ML20042F379
| ML20042F379 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1989 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ND3VPN:6162, NUDOCS 9005080257 | |
| Download: ML20042F379 (171) | |
Text
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Reference:
Beaver Valley Power Station Unit No. I t Docket No. 50-334, License No. DPR-66 Beaver Valley Power Station Unit No. 2 Docket No. 50-412, ticense No. NPT-73 1989 Annual Environmental Report Radiological - Volume #2 Gentlemen The 1989 Annual Environmental Report (Radiological - Volume #2), is hereby submitted in accordance with the requirements of Technical Specifications 6.9.1.10 and 6.9.1.11 f or Beaver Valley Power Station Unit I license DPR-66 and Beaver Wiley Pover Station Unit 2 license NPF-73. Very truly yours,
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.D }f 5febN Vice President Nuclear Group JVHicat Enclosure cci United States Nuclear Regulatory Commission Regional Administrator, Region 1 475 Allendale Road King of Prussia, PA 19406 United States Nuclear Regulatory Commission Resident-Inspector Beaver Valley Power Station Ms. Dottie Sherman American Nuclear Insurer's Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 9005080257 900430 PDR ADOCK 05000334 ((h R PDC
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l 1989 ANNUAL ENVIRONMENTAL' REPORT RADIOLOGICAL - VOLUME #2 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNITS 1 AND 2
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I DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report EXECUTIVE
SUMMARY
This report describes the Radiological Environmental. Monitoring Program conducted during 1989 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 , I. sediments, soils, food pathway samples,-and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1989.
I Duquesne Light _ Coarpany 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 I was shutdown on September 1, 1989 for the Seventh Refueling Outage. Unit 1 was returned to service on December 26, 1989. The highest average daily output generated during the year was 817 megawatts net 'in March, 1989, and the total gross electrical generation during the year was 4,026,350 megawatt-hours. Beaver Valley Power Station Unit 2 was shutdown on March 17, 1989 for the First Refueling Outage. Unit 2 was returned to service on May 29, 1989 and operated throughout the year. The highest average daily output guerated during the year was 821 megawatts net in October, 1989, and the total gross electrical generation during the year was 4,836,300 megawatt-hours. I
DUQUESNE LIGHT COMPANY , 1989 Annual Radiological Environmental Report i EXECUTIVE
SUMMARY
(continued) ( In 1989, samples were taken from over 60 sites around Beaver ! ii Valley Power Station that included the aquatic, atmospheric and - terrestrial environments. More than 3,000' analyses were performed on these samples. I During the year, the-radioactive releases from BVPS Units 1 and-2 - ! did not exceed the Limiting-Conditions for Operation identified in. .;- the -Beaver Valley Power Station ' Operating License Technical .q 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 -
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(4 million people) . from the operation o. Beaver Valley Power Station - Unit No. I and No. 2, is less=than 0.0003%_of the annual background. See Section V.I for specific details. The National Academy of Sciences 1980 BEIR Report shows that'the typical dow to- an individual from natural radiation exposure is 101 mrem per year. r. i The environmental monitoring program outlined in-the Beaver Valley Power Station Units 1 and 2 Technical Specifications was followed throughout 1989. 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. 4
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DUQUESNE LIGliT COMPANY d 1989 Annual Radiological Environmental Report r TABLE OF CONTENTS l P_agg EXECUTIVE
SUMMARY
--------------------- 1 I. INTRODUCTION----------------------------------------------- 1 A. Scope and Objectives of the Program 1 i
B. Description of the Beaver Valley Site 1
-)
-4 II ' RE SULTS & COL'C LUS I ONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 6 l i
III. ENVIRONMENTAL MONITORING CONSIDERATIONS-------------------- 8 l A. -Environmental Quality Control Programs' 8 B.- Evaluation of the Quality Control (QC) Program Data 24 C. Standard Requirements and Limitations for Radiological -l
.and Other Effluents 24 D. Reporting Levels 25 IV. MONITORING EFFLUENTS--------------------------------------- 26 ,
d A. Monitoring of Liquid Effluents 26 i
- 1. Effluent Treatment, Sampling, and Analytical l Procedures 32 i i
- 2. Results 32 B. Monitoring of Airborne Effluents 33
- 1. Description of Airborne Effluent Sources 33
- 2. Airborne Iffluent Treatment and Sampling 37 ;
- 3. Results 41 C. Solid Waste Disposal 42 l
3
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DUQUESNE LIGHT COMPANY 1989 Annual-Radiological Environmental Report ; TABLE OF CONTENTS (Continued) [ V. ENVIRONMENTAL MONITORING PROGRAM h A. Environmental Radioactivity Monitoring Program 44
- 1. Program Description 44
- 2. . Summary of Results 51
- 3. Quality Control Program 51 _
B. Air Monitoring '67 .g j
- 1. Characterization of Air and Meteorology 67
- 2. Air Sampling Program and Analytical Techniques 67
- 3. Results and Conclusions 70 C. Monitoring of Sediments and Soils 73
- 1. Characterization of Stream Sediments and Soils ~ 73
- 2. Sampling Program and Analytical Techniques 73
- 3. Results and Conclusions 75 D. Monitoring of Feederops and Foodcrops: 77
- 1. Characterization of Vegetation and'Fooderops- 77
- 2. Sampling Program and Analytical Techniques 77
- 3. Results and Conclusions 80 L
j- E. Monitoring of Local Cow's Milk 82
- 1. Description - Milch Animal Locations 82
- 2. Sampling Program and Analytical Techniques 82 l
- 3. Results and Conclusions 86 i i l l
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DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report TABLE OP CONTENTS (continued)' V. ENVIRONMENTAL MONITORING PROGRAM (continued) h [- F. Environmental Radiation Monitoring BB
- 1. Description of Regional Background Radiation Levels and Sources 88
- 2. Locations & Analytical Procedures 88
.3, Results and Conclusions 89
.G. Monitoring of Pish 96
- 1. Description 96
- 2. Sampling Program and Analytical Techniques 96
- 3. Results and Conclusions 96 H. Monitoring of Surface, Drinking, Well Waters, '
and Precipitation 98 Description of Water Sources
- 1. 98
- 2. Sampling Program and Analytical Techniques 99 j i
- 3. Results and Conclusions 102
.I I. Estimates of Radiation Dose to Man 106 [
- 1. Pathways to Man - Calculational Models 106 l 2. Results of Calculated Radiation Dose to Man - Liquid Releases 107
]
- 3. Results of Calculated Radiation Dose -
to. Man - Airborne Releases 110 l
- 4. Conclusions - Beaver Valley Power Station 111 ,
I a Appendix I Contractor Laboratory EPA Interlaboratory , Comparison Program J Appendix II QC Laboratory EPA Interlaboratory Comparison Program
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DUQUESNE LIGHT COMPANY 1989 Annual Radiological = Environmental Report-l LIST OF FIGURES
]
Figure j No, M
- 1.0 View of the Beaver Valley Site 3 J 1.1 Geographical Map - 40 Mile Radius 4 I 4.1 Liquid Discharge Points to Ohio River 27 4.2 Water Flow Schematic-- l Beaver Valley Power Station Unit 1 28 4.3 Water Flow Schematic -
Beaver Valley Power Station Unit 2 29 4.4 Liquid Radwaste' Systems - . Beaver Valley Power Station Unit 1 30 4.5 Liquid Radwaste Systems - g 4.6 Beaver Valley Power Station Unit 2 Gaseous Waste Processing - 31 gs i Beaver Valley Power Station Units 1 and'2 35 . 4.7 Gascous Release Points - Beaver Valley Power Station Units 1 and 2 36 - 4.8 Solid Waste Disposal Diagram 43 i 5.B.1 Environmental Monitoring Locations - Air Sampling Stations 69 5.B.2 Concentrations of Gross Beta in Air Particulates 71 S . C .1 - Environmental Monitoring Locations - Sediments 74 . . 5.D.1 Environmental Monitoring Locations - Feederop and Fooderop 78 5.E.1 Dairy Farm Locations (August September 1989 Survey) 84-5.E.2 Environmental Monitoring Locations - Milk 85 .; 5.F.1 Environmental Monitoring Locations - TLDs 90 5.F.2 Environmental Monitoring-Locations - TLDs 91 5.F.3 Environmental Monitoring-Locations - TLDs 92 5.F.4 Environmental Monitoring Locations-- TLDs 93 5.F.5 Environmental Monitoring Locations - PICS 94 5.G.1 Environmental Monitoring Locations - Fish 97 5.H.1 Surface Water and Wells - Locations 101 l l
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I DUQUESNE L1GHT COMPANY
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1989 Annual Radiological Environmental Report I.- LIST OF TABLES Table Number Pm III.1 Quality Control Data - TLD Comparisons 9 III.2 Quality Control Data - Water' Split Samples 10 III.3. Quality Control Data - Split Samples - Miscellaneous 12 III.4 Quality Control Data - Spiked Samples 16 III.5 Quality Control Data - Spiked Samples . 17 III.6 Quality Control Data - Air Particulates and I-131 18 III 7 Quality Control Data - Milk and Water 22
.; IV.A.1 Effluent Treatment, Sampling and Analytical ;
Procedures Beaver Valley Power Station 32 IV.A.2 Results - Liquid Effluents - Beaver Valley 1 Power Station 32 IV.B.1 Radioactive Gaseous Waste Sampling and Analysis Program 39 V.A.1 Environmental Monitoring Program Summary 45 V.A.2 Environmental Monitoring Program Results (1989) 52 V.A.3 Pre-Operational Monitoring Program Results (1974-1975) 62 V.A.4 Typical LLDs for Gamma Spectrometry - DLC Contractor 66 V.D 1 Closest Residence and Garden.in Each Sector 79 V.F.1 Pressurized Ion Chambers Results 95 V.I.1 Radiation Dose to Maximum Individual - Beaver Valley Power Station - Liquid Releases 108 V.I.2 Results of Calculated Radiation Dose to Man - Beaver Valley Power Station - . E: Liquid Releases . 109 l3 V.I.3 Results of Calculated Radiation Dose to Man - Beaver Valley Power Station - Airborne Releases 112 l l lI I -vil-lI
P t SECTION I DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report-I. INTRODUCTION
- A. Scope and Objectives of the Program 3 The environmental- program consists- of -environmental
- g monitoring for radioactivity.in the vicinity of the Beaver g Valley Power Station. Environmental sampling and analyses .l included air, water, milk, soil, vegetation, river sediments, t fish, and ambient radiation levels in areas surrounding the ;
site. The results of these media are assessed to determine
.I impacts of the plant Loperation- on' the environment. The Annual Radiological Environmental = Report for the Beaver Valley Power Station summarizes the radiological .p I. environmental program conducted by the Duquesne Light Company in 1989. '
. B. Description of the Beaver Valley Site-The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver I. County,. Pennsylvania, on a 501 acre tract of land. Figure 4 1.0 is a view of the Beaver Valley Power Station. _ The site ; is approximately one mile from Midland, Pennsylvania; 5 miles ' from East Liverpool, Ohio; and 25. miles from Pittsburgh, . Pennsylvania. Figure 1.1.shows the site location in relation- ! to the principal population centers. Population density 'in the immediate vicinity of the site is relatively low. The ..I population within a 5 mile radius 'of the plant is approximately 18,000 and the only area within that radius'of concentrated population is the Borough of Midland, , I- Pennsylvania, with a population of'approximately 4,300. The . site lies in a valley along the Ohio River. I It extends. from the river (elevation 665 feet above sea level) to a , l ridge along the border. south of the Beaver Valley Power f l Station at an elevation of 1,160 feet. Plant ground level is approximately 735 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 l 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 I ranges from a minimum of approximately 5000 cubic feet per second (CFS) to a maximum of approximately 100,000 CFS. mean annual flow is approximately 25,000 CFS. The g . , 1
SECTION I DUQUESN2 LIGirr COMPANY I 1989 Annual Radiological Environmental Report-B. Description of the Beaver Valley Site (continued)
. Water temperature of the-Ohio River varies from 32'F to B4*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 precipitation is- approximately 36 l{ inches, typical yearly temperatures vary from approximately - 5 i 3'T to 93*F with an annual average -temperature of 52.8'F. ; The predominant wind direction is typically from the. I southwest in summer and from the northwest in winter, 3 g. f I . i i
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SECTION.I FIGURE 1.1 l DUQUESNE LIGHT COMPANY I 1989 Annual Radiological Environmental Report g YOUNGSO( g"w i h i 2 -NEW CASTLE - ALLIANCE
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BORO OF 30 SHIPP g g
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l_ BEAVER VALLEY' POWER STATION FIGURE 1.1 -
i SECTION I -DUQUESNE LfGHT COMPANY , 1989 Annual Radiological Environmental Report' , I. INTRODUCTION i
- 0. Description of the Beaver Vs11ey Site (continued)'
i The design ratings and basic features of the Beaver Valley Power station Units 1 and-2 are tabulated below: r Beaver Valley Unit l' Beaver Valley Unit 2 , Thermal & Ele:. ' q Rating (Net MW, ) 2660 FM 835 FN , 2660 FN . 836 FM , Type of Reactor PWR PWR No. of Reactor , Coolant Loops 3 3 No. of Steam Generators & Type 3'- Vertical 3 - Vertical , f-Steam Used by-Main Turbine Saturated Saturated .e The units utilize. two separate systems (primary and secondary) for transferring heat from the ssurce (the. l reactor) to the receiving component (turbine generator). g Because the two systems are' isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in I" ,- the primary system water is normally ' isolated from the
- secondary system. Reactor coolant in the primary system is pumped through the reactor core'and steam generators by means of reactor coolant pumps. Heat is given up from-the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed L after passing through the turbine, and returned to'the steam generators to begin another steam / water cycle.
i l NOTE: FN g - megawatts thermal FM, megawatts electrical r-
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SECTION.ll DUQUESNE LIGHT COMPANY ! 1989 Annual Radiological Environmental Report II. RESULTS AND CONCLUSIONS Plant operations at the Beaver Valley Power Statien had no adverse effects on the environment as a result of activity at the station during 1989. The Beaver Valley Power Station Unit I was shutdown on September 1,.1989 for the Seventh Refueling Outage. Unit I was returned -to # service on December 26, 1989. Beaver-Valley Power Station Unit 2
, was-shutdown on' March 17, 1989.for the First Refueling Outage, Unit 2- was returned- tol service on June 3, 1989 and operated throughout the year. During the year, the radioactive releases were below the limits of 10 CFR Part- 50, Appendix I. 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 1989-was the same as in 1988 except for several changes in- dairy locationsL which were . revised as required by the Beaver Valley Technical Specifications. (Refer to Table V. A.1 for the 1989 Radiological Monitoring Program Outline). The Beaver Valley Power Station Technical Specifications require-sampling of three (3) dairies which have- the highest calculated milk pathway potential and one large local dairy. The three-dairies are determined from calculations based on - the - metcorological -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 ' I- revisions due to updated calculations and surveys normally- result in sampling of several additional dairies during the year in. i
- different sampling periods.
The Environmental Monitoring Program also includes two larger dairies in order to provide continuity in the sampling / analyses ,I - 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 milk monitoring program of this report (Section V-E). + l r 4 F
SECTION 83 DUQUESNE LfGHT COMPANY I 1969 Annual. Radiological = Environmental Report II. RESULTS AND CONCLUSIONS (continued) Activity ~ detected was attributable ,to naturally occurring-- re.dionuclides, BVPS of fluents, previous.' nuclear weapons tests or to the normal statistical fluctuation- for; activities near the lower limit of detection (LLD). The positive =results attributable-to the Beaver Valley Power Station were consistent.with station data of authorized radioactive discharges and were within limits permitted by the NRC-license. i The - ~ results- and conclusions for each media of the 1989 Radiological Environmental Monitoring Program are contained in
, Section V of this~ report. - A' summary of the:1989 operational- E
-environmental data is found. in Table V.A.2' and a summary of 5 ,
preoperational data -(1974-1975)- environmental data is found in { Table V.A.3. l Examination of effluents from the Beaver Valley Power Station and ~ environmental media demonstrated compliance with regulations and Station Technical Specifications. In q . s. 1 I I
~1- 1
~ SECTION III DUQUESNE LIGHT COMPANY-1989 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS A. -Environmental Quality Control Programs. 1 } The Quality Control (QC) Program used for the Beaver Valley ! Environmental Radioactivity Monitoring Program consisted of l I seven (7) elements. It should be noted that the comparisons made were at very low levels of. radioactivity and _l consequently, the activities at these levels are difficult to i I measure. However, acceptable correlation was achieved 'in most instances as outlined in the discussions and tables which follow. y
- 1. TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and QC Laboratory) ;
Thirteen (13) TLDs from the Contractor Laboratory and QC .;' Laboratory are co-located, replaced quarterly and results compared. The average of the. contractor i l laboratory and the average of the quality control laboratory agree within i 5 . 3*. of the mean of all i results. This is well within the precision of typical .! TLD Systems. Summary data of the TLD Monitoring Progrtan 1 is provided in Table III.1.
- 2. Split Sample Program (DLC Contractor Laboratory - DLC QC l*
Laboratory) Samples of surf ace (river) water ar.d drinking water were ; routinely split and analyzed by the DLC Contractor ' I Laboratory and the DLC .QC Laboratory. In addition,- ; samples of other media, such as milk, soil, sediment and , feedcrop were also split with the DLC QC Laboratory. ; A summary of results of split water samples is provided in Table III.2. Five (5) of eight (8) split drinking and surface water samples analyzed for Gr-B were not in cgreement. The disagreement in the Gr-B split water samples- is attributed to differences in the analytical ; procedures used by the two laboratories. This issue has
>I been identified to the laboratories and will be resolved -i in 1990. The two (2) spiked Gr-B water samples and EPA !
Interlaboratory Cross Check Program Gr-B'results are in I agreement. See Appendix I and II; A summary of milk, sediment and feed / food crop split samples is provided in Table III.3. Some variation is expected due to small variations in duplicate samples, variations .in I analytical procedures, and in calibration, source type,. l etc. I 1
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~5ection 111 DUQUESNE LIGHT COMPANY IABLE'311.1 -
1989 Annual Radiological Environmental Report l TABLE !!!.1 ' QUALITY CONTROL RESULTS TLO MONITORING' mR/ Day . IST QUARTER , 2ND QUARTER OLC DLC ! DLC. -QC . OLC OC t Location Contractor Lab Location Contractor Lab " No. (CaSO,Dv) (CaSO ,:Dy L No. (CaSO ,:Dy) (CaSO,.Dy) 10 0.14 0.17 10 0.16 - 0.18 , 0.16 '13 0.15 0.16
- 13. 0.11 14 0.14 0.15 14 0.14- 0.17.
-15 0.11 0.12 15 0.12 0.13- O 27 0.13 0.16 27 0.15 0.17 g' 28 0.14 0.16 28 0.16- 0.18 gi '
298 0.17 0.22 2 91 0.19 0.22 32 0.15 0.18 32 0.16 0.21 45 0.14 0.17 45 0.16 0.21 i 46 0.12 0.14 46 0.14 0.14 47 0.15 0.18 47 0.17 0.22 48 0.15 0.18 48 ' O.16 0.21 51 0.15 0.16 51 0.16 0.19 3RD QUARTER 4TH.. QUARTER ANNUAL DLC DLC DLC DLC- QC DLC QC - QC , Location Contractor Lab Location Contractor Lab Location Contractor -Lab I No. (CaS02:Dv) (CaSO4:Dy) No. (Ca504:0y) (CaSO4:Dy) No. (CaSO,:Dy) (CaSO,:Dy) 10 o,17 10 0.20 0.18 10 0.16 0.18' 0.18 13 0.'15 o,17 13 0.17 0.16 13 0.15 0.16 14 0.16 'o,17 *14 0.16 0.17 14 0.15 0.16' 15 0.12 15 0.14 0.14 15 0.13 0.14 l 0.14 27 0.16 o,17 27 0.17 0.18 ??. 0.15 037' ! 28 0.18 28 0.19 -0.18 28- 0.17 0.18 0.18 298 0.20 298 0.21 0.21 298 0.20 0.21 0.22 32 0.17 32 0.20 0.20 32 0.18 0.19-0.18 45 0.19 45 0.16 0.20 45 0.17 0.17 0.20 46 '0.14 46 0.15 0.13 46 0.15 0.15 0.15 , 47 0.18 o,19 47 0.20 0.22 47 0.17 0.19 48 0.17 48 0.16 0.18 48 0.16 0.19 0.18 0.18 0.17 0.19 51 0.16 0.18 51 0.18 51
s-Section !!! DUQUCSNE LIGHT COMPANY TABLE !!!.2 1989 Annual . Radiological Environmental Report (Pa9e 1 of 2)- TABLE 111.2 [- QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS
- Comparison of Contractor and DLC-0C Labs DLC Contractor OLC - QC
- Media Analysis Samplino Pariod Lab (1) -Lab (1) Units-Surface Weter Gross Alpha January < 2.0 1.2 + 0.5 pCi/1 April i1.1 0.8 1 0.5 pCi/1 July < 1.5- < 0.3- pC1/1 October < 1.6 < 0.4 pC1/1 Surface Water Gross Beta January 9.4 + 1.6 3.6 + 0.4*
pC1/1 April 12 + 0.2 5.3 + 0.5* pCi/1 July 8 + 1.7 2.9 2 0.4* pCi /1. October 12 + 0.2 4.9 + 0.4* PC1/1 l Surface Water Co-60 January < 4.0 < 2.6 pC1/1 April < 4.0 $ 1.5 pC1/1 July < 3.0 < 2.1 pCi/1 { October . < 3.0 < l.6 pC1/1 i Surface Water Cs-134 January < 4.0- < 2.3- pCi/1 April < 4.0 < 1.4 pC1/1 July < 3.0 < 4.3 pCi/1 October < 3.0- < 2.1 pCi/l Surface Water Cs-137 January < 5.0 < 2.6 pC1/1 April < 4.0 < 1.5 pCi/1 July < 3.0 ' < 2.4 pC1/1 October < 3.0 < 2.2 pCi/l' Surface Water Tritium ist Quarter j Composite 5,000 3 200 5,803 + 177 pCi/1 'j 3rd Quarter Corr.posite 8.600 + 100 .pCi/1 8.741 1 211 Surface Water Sr-89 2nd Quarter i Composite < 1.8 < 0.5 pCi/1
^
4th Quarter Composite < 1.2 < 0.4 pCi/1' Surface Water Sr 90 2nd Quarter ' Composite 3.2 + 0.9 < 0.4* PCi/1 4th Quarter Composite < 0.24_ < 0.3 pCi/1 Surface Water Co-50 2nd Quarter (high Cornposite < 0.8 < 1.8 pCi/1 sensitivity analysis) 4th Quarter Composite <1 < 1.7 pCi/1 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
- See Section !!! B l
l i i .. .
.Section'!!!' DUQUESNE LIGHT COMPANY TABLE !!!.2' 1989 Annual Radiological Environmental R1 port (Page 2 of 2). j l
l TABLE I!!.2 (Continued)'-
-QUALITY CONTROL RESULTS l SPLIT SAMPLE ANALY$15 RESULTS , .l Comparison of Contractor and DLC-0C Labs I
DLC { Contractor DLC - OC ! Media Analysis $4mp11no Period Lab (1) ' Lab (1) Units , q pC1/1 I Drinking Water Cs 137 February .< 6.0'
< 1. 6 -
(weekly split)- May-
~
< 5.0
~
< l .0 pC1/1
.l3 '
August 1 6.0 'j 2.7 pCi/1 November 1 4.0 < 0.8 pCi/1 , Drinking Water Cs-134 February < 6.0 < l.9 pCi/1
-(weekly split)
May < 5.0 ' < 0.9 . pC1/1 August i 6.0 ' < 2.3 pCi/1 , November 1 5.0 < 1.0 pCi/1 Drinking Water Co-60 February < 7.0
~ ~< l.8 pC1/1 (weekly split) -
May <; 5.0 < 0.9 pCi/1 s August < 5.0
< 2.6 pC1/l' November < 4.0
< 1.0 pCi/1 Drinking Water Gross Alpha March < 1,2-
~ ~< 0.5 pCi/1 (monthly composite)
June < 2.0 < 0.3 pCi/l August < 1.5 < 0.5 pCi/1 November < _ 2.0 < 0.4 pCi/l l Drinking Water Gross Beta March 3.9 + 1.1 2.45 + 0.62 pCi/l (monthly composite) June- 4.0 pCd!1 16 1 3.98 2 0.49 August 7.61 1 5 pCi/l 3.64 3 1.09 l November 6.2 + 1.4 2.17 2 0.53* PCi/l l Drink'ing Water Tritium 2nd Quarter < 100 < 141 pCi/1 l 4th Quarter < 100 -< 81' pCi/1' S (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval, e
- See Section III B qg
Section !!! . OUQUESNE LIGHT COMPANY TABLE III.3 1989 Annual Radiological Envircnmental Report (Page 1 of 2)~ TABLE 111.3 ! OUALITY CONTROL RESULTS 'I SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor'and DLC-0C Labs ' OLC Contractor OLC - QC I Milk Media Analysis Sr 89 Samplino Period Lab (1) Lab (1) Units 3 21-89 16 1 < 0.3 pC1/1 (Location 25) I Sr 90 1 131 K 40 3-21 89 3-21 89 1.3 19 0 1 28 0 3.0 1 0.6
< 0.2 -
pCi/1 pCi/1 3 21-89 1450 + 140 1390 + 107 pC1/1 Co 60 32189 I Cs 134 3 21-89 14
<4
< 2.3
< 2.1 pC1/1 pCi/1-j Cs 137 3-21-89 <4 < 2.7 pti/l Milk 1-131 6-13-89 < 0.22
-(Location 25) < 0.2
~
pCi/1 K 40 6-13 89 1440I140 1288 + 91 pCi/1 Co-60 6-13 89 <S < 2.0 pC1/1 Cs 134 6-13-89 <4 < 2.2 pCi/l Cs-137 6 13 89 <4 < 2.4 pC1/1 - Feed 1-131 6-14 89 < 0.011 I (Location 25) Be 7 6 14 89 1.87[0.42
< 0.010 0.40[0.13 pCi/gm (dry) pC1/gm (dry)
K 40 6-14 89 2.58 1 0.26 4.63,0.4 pct /gm (dry) -lB Co 60 6-14-89 15 1 0.006 pC1/gm (dry) Cs-134 6-14 89 <5 1 0.006 pCi/gm fdry) Cs-137 6-14 89 ~ <5
< 0.008 pCi/gm (dry)
Feed Sr 90 6-14 89 0.054 + 0.01 < 0.036 pC1/gm (wet) i (Location 25) ~ '" l Food- I-131 9 28-89 < 0.092 < 0.014 pCi/gm (wet) (Location 25) K-40 9 28 89 I 1.9k0.19 1.92 1 0.26 pC1/gm (wet) Co-60 9-28-89 < 0.01 < 0.006 pCi/gm (wet) Cs 134 9 28-89 < 0.008 1 0.006 pC1/gm (wet) Cs-137 9-28 89: < 0.01 3 0.007 pCi/gm (wet) I . I m enoe,ta,nt,es .,e ,a,ed on _in, stat,s,1., and a,e s,eo,,,ed a, t,e ,,, _,idence ,n,e,,a, . I I
TABLE Ill.3' Section !!!_ OUQUESNE LIGHT-COMPANY (Page 3 of 8)
~ 1989 Annual Radiological Environmental Report
~
TABLE !!!.3 (Continued) l' QUALITY CONTROL RESULTS i SPLIT SAMPLE ANALYSIS RESULTS L
- 1: Comoarison of Contractor and OLC-0C Labs L
OLC Contractor OLC - QC . Analysis Samolina period Lab (1) Lab (1) Units Media , l
- Milk 1-131 9 19 89 ' < 0.17 < 0.1- pCi/1 (Location 25) Sr 89 9 19 89 < 1.1 < 0.2 pC1/1
$r 90 9-19 89 2.7 1 0.7 1.2 1 0.4 pti/1 _
Cs 134 9 19 89 <4 < 2.9 pCi/1 Cs-137 9-19-89. $ 4' < 3.6 pct /1' Co 60 9-19 89 <5 < 3.6 pC1/1-K 9 19 89 1400 + 140 1440 1 150 pCi/1
- Sediment Gross Alpha 10 8-89 25 + 7 12.6 + 5.5 pCi/gm (dr
=(Location 2A) -26.7 5.5 Gross Beta 10-8-89 44[3 pC1/gm-(dr Sr 89 10-8-89 < 0.2 - < 0.01 ' _p Ct/gm (dr Sr-90 10-8-89 1 0.05 0.033 + 0.009 pCi/gm (dr Co-58 10 8-89 0.49 1 0.07 0.53 + 0.04- pC1/gm (dr Co-60 10-8 89 0.67 + 0.07 0.72 + 0.04 pC1/gm (d Cs 134 10 8 89 < 0.05 < 0.01 pCi/gm (d ;
Cs 137 10-8 89 0.25 + 0.05 0.29 + 0.03 pCilgm (dr K-40 10-8-89 14.1 34 1 13.5 + 0.4 pC1/gm (dr Ra-226 10 8-89 1.9) + 0.51' 3.7 + 0.5' pC1/gm (d Th-228 10-8-89 1.34 + 0.13 0.60 + 0.03* pCi/gm (dry) Hl1L (Location 25) I-131 K-40 12-12-89 12 12-89
< 0.21 '< 0.1 pCi/1 pCi/1 g
m 1450 + 140 1304 + 134 L Co 50 12-12 89 <5 < l.9 pCi/1 Cs-134 12-12-89 <4 < 1.6 pCi/1 Cs 137 12-12 89 <5 < 2.3 pli/1 l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval. I
- See Section !!! B IH
-n-y
SECTION III DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING PROGRAMS A. Environmental Quality Control Programs (continued)
- 3. DLC QC Laboratory Program i
Spiked samples prepared by DLC QC Laboratory were
. routinely submitted to the Contractor Laboratory for. i analysis. Tables III 4 (water) and III.5 (milk) provide l data from this portion of the aQC Program.
