ML20073H002
| ML20073H002 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ND3VPN:6613, NUDOCS 9105060114 | |
| Download: ML20073H002 (184) | |
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- Nati 19dr @ Lidg Aptil 25. 1991 11D3 Vill: 6613 United States 14uclear Regulatoly Commission Document Contiol Desk Varhington, DC ?O555 Subj ec t :
1990 Annual 1:nvironmental Report, Radiological - Volume #2 lu f t
- 1) 11enver Valley Pover Station Unit No. 1 Docket flo. 50-334, License No. DPit-66
- 2) Deavet Valley Povet Station Unit flo. 2 Docket No. $n-412, License flo. NPT-73 1hc 1490 Annual Envitonmental Repott (Radiological Voltime ti2 ) 1:
het < by tuhmi t ted in actordance vith the equiiements of Technien1 Sperif it a t ionn 6.9.1.10 antt 6.9.1.11 fot llenver Valley Povet Station Unit 1 License flo. Drit 66 and ik/w' t Valley Povet Station Unit 2 1.icense No. NPF-73.
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Sieber ice Plesident Nuclent Gloup
. lull / l a i Enclosule ces tini ted States Nuclear Regulatory Commission P,egional Administratot, Region 1 475 Allendale Road King of I'i ussia, PA 10406 lini ted States Nuclear Regulatory Commission lit t. i d e n t inspectot bea'c e t Valley Pover Station Hs. Dottle Shotman l
Amet ican Nuclear Insurer's Library The Exchange Suite 245 l
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Fat mingion, CT 06032 conttal File v/o enclosure 9Ih,202 9105060114 901231 1, [] y g [ 6 PDR ADOCK 05000334
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1990 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL - YOLUME #2 DUQUESNE LIC}rr COMPANY BEAVER VALLEY POWER STATION c
UNITS 1 AND 2 i
DUQUESNE LIGlIT COMPANY 1990 Annual Radiological Environmental Report i
EXECUTIVE
SUMMARY
This report describes the Radiological Environmental Monitoring Program conducted during 1990 in the vicinity of the Beaver Valley Power Station Units 1 and 2.
The Radiological Environmental Program consists of off site monitoring of water,
- air, river sediments,
- soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1990.
Duquesne Light Company operates the Beaver Valley Power Station Units 1 and 2 pressurized water reactors as part of the Central Area Power Coordination Group.
The Beaver Valley Power Station Unit 1 operated throughout 1990.
The highest average daily output generated during the year was 838 megawatts net in January, 1990, and the total gross electrical generation during the year was 6.563,040 megawatt hours, Beaver Valley Power Station Unit 2 was shutdown on September 3, 1990 for the Second Refueling Outage.
Unit 2 was returned to service on November 22, 1990 and operated throughout the year.,
The highest average daily output generated during the year was 823 megawatts net in December, 1990, and the total gross electrical generation during the year was 4,570,700 megawatt hours.
i-
DUQUESNE LIGHT COMPANY 1990 Annual Radiological Euvironmental Report EXECUTI\\T,
SUMMARY
(continued)
In 1990, s amples were taken from over 60 sites around Beaver Valley Power Station that included the aquatic, atmosphetic and terrestrial environments.
More than 3,000 analyses were performed on these samples.
During the year, the radioactive releases from BVPS Units 1 and 2 did not exceed the Limiting Conditions for Operation identified in the Beaver Valley Power Station Operating License Technical Specifications for Unita 1 and 2.
Based upon the estimated dose to individuals from the natural background radiation exposure, the incremental increase in total body dose to the 50 mile population (4 million people),
from the operation of Beaver Valley Power Station Unit No. 1 and No. 2, is less than 0.0001% of the annual background.
See Section V.! for specific details. The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) is 296 mrem per year.
The environmental monitoring program outlined in the Beaver Valley Power Station Units 1 and 2 Technical Specifications was-followed throughout 1990.
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.
11-
DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report
, TABLE OF CONTENTS tara t
EXECUTIVE
SUMMARY
- * - -= *
=
- - -==-
1 1.
INTRODUCTION - =-
A.
Scope and Objectives of the Program 1
B.
Description of the Beaver Valley Site 1
II.
RESULTS & CONCLUSIONS.-
++- ----
6 III.
ENVIRONMENTAL MONITORING CONSIDERATIONS ---
a-8 A.
Environmental Quality Control Programs 8
B.
Evaluation of the Quality Control (QC) Program Data 24 C.
Standard Requirements ar.3 Limitations for Radiological and Other Effluents 24 D.
Reporting L6vels 25 IV.
MONITORING EFTLUENTS --
26 A.
Monitoring of Liquid Effluents 26 1.
Effluent Treatment, Sampling, and Analytical l
Procedures 32 2.
Results 32 B.
Monitoring of Airborne Effluents 33 1.
Description of Airborne Effluent Sources 33 2.
Airborne Effluent Treatment and Sampling 37 3.
Results 41 C.
Solid Waste Disposal 42
-111-
DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report TABLE OF CONTENTS (Continued)
V.
ENVIRONMENTAL MONITORING PROGRAM M
A.
Environmental Radioactivity Monitoring Program 44 1.
Program Description 44 2.
Summary of Results 51 3.
Quality Control Program
$1 B.
Air Monitoring 67 e
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 Foodcrops 77 2.
Sampling Program and Analytical Techniques 77 3.
Results and Conclusions 80 E.
Monitoring of Local Cow's Milk 82 1.
Description - Milch Animal Locations 82 2.
Sampling Program and Analytical Techniques 82 3.
Results and Conclusions 86
-iv-1
DUQUESNE LICitT COMPANY l
1990 Annual Radiological Environmental Report TABLE OP CONTENTS (continued)
V.
ENVIRONMENTAL MONITORING PROGRAM (continued)
Page F.
Environmental Radiation Monitoring 88 1.
Description of Regional Background Radiation Levels and Sources 88 2.
Locations 6 Analytical Procedures 68 3.
Results and Conclusions 89 G.
Monitoring of Fish 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 1.
Description of Water Sources 98 2.
Sampling Program and Analytical Techniques 99 3.
Results and Conclusions 102 I.
Estimates of Radiation Dose to Man 106 1.
Pathways to Man - Calculational Models 106 2.
Results of Calculated Radiation Dose to Man - Liquid Releases 107 3.
Results of Calculated Radiation Dose to Man - Airborne Releases 110 4.
Conclusions Beaver Valley Power Station 111 Appendix I Contractor Laboratory EPA Interlaboratory Comparison Program Appendix II QC Laboratory EPA Interlaroratory Comparison Program
.v.
DUQUESNE L30HT COMPANY 1990 Annual Radiological Environmental Report q
LIST OF TIGURES j
Figure No.
[ag_e 1.0 View of the Beaver Valley Site 3
1.1 Geographical Map - 40 Mile Radius 4
- 4.1 Liquid. Discharge Points to Ohio River 27 4.2 Water Flow Schematic -
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 \\ alley Power Station Unit 1 30.
-4.5 Liquid Rsdwaste Systems -
- )
Beaver-V.(11ey Power Station Unit 2 31 4.6 Gaseous Weste Processing.
Beaver Valley Power Station Units 1 and 2 35 4.7' Gaseous Release Points -
- 4.8 ~
Beaver Valley-Power Station Units ~1 and 2 36 Solid Waste Disposal-Diagram 43 S.B.1-Environmental Monitoring Locations - Air Sampling Stations 69 5.B.2 Concentrations of Gross Beta in-Air Particulates 71-5.C.1 Environmental Monitoring. Locations Sediments 74 5.D.1 Environmental: Monitoring Locations - Feederop and Fooderop 78 s
5.E.1 Dairy Farm Locations (August --September 1990 Survey) 84 5.E.2 Environmental Monitoring Locations - Milk 85 15.F.1 Environmental Monitoring Locations - TIbs 90 5.F.2 Environmental Monitoring Locations TLDs 911 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-I s
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r DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report LIST OF TABLES Table Number Page III.1 Quality Control Data TLD Comparisons 9
111.2 Quality Control Data Water Split Samples 10 III.3 Quality Control Data Split Samples - Miscellaneous 12 III.4 Quality Control Data - Spiked Samples 16 111.5 Quality Control Data - Spiked Samples 17 III.6 Quality Control Data - Air Particulates and I-131 18 III.7 Quality Control Data - Milk and Vater 22 IV.A.1 Effluent Treatment. Sampling and Analytical Procedures Beaver Valley Power Stat 10n 32 IV.A.2 Results_- Liquid Effluents - Beaver Valley 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 Monitorint Program Results (1990) 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 -
Liquid Releases 109 V.I.3 Results of Calculated Radiation Dose to Man -
Beaver Valley Power Station - Airborne Releases 112 vil-
SECTION I DUQUT.SNE LIGHT COMPANY 1990 Annual Radiological Enviroamental Report j'
I.
INTRODUCTION A.
Scope and Objectives of the Program The envitonmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaves Valley Power Station.
Environmental sampling and analyses included air, water, milk, soil, vegetation, river sediments,
- fish, and ambient radiation levels in areas surrounding the rite. The results of these media are assessed to determine impacts of the plant operation on the environment. The Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1990.
B.
Description of the Beaver Valley Site The Beavec Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport. Beaver County, Pennsylvania, on a 501 acre tract of land.
Figure 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 af the site is relatively low. The population uithin 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, Prnnsylvania, with a population of approximately 4,300.
The site lies in a valley along the Ohio River.
It extends from the river (elevation 665 fe'et above sea level) to a ridge along the border south of the Beaver Volley Power Station at an elevation of 1,160 feet.
Plant ground level is approximately 735 foot above sea level.
The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream f rom New Cumberland Lock and Dam.
The Pennsylvania-Ohio-West Virginia border is located 5,2 river miles downctream 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 minimum of approximately 5000 cubic feet per ranges from a second (CFS) to a maximum of approximately 100,000 CFS.
The mean annual flow is approximately 25,000 CFS.
1
SECTION I DUQUESNE LIGHT COMPANY 1990 Annual Rcdiological Environmantal Rsport I
I.
INTRODUCTION B.
Description of the Beaver Valley Site (continued)
Water temperature of the Ohio River varies from 32'F to 84*F, the minimum temperatures occur in January and/or February and maximum temperatures in July and August. Water quality in the Ohio River at the site location is affected primarily 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 inches, typical yearly temperatures vary from approximately -
3'F to 95*F with an annual average temperature of 52.B'F.
The predominant wind direction is typically from the southwest in summer and from the northwest in winter. 4 1
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SECTION I DUQUESNE LIGHT CC# PANy FIGURE 1.I 1990 Annual Radiological En..ronmental Report 40 T03 CST 09,1
'2 NEW CASTLE ALLIANCE
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Ci:1es GEOGRAPHICAL l TAP AND PRINCIPAL CO t! UNITIES IN 40-:!ILE RADIUS OF THE BEAVER VALLEY POWER STATION FIGUPI 1.1 l
l SECTION I DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report I.
INTRODUCTION B.
Description of the Beaver Valley Site (continued) l The design ratings and basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below:
Beaver Valley Unit 1 Beaver Valley Unit 2 Thermal & Elec, Rating (Not MV,)
2660 MV 835 MW 2660 tN 836 MV, t
g Type of Reactor PVR PWR No. of Reactor Coolant Loops 3
3 No. of Steam Generators & Type 3 - Vertical 3 - Vertical Steam Used by Main Turbine Saturated Saturated The units utilize two separate systems (primary and
, secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator).
Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the-primary system water is normally isolated from the secondary system.
Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical-generator.
The steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam / water cycle.
megawatts thermal NOTE:
MV.
g MV, megawatts electrical
SECTION II DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report j
II. RESULTS AND CONCLUSIONS Plant operations at the Beaver Valley Power Station had no adverse effects on the environment as a result of activity at the station during 1990.
The Beaver Valley Power Station Unit 1 operated throughout 1990.
on September 3,
Beaver Valley Power Station Unit 2 was shutdown 1990 for the Second Refueling Outage. Unit 2 was returned to service on November 22, 1990 and cper ated throughout the year.
During the year, the radioactive releases were below the limits of 10 CFR Part 50 Appendix 1.
The releases at Beaver Valley Power Station Units 1 and 2 did not exceed the limiting conditions identified in the Beaver Valley Power Station Units 1 and 2 Operating License Technical Specifications.
The environmental program for 1990 was the same as in 1989 except for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications.
(Refer to Table V.A.1 for the 1990 Radiological Monitoring Program Outline).
The Beaver Valley Power Station Technical Specifications require sampling of three (1) dairies which have the highest calculated milk pathway potential and one large ;ocal dairy. The three dairies are determined from calculations based on the meteorological data and the latest milch animal survey. However, these dairies are frequently small, consisting of as few as one cow or goat. The availability of milk from single cow dairies and revisions due to upcated calculations and surveys normally result in sampling of several additional dairies during the year in different sampling periods.
The Environmental Monitoring Program also includes two larger dairies in order to provide continuity in the sampling / analyses program and a control location, Samples from each of these dairies-are obtained in addition to the four dairies required by the Environmental Technical Specifications.
The collection periods associated with each of the locations are provided in the detailed summary of the milk monitoring program of this report (Section V-E).
6-
SECTION II DUQUESNE LicitT COMPANY 1990 Annual Radiological Environmental Report
- 11. RESULTS AND CONCLUSIONS (continued)
Activity' detected was attributable to naturally occurring radionuclides, BVPS effluents, 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.
The results and conclus!Sns for each media of the 1990 Radiological Environmental Monitoring Program are contained in Section V of this report.
A summary of the 1990 operational environmental data is found in Table V.A.2 and a summary of preoperational data (1974-1975) environmental data is found in Table V.A.3.
Examination of effluents from the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and Station Technical Specifications.
, l
SECTION 181 DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report III.
ENVIRONMENTAL MONITORING CONSIDERATIONS A.
Environmental Quality Control Programs The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) elements.
It should be noted that the comparisons made were at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure.
However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.
1.
TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and QC Laboratory)
Thirteen (13) TLDs from the Contractor Laboretory and QC Laboratory are co-located, replaced quarterly and results compared.
The average of the contractor laboratory and the average of the quality control laboratory agree within i 7.8% of the mean of all results.
This is well within the precision of typical TLD Systems.
Summary data of the TLD Monitoring Program is provided in Table III.1.
2.
Split Sample Program (DLC Contractor Laboratory - DLC QC Laboratory)
Samples of surf ace (river) water and drinking water were routinely split and analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory.
In addition, samples of other media, such as milk, soil, sediment and feederop were also split with the DLC QC Laboratory.
A summary of results of split water samples is provided in Table III.2.
In 1989, five (5) of eight (8) split drinking and surface water samples analyzed for Gr-B were not in agreement. The disagreement in the Gr-B split water samples was attributed to differences in the analytical procedures used by the two laboratories.
Subsequently, an investigation attributed the primary differences to the self absorbtion curves utilized by contractor and QC laboratories.
See Appendix I.
In 1990, two (2) of eight (8) split drinking and surface water samples -analyzed for Gr-B were not in agreement which was an improvement over the 1989 results.
The 1991 results will be closely monitored for unacceptable trends or results'to assure the problem has been corrected.
The two (2) spiked Gr-B water samples and EPA Interlaboratory Cross Check Program Gr-B results are in agreement.
See Appendix I and II.
A summary of milk, sediment and f eed/ food crop split samples is provided in Table III.3.
Some variation may be expected due to small variations in duplicate samples, variations in analytical procedures, and in calibration, source type, etc.
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Secticn III DUQUESNE LIGHT COMPANT TABLE III.A 1990 Annual Radiological Environmental Report TABLE III.1 QUALITY CONTROL RESULTS TLD HONITORING mR/ DAY 1ST QUARTER 2ND OUARTER DLC DLC - OC DLC DLC - OC Contractor Lab Contractor Lab Location #
(CaSO :Dy)
(CaSO :Dy)
Location #
(CaSO Dy)
(CaSO :Dy) 4 4
4 4
10 0.18 0.17 10 0.15 0.18 13-0.15 0.16 13 0.15 0.16 14 0.17 0.17 14 0.15 0.17 15 Lost Lost 15 0.12 0.15 27 0.16 0.18 27 0.16 0.18 28 0.18 0.18 28 0.16 0.18 29B 0.20 0.21 29B 0.19 0.20 32 0.18 0.19 32 0.18 0.20 45 0.16 0.19 45 0.15 0.20 46 0.13 0.14 46 0.14 0.14 47 0.19 0.21 47 0.17 0.23 48 0.17 0.22 48 0.15 0.19 51 0.18 0.19 51 0.16 0.19 3RD OUARTER 4TH OUARTER DLC DLC - OC DLC DLC - QC Contractor Lab Contractor Lab Location 8 (CaSO :Dy)
(CaSO :Dy)
Location #
(CaSO :Dy)
(CaSO tDy) 4 4
4 4
10 0.14 0.17 10 0.15 0.16 13 0.15 0.17 13 0.15 0.15 14 0.15 0.17 14 0.16 0.16 15 0.12 0.15 15 0.12 0.13 27 0.14 0.15 27 0.15 0.16 28 0.16 0.17 28 0,,16 0.16 29B 0.17 0.21 29B 0.19 0.1A 32 0.17 0.19 32 0.17 0.18 45 0.14 0.18 45 0.17 0.19 46 0.13 0.15 46 0.13 0.16
-47 0.18 0.20 47 0.16 0.18 48 0.15 0.19 48 0.16 0.16 51 0.17 0.19 51 0.15 0.16 ANNUAL DLC DLC - OC Contractor Lab Location #
(CaSO :Dy)
(CaSO tDy) 4 4
10 0.15 0.15 13 0.14 0.14 14 0.14 0.15 15 0.12 Lost 27 0.14 0.15 28 0.15 0.15 29B 0.17 0.17 32 0.16 0.16 45 0.14 0.14 46 0.13 0.14 47 0.15 0.17 48 0.14 0.15 51 0.15 0.14
_9_
I
Scction III DUQUESNE LICHT COMPANY TABLE III.2 1990 Annual Rcdiological Environmental Report (Page 1 of 2)
TABLE III.2 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison Of Contractor And DLC-0C Labs DLC Sampling Contractor DLC - OC Hedia
_ Analysis Period Lab (1)
Lab (1)
Units Surface Vater Gross Alpha January 3 2.0 f 0.3 pC1/1 April
$ 1.6 5 0.5 pC1/1 July 5 1.9 3 1.4 pCi/l October 3 2.0
$ 0.9 pCi/l Surface Vater Gross Beta January 11 1 2 4.2 1 0.5*
pCi/l April 8.9 1 1.6 3.0 1 0.2 pC1/1 July 9.0 : 1.8 3.8 1 0.7 pC1/1 October 7.5 3 1.3 4.0 1 0.4 pC1/1 Surface Vater Co-60 January
$3 f 4.1 pCi/l April f3
$ 5.2 pC1/1 July
$3
$ 1.6 pCi/l October 55
$ 1.9 pCi/1 Surface Vater Cs-134 January
$3 3 3.4 pC1/1 April f3 1 3.7 pCi/l July
$3
$ 1.3 pCi/1 October
$5 3 2.0 pC1/1 Surface Vater Cs-137 January
$4 3 4.5 pci/l April j3
$ 3.9 pCf/1 July
$3
$ 1.6 pCi/l October f6 3 2.2 pCi/l Surface Vater Tritium ist Quarter 190 1 110 192 1 69 pCi/l Composite 3rd Quarter 11000 g 1000 11373 1 305 pC1/1 Composite Surface Vater Sr-89 2nd Quarter f 1.3 3 0.9 pC1/1 Composite 4th Quarter
$ 1. 3
$ 1.0 pCi/l Composite surface Vater Sr-90 2nd Quarter 3 0.24 0.6 1 0.4 pCi/1 Composite 4th Quarter f0.2
$0.5 pC1/1 Composite Surface Vater Co-60 2nd Quarter f1.0 f 1.8 pC1/1 (high composite sensitivity 4th Quarter 3 1.0 f 1.7 pCi/l analysis)
Composite (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval.
i
- See Section III A.2 _____-____ -
S3cti:n III DUQUESNE LIGHT COMPANT TABLE III.2 1990 Annu21 Radicicgical Envirent ntol R0 Pert (P0g3 2 of 2)
TABLE III.2 (Continued)
QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison Of Contractor And DLC-0C Labs DLC Sampling Contractor DLC - OC Media Analysis Period Lab (1)
Lab (1)
Units Drinking Vater Cs-137 February
<6
< 4.4 pCi/l (veekly split)
May 36 36.0 pC1/1 August
$6 5 4.4 pCi/l November 53 3 2.5 pCi/l Drinking Vater Cs-134 February 36 3 3.5 pC1/1 (veckly split)
Hay
$6 5 5.2 pC1/1 August
<5
< 3.5 pC1/1 November
$3 32.2 pCi/1
~
Drinking Vater Co-60 February
<6
< 3.4 pC1/1 (veekly split)
.May
$6 35.1 pCi/l
~
August
<5
< 3.2 pC1/1 November 33 32.8 pCi/l Drinking Vater Gross Alpha March
< 1.5
< 1.0 pCi/1 (monthly June i 1.7 i 0.6 pCi/l composite)
August I 1.8 I 1.R pC1/1 November 31.6 31.8 pCi/l Drinking Vater Gross Beta March 12 + 2 2.8 + 0.5*
pCi/1 (monthly June 4.1 ~ 0.7 2.3 ~ 0.4 pCi/l 1
1 composite)
August 4.6 g 1.1 2.4 3 1.0 pCi/1 November 4.6 1 1.4 2.1 1 0.7 pCi/l Drinking Vater Tritium 2nd Quarter
< 100
< 122 pCi/1 4th Quarter 3200 3177 pCi/1 (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval.
l
- See Section III A.2. _ _ _ _. __
Ssetion III DUQUESNE LIGHT COMPANT TABLE III.3 1990 Annuni Radiological Environmantal Report (Page 1 of 2)
TABLE III.3 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison Of Contractor And DLC-QC Labs DLC Sampling Contractor DLC - OC Med i e.
Analysis Period Lab (1)
Lab (1)
Units Milk Sr-89 3/19/90
$1.5 5 0.6 pCi/1 (Location 25)
Sr-90 3/19/90 1.1 1 0.3 2.0 3 0.4 pCi/l I-131 3/19/90 3 0.16 3 0.3 pCi/1 K-40 3/19/90 1270 1 130 1230 1 110 pC1/1 Co-60 3/19/90 35 3 5.5 pCi/1 Cs-134 3/19/90
$4
$ 4.2 pri/1 Cs-137 3/19/90
$4 f 4.8 pCiil Feed I-131 6/8/90
$ 0.006 3 0.009 pci/gm (dry)
(Location 25)
Be-7 6/8/90 2.63 3 0.30 2.6 1 0.1*
pC1/gm (dry)
K-40 6/8/90 19.3 1 1.9 17.6 1 0.6*
pC1/gm (dry)
Co-60 6/8/90
$ 0.03
$ 0.002 pCi/gm (dry)
Cs-134 6/8/90 3 0.03
$ 0.001 pCi/gm (dry)
Cs-137 6/8/90 f 0.03 f.0.002 pCi/gm (dry)
Feed Sr-90 6/8/90 0.11 3 0.01 0.068 3 0.015* pCi/gm (vet)
(Location 25)
Hilk I-131 6/12/90 3 0.26 f 0.3 pC1/1 (Location 25)
K-40 6/12/90 1250 3 130 1236 i 96 pC1/1 Co-60 6/12/90 f4
$ 3.7 pC1/1 Cs-134 6/12/90 f4
$ 3.4 pC1/1 Cs-137 6/12/90 34 f 4.6 pC1/1 Food 1-131 9/14/90 f0.042 f 0.049 pC1/gm (vet)
(Locntion 25)
K-40 9/14/90 1.95 g 0.2 2.38 1 0.28 pCi/gm (vet)
Co-60 9/14/90 3 0.01 5 0.014 pC1/gm (vet)
Cs-134 9/14/90
$ 0.01 f0.011 pCi/gm (vet)
Cs-137 9/14/90 f 0.01 f0.016 pCi/gm (vet)
(1) Uncertainties are based on counting statistics and are specified at the 957, confidence interval.
- See Section III B _ - _ _ _ _ _ _ _ _ _
Section III DUQUESNE LIGHT COMPANY TABLE III.3 1990 Annual Radiological Environmental Report (Page 2 of 2)
TABLE III.3 (continued)
OUALITY CORTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison Of Contractor And DLC-0C Labs DLC Sampling Contractor DLC - QC Hedia Analysis Period Lab (1)
Lab (1)
Units Hilk I-131 9/18/90 f 0.2 f 0,2 pC1/1 g'
(Location 25)
Sr-89 9/18/90 f 1.7 f 0.4 pC1/1 l
Sr-90 9/18/90 2.8 3 0.4 2.6 3 0.4 pCi/1 Cs-134 9/18/90 f4 f 1.4 pCi/1 Cs-137 9/18/90 f4 3 2.0 pC1/1 Co-60 9/18/90 f4 3 1.6 pCi/1 K-40 9/18/90 1280 1 130 1244 1 45 pCi/1 Sediment Gross Alpha 10/28/90 17.0 3 6 12.8 3 3.9 pCi/gm (dry)
(Location 2A) Gross Beta 10/28/90 59.0 g 4 44,0 3 3.8 pC1/gm (dry)
Sr-89 10/28/90
$ 0.13 3 0.011 pCi/gm (dry)
Sr-90 10/28/90 3 0.18 0.025 1 0.007 pCi/gm (dry)
Co-58 10/28/90 33.2 1 3.3 50.0 1 0.2*
pCi/gm (dry)
Co-60 10/28/90 3.67 1 0.37 4.71 1 0.05 pCi/gm (dry)
Cs-134 10/28/90
$ 0.1 3 0.045 pCi/gm (dry)
Cs-137 10/28/90 0.28 1 0.092 0.46 1 0.04*
pCi/gm (dry)
K-40 10/28/90 14.6 1 1.5 15.8 1 0.3 pCi/gm (dry)
Ra-226 10/28/90 1,91 $ 2 4.3 1 0.6*
pCi/gm (dry)
Th-228 10/28/90 1.22 g 0.12 1.9 1 0.1-pC1/gm (dry)
Hilk I-131 12/11/90
$ 0.15 3 0.3 pC1/1 (Location 25)
K-40 12/11/90 1380 1 140 1310 1 131 pCi/1 Co-60 12/11/90 34 5 6.5 pCi/1 Cs-134 12/11/90
$4 36.9 pC1/1 Cs-137 12/11/90 f4 16.3 pCi/1 (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval.
