ML20082Q090
| ML20082Q090 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1994 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20082Q087 | List: |
| References | |
| NUDOCS 9504280044 | |
| Download: ML20082Q090 (243) | |
Text
{{#Wiki_filter:I . I I I ! DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNITS 1 AND 2 l LICENSES DPR-66 AND NPF-73 1994 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL I I. I I . I I I I I I g gsen88a:s89;r
l Duqu::sna Light Company g 1994 Annual Rrdiological Environmental Report g EXECUTIVE
SUMMARY
This report describes the Radiological Environmental Monitoring Program conducted during 1994 in the vicinity of the Beaver Valley Power Station Units 1 and 2. The Radiological Environmental Program consists of off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1994. Duquesne Light Company operates the Beaver Valley Power Station Units 1 and 2 pressurized water reactors as part of the Central Area Power Coordination Group. The Beaver Valley Power Station Unit 1 operated'throughout 1994 except during maintenance outages January 9 through 19, May 6 through 20, June 1 through July 8 and July 19 through August 2,1994. The high average daily output generated during the year, 838 niegawatts net was reached in November,1994 and the total net electrical generation during the year was 5,504,384 megawatt-hours. Beaver Valley Power Station Unit 2 operated throughout the year except during a g plant outage from June 1 through June 13, 1994. The highest average daily output 5 generated during the year was 847 megawatts net in both January and April 1994 and the total net electrical generation during the year was 7,024,726 g megawatt-hours. 3 in 1994, samples were taken from over 60 sites around Beaver Valley Power Station that included the aquatic, atmospheric and terrestrial environments. More than 3,000 analyses were performed on these samples. During the year, the radioactive releases from BVPS Units 1 and 2 did not exceed the Technical Specification Environmental Limits identified in the Beaver Valley Power Station Operating License Technical Specifications for Units 1 and 2. Based upon the estimated dose to individuals from the natural background radiation exposure, the incremental increase in total body dose to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit No.1 and No. 2, is less than 0.0001% of the annual background. See Section V.I for specific details. The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) is 296 mrem per year. The environmental monitoring program outlined in the Beaver Valley Power Station Units 1 and 2 Technical Specifications was followed throughout 1994. The results for each media are contained in Section V of this report. Examination of effluents and environmental media show that the Beaver Valley Power Station Units 1 and 2 operations have not adversely affected the surrounding environment. F Il EXECUTIVE
SUMMARY
Duqu:snn Light CompIny ; 1994 Annuil Redislogical Environm:ntal Report ' Table of Contents i Section 1. INTRODUCTION .. . . 1-1 l A. Scope and Objectives of the Program . 1-1 B. Description of the Beaver Valley Site . .. 1-1 Section 2. RESULTS AND CONCLUSIONS .. . 2-1 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS . 3-1 A. Environmental Quality Control Program 3-1 B. Evaluation of the Quality Control Program Data 3-16 C. Standard Requirements and Limitations for Radiological ; and Other Effluents . . . 3-18 l D. Reporting Levels . .. . . 3-18 Section 4. MONITORING EFFLUENTS . . . . . 4-1 - A. Monitoring of Liquid Effluents . . 4-1 i
- 1. Description of Liquid Effluents at the Beaver Valley i Power Station. . 4-1 l
- 2. Radioactive Liquid Waste Sampling and Analysis 1 Program . . . 4-1 l
- 3. Results of Liquid Effluent Discharge to the Environment 4-1 l B. Monitoring of Atmospheric Effluents . .. 4-10 4
- 1. Description of Atmospheric Effluent Sources . . 4-10
- 2. Atmospheric Effluent Treatment and Sampling . 4-13 )
. 3. Results . .. . . .. . 4-17 l C. Solid Waste Disposal . . .. . . . 4-17 Section 5. ENVIRONMENTAL MONITORING PROGRAM , 5-1 l A. Environmental Radioactivi.f Monitoring Program . 5-1
- 1. Program Description .. . 5-1
- 2. Summary of Results . . ... 5-6
- 3. Quality Control Program . .. . 5-6 B. Air Monitoring . . 5-22
- 1. Characterization of Air and Meteorology . 5-22
- 2. Air Sampling Program and Analytical Techniques . . 5-22
- 3. Results and Conclusions 5-24 I C. Monitoring of Sediments and Soils 1.
2. Characterization of Stream Sediments and Soils Sampling Program and Analytical Techniques 5-26 5-26 5-26
- 3. Results and Conclusions . . 5-28 D. Monitoring of Feederops and Fooderops 5-29
- 1. Characterization of Vegetation and Foodcrops . 5-29
- 2. Sampling Program and Analytical Techniques 5-29
- 3. Results and Conclusions . 5-32 E. Monitoring of Local Cows Milk 5-33
- 1. Description - Milch Animal Locations 5-33
- 2. Sampling Program and Analytical Techniques 5-33
- 3. Results and Conclusions . 5-36 Two of contents ill
- Duquesna Light Company CI 1994 Annu21 Rcdiologic:1 Environm:ntal Report O !
l F. Environmental Radiation Monitoring . .. 5-37
- 1. Description of Regional Background Radiation and Sources . . . . 5-37 ;
- 2. Locations and Analytical Procedures . 5-37 l
- 3. Results and Conclusions . 5-38 i G. Monitoring of Fish .. . .. 5-43 g
- 1. Description . 5-43 g
- 2. Sampling Program and Analytical Techniques 5-43
- 3. Results and Conclusions . 5-43 H. Monitoring of Surface, Drinking, Well Waters and Precipitation .. . 5-45
- 1. Description of Water Sources . 5-45
- 2. Sampling and Analytical Techniques . 5-46
- 3. Results and Conclusions . . 5-49
- 1. Estimates of Radiation Dose to Man 5-52
- 1. Pathways to Man - Calculational Models 5-52
- 2. Rescits of Calculated Radiation Dose to Man - Liquid Releases . . 5-53
- 3. Results of Calculated Radiation Dose to Man -
Atmospheric Releases . 5-56
- 4. Conclusions . 5-57 I
I l I l l l Iv Tome of contents =
L l Duqu::sns Light Comp ny 1994 Annurl Redi: logic:1 Envircnmsntil R: port m List of Tables 3-1. Quality Control Data - Contractor Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/ day . . .... . . . 3-2 3-2. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Surface Water Samples .. . ... . . . 3-3 3-3. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Drinking Water Samples . .. . . 3-4 3-4. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Milk Samples . .. . . . .. 3-5 3-5. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Feerf, Food and Sediment Samples . . . 3-6 3-6. Quality Control Data - Contractor / Quality Control Laboratory Comparison Spiked Water Samples . . . . .. 3-8 3-7. Quality Control Data - Contractor / Quality Control Laboratory Comparison Spiked Milk Samples . .. . 3-9 3-8. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate and Charcoal Filter Samples 3-10 l 3-9. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/m*) . 3-12 I 3-10. Quality Control Data - Contractor / Quality Control Laboratery Air Particulate Composite Samples Comparison Split for Sr-89 and Sr-90 (pCi/m*) . . .. 3-13 3-11. Quality Control Data - Independent Laboratory / Contractor / Quality I, , Control Laboratory Comparison Spiked Water Samples (pCi/l) 3-14 i i 3-12. Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Comparison Spiked Milk Samples (pCill) . 3-15 ) 4-1. Radioactive Liquid Waste Sampling and Analysis Program 4-7 l 4-2. Results of Liquid Effluent Discharges to the Environi, ent . . 4-9 l 4-3. Radioactive Gaseous Waste Sampling and Analysis Program 4-15 5-1. Radiological Environmental Monitoring Program . . . 5-2 5-2. Environmental Monitoring Program Results (1994) . . 5-7
.g S-3. Pre-operational Environmental Radiological Monitoring Program E Summary . . . . . 5-18 l 5-4. Typical LLDs For Gamma Spectrometry . . .. 5-21 l 5-5. Closest Residence and Garden in Each Sector . . 5-31 5-6. Radiation Dose to Maximum Individual, mrem /yr - Liquid Releases 5-54 5-7. Results of Calculated Radiation Dose to Man - Liquid Releases 5-55 5-8. Results of Calculated Radiation Dose to Man - Atmospheric Releases 5-58 I. -
I ; l l I Ust of Tables V
Duquasna Light Comp:ny U 1994 Annu:1 Ridi:l:gic 1 Environm:nt:1 Report C List of Figures 1-1. View of the Beaver Valley Power Station . 1-2 1-2. Geographical Map and Principal Communities in 40-mile Radius of the Beaver Valley Power Station 1-3 4-1. Liquid Discharge Points to Ohio River 4-2 4-2. Unit 1 Water Flow Schematic . 4-3 4-3. Unit 2 Water Flow Schematic . .. . 4-4 4-4. Unit 1 Liquid Waste System . . 4-5 4-5. Unit 2 Liquid Waste System . . 4-6 4-6. Units 1 and 2 Gaseous Radwaste System . . 4-11 4-7. Units 1 and 2 Gaseous Release Points .. 4-12 4-8. Solid Waste Disposal Diagram . . . . 4-18 5-1. Air Sampling Stations .
. 5-23 5-2. Average Concentration of Gross Beta in Air Particulates 5-25 5-3. Environmental Monitoring Locations - Shoreline Sediments and Soil 5-27 5-4. Environmental Monitoring Program - Feedcrop and Foodcrop Locations 5-30 5-5. Beaver Valley Power Station Milch Animal Census 5-34 5-6. Environmental Monitoring Locations - Milk . 5-35 5-7. TLD Locations - Northwest Quadrant . 5-39 5-8. TLD Locations - Northeast Quadrant 5-40 3-9. TLD Locations - Southeast Quadrant 5-41 5-10. TLD Locations - Southwest Quadrant 5-42 5-11. Environmental Monitoring Program - Fish Sampling Locations 5-44
. 5-12. Environmemal Monitoring Stations Locations - Wells, Surface Water, Drinking Water and Precipitation . . 5-48 I I I' I Vl Ust of Figures a.
Duqu:sna Light Crmp ny 1994 Annurl Ridi: logical Environm:ntil R:p:rt l Section 1. INTRODUCTION l l l A. Scope and Objectives of the Program The environmental program consists of environmental monitoring for radioactivity in j the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, vegetation, river sediments, fish, and ambient l radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. The , Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1994. B. Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsyivania, on a 501 acre tract of l land. Figure 1-1 is a view of the Beaver Valley Power Station. The site is approximately one mile from Midland, Pennsylvania; 5 miles from East Liverpool, I Ohio; and 25 miles from Pittsburgh, Pennsylvania. Figure 1-2 shows the site location in relation to the principal population centers. Population density in the immediate vicinity of the site is relatively low. The population within a 5 mile radius of the plant is approximately 18,000 and the only area within the radius of I concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,500. The site lies in a valley along the Ohio River, it extends from the river (elevation 665 feet above sea level) to a ridge along the border south of the Beaver Valley Power Station at an elevation of 1,160 feet. Plant ground level is approximately 735 feet above cea level. The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery j Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The l Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries: Flow ranges from a minimum of approximately 5000 cubic feet per second (CFS) to a maximum of approximately 100,000 CFS. The mean annual flow is ap;,roximately 25,000 CFS. Water temperature of the Ohio River varies from 32*F to 84*F, the minimum temperatures occur in January and/or February and maximum temperatures in July and August. Water quality in the Ohio River at the site location is affected primarily i by the water quality of the Allegheny, Monongahela, and Beaver rivers. I The climate of the area may be classified as humid continental. Annual precipitation is approximately 36 inches, typical yearly temperatures vary from
- approximately - 3 F to 95"F with an annual average temperature of 52.3'F. The predominant wind direction is typically from the southwest in summer and from the northwest in winter. I Secdon 1. INTRODUCTION 1-1
~_ __ _ _ _ _ . _ _ _ _ _ . _ _ _ . . ._ _ _ _ __ ___
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15 1994 Annuti Radiological Environmsntal Report as Figure 1-2 Geographical Map and Principal Communities in 40-rnile Radius of the Beaver Valley Power Station I LC YCUNGSTCL*N
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CE0 GRAPHICAL HAP AND PRINCIPAL Catt!U:!ITIES IN 40-: TILE RADIUS OF THE BEAVER VALLEY POWER STATION l FIGURE 1-2 i l I
= Section 1. INTRODUCTION 1-3
Duqu:sna Light Company 1994 Annut! Rcdislogic:1 Environm:ntil R: port The design ratings and basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below: Beaver Vallev Unit i Beaver Vallev Unit 2 Thermal & Elec. Rating (Net MW,) 2660 MW,835 MW, 2660 MW,836 MW, l Type of Power PWR PWR No. of Reactor Coolant Loops 3 3 No. of Steam Generators
& Type 3 - Vertical 3 - Vertical Steam Used by Main Turbine Saturated daturated The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator).
Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing g through the turbine, and returned to the steam generators to begin another g steam / water cycle. NOTE: MW,- megawatts thermal MW,- megawatts electrical i I 1-4 Sechon 1. INTRODUCTION "
i-Duqu2sna Light Company J 1994 Annurl Radislogicel Envir nm:ntal Repsrt ) Section 2. RESULTS AND CONCLUSIONS Plant operations at the Beaver Valley Power Station had no adverse effects on the environment as a result of activity at the station during 1994. The Beaver Valley Power Station Unit 1 operated throughout 1994, except during p maintenance outages January 9 through 19, May 6 through 20, June 1 through July 8 L' and July 19 through August 2,1994. Unit 2 operated throughout the year except during a plant outage from June 1 through June 13, 1994. During the year, the p _- radioactive releases were below the limits of 10 CFR Part 50, Appendix 1. The L releases at Beaver Valley Power Station Units 1 and 2 did not exceed the limiting conditions identified in the Beaver Valley Power Station Units 1 and 2 Operating License Technical Specifications. The environmental program for 1994 was the same as in 1993 except several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications and deletion in October of the DLC Training Building Drinking Water Sampling, See Section 5.H.2.b. The Training Building now receives water from the Midland Water Plant (Refer to Table 5-1 for the 1994 Radiological Monitoring Program Outline.) The Beaver Valley Power Station Technical Specifications require sampling of three (3) dairies which have the highest calculated milk pathway potential and one large local dairy. The three dairies are determined from calculations based on the meteorological data and the latest milch animal survey. However, these dairies are L frequently small, consisting of as few as one cow or goat. The availability of milk from single cow dairies and revisions due to updated calculations and surveys y normally result in sampling of several additional dairies during the year in different i sampling periods. The Environmental Monitoring Program also includes two larger dairies in order to L provide continuity in the sampling / analyses program and a control location. Samples from each of these dairies are obtained in addition to the four dairies required by the Environmental Technical Specifications. The collection periods I associated with each of the locations are provided in the detailed summary of the milk monitoring program of this report (Section 5-E). { Activity detected was attributable to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests, medical procedures or to the normal statistical fluctuation for activities near the lower limit of detection (LLD). The { positive results attributable to the Beaver Valley Power Station were consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license. E The results and conclusions for each media of the 1994 Radiological Environmental Monitoring Program are contained in Section 5 of this report. A summary of the 1994 operational environmental data is found in Table 5-2 and a summary of { preoperational data (1974-1975) environmental data is found in Table 5-3. F L
- Section 2. RESULTS AND CONCLUSIONS 2-1
l Duquesna Light Company 0l 1994 Annual Radiological Environmsutal Report O Evaluation of effluent release data from the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and Station Technical Specifications. I l I I Il I Il i 2-2 section 2. RESuLTS AND CoNCLuslONS M
Duqu:sna Light C:mp ny 1994 Annuel Radi: logic 1 Envir nment:1 Rrport Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS [; A. Environmental Quality Control Program The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) elements. _lt should be [ noted that the comparisons made were at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure. See Section 3-8 for discussion of comparison criteria for radiochemical determinations. Values in Table 3-2 through Table 3-12 identified with an asterisk (*) do not meet comparison criteria. However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.
- 1. TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and QC Laboratory)
[. Thirteen (13) TLDs from the Contractor Laboratory and QC Laboratory are co-located, replaced quarterly and results compared. The average of the contractor laboratory and the average of the quality control laboratory agree within i 8.9% of the mean of all results. This is within the precision of typical TLD Systems. However, the annual QC comparison TLDs were noted to have an unacceptable bias (> 30% low). When annual TLDs are removed from the g overall comparison, the average of the contractor laboratory and the average of the quality control laboratory improves to within 7.8% of the mean of all results. Summary data of the TLD Monitoring Program is provided in Table 3-1.
- 2. Split Sample Program (DLC Contractor Laboratory - DLC QC Laboratory)
Samples of surface (river) water and drinking water were routinely split and ' analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory. In addition, samples of other media, such as milk, soil, sediment and'feederop were also split with the DLC QC Laboratory. F L A summary of results of split water samples is provided in Table 3-2 and Table 3-3. There were no non-comparisons in all of the surface and drinking water analysis. Summaries of milk, sediment, soll and feed / food crop split samples is provided in Table 3-4 and Table 3-5. Good overall agreement was obtained with only [ one non-comparison observed of gross alpha in sediment. Some variation may be expected due to small variations in duplicate samples, variations in analytical procedures and in calibration, source type, etc. E Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-1
Duqu:snm Light Company g 1994 Annual Rrdici:giCal Environm:ntCl Repsrt g Table 3-1. Quality Control Data - Contractor Quality Control Laboratory Companson Thermoluminescent Dosimeters - mR/ day TABLE 31 QUALITY CONTROL DATA - CONTRACTOR QUALi1Y CONTROL LABORATORY COMPARISON THERMOLUMINESCENT DOSIMETERS - mRIday 1ST QUARTER 2ND QUARTER DLC DLC - QC DLC DLC - QC Location No. Contractor Lab Location No. Contractor L45 (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) 10 0.15 0.17 10 0.17 0.18 13 0.14 0.17 13 0.15 0.18 14 0.15 0.17 14 0.15 0.18 15 0.12 0.14 15 0.14 0.15 27 0.15 0.17 27 0.15 0.19 28 0.14 0.15 28 0.16 0.19 29B 0.19 0.21 29B 0.18 0.23 32 0.16 0.19 32 0.17 0.18 45 0.15 0.18 45 0.17 0.19 46 0.13 0.16 46 0.14 0.16 47 0.17 0.20 47 0.17 0.21 48 0.16 0.19 48 0.15 0.19 51 0.15 0.19 51 0.15 0.20 3RD QUARTER 4TH QUARTER DLC DLC - QC DLC DLC - QC Location No. Contractor Lab Location No. Contractor Lac (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) (CaSO4.Dy) 3 10 0.15 0.18 10 0.15 0.17 13 0.14 0.18 13 0.15 0.17 14 0.15 0.18 14 0.15 0.17 15 0.13 0.15 15 0.14 0.15 27 0.16 0.17 27 0.16 0 18 28 0.16 0.18 28 0.15 0.18 29B 010 0.24 298 0.18 0.21 32 0.16 0.20 32 0.17 0.17 45 0.16 0.20 45 0.16 0.17 46 0.14 0.16 46 0.16 0.15 ; 47 0.17 0.21 47 0.17 0.20 1 48 0.16 0.20 48 0.17 0.18 ) 51 0.16 0.20 51 0.16 0.18 l l I ANNUAL l DLC DLC - QC l Location No. Contractor lad (CaSO4:Dy) (CaSO4;Dy) 10 0.12 0.16 13 0.12 0.16 14 0.12 0.16 15 0.10 0.14 27 0.12 0.16 28 0.12 0 18 29 8 0.14 0.20 32 0.13 0.19 45 0.13 0.16 46 0.12 0.14 47 0.15 0.17 , 44 0.14 0.18 51 0.14 0.16 3-2 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS ,
Duqu=n3 Light C:mp*ny 1994 Annurl Rrdiologicci Environm:ntal R port Table 3 2. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Surface Water Samples TABLE 3-2 QUALITY CONTROL DATA CONTRACTOR /QUAUTY CONTROL LABORATORY COMPARICON SPUT SURFACE WATER SAMPLES y,, Sampling DLC Contractor DLC - QC g,,p, , ,, Penod Lab (1) Lab (1) I Surface Water (2A) Gross Alpha January April July
<19
<20
<19 15t07 1.5 t 0 7
<10 pCui pCsA pCaA October < 1.2 < 19 pCiA Surface Water Cross Data January 54114 29204 pCiA Apnl 59t13 54104 pCut I Surface Water Co40 July October January 7.1 14 7.5 i 1.5
<30 39!08 57109
<29 pCIA pCut pCA Apnl <30 <20 pCiA July <30 <26 pCa4 October <40 <14 pCA 5urface Water Cs-t 34 January <30 < 1.3 pCiA Apnl < 3.0 < 2.3 pCA Juty <30 < 2.5 pC A October <40 < 1.2 pCiA Surface Water Cs-137 January <30 < 2.5 pCiA Apnl <30 < 14 pCui July <40 < 2.2 pCui October <40 <18 pCut Surface water Tntium tst Quarter < 200 pcui I 220 i 100 composite 3rd Quarter < 200 < 150 pCA Composite Surface Water Sr 89 2nd Quarter < t .2 <08 pCut Composite i
Ath Quarter <t2 <08 pCiA l Composite Surface Water Sr 90 2nd Quarter < 018 <06 pCiA Cornposite l 4th Quarter < 0 22 <0$ pCut Composite Surface Water Co40 2nd Quarter <06 < 14 pCA (high Composite j
**"'*'Y 4th ouarter <i0 <1e pCA anayisis) ,,,
I (1) Uncertainties are based on counting statistics and are speerned at the 95% confidence coefficient.
)
I Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-3
Duquisna Light Comp:ny U, 1994 Annuti Rrdi:l:gic 1 Environm:ntal Rrp;rt C Table 3 3. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Drinking Water Samples TABLE 3-3 I QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPAR: SON SPLIT DRINKING WATER SAMPLES gg, y,, Samphng DLC Contractor DLC - QC Penod Wts Lab (1) Lab (1) Onnoung Water (4) Cs-137 February <3 < 2.2 pCiA (mkiy sput) May <4 <25 pCaA August <4 <39 pCM November <3 <32 pCe/l Dnnking Water CS 134 February <3 < 2.4 pCM YI May <3 pCM
< 2.2 August <4 <37 pCiM November <3 <33 pct /]
Dnnking Water Co40 February <3 <32 pCiA M**dlY spl't) May <3 < 2.2 pCM August <4 <37 pCi/t November <3 <18 pCM Dnnking Water Gross Alpha March < 18 <09 pCM po to) August < 1.4 <18 pCM November < 10 <15 pCM Onnking Water Gross Data March 33211 19105 pCiA
"[,,3 June 3s 1.7 1910e pciA August 39 11 24108 pCiA November 43t06 22t07 pCM Dnnking Water Tntium 2nd Quarter < 200 < 159 pCiA eth Quarter < 100 < 157 pCIA (1) Uncenannties are based on counting statistics and are specified at the 95% confidence coefficient.
I i Il , i I' , 1 I 3-4 section 3. ENVIRONMENTAL MONITORING CONSIDERAT;ONS C
Duqu:sns Light Camp;ny 1994 Annu21 Rrdislogic 1 EnvirCnm:ntil Report ) Table 3-4. Quality Control Data . Contractor /Ouality Control Laboratory Comparison Split Milk Samples TABLE 3-4 I y Sampling QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL 1/.BORATORY COMPARISON SPLtT MILK SAMPLES Analysis
* ~
Units Period I Lab (1) Lab (1) Milk (25) 3-21-94 Sr-89 < 1.0 < 0.4 pCl/l Sr-90 2.0 i 0.2 2.6 i 0.5 pCill 1-131 < 0.21 < 0.1 pCVI Cs-134 < 4.0 < 4.1 pCVI Cs-137 < 5.0 < 3.9 pCl/l I Milk (25) 6-14-94 K-40 Co 50 1-131 1430 i 140
<5
< 0.16 1260 i 180
< 7.2
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<4
<4
< 7.2
< 9.1 pCVI pCVI K-40 1240 i 120 1410 i 170 pCVI I Mak (25) 9-19-94 Sr49 Sr-90
< 0.072
. 5 i 0.2
< 0.8 3.2 i 0.7 pCl/l pCl/l l-131 < 0.16 < 0.4 pCi/l Cs-134 <4 < 2.6 pCl/l Cs-137 <4 < 4.5 pCl/l I Milk (25) 12-12-94 K-40 Co-60 1-131 1280 i 130
<5
< 0.2 1340 i 130
< 7.8
< 0.4 pCVI pCi/l pCh/l Cs-134 <5 < 4.7 pct /l Cs 137 <5 < 4.4 pCill K-40 1300 i 130 1210 120 pCi/l (1) uncertainties are based on countino statistics and are specieed at tne 95% conocence coemcient.
I
)
l Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-5
Duqu sna Light Comprny 1994 Annut! Rrdi:IrgiC 1 Environm:ntal R: port O Table 3-5. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Feed, Food and Sediment Samples TABLE 3-5 I QUAUTY CONTROL DATA CONTRACTOR /QUAUTY CONTROL LABORATORY COMPARISON SPUT FEED, FOOD AND SEDIMENT SAMPLES g Sampling DLC Contractor DLC - @ Period Units Lab (1) Lab (1) Feed (25) 6-14-94 Be-7 0.6 i 0.31 0.7 i 0.21 pCugm (dry) K40 14.6 i 1.5 11.81 i 0.6 pCugm (dry) Co-60 < 0.05 < 0.036 pCugm (dry) 1-131 < 0.004 < 0.028 pCugm (cry) Cs-134 < 0.05 < 0.024 pCugm (dry) Cs-137 < 0.05 < 0.021 pCugm (dry) Feed (25) 4/17 6/14 Sr-90 0.075 0.004 0.013 i 0.004 pCVgm (dry) Food (10) 9-26-94 K-40 1.7 i 0.2 2.3 i 1.6 pCugm (wet) Co-60 < 0.01 < 0.007 pCugm (wet) 1-131 < 0.0045 < 0.012 pC1/gm (wet) Cs 134 < 0.01 < 0.007 pCugm (wet) Cs 137 < 0.01 < 0.004 pCugm (wet) Sediment (2A) 10-7-94 Gross Alpna 11.015.0* 30.5 i 6.4 pCugm (dry) Gross Beta 34.0 i 3.0 22.4 i 3.9 pCugm (dry) , Sr-89 < 4.7E-2 < 4 3E-2 pCugm (dry) St-90 < 2.0E-2 < 2.1E-2 pCugm (dry) Co-58 0.10 t 0.05 0.1310.05 pCugm (dry) Co-60 0.6210.07 0.58 i 0.05 pCugm (dry) Cs-134 < 0.07 < 0.11 pCugm (dry) Cs-137 0.19 i 0.05 0.2010.05 pCl/gm (dry) Ra-226 2.34 i 0.75 2.8210.67 pCugm (dry) K40 12.60 i 1.30 14.29 i 0.99 pCUgm (dry) Soil (30) 7-21-94 Gross Alpha 17.0 i 6.0 13.6 i 4.0 pCugm (dry) Gross Beta 29.013.0 17.6 i 2.9 pCugm (dry) Sr-90 0.056 i 0.011 0.058 i 0.02 pCugm (dry) Co-58 < 0.03 < 0.12 pCVgm (dry) m Co-60 < 0.03 < 0.019 pCVgm (dry) Cs-134 < 0.03 < 0.077 pCugm (dry) Cs-137 0.3310.04 0.3910.05 pCugm (dry) Ra-226 1.42 i 0,45 1.9010.41 pCUgm (dry) K40 10.40 i 1.00 11.39 i 0.65 pCugm (dry) (1) Uncertaintres are based on counting statistics and are specined at the 95% contdence coemcient. See Section 3A2 and 3-B. 3-6 Secton 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
- E Duqu:sna Light Ccmp ny
-5 1994 Annurl R dislogic 1 Environm:ntal Report
- 3. DLC QC Laboratory Program Spiked samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for analysis. Table 3-6 (water) and Table 3-7 (milk) provide data from this portion of the QC Program. See Section 3-B for evaluation of the data.
- 4. Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory)
Duplicate air particulate and charcoal filters (radioiodine) samples were collected at Location #30 and compared during the year on a weekly basis. Comparison of particulate and charcoal samples alternated from week to week. Duplicate monthly air particulate filters, composited from the weekly air particulate filters, were analyzed 6 months out of the year for gamma activity. Duplicate quarterly air particulate filters, composited from the weekly air I particulate filters, were analyzed for Sr-89 and Sr-90 activity for each quarter of the year. Table 3-8, Table 3-9 and Table 3-10 provides data for this portion of the QC program.
- 5. Contractor and QC Laboratory - Internal QC Program The Contractor and QC Laboratory maintained their own QC Program which I included participation in the Environmental Protection Agency - Environmental Monitoring Safety Laboratory (EPA - EMSL) Interlaboratory Cross Check Program. This cross check program indicated that the Contractor and QC I.
. 6.