- 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 III.6 provides data for this portion of th . QC program.
- 5. Contractor and QC Laboratory - Internal QC Program Tne Contractor and QC Laboratory maintained their own QC Program which' included participation in the Cnvironmental Protection Agency -
Environmental Monitoring Setety Laboratory- (EPA - EMSL) Interlaboratory Cross Check Program. This cross check' - program indicated that the Contractor and QC Laboratory results were in agreement with EPA EMSL. See Appendix I and 11. DLC also audited the Contractor- and QC Laboratory and determined that internal QC practices were in effect and that procedursa and laboratory analytical techniques conformed to approved DLC procedures. l i e
t SECTION ffI- DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS A. Environmental Quality Control Programs (continued)
- 6. Special QC Pr,ogram -(DLC Contractor Laboratory -
Independent Laboratory - DLC QC Laboratory)
' Milk and water samples were prepared by an Independent Laboratory. This included low level spiking of The ' prepared samples were split specified nuclides. .
three ways and analyzed by _the DLC-QC Laboratory and l Independent Laboratory- as well as the Contractor Laboratory. _A summary of results of this portion of the ! QC program is-provided in Table III.7. j 1 L 1 l l l 1 ll Il-
Section !!! . DUQUESNE' LIGHT COMPANY. TABLE !!!.4 1989 Annual Radiological Environmental Report TABLE !!!.4 OVALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS RESULTS Sample Type DLC
. and Contractor DLC - QC Sample Date Ident. No. Analysis Lab (1) Lab (1) Units
!~ 3 13-89' W 46' Water: Sr 89 14 2 3 15.2 1 3.8 pC1/1 Sr-90 18 1 1 16.4 271 pCi/1 4 12-89 W 47 Water: Cs-134 22.3 + 4.6 24.2 + 1.1 pCi /.1 Cs 137 23.7 + 3.6 23.6 + 1.2 pCi/1 Co 60 24.0 2 4.6 23.5 + 2.0 pCi /1 l 4 12-89 'W-48 Water: 1 131 < 3.7 37.2 + 3.7
- pti/1 4 12-89 W 49 Water: H3 2900 + 100 3011 1 59 pC1/1 l
I 6 15-99 'W 50 Water: Gross Alpha 10 + 1 13.0 + 1.8 pC1/1 Gross Beta 20 + 1 c6.0 + 1.2- pCi/1 l-L 9 25-89 W-51 Water; l-131 7.2 14-0 9.6 + 0.3 pC1/1 a 9-25 89 Water: 1-131 .pCi/1 W-52 14 3 1 19.0 220 9-20-89 W Water: Sr-89 22 +'2 29,1 + 1.8 pC1/1 Sr 90 23 + 2 26.5 + 9.3 pC1/1 L 10-30-89 W-54 Water: 1-131 28 22 33.3 + 1.3 pC1/1~ 10-30-89 W 55 Water: Co-60 -15.3 + 1.9 15.2 + 0.9 pCi/1 L Cs-134 14.6 + 2.2- 22.1 + 4.4 pCi/1' Cs-137 21.9 + 2.2 27.2 + 1.2 pCi/1 m-L 10 30-89 W-56 Water: H-3 3400 + 100 pCi/1
'3334 2 22 12 30-89 W-59 Water: Gross Alpha 11 + 1 10.8 + 1.1 pCi/1 E Gross Beta 13 + 1 11.6 + 0.5 pC1/1 b
r (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
- See Section !!! 8 I
c . s L F L r I
-TABLE !!!.5 E Section'll! 000VESNE LIGtT COMPANY.
1989- Annual Radiolo91 cal Environmental Report g-2 TABLE 111.5-QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS. Sample Type OLC-and. . Contractor OLC - QC c Lab (1) Units 3 Sample Date' ident. No. Analysis Lab (1) 1 1-1-89 M1'*20 Milk: Sr-89 15 2 2 25.5 1 10.3 pC1/1 - Sr 90 21 2 2 28.3 12 3 pti/1. 1-131 480 + 20 540 + 13 pCi/1 ' K 40 1360 + 140 1293 + 55. pCi/1 l Cs-134 24.5 + 5.1 '24.5 + 2.6 pCi/1 Cs 137 21.7 + 4.2 24.0 2 0.6 pCi/1 , 4-12-89 M1 21 Milk: 1 131 37 + 2. 36.3 + 1.1 pC1/1 K-40 1370 + 140 1332 + 89 pC1/1 Cs-134 - 15.8 3 6.7 20.8 + 2.8. pCi/1 Cs-137 26.2 + 5.0 22.2_+ 2.4 pC1/1 7-31 89 M1 22 . Milk: Sr 89 15 + 4 19.4 1 6.5 pCi/1 Sr-90 20 + 2 27.6 + 3.5 pCi/1 1-131 42 + 1 46.8 + 3.2 pCi /1-K-40 1400 2 140 1294 3 33 pCi/1 Cs-134 '27.0 + 5.7 27.4 28 1 pC1/1 Cs-137 22.6 + 4.3 24.1 + 1.8 pCi/1
- j. 10-30-89 Mi 23 Milk: 1-131 57 22 70.0 33.3- pCi/1-l K 40 1250 1 130 1341 2 45 pCi/1-Cs-134 19.9 + 3.1 22.1 + 2.6 pct /1 Cs-137 24.8 + 4.4 29.4 + 1.5 pCi/1 (1) Uncertainties are based on counting statistics and are sp cified at the 95% confidencr. interval. -
t I l I
~ TABLE 111.6- "' Section III DUQUESNE.LIGH7 COMPANY (Page 1 of 4) 1989 Annual Radiological Environmental Report f L TABLE 111.6 r 00ALITY CONTROL RESULTS L . AIR PARTICULATES AND CHARC0AL FILTER: COMPARABLE SAMPLES _ Air Particulates Air lodine pCi/Cu. Meter (Beta) pCi/Cu. Meter [. OLC -; DLC Contractor DLC - QC Contractor OLC - QC i Lab (1) Sample Date Lab (1) Lab (1) Sample Date Lab (1)
;12 26-89 to 0.036 + 0.004 0.037 ~+ 0.004 1 2-89 to < 0.02
- ~
< 0.01-1 2 89 1-9-89 ;
i 1 9 54 to- 0.024 + 0.003 0.026 + 0.004 1-16-89 to -< 0.02 ~
< 0.01 ;
- ~
l 16-89 1-23 89 l f' l-23 89 to 0.034 + 0.004- 1-30-89 to < 0.01 0.040 +- 0.004 - -< 0.01 - 1-30-89 2 6-89 , { 1 '2-6 89 to 0.026 + 0.004 0.032 + 0.003 2-13-89 to -< 0.01' -
< 0.01 2-13 89 2-21-89 2 21-89 to 0.026 -+ 0.004- 0.026 + 0.004 2 27-89 to ""< 0.01 < 0.01 i 1 2027-89 3-7-89 3-7-89 to 0.025 + 0.004 0.033 + 0.005
~
3-13-89 to -< 0.02 -
< 0.01 ;
3 13-89 3-20 89 1 3-20-89 to 0.021 +- 0.003 0.028 + 0.004 3-27-89 to < 0.01 ~
< 0.01 3-27-89 4 3 89 4 3-89 to 0.016 + 0.003 0.021 '~+ 0.004- 4-10-89 to ~
< 0.01 '~
< 0.01 ;
4-10-89 4 17-89 ! 4 17 89 to 0.023 + 0.004 0.021 -+ 0.004 4 24 89 to ~< 0.01 -< 0.01
;l 4-24-89 5 1-89 5-1-89 to 0.018 + ~
0.003 0.017 + 0.004
~
5-8 89 to < 0.01
~ '~
< 0.01 5-8-89 5-15-89 5 15-89 to '0.017 + ~
0.003 0.021 + 0.003 5 22 89 to -< 0.01 < 0.01
-l 5 22-89 5-30-89 5 30 89 to 0.023 + -
0.004 0.021 -+ ~0.003 6-5-89 to ~
< 0.01 .< 0.01
~
6-5-89 6-12-89 6-12-89 to 0.014 + 0.003 0.013 ~+ 0.004 6 19-89 to -< 0.01 < 0.01 '
! 6 19-89 6-26-89
~
(1) uncertainties are based on counting statistics and are specified at the 95% confidence interval. t Section !!! OUQUESNE LIGHT COMPANY TABLE-!!!.6
- 1989 Annual Radiological-Environmental Report (Page 2 of 4)'
l' (' TABLE 111.6 (Continued) 1 OVALITY CONTROL RESULTS ,
-AIR PARTICULATES AND CHARCOAL FILTER: COMPARABLE SAMPLES Air Particulatet Air lodine !
pCi/Cu. Meter (Beta) pCi/Cu. Meter { l
- l. -
OLC ~ DLC' Contractor DLC - OC Contractor OLC - QC Lab (1) Lab-(1) Sample Date Lab (1) Lab (1)-
}33 e1 Date 6 26-89 to 0.022 + 0.003 0.016 ~+ 0.003 7389 to -< 0.02' "
< 0.01 7 3 89 7 10-89 7-10-89 to 0.017 ~+ 0.003 ' 0.018 + 0.003
~
7-17-89 to '~
< 0.02 < 0.01 -
7-17 89 7-24-89 7 24 89 to 0.023 -+ 0.003 0.018 -+ 0.003 7-31 89 to- ~
< 0.02 ~< 0.01 7-31-89 8 7 .
8-7 89- to- 0.016 +~ 0.004 0.018 ~+ 0.003 8 14-89 to <
~ 0.01 ~~< 0.01 s 8 14 89 8 21-89 i
8-21-89 to 0.025 +~ 0.003~ 0.022 ~+ 0.003 8 28 89 to < 0.01
~'
< 0.01 a.28 89- 9-5 89 9 5-89 to 0.020 +~
0.004 0.021 ~+ 0.004 9-11-89 to -
< 0.01 ~
< 0.01 9-11-89 9 18 89 9 18 89 to 0.008 +-
0.003 0.010 + 0.003 9 25-89 to < 0.01 < 0.01 I 9 25-89 10 2-89; 10-2 89 to - 0.018 + 0.003 0.023 -+ 0.004 10 9 89 to ~< 0.01 < 0.01 10-9-89 10 16-89~ t 10-16-89 to 0.010 ~+ 0.003 0.011 +~ 0.002 10 23-89 to < 0.01 ~
< 0.01 '10-23 89 10 30 -
10-30 89 to 0.022 + 0.003 0.020 + ~ 0.003 11-6-89 to - ~
< 0.01 ~
< 0.01 l 11-6 89 11-13 89-11-13-89 to 0.023 + 0.003 0.025 + 0.003.
~
11 20 89 to < 0.01
< 0.02
~
11 20 89 11-27-89 1127-89 to 0.026 + 0.003 0.023 ~+ 0.003 12-4-89 to ~
< 0.01 ~
< 0.01' 12 4-89 12 11-89' 12-11 89 to 0.030 + ~
0.004 0.038 + 0.004 12-18 89 to ~
< 0.01 ~< 0.01 12-18 89 12-26-89 l
l I I (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
.~e w ,- p
Section !!! DUQUESNE LIGHT COMPANY TABLE !!!.6 1989 A.: ual Radiological Environmental Report (Page 3 of 4) l TABLE !!I.6 QUALITY CONTR0'. AIR PARTICULATES (D'i/m3 ) . DLC Contractor DLC - OC
$ ample Date Nuclide Lab (1) Lab (1) ;
January Be-7 0.112 2 0 011 0.135 + 0.019 Others LLD LLD i l March Be 7 0.111 2 0.011 0.122 + 0.025 K 40 0.022 + 0.009 LLD Others LLD LLD i May Be 7 0.093 + 0.012 0.100 + 0.02? Others LLD LLD July Be 7 0.104 1 0.016 0.086 ; 0.023 l Others LLD LLD -{ September Be 7 0.81 + 0.015 0.087 + 0.024 Others LLD' LLD 1 November Be-7 0.093 + 0.017 0.060 + 0.017 Others LLD LLD I l l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval. - LLD Lower Limit of Detection t
TABLE !!!.6 5ection !!! DUQUE$ht Ll&H7 COMPANY (Page 4 of 4) 1989 Annual Radiological Environmental Report i TABLE 111.6 QUALITY CONTROL C g AIR PARTICULATE LOCATION 33 AND - (DC1/m CHARC0AL FILTER 3)OMP/AABLE' g OLC Contractor DLC 00 ) Sample Date Nyc11de Lab (1) Lab (1)
$r 89 1 0 0003 Ist Quarter Composite 1 0.0009
$r 90 < 0.0002 < 0.0002 i 2nd Quarter Composite Sr 89 1 0.0013 1 0.0002
$r 90 < 0.0002 < 0.0001 3rd Quarter Composite Sr 89 1 0.0018 1 0.0002 Ei 5
$r 90 1 0.0004 1 0.0002 ,
1 4th Quarter Compositu $r 89 1 0 0002 1 0.000$ .
$r-90 0 0001 1 0 0002 1 ,
I; I (1) Uncertainties are based on counting statistics and are specified at the 951 confidence interval. I I'
- e. - 9 cm w - w. .-
9 .,,,y .% .,. , - .,y..,
h I TABLE !!!.7 I Section !!! DUQUE$NE LIGHT COMPANY 1989 Ainual Radiological Environmental Report (Pa9e 1 of 2) h
- TABLE !!!.7 '
OVALI1'r CONTROL DATA' f> OC Sample Comparisons (All Analyses in DC1/11 Sample type DLC. and Independent Contractor DLC . OC Samole Date 16ent. he. Analyses Lab (1) Liab (1) Lab (1) { 2 6 89 $3 295 Water: Sr 89 18;,4 20 + 4
, 18.9 1 1 4 Sr 90 14.2f,0.6 25 1 2- 20.0f,1.1 1 131 7.81 0 .B ' 8.2 1 3 8.8 + 0.4 Cs 134' 191 8 19.2'+ 6.3 20.5 + 2.7-Cs 137 24 f, 7- 29.1 11 4 33.4 1 1 2-
'2 6 89 53 296 Water H3 943 1 130- 8701 80 ^ V61 1 .86 5*8 89 53 297 Water: Sr 89 11.6 + 1.3- 9.0 + 1.1 7.4 + 1.9 Sr 90 12.0 + 0.5 14 4 1 9.9 + ).6 1 131 .19.4 + 0.4 16 + 1 17.8 + 0.6 Cs 137 14 13 ' 14.5 f, 4.8 20.6 1 1.6 Co 60. 11 13 18.2 17 5 17.2 1 .1.6 5 8 89 53 298 Water: H 3- 1180 + 140 1400 + 100 .1646 + 195 8 28 89 53 299 Water ~ Sr 89 16 + 2 24 + 2 18.4 + 4 Sr 90 19.1 1 0.5 24 1 2 19.7 17 1 1 131 3.05,1 0.12 3.4 1 0.3 3.5 1 0.2 Mn 54' 281'? 41.8 1 4.9 , 46.7 1 3.7 Cs-137 2316 33.9 1 4.6 30.8.1 1 1 8 28 89 53-300 Water: H3 2100 1 1000- -1800 + 200 1035 1 30
.s
-(1) Uncertainties are based on counting statistics and are specified at the 95% confidence level.
l- .. L
Section !!! DUQUE5NI 6!SH7 COMPANY TABLE !!! 7 I 1989 Annual Radiolo91 cal Environmental Report (Pa9e 2 of 2) TABLE !!!.7 I,. ! QUALITY CONTROL DATA , ; OC Sample Comparisons !
!All Antivses in 0C1/11 Sample Type OLC I and Independent Contractor DLC - QC = .
56 ele Date Ident. ND. Analyses Lab (1) Lab (1) f _ lab (1) , 2 6 89 52 250 Milk: Sr 89 13 2 6 2312 5.9. 3 1.0
$r 90 18 + 2 28 + 2 17.7 + 1.7 1 131 9.2 + 0.6 9.1 + 0.3 8.7 + 0.5 Cs 134 16 7 18.3 4.0 19.7 4.8 ;
Cs 137 26 3 7 30.6 26 4 32.6 ; 2.2 K 40 4 1300 1 200 1540 f 150 1224 28 , 5 0 89 52 251 Milk: Sr 89 22 2 3 8.6 1 2.3 16.9 3 3.0 l Sr 90 25.2 + 1.1 11 + 1* 22.5 + 5.1 , 1 131 17 + 6 17 + 1 ** ! Cs 134 20 + 4 15.2 + 3.8 17.0 + 3.6 Cs 137 20 + 4 25.7 + 4.1 27.5 + 1.9 K 40 1420 3 90 1440 1 140 1052 2 43 1 8 28 89 52 252 Milk Sr 89 8.8 7 23 23 1 9.7 26 1 Sr 90 10.9 20 1 12 1 1 11.3 ; 0.2 1 131 2.03 1 0.08 2.8 1 0.3 2.7 3 0.2 Cs 134 8 f, 6 11.8 + 2.3 ' 8.2 1 0.9 Cs 137 lb+6 21.9 + 4.1 18.8 + 2.6 , K 40 1000 + 200 1480 + 150 1209 + 58
- See Section 111 8
" !*131 not analyzed due to spoilage of container.
(1) Uncertainties are based on counting statistics and are specified at the 95% confidence level. "" h h SECT 20N III DUQUESNE LfGHT COMPANY 1989 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING PROGRAM ~ , A. Environmental Quality Control Programs (continued) [ 7. Pennsylvania Departrnent 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, I drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program. Comparison of results also indicated agreement between I the PDER Laboratory and the Duquesne Light Jompany Contractor Laboratory. B. Evaluation of the Quality Control (QC) Program Data . The split and spiked sample program indicates that the Contractor and QC Laboratory are generally performing I satisfactorily in accordance with "CriteriaforComp'aring Analytical Measurements from NRC Compliance Office. In addition, an independent laboratory is used to supplement the I regular program. Comparisons between the independent, QC and Contractor laboratories are acceptable at.J demonstrate a satisfactory performance by the DLC contractor. All media were found to be in agreement in accordance with NRC criteria I with the exception of those media in Tables III.2 - III.7 identified with an asterisk (*). Based on all available QC data and the data from the Contractor and QC Laboratory's internal EPA Interlaboratory Cross Check Program, the Environmental Monitoring Program for I 1989 is acceptable with respect to both accuracy and measurement. C. Standard Requirements and Limitations for Radiological and Other Effluents The Beaver Valley Power Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases are controlled to ensure that limits set by Federal or State governments are not
) exceeded. In addition, self-imposed limits have been established to further limit discharges to the environment. ;
[ 9 SECT 20N 111 DUQtJESNE LIGHT COMPANY ! 1989 Annual Radiological Environmental Report 111. ENVIRONMENTAL MONITORING PROGRAM i C. Standard Requirements __and Limitations for_ Radiological and Other Ef fluents (continLW) Beaver Valley Power Statton is subject to regulations which ' include the Code of Pedee 1 Regulations 10 CPR (Energy), Pennsylvania Department n Environmental Resources (PDER) Industrial Waste Permit #04/ til, Gaseous Discharge Permit '
#04 306-001, PA Code - Tit.t 24, Part 1, Ohio River Valley Water Sanitation Commission (0,1ANCO) Standards No. 1-70 and 2 70, Environmentul ProtectJon Agency (EPA), National Pollution Discharge Elimination (NPDES) Permit #0025615, and the Beaver Valley Power Station Technical Specifications.
r D. Deporting Levels i 4 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 averaged over any calendar quarter. Also, when more than one of the radionuclides are detiected in the sampling medium, this report shall be submitted ift Concentration (1) 4 Concentration (2) , . . 2: 1.0 Limit Level (1) Limit Level (2) i There were no analytical results of environmental samples a during 1989 which exceeded Beaver Valley Power Station g reporting levels.
5 I 4 4 I- SECTION IV DUQUESNE LIGHT COMPANY ; 1989 Annual Radiological Environmental Report ; IV. MONITORING EFTLUENTS l A. Monitoring of Liquid Effluents i Description of Liquid Effluents at the Beaver Valley Power
~
Station. ' 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, nall amounts of well water and liquid effluents are discharge. to the Ohio River using discharge points shown in Tigu.e 4.1. Figures 4.2, 4.3, 4.4 and 4.5 are schematic diagrams of liquid flow paths for the Beaver Valley Power Station. The following two (2) tables sum.narize radioactive liquid effluents at the Beaver Valley Power . Station: Table IV.A.1 - Effluent Treatment, Sampling, and Analytical 3 Procedures - Beaver Valley ; Table IV.A.2 - Results of Liquid Effluent Discharges to the l Environment Beaver Valley 1 l 1 I I . I !
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-*- m 8j 4 COLLECTim O_ y FROM 9YPS-1 CEMtMERAti2tn s WAfta tad tIEL Res54 7 20 om y FftTERED W TER F#0pt 87P5-1 FROM EfPS-1 1dAffR SfFTfifR %
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SECTION IV ilGURE 4.4 ' DUQUESNC LIGNT C0r1PANY 1989 Anaval Radiological Environtnental deport } - a
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SICTION IV s'lGy;tg 4, $ g DUQUESNE LIGHT CDP. PAN? g 1989 Annual .ladiological Environmentel Roport i2 ricuRE 4.5 I NEgoo
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SECTION IV DUQtESNE LIGHT COMPANY s 1969 Annual Radiological Environmental Report I TABLE IV. A.1
,1. Effluent Treatmunt. Sampling and Analytical Procedures Beaver Valley l Treatment, Sampling Standard and/or Effluent Type andf,gtMonitoring Analytical Procedures (a) Steam System Recycled or directed to If discharged, procedures Blowdown Radwaste System for adhere to Tt hnical discharge. Specifications.
1 (b) Radioactive Effluents shall not exceed Procedures adhere to Vaste values specified in the requirements of Technical Specifications. Technical Specifications. All discharges are performed in accordance with the Offsite Dose Calculation Manual (ODCM). l TABLE IV. A.2 8 Results of Liquid Effluent Discharges to the Environment Beaver Valley Effluent Type Results for 1989 (a) Steam System The Steam System Blowdown was recycled. Blowdown (b) Radioactive Routine planned releases of liquid effluents !' Weste Liquids from the Beaver Valley Power Station were released in accordance with conditions noted in the Section 3/4.11.1 of the Technical Specifications for Units 1 and 2 and no limits were exceeded. These values have been reported in the Beaver Valley Power Station I Semiannual Radioactive Effluent Release Reports for 1989. S
SECTION IV DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report IV. MONITORING EFTLUENTS B. Monitoring of Airborne Ef fluents i
- 1. Description of Airborne Effluent Sources Beaver Valley Power Station (Units 1 and 2)
}'
The Beaver Valley Power Station identifies isotopes at,cerding to the Environmental Technical Specifications
~
and Regulatory Guide 1.21. Prior to waste gas decay tank batch releases and containment purge releases, an , analysis of the principal gamma emitters is performed. gi The principal gamn.a emitters include noble gases, g , fodines, 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.
l 2) The Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Unit l 2 Containment Building.
- 3) The Condensate Polishing Building Vent located .
on top of the Unit 2 Condensate Polishing l Suilding.
- 4) The Waste Gas Storage Vault Vent located on top of the Unit 2 Decontamination Building. ~
- 5) The Decontamination Building Vent located on top of the Unit 2 Decontamination Building. -
- c. Unit I and Unit 2 shared release points;
- 1) The Process Vent located on top of the Unit 1 ,
Cooling Tower. -
- I
~ SECTION IV DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report 7 IV. MONITORING ETTLUENTS B. Monitoring of Airborne Effluents (continued)
- 1. Description of Airborne Effluent Sources (continued)
Beaver Valley Power Station (Units 1 and 2) (continued) These points are continuously monitored for particulates and gases. Orsb se:.eples are obtained on a weekly basis l and are analvted for noble gas gamma emitting isotopes i and tritium. Weekly continuous samples are obts.ined on filter paper and charcoal cartridges. The filter papers I ar* .nalyzed for particulate gamma emitting isotopes and gross alpha. Composites of the filter papers are
- n analyzed monthly for Sr-89 and Sr-90. The charcoal l cartridges are analyzed for 1 131, 1-133 and I 135.
