ML20108A334
| ML20108A334 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1995 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20108A316 | List: |
| References | |
| NUDOCS 9605020227 | |
| Download: ML20108A334 (150) | |
Text
.----.c.
DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNITS 1 AND 2 LICENSES DPR-66 AND NPF-73 1995 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL D DO K 0 0 M R PDR
- r. .. .
)
Duquesne Light Company 1995 Annual Radiological Environmental Report l l
EXECUTIVE
SUMMARY
q This report describes the Radiological Environmental Monitoring Program conducted during 1995 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 1995.
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 1995 except during a refueling outage January 3 through March 8, 1995 and maintenance outages August 19 through August 27 and December 18 through December 26,1995. The high average daily output generated during the year, 840 megawatts net was reached in November 1995 and the total net electrical generation during the year was 5,442,920 megawatt-hours.
Beaver Valley Power Station Unit 2 operated throughout the year except during a refueling outage March 24 through May 9,1995 and a maintenance outage August 13 through August 15, 1995. The highest average daily output generated during the year was 845 megawa'ts net in both November and December 1995 and the total net electrical generation during the year was 6,044,518 megawatt-hours.
In 1995, samples were taken from over 60 sites around Beaver Valley Power Station that included the aquatic, atmospheric and terrestrial environments. More than 3,000 analyses were performed on these samples.
During the year, the radioactive releases from BVPS Units 1 and 2 did not exceed the effluent limits identified in the Beaver Valley Power Station Operating License Technical Specifications /Offsite Dose Calculation Manual (ODCM) for Units 1 and 2.
Based upon the estimated dose to individuals from the natural background radiation exposure, the incremental increase in total body dose to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit No.1 and No. 2, is less than 0.0003% of the annual background. See Section V.I for specific details. The National Academy of Sciences 1990 BEIR Report shows that the typical j dose to an individual from background (natural radiation exposure including radon) j is 296 mrem per year. l 1
The environmental monitoring program outlined in the Beaver Valley Power Station ,
Operating License Technical Specifications /ODCM for Units 1 and 2 was followed throughout 1995. 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.
ll EXECUTIVE
SUMMARY
1 I
Duquesne Light Company 1995 Annual Radiological Environmental Report Table of Contents Section 1. INTRODUCTION . . . .. . ... .... 1-1 A. Scope and Objectives of the Program ... . .. 1-1 B. Description of the Beaver Valley Site . . . . 1-1 Section 2. RESULTS AND CONCLUSIONS ...... .. .. . . . 2-1 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS . .. . 3-1 A. Environmental Quality Control Program .. . ....... 3-1 B. Evaluation of the Quality Control Program Data . . 3-16 C. Standard Requirements and Limitations for Radiological and Other Effluents . .. . ... .. . .. . 3-18 D. Reporting Levels .. ............ ... 3-18 Section 4. MONITORING EFFLUENTS ... .... . .. .. 4-1 A. Monitoring of Liquid Effluents . .. .. . 4-1
- 1. Description of Liquid Effluents at the Beaver Valley Power Station. . . .. .. 4-1
- 2. Radioactive Liquid Waste Sampling and Analysis Program . . . . . . , .. . 4-1
- 3. Results of Liquid Effiuent Discharge to the Environment 4-1 B. Monitoring of Atmospheric Effluents .. ... ... 4-10
- 1. Description of Atmospheric Effluent Sources .. . 4-10
- 2. Atmospheric Effluent Treatment and Sampling .. 4-13
- 3. Results . .. . . . ..... 4-17 C. Solid Waste Dicposal . . . . . 4-17 Section 5. ENVIRONMENTAL MONITORING PROGRAM .. .. . 5-1 A. Environmental Radioactivity Monitoring Program .. . 5-1
- 1. Program Description . ... .. .. . . 5-1
- 2. Summary of Results ... . ...... ........ 5-6
- 3. Quality Control Program .. ..... ...... . . 5-6 B. Air Monitoring .... .... .......... ....... 5-22
- 1. Characterization of Air and Meteorology . ...... 5-22
- 2. Air Sampling Program and Analytical Techniques .. .. . . ... . 5-22 3 Results and Conclusions . . .. . . ... 5-24 C. Monitoring of Sediments and Soils . .... ... . . 5-26 l 1. Characterization of Stream Sediments and Soils . 5-26
- 2. Sampling Program and Analytical Techniques 5-26
- 3. Results and Conclusions .......... .. .. 5-28 D. Monitoring of Feedcrops and Foodcrops .. .. .. 5-29
- 1. Characterization of Vegetation and Foodcrops . 5-29
- 2. Sampling Program and Analytical Techniques . . 5-29
- 3. Results and Conclusions . . . . . . 5-32 E. Monitoring of Local Cows Milk . ..... .. . . . 5-33
- 1. Description - Milch Animal Locations . .. .. . 5-33 l 2. Sampling Program and Analytical Techniques ... 5-33
- 3. Results and Conclusions .... . .. ..... . 5-36 Tame of contents ill
Duquesne Light Company 1995 Annual Radiological Environmental Report F. Environmental Radiation Monitoring . 5-37
- 1. Description of Regional Background Radiation and Sources . . .... 5-37
- 2. Locations and Analytical Procedures . . 5-37
- 3. Results and Conclusions . . . 5-38 G. Monitoring of Fish . . ... 5-43
- 1. Description .. . 5-43
- 2. Sampling Program and Analytical Techniques 5-43
- 3. Results and Conclusions . .. .. 5-43 H. Monitoring of Surface, Drinking, Well Waters and Precipitation .
5-45
- 1. Description of Water Sources .
5-45
- 2. Sampling and Analytical Techniques 5-46
- 3. Results and Conclusions .
5-49
- 1. Estimates of Radiation Dose to Man . 5-52
- 1. Pathways to Man - Calculational Models 5-52
- 2. Results of Calculated Radiation Dose to Man - Liquid Releases .. . . 5-53 E
- 3. Results of Calculated Radiation Dose to Man - 3 Atmospheric Releases . 5-56
- 4. Conclusions .. . . . 5-57 I
l I
l l
i I
I IV Table of Contents
Duquesne Light Company 1995 Annual Radiological Environmental Report List of Tables 3-1. Quality Control Data - Contractor Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/ day . . . . 3-2 3-2. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Surface Water Samples . . . 3-3 3-3. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Drinking Water Samples . 3-4 3-4. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Milk Samples . .. . . 3-5 3-5. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Feed, Food and Sediment Samples . 3-6 3-6. Quality Control Data - Contractor / Quality Control Labora*.'ry Comparison Spiked Water Samples . .. . . 3-8 3-7. Quality Control Data - Contractor / Quality Control Laboratory Comparison Spiked Milk Samples . 3-9 3-8. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate and Charcoal Filter Samples . 3-10 3-9. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/m') . . 3-12 3-10. Quality Control Data - Contractor / Quality Control Laboratory Air Particulate Composite Samples Compalison Split for Sr-89 and Sr-90 (pCl/m 8) . .. . 3-13 i
3-11. Quality Control Data - Independent Laboratory / Contractor / Quality d Control Laboratory Comparison Spiked Water Samples (pCl/l) 3-14 3-12. Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Comparison Spiked Milk Samples (pCl/l) 3-15 4-1. Radioactive Liquid Waste Sampling and Analysis Program . .. 4-7 4-2. Results of Liquid Effluent Discharges to the Environment . . 4-9 4-3. Radioactive Gaseous Waste Sampling and Analysis Program 4-15 5-1. Radiological Environmental Monitoring Program . . . 5-2 5-2. Environmental Monitoring Program Results (1995) . .. . 5-7 5-3. Pre-operational Environmental Radiological Monitoring Program Summary . ... . . . ... 5-18 5-4. Typical LLDs For Gamma Spectrometry . . . 5-21 5-5. Closest Residence and Garden in Each Sector ... . 5-31 5-6. Radiation Dose to Maximum Individual, mrem /yr - Liquid Releases 5-54 5-7. Results of Calculated Radiation Dose to Man - Liquid Releases . 5-55 5-8. Results of Calculated Radiation Dose to Man - Atmospheric Releases 5-58 I
I l
Ust of Tables V
i Duquesne Light Company 1995 Annual Radiological Environmental Report List of Figures 1-1. View of the Beaver Valley Power Station 1-2 1-2. Geographical Map and Principal Communities in 40-mile Radius of the Beaver Valley Power Station . 1-3 4-1. Liquid Discharge Points to Ohio River 4-2 4-2. Unit 1 Water Flow Schematic .. . 4-3 4-3. Unit 2 Water Flow Schematic . 4-4 4-4. Unit 1 Liquid Waste System ... 4-5 4-5. Unit 2 Liquid Waste System 4-6 4-6. Units 1 and 2 Gaseous Radwaste System 4-11 g 4-7. Units 1 and 2 Gaseous Rebse Points 4-12 3 4-E. Solid Waste Disposal Diagram 4-18 5-1. Air Sampling Stations . 5-23 5-2. Average Concentration of Gross Beta in W Particulates 5-25 5-3. Environmental Monitoring Locations - 9 oreline Sediments and Soll 5-27 5-4. Environmental Monitoring Prograra - Fsederop and Foodcrop Locations 5-30 5-5. Beaver Valley Power Station Milch Animal Census . 5-34 5-6. Environmental Monitoring Locations - Milk . 5-35 5-7. TLD Locations - Northwest Quadrant 5-39 g 5-8. TLD Locations - Northeast Quadrant . . 5-40 g 5-9. TLD Locations - Southeast Quadrant . 5-41 5-10. TLD Locations - Southwest Quadrant . 5-42 5-11. Environmental Monitoring Program - Fish Sampling Locations . . 5-44 5-12. Environmental Monitoring Stations Locations - Wells, Surface Water, Drinking Water and Precipitation . ... . 5-48 I
I I
I i
l vi Ust of Figures I
l l
Duquesne Light Company 1995 Annual Radiological Environmental Report !
1 Section 1. INTRODUCTION A. Scope and Objectives of the Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are 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 1995.
B. Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land. Figure 1-1 is a view of the Beaver Valley Power Station. The site is approximately cz mile from Midland, Pennsylvania; 5 miles from East Liverpool, Ohio; and 25 miles from Pittsburgh, Pennsylvania. Figure 1-2 shows the site location in relation to the princi; , population centers. Population density in the immediate vicinity of the site is relatively low. The population within a 5 mile radius of the plant is approximately 18,000 and the only area within the radius of ,
concentrated population is the Borough of Midland, Pennsylvania, with a population I of approximately 3,500.
The site lies in a valley along the Ohio River, it extends from the river (elevation l 665 feet above wa level) to a ridge along the border south of the Beaver Valley l Power Station at an elevation of 1,160 feet. Plant ground level is approximately 735 feet above sea level.
The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam.' The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from l the site. The river flow is regulated by a series of dams and reservoirs on the l Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. Flow ranges from a minimum of approximately 5000 cubic feet per second (CFS) to a maximum of approximately 100,000 CFS The mean annual flow is approximately 25,000 CFS.
Water 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 52.3 F. The predominant wind direction is typically from the southwest in summer and from the northwest in winter.
section 1. INTRODUCTION 1-1
Duquesne Light Company 1995 Annual Radiological Environmental Report i Figure 1-1. View of the Beaver Valley Power Station
.n. g..s
- 4. v
... 4 . ..
..I . + %) '
l j , .
w
- Mg
,p 4p
..s
,j >,. u j y. ,. ,
{
2 hi
-e
(('
r
.m
- g i'
, pM N" .' J i
. M_a g y, . si' ial, l
s ,
7 g
...s s f&
S g./.. g$?lWtif p sis-
. 2.g., ,
b ,,I l ^ l? ?ffffy;
%%h 1As' 1: ;JQ CNhf- e s ' 4'. . %ef . ik!j$,.
~;g 7
- w. _3 b35hi -
a .', D Ifk #
I 1-2 Section 1. INTRODUCTION
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 1-2. Geographical Map and Principal Communities in 40-mile Radius of the Beaver Valley Power Station
! ao YoycsTc'g 42' NrJ CASTI2 ,-
\ I
{.
""",, } n 42:,
anLER f
[- \
45 l 4,%, 6 g
10 <+,
O
( 30 acao or SFIPPac?ou g4 EAST 'q,IQ EPPA KE55I1C.cyl uvrns of, ,
[ 6 I Si a
1 4 / / 'e 27 rITTsatra / 22 ~
"",'/h
@ l j.m,P- %
2
[$ lj
'JASHINGTCN y
40
/ 40 ag _
[ (
- Roads
[ Rivers y Cities
[ CEOGRAPHICAL MAP AND PRINCIPAL C0tEPJ:!ITIES IN 40-:!ILE RADIUS OF THE BEAVER VALLEY POWER STATION FIGURE 1-2
[
L Section 1, INTRODUCTION 1-3
Duquesne Light Company 1995 Annual Radiciogical Environmental Report The design ratings and basic features of the Beaver Valley ' Power Station Units 1 and 2 are tabulated below:
Beaver Vallev Unit 1 Beaver Vallev Unit 2 Thermal & Elec. Rating (Net MW,) 2660 MW,835 MW, 2660 MW,836 MW, Type of Power PWR PWR No. of Reactor Coolant Loope 3 3 No. of Staam 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.
NOTE: MW,- megawatts thermal MW, - megawatts electrical I
1-4 section 1. INTRODUCTION
l Duquesne Light Company 1995 Annual Radiological Environmental Report Section 2. RESULTS AND CONCLUSIONS Plant operations at the Beaver Valley Power Station had no adverse effects on the environment as a result of activity at the station during 1995.
The Beaver Valley Power Station Unit 1 operated throughout 1995 except during a refueling outage January 3 through March 8,1995 and maintenance outages August 19 through August 27 and December 18 through December 26,1995. Unit 2 operated throughout the year except during a refueling outage March 24 through May 9,1995 and a maintenance outage August 13 through August 15,1996. 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 Operating License Technical Specifications /Offsite Dose Calculation Manual (ODCM) for Units 1 and 2.
The environmental program for 1995 was the same as in 1994 except several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications /ODCM. (Refer to Table 5-1 for the 1995 Radiological Monitoring Program Outline.)
The Beaver Valley Power Station Technical Specifications /ODCM require sampling of three (3) dairies which have the highest calculated milk pathway potential and one large local dairy. The three dairies are determined from calculations based on the meteorological data and the latest milch animal survey. However, these dairies are frequently small, consisting of as few as one cow or goat. The availability of milk from single cow dairies and revisions due to updated calculations and surveys normally result in sampling of several additional dairies during the year in different 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 dalries required by the Technical Specifications /ODCM. The collection periods associated with each of the locations are provided in the detailed summary of the milk monitoring program of this report (Section 5-E).
Activity detected was attributable to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests, medical procedures or to the normal statistical fluctuation for activities near the lower limit of detection (LLD). The positive results attributable to the Beaver Valley Power Station were consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license.
The results and conclusions for each media of the 1995 Radiological Environmental Monitoring Program are contained in Section 5 of this report. A summary of the 1995 operational environmental data is found in Table 5-2 and a summary of preoperational data (1974-1975) environmental data is found in Table 5-3.
l L Section 2. RESuLTS AND CoNCluSloNS 2-1
Duquesne Light Company 1995 Annual Radiological Environmental Report Evaluation of effluent release data from the Beaver Valley Power Station and environmental media demonstrated complience with regulations and Station 1
j Technical Specifications /ODCM.
j s
l 4
4 I
2-2 Section 2. RESULTS AND CONCLUSIONS
Duquesne Light Company 1995 Annual Radiological Environmental Report Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS A. Environmental Quality Control Program The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) elements. It should be noted that the comparisons made were at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure. See Section 3-B for discussion of comparison criteria for radiochemical determinations. Values in Table 3-2 through Table 3-12 identified with an asterisk (*) do not meet comparison criteria. However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.
Thirteen (13) TLDs from the Contractor Laboratory and QC Laboratory are co-located, replaced quarterly and results compared. The average of the Contractor Laboratory and the average of the quality control laboratory agree within i 4.0% 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 3-1.
- 2. Split Sample Program (DLC Contractor Laboratory - DLC QC Laboratory)
Samples of surface (river) water and drinking water were routinely split and analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory. In addition, samples of other media, such as milk, sediment and feedcrop were also split with the DLC QC Laboratory.
A summary of results of split water samples is provided in Table 3-2 and -
Table 3-3. There were two non-comparisons with surface water. One was for gross beta which was close to comparison and the other was a positive alpha by the QC Laboratory which was reported as LLD by the Contractor Laboratory.
More variability in duplicate samples is expected in surface water due to entrained solids. There were no non-comparisons in all of the drinking water analysis.
Summaries of milk, sediment and feed / food crop split samples are provided in Table 3-4 and Table 3-5. Good overall agreement was obtained with only one non-comparison observed of potassium-40 in feed and non-comparisons in sediment for cobalt-58 and 60 which were close to comparison. Some variation may be expected due to variations in duplicate samples, variations in analytical procedures and in calibration, source type, etc.
(Text continued on page 3-7)
Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-1
Duqueano Light Company l 1995 Annual RadiologiCnl Environmental Report l Table 3-1. Quality Control Data - Contractor Quality Control Laboratory Comparison ,
Thermoluminescent Dosimeters - mR/ day l TABLE 3-1 ll g ,
QUALITY CONTROL DATA - CONTRACTOR QUALITY CONTROL LABORATORY COMPARISON THERMOLUMINESCENT DOSIMETERS - mRIday 1ST QUARTER 2ND QUARTER l DLC DLC - QC DLC DLC - QC Location No. Contractor Lab Location No. Contractor Lah (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) (CaSL,4:Dy) 10 0.20 0.16 10 0.19 0.18 13 0.16 0.15 13 0.18 0.17 14 0.17 0.16 14 0.19 0.18 15 Lost Lost 15 0.17 0.15 27 0.18 0.15 27 0.19 0.18 28 0.17 0.15 28 0.19 0.19 29B 0.20 0.21 29B 0.21 0.23 32 0.18 0.19 32 0.21 0.18 45 0.18 0.17 45 0.20 0.18 46 0.17 0.15 46 0.19 0.17 47 0.20 0.19 47 0.21 0.21 1 48 0.18 0.17 48 0.20 0.18 51 0.18 0.19 51 0.19 0.19 3RD QU ARTER 4TH QUARTER L DLC DLC - QC DLC DLC - QC Location No. Contractor Lab Location No. Contractor Lab (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) 10 0.19 0.15 10 0.17 0.16 13 0.17 0.16 13 0.15 0.15 14 0.18 0.16 14 0.16 0.16 1 15 0.16 0.15 15 0.15 0.14 l 27 0.18 0.15 27 0.17 0.16 i 28 0.19 0.15 28 0.15 0.15 298 0.23 0.19 298 0.20 0.20 32 0.19 0.17 32 0.18 0.16 )
45 0.18 0.16 45 0.18 0.16 j 46 0.16 0.15 46 0.19 0.14 l 1
47 0.20 0.17 47 0.19 0.18 48 0.18 0.17 48 0.13 0.16 51 0.17 0.16 51 0.17 0.17 E
ANNUAL DLC DLC - QC '
Location No. Contractor Lab (CaSO4:Dy) (CaSO4:Dy) 10 0.16 0.15 13 0.15 0.14 14 0.15 0.15 15 Lost Lost 27 0.16 0.15 28 0.16 0.16 29B 0.20 0.18 32 0.18 0.16 45 0.16 0.16 46 0.15 0.15 47 0.19 0.17 48 0.18 0.14 51 0.17 0.15 3-2 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
j Duquesne Light Company i 1995 Annual Radiological Environmental Report Table 3-2 Oulity Control Data - Contractor /Ouality Control Laboratory Comparison Split Surface f Water Samples TABLE 3-2
, QUALITY CONTROL DATA CONTRACTOR /QUALITV CONTROL LABORATORY COMPARISON SPLIT SURFACE WATER SAMPLES Samphng OLC Contractor" DLC - QC Mea Anaysis Unas Penod Lab (1) Lab (1)
January <08 <18 pCiM
~
Surface Water Gross Alpha July < 1.1 1.4110 pCl4 October < 1.8 1.6 i 1.1 pCiM January 45i1.1 35i13 pClM Surface Water Gross Beta July 95i1.7* 46110 pCiM
{ October 11.011.0 7.9 i 1.1 pCIA January <40 <24 pCIA Apr61 <30 < 1.7 pCIA Surface Water Cm July <30 < 1.2 pCl4 October <40 < 10 pC6M January <40 <57 pCIA L
Surface Water Cs 134 July <30 < 1. 7 pCIA October <40 <08 pCIA January <40 <61 pCIA April <40 <18 pCl4 Surface Water Cs 137 July < 3.0 <09 pCIM October <40 < 1.1 pCIM I *'
1700 1 200 1574 i 144 pCtM Surface Water Trttlum
< 0 69 <08 pCIM Composite Surface Water Sr-89
< 0 94 <03 pCIM 2nd Quarter Composite
< 017 <05 pCIM Surface Water Sr 90 f, *{ < 022 <04 pCiM Co-60 2nd Quarter Composite 09 < L2 AM (high Surface Water sensitivity 4th Quarter anayists) Composite
< <' # '^
(1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefflcient.
f
- See Section 3 A.2.
i; I
d Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-3
Duquesne Light Company 1995 Annual Radiological Environmental Report Table 3-3. Quality Control Data Contractor /Ouality Control Laboratory Comparison Split Drinking Water Samples TABLE 3 3 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT DRINKING WATER SAMPLES gg,, Sampling DLC Contractor DLC - QC
, ,, Units Period Lab (1) Lab (t)
February <4 <44 pC6A Dnnking Water May <3 < 2.4 A Cs 137 (weekly split) August <3 <24 pCIA ,
November <5 <33 pCl4 l 1
February <4 <29 pCIA i Dr6nking Water Cs 134 (weekly split) August <3 <28 pC6M November <4 <29 pCiM February <3 <26 pCIM Drtnking Water May <3 <23 pCM i
Co-60 (weekly split) August <3 <20 pCIA November <5 <25 pCiA March < 1.1 <15 pClM Dnnk6ng Water June < 1.8 < 1.1 pCIA (monthly Gross Alpha composite) August <10 < 1.1 pCl4 November <10 < 1.0 pCIA March 33i1.1 60i14 pCIM Dnnking Water June 2.0 10 18i09 pCiA (monthly Gross Beta composite)
November 43i11 28108 pCiA 2nd Quarter < 200 < 154 pCid Dnnking Water Tritium 4th Quarter < 200 < 152 pCl4 (1) Uncertaintles are based on counting statistics and are spectried at the 95% confidence coefficient.
l l
l l
i i
3-4 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 1
1 i
Duquesna Light Company 1995 Annual Radiological Environmental Report Table 34. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Milk Samples TABLE 3-4 I QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT MILK SAMPLES
- P "9 0""" ' ~
I Media Penod Analysis Sr-89 Lab (1)
< 0.81 Lab (1)
< 1.0 Units pCl/l Sr-90 3.0 i 0.2 4.0 i 1.0 pCl/l I Milk (25) 3-20 95 1-131 < 0.17 < 0.1 pCl/l Cs-134 <4 < 3.2 pCl/l Cs 137 <4 < 3.6 pCi/l I K-40 1250 i 120 1360 i 100 pCi/l Co-60 <4 < 8.6 pCl/l 1-131 < 0.23 < 0.3 pCl/l Milk (25) 6-12-95 Cs-134 <4 < 3.7 pCi/l Cs-137 <4 < 5.7 pCl/l K-40 1310 i 130 1440 i 160 pCl/l Sr-89 < 0.82 < 0.5 pCl/l Sr-90 3.5 i 0.2 3.210.50 pCl/l i Milk (25) 9-18-95 1-131 Cs-134
< 0.28
<5
< 0.2
< 3.6 pCl/l pCl/l Cs-137 <5 < 3.5 pCl/l I K-40 1220 i 120 1470 i 120 pCl/l Co-60 < 3.0 < 5.2 pCl/l l-131 < 0.2 < 0.5 pCl/l I Milk (25) 12 11-95 Cs-134 < 3.0 < 6.5 pCl/l Cs-137 < 3.0 < 5.5 pCl/l K-40 1310 i 130 1220 i 150 pCl/l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
I I
i 1
L r-Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-5
I Duquesne Light Company 1995 Annual Radiological Environmental Report Table 3-5. Quality Control Data Contractor /Ouality Control Laboratory Comparison Split Feed, Food and Sediment Samples TABLE 3-5 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL l.ABORATQRY COMPARISON SPLIT FEED, FOOD AND SEDIMENT SAMPLES Sampling DLC Contractor DLC - QC Units Media ,,,
Period Lab (1) Lab (1)
Be-7 < 0.4 < 0.097 pCl/gm (dry)
K-40 34.3 i 0.3* 9.8 i 0.5 pCl/gm (dry)
Co-60 < 0.04 < 0.014 pC1/gm (cry)
Feed (25) 6-12-95 l-131 < 0.009 < 0.017 pCi/gm (dry)
Cs-134 < 0.04 < 0.015 pCl/gm (dry)
Cs-137 < 0.04 < 0.012 pCl/gm (dry)
Feed $5) 4/18 - 6/12 Sr-90 0.17 i 0.02 0.004 i 0.002 pCl/gm (dry)
K-40 2.3 i 0.2 3.8 i 0.6 pCl/gm (wet)
Co-60 < 0.009 < 0.013 pCi/gm (wet)
Food (10) 10-31-95 l131 < 0.003 < 0.047 pCl/gm (wet)
Cs-134 < 0.009 < 0.028 pC!/gm (wet)
Cs-137 < 0.009 < 0.014 pCl/gm (wet)
Gross Alpha 14.0 i 6.0 25.1 i 7.4 pCl/gm (dry)
Gross Beta 43.0 i 4.0 32.2 i 4.8 pCl/gm (dry)
Sr-89 < 0.081 < 0.011 pCl/gm (dry)
Sr 90 < 0.024 < 0.024 pCi/gm (dry)
Mn.54 0.4210.10 049 i 0.13 pCl/gm (dry)
Co-58 3.4110.34* 4.67 i 0.24 pCl/gm (dry)
Sediment (2A) 10-15-95 Co-60 6.32 i 0.63* 8.43 i 0.16 pC1/gm (dry)
Ag-110 0.93 i 0.09 - pCi/gm (dry) W Sth125 0.88 i 0.21 - pCl/gm (dry)
Cs-134 < 0.1 < 0.13 pCl/gm (dry)
Cs-177 0.153 i 0.057 0.225 i 0.77 pCl/gm (dry)
Ra-226 2.81 i 1.37 3.19 i 0.83 pCl/gm (dry)
Th-228 1.19 i 0.12 - pC1/gm (dry)
K-40 11.40 i 0.11 15.04 i 1.14 pCi/gm (dry)
(1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
See Section 3.A.2 and 3-B.