Laboratory results were in agreement with EPA EMSL. See Appendix i and 11. Special QC Program (DLC Contractor Laboratory - Independent Laboratory - DLC QC Laboratory) Low level spiked water and milk samples are prepared by a vendor noted for supplying quality primary standards with NIST traceability. The " spiked to" values are used for calculating comparison acceptance criteria. The prepared spiked samples are then split 3 ways between an Independent Laboratory (a I laboratory qualified to perform analysis for REMP programs), the DLC Contractor Laboratory, and the DLC QC Laboratory. A summary of results of this portion of the QC program is provided in Table 3-11 and Table 3-12. See Section 3-B for evaluation of this data. ! I I ! 'I section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-7
Duqu sna Light Ccmptny b 1994 Annual Rrdiologic:l Environmsntcl Report C = Table 3-6. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Spiked Water Samples TABLE 3-6 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPIKED WATER SAMPLES Sample Identification Sample DLC - QC Date N o. Analysis Lab (1) 3-25-94 W-109 Sr-89 28.0 i 1.0 26.4 i 5.3 pCi/l Sr-90 18.0 i 1.0 18.8 i 3.8 pCi/l 4-27-94 W-110 H-3 9200 i 300 9848 i 295 pCi/l 4-27-94 W-111 Co-60 28.5 i 3.4 23.9 i 1.6 pCi/l Cs-134 36.2 i 3.6 32.1 i 1.7 pCl/l Cs-137 40.0 i 4.0 35.1 i 2.5 pCl/l 6-8-94 W-112 1-131 46.0 i 1.0 46.0 0.7 pCill 6-30-94 W-113 Gross 20.0 i 2.0 20.8 i 1.0 pCi/l Alpha Gross 34.0 i 2.0 29.5 i 1.1 pCill Beta 9-15-94 W-114 Sr-89 38.0 i 1.0 31.4 i 2.7 pCl/l Sr-90 35.0 i 1.0 35.6 i 1.6 pCill 10-6-94 W-115 l-131 91.0 i 1.0 92.5 i 1.0 pCi/l 11-30-94 W-116 H-3 23000 i 1000 24099 i 424 pCl/l 12-8-94 W-117 Gross 15.0 i 5.0 21.9 i 1.7 pCi/l Alpha Gross 63.0 i 6.0* 45.9 i 1.2 pCi/l Beta (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. See Section 3-B. I 3-8 s" Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
Duqursnn Light Comp:ny 1994 Annuri Rrdiologicci Environm:ntil Report Table 3-7 Quality Control Data - Contractor / Quality Control Laboratory Comparison Spiked Milk Sarnples I TABLE 3-7 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPIKED MILK SAMPLES Sample identification Sample DLC - QC Date N o. Analysis Lab (1) 1-14-94 Mi-51 Sr-89 30.0 i 3.0 28.2 i 3.8 pCill i Sr-90 45.0 i 1.0 41.2 i 1.2 pCl/l Cs-134 21.2 i 4.1 27.2 i 5.7 pCi/l Cs-137 28.5 i 4.6 34.6 8.2 pCill K-40 1050 i 100 1290 i 100 pCi/l 2-9-94 Ml-52 1-131 56.0 i 1.0* 40.4 i 1.0 pCi/l I 4-27-94 Ml-53 Cs-134 51.3 i 5.2 52.0 i 5.3 pCill I Cs-137 62.4 i 6.2 61.9 i 8.3 pCi/l K-40 1320 i 130 1450 i 130 pCl/l 6-8-94 Mi-54 l-131 45.0 i 1.0 51.7 i 0.6 pCi/l I. . 7-26-94 Mi-55 Sr-89 31.0 i 3.0" 16.4 i 4.8 pCi/l Sr-90 25.0 i 1.0 25.3 i 1.4 pCi/l Cs-137 47.8 i 7.4 47.8 i 7.4 pCi/l l K-40 1550 i 130 1550 i 130 pCi/l l 10-6-94 Ml-56 l-131 pCi/l I 10-6-94 Ml-57 l-131 Cs-134 80.0 i 1.0 63.0 i 1.0 35.9 i 4.0 77.4 i 0.9 65.2 0.9 35.0 t 6.0 pCi/l pCi/l I Cs-137 K-40 49.1 i 4.9 1350 i 140 46.1 i 9.4 1310 i 150 pCill pCi/l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. See Section 3-B 4. I ! Section 3. ENVIRONMENTAL MONITORlhG CONSIDERATIONS 3-9
en y, TABLE 3 8 d j QUALITY CONTROL DATA p p CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON E m SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES
- z
< Air Particulates g Air lodine [ Q pCl/Cu. Meter (Beta) pCi/Cu. Meter , M DLC DLC 5 e Sample Date Contractor Sample Date Contractor DLC - @ gg I Lab (1) UI * "I Lab (1) a t O 1/3 - 1/10 0.017 i 0.003 0.017 0 003 12/27 - 1/3 < 0.02 < 0.01 El g q y $ 1/17 - 1/24 0.030 1 0.003 0.029 1 0.003 1/10 - 1/17 < 001 < 0.01 bE g o 1/31 - 2/7 0.023 i 0.003 0.020 i 0.003 1/24 - 1/31 < 0.01 < 001 3
$ c m
8 a 2/14 - 2/21 0.017 i 0.030 2/7 - 2/14 < 0.01 < 0.01 0.021 1 0.003 !!L . n ]mc g 2/28 - 3/7 0 016 i 0.030 0.019 i 0.003 2/22 - 2/28 < 0.01 < 0.02 yp $g j 3/14 - 3/21 0.014 i 0.003 0.020 i 0.003 3/7 - 3/14 < 0.02 < 0.01 hh o$- y 3/28 - 4/4 0.014 i 0.003 0.017 i 0.003 3/21 - 3/28 < 0.01 < 0.01 jk $c 5
- 4/11 - 4/18 0.016 i 0.003 0.010 1 0.002 4/4 - 4/11 < 0.01 < 0.01 E 4/25 - 5/2 0.012 1 0.003 0.010 1 0.003 4/18 - 4/25 < 0.02 < 0.01
{ {Q 5/9 - 5/16 0.014 i 0.003 0.011 1 0.002 5/2 - 5/9 < 0.01 < 0.01 g yj 5/23 - 5/31 0.012 t 0.003 0 013 1 0.002 5/16 - 5/23 < 0 02 < 001 ?. 3 8 m$ x 6/6 - 6/i3 0.017 i O.003 0.018 i 0 002 5/31 - 6/6 < 0.02 < 0.01 E 6/20 - 6/27 0 016 i 0.003 0.012 1 0.002 6/13 - 6/20 < 0.01 < 0.01 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. $o Q 3
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TABLE 3 8 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES Air Particulates Air lodine pCI/Cu. Meter (Beta) pCl/Cu. Meter Sample Date Cont or Sample Date con actor Lab (1) Lab (1) a e 7/5 - 7/11 0.010 i 0.003 0.014 i 0.002 6/27 - 7/5 < 0.01 < 0.01 y 7/18 - 7/25 0.022 i 0.003 0 020 1 0.003 7/11 - 7/18 < 0.01 < 0.01 g 8/1 - 8/8 0.023 1 0.003 0.020 1 0.003 7/25 - 8/1 < 0.01 < 0.01 $
=
8/15 - 8/22 0.019 i 0.003 0.016 1 0.003 8/8 - 8/15 < 0.02 < 0.01 8/29 - 9/6 0.015 i 0.003 0.015 i 0.002 8/22 - 8/29 < 0.01 < 0.01 $.g 9/12 - 9/19 0.031 i 0.004 0.030 1 0.003 9/6 - 9/12 < 0.02 < 0.01 [--, m 9/26 - 10/3 0.017 i 0.003 0.014 i 0.002 9/19 - 9/26 < 0.01 < 0 01 $t 10/10 - 10/17 0.023 1 0.003 0.020 i 0.003 10/3 - 10/10 < 0.02 < 0.01 g P 10/24 - 10/31 0.020 i 0.003 0.019 i 0.003 10/17 - 10/24 < 0.01 < 0.01 {Q j 11/7 - 11/14 0.021 1 0.003 0.024 i 0.003 10/31 - 11/7 < 0.02 < 0.01 yj y 11/21 - 11/28 11/14 - 11/21 < 0.01 < 0.01 3 z 0.019 i 0.003 0.016 i 0.002 e$x c 12/5 - 12/12 0.012 1 0.003 0.017 i 0.003 11/28 - 12/5 < 0.02 < 002 g 12/19 - 12/27 0.025 i 0.003 0.027 i 0.003 12/12 - 12/19 < 0.01 < 0.01 ] h E (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. $ Y 8 2 5 8 s . a Y
Duqu:sna Light Comp ny C 1994 Annurl Redi:l:gic 1 Environm:ntil Rep:rt C Table 3-9. Quahty Control Data - Contractor /Ouality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/m') TABLE 3-9 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE SAMPLES (GAMMA)(pCl/m*) Sample Date Nuclide ntrador DLC - QC Lab (1) Lab (1) < Be-7 0.097 i 0.010 0.071 i 0.027 January Others < LLD < LLD Be-7 0.125 i 0.012 0.103 i 0.027 Others < LLD < LLD Be-7 0.140 0.014 0.119 i 0.023 May Others < LLD < LLD Be-7 0.173 i 0.017 0.101 t 0.027 July Others < LLD < LLD Be-7 0.117 0.012 0.082 i 0.018 September Others < LLD < LLD Be-7 0.121 i 0.012 0.076 i 0.021 November K-40 0.012 i 0.006 < LLD Others < LLD < LLD (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. LLD - Lower Limit of Detection . 3-12 I C Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
Duquesna Light Comptny 1994 Annual Rrdiologic:1 Environm:ntal Report Table 310. Quality Control Data - Contractor / Quality Control Laboratory Air Particulate Composite Samples Comparison Split for Sr-89 and Sr-90 (pCl/m') TABLE 3-10 QUALITY CONTROL DATA CONTRACTORIQUALITY CONTROL LABORATORY AIR PARTICULATE COMPOSITE SAMPLES COMPARISON SPLIT FOR Sr-89,90 (pCl/m') DLC - Contractor DLC - QC Sample Date Nuclide g ist Quarter Sr-89 < 4.9E-4 < 4E-4 Composite Sr-90 < 1.0E-4 < 2E-2 2nd Quarter Sr-89 < 2.3E-3 < 6E-4 Composite Sr-90 < 4.1E-4 < 4E-4 3rd Quarter Sr-89 < 8.6E-4 < 4E-4 Composite Sr-90 < 1.0E-4 < 2E-4 4th Quarter Sr-89 < 2.7E-3 < 4E-4 Composite Sr-90 < 4.1 E-4 < 4E-4 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. I l l i l 1 I . \ . l Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-13
--_--_______J
Duquasn3 Light Campany C 1994 Annurl Rcdini:giC 1 Envircnmentil R: port Table 3-11. Quality Control Data - Independent Laboratory / Contractor /Ouality Control Laboratory Comparison Spiked Water Samples (pCi/l) TABLE 3-11 QUALITY CoffTROL DATA INDEPENDENT LABORATORY / CONTRACTOR /QUAUTY CONTROL LABORATORY COMPARISON SPIKED WATER SAMPLES (pCl/l) Sarnple identification Samp6e Type independent DLC - OC Date No. and Analyses T M Lab (1) Lae (1) 3) Sr-89 20.7 i 1.0 21.5 i 1.0 13.1 i 1.4* Sr-90 14.6 i 0.7 14.5 i 1.0 14.9 i 0.8 2-7-94 6-131 10.2 i 03 9.6 i 0.7 10.3 i 0.4 Cs-134 20.0 i 1.0 19.7 i 3.0 15.8 i 3.1 Cs-137 10.1 i OS 14.9 i 3.1' 10.2 i 4.1 2-7-94 H-3 680 i 30 790 i 120 778 i 120 5 Sr-89 18.4 i 0.8 20 5 i 2.5 12.4 i 2.7* Sr-90 15.4 1.0 16.0 i 1.0 14.4 i 0.8 5-10-94 Co-60 9.5 i 1.0 11.1 i 3.7 10.4 i 2.1 53 7 1-131 25.0 i 1.2 24.0 i 1.0 10.8 i 0.2' Cs-137 16.0 i 0.8 20.8 i 4.1 15.7 i 3.2 5-10-94 H-3 980 i 50 840 i 120 1094 i 74 5 Sr-89 9.5 i 05 10.0 i 1.0 4.7 i 5.3* St-90 10.6 i 0.5 10.5 i 1.0 10.0 i 1.9 8-8-94 M n-54 23.9 i 1.2 30.1 i 4.3 25.4 i 1.7 3 , 6-131 18.9 i 0.9 19.0 i 1.0 19.2 i 0.4 Cs-137 9.6 i 05 12.1 i 3.7 10.1 i 1.6 8-8-94 H-3 1140 i 60 1100 i 100 1239 i 72 5 Sr-89 14.9 i 0.8 13.5 i 1.0 13.1 i 1.6 Sr-90 20.0 i 1.0 22.0 i 1.0 18.4 i 0.6 10-24 94 Co-58 20.0 i 1.0 20.512.5 20.8 i 3.2 5 1 Co-60 9.9 i 0.5 12.1 i 2.8 10.4 i 1.5 l-131 20.0 i 1.0 15.0 i 1.0 19.5 i 0.5 10-24-94 H-3 1210 i 60 1100 i 100 1228 i 70 5 (1) Uncertaintres are based on cou iting statistics and are reported at the 95% confidence coeffloent. See Section 3-B. I i i l 1 3-14 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS l
l Duquisne Light Company l 1994 Annucl Rcdi:l gICc1 Envir:nm:ntil Rep:rt ; Table 3-12. Quality Control Data . Independent Laboratory / Contractor /Ouality Control Laboratory Comparison Spiked Milk Samples (pCill) i I - TABLE 3-12 QUAUTY CONTROL DATA INDEPENDENT LABORATORY # CONTRACTOR /QUAUTY CONTROL LA80ftATORY COMPARISON SPIKED MILK SAMPLES (pciti) Sample Identincatten Sample Type indspondent DLC.OC Date No. and Analyses T TM Lab (1) M (1) Sr-89 29.7 i 1 3 25.5 i 1.0 25.5 i 2.2 Sr-90 19.9 i 1.0 223 i 1.0 24.4 i 0.9 2-7-94 1-1 4. t 0.7 163 i 1.0 iti i 05 52 70 Cs-134 15.3 i 0.8 16.2 i 2.9 14.4 i 3.7 Cs 137 191 i 1.0 26.2 i 3.3 17.6 i 5.0 Sr-89 22.3 i 0.8 19.5 i 1.5 16.512.0* Sr-90 15.110.7 18.5 i 1.0 18.0 i 0.7 5-10-94 3,",h s-131 24.0 i 0 5 26.0 i 1.0 24.1 i 0.4 Cs 134 9.4 i 0.5 12.513.8 9.512.0 Cs-137 19.4 i 0.7 24.5 i 4.5 22.8 i 3.0 Sr-89 25.0 i 1.3 19.5 i 2.0 18.8 i 1.6 Sr-90 14.9 i 0.7 19.5 i 1.0 14.9 i 0.6 8-8-94 1-131 5.5 i 0.3 6.2 i 0.3 5.7 i 0.2 52 2 Cs-134 10.3 i 0.5 11.3 i 3.5 9.3 i 1.0 Cs-137 16.6 i 0.8 22.1 i 3.9 17.9 i 1.5 Sr-89 20.0 i 1.0 19.5 i 1.5 18.7 i 1.7 Sr-90 20.0 i 1.0 23.011.0 19.4 i 0.7 10 24-94 1-131 21.0 i 1.0 22.011.0 19.9 i 0.4 52 Cs-134 11.3 i 0.6 12.0 i 3.0 12.6 1.2 Cs-137 10.110.5 11.2 i 3.4 12.1 i 1.9 (1) Uncertainties ;are based on counting statistics and are based on the 95% confidence coefficent. See Section S-B. r- [ [ [ [ E Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-15
q Duqucsn3 Light Comp:ny La 1994 Annu 1 Rcdiol::gical Environm:ntal R: port 0
- 7. Pennsylvania Department of Environmental Resources Program The Pennsylvania Department of Environmental Resources (PDER) also conducted a surveillance program in the vicinity of the site. Samples of air, river water, drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program. Results were compared quarterly in 1994.
B. Evaluation of the Quality Control Program Data The split and spiked sample program indicates that the Contractor and QC Laboratory are generally performing satisfactorily in accordance with " Criteria for Comparing Analytical Measurements from NRC Compliance Office." In addition, an independent laboratory is used to supplement the regular prograni. Comparisons r between the independent, QC and Contractor laboratories are generally acceptable and demonstrate a satisfactory performance by the DLC contractor. All media were found to be in agreement in accordance with NRC criteria as listed in Inspection Guidance 84750-03 dated 12/04/90 with the exception of those media in Table 3-2 through Table 3-12 identified with an asterisk (*). Comparisons are obtained by dividing the comparison standard by its associated uncertainty to obtain the resolution. The standard value is multiplied by the ratio values obtained from the following table to find the acceptance band for the result to be compared. Note that in the case where the counting precision of the standard yields a resolution of less than 4, a comparison cannot be calculated. Resolution Ratio
<4 -
4-7 0.5 - 2.0 8 - 15 0.6 - 1.66 15 - 50 0.75 - 1.33 51 - 200 .8 - 1.25
> 200 .85 - 1.18 i
I l I l l 3-16 E Section 3. ENVIRONMENTAL MONITORING CONSloERATIONS
Duqu:sna Light Comp ny 1994 Annuri Rcdialzgicci Environmsntal Report B. Evaluation of the Quality Control Program Data (Cont.) j l
- Contractor Laboratory
.I The Contactor Laboratory had a very satisfactory performance throughout the 1994 QC Laboratory Program. In the Independent Laboratory Program, with reference to the high quality spikes as reported in Table 3-11 and Table 3-12, )
only one result for Cs-137 in water was slightly out of comparison, with all other i results for water and milk meeting the comparison criteria. In the QC Laboratory spike sample program, as reported in Table 3-6 and Table 3-7 for water and milk, there were a total of three non-comparisons. Two non-comparisons, water sample W-117 for gross beta and milk sample M-52 for 1-131 were close to agreement and were supported by other comparisons. The non-comparison for milk sample M-55 Sr-89 is considered to be due to Sr-89 analysis problems early in the year by the QC laboratory (See QC Laboratory
'I below) and since the Contractor result compared with the " spiked to" Sr-89 value provided by the QC laboratory. Note also that all Sr-89 analysis performed within the Independent Laboratory Program by the Contractor achieved comparison.
Within the Contractor /QC Lab split sample program samples for feed, sediment, and soil are particularly subject to sample variability. Only one non-comparison was noted for gross alpha in sediment.
= Quality Control Laboratory The QC Laboratory had generally satisfactory performance within the independent Laboratory Program. One result for 1-131 in water was out of I comparison low in the second quarter, but was followed by excellent results for I-131 in the third and fourth quarters. Four non-comparisons for Sr-89 occurred.
Three were in water (the last in the third quarter was compounded by loss of sample and chemical yield) and one in milk. Following procedure enanges and training good results were achieved for the remainder of the year. Based on all available QC program data, the data from the Contractor and QC Laboratory's internal EPA Interlaboratory Cross Check Program, and comparisons with the PDER, the Environmental Monitoring Program for 1994 is acceptable with I respect to both accuracy and measurement. Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-17
Duqu:sno Light Comp:ny U 1994 Annu:1 R:diol:gic:1 Environm:nt:1 Report U C. Standard Requirements and Limitations for Radiological and other Effluents The Beaver Valley Power Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases are controlled to ensure that limits set by Federal or State governments are not exceeded, in addition, self-imposed limits have been established to further limit discharges to the environment. Beaver Valley Power Station is subject to regulations which include the Code of Federal Regulations 10 CFR (Energy), Gaseous Discharge Permits for auxiliary boilers and diesel generators, PA Code - Tit.e 24, Part I, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No.1-70 and 2-70, Environmental Protection Agency (EPA), National Pollution Discharge Elimination (NPDES) Permit I
#0025615, and the Beaver Valley Power Station Technical Specifications. m D. Reporting Levels A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in the Beaver Vsliey Power Station Technical Specifications when averaged over any calendar quarter. Also, when more than one of the radionuclides are detected in the sampling medium, this report shall be submitted if:
Concentration (1) Concentration (2)
+ + .. 2: 1.0 i Limit Level (1) Limit Level (2) l There were no analytical results of environmental samples during 1994 which '
exceeded Beaver Valley Power Station reporting levels. 3-18 Secton 3. ENVIRONMENTAL MONITORING CoNSIDERAT!oNS E
l Duquesne Light Company l 1994 Annut! Radiologic:1 Environmental Report Section 4. MONITORING EFFLUENTS j l Monitoring of Liquid Effluents A. i
- 1. Description of Liquid Effluents at the Beaver Valley Power Station.
l Most of the water required for the operation of the Beaver Valley station is taken from the Ohio River, and returned to the river, used for makeup to various plant systems, consumed by station personnel, or discharged via a sanitary waste , system. In addition, well water and liquid effluents are discharged to the Ohio i River using discharge points shown in Figure 4-1. Schematic diagrams of liquid i flow paths for the Beaver Valley Power Station are shown in Figure 4-2, ) Figure 4-3, Figure 4-4 and Figure 4-5 i , 2. Radioactive Liquid Waste Sampling and Analysis Program See Table 4-1. l
- 3. Results of Liquid Effluent Discharge to the Environment ..
.- See Table 4-2.
I I l 1 I 'I I l I Section 4. MONITORING EFFLUENTS 4-1 i
Duqu sna Light Company EI 1994 Annuct Radiological Environmsntal Report g Figure 41 Uquid Discharge Points to Ohio River I.
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I I Duqu sna Light Company 1994 Annu:1 Rrdial gic 1 Environm:ntal R:p:rt Figure 4-2. Unit 1 Water Flow Schematic E! ;
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Duqu:sna Light Company 1994 Annuri Rcdiologicil Environm:ntrl Report l Figure 4-4. Unit 1 Uquid Waste System 22
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q g y y . y y TABLE 4-1 Radioactive Liquid Waste Sampling and Analysis Program y LIQUID SAMPLlHG N OF MER UMIT OF ANALYSIS ACTIVITY DETECTION (LLD) p RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml)*
- n p p Principal Gamma E SE-7 Emitters' 6' Each Batchh Each Batchh I-131 1E-6 _.
< e p Dissolved and h T Batch Waste Release One Batch /Mh Tanksd Namma Mtters) a y Each Batchh P
Compositeb M H-3 Gross Alpha 1 E-5 IE-7 f 5 g O Sr-89, Sr-90 P SE-8 v
$ hm
-3 Each Batchh Compositeb Fe-55 1E-6 o
? e 8_.p:
Principal Gamma 5 6 W SE-7 Grab Samples Emitters' a yg mPoh I-131 1E-6 ., [h Dissolved and j- fM B. Continuous ra Sampeo ntraM Gases ES p gg Releasests ( amma m tiers) q gx M H-3 1 E-5 g !!L Grab Samples x
- Compositec Gross Alpha 1E-7 m 3 u 5 O Sr-89, Sr-90 SE-8 o
" Grab Sampleg 3
-" Compositec Fe-55 1E-6 E
o W - At least once per 7 days
$ M - At least once per 31 days 8 O - At least once per 92 days g P - Completed prior to each release Q
?
Ei w
'i
-4
n Duqu:sns Light Comp ny M 1994 Annut! Rrdisl:gicri Environm:nt:I Report u TABLE 4-1 NOTATION
- a. The Lower Limit of Detection (LLD).
l b. A composite sample is one in which the quantity of liquid sainpled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. To be representative of the quantities and concentrations of radioactive ,
materials in liquid effluents, samples shall be collected continuously in ' proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- d. A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to a,sure representative sampling.
- e. A continuous release exists when the discharge of liquid wastes is from a l non-discrete volume; e.g., from a volume of a system having an input flow l during the continuous release. For BV-1, this is applicable to the Turbine l Building drains and the AFW Pump Bay Drain System and chemical waste sump, when the secondary coolant gross radioactivity (beta and gamma) is greater than 1E-5 Cl/ml. For BV-2, this is applicable to the Turbine Building drains when the secondary coolant gross radioactivity (beta and gamma) is j greater than 1E-5 Ci/ml.
- f. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59 Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are ,
measurable and identifiable, together with the above nuclides, shall also be I identified and' reported. Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD level for that nuclide. The "less than" g values should not be used in the required dose calculations. When unusual E circumstances result in LLD's higher than required, the reasons shall be documented in the Semi-Annual Radioactive Effluent Release Report. g) g!
- g. Whenever there is primary to secondary leakage, sampling is done for Turbine 1 Building drain effluents by means of grab samples taken every four hours during the period of discharge and analyzed for gross radioactivity (beta and j gamma) at a senstivity of at least 1E-7 Cl/ml and recorded in the plant I I
records, along with the flow rate. Primary to secondary leakage is considered to be occurring whenever measurements indicate that secondary coolant gross radioactivity (oeta and gamma) is greater than 1E 5 Ci/ml. In addition, two (2) ) plant personnel shall check release calculations to verify that the limits of Technical Specifications 3.11.1.1 and 3.11.1.2 are not exceeded .
- h. Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling will be performed by means of a grab sample taken every 4 hours during pump operation.
4-8 Section 4. MONITORING EFFLUENTS "
Duquesna Light Company 1994 Annual Radiol:gical Environm:nt:1 Report Table 4-2. Results of Uquid Effluent Discharges to the Environment TABLE 4-2 RESULTS OF LIQUID EFFLUENT DISCHARGES TO THE ENVIRONMENT Effluent Type Results for 1994 Steam System The Steam System Blowdown was recycled when Biowcown practicable. I Batch Radioactive Waste Liquids Routine planned releases of liquid effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 3/4.11.1 of the Technical Specifications and Section 1 of the Offsite Dose Calculation Manual. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi-annual Radioactive Effluent Release Reports for 1994. Continuous Radioactive waste liquids were not discharged in a Radioactive continuous mode during 1994. Waste Liquids
.I. .
I !I I s._ __ _ _s 49
Duqu::sna Light Comp:ny 1994 Annual Rcdirl:gictl Environm:nt:1 R:p;rt O B. Monitoring of Atmospheric Effluents
- 1. Description of Atmospheric Effluent Sources Beaver Valley Power Station (Units 1 and 2)
The Beaver Valley Power Station identifies isotopes according to the Technical Specifications and Regulatory Guide 1.21. Prior to waste gas decay tank batch releases and containment purge releases, an analysis of the principal gamma emitters is performed. The principal gamma emitters include noble gases, iodines, and particulates. Figure 4-6 shows the gaseous radwaste system at [ Beaver Valley Power Station. The environmental gaseous release points also require specific nuclide identification. These points include:
- a. Unit 1 Release Points:
- 1) The Ventilation Vent located on top of the Unit 1 Primary Auxiliary Building.
- 2) The Supplementary Leak Collection and Release System (SLCRS)
Vent located on top of the Unit 1 Containment FJuilding.
- b. Unit 2 Release Points;
- 1) The Ventilation Vent located on top of the Unit 2 Primary Auxiliary Building.
- 2) The Supplementary Leak Collection and Release System (SLCRS)
Vent located on top of the Unit 2 Containment Building.
- 3) The Condensate Polishing Building Vent located on top of the Unit 2 Condensate Polishing Building.
1
- 4) The Waste Gas Storage Vault Vent located on top of the Unit 2 )
Decontamination Building. ,
- 5) The Decontamination Building Vent located on top of the Unit 2 Decontamination Building.
- c. Unit 1 and Unit 2 shared release point; ;
- 1) The Process Vent located on top of the Unit 1 Cooling Tower.
These points are continuously monitored t'or particulates and gases. Grab samples are obtained on a weekly basis and are analyzed for noble gas gamma emitting isotopes and trit!um. Weekly continuous samples are obtained on filter paper and charcoal cartnoges. The filter papers are analyzed for particulate gamma emitting isotopes and gross abha. Composites of the filter papers are analyzed monthly for Sr-89 ano Sr-90. The charcoal cartridges are analyzed for 1-131.1-133 and 1-135. Figure 4-7 shows these gaseous release points. 4-10 section 4. uoNIToRING EFFLUENTS
I Duquasna Light Comp:ny ; 1994 Annual Rcdiological Environm ntel Report ! Figure 4-6. Units 1 and 2 Gaseous Radwaste System
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FIG'JRE 4 UNITS 1 AND 2 GASEOUS stADWASTE SYSTEM l 1 l _I Section 4. MONITORING EFFLUENTS 4-11 I l
Duqu:sna Light Company '] L 1994 Annual Radiol:gic:1 Environm:ntal R port O Figure 4-7. Units 1 and 2 Gaseous Release Points
--z., - Ohio R'"'
Uh ~
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- 1. Unit 1: Testilation Test 79 feet : 24 seters
- 2. Cait 1: Costalasest / SMIS feet 154 feet : 47 seters
- 3. Osit 1 & 2: Process fest 475 feet : 145 seters N I
- 4. hit 2: festilsties Test 1) 85 feet : 25 seters
- 5. Dsit 2: Costaissent / S,C15 Test 154 feet : 47 seters
- 5. Unit 2: Ceedessate Polishing Beilding feet 80 feet : 24 seters g 1 1.Delt2: Easts Gas Storage Tanit feat 80 feet: 21 seters l.Dait2: Decestasinatios Evilding feet 80 fest : 24 seters
( FIGURE 4 UNITS 1 AND 2 GASEOUS RELEASE POINTS i l l 4.n s _ o om10 - m uters I
Duqu:sn3 Light Comp:ny 1994 Annuri Rrdi:logicri Envircnm:nt:1 Report
- 2. Atmospheric Effluent Treatment and Sampling Beaver Valley Power Station (Units 1 and 2)
Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gt;, is chilled to condense most of the water vapor. Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A smali amount of
'litrogen and radioisotopes consisting of noble gases, particulates and radiolodines are also present in this system.
The overhead gas compressor directs the radioactive gas stream to a gas surge tank. Gas is periodically transferred from the Unit 1 or Unit 2 surge tank to one of the three (3) decay tanks at Unit 1 or one of the seven (7) decay tanks at Unit
- 2. After the decay tanks are sampled and authorization obtained for discharge, the flow of the waste gases from the decay tanks (2 scfm) is rapidly diluted with about 1000 scfm of air in order to dilute hydrogen and radioactive effluent I concentration. The gases are then combined with nitrogen purge from the oxygen analyzers, calibration gas from the oxygen analyzers, the main condenser air ejector exhaust, the containment vacuum system exhaust, aerated I vents of the vent and drain system, discharge of the overhead gas compressor and the purge from the multi sample point radiation monitor. The mixture is then filtered through one of the gaseous waste disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the i atmosphere via the process vent on the top of the Unit 1 cooling tower. The radioactivity levels of the stream are monitored continuously.
Should the radioactivity release concentration of the stream go above the I allowable setpoi.it, a signal from the radiation monitor will stop all flow from the Unit 1 or Unit 2 decay tanks being discharged. I During a shutdown period after the Unit 1 or Unit 2 containment has been sampled and the activity levels determined, purging may commence through the Ventilation Vent located on top of the Auxiliary Building or the Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Reactor Containment Building or the Process Vent located on top of the Cooling Tower. Areas in the Unit 1 Auxiliary Building (subject to radioactive contamination) are l monitored for radioactivity prior to entering the common Ventilation Vent. These individual radiation monitors aid in identifying any sources of contaminated air, j The Ventilation Vent is also monitored continuously by several redundant channels of the Radiation Monitoring System (RMS) and is sampled periodically. Upon a upper activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the Supplementary Leak Collection and Release System (SLCRS) and to the SLCRS Vent. I I l i Section 4. AAONITORING EFFLUENTS 4-13
Duqu sna Light Compsny E 1994 Annut! Radiological Envirenmsntel R: port n" Areas in the Unit 2 Auxiliary Building (subject to radioactive contamination) are monitored for radioactivity prior to entering the filter banks for the Supplementary Leak Collection and Release System (SLCRS) Vent. This system is sampled periodically for determination of radioactive material and is monitored continuously by other channels of the Digital Radiation Monitoring System (DRMS). Each Unit 1 and Unit 2 filter bank consists of roughing filters, charcoal filters,and pleated glass fiber type HEPA filters. The roughing filters remove large particulates to prevent excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the HEPA filters remove particulates and charcoal fines. Release points for Unit 1 and Unit 2 of the Beaver Valley Power Station are shown in Figure 4-7. Some of these release points discharge small amounts of radioisotopes consisting of noble gases, particulates and radiciodines. See Table 4-3 for Radioactive Gaseous Waste Sampling and Analysis Program. I I I I I I
-l 4-14 Section 4. MONITORING EFFLUENTS =l I
M M M M M M . M M M .M TABLE 4-3 Radioactive Gaseous Waste Sampling and Analysis Program y k GASEOUS SAMPUNG RELEASE TYPE FREQUENCY
^ ' ^ I FREQUENCY ANALYSIS ( Ci/cc) h
- o Principal Gamma *
- 1. Waste Gas P P Emitterso 1 x 104 n o
Storage Tank Each Tank Grab Sample Each Tank H-3 1 x 10 s h. m o S P Principal Gamma o W
- 2. Containment P Emitterse
*' " y Purge Each Purgeb Grab Each Purgeb h 3 Sample H-3 1 x 10 s g g
- 3. Ventilation Principal Gamma 1 x 10 4 h Systemsh Mb.c.* Grab Sample Mb Emitters 9 e
. g
- a. Process Vent H-3 1 x toe p yg
- b. Containment Wd 1-131 1 x 10-12 j [5 Vents Continuous' = -r Charcoal Sample 1-133 1 x 10-80 a @g
- c. Aux. Bldg.
wa Principal Gamma $ mI Vents Continuoust Emitterse (1-131, 1 x 10-18 $ E
- d. Cond. Polish.
