < 10.0 SPMI-11758 MILK Dec 2001 Cs-137 < 4.00 < 10.0 SPMI-11758 MILK Dec 2001 1-131(g) < 16.57 < 20.0 SPF-11760 FISH Dec 2001 Cs-137 < 7.96 < 100.0 a Liquid sample results are reported in pCi/Liter, air filter sample results are in pCi/filter, charcoal sample results are in pCi/charcoal, and solid sample results are in pCi/kilogram.

b The activity reported is the net activity result.

152

Davis-Besse Ntcicar Powe'r S3,ation 2001 Annual Radiological Environrental Operating Report Table A-5. In-house "duplicate" samples.

Concentration in pCi/LU Lab Sample First Second Averaged Result Result Result Codes Date Analysis Be-7 0.06 +/-+0.02 0.06 +/- 0.02 0.06 +/- 0.01 AP-10675, 10676 Jan, 2001 Be-7 0.04:+/- 0.01 0.04 +/- 0.01 0.04 +/- 0.01 AP-10803, 10804 Jan, 2001 Be-7 0.04 +/- 0.01 0.04 +/- 0.01 0.04 +/- 0.01 AP-10833, 10834 Jan, 2001 H-3 362.60 +/- 94.70 417.20 +/- 96.80 389.90 +/- 67.71 WW-51, 52 Jan, 2001 K-40 1,566.90 +/- 196.80 1,372.40 +/- 152.50 1,469.65 +/- 124.49 M1-72, 73 Jan, 2001 K-40 1,418.30 :+/- 117.80 1,545.70 +/- 162.50 1,482.00 +/- 100.35 MI-96, 97 Jan, 2001 Gr. Beta 2.17 +/- 2.47 4.23 +/- 2.74 3.20 +/- 1.84 U-858, 859 Jan, 2001 K-40 1,489.20 +/- 141.10 1,463.30 +/- 168.20 1,476.25 +/- 109.77 M1-389, 390 Jan, 2001 Gr. Beta 2.63 +/- 0.52 2.37 +/- 0.50 2.50 +/- 0.36 DW-879, 880 Jan, 2001 2.48 + 0.58 2.46 t 0.63 2.47 +/- 0.43 SWU-813, 814 Jan, 2001 Gr. Beta K-40 1,179.40 +/- 103.00 1,280.40 +/- 90.26 1,229.90 +/-68.48 141-708, 709 Feb, 2001 1-131 0.01 +/- 0.26 -0.12 +/- 0.26 -0.05 +/- 0.18 MI-740, 741 Feb, 2001 K-40 1,434.00 +/- 156.50 1,435.00 +/- 126.10 1,434.50 +/- 100.49 MI-740, 741 Feb, 2001 K-40 1,584.30 +/- 158.80 1,390.70 +/- 136.50 1,487.50 +/- 104.70 MI4-789, 790 Feb, 2001 Gr. Beta 4.67 +/- 1.08 5.54 +/- 1.13 5.11 +/-0.78 DW-901, 902 Feb, 2001 3.13 +/- 0.63 2.33 +/- 0.52 2.73 +/- 0.41 SWU-1544, 1545 Feb, 2001 Gr. Beta 2.05 +/-0.92 2.34 +/- 0.93 2.20 +/- 0.65 DW-1426, 1427 Feb, 2001 Gr. Beta H-3 42.60 +/- 94.23 131.31 +/- 95.34 86.96 +/- 67.02 DW-1426, 1427 Feb, 2001 H-3 53.06 +/- 65.79 53.06 +/- 93.03 53.06 +/- 56.97 WW%-1476, 1477 Feb, 2001 1-131 -0.01 +/- 0.20 -0.10 +/-0.37 -0.06 +/- 0.21 M1-1523, 1524 Mar, 2001 K-40 1,396.00 +/- 184.80 1,576.00 +/- 184.90 1,486.00 +/- 130.71 M1-1523, 1524 Mar, 2001 K-40 1,499.20 +/- 113.30 1,326.00 +/- 118.80 1,412.60 +/- 82.08 N,1-1572, 1573 Mar, 2001 Sr-90 1.65:+/- 0.44 1.51 +/-0.52 1.58+/- 0.34 MI-1572, 1573 Mar, 2001 K-40 297.80 +/- 67.20 344.80 +/- 82.30 321.30 +/- 53.13 SW-1648, 1649 Mar, 2001 K-40 1,425.80 +/- 183.30 1,372.20 +/- 119.70 1,399.00 +/- 109.46 MI-1800, 1801 Mar, 2001 2.22 +/- 0.73 2.14 +/- 0.69 2.18 +/- 0.50 SW-1779, 1780 Mar, 2001 Gr. Alpha 6.28 +/- 0.74 6.62 +/- 0.70 6.45 +/- 0.51 SW-1779, 1780 Mar, 2001 Gr. Beta 1-131 -0.65 +/- 0.27 0.13 +/- 0.55 -0.26 +/- 0.31 MI-1447, 1448 Mar, 2001 1,413.40 +/- 169.60 1,454.80 +/- 115.01 NU1-1447,1448 Mar, 2001 K-40 1,496.20 +/- 155.40 H-3 540.04 +/--111.84 500.85 +/- 110.46 520.44 +/- 78.59 WW-2115, 2116 Mar, 2001 Gr. Beta 6.07 +/- 1.75 5.57 +/- 1.85 5.82 +/- 1.27 SW-1698, 1699 Mar, 2001 Gr. Beta 2.10 +/-:0.86 1.63 +/-0.83 1.87 +/- 0.60 DW-2272, 2273 Mar, 2001 1.22 +/- 0.50 1.32 +/- 0.47 1.27 +/- 0.35 WWr-2356, 2357 Mar, 2001 Gr. Beta Be-7 0.07 +/- 0.02 0.05 +/- 0.01 0.06 - 0.01 AP-2812, 2813 Mar, 2001 0.07 +/- 0.02 0.05 +/- 0.01 0.06 +/- 0.01 AP-2812, 2813 Mar, 2001 Be-7 Gr. Beta 1.85 +/- 0.51 2.23 +/- 0.55 2.04 +/- 0.37 LW-2217, 2218 Mar, 2001 153

D1avis-Bessc Nuclear Power Station 2001 Animal R'adiological Environmental Operating Report Table A-5. In-house "duplicate"' samples.