I 3-6 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS I!
[ Duquesne Light Company i 1995 Annual Radiological Environmental Report
[ 3. DLC QC Laboratory Program Spiked samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for analysis. Table 3-6 (water) and Table 3-7 (milk) provide data from this portion of the QC Program. See Section 3-B for evaluation of the data.
[ 4. Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory)
[ Duplicate air particulate and charcoal filters (radiolodine) samples were I collected at Location #30 and compared during the year on a weekly basis.
Comparison of particulate and charcoal samples alternated from week to week.
j Duplicate monthly air particulate filters, composited from the weekly air t particulate filters, were analyzed 6 months out of the year for gamma activity.
Duplicate quarterly air particulate filters, composited from the weekly air particulate filters, were analyzed for Sr-89 and Sr-90 activity for each quarter of the year. Table 3-8, Table 3-9 and Table 3-10 provides data for this portion of the QC program.
- 5. Contractor and QC Laboratory - Internal QC Program The Contractor and QC Laboratory maintained their own QC program which included participation in the Environmental Protection Agency - Environmental f Monitoring Safety Laboratory (EPA - EMSL) Interlaboratory Cross Check Program. This cross check program indicated that the Contractor and QC Laboratory results were in agreement with EPA EMSL. The Contractor data for f 1994 and 1995 is presented with trending graphs from 1981. See Appendix I and ll.
- 6. Special QC Program (DLC Contractor Laboratory - Independent Laboratory -
{ DLC QC Laboratory)
Low level spiked water and milk samples are prepared by a vendor noted for f supplying quality primary standards with NIST traceability. The " spiked to" values are used for calculating comparison acceptance criteria. The prepared spiked samples are then split between the DLC Contractor Laboratory and the f DLC QC Laboratory. A summary of results of this portion of the QC program is provided in Table 3-11 and Table 3-12. See Section 3-B for evaluation of this data.
(Text continued on page 3-16) l Section 3. ENVIRONMENTAL MONITORING CONSIDERATloNs 3-7
Duquesne Light Company 1995 Annual Radiological Environmental Report Table 3-6. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Spiked Water Samples TABLE 3-6 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPIKED WATER SAMPLES Sample Identification Sample DLC - QC Date N o. Analysis Lab (1) 3-14-95 W-119 I*
- b E
Sr-90 39.0 i 1.0 39.1 i 5.0 pCi/l 4-10-95 W-120 H-3 8900 300 9656 i 292 pCi/l Co-60 24.7 i 3.6 23.8 2.4 pCi/l 4-13-95 W-121 Cs-134 29.1 i 3.8 29.3 i 2.3 pCl/l Cs-137 48.1 i 4.8 423 i 3.9 pCill 6-8-95 W-122 1-131 46.0 i 1.0 48.2 i 1.9 pCl/l ss 16.0 i 4.0 17.3 i 1.4 pCi/l Alpha 6-8-95 W-123 29.0 5.0* 21.2 i 1.0 pCl/l Be a Sr-89 21.0 i 2.0 18.7 i 2.4 pCi/l 5-31-95 W-124A Sr-90 23.0 i 1.0 21.2 i 1.1 pCi/l S r-89 43.0 i 1.0 34.6 i 4.9 pCi/l 9/27/95 W-124B Sr-90 21.0 i 1.0 20.3 i 1.3 pCl/l 11-29-95 W-125 H-3 28000 i 1000 27963 i 445 pCi/l Co-60 27.0 i 3.7 22.0 i 1.9 pCi/l 11/29/95 W-126 Cs-134 45.5 i 4.6 38.1 i 2.0 pCill Cs-137 30.9 i 4.1 27.2 i 3.0 pCl/l 19.0 i 5.0 19.6 3.0 pCl/l h
12-29-95 W-127 31.0 i 5.0 21.0 i 1.8 pCl/l Bet (1) Uncertainties are based on counting statistics and are specified at the 95% ,
confidence coefficient.
See Section 3-B.
I' I
3-8 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS I
Duquesne Light Company 1S95 Annual Radiological Environmental Report i
Table 3-7. Quality Control Data Contractor /Ouality Control L.aboratory Comparison Spiked Milk Samples TABLE 3-7 QUALITY CONTROL DATA.
CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPIKED MILK SAMPLES f
Sample identification Sample DLC - QC Date
" " I ni s N o. Analysis Lab (1)
Sr-89 31.0 i 2.0 19.4 i 3.4 pCl/l Sr-90 26.0 i 1.0 26.2 i 1.3 pCl/l 1-13-95 M i-58' Cs-137 60.3 6.0 51.2 7.5 pCill J K-40 1380 140 1250 i 120 pCl/l 1-31-95 Mi-59 l-131 81.0 i 2.0 84.8 i 10.4 pCi/l Cs-134 37.6 3.8 - 37.7 i 1.8 pCi/l 4-26-95 Mi-60 Ca-137 68.5 i 6.9 69.4 i 3.1 pCl/l K-40 1310 i 130 1426 i 49 pCl/l 6-1-95 Mi-61 1-131 83.0 i 1.0 78.8 i 2.3 pCl/l Sr-90 29.0 i 1.0 28.0 i 1.4 pCl/l 1-131 50.0 i 1.0 44.7 i 5.4 pCill 7-5-95 Ml-62 Cs-134 34.1 i 4.6 31.5 i 2.5 pCi/l Cs-137 54.8 i 5.5 50.2 i 4.0 pCl/l K-40 1470 i 150 1350 i 60 pCi/l 1-131 76.0 i 1.0 70.9 i 0.8 pCill Cs-134 25.2 i 4.3 27.9 i 3.9 pCl/l 10-17-95 Mi-63 Cs-137 47.9 i 4.8 52.3 i 6.9 pCi/l K-40 1320 i 130 1340 i 110 pCi/l (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence coefficient.
f See Section 3-B Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-9
.m to
, TABLE 3-8 6
j QUALITY CONTROL DATA p p CONTRACTOR /QUAll1Y CONTROL LABORATORY COMPARISON E m SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES z
j Air Particulates Air lodine [
g pCi/Cu. Meter (Beta) pCi/Cu. Meter oO E DLC DLC $E
- ~N Ed
~
- Sample Date Contractor Sample Date Contractor N Lab (1)
- II Lab E C *oo a D
g 1/3 - 1/9 0.024 i 0.004 0.021 i 0.003 1/9 - 1/16 < 0.02 < 0.01 *3
$ 1/16 - 1/23 0.008 i 0.003 0.011 1 0.002 1/23 - 1/30 < 0.02 < 0.01 o E g 1/30 - 2/6 0.019 i 0.003 0.019 i 0.003 2/6 - 2/13 < 0.02 < 0.01 $ 5 0 oa w
-a 8 2/13 - 2/21 0.019 1 0.003 0.021 i 0.003 2/21 - 2/27 < 0.01 < 0.01 !!!. . c 2 7 g 2/27 - 3/6 0.015 i 0.003 0.015 1 0.002 3/6 - 3/13 < 0.02 < 0.01 gQ $a@
3/13 - 3/20 0.015 i 0.003 0.017 i 0.003 3/20 - 3/27 < 0.01 < 0.01 hh h y 3/27 - 4/3 0.013 i 0.003 0.013 1 0.002 4/3 - 4/10 < 0.02 < 0.02 jk $-r-E 4/10 - 4/17 0.011 i 0.003 0.012 i 0.002 4/17 - 4/24 < 0.02 < 0.01 5 g 4/24 - 5/1 0.010 i 0.003 0.015 i 0.002 5/1 - 5/8 < 0.02 < 0.01 g {Q 5/8 - 5/15 0.009 1 0.003 0.012 i 0.002 5/15 - 5/22 < 0.03 < 0.01 5/22 - 5/30 0.012 1 0.003 0.011 1 0.002 5/30 - 6/5 < 0.02 < 0.01 ". o 3$ ox
~
6/5 - 6/12 0.014 i 0.003 0.010 i 0.002 6/12 - 6/19 < 0.02 < 0.01 ?. 6/19 - 6/26 0.022 0.003 0.021 i 0.003 6/26 - 7/3 < 0.02 < 0.01 h m (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. $o o E 3 9 3 E 2. O 3 T3
.=.
mas
TABLE 3 8 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES Air Particulates Air lodine pCi/Cu. Meter (Beta) pCi/Cu. Meter Sample Date con actor Sample Date Con ractor Lab (1) Lab - 7/3 - 7/10 0.014 i 0.003 0.013 0.003 7/10 - 7/17 < 0.03 < 0.01 7/17 - 7/24 0.021 i 0.003 0.021 1 0.003 7/24 - 7/31 < 0.02 < 0.01 g 7/31 - 8/7 0.015 i 0.003 0.018 i 0.003 8/7 - 8/14 < 0.02 < 0.01 S 8/14 - 8/21 0.027 i 0.003 0.027 i 0.003 8/21 - 8/28 < 0.02 < 0.01 8/28 - 9/4 0.026 i 0.003 0.024 i 0.003 9/4 - 9/11 < 0.04 < 0.01 E.@ 9/11 - 9/18 0.018 i 0.003 0.018 i 0.003 9/18 - 9/25 < 0.01 < 0.01 $- vi 9/25 - 10/2 0.037 i 0.004 0.038 i 0.003 10/2 - 10/9 < 0.02 < 0.02 $t 10/9 - 10/16 0.025 i 0.003 0.030 1 0.003 10/16 - 10/23 < 0.02 < 0.01 g
!* 10/23 - 10/30 0.016 i 0.003 0.014 i 0.003 10/30 - 11/6 < 0.01 < 0.01 {p j 11/6 - 11/13 0.016 i 0.003 0.019 i 0.003 11/13 - 11/20 < 0.02 < 0.01 jj
@ 11/20 - 11/27 0.022 i 0.003 0.025 1 0.003 11/27 - 12/4 < 0.01 < 0.01 3$
mx 2 g 12/4 - 12/11 0.023 i 0.003 0.027 i 0.003 12/11 - 12/18 < 0.01 < 0.02 y 12/18 - 12/26 0.011 i 0.003 0.014 0.002 12/26 - 1/2 < 0.01 < 0.01 ] h E (1) Uncertainties are based on counting statistics and are specified at the 95*4 confidence coefficient. $ 0 $ a 27 s O 8 5 ~6 E 6 w
Duquesne Light Company 1995 Annual Radiological Environmental Report Table 3-9. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/m') TABLE 3-9 QUALITY CONTROL DATA ! CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE SAMPLES (GAMMA)(pC1/m') ntractor DLC - QC Sample Date Nuclide l Lab (1) Lab (1) Be-7 0.097 i 0.010 0.079 i 0.022 January i Others < LLD < LLD l Be-7 0.137 i 0.014 0.120 i 0.022 Others < LLD < LLD Be-7 0.124 i 0.012 0.153 i 0.030 May Others < LLD < LLD Be-7 0.186 i 0.019 0.189 i 0.037 July _ Othors < LLD < LLD 3e-7 0.176 i 0.018 0.125 i 0.025 September Others < LLD < LLD Be-7 0.116 i 0.012 0.139 i 0.031 Others < LLD < LLD (1) Uncertaintics are based on counting statistics and are specified at the 95% confidence coefficient. LLD - Lower Limit of Detection l l 1 I 3-12 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
Duquesne Light Company 1995 Annual Radiological Environmental Report Table 310. Quality Control Data - Contractor / Quality Control Laboratory Air Particulate Cornposite Samples Comparison Split for Sr-89 and Sr-90 (pCi/m') TABLE 3-10 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY AIR PARTICULATE COMPOSITE SAMPLES COMPARISON SPLIT FOR Sr-89,90 (pCl/m*) DLC - Contractor DLC - QC Sample Date Nuclide Lab Lab ist Quarter Sr-89 < 7.4E-4 < 4E-4 Compos!te Sr-90 < 1.9E-4 < 3E-4 2nd Quarter Sr-89 < 1.1 E-3 < 4E-4 Composite Sr-90 < 2.5E-4 < 3E-4 3rd Quarter Sr-89 < 7.9E-4 < SE-4 Composite Sr-90 < 1.5E-4 < 3E-4 4th Quarter Sr-89 < 5.1 E-4 < SE-4 Composite S r-90 < 9.5E-5 < 3E-4 l Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-13
9 Duquesne Light Company 1995 Annual Radiological Environmental Report Table 3-11. Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Cornparison Spiked Water Samples (pCi/l) TABLE 3-11 QUALITY CONTROL DATA INDEPENDENT LABORATORY / CONTRACTOR / QUALITY CONTROL LABORATOFlY COMPARISON SPlKED WATER SAMPLES (pCl/l) Sample identification Sample Type Independent DW - QC CONTRACTOR Date No. and Analyses Lab (1) Lab (1) Sr.89 40.0 i 2.0 36.5 i 1.0 35.4 i 1.9 Sr-90 15.0 i 1.0 13.5 i 1.0 13.3 i 0.6 3-14-95 53 1-131 42.0 i 2.0 39 5 i 1.0 37.5 i 1.5 Cs 134 15.0 i 1.0 15.4 3.5 13.6 i 1.4 Cs-137 9.8 i 0.5 11.4 i 3.3* 11.1 i 2.0 3-14-95 53 H-3 608 i 30 560 i 50 657 i 65 Sr-89 14.5 i 0.7 13.5 i 5.0" 12.4 i 1.1 Sr-90 10.5 i 0.5 9.9 i 1.0** 10.1 i 0.5 6-13-95 Co-60 15.5 i 0.8 18.7 i 3.9 16.3 i 1.1 1-131 21.0 i 1.0 20.5 i 1.0 20.0 i 0.4 Cs-137 10.2 i 0.5 8.2 i 3.2 10.2 i 1.3 6-13-95 H-3 1490 i 70 1400 i 200 1514 i 73 53 6 Sr-89 19.0 i 1.0 22.0 i 2.0 13.8 i 3.1* Sr-90 20.5 i 1.0 20.5 i 1.0 21.5 i 0.7 9-12 95 M n-54 15.0 i 0.8 18.1 i 2.9 17.6 i 1.5 53 7 l-131 14.0 i 0.7 16.5 i 1.0 12.3 i 0.3 Cs-137 10.0 i 0.5 12.8 i 3.2 12.7 i 1.5 9-12-95 H-3 976 i 49 933 i 160 993 i 65 53 8 Sr-89 25.0 i 1.3 24.5 i 2.5 21.8 i 2.7 Sr-90 10.0 i 0.5 9.9 i C.9 10.0 i 0.5 12-12-95 Co-58 16.0 i 0.8 16.6 i 2.8 15.8 i 1.8 53 9 Co-60 15.0 i 0.8 18.1 i 3.0 17.2 i 1.4 l-131 19.0 i 1.0 22.0 i 1.0 16.0 i 0.3 12-12-95 53 H-3 685 i 34 720 i 130" 726 i 60 (1) Uncertainties are based on counting statistics and are reported at the 95% confidence coefficient. See Section 3-B. Re-analysis value I l 3-14 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS
Duquesne Light Company 1995 Annual Radiological Environmental Report Table 3-12. Quality Control Data - Independent Laboratory / Contractor /Ouality Control Laboratory Comparison Spiked Milk Samples (pCi/l) TABLE 3-12 QUAUTY CONTROL DATA INDEPENDENT LABORATORY / CONTRACTOR /QUAUTY CONTROL LABORATORY COMPARISON SPIKED MILK SAMPLES (pC1/I) Sample Identification Sample Type Independent ~ CONTRACTOR Date No. and Analyses Lab (1) ggg (9) M (1) Sr 89 51.0 i 3.0 49.0 i 2.0 45.4 t 1.9 Sr-90 20.0 i 1.0 23.0 i 1.0 18.5 i 0.7 3-14-95 l-131 50.0 i 3.0 49.5 i 1.0 47.0 i 1.6 52- 4 Cs-134 10.0 i 0.5 11.013.8 8.9 i 1.5 Cs 137 15.0 i 1.0 21.1 i 4.0 ~18.1 i 2.8 Sr-89 36.0 i 2.0 37.5 i 1.5 31.9 i 1.9 Sr-90 15.4 i 0.b 16.0 i 1.0 15.8 i 0.6 6-13-95 .0 i 1.0 25.0 i 1.0 22.7 i 0.4 52- 5 Cs-134 15.0 i 0.8 13.1 i 3.4 13.3 i 1.2 Cs-137 15.6 i 0.8 16.3 i 3.1 17.1 i 2.1 Sr-89 24.0 i 1.0 24.0 i 1.0 13.6 i 3.1* Sr-90 16.0 i 0.8 16.5 i 1.0 18.0 i 0.7 9-12-95 52- 6 1 i 1.0 20.0 i 1.0 W i 0.8* Cs-134 10.0 i 0.5 10.6 3.2 9.6 i 1.0 Cs-137 15.0 i 0.8 18.4 i 3.8 16.8 i 1.8 Sr-89 23.011.2 26.0 i 1.5 20.5 i 3.9 Sr-90 19.0 i 1.0 20.5 i 1.0 20.8 i 0.8 12-12-95 52j7 l-131 29.0 i 1.5 31.0 i 1.0 2f1 i 2.3 Cs 134 9.0 i 0.5 8.3 i 3.3 e.7 i 1.2 Cs-137 18.0 i 0.9 21.6 i 3.6 22.5 i 2.0 (1) Uncertainties are based on counting statistics and are based on the 95% confidence coefflctent. See Section 3-B. Section 3. ENVIRONMENTAL MONITOR!NG CONSIDERATIONS 3-15
Duquesne Light Company 1995 Annual Radiological Environmental Report
- 7. Pennsylvania Department of Environmental Protection Program The Pennsylvania Department of Environmental Protection (PDEP) also g conducted a surveillance program in the vicinity of the site. Samples of air, B river water, drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program. Results were compared quarterly in 1995.
B. Evaluation of the Quality Control Program Data The split and spiked sample program indicates that the Contractor and QC Laboratory are generally performing satisfactorily in accordance with " Criteria for l Comparing Analytical Measurements from NRC Compliance Office." Comparisons between the QC and Contractor laboratories are generally acceptable and j demonstrate a satisfactory performance by the DLC contractor. All media were in agreement in accordance with NRC criteria as listed in Inspection Guidance 84750-03 dated 12/04/90 with the exception of those media in Table 3-2 through l Table 3-12 identified with an asterisk (*). Comparisons are obtained by dividing the comparison standard by its associated uncertainty to obtain the resolution. The standard value is multiplied by the ratio values obtained from the following table to find the acceptance band for the result to be compared. Note that in the case where the counting precision of the standard yields a resolution of less than 4, a comparison cannot be calculated. Resolution Ratio l
<4 -
4-7 0.5 - 2.0 8 - 15 0.6 - 1.66 15 - 50 0.75 - 1.33 51 - 200 .8 - 1.25
> 200 .85 - 1.18 I
3-16 Section 3. ENVIRONMENTAL MONITORING CoNSIDERATloNS
1 Duquasna Light Company 1995 Annual Radiological Environmental Report B. Evaluation of the Quality Control Program Data (Cont.)
- Contractor Laboratory The Contactor Laboratory had a very satisfactory performance throughout the 1995 QC Laboratory Program. In the Independent Laboratory Program, with reference to the high quality spikes as reported in Table 3-11 and Table 3-12, excellent comparisons were achieved for all milk and water spikes. Re-analysis was required for the last H-3 in water spike of the year and for the strontium in water spike sample of June 13,1995.
In the QC Laboratory spike sample program, as reported in Table 3-6 and Table 3-7 for water and milk, there was one non-comparison. The non-comparison, spike water sample W-123 for gross beta was very close to comparison. The following spike sample for gross beta, W-127, compared. Split drinking water samples for gross beta also compared. Within the Contractor /QC Lab split sample program samples for feed and sediment are particularly subject to sample variability. One non-comparison was noted for pothssium-40 in feed and in sediment cobalt-58 and cobalt-60 were non-comparisons although very close to comparison.
- Quality Control Laboratory The QC Laboratory hac satisfactory performance within the Independent Laboratory Program. One resJt for 1-131 in milk was slightly out of comparison low in the third quarter and was Milowed by comparison for 1-131 fourth quartur.
Two non-comparisons for Sr-89 occurred in the third quarter, one in water and one in milk. In the fourth quarter, comparisons were achieved for Sr-89 in both milk and water. Based on all available QC program data, the data from the Contractor and QC - Laboratory's internal EPA Interlaboratory Cross Check Program, and comparisons with the PDEP, the Environmental Monitoring Program for 1995 is acceptable with respect to both accuracy and measurement. Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-17
Duquesne Light Company 1995 Annual Radiological Environmental Report C. Standard Requirements and Limitations for Radiological and Other Effluents The Beaver Valley Power Station is governed by rules and regulations of the E Federal Government and the Commonwealth of Pennsylvania. Effluent releases are g controlled to ensure that limits set by Federal or State governments are not exceeded. in addition, self-imposed goals have been established to further limit discharges to the environment. Beaver Valley Power Station is subject to regulations which include the Code (J Federal Regulations 10 CFR (Energy), Gaseous Discharge Permits for auxiliary boilers and diesel generators, PA Code - Title 24, Part 1, 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 /ODCM.
D. Reporting Levels A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in the Beaver Valley Power Station Technical Specifications /ODCM 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)
+ + . . > 1.0
~
Limit Level (1) Limit Level (2) There were no analytical results of environmental samples during 1995 which exceeded Beaver Valley Power Station reporting levels. , I Il I I l 3-18 section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS i
. __ _ _ _ = . _ ..
Duquesne Light Company 1995 Annual Radiological Environmental Report
- Section 4. MONITORING EFFLUENTS '
1 A. Monitoring of Liquid Effluents
- 1. Descriptico of Liquid Effluents at the Beaver Valley Power Station.
l . Most of the water required for the operation of the Beaver Valley station is taken from the Ohio River, and returned to the river, used for makeup to various plant systems, consumed by station personnel, or discharged via a sanitary waste system. In addition, well water and liquid effluents are discharged to the Ohio River using discharge points shown in Figure 4-1. Schematic diagrams of liquid flow paths for the Beaver Valley Power Station are shown in Figure 4-2,
- Figure 4-3, Figure 4-4 and Figure 4-5
- 2. Radioactive Liquid Waste Sampling and Anasy2 Program See Table 4-1.
i r
- 3. Results of Liquid Effluent Discharge to the Environment I i
See Table 4-2.