- See Section III B _ - - - - -_____- _ _-_-_ - ___
SECTION III DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING PROGRAMS A.
Environmental Quality Control Programs (continued) 3.
DLC QC Laboratory Program Spiked samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for analysis. Tables III 4 (water) and III.5 (milk) provide data from this portion of the QC 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 the QC program.
5.
Contractor and QC Laboratory - Internal QC Program The Contractor and QC Laboratory maintained their own QC Program which included participation in the Environmental Environmental Protection Agency EMSL)
Monitoring Safety Laboratory (EPA 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' II.
DLC also. audited the Contractor and QC Laboratory and determined that internal QC practicos were in effect and that procedures and laboratory analytical techniques conformed to
. approved DLC procedures. -
SECTION III DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report III.
ENVIRONMENTAL MONITORING CONSIDERATIONS A.
Environmental Quality Control Programs (continued) 6.
Special QC Program (DLC Contractor Laboratory Independent Laboratory - DLC QC Laboratory) i Milk and water samples were prepared by an Independent Laboratory.
This included low level spiking of specified puclides.
]he prepared samples were split three ways and analyzed by the DLC-QC Lib 6rdtory ind Independent Laboratory as well as the Contractor Laboratory. A summary of results of this portion of the QC program is provided in Table 111.7.
5 i
^^^
Section III DUQUESNE LIGHT COMPANT TABLE III.4 1990 Annual Radiological Environmental Report TABLE III.4 QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS RESULTS DLC Sample Type Contractor OLC - OC Sample Date Ident. No.
6 Analysis Lab (1)
Lab (1)
Units 4/24/90 V-61 Vater: Sr-89 21.0 1.0 17.9 : 5.5 pCi/1 St-90 25.0 1 2.0 19.4 1 2.5 pC1/1 4/30/90 V-62 Vater Cs-134 20.7 3 6.1 20.0 1 0.2 pct /1 Cs-137 28.2 3 4.5 28.7 1.4 pC1/1 Co-60 11.5 1 4.3 8.7 0.4 pCi/1 4/30/90 V-63 Vater: I-131 44.0 3 2.0 63.5 3 8.0 pC1/1 4/30/90 V-64 Vater: H-3 1900 1 100 1941 1 13 pC1/1 6/30/90 V-68 Vater: Gross Alpha 10.0 0.2 9.8 0.3 pC1/1 Gross Beta 12.0 : 1 11.4 3 0.6 pCi/1 9/28/90 V-69 Vater Sr-89 19 1
17.7 1 1.6 pC1/1 St-90 17 2 1 13.9 1 1.6 pCi/1 10/15/90 V-70 Vater: H-3 2400 100 2355 59 pC1/1 10/15/90 V-71 Vateri 1-131 40 1
55.9 : 0.9*
pCi/1 10/31/90 V-73 Vater: Co-60 19.0 4.5 18.3 1 2.7 pC1/1 Cs-134 24.6 4.9 28.3 1 2.3 pC1/1 Cs-137 23.0 1 4.1 22.7 2 2.3 pC1/1 12/31/90 V-74 Vater Gross Alpha 24 3 2 21.4 1 1.0 pCi/1 Gross Beta 20 1 1 25.9 3 1.0 pC1/1 (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval.
- See Section III B __
DUQUESNR LIGHT COMPANT
. TABLE III.5-
~
S:cticn:III' 1990 Annus11R:diological Environnntal Roport-
!l TABLE III.5 1
QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS DLC Sample Type Contractor DLC - QC' y
- Sample Date- -Ident. No.
& Analysis Lab (1)
Lab (1)
Units j
1/30/90 MI-26 Milk Sr-89
< 1.7 12.8 g 1.6* -
pC1/1 Sr-90 3.2 g 1.6 23.6 g 5.0*
pC1/1 K 1120 g 110 1162 2 29 pC1/1 q
Cs-134
-16.1_3 4.0-19.3 1.0 pC1/1 Cs-137 26.2 3 3. 7-25.2 g 1.2 pC1/1 3/5/90 MI-28 Milk I-131 45 1
63.8 3 2.2*-
pC1/1 4/30/90 MI-29 Milk: 1-131-43.3 g 3 90.7 g 9.2*
pC1/1 K-40 1220 1 120 1213 3 15 pC1/1 Cs-134-20.4 1 4.5 18.3 g 1.0 pC1/1 Cs-137 19.7 3 4.2 20.3 1 1.0 pC1/1 7/30/90 MI-30 Milkt Sr-89 19.0 g 4.0 12.8 1 0.4 pCi/l Sr-90.
16.0 g 3 18.2 1 1.4
-pC1/1 K-40 1290-1 130 1274 3 32 pCi/l Cs-134 42.0-3 4.2 46.0 g'1.3 pCi/1 Cs-137 28.7 3 4.7 27.6 3 1.3
'pCi/l 8/7/90 MI-31 Milk I-131 63 0 3 1.0 68.8 g 1.6' pCi/1 L10/15/90 MI-32 Milk I-131 27.0 g 1 34.8 g-0.2-pCi/1
%-40 1170 g 120 1207 1 46 pCi/1-Cs-134 26.3 g 3.6 25.8 y 1.2
-pC1/1 Cs-137 27.3'1 4.9 25.3 g 2.0-
-pC1/1 i
(1) Uncertainties are based'on counting statistics and are specified at the-95%
-coniidence. interval.
- See Section'III B hwrug1' u u in.r i
ui
Soction III DUQUESNE LIGHT COMPANT TABLE III.6 1990 Annuci Radiological Environmsntal Report (Pcge 1 of 4)
TABLE III 6 0UALITY CONTROL RESULTS AIR PARTICULATES AND CHARCOAL FILTER:
COMPARABLE SAMPLES Air Particulates Air Iodine pCi/Cu. Meter (Beta) pCl/Cu. Heter DLC DLC Contractor DLC - OC Contractor DLC - OC Sample Date Lab (1)
Lab (1)
Sample Date Lab (1)
Lab (1) 01/02/90
~
01/02/90 to
< 0.01
< 0.01 12/26/89 to 0.021 + 0.003 0.021 + 0.003
~
~
01/08/90 01/08/90 to 0.016 + 0.003 0.021 + 0.003 01/15/90 to
-< 0.01
< 0.02
~
01/15/90
~
01/22/90 01/22/90 to 0.015 + 0.003 0.017 + 0.003 01/29/90 to
< 0.01
~< 0.02
~
01/29/90
~
02/05/90 02/05/90 to 0.014 + 0.003 0.019 + 0.003 02/12/90 to
< 0.01
~< 0.01
~
02/12/90
~
02/20/90 02/20/90 to 0.013 + 0.003 0.012 + 0.003 02/26/90 to
-< 0.01
< 0.01
~
~
~
02/26/90 03/05/90 03/05/90 to 0.015 + 0.003 0.016 + 0.003 03/12/90 to
< 0.01
< 0.01
~
~
03/12/90'
~
03/19/90 03/19/90 to 0.014 + 0.003 0.018 + 0.002 03/26/90 to
< 0.01
~< 0.02
~
03/26/90
~
04/02/90 04/02/90 to 0.011 + 0.003 0.010 + 0.003 04/09/90 to
< 0.01
< 0.01
~
~
~
~
04/09/90 04/16/90 04/16/90 to 0.018 + 0.003 0.015 + 0.003 04/23/90 to
-< 0.01
< 0.01
~
04/23/90
~
04/30/90 04/30/90 to 0.010 + 0.002 0.014 + 0.003 05/07/90 to
-< 0.01
-< 0.01
~
~
05/07/90 05/14/90 05/14/90 0.011 + 0.003 0.014 + 0.002 05/21/90 to
< 0.01
< 0.01
~
~
~
05/21/90 05/29/90 4
05/29/90 to 0.016 + 0.003 0.014 + 0.003 06/04/90 to
-< 0.01
~< 0.01 06/04/90 06/12/90 06/12/90 to 0.018 1 0.003 0.017 1 0.003 06/18/90 to f 0.01 3 0.01 06/18/90 06/25/90 06/25/90 to 0.016 1 0.003 0.021 1 0.003 07/02/90 to
$0.01 3 0.01 07/02/90 07/09/90 (1) Uncertainties are based on counting statistics and are specified at the 95%
l confidence interval. _ _ _ _ _ - _ _ _ _ - _ _
Section III DUQUESNE LIGHT COMPANT TABLE III.6 1990 Annual Radiological Environmental Report (Page 2 of 4)
TABLE III.6 (continued) 00ALITY CONTROL RESULTS AIR PARTICULATES AND CHARCOAL FILTER:
COMPARABLE SAMPLES Air Particulates Air Iodine pCi/Cu. Meter (Beta) pCi/Cu. Meter DLC DLC Contractor ptC - OC Contractor DLC - OC Sample Date Lab (1)
Lab (1)
Sample Date Lab (1)
Lab (1).
07/09/90 to 0.010 + 0.002 0.007 + 0.002 07/16/90 to
< 0.01
< 0.01
~
~
~
07/16/90 07/23/90
~
07/23/90 to 0.015 + C.003 0.015 + 0.004 07/30/90 to
< 0.01
< 0.01
~
~
~
07/30/90 08/06/90 08/06/90 to 0.021 + 0.003 0.020 + 0.003 08/13/90 to
< 0.01
< 0.01
~
~
~
08/13/90 08/20/90
~
08/20/90 to 0.009 + 0.003 0.008 + 0.003 08/27/90 to
< 0.01
< 0.01
~
~
~
~
08/27/90 09/04/90 09/04/90 to 0.021 + 0.003 0.022 + 0.004 09/10/90 to
< 0.01
< 0.01
~
~
~
09/10/90 09/17/90
~
09/17/90 to 0.011 + 0.003 0.016 + 0.003 09/24/90 to
< 0.01
~< 0.01
~
~
~
09/24/90 10/02/90 10/02/90 to 0.016 + 0.003 0.027 + 0.004 10/09/90 to
< 0.01
< 0.01
~
~
~
10/09/90 10/15/90
~
10/15/90 to 0.022 + 0.003 0.019 + 0.003 10/22/90 to
~< 0.02
< 0.01
~
~
~
10/22/90 10/29/90 10/29/90-to 0.031 + 0.003 0.034 + 0.004 11/05/90 to
< 0.01
< 0.01
~
~
~
11/05/90 11/12/90
~
11/12/90 to 0.023 + 0.003 0.025 + 0.003 11/19/90 to
< 0.02
< 0.01
~
~
~
-11/19/90 11/26/90
~
11/26/90 to 0.022 + 0.003 0.023 + 0.003 12/03/90 to
< 0.01
< 0.01
~
~
~
12/03/90 12/11/90 12/11/90 to 0.015 + 0.003 0.019 + 0.003 12/18/90 to
< 0.02
< 0.01
~
~
~
12/18/90 12/24/90
~
12/24/90 to 0.017 3 0.003 0.020 g 0.003 12/31/90 (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval. --_
Section III DUQUESNE LICIIT COMPANT TABLE III.6 U/90 Annual Radiological Environmental Report (Page 3 of 4)
TABLE III.6 QUALITY CONTROL AIR PARTICULATES (pCi/m )
DLC Contractor DLC - QC Sample Date Nuclide Lab (1)
Lab (1)
January Be-7 0.075 1 0.013 0.072 1 0.018 Others LLD LLD Harch Be-7 0.095 + 0.017 0.079 + 0.012 Others LLD LLD
~
~
Hay Be-7 0.087 1 0.015 0.087 1 0.015 Others LLD LLD July Be-7 0.089 3 0.017 0.094 1 0.018 Others LLD LLD September Be-7 0.114 1 0.015 0.055 1 0.019 Others LLD LLD November Be-7 0.130 + 0.014 0.081 + 0.016
~
~
Others LLD LLD (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval.
LLD - Lover Limit of Detection _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 111.0 Section III DUQUESNE LIGHT COMPANY (Page 4 of 4) 1990 Annual Radiological Environmental Report TABLE III.6 00ALITY CONTROL AIR PARTICULATE AND CHARCOAL FILTER 3)OMPARA C
LOCATION 30 - (pci/m DLC Contractor DLC - OC Sample Date Nuclide Lab (1)
Lab (1) ist Quarter Composite Sr-89 3 0.0009 5 0.0004 Sr-90 3 0.0001 3 0.0003 2nd Quarter Composite St-89
$ 0.0009 3 0.0006 St-90 3 0.0002 3 0.0005 3rd Quarter Composite St-89 3 0.0002 30.0003 St-90 f 0.0002 3 0.0003 4th Quarter Composite Sr-89 3 0.0006 3 0.0002 Sr-90
$0.0001 30.0002 (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence interval. --
Soction III DUQUESNE LICHT COMPANT TABLE III.7 1990 Annual Radiological Environmental Report (Page 1 of 2)
TABLE III.7 OUALITY CONTROL DATA OC Sample Comparisons (All Analyses In pCl/1)
DLC Sample Type Independent Contractor DLC - QC Sample Date Ident. No.
& Analyses Lab (1)
Lab (1)
Lab (1) 2/28/90
$3-303 Vater Sr-89 21 1 2 16 3 1 7.1 1 1.4*
St-90 21.3 3 0.7 19 3 2 16.0 1 3.5 I-131 9.0 3 0.2 8.0 1 0.5 11.3 1 1.3 Cs-134 17 3 11 24.6 3 3.7 22.7 1 1.6 Cs-137 29 3 11 32.5 3 4.4 32.3 3 1.2 2/28/90 53-304 Vater s 11-3 1000 1 200 940 1 90 1058 3 17 5/2/90 53-305 Vater: St-89 13.0 1 1.3 11 g 1 7.9 1 1.6 Sr-90 13.0 1 0.7 11 1 2 12.2 1 0.2 I-131 18.9 3 0.2 19 3 1 25.6 1 1.0 Cs-137 11 1 6 12.9 3 3.7 16.1 1.2 Co-60 9 1 8 19.9 3 4.3 14.4 3 0.9 5/2/90 53-306 Vater H-3 1700 1 200 1200 3 100 1578 3 27 8/7/90 53-307 Vater Sr-89 20 1 2 19.0 1 1 15.4 3 4.1 St-90 22.7 1 0.6 24.0 3 1 25.3 1 0.3 I-131 13.7 3 0.3 11 1 1 17.3 3 1.4 Hn-54 31 1 4 35.9 1 4.7 40.6 1 2.4 Cs-137 19 3 3 28.7 3 4.3 28.9 3 2.0 8/7/90 53-308 Vater: H-3 2020 3 80 2200 g 200 2146 1 40 10/30/90 53-309 Vater: Sr-89 16.3 1 1.2 15 3 3 11.0 1 1.2 Sr-90 12.6 1 0.6 14 1 1 10.7 3 1.0 I-131 16.7 1 0.4 20 g 1 27.1 1 0.8*
Cs-137 10 3 3 21.3 2 3.7*
18.9 1 1.6 Co-60 12 3 4 11.0 2 3.7 13.2 3 n,7 10/30/90 53-310 Vater: H-3 480 1 70 560 2 60 498 1 29 (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence level.
- See Section III B _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ - _ - _ _
1 S cticn III DUQUESNE 1IGirf COMPANY -
TABLE III.7.
1990' Annual R:diolcgical-Enviren30ntal Report (Pego 2 of 2).
~ TABLE III.7 QUA!ITY CONTROL DATA QC Sample comparisons (All Analyses In pC1/1)
DLC-i
Sample Type Independent contractor DLC - 00
. Sample Date Ident. No.
& Analyses Lab (1)
Lab (1)
Lab (1) - '
2/28/90 52-254 Milk: Sr 10 1 3 3.7 3 1.7 4.0 1 0.6 Sr 16.3 3 0.7 12 g 2 12.6 1 1.6 I-131 10.2 g 0.2 12 g 1 12.4 g 1~.4 Cs 134 25 g 4 20.8 g 5.6 23.9_g 0.3 Cs-137 21 g 3 31.1 i S.2 32.8 g 2.0 K-40 1330 1 90 1330 1 130 1221 1-36
-5/2/90 52-255 Milk: Sr-89
-24 1 2 20 1 2 21.5 g-1.4J Sr-90 23.7 1 0.8 27 1 1 24.4 g_1.2,
1-131 16.8 1 0.2 20 1 1 25.8 1 2.9A Cs-134 16 g 2 20.1_1 8.3 19.9
_0.2 Cs-137 15 1 2 17.5 i_9.4-18.8 g 0.8 K-40 1290 g 90 1350 g 140 1187 g 35 8/7/90 52-256 Milk Sr-89 8 1 2-7.6 3 1.3 8.7 1 2.3
~
Sr-90 14.0 1 0.5 10.0 31 12.9 3 0.4 I-131 13.2 g 0.2 13 3 1 16.8 3' O.1 Cs-134 12 g-3 14.4 g 3.6 12.0 i--0.6i Cs-137 11 1 3 14.0 1 3.8 14.7=1 1.0!
K-40 1180 1 90 1290' 130 1229 3 55 10/30/90-52-257 Milkt:Sr-89
-16 12 16 1 3-10.4.1-1.8; Sr-90 17.4 1 0.5
'13 11 11.1 g 0.1; I-131 11.1 i 0.'13 6.7 1 0.6 16.7 1 0.4s Cs-134 11-1 3 10.9 3l4.4:
'12.0 g(1.5 Cs-137' 15 1 3 17.7 i 3.5.
17.8 1 ;1. 5l K-40 1200 + 90 1280 + 130-1223 + 14 >
d (1) Uncertainties are based on counting statistics and are specified at'the 95%-
confidence level.
- See Section III B i.
L s v
SECTION III DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report h
III. ' ENVIRONMENTAL MONITORING PROGRAM A.
Environmental Quality Control Programs (continued) 7.
Pennsylvania Department of Environmental Resources Program The Pennsylvania Department of Environmental Resources (PDER) also conducted a surveillance program in the i
vicinity of the site.
Samples of air, river water, drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program.
Comparison of results also indicated agreement between the PDER Laboratory and the Duquesne Light Company 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 satisfactorily in accordance with " Criteria for Comparing Analytical Measurements from NRC Compliance Office."
In addition, an independent laboratory =is used to supplement the
. regular prograhi.
Comparisons between the independent, QC and Contractor laboratories are acceptable and demonstrate a satisfactory performance by the DLC contractor.
All media were found to be in agreement in accordance with NRC criteria III.7 with the exception of those media in Tables III.2 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 1990 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 I
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 i
i established to further limit discharges to the-environment, l
1 SECTION Ill DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING PROGRAM C.
Standard Requirements and Limitations for Radiological and Other Effluents (continued)
Beaver Valley Power Station is subject to regulations which include the Code of Federal Regulations 10 CFR (Energy),
Pennsylvania Department of Environmental Resources (PDER)
Industrial Vaste Permit #0473211, Gaseous Discharge Permit
- 04-306-001, PA Code - Title 24, Part I, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No. 1-70 and 2-70 Environmental Protection Agency (EPA), National Pollution Discharge Elimination (NPDES) Permit #0025615, and the Beaver Valley Power Station Technical Specifications.
D.
Reporting Levels A
report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environtuental 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 detected in the sampling medium, this report shall be submitted if:
Concentration (1), Concentration (2) 4
.2 1.0 Limit Level (1)
Limit Level (2)
There were no analytical results of environmental samples during 1990 which exceeded Beaver Valley Power Station reporting levels.
25-
r?
]
i SECTIONllV DUQUESNE LIGHT COMPANY l
1990 Annual Radiological Environmental Report j
1 IV. MONITORING EFFLUENTS l
A.
' Monitoring of~ Liquid Effluents
-Description of Liquid Effluents at the Beaver Valley Power f
Station.
4 l
tios t of the water required for the operation of the Beaver l
Valley station is taken from the Ohio River, and returned to I
the,iver, used for makeup to various plant systems, consumed
-i by station personnel, or discharged via a sanitary waste system.
In addition, small amounts of well water and liquid effluents are discharged to the Ohio River using discharge points shown in Figure 4.1.
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 summarize radioactive liquid effluents at the Beaver Valley Power Station:
Table. IV.A.1 - Effluent Treatment, Sampling, and Analytical Procedures - Beaver Valley 1
Table IV.A.2-- Results of Liquid Effluent Discharges to the Environment - Beaver Valley 1
t'
' SECTION -IV-:
..DUQUESNE LIGHT COMPANY-FIGURE 4.1 l 1990-Annual Rediological Environmsntal Report j
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SECTION IV DUQUESNE LIGHT COMPANY 1990 knnual Radiological Environmental Report TABLE IV. A.1 1.
Effluent Treatment. Sampling and Analytical Procedures Beaver Valley Treatment, Sampling Standard and/or
, Effluent Type
_and/or Monitoring Analytical Procedures (a) Steam System Recycled or directed to If discharged, procedures Blowdown Radwaste System for adhere to Technical discharge.
Specifications.
(b) Radioactive Effluents shall not exceed Procedures adhere to Waste values specified in the requirements of Technical Specifications.
Technical Specifications.
All discharges are performed in accordance with the Offsite Dose Calculation Manual (ODCM).
TABLI IV.A.2 2.
Results of Liquid Effluent Discharges to the Environment - Beaver Valley Effluent Type kesults for 1990
-(a) Steam System The Steam System Blowdown was recycled.
Blowdown (b) Radioactive Routina planned releases of liquid effluents Waste 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 Beaset. Valley Power Station Semiannual Radioactive Effluent Release Reports for 1990.
32-
SECT 20N IV DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report IV. M0NITORING EFFLUENTS B.
Monitoring of Airborne Effluents 1.
Description of Airborne Effluent Sources Beaver Valley Power Station (Units 1 and 2)
The Beaver Valley Power Station identifies isotopes according to the Technical Specifications and Regulatory Guide 1.21.
Prior to waste gas decay tank batch releases and containment purge releases, an analysis of the principal gamma emitters is performed.
The principal gamma emitters include noble gases,
- iodines, and particulates.
Pigure 4.6 shows the gaseous radwaste system at Beaver Valley Power Station.
The environmental gaseous release points also require specific nuclide identification. These points include:
a.
Unit 1 Release Points; 1)
The Ventilation Vent located on top of the Unit 1 Primary Auxiliary Building.
2)
The Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Unit 1 Containment Building, b.
Unit 2 Release Points; 1)
The Ventilation Vent located on top of the Unit 2 Primary Auxiliary Building.
2)
The Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Unit 2 Containment Building.
3)
The Condensate Polishing Building Vent located on top of the Unit 2 Condensate Polishing Building.
4)
The Waste Gas Storage Vault Vent located on top of the Unit 2 Decontamination Building.
5)
The Decontamination Building Vent located on top of the Unit 2 Decontamination Building, c.
Unit 1 and Unit 2 shared release points; 1)
The Process Vent located on top of the Unit 1 Cooling Tower.,
SECTION IV DUQUESNE L8 Girt COMPANY 1990 Annual Radiological Environmental Report IV. MONITORING ErrLUEhTS B.
Monitoring of Airborne Effluents (continued) 1.
Description of Airborne Effluent Sources (continued) i Beaver Valley Power Station (Units 1 and 2) (continued)
These points are continuously monitored for particulates and gases. Grab samples are obtained on a weekly basis and are analyzed for noble gas gamma emitting isotopes and tritium. Weekly continuous samples are obtained on filter paper and charenal cartridges. The filter papers are analyzed for particulate gamma emitting isotopes and gross alpha.
Composites of the litter papers are analyzed monthly for Sr 89 and Sr*90.
The charcoal cartridges are analyzed for I 131, I D3 and I 135.
Tigure 4.7 shows these gaseous release points.
I e
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SECTION IV DUQUESNE LIG}{T COMPANY FIGURE 4.6 1990 Annual Radiological Environmental Report rp mit 2 20l1 Wit systet (stn!LAR to mit D toAfscnnt I
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1990 Annual Radiological Enviroruoental Report
--z.-- Ohio IUver FIGURE 4.7 8
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- 3. Process Vent-thit 1 & 2 475
- 4. Ventilation Vent'- thit 2 85
- 5. Contalment Vene (SLcRS)-thit 2 153
- 6. Condensate Polishing Ibilding as Vent-thit 2 k
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- 8. Decontanination Ebilding Vent-thit 2 80 Q
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- Elevation atne plant rade, in feet FIGURE 4.7 GASEOUS RELEASE POINTS - BEAVER-VALLEY POWER STATION UNii I & 2 ;
SECTION IV DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmentc1 Report IV. MONITORING EFTLUENTS B.
Monitoring of Airborne Ef fluents (continued) 2.
Airborne Effluent Treatment and Sampling Beaver Valley Power Station (Units 1 and 2)
Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the 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 radiciodin'es are also present in the eight continuous ventilation system pathways.
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 scim) 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 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 point radiation monitor.
The mixture is then filtered through one of the gaseous waste dicposal tilters, 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 1 cooling tower.
The radioactivity levels of the stream are 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. -
- - ~
SECTION IV DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B.
Monitoring of Airborne Effluents (continued) 1 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 determined, purging may commence through the Ventilation Vent located on top of the Auxiliary Building or the Supplementary Leak Collection and Release System (SLCRS)
Vent located on top of the Reactor Containment Building or the Process Vent located on top of the Cooling Tower.
Areas in the Unit 1 Auxiliary Building (subject to radioactive contamination) are monitored for radioactivity prior to entering the common Ventilation Vent.
These individual radiation monitors aid in identifying any sources of contaminated air.
The Ventilation Vent is also monitored continuously by several redundant channels of the Radiation Monitoring 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 (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 system is sampled periodically for determination of radioactive material and is monitored continuously by other channels of the Digital Radiation Monitoring System (DRMS).
Each Unit 1 and Unit 2 filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type HEPA filters.
The renghing 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 KEPA filters remove particulates and charcoal fines.