Figure 4.7 shows these gaseous release points. I I I I I l 1 I l ..
_ . - . . - - .. . . _ ~ - . _ . - . - - - . - . . _ . - . - - - - - - _ - _ _ _ . i SLCTION IV UUQUESNE LIGirt C0;UWW FIGURE 4.6 3 1989 Annual Radiological EWironmental Report
,o o I
i FM Wlf 2 WIWB Nft tftfBI (8ill!W 70 Wit 1) . 10 A N N DE ,
)
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; 0 o o o o o o
- FIGURE 4.6 E
MG4tillR g~ BEAVER VALLEY POWER STATION Eg l UNITS 1 and 2 RlRP W U NQ4SIFIR )!!Alf1011 All . h - OXfGBl MLVER h ' 0110B190R AllIJICTOR h
>{BAC10R GASEOUS RADI0 ACTIVE WASTE WlA!!WIIUllf0R FIRE h (20WT PR0 CESSING SYSTEM 00llfnllflDif UAQUI PLfrS h
~ SECTION IV FIGURL 4./ DUQUESfvE LIGHT COMPANY 1989 Annual Radiological Environmental Report hio River FIGURE 4.7
- __ m__
f ~- ( J _- f L o , ,.- I l = l m
\
5 x/ r- '* x.
- t. __
j .J ' - i Unit 2
\L Unit i i 1 m @
{ D a C q ELIASE P0!t# ELEVATION *
- 1. Ventilation Vent-thit 1 79 I I
- 2. Contaiment Vent (SLCRS)-lhit 1 153
- 3. Pmcess Vent-thit 1 & 2 475
- 4. Ventilat.. ; vent - thit 2 85
- 5. Contaiment Vmt (SLCRS)-lhit 2 153
- 6. Condensate Fblishing Mlding Vent-thit 2 85 j
- 7. Waste Gas Storage Vault Vent-thit 2 80 U/ !
- 8. Decontamination Mlding Vent-thit 2 80 N '
- Elevation abwe plant grade, in feet i
FIGURE 4.7 GASEOUS RELEASE POINTS - BEAVER VALLEY POWER STATION UNIT 1 & 2 i
'l
SECTION 8V DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report IV. MONITORING EFTLUT.NTS B. Monitoring of Airborne Ef fluents (continued)
- 2. Airborne Effluent Treatment and Sampi g ;
Beaver Valley Power Station (Units 1 and 2) Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste ; charcoal delay subsystem upstream of the overhead gas l 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 radiciodines are also i present in the eight continuous ventilation system pathways. I The overhead gas compressor directs the radioactive gas stream.to a gas surge tank. Gas is periodically - discharged from the Unit 1 or Unit 2 surge tank to one of the three (3) decay tanks at Unit 1 or one of the seven (7) decay tanks at Unit 2. After the decay tanks are sampled and authorization obtained for discharge, > the flow of the waste gases from the decay tanks (2 scfm) is recorded and rapidly diluted with about 1000 scfm 'of air in order to dilute hydrogen and radioactive effluent concentration. The gases are then combined with nitrogen purge from the decay tank radiation monitor and 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 and the purge from the multi , sample pos.nt radiation monitor. The mixture is then ' filtered through one of the gaseous waste disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the Unit ) cooling tower. The radioactivity levels of the stream tre monitored continuously. 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.
~ SECTION IV LUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report IV. MONITORING ETTLUENTS B. Monitoring of Airborne Ef fluents (continued) [ 2. Airborne Effluent Treatment and Sampling (continued) Beaver Valley Power Station (continued) During a shutdown period after the Unit 1 or Unit 2 containment has been sampled and the activity levels I determined, purging may commence through the Ventilation Vent located on top of the Auxiliary Building or the Supplementary Leak Collection and Release System (SLCRS) I Vent located on top of the Reactor Containment Building or the Process Vent located on top of the Cooling Tower. Areas in the Unit 1 Auxiliary Building (subject to I radioactive contamination) are monitored for radioactivity prior to entering the common Ventilation Vent. These individual radiation monitors aid in I identifying any sources of contaminated air. The Ventilation Vent is also monitored continuously by several redundant channels of the Radiation Monitoring I System (RMS) and is sampled periodically. Upon a high activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the Supplementary Leak Collection and Release System I (SLCRS) and to the SLCRS Vent. Areas in the Unit 2 Auxiliary Building (subject to radioactive contamination) are monitored for radioactivity prior to entering the filter banks for the Supplementary Leak Collection and Release System (SLCRS) Vent. This is I system sampled periodically for determination of radioactive material and is monitored continuously by other channels of the Digital Radiation Monitoring System (DRMS). Each Unit 1 and Unit 2 filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type I HEPA filters. The roughing filters remove large particulates to prevent excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the i HEPA filters remove particulates and charcoal fines. Release points for Unit I and Unit 2 of the Beaver I Valley Power Station are shown in Figure 4.7. See Table IV.B.1 for Radioactive Gaseous Waste Sampling and Analysis Program. 1 TABLE IV.B.1 Radioactive Gaseous Waste Sampling and Analysis Program MINIMUM E-IEWER LIMIT OF 'O SAMPLING ANALYSIS TYPE OF GASEOUS RELEASE TYPE DETECTION (LLD) 8 FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pC1/ml)* '# e A. Waste Gas Storage Tank P P < Each Tank Each Tank 4 Principal Gasuna Emitters 1 x 10 Grab --
-6
- Sample H-3 1 x 10 %
B. Containment Purge P P Each Purge Each Purge Principal Gaauna Emitters 8 1x 10 E Crab Sample H-3 -6 o 1 x 10 h gb.c,e gb C. Ventilation Systens Principal Canmaa Emitters E I x 10 SM Grab 0" i
- 1. Process Vent
- 2. Containment Vents 3 -6
[$ RC
. eo e 3. Aux. Bldg. Vents "$
- 4. Cond. Polish. Continuous W I-131 1 x 10
-12 {g Bldg. Vent Charcoal 74
- 5. Decon. Bldg. Vent
- f d 3
- 6. Waste cas Vault ntinuw s rinciP al h m M ttersE e,
- y Particulate (1-131. Others) 1 x 10 ,g _
=
Sample f -11 e Gross alpha Continuous M 1 x 10 g
- Composite 3 Particulate Sample
~II Continuous Q Sr-89. Sr-90 1 x 10 i Composite g Particulate g
- Sample g Continuous Noble Cas Noble Cases 1 x 10' ~
- Monitor Cross Beta and Gamma -
~
M M M M M M M M
[- SECTION T/ DUQUESNE LIGHT COMPANY l 1989 Annual Radiological Environmental Report ( IV. MONITORING ETTLUENTS I . TABII NOTATION
- f. 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 .sonitoring is provided. When samples collected for 24 hr ars 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 sperit 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 b_y ear.h 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, En 65, Mo 99, Cs- '
134, Cs-137, Ce-141, and Ce-144 for particulate emissions. ; This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable-and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD ; for the analyses should not be reported as being present at the LLD level for that nuclide. When unusua1' circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report. '
- h. Only when release path is in use.
~40
SECTION IV DUQUESNE LIG)fT COMPANY 1989 Annual Radiological Environmental Report IV. MONITORING ETTLUENTS B. Monitoring of Airborne Effluents (continued)
- 3. Results Beaver Valley Power Station Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 3/t. 11.2 . of the Technical Specifications. Ne limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi Annual l Radioactive Effluent Release Reports for 1989. 5 I
I I I I I I
-41 I .
j SECTION IV DUQLTSNE LIGHT COMPANY 1989 Annual Radiological Environmental Report IV. MONITORING EpTLt'ENT,S C. Solid Vaste Disposal at the Beaver Valley Power Station During Beaver Valley Power Station normal operations and periodic maintenance, small quantities of solid radioactive waste materials were generated such as evaporator concentrates, 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 and super compact the vaste. At the Beaver Valley Power Station, the compactable wastes are segregated and compressed in $$- gallon drums to minimize disposal volumes. The compressed waste was shipped for disposal at a commercial radioactive material burial site licensed by the Nuclear .Reguistory Commission (NRC) or a state under agreement with the NRC. No radioactive waste material was 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 a:cordance with DOT and NRC regulations. Figure 4.8 depicts solid waste handling at the site. At Beaver Valley Power Station approximately 9,600 cubic feet of radioactive solid waste was buried offsite in 1989. The forty-three (43) shipments contained a total activity of 1,349 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. 4 I
-42 j l
SECTION IV b 4' DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report l i l i gi i gi i j l ggg y set ?n WAstr DISPOSAL DIACRAM I' !, MADIOACTIVE Sul,Ill WASTE DISPOSA L i Misc. Radioactive Solid Wastes -
% Compactor and Drumming Station 1
. E[
3, I Itadioactive Waste -- Sludge Solidify- a, m o_ _ j g. Diannaal Evanorater ine Station g r 8 Spent Radioactive Special Shipping {
- it g
Resin Casks & Containers < y g{ . I' g; I l
. . - . . . , ,--..- -... .-. .-.~-. -.-..--.,.- .-..
~ SECTION Y - A DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program
- 1. program Description The program consists of monitoring water, air, soil, river bottoms, vegetation and foodcrops, cow's milk, ambient radiation levels in areas surrounding the site.
I and aquatic life as summarized in Table V.A.1. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are included in parts V-B through V I of this report. V-B - Air Monitoring V-C - Sediments and Soils Monitoring V D - Vegetation and Tooderops VE Cow's Milk i V F - Environmental Radiation Monitoring V G - Fish V H - Surface, Drinking, Well Waters and Precipitation V I - Estimates of Radiation Dose to Man 1 i I W TA8tE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIRGIWENTAL MoulTORING PROGRAM k 2 o X DLC Sample Sample Analysis Type of Sample Points Sector Miles Senple Point Description Sample Frequency Preparation Frequency Acalysis(b) b
- 1. Air Particulate 13. 11 1.6 Meyer's Fem Continwows Samp1 fag Weekly Composite (d) Gress Dete. ICI I-131 and Radiofodine 30 4 0.6 shippingport. PA. (5.5.) with sample collec-
! 46.1 3 2.4 Industry. PA tion at least Monthly Compestte (d) Gesume -scan I weekly { 32 15 0.8 Midland. PA (5.5.) 48(a) 10 16.5 Wef rton, W (a) Omarterly Composite (d) 51 5 8.0 Alfovippe. PA (5.5.) $r-89.90 47 14 4.8 East Ltverpool. OM - 27 7 6.2 Brunton's Fam 3 28 1 8.7 Shemen's Fem 298 3 8.1 Beaver County Hospital , 5
- 2. 01 rect 30 4 0.6 Shippingport. PA (5.5.) Continuous Quarterly y Radiation 13 11 1.6 Meyer's Fem (TLD) Annually Gaume Dose y E 46 3 2.5 Indestry. PA(Church) g 8 32 15 0.8 Midiend. PA (5.5.) e, ;:
*- 48 (a) 10 16.5 Weirton. W (a) g n y 45.1 6 2.0 Raccoon Tup. PA Kennedy's Crnrs. ; ,
51 5 8.0 Aliquippa. PA (5.5.) = E 47 14 4.8 East Liverpool. ON , 5 70 1 3.0 West. Svr. School i n 80 9 8.4 Raccoon Park ; 7 81 82 9 9 3.9 7.1 Seethside School Menever Municipal Bldg. Mill Creek Rd 35% g 3 83 10 4.5
- 14 11 2.6 Mootstoun _,
' 84 11 8.5 Moncock Co. Children Mome ,, 85 12 5.8 Rts. 8 8 30 Intersection 7, 86 13 6.5 E. Efwerpool Cahills Mouse S i 92 12 3.0 Georgetown Rd. - 87 14 7.0 Calcutta Road 88 15 3.1 Midland Neights 89 15 4.7 Ohloville 90 16 5.2 Fairview School 10 4 0. 8 - Shippingport Doro. PA 45 5 2.2 Mt. Pleasant Church 60 13 3.7 Money's Fam 93 16 1.3 Sunset M111s. Midland
- 95 10 2.4 McCleery Ad. Mo11fe Williams !
E W 5.5. - Substation L M . m ' m m
- - n ~ , ~
TABLE V.A.1 CON 5OLIDATED RAD!0 LOGICAL ENVIRONENTAL MONITORING PROGRAM (Continued) k-DLC ? 5 pie Sa. ,le Anaissis g,3 . Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparatlow Frequency Analysis . I 8.7 Shermen's Farm Continvows II nasune-Dose
- 2. Direct 28 Quarterly UI Radiation TI 2 5.6 Brighton Tup. School (TLD) Annually (Continued) 72 3 3.2 Legen School 298 3 8.1 - Beaver Cownty Hospital 73 4 2.2 Potter Tap. School 74 4 6.8 Coeur. Col-Center Twp.
75 5 4.3 Holt Road 16 6 3.8 Raccoon Twp. School 77 6 5.8 Green Garden Rd (Meyne's) j 59 7 1.1 frons = 78 7 2.3 Raccoon Mun. 81dg. 27 7 6.2 Brunton's Taru 7 79 8 4.6 Rt. 18 & Rt. 151 ! 15 14 3.3 Georgetown - 46.1 3 2.1 Industry PA , g 91 2 3.7 Fine Grove Rd and Doyle Ed ag 94 8 2.4 skCleary Rd. Wilson {g g E N $I 3. Serface 49.1(a) 4 14 5.0 1.3 Arco Polymers Downstream (Midland) J & L Interefttent Monthly Composite of Composite Samples (j) IIeekly Sample (d) Gross Seta Gross Alpha
h 3
afater 2.1 Collected ideetly Gamme-scan 7 o 3 13 0.2 shippingport Ateefe Power tseekly Grob Overterly Cameosite Co-60. H-3 i g
%tation Discharge Samples Only Sr-89. Sr-90 3 ;:
49 (a) 3 3.2 Montgomery Den j % (Upstream) 2 2A 13 0.2 Downstreae 8vPS Outfall C 5 14 4.8 East Liverpool (row water) Defly Grab Sample " Only - Collected leeckly (j)
~
- 4. Groundwater 13 Il 1.6 phyer's Farm 14 II 2.6 Hootstown. PA 15 15 3.3 Georgetown. PA II 3 0.8 Shippingport Soro Quarterly Qtrarterly Gausne-scan, Gross Beta. Gross Alpha.
M-3
- 5. Drinking 4 14 1.3 Midlend. PA (Midland teater Interzfttent I'I thekly Composite of Gaeume-scen. 1-131 N Treatment Plent) Sample Collected Daily Sample (d) 7.
Ideekly Monthly Ceaposite (d) Gross Alpha. Gross Beta y 5 14 4.8 East Liverpool. OH (Eest Quarterly Composite (d) H-3.Co-60. $r-89. 90 L ifverpool Water Treatment , Plant) 6 5 0.5 DLC senw Training 81 egg. afectly Grab Sale _ _ _ . - . - . . - - -_~ ,.
i e TABLE V.A.1 3 CONSOLIDATED RADIOLOGICAL ENVIRONENTAL pWIITORING PROGRAM E ( Continwed) [ , DLC Sample Sample Analysis Type of Sample Points Sector Miles Sample Point Descrfptfon Sample Frequency Preperation Frequency Analysis (b)
- 6. Sherel f er* 2A 13 0.2 Dounstream BVPS Outfall Sentenemel Seefonnual Gamme-scan. Gross Beta Sediment Gross Alpha 3 13 0.2 victatty SAPS Discharge tirentum Isotopic 49 3 3.2 Upstream Side of Montgomery Sr-89. 90 l
Dom (a) 59 13 8.2 tipstream side of New Cumberland Den
- 7. Milk 25 10 2.1 Searight's Detry 10eekly I#I Weekly sample from I-131 0 Searight's only 3 Sfweekly (g) Bfweetly (grazin9) 6eume-scen When enfeels are Monthly (Indoors) Sr-89. 90 y en pastere; I-131. Cs-137 g
%(a) 10 10.3 windsheimer 1 monthly at other
- 27 7 6.2 Brunton's Dairy (h) . times. ,, o 29 3 8.3 Nico1's Defry (h) Monthly Monthly Gemme-scan Sr-89. 90 38 I-131. Cs-137 {3 8
C 8. Fish 2A 13 0.2 Vicinity of BVP5 #1 Sealannual Composite of edible h + scan on cotble $Og[r s Station Discherge and parts by species (f) portions Shippingport Dis. Ste. ~ 49(a) 3 4.7 Upstream Side of ';' ,$ Montgomery Den gg
*A
- 9. Food Crops (Shipp.) 10 (Georg.) 15 4 0.8 3.3 (Three locations within Anneel at Csayosite of each sample species Genne-scan k5 14 5 miles Selected by hervest if 1-131 on green f.
(Indus.) 46 3 2.5 Company) available leafy vegetables - 48(a) 10 16.5 tiefrton, W ,, O
- 10. Feedstuff and 25 10 2.1 Seerfght's Delry Farm Monthly Monthly Gamme-scan %
Sasuser Forege Owarterly Overterly compostte Sr-90 ,
- 11. Soll 13 11 1.6 f>yer's Farm Every 3 years 12 Core Samples Gemme-scan 30 4 0.6 Shtpplegpert. Pa. 3* Deep (3* Dia. Sr-90 46 3 2.6 Industry. Pa.
- I E * ****I et each location Gross Seta 32 15 0.8 (North of Site) Midle.ed (approx. 10* Gross Alpha 48(a) 10 16.5 tiefrton,ti. Va. radies) Uranium Isotopic
. 51 5 8.0 Aligelppe. Pa.
47 14 4.8 E. Liverpool. Oh. 27 7 6.2 Brunton's Defry 22 8 0.3 Seeth of BVPS Site 29A 3 8.3 Nichol's Defry- g e, i
- EvFS Technical Specificatioe Table 3.12-1 regelres three(3) dairles be selected en basis of highest potential thyroid dose wofag N
. milch censue data. See Section V.E. for specific locations sampled. .c
?
_- _ _ _ _ _ _ _ . - _ - - - - - - - _ _ ~ _ _ ._ .~ _ . . _ ._ __ - _ _ _ .
SLC?!DN V A DUOVith! LIGHT COMPANY TAtti v.A.1 , 1969 Annal Rectological Environmental Report I s L e' . 2 1
. a
,8 .
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dig l s: zu e
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. r H.
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- :18 I . 3 to: .
f h35 l , m i 5 3 -se ex: 8[$" ROS s b 5 t i= b e
SECTION V - A _DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report TABLE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING RROGRAM (Continued) Notes: . (a) Control sample station: These are ' locations which are presumed to be'outside the influence of plant effluents. 1 (b) Typical LLD's for Gamma Spectrometry are shown in Table V.A. l (c) Particulate samples aa not counted for 2: 24 hours after filter change. Periore gamma isotopic analysis on each sample when gross hna is > 10 times the yearly mean of - L control samples. (d) Analysis compositsc 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 b hours. (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 i pasture and monthly at other times. [ Assume April - October for grazing season (pasture).] (h) The milk samples from Brunton's and Nicol's are collected once per month. (1) The fish samples will contain whatever species are available. If the available sample size permits, then the sample will be I.yj , separated according to species and compositing will provide ' one sample of each species. If the available size is too 3 small to make separation by_ species practical, then edible E parts of all fish in the sample will be mixed to give one sample. (j) Composite samples are collected _at intervals not exceeding 2 hours at locations 49.1 and 2.1. Weekly grab samples are j obtained at location 3, 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 location, e I
SECTION V - A DUQUESNE LIGHT COMPANY' 1989 Annual Radiological: Environmental Report TABLE V. A.1
-CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING, PROGRAM (Continued)
Additional Notes: Sample points correspond to site numbers shown on maps. All Iodine I-131 analyses are performed within 40 hours of sample collection,if possible. All Air samples are decayed for.72 hours before analyzing for Gross Beta.
L SECT 10N V - A DUQUESNE L1 Gilt COMPANY ll! ' 1989 Annual Radiological Environmental Report- - V. ENVIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program (continued) 1 + 2.- Summary of Results All results of this monitoring program are summarized in Table V.A.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 V-B through V H and an assessment of radiation :g I doses are found in'Section V-I. Table V.A.3 summarizes' g4 Beaver Valley Power Station pre-operational ranges'for the various sampling media during the years 1974 and- . - 1975. Comparisons .of pre-operational- 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, previous nuclear weapons, tests or. to the normal statistical fluctuation for 3 activities near the lower limit of detection (LLD). gi 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 III of this report. The lower limits of detection for various analysis for each media mor.itored by this program by -the DLC Contractor l Laboratory are provided in Table V.A.4. E-d
-$1-n -
a - - -
ENVII'ONMENTAL RADIOLOGICAL MONff0 RING PROGRAM
SUMMARY
Name of Facility Beaver Vallev Power Station Unit 1 and 2' Docket No. 50-334/50/412 ' tn location of Facility Beaver. Pennsvivania Reporting Period Annual 1989 p 4 (County. Statel o v. Number of < Analysis and Lower Limit All Indicator locations Ig;ation with Illahest Annual Mean Control Locations Nonroutine e Medium of Pathway Total Number of "Mean (0 "Mean (0 Reported y Sampled ofAnalysis Detection " Mean (0 Name Distance and Directions "Hange "Ra nge (Unit of Measurement) Performed (LLD) " Range _ Measurements *" Wetrton. WV No 48 2.5 21(519/519) 30. Shtppingert. PA 72(52/52) 2)(51/51) 0 $ e Air Particulate Gross (519) . (7.6-55) (6.4 -54) Beta (5.9-55) 0.6 mt ENE and Rad!otodine (X10-3 pct /Cu.M.) Sr-89 (40) 5 IID - f
- 46. Industry. PA 0.62(1/4) LID -
0.62(1/40) Sr-90 (40) 0.2 p8 2.4 mi NE -- 40 IID -- -- -- - gg I-131(520) o G;
-n Gamma (120) 8M d 92(120/120) 29B. Beaver Cty Hosp. 111(12/12) 89(12/12) 0 7[
D Y Be-7 40 (46-304) 8.1 mt NE (57-304) (66-129) @.
.i 298. Beaver Cty Hosp. 84(1/12) IlD 0 9e K-40 20 35(4/120) 18 (16-84) 8.1 mi NE --
cY IID -- -- -- - yy Others Table V.A. B E 5" o 4 r
- Nominal lower Limit of Detecuon (LLD)
" Mean and range based upon detectabic measurements only. Fraction of detectable measuremems at spectned locations is ind!cated in parenthese
*' Nonmutine reported measurements are defined fra Reguilatory Guide 4.8 (MARCH 1975) and the Beaver Valley Power Station Specifications .
_ _ _ _ _ _ _ _ _ _ = . . . . .
i ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
l Name of Facility Beaver Vallev Power Statien Unit I and 2 Docket No. 50-334/50/412 m location of Facility Beaver. Pennsvivania Reporting Period Annual 1989 m (County. State! -O
~
! O Analysis and lower Limit Number of < Medium of Pathway Total Number of All Indicator Imcations location with Highest Annual Mean Control locations Nonroutine e Sampled ofAnalysis Detection " Mean (0 Name "Mean (G "Mean (O Reported > (Unit of Measurement) Performed (LLD) " Range Distance and Directions" Range " Range Measurements"* Weirton. WV No. 48 External Radiation Gamma 0.05 0.17(175/175) 84. Hancock County 0.21(4/4) 0.17(4 /41 0 - (mR/ day) (175 quarterly) (0.12-0.22) Children's Home - (0.19-0.22) (0.16-0.18) g 8.5 mi SW e Gamma 0.16(43/43) 87. Calcutta Road 0.20(1/1) 0.16(1/I) 0 o (43 annuaD (0.12-0.20) 7.0 ml WNW - -- c-
"c WC Feed and Forage 1-131 (12) 0.01 IID -- -
One Sample - ElO ! (PCl/g) location cE-
~ ::
(dry weight) 8
$ Sr-90 (4) 0.003 0.083(4/4) -- - -- 0 $M s (0.040 0.14} pg
' as o Gamma (12) H g. . n Be-7 0.3 2.2(5/12) - - -- 0 5y. (0.93-4.6) yg
,j.
K-40 0.5 28(12/12) -- -- -- O c 3' (11-58) ! o Others Table V.A. IID -- - -- - S
. ~
e i N 4 p is en
- Nominal lower Limit of Detection (LLD) . >
" Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses {0 *
"* Nonroutine reported measurements are de6ned in Reguilatory Guide 4.8 (MARCH 19751 and the Beaver Valley Power Station Specifications .
M m - m.
l lmu iId EI ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
~
Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50/412 E e
. location of Facility Beaver. Pennsvivania ReportingItried Annual 1989 d (County. State) @
Analysts and Lower Limit Number eI Medium of Pathway Total Number of All Indicator Locations location with Hiahest Annual Mean Control Locations Nonroutine > Sampled ofAnalysts Detection " Mean (0 Name **Mean (0 ~Mean (O Reported (Unit of Measurement) Performed (LLD) " Range Distance and D',m'h" Range "Ra nge Measurements"* Montgomery Dam No. 49 G co 4"> Fish Gamma (10) (pC1/g) K-40 0.05 3.0(10/10) 49. Upstream - 3.1(4/4) Same as O g (wet weight) (1.4-4.3) Montgomery Dam (1.4-3.7) high location :s 4.7 mi NE E Others Table V.A. IID -- -- - - EE
- o. c. ^
oE w :r. 0 tM 3 b
- eH hO
< O e3 oh ii 5 G
w
?
=
k n H en Nominal Lower Limit of Detection (LtDI "
" Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled locations is indicated in parentheses (f)
"* Nonroutine reportM measurements are defined in Reguitatory Culde 4.8 (MARCH 1975) and the Beaver VaBey Power Station SpecfBcations .
,_ _ . = -
t tn ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
E: H-Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50/412 "8 z location of Facility Beaver. Per..-,;.s.11. Reporting Period Annual 1989 <- (County. State) t
- y. ,
Analysts and lower Limit Number of Medium of Pathway Total Number of All Indicator locations Location with Highest Annual Mean Control locations Nonroutine Sampled ofAnalysis Detection " Mean (f) Name .
