ML20065Q895
| ML20065Q895 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1993 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20065Q861 | List: |
| References | |
| NUDOCS 9405060265 | |
| Download: ML20065Q895 (100) | |
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{{#Wiki_filter:- - - - - - - - - - , . - - - - - - - . - - - - - - - - - - 4 DUQUESNE LIGHT LDMPANY BEAVER VALLEY POWER STATION UNITS 1 AND 2 LICENSES DPR-66 AND NPF-73 1993 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL l w
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l l Duquesne Light Company 1993 Annual Radiological Environmental deport EXECUTIVE
SUMMARY
This report describes the Radiological Environmental Monitoring Program conducted during 1993 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 1993. Duquesrie 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 1993 except during the nineth refueling outage March 26, 1993 through June 18, 1993 and during plant maintenance October 12,1993 through November 17,1993. The high average daily output generated during the year,821 megawatts net was reached in both October and November,1993 and the total net electrical generation during the year was 4,353,580 megawatt-hours. Beaver Valley Power Station Unit 2 operated throughout the year except during the fourth refueling outage which began September 17,1993 and was extended by plant maintenance until December 7,1993. The highest average daily output generated during the year was 842 megawatts net in December,1993, and the total net electrical generation during the year was 5,200,472 megawatt-hours. In 1993, 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 BVP3 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 0.00012 % 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 1993. 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, i 11 EXECUTIVE SUMM ARY
Duquesne Light Company ' 1993 Annual Radiological Environmental Report Table of Contents Section 1. INTRODUCTION .. 1-1 A. Scope and Objectives of the Program 1-1
- 8. Description of the Beaver Valley Site . 1-1 Section 2. RESULTS AND CONCLUSIONS . . . . . 2-1 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-1 l A. Environmentai 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 .. . .. 3-17 D. Reporting Levels ... . . . 3-17 Section 4. MONITORING EFFLUENTS . . 4-1 A. Monitoring of Liquid Effluents . 4-1
- 1. Description of Liquid Effluents at the Beaver Valley Power Station. .... . .. . 4-1
- 2. Radioactive Liquid Waste Sampling and Analysis Program . . . . . 4-1
- 3. Results of Liquid Effluent Discharge to the Environment 4-1 B. Monitoring of Atmospheric Effluents . . . 4-10
- 1. Description of Atmospheric Effluent Sources 4 10
- 2. Atmospheric Effluent Treatment and Sampling 4-13
- 3. Results . . . . . . 4-17 C. Solid Waste Disposal ..... . 4-17 Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-1 A. Environmental Radioactivity Monitoring Program 5-1
- 1. Program Description . . . 5-1
- 2. Summary of Results . ... 5-6 1 Quality Control Program . 5-6 B. Air Monitoring . . . 5-21
- 1. Characterization of Air and Meteorology 5-21
- 2. Air Sampling Program and Ana'.ytical Techniques 5-21
- 3. Results and Conclusions 5-23 C. Monitoring of Sediments and Soils 5-25
- 1. Characterization of Stream Sediments and Soils 5-25
- 2. Sampling Program and Analytical Techniques 5-25
- 3. Results and Conclusions . 5-27 D. Monitoring of Feederops and Foodcrops 5-28
- 1. Characterization of Vegetation and Foodcrops 5-28
- 2. Sampling Program and Analytical Techniques 5-28
- 3. Results and Conclusions . 5-31 E. Monitoring of Local Cows Milk .. 5-32
- 1. Description - Milch Animal Locations . 5-32
- 2. Sampling Program and Analytical Techniques 5-32
- 3. Results and Conclusions 5-35 Tae of contents ill
Duquesna Light Company 1993 Annual Radiological Environmental Report F. Environmental Radiation Monitoring . ... 5-36
- 1. Description of Regional Background Radiation and )'
Sources .. . . . . .. . 5 '36
- 2. Locations and Analytical Procedures . . . 5-36
- 3. Results and Conclusions ... .
. 5-37 .
G. Monitoring of Fish .. .. . 5-42
- 1. Description . . .... . . 5-42
- 2. Samplirig Program and Analytical Techniques . .. 5-42
- 3. Results and Conclusions . . . . 5-42 H. Monitoring of Surface, Drinking, Weil Waters and {
Precipitation .. .. .. . . ....... 5-44 l
- 1. Description of Water Sources . .. . . 5 44 !
- 2. Sampling and Analytical Techniques .... . . . 5-45
- 3. Results and Conclusions . . . 5-48 .
- l. Estimates of Radiation Dose to Man ... . 5-51
- 1. Pathways to Man - Calculational Models . . 5-51 <
- 2. Results of Calculated Radiation Dose to Man - Liquid l Releases ... . .. . . . 5-52 1
- 3. Results of Calculated Radiation Dose to Man -
Atmospheric Releases . . .. .. . . 5 4. Conclusions .. . .. . 5-56 ; i l l l l' i 1 [ IV-- Twe of contents
Duquesne Light Company 1993 Annual Radiological Environmental Report 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 Feed, 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 Ai Particulate and Charcoal Filter Samples . 3-10 3-9. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/m') 3-12 3-10. Quality Control Data - Contractor / Quality Control Laboratory Composite Samples Comparison Split for Sr-89 and Sr-90 (pCi/m') 3-13 3-11. Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Comparison Spiked Water Samples (pCill) 3-14 3-12. Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Comparison Spiked Milk Samples (pCl/l) 3-15 4-1. Radioactive Liquid Waste Sampling and Analysis Program .. . 4-7 4-2. Results of Liquid Effluent Discharges to the Environment 4-9 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 (1993) . 5-7 5-3. Pre-operational Environmental Radiological Monitoring Program Summary 5-17 5-4. Typical LLDs For Gamma Spectrometry 5-20 5-5. Closest Residence and Garden in Each Sector . 5-30 5-6. Radiation Dose to Maximum Individual, mrem /yr - Liquid Releases 5-53 5-7. Results of Calculated Radiation Dose to Man - Liquid Releases 5-54 5-8. Results of Calculated Radiation Dose to Man - Atmospheric Releases 5-57 List of Tames V
Duquesno Light Company 1993 Annual Radiological Environmental Report 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 . 42 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 . 5-22 5-2. Average Concentration of Gross Beta in Air Particulates 5-24 5-3. Environmental Monitoring Locations - Shoreline Sediments and Soil 5-26 5-4. Environmental Monitoring Program - Feederop and Foodcrop Locations 5-29 5-5. Milch Animal Census .
. 5-33 5-6. Environmental Monitoring Locations - Milk . 5-34 5-7. TLD Locations - Northwest Quadrant . 5-38 5-8. TLD Locations - Northeast Quadrant 5-39 5-9. TLD Locations - Southeast Quadrant .
5-40 5-10. TLD Locations - Southwest Quadrant . 5-41 5-11. Environmental Monitoring Program - Fish Sampling Locations 5-43 5-12. Environmental Monitoring Stations Locations - Wells, Surface Water, Drinking Water and Precipitation . 5-47 VI L!st O' ECJ#e5
Duquesne Li0ht Company 1 1993 Annual Radiological Environmental Report i. J Section 1. INTRODUCTION + 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 radiation levels in areas surrounding the site. The results of these media are j assessed to determine impacts of the plant operation on the environment. The l j Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne ] Light Company in 1993. ) B. Description of the Beaver Valley Site ' I The Beaver Valley Power Station is located on the south bank of the Ohio River in j the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of 4 land. Figurc 1-1 is a view of the Beaver Valley Power Station. The site is l approximately one mile from Midland, Pennsylvania; 5 miles from East Liverpool, Ohio; and 25 miles from Pittsburgh, Pennsylvania. Figure 1-2 shows the site 4 location in relation to the principal population centers. Population density in the j 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 concentrated population is the Borough of Midland, Pennsylvania, with a population I of approximately 3,300. f 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 .l i Power Station at an elevation of 1,160 feet. Plant ground level is approximately 735 I feet above sea 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 Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The } 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 approximately 25,000 CFS.
Water tempbrature 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 by the water quality of the Allegheny, Monongahela, and Beaver rivers. The climate of the area may be classified as humid continental. Annual l 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 Section 1. INTRODUCTION 1-1
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Duquesne Light Company 1993 Annual Radiological Environmental Report Figure 1-2 Geographical Map and Principal Cornmunities in 40-mile Radius of the Beaver Valley Power Station ye YCL,'5CSIC'g jj U NEW CASTLI , I \\ Y ALL uNCE '. g*
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I ; I q l Roads Rivers g Cicies GEOGRAPHICAL liAP AND PRINCIPAL C0;t1 UNITIES IN 40-li1LE RADIUS OF THE BEAVER VALLEY POWER STATION FIGURE 1-2 section 1. mTRooucTioN 1-3
Duquesne Light Company l' 1993 Annual Radiological Environmental Report The design ratings and basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below: Beaver Vallev Unit 1 Beaver Vallev Unit 2 Thermal & Elec. Rating 2660 MW,835 MW, 2660 MW,836 MW, (Net MW,) Type of Power PWR PWR > No. of Reactor Coolant 3 3 Loops No. of Steam Generators
& Type 3 - Vertical 3 - Vertical !
t l Steam Used by Main Saturated Saturated Turbine The units utilize two separate systems (primary and secondary) for transferring heat l-from the source (the reactor) to the receiving component (turbine-generator). ! Because the two systems are isolated fror each other, primary and secondary waters do not mix; therefore, radioactivity lo the primary system water is normally 1 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 g!ven 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 through the turbine, and returned to the steam. generators to begin another steam / water cycle. NOTE: MW,- megawatts thermal MW,- megawatts electrical 1-4 secton 1. INTRoOUCTioN
--- ~ . - - _ _ . . - . _.
Duquesne Light Company ? 1993 Annual Radiological Environmental Report 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 1993. ! The Beaver Valley Power Station Unit 1 operated throughout 1993, except during the ninth refueling outage March 26, 1993 through June 18, 1993 and during plant l maintenance October 12, 1993 through November 17, 1993. Unit 2 operated 4 throughout the year except during the fourth refueling outage which began September 17,1993 and was extended by plant maintenance until December 7,1993. l During the year, the radioactive releases were below the limits of 10 CFR Part 50, j Appendix 1. The 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 1993 was the same as in 1992 except several i changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications. (Refer to Table 5-1 for the 1993 Radiological Monitoring l Program Outline.) The Beaver Valley Power Station Technical Specifications require sampling of three J (3) dairies which have the highest calculated milk pathway potential and one large j i local dairy. The three dairies are determined from calculations based on the ) j meteorological data and the latest milch animal survey. However, these dairies are 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 normally result in sampling of several additional dairies during the year in different sampiing periods, i The Environmental Monitoring Program also includes two larger dairies in order to
- 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 associated with each of the locations are provided in the detailed summary of the j milk monitoring program of this report (Section 5-E). i 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 datamf authorized radioactive discharges and were within limits permitted by the NRC license. I ~ The results and conclusions for each media of the 1593 Radiological Environmental Monitoring Program are contained in Section 5 of this report. A summary of the 1993 operational environmental data is found in Table 5-2 and a summary of j preoperational data (1974-1975) environmentai data is found in Table 5-3. 5 Section 2. RESULTS AND CONCLUStONS 21
Duquesne Light Company 1993 Annual Radiological Environmental Report Evaluation of effluent release data from the Beaver Valley Power Station and environmental media demenstrated compliance with regulations and Station Technical Specifications, l l 1 I l f l l i l l l l 2-2 Section 2. RESULTS AND CoNCLUS!ONS
Duquesne Light Company 1993 Annual Radiological Environmental Report Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS l l l Environmental Quality Control Program !
- A.
1 The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) elements. It 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. Values in Table 3-1 through Table 3-12 identified with an asterisk (*) do not meet comparison critere. However, acceptable correlation was achieved in most instances as outlined in the discussions and i I tables which follow.
- 1. TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and QC l
Laboratory) , i 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 11.0% of the mean of all results. This is within the precision of typical TLD Systems. 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, soll, sediment and feederop were also split with the DLC QC Laboratory. A summary of results of split water samples is provided in Table 3-2 and Table 3-3. The only non-comparison in all of the surface and drinking water analysis was one gross beta analysis of a surface water sample. The one non-comparison of surface water gross beta is believed due to variation in the 4 presence of small amounts of sediment which can affect comparison at low 1 levelt of activity. All gross beta analysis of drinking water (which are relatively - free of sediment) compared. Summaries of milk, sediment 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 K-40 in feed and one non-comparison of Co-60 in sediment. Some variation may be expected due to small variations in duplicate samples, variations in analytical procedures and in calibration, source type, etc. l 3-1 Section 3. ENVIRONMENTAL MONITORING CoNSIDERATloNs
Duquesne Light Company 1993 Annual Radiological Environmental Report Control Data - Contractor /Ouality Control Laboratory Comparison Tabh 31. Quality l Thermoluminescent Dosimeters - mR/ day TABLE 31 l l QUALITY CONTROL DATA CONTRACTORIQUALITY CLNTROL LABORATORY l COMPARISON THERMOLUMINESCENT DOSIMETERS - mR/ day l 2ND QUARTER 1ST QUARTER DLC DLC - QC i DLC DLC - QC Location No. Contractor Lab Location No. Contractor Lab (CaSO4:Dy) (CaSO4:Dy) l (CaSO4.Dy) (CaSO4:Dy) 10 0.15 0.17 1 10 0.14 0.18 i 13 0.16 0.17-13 0.13 0.16 14 0.16 0.18 14 0.14 0.20 15 0.14 0.15 15 0.11 0.15 27 0.17 0.19 27 0.15 0.18 28 0.17 0.19 28 0.15 0.18 l 298 0.24 0.21 298 0.18 0.20 l 32 0.14 0.19 32 0.17 0.20 l 45 0.17 0.19 45 0.16 0.18 l 46 0.16 0.16 46 0.13 0.16 I 47 0.16 0.21 47 0.17 0.20 l 48 0.15 0.19 48 0.15 0.18 i 51 0.17 0.18 51 0.17 0.17 l 1 4TH QUARTER 3RD QUARTER DLC DLC - QC DLC DLC - QC Location No. Contractor Lab Locatio". No. Contractor Lao (CaSO4:Dy) (CaSO4:Dyl (CaSO4:Dy) (CaSO4:Dy) 10 0.16 0.16 0 0.16 0.19 13 0.14 0.16 13 0.15 0.18 14 0.15 0.17 14 0.15 0.18 15 0.14 0.14 15 0.12 0.14 27 0.17 0.17 27 0.16 0.18 28 0.14 0.17 28 0.16 0.18 299 0.20 0.21 299 0.20 0.23 32 0.19 0.17 32 0.17 0.20 45 0.16 0.17 45 0.16 0.19 46 0.14 0.14 46 0.14 0.16 47 0.19 0.18 47 0.18 0.20 48 0.16 0.18 48 0.17 0.20 1 51 0.16 0.17 51 0.17 0.20 ANNUAL DLC DLC - QC Location No. Contractor Lab (CaSO4:Dy) (CaSO4:Dy) 10 0.14 0.16 13 0.14 0.16 14 0.14 0.16 15 0.11 0.14 27 0.14 0.16 l
' 28 0.14 F16 29B 0.17 0.19 32 0.15 0.17 45 0.14 0.17 46 0.12 0.15 47 0.16 0.19 l 48 0.15 0.16
- 0.16
' 51 0.15 3-2 Sect:on 3 ENVIRONVENTAL VONITORING CONSCER ATrONS
Duquesne Light Company 1993 Annual Radiological Environmental Report Table 3-2. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Surface Water Samples TABLE 3 2 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT SURFACE WATER SAMPLES Sampling DLC Contractor DLC - QC gg,,, Pened Lab (t) Lab (1) Surf ace Water Gross Alpna January < 17 <06 pC A Apnl <16 <06 pCia July <16 < 1.1 pCIA October <14 <10 pCiA Surface Water Gross Beta January 62t18 38104 pCiA Apnl 79112" 25104 pCu: July 87118 58 05 pCiA October 49108 39105 pCiA Surface Water CMo January <30 < 19 pCiA Apnl <30 <i0 pC6A July <30 <18 pC A October <30 <16 pCIA Surface Water Cs 134 January <30 < 14 pCiA Anni <30 <19 pCiA July <40 < 19 pCia October <30 <22 pC4A Surface Water Cs 137 January <30 <18 pCiA Apnl <30 <19 pCIA July <30 <26 pCIA October <30 < 19 pCLA Surf ace Water Tntium 1st Quarter 29000 1 1000 33965 i 505 pCiA Composite 3rd Quarter 25000 1000 25670 1 447 pCiA Composite Surface Water Sr-89 2nd Quarter < 10 <10 DCLA Composite 4tn Quarter <08 <07 pCiA Composite 2nd Quarter < 0 24 <0? pCiA Surface Water S r-90 Composite 4th Quarter < 016 <06 pC6A Composite 2nd Quarter <08 <16 pCIA Surface Water Co-60 (nign Composite
"'"'Y 4tn Quaner <08 <21 pCia anarsis) Composite (1) uncertainties are based on counting statistics and are specified at the 95% conhoence coe#icient See Section 3 A2 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-3
Duquesne Light Company 1993 Annual Radiological Environmental Report Table 3 3. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Drinking Water Samples TABLE 3 3 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT DRINKING WATER SAMPLES Sampling DLC Contractor OLC - QC Units
, , Lab (t)
Penod Lab (1) February <50 < 1.7 pCid Onnking Water C et37
<40 <t5 pCIA
(****'Y 'DI") May August <40 <14 pCiA November <30 <19 DC6A February <30 <14 pCid Dnnking Water C s-134 (weekly soitt) <40 < 14 pCiA May August <30 <18 pCid
<30 < 1.7 pCIA November
<30 <18 pC6A Onnking Water Co February (weekly split) May <40 <16 pCLA
<30 <21 pC6A August
<30 < 1.3 pCLA November March <10 <09 pCiA Dnnking Water Gross Alpha
< 1.5 < 1.2 pCLA June
,, )
August < 1.9 <14 pCl4 November < 16 < 2.3 pCl4 24105- pCiA Dnniong Water Gross Beta March 46108 sun. .ria .0.0. ,Cm
";;,7,e, August 42 10 41108 pCIA 2811.1 pCIA November 5111.3
< 200 < 173 pCL/I Dnniong Water Tritium 2nd Quarter
< 200 < 190 pCIA 4th Quarter j
(1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient I i 3-4 Sect;on 3 ENVIRONMENTAL MONITORING CONSIDERATIONS
1 l Duquesne Light Company 1993 Annual Radiological Environmental Report Table 3-4. Quality Control Data Contractor /Ouality Control Laboratory Comparison Split Milk Samples TABLE 3-4 QUALITY CONTROL DATA f l CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT MILK SAMPLES Sampong DLC Contractor DLC - QC units g ,, ,n,, y,,, Lab (1) Period Lab (1)
< 1.2 < 0.7 pCul Milk (25) 3-24-93 Sr-89 2.9 i 0.5 pCi/l Sr-90 2.4 i 0.2
< 4.0 < 2.6 pCf/l Co-60 I131 < 0.1 < 0.4 pCl/l
< 5.0 < 2.1 pCl/l Cs 134
< 5.0 < 2.3 pct /l Cs 137 1300 i 90 pCI/I K40 1320 i 130
< 4.0 < 1.7 pCi/l Milk (25) 6-16-93 Co-60
< 0.15 < 0.4 pCth 1131 Cs 134 < 4.0 < 1.4 pCIM Cs-137 < 4.0 < 1.7 pCl/l l 990 i 110 pCi/l K 40 1360 i 140 Sr-89 < 0.64 < 0.7 pCl/l Milk (25) 9-20-93 3.2 0.6 pCl/l Sr-90 2.6 i 0.2
< 4.0 < 2.1 pCi/l Co-60
< C.17 < 0.3 pCl/l 1-131
< 4.0 < 3.3 pCl/l Cs 134 Cs 137 < 4.0 < 3.0 pCl4 K40 1230 57 pCi/l 1450 i 140
< 5.0 < 2.4 pCl/l Milk (25) 12-14-93 Co-60
< 0.16 < 0.2 pCth 1-131
< 4.0 < 2.4 pCin Cs 134
< 4.0 < 2.2 pCtM Cs 137 pCIM K40 1550 i 150 1420 i 50 i
l (1) Uncertaintles are based on counting statistics and are specified at tne 95% confidence coemcient. l l i
~
f l I i a 3-5 section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
Duquesna Light Company 1993 Annual RadioIOgical Environmental Report Table 3-5. Quality Control Data Contractor /Ouality Control Laboratory Comparison Split Feed, Food and Sediment Sarnples TABLE 3-6 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPUT FEED, FOOO AND SEDIMENT SAMPLES amphng ""* ' ' Units Medta Ana!ysis Lap (1) Period Lao (1) Be-7 1.63 i 0.26 1.14 i 0.15 pCi/gm (dry) Feed (25) 6-16-93 K40 9.63 i 0.50 pct /gm (cry) 16.1 i 1.6*
< 0.03 < 0.020 pCl/gm (dry)
Co-60 1131 < 0.006 < 0.021 pCl/gm (cry)
< 0.03 < 0.014 pct /gm (dry)
Cs-134
< 0.03 < 0.016 pct /gm (dry)
Cs-137
< 0.011 pct /gm (dry)
Feed (25) 6-14-93 Sr-90 0.041 i .011 2.33 i 0.34 pCi/gm (wet) Food (10) 6 24-93 K-40 1.56 i 0.16
- CMOS < 0.018 pct /gm (wet)
Co-60 l-131 < 0.35 < 0.025 pC1/gm (wet)
< 0.006 < 0.012 pct /gm (wet)
Cs-134 Cs-137 < 0.005 < 0.014 pCi/gm (wet) Gross Alpha 12.8 i 4.2 pC1/gm (cry) Sediment (2A) 10-7-93 18 i 0.6 Gross Beta 38 i 3.0 22.0 i 3.1 pCi/gm (dry) Sr-89 < 0.16 < 0.041 pC1/gm (cry' Sr-90 < 0.38 < 0.014 pct /gm (cry) 2.4410.06 pct /gm (cry) Co-58 0.325 i 0.062 3.25 i 0.08 pC1/gm (cry) Co-60 1.52 i 0.15' Cs 134 < 0.07 < 0.037 pCi/gm (dry) 0.23 i 0.04 pct /gm (dry) Cs 137 0.232 i 0.040 2.24 i 0.56 pCi/gm (dry) Ra-226 0.232 i 0.04 1.14 i 0.16 pCl/gm (cry) Th-226 1.18 i 0.12 14.110.77 pCl/gm (cry) K 40 11.7 i 1.2 (1) Uncertainties are based on counting stattstics and are specined at the 95% conedence coefncient. See Section 3.A.2 and 3-B. 36 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
i Duquesne Light Company 1993 Annual Radiological Environmental 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 3-8 for evaluation of the data.
- 4. Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory)
Duplicate air particulate and charcoal filters (radiciodine) 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 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 included participation in the Environmental Protection Agency - Environmental Monitoring Safety Laboratory (EPA - EMSL) Interlaboratory Cross Check l 1 Program. This cross check program indicated that the Contractor and QC 4 Laboratory results were in agreement with EPA EMSL. See Appendix ! and 11.