Release points for Unit 1 and Unit 2 of the Beaver Valley Power Station are shown in Figure 4.7.
See Table IV.B.1 for Radioactive Gaseous Waste Sampling and Analysis Program..-
TABLE IV.B.I Radioactive Gaseous Waste Sampling and Analysis Program LOVER LIMIT OF MINIMUM DETECTION (LLD) 5 SAMPLING ANALYSIS TYPE OF (pCi/ml)"
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS U
A. Waste Gas Storage Tank P
P E
I x 10 Each Tank Each Tank Principal Gamma Emitters G
Grab 1 x 10' 8
H-3 Sample P
P E
Ix 10 B. Containernt Purge Each Purge Each Purge Principal Gamma Emitters 5
Grab 1 x 10'
- e E H-3 Sample E
1 x 10' b
b M.c.e g
Principal Camma Emitters E
C. Ventilation Systems
-6 ggn Grab I x 10 H-3
- 1. Process Vent Saepte o
- 2. Containment Vents n4 4
- 3. Aux. Bldg. Vents 1 x 10' O
e W
- 4. Cond. Polish.
Continuous
-10 Charcoal 1 x 10 e
Bldg. Vent Sample I-133 g
E a
- 5. Decon. Bldg. Vent W
Principal Gama Emitters I x 10 ;g m
Continuous y
g y
Particulate (I-131, Others) y Sample
-11 e
I x 10 7
f M
Gross alpha Continuous g
Composite Particulate Sample 1 x 10 Continuous Q
Sr-89, Sr-90 g
Composite g
Particulate y
Sample 1 x 10 g
Continuous Noble Gas Noble Cases Monitor Cross Beta and Ca-ma
SECTION IV DUQUESNE L8GHT CO !PANY 1990 Annual Radiological Environmental Report IV.
MONITORING ETTLUENTS TABLE NOTATION a.
The Lower Limit of Detection (LLD).
b.
When reactor coolant system activity exceeds the limits stated in the BVPS Technical Specification, analyses shall be performed once evory 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during startup, shutdown and 25% load changes and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving the maximum steady state power cperation unless continuous monitoring is
- provided, c.
Tritium grab samples 6 hall be taken at least once per 24 i
hours (from the appropriate ventilation release path) when I
the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
Sampling and analyses shall j
also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, during startup, j
shutdown and 25% load changes and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving the maximum steady state power operation when RCS activity exceeds the limits stated in the Technical Specification unless continuous monitoring is provided.
Whea samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10, c.
Tritium grab samples shall be taken at least once per 7 days f rom the ventilation exhaust from the spent fuel pool
- area, whenever spent fuel is in the spent fuel pool.
f.
The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with the BVPS Technical Specification.
g.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe 135, and Xe-138 for gaseous emissions and Mn-54. Te-59, Co-58, Co-60, Zn-65 Mo 99, Cs-134, Cs-137, Ce-141, and Ce 144 for particulate emissions.
+
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.
When unusual circumstances result in LLD's hie er than required, the reasons shall be h
documented in the semi-annual effluent report, h.
Only when release path is in use..
SECTION IV DUQUESNE L80HT COMPANY 1990 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 3/4.11.2 of the Technical Specifications. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi Annual Ra m active Effluent Release Reports for 1990.
I d
e
-41 I
SECTION IV DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report IV. MONITORING ETTLUENTS 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, incinerate, and super compact the waste.
At the Beaver Valley Power Station, the compactable wastes are segregated and the capability exists to compress the waste in SS-gallon drums to minimize disposal volumes. The compressed waste is shipped for disposal at a commercial radioactive material burial site licensed by the Nuclear Regulatory Commission (NRC) or a state under agreement with the NRC.
No radioactive waste material is buried at the Beaver Valley Power Station site.
All containers used for packaging, transport, and disposal of radioactive materials met the requirements of the
'l nit ed States Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC).
Shipments offsite were made in accordance with DOT and NRC regulations. Figure 4.8 depicts solid waste handling at the site.
At Beaver Valley Power Station approximately 5,450 cubic feet of radioactive solio waste was buried offsite in 1990. The twenty six (26) shipments contained a total activity of 544 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.
42
r SECTION IV DUQUESNE LIGHT COMPANY TICURE 4.8 1990 Annual Rcdiological Environmsntal Report
.i l
i SOLID WASTE DISPOSAL DIACRAM SECTION IV gpACTfvt ml tli WASTM DISPOSAL i
4 Misc. '.adioactive jh Compactor and j
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Solid Wastes Drumming Station
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SECTION V a A DUQUESNE LIGHT COMPANY 1990 Annual R diological Environm:ntal R3 port 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 Foodcrops V E - Cow's Milk V F Environmental Radiation Monitoring V G - Fish V-H Surface. Drinking, Well Waters and Precipitation l
V !
Estimates of Radiation Dose to Man i
i._
l I
TABLE 1.A.D CONSOLIDATED RADIOLOGICAL [ Mitt 0gENTAL 10EITORING P90G8AM en O
Sample Sample Analys1s DLC Analysts (b) m Type of Sample Points Sector Miles Seaple Point Description Seaple frequency Preparatten Frequency Oz IdI Gross Seta. ICI -131 I
1.
Af r Particulate 13.
11 1.6 nryer's Fam Contineous semellag iketty Coupestte e
and Radiofodine 35 4-0.6 Shippfsgport.PA.(5.5.)
with saspie coIIec-W Gassie -scen y
48.1 3
- 2. 4 Indestey. PA ties at least femthly Campestte weekly I#I j
32 15 0.8 Ntdle.d. PA (5.5.)
Omerterly Compostte 48(e) 10 16.5 Wetrt.on. W (s)
Sr-89.90 e
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47 14 4.4
'ast Liverpool. Os 27 7
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28 1
8.7 Shetison's Fare e
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as 298 3
8.1 Seever County Hospital m;
C Ih) e 2.
Direct 30 4
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Centfasees Omerterly ggy Gasume-Dese E%
(ilD)
Annually
- m Radiation 13 11 1.6 Meyer's Form 46 3
2.5 Industry. PA(Cherett) 8 cb-32 15 0.8 Nfdiend. PA (5.5.]
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'N111 Creek 8d D +4 14
, 11 2.6 Mooksto n j
84 II 8.5 Moscock Co. Chlidree Rame D
85 12 5.8 Rts. 8 & 30 Intersectio=
g 86 13 6.5 E. Liverpool Cahflis Newse 92 12 3.0 Ecorgetown Rd.
87 14 7.0 Calcutte Road 88 15 3.1 Midland tiefghts
'"7 S.
89 15 4.7 Ohfouille 90 16 5.2 Fairview School c
to 4
0.8 Shippingport Soro. PA N
45 5
2.2 Mt. Pleasant Charth 60 13 3.7 M*ney's f*f*
h 93 16 f.3 Senset Hills. Midlead t-t1 95 10 2.4 Mttleary Rd. Mellte Willfres 4
b 5.5. - Settstation
'-m
TAOLE V.A.1 i
CONSOLIBATED RAGIOLOGICAL EW11mesutWTAt_ lentTottnG P90CDAM (Continued) m BLC et semple semple Analysis Q
I,I Tyre of semple Potets Secter Rites Sample Petat sescriptiese semple Frequency Preperstlen Frequency Analysts w
o I
Z 2.
Ol m t 73 1
S.E Shevison's Fem Centlasses Geerterly Gemme-sese Red!stlen 71 2
5.6 trighton T g. Scheel (7ts)
Anneetty
{
(Centtaved) 72 3
3.2 tegen Scheel 293 3
S.1 teamer County 8Eesettet 73 4
2.2 Petter Tige. School s
i y
74 4
6.8 Com. Cet-Center Tg-e 75 5
4.3 IIsit Reed eo
,i 76 6
3.8 aocceen Tg. Scheet 77 6
.- 5.s seven sorden ad (se pe's) 59 7
1.1 frens P
73 7
2.3 Ascceen seen. 31dg.
27 7
6.2 trwaten's Fare l
79 8
4.6 at.181 tt.151
}
15 14 3.3 Georgetoun
- o o 46.1 3
2.1 Industry Pa g
91 2
3.7 Pine Grove ad and 9eyte ad
- vs 94' 8
2.4 settleery ad utisen O%
y
.e c 3.
Serfere 49.1(e) 4 5.8 Arco Polymmers Inteentit-et monthly tempestte er Gross sete Water 2.3 14 1.3 Sounstreen (8Hdiend) J s 3.
Campestte Seaples (j) wenty Seaple (d)
Gress Alphe p-"O Collected Meetly Gesume-scan 3
13 0.2 shippingpert Atomic Pouer Meetly Greer Omerterly Caposite co-40. 86-3 mo stetten 01schery semples Only Sr-89. Sr-90 gO r
49 (e) 3 3.2 feentgomery Den (Urstreen)
"O g 2A 13 0.2 Domastrese BVPS Ostfall 5q 5
14 4.8 Cast tiverpoet (row meter)
Detty Grab 5emple thily - Collected Weetly (j) e A
w 4.
Groundwater 13 11 1.6 stayer's Fare w
14 11 2.6 Meetstown. FA 11-3 0.8 shippingoert more Guerterly 0.orterly Gemme-scen. Gross 3
j 15 15 3.3 Georgeto==. FA 1
~
1 te. G,ess Ai 38-3 4
4 b
I'I 5.
Drinting 4
14 1.3 Mfdiend. PA (Midless Meter Intermitteet u=enty Composite of Gessne-scea. 1-133
{
Treatment Plent)
Seaple Cettected centy semple (d) p.
Confes~Tte Td)
Gress Alphe.Gress arte mEthlyViempestte (d)
N-3.Ce4. Kr-89. 90 apetty Quarter 5
14 4.8 East tiverpoet. Os9 (East tiverpeet Wate-Treatment b
Flent) 6 5
0.5 otC new Tresning 81de.
W Ely Grab W ie 1
1ASLE V.A.T
[9FAlf3ATEB ahDIR06tCAL EWritmENTAL INTigeIE PilemAus
( Centf asee)
SLC m
t**
5eeple Q
Segle Ametysts Type of Seaple Polets Sector Rtles.
Sample Pelet Descrfptfee Saeyte Fregeracy Properetten Fregnency Amelysts(b)
- g
~z 6.
Shorellee M
13 S.2 Somerstross SUPS Detfell Sentenemmi senteammet Games-scas. Eress Sete Sedlemet Gross Alpha 3
! 13 8.2 Tietetty SAPS Stscherpe erseten Iseteyte 49 3
3.2 Systrees 5?de of stentyneery
$r-89. Se See (a)
SS 13 8.I Spstroes side of Itow Centerleed tem
~eo N
7.
Stilt 25 19 2.1 Seerfght's Satry theetly ttretly seaple free I-134 O
Seertsht's esty Stare 4Ty (g) 51.e411 (,rerie,)
Go-e-scan p
IAnon esteels are Stenthly (tessors)
Sr-99. 90 en postura; I-131. Cs-137 m
96(e) 19 14.3 1Hadsholeer suethly at other 27 7
6.2 Greatee's Safry (b)
.gnsethly 9tsstely Geome-scoe SrM'._90_
pr o t aes.
29 3
S.3 Stcot's Seiry (b) e
- Q 3-131. Cs-137 O 7.
S.
Fish R
13 8.2 Victatty of SUPS F1 Senteensel Ceepestte of eettle Go - e-scos en edible
- -* t*8
[
5tatfee Discharge and ports by spectes (t) porttees M
t'*
w Shipplagpe-t Dis. Ste.
49(e) 3 4.7 Wystream Side of Q9 e
stootgenery too e, Q t=t O 9.
Food Crops (Shipp.
le 4
S.S (Three facettees withfe Amenal at Campestte of esct Gosse-scoe DO 1.t %
(Georg.
15 14 3.3 5 ettes Selected by heroest tf sesyte species 1-131 en green (ledes.
46 3
2.5 Ceepesy) eestlette leefy eegete61es GS(s) 16 16.5 teatrton, uv g$
- 10. Feedstuff and 25 ft 2.1 Seerfght's befry Face monthly sheethly Gemen-sces 3
Saeerr ferope Geerterly Omerterly tempestte Sr-95 II. Sell 13 Il I.6 stryer's Fece E,ery 3 years 32 Ceee semeles Gesman.scee 30 4
9.6 Shtpplejpert. Pa.
3* Derp (3-Ste.
St-90 y,
NN' N * '"'I et each location Gross Sete e
46 3
2.6 ledestry. Pa.
i 32 15 S.S (merth ef Site) Risland (oppres. 10*
Gross Alphe
- U 4e(s) is 16.5 esefrtes,s. ve.
redtes) eresse. Isetepec Se 51 5
S.O Allgetype. Ps.
47 14 4.8 E. Ifserpoet. Oh.
27 7
6.2 Dreatee's Seiry 4
22 3
9.3 Scotte of SWP5 Site g
29A 3
8.3 Richo1*s Befry t=s 3rrs Techetcal Specifiesttee Tabt 3.12-3 retstree t'are-(3) deletee be selected en beste of highest poteettet thyeeld eme metag e
estch cemove dete. See Sectise V.E. for efectfle loestiene esseled.
I i
a 1
t taste V.A.1 4
CeI6ettasIE9 IWetMeGiCat (gesteestaint mentfeates reessume
'(Cents==ed) m m
'KC O
Segle semyte anelysIs d.
gI
. Type of Sample; Petets Sector' IMies Sample Petet SescrfM ies Sample Fr w y Properetten l'rwy Ametysts O
q.
E
$t -
i 12.
Prectritecten 3e 4
0.6 shippinarort. PA
- M ir arab
- betbly e-r-atte Crees S 47
'I4 4.8 test L1werpool, esp eseptee when of aesh emmete.
W=
i i
i es to -
16.5 inetrees. tft
===t1 61e goerteray tes, ette s-3. se-ev se-9J I
i 4
e a
D 3C>** O C
4 1
30 O 4
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$ECTION V = A DUQUESNE LIGHT COMPANY e
1990 Annual Radiological Environm2ntal Report TABLI V.A.!
CONSOLIDATED RADIOLOGICAL ENVikONMENTAL MONITORING PROGRAM (Continued) t Notes:
- (a) ' Control sample station:
These are locations which are presumed to be outside the influence of plant effluents.
(b) Typical LLD's for Gamma Spectrometry are shown in Table
+
V.A.44 (c) Particulate samples are not counted for 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change.
Perform gamma isotopic' analysis on each 10 times the ye'arly mean of sample when gross. beta is >
control samples.
(d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location.
i (e) Composite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(f) Weekly milk sample from Searight's Dairy is analyzed for 1 131~only.
_(g) 'Hilk samples are-collected -bi weekly when animals are in pasture and monthly at other_ times. _(Assume April - October for grating season-(pasture).]
1 (h) The' milkI samples from Brunton's and Nicol's'are collected -
once per month.
E(1) The fish _ samples will contain whatever species are available, If the available samplo size permits, then the sample will be -
separated _ according to species and compositing will provide-one sample of.each species.
If ths available_ size is too small to make separation.by species practical, then edible parts of all fish in the sample will be. mixed to give one sample.
-(j) Composite samples _are collected _ at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at locations 49.1 and 2.1._
Vsekly_ grab samples _ at e -
obtained at location 3, 49-and 2A..A weekly-grab snaple is also obtained from daily composited grab samples obtained-by the waterLtreatment plant operator at location 5.
(k) Two (2) TLDs are collected quarterly and annually from each i
monitoring location.
49-
.. =.-
-. -.. -. =,.
.-,-.:... -,...--...,.,, _ -, =. -,
SECTION Y
- A DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report TABLE V.A.1 CONSOLIDATED RADIOLOGICAL ENTIRONMENTAL MONITORING PROGRAM (Continued)
. Additional Notest Sampic points correspond to site numbers shown on maps, All lodine I 131 analyses are perictmed within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of sample collection if possible.
All Air samples are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for i
Gross Beta.
.1 P
i 4
s.
50-
~. -
.. ~
. - - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ = - _ _ _ _.__._ _ _ _ ___ _ -_________-.
SECTION V *'A DUQUESRE LIGHT COMPANY 1990 Annual Radiological Environmental Report V..
ENVIRONMENTAL HONITORING A.
Environmental Radioactivity Monitoring Proaram (continued) 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).
Cummaries of results of analysis of each media are discussed in Sections V B through V H and an assessment of radiation
)
doses are found in Section V I.
Table V.A.3 summarizes Beaver Valley. Power Station pre operations 1 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 activities near the lower limit of detection (LLD).
The conclusion from all program data is that the operation of the Beavet Valley Power Station has resulted in insignificant changes to the environment.
3.
Quality Cr.ntrol Proaram The -Quality Control Program implemented by Duquesne-Light Company.to assure reliable performance by the DLC
-contractor and the supporting QC data are prenanted and discussed in Section !!!' of this - report =.
The lower limits of detection for various analysis-for-each media monitored by this program by the DLC Contractor Laboratory are provided in Table V.A.4.
4 5
l
+
I !
1 y
+
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,,,.-,iv.-,.r-e,_
-_+,,,.*-
-.m
____-...,--m
.. - -.. - ~.
SLCTION V - A DUQUESNE 1.1CitT COMPANY 1990 Annual Radiolot;ical Environmental I'.cport I
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o mm ENVIRONMAL RADIOtDGICAL MONITINGNG PROGRAM
SUMMARY
Manne of Fadhey % Vh h e' "- 18aat t *-.a 2 Docket No. 50 334/5C/412 O
Imcmeson of Fadtwy Beaucr Pennsytraata Reportang ivrted apnasal 1990 IConney. sentes a
-e and Lower IJnsM Number <d U
Medeems of Paeseaf - T N==her of AE Inecatar tacations Imcattan wtth Highest Annasal Mcan Control I.mcations Nonroutkx
-LO efAnsipues Detect $ers
~ Mean it Name "tseen (f)
-Mean IG Reported g
I-(Unst of
__ A./.; Perforuned 5.114 "Renee Destance acd Deredsons** Ranee
" Range Me===rement s***
a Weertori. %T No. 48 g
External Radiation Canossna 1443 0.05 e.!6(I75/1754
- 29. Beaver Cty flesp 0.19t4/43 4514/41 O
g (enR/dmyl (175 g _: ;y)
(0.12 0.I99 8.I sie NE 10.18 C.20t t0.15 O 17)
Eo o-c M t-1 om Genune 0.05 0.15(44/443
- 84. flancerk Cay O.1 9(1 / 11 0.I 411 / 11 o
yy l
i (44 annues 10.12-0.199 Ch48dren's llome n
i d
8.5 sne SW
- [
s>
se o e
r :::
-4 m
Feed and Forage 1-131 (123 0.01 11D one sar,pse jg Locattori r-IPC1/g)
- f j
lary el Sr-90 (4) 0.003 0.074(4/41
- s 6 (0.048-0.1 Il
{d v
'o' r
Gasmsma (125 Be-7 0.3 4.746/1 21 O
E (0.41-111.
]
l K-40 0.5 21112/12) o F
18.6-4 II
?
I i
Th 228 0.08 0.2 114 / 1 21 0
l (O. I5-0.31I
?
Others Table V.A.
IID i
n.r.a-,. a - iuu Fraeterne est dese, tabic swore,*sremeenes at v eter.t t..sene w==tw ae,s en po e,when EU i
- Mean and range based opera detectath mem
.-.. s crufy afwa tfw tirseer Vaticy t%wer Wese, y skatw see.
- Pearnewentine sepursed vractsuresweruts are dcCned en Stegisstategy Casade 4 81%4ABN.15 89758
1 SECTION V - A DUQUESNE 1.1011T COMPANY 1990 Annus1 Ittdiological Cnvironmental Report
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- h MONITORING PROGRAM
SUMMARY
o Masse of Facesty Beaver v2 L * "
Unat1--e2 Docks t No. 9J-334/M/412 o
IAcetson of F=remy 1 r-
' rWJ-iFW Annual 1990 m.
4 County. Statet t
I and I.meer IJimm Ntsmber el Medhamn of Passiemey Nes=mawr of AE Indicasar Imcations L-useth "' ' -2 a=---*""
Conistd Imcations Nonreuune G
~
ofAmeDuan Detection
- Mean tG Manne "Mean ($
"Mean (O Reported (Unst es,"
C Forfursmed WJJ)B
" Range Destance and Derectmens
" Range
" Range Menomeesseets"*
g Weerton. WV h_48 ac Food and Camisen 5-131 (48 0.00s IID cw tyc /g Eo (wet wetgk)
P - let
,3 ac an n an E-40 0.5 1114/4)
- 15. Georgetoum. PA 2.4(1/1) 1.7(1 / 11 0
oz (4.7 14) 3.3 mit NW y"
n r*
c o ero DMeVA 12 w
78 Ut
.=
MH
[
MO k0
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O39 en 3n>
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Namenal louser Lamst of Detectsori (LAD)
- Mean and range based aspen detectat4e measurements enY Fractiori af desertath measuremenes at spnthet 3.= aew, e, e,wh me.e w pa,enthew, gr)
- Monreuttne reported erseasurements are deBewd fra Rettstiatory Cusde 4 8 IMARCit 19758 arid the 11 caver Vaticy 8%se cr saae, sgn,s., ass,.
~
SECTION V - A DUQUESNL LIGHT CO:!PANY 1990.unual Radiological Environmental Report i
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x ENVlHONMENTA1: HADIOt.OCICAI. MONITORING IHOCRAM StfMMARY 1
Name of Fac9 tty Beaver Vallev Power Station Ifnet I armt 2 Derket No. 50 334/50/412 o-
-z.
Imcation of Factiety Beaver. Pennsv!varda Reporting Perkxl Armual 1990 ICounty. Statel
~
~
f_--C _ and L,-.
IJmet Namit>cr of Medium of Pathway. Total Number..
of' All Ind6eator locations imcation wtth Hwhest Annual Mean Control lorsthms Nonroutene Sampled ofAnalysta
. Detecuon
" Mean (f) '
Name.
- Mean II)
"Mean JI Heported 5
(Unit of Measurement) Performeed ll.LD)
" Range Destance and Directions " Range
- " Range Measurements *"
e O
Montgomery Dam No. 49 Sediment Gross 18) 0.3
'16(8 / 81 2A. BVPS Descharge 1942/21
' 1812/2) 0
((pCligi Alpha (8.0-2 01 0.2 mil. W (17-20)
(17 18) c idry weight)
Eo Gross (81 0.1 40(8/8) 2A. BVPS Discharge 5 2(2/21 39(2/2) 0 C
Beta (19-59) 0.2 ad. W -
(45-59)
(36-42)
.M
- a. m -
Sr-89 (81 0.2 IL9 py l
wn Sr 90 $80
.0.04 11D E e.* -
w n.-
18g g y-8 Be 0.2 1.5(4 / 81 2A. BVPS Descharge 2.3(2 /21 0.66(I/2) 0
- *i (0.86-2.51 0.2 nd. W (2.1-2.51 no ao K-40 0.5 1 2(8 / 81.
2A. BVPS Descharge 16(2/2) 13(2/2)
O Eis (7.1-17) 0.2 me. W '
(15-17)
(I l-15) gg ad I
Mn-54 0.05
.' O.52(2/8).
2A. BVPS Descharge 0.52t2/2) 11D 0
3 10.46-0.58).
0.2 ad. W (0.46 0.58)
@n
. Co-58 0.2 9.2(4 / 81 2A. BVPS Descharge 17(2/2) k1D o
E (0.59-33) 0.2 ad. W (0.59-33)
[
Co-60 0.2 1.9(4 /8) 7A. BVPS Discharge 3.2(2/2) 1.tD 0
o 10.3 1-3.7)
' O.2 ms. W (2.8-3.7) n Cs-137 0.02 0.20(8/8) 2A. BVPS Descharge 0.27(2/7) 0 2212/2) 0 10.071-0.28) 0.2 ad. W (0.27 0.28) eo.20 0.23) i Ra-226 0.1 2.0(7 / 84 2A. BVIS Descharge '
- 2. Ill /2).
2 ti?/23 0
4 (I.4-2.6) 0.2 me. W (2.08-2.13
. Th 228
~ 0.02 1.388 / 8).
2A. BVIS Discharge 1.6(2/2) 1.3(2 / 23 0
(0.73 2.0) 0.2 nd. W (l.2 2.01 (OE7-I.75 Others
- Table V.A.
[ID t
Nominal Imurer Lkmtt of Detection (t1DB
_ -~*
- Mean and range based.upon detectabic measurernents onryc Fraceson of desemth measurements me sgnet.r 0 8..meses as 6,wtw[
Ghnfh Gf1 11 19753 and the Incawr Vary Ibeer seatsen Somsf=esuns.
tn ENVIRONMENTAL RADIOLOGICAL MONTTORING PROGRAM
SUMMARY
g H
Name of Facility Beaver Valley Power Station Unit I and 2 Docket No. 50-334/50/412 g
z Locatson of Facility Bea:rr. IYnnsylvanta Reporting Period Annual 1990 (County. Statel t
twumber os Analyons and Lower Limit Medium of Pathway Total Number of All Indscator locations lagtaon with f & hest Annual Mean Control Locations Nonrotstane g
Sampled ofAnalysis Detection
" Mean (!)
Name "Mean 10
- Mean 10 Reported eo (Unit of Measurement) Performed (LLD)
" Range Distance and Directkwis ** Range
- Range g
Measurements ***
ac Drinking 1-131 (155) 0.2 0.45(8/1551
- 05. E. Overpool. Oil 0.4 7(3 / 5'23 0
$e (0.20-0.78) 4.8 ml WNW
{0.29-0.59) c E#
Water c
(PCl/I)
Crose (36) 0.6 IID c rs oE Alpha
~ tn d
C nne (36) 1 4.l(36/36)
- 04. Midland. PA 4.7112/12) 0 j
7 Be s (1.9-121 1.3 mi WNW (2.9-12) y.-*
e y
"H m:
Gamma (155)
Table V.A.
11D es a Sr-89 (12) 1.5 IID yO r 80 Sr-90 (12) 0.5 IID g P, od Co-60 (121 (a) 1 11D g
o 11-3 (1 2) 100 180(I/123
- 05. E. Liverpool. Oli 180(I/41 O
n 4.8 mi WNW
?