"Mean (0 "Mean (f) Reported (Unit of Measurement) Performed (LLD) "Ra nge Distance and Directions" Range " Range Measurements"*
Montgomery Dam No. 49 _ e Food and Garden 1-131 (4) 0.006 IJD Crops (pCl/g) twet weight) Gamma (4) 6
=
K-40 0.5 3.l(4/4) 48. Weirton. WV 5.2(1/1) Same as high 0 $ (1.9-5.2) 16.05 mi SSW -- location := 8x) ! Others Table V.A. IlD -- - - - E.E. n tn t O Z t.r. w t' t.n O 8 oc t-
** g in ::
~H rn O U
< .O.
**8$
bN a e i o
.- g so 1
C i T C M, r d g _ . c-
-i
- ' " ~ '
4 Nominal Lower Limit of Detection (LLD) ~'~~~~."^~~" Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified Iwations is indwwted in parenirses (f) i * " Nonrouttne reported measurements are defined in Regullatory Culde 4.8 (MARC 11 1975) and the Heaver Vailey new Sentum Sp-tifw-ntions . 2
._ . _ -_ _ - . _ _ - _=
m - - i r .1 e i ... . . r - - m ENVIRONMENTAL RADIOlfGICAL MONfTORING PROGRAM
SUMMARY
E
.g Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50/412 c z
location of Facility Beaver. Pennsvivania Reporting Period Annual 1989 < (County. Statel .. Number of Analysis and lower Limit Medium of Pathway Total Number of All Indicator locations f_m'h with Hintent Anm==f *== Controllocations Nonroutine Reported Sampled ofAnalysis Detection " Mean (f) Name "Mean 10 "Mean (O
" Range Distance and Directions " Range " Range Measurements"*
(Unit of Measurement) Performed (LLD) Brunton Didiy No. 27 ,,_ e Milk 1-131 (165) 0.2 11D -- -- (pC1/1) - -- - Sr-89 (132) 2 11D - o 102. Ferry Dairy 5.7(3/3) 2.3(18/19) 0' E Sr-90 (132) 1 2.7(129/132) (0.54-8.3) (3.8-7.0) (0.5-8.3) "@~ hO.
- c. r-Gamma (132) nm K-40 100 1490(132/132) 69. Collins Dairy 1690(2/2) 1350(19/19) O bN i
(1610-1770) (1120-1470) jg y (1120-2020) -- s Cs-137 5 6.0(2/132) 103. Conkle Dairy ' 6.7(1/16) 5.4(1/19) O EO
- -4 (5.4-6.7) in n IID - -- - U9-Others Table V A. -
gs R E w
?.,
- re
+-t r-r.
I
- Nominal lower Ifmit of Detection (11D) ts
" Mean and range based upon detectable ii ew.. ants only. Fraction of detectable measurements at specified locations is indicated in parentheses (0
" Nonroutine reported measurements are denned in Reguttatory Culde 4.8 (MARCH 19751 and the Beaver Valley Power Station Spect8 cations .
. =- . - - _ -= _
--i l
l l ENVIRONMENTAL RADIOIDGICAL MONTTORING PROGRAM
SUMMARY
Name of Facility Beaver Vallev Pbwer S***aan Unit I =ad 2 Docket No. 50-334/50/412 location of Factitty Beaver. Pennsyhrania . Reporting Period Annual 1989 m (County. State) F,. H O
^ '
Analysis and Imwer Limit Number of < Medium of Pathway Total Number of All Indicator locauons location with Highest Annual Mean Control Imcations Nonroutine Sampled ofAnalysis Detection " Mean (f) Name ."Mean (0 "Mean (O Reported 8 (Unit of Measurement) Performed (LLD) " Range Distance and Directions " Range ~ " Range Measurements"* > Montgomery Dam No. 49 Sediment Gross (8) 0.3 16(8/8) 2A. BVPS Discharge 21(2/2) 14(2/2) - 0 - ((pCl/g) Alpha (10-25) 0.2 mi. W (16-25) (12-15) (dry weight)
- Gross (8) 0.1 39(8/8) 2A. BVPS Discharge 47(2/2) 34(2/2) O p Beta (22-51) 0.2 mL W (44-50) (31-37) g c-Sr-89 (8) 0.2 IID - - - - o e
Sr-90 (8) 0.04 IID - - - - pj C. C r l Gamma (8) 7y ! I wg
**8 U' Be-7 0.2 2.0(2/8) 2A. BVPS Discharge 2.8(1/2) IJD 0 S (1.3-2.8) 0.2 mL W -
p[ ua K-40 0.5 12(8/8) 3. SAPS Discharge 15(2/2) 11(2/2) O ~y , ! (6.2-16) 0.2 mL W (14-16) (10.6-11.4) en !
! co I
2A. BVPS Discharge 0.47(2/2) 11D 0 Co-58 ' O.2 0.32(4/8) (0.08-0.49) 0.2 mL W - (0.45-0.49) Nh oy ' ox . Co-60 0.2 0.33(3/8) - 2A. BVPS Discharge 0.67(1/2) IID 0 S# (0.073-0.67) 0.2 mL W .-. E i u Cs-137 0.02 0.20(8/8) 2A. BVPS Discharge ' O.27(2/2) . 0.20(2/2) . 0 (0.056-0.29) .. 0.2 mL W (0.24-0.29) (0.19-0.21) y v i Ra-226 0.1 1.8(8/8) 3. SAPS Discharge 2. l(2/2) - 1.7(2/2) 0 o ' (1.3-2.2) 0.2 mi. W (1.9-2.21 (1.5-1.8) n Th-228 0.02 1.2(8/8) 2A. BVPS Discharge 1.7(2/2) . .1.2(2/2) 0 a (0.60-2.0) 0.2 mL W (1.3-2.0) (1.2- 1.2) @ r-Others Table V.A. IJD -- - - - - -
- Nominal tower Limit of Detection (LLD)
~
" Mean and range based upon detectable measurements only. Fraction of detectable nacasurements at spectised locations is indicated in parentheses (0 S
~
'" Nonroutine reported measurements are defined in Reguilatory Culde 4.8 (MARCH 19751 and the Beaver Valley Power Station Spectftcations .
e i
ENVIRONMElfrAL RADIOLOGICAL MONTIORING PROGRAM
SUMMARY
Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50/412 tn Location of Facility Beaver. Penn..:..nla Reporting Period Annual 1989 ~F.5 (County State) o
=
Number of - <- Analysis and - Lower Limit Medium of Pathway Total Number of All Indicator Iscations LeHan with Hiehest Annual Mean . Control Locations Nonroutine Sampled ofAnalysis Detection " Mean (0 Name "Mean (f) "Mean (f) Reported > (Unit of Measurement) Performed (LLD) " Range Distance rad Directions " Range " Range i Measurements *" 0.2 0.37(8/155) 04. Midland. PA 0.39(5/51) -- O cx, Drinking 1-131 (155) o Water (0.27-0.45) 1.3 mi WNW ' (0.33-0.45) (pCl/1) > Cross (36) 0.6 11D -- -- -- - c Alpha E 04 Midland. PA 5.7(12/12) O t Cross (36) 1 4.7(36/36) -- [fj. Beta (2.2-13) 1.3 mi WNW (3.5- 13) c. c-Gamma (155) Table V.A. 11D - -- -- - oE
-n Sr-89 (12) 1.5 IJD -- -- - - t0 "
Mi XC Sr-90 (12) 0.5 IJD -- -- -- - epH Co-60 (12) (a) 1 IID -- -- -- - pn
54 e E o . w a v S e .a tn r-(a) Co-60 analyzed by high sensitivity method. .
- Nominal tower Limit of Detection (LID) >'
' Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectned locations is indicated in parenthen (Q o "* Nonroutine reported measurements are denned in Reguilatory Guide 4.8 (MARCH 1975) and the Beaver Valley Power Station Spectncations . ~ ~ ~ . . - . ~ . - - - -.. - - = ~ - - - . . . - . - - -_---_-.___v. ___ :.- =. . .;.--.-,~-.~,-,-..- - - - - - ENVIRONMENTAL RADIOLOGICAL MONTTORING PROGRAM
SUMMARY
Name of Facility Beaver Vallev Power Ss.eaan Unit I and 2 Docket No. 50-334/50/412 - tn m location of Fadlety Beaver. Pennsvirania Reporting Period Annual 1969 O (County. Statel g z Number of < Analysts and lower Limit e Medium of Pathway Total Number of All Indicator locations L-tion with Hiahest An===1 Mean Control Locations Nontoutine Reported ofAnalysis Detection " Mean (0 Name . "Mean (0 "Mean 10 3 Sampled Distance and Directions " Range - "Renge (Unit of Measurement) Performed (LLD) " Range Measurements *" Georgetown. PA No.15 Groundwater Gross (16) 2 11D - (pCl/l) Alpha 4.l(14/16) 11. Shippingport. PA 5.3(4/4) 3.2(4/4) 0 b Gross (16) 1 (4.3-6.9) (2.8-3.8) $ Beta (1.5-6.9) 0.8 mi NE N
- - - o Gamma (16) TableV.A. 11D -
O 55
- c. c Tritium (16) 90 300(3/16) I1. Shippingport. PA 560(1/4)- -
(150-560) 0.8 mi NE - 7Q
-z h"
- C
&@~3 bo
,S #&
i!i
,E_
. YI
?
m
~
- Nominal Lower Ltmit of Detection (LLDI
' Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectned locations is indscated in parenthess 73 10
'* Nonroutine reported measurements are deSned in Reguilatory Culde 4.8 (MARCH 1975) and the Beaver Valley Power Station Specificatu.e :'
M' I4 E ' tr E ENVIRONMEPTTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
g C Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50/412
~
location of Facility Beaver. Pe. -.: -ida Reporting Period Annual 1989 , (County. State) > Analysis and lower Limit Nuirb of Medium of Pathway Total Number of All Indicator locations L-tion with Ih* A-==*8 Mean Contml locations Nonmuune Sampled ofAnalysis Detection " Mean 10 Name "Mean (0 "Mean (O Reported (Unit of Measurement) Performed (LLD) "Ra nge Distance and Directions" Range " Range Measurementn~* ~ Wetrton. WV No.48 e os Water Gross (32) 9.6(32/32) 48. Weirton. WV 12(11/1I) Same as high 0 Precipitation Beta 1 (3.1-23) 16.05 ml SSW ($.8-23) location . g (pCl/l) g D Camma (32) *y
- e o Be-7 40 59(17/32) 47. E. Liverpool. OH 72(4/101 - 58(7/11) 0 @, $
4.8 mi WNW (45-99) (l4-107) rm (14-107) oz W tn i o
& K-40 36(2/32) 30. Shippingport. PA 36(2/1I) IlD 0
? (16-55) 0.6 mi ENE - (16-55) - EC 0$
"d Others Table V.A. LID - ~ ~ -
t-r o 2 IID - - -- - ap Sr-89 (12) 1 80 ' Sr-90 (12) 0.5 11D -- -- - - gg
- s R 100 320(3/12) 30. Shippingport. PA 470(1/4) 250(1/4) 0 g H-3 (12) p (240-470) 0.6 mi ENE -- -
e
~
b
,if, O
n H to b b-b Nominal lever IJmit of Detection (LLD)
' Mean and range based upon detectable measurements only. Fraction of detectable measurements at spedfled locations is indicated in perentheses (f)
*" Nonroutine reported measumments are deftr:ed in Reguilatory Guide 4.8 (MARCII 19751 and the Beaver Valley Power Statim speciftcations .
= _ _ _ - _ _ - - . . .-,_ ---,. .- - -- ~- ---. .. v.. . ~ - - - ~ - ~ - - , ~ . ~ . - - - ~ ~ ~ - ~ - - - . - - = + - .. -
ENVIRONMENTAL RADIOLOGICAL MONHURING PROGRAM SUMu_4RY :.i Name of Fadlity Beaver Valley Power Station Unit 1.me 2 Docket No. 50-334'50/412 location of Fadlity Beaver lb--.:.- :- Reporting Period Annual 1989 , (County. State) [ ! O. ? Analysis and Lower Limit # Number of . Medium of Pathway Total Number of AI! Indicator Locations Incation with Hanhest An--I ha Control Locations Nonroutine 8 l Sampled ofAnalysts Detection " Mean (9 Name "Mean 10 "Mean (S Reported > (Unit of Measurement) Performed (LLD) " Range Distance and Directions " Range " Range Measurements *" Montgomery Dam No. 49 - Surface Water 0.5 $' I-131 (52) IID - -- -- - e (pCl/1) Gross (72) 2 5.6(2/72) ' 05. E. IJverpool. OH 5.6(2/12) IlD - 5 Alpha (3.7-7.5) 4.8 mi WNW (3.7-7.5)
- o Gross (72)
Beta 1 7.6(72/72) 05. E. IJverpool. OH 4.8 mi WNW 12(12/12) 6.2(12/12) 0 yj
- o. c-(2.8-30) (5.4-30) (4.0-11) cE os Gamma (72) yy co
*;* Others Table V.A.11D - - -- -
p[ , eo Sr-89 (24) 2 IID - -- --- -- -
* 5 ,
w Sr-90 (24) 0.5 11D - -- -- - 5 .8. . n 80 Co-60 (24) (a) 2 11D - - - -- -- - y#,4
- l Tritium (24) 100 1800(13/24) 02A. BVPS Discharge. 4200(4/4). 210(1/4) 0 .5*
(160-8600) 0.2 mi W (560-8600) -- E-u- 0, e
.-4 en E
(a) Co-60 analyzed by high sensitivity method. ,4 - Nominal tourer Limit of Detection (LID)- >-
~
*
- Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled locations is indicated in parentheses (f) r
*" Nonroutine rsported measurements are defined in Reguilatory Guide 4.8 (MARCH 1975) and the Beaver Valley Power Station Specificauons .
l.
-SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1989 Annual Radiological Environmental Report (Page 1 of 4)'
_ TABLE V.A.3 (Page 1 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Nems of Tacility beaver W11ev Power Stetton Docket No. 50-134 toe.ation of Tacility beaver. Pennevivente Reporting Period CT 1974 - 1975 (County. State) PRE-0PERATIONAL FilDCRAM
SUMMARY
(CCH3tNED 1974 = 1975) Medius or fotbway lower Limit sempted Analysis and Total Number of ul ladicator locatione (Unit of Measurement) of AnalveLe Performed Detection 1.!b Heaa. (f) Ranae Surface Water Croce Alpha (40) 0.3 3.75 3/ 40- 0.6 - 1.1
- pci/1 UD Grose leta (12 0) 0.6 4.4 /12 0 2.5 - 11.4 Gemma (1) 10 - 60 < t.LD Tritima (121) 100 300 uo/121 180 - 800 3r-89 (0). - -
$r-90 (0) - -
C-14 (0) - - D-ankin8 Yater 1-131 (0) - PC1/1 4 Crose upha (50) 0.3 0.6 /50- 0.4 - 0.8
-. Groes neta (208) 0.6 3.8 208/208 2.3 - 6.4 Camma (0) - -
Tritium (211) 100 310 2n/211 130 - 1000 C-14 (0) - - Sr-49 (0) - - Sr-90 (0) - - Cround Water Cross Alpha (19) 0.3 < t.LD pC1/1 Crose tota (76) 0.6 2.9 I3/75I *I 1.3 - 8.0 77 Tritium (81) 100 440 /81 80 - 800 Comma (1) 10 - 60 < t.ta Air Particulates Cross Alpha (188) 0.001 0.003 35/138 0.002 - 0.004
, and Caseous pC1/s3 Cross Beta (927) 0.006 0.07 927/927 0.02 - 0.32 St-81 (0) -
Sr-90 (0) - 1-131 (816) 0.04 0.08 2/ 816 0.07 - 0.08 Camoa (197) 5 ZrNb-95 0.005 0.04 122/ 197 0.01 - 0.16 50 Ru-106 0.010 0.04 /197 0.02 - 0.09 3 Ce-141 0.010 0.02 /197 0.01 - 0.04 Co-144 0.010 0.02 "/197 0.01 - 0.04 f others < !.I.D
.. ---. . - - ~. . - . _ - _ . . . - - - - - . . - - . . - _ . - - . _ . . . -
SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.Ae3 1989 Annual Radiological Environmental Report (Page 2 of 4) l TABLE V.A.3 (Page 2 of 4) 1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAM
SUMMARY
Name of Facility leaver valley Power Station Docbt30. M
.J 14catico of Facility leaver. Penasvivania taPorting Period CT 1974 - 1975 !
(County, State) I PRE-0FERATIONAL PROGRAM SIRetART (COMBINID 1974 - 1975) Medium or Pathmar laver Limit ' sempled Analysis and Total Nimber of All Indiastor Locatione (Unit of "-- _- t) of A-=19eis Perf r--.: Detectien 1.1.D "- . (f) *-- _ j Seil- Gross Alpha (0) - - ' PC1/g (dry) (Template samples) Grose Beta (64) 1 22 g/4 6 14 - 32 i Sr-49 (64) 0.25 0.4 1/64 - f. I sr-90 (64) 0.05 0.3 a esf,4 ,,g ,3,3 I U-234.235,238 (0) - - - b Geena (64) E-40 1.5 - 13 '3/64 5 - 24 l co-137 0.1 1.5 3'/ 64 0.1 - 6,8 f co-144 0.3 1.1 I/64 0.2 - 3 trub-95 0.05 0.3 - U /34 - 0.1 - 2 to-106 0) 0.3 - 1.1 3/64 0.5 - 2 othere < t.LD PC1/s (dry)
.r.1. (0) _ = I (Core samples) Grose Beta (0) 1 21 g/8 16 - 24 Sr-49 (8) 0.25 < Lla 1 se-90 (s) 0.05 0.2 5/8 0.0a - 0.5
- (.) .
l E-40 1.5 13 8/8 7 - 20 Co-137 0.1 1.2 I/ 8 0.2 - 2.4 'I 1 Ce-40 0.1 0.2 - /s' - 1 Othere <W l 1 g. J
I SECTION'V - A DUQUES.lE LIGHT COMPANY TABLE V.A.3 L .1989 Annual Radiological Environmental Report (Page 3 of'4) , e TABLE V. A.3 (Page 3 of 4) , L ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAtt
SUMMARY
j Isene of tecility leaver Valler tower Station Docket No. M' location of Facility 24ever. Peamerivaala Reportist level CT 1974 - 1975 I U.euety, 8 tote) Ptt-OPERAT10lW1 PRDORAM 80etART(COMsurID 1974 - 1973) Itadie or tethuey . Imwar Liest Sampled analysis and Total N eber of All Indiastor 14catione M t of Measuremant) of A*alysia Per greet Detection t.12 Maan.-ff) *-- :
$sdinants Croes Alpha- (0) ' -
I * ' PC1/8 (MT) 33f 33-Groes Seta (33) 1 18 3 - 30 ~f St-90 (0) - - U-234.233, 138 (0) -- - . Gamma (33) 13 33/33' . 3 - 30 E-40 33 1.5 13 /33 2 - 30 I Co-137 0.1 0.4 21/33 0.1 - 0.6 trub-95 0.05 0.8 U /33 0.2 - 3.2 Co-144 3 0.3 0.3 /33- 0.4 - 0.7 i to-106 M 0.3 1.3 3/33 1.3 - 1.8 others e 11D Foodstuff Gamma (8) PC1/8 (8ry) 8 l E-40 Ce-137 1 33 /8 10 - 33 0.1 0.2 1/8 - trub-95 1 0.03 0.2 /8 I a -106 0) 0.3 0.8 1
/8 _
Othere < 11D Feedstuff Grose Seta 80 (80) 0.0$ 19 /40 8 - 50 PC1/8 (dry) ar-89 33 (81) 0.023 - 0.2 /81 0.04 - 0.93 3r-90 (81) 0.003 0.4 3'/81 0.02 - 0.81 Osama (81) E-40 I3 /81 1 19 5 - 44 l t Co-137 6 fgg. 0.1 0.5 0.2 - 1.6 C*-144 5 0.3 1.5 /01 0.9 - 1.6 Zrub-95 0,03 0.8 U/81 0.2 - 1.8 Ru-106 M 0,3 1.4 U/81 0.6 - 2.3 Others < 11D l SECTION V.- A DUQUESNE LIGHT COMPANY- . TABLE VeAe3- ) 1989 Annual Radiological Environmental' Report (Page 4 of 4); i 1 TABLE V.A.3 (Page 4 of 4) .j ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver valle, Power Statico. Docket No. 50-334 location of Facility leJygra l e Pennsvivania Reporting Level CT 1974 - 1975 1 (comey, state) J l Ft2-OPERATIONAL PRDORAN St29(ART (COMBINED 1974 - 1975) ) l Medium or Pathway . Immer Limit Seapled Analysis and Total pueber of All Indicator tacations h it of Measurement) of Analvois Performed Detection LLD Mean. (f) Ramme 1 Milk 1-ul (91) 0.25, 0.6 '/ 91 ' 0.3 - 0.8 PC1/1 sr-49 (134) 5 7 6/134 6 - 11 Sr-90 (134) 1~ 5.3 U2 /134 1.5 - 12.8 . Gamme (134) Co-137 10 13 U /134 11 - 16 Others e 11D Baternal Radiation y - Monthly 0.20 599/399 (S99) 0.$ mR
- 0.04 - O.31 eP/ day 195 y - Quarterly. (193) 0.3 mR* 0.20 /195 0.11 - 0.38
'8 i
y - Annual (44) 0.3 mR
- 0.19 /44 0.11 - 0.30-l l Fish Gross Beta (17) 0.01' 1.9 U/17' ~1.0 - 3.2
! pC1/g (wet) m l 3r-90 (17) 0.005 0.14 'U/17 0.02 - 0.30 Gamma (17) 1-40 0.5 U /17 2.4 1.0 - 3.7 Other a 11D l i LLD in units of MR - Lower end of useful integrated exposure detectability range for s Ii j passive radiation detector (TLD). l I*) Cae outlier not included in mean. (Water takan from dried-up spring with high sediment [ and potaasium content. Not considered typical groundwater sample.) l M May include Re-106, Ru-103. Be-7. j i _ .- _ - _ _ - - -- ~ - - - - -
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)
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, etL mi .
0 ivr 5 4 ti e e 9 M 1 t w d - 3 6 D 2 4 6 7 - 1 4 6 8 t co i 1 4 8 9 0 5 b 0 0 l 1 3 3 3 3 3 a 4 4 2 2 AAL l 7 01 5 5 5 5 6 6 N 1 1 i 3 1 3 1 1 1 L 1 1 2 2 c - - - - - - / - - - - - - - / - - a'h 1 1 u r n o e o n r u u e t - e - s s s s e c * *ET N c nC M C r C 2 2 R R A 1 T I C C C B C C R T
- O N
[7
- q SECTION V B DUQUESNE 42GHT COMPANY
'1989 Annual Radiological Environmenta1 Report V. ENVIRONMENTAL MONITORING ,
B. Air Monitoring f ^
- 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 -
i ! 'The air is sampled for gaseous radiciodine and ' f
! radioactive particulates at each of ten (10) off- -
-site air sampling stations. The' locations of these stations are listed in Table V.A.1 and,shown on a _
map-in Figure S.B.I. Samples are collected at each of these stations by_ continuously drawing about one cubic foot per
}
minute of atmosphere air through a glass fiber. filter and through a enarcoal cartridge. . The former collects airborne particulates; the latter is for radioiodine sampling. Samples are collected- 5; for analysis on a weekly basis. The charcoal is used in the weekly analysis of airborne I-131. The filters are analyzed each week for gross beta, then composited by station for monthly analysis by gamma spectrometry. They are further composited in a quarterly sample from each. station for Sr-89 and Sr-90 analysis. In order to reduce interference from natural radon and thoron' radioactivities,.all filters are allowed to decay for a few days after collection prior to counting for beta in-a low background counting system.
- b. Procedures Gross Beta analysis is performed by placing the -1 filter paper from the weekly air sample in a 2" x 'L 1/4" planchet and counting it in a low background, .j
( gas flow proportional counter, i
.t
+-
4
~- ;.1 ,
SECTION V - B- = DUQUESNE LIGHT. 'CONPANY.
.1989 Annual Radiological' Environmental Report-
'V. ENVIRONMENTAL MONITORING-w .
B. -Air tjonitoring (continued).' I 2. ' Air ~ Sampling Program and ' Analytical Techniques icontinued). b.- Procedures (continued)- {- Gamma emitters;- are determined by stacking all .the i
~ filter,,; papers from each- monitoring .-station b.- collected during~ the . month and. scanning fthis i
-composite on a lithium drifted' germanium -(Ge(Li)) '
-gamma-spectrometer.
[' =Radiciodine '(I - 131 ) ' analysis- is performed =by'a gamma-scan of thet charcoal ~ -in a weekly charcoal-cartridge.; The activity is referenced to the mid-
-collection time.
(.- { ( t 1
- [
j i V , o , a 6 -
~68-
_ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ ~ _ _ . _ . _ _ _ _ _ _ . . _ _ - . _ _ _ _ . _ _ . . - _ _ . _ _ _ _ _ _ _ _ . . . . . _ _ . . . ! SECTION V - B TIGURE 5.B.1 . (, DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report l l . FIGUM 5.B.1 l m m m m m. m To mas LOCATHN0" AIR S#PLIE LOCATI(76 N t**assera omewrY AIR SAfl_!E STATIJC l E ' y E, n u o. imm ) \ - is rena's mm r. L
-u l
~~-- L.h 27 28 2x
- m. ,.
s m miny wa, cam wn , r~ - y , _ ,, u ~ ,
.g (g (:,:
j
- 3-g.
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- 3 k,
% 1mm gg
~ "
w 47 EAsi Llwamx., Guo ' f,' 48 winTon, est vinaisia g ~a .
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51 A.sanPPA o, N ,, ,,, / o I ~
)
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m.~, 46 ' , y. , O- 30 , A.g l ,- l, F d **"*'g.. "\ .
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s-SECTION V - B DUQUESNE LIGHT C0riPANY + 1989 Annual Radiological Environmental Report - V. ENVIRONMENTAL MONITORING B. Air Monitoring (continued) [ 2. Air Sampling (continued) Program and Analytical Techniques
- b. Procedures (continued)
Strontium-89 and Strontium-90 activities are I determined in quarterly composited air particulate filters. . Stable strontium carrier is- added to the sample and it is leached in nitric acid to bring I depesits 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 ! as Sr(NO3 ): using fuming I precipitated nitric acid. An iron (90*4) (ferric hydroxide) , scavenge is performed, followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium I ' ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated 'as oxalat;e. The yttrium oxalate is mounted on a nylon planchet and is , I counted in a low' level beta counter to infer Sr-90 l activity. Sr-89 activity is determined by l precipitating SrCO from the sample after yttrium ! separation. This . precipitate is mounted on a : nylon l planchet and is covered with 80 mg/cm 8 aluminum absorber for level beta counting.
- 3. Results and Conclusions l
A summary of data is presented in Table V.A.2. ,
- l. a. Airborne Radioactive Particulates i
A total of five hundred nineteen (519) weekly samples from ten (10) locations were analyzed for gross beta. One air . particulate was not obtained due to sandblasting interference at the station location, j I Results were comparable to previous years. Figure j 5.B.2 illustrates the average concentration .of ' gross
~
i beta in air particulates. j i I l .,..