Bldg. Vent Particulate Sample y Others) [ 1 [99 33
- e. Decon. Bldg.
3s Continuous' Composite Particulate Gross alpha 1 x 10-88 7 $* Vent q 3,,p,, {
- f. Waste Gas Vault Vent n E y u
8 Continuous' Composite Particulate Sr-89, Sr-90 1 x 10-11 o
-" Sample t
Continuousf Noble Gas Monitor x 10 s d Ga a . O l y W - At least once per 7 days j o M - At least once per 31 days ! Q O - At least once per 92 days {E P - Completed prior to each release d
=
?. _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ - - _ - _ - - - _ - _ . . - _ _ _ - - _- _ - - -- - -~
Duqu:sna Light Company 9 LJ ' 1994 Annu 1 Rcdi:: logic 1 Environm:nt:1 R: port , TABLE 4-3 NOTATION
- a. The Lower Limit of Detection (LLD).
- b. When reactor coolant system activity exceeds the limits stated in the BVPS Technical Specification, analyses shall be performed once every 24 hours during startup, shutdown and 25% load changes and 72 hours after achieving the maximum steady state power operation unless continuous monitoring is provided,
- c. Tritium grab samples shall be taken at least once per 24 hours (from the appropriate ventilation release path) when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler).
Sampling and analyses shall also be performed at least once per 24 hours, during startup, shutdown and 25% load changes and 72 hours after achieving the maximum steady state power operation when RCS activity exceeds the limits stated in the Technical Specification unless continuous monitoring is provided. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10.
- e. Tritium grab samples shall be taken at least once per 7 days from the g.
ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the g spent fuel pool.
- f. The average ratio of the sample flow rate to the sampled stream ilow rate shall
~~
be known for the time period covered by each dose or dose rate calculation made in accordance with the BVPS Technical Specification.
- g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134 Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Semi-Annual Effluent Release Report.
- h. Only when release path is in use.
I
~
4-16 section A MONITORING EFFLUENTS ""
Duqu:sna Light Ccmpany 1994 Annurl Redi::logierl Environm:nt:1 R: port
- 3. Results I' Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 3/4.11.2 of the Technical Specifications and Section 2 of the Offsite Dose Calculation Manual. No limits I were exceeded. These values have been reported in the Beaver Valley Power Station Semi-Annual Radioactive Effluent Release Reports for 1994.
C. Solid Waste Disposal During Beaver Valley Power Station normal operations and periodic maintenance, small quantities of solid radioactive waste materials were generated such as contaminated rags, paper, plastics, filters, spent ion-exchange resins, and I miscellaneous tools and equipment. Tnese were disposed of as solid rsdioactive waste. The services of offsite vendors were used to segregate, incinerate, and super-compact the waste. Until June 30, 1994, the waste was shipped for disposal at a commercial radioactive material burial site licensed by the Nuclear Regulatory Commission (NRC) or a state under agreement with the NRC. No radioactive waste material is buried at the Beaver Valley Power Station site. The waste will be stored onsite until the Appalachian States Compact Disposal Facility is available (the year 2000 at the earliest). All containers used for packaging, transport, and disposal of radioactive materials met the requirements of the United States Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Shipments offsite were made in accordance with DOT and NRC regulations. Figure 4-8 depicts solid waste handling at the site. At Beaver Valley Power Station approximately 3,183 cubic feet of radioactive solid I waste was buried offsite in 1994. Both units set record low volumes for an I operational year. The eighteen (18) shipments contained a total activity of 228 curies. j industrial solid wastes were collected in portable bins, and removed to an approved offsite burial ground. No burning or burial of wastes was conducted at the Beaver Valley Power Station site. I l I Section 4. MONITORING EFFLUENTS 4-17
l Duquesne Light Company 5 1994 Annuel Rediological Environmental Report U Figure 4-8. Solid Waste Disposal Diagram I watitt1ACT!ve m' un WASTE 01sPosAL t I i Misc. Radioactive Coc:pactor and
' )
solid Wastes Drumming Station ,
,g l
'OO OL la C'f y, nadioactive Waste - Sludge Solidify- ,
o Simeosal Eva*,orater ine Station - ; jg
,1 Spect Radioactive - -
Special Shipping I sesin Casks & Containers i'
;1 $ g
$[
&3 00' -nn'0"O1 $S E
FIGURE 4 SOLID WASTE DISPOSAL DIAGRAM g 5 , I I. I' I I l I a 4-18 Section 4. MONITORtNG EFFLUENTS
l Duquesna Light Comp:ny I E 1994 Annuti R:diological Environmsntal Report I Section 5. ENVIRONMENTAL MONITORING PROGRAM 1 l l I A. Environmental Radioactivity Monitoring Program l l l 'm 1. Program Description l The program consists of monitoring water, air, soil, river bottoms, vegetation and foodcrops, cows mitk ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table 5-1. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) j are included in parts 5-B through 5-1 of this report. ; i 5 Air Monitoring l i 5-C - Sediments and Soils Monitoring ; 5-D - Vegetation and Foodcrops l l 5-E - Cows Milk j 5-F - Environmental Radiation Monitoring 5-G - Fish 5-H - Surface, Drinking, Well Waters and Precipitation 5 Estimates of Radiation Dose to Man l l I ' l I I I I Section 5. ENVIRONMENTAL MONITORING PRoGRAu 5-1
Y M to TABLE 5-1 3 6 3 RADIOLOGICAL ENVIRONMENTAL MOlelTORING PROGRAM
-4
'in as E Type of Sample
- Sa le sector Miles Sample Point Description Sample Frequency ,
Anatysis(b) 3 Points jR O 2 1 Air Particulate 13 11 18 Meyer's Farm Continuous Sampimg Weekly Composite (d) Gross Beta. (C) l-131 C and Radiceodme 30 4 06 Stuptungport, PA (S S ) with sample Monthly Composite (d) Gamma -scan 2 48 1 3 24 Industry, PA collection at least Quarterly Composite (d) St 89.90 [ N ****'y E r 32 15 08 Midland. PA (S S ) d dela) 10 tt 5 Weerton WV (a) 5 y 7 51 5 80 Aliquippa. PA (S S ) *L 4 47 14 48 East Uverpool. OH p Q 27 7 82 Brunton's Farm < > 3 28 1 87 Sherman's Farm [ y O 298 3 81 Beaver County Hospital 3 C i rg 3 fu
-O 2 Direct Radiation 30 4 06 Shippmgport. PA (S S ) Continuous (TLD) Quarterty&) Gamma Dose .
h 13 11 18 Meyer's Farm Annuatty(k) ED 48 3 25 Industry, PA (Church) h C ( 32 48(a) 15 10 08 18 5 Midland, PA (S S ) Weirton. WV (a) { a g@ 3-
-3 20 Raccoon Twp. PA @
45 1 8 Kennedy's Crnrs. h f* [ 51 5 80 Aliquippa. PA (S S ) a 12 40 47 14 48 East Liverpool, OH West Ovr, School y ]d 70 80 1 9 30 84 Raccoon Park g 3
$. og 81 9 38 Southside School y3 82 9 7i Hanover Muntcipal Bldg 3V 83 14 to 91 43 28 Mill Creek Rd Hookstown 3$
GM 84 11 85 Hancock Co Children Home d E1 85 12 58 Rts 8 & 30 Intersection _ 88 13 45 E Leverpool Cronall House m 92 12 30 Georgetown Rd m 87 14 70 Calcutta Road
]
88 89 15 I5 31 47 Midland Heights Oheovil!e a 80 18 52 Fairview School 10 4 08 Shippingport Boro. PA 45 5 22 Mt. Pleasant Church 60 13 37 Haney's Farm 33 18 13 Sunsel Hsits. Midland IM M M M M M M M M M M M EE
E E -
,E E E E E TABLE 5-1 RADtOLOOtCAL ENVIRONMENTAL MONITORlNG PROGRAM DLC Type of Sample Sample Sector Miles Sample Point DescripHon **
Sample Frequency , , Analysle(b) 2 Direct Radiation 95 to 24 McCleary Rd, Hottie Will6ams Contmuous (TLD) Quarterty(k) Gamma-Dose (continued) 28 8 87 Sherman's Farm Annualty@) 79 2 58 enghton Twp School 72 3 32 Logan School 298 3 91 Beaver County Hospital 73 74 4 4 22 80 Potter Twp School Comm. Coe Center Twp y to 75 5 43 Holt Road A 76 8 38 Raccoon Twp School > 3 77 8 50 Green Garden Rd (Wayne's) 3 53 7 1i frons c 18 7 23 Raccoon Mun Bldg Eg 27 7 62 Brunton's Farm g C 79 8 44 Rt tg & Rt 15l gu E 15 14 33 Georgetown Q. m 46 1 3 21 Industry, PA O~ to 91 2 37 Pine Grove Rd and Doyle Rd O 94 8 24 McCleary Rd, Wilson O. (D 3 Surface Water 491(a) 4 50 Arco Polymers Weekly, intermittent Weekly Sample from l-831 gO 21 14 13 Downstream (M4diand) J&L Composite SamplesU) Arco onty 20 3 32 Station Discharge BVPS Collected Wwkly m en 2A 13 02 Downstream BVPS Outfalf Weekty Grab Samples Mm mWe W Gras % 3 O
.O y Sam (d) Gross @a
$ 5 14 40 East Uverpool (raw water) Only Gamma scan O 3 3 Quarterly Composite Co-60. H-3 3E g Dally Grab Sample (D k m Only - Collected 3 h WeektyG) E h 4 Groundwater 13 18 18 Meyer's Farm Quarterty QuarteMy Gamma-scan, Gross { m 14 15 il 15 26 33 Hookstcwn, PA Georgetown, PA Beta, Gross Alpha, H-3 y 0 % 11 3 08 Shippingport Boro 3 k 5 Drinking 4 14 13 Midland. PA (Midland Water Intermittent (e) Sample Weekly Composite of Gamma scan,1131 C Treatment Plant) Collected Weekly Daily Sample (d) O 5 Mntti Composite (d) Gross Alpha, a 14 45 East uverpool, OH (East Gross Bata O tsverpool Water Treatment Quart Composite (d) H-3, Co-60. Sr-89, 90 Plant) o Weekly Grab Sample d 8 Shoretme 2A 13 02 Downstream BVPS Outfall Somsannual Semeannual Gamma-scan. Sediment Gross Beta Q 3 02 Vicinity SAPS Discharge Gross Alpha s 13 > 49 3 32 Upstream Side of Uramum isotopic Montgomery Dam (a) gr.gg, go 50 13 82 Upstream side of g New Cumbertand Dam Cd
to TABLE S-1 8 g RADIOLOGICAL ENVIRONMENTAL MONITORING PROGR AM Sa rn DLC g Type of Sample Sample Sector Miles Sample Point Description Sample Frequency , , Analysis (b) a Points O z 7 Mith 25 to 21 Searight's Dairy Weekty(f) Weekly sample from 1-131 C Seanghrs only z Biweekly (9) when Beweekty (grartng) Gamma-scan y
- ammals are on Monthly (mdoors) Sr 89, 90 8- pasture, monthly at 1-131. Cs-137 96(a) 10 10 3 Wmd shesmer other times y z 27 7 82 Brunton's Dairy (h) to 4 29 3 83 f* col's Dairy (h) " Y Monthly Gamma-scan St-99. A h
90, I 131, Cs-137 >3 y
- BVPS Technical Specification Table 312-1 requtres three (3) daines to be selected on basis of highest potential thyroid dose us6ng milch census data See Section 5 E for 3 specific locations sampled EO h" 8 Fesh 2A i3 02 Vicinity of BVPS #1 Semiannual Composite of edible Gamma-scan y C y Station Discharge parts by species (l) on edible mj y Upstream Stoe of portions O- (D E 49(8) 3 47 Montgomery Dam 9 Food Crops Annual at harvest if Composete of each Gamma-scan $gG O_
(Shepp ) 10 4 08 (Three locations withm available sample species 9-130 on green F[ (Georg ) 15 14 33 5 miles Selected by leafy vegetables o> in (Indus ) 46 3 25 Company) m 48(a) to 16 5 Weirton. WV 3 O 10 Feedstuff and 25 10 21 Searight's Da6ry Farm Monthly Monthly Gamma-scan WO Summer Forage Quarterly Quarterly Composite Sr 90 Og u t1 Soit 13 30 11 4 18 08 Meyer's Farm Shippengport, PA Every 3 years (1994 1997, etc ) 12 Core Samples 3* Deep (3" Dia Gamma-scan Sr 90 3$ 8 X 48 3 26 Industry, PA at each location Gross Beta d 32 15 08 (North of Site) Mediand (approm 10' Gross Alpha 1 ag(a) to 14 5 Weerton, WV radius) Uramum Isotopic m 51 5 80 Aliquippa, PA (D E Liverpool, OH 47 14 48 Brunton's Dairy
]
27 7 82 a 22 5 03 South of BVPS Site 29A 3 83 Nicot's Daery 12 Proctpitation 30 4 08 Shippengport, PA Weekly grab samples Monthly Compos 6te Grossp 47 14 48 East Liverpoca, OH when available of grab samples r-scan 48 10 16 5 Weirton. WV Quarterly Composete H-3 Sr-89. St-90 SE ' -
- EE
Duqu=n3 Light Comprny l 1994 Annusi Radiol:gicci Environm:ntcl R:; port i TABLE 5-1 i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) Notes: I (a) Control sample station: These are locations which are presumed to be outside the influence of plant effluents. (b) Typical LLD's for gamma spectrometry are shown in Table 5-4. (c) Particulate samples are not counted for 2: 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is > 10 times the yearly mean of control samples. (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location. (e) Composite samples are collected at intervals not exceeding 2 hours. Weekly milk sample from Searight's Dairy is analyzed for 1-131 only. I (f) (g) Milk samples are collected bi-weekly when animals are in pasture and monthly at other times. [ Assume April- October for grazing season (pasture).] (h) The milk samples from Brunton's and Nicol's are collected once per month. (i). The fish samples will contain whatever species are available. If the available sample size permits, then the sample will be separated according to species I, , and compositing will provide one sample of each species. If the available size is too small to make separation by species practical, then edible parts of all fish in the sample will be mixed to give one sample. (j) Composite samples are collected at intervals not exceeding 2 hours at ! locations 49.1 and 2.1. Weekly grab samples are obtained at locations 49 and 1 2A. A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5. l I (k) Two (2) TLDs are collected quarterly and annually from each monitormg location. Additional Notes: Sample points correspond to site numbers shown on maps. All 1-131 analyses are performed within 40 hours of sample collection if l possible. All air samples are decayed for 72 hours before analyzing for Gross Beta. I Section 5. ENVIRONMENTAL MONITORING PRoGRAu 5-5
i Duqu:sna Light Comp:ny 1994 Annu 1 R diologicci Envir nm:ntal R: port h; U l
- 2. Summary of Results All results of this monitoring program are summarized in Table 5-2. This table is prepared in the format specified by NRC Regulatory Guide 4.8 and in accordance with Beaver Valley Power Station Operating License, (Appendix A, Technical Specifications). Summaries of results of analysis of each media are discussed in Sections 5-8 through 5-H and an assessment of radiation doses are found in Section 5-l. Table 5-3 summarizes Beaver Valley Power Station ,
preoperational ranges for the various sampling media during the years 1974 and 1975. Comparisons of preoperational data with operational data indicate the ranges of values are generally in good agreement for both periods of time. , Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, medical procedures, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the lower limit of detection (LLD). The conclusion from all program data is that the operation of the Beaver Valley Power Station has resulted in insignificant changes to the environment.
- 3. Quality Control Program The Quality Control Program implemented by Duquesne Light Company to >
assure reliable performance by the DLC contractor and the supporting QC data are presented and discussed in Section 3 of this report. The lower limits of detection for various analysis for each media monitored by this program by the DLC Contractor Laboratory are provided in Table 5-2 and in Table 5-4. I I I I s, S-6 Section 5. ENVIRONMENTAL WoNIToRiNG PROGRAM C
o ra rm ro F7 F7 JR F7 F7 F] F7 m F1 . n E w-ENVIRONMENTAL RADIOLOGICAL MONIIDRING PROGRAM
SUMMARY
-4 -4 Name of Facility lleaver Valley Power Seash Unit I and 2 Docket No. 50-334/50-412 h- ke locauon of Facetty Beaver. Pennevivanam Reporting fvtled Annual 1994 *
(County. State) Y Y' i t' ro M i i Ar ; l~ - . Lamil E Medium of Pathway TotaINumber e and of AE t,wtarator f-sans t-saaa wuh laans e A,.n. " Nuniber of i ' Sam led ofAnalyste t Control Imcauona Nontouune y Detection " Mean 10 Name "Mean (Q "Mean (0 Reported (Unit of casurement) Performed (1.1.D) " Range Destance and Directiona " Range Measuremente*" g
" Range Wetrion. WV No. 48 e y
?. to Air Paruculate *L ^
Crose (5301 2.5 17(530/530) 30. Shippingport. PA and Radiotodine Beta (4.0-32) 0.8 mi tJwE 16(53/53) 17153/53) 0 g > (7.0 31) (4.0 28) g 3 gxgo 3pCl/Cu.M.) St-89 (40) 5 11D kO k3 C Sr-90 (40) 0.2 11D -- -- -- - I-131(530) 40 11D -- -- -- - k E" oOm as Gamma (1201 3 3 gC e su o Be 7 40 139(120/120) 154112/123 131112/12) 173 203)
- 32. Mkiland. PA 0.S int N W (95-198) (73-179)
O E E
$3 3 O 3 S. O h K-40 20 14115/120) 28. Sherman's Dairy 33(I/12) 19f2/123 0 3 (6.9 33) 8.7 ml N g ff (15-23) -
g su m Others Table V.A. 11D -- -- mx k R s _ O .g b
- m V z O j y 3 I r-1 0 '
Z 2 O Nominal lower Limit of Detection (LLD) o" *
- nican and range based upon detectable measuremente only. F'ractinn of detectable meneurements at spedned locatsons to enderated in parenthence (fl O "* Notercuttne reported measurementa are defined in Regulatory Culde 4.8 (December 19751 and the Beaver Valley I%mer Station Sg'edAcettone .
3 C Y w
Y ce ENVIRONMENTAL RADIOLOGICAL MONTTDRING PROGRAM
SUMMARY
s -4 m Name of Facs! sty Deaver Vallev Ibwer Station Unit I arx12 Docket No. 50 334/50 412 tu m -- z Incation of Factitty Beaver. Pennsvlyania Reporting Period Annual 1994 G { o (County. Statel (p N z C m Analyste and lower Limit Numtwr of 6 Medium of Pathway Total Number of All Indicator Incationa location with Illghest Annual Mean Control tmationa Nonroutine K Sampled ofAnalysta Detection " Mean (Q Name "Mean (Q "Mean (O Reporled g (Unit of Measurement) Performed (LLD) "Ra nge Destance and Directione" Range "Ra nge Measu rement s*" - O Wefrton WV No. 48 S z e
$ External Hadiation Gamma 0.05 0.15(175/175) 84. Itancock County 0.19(4/4) 0.16(4/4) 0 y m (mR/ day) (175 quarterly) (O. I I -0.201 Chikiren's llome (O. I7 0.20) (O. I 4 -0.. I 81 s g 8.5 ml SW g
=o Gamma 0.05 0.13(43/43) 84. flantuck County 0.16(I/11 0.14(1/I) 0 25 g
(43 annual) (0.10-0.161 Chikiren'a llome 8.5 ms SW Ec g$ o58 Feed and Fnrage t-131 (12) 0.01 11D 5I (pCl/g) One Sample m6 Incation r (dry weight)
@~
St-90 (4) 0.003 0.096(4/41 (0.02-0.151 O <h gg a v Camma (12) 3* eJ 3 Be-7 0.3 1.9(7/12) -- - - O g (0.26-5.2) - 2) K-40 0.5 20(12/12) (5.4-51) 0 $o 3 Ca-137 0.01 0.076(1/12) -- -- -- 0 Th 228 0.08 0.23(2/12) -- -- -- 0 (0.16-0.30) Others Table V.A. IJD -- -- Nominal Imwer Limit of Detetuon (LLDB
' Mean and range based upon detectable measurements only. Fraction of detectable measueements at specifled larathms is Indtrated in parentheses 10
"* Nonroutine reported measuremente are defined in Regulatory Culde 4 S (December 1975) and the Ileaver Valley lbwer Station Specifications .
M ~ M M M M M M M M M EE
M M M M ,M M M M M M ENVIRONMEPfrAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Factitty Beaver Vallev lbwer Station Unit I and 2 Docket No. 50 334/50-412 g Imration of Facility Beaver. Pennevivanam Reporting IVrlod Annual 1994 (County Statej [- Y to A.O I.~m . Limit Number of Maltum of Pathway TotaI.te and Number of All Indacator Imcauona lacataan with :"" _ : A '"= Control locatione Nonmuttne Sampled of Analyets Detection " Mean 10 Name "Mean (Q (Unit of Measurement) Performed " Range "Mean (Q Reported (1.LD) Destance and Directione "Ra nge "Ra nge Mea su rement a *" Montgomery Dam No. 49 $ e Flah Gamma (9) A (pCI/g) K-40 0.05 3.3(9/9) 49. Upstream 3.6(5/5) twet weight) (2.3-4.8) Montgomery Dam Same as high location O > (2.7 4.8) 3 4.7 me NE Othern m Table V.A. IlD -- - - {Dh D C b (D
-E em 6E mo r
ma 3 O 10
$ O3 3 au
. 3$
.x 3
$ 5 E II O
z CD C u o S A C r-C O E a 0 2 8 - Nantnal tower umet of Deteetton (ual
, *
- Mean and range based upon detectable measuremente only. Fraction of detectable measurements at spedRed locatione la inderated in parenthence (Q n "* Monmutine reported sneasurements are denned in Regulatory culde 4 8 l December 1975) and the Beaver Valley Ibwer Station Spectilratione .
8 c c Y e
= -
Y a o ENv1RONMENTAL RADIOIDGICAL MONTIURING PHOGRAM
SUMMARY
s -
,, Name of Facility llenver Vallev Power Station Unit I and 2 Docket No. 50-334/50-412 lu g
Q location of Factisty Beaver. Pennavivania Reporting Period Annual 1994 *
$ (County. Statet Y 8 "
2 k Analysts and lower LJmit Number of
$ Medium of Pathway Total Number of All Indicator 1meatione inc=% with 18asheet Anan=6 Mean Control locations Non vutine '~
Sampled ofAnalyets Detection " Mean (f) Name "Mean (Q "Mean (0 Reported (Unit of Measurement) Perfermed (LLD) "Ra nge Destance and Directions " Range " Range Measurements"* - h Food and Carden 0.006 Wetrton. WV No. 48 8' 2 I 131 (4) 11D - -- -- - A 4 Crops (pCl/gl (wet weight)
@ Camma (4) 3 5 5 O K-40 0.5 1.9(4 /4) 48. Weltton. WV 2.5(I/Il Same as O tu v (1.6 2.51 16.05 mi SSW -
high location -O E c Others Table V.A. IJD C E_.m n D
> 0 EA c$
O dC as c 7 m" 3
- 5. O O
O3 a u b a__
'O m
D O 3 Nominal tourer LJmit of Detection (11D)
** Mean and range based upon detettable measurements only. Fractkm of detectable measuremente at spectfled locatione Is indscated in parenthence 10
* ** Nonroutine reported menausementa are denned in Reguitatory Guide 4 8 (MARCil 1975) and the fleaver Vallev 5%ver Statkm Spectflcathme .
3 m m m m M M M m - M EE
M M .M - M - M ENVIRONMENTAL RADIORDGICAL MONITORING PROGRAM
SUMMARY
Name of Factitty Beaver Valley Power Stash Unit I and 2 Dechet h. 50-334/50-412 [ c' location of Factitty Beaver. Pennavirania Reporting Period Annual 1994 m-(County. Statel g to Analysk and lower I.amit Number of ledium of Pathway Total Number of All Indicator incathna locathn with Haghest Annual Mean Control locationa Nonrouune Sampled of Analyste Detection " Mean 10 Name **Mean 10 "Mean (O Reported (Unit of Measurement) Performed (LLDI "Ra nge Destance and Derectione " Range " Range Measuremente"* Brunton Dairy N. 27 . u) Milk l-131 (186) 0.2 11D -- -- - . (pct /II Sr-89 l132) 2 IJD -- -- -- - [ a Sr-90 (1321 1 2.78132/1321 102. Feny Dairy (al 4.6(15/15) 1.9119 /191 0 C (1.2 9.21 (2.5-9.21 (1.2-4.01 S.- O Gamma (132) K-40 100 13911132/1321 102. Ferry Dairy ini 1516(15/15) 1395(19/191 0 a. O_ " (1110-1640) (1290 1640) (1250 16301 o Others Table V.A. 11D D. ge
.. .. . . n _.
mo ar m~
.O 8 aau
=
m a$ 3 I s 8
- 9 C m T3 E O s
- r-C O
2 1 8
$ (al Goat Defry O
meninal Lower Limit of Na. ILWI o" *
- Mean and range based upon detectable =:;a........to only. Fraction of detectable saeasurementa et spectfled locanone la andtrated in parenthence Ifl O "* 19enmuttne reported sneasureunente are defined in Regulatory Cukte 4.8 l December 19751 and the Beaver Valley Iweer Station Spectilmtlone .
C Y 2
.Y.a PJ ENVIRONMF.NTAL RAfilOLOCICAL MONITORING PROGRAM StJMMARY h Name of Farthty Beawr Vallev Ibwer Rearba tJntt I and 2 Darket No. 50-334150-412 l s -
l.mration of Farttity nenwer Pennawivaan= Reporting Pertnd Manual 1994 Al (County. Statel E m l (3 Medium of Pathway Analysts and Total Number Imwer Limit of All Indicator imcauona t-- wah II aheet Annual Mena Number of CD y l Contral a ar=Hons Nanroutine O Sampled of Analyses Detection " Mean (0 Name "Mean (Q m
"Mean (O Reported
{ rn (Unit of Measuremer el Performed (1,LD) " Range Distance and Directions "R onge "Ra nge Measurements *" r 2 Monagemery Dam No. 49
$ Sediment Crose (61 0.3 12(6 / 61 49. Upstream 1 6(2 /21 Same as litgh 0 r- lpCI/g! Alpha (7. I -l 71 Montgomery Dam (l4-I7) Imtstton l C (dry weight) 4.7 me NE a
O t.0 2 O Crose (61 0.1 3886/ 61 49. Upstream 42[2/2) y Beta (33-47) Montgomery Dam (36-47) Same as litgh location 0 y Z 4.7 mt NE [ 3 O Sr-89 (6) 0.2 IJD -- - c i - su _g 8 Sr 90 (61 0 04 0.15(1/6) 50. Upstream 0.1 5(1 / 21 11D 0 % O N. Cumberland Dam
$C g 8.2 ml W g Gamma (Si g- @
Be.7 0.2 2.2t3/61 2A. BVPS Descharge -3 (0 97-3.41 0.2 mt. W 2.712 / 21 (2.I-3.48 12D 0 Om K.40 0.5 12(6/6) 2A. BVPS Deerharge 13(2/2) 13(2/2) 0 "0 (11-15) 0.2 mL W (13-14) (31 151 -3 m~ Co 58 0.2 0.11(2/6) 2A. BVPS Deerharge 0.11(2/2) 11D 3 O (0.096-0.12) 0.2 me. W (0.096-0.121 0 io 33 3V Co-60 0.2 0.5 0(2 / 61 2A, DVPS Discharge 0.50(2/2) IJD 0 l0.39-0.62) 0.2 mt. W (0.39-0.62) g fu ~3 g Co-137 0.02 3 0.25(8/6) 50. Upstream 0.3 3(2 / 21 0.24t(2/2) 0 10.16-0.50) 4 Cumbettand Dam 10.16-0.50) (0.2I 0.26) g-8.2 mi W 0 (D Ra-226 0.1 2.2(6 / 61 49. Upstream 2.8(2 / 21 Same as litch 0 V (1.5-3.51 Montgomery Dam (2.0-3.5) Imratton O 4.7 mi NE N Th-228 0.02 1.2(6 / 61 2A. BVPS Descharge 1.3(2/2) 1.3(2 / 23 0 (0.91 1.61 0.2 ml. W (1.3-1.41 (0 9 l-1.61 Others Table V.A. IJD -- - - Nominal lower LJmet of Detection EllD)
'* Mean and range based upon detectable measurements only. Fracuen of detectable measuremente at spectfled locatsans to indicated in parentheses til Nonroutine reported smeasuremente are defined in Regulatasy Gusde 4.8 (December 1975) and the Beaver vaBey Ibwer Stasian SpersAcations .
g m m m M M M, M M M - 55
Duquesne Light Company 1994 Annual Radiologicci Environmantal Report Table 5 2 i* f I 3) j ?.E s 5 E$ 8.3 o o o o o o o . E. 3 E*2$ . $j w I. e f L ab c5h- =- - = n}E
** ~
2 ~
> Aj n $a %b=: n D: C D: E: =: g: : -
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,si et ,s t: i b D a
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Y b E2fYlBQNMENTAL RADIOLOctCAL MONITORING PROGRAM SUMMAEI 3 -4 g Name of Facility Deaver Vallev Power Slauon Unit I and 2 Docket No. 50-334/50 412 ai g m location of Fartitty Beaver. Pennsvivania Reporttryg IVriod Annual 1994 G h (County. Statel tr 8 " 2 k As !-eeand fewer Limit Number of 3 Medium of Pathway Totaf Number of AILindicator Locations locauon with Hwheat Annanal Mean Control Impations Nonmuttne
> Sampled of Analysto Detection ** Mean 10 Name **Mean 10 **Mean 10 Reported r
(Unit of Measurement) Performed (LLD) **Ra nge Distance and Directions ** Range **R a nge Measurements"* -* C to O C 2 h 4 Drinking 1 131 il45) 0.5 0.49(73/I45) 04. Midland. PA 0.56(31/531 - 0 Weter 3>
$ 1pcs/il (O.I8-1.2l I.3 mt WNW (0.2 3-I.21 3 5
o Grose (33) 0.6 UD - - Alpha
.m
-O n's C x
b Grose (33) 4.4133/33) 04. Midland. PA 4.5(12/12) y Beta 1 (2.8-6.6) 1.3 mi WNW 0 $0 C (3.3-6.6l g$
-a Gamma (145) OG Others Table V.A. g I-IID -- -- --
m6 ar Sr.89 (Ill 1.5 11D --
@{
Sr.90 ill) <O 0.5 11D -- -- -- - gg Co-60 (II) (al I 11D -- -- -- -
"E Ba 113 (Ill 100 11D -- -- -- -
3 8 2 m V O 3 la) Co.60 analyzed by higli eenaltivity method Ncminal Lcwer Lamat of Detection tuDl
*
- Mean and range based upon detectable measurements only. Fraction of detectable meneurements at spectfled locations to Indicated in parenthemes (fl
**
- Noncouttne reported measuremente are defined in Regulatory Culde 4.8 (December 19751 and the Denver Valley Ibwer Station Speditcatkms .