I.,
i (a) Co-60 analyd by high =eiisitivity method.
Nominal Imrer Lamra of Detecuon (LLD)
Fraction of detectable measurerrunts at spectised locai;,-.; as endicated in rentheses 14
- Mean and range based uport detectable measurements only.
- *
- Nonmuttne reported measurements are defined in Reguilatory Cutdc 4.8 (MARCil 19751 and the Beaver Vaticy tbwer Statson 55"1 i
' 4 :1- '
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.m ENVIRONMENTAL RAIMOLOGICAL MONITO_RiteG PROGRAM
SUMMARY
E-
.H Masne of Fadisty Beaver Vallev Pmmer heta n Unit I and 2 Docket No. 50-334/50/412
'O.
.z tocation of Facility Beaver. Pennsvivania Reportsng Period Anntaal 1990 acounty. staie l
i and Emeser Launit Number of f
Medeusa of Patlessay Ne w
- of AE Inacasar lmcations lasation with Highest Annual Mean Control Imcations Nonroutine -
[
h= pled -
et Analysis.. Detection
" Mean (9 Masne
- **Mean (f)
"Mean (O Heported o.
(Unit of hiemeuressent) Perforuned ILID) 1 ** Range.
i Measuressments"* -
Destance and Derections ** Range :
- Range
- N Omp. PA No.15 Grounderater.
Gross (16) 2
- UD IP 1/5 Alpha
. pg' C
- o. r s -
Gross (16) '
3.7(13/16)
- 13. Meyers Farm 5.2(1/4) 2.6(4 /4)
O
+m 1
+
r $.
O Beta (1.9-5.21 1.6 set SW (2.0-2.91 o
t' - (16)
TaMeV.A. J UD E C" l
y Ttttsuma (161 90 17512/16)
- 14. Hookstown. PA 210(1/41 140(1/4) 0
. "9' v.
- q; (140-210)
- 26satSW gg I
. $9 r 82 i
n.
l..
O3
- 9a 3
et -
l r
I
~/t i
o
~J O
1 r*
i i
Nominal immer Lemet of Detection (LLD)
- Mean and rary based upon detectatste au....a..:s only. Fraetton of detectable measurements at spectfled Inrations es endscated to parenthews (0
- *
- Nonsoutine reported measurements are deAned in Reguitatory Guide 4.8 (MARCII 1975) and the Beaver Vaucy tw Statson Spertikatsons.
m..
.~.c
>..-e w
-.-s n..
-- + ~..,. -
..w...
ENVIRONMENTAL RADIOLOGICAL MONTTORJNC PitOCRAM.
SUMMARY
-3 Name of Faci!!ty Beaver Vallev Power Station Unit I and 2 Docket No. 50 334/50/412 8
- z:
Location of Facthly Beaver Pmnsylvanta Reporting Period Annual 1990 (County. State)
Number of Analysts and im m Limit Medium of Pathway Total Number of A!! Indkator locations locauon with fitchest Annual Mean Control locations Nonroutine Sampled ofAnalyslo Detection
~ Mean (f)
Name "Mean tr)
~ *-Mean 10 Reported (Unit of Measurement) Performed (LLD)
" Range Distance and Direcuons" Range "Ra nge o
Measurements *"
Wetrton. WV No.48 o
5 Water Cross (34) 1 7.1133/34)
- 48. Wetrion. WV 8.1II I/ I 1) same as ht;1:
0 Preetpttation Beta (1.9-14) 16.05 ml SSW (3.2-14) location gg (pC1/l) an W U3 Gamma (34)
~n Be-7 40 66(11/34)
- 30. Shippingprt. PA 77(4/12) 6414/11) 0 o
(42 99) 06miENE (63-99)
(43-771 3C oa
?
Others Table VJL 11D
~
"s d
,e Sr-89 (12) 2 IID EO
."toh Sr-90 (12) 0.5 IlD 11-3 (12) 100 210(7/12)
- 48. Weirton. WV 310(I/4) same as high 0
(120-310) 16.05 ml SSW location g
eww
?
m On a
1 Nantnal lower Lsmit of Detna. (LLD) dkared in parentheses If)
Mean and range based upon detectable measurements only. Fracitori el detectable measu...aats at specified Iwattores is h.
'* Nonroutine reported measurements are defined in Reguitatory Cutdc 4.8 (MARCil 19751 and the ficam Valley Iwwer St.atwsn Spectftcat
l tn
.m.
ENVIRONMENTAL RADIOIDGICAL MONITORING PROGRAM
SUMMARY
O d
Name of Fadhty Beaver Valkv Power S'-*% Unit I and 2 Docket No. 50-334/50/412 O
.. z '
Imcation of FacNety Beaver. Pennsvivania Reporting Period Annual 1990 (County. Statel and I-.
Limit Number of Medium of Pathway T
N===dwr of AM Indicater Imcations Imcataan with Haghest Annual Mean ControlIncations Nonroutine
. Sam ofAnalpels
' Detection
" Mean it Name.
"Mean If)
"Mean 10 -
. Reported -
'o (Unit of Performed
. ItJD)
?* Range Destance and Directions " Range "Ra nge Measurements"*
>b MorWgomery Dam No. 49
$p Surface Water l I-131 - {52).
0.5 0.48(2/52) 49.1. Upstream. ARCO one sample ~
O
". E (pC1/l) 10.42 4.53).
Polymers location wo 5.0 me ENE E, @
n tn I
o=
Crose U2) 2 IID
@p.
~[
wm t
Alpha
- H-na Cross (72)
I 7.1171/72) 02A. BVPS Descharge Itil2/12) 5.8(12/12) 0
$, G Beta 13.0-2 8)-
0.2 mi W (7. I -28)
(4.1-1 01 Eo Camma a2i
- i y Co-58 16(2/72) 02A. BVPS Descharge 17II/12)
IID 0
(15-17) 0.2 ml W g
r, Others Table V.A.
IlD -
- sw Sr-89 (24) -
2 UD ye o
Sr-90 (24) -
0.5 11D o
O Co-58124) (a) 5.2(2/24) 02A. BVPS Descharge ' 6.1(I/41 11D 0
t (4.3-6.1)
O_2 mi W Co-60 (24) (a) 2' IID
' Trttlum (24) 100 2210(11/241 02A. BVPS Discharge 5088(4/41 220(1/4) 0 (190-11000) 0.2 ml W (190-11000) l (a) Co-60 and Co-58 analyzed by high sensitivity method.
- Nominal tower 1.tenst of Deteetten l LID 9 Mean and range based upon detectable measurements any. Fraction of detectable measurements at spertiled locattom ts indicated in parentheses (0
"* feoneoutine reported measurements are defined in Reguttatory Guide 4.8 (MARCfl 1975) and the Beaver Valley Power Station SpectScatkw,s.
4
~ ~.-
SECTION Y - A-
..-DUQUESNE LIGHT COMPANY TABLE V.A.3 1990 Annual R:diological Environmantal Report i
ENVIRONMENTAL RADIOLOGICAL H0H1TORING PROGRAM
SUMMARY
Name of facility leaver Vallet Power Stattee Donet h. M 1mcasico of facility Besveti Penaattvaala toportia8 level CT 1914 1911 (county. 8 480)
PES =0PERAT100tAL Pk00 RAM 899%tf(COMBLVED 1974 1973)
Hadian er Fathuey lavet Limit Sampled eaalreis and Total shader of AU 1adic.ater Locations (Omit of Maeuraamat) of &aalveis Performed beteetten LI.D Mose. (f) Raate lediaants Groes Alpha (0)
PC4/8 (dry) 3)/
Geese beta -
(33) 1 18 33 3 30 St-90
-(0)
U+234,233. 238
.(0)
==
Camus (33)
U 3I/ 33 2 - 30 33 Edo 1.3 13
/33 2 - 30
- I/33 0.1 - 0.6 Ca* U 7 01 0.4 U
ItNb-93 0.05 0.8
/33 0.2 - 3.2 I/33 0.4 - 0.7 C++144 0.3 0.3 I/33 1.3 - 1.8 Bu-106 0.3 1.3 others e LLD
-Foodstuff-Canna -
(8) 8 E-40 1
33
/8 10 - 33 1
Ce=U 7 0.1 0.2
/8 I
tesb-93
'0,03 0.2
/8 -
Bu-106 0.3 0.8
/4 othere
= 11D 80
- feedotutf Crose aeta (80) 0.03-13
/80 8 - 30
- St=89 (81) 0.023 0.2
/81 0.04 = 0.93'-
8/
8t (81) 0.003 0.4 11 ~
0.02 a 0.41 Caana (81)
I E 1
-19
/81 3 Co-U7 0.1
- 0. 3
'/81 0.2 - 1.6 I/81 0.9 2.6 Co-14A
-0.3 1.3 trsh-93 0.03 0.8
/81 0.2 a 1.3 N
1 /81 0.6 - 2.3 lu-106 0.3 1.4 others
- LL.D,
,n-r
SECTION V A
DUQUESNE LIGHT COMPANY TABLE V. A. 3 1990 Annual Radiological Environmental Report ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of racility Beaver Vallev Power Station Docket No.
50-3%,
location of Fac.111ty Beaver. Pennsylvania toportin8 Feriod CT 1974 - 1975 (County. State)
PR2-CPP.tATIONAL PPDCRAM SUMKAE! (COMBINED 1974 - 1975) tower 1.init Medium or fathway Smepted Analysts and Total N aber of All ladicator Locatione 00ait of Masurement, of Analysis Perforsed Detection ID M u, (f) Kanae Soil Gross Alpha (0)
(Template Samples)
Gioes Beta (64) 1 22 g/64 14 - 32 PC1/3 (dry) s -89 (64) 0.25 0.4
/64
$r-90 (64) 0.05 0.3 A
/64 0.1 - 1.3 0-134.235.238 (0)
Conna (64)
'3 E-40 1.5 13
/64 5 - 24 56/64 0.1 - 6,8 Cs-137 0.1 1.5
/4 0.2 - 3 6
Ce-144 0.3 1.1 D
IrNb-95 0.05 0.3
/64 0.1 - 2 tu-106(b) 0.3 1.1
/64 05-2
- L1D Others sol 1 Cross Alpha (0)
(Core s4 spies)
Cross leta (8) 1 21 g/8 16 - 28 PC1/g (dry) sr-89 (8) 0.23 e In 3/8 0.08 - 0.5 Sr-90 (8) 0.05 0.2 Camma (8) 8/8 7 - 20 E-40 1.5 13 7/ 8 0.2 - 2..
/8
- L13 Others __-_____-_-__-
. ~..
-i
..SECTION V- 'A DUQUESNE LIGHT COMPANY TABLE V.A.3 1990 Annual Radiological Envirortmental Report ENVIRONMENTAIi RADIOLOGICAL MONITORINC PROGRAM StMtARY l
' home of Facility 6* aver valle, Power stattgg Docket No. M-1.ocattaa of facility ' beaver. Pennevivanta Reportine Perted CT 1976 - 1971 l
LCounty. 6 tate)
_PR2-OttAAT10MA1 PttCRAM $1'HMART (COMBl?ffD 1974 - 1913)
Medium or Pathway Lower LLait Sempted Aaalysts and Total. Number of All IndWser Locations Malt of Measurement) of Analista Performed Detetttas llt,, _, A ff) Lamae 3/
surface Water Groes Alpha (40) 0.3 0.75 40 0.6 1.1 UO Grose Beta (12 0) 0.6 4.4
/UD 2.5 - 11.4 Caama (1) 10 - t9
< LLD 12 0/121 180 - 800 Trtstum (121) 100 300 8r-89 (0)
$r-90 (0)
C-14 (0)
Dytakind Water 1-131 (0).
~
Gross Alpha (30) 03 0.6
/50 0.4 - 0.8 106/208 2 3 - 6.4 Crose Beta-(108) 0.4 3.8 Camma (0)
IU/211 130 - 1000 Tritium (211) 100 310 C-14 (0)
$r-49 (0)
St-90 (0)
Croved Water Cross Alpha (19) 0.3
- LLD.
i
'PC1/1
~
2.9 II/75 *I 1.3'= 8.0 I
Crose loca (76) 0.6 II Tritium (81) 100 440
/81 80 - 800 Camma (1) 10 - 60
< LLD 33/
Air Particulates Croes Alpha (188) 0.001 0.003 188 0.002 - L ;:-
and Caseous g..
927/927- 0.02 04;;
32UM Gross-leta' (927).
0.006 0.07 St-89 '
(0)
St-90 (0) 1-131-(816) 0.04 0.08
/816 0.07 - O.;i ~
Casma (197)-
U2/ 197 0.01 - 1.a l-ZrNb-95 0.005 0.04 l
$0/197 0.02 - 0.;9 Su-106 0.010 0.04 I
Ca-141 0.010 0.02
/197 0.01 > L -
Ca-144 0.010 0.02
"/197 0.01 - t Otners
-64
< ' LD l-
.. ~
a
SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1990 Annual Rcdiologiczl Environm2ntal Rsport ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Naan of Facility Beaver Valler rever Station Docket No.
50-334 Location of Facility leaver. Pennsylvanta Raporttas Wvel CT 1974 - 1975 (County. Stata)
FRE-OPERATIOMAL F1t0 CRAM SIMMART (C0KBINID 1974 - 1975)
Hadi m or Fachway lower 1.imit sampled Analysis and Total Numbat of All Indicator locations
@ nit of Measurement) of Ana. lysis Performed Detection (1D Mean. (f) Ranae Milk I-131 (91) 0.23 0.6
'/91 0.3 - 0.5 Sr-89 (134) 5 7
'/ 134 6 - 11 W/134 1.5 - 12.8 3r-90 (134) 1 5.3 L== =
(134)
II Ce-137 10 13
/D4 u - 16 Others
< 11D SM/599 0.08 - 0.5 F.xternal Radiation y - Monthly (599)
- 0. 5 a1
- 0.20 mA/ day 195 y - Quarterly (195)
- 0. 5 sA
- 0.20
/195 0.11 - 0.38 48 y - Annual (48) 0.5 at
- 0.19
/48 0.11 - 0.3C U/17 1.0 - 3 ;
Fish Cross Beta (17) 0.01 1.9 PC1/g (wet) 1 /17 0.0 - 0. 5 -
St-90 (17) 0.005 0.14 6===
(17)
I /7 1.0 - 3.7 E-40 0.5 2.6 1
Other
< LI.D IID in units of MR - Lower and of useful integrated exposure detectability range for a passive radiation detector (t"D).
Cue outlier not included in mean. (Vater taken from dried-up spring with high sediment and potaastua contant. Not considered typical groundwater sampia.)
May include tu-106. Ru-103. Be-7. --
m
~
TABLE V A'e4-SECTION V:- A-DUQUESNE LIGitT COMPANY.
,Y-
-1990 Annus! Radiological Environmsntal Report O
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- I e.
g mmga -
m mm ~ ~ m w
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SECTION V - B DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING B.
Air Monitoring 1.
Characterization of Air and Meteorology The air in the vicinity of the site contains pollutanic typical for an industria; area. Air flow is generally from the Southwest in summer and from the Northwest in the winter.
2.
Air Sampling Program and Analytical Techniques a.
Program The air is sampled for gaseous radioiodine and 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 5.B.1, 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 charcoal cartridge.
The former collects airborne particulates; the latter is for radioiodine sampling.
Samples are collected for analysis on a weekly basis.
The charcoal is used in the weekly analysis of airborne I-131. The filters are anulyzed 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 few days after collection prior to counting for a for beta in a low background counting system, b.
Procedexes Grost Beta analysis is performed by placing the filte. paper f rom the weekly air sample in a 2"
x 1/4" planchet and counting it in a low background, gas flow proportional counter. _ _. _ _ - _ _ - -
SECTI N V -
B'.
DUQUESNE LIGl!T COMPANY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL HONITORING B.
Air Monitoring -(continued) l-2.
Air Sampling Program and Analytical Techniques I
(continued) b.
Procedures (continued)
Gamma emitters are determined by stacking all the filter papers from each monitoring station collected during the month and scanning this composite on a lithium drifted germanium (Ge(Li))
gamma spectrometer.
Radiciodine (I 131) analysis is performed by a gamma scan of the charcoal in a weekly charcoal cartridge.
The activity is referenced to the mid-collection time.
1 l.
SECTION V - B DUQUESNE LIGHT COMPANY FIGURE 5.B.1 1990 Annual Radiological Environmental Report FIGUME 5.B.1 mmmAL. taoumwuMe LOCATHMs-AIR kVPUE LDCATIOC H
"**cs ***i
&li$NRIn6 STAT!M b.
f
~~
SIL_TL LZAI121 13
'tytn's kiev Fw L
h 27 BaaiskinyFw
- d. -
'g.-}"**
28 Soem's thiny K
l (l
_,,",l a
eun can w,a
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SHIPP:NamRT Boso f*
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FIGSE 5.B.L ___ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ -
SECTION V - B DUQUESNE LZGHT COMPANY
,1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL MON!TORINO B.-
Air Monitoring (continued)
.2.
Air Sampling Program and Analytical Techniques (continued) l b.
Procedures (continued)
Strontium 89 and Strontium-90 activities are determined in quarterly composited air particulate filters.
Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered.
Half of the filtrate is taken for strontium analysis and is reduced in volume by evaporation.
Strontium is precipitated as Sr(NO ):
using fuming (90%)
3 nitric acid.
An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth.
Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The i
yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr 90 activity.
Sr-89 activity is determined by precipitating SrCO:
from the sample after yttrium separation. This precipitate is mounted on a nylon 8
planchet and 1s covered with 80 mg/cm aluminum absorber for level beta counting.
3.-
Results and Conclusions A summary of data is presented in Table V,A.2.
a.
Airborne Radioactive Particulates A total of five hundred twenty (520) weeklyfsamples-from ten (10) locations were analyzed for gross beta.
Results were comparable to previous years.
Figure 5.B.2 illustrates the average concentration of gross beta in air particulates..
4 AVERAGE CONCENTRATION' 0F GROSS BETA IN AIR PARTICULATES --- 1990 1
_.____..g.______e,.-_
y
- -.-.l_--
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SECTIONV6B
-DUQUESNE LIGHT COMPANY 1990 Annual-Radiological Environmental Report Vi. ENVIRONMENTAL MONITORING B.-
Air Monitoring-(continued)-
3. --.ResultsandConclusion[(continued) a.
Airborne Radioactive Particulates-(continued) l The' weekly air particulate samples were composited-to one hundred twenty (120) monthly samples which h
wereanalyzed by gamma spectrometry, Naturally occurring Be-7 was. present. in every sample,.
Occasional traces above detection levels of other naturally. occurring -nuclides such as K 40 were present. These :are: listed in the summary Table V.A.2, J
A _ tota ' of forty (40) quarterly samples were each l
analyzed for St-89 and Sr-90. No Sr 89 or Sr 90 was detected..
l
- t' Based on the analytical results, the operation of Beaver-Valley Power Station did not contribute to any--
increase -in air particulate radioactivity during:CY 1990.
- n b,
Radiciodine A
total ;of five-hundred twenty- (520) weekly
[
-charcoal filter samples were ' analyzed for I-131.
No : detectable concent' rations were-found; at any-locationst
. Based oon analytical results, :'the operation of Beaver Valley Power Station did not;2 contribute -to:
r any ~. ' increase ' in' airborne cradioiodine :during CY.
- 1990.
l a
i.
. - ~.. -, -.
SECTION V o C DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING C.
Monitoring of Sediments and soila (Soil Monitoring is required every 3 years and was not required in 1990) 1.
Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt.
Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.
)
2.
Sampling Program and Analytical Techniques a.
Program 4
River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and 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 and are shown in Figure 5 C l.
Bottom sediments are analyzed for gross alpha and beta activity, strontium, uranium, and the gamma-emmitting radionuclides, b.
Analytical Procedures Gross beta - sediments and soils are analyzed for gross beta by mounting a 1 gram portion of dried sediment in a 2" planchet. The sample is counted in a low background, gas flow proportional counter.
Self absorption corrections are made on the basis of sample weight.
Gross alpha activity of sediment or soil is.
analyzed in the same manner as gross beta except that the counter is set up to count only alpha.
Gamma analysis of sediment or soil is performed in a 300 ml plastic bottle which is counted by a gamma spectrometer. -..
SECTION V - C DUQUESNE LIGirr COMPANY TIGURE. 5.C.1 1990 Annual Radiological Environmental Report FIGUM 5.C.1 DMMEMM N LOCATioM8-900.!T su)les a g)tt N
64= ness amany anA nn'~CouW,T l
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SECTION V - C DUQUESNE LIGHT COMPANY 1990 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 1990)
(continued) 2.
Sampling Program and Analytical Techniques (continued) b.
Analytical Procedures (continued)
Strontium 89 and 90 are determined by radiochemistry. A weighed sample of sediment or soil is leached with Nitric Acid HNO. A stable 3
carrier is added for determination of recovery.
Strontium concentration and purification is ultimately realized by precipitations of strontium nitrate in fuming nitric acid.
Additional hydroxide precipitations and barium chromate separations are also used. The purified strontium is converted to a carbonate for weighing and counting.
Samples are counted soon after separation (5 - 7 days is allowed for yttrium ingrowth).
Activities are calculated on the basis of appropriate Sr-89 decay and Y-90.
Separate 8
mounts covered with a 80 mg/cm aluminum absorber are used for counting in a low background beta counter.
Uranium isotopic analysis of sediment and soil samples were performed by alpha spectrometry after leaching and isolation' of the uranium by an ion exchange chromatography plus mercury cathode electrolysis, then electroplated onto a planchet.
3.
Results and Conclusions A summary of data is. presented in Table V.A.2.
a.
Sediment A total of (8) samples were analyzed for gross alpha and gross beta. Results were comparable to previous years.
A total of eight (8) samples were analyzed for Sr-
'89 and Sr-90.
No Sr-89 or Sr-90 was detected.
l l
1 1
SECTf0N V - C DUQUESNE LIGl!T COMPANY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING C.
Monitoring of Sediments and Soils (Soil Manitoring is required every 3 years and was not required in 1990)
(continued) 3.
Results and Conclusion (continued)
'a.
Sediment (continued)
A total' of eight (8) samples were analyzed by gamma spectrometry.
Naturally occurring K 40 and Th 228 was found in every sample; Be-7 was found in four samples; and Ra-226 was found in all but one sample.
Small amounts of Cs-137 from previous nuclear weapons tests were found in all river sediment samples including upstream above Montgomery' Dam-which are unaffected by plant effluents.
A small amount of-Co-58 was detected in one samplo downstream of the plant at New Cumberland Dam. 11e result was slightly above the minimum detectable activity and may be attributed to station releases or from expected variability in the analyses results of very low activity.
Small amounts of Mn-54, Co-58 Co-60 and Cs-137 were i
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, f
The analyses demonstrate that the Beaver Valley
-Power Station-did not contribute a significant
'I increase of radioactivity in the Ohio Rivtr sediment.
.The positive.results detected are attributable to authorized releases from the. Beaver Valley Power Station and are characteristic of the effluent.
These.results confirm that the station assessments. prior to' authorizing radioactive discharges,Lare adequate and that the environmental monitoring program is sufficiently sensitive.
SECTION V'
- D' DUQUESNE L2GHT COMPANY 199_0 Annual Radiological Environmental heport V.
ENVIRGNMENTAL MONITORING D.
_ Monitoring'of Feederops and Fooderops
- 1. '
Ch'aracterization of Vegetation and Fooderops According ~ to a survey __ made in 1985, there were approximately_610 farms in Beaver County. The principal source of revenue for=the farms was in dairy products which amounted to nearly $5,998,000.
Revenues from other farm products were as follows:
. $2,013,000 Field Crops, Truits....
169,000 Horticulture and
~ 994,000 Mushrooms.
-Heat and Anims1 Products...,,.
. $1,638,000 Vegetables and i
Potatoes.-.
266,000 Poultry Products..
. $- 426,000 c.
-The-total-land in Beaver County is -218,600 acres.
~
Approximately.- 134,592 acros are forested land and 61,176
-acres are pasture and crop land.
q
-2.
Sampling Program and Analytical Techniques-a'.
Program 3
Representative samples of cattle feed are collected t
monthly from the -nearest-. dairy (Searight).
- See' Figure 5. D.1 '.
Each-sample is analyzed by gamma spectrometry.
The monthly' samples are. composited:
.into a. quarterly sample which-is' analyzed-for Sr-L
-90.
n was. performed August,Ji990_to A-land use census L
locate the nearest'rasidence and nearest garden _of-greater than 500-square feet producing fresh leafy l-
. vegetables within a - five -(5): mile. radius of1 thel
. ite. -See'_ Table V.D.1 for results.
s Fooderops (vegetables)l were callected at garden.
i locations during the. summer of
_1990.
Leafy
,,E
'getables
'i.e.,
' cabbage were obtained :from-
..ippingport, Georgetow,:
- Industry, PA, - -and.
Weirton,- WV.._All samples were; analyzed for: gamma emitters'(including I-131 by gamma spectrometry).,
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1 FIGUE 5.D.1 P
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SECTION V - D DUQUESNE LIGRT COMPANY l
1990 Annual Radiological Environmental Report l
TABLE V.D.1 Closest Residence and Garden in Each Sector Sector Closest Residence
- Closest Garden
- 1 1,55 mi N 2.54 mi N 2
1,59 el NNE 1,61 mi NNE 3
0.42 mi NE 0,57 mi NE 4
0.38 mi ENE 0.98 mi ENE 5
0.42 mi E 1.93 mi E 6
0.87 mi ESE 1.00 mi ESE 7
1.40 mi S 1.99 mi S 10 0.80 mi SSV 1.55 mi SSW 11 1.46 mi SW 1.67 mi SW 12 1.46 mi WSW 1,46 mi WSW 13 2.27 mi V 2.27 mi W
.14 2.77 mi WNW 2.92 mi WNW 15 0.91 mi NW 0.92 mi NW 16 0.91 mi NNW 1.29 mi NNW
- Direction and Distance from Midpoint between Reactors -
SECTION V - D DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report V.
ERVIRONMENTAL MONITORING D.