- 6. 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 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. l 3-7 Section 3. ENV RoNMENTAL MONITORING CONSIDERATIONS
Duquesno Light Company 1993 Annual Radiolc gical Environmental Report , l Table 3 6. Quality Control Data Contractm/Ouality Control Laboratory Comparison Spiked Water Samples l 1
)
TABLE 3-6 QUALITY CONTROL DATA l CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPIKED WATER SAMPLES Sample Identification Sample DLC - QC
" " ' nits Date No. Analysis ( Lab (1) pCi/l
~
3-31-93 W-98 Sr-89 14.0 i 1.0 18.2 i 5.0 Sr-90 15.0 i 1.0 20.1 t 1.8 pCl/l 4-30-93 W-99 H-3 4900 i 200 5464 i 219 pCl/l 4-30-93 W-100 1-131 160 10 149.8 i 1.9 pCl/l 4-30-93 W-101 Co-60 20.5 i 4.3 24.8 i 2.3 pCl/l Cs-134 26.1 i 3.9 26.4 i 1.9 pCill Cs-137 30.8 i 3.9 34.0 i 2.6 pCi/l 6-30-93 W-102 Gross 23 i 2.0 21.9 i 1.6 pCi/l Alpha Gross 34.0 i 2.0 33.6 i 1.1 pCl/l Beta 9-28-93 W-103 Sr-89 32.0 i 2.0 21.9 i 3.9 pCi/l Sr-90 18.0 i 1.0 19.5 i 1.8 pCl/l 10-7-93 W-104 H-3 17000 i 1000 16900 i 368 pCl/l 10-8-93 W-105 l-131 92.0 i 2.0 95.2 i 10.6 pCl/l 10-8-93 W-106 Co-60 19.4 i 2.9 19.3 i 3.1 pCill Cs-134 33.2 i 3.3 31.5 i 3.3 pCl/l Cs-137 47.8 i 4.8 44.4 i 3.6 pCl/l W-107 Gross 38.0 i 8.0 35.0 2.0 pCl/l 12-30-93 Alpha Gross 45.0 i 7.0 32.0 i 2.0 pCl/l Beta W-108 Gross 79.0 i 12.0 66.8 i 2.1 pCill 12-30-93 Alpha j Gross 75.0 i 9.0 63.8 i 1.5 pCl/l l l Beta I (1) Uncertainties are based on counting statistics and are specified at the 95% l confidence coefficient. See Section 3-8. 3-8 sect >on 3 ENVIRONMENTAL McNIToRING CONSIDERATIONS
Duquesne Light Company 1993 Annual Radiological Environmental Report Table 3 7. Quality Control Data Contractor /Ouality Control Laboratory Comparison Spiked Milk Samples TABLE 3-7 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPlKED MILK SAMPLES Sample identification Sample DLC - QC
' nits Date N o. Analysis "," Lab (1)
Mi-45 Sr-89 13.0 i 1.0* 6.7 i 3.1 pCl/l 1-25-93 Sr-90 15.0 i 1.0 20.0 i 1.2 pCl/l Cs-134 21.1 i 3.9 17.1 i 2.0 pCi/l Cs-137 26.1 i 4.4 21.4 I 2.2 pCl/l K-40 1470 i 150 1390 t 60 pCl/l pCill j 2-2-93 MI-46 l-131 81.0 i 2.0 72.5 i 8.4 4-30-93 Ml-47 l-131 150.0 i 10 139.8 i 1.6 pCl/l Cs-134 55.2 i 5.5 48.8 i 2.9 pCl/l Cs-137 68.5 i 6.9 65.2 i 3.1 pCl/l K-40 1470 t 150 1406 i 50 pCill 8-20-93 Ml-48 Sr-89 43.0 i 2.0 29.1 i 4.9 pCill l l Sr-90 21.0 i 1.0 18.3 i 1.3 pCi/l Cs-134 23.4 3.0 31.4 i 7.2 pCi/l Cs-137 33.8 i 3.6 32.3 i 7.5 pCill K-40 1340 130 1310 i 150 pCill 9-28-93 Ml-49 l-131 48.0 i 1.0 40.2 i 0.8 pCi/l 10-8-93 Mi-50 1-131 45.0 i 1.0 49.7 i 8.6 pCl/l Cs-134 33.3 i 3.8 30.8 i 4.5 pCl/l l pCl/l Cs-137 54.9 i 5.5 43.4 i 6.0 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. See Section 3-8 Section 3. ENVIRONMENTAL McNtTORING CONSIDERATIONS 3-9
"kA- E+-44-'.4_. ns. a..h.a _ 4 ._,
Y TABLE 3 8
$ -4 n QUALITY CONTROL DATA 6 $
$ CONTRACTORIQUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES m
Air Particulates Air Iodine [ pC1/Cu. Meter uO O pCIICu. Meter (Beta) DLC 5m M# ' DLC Contractor
~
Sample Date Contractor Lab 0) kd g 4 Sample Date
- UI n ,
Lab (1) 8 @
# Lab (1) o
- C 0.026 i 0.003 12/28 - 1/4 < 0.02 < 0.01 tj g O 1/4 - 1/11 0 015 1 0.003* >
1/11 - 1/18 < 0.02 < 0.01 o- 3 1/18 - 1/25 0 013 1 0.003 0.014 i 0.003 7
.m 2 2/1 - 2/8 0.017 1 0 003 0 021 1 0.003 1/25 - 2/1 < 0.01 < 0.01 %$
ou .m9 , 0 2/8 - 2/16 < 0.01 < 0.01 m, ]c0 t 2/16 - 2/22 0.013 i 0.003 0.019 i 0.003 - Q z 0.021 i 0.003 2/22 - 3/1 < 0.01 < 0.01 fp E. g i m 3/1 - 3/8 0 017 i 0.003
< 0.01 [A -$
m *d 3/8 - 3/15 < 0.02 O 3/15 - 3/22 0.014 i 0.003 0.019 1 0.003
'S.
2 0.009 i 0.002 0.012 i 0.002 3/22 - 3/29 < 0.02 < 0.01 ak %mg y 3/29 - 4/5
< 0.01 5 g 4/5 - 4/12 < 0.02 5 4/12 - 4/19 0.010 1 0.003 0.012 1 0.003 4/19 - 4/26 < 0.01 < 0.02 x 5 5. O
_O 4/26 - 5/3 0.015 i 0 003 0.019 i 0.003 5/3 - 5/10 < 0.01 < 0.01 o sV 3. 5/10 - 5/17 0.009 i 0.003 0.014 i 0.003 j 0.014 1 0.003 5/17 - 5/24 < 0.01 < 0.01 ?. 3$ mx ! 5/24 - 6/1 0.009 i 0.002 a
-- 3 6/1 - 6/7 < 0.01 < 0.01 =
6/7 - 6/14 0 011 0 003 0.017 i 0.003 . S/21 - 6/2R 0009 i 0.003 0.016 i 0 003 6/14 - 6/21 < 001 . < 0.01 ] m o , I (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. o O Q 3 See Section 3-B. 9 a 3 , ii- : o ,
* (o i E !
3 t M, f i
l l l TABLE 3-8 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES Air lodine Air Particulates pCi/Cu. Meter pCl/Cu. Meter (Beta) Sample Date Cont actor Sample Date Cont actor a Lab (1) Lab (1) 6/28 - 7/6 < 0.01 < 0.01 w 7/6 - 7/12 0 017 i 0.003 0.019 i 0.003 7/12 - 7/19 < 0.02 < 0.01 g 7/19 - 7/26 0.013 1 0.003- 0.010 1 0.003 7/26 - 8/2 < 0.02 < 0.01 8/2 - 8/9 0.013 i 0.003 0.014 i 0.003 0.022 1 0.003 8/9 - 8/16 < 0.01 < 0.01 -2 ; 8/16 - 8/23 0.019 i 0.003 8/30 - 9/7 0.018 i 0.003 0 014 i 0.003 8/23 - 8/30 < 0.02 < 0.01 $og 9/13 - 9/20 0.016 i 0 003 0.019 i 0.003 9/7 - 9/13 < 0.01 < 0.01 h$ 9/20 - 9/27' < 0.02 < 0.01 y-r-9/27 - 10/4 0.012 i 0.003 0.017 i 0.003 10/4 - 10/11 < 0.01 < 0.01 g 10/11 - 10/18 0 024 i 0 004 0.023 i 0.003 y 10/25 - 11/1 0 016 i 0 003 0 018 i 0.003 10/18 - 10/25 < 0.01 < 0 01 {Q 11/1 - 11/8 < 0.02 < 0.01 o33u 11/8 - 11/15 0.034 i 0 004. 0 033 1 0.004 9 < 0.01 3$ 0.022 i 0.003 11/15 - 11/22 < 0.02 @% 11/22 - 11/29 0 019 i 0.003 8z 11/29 - 12/6 < 0.02 < 0.01 3 12/6 - 12/13 0.020 1 0 003 0.022 i 0.003 m c m 12/13 - 12/20 < 0.01 < 001 } 0.026 i 0.003 f (1) 12/20 - 12/27 0.021 1 0 004 Uncertainties are based on counting statistics and are specified at the 95% confidence coeificient.
$o g
O z - See Section 3-B. O e 5 8 5 6 5 6 b u
l Duquesna Light Company 1993 Annual Radiological Environmental Report Table 3 9. Quality Control Data Contractor /Ouality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/m') TABLE 3-9 l QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE SAMPLES (GAMMA)(pCl/m') DLC - Contractor DLC - QC Sample Date Nuclide Lab (1) Lab (1) Be-7 0.080 i 0.01 0.095 i 0.03 January K-40 0.015 I 0.006 LLD Others LLD LLD Be-7 0.092 0.01 0.070 i 0.03 March Others LLD LLD Be-7 0.124 i 0.01 0.130 i 0.03 May Others LLD LLD Be-7 0.126 i 0.01 0.088 i 0.04 July Others LLD LLD Be-7 0.131 1 0.01 0.041 i 0.02 September Others LLD LLD Be-7 0.120 i 0.01 0.085 i 0.04 November Others LLD LLD (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. LLD - Lower Limit of Detection 1
)
I 3 12 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 1
l l Cuquesne Light Comps 1y 1993 Annual Radiological Environmental Repor? Table 310. Quality Control Data Contractor / Quality Control Laboratory Composite Samples Comparison Split for Sr-89 and Sr 90 (pCi/m') TABLE 310 l QUALITY CONTROL DATA j l CONTRACTORIQUALITY CONTROL LABORATORY COMPOSITE SAMPLES COMPARISON SPLIT FOR Sr 89,90 (pCilm') DLC - Contractor DLC - QC Sample Date Nuclide Lab (1) Lab (1) l Sr-89 < 1.2 E-3 < 3.0 E-4 1st Quarter Composite S r-90 < 2.1 E-4 < 3.0 E-4 Sr-89 < 6.2 E-4 < 2.0 E-4 2nd Quarter Composite Sr-90 < 1.2 E-4 < 2.0 E-4 Sr-89 < 1.2 E-3 < 4.0 E-4 3rd Quarter l Composite Sr-90 < 1.8 E-4 < 3.0 E-4 Sr-89 < 7.1 E-4 < 3.0 E-4 l l 4th Quarter l Composite Sr-90 < 1.1 E-4 < 3.0 E-4 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3 13
_~ - - - . -. Duquesne Light Company 1993 Annual Radiological Environmental Report Table 311. Quality Control Data . Independent Laboratory / Contractor /Ouality Control Laboratory Comparison Spiked Water Samples (pCill) TABLE 311 QUALITY CONTROL DATA INDEPENDE"T LA80RATORYtCONTRACTOR10UAUTY CONTROL LA80RATORY COMPARISON SPIKED WATER SAMPLES (pCL/l) Sample ler.itification Sample Type - ' . in ' CONT TOR No. and Analyses Lab (1) g gy Lab (1) Date Sr 89 24.2 i 5.4 24.0 i 2.0 26.3 i 4.3 Sr 90 15.1 t 5.7 11.0 i 1.0 11.3 i 1.4 . l-131 18.1 i 1.8 16.5 i 1.0 17.0 i 0.5 2-28 93 53 27 Cs-134 14.8 i 5.4 15.1 i 3.3 18.0 i 1.9 Cs-137 22.0 i 6.6 25.0 i 3.7 19.6 i 2.9 H-3 1050 i 330 940 i 110 960 i 116 2-8-93 SS 28 St-89 10.2 i 4.8 10.0 i 2.0 5.4 i 2.i' Sr-90 11.8 i 6.0 15.5 i 1.0 14.3 i 1.0 4-30-93 Co40 9.7 i 7.0 11.3 i 1.0 10.1 i 1.7 SS 9 M31 16.8 i 1.5 14.0 i 1.0 19.9 i 0.3* Cs 137 20.1 i 7.2* 13.8 i 2.9 14.0 i 1.3 4-30-93
- H3 860 i 300 790 i 130 972 1 70 53 b Sr-89 14.0 i 3.9 14.0 i 1.0 12.6 i 5.6 Sr 90 9.5 i 3.6 10.2 i 0.8 9.1 i 1.7 8 4-93 Mn-54 22.4 i 4.0 24.0 i 3.0 22.5 i 2.4 53 1 M31 21.0 i 2.7 23.0 i 1.0 18.4 i 0.7 Cs-137 15.4 i 5.0 16.2 i 3.4 17.1 i 2.3
- H-3 1100 i 300 840 i 130 956 1 130 8-6-93 53 32 Sr-89 11.7 i 7.2 17.0 i 1.0 12.4 i 4.1 Sr-90 9.4 i 5.4 10.5 i 1.5 9.5 i 1.3 10 29-93 Co-58 22.0 i 4.5 23.6 I 4.1 25.8 i 5.0 53 I CcHl0 12.6 i 5.8 12.3 i 3.4 14.0 i 3.5 l 131 20.3 i 1.7 29.0 i 1.0* 14.9 i 0.3*
i H-3 884i291 690 i 120 958 i 129 10-29-93 53 (1) uncertainties are based on counting statistics and are reported at the 95% conridence coefhesent. See Section 3-B. I l 3-14 Section 3. ENVIRONVENTAL MONITORING CONSIDERATIONS
-~
Duquesne Light Company 1993 Annual Radiological Environmental Report Table 312. Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Comparison Spiked Milk Samples (pCi/l) TABLE 312 QUAUTY CONTROL DATA INDEPENDENT LABORATORY / CONTRACTOR /QUAUTY CONTROL LABORATORY COMPARISON SPIKED MILK SAMPLES (pCl/I) Sample identification Sample Type lr ^ ; -. .t rit TOR CONT Date No, and Analyses Lab (1) , g, p} Lab (1) Sr-89 30.7 i 4.5 23.5 i 2.0" 24.213.2 Sr-90 20.0 4.5 21.0 i 1.0 20.4 i 1.3 M s 2 4-93 -131 29.8 i 2.4 26.0 i 1.0 28.2 i 0.7 52 66 Cs-134 15.6 i 5.0 14.4 i 3.6 13.4 i 1.4 Cs 137 13.8 i 4.0 16.1 3.7 13.6 i 2.4 Sr49 16.6 i 6.9 13.5 i 3.0 10.0 i 2.3* Sr-90 14.8 i 6.6 21.0 i 1.0 19.2 i 1.0 4-30-93 52 7
' A b' A '
Cs 134 10.6 i 4.0 9.7 i 3.4 9.5 i 1.3 Cs 137 22.6 i 5.4 21.3 i 3.6 21.5 i 1.9 Sr-89 12.3 i 5.4 14.0 i 1.0 8.9 i 4.4* Sr-90 18.0 i 3.9 18.5 i 1.0 18.6 i 1.3 8 4-93 l-131 21.9 i 3.3 25.5 i 1.0 21.9 i 1.7 52- 68 Cs 134 15.5 i 5.5 15.6 i 3.0 15.3 i 5.6 Cs 137 18.5 i 3.9 16.413.1 18.216.3 Sr49 10.1 i 5.4* 16.0 i 2.0 9.5 i 5.3* Sr-90 14.4 i 5.4* 12.0 i 1.0 12.1 i 0.9 10 29-93 l-131 21.4 i 1.8 27.0 i 1.0" 21.8 i 0.5 52- 9 Cs 134 10.0 i 5.1 12.5 2.9 9.5 i 1.4 Cs 137 11.514.8 11.0 i 2.7 13.7 i 2.9 (1) Uncertainties are based on counting stat:stics and are based on the 95% confidence coefficient. See Section 3 B.
" One sample of duplicate analysis compared
~~
Section 3. ENVIRONVENTAL MONITORING CONSIDERATIONS 3-15
Duquesne Light Ccmpany 1993 Annual Radiological Environmental Report
- 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 1993.
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 program. Comparisons 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 3-1 through Table 3-12 identified with an asterisk (*). The QC Laboratory was noted to have a slightly low bias for strontium 89 in milk as indicated by three non-comparisons in the Independent Laboratory Program data shown in Table 3-12. This bias may also have contributed to a non-comparison for strontium 89 in Table 3-7 for the QC sample spike program with the Contractor. The QC Laboratory bias has been addressed by a strontium in milk procedure revision. The corrective action will be followed by the ongoing QC program in 1994. The Contractor had minor non-comparisons within the independent Laboratory Program. One sample out of a duplicate set for strontium 89 was slightly low, one sample out of a duplicate set for iodine 131 in milk was slightly high, and there was one non-comparison for iodine 131 in water, which was slightly high. The remainder of the Quality Control Program non-comparisons are random in nature. Comparison samples for feed and sediment are particularly subject to sample variability. Single non-comparisons were noted for potassium 40 in feed and cobalt 60 in sediment, however, overall these samples compared in other isotopes. Several air sample gross beta's did not compare, but comparison was demonstrated on the whole. In the QC Laboratory spike program, agreement was reached for W-102 gross alpha and beta after re-analysis by the QC Laboratory. Agreement was reached for W-107 gross alpha and beta after re-analysis by both laboratories. These areas will be followed by th's ongoing QC program in 1994. 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 1993 is acceptable with respect to both accuracy and measurement. 3-16 Section 3. ENVIRONMENTAL UONITORING CONSIDERATIONS
l Duquesne Light Company 1993 Annual Radiological Environmental Report 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 envkonment. Beaver Valley Power Station is subject,to regulations which include the Code of Federal Regulations 10 CFR (Energy), Pennsylvania Department of Environmental Resources (PDER) Inoustrial Waste Permit #0473211, Gaseous Discharge Permit
#04-306-001, PA Code - Title 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 #0025615, and the Beaver Valley Power Station Technical Specifications.
D. Reporting Levels ; i 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 Valley Power Station Technical Specifications when l I 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)
+ + ** '
Limit Level (1) Limit Level (2) There were no analytical results of environmental samples during 1993 which exceeded Beaver Valley Power Station reporting levels. Sect:en 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-17
1 l { Duquesne Light Company 1993 Annual Radiological Environmental Report Section 4. MONITORING EFFLUENTS A. Monitoring of Liquid Effluents
- 1. Description of Liauid 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, small amounts of well water and liquid effluents are discharged to the Ohio River using discharge points shown in Figure 4-1. Schematic diagrams of liquid flow paths for the Beaver Valley Power Station are shown in Figure 4-2, Figure 4-3, Figure 4-4 and Figure 4-5 1
- 2. Radioactive Liquid Waste Sampling and Analysis Program See Table 4-1.
l I
- 3. Results of Liquid Effluent Discharge to the Environment See Table 4-2.
Section 4. MONITORING EFFLUENTS 4-1
l Duquesno Light Company 1993 Annual Radiological Environmental Report Figure 4-1. Uquid Discharge Points to Ohio River 1 v v,
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-42 secton 4. MONITORING EFFLUENTS
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l COLLECTl0f1, TREATMEf1T. C DISCH ARGE evPS-2 m STREAM ST9EAM
- TO ER 8 40GF0 EVAPORATOR BLOWOOWN
- 1. CONT SUMP HIGH -LEV EL Lt0VID T,800 0P M WASTE WASTE TEST 200GPO 6 GPM 2, AUX BLOG SUMP DR AINS EVAPOR ATOR T AN KS (2)
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- 6. MISC. SOURCE S 40GPg OR AtNS 30 GPM i BVPS-lE 2 E $
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- 8 7 SG PRE FILTER 2000 GAL OISCHARGE $
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- 10. BVPS-1 TUR8tNE 7,2 O O G P D J BLOG ORAINS DISCHARGES TO BVPS-1 ENVIRON u CN T COOLING TOWER (BVPS-t YARD BLOWDOWN AND ENVIRONMENT 5 OR Att4 AGt I DISCHARGE Point)
O e 5 I" FIGURE 4 UNIT 1 LIQUID WASTE SYSTEM
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- 3. MISC SOURCES 700 GPD .,
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- 9. (CD STEAM 0
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- n E
o 2 DISCHARGES TO BVPS- 2 COOLING TOWER BLOWDOWN AND ENVIRONMENT FIGURE 4 UNIT 2 LIQUID WASTE SYSTEM .
- - -- - - - - - - . _ - - _ . --__.a.- - _ _ _ - - _ - - - _
.- .~ . - _ . . - . ~ . - . . _ _ - - . - . _ _ _ . . ~ . - .- _ c .. . -.. ... - - . . .._..~.-~..--u . .. - - - . . -. - -.
i TABLE 4-1 , Radioactive Liquid Waste Sampling and Analysis Program E MINIMUM TYPE OF LOWER LIMIT OF A O' ^ m ANALYSIS ACTIVITY DETECTION (LLD) a RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS !/iCi/ml)*
- o i I p p Principal Gamma SE-7 5 o ,
Emitters' E > Each Batchh Each Batchh l-131 1E-6 c. a
- to u>
Dissolved and g a p 1 E-5 m y M Entrained Gases ' 3 E 3 Batch Waste Release One Batch /Mh (Gamma Emitters) Tanksd M H-3 1 E-5 h E O P Compositeb Gross Alpha 1E-7 CA WE m Each Batchh Sr-89. Sr-90 SE-8 3 y@C P O n -o Fe-55 1E-6 f gto Each Batchh Compositeb o _ . r--
"# P*' **** SE-7 5 88 W Emitters' a ~d m
Grab Samples Ponte 1-131 1E-6 [h
- O 3 Dissolved and s 13 M Entrained Cases 1 E-5 o gm Grab Sampieg j gE B. Contmuous (Gamma Emitters) ' ~
Releasese.o
- m-M H-3 1E-5 3 Grab Sample 9 Compositec Gross Alpha 1E-7 y T) g SE-8 o
' E O Sr-89. Sr-90 2 o Grab Sampleo ' 3 Fe-55 1E-6
- Compositec O W - At least once per 7 days M - At least once per 31 days 3 i O - At least once per 92 days 3 P - Completed prior to each release i
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b , N ______________-____ - -_ - - - - - - - - - . _ - _ - _ _ _ _ ___ _ _ _ _ _ _ _ - _ _ - - _ - _ - _ _ - - _ _ _ _ - - _ _ _ .
Duquesne Light Company 1993 Annual Radiological Environmental Report TABLE 4-1 NOTATION
- a. The Lower Limit of Detection (LLD).
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed reruits in a specimen which is represem ative 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 assure representative sampling.
- e. A continuous release exists when the discharge of liquid wastes is from a non-discrete volume; e.g., from a volume of a system naving an input flow during the continuous release. For BV-1, this is applicable to the Turbine 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 Ci/ml. For BV-2, this is applicable to the Turbine Building drains when the secondary coolant gross radioactivity (beta and gamma) is 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 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" values should not be used in the required dose calculations. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Semi-Annual Radioactive Effluent Release Report,
- g. Whenever there is primary to secondary leakage, sampling is done for Turbine Building drain effluents by means of grab samples taken every four hours during the period of discharge and analyzed for gross radioactivity (beta and gamma) at a senstivity of at least 1E-7 Ci/ml and recorded in the plant records, along with the flow rate. Primary to secondary leakage is considered to be occurring whenever measurements indicate that secondary coolant gross radioactivity (beta and gamma) is greater than 1E-5 yCi/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 voNIToRING EFFLUENTS
1 l Duquesne Light Company 1993 Annual Radiological Environmental Report Table 4-2. Results of Uquid Effluent Discharges to the Environment f TABLE 4-2 l RESULTS OF LlQUID EFFLUENT DISCHARGES TO THE ENVIRONMENT Effluent Typo Results for 1993 Steam System The Steam System Blowdown was recycled when 4 Blowdown practicable. Batch Routine planned releases of liquid effluents from the l Radioactive Beaver Valley Power Station were released in accordance - Waste Liquids with conditions noted in Section 3/4.11.1 of the Technical Specifications and Section 1 of the Offsite Dose Calculation l Manual. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi-annual Radioactive Effluent Release Reports for 1993. Continuous Radioactive waste liquids were not discharged in a l Radioactive continuous mode during 1993. i Waste Liquids 1 4 f i 1 i 4 4 i ] i Section 4. MoNIToRfNG EFFLUENTS 49
Duquesne Light Company 1993 Annual Radiological Environmental Report B. Monitoring of Atmospheric Efflisents
- 1. Descript on 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 end 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 Building.
- 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 Conder t ate Polishing Building.
- 4) The Wete 9as 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.
