ML061430031

2005 Annual Radiological Environmental Operating Report

ML061430031
Person / Time
Site:	Columbia
Issue date:	12/31/2005
From:	Energy Northwest
To:	Office of Nuclear Reactor Regulation
References
Q-070
Download: ML061430031 (84)

Text

COLUMBIA GENERATING STATION 2005 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR THE COLUMBIA GENERATING STATION PENERGY NORTHWEST People-Visian- Solutions

ENERGY SNORTHWEST People- Vision- Solutions COLUMBIA GENERATING STATION 2005 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Calendar Year 2005 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Prepared by:

Energy Northwest - Environmental Services Staff Richland, WA

TABLE OF CONTENTS SECTION PAGE 1.0 EXECUTIVE

SUMMARY

1-1 2.0 DEFINITIONS 2-1

3.0 INTRODUCTION

3-1 3.1 Site Description 3-1 3.2 Program Background 3-1 3.3 Program Objectives 3-2 4.0 PROGRAM DESCRIPTION 4-1 4.1 Sample Locations 4-1 4.2 Independent Spent Fuel Storage Installation (ISFSI) 4-1 4.3 Land Use Census 4-2 4.4 Sampling Methods 4-2 4.4.1 Direct Radiation 4-2 4.4.2 Airborne - Particulate/Iodine 4-3 4.4.3 Water 4-3 4.4.4 Soil 4-4 4.4.5 Sediment 4-4 4.4.6 Fish 4-4 4.4.7 Milk 4-5 4.4.8 Garden Produce 4-5 4.5 Sample Analyses 4-5 4.5.1 Analysis of TLDs 4-6 4.5.2 Gross Beta Activity on Air Particulate Filters 4-6 4.5.3 Measurement of Gamma Emitting Radionuclides 4-6 4.5.4 Gross Alpha and Gross Beta Activity in Water 4-7 4.5.5 Tritium in Water 4-7 4.5.6 Strontium-89 and 90 in Soil 4-7 4.5.7 Low Level Iodine-131 in Milk and Water 4-7 Energy Northwest/Columbia Generating Station i 2005 Annual Radiological Environmental Operating Report

TABLE OF CONTENTS SECTION PAGE 4.6 Data Analysis Methods 4-7 L 4.7 Changes to the Sampling Program in 2005 4-8 L 5.0 RESULTS AND DISCUSSION 5-1 5.1 Direct Radiation 5-1 5.2 Airborne Particulate/Iodine 5-4 5.3 Water 5-5 5.4 Soil 5-6 L 5.5 River Sediment 5-6 5.6 Fish 5-6 U 5.7 Milk 5-6 5.8 Garden Produce 5-6 5.9 Special Interest Stations 5-7 5.9.1 Storm Drain Pond (Station 101) 5-7 5.9.2 Sanitary Waste Treatment Facility (Station 102) 5-7 L 5.9.3 Cooling Tower Sediment Disposal Area (Station 119) 5-8 5.9.4 Spray Pond Drain Field (Station 120) 5-8 U 5.9.5 Independent Spent Fuel Storage Installation 5-9 5.10 2005 Sample Deviations 5-9 U 6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6-1 6.1 Quality Control for the Energy Northwest Environmental TLD Program 6-1 6.2 Quality Control for the Environmental Sample Program 6-2 6.2.1 Quality Control Activities for Sample Collection 6-2 6.2.2 Teledyne Brown Engineering Quality Control Program 6-2 6.2.3 Energy Northwest Environmental Services Quality Control 6-3 6.3 Sample Batch Quality Control 6-4 U

2005 Annual Radiological Environmental Operating Report Hi Energy Northwest/Columbia Generating Station

TABLE OF CONTENTS 6.4 Laboratory Intercomparison Program Participation 6-5

7.0 REFERENCES

7-1

'U 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Station Northwest/Columbia Generating Station oif 2005 Annual Radiological Environmental Operating Report

LIST OF TABLES TABLE PAGE 4-1 Radiological Environmental Monitoring Program Plan 4-9 U 4-2 REMP Sample Stations and Requirements 4-11 U 4-3 2005 Five-Mile Land Use Census Results 4-14 4-4 Comparison of Laboratory Nominal Lower Limits of Detection With Offsite Dose Calculation Manual Requirements 4-15 U

5-1 2005 Sample Deviations 5-9 5-2 Radiological Environmental Monitoring Program Sample Analysis Results Summary 5-10 U 5-3 Quarterly TLD Data Summary For The Preoperational and Operational Periods 5-23 5-4 Annual TLD Data Summary For the Preoperational and Operational Periods 5-25 5-5 2005 Quarterly Versus Annual TLD Data 5-27 6-1 2005 Energy Northwest Spiked Dosimeter Results 6-6 6-2 Teledye Brown Engineering Results-2005 Analytics, Inc. Cross Check Comparison Program 6-7 U 6-3 Teledye Brown Engineering Results-2005 MAPEP Environmental Radioactivity Cross Check Program 6-10 6-4 Teledye Brown Engineering Results-2005 ERA Cr6sschecks Performance Evaluation Program 6-12 U 6-5 Energy Northwest Results-2005 ERA Crosschecks Performance Evaluation Program 6-13 6-6 Energy Northwest Results-2005 Analytics, Inc. Cross Check Comparison Program 6-15 U Operating Report iv Energy Northwest/Columbia Generating Station 2005 Annual 2005 Radiological Environmental Annual Radiological Environmental Operating Report iv Energy Northwest/Columbia Generating Station

LIST OF FIGURES FIGURE PAGE 4-1 REMP Sampling Locations Inside the 10-Mile Radius 4-16 4-2 REMP Sampling Locations Outside the 10-Mile Radius 4-17 4-3 REMP Near Plant Sampling Locations 4-18 4-4 TLD Stations 121 and 122 4-19 4-5 ISFSI TLD Stations Layout 4-20 5-1 Site Boundary Quarterly TLDs 1984-2004 Hi/Low/Mean vs. 2005 Mean by Sector o.. - 5-2 5-2 Inner Circle Quarterly TLDs 1984-2004 Hi/Low/Mean vs. 2005 Mean by Sector 5-3 5-3 Remote Quarterly TLDs 1984-2004 Hi/Low/Mean vs. 2005 Mean by Sector 5-3 5-6 1985-2004 Weekly Hi/Low/Mean vs. 2005 Weekly Mean Gross Beta in Air - Near Plant Stations 5-4 5-7 1985-2004 Weekly Hi/Low/Mean vs. 2005 Weekly Mean Gross Beta in Air- Remote Stations . ý 1 .... -1 ;. -, *

• I5-5 Station V 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Energy Norffiwest/Columbia Generating Station V 2005 Annual Radiological Envirorunental Operating Report

1.0 EXECUTIVE

SUMMARY

1.0 EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program (REMP) for Columbia Generating Station (CGS) and its associated Independent Spent Fuel Storage Installation (ISFSI) for calendar year 2005. The REMP is administered by the Energy Northwest Environmental Services group. The purpose of the REMP is to assess the potential radiological impacts of CGS activities on the environment through the monitoring of various exposure pathways.

The Offsite Dose Calculation Manual (ODCM) requires monitoring of direct radiation exposure levels, and of the inhalation and ingestion radiation exposure pathways. Direct radiation levels were monitored continuously with thermoluminescent dosimeters (TLDs). The inhalation pathway was monitored by collecting air particulate and air iodine samples and analyzing them to quantify the concentrations of radiation, and radioisotopes. The ingestion pathway was monitored by collecting samples of water, milk, soil, sediment, fish, and garden produce throughout the year and evaluating them for radioactivity that might be present as a result of plant emissions.

Results from the offsite direct radiation monitoring conducted in 2005 for CGS indicate that there was no measurable dose contribution from plant operations. No new casks were placed in the ISFSI during 2005 and radiation levels nearby showed a gradual decrease in the quarterly monitoring results. No measurable increases in the dose rates were seen inside controlled areas at CGS relative to the previous year.

Results of the offsite monitoring of the other exposure pathways indicate that there is no measurable radiological impact on the environment from CGS. The vast majority of the activity that was detected in environmental samples was the result of naturally occurring radionuclides. Small amounts of Cs-137 were measured in some of the samples collected; the concentrations were consistent with levels found in the surrounding environment as a result of atmospheric nuclear weapons test fallout and past activities on the Hanford Site. The results seen in the samples taken this year are consistent with the results obtained in the previous operational and preoperational years.

No significant trends or changes in the environmental radiological levels in the vicinity of CGS were observed in 2005.

1-1 2005 Annual Radiological Environmental Operating Report Energy Nordiwest/Columbia Generating Station Northwest/Columbia Generating Station 1-1 2005 Annual Radiological Enviromnental Operating Report

2.0 DEFINITIONS 2.0 DEFINITIONS EFSEC: Energy Facility Site Evaluation Council.

Airborne Activity Sampling: Continuous sampling of FFTF: Fast Flux Test Facility, also referred to as the air through the collection of particulates and DOE 400 area.

radionuclides on filter media. Periodic soil samples are collected for gamma isotopic analysis to provide Flow Proportional Sampling: Sample collection information on deposition to the soil from airborne volume or frequency determined as a function of the releases. flow rate of the water being sampled.

Alpha Particle (at): A charged particle emitted from Grab Sample: A single discrete sample drawn at one the nucleus of an atom having a mass and charge equal point in time.

in magnitude of a helium nucleus.

Indicator Station: A sampling location that is likely Becquerel (Bq): One disintegration per second. One to be affected by plant effluents due to its proximity picocurie (pCi) equals 0.037 becquerel. and/or direction from the Columbia Generating Station.

Beta Particle (B3): Charged particle emitted from the nucleus of an atom with a mass and charge equal in Ingestion Pathway Monitoring: The ingestion magnitude to that of an electron. pathway includes milk, soil, fish, and garden produce.

Also sampled (under special circumstances) are other Blank Sample: A sample of the same media as the media such as vegetation and animal products such as field sample being analyzed but without any eggs and meat when additional information about radionuclide(s) being measured. It enables correction particular radionuclides is needed.

for the inherent sample background.

ISFSI: Independent Spent Fuel Storage Installation.

Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The Lower Limit of Detection (LLD): The smallest aliquots making up the sample are collected at time concentration of radioactive material in a sample that intervals that are very short compared to the composite will yield a net count (above system background) that period. will be detected with 95% probability with a 5%

probability of a false conclusion that a blank Control Station: A sampling station in a location not observation represents "real" signal.

likely to be affected by plant effluents due to its distance and/or direction from the Columbia MAPEP: Mixed Analyte Performance Evaluation Generating Station. Program.

Counting Error: An estimate of the two-sigma Mean: The average, i.e., the sum of results divided by uncertainty associated with the sample results based on the number of results.

respective count times.

+ / - 2NFrSampleCPM/CountTime+ BkgCPM/CountTime) Microcurie: 3.7 x 10 4 disintegrations per second, or 2.22 x10 6 disintegrations per minute.

Curie (Ci): A measure of radioactivity; equal to 3.7 x Milliroentgen (mR): 1/1000 Roentgen; a unit of 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute. exposure to X or gamma radiation.

Direct Radiation Monitoring: The measurement of MDA: Minimum Detectable Activity.

radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters and NIST: National Institute of Standards and Technology.

pressurized ionization chambers.

NPDES: National Pollutant Discharge Elimination DOE: U.S. Department of Energy. System.

DOH: Washington State Department of Health. NRC: U.S. Nuclear Regulatory Commission.

Energy Northwest/Colurnbia Generating Station 2-1 2005 Annual Radiological Environmental Operating Report

ODCM: Offsite Dose Calculation Manual. Licensing document that contains the offsite radiological requirements.

Picocurie (pCi): 1 x 10"12 Curie or 2.22 disintegrations per minute; one millionth of a microcurie.

REMP: Radiological Environmental Monitoring Program.

Range: The difference between the smallest and largest results.

U Restricted Area: Any area to which access is controlled for purposes ofprotection of individuals from exposure to radiation and radioactive materials.

Roentgen: Unit of exposure to ionizing radiation in air.

Site Certification Agreement (SCA): The Columbia Generating Station licensing agreement with the State U

of Washington.

Spiked Sample: A sample that has had a known .

quantity of radionuclide(s) added for the purposes of assessing analytical performance. L Standard Deviation: A measure of the scatter of a set of observations (or samples) around their mean value.

Indicated by "a".

Standard Error of the Mean: An estimate of the uncertainty associated with the mean of observation (or sample) averages. Also known as the standard deviation.

SE=4 where S2, the variance is m= (nI 12 " i- )

SWTF: Sanitary Waste Treatment Facility; sanitary waste processing facility for the Columbia Generating Station, industrial development complex and the Department of Energy's 400 Area. u TEDA: triethylene diamine Thermoluminescent Dosimeter (TZLD): A TLD is a phosphor that stores energy from exposure to radiation and emits that energy in the form of light when heated.

2005 Annual Radiological Environmental Operating Report 2-2 Energy Northwest/Columbia Generating Station

3.0 INTRODUCTION

3.1 Site Description Columbia Generating Station (CGS) is a 1200 MWe commercial nuclear power plant that achieved initial criticality on January 19, 1984. The plant is located in a sparsely populated shrub-steppe region within the Department of Energy (DOE) Hanford Site in southeastern Washington. The plant is approximately three miles west of the Columbia River and is surrounded on all sides by uninhabited desert land. The nearest large population centers are Richland, Pasco, and Kennewick; which are 12 miles south, 18 miles southeast, and 21 miles southeast, respectively. The nearest privately owned lands are located approximately four miles east-northeast of the plant, across the Columbia River. The site has a bimodal wind pattern with winds primarily from the northwest and south.(20 ) The primary region of focus for REMP sampling is the farming region east of the plant.

Naturally occurring radionuclides exist in detectable quantities throughout the world and are seen in many of the samples collected for the REMP. Some examples of naturally occurring radionuclides that are frequently seen in samples are K-40, Be-7, Ac-228 (present as a decay product of Ra-228),

and Ra-226. Additionally, some relatively long lived anthropogenic radioisotopes, such as Sr-90 and Cs-137, are also periodically seen in some REMP samples; these radionuclides exist in measurable (21) quantities throughout the world as a result of fallout from atmospheric nuclear weapons testing.

Due to the location of CGS on the Hanford Site, there are other sources of reactor produced radionuclides in close proximity to the plant. Hanford related radionuclides, which are sometimes measured in CGS REMP samples, are distinguishable from those that may be present as a result of CGS activities by the improper ratios of several characteristic shorter-lived radionuclides. The DOE has an active REMP for the Hanford Site that overlaps the CGS REMP.

3.2 Program Background The CGS REMP is designed to conform to the Nuclear Regulatory Commission (NRC) Regulatory Guides 4.1, 4.8,(2) and the Radiological Assessment Branch Technical Position. 3) In addition, the REMP also meets the requirements of IOCFR72.44(d)(2) for coverage of the ISFSI.

The quality assurance aspects of the sampling program and the thermoluminescent dosimetry are conducted in accordance with Regulatory Guides 4.15(4) and 4.13.() The REMP also adheres to the requirements of the Washington Energy Facility Site Evaluation Council (EFSEC),(6) the Columbia Generating Station Technical Specifications(7) and the Offsite Dose Calculation Manual (ODCM).(8)

These requirements cover the environmental sampling and sample analysis aspects of the program, and also the reporting and quality assurance requirements.

The preoperational phase of the program, which lasted from March 1978 until initial criticality in January 1984, provided a baseline of background environmental data. The variability in the background levels of radioactivity is due to differences in geologic composition, meteorological conditions, and seasonal changes.

Energy Northwest/Columbia Generating Station 3-1 2005 Annual Radiological Environmental Operating Report

Teledyne Brown Engineering-Environmental Services was contracted to perform analyses of REMP L samples for the first three quarters of 2005. The Energy Northwest Environmental Services Laboratory performed the analysis of REMP samples towards the end of 2005. The Pacific L Northwest National Laboratory processed the thermoluminescent dosimeters used for the REMP in 2005.

Quarterly averages of the monitoring results are compared to the NRC non-routine reporting levels L listed in the ODCM. In addition to evaluating the environmental concentrations against regulatory limits, the REMP also compares the results to state standards.(I l'12,13) The results are also evaluated by comparing them to similar measurements made during the preoperational and previous operational periods and to the detection capabilities associated with the current methods of analysis.

3.3 Program Objectives The REMP provides a mechanism for determining whether the levels of radioactivity in the plant environs are within established limits and to ensure that the accumulation of radionuclides in the environment will not become significant as a result of station operations.

While in-plant monitoring programs are used to ensure that 10 CFR 20(9) and 10 CFR 50(10) criteria for releases of radioactive effluents are met, the REMP provides verification of the effectiveness of these programs and confirms that the concentrations of radionuclides in the environment are not greater than anticipated.

L L

L.

L L

205 nua eor adolgca 32Enry nvromntlOpraig orbes/olnbaGeeatngSaLo 2005 Annual Radiological Environmental Operating Report 3-2 Energy Northwest/Columbia Generating Station

4.0 PROGRAM DESCRIPTION 4.0 PROGRAM DESCRIPTION The CGS ODCM defines the requirements for the REMP. The sampling plan presented in Table 4-1 in this report shows which samples are required by the ODCM and the Site Certification Agreement (SCA). The table also provides a summary of the sample locations, collection frequency, and types of analyses performed. The methods of sampling and sampling frequencies utilized in the program have been determined by such factors as the half-lives and major exposure pathways for the radionuclides potentially released from the plant to the surrounding environment.

4.1 Sample Locations Ninety-five sampling locations (referred to as 'stations') are included in the monitoring program.

Eighty-five indicator and three control stations are located within a 10-mile radius of CGS. Three additional control stations and four indicator stations are located outside of a 10-mile radius from the plant. Sample stations are listed in Table 4-2.

The locations of most of the stations used for sampling have been selected on the basis of an exposure pathway analysis. The exposure pathway analysis was based on factors such as weather patterns, anticipated emissions, likely receptors, and land use in the surrounding areas. Additional samples are collected at locations as specified by the SCA with the State of Washington Energy Facility Site Evaluation Council (EFSEC). Samples for the REMP collected from stations in areas that are likely to be influenced by CGS are used as indicators. Other samples collected from stations in areas that are not likely to be influenced by CGS serve as controls. The results from the indicator stations are compared to the results at the control stations, and also to the results obtained during the previous operational and preoperational years of the program.

The REMP sampling locations listed in Tables 4-1 and 4-2 are shown in Figures 4-1 and 4-2. Figure 4-3 shows the relative locations of the storm drain outfall and pond (Station 101) and the Sanitary Waste Treatment Facility (Station 102). Also shown are the cooling tower sediment disposal area (Station 119B and Station 119-Control) and the spray pond drainfield (Station 120), which are special interest stations.

4.2 Independent Spent Fuel Storage Installation (ISFSI)

The Independent Spent Fuel Storage Installation (ISFSI) was constructed to provide additional storage capacity for spent fuel. The spent fuel is stored in HI-STORM dry storage casks, which are placed on one of two concrete pads, each measuring 30-feet wide by 135-feet long. The ISFSI is located approximately 500 meters north-northwest of the reactor building.