I R O D R .R R R R I ,1 I l Il R R fl f~} CE E~W EtnanONh8FVTAL HADIOLOGICAL h00NTIORING PilOrmm so-__ny Name of Factiety Beaver Vatew Poem e-"-- Unna i " 2 Docket Na 50 334/50 412 --t en J location of Facttty Beaver. Pennartranen Reporting Period Annaani 1994 ICounty, alatel [- 4' to Analyses end lower IF.~ Matsum of Pathway Total Nuenber of Museber of Sean a lasticalar I.mentanna lmcatkan unth Highest AnnenL Mean Camisel Istatanna Moneoutine efAnalysee Detection " Mean ill Name "Mean Ifl (Uret of ressent) Perfornned (LLDI "Renee "Mean Ifl Reported Destance end Derects no "Renee "Ranae Measur:x..te'" Cecreetown. PA Mo.15 - Croundwater f Croce (ISI 2 IJD -- -- -- Ipcs/II Alphe a Groes l168 I S.8(14/161 14. Hookstown. PA 10(4/4) Beta 3. l(4/4) O S 12.2 ISI 2.6 ene SW 18.1-1 51 12.5-4.31 gg. ca n.1861 K 40 100 68(1/16) 15. G ,io. . PA 3.3 sul N W 68(1/4) Some as Hegli tocation o h$ Othere o og TetneV.A. IJD -- -- -- - 5 C" Ip e H-3 (161 90 160(I/161 I I. Sh - e ;. PA 160(I/41 IJD 0 0.8 me Id!: -- m 3 g 3 S. og 9 g o3-av 3 %. 5 z a*
-+
O E 2 m C (D m V 3 O r-3 C O iE O . E l o
- reainenes Imwer i h-= or me. ILwt E ** teeen and rence heard upon detectable -- ;.a..to only. Frertsen of detectalde --;- ;_..te et operened seemisens se inderated en parentheses ill g ++ + Nonneuesne repeeted _ __ _ _ -.. are denned in nesuistory cuade 4 e toeccomener eersi and tiie tience, vessey sweer steinen sperterettene .
S C _Y. t89
Y a ENVIRONMENTAL RADIOLOGICAL MONITDRING PROGRAM
SUMMARY
-4 Name of Factitty Beaver Vallev 1%wer Staten IJnat I an<t 2 Docket No. 50-334150-412 "o..
E location of Facility Beaver. IVnnsv!vants Reportmg IVrtad Anrmal 19M
$ ICounty. Statel Y
.n to .
O 2 k Analysis and Lower Limit Number of 3 Medium of 14thway Total Number of All Indtcalor Imcations Imcathn with liighest Annual Mean Cantal locations Nonroutine y Sampled of Analysen Detection " Mean 10 Name "Mean 10 "Mean (0 Reported (Unit i Mesourement) Performed (LLD) "Ra nge Distance and Directions " Range " Range Mesouremente"* C "o g o Wetrton. WV No.48 g 4 Water Groes (35) I 13134/35) 48. Wetrion. WV > I41II/Ill Same as high 0 hz Prectpliation Beta (5.9-45) 16.05 mi SSW (7.0 45) location 3 fpCl/II c 0
% Gamma (35)
EO Be-7 40 105(29/35) 48. Wetrton. WV 125110/1Il Same as high 0 $q N (43 3601 18.05 ml SSW (43 360) location 5' ra5 E 6' K-40 100 46( t /35) 30. Shigtngport. PA 0.6 ml wE 46(I/I2) 11D 0 o$ 6E Others Table V.A. UD -- - -- - EO l Sr-89 (12) 2 UD -- - -- m~ 3 O 1o Sr-90 (123 0.5 UD -- -- - 83 3u 11-3 (12) 100 22713/12) 30. Shtppingport PA 227(3/4) UD 0 3*
- (180-280) 0.6 ml mE (180-280) m x 3
l E x m V O 3 I l l Nominal tower Lamit of Detecuan (LLD)
** Mean and range based upon detectable measurements only. Fraction of detectable measurements et specified locatsans to andtested In parentheses (f)
"* Nonroutine reported measurementa are defined in Regulatory Guide 4 8 (December 19751 and the Beaver Valley Power Station Specificatione .
l E M - M M EE
i e n rm .. FR ra ra rl . . F- t FR .r7 r7 o. n n _m D q g l i ENVIRONMENTAL RADIOLOGICAL MONITORING PHOCRAM
SUMMARY
Name of Factitty L.u- Vallev INnuer *-"-- Unit I and 2 beket No. 50 334/50-412 '( to Location of Factitty llenver. Penneviransa Reporting Pe:1od Anniaal 1994 E ICounty. Statel G- j Y to 1 I and Lower IJmet Number of Medtussa of Pathway T Muamber of All Indicator incationq 1mcallon 1stih IW Annanal hican control I.acatanna Nonsnuttne Sampled of Analysen Detection " Mean 10 Name "Mean 10 "Mean 80 Reported (Unst of MeeeuremenQ Performed (LLD) ** Ra nge Destance and Directions **Ra nge " Range Measurement s"* Upseseem - ARCO Chemical No. 49.1 g so Surface Water I 13I 1531 0.5 0.4Ill6/531 49.1. Upstream. ARCO one sample O *= (pCI/II (0.20-0.641 Chemical location y 5.0 mi ENE a n Groes (48) 2 IID -- -- -- - 5 AIPita
-[
3 I' Groes (481 Beta 1 5.6(48/48) (2.2-14) 02A, BVPS Descharge 0.2 ma W 7.6(12/12) (3.8 141 4.5112/12) 12.2-8.31 0 $o g* c-3 Comma (28) G F-K-40 100 6713/48) 2.I. J&L Steel t il(I /12) 49(1/121 0 6' cu 6 (41-1 I Il 1.3 me WNW -- -- r Others Table V.A. 11D $b Sr-89 (16) 2 11D -- -- -- h Sr-90 (16) 0.5 11D -- -- --
"E 3
9 Co-60 (16) (al 2 11D -- -- --
$ *3
$ E D H-3 (16) 100 1500(I/16) 02A BVPS Descharge 1500(I/41 IJD 0 -
9 -- 0.2 mt W -- 2 C
- T3 7 (al Co 60 analyed by hagh sensatwety method. o y a.
r-C O
?
o LU z O i 7 Namenal lower Limit d Deterunn (tJDI R " Mean and range based ta,m detectalde enessuremente only. Fraction ad detectable meneuremente at spectned lurattems to t=Strated en parentheses If) 8 *" feonroutine reported measuremente are denned in Regulatomy Suede 4 8 Itkeember 19755 and the Beaver Valley Ibser Stattern SpeclAs*he . W c Y N
Duqu cn3 Light Comp ny 1994 Annut! R:diologicci Environm:nt:1 R: port - Table 5-3. Pre-operational Environmental Radiological Monitoring Program Summary TABLE 5-3 PRE OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 (County, State) l PRE-OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 1975)
* "" ' 'I Analysis and Total Number Lower Limit All Indicator Locations of Analysis Performed of Detection LLD Mean, (f) Range (Unit of asu ement)
Sediments Gross Alpha (0) - - pCi/g (dry) Gross Beta (33) 1 18 33/33 5 - 30 Sr-90 (0) - - U-234, 235, 238 (0) - - Gamma (33) - 13 33/33 2 - 30 K-40 1.5 13 33/33 2 - 30 Cs-137 0.1 0.4 21/33 0.1 - 0.6 ZrNb-95 0.05 0.8 12/33 0.2 - 3.2 Ce-144 0.3 0.5 3/33 0.4 - 0.7 Ru-106(b) 0.3 1.5 3/33 1.3 - 1.8 Others - < LLD Foodstuff Gamma (8) - - pCi/g (dry) K-40 1 33 8/8 10 - 53 Cs-137 0.1 0.2 1/8 - ZrNb-95 0.05 0.2 1/8 - Ru-106(b) 0.3 0.8 1/8 - Others -
< LLD Feedstuff Gross Beta (80) 0.05 19 80/80 8 - 50 pCi/g (dry) Sr-89 (81) 0.025 0.2 33/81 0.04 - 0.93 Sr-90 (81) 0.005 0.4 78/81 0.02 - 0.81 Gamma (81) - -
K-40 1 19 75/81 5 - 46 Cs-137 0.1 0.5 6/81 0.2 - 1.6 Ce-144 0.3 1.5 5/81 0.9-2.6 ZrNb-95 0.05 0.8 13/81 0.2 - 1.8 Ru-106(b) 0.3 1.4 12/81 0.6-23 Others - < LLD Soil Gross Alpha (0) - - pCi/g (dry) Gross Beta (64) 1 22 64/64 14 - 32 (Template Samples) Sr-89 (64) 0.25 0.4 1/64 - Sr-90 (64) 0.05 0.3 48/64 0.1 - 1.3 U-234, 235, 238 (0) - - Gamma (64) - - K-40 1.5 13 63/64 5 - 24 Cs-137 0.1 1.5 56/64 0.1 - 6.8 Ce-144 0.3 1.1 7/64 0.2 - 3 ZrNb-95 0.05 0.3 13/64 0.1 - 2 Ru-106(b) 0.3 1.1 3/64 0.5-2 Others < LLD g 5 I 5-18 Section 5. ENVIRONMENTAL MONITORING PROGRAM "J l l
f Duquesnm Light Comp ny 1994 Annu:1 Radi: logical Environm:ntal Report TABLE 5-3 I PRE OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 (County, State) PRE-OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 1975)
" * * ' * **I Analysis and Total Number Lower Limit All Indicator Locations f na s e orme f etectkn M Mean, m Range (Unit of asu ement)
Soil Gross Alpha (0) - - pCi/g (dry) Gross Beta (8) 1 21 8/8 16 - 28 I (Core Samples) Sr-89 Sr-90 Gamma (8) (8) (8) 0.25 0.05 0.2
< LLD 5/8 0.08 - 0.5 K-40 1.5 13 8/8 7 - 20 Cs-137 0.1 1.2 7/8 0.22.4 Co-60 0.1 0.2 1/8 -
Others -
< LLD Surface Water Gross Alpha (40) 0.3 0.75 5/40 0.6 - 1.1 pCill Gross Beta (120) 0.6 4.4 120/120 2.5 - 11,4 Gamma (1) 10 - 60 < LLD Tritium (121) 100 300 120/121 180 - 800 Sr-89 (0) - -
Sr-90 (0) - - C-14 (0) - - Drinking Water 1-131 (0) - - pCi/l Gross Alpha (50) 0.3 0.6 4/50 0.4 - 0.8 Gross Beta (208) 0.6 3.8 208/208 2.36.4 Gamma (0) - - Tritium (211) 100 310 211/211 130 - 1000 C-14 (0) - - Sr-89 (0) - - Sr-90 (0) - - Ground Water Gross Alpha (19) 0.3 < LLD pCi/l Gross Beta (76) 0.6 2.9 73/75(a) 1.3-8.0 Tritium (81) 100 440 77/81 80 - 800 Gamma (1) 10 - 60 < LLD Air Particulates Gross Alpha (188) 0.001 0.003 35/188 0.002 0.004 and Gaseous Gross Beta (927) 0.006 0.07 927/927 0.02 - 0.32 pCi/m3 Sr-89 (0) - - Sr-90 (0) - - l-131 (816) 0.04 0.08 2/816 0.07 0.08 Gamma (197) - - I ZrNb-95 Ru-106 Ce-141 0 005 0.010 0.010 0.04 122/197 0.01 - 0.16 0.04 50/197 0.02 - 0.09 0.02 3/197 0.01 - 0.04 Ce-144 0.010 0.02 44/197 0.01 - 0.04 I Others < LLD Section 5. ENVIRONMENTAL MONITORING PROGRAu S-19 '
r3 Duqu:sn3 Light Comp:ny %, L 1994 Annu:1 Radiologic:1 Environm:ntal Report j TABLE 5 3 l PRE-OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver. Pennsvivania Reporting Level CY 1974 - 1975 (County, State) PRE-OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 - 1975)
- Medium or Pathway Analysis and Total Number Lower Limit All Indicator Locations f na sis e ormed of Detection RD Mean,(O Rany (Unit of a u ement) ,
Milk l-131 (91) 0.25 0.6 4/91 0.3 - 0.8 pCi/l Sr-89 (134) 5 7 4/134 6 - 11 Sr-90 (134) 1 5.3 132/134 1.5 - 12.8 3 Gamma (134) - - g Cs-137 10 13 19/134 11 - 16 Others < LLD External Radiation y - Monthly (599) 0.5 mR" 0.20 599/599 0.08 - 0.51 mR/ day y - Quarterly (195) 0.5 mR* 0.20 195/195 0.11 - 0.38 y - Annual (48) 0.5 mR* 0.19 48/48 0.11 - 0.30 Fish Gross Beta (17) 0.01 1.9 15/17 1.0 - 3.2 pCl/g (wet) Sr-90 (17) 0.005 0.14 17/17 0.02 - 0.50 Gamma (17) 0.5 K-40 - 2.4 17/17 1.0 - 3.7 Others - < LLD LLD in units of MR Lower end of useful integrated exposure detectability range for a passive radiation l detector (TLD). E ' (a) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium , content. Not considered typical groundwater sample). l l (b). may include Ru-106, Ru-103, Be-7. l 1 l 5-20 Section $. ENVIRONMENTAL MONITORING PROGRAM
L-Duquosna Light Comp ny
. 1994 Annurl R:diological Environm:ntti R: port Table 5-4. Typical LLDs For Gamma Spectrometry E
TABLE 5-4 TYPICAL LLDs
- FOR GAMMA SPECTROSCOPY ment Air Particulates Vegetation Fish I I 8 (PCilg wet)
(p i i r) (pCilg ry) Be-7 50 20 200 0.2 0.02 K-40 80 50 400 0.4 0.4 Cr 51 50 20 200 0.2 0.2 M n-54 5 2 20 0.02 0.02 Co-58 5 2 20 0.02 0.02 Fe 59 10 3 40 0.04 0.04 Co-60 5 2 20 0.02 0.02 Zn-65 10 5 40 0.04 0.04 Zr/Nb-95 5 3 40 0.04 0.04 [ Ru-103 Ru-106 50 5 20 3 30 200 0.03 0.2 0.03 0.2 ~ Ag-110M 10 5 50 0.05 0.05 L i-131 15 4 200 0.2 0.2 Te-132 8 4 20 0.02 0.02 1-133 8 4 20 0.02 0.02 [' ~ Cs-134 5 2 20 0.02 0.02 Cs-136 8 4 50 0.05 0.05 Cs-137 5 2 20 0.02 0.02 I Ba-La-140 10 3 200 0.2 0.02 Ce-141 10 20 100 0.1 0.1 Ce-144 40 10 200 0.2 0.2 L Ra-226 80 10 100 0.1 0.1 Th-228 10 10 20 0.02 0.02 F
- L. At time of analysis (DLC Contractor Lab).
NOTE: Lower Level of Detection is defined in Beaver Valley Power Station Technical . [ Specifications. E [ E - Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-21
I I Duqu:nne Ught Camp ny E 1994 Annurl Rcdiologic l Envirenm:ntcl R:: port C B. Air Monitoring
- 1. Characterization of Air and Meteorology l
The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is generally from the Southwest in summer and from the Northwest in the winter.
- 2. Air Sampling Program and Analytical Techniques ;
I
- a. Program The air is sampled for gaseous radiolodine and radioactive particulates at each of ten (1) offsite air sampling stations. The locations of these stations are listed in Table 5-1 and shown on a map in Figure 5-1.
Samples are collected at each of these stations by continuously drawing one cubic foot per minute of atmosphere air through a glass fiber filter and through a charcoal cartridge. The former collects airborne particulates; the latter is for radiciodine sampling. Samples are collected for analysis on a weekly basis. , The charcoal is used in the weekly analysis of airborne 1-131. The filters are analyzed each week for gross beta, then composited by station for monthly analysis by gamma spectrometry. They are further composited in
.- a quarterly sample from each station for Sr-89 and Sr-90 analysis. In order ;
to reduce interference from natural radon and thoron radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.
- b. , Procedures Gross Beta analysis is performed by placing the filter paper from the weekly air sample in a 2" x 1/4" planchet and counting it in a low ,
background, gas flow proportional counter. Gamma emitters are determined by stacking all the filter papers from each monitoring station collected during the month and scanning this composite on a high resolution germanium gamma spectrometer. Radiciodine (1-131) analysis is performed by a gamma scan of the charcoal in a weekly charcoal cartridge. The activity is referenced to the mid-collection time. 5-22 Section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1994 Annual Radiological Environmental Report Figure 5-1. Air Sampling Stations N u==e=4 emm ro w'r> rn"rc _
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I I Section 5. ENVIRONMENTAL MONITORING PROGRAu 5-23 i
I Duqu:snm Light Company 0i 1994 Annuel Radiol gieri Envircnm:ntrl Report O' Strontium-89 and Strontium-90 activities are determined in quarterly i composited air particulate filters. Stable strontium carrier is added to the l sample and it is leached in nitric acid to bring deposits into solution. The g ; mixture is then filtered. Half of the filtrate is taken for strontium analysis g; and is reduced in volume by evaporation. Strontium is precipitated as Sr(NO3 ): using fuming (90%) nitric acid. A barium scavenge is performed to remove radium and other natural nuclides. An iron (ferric hydroxide) ' scavenge is performed, followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level 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 is covered with 80 mg/cm2 aluminum absorber for low level beta counting.
- 3. Results and Conclusions I A summary of data is presented in Table 5-2.
- a. Airborne Radioactive Particulates A total of five hundred thirty (530) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years.
Figure 5-2 illustrates the average concentration of gross beta in air particulates. The weekly air particulate samples were composited to one hundred twenty (120) monthly samples which were analyzed by gamma spectrometry. Naturally occurring Be-7 was present in every sample. Naturally occurring K-40 was detected in fifteen (15) of the one hundred twenty (120) monthly samples. Results are listed in the summary Table 5-2. A total of forty (40) quarterly samples were each analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 was detected. Based on the analytical results, the operation of Beaver Valley Power Station did not contribute to any increase in air particulate radioactivity during 1994.
- b. Radioiodine A total of five hundred thirty (530) weekly charcoal filter samples were analyzed for 1-131. No detectable concentrations were found at any locations. ,
Based on analytical results, the operation of Beaver Valley Power Station did not contribute to any increase in airborne radiolodine during 1994. l I, 5-24 Section 5. ENVIRONMENTAL MONITORING PROGRAM =l
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1 Duqu:sn3 Light Company [4 r 1994 Annuri Rcdiological Environm:ntri Report " C. Monitoring of Sediments and Soils (Soll Monitoring is required every 3 years and was required in 1994)
- 1. Characterization of Stream Sediments and Soils I The stream sediments consist largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.
- 2. Sampling Program and Analytical Techniques '
- a. Program River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 5-1 and are shown in Figure 5-3.
Soil samples were collected at each of ten (10) locations during 1994. At each location,12 core samples (3" diameter by 2" deep) are gathered at prescribed points on a 10 foot radius circle. Each location is permanently marked with reference pins. Each set of samples is systematically selected by moving along the radius in such a manner as to assure representative undisturbed samples. Sampling locations are listed in Table 5-1 and are shown in Figure 5-3. Bottom sediments and soils are analyzed for gross alpha and beta activity, g strontium, and the gamma-emitting radionuclides. g
- b. Analytical Procedures Gross beta - sediments and soils are analyzed for gross beta by mounting a 1 gram portion of dried sediment in a 2" planchet. The sample is counted in a low background, gas flow proportional counter. Self absorption corrections are made on the basis of sample weight.
Gross alpha activity of sediment or soil is analyzed in the same manner as gross beta except that the counter is set up to count only alpha. Gamma analysis of sediment or soll is performed in a 300 mi piastic bottle which is counted by a gamma spectrometer. I E 5-26 Section 5. ENVIRONMENTAL MONITORING PROGRAM
I Duquesne Light Company 1994 Annual Radiological Environmental Report I Figure 5-3. Environmental Monitoring Locations - Shoreline Sediments and Soil N NM sotuut::=tus j , ; 5 I , toc.no
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Duqu:sna Light Comp ny b ' 1994 Annu 1 Rtdiologic51 Environmsntil Report LJ . Strontium 89 and 90 are determined by radiochemistry. The sample is first { dried and weighed. Stable strontium and calcium carriers are added and the sample is leached in hydrochloric acid. The sample is filtered. gl Calcium and strontium are precipitated as phosphates, collected by 3l vacuum filtration, then dissolved in nitric acid. Strontium is separated by I precipitating Sr(NOs): using nitric acid. A barium scavenge is performed to remove radium and other natural nuclides. Final purification of , strontium is accomplished by precipitating SrSO4 An iron scavenge is I performed, followed by addition of stable yttrium carrier and a minimum S-day period for Y-90 ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium, oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Sr-89 activity is determined by precipitating SrCOs from the sample after yttrium separation. This precipitate is mounted on a j nylon planchet and is covered with an 80 mg/cm8 aluminum absorber for low level beta counting.
- 3. Results and Conclusions A summary of sediment and soil analysis is presented in Table 5-2.
I
- a. Sediment A total of six (6) samples were analyzed for gross alpha and gross beta.
Results were comparable to previous years. A total of six (6) samples were analyzed for Sr-89 and Sr-90. No Sr-89 was detected. Sr-90 was detected at low level on one sample upstream of the New Cumberland Dam. A total of six (6) sample were analyzed by gamma spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was found in every sample. Be-7 was found in three samples. Small amounts of Cs-137 from previous nuclear weapons test were found in all six river sediment samples including two upstream above Montgomery Dam, which are unaffected by plant effluents. Small amounts of Co-58, Co-60 and Cs-137 were detected in the Beaver Valley Power Station discharge area and are attributable to station releases. The activity found in the station discharge area is consistent with station data of authorized radioactive discharges which were within limits permitted by the NRC license. The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River sediment. The positive results detected are attributable to authorized releases from the Beaver Valley Power Station and are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.
- b. Soil Results of soil analysis are comparable to preoperational data.
E 5-28 SecDon 5. ENVIRONMENTAL MONITORING PROGRAM E
l.I Duquisn3 Light Comprny 1994 Annu:1 Rcdiol:gic 1 Environm:nt:1 Rrport l D. Monitoring of Feederops and Foodcrops
- 1. Characterization of Vegetation and Foodcrops According to the 1993 statistical summary of the Pennsylvania Department of Agriculture, there were approximately 512 farms in Beaver County. The total value of farm crops and livestock was $15,948,000. The principal source of revenue was in dairy products which were estimated at $5,976,000. Revenues from other farm products were estimated as follows:
Field Crops $1,520,000 Fruits $255,000 I Horticulture and Mushrooms Meat and Animal Products
$3,763,000
$3,533,000 Vegetables and Potatoes $567,000 Poultry Products $94,000 I ,
The total land in Beaver County is 279.020 acres. Approximately 147,900 acres are forested land and 57,960 acres are pasture and crop land.
- 2. Sampling Program and Analytical Techniques
- a. Program Representative samples of cattle feed are collected monthly from the I nearest dairy (Searight). See Figure 5-4. Each sample is analyzed by gamma spectrometry. The monthly samples are composited into a quarterly sample which is analyzed for Sr-90.
A land use census was performed July 1994 to locate the nearest residence and nearest garden of greater than 500 square feet producing fresh leafy vegetables within a five (5) mile radius of the site. See Table 5-5 for results. Fooderops (vegetables) were collected at garden locations during the summer of 1994. Leafy vegetables, i.e., cabbage were obtained from I Shippingport, Georgetown, Industry, PA and Weirton, WV. All samples were analyzed for gamma emitters (including 1-131 by gamma spectroscopy). I I Section 5. ENVIRONMENTAL MONITORING PRoGRAu 5-29
Duquesno Light Company 1994 Annual Rcdiologicci Environmental Report h U Figure 54. Environmental Monitoring Program . Feederop and Foodcrop Locations I I s ... .l - g t t s. , N bk 8 4 % = 5 j ~4.4 I ws 1 e !! j
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l I I 5 30 section 5. ENVIRONMENTAL MONITORING PROGRAM !
Duqu;sna Light Company 1994 Annual Rrdial:gicci Envir nm;ntal R: port Table 5-5. Closest Residence and Garden in Each Sector TABLE 5-5
,- Closest Residence and Garden in Each Sector Sector Closest Residence
- Closest Garden
- 1 1.55 mi N 1.55 mi N 2 1.59 mi NNE 1.61 mi NNE 3 0.42 mi NE 2.53 mi NE 4 0.38 mi ENE 0.98 mi ENE 1 5 0.42 mi E 2.16 mi E
{ 6 7 0.87 mi ESE 1.10 mi SE 1.60 mi ESE 1.78 mi SE { 8 9 1.10 mi SSE 1.40 mi S 2.16 mi SSE 2.20 mi S q 10 0.80 mi SSW 1.55 mi SSW ~ 11 1.46 mi SW 1.67 mi SW
- r. 12 1.46 mi WSW 1.46 mi WSW L 13 2.27 mi W 2.27 mi W r 14 2.77 mi WNW 3.33 mi WNW 15 0.91 mi NW 0.92 mi NW r 16 0.91 mi NNW 1.36 mi NNW L
- Direction and Distance from Midpoint between Reactors I
1 I Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-31
Duqu sna Light Comp ny C 1994 Annuri Rcdiological Envircnm:ntrl R:: port O 4
- b. Procedures Gamma emitters, including 1-131, are determined by scanning a dried, homogenized sample with the gamma spectroscopy system. A high resolution germanium detector is utilized with this system.
Strontium 90 analysis for feedstuff is performed by a procedure similar to that described in S-C.2 after drying, weighing and ashing the sample. Radiciodine (1-131) is determined by radiochemistry. Stable iodide carrier is first added to a chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and treated with sodium hypochlorite. The iodate is then reduced to lodine with hydroxylamine hydrochloride and is extracted into chloroform. It is then back-extracted as lodide into sodium bisulfite solution and is precipitated as palladium j iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. ) l
- 3. Results and Conclusions I l
A summary of data is presented in Table 5-2.
- a. Feed A total twelve (12) samples were analyzed for 1-131. No detectable j concentrations were found.
^
A total of four (4) samples were analyzed for Sr-90. Small amounts of Sr-90 from previous nuclear weapons tests were found in all samples. A total of twelve (12) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was found in all samples and Be-7 was detected in seven (7) samples.
- b. Food A total of four (4) samples were analyzed for 1-131. No detectable concentrations were found.
A total of four (4) samples were analyzed by gamma spectrometry.
. Naturally occurring K-40 was found in all samples.
- c. The data from food and feed analyses were consistent with previous data.
These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in foods and feeds in the vicinity of the site. l J. ; S-32 Sectica 5. ENVIRONMENTAL MONITORING PROGRAM =
Duqursno Light Comp:ny 1994 Annucl Rcdiological Environm:ntil Rrp rt E. Monitoring of Local Cows Milk
- 1. Description - Milch Animal Locations During the seasons that animals producing milk (milch animals) for human consumption are on pasture, samples of fresh milk are obtained from these animals at locations and frequencies noted in Table 5-1. This milk is analyzed for its radiciodine content calculated as lodine-131. The analyses are performcd within eight (8) days of sampling.
Detailed field surveys are performed during the grazing season to locate and enumerate milch an;mals within a five (5) mile radius of the site. Goat herd locations out to fifteen (15) miles are identified. Survey data for the most recent survey conducted in is shown in Figure 5-5.
- 2. Sampling Program and Analytical Techniques
- a. Program Milk was collected from these (3) reference dairy farms (Searight's, Brunton's and Nicol's) within a 10-mile radius of the site and from one (1) control location (Windsheimer's) outside of the 10-mile radius. Additional dalries, which represent the highest potential milk pathway for radiciodine I '
based on milch animal surveys and meteorological data were selected and sampled. These dairies are subject to change based upon availability of milk or when more recent data (milch animal census) indicate other locations are more appropriate. The location of each is shown in I Figure 5-6 and described below. I ite Dah o An al Direction and Distance from Midpoint between Resctors Collection Period Searight Jan. Dec. I 25 49 Cows 2.2 miles SSW 27 Brunton 94 Cows 7.3 miles SE Jan. - Dec. 29A Nicol 76 Cows 8.0 miles NE Jan. - Dec. 96 Windsheimer 55 Cows 10.3 miles SSW Jan. - Dec. 109" Soissen 34 Cows 3.83 miles WSW Jan. - Dec. 102 " Ferry 3 Goats' 3.3 miles SE Aor. - Dec. 105" Ambrose 25 Cows 3.86 miles WSW Jan. - Apr. 106 " Conkle 32 Cows 3.75 miles WSW Jan. - Dec. Milk Usage - Home Only. Highest potential pathway cairies. I y section 5. ENVIRONMENTAL MONITORING PROGRAu 5-33
Duquesna Light Company E, 1994 Annurl Radiologicci Environmsntal Report O , Figure 5-5. Beaver Valley Power Station Milch Animal Census ,
, BEAVER VALLEY POWER STATION l MILCH ANIMAL CENSUS --
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L Duquesne Light Company 1994 Annual Radiological Environmental Report E Figure 5-6. Environmental Monitoring Locations - Milk [ E MIII y u- cas on m 1
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[ % MILK j Section 5. ENVIRONMENTAL WONITORAG PROGRAM F35 ,
Duqu:sn3 Light Company 1994 Annuci Rcdirlogicri Envircnm:ntil R: port Cl L d The sample from Searight Dairy was collected and analyzed weekly for radiciodine using a procedure with a high sensitivity. Samples from each of the other selected dairies were collected monthly when cows are g indoors, and bi-weekly when cows are grazing. This monthly or bi-weekly 3 sample is analyzed for Sr-89, Sr-90, gamma emitters including Cs-137 (by high resolution germanium gamma spectroscopy) and 1-131 (high sensitivity analysis).