Grab 1hese points are continuously monitored for particulates and gases. l samples ar,e obtained on a weekly basis and are analyzed for noble gas gamma emitting isotopes and tritiurn. Weekly continuous samples are obtained on filter paper and charcoal cartridges. The filter papers are analyzed for particulate l ! gamma emitting isotopes and gross alpha. Composites of the filter papers are analyzed monthly for br-89 and Sr-90. The charcoal cartridges are analyzed for 1131,1133 and 1-135. Figure 4 7 shows these gaseous release points. l l 4-10 sect ea 4 voyiTOqlNG EFFLUENTS
1 Duquesne Light Company . 1993 Annual Radiological Environmental Report l j Figure 4-6. Units 1 and 2 Gaseous Radwaste System l i "
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Duquesne Light Company 1993 Annual Radiological Environmental Report Figure 4 7. Units 1 and 2 Gaseous Release Points Ohio River
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ol , i. Q x \ ! e r . r , N . 1 1 i j_ s Unit 2 L
/ Unit i i 1 7 m @
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- 1. Unit 1:
- 2. Unit 1:
VentilationVent Containment / SLCRS Vent 79 feet : 24seters 154 feet: 47 meters
- 3. Unit 1&2:ProcessTest 475 feet:145 meters A l
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- 4. Unit 2: VentilationVent 85 feet: 26 seters A 7
- 5. Unit 2:
- 6. Unit 2:
Containment /SLCISfest CondensatePolishingBuildingVent 154 feet: 47 meters 80 feet : 24 meters g N'
- 7. Unit 2: VasteGasStorageVanitVent 80 feet: 24 meters l )
- 8. Unit 2: DecentasinationBuildingVent 80 feet: 24 meters i
FIGURE 4 UNITS 1 AND 2 GASEOUS RELEASE POINTS I I I 4-12 section 4. MONITORING EFFLUENTS "7 7 -" m-
I, i Duquesne Light Company l I l 1993 Annual Radiological Environmental Report
- 2. Atmospheric Effluer.t Treatment and Sampling Beaver Valley Power Station (Units 1 and 2) 1 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 gas is chilled to condense most of the water vapor. Gases from the degasifier
- vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and radioisotopes consisting of noble gases, particulates and radiolodines are a!so present in this system.
j 1 I 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 l of the three (3) decay tanks at Unit 1 or one of the seven (7) decay tanks at Unit l j j 2. After the decay tanks are sampled and authorization obtained for discharge, 1 the flow of the waste gases from the decay tanks (2 scfm) is rapidly diluted with j about 1000 scfm of air in order to dilute hydrogen and radioactive effluent 4
' 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 vents of the vent and drain system, discharge of the overhead gas compressor ar.d 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 c' a charcoal bed and a high efficiency filter. ~ The filtered gases are i ! then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the Unit 1 cooling tower. The l ! radioactivity levels of the stream are monitored continuously. 4 Should the radioactivity release concentration of the stream go above the
; allowable setpoint, 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 i sampled and the activity levels determined, purging may commence through the Ventilation Vent located on top of the Auxiliary Building or the Supplementary j ' 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. I i Areas in the Unit 1 Auxiliary Building (subject to radioactive contamination) are i monitored for radioactivity prior to entering the common Ventilation Vent. These individual radiation monitors aid in identifying any sources of contaminated air, } The Ventilation Vent is also monitored continuously by several redundant j channefs of the Radiation Monitoring System (RMS) and is sampled periodically. l Upon a high activity alarm, automatic dampers divert the system's exhaust air l' stream through one of the main filter banks in the Supplementary Leak . Collection and Release System (SLCRS) and to the SLCRS Vent. l 1 4 i b section 4. MONITORING EFFLUENTS 4-13 l
Duquesne Light Company 1993 Annual Radiological Environmental Report J Areas in the Unit 2 Auxiliary Building (subject to radioactive contamination) are i 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 i and Unit 2 filter bank consists of roughing filters, charcoal filters,and pleated glass fiber type HFDA filters. The roughing filters remove large 1 particulates to prevent excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive lodine 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. 1 l 1 l 4-14 Section 4. MONITORING EFFLUENTS
TABLE 4-3 Radioactive Gaseous Waste Sampling and Analysis Program g E M NIMUM TYPE OF LOWER LIMIT OF GASEOUS SAMPLING A SIS ACWW DM, TION M RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/cc) x Principal Gamma 1 x 10 4 9 s P P , ,
- 1. Waste Gas N Storage Tank Each Tank Grab Sample Each Tank 1 x toe e. .
H-3 < e Principal Gamma W P P 1 x 10 4 @
- 2. Containment Emitters 9 Purge Each Purgeb Grab Each Purgeb 1 x 10 8
$c a H-3 C Sample y Principal Gamma :lE EO c
- 3. Ventilation 1 x 10 4 =
. Noc Mb Emitters 9 Systemsh us.c.e Grab Sample e Process Vent H-3 1 x 10 e p yg
-a
- a. 3 Wd 1-131 1 x 10-12 u
- b. Containment = S.
- g-G Vent
- Continuousf Charcoal Sample I-133 1 x 10-10 $ Qg Aux. Bldg. Principal Gamma 5 md
- c. wa Vents Continuoust Emitters 9 (I-131, 1 x 10-11 $ 5@
'g
- d. Cond. Polish.
Particulate Sample Others) y { y'j 3 Bldg. Vent y . 3s
- e. Decon. Bldg- Continuoust Composite Particulate Gross alpha 1 x 10'11 y @<
Vent Sample S $
- f. Waste Gas O
- e Vault Vent Continuousf Composite Particulate Sr-89, Sr-90 1 x 10-11 33 3
-* Sample C e as s oss 1 x 10-s Continuousf Noble Gas Monitor ,
o I y W - At least once per 7 days o M - At least once per 31 days
% O - At least once per 92 days ? P - Completed prior to each release m
2; w Zb A r.n
-- - -. ~ . - - - . . - .- .-- -- Duquesne Light Company 1993 Annual Radiological Environmental Report 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 ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
- f. The average ratio of the sample flow rate to the sampled stream flow 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 mear; 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 tt e 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.
4-16 section ( vcNiToRING EFFLUENTS
l Duquesne Light Company 4 1993 Annual Radiological Environmental Report l
- 3. Results 1
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 l were exceeded. These values have been reported in the Beaver Valley Power Station Semi-Annual Radioactive Effluent Release Reports for 1993. l l C. Solid Waste Disposal j 4 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 miscellaneous tools and equipment. These were disposed of as solid radioactive waste. The services of offsite vendors were used to segregate, incinerate, and super-compact the waste. The waste is 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. 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 i at the site. At Beaver Valley Power Station approximately 5,174 cubic feet of radioactive solid 4 waste was buried offsite in 1993. The forty-seven (47) shipments contained a total activity of 1,371 curies, 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. Section 4. MONITORING ERFLUENTS 4=17
Duquesna Light Company 1993 Annual Radiological Environmental Report i I Figure 4-8. Solid Waste Disposal Diagram t } j WAtJIOACTIVis SOf Un WASTE DISPOSAL ,
< c O
h / 4
/ 4 Compactor and "g Misc. Radioactive . .,
w Solid Wastes Drumming Station ,, O r
- ?$
g .3
'on noccr u ! Madioactive Waste = Sludge Solidify- m, [ j.
Discosal Evacorator .. ine Station ja u = J ix 1" munuman "O Spent Radioactive - Special Shipping u g( j j oo Resin Casks & Containers ' 00' -CYTON E3
- 3 FIGURE 4 SOLID WASTE DISPOSAL DIAGRAM i
e 1 i I
- l l
l I 4-18 section 4. MONITORING EFFLUENTS
I Duquesna Light Company 1993 Annual Radiological Environmental Report Section 5. ENVIRONMENTAL MONITORING PROGRAM l 1 A. Environmental Radioactivity Monitoring Program l t l
- 1. Program Description The program consists of monitoring water, air, soll, river bottoms, vegetation and
' fooderops, cows milk, 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) .l are included in parts 5-B through 51 of this report. 5-B - Air Monitoring 5-C - Sediments and Soils Monitoring j 5-D - Vegetation and Foodcrops f l 5-E - Cows Milk 5-F - Environmental Radiation Monitoring 5-G - Fish
> 5-H - Surface, Drinking, Well Waters and Precipitation 1 5 Estimates of Radiation Dose to Man i
J i a s y 4 s Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-1
l w lh i TABLE 5-1 rr 2 RADIOLOGICAL ENVIRONMENTAL MONITORING FilOGRAM -9 6 - o
.3 E (P
Analysis (b) Ss le Sector Miles Sample Point Description Semple Frequency p[ Y Type of Sample ~' Points ,g Contmuous Sampling Weekly Composite (d) Gross Beta. (C) 1-131 Meyer's Farm 29 ' Oz I. Asr Particulate 13 91 18 with sample Monthly Composite (d) Gamma -scan C and Radicted6ne 30 4 08 Shippingport, PA (S S ) Ir dustry PA collection at least Quarterly Composite (d) Sr.83 go h I 46 8 3 24 9 z 15 00 Midland PA (S S ) we*AfY Jg ^ r- 32 48(a) to 16 5 Weerton. WV (a) N!.
.C 5 80 Aliquippa. PA (S S ) m 'A 51 h 47 14 48 East Overpool. OH E >
j'a 4 7 62 Brunton's Farm O 27 87 Sherman's Farm
]
' 28 1 c l 5 290 3 81 Beaver County Hospital 3 In O O Quarterty(k) Gamma-Dose e C Contmucus {TLD)
,a tr 2 Direct Radiation 30 4 06 Shippingport. PA (S S )
Meyer's Farm Annually (k) Q ID 93 11 14 - h 46 3 25 fr4ustry. PA (Church) C 9.C (D a 05 Midland. PA (S S ) g O_ g
# 32 15 48(a) 10 18 5 Weerton WV (a) g go (D i
45 1 6 20 Raccoon Twp. PA , g r- ~ KennedV's Crnrs. y_, gp c l 51 5 80 Al64uippa. PA (S S ) East Uverpool. OH y
~3 47 14 48 3 !
( West Ovr. School 70 1 30 , S. O 80 8 84 Raccoon Park e g 81 9 39 Southside School Hanover Municipal Bldg 3 hg ; 82 9 7i g ID l 83 to 45 Miti Creek Rd (D k 14 11 26 Hookstown 3 l j 85 Hancock Co Children Home su 84 11 _ 85 12 58 P*s 8 & 30 Intersection ' [ 96 13 65 E. Overpool Cahills House t 92 12 30 Georgetown Rd V l 14 70 Calcutta Road O 87 l 15 31 Midtand He+ghts 3 i 88 89 15 47 . Ohioville , i ' 90 16 52 Fairview School 10 4 08 Sheppingport Boro. PA 45 5 22 Mt Pleasant Church 60 13 37 Haney's Farm j 93 16 13 Sunset Hills. Midland l 1 l _ _ _ _ % % , m.- ,m
- vtespa _ T- if- - ,- e m ..__ , __. --__-_ .____h.
e TABLE 5-1 i R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Sample Frequency Analysis {b) Type of Sample Sa to Sector Miles Semple Point Description , ,,, Points Quarterly @) Gamma-Dose 95 to 24 McCleary Rd. Hollie Williams Contmuous (TLD) 2 Direct Radiation Annuallyel 28 1 07 Sherman's Farm (contmg) 56 Brighton Twp School 71 2 72 3 32 Logan School Beaver County Hospital 298 3 8i 22 Potter Twp School y ; 73 4 Comm Coltenter Twp u) 74 4 88 G3 75 5 43 Holt Road Raccoon Twp School 76 8 38 58 Green Garden Rd (Wayne's) y 77 6 11 frons 59 78 7 7 23 Raccoon Mun. Bldg EOC ! y 27 7 8 42 40 Brunton's Farm Rt 18 & Rt 151 tu j 79 O- (D 15 14 33 Georgetown O IA Industry, PA ~ 46 1 99 3 2 2I 37 Pme Grove Rd and Doyle Rd Oh . 94 8 24 McCleary Rd, Wlison Weekly, intermittent Wee 6ty Sample from 1-131 g 40 49 f(a) 4 50 Arco Polymers 3 Surface Water Composste Samples 0) Arco only m l 21 14 13 Downstream (Midland) J&L ' 20 3 32 Station Discharge BVPS Collected Weekty Weekly Grab Samples 3<g ,o 2A 13 02 Downstream BVPS Outfatt 3 , , , m 14 48 East Overpoot (raw water) Only Gamma-scan O 3 5
@ Quarterly Composite Co 60. H-3 ,
h Sr 9. r 0 (D Daity Grab Sample
? - Only - Collected 3 m Weekty0) E
( 19 16 Meyer's Farm Quarterty Quarterly Gamma-scan, Gross 4 Groundwater 13 Beta, Gross Alpha. O o 14 11 28 Hookstown, PA 0 Z H-3 15 33 Georgetown, PA 3 k 15 it 3 Os Sh.ppingport Boro 3 13 M6dland, PA (Midland Water intermettent(e) Sample Weekly Com,msite of Gamma scan,1131 Drin6mg 4 84 N 5 Treatment Plant) Collected Weetly Daily Sample (d) i g unth Composite (d) Gross Alpha. O 5 Gross Beta East Uverpool, OH (East ( O 14 40 Liverpool Water Treatment Quart Composite (d) H-3. Co-60, Sr 89. 90 Plant) 13 Weebly Grab Sample G h 5 0$ Ot.C Training Bldg v 23 8n b C . ( 'w
i
?b i t
TABLE 5-1 m I te l Q~ RADIOLOGICAL. ENVIRONMENTAL MONITORING PROGRAM S m DLC "," Analysis (b) Sample Point Description Sample Frequency p
,r, Type of Sample S to Sector Miles m Semsannual Gamma-scan.
02 Downstream BVPS Outfall Semiannual Shorelme 2A 13 Gross Beta 3 6 Sediment Gross Alpha C 02 Vicenity SAPS Discharge 3 13 Uranium isotopec
' 49 3 32 Upstream S6de of Sr 89. 90 g Montgomery Dam (a) y r- Upstream side of 50 13 82 to New Cumberland Dam G3 f
Seartght's Dairy Weekly (f) Weebly sample from I-131 y 7 Milk 25 10 21 Seanght's only 3 h' a Biweekly (g) when Biweekly (grazing) Gamma-scan 3 Z animals are on a Monthly (indoors) Sr 89. 90 h O
- f-f 31, Cs-137 a
pasture, monthly at other times Il5 O m 96(*) to 7 10 3 82 Wmdsheimer Bruntori's Dairy (h) Gamma scan Sr-89,
$C g O, 27 Monthly O 29 3 83 Nicot's Dairy (h) 90.1-131, Cs-137 -
g y 0 (3D See Section 5 E for .
- BVPS Technscal Specif cation Table 312.t requires three (3) dairies to be selected on basis of highest potential thyroid dose using milch census data 03 40 specific for.nons sampled Fish 2A 13 02 Vicinsty of BVPS #1 Semiannual Composite of edible parts by specaestil Gamma. scan on edible hd 3 g 9 Stabon Discharge portions S. O Upstream Side of Montgomery Dam
'O 3 49(a) 3 47 3 D Annual at harvest of Comoosite of each Gamma-scan g 03 9 Food Crops 0g (Three locat6ons withm available sample species 1-13t on green gy (Shipp ) to 4 seafy vegetables 3 14 33 5 miles Selected by 5 (Georg ) 15 46 3 25 Company) ~
(tradus ) 4g(a) to 16 5 Weirton, WV D 2- 4D Monthty Monthly Gamma scan to 21 Searight's Dairy Farm to Feedstuff and 25 Quarterty Quarterty Composite Sr,90
]
Summer Forage 12 Core Samples Gamma-scan 3 Meyer's Farm Every 3 years (1991J 13 1i ea 3" Deep (3* Dia Sr 90 11 Sosi 1994, etc ) 4 0t Shippingport, PA 30 at each location Gross Beta 48 3 28 fndustry. PA Gross Alpha (approx 10' 32 15 0$ (North of Site) Mediand Uranium isotopic Weirton, WV radsus) 48(a) 10 16 5 5 50 Alequippa. PA 51 14 4S E. Uverpoca. OH 47 7 s2 Brunton's Dairy 27 , 22 s 03 South of BVPS Site 3 83 Nicol's Dairy 29A Weekfy grab sampaes Monthly Composite Gross p 4 06 Shippingport. PA t 12 Precipctation 30 when available of grab samples y scan ' 14 48 East Uverpoos. OH H 3, Sr-89. Sr-90 47 Quarterly Composite to 16 5 mrton, WV 48 t
Duquesne Light Company l 1993 Annual Radiological Environmental Report TABLE 5-1 ) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) Notes: ) (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 anal / sis 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. l (f) Weekly milk sample from Searight's Dairy is analyzed for I-131 only. (g) Milk samples are collected bi-weekly when animals are in pasture and monthly I at other times. [ Assume April- October for grazing season (pasture).] (h) The milk samples from 3runton's and Nicot's are collected once per month. (1). The fish samples will contain whatever species are available. If the available sample size permits, then the sample will be separated according to species , and compositing will provide one sample of each species. If the available size l 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. l (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 2A. A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5. ] (k) Two (2) TLDs are collected quarterly and annually from each monitoring I 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 possible.
- All air wmples are decayed for 72 hours before analyzing for Gross Beta.
Section 5. ENVIRONMENTAL MONITORING PROGRAM 55
Duquesne Light Company 1993 Annual Radiological Environmental Report
- 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 B through 5-H and an assessment of radiation doses are found in Section 5-1. Table 5-3 summarizes Beaver Valley Power Station preoperational rariges 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
- ~_.- -- - _ - .. .~ .. . .- . ~ . . .-. . . .-
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Far 11ty Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50-412
--4 -4 location of Factitty Deaver. Pennsvivanta Reporting Period Annual 1993 m Er (County. State) U
- F (D
Y M Y Analysts and Lower ' tmit Number of Medtum of Pathway Total Number of All Indicator Locations location with l{jahest Annual. Mean control locations Nonroutine rn Sampled of Analysis Detection " Mean (0 Name **Mean (0 "Mean (0 Reported E (LLD) ** Ra nge Distance and Directions "Ra nge " Range Measurements *" ; (Unit of Measurement) Performed 5 Weirton. WV No. 48 0 3 . Air I-articulate Gross (5201 2.5 16(520/520) 32. Midland. PA 16(52/52) 15(52/52) O @ @ and Radiotodine Beta (6.0-36) 0.8 mi NW (6.8-32) (6.6-31) g- 8 (X10-3pCl/Cu.M.) Sr-89 (401 5 IJD -- -- -- - g [ Sr-90 (40) 0.2 IlD -- -- -- -
- 2. [O I- 131tS20) 40 llD -- -- -- - S 'UE
-o.
O CL e C Gamma (120) 8 E us
~
S O$ Be-7 40 117(120/120) 32. Midland. PA 128(12/12) 111(12/13) 0 3 Q r (63-171) 0.8 ml NW (95-165) (63-150) g Qg
. r K 40 20 14(13/120) 48. Welrton. WV 35( t / .2) Same as o g m~
(8.2 35) 16.05 mi SSW -- Illgh location [h e O 3 Others Table V.A. IlD -- -- -- 8 2 V B* s <D < P A m - k-(D 8Z " O C 3 E--4 r-C O Nominal Lower Umst of Detection (LU>) O
** Mean and range based upon detectable measurements only Frattkm of detectable measurements at spectned locations is Indicated in parentheses (f) o **
- Nonroutine reported measurements are defined in Regulatory Guide 4 8 (December 1975) and the Deaver Valley Ibwer station spectncations .
2 0
?
O O
.n T>
C Y w
i l l Y. ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
b 6 u. Name of Factitty Beaver Vallev Power Stataan Unit I and 2 Docket No. 50 334/50-412 h location of Factitty Beaver. Pennsvivania Reporting Period Annual 1993 0-m m (County Statel 5 9 to a O z Analysis and lower Limit Number of C Medium of Pathway Total Number of A(( Indicator Imrattena location with Highest Annual Mean control locations Nonroutine
'$ Sampled of Analysis Detection " Mean 10 Name "Mean 10 "Mean (Q Reported y (Unit of Measurement)' Performed (LLD) " Range Distance and Disections" Range "Ra nge Measurements *" ,
r- Weirton. WV No. 48 e C @ O External Radiation Gamma (44) 0.05 0.161175/175) 84. Hancock County 0.20(4/4) 0.15(4/4) 0 W
; (mR/ day) (175 quarterly) 10.12-0.29) Children's Home (0.18-0.24) (0.14-0.17) >
3-O 8.5 ml SW 3
-m C Camma 0.05 O.14(44/44) 84. Hancock County 0.19(1/11 0.1 5(I / 11 0 m (44 annuall-10.07-0.191 Children's Home -- --
g, D Q 8.5 mi SW
- o. $
2 o.E C jm Feed and Forage I-131 (12) 0.01 11D -- --- One Sample - 3C (pct /g) Imration as c (dry weight) Sr-90 (4) 0.003 0.030(4/4) (0.005-0.056) 0 [K g g, o O 3 Camma (12) "E 3s Be 7 0.3 1.187 / 121 10.3 6-1.7) 0 $* g_ K-40 0.5 18tl2 /121 -- -- ~ 0 0 (12 29) @ V O Th-228 0.08 0.0812/12) -- -- -- O a 10.078-0.089) Others Table V.A. IID -- -- -- Nominal tower Limit of Detecuan (LLD)
** Mean and range based upon detectable rnessurements only Fraction of detectable measurements at spectned locations is indtrated in parenthe.es II)
'" Nonrouttne reported measurements are defined in llegulatory Gutde 4 8 (December 1975) and the Heaver Valley Power Station Spectnrations .
ENylRQNJiFJTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility IJrgy_stVallev Power Station Unit I and 2 Docket No. 50-334/50-112 l I tocation of Facility Deaver. P6i n,1,orda Reporting Period Annual 1993 g (County. Statel g o Number of Analysis armt Lower Limit Mnitum of Pathway Total Number of A!! Indtrator Locations location with litahest Annual. Mean "Mean 10 Control locations "Mean (O Nonroutine Reported Sampled of Analysts Detection " Mean (0 Name Measurements *** Distance and Directions "Ra nge "Ra nge (Lt.D1 "Ra nge (t!ntt of Measurementi Performed Montgomery Dam No. 49 a Fish Gamma (8) K 10 0.05 3 Of 8/8) 49. Upstream 3.3(4/4) Same as 0 $ w (pC1/g) Montgomery Dam (2.5-4.1) high locauon (wet weight) (2.4 4.11 y 4.7 mi NE a 0 3 0.006 0.0066(1/8) 02A. DVPS Discharge 0.0066(1/4) IlD C Cs- 137 0.2 mt W -- 1O 11D - -
- Ij 8
Others Table V.A. C S (D Om
-3 O
wc mo 7 m ** 3 S. OO O 3
- a u BE mx 3
n n m
? D . O T, ~1 ?
O
- Nomtnal lavwer Limit of Octection U.LD) Fraction of detectable measurements at spectMed locations is indicated in parentheses (Q
" *
- Mean and range baned upon detectabic measurements only.
*** Nonmuttne regwwted meagurements are defined in Itegulatory Gutde 4 ft (December 1975) and the Deaver Vaticy Ibwer Station Spertncations .
[ o o JF P C T _ . _ _ .
~_s_
Y a o ENVIRONMENTAL RADIOLOGICAL MONTTURING PROGRAM
SUMMARY
Name of Factitty Deaver Vallev Power Station Unit I and 2 Docket No. 50 334/50-412
- q 3 12watton of Facil:ty Deaver. Pennsvivanta Reporting Period Annual 1993 tu tr
- u. (County. Statel -
m m sg Y Analysts and Lower Limit Nu.nber of O Medium of Pathway Total Number of All Irxtigator locations Location with litchest Anntial Mean C9ntrol locations Nonroutine m { Sampled of Analysts (Unit of Measurement) Performed Detection (LLDI
" Mean (Q
" Range Name **Mean 10 Distance and Direcuons "Pange "Mean (0 "Ra n ge Reported Measurements *"
2
%etrton. WV No. 48 N Food and Garden e I 131 15) 0.006 11D --
F Crops (pCl/g) e e h (wet weight)) Gamma (5) W z >
~4 K-40 0.5 I.9(5/5) 10. Shippingport. PA 2.l(2/2) 1.6(1/l) 3 og i1.6-2.6) 0.8 mi ENE (1.6-2.6) --
O c h others Table V.A. tJD - -- -- 2 a o fnC O Em m O Ut y -a C Om D 5C tu O 7 ITI
- 3 O
- 5. O O 3 oD 5
O% 3
*L r
m V O
~1 Nominal lower Limet of Deter:6on (11D)
Mean and raryte based upon detectable measurements only Fraction of detectabic measurements at specifled inrat.nns is traitcated in parentheses til
* ** Nonroutine reported measurements are denned in Reputatory Culde 4 8 (MARCil 1975) and the Beaver Valley Ibwer Etation Specifications .
l l l______-_ _ - _ _ - _ _ _ _ _ _ _ . _ . _ . _ . . .__ _ - - - - - - - . - ---- - -- -
ENVIRONMENTAL RADIOLOGifAL MONIMRING PROGRAM
SUMMARY
Name of Fact'ity Deaver Vallev Power Station Unit I arwi 2 Docket No. 50-334/50-412 locanon of Facility Deaver. Pennsv!vania Reporting IYrtad Annual 1993 ICounty. State) -4 as T. Medium of Pathway Wts and I.nwer Limit (D t Total Number of Number of on Sampled of Analysis Detection All Indicator " Mean Locations location with Hasheet Annual ".tran Control locations Nonroutine (f) (Unit of Measurement) Performed (LLD) "Ra nge Name "Mean (0 **Mean (O Reported 6 Distance and Direcuons " Range " Range Measurements"* l Brunton Dairy No. 27 Milk l-131 1166) 0.2 IlD (pCl/l) F Sr-89 (133) 2 IlD . a
.. . to g
Sr-90 (133) I 2.5(133/133) 102. Ferry Dairy (a) u (0.93-9.0) 7.2(5/5) 1.8(19/19) 0 (6.0-9.0) (0.94-3.1) > 3 Camma (133) 3 c K-40 100 1451(133/133) ".'. O 110. Darnley Dairy (a) 1768(18/18) 1367(19/19) O (1220-2140) (1370 2140) (1290-1490) ME 8' Others Table V.A. IlD .. g o__3u O m U.-. g-O _. An O
""'3' m*
3 O io
? '3 9 Ou '
s
,, 3 3
x" i m E~ O @ 2 D C O
$-4 y la) Coat Dairy C
o
- Nominal tower Limit of Detection (LLD)
E " Mean and range based upon detectable measurements only.