REMP monitoring of the ISFSI is performed with a set of quarterly and annual TLDs located at 10 stations on the isolation fence surrounding the pads. In addition, two other stations are located on other fence lines. Station 121 is located on a fence line approximately 200 meters north of the turbine building and Station 122 is located on the fence approximately 100 meters north of the ISFSI.

Figure 4-4 shows the ISFSI location in relation to CGS. Figure 4-5 shows the location of the 10 TLD stations located around the ISFSI. This arrangement of TLDs in conjunction with the other monitoring activities that are conducted in support of CGS REMP, satisfies the monitoring requirements listed in 10 CFR 72.44(d)(2) for the ISFSI.

Energy Nordiwest/Columbia Generating Station 4-1 2005 Annual Radiological Environmental Operating Report

4.3 Land Use Census A land use census for areas within five miles of CGS is performed annually.'The objectives of the land use census are to identify the locations of the nearest milk animal, residence, and garden greater than 50 m2 (approximately 500 fl2) producing broadleaf vegetation. This information is used to determine whether any site located during the census has a calculated dose or dose commitment greater than the sites currently monitored for the same exposure pathway. If a new location with a higher dose commitment were found, routine sampling of that dose pathway would be initiated at that new site.

The results of the 2005 land use census within five milesof CGS-are presented in Table 4-3. No -

significant changes from the 2004 land use census were observed.

4.4 Sampling Methods Energy Northwest personnel collect environmental samples in accordance with the program plan in Table 4-1. Procedures for sample collection and TLD handling are contained in the department instruction manual. Samples that were collected for the REMP in 2005 were either shipped to Teledyne, or transported to the Energy Northwest Environmental Services Laboratory shortly after collection.

Generic descriptions of the sample analysis methods that are employed for the analysis of CGS REMP N samples are described in section 4.5. This section describes the sampling methods and sample locations.

4.4.1 Direct Radiation Direct radiation dose levels are mnonitored withý Har hawModel 8807 thernoluminesc~ent dosimeters (TLDs). Two sets of TLDs are placed in the field approximately three feet above the ground at each monitoring station. One set of TLDs is exchanged on a quarterly basis (Quarterly TLDs); the other is exchanged on an annual basis (Annual TLDs).

The locations of the TLD stations are listed in Table 4-2, and are shown in Figures 4-1, and 4-2. Station L 9A in Sunnyside, serves as a control for CGS TLDs. Station 119-Control serves as the control for Station 119B (the cooling tower/system sediment disposal basin). The remaining TLDs deployed in the field serve as indicator TLDs.,

The TLDs are arranged in a series of rings that.encircle, CGS. The innermost ring of TLD stations, which are located inside the fence line at distances that range from 0.3-0.8 miles from the reactor centerline, are referred to as the 'S stations.' The next group of TLDs, which are located outside of the fence line, are called the inner ring. The inner. ring TLDs are located at distances that range from around 1-2 miles from the reactor. The outer ring of TLDs are located at distances that range from a little under three (3) miles out to around ten (10) miles.

A Reuter-Stokes pressurized ion chamber (PIC) is maintained as a backup monitoring system to provide additional capability for measuring direct radiation exposure. This unit is no longer part of the routine monitoring programn, but may be used in special monitoring situations.

2005 Annual Radiological Environmental Operating Report 4-2 Energy Northwest/Columbia Generating Station

4.4.2 Airborne - Particulate/Iodine Air particulate and air radioiodine (1-431) samples are obtained through the use of low volume (1.5 cfm), constant flow-rate sampling units at 12 locations. The samples drawn at Station 9A (Figure 4-2) are considered controls,.the samples drawn at the other locations (Figure 4-1) are indicators.

Air particulate samples are collected byodrawiig air through a 47-mm diameter glass fiber filter. Air iodine samples are collected by dr*wipg ai through Radeco CP-100 TEDA impregnated charcoal cartridges. The air particulate filter and charcoal cartridge are placed in tandem, particulate filter first, in a holder that attaches to the air inlet of the sampler unit. The sampler units are placed in ventilated metal weatherproof housings mounted on elevated platforms at each air sample location. The filter media are changed weekly.

4.4.3 Water There are nine locations where wate" sampling is performed for the REMP. They are categorized as follows:

o Intake-River/Drinking Water; two locations (Stations 26, and 29) o ,,Groundwater; three locations (Stations 52,31, and 32)

• Plant Discharge Water; one location (Station 27)'

• Storm Drain Water; one location (Station 101)

" Sanitary Wastewater; two locations (Stations 102A, and 102B)

The sample at Station 26 is drawn from the (plant intake water which comes from the Columbia River.

Station 26 is upstream from tliý plant discharge soitfim the background; or control. The drinking water for CGS comes from this intake water so this sample also serVes'as a,drinking water sample.. Station 29 is located at the Richland Water Treatment Plant, 11 miles downstream from the discharge and is the indicator station for both ni ier and diinkiig water.'

The ODCM requirement ýfor a downstream water-sample I"near but beyond the mixing zone" is conservatively met by sampling water from Station 27, the cooling tower discharge line to the Columbia River. This sample reflects the radioactivity present in the plant discharge prior to any river dilution, rather than thecttceentrations that would be found after dilution in'the mixing zone.

The Station 27 sample is afi indicator. Composite sampiers'are, used to collect samples at Stations 26, 27, and '29. The samplersjcollect 25-ml hliquots'ofwaterat regular intervals. Samples are collected

-monthly at each of these stations and are analyzed for gamma, gross beta, and tritium.

Three wells within the vicinity of CGS are used as groundwater sampling locations. These include a deep well on CGS site (Station 52, 0.1 mile north of the reactor building) and two wells on the WNP-1 site (Station 31 and Station 32, 1.2 miles downgradient from CGS). Water from CGS well'can be used as a backup source for drinking water and fire protection. The WNP-1 wells supply water for drinking and fire protection at the WNP-1 site. All of these wells are considered indicator locations. Quarterly grab samples are collected from each of these wells and are analyzed for gamma emitting radionuclides and tritium.

Water samples are collected monthly from the storm drain outfall (Station 101) using a flow-proportional composite sampler. These samples are analyzed for gross beta, gamma, and tritium.

Energy Northwest/Columbia Generating Station 4-3 2005 Annual Radiological Enviromnental Operating Report

The SWTF receives wastewater from the DOE 400 Area. A flow meter and composite sampler is located on the 400 Area sewer line just above the 400 Area/Plant Support Facility (PSF) intertie (Station 102A). The sampler collects aliquots of the effluent on a timed basis, the composite sample that is produced is analyzed monthly as required by EFSEC Resolution No. 300.(15) A portion of the water used in the 400 Area is drawn from aquifers that are contaminated with tritium as a result of DOE activities on the Hanford Site, consequently, the water sampled at Station 102A has tritium ý concentrations above 2000 pCi/L. Another automatic water sampler is located at the headworks of the SWTF (Station 102B) where a monthly composite sample is taken. Both sample locations are analyzed for gross alpha, gross beta, tritium, and gamma emitting radionuclides.

4.4.4 Soil Annual soil samples are collected at the indicatorStations, 1, 7, 21, and 23 as required by the SCA L (EFSEC Resolution No. 260(6)). A sample is alsolcollected at the control location, Station 9A (Figure 4-2). Each sample is collected from an area of approximately one square foot to a depth of approximately one inch. About two kilograms of soil are collected for each sample.

Soil samples are analyzed for gamma activity. If the Cs-137,1evel in an indicator sample exceeds ten (10) times the level in the control sample, strontium analysis is required.

4.4.5 Sediment -

River sediment samples are collected in the, spring and fall. The upstream sediment sample location (Station 33) is approximatelytwo miles upriver from the plant discharge.-, The downstream sample (Station 34).is collected approximately one mile downstream from the plant discharge. Each sample consists of approximately two kilograms of the shallow surface sediment scooped from below the waterline. . towers.

Cooling tower sediment samples are collected, dried, and analyzed per EFSEC Resolution No. 299( "

(Station 119B, Figure 4-3) within thirty days of the completion of cleaning the cooling towers.

Wastewater sludge/sediment samples are collected annually at Station 102D (the SWTF). All sediment samples are analyze4 for gamma activity. ,,

4.4.6 Fish Annual fish sampling is performed in the late summer and fall. Fish samples collected from the Columbia River (Station 30 in Figure 4-1) are indicator samples, whereas fish collected on the Snake River (Stations 38 and 38A in Figure 4-2) serve as control samples.

Three categories of fish samples are collected, an anadromous species (either a salmon or steelhead),

and the two other species generally considered edible or potentially edible (such as carp, catfish, sucker, and whitefish) are collected at each location. Electro-shocking and netting is used for fish collection, except for the samples of the anadromous species, which are collected at the fish hatcheries.

2 2005 Annual Radiological Enviromnental Operating Report 4-4 Energy Northiwest/Cohanbia Grenerating Station LU

4.4.7 Milk Milk samples are collected monthly during the fall and winter months (October through December).

During the spring and summer months when cows are likely to be grazing, or on fresh feed, milk samples are collected twice each month. Enough raw milk is collected from each sampling location to obtain a one-gallon sample after the cream has been skimmed off. The milk samples are chilled and then either taken to the laboratory for analysis or shipped to the analytical contractor within a day of collection.

Milk samples were collected in 2005 from two locations, Station 36, and Station 9B. Station 36 is in Franklin County and is the only dairy within a ten mile radius of CGS that will allow REMP personnel to obtain samples; Station 9B is in the Sunnyside/Grandview area (Figure 4-2). Station 9B has been used primarily as a control location; at times it was also an indicator station, because a portion of the feed used there came from Franklin County whichis downwind from CGS. To account for this discrepancy of having some feed-grown in the *indicator-location being fed to the control location cows, samples of feed grown at Station,9Bwere collected monthly when it was available and labeled as

'Station 9G' to serve as the control.. In June of 2005, the dairy where the control sample feed and indicator/control milk samples had been collected closed, however, at the same time a new milk sampling location a short distance from the old 9B was obtained. There are no other dairies available for sampling within the 10-mile radius 0f the-plant. .

4.4.8 Garden Produce Samples of localgarden produce are collected monthly during the growing season when the produce is readily available. When possible,'three types of prodcuc-,sahrples,(a toot crop,- fruit, and a leafy vegetable) are collected at ekh lodation. The indicator samples are ollected from a region in the predominantly downwind direction (Station 37) where crops are irrigated with Columbia River water.

The control samples are obtained from produce stands in the Sunnyside area (Station 9C in Figure 4-2),

the direction least likely to be affected by plant effluents. Apples are collected in late summer or early fall from Station 91, the Rio Vista Farms-6rchard, which is irrigated with Columbia Riveriwater.

During 2005, a broadleaf vegetable sample was grown in a garden that was planted next to the SWTF.

The garden was named' Station 102G, 'and was planted specifically to produce samples that could be analyzed for the REMP. The garden does not meet the criteria in the ODCM to iiiake it a required sampling location, however, a sample was collected from it and analyzed.

4.5 Sample Analyses General descfiptions'of he procedures used for the analysis of the REMP TLDs and samples are provided in the following sections. The REMP TLDs are processed by Battelle at the Pacific Northwest National Laboratory (PNNL). Sample analyses for the REMP were performed by Teledyne Brown Engineering - Environmental Services for the first eight (8) months of the year; analyses for the last four (4) months of the year were performed by Energy Northwest Environmental Services. The analysis methods for REMP samples used by Teledyne and Energy Northwest are almost identical. Details of the differences between the laboratories are provided in the following text. Sample holding times prior to analysis for most sample types are kept as short as possible in order to ensure that the LLD requirements for shorter lived radionuclides are met with reasonable counting times. In samples where very long lived isotopes are the only isotopes of concern, longer sample holding times are permitted.

Energy Northwest/Columbia Generating Station 4-5 2005 Annual Radiological Environmental Operating Report

4.5.1 Analysis of TLDs U The REMP TLDs are measured at the Pacific Northwest National Laboratory (PNNL) on a Harshaw Model 8800 hot gas reader. The reader is calibrated weekly and immediately prior to processing the environmental TLDs. The reader is calibrated with TLDs'that have been given a known exposure from U

a Cs-137 source. Each group of environmental TLDs is processed with blank (freshly annealed) TLDs and spiked TLDs that have been given a known exposure. Exposure received by the field TLDs during transport is monitored with a set of 'trip' control dosimeters that accompany the field dosimeters to and from the field locations and while they are in storage. Another set of TLDs, the building controls, are used to determine the exposure of the TLDs at the storage location. The TLD exposure during transport to and from the field was determined from the difference between the building control results and the trip control results.

4.5.2 Gross Beta Activity on Air Particulate Filters Air particulate filters are counted in a gas flow-proportional counter after a delay of several days to allow for the decay of radon and its progeny. Air particulate filters are counted directly with a sufficient count time to meet the LLD requirements. However, the LLD for air particulate samples is generally not applicable as all valid air samples collected have yielded measurable beta results. .

4.5.3 Measurement of Gamma Emitting Radionucides Shielded, high purity germanium (HPGe) detectors are used to assay environmental samples to quantitatively determine concentrations of gamma emitting radionuclides. Samples are counted in a L

standardized geometry; some samples are measured directly and others are loaded into Marinelli II beakers.' Samples ate counted for a sufficient imeý to reAch the required'LLLDs.

" Liquids - Measured aliquots ofrliquid:samples are poured into appropriately sized Marinelli beakers. Results are reported in pCi/L. U

" Solids - Soils, sludges, and sediments are dried and if needed ground& Foodstuff, biota (fish), LI and vegetation, are chopped finely or pureed and then analyzed wet (no drying is done). For foodstuff (including fish); only ithe edibl6'po6it'i of the sample isu sed.: Measured aliquots of the solid samiples (0.56ir 1.0 liter'tepieding on sample te, anadsample quantity) are placed into tared Marnelhibeakers atdweighed.- Results are reported i pCilkg.

• Charcoal Cartridges - Asmany, as five charcoal cartridges may beco3tited simultaneously with one positioned on the face of the detector and up to four on the sides' of the detector in a cartridge holder. -The detector is calibrated for both positions. The reportable sample activity for each charcoal cartridge is calculated (assuming no positive 1-131) uniquely for each cartridge from the volume of air that passed through it, and the reported activity for the group of U

cartridges. If 1-131 is measured in the assay of a group, each charcoal cartridge in the group would then be assayed separately. A collection efficiency of 98% for iodine is used in the activity calculations. Results are reported in pCi/m 3.

• Air Particulate Filters - At the end of each quarter, AP filters from each station are composited on a station by station basis. The filters are stacked in a Petri dish and assayed. Results are reported in pCi/m3 and represent the total quarterly gamma activity collected at each station.

2005 Annual Radiological Environmental Operating Report 4-6 Energy Northwest/Columbia Generating Station

4.5.4 Gross Alpha and Gross Beta Activity in Water A measured aliquot of each sample is evaporated to a small volume in a beaker and rinsed into a 2-inch diameter stainless steel planchet that is stamped with a concentric ring pattern to distribute residue evenly. The final evaporation of the sample is done under heat lamps, on a hot plate, or in a drying oven. Residue mass, is determined by weighing the planchet before and after mounting the sample. The planchet may be -counted for alpha and beta activity, or for just beta activity depending on the required results for the sample. An automatic proportional counter is used for gross alpha and gross beta measurements. The results are calculated using self-absorption curves that correct for the change of effective counting efficiency caused by the sample residue.

4.5.5 Tritium in Water The sample is distilled and the distillate is collected for analysis with a liquid scintillation counter.

Approximately 10 ml of the distillate is mixed with 10-15 ml of liquid scintillation cocktail. The mixture is then counted in an automatic liquid scintillation analyzer.

4.5.6 Strontium-89 and 90 in Soil The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrochloric acid. After filtering the mixture, strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO 3)2 using fuining (90%) nitric acid. A barium chromate scavenge and an iron (feric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sampleis allowed to stand for five days or more for yttrium ingrowth. Yttrium is then precipitated as hydro)ýde, dissolved and r=-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and counted infalow-leye! beta counter to infer Sr-90 activity. Sr-89 activity is determined by precipitating SrCO 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and covered with an 80 mg/cm2 ,aluminym~absorber for low-leyel beta counting.

4.5.7 Low Level Iodine-131,in Milk and Water Up to four (4) liters of satple are first equilibratedwith stabl iride c er. A batch treatment with an anion exchange resin is uspd to remove iodine from the sample, At the Energy Northwest laboratory, the resin is loaedintoa fpur (4) oz. container and counted directly by gamma spectroscopy. At Teledyne, the iodine is eluted from the resin with a sodium hypoclorite solution, reduced with hydroxylamine hydrochloride, and extracted into carbon tetrachloride as free iodine. ttjs then back-extracted as iodide into a sodium bisulfite solution and precipitated as palladium iodide. The precipitate is weighed for chemical yield and mounted on a nylon planchet for low-level beta counting.

The chemical yield is corrected by measuring the stable iodide content of the milk with a specific ion electrode.

4.6 Data Analysis Methods Since mid-1984, the results of the REMP analyses have been presented as net results calculated from the gross or total counts determined for each radionuclide minus the background counts of the counting or detection instrument. Consequently, the results range from negative to positive numbers in samples where the analytes of interest are sometimes not detected. This manner of presenting environmental data prevents the positive bias and loss of individual results inherent in the use of "less than" (<) values.

Energy Northwest/Colurnbia Generating Station 4-7 2005 Annual Radiological Environmental Operating Report

A listing of the Teledyne and Energy Northwest nominal target LLDs for each sample type is provided in Table 4-4; the ODCM required LLDs are also included for a comparison. The actual LLDs may vary due to sample holding time and available sample volumes. In most cases Energy Northwest LLDs have been selected to match those of Teledyne; in some cases the LLDs foi Energy Northwest are lower.

Plots of the sample results versus time are used to represent the results for analyses such as gross beta on air particulate filters, where the results are normally above the detection limit. In such cases, the indicator station results are plotted with the control station results for easy comparison. Other data analysis techniques are also used to evaluate whether trends that could be attributed to CGS operations are evident.

Thermoluminescent dosimeter (TLD) data is presented in terms of the net mrem/day exposure rate.

These results are determined from the total exposure (in mrem) calculated for each TLD minus the TLD background and any transit (or trip) exposure received during distribution and retrieval, and divided by U

the number of days the TLD was in the field. The total mrem/standard quarter and mrem/year values are also reported.

The quarterly TLD results are compared with the annual TLD results and expressed as a ratio by dividing the sum of the quarterly results over the annual results. The agreement between the two sets is usually within plus or minus ten percent (10%); occasionally fade can be more significant than expected in the annual set and the results may be lower than the sum of the quarterly data. A 4.7 Changes to the Sampling Program in 2005 A new control sampling location for milk in Sunnyside was obtained a short distance from where feed sampling had been performed in lieu of milk sampling previously. The number designation for the new control station was retained (9B); the reference name for it changed from "Meeker" to "Scheenstra." The old control location was terminated when the farm got rid of the last cow. The new control station is a significant improvement; the sample collected there is milk produced by cattle that feed exclusively on material grown in the control area. Milk samples were collected at the previous location (Meeker), but the feed that the cows were given there was sometimes grown in the indicator location; this made the milk samples obtained there ambiguous and not consistently representative of either a control or an indicator. As a result of this ambiguity, feed was collected to use as the control.