Monitoring of Feederops and Fooderops (continued) 2.
Sampling Program and Analytical Techniques (continued) b.
Procedures Gamma emitters, including I-131, are determined by scanning a dried, homogenized sample with the gamma spectrometry system.
A Ge(Li) detector in utilized with this system.
Strontium 90 analysis for feedstuff is performed by a procedure similar to that described in V.C.2.
Radiciodine (I-131) is dete'rmined by radiochemistry.
Stable iodide carrier is first added to a chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt in dissolved in water, filtered and treated with sodium hypochlorite. The iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into chloroform.
It is then back-extracted as iodide into 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 cout.t ing.
3.
Results and Conclusions A summary-of data is presented in Table V.A.2.
4 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 six (6) samples and Th-228 was detected in four (4) samples. __
SECTION V - D DUQUESNE LIGHT COMPANY
'1990 Annual Radiological Environmental Report V.
ENVI(10NMENTAL MONITORING D.
Monitoring of Feederops and Fooderops (continued) 3.
Results and-Conclusions (continued) b.
Food i
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 consistent with (or lower than) those. obtained in the pre-operational program.
These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in foods and feeds in the vicinity of the site.
I _
SECTION Y - E DUQUESNE LIGHT COMPANY 1990 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 1
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, 1990 is shown in-Figure 5 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 S.E.2 and described below.
Number of Milch Direction and Distance from Collection Site Dairy Animals Midpoint between Reactors Period 25 Searight 40 Cows 2.2 miles SSW J an. - Dec.
27 Brunton 90 Cows 7.3 miles SE Jan. - Dec.
29A Nichol 65 Cows 8.C miles NE
-Jan. - Dec.
96 Windsheimer 45 Cows 10.3 miles SSW Jan. - Dec.,
r SECTION V - E DUQUTSNE LIGHT COMPANY 1990 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 2 Goats
- 3.5 miles SE July - Sept.
'101**
Telesz 5 Goats
- 2.6 miles E Apr. - July 102**
Ferry 4 Goats
- 3.3 miles SE June - Sept.
104**
Fordyce 3 Goats
- 2.50 miles NNW May - Dec.
105**
Ambrose 45 Cows 3.86 miles WSW Jan. - May Oct. - Dec.
106** -Conkle 41 Cows 3.75 miles WSW Jan. - May Oct. - Dec.
107**
Boyd 45 Cows 5.11 miles SSW Jan. - March
- Milk Usage - Home Only.
- Highest potential. pathway dairies.
I,
FIGURE 5.E.1 SECTION V - E DUQUESNE LIGHT COMPANY 1990 Annual Radiological Lw ironmental Report l
EsEAVER VALLEY POWER STATION MILCH ANIM As_ CENSUS m.m.m
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SECTION V E
DUQUEbNE L10}lT COMPANY TIGURE 5.E.2 1990 Annual RadiologAcal Environmontal Report W8WitWTAL teosetesuses LOCATHhat -
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SECTION V E
DUQUESNE LIGHT COMPANY 1990 Annual hadiological Environment al Report V.
ENVIRONMENTAL MONITORING E.
Monitoring of Local Cow's Milk (continued) 2 Samp;
- g, Program and Anaiytical Techniques (continued) a.
Program (continued)
The sample from Searight Dairy was collected and analyzed weekly for radiciodine using a procedure with a high sensitivity.
Samples from each of the other selected dairies were collected monthly when cows are indoors, and bi-weekly when cows are grating.
This monthly or bi-weekly sample is analyzed for Sr 89 Er-90, gamma emitters including Cs-137 (by Spectrometry) and 1 131 (high sensitivity annlysis),
b.
Procedure Radiciodine (1 131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low level bets counting system.
Gamma emittern are determined by gamma spectrometry of a one liter Marinelli container of milk.
S t ront ium analysis of milk is similar to that of other foods (refer to V.C.2) except that
- n. ilk 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 seven (167) samples were analyred for I-131 during 1990.
All 1-131 activities in milk were below the minimum detectable level.
1 86
SECTION V = E DUQUESNE LIGHT COMPANY 1990 Annual Rcdiolegical Environs:ntal Report V,
ENVIRONMENTA!, MONITORING E.
Monitoring of Local Cow's Milk (continued) 3.
Results and Conclusions (continued)
A total of one hundred thirty three (133) samples were analyzed for Sr 89 and Sra90.
No Sr 89 was detected.
St 90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the normally expected range.
A total of one hundred thirty four (134) samples were analyzed by gamma spectrometry.
The predominant isotope detected was naturally occurring K 40 and was found in all samples.
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.
r I l.
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SECTION Y o F DUQUESNE &lGHT COMPARY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING F.
Environmental Radiation Monitoring 1.
Description of Regional Background Radiation Levcis and Sources The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300 400 feet.
Most of the land is wooded.
The principal geologic features of the region are nearly flat-laying sedimentary beds of the Pennsylvania Age.
Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers.
Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest.
Most of tho' 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 Ohio River Valley and along major tributary streams.
Based on surveys reported in previous annual reports, exposure rates ranged from 6 12 p.4/hr. Results for 1990 indicated that background radiation continued in this range.
2.
Locations & Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).
In 1990 there were a total of forty four (44) off site 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.
1
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l SECTION V F
DUQUESNE LICHT COMPANY 1990 Annual Radiological Environmental Report
{
V.
ENVIRONMENTAL MONITORINJ T.
Environmental Radiation Monitoring (continued) 2.
Locations & Analytical Proceiures (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) provide continuous integrating monitoring.
Sixteen PICS (Sites 1 16) are part of the Sentri 1011 Radiation Monitoring System which is a microcomputer based data acquisition system. Data from the stations are sent at 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 rcadings. 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 teflon) during 1990 are summarized in Table V.A.2, and the-quality control TLD results are listed in Table 111.1.
Results for the PICS are listed in Table V.F.1.
The annual exposure rate of all off-site TLDs averaged 0.15 mR/ day in 1990.
As in previous years, there was some variation among locations and seasons as would be expected.
In 1990, ionizing radiation dose determinations from TLDs averaged approximately 55 mR for the year. This is l
comparable to previous years. There wat no evidence of anomalies that could be attributed to the operation of l
the Beaver Valley Power Station. The TLDs confirm that l
changes from natural radiation levels, if any, are f
neglible.
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1990 Annual Radiological Environmental Report I
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94-
SECT!0N V F
DUQUESRE LIGHT COMPANY 1990 Annual Radiological Environmental Report TABLE V.F.1 I
Prensurized Ion Chambers - Results Distance and Direction from Midpoint Average Site Location Between Reactors (mR/ day) 1 Industry Hill 0.5 mi N 0.193 2
Industry Rt. 63 0.9 mi NNE 0.204 3
Industry 2.25 mi NE 0.196 4
Cooks Ferry 0.5 mi ENE 0.210 Shippingport Bridge South 0.45 mi E 0.219 6
BVPS Entrance 0.4 mi ESE 0.217 7
Unit #2 Laydown 0.3 mi SE 0.211 8
Birdhill Road 0.9 mi SSE 0.200 9
Past DLCO Microwave 0.35 mi 5 0.213 10 DLCO Microwave 0.35 mi SSW 0.204 11-Heyer's Farm 1.45 mi SW 0.229 12 J & L Steel Tie 0.75 mi WSW 0.215 13 F. P. Microwave 1.5 mi W 0.176 14 Midland Substation South 0.6 mi VNW 0.225 15 Midland Substation North 0.75 mi NW 0.232 16 Sunrise Hills 1.1 mi NNW 0.211 AC-201 Raccoon Municipal Building 2.4 mi SE 0.247 AC-202 Kennedy's Corners 2.0 mi t.T 0.228 2-054 Hookstown Substation 2.9 mi WSW 0.243 l
Y-028 J&L 1.3 mi NW 0.180 l
SECTION V - G DUQUESh'E LIGHT COMPANY 1990 Annual Radiological Environmental Report V.
ENVIR0tfENTAL MONITORING G.
Monitoring of Fish 1.
Description During
- 1990, fish collected 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 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 spectrometry.
Fish sampling locations are shown in Figure 5.G.I.
b.
Procedure A sample is prepared in a standard tared 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a 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 nine (9) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was found in all samples.
Co 58 was detected in one sample and is attributable to station releases. The activity found is consistent with station data of authorized radioactive discharges which were well within the limits permitted by the NRC license.
The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River fish population.._ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _
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49 Upstream - Montgornery Dam ENVIRONMENTAL MONITORING PROGRAM M
FISH SAMPLING LOCATIONS
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SECTION V o H DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report V.
l'NVIRONMEN AL HONITORING H.
Monitoring of
- Surface, Drinking, Well Vaters and Precipitation 1.
Description of Vater Sources The Ohio River is the main body of water in the area.
It is used by the Beaver Valley Power Station for plant make-up for the cooling tower and for receiving plant liquid effluents.
Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site.
It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Hunicipal 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 dovastream.- The heavy industries in Midland, as well as others downstream use river water for cooling purposes. Some.of these plants also have private treatment facilities for plant sanitary water.
Ground water occurs in large volumes in the gravel terraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm.
In general, the BVPS site experiences cool winters cnd 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.
98-
~
SECTION V = H DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Rsport V.
ENVIRONMENTAL MONITORING.(continued) and Precipitation H.
Monitoring of Surface. Drinking. Wel_1__Wa_tersa (continued) i -
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 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 1 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 locations:
Upstream of Montgomery Dam [ River Mile 29.6); and at J6L Steel's river water intake [ River Mile 36.2). The automatic sampler takes a 20 40 m1 sample every 15 minutes and
- is collected on a 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.
1 The weekly composites from the automatic river water sampler upstream at Montgomery Dam _are analyzed for I-131.
Tho' 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) l _
L Drinking (treated) water is collected at both Midland
-(PA) and East Liverpool (OH) Water-Treating Plants.
1m automatic _ sampler at each-location _ collects 20 40-mi every 20 minutes. These intermittent samples are then _composited into a weekly sample.
A weekly grab-sample is also taken at the DLC Training Building in E
Shippingport, PA.
The weekly sample _ from each location is analyzed. by gamma spectrometry.
The weekly samples are also analyzed for I-131.
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SECTION V H
DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report l
V.
ENVIRONMENTAL. MONITORING H.
Monitorint, of
- Surface, Drinking.
Well_
- Vaters, and precipitation (continued) 2.
Sampling and Analytical Techniques (continued) b.
Drinking Vater (Public Supplies) (continued)
Monthly composites of the weekly samples are analyzed for gross alpha. gross beta, and by ganen spectrometry.
Quarterly composites are analyzed for H-3, Sr 89, St 90 and Co 60 (high sensitivity).
Locations of each sample point are shown in Figure 5.H.l.
c.
Ground Water 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 aret 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
- Leta, tritium, and by gamma spectrometry, d.
Precipitation Precipitation is collected at Shippingport, PA, East Liverpool, OH and Weirton, VV.
Precipitation when available is collected each week and then composited into monthly and quarterly samples. The monthly samples are analyzed for gross beta end gamma emitters and the quarterly composites are analyzed for H-3, St-89 and Sr 90.
Locations of each sample point are shown in Figure 5.H.l.
-100-
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SECTION Y a H DUQUESNE LIGHT COMPANY 1990 Annual Rediological Environm2ntc1 Rsport V.
ENVIRONMENTAL MONITORING H.
Monitoring of Surface.
- Drinking, Vell Waters.
and Precipitation (continued) 2.
Sampling and Analytical Techniques (continued) f e.
Procedures Gross alpha and gross beta activitics are determined first by evaporating one liter of the sample on a hotplate. The residue is mounted and I
dried on a 2 inch stainless steel planchet.
The sample is counted in a low background, gas flow proportional counter.
Self absorption corrections are made on the basis of sample weight.
Gamma analysis is performed on water sample by loading one liter of sample into a one liter marinelli container and counting on a Ge(L1) gamma spectrometry system.
Strontium 89 and 90 are determined on water samples by a procedura similar to that described in V.C.2 except that the leaching step is eliminated.
Cobalt-60 is determined with a sensitivity of 1 pC1/1 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 s ample to hydrogen and counting the activity in a 1 liter low level gas counter which is operated in the proportional range in anti coincidence mode.
Radiciodine (I-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low level beta counting system.
3.
Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, ground and precipitation) are provided by sample type and analy' sis in Table V. A.2.
These are discussed below.
l
-102-
SECTION V H
DUQUESNE LIGHT COMPANY
-1990 Annual Radiological Environmsntal Roport V.
ENVIRONMENTAL MONITORING-
'H.
Monitorina of Surface.
Drinkinn.
Well Vaters.
and Precipitat f or) (continued) 3.
Results and Conclusions (continued) 1 a.-
Surface Water A total of seventy-two (72) samples were analyzed for gross alpha and gross beta. No alpha activity was detected in any of the samples.
Positive beta results above preoperational levels were detected in the BVPS discharge area and are attributable to station-releases. The beta activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license.
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 Co 58 and tritium results were detected in the BVPS discharge area -and are attributable to station releases. All other samples taken upstream and downstream were within pre operational levels.
The activity found-.in the station discharge area is consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license.
A ' total of seventy-two (72) samples were anlayzed by gamma spectrometry.
Positive Co 58 results were detected in the BVPS discharge area and tre attributable' to station releases.
The Co-58 activity found in the -station-discharge area is consistent with station data of-authorized radioactive discharges. and were within limits-permitted by the NRC ~1icense.
No other gamma j
omitting adionuclides were detected.
A total of fifty two (52) samples were analyzed for I-131 using a highly sensitive technique.
Trace levels of I-131 were measured in two (2) of the weekly samples.- The results were slightly above the minimum detectable activity.
The positive results were detected at a control location above the BVPS discharge and could not be attributed to -
plant releases. The results may be attributed.to expected variability in the analyses results of very low levels of activity.
-103-L.
~,. -,
SECTION Y
- H DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report j
V.
ENVIRONMENTAL MONITORING H.
Monitoring of
- Surface, Drinking, Well Waters,_
and Pretipitatforn (continued) 3.
Results and Conclusionn (continued) b.
Drinking Water A total of thirty six (36) samples were analyzed for gross alpha and gross beta.
All results wers within a normal range.
A total of twelve (12) samples were analyzed for H 3, Sr-69 and Sr-90 as well as a high sensitivity analysis for Co 60.
No Sr 89, Sr 90, or Co 60 were detected.
The H3 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 1 131 using e highly sensitive technique.
Trace levels of 1-131 were measured in eight (8) 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 releaser.
The results may be attributed to expected variability in the analyses results of very low levels of activity, c.
Ground Water A total of. sixteen (16) samples were each analyzed for gross alpha, gross beta, H3 and by gamma spectrometry.
No alpha activity was detected in any of the samples. The gross beta and H 3 results are within pre-operational rangen.
No gamma emitting radionuclides were detected.
-104-
t SECTION V
- H DUQUESNE LIGHT COMPANY 1990 Annual Rediological Environm2ntal Rsport V.
ENVIRONMERTAL MONITORING (continued)
H.-
Monitoring of Surface.
Drinking.
Well
- Waters, and Precipitation (continued) 3.
Results and Conclusions (continued) d.
Precipitation A total of thirty four (34) samples were analyzed for gross beta.
All results were within a -normal range.
A total of twelve (12) samples were analyzed for H 3 Sr 89 and St-90.
Seven (7) positive tritium results detected were within normal levels.
No Sr-89 or Sr 90 was detected.
[
A total of thirty four (34) samples were analyzed by gamma spectrometry.-
Naturally occurring Be 7 F
was detected in eleven (11) samples.
e..
Summary The data from water analyses demonstrates that the Beaver Valley Power Station did not contribute a significant increase of radioactivity. in local river _ drinking, well waters or precipitation. The few positive results which.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 concent ration :
(averaged-over a year) attributable to Beaver.
Valley Power' Station, was only 0.301% of the Maximum Permissible Concentration allowed by the Federal Regulations for water discharged to the Ohio River.; The Ohio' River.further reduced this s
L concentration by a factor of ~ 600 prior to its p
potential use by members of the public, t
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SECTION V - I DUQUESNE LIGRT COMPANY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL. MONITORING I.
Estimates of Radiation Dose to Man 1.
Pathways to Man - Calculat ional Models The radiation doses to man as a result of itenver Valley operations were calculated for both gaseous and 11guld effluent pathways using NRC computer codes X0QD0Q2, GASPAR, and LADTAP.
Dose factors listed in the ODCH were used to calculate doses to maximum individuals from radioactive noble gases in discharge plumes.
Beaver Valley effluent data, based on sample analysis in accordance with the schedule set forth in Appendix A of the BVPS license, were used as the radionuclide activity input.
Each radionuclido contained in the Seini Annual Radioactive Effluent Release Report (noble
- gases, particulates, radiciodines and tritium) were included as source terms when they were detected above the LLD values.
All LLD values reported by Beaver Valley Power Station are equal to or lower than those required by the Technical Specifications.
All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments.
The release activities are based on laboratory analysis.
When the activity of noble gas was below detection sensitivity, either the inventory based on its MDL or an appropriate but conservative ratio to either measured activity of Kr 85 or Xe 133 was used. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to XOQD0Q2 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.
-106-
SECTION V I
DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report V.
ERV!RONMENTAL MONITORING Estimates of_ Radiation Dese to Man (continued) 1.
Pathways to Man Calculational Models (continued)
All potentially radioactivo liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using Intrinsic Gerr;anium 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 fron. these analyses are tabulated and used as the radionuclide activity input term in LADTAP.
A_ hypothetical real individual for liqui 6 pathways is located at Midland.
Except when more recent or specific data for the period is available, all other input to LADTAP are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109.
Pathwsys, which were evaluated, are drinking
- water, fish consumption, shoreline recreation, swimming., and boating.
2.
Results of Calculated Radiation-Done to Man Liquid Releases a.
Individual Dose The doses which are _ calculated by the model described above are to a
hypothetical real individual located at Midland since this is the nearest location where significant exposure of a member of the public could potentially--occur; therefore, this location is used to calculate the-maximum - exposure. A breakdown of doses by pathway and organ is provided in Table V.1.1 for the maximum individual.
Included in this table is a breakdown of a typical dosa to individuals from natural ~
radiation exposure.-
The results of calculated-radiation. dose to the hypothetical real o
-individual are' compared to BVPS annua 1111mits in Table V.I.2..
b.
.Upon - implementation of the Unit 2 Technical-Specifications and incaption of
'the.
liquid.
discharge procedures at Unit 2 on July 24,.1987, g
l the discharge limits were. clarified to be reactor specific; i.e..
Unit 1=and Unit 2 have individual (not combined) dose limits. Therefore, the annual limits listed in Table V.I.2 were derived by multiplying the. individual Technical Specification reactor limits by a factor of two (2).
107-
. ~
i TA;LE V.I.I Radiation Dose to Maximum Individual" arem/yr5 Beaver Valley Power Station - Liquid Releases p
i O
i o
z MAXIMUM USAGE WHOLE g-PATHWAY-GROUP FACTOR-SKIN ORGAN THTROID BONE BODT j
a i
Fish Consumption Adult 21.0 kg N/A 0.00199 0.0000453 0.000598 0.000827 (CI-LLI) s e
i Drinking Water Infant 510 liter N/A 0.00336 0.00279 0.000101 0.00326 C
(CI-LLI) g Shoreline Activities Teen 67 hr.
0.000474 0.000403 5E DE TOTAL HREM 0.000474 0.00489 0.00279 0.000682 0.00326 ow O
MAXIMUM (Teen)
(Adult)
(Infant)
(Adult)
(Infant) 8' l
INDIVIDUAL (GI-LLI) p[
i EE
-4 TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE yn C
<o 4
Ambient Camma Radiation:
58
)
3h i
40 f
Radionuclides in Body :
e 1
m i
Global Fallout
<1 E
Radon 198 3
TOTAL mren 296 i
- Located at Midland Drinking Water Intake
.-a Total liquid releases are from Site (combined Units 1 and 2) g b
b National Academy of Sciences "The Effects on Populations of Exposure to Low Levels of f
C Ionizing Radiation," BEIR Report, 1990 g
-6.
SECTION V - I DUQUESRE LIGHT COMPANY 1990 Annus1 Rediological Environmsntal Report TABLE V. I.2 Results of Calculated Radiation Dose to Man Beaver Valley Power Station. Liquid Releases Maximum Exposure Hypothetical BVPS Annual Percent of Real Individual Limits Annual mrem mrem Limit TOTAL BODY Adult 0.00277 6.0 0.046 Teen 0.00171 6.0 0.029 Child 0.00251 6.0 0.042 Infant 0.00326 6.0 0.054
'T ANY ORGAN Adult 0.00489 20.0 0.025 (GI-LLI)
Teen 0.00305 20.0 0.0015 (GI LLI)
Child 0.00307 20.0 0.0015 (Liver)
Infant-0.00336 20.0 0.017 (GI-LLI)
Maximum Total Body Dose - Capsule Summary mrem 1990 Cel;ulated 0,00326 Final Environmental Statement 3.5 Highest Organ Dose 1990 Calculated 0.00489 Final Environmental Statement 4.7
-109-
SECTION V = I DUQUESNE LIGift COMPANY 1990 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING I.
Estimates of Radiacion Dose to_ Man (continued) 2.
Results of Calculated Radiation Doso to Man - Liquid heleases (continued) c.
Population Dose The 1990 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was Largest Isotope Han Millirem Contributors TOTAL BODY 108 11 - 3 95.7 mrom Co 58 5.5 mrem To 55 4.4 mrem TifYROID 95.7 Il-3 95.7 mrem 3.
Results of Calculated Radiation Done to Man Airborne Releases The results of calculated radiation dose to the maximum exposed individual for BVPS airborne radioactive effluents during 1990 are provided in Table V.I.3.
The doses include the contribution of all pathways.
A 50-mile population dose is also calculated and provided in Table V.I.3.
li 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, tnc annual limits listed in Table V.1.3 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.
-110
ll SECTION V o I DUQUESNE LIGHT COMPANY 1990 Annual Radiological Environmental Report j
i V,
[NVIRONMENTAL MONITORING l
I.
Estimates of_ Radiation Done to Man (continued) 4.
Conclusions - (Beaver Vallev_Powet Station) l Bened upon the estimated dose to individuals from the natural background radiation exposure in Table V.I.1.,
i the incremental increase in total body dose to the 50-i mile populction (4 million people), from the operation of-Beaver Valley Power Station - Unit No.1 and No. 2, is less than 0.0001% of the annual background.
l The calculated doses to the public from the operation of i
Beaver Valley Power Station - Unit No. 1 and No. 2, are l
below BVPS annual limits and resulted in only a small incremental done to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public.
f l
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-111-
i TABLE V.I.3 Results of Calculated Radiation Dose to Man (1990) m" O
Beaver Valley Fever Station - Airborne Radioactivity
~
z 50-MILE PERCENT OF FOPULATION DOSE
~
MAXIMUM EXFOSURE BVPS ANNUAL LIMIT eAn ren ANNUAL LIMIT ures INDIVIDUAL, mrem ORGAN _
~
k e
30 0.19 0.764 8
0.0556 TOTAL BODY 30 C.22 0.977 5
0.0655 SKIN 30 o,19 0.768 "e
0.0563 "e E LUNG 30 o,19 o,773 gg 0.0570 E
THYROID C T4
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APPENDIX i
Contractor Laboratory EPA Interlaboratory
. Comparison Program
DUQUESNE LIGIIT COMPANY - 1990 US EPAINTERI.ABORATORY COMPARISON PROGRAM 1990 J
(Page 1 of 3)
EPA TI Norm Dev.
"Warmieg EPA Date TI Malled Date EPA Preparation Rescles '
Issued Results Media Naclide Results(a)
Results(b)
(Known)
'" A ctles 01/12/90 03/21/90 0409/90 Weser Sr-89 25.00 1 5.00 24.00 1.73 035 Sr-90 20.00 i 1.50 19.67 2.52
-038 01/26/90 02/23SO 03/30$0 Weser '
Gr-A%As 12.0 i 5.0 10.00 i 1.73
-0.69 Gr-Beta 12.0 5.0 1233i 1.53 0.12 02 S 9!90 03/23SO 040960 Weser Co40 15.00 1 5.00 15.00 i 3.46 0.00 9.07
-0.95 2n45 139.00 i 14.00 13133 i ~
4.04
-3.13
- "(c)
Rn-106 139.00 i 14.00 113.67 i Cs-134 18.00 1 5.00 1533 1 231
-0.92 Cs-137 18.00 1 5.00 19331 321 0.46 Ba-133 74.00 1 7.00 66.00 1 3.46
-1.98 02/23/90 03/22/90 0409/90 Waar H-3 4976.00 i 498.00 4900.00 i 100.00
-0.26 03S 9/90 05 S 3/90 05/21/90 Weser Ra-226 4.9 1 0.7 4.73 i 0.47
-0.41 Ra-228 12.7 i 1.9 13.00 i 1.00 0.27 03/30/90 0608/90 07#3/90 AkFilmer Gr-A%As 5.0 i 5.0 633 i 038 0.46 Gr-Beta 31.0 i 5.0 31.67 i 0.58 0.23 Y
Sr-90 10.0 i 1.5 9331 0.58
-0.77 Cs-137 10.0 1 5.0 10.67 1 1.15 0.23 04/17B0 06/22/90 07/20/90 Weser Gr-A%As 90.00 1 23.0 79331 2.89
-0.80 Ra-226 5.0 i 0.8 5.67 i 0.15 1.44 Ra-228 10.2 i 1.5 937 i 1.44
-0.%
Gr-Beta 52.0 1 5.0 5333i 1.53 0.46 Si-89 10.0 i 5.0 10.67 1 1.15 0.23 Sr-90 10.0 i 1.5 9.67 i 0.58
-038 Cs-134 15.0 1 5.0 12.67 i 1.53
-0.81 Cs-137 15.0 i 5.0 1633i 1.15 0.46 04/27/90 06/22/90 07/27BO Mist Sr-89 23.0 1 5.0 24.67 1 1.53 0.58 Sr-90 23.0 i 5.0 24.00 1 0.00 035 I-131 99.0 i 10.0 89.67 1 3.21
-1.62 Cs-137 24.0 i 5.0 2733 1 2.52 1.15 K-40 1550.0 i 78.0 148333 i 75.06
-1.48 f
See footnotes at end of table.