- j l
Section 4. MONITORING EFFLUENTS 4-1
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 4-1 Uquid Discharge Points to Ohio River
. I v Ver! .sg g v
$!_! IE8 Now s os.ys
. 0 8G E
^
^
s
- ss
,em w:!d Is - ta
-g lip
=!!
= r j2 -
- g!- 52 .. ~i8
-g r ~5 -
- .1 8-- gi ~
ng b !=g$ h_ v =
- n. + 2ay! W
- y d- 1951 '...; E a U -:E5 o ilh! 8
- -1 S j T l 0 2 ;@' T 5 5 s
^
-ser Es!. =
T iiEi !!55 0 n o 5
' E
't In '
_s T V a O ( [eiil iji i L ij E I il-E _i_ v: 5 s
,h - ho m& _ur, k.
' n _-
_E: _:a=
- jE' 5 lis iL'JL5 g , o w(o if-3 Y eg. 3l g
s gg3 8 l :En aus
*:5
.c is 22
- uI= -
8
- g!l 15l]'
Rw-s I. 1 l l 4-2 Section 4. MONITORING EFFLUENTS
iI Qc e"h (~gy* OOBuW4 g O C_ Dbo OOgg_ M
)
(
.'Omgeg ym 2 1
2oke ee c s a$e$' n E ,N G E N T R '56 1 DST TO N E I f L l J
/
S H' A Cy siuACDR pOWENT E S y guDL LAA E 0"t 1 A O RT RC
> se
/
h N W O D / W E E S i O K T S E L A A T B T S T R N W A N E D W E R Y A l u E W R R E T W O T U 4 L V I
,E A O
l T R E T f .,1 R f G R V C R' VWT T h P E A A E L O ,AE M t O f t e D T I T ST O W N S S O A A A MC C R J,w O L R S W A W C I 2 S T P 1 GSf 1R-A V - Nl S B SUE P M P V OS T B V i E BOY CS N H g R > N _T
,P
,R A
L C S E T A O ,e
,T W
TI A ,A O W E S R ,W L C R E F E NE t Y N Z ET R R E O I U GS E E S T A A RM T R h R R E
/
i A E E T R NE N M I D W A R E T ET GS E > ER , 1 S 1 G A W RW EA D RE ET ; P V T I N G TM L , B N T A N I
^ I F y N
U L T W - U A C L O 2-R U H D I C S W 4 C R A I C W O L E K B R C R U
$ A D R R B E W G M
E T E T v^ W
, V O I
F A E T S Y A W R N W O T G s P U S O Y t
'GN W O L 1 R O $, G l O A I E L M C S S L I
F B u O MP V O t R lv T T" P S O& B D'O C A L s" E I D E T
) C > g L T j A S
Y D I S O L O E F 2 T O L - gA P r F o O ' T STEA S OS T P YDSO S S 1 B TN O DIOS V SitP LF D S P et T S uFPA oft S B OF tS SOO E n B V OO CP D SOO $ 2E U ) r r R E -G 4R O S H E H 0 W 1A S A EG sR S H 04 E S SH W eA M s a 1 D PC VtS L H N N u R BD E E R C XK UA E TC SS Et TO E E R C Y RE AR E A MT t s o t n
-- A V
S ATN e RN s jN I j3 S,' PI j* j)' W)_5 O_yO g5= ". Eh~4OgzO m ?Cm24R. -f w I !
a 2! " E' E
- e 3
h Y c C O $ > h M O 3 , COOLING TOWER BLOWDOWN - BVPS.2 g A EVAPORATION ORFT E h l y BVPS-1 & BVPS-2 CCMSINED m BVPS 2 C m DISCHARGE POINT M/ ( CIRCULATING WATER
> COOUNG
( ""' k g g l , SYSTEMS M c) [ n m SERV 1CE WAYER 3 3 CIRCULATfMG WATER gg $ a
$_ o
, etevre enra.n=ce 4 eVPS-2 SAMTARY Z N WASTE TREATMENT g k ( man,,,,.. .
FLOOR DRAtNS sam 1Amy wa5 Test bQ BVPS-2 / O fA TO BVPS-1 -3
$ /\ ananacrws nnseas s evps n m onaownsTE ROOF DRAINS e CMCm am mEnnTMkRADwASTE NO O g O
WA ER COLLECTION
- FROM BVPS 1 DEMINERALIZER ,
FLTERED WATER FROM BVPS-1 s TREATMENT y
' (T1
- FROM BVPS-1 WATER SOFTENER O
< 3 S.()
O Z FROM MIDLAND s m me.m TO BVPS 2 9 g WATER PLANT > SERvtCE tNATER 3 3 mx 3
.+
x (D V O V A FIGURE 4 UNIT 2 WATER FLOW SCHEMATIC M
2! E STREAM STREAM FLOW COLLECTION, TREATMENT E. DISCHARGE t No. RATE 8vPS-2 COOLING C
- 1. CONT SUMP 40GPO HIGH-LEVEL LIQUID E VAPOR ATOR 8 0
- 2. ADE BLDG SUMP 200GPD WASTE TEST * "
DRAINS 50 GPM C ON EXCHANGER ; TANKS 2 m
- 3. LAB DRAINS 400GPD d b DF a 10 3,000 G AL
- 4. R.P. SA MPLES 35GPD BVPS-l q
, ,COQLIN G e a S. MISC. SOURCES - tower s.' (D 660GFD a , Blow 00wN e. LD STEAM D 15,000 GPM ya
- 6. Misc. SOuRC ES 40GPO CENERA1VR
^
NN -
}* [
, gypg.g g.2 3 7 SG PRE FILTER 10GPO TANKS 2 _
l BACK WASH 30,000 CAL ' COMeINED OISCHARGE 5
-O SO GPM POINT lU5 90 ROM TEST Q. h 5' m TAN KS 2 U
oy 14.500 GAL mo
~ "Y IT1 "
- 8. -CVCS LETDOWN 606PM l PURIFICATION ION EXCHAN6ER DEGAStFIER CS ION 500 # EXCHANGER BORON RECOVERY DORON EVAPOR ATOR$ 2 kO y O 8vPS-11 % -
DF : 10
/HR Drsio d' TANKS 2 195,000
-- IS GPM 103ALL ENCEPT I o3 a 'O GAL lor y gg
' SVPS-2"I $M PUNIFICAIION CS10N STEAM g
- 9. 60GPM
- YP -2 -
DF*to OEGAStFIER
/HR OF al0 Ow 0 N EVAPORATOR h g
..-> u 5 0
- 10. SvPS-l TURBtNE T.200GPO
." BLDG ORAINS E NOTES
- ENYlRON M EN T h I. INPUT TO BVPS 2 STEAM GENERATOR (EVPS-1 YARD a eL0wD0wN EvAr0RATOR l$ NOT USED DRAlNAGE BLOWDOWN AND ENVIRONMENT Q DURING NORMAL BASE LOADED OPERATIONS- DISCIIARGE PotNT) i h
m
- 2. IF RADIOACTMTYlS DETECTED. TURBINE BUILDING DRAINS CAN BE TRANSFERRED TO
? THE CHEh0CALWASTE SUMP AND TREATED AS $ LIQuio WASTE.
i m m
I e
? " E 3
s + Y r C O 2
*3 -4 c
S AM COLLECTION, TREATMENT, C. DISCHARGE E STR EA M AT BVPS-1 BVPS -I COOLING $
? TOWER BLOWOOWN su =
C Q l. CONT SUMP 40 GPD EVAPORATOR FEED PUMPS 15pOO GPM h cn
$ k
- 2. AUX BLOG SUMP 2OO GPO WASTE LIQUtp WASTE BVPS-2 S
f 3 TEST 100 GPM COOLING DR AINS < r WASTE , TOWER 3
- 3. MISC SGURCES 700 GPO TANKS 2 ION EXCHANGER TANKS 2 BLOWDOWN @O 7,$00 GAL DF 10 18,000 GAL p
- 4. R.R S A M PLES 35 GPD STEAM 0, g O
S. LAB DRAINS 400 G PD B WDOWN
- n F TANNS 2 BVP S-1 E -2 fu (O SO,000 G AL COMBINED m K CONDENSATE DEMIN 2,685 GPD l
(
- 6. RINSE WASTE COOLING TOWER
$O z-DISC ARGE O NO COLLECTION OR TREATMENT (2) ENVIRONMENT 8vPS-2 TUR8INE 7,
BUILDING DRAINS UCO GPO , (gypg.2 YARD DP41NAGE 3$ DISCH ARGE POtNT) gx Ei I I NOTES:
- l. NO STEAM GENERATOR BLOWOOWN IS DISCHARGED. D
- 2. TUR8tNE-BUILDING DRAINS ARE PROCESSED BY THE LIOulD $
WASTE SYSTEM UPON HIGH ACTivtTY. DISCHARGES TO BVPS- 2 COOLING TOWER i 8 LOWDOWN AND ENVIRONMENT l l l l l M M M
1 + - - - - m m -w TABLE 4-1 Radioactive Uquid Waste Sampling and Analysis Program y E_ LIQUID SAMPLING A St A D) g RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS ( Ci/ml)a
- o p p Principal Gamma E SE-7 Emitterst 5' Each Batchh Each Batchh l-131 1E-6 a
< u) p Dissolved and h m
8 Batch Waste Release M Entrained Gases 1 E-5 > One Batch /Mh 5 3 Tanksd (Gamma Emitters) g P M H-3 1 E-5 g gg Each Batchh Compositeb Gross Alpha 1E-7 [ P O Sr-89, Sr-90 SE-8 3 h*
-n Each Batchh Compositeb Fe-55 1E-6 h o
j m __. r Principal Gamma A W Emitterst SE-7 5 Grab Sampieg '~ j! mPosh I-131 1E-6 [ [@ Grab Samples M Dissolved and Entrained Gases hh B. Continuous 1 E-5 y 3g Releas se.o ( amma m tiers) q x M H-3 1E-5
- EL Grab Samplos 3 m Compositec Gross Alpha 1E-7 m
m d T3 A O Sr-89, Sr-90 SE-8 o
' 3 Grab Sampleg -" Compositec Fe-55 1E-6 C
o W - At least once per 7 days
$ M - At least once per 31 days @ O - At least once per 92 days g P - Completed prior to each release 9 ?
,E 5 w Jh N
Duquesne Light Company 1995 Annual Radiological Environmental Report TABLE 4-1 NOTATION
- a. The Lower Limit of Detection (LLD).
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released,
- c. To be representative of the quantities and concere -ations of radioactive ,
materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- d. A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then ,
thoroughly mixed to assure representative sampling.
- e. A continuous release exists when the discharge of liquid wastes is from a non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. Releases from the Turbine Building drains and the Auxiliary Feedwater Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd).
- f. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. This list does not rnean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLD's highe,- than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
- g. When radioactivity is identified in the secondary system, a discharge permit should be prepared on a monthly basis to account for the radioactivity that will i eventually be discharged to the Ohio River. i
- h. Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling will be performed by means of a grab sample taken every 4 hours during pump operation.
4-8 Section 4. MONITORING EFFLUENTS
1 Duquesno Light Company 1995 Annual Radiological Environmental Report Table 4-2. Results of Uquid Effluent Discharges to the Environment TABLE 4-2 RESULTS OF LIQUID EFFLUENT DISCHARGES TO THE ENVIRONMENT Effluent Type Results for 1995 Steam System The Steam System Blowdown was recycled when Blowdown practicable. Batch Routine planned releases of liquid effluents from the , Radioactive Beaver Valley Power Station were released in accordance I Waste Liquids with conditions noted in Section 6.8.6a of the Technical Specifications and Appendix C of the ODCM. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Annual Radioactive Effluent Release Report for 1995. Continuous Radioactive waste liquids were not discharged in a Radioactive continuous mode during 1995. Waste Liquids l l l l l l l Section 4. MONITORING EFFLUENTS 4-9
Duquesne Light Company l 1995 Annual Radiological Environmental Report B. Monitoring of Atmospheric Effluents
- 1. Description of Atmospheric Effluent Sources Beaver Valley Power Station (Units 1 and 2)
The Beaver Valley Power Station identifies isotopes according to Section 6.8.6a of the Technical Specifications, Appendix C of the ODCM 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, lodines, and particulates, g Figure 4-6 shows the gaseous radwaste system at Beaver Valley Power Station. E 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 Auxillary 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 Decontamination Building Vent located on top of the Unit 2 Decontamination Building.
- 4) The Waste Gas Storage Vault Vent located on top of the Uni! 2 Decontamination Building.
- 5) The Condensate Polishing Building Vent located on top of the Urit 2 Condensate Polishing Building,
- c. Unit 1 and Unit 2 shared release point;
- 1) The Process Vent located on top of the Unit 1 Cooling Tower.
These points are continuously monitored for particulates and gases. Grab samples are obtained on a weekly basis and are analyzed for noble gas gamma emitting isotopes. Grab samples are obtained on a monthly basis and analyzed E for tritium. Weekly continuous samples are obtained on filter paper and charcoal E cartridges. The filter papers are analyzed for particulate gamma emitting isotopes and gross alpha. Composites of the filter papers are analyzed monthly for Sr-89 and Sr-90. The charcoal cartridges are analyzed for 1-131,1-133 and 1-135. Figure 4-7 shows these gaseous release points. 4-10 Section 4. MONITORING EFFLUENTS
l l Ouquesne Light Company 1995 Annua! Radiological Environmental Report Figure 4-6. Units 1 and 2 Gaseous Radwaste System or
- "af!Uli!'.*idi" """ 1. . m=
1 1 codIN lme vast a unit a ll - raattfas Gal Gas CourREsset CourRDice ll . . . . k 4 sesas rann sanct tne (..__ . c....... gg nCat ram ., (..__) MCAV TAME oascent so NCAV THGt (- -) qi_,,_ ip j ._ o!!ans
<i_, ,_ ip qi_,,.. ip ! .
Decs, tem etcs, tee , A
<i_,,_iy 4;_1,_ i> .
.c ,
=
X .. stistlet att +S D
~
onept asemrtta Dh coonses sts IJactet >b
. .n. -n.. .,p a
ceNistseepft oncuen Peel th T.S.1 FIGURE 4 UNITS 1 AND 2 GASEOUS RADWASTE SYSTEM Section 4. MONITORING EFFLUENTS 4-11
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 4 7. Units 1 and 2 Gaseous Release Points
+ Ohio Rive' C ~~ -
Cl l I
- i m
l s x m\./ 7 s 1 N - J I 1
,l .,
i j_ - Unit 2 m Unit 1 l t_ ] 6 m e c3 l 1 s I 1XLIASI Pol #f & IISCRIPf!0N ILITit!01 1.Usit1: Ventilation Tent 2, tsit 1: Containment / SLC15 Tent 79 feet : 24 meters 154 feet : 47 seters
- 3. Unit 1 & 2: Process Test 65 feet : 145 seters
- 4. Unit 2: Tectilatics Tent 85 feet : 26 seters 1 7
- 5. Ocit 2:
- 5. Unit 2:
Costaicaest / SLC15 Test 154 feet : C neters Condeante Polisillag Builditg Test 80 feet : 24 esters g D
- 7. Unit 2: faste Gas Storage Taalt Test 80 feet : 24 meters i
- 8. Esit 2: Deccatasination Building Test 80 feet : 24 seters g FIGURE 4 UNITS 1 AND 2 GASE0US RELEASE POINTS I
4-12 Section 4. MONITORING EFFLUENTS
i . l Duquesne Light Company 1995 Annual Radiological Environmental Report
- 2. Atmospheric Effluent Treatment and Sampling )
l Beaver Valley Power Station (Units 1 and 2) i 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 j charcoal delay subsystem upstream of the overhead gas compressor where the i gas is chilled to condense most of the water vapor. Gases from the degasifier i vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and radioisotopes consisting of noble gases, particulates and radiolodines are also present in this system. The overhead gas compressor directs the radioactive gas stream to a gas surge l tank. Gas is periodically transferred from the Unit 1 or Unit 2 surge tank to one l of the three (3) decay tanks at Unit 1 or one of the seven (7) decay tanks at Unit l
- 2. After the decay tanks are sampled and authorization obtained for discharge, l the flow of the waste gases from the decay tanks (2 scfm) is rapidly diluted with about 1000 scfm of air in order to dilute hydrogen and radioactive effluent j 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 disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the Unit 1 cooling tower. The radioactivity levels of the stream are monitored continuously. l Should the radioactivity release concentration of the stream go above the l allowable setpoint, a signal from the radiation monitor will stop all flow from the -
Unit 1 or Unit 2 decay tanks being discharged. 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. Most areas in the Unit 1 Auxiliary Building are individually monitored for radioactivity prior to entering the common Ventilation Vent. These individual radiation monitors aid in identifying any sources of contaminated air. The normal exhaust is through the Ventilation Vent effluent pathway. This pathway is monitored continuously by several redundant channels of the Radiation Monitoring System (RMS) and is sampled periodically. However, upon a upper activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the Supplementary Leak Collection and Release System (SLCRS) and to the SLCRS Vent effluent pathway. Section 4. MONITORING EFFLUENTS 4-13
Duquesne Light Company 1995 Annual Radiological Environmental Report 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). l Each Unit 1 and Unit 2 filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type HEPA filters. The roughing filters remove large particulates to prevent excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the HEPA filters remove particulates and charcoal fines. Release points for Unit 1 and Unit 2 of e Beaver Valley Power Station are shown in Figure 4-7. Some of these release points discharge small amounts of radioisotopes consisting of noble gases, particulates and radiciodines. See Table 4-3 for Radioactive Gaseous Waste Sampling and Analysis Program. I I 4-14 Section 4. MONITORING EFFLUENTS l
T r - numme summm e e m l 1 TABLE 4-3 Radioactive Gaseous Waste Sampling and Analysis Program y Er GASEOUS SAMPLING OF LOWER M OF ANA I A ON (RD) g RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS ( Ci/cc) -
- D Principal Gamma =
- 1. Waste Gas P P 1 x 104 g.
Emiws9 Storage Tank Each Tank Grab Sample Each Tank N H-3 1 x 10-s e. .
< to ,
P p Principal Gamma
- 2. Conta,m ment 1 x 104 m Emitters 9 Purge Each Purgeb Grab Each Purgeb $
Sample H-3 1 x 104 c s
= c
- 3. Ventilation Principal Gamma 1 x 104 h Systemsh Mb.c.e Grab Sample Mb Emitters 9 g g j l
- a. Process Vent H-3 1 x 10--s gg g -a
- b. Aux. Bldg. Wd I-131 1 x 10-12 g j co Vents
- c. Containment Charcoal Sample I-133 1 x 10-10 d h wa Principal Gamma $ m -+
Vents
- d. Decon. Bldg. Particulate Sample Emitters 9 (I-131, 1 x 10-11 $ Sh Others) { [3 Vent y j,e 3y Bo
- e. Wcste Gas Continuousf Vault Vent Composite Particulate Gross alpha 1 x 10-11 y $x Sample k $
T f. Cond. Polish. 'U E O $ 3 Bldg. Vent Composite Particulate Sr-89, Sr-90 1 x 1011
$o
-" Sample A c 0 * **** ' ** Noble Gas Monitor 1 x 10-s a Beta and Gamma o j W - At least once per 7 days o M - At least once per 31 days Q O - At least once per 92 days y P - Completed prior to each release E a a 1 tn
i Duquesne Light Company 1995 Annual Radiological Environment:1 Report TABLE 4-3 NOTATION I!, I l
- a. The Lower Limit of Detection (LLD).
- b. Sampling and analysis shall also be performed following shutdown, startup, or l a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour period. This rec;uirement does not apply if (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- c. Tritium grab samples shall be taken at least once per 24 hours (from the appropriate ventilation release path) when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing or after removal from sampler.
Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
- f. The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Appendix C CONTROLS 3.11.2.1, 3.11.2.2 and 3.11.2.3.
- g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 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 higher than required, the ;
reasons shall be documented in the Annual Radioactive Effluent Release Report.
- h. Only when release path is in use. )
l I l l 4-16 secton 4. MoMToRING EFFLUENTS
Duquesne Light Company 1995 Annual Radiological Environmental Report
- 3. Results Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 6.8.6a of the Technical Specifications and Appendix C of the ODCM. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Annual Radioactive Effluent Release Report for 1995.
C. Solid Waste Disposal During Beaver Valley Power Stat.on normal operations and periodic maintenance, small quantitles of solid radioactive waste materials were generated such as contaminated rags, paper, plastics, filters, spent lon-exchange resins, and miscellaneous tools and equipment. These were disposed of as solid radioactive waste. The services of offsite processors were used to segregato, incinerate, and super-compact the waste. The volume reduced waste was then shipped for disposal. All containers used for packaging, transport, and disposal of radioactive materials met the requirements of the United States Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Shipments offsite were made in accordance with DOT and NRC regulations. Figure 4-8 depicts solid waste handling at the site. During 1995, 1,619 cubic feet of radioactive solid waste were buried offsite. Both units set record low disposal volumes for a refueling outage year. The shipments to the Offsite Processors and Disposal Facility contained a total activity of 500 curies. Industrial solid wastes were collected in portable bins, and removed to an approved offsite burial ground. No burning or burial of wastes was conducted at the Beaver Valley Power Station site. Section 4. MONITORING EFFLUENTS 4-17
Duquesne Light Company 1995 Annual Radiological Environmental Report I; Figure 4-8. Solid Waste Disposal Diagram RADIOACTIVE SOLID WASE DISPOS AL
> g s
Misc. Radioactive Compactor and y, g 1 Solid Wastes Drumming Station 4
'On OGOW i30 8e G.e mE g2 Spent Radioactive
. - - mm Spec.ial Sh.ipping Resin & Filters Casks & Containers
# a gg3 e
_.Q Q W CY TO'O" &8 FIGURE 4 SOLID WASTE DISPOS AL DI AGRAM i i I 4-18 Section 4. MONITORING EFFLUENTS
Duquesne Light Company l 1995 Annual Radiologicsl Environmental Report [ Section 5. ENVIRONMENTAL MONITORING PROGRAM
'A. Environmental Radioactivity Monitoring Program
[ 1. Program Description The program consists of monitoring water, air, soil, river bottoms, vegetation and { foodcrops, cows milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table 5-1. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results)
'{ are included in sections 5-8 through 5-l of this report.