2005 Annual Radiological Environmental Operating Report 4-8 Energy Northwest/Columbia Generating Station

TABLE 4-1 RADIOLOGICAL. ENVIRONMENTAL MONITORING PROGRAM PLAN SAMPLE SAMPLE STATION

• SAMPLING AND COLLECTION TYPE AND FREQUENCY OF TYPE(') NUMBER FREQUENCY() ANALYSIS 1.AIRBORNE Particulates and 1, 4-8, 9A, 21, 23, 40,48, and 57 Continuous sampling; weekly collection Particulate: Weekly gross betae; gamma radioiodine isotopic(* of quarterly composite (by (6/12)(d' location)

Iodine: Weekly gamma analysis.

Soil'"(0/5) 9A, 1, 7, 21 and 23 Annually Gamma isotopic(Q; Sr-90(h)

2. DIRECT RADIATION TLD(i)(34/72) 1-8 9A 10-25, 40-47,49-51,53- Quarterly, annually Thermoluminescent output; quarterly and 56,,65, 71-86( 1S- 16S)0),;l1 i9B, annual processing.

119-Control, 120,121-129, 136A-138A PlC, Various locations, as fieedMdM Continuousirecording, as needed Exposure rate accumulated in internal memory

3. WATERBORNE River/Drinking 2-6 27 and 29 Composite aliquots(m); monthly collection Gamma isotopic(t, gross beta, quarterly; Water?) (3/4) tritium composite; Sr-90('); 1-131 (°)

Storm Drain 101 ,omposite aliquotstw), monthly collection; Gamma isotopic(t ), tritium, gross beta Water(0/l) , Igrabsamples-Sanitary Waste 102A, 102B Composite aliquots(), monthly collection Gamma isotopic(°, gross beta, gross alpha, Treatment tritium Facility Water (0/2)

Ground Water 31,32, and 52 Quarterly Gamma isotopic(0; tritium (2/3)'P) . .' j*.i River Sediment 33 and 34 Semiannually Gamma isotopict ý (l/2)q) .

Sanitary Waste 102D ,Annually Gamma Isotopic(0 Treatment Facility Sediment (011) .

Cooling Tower 119B Within.Odays folloWingCooling , Gamma Isotopic()

Sediment Tower cleaning event Disposal Area (0/1)

4. INGESTION MiIV) (3/3) 2BV), 29G), 36 Semimonthly during grazing season, monthly Gamma isotopic(t; 1-131; Sr-90(')

at other times Fish(') (2t2) 30,.U Annually (v) Gamma isotopic(O Garden 29,. 91,(x) 37, 102GOv Monthly during growing season in the Gamma isotopic(t Produce(w)(1/4) Riverview area of Pasco and a control near Grandview; annual collection at Station 91.

FOOTNOTES:

(a) The fraction in parentheses for each sample type indicates the ratio of ODCM-required sample locations to the total number of sample locations currently being monitored in the surveillance program. The SCA also requires certain numbers of sampling stations for each type of media.

(b) The underlined sample location designates a control station.

(c) Deviations are permitted if samples are unobtainable due to hazardous conditions, seasonal availability, malfunction of automatic sampling equipment, or other legitimate reasons. Such deviations are documented in Section 5.

Energy Northwest/Columbia Generating Station 4-9 2005 Annual Radiological Environmental Operating Report

FOOTNOTES (con..:

(d) The SCA requires nine or more air sampling stations.

(e) If gross beta activity is greater than 10 times the mean of the result for the control, Station 9A, gamma isotopic analysis shall be performed on the individual sample.U (M Gamma isotopic means identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents of CGS.

(g) Soil samples are collected to satisfy the requirements of the SCA for CGS. The SCA requires that soil samples be collected at five air-sampling locations.

(h) Sr-90 analysis shall be performed on any indicator soil sample having cesium results greater than ten times the result for the control location.

(i) TLD an abbreviation for thermoluminescent dosimeter.

(j) TLD Stations 71-86 are not included among the 34 routine TLD stations required by the ODCM Table 6.3.1-1. Their alternate designations are IS-16S. The SCA requires 25 ormore TID stations to be located within a 10-mile radius of the plant (k) Pressurized ion chambers (PICs) are required by EFSEC Resolution No. 260 to be maintained as a supplemental or backup system.U (1) The term "river/drinking water" is used throughout this report because the drinking water is taken from the Columbia River. Station 26, CGS makeup water intake from the Columbia River is both an upstream water sample and the drinking water sample location. Station 29 is a downstream drinking water sample. The Station 27 sample, which is drawn from the plant discharge line, is taken in place of a "downstream" water sample near but beyond the mixing zone. It reflects the radioactivity present in the plant discharge prior to any river dilution. The SCA requires two drinking water locations downstream from the plant discharge and requires sampling from the plant intake and discharge water.

U Only one drinking water station is now sampled after DOE closed the intake at the 300 Area (Station 28) in 1998.

(in) Composite samples are collected with equipment that collects an aliquot at time intervals that are short relative to the compositing period.

(n) When the gross beta activity in drinking water exceeds 8 pCi/liter, a Sr-90 analysis is performed.

(o) When the dose calculated via ODCM methodology for consumption of water exceeds I mrem per year, low level 1-131 analyses are performed on the drinking water samples.U (p) The SCA requires sampling from wells used for fire protection and as backup drinking water sources.

(q) The SCA requires sediment sample collection upstream and downstream of the plant discharge.

(r) Milk samples will be obtained from farms or individual milk animals that are located in the most prevalent wind directions from CGS. The SCA requires at least three milk locations within the 10-mile radius of the plant and one in a control location, however, Energy Northwest currently has accesý to only one dairy within a 10-mile radius of the plant (Station 36) and one control location at 30 miles. Broadleaf vegetation is sampled in lieu of milk when available.

(s) Samples of feed for dairy animals were collected in lieu of milk at a control station (Station 9G) for the first halfof 2005. The dairy cattle at Station 9B were not suitable for use as a control prior to June of 2005 because a portion of their feed came from a portion ofFranklin County which is an indicator region for CGS. Station 9B was moved a short distance in June of 2005 and became the new sample control location for milk, at the new location dairy cattle are only given feed grown in the control location (Sunnyside).

(t) If Cs-134 or Cs-137 is measured in an individual milk sample in excess of 30 pCi/l, then the Sr-90 analysis will be performed.

(u) There are no species fished commercially in the Hanford Reach of the Columbia River. The most recreationally important species in the area are anedromons, which ascend rivers fromý the ocean for breeding. Anadromons fish species are normally obtained frora hatcheries; Snake River samples are obtained from the Lyons Ferry Fish Hatchery, and Columbia River samples are obtained at the Ringold fish Hatchery.

(v) If an impact is indicated, sampling will be conducted semiannually.

(w) Garden produce will routinely be obtained from farms or gardens using Columbia River water for irrigation when available. One sample of a root crop, leafy vegetable, and a fruit is collected each sample period, if available. The variety of the produce obtained will be dependent on seasonal availability.

(x) Station 91 is an apple orchard irrigated with Columbia River water. The apple crop from Station 91 is sampled annually.

(y) Station 102G was used to collect one sample. This station does not meet the ODCM criteria for a garden which requires sampling; it was used to provide a broadleaf sample that was grown inside the 5-mile radius from the plant.

2005 Annual Radiological Environmental Operating Report 4-10 Energy Northwest/Columbia Generating Station

TABLE 4-2 REMP SAMPLE STATIONS AND REQUIREMENTS STATION()

SECTOR(& NUMBER DISTANCE() ODCMt4 ) STATE(* OTHER()

N (1) 52 0.07 GW 71(1S) 0.28 TLD 47 0.70 TLD 57 0.70 AP/AI 18 1.16 TLD, TLD 53 7.54 TLD NNE (2) 72(2S) 0.32 TLD 2 1.45 TLD TLD 54 6.08 TLD NE (3) 101 0.19 .SW 73(3S) 0.54 TLD 19 1.74, TLD TLD 48 4.59 AP/AI 46 4.99 TLD ENE (4) 74(4S) 0.38 TLD 21 1.45 TLD, AP/AT, SO 20 1.93 TLD TLD 11 3.16 TLD 33 3.44 SE 45 4.45 TLD 44 5.90 TLD,.

E (5) 75(5S) 0.37 TLD 22 2.08 TLD 10 -3.16 TLD TLD 26 3.19 SW, DW SW 27 3.19 DisW 30 3.28 FI FI 43 5.16 ' TLtD ESE (6) 76(6S) 0.42 TLD 31 1.06 GW GW 32 1.27 oW 51 2.14 TLD 23 3.03 TLD, AP/AI, SO 34 3.32 SE SE 8 4.39 TLD, AP/AI TLD, AP/AI 91 4.30 GP 42 5.85 TLD 36W 7.33 MI MI 4-11 2005 Annual Radiological Environmental Operating Report Generating Station Northwest/Columbia Generating Energy Northwest/Columbia Station 4-11 2005 Annual Radiological Environmental Operating Report

TABLE 4-2 (cont.)

REMP SAMPLE STATIONS AND REQUIREMENTS STATIONO)

SECTOR(,) NUMBER DISTANCE)° ODCM~) STATE&') OTHER()

U ESE (6)(cont.) 5 7.72 TLD AP/AI 38 26.50 Fl Fl SE (7) 77(7S) 0.57 TLD 24 3

1.87 2.06 TLD TLD TLD U

41 5.79 U

TLD 40 6.51 TLD, AP/A]

SSE (8) 119-Control 0.28 TLD 120 102B 0.32 0.50 SFW TLD U

102D 0.50 SFW, SE 102G 78(8S) 0.56 0.81 GP TLD U

4 25 55 1.50 6.05 9.57 TLD TLD TLD, AP/AI TLD TLD, AP/AI U

29 11.57 DW DW 37B 14.79 oP GP S(9) 37A 119B 102A 1,4.62 0.31 0.67.

OP TLD. SE SFW U

79(9S) 0.76 TLD 1 .1.25 TLD TLD, AP/AI, SO 6 7.72 TLD AP/AI 65 8.87 TLD SSW (10) 80(10S) 0.83 TLD 50 1.26 TLD RLD 56 6.65 TLD SW (11) 13 1.26 'LD 'LD WSW (12) 81(11S) 82(12S) 0.74 0.57

'LD TLD U

14 9A 1.26 28.35 TLD TLD, AP/AI TLD TLD, AP/A] V 9B, 9G 32.82 NMl,VEO) MI, VEoh)

W (13) 9C 83(13S) 32.15 0.52 GP GP TLD

£ 15 1.24 TLD TLD WNW (14) 84(14S) 0.55 TLD 2005 Annual Radiological Environmental Operating Report 4-12 Energy Northwest/Columbia Generating Station

TABLE 4-2 (cont.)

REMP SAMPLE STATIONS AND REQUIREMENTS STATION(b)

SECTOR(*) NUMBER, *DISTANCE(t )... .ODcM(d) STATE(e) OTHER(0 WNW(14) (cont.) 16 1.2i TLD TLD 7 2.83 TLD TLD, AP/AI, SO NW (15) 85 (15S) 0.43 TLD 49 1.19 TLD TLD NNW (16) 121 0.12 TLD TLD 122 0.31 TLD TLD 123 0.29 TLD TLD 124 0.28 TLD TLD 125 0.28 TLD TLD 126 0.28 TLD TLD 127 0.26 TLD TLD 128 0.25 TLD TLD 129 0.17 TLD TLD 136A 0.29 TLD TLD 137A 0.24 TLD TLD 138A 0.17 TLD TLD 86(16S) 0.31 TLD 17 1.19 TLD TLD 12 .6.74 TLD ISAMPLE TYPE KEY:

AP/AI - Air Particulate/Air Iodine DW - Drinking Water Dis W - Discharge Water Fl-Fish GP - Garden/Orchard Produce GW - Ground Water MI - Milk SE - Sediment SFW - Sanitation Facility Water SO - Soil SW - Surface Water TLD - Thermoluminescent Dosimeter VE - Vegetation FOOTNOTES:

(a) The area in the vicinity of CGS is separated into 16 sectors for reporting purposes. The 16 sectors cover 360 degrees in equal 22.5 degree sections, beginning with sector 1 (N) at 348.75 to 11.25 degrees and continuing clockwise through sector 16 (NNW).

(b) The alternate designations for TLD Stations 71-86 are given in parentheses, i.e., 1S-16S.

(c) Distances are from GPS positions for each location as a radial distance from CGS reactor building.

(d) ODCM - Offsite Dose Calculation Manual Table 6.3.1-1 requirement.

(e) State of Washington SCA requirements.

(f) OTHER -Special study stations. TLD Stations 121 through 138A satisfy ISFSI monitoring requirements 10CFR72.44(d)(2).

(g) Duplicate samples, i.e., samples drawn at the same time as the routine samples and submitted for analysis as a quality control check, are collected at this location. The station designation for the duplicate of Station 36 is Station 37.

(h) Broadleaf vegetation collected in lieu of milk from a control station.

Generating Station 4-13 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Northwest/Columbia Generating Station 4-13 2005 Annual Radiological Environmental Operating Report

TABLE 4-3 2005 FIVE-MILE LAND USE CENSUS RESULTS NEAREST GARDEN DAIRY Lil SECTOR(a) RESIDENTO) (>50M2 ) ANIMALS LIVESTOCK NE 4.47 none none none L ENE 4.01 none none 4.96 E 4.59 none none none ESE SE 4.24 none none none none none none none U

FOOTNOTES U (a) Within a five-mile radius of the plant, only 4.5 sq. miles of the land in the sixteen meteorological sectors is privately owned farmland. The remainder of the land is on the federally owned Hanford Site. Only those sectors containing points of interest are presented here.

U (b) Estimated distances in miles from CGS Reactor Building based on GPS readings.

U U

U 2

2005 Radiological Environmental Aanual Radiological 2005 Annual Operating Report Environmental Operating Report 4-14 4-14 Energy NorthwestlCohmibia Generating Station Energy Northwest/Columbia Generating Station U

TABLE 4-4 COMPARISON OF LABORATORY NOMINAL LOWER LIMITS OF DETECTION WITH OFFSITE DOSE CALCULATION MANUALO8 ) REQUIREMENTS TELEDYNE ENERGY ODCM REQUIRED MEDIA (UNITS) ANALYSIS LLDs(a) NORTHWEST LLDs(c) LLDs Air Gross Beta 0.003 0.003 0.01 (PCl/m3) Gamma Spectrometry Cs-134 0.001 0.001 0.05 Cs-137 0.001 0.00 0.06 1-131 0.01 0.05 0.07 Water: Gross Beta 4 2 4 (pCi/L) Tritium 300 300 2000()

1-131 1 1 --

Sr-90 1 1 --

Gamma Spectrometry Mn-54 10 10 15 Fe-59 20 20 30 Co-58 10 10 15 Co-60 10 10 15 Zn-65 20 20 30 Zf-95 15 15 15 Nb-95 10 10 15 Cs-134 10 10 15 Cs-137 10 10 18 Ba-140 15 15 15 La-140 10 10 15 Soi/Sediment: Gamma Spectrometry (pCi/kg dry) Co-57 120 120 --

Co-60 30 30 Zn-65 100 100 -

Cs-134 30 30 150 Cs-137 40 40 180 Sr-90 10 10 -

Fish: Gamma Spectrometry (pCi/kg wet) Mn-54 20 20 130 Fe-59 30 30 260 Co-59 20 20 130 Co-60 20 20 130 Zn-65 30 30 260 Cs-134 20 20 130 Cs-137 20 20 150 Milk: 1-131 0.5 0.5 1 (pCl/L) Gamma Spectrometry Cs-134 10 10 15 Cs-137 10 10 18 Ba-140 15 15 15 La-140 10 10 15 Sr-90 I I Garden Produce: Gamma Spectrometry (pCi/kg wet) Cs-134 20 20 60 Cs-137 20 20 80 1-131 30 30 60 (a)These are the contract LLDs; actual LLDs may be higher or lower for specific samples.

(b)If no drinking water pathway exists, a value of 3,000 pCi/L may be used.

(c)These are the nominal target LLDs for the analyses performed in the Energy Northwest Environmental Services Laboratory.

Station Generating Station 4-15 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Northwest/Columbia Generating 4-15 2005 Annual Radiological Environmental Operating Report

FIGURE 4-1 REMP SAMPLING LOCATIONS INSIDE THE 10 MILE RADIUS 2005 Annual Radiological Environmental Operating Report 4-16 Energy Northwest/Columbia Generating Station

am -- " w m la m 40 a m - " sm -

-17 1lu 7r 4, Nk A ni CD m

!CD ROY111' C tY S L It .

z 0 -V4 CD 0 M 0 4 T A N L' 0

0~ Hat J, CD A woaht u0m r VLOW DC rj DD w uve PAFk i10 AIAVA) A _J77 rf 0G n

K I" U4, 0 mile dius molm. 1000 ST38A call 0 000 I I 1C[

iCFItzl CST2 Ittbul 0

ST9B ST34, Idqý L ST9C ST9A Ham. 4't 0

ut SIC ni roi~rN t .0N Ken UC0 4 I

0 CD TNImN 0

o 5 10 15 t

20 Fin$__"I 1,5 25 30 25mk 35 40 km REFU 0

Pdnted ftm TOMO 0200 Naticual Geogmplbic Holffip (www topo corn)

FIGURE 4-2 REMP SAMPLING LOCATIONS OUTSIDE THE 10-MILE RADIUS (NOTE: Station 38A is the Lyons Ferry Hatchery)

COt

I I

i I

I I

I 5

I I

I I

I I

I FIGURE 4-3 REMP NEAR PLANT SAMPLING LOCATIONS II STATION 102A (APPROXIMATELY 0.25 MI SOUTH). STATION 102 IN PICTURE IS BOTH 102B, 102D AND 102G.

I 2005 Annual Radiological Environmental Operating Report 4-18 COZ-Energy Northwest/Columbia Generating Station I

II

4A

.......... , SCALEINFEET mmim m im m I GIE NF U

ioi FIR I

PARKINGL 1ý l l I Z POECIMICAVNrCG S NPA IIELmmIRICAL SGNE RC,!j

/ ELI II iiI I

• +,*. +* .it' ""

m ------A -H -

,DELARY]FOY PARLING

• g I'U 0301 25 Ron Wick REV 33 Apr 2003 FIGURE 4-4 TLD STATIONS 121 AND 122 Energy Nordiwest/Columbia Generating Station 4-19 2005 Annual Radiological Environmental Operating Report

I- 250 It ST. 123 "* ST."124 ST. 125

'0" Isolation Fence Security Fence r-- ----------------------------------

Electrical Cntrl Bldg ,

135 ft ST.126 + + ST.127 0

0

20. Dry Fuel Cask ST.128 I + ST.129 II_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _,

ST. 136A ST.*137A ST.138A

+ REMP TLD FIGURE 4-5 ISFSI TLD STATIONS LAYOUT 2005 Annual Radiological Environmental Onerating Report 4-20 Energy Northwest/Columbia Generating Station

5.0 RESULTS AND DISCUSSION 5.0 RESULTS AND DISCUSSION For the first three quarters of 2005, REMP samples were analyzed by Teledyne Brown Engineering Environmental Services (TBE-ES) in Knoxville, Tennessee. For the latter portion of the third quarter and the fourth quarter of 2005, samples were analyzed in the Energy Northwest Environmental Services Laboratory using nearly identical methods to those employed by Teledyne to prevent any sudden shifts in the analysis results. The environmental TLDs were analyzed at the Pacific Northwest National Laboratory (PNNL). Table 5-2 provides a summary of the REMP results for 2005; the results for naturally occurring radionuclides that are not related to CGS operations have not been included in the summary table. The nominal lower limits of detection (LLDs) listed in Table 5-2 are the ODCM or EFSEC required detection limits and are not the method detection limits. The data tables of the 2005 results which include the measured naturally occurring radioisotopes comprise a separate volume that is available to interested parties upon request.