- b. Procedure Radiciodine (1-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low-level b, eta counting system.
Gamma emitters are determined by gamma spectroscopy of a one liter Marinelli container of milk. Strontium milk samples are prepared by adding stable strontium carrier and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is purified in all samples in a chromatographic column. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for the ingrowth of Y-90. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated E as oxalate. The yttrium oxalate is mounted on a nylon planchet and is g counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO2 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm8 aluminum absorber for low level beta counting. Chemical yields of strontium and yttrium are determined gravimetrically.
- 3. Results and Conclusions A summary of data is presented in Table 5-2.
A total of one hundred sixty-six (166) samples were analyzed for 1-131 during 1994. All 1-131 activities in milk were below the minimum detectable level. A total of one hundred thirty-two (132) samples were analyzed for Sr-89 and S r-90. No Sr-89 was detected. Sr-90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the normally expected range. A total of one hundred thirty-two (132) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was found in all samples. It was noted that the dairies with the highest annual mean activities were goat dairies, which are known to concentrate activities over a factor of two compared to a cow dairy. All results were consistent with (or lower than) those obtained in the j preoperational program. These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in milk in the vicinity of the site. 1 I I: C 5-36 section 5. ENVIRONMENTAL MONITORING PROGRAM 1 l
Duquesna Light Comp!ny . H 1994 Annual Redisl:gical Environmsntal Rap;rt k= .
. F. . Environmental Rs.diation Monitoring -
f Description of Regional Background Radiation and Sources 1. The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300-400 feet. ' Most of the land is wooded. The principal geologic features of the region are.nearly flat-laying sedimentary
. beds of the Pennsylvania Age. - Beds of limestone alternate with sandstone and )
shale with abundant interbedded coal layers. Pleistocene glacial deposits - J
- h. partially. cover' the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. -Outcrops of sandstone, shale, and . limestone of the Allegheny-h, Formation exist within the Ohio River Valley and along major tributary streams.
Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 R/hr. Results for 1994 indicated that background radiation continued in this range.
- 2. Locations and Analytical Procedures q Ambient external radiation levels around the' site were measured - using
{. , thermoluminescent dosimeters (TLDs). In 1994 there were a total of forty-four (44) off-site environmental TLD locations. The locations of the TLDs are shown in Figure 5-7 through Figure 5-10. Thirteen [. .~ (13) locations also have QC Laboratory TLDs. Both laboratories use calcium sulfato dysprosium. (CaSO,:Dy) in Teflon matrix. The calcium sulfate (CaSO,:Dy) TLDs were annealed shortly before placing the { TLDs in their field locations. The radiation dose accumulated in-transit between.. the field location and the laboratory was corrected by annealing control' dosimeters shortly before the field dosimeters were removed from the field { location, then shipping the freshly annealed control dosimeters with the exposed field dosimeters to the laboratory for readout at the same time. All dosimeters were exposed in the field in a special environmental holder. The dosimetry { system was calibrated by reading calcium sulfate' dosimeters which have been exposed in an accurately known gamma radiation field. , g [ ~ Section 5. ENVIRONMENTAL WONITORING PROGRAW 5-37
Duquisn3 Light Comp:ny EI 1994 Annurl R diologicci Envircnm:ntel Report C l
- 3. Results and Conclusions Data obtained with the contractor TLD (CaSO.:Dy in Teflon) during 1994 are summarized in Table 5-2, and the quality control TLD results are listed in Table 3-1.
The annual exposure rate of all offsite TLDs averaged 0.149 mR/ day in 1994. Since the QC comparisons suggest the Contractor annual TLD dose values are low, the annual exposure rate of all cuarterly TLDs were also averaged to obtain 0.153 mR/ day in 1994. As in previous years, there was some variation among locations and seasons as would be expected. Two TLDs (one quarterly, one annual) were lost in the field during the year. In 1994, ionizing radiation g dose determinations from TLDs averaged approximately 54.3 mR for the year. 3 When using the exposure rate from ouarterly TLDs the result is 56.0 mR for the year. This is comparable to previous years. There was no evidence of g anomalies that could be attributed to the operation of the Beaver Valley Power g Station. The TLDs confirm that changes from natural radiation levels, if any, are negligible. I I i 5-38 Section 5. ENVIRONMENTAL MONITORING PROGRAM "" 1
Duquusna Light Comp:ny 1994 Annu:1 Radiological Environm5ntal Report I Figure 5 7. TLD Locations . Northwest Quadrant ' FIGURE 5 TLD LOCATIONS - 8 l NORTHWEST GUADRANT _ .. 'y i ' I BEAVER VALLEY POWER STATION
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14 15 Georgetown 14 87 Calcutta 14 47 E. uverpood Water Co. ( 15 32 Midlano S.S. ( 15 88 Midland Heights l 15 89 Ohioville { 16 90 Fairview School 16 93 Sunset Hills Midland Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-39
Duqu:sn3 Light Compsny O 1994 Annuti Redirl giCal Envircnmental Report O I Figure 5-8. TLD Locations - Northeast Quadrant I FIGURE 5 8 - TLD LotAT10N5 NORTHEAST QUADRANT
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3 48 Industry (Church) 3 72 Logan School 3 298 Beaver County Hosp. 4 10 Shippingport Post Office 4 30 Shsppingport. PA (S.S.) 4 73 Potter Twp. School 4 74 Community College (Center Twp.) 5 51 Ahquippa 5 75 Mott Road S 45 ML Pleasant Church 5 40 Section 5. ENVIRONMENTAL MONITORING PROGRAM I E
l Duqu sns Light Comp ny 1994 Annu:1 Rcdi logical Environm:ntal R:p2rt l Figure 5-9. TLD Locations - Southeast Quadrant L l I !
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BEAVER VALLEY POWER STATION L Sector Sjte Location 5 51 Ahquippa 5 75 Holt Road F $ 45 Mt. Pleasant Church l 6 45.1 Raccoon Twp. 6 76 Raccoon Twp. School 6 77 Green Garden Road 7 59 fron's Farm 7 78 Raccoon Municipal Bldg. 7 27 Brunton's Dairy 8 94 McCleary Road 8 79 Rt.18 and Rt.151 9 80 Raccnon Park 9 81 Southside School 9 82 Hanover Municipal BJog. l
- Section 5. ENVIRONMENTAL MONITORING PROGRAu 5-41
Duqu:sn2 Light Comp:ny U' 1994 Annut! Rcdiological Environm:nt:1 Rep:rt O Figure 510. TLD Locations . Soutnwest Quadrant
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BE AVER VALLEY POWER STATION I. Sector ).!te Location 9 0 Raccoon Park 9 81 Southside School 9 82 Hanover Municipal Biog. 10 48 Weirton Water Company 10 83 Mill Creek Road 10 95 McGeary Road 11 13 Meyer's Farm 11 14 Hookstown 11 84 Hancock Children's Home 12 92 Georgetown Road 12 85 Rt. 8 and Rt. 30 13 86 E. Uverpool 13 60 Haney's Farm 5-42 B ElB Section 5. ENVIRONMENTAL MOMTORING PROGRAM
F. Duqu:sna Light Compsny 1994 Annu 1 Redi: logic 1 Environm:ntal Report G. Monitoring of Fish
- 1. Description During 1994, fish collected for the radiological monitoring program included carp, catfish, and sheepshead.
- 2. Sampling Program and Analytical Techniques !
- a. Program Fish samplus are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectroscopy. Fish sampling locations are ,
shown in Figure 5-11.
- b. Procedure A sample is prepared in a standard tared 300 mi plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a high resolution germanium detector.
. 3. Results and Conclusions ;
'~
A summary of the results of the fish monitoring data is provided in Table 5-2. A total of nine (9) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was found in all samples. No other gamma emitting radionuclides were detected. The analyses demonstrate that the Beaver Va!!ey Power Station did not contribute a significant increase of radioactivity in the Ohio River fish population. I I I I Secta 5. ENVIRONMENTAL MONITORING PROGRAM 5-43
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Duqu:sno Light Comp ny iI. 1994 Annu 1 R diological Environm:nt:1 R:: port H. Monitoring of Surface, Drinking, Well Waters and Precipitation
- 1. Description of Water Sources The Ohio River is the main body of water in the area. It is used by the Beaver Valley Power Station for plant make-up for the cooling tower and for receiving plant liquid effluents.
I Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site. It is used by several municipalities and industries downstream of the site. The nearest user of the g Ohio River as a potable water source is Midland Borough Municipal Water 5 Authority. The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river. The next downstream user is East Liverpool, Ohio which is approximately 6 miles downstream. The heavy
- I industries in Midland, as well as others downstream use river water for cooling purposes. Some of these plants also have private treatment facilities for plant sanitary water.
.I Ground water occurs in large volumes in the gravel terraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm. In general, the BVPS site experiences cool winters and moderately warm .I - summers with ample annual precipitation evenly distributed throughout the year. The record mean annual precipitation for the area is 36.40 inchec based on 1972 to 1990 data collected at the Pittsburgh International Airport. I .I Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-45
Duqu:sn3 Light C:mp ny O 1994 Annuri Rcdisl:gicsl Envirenm:ntal R: port Ul l l l
- 2. Sampling and Analytical Techniques
- e. Surface (Raw River) Water The sampling program of river water includes five (5) sampling points l along the Ohio River. Raw water samples are normally collected at the i East Liverpool (Ohio) Water Treatment Plant [ River Mile 41.2] daily and composited into a monthly sample. Weekly grab samples are taken from j the Ohio River at the following locations: upstream of Montgomery Dam gi
[ River Mile 31.8]; and near the discharge from the Beaver Valley Power 5; Station [ River Mile 35.0]. Two automatic river water samplers are at the i following locations: Upstream of Montgomery Dam [ River Mile 29.6]; and gl at J&L Steel's river water intake [ River Mile 36.2]. The automatic sampler g) takes a 20-40 mi sample every 15 minutes and samples are collected on a i weekly basis. The weekly grab samples and automatic water samples are l composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point. The weekly composites from the automatic river water sampler upstream at Montgomery Dam are analyzed for 1-131. ; The monthly composites are analyzed for gross alpha, gross beta, and g i gamma emitters. The quarterly composites are analyzed for H-3, Sr-89, gl Sr-90, and Co-60 (high sensitivity). Locations of each sample point are shown in Figure 5-12.
- b. Drinking Water (Public Supplies)
Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Water Treating Plants. An automatic sampler at each location collects 20-40 mi every 20 minutes. These intermittent samples are then composited into a weekly sample. The weekly grab sample taken ) at the DLC Training Building was discontinued in October. The Training Building drinking water is now supplied by Midland Water Plant. Sampling at the Training Building was discontinued after results were proven consistent with those obtained in Midland. The weekly sample from each l location is analyzed by gamma spectroscopy. The weekly samples are also analyzed for 1-131. Monthly composites of the weekly samples are analyzed for gross alpha, l gross beta, and by gamma spectrometry. Quarterly composites are analyzed for H-3, Sr-89, Sr-90 and Co-60 (high sensitivity). Locations of each sample point are shown in Figure 5-12. I E 5 46 Section 5. ENVIRONMENTAL MONITORING PROGRAW E
Duqu:sna Light Comp ny i 1994 Annu 1 R di;l gic l Envircnm:ntil Report l
- c. Ground Water i
) Grab samples were collected each quarter from each of four (4) well locations (see Figure 5-12) within four (4) miles of the site. These
- locations are
f I One (1) well at Shippingport, PA One (1) well at Meyer's Farm (Hookstown, PA) One (1) well in Hookstown, PA One (1) well in Georgetown, PA Each ground water sample is analyzed for gross alpha, gross beta, tritium, and by gamma spectroscopy. F L d. Precipitation Precipitation is collected at Shippingport, PA, East Liverpool, OH and F Weirton, WV. Precipitation when available is collected each week and then L composited into monthly and quarterly samples. The monthly samples are analyzed for gross beta and gamma emitters and the quarterly composites E are analyzed for H-3, Sr-89 and Sr-90. Locations of each sample point are E shown in Figure 5-12. c w a U F L._ I L F L F sechon S. ENVIRONMENTAL MONITORING PROGRAM 5-47 [ - - _ - _ _ _ _ _ _ _ _
Duqu:sna Light Company O 1994 Annuni Rcdiologic l Environmsnt:1 Report g Figure 5-12. Environmental Monitoring Stations Locations - Wells, Surface Water, Drinking Water and Precipitation
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et 4 5 5.. O l l t M s &\is 1AMPt.E SAMPLE SAMPUNG PO!NT TYPE POINT DESCRIPTON Surfuse weier 2A Downstroem SVPS 21 Deumstroom . J & L Intste 5 East Overpeel weier Ptevit (Asw weeer) as Memgemory Dem (Upsireend de 1 Upsesem Arte Petymore eneses Dnnoung . Midlans weier Plent water 5 East Uwerpent water Pieve j well 11 Shepptngpset Sete weier 13 Meyero Form 14 Hootstown, PA il Coorgetown. PA Proctpetstion 30 $Nepengpert PA 47 East uwerpeel, OH es weerton, WV I
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[ Duquasn3 Light Comprny 1994 Annuri Redi:l:gicci Envircnm:ntil R:: port
- e. Procedures
( Gross aloha and cross beta activities are determined first by evaporating one liter of the sample on a hotplate. The residue is mounted and dried on a 2-inch stainless steel planchet. The sample is counted in a low background, gas flow proportional counter. Self-absorption corrections are made on the basis of sample weight. Gamma analysis is performed on water sample by loading one liter of sample into a one liter Marinelli container and counting a high resolution germanium gamma spectrometry system. Strontium-89 and 90 are determined on water samples by a procedure similar to that described in 5-C.2 except that the leaching step is eliminated. Cobalt-60 is determined with a sensitivity of 1 pCi/ liter by evaporating 2 liters of sample on a hotplate and transferring the residue to a 2-inch planchet. The planchet is counted on a high resolution germanium gamma , spectrometry system. l Tritium is determined in water samples by liquid scintillation counting. l Radiciodine (1-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system. (
- 3. Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, ground and precipitation) are provided by sample type and analysis in Table 5-2. These
[ are discussed below,
- a. Surface Water
( A total of forty-eight (48) samples were analyzed for gross alpha and gross beta. Alpha activity was not detected in any of the samples. Positive beta results above preoperational levels were detected in the BVPS discharge area and are attributable to station releases. The beta activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC ( license. section 5. ENVIRONMENTAL MONITORING PROGRAM 5-49
l Duqu=ns Light Company /' 1994 Annur.1 Rrdiol:gicd Environm:nts! Rep;rt U A total of sixteen (16) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-58 and Co-60. Positive tritium results were detected in the BVPS discharge area and are attributable to g station releases. The highest tritium results were noted, however, to 5 correspond to shore samples taken when mixing zone sampling by boat was not possible. All other samples taken upstream and downstream were within preoperational levels. The activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license. A total of forty-eight (48) samples were analyzed by gamma spectrometry. K-40 was detected in three of the samples. No other gamma emitting radionuclides were detected. A total of fifty-three (53) samples were analyzed for I-131 using a highly sensitive technique. Trace levels of I-131 were measured in sixteen (16) of g the weekly samples. The results were slightly above the minimum 3 detectable activity. The positive results were detected at a control location above the BVPS discharge and could not be attributed to plant releases. The results may be attributed to medical procedures and the expected variability in the analyses results of very low levels of activity.
- b. Drinking Water A total of thirty-three (33) samples were analyzed for gross alpha and l gross beta. All results were within a normal range.
A total of eleven (11) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-60. No H-3, Sr-89, Sr-90, or Co-60 were detected. A total of one hundred forty-five (145) samples were analyzed by gamma spectrometry. A total of one hundred forty-five (145) samples were analyzed for 1-131 using a highly sensitive technique. Trace levels of I-131 were measured in seventy three (73) of the weekly samples. The results were slightly above the minimum detectable activity. The positive results were detected at l Midland and East Liverpool and could not be attributed to plant releases. As noted under Surface Water above,1-131 has been observed upstream of the site. The results may be attributed to medical procedures and the l expected variability in the analyses results of very low levels of activity.
- c. Ground Water A total of sixteen (16) samples were each analyzed for gross alpha, gross beta, H-3 and by gamma spectrometry. Alpha activity was not detected.
H-3 activity was detected in one of the samples. The gross beta results are comparable to preoperational ranges. K-40 was detected in only one sample. No other gamma emitting radionuclides were detected. 5-50 section s. ENVIRONMENTAL MONITORING PROGRAM "
I Duqu:sna Light Company
-I 1994 Annu 1 Radirlagical Environm:nt:1 R::psrt
, d. Precipitation A total of thirty-five (35) samples were analyzed for gross beta. All results were within a normal range. A total of twelve (12) samples were analyzed for H-3, Sr-89 and Sr-90. Three (3) positive tritium results detected were within normal levels. No Sr-89 or Sr-90 was detected. A total of thirty-five (35) samples were analyzed by gamma spectrometry. Naturally occurring Be-7 was detected in twenty-nine (29) samples.
- e. Summary The data from water analyses demonstrates that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in local river, drinking, well waters or precipitation. The few positive results which I could be attributable to authorized releases from the Beaver Valley Power Station are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.
Further, the actual detected concentration (averaged over the total batch discharge period during the year) attributable to Beaver Valley Power Station, was only 0.40% of the Maximum Permissible Concentration allowed by the Federal Regulations for water discharged to the Ohio River. The Ohio River further reduced this concentration by a factor of ~ 600
.- prior to its potential use by members of the public.
I i Section 5. ENVIRONMENTAL MONIToRI 4G PROGRAM 5-51
Duqu:sna Light Comprny 'n ' 1994 Annuti Rrdiologic:1 Envir:nm:ntil Rep:rt CI
- 1. Estimates of Radiation Dose to Man
- 1. Pathways to Man - Calculational Models The radiation doses to man as a result of Beaver Valley operations were g calculated for both gaseous and liquid effluent pathways using codes for the ARERAS/ MIDAS computer system equivalent to NRC computer codes XOQDOQ2, E
GASPAR, and LADTAP. Dose factors listed in the ODCM were used to calculate doses to maximum individuals from radioactive noble gases in discharge l plumes. Beaver Valley effluent data, based on sample analysis in accordance with the schedule set forth in Appendix A of the BVPS license, were used as the radionuclide activity input. Each radionuclide contained in the Semi-Annual Radioactive Effluent Release Report (noble gases, particulates, radiciodines and tritium) were included as source terms when they were detected above the LLD values. All LLD values reported by Beaver Valley Power Station are equal to or lower than those required by the Technical Specifications. All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to code equivalent to XOQDOQ2 which in
. turn provided input for the GASPAR equivalent. Except when more recent or specific data was available, all inputs were the same as used in the Beaver
. Valley Power Station Environmental Statements or in Regulatory Guide 1.109. The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the " cow-milk-child", and other ingestion pathways. All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using Intrinsic Germanium detectors. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0). The actual data from these analyses are tabulated and , used as the radionuclide activity input term in code equivalent to LADTAP. A s hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is available, all other input are g obtained from the Beaver Valley Power Station Environmental Statement or E Regulatory Guide 1.109. Pathways, which were evaluated, are drinking water, fish consumption, shoreline recreation, swimming, and boating. I 5-52 Section 5. ENVIRONMENTAL MONITORING PROGRAM EB
'?I ,
Duquzsn2 Light Ccmprny 1994 Annuni Radi: logic 1 Envircnmxntrl Rsport
- 2. Results of Calculated Radiation Dose to Man - Liquid Releases
{: '
- a. Individual Dose The doses which are calculated by the model described above are to a
{ hypothetical real individual located at Midland since this is the nearest
.. location where significant exposure of a member of the public could potentially occur; therefore, this location is use to calculate the' maximum
{ exposure. A breakdown of doses by pathway and organ is provided in Table 5-6 for the maximum individual. Included in this table is a breakdown of r typical dose to individuals from natural radiation exposure. {* The results of calculated radiation dose to the hypothetical real individual are compared to BVPS annual limits in Table 5-7.
- b. Upon implementation of the Unit 2 Technical Specifications and inception of the liquid discharge procedures at Unit 2 on July 24,1987, the discharge i limits were clarified to be reactor specific; i.e., Unit .1 and Unit 2 have i reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annual site limits listed in Table 5-8 are specific to this report only, and were derived by multiplying the individual L. Technical Specification reactor limits by a factor of two (2).
F L p.- L-r L E L. L Section S. ENVIRONMENTAL WoNIToRING PROGRAM 5-53
Y l' TABLE 5-6 w a j Radiation Dose to Maximum Individual *, mrem /yr - Liquid Releases 6 y a e PATHWAY SKIN ORGAN THYROID BONE BODY Fish Consumption N/A O m77 0 6 42 0E524 ' OM79 y 5 (Teen) (Liver) (Adult) (Child) (Adult) E z ii;- r c Drinking Water N/A 0M9 (Infant) (Thyroid) O M 59 (Infant) O M 91 (Child) O M 33 (Child) o { , e o o e O M 267 O M 267 Shorehne Activit es
- 0. M H OM3M OM267 (Teen)
{o [ m 8 ' i (Teen) (Teen) (Skin) (Teen) (Teen) E z E 0 0 0000314 0.00195 0.00159 0.000568 0.00147 5- EO
^
(Teen) (Child) (Liver) (infant) (Child) (Adull) D U E TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSUREc h E
-h 9-g-Ambient Gamma Radiation $.
58 g O.{ m~ Radionuclides in Body 40 3 s.9 h o3 Global Fallout <1 7 $A E' $ Radon 198 E E
? D TOTAL mrem 296 [ $
5 3 a Located at Midland Drinking Water intake . b Total liquid releases are from Site (combined Units 1 and 2) c National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation", BEIR Report, 1990 M M M M M M M M EE
X I Duquesn3 Light Company 1994 Annuel Rrdiologic:1 Environmentsi Report i Table 5-7. Results of Calculated Radiation Dose to Man Uquid Releases l TABLE 5-7 - Results of Calculated Radiation Dose to Man - Liquid Releases Maximum Exposure BVPS Annual Percent of Hypothetical Real yg Organ ,, Individual mrem TOTAL BODY Adult 0.00147 6.0 0.025 Teen 0.00100 6.0 0.017 Child 0.00145 6.0 0.024 Infant 0.00130 6.0 0.022 ANY ORGAN Adult 0.00165 (Liver) 20.0 0.0083 Teen 0.00140 (Liver) 20.0 0.0070 Child 0.00195 (Liver) 20.0 0.0098 infant 0.00:59 (Thyroid) 20.0 0.0080 Maximum Total Body Dose - Caosule Summary i mrem : I 1994 Calculated 0.00147 Final Environmental Statement 3.5 ; Hiohest Oroan Dose l I 1994 Calculated Final Environmental Statement 0.00195 4.7 l i l 1 i section 5. ENVIRONMENTAL MONITOR!NG PROGRAu 5-55
/ Duqu:sn2 Light Company o l 1994 Annual Rcdi:l gical Environment:1 R: port U i
- c. Population Dose The 1994 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was:
* ' Pe Organ Man-Millirems Iu r TOTAL BODY 95.5 H-3 94.2 mrem THYROID 104.0 H-3 94.2 mrem
- 3. Results of Calculated Radiation Dose to Man - Atmospheric Releases The results of calculated radiation dose to the maximum exposed individuals for BVPS airborne radioactive effluents during 1994 are provided in Table 5-8. The doses include the contribution of all pathways. A 50-mile population dose is also calculated and provided in Table 5-8. H-3 is the primary radionuclide contributions to these doses.
The results are compared to the BVPS annual limits in Table 5-8. As in the liquid discharge limits, the gaseous effluent limits are reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annual limits listed in Table 5-8 are specific to this report only, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2). The results show compliance with the BVPS annual limits. I l l l 5-56 section s. ENVIRONMENTAL MONiioRING PROGRAM
Duqu:sna Light Company i 1994 Annust Rrdiological Environm ntal Report I
- 4. Conclusions
'I Based upon the estimated dose to individuals from the natural background radiation exposure in Table 5-6, the incremental increase in total body dose to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit 1 and 2, is less than 0.0001% of the annual background.
The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to t,he public. I I
;I l
l lI .+ Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-57 i I
Duquisn3 Light Company 0 1994 Annu 1 Rcdlol:gic 1 Environm:nt:1 Report C Table 54. Results of Calculated Radiation Dose to Man - Atmospheric Releases TABLE 5-8 Results of Calculated Radiation Dose to Man - Atmospheric Releases MAXIMUM I BVPS ORGAN ANNUAL LIMIT OF PONTION INDIVIDUAL ANNUAL LIMIT DOSE mrem man rem TOTAL BODY 0.248 30 0.83 0.869 SKIN 0.249 30 0.83 0.165 LUNG 0.247 30 0.83 0.869 THYROID 0.252 30 0.84 0.874 l l _ I I' I 5-58 secuon s. ENVIRONMENTAL MONITORING PROGRAM s=
I l I i I m E APPENDIX 1 ! n i L r u
- 7. .
u Contractor Laboratory n u EPA Interlaboratory L E Comparison Program E [ . E _ . . . - . . . . - - - . . . .. ...........A
I I EPA INTERLABORATORY COMPARISON PROGRAM Teledyne Brown Engineering Environmental Services panicipates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section trending graphs (since 1981) and the 1994 data summary tables are presented for isotopes in the various sample media applicable to the Duquesne Light Company's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of I ' problems encountered in a few cases and the steps taken to prevent reoccurrence. t i l I l I l I l l I W a [ E f - --
.is l'4g f A, I UNITED OTATE3 ENVIRONMENTAL PROTECTICN ACENCY
^
,I CFFICE OF RESE ARCM ANO DEVELOPMENT ENvlRONMENTAL McNitomiNG SYSTEMS LASONATony LAS VEGAS l ao sox es47s LAs vegas NEvAOA esies 247s (702/7s4 2100 FTS 545 21001 l
Dear Participants The Radiation Quality Assurance Program has been experiencing problems with the Ruthenium-106 currently used in the Performance Evaluation (PE) Studies and in the Standards Distribution Program. If these problems can be satisfactorily resolved, this analyte vill once again J be placed into this PE Study. If the problems cannot be resolved, the i Ruthenium-106 vill be replaced. I Formal written notice vill be given to all participants that are enrolled in the Gamma in Vater PE Study before the Ruthenium-106 is reintroduced or replaced. At that time, new calibration standards vill be available to all participants in the Gamma in Vater PE Study. I Sincerely,"(- - t George Dilbeck ! Chemist Performance Evaluation Program Radionnalysis Branch (RSA-RADOA) i I l I __ __ __ w
DUQUESME LIGHT COMPANY EPA INTERLABORATORY COMPARISON PROGRAM 1994 (Page I of 2) Date EPA EPA TI Norm Dev. " Warning EPA Date TI Malled Preparation Re sults Issued Results Media Nuclide Results(a) Resulte(b) (Enown) "* Action __ 05/13/94 Water Sr-89 25.0 1 5.0 24.00 i 1.00 -0.35 01/14/94 03/04/94 15.67 i 1.53 0.23 Sr-90 15.0 t 5.0 01/28/94 02/25/94 04/12/94 Water Gr-Alpha 15.0 1 5.0 21.67 1 0.58 2.31 " (c) Gr-Beta 62.0 i 10.0 72.33 i 3.79 1.79 02/04/94 03/04/94 04/26/94 Water I-131 119.0 1 12.0 110.33 1 0.00 -1.30 04/14/94 05/23/94 Water Ra-226 19.9 i 3.0 21.00 i 1.00 0.64 02/11/94 15.67 i 1.53 0.45 Ra-228 14.7 i 3.7 03/31/94 05/13/94 Water H-3 4936.0 1 494.0 4833.33 1152.75 -0.36 03/04/94 06/13/94 08/02/94 Water Gr-Beta 117.0 1 18.0 102.67 1 6.43 -1.38 04/19/94 20.0 1 5.0 19.00 i 1.00 -0.35 Sr-89 Sr-90 14.0 1 5.0 13.00 1 0.00 -0.35 Co-60 20.0 1 5.0 23.67 i 3.21 1.27 Cs-134 34.0 1 5.0 34.00 i 1.73 0.00 Cs-137 29.0 1 5.0 34.00 1 2.65 1.73 Gr-Alpha 86.0 1 22.0 78.00 1 3.00 -0.63 Ra-226 20.0 i 3.0 15.67 i 1.53 -2.50 * * (d) Ra-228 20.1 1 5.0 15.33 i O.58 -1.65 06/10/94 07/15/94 10/31/94 Water Co-60 50.0 i 5.0 43.00 1 2.00 -2.42 * * (e) Zn-65 134.0 i 13.0 13.33 1 0.58 -16.08 * ' (I) Ru-106 252.0 1 25.0 201.33 i 9.29 -3.51 " * (g) Cs-134 40.0 1 5.0 29.33 i 3.79 -3.70 ' * (h) Cs-137 49.0 1 5.0 49.67 i 1.53 0.23 Ba-133 98.0 i 10.0 85.00 1 3.00 -2.25 * * (1) 06/17/94 08/10/94 10/03/94 Water Ra-226 15.0 1 2.3 15.33 i 0.58 0.25 Ra-228 15.4 1 3.9 16.33 i 1.53 0.41 07/22/94 08/19/94 10/14/94 Water Gr-Alpha 32.0 1 8.0 25.33 1 2.89 -1.44 Gr-Beta 10.0 1 5.0 16.00 1 0.00 2.08 * * (j) 08/05/94 08/29/94 10/24/94 Water 11-3 9951.0 i 995.0 9700.00 1100.04 -0.44 m M M M - M M EE
DUQUESNE LIGHT COMPANY EPA INTERLABORATORY COMPARISON PROGRAM 1994 (Page 2 of 2) EPA TI Norum Dev. **Waratog EPA Date TI Resuod Date EPA --
*Actles '
see suits teamed mesuits Media NecMde
~ :-: T" (Emews)
- 7. _ __ tsee Water U 10.2 i 2.6 9.70 1 0.52 2.12 * * (k) 09/16/94 09/16/94 10.67 1 0.58 0.77.