5-B - Air Monitoring 5-C - Sediments and Soils Monitoring 5-D - Vegetation and Foodcrope ( 5-E - Cows Milk 5-F - Environmental Radiation Monitoring f 5-G - Fish 5-H - Surface, Drir' king, Well Waters and Pre :ipitation 5 Estimates of Radiation Dose to Man { l I Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-1
Y N m TABLE 5-1 a 63 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
-4 (n
es (7 m DLC - g g Type of Sample Sample Sector Miles Sampfe Point Description Sample Frequency p Analysis (b) 3 Points Y oz 1. Air Particulate 13 11 16 Meyer's Farm Continuous Sampling Weekly Composite (d) Gross Beta, (C) 1-131 C and Radiciodine 30 4 06 Shippingport, PA (S A) with sample Monthly Composite (d) Gamma -scan M
$ 48.1 3 24 Industry, PA collection at least Quarteriy Composite (d) Sr-89.90 h y weekly O_
r-C 32 15 08 Midland, PA (S S ) $ h 48(a) 51 10 5 18 5 80 Weirton, WV (a) Aliquippa, PA (S S } 5' 88L to Q 47 14 48 East uverpool. OH m W O 27 7 62 Brunton's Farm k > U h 28 1 8.7 Sherman's Farm [ O 298 3 81 Beaver County Hospital 3 c
= 3 a
h
- 2. Direct Radiation 30 13 4
11 06 18 Shippingport, PA (S S } Meyer's Farm Continuous (TLD) Quarterfy(k) Annually (k) Gamma-Dose # m[ g m 48 3 25 Industry. PA (Church) ~ g C ( 32 48(a) 15 10 08 16 5 Midland, PA (S.S } Weirton, WV (a) { a gh
-s 45.1 6 20 Raccoon. Twp, PA O
[ Kennedy's Crnrs. "1 6[ 51 5 80 Aliquippa, PA (S S ) $ $C 47 14 48 East Uverpool, OH
? m 70 1 30 West. Bvr, School O s c) 80 9 84 Raccoon Park % 5. O 81 9 39 Southside School g o' 3 82 9 7.1 Hanover Municipal Bidg 3 V 83 14 10 11 4.5 28 Mill Creek Rd Hookstown 3$
Ox 84 11 8.5 Hancock Co. Children Home U, 85 12 58 Rts. 8 & 30 Intersection 1 86 13 65 E. Uverpool Croxall House y 92 12 30 Georgetown Rd. (D 87 14 70 Calcutta Road 88 15 31 Mrdland Heights
]
3 89 15 4.7 Ohioville 90 16 5.2 Fairview School to 4 08 Shippingport Boro, PA 45 5 2.2 Mt Pleasant Church 60 13 3.7 Haney's Farm 93 16 13 Sunset Hills. Midland M M M
TABLE 5-1 RADIOLOGICAL ENVtRONMENTAL MONITORING PROGRAM Sample Point Description Sample Frequency Analysis (b) - Type of Sample Sa pie sector Miles , Points 24 McCleary Rd, lialite Williams Continuous (TLD) Quarterty(k) Gamma-Dose
- 2. Direct Radiation 95 10 28 8.7 Sherman's Farm Annually (k)
(continued) 1 71 2 58 Brighton Twp. School 72 3 32 Site of Former Logan School 298 3 81 Beaver County Hospital a 73 4 2.2 Potter Twp. School g 4 6C Comm. Col-Center Twp to 74 O 75 5 43 Holt Road 76 6 38 Raccoon Twp Schoot > 77 6 58 Green Garden Rd (Wayne's) $ 59 7 1.1 frons c 78 7 2.3 Raccoon Mun. Bldg EO C 27 7 62 Brunton's Farm g 79 8 4.8 Rt.18 & Rt.151 n3 Og 15 14 33 Georgetown 0- m Industry, PA O ft>
- 46. t 3 21 ~
Si 2 37 Pine Grove Rd and Doyle Rd Oh O 94 8 24 McCleary Rd, Wilson Surface Water 4 50 Arco Polymers Weekly, Intermittent Weekly Sample from I-131 gC
- 3. 49. t(a) 2.1 14 1.3 Downstream (Midland) J&L Composite Samples 0) Arco only m d 2.0 3 32 Station Discharge BVPS Cottacted Weekty d Gm %
~3 O 02 Downstream BVPS Outfall Weekly Grab Sampies O (n 2A 13 My Sample (d) Gross Mpha g 5 14 48 East Uverpool (raw water) Only Gamma-scan O3 Quarterty Composite Co40, H-3 g 3
Daity Grab Sample O m Only . Collected d WeeklyG) E ; h O 4. Groundwater 13 11 1s Meyer's Farm Quarterty Quarterly Gamma-scan, Gross Beta, Gross Alpha, [ n 14 11 28 Hookstown, PA { Georgetown, PA H-3 0 15 15 3.3 m Shipp6ngport Boro A 11 3 08
$ Gamma scan,1-131 intermittent (e) Sample Weekly Compostte of k 5. Drinking 4 14 1.3 Midland, PA (Midland Water Collected Weeldy Dany Sample (d) r Treatment Plant)
Mnth. Composite (d) Gross Alpha,
@ 48 East uverpool, OH (East Gross Beta a 5 14 Uverpool Water Treatment Quart. Composite (d) H-3, Co40, Sr-89, 90 O
E Plant) , Weekly Grab Sample b 0.2 Downstream BVPS Outfall Semiannual Semiannual Gamma-scan,
] 8. Shoreline 2A 13 Gross Deta Sedtment Q 3 13 0.2 Vicinity SAPS Discharge Gross Alpha a Uranium Isotopic > 49 3 32 Upstream Side of Sr-89, 90 Montgomery Dam (a) 50 13 82 Upstream side of New Cumbertand Dam g
M i i
e TABLE 5-1 K RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 6 3 58 Sample Point Description Sample Frequency Analysis (b) Type of Sample Sa le Sector Miles p, g Points h 7 M!!k 25 to 21 Saaright's Dairy WhyW Weekly sample from 1-131 C Sear'ght's only Bsweekly(9) when Biweekly (grazing) Gamma-scan animals are on Monthly (indoors) Sr-89. 90 g *
- pasture. monthly at 1-131. Cs-137 r-96(a) 10 10 3 Windsheimer other times. y 7 62 Brunton's Dairy (h) to 27 Monthly W z Nicol's Dalry(h) Monthly Gamma-scan Sr-89 82 R
O 29 3 80, 3-131. Cs-137 > m M g
- OvPS Technical Specification Table 312-1 requires tivee (3) dairies to be selected on basis of hachest potential thyrood dose using milch census data See Section 5-E for y spectftc tricat: ens sampled g
, O n 2A 13 02 Vicimty of BVPS #1 Semiannual Composite of edible Gamma-scan Q
O C. Fle Station Discharge parts by species (I) on edible y(C m 49(a) 3 47 Upstream Side of portions O- CD
> Og C Montgomery Dam _
CD 9 Food Crops Annual at harvest if Composite of each Gamma-scan o (Shipp ) 10 4 08 (Three locations within available sample species 1-13t on green 6[ (Georg ) 15 14 33 5 miles Selected by leafy vegetables 2O 0 (indus ) 46 3 25 Company) mK 48(8) 10 16 5 Weirton WV mo
<O 10 Feedstuff and 25 10 21 Searight's Dairy Farm Monthly Monthly Gamma-scan :i' g Summer Forage Ouarterty Quarterly Composite Sr-90 0 "O 11 Soil 13 11 16 Meyer's Farm Every 3 years (1994, 1997, etc )
12 Core Samples 3" Deep (3" Dia. Gamma-scan Sr 90 3$ CD *< 30 4 06 Shippingport, PA 46 3 2.6 :ndustry. PA at each location Gross Beta -, Gross Alpha D 32 15 08 (North of Site) Midland (approx 1(f 48(a) 10 16 5 weirton, WV radius) Uranium Isotopic y 80 Aliquippa. PA (D 51 5 47 14 48 E. Uverpoot. OH ] 27 7 62 Brunton's Dairy 3 22 8 03 South of BVPS Site 29A 3 83 Nicol's Dairy 12 Precipitation 30 4 06 Shippingport. PA Weekly grab samples Monthly Composite Gross # 47 14 48 East Uverpool. OH when available of grab samples r-scan 48 10 16 5 Weirton. WV Quarterly Composite H-3. Sr-89. Sr-90 m M M M M M m
r Duquesne Light Company l 1995 Annual Radiological Environmental Report TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued) Notes: [ (a) Control sample station: These are locationc which are presumed to be outside i the influence of plant effluents. (b) Typical LLDs for gamma spectrometry are shown in Table 5-4. (c) Particulate samples are not counted for 2: 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is > 10 times the yearly mean of control samples. (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location. (e) Composite samples are collected at intervals not exceeding 2 hours. (f) Weekly milk sample from Searight's Dairy is analyzed for I-131 only. (g) Milk samples are collected bi-weekly when animals are in pasture and monthly at other times. [ Assume April- October for grazing season (pasture),] (h) The milk samples from Brunton's and Nicol's Dalries are collected once per month. (i). The fish samples will contain whatever species are available. If the available sample size permits, then the sample will be separated according to species and compositing will provide one sample of each species. If the available size is too small to make separation by species practical, then edible parts of all fish in the sample will be mixed to give one sample. (j) Composite samples are collected at intervals not exceeding 2 hours at locations 49.1 and 2.1. Weekly grab samples are obtained at locations 49 and { 2A. A weekly grab sample is also obtained from ' daily composited grab samples obtained by the water treatment plant operator at location 5. f (k) Two (2) TLDs are collected quarterly and annually from each monitoring location. Additional Notes: Sample points correspond to site numbers shown on maps. All 1-131 analyses are performed within 40 hours of sample collection if possible. ' All air samples are decayed for 72 hours before analyzing for Gross Beta. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-5
Duquesne Light Company 1995 Annual Radiological Environmental Report
- 2. Summary of Results All results of this mea'toring program are summarized in Table 5-2. This table is prepared in the format specified by NRC Regulatory Guide 4.8 and in accordance with Beaver Valley Power Station Operating License, (Appendix A, Technical Specifications /ODCM). Summaries of results of analysis of each media are discussed in Sections 5-B through 5-H and an assessment of radiation doses are given in Section 5-l. Table 5-3 summarizes Beaver Valley Power g Station preoperational ranges for the various sampling media during the years l 1974 and 1975. Comparisons of preoperational data with operational data indicate the ranges of values are generally in good agreement for both periods g of time. g Activity detected was attributed to naturally occurring rad;onuclides, BVPS effluents, medical procedures, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the lower limit of detection (LLD).
The conclusion from all program data is that the operation of the Beaver Valley g Power Station has resulted in insignificant changes to the environment. g
- 3. Quality Control Program The Quality Control Program implemented by Duquesne Light Company to assure reliable performance by the DLC contractor and the supporting QC data are presented ard discussed in Section 3 of this report. The lower limits of detection for various analysis for each media monitored by this program by the DLC Contractor Laboratory are provided in Table 5-2 and in Table 5-4.
I I I 5-6 Section 5. ENVIRONMENTAL MONITORING PROGRAM
, c-- - m c- .m e--, e--- c. . - n n m m - - - - -
ENVIRONMENTAL RADIOtJOGICAL MONIIDEING PROGRAM
SUMMARY
Name of Facility Deaver Vallev Power Station Unit 1 and 2 Docket No. 50-334/50-412 vi Incation of Fad 11ty BeaYcr. Pennsylvania Reporting Wriod Annual 1995 y (County, State) k.. Analyste and Immer IA-tt Number of 3 Medium of Pathway Total Number of AR Indicator Imcatanns ipcation with Higtheat Annual Mean Contml Imcationa Nonmutine 3 m Sampled efAnalysto Detection " Dan (0 Name "Mean (f) "Mean (O Reported g e
" Range Distance and Directions " Range " Range Mesourements'" g W (Unit of Mesourement) Perfornied (1.I D) m Weirton, WV No. 48 y
{ Air Parttrth Grose (57.0) 2.5 17(520/520) 48, Weirton. WV 18(52/52) Same as 0 0 5 and Radletodine Beta (5.4-41) 16.05 mi SSW (8.3-41) high location g g 2 -O p(10-3 pct /Cu.M.) Sr-89 (40) 5 11D -- -- - - 5 mj T Sr-00 (40) 0.2 UD -- -- -- - j [C. G 3 o6o U 1-131(520) 40 11.D -- -- -- - 3
;u 6C Gamma (120) $ " C.a c__ m -+
g Be-7 40 138(119/120) (73-202) 298, Beaver Cty Hosp. 8.1 ml NE 143(12/12) 139(12/12) (94-202) (96-195) O [ g (Q gg o $ sV
, K-40 20 15(10/120) 27. Brunton's Dairy 6.2 mi SE 24:2/12) 24(3/12) 0 -
3$ Ox (5.4-52) (20-28) (9.4 -52) . s k Others Table V.A. 11D -- -- -- - - N 0 m z 'O C O m z a r-C O z o 50 z O h
- Namfnal Lower Limit of Detecuon (LLD) y " Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectned Incations is Indicated in parentheses (Q
'" Nonmuttne reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power station Spectncations .
g Y s
Y co tn k _, 8
!a ENVIRONMf*NTAL RADIOIDGICAL MONTIURING PROGRAM St1MMARY 6 E
Name of Facility Beaver '/allev Power Station Unit I and 2 pocket No. 50-334/50-412 m o" location of Fadlity Beaver. Tuomb rta Reporting Period Annual 1223 ro 2 (County. Statel r 2
-4
' Analysts and lower 1.tmit Number of f Medium of Pathway Total Number of All Indicator imentions Imention with Hishest Annual Mean Control locations Nonroutine a g e o Sampled ofAnalysts Detection " Mean (0 Name "Mean (0 "Mean (0 Reported if (Unit of Measurement) Performed (1.1.D) " Range Distance and Directions" Range ** Range Measurements"* $ Weirton, WV No. 48 y o 3 2 84. Hancock County 0.19(4/4) 0 3 z External Radtauon Camma (45) 0.05 0.18(180/180) 0.22(4/4) Children's llome (0.20-0.23) (0.18-0.19) i m (mR/ day) (180 quarterly) (0.13-0.23) 8.5 mi SW @O
- U.8 8
m Gamma 0.05 O.17(44/44) 29. Beaver Cty Hoep. 0.2 0(l / 11 0.I8(l/1) O gc-g (44 annuaD [0.13-0.20) 8.1 mi NE - -- g.g E5 Er su o~ Feed and Forage 1 131 (12) 0.01 IID - -- One Sample - =r location m~ (pct /g) I j (dry weight) 0 Eg W O Sr-90 (4) 0.003 0.34(4/4) -- -- - (0.061-0.20) Of aa Gamma (12) $* E De-7 0.3 2.8(5 / I 21 -- -- - 0 - (0.98-3.9) :D l m l K-40 0.5 21(12/12) -- -- -- 0 32 (9.4-34) Th-228 0.08 0.28(1/12) -- - -- 0 Others Table V.A. 11D - -- -- - l Nominal Lower Limit of Detection (LLD)
" Mean and range based upon detectable measurements only. Fraetton of detectable measurements at spectaed locations is indicated in parentheses (f)
'" Nonrnuttne reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Fbwer Station Specificatkms .
1 M M M M M m m
-a r m m .m_ r7 m_ m r, r, o rv .. r~m .m e- , m r- , m e,
.. r-1 ENVIMONMENTAL RADIOIDGICAL MolG10HING PROGRAM
SUMMARY
m tT Name of Factitty Bummr VaBey Peser Stataan Undt I and 2 Docket No. 50-334/I50-412 6 1mcation of Facalty Beaver. I%nnsylvania Reporthq Period Annual 1995 (County Statel Analpean and Lower Limit Number of Medium of Pathway Total Number of AllIndrator Imattens Incation wah Highest Annual Mean Control Imcations Nonroutine a Samoted ofAnalysis . Detection " Mean (0 Name "Mean 10 "Mean 10 Reported e (Unit of Measurement) Performed it1D) * *Ra nge Distanm and Directennn " Range " Range Measuremente*" Montgomery Dam No. 49 8 p. 3 Flah Gamma (8) s (pCs/g) K-40 0.05 3.0(8 / 81 02A. BVPS Discharge 3.1[4/4) 2.O(4/4) 0 y twet weight) (2.2-4.01 0.2 me w (3.0-3.Il (2.2-4.01 -O Others Table V.A. IID -- - - - 2.5 W Q. _ (D c g.- nc
=c
~r IT1
- 3O ui io R' 03 on n
3 N 3 m4' 3 m . I - U " z 8 .C
' V m O h ?
e O Z
-4 0
2 z O N b
- Nominal Immer Larnit of Detection (IlD) y "
Mean and range based upon detectable measurements only. Tracthm of detectable measurements at spectRed locations is indicated in parectheses (Q g teoneoutine reported measurements are defhied in Regulatory Guide 4.8 IDecember 1975) arul the Beaver Vallcy Puwer Station Spec!Dcathms . Y' e
Y a O 9 ENVIRONMEPTTAL EADIOLOGICAf_ MONITORING PROGRAM
SUMMARY
CT Y ~ (D g Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50 334/50-412
< T m
5ii lomtlen of Facility Beaver. I'umniv=-a Reporting Period Am=1 1995 (County State) Q C E Number of y Analysis and lower IJmtt r- Medium of Pathway Total Number of All Indicator locations location with Ilichest Annual Mean Control locallom Nonroutine a o c Sampled ofAnalysis Detection " Mean (0 Name "Mean (0 "Mean (O Reported Q (Unit of Measurement) Performed (t.I.D) "Ra nge Distance and Directions " Range " Range Weirton, WV No. 48 Measurementa m $ 4 y Food and Carden I-131 [4) 0.006 LID -- -- -- - a Q 3 y Crepe (pCl/p o (wet, weighy Gamma (4) @O v K-40 0.5 2.4(4/4) 4G. Industry Ch. Area 2.8(1/1) 2.2(1/1) O aj 2 b" 2.6 mi NE (2.1-2.8) 9.c(D m E Others Table V.A. 11D -- -- - - 0E q0
- wc 2C 7
m~ 3
- 5. o O
o3 s 'O 3$ mx 3 EL x to D o 3 Nominal Lower Limit of Detection (LLD)
" Mean and range based upon detectable measurements only. Fraction of detectatile measuremmts at spectned locations is indicated in parentheses (!)
* *
- Nonrouttne reported measurements are denned in Heguilatory Gukte 4.8 (MARCl! 1975) and the Deaver Valley Ibwer Station Spectftcattons .
E '. E E E
IillIIllll ljlj li!I 2 )j j, l l ji ,i ' 1 l1Iiii1 l,l 5cm$m r6-: O3.g $% at*Co n. h C M0EO_OU O m.'S'O 3O3 mm O 2 3 E(D Ym "s t n e e ) f oide nm f ( s rt - - O 0 0 - e euter s e boru ros ht . mnpa 7 ns uoe e 2 en NNRM . r o ait o pa s N c n y ) int i o0 r ) 9 )0 de t c i i a 0 13 ep t a ( /5 t nge D 1) 91 aS c /7 c o an n 1 - i n l o 02 (0 l rao ea t - 1 - t2 62 6 -
- ti t lMR o n 2 Dl a
"" G.1 st 2 r u 3 1 t r 1( 1(
1 i S 4- n B I s r o ) n e 0 C 2 )0 t ew 5 Q
)
13 tab Y / 5 2 R 4 9 9 n( a e 1)
/7
/7 21 2) luy cI A 3 e ng 1 - 1 tk M
3- 1 M an ea 24 (0 5
/ sl M 0 l a .MR 1 -
(3 3 0 1 1
- fea l v U
5 u n l a"" u 21 3( 5 3 1( 1 0. ~ 8 tcr ee pv S o n n sa N A n t e M t A s aD A e d n se R k o t s o th G c t r e u ) ) ) nt o V c a a a e O D h c e ( ( ( md R l g i i r y y y e n P l D r r r ra 2 ni f i a i a i a u1 s5 G i t r h d D D D a7 N r r o t i n e9 I a p w a y y y m1 R e e r T n
)
t I R n o c r e r e e er l e f T t ti e n F F F bb N i n a a mt a . . . tam O U t c ai s 2 2 2 ce ec m 0 0 0 M n n.)e IND - - 1 1 1 t e eD o h ta s d( w L i t v t f A a n o8
-o S o C t S u y. i )
n4 3 io e I i t G e t a )
- 3) td D r n r m 0 3 10 ci au I
O I P
- eC r o v (
u I r o ( ne ag 3 1)
/7
/3 37 31
)
3 3 FrG y w D A R L l l y e a V_ D a e ty t n die** n en Ma R DD I I 34 3-16 19 30 2( 1 - (0 2 7 18 3 1 1
/
1 (
- 0. ~~ D 8 J lyot na
.r ol u sg A
T r I I I 1 1 I t e nR e A l l e N v a A mn m E M N O B e y C J" r. L t i i m no i e rd ue sn ai i R t i o .ft)ocD 2 e fe I li c s eL 0 2 0 0 A. md V a t a m tL e 1 0 0 V ) Dee N F c e l r m E f o l e o l db
~
r e D(
) ) )
)
3 3 1 1 l b T a Lba [La nen t s ot e ct m n 6 3 3 ie N a a us s ym mie sd 6 1 3 13 1 1 ( t cdm e nr e iNl ( ( ( a t eou 7 s lyl ar s D ps 9 0 m 3 r a nfo m0 uae 1 3 8- 9 1 e f atAr nof e 1 r r a -4 s
- ht odm AT oP -
C K C e 1 S S O t sd
) ima e t
n Abe i. I e en c y rg am wa u h w er mr e t u s idn Pead ae y r a nit l au fl o pM i a n o inr m D man oeo mfao l) t a NMN N iuS t kt / o de i n liC C * *
)
- M U( M (p (
a F E5 P mz OZ zhr CO24OEzO 38oy aa l 1li il
Y.a' M tn 5 S ENVIRONMENTAL RADIOLOGICAL MONTTORING PROGRAM SifMMARY [ cr P Name of Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50-412 g m Z j 1.ecation of Fadlity Beaver. Pennsvivania Reporting Period Annual 1995 0 (County, Statej x kz Analysts and lower Limit Number of Medium of Pathway Total Number of All Indicator Incations Imcation with 11tchest AnnEalllCam Contret imenilana Nonroutinc
> Sampled ofAnalysts Detection " Mean (0 Name "Mean (0 "Mean (0 Reported r- (Unit of Measurement) Performed ILID) " Range Distance and Directions " Range "Ra n ge Mea srements"* a Montgomery Dam No. 4's 8 Z
g Sediment Gross (6) 0.3 13(6/6) 2A. DVPS Discharge 16(2/2) 9.4(2/2) O > 3 m (pct /g) Alpha (8.7 17) 0.2 mt. W (14-17) (8.7- 10) z (dry weight) e O 24(2/2) EOc Gross (6) 0.1 32(6/6) 2A. BVPS Discharge 40(2/2) O
] Beta (19-43) 0.2 mt. W (37 43) (19-28) y#
m 8, Er-89 (6) 0.2 11D -- -- - -
- c. 5
> 0 un C Sr-90 (6) 0.04 0.037(2/6) 50. Upstream 0.046(1/2) IID 0 gG3 (0.028-0.046) N. Cumberland Dam -- c 8.2 ml W 5' C Camma (6) Eo Be-7 0.2 1.7(I /6) 2A, DVPS Discharge 1.7(1/2) IID 0 m3
-- 0.2 ml. W -- 3
- 5. Og K-40 0.5 l't(6/6) 2A. BVPS Discharge 12(2/2) 12(2/2) 0 g3 (10-14) 0.2 mt. W (11-13) (10-14) 3 o 3*
Mn-54 0.03 0.42(1/G) 2A, BVPS Discharge 0.2 mi. W 0.42(1/2) IID 0 mM 3 m Co-58 0.2 2.3(2/G) 2A, DVPS Discharge 2.3(2/2) IID 0 (1.2-3.4) 0.2 mi. W (1.2-3.4) y Co-60 0.2 3.9(2/6) 2A, BVPS Discharge 3.9(2/2) IJD 0 A (l.5 6.3) 0.2 mi. W (l.5-6.3) .~1 Cs-137 0.02 0.28(6/6) 50. Upstream 0.48(2/2) 0.17((2/2l 0 (0.14-0.83) N. Cumt,criand Dam (0.14-0.83) (0.1G-0.19) 8.2 mi W Ra-226 0.1 2.4(6/6) 2A. DVPS Discharge 2.6(2/2) 2.4(2/2) 0 (l.4-3.2) 0.2 mt. W (2.3-2.8) (l.7-3.2) Th-228 0.02 1.l(6/6) 2A. BVPS Discharge 1.3(2 /2) 1. l(2/2) 0 j 1 (0.86- 1.3) 0.2 ml. W I1.21.2 (0.86- 1.3)
.
- Nominal tower Limit of Detection (11D)
" Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled lucations is Indicated in parentheses (f)
"* Nonroutine reported measurements are defined in Regulatory Guide 4 8 (December 1975) and the Beaver Vaticy Ibwer Station Spectftcations .
l
ENVIRONMENTAL RADf0fBCfCAL MONTTORING PROGRAM StfMMARY ' h a co Name of Fact 11ty Beaver Vallev Power Station Unit 1 and 2 Dnr1 ret No. 50-334150-412 01 Location of Faditty Beaver. Pennsvivanta Reporting Period Annual 1995 y (County, State) Number of Analysts and Imwer IJmit Medtum of Pathway Total Number of All indtrator forations location with 11tchest Anmini Mean Contruf fmcations Nonroutine Reported Detection " Mean (f) Name "Mean IO "Mean ID Sampled of Analysts (Unit of Measu.m..s,.t) Performed (LLD) **Ra nge Distance and Directions " Range "Ra nge Measurements"* g Montgomery Darn No. 49 to on
<0.3 0.96(2/6) 2A. DVPS Disc! arge 0.96(2/2) LID 0 g Sediment Sb-125 a (pCl/g) (0.88-1.0) 0.2 mL W (0.8ft4.0) c (dry weight) 2A. BVPS Discharge 0.93(1/2) LID 0 "O Ag 110M 0.1 0.93(1/6) 0.2 ms. W -- mj
- GC .m Others Table V.A. IID e =5 nC
=o
~~ "T (T1 "
3 () un S. O R 0 3 n 2 O 3 gW P E k
=
S 2 8 z (D
'O C O m
z 3 5 r-E O 2_ -4 0 i!! z O 8 $
- Nominal Immer Limit of Detectenti (f.LDI _
C " Mean and range based upon detectable measurements only. Fraetton of detectable measurements at specified locations is Indleated tri parentheses 10
*" Nonrouune reported measurements are defined in Itegulatory Guide 4.8 (December 1975) and the Deaver Valley Power Station Spectftcations .