The analytical data for the preoperational period and the first six months of 1984 included "less than" (<) designations for results below the actual LLD, the contractual LLD, or the two-sigma error, depending upon the convention employed by the analytical contractor. Consequently, the data averages using "less than" values are biased high. Since mid-1984, REMP data have been reported as net results (i.e. the detector counting background is subtracted from the gross results).

The analytical results for the REMP sampling locations during 2005 are very similar to the results reported for previous years. No significant trends indicating an environmental impact, or unexpected change in the environmental concentrations, or exposure levels at REMP monitoring stations were observed.

5.1 Direct Radiation The environmental radiation exposure rates measured near the plant and at remote stations were consistent with the rates seen in previous years. The results for the NNW sector were above the long term average; this was also the case last year and is attributable to the ISFSI. No additional spent fuel storage casks were placed in the ISFSI during 2005 and a gradual decrease in the dose rates measured in the quarterly TLDs near the ISFSI was seen.

Figure 5-1 presents a plot of the 2005 mean quarterly TLD results for each of the sixteen meteorological sectors near the plant, the "S" stations are located at distances of 0.3-0.8 miles from the reactor and are all inside the property boundary. The chart also includes the high, low, and mean result in each sector for 1984 through 2004. The TLDs in the N, NNE, and NNW sectors show higher exposures rates than other "S" stations as a result of being physically closer to the plant and from the increases caused by the ISFSI.

Energy Nordiwest/Columbia Generating Station 5-1 2005 Annual Radiological Environmental Operating Report

U 0.36 Figure 5-1 Site Boundary Quarterly TLDs 1984-2004 Hi/Low/Mean vs. 2005 Mean by Sector U 0.34 0.32 U

0.30 0.28 U

0.26 0.22 0.20 U

0.18 0.16 U

0.14 N NNE NE ENE E ESE SE SSE SECTIOR S SSW SW WSW W WNW NW NNW U

0 PRE-OPERATIONAL MWAN - 1984-2004H1GFLOW/MEAN -&-2005 MEAN LX The 2005 TLD results are very similar to the results obtained during the previous operational periods in all sectors with the exception of NNW. The increase in the dose rate near the plant in the NNW U

sector (Station 86) is related to the ISFSI. Station 86 is inside the fence line; just outside of the fence line, at Station 17 in the same sector (see Figure 5-2), there was no increase in the dose rates relative to historical results.

Exposure rates from the inner circle of TLDs are presented in Figure '5-2. The exposure rates measured in the near plant TLDs, which are located at distances between 0,9 and 2.1 miles from the plant, are close to the preoperational mean in most sectors.

For the remote TLDs, Station 46 in the Wahluke Reserve (NE sector) remained the location' with the L

highest exposure rate, as shown in Figure 5-3. Since the preoperational measurement phase, the results for this location have exceeded the results for all other locations except those located near the ISFSI. Variations in the soil and underlying rock composition most likely account for localized U

differences such as those shown in the TLD results for Station 46.

The environmental radiation exposure rates from 2005 and from the historical data are summarized

'U in Tables 5-3 and 5-4. Presented in Table 5-5 is a comparison of the 2005 annual and summed quarterly TLD results. U Operating Report 5-2 Energy Northwest/Columbia Generating Station 2005 2005 Annual Radiological Environmental Annual Radiological Environmental Operating Report 5-2 Energy Northwest/Columbia Generating Station

Figure 5-2 Inner Circle Quarterly TLDs 1984-2004 Hi/Low/Mean vs. 2005 Mean by Sector 0.36 0.34 0.32 0.30 0.28 0.26

a. 0.24 0.22 0.20 0.18 0.16 0.14 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SECTOR 0 p.QPERATIoNALMEAN . -- q ;984-41_H/LO.WMEAN -- 20Q5 MEAN Figure 5-3 Remote Quarterly TLDs 1984-2004 Hi/Low/Mean vs. 2005 Mean By Sector 0.36 0.34-0.32 0.30 0.28 1 0.26

'1 0.24 0.22 0.20 0.18 0.16 0.14 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SECTOR 0 PRE-QPERATIONAL MEAN - 1984-2004 HIGH/LOW/'MEAN A 2005 MEAN Energy Northwest/Coluinbia Generating Station 5-3 2005 Annual Radiological Environmental Operating Report

I 5.2 Airborne Particulate/Iodine The 2005 mean weekly gross beta on particulate filter results for the inner ring indicator stations (within three miles) for CGS are plotted in Figure 5-4. The gross beta in air results for 2005 were within the ranges observed during the during previous operational periods. In Figures 5-4 and 5-5, the similarity between results from near-plant locations and those from remote locations can be seen.

The control location (Station 9A) results follow a nearly identical pattern to the remote and near-plant locations. As observed previously, gross beta levels increased during periods of inversion occurring in the fall and winter months. Gross beta results plotted over a period of several years show a cyclical pattern of fall and winter increases. I A sharp increase was seen in the gross beta results for all of the air stations in weeks 50 and 51 as a result of an unusually strong temperature inversion. This increase was not caused by or related to any CGS activities or effluents. A smaller increase was also seen around week 9; this was likely

'I also due to a temperature inversion and was seen at all stations including the control.

The quarterly gamma analyses of the particulate filter composites indicated only the presence of two I

naturally-occurring radionuclides, Be-7 and K-40, at levels above detection limits at indicator locations and the control location. All 1-131 in air results for 2005 were below the LLD. There is no I evidence of any measurable impact from plant operations on the environment in the air particulate filter and charcoal cartridge results for 2005. I I

S I

H

£

£ I

1 3 5 7 9 11 13 15 17 19 21 23 25 27 WEEK 29 31 33 35 37 39 41 43 45 47 49 51 S I

- HIGH/LOW/MEAN 1985-2004 -OMEAN 2005 -- Control (Sta. 9)

Figure 5-4 1985-2004 Weekly Hi/Low/Mean vs. 2005 Weekly Mean Gross Beta in Air - Near Plant Stations 2005 Annual Radiological Environmental Operating Report 5-4 C0 Energy Northwest/Columbia Generating Station V- S I

1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51

- HIGH/LOW/MEAN 1985-2004 MEAN 2005 `- Controi (Sta. 9)

Figure 5-5 1985-2004 Weekly Hi/Low/Mean vs. 2005 Weekly Mean Gross Beta in Air - Remote Stations 5.3 Water The gross beta results for the plant intake and river/drinking water (Stations 26, and 29) were within the normally observed ranges. In the drinking water and river samples the gross beta results were less than the eight picocurie per liter (pCi/L) level, at which a strontium analysis is required to be performed to verify compliance with the state drinking water standard for Sr-90. (11) Tritium levels in all samples from Stations 26, and 29 were below the detection limits. No radionuclides of interest were detected in any of-the gamma assays.

The results of deep groundwater samples (Stations 52, 31, and 32) were consistent with the results seen in previous years; Tritium was below the detection limit. Shallow groundwater samples were not collected by Energy Northwest during 2005. The shallow aquifer directly below CGS is contaminated with high levels of Tritium as a result of past DOE activities on the Hanford Site(22 ).

The gross beta levels in the plant discharge water (Station 27) were typically a factor of 3-8 higher than the levels seen in the intake water (Station 26). This is the result of two causal factors; (1) the natural radioactivity in the water is concentrated through evaporation, and (2) the cooling towers scrub particulates from the air that contain naturally occurring radionuclides, and isotopes that are present from atmospheric weapons testing and past Hanford activities. The cooling water discharged from CGS is typically concentrated through 5 to 10 cycles. The discharge sample results are representative of the radioactivity present in plant discharges before any mixing with river water occurs. No radionuclides of interest were identified in any of the assays performed on the discharge water in 2005.

Energy Northwest/Columbia Generating Station 5-5 2005 Annual Radiological Environmental Operating Report

5.4 Soil The gamma assays performed on soil samples in 2005 indicated onlya few naturally occurring radionuclides (Th-228, Ra-226, and K-40) and Cs-137 in some of the samples. Cs-137 was below-the LLD at the background station (Station 9), but was measured in the samples from Stations 7, 21, and 23. When the Cs- 137 at an indicator station exceeds ten (10): times the level in the. control sample, Sr-90 analysis is required. Sr-90 analysis was performed-for the samples from Stations 7, 21, and 23. The Sr-90 results were below the detection-limits. Results from the gamma assays were consistent with those seen in previous years. The soil sample results did not indicate a measurable impact from CGS operations.

5.5 River Sediment Gamma assays of river sediment showed several naturally occurringradionuclides (primarily Ac-228, K-40, Ra-226, and Th-228) and Cs-137, Cs-137 was detected in both the upstream (Station

33) and downstream (Station 34) samples (relative to the cooling tower discharge point) that were collected. The downstream concentrations were higher, butthe levels are consistent with the values seen in the preoperational phase of the REMP and previous operational years. Cs-137 hasbeen previously identified as a component of the Columbia River sediment originating from past weapons production activities at Hanford and operation of the now decommissioned Hanford reactors. (4).

5.6 Fish£ The results of the gamma assays of fishsamples collected in the near, vicinity of CGS cooling water discharge and at the control location on the Snake River were below the detection limits for all radionuclides of interest; K-40, which is naturally ocurring, was measured.

5.7 Milk Z There were no detectable 1-131 results in any. of themilk samples collected in 2005. The gamm r assay results of milk were.lessthan the detection limits for all radionuclides of interest; K-40, which is naturally occurring, Was measured.

Since August 1998, samples of feed grown by the owners of the dairy at Station 9 have been collected as a substitute for the control, stýtion. No,dairy in the area of the control was located that did not use some feed grown downwind from the plant as Supplemental feed. In June of 2005 a new control sample location was obtained that only uses feed grown in the control area; sampling of feed at the previous farm was discontinued and replaced with milk samples from the new location. No radionuclides of interest were detected in any, of the control location feed or milk samples collected.

during 2005.

5.8 Garden Produce The gamma assays of all of the root crops, fruit, and leafy vegetables collected in 2005 were below the detection limits for all radionuclides of interest; K-40, which is naturally occurring, was .

measured.

2005 Annual Radiological Environmental Operating Report 5-6 Energy Nofthwest/Columbia Generating Station

5.9 Special Interest Stations The storm drain pond andthe Sanitary Waste Treatment Facility (SWTF) were incorporated into the routine sampling schedule,&n1992. In' 1995, the cooling tower sediment disposal area was added.

TLDS were placed around the sprdy pond drainfield (Station 120) in June 1995. TLDs were hung in the vicinity of the planned Independent Spent FueleStorage Installation (ISFSI) during the first quarter of 1998 to ed1lectbackgr6und data and an,additional ten TLDs were hung on the ISFSI fence after construction was, completed in 2002..Discussions of the results from each of the locations are

' ,, 1..I. I given in the follow ing gections:

5.9.1 Storm Drain Pond (Station 101)

The storm drain pond is located approximately 1500 feet northeast of CGS. Water is sent to the pond through an 18-inch diameter pipe that discharges into a 300-foot long earthen channel that leads to a 100-foot diameter pond. 'The' pdnd is a shalloiv, unlined percolation/evaporation basin.,

Water at the storm drainloutfall is sarnpled using a-flow proportional automatic sampler to collect monthly composite samples. ,Samples were analyzed for tritium, gross beta, and gamma emitting radionuclides. Tritium was detected; in just over half of the outfall water samples during 2005. The tritium concentrations were consistent with the levels that have been seen in previous years. In the sample from May, a higher than average gross beta result was measured. The concentration was reported at 38.3 pCi/L; this result was not supported by the gamma analysis results. All other beta measurements at Station 101 in 2005 were within the normal range. The September sample contained Co-60 at a concentirtion of 18.4 pCi/L;'. This vNalue was within the range for Co-60 values measured previously;,but C-601hadtiotfbeen sefn kt this!station for several years. No other gamma emitting radionuclides of interestwere measured at Stadnon 101 in 2005.'

5.9.2 Sanitary Waste Treatment Facility (Station 102)

The Sanitary Waste Treatmen( Facility;(SWTF) islocated approximately 0.5 miles south-southeast of CGS. The facility processes ithe sahitary wastewater from CGS; the WNP-1 and WNP-4 sites, the Kootenai Building, and the DOE 400 Area (since April 1997). Discharge Standards and monitoring requirements for the SWTF are established in EFSEC Resolution No. 300's),

The gross beta results in the monthly compositewater sarmipleg of the 400-Area effluent were consistent with.leve61 seen in previous years. The 400 Area effluent samples and SWTF headworks were also analyzed for gross alpha; all gross alpha results -w'ere below the detection limit. Due to cohtributions from the 400 Area effluent, tritiumýconcentrations in SWTF samples were above the detection limit. The 400 Area draws part of its water from an unconfined aquifer that is contaminated with tritium as a result of effluents from the 200 Area on the Hanford Site.

All of the water samples collected at the SWTF received a gamma analysis; no radionuclides of interest were detected, but some naturally occurring radioisotopes were measured. The sediment sample collected from the north stabilization pond contained Cs-137 and Co-60 at concentrations that were within the ranges seen in previous years; several naturally occurring radionuclides were also measured. The Cs-137 levels were within the range of those seen in environmental soil and river sediment samples in the area.

Energy Northwest/Colunibia Generating Station 5-7 2005 Annual Radiological Enviromnental Operating Report

5.9.3 Cooling Tower Sediment Disposal Area (Station 119) U EFSEC Resolution No. 299(16) authorized the onsite disposal of sediments from plant cooling systems containing very low levels of radionuclides. The disposal area for these sediments is located just south of the cooling towers. Resolution No. 299 requires the REMP to monitor the direct radiation dose using quarterly and annual TLDs in the vicinity of the disposal cells.

Resolution 299 also requires the collection of a dry composite sediment sample from the disposal cell within thirty days following each cleaning to confirm that the disposal criteria outlined in the resolution have not been exceeded. fj Cleaning of the cooling towers was done once in 2005. An estimated 85 cubic yards of sediment was placed in the disposal area in June. Using the estimated volume of 85 cubic yards and a density of 1.48 g/crm3, along with the associated activities (the LLDs were used as the activity for all non-detected isotopes), the following quantities of radionuclides could have been placed in the disposal area in 2005: U Nuclide Analytical Result (pCi/kg) Limit (pCi/kg) Total Curies U

Co-60 Mn-54

<7.08E+01

<6.23E+01 5.OE+03 3.OE+04

< 8.91E-06

< 7.84E-06 I)

Zn-65 <1.07E+02 5.OE+04. <.1.35E-05 U Cs-134 <5.25E+01 L.OE+04 < 6.60E-06 Cs-137 2.51E+02 2.OE+04 3.16E-05 £ Of the above radionuclides, only the'Cs-137 result was above the detection limit. The result for Cs-137 is similar to the concentrations found in many of the Columbia River sediment samples.

Since the results for the other radionuclides were less than the lower limit of detection (LLD), the reported quantities disposed of in the table are conservative estimates.

U Measurements of direct radiation at the disposal basin were taken using TLDs. Two locations were used, one next to the collection area (Station 119B) and the other approximately 100 yards to the east as the control (Station 119-Control). The mean quarterly and annual TLD results agree well with results from previous operational years. The difference between the indicator and the control TLD (Station 119-Control) indicate that there was no significant measurable dose above background.

5.9.4 Spray Pond Drain Field (Station 120)

There were no discharges to the Spray Pond Drain Field in 2005. The TLD results at Station 120 in 2005 are in agreement with those seen in previous operational years.

U 2005 Annual Radiological Environmental Operating Report 5-8 Energy Northwest/Columbia Generating Station U

U

5.9.5 Independent Spent Fuel Storage Installation The Independent Spent Fuel Storage Installation (ISFSI) is in an area immediately north of CGS.

Station 121 is located approximately 0.1 mile north of the plant and is between the plant and the ISFSI. Station 122 is on the fence line approximately 0.3 mile north of the plant. Ten more TLD stations are located on the security fence surrounding the ISFSI. These stations are Stations 123-129 and Stations 136A-138A. These TLDs are located approximately 0.25 mile north of the plant.

No new spent fuel storage casks were added to the ISFSI in 2005. The dose rates in close proximity to the ISFSI are elevated, however, this is within the roped-off restricted area and personnel are not permitted to go near the installation without authorization. There is a barricade rope further out from the security fence; if individuals trespass into this roped off area without receiving prior permission, they will be moved away by security personnel.

5.10 2005 Sample Deviations The majority of deviations for sampling were again connected with air sampling. Most of the air sampling deviations resulted from power outages, which were caused by maintenance work and blown fuses. A drastic decrease in the number of air sample deviations was seen in 2005. This is primarily attributable to more thorough preventive maintenance. A summary of the sample deviations from 2005 are listed in Table 5-1.

Table 5-1: Sample Deviations for 2005 SAMPLE MEDIA DATE LOCATION PROBLEM Air Particulate/Iodine 1/31/2005-2/7/2005 Stations 5 & 40 Power off I day at substation. Sample volume acceptable.

2/7/2005-2/14/2005 Station 23 Unit failure due to loose wire. Sample volume unacceptable.

2/14/2005-2/22/2005 Station 23 Unit failure. No sample sent in.

5/23/2005 Station 1 Power turned off in support of refueling outage.

Sample volume unacceptable. -

,5/31/200526/8/2005 Stati6n I Power turned off in support of refueling outage.

Sample volume unacceptable.

5/31/2005-6/6/2005 Station 21 Power turned off in support of refueling outage.

Sample volume ac66ptable.

6/27/2006 Station 57 Power off 1 day at substation. Sample volume acceptable.

7/6/2005 Station 48 Power outage. Sample volume acceptable. Fish hatchery personnel turned off power.

8/22/2005 Station 6 'Blown fuse. Sample volume unacceptable.

9/6/2005 Station 57 Blown fuse. Sample volume unacceptable.

9/6/2005-9/12/2005 Station 21 Power off for three hours for scheduled maintenance. Sample acceptable.

Fish 4th Quarter 2005 Station 38 Unable to catch a carp on the Snake River to use as the control sample. Only 2 species of fish were available for collection.

Energy Northwest/Columbia Generating Station 5-9 2005 Annual Radiological Environmental Operating Report

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Environmental Direct Radiation (TLD) Units: mremlperiod ,U Nominal Indicator Location With Highest Annual Mean Control Locations Number of Analysis Type Total Lower Limit Analyses of Detection Performed (LLD)

Locations Mean (f)"

Range Location Information Mean (f)c Range Mean (f)r Range Nonroutine Measurements U TLD 228 - 20.69 (224/224) 86' 28.06'(4/4) 18.06(4/4) 0 Quarterly (16.6-29.91) NNW 0.3 miles (26.84-29.91) (17.28-19.61)

TLD 57 - 78.99(56 /56) .86 107.48 (1/1) 70.13(1/1) 0 Annual (70.13-107.48) NNW 0.3 miles

a. (f) is the number of positive measurements / total measurements at specified location.