Concentration in pCiiLa Lab Sample First Second Averaged Codes Date Analvsis Result Result Result AP-2833, 2834 Mar, 2001 Be-7 0.04 +/- 0.01 0.06 +/- 0.02 0.05 +/- 0.01 AP-3038, 3039 Mar, 2001 Be-7 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 AP-3038, 3039 Mar, 2001 Be-7 0.06 +/- 002 0.07 +/- 0.01 0.07 +/- 0.01 DW-2398, 2399 Mar, 2001 Gr. Beta 1.58 +/- 0.89 1.81 +/- 0.88 1.69 +/- 0.63 LW-2467, 2468 Mar, 2001 Gr. Beta 2.52 +/- 0.53 2.42 +/- 0.53 2.47 +/- 0.37 MI-2446, 2447 Apr, 2001 K-40 1,285.40 +/-177.10 1,376.00 175.90

+/-+ 1,330.70 +/- 124.81 AP-3017, 3018 Apr, 2001 Be-7 0.05 ! 0.01 0.05 +/- 0.01 0.05 +/- 0.00 SW-2423, 2424 Apr, 2001 K-40 255.60 +/- 59.80 268.40 +/- 65.40 262.00 +/- 44.31 BS-3103, 3104 Apr, 2001 Gr. Beta 7.99 +/- 1.80 8.17+/-1.73 8.08+/- 1.25 SWU-3239, 3240 Apr, 2001 Gr. Beta 3.30 +/- 0.60 4.30 +/- 0.74 3.80 +/- 0.48 SS-3322, 3323 Apr, 2001 K-40 15.99 +/- 1.08 15.59 +/- 1.01 15.79 +/- 0.74 W-3990, 3991 Apr, 2001 Sr-89 91.35 +/-18.94 85.29 +/- 23.99 88.32+/- 15.28 BS-4347, 4348 Apr, 2001 K-40 3,982.40 +/- 489.60 3,255.80 +/- 450.10 3,619.10 +/- 332.53 BS-4347, 4348 Apr, 2001 K-40 3.26 +/- 0.45 3.98 +/- 0.49 3.62 +/- 0.33 MI-3364, 3365 May, 2001 K-40 1,325.90 +/- 160.20 1,453.20 +/- 163.00 1,389.55 +/- 114.27 SO-3385, 3386 May, 2001 Gr. Alpha 6.51 +/-3.09 9.01 +/- 3.44 7.76 +/- 2.31 SO-3385, 3386 May, 2001 Gr. Beta 24.63+/-3.15 28.17 +/- 3.12 26.40 +/- 2.22 SO-3385, 3386 May, 2001 K-40 19.17 +/- 1.08 17.94 +/- 0.76 18.56 +/- 0.66 CL-4068, 4069 May, 2001 K-40 1.09 +/- 0.27 1.13 +/- 0.23 1.11 +/-0.18 MI-3475, 3476 May, 2001 Gr. Beta 1,297.10+/-114.60 1,433.60 +/- 156.60 1,365.35 +/- 97.03 Vv'XV-3545, 3546 May, 2001 Gr. Beta 1.57 +/- 0.55 1.36 +/- 0.53 1.47 +/- 0.38 MI-3681, 3682 May, 2001 K-40 1,417.20 +/- 125.70 1,496.20 +/- 124.50 1,456.70 +/- 88.46 SIW-3702, 3703 May, 2001 Gr. Alpha 4.51 +/- 1.66 3.22 +/- 1.55 3.87 +/- 1.13 SW-3702, 3703 May, 2001 Gr. Beta 8.74 +/- 1.36 7.11 +/- 1.38 7.93 +/- 0.97 BS-4021, 4022 May, 2001 Cs-137 224.30 +/- 30.20 205.90 +/- 43.00 215.10 +/- 26.27 BS-4021, 4022 May, 2001 H-3 842.00 +/-47.00 860.00 +/- 48.00 851.00 +/- 83.59 BS-4021, 4022 May, 2001 K-40 21,117.00 +/-953.00 21,629.00 +/- 1,357.00 21,373.00 +/- 829.10 BS-4021, 4022 May, 2001 Pu-238 80.30 +/- 36.50 59.50 +/- 22.00 69.90 +/- 21.31 BS-4021, 4022 May, 2001 Pu-239/40 49.40 +/- 31.80 41.10 +/- 19.60 45.25 +/- 18.68 BS-4021, 4022 May, 2001 Ra-226 7,436.00 +/- 577.90 9,126.00 +/- 751.90 8,281.00 +/- 474.16 BS-4021, 4022 May, 2001 Sr-90 10.60 +/- 2.71 16.80 +/- 3.22 13.70 +/- 2.10 F-3813, 3814 May, 2001 K-40 2.10+/-0.17 2.30 +/- 0.26 2.20.+/- 0.16 G-4158, 4159 May, 2001 Be-7 0.37 +/- 0.13 0.41 +/- 0.14 0.39 +/- 0.10 SO-4179, 4180 May, 2001 Ac-228 0.45 +/- 0.13 0.52 +/- 0.14 0.49 +/-+-0.10 SO-4179, 4180 May, 2001 Bi-214 0.31 +/- 0.06 0.41 +/- 0.06 0.36 +/-0.04 SO-4179, 4180 May, 2001 Cs-137 0.46 +/- 0.05 0.47 +/-0.04 0.47 +/- 0.03 154

Davis.-Bi3ý,wS Ntcleair Power Station 2001 Annual Ra1diological IEnvironmcntal Operating Reporl Table A-5. In-house "duplicate" samples.

Concentration in pCi/L" Lab Sample First Second Averaged Codes Date Analvsis Result Result Result SO-4179, 4180 May, 2001 Gr. Beta 26.65 +/- 2.63 24.68 +/- 2.52 25.67 _ 1.82 SO-4179, 4180 May, 2001 K-40 16.35 +/--0.86 16.05 +/- 0.82 16.20 +/- 0.59 SO-4179, 4180 May, 2001 Pb-212 0.35 +/- 0.04 0.43 +/- 0.05 0.39 - 0.03 SO-4179, 4180 May, 2001 Ra-226 0.56 +/- 0.98 1.03 +/- 0.31 0.79 t 0.51 SO-4179, 4180 May, 2001 T1-208 0.14 +/- 0.03 0.17 +/- 0.03 0.15 --t 0.02 BS-423.3, 4234 May, 2001 Cs-137 0.03 +/- 0.01 0.03 +/- 0.02 0.03 - 0.01 BS-4233, 4234 May, 2001 K-40 8.18 +/-0.48 7.80 +/- 0.58 7.99 -0.38 SWU-4376, 4377 May, 2001 Gr. Beta 2.58 +/- 0.55 2.94 +/- 0.58 2.76+/-0.40 DW-4449, 4450 May, 2001 Gr. Beta 2.83 +/- 0.55 3.74 +/- 0.65 3.29 +/- 0,43 DW-4397, 4398 May, 2001 Gr. Beta 9.13 +/- 1.26 10.20 +/- 1.34 9.66 +/- 0.92 MI-4114, 4115 May, 2001 K-40 1,325.90 +/- 118.80 1,394.70 +/- 133.10 1,360.30 +/- 89.20 F-4284, 4285 May, 2001 K-40 2.23 +/- 0.32 2.12 +/- 0.35 2.18 _t 0.24 DW-4326, 4327 Jun, 2001 Gr. Beta 2.60 +/- 0.97 1.47 +/- 0.83 2.04 +/- 0.64 MI-4470, 4471 Jun, 2001 K-40 1,514.50 +/- 116.60 1,456.80 +/- 130.90 1,485.65 +/-87.65 SW-4493, 4494 Jun, 2001 Gr. Beta 4.05 +/- 1.23 4.64