--- -------------_-,__.-___-------,-------_-._--,-,----,--,-.-__----,----..--.-_----,.-,._a .,g .. ..a , w g g .
l l
- 1989 m AVERAGE CONCENTRATION O_F GROSS BETA IN AIR PARTICULATES I N
, O l z ,
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tp 3
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E 178 x - 5 . g gia mi on
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.001 8 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC y sees n-
[ u
s. ^ SECTION V - B DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmen.tal Report - V. ENVIRONMENTAL MONITORING B. Air Monitoring (continued) I -3. Results and Conclusions (continued)
- a. Airborne Radioactive Particulates.(continued)
The weekly air particulate samples were composited to one hundred twenty (120) monthly samples which I were analyzed by gamma spectrometry. Naturally _! occurring Bo-7 was present in every sample, ' Occasional traces' above detection levels of other i I naturally occurring nuclides such as K-40 were present. These are listed in the summary Table V.A.2. ' I A total of forty _(40) quarterly samples were each 1 analyzed for Sr-89 and Sr-90. Sr-90 was detected'in I one sample atz Location 46, Industry, PA. The I positive result may be attributed to Station releases, however, none of the_ other sample g locations showed positive results and this_ positive j result is more likely attributable to expected variability in the analyses _results of very low 1 levels of activity, i I l Based on the analytical results, the operation of ! Beaver Valley Power Station did not contribute to any increase in air particulate radioactivity I during CY 1989. '
- b. Radioiodine I A total of five hundred twenty '(520) weekly l charcoal filter samples were analyzed for I-131. .
No detectable concentrations' were found at any I locations. ! Based on- analytical results, the operation of I Beaver Valley Power Station did not contribute to l any increase in airborne radiciodine during CY 1989. l
SECTION V - C DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and' Soils (Soil Monitoring is required-every 3= years and was not required in 1989)
- 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 i
River bottom sediments were cc,11ected semi-annually. g', above the Montgomery Dam in the vicinities of the- gt Beaver..' Valley discharge and Shippingport 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 V.A.1 - f and are shown in Figure 5.C.I. Bottom sediments are analyzed for gross alpha and , beta activity, strontium, uranium, and _the gamma-emmitting radionuclides. I
- b. Analytical Procedures = I-q 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. ^ l Gross alpha activity of sediment or soil is analyzed in the same manner.as gross beta except that the counter is set up to count only alpha. Gamma analysis of sediment or soilL is performed in a 300 ml plastic bottle which is counted by a gamma-spectrometer, i I l l
3 SECTION V~- 'C FIGURE 5.C01 . ~- f DUQUESNE L1GitT COMPANY 1989 Annual Radiological Environmental Report SEDI!:ENTS AND SOILS i~ L-Fl8U M 5.c.1 EWIRolmassetAL edcastomaNe ulMATIONS- SHDEL!!E SEDITNTS & S0ll i [ N - "Y l geAsn Ceuthf 1 } smEur sEImxis I b-g a2A txamstrem BWS Outta11
\
.t _
~7 f i i
3 Vicinity SN'S Dimetarge 49 Upstrearn Side of nmtgtmuary .e .. L .* % , l l -
)
$0 tross Side of New [f _
~~a a- ,
s .- p# < I - anL ,_
') .' !-
yy
~
I. a W 1 W M=yer's rarn- p" ). 22 South of BVPS Site , y*' ..
- 1 h .. O'S ,
n 9A w rt. ,A Da
,' m /,# .
I !! 1re stry. ,A 1 k
- =m. ,<.- o i _. .
s1 . - I A . p;^ _ls 9
.i -
s u.. , 6 i ,
. fs,hs f
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. ]'4
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@ (CtY ~~
.."e' h l .
ere Af=g i pl . .. y a
~\
P 1 I M*"' l m@ g ia i
/
/
5 a ly __e_, 1 . s/ - - y g . . . uneemotoo4 couary , q l I (';;3, I g_5 . . Ni u.u/ s 1
.1 c[-\ _h, l a,l %~.
s SECTION V - C _ DUQUESNE fdGHT COMPANY 1989 Annual Radiological' Environmental Report V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and- was not required in 1989) . (continued)
- 2. Sampling Program and Analytical Techniques (continued) . ,
,['
- b. Analytical Procedures (continued) i Strontium 89 and '90' are determined by- Ll radiochemistry. A weighed sample of sediment or .
soil is leached with Nitric Acid HNO 3 . A stable : g-carrier is added for determination- of recovery. -3 Strontium concentration- and purification . is 1,
" ultimately realized by precipitations of strontium nitrate in fuming nitric acid. Additional- ]
hydroxide precipitations and- barium chromate ; separations 'are also used. The purified strontium- -l 1s- converted to .a carbonate for weighing. and 1 counting. Samples are counted soon after- i separation (5 - 7 days is allowed for~ yttrium ! ingrowth). ' Activities are calculated on the-basis -- of appropriate Sr-89 decay and Y-90. mounts covered. with a 80.mg/cm 8aluminum absorber Separate
~
3-! E' are used for~ counting in a low background beta e'>unter. -- Uranium isotopic analysis _of sediment and soil' samples were performed.by alpha spectrometry' after l leaching and isolation 'of the uranium by an ion m' exchange chromatography' plus- mercury cathode i electrolysis, then electroplated onto a planchet.
- 3. Results and Conclusions A summary of data is presented in Table V.A.2. ,
i
- a. Sediment .,
A total of (8) ' samples were analyzed for gross alpha and gross beta. Results were comparable to .l previous years. A . total of eight (8) samples were analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 was detected, i d d I
k SECTION V - C DUQUESNE. LIGHT COMPANY (. 1989 Annual Radiological. Environmental Report V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil' Monitoring is required every 3 years and was not required in 1989) v (continued)
- 3. Results and Conclusion.(continued)
- a. Sediment (continued)
A total of eight (8) samples were analyzed by gamma [- spectrometry. Naturally occurring K-40, Ra-226 and-Th-228 was found in every sample and Be-7 was found in two samples. Small . amounts. of Cs-137. from i previous nuclear weapons. tests-were found in all {- river sediment samples- including upstream above Montgomery Dam- which are unaffected by plant r., effluents. Small amounts.of Co-58, Co-60 and Cs- .j ( 137 'were detected in .the Beaver Valley = Power Station discharge . area and are attributable to station -releases. .The activity found in .the station discharge area,is consistent with -station data of authorized radioactive discharges which were within limits. permitted by the NRC license. - i l 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-- T I' assessments, prior to authorizing radioactive discharges, are adequate and that the environmental ; monitoring program is sufficiently sensitive. 1 I'
.. ~.
SECTION V D DUQl'E.tNE L1 Gift COMPANY .i 1989 Annual Radiological Envitonmental Report i 1 V. ENVIRONMENTAL MONITORING 11 Monitorint. of Teederops and Tooderops i
- 1. Characterization of Vegetation and Fooderops l According to a survey made in 1985, there wete approximately 610 farms in Beaver County. The principal i source of revenue for the farms was in deiry products ;
which amounted to nearly $$,998,000. Revenues from ; other farm products were as followL: - Field crops. . . . . . . $2,013,000 Fruits . . . . . . . . . $ 169,000 l
}lotticulture and >
Mushrooms . .....$ 994,000 E i Heat and Animal Products. . . . . . . $1,638,000 g Vegetables and Potatoes. . .....$ Poultry Products . . . .$ 266,000 426,000 l1 W The total land in Beaver County is 218,600 acres. Approximately 134,592 acres are forested land and 6) 176 acres are pasture and crop land. ,
- 2. Sampling Program and Analytical Techniques
- a. Program ,
Representative samples of cattle feed are collected monthly from the nearest. dairy (Searight). See Figure 5.D.1. Each sample is analysed by Lamma spectrometry. The monthly samples are composited [ into a quarterly sample which is analyzed for Sr- ! ! 90. A land use census was performed August, 1989 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 V.D.1 for results. Foodcrops (vegetables) were collected at garden locations during the summer of 1989. Leafy vegetables, i.e., cabbage were obtained from Shippingport, Georgetown, Industry, PA, and l Weirton, W. All samples were analyzed for gamma ! emitters (including 1-131 by gamma spectrometry). l I
l
=
"n .
_, ca y FIGlillE 5.o.1 E! t .
- MournoncarDsn <
p- , i ke* l-- - 7 G+ faf O#/O l g , - Na_Ae , g l i
,e 03 1 g goRl"R % "
l 1 o V
.Bogo & \
E l tyr oog. g.Qtonqcrown R O N/9PvNGPCstr i Guam I R%, J q $$ l [ &R \s l"-a \ YM 44 " __, ? (x 5 sw v tu 5 eun-
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i N \ 3 err , tis
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- 0h 1
N c' E 1 b LEGEND: - ( 8 h - Vegetable Garden
~
h - Searight's Dairy Farm i Feedcrop O
- e I
ENVIR0f9fENTAL MONITORING FROGRAM N FEEDCROP AND FOODCRC? LOCATIONS , FIGURE 5.D.1 ) i i _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ . . _ _ _ . . _ _ _ _ _ , _
i SECTION V - D DUQUESNE LIGHT COMPANY . 1989 Annual Radiological Environmental Report ; TABLE V.D.1 l Closest Residence and Garden _in Each Sec' tor i Sector Closest Residence
- Closest Garden
- j 1 1,55 mi N 1.76 mi N 2 1.59 mi NNE 1.61 mi NNE :
3 0.42 mi NE 0.57 mi NE l 4 0.38 mi ENE 0.98 mi ENE t i 5 0.42 mi E 2.16 mi E ; 6 0.87 mi ESE 1.00 mi ESE ! 7 1.10 mi SE 1.25 mi SE ; 8 1.10 mi SSE 2.31 mi SSE l 1 9 1.40 mi S 2.16 mi S l 10 0.80 mi SSW 1.55 mi SSW ! 11 1.46 mi SW 1,67 mi SW , 12 1.46 mi WSW 1.46 mi VSW 4 13 2.27 mi V 2.27 mi W ! 14 2.77 mi WNW 2.84 mi WNW 15 0.91 mi NW 0.92 mi NW 16 0.91 mi NNW 1.10 mi NNW t
- Direction and Distance from Midpoint between Reactors !
t i 6 4 h i I .
~ SECTION V
- D DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report r V.- ENVIRONMENTAL MONITORING L .
D. Monitoring of Teederops and Tooderops (continued) h 2. Sampling Program and Analytical Techniques (continued)
- b. Procedures Gamma emitters, including 1 131, are determined by scanning a dried, homogenized sample with the gamma spectrometry system. A Ge(Li) detector is utilized with this system.
Strontium 90 --Alysis for feedstuff is performed by (- a procedur< aimi ce to that described in V.C.2. Radiciodi, L . ,1 131) is determined by [ radiochemis r; Stable iodide carrier is first i added .to . chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is
.[- dissolved in water, filtered and treated with sodium hypochlorite. The todate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into chloroform. It is then back-extracted as iodide into sodium 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 V.A.2. I a. Feed A total of twelve (12) samples were analyzed for I-131. No detectable concentrations were found. A total of four (4) samples were analyzed for Sr-
- 90. Small amounts of Sr-90 from previous nuclear weapons tests were found in all samples.
A total of twelve- (12) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was found in all samples, Be-7 was detected in five (5) samples. 80
I SECTION V D DUQUESNE 1.1GHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING D. Monitoring of Teederops and Tooderops (continued)
- 3. Results and Conclurions (continued)
- b. Tood A total of four (4) samples were analyzed for I*
131. No detectable concentrations were found. A total of four (4) samples were analyzed by gamma spectrometry. Naturally occurring K 40 was found in all samples.
- c. The data from food and feed analyses were g consistent with (or lower than) those obtained in g the pre-operational program. These data.confira that the Beaver Valley Power Station did not contribute to radioactivity in foods and feeds in 5 the vicinity of the site. B I
I I I I
SECTION V o E DUQUESNE LICHT COMPANY { 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's 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 V.A.1. This milk is analyzed for its radiciodine content calculated ! { as Iodine 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 August, 1989 is shown in Figure S.E.1. '
- 2. Sampling Program and Analytical Techniques
- a. Program Milk was collected from three (3) reference dairy farms (Searights, Brunton 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 pathway 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.E.2 and described below. Number of Milch Direction and Distance from Collection ' Site pairy Animals Midpoint between Reactors Period 35 Searight 42 Cows 2.2 miles SSW Jan. - Dec. 27 Brunton 83 Cows 7.3 miles SE Jan. - Dec. 39A Nichol 60 Cows 8.0 miles NE Jan. - Dec. 96 Windsheimer 30 Cows 10.3 miles SSW Jan. - Dec. - 61** Allison 35 Cows 3.3 miles WSW Jan. - Apr. SECTION Y = E DUQUESNE LIGHT COMPANY I 1989 Annual Radiological Environmental Report - V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued)
- 2. Sampling Program and Analytical Techniques (continued)
- a. Program (continued)
Number of Milch Direction and Distance from Collection Site Dairy Animals Midpoint between Reactors Period 69** Collins 6 Goats
- 3.5 miles SE Oct. g 98** Toxall 5 (llammond) 2 Goats
- 3.0 miles ESE Jan. - Oct.
101** Telesz 4 Goats
- 2.6 miles E Jan. - Feb.
102** Terry 4 Goats
- 3.3 miles SE Apr. - Nov.
103** Mosien 2 Goats
- 1.0 miles ESF. May - Dec.
104** Tordyce 2 Goats
- 2.50 miles NNbf May - Sept.
105** Ambrose 39 Cows 3.86 miles WSW Dec. 106** Conkle 39 Cows 3.75 miles WSW Feb. - Dec.
*Hilk Usage llome Only.
**llighest potential pathway dairies.
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s I SECTION V - E DUQUESNE LIGllT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued)
- 2. Sampling Program and Analytical Techniques (continued)
- a. Program (continued)
The sample from Searight Dairy was collected and analyzed weekly for radiolodine using a procedure with a high sensitivity. Samples from each of the 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 Spectrometry) and I-131 (high sensitivity analysis).
- b. Procedure Radiciodine (I-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low level beta counting system.
Gamma emitters a4a determined by gamma spectrometry of a one liter Marinelli container of milk. Strontium analysis of milk is similar to that of other foods (refer to V.C.2) except that milk samples are prepared by addition of Trichloracetic Acid (TCA) to produce a curd which is removed by filtration and discarded. An oxalate precipitate is ashed for counting.
- 3. Results and Conclusions A summary of data is presented in Table V.A.2.
A total of one hundred sixty-five (165) samples were analyzed for I-131 during 1989. All I-131 activities in milk were below the minimum detectable level. 86-
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1; l SECTION V E DUQUESNE LfGHT COMPANY j 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued) i
- 3. Results and Conclusions (continued)
A total of one hundred thirty two (132) samples were analyzed for St 89 and St-90. No Sr 89 was detected. ; Sr 90 levels attributable to previous nuclear weapons tests were detected in one hundred ' twenty nine (129) samples and were within the normally expected range. A total of one hundred thirty two (132) samples were analyzed by gamma spectrometry. The predominant isotope detected was naturally occurring K-40 and was found in all samples. Cs-137 which is attributable to previous a nuclear weapons tests was detected in two (2) samples, g: 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. ll . II l w ll I l e h
SECT!ON V - F DUQt'ESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring [ 1. Description of Regional Background Radiation Levels ag Sources l 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 I deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the I Ohio River Valley and along major tributary streams. Based on surveys reported in previous annual reports, I exposure rates ranged from 6-12 VR/hr. Results for 1989 indicated that background radiation continued in this range. I 2. Locations & Analytical Procedures j Ambient external radiation levels around the site were l measured using thermoluminescent dosimeters (TLDs). In 1989 there were a total of forty-four (44) off-site I environmental TLD locations. The locations of the TLDs are shown in Figures 5.F.1 thru 4. Thirteen (13)
. locations also have QC Laboratory TLDs. Both laboratories use calcium sulphate dysprosium, (CaSO.:Dy) in teflon matrix.
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SECTION Y F DUQUESNE LIGHT COMPAbT 1989 Annual Radiological Envirenmental Report V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring (continued),
- 2. Locations 6 Analytical Procedures (continued)
The calcium sulfate (CaSO. Dy) TLDs were annealed shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit between the field location and the laboratory was corrected by annealing control dosimeters shortly before the field dosimeters were removed from the field location, 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. In addition to TLDs , Pressurized Ion Chambers (PIC) l provide continuous integrating monitoring. Sixteen PICS 5 (Sites 1-16) are part of the Sentri 1011 Radiation Monitoring System which is a microcomputer based data g acquisition system. Data from the stations are sent at g regular intervals to the Central Processing Unit where integrated doses are calculated. In addition there are four PICS which are AC Radiation Monitors. These are inspected weekly for integrator readings. The locations - of the PICS are shown in Figure 5.F.5.
~
- 3. Results and Conclusions Data obtained with the contractor TLD (CaSO.:Dy in g teflon) during 1989 are summarized in Table V.A.2,. and g the quality control TLD results are listed in Table III.1. Results for the PICS are listed in Table V.F.1.
The annual exposure rate of all off-site TLDs averaged 0.16 mR/ day in 1989. As in previous years, there was some variation among locations and seasons as would be expected. In 1989, ionizing radiation dose determinations from TLDs averaged approximately 58 mR for the year. This is comparable to previous years. There was no evidence of anomalies that could be attributed to the operation of the Beaver Valley Power Station. The TLDs confirm that E changes from natural radiation levels, if 'any, are B neglible. I
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l SEC*EION Y - F DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report TABLE V.F.1 Pressurized Ion Chambers - Results i Distance and Direction l from Midpoint Average ; Site Location Between Reactors hRiday] l 1 Industry Hill 0.5 mi N 0.196 2 Industry - Rt. 68 0.9 mi NNE 0.208 ) 3 Industry 2.25 mi NE 0.194 4 Cooks Ferry 0.5 mi ENE 0.212 5 Shippingport Bridge South 0.45 mi E 0.206 r 6 BVPS Entrance 0.4 mi ESE 0.224 7 Unit (12 Leydown 0.3 mi SE 0.210 8 Birdhill Road 0.9 mi SSE 0.184 9 Past DLCO Microwave 0.35 mi S 0.224 ', 10 DLCO Microwave 0.35 mi SSW 0.210 11 Meyer's Farm 1.45 mi SW 0.230 12 J & L Steel Tie 0.75 mi WSW 0.214 13 F. P. Microwave 1.5 mi W 0.170 14 Midland Substation South 0.6 mi WhV 0.222 15 Midland Substation North 0.75 mi hV 0.230 , 16 Sunrise Hills 1.1 mi NhV 0.214 AC-201 Raccoon Municipal Building 2.4 mi SE 0.248 AC-202 Kennedy's Corners 2.0 mi NE 0.239 Z-054 Hookstown Substation. 2.9 mi VSW 0.241 Y-028 J&L 1.3 mi hV 0.203 1 SECTION V - G DUQUESNE LIGHT COMPANY l 1989 Annual Radiological Environmental Report ! V. ENVIRONMENTAL MONITORING G. Monitoring of Fish
- 1. Description During 1989, fish col'lected for the radiological monitoring program included carp, catfish, sheephead and walleye.
- 2. Sampling Program and Analytical Techniques
- a. Program Fish samples are collected semi-annually in the New I
Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam, The edible portion of each different species caught is analyzed by gamma I spectrometry. Fish sampling locations are shown in Figure 5.G.I.
- b. Procedure '
A sampls is prepared in a standard tared 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a Ge(Li) detector.
- 3. Results and Conclusions A summary of the results of the fish monitoring data is provided in Table V.A.2.
A total of ten (10) samples were analyzed by gamma spectrometry. The only gamma emitter detected was I naturally occurring K-40 which was found in all samples. This indicates that the operation of the Beaver Valley Power Station has not resulted in radioactivity in fish in the Ohio River. 4 Y I
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/*9 Upstream - Montgomery Dam ENVIRONMENTAL MONITORING FROGRAM EI g FISH SAMPLING LOCATIONS .
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SECT 20N V H DUQL'ESNE L2GHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORINO H. Monitoring of Surface. Drinking. Well' Vaters and Precipitation
- 1. Description of Water Sources 1
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 j liquid effluents. Ohio River water ts- a source of water for some towns both upstream and downstream of the Beaver Valley Power Station. sitc. 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 industries 1 in Midland, as well as others downstream use river water for cooling purposes. Some of these plants 'also have private treatment facilities for plan. sanitary water. Ground water occurs in large volumes .in the gravel , terraces which lie along the -river,. and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per i minute (spm) with occasional wells yielding up'to 60 t gpm. - In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. -Normal annual precipitation for the area is.36.20 inches based on 1958 to 1987 data collected at the Pittsburgh International Airport. - H 5 F 98.. ( I
e SECTION V
- H DUQUESNE LIGHT COMPANY 1969 Annual Radiological Environmental Report l Y. ENVIRONMENTAL MONITORING (continued)
H. Monitoring of Surfact. Drinking. Well' Waters. and Precipitation (continued)
- 2. Sampling and_ Analytical Techniques ;
- a. Surface (Raw River) Vater The sampling program of river water includes six (6) sampling points along the Ohio River. Raw ,
water samples are normally collected at the East !
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Liverpool (Ohio) Water Treatment Plant [ River Mile 41.2) daily and composited into a monthly sample. - Veekly grab samples are taken from the Ohio River at the discharge following locations: upstream of , Montgomery Dam [ River Mile 31.8); from Shippingport Station Decommissioning Project [ River Mile 34.8); and near the discharge from the Beaver Valley Power Station [ River Mile 35.0). Two automatic river , water samplers are at the following locationst , Upstream of Montgomery Dam [ River Mile 29.6); and at J&L Steel's river water intake [ River Mile g : 36.2). The automatic sampler takes a 20-40 ml sample every 15 minutes and .. s collected on a g' weekly basis. The weekly grab samples and automatic water samples are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each - sample point. The monthly composites are analyzed for gross alpha, gross beta, and gamma emitters. The 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.H.1.
- b. Drinking Water (Public Supplies)
Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Water Treating
- Plants. An automatic sampler at each location collects 20-40 m1 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 spectrometry. The weekly samples are elJo analyzed for I-131. I
SECTION V o H DUQUESSE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING L . H. Monitoring of Surface. Drinking. -Well Waters, and Precipitation (continued) 2.- Sampling and Analytical Techniques (continued)
- b. Drinking Water (Public Supplies) (continued)
{: Monthly- composites of the weekly samples are r 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.H.1. (.
- c. Ground Water f-( Grab samples were collected each quarter from each of four (4) well locations (see Figure 5.H.1) within four (4) miles of the site. These locations
( are One (1) well at Shippingport PA '( One (1) well at Meyer's Farm (Hookstown, PA) One (1) well in Hookstown, PA One (1) well in Georgetown, PA { Each ground water sample is analyzed for gross alpha, gross beta, tritium,- and- by gamma spectrometry,
- 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 siamples 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.H.1.
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Q ty GEORCETOWN. PA ENI N N N-N M EAT 57 h ns [A wEIRT0w, wV OM L W M/OY8 l IDCATIONS - WELLS, SURFACE WATER, DRINKING N ; { WATER AND PRECIFITATION v'
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SECTION V - H DUQL'ESNE LIGHT. COMPANY ~ 1989 Annual Radiological Environmental Report - V. ENVIRONMENTAL MONITORING H. Monitoring of Surface, Drinking.- Vell ' Vaters, and Precipitation (continued) I
- 2. Sampling and Analytical Techniques (continued)
- e. Procedures Gross alpha and gross beta activities are determined first by. evaporating one- liter of the h sample on a hotplate. The residue is mounted and dried on a 2 inch stainless steel planchet. The sample is counted in a low background, gas flow proportional counter. Self-absorption corrections
{ are made on the basis of sample weight. r Gassa analysis is performed on water sample by L loading one. liter of sample into a one . liter marinelli container and counting on a Ge(Li) gamma spectrometry system. .
.I Strontium 89 and 90 are determined on water samples l~
by a procedure similar.to that described in V.C.2 except that the leaching step is eliminated. Cobalt-60 is determined with a sensitivity of 1 pCi/1 by evaporating 2 liters of sample on a
'[ hotplate and transferring the residue to a 2 inch planchet. The planchet is counted on a Ge(Li) spectrometry system.
Tritium is determined in water samples by converting 2 ml of the sample to hydrogen and r counting the activity in a 1 liter low level' gas 1_ counter which is operated in the proportional range in anti-coincidence mode, f Radiofodine (I-131) analysis in water was normally performed using chemically prepared sarples and analyzed with a low-level beta counting system. {-
\. 3. Results and Conclusions A summary of results of all analyses of water samples f '
(surface, drinking, ground and precipitation) are provided by sample type _and analysis in Table V.A.2. These are discussed below. l
-102- !
SECTION V - H DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Menitoring of Surface. Drinking. Well Waters, and l Precipitation (continued) W
- 3. Results and Conclusions (continued)
- a. Surface Water A total of seventy two (72) samples were analyzed for gross alpha and gross beta. All alpha results were within the normal range. Positive bete results above preoperational levels were detected E in the BVPS discharge area and are attributable to . E station releases. The beta activity found jn the station discharge area is consistent with station data of authorized radioactive discht.rges and were within limits permitted by the NRC license.
l A _ total of twenty-four (24) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-58 and Co-60. Positive tritium results were detected in the BVPS discharge g area and are attributable to station releases. All g other sampics taken upstream and downstream were within pre-operational levels. The activity found g in the station discharge area is consistent with station data of authorized radioactive discharges I and were within limits permitted by the NRC license. A total of seventy two (72) samples were analyzed by gamma spectrometry. No gamma emitting - radionuclides were detected. - I
.I I .
I
-103-I
SECTION V - H DUQUESNE MGHT COMPANY ~ 1989 Annual Radiological Environmental Report c V. ENVIRONMENTAL MONITORING H. Monitoring of Surface. Drinking. Well' Vaters, and Precipitation (continued)
- 3. Results and Conclusions (continued)
- b. Drinking Vater A total of thirty six (36) samples were analyzed I for gross alpha and gross beta. All results were within a normal range.
A total of twelve (12) samples were analyred 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 were detected. The H-3 data were within the pre-operational range indicative of normal environmental levels. A total of another one hundred fifty five (155) samples were analyzed by gamma spectrometry. No gamma emitting radionuclides were detected. A total of one hundred fifty-five (155) samples were analyzed for I 131 using a highly sensitive technique. Trace levels of I-131 were measured in I eight (5) 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. The results may be attributed to expected variability in the analyses results of I very low levels of activity.