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: ISFSI Direct Radiation (T-LD) Units: mremlperiod U T Nominal Indicator Location With Highest Annual Mean Analysis AnlssAnli LControl Lower Limit Locations'" ..... *.. Locations' a- Number of Type of Detection Mean (f)a Location Mean (ts Mean (f)S Nonroutine Type Performed (LLD) Range Information Range Range Measurements TLD Quarterly 48 - 85.20(48/48)

.(34,34-194.12) 124 N 0.28 miles 182.02 (4/4)

(174.53-194.12): _ _,,

-(0/0) 0 U

TLD 12 - 335.98(12/12) 124. 700.28(1/1) -(0/0) 0 Annual .... (144.07-700.28) N 0.28.miles.

a. (f) is the number of positive measurements / total measurements at specified location.

TABLE 5-2 RADIOLOGICAL ENVIRONIENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington . Calendar Year 2005 Medium: ST 119 Direct Radiation (TLD) Units: mrem/period Total Nominal Indicator Location With Highest Annual Mean Control Locations Number of Analysis Anayes Lower Limit Locations TypeyPeo of Detection Mean (0) Location Mean (0' Mean (f)Q Nonroutine Type Performed (LLD) Range Information Range Range Measurements TLD - 21.52(4/4) 119 21.52(4/4) 21.21(4/4)

Quarterly 8 (19.78-22.64) SSE 0.3 Miles (19.78-22.64) (19.94-22.97) 0 TLD 2 - 78.94(1/1) 119 78.94(1/1) 82.42(1/1) 0 Annual SSE 0.3 Miles

a. (f) is the number of positive measurements I total measurements at specified location.

2005 Annual Radiological Environmental Operating Report 5-10 Energy Northwest/Columbia Generating Station

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: ST 120 Direct Radiation (TLD) Units: mremlperiod Total Nominal Indicator' Location With Highest Annual Mean Control Locations Number of Analysis Lower Limit Locations p erformed of Detection (LLD) Mean Rangi-(f) Location .

Information Mean Range.(0 Mean Range(f) M Nonroutine Measurements TLD 4 21.93(41*4) 120 21.93(4/4) -(01/0)

Quarterly (20.69-22-05) SSE 0.3 Miles (20.69-22.65) 0 TLD 1 83.66(1/-1) 120 83.66(1/1) -(0/0) 0 Annual SSE 0.3 Miles

a. (f)is the number of positive measurements / total measurements a-t specified location.

TABLE-5-2 . .

RADIOLOGICAL ENVIRO6NMENTAL' MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Air Particulate/Air Raidioiodine :units: pCi/m 3 Nominal Indicator Location With Highest Annual'Mean Analysis Total yses Limit. ocati Control Locations Number of Anlyi a Lwelyses octin Mean (0)S Nonroutine Type Ales of Detection Mean Range Range(f0 Performed -Location Mean (f). Measurements (LLD) Information Range Gross Beta 619 1.00E-02 0.0186(566/566) St. 4 0.02062 (52152) 0.0167 (52/52) 0 (0.0019-0.1145), SSE,9.9 Tiles, (0.04.,1-0.0954) ý0,0044-0.0736).

1-131 619: 7..00E-02 -(0/567) (0152)i 0 Cs-134 48 5.OOE-02 -(0/44) - - -(0/4) 0 Cs-137 48 6.00E-02 -(0144) - -(0/4) 0

a. (f)is the number of positive measurements I total measurements at specified location.

Station Generating Station 5-11 2005 Annual Radiological Environmental Operating Report NortbwestlColumbia Generating Energy Northwest/Columbia 5-11 2005 Annual Radiological Enviromnental Operating Report

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Water-River/Ddnin1g Units: pCi/L Nominal Indicator Location With Highest Annual MeanC Anlyi Analysis Analyses Total oDeeto Lower Limit Man()

Locations LctMean ea () Mean Control (f)"

Locations Nonroutine Number of Type Performned of Detecdn ,r Ma Lction mean (Q) Range Measurements (LLD) Range Information Range, Gross Beta 24 4.00E+00 1.48 (10 / 24)(bl 29 1.54(5 /12) 1.74(5/12) 0 (1.18-1.79) SSE 11.6 miles (1.25-1.79) (1.18-1.74)

H-3 8 2.OOE+03 -- (0 / 8), - -(0/4) 0 Mn-54 24 1.50E+01 -(0/24) b) - --- (0/12) 0 Fe-59 24 3.OOE+01 (0 / 24) r -(0/12) 0 Co-58 24 1.50E+01 -(0/24) (b) -(0/12) 0 Co-60 24 1.50E+01 -(0/24) - - -(0/12) 0 Zn-65 24 3.00E+01 -(0/24) b) - - -(0/12) 0 Zr-95 24 1.50E+01 (0/24)t') - - -(0/12) 0 Nb-95 24 1.50E+01 -(0/24)tb) - - -(0/12) 0 Cs-134 24 1.50E+01 -(0124)(b) -- -(0/12) 0 Cs-137 24 1.80E+01 (0 /24)(b) - -(0/12) 0 Ba/La-140 24 1.50E+01 -(0 24) - -( -(0/12) 0 Sr-90 0 1.00E+00 (0/) " --- (0/0) 0

a. (f) is the number of positive measurements ( total measurements at specified location.

b. This Includes the control sample for this group; the control (Station 26) Is also a drinking water sample.

L L

Report 5-12 Energy Northwest/Columbia Generating Station 2005 Annual Radiological 2005 Annual Environmental Operating Radiological Environmental Operating Report 5-12 Energy Norffiwest/Columbia Generating Station

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Water-Discharge Units: pCi/L Nominal Indicator Location With Highest Annual Mean Analysis Total Lower Limit Locations Control Locations Number of Type Analyses of Detection Mean (f) Location Mean (f)S Mean (f) Nonroutine Performed (LLD) Range Information Range Range Measurements Gross Beta 24 4.OOE+00 12.30 (10/12) 27 12.30 (10/12) 1.425 (5 /12) 0 (5.09-22.5) E 3.2 miles (5.09-22.5) (1.17-1.74)

H-3 8 2.00E+03 -(014) - - -(0/4) 0 Mn-54 24 1.50E+01 -(0112) - -,(0/12) 0 Fe-59 24 3.OOE+01 -(0/12) - -(0/12) 0 Co-58 24 1.50E+01 -(0/12) - -(0/12) 0 Co-60 24 1.50E+01 -(0/1.2) -- -(0/12) 0 Zn-65 24 3.OOE+01 -(0/12) - - -(0/12) 0 Zr-95 24 1.50E+01 .,-(0/12) - - -(0/12) 0 Nb-95 24 1.50E+01, -(0/12) - -(0/12) 0 Cs-134 24 1.50E+01 I-(0/12) - - -(0/12) 0 Cs-137 24 1.80E+01., -- (0/12) - - -(0/12) 0 BaILa-140 24 1.50E+01 -(0/12) . - .(0/12) 0

a. (f)is the number of positive measurements / total measurements at specified location.

Energy Northwest/Columbia Generating Station 5-13 2005 Annual Radiological Environmental Operating Report

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Water- Deep Ground Units: DCiIL Nominal Indicator Location With Highest Annual Mean Analysis Total Anal Iyses Lower Limit Locations Control MenLocations., Number orotn of Analyses of Detection Mean (f)O Location Mean (f) Mean (f)r Nonroutne Type Performed (LLD) Range Information Range Range Measurements H-3 12 2.OOE+03 -(0/12) - - -(010) 0.

Mn-54 12 1.50E+01 -(0112) - - -(0/0) 0 Fe-59 V2 3.00E+01 -(0/12) -1 - -(0/0) 0 Co-58 12 1.50E+01 -(0/12) - - -(0/0) 0 Co-60 12 1.50E+01 -(0/12) - " -(0/0) 0 Zn-65 12 3.00E+01 -(0/12) - - -(0/0) "0 Zr-95 12 1.50E+01 -(0112) - - -(0/0) 0 Nb-95 12 1.50E+01 -"(0/12) - - -(0/0) 0 Cs-134 12 1.50E+01 -(0/12) -(0/0) *0 Cs-137 12 1.80E+01 -- (0/12) - - -(0/0) 0 Ba/La-140 12 -(0112)

- - - -(0/0) 0

a. (f)is the number of positive measurements /total measurements at specified location.

U Operating Report 5-14 Energy Northwest/Columbia Generating Station 2005 Annual 2005 Radiological Environmental Annual Radiological Environmental Operating Report 5-14 Energy Nordiwest/Columbia Generating Station

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING, PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Wdshington Calendar Year 2005 Medium: Water-SWTF (102B) Units: pCilL Nominal Anayt -InIdicator Location With Highest Annual Mean AnaIyses Lower Limit Locations Control Locations Number of Type Analyses of Detection Mean (f)' Location Mean (f)' Mean (f)r Nonroutine Performed (LLD) Ran.ge Information Range Range Measurements Gross Alpha 12 (0/12) -(0/0) 0 Gross Beta 12 4.00E+00 27.70 (12/12) 102B SSE 27.70 (12/12) -(0/0) 0 (13.76-36.25) 0.5 miles (13.76-36.25)

H-3 12 2.00E+03 813.9 (12/12) 102B SSE 813.9 (12/12) -(0/0) 0 (239-1123) 0.5 miles (239-1123)

Mn-54 12 1.50E+01 -(0/12) - - -(0/0) 0 Fe-59 12 3;OOE+01 -(0/12) - -- (0/0) 0 Co-58 12 1.50E+01 -(0/12) - - -(0/0) 0 Co-60 12 1.50E+01 -(0/12) - - -(0/0) 0 Zn-65 12 3.00E+01 -(0112) - - -(0/0) 0 Zr-95 12 i.50E+01 -(0/12) - ..- (010) 0 Nb-95 12 1.50E+01 -(0112) - -(010) 0 Cs-134 12 1.50E+01 -(0/12) - - -(0/0) 0 Cs-137 12 1.80E+01 -(0/12) - -(0/0) 0 Ba/La-140 12 1.50E+01 -(0/12) -- -(0/0) 0

a. (f) Is the number of positive measurements I total measurements at specified location.

5-15 2005 Annual Radiological Environmental Operating Report Energy Nordiwest/Columbia Generating Station Northwc~tICoIumbia Generating Station 5-15 2005 Annual Radiological Environmental Operating Report

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Water-FFTF Sewage (002A) Units: pCi/L Location With Highest Annual Mean Totrl Nominal Indicator ControlLocations Number of Analysis Analys Lower Limit Locations Type of Detection Mean (f)' Location Mean (f) Mean (f) Nonroutine.

Performed (LLD) Range Information Range ..Range Measurements Gross Alpha 12 - (0/12) - - -(0/0) 0 Gross Beta 12 4.00E+00 26.40(12/12) 102A SSE 26.40(12112) -(0/0) 0 (18.20-37.08) 0.7 miles (18.20-37.08)

H-3 12 2.OOE+03 2843 (12/12) 102A SSE 2843 (12/12) -(0/0) 0 (2325-3230) 0.7 miles (2325-3230)

Mn-54 12 1.50E+01 -(0/12) - -- - -(010) 0 Fe-59 12 3.00E+01 -(0/12) - - -(0/0) 0 Co-58 12 1.50E+01 -(0/12) - " - , (0/0) 0 Co-60 12 1.50E+01 -(0/12) - - -(0/0) 0 Zn-65 12 3.00E+01 -(0112) - - -(0/0) 0 Zr-95 12 1.50E+01 -(0/12) - - 0) 0 Nb-95 12 1,50E+01 -(0/12) - - -(0/0) 0 Cs-134 12 1.50E+01 -(0/12) - - -(0/0) 0 Cs-137 12 1.80E+01 -(0/12) -- (0/0) 0 Ba/La-140 12 .1.50E+0. -(0112): -. -(0/0) - 0

a. (f) is the number of positive measurements / total measurements at specified location.

U; 2005 Annual Radiological Environmental Operating Report 5-16 Energy NoTthwest/Columbia Generating Station

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Stormwater Ouffall (101) Units: pCilL Location With Highest Annual Mean Nomin al"....

Total Nominal IndMator Control Locations Number of AnalysesLower Limit Locaons Type' Aalyse of Detection' MeanM(f), Location, Mearn (f)a Mean (f)a Nonroutine Performed (LLD) Rangel Information. RIange Range Measurements Gross Beta 12 4.OOE+00 8.87 (8/ 12) 101 8.87(8/12) -(0/0) 0 (1.32-38.30) ENE 0.2 miles (1.32-38.30)

H-3 12 2OOE+03 3478 (7/12) 101 3478 (7/12) -(0/0) 0 (353-17100) ENE,0.2 miles (353-17100)

Mn-54 12 1,50E+01 -(0 12). - - -(010) 0 Fe-59 12 3.00E+01 -(0/12) - - -(0/0) 0 Co-58 12 1;50E+01 -(0/12) - - -(0/0) 0 Co-60 12 1.50E+01 18.4 (1/12) 101. 1A.4 (1,/12) -(0/0) 0 ENE 0.2 miles Zn-65 12 300E+01 (0112) . - -(010) 0 Zr-95 12 1.50E+01 -(0 / 12) - - (0 / 0) 0 Nb-95 12 1.50E+01 -(0/12) - - -(0/0) 0 Cs-134 12 1.50E+01 -- (0/12) -- - -(0 /0) 0 Cs-137 12 1'80E+01 -(0112) - - -(0/0) 0 Ba/La-140 12 1.50E+01 -(0/12) - -,(0/0) 0

a. (f)is the number of positive measurements total measurements at specified Iocation.

Energy Nordiwest/Columbia Generating Station 5-17 2005 Annual Radiological Enviromnental Operating Report

TABLE.5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: River Sediment Units: pC/gk Totals An Nominal Indicator Location With Highest Annual Mean Analysis Lower Limit Locations CoMean (f)L Nonroutine Type Analyses of Detection Mean (f)a Location Mean (fl Range Measurements Performed (LLD) Range Information Range Cs-134 4 1.50E+02 -(012) -- -(0/2) 0 Cs-137 4 1.80E+02 134.65 (2/2) 34 134.65 (2/2) -135.2(2/2) 0 (70.3-199) (70.3-199) (112.4-158)

Co-60 4 1.00E+02 -(0/2) - - -(0/2) 0

a. (f) is the number of positive measurements I total measurements at specified location.

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Caleidar Year.2005 Medium: Soil _______Units: pCi/kg Location With Highest Annual Mean Analysis tal Nominal ndicator Control Locations Number of TAnalysis Anal Lower Umit Locations Mean (f)a Nonroutine Type p yrfe of Detection' Mean'(f)a Location P(LD) Range Information Mean (f)aRange Range Measurements Cs-134 5 1.50E+02, -(0/4) - -- (0/1) 0 Cs-137 5 1.80E+02 62.47(3/4) 23 83.20(1/1) -(0/1) 0

. (42.99-83.20) ESE 3.0 Miles Sr-90 3 1.OOE+01 -(0/3) -(0/0) 0

a. (f) is the number of positive measurements / total measurements at specified location.

2005 Annual Radiological Environmental Operating Report 5-18 Energy Norffiwest/Columbia Generating Station

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Cooling Tower Sediment Units: pCi/kg Analysis Total Toa Nominal Indicator Location With Highest Annual Mean Control Locations Number of Tyse Analyses Lower Limit Locations Mean Or Nonroutine Performed of Detection Mean (f)8 Location Mean (f)MeeaurNnr t (LLD) Range Information Range Range Measurements Co-60 - - (0 / 1) -(0/0) 0 Mn-54 1 -(0/1) -(0/0) 0 Zn-65 1 -(0il) -(0/0) 0 Cs-134 I 1.50E+02 -(0/1) - - -(0/0) 0 Cs-137 1 1.80E+02 251 (1/1) 119 251 (111) -(0/0) 0 SSE 0.3 Miles

a. (f) is the number of positive measurements I total measurements at specified location.

TABLEt5'-2 RARADIOLOGICAL ENVIRONMENTAL MONITORING PR1OGRAM

SUMMARY

cdLUfndlA GENERATING STATION DOCKET NO. 50'-397 Benton County, Washington Calendar Year 2005 Medium: Sanitary.Waste"Treat ment Facility:Sedimenrt- Units: pCi/kg Anlsi otl Totale Nomiinal Indicator , C Location With -ighest Anhual Mean Control L o Locations m Of Number Analysis al Lower Limit Locations a' pAnalyses of Detection Mean (f)S Location Mean (f)a Mean (f)a Nonroutine Performed (LLD) Range. Information ,Range Range Measurements Co-60 1 - 144 (1/1) 102D 144 (1 /1) -(0/0) 0 SSE 05 miles -

Mn-54 '1 - -(0/1) - - -(0/0) 0 Zn-65 1 - -(0/1) - - -(0/0) 0 Cs-134 1 1.50E+02 -(0/1) - - -(0/0) 0 Cs-137 1 1.80E+02 133 (1/1) 102D 133.0 (1/1) -(0/0) 0 SSE 0.5 miles

a. (f) is the number of positive measurements / total measurements at specified location.

Generating Station 5-19 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Energy Northwest/Columbia Station 5-19 2005 Annual Radiological Environmental Operating Report

U TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

U COLUMBIA GENERATING STATION Benton County, Washington DOCKET NO. 50-397 Calendar Year 2005 U Medium: Roots Analysis Total Analyses Nominal Lower Limit Indicator Locations Units: pCilkg Location With Highest Annual Mean Control Con Locations Lao Number of Number of Li Type 1-131 Performed 8

of Detection (LLD) 6.00E+01 Mean Range(f)"

-(014)

Location Information Mean Range(f)a Range

-(0/4)

Measurements 0

U Cs-134 8 6.00E+01 -(0/4) - - -(014) 0 U

Cs-137 8 8.00E+01 -(0/4) j - - -(014) 0

a. (f) is the number of positive measurements I total measurements at specified location.

U TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

U COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 U

Medium: Fruits Units: n . _ ___

Analysis Type Total Analyses Nominal Lower imit of Detection Indicator Locationsna Mean (s2 Location With Highest Annual Mean Location Mean (f)

Control Locations Mean (f)"

Number of Nonroutine.

Li Performed (LLD) Range Information Range Range Measurements 1-131 9 6.OOE+01 -(0/5) - - -(014) 0 U Cs-134 Cs-137 9

-9 6.OOE+01 8.00E+011

-(01.5)

-(0/5) -

(0/4)

-(014) 0 0

U

a. (f) is the number of positive measurements / total measurements at specified location. U U

U L

2005 Annual Radiological Environmental Operating Report 5-20 Energy Northwest/Columbia Generating Station L

L

TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Vegetables Units: pCi/kg SLwLocation With Highest Annual Mean Total ODCM Lower Indicator Locations Control Locations Number of Type Ty Analyses.

Performed Detection (LLD)

Mean (f)r Location Mean (f) Mean (f)8 Nonroutine Range Information Range Range Measurements 1-131 12 6.00E+01 -(0/6) - -- (0/6) 0 Cs-134 12 6.OOE+01 -(0/6) - - -(0/6) 0 Cs-137 12 8.OOE+01 -(0/6) - - -(0/6) 0

a. (f) is the number of positive measurements /total measurements at specified location.