• 1.32 4.35 +/- 0.90 BS-4725, 4726 Jun, 2001 Co-60 112.00 +/- 24.30 84.50 +/- 8.70 98.25 +/- 12.91 BS-4725, 4726 Jun, 2001 Cs-137 3,083.10 +/- 100.10 3,094.80 +/- 35.30 3,088.95 +/- 53.07 BS-4725, 4726 Jun, 2001 K-40 8,143.70 +/- 640.40 8,083.80 +/- 225.10 8,113.75 +/- 339.40 MI-4775, 4776 Jun, 2001 K-40 1,362.20 +/- 71.80 1,363.90 +/-73.40 1,363.05 +/- 51.34 Cr-5110, 5111 Jun, 2001 H-3 1,173.50 +/- 129.10 1,046.80 +/- 125.20 1,110.15 +/- 89.92 G-5085, 5086 Jun, 2001 Be-7 0.89 +/- 0.17 1.14 +/- 0.39 1.02 +/- 0,21 G-5085, 5086 Jun, 2001 K-40 5.13 +/- 0.39 5.22 +/-0.70 5.17 +/- 0.40 MI-5259, 5260 Jun, 2001 K-40 1,529.70 +/-122.70 1,406.20 _123.80 1,467.95 +/- 87.15 MI-5259, 5260 Jun, 2001 Sr-90 1.69 +/- 0.42 1.71 +/- 0.44 1.70 +/- 0.30 SWU-5422, 5423 Jun, 2001 Gr. Beta 2.59 +/- 0.54 1.91 +/-_0.52 2.25 +/- 0.37 VE-5401, 5402 Jun, 2001 Gr. Beta 8.12:+/- 0.24 8.88 +/- 0.26 8.50 +/- Q.18 VE-5401, 5402 Jun, 2001 K-40 6.55 +/- 0.52 6.26 +/- 0.65 6.40 +/- 0.42 AP-5830, 5831 Jun, 2001 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 SW-5557, 5558 Jun, 2001 Gr. Beta 5.43 +/- 1.70 5.96 +/- 1.56 5.70 +/- 1.15 AP-5851, 5852 Jun, 2001 Be-7 0.07 +/- 0.02 0.07 +/- 0,02 0.07 +/- 0.01 SW-5636, 5637 Jun, 2001 Gr. Beta 4.75 +/- 1.38 4.18 +/- 1.34 4.47 +/- 0.96 LW-5681, 5682 Jun, 2001 Gr. Beta 2.42 +/- 0.37 2.18 +/- 0.34 2.30 +/- 0.25 G-5535, 5536 Jul, 2001 Be-7 0.99 +/- 0.29 0.97 +/- 0.54 0.98 +/- 0.31 G-5535, 5536 Jul, 2001 Gr. Beta 7.62 +/- 0.12 7.72 +/- 0.12 7.67 - 0.08 G-5535, 5536 Jul, 2001 K-40 7.26 +/- 1.03 7.64 +/- 0.93 7.45 +/- 0.69 AP-5788, 5789 Jul, 2001 Be-7 0.08 +/- 0.02 0.07 +/- 0.02 0.08 +/- 0.01 155

II Davis-Besse Nuclear Power Station 2001 Annuwa Radiolhgical Enviromierual Operating Report Table A-5. In-house "duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes Date Analysis Result Result Result AP-5872, 5873 Jul, 2001 Be-7 0.07 _ 0.02 0.08 4 0.02 0.07 +/- 0.01 AP-5893, 5894 Jul, 2001 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 AP-5809, 5810 Jul, 2001 Be-7 0.07 +/- 0.02 0.06 +/- 0.01 0.06 +/- 0.01 SW-5724, 5725 Jul, 2001 Gr. Alpha 2.95 +/- 0.70 2.89 +/- 0.60 2.92 +/- 0.46 SW-5724, 5725 Jul, 2001 Gr. Beta 8.79 +/- 0.71 8.21 +/- 0.65 8.50 +/- 0.48 SW-5767, 5768 Jul, 2001 1-131 0.79 +/- 0.31 0.61 -t 0.26 0.70 +/- 0.20 LW-5920, 5921 Jul, 2001 Gr. Beta 3.06 +/- 0.64 3.15 +/- 0.58 3.11 +/-0.43 SO-6172, 6173 Jul, 2001 Cs-137 0.30 +/- 0.05 0.32 +/- 0.04 0.31 +/- 0.03 SO-6172, 6173 Jul, 2001 K-40 18.20+/- 1.08 17.55 +/- 0.82 17.88 +/- 0.68 SO-6172, 6173 Jul, 2001 Sr-90 0.03 +/- 0.01 0.05 "-+/-0.02 0.04 +/- 0.01 MI-6353, 6354 Jul, 2001 K-40 966.35 +/- 82.28 986.31 +/-91.91 976.33 +/- 61.68 SW-6376, 6377 Jul, 2001 1-131 0.58 +/- 0.16 0.81 +/- 0.17 0.70 +/-0.12 VE-6424, 6425 Jul, 2001 Gr. Beta 2.52 t 0.05 2.49 +/- 0.05 2.51 +/- 0.03 VE-6424, 6425 Jul, 2001 K-40 3.04 +/- 0.26 3.12 +/- 0.37 3.08 +/- 0.23 MI-6445, 6446 Jul, 2001 K-40 1,407.40 +/- 97.10 1,442.20 - 189.60 1,424.80 +/- 106.51 LW-6489, 6490 Jul, 2001 Gr. Beta 2.61 +/- 0.57 2.79 +/- 0.54 2.70 +/- 0.39 MT-6533, 6534 Jul, 2001 K-40 1,498.60 +/- 113.90 1,375.50 +/- 129.60 1,437.05 +/- 86.27 DW-6835, 6836 Jul, 2001 Gr. Beta 2.01 +/- 0.59 2.36 +/- 0.63 2.19 +/- 0.43 MI-6693, 6694 Aug, 2001 K-40 1,294.30+/-118.70 1,417.30 +/- 176.50 1,355.80 106.35 MI-6693, 6694 Aug, 2001 Sr-90 1.47+/-0.42 1.23 +/- 0.41 1.35 +/- 0.29 WW-6952, 6953 Aug, 2001 Gr. Beta 5.49 +/- 0.69 5.80 +/-t 0.69 5.64 +/-0.49 MI-6906, 6907 Aug, 200i K-40 1,613.80 +/- 218.50 1,532.70 +/- 135.80 1,573.25 +/- 128.63 VE-6973, 6974 Aug, 2001 K-40 4.21 +/- 0.24 4.29 t 0.64 4.25 +/- 0.34 LW-7851, 7852 Aug, 2001 Gr. Beta 2.20 +/- 0.48 2.12 _ 0.42 2.16 +/- 0.32 MI-7001, 7002 Aug, 2001 K-40 1,453.80 +/- 148.10 1,285.30 +/- 190.50 1,369.55 +/- 120.65 MI-7073, 7074 Aug, 2001 K-40 1,217.30 +/- 80.83 1,218.30 +/- 99.13 1,217.80 +/- 63.95 LW-7145, 7146 Aug, 2001 Gr. Beta 2.77 +/-0.53 3.60 +/- 0.59 3.19 +/--0.39 MI-7221, 7222 Aug, 2001 K-40 1,192.90 +/- 95.40 1,388.90 +/- 132.70 1,290.90 +/- 81.72 MI-7221, 7222 Aug, 2001 Sr-90 2.10 +/- 0.48 1.72 +/- 0.47 1.91 +/- 0.34 SWU-7527, 7528 Aug, 2001 Gr. Beta 17.51 +/- 3.06 20.36 t 3.31 18.93 +/- 2.25 VE-7485, 7486 Aug, 2001 K-40 2.12 +/- 0.47 2.47 +/- 0.34 2.30 +/- 0.29 DW-7506, 7507 Aug, 2001 Gr. Beta 4.25 +/- 1.18 4.13-+/-1.12 4.19:+/-0.81 MI-7622, 7623 Sep, 2001 K-40 1,340.10 +/- 111.10 1,290.80 +/- 116.50 1,315.45 +/- 80.49 MI-7664, 7665 Sep, 2001 K-40 1,408.10 +/-102.70 1,396.90 +/- 114.30 1,402.50 +/- 76.83 MI-7876, 7877 Sep, 2001 K-40 1,416.40 +/-192.30 1,318.00 +/- 155.50 1,367.20 +/- 123.65 G-7960, 7961 Sep, 2001 Be-7 1.27 +/- 0.21 1.25 +/- 0.25 1.26 +/- 0.16 156

Davi',.-Be1se Nudiear Power Station 20) 1 Armual I.'idiological Elvironnrental Ope.ating Report Table A-5. In-house "duplicate" samples.

Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result G-7960, 7961 Sep, 2001 K-40 5.21 +/-0.57 5.70 +/- 0.63 5.45 +/- 0.43 F-8011, 8012 Sep, 2001 Cs-137 0.06 +/-0.02 0.04 +/- 0.02 C.05 +/- 0.01 F-8011, 8012 Sep, 2001 Gr. Beta 3.68 +/- 0.12 3.50+/- 0.11 3.59 +/- 0.08 F-8011, 8012 Sep, 2001 K-40 3.47 +/- 0.49 3.38 - 0.47 3.43 +/- 0.34 INU-8149, 8150 Sep, 2001 K-40 1,551.70 +/- 118.00 1,489.90 +/- 123.60 1,520.80 +/- 85.44 MI-8343, 8344 Sep, 2001 K-40 1,550.30 +/- 170.60 1,368.10 +/- 126.70 1,459.20 +/- 106.25 VE-8319, 8320 Sep, 2001 Gr. Beta 3.37 - 0.10 3.42+/-0.11 3.39 +/- 0.07 VE-8319, 8320 Sep, 2001 K-40 2.14 +/- 0.46 2.24 +/- 0.37 2.19 +/- 0.29 AP-9069, 9070 Sep, 2001 Be-7 0.07 +/- 0.02 0.07 +/- 0.01 0.07+/-0.01 AP-9566, 9567 Sep, 2001 Be-7 0.08 +/- 0.02 0.09 +/- 0.03 0.09 +/- 0.02 VE-8700, 8701 Oct, 2001 Be-7 0.24 +/- 0.10 0.19 +/- 0.10 0.22 +/-0.07 VE-8700, 8701 Oct, 2001 K-40 2.03 +/- 0.24 2.03 +/- 0.21 2.03 +/--0.16 VE-8700, 8701 Oct, 2001 Sr-90 0.01 +/- 0.00 0.01 +/-!0.00 0.01 +/- 0.00 AP-9048, 9049 Oct, 2001 Be-7 0.07 +/- 0.01 0.07 +/- 0.00 0.07 +/- 0.01 DW-8636, 8637 Oct, 2001 Gr. Beta 4.74 +/- 1.06 5.08 +/- 1.21 4.91 +/- 0.80 DW-8615, 8616 Oct, 2001 Gr. Beta 4.65 +/-0.58 4.28 +/- 0.54 4.47 +/- 0.40 AP-9090, 9091 Oct, 2001 Be-7 0.07 -0.01 0.07 +/- 0.01 0,07 +/- 0.01 AP-9166, 9167 Oct, 2001 Be-7 0.08 +/- 0.02 0.08 +/- 0.02 0.08 +/- 0.01 AP-9187, 9188 Oct, 2001 Be-7 0.07 +/- 0.01 0.05 +/- 0.01 0.06 +/- 0.01 VE-10562, 10563 Oct, 2001 Be-7 309.90 +/- 158.80 348.30 +/- 168.10 329.10 +/- 115.62 VE-10562, 10563 Oct, 2001 K-40 6,407.10 +/- 620.70 6,057.50 +/- 660.40 6,232.30 +/- 453.15 WW-8636, 8637 Oct, 2001 Gr. Beta 5.08 +/- 1.20 4.74 +/- 1.06 4.91 +/- 0.80 DW-8894, 8895 Oct, 2001 Gr. Beta 4.28 +/- 0.89 3.40 +/- 0.90 3.84 +/- 0.63 MI-9232, 9233 Oct, 2001 K-40 1,440.70 +/- 46.60 1,424.80 +/- 76.40 1,432.75 +/- 44.75 VE-9518, 9519 Oct, 2001 K-40 1.91+/-0.22 1.97 +/- 0.39 1.94 +/- 0.22 WW-10257, 10258 Nov, 2001 H-3 755.90 +/- 10250 684.70 +/- 99.90 720.30 +/- 71.57 VE-10333, 10334 Nov, 2001 Be-7 0.68 +/- 0.26 0.99 +/- 0.26 0.84 +/- 0.18 VE-10333, 10334 Nov, 2001 K-40 6.10 +/- 0.72 5.83 +/- 0.72 5.97 +/- 0.51 MI-10588, 10589 Nov, 2001 K-40 1,428.40 +/- 114.70 "1,445.50+/- 129.40 1,436.95 +/- 86.46 DW-10688, 10689 Nov, 2001 Gr. Beta 3.49 +/-0.91 2.36 -0.76 2.93 +/- 0.60 WW-10905, 10906 Dec, 2001 H-3 233.90 +/- 90.60 226.30 +/- 90.20 230.10 +/- 63.92 SS-10953, 10954 Dec, 2001 Ac-228 1.10+/- 0.25 0.91.+/-0.16 1.00 +/- 0.15 SS-10953, 10954 Dec, 2001 Bi-214 0.69 +/-0.08 0.75 +/- 0.08 0.72 +/- 0.06 SS-10953, 10954 Dec, 2001 Co-58 0.21 +/- 0.05 0.18 +/- 0.04 0. 19 +/-0.03 SS-10953, 10954 Dec, 2001 Co-60 0.93 +/- 0.06 0.94 +/- 0.06 0.93 +/- 0.04 SS-10953, 10954 Dec, 2001 Cs-137 0.13 +/- 0.03 0.16 +/- 0.03 0.14 +/- 0.02 157

I . .- -

Davis-P~sse Ntuclear Powe'r Station 2001 Aanuzil Radiological Environmental Operating Report Table A-5. In-house 'duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes Date Analysis Result Result Result SS-10953, 10954 Dec, 2001 K-40 9.91 t+/-0.83 8.36 +/- 0.80 9.13 + 0.57

$5-10953, 10954 Dec, 2001 Pb-212 0.94 +/- 0.05 0.91 +/- 0.06 0.92 +/--0.04 SS-10953, 10954 Dec, 2001 Pb-214 0.83 +/- 0.08 0.82 +/- 0.07 0.83 t 0.05 SS-10953, 10954 Dec, 2001 Ra-226 1.76 +/- 0.37 1.67 +/- 0.37 1.72 +/- 0.26 SS-10953, 10954 Dec, 2001 TI-208 0.34 . 0.05 0.31 +/- 0.05 0.32 +/- 0.04 MI-11033, 11034 Dec, 2001 K-40 1,339.80 4-128.70 1,435.80 +/--117.30 1,387.80 +/- 87.07 MI-11033, 11034 Dec, 2001 Sr-90 1.31 -0.41 1.38 + 0.37 1.35 _ 0.28 AP-11888, 11889 Dec, 2001 Be-7 0.06 t 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

Results are reported in units of pCi/L, except for elemental potassium (K) in milk (mg/L), air filters (pCi/Filter),

food products and vegetation (pCi/g), soil and sediments (pCi/kg).