- c. Vell Water A total of sixteen (16) samples were each analyzed for gross alpha, gross beta. H3 and by gamma spectrometry. No alpha activity was detected in i' any of the samples. The gross beta and H-3 results are within pre-operational ranges. No gamma emitting radionuclides were detected.
-104-
SECTION V - H DUQUESNE LIGHT COMPANY I 1989 Annual Radiological Environmental Report V.- ENVIRONMENTAL MONITORING (continued)' H. Monitoring of Surface, ' Drinking, Well Waters, and Precipitation (continued)
- 3. Results and Conclusions-(continued)
- d. Precipitation A total of thirty-two (32) samples were analyzed for gross beta. All results were within a normal-l-
=
range. A total of twelve'(12) samples were analyzed for H-3, Sr-89 and Sr-90. Three (3) posi W e . tritium results- were detected Lwhich were within normal levels and no Sr-89 or Sr-90 was detected. A total of thirty-two (32) samples were analyzed by .
. gamma spectrometry. Naturally occurring Es .7 was .
detected in : seventeen (17) samples and K-40 was - detected in two (2) samples.
- e. Summary The data from water analyses demonstrates tl'at the Beaver Valley Power Station did not contribute a significant increase. of radioactivity in local river, drinking,' wull 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 station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.
Further, _ the actual detected concentration (averaged over. a year) attributable to Beaver Valley Power Station, was only 0.213% of' the 3: Maximum Permissible Concentration' allowed by the E Federal Regulations for water discharged to the Ohio River. The.0hio River further reduced- this concentration by' a factor of ~ 600 prior to its - potential use by members of the public. l
-105-
)
SECTION V - 1 DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report r V. ENVIRONMENTAL MONITORING L , I. Estimates of Radiation Dose to Man [ 1. Pathways to Man - Calculational Models The radiation doses to man las a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using NRC computer codes X0QD0Q2, GASPAR, and 1ADTAP. Dose factors listed in the ODCM- , were used to calculate doses to maximum individuals from radioactive noble gases in discharge plumes. ' Beaver Valley offluent data, based on sample analysis in accordance with the schedule set forth in Appendix A of the BVPS license, were used as the radionuclide activity-input. ! Each radionuclide' contained in- the Semi-Annual Radioactive Effluent - Release Report (noble gases, particulates, radiciodinei and tritium) were included as : source' terms when they were detected above the' LLD I values. All LLD values reported by Beaver Valley Power Station are equal-to or lower than those required by the Technical Specifications. All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. When the activity of noble gas was below detection ' sensitivity, either the inventory based on its HDL or an 3 appropriate but conservative ratio Eto either measured ; activity 'of Kr-85 or Xe-133 was used. Meteorological j data collected by the Beaver _ Valley Power' Station c Meteorology System was used as input to X0QD0Q2 which in. ; turn provided input for GASPAR.' 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, q i i I s
-106-l
v. SECTION V - ! DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 1. Estimates of Radiation Dose to Man (continued').
- 1. Pathways to Man - Calculaticua Models (continued) i 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 g tabulated and used as the radionuclide activity input 3-term in 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 - oth6r input to LADTAP are obtained from' the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109. Pathways, which were evaluated, - are drinking water, fish consumption, shoreline recreation, swimming, and boating.
- 2. Results of Calculated Radiation Dose to Man - Liquid Releases J
- a. Individual Dose The doses which are calculated by the model described above~ are to a- hypotheticali '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 used to . calculate .the maximum exposure. A breakdown of doses by pathway and organ is provided in Table V.I.1. for' the . maximum individual. Included in this table is a breakdown of a typical dose to individuals from- y natural radiation exposure. The results of ! calculated radiation dose to the hypothetical real 3=; individual are compared to BVPS annual limits in [ Table V.I.2.
- 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 l specific; Unit 1 and Unit 2 have individual i.e., (not combined) dose limits. Therefore, the annual limits listed in Table V.I.2 were derived by 4 multiplying the individual Technical Specification reactor limits by a factor of two (2).
-107-1
- - w 1 ,
v TABLE V.I.1 Radiation Dose to Maximum Individual
- mres/yr5 Beaver Valley Power Station - Liquid Releases y 0
-8 MAXIMUM USAGE WHOLE PATHWAY GROUP FACTOR SKIN ORGAN THYROID BONE BODY Fish Consumption Adult 21.0 kg N/A 0.000615 0.0000552 0.000187 0.000270 (Liver) g c
Drinking Water Infant 510 liter N/A 0.00344 0.00323 0.0000338 0.00327 g (Lung) , E Shoreline Activities Teen 67 hr. 0.000110 - - - 0,0000935 e ilfE 2M d TOTAL MREM 0.000110 0.00344 0.00323 0.000286 0.00327 E S' MAXIMUM (Teen) (Infant) (Infant) (Teenager) (Infant) e "' INDIVIDUAL (Lung) pC TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE gn Ambient Casma Radiation: 69 d Nh g Radionuclides in Body :- 28* ,.
- 4" I-Global Fallout o"
TOTAL aren 101 y A
- Located at Midland Drinking Water Intake- 4 b Total liquid releases are from Site (combined Units I and ?) @
U Adult is the critical group for bone with a dose of 0.0000363 arem/yr. 5
~
d - ~ Pre-operational average ambient gamma radiation
- National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of ,
Ionizing Radiation," BEIR Report, 1980
SECTION Y - I DUQUESNE LfGHT COMPANY
- I-1989 Annual Radiological Environmental Report -
TABLE V.I.2 = Results of Calculated Radiation Dose to Man' E. Beaver Valley Power Station - Liquid Releases E Maximum g Exposure g_ Hypothetical BVPS Annual- Percent of Real Individual Limits Annual mrem mrem Limit-TOTAL BODY Adult 0.00233- 6.0 0.039 Teen 0.00142 6.0 0.024 Child 0.00229 6.0 0.038 Infant 0.00327 6.0 0.055 ANY ORGAN Adult 0.00291 20.0 0'.015 (Lung) ; Teen 0.00186 20.0 0.009 (Lung) 1 Child 0.00257 20.0- 0.013- ' (Lung) Infant 0.00344 20.0 0,017-(Lung) Maximum Total Body Dose - Capsule Summary . 1 mrem i 1989 Calculated 0.00327 ' Final Environmental Statement 3.5 Highest Organ Dose un g i 1989 Calculated 0.00344 Final Environmental Statement 4.7 IR I ; I'
-109-I
SECTION V I DUQUESNE LIGHT COMPANY 1989 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING . I. Estimates of Radiation Dose to Man (continued)
- 2. Results of Calculated Radiation Dose to Man - Liquid Releases (continued)
- c. Population Dose The 1989 calculated dose to the entire population-of almost.4 million people within 50 miles of the plant was:
Largest Isotope Man-Millirem Contributors TOTAL BODY 113 H-3 110 mrem Fe-55 1.95 ares Co-60 0.56 mrem THYROID -110 H-3 110 mrem
- 3. Results of Calculated Radiation Dose to Man - Airborne l Releases The results of calculated radiation dose to the maximum exposed individual for BVPS airborne radioactive effluents during 1989 are provided in Table V.I.3, The. 1 doses include.the contribution of all pathways. A 50- i mile population dose is also calculated and provided.in Table V.I.3. H-3 is the primary radionuclide contributions to these doses.
The results are' compared to the BVPS annual limits in Table V.I.3. As in the liquid discharge limits, the gaseous effluent limits are reactor specific; i.e., Unit 1 and Unit 2 have individual (not combined) dose limits. Therefore, the annual limits listed in Table V.I.3 were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2). The results show compliance with the BVPS annual limits. I i 1 1
-110-
SECTION V - 1 DUQUESNE LIGitT COMPANY < 1989 Annual Radiological Environmental Report , V. ENVIRONMENTAL MONITORING i
- 1. Estimates of Radiation Dose to Man (continued) ._
- 4. Conclusions - (Beaver Valley Power Station) ;
Based upon the estimated dose to-individuals from the ' natural background radiation exposure in Table V.I.1., ; the incremental increase in total body dose to the 50- i mile population (4 million people), from -the operation of Beaver Valley Power Station - Unit No. 1 and No. 2, {y is less than 0,0003% of the annual background. -! The calculated doses to the public from the operation of Beaver Valley Power Station - Unit No. I and No. 2,- are l below BVPS annual limits and resulted in only a small' .l incremental dose'to that which . area residents already . received as a result of natural background.. The doses-- I constituted no meaningful risk to the public. 4 Il 4 i If I , I I1 I 4 1
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TABLE V.I.3 Results of Calculated Radiation Dose to Man (1989) Beaver Valley Power Station - Airborne Radioactivity . sz
~~
50-MILE PERCENT OF POPULATION DOSE MAXIMUM EXPOSURE BVPS ANN AL LIMIT " aren ANNUAL LIMIT man rem ORGAN INDIVIDUAL arem
~
c 0.127 30 0.42 0.871 g TOTAL BODY SKIN 0.166 30 0,55 1.22 h 5 LUNG 0.139 30 0.46 0.964 "o
;?E 0.131 30 0.44 0.937 gg
,L THYROID S 12 C gm XC 0
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I I I I Ii APPENDIX 1 I I. . I I] . Contractor Laboratory I l EPA Interlaboratory I t i I: ; Comparison Program I I I ' I g, I ;
- s. _
_ m -- w t 1 .t i DUQUESNE llGitT COMPANY- 19ft9 US EPA INTERIABORATURY COMPARISON PROGRAM 1989 (Page I of 3) EPA Date TI Malled Date EPA . EPA TI Norm Dev. ** Warning issued Results Media Nuclide Resultsta) Results(h) (Known) * *
- A ction Preparation Results 04/17/89 W aer Ra-226 3.50 i 0.50 3.40 i 0.00 -035 12/16/88 02/09/89 -i.69 Ma-228 1030 i 1.50 8.83 1 0.8 I Waer Sr-89 40.00 1 5.00 37.00 1 2.65 -1.04 01/06/89 03/07/89 05J01/89 Sr-90 25.00 i 1.50 26.00 i 2.00 1.15 02/17/89 04/28/89 W aer Gr-Alpha 8.00 1 5.00 8.00 i 1.00 0 00 01/20/89 6.00 1 0.00 0.69 Gr-Beta 4.00 1 5.00 03/14/89 05/12/89 Waer Cr-51 235.00 1 24.00 245.67 i 11.72 0.77 02/10/89 1 2.67 i 0.92 Co40 10.00 1 5.00 I33 Zn45 159.00 i 16.00 . I8133 i 5.51 2.42 * *(c)
Ru-106 178.00 1 18.00 191.00 i 9.85 1.25 Cs.134 10.00 1 5.00 1033i 0.58 0.12 Cs-137 10.00 1 5.00 13.67 1 0.58 1.27 Wacr 1-131 106.00 11.00 98.67 1 0.58 -1.15 02/17/89 03/22/89 05/12/89 03/22/89 05/01/89 W aer H-3 2754.00 i 356.00 2866.67 i 251.66 0.55 02/24/89 05/2N89 06/16/89 Wsw Ra-226 4.90 1 0.70 5.07 i 0.29 0.41 03/10/89 -135 Ra-228 1.70 1 030 1.47 1 0.29 06/08/89 07/10/89 Air Filter Gr-Algdia 21.00 1 5.00 28.67 i 1.15 2.66 "(d). 03/31/89 5.00 65.67 i 1.53 1.27 Gr-Bets 62.00 1 Sr-90 20.00 i 1.50 19.67 2.08 -038 Cs-137 20.00 i 5.00 18.00 i 1.00 0.69 07/28/89 Lab Perf Gr-Alpha 29.00 1 7.00 21331 231 -f.90 ' 04/18/89 06/21/89 3.47 i 0.23 -0.12 Sample A Ra-226 3.50 1 0.50 Ra-228 3A01 0.50 3.60 1 0.10 0.00 Sampic B Gr-Beta 57.00 i 5.00 $3.001 3.61 -139 Sr-89 8.00 i 5.00 8.00 1 0.00 0.00 Sr-90 8.00 i 1.50 7.67 i 0.58 -038 Cs-134 20.00 1 5.00 19.67 i 1.53 -0.12 Cs-137 20.00 5.00 20.00 1 2.65 0.00
- Footnotes at end of table.
t DUQUESNE I.lGHT COMPANY- 19R9 US EPA INTERLABORATORY COMPARISON PR(XiRAM 1989 (Page 2 of 3) EPA Date TI Malled Date EPA EPA TI Noran Dev. " Warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) '" Action 01/28/89 06/21/89 08/07/89 MA Sr-89 39.00 1 5.00 36.671 1.15 -0.81 - Sr.90 55.00 1 3.00 5633 1.53 0.77 Cs-137 50.00 1 5.00 53331 2 31 1.15 K 1600.00 i 80.00 1760.00 i 113.58 3.46 "*(c) OW.3/89 07/06/89 08/14/89 W aer Sr-89 6.00 i 5.00 633i 0.58 0.12 Sr-90 6.00 i 1.50 6331 0.58 038 06/09/89 07/19/89 08/28/89 W eer Ba.133 49.00 1 5.00 33.00 i 3.61 -5.54 "*(f) Co40 31.00 i 5.00 30.00 1 2.65- 0.35 2n-65 165.00 i 17.00 165.33 1 0.58 0.03 Ro-106 128.00 13.00 113.67 i 17.50 -1.91 Cs-134 39.09 5.00 34.00 1 2.65 -1.73 Cs-137 20.00 i 5.00 22.00 i 3.61 0.69 06/23/89 07/19/89 08/14/89 W aer H-3 4503.00 1 450.00 4466.67 i 152.75 -0.14 08/25/89 12/19/89 Air Filter Gr-alpha 6.00 1 5.00 833i 0.98 0.81 Cs-137 10.00 i 5.00 12.00 i 1.00 0.69 09/22/89 10/19/89 11/13/89 Waer Gr-Alpha ' 4.00 1 5.00 5.00 i 0.00 0.35 Gr-Beta 6.00 1 5.00 8.00 1 0.00 0.69 10/06/89 12/19/89 Wacr Be-133 59.00 i 6.00 51.00 i 436 -2.31 "(g) Co-60 30.00 1 5.00 30.67 1 2.08 . 0.23 ~ Zn45 129.00 i 13.00 12833 1 2.89 -0.0) Ru-106 161.00 i 16.00 139.00 i 15.72 -238 "(g) Cs-134 29.00 i 5.00 23.67 1 1.15 -1.85 Cs-137 ' 59.00 1 5.00 61.67 i - 1.53 0.92 10/20/89 12/19/89 W aer H-3 3496.00 i 364 00 343333 i 57.74 -030 I II/10/89 01/30/90 Waer - Ra'226 8.70 i 1.30 - 8.47 1 0.49 -031 i ' Ra-228 930i 1.40 8.57 i 1.46 -0.91 l'ootnotes at end of table. M M M M M: M.
e -. t J--~T I . > I)UQUESNE LIGIIT COMPANY - 39R9 US EPA INTERLABORATORY COMPARISON PROGRAM 1989 (Page 3 of 3 Footnofes: (a) Average i experimental sigma. (b) Expected laboratory precision (I sigma. I determinatkm). (c) De three Zn-65 measurements were 184.175 and 185 pCi/ liter. These were measured on three detectors using the same aliquot. %c other reported resuhs (t * .Gw60J Ro 106.Cs-134.Cs-137) were all within two standard deviations of the EPA results. His would indicate that the delution made was correct (cacept that pmsibly the Zn 65 was not well mixed). Other parameters were investigated. The branching intensity. decay facior, and detection efficicncies were checked. Since one of the Ca>60 gamma ray - energies is only 60 KcV frorn 2n-65. the detector efficiencies must be correct. There is no obvmus reason for the deviatkm. Another aliquot will be prepared frtwn the ongmal solution and will be counted. (d) The EPA deposits activity on the filter over a small diameter (nearly a point source) whereas our calibration is based on a deposit nearly 2 inches in diameter. In order to correct to point source geometry our gractice has been to divide ocs results by 1.2. We neglected to do it on this test. (c) There is no apparent reason why the potassium was high. Three separate detectors were used and the K.40 value for each was correcdy divided by 0.86 to convers to potassium in mG/ liter. (f) There is no apparent reason why Ba-133 was low by 5.54 standard deviation while the other isosopes were wi-:hin i2 starmhrd deviations. The detector efficiencies and Ba-133 branching intensities were checked and found to be cmect. On 10/31/89. 300 ml of the original. undiluted sampic was counted giving 43.9 i 5.8 Cill of Ba-133 (g) His EPA samples was counted in two geometnes;one in diluted stage the other undiluted. There was no significant difference. Comparing detector efficiencies between two annual sets did not reveal any significant difference. 'Thus there is no apparent reason why our resuhs differed as much as they did. me.
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spaud c . r i I i APPENDIX ll 1 I 4 I QC Laboratory i I EPA Interlaboratory l l 1 Comparison Program i l i I l
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h.) Appendix A Interlaboratory Comparison Program Results g i
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I i i NOTE: TIML participates in intercomparison studies administered by U.S.. EPA . Environmental Monitoring Systems Laboratory, Las Vegas. Nevada. The i results are reported in Appgndix A. Also' reported are results of in- ' house spikes and blanks. Appendix A is updated twice-a ear and' the y complete Appendix is included in January and July monthb reports only. : Please refer to January and July Reports for information. . January 1990, h-A-1 I
s + en Appendix A- ' Interlaboratory Comparison Program Results 1 l Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison ' (crosscheck) programs since the formul ation : of its quality control ~ program Lin December 1971. These ; are operated by agencies- which supply environmental-type samples (e.g., programs milk or ; water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program _is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations 'of specified radionuclides-and report them to the issuing -agency. Several months later, the agency reports - I the known values to the~ participant laboratories and specifies : control limits. a Results consistently higher or lower than the known values or outside the control l limits indicate a need to check the instruments or procedures used. 3 The results in Table A-1 were obtained-through participation'in the environmental sample crosscheck program for milk, -water, air filters, and - food samples Jduring the period January 1986 through November,1989. This -program 'has been conducted i by the U.S. ' Environmental Protection Agency Intercomparison 'and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Labora-tory -Las Vegas, Nevada. The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980,1984, and 1985-1986 through partici-pation in the Second, Third, Fourth, Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships- listed in , i 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 B lists acceptance criteria for " spiked" samples. Addendum to Appendix A provides explanation for out of limit results. ; 1 A-2
Appendix A - I-nterlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly.Hazleton Environmental Sciences) I has participated in interlaboratory comparison (crosscheck) programs since the foraulation of its quality control program in December 1971. These programs ar.' operated by agencies which supply environmental-type samples.(e.g., milk or water) containing concentrations of radionuclides known- to the issuing agency a but not to participant laboratories. The purpose-of such a program is to provide g an independent check on the laboratory's analytical procedures and to alert it to any possible problems, i Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several~ months later, the agency reports the known values to the participant laboratories and specifies control limits.: Results consistently higher or lower than the known values or outside the control t limits indicate a need to check the instruments or procedures used. The results in Table A-1 were obtained through participation in the environmental-sample crosscheck program for milk, water, air filters, and food' samples during the period January 1986 through January,1990. This program has been conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration l1 . Section, Quality Assurance Branch, Environmental Monitoring and -Support Labora- _E l tory. Las Vegas, Nevada. Ej The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980, 1984, and 1985-1986 through partici-pation in the Second, Third, Fourth, Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed. l 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. 3 Attachment B lists acceptance criteria for " spiked" samples. Addendum to Appendix A provides explanation for out of limit results. l-e A-2
G ~ Table A-1. U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1986 through 1989.a I Con' centration in pC1/l b I Lab Sample Date TIML Result EPA Resultd l Code Type Collected Analysis 12cc Is, N=1 Control Limits ! I STF-447 Food Jan 1986 Sr-89 24.312.5 25.025.0 16.3-33.7 Sr-90 17.310.6 10.021.5 7.4-12.6 I-131 22.722.3 20.0t0.6 9.6-30.4 I Cs-137 16.310.6- 15.025.0 6.3-23.7-K 927246 9501144 701-1199 i STW-448 Water Feb 1986 Cr-51 45.013.6 38.015.0- 29.3-46.7 Co-60 19.721.5 18.025.0 9.3-26.7 Zn-65 44.013.5- 40.015.0 31 .3-4 8 .7 ' Ru-106 <9.0 0.025.0 0.0-8.7 Cs-134 28.322.3 30.025.0 21.3-38.7 Cs-137 23.710.6 22.025.0 13.3-30.7 STW-449 Water Feb 1986 H-3 5176148 5227t525 4317<6137 STW-450 Water Feb 1986 U total 8.010.0 9.026.0 0.0-19.4 STM-451 Milk Feb 1986 I-131 7.0t0.0 9.0t6.0 0.0-19.4 f STW-452 Water Mar 1936 Ra-226 Ra-228-3.810.1 11.010.5 4.120.6 3.0-5.2 12.4*1.8 9.2-15.5 : STW-453 Water Mar 1986 Gr. alpha 6.720.6 15.015.0 6.3-23.7 ~! Gr. beta 7.320.6 8.015.0 0.0-16.7 j l STW-454 Water Apr 1986 I-131 7.020.0 9.016.0 0.0-19.4-STW-455 Water Apr 1986 y 456 (Blind) Sample A Gr. alpha 15.011.0 17.025.0 8.3-25.7 Ra-226 3.120.1 2.920.4 2.1-3.7 l Ra-228- 1.5*0.2 2.0*0.3 1.5-2.5 Uranium 4.720.6 5.026.0 0.0-15.4 : Sample 8 Gr. beta 28.711.2 35.015.0 26.3-43.7 Sr-89 5.720.6 7.015.0 0.0-15.7 ' Sr 7.0t0.0 7.021.5 4.4-9.6 Co-60 10.711.5 10.025.0 1.3 18.7 Cs-134 4.021.7 5.025.0 0.0-13;7 ; Cs-137 5.3t0.6 5.015 0