~
DUQUESNE LIGilT COMPANY - 1990 US EPA INTERLABORATORY COMPARISON PROGRAM 1990 (Page2of3)
EPA T1 Norra Dev.
Results(b)
(Known)
" Action 05/04/90 OS22SO 07/31 S 0 Wakr Sr-89 7.0 i 5.0 6.67 i 0.58
-0.12 Sr-90 7.0 5.0 6 67 i 038
-0.12 05/11/90 06/0R)90 07J03SO Waar Gr-A%s 22.0 i 6.0 16.00 i 1.00
-I.73 Gr-Beta 15.0 1 5.0 17.00 1 1.00 0.69 06/08/90 07/17/90 08/14190 Weser Co40 24.0 1 5.0 25331 2.52 0.46 Zn45 148.0 i 15.0 148.67 i 3.06 0.08 Re-106 210.0 1 21.0 196 00 1 20.66
-1.15 Cs-I34 24.0 1 5.0 23.67 i 2.89
-0.12 s
Cs-137 25.0 i 5.0 24.67 i 2.08
-0.12 Ba-133 99.0 i 10.0 93.00 1 6.08
-1.04 OS22/90 0f/19BO 08/14!90 Warr 11-3 2933.0 i 352 0 2900.i 100.00
-0.I6 07/13/90
( M)6/90 1009/99 Waser Ra-226 12.1 i 1.8 1137i 0.60
-0.71 Ra-2'8 5.11 1.3 4.20 0.75 1.20 08/10/90 09,'10/90 IW26/90 Warr I-131 39.0 i 6.0 36.00 i 3.00
-0.57 G8/31/90 11/09 X) 11/29/93 Air Fiher Gr-A%a 10.0 i 5.0 16 00 i I.00 2.08
- (d)
Gr-Beta 62.0 1 5.0 6333i 1.53 0.46 1
Sr-90 20.0 i 5.0 18001 1.00
-0.69 Cs-137 20.0 i 5.0 1833i 3.21
-0.58 09/14 S 0 11/2060 12/11/90 Warr Sr-89 10.0 1 5.0 8.67 i 0.58
-0.46 Sr-90 9.01 5.0 9.0 i 1.00 0.00 C9/21SO IW17SO 11]Q5SO Warr Gr-A@s 10.0 1 5.0 11001 1.00 035 l
Gr-Beta 10.0 1 5.0 11.0') i 1.00 0.35 09/28/90 12/04/90 12/24/90 PRk Sr-89 16.0 1 5.0 9.0 f 2.65
-2.42
- (c)
St-90 20.0 1 5.0 1533 1 038
-1.62 I-11 58.0 1 6.0 54.67 i 1.53
-0.96 Cs-137 20.0 1 5.0 2_.00 1.73 1.04 K-40 1700.0 1 85.0 1710.00 1 65.51 0.20 r
See fcomotes at erx! of table-
DUQUESNE LIGHT CO'1PANY - 1990 t-US EPA INERIABO*ATORY COMPARISON PROGRAM 1990
)
(Page 3 of 3)
EPA Date TI Malled Date EPA EPA TI Norm Dev.
- Wareleg Preparation Results Issued Reseh Medle Neellde Result.(a)
Results(b)
(Known)
- *
- A ction l
l IQf1530 11/1660 12J04SO Weser Co40-20.0 1 5.0 21.00 1.00 035 Zr-65 115.0 i 12.0 115.00 11.53 0.00 Ru-106 151.0 i 15.0 142.00 1 8.66
-1.e4 Cs-134 12.0 1 3.0 11.00 1 0.00 035 Cs-137 12.0 i 5.0 1633i 2.52 1.50 Ba-133 110.0 1 11.0 94.67 1 5.13
-2.41
- (f)
IW1960 11/1660 12/04SO Waner H-3 7203.0 1 720.0 713333 1 251.66 0.17 10G060 01/10 S 1 02J04S1 Lab Perf.
Gr-Alpha 62.00 i 16.00 57.00 i 1.C0
-0.54 Sample A
-Ra-226 13.6 i 2.0 12.67 i 1.27
.-J.81 Ra-228 5.0 1 1.3 4.87 1 0.23
-0.18 Sample B Gr-Beta 53.0 1 5.0 51.00 1 231 0.12 Sr-89 20.0 1 5.0 19.00 1 3.61 035 Sr-90 15.0 i 5.0 14331 0.58
-0.23 Cs.134 7.0 1 5.0 9.00 1 0.00 0.69 Cs-137 5.0 1 5.0 7.67 1 1.15 0.92
$ 11J09S0 01J04S1 01/29 S 1 Weser Ra-226 7.4 i
'1.1 7.27 1 038
-0.21 Ra-228 7.7 i 1.9 7.57 i 032
-0.12 6
(a)
Average iexpenmental sigma-Expected 1aborssory pecisum(1 sigma.1 deserrnmation)u curve fit is good (0.997). Rinhemern-106 was obtamed from the EPA. Resuhs of spikes wae ac (b)
(c) normahzed standard devistxsi. No additional fenow-ap is necessary,but we will continue no snomsor the results. New calibrer. ions were m.
a u March,1991.
The EPA deposit occupies a amener area ihan our calibraion planchet and heruz has a higher couresng efficiency. No further conectiv: act (d) standard bener represer.zs an air part==taar fiber.
L-A removal of esicium, lead so mAj high suoranen yields. More care le being taken in the stronnum nitrate and stroritmm sulfate,m;,,;4 sis ofintemal QC samples produced good results after L@.~.ag the corrective actxm.
(e) final volume of a least 20 ml "m the stroseum sulfane seep.
Teledyne 1songes vehes. Other isotopes in the sample were measured accars:ely. The calculations wae Ther : is no appuent reason for the devnetsons between the EPA re sewed and activities calculated from other Ba-133 gamma rays. Results were reproduced as reponed.
(f)
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ISOTOPES SO VAN SUMEN AVfNUE WESTWOOD, Ntw JER$tY 075751 November 27, 1990 Mr. J. W. McIntire 3
Duquesne Light Company Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077-0004
Dear Mr. McIntire:
We have made significant progress in resolving the differences in the mea-surement of gross beta in water samples between our laboratory and the midwest laboratory. The primary difference was due to separate self ab-sorption curves for determining the detector efficiency as the function of the residue mass of the sample. The midwest laboratory uses Sr-90 and we use Cs-137. Both are considered acceptable isotopes by the EPA and at very low masses the two curves give essentially the same detector efficiency.
Please see the attached figure. Our laboratory has chosen to use Cs-137 since that is the isotope the EPA uses for the preparation of tntercompart-son samples. Cesium-137 counts with an efficiency closer to the efficiency for Co-60, the one beta-emitter that we occasionally measure in water sam-ples for your program, than the efficiency using Sr-90.
A second feature is that after the initial drying of the residue on the planchet the midwest laboratory " ashes" the residue on the planchet for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in a furnace at 400 degrees C.
Listed below is a comparison of the results of gross beta analysis (in pC1/l) for both laboratories using Cs-137 for determining the self absorption curve, counting for 50 minutes, and no final ashing of the planchet.
TI#
SAMPLE TYPE WESTWOOD MIDWEST 18459 WT 7.2 i 2.1 6.3 i 1.6 18460 WT 6.9 i 2.0 5.1 i 1.3 18464 WD 4.6 i 1.9 4.4 1.4 When we first started this intercomparison, the midwest laboratory, using Sr-90 for the self absorption curve, reported 4.4 i 0.5, 3.1 i 0.5, and 2.5 0.4, respectively. 'Ihus we have made good progress.
l AI-19 Easyunk 62877198 5586
W TELEDYNE ISOTOPES We suggest that for your program the midwest laboratory use the Cs-137 self absorpuon curve and not to perform the final ashing step. For the 1990 data the midwest laboratory could recalculate the results using the Cs-137 self absorption curve and the agreement between the two laboratories should be much better.
You had requested that we a. alyze six samples, three surface and three drinking water samples. We did a total of six, but the results from the mid-west laboratory of the three listed below included the ashing step (and 800 minutes counting times).
TI#
SAMPLE TYPE WESTWOOD MIDWEST 18461 WT 5.5 1 2.0 4.7 i 0.5 18462 WD 2.6 i 1.6 3.6 i 0.5 18463 WD 2.8 i 1.6 3.4 i 0.5 The agreement between the laboratories is good.
Sincerely, h
N
, David' Martin, Ph.D Vice President-Technical JDM:cs cc: L. Huebner 2
1 AI-20 4
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WTEUiD(NE ISOTOPES l
COMPARISON OF SELF-ABSORPTION
.9 Sr-90/Y-90
.0 in Ha2C05 mo e
.6 in Na2CO3
.5
.4 6
.2 4
.6
.0 1
NASS in grams A1-21
SPTEI AWNE ISOTOPES 60 VAN SyntN AvtNyt t
Wiliwo00. Mtw Jtm6tV Crt?S
^
April - 1, 1991 -
Mr. J W. McIntire Duquesne Light Company Beaver Valley Power Station
' Post Office Box 4:
Shippingport, PA-15077 0004
Dear Mr. McIntire:
In reference to my letter, dated November 27, 1990, the Tl midwest laborctory has, until recently, been " ashing" the residue of water samples as the final step in preparation-for gross alpha / gross beta counting, in the j
Westwood laboratory we do not perform that step because we feel that sorne of the residue may be volatilized and consequently some of the radioactivity may be lost.
Sincerely,
, Lk.
J, David Martin, Ph.D Vice President-Technical JDM:cs TELsx is4474 Tovisor wiwt AI.22
' * * " x (200 mm
l l
APPENDIX ll QC Laboratory i
l' EPA Interlaboratory l
Comparison Program i
- u..
INTERLABORATORY COMPARISON PROGRM1 RESULTS NOTE: TIML participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results are reported in Appendix A.
Also reported are results of in-house. spikes and blanks.
Appendix A is updated twice a year; the complete Appendix is included in January and July monthly reports only.
-Please refer to January and July Reports for information.
January, 1991 AII-l l
Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971.
These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.
The purpose of such a program is to provide an independent check on 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 the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environ-mental sample crosscheck program for milk, water, air filters, and food sampics during the period January 1986 through December,1990.
This program has been conducted by the U.S.
Environmental Protection Agency Intercompari son and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for thermoluminescent dosimeters (TLDs) 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.
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.
An-2
A
-Table A-1.
U.S. -Environmental Protection Agency's' crosscheck program, comparison of EPA and Teledyne isotopes Midwest Laboratory -results for milk, water, air filters, and food samples,1986 through 1990.8 Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 12 :C
- 15. N=1 Limits STF-447 Food Jan 1986 Sr-89 24.312.5 25.0 5.0 16.3-33.7 Sr-90 17.320.6 10.021.5 7.4-12.6 I-131 22.712.3 20.010.6 9.6-30.4 Cs-137 16.320.6 15.015.0 6.3-23.7 K
-927146 9501144 701-1199 STW-448 Water Feb 1986 C r-51 45.013.6 38.025.0 29.3-46.7 Co-60 19.711.5 18.015.0 9.3-26.7 Zn-65 44.013.5 40.015.0 31.3-48.7 Ru-106
<9.0 0.015.0 0.0-8.7 Cs-134 28.312.3 30.015.0 21.3-38.7 Cs-137 23.710.6 22.015.0-13.3-30.7
- STW-449. -Water Feb 1986 H-3 5176148 52271525 4317-6137 STW-450 Water Feb 1986 U total 8.010.0 9.016.0 0.0-19.4
- STM-451-Mil k Feb-1986 I-131 7.010.0 9.016.0 0.0-19.4 STW-452
-Water Mar.1986 Ra-226 3.810.1 4.110.6 3.0-5.2 Ra-228 11.020.5 12.421.8 9.2-15.5
-STW-4531 Water Mar 1986 Gr. alpha 6.710.6 15.025.0 6.3-23.7 Gr. beta 7.310.6 8.0*5.0 0.0-16.7
-STW-454 Water Apr 1986 I-131 7.010.0 9.016.0 0.0-19.4-STW-455 Water.
Apr 1986 456
'(Blind)
Sample A Gr. alpha 15.011.0 17.025.0 8.3-25.7 Ra-226 3.120.1 2.910.4 2.1-3.7!
Ra-228 1.510.2-2.010.3 1.5-2.5
. Uranium 4.710.6-5.026.0 0.0-15.4-Sample B Gr. beta 28,721.2 35.025.0 26.3-43.7 Sr-89 5.710.6 7.015.0 0.0-15.7 Sr-90 7.010.0-7.011.5 4.4-9.6 Co-60 10.721.5 10.015.0 1.3-18.7 Cs-134 4.021.7 5.025.0 0.0-13.7 Cs-137 5.310.6 5.015.0 0.0-13.7 a
AII-3
Table A-1.
(continued)
Concertration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 12cc 15, N=1 Limits
- r. alpha 13,710.6 15.015.0 6.3-23.7 STAF-457 Air Apr 1986 c
Filter Gr. beta 46.310.6 47.025.0 38.3-55.7 Sr-90 14.7 0.6 18.021.5 15.4-20.6 Cs-137 10.710.6 10.015.0 1,3-18.7 STU-458 Urine Apr 1986 Tritium 4313170 44231189 4096-4750 STW-459 Water May 1986 Sr-89 4.310.6 5.015.0 0.0-13.7 Sr-90 5.020.0 5.021.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.3 0.6 8.015.0 0.0-16.7 Gr. beta 11.311.2 15.025.0 6.3-23.7 STW-461 Water Jun 1986 Cr-51
<9.0 0.015.0 0.0-8.7 Co-60 66.021.0 66.015.0 57.3-74.7 Zn-65 87.321.5 86.025.0 77.3-94.7 Ru-106 39.712.5 50.015.0 41.3-58.7 Cs-134 49.312.5 49.015.0 40.3-57.7 Cs-137 10.3tl.5 10.025.0 1.3-18.7 STW-462 Water Jun 1986 Tritium 3427125 31251361 2499-3751 STM-464 Mil k Jun 1986 Sr-89
<1.0 0.015.0 0.0-8.7 Sr-90 15.320.6 16.011.5 13.4-18.6 1-131 48.322.3 41.016.0 30.6-51.4 Cs-137 43.711.5 31.015.0 22.3-39.7 K
15671114 1600180 1461-1739 STW-465 Water Jul 1986 Gr. alpha 4.7 10.6 6.0 5.0 0.0-14.7 Gr. ceta 18.721.2 18.0i5.0 9.3-26.7 STW-467 Water Au9 1986 1-131 30.310.6 45.016.0 34.4-55.4 STW-468 Water Au9 1986 Pu-239 11.310.6 10.111.0 8.3-11.9 STW-469 Water Aug 1986 Uranium 4.020.0 4.016.0 0.0-14.4 STAF-470 Air Sep 1986 Gr. alpha 19.311.5 22.0i5.0 13.3-30.7 471 Filter Gr. beta 64.012.6 66.025.0 57.3-74.7 472 Sr-90 22.011.0 22.015.0 19.4-24.6 Cs-137 25.7 1.5 22.015.0 13.3-30.7 STW-473 Water Sep 1986 Ra-226 6.020.1 6.110.9 4.5-7.7 Ra-228 8.711.1 9.111.4 6.7-11.5 1
A11-4
Ta01e A-1.
(continued)
{
Concentration in pCi/Lb EPA Resultd l
Lab Sample Date TIML Result Control Code Type Collected Analysis 12cc Is, N=1 Limits STW-474 Water-Sep 1986 Gr. alpha 16.313.2 15.015.0 b.3-23.7 Gr. beta 9.011.0 8.015.0 0.0-16.7 i
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-657 87.315.9 85.025.0 76.3-93.7 Ru-106 74.717.4 74.015.0 65.3-82.7 Cs 134 25.710.6 28.015.0 19.3-36.7 Cs-137 46.311.5 44.015.0 35.3-52.7 STW-476 Water Oct 1986 H-3 5918160 59731597 4938-7008 SPW-477 Water Oct 1986 (Blind)
Sample A Gr. alpha 34.016.0 40.015.0 31.3-48.7 Ra-226 5.810.2 6.010.9 4.4-7.6 Ra 228 2.721.0 5.010.8 3.7-6.3 Uranium 11.010.0 10.016.0 0.0-20.4 Sample B Gr. beta 38.711.2 51.015.0 42.3-59.7 Sr-89 5.010.0 10.015.0 1.3-18.7 S r-90 3.010.0 4.011.5 1.4-6.6 Co-60 24.711.2 24.015.0 15.3-32.7 Cs-134 11.012.0 12.015.0 3.3-20.7 Cs-137 9.311.2 8.015.0 0.0-20.4 STH-479 Mil k Nov 1986 Sr 89 7.711.2 9.015.0 0.3-17.7 Sr-90 1.010.0 0.011.5 0.0-2.6 1-131 52.313.1 49.016.0 38.6-59.4 Cs-137 45.713.1 39.015.0 30.3-47.7 K
14891104 1565178 1430-1700 SRI-480 Urine Nov 1986 H-3 5540126 52571912 4345-6169 STW-481 Water Nov 1986 Gr. alpha 12.014.0 20.015.0 11.3-28.7 Gr. beta 20.013.5 20.015.0 11.3-28.7 STW-482 Water Dec 1986 Ra-226 6.710.2 6.811.0 5.0-8.6 Ra-228 5.210.2 11.111.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.715.0 25.015.0 16.3-33.7 Sr-90 21.012.0 25.021.5 22.4-27.6 A11-5
i Table A 1.
(continued)
Concentration in pC1/Lb EPA Resultd TIML Result Control Lab Sample Date Crde.
Type Collected Analysi s
?.2 cc is N=1 Limits STW-484 Water Jan 1987 Pu 239 17.0e?.,
16.721.7 13.8-19.6 STF-486 Food Jan 1987 Sr-90 36.024.0 49.0210.0 31.7-66.3 1-131 78.013.4 78.018.0 64.1 91.9 Cs 137 89.713.0 84.025.0 75.3 92.7 K
942156 980249 895-1065 STF-487 Food Jan 1987 Sr-90 2.010.0 (Blank) 1-131
<3 Cs-137
<2 K
9932102 STW-488 Water Feb 1987 Co-60 49.010.0 50.015.0 41.3 58.7 L
Zn-65 96.027.2 91.015.0 82.3-99.7
.Ru 106 92.0220.2 100.015.0 91.3-108.7 Cs 13A 53.023.4 59.025.0 50.3-67.7 Cs-137 89.314.6 87.025.0 78.3-95.7 2-
- ST W-489 -
Water Feb 1987 H-3 41301140 42091420 3479-4939 STW-490 Water Feb 1987 Uranium 8.321.2 8.026.0 0.0-18.4 STM-491 Mil k Feb 1987 1-131 10.0*0.0 9.010.9 7.4-10.6 STW-492_
Water:
Mar 1987 Gr. alpha 3.711.2 3.015.0 0.0-11.7 Gr. beta 11.321.2 13.015.0 4.3-21.7 STW 493 Water.
Mar 1987 Ra 226 7.020.1 7.311.1 5.4 9.2 Ra-228.
7.112.3 7.511.1 5.5-9.5 STW-494 Water Apr.1987 1-131 8.020.0 7.010.7 5.8-8.2 STAF-495 Air Apr 1987 Gr. alpha 15.020.0 14.025.0 5.3-22.7
-Filter Gr. beta 41.0t2.0 43.015.0 34.3-51.7 Sr 90 16.3tl.2 17.021.5 14.4-19.6
.Cs-137 7.010.0 8.015.0 0.0-16.7
-STW-496 Water
'Apr 1987 497' (Blind)
Sample A Gr. alpha 30.721.2 30.028.0-16.1-43.9 Ra-226 3.910.2 3.910'.6 2.9-4.9 Ra-228 4.920.9 4.020.6 3.0-5.0 Uranium 5.010.0 5.016.0 0.0-15.4 AII-6 2
l Table A 1.
(continued)
Concentration in pCi/Lb EPA Resultd Lab Sample Date TlHL Result Control Code Type Collecteo Analysis 12 c4 15, N=1 Limits STW-496 Water Apr 1987 497 (Blind)
Sample 8 Gr. beta 69.319.4 66.015.0 57.3-74.7 Sr-89 16.313.0 19.015.0 10.3 27.7 Sr-90 10.010.0 10.011.5 7.4-12.6 Co-60 8.313.0 8.015.0 0.0-16.7 Cs-134 19.012.0 20.015.0 11.3-28.7 Cs 137 14.711.2 15.015.0 6.3-23.7 ST U-498 Urine Apr 1987 H-3 60171494 56201795 4647-6593
.STW 499 Water
.May 1987 Sr-89 38.016.0 41.015.0 32.3-49.7 Sr-90 21.012.0 20.011.5 17.4 22.6 STW-500 Water May 1987 Gr. alpha 9.013.4 11.015.0 2.3-19.7 Gr. beta 10.311.2 7.015.0 0.0-15.7 STW-501 Water Jun 1987 Cr-51 40.018.0 41.015.0 32.3-49.7 Co-60 60.313.0 64.015.0 55.3-72.7 Zn-65 11.315.0 10.015.0 1.3-18.7 Ru-106 78.326.4 75.015.0 66.3-83.7 Cs-134 36.713.0 40.015.0 31.3-48.7 Cs-137 80.314.2 80.015.0 71.3-88.7 STW-502 Water Jun 1987 H-3 2906186 28951357 2277-3513 STW-503 Water Jun 1987
.Ra-226 6.910.1 7.311.1 5.4-9.2 i
Ra-228 13.311.0 15.212.3 11.2-19.2 STM-504 Mil k Jun 1987 S r-89 57.014.3 69.015.0 60.3-77.7 Sr-90 32.011.0 35.015.0 32.4-37.6 1-131 64.012.0 59.016.0 48.6-69.4 Cs-137 77.720.6 74.015.0 65.3-82.7 K
1363117 1525176 1393-1657 STW-505 Water Jul 1987 Gr. alpha 2.310.7 5.015.0 0.0-13.7.
Gr. beta 4.011.0 5.015.0 0.0-13.7 i
STF-506 Food-1.'.
1987 1-131 82.714.6 80.018.0 66.1-93.9.
Cs-137 53.713.0 50.015.0 41.3-58.7 K
1548257 1680184 1534-1826 STW-507 Water Aug 1987 1-131 45.714.2 48.016.0 37.6-58.4 AII-7
.. _. _ _.. _.. _.. _ _ _. _ _... ~ _.. _ _ _
)
Table A-1.
(continued) o Concentration in pCi/Lb i
EPA Resultd Lab Sample Date TIML Result Control Code Type Collected A.nelysis 22:C 1s, N=1 Limits STW-508 Water Aug 1987 Pu-239 5.820.2 5.310.5 4.4 6.2 l
STW-509 Water Aug 1967 Uranium 13.320.3 13.026.0 2.6-23.4 STAF-510 Air Ar 1987 Gr. alpha 9.720.4 10.025.0 1.3-18.7 Fil ter Gr. beta 28.320.6 30.015.0 21.3-38.7 Sr-90 10.C10.9 10.021.5 7.4-12.6 Cs-137-10.021.0 10.025.0 1,3-18.7 STW-511 Water Sep 1987 Ra 226 9.920.1 9.711.5 7.2-12.2 Ra-228 8.111.4 6.311.0 4.6-8.0 STW-512 Water Sep 1987 Gr. alpha 2.010.6 4.025.0 0.0-12.7 Gr. beta 11.321.3 12.025.0 3.3-20.7 STW-513 Water Sep 1987 H-3 44732100 44921449 3714 5270 STW-514 Water Oct 1987 (Blind)
Sample A Gr. alpha 29.322.6 28.0 7.0 15.9-40.1 Ra 226 4.920.1 4.820.7 3.6-6.1 Ra-228 4.221.0 3.610.5 2.7-4.5 Uranium 3.0t0.1 3.016.0 0.0-13.4 Sample B Sr-89 14.321.3 16.025.0 7.3-24.7 Sr-90 9.710.4 10.011.5 7.4-12.6 Co-60
.16.713.0 16.015.0 7.3-24.7 4
Cs-134 16.712.3 16.015.0 7.3-24.7 Cs-137 24.313.3-24.015.0 15.3-32.7 STW-516 Water.
Oct 1987 Cr-51 80.3117.5 70.015.0-61.3-78.7 Co-60 16.012.3 15.015.0 6.3-23.7 Sample A Zn 46.315.6 46.025.0 37.3-54.7 Ru-106 57.3115.4 61.015.0 52.3-69.7
.Cs-134 23.712.5 25.025.0 16.3-33.7 Cs-137 51.7t3.2 51.015.0 42.3-59.7 STU-517 Urine Nov 1987 H-3 72671100 74322743 6145-8719 STW-518.
Water Nov 1987 Gr. alpha 3.012.0 7.015.0 0.0-15.7 Gr. beta 15.712.3 19.015.0 10.3-27.7 STW-519 Water Dec 1987.
1-131 26.023.0 25.026.0 15.6-36.4 AII-8
. ~
l Table A-1.