-4 O
D *' Nonmuttne reported measurements are defined in Regulatory Culde 4.8 (December 1975) and the Deaver Valley Power Station Specificati
-Z O
v 2) O O as C Y i i =^ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . - _ _ _ = - - - - _ .- - - - - - _ - - _ _ _ _ - - - - _ - - - - . - -
Y a P@ ENV1ftONMENTAL RADIOLOGICAL MONITORINC PROCRAM
SUMMARY
tn 12me of Factitty Beaver Vallev Ibwer station Unti t and 2 Dorket No. 50-334/50-412 d a m 5 Imation of Factitty Beaver Pennwivanta Reporting Period Annua! 1993 O' 3 (County. State) _ P O Number of Y
$ Analysis and I.mwer Ltmit Control f ocatfons Nonrouunc Total Number of A!! Indkator incations Imatton with litshest Annumf Mean M $ Medium of Pathway of Analysis Detection " Mean (Q Name "Mean (Q "Mean (Q Reported y Sampled (Unit of Measurementi Performed (t_LD) "R ange Distance and Directions *
- R a n ge "Ra nge Me a sure me nt s*"
2 Montgarr. cry Dam No 49 C m 13(2/2) O
- f,ross (6) O3 1416/6) 2A. DVPS Discharge 19(2/2) 4 Sediment 0.2 mL W (18-20) (Il-141 Alpha (9 2-20) p (pct /g)
(dry weight) O Q h OI 35(6/6) 2A. DV0S Discharge 43(2/2) 3 6(2 /21 z Gross (61 0 2 mL W (38-48) (32-39) y Deta (26-48) 3 Q p 0 IJD C 0.2 3 Sr-89 (6) 2 0 04 IJD -
-- O $OC Sr 90 (6) g D
m g C Gamma (6) 2A. DVPS Discharge 2.2( t /2) O 82(t/2) O a@ {1 lle .7 02 1.213 / 6) (O 74 2.2) 0.2 ml W -- gg y -2 Oe c 2A. DVPS Discharge 14(2/2) 12{2/2) O K-40 0.5 12(6/6) (12-16) (8.1 16) 0.2 mL W (Il-13) Co-58 0.2 0.26(2/6) 2A. DVPS Discharge 0.2 6(2 / 21 11D 0 "$ m* (O.I8 0 33) 0.2 mL W (O.I8-0 331 3O 2A. DVPS Discharge 0.84(2/2) llD 0 iO Co 60 02 0 8412/6) (O. I 5- 1.5) 0.2 mL W (O. I 5- 1.5) gg 0 02 0.1 8(5 / 61 2A. DVPS Dtscharge 0.23(t /2) 0.19{(2/2) O 33 Cs- 137 (O.I7 0.20) mx (O.15-0 23) 0.2 mL W --
- 1. 9(2/2) O b
01 2. l(6/6) 2A. DVPS Discharge 2.2(2 /2) E Ra-226 02mLW (l.8-2.7) (1.8 2.0) (1.6-2 71 2) 2A. DVPS Discharge 1.4(2/2) 1.O(2 / 2) O m Th-228 0 02 1.l(6 / 61 O (1 0. l .6) 0.2 mL W (I.2-1.61 (0.87 1.0) O
~1 Others Table V A. IJD --
Nominal lower IJmit of Detection (LLD) Fraction of detectable measurements at specified locathms is indtrated in parentheses (Q
** Mean and range based upon detectable measurements nnly
*" Nonroutine reported measurements are defined in Regeelatory Guide 4 8 (December 1975) and the Deawr Valley Ibwer Station Specifications .
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Factitty Deaver Vallev Power Station Unit I and 2 Docket No. 50-334/50-412 -4 location of Facility Beaver. Pennsylvania Reporting Period Annual 1993 E (County. State) Y IV Analysis and Lower Limit Medium of Pathway Total Number of Number of Sampled of Analysts Detection All Indicator ** Mean Locations (0 location with litchest Annual Mean Control tocations Nonroutine Name (tJnit of MeasurementiPerformed (LLD) ."Ra nge "l%ean 10 **Mean (O Reported Distance and Directions "R ange " Range Mea su r em en t s"* a (D Drtnking (o I-131 (156) 0. 5 0.63146/156) 04. Mirliand. PA G) Water 0.68(25/52) - O (pCl/l) (0.22- 1.5) 1.3 mi WNW (0.22- 1.5) )> n Cross (36) 0.6 IJD -- -- a C Alpha mO Cross (36) Beta l 4.7(36/36) 04. Midland. PA 4.9(12/12) -- 0 DE W c (2.8-6.7) 1.3 mi WNW (3.6-6.7) 9 (D Camma (156) O (A Others Table V.A. IlD - -- -- [3 (o
- O -
Sr-89 (12] I.5 11D -- -- -- m~ Sr-90 (12) 0.5 IJD -- -- 3
- 5. O O
m 8 Co-60 (12) (a) 1 IlD -- ~ o3u g 3 11- 3 (1 2) 100 15012/12) (ISO 150)
- 04. Midland. PA 1.3 ml WNW 150(1/4) --
0 a$ 3 (D x Y -- 3 m
- W_
< D 5 O O V z
C O
- 3 z
-4
> (a) Co 60 analyzed by h!gh sensitivity method.
r-C O Z Nominal tower Limit of Detecuon (LLD) 3 o *
- Mean and range based upon detectable measurements only. I'raction of detectable measurements at spectned locations is indicated in parentheses (f) u * *
- Nonroutine reported measurements are defined in Regulatory Guide 4 8 (December 1975] and the Deaver Valley Power Station Specincations .
D O O D D C a Y
Y' a h un ENVIRONMEt(TAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
g h o Name of Facility tha Vallev Power Station Unit I and 2 Dorket No. 50-334/50-412 m g h location of Facility Beaver. Pennw!vania Reporting Period Annual 1993 m y (County. State) Y n O Numter of z Analysts and Lower Limit All indtrator Locations 1/ ration with litehest Annual Mean Control tocations Reported Nonroutine
.5 Medium of Pathway Total Number of **Mean 10 **Mean (Q 2 Detection ** Mean 10 Name ** Ra n ge Measurements ***
Sampled , of Analysts ** Ra nge Distance and Directioris **Ra nge t- (Unit of Measuremedt) Performed (Lt.Di Georgetown. PA No.15 , to to y 11. Shippingport Boro 3.6(1/4) llD W s Cross (161 2 3 611/16) -- 0.8 ml NE 1 a Groundwater y O (pCl/l) Alpha 0 6.4(4/4) 4.3(4/4) c 4.7(13/16) 14. Ilookstown. PA (1.0- 10) Gross (16) 'l 2.6 mI SW (4.3-8.41 8 Beta (1.0 10) su h m
,o }OC Gamma (16) 0 "a .
8n 100 43(1/16) 14. Hookstown. PA 4 311/41 IID g$ K-40 -- 2.6 mi SW s E (D ri r-Others TabicV.A. IlD su 6
-- ~1 II-3 (16) 90 UD m "*
3 I. OO O 3 s e e< E x e V O
.l
~
Nominal Luwer Ldiit n' Detecuan (LLD) Fraction of detectable measurements at specthed locations ss Indicated in parentheses (f)
*
- Mean and range based upon detectable measuremente nnly. h Valley fbwer Station Specincations ,
**
- Nonmuttne reported measurements are defined in Regulatory Guide 4.8 (December 1975) and t e Beaver
-_.__...._.._.._..m.. ._ m .-. - .4_...m.._-..--. - __m.. ___.._.m._ - . _ - .
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Faitlity Deaver Vallev Power Stauon Unit I and 2 Docket No. 50-334/50-412 q location of Farthly 13eaver. Pennsvivania Reporting Period Annual 1993 su (County. State) U_ (D Number of Y to Analysts and Lower Limit Medium of Pathway Total Number of All Indicator I.mcations Imcation with finchest Am==l Mean Control "Mean (0 locations Nonroutine Reported a Mean (0 Name "Mean (0 Sampled of Analysis Detection "Ra nge **Ra nge Measurements"* (LLD) "Ra nce Distance and Directions (Unit of Measurement) Performed Weirton. WV No.48 F 12(11/11) 0 , i 12134/34) 47. E. Liverpool. Of f 13(12/121 to Water Gross 134) 4.8 mi WNW (2.3-51) (4.8-22) to Precipitation Beta 12.3-51) GB (pCl/l) 3 Camma (34) 3 Same as high 0 c-40 92(28/34) 48. Wetrton. WV 95(I1/I1) He-7 16.05 mi SSW (53-143) location su O 152-205) su Others Table V.A. IJD -- a. g gi 3 i Sr-09 (12) 2 11D -- tD Sr-90 (12) 0.5 IJD -
-r ,
0 su c6
- 20. Shippine, port. PA 318(4/4) tJD 11 3 (12) 100 280(5/12) 0.6 mt ENE (190 670) 3 (130 670) 3 O 10 e O 3 "E
$ E O! : m in~ Z < 2) in m O U
- O k.
3 4 r-C O E e a t Nominal inwer Limit of Detecuon (LLIM Fractkn of detectable measurements at spectned locations is indicated in parentheses (0 O
- 2 *
- Mean and range bawd upon detectable measurements only.Nonrouttne reported measurements are denned in Itegulatory Culde 4.8 (Decemb
[
,u 8-C r
a
l i Y'
.A i
- i ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
--i l $ tu a3 Name of Factitty 11taver Vallev Power Station Unit I and 2 Dorket No. 50-334/50-412 (7
~
I (D Y location of Factitty Beaver. Pennsylvanta Reporting Period Annual 1993 m (County. Statel g 2 M !
$ l n '
O Number of 2 Analysts azul lewer LimitAll indicator Lormisona Imration with Hiehest Annual Mgan Control IAcations Nonroutine C Reported g Medium of Pathway Total Number of a Mean (1) Name "Mean (Q "Mean (O Sampled of Analysis Detection Dtstance and Directions " Range " Range Measurements"* , t
-4 (LLD) "Ra nge "o g
(Unit of MeasuremeAtl Performed Upstream - ARCO Chemtral No. 49.1 W f W g one sample 0 O' I-131 {52) 0.5 0.53(20/52) 49.1. Upstream. ARCO location Z Surface Water (0.23. l .4) Chemical 3 O IPCI/l] 5.0 mi ENE C p 0 su O Z 2 1.6ll / 48) 05. E. Liverpool. Oli 1.6(I/12) IlD O Gross (48) - 4.8 ml WNW - Alpha 3 02A. BVPS Discharge 7.2(12/12) 4.7(12/12) 0 $C g$ Cross (48) 1 5.8(48/48) (4.7-9.9) (2.9-8.51 (2.9- 16) 0.2 mi W -o . Beta , p C S 'O Camma (48) g I-gu es IlD -- r Others Table V.A. m -+ 7 2 ljD -- ' Sr-89 (16) {O O 3 Sr-90 (16) 0.5 UD - 3E S 3 Co-60 (16) (a) 2 IlD i 11202(5/16) 02A. BVPS Discharge 18567(3/4) 130(1/41 0 $x 11-3 (1 6) 100 g_ (130 290001 0.2 ml W (1700 29000) -- 73 to (a) Co 60 analyzed by high sensittvity method. T) O 3
- Nominal Lower Limit of Detection (LLD) Fraction of detectable measurements at spectned locations in Indicated in parentheses (Q
*
- Mean and range based upon detectable measuremente nnly.
' *** Nonrouttne reported measurements are defined in Hegulatory Guide 4 8 (December 1975] and the Heaver Valley Power Station SpectGeations .
I l Duquesne Light Company 1993 Annual Radiological Environmental Repori Table 5-3. Pre-operational Environmental Radiological Monitoring Program Summary I I i TABLE 5 3 , PRE-OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
l Name of Facl!!ty Beaver Valley Power Station Dor.ket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 f i (County, State) PRE OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 1975) Medium or Pathway Analysis and Total Number Lower Limit AllIndicator Locations
' "* " '** ' ** " **"' ""U" (Unit of a u ement)
Sediments Gross Alpha (0) - pCilg (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 i l
Cs-137 0.1 0.4 21/33 0.1 - 0.6 ZrNb-95 0.05 0.8 12/33 0.2 - 3.2 Co-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 0.21.8 Ru-106(b) 0.3 1.4 12/81 0.6 - 2.3 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 04 1/64 - Sr-90 (64) 0.05 0.3 48/64 0.1 - 1.3 , l U-234, 235, 238 (0) - - Gamma (64) - K-40 1.5 13 63/64 5 - 24 l 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 I Ru-106(b) 0.3 1.1 3/64 0.5-2 Others - < LLD l Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-17
Duquesne Light Company 1993 Annuel Radiological Environmental Report t I
)'
TABLE 5 3 f 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) Medium or Pathway Analyals and Total Number Lower Limit All Indicator Locations (un, o,'"a " < a 'v i a ' r- d ' o * aa - (') a -
.m..t)
Soil Gross Alpha (0) Gross Beta 1 21 8/8 16 - 28 pCl/g (dry) (8) (Core Samples) Sr 89 (8) 0.25 < LLD Sr-90 (8) 0.05 0.2 5/8 0.08 - 0.5 Gamma (8) K-40 1.5 13 8/8 7 - 20 Cs-137 0.1 1.2 7/8 0.2-2.4 Co 60 0.1 0.2 1/8 - Others - < LLD Surfac'e 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) - g pCill Gross Alpha (50) 0.3 0.6 4/50 0.4 - 0.8 Gross Beta (208) 0.6 3.8 208/208 2.3 - 6.4 Gamma (0) - - Tritium (211) 100 310 211/211 130 - 1000 C 14 (0) - Sr-89 (0) - Sr-90 (0) - Grourtd Water Gross Alpha (19) 0.3 < LLD 7 pCill Gross Beta (76) 0.6 2.9 73/75(a) 1.3 8.0 -( Tr. tium (81) 100 440 77/81 80 - 800 L Gamma (1) 10 - 60 < LLD i 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) . 1-131 (816) 0.04 0.08 2/816 0.07 - 0.08 ; Gamma (197) i ZrNb-95 0.005 0.04 122/197 0.01 0.16 Ru-106 0.010 0.04 50/197 0.02 - 0.09 Co-141 0.010 0.02 3/197 0.01 - 0.04 Ce-i44 0.010 0.02 44/197 0.01 - 0.04 Others < LLD l l 1 5-18 Section 5. ENVIRONMENTAL MONITORING PROGRAM i
J s Duquesne Light Company 1 1993 Annual Radiological Environmental Report - U 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. Pennsvivania Reporting Level CY 197/ 1975 (County, State) PRE,CPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 1975) -. Medium or Pathway Analysis and Total Number Lower Limit All Indicator Locations
< a +* e ~-- ' a i ai uo a m a (unit o,'2". ment) l-131 (91) 0.25 0.6 4/91 0.30.8 Milk Sr-89 (134) 5 7 4/134 6 - 11 pCi/l Sr-90 (134) 1 5.3 132/134 1.5 - 12.8 Gamma (134)
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 1.03.2 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 i i Others - < LLD
- LLD in units of MR - Lower end of useful integrated exposure detectability range for a passive radiation l l
detector (TLD). (a) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium ) content. Not considered typical groundwater sample). (b). may include Ru-106, Ru-103, Be-7. , 1 i l Section 5. ENVIRONMENTAL MONITORING PROGRAu 5-19
l Duquesne Light Company 1993 Annual Radiological Environmental Report Table 5-4. Typical LLDs For Gamma Spectrometry I TABLE 5-4 TYPICAL LLDs " FOR GAMMA SPECTROSCOPY j Hk **"' Air Particulates Vegetation Fish l (PCI) (pCllkg dry) (pCilg wet) (p g; 7) pCilg 50 20 200 0.2 0.02 Be-7 80 50 400 0.4 0.4 K-40 20 200 0.2 - 0.2 Cr-51 50 5 2 20 0.02 0.02 Mn-54 5 2 20 0.02 0.02 Co-58 10 3 40 0.04 0.04 Fe-59 5 2 20 0.02 0.02 Co-60 10 5 40 0.04 0.04 Zn-65 5 3 40 0.04 0.04 Zr/Nb-95 5 3 30 0.03 0.03 Ru-103 50 20 200 0.2 0.2 Ru-106 Ag-110M 10 5 50 0.05 0.05 l-131 15 4 200 0.2 0.2 l Te-132 8 4 20 0.02 0.02 l-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 10 3 200 0.2 0.02 Ba-La-140 10 20 100 0.1 0.1 Ce-141 40 10 200 0.2 0.2 Ce-144 80 10 100 0.1 0.1 Ra-226 10 10 20 0.02 0.02 Th-228 At time of analysis (DLC Contractor Lab). NOTE: Lower Level of Detection is defined in Beaver Valley Power Station Technical Specifications. 5-20 Sectron 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1993 Annual Radiological Environmental Report B. Air Monitoring
- 1. Characterization of Air and Meteorology 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. I
- 2. Air Sampling Program and Analytical Techniques
- a. Program The air is sampled for gaseous radiciodine 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 radiolodine sampling. Samples are collected for analysis l on a weekly basis. l The charcoal is used in the weekly analysis of airborne I-131. The filters 1 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 l
Gross Beta analysis is performed by placing the filter paper from the l 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. Radioiodine (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. , Section 5. ENVIRoNVENTAL MONITORING PRoGRAu 5-21
i Duquesne Light Company 1993 Annua Radiological Environmental Report i i , Figure 51. Air Sampling Stations , i ) l i i N um ** )
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5-22 Section 5. ENVIRONMENTAL MONITORING PROGRAM
~ ___ _
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l Duquesne Light Company 1993 Annual Radiological Environmental Report Strontium-89 and Strontium-90 activities are determined in quarterly composited air particulate filters.. Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The ' mixture is then filtered. Half of the filtrate is taken for strontium analysis , and is reduced in volume by evaporation. Strontium is precipitated as l 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 oxalato. The yttrium oxalate ; , l 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 2 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. , 4
- 3. Results and Conclusions l
A summary of data is presented in Table 5-2. 4
- a. Airborne Radioactive Particulates
- A total of five hundred twenty (520) 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. I 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 thirteen (13) 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 i Station did not contribute to any increase in air particulate radioactivity l during 1993.
- b. Radiciodine A total of five hundred twenty (520) weekly charcoal filter samples were an'alyzed 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 radiciodine during 1993. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-23
P ! u, n 2
- 3 6 y O
u AVERAGE CONCENTRATION OF GROSS BETA IN AIR PARTICULATES - 1993 ' l m _ . . .
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Duquesne Light Company 1993 Annuct Radiological Environmental Report l C. Monitoring of Sediments and Soils (Soll Monitoring is required every 3 years and was required in 1991) a
- 1. Characterization of Stream Sediments and Soils 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
] 4 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.
Soll samples were not collected during 1993. The next set of samples will be taken in 1994. 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, strontium, and the gamma-emitting radionuclides,
- b. Analytical Procedures J 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. 5 Gamma analysis of sediment or soll is performed in a 300 ml plastic bottle i which is counted by a gamma spectrometer. I i i i 1 6 i
- Section S. ENVIRONMENTAL MONITORING PROGRAM 5-25
f
- Duquesne Light Company l
' 1993 Annual Radiological Environmental Report 1 l 5-3. Environmental Monitoring Locations - Shoreline Sediments and Soil 4 Figure l I j s -m 1-C#EL ,E :: WEN's . i 1 I sea @l COWIM l l
') l
- ( ,,
SArdo([ 80I%* '.0C A"04 2A ;Cwestream SIPS Cut8 sil M Og m ' M Ju=***y *,N' , q MA , ( , i k.]y- ,/ f ' 49 45tream Sice of "Crtgomery Oam *"g
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- h*r l 29A Nicnol's Dairy 9 'I
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.l I t ,j, - 30 Snicoin9 port. PA li A7 48 M ;. . OH E. Liverpool weirton, W,vA. 1) ir { ., W) ' . 51 Aligwtope, PA ensi db i 4 * .... ,R.'^'%J .,, J ..c--... . .., 1 h 9 4 n, 6, ( ,
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. SHORELINE SEDIMENTS AND S0IL
- %. s I
+ 5-26 Section 5. ENVIRONMENTAL MONITORING PROGRAM
I Duquasne Light Company 1993 Annual Radiological Environmental Report 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. l Calcium and strontium are precipitated as phosphates, collected by l vacuum filtration, then dissolved in nitric acid. Strontium is separated by precipitating Sr(NO3): 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 performed, followed by addition of stable yttrium carrier and a minimum 5-day period for Y-90 ingrowth. Yttrium is then precipitated as hydroxide, I is dissolved and re-precipitated as oxalate. The yttrium oxalate is l mounted on a nylon planchet and is counted in a low level beta counter to l [ Infer Sr-90 activity. Sr-89 activity is determined by precipitating SrCOs l l from the sample after yttrium separation. This precipitate is mounted on a 8 nylon planchet and is covered with an 80 mg/cm aluminum absorber for low level beta counting.
- 3. Results and Conclusions A summary of sediment and soll analysis is presented in Table 5-2.
- a. Sediment A total of six (6) samples were analyzed for gross alpha and gross beta. l l Results were comparable to previous years.
A total of six (6) samples were analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 was detected. 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 l found in three samples. Small amounts of Cs-137 from previous nuclear weapons test were found in five 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 l 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 l authorizing radioactive discharges, are adequate and that the l environmental monitoring program is sufficiently sensitive. f Section 5. ENVIRONMENTAL MONITORING DROGRAM 5-27
Duquesne Light Company 1993 Annual Radiological Environmental Report D. Monitoring of Feederops and Fooderops
- 1. Characterization of Vegetation and Foodcrops Accordir.g to the 1992 statistical summary of the Pennsylvania Department of Agriculture, there were approximately 570 farms in Beaver County. The total value of farm crops and livestock was $17,929,000. The principal source of revenue was in dairy products which were estimated at $7,969,000. Revenues from other farm products were estimeted as follows:
d Field Crops $1,536,000 , Fruits $373,000 Horticulture and Mushrooms $3,521,000 Meat and Animal Products $3,839,000 Vegetables and Potatoes $468,000 Poultry Products $78,000 The total land in Beaver County is 279,020 acres. Approximately 147,900 acres are forested land and 59,063 acres are pasture and crop land.
- 2. Sampling Program and Analytical Techniques
- a. Prograra Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 5-4. Each sample is analyzed by gamma spectrometry. The monthly samples are composited into a quarterly sample which is analyzed for Sr-90.
4 A land use census was performed July 1993 to locate the nearest residence and nearest garden of greater than 500 square feet producing fresh leafy vegetables within a five (5) mile radius of the site. See Table 5-5 for results. Foodcrops (vegetables) were collected at garden locations during the summer of 1993. Leafy vegetables, i.e., cabbage were obtained from i I Shippingport, Georgetown. Industry, PA and Weirton, WV. All samples were- analyzed for gamma emitters (including 1-131 by gamma spectroscopy). E i 5-28 Sect:on 5. ENVIRONMENTAL MONITORING PROGRAM l
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$ FEEDCROP AND FOODCROP LOCATIONS 5
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_ _ _ .. _ . = . . __ . . _ _ . . 1 Duquesne Light Company 1993 Annual Radiological Environmental Report 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 rni 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 5 0.42 mi E 2.16 mi E 6 0.87 mi ESE 1.74 mi 6SE 7 1.10 mi SE 1.25 mi SE 8 1.10 mi SSE 2.84 mi SSE 9 1.40 mi S 2.16 mi S 10 0.80 mi SSW 1.53 mi SSW 11 1.46 mi SW 1.67 mi SW 12 1.46 mi WSW 1.46 mi WSW 13 2.27 mi W 2.27 mi W 14 2.77 mi WNW 2.77 mi WNW l
15 0.91 mi NW 0.92 mi NW 16 0.91 mi NNW 1.10 mi NNW
' Direction and Distance from Midpoint between Reactors 5-30 Section 5. ENVIRoNVENTAL MONITORING PROGRAM
l Duquesna Light Company l j 1993 Annual Radiological Environmental Report
- b. Procedures Gamma emitters, including I-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 5-C.2 after drying, weighing and ashing the sample. ; Rad!oiodine (1-131) is determined by radiochemistry. Stable iodide carrier l is first addcd to a chopped sample which is then leached with sodium l 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 iodine with hydroxylamine hydrochloride and is extracted into chloroform, it is then back-extracted as iodide into sodlum bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
- 3. Results and Conclusions A summary of data is presented in Table 5-2.