TABLE 5-2 RADiOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Fish "______ __-_____Units: pCilkg Nominal' Location With HighestAnnual Mean Analysis Total Lower Limit Indicator Locations Control Locations Number of T Analyses of Detecion Mean (Q' Location Mean (a Mean (f)a Nonroutine Performed (LLD) ....... Range Information Range Range Measurements Mn-54 5 1.30E+02 -(0/3) - - -(0/2) 0 Fe-59 5 2.60E+02 -(0/3) - - -(0[2) 0 Co-58 5 1.30E+02 -(0/3) . .-.-- (0/2) 0 Co-60 5 1.30E+02 -(0/3) - - -(0/2) 0 Zn-65 5 2.60E+02 -(0/3) - - -(0/2) 0 Cs-134 5 1.30E+02 -(0/3) - - -(0/2) 0 Cs-137 5 1.50E+02 -(0/3) - - -(0/2) 0

a. (f) is the number of positive measurements / total measurements at specified location.

Energy Northwest/Columbia Generating Station 5-21 2005 Annual Radiological Environmental Operating Report

U TABLE 5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

U COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 U

Medium: Milk Units: pCIlL Nominal ILocation With Highest Annual Mean Control Locations Number of Analysis Total lysesLower lPerormed oem (LD)

Lmit Indicator Mean Locations efLD)

Range(f) Location Information Mean (f Range Mean Range(f)a Nonroutine Measurements U

1-131 36 1.OOE+00 -(0118) -- -(0/18) 0 Cs-134 36 1.50E+01 -(0/18) .- (0/18) 0 U

Cs-137 36 1.80E+01 -(0/18) - - -(0/18) 0 Ba/La-140 36 1.50E+01 -(0/18) - - -(0/18) 0

a. (f) is the number of positive measurements I total measurements at specified location.

TABLE5-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

COLUMBIA GENERATING STATION DOCKET NO. 50-397 Benton County, Washington Calendar Year 2005 Medium: Broadleaf in Lieu of Milk Units: pCi/k_ _

Total Nominal Indicator Locations Location th Highest Annual Mean Control Locations Number of Analysis Analys Lower Limit Meanr (ft Mean (f Nonroutine Type TyePromd of Detection (LID) Inocmation.

Inforation Rang(fr Mean en()*Nnotn (LLD) tion Range Range Measurements 1-131 10 6.OOE+01 (05/0)b - - -(0/10) 0 Cs-134 10 6.OOE+01 -(010)b f -/ -(0/10) 0 Cs-137 Ba/La-140 10 10 8.00E+01 6.00E+01

-(0/0)f

-(00)

-(0/10)

-/ (0/10) 0 U

a. (f)is the number of positive measurements I total measurements at specified location.

b. Collected at control location only.

U U

U 2005 Annual Radiological Environmental Operating Report 5-22 Energy Northwest/Columbia Generating Station U

U

TABLE 5-3 QUARTERLY TLD DATA

SUMMARY

FOR THE PREOPERATIONAL AND OPERATIONAL PERIODS Results in mrem/Standard Quarter PREOPERATIONAL(a) 1984- 2004 OPERATIONAL 2005 OPERATIONAL STATION LOW HIGH MEAN LOW HIGH MEAN LOW HIGH MEAN 1 19.16 23.73 21.90 18.25 27.38 22.54 19.80 21.72 20.99 2 17.34 22.81 21.08 16.43 25.55 21.99 18.98 22.72 20.44 3 18.25 21.90 20.44 16.43 24.64 21.35 18.62 20.71 19.25 4 15.51 23 .73 19.98 14.60 22.81 19.89 16.61 19.07 18.25 5 18.25 22.81 20.81 16.43 23.73 20.44 17.61 20.62 18.62 6 18.25 21.90 20.17 16.43 23.73 20.62 17.98 20.17 18.62 7 19.16 22.81 21.35 16.43 24.64 21.63 18.62 20.81 19.44 8 21.90 *25.55 23.82 15.51 27.38 23.73 20.90 22.72 21.63 9 15.51 21.90 19.89 16.43 23.73 20.08 17.34 19.71 18.07 10 19.16 22.81 20.99 16.43 24.64 21.35 18.52 21.17 19.53 11 19.16 22.81 21.44 16.43 24.64 21.81 19.98 21.72 20.44 12 20.99 24.64 23.09 18.25 26.46 23.54 20.90 22.63 21.90 13 19.16 22.81 21.44 17.34 27.38 21.90 18.98 21.35 19.80 14 19.16 24.64 21.90 17.34 25.55 21.90 19.71 21.72 20.35 15 20.99 25.55 23.18 17.34 27.38 23.45 20.99 23.00 21.72 16 20.08 23.73 22.17 16.43 26.46 22.45 19.71 21.63 20.53 17 19.16 23.73 22.81 17.34 26.46 22.81 20.90 23.27 21.72 18 20.08 23.73 22.17 16.43 25.55 22.36 19.89 21.26 20.71 19 20.08 23173 21.99- 17.34 25.55 22.54 20.44 22.08 21.08 20 19.16 23.73 21.44 17.34 25.55 22.17 20.08 22.45 20.81 21 19.16. 21.96x io.71 15.51 '23.73 18.43 20.35 19.16

'19.16 23.73 21.99 16.43 25.55

'22.08 20.08 'i1.90 20.71 22 21:

23 20.08 23.73 21.63 17.34 25.55 18.62 21.26 19.44 24 20.99 23.73 21.90 17.34 50.46 22.72 19.07 21.35 20.44 25 20.99 24.64 , 23.18 "17.1,4 27.38 23.27 20.62 22.17 21.08 40 17.34 "21.90 19.98 15.51 24.64 20.62 17.61 20.17 18.89 41 20.08 25.55 23.73 17.34 27.38 23.00 :19.7i 22.17 20.71 42 20.08 23.73 22.36- 17.34 26.46 22.54 19.16 22.36 20.35 43 20.99 24.64 23.09 16.43 27.38 23.09 19.44 22.63 20.35 19.16 22.81 21.08 15.51 24.64 S21.35 17.A3 20.26 19,07 44 45 19.16 22.8i 21.26 16.43 25.55 21.72 18.98 21.08 19.62 "22..81 *28.29 26.10 19.16 31.94 27.01 24.00 25.92 25.09 46 47 17.34 20.99 19.89 15.51 26.28 20.62 17.79 20.35 18.80 49 - - 21.90 16.43 25.55 22.17 20.44' 23.27 21.35 50 - 20.08 16.43 26.46 22.08 18.80 21.72 20.26 51 19.16 21.90 20.53 16.43 24.64 21.54 18.62 21.54 19.80 53 - - 24.64 18.25 29.57 24.00 21.08 23.54 22.08 54 - - 23.73 18.16 26.46 22.63 19.35 22.17 20.62 55 - - 20.99 16.43 25.55 21.72 18.62 21.81 20.26 56 - - 21.90 16.43 25.55 22.27 19.07 21.63 20.26 Energy Northwest/Columbia. Generating Station 5-23 2005 Annual Radiological Environmental Operating Report

TABLE 5-3 (cont)

U QUARTERLY TLD DATA

SUMMARY

FOR THE PREOPERATIONAL AND OPERATIONAL PERIODS Results in mrero/Standard Quarter U STATION LOW PREOPERATIONAL(a)

HIGH MEAN LOW 1984 - 2004 OPERATIONAL HIGH MEAN LOW 2005 OPERATIONAL HIGH MEAN U

65 18.07 22.72 20.44 18.16 20.53 19.35 U

(b) 71(IS) 20.08 22.81 21.90 18.25 30.39 25.37 22.90 26.74 24.73 72(2S) 21.90 23.73 22.81 18.25 28.38 24.55 21.72 29.66 25.09 73(3S) 20.08 21.90 20.99 16.43 24.64 21.54 19.25 22.72 20.44 74(4S) 75(5S) 23.73 19.16 24.64 21.90 24.00 20.35 18.25 15.51' 28.29' 26.46 23.82 22.54 21.26 20.53 23.82 23.18 21.99 21.99 U

76(6S) 20.99 22.81 21.90 17.34 26.46 22.36 20.35 23.45 21.08 77(7S) 78(8S) 21.90 21.90 23.73 23.73 22.81 22.54 17.34 17.34 25.55 25.55 22.36 21.90 19.98 18.62 22.08 21.54 20.81 20.35 U

79(9S) 22.81 23.73 23.09 17.34 25.55 22.27 19.35 21.99 20.62 80(lOS) 81(11S) 20.99 20.08 22.81 23.73 21.90 22.17 16.43 17.34 25.55 25.55 21.44 21.90 18.07 19.25 20.81 21.81 19.16 20.44 U

82(12S) 21.90 24.64 23.45 17.34 26.46 22.72 20.62 22.72 21.54 83(13S) 84(14S) 21.90 20.99 23.73 22.81 22.81 22.17 17.34 16A3 26.46 27.19 22.81 22.72 19.35 20.53 22.90 23.00 20.71 21.44 U

85(15S) 21.90 24.64 23.73 17.34 27.83 23.54 20.71 25.37 22.27 86(16S) 119B 21.90 23.73 22.81 (c)

(c) 18.25' 19.35 30.11 25.64 25.37 22.45 26.92 19.80 30.02 22.72 28.11 21.54 U

119Ctrl 19.53 26.55 22.08 19.98 23.00 21.26 120 121 (ISFSI) -

- (c)

(d) 19.80 20.81 31.12 110.78 22.72 73.00 -

20.71 53.20 22.72 99.10 21.99 78.66 U

122 (ISFSI) (d) 19.62 39.24 24.55- 34.40 38.05 35.77 123 (ISFSI) -(4) 25.00 159.23 73.18 133.77 153.48 141.62 124 (ISFSI) (e) 26.92 201.02 91.89 175.02 194.64 182.50 125 (ISFSI) . (e)0 26A6 131.77. 69.35 114.88 130.58 122.37 126 (ISFSI) 127 (ISFSI)

(e)

(e) 26.01 29.02.

79.94 64.51 50.46 44.90 68.07 56.21 80.21 65.24 72.27 59.59 U 128 (ISFSI) (e) 25.64 84.13 46.63 73.27 86.69 78.02 129 (ISFSI) 136A (ISFSI)

(e)

(e) 30.11 29.02 69.26 65.24 44.80 41.34 ,

60.59 57.94 69.90 66.80 63.42 60.68 U

137A (ISFSI) (e) 29.47 73.18 43.80 63.33 75.37 67.71 138A (ISFSI)

(a)

(e)

The preoperational mean is from 1982-1983 data.

28.29 82.40 44.17, 58.22 70.26 62.60 U

(b) Station 65 was added in 1997.

(c)

(d)

(e)

Stations 119B, 11 9Ctrl, and 120 were added in 1995.

Stations 121 and 122 were added in 1998 for the ISFSI.

Stations 123-129 and 136A-138A were added in the 2ld quarter of 2002.

U U

2005 Annual Radiological Environmental Operating Report 5-24 Energy Northwest/Columbia Generating Station U

TABLE 5-4 ANNUAL TLD DATA

SUMMARY

FOR THE PREOPERATIONAL AND OPERATIONAL PERIODS Results in mrem/year PREOPERATIONAL(a) 1984 - 2004 OPERATIONAL 2005 OPERATIONAL STATION LOW HIGH MEAN LOW HIGH MEAN RESULT 1 85.41 98.55 91.98 73.00 102.20 84.73 78.26 2 83.59 84.68 83.95 73.00 98.19 82.93 76.92 3 82.13 85.78 83.95 72.27 94.17 79.34 70.99 4 74.46 100.38 87.60 65.70 87.24 75.19 72.04 5 81.40 93.81 87.60 69.75 88.33 76.70 71.66 6 79.94 83.95 81.76 69.35 90.52 77.10 71.72 7 84.32 86.51 85.41 72.92 97.09 81.74 71.58 8 94.54 98.55 96.73 80.34 108.04 91.11 80.57 78.11 81.76 79.94 68.99 91.98 76.14 70.13 9

10 82.13 86.87 84.32 69.35 93.81 80.43 75.73

.11 83.22 88.33 85.78.- 73.00 99.28 82.56 76.15 12 92.35 94.17 93.08 80.30 102.57 88.41 84.21 13 85.41 87.97 86.87 76.65 97.46 83.56 77.63 14 84.68 86.14 85.41 69.35 97.09 81.98 78.88

.15 83.95 94.90 89.43 76.65 104.03 88.90 82.48 89.79 91.98 90.89 76.65 101.47 85.32 80.54 16

17. 85.78 91.62 88.70 76.65 101.84 86.54 81.10 18 86.51 97.82 . 91.98 76.65 101.47 85.95 80.24 85.78b) 19 76.65 104.03 85.28 78.80 20 85.41 90.16 87.60 76.58 101.84 84.58 80.27 79.57 84.32 82.13 69.35 91.25 77.38 72.80 21 22 84.68 87.97 . 86.51 75.37 97.09 83.20 74.98 23 83.59 87.24 85.41 73.00 94.90 81.08 72.65 24 85.41 87.97 86.51 74.28 100.01, 83.67 75.85 25 90.52 95.27 93.08 76.65 104.03 88.37 85.15 40 76.650b) 68.99 91.25 76.48 71.29 41 94.90 97.46 96.36 75.19 102.20 86.46 77.60' 42 85.78(b) 75.92 104.03 84.38 77.00 43 , 88.33(b) 71.18 107.68 85.48 76.27 "83.59 " 89.43 86.51 71.91 94.17 80.32 74.22 44 45 82.49 86.14 84.32 72.64 96.36 81.58 76.01 46 '102.57 107.68 105.12 94.90 123.37 103.50 97.72 47 - 80.30(b) 69.35 95.27 78.81 73.45 49 (c) 76.65 100.74 83.40 78.44 50 (c) 73.00 100.01 82.38 75.38 51 (c) 73.00 97.46 81.03 77.08 53 (c) 77.75 104.03 90.98 83.69 54 (c) 77.16 100.38 86.07 78.08 55 (c) 73.00 96.36 81.10 75.17 56 (c) 71.18 101.47 84.43 79.23 65 (d) 72.77 86.51 76.75 72.58 Generating Station 5-25 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Energy Northwest/Columbia Generating Station 5-25 2005 Annual Radiological Environmental Operating Report

TABLE 5-4 (cont.)

U ANNUAL TLD DATA

SUMMARY

FOR THE PREOPERATIONAL AND OPERATIONAL PERIODS Results in mrem/Year U

STATION 71 (1S)

LOW PREOPERATIONAL(s)

HIGH MEAN 87.97 0) 1984 - 2004 OPERATIONAL LOW 83.95 HIGH 112.06 MEAN 2005 OPERATIONAL RESULT 95.47 U

96.90 72(2S) 73 (3S) 91.62b) 83.59ob) 83.95 73.00 110.96 94.90-94.19 81.02 90.04 74.70 U

74 (4S) - - 89.06°() 80.30 106.22 90.34 86.47 75(5S) 76(6S) 86.510()

88.33(b) 73.00 76.65 100.74 101.47 84.93 85.01 80.85 83.11 U

77(7S) - - 89.79b) 73.00 99.28 84.58 78.28 78 (8S) 79(9S) -

- 89.79b) 91.980b 73.00 73.00 97.71 101.11 83.39 83.59 78.11 84.47 U

80 (10S) - 85.41b) 69.42 97.09 81.40 75.19 81 (IIS) 82 (12S) 82.86b) 89.79b) 73.00 74.83 96.36 101.47 81.94 85.84 75.50 79.78 U

83 (13S) - - 91.250) 76.65 99.65 87.10 80.16 84(14S) 85 (15S) 83.95b) 91.98b) 76.03 80.30 99.28 105.85 85.25 90.23 81.21 86.80 U

86(16S) - 87.97b) !87.60 112.79 97.77 107.48 119B ll9Ctrl -

- (e)

(e) 75.92 77.75 107.68 101.84 84.13 86.09 78.94 82.42 U

120 - (e) 78.11 112.79 88.63 83.66 121 (ISFSI) 122 (ISFSI)

(f)

(f) 177.76 76.29 365.37 138.20 284.39 92.55 306.72 144.07 U

123 (ISFSI) - - (g) 126.22 543.99 287.12 567.27 124 (ISFSI) 125 (ISFSI)

(g)

(g) 128.66 119.59 681.34 460.66 347.78 263.84 700.28 499.10 U

126 (ISFSI) - (g) 123.06 284,89 195.52 288.46 127 (ISFSI) 128 (ISFSI)

(g)

(g) 120.60.

.112.96 233.40 28.7.67 172.99 182.58 235.81 302.81 U

129 (ISFSI) , - (g) 121.78 240.98 169.55 244.35 U

136A (ISFSI) -- (g) .:119.31 229.44 160.11 237.05 137A (ISFSI) - * - (g) 124.36 258,38 172.42 262.61 138A (ISFSI) - (g) 122.70 239.26 (a)

(b)

The preoperational mean is from 1982 - 1983 data.

There was only one annual exchange during the preoperational period.

164.01 243.27 U

(c) Stations 49-56 were first monitored during the Fourth Quarter of 1983.

(d)

(e)

(f)

Station 65 was added in 1997.

Stations I19B, 119C03d, and 120 were added in 1995.

Station 121 and 122 were added in 1998 to gather baseline data for the ISFSI.

U (g) Stations 123-129 and 136A-138A were added in the 2 nd quarter of 2002 U

Operating Report 5-26 Energy Northwest/Columbia Generating Station 2005 Annual 2005 Radiological Environmental Annual Radiological Environmental Operating Report 5-26 Energy Northwest/Columbia Generating Station

TABLE 5-5 2005 QUARTERLY VERSUS ANNUAL TLD DATA Results in mrem/Year

-QUARTERLY ANNUAL STATION TOTAL(a) RESULTS RATIO(b) 1 83.58 78.26 1.068 2 81.37 76.92 1.058 4

5 3 76.76 72.67 74'.25 70.99 72.04 71.66 1.081 1.009 1.036

/

6 74.40 71.72 1.037 7 77.69 71.58 1.085 8 86.25 80.57 1.071 9 72.22 70.13 1.030 10 77.93 75.73 1.029 11 81.52 76.15 1.071 12 87.48 84.21 1.039 13

• 78.90 77.63 1.016 14 81.16 78.88 1.029 15 86.57 82.48 1.050 16 81.79 80.54 1.015 17 86.53 81.10 1.067 18 82.80 80.24 1.032 19 84.02 - 78.80 1.066 20 82.90 80.27 1.033 21 76.52 .72.80 1.051 22 82.63 74.98 1.102 23 77.62 72.65 1.068 24 81.66 75.85 1.077 25 84.25 85.15 0.989 40 75.26' 71.29 1.056 41 82.77 77.60 1.067 42 81.28 77.00 1.056 43 81.29 ' 76.27 1.066 44 76.18 '74.22 1.026 45 78.23 76.01 1.029 46 100.14 97.72 1.025 47 75.09 73.45 1.022 49 85.21 78.44 1.086 50 80.98 75.38 1.0.14 51 78.99 77.08 1.025 53 88.07 83.69 1.052 54 82.15 78.08 1.052 55 80.75 75.17 1.074 56 80.74 79.23 1.019 65(c) 77.25 72.58 1.064 71 (iS) 98.67 95.47 1.033 5-27 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Energy Generating Station Northwest/Columbia Generating Station 5-27 2005 Annual Radiological Environmental Operating Report

TABLE 5-5 (cont.)