(continued) m Concentration in pCi/Lb EPA Resultd
~~
Lab Sample Date TIML Result Control Code Type Collected Analysis 22cC
- 15. N=1 Limits STW-520 Water Dec 1987 Ra-226 5.120.8 4.810.7 3.6-6.0 Ra-228 3.420.1 5.310.8 3.9-6.7 STW-521 Water Jan 1988 Sr-89 27.315.0 30.025.0 21.3-38.7 Sr-90 15.311.2 15.021.5 12.4-17.6 STW-523 Water Jan 1988 Gr. alpha 2.321.2 4.015.0 0.0-12.7 Gr. beta 7.721.2 8.015.0 0.0-16.7 STF-524 Food Jan 1988 Sr-89 44.024.0 46.025.0 37.3-54.7 Sr-90 53.022.0 55.022.8 50.2-59.8 I-131 102.314.2 102.0110.2 84.3-119.7 l
Cs-137 95.716.4 91.015.0 82.3-99.7 K
1011:158 1130262 1124-1336 STW-525 Water Feb 1988 Co-60 69.312.3 69.025.0 60.3-77.7 2n-65 99.013.4 94.029.4 77.7-110.3 Ru-106 92.7214.4 105.0210.5 86.8-123.2 Cs-134 61.718.0 64.015.0 55.3-72.7 Cs-137 99.713.0 94.025.0 85.3-102.7 STW-526 Water Feb 1988 H-3 34531103 33272362 2700-3954 STW-527 Water Feb 1988 Uranium 3.020.0 3.026.0 0.0-13.4 STM-528 Mil k -
Feb 1988 I-131 4.721.2 4.020.4 3.3-4.7 STW-529 Water Mar 1988 Ra-226 7.120.6 7.611.1 5.6-9.6 Ra-228 nae 7.711.2 5.7-9.7 STW-530 Water Mar 1988 Gr. alpha 4.311.2 6.015.0 0.0-14.7 Gr. beta 13.3t1.3 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 48.020.0 50.015.0 41.3-58.7 Sr-90 16.721.2 17.0 1.5 14.4-19.6 Cs-137 18.711.3 16.015.0 7.3-24.7-
- STW-632 Water Apr 1988 I-131 9.012.0 7.5*0.8 6.2-8.8 m.
AII-9
?
l Table A-1.
(continued)
Concentration in PC1/Lb l
EPA Resultd L ab Sample Date TIML Result Cont rol i
Code Type Collected Analysis 22cc Is, Nel Limits STW-533 Water Apr 1988 J'
534 (Blind)
Sample A Gr. alpha NDf 46.0211.0 27.0-65.0 Ra-226 ND 6.421.0 4.7-8.1 Ra 228 ND 5.610.8 4.2-7.0 Uranium 6.020.0 6.026.0 0.0-16.4 Sample B Gr. beta ND 57.015.0 48.3-65.7 Sr-89 3.321.2 5.025.0 0.0-13.7 Sr-90 5.311.2 5.011.5 2.4-7.6 Co-60 63.321.3 50.025.0 41.3 50.7 Cs-134 7.721.2 7.025.0 0.0-15.7-Cs-137 8.311.2 7.015.0 0.0-15.7 STU-535 Urine Apr 1988 H-3 64832155 62022620 5128-7376 STW-536 Water Apr 1988 Sr-89 14.711.3 20.015.0 11.3-28.7 Sr-90 20.012.0 20.011.5 17.4-22.6 STW-538 Water' Jun 1988 Cr-51 331.7213.0 302.0130.0 250.0-354.0 Co-60 16.022.0.
15.015.0 6.3-23.7 Zn 65 107.7111.4 101.0110.0 83.7-118.3 Ru-106 191.3i11.0 195.0120.0 -160.4-229.6 Cs-134 18.314.6 20.015.0 11.3-28.7 Cs-137 26.311.2 25.015.0 16.3-33.7 STW-539 Water Jun 1988 H-3 5586192 55652557 4600-6530 STM-541 Mil k -
Jun 1988 Sr-89 33.7111.4 40.015.0 31.3-48.7 Sr-90 55.325.8 60.023.0 54.8-65.2 1-131 103.713.1-94.019.0 78.4-109.6 Cs-137 52.713.1 51.015.0 42.3-59.7 K-1587223-1600280
'1461-1739 STW-542' Water Jul_1988 Gr. alpha-8.714.2 15.0*5.0 6.3-23.7-
~Gr. beta 5.321.2-
-4.025.0 0.0-12.7
[
-STF-543 Food Jul'1988 Sr-89_
NDf 33.015.0 24.3-41.7:
Sr ND 34.012.0
'30.5-37'.5 I-131 115.025.3 107.0211.0 88.0-126.0 Cs-137 52.726.4 49.015.0 40.3-57.7 K
1190166 1240162 1133-1347 l
AII-10
. ~.
. -. ~.
Table A-1.
(continued) i Concentration in pCi A b I
EPA Resultd
~
Lab Sample Date TIML Result Control Code Type Collected Analysis 22cc 15, N=1 Limits l
3 STW 544 Water Aug 1988 1-131 80.020.0 76.028.0 62.1-89.9 STW-545 Water Aug 1988 Pu 239 11.020.2 10.221.0 8.5-11.9 STW 546 Water Aug 1988 Uranium 6.020.0 6.026.0 0.0-16.4
$TAF-547 Air Aug 1988 Gr. alpha 8.010.0 8.015.0 0.0-16.7 Filter Gr. beta 26.311.2 29.015.0 20.3-37.7 Sr-90 8.022.0 8.021.5 5.4 10.6 Cs-137 13.012.0 12.015.0 3.3-20.7 o
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 8.025.0 0.0-16.7 Gr. beta 11.321.2 10.015.0 1.3-18.7 j
STW-550 Water Oct 1988 Cr-51 252.0214.0 251.0225.0 207.7 294.3 Co-60 26.0t2.0 25.015.0 16.3-33.7 Zn 158.3110.2 151.0215.0 125.0-177.0 Ru-106 153.019.2 152.0115.0 126.0-178.0 Cs 134 28.715.0 25.015.0 16.3-33.7 Cs-137 16.311.2 15.015.0 6.3-23.7 STW-551 Water L 1988-H 23331127 23162350 1710-2927 l
STW-552 Water Oct 1988 553 (Blind) l Sample A Gr. alpha 38.318.0 1.0210.0
- 23.7-58.3 4
Ra-226 4.510.5 5.010.8
-3.6-6.4 Ra-228 4.420.6 5.210.8 3.6-6.4 L
Uranium 4.721.2 5.016.0 0.0-15.4 1
Sample B Gr. beta-51.3t3.0 54.015.0 45.3-62.7 Sr-89' 3.711.2 11.015.0 2.3-19.7 Sr-90 10.711.2 10.021.5
-7.4-12.6-Cs-134 15.312.3 15.015.0 6.3-23.7 Cs-137 16.711.2 15.025.0 6.3-23.7 AII-11
-..u-
--.-.---_-..:-__..-..~..-..-..,--.--
lable A-1.
(continued)
Concentration in pCi/Lb EPA Resultd Lab S ample Date TIML Result Control C ode Type Collected Analysis 22cC 15, N=1 Limits STM-554 Mil k Oct 1988 Sr-89 40.317.0 40.015.0 31.3-48.7 Sr-90 51.022.0 60.023.0 54.8-65.2 1-131 94.013.4 91.029.0 75.4-106.6 Cs-137 45.024.0 50.015.0 41.3-58.7 K
1500145 1600280 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 9.711.2 9.015.0 0.3-17.7 STW-557 Water Oec 1988 1-131 108.713.0 115.0112.0 94.2-135.8 STW-559 Water Jan 1989 Sr-89 40.028.7 40.025.0 31.3-48.7 Sr-90 24.323.1 25.011.5 24.4-27.6 STW-560 Water Jan 1989 Pu-239 5.811.1 4.210.4 3.5-4.9 STW-561 Water Jan 1989 Gr. alpha 7.311.2 8.015.0 0.0-16.7 Gr. beta 5.311.2 4.015.0 0.0-12.7 STW-562 Water Feb 1989 C r-51 245146 235124 193.4-276.6 Co-60 10.012.0 10.015.0 1.3-18.7 Zn-65 170110 159216 139.2-186.7 Ru-106 18117.6 178118 146.8-209.2 Cs-134 9.713.0 10.015.0 1.3-18.7 Cs-137 11.711.2 10.015.0 1.3-18.7 STW-563 Water Feb 1989 1-131 109.014.0 106.0111.0 86.9-125.1 STW-564 Water Feb 1989 H-3 2820i20 27541356 2137-3371 STW 565 Water Mar 1989 Ra-226 4.210.3 4.920.7 3.7-6.1 Ra 228 1.911.0 1.710.3 1.2-2.2 STW-566 Water Mar 1989 U
5.020.0 5.016.0 0.0-15.4 STW-567 Air Mar 1989 Gr. alpha 21.721.2 21.015.0 12.3-29.7 Filter Gr. bete 68.314.2 62.015.0 53.3-70.7 S r-90 20.012.0 20.011.5 17.4-22.6 Cs-137 21.311.2 20.015.0 11.3-28.7 AII-12
Table A-1, (continued)
Concentration in pCi/Lb EPA Resultd L ab Sample Date TIML Result Control Code Type Collected Analysis 12 cC 15 N=1 Limits STW-568 Water Apr 1989 569 (Blind)
Sample A Gr. alpha 22.712.3 29.017.0 16.9-41.2 Ra-226 3.620.6 3.510.5 2.6-4.4 Ra-228 2.621.0 3.610.5 2.7-4.5 V
3.020.0 3.016.0 0.0-13.4 Sample B Gr. beta 52.316.1 57.015.0 43.3-65.7 Sr-89 9.315.4 8.015.0 0.0-16.7 Sr-90 7.010.0 8.011.5 5.4-10.6 Cs-134 21.015.2 20.025.0 11.3-28.7 Cs-137 23.012.0 20.015.0 11.3-28.7 STW-570 Mil k Apr 1989 Sr-89 26.0110.0 39.015.0 30.3-47.7 S r-90 45.714.2 55.013.0 49.8-60.2 Cs-137 54.016.9 50.015.0 41.3-58.7 K-40 15211208 1600180 1461-1739 STW-5719 Water May 1989 Sr-89
<0.7 6.015.0 0.0-14.7
$r-90 5.021.0 6.011.5 3.4-8.6 STW-572 Water May 1989 Gr. alpha 24.012.0 30.028.0 16.1-43.9 Gr. beta 49.3115.6 50.015.0 41.3-58.7 STW-573 Water Jun 1989 Ba-133 50.711.2 49.015.0.
40.3-57.7 Co-60 31.312.3 31.015.0 22.3-39.7 Zn-65 167110 165117 135.6-194.4 Ru-106 12319.2 128113 105.5-150.5 Cs-134 40.311.2 3915 30.3-47.7 Cs-137 22.311.2 20 t5 11.3-28.7 STW-574 Water Jun 1989 H-3 15131136 4503t450 3724-5282 STW-575 Water Jul 1989 Ra-226 16.813.1 17.722.7 13.0-22.4 Ra-228 13.813.7 18.312.7 13.6-23.0 STW-576 Water Jul 1989 U
40.321.2 41.026.0 30.6-51.4 STW-577 Water Aug 1989 l-131 84.715.8 83.018.0 69.1-96.9 STAF-579 Air Aug 1989 Gr. alpha 6.020.0 6.015.0 0.0-14.7 Filter Cs-137 10.312.3 10.025.0 1.3-18.7 AII-13
Table A-1.
(continued)
Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 220C is. N=1 Limits STW-580 Water Sep 1989 Sr-89 14.721.2 14.025.0 5.3-22.7 Sr-90 9.721.2 10.011.5 7.4-12.6 STW 581 Water Sep 1989 Gr. alpha 5.010.0 4.025.0 0.0-12.7 Gr. Beta 8.712.3 6.025.0 0.0-14.7 STW-583 Water Oct 1989 Ba-133 60.3210.0 59.016.0 48.6-69.4 Co-60 29.014.0 30.025.0 21.1-38.7 Zn-65 132.326.0 129.0213.0 106.5-151.5 Ru-106 155.326.1 161.0216.0 133.3-188.7 Cs-134 30.716.1 29.025.0 20.3-37.7 Cs-137 66.324.6 59.015.0 50.3-67.7 STW-584 Water Oct 1989 H-3 34072150 34961364 2866-4126 STW-585 Water Oct 1989 586 (Blind)
Sample A Gr. Alpha 41.719.4 49.0212.0 28.2-69.8 Ra-226 7.920.4 8.421.3 6.2-10.6 Ra-228 4.420.8 4.120.6 3.1-5.1 0
12.010.0 12.026.0 1.6-22.4 Sample B Gr. Beta 31.722.3 32.015.0 23.3-40.7 Sr-89 13.324.2 15.025.0 6.3-23.7 Sr-90 7.022.0 7.023.0 4.4-9.6 Cs-134 5.020.0 5.025.0 0.0-13.7 Cs-137 7.020.0 5.025.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.910.4 8.711.3 6.4-11.0 Ra 228 8.921.2 9.321.2 6.9-11.7 STW-588 Water Nov 1989 U
15.010.09 15.016.0 4.6-25.4 STW-589 Water Jan 1990 Sr-89 22.725.0 25.015.0 16.3-33.7 Sr-90 17.321.2 20.021.5 17.4-22.6 STW-591 Water Jan 1990 Gr. Alpha 10.313.0 12.025.0 3.3-20.7 Gr. Beta 12.311.2 12.025.0 3.3-20.7 A11-14
Table A-1.
(continued)
Concentration in PCi/LD EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis 12cC
- 15. N=1 Limits STW-592 Water Jan 1990 Co-60 14.712.3 1515.0 6.3-23.7 Zn-65 135.016.9 139.0214.0 114.8-163.2 Ru-106 133.3113.4 139.0114.0 114.8-163.2 Cs-134 17.321.2 18.015.0 9.3-26.7 Cs-137 19.311.2 18.015.0 9.3-26.7 Ba-133 78.020.0 74.027.0 61.9-86.1 STW-593 Water Feb 1990 H-3 4827183 49761498 4113-5839 STW-594 Water Mar 1990 Ra-226 5.010.2 4.910.7 4.1-5.7 Ra-228 13.510.7 12.711.9 9.4-16.0 STW-595 Water Har 1990 0
4.010.0 4.016.0 0.0-14.4 STW-596 Air Mar 1990 Gr. Alpha 7.311.2 5.015.0 0.0-13.7 Filter Gr. Beta 34.010.0 31.015.0 22.3-39.7 Sr-90 10.010.0 10.011.5 7.4-12.6 Cs-137 9.311.2 10.015.0 1.3-18.7 STW-597 Water Apr 1990 598 (8lind)
Sample A Gr. Alpha 81.023.5 90.0123.0 50.1-129.9 Ra-226 4.910.4 5.010.8 3.6-6.4 Ra-228 10.610.3 10.211.5 7.6-12.8 U
18.713.0 20.016.0 9.6-30.4 Sample B Gr. Beta 51.0110.1 52.015.0 43.3-60.7 Sr-89 9.311.2 10.015.0 1.3-18.7 Sr-90 10.313.1 10.011.5 8.3-11.7 Cs-134 16.010.0 15.015.0 6.3-23.7 Cs-137 19.012.0 15.025.0 6.3-23.7 STM-599 Milk Apr 1990 Sr-89 21.713.1 23.015.0 14.3-31.7 Sr-90 21.027.0 23.015.0 14.3-31.7 l-131 98.711.2 99.0210.0 81.7-116.3 Cs 137 26.016.0 24.015.0 15.3-32.7 K
1300.0169.2 1550.0278.0 1414.7-1685.3 STW-600 Water May 1990 Sr-89 6.012.0 7.015.0 0.0-15.7 Sr-90 6.711.2 7.015.0 0.0-15.7 STW-601 Water May 1990 Gr. Alpha 11.022.0 22.016.0 11.6-32.4 Gr. Beta 12.311.2 15.015.0 6.3-23.7 AII-15
Table A-1.
(continued)
Concentration in PCi/Lb EPA Resultd L ab Sample Date TIML Result Control Code Type Collected Analysis 12 cC 1s, N=1 Limits STW-602 Water Jun 1990 Co-60 25.322.3 24.025.0 15.3-32.7 Zn-65 155.0110.6 148.0115.0 130.6-165.4 Ru-106 202.7217.2 210.0221.0 173.6-246.4 Cs-134 23.721.2 24.025.0 18.2-29.8 Cs-137 27.713.1 25.025.0 16.3-33.7 Ba-133 100.718.1 99.G.10.0 81.7-116.3 STW-603 Water Jun 1990 H-3 29272306 29331358 2312-3554 STW-604 Water Jul 1990 Ra-226 11.820.9 12.111.0 9.0-15.2 Ra-228 4.111.4 5.111.3 2.8-7.4 STW-605 Water Jul 1990 V
20.311.7 20.813.0 15.6-26.0 STW-606 Water Aug 1990 1-131 43.021.2 39.026.0 28.6-49.4 STW-607 Water Aug 1990 Pu-239 10.011.7 9.110.9 7.5 10.7 STW-608 Air Aug 1990 Gr. alpha 14.010.0 10.015.0 1.3-18.7 Filter Gr. beta 65.311.2 62.015.0 53.3-70.7 Sr-90 19.026.9 20.015.0 11.3-28.7 Cs-137 19.012.0 20.015.0 11.3 28.7 STW-609 Water Sep 1990
$r-89 9.012.0 10.015.0 1.3-18.7 Sr 90 9.012.0 9.015.0 0.3-17.7 STM-610 Water Sep 1990 Gr. alpha 8.3tl.2 10.015.0 1.3-18.7 Gr. beta 10.311.2 10.015.0 1.3-18.7 STH-611 Mil k Sep 1990 Sr-89 11.713.1 16.015.0 7.3-24.7 Sr-90 15.020.0 20.015.0 11.3-28.7 l-131 63.016.0 58.016.0 47.6-68.4 Cs-137 20.012.0 20.015.0 11.3-28.7 K
1673.3170.2 1700.0285.0 1552.5-1847.5 STW-612 Water Oct 1990 Co-60 20.313.1 20.015.0 11.3-28.7 Zn-65 115.3112.2 115.0112.0 94.2 135.8 Ru 106 152.028.0 151.0215.0 125.0-177.0 Cs-134 11.010.0 12.015.0 3.3-20.7 Cs-137 14.0t2.0 12.025.0 3.3-20.7 Ba-133 116.729.9 110.0211.0 90.9-129.1 STW-613 Water Oct 1990 H-3 71671330 72031720 5954-8452 AII-16
Table A-1.
(continued) i
~
Concentration in pC1/Lb EPA Result 0 Lab Sample Date TIML Result Control Code Type Collected Analysis 12 -C 15, Nel Limits 6
STW-614 Water Oct 1990 615 Sample A Gr. alpha 68.717.2 62.0216.0 34.2-89.8 Ra-226 12.910.3 13.612.0 10.1-17.1 Ra-228 4.210.6 5.011.3 2.7-7.3 U
10.420.6 10.213.0 5.0-15.4 Sample B Gr. beta 55.018.7 53.015.0 44.3-61.7 S r-89 15.712.9 20.015.0 11.3-28.7 Sr-90 12.012.0 15.015.0 6.3-23.7 Cs-134 9.011.7 7.015.0 0.0-15.7 Cs-137 7.711.2 5.015.0 0.0-13.7 STW-616 Water Nov 1990 Ra-226 6.811.0 7.411.1 5.5-9.3 Ra-228 5.311.7 7.711.9 4.4-11.0 STW-6179 Water Nov 1990 0
35.010.4 35.513.6 29.3-41.7 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample croucheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. Environmental Protect. ion Agency (EPA), Las Vegas,
- Nevada, b All results are in the pCi/1, except for elemental potassium (K) data in milk, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in mg/kg.
c Unless otherwise indicated, the TIML results are given as the mean i 2 standard deviations for three determinations, d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits as defined by EPA.
e NA = Not analyzed.
f ND = 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 (all data on file).
AII-17
I Table A-2.
Crosscheck program results, thermoluminescent cosimeters (TL0s).
nR Teledyne Average 22 d Lab Result Known (All Code TLD Type Measurement 12co valueC Participants) 2nd International Intercomparisonb CaF :Mn Field 17.021.9 17.1 16.427.7 115-2 2
Bulb Lab 20.824 1 21.3 18.827.6 3rd International Intercomparisone CaF :Mn Field 30.713.2 34.914.8 31.513.0 115-3 2
Bulb Lab 89.616.4 91.7114.6 86.2224.0 4th International Intercomparisonf CaF :Mn Field 14.111.1 14.111.4 16.019.0 115-4 2
Bulb Lab (Low) 9.321.3 12.212.4 12.027.4 Lab (High) 40.421.4 45.819.2 43.9113.2 Stb International Intercomparison9 CaF :Mn Field 31.411.8 30.026.0 30.2114.6 115-5A 2
Bulb Lab at beginning 77.415.8 75.217.6 75.8240.4 Lab at the end 96.615.8 88.418.8 90.7131.2 115-5B Lif-100 Field 30.314.8 30.016.0 30.2114.6 Chips Lab at beginning 81.117.4 75.217.6 75.8140.4 Lab at the end 85.4211.7 88.418.8 90.7131.2
_7th International Intercomparisonh 115-7A LiF-100 Field 75.412.6 75.816.0 75.1129.8 Chips Lab (Co-60) 80.013.5 79.914.0 77.9127.6 Lab (Cs-137) 66.612.5 75.013.8 73.0122.2 AII-18
Table A.2.
(continued) mR Teledyne Avera9e 22cd Lab Result Known (All Code TLD Type Measurement 22c4 ValueC Participants)
CaF :Mn Field 71.5t2.6 75.826.0 75.1529.8 115-78 2
Bulbs Lab (Co-60) 84.816.4 79.914.0 77.9177.6 Lab (Cs 137) 78.821.6 75.013.8 73.022?.2 115-7C CaSO :Dy Field 76.812.7 75.816.0 75.1125.8 4
Cards Lab (Co-60) 82.513.7 79.924.0 77.9127.6 Lab (Cs-137) 79.023.2 75.013.8 73.0172.2 8th International Intercomparison,i 115-8A LiF-100 Field Site 1 29.511.4 29.711.5 28,9112.4 Chips Field Site 2 11.310.8 10.420.5 10.119.06 Lab (Cs-137) 13.710.9 17.220.9 16.216.8 115-8B CaF2:Mn Field Site 1 32.311.2 29.711.5 28,9212.4 Bulbs Field Site 2 9.021.0 10.420.5 10.129.0 Lab (Cs-137) 15.810.9 17.220.9 16.216.8 115-8C CaSO4:Dy Field Site 1 32.310.7 29.721.5 28.9112.4 Cards Field Site 2 10.620.6 10.410.5 10.119.0 Lab (Cs-137) 18.110.8 17.210.9 16.216.8 Teledyne Testingd 89-1 LiF-100 Lab 21.020.4 22.4 Chips 89-2 Teledyne Lab 20.911.0 20.5 CaSO :Dy 4
Cards A11-19
l Table A-2.
(continued) r,R Teledyne Average 22:d Lab Result Known (All Code TLD Type Measurement 12ca ValueC Participants)
.Teledyne Testingj 90-1k Teledyne Lab 20.621.4 19.6 CaSO4:Dy Cards 90-1 I Teledyne Lab 100.814.3 100.0 CaSO4 :Dy Cards a Lab result given is the mean 22 standard deviations of three determinations.
b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas, c Value determined by spon:ior of the intercomparison using continuously operated pressurized ion chamber, d Mean 12 standard deviations of results obtained by all laboratories parti-cipating in the program.
O Third International Intercomparison of Environmental Dosimeters conducted in sumer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas, f Fourth International Intercomparison of Environmental Dosimeters conducted in sumer 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, !daho and sponsored by the School of Public Health of the University of Texas. Houston, Texas and Environmental Measure-ments Laboratory, New York, New York, U.S. Department of Energy.
h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 et 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.
i 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.
J Chips were submitted in September 1989 and cards were submitted in November 1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation.
k Cards were irradiated by Teledyne isotopes, Inc., Westwood, NJ on June 19, 1990.
I Cards were irradiated by Dosimetry Associates, Inc., Northville, M1 on October 30, 1990.
AII-20
Table A 3.
In-house spiked samples.
Concentration (pC1/L)
Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 15, n=3a QC-HI-6 Hil k Feb 1986 Sr-89 6.021.9 6.413.0 8.7 Sr-90 14.221.7 12.922.0 5.2 1-131 34.213.8 35.213.5 10.4 Cs-134 32.011.8 27.315.0 8.7 Cs-137 35.812.1 35.025.0 8.7 QC-W 14 Water Har 1986
$r-89 1.610.4 1.621.0 7.1 Sr-90 2.410.2 2.412.0 4.2 QC-W-15 Water Apr 1986 1-131 44.922.4 41.527.0 10.6 Co-60 10.621.7 12.115.0 7.lb Cs-134 30.222.4 25.828.0 7.lb Cs-137 21.911.9 19.915.0 7.lb QC-HI 7 Mil k Apr 1986 1-131 39.713.3 41.517.0 10.4 Cs-134 28.712.8 25.818.0 8.7 Cs-137 21.212.8 19.925.0 8.7 SPW-1 Water May 1986 Gr. alpha 15.811.8 18.025.0 Sc QC-W-16 Water Jun 1986 Gr. alpha 16.220.7 16.922.5 8.7 Gr. beta 38.413.5 30.225.0 8.7 QC-MI-9 Milk Jun 1986 Sr-89
<1.0 0.0 7.lb Sr-90 12.621.8 13.323.0 4.2b 1-131 38.917.0 34.817.0 10.4 Cs-134 33.013.4 36.115.0 8.7 Cs-137 38.512.8 39.025.0 8.7 SPW-2 Water Jun 1986 Gr. alpha 16,811.8 18.015.0 SC SPW-3 Water Jun 1986 Gr. alpha 17.710.8 18.015.0 Sc QC-W-18 Watt.r Sep 1986 Cs-134 34.715.6 31.315.0 8.7 Cs-137 51.lt7.0 43.318.0 8.7 QC-W-19 Water Sep 1986 Sr-89 13.614.1 15.623.5 7.lb Sr-90 6.411.6 6.212.0 4.2b An-21
l Table A-3.