Y 14
Y .a A w B 5 ,b ENVIRONMENTAL RADIOLOGICAL MONTIURING PHOCRAM StJMMARY [ CT Name of Facility Ikaver Vallev Power Station Unit 1 and 2 Docket No. 50 334/50-412 5 E location of Facility Beaver. Pennsylvania Reporting Period Annual 1995 (County, State) z C z Number of N Analysts and inwer Limit ' r- Medium of Pathway Total Number of All Indiator locations Imcation with flichest Annual. Mean Control "Mean locations (O Nonrouune Reported
^
Sampled of Analysts Detection " Mean (f) Name "Mean (f) g e $ "Ra nge Distance and Directions " Range " Range Measurements"* LD z (Unit of Measurernent) Performed (LI.DI 4 > 3 B 04. Mkiland. PA 0.71(38/52) -- 0 Drinking I-131 (104) 0.5 0.63(71/104) e 2 (0.23-1.5) 1.3 mi WNW 10.2 5-1.51 o Water m
~U (pct /1) 5 Cross (24) 0.6 [ID -- --
"c 8o b" Alpha Oe 23
> 05. E. Liverpool. Oli 4.5(12/121 -- 0 6$
c cross (24) Beta 1 4.3(24/24) (2.0-7.3) 4.8 mt WNW (3.2-7.3) gg o EC Camma (104) mo
~
Others Table V.A- IID -- -- - - m Sr-89 (8) 1.5 11D -- -- -- - koO
'3 O y Sr-90 (8) 0.5 IID --
3* co-60 (8) (a) I 11D -- -- - - m4 o 11-3 (0) 100 11D -- -- -- E.- D m V O A (a; Co-60 analyzed by higi sensitivity method.
- Nominal tower Ltmtt of Detection (LLD)
' Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses til
"' Nonroutine reported measurements are defined in Regulatory Cukje 4.8 (December 1975) and the Desver Valley Tbwer Station Specifications -
M m m g g
M M I M M M ' M' -
-4 ENVIRONMEffrAL RADIOLOGICAL MONFIDRING PROGRAM
SUMMARY
02 CT Name of Facility Beaver VaBev Power Stattan Unit 1 and 2 Docket No. 50-334/50 412 m~ Incation of Fact! sty Beaver. Pennsylvania Reporting Period Annual 1995 Y' m (County. State) t Analyt.is and Lower L!mit Number of Medium of Pathway Total Number of AH Indicator Locauons location with IIuhest Annual. Mean Control locations Nontoutine a Sampbt ofAnalysts Detection " Mean (0 Name "Mean (f) "Mean (f) Reported to i (tInit of Measurement) Performed (1.LD) "Ra nge Distance and Dirretion, "Ra n ce Georgetown. PA No. Ib
" Range Measurements"* $ l y
Groundwater Gross (14) 2 IID -- -- -- - 5 (pC1/D Alpha C EO C Gross (14] I 4.7(13/14) 11. Shippingport. PA 5.6(4/4) 2.2(4 /4) O m Beta (1.6-7.8) 0.8 mi NE (4.3 7.8) 11.6-2.4) cu E Be Gamma (14) O_y O o Others TableV.A. IID - -- -- - C._, oC 11-3 (14) 9 ;- IID -- -- -- - Er m-1 sn 3
- g 5. O O l5
,3 0 3 T3 3 ! -* BE O X .m 2 3 'x 55 E 'Q D c G m V z O r-C D E o 50 z O v a b
- Nominal lower Limit of Detection (LU))
y " Mean and range based upon detectable measuren.ents only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
'g "* Nonroutine reported encamurements are defined in Regulatory Cutde 4.8 [ December 1975) and the Beaver Valley Power Station Spectitcations .
a Ul
Y a e m 0 ENVIRONMENTAL RADIO 1DGICAL MONITORING PROGRAM
SUMMARY
[ er Name of Fadlity Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 E m locauon of Faellity Beaver. Pennsvivanta Reporting Period Annual 1995 [ o (County. State) z c E Analpis and lower Ltmit Number of -4 Medium of Pathway Total Number of AH Indleator Locations location with IItchest Annual. Mean Csntrol Locations Nonroutine , f of Analysis Detection " Mean (0 Name "Mean (0 "Mean (O Reported e g Sampled " Range Mea surement s*" W "Ra nge Distance and Directions " Range O (Unit of Measumnent) Performed (LLD) Wetrion. WV No.48 io Water Gross (36) 1 9.5(34/36) 47. E.1Jverpool. OH 13(10/12) 9.4(12/12) 0 $ 4.8 mt WNW (1.2-47) (1.6-31) c z Preetp!tauon Beta (1.2-4 71 Eg 0 (pCl/l) mc
- o Camma (36) mp g O- a x 48. Weirton. WV 114(9/12) Same as high 0 om C
Be-7 40 100(26/36) (50-346) 16.05 mi SSW (54-346) location oy to K-40 100 98(2/36) 47. E. Liverpool Olt 134(1/12) 62(1/12) 0 6C (G2-134) 4.8 mi WNW -- -- EC Othern Table V.A. LID -- -- -- - md 3 Sr-89 (12) 2 11D -- -- -- - 5O o o3 pV Sr.90 (12) 0.5 UD -- -- -- - B* 11-3 (12) 100 420(2/12) 30. Shippingport. PA 420(2/4) UD 0 mM (250-590) 0.6 mi ENE (250-590) 3 E x to V O A
- N.antnal lower Limit of Detecuan (LLD)
' Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locauons is trulicated in parentheses (Q
"* Nonmuttne reported measurements are defined in Regulatory Guide 4.8 (December 19751 and the Denver Valley Power station specincattons .
M M M M M M
ENVIRC:-^7TAL RADIOIDCICAL MONTIURING PROGRAM SUuuaqy [ rr Name of Facility Beaver Vallev Power Station Unit 1 and 2 Docket No. 50-334/50-412 m Incation of Facility Beaver. B -- le-- h Reporting Period Annual 1995 (County. State) Analysts and Lower LAmit Number of Medium of Pathway Total Number of All Indicator Locations location with liighest Annual Mean Control Imattena Nonroutine , Sampled ofAnalysts Detection " Mem (0 Name "Mean (0 **Mean (f) Reported co , Distance and Directions " Range ** Ra nge Measurements"* to (Unit of Measurement) Performed (LLD) ** Ra nge
- Upstrcr.m - ARCO Chemical No. 49.1 Surface Water 1-131 (52) 0.5 0.56(22/52) 49.1. Upstream. ARCO one sample 0 $
(pct /l) (0.21-1.1) Chemical locauon c 5.0 mi ENE Eg Cross (48) 2 1.8(1/48 2.1. J&L Steel 1.8(1/12) 11D 0 45a -- 1.3 mi WNW -- O. o O to r
-3 02A DVPS Discharge 7.0(12/12) 3.7(12/12) 0 o Gross (48)
Beta 1 4.9(48/48) (1.7-11) 0.2 mt W (4.3-11) (1.7-5.9) o* oC Camma (48) E C, m~ Others Table V.A. IID -- - s
- 5. g m O g Sr-89 (16) 2 IID -- -- -- -
g3
- g 3 o
- !a Sr-90 (16) 0.5 IlD -- -- -- -
3g m (D 3 x Co-60 (16) (a) 2 IID - -- - .g tu 950(2/16) 02A. DVPS Discharge 950(2/4) 0 100 y o H-3 (16) 2 (200-1700) 0.2 ml W (200-1700) c o O z A
- (a) CW analyzed by high sensitivity method.
E O , 2E 'O
--M Z
O 3 'h .m . " Nominal Lower 1.imit of Detecuan G.LD) Mean and raryte based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) { *" Nonrouttne reported measurements are defined in Regulatory Culde 4.8 (December 1975) and the Beaver Valley Power Station Specifications . V' _a N
Duquesne Light Company 1995 Annual Radiological Environmental Report Table 5-3. Pre-operational Environmental Radiological Monitoring Program Summary TABLE 5 3 PRE OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station D acket No. 50-334 Location of Facility Beaver Pennsylvania Reporting Level CY 1974 - 1975 (County, State) PRE-OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 1975) Medium or Pathway Allindicator Locations Analysis and Total Number Lower Limit f Analysis Performed of Detection LLD Mean, (f) Range (Unit of a u ement) Sediments Gross Alpha (0) - - pCi/g (dry) Gross Beta (33) 1 18 33/33 5 - 30 Sr-90 (0) - - l U-234, 235, 238 (0) - - E Gamma (33) - 13 33/33 2 - 30 K-40 1.5 13 33/33 2 - 30 Cs-137 0.1 0.4 21/33 0.1 - 0.6 Zr/Nb-95 0.05 0.8 12/33 0.2 - 3.2 Ce-144 0.3 0.5 3/33 0.4 - 0.7 Ru-106(b) 0.3 1.5 3/33 1.3 - 1.8 Others - < LLD Foodstuff Gamma (8) - - pCi/g (dry) K-40 1 33 8/8 10 - 53 Cs-137 0.1 0.2 1/8 - Zr/Nb-95 0.05 0.2 1/8 - Ru-106(b) 0.3 0.8 1/8 - Others -
< LLD g Feedstuff Gross Beta (80) 0.05 19 80/80 8 - 50 W pCi/g (dry) Sr-89 (81) 0.025 0.2 33/81 0.04 - 0.93 Sr-90 (81) 0.005 0.4 78/81 0.02 0.81 Gamma (81) - -
K-40 1 19 75/81 5 - 46 Cs-137 0.1 0.5 6/81 0.21.6 Ce-144 0.3 1.5 5/81 0.9 - 2.6 3 0.8 13/81 02-1.8 Zr/Nb-95 0.05 0.3 1.4 12/81 0.6 - 2.3 E Ru-106(b) Others - < LLD Soil Gross Alpha (0) - - pCl/g (dry) Gross Beta (64) 1 22 64/64 14 - 32 (Template Samples) Sr-89 (64) 0.25 0.4 1/64 - Sr-90 (64) 0.05 0.3 48/64 0.1 - 1.3 . U-234, 235, 238 - ! (0) - Gamma (64) - - K-40 1.5 13 63/64 5 - 24 i 0.1 1.5 56/64 0.1-6.8 Cs-137 Co-144 0.3 1.1 7/64 0.2 - 3 lg ll Zr/Nb-95 0.05 0.3 13/64 0.1 - 2 l Ru-106(b) 0.3 1.1 3/64 0.5-2 I l Others - < LLD (f) Fraction of detectable measurements at specified location. 5-18 section S. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1995 Annual Radiological Environmental Report i TABLE 5-3 ) l PRE OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 ; I (County, State) PRE OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 - 1975) Medium or Pathway Analysis and Total Number Lower Limit All Indicator Locations f Analysis Performed of Detection LLD Mean, (f) Range (Unit of a u ement) Soil Gross Alpha (0) - - pCi/g (dry) Gross Beta (8) 1 21 8/8 16-28 (Core Samples) Sr-89 (8) 0.25 < LLD Sr-90 (8) 0.05 0.2 5/8 0.08 0.5 i Gamma (8) - - l K-40 1.5 13 8/8 7 - 20 ) Cs-137 0.1 1.2 7/8 0.2 - 2.4 ! Co-60 0.1 0.2 1/8 - Others -
< LLD Surface Water Gross Alpha (40) 0.3 0.75 5/40 0.6 - 1.1 pCi/l Gross Beta (120) 0.6 4.4 120/120 2.5 - 11.4 Gamma (1) 10 - 60 < LLD ]
Tritium (121) 100 300 120/121 180 800 Sr-89 (0) - - Sr-90 (0) - - C 14 (0) - - Drinking Water 1-131 (0) - - pCi/l Gross Alpha (50) 0.3 0.6 4/50 0.40.8 Gross Beta (208) 0.6 3.8 208/208 2.3-6.4 ; Gamma (0) - -- i Tritium (211) 100 310 211/211 130 - 1000 l C-14 (0) - - l 1 Sr-89 (0) - - Sr-90 (0) - - Ground Water Gross Alpha (19) 0.3 < LLD pCill Gross Beta (76) 0.6 2.9 73/75(a) 1.3-8.0 Tritium (81) 100 440 77/81 80 - 800 Gamma (1) 10 - 60 < LLD Air Particulates Gross Alpha (188) 0.001 0.003 35/188 0.002 - 0.004 and Gaseous Gross Beta (927) 0.006 0.07 927/927 0.02 - 0.32 pCi/m3 Sr-89 (0) - - Sr-90 (0) - - I-131 (816) 0.04 0.08 2/816 0.07 - 0.08 Gamma (197) - - Zr/Nb-95 0.005 0.04 122/197 0.01 - 0.16 Ru-106 0.010 0.04 50/197 0.02 - 0.09 Ce-141 0.010 0.02 3/197 0.01 - 0.04 3 Ce-144 0.010 0.02 44/197 0.01 - 0.04 Others < LLD (f) Fraction of detectable measurements at specified location. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-19
Duquesne Light Company 1995 Annual Radiological Environmental Report TABLE 5 3 PRE OPERATIONAL ENVIRONMENTAL. RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station Docket No. 50-334 j Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 (County, State) PRE-OPERATIONAL PROGRAM
SUMMARY
(COMBINED 1974 - 1975) Medium or Pathway All Indicator Locations Analysis and Total Number Lower Limit f Analysis Performed of Detection LLD Mean, (f) Range (Unit of a u ement) Milk l-131 (91) 0.25 0.6 4/91 0.3-0.8 I pCi/l Sr-89 (134) 5 7 4/134 6 - 11 ; Sr-90 (134) 1 5.3 132/134 1.5 - 12.8 Gamma (134) - - Cs-137 10 13 19/134 11 - 16 Others < LLD External Radiation y - Monthly (!'99) 0.5 mR* 0.20 599/599 0.08 - 0.51 mR/ day y - Quarterly (135) 0.5 mR* 0.20 195/195 0.11 - 0.38 y - Annual (48) 0.5 mR* 0.19 48/48 0.11 - 0.30 Fish Gross Beta (17) 0.01 1.9 15/17 1.0 - 3.2 pCi/g (wet) Sr-90 (17) 0.005 0.14 17/17 0.02 - 0.50 Gamma (17) 0.5 K-40 - 2.4 17/17 1.0 - 3.7 Others - < LLD LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD). (a) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample). (b) May include Ru-106, Ru-103, Be-7. (f) Fraction of detectable measurements at specified location. I 5-20 Section 5. ENVIRONMENTAL MONITORING PROGRAM !
Duquesne Light Company 1993 Annual Radiological Environmental Report l Table S-4. Typical LLDs For Gamma Spectrometry TABLE 5-4 TYPICAL LLDs
- FOR GAMMA SPECTROSCOPY Air Particulates Vegetation Fish (PCI) (pCl/kg dry) (pCilg wet)
(p i li r) pCilg Be-7 50 20 200 0.2 0.02 K-40 80 50 400 0.4 0.4 Cr-51 50 20 200 0.2 0.2 I M n-54 5 2 20 0.02 0.02 Co-58 5 2 20 0.02 0.02 Fe-59 10 3 40 0.04 0.04 I Co-60 Zn-65 5 2 20 0.02 0.02 10 5 40 0.04 0.04 Zr/Nb-95 5 3 40 0.04 0.04 I R u-103 Ru-106 5 50 3 20 30 200 0.03 0.2 0.03 0.2 Ag-110M 10 5 50 0.05 0.05 l-131 I Te-132 15 8 4 4 200 20 0.2 0.02 0.2 0.02 1-133 8 4 20 0.02 0.02 Cs-134 5 2 20 0.02 0.02 Cs-136 8 4 50 0.05 0.05 Cs-137 5 2 20 0.02 0.02 Ba/La-140 10 3 200 0.2 0.02 Ce-141 10 20 100 0.1 0.1 Co-144 40 10 200 0.2 0.2 Ra-226 80 10 100 0.1 0.1 Th-228 10 10 20 0.0". 0.02 At time of analysis (DLC Contractor Lab). NOTE: Lower Level of Detection is defined in Beaver Valley Power Station ODCM. I F Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-21
Duquesne Light Company 1995 Annual Radiological Environmental Report B. Air Monitoring
- 1. Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an indtstrial 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 radiolodine and radioactive particulates at each of ten (1) offsite air sampling stations. The locations of these' stations are listed in Table 5-1 and shown on a map in Figure 5-1.
Samples are collected at each of these stations by continuously drawing one cubic foot per minute of atmosphere air through a glass fiber filter and through a charcoal cartridge. The former collects airborne particulates; the latter is for radiolodine sampling. Samples are collected for analysis on a weekly basis. The charcoal is used in the weekly analysis of airborne 1-131. The filters are analyzed each week for gross beta, then composited by station for monthly analysis by gamma spectrometry. They are further composited in a quarterly sample from each station for Sr-89 and Sr-90 analysis. In order to reduce interference from natural radon and thoron radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.
- b. Procedures Gross Beta analysis is performed by placing the filter paper from the weekly air sample in a 2" x 1/4" planchet and counting it in a low background, gas flow proportional counter.
Gamma emitters are determined by stacking all the filter papers from each monitoring station collected during the month and scanning this composite on a high resolution germanium gamma spectrometer. Radiciodine (1-131) analysis is performed by a gamma scan of the charcoal in a weekly charcoal cartridge. The activity is referenced to the mid-collection time. l l 5-22 section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company
'i995 Annual Radiological Environmental Report Figure 5-1. Air Sampling Stations
' unosa es,vry N j Amtm!'ce ms AtIL L7.E 2 l l ) l l 13 Mim's Dniny b , j
- W'.
}
27 bioi s Dam % l %** ! */ . , q w a. f Sews Dam L-23 *; } 1- I 2SB T Bam Qum wits 5.nposespont & (- ,,
'( ,
, j k%
32 m < a ) , 4 *Am +.% 28 , , , 47 East Lieraa.,0 io i A J-4 Amos, est vimma Q ~~I . m, I 51 Aicu:m o , N
, n l
~
)
- ~ %J 3
< /: .1Q;4 ..,
',46[~y.
~
c...-. . . . .
**"7
. um , l 0.%
~
-py '- . 30 ;, _ [, (
s J *= f .n - ..".e m s . . .d I
.d .
r ./.! (2icl 51 '- ;~j, fl I \s\ ..-
-I 5 -
g' ,, ~i f; I l m y [ - 2._ _
! // ~
i 1-i
, 4
\. % ~
bl yA% %
.)_
%- .: a : .-
i 4 s'.')'- i-FIGURE 5-1 . AIR SAMPLING STATIONS Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-23
l Duquesne Light Company I 1995 Annu:1 Radiological Environmental Report Strontium-89 and Strontium-90 activities are determined in quarterly composited air particulate filters. Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered. Half of the filtrate is taken for strontium analysis and is reduced in volume by evaporation. Strontium is precipitated as Sr(NO3 )2 using fuming (90%) nitric acid. A barium scavenge is performed to remove radium and other natural nuclides. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carr.ier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Sr-89 activity is determined by precipitating SrCO3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for low level beta counting.
- 3. Results and Conclusions A summary of data is presented in Table 5-2.
- a. Airborne Radioactive Particulates A total of five hundred twenty (520) weekly samples from ten (10) Mations were analyzed for gross beta. Results were comparable to previous years.
Figure 5-2 illustrates the average concentration of gross beta in air particulates. The weekly air particulate samples were composited to one hundred twenty (120) monthly samples which were analyzed by gamma spectrometry. Naturally occurring Be-7 was present in all but one sample. Naturally occurring K-40 was detected in twenty (20) of the one hundred twenty (120) monthly samples. Results are listed in the summary Table 5-2. A total of forty (40) quarterly samples were each analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 was detected. Based on the analytical results, the operation of Beaver Valley Power Station did not contribute to any increase in air particulate radioactivity during 1995.
- b. Radiolodine A total of five hundred twenty (520) weekly charcoal filter samples were analyzed for I 131. No detectable concentrations were present at any g locations. 5 Based on analytical results, the operation of Beaver Valley Power Station did not contribute to any increase in airborne radiciodine during 1995.
l l I 5-24 section s. ENVIRONMENTAL MONITORING PROGRAM i
ili lljI i ll
,iil1j!,lIjillf!! l OC$$5 r.o - . r o03n$
$ * >ooCE yW o cC nE ms58a!ai E:ommoa o!e I >2@Go OgS$&a o O8$ mA F >
i o ,::aEEg n
- 5 9
f } ,; ,g.
;4i,' iIit i 4!;;i J
a 9 . 1
- c
' t;:;rii!-.
e S *i ;,I !!
- !;! j t D
E T A v L I ti t . Ii+ + o U .
!ia! N C
I T R . t c A f l i1 I 4!;gi l' O P R I p
- A i
d .'[i . t*II 4!ie e N - S I ^ - A . T . g u E ,i it,
+ u B A S ..
S . O .ti +i+!4! um-l u R J G F
- O -:4 n
.- e . ! u N J O
I - T
- A ti+
A 4.: i- i1 t8ii' y a R - M T
'-' N E r p
C t Il t' - + A N O C - E .r! i ;l i , i+ ,l
- r a
G
- M A -
R b E +!t i f 4 e V / ux-F A - 2 n a J 1 1 1 1 0 0 0 0 0 ~ 0 2 :=OD 1 I ,1
*d6' ~ mz $ o2cm' >rroE- @ zo , y S c Pnm
1 Duquesne Light Company l 1995 Annual Radiological Environmental Report , l l C. Monitoring of Sediments and Soils (Soll Monitoring is required every 3 years and is required in 1997)
- 1. Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt. Soil saraples may vary from sand and sitt to a heavy clay with variable amounts of organic material.
- 2. Sampling Program and Analytical Techniques I
- a. Program River bottom sediments were collected semi-annually above the Montgomery Dam, in the vicinities of the Beaver Valley discharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 5-1 and are shown in Figure 5-3.
Bottom sediments are analyzed for gross alpha and beta activity, strontium, and the garnma-emitting radionuclides.
- b. Analytical Procedures Gross beta - sediments and soils are analyzed for gross beta by mounting g a 1 gram portion of dried sediment in a 2" planchet. The sample is I 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 soll 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. I l 5-26 section S. ENVIRONMENTAL MONITORING PROGRAM
f Duquesne Light Company 1 1995 Annual Radiological Environmental Report Figure 5-3. Environmental Monitoring Locations Shoreline Sediments and Soil N N 8'af sortist st:ratus , ; SAMPLt PO? ht t0CAff0N h. 2a Cowastream BvP5 Outf all *W %, / " M'. .N* .q M* lq g/'-,, t 31 50 s pstream vtgo ry o,.of lide
--( %. ( -, l battre.a.n we .. oS.tae of 4ew ,~" , .
( na g .b*'. 90lni L3CAf ton , 13 me yer's Face - 22 South of BV'5 5tte
" /
***-===s ,I Q
' ' ~
Na w !7,,8,,..'.o!,Uy.
- i. =, , ' , , .->s
* '""~'
L-
}$ INU),"a f >3 o i . u .e -i . > q l --
as meerson, v.va. l si aitw po . sa $ ys,,) ' A r?ge s., G.
,- x----- ...
f ...'
"-" 6 { ,
'o,
_. Ig, .
Y .
l ./ ' .
*/. , '
- c r .
o\ ' .~ *. f
- F :
g' w
~ '
s 2 '
.', g
\\
*I /
/ g i m g e.d =ra
- l b g' I \
l w ly l - J, _,> A,/I ~~(' ame=**', c===v . l 0 l- l s f % wk % . e i e e , b'** # (, _ J_ FIGURE 5 ENVIRONMENTAL MONITOR!nG LOCATIONS
'- SHORELINE SEDIMENTS AND SOIL s .,
'~
l Section 5. ENVIRONMENTAL MONITORING PROGRAu 5-27
l Duquerna Light Company 1995 Annual Radiologics! Environmental Report Strontium 89 and 90 are determined by radiochemistry. The sample is first dried and weighed. Stable strontium and calcium carriers are added and the sample is leached in hydrochloric acid. The sample is filtered. Calcium and strontium are precipitated as phosphates, collected by vacuum filtration, then dissolved in nitric acid. Strontium is separated by precipitating Sr(NO3) using nitric acid. A barium scavenge is performed to remove radium and other natural nuclides. Final purification of strontium is accomplished by precipitating SrSO4 An iron scavenge is performed, followed by addition of stable yttrium carrier and a mlnlmum 5-day period for Y-90 ingrowth. Yttrium is then precipitated as hydroxide, is discolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Sr-89 activity is determined by precipitating SrCOs from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm' aluminum absorber for low level beta counting.