158

Davis-Bcsse Nude-ar Power Station 2001 Animal Radiological Environmnental Operating Report Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentrationb Lab Sample Date MAPEP Resultd Control Code Type Collected Analysis Laboratory resultc Is, N=I Limits ST'SO-923 SOIL Jan, 2001 Am-241 0.00 - 2.60 Included as false positive. Result of analyses; < 0.8 Bq/L.

STSO-923 SOIL Jan, 2001 Co-57 100.20 +/- 3.50 103.00 +/- 10.30 72.10 - 133.90 STSO-923 SOIL Jan, 2001 Co-60 1,285.10+/-5.30 1,270.00+/- 127.00 889.00 - 1,651.00 STSO-923 SOIL Jan, 2001 Cs-134 81.10 +/- 1.80 91.10 +/- 9.11 63.77 - 118.43 STSO-923 SOIL Jan, 2001 Cs-137 1,210.60 +/- 6.60 1,240.00 +/- 124.00 868.00 - 1,612.00 STSO-923 SOIL Jan, 2001 K-40 732.60 +/- 21.20 652.00+/- 65.20 456.40 - 847.60 STSO-923 SOIL Jan, 2001 Mn-54 212.60:+/-6.70 203.00 t 20.30 142 263.90 STSO-923 SOIL Jan, 2001 Pu-238 110.70 +/- 7.20 115.00 +/- 11.50 80.50 - 149.50 STSO-923 SOIL Jan, 2001 Pu-239/40 79.60 +/-5.90 83.40 -+/-8.34 58.38 - 108.42 STSO-923 SOIL Jan, 2001 Sr-90 159.80 +/- 9.50 209.00 +/- 20.90 146.30 - 271.70 STSO-923 SOIL Jan, 2001 U-233/4 45.00 +/- 3.90 60.00 +/- 6.00 42.00 - 78.00 STSO-923 SOIL Jan, 2001 U-238 165.60 +/- 7.40 191.00 +/- 19.10 133.70 - 248.30 STSO-923 SOIL Jan, 2001 Zn-65 428.50 +/- 10.90 382.00 +/- 38.20 267.40 - 496.60

" Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

b All results are in Bq/kg or Bq/L as requested by the Department of Energy.

SMAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.

159

Davis-iBsse Nuclear Power Statio..2001 Am mai Radioiogical EnviTomnenta OpCerating Report Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)'.

Concentration b Lab Sample Date Control Code Type Collected Analvsis Laboratory result EML Result Limitsd STSO-904 SOIL Mar, 2001 Ac-228 45.600 +/- 4.000 42.700 0.80- 1.50 STSO-904 SOIL Mar, 2001 Am-241 14.400 +/- 0.500 14.800 0.63 - 2.64 STSO-904 SOIL Mar, 2001 Bi-212 53.200 +/- 3.100 42.000 0.45- 1.23 Possible effect of shield background.

STSO-904 SOIL Mar, 2001 Bi-214 42.100 +/- 7.700 32.600 0.78 - 1.50 STSO-904 SOIL Mar, 2001 Cs-137 1,772.600 +/- 79.800 1,740.000 0.80- 1.29 STSO-904 SOIL Mar, 2001 K-40 583.800 +/- 52.600 468.000 0.80- 1.37 STSO-904 SOIL Mar, 2001 Pb-212 46.600 +/- 8.500 41.500 0.74- 1.36 STSO-904 SOIL Mar, 2001 Pb-214 45.300 +/- 8.600 34.300 0.76 - 1.53 STSO-904 SOIL Mar, 2001 Pu-239/40 26.000 +/-0.800 25.600 0.71 - 1.33 STSO-904 SOIL Mar, 2001 Sr-90 55.600 +/- 2.200 69.000 0.61 - 3.91 STW-905 WATER Mar, 2001 Am-241 2.150 +/- 0.140 1.670 0.76- 1.48 STW-905 WATER Mar, 2001 Co-60 97.000 +/- 0.800 98.200 0.80- 1.20 STW-905 WATER Mar, 2001 Cs-137 70.100 +/- 4.000 73.000 0.80 - 1.20 STW-905 WATER Mar, 2001 H-3 76.500 +/-5.500 79.300 0.74 - 2.29 STW-905 WATER Mar, 2001 Pu-238 1.690 +/- 0.070 1.580 0.74- 1.22 STW-905 WATER Mar, 2001 Pu-239/40 1.690 +/- 0.070 1.640 0.75 - 1.26 STW-905 WATER Mar, 2001 Sr-90 3.850 +/- 0.130 4.400 0.64- 1,50 STW-905 WATER Mar, 2001 U-233/4 0.900 +/-0.050 1.040 0.80- 1.40 STW-905 WATER Mar, 2001 U-238 0.880 +/- 0.050 1.040 0.80- 1.29 STW-906 WATER Mar, 2001 Gr. Alpha 1,724.600 +/-141.700 1,900.000 0.58 - 1.26 STW-906 WATER Mar, 2001 Gr. Beta 1,246.400 +/- 31.100 1,297.000 0.56- 1.50 STAP-907 AIR FILTER Mar, 2001 Am-241 0.470 +/- 0.040 0.486 0.69 - 2.40 STAP-907. AIR FILTER Mar, 2001 Co-60 20.110 +/- 0.160 19.440 0.79 - 1.30 STAP-907 AIR FILTER Mar, 2001 Cs-134 2.710 +/- 0.150 2.830 0.74- 1.21 STAP-907 AIR FILTER Mar, 2001 Cs-137 9,860 +/- 0.230 8.760 0.78 - 1.35 STAP-907 AIR FILTER Mar, 2001 Mn-54 7.250 +/- 0.220 6.520 0.80- 1.36 STAP-907 AIR FILTER Mar, 2001 Pu-238 0.230 +/- 0.030 0.215 0.66- 1.35 STAP-907 AIR FILTER Mar, 2001 Pu-239/40 0.120 +/- 0.020 0.136 0.69- 1.29 160

Davis-Bcss',: Nnclcr IPower StaLioni 2001 Annual Radiological Environniental Operating Report Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)'.

Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory result EML Result' Limits" STAP-907 AIR FILTER Mar, 2001 Sr-90 7.410 +/- 0.150 7.100 0.55 - 2.05 STAP-907 AIR FILTER Mar, 2001 U-233/4 0.050 +/- 0.010 0.046 0.80- 1.92 STAP-907 AIR FILTER Mar, 2001 U-238 0.050 +/- 0.010 0.046 0.80- 1.59 STAP-908 AIR FILTER Mar, 2001 Gr. Alpha 2.660 +/- 0.020 3.970 0.57- 1.47 STAP-908 AIR FILTER Mar, 2001 Gr. Beta 2.300 +/- 0.020 2.580 0.76- 1.52 STVE-909 VEGETATION Mar, 2001 Am-241 6.100 +/- 0.200 6.170 0.72- 2.34 STVE-909 VEGETATION Mar, 2001 Cm-244 3.500 +/-0.500 3.690 0.61- 1.61 STVE-909 VEGETATION Mar, 2001 Co-60 28.500:+/- 2.100 30.400 0.75- 1.51 STVE-909 VEGETATION Mar, 2001 Cs-137 795.500 +/- 76,400 842.000 0.80- 1.37 STVE-909 VEGETATION Mar, 2001 K-40 592.600 +/- 42.500 603.000 0.78- 1.43 STVE-909 VEGETATION Mar, 2001 Pu-239/40 8.500 +/- 0.600 9.580 0.67- 1.49 STVE-909 VEGETATION Mar, 2001 Sr-90 1,239.600 +/- 130.000 1,330.000 0.52- 1.23 STW-925 WATER Sep, 2001 Am-241 0.700 +/- 0.100 0.760 0.76- 1.48 STW-925 WATER Sep, 2001 Co-60 206.700 +/- 4.700 209.000 0.80- 1.20 STW-925 WATER Sep, 2001 Cs-137 46.600 +/- 0.800 45.133 0.80- 1.24 STW-925 WATER Sep, 2001 H-3 254.100 +/- 3.600 207.000 0.74 - 2.29 STW-925 WATER Sep, 2001 Ni-63 50.900 +/- 3.000 45.250 0.70- 1.30 STW-925 WATER Sep, 2001 Pu-238 1.100 +/- 0.100 1.088 0.74- 1.22 STW-925 WATER Sep, 2001 Pu-239/40 1.600 +/- 0.100 1.628 0.75- 1.26 STW-925 WATER Sep, 2001 Sr-90 4.100 +/- 0.300 3.729 0.64 - 1.50 STW-925 WATER Sep, 2001 Uranium 2.200 +/- 0.200 2.372 0.73- 1.37 STW-926 WATER Sep, 2001 Gr. Alpha 1,220.000 +/- 32.000 1,150.000 0.58- 1.26 STW-926 WATER Sep, 2001 Gr. Beta 8,461.000 +/- 206.000 7,970.000 0.56- 1.50 STSO-927 SOIL Sep, 2001 Ac-228 68.100 +/- 1.400 59.570 0.80- 1.50 STSO-927 SOIL Sep, 2001 Am-241 5.200 +/- 1.300 4.432 0.63- 2.64 STSO-927 SOIL Sep, 2001 Bi-212 65.100 +/- 1.600 62.067 0.45- 1.23 STSO-927 SOIL Sep, 2001 Bi-214 47.300 +/-4.700 36.900 0.78 - 1.50 STSO-927 SOIL Sep, 2001 Cs-137 659.200 +/-10.800 612.330 0.80 - 1.29 STSO-927 SOIL Sep, 2001 K-40 737.700 +/- 16.600 623.330 0.80- 1.37 161

oII I)1.vis-1Rc.ss, Nuc'ear Power Station 2001 Anana.m I ca1 LnVirommn)eal EIdIio, Opeatirng Report Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)ý.

Concentration, Lab Sample Date Code Control Type Collected Analysis Laboratory result EML Resu It,: Limits" STSO-927 SOIL Sep, 2001 Pb-212 64.700 +/- 3.800 58.330 0.74- 1.36 STSO-927 SOIL Sep, 2001 Pb-214 53.700 +/- 7.700 39.670 0.76- 1.53 STSO-927 SOIL Sep, 2001 Pu-239/40 9.300 +/- 2.900 8.948 0.71 - 1.33 STSO-927 SOIL Sep, 2001 Sr-90 27.400 +/- 6.300 30.596 0.61 - 3.91 STSO-927 SOIL Sep, 2001 Uranium 155.600 +/- 7.800 194.230 0.62 - 1.35 STVE-928 VEGETATION Sep, 2001 Am-241 7.000 +/- 0.300 6.915 0.72 - 2.34 STVE-928 VEGETATION Sep, 2001 Cm-244 4.300 +/- 0.800 4.308 0.61 - 1.61 STVE-928 VEGETATION Sep, 2001 Co-60 40.200 +/- 0.900 35.300 0.75- 1.51 STVE-928 VEGETATION Sep, 2001 Cs-137 1,184.000 +/- 2.800 1,030.000 0.80 - 1.37 STVE-928 VEGETATION Sep, 2001 K-40 1,023.000 +/-44.100 898.670 0.78- 1.43 STVE-928 VEGETATION Sep, 2001 Pu-r-39/40 8.900 +/- 1.400 11.022 0.67- 1.49 STVE-928 VEGETATION Sep, 2001 Sr-90 1,364.000 +/- 18.400 1,612.800 0.52- 1.23 STAP-929 AIR FILTER Sep, 2001 Am-241 0.090+/-30.000 0.088 0.69 - 2.40 STAP-929 AIR FILTER Sep, 2001 Co-60 16.900 +/-0.300 17.500 0.79- 1.30 STAP-929 AIR FILTER Sep, 2001 Cs-134 11.800+/-0.200 12.950 0.74- 1.21 STAP-929 AIR FILTER Sep, 2001 Cs-137 18.300 +/- 0.300 17.100 0.78- 1.35 STAP-929 AIR FILTER Sep, 2001 Mn-54 85.400 +/-1.300 81.150 0.80- 1.36 STAP-929 AIR FILTER Sep, 2001 Pu-238 0.051 +/-0.010 0.071 0.66- 1.35 STAP-929 AIR FILTER Sep, 2001 Pu-239/40 0.220 +/- 0.020 0.229 0.69- 1.29 STAP-929 AIR FILTER Sep, 2001 Sr-90 3.110 +/- 0.060 3.481 0.55 - 2.05 STAP-929 AIR FILTER Sep, 2001 Uranium 0.240 +/- 0.050 0.222 0.80 - 2.54 STAP-930 AIR FILTER Sep, 2001 Gr. Alpha 6.300 +/-0.100 5.362 0.57- 1.47 STAP-930 AIR FILTER Sep, 2001 Gr. Beta 12.770 0,76- 1.52 13.800 t 0.100

" The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Vegetation and Water.

b Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.

' The EML result listed is the mean of replicate determinations for each dControl limits are reported by EML as the ratio of Reported nuclide+/-the standard error of the mean.

Value / EML value.

162

Davis-Bessý Nlucleai Pow-.r Sial.lon 200 i Annual Radioloý,.ical 1; iroriniental OperzW)g RCPOrt

.APPLNDD(.B DkTA REpORTING coNVENTIONS 163

Dav\s-Bessc Nuckea= lower Station 2001 Annimal Radiological Environ.merntr Operating Report Data Renorting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows: x 4- s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L,- it is reported as: : <L, where L =.the lower limit of detection based on 4.66s uncertainty for. a background :sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xj I sI and x2 :L S2 (W/2) 2 S2 Reported result: x + s; where x = (1/2) (xl + x2) and s 3.2. Individual results: <L 1, <L2 Reported result: <L, where L = lower of LI -and L'2 3.3. Individual results: x : s, <L Reported result: x - s if x>_ L; <L otherwise..

4.0... Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individue.l measurements over the period averaged; for example, an annual standard deviation would not b.

the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers xI, x 2 ... Xn are defined as follows:

4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to tt.45.