In house spiked samples (continued)
Concentration (pCi/L)
Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-21 Water Oct 1986 Co-60 19.212.2 18.513.0 8.7 Cs 134 31.715.2 25.618.0 8.7 Cs 137 23.811.0 21.615.0 8.7 QC-M1-11 Mil k Oct 1986
$r-89 12.321.8 14.313.0 8.7 QC W-20 Water Nov 1986 H3 38551180 39602350 520b QC-W-22 Water Dec 1986 Gr. alpha 9.821.4 11.224.0 8.7 Gr. beta 21.712.0 23.825.0 8.7 QC-W-23 Water Jan 1987 1-131 29.822.5 27.913.0 10.4 QC-MI-12 Mil k Jan 1987 1-131 36.521.3 32.625.0 10.4 Cs-137 32.624.2 27.418.0 8.7 QC-MI-13 Milk Jan 1987 Sr-89 10.422.1 12.214.0 8.7 Sr-90 14.611.6 12.623.0 5.2 1-131 49.521.2 54.928.0 10.4 Cs-134
<1.6 0.0 8.7 Cs-137 33.320.6 27.428.0 8.7 QC-W-24 Water Har 1987 Sr-89 24.7t3.6 25.925.0 8.7 Sr-90 23.913.8 22.828.0 5.2 QC-W-25 Water Apr 1987 1 131 28.021.9 29.325.0 10.6 QC-M1-14 Milk Apr 1987 1-131 25.022.2 23.925.0 10.4 Cs-134
<2.1 0.0 8.7 Cs-137 34.212.0 27.227.0 8.7 QC-W-26 Water Jun 19G7 H-3 34221100 33621300 520 Co-60 24.811.4 26.Si?.0 8.7 Cs-134
<2.0 0.0 8.7 Cs-137 21.210.5 21.627.0 8.7 QC-W-27 Water Jun 1987 Gr. alpha 8.Sil.9 10.124.0 8.7 Gr. beta 22.611.9 21.225.0 8.7 QC-W-28 Water Jun 1987 Gr. alpha 8.711.3 10.114.0 8.7 Gr. beta 12.215.2 9.413.0 8.7 AII-22
\\
Table A 3.
In-house spiked samples (continued)
Concentration (pCi/L)
Lab Simple Date TIML Expected Code 1pe Collected Analysis Result Known Precision n*3 Activity 1s, n=3a QC-W-29 Water Jun 1987 Gr. alpha 16.411.3 18.915.0 8.7 Gr. beta 15.914.0 11.814.0 8.7 QC-MI-15 Mil k Jul 1987 Sr 90 19.411.6 18.813.5 5.2 1-131 43.510.7 45.317.0 10.4 Cs-134 17.912.2 16.015.3 8.7 Cs-137 25.421.8 22.715.0 8.7 QC-W-30 Water Sep 1987 Sr-89 17.513.0 14.315.0 8.7 Sr-90 18.412.2 17.512.2 5.2 QC-W-31 Water Oct 1987 H3 20531939 20591306 520 QC-W-32 Water Dec 1987 Gr. alpha 8.611.0 10.115.0 8.7 Gr. beta 15.210.1 13.113.0 8.7 QC-W-33 Water Dec 1987 Gr. alphe 7.711.4 10.115.0 8.7 Gr. beta 10.911.0 7.913.0 8.7 QC-W-34 Water Dec 1987 Gr. alpha 4.010.9 5.113.0 8.7 Gr. beta 9.410.9 7.913.0 8.7 QC-MI-16 Milk Feb 1988 S r-89 31.814.7 31.726.0 8.7 Sr-90 25.512.7 27.813.5 5.2 1-131 26.410.5 23.215.0 10.4 Cs-134 23.812.3 24.2t6.0 8.7 Cs-137 26.520.8 25.116.0 8.7 QC-MI-17 Mil k Feb 1988 1-131 10.6tl.2 14.321.6 10.4 QC-W-35 Water Feb 1988 1-131 9.711.1 11.621.1 10.4 QC-W-36 Water Feb 1988 1-131 10.521.3 11.6tl.0 10.4 QC-W-37 Water Mar 1988 Sr-89 17.122.0 19.818.0 8.7 Sr-90 18.710.9 17.315.0 5.2 QC-HI-18 Milk Har 1988 I-131 33.212.3 26.725.0 10.4 Cs-134
?1.312.1 30.215.0 8.7 Cs-137 29.911.4 26.215.0 8.7 AII-23
Table A-3.
In house spiked samples (continued)
Concentration (pCi/L)
Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-38 Water Apr 1988 1-131 17.111.1 14.ti5.0 10.4 QC-W-39 Water Apr 1988 H-3 4439231 41762500 724 QC-W-40 Water Apr 1988 Co-60 23.710.5 26.114.0 8.7 Cs-134 25.412.6 29.224.5 8.7 Cs-137 26.6x2.3 26.214.0 8.7 QC-W-41 Water Jun 1988 Gr. alpha 12.310.4 13.125.0 8.7 Gr. beta 22.611.0 20.115.0 8.7 QC-M1-19 Mil k Jul 1988 Sr-89 15.111.6 16.415.0 8.7 Sr-90 18.010.6 18.315.0 5.2 1-131 88.424.9 86.618.0 10.4 Cs-137 22.710.8 20.816.0 8.7 QC-W-42 Water Sep 1988 Sr-89 48.513.3 50.818.0 8.7 Sr-90 10.911.0 11.423.5 5.2 QC-W-43 Water Oct 1988 Co-60 20.923.2 21.413.5 8.7 Cs-134 38.711.6 38.026.0 8.7 Cs-137 19.012.4 21.023.5 8.7 QC-9-44 Water Oct 1988 1-131 22.210.6 23.313.5 10.4 Qt &45 Water Oct 1988 H-3 4109143 41531500 724 QC-MI-20 Mil k Oct 1988 I-131 59.820.9 60.629.0 10.4 Cs-134 49.621.8 48.627.5 8.7 Cs-137 25.824.6 24.714.0 8.7 QC-h-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 Mil k Jan 1989 Sr-89 25.5110.3 34.0110.0 8.7 Sr-90 28.313.2 27.113.0 5.2 1-131 540213 550120 10.4 Cs-134 24.Si2.6 22.625.5 8.7 Cs-137 24.020.6 20.515.0 8.7 AII-24
I j
Table A-3.
In-house spiked samples (continued)
Concentration (pCi/L)
Lab Sample Date TIML Expect ed Code Type Coll ected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-47 Water Mar 1989 Sr-89 15.2 3.8 16.115.0 8.7 Sr-90 16.411.7 16.923.0 5.2 QC-MI-22 Milk Apr 1989 l-131 36.311.1 37.215.0 10.4 Cs-134 20.822.8 20.718.0 8.7 Cs-137 22.2i2.4 20.428.0 8.7 QC-k-48 Water Apr 1989 Co-60 23.512.0 25.118.0 8.7 Cs-134 24.221.1 25.928.0 8.7 Cs-137 23.621.2 23.018.0 8.7 QC-W-49 Water Apr 1989 l-131 37.213.7 37.215.0 10.4 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 25.518.0 8.7 QC-MI-23 Mil k Jul 1989 Sr-89 19.426.5 22.0110.0 8.7 Sr-90 27.6t3.5 28,623.0 5.2 1 131 46.813.2 43.415.0 10.4 Cs-134 27.411.8 28.316.0 8.7 Cs-137 24.111.8 20.816.0 8.7 QC-MI-24 Mil k Aug 1989 Sr-89 25.412.7 27.2110.0 8.7 Sr-90 46.021.1 47.819.6 8.3 QC-W-52 Water Sep 1989 l-131 9.610.3 9.711.9 10.4 QC-W-53 Water Sep 1989 l-131 19.010.2 20.914.2 10.4 QC-W-54 Water Sep 1989 Sr-89 25.824.6 24.714.0 8.7 Sr-90 26.515.3 29.715.0 5.2 QC-M1 Mil k Oct 1989 I-131 70.013.3 73.5120.0 10.4 Cs-134 22.112.6 22.618.0 8.7 Cs-137 29.4il.5 27.518.0 8.7 QC-W-55 Water Oct 1989 l-131 33.311.3 35.3110.0 10.4 A11-25
Table A-3.
In-house spiked samples (continued)
Concent ration (pCi/Q Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=3a QC-W-56 Water Oct 1989 Co-60 15.220.9 17.425.0 8.7 Cs-134 22.114.4 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 10.921.4d 11.lil,0d 8.7 Sr-90 10.4tl.0d 10.311.0d 5.2 QC-W-59 Water Nov 1989 Sr-89 101.026.0d 104. li10,5d 17.5 S r-90 98.013.0d 95.0110.0d 17.0 QC-W-60 Water Dec 1989 Gr. alpha 10.811.1 10.624.0 8.7 Gr. beta 11.610.5 11.414.0 8.7 QC-MI-26 Milk Jan 1990 Cs-134 19.311.0 20.828.0 8.7 Cs-137 25.221.2 22,818.0 8,7
. QC-MI-27 Milk Feb 1990 Sr-90 18.011.6 18.815.0 5.2 QC-MI-28 Mil k Mar 1990 1-131 63.822.2 62.616.0 6.3 QC-MI-61 Water Apr 1990 Sr-89 17,915.5 23.118.7 8.7 Sr-90 19.412.5 23.515.2 5.2 QC-MI-29 Mil k Apr 1990 1-131 90.719.2 82.518.5 10.4 Cs-134 18.321.0 19.715.0 8.7 Cs-137 20,311.0 18.215.0 8.7 QC-W-62 Water Apr 1990 Co-60 8.710.4 9.415.0 8.7 Cs-134 20.010.2 19.715.0 8.7 Cs-137 28.711.4 22.715.0 8.7 QC-W-63 Water Apr 1990 1-131 63.528.0 66.016.7 6.6 QC-W-64 Water Apr 1990 H-3 19411130 1826.02350.0 724 QC-W-65 Water Jun 1990 Ra-226 6.410.2 6.921.0 1.0 QC-W-66 Water Jun 1990 U
6.210.2 6.016.0 6.0 AII-26
l Table A-3.
In-house spiked samples (continued)
Concentration (pCi/L)
Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=3 Activity 1s, n=38 QC-M1-30 Mil k Jul 1990 Sr 89 12.820.4 18.4110.0 8.7 Sr-90 18.221.4 18.716.0 5.2 Cs-134 46.011.3 49.015.0 8.7 Cs-137 27.611.3 25.325.0 8.7 QC-W-68 Water Jun 1990 Gr. alpha 9.820.3 10.626.0 8.7 Gr. beta 11.410.6 11.317.0 8.7 QC-M1-31 Mil k Aug 1990 1-131 68.821.6 61.4t12.3 10.4 QC-W-69 Water Sep 1990 Sr-89 17.711.6 19.2110.0 8.7 Sr-90 13.921.6 17.4110.0 5.2 QC-MI-32 Milk Oct 1990 1-131 34.810.2 32.426.5 8.7 Cs-134 25.811.2 27.3110.0 8.7 Cs-137 25.322.0 22.4110.0 8.7 QC-W-70 Water Oct 1990 H-3 2355159 22762455 605 QC-W-71 Water Oct 1990 1-131 55.910.9 51.8110.4 10.4 QC-M-73 Water Oct 1990 Co-60 18.312.7 16.815.0 8.7 Cs-134 28.322.3 27.015.0 8.7 Cs-137 22.711.3 22.415.0 8.7 QC-W-74 Water Dec 1990 Gr. alpha 21.411.0 26.116.5 11.3 Gr. beta 25.921.0 22.315.6 9.7 a n = 3 unless noted otherwise.
b n = 2 unless noted otherwise.
c n = 1 unless noted otherwise.
d Concentration in pCi/ml.
A11-27
i Table A-4.
In-house " blank" samples.
Concentration (pCi/L)
Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 c)
(4.66o)
BL-1 D.I. Water Nov 1985 Gross alpha
<0.1
<1 Gross beta
<0.4
<4 BL-2 0.1. Water Nov 1985 Cs-137 (gamma)
<1.9 (10 BL-3 0.1. 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 0.1. Water Apr 1985 Gross alpha
<0.6
<1 Gross beta
<2.2
<4 Sr-89
<0.2
<5 Sr-90
<0.4
<1 1-131
<0.2
<1 Cs-137 (gamma)
<7.4
<10 BL-6 0.1. Water Apr 1986 Gross alpha
<0.4
<1 BL-7 0.1 Water Apr 1986 Gross alpha
<0.4
<1 BL-8 D.I. Water Jun 1986 Gross alpha
<0.4
<1 BL-9 0.1. Water Jun 1986 Gross alpha
<0.3
<1 SPW-3185 0.1. Water Jan 1987 Ra-226
<0.1
<1 Ra-228
<0.9
<1 SPS-3292 Mil k Jan 1987 1-131
<0.1
<1 Cs-134
<6.2
<10 C s-137
<6.4
<10 SPW-3554 0.1. Water Feb 1987 H-3
<180
<300 Gross beta
<2.6
<4 SPS-3555 Mil k Feb 1987 Sr-89
<0.6
<5 Sr-90 1.910.4a
<1 SPS-3731 Milk Mar 1987 Cs-134
<2.2
<10 Cs-137
<2.5
<10 AII-28
Table A-4.
In-house " blank" samples (continued)
Concentration (pCi/L)
A::cotance Lab Sample Date Results Criteria Code Type N11 ected Analysis (4.66 c)
(4.66c)
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 Np-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 Mil k 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 Mil k May 1987 Sr-89
<0,5
<5 Sr-90 2.410.6a
<1 SPS-4390 Mil k Jun 1987 Cs-134
<4.7
<10 Cs-137
<5.2
<10 SPS-4391.
0.1. 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 Ra-226 (0.1
<1 Ra-228
<0.9
<1 SPW-4627 0.1. Water Aug 1987 Gross alpha
<0.6
<1 Gross beta
<1.4
<4 Tritium (150
<300 SPS-4628 Mil k Aug 1987 Sr-89 (0.6
<5 Sr-90 2.410.6a
<1 AII-29
Table A-4, in-house " blank" samples (continued)
Concentration (pCi/L) i Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66o)
(4.66 o)
SPS-4847 Mil k Sep 1987 Cs-134
<4.4 (10 Cs-137
<5.3
<10 SPS-4848 0.1. Water Sep 1987 1-131
<0. 2
<1 SPW-4849 0.1. Water Sep 1987 Co-60
<4.1
<10 Cs-134
<4.8 (10 C s-137 (4.0
<10 Sr-89
<0.7 (5
<0.7
<1 SPW-4850 D.I. Water Sep 1987 Th-228
<0.04
<1 Th-232 (0.0
<1 U-234
<0.03
<1 U-235
<0.03
<1 U-238
<0.02
<1 Am-241
<0.06
<1 Cm-242
<0.04
<1 Ra-226
<0.1
<1 Ra-228
<1.0
<2 SPW-4859 0.1. Water Oct 1987 Fe-55
<0.5
<1 SPS-5348 Mil k Dec 1987 Cs-134
<2. 3
<10 Cs-137
<2.5
<10 SPW-5384 0.1. Water Dec 1987 Co-60
<2.8
<10 Cs-134
<2.6
<10 Cs-137
<2.8
<10 1-131
<0.2
<1 Ra-226
<0.1
<1 Ra-228
<1.2
<2 Sr-89
<0.5
<1 S r-90
<0.4
<1 SPW-5385 0.1. Water Nov 1987 Gross alpha
<0.4
<1 Gross beta
<2.2
<4 Fe-55
<0.3
<1 SPS-5386 Milk Jan 1988 1-131
<0.1
<1 SPW-5448
" Dead" Water Jan 1988 H-3
<177
<300 AII-30
Table A-4 In-house " blank" samples (continued)
Concentration (pCi/L)
Ac cept ance Lab Sample Date Results Criteria Code Type Collected Analysi s (4.66 o)
(4.66 c)
SPS-5615 Mil k Mar 1988 Cs-134
<2.4
<10 Cs-137
<2.5
<10 1-131
<0.3
<1 Sr-89
<0.4
<5 Sr-90 2.410.Sa
<1 SPS-5650 0.1. Water Mar 1988 Th-228
<0.3
<1 Th-230
<0.04
<1 Th-232
<0.05
<1 U-234
<0.03
<1 0-235
<0.03 (1
<0.03
<1 Am-241
<0.06
<1 Cm-242
<0.01 (1
<0.08
<1 Pu-240
<0.02
<1 SPS-6090 Mil k Jul 1988 Sr-89
<0.5
<1 S r-90 1.820.5
<1 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 Mil k Oct 1988 I-131
<0.2
<1 Cs-134
<6.1
<10 Cs-137 (5.9
<10 SPW-6478 Water Oct 1988 1-131
<0. 2
<1 SPW-6479 Water Oct 1988 Co-60
<5.7
<10 C s-134
<3.7
<10 Cs-137
<4. 3
<10 SPW-6480 Water Oct 1988 H-3
<170
<300 SPW-6625 Water Dec 1988 Gross alpha
<0.7
<1 Gross beta
<1.9
<4 AII-31
Table A-1 In-house " blank" samples (continued)
Concentration (pC1/L)
Acceptance Lab Sample Date Results Criteria Code Type Collected Analysi s (4.66 c)
(4.66 c)
SPS-6723 Mil k Jan 1989 Sr-89
<0.6
<5 Sr-90 1.9t0.Sa
<1 1-131
<0.2
<1 Cs-134
<4.3
<10 C s-137
<4.4
<10 SPW-6877 Water Mar 1989 Sr-89
<0.4
<5 Sr-90
<0.6
<1 SPS-6963 Milk Apr 1989 l-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 Mil k Jun 1989 Sr-89
<0.6
<5 Sr-90 2.110,5a
<1 1-131
<0. 3
<1 Cs -134 (6.4
<10 Cs-137
<7.2
<10 SPW 7558 Water Jun 1989 Gross alpha
<0.2
<1 Gross beta
<1.0
<4 SPS-7322 Mil k Aug 1989 Sr-89
<1.4
<5 Sr-90 4.821.0a
<1 1-131
<0.2
<1 Cs-134
<6.9
<10 Cs-137 (8.2 (10 SPW-7559 Water Sep 1989 Sr-89
<2.0
<5 Sr-90
<0.7
<1 SPW-7560 Water Oct 1989 l-131
<0.1
<1 SPW-7562 Water Oct 1989 H-3
<140
<300 AII-32
Table A-4.
In-house " blank" samples (continued)
Concentration (pCi/L) j Acceptance Lab Sampl e Date Results Criteri a Code Type Collected Analysi s (4.66 c)
(4.66 c)
SPS-7605 Mil k Nov 1989 l-131
<0.2
<1 Cs-134
<8.6
<10 Cs-137
<10
<10 SPW-7971 Water Dec 1989 Gross alpha
<0.4
<1 Gross beta
<0.8
<4 SPW-8039 Water Jan 1990 Ra-226
<0. 2
<1 SPS-8040 Mil k Jan 1990 Sr-89
<0.8
<5 Sr-90
<1.0
<1 SPS-8208 Mil k Jan 1990 Sr-89
<0.8
<5 Sr-90 1.620.5a
<1 Cs-134
<3.6
- 10 Cs-137
<4.7
<10 SPS-8312 Mil k Feb 1990 Sr-89
<0.3
<5 Sr-90 1.2 0.3a
<1 SPW-8312A Water Feb 1990 Sr-89
<0.5
<5 Sr-90
<0.7
<1 SPS-8314 Mil k Mar 1990 1-131
<0. 3
<1 SPS-8510 Mil k May 1990 1-131
<0.2
<1 Cs-134
<4.6
<10 Cs-137
<4.8
<10 SPW-8511A Water May 1990 H-3
<200
<300 SPS-8600 Mil k Jul 1990 Sr-89
<0.8
<5 Sr-90 1.710.6a
<1 1-131
<0.3
<1 Cs-134
<5.0
<10 Cs-137
<7.0
<10 SPM-8877 Mil k Aug 1990 1-131
<0. 2
<1 SPW-8925 Wate.-
Aug 1990 H-3'
<200
<300 An -33
Liable A-4. _ in-house " blank" samples (continued):
Concentration (DCi/L1 Acceptance Lab Sample Date Results Criteria ype-Collected Analysis (4.66c)
(4.o6o)
T Code SPW-8926 Water Aug 1990 Gross alpha
<0.3
<1 Gross beta
<0.7
<4-SPW-8927 Water Aug 1990 V-234
<0.01
<1 U-235
<0.02
<1 U-238
<0.01
<1 SPW-8928 Water-Aug 1990 Mn-54
<A.0
<5 Co-58
<4.1
<5 Co-60
<2.4
<5 Cs-134
<3.3
<5 Cs-137
<3.7
<5
' 1.4
<5
'SPW-8929 Water Aug 1990 S r-89 Sr-89
<0.6-
<1
- SPW-69 Water Sep 1990 S r <1.8
<5 S r-90
<0.8
<1
- SPW-106; Water Oct 1990 H-3
<180
<300-
^
'SPM-107 Mil k Oct 1990; I-131:
<0.4
<1 Cs-134'
<3.3
<5 5
Cs-137-
<4.3 SPW-370 Water-Oct 1990 Mn-54
<1.7
<5 Co-58
<2.6
<5 Co-60
<1.6
<5 Cs-134-
< 1 =. 7
<5 Cs-137-
<1.8'
<5 SPW-372; Water:
. Dec 1990 Gross alpha
<0.3_
<1 Gross-beta-
<0.8=
<4 y
a low level of Sr-90 concentration in milk (1_- 5 pCi/L) is not unusual.
AII-34
,w
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TIML-BLIND-01 Pevision 0, 12 29-86 l
ATTACHMENT B ACCEPTANCE CRITERIA FOR " SPIKE 0" SAMPLES LABORATORY PRECISION:
ONE STANDARD DEVIATION VA'.UES FOR VARIOUS ANALYSESa j
One Standard Deviation 1
Analysis Level for Single Determination I
Gama Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-89b 5 to 50 pCi/ liter or kg 5 pCi/ liter
>50 pCi/ liter or kg 10% of known value St ronti uia-90b 2 to 30 pC1/ liter or kg 3,0 pC1/ liter
)
>30 pCi/ liter of kg 10% of known value Pctassium
>0.1 g/ liter or kg 5% of known value Gross Alpha
<20 pCi/ liter 5 pCi/ liter
>20 pC1/ liter 25% of known value Gross Beta
<100 pCi/ liter 5 pCi/ liter
>100 pCi/ liter 5% of known value Tritium
<4,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known).0933
>4,000 pCi/ liter 10% of known value Radium-226,
<0.1 pC1/ liter 15% of known value Radium-228 Plutonium 0.1 pC1/ liter, gram, 10% of known value or sample lodine-131, b
<55 pCi/ liter 6 pCi/ liter lodine-129
>55 pCi/ liter 10% of known value Uranium-238
<35 pCi/ liter 6 pCi/ liter 6
Nickel-63,
>35 pCi/ liter 15% of known value Technetium-99b I
Iron-55b 50 to 100 pCi/ liter 10 pC1/ liter
>100 pCi/ liter 10% of known value a From EPA publication, " Environmental Radioactivity Laboratory Intercompari-son' Studies Program, Fiscal Year 1981-1982, EPA-600/4-81-004.
b TIML limit.
A11-35
ADDENDUM TO APPENDIX A The following is an explanation of the reasons why certain samples were outside the control limit specified by the Envi ror. ment al Protection Agency for the Interlaboratory Comparison Program starting January 1987.
EPA TIML Control Result Limit Lab Code Analysis (pC1/L)a (pCi/L)a Explanation STM-504 Sr-89 57.014.3 60.3-77.7 Milk had high f at content which Sr-90 32.011.0 32 4-37.6 made analyses difficult.
Ad-dition of errors to TIML result would put values within EPA control limits.
EPA also had the same problera in analyzing its own sample.
STW-511 Ra-228 8.1 1.4 4.6-8.0 T!rtL results are usually within EPA control limits.
Analysis of the next sample was within EPA control limits.
No further action is planned.
STW-516 C r-51 80.3117.5 61.3-78.7 Results in the past have been within EPA control limits and TIML will monitor the situation in the future.
STF-524 K
1010.72158.5b 1123.5-1336.5b Error in transference of data.
Correct data was 1105133 mg/kg.
Results in the past have been within the limits and TIML will monitor the situation in the future.
STW-532 1-131 9.0 2.0 6.2-8.8 Sample recounted af ter 12 days.
The average result was 8.8al.7 pCi/L (within EPA control limits).
The sample was recounted in order to check the decay.
Results in the past have been within the limits and l
TIML will continue to monitor the situation in the future.
a Reported in pCi/L unless otherwise noted.
b Concentrations are reported in mg/kg.
AII-36
ADDENDUM TO APPENDIX A (continued)
EPA TIML Control Result Limit Lab Code Analysis (pC1/L)a (pCi/L)a Expl anation STW-534 Co-60 63.311.3 41.3-58.7 High level of Co-60 was due to contamination of beaker. Beaker i
was discarded upon discovery of contamination and sample was recounted.
Recount results 53.213.6 and 50.922.4 pCi/L.-
STM-554 Sr-90 51.022.0 54.8-65.2 The cause of low result was due to very high fat content in-the i
milk.
It should be noted that -
63% of all participants failed this test.
Also, the average for all participants was 54.0 pCi/L before the Grubb and 55.8 pC1/L after the Grubb.
STW-560 Pu-239-5.8 1.1 3.5-4.9 The cause of high results is not known it is suspected that the standard was not properly calibrated by supplier and is-uiide r - investigation.
New Pu-236 standartl was obtained y
and will be use0 for-the next test.
STW-568 Ra-228 2.621.0-2.7-4.5 The cause of low results is not known.
Next EPA crosscheck-results were within the control limits.
No further action is pl anned.
STM-570-Sr-89 26.0110.0 30.3-47.7 The cause' of low results was S r-90 45.724.2 49.8-60.2 falsely high recovery due to suspected incomplete calcium removal.
Since EPA sample was used up, internal spike was prepared and analyzed. _. The -
results were within control limits (See tabie A-3, sample QC-MI-24).
No further action -
is planned.
a Reported in pC1/L unless otherwise noted.
l l
l-11 AII-37
ADDENDUM TO APPENDIX A (continued)
EPA TIML Control Result Limit Lab Code Analysis (pC1/L)a (pC1/L)a Expl anation STW-589 Sr-90 17.321.2 17.4-22.6 Sample was reanalyzed in tri-plicate; results of reanalyses 18.811.5 pC1/L.
No further action is planned.
STM-599 K
1300.0169.2C 1414.7-1685.3C Sample was reanalyzed in trip-licate. Results of reanalyses, 1421.7195.3 mg/L. The cause of low results is unknown.
STW-601 Gross 11.022.0 11.6-32.4 Sample was reanalyzed in trip-Alpha licate. Results of reanalyses, 13.411,0 pCi/L.
a Reported in pC1/L unless otherwise noted, c Concentrations are reported in mg/L.
A11-38
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