. 0.0 13.7 A-3 l 1
l l f l Table A-1. (continued) , Conceritration in pCi/lb l.ab Sample Date TIML Result EPA Result 0 Code Type Collec ted Analysis t20C 15, N=1 Control Limits STAF-457 Air Filter April 1986 Gr. alpha Gr. beta 13.7t0.6 46.3t0.6 15.0i5.0 47.0t5.0 6.3 23.7 I 38.3-55.7 Sr-90 14.7t0.6 18.011.5 15.4-20.6 E Cs-137 -10.7t0.6 10.0t5.0 1.3-18.7 E STU-458 Urine April 1986 Tritium 4313170 4423t189 4096-4750 ETW-459 Water May 1986 Sr-89 4.3t0.6 5.015.0 0.0-13.7 Sr 90 5.0t0.0 5.0tl.5 { 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.3t0.6 8.015.0 0.0-16.7 Gr. beta 11.311.2 15.015.0 6.3-23.7 STW-461 Water June 1986 Cr-51 <9.0 0.015.0 0.0-8.7 Co-60 Zn-65 66.0tl.0 87.3tl.5 66.0t5.0 86.0t5.0 57.3-74.7 77.3-94.7 m j Ru-106 39.7t2.5 50.015.0 41.3-58.7 E Cs 134 49.3t2.5 49.0t5. 0 40.3-57.7 Cs-137 10.3tl.5 10.0t5.0 1,3-18.7 STW 462 Water June 1986 Tritium 3427t25 3125t361 2499 3751 I STM-464 Milk June 1986 Sr-89 <1.0 0.0t5.0 0.0-8.7 Sr 90 15.3t0.6 16.011.5 13.4-18.6 g I-131 48.3t2.3 41.0t6.0 30.6-51.4 Cs-137 43.7tl.5 31.0t5.0 22.3-39.7 K 1567t114 1600t80 1461-1739 STW-465 Water July 1986 Gr. alpha 4.7t0.6 6.0t5.0 0.0-14.7 STW-467 Water August 1986 Gr. beta I.131 18.7tl.2 30.3*0.6 18.015.0 45.0t6.0 9.3-26.7 34.4-55.4 l STW-468 Water August 1986 Pu-239 11.3t0.6 10.1tl.0 8.3-11.9 STW-469 Water August 1986 Uranium 4.0t0.0 4.0t6.0 m e 14.4 STAF-470 Air Sept 1986 Gr. alpha 19.3tl.5 22.0i5.0 13.3-30.7 471 Filter Gr. beta 64.012.6 66.0t5.0 57.3-74.7 472 Sr-90 Cs-137 22.0il.0 25.7tl.5 22.0i5.0 22.0i5.0 19.4-24.6 13.3-30.7 l STW-473 Water Sept 1986 Ra 226 Ra-228 6.0t0.1 8.7tl.1 6.li0.9 9.1tl.4 4.5-7.7 6.7-11.5 l A-4 I l' 4 - y
s - Table A 1. (continued). Concentration in pCi/lb c Lab k ple Date TIML Result EPA Resultd L Code Type Collected Analysis 15 N=1 1200 Control Limits f STW-474 Water Sept 1986 Gr. alpha 16.3i3.2 15.015.0 6.3-23.7 L Gr. beta 9.011.0 8.015.0 0.0-16.7 STW-475 Water Oct 1986 Cr-51 63.315.5 59.015.0 50.3-67.7 ( Co-60 31.012.0 31.015.0 22.3 39.7 Zn-65 87.3i5.9 85.0*5.0 76.3-93.7 Ru-106 74.717.4 74.015.0 65.3-82.7 1 ( Cs 134 25.710.6 28.015.0 19.3-36.7 i Cs-137 46.311.5 44.0i5.0 35.3 52.7 STW-476 Water Oct 1986 H-3 5918i60 5973tS97 4938-7008 { SPW-477 Water Oct 1986 478 (Blind) Sample A Gr. alpha 34.0t6.0 40.015.0 31.3-48.7 Ra-226 5.8i0.2 6.010.9 4.4-7.6 ( Ra-228 2.7tl.0 5.0*0.8 3.7-6.3 Uranium 11.0f0.0 10.016.0 0.0-20.4 Sample B Gr. beta 38.711.2 51.015.0 42.3-59.7
-[ Sr-89 5.0t0.0 10.0i5.0 1.3 18.7 Sr-90 3.010.0 4.0il.5 1.4-6.6 r Co-60 24.711.2 24.015.0 15.3-32.7 L Cs-134 11.0*2.0 12.0i5.0 3.3 20.7 Cs-137 9.311.2 8.0t5.0 0.0 16.7
.l
( STM-479 Milk Nov 1986 Sr-89 7. 7tl . 2 9.0*5.0 0.3-17.7 Sr-90 1.010.0 0.011.5 0.0-2.6 I-131 52.313.1 49.0t6.0 38.6-59.4 ( Cs-137 45.7*3.1 39.015.0 30.3-47.7 K 14891104 1565t78 1430-1700 STU-480 Urine Nov 1986 H-3 5540i26 5257t912 4345 6169 STW-481 Water Nov 1986 Gr. alpha 12.014.0 20.0t5.0 11.3-28.7 Gr. beta 20.013.5 20.0 5.0 11.3-28.7 STW-482 Water Dec 1986 Ra-226 6.7i0.2 6.811.0 5.0-8.6 Ra-228 5.2i0.2 11.111.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.7i5.0 25.015.0 16.3-33.7 Sr-90 21.0i2.0 25.011.5 22.4-27.6 l i A-5 mm ,
a .s- .-. .~- . - . . . - - - . - - - - -. i Table A-1. (continued). Concentration in DCi/j ; Lab Sample Dr.te TIML Result EPA Resv1:0 i Code Type Collected Analysis 120C 1s, N=1 Conte::1 Limits ! STW-484 Water Jan 1987 Pu-239 17.012.3 16.711.7 2D.0-19.6 Ii STF-486 Food Jan 1987 Sr-90 36.014.0 49.0 10.0 31.7-56.3 > I-131 78.0t3.4 78.0t8.0 66.2 -91.9 ( Cs-137 89.7t3.0 84.0t5.0 75.1-92.7 STF-487 Food Jan 1987 K SR 90 942iS6 2.0f0.0 980249 S9!-1065 l , (Blank) 1-131 <3 --- E , Cs-137 <2 --- 3 K 993t102 --- i STW-488 Water Feb 1987 Co-60 49.0t0.0 50. 0t5. 0 41.3-58.7 ' Zn-65 96.0t7.2 91. 0t5. 0 B2. 0- 99. 7 ' Ru-106 92.0t20.2 100.0t5.0 91.3-1 08.7 - Cs-134 53.0t3.4 59.0t5.0 50.3-67.7 Cs-137 89.3t4.6 87.0t5.0 78.S 95.7 STW-489 Water Feb 1987 H3 4130t140 4209t420 3479 t.939 .l STW 490 Water Feb 1987 Uranium 8.3tl.2 8.0t6.0 0.0-18.4 STM-491 STW-492 Milk Water Feb 1987 Mar 1987 I-131 Gr. alpha 10.0t0.0 3.7tl.2 9.0t0.9 3.015.0 7.4-10.6
- 0. D-11. 7 l
Gr. beta 11.3tl.2 13.0i5.0 4.!-21.7 - , STW-493 Water Mar 1987 Ra-226 7.0t0.1 7.3tl.1 5.4-9.2 Ra-228 7.lt2.3 7.Sil.1 5.5-9.5 STW-494 Water Apr 1987 l-131 8.0*0.0 7. 0f0. 7 5.8-B.2 STAF-495 Air Filter Apr 1987 Gr. alpha Gr. beta Sr-90 15.0t0.0 41.0t2.0 16.3tl.2 14.0t5.0 43.0t5.0 17.0*1.5 5.3-22.7 34.3-51.7. 14.4-19.6 l Cs-137 7.0f0.0 8.0t5.0 0.0-16.7 l- STW-496 Water Apr 1987 l 497 (Blind) l Sample A Gr. alpha 30.711.2 30.018.0 16.1-43.9 Ra-226 3.910.2 3.9t0.6 2.9-4.9 Ra-228 Uranium 4.910.9 5.0f0.0 4.0f0.6 5.0t6.0 3.0-5.0 0.0-15.4 ( I o A-6
+
v- ,,- -,r m - a- nn ew-,, - --e e- -we- -,e, - -
?able A-1. (continued)
[ Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 120C 15. N=1 Control Limits STW-496 Water Apr 1987 = 497 (Blind) __-- Sample B Gr. Beta 69.319.4 66.0t5.0 57.3 74.7 Sr-89 16.3t3.0 19.0t5.0 10.3 27.7 ( Sr-90 10.0t0.0 10.0il.5 7.4-12.6 Co-60 8.3t3.0 8.0t5.0 0.0-16.7 = Cs-134 19.0t2. 0 20.015.0 11.3-28.7 - { Cs-137 14.7tl.2 15.015.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 6017i494 5620t795 4647-6593 ( STW-499 Water May 1987 Sr-89 38.0t6.0 41.0i5.0 32.3-49.7 Sr-90 21.012.0 20.0*1.5 17.4-22.6 ( STW-500 Water May 1987 Gr. alpha 9.0t3.4 11.0t5.0 2.3 19.7 illi Gr. beta 10.311.2 7.0t5.0 0.0-15.7 , STW-501 Water June 1987 Cr-51 40.0t8.0 41.0t5.0 32.3-49.7 { Co-60 60.3t3.0 64.0t5.0 55.3-72.7 Zn-65 11.3t5.0 10.0t5.0 1,3-18.7 Ru-106 78.3t6.4 75.0t5.0 65.3 83.7 ( Cs-134 36.7t3.0 40.015.0 31.3-48.7 Cs-137 80.3t4.2 80.0t5.0 71.3-88.7 ( STW-502 Water June 1987 H-3 2906t86 2895t357 2277-3513 - STW-503 Water June 1987 Ra-226 6.910.1 7.311.1 5.4-9.2 Ra-228 13.3t1.0 15.2t2.3 11.2-19.2 STM-504 Milk June 1987 Sr-89 57.0t4.3 69.0t5.0 60.3 77.7 Sr-90 32.0*1.0 35.0tl.5 32.4-37.6 1-131 64.0t2.0 59.0 6.0 48.6-69.4 Cs-137 77.7t0.6 74.0t5.0 65.3-82.7 K 1383t17 1525t76 1393-1657 k STW-505 Water July 1987 Gr. alpha 2.3t0.7 5.0t5.0 0.0-13.7 Gr. beta 4. 0tl . 0 5.0t5.0 0.0-13.7 STF-506 Food July 1987 I-131 82.7t4.6 80.0t8.0 66.1-93. 9 Cs-137 53.7t3.0 50.0t5.0 41.3-58.7 K 1548157 1680t84 1534-1826 STW-507 Water Aug 1987 1-131 45.714.2 48.0t6.0 37.6-58.4 STW-508 Water Aug 1987 Pu-239 5.8t0.2 5.310.5 4.4-6.2 A-7
Table A-1. (continued) l Conc'entration in pCi/lb L ab Sample Date TIM. Result EPA Resultd ; C ode Type Collected Analysis 22a C 1s, N=1 Control Limits . STW-509 Water Aug 1987 Uranium 13.320.3 13.0s6.0 2.6-23.4 ' STAF-510 Air Filter Aug 1987 Gr. alpha Gr. beta S o 90 9.7 s0.4 28.3s0.6 10.0s0.9 10.0:5.0 30.025.0 10.011.5 1.3-18.7 21.3 38.7 7.4-12.6 l , C s-137 10.011.0 10.025.0 1.3-18.7 gl i STW-511 Water Sept 1987 R&226 9.920.1 9.711.5 7.2 12.2 , R&228 8.121.4 6.311.0 4.6-8.0 STW-512 Water Sept 1987 G r. alpha 2.020.6 4.0 s5.0 0.0-12.7 G r. beta 11.321.3 12.0s5.0 3.3-20.7 STW-513 Water Oct 1987 H-3 44732100 44922449 3714-5270 I : STW-514 Water Oct 1987 ' (Blind) Sample A G r. alpha 29.322.6 28 .0 17 .0 15.9-40.1 , R&226 4.920.1 4.820.7 3.6-6.1 Re-228 4 .2 11 .0 3.6 s0.5 2.7-4.5 ' Vranium 3.O s0.1 3.0 s6 .0 0.0-13.4 : Sample 8 S r-89 14.311.3 16.085.0 7.3-24.7 Sr 90 9.7s0.4- 10.011.5 7.4-12.6 C >60 16.723.0 16.025.0 7.3-24.7 C s-134 16.722 .3 16.025.0 7.3-24.7 ' C s-137 24.323.3 24.025.0 15.3-32.7 STW-516 Water Oct 1987 C r-51 80.3217.5 70.025.0 61.3-78.7 C&60 16.022.3 15.025.0 6.3-23.7 .. Z n-65 46 .3 25 .6 46.025.0 37.3-54.7 mm R u-106 57.3*15.4 61.025.0 52.3-69.7 gi ' C s-134 23.712.5 25.025.0 16.3-33.7 C s-137 51.713.2 51.025.0 42.3-59.7 , STU-517 Urine Nov 1987 H-3 72672100 74321743 6145-8719 STW-518 Water Nov 1987 G r. alpha 3.022.0 7 .0 25 .0 0.0-15.7 E j Gr. beta 15.7s2.3 19.025.0 10.3-27.7 E, STW-519 Water Dec 1987 I-131 26.013.0 26.086.0 15.6-36.4 Ii A-8
Table A-1. (continued) I ' Concentration in pC1/lb Lab Sample Date TIML Result EPA Resultd r Code Type Collected Analysis 22ec is, y.1 Control Limits l l STW-520 Water Dec 1987 Ra-226 5.1t0.8 4.820.7 3.6-6.0 - Ra-228 3.410.1 5.310.8 3.9-6.7 .- STW-521 Water Jan 1988 Sr-89 27.315.0 30.025.0 21.3-38.7 I Sr-90 15.321.2 15.011.5 12.4-17.6 ] STW-523 Water Jan 1988 Gr. alpha 2.341 .2 4.015.0 0.0-12.7 l Gr. beta 7.711.2 8.015.0 0.0-16.7 i STF-524 Fopd Jan 1988 Sr-89 44.024.0 46.015.0 37.3-54.7 l Sr-90 53.0t2.0 55.012.8 50.2-59.8 1-131 102.324.2 102.0110.2 84.3-119.7 Cs-137 95.7t6.4 91.015.0 82.3-99.7 K 1011t158 1230t62 1124-1336 l ' STW-525 Water Feb 1988 Co-60 69.3t2.3 69.015.0 60.3-77.7 Zn-65 99.013.4 9a.0t9.4 77.7-110.3 I Ru-106 92.7114.4 103.0210.5 86.8-123.2 I Cs-134 61.7t8.0 64.015.0 55.3-72.7 Cs-137 99.7t3.0 94.015.0 85.3-102.7 STW-526 Water Feb 1988 H-3 34531103 33271362 2700-3954 , STW-527 Water Feb 1988 Uranium 3.0t0.0 3.016.0 0.0-13.4 l STN-528 Milk Feb 1988 1-131 4.7tl.2 4.0t0.4 3.3-4.7 STW-529 Water Mar 1988 Ra-226 7.120.6 7.6tl.1 5.6-9.6 Ra-228 NAt 7.7tl.2 5.7-9.7 STW-530 Water Mar 1988 Gr. alpha 4.3tl.2 6.0t5.0 0.0-14.7 Gr. beta 13.3tl.3 13.025.0 4.3-21.7 STAF-531 Air Mar 1988 Gr. alpha 21.012.0 20.015.0 11.3-28.7
~
Filter Gr. beta 48.0t0.0 50.015.0 41.3-58.7 Sr-90 16.711.2 17.041.5 14.4-19.6 Cs-137 18.7tl.3 16.015.0 7.3-24.7 STW-532 Water Apr 1988 1-131 9.012.0 7.520.8 6.2-8.8 A-9
I! Table A-1. (continued) Concentration in pC1/1b ll Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis bc Is, N=1 Control Limits " l 1 STW-533 Water Apr 1988 ! 534 (Blind) I Sample A Gr. alpha NDf 46.0111.0 27.0-65.0 ! Ra-226 ND 6.4tl.0 4.7-8.1 i Ra-228 ND 5.6t0.8 4.2-7.0 Uranium 6.0t0.0 6.026.0 0.0-16.4 Sample B Gr. beta ND 57.025.0 48.3-65.7 ' Sr-89 3.311.2 5.0t5.0 0.0-13.7 Sr-90 5.3tl.2 5.011.5 2.4-7.6 i Co-60 63.3tl,3 50.015.0 41.3-58.7 Cs-134- 7.7tl.2 7.015.0 0.0-15.7 Cs-137 8.3t1.2 7.015.0 0.0-15.7 STU-535 Urine Apr 1988 H-3 6483t155 6202t620 5128-7276 STW-536 Water Apr 1988 Sr-89 14.711.3 20.0t5.0 11.3-28.7 Sr-90 20.0t2.0 20.021.5- 17.4-22.6 STW-538 Water June 1988 Cr-51 331.7t13.0 302.0130.0 250.0-354.0 ! Co-60 16.012.0 15.0t5.0 6.3-23.7 ? Zn-65 107.7111.4 101.0210.0 83.7-118.3
- Ru-106 191.3t11.0 195.0120.0 160.4-229.6 Cs-134 18.314.6 20.0t5.0 - 11.3-28.7 Cs-137 26.3tl.2 25.025.0 16.3-33.7 i STW-539 Water June 388 H-3 5586t92 5565t557 4600-6530 STN-541 Milk June 1988 Sr-89 33.7t11.4 40.015.0 31.3-48.7 Sr-90 55.315.8 60.0t3.0 54.8-65.2 '
1-131 103.7*3.1 94.0t9.0 78.4-109.6
!W*!;'
July 1988 i'~2' Gr. alpha
!W*i6 ' W :i N l STW-542 Water 8.7t4.2 15.015.0 6.3-23.7 Gr. beta 5.3tl.2 4.015.0 0.0-12.7 STF-543 Food July 1988 Sr-89 ND 33.0t5.0 24.3-41.7' -
Sr-90 ND 34.022.0 30.5-37.5 1-131 115.015.3 107.0t11.0 88.0-126.0 Cs-137 52.726.4 49.015.0 40.3-57.7 i K 1190166 1240262- 1133-1347 l A-10 __ _ _ , . _ _ . _ _ _ . . _ _ . _ - _ - , _ . -J
Table A-1. (continued) [ Concentration in pC1/lb Lab Sample Date TIML Result ,, EPA Resultd Code Type Collected Analysis 120c is, y.1 Control Limits STW-544 Water Aug 1988 1-131 80.0t0.0 76.018.0 62.1-89.9 STW-545 Water Aug 1988 Pu-239 11.010.2 10.211.0 8.5-11.9 STW-546 Water Aug 1988 Uranium 6.0t0.0 6.0t6.0 0.0-16.4 STAF-547 Air Aug 1988 Gr. alpha 8.010.0 8.015.0 0.0-16.7 i Filter Gr. beta Sr-90 26.311.2 8.012.0 29.0t5.0 8.011.5 20.3-37.7 5.4-10.6 Cs-137 13.012.0 12.025.0 3.3-20.7 STW-548 Water Sep 1988 Ra-226 9.310.5 8.412.6 6.2-10.6 Ra-228 5.810.4 5.411.6 4.0-6.8 STW-549 Water Sep 1988 Gr. alpha 7.012.0 8.0t5.0 0.0-16.7 Gr. beta 11.311.2 10.0t5.0 1.3-18.7 STW-550 Water Oct 1988 Cr-51 252.0114.0 251.0125.0 207.7-294.3 C9-60 26.012.0 25.015.0 16.3-33.7 a Zn-65 158.3110.2 151.0t15.0 125.0-177.0 l g Ro-106 Cs-134 153.019.2 28.715.0 152.0115.0 25.015.0 126.0-178.0 16.3-33.7 Cs-137 16.311.2 15.015.0 6.3-23.7 STW-551 Water Oct 1988 H3 2333t127 2316t350 1710-2927 STW-552 Water Oct 1988 - I 553 (Blind) Sample A Gr. alpha 38.318.0 41.0110.0 23.7-58.3 I Ra-226 4.5t0.5 4.420.6 5.0t0.8 3.6-6.4 Ra-228 5.220.8 3.6-6.4 Uranium 4.711.2 5.0t6.0 0.0-15.4 Sample B Gr. beta 51.313.0 54.0t5.0 45.3-62.7 Sr-89 3.7tl.2 11.015.0 2.3-19.7 Sr-90 10.711.2 10.011.5 7.4-12.6 I Cs-134 15.312.3 15.015.0 6.3-23.7 Cs-137 16.711.2 15.015.0 6.3-23.7 1 A-11
l Table A-1. (continued) g Concentration in pC1/lb l Lab Sample Date TIML Resuit _ EPA Resultd E! ' Code Type Collected Analysi s
- 2cc Is, N=1 Control Limits 8 STM-554 Milk Oct 1988 Sr-89 40.3t7.0 40.025.0 31.3-48.7 ,
Sr-90 51.0t2.0 60.013.0 54. 8 -6 5.2 ! I-131 94.013.4 91.0t9.0 75.4-106.6 Cs-137 45.0t4.0 50.0*$.0 41.3-58.7 1 K 1500:45 1600180 1461-1739 STU-555 Urine Nov 1988 H-3 30301209 30251359 2403-3647 STW-556 Water Nov 1988 Gr. alpha 9.013.5 9.015.0 0.3-17.7 Gr. beta 9.7tl.2 9.015.0 0.3-17.7 STW-557 Water Dec 1988 1-131 108.7t3.0 115.0t12.0 94.2-135.8 l STW-559 Water Jan 1989 Sr-89 40.019.7 40.015.0 31.3-48.7 Sr-90 24.313.1 25.011.5 22.4-27.6 STW-560 Water Jan 1989 Pu-239 5.811.1 4.2t0.4 3.5-4.9 i STW-561 Water Jan 1989 Gr. alpha 7.311.2 8.0*5.0 0.0-16.7 Gr. beta 5.3tl.2 4.025.0 0.0-12.7
- t STW-562 Water Feb 1989 Cr-51 245t46 235t24 193.4-276.6 Co-60 10.012.0 10.015.0 1.3-18.7 Zn-65 170110 159t16 139.2-186.7 Ru-106 18117.6 178t18 146.8-209.2
., Cs-134 9.7t3.0 10.015.0 1.3-18.7 Cs-137 11.7tl.2 10.015.0 1.3-18.7 l 4 l l l l l I i A-12 l r I
l Table A-1. (continued) Concentration in DCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis C 2 2c . 1s, N=1 Control Limits STW-563 Water Feb 1989 l-131 109.044.0 106.0111.0 86.9-125.1 STW-564 Water Feb 1989 H-3 2820t20 2754 1356 2137-3371 STW-565 Water Mar 1989 Ra-226 4.2t0.3 4.920.7 3.7-6.1 Ra-228 1.911.0 1.7*0.3 1.2-2.2 STW-566 Water Kir 1989 U 5.0t0.0 5.016.0 0.0-15.4 STW-567 AirFilter Mar 1989 Gr. alpha 21.7 tl .2 21.015.0 12.3-29.7 Gr. beta 68.314.2 62.015.0 53.3-70.7 Sr-90 .0.012.0 20.0tl.5 17.4-22.6 Cs-137 21.321.2 20.015.0 11.3-28.7 STW-568 Water Apr 1989 569 (Blind) Sample A Gr. alpha 22.712.3 29.0t7.0 16.9-41.2 Ra-226 3.6t0.6 3.510.5 2.6-4.4 Ra-228 2.611.0 3.6t0.5 2.7-4.5 V 3.0t0.0 3.0*6.0 0.0-13.4 Sample B Gr. beta 52.3*6.1 57.025.0 43.3-65.7 Sr-89 9.315.4 8.025.0 0.0-16.7 Sr-90 7.020.0 8.0tl.5 5.4-10.6 Cs-134 21.015.2 20.025.0 11.3-18.7 Cs-137 23.0*2.0 20.0*5.0 11.3-28.7 STW-570 Milk Apr 1989 Sr-89 26.0t10.0 39.015.0 30.3-47.7 Sr-90 45.7t4.2 55.013.0 49.8-60.2 Cs-137 54.0t6.9 50.0t5.0 41.3-58.7 K-40 1521*208 1600t80 1461-1739 G A-13
___ _ _ _ . . _ . . . . . _ . . ~ _ _ .._ _ _ _. . _ _ _ . . - _ _ . . _ _ . _. Table A-1. (continued) Concentration in DCi/lb Lab Sample Date TIML Result EPA Resultd l Code Type Collected Analysis 22bc 15, N=1 Control Limits STW-571 Water May 1989 Sr-89 40.7 6.025.0 0.0-14.7 Sr-90 5.0tl.0 6.021.5 3.4-8.6 STW-572 Water May 1989 Gr. alpha 24.012.0 30.028.0 16.1-43.9 Gr. beta 49.3t15.6 50.015.0 41.3-58. STW-573 Water Jun 1989 Ba-133 50.7tl.2 49.0t5.0. 40.3-57.7 Co-60 31.312.3 31.0t5.0 22.3-39.7 Zn-65 167t10 165t17 135.6-194.4 . Ru-106 123t9.2 128113 105.5-150.!g " Cs-134 40.311.2 3915 30.3-47.7 g Cs-137 22.3tl.2 20t5 11.3-28.7 STW-574 Water Jun 1989 H-3 4513t136 4503t450 3724'5282 l STW-575 Water Jul 1989 Ra-226 16.813.1 17.7t2.7 13.0-22.4 Ra-228 13.813.7 18.312.7 13.6-23.0 , STW-576 Water Jul 1989 U 40.3tl.2 41.016.0 30.6-51.4 STW-577 Water Aug 1989. 1-131 84.7t5.8 83.0t8.0 69.1-96.9 STW-579 Air Aug 1989 Gr. alpha 6.0t0.0 6.015.0 0.0-14.7 Filter Cs-137 10.3t2.3 10.0t5.0 1.3-18.7
- STW-580 Water Sep 1989 Sr-89 14.7tl.2 14.015.0 Sr-90 9.7tl.2 10.0tl.5 7.4-12.6 5.3-22.7 i STW-581 Water Sep 1989 Gr. alpha 5.0t0.0 4.015.0 0.0-12.7 l Gr. Beta 8.712.3 6.0t5.0 0.0-14.7 3
h t f A-14
Table A-1. (continued) j Concentration in pC1/lb [ Lab Sample Date TIML Result EPA Resulta Code Type Collected Analysis $2cc Is, N=1 Cntrol Limits __ STW-583 Water Oct 1989 Ba-133 60.3210.0 59.026.0 48.6-69.4 Co-60 29.02 4.0 30.0 5.0 21.3-38.7 = In-65 132.3 6.0 129.0 13.0 106.5-151.5 -- Ru-106 155.326.1 161.0116.0 133.3-188.7 i
' Cs-134 30.7 6.1 29.025.0 20.3-37.7 i Cs-137 66.3t4.6 59.0 5.0- 50.3-67.7 STW-584 Water Oct 1989 H-3 3407 150 34961364 2866-4126 STW-58$ Water Oct 1989 586 (Blind) ]
Seple A Gr. Alpha 41.729.4 49.0 12.0 28.2-69.8 Ra-226 7.91.4 8.421.3 6.2-10.6 Ra-228 4.410.8 4.110.6 3.le5.1 - U 12.020.0 12.0 6.0 1.6-22.4 ; Sample B Gr. Beta 31.712.3 32.0 5.0 23.3-40.7 Sr-89 13.3 4.2 15.025.0 6.3-23.7 Sr-90 7.0 2.0 7.013.0 4.4-9.6 Cs-134 5.0 0.0 5.025.0 0.0-13.7 Cs-137 7.010.0 5.0 5.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.920.4 8.7 1.3- 6.4-11.0 Ra-228 8.911.2 9.3 1.2 6.9-11.7 STW-588 Water Nov 1989 U 15.020.09 15.026.0 4.6-25.4 _. a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Cali-bration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protection Agency (EPA), Las Ve b All results are in the pC1/1, except for elemental potassium (K) gas, Nevada, data in milk, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in ag/kg. c Unless otherwise indicated, the TIML results are given as' the mean i 2 standad 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 EPA. e NA = Not analyzed, f NO = No data. Not analyzed due to relocation of the lab. 9 Sample was analyzed but the results not submitted to EPA because deadline was missed. - A-15
Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs). mR Teledyne Average 12 od Lab TLD Result Known (all Code Type Measurement 12aa Valuec partic ipants) 2nd International Intercomparisonb Field 115-2 CaF2:Mn 17.011.9 17.1 16.417.7 Bulh .; Lab 20.814.1 21.3 18.817.6 i 3rd International Intercomparisone 115-3 CaF2:Mn Field 30.713.2 34.924.8 31.513.0 Bulb r Lab 89.616.4 91.7114.6 86.2124.0
~
- 4th International Intercomparisonf
! 115-4 CaF7:Mn Field 14.111.1 14.111.4 16.029.0 Bulb Lab (Low) 9.311.3 12.212.4 12.027.6 l Lab (High) 40.411.4 45.819.2 43.9113.2 !
- Sth International Intercomparison9-f 115-5A CaF2
- Mn Field 31.411.8 30.016.0 30.2114.6 '
Bulb i Lab at 77.415.8 75.217.6 75.8140.4 ) beginning
- l. Lab at 96.615.8 88.418.8 90.7131.2 end l
l Table A-2. (Continued) = nG ' Teledyne Avera9e 120 d Lab TLD Result Known (all Code Type Measurement 12oa valuec partic ipants) 115-5B LIF-100 Field 30.314.8 30.016.0 30.2114.6 Chips Lab at 81.117.4 75.217.6 75.8140.4 beginning , Lab at 85.4111.7 88.418.8 90.7131.2 the end 7th International Intercomparison h 115-7A LiF-100 Fleid 75.412.6 75.816.0 75.1129.8 Y Chips C Lab (Co-60) 80.013.5 79.914.0 77.9127.6 Lab (Cs-137) 66.612.5 75.013.8 73.0t22.2 115-78 CaF2:Mn Fleid 71.512.6 75.816.0 75.1129.8 Bulbs . Lab (Co-60) 84.816.4 79.914.0 77.9t27.6 Lab (Ca-137) 78.811.6 75.013.8 73.0122.2 115-7C CaSO4 :Dy Field 76.812.7 75.816.0 75.1129.8 Cards Lab (C0-60) 82.513.7 79.914.0 77.9127.6 Lab (Cs-137 79.013.2 75.013.8 73.0122.2 I
i Tcble A-2. (Continued) mR l Teledyne Average 2o d I Lab TLD Result Known (all Code Type Measurement 2ca Valuec participants) Sth International Intercomparisoni - . 115-8A LiF-100 Field Site 1 29.511.4 29.711.5 28.9112.4 , Chips Field Site 2 11.310.8 10.410.5 10.119.06 :
- Lab (Cs-137) 13.720.9 17.210.9 16.2t6.8 i 115-88 CaF2
- Hn Field Site 1 32.311.2 29.721.5 28.9112.4 8ulbs Field Site 2 9.011.0 10.4t0.5 10.119.0 1
Lab (Cs-137) 15.820.9 17.2t0.9 16.216.8
- 115-8C CaSO4
- Dy Field Site 1 32.310.7 29.711.5 28.9212.4 Cards Field Site 2 10.610.6 10.410.5 10.119.0 Lab (Cs-137 18.120.8 17.210.9 16.216.8 Teledyne Testing 3 i
. 89-1 LiF-100 Lab 21.0t0.4 22.4 - Chips 89-2 Teledyne Lab 20.9tl.0 20.3 - CaSO4 :Dy . Cards a Lab result given is the mean #2 standard deviations of three determinations. b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the i Health and Safety Laboratory (GASL), New Yort, New Yort, and the School of Public Health of the Uni-versity of Texas, Houston, Texas. c Value detemined by sponsor of the intercomparison using continously operated pressurized ion chamber. d Mean 32 standard deviations of results obtained by all laboratories participating in the program. i
e - ( n1 f 1 i Table A-2. (continued) mR Teledyne Averap !?o d Lab TLD Result Known (all Code Type Measurement 22ca Valuec participants) Footnotes continued
- Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
I f Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 9 Fifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and
" "" "I '5"#'" " 5 #8 U' "*" ' ' ** *# " * "'#8Y~
h Seventh International .'Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. 9 g Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, 'and sponsored by the U.S. Department of Energy. Chips were submitted in September, 1989 and cards were submitted in November, 1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation.