- a. Feed l
A total twelve (12) samples were analyzed for 1-131. No detectable l concentrations were found. A total of four (4) samples were analyzed for Sr-90. Small amounts of i Sr-90 from previous nuclear weapons tests were found in all samples. l 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 five (5) samples were analyzed for 1-131. No detectable concentrations were found.
l A total of five (5) samples were analyzed by gamma spectrometry. i l Naturally occurring K-40 was found in all samples. l ! l
- 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 l Section 5. ENVIRONMENTAL voNIToRING PROGRAM 5-31)
l Duquesne Light Company 1993 Annual Radiological Environmental Report 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 performed within eight (8) days of sampling.
Detailed field surveys are performed during the grazing season to locate and enumerate milch animals 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. ,,npling 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 dairies, which represent the highest potential milk pathwn:y for radiciodine 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 Figure 5-6 and described below.
"* ' Direction and Distance from Collection Midpoint between Reactors Period An als Searight 43 Cows 2.2 miles SSW Jan. - Dec.
25 27 Brunton 93 Cows 7.3 miles SE Jan. Dec. 29A Nicol 73 Cows 8.0 miles NE Jan. - Dec. Windsheimer 46 Cows 10.3 miles SSW Jan. - Dec. 96 36 Cows 3.83 miles WSW Jan. - Dec. e 109" Soissen 110" Darnley 6 Goats 4.24 miles WSW [D Ferry, 3 Goats" 3.3 miles SE Aug. - Oct. 102" Ambrose 30 Cows 3.86 miles WSW March 105" 106" Conkle 29 Cows 3.75 miles WSW Jan. Dec. Milk Usage - Home Only. Highest potential pathway dairies. 5-32 Section 5. ENVIRoNUENTAL MONITORING PROGRAM
- Duquesne Light Company . 1993 Annual Radiological Environmental Report Figure 5-5. Beaver Valley Power Station Milch Animal Census
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Duquesna Light Company 1993 Annual Radiological Environmental Report l Figure 5 8. Environmental Monitoring Locations Milk MILK n u a ..m ( SAMPLE i suwa conm 1 ) l V' SITE LOCATION i 25 Seabright l
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l 1 Duciuesna Light Company 1993 Annual Radiological Environmental Report The sample from Searight Dairy was collected and analyzed weekly for radiciodine using a procedure with a high sensitivity. Samples from each of sne other selected dairies were collected monthly when cows are indoors, and bi-weekly when cows are grazing. This monthly or bi-weekly 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 Radiolodine (1-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low-level beta 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 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. Strontium-89 activity is determined by precipitating SrCOs 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 ) 1993. All 1-131 activities in milk were below the minimum detectable level. A total of one hundred thirty-three (133) 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 viere within the normally expected range. A total of one hundred thirty-three (133) samples were aralyzed by gamma spectros, copy. Naturally occurring K-40 was found in ad 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 preoperational program. These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in milk in the vicinity of the site. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-35
Duquesne Light Company 1993 Annual Radiological Environmental Report F. Environmental Radiation Monitoring
- 1. Description of Regirnal Background Radiation and Sources 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 partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and sorne coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny 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 1993 indicated that background radiation continued in this range.
- 2. Locations and Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs). ,
In 1993 there were a total of forty-four (44) off-site environmental TLD locations. The locations of the TLDs are shown in Figure S-7 through Figure 5-10. Thirteen (13) locations also have QC Laboratory TLDs. Both laboratories use calcium sulfate dysprosium, (CaSO4 :Dy) in Teflon matrix. The calcium sulfate (CaSO4 :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, when 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. 1 l l l I 5-36 Section 5. ENVIRONMENTAL MONITORING PRoGRAV
l Duquesne Light Company 1993 Annual Radiological Environrnental Report
- 3. Results and Conclusions Data obtained with the contractor TLD (CaSO.:Dy in Teflon) during 1993 are summarized in Table 5-2, and the quality control TLD results are listed in Table 3-1.
The annual exposure rate of all off-site TLDs averaged 0.154 mR/ day in 1993. As in previous years, there was some variation among locations and seasons as would be expected. Two TLDs were lost in the field during the year. In 1993, ionizing radiation dose determinations from TLDs averaged approximately 56.2 mR for the year. This is comparable to previous years. , , There was no evidence of anomalies that could be attributed to the operation of l the Beaver Valley Power Station. The TLDs confirm that changes from natural i radiation levels, if any, are negligible. t l l l i Section 5 ENVIRONMENTAL MONITORING PROGRAM 5 _ _ _ __ _ . _ . - __ _ - . . - - . _. _ _ . _ _ . . . .
I Duquesne Light Company l 1993 Annual Radiological Environmental Report l l l Figure 5 7. TLD Locations - Northwest Quadrant ( 1 FIGURE 5 TLD LOCATIONS ' ' ' NORTHWEST QUADRANT ,m,.,, ,5 i BEAVER VALLEY POWER STATION
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Duquesne Light Company 1993 Annual Radiological Environmental Report Figure 5-8. TLD Locations Northeast Quadrant Beaver Valley Power Station FIGURE 5 TLD LOCATIONS
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Duquesne Light Company 1993 Annual Radiological Environmental Report Figure 5-9. TLD Locations . Southeast Quadrant
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5-40 sectron 5 ENVIRONMENTAL MONITORING PROGRAM l
Duquesne Light Company 1993 Annual Radiological Environmental Report Figure 5-10. TLD Locations Southwest Quadrant Beaver Valley Power Station a a >
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l k Duouesne Light Company
.1993 Annual Radiological Environmental Repcrt l
J G. Monitoring of Fish ! l l 1. Description i During 1993, fish collected for the radiological monitoring program included carp, catfish, sucker and freshwater hum.
- 1 l 2. Sampling Program and Analytical Techniques I i
! a. Program l
! Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Momgomery 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 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which - utilizes a high resolution germanium detector.
- 3. Results and Conclusions j A summary of the results of the fish monitoring data is provided in Table 5-2.
A total of eight (8) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was found in all samples. One of four fish samples at the Beaver Valley discharge indicated Cs-137 near the lower limit of detection. The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River fish population, l 1 l 5-42 Section 5. ENVIRONMENTAL MONITORING PROGRAM ) l
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l Duquesne Light Company 1993 Annual Radiological Environmental Report 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.
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 Ohio River as a potable water source is Midland Borough Municipal Water 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
!ndustries 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.
l 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 I well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm. I In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The record mean annual precipitation for the area is 36.40 inches based on 1972 to 1990 data collected at the Pittsburgh International Airport. I l l l l l l 5-44 Section 5. ENV:RoNMENTAL MONITORING PROGRAM
l Duquesne Light Company 1993 Annual Radiological Environmental Report
- 2. Sampling and Analytical Techniques
- a. Surface (Raw River) Water The sampling program of river water includes five (5) sampling points along the Ohio River. Raw water sarnples are normally collected at the East Liverpool (Ohio) Water Treatment Plant [ River Mile 41.2] daily and composited into a monthly sample. Weekly grab samples are taken from the Ohio River at the following locations: upstream of Montgomery Dam
[ River Mile 31.8]; and near the discharge from the Beaver Valley Power ! Station [ River Mile 35.0]. Two automatic river water samplers are at the f following locations: Upstream of Montgomery Dam [ River Mile 29.6]; and I at J&L Steel's river water intake [ River Mlle 36.2]. The automatic sampler takes a 20-40 mi sample every 15 minutes and samples are collected on a weekly basis. The weekly grab samples and automatic water samples are In addition, a composited into monthly samples from each location. quarterly composite sample is prepared for each sample point. l The weekly composites from the automatic river water sampler upstream l at Montgomery Dam are analyzed for I-131. l t The monthly composites are analyzed for gross alpha, gross beta, and gamma emitters. The quarterly con posites 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.
- b. Drinking Water (Public Supplies)
Drinking (treated) water is collected at both Midiarid (PA) ar.d 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. A weekly grab sample is also taken at the DLC Training Building in Shippingport, PA. The weekly sample from each location is analyzed by gamma spectroscopy. The weekly samples are also analy.ted for 1-131. Monthly composites of the weekly samples are analyzed for gross alpha, 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. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-45
Duqunsno Light Company l 1993 Annual Radiological Environmental Report
- c. Ground Water Grab samples were collected each quarter from each of four (4) well 1 locations (see Figure 5-12) within four (4) miles of the site. These locations are: )
I One (1) well at Shippingport, PA One (1) well at Meyer's Farm (Hookstown, PA) J 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,
- d. Precipitation Precipitation is collected at Shippingport, PA, East Liverpool, OH and Weirton, WV. Precipitation when available is collected each week and then composited into monthly and quarterly samples. The monthly samples are analyzed for gross beta and gamma emitters and the quarterly composites are analyzed for H-3, Sr-89 and Sr-90. Locations of each sample point are shown in Figure 5-12.
i l l 5-46 Section 5. ENVIRONVENTAL MONITORING PROGRAM
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- e. Procedures Gross alpha and cross beta activities are determined first by evaporating one liter of the sample on a hotplate. The residue is mounted and dried l on a 2-inch stainless steel planchet. The sample is counted in a low background, gas flow proportional counter. Self absorpJon corrections are made on the basis of sample weight. l l
Gamma analysis is performed on water sample by loadint, one liter of l ! sample into a one liter Marinelli container and counting :: nigh resolution germanium gamma spectrometry system. Strontium-89 and 90 are determined on water samples by a procedure similar to that described in S-C.2 except that the leaching step is eliminated. Cobalt-60 is determined with a sensitivity of 1 pCl/ 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. Tritium is determined in water samples by liquid scintillation counting. l Radiolodine (I-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
- 3. Results and Conclusions l
A summary of results of all analyses of water samples (surface, drinking, ground and precipitation) are provided by sample type and analysis in Tabie 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 detected in one of the samples at a level comparable to preoperational values. 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.
5-48 Section 5. ENVIRONMENTAL MONITORING PROGRAM
l l 1 Duquesno Light Company 1993 Annual Radiological Environmental Report 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 disch'rge area and are attributable to i station releases. The highest tritium resub were noted, however, to correspond to shore samples taken when mixiag zone sampling by boat , was not possible. All other samples taken upstream and downstream l were within preoperational levels. The activity found in the station l discharge area is consistent with station data of authorized radioactive i discharges and were within limits permitted by the NRC license. A total of forty-eight (48) samples were analyzed by gamma spectrometry, i No gamma emitting radionuclides were detected. , A total of fifty-two (52) samples were analyzed for I-131 using a highly sensitive technique. Trace levels of I-131 were measured in twenty (20) of the weekly samples. The results were slightly above the minimum 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 l I variability in the analyses results of very low levels of activity.
- b. Drinking Water l l
( A total of thirty-six (36) samples were analyzed for gross alpha and gross l beta. All results were within a normal range. i l A total of twelve (12) samples were analyzed for H 3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-60. No Sr-89, Sr-90, or Co 60 ! weie dalected. Tho K-3-data were wiun me picoperational range j indicative of normal environmental levels. A total of another one hundred fifty-six (156) samples were analyzed by gamma spectrometry. A total of one hundred fifty-six (156) samples were analyzed for 1-131 using a highly sensitive technique. Trace levels of I-131 were measured in j forty-six (46) of the weekly samples. The results were slightly above the minimum detectable activity. The positive results were detected at 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 expected variability in the analyses results of very low levels of activity.
- c. Ground Water l A total of sixteen (16) samples tiere each analyzed for gross alpha, gross l beta, H 3 and by gamma spectrometry. One sample had alpha activity near the detection limit. No H-3 activity was detected in any of the samples.
The gross beta results are comparable to preoperational ranges. No gamma emitting radionuclides were detected. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-49 l
Duquesne Light Company 1993 Annual Radiological Environmental Report
- d. Precipitation l A total of thirty-four (34) samples were analyzed for gross beta. All results were within a normal range.
l A total of twelve (12) samples were analyzed for H-3, Sr-89 and Sr-90. Five (5) positive tritium results detected were within normal levels. No Sr-89 or Sr-90 was detected. A total of thirty-four (34) samples were analyzed by gamma spectrometry. NL:urally occurring Be-7 was detectec' in twenty-e!ght (28) samples. 1
- 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, weli waters or precipitation. The few positive results which could be attributable to authorized releases from the Beaver Valley Power Station are characteristic of the effluent. These results confirm that the ctation 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 oy members of the public.
4 , 1 5-50 Section S. ENVIRONMENTAL MONITORING PROGRAM
l ! ! Duquesns Light Company 1993 Annual Radiological Environmental Report i Estimates of Radiation Dose to Man l.
- 1. Pathways to Man - Calculational Models The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using codes for the ARERAS/ MIDAS computer system equivalent to NRC computer codes XOQDOQ2, GASPAR, and LADTAP. Dose factors listeo in the ODCM were used to calculate doseb 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 l 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 l l analysis. When the activity of noble gas was below detection sensitivity, either the inventory based on its MDL or an appropriate but conservative ratio to either l measured activity of Kr-85 or Xe-133 was used. Meteorological data collected by l 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 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 obtained from the Beaver Valley Power Station Environmental Statement or l i Regulatory Guide 1.109. Pathways, which were evaluated, are drinking water, fish consumption, shoreline recreation, swimming, and boating. 5-51 Secon 5. ENVIRONMENTAL MONITORING PROGR AM
Duquesne Light Company 1993 Annual Radiological Environmental Report
- 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 r.1aximum individual. Incluoed in this table is a breakdown of a 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 limits were clarified to be reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR < art 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 Technical Specification reactor limits by a factor of two (2).
1 i l 5-52 Section 5. ENVIRONVENTAL MONITORING PROGRAM t
m . _ _ . . ._ - _ _ . _ . ._ _ . _ . _..._ .- ._ ~.-. . .m. . - m. .._.-_-_____,.-m.___ . _ _ . . .- _.-_ . . - . _ _ - t TABLE 5-6 Radiation Dose to Maximum Individuala, mrem /yr - Liquid Releasesh WHOLE o'- PATHWAY SKIN ORGAN THYROID BONE BODY O M 582 0 N08 0.N3 3 Fish Consumption N/A (Child) (Adult) E
* (Teen) (Liver) (Adult) 0.00194 0.00194 0.0000528 0.00186 k-3 Drinking Water N/A O W 0.000039 0.000033 0.000033 - 0.000033 3 0.000039 6 N Shoreline Activit.ies TM (T W (S W (T W (T M (TW r E 0.000568 0.00200 E- EO 0.000039 0.00246 0.00199 MAWU (Child) (Liver) (Child) (Child) (Child)
,gg gU (Teen)
E -S , TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSUREc i o e E EC Ambient Gamma Radiation . 58 - _t. Ee
- g m -+
Radionuclides in Body 40
* $h W h o3 S
Global Fallout <1 7 gE [n E $ Radon 198 i { g f ;U 3 TOTAL mrem : 296 { .@ c m O
- 3 a Located at Midland Drinking Water intake h
b Total liquid releases are from Site (combined Units 1 and 2) y c National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of ionizing Radiation", BEIR Report. 2 1990
- 5 E
8 E c E
. - - . _ . .. _ . - . . _ - . . . . _ . . .~ _ .-. . - - . .
1 l Duquesna Light Company 1993 Annual Radiological Environmental Report s , a Table 5-7. Results of Calculated Radiation Dose to Man Uquid Releases J TABLE 5-7 1 i Results of Calculated Radiation Dose to Man - Liquid Releases
"*I*"* E** BVPS Annual Percent of Hypothetical Real ""' """'I Organ Individual
' mrem Limit
- mrem TOTAL BODY 0.00185 6.0 0.031 Adult 0.00128 6.0 0.021 Teen 0.00200 6.0 0.033 Child 0.00182 6.0 0.030 infant i ANY ORGAN 1
0.00203 (Liver) 20.0 0.0102 j Adult 0.00167 (Liver) 20.0 0.0083
! Teen 20.0 0.0123 i Child 0.00246 (Liver) 0.00198 (Thyroid) 20.0 0.0099 infant l
4 Maximum Total Body Dose - Caosule Summary i mrem i 1993 Calculated 0.00200 - Final Environmental Statement 3.5 i Hiahest Oraan Dose f i 0.00246 1993 Calculated . Final Environmental Statement 4.7 l 4 1
.~ 1 4
4 4 l 1 1 1 5-54 Section 5. ENVIRONMENTAL MONITORING PROGRAV
l 1 Duquesne Light Company 4 1993 Annual Radiological Environmental Repor? {
\
l c. Population Dose i The 1993 calculated dose to the entire population of almost 4 million 7 people within 50 miles of the plant was: 4 d Large sotope ! Organ Man-Millirems TOTAL BdDY 135 H-3 132 mrem i
< THYROID 138 H-3 132 mrem .
( Results of Calculated Radiation Dose to Man - Atmospheric Releases j 3. i 1 The results of calculated radiation dose to the maximum exposed individuals for j BVPS airborne radioactive effluents during 1993 are provided in Table 5-8. The j 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 !
j 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 Techn.ical Specification reactor limits by a factor of two (2). The results show compliance (
with the BVPS annual limits. j' i' I i i 2 j .. 4 T Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-55
Duquesne Light Company 1993 Annual Radiological Environmental Report -
- 4. Conclusions 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 0.00012% of the annual background.
The calculated doses to the public from the operation of Beaver Valley Power Station - Unit i and 2, are below BVPE annual limits and resulted in only a small incremental doce to that which area residents already ' received as a result of natural background. The doses constituted no meaningful risk to the public. t i (
\
l l I 5 56 Section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1993 Annual Radiological Environmental Report Table S 8. Results of Calculated Radiation Dose to Man Atmospheric Releases TABLE 5-8 l Results of Calculated Radiation Dose to Man - Atmospheric Releases i MAXIMUM 50-MILE BVPS OF POPULATIOP OSURE P ORGAN ANI4UAL LIMIT ANNUAL LIMIT ' DOSE INDIVIDUAL ** mrem man rem 0.488 30 1.63 1.241 TOTAL BODY 0.488 30 1.63 0.687 SKIN 0.488 30 1.63 1.263 LUNG 0.574 30 1.91 1.421 THYROID 1 l l l l f 1 l I i 1 Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-57
APPENDIX i Contractor Laboratory EPA Interlaboratory Comparison Program
, Al-1
)
i EPA Interlaboratory Comparison Program l Teledyne isotopes participates 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 1993 data ] summary tables are presented for isotopes in the various sample media l applicable to the Duquesne Light Company's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems. encountered in a few cases and the steps taken to prevent reoccurrence. i 4 4 1 h l 4
.i
" ss ^
._ . . _. m . - _ _. _ ._ . _ . - _ . _ _ _ . _ - . _ . . .- .m.m _ . _. -- _ _ . _ . - _ _ _ _ . _ _ _ _ . . _ . . _ . .._,_ __ _ . _ _ . DUQUESNE LIGHT COMPANY EPA INIERLABORATORY COMPARISON PROGRAM 1993 (Page 1 of 3) TI Norrn Dev. " Warning EPA Date TI Malled Date EPA EPA Results(b) (Known) "* Action Preparation Re sults Issued Results Media Nuclide Results(a) Sr-89 15.0 i 5.0 12.67 i 1.15 -0.81 01/15/93 03/23/93 04/26/93 Water -0.58 Sr-90 10.0 i 5.0 8.33 i 1.15 Gr-Alpha 34.0 1 9.0 17.33 i 1.15 -3.21 (c) 02/22/93 05/10/93 Water ** (d) 01/29/93
- Gr-Beta 44.0 1 5.0 52.00 1 1.00 2.77 Water I-131 100.0 i 10.0 106.67 i 5.77 1.15 02/05/93 03/04/93 04/20/93 Water Ra-226 9.8 i 1.5 7.67 i 0.12 -2.46 (e) 03/05/93 04/30/93 06/10/93 18.5 i 4.6 19.33 i 2.31 0.31 Ra-228 Water Gr-Beta 177.0 1 27.0 150.0 1 0.00 -1.73 04/20/93 07/02/93 08/16/93 41.0 1 5.0 35.33 i 1.53 -1.96 Sr-89 Sr-90 29.0 i 5.0 27.33 i 0.58 -0.58 Co-60 39.0 1 5.0 40.67 i 3.51 0.58 Cs-134 27.0 1 5.0 23.67 1.53 -1.15 Cs-137 32.D i 5.0 34.33 1 2.08 0.81 Gr-Alpha 95.0 i 24.0 94.33 1.15 -0.05 Ra-226 24.9 i 3.7 19.00 i 1.00 -2.76 (c)
Ra-228 19.0 i 4.8 18.33 1 0.58 -0.24 Water H-3 9844.0 t 984.0 9306.67 1152.75 -0.84 06/04/93 07/02/93 8/16/93 Water Co-60 15.0 i 5.0 16.33 i 1.53 0.46 06/11/93 07/23/93 08/27/93 103.0 i 10.0 121.33 1 2.08 3.18 "* (f) Zn.65 Ru-106 119.0 i 12.0 106.33 i 15.89 -1.83 Cs-134 5.0 i 5.0 5.67 i 0.58 0.23 Cs-137 5.0 i 5.0 6.67 1 0.58 0.58 Ba-123 99.0 i 10.0 104.33 i 9.29 0.92 Water Sr-89 34.0 i 5.0 31.67 1 2.52 -0.81 07/16/93 09/14/93 12/02/93 5.0 24.00 1 0.00 -0.35 Sr-90 25.0 i Water Gr-Alpha 15.0 i 5.0 18.67 i 2.08 1.27 07/23/93 08/20/93 10/23/93 6.9 42.67 1 2.52 -0.08 Gr-Beta 43.0 i Air Filter Gr-Alpha 19.0 i 5.0 17.0 1 0.00 -0.69 08/27/93 11/05/93 12/28/93 47.0 1 5.0 49.00 i 1.73 0.69 Gr-Beta Sr-90 19.0 i 5.0 17.67 i 0.58 -0.46 Cs-137 9.0 i 5.0 9.67 1 0.58 0.23
- Footnotes located at end of table.
DUQUESNE LIGHT COMPANY EPA INTERLABORATURY COMPARISON PROGRAM 1993 (Page 2 of 3) EPA TI Norm Dev. ** Warning EPA Date Tl Malled Date EPA * * *Ac tion Re sults Issued Results Media Nuclide Results(a) Results(b) (Known) Preparation Water Ra-22G 14.9 1 2.2 ni.331 0.58 0.34 09/09/93 11/12/93 12/21/93 20.67 i 1.15 0.09 Ra-228 20.4 1 5.1 Milk Sr-89 30.0 1 5.0 35.67 i 3.51 1.96 09/24/93 11/24/93 , 01/24/94 5.0 1.73 -0.35 Sr-90 25.00 1 24.00 i l-131 120.0 i 12.0 126.67 i 5.77 0.96 Cs-137 49.0 i 5.0 50.67 i 1.15 0.58 K 1679.0 i 84.0 1620.00 i 17.32 -1.22 Water I-131 117.0 i 12.0 103.33 1 5.77 -1.97 10/08/93 11/10/93 12/23/93 Water Gr-Alpha 40.0 i 10.0 39.67 i 0.58 -0.06 10/19/93 12/29/93 02/14/94 1.5 10.10 1 0.79 0.23 Ra-226 9.9 i Ra-228 12.5 i 3.1 14.67 i 1.15 1.21 Gr-Beta 58.0 i 10.0 51.33 i 3.21 -1.15 Sr-89 15.0 1 5.0 15.00 i 1.00 0.00 Sr-90 10.0 1 5.0 10.00 i 0.00 0.00 Co-60 10.0 1 5.0 12.00 i 1.00 0.69 Cs-134 12.0 i 5.0 9.00 i 1.00 -1.04 Cs-137 10.0 i 5.0 12.67 i 2.52 0.92 Water Gr-Alpha 20.0 t 5.0 20.33 1 2.08 0.12 10/29/93 11/02/93 01/17/94 5.0 15.67 1 2.08 0.23 Gr-Beta 15.0 1 Water H-3 7398.0 i 740.0 6900.00 i100.00 -1.17 11/05/93 11/02/93 01/17/94 Water Co-60 30.0 1 5.0 28.67 i 2.89 -0.46 11/02/93 12/23/93 02/14/93 150.0 i 15.0 152.00 i 9.17 0.23 Zn-65 Ru-106 201.0 i 20.0 177.33 i 5.51 -2.05 ** (g) Cs- 134 59.0 i 5.0 53.33 i 4.93 -1.96 Cs- 137 40.0 1 5.0 41.33 i 3.06 0.46 Ba-133 79.0 i 8.0 69.33 i 3.06 -2.09 ** (g)
-. .- . - , - -. . . . _ - ~ . - . .. .. . . - - . . - . . .- . . - . _ - . - ~ . _ - . . _ - - . -- _._
i DUQUESNE LIGHT COMPANY EPA INTERLABORATORY COMPARISON PROGRAM 1993 (Page 3 of 3) EPA TI Norm Dev. ** Warning EPA Date TI Malled Date EPA (Known) *** Action Issued Results Media Nuclide Results(a) Results(b) Feration Re suits Footnotes (a) Average i expedmental sigma. (b) The Feted laboratory precision (I sigma. I determination) EPA switched from Am-241 to %-230 alpha spike. We calibrated with Th-230, using sodium nitrate to generate a self-absorption curve.1he EPA water however has ; (c) minerals which have greater self-absorption that the sodium nitrate matrix. The EPA has agreed to send us a gallon d their water which we can use to prepare a scif-(d) absorption curve with Th-230.Dy overssght, we did not use the special self-absorption turve which we had previously derived using EPA water and Cs.137 st We may also re-derive this curve using a water sample which the EPA has agreed to send us. (c) The counting data and backgrounds were vertfled. Possibly some effletendes used were erroneously high. causinglow values. A less hkely cause is an error in dilu Ra-226 standards wtl! be prepared. Closer monitoring of out of control efiletendes will be done and extra care in preparation of the sample will be maintained. (f) The calculations were checked and found to be correct. Thc results of six gamma emitting isotopes were reported to the EPA. The results of four were within I normalfred 4 dotation; a fifth. within 2 normalized deviations. Only the 2n45 average was outside the control limits. There is no obylous reason why one isotope should be outside the control Itmits, while five other isotopes were within control limits. (g) An investigation is being conducted: results will be available shortly. . i 1 4 a 1 l I
EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICUi.ATES (pg.1 of 1) 80 60 - Un. 40 - -
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i i l APPENDIX ll ) i j i ) i 4 h i QC Laboratory 1 i. I 4 EPA Interlaboratory 4 l i 1 l -Comparison Program 4 i i 4 i AT1-1 I
l l Annendix A , Interlaboratorv Comnarison Program Results
'Teledyne Brown Engineering Environmental Services Midwer,t Laboratory (formerly Teledyne Isotopes ;
and Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing . concentrations of radionuclides know to the issuing agency but not to participant laboratories. The purpose i 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 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 cons limits indi: ate 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, air filters, and food samples during the period 1990 - 1993. This program is conducted by the U.S. Environmental Protection Agency Intercomparison and ; Calibration Section, Quality Assurance Branch, Environmental Monitoring'and Support Laboratory, I Las Vegas, Nevada.