- 3. Results and Conclusions A summary of sediment analysis is presented in Table 5-2.
- a. Sediment A total of six (6) samples were analyzed for gross alpha and gross beta. g Results were comparable to previous years. l A total of six (6) samples were analyzed for Sr-89 and Sr-90. No Sr-89 was detected. Sr-90 was detected at low level on one sample in the Beaver Valley Discharge Area and one sample upstream of the New Cumberland Dam.
A total of six (6) sample were analyzed by gamma spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was found in every sample. Be-7 was found in one sample. Small amounts of Cs-137 from previous nuclear weapons test were found in all six river sediment samples including two upstream above Montgomery Dam, which are unaffected by plant effluents. Small amounts of Mn-54, Co-58, Co-60, Ag-110M, Sb-125 and Cs-137 were detected in the Beaver Valley Power Station discharge area and are attributable to station releases. The activity found in the station discharge area is consistent with station data of authorized radioactive discharges which were within limits permitted by the NRC license. The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River sediment. The positive results detected are attributable to authorized releases from the Beaver Valley Power Station and are characteristic of the effluent, These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the I environmental monitoring program is sufficiently sensitive. 4 5-28 section 5. ENVIRONMENTAL MONITORING PROGRAM j
Duquesne Light Company 1995 Annual Radiological Environmental Report D. Monitoring of Feederops and Foodcrops
- 1. Characterization of Vegetation and Foodcrops According to the 1994 statistical summary of the Pennsylvania Department of Agriculture, there were approximately 575 farms in Beaver County. The total value of farm crops and livestock was $17,332,000. The principal source of I revenue was in dairy products which were estimated at $6,693,000. Revenues from other farm products were estimated as follows:
Field Crops $1,786,000 Fruits $301,000 I Horticulture and Mushrooms S3,797,000 Meat and Animal Products $3,893,000 Vegetables and Potatoes $490,000 Poultry Products $112,000 The total land in Beaver County is 279,020 acres. Approximately 147,900 acres are forested land and 57,960 acres are pasture and crop land.
- 2. Sampling Program and Analytical Techniques
- a. Program Representative samples of cattle feed are collected monthly from the -
nearest dairy (Searight). See Figure 5-4. Each sample is analyzed by gamma spectrometry. The monthly samples are composited into a quarterly sample which is analyzed for Sr-90. A land use census was performed July / August 1995 to locate the nearest residence and nearest garden of greater than 500 square feet producing I fresh leafy vegetables within a five (5) mile radius of the site. Table 5-5 for results. See Foodcrops (vegetables) were collected at garden locations during the summer of 1995. Leafy vegetables, i.e., cabbage, were obtained from Shippingport, Georgetown, and Industry, PA, and Weirton, WV. All samples were analyzed for gamma emitters (including 1-131 by gamma spectroscopy). I I W section 5. ENVIRONMENTAL MONITORING PROGRAM 5-29
Y
$ 21 E
5 I
?
E 6 !~ 9 5
!y l
//.e-
% d'$0M1Ye OstCR Y . DAM f
s 9 'M I~l 5 $ c,,.saa, $- ? ouro %, I L - - -. l n,ouuo p# l
, "l, a m
o a o RWER% y e.
, i g .o_. m s .
$ ner o n. g. Cycongt'rowns R w 0 S/PP/NGPORT {
~/ $ C
\
c,n a,, i l
#'% l
> @ q wc
., m I wan peuusn.vana O e a~ y' a t9
""d 5 (K \ vI [. !B* ,
ACACTOR n N \ S'" . V 8 m4
% g' E
- 5 *
% } -
O IO LEGEND: V - Vegetable Carden
" k
'5 - Ocaright's 3 airy Farm Feedcrop r ~@
FIGURE 5 ENVIRONMENTAL MONITORING PROGRAM FEEDCROP AND F00DCR0P LOCATIONS
l Duquesna Light Company 1995 Annual Radiological Environmental Report ' Table 5-5. Closest Residence and Garden in Each Sector TABLE 5-5 l l Closest Residence and Garden in Each Sector Sector Closest Residence
- Closest Garden
- 1- 1.55 mi N 1.55 mi N 2 1.59 ml NNE 1.61 mi NNE 3 0.42 mi NE 2.65 mi NE 4 0.38 mi ENE 0.98 mi ENE 5 0.42 mi E 2.06 mi E 6 0.87 mi ESE 1.63 mi ESE 7 1.10 mi SE 1.25 mi SE 8 1.10 mi SSE 2.16 mi SSE 9 1.40 mi S 2.31 mi S 10 0.80 mi SSW 1.55 mi SSW 11 1.67 mi SW 1.67 mi SW 12 1.46 mi WSW 1.55 mi WSW 13 2.27 mi W 2.27 mi W 14 2.84 mi WNW 3.18 ml WNW 15 0.91 mi NW 0.92 mi NW 16 0.91 mi NNW 1.36 mi NNW
' Direction and Distance from Midpoint between Reactors 4
l l Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-31
Duquesne Light Company 1995 Annual Radiological Env!ronmental Report
- b. Procedures Gamma emitters, including 1-131, are determined by scanning a dried, homogenized sample with the gamma spectroscopy system. A high resolution germanium detector is utilized with this system.
Strontium 90 analysis for feedstuff is performed by a procedure similar to that described in 5-C.2 after drying, weighing and ashing the sample. Rad!oiodine (1-131) is determined by radiochemistry. Stable iodide carrier is first added to a chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. j The melt is dissolved in water, filtered and treated with sodium j hypochlorite. The iodate is then reduced to lodine with hydroxylamine l hydrochloride and is extracted into chloroform. It is then back-extracted l as iodide into sodium bisulfite solution and is precipitated as palladium 3l iodide. The precipitate is weighed for chemical yield and is mounted on a El nylon planchet for low level beta counting.
- 3. Results and Conclusions A summary of data is presented in Table. 5-2.
- a. Feed A total twelve (12) samples were analyzed for 1-131. 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 present in all samples. A total of twelve (12) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was present in all samples and Be-7 was detected in five (5) samples.
- b. Food A total of four (4) samples were analyzed for I-131. No detectable concentrations were present.
A total of four (4) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was present in all samples.
- c. The data from food and feed analyses were consistent with previous data. .
These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in foods and feeds in the vicinity of the site. I; l l 5-32 SecUon S. ENVIRONMENTAL MONITORING PROGRAM Il l
l j Duquesne Light Company ! 1995 Annual Radiological Environmental Report l E. Monitoring of Local Cows Milk
- 1. Description - Milch Animal Locations 1
During the seasons that animals producing milk (milch animals) for human consumption are on pasture, samples of fresh milk are obtained from these g animals at locations and frequencies noted in Table 5-1. This milk is analyzed g for its radiciodine content calculated as lodine-131. The analyses are performed I within eight (8) days of sampling, i Detailed field surveys are performed during the grazing season to locate and enumerate milch animals within a five (5) mile radius of the site. Goat herd locations out to fifteen (15) miles are Identified. Survey data for the most recent I survey conducted in is shown in Figure 5-5.
- 2. Sampling Program and Analytical Techniques I a. Program Milk was collected from these (3) reference dairy farms (Searight's, Brunton's and Nicol's) within a 10-mile radius of the site and from one (1) control location (Windsheimer's) outside of the 10-mile radius. Additional ,
dairies, which represent the highest potential milk pathway for radiciodine l 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 i locations are more appropriate. The location of each is shown in i Figure 5-6 and described below. l l Direction and Distance from Collection
*
- h al, Midpoint between Reactors Period l
n 25 Searight 47 Cows 2.2 miles SSW Jan. - Dec. ; 27 Brunton 93 Cows 7.3 miles SE Jan. - Dec. 29A Nicol 75 Cows 8.0 miles NE Jan. - Dec. 96 Windsheimer 58 Cows 10.3 miles SSW Jan. - Dec. 109"* Soissen 30 Cows 3.83 miles WSW Jan/ - Dec. I 102** 105" Ferry Ambrose 2 Goats' 25 Cows 3.3 miles SE 3.86 miles WSW Apr. - Oct. Nov. - Dec. 106" Conkle 32 Cows 3.75 miles WSW Jan. - Dec. Milk Usage - Home Only. Highest potential pathway dairies. I I I Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-33
l Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 5-5. Beaver Valley Power Station Milch Animal Census I! BEAVER VALLEY POWER STATION MILCH ANIM AL CE NSUSr -- -
/- \+ -% I!
2 r. ,
~~
l
~
.M ..,
9 ! S7 .,.
' \
y_ J. -
\
- e. ,
, '~,
l
~
n? ,
, 4
<- . J '~ -
.e ..,.. .
y a
,/* . i
" . fr J n
~f. . * *
- _,
hs / '.:
.i em 1
0 g I ' ' N .[W XQ l' yQ,,(#'
/[ 7 l, l
e' . a * ,/ l z > . -
)/w).
- rh ^ ~
.y a l
~
" T
,s t s c s
' shd. .. ,
I! J' ~ ~ ~ ~ m GOATS
,_ Ei SUMMER 1995 E s .
eCOWS I I 5-34 Section 5. ENVIRONMENTAL MONITORING PROGRAM I
Duquesne Light Company
'1995 Annual Radiological Environmental Report Figure 5-6. Environmental Monitoring Locations - Milk l
l I l MIII g uw-c.ca on.en SAMP1.E eue wh ] ) i SITE 1.0 CATION V
. I i 25 Searight S., l a,"1 4 %., ., ,n ,, . I
~- l 27 brunton ~~ l 29A Nicol ,g %,,, ,, l ' 8' l l 96 102 Windsheimer Ferry
(' , j( l 105 Ambrose j.**,. ~
< ..'-. . ~ . . - .
106 Conkle f 'l i ,e ' a {; 109 Soissen , 7 We o . i. " r, g -
~. {
i p N
./ . - - - l , ,,,,,,,,
O i _ . , y, -
. . i d k .,
oa v. -
, ,,J. g .3" ~ 3., . . . ,
-* ,i
.hg j W
s , %. :' -% u.. , <
.f ,, ... ' z, ~~'~.*r- '
./ ^ .
.e a
/
/
s "m f
, j @
n _..; l s
- m c..
4 3
. . ...i L..' ,.i w
m \\ - 4 !. 6 : I
'l s27
~b. t \, I r e i. .
.\
z y w w ,./ 3 e_ = Q ' &< / p,
/
5 m j% r g; b /.u.a. m.,n ! d# d""' y _. . .._
- s. -
-y an,,n s, N
es - s 3, ' g Wh' b. ,
** s i. e ~ .
' '\<
k.
,T+_ .
FIGURE 5 ENVIRONMENTAL MONITORING LOCATIONS MILK w, Section 5. ENVIRO" MENTAL MONITORING PROGRAM 5-35
Duquesne Light Company , 1995 Annual Radiological Environmental Report l l 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 grazing. This monthly or bi-weekly sample is analyzed for Sr-89, Sr-90, gamma emitters including Cs-137 (by high resolution germanium gamma spectroscopy) and 1-131 (high sensitivity analysis),
- b. Procedure Radiciodine (1-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
Gamma emitters are determined by gamma spectroscopy of a one liter Marinelli container of milk. Strontium milk samples are prepared by adding stable strontium carrier and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is purified in all samples in a chromatographic column. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days- for the ingrowth of Y-90. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO2 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm' aluminum absorber for low level beta counting. Chemical yields of strontium and yttrium are determined gravimetrically.
- 3. Results and Conclusions A summary of data is presented in Table 5-2.
A total of one hundred sixty-six (166) samples were analyzed for I-131 during 1995. All 1-131 activities in milk were below the minimum detectable level. A total of one hundred thirty-three (133) samples were analyzed for Sr-89 and S r-90. No Sr-89 was detected. Sr-90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the no mally expected range. A total of one hundred thirty-three (133) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was present in all samples. It was noted that the dairies with the highest annual mean activities were goat dairies, which are known to concentrate activities over a factor of two compared to a cow dairy. All results were consistent with (or lower than) those obtained in the preoperational program. These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in milk in the vicinity of the site. 5-36 Section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesn3 Light Company 1995 Annu:1 Radiological Environmental Report F. Environrnental Radiation Monitoring
- 1. Description of Regional Background Radiation and Sources The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300-400 feet. Most of the land is wooded.
The principal geologic features of the region are nearly flat-laying sedimentary I beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the I 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 />R/hr. Results for 1995 indicated that background radiation continued I in this range.
- 2. Locations and Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).
In 1995 there were a total of forty-four (44) off-site environmental TLD locations. The locations of the TLDs are shown in Figure 5-7 through Figure 5-10. Thirteen (13) locations also have QC Laboratory TLDs. Both laboratories use calciem sulfate dysprosium, (CaSO4:Dy) in Teflon matrix. The calcium sulfate dysprosium (CaSO.:Dy) TLDs were. angealed at the I Contractor Central Laboratory shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit between the Central Laboratory, the field location, and the Central Laboratory was corrected by I transit controls maintained in lead shields at both the Central Laboratory and the field office. All dosimeters were exposed in the field in a special environmental holder. The dosimetry system was calibrated by reading calcium sulfate I dosimeters which have been exposed in an accurately known gamma radiation field. I l r l ] Section 5. ENVIRONMENTAL MONITORING PROGRAu 5-37
l Duquesne Light Company 1995 Annual Radiological Environmental Report
- 3. Results and Conclusions l
Data obtained with the contractor TLD (CaSO :Dy in Teflon) durirg 1995 are summarized in Table 5-2, and the quality control TLD results are . listed in Table 3-1. The annual exposure rate of all offsite TLDs averaged 0.179 mR/ day in 1995. As in previous years, there was some variation among locations and seasons as would be expected. Four TLDs (two quarterly, two annual) were lost in the field during the year. Two quarterly TLDs were also lost in processing. In 1995, ionizing radiation dose determinations from TLDs averaged approxirnately I 65.3 mR for the year. This is comparable to previous years. There was no evidence of anomalies that could be attributed to the operation of the Beaver Valley Power Station. The TLDs confirm that changes from natural radiation levels, if any, are negligible. l l l l l l 1 1 l 1 l 5-33 Section 5. ENVIRONMENTAL MONITORING PROGRAM j
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 5-7. TLD Locations - Northwest Quadrant FIGURE 5 TLD LOCATIONS i NORTHWEST QUADRANT __ ,,
~
BEAVER VALLEY POWER STATION :
's [
t
, y l U
k'
\.
.... ... ........ .. y .. . . . . . . . ; ,
\
a
. fj . . a-.
N .........-
^' .
- y. f.N .
e
ii l s
\ I , ... ..
x
\ ! ))N
, .- . . . . . .a : <
l ,, <-
- .I , ,,
#~ ,, --
.:. n
,, J'~.'
<i k'-
- 3
) \
si N / s
.b't i N ,
' r
[..(..N h i.I,. y I /
,,.,~~~... da-'
~. .
e.
- , . . . ,q ,;.
.. l .
)
" "W"'.&,fRN N., , *f'\q - \ ,
Y '
, . . . . . . . ,, i .- .\ . .l <
'g '
.,e- u ,
o -~.. g-ys .,,j","E b '
, y~ , ' . . . a
L s ', -
%:gfy'. *>
K l._. . *.N e /- s ,
- \
\ @ s l 1
./ <
/ '
r
\ ,, ., _- u \ ,
Sector SLte Location 1 70 Western Beaver 1 28 Sherman's F..e m 13 86 East Uverpool 13 60 Haney's Farm 14 15 Georgetown 14 87 Calcutta 14 47 E. Uverpool Water Co. , 15 32 Midland S.S. 15 68 Midland Heights 15 89 Ohioville 16 90 Fairven School 16 93 Sunset Hills Midland Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-39
I Duquesne Light Company 1995 Annual Radiological Environmental Report 1 Figure 5-8. TLD Locations - Northeast Quadrant iIGURE 5 8 - TLD LOCAT10f45 ; I , f40RTHEAST QUCPAiil
.-*--"' BEAVER VALLEY POWER STATION 1
_ _,m. p , , : % i f ~~.,
' . T e- s l
~""
-k j '..
s 5. (
- '- g , . e wa
/
/
'(x, ..
. . . .h
; ,r
/
! l
/' j . . . ~. ,
l Mr
,; '.g
- 4 m .. .
-, e
- - . , . .- j s % / {o."
1 ' 7~ ' ' r . _ . ., .: .; , M. ; j -/,, n .
\ / -
t
)*
=.' ;
t f h7
..--r.,
l% ( ,7
' %., O
'I
. .' [ /,.
t', V
\
// /' . $ . - y '. -,'
e r- ~, t
\ ,
u ,,. - ; 6
* *;. it .
i a# , M, / w - : t. E
. N"
..'sd:./[
MI s,./ , , % g
\ '
} r3
,~
/
, - . D I ,
("/'.j (N *
/
l !% .-l .,
's , .-
lu, a l \'- , ,/ ,
. k ,
)
/
k j, ' - . s
- 3
'%_ a
.,^
i 4 N, m
- . .. F , b y
6.
- r. ,s- < r
.r ; ,
l ! Sector S.iLe Location 1 70 Western Beaver 1 28 Sherman's Farm 2 91 Pine Grove & Doyle 2 71 Brighton Twp. School 3 46.1 Industry (Tire Co.) 3 46 Industry (Church) 3 72 Site of Fe-mer Logan School 3 29B Beaver County Hosp. 4 10 Shippingport Pest O*fice 4 30 Shippingport, PA (S.S.) 4 73 Potter Twp. School 4 74 Community College (Center Twp.) 5 51 Aliquippa ! 5 75 Holt Road l 5 45 Mt. Pleasant Church I l l 5-40 Section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure S-9. TLD Locations - Southeast Onadrant 4 ,.N f.
/ .s ,.
n
" d Q* .
ts / )
..' t ... t p' *o . ,
.z y .
G ir' , ' - d y - n
}f
, g
' 4 f,
/' ' ( ..... .' y ( .I _
l '
?' h Y - - ' '
%, & y l_ _
, i* "**M*~
g) N
- a,a O..
s, _ s.. [11 ,,
\ \ A j
S ' ' gw
\
g w. j y ,
'a** **
% .4 N j/
\' T
('}. k e Q-
.'f s f .
/ .
\ N j
/ ,
\
)
~_.
a \ \
\
. , .g (
. \.1 es 'Wh p .,
r_ /. ._ '.)^-- 7'N
\q f' g-- , s A. ,,.* R J W\,
- c. 7.' (
g . . . . . . , . . . - . . . k-s.
\ / *; -
) '
a
. FIGURE 5 TLD LOCATIONS
.. w- SOUTHEASE QUADRANT
'-Y~ '""
BEAVER VALLEY POWER STATION Sector SLte Location 6 51 Aliquippa S 75 Holt Road S 45 Mt. Pleasant Church 6 45.1 Raccoon Twp. 6 76 Raccoon Twp. School 6 77 Green Garden Road 7 59 Iron's Farrn 7 78 Raccoon Municipal Bldg. 7 27 Brunton's Dairy 8 94 McCleary Road 8 79 Rt.18 and Rt.151 9 80 Raccoon Park 9 81 Southside School a 82 Hanover Municipal Bldg. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-41
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 5-10. TLD Locations - Southwest Quadrant I s .. f a ..s a [5'/, y* s . y! s
'N .e / Q. ~1
*/ l !
( / 9'C ? .p.
-~...
[*~~'Tl ' [ A]'f , ,r N y_g a ****** f-d / g . d
= = = = = - . I k ,. I ,
,...e:% a % l
+ ,' '
S,, :n-w; -
~' "
's. ./ v ' ( '..)
" g ? "
^s *x-
\
3- -, y+ Q N ,'t s.
,i-.- (' . - . _ ,
a
~
5 . -* '" I y- { s' s @ (
\
.3 m
\ ~
N, / , g
/
, 7
\ x .
\g .
r)s p p' x . . si 2 , , , 4, J b
\
h
--k - j - - -. - - '
~
. s '/
, . , t ~ ~ .. - -
( W $- l l
~
, .i ,
.... 5 ,/ .
\ \
4 '
/ ,' @ *5~~
l
\L . es '
,/ lt1 j '
r vg; y ll
",~ *
,dy" '.t a u;. c g
\
FIGURE 5 TLD LOCATIONS SOUTHWEST QUADRANT {, '
' . . ~'i-~~,,,,....-
BEAVER VALLEY POWER STATION Sector ,Sjt_e Location 9 80 Raccoon Park 9 81 Southside School 9 82 Hanover Municipal Bldg. 10 48 Weirton Water Company 10 83 Mill Creek Road 10 95 McCleary Road 11 13 Meyer's Farm 11 14 Hookstown 11 84 Hancock Children's Home 12 92 Georgetown Road 12 85 Rt. 8 and Rt. 30 13 66 E. Uverpool 13 60 Haney's Farm l l I 5-42 Section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1995 Annual Radiological Environmental Report G. Monitoring of Fish
- 1. Description During 1995, fish collected for the radiological monitoring program included carp and catfish.
- 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 spectroscopy. Fish sampling locations are shown in Figure 5-11.
I
. b. Procedure A sample is prepared in a standard tared 300 mi plastic bottle and scanned I for gamma emitting nuclides with gamma spectrometry system which utilizes a high resolution germar,Lm detector.
- 3. Results and Conclusions A summary of the results of the fish monitoring data is provided in Table 5-2.
A total of eight (8) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was found in all samples. No other gamma emitting I radionuclides were detected. The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River fish population. I I I l I i I ~ Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-43
ac@mh Ce z~ @3Am g8 >lE xm&h a mE 0"3ka y( D a m* a Y ".mi:o3k A E 8 g j ?' 8B3 $ m gnF. - r?R!- 1 m 4b S'
'4e
\
'o , \ \/ (-q' i A
M r t M e (' t G O a x. D Y A f i g o e eu as g
/
s n o R P G N I S N R /na R E 0 B. on i t a O T O I M 0 re 9Y k ~i r c" s -) a a c a I. I N O M T A C O r t e ' L W 3 O R#' t g n L A T G
- f.
- i N N h \ % @ p l E M
N I L P
% Q ma O R
M QSh I A S 6 ( i s E V N H S M T F - I
-ll lg s 1 F
I ' N h 1 5 _. ,( % E R U _ - G I F _ u g a L n, w m 7 7 g e
- R s o .
I' /c/ f _
%a ,
R E N w o r e n dr e w o R o n l A P D m a c A y og q V L N O ee l g y r e g \s Y I T l r aa m o g o s~ S N A C Vh c t n o
' DA rs ei M
' N vD -
' f u a
en m a P s Bo n rt i t e r
%e 3 A aa et s
p
'k t
t NS U
/a p _
w r' o ' l
," gr C
T . A r t s R i04 56 2 9 4 a - [^"x o. #W M Ysb .
=$8v miso 2C # eN8"g m"8$
Duquesne Light Company 1995 Annual Radiological Environmental Report H. Monitoring of Surface, Drinking, Well Waters and Precipitation
- 1. Description of Water Sources The Ohio River is the main body of water in the area. It is used by the Beaver Valley Power Station for plant make-up for the cooling tower and for receiving plant liquid effluents.
Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site. It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water Authority. The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river. The next downstream user is East Liverpool, Ohio which is approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream use river water for cooling purposes. Groundwater occurs in large volumes in the gravel terraces which li e 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 v ells yielding up to 60 gpm. In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The record mean annual precipitation for the area is 36.43 inches based on 1965 to .1994 data collected at the Pittsburgh International Airport. ( section 5. ENVIRONMENTAL MONITORING PROGRAM 5-45
Duquesna Light Company 1995 Annual Radiological Environmental Report
- 2. Sampling and Analytical Techniques
- a. Surface (Raw River) Water The sampling program of river water includes five (5) sampling points along the Ohio River. Raw water samples are normally collected at the East Liverpool (Ohio) Water Treatment Plant [ River Mile 41.2] daily and composited into a monthly sample. Weekly grab samples are taken from the Ohio River at the following locations: upstream of Montgomery Dam
[ River Mile 31.8]; and near the discharge from the Beaver Valley Power Station [ River Mile 35.0]. Two automatic river water samplers are at the following locations: Upstream of Montgomery Dam [ River Mile 29.6]; and at J&L Steel's river water intake [ River Mile 36.2]. The automatic sampler takes a 20-40 mi sample every 15 minutes and samples are collected on a weekly basis. The weekly grab samples and automatic water samples are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point. The weekly composites from the automatic river water sampler upstream at Montgomery Dam are analyzed for 1-131. The monthly composites are analyzed for gross alpha, gross beta, and 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 5-12.