164

Davis-IDcsske N uclear Pc}'ver Stati.-on 20 A~iwai Ridc1logical EnvronnrCflVlT)01 OPCIuilling RCII(rl APPENDIX C Emuent Conicentration Limit of Radioactivity in Air and Water Above Natural Background in Uartstricted Areas 165

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.)ais-13s.-u .~Nuciear Powe'r Station 2001 Annual Radiologi.cal I.virionmental Operating Report Table C-I Effluent Concentration Limit of Radioactivity in Air and Water Abbvc Natural Background in Unrestricted Area?

Air Water 3 Strontium-89 Gross Alpha IE-03 pCi/m 8,000 pCi/I Gross Beta I pCu/r' Strontium -90 500 pCi/O lodine-131b 2.86E-01 pCi/mr Cesium-137 1,000 pCiA Barium-l40 8,000 pCa Iodine-131 1,000 pCi/I Potassium.40C 4.0)00 pCP/

Gross Alpha 2 pCi/I Gross Beta 1x00* pCi/A Tritium Taken from Code of Federa Regulation Title 10, Part 20, Table II and appropriate footnotes. Concentrations may be averaged over a period not greater than one year.

b From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air grass-cow-child pathway.

A natural radionuclide.

166

Davis-l.ks.w Nuchnr Povvcr Slý,.tiojl 200 1 Armiml k,,jcjl()[ovjc,,jj ETI-vir)Ijillental Operating Rt.port APPEN'DIX D REEPAP SAMPUNG

SUMMARY

167

II Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Tabie 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Loca'ion of Facility Ottawa, Ohio Reporting Period January-December, 2001 (County, State}

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)c Mean (Fl Mean (Ff Routine (Units) Analyses _ Range' Locationc Range-^ RangeC Resultse Airbome GB 519 0.005 0.025 (3111311) T-9, Oak Harbor 0.027 (52/52) 0.025 (208/208) 0 Particulates (0.009-0.067) 6.8 mi. SW (0.012-0.058) (0.006-0.064)

(pCiim3)

Sr-89 0.0016 < LLD < LLD 0 Sr-90 0.0017 < LLD - < LLD 0 GS 40 Be-7 0,015 0.069 (24/24) T-4, Site Boundar, 0.076 (414) 0.069 (16/16) 0 (0.042-0.093) 0.8 mi. S (0.053-0.093) (0.047-0.107)

K-40 0.039 < LLD - < LLD 0 Nb-95 0.0014 < LLD - - < LLD 0 Zr-95 0.0017 < LLD - - < LLD 0 Ru-103 0.0014 < LLD - - < LLD 0 Ru-106 0.0102 < LLD - - < LLD 0 Cs-1 34 0.0140 < LLD - - < LLD 0 Cs-137 0.0011 < LLD - - < LLD 0 Ce-141 0.0023 < LLD - - < LLD 0 Ce-!44 0.0075 < LLD - - < LLD 0 Airborne Iodine 1-131 519 0.07 < LLD - - < LLD 0 (pCi/m3)

TLD (Quarterly) Gamma 340 1.0 14.4 (2941294) T-45. Site Boundary 20,2 (414) 14,8 (46/46) 0 (mRJ91 days) (6.4-24.1) 0.5 mL. WNW (17.4-23.2) (9,6-19.7)

TLD (Quarterly) Gamma 4 1.0 6,7 (4/4) None 0 (mR/91 days) (5.9-7.1)

(Shield)

TLD (Annual) Gamma 85 1.0 55.6 (76t76) T-87, Site boundary 79.6 (1/1i) 58.0 (9/9) 0 (mR'365 days) (31.1-79.6) 0.3 mi. NNW (38.6-72,6)

TLD (Annual) Gamma 1 1.0 21.9 (111) - None 0 (mRi365 days)

(Shield) 168

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environinental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Penod January-December, 2001 (County, State)

Indicator Location with Highest Control Number Sample Type and Locatiions Annual Mean Locations Non Type Number of LLDb Mean (F)' Mean (F)f Mean (F)f Routine (Units) Analyses" Rangec Locationd Ranqec Rangec Resultse Milk (pCUi.) 1-131 12 0.4 none < LLD 0 Sr-89 12 1.7 none - < LLD 0 Sr-90 12 1.0 none T-24, Sandusky 1.2 (5112) 1.2 (5!12) 0 21.0 mi. SE (1.1-1.4) (1.1-1.4)

GS 12 K-40 100 none T-24, Sandusky 1378 (12112) 1378 (12/12) 0 21.0 mi. SE (1.1-1.4) (1.1-1.4)

Cs-134 6.5 Cs-137 6.0 none < LLD 0 Ba-La-140 9.6 none < LLD 0 (g/L) Ca 12 0.50 none T-24, Sandusky 0.87 (12/12) 0.87 (12-112) 0 21.0 ml. SE (0.79-1.00) (0.79-1.00)

(gL) K (stable) 12 0.10 none T-24, Sandusky 1.59 (12/12) 1.59 (12/12) 0 21.0 mi. SE (1,45-1.91) (1.45-1.91)

(pCi/g) Sr-90/Ca 12 0.00 none T-24, Sandusky 1.37 (6i12) 1.37 (6/12) 0 21.0 mi. SE (1.18-1.77) (1.18-1.77)

(pCilg) Cs-137/K 12 0.00 none < LLD 0 Ground Water GB (TR) 5 3.7 < LLD < LLD (pCi!L)

H-3 5 330 416 (1I) T-225, residence - LLD 0 1.55 mi. NW Sr-89 5 1.1 < LLD - < LLD 0 Sr-90 5 0.7 < LLD - < LLD 0 GS Mn-54 15 < LLD - < LLD 0 Fe-59 30 < LLD - - < LLD 0 CO-58 15 < LLD - - < LLD 0 Co-60 15 < LLD - - < LLD 0 Zn-65 30 < LLD - c 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 0 169

. .. - -1.

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January-December, 2001

( County, State Indicator Location with Highest Controt Number Sampie Type and Locations Annual Mean Locations Non Type Number of LLD" Mean (F)' Mean (F)f Mean (F)c Routine (Units) Analyses* Range' Locationd RangeC Range' Results' Edible Meat GS 4 (pCi/g wet) K-40 0.10 2.94 (2/2) T-34, Offsite 3.44 (212) 3,44 (212) 0 (2.73-3.15) Roving location (2,84-4.03) (2.84-4.03)

Nb-95 0,032 < LLD - - < LLD 0 Zr-95 0.033 < LLD -< LLD 0 Ru-i 03 0.032 < LLD - < LLD 0 Ru-106 0.12 < LLD - < LLD 0 Cs-137 0.013 < LLD - - < LLD 0 Ce-141 0.072 < LLD - - < LLD 0 Ce-144 0.093 < LLD - - < LLD 0 Fruits and St-89 3 0.002 < LLD < LLD 0 Vegetables Sr-90 3 0,001 < LLD < LLD 0 (pCi/g wet) 1-131 3 0.017 < LLD < LLD 0 GS 3 K-40 0.50 1.17 (2/2) T-209, Orchard 1.34 (111) 1.34 (1/1) 0 (0.67-1.66) 18.9 mi. W Nb-95 0.011 < LLD < LLD 0 Zr-95 0.030 < LLD < LLD 0 Cs-137 0,010 < LLD < LLD 0 Ce-141 0.021 < LLD < LLD 0 Ce-144 0.077 < LLD < LLD 0 Broad Leaf Sr-89 9 0.007 < LLD < LLD 0 Vegetation Sr-90 9 0.004 0.008 (2/6) T-19, Farm 0.009 (1/3) < LLD 0 (pCi/g wet) (0.006-0.009) 0.68 mi. W 1-131 9 0,025 < LLD < LLD 0 GS 9 K-40 0.50 1.90 (6/6) T-19, Farm 1.95 (3/3) 1.79 (3;3) 0 (1.48-2.20) 0.68 mi. W (1.48-2.20) (1.64-1.89)