Ra-226 10.0 i 1.5 Ra-228 10.2 i 2.6 9.70 i O.52 -0.33 Water. 1-131 79.0 i 8.0 71.00 1 3.00 ' -1.73 10/07/94 12/23/94 Ftsetmetes (a) Average i experimental segma. (b) Espected laboratory precteson (I silyna. I determination) (c) There appears to be variation in seK. absorption metrtz. 'the EPA conArms that the composition of their tap water from take Mead, vartes seasonally which can cause wartation in alpha. beta results. No corrective action required at this time since results are within i 3 sigma control limMs. (di No spectAc or apparent reason found. Data sheets verthed and detector efRctencies cahbrated. WSI exert care in makirig dilutions and using terrect sample type m concentration of ackis. WlE check future samples to see N a pattern develops. (c) A second ahquot was analysed. paying particular attention to volume ahquoted. The result. 52 pC1/l. was in good e,im...sn with the EPA. The three ortsnal results. each munted on a stSerent detector, showed good predaton. The measurement d Co-60 has not been a problem Future EPA croe& checks wtB be weghted and results followed to check for a possible trend "out of control". (f) The average value of three analyses on the " Report of Analysis" was 133 pct /leter which is in good agreement with the EPA. Apparettiy, incosTect results . were entered into the EPA computer. hature data wtB be printed from the computer screen to check erdries. See attached letter from EPA. (W The EPA has tavacated that the Radiation Quahty Assurance Program has been ,m.L. ag problems with the ruthentum-106 analysis (h) The Srst auquet. prepared accoritng to EPA ddution snetructions was counted on four detectors in the I liter Martneut geometry wtth Cs-134 results (based on the 796 ~ NeV peak) In pct /I d 32.0,25.1. 31.7. and 30.8. The 31.7 result was not reported. Had that been reported Instead of 25.1. the average wouki have been 31.5 and the nonnaheed deviation would have been -2.94 Instead of -3.70. A second ahquot was prepared and a sende measurement was made with the resuN of 31.1 pct /l. An undeuted attquot was measured in a 150 nl geometry with the resuN of 33.5 pCS/l. "Ihat result is -- . . _ A with the MastneSt resuMs. Thus none cri sample peeparation (<Wutton. volume determination. maintaining correct pH etc.), sample geometry, or detectw effletency seem to be the cause of the low results. (t) 1here is no apparent tenson for the low result. however the average value 85 pct /l is in good agreennerd to the greswl average 186.46). No correctsve action planned. U) EPA result for grose beta in water were corrected for 20% creestalk into the beta channel tem the Th-230 alpha spike. Recent nicasurements shoor that the aneme=Ils can be much hp (37% for *Rnnelee counter #3 and 54% for geenma products counter #1). The nonnettsed deviation from the grand average was only 0.38. hature results will be conected with spectSc crosstalk values determined by counting Th-230 standards ik) Ass tesvrolleettnen in Irhist evnnluctest; lier rrenalte will le sevnIIselde plusity.
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I I I I I
, APPENDIX ll 1
.I I I. QC Laboratory I 1 EPA Interlaboratory I i Comparison Program .I
I Apoendix A litterlaboratory Comoarison Program Results I Teledyne's Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in I December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides know to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentration of specified radionuclides and report them to the I issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. I The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request. Ris program is conducted by the U.S. Environmental Protection Agency Intercomparison and I, Cahbration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. I l The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), since 1976 via various intemational Intercomparisons of Envirorunental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed. { 1 Table A-3 lists results of the analyses on in-house " spiked" samples for the past twelve months. Data for previous years available upon request. ! 1 I Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months. Data for previous years available upon request. 1 Table A-5 list results of the in-house " duplicate" program for the past twelve months. Acceptance I is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request. l I Attachment A lists acceptance criteria for " spiked" samples. Out-of-limit results are explained directly below the result. Al I
~ l { I 12-31-94 ATTACHMENT A ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-896 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-90* 2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>30 pCi/ liter or kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value
~ Gross beta
~
s100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter 5% of known value Tritium s4,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known)8"
>4,000 pCi/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value I lodine-131, Iodine-1296 s55 pCi/ liter
>55 pCi/ liter 6.0 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-646 >35 pCi/ liter 15% of known value Technetium-996 I 1r n-55, 50 to 100 pCi/ liter
>100 pCi/ liter 10 pCi/ liter 10% of known value Others* -
20% of known value
- From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981 1982, EPA-600/4-81-004.
- Teledyne limit.
A2
O E Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teled Midwest Laboratory results for various sample media'. Concentration in pCi/L" I Lab Sample Date Teledyne Results Code Type EPA Resultd Control Collected Analysis 2 Sigma
- 1s, N=1 Limits STW-702 WATER Jan,1994 Sr-89 20.0 i 1.7 25.0 t 5.0 16.3 - 33.7 STW-702 WATER Jan,1994 Sr-90 14.011.0 15.0 5.0 g
STW-703 WATER Jan,1994 Gr. Alpha 20.3 0.6 6.3 - 23.7 g STW-703 15.0 5.0 6.3 - 23.7 WATER Jan,1994 Gr. Beta 55.313.2 62.0 i 10.0 STW-704 WATER Feb,1994 I-131 110.0 i 2.7 119.0il2.0 44.7 - 79.3 g STW-705 WATER Feb,1994 Ra-226 98.2 - 139.8 E 19.4 t l.5 19.913.0 STW-705 WATER Feb,1994 Ra-228 14.7 - 25.1 15.010.8 14.713.7 STW-705 WATER Feb,1994 Uranium 8.3 - 21.1 9.7 0.4 10.113.0 4.9 - 15.3 l STW-706 WATER Mar,1994 H-3 4,843.3 231.2 l STW-707 4,936.0 t 494.0 4,078.9 - 5,793.1 WATER Mar,1994 Pu-239 28.2 0.9 STW-708 27.6 i 2.8 22.7 - 32.5 WATER Apr,1994 Gr. Alpha 73.3 2.9 STW-708 86.0122.0 47.8 - 124.2 ' WATER Apt,1994 Ra-226 16.911.2 STW-708 20.013.0 14.8 - 25.2 WATER Apr,1994 Ra-228 19.710.7 STW-708 20.115.0 11.4 - 28.8 WATER Apr,1994 Uranium 25.110.1 STW-709 25.0 3.0 19.8 30.2 WATER Apr,1994 Co-60 20.3 i 0.6 STW-709 20.0 i 5.0 11.3 - 28.7 WATER Apr,1994 Cs-134 32.310.6 STW-709 34.0 i 5.0 25.3 - 42.7 WATER Apr,1994 Cs-137 31.310.6 STW-709 29.015.0 20.3 37.7 WATER Apr,1994 Gr. Beta 101.0 i 10.5 STW-709 117.0 1 18.0 85.8 - 148.2 WATER Apr,1994 Sr-89 15.011.7 STW-709 20.015.0 11.3 - 28 7 WATER Apr,1994 Sr-90 14.310.6 STW-710 14.015.0 5.3 - 22.7 WATER Jun,1994 Ba-133 87.310.6 STW-710 98.0 i 10.0 80.7 - 115.3 WATER Jun,1994 Co-60 48.7 i 3.2 STW-710 50.015.0 41.3 58.7 WATER Jun,1994 Cs-134 35.0 t 2.7 STW-710 40.015.0 31.3 - 48 7 WATER Jun,1994 Cs-137 51.310.6 STW-710 49.0 5.0 40.3- 57 7 WATER Jun 1994 Ru-106 184.716.7 252.0 25.0 208.6 295 4 A Ixtter from the EPA was received with the report. It states,"The Radiation Quality Assurance Pro has been experiencing problems with the Ruthenium-106 currently used in the Performance Evalua Studies and in the Standards Distribution Program. If these problems can be satisfactorily resobed, this analyte will once again be placed into this PE Study, if the problems cannot be resolved, the Ruthenium 106 will be replaced. Formal written notice will be given to all participants in the Gamma t in Water PE before the Ruthenium-106 is reintroduced or replaced. At that time, new calibration standards will be available to all participants in the Gamma in Water PE Study." Teledyne will continue to monitor this 3 situation, but at this time, plans to take no additional action. E STW-710 WATER Jun,1994 Zn-65 135.3 2.3 134.0 1 13.0 111.4 - 1 % STW-711 WATER Jun,1994 Ra-226 15.010.4 15.012.3 g STW-711 WATER Jun,1994 Ra-228 14.810.3 11.0 - 19 0 g STW-711 15.413.9 8.6 - 22 2 WATER Jun,1994 Uranium 45.710.2 52.6 i 5.3 STW-712 WATER Jul,1994 Sr-89 26.011.7 30.0 5.0 43.4 - ol 8 g 21.3 - V 7 E Al-1 5
=i
_- - - - - - - - - - - - }
u Table A-1. U.S. Environmental Protection Agency's crosscheck program, companson of EPA and Teledyne's { Midwest Laboratory results for various sample media'. Concentration in pCi/L' Lab Sample Date . Teledyne Results EPA Resultd Control Code Type Collected Analysis i2 Sigma
- 1s, N=1 Limits b' STW-712 WATER Jul,1994 Sr-90 18.7 i 0.6 20.0 i 5.0 11.3 - 28.7 STW-713 WATER Jul,1994 Gr. Alpha 19.311.2 32.018.0 18.1 - 45.9 .
STW-713 WATER Jul,1994 Gr. Beta 12.711.5 10.0 i 5.0 1.3 - 18.7 [L STW-714 WATER - Aug,1994 H-3 10,186.71 66.6 9,951.0 1 995.0 8,224.7 - 11,677.3 STAF-715 AIR FILTER Aug,1994 Cs-137 14.0 i 0.0 15.0 5.0 6.3 - 23.7 STAF-715 AIR FILTER Aug,1994 Gr. Alpha 29.3 i 1.2 35.0 i 9.0 19.4 - 50.6 STAF-715. AIR FIL'11ER Aug,1994 Gr. Beta 56.010.0 56.0t 10.0 38.7 - 73.3 STAF-715 AIR FILTER Aug,1994 Sr-90 18.0i l.0 20.015.0 11.3 - 28.7 , WATER Sep,1994 Ra-226 10.li 0.3 { STW-716 - STW-716 WATER Sep,1994 Ra-228 9.810.1 10.0 1.5-10.2 i 2.6 7.4 - 12.6 5.6 - 14.7 l STW-716 WATER Sep,1994 Uranium 31.911.8 35.0 i 3.0 29.8 - 40.2 MILK { . STM-717. STM-717 MILK Sep,1994 Cs-137 Sep,1994 I-131(g) 61.3 i 0.6 76.011.7 59.0 i 5.0 75.0 i 8.0 50.3 - 67.7 61.1 - 88.9 STM-717 MILK Sep,1994 K-40 1,770.0 1 40.0 1,715.0 i 86.0 1,565.8 - 1,864.2 { STM 717 STM-717 MILK MILK Sep,1994 Sr-89 Sep,1994 Sr 90 23.0 i 1.7 14.710.6 25.0 i 5.0 15.0 i 5.0 16.3 - 33.7 6.3 - 23.7
, . STW-718 WATER Oct,1994 I-131 81.3 3.1 79.0 i 8.0 65.1 - 92.9
- Results obtained by Teledyne's, Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protection Agency (EPA), Las Vegas, Nevada.
[
- All results are in pCi/ liter, except for elemental potassium (K) data in milk, which are in mg/ liter, air filter samples, which are in pCi/ filter; and food products, which are in mg/ kilogram.
- Unless otherwise indicated, the Teledyne results are given as the mean i 2 standard deviations for three
{ determinations. d U.S. EPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits are defined by the EPA. E 1 e [ Al-2 r .
m E Table A-2. Crosscheck program results;'Ihermoluminescent Dosimeters. (TLDs). i mR I Lab Teledyne Results Known Average 2 Sigma Code T1.D Type Date Measurement 2 Sigma Valuei2 Siena (All Participants) 2nd Intemational Intercomparison 115-2 CaF:: Mn Bulb Apr,1976 Field 17.0i l.9 17.1 16.417.7 115-2 CaF : Mn Bulb Apr,1976 Lab 20.8 i 4.1 21.3 18.8 7.6 Second IntemationalIntercomparison of Environmental Dosimeters conducted in April of 1976 by the Health l = and Safety Texas, Laboratory Houston, Texas. (HASL), New York, new York, and the School of Public Health of the University of 3rd Intemational Intercomoarison 115-3 CaF2 : Mn Bulb Jun,1977 Field M.7i 3.2 34.9 i 4.8 31.5 3.0 115-3 CaF2 : Mn Bulb Jun,1977 Lab 89.6i 6.4 91.7 14.6 86.2124.0 Tiurd Intemational Intercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. 4th Intemational Intercomoarison g 115-4 CaF,: Mn Bulb Jun,1979 Field 5 14.1 1.1 14.1 1.4 16.0 9.0 115-4 CaF2 : Mn Bulb Jun,1979 Lab, High 40.4 i 1.4 45.8 i 9.2 43.9 i 13.2 115-4 CaF2 : Mn Bulb Jun,1979 Lab, Low 9.8 t l.3 12.212.4 E 12.0 7.4 5 Fourth Intemational Intercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5th International Intercomp.ari*Dn 115-5A CaF2 : Mn Bulb Oct,1980 Field 31.411.8 30.0 6.0 30.2 14.6 115-5A CaF2 : Mn Bulb Oct,1980 Lab,End 96.6 i 5.8 88.4 8.8 90.7 31.2 115-5A CaF2 : Mn Bulb Oct,1980 Lab, Start 77.4 5.8 75.217.6 75.8140.4 Fifth Intemational Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the E Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 3 5th Intemational Intercomoarison 115-5B LiF-100 Chips Oct,1980 Field 30.3 i 4.8 30.0 i 6.0 30.2 14.6 115-5B LiF-100 Chips Oct,1980 !.ab,End 85.4 i 11.7 88.4 i 8.8 90.7131.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.l i 7.4 75.2 i 7.6 75.8 i 40.4 Fifth Intemational Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls. Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 6th Intemational Intercomparison 115-6 Teledyne did not participate in the Sixth Intemational Intercomparison of Environmental Dosimeters. 7th Intemational Intercomoarison 115-7A LiF-100 Chips Jun,1984 Field 75.412.6 75.816.0 75.1 29.8 A2-1 e a
Table A-2. Crosscheck program results; nermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Da te Measurement t 2 Sigma Valuei2 Sigma (All Participants) 115-7A LiF-100 Chips Jun,1984 Lab, Co-60 80.013.5 79.914.0 77.9127.6 115-7A LiF-100 Chips Jun,1984 Lab, Cs-137 66.6 i 2.5 75.0 i 3.8 73.0 i 22.2 I Seventh Intemational Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, he Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. 7th International Intercomoarison 115-7B LiF-100 Chips Jun,19M Field 71.5 i 2.6 75.816.0 75.1 t 29.8 115-7B LiF-100 Chips Jun,1984 Lab, Co-60 84.8 6.4 79.9 4.0 77.9 27.6 115-7B LiF-100 Chips Jun,1984 Lab, Cs-137 78.8 i l.6 75.0 3.8 73.0 22.2 Seventh Intemational Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, ne Nuclear Regulatory I Comnussion, and the U.S. Environmental Protection Agency. 7th Intemational Intercomoarison 115-7C Jun,19M CaSOg Dy Field 76.812.7 75.8 6.0 75.1 29.8 Cards 115-7C CaSOg Dy Jun,1984 Lab,C M 0 82.513.7 79.9 i 4.0 77.9 27.6 Cards 115-7C CaSOg Dy Jun,1984 Lab, Cs-137 79.013.2 75.0 i 3.8 73.0122.2 Cards Seventh International Intercomparison of Environmental Dosin3eters conducted in the spring and summer of I 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. 8th Intemational Intercomoarison 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.5i l.4 29.711.5 28.9 12.4 115-8A LiF-100 Chips Jan,1986 Field, Site 2 11.3 i 0.8 10.4 i 0.5 10.1 i 9.1 115-8A LiF-100 Chips Jan,1986 Lab, Cs-137 13.7 0.9 17.2 0.9 16.216.8 Eighth Intemational Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. Bih Intemational Intercomoarison 115-8B LiF-100 Chips Jan,1986 Field, Site 1 32.311.2 29.711.5 28.9 12.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.011.0 10.4 i 0.5 10.1 9.0 l I 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 15.8 i 0.9 17.2 i 0.9 16.2 6.8 Eighth Intemational Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. I 8th Intemational Intercomoarison 115-8C CaSOg Dy Jan,1986 Field, Site 1 32.210.7 29.7 1.5 28.9 12.4 Cards I A2-2 I i
rg l Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). I. I 1 mR Lab Teledyne Results Code TLD Type Known Average i2 Sigma Date Measurement i 2 Sigma Value 2 Sigma (All Participants) 115-8C CaSO.: Dy Jan,1986 Field, Site 2 10.610.6 10.4 i 0.5 10.1 9.0 Cards 115-8C CaSO : Dy Jan,1986 Lab, Cs-137 18.110.8 17.210.9 16.2 i 6.8 Cards l E Eighth Intemational Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. 9th International Intercomoarison 115-9 The Ninth Intemational Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory. 1Qth International Intercomnarison 115-10A LiF-100 Chips Aug,1993 Field 25.7 i 1.4 27.0 i 1.6 26.4 i 10.2 115-10A LiF-100 Chips Aug,1993 12b,1 22.7i l.6 25.911.3 25.0 i 9.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.7 i 2.6 72.7 t l.9 69.8 20.3 The Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho Stat g University and sponsored by the U.S. Department of Energy and the Idaho Stat University. E 10th International Intercomnarison 115-10B CaSO : Dy Aug,1993 Field 26.0 i 2.3 27.0 1.6 26.4 i 10.2 = Cards 115-10B - CaSOpDy Aug,1993
- 12b,1 24.1 i 1.7 25.9 i 1.3 25.0 i 9.4 Cards l 115-10B E
CaSO.: Dy Aug,1993 Lab,2 69.213.0 72.711.9 69.8 i 20.3 Cards The Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho Stat University and sponsored by the U.S. Department of Energy and the Idaho Stat University. Teledyne Testing 89-1 LiF-100 Chips Sep,1989 Lab 21.010.4 22.4 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in September,1989. Ieledvne Testing 89-2 Teledyne Nov,1989 Lab 20.9i l.0 20.3 ND CaSo.: Dy g Cards B' ' ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in June,1990. sl
=
Table A-2. Crosscheck program results; nermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value 2 Sigma (All Participants) Teledvne Testing 90-1 Teledyne Jun,1990 Lab 20.6 1.4 19.6 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. Teledyne Testing 90-2 Teledyne Jun,1990 Lab 100.8 i 4.3 100.0 ND CaSo.: Dy I Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990. Teledyne Testing 91 1 Teledyne Oct,1990 Lab,1 33.4 i 2.0 32.0 ND I 91-1 Caso.: Dy Cards Teledyne Oct,1990 Lab,2 55.2 4.7 58.8 ND CaSo.: Dy Cards 91-1 Teledyne Oct,1990 Lab,3 87.8i 6.2 85.5 ND Caso.: Dy I Cards ND = No Data; Teledyne Testing was only performed by Teledyne. I 92-1 Cerds were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teledvne Testine LiF-100 Chips Feb,1992 Lab,1 11.1 0.2 10.7 ND 92-1 LiF-100 Chips Feb,1992 Lab,2 25.610.5 25.4 ND 92-1 LiF-100 Chips Feb,1992 Lab,3 46.410.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992. Teledyne Testin_c 92-2 Teledyne Apr,1992 Reader 1, #1 20.l i 0.1 ND I CaSo.: Dy Cards 20.1 92-2 Teledyne Apr,1992 Reader 1, #2 40.610.1 40.0 ND I CaSo.: Dy Cards I tg A24
E O Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value
- 2 Sigma (All Participants) 92-2 Teledyne Apr,1992 Reader 1, #3 60.0 1.3 E
60.3 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #1 20.3 i 0.3 20.1 ND CaSo.: Dy Cards , 92-2 Teledyne Apr,1992 Reader 2, #2 39.2 i 0.3 40.0 ND l CaSo.: Dy i Cards 92-2 Teledyne Apr,1992 Reader 2, #3 60.7 0.4 60.3 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in April,1992. Teledyne Testing g 93 1 Teledyne Mar,1993 Lab,1 10.011.0 10.2 ND E LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,2 25.2 i 2.2 25.5 ND E LiF-100 Chips E , 93-1 Teledyne Mar,1993 Lab,3 42.715.7 45.9 ND LiF-100 Chips E ND = No Data; Teledyne Testing was only performed by Teledyne. E Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1993. Due to a potential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is 3 available upon request. l l Teledvne Testing 94-1 Teledyne Nov,1994 Lab,1 15.6 i 0.4 14.9 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,2 30.210.4 29.8 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,3 59.210.3 59.7 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Reader 1, #1 14.910.1 14.9 ND g CaSo.: Dy g Cards 94-1 Teledyne Nov,1994 Reader 1, #2 30.8 i 0.1 29.8 ND g CaSo.: Dy g Cards A2-5
Table A 2. Crosscheck program results; 7hermoluminescent Dosimeters. (TLDs). l mR W 1.ab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement i 2 Sir.ma Value i 2 Sigma (All Participants) h E 94-1 Teledyne Nov,1994 Reader 1, #3 58.910.?, 59.7 ND CaSo.: Dy Cards I 94 1 Teledyne CaSo.: Dy Cards Nov,1994 Reader 2, #1 15.4 0.2 14.9 ND
%1 Teledyne Nov,1994 Reader 2, #2 31.4 i 0.2 29.8 ND CaSo.: Dy Cards I 94-1 Teledyne CaSo.: Dy Cards Nov,1994 Reader 2, #3 60.1 0.3 59.7 ND I ND = No Data; Teledyne Testing was only performed by Teledyne.
Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in November,1994. I I~' I - I I I I I
'I ^2-e I -
OI E Table A-3. In-house " spike" samples. Concentration in pCi/I,' Lab Sample Date l Teledyne Results Known ' Code Type Collected Analysis Control' 2s, n=16 Activity Limits SPW-4821 WATER Jan,1994 Ce-144 2593.1 1 54.9 2692.5 1615.5 - 2 % 1.8 < SPW-4822 WATER Jan,1994 Ce-144 1705.1 1 48.1 1749.8 1049.9 - 1924.8 SPW-4823 WATER Jan,1994 Ce-144 55.4117.5 49.0 29.4 - 59.0 SPW-4825 WATER Jan,1994 Gr. Alph; 34.4 i 1.6 41.7 20/> - 62.6 SPW-4825 WATER Jan,1994 Gr. Beta 33.6 i 1.2 30.2 20.2 - 40.2 SPW-4826 WATER Jan,1994 Gr. Alpha 66.812.1 83.4 41.7- 125.1 SPW-4826 WATER Jan,1994 Gr. Beta 63.8i l.5 60.4 50.4 - 70.4 SPMl-4848 MILK Jan,1994 Cs-134 27.2 i 5.7 31.7 21.7 - 41.7 SPMI-4848 MILK Jan,1994 C3-137 34.6 8.2 34.8 24.8 44.8 SPMI-4848 MILK Jan,1994 Sr-89 28.2 i 3.8 35.0 25.0 - 45.0 SPM1-4848 MILK Jan,1994 Sr-90 E 41.211.2 40.7 32.6 - 48.8 SPMI-4849 MILK Jan,1994 Sr-89 E 9.5 i 1.6 11.9 1.9 - 21.9 SPMI-4849 MILK Jan,1994 Sr-90 19.4 i 0.8 20.1 10.1 - 30.1 SPMI-4862 MILK Jan,1994 Cs-134 328.3 i 16.3 338.0 304.2 - 371.8 SPMI-4862 MILK Jan,1994 Cs-137 1019.5 1 18.3 1114.4 1003.0 - 1225.8 SPAP-4953 AIR FILTER Jan,1994 Gr. Beta 4.8 0.1 4.2 0.0 - 14.2 SPAP-4954 AIR FILTER Jan,1991 Cs-137 1.4 0.1 1.3 0.8 - 1.8 SPW-4955 WATER Jan,1994 H-3 17080.0 i 364.0 17163.0 13730.4 - 20595.6 SPW-4956 WATER Jan,1994 Co-60 1514.0 i 46.2 1545.0 1390.5 - 1699.5 SPW-4956 WATER Jan,1994 Cs-134 433.7 25.5 479.0 431.1 - 526.9 SPW-4956 WATER Jan,1994 Cs-137 742.7 i 45.9 73 2.0 658.8 - 805.2 C SPCH-4928 gL Feb,1994 I-131(g) 1449.9 i 65.1 1452.8 871.7 - 1598.1 SPW-4934 WATER Feb,1994 I-131 76,4 t l.4 90.8 72.6 - 109.0 SPW-4934 WATER Feb,1994 I-131(g) 90.217.6 90.8 S4.5 - 100.8 SPMI-4935 MILK Feb,1994 I-131 40.4 1.0 43.6 31.6 - 55.6 SPM1-4935 MILK Feb,1994 I-131(g) 41.816.7 43.6 g 26.2 - 53.6 E SPBS-5102 SEDIMENT Mar,1994 H-3 97.211.0 105.4 0.0 - 630.0 SPW-5146 WATER Mar,1994 Sr-89 25.513.9 26.4 16.4 - 36.4 SPW-5146 WATER Mar,1994 Sr-90 16.211.1 18.8 8.8 - 28.8 SPW-646 WATER Apt,1994 H-3 9847.8 1 294.9 9855.0 7884.0 - 11826.0 SPW-648 WATER Apr,1994 Co40 21.6 6.6 22.6 g 12.6 - 32.6 3 SPW-648 WATER Apr,1994 Cs-134 33.318.5 33.6 23.6 - 43.6 SPW-648 WATER Apr,1994 Cs-137 37.619.8 36.3 26.3 - 46.3 SPMI-650 MILK Apr,1994 Cs-134 52.015.3 50.6 40.6 - 60.6 A3-1 I 5 as
I I l l Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Code Known Controf Type Collected Analysis 2s, n=1' Activity Limits MILK 'I SPMI-650 SPW-652 WATER Apr,1994 Cs-137 Apr,1994 Gr. Alpha 61.618.3 44.8 1.2 54.5 41.6 44.5 - 64.5 20.8 - 62.4 SPW-652 WATER Apr,1994 Gr. Beta 24.1 i 1.0 25.4 15.4 - 35.4 SPAP-654 AIR FILTER Apr,1994 Cs-137 1.310.1 1.3 0.8 - 1.8 SPW-974 WATER May,1994 Fe-55 56.7 i 12.0 58.5 38.5 - 78.5 I SPF 1023 5PBS-1024 FISH UELLO) May,1994 Cs-137 SEDIMENT May,1994 Cs-137 6.9i0.1 6.2 i 0.1 6.8 6.0 0.0 - 16.8 0.0 - 16.0 SPW-1850 WATER Jun,1994 I-131 46.010.7 51.8 39.8 - 63.8 SPW 1850 WATER Jun,1994 I-131(g) 50.918.3 51.8 31.1 - 61.8 SPMI 1851 MILK Jun,1994 I-131 51.7i 0.6 51.8 39.8 - 63.8 SPMI-1851 MILK Jun,1994 I-131(g) 51.3 i 10.8 51.8 31.1 - 61.8 SPVE-1854 V N Jun,1994 I-131(g) 0.9i0.1 1.0 0.6 - 1.4 SPCH-1855 C AL Jun,1994 I-131(g) R 1.910.1 1.8 1.1 - 2.5 SPW-3278 WATER Jun,1994 Gr. Alpha 20.811.1 23.4 11.7 - 35.1 SPW-3278 WATER Jun,1994 Gr. Beta 29.5 i 1.1 31.8 21.8 - 41.8 SPW-3276 WATER Jul,1994 H-3 24504.6 421.7 25019.0 20015.2 - 30022.8 SPMI-3282 MILK Jul,1994 Sr-89 16.4 4.8 22.5 12.5 - 32.5 SPMI-3282 MILK Jul,1994 Sr-90 25.311.4 25.4 15.4 - 35.4 SPW-3284 WATER Jul,1994 Cs-137 240.8 i 19.3 221.5 199.4 - 243.7 SPAP 3388 AIR FILTER Jul,1994 Gr. Beta 7.9i0.1 8.3 0.0 - 18.3 SPAP-3390 AIR FILTER Jul,1994 Cs-137 1.310.1 1.3 0.b - 1.8 SPF-3603 FISH GELLO) Jul,1994 Cs-137 8.311.3 8.5 0.0- 18.5 I SPW-5549 SPW 5549 WATER WATER Oct,1994 I-131 Oct,1994 I-131(g) 77.4 0.9 85.5i9.5 79.9 79.9 63.9 - 95.9 47.9 - 89.9 SPMI-5550 MILK Oct,1994 Cs-134 35.0 i 6.0 36.4 26.4 - 46 4 SPMI-5550 MILK Oct,1994 Cs-137 46.l i 9.4 44.1 34.1 - 54.1 SPMI-5550 MILK Oct,1994 I-131 65.2 0.9 63.9 51.1 - 76.7 I SPMI-5550 SPW-5594 MILK WATER Oct,1994 1-131(g) Oct,1994 I-131 68.4 11.1 92.511.0 63.9 95.8 38.3 - 73 9 76.6 - 115 0 SPW-5594 WATER Oct,1994 I-131(g) 98.2 10.1 I SPVE-6067 SPS-5946 VEGETATION Oct,1994 I-131(g) (SAWDUST) SEDIMENT 1.7i 0.1 95.8 1.6 57.5 - 105 8 1.0 - 2.2 Oct,1994 Cs-134 0.3 24.2 0.3 I SPF-6208 (BOTTOM) FISH UELLO) Oct,1994 Cs-137 11.6 i 0.1 12.1 0.2 - 0.5 2.1 - 22.1 A3-2
E,
=4 Table A-3. In house " spike" samples.