2005 QUARTERLY VERSUS ANNUAL TLD DATA Results in mrem/Year U QUARTERLY ANNUAL STATION TOTAL(a) RESULTS RATIOb) 72(2S) 100.09 90.04 1.112 73 (3S) 81.39 74.70 1.089 74(4S) 75(5S) 87.90 87.60 86.47 80.85 1.017 1.083 U

76(6S) 84.22 83.11 1.013 77(7S) 78(8S) 82.88 81.05 78.28 78.11 1.059 1.038 U

79(9S) 82.10 84.47 0.972 80(10S) 81(1lS) 76.30 81.56 75.19 75.50 1.015 1.080 L

82(12S) 86.02 79.78 1.078 83(13S) 84(14S) 82.62 85.64 80.16 81.21 1.031 1.054 U

85 (15S) 88.91 86.80 1.024 86 (16S) 119B (d) 112.24 86.06 107.48 78.94 1.044 1.090 L

1 19Ctrl(4 ) 84.83 82.42 1.029 120(d) 87.71 83.66 1.048 121 (ISFSI)( 313.71 306.72 ,L023 122 (ISFSI)() '142.58 144.07 0.990 123 (ISFSI)(

124 (ISFSI)W° 0

564.96 728.06 567.27 700.28 0.996 1.040 L

125 (ISFSI)(0 126 (ISFSI)(o 127 (ISFSI)( 0 487.97 288.42 237.76 499.10 288.46 235.81 0.978 1.000 1.008 L

128 (ISFSI(° 129 (ISFSI)OM 136A (ISFSI)OM 311.15 253.04 242.07 302.81 244.35 237.05 1.028 1.036 1.021 U

137A (ISFSI)t° 138A (ISFSI) t0 270.12 249.67 262.61 243.27 1.029 1.026 U (a) Sum of the quarterly results.

(b)

(c)

(d)

Quarterly result/Annual result.

Station 65 added in 1997.

Stations 1 19B, I I9Ctrl, and 120 were added in 1995.

L (e) Station 121 and 122 were added in 1998 to gather baseline data for the ISFSI.

(M) Stations 123-129 and 136A-138A were added in the 2d quarter of 2002 for the ISFSI.

L L

L 2005 Annual Radiological Environmental Operating Report 5-28 Energy Northwest/Columbia Generating Station

6.0 QUALITY ASSURANCE AND QUALITY CONTROL 6.0 QUALITY ASSURANCE AND QUALITY CONTROL The REMP is designed to meet the quality assurance and quality control criteria of the NRC Regulatory Guide 4.15(4). To accomplish this, the REMP requires that its analytical contractors also meet these criteria. The Energy Northwest Quality group performs audits of the REMP records and activities and the records and activities of its support organizations at least annually.

Quality assurance and technical audits of the analytical contractor (Teledyne Brown Engineering) are also conducted periodically to verify their compliance to regulatory and contractual requirements. The adequacy of their quality assurance program is also assessed during the audits.

The following sections summarize the quality assurance and quality control aspects of the TLD, sample collection, and sample analysis components of the REMP.

6.1 Quality Control for the Energy Northwest Environmental TLD Program The Quality Control program for the Energy Northwest REMP TLDs covers the preparation, transportation, deployment, collection, storage, processing, and evaluation.

From the time the TLDs are annealed to the time they are placed in the field, they are stored and transported with control TLDs. Two sets of control TLDs are used, the building controls and the transportation (trip) controls. The building controls monitor the exposure that the TLDs receive while being transported to and from the TLD vendor and while in storage awaiting deployment and analysis. The trip controls accompany the field TLD set while they are being transported to and from the vendor and also while they are being deployed and collected in the field. The building controls and trip controls are stored in a low background lead shield while the field TLDs are deployed. If the trip control results are greater than the building control results, the difference between the two is subtracted from the field dosimeters to account for exposure during transit.

Reader QC dosimeters are prepared by Battelle at the Pacific Northwest National Laboratory and serve as indicators that the reader calibration is satisfactory and that the TLDs were processed correctly. These TLDs are annealed and then given a known exposure (typically 100 mR) to a cesium-137 source. The number of QC dosimeters used during each processing is generally 10% of the number of field dosimeters. Evaluation of the 2005 reader QC dosimeter results indicated satisfactory agreement for all four quarters and the annual processing results.

Spiked TLDs are submitted by Energy Northwest for processing along with the environmental TLDs. The processing results from these QA TLDs are used to demonstrate reader performance during environmental TLD processing. Quarterly spikes receive a target exposure of 25 mR and annual spikes receive a target exposure of approximately 90 mR. The spiked dosimeters are processed with the field dosimeters to verify the accuracy and consistency of the environmental TLD evaluations. All results were within +/-10% of the known exposure and are provided in Table 6-1.

Station 6-1 2005 Annual Radiological Environmental Operating Report Energy NorthwestlColunibia Generating Energy Nordiwest/Columbia Generating Station 6-1 2005 Annual Radiological Enviromnental Operating Report

6.2 Quality Control for the Environmental Sample Program Quality control for the environmental sample program involves two components: the quality control activities performed for the sample collection aspects of the program and the quality control activities conducted to ensure accurate and reliable sample analyses. Both of these components are described in the following sections.

6.2.1 Quality Control Activities for Sample Collection Duplicate samples are periodically collected and submitted to the sample analysis laboratories (Teledyne or Energy Northwest). The duplicate samples are in some cases blind, and in others they may be of a known origin. Duplicate samples are used primarily to assess the repeatability of the sample collection process, but may also be used to help assess the precision in the results produced by analytical laboratories. ": : '*" '

Chain of custody forms are produced and kept with samples when they are transported or shipped to analytical laboratories to maintain sample control and traceability.,-

U 6.2.2 Teledyne Brown Engineering Quality Control Program ,

The goal of the quality control program at Teledyne Brown Engineering - Environmental Services is to produce analytical results that are accurate, precise and supported by adequate documentation. The program is based on the requirements of IOCFR50 Appendix B('9),

Regulatory Guide 4115(4) and the program as described in Teledyne's Quality Assurance Quality Control Manual.

All measuring equipment is calibrated for efficiency at least annually' using standard reference material traceable to the National Institute of Standards and Technology (NIST). For alpha and beta counting, check sources are counted each weekday'the counter is in use. :Control charts are maintained with three-signma limits specified. Backgrounds are usually meaisured at least once per week.('-) Gamma spectrbmeters are calibrated annually with a NIST-traceable standard reference material selected to coverthe energy range of the nuclides to be monitored for all of the geometries measured.! Backgroinds are determined every-other week and check'sources are counted 1352 KeV) weekly. The energy resolution and efficiency -areplotted at two energy levels (59.5 and and held within t~hree-sigruatcontrol. limits.0**' .

U The efficiency of the liquid scintillation counters is determined at least annually by counting L NIST traceable standards which have been diluted in a known amount of distilled water and various amounts of quenching agent.( 9 ) The background of each counter is measured with each batch of samples. 'A control chart is maintained for the background and check source measurements as a stability check.

U Results are reviewed before being entered into the data system by the Quality Assurance and/or the Department Manager for reasonableness of the parameters (background, efficiency, decay, etc.). Any sample results that are suspect, are returned to the laboratory for recount. If a'longer count, decay check, recount on another system or recalculation does not give acceptable results based on experience, a new aliquot is analyzed.

2005 Annual Radiological Environmental Operating Report 6-2 Energy Northwest/Columbia Generating Station

6.2.3 Energy Northwest Environmental Services Quality Control The Energy Northwest - Environmental Services Laboratory maintains a quality control program to ensure that analytical results are accurate, precise,,and defensible. The program is based on the requirements of 10CFR50 Appendix B(l°),.Regulatory Guide 4.15,(4) and the Energy Northwest - Environmental Services Laboratory Quality Assurance Manual. A summary of the various key aspects to the Energy Northwest quality control program are provided below.

Laboratory Sample Preparations - Analytical balances used in the laboratory for sample preparations are calibrated every six months. Daily checks are performed prior to use on all analytical balances; thesechecks are documented on sample preparation forms and should span the range of intended use when checked. Devices used for volumetric measurements of samples are periodically verified for accuracy. with reagent grade water.; if they are found to be out of specifications they are removed from use....  :

Analytical Instruments - Analytical instruments used for determining radioactive emissions in samples are calibrated for efficiency at. least annually using standard reference material traceable to the National Institute of Standards and Technology (NIST). Specific requirements for radiation measuring instrument QC are desetib&d bel,**W;.

• Gas-flow proportional qounter%used f9r alpha ,aadbeta counting are checked for performance daily whe in use. Control charts are mtntained with two and three-sigma limits, specified; the ehetcJ7must irh!! tvito-sigma warning limits prior to use.

End of batch performance checks are also performed. Background checks are performed daily when in use and must fall below the two-sigma upper limit prior to use.

Background measurements, are performed weqkly..,

• Gamma spectrometqrs ar*,eheeke4daily. for efficiencythe ,energy per, channel

.relationship, anl for,re olution. *he checks.arp perfopned, and plotted at two energy levels 59.5 and 1332XKeV. Eiffliency checks are held within two-sigma control limits.

The energy checks, are plotted apndlare:held within statistical control limits that are based on the known energy for ite peakpof,interest. Resolution checks are plotted and are held within statistical lir its. Background hecks .fior gross contamination are performed daily.

Backgrounds are,determined every ot *r week.,,,

Liquid scintillation counters are subjected tQ*instrumqnt performaqee assessment checks each day that they are in use. The performance checks verify the instrument efficiency for two nuclides and assess the background. The background is measured with each batch of

.samples with a sample blank. The efficiency of the instrument is also assessed with each batch of samples by measuring several known addition standards that are made from, NIST traceable standard solutions. Control charts are maintained for the background and performance check measurements.

Results are reviewed by the radiochemistry lead and/or the laboratory lead for reasonableness, acceptability of performance checks and recovery on known-addition samples, and for data entry errors. Any sample results that are suspect, are returned to the laboratory for recount. If reanalyzed results are still suspect, a new aliquot is analyzed. The information about the sample is contained on the sample processing forms.

Energy NorthwestIColumbia Generating Station 6-3 2005 Annual Radiological Enviromnental Operating Report

6.3 Sample Batch Quality Control Sample batches are analyzed along with sample blanks and known-addition samples (or spiked samples) as appropriate, and as dictated by the sample type, primary analytes of interest, and method being used. The following is a summary of sample batch QC activities that were performed in 2005. Teledyne and Energy Northwest generally follow the same QC/QA protocols for analysis batches; differences will be specified in the following texts when they exist along with general descriptions of the QC activities performed for batches of samples.

Iodine-131 Cartridges - At least one blank charcoal cartridge was analyzed with each batch of samples assayed. All blanks were below the detection levels. Energy Northwest assayed at least one known-addition sample with each batch and also performed at least one replicate measurement (usually on the known-addition sample) inside of each batch. For the known-addition samples at Energy Northwest, the 356 keV peak from Ba-133 was evaluated. At least one replicate assay is performed inside each batch at Energy Northwest.

Gross Beta Filters - One or more blank filters were measured with each set of filters assayed.

The blanks were below or slightly above the detection limit. Energy Northwest counted at least one unused blank AP filter and at least one known-addition AP filter (or spiked laboratory-control sample) with each batch. At least one replicate measurement is performed inside each batch at Energy Northwest.

1-131 in Milk - Teledyne analyzed several blank milk samples during 2005. Energy Northwest analyzed milk samples collected from ie,control location as blanks. The Energy Northwest method for 1-131 in milk is a gamma spectroscopy method, so the QC requirements are different.

Energy Northwest analyzed a known-addition sample with each batch of 1-131 in milk samples.

At least one replicate assay is performed inside of each batch at Energy Northwest.

Gross Beta in Water - Blank samples were prepared from reagent grade water with each batch of samples and analyzed. Energy Northwest analyzed at least one known addition sample with each batch of gross alpha and gross beta samples. At least one replicate sample is prepared and analyzed inside of each batch at Energy Northwest. C Tritium in Water - Blank samples were analyzed with each batch. At Energy Northwest known addition samples were also measured with each batch. At least one replicate sample is prepared and analyzed inside of each batch at Energy Northwest.

Gamma Spectroscopy - Background counts were performed semimonthly for gamma f spectrometers. All nuclides of interest were less than the level of detection indicating no contamination. Spiked samples were prepared and measured using Cs-137 with a peak at 662 keV at Teledyne, ad the Cs-137 results were within the :- 3 sigma limits. Energy Northwest measured known addition samples containing a mixtures of radionuclides, the results were within the acceptance limits for all analyses. At least one replicate assay is performed inside of each batch of samples at Energy Northwest.

2005 Annual Radiological Environmental Operating Report 6-4 Energy Northwest/Columbia Generating Station

6.4 Laboratory Intercomparison Program Participation Participation in laboratory intercomparison studies is mandatory for all laboratories performing analyses of CGS REMP samples. Intercomparison studies provide a consistent and effective means to evaluate laboratory, performance on sample analyses. Results from studies should fall within the control limits specified for the study or corrective actions are to be performed.

Teledyne participated in the following intercomparison programs in 2005:

" Analytics, Inc. Cross Check Program

" Environmental Resource Associates (ERA) RadCheM Proficiency Testing Program

" Department of Energy Mixed'Analyte Performance Evaluation Program (MAPEP).

MAPEP distributed radiological performance test samples for gross alpha/beta measurements of water and air particulate filters beginning in the latter part of July 2005 The results for Teledyne in the intercomparison studies done in 2005 are shown in Tables 6-2 through 6-4.-

Energy Northwest participatedin the following intercomparison programs in 2005:

• Analytics, Inc. Cross Check Program

• Environmental Resource Associates (ERA) RadCheM Proficiency Testing Program The results Of EDiergy Northwest's, participation inf itercompaiso'n studies done;in 2005 are shown in Tables 6-5 thr0ugh 6-6.

Energy Northwest/Columbia Generating Station 6-5 2005 Annual Radiological Environmental Operating Report

TABLE 6-I L

2005 ENVIRONMENTAL SPIKED DOSIMETERRESULTS DISTRIBUTION GIVEN REPORTED U

PERIOD EXPOSURE (mR) EXPOSURE (mR) BIAS (%)

First Quarter 26 25.47 -2.04%

U 24.74 -4.83%

25.88 -0.47% U Second Quarter 26 25.97 -0.10%

26.31 1.20%

.25.63 -1.42%

Third Quarter 22 21.27 -3.33% U 20.37 21.53

-7.42%

-2.15% U Fourth Quarter 22 22.39 1.79%

22.65 2.94%

22.02 0.09%

Annual 88 84.21 -4.31%

S82.75 -5.97%

80.91 -8.05%

L1 2005 Annual Radiological Environmental Operating Report 6-6 Energy Northwest/Columbia Generating Station U

TABLE 6-2 TELEDYNE BROWN ENGINEERING RESULTS 2005 ANALYTICS, INC. CROSS CHECK COMPARISON PROGRAM Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

March 2005 E4522-396 Milk Sr-89 pCi/L 96.9 107 0.91 A Sr-90 pCi/L 16.9 17.9 0.94 A E4523-396 Milk 1-131 pCi/L 82.7 92.3 0.90 A Ce-141 pCi/L 217 229 0.95 A Cr-51 pCiIL 314 334 0.94 A Cs- 134 pCi/L 123 139 0.89 A Cs-137 pCilL 125 130 0.96 A Co-58 pCi/L 110 115 0.96 A Mn-54 pCi/L 158 160 0.99 A Fe-59 pCi/L 118 111 1.06 A Zn-65 pCi/L 191 198 0.96 A Co-60 pCi/L 140 144 0.97 A E4525-396 AP Ce-141 PCi 150 172 0.87 A Cr-51 pCi 278 250 1.11 A Cs-134 pCi 105 104 1.01 A Cs-137 pCi 95.6 97.1 0.98 A Co-58 pCi 84.4 86.3 0.98 A Mn-54 pCi 112 120 0.93 A Fe-59 pCi 92.8 83.2 1.12 A Zn-65 pCi 162 148 1.09 A Co-60 pCi 102 108 0.94 A E4524-396 -Charcoal 1-131 :pCI ý 67.4 60.7 1.11 A June 2005 E4630-396 Milk Sr-89 pCi/L 89.4 88.1 1.01 A Sr-90 pCi/L 11.6 11.4 1.02 A E4631-396 Milk 1-131 pCiL 82.3 86.9 0.95 A Ce-141 pCi/L 91.6 92.4 0.99 A Cr-51 pCiIL 278 303 0.92 A pCVL Cs-134 81.1 95.0 0.85 A Cs-137 pCVL 180 189 0.95 A Mn-54 pCi/L 124 125 0.99 A Fe-59 pCi/L 61.1 63.9 0.96 A Zn-65 pCIL 156 155 1.01 A Co-60 pCVL 136 145 0.94 A E4633-396 AP Ce-141 pCi 79.2 64.2 1.23 W Cr PCi 263 210 1.25 W Cs-134 pCi 69.7 66.1 1.05 A Cs-137 PCi 135 131 1.03 A Mn-54 pCi 94.9 87.0 1.09 A Fe-59 PCi 48 44.4 1.09 A Zn-65 PCi 120 108 1.11 A Co-60 PCi 104 101 1.03 A E4632-396 Charcoal 1-131 pCi 88.9 92.5 0.96 A Generating Station 6-7 2005 Annual Radiological Environmental Operating Report Northwest/Columbia Generating Energy Northwest/Columbia Station 6-7 2005 Annual Radiological Environmental Operating Report

TABLE 6-2 (cont.)

TELEDYNE BROWN ENGINEERING RESULTS 2005 ANALYTICS, INC. CROSS CHECK COMPARISON PROGRAM ,

Identification Reported Known U

Ratio (c)

Month/Year Number '-' Matrix Nuclide Units Value (a) Value (b) TBEFAnalytics Evaluation (d)

September 2005 E4766-306 Milk Sr-89 pCiIL 135.0 146.0 0.92 A E4767-396 Milk Sr-90 1-131 Ce-141 pCiVL pCVL pCi/L 9.7 87.5 203 11.5 94.3 233 0.84 0.93 0.87 A

A A

U Cr-51 pCi/L 279 338 0.83 A Cs-134 pCi/L 102 122.0 0.84 A Cs-137 pCi/L 178 195 0.91 A Co-58 pCi/L 55.3 63.4 0.87 A Mn-54 pCi/L 81.8 92.0 0.89 A Fe-59 pCi/IL 59.9 61.0 0.98 A Zn-65 pCiIL 120 123 0.98 A Co-60 pCVL 146 167 0.87 A E4769-396 AP Ce-141 pCi 193 169 1.14 A Cr-51 Cs-134 Cs-137 pCi PCi pCi 267 78.4 166 246 88.8 142 1.09 0.88 1.17 A

A A

L Co-58 PCi 53.7 46.0 1.17 A Mn-54 PCi 81.6 66.8 1.22 W Fe-59 pCi 59.6 44.3 1.35 N (1)

Zn-65 Co-60 pCi PCi 107 133 89.6 122 1.19 1.09 A

A L E4768-396 Charcoal 1-131 pCi 63.9 64.2 1.00 A December 2005 E4766-396 Milk Sr-89 Sr-90 pCi/L pCiIL 114 11.6 128 10.3 0.89 1.13 A

A L

E4767-396 Milk 1-131 Ce-141 Cr-51 pCi/L pCVL 79.6 202 185 74.6 224 193 1.07 0.90 0.96 A

A A

L Cs-134 pCiIL 74.9 87.3 0.86 A Cs- 137 pCi/L 177 189 0.94 A pCVL Co-58 pCi/L 73.9 77.5 0.95 A Mn-54 pCi/L 152 152 1.00 A Fe-59 pCi/L 97.5 82.4 1.18 A Zn-65 pCiIL 161 154 1.05 A Co-60 102 111 0.92 A E4633-396 AP Ce-141 Cr-51 pCi pCi pCi 221 195 201 173

,78.3 1.13 A

A U

Cs-134 Cs- 137 Co-58 Mn-54 pCi PCi pCi 68.4 194 77.4 171 170 69.4 137 0.87 1,14 1.12.