Table A-3. In-house spiked samples. '
. l Concentration in pC1/1 M Lab Sample Date TIML Result Known Expected
- Code Type Collected Analysis n=3 Activity Precision 1s, n=3a -
QC-MI-6 Milk Feb. 1986 Sr-89 6.0x1.3 6.4t3.0 8.7 l Sr-90 14.2tl.7 12.9t2.0 5.2 I-131 34.213.8 35.2i3.5 10.4 E E lI Cs-134 32.0tl.8 27.3t5.0 8.7 j Cs-137 35.8t2.1 35.0t5.0 8.7 E ! QC-W-14 Water Mar. 1986 Sr-89 1.6*0.4 1.6tl.0 7.1 l 1 Sr-90 2.4t0.2 2.4*2.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9t2.4 41.St7.0 10-6 ! Co-60 10.6tl.7 12.115.0 7.lb ; Cs-134 30.2t2.4 25. 8t8.0 7.lb a l Cs-137 21. 9tl . 9 19. 9tS .0 7.lb g QC-MI-7 Milk Apr. 1986 I-131 39.7t3.3 41.5t7.0 10.4 i Cs-134 28.7t2.8 25.8t8.0 8.7 ) Cs-137 21.2t2.8 19.9t5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8*1.8 18.0t5.0 Sc
]
QC-W-16 Water June 1986 Gross alpha 16.2t0.7 16.9t2.5 8.7 QC-MI-9 Milk Gross beta 38.413.5 30.2t5.0 8.7 g' June 1986 Sr-89 <1.0 0.0 7.lb Sr-90 12.6tl.8 13.313.0 4.2b I-131 38.9t7.0 34.8t7.0 10.4 Cs-134 33.0t3.4 36.lt5.0 8.7 Cs-137 38.St2.8 39.015.0 8.7 i SPW-2 Water June 1986 Gross alpha 16.8tl.8 18.015.0 Sc SPW-3 Water June 1986 Gross alpha 17.7t0.8 18.015.0 SC g QC-W-18 Water Sep. 1986 Cs-134 34.715.6 31.3t5.0 8.7 . Cs-137 51.lt7.0 43.3t8.0 8.7 j i QC-W-19 Water Sep. 1986 Sr-89 13.6t4.1 15.6*3.5 7.lb 1 Sr-90 6.4 tl . 6 6.2t2.0 4.2b 4 4 .
.)
A-20 -
~ Table A-3. In-houst spiked samples (continued) F L , Concentration in pC1/1 Lab Sample Date TIML Result Esown [ Code Type Collected Analysi s n=3 Expected Activity Precision is, n=3a ( QC-W-21 Water Oct. 1986 C -60 19.212.2 18.513 0 8.7 Cs-134 31.7t5.2 25.628.0 8.7 Cs-137 23.821.0 21.6t5.0 8.7 [ QC-MI-11 Milk .st 1986 Sr-89 12.3tl.8 14.3t3.0 8.7 QC-W-20 Water Nov. 1986 H-3 38551180 3960t350 520b { QC-W-22 Water Dec. 1986 Gross alpha 9.811.4 11.214.0 8.7 Gross beta 21.7t2.0 23.825.0 8.7 QC-W-23 Water Jan. 1987 1-131 29.8t2.5 27.923.0 10.4 ( QC-MI-12 Milk Jan. 1987 1-131 36.511.3 32.6t5.0 10.4 Cs-137 32.624.2 27.428.0 8.7 QC-MI-13 Milk Jan 1987 Sr-89 10.4t2.1 12.2t4.0 8.7 Sr-90 14.6tl.6 12.613.0 5.2 1-131 49.5tl.2 54.928.0 10.4 Cs-134 41.6 0.0 8.7 Cs-137 33.3t0.6 27.418.0 8.7 QC-W-24 Water Mar 1987 Sr-89 24.713.6 25.915.0 8.7 j( Sr-90 23.913.8 22.818.0 0.2 QC-W-25 Water Apr 1987 1-131 28.0tl.9 29.325.0 10.6
;[
QC-MI-14 Milk Apr 1987 1-131 25.0t2.2 23.925.0 10.4 Cs-134 42.1 ' O.0 8.7 Cs-137 34.222.0 27.2t7.0 8.7 QC-V-26 Water Jun 1987 H-3 3422t100 3362t300 520 Co-60 24.811.4 26.St7.0 8.7 Cs-134 42.0 0.0 8.7 Cs-137 21.210.5 21.6t7.0 8.7 QC-W-27 Water Jun 1987 Gr. alpha 8.521.9 10.124.0 8.7 Gr. beta 22.611.9 21.225.0 8.7 QC-W-28 Water Jun 1987 Gr. alpha 8.7tl.3 10.124.0 8.7 Gr.-beta 12.2tS.2 9.4t3.0 8.7 A-21
f Table A-3. In-house spiked samples (continued) Copeentration in pC1/1 ! Lab Sample Date TIML Result Known Expected Code- Type Collected Analysis n=3 Activity Precision 1s, n=3a QC-W-29 Water Jun 1987 Gr. alpha 16.421.3 18.9t5.0 8.7 :
- Gr. beta 15.9t4.0 11.814.0 8.7 4
' QC-MI-15 Mil k Jul 1987 Sr-90 19.411.6 18.813.5 5.2 , I-131 43.510.7 45.327.0 10.4 - Cs-134 17.912.2 16.015.3 8.7 Ei
- Cs-137 25.4tl.8 22.715.0 8.7 5, QC-W-30 Water Sep 1987 Sr-89 17.St3.0 14.315.0 8.7 ~
Sr-90 18.422.2 17.522.2 5.2 s QC-W-31 Water- Oct 1987 H-3 20532939 2059t306 520 QC-W-32 Water Dec 1987 Gr. alpha 8.621.0 10.115.0 8.7 Gr. beta 15.210.1 13.lt3.0 8.7 l QC-W-33 Water Dec 1987, Gr. alpha 7.7tl.4 10.1t5.0 8.7 i Gr. beta 10.911.0 7.9t3.0 8.7 ! QC-W-34 Water Dec 1987 Gr. alpha 4.0 0.9 5.113.0 8.7 Gr. beta 9.4t0.9 7.923.0 8.7 QC-MI-16 Milk Feb 1988 Sr-89 31.824.7 31.726.0 8.7 : Sr-90 25.512.7 27.823.5 5.2 , 1-131 26.410.5 23.215.0 10.4 J Cs-134 23.812.3 24.2t6.0 8.7 , Cs-137 26.510.8 25.116.0 8.7 , QC-MI-17 Milk Feb 1988 I-131 10.611.2 - 14.321.6 10.4 QC-W-35 Water Feb 1988 I-131 9.721.1 11.621.1 10.4-l QC-W-36 Water Feb 1988 I-131 10.511.3 11.611.0 10.4 QC-W-37 Water Mar 1988 Sr-89 17.112.0 19.818.0 8.7 Sr-90 18.7*0.9 17.3t5.0 5.2 , QC-MI-18 Milk Mar 1988 I-131 33.222.3 26.715.0 10.4 Cs-134 31.322.1 30.215.0 8.7 Cs-137 29.921.4 26.215.0 8.7 A-22 I sw---,--
Table A-3. In-house spiked samples (continued) L Concentration in pCi/1 Lab Sample Date TIML Result Known Expected [ Code Type Collected Analysis n=3 Activity Precision 15, n=3a l QC-W-38 Water Apr 1988 I-131 17.111.1 14.215.0 10.4 QC-W-39 Water Apr 1988 H-3 4439131 41761500 724 QC-W-40 Water Apr 1988 Co-60 23.710.5 26.114.0 8.7 Cs-134 25.412.6 29.214.5 8.7 Cs-137- 26.612.3 26.224.0 8.7 QC-W-41 Water Jun 1988 Gr. alpha 12.310.4 13.115.0 8.7 Gr. beta 22.611.0 20.125.0 8.7 QC-MI-19 Milk Jul 1988 Sr-89 15.111.6 16.415.0 8.7 Sr-90 18.020.6 18.315.0 5.2 1-131 88.414.9 86.618.0 10.4 Cs-137 22.7t0.8 20.8t6.0 8.7 QC-W-42 Water Sep 1988 Sr-89 48.513.3 50.818.0 8.7 Sr-90 10.921.0 11.413.5 5.2 QC-W-43 Water Oct 1988 Co-60 20.913.2 21.4t3.5 8.7 Cs-134 38.711.6 38.016.0 8.7 Cs-137 19.012.4 21.013.5 8.7 QC-W-44 Water Oct 1988 I-131 22.220.6 23.313.5 10.4 QC-W-45 Water Oct 1988 H-3 4109243 41531500 724 QC-MI-20 Milk Oct 1988 I-131 59.8 0.9 60.629.0 10.4 Cs-134 49.6tl.8 48.627.5 8.7 Cs-137 25.814.6 24.724.0 8.7 QC-W-46 Water Dec 1988 Gr. alpha 11.512.3 15.215.0 8.7 Gr. beta 26.512.0 25.715.0 8.7 QC-MI-21 Milk Jan 1989 Sr-89 25.5i10.3 34.0110.0 8.7 Sr-90 28.313.2 27.123.0 5.2 1-131 540113 550220 10.4 Cs-134 24.522.6 22.615.5 8.7 Cs-137 24.020.6 20.515.0 8.7 A-23
Table A-3. In-house spiked samples (continued) I: i I. ' C,oncentration in pC1/1 Lab Sample Date TIML Result Known Expected , Code Type Collected Analysis n=3 Activity Precision ' Is, n=3a P QC-W-47 Water Mar 1989 Sr-89 15.2 3.8 16.115.0 8.7 ; Sr-90 16.411.7 16.913.0 5.2 ' QC-MI-22 Milk Apr 1989 l-131 36.321.1 37.215.0 10.4 : Cs-134 20.812.8 20.718.0 8.7 Cs-137 22.212.4 20.418.0 8.7 = QC-W 48 Water Apr 1989 Co-60 23.512.0 25.118.0 8.7 g, 1 QC-W-49 Water Apr 1989 Cs-134 Cs-137 I-131 24.211.1 23.6tl.2 37.213.7 25.918.0 23.018.0 37.215.0 8.7 8.7 10.4 l! ~ QC-W 50 Water Apr 1989 H-3 3011159 30891500 724 QC-W-51 Water Jun 1989 Gr. alpha 13.011.8 15.015.0 8.7 Gr. beta 26.011.2 25.5t8.0 8.7 ; QC-MI-23 Milk Jul 1989 Sr-89 19.416.5 22.0110.0 8.7 Sr-90 I-131 27.613.5 46.813.2
-28.613.0 43.415.0 5.2 10.4.
l,: Cs-134 .411.8 28.3t6.0 8.7 Cs-137 . ' i .8 20.826.0 8.7 { l QC-MI-24 Milk Aug 1989 Sr-89 25.4 . 7 27.2110.0 8.7 Sr-90 46.0 1.1 47.819.6 8.7 QC-W-52 Water Sep 1989 I-131 9.610.3 9.711.9 10.4 l QC-W-53 QC-W-54 Water Water Sep 1989 Sep 1989 I-131 Sr-89 19.020.2 25.814.6 20.914.2 24.714.0 10.4 8.7 l Sr-90 26.525.3 29.715.0 5.2 I a n=3 unless noted otherwise.
-ll b n=2. -
c n=1. A-24
Table A-3. In-house spiked samples (continued) QoncentrationinpC1/1 Lab Sample Date TIML Result Known Expected 7 Code Type Collected Analysis n=3 Activity Precision L 15, n=3a QC-M1-25 Milk Oct 1989 l-131 70.013.3 73.5120.0 10.4 [ Cs-134 22.112.6 22.618.0 8.7 Cs-137 29.411.5 27.518.0 8.7 ._ QC-W-55 Water Oct 1989 l-131 33.311.3 35.3t10.0 10.4 l QC-W-56 Water Oct 1989 Co-60 15.2t0.9 17.415.0 8.7 Cs-134 22.124.4 18.918.0 8.7 Cs-137 27.211.2 22.918.0' 8.7 QC-W-57 Water Oct 1989 H-3 3334122 33792500 724
] QC-W-58 Water Nov 1989 Sr-89 10.911.4d 11,1 1,od 8.7 -
I Sr-90 10.411.0d 10,3tl,od 5.2 QC-W-59 Water Nov 1989 Sr-89 101.0t6.0d 104,1,10,$d 17,5 Sr-90 98.013.0d 95.0t10.0d 17.0 QC-W-60 Water Dec 1989 Gr. alpha 10.811.1 10.614.0 8.7 l Gr. beta 11.610.5 11.414.0 8.7 a n= -- b n=32. unless noted otherwise. c n=1. d Concentration in pCi/ml . I 1
-R a
A-25
l Table A-4. In-house " blank' samples. l l Qoncentration in pC1/1 l 1 Acceptance ' Lab Sample Date Results Criteria j Code Type Collected Analysi s (4.66o ) (4.66o ) i
~
- l BL -1 D.I. Water Nov. 1985 Gross alpha <0.1 <1 i Gross beta <0.4 <4 i BL 2 D.I. Water Nov. 1985 Cs-137 (gamma) <1.9 <10 l BL-3 D.I. Water Nov. 1985 Sr-89 <0.5 <5 Sr-90 <0.6 <1 BL-5 D.I. Water Nov. 1985 Ra-226 (0.4 <1 Ra-228 <0.4 <1 SPW-2265 D.I. Water Apr. 1985 Gross alpha <0.6 <1 Gross beta <2.2 <4 Sr-89 <0.2 <5
$r-90 <0.4 <1 1-131 <0.2 <1 Cs-137 (gamma) (7.4 (10 8L-6 D.I. Water Apr. 1986 Gross alpha <0.4 <1 BL-7 D.I. Water Apr. 1986 Gross alpha <0.4 <1 1
BL-8 0.I. Water June 1986 Gross alpha <0.4 <1 l BL-9 D.I. Water June 1986 Gross alpha <0.3 <1 4 SPW-3185 D.I. Water Jan 1987 Ra-226 <0.1 <1 ) Ra-228 <0.9 <1 SPS-3292 Milk Jan 1987 I-131 (0.1 <1 Cs-134 <6. 2 (10 Cs-137 <6.4 <10 SPW-3554 D.I. Water Feb 1987 H-3 (180 <300 Gross beta <2.6 <4 : SPS-3555 Milk Feb 1987 Sr-89 <0.6 (5 Sr-90 1.920.4a <1 SPS-3731 Milk Mar 1987 Cs-134 <2.2 <10 Cs-137 (2.5 . <10 a Low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual. 1 A-26 l
Table A-4. In-house ' blank" samples (continued).
. Concentration in pCi/1 Acceptance Lab Sample Date Resul ts Criteria Code Type Collected Analysis (4.663 ) (4.663 )
=
SPS-3732 0.1. Water Mar 1987 Sr-89
<0.9 (5 Sr-90 (0.8 <1 1-131 <0.3
<1 Co-60 (2.3 <10 Cs-134 <2.2 <10 Cs-137 -
(2.4 <10 - Ra-226 <0.1 <1 = Ra-228 <1.0 <1 Wp-237 (0.04 <1 Th-230 <0.05 (0.1 Th-232 <0.02 (0.1 U-234 <0.05 <0.1 U-235 <0.03 <0.1 U-238 <0.03 <0.1 = SPS-4023 Milk May 1987 1-131 <0.1 <1 SPS-4203 0.1. Water May 1987 Gross alpha (0.7 <1 Gross beta <1.7 <4 SPS-4204 Milk May 1987 Sr-89 <0.5 <5 Sr-90 2.4 0.6a <1 SPS-4390 Milk Jun 1987 Cs-134 <4.7 <10 Cs-137 (5.2 (10 SPS 4391 0.I. Water Jun 1987 Sr-89 <0.4- (5 Sr-90 <0.4 <1 1-121 <0.1 <1 Co-60 <3.8 (10 Cs-137 (5.7 <10 i Ra-226 <0.1 <1 Ra-228 <0.9 <1 - SPW-4627 D.I. Water Aug 1987 Gross alpha <0.6 <1- M Gross beta <1.4 <4 Tritium (150 SPS-4628 Milk Aug 1987 Sr-89 <0.6 <5 Sr-90 2.4.0.6a <1
=
SPS-4847 Milk Sep 1987 Cs-134 <4.4 (10 Cs-137 <5.3 (10 a low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual. A-27
i Table A-4. In-house " blank
- samples (continued).
1 Concentration in pC1/1 Acceptance
- Lab Sample Date Results Criteria Code Type Collected Analysis (4.66o ) (4.66o )
SPS-4848 0.I. Water Sep 1987 I-131 <0.2 <1 SPW-4849 D.I. Water Sep 1987 Co-60 <4.1 <10 . Cs-134 (4. 8 <10 Cs-137 (4.0 <10 Sr-89 <0.7 (5
- Sr-90 <0.7 <1 SPW-4850 D.I. Water Sep 1987 Th-228 <0.04 <1 Th-232 (0.8 <1 U-234 (0.03 <1 :
U-235 <0.03 <1 U-238 <0.02 '
<1 2-241 (0.06 <1 cm-242 (0.04 <1 ,
Ra-226 (0.1 <1 Ra-228 <1.0 <2 : SPW-4859 0.I. Water Oct 1987 Fe-55 <0. 5 <1 . SPS-5348 Milk Dec 1987 Cs-134 <2.3 <10 Cs-137 <2.5 <10 SPW 5384 D.I. Water Dec 1987 Co-60 <2.8 (10 , Cs-134 <2.6 <10 I Cs-137 <2.8 <10 1-131 <0.2 <1 li. l Ra-226 <0.1 <1 Ra-228 <1.2 <2 Sr-89 <0,5 <1 l Sr-90 <0.4 <1 SPW-5385 0.I. Water Nov 1987 Gr.- alpha <0.4 <1~ Gr. beta , <2. 2 <4 ; Fe-55 <0.3 <1 SPS-5386 Milk Jan 1988 I-131 (0.1 <1 SPW-5448 " Dead" Water Jan 1988 H-3 <177 <300 A-28
Table A-4. In-house " blank" saples (continued).
, Concentration in pCi/1 -
Acceptance - Lab Sample Date Resul ts Criteria _ Code Type Collected Analysis (4.660 ) (4.663 ) z SPS-5615 Milk Mar 1988 Cs-134 (2.4 (10 Cs-137 <2.5 <10 " 1-131 <0. 3 <1 Sr-89 <0. 4 <5 Sr-90 2.420.5a <1 SPS-5650 D.I. Water Mar 1988 Th-228 <0. 3 <1 m Th-230 <0.04 <1 Th-232 <0.05 <1 - U-234 <0.03 <1 U-235 <0.03 <1 - U-238 <0.03 <1 Am-241 <0. 06 <1 Cm-242 <0.01 <1 = Pu-238 <0. 08 <1 M Pu-240 <0.02 <1 SPS-6090 Milk Jul 1988 Sr-89 <0. 5 <1 Sr-90 1.8 0.Sa <g 1-131 <0. 4 <1 Cs-137 <0. 4 <10 SPW-6209 Water Jul 1988 Fe-55 <0.8 <1 SPW-6292 Water Sep 1988 Sr-89 <0.7 <1 Sr-90 <0. 7 <1 SPS-6477 Milk Oct 1988 I-131 <0. 2 <1 - Cs-134 <6 .1 <10 Cs-137 <5. 9 (10 SPW-6478 Water Oct 1988 I-131 <0. 2 <1 SPW-6479 Water Oct 1988 Co-60 <5. 7 <10 Cs-134 <3.7 <10 Cs-137 (4. 3 <10 SPW-6480 Water Oct 1988 H-3 <170 (300 SPW-6625 Water Dec 1988 Gr. alpha <0.7 <1 Gr. beta (1.9 . <4 a low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual. A-29
Table A-4 In-house " blank' suples (continued). l. Concentration in pC1/1 l Acceptance ; Lab Suple Date Results Criteria g i Code Type Collected Analysis (4.66o ) (4.660 ) gl SPS.6723 ' Mil k Jan 1989 Sr-89 <0.6 <5 Sr-90 1.9 0.5a <1 I-131 <0.2 <1 Cs-134 <4. 3 (10 E Cs-137 <4.4 <10 5 SPW-6877 Water Mar 1989 Sr-89 <0.4 <5 Sr-90 <0.6 <1 SPS-6963 Milk Apr 1989 I-131 <0.3 <1 Cs-134 <5.9 (10 Cs-137 <6. 2 <10 SPW-7561 Water Apr 1989 H-3 <150 <300 SPW-7207 Water Jun 1989 Ra-226 <0. 2 <1 Ra-228 <0.6 <1 SPS-7208 Milk Jun 1989 Sr-89 <0.6 <5 Sr-90 2.120.5a <1 1-131 <0.3 <1 Cs-134 (6.4 <10 Cs-137 <7.2 (10 SPW-7558 Water Jun 1989 Cr. alpha <0.2 <1 Gr. beta <1.0 <4 SPS-7322 Milk Aug 1989 Sr-89 <1.4 (5 : Sr-90 4.811.0a <1
. 1-131 <0.2 <1 i Cs-134 <6. 9 <10 l Cs-137 <8.2 <10
)
SPW-7559 Water Sep 1989 Sr-89 <2.0 <5 l Sr-90 <0. 7 <1 m 1 SPW-7560 Water Oct 1989 I-131 (0.1 <1.0 SPW-7562 Water Oct 1989 H-3 <140 <300 SPS-7605 Milk Nov 1989 I-131 <0.2 <1 Cs-134 <8.6 <10 Cs-137 (10 <10 SPW-7971 Water Dec 1989 Gr. alpha <0.4 <1 Gr. beta (0.8 (4 a Low level ( g.$ pCi/1) of Sr-90 concentration in milk is not unusual. A-30. '
?!ML.8LIND-01 Revision 0, 12o29-86 ATTACHMENT B ACCEPTANCE CRITERIA FOR ' SPIKED" SAMPLES
( LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa ( One Standard Deviation Analysis Level for Single Determination { Ganna Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
>100 pC1/11ter or kg 55 of known value Strontium-89b 5 to 50 pCi/ liter or kg 5 pCi/ liter
>50 pCi/ liter or kg los of known value
[' Strontium-90b 2 to 30 pCi/ liter or kg 3.0 pCi/ liter
>30 pCi/ liter of kg lot of known value
[ Potassium >0.1 g/ liter or kg 55 of known value Gross Alpha <20 pCi/ liter 5 pCi/ liter
>20 pCi/ liter 25% of known value
[ Gross Beta <100 pCi/ liter 5 pCi/ liter
>100 pCi/ liter 55 of known value Tritium (4,000 pCi/ liter is=(pC1/11ter)=
169.85 x (known).0933 [ >4,000 pCi/ liter 105 of known value Radium-226, <0.1 pCi/ liter 15% of known value Radium-228 Plutonium 0.1 pCi/ liter, gram, 10% of known value or sample lodine-131, b <55 pCi/ liter 6 pCi/ liter Iodine-129 >55 pCi/ liter 105 of known value Uranium-238, <35 pCi/ liter 6 pCi/ liter Nickel-63b, >35 pCi/ liter 155 of known value Technetium-99b Iron-55b 50 to 100 pCi/ liter 10 pCi/ liter 105 of known value
- From EPA publication, " Environmental Radioactivity Laboratory Intercompari-b son Studies Program, Fiscal Year 1981-1982 EPA-600/4-81-004.
TIML limit. A-31
ADDEt10VM TO APPENDIX A The following is an explanation of the reasons why certain samples were outside the control limit specified by the Environmental Protection Ag,ency for the Interlabora-tory Comparison Program starting January 1987. EPA Lab Code Analysis TIML Result Control Limit Explanation STil-504 Sr-89 57.024.3 60.3-77.7 Milk had high fat content which g Sr-90 32.021.0 32.4-37.6 made analyses difficult. Ad- g dition of errors to Titil result would put values within EPA - control limits. EPA also had , the same problem .in analyzing p its own sample. STW-511 Ra-228 8.121.4 4.6-8.0 T!!!L results are usually within EPA control limits. Analysis of the next sample was within g ; EPA control limits. No further g ;~ action is planned.- STW-516 Cr-51 80.3217.5 61.3-78.7 Results - in the past have been within EPA control limits and TIML will monitor the situation in the future. ! ST F-524 K 1010.72158.5 1123.5-1336.5 Error in transferrance of data. Correct data- was 1105233. E Results in the past have been g within the limits and TIML will monitor the situation in the 1 future. t STW-532 1-131 9.022.0 6.2-8.8 Sample recounted af ter 12 days. i The average result was 8.821.7 E (within EPA control limits). B The sample was recounted in order to check the decay. 3 Results in the past have been g within the limits and TINL will continue to monitor the situ-etion in the future. STW-534 Co-60 63.321.3 41.3-58.7 High level of Co-60 was due to contamination of beaker-Beaker was discarded upon dis- . cove ry of ' contamination and sample was reco0nted. Recount g results were 53.223.6 and 3. 50.922.4. I A-32 I
l l l ADDENDUM TO APPENDIX A (continued) I EPA : Lab Code Analysis TIML Result Control Limit Explanation STM-554 Sr-90 51.0i2.0 54.8-65.2 The cause of low result is not known and is under investi-gation. It should be noted I that 63% of all participants failed this test. Also, the average for all participants I 1 was 54.0 pC1/1 before the Grubb and 55.8 pC1/1 after the Grubb. 3.5-4.9 I STW-560 Pu-239 5.821.1 The cause of high results is not known (suspected contami-nated standard) and is under investigation. New Pu-236 I standard was obtained and will be used for the next test. I STW-568 Ra-228 2.6 1,0 2.7-4.5 The cause of low results is under investigation. New dilution was prepared and I sample is being reanalyzed. Sample was used up during testing. Next EPA crosschecks with the control limits. STM-570 Sr-89 26.0 10.0 39.0 5.0 The cause of low' results is Sr-90 45.724.2 55.0 3.0 under investigation. New I " spike" milk sample was pre-pared and being analyzed. Results of analysis: See-Table A-3, sample QC-Mi-24. I , i s b A-33
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