Concentration in pCi/If Lab Sample Date Teledyne Results Known Control' Co8e Type Collected Analysis 2s, n=1" Activity Limits SPW-6955 WATER Nov,1994 Ni-63 1851.6 34.3 1931.0 1158.6 - 2703.4 SPW-6994 WATER Nov,1994 Tc-99 63.2 7.8 66.0 46.2 - 85.7 SPW-7440 WATER Nov,1994 H 3 24099.2 423.9 24260.0 19408.0 - 29112.0 SPAP-7507 AIR FILTER - Nov,1994 Cs-137 2.2 0.0 1.9 1.2 - 2.7 I I I A3-3 I
Table A-4. In-house " blank" samples. Concentration pCi/L'. I Lab Code Sample Type
. Sample Da te Analysis LLD Teledyne Results (4.66 Sigma)
Activity
- Acceptance Criteria (4.66 Sigma)
SPW-4820 WATER Jan 1994 Cs-134 < 1.9 -1.76 i 7.24 < 10.0 SPW-4820 WATER Jan 1994 Cs-137 <4.4 -0.3112.67 < 10.0 SPW-4824 WATER Jan 1994 Gr. Alpha <0.3 0.0010.20 < 1.0 SPW-4824 WATER Jan 1994 Gr. Beta <0.9 0.4010.59 < 3.2 SPW-4827 WATER Jan 1994 Co-60 < 1.8 1.1011.04 < 10.0 SPW-4827 WATER Jan 1994 Cs-134 < 1.9 0.5116.76 < 10.0 SPW-4827 WATER Jan 1994 Cs-1~,7 < 2.0 0.4310.84 < 10.0 SPW-4827 WATER Jan 1994 Gr. Alpha <0.4 0.12 i 0.25 < 1.0 SPW-4827 WATER Jan 1994 Gr. Beta <0.8 0.21 0.55 < 3.2 SPW-4827 WATER Jan 1994 H-3 <192.0 133.90 i 101.00 < 200.0 SPW-4827 WATER Jan 1994 I-131 <0.3 -0.12 0.14 <0.5 SPMI-4846 MILK Jan 1994 Co-60 <3.6 0.6212.67 < 10.0 SPMI-4846 MILK Jan 1994 Cs-134 <5.4 0.52 i 3.83 < 10.0 SPMI-4846 MILK Jan 1994 Cs-137 <3.4 -0.74 i 2.93 < 10.0 SPMI-4846 MILK Jan 1994 I-131 <0.5 0.2710.34 <0.5 I SPMI-4846 SPMI-4846 MILK MILK Jan 1994 Sr-89 Jan 1994 St-90
<0.5 N/A
-0.5410.79 1.9310.44
< 5.0
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPAP-4950 AIR FILTER Jan 1994 Co-60 <2.2 -2.61 i 2.19 < 10.0 SPAP-4950 AIR FILTER Jan 1994 Cs-134 <3.1 -0.31 i 3.65 < 10.0 g SPAP-4950 AIR FILTER Jan 1994 Cs-137 <2.9 2.78 i 23.94 < 10.0 E SPAP-4952 AIR FILTER Jan 1994 Gr. Beta <0.9 0.0010.58 < 3.2 SPCH-4951 CHARCOAL Feb 1994 I-131(g) <7.0 0.6414.80 < 9.6 CANISTER SPW-5054 WATER Mar 1994 Ra-226 <0.1 0.01 0.03 < 1.0 SPW-5054 WATER Mar 1994 Ra-228 < 1.0 0.54 i 0.67 < 1.0 SPBS-5101 SEDIMENT Mar 1994 Co40 <5.9 -0.19 i 1.63 < 10.0 SPBS-5101 SEDIMENT Mar 1994 Cs-134 <6.2 -31.20 i 13.10 < 10.0 SPBS-5101 SEDIMENT Mar 1994 Cs-137 <4.4 -0.26 i 2.75 < 10.0 SPW-647 WATER Apr1994 Co40 <5.8 0.56 i 0.53 < 10.0 SPW-647 WATER Apr 1994 Cs-134 <3.4 0.86 i 0.72 < 10.0 SPW-647 WATER Apr1994 Cs-137 <5.1 2.6512.75 < 10.0 SPW-647 WATER Apr 1994 H-3 <191.5 148.40 i 100.90 < 200.0 SPW-647 WATER Apr1994 I-131 <0.5 -0.34 0.22 ,I SPMI-649 MILK Apr 1994 Co-60 <6.5 0.55 1.39
<0.5
< 10.0 A4-1 I
L - - - -- - - -
E_ m - Table A-4. In-house " blank" samples. Concentration pCi/L'. Teledyne Results Acceptance Lab Sample . Sample (4.66 Sigma) Code Type Criteria Date Analysis LLD Activity * (4.66 Sigma) l SPMI-649 MILK Apr1994 Cs-134 <3.4 -3.4515.60 < 10.0 ! SPMI-649 MILK Apr 1994 Cs-137 <4.6 0.59 i 3.98 < 10.0 SPMI-649 MILK Apr 1994 I 131 <0.5 -0.11 i 0.19 <0.5 SPW-651 WATER Apr1994 Gr. Alpha <0.4 0.14 i 0.25 < 1.0 SPW-651 WATER Apr 1994 Gr. Beta <0.8 0.12 i 0.54 <3.2 SPAP-653 AIR FILTER Apr1994 Cs-134 <2.1 -0.1210.18 < 10.0 SPAP-653 AIR FILTER Apr 1994 Cs-137
<3.4 1.05 i 1.55 < 10.0 SPCH-654 CHARCOAL Apr 1994 I-131(g) < 6.1 0.9613.84 < 9.6 CANISTER SPAP-4956 AIR FILTER Apr 1994 Gr. Beta < 1.0 0.3210.96 <3.2 SPW-974 WATER May 1994 Fe-55 <0.8 0.10 0.47 g
< 1000.0 5 SPF-1022 FISH (JELLO) May 1994 Cs-134 <9.2 12.70 i 31.70 s SPF-1022 FISH (JELLO) May 1994 Cs-137 <10.0 27.30 iT ' 30 < 10.0 SPW-1075 WATER May 1994 Ra-226 <0.1 0.0110.04 <1.0 SPBS-3254 SEDIMENT May 1994 Co-60 <5.8 5.93 i 8.06 < 10.0 SPBS-3254 SEDIMENT May 1994 Cs-134 <2.0 5.67 6.69 g
< 10.0 g SPBS-3254 SEDIMENT May 1994 Cs-137 <5.0 -2.11 4.69 < 10.0 SPVE-1852 VEGETATION Jun1994 Cs-134 <5.4 -1.47 i 2.14 < 10.0 E (SAWDUST) 5 SPVE-1852 VEGETATION Jun1994 Cs-137 <6.6 2.12 i 3.44 < 10.0 (SAWDUST)
SPVE-1852 VEGETATION Jun1994 I-131(g) <5.6 -0.73 i 1.08 < 20.0 (SAWDUST) SPW-3277 WATER Jun1994 Gr. Alpha <0.3 0.10 i 0.22 < 1.0 SPW-3277 WATER Jun1994 Gr. Beta <0.8 0.1410.54 < 3.2 SPW-3275 WATER Jul1994 H-3 <154.9 22.81 i 77.81 < 200.0 SPMI-3281 MILK Jul1994 Co-60 <3.6 g 0.87 2.22 < 10.0 E SPMI-3281 MILK Jul 1994 Cs-134 <2.3 -0.45 2.61 < 10.0 SPMI-3281 MILK Jul1994 Cs-137 <4.2 0.0712.28 < 10.0 SPMI-3281 MILK Jul1994 I-131 <0.2 0.1010.16 <0.5 SPMI-3281 MILK Jul1994 Sr-89 <0.9 -0.5411.32 < 5.0 SPMI-3281 MILK Jul1994 Sr-90 N/A 2.29 0.56 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPW-3283 WATER Jul1994 Co-60 <2.2 -3.09 3.52 < 10.0 SPW-3283 WATER Jul1994 Cs-134 <5.4 0.79 i 3.13 < 10.0 A4-2 I
I Table A-4. In-house " blank" samples. Concentration pCi/L*. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma) SPW 3283 WATER Jul1994 Cs-137 <5.0 -0.10 3.05 < 10.0 SPW-3283 WATER Jul1994 I-131 <0.4 0.14 0.22 <0.5 SPAP-3389 AIR FILTER Jul1994 Gr. Beta <0.2 0.16 i 0.26 < 3.2 SPAP-3391 AIR FILTER Jul 1994 Cc@ < 1. 7 -0.74 il.44 < 10.0 SPAP-3391 AIR FILTER Jul1994 Cs-134 <2.3 0.9514.86 < 10.0 l SPAP-3391 AIR FILTER Jul1994 Cs-137 < 4.1 -3.0313.15 < 10.0 SPF-3602 FISH (JELLO) Jul1994 Co 60 <3.6 -4.45 i 4.27 < 10.0 I SPF-3602 SPF-3602 FISH (JELLO) Jul1994 FISH (JELLO) Jul1994 Cs-137 Cs-134 <4.1
<4.7
-3.91 i 5.63
-5.17 5I
< 10.0
< 10.0 SPMI-5551 MILK Oct 1994 Cs-134 <4.3 0.90 3.34 < 10.0 SPMI-5551 MILK Oct 1994 Cs-137 < 4.1 -0.55 i 3.43 < 10.0 SPMI-5551 MILK Oct 1994 I-131 <0.2 -0.0310.16 <0.5 SPSO-5947 SOIL Oct 1994 Cs-134 <2.3 -4.8414.84 < 10.0 l SPSO-5947 SOIL Oct 1994 Cs-137 <6.4 -0.50 i 4.71 < 10.0 SPW-6995 WATER Nov 1994 Tc-99 <4.2 1.24 i 2.19 < 10.0 l SPW-7441 WATER Nov 1994 H-3 <169.0 -74.64 i 80.48 < 200.0 f SPW 7442 WATER Nov 1994 H-3 <169.0 -37.02 i 82.14 < 200.0 SPAP-7506 AIR FILTER Nov 1994 Cc4 <2.1 0.17 t 1.63 < 10.0 SPAP-7506 AIR FILTER Nov 1994 Cs-134 < 1.6 -1.0811.70 < 10.0 SPAP-7506 AIR FILTER Nov 1994 Cs-137 <3.0 -0.55 i 1.65 < 10.0 o Liquid sample results are reported in pCi. Liter, air filter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.
I
- The activity reported is the net activity result.
l l A4-3
O G Table A 5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Codes
- Date Analysis Averaged Result Result WATER-4607, 4608 Result Jan,1994 Gr. Beta 1.3510.70 MILK-166,167 1.3810.70 1.37 t 0.49 Jan,1994 Co-60 1.4213.73 MILK 166,167 -1.13 i 4.25 0.15 i 2.83 Jan,1994 Cs-137 -0.26 i 3.42 -0.65 t 2.61 -0.4612.15 MILK-166,167 Jan,1994 I-131(G) -0.1010.22 0.2210.22 g
WATER-4711,4712 Jan,1994 Gr. Beta 0.06 i 0.16 g 1.70 i 0.60 1.8010.60 MILK-187,188 Jan,1994 1.75 i 0.42 CcH4 0.05 t 2.88 -1.4313.35 MILK-187,188 Jan,1994 Cs-137 0.16 t l.87 1.8612.61
-0.6912.21 g MILK-187,188 Jan,1994 1-131 1.0111.61 E 0.16 0.18 0.1310.23 WATER-4664, 4665 Jan,1994 Gr. Beta 0.15 0.15 8.80 i 1.80 4.4011.40 6.60 i 1.14 A review of the raw data revealed no errors or discrepancies. The sample was reanalyzed. The result ofE Ethe reanalysis was 6.611.5 pCi/L. No further action is planned. ~ WATER-4664, 4665 Jan,1994 H-3 92.98 i 95.90 37.19 i 93.63 WATER-4687,4688 Jan,1994 Gr. Alpha 1.57 t l.48 0.0011.19 65.09 67.01 g WATER-4687,4688 Jan,1994 Gr. Beta 0.7910.95 E 3.23 i 0.82 2.5110.79 WATER-4687, 4688 Jan,1994 2.87 i 0.57 H-3 171.80 t 98.99 183.40 i 99.44 WATER-4741,4742 177.60 1 70.16 Jan,1994 H-3 105.00 1 101.00 127.00 i 102.00 E
MILK-208,209 Jan,1994 116.00 i 71.77 E K-40 1,396.00 i 148.00 1,586.00 i 162.00 MILK 208,209 1,491.00 i 109.71 Jan,1994 St-90 2.96 0.56 3.58 i 0.68 3.27 i 0.44 WATER-4830,4831 Jan,1994 H3 73.80t 89.38 79.33 89.60
. WATER-4865, 4866 76.57 1 63.28 Jan,1994 Gr. Beta 1.93 i 0.19 WATER-5052, 5053 1.94i0.18 1.9410.13 Jan,1994 Gr. Beta 2.20 i 0.55 2.58 i 0.56 2.3910.39 WATER-4890,4891 Jan,1994 H3 l 421.90 1 109.00 454.80 i 106.60 =
WATER-4919, 4920 Jan,1994 Gr. Beta 438.35 76.23 2.8010.80 3.4010.80 3.1010.57 WATER-4952,4953 Feb,1994 Gr. Beta 2.6610.55 2.14 i 0.52 2.4010.38 WATER-5010,5011 Feb,1994 H-3 142.00 1 99.00 119.00 i 98.00 MILK-250,251 130.50 1 69.65 Feb,1994 K-40 1,087.00 i 77.00 1,036.00t 98.00 MILK-250,251 1,061.50 i 62.32 Feb,1994 Sr-90 3.68 i 0.62 ' 4.0910.61 3.89 i 0.43 MILK-271,272 Feb,1994 K-40 1,510.00 i 90.00 1,520.00 i 110.00 1,515.00 1 71.06 WATER-4978, 4979 Feb,1994 H-3 83.75 i 96.98 69.80 i 96.41 76.78 68.37 MILK-229, 230 Feb,1994 Co-60 -1.48 i 4.16 -1.60 5.54 -1.54 3.46 l MILK-229,230 Feb,1994 Cs-137 -0.6713.05 -1.96 i 3.72 -1.32 2.41 MILK-229,230 Feb,1994 I131 0.17 0.24 0.1010.17 0.14 0.15 WATER-5081,5082 Feb,1994 H-3 28.00 95.00 72.00 1 96.00 50.00. 67.53 WATER-5124, 5125 Feb,1994 H-3 465.80 i 113.65 358.00 1 109.80 411.90 1 79.01 WATER-5212,5213 Feb,1994 Gr. Beta i 2.8610.67 2.22 i 0.59 2.54 0.45 WATER-5183, 5184 Feb,1994 Co-60 1.46i l.64 -0.7012.04 0.38 1.31 WATER-5183, 5184 Feb,1994 Cs-137 ) 0.33 i 1.63 0.3712.05 0.35 1.31 WATER-5183,5184 Feb,1994 Gr. Beta 4.92 1.09 4.5211.07 4.72 0.76 MILK-292, 293 Mar,1994 K-40 1,377.00 85.00 1,364.00 1 100.00 1,370.50 65.62 MILK-292,293 Mar,1994 Sr-90 1.20 i 0.38 1.49i0.41 1.35 0.28 MILK-5246. 3.'.47 Mar,1994 Gr. Beta 6.54 0.83 6.42 i 0.88 6.48 0.60 AS-1 l ,
Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lob 5arnple First Second Avetaged Codes
- Date Analysis Result Result Result WATER-5270, 5271 Mar,1994 Gr. Beta 3.2810.98 2.84 i 0.96 I WATER 5293,5294 3.06 i 0.69 Mar,1994 H-3 620.18 i 118.74 582.33 i 117.46 601.26 i 83.51 MILK-313,314 Mar,1994 I-131(G) 1.261 47.70 -0.30 i 0.78 0.48 1 23.85 Mar,1994 K-40 1,392.00 95.00 1,437.00 i 115.00 1,414.50 i 74.58 I MILK-334,335 WATER 5400,5401 Mar,1994 H-3 77.70 i 97.20 66.76 i 96.54 72.23 i 68.50 WATER 5485,5486 Mar,1994 H-3 336.00 1 107.00 272.00 1 105.00 304.00 t 74.96 WATER-5446, 5447 Mar,1994 Co-60 1.84 i 4.35 0.07i 0.45 0.96 2.19 WATER-5446, 5447 Mar,1994 Cs-137 0.68 i 1.61 1.0111.91 0.85 i 1.25 WATER-5446,5447 Mar,1994 Gr. Beta 3.84 t 1.25 3.72 i 1.25 3.78 0.88 WATER-5510, 5511 Mar,1994 H-3 396.00 i 89.00 458.51 113.14 427.26 1 71.98 WATER-5538, 5539 Mar,1994 Gr. Beta 2.58 0.62 2.0210.60 2.30 0.43 WATER-5593, 5594 Mar,1994 H-3 139.87 1 101.14 169.37 i 101.75 154.62 71.73 WATER-5614,5615 Mar,1994 Co-60 0.36 i 1.04 0.22 i 2.15 0.29 1.19 WATER-5614,5615 Mar,1994 Cs-137 0.90 i 3.78 -0.39 i 2.59 0.26 t 2.29 WATER-5566, 5567 Mar,1994 Gr. Beta 2.76 0.50 2.20 i 0.48 2.48 i 0.35 WATER 72,73 Mar,1994 Gr. Beta 1.5810.50 1.4610.48 1.5210.35 WATER-49, 50 Apr,1994 Gr. Deta 3.4310.92 3.43 0.92 3.4310.65 WATER-102,103 Apr,1994 Gr. Beta 2.02 i 0.50 2.05 i 0.47 2.04 i 0.34 NATER-102,103 Apr,1994 H-3 165.00 1 102.00 79.00 1 98.00 122.00 70.72 t
WATER-187,188 Apr,1994 Gr, Beta 3.3810.66 3.1910.64 3.29 0.46 MILK-246,247 Apr,1994 Co-60 1.75 i 1.61 1.76 i 1.61 1.76 1.14 MILK-246, 247 Apr,1994 Cs-137 0.10 i 1.86 0.1011.86 0.1011.32 MILK-246, 247 Apr,1994 1-131 0.07 i 0.23 l 0.15 0.34 0.11 0.21 WATER-257,258 Apr,1994 Gr. Beta 3.2810.74 3.2810.79 3.28 0.54
; WATER-267,268 Apr,1994 Cs-137 0.19 2.69 1.2212.18 0.71 1.73 WATER-281, 282 Apr,1994 Gr. Beta 15.73 1 2.02 30.38 1 2.60 23.06 1.65 A review of the raw data revealed no errors or discrepancies. Both samples were recounted. He results of the
-I recounts were in agreement with the initial results. The sample was reanalyzed. He result of the reanalysis was 30.712.1 pCi/L No further action is planned. WATER-281,282 Apt,1994 H-3 381,181.00 1 1,740.00 378,406.00 1,733.00 379,793.50 1,227.89 WATER-454, 455 Apr,1994 Gr. Beta 3.3412.10 3.67 2.20 3.5111.52 WATER-405, 406 Apr,1994 H3 65.90 1 98.21 61.95 1 98.05 63.93 1 69.39 MILK-464,465 Apr,1994 K-40 1,630.00 i 130.00 1,589.00 1 162.00 1,609.50 103.86 I WATER-516,517 Apr,1994 H-3 37.601 94.95 69.26 1 95.77 53.43 1 67.43 WATER-267, 268 Apr,1994 Cs-137 0.1912.69 1.2212.18 0.71 1.73 g WATER-616,617 Apr,1994 Gr. Beta 2.5010.52 3.04 i 0.55 2.7710.38 lg WATER-616,617 Apr,1994 H-3 193.00 i 102.00 203.001 103.00 198.00 72.48 WATER-739, 740 Apr,1994 Co-60 0.84 i 11.40 0.3110.43 0.5815.70 E WATER 739,740 Apr,1994 Cs-137 -0.3013.59 0.77 3.23 0.24 2.41 g WATER-739,740 Apr,1994 Cs-137 -0.3013.59 0.7713.23 0.24 2 41 IATER-697, 698 Apr,1994 Co-60 3.41 4.36 2.0512.79 2.73 2.59 E A5-2 o
E Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes6 Date Analysis Result Result Result WATER-697, 698 Apr,1994 Gr. Beta 2.93 i 0.98 3.0910.78 WATER-1003,1004 3.0110.63 May,1994 Gr. Beta 2.77 i 0.29 2.57 i 0.34 WATER-796, 797 2.67 i 0.22 May,1994 Gr. Beta 1.66 i 0.47 2.13 i 0.48 WATER-931,932 May,1994 H-3 531.26 i 109.73 554.52 i 110.55 1.9010.34 g WATER-893, 894 May,1994 Co-60 -1.45 i 4.08 542.89 1 77.88 g 1.27 i 3.23 -0.0912.60 WATER-893,894 May,1994 Cs-137 0.85 2.25 1.46 i 3.09 WATER-893, 894 May,1994 Gr. Beta 1.34 i 1.85 -0.22 i 1.75 1.16 i 1,91 g WATER-893, 894 May,1994 H-3 0.56 i 1.27 E 158.96 i 95.60 118.25 i 93.99 MILK-900,901 138.61 67.03 May,1994 Co-60 -2.76 i 2.98 -1.74 i 6.09 MILK-900,901 May,1994 Cs-137 -0.14 i 1.31
-2.2513.39 g 0.54 i 1.67 0.20 i 1.06 E MILK-900,901 May,1994 I-131 0.10 i 0.17 0.1110.19 MILK 1001,1002 0.11 i 0.13 May,1994 K-40 1,250.00 180.00 1,370.00 i 140.00 1,310.00 1 114.02 WATER-1171,1172 May,1994 Gr. Beta 9.6912.01 7.49 i 2.21 8.5911.49 WATER-1171,1172 May,1994 H-3 950.00 i 108.00 1,012.00 i 109.00 MILK-1214,1215 981.00 t 76.72 May,1994 CM) 0.72 2.41 0.21 i 0.58 MILK-1214,1215 0.4711.24 May,1994 Cs-137 -0.42 1.47 1.42 i 1.82 MILK-1214,1215 0.50 i 1.17 May,1994 I-131 0.10 i 0.19 0.06 i 0.17 WATER-1565,1566 0.08 i 0.13 May,1994 Gr. Beta 2.63 i 0.88 2.6110.91 WATER-1399,1400 2.62 0.63 May,1994 Gr. Beta 5.9710.67 5.46 i 0.65 MILK-1301,1302 5.72 0.47 May,1994 I-131(G) -0.1010.18 0.0010.18 SEDIMENTS-1550,1551 -0.05 0.13 May,1994 Gr. Beta 2.1010.10 2.1510.10 WATER-1545,1546 2.13 0.07 l May,1994 Gr. Beta 6.63 i 0.62 5.38 i 0.63 6.0110.44 WATER-1670,1671 May,1994 Co-60 -0.33 i 0.55 1.3512.44 0.51 i 1.25 WATER-1670,1671 May,1994 Cs-137 1.73 t 2.95 -1.73 t 2.64 0.00 i 1.98 MILK-1510,1511 May,1994 I-131(G) 0.08 i 0.13 -0.07 i 0.12 0.0110.09 WATER-1520,1521 May,1994 H3 48.44 i 97.26 79.87 i 98.52 64.16 69.22 MILK-1744,1745 Jun,1994 1-131 0.90 i 0.15 0.1010.15 0.5010.11 WATER-1786,1787 Jun,1994 Gr. Beta 31.36 i 3.13 31.37 2.98 31.37 i 2.16 WATER-1786,1787 Jun,1994 H3 236,078.00 i 1,364.00 235,776.00 1 1,363.00 235,927.00 1 964.14 WATER-1843,1844 Jun,1994 Co-60 1.25 i 1.03 0.48 i 2.23 0.87 1.23 WATER-1843,1844 Jun,1994 Cs-137 -0.02 i l.10 1.0211.79 0.5011.05 l WATER-1843,1844 Jun,1994 H-3 138.74 1 79.60 69.64 i 76.69 104.19 t 55.27
! MILK-1818,1819 Jun,1994 Co40 E
-1.28 i 3.11 0.1614.48 MILK-1818,1819 Jun,1994 Cs-137
-0.56 t 2.73 g 0.3412.27 1.9213.45 1.1312.06 MILK-1818,1819 Jun,1994 1-131(G) -0.1510.16 0.04 0.14 WATER-1882,1883 Jun,1994 Gr. Beta 5.0010.72 5.6110.77
-0.0610.11 g WATER-1882,1883 5.31 0.53 3 Jun,1994 H-3 -32.601 76.90 -55.80 i 76.90 -44.20i S4.38 GRASS-1900,1901 Jun,1994 Be-7
' 0.5110.08 0.4910.07 0.5010.05 GRASS-1900,1901 Jun,1994 K-40 4.31 i 0.17 4.28 0.17 E MILK-1982,1983 4.3010.12 3 Jun,1994 I-131 0.0010.23 0.08 i 0.13 0.04 0.13 MILK-1982,1983 Jun,1994 K-40 1,562.00 98.00 1,553.00 116.00 1,557.50 75.93 A5-3 1
I Table A-5. In-house " duplicate" samples. Concentration in pCi/L' i Lob Sample First Second Averaged Codes
- Date Analysis Result Result Result l
WATER-1972,1973 Jun,1994 Gr. Beta 25.66 1 2.41 23.67 i 2.33 24.67 i 1.68 ' MILK 2092,2093 Jun,1994 K-40 1,430.00 i 170.00 1,430.00 i 140.00 1,430.00 i 110.11 WATER-2116,2117 Jun,1994 C-14 -28.00 1 49.00 -9.00 1 52.00 -18.50 i 35.72 WATER-2116, 2117 Jun,1994 Gr. Alpha 0.60 i 0.50 1.1010.60 0.85 i 0.39 WATER-2116, 2117 Jun,1994 Gr. Beta 8.4010.80 7.20 i 0.70 7.80 i 0.53 WATER-2116, 2117 Jun,1994 H3 2,544.00 i 152.00 2,522.00 i 152.00 2,533.00 i 107.48 WATER-2116, 2117 Jun,1994 U-233/4 1.54 i 0.20 1.4610.19 1.50 i 0.14 WATER-2116, 2117 Jun,1994 U-235 0.0010.06 0.0010.06 0.00 i 0.04 WATER-2116, 2117 Jun,1994 U-238 0.91 i 0.16 1.0710.17 0.99 i 0.12 WATER-2198, 2199 Jun,1994 Gr. Beta 5.31 i 0.92 5.16i0.84 5.24 i 0.62 MILK-2156,2157 Jun,1994 Co-60 -0.51 i 3.05 1.51 3.95 0.5212.50 MILK-2156,2157 Jun,1994 Cs-137 1.27 3.59 1.16 i 5.91 1.22 i 3.46 MILK-2156,2157 Jun,1994 I-131(G) -0.0810.23 0.01 0.18 -0.0410.15 MILK-2194,2195 Jun,1994 I-131 0.1510.32 0.08 i 0.21 0.12 0.19 WATER-2238, 2239 Jun,1994 Gr. Beta 1.50 0.63 1.68 i 0.62 1.59 i 0.44 WATER-2363, 2364 Jun,1994 Gr. Beta 69.49 i 84.03 5.89 81.31 37.69 i 58.46 WATER-2336, 2337 Jun,1994 Gr. Beta 6.17 i 1.26 6.44 i 1.27 6.31 i 0.69 WATER-2336, 2337 Jun,1994 H-3 23.60 i 80.07 -20.93 i 78.21 1.34 55.96 SLIME-2480,2481 Jun,1994 Be-7 0.4110.20 0.40 i 0.17 0.4110.13 SLIME-2480,2481 Jun,1994 Cs-137 0.03 i 0.01 0.03 i 0.01 0.03 i 0.01 l g SLIME-2480,2481 Jun,1994 K-40 1.31 i 0.20 1.33 i 0.19 1.32 i 0.14 g MILK-2334,2335 Jun,1994 I-131 0.0610.17 0.04 i 0.20 0.0510.13 WATER-2733,2734 Jun,1994 Gr. Beta 1.98 0.45 1.5710.44 1.78 0.31 l WATER-3056,3057 Jun,1994 Sr-89 -0.64 i 1.05 -0.12 i 0.76 -0.3810.65, hrATER-3056, 3057 Jun,1994 Sr-90 0.47 i 0.36 0.28 i 0.25 0.38 i 0.22 l MILK-2405,2406 Jun,1994 K-40 1,730.00 i 190.00 1,710.00 i 120.00 1,720.00 1 112.36 WATER-2432, 2433 Jun,1994 H-3 26.85 81.89 123.15 1 85.91 75.00 1 59.34 WATER-3000, 3001 Jun,1994 H-3 213.55 1 86.19 192.43 i 85.32 202.99 i 60.64 WATER-2459, 2460 Jun,1994 Gr. Alpha 0.1210.20 0.0210.18 0.07 0.13 I WATER-2459,2460 WATER-2712, 2713 WATER-2501, 2502 Jun,1994 Jun,1994 Jun,1994 Gr. Beta H-3 H-3 2.26 i 0.15 260.00 1 90.00 70.00 80.00 2.03 0.17 170.00 i 80.00 137.00 i 80.00 2.15 0.11 215.00 60.21 103.50 1 56.57 WATER-2662, 2663 Jun.19M Gr. Beta 5.0110.89 5.53 0.88 5.27 0.63 WATER-2691, 2692 Jun,1994 Gr. Beta 2.41 i 0.52 2.1210.46 2.2710.35 WATER-2691, 2692 Jun,1994 H-3 192.56 87.03 108.28 83.56 150.42 i 60.33 # MILK-2522,2523 Jul,1994 Co40 5.7214.46 -3.2115.27 1.26 3.45 MILK-2522,2523 Jul,1994 Cs-137 0.22 i 3.28 2.03 i 3.29 1.13 2.32 MILK-2522,2523 Jul,1994 I-131(G) 0.08 0.20 0.0910.23 0.0910.15 WATER-2543, 2544 Jul,1994 Gr. Beta 1.13 0.31 1.11 0.44 1.1210.27 WATER-2543,2544 Jul,1994 K-40 1.2010.12 1.20 0.12 1.20 0.08 WATER-2631, 2632 Jul,1994 Gr. Alpha a.28 0.87 0.84 0.98 0.56 0.66
- AS-4
r- - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - _ _ _ _ O, D' Table A-5. In-house " duplicate" samples. I', Concentration in pCi/L' Lab Samp!: First Codes