W A

A A

L pCi 1.25 Fe-59 94.2 73.9 1.27 W pCi Zn-65 173 138 1.25 W Co-60 pCi 109 99.1 1.10 A 2005 Annual Radiological Environmental Operating Report 6-8 Energy Northwest/Columbia Generating Station U

U

TABLE 6-2 (cont.)

TELEDYNE BROWN ENGINEERING RESULTS 2005 ANALYTICS,, INC. CROSS CHECK COMPARISON PROGRAM Identificatior.  ;*.. Reported Known Ratio (c):

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2005 E4632-396 Charcbal 1-131 - pCI 73.3 73.3 1.00 A (1) New technician -AP not counted in petti dish resulted in high Fe-59 activity. Counting in petri dish, the Fe-59 would have been acceptable as evidenced by the 4t05AP recountdata. NCR 06.01 (a) Teledyne Brown Engineering reportedresult.

(b) The Analytics known value is equalto 100% of the parameterpresent In the standardas determined by gravimetricand/or volumetric measurements made during standardpreparation.

(c) Ratio of Teledyne Brownl Engineering to Analytics results.

(d) Analytics evaluationbased on TBE internal QC limits: A= Acceptable. Reportedresult falls within ratio limits of 0.80-1.20.

W-Acceptable with warning. Reportedresult falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

6-9 2005 Annual Radiological Environmental Operating Report Energy Nordiwest/Columbia Generating Station Northwest/Columbia Generating Station 6-9 2005 Annual Radiological Enviromnental Operating Report

TABLE 6-3 U

TELEDYNE BROWN ENGINEERING RESULTS 2005 MAPEP ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM U Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

April 2005 05-MaW13 Water Cs-134 Cs-137 Co-57 BqIL Bq/L Bq/L 108 305 215

-. 127 332 227 88.90. -165.10 232.40 - 461.60 158.90 - 295.10 A

A A

U Co-60 Bq/L 241 251 175.70 - 326.30 A H-3 Mn-54 Sr-90 BqIL Bq/L Bq/L 283 314 0.093 280 331 196.00 - 364.00 231.70 - 430.30 no range given A

A A

U Zn-65 Bq/L 509 496 347.20 - 644.80 A MaS13 Soil Cs-134 Cs-137 Bq/L Bq/L 655 310.

759 315 531.30 - 986.70 220.50 - 409.50 A

A U

Co-57 Bq/L 234 242 169.40 - 314.60 A Co-60 Mn-54 K-40 Bq/L Bq/L Bq/L 219 512 642 212 485 604 148.40 - 275.60 339.50 - 630.50 422.80 - 785.20 A

A A

U Zn-65 Bq/L 890 810 567.00- 1053 A GrW13 Water Gr-A Gr-B Bq/L Bq/L 0.601 1.54 0.525 1.67

>0.0 - 1.05 0.84 -2.51 A

A U

RdF13 AP Cs-134 Cs-137 Co-57 Bq/sample Bq/sample Bq/sam.pe 3.26 2.05 4.78 3.51 2.26 4.92 2.46 - 4.56 1.58 - 2.94 3.44 - 6.40 A

A A

U Co-60 Bq/sample 3.02 2.12 - 3.94 A U

3.03

• Mn-54. Bq/sample 3.31 3.33.,. 2.33-4.33 A Sr-90. Bq/sample 1.15 1.35 0.95 - 1.76 A Zn-65 Bqfsample 3.14 3.14 2.20 -4.08 A GrF13 AP Gr-A Gr-B Bqlsample Bq/sample 0.0764 0.30.5 0.232 0.297

>0.0 - 0.46 0.15 -0.45 A

A U April 2005 RdV13 Vegetation Cs-134 Cs-137 Co-57 Bq/kg Bq/kg Bq/kg 5.45 4.80 13.4 5

4.1 9.88 3.50-6.50 2.88-5.34 6.92 - 12.84 A

A A

U Co-60 Bq/kg 3.67 3.15 2.21 -4.10 A Mn-54 Bqlkg 6.45 5.18 3.63-6.73 A Sr-90 Bq/kg 1.49 1.65 1.16-2.15 A Zn-65 Bqlkg 7.71 6.29 4.40 - 8.18 A October 2005 05-MaW14 Water Cs-134 Cs-137 Bq/L Bq/L 142 302 167 333 116.90-217.10 233.10 - 432.90 A

A U

Co-57 Bq/L 251 272 190.40 - 353.60 A Co-60 H-3 Mn-54 Bq/L BqIL Bq/L 243 547 383 261 527 418 182.70 - 339.30 368.90 - 685.10 292.60 - 643.40 A

A A

U Sr-90 Bq/L 8.75 8.98 6.29 - 11.67 A Zn-65 Bq/L 324 330 231.00 - 429.00 A L

2005 Annual Radiological Environmental Operating Report 6-10 Energy Nordiwest/Columbia Generating Station

TABLE 6-3 (cont)

TELEDYNE BROWN ENGINEERING RESULTS 2005 MAPEP ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM Identification Reported Known Acceptance Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

October 2005 MaS14 Soil Cs-1 34 Bq/L 494 568 397.60 - 738.40 A Cs-137 aq/L 446 439 307.30 - 570.70 A Co-57' aq/L 506 524 366.80 - 681.20 A Co-60 Bq/L 289 287 200.90 - 373.10 A Mn-54 Bq/L 460 439 307.30 - 570.70 A K-40 Bq/L 626 604 422.80 - 785.20 A Sr-90 Bq/L 571 757 529.90 - 984.10 W (1)

Zn-65 Bq/L 889 823 576.10 - 1070 A GrW14 Water Gr-A Bq/L 0.858 0.79 0.21 - 1.38 A Gr-B Bq/L 1.22 1.35 0.85- 1.92 A October2005 RdF14 AP Cs-134 Bq/sample 4.11 3.85 2.70 - 5.01 A Cs-137' Bq/sample 3.16 3.23 2.26 - 4.20 A Co-57 Bqlsample 6.14 6.2 4.34-8.06 A Co-60 Bq/sample 2.86 2.85 2.00 - 3.71 A Mn-54 Bq/sample 4.54 4.37 3.06 - 5.68 A Sr-90 Bq/sample 2.12 2.25 1.58-2.93 A Zn-65 Bq/sample 4.28 4.33 3.03 - 5.63 A GrF14 AP - Gr-A Bq/sample 0.304 0.482 >0.0 - 0.80 A Gr-B Bq/sample 0.858 0.827 0.55- 1.22 A RdV13 Vegetation Cs-134 Bq/kgf 4.35 4.09 2.86 - 5.32 A Cs-137 Bq/kg; 5.99 5.4 3.80 - 7.06 A Co-57 Bq/kg 17.0 13.30 9.31 - 17.29 W Co-60 Bq/kg 4.87 4.43 3.10 - 5.76 A Mn-54 Bq/kg 7.40- 6.57 4.60-8.54 A Sr-90 Bq/kg 2.031 2.42 1.69-3.15 A Zn-65 Bq/kg 11.8 10.2 7.14-13.26 A (1) NCR 05-18 asigned to investigate low bias in Sr-90 in soil - pending fusion procedure development.

(a) Teledyne Brown Engineering reportedresult.

(b) The MAPEP known value is equal to 100% of the parameterpresentin the standardas determinedby gravimetricand/or volumetric measurements made during standardpreparation.

(c) DOE/MAPEP evaluation:A=acceptable, W=acceptable with warning, N=not acceptable.

Energy Nordiwest/Columbia Generating Station 6-11 2005 Annual Radiological Enviromnental Operating Report

TABLE 6-4 TELEDYNE BROWN ENGINEERING RESULTS L

2005 ERA CROSSCHECKS PERFORMANCE EVALUATION PROGRAM Identification Reported Known Month/Year Number Media Nudide - Units Value (a) , Value (b) , Control Limits Evaluation (c)

May 2005 Rad 61 Water Sr-89 pCiJL 37.5 41.3 32.6- 50.0 U Sr-90 pCi/L 5.371 5.92 0.00- 14.6 Ba-133 Cs-134 Cs-137 Co-60:

pCiJL pCi/L pCVL pCiIL 88.6; 70.5 201 37.5 88.4 78.6 201 37.0 73.1-104 69.9 - 87.3 184-218 28.3-45.7 U

Zn-65 Gr-A Gr-B H-3 pCi/VL pCiIL pCi/L pCVL 122 35.5 35.6 .. 34.2 24600 118 37.0 24400 97.6-138 21.0 -53.0 25.5 -42.9 20200 - 28600 U

November 2005 Rad 63 Rad 61 Water Water 1-131 Sr-89 pC-L pCVL 13.6 18.0 15.5 19.0 10.3 -20.7 10.3-27.7 U

Sr-90 Ba-133 Cs-134 Cs-137 pCi/L pCi/L pCi/L pCi/L 16.6 31.7 30.8-26.8 16.0 31.2 33.9 28.3 7.37-24.7 22.5- 39.9 25.2 -42.6 19.6-37.0 U

Co-60 Zn-65:

Gr-A pCi/L pCi/L pCi/L 83.9 109 19.5 84.1 105 23.3 75.4-92.8 86.8-123 13.2-33.4 U

Gr-B pCi/L 34.0 39.1 30.4 -47.8 Rad 63 Water-H-3 1-131 pCi/.

pCiL 12400 17.8 12200 17.4 10100- 14300 12.2 - 22.6 A U

Lý LT (a) Teledyne Brown Engineeing reportedresult.

(b) The ERA known value i8 equalto 100% of the parameterpresentin the standardas determinedby gravimetricand/or volumetric measurementsmade during standardpreparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reportedresult falls outside of the Control Limits. CE=checkfor Error. Reported result falls within the ControlLimits and outside of the Warning Limit.

2005 Annual Radiological Environmental Operating Report 6-12 EneW NoMwest/Columbia Generating Station t2

TABLE 6-5 ENERGY NORTHWEST RESULTS 2005 ERA CROSSCHECKS PERFORMANCE EVALUATION PROGRAM Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)

March 2005 RAD 60, Water H-3: pCiIL 30800 30200 25000 - 35400 A MRAD 002 AP Am-241: pCi/Filter 24.8 22.7 15.9 -53.1 A Cs-134 / pQi/Filler 74.7 77.5 57.4 - 93.8 A Cs-137.,, pCi/Fjlter 806 650 520 - 858 CE Co-60 !-, pCi/Filter 1090.0 1040.0 832 - 1310 A AP Gr-B1 pCi/Filter 74.2 76.4 58.1 - 104 A Gr-A

• pCi/Filter 79.2 103 46.4 - 103 A Water Am-24.1 pCi/L 68.7 75.6 59.7- 107 A Cs-134 pCi/L 141 128 102-166 A Cs-137 pCi/L 2390.0 2250.0 1800 - 2740 A Co-60 pCi/L 3260 2950.0 2360 - 3540 A Water Gr-A pCi/L 7930 8500 4930- 11000 A Gr-B13 pCi/L 15300 17200 10500 - 24600 A Soil Ac-228i pCi/kg 4420 4230 3380- 5840 A Am-241 pC'.kg 3000 2700.0 1760-6160 A Bi-212. pCi/kg 4850.0 4910 2450-6580 A Bi-214 pCi/kg 2410., 2080 1620-2950 A Cs-137. pCi/kg 49600 44700 35800 - 55900 A Pb-212 pCi/kg 4620,-., 4330 3380-5720 A Pb-214, pCi/kg 2210 2070 1570-3020 A K-40 pCi/kg 29500.0 26800.0 21400 - 35400 A Th-234- pCi/kg 1920,0 1690.Q 1060 - 3970 A Vegetation IAm-241 pCi/kg 297 267 195-539 A Cs-137 pCi/kg 25300 22700 18200 - 29700 A Co-60 pCi/kg 2280 2330 1860-3360 A K-40 pCi/kg 25600 22100.0 17500 - 30700 A May 2005 RAD 61 Water Ba-133 pCi/L 85.4 88.4 73.1-104 A Cs- 134 pCi/L 80.7 78.6 69.9 - 87.3 A Cs-137 pCi/L 212 201 184-218 A Co-60 pCi/L 43.9 37 28.3 -45.7 CE Zn-65 pCi/L 123 118 97.6-138 A Water Gr-A pCi/L 27.5 37 21.0-53.0 A Gr-B pCi/L 33.4 34.2 25.5 - 42.9 A Milkd/Water 1-131 pCi/L 16.7 15.5 10.3-20.7 A Water Ra-228 pCi/L 16.3 18.9 10.7-27.1 A U-Nat pCi/L 10.2 10.1 4.90-15.3 A U-Mass pg/L 14.5 15.1 7.34-22.9 A Energy Nordiwest/Columbia Generating Station 6-13 2005 Annual Radiological Environmental Operating Report

TABLE 6-5 (cont)

ENERGY NORTHWEST RESULTS 2005 ERA CROSSCHECKS PERFORMANCE EVALUATION PROGRAM Identification Reported Known Month/Year September 2005 MRAD 003 Number, AP Media Nuclide Gr-A Units pCi/Filter Value (a) 18.9 Value (b) 41.1 Control Limits 7.56-41.5 Evaluation (c)

A 2

Gr-B pCVFilter 21.8 24 18.2-32.6 A Water Am-241 Cs-134 pCi/L pCiIL 235 1050 232 1070 183-327 856-1390 A

A U

Cs-137 pCi/L 267 269 215-328 A Water Co-60 Gr-A pCil/L pCi/L 5570 28700 5320 31900 4260-6380 18500-41200 A

A U

Gr-B pCi/L 42600 48300 29500-69100 A H-3 pCi/L 12800 13400 10500- 32800 A U U

U L

(a) Energy Northwest reported result.

L (b) The ERA known value is equal to 100% 6f the parameterpresent in the'standardas determined by gravimetn'cand/or volumetric measurementsmade during standardpreparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the WarningLimits. NA=not acceptable. Reported resultfalls T outside of the Controllimits. CE=checkfor Error. Reported resultfalls within the ControlLimits and outside of the Warning Limit.

(d) A milk was spiked instead of water to validate method.

fU 2005 Annual Radiological Environmental Operating Report 6-14 Energy Northwest/Columbia Generating Station

TABLE 6-6 ENERGY NORTHWEST RESULTS 2005 ANALYTICS, INC. CROSS CHECK COMPARISON PROGRAM Identification, Reported Known Ratio. (c)

Month/Year Number "-Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

December 2005 E4877-723 Charcoal 1-131 pCi 75.4 72.4 1.04 A (a) EnergyNothwest reportedresult.

(b) The Analytics known value is equal to 100% of the parameterpresentin the standardas determined by gravimetric and/or volumetric measurements made during standardpreparation.

(c) Ratio of EnergyNothwest to Analytics results.

(d) Analytics evaluation basedon EN internalQC limits. A= Acceptable. Reported resultfalls within ratiolimits of 0.80-1.20.

W-Acceptable with warning. Reported resultfalls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0.70 and > 1.30.

Energy Northwest/Colurnbia Generating Station 6-15 2005 Annual Radiological Environmental Operating Report

7.0 REFERENCES

1. U.S. Nuclear Regulatory Commission, "Programs For Monitoring Radioactivity in the Environs of Nuclear Power Plants," Regulatory Guide 4.1, Revision 1, April 1975.

2. U.S. Nuclear Regulatory Commission, "Environmental Technical Specifications For Nuclear Power Plants," Regulatory Guide 4.8, December 1975.

3. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Assessment Branch Technical Position Revision 1, November 1979.

4. U.S. Nuclear Regulatory Commission, "Quality Assurance For Radiological Environmental Monitoring Program (Normal Operations), Effluent Streams and the Environment,"

Regulatory Guide 4.15, Revision 1, February 1979.

5. U.S. Nuclear Regulatory Commission, "Performance, Testing and Procedural Specifications For Thermoluminescence Dosimetry-Environmental Applications,"

Regulatory Guide 4.13, Revision 1, July 1977.

6. Energy Facility Site Evaluation Council, Resolution No. 260, January 1992.

7. Energy Northwest Nuclear Columbia Generating Station, Operating License NPF-21, "Technical Specifications" Sections 5.5.1, 5.5.4, and 5.6.2

8. Columbia Generating Station Offsite Dose Calculation Manual (ODCM).

9. Code of Federal Regulations, Title 10 Part 20, "Standards for Protection against Radiation."

10. Code of Federal Regulations, Title 10 Part 50, "Domestic Licensing of Production and Utilization Facilities."

11. Washington Administrative Code 246-290, "Group A Public Water Systems."

12. Washington Administrative Code 173-200, "Water Quality Standards for Ground Water of the State of Washington."

13. Washington Administrative Code 173-201A, "Water Quality Standards for Surface Waters of the State of Washington."

14. Robertson, D. E., and J. J. Fix, "Association of Hanford Origin Radionuclides With Columbia River Sediment," BNWL-2305, August 1977.

15. Energy Facility Site Evaluation Council, Resolution No. 300, approved September 10, 2001.

16. Energy Facility Site Evaluation Council, Resolution No. 299, approved August 13, 2001.

7-1 2005 Annual Radiological Environmental Operating Report Energy Northwest/Columbia Generating Station Northwest/Columbia Generating Station 7-1 2005 Annual Radiological Environmental Operating Report

17. Teledyne Brown Engineering - Environmental Services TBE-3003, "Calibration and Control of Alpha/Beta Counters."

18. Teledyne Brown Engineering - Environmental Services TBE-3001, "Calibration and Control of Gamma Ray Spectrometers."

19. Teledyne Brown Engineering - Environmental Services TBE-20 10, "Tritium and Carbon-14 Analysis by Liquid Scintillation."

20. Energy Northwest, "Columbia Generating Station Final Safety Analysis Report," Section 2.3.1.1.

21. Eisenbud, M., Gesell, T., "EnvironmentalRadioactivity", Academic Press, Inc., San Diego, CA, 1997.

22. PNNL, 2004, HanfordSite Near-FacilityEnvironmentalMonitoringReportfor Calendar Year 2003, PNNL-14687, Pacific Northwest National Laboratory, Richland, Washington.

23. Code of Federal Regulations, Title 10 Part 50, "Domestic Licensing of Production and Utilization Facilities."

Report 7-2 Energy NortbwestlColumbia Generating Station 2005 Annual Radiological 2005 Annual Environmental Operating Radiological Environtnental Operating Report 7-2 Energy Northwest/Columbia Generating Station