'lhe results in Table A-2 were obtained for Thermoluminescent dosimenters (TLDs), since1976 via various Intemational Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed.
Table A-3 lists results of the analyses on in-house " spiked" samples. Table A-4 lists results of the analyses on in-house " blank" samples. Attachment A lists acceptance criteria for " spiked" samples. Out-of-limit results are explained directly below the result. A1
i l TBEESML-BLIND-01 Revision 0,12-29-86 December,1993 ATTACHMENT A ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES
- 1 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-89 6 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-90b 2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>30 pCi/ liter or kg 10% of known value Potassium >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 $100 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)""
>4,000 pCi/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value Iodine-131, s55 pCi/ liter 6.0 pCi/ liter j Iodine-129 b >55 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-64 6 >35 pCi/ liter 15% of known value Technetium-996 50 to 100 pCi/ liter 10 pCi/ liter Ir n-55, i
>100 pCi/ liter 10% of known value Others 6 . 20% of known value
- From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
6 TBEESML limit. l A2 1 l l 1
1 I I Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown ! Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses 2 Sigma
- 1s, N=1 Limits STW-589 WATER Jan,1990 Sr-89 22.7 i 5.0 25.015.0 16.3 - 33.7 Sr-90 17.311.2 20.0 i 1.5 17.4 - 22.6 The sample was reanalyzed in triplicate for Sr-90; results of reanalyses were 18.811.5 pCi/L.
No further action is planned. STW-591 WATER Jan,1990 Gr. Alpha 10.3 i 3.0 12.015.0 3.3 - 20.7 Gr. Beta 12.3 i 1.2 12.0 i 5.0 3.3 - 20.7 STW-592 WATER Jan,1990 Co40 14.7 i 2.3 15.015.0 6.3 - 23.7 Zn-65 135.0 i 6.9 139.0 i 14.0 114.8 - 163.2 Ru-1% 133.3 i 13.4 139.0 1 14.0 114.8 - 163.2 Cs-134 17.3 i 1.2 18.0 i 5.0 9.3 - 26.7 Cs-137 19.3 i 1.2 18.015.0 9.3 - 26.7 Ba-133 78.0 i 0.0 74.017.0 61.9 - 86.1 STW-593 WATER Feb,1990 H-3 4827.0 i 83.0 4976.0 1 498.0 4113.0 - 5839.0 STW-594 WATER Mar,1990 Ra-226 5.0i0.2 4.9 i 0.7 4.1 - 5.7 Ra-228 13.5 i 0.7 12.711.9 9.4 - 16.0 STW-595 WATER Mar,1990 Uranium 4.0i0.0 4.0 i 6.0 0.0 - 14.4 STAF-596 AIR FILTER Mar,1990 Gr. Alpha 7.3 i 1.2 5.0 5.0 0.0 - 13.7 Gr. Beta 34.010.0 31.015.0 22.3 - 39.7 Sr-90 10.0 i 0.0 10.0 i 1.5 7.4 - 12.6 Cs-137 9.3 i 1.2 10.0 i 5.0 1.3 - 18.7 WATER Apr,1990 Gr. Alpha 81.0 i 3.5 90.0 i 23.0 50.1 - 129.9 STW-597 Ra-226 4.9 i 0.4 5.0i0.8 3.6 - 6.4 Ra-228 10.6 i 0.3 10.211.5 7.6 - 12.8 U 18.713.0 20.016.0 9.6 - 30.4 WATER Apr,1990 Gross Beta 51.0110.1 52.015.0 43.3 - 60.7 STW-598 Sr-89 9.3 i 1.2 10.015.0 1.3 - 18.7 Sr-90 10.313.1 10.0 i 1.5 8.3 11.7 Cs-134 16.0 0.0 15.015.0 6.3 - 23.7 Cs-137 19.012.0 15.0 i 5.0 6.3 - 23.7 ! ~ I Al-1 i i i
1 1 Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown I Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Saraple Date TBEESML Results EPA Resultd Control Code Type Collected Analysts 12 Sigma' 1s, N=1 Limits STM-599 MILK Apr,1990 Sr-89 21.7i ' . I 23.015.0 14.3 - 31.7 Sr-90 21.0 i 7.0 23.0 5.0 14.3 - 31.7 I-131 98.7i 1.2 99.0 i 10.0 81.7 - 116.3 Cs-137 26.016.0 24.015.0 15.3 - 32.7 K 1300.0 i 69.2 1550.0 i 78.0 1414.7 - 1685.3 The K analysis was repeated in triplicate; result of reanalysis was 13.411.0 mg/L. No further action is planned. STW-600 WATER May,1990 Sr-89 6.012.0 7.0 5.0 0.0 - 15.7 Sr-90 6.7i 1.2 7.0 i 5.0 0.0 - 15.7 STW-601 WATER May,1990 Gr. Alpha 11.012.0 22.0 6.0 11.6 - 32.4 Gr. Beta 12.3 i 1.2 15.015.0 6.3 - 23.7 Gross Alpha analysis was repeated in triplicate; results of reanalyses were 13.411.0 pCi/L. No further action is planned. STW-602 WATER Jun,1990 Co-60 25.3 i 2.3 24.015.0 15.3 - 32.7 Zn-65 155.0 i 10.6 148.0 i 15.0 130.6 - 165.4 Ru-106 202.71 17.2 210.0 21.0 173.6 - 246.4 Cs-134 23.711.2 24.0 i 5.0 18.2 - 29.8 Cs-137 27.7i 3.1 25.015.0 16.3 - 33.7 Ba 133 100.7 i 8.1 99.0110.0 81.7 - 116.3 STW-603 WATER Jun,1990 H-3 2927.0 1 306.0 2933.0 1 358.0 2312,0 - 3554.0 STW-604 WATER Jul,1990 Ra-226 11.810.9 12.li l.8 9.0 - 15.2 Ra-228 4.1 i 1.4 5.1 i 1.3 2.8 - 7.4 STW-605 WATER Jul,1990 U 20.3 i 1.7 20.8 i 3.0 15.6 - 26.0 STW-606 WATER Aug,1990 I-131 43.011.2 39.0 i 6.0 28.6 - 49.4 I STW-607 WATER Aug,1990 Pu-239 10.0i 1.7 9.1 i 0.9 7.5 - 10.7 STAF-608 AIR FILTER Aug,1990 Gr. Alpha 14.0i0.0 10.0 5.0 1.3 - 18.7 Gr. Beta 65.3 i 1.2 62.0 i 5.0 53.3 - 70.7 Sr-90 19.0 i 6.9 20.0 i 5.0 11.3 - 28.7 Cs-137 19.012.0 20.0 i 5.0 11.3 - 26.7 STW-609 WATER 'Sep,1990 Sr-89 9.012.0 10.015.0 1.3 - 18.7 Sr-90 9.0i 2.0 9.015.0 0.3 - 17.7 1 STW-610 WATER Sep,1990 Gr. Alpha 8.311.2 10.0 t 5.0 1.2 - 18.7 Gr. Beta 10.311.2 10.0 5.0 1.3 - 18.7 i Al-2 ! I I 1
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentrationin pCi/L6 Lab Sample Date TBEESML Results EPA Resultd Control i Code Type Collected Analyses t2 Sigma
- 1s, N=1 Limits STM-611 MILK Sep,1990 Sr-89 11.7 i 3.1 16.0 i 5.0 7.3 - 24.7 Sr-90 15.010.0 20.015.0 11.3 - 28.7 I131 63.016.0 58.0 i 6.0 47.6 - 68.4 Cs-137 20.0 i 2.0 20.015.0 11.3 - 28.7 K-40 1673.3 1 70.2 1700.0 85.0 1552.5 - 1847.5 STW-612 WATER Oct,1990 Co-60 20.3 i 3.1 20.0 i 5.0 11.3 - 28.7 l Zn-65 115.3 i 12.2 115.0 1 12.0 94.2 - 135.8 Ru-106 152.0 i 8.0 151.0 i 15.0 125.0 - 177.0 Cs-134 11.010.0 12.015.0 3.3 - 20.7 Cs-137 14.0 2.0 12.015.0 3.3 - 20.7 Ba-133 116.7 i 9.9 110.0 i 11.0 90.9 - 129.0 i
STW-613 WATER Oct,1990 H-3 7167.0 i 330.0 7203.0 i 720.0 5954.0 - 8452.0
, STW-614 WATER Oct,1990 Gr. Alpha 68.717.2 62.0116.0 34.2 - 89.8
- Ra-226 12.9 i 0.3 13.6 i 2.0 10.1 - 17.1 Ra-228 4.2 i 0.6 5.0 i 1.3 2.7 - 7.3 U 10.4 i 0.6 10.2 i 3.0 5.0 - 15.4 sTW-615 WATER Oct,1990 Gross Beta 55.0 i 8.7 53.0 i 5.0 44.3 - 61.7 Sr-89 15.7 i 2.9 20.0 i 5.0 11.3 - 28.7
- Sr-90 12.012.0 15.015.0 6.0 - 23.7 Cs-134 9.011.7 7.015.0 0.0 - 15.7 Cs-137 7.7i 1.2 5.015.0 0.0 - 13.7 STW-616 WATER Nov,1990 Ra-226 6.811.0 7.4il.1 5.5 - 9.3 Ra-228 5.3 i 1.7 7.7i 1.9 4.4 - 11.0 STW-617 WATER Nov,1990 U 35.010.4 35.5 i 3.6 29.3 - 41.7 Sample was analyzed but the results where not submitted to the EPA because the deadline was missed (all data on file).
STW-618 WATER Jan,1991 Sr-89 4.3 i 1.2 5.0 5.0 0.0 - 13.7 Sr-90 4.711.2 5.015.0 0.0 - 13.7 STW-619 WATER Jan,1991 Pu-239 3.6 i 0.2 3.3 i 0.3 2.8 - 3.8 STW-620 WATER -Jan,1991 Gr. Alpha 6.713.0 5.015.0 0.0 - 13.7 Gr. Beta 6.3 i 1.2 5.015.0 0.0- 13.7 Al-3
i Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teled>me Browm Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L" l Lab Sample Date TUEESML Results EPA Resultd Control ) Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits STW-621 WATER Feb,1991 Co-60 41.3 i 8.4 40.0 i 5.0 31.3 - 48.7 l Zn-65 166.7 i 19.7 149.0 i 15.0 123.0 - 175.0 Ru-106 209.7 1 18.6 186.0 1 19.0 153.0 - 219.0 Cs-134 9.0i2.0 8.0i5.0 0.0 - 16.7 Cs-137 9.7i 1.2 8.0i5.0 0.0 - 16.7 Ba-133 85.7 i 9.2 75.0 i 8.0 61.1 - 88.9 STW-622 WATER Feb,1991 1-131 81.3 6.1 75.0 i 8.0 61.1 - 88.9 STW-623 WATER Feb,1991 H-3 4310.0 i 144.2 4418.0 1 442.0 3651.2 - 5184.8 STW-624 WATER Mar,1991 Ra-226 31.413.2 31.8 i 4.8 23.5 - 40.1 Ra-228 21.115.3 11.9 - 30.3 No data for Ra-228 was reported; sample was lost during analysis. STW-625 WATER Mar,1991 U 6.7i 0.4 7.6i3.0 2.4 - 12.8 STAF-626 AIR FILTER Mar,1991 Gr. Alpha 38.711.2 25.016.0 14.6 - 35.4 Gr. Deta 130.0 i 4.0 124.0 i 6.0 113.6 - 134.4 Sr-90 35.711.2 40.0 i 5.0 31.3 - 48.7 Cs-137 33.714.2 40.015.0 31.3 - 48.7 The cause of the high Cross Alpha result is the difference in geometry between the standard used in the TIML lab and the EPA filter. i STW-627 WATER Apr,1991 Gr. Alpha 51.0 i 6.0 54.0114.0 29.7 - 78.3 Ra-226 7.0i 0.8 8.011.2 5.9 - 10.1 Ra-228 9.711.9 15.213.8 8.6 - 21.8 U 27.712.4 29.813.0 24.6 - 35.0 j 1 STW-628 WATER Apr,1991 Gross Beta 93.3 i 6.4 115.0 i l7.0 85.5 - 144.5 l Sr-89 21.0 i 3.5 28.015.0 19.3 - 36.7 { Sr-90 23.010.0 26.0 i 5.0 17.3 - 34.7 [ Cs-134 27.3 i 1.2 24.0 i 5.0 15.3 - 32.7 Cs-137 29.0 i 2.0 25.0 i 5.0 16.3 - 33.7 STM-629 MILK Apr,1991 Sr-89 24.018.7 32.0i 5.0 23.3 - 40.7 Sr-90 28.0 i 2.0 32.015.0 23.3 - 40.7 I-131 65.3114.7 60.0 i 6.0 49.6 - 70.4 Cs-137 54.7111.0 49.0 t 5.0 40.3 - 57.7 l K-40 1591.7 1 180.1 1650.0 83.0 1506.0 - 1794.0
. STW-630 WATER May,1991 Sr-89 40.7 i 2.3 39.015.0 30.3 - 47.7 Sr-90 23.7.i 1.2 24.015.0 15.3 - 32.7 Al-4 l l
1 I
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Tcledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses i2 Sigma
- 1s, N=1 Limits STW-631 WATER May,1991 Gr. Alpha 27.7 i 5.8 24.016.0 13.6 - 34.4 Gr. Beta 46.010.0 46.015.0 37.3 - 54.7 STW-632 WATER Jun,1991 Co-60 11.3 i 1.2 10.015.0 1.3 - 18.7 Zn-65 119.3 i 16.3 108.0 i 11.0 88.9 - 127.1 Ru-106 162.3 i 19.0 149.0 i 15.0 123.0 - 175.0 Cs-134 15.3 i 1.2 15.015.0 6.3 - 23.7 Cs-137 16.3 i 1.2 14.0 5.0 5.3 - 22.7 Ba-133 74.0 i 6.9 62.016.0 51.6 - 72.4 Sample was reanalyzed for Ba-133. Result of the reanalysis was 63.8i6.9 pCi/L; within the EPA control limits.
STW-633 WATER Jun,1991 H-3 13470.0 1 385.8 12480.0 1 1248.0 10314.8 - 14645.2 STW-634 WATER Jul,1991 Ra-226 14.9 i 0.4 15.9 i 2.4 11.7 - 20.1 Ra-228 17.6i 1.8 16.714.2 9.4 - 24.0 STW-635 WATER Jul,1991 U 12.8 0.1 .2 3.0 9.0 - 19.4 STW-636 WATER Aug,1991 1-131 19.3 i 1.2 20.016.0 9.6 - 30.4 STW-637 WATER Aug,1991 Pu-239 21.410.5 19.4 i 1.9 16.1 - 22.7 STAF-638 AIR FILTER Aug,1991 Gr. Alpha 33.0 i 2.0 25.0 i 6.0 14.6 - 35.4 Gr. Beta 88.7 i 1.2 92.0110.0 80.4 - 103.6 Sr-90 27.0 i 4.0 30.015.0 21.3 - 38.7 Cs-137 26.3 1.2 30.015.0 21.3 - 38.7 ETW-639 WATER Sep,1991 Sr-89 47.0110.4 49.015.0 40.3 - 57.7 Sr-90 24.012.0 25.015.0 16.3 - 33.7 STW-640 WATER Sep,1991 Gr. Alpha 12.014.0 10.0i5.0 1.3 - 18.7 Gr. Beta 20.3 i 1.2 20.0 i 5.0 11.3 - 28.7 STM-641 MILK Sep,1991 Sr-89 20.3 t 5.0 25.0 i 5.0 16.3 - 33.7 Sr-90 19.7 i 3.1 25.015.0 16.3 - 33.7 I-131 130.7 1 16.8 108.0 i 11.0 88.9 - 127.1 Cs-137 33.7 3.2 30.0 i 5.0 21.3 - 38.7 K 1743.3 1 310.8 1740.0 1 87.0 1589.1 - 1890.9 The cause of the high result for the 1-131 analysis is unknown. An in-house spike sample was prepared with activity for I-131 of 68.3i6.8 pCi/L. Result of TIML's analysis of the in-house spike was 69.119.7 pCi/L. Al-5
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Tcledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Sample Date TBEESML Results EPA Result d Control Code Type Collected Analyses 12 Sigma' 1s, N=1 i imits STW-642 WATER Oct,1991 Co-60 29.7 i 1.2 29.015.0 20.3 - 37.7 Zn-65 75.7 i 8.3 73.017.0 60.9 - 85.1 Ru-106 196.3 i 15.1 199.0 1 20.0 164.3 - 233.7 Cs-134 9.7i 1.2 10.015.0 1.3 - 18.7 Cs-137 11.012.0 10.015.0 1.3 - 18.7 Ba-133 94.7 i 3.1 98.0110.0 80.7 - 115.3 STW-643 WATER Oct,1991 H-3 2640.0 1 156.2 2454.0 1 352.0 1843.3 - 3064.7 STW-644 WATER Oct,1991 Gr. Alpha 73.0113.1 82.0121.0 45.6 - 118.4 Ra-226 20.9 i 2.0 22.013.3 16.3 - 27.7 Ra-228 19.612.3 22.215.6 12.5 - 31.9 U 13.510.6 13.5 i 3.0 8.3 - 18.7 STW-645 WATER Oct,1991 Gross Beta 55.313.1 65.0 i 10.0 47.7 - 82.3 Sr-89 9.7i 3.1 10.0 i 5.0 1.3 - 18.7 Sr-90 8.711.2 10.0 i 5.0 1.3 - 18.7 Co-60 20.3 i 1.2 20.015.0 11.3 - 28.7 Cs-134 9.0i 5.3 10.015.0 1.3 - 18.7 Cs-137 14.7 i 5.0 11.0 i 5.0 2.3 - 19.7 STW-646 WATER Nov,1991 Ra-226 5.611.2 6.5il.0 4.8 - 8.2 Ra-228 9.610.5 8.112.0 4.6 - 11.6 1 STW-647 WATER Nov,1991 U 24.712.3 24.923.0 19.7 - 30.1 STW-648 WATER Jan,1992 Sr-89 42.7i 6.4 51.J i 5.0 42.3 - 59.7 Sr-90 18.313.1 20.*e 5.0 11.3 - 28.7 STW-649 WATER Jan,1992 Pu-239 16.li 0.8 16.8i l.7 13.9 - 19.7 STW-650 WATER Jan,1992 Gr. Alpha 23.7 i 9.2 30.018.0 16.1 - 43.9 Gr. Beta 27.7 i 4.2 30.0i5.0 21.3 - 38.7 WATER Feb,1992 1-131 60.3 i 4.2 59.0 i 6.0 48.6 - 69.4 STW-651 WATER Feb,1992 Co-60 40.3 i 5.0 40.0 i 5.0 31.3 - 48.7 STW-652 Zn-65 148.0 1 15.0 150.7 i 6.1 122.0 - 174.0 Ru-106 188.7 i 28.8 203.0 1 20.0 168.3 - 237.7 Cs-134 31.7 i 4.2 31.015.0 22.3 - 39.7 Cs-137 51.0 i 3.4 49.015.0 40.3 - 57.7 Ba-133 79.0 i 3.4 76.0 i 8.0 62.1 - 89.9 WATER Feb,1992 H-3 7714.0 i 119.6 7904.0 1 790.0 6533.4 - 9274.6 STW-653 Al-6 11
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses 2 Sigma' 1s, N=1 Limits STW-654 WATER Mar,1992 Ra-226 9.010.4 10.lil.5 7.5 - 12.7 Ra-228 18.8 i 0.6 15.5 i 3.9 8.7 - 22.3 STW-655 WATER Mar,1992 Rn-222 0.0 0.0 ND = No Data; Special EPA testing. STW-656 WATER Mar,1992 U 25.111.9 25.3 3.0 20.1 - 30.5 STW-657 WATER Mar,1992 Rn-222 No Data is available; Special EPA testing. STAF-658 AIR FILTER Mar,1992 Gr. Alpha 7.0 0.0 7.015.0 0.0 - 15.7 Gr. Beta 39.3 i 1.6 41.0 i 5.0 32.3 - 49.7 Sr-90 13.711.6 15.015.0 6.3 - 23.7 Cs-137 10.010.0 10.0 i 5.0 1.3 - 18.7 STW-659 WATER Apr,1992 Gr. Alpha 35.7 i 6.1 40.0 10.0 22.7 - 57.3 Ra-226 12.711.2 14.9 i 2.2 11.1 - 18.7 Ra-228 14.5 i 2.1 14.013.5 7.9 - 20.1 U 3.9 i 0.2 4.0 3.0 0.0 - 9.2 STW-660 WATER Apr,1992 Gross Beta 113.017.2 140.0 1 21.0 103.6 - 176.4 Sr-89 12.314.2 15.0 i 5.0 6.3 - 23.7 Sr-90 15.0 i 1.2 17.0 i 5.0 8.3 - 25.7 Co-60 61.0 i 4.0 56.0 5.0 47.3 - 64.7 Cs-134 24.311.2 24.0 i 5.0 15.3 - 32.7 Cs-137 24.012.0 22.015.0 13.3 - 30.7 STM-661 MILK Apr,1992 Sr-89 25.3 7.6 38.015.0 29.3 - 46.7 Sr-90 24.313.1 29.015.0 20.3 - 37.7 I-131 78.7 i 9.5 78.018.0 64.1 - 91.9 Cs-137 39.312.3 39.0 5.0 30.3 - 47.7 K-40 1610.0 1 72.1 1*/10.0 i 86.0 1560.8 - 1859.2 The cause of the low Sr-89 results is unknown. Data were checked for errors. An in-house spike sample was prepared with activity for Sr-89 of 41.0i10.0 pCi/L. Result of the analysis of the in-house spike sample for Sr-89 was 37.2 3.6 pCi/L. STW-662 WATER May,1992 Sr-89 24.014.0 29.0 5.0 20.3 - 37.7 Sr-90 6.7 1.2 8.0 5.0 0.0 - 16.7 STW-663 WATER May,1992 Gr. Alpha 12.3 i 2.1 15.015.0 6.3 - 23.7 Gr. Beta 46.0 t 5.0 44.015.0 35.3 - 52.7 Al-7 e
4 Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L' Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses 2 Sigma' 1s, N=1 Limits STW-664 WATER Jun,1992 Co-60 20.3 i 1.2 20.0 i 5.0 11,3 - 28.7 Zn-65 103.3 i 10.6 99.0110.0 81.7 - 116.3 Ru-106 142.7 1 23.7 141.0 i 14.0 116.7 - 165.3 Cs-134 14.3 2.3 15.0 i 5.0 6.3 - 23.7 Cs-137 15.0 2.0 15.015.0 6.3 - 23.7 Ba-133 92.7 i 11.0 98.0110.0 80.7 - 115.3 STW-665 WATER Jun,1992 H3 2153.3 t 144.6 2125.0 i 347.0 1523.0 - 2727.0 STW-666 WATER Jul,1992 Ra-226 22.3 i 2.2 24.9 i 3.7 18.5 - 31.3 Ra-228 16.7 i 3.1 16.7i 4.2 9.4 - 24.0 STW-667 WATER Jul,1992 Uranium 3.6 i 0.3 4.013.0 0.0 - 9.2 STW-668 WATER Aug,1992 1-131 47.0i 3.5 45.016.0 34.6 - 55.4 STW-669 WATER Aug,1992 Pu-239 8.5 i 0.9 9.0 i 0.9 7.4 - 10.6 STAF-670 AIR FILTER Aug,1092 Alpha 25.711.2 30.018.0 16.1 - 43.9 Beta 69.012.0 69.0 i 10.0 51.7 - 86.3 Sr-90 26.0 i 4.0 25.015.0 16.3 - 33.7 Cs-137 16.0 i 0.0 18.015.0 9.3 - 26.7 STW-671 WATER Sep,1992 Sr-89 16.0 i 4.0 20.0i5.0 11.3 - 28.7 St-90 14.3 i 3.1 15.0 i 5.0 6.3 - 23.7 STW-672 WATER Sep,1992 A1pha 43.0 i 13.1 45.0111.0 25.9 - 64.1 Beta 41.3 i 18.6 50.0 i 5.0 14.3 - 58.7 STM-673 MILK Sep,1992 1-131(gamma 109.7 i 19.4 100.0 i 10.0 82.7 - 117.3 Sr-89 11.013.5 15.015.0 6.3 - 23.7 Sr-90 12.7i 1.6 15.015.0 6.3 - 23.7 Cs-137 14.0 i 3.5 15.015.0 6.3 - 23.7 K 1540.0 i 103.9 1750.0 i 88.0 1597.3 - 1902.7 The K activity was calculated using the wrong volume (3.5 L), instead of 3.25 L Correction for volume resulted in a value of 1660.0i110.1; within EPA controllimits. STW-674 WATER Oct,1992 Co-60 11.312.3 10.0i5.0 1.3 - 18.7
, Zn-65 169.7 i 25.0 148.0 1 15.0 122.0 - 174.0 Ru-106 170.712.3 175.0 1 18.0 143.8 - 206.2 Cs-134 9.712.3 8.0 i 5.0 0.0 - 16.7 Cs-137 9.7i 1.2 8.015.0 0.0- 16.7 Ba-133 80.3 9.0 74.017.0 61.9 - 86.1 STW-675 WATER Oct,1992 H-3 5896.7 i 136.2 5962.0 i 596.0 4928.0 - 6996.0 Al-8