- Second Averaged Ds4e Analysis Result WATER-2631, 2632 Result Result Jul,1994 Gr. Beta ;
8.0511.01 7.13 i 0.99 MILK 2863,2864 Jul,1994 7.5910.71 I-131 0.10 i 0.21 ! MILK-2863,2864 Jul,.1914 0.0310.20 0.07 i 0.15 K-40 1,360.00 i 130.00 1,450.00 1 100.00 l GRASS-2754,2755 1,405.00 t 82.01 Jul,1994 Be-7 2.1510.18 GRASS-2754,2755 2.18 i 0.08 2.1710.10 Jd 1994 K-40 7.29 i 0.35 : WATER-2775,2776 Jul,1994 6.93 i 0.16 7.1110.19 Co-60 -0.53 i 3.13 , 0.3013.26 WATER-2775,2776 WATER-2775,2776 Jul,1994 Cs-134 -0.76 i 3.35 -1.03 i 3.16
-0.1212.26 g' Jul,1994 Cs-137 1.9413.03
-0.90 i 2.30 g WATER 2775,2776 0.65 i 2.91 1.30 i 2.10 Jul,1994 Gr. Beta t 3.0310.52 2.9410.54 WATER-2775,2776 Jul,1994 2.99 0.37 MILK-2889,2390 1-131 0.0110.15 0.07 i 0.20 0.04 i 0.13 E'
Jul,1994 I-131 0.11 i 0.21 0.15 i 0.22 3 WATER 2842,2843 Jul,1994 0.13 i 0.15 Gr. Beta 3.97 1.14 WATER-2842,2843 Jul,1994 5.20i l.19 4.59 t 0.82 WATER-2910, 2911 H-3 65.78 i 83.65 32.30 i 82.23 . 49.04 i 58.65 E' 5 J41994 Gr. Beta 1.5810.44 WATER-2910, 2911 1.4810.45 1.53 i 0.31 Jul,1994 H-3 74.86 i 82.57 146.79 i 85.57 WATER-2930, 2931 110.83 i 59.46
'd 1994 Gr. Beta 1.66 i 0.56 MILK-2958,2959 2.1910.58 1.93 i 0.40
,ul,1994 I-131 -0.0710.24 -0.06 i 0.24 MILK-2958,2959 Jul,1994 -0.07 i 0.17 K-40 1,445.00 t 122.00 1,445.00 i 134.00 '
MILK-3010,3011 1,445.00190.~61 J41994 Sr-89 -0.54 i 1.01 MILK-3010,3011 -0.3610.73 -0.45 i 0.62 Jul,1994 Sr-90 1.6410.55 WATER-3031, 3032 1.34 i 0.39 1.49 i 0.34 J 4 1994 1-131 0.2310.24 i MILK-3083,3084 0.2410.28 0.2410.18 Jul,1994 I-131 0.21 0.22 0.08 i 0.22 MILK-3083,3084 Jul,1994 0.1510.16 K-40 1,420.00 i 170.00 1,380.00 i 150.00 WATER-3106, 3107 Jul,1994 1,400.00 t 113.36 H-3 79.09 i 80.43 WATER-3154, 3155 98.42 i 81.27 88.76 t 57.17 Jul,1994 Gr. Beta 1.73 i 0.76 2.20 i 0.78 URINE-3748, 3749 Jul,1994 1.9710.54 C-14 76.00 1 83.00 URINE-3748, 3749 74.00 i 96.00 75.00 i 63.45 Jul,1994 Gr. Alpha 0.30 i 2.30 URINE-3748, 3749 2.10 i 2.50 1.20 i 1.70 Jul,1994 Gr. Beta 3.90 i 2.50' i URINE-3748, 3749 3.30 i 2.70 3.60 i 1.84 Jul,1994 H-3 175.00 1 583.00 198.00 i S84.00 ' WATER-3209, 3210 Jul,1994 186.50 i 412.60 H-3 -25.26 i 82.29 WATER-3234,3235 0.87i 83.39 -12.20 1 58.58 Jul,1994 H-3 7.67 i 82.81 -38.33 1 80.82 WATER-3261, 3262 -15.33 1 57.86 J4 1994 Gr. Beta 4.42 0.82 WATER-3310, 3311 4.7910.87 4.6110.60 Jul,1994 Gr. Beta > 2.60 1.30 1.40 i 1.20 VEGETATION-3403,3404 Jul,1994 K-40 2.00 0.88 3.38 0.41 3.50 i 0.44 WATER-3469, 3470 Jul,1994 H-3 3.44 0.30 563.13 i 99.60 510.56 i 97.74 WATER-3811,3812 Jul,1994 536.85 1 69.77 Co-60 5.57 i 4.23 E WATER-3811,3812 0.1212.26 Jul,1994 Cs-137 2.93 3.99 -0.35 i 2.27 2.8512.40 g, WATFR-3358, 3359 Jul,1994 1.29 i 2.30 H-3 180.00 i 100.00 WATER-3559, 3560 200.00 i 100.00 190.00 1 70.71 Aug,1994 Gr. Deta 2.1010.78 E-GRASS-3586, 3587 1.4110.74 1.76 i 0.54 Aug,1994 Be-7 3.5210.51 3.6810.51 3 GRASS-3586, 3587 Aug,1994 Gr. Beta 3.60 0.36 7.4210.25 7.07t 0.23 7.25 0.17 AS-5 E'
L F u Table A-5. In-house " duplicate" samples. { Concentration in pCi/L' Lab Sample First Second Averaged p Cedes
- Date Analysis Result Result Result L GRASS 3586, 3587 Aug,1994 K-40 7.39 i 0.78 7.07 i 0.79 7.23 i 0.56 GRASS-3586, 3587 Aug,1994 Sr 89 0.0010.01 0.0010.01 0.00 0.01 GRASS-3586, 3587
" Aug,1994 Sr-90 0.0010.00 0.0010.00 0.0010.00 WATER 3611,3612 Aug,1994 Gr. Beta 1.8710.57 2.02 0.49 1.95 0.38 MILK-3942,3943 Aug,1994 I-131 -0.14 i 0.23 0.1810.25 0.0210.17 f' MILK 3942,3943 Aug,1994 K-40 1,544.00 1 128.00 1,416.00 i 191.00 ' 1,480.00 1 114.% WATER-3638,3639 Aug,1994 H-3 147.41 i 86.26 38.61 i 81.71 93.01 59.41 WATER-3683, 3684 Aug,1994 H-3 7.07 i 80.96 38.90 1 82.34 22.99 i 57.74 [ WATER-3727, 3728 Aug,1994 Gr. Beta 4.47 i 0.77 ' 4.8210.84 4.65 0.57 MILK-3842,3843 Aug,1994 K-40 1,419.00 1 120.00 1,411.00 1 142.00 1,415.00 92.96 WATER-3869, 3870 Aug,1994 Gr. Beta 4.1510.67 3.15 i 0.64 3.6510.46 i WATER-3869, 3870 Aug,1994 H-3 43.82 i 81.84 33.30 1 81.38 38.56 1 57.71 VEGETATION-3892,3893 Aug,1994 Gr. Beta 2.49 0.08 2.5410.08 2.52 0.% VEGETATION-3892,3893 Aug,1994 K-40 1.8910.26 2.27 i 0.28 2.0810.19 L WATER-3964, 3%5 Aug,1994 Gr. Beta 3.9110.73 4.9010.83 4.4110.55 WATER-3913, 3914 Aug,1994 Gr. Beta 4.26 i 0.83 3.8410.73 4.0510.55 r WATER-3991,3992 Aug,1994 Tc-99 84.90 1 9.30 96.40 i 9.90 90.65 6.79 L. MILK-4016,4017 Aug,1994 Co-60 0.9613.58 -0.90 i 0.43 0.0311.80 MILK-4016,4017 Aug,1994 Cs-137 -0.3012.66 2.33 i 3.87 1.0212.35 p . MILK-4016,4017 Aug,1994 I-131 0.1710.22 0.04 i 0.23 0.11 ! 0.16 L MILK-4040,4041 Aug,1994 Sr-89 0.9111.05 -0.05 i 0.82 0.4310.67 MILK-4040,4041 Aug,1994 Sr-90 0.9210.45 1.05 i 0.40 0.9920.30
- MILK-4459,4460 Aug,1994 K-40 1,528.00 i 170.00 1,481.00 1 151.00 1,504.50 1 113.69 L WATER-4061,4062 Aug,1994 Gr. Beta 4.56 0.84 4.5710.79 4.5710.58 WATER-4113, 4114 Aug,1994 Gr. Beta 1.62 i 0.61 1.83 i 0.64 1.731044 r MILK-4168,4169 Aug,1994 K-40 1,300.00 1 140.00 1,390.00 i 140.00 1,345.00 t 98.99 L WATER-4284, 4285 Aug,1994 Gr. Beta 5.4210.92 5.17i0.89 5.30 t 0.64 WATER-4504, 4505 Aug,1994 H-3 378.00 1 99.00 428.00 1 100.00 403 00 t 70.36 I WATER-4259, 4260 Aug,1994 Gr. Beta 2.9210.53 2.48 0.50 2.70 ! 0.36 L
WATER-4308,4309 Aug,1994 Gr. Beta 2.0710.49 2.05 0.50 2.062033 WATER-4308, 4309 Aug,1994 H-3 172.74 i 88.95 148.06 i 87.97 160 40 t e2 55 WATER-4333, 4334 Aug,1994 Gr. Beta 5.13 i 2.14 L 4.0712.03 4602147 WATER-4333, 4334 Aug,1994 H-3 161.29 i 87.44 97.95 i 84.86 129 62 ! n192 VEGETATION-4402,4403 Aug,1994 K-40 2.73 i 0.12 2.95 0.96 2841048 [ MILK-4459,4460 Aug,1994 K-40 1,528.00 1 170.00 1,481.00 i l51.00 1,504 50 2 !!3 69 WATER-4475, 4476 Aug,1994 Gr. Beta 2.8010.28 2.8510.27 2 53 t d 19 WATER-4475, 4476 Aug,1994 H-3 51.05 1 80.26 56.34 80.50 53~0t % 84 ( MILK-4423,4424 Sep,1994 Co-60 -0.96 i 5.00 -0.8814.05 -0 42 : 1 22 MILK-4423,4424 Sep,1994 Cs-137 0.70 i 4.06 -0.6412.83 0 01 e 2 47 MILK-4423,4424 Sep,1994 1131 0.21 i 0.23 0.2210.23 0222016 f WATER-4446,4447 Sep,1994 H-3 186.23 i 88.96 223.36 90.42 204 N1 t at 42 F [ A5-6 [_ - - - - -
O O Table A 5. In-house " duplicate" samples. Concentration in pCi/L' - Lab Sample First Second Averaged Codes 6 Date Analysis Result Result Result MILK-4525,4526 Sep,1994 Co-60 2.8013.47 1.2312.86 2.0212.25 MILK-4525,4526 Sep,1994 Cs-137 0.39 i 3.22 1.2712.36 0.83 i 2.00 MILK-4525,4526 Sep,1994 I-131 0.1610.26 -0.05 i 0.25 0.06 0.18 WATER-4571,4572 Sep,1994 Gr. Beta 0.09 i 0.22 0.12 0.23 0.1110.16 WATER-4571, 4572 Sep,1994 K-40 7.20 i 1.00 7.20i LOO 7.2010.71 WATER-3636,3637 Sep,1994 H-3 445.19 i 99.02 529.66i10L98 487.43 i 71.07 MILK-4550,4551 Sep,1994 I-131 -0.01 0.24 0.2510.28 0.12 i 0.18 MILK-4550,4551 Sep,1994 K-40 1,410.90 t 109.00 1,398.10 155.00 1,404.50 1 94.74 SLUDGE-4613,4614 Sep,1994 Ra-226 1.38 0.04 1.39 i 0.05 1.3910.03 WATER-4810, 4811 Sep,1994 H-3 36,966.34 1 557.20 37,782.99 t S63.06 37,374.67 i 396.08 WATER-4688, 4689 Sep,1994 H-3 62.77 82.11 -9.39 1 78.95 26.69 t 56.95 MILK-4886,4887 Sep,1994 I-131 -0.04 i 0.25 -0.06 i 0.24 MILK-4886,4887 Sep,1994 K-40 1,397.90 1 152.00 1,319.00 i l71.00
-0.05 i 0.17 g WATER-4744, 4745 1,358.45 1 114.40 g Sep,1994 Gr. Alpha 7.10 i 2.30 7.6012.20 WATER-4744, 4745 7.3511.59 Sep,1994 Gr. Beta 16.40i l.70 16.00i l.70 SEDIMENTS-6570, 6571 Sep,1994 K-40 7.8010.59 16.20 1 1.20 g 7.68 i 0.56 7.7410.41 5 MILK-4934,4935 Sep,1994 K-40 1,519.50 1 170.00 1,421.30 i 190.00 1,470.40 127.48 SEDIMENT-5000, 5001 Sep,1994 Gr. Beta 8.5712.00 MILK-5022,5023 Sep,1994 I-131 0.17 i 0.19 8.57 i 2.00 8.57 1.41 g 0.29 0.33 0.23 0.19 5
. - VEGETATION-5253,5254 Sep,1994 Sr-89 0.00 i 0.00 0.00i o.00 0.00 0 00 VEGETATION-5253,5254 Sep,1994 St-90 0.0010.00 0.0010.00 0.00 0 00 WATER-5952, 5953 Sep,1994 Co-60 L73 2.46 1.1512.36 1.44 t 1.70 WATER-5952,5953 Sep,1994 Cs-137 1.75 i 2.38 0.3212.24 1.03 t 1.63 AIR FILTER-5348,5349 Sep,1994 Sr-89 420.10iIL40 439.40 i 22.00 429.75 t 12.39 FILTER-5348,5349 Sep,1994 , Sr-89 420.10i ll.40 439.40 i 22.00 429.75 t 12.39 l AIR FILTER-5348,5349 Sep,1994 Sr-90 5.60 i 1.20 7.1012.00 6.35 t i 17 FILTER-5728,5729 Sep,1994 Gr. Alpha -0.8312.56 1.90 i 2.63 0 54 t i 84 FILTER-5728,5729 Sep,1994 Gr. Alpha -0.8312.56 1.9012.63 0.54 t 184 FILTER-5728,5729 Sep,1994 Sr-89 2.02 i 6.30 -3.0213.57 -0.50 t 3 62 FILTER-5728,5729 Sep,1994 Sr-90 0.86 i 1.94 1.66 i 1.26 126 t i 16 WATER-5373,5374 Sep,1994 H-3 565.00 i 96.00 561.00 96.00 563 00 ! a7 88 MILK-5274,5275 Oct,1994 I-131 0.16 i 0.21 0.18 0.25 017 t 016 SOIL-5394,5395 Oct,1994 Be-7 0.6610.36 0.8710.52 0~7e012 SOIL-5394,5395 Oct,1994 Cs-137 0.2410.% 0.20 i 0.05 0 22 t 0 04 SOIL-5394, 5395 Oct,1994 Cs-137 0.2410.06 0.20 0.05 0222004 SOIL-5394, 5395 Oct,1994 Gr. Alpha 8.89 i 2.52 9.72 i 2.71 9 30 I 85 SOIL-5394, 5395 Oct,1994 Gr. Beta 27.15 1 2.36 27.83 i 2.24 27.49 t i 63 SOIL-5394,5395 Oct,1994 K-40 22.93 1 1.20 22.40 1 1.36 22.672091 SOIL-5394,5395 Oct,1994 Sr-89 0.00 0.03 0.0210.03 0 01 t 0 02 l S01L-5394, 5395 Oct,1994 Sr-90 0.0910.01 0.08 i 0.01 0m 00i WATER-5421,5422 Oct,1994 Gr. Beta 2.56 0.53 3.54 i 0.51 3 04 e o 17 I I A5-7 II
=li
l i Table A-5. In-house " duplicate" samples. Concentration in pCi/L' ! Lab Sample ! First Second Codes 6 Date Analysis Averaged Result Result { WA s t.x-5421, 5422 Result Oct,1994 K-40 0.8710.09 MILK-5527,5528 0.95 0.10 0.9110.06 Oct,1994 CcM0 -1.1113.26 0.89 i 3.88 -0.1112.53 f MILK-5527,5528 Oct,1994 Cs-137 3.2112.44 -0.55 i 3.51 L MILK-5527,5528 Oct,1994 I-131 0.0010.18 1.33 i 2.14
-0.0310.20 -0.02 i 0.13 VEGETATION-5573,5574 Oct,1994 K-40 3.00 i 0.30 2.8210.37 p MILK-5552,5553 Oct,1994 2.9110.24 Cc40 2.04 i 3.26 1.3214.10 L MILK-5552,5553 Oct,1994 1.6812.62 Cs-134 -0.79 i 2.79 MILK-5552,5553 0.25 2.99 -0.2712.04 Oct,1994 Cs-137 1.03 i 2.58 -0.53 i 3.59 0.2512.21 p MILK-5552,5553 Oct,1994 I-131 0.1010.22 -0.09 i 0.21 L MILK-5552,5553 Oct,1994 0.01 0.15 I-131 0.10 i 0.22 MILK-5552, 5553 -0.0910.21 0.01 i 0.15 Oct,1994 K-40 1,468.10 1 122.00 1,322.00 146.00 1,395.05 i 95.13
{ MILK-5552,5553 MILK-5552,5553 Oct,1994 Oct,1994 Sr-89 Sr-90 0.69 i 1.06 1.73 i 0.45
-0.08 i 0.88 1.37 i 0.39 0.31 0.69 WATER-5595,5596 Oct,1994 1.5510.29 I-131 0.13 i 0.21 0.1210.26 FISH-5637, 5638 Oct,1994 0.12 0.17 Co-60 -0.06 i 1.28
{ FISH-5637,5638 Oct,1994 Cs-137
-0.8211.92 -0.44 i 1.15 0.27 1.25 2.0211.65 1.1511.04 SEDIMENT-5850, 5851 Oct,1994 Cs-137 0.2210.04 0.2210.05 Oct,1994 0.22 0.03
{ SEDIMENT-5850,5851 K-40 13.53 i 0.85 12.20 0.85 VATER-5658,5659 Oct,1994 Gr. Beta 12.87 0.60 7.42 i 1.07 7.97 i 1.03 7.70 0.74 WATER-5682, 5683 Oct,1994 Co-60 0.1613.36 2.01 3.54 1.09 2.44
' WATER-5682, 5683 Oct,1994 Cs-137 0.2313.07 0.70 i 3.68 0.47 2.40 WATER-5682,5683 Oct,1994 H-3 78.63 1 76.44 -41.76 t 71.13 WATER-5707,5708 Oct,1994 18.44 52.21 H-3 12,727.10 i 1,756.35 12,799.14 i 1,766.14 12,763.12 1 1,245.39 SEDIMENTS-5829,5830 Oct,1994 Co-60 0.4011.51 -0.5811.68 -0.09 1.13 SEDIMENTS-5829, 5830 Oct,1994 Cs-137 0.19 i 0.04 0.19 i 0.05 0.19 i 0.03 GRASS-5879, 5880 Oct,1994 Be-7 2.40 0.12 2.40 0.13 2.4010.09 h GRASS-5879,5880 Oct,1994 K-40 6.5510.22 63810.25 6.5610.17 VEGETATION-5903,5904 Oct,1994 K-40 3.40 0.38 3.1310.29 3.26 t 0.24 VEGETATION-5903,5904 Oct,1994 Sr-89 0.00 i 0.00 0.0010.00 0.00 0.00 VEGETATION-5903,5904 Oct,1994 Sr-90 0.00 0.00 0.0010.00 0.00 0 00 WATER-5928, 5929 Oct,1994 H-3 402.89 i 94.65 446.30 96.23 424.59 67.49 p WATER-6018,6019 Oct,1994 Gr. Beta 2.4010.69 1.59 i 0.44 1.9910.41 L SEDIMEN15-6301,6302 Oct,1994 Co-60 1.0710.06 1.0710.06 1.07 : 0 04 SEDIMENTS-6301, 6302 Oct,1994 Cs-137 1.6410.10 1.5710.08 1.60 0 06 SEDIMENTS-6301, 6302 Oct,1994 Gr. Beta 11.82 1 1.72 8.28 t 1.83 SEDIMENTS-6301, 6302 10.05 1.26 ~~
Oct,1994 Mn-54 0.74 i 0.06 0.79 0.08 0.77 : 0 05 WATER 6070,6071 Oct,1994 I-131 0.0710.22 -0.1710.21 -0.05 i 0.15 WATER-6116,6117 Oct,1994 H-3 -7.55 i 76.85 -21.48 76.21 -14.51 54.12 SEDIMENT-6256, 6257 Oct,1994 Gr. Beta 5.47 1.69 7.4411.37 6.46 1 09 SEDIMENT-6256, 6257 Oct,1994 K-40 9.3410.27 9.3410.29 9.34 ! 0.19
.EDIMENT-6256, 6257 Oct,1994 Ra-226 0.13 0.02 0.11 0.02 0.12 0 01 AS-8
O O Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample Codes 6 First Second Date Analysis Result Averaged Result Result SEDIMENT-6256, 6257 Oct,1994 Ra-228 0.0610.01 0.05 t 0.01 MILK-6091,6092 Oct,1994 I-131 0.05 i 0.01 0.2210.24 0.0310.22 WATER-6139, 6140 Oct,1994 H-3 0.1210.16 ' 23,478.00 i 782.00 23,509.00 t 782.00 FISH-6162, 6163 Oct,1994 23,493.50 i 552.% Co-60 0.0010.01 l FISH-6162, 6163 0.01 i 0.02 0.01 i 0.01 Oct,1994 Co-60 ! 0.09 i 0.03 0.0810.02 WATER 4635, 6636 Oct,1994 Co-60 0.09 i 0.02 1.8312.42 -0.20 i 1.66 WATER-6635, 6636 Oct,1994 Cs-137 0.81 i 1.47 1.07 i 3.38 0.68 2.25 l GRASS 4235, 6236 Oct,1994 0.88 i 2.03 Be-7 1.89 i 0.14 , GRASS-6235, 6236 1.93 i 0.12 1.91 i 0.09 Oct,1994 K-40 7.0310.28 6.8010.24 WATER-6277, 6278 Oct,1994 Gr. Beta 6.91 i 0.19 i 2.38 i 0.56 2.37 i 0.56 WATER-6277, 6278 Oct,1994 H-3 2.38 0.40
-4.11 i 79.62 66.30 i 89.86 WATER-6489, 6490 Oct,1994 Gr. Beta 31.10 t 60.03 1.98 0.49 2.0410.46 WATER-6489,6490 Oct,1994 H-3 2.01 0.34 gi 742.19 i 106.47 763.16 1 107.15 WATER-6214,6215 Oct,1994 H-3 4,466.00 i 189.00 4,595.00 t 191.00 752.68 75.53 g WATER-6327,6328 Oct,1994 4,530.50 1 134.35 H-3 131.64 i 82.83 1
147.29 i 83.49 SOIL-6447, 6448 Oct,1994 AC-228 0.7210.06 0.68 t 0.05 139.46 i 58.80 gi SOIL-6447, 6448 Oct,1994 BI-212 0.67 i 0.17 0.70 0.04 g SOIL-6447, 6448 0.67 i 0.10 0.67 i 0.10 Oct,1994 BI-214 0.5210.02 0.5310.02 SOIL-6447, 6448 Oct,1994 Gr. Alpha 6.5412.67 6.6212.51 0.53 i 0.02 g SOIL-6447, 6448 Oct,1994 Gr. Beta 6.5811.83 3 21.52 i 2.41 20.61 i 2.42
~ SOIL-6447, 6448 Oct,1994 K-40 21.06 1.71 18.071 0.37 18.72 i 0.31 SOIL-6447, 6e'S Oct,1994 PB-212 18.40 0.24 0.7110.02 0.68 i 0.02 E SOIL-6447, 6448 Oct,1994 PB-214 0.7010.02 5 0.58 0.03 0.60 i 0.03 SOIL 4447, 6448 Oct,1994 RA-226 0.5910.02 1.15 i 0.17 0.96 i 0.16 SOIL-6447, 6448 Oct,1994 TL-208 1.06 t 0.11 0.24 i 0.02 0.25 i 0.01 FISH-6372, 6373 Oct,1994 Co-60 0.2410.01 0.00 i 0.02 0.01 i 0.02 FISH-6372, 6373 Oct,1994 Cs-137 0.001001 0.00 i 0.01 0.00 i 0.01 WATER-6468,6469 Oct,1994 Gr. Beta 0.0010.01 1.76 i 0.47 1.79 i 0.49 WATER-6468, 6469 Oct,1994 1.7810.34 H-3 137.58 i 84.56 WATER-6401, 6402 90.36 i 82.58 113.97 i 59.10 Nov,1994 Gr. Beta 1.78 t 0.47 SEDIMENTS-6422, 6423 1.67 i 0.64 1.72 0.40 Nov,1994 Gr. Beta 6.0610.61 SEDIMENTS-6422, 6423 6.4410.59 6.25 t 0.42 Nov,1994 K-40 8.18 0.49 4
SEGIMENTS-6422, 6423 7.18 i 0.56 7.68 0 37 Nov,1994 Sr-89 0.01i o.01 0.00 i 0.02 SEDIMENTS 4422,6423 Nov,1994 Sr-90 0.00 0 01 0.0010.00 0.0010.01 WATER-6534, 6535 Nov,1994 0.00 t 0 00 H-3 67.94i82.60 WATER-6614, 6615 36.31 1 81.24 52.13 t 57.93 Nov,1994 Gr. Beta 4.97 2.01 l WATER-6614,6615 3.94 i 1.82 4.45 t 135 Nov,1994 H-3 30.68 i 81.46 l WATER-6746, 6747 -4.05 79.96 13.31 57.07 Nov,1994 H-3 2,734.00 t 176.00 l 2,851.00 i l78.00 2,792.50 125.16 WATER-6767, 6768 Nov,1994 H-3 107.00 1 83.00 95.00 1 82.00 101.00 58 34 { WATER-6788, 6789 Nov,1994 Co-60
-1.8712.17 -0.16 i 3.22 -1.01 WATER 4788, 6789 Nov,1994 Cs-137 194 1.6013.68 -1.8113.04 -0.11 2%
AS-9 'Hm% _ _ _ _ _ _ _ _ _ _ - - _ . - _ _ _ _ _ - - _ - _ _ _ _ _ _ .
u Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Saraple First Second Averaged Cedes
- Date Analysis Result Result Result WATER-6788,6789 Nov,1994 Gr. Beta 5.2011.30 3.00 i 0.90 4.10 0.79 WATER-6985, 6986 Nov,1994 Gr. Beta 2.0210.46 1.99 i 0.48 2.0010.33 L WATER-7059,7060 Nov,1994 Gr. Beta 8.6211.30 7.6811.70 8.15 1.07 WATER-7059, 7060 Nov,1994 H-3 0.00 1 100.12 0.00 1 100.12 0.00 i 70.79 g WATER-7615, 7616 Nov,1994 Co-60 1.33 i 2.68 1.43 i 3.14 1.38 i 2.06 L WATER-7615, 7616 Nov,1994 Cs-137 -1.6413.77 1.05 i 3.01 -0.30 2.41 MILK-7144,7145 Nov,1994 I-131 0.2410.28 0.27 i 0.32 0.26 i 0.21
- MILK-7144,7145 Nov,1994 K-40 1,226.80 1 161.00 1,298.20 1 152.00 1,262.50 i l10.71 b MILK-7144,7145 Nov,1994 Sr-89 0.52 i 0.73 -0.47 i 0.75 0.03 i 0.52 MILK-7144,7145 Nov,1994 Sr-90 0.79 i 0.40 1.1210.46 0.96 i 0.30 F SO!1<7193, 7194 Nov,1994 Cs-137 0.08 i 0.04 0.0910.03 0.09 i 0.02 L SOIL-7193, 7194 Nov,1994 Gr. Alpha 11.65 1 4.05 8.1513.44 9.90 i 2.66 SOlle7193,7194 Nov,1994 Gr. Beta 21.96 1 2.80 18.00 i 2.63 19.98 1.92 [ SOIL-7193, 7194 Nov,1994 K-40 15.93 1 0.83 17.12 0.78 16.53 1 0.57 L WATER-7594, 7595 Nov,1994 Co-60 2.38 i 3.00 -2.71 i 3.15 -0.1712.18 l WATER-7594, 7595 Nov,1994 Cs-137 1.52 i 2.62 1.5512.89 1.5411.95 [~ GRASS-7246, 7247 Nov,1994 Be-7 5.2510.19 5.30 0.21 5.27 i 0.14 L GRASS-7246, 7247 Nov,1994 K-40 5.76 i 0.29 5.9610.35 5.86 0.23 NATER-7367, 7368 Nov,1994 Gr. Beta 6.00 i 0.61 4.93 0.51 5.46 0.40 I WATER-7367,7368 Nov,1994 H-3 -67.81 i 80.94 -98.69 i 79.54 -83.25 1 56.74 WATER-7288, 7289 Dec,1994 Gr. Beta 2.21 i 0.72 2.57 0.73 2.39 0.52 WATER-7330, 7331 Dec,1994 Co.60 -0.29 i 2.79 -0.9712.68 -0.63 1.93 I WATER-7330,7331 Dec,1994 Cs-137 1.37 i 2.82 1.22 2.44 1.30 1.86 WATER-7330, 7331 Dec,1994 Gr. Beta 2.55 i 0.75 2.3810.77 2.46 0.54 MILK-7391,7392 Dec,1994 I-131(G) 1.5712.82 -2.96 4.55 -0.7012.68 WATER-7536, 7537 Dec,1994 H-3 142.34 i 83.52 61.00 i 79.84 101.67i 57.77 WATER-7639, 7640 Dec,1994 Gr. Beta 5.5210.83 4.83 i 0.77 5.18 0.57 - WATER-7639, 7640 Dec,1994 H-3 60.87 i 82.65 23.60 i 80.95 42.24 57.84 L . WATER-7691,7692 Dec,1994 H-3 117.13 1 84.51 89.90 i 83.26 103.51 59.32 WATER-7838, 7839 Dec,1994 Co-60 3.81 i 2.82 -0.32 i 2.18 1.7411.78 ~ WATER-7838, 7839 Dec,1994 Cs-137 1.1612.94 -0.24 i 2.72 0.46 2.00 L WATER-7838,7839 Dec,1994 Gr. Beta 2.6810.83 3.88 0.96 3.28 0.63 WATER-7940, 7941 Dec,1994 Gr. Beta 1.9610.42 2.39 0.46 2.18 0.31 MILK-7889,7890 Dec,1994 K-40 1,468.10 i 191.00 1,373.20 i 160.00 1,420.65 124.58 L_ WATER-7961, 7962 Dec,1994 Gr. Beta 2.0111.06 2.57i l.06 2.29 0.75 WATER-7961, 7962 Dec,1994 H-3 49.77 i 82.72 -9.95 1 79.98 19.91 57.53 p WATER-8107,8108 Dec,1994 Gr. Alpha 0.26 i 0.77 0.59 i 0.82 0.43 0.56 L WATER-8107, 8108 Dec,1994 Gr. Beta 1.21 0.69 1.54 0.69 1.38 0.49 WATER-8086, 8087 Dec,1994 Gr. Beta 3.30 0.64 2.51 i 0.57 2.91 0.43 WATER-8009, 8010 Dec,1994 H-3 71.38 82.32 11.79 i 79.58 41.59 57.25 A5-10
r:: a
?
Attachment 2 3 5 5 1994 Annual Environmental Report - t Non-Radiological i l 1 i l l 1 i i
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