Nb-95 0.019 < LLD < LLD 0 Zr-95 0.022 < LLD < LLD 0 Cs-137 0.015 < LLD < LLD 0 Ce-141 0.029 < LLD < LLD 0 Ce-144 0.13 < LLD < LLD 0 170

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Ottawa, Ohio Reporting Period January- December. 2001 Location of Facility

( County, State)

Indicator Location with Highest Control Number Type and Locations Annual Mean Locations Non Sample Number of LLDb Mean (F)C Mean (F)C Mean (F)' Routine Type t

(Units) Analysesa Rangec Locationd Rangec Rangec Results Animal I GS 5 Wildlife Feed Be-7 0.33 0.81 (1/3) T-31, Onsite 0.81 (1/1) 0.70 (1/2) 0 (pCilg wet) Roving location K-40 0,10 3.15 (3/3) T-34, Offsite 8.05(1/1) 6.09 (2/2) 0 (1.11-7.01) Roving location (4.13-8.05)

Nb-95 0.033 < LLD < LLD 0 Zr-95 0.069 ,< LLD < LLD 0 Ru-103 0.028 < LLD -< LLD 0 Ru-106 0.20 < LLD - - < LLD 0 Cs-137 0.019 < LLD - - < LLD 0 Ce-141 0.073 < LLD - - < LLD 0 Ce-144 0.19 < LLD -< LLD 0 Soil GS 20 (pCi/g dry) Be-7 0.50 1.02(5/12) T-4, Site Boundary 1.98(112) 0.92 (2/8) 0 (0.58-1.98) 0.8 mi. S (0.82-1.02)

K-40 0.10 13.35 (12112) T-9, Oak Harbor 24.76 (2/2) 21.28 (818) 0 (4.68-23.10) 6.8 mi. SW (24.22-25.30) (18.77-25.30)

Nb-95 0.083 < LLD - < LLD 0 Zr-95 0.11 < LLD - < LLD 0 Ru-103 0,064 < LLD - < LLD 0 Ru-106 0.38 < LLD - < LLD 0 Cs-137 0.050 0.13 (7/12) T-12, Water Treatment 0.23(2/2) 0.18 (7/8)

(0.052-0.25) Plant, 23.5 mi. WNW (0.20-0.26) (0.086-0.26) 0 Ce-141 0.12 < LLD -< LLD 0 Ce-144 0.19 < LLD -< LLD 0 171

Davis-Besse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Ohio Reporting Period January-December, 2001

( County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)' Mean (F)' Routine (Units) Analysese Rangec Locationd Range' Rangec Resultse Treated GB (TR) 48 1.0 2.5 (24/24) T-1 1, Port Clinton 2.7(12/12) 2.3 (24/24) 0 Surface Water (1.7-3.2) VVTP, 9.5 mi. SE (2.1-3.5) (1.6-3.5)

(pCVL) H-3 16 330 593 (1/8) T-22, Carroll Twp. 593 (1/4) < LLD 0 WTP, 3.0 mi. NW Sr-89 16 1.7 < LLD - < LLD 0 Sr-90 16 1.0 < LLD - - < LLD 0 GS 16 Mn-54 15 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 15 < LLD - - < LLD 0 Co-60 15 < LLD .< LLD 0 Zn-65 30 < LLD < LLD

- 0 Zr-Nb-95 15 < LLD - < LLD 0 Cs-134 10 < LLD - < LLD 0 Cs-137 10 < LLD - < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Untreated GB (TR) 95 1.0 3.1 (50/50) T-137, Lake Erie 4.4 (7/7) 3.1 (45/45) 0 Surface Water (2.1-5.4) 7.0 mi. WNW (2.1-12.7) (1.9-12.7)

(pCt'L) H-3 95 330 713 (2/50) T-3. Site Boundary 986 (1/12) <LLD 0 330 (439-986) 1.4 mi. ESE Sr-89 20 1.6 < LLD -< LLD 0 Sr-90 20 0.8 1.9 (1/12) T-3, Site Boundary 1.9 (114) < LLD 0 1.4 mi. ESE GS 95 Mn-54 15 < LLD < LID 0 Fe-59 30 < LLD - < LLD 0 Co-58 15 < LLD - -< LLD 0 Co-60 15 < LLD - -< LLD 0 Zn-65 30 < LLD - -< LLD 0 Zr-Nb-95 15 < LLD - -< LLD 0 Cs-134 10 < LLD - -< LLD 0 Cs-137 10 < LLD - -< LLD 0 Ba-La-140 15 < LLD - -< LLD 0 172

Davis-Bcsse Nuclear Power Station 2001 Annual Radiological Environmental Operating Report Table 4.5 Radiological Environmental Monitoring Program Summary Name of Facility Davis-Besse Nuclear Power Station Docket No. 50-346 Location of Facility Ottawa, Oh;o Reporting Period January-December. 2001

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDO Mean (F) Mean (F' Mean (F)' Routine (Units) Analysese Range. Locationd Range' Rangeý Resultso Fish GB 6 0.1 2.97 (3/3) T-33, Lake Erie 2.97 (313) 2.82 (3/3) 0 (pCi/g wet) (2.70-3.12) 1.5 mi. NE (2.70-3.12) (1.86-3.53)

GS 6 K-40 0.10 2.48(3/3) T-35, Lake Erie 2.96 (3,3) 2.96 (3/3) 0 (1.95-3.11) > 10mi. (2,76-3.10) (2.76-3.10)

Mn-54 0.013 < LLD < LLD 0 Fe-59 0.032 < LLD <LLD 0 Co-58 0.013 < LLD < LLD 0 Co-60 0.014 < LLD < LLD 0 Zn-65 0.026 < LLD < LLD 0 Cs-134 0.014 < LLD < LLD 0 Cs-137 0.020 < LLD < LLD 0 Shoreline GS 8 Sediments K-40 0.10 10.80(6/6) T-27B, Crane Creek S.P. 11.87 (2/2) 11.87 (2/2) 0 (pCi/g dry) (8.06-12.82) 5.3 mi. WNW (10.61-13.13) (10.61-13.13)

Mn-54 0.026 < LLD < LLD 0 Co-58 0.028 < LLD < LLD 0 Co-60 0.025 < LLD < LLD 0 Cs-134 0.029 < LLD < LLD 0 Cs-137 0.026 < LLD < LLD 0 "GB = gross beta, GS = gamma scan.

bLLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

C Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).

Locations are specified by station code (Table 4.1) and distance (miles) and direction relative to reactor site..

e Non-routine results are those which exceed ten times the control station value.

173