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L' Lab Sample Date TBEESML Results EPA Result d Control Code Type Collected Analyses i2 Sigma' 1s,N=1 Limits WATER Oct,1992 Gr. Alpha 24.715.0 29.017.0 16.9 - 41.1 STW-676 Ra-226 7.1 i 0.4 7.421.1 5.5 - 9.3 Ra-228 11.5 i 1.0 10.0 i 2.5 5.7 - 14.3 Uranium 9.7 i 0.5 10.2 i 3.0 5.0 - 15.4 Oct,1992 Gr. Beta 42.7 8.1 53.0 i 10.0 35.7 - 70.3 STW-677 WATER i Co-60 15.0 i 2.0 15.0 i 5.0 6.3 - 23.7 i l Cs-134 5.7 i 1.2 5.0 i 5.0 0.0 - 13.7 Cs-137 8.0 2.0 8.0 5.0 0.0 - 16.7 Sr-89 6.7i 1.2 8.015.0 0.0 - 16.7 Sr-90 10.0 i 2.0 110.015.0 1.3- 18.7 STW-678 WATER Oct,1992 Ra-226 7.S i 0.8 7.511.1 5.6 - 9.4 - Ra-228 5.8 i 0.7 5.0 i 1.3 2.7 - 7.3 WATER Nov,1992 Uranium 15.511.1 15.213.3 10.0 - 20.4 STW-679 4 STW-680 WATER Jan,1993 Sr-89 15.0 i 2.0 15.0i5.0 6.3 - 23.7 St-90 10.311.2 10.0 i 5.0 1.3 - 18.7 WATER Jan,1993 Pu-239 17.5 i t.6 20.0 i 2.0 16.5 - 23.5 STW-681 WATER Jan,1993 A1pha 17.1 i 1.2 34.0 9.0 18.4 - 49.6 i
, STW-682 Beta 46.7 i 3.2 44.0 i 5.0 35.3 - 52.7 l Gross Alpha analysis was repeated with similar results. An investigation of possible causes for the deviation from the EPA was conducted with no cause discovered. The sample was spiked with Th-230; so Alpha Spec Analysis for Th-230 was performed in triplicate with results of 15.5 2.1,13.4 1.4, and 14.8i2.0. It should be noted that 66% of all participants failed this analysis with a grand average of 17.1. This coupled with the support of the Alpha j Spec results leaves TIML cause to believe that there may have been a dilution error at the EPA. It should be noted that on the next Gross Alpha EPA check, TIML reported results that where exactly the known value. Since no apparent cause can be found, and TIML had '
outstanding results on the following sample, it is felt that no further investigation is needed. Feb,1993 I-131 106.0 i 10.0 100.0 i 10.0 82.7- 117.3 STW-683 WATER Feb,1993 Uranium 7.210.5 7.6 i 3.0 2.4 - 12.8 STW-684 WATER WATER _ Mar,1993 Ra 226 9.311.3 9.811.5 7.2 12.4 STW-685 Ra-228 20.8 i 2.2 18.5 i 4.6 10.5 - 26.5 A1pha 88.318.1 95.0124.0 53.4 - 136.6 STW-686 WATER Apr,1993 Ra-226 25.4 i 1.4 24.913.7 18.5 - 31.3 Ra-228 17.4 i 1.2 19.0 i 4.8 10.7 - 27.3 Uranium 27.8 i 2.2 28.9 i 3.0 23.7 - 34.1 Al-9
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Browm Engineering Environmental Services, Midwest Laboratory results for various sample media'. I l i Concentration in pCi/L6 j Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits STW-687 WATER Apr,1993 Beta 141.7 i 9.0 177.0 i 27.0 130.2 223.8 ) Sr-89 28.719.4 41.015.0 32.3 - 49.7 Sr-90 28.013.5 29.0 t 5.0 20.3 - 37.7 ) Co-60 41.3 i 1.2 39.015.0 30.3 - 47.7 Cs-134 24.7 t l.2 27.0 5.0 18.3 - 35.7 Cs-137 30.0 i 0.0 32.0 i 5.0 23.3 - 40.7 The EPA report was received 08-16-93. No cause for the low result for Sr-89 was found. The analyst has been observed performing this procedure with no noted descrepancies. Teledyne will continue to monitor this procedure in the future. No further action is anticipated unless conditions warrant. STW-688 WATER Jun,1993 H-3 9613.3 i 46.2 9844.0 i 984.0 8136.8 - 11551.2 STW-689 WATER Jun,1993 Co-60 17.3 4.6 15.0i5.0 6.3 - 23.7 Zn-65 114.0 i 13.2 103.0 1 10.0 85.7 - 120.3 Ru-1% 108.018.0 119.0 1 12.0 98.2 - 139.8 Cs-134 5.7i 1.2 5.0 t 5.0 0.0 - 13.7 Cs-137 6.0 i 2.0 5.0 i 5.0 0.0 - 13.7 Ba-133 101.7 i 10.3 99.0 i 10.0 81.7 - 116.3 STW-690 WATER Jul,1993 Sr-89 28.312.3 34.0 i 5.0 25.3 - 42.7 St-90 25.0 1.0 25.0 i 5.0 16.3 - 33.7 STW-691 WATER Jul,1993 A1pha 15.0 i 2.7 15.0 i 5.0 6.3 - 23.7 Beta 41.3 i 4.9 43.0 i 6.9 31.0 - 55.0 STW-692 WATER Aug,1993 Uranium 24.9 i 1.4 25.3 i 3.0 20.1 - 30.5 STAF-693 AIR FILTER Aug,1993 Alpha 17.0il.0 19.0 t 5.0 10.3 27.7 Beta 47.310.6 47.0 i 5.0 38.3 - 55.7 Sr-90 19.3 i 0.6 19.015.0 10.3 - 27.7 Cs-137 10.0 i 1.0 9.015.0 0.3 - 17.7 i I STW-694 WATER Sep,1993 Ra-226 15.9 0.7 14.9 i 2.2 11.1 - 18.7 j Ra-228 21.011.6 20.415.1 11.6 - 29.2 i l l Al-10 1
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media'. Concentration in pCi/L6 Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses 2 Sigma' 1s, N=1 Limits STM-695 MILK Sep,1993 1-131 125.3 i 4.5 120.0 1 12.0 99.2 - 140.8 Sr-89 19.3 t l.5 30.015.0 21.3 - 38.7 Sr-90 22.010.0 25.0 i 5.0 16.3 - 33.7 Cs-137 49.013.0 49.015.0 40.3 - 57.7 K 1616.7 i 37.9 1679.0 i 84.0 1533.3 - 1824.7 Report was received 01-18-94; an investigation is underway as to the cause of the low St-89 results. In house spikes have been prepared and the analysis is in progress (see SPM-4848 and SPM-4849 in future reports). There is no apparent cause of the low Sr-89 results. In-house spikes have been prepared and the analysis is in progress. The analyst has been observed performing this procedure with no discrepancies noted. No further action is planned unless the i results of the In-House spikes show a problem. j STW-696 WATER Oct,1993 I-131 116.712.3 117.0 1 12.0 96.2 - 137.8 STW-697 WATER Oct,1993 Gr. Alpha 39.711.5 40.0 i 10.0 22.7 - 57.3 Ra-226 10.610.5 9.9i1.5 7.3 - 12.5 Ra-228 13.211.5 12.5 i 3.1 7.1 - 17.9 Uranium 15.3 i 0.6 15.li 3 0 9.9 - 20.3 STW-698 WATER Oct,1993 Beta 52.0i l.0 58.0110.0 40.7 - 75.3 ! Sr-89 11.3 i 0.6 15.0 i 5.0 6.3 - 23.7 l Sr-90 11.010.0 10.015.0 1.3 - 18.7 Co-60 10.7 i 0.6 10.015.0 1.3 - 18.7 Cs-134 10.011.0 12.015.0 3.3 - 20.7 Cs-137 12.3 i 1.2 10.015.0 1.3 - 18.7 STW-699 WATER Oct,1993 Alpha 18.312.5 20.0i5.0 11.3 - 28.7 Beta 13.7 i 0.6 15.015.0 6.3 - 23.7 STW 700 WATER Nov,1993 H-3 7310.0 i 175.2 7398.0 i 740.0 6114.1 - 8681.9 i STW-701 WATER Nov,1993 Ba-133 75.717.6 79.018.0 65.1 - 92.9 i Co-60 30.7 i 2.1 30.0 i 5.0 21.3 - 38.7 l Cs-134 51.3 i 5.9 59.0 i 5.0 50.3 - 67.7 Cs-137 41.7 1.2 40.0 i 5.0 31.3 - 48.7 Ru-106 163.313.2 201.0 i 20.0 166.3 - 235.7 l Zn-65 157.0 i 8.7 150.0 1 15.0 124.0 - 176.0 - i ! The report was received on 02-14-94; the cause of the low Ru-106 is under investigation. It l should be noted that the grand average of all participants in this analysis was 175.2 pCi/L, l with 54% of the participants outside of limits. l A1-11 l
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Engineering Environmental Services, Midwest Laboratory results for various sample media *. Concentration in pCi/L6 Lab Sample Date TBEESML Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a l 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, Neveda. I b All results are in pCi/L, except for elemental potassium (K) data in milk, v'hich are in mg/L; air filter samples, which are in pCi/ Filter; and food products, which are in mg/Kg. ;
- Unless otherwise indicated, the TBEESML results are given as the mean 12 standard deviations for three determinations.
d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits as defined by the EPA. f i l 1 l 1 b i 4 l o Al-12 I l
- l l 1
( Table A-2. Crosscheck program results; thermoluminescent dosimeters. (TLDs). mR Lab TDEESML Results Known Average i2 Sigma Ccde TLD Type Measurement i 2 Sigma Value i 2 Sigma (All Participants)
\
2nd International Intercomoarison 115-2 CaF2 : Mn Bulb Apr,1976 Field 17.0i l.9 17.1 16.4 i 7.7 Lab 20.8 i 4.1 21.3 18.817.6 Second IntemationalIntercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas. 3rd International Intercomnarison 115-3 CaF,: Mn Bulb Jun,1977 Field 30.713.2 34.914.8 31.5 3.0 Lab 89.6 i 6.4 91.7114.6 86.2 i 24.0
'Ihird 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 International Intercomoarison 115-4 CaF2 : Mn Bulb Jun,1979 Fie1d 14.1 i 1.1 14.1 i 1.4 16.019.0 Lab, Low 9.811.3 12.212.4 12.017.4 Lab, High 40.4 1.4 45.819.2 43.9113.2 Fourth International 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 Intercomoarison 115-5A CaF2 : Mn Bulb Oct,1980 Fie1d 31.4 i 1.8 30.016.0 30.2 i 14.6 Lab, Start 77.4 i 5.8 75.217.6 75.8 i 40.4 Lab,End 96.6 i 5.8 88.4 i 8.8 90.7 i 31.2 115-5B LiF-100 Chips Oct,1980 Field 30.314.8 30.0 i 6.0 30.2 i 14.6 Lab, Start 8L1i 7.4 75.217.6 75.8140.4 Lab,End 85.4 i 11.7 88.4 i 8.8 90.7 i 31.2 Fif th International 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 Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 7th International Intercomna'rison 115-7A LiF-100 Chips Jun,1984 Fie1d 75.4 i 2.6 75.8 i 6.0 75.1129.8 Lab, Co-60 80.013.5 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 66.612.5 75.0 i 3.8 73.0 i 22.2 A2-1
Table A-2. Crosscheck program results; thermoluminescent dosimeters. (TLDs). mR Lab TBEESML Results Known Average i 2 Sigma Code TLD Type Measurement 2 Sigma Value i 2 Sigma (All Participants) 115-7B CaF2 : Mn Bulb Jun,1984 Fieid 71.512.6 75.8 i 6.0 75.1 i 29.8 Lab, Co-60 84.8 i 6.4 79.9 4.0 77.9127.6 Lab, Cs-137 78.8 i 1.6 75.0 t 3.8 73.0 i 22.2 l 115-7C CaSO :Dy Jun,1984 FieId 76.812.7 75.8 i 6.0 75.1 i 29.8 Cards Lab, Co-60 82.513.7 79.9 i 4.0 77.9 27.6 Lab, Cs-137 79.0 3.2 75.0 3.8 73.0 i 22.2 Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Neveda, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. Teledyne did not participate in the Sixth International Intercomparison of Environmental Dosimeters. 8th International Intercomoarison 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.Si l.4 29.711.5 28.9 i 12.4 ] Field, Site 2 11.3 i 0.8 10.4 i 0.5 10.119.1 Lab, Cs-137 13.710.9 17.210.9 16.2 i 6.8 115-8B CaF2 : Mn Bulb Jan,1986 Field, Site 1 32.3 1.2 29.711.5 28.9 i 12.4 Field, Site 2 9.0 i 1.0 10.4 i 0.5 10.1 i 9.0 Lab, Cs-137 15.8 i 0.9 17.2 i 0.9 16.2 i 6.8 115-8C CaSO.:Dy Jan,1986 Field, Site 1 32.210.7 29.711.5 28.9112.4 i Cards Field, Site 2 10.6 i 0.6 10.4 i 0.5 10.119.0 Lab, Cs-137 18.1 i 0.8 17.210.9 16.2 i 6.8 Eighth IntemationalIntercomparison 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. 10th International Intercomparison 115-10A LiF-100 Chips Aug,1993 Field 25.7i l.4 27.0 i l.6 26.4 i 10.2 Lab 22.711.6 25.9 i 1.3 25.0 9.4 I Lab 62.712.6 72.7 i 1.9 69.8 i 20.3 Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University. The Nineth 1nternational Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory. 1 A2-2 i I
Table A-2. Crosscheck program results; thermoluminescent dosimeters. (TLDs). mR Lab TBEESML Results Known Average 12 Sigma Code TLD Type Measurement i 2 Sigma Value i 2 Sigma (All Participants) 115-10B CaSO.:Dy Aug,1993 Field 26.012.3 27.011.6 26.4 10.2 Cards Lab 24.li l.7 25.911.3 25.019.4 Lab 69.2 i 3.0 72.7 i 1.9 69.8120.3 Tenth Intemational Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University. The Nineth InternationalIntercomparison of Environmental Dosimeters was not available to Tcledyne's Midwest Laboratory. Tatedvne 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 Isotopes. Chips were irradiated by Teledyne Isotopes, Inc., Westwood NJ. in September,1989 89-2 Teledyne Nov,1989 Lab 20.9 i 1.0 20.3 ND CaSO :Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Cards were irradiated by Teledyne isotopes, Inc., Westwood NJ. in November,1989. 90-1 Teledyne Jun,1990 Lab 20.611.4 19.6 ND CaSO :Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Cards were irradiated by Teledyne Isotopes,Inc., Westwood NJ. on June 19,1990. 90-2 Teledyne Sep,1990 Lab 100.8 i 4.3 100.0 ND CaSO :Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Cards were irradiated by Dosimetry Associates, Inc., Nortlwille, MI on October 30,1990. , l 91 1 Teledyne Oct,1990 Lab 33.4 2.0 32.0 ND CaSO.:Dy 55.214.7 58.8 ND Cards 87.8 6.2 85.5 ND ND = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on October 8,1991. 92-1 LiF-100 Chipr Feb,1992 Lab 11.110.2 10.7 ND 25.6 i 0.5 25.4 ND 46.410.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Chips were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on February 26,1992. 1 l l A2-3
Table A-2. Crosscheck program results; thermoluminescent dosimeters. (TLDs). ! 1 mR l Lab TBEESML Results Known Average i2 Sigma Code TLD Type Measurement 12 Sigma Value 2 Sigma (All Participants) 92 2 Teledyne Apr,1992 Lab, Reader 1 20.1 0.1 20.1 ND l CaSOpDy 40.610.1 40.0 ND Cards 60.0i l.3 60.3 ND Lab, Reader 2 20.310.3 20.1 ND 39.210.3 40.0 ND 60.7 i 0.4 60.3 ND N'D = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on April 1,1992. 93-1 Teledyne Mar,1993 Lab 10.0 i 1.0 10.2 ND LiF-100 Chips 25.5 i 2.2 25.5 ND 42.7 i 5.7 45.9 ND ND = No Data; Teledyne Testing was only performed by Teledyne Isotopes. Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on March 10,1993. l 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 available upon request. e i l l
^
1 I i l l
)
l A2-4 ! .I
l Table A 3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date TBEESML Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits QCMI-26 MILK Jan,1990 Cs-134 19.3 i 1.0 20.8 10.8 - 30.8 Cs-137 25.2 i l.2 22.8 12.8 - 32.8 QCMI-27 MILK Feb,1990 St 90 18.0il.6 18.8 8.8 - 28.8 QCMI-28 MILK Mar,1990 1 131 63.8 t 2.2 62.6 50.1 - 75.1 QCMI-29 MILK Apr,1990 I-131 90.719.2 82.5 66.0 - 99.0 Cs-134 18.3 i 1.0 19.7 9.7 - 29.7 I Cs-137 20.3 1.0 18.2 8.2 - 28.2 QCW-61 WATER Apr,1990 Sr-89 17.915.5 23.1 13.1 - 33.1 l St-90 19.412.5 23.5 13.5 - 33.5 l QCW-62 WATER Apr,1990 Co-60 8.7 0.4 9.4 0.0 - 19.4 Cs-134 20.010.2 19.7 9.7 - 29.7 Cs-137 28.7 i 1.4 22.7 12.7 - 32.7 QCW-63 WATER Apr,1990 1-131 63.5 i 8.0 66.0 52.8 - 79.2 QCW-64 WATER Apr,1990 H-3 1941.0 i 130.0 1826.0 1141.5 - 2510.5 QCW-65 WATER Jun,1990 Ra-226 6.4 i 0.2 6.9 4.8 - 9.0 l QCW-66 WATER Jun,1990 Uranium 6.2 0.2 6.0 3.6 - 8.4 QCMI-30 MILK Jul,1990 Sr-89 12.8 i 0.4 18.4 8.4 - 28.4 Sr-90 18.2 i 1.4 18.7 8.7 - 28.7 l l Cs-134 46.0 i 1.3 49.0 39.0 - 59.0 Cs-137 27.611.3 25.3 15.3 - 35.3 QCW-68 WATER Jul,1990 Gr. Alpha 9.8 0.3 10.6 0.6 - 20.6 Gr. Beta 11.410.6 11.3 1.3 - 21.3 QCMI-31 MILK Aug,1990 1-131 68.811.6 61.4 49.1 - 73.7 l QCW-69 WATER Sep,1990 St-89 17.7i l.6 19.2 9.2 - 29.2 Sr-90 13.9i l.6 17.4 7.4 - 27.4 ! MILK Oct,1990 1-131 34.8 i 0.2 32.4 20.4 - 44.4 QC MI-32 Cs 134 25.8 i 1.2 27.3 17.3 - 37.3 ( Cs-137 25.312.0 22.4 12.4 - 32.4 ( QCW-70 WATER Oct,1990 H-3 2355.0 59.0 2276.0 1577.3 - 2974.7 WATER Oct,1990 I-131 55.9 i 0.9 51.8 39.8 - 63.8 QCW-71 WATER Oct,1990 Co-60 18.312.7 16.8 6.8 - 26.8 QCW-73 Cs-134 28.312.3 27.0 17.0 - 37.0 Cs-137 22.7 i 1.3 22.4 12.4 - 32.4 WATER Dec,1990 Gr. Alpha 21.4 i l.0 26.1 13.1 - 39.2 QCW-74 Gr. Beta 25.911.0 22.3 12.3 - 32.3 A3-1
Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date TBEESML Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits QCMI-33 MILK Jan,1991 Sr-89 20.7 i 3.3 21.6 11.6 - 31.6 St-90 19.0 1.4 23.0 13.0 - 33.0 Cs-134 22.2 i 1.7 19.6 9.6 - 29.6 Cs-137 26.1 i 1.6 22.3 12.3 - 32.3 The cause of the low St-90 data is unknown. All data was reviewed, no errors where found in the calculations. De employee was observed performing this analysis and no deviations from the procedure where observed. 'Ihe employee's results have been good in the past; no further action is planned. QCMI-34 MILK Feb,1991 1-131 40.7i l.8 40.1 28.1 - 52.1 QCW-75 WATER Mar,1991 Sr-89 18.811.5 23.3 13.3 - 33.3 Sr-90 16.0 i 0.8 17.2 7.2 - 27.2 QCMI-35 MILK Apr,1991 1-131 48.0 0.8 49.2 37.2 - 61.2 Cs-134 19.2 i 2.0 22.6 12.6 - 32.6 Cs-137 22.8
- 2.2 22.1 12.1 - 32.1 QCW-76 WATER Apr,1991 1-131 56.5 i 1.7 59.0 47.2 - 70.8 QCW-77 WATER Apr,1991 Co-60 16.4 i 2.2 15.7 5.7 - 25.7 Cs-134 23.812.5 22.6 12.6 - 32.6 Cs-137 25.0 i 2.4 21.1 11.1 - 31.1 QCW-78 WATER Apr,1991 H-3 4027.0 i 188.0 4080.0 3264.0 - 4896.0 QCW-79 WATER Jun,1991 Gr. Alpha 7.4 1 0.7 7.8 0.0 - 17.8 Gr. Beta 11.010.7 11.0 1.0 - 21.0 SPM-36 MILK Jul,1991 Sr-89 28.1 i 2.1 34.0 24.0 - 44.0 Sr-90 11.6 i 0.7 11.5 1.5 - 21.5 I-131 14.4 i 1.9 18.3 6.3 - 30.3 Cs-137 34.3 i 3.0 35.1 25.1 - 45.1 The cause of the low Sr-89 data is unknown. All data was reviewed, no errors where found in the calculations. 'Ihe employee was observed performing this analysis and no deviations from the procedure where observed. The employee's results have been good in the past; no further action is planned.