- b. Drinking Water (Public Supplies)
Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Water Treating Plants. An automatic sampler at each location collects 20-40 mi every 20 minutes. These intermittent samples ; are then composited into a weekly sample. The weekly sample from each location is analyzed by gamma spectroscopy. The weekly samples are also analyzed for 1-131. l Monthly composites cf the weekly samples are analyzed for gross alpha, gross beta, and by gamma spectrometry. Quarterly composites are analyzed for H-3, Sr-89, Sr-90 and Co-60 (high sensitivity). Locations of each sample point are shown in Figure 5-12. 1 i I 5-46 Section 5. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1995 Annual Radiological Environmental Report [ c. Groundwater Grab samples were collected each quarter (when occupied) from each of four (4) well locations (see Figure 5-12) within four (4) miles of the site. { These locations are: One (1) well in Shippingport, PA One (1) well at Meyer's Farm One (1) well in Hookstown, PA One (1) well in Georgetown, PA Each ground water sample is analyzed for gross alpha, gross beta, tritium, [ and by gamma spectroscopy.
- d. Precipitation f Precipitation is collected at Shippingport, PA, East Liverpool, OH and Weirton, WV. Precipitation when available is collected each week and then composited into monthly and quarterly samples. ~he monthly samples are
( analyzed for gross beta and gamma emitters a:d the quarterly composites are analyzed for H-3, Sr-89 and Sr-90. Locations of each sample point are shown in Figure 5-12. { [ { ( ( ( Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-47
Duquesne Light Company 1995 Annual Radiological Environmental Report Figure 5-12. Environmental Monitoring Stations Loca*'ons Wells, Surface Water, Drinking Water and Precipitation l I
.,(, * g t
.. vt >6 -
; sg i g s : *E d
s: k T. 4 e N.1 !
=
!}
i I s:s e4 t'. a ghb, s d ets E .yO = ! ErdS i (
! I gy5d
/ 1 .5 E
//
/
!e 8i !.aiP e
,_ _ _ _.) / s j. : d
/
c-* ? u ni g y ome l
..jlf <
Y
/
2
^
l
-N, eet ,
I tOg~I (# 1 g .A u\gn 3 SAMPLE SAMPLE SAMPUNG POINT TYPE POINT DESCRIPTION 2A Downstroom . BVPS 21 Downstroom . J & L intake
$vrface Water 5 East Uverpeel Water Plant (Raw water) 48 Montgomery Dam (Upstream) 48 1 Upstream . Arte Petymers imake Drintung 4 Midland Wster Plant Water 5 East uwerpeel Water Plam 11 Shipp*ngpert Bere
- Well 13 Meyers Farm I Water 14 Hoekstown, PA 15 Georgetown, PA 30 Shippingport PA Precipitation 47 East Uverpent, OH 48 Weerten. WV I
5-48 Section 5. ENVIRONMENTAL MONITOP. NG PROGRAM
Duquesne Light Company 1995 Annual Radiological Environmental Report
- e. Procedures Gross alpha and cross beta activities are determined first by evaporating one liter of the sample on a hotplate. The residue is mounted and dried on a 2-inch stainless steel planchet. The sample is counted in a low background, gas flow proportional counter. Self-absorption corrections are made on the basis of sample weight.
Gamma analysis is performed on water sample by loading one liter of sample into a one liter Marinelli container and counting a high resolution germanium gamma spectrometry system. Strontium-89 and 90 are determined on water samples by a procedure similar to that described in 5-C.2 except that the leaching step is eliminated. Cobalt-60 is determined with a sensitivity of 1 pCl/ liter by evaporating 2 liters of sample on a hotplate and transferring the residue to a 2-inch planchet. The planchet is counted on a high resolution germanium gamma spectrometry system. Tritium is determined in water samples by liquid scintillation counting. Radiolodine (I-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
- 3. Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, ground and precipitation) are provided by sample type and analysis in Table 5-2. These are discussed below.
- a. Surface Water A total of forty-eight (48) samples were analyzed for gross alpha and gross beta. Alpha activity was detected at the lower limit of detection ~in one of the samples. Surface water may contain sediment which contains naturally occuring alpha radioactivity. Positive beta results above preoperational levels were detected in the BVPS discharge area and are attributable to station releases. The beta activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license.
Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-49
i Duqunsne Light Company 1995 Annual Radiological Environmental Report A total of sixteen (16) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-58 and Co-60. Positive tritium results were detected in the BVPS discharge area and are attributable to station releases. The highest tritium results have been noted, however, to correspond to shore samples taken when mixing zone sampling by boat was not possible. All other samples taken upstream and downstream were within preoperational levels. The activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license. A total of forty-eight (48) samples were analyzed by gamma spectrometry. No gamma emitting radionuclides were detected. A total of fifty-two (52) samples were analyzed for I-131 using a highly sensitive technique. Trace levels of I-131 were measured in twenty-two (22) of the weekly samples. The results were slightly above the minimum detectable activity. The positive results were detected at a control location above the BVPS discharge and could not be attributed to plant releases. The results may be attributed to medical procedures and the expected variability in the analyses results of very low levels of activity.
- b. Drinking Water A total of twenty-four (24) samples were analyzed for gross alpha and gross beta. All results were within a normal range.
A total of eight (8) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-60. No H-3, Sr-89, Sr-90, or Co-60 were detected. ; A total of one hundred four (104) samples were analyzed by gamma ) spectrometry. No gamma emitting radionuclides were detected. A total of one hundred four (104) samples were analyzed for I-131 using a highly sensitive technique. Trace levels of I-131 were measured in i seventy-one (71) of the weekly samples. The results were slightly above l tho minimum detectable activity. The positive results were detected at Midland and East Liverpool and could not be attributed to plant releases. As noted under Surface Water above,1-131 has been observed upstream of g ' the site. The results may be attributed to medical procedures and the l expected variability in the analyses results of very low levels of activity,
- c. Groundwater A total of fourteen (14) samples were each analyzed for gross alpha, gross beta, H-3 and by gamma spectrometry. Only two samples were obtained g at Meyer Farm because the farm was only occupied two quarters. Alpha g and H-3 activity were not detected. The gross beta results are comparable to preoperational ranges. No gamma emitting radionuclides were detected.
I 5-50 Section 5. ENVIRONMENTAL MONITOR'NG PROGRAM
l [ Duquesne Light Company i 1995 Annual Radiological Environmental Report f d. Precipitation A total of thirty-six (36) samples were analyzed for gross beta. All results were within a normal range. A total of twelve (12) samples were analyzed for H-3, Sr-89 and Sr-90. Two (2) positive tritium results detected were within normal levels. No Sr-89 or f Sr-90 was detected. A total of thirty-six (36) samples were analyzed by gamma spectrometry. Naturally occurring Be-7 was detected in twenty-six (26) 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 l Station are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive. Further, the actual detected concentration (averaged over the total batch discharge period during the year) attributable to Beaver Valley Power Station, was only 0.110% of the limits set forth in Appendix C of the ODCM for water discharged to the Oh!o River. The Ohio River further reduced [ this concentration by a factor of ~ 600 prior to its potential use by members of the public. [ { { [ [ [ { Section S. ENVIRONMENTAL MONITORING PROGRAM 5-51
Duquesne Light Company 1995 Annual Radiological Environmental Report 1
- 1. Estimates of Radiat!on Dose to Man
- 1. Pathways to Man - Calculational Models l l
The radiation doses to man as a result of Beaver Valley operations were ; calculated for both gaseous and liquid effluent pathways using codes for the l ARERAS/ MIDAS computer system equivalent to NRC computer codes XOQDOQ2, GASPAR, and LADTAP. Dose factors listed in the ODCM 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 radionuclide contained in the Annual Radioactive Effluent Release Report (noble gases, particulates, radiolodines 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 lODCM. All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to code equivalent to XOQDOQ2 which in turn provided input for the GASPAR equivalent. Except when more recent or specific data was available, all inputs were the same as used in the Beaver Valley Power Station Environmental Statements or in Regulatory Guide 1.109. The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the " cow-milk-child", and other ingestion pathways. All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using Intrinsic Germanium detectors. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0). The actual data from these analyses are tabulated and used as the radionuclide activity input term in code equivalent to LADTAP. A hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is available, all other input are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109. Pathways, which were evaluated, are drinking water, fish consumption, shoreline recreation, swimming, and boating. i l l I: 5-52 section 5. ENVIRONMENTAL MONITORING PROGRAM
1995 Annual Radiological Environmental Report
- 2. Results of Calculated Radiation Dose to Man - Liquid Releases I a. Individual Dose The doses which are calculated by the model described above are to a i hypothetical reel individual located at Midland since this is the nearest location where significant exposure of a member of the public could potentially occur; therefore, this location is use to calculate the maximum I exposure. A breakdown of doses by pathway and organ is provided in Table 5-6 for the maximum individual. Included in this table is a breakdown of a typical dose to individuals from natural radli; tion exposure.
i The results of calculated rad!ation dose to the hypothetical real individual are compared to BVPS annual limits in Table 5-7.
- b. Upon implementation of the Unit 2 Technical Specifications and inception of the liquid discharge procedures at Unit 2 on July 24,1987, the discharge limits were clarified to be reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annual site limits listed in Table 5-8 are specific to this report only, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2).
I I I I I i rl l
.I i
l W Section 5. ENvlRONMENTAL MONITORING PROGRAM 5-53
V' E TABLE 5-6 un E g Radiation Dose to Maximum Individual , mrem /yr - Liquid Releasesh p PATHWAY SKIN ORGAN THYROID BONE BODY , m 0 O M 297 y Fish Consumption N/A 5 (Teen) (Liver) (Adult) (Child) (Adult) E z Drinking Water N/A (infant) (Thyroid) (Infant) (Child) O M 77 (Child) { g $ c o O O
~
~
Shoreline Activities (Teen) o s m (Tecn) (Teen) (Skin) (Teen) (Teen) E i:' E 0.0000480 0.00216 0.00190 0.000381 0.00187 E- EO
"" (Child)
(Teen) (Child) (Liver) (Child) (Child) b TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSUREc fk hh C Ambient Gamma Radiation . 58 y_ Eo g m~ Radionuclides in Body 40 j s.9 o3 4 Global Fallout <1 7 g E-E @ Radon 198 5 {
? D TOTAL mrem 296 { .@
e O Located at Midland Drinking Water intake 3 3 a b Total liquid releases are from Site (combined Unith 1 and 2) c National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of lonizing Radiation", BEIR Report, 1990 M M
l l Duquesno Light Company 1995 Annual Radiological Environmental Report Table 5-7. Results of Calculated Radiation Dose to Man - Uquid Releases TABLE 5-7 Results of Calculated Radiation Dose to Man - Liquid Releases I Maximum Exposure BVPS Annual Percent of Hypothetical Real Organ ,g , Individual I mrem
,g TOTAL BODY Adult 0.00161 6.0 0.027 Teen 0.00114 6.0 0.019 I Child Infant 0.00187 0.00174 6.0 6.0 0.031 0.029 ANY ORGAN Adult 0.00173 (Liver) 20.0 0.0086 Teen 0.00139 (Liver) 20.0 0.0069 I Child 0.00216 (Liver) 20.0 0.0110 Infant 0.00188 (Thyroid) 20.0 0.0094 I Maximum Total Body Dose - Caosule Summary mrem 1995 Calculated 0.00187 Unit 2 Updated Final Safety Analysis Report 3.5 Hiahest Oraan Dose 1995 Calculated 0.00216 Unit 2 Updated Final Safety Analysis Report 4.7 1
P Section S. ENVIRONMENTAL MONITORING PROGRAM 5-55
l Duquesne~ Light Company
- 1995 Annual Radiological Environmental Report l
- c. Population Dose The 1995 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was:
Organ Man-Millirems a9 S Pe TOTAL BODY 128 H-3 126 mrem THYROID 137 H-3 126 mrem
- 3. Results of Calculated Radiation Dose to Man - Atmospheric Releases The results of calculated radiation dose to the maximum exposed individuals for BVPS airborne radioactive effluents during 1995 are provided in Table 5-8. The doses include the contribution of all pathways. A 50-mile population dose is riso a calculated and provided in Table 5-8. H-3 is the primary radionuclide contributions to these doses.
The results are compared to the BVPS annual limits in Table 5-8. As in the liquid discharge limits, the gaseous effluent limits are reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annual limits listed in Table 5-8 are specific to this report only, and were derived by multiplying the individual Technical g Specification reactor limits by a factor of two (2). The results show compliance 5 with the BVPS annual limits. I I 5-56 Section S. ENVIRONMENTAL MONITORING PROGRAM
Duquesne Light Company 1995 Annual Radiological Environmental Report
- 4. Conclusions Based upon the estimated dose to individuals from the natural background radiation exposure in Table 5-6, the incremental increase in total body dose to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit 1 and 2, is less than 0.0003% of the annual background.
The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-57
Duquesne Light Compar.y 1995 Annual Radiological Environmental Report Table 5-8. Results of Calculated Radiation Dose to Man - Atmospheric Releases TABLE 5-8 Results of Calculated Radiation Dose to Man - Atmospheric Releases MAXIMUM OME BVPS OSURE OMATION ORGAN ANNUAL LIMIT INDIVIDUAL ANNUAL LIMIT DOSE
*'** man rem mrem TOTAL BODY .664 30 2.20 2.91 SKIN .678 ,
30 2.26 0.28 I LUNG .689 30 2.30 2.95 THYROID .674 30 2.25 2.96 I 1 l I I 5-58 Section 5. ENVIRONMENTAL MONITORING PROGRAM I
l APPENDIX 1 Contractor Laboratory EPA Interlaboratory Comparison Program
EPA INTERLABORATORY COMPARISON PROGRAM I Teledyne Brown Engineering Environmental Services participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section, trending graphs (since 1981) and the 1994 and 1995 data summary tables are presented for isotopes in the various sample media applicable to the Duquesne Light Company's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence. I I I ! I
EPA INTERLABORATORY COMPARISON PROGRAM 1994 Environmental Collecuon Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) 01/14/94 Water Sr-89 25.0 5.0 24.00 1.00 -0.35 Sr-90 15.0 5.0 15.67 1.53 0.23 01/28/94 Water Gr-Alpha 15.0 5.0 21.67 0.58 2.31 (d) Gr-Beta 62.0 10.0 72.33 3.79 1.79 02/01/94 Water I-131 119.0 12.0 110.33 0.00 -1.30 02/11/94 Water Ra-226 19.9 3.0 21.00 1.00 0.64 Ra-228 14.7 3.7 15.67 1.53 0.45 03/04/94 Water H-3 4936.0 494.0 4833.33 152.75 -0.36 04/19/94 Water Gr-Beta 117.0 18.0 102.67 6.43 -1.38 Sr-89 20.0 5.0 19.00 1.00 -0.35 Sr-90 14.0 5.0 13.00 0.00 -0.35 Co-60 20.0 5.0 23.67 3.21 1.27 Cs-134 34.0 5.0 34.00 1.73 0.00 Cs-137 29.0 1 5.0 34.00 2.65 1.73 Gr-Alpha 86.0 1 22.0 78.00 3.00 -0.63 Ra-226 20.0 3.0 15.67 i 1.53 -2.50 (e) Ra-228 20.1 i 5.0 15.33 1 0.58 -1.65 06/10/94 Water Co-60 50.0 1 5.0 43.00 2.00 -2.42 (f) Zn-65 134.0 13.0 13.33 i 0.58 -16.08 (g) Ru-106 252.0 1 25.0 201.33 9.29 -3.51 (h) Cs-134 40.0 1 5.0 29.33 1 3.79 -3.70 (0 Cs-137 49.0i 5.0 49.67 1.53 0.23 Ba-133 98.0 i 10.0 85.00 i 3.00 -2.25 0) 06/17/94 Water Ra-226 15.0 1 2.3 15.33 0.58 0.25 Ra-228 15.4 1 3.9 16.33 i 1.53 0.41 07/15/94 Water Sr-89 30.0 5.0 26.00 i 1.73 -1.39 Sr-90 20.0 5.0 19.00 1 0.00 -0.35 07/22/94 Water Gr-Alpha 32.0 1 8.0 25.33 1 2.89 -1.44 Gr-Beta 10.0 1 5.0 16.00 1 0.00 2,08 (k) 08/05/94 Water H-3 9951.0 i 995.0 9700.00 100.04 -0.44 08/26/94 Air Filter Gr-Alpha 35.0 i 9.0 31.33 1 2.08 -0.71 Gr-Beta 56.0 t 10.0 59.33 i 3.21 0.58 Sr-90 20.0 i 5.0 18.00 i 1.00 -0.69 Cs-137 15.O i 5.0 17.00 1.73 0.69 09/16/94 Water U 35.Oi 3.0 38.67 i 0.58 2.12 0) Ra-226 10.0 i 1.5 10.67 i 0.58 0.77 Ra-228 10.2 i 2.6 9.70 0.52 -0.33
EPA INTERLABORATORY COMPARISON PROGRAM 1994 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) 09/30/94 Milk Sr-89 25.0 5.0 24.33 2.52 -0.23 Sr-90 15.00 5.0 17.67 1.53 0.92 1-131 75.0 8.0 81.67 5.86 1.44 Cs-137 59.0 5.0 70.33 4.62 3.93 (m) K 1715.0 86.0 1740.00 153.95 0.50 10/07/94 Water 1-131 79.0 t 8.0 71.00 3.00 -1.73 10/18/94 Water Gr-Beta 142.0 21.0 120.00 0.00 -1.81 Sr-89 25.0 5.0 24.67 2.08 -0.12 Sr-90 15.0 5.0 14.33 1.15 -0.23 Co-60 40.0 5.0 41.00 1.00 0.35 Cs-134 20.0 5.0 21.67 1.53 0.58 Cs-137 39.0 5.0 41.67 2.31 0.92 Gr-Alpha 57.0 14.0 51.33 1.53 -0.70 Ra-226 9.9 1.5 11.33 0.58 1.66 Ra-228 10.1 2.5 9.33 0.58 -0.53 10/28/94 Water Gr-Alpha 57.0 14.0 47.00 i 3.00 -1.24 Gr-Beta 23.0 5.0 25.33 1.53 0.81 11/04/94 Water Co-60 59.0 5.0 52.00 1 0.00 -2.42 (n) Zn-65 100.0 1 10.0 81.33 i 7.02 -3.23 (19 Cs-134 24.0 1 5.0 19.67 2.52 -1.50 Cs-137 49.0 1 5.0 54.33 1 2.31 1.85 Ba-133 73.0 i 7.0 58.33 1 2.89 -3.63 (n) P Footnotes: . (a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters. (b) Teledyne Results - Average i one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters. (c) Normalized deviation from the known. (d) There appears to be variation in self-absorption metrix. The EPA confirms that the composition of their tap water from Lake Mead, varies seasonally which can cause variation in alpha, beta results. No corrective action required at this time since results are within i 3 sigma control limits. (e) No specific or apparent reason found. Data sheets verified and detector efficiencies calibrated. Will exert extra care in making dilutions and using correct sample type on concentration of acids. Will check future samples to see if a pattern develops. I
[ [ - EPA INWRLABORATORY COMPARISON PROGFAM 1994 ( Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (al Engineering Result (b) Deviation (c) (f) A second aliquot was analyzed, paying particular attention to volume aliquoted. The result, 52 pCi/1. was in gcod agreement with the EPA. The three original results, each counted on a different detector, showed good precision. The measurement of Co-60 has not been a problem. Future EPA cross-checks will be weighed and results followed to check for a possible trend "out of control". (g) The average value of three analyses on the " Report of Analysis" was 133 pCi/ liter which is in good agreement with the EPA. Apparently. Incorrect results were entered into the EPA computer. Future data will be printed from the computer screen to check entries. (h) The EPA has indicated that the Radiation Quality Assurance Program has been experiencing problems v"th the ruthenium-lO6 analysis. See attached letter from EPA. { (0 The first aliquot, prepared according to EPA dilution instructions was counted on four detectors in the 1 liter Marinelli geometry with Cs-134 results (based on the 796 kev peak) in pCl/l of 32.0, 25.1, 31.7, and 30.8. The 31.7 result was not reported. Had that been ( reported instead of 25.1, the average would have been 31.5 and the normalized deviauon would have been -2.94 instead of -3.70. A second aliquot was prepared and a single measurement was made with the result of 31.1 pCi/1. An undiluted aliquot was measured in [ a 150 ml geometry with the result of 33.5 pCi/1. That result is comparable with the Marinelli results. Thus none of : sample preparation (dilution, volume determinauon, maintaining correct pH, etc.), sample geometry, or detector efficiency seem to be the cause of the low results. { Q) There is no apparent reason for the low result, however the average value, 85 pCl/l is in good agreement to the grand average (86.46). No corrective action planned. [ (k) EPA results for gross beta in water were corrected for 20% crosstalk into the beta channel from the Th-230 alpha spike. Recent measurements show that the crosstalk can be much r higher (37% for Tennelec counter #3 and 54% for gamma products counter #1). The L normalized deviation from the grand average was only 0.38, Future results will be corrected with specific crosstalk values determined by counting Th-230 standards. Possible aliquoting error. The instrument calibration, spike, and blank results all appear
~
(O normal. No procedural changes are planned. Previous results were well within one normalized deviation. Future measurements will be reviewed to determine if a trend in results above the two sigma warning limit is occurring. (m) The milk sample was counted four times. The reported Cs-137 values were based on one aliquot of I liter volume and an aliquot of 0.865 liter counted two times. It is suspected that the 0.865 liter volume was incorrectly determined. If I liter (the usual volume for counting milk samples) is used in the calculation, then the average of three results equals 63.6 pC1/1 which gives a normalized deviation to the Known of 1.59. The fourth count (a 1 liter aliquot) had a Cs-137 equal to 64.2 pC1/1 which is in good agreement with the average of the other three. Teledyne will set up a log for recording aliquots used for EPA samples and record how the aliquot volume was determined. ; L
EPA INTERLABORATORY COMPARISON PROGRAM 1994 Environmental ll Collection Teledyne Brown ' Date Media Nuclide EPA Resultla) Engineering Result (b) Deviation (c) (n) The EPA requires that water samples be diluted before gamma analysis. That imposes a feature not appropriate for the handling of environmental samples. As in the 06/10/94 water sample. It appears that the first aliquot may not have bcen accurately prepared. A second aliquot was prepared and counted three times with results in pC1/1 and normalized deviation of: Co-60 60.6 +0.55 Zn-65 100. 0.0 g Cs-134 22.9 -0.38 g Cs-137 58.5 +3.29 Ba-133 69.8 -0.79 Four of the five are now in good agreement with the EPA results. The Cs-137 is high, but within the control limits when compared to the grand average deviation of all laboratories of 2.89. The grand average was 51.9 pCi/1. For future samples of this type we will have two technicians each prepare an aliquot and compare the counting results to check for preparation technique differences. I l I
a
.i e t re .,
[ O 'g I UNITED GTATEO ENVIRONMENTAL PROTECTION AGENCY
.. ,* OFFICE OF RESE ARCM AND DEVELOPMENT
' en:**
- ENVIRONMENTAL MONITO#1NG SYSTEMS LA80RATORY LAS VEGAS PO SOK93478 LAS VEGAS NEVADA 89193 3478 !