QCMI-37 M1LK Oct,1991 1-131 23.6 i 3.2 25.8 13.8 - 37.8 Cs 134 22.712.8 22.1 12.1 - 32.1 Cs-137 38.3 i 3.0 35.1 25.1 - 45.1 QCW-80 WATER Oct,1991 Sr-89 27.4 i 6.9 24.4 14.4 - 34.4
. Sr-90 11.711.4 14.1 4.1 - 24.1 QCW-81 WATER Oct,1991 1-131 19.1 i 0.7 20.6 8.6 - 32.6 WATER Oct,1991 Co-60 22.612.7 22.1 12.1 - 32.1
( QCW-82 Cs-134 15.5 i 1.8 17.6 7.6 - 27.6 Cs-137 17.512.1 17.6 7.6 - 27.6 A3-2 )
i l Table A 3. In-house " spike" samples. l Concentration in pCi/L' Lab Sample Date TBEESML Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits WATER Oct,1991 H-3 4639.0 i 137.0 4382.0 3505.6 - 5258.4 QCW-83 WATER Dec,1991 Gr. Alpha 6.2 i 6.0 7.8 0.0 - 17.8 l QCW-84 Gr. Beta 11.0 0.7 11.0 1.0 - 21.0 hilLK Jan,1992 Sr-89 21.616.5 31.2 21.2 - 41.2 QCMI-39 l Sr-90 38.7 i 1.8 42.3 33.8 - 50.8 l-131 76.8 i 0.9 83.7 67.0 - 100.4 l ! Cs-134 42.115.7 49.4 39.4 - 59.4 Cs-137 55.2 6.4 53.0 43.0 - 63.0 The cause for the low result for Sr-89 analysis is unknown. Calculations and data were verified. l The results of the next Sr-89 analysis in milk where within controllimits (see sample QCMI-42 in this table). No further action is planned. WATER Mar,1992 Sr-89 26.2 i 3.1 32.0 22.0 - 42.0 QCW-85 Sr-90 24.4 i 1.4 28.0 18.0 - 38.0 The cause of the low Sr-89 and Sr-90 data is unknown. All data was reviewed, no errors where found in the calculations. The employee was observed performing these analyses and no deviations from the procedures where observed. The employee's results have been good in the past; no further action is planned. QCMI-40 hilLK Apr,1992 Cs-134 58.0 i 2.6 55.9 45.9 - 65.9 j 28.9 - 48.9 ! Cs-137 43.7 i 3.0 38.9 QC MI-41 MILK Apr,1992 I-131 50.3 0.8 55.9 44.7 - 67.1 l QCW-86 WATER Apr,1992 H-3 4080.0 190.0 4027.0 3221.6 - 4832.4 QCW-87 WATER Apr,1992 1-131 33.5i0.6 33.2 21.2 - 45.2 WATER Apr,1992 Co-60 17.512.7 19.7 9.7 - 29.7 QCW-88 Cs-134 28.912.5 33.5 23.5 - 43.5 Cs-137 41.013.0 38.9 28.9 - 48.9 WATER Jun,1992 Gr. Alpha 15.310.8 13.6 3.6 - 23.6 i QCW-89 I Gr. Beta 17.210.9 17.6 7.6 - 27.6 MILK Aug,1992 Sr-89 41.4 i 5.9 51.2 41.0 - 61.4 QCMI-42 Sr-90 48.912.5 51.9 41.5 - 62.3 Cs-134 20.1 i 2.8 20.2 10.2 - 30.2 Cs-137 26.212.7 26.1 16.1 - 36.1 The cause of the low Sr-89 data is unknown. All data was reviewed, no errors where found in the calculations. The employee was observed performing this analysis and no deviations from the procedure where observed. The employee's results have been good in the past; no further action is planned. 1 I l l i A3-3
Table A-3. In-house " spike" samples. Concentration in pCi/11 Lab Sample Date TBEESML Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits QCW-90 WATER Sep,1992 Sr-89 6.7i 3.4 12.6 2.6 - 22.6 Sr-90 16.1 i 1.4 15.6 5.6 - 25.6 The cause for the low result for Sr-89 analysis is unknown. Calculations and data were verified. The results of the next Sr-89 analysis in water where within control limits (see sample SPW-3556 in this table). No further action is planned. QCMI-43 MILK Oct,1992 I-131 19.9 i 1.0 21.5 9.5 - 33.5 Cs-134 14.2 3.4 12.7 2.7 - 22.7 Cs-137 14.1 i 5.2 17.1 7.1 - 27.1 QCMI-44 MILK Oct,1992 1-131 36.1 i 1.2 43.0 31.0 - 55.0 Cs-134 28.2 4.0 25.4 15.4 - 35.4 Cs-137 38.815.1 34.2 24.2 - 44.2 The cause of the low 1-131 data is unknown. All data was reviewed, no errors where found in the calculations. The employee was observed performing this analysis and no deviations from the procedure where observed. The employee's results have been good in the past; no further action is planned. QCW-91 WATER Oct,1992 I-131 34.912.2 34.9 22.9 - 46.9 QCW-92 WATER Oct,1992 Co-60 11.4 i 1.9 9.2 0.0 - 19.2 Cs-134 18.7 i 2.3 14.3 4.3 - 24.3 Cs-137 14.111.8 15.0 5.0 - 25.0 QCW-93 WATER Oct,1992 H-3 3704.0 t 186.0 3904.0 3169.2 - 4638.8 QCW-94 WATER Oct,1992 H-3 14925.0 i 339.0 15616.0 12492.8 - 18739.2 QCW-95 WATER Oct,1992 1-131 64.212.7 67.2 53.8 - 80.6 QCW-36 WATER Dec,1992 Alpha 11.512.3 15.2 9.1 - 21.3 Beta 26.5 2.0 25.7 15.4 - 36.0 QCW-96 WATER Dec,1992 Gr. Alpha 8.310.6 10.4 0.4 - 20.4 Gr. Beta 19.811.5 20.6 10.6 - 30.6 SPM-3341 MILK Jan,1993 St-89 6.713.1 8.7 0.0 - 18.7 Sr-90 20.0 i 1.2 19.2 9.2 - 29.2 Cs-134 17.1 i 2.0 21.3 11.3 31.3 Cs-137 21.4 i 2.0 23.8 13.8 - 33.8 SPM-3387 MILK Feb,1993 1-131 72.5 i 8.4 71.5 57.2 - 85.8 SPVE-3401 VEGETATION F,eb,1993 1-131 994.5 1 53.2 953.7 763.0 - 1144.4 (SAW DUST) SPCH-3402 CHARCOAL Feb,1993 1-131 95.2 i 12.8 95.4 76.3 - 114.5 SPW-3434 WATER Apr,1993 Gr. Alpha 10.4 i 1.8 10.4 0.4 - 20.4 Gr. Beta 22.012.0 20.6 10.6 - 30.6 l l l A3-4 l l } 1
Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date TBEESML Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits SPW-3556 WATER Apr,1993 Sr-89 18.215.0 22.2 12.2 - 32.2 Sr-90 20.lil.8 17.0 7.0 - 27.0 SPW-3597 WATER Apr,1993 H-3 5464.0 i 219.0 5428.0 4342.4 - 6513.6 ) SPW-3599 WATER Apr,1993 I-131 149.8 i l.9 145.0 116.0 - 174.0 SPW-3606 WATER Apr,1993 Co-60 24.8 i 2.3 21.5 11.5 - 31.5 Cs-134 26.4 i l.9 26.4 16.4 - 36.4 Cs-137 33.9 i 2.6 31.7 21.7 - 41.7 SPM-3631 MILK Apr,1993 1-131 139.8 t l.6 145.0 116.0 - 174.0 Cs-134 48.8 i 2.9 52.8 42.8 - 62.8 Cs-137 65.2 i 2.9 63.4 53.4 - 73.4 SPF-3681 FISH May,1993 Cs-137 68.2 i 7.7 67.6 57.6 - 77.6 UELLO) Concentrations are in pCi/ Total Volume (550g). SPW-3842 WATER Jun,1993 Th-230 4.210.5 4.5 2.7 - 6.3 SPW-4160 WATER Jun,1993 Alpha 8.9 i l.4 12.9 7.7 - 18.1 Beta 22.0 i 1.9 31.9 19.1 - 44.7 j SPW-4232 WATER Aug,1993 Fe-55 1684.0 i 415.0 1420.0 1136.0 - 1704.0 l SPW-4246 WATER Aug,1993 Sr-90 32.2 i 2.6 30.4 24.3 - 36.5 : SPM-4247 MILK Aug,1993 Sr-89 29.1 i 4.9 35.4 25.4 - 45.4 f Sr-90 18.3 i 1.3 19.2 9.2 - 29.2 SPW-4248 WATER Aug,1993 H-3 9910.0 1 300.0 10430.0 8344.0 - 12516.0 SPW-4250 WATER Aug,1993 Co-60 247.0 i 23.1 247.7 222.9 - 272.5 Cs-134 141.6i l5.9 141.1 127.0 - 155.2 , Cs-137 283.5 1 27.8 247.2 222.5 - 271.9 The cause of the high Cs-137 data is unknown. All data was reviewed, no errors where found in the calculations. The employee was observed performing this analysis and no deviations from l the procedure where observed. The employee's results have been good in the past; no further action is planned. SPF-4251 FISH 0ELLO) Aug,1993 Cs-134 68.8 i 3.3 75.3 65.3 - 85.3 Cs-137 203.6 i 8.2 198.1 178.3 - 217.9 SEDIMENT Aug,1993 Cs-134 74.1 i 9.9 71.0 61.0 - 81.0 SPS-4262 (BOTTOM) Cs-137 4 i 14.8 197.8 178.0 - 217.6 WATER $p,1993 1-131 39.0110.0 42.1 30.1 - 54.1 SPW-4377 MILK Sep,1993 1-131 44.515.5 42.1 30.1 - 54.1 SPM-4378 SPCH-4379 CHARCOAL Sep,1993 1-131 90.3113.5 84.3 67.4 - 101.2 SPVE-4380 VEGETATION Sep,1993 1-131 193.2 1 20.0 170.2 136.2 204.2 (SAW DUST) l I A3-5 l
Table A-3. In-house " spike" samples. 1 Concentration in pCi/L' l Lab Sample Date TBEESML Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits SPW-4381 WATER Sep,1993 Sr-89 21.9 i 4.0 28.8 18.8 - 38.8 Sr-90 19.5 i 1.8 19.0 9.0 - 29.0 SPW-4382 WATER Sep,1993 I-129 18.111.0 18.6 6.6 - 30.6 SPW-4421 WATER Oct,1993 H-3 16900.0 i 368.0 17380.0 13904.0 - 20856.0 SPW-4428 WATER Oct,1993 Co-60 19.3 i 3.1 18.3 8.3 - 28.3 Cs 134 31.513.3 33.5 23.5 - 43.5 Cs-137 44.413.6 43.2 33.2 - 53.2 SPM-4426 MILK Oct,1993 I-131 49.7 i 8.6 44.5 32.5 - 56.5 Cs-134 30.814.5 33.0 23.0 - 43.0 Cs-137 43.4 i 6.0 43.2 33.2 - 53.2 SPW-4427 WATER Oct,1993 1-131 95.2 i 10.6 88.9 71.1 - 106.7
' All results are in pCi/L, except elemental potassium (K) data in milk, which are in mg/L; air filter l samples, which are in pCi/ Filter; charcoal which are in pCi/ charcoal; and food products which are in mg/kg.
6 All samples prior to January 1991 are the results or three determinations; after January 1991, all determinations are single. Control Limits are based on EPA publication;" Environmental Radioactive Laboratory Intercomparison Studies Program", Fiscal Year 1981-1982, EPA-600/4-81-004 (see Attachment A) or limits imposed by TBEESML. i l 1 A3-6 I l
i j ~ Table A-4. In-house " blank" samples. Concentration pCi/L'. l TBEESML Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria j Code Tvoe Date Analyses LLD Activitvo (4.66 Sigma) l SPW 8039 WATER Jan 1990 Ra 226 < 0.2 < 1.0 SPM-8040 MILK Jan 1990 St-89 < 0.8 < 5.0 Sr 90 < 1.0 < 1.0 SPM-8208 MILK Jan 1990 Sr 89 < 0.8 < 5.0 Sr 90 N/A 1.6 i 0.5 < 1.0 Cs 134 < 3.6 < 10.0 Cs-137 < 4.7 < 10.0 l Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. ) SPM-8312 MILK Feb l990 Sr-89 < 0.3 < 5.0 l St 90 N/A 1.2 i 0.3 < 1.0 j Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPW 8312 WATER Feb 1990 Sr-89 < 0.6 < 5.0 Sr-90 < 0.7 < 1.0 SPM-8314 MILK Mar 1990 1-131 < 0.3 < 1.0 SPM-8510 MILK May 19901131 < 0.2 < 1.0 Cs-134 < 4.6 < 10.0 l Cs-137 < 4.8 < 10.0 ' l SPW-8511 WATER May 1990 H-3 < 200.0 < 300.0 SPM-8600 MILK Jul1990 Sr-89 < 0.8 < 5.0 l Sr 90 N/A 1.7 i 0.6 < 1.0 1131 < 0.3 < 1.0 i Cs-134 < 5.0 < 10.0 i Cs-137 < 7.0 < 10.0 l Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPM-8877 MILK Aug 1990 1-131 < 0.2 < 1.0 l SPW-8925 WATER Aug1990 H 3 < 200.0 < 300.0 SPW-8926 WATER Aug1990 Gr. Alpha < 0.3 < 1.0 Gr. Beta < 0.7 < 5.0 SPW-8927 WATER Aug1990 U-234 < 0.01 < 1.0 U 235 < 0.02 < 1.0 U 238 < 0.01 < 1.0 SPW-8928 WATER Aug1990 Mn-54 < 4.0 < 10.0 l Co-58 < 4.1 < 10.0 Co-60 < 2.4 < 10.0 Cs-134 < 3.3 < 10.0 Cs-137 < 3.7 < 10.0 SPW-8929 WATER Aug1990 St 89 < 1.4 < 5.0 Sr-90 < 0.6 < 1.0 A4-1
Table A-4. In-house " blank" samples. Concentration pCi/L'. TBEESML Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Type Date Analyses LLD Activitv 6 (4.66 Sigma) l Code SPW 69 WATER Sep 1990 St-89 < 1.8 <5.0 i Sr 90 < 0.8 < 1.0 SPW 106 WATER Oct 1990 H-3 < 180.0 < 300.0 1131 < 0.3 < 1.0 SPM-107 M1LK Oct 1990 1-131 < 0.4 < 1.0 Cs-134 < 3.3 < 10.0
- Cs-137 < 4.3 < 10.0 SPW-370 WATER Oct 1990 Mn-54 < 1.7 < 10.0 Co-58 < 2.6 < 10.0 Co-60 < 1.6 < 10.0 Cs-134 < 1.7 < 10.0 Cs-137 < 1.8 < 10.0 SPW-372 WATER Dec 1990 Gr. Alpha < 0.3 < 1.0 Gr. Beta < 0.8 <5.0 SPM-406 MILK Jan 1991 Sr-89 < 0.4 < 5.0 Sr-90 N/A 1.8 i 0.4 < 1.0 Cs-134 < 3.7 < 10.0 Cs-137 < 5.2 < 10.0 Low level of Sr-90 concentration in milk (1 5 pCi/L) is not unusual.
SPM-421 MILK Feb 1991 1-131 < 0.3 < 1.0 i SPM-451 MILK Feb l991 Ra 226 < 0.1 < 1.0 Ra-228 < 0.9 < 1.0 SPW 514 WATER Mar 1991 Sr-89 < 1.1 < 5.0 Sr-90 < 0.9 < 1.0 SPW 586 WATER Apr 1991 1-131 < 0.2 < 1.0 Co-60 < 2.5 < 10.0 Cs-134 < 2.4 < 10.0 Cs-137 < 2.2 < 10.0 SPM-587 MILK Apr 1991 1-131 < 0.2 < 1.0 Cs-134 < 1.7 < 10.0 Cs-137 < 1.9 < 10.0 SPW 837 WATER Jun1991 Gr. Alpha < 0.6 < 1.0 Gr. Beta < 1.1 <5.0 SPM-953 MILK Jul1991 Sr 89 < 0.7 < 5.0 Sr-90 N/A 0.4 0.3 < 1.0 I-131 < 0.2 < 1.0 Cs-137 < 4.9 < 10.0 SPM-1236 MILK Oct 1991 1-131 < 0.2 <1.0 Cs-134 < 3.7 < 10.0 Cs-137 < 4.6 <10.0 l A4-2 l l
Table A-4. In-house " blank" samples. Concentration pCi/L'. TBEESML Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Date Analyses ILD Activitv 6 (4.66 Sigma) Code Tvoe SPW-1254 WATER Oct 1991 Sr-89 < 2.8 < 5.0 Sr-90 < 0.7 < 1.0 SPW-1256 WATER Oct 1991 1-131 < 0.4 < 1.0 Co-60 < 3.6 < 10.0 Cs-134 < 4.0 < 10.0 Cs-137 < 3.0 < 10.0 SPW-1259 WATER Oct 1991 H-3 < 160.0 < 300.0 SPW-1444 WATER Dec 1991 Gr. Alpha < 0.4 < 1.0 Gr. Beta < 0.8 < 5.0 SPM-1578 MILK Jan 1992 Sr-89 < 0.5 < 5.0 Sr-90 N/A 1.310.4 < 1.0 1-131 < 0.2 < 1.0 Cs-134 < 7.2 < 10.0 Cs-137 < 8.0 < 10.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPW-1860 WATER Mar 1992 Sr-89 < 0.6 < 5.0 Sr 90 < 0.4 < 1.0 SPW-2067 WATER Apr1992 H 3 < 168.0 < 300.0 SPW-2114 WATER Apr 1992 C-14 < 1.0 < 200.0 SPM-2119 MILK Apr 1992 Co-60 < 6.3 < 10.0 l Cs-134 <4.5 < 10.0 j Cs-137 < 5.4 < 10.0 SPW-2126 WATER Apr 1992 1-131 < 0.2 < 1.0 SPM-2133 MILK Apr 1992 I-131 < 0.2 < 1.0 SPW-2220 WATER May 1992 Co-60 < 2.1 < 10.0 Cs-134 < 2.1 < 10.0 CS-137 < 2.3 < 10.0 SPW-2369 WATER Jun1992 Gr. Alpha < 0.4 < 1.0 Gr. Beta < 0.8 < 5.0 SPM-2500 MILK Aug1992 I-131 < 0.4 < 1.0 Sr-89 < 1.2 < 5.0 Sr-90 < 0.9 < 1.0 SPW-2666 WATER Sep 1992 Sr-89 < 0.8 < 5.0 Sr-90 < 0.5 < 1.0 WATER Oct 1992 Co-60 < 4.8 < 10.0 SPW-2828 Cs-134 < 6.0 < 10.0 Cs-137 < 6.1 < 10.0 I-131 < 0.3 < 1.0 H-3 < 177.0 < 300.0 A4-3
Table A-4. In-house " blank" samples. l 1 Concentration pCi/L'. TBEESML Results Acceptance , Lab Sample Sample (4.66 Sigma) Criteria ' Code Tyne Date Analyses LLD Activity b (4.66 Sigma) l SPM 2829 MILK Oct 1992 Co-60 < 9.3 < 10.0 1 Cs-134 < 6.4 < 10.0 Cs-137 < 7.2 < 10.0 SPW-3212 WATER Oct 1992 Ra-228 < 1.0 < 1.0 j SPW-3057 WATER Nov1992 Ra-226 < 0.03 < 1.0 SPW-3294 WATER Dec 1992 Gr. Alpha < 0.4 < 1.0 Gr. P, eta < 0.8 < 5.0 SPM-3342 MILK Jan 1993 Sr-89 < 0.7 -0.9 i 1.1 < 5.0 Sr-90 N/A 1.6 i 0.5 < 1.0 Cs-134 < 4.1 -0.9 2.6 < 10.0 l Cs-137 < 3.9 0.8 i 2.2 < 10.0 Low levels of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPM-3386 MILK Feb 1993 I-131 < 0.2 0.1 1 0.1 < 1.0 SPW-3557 WATER Mar 1993 Sr-89 < 0.5 0.3 i 0.5 < 5.0 Sr-90 < 0.5 0.1 1 0.2 < 1.0 SPW-3598 WATER Apr 1993 H-3 < 180.0 84.7 i 94.2 < 300.0 SPW-3600 WATER Apr 1993 1-131 < 0.2 0.110.2 < 1.0 SPW-3601 WATER Apr1993 Co-60 < 4.2 < 10.0 1 Cs-134 < 4.4 < 10.0 l Cs-137 < 3.4 < 10.0 l I-131 < 0.4 0.3 i 0.9 < 1.0 l Activity results for the gamma-emitters are not available for this sample. SPM-3651 MILK May 19931-131 < 0.2 0.110.1 < 1.0 Cs-134 < 4.4 < 10.0 l Cs-137 < 6.3 < 10.0 Activity results for the gamma-emitters are not available for this sample. SPFP-3680 FOOD May 1993 Cs-137 <6.5 0.0 1 0.0 < 10.0 SPW-3844 W.ATER Jun1993 Th-228 < 0.1 0.0 i 0.1 < 1.0 Th-230 < 0.1 0.210.1 < 1.0 Th-232 <0.1 0.010.0 < 1.0 SPW-4234 WATER Jun1993 Gr. Alpha < 0.3 0.0 1 0.2 < 1.0 Gr. Beta < 0.8 0.2 0.3 < 5.0 SPS-4059 SEDIMENT Jul1993 Cs-134 <5.0 0.0 i 0.0 < 10.0 (BOTTOM) Cs-137 < 7.2 0.0 0.0 < 10.0 SPVE-4060 VEGETATION Jul1993 1-131(g) < 13.5 0.0 i 0.0 < 20.0 (SAW DUST) Cs-134 < 4.8 0.0 1 0.0 < 10.0 , Cs-137 < 6.4 0.0 i 0.0 < 10.0 ll SPM-4061 MILK Jul1993 Cs-134 < 8.6 0.0 0.0 < 10.0 Cs-137 < 5.8 0.0 i 0.0 < 10.0 A4-4 ; i
)
d I Table A-4. In-house " blank" samples, l Concentration pCi/L'. TBEESML Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria l (4.66 Sigma) Code Tvtse Date Analyses LLD Activity b SPM-4062 MILK Jul1993 Cs-134 < 3.8 1.5 i 1.5 < 10.0 l Cs-137 < 4.4 -1.6 i 3.3 < 10.0 SPW-4063 WATER Jul1993 Co-60 <4.0 1.2 2.3 < 10.0 Cs-134 < 3.7 0.3 1.2 < 10.0 Cs-137 <3.2 0.4 1 3.2 < 10.0 SPAP-4064 AIR FILTER Jul1993 Cs-134 < 2.1 0.0 i 0.0 < 10.0 l (COMPOSITE) Cs-137 < 2.8 0.0 i 0.0 < 10.0 SPCH-406 CHARCOAL Jul1993 I-131 < 0.1 0.0 i 0.0 < 1.0 8 l Based on a volume of 300 m l SPW-4233 WATER Aug1993 Fe-55 < 506.0 0.0 i 0.3 < 1000.0 l SPM-4235 MILK Aug 1993 1-131 < 0.1 0.0 1 0.2 < 1.0 l Cs-134 < 8.1 1.6 1 1.8 < 10.0 ; Cs-137 < 4.2 -1.7 i 3.4 < 10.0 St-89 < 0.8 -1.0 i 1.1 < 5.0 Sr-90 N/A 1.8 0.5 < 1.0 l Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. l SPW-4241 WATER Aug1993 H-3 < 190.0 72.9 i 99.1 < 300.0 l SPW-4243 WATER Aug1993 Sr-89 <1.1 -0.6 i 0.9 < 5.0 l Sr-90 < 0.7 0.4 0.4 < 1.0 l I-131 < 0.5 0.0 0.1 < 1.0 Co-60 < 7.0 0.4 i 3.1 < 10.0 Cs-134 < 7.6 0.8 i 15.6 < 10.0 Cs-137 < 5.4 -0.7 i 4.2 < 10.0 l SPW-4244 WATER Aug1993 U-233/234 < 0.1 0.1 i 0.1 < 1.0 i U-235 < 0.1 0.0 0.1 < 1.0 U-238 < 0.1 0.1 0.1 < 1.0 l l Th-228 < 0.4 -0.1 1 0.3 < 1.0 Th-230 < 0.1 0.0 i 0.1 < 1.0 Th-232 < 0.1 0.0 i 0.0 < 1.0 Pu-238 < 1.0 0.4 1 0.7 < 1.0 Pu-239/240 < 0.3 0.1 0.2 < 1.0 SPW-4245 WATER Aug1993 Ra-226 <0.1 0.0 0.0 < 1.0 Ra-228 < 0.8 -0.2 0.5 < 1.0
~
SPW-4422 WATER Oct 1993 H-3 < 180.0 -27.5188.9 < 300.0 f 0 All results are in pCi/L, except for air filter samples, which are in pCi/ Filter.
- Prior to 1993, results where reported as only an LLD, the activity reported is the net activity result.
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