(702/798 2100 rTS 545 2100) I l i Dear Participant j l l The Radiation Quality Assurance Program has been experiencing problems i with the Ruthenium-106 currently used in the Performance Evaluation ! (PE) Studies and in the Standards Distribution Program. If these i problems can be satisfactorily resolved, this analyte vill once again be placed into this PE Study. If the problems cannot be resolved, the j Ruthenium--106 vill be replaced. Formal vritten notice vill be given to all participants that are enrolled in the Gamma in Vater PE Study before the Ruthenium-106 is 1 reintroduced or replaced. At that time, new calibration standards I will be available to all participants in the Gamma in Vater PE Study. l Sincerely, ~ - ! George Dilbeck
;n st phi <<mance Evaluation Program Ra34 w..alysis Branch (RSA-RADOA)
I l
DULUEONE EPA INTERLABORATORY COMPARISON PROGRAM 1995 (Page 1 of 2) l EPA Date TI Mailed Date EPA EPA TI Norm Deir. " Warning Preparation Re suits Issued Results Media Nuclide Results(a) Results(b) (Known)(c) *" Action ! 01/13/95 03/24/95 04/21/95 Water Sr-89 20.0 5.0 19.00 1 2.65 -0.35 Sr-90 15.0 1 5.0 14.00 1 0.00 -0.35 01/27/95 03/24/95 03/24/95 Water Gr-Alpha 5.0 i 5.0 5.00 1 1.00 0.00 Gr-Beta 5.0 5.0 6.00 1.00 0.35 02/03/95 03/20/95 04/21/95 Water I-131 100.0 10.0 88.33 i 2.31 -2.02 * * (d) 02/10/95 04/07/95 05/23/95 Water Ra-226 19.1 2.9 20.67 1 0.58 0.94 Ra-228 20.0 i 5.0 18.67 i 0.58 -0.46 03/10/95 04/06/95 05/19/95 Water II-3 7435.0 744.0 7066.67 1115.47 -0.86 03/17/95 05/12/95 06/05/95 Water Pu-239 11.1 i 1.1 10.33 1 0.58 -1.21 04/18/95 06/30/95 08/18/95 Water Gr-Beta 86.6 i 10.0 80.33 1 2.52 -1.09 Sr-89 20.0 1 5.0 20.67 1.15 0.23 Sr-90 15.0 1 5.0 14.67 i 0.58 -0.12 Co-60 29.0 1 5.0 31.67 i 2.08 0.92 Cs-134 20.0 i 5.0 19.67 1.73 -0.12 Cs-137 11.0 i 5.0 11.67 i 1.53 0.23 Gr-Alpha 47.5 11.9 39.67 1 2.52 -1.14 Ra-226 14.9 i 2.2 15.67 i 0.58 0.60 Ra-228 15.8 i 4.0 13.00 1.73 -1.21 06/09/95 08/09/95 02/26/96 Water Co-60 40.0 i 5.0 42.33 1 2.52 0.81 Zn-65 76.0 8.0 82.33 1 3.51 1.37 Cs-134 50.0 1 5.0 46.67 1 2.08 -1.15 Cs-137 35.0 5.0 37.67 1.15 0.92 Ba 133 79.0 8.0 74.33 1 2.08 -1.01 06/16/95 08/09/95 09/05/95 Water Ih-226 14.8 i 2.2 15.00 0.00 0.16 Ra-228 15.0 3.8 14.00 1 0.00 -0.46 07/14/95 08/09/95 09/05/95 Water Sr-89 20.0 5.0 18.33 i 1.53 -0.58 Sr-90 8.0 i 5.0 8.0 1 0.00 0.00 07/21/95 08/18/95 09/27/95 Water Gr-Alpha 27.5 1 6.9 18.33 1 1.53 -2.30 ** (e) Gr-Beta 19.4 5.0 19.33 i 1.53 -0.02 08/04/95 09/01/95 09/29/95 Water 11-3 4872.0 487.0 4866.67 152.75 -0.02 Footnotes at erxl of table.
DU;UE!NE EPA INTERIABORATORY COMPARISON PROGRAM 1995 (Page 2 of 2) EPA Date TI Malled Date EPA . EPA TI Norm Dev. ** Warning Preparation Re sults Issued Resulis Media Nuclide Results(a) Results(b) (Known) " Action 08/25/95 10/21/95 02/29/96 Air Filter Gr-Alpha 25.0 6.3 23.67 1.53 -0.37 Gr-Beta 86.G 10.0 84.67 i 1.53 -0.33 Sr-90 30.0 i 5.0 25.33 0.58 -1.62 Cs-137 25.0 5.0 27.00 i 1.00 0.69 09/15/95 11/10/95 02/26/9G Water Ra-22G 24.8 1 3.7 27.33 1.15 1.19 Ra-228 20.0 5.0 14.G7 0.58 -1.85 09/29/95 11/28/95 02/29/96 Milk Sr-89 20.0 5.0 23.33 3.06 1.15 Sr-90 15.00 5.0 16.33 0.58 0.4 G i-131 99.0 10.0 103.33 5.77 0.75 Cs-137 50.0 5.0 54.67 2.52 1.G2 Total K 1654.0 83.0 1683.33 136.50 0.G 1 10/0G/95 11/10/95 02/26/96 Water 1-131 148.0 15.0 150.00 i 0.00 0.23 10/27/95 12/01/95 03/04/96 Water Gr-Alpha 51.2 12.8 37.00 1 3.00 -1.92 Gr-Beta 24.8 i 5.0 25.33 1.53 0.18 Footnotes: ta) Average i experimental sigma. (b) Expected laboratory precision (1 sigma. I deterir- on) (c) Normalized deviation from the known. (d) An investigation is being conducted; results will be available shortly. (d) The normalized deviation marginally exceeded the warning Icvel and an apparent trend in the results appeared. The cause was a probable high bias in the beta counting effletency. Check source control charts did not indicate any changes in the counting equipment, so the I-131 calibration was suspected. New 1-131 calibrations were performed July 3 thtough G. 1995 after receiving a new standard from the EPA. De Interromparison sample data sheets were recalculated with the new efliciencies and the average result was in excellent agreement with the EPA (96 pCl/l versus the EPA value of 100 pCi/I). The discrepancy in the I-131 efficiency between the current calibration and the previous one (aside from the uncertainty in the standard) appears to be an abnormally low yield in the preparation of the standard for the older calibration which crea;ed a high bias in the owter efficiencies. he bias was less than ten percent, therefore further corrective action or revision of previously reported data is deemed not necessary. (e) he mineral salt content of the water used by the EPA to prepare the samples has been shown to vary substantially throughout the year. Absorption curves to amount for mount weight may vary from the true absorption characteristics of a specific sample. Previous results do not indicate a trend toward "out of control' for gross alpha / beta analysts and the normalized deviation from the grand average is only -0.36. De normalized deviation from the known for'IIIE-ES does not exceed three standard deviation and internal spikes have been in control. No corrective action is planned at this time. M M M M
lil ll1 l i 6 9
' 9 1
5
, 9
> 9 1
4 9
, 9
< 1 3
f"t , 9 9 1
, 2 9
, 9
) n" 1 1
f f 1 M o , 9 9 a A 1 1 m
. ig R g p
0 9 S G ( , 9 3 i O S " 1 A R E 9 P T E P A , , 8
, 9 K L 1
o C U C 8 E C 8 I
, 9 H T , 1 C R A t 7 a S P 8
, 9 m S R p 1 ig S
O I A i. 6 3 R N 8
, 9 1
C I 1 1 T A A P H 5 D P E L A p 8
, 9 1
S 4 8 S , 9 O R f 1 3 G , 8 L
, 9 1
e 2 8
, 9
' 1 T 1 8
- - ~ - 9 0 0 0 O 01 8 6 4 ' 2-
_ 3" il:
EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg.1 of 1) 160 140 -
o 120 -
100 - D i Y p, k 80 - ] ,, .
,3 g' I' 60 - il th ' v e 40 - "
l A, do 2> 20 - O i . . . . . i i e i i i i i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl 3 Sigma o EPA i 3 Sigma M M M M M M M M M - M
- n. rx cm m m rm _ rm rm em m rm rm_ m r~ m r- r, m EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES (pg.1 of 1) 80
{ l 70 - 60 - 50 - 40 - <> k 30 - o t'
' I o
10 - 0 0- - 981 1982 1983 1984 1985 1986 1987 1983 1989 1990 1991 1992 1993 1994 1995 1996 o TIi 3 Sigma o EPA i 3 Sigma
EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg.1 of 1) 80 60 - is 40 - , o 6E 3 o f Jo 3 o t [ ,jl @ 20 -t) o >
" '{ h5 J>
1 o
<b<[ <
,[<E 3' ko }> 5, g,
<n
<[
0-6 i
-20 . . . . . i . . . i i i i i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 a Tli 3 Sigma o EPA i 3 Sigma
,Ill,l1lllll1 l ill 1lllIl ll 1 ll1ll ,
m 6 9 9 1 5
, 9
. 9 1
4 1 o , 9 1 9 1 3 3 9
, 9 1
I 2
, . 9 I 9 I 1 1
9
. 9 a
) ,
1 1 m g M f 0 i S A o . 9 9 3 R 1 , 1 i G g A P O p >
- 9 E
( h- 8 R K ]
> i 9 1
o P L I K M 8 8 C N i 9 1 E I , l ( H 9 8- 7 a C D , 9 8 m M ig S U 1 S S I T 6 3 mORC N O R k . 9 8 1 i T i T 5 o 8 S m , 9 1 4 8 o >
, 9 m
( 1 I> t' b 3 I 8 O o . 9 m
]'
1 2 8 y , 9 r i iK 5" - 1 1 3 0 8 m 0 0 0 8 0 6 0 4 0 2 0 01 2-9 1 m r 3 C UD- r r 1 l 1
t EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg.1 of 1) 80 60 - > o i n 40 - u - n (>
" o 5 f q, o >
- i r 0-
-20 , , , , , , , , , , , , , ,
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tli 3 Sigma o EPA i 3 Sigma
EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg.1 of 1) 2600 2400 - 2200 - 2000 - 1800 - - t,
, ,,, o ,
I {' l ' w I g i q, If l>
- 1600 -
'f f ' ] t) <
> hr .) in I
= I>' ,
,l
'<> g i O
]
y ' > t l ,
< > o g in }L ti >
- ) II .
S 1400 - I ' ' ' ' ' 1 t i y 1200 - 1000 - 800 - 600 . . . . . i . . . . . i i i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o TIi 3 Sigma o EPA i 3 Sigma
EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg.1 of 1) 160 140 - ll 120 - " 13 o 1) 100 - ' > 11' ' o 80 - o $ ) = 3 60 - < > O a. {f
- 1) -
t r fo II ( [ " 40 - t? b'o - N fI 20 - gi
#-u g g E ff
,, k g 0- -
0 -
-20 i i i i . . . i i i i i a i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tli 3 Sigma o EPA i 3 Sigma M .
M . M M M
ll i 1 ll ll 6 j 9 r i 9 1 5
, 9
]
i
. 9 1
4 o 9 T . 9 1 3
. 9 T' 9 1
o 2
' 9
'l . 9 i 1 o
1 9 M . 9 1 a A J' m ig R ) 0 9 S G 1 . 9 3 1 O f o o 1 A P R 1
, 9 E P .
. 9 8
g > K p 1 o C ( K 8 E L . 9 8 H I
)
I 1 C M i 7 a S N > 8 m I :
. 9 S
i ig 7 , 1 S O
) ;
3 - 1 6 3 R - 8 C M . 9 l T U ) 1 A t I i S 5 a P E , 8 E C i i
. 9 1
T 4 8 i
. 9 1
I I 3 8 J " . 9 I 1 y 2 8
. 9
, 1 i '
, 1
' o <
8
- - - - 9 0 0 0 0 0 01 0 8 6 4 2 1
eg2S 1
l EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER (pg.1 of 1) 180 160 - 140 - [ 120 - 100 - ' Q 5 8 - g
- c. 60 - o .n o o .,, ,, }
40 -- g " { o o i D " i e. NdIdd$),pyA~"d';")3,.bg"~mdf;,")f- .
-20 . . , , , , , , ,
1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996
- Tl 3 Sigma o EPA 'J Sigma M m m e g g
EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg.1 of 2) 220 200 - 180 - ll 160 - i x h 140 - 5 - 3 120 - - i, 2 .
$ 100 -
80 - d i 60 -
~
'.) .
I . 40 - -
'I 43 .g 20 -
,, ,g <
[,h 4 , 0 - -
-20 . . . .
1981 1982 1983 1984 1985 1986 o TI 3 sigma o EPA 13 sigma
EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 260 220 - , 1 180 - o 140 - o " o D o O E ' 5 100 - y
= o
"~
y k{ { m{ fI a kg o) I W Ipisfih'Jiil p f + d' p'I' 986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 O Tli 3 Sigma o EFA i 3 Sigma >
, 1 l)1I 1 l i!'! )'\ lll >
5 8
- - - - 9 1
)
2 4
,8 M f o ,
9 1 A R 1 G . a O g p m g R ( is 3 P 1 R g A K E . ' P E C T E A o H W 3 C N
,8 9
1 S I a S 9 m O 8
- is g
R M 3 C U I l i T A T N P n E O R T S " 2 8
,8 9
1 o o"
- 1
- - - ; 8 9
0 0 0 0 0 o 0 2- 1 0 8 6 4 2 1
- C~
l1 l
EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2 of 2) 80 70 - 60 - T U " 50 - n T 40 -- ti o g , o h 30 -f , I, 3
,, r, ~ ,
U ' o o jjo
- o. 20 - o >
i , . i b j' " o o 10 - g" > > 'b ge - . m , 0- 1
-20 . . . . . . . . . .
i 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 l D Tl 3 Sigma o EPA i 3 Sigma
EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER (pg.1 of 1) 80 70 - 60 - 50 - 40 - , , i l t i 30 - f ~ f h " I ..g' 5 . d*- 20 - f i o
>;; NfI ly, [f g II!;4( h d )dd,M .
981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl i 3 Sigt'a o EPA i 3 Sigma
.-_ . . . . . .. . _ _ _ . _ . ..m.. _. . _ _ _ . _ _ . _ . _ _ _ _ . . . . . . . . _ . . . _ . . _ _ _ _ . . . _ . _ _ _ . _ . . _ . _
EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg.1 of 2) 5000 4000 - .
~
e' d ti o 3000 -
}
esi i
.n t' .tT , .
e T ist o n U 3 , . . g a 2000 - r en ,,
,b i{ -
49
<a 1000 -
O - t
-1000 . . .
1981 1982 1983 1984 1985 i a Tii3 sigma o EPA 13 sigma l l 1 m l
3 7-- =mmes ummme ammum ummum ummer m -- - EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 16000 14000 - 12000 - 10000 - o.- o f 0 8000 -
'E 5 "g . 's a '.[
6000 - ,g
'h ii 'l 4000 - 1 'E j' 'O 'Q
<[
L 9 '@
<g 2000 - <l 0 , , ' '
1984 1986 1988 1g9o jggg 1g94 1996 D Tl 3 Sigma o EPA 3 Sigma
EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg 1 of 2) 100 80 - . o,, 60 - o 3 .
=
2 40 -- o . g ~ ih 'L 'Q g i . .
' i -
20
.['j,
,g o, '{ a i .
o g o . .
*,o ,
- .g 0 - o o o - -
-20 , , , , , ,
1981 1982 1983 1984 1985 1986 1987 1988 o Tli3 sigma o EPA 13 sigma M M M M M M
l : l 6 9 9 1 g g
'o.
5 9 i 9 1 o
)
o. 4 oi f, 9 i 9 1 o M ) 2 { a m A f o 3 9 ig R , 9 S G 2 1 3
. b i O g p o o A P
R ( U E P R " 2 K E 5 , 9 o T 1 9 C A < 1 E W o, H N C I u a S 0 o 1 m 6 ig S T- , 9 9 S O L o 1 3 R A o, i i B T C O A C o P , 9 0 E > 9 1 o , , 9 8 g, . 9 1 l > l , P 8 8
- - - - - 9 0 0 0 0 0 0 01 0 8 6 4 2 2 1 -
byCU 7 l
EPA CROSS CHECK PROGRAM IODINE-131 IN WATER (pg.1 of 1) 180 160 - 4. 140 - 120 - o o ti o II o U i 100 - C u o y 80 - g i g ti s f , 5" ' {o S 60 - D . o o of I 20 - c .. o d14. g .. Oo g c 0 00 D E DE O-
-20 . . . . . . . . . . . . . .
1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 ; o Tli 3 Sigma o EPA i 3 Sigma M M M M M M M m
EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg.1 of 2) 100 80 - 60 -
,l3 -
u "i e . . '2 U
~
40 - L - t - O . : i -
. .[ s
~, L -
[
'li
} 20 i ij
'h L , i -
I ' ' f' i 'f
'li 1 0 - - 1 -
I l
-20 , , , , , ,
1981 1982 1983 1984 1985 1986 1987 1988 o Tli 3 sigma o EPA 13 sigma
EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 2 of 2) 100 80 - tt 60 - o II 4) k 40 - o y o'
,,p 20 - o o [ t oI 11 oIo oI
.ii o
" D o o a "j
- 0. .p 1 h o o o g .
0- -
-20 , , , , . . .
1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl 3 Sigma o EPA i 3 Sigma L t
EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg.1 of 2) 80
- l
\ . 60 - k. 1 - 1 40 - g -
. C -
-r.
= 'l:
T T , 2 o
<f L
y t f f- n x g i l . ll .
'i
, 4 .
20 - 8-k e
,f 3 g
<1 i
, ; <i 1 ,, o .. 18 -
3 41 j O - -
-20 , , , , ,
1981 1982 1983 1984 1985 1986 1987 o Tl13 sigma o EPA 13 sigma
EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 2 of 2) 120 100 -
"o 80 -
60 - o
- I ..g-{
s ... tr-h" 40 - o g o ..y II I) tt '
) O II 20 - < 'Ip>
"i t
, , ,1 "Me
,,o y ,, , I o s ,,, g,
,,f 0- 1
-20 , , , , , , ,
1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl 3 Sigma o EPA i 3 Sigma
~
l APPENDIX II QC Laboratory EPA Interlaboratory Comparison Program
)
Accendix A Interlaboratory Comoarison Program Results Tcledyne's Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides know to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency, Several months later, the agency reports the known values to the participant laboratories and specifies controllimits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
'Ihe results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.
This program is conducted by the U.S. Environmental Protection Agency Intercomparison and
. Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for Thermoluminescent Pasirr eters (TLDs), since 1976 via various International Intercomparisons of Em ironmental Dor,uneter , 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 for the past twelve months. Data for previous years available upcn request. Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months. Data for previous years available upon request. Tab!c A-5 list results of the in-house " duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon requ-st. Attschment A lists acceptance criteria for " spiked" samples. Out-of-limit results are explained directly below the result. A1
9
~
I 12-31-95 ATTACHMENT A
- ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value 6
Strontium-89 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-90 6
2 to 30 pCi/ liter or kg 5.0 pCi/ liter
>30 pCi/ liter or kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross alpha $20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value Gross beta $100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter 5% of known value Tritium s4,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known)*"
>4,000 pCi/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value lodine-131, s55 pCi/ liter 6.0 pCi/ liter lodine-129 6 >55 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-646 >35 pCi/ liter 15% of known value 6
Technetium-99 Iron-55, 50 to 100 pCi/ liter 10 pCi/ liter
>100 pCi/ liter 10% of known value Others' -
20% of known value l ' From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies , Program, Fiscal Year,1981-1982, EPA-600/4-81-004. Tcledyne limit. A2 I
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result d Control Code Type Collected Analysis 12 Sigma' 1s, N=1 Limits dTW-723 WATER Jan,1995 St-89 17.7 t l.5 20.0 5.0 11.3 - 28.7 STW-723_ WATER Jan,1995 Sr-90 13.7 0.6 15.015.0 6.3 - 23.7 STW-724 WATER Jan,1995 Gr. Alpha 4.3 0.6 5.0 5.0 0.0 - 13.7 STW-724 WATER Jan,1995 Gr. Beta 4.710.6 5.0 5.0 0.0 - 13.7 STW 725 WATER Feb,1995 1-131 99.0 4.4 100.0 10.0 82.7 - 117.3 STW-726 WATER Feb,1995 Ra-226 19.2 i 0.4 19.1 2.9 14.1 - 24.1 STW-726 WATER Feb,1995 Ra-228 19.212.0 20.0 5.0 11.3 - 28.7 STW-726 WATER Feb,1995 Uranium 24.9 i 0.2 25.5 3.0 20.3 - 30.7 STW-727 WATER Mar,1995 H-3 7,460.0 87.2 7,435.0 744.0 6,144.2 - 8,725.8 STW-728 WATER Mar,1995 Pu-239 11.0 i 0.6 11.1 1.1 9.2 - 13.0 STW-729 WATER Apr,1995 Gr. Alpha 41.7i 0.6 47.5 11.9 26.9 - 68.1 STW-729 WATER Apr,1995 Ra-226 13.4 i 0.5 14.9 2.2 11.1 - 18.7 STW-729 WATER Apr,1995 Ra-228 13.l i 2.4 15.814.0 8.9 - 22.7 STW-729 WATER Apr,1995 Uranium 9.5 0.6 10.0 3.0 4.8 - 15.2 STW-730 WATER Apr,1995 Co-60 29.0i l.7 29.015.0 20.3 - 37.7 STW-730 WATER Apr,1995 Cs-134 17.311.2 20.0 i 5.0 11.3 - 28.7 STW-730 WATER Apr,1995 Cs-137 11.0 1.0 11.0i5.0 2.3 - 19.7 STW-730 WATER Apt,1995 Gr. Beta 74.8 i 3.2 86.6 i 10.0 69.3 - 103.9 STW-730 WATER Apr,1995 Sr-89 17.010.0 20.0 5.0 11.3 - 28.7 STW-730 WATER Apr,1995 Sr-90 12.7 1.2 15.015.0 6.3 - 23.7 STW-732 WATER Jun,1995 Ra-226 14.710.3 14.8 2.2 11.0 - 18.6 STW 732 WATER Jun,1995 Ra-228 11.910.6 15.0 i 3.8 8.4 - 21.6 STW-732 WATER Jun,1995 Uranium 13.9 i 0.3 15.213.0 10.0 - 20.4 STW-735 WATER Jul,1995 Gr. Alpha 16.4 2.4 27.5 6.9 15.5 - 39.5 STW-735 WATER Jul,1995 Gr. Beta 16.811.0 19.415.0 10.7 - 28.1 STW-736 WATER Aug,1995 H-3 4,773.7 i 49.9 4,672.0 487.0 4,027.1 - 5,716.9
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental Protection Agency (EPA), Las Vegas, Neveda.
- All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/ Filter.
- Unless otherwise indicated, the TREESML results are given as the mean 12 standard deviations for three determinations.
d USEPA results are presented as the known values and expected laboratory precision (1s,1 detenrination) and controllimits as defined by the EPA. Al-1
1 y l Table A-2. Crosscheck program results, Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value 2 Sigma (All Participants) 2nd International Intercomparison 115-2 CaF2 : Mn Bulb Apr,1976 Field 17.0 1.9 17.1 16.4 i 7.7 ] 115-2 CaF2 : Mn Bulb Apr,1976 Lab 20.8 4.1 21.3 18.8 7.6 Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, new York, and the School of Public Health of the University of a Texas, Houston, Texas. g 3rd International Intercomoarison 115-3 CaF2 : Mn Bulb Jun,1977 FieM 30.7 3.2 34.9 i 4.8 31.5 3.0 g 115-3 CaF2 : Mn Bulb Jun,1977 Lab 89.6 6.4 91.7114.6 86.2 24.0 m Third Internationallntercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas. 4th International Intercomparison 115-4 CaF2 : Mn Bulb Jun,1979 FieId 14.111.1 14.1 1.4 16.0 i 9.0 115-4 CaF2 : Mn Bulb Jun,1979 Lab, High 40.4 1.4 45.819.2 43.9 i 13.2 115-4 CaF2 : Mn Bulb Jun,1979 Lab, Low 9.8 i l.3 12.2 i 2.4 12.0 7.4 Fourth InternationalIntercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas. 5th International Intercomoarison 115-5A CaF2 : Mn Bulb Oct,1980 Field 31.4 1.8 30.0 i 6.0 30.2 14.6 115-5A CaF2 : Mn Bulb Oct,1980 Lab,End 96.6 i 5.8 88.4 i 8.8 90.7 31.2 115-5 A CaF 2: Mn Bulb Oct,1980 Lab, Start 77.4 5.8 75.2 7.6 75.8 i 40.4 Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. 5th International Intercomoat ison 115-5B LiF-100 Chips Oct,1980 Field 30.314.8 30.016.0 30.2 14.6 115-5B LiF-10t Chips Oct,1980 Lab,End 85.4111.7 88.4 i 8.8 90.7 i 31.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.1 7.4 75.217.6 75.8140.4 ) Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy. ) 6th International Intercomoarison
~
l l 115-6 1 Teledyne did not participate in the Sixth International Intercomparisen of Environmental Dositheters. 7th International Intercomparison 115-7A LiF-100 Chips Jun,1984 Field 75.412.6 75.816.0 75.1 29.8 A2-1 l l l
l Tcble A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs). mR Lab Teledyne Results Known Averege i2 Sigma Code TLD Type Date Measurement 2 Sigma Value t 2 Sigma (All Participants) 115-7A LiF-100 Chips Jun,19M Lab, Co-60 80.0 3.5 79.9 4.0 77.9 27.6 115-7A LiF-100 Chips Jun,19M Lab, Cs-137 66.6 2.5 75.0 3.8 73.0 i 22.2 Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of
, 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.
7th International Intercomparison 115-7B LiF-100 Chips Jun,19M Field 71.S i 2.6 75.816.0 75.1 29.8 115-7B LiF-100 Chips Jun,19S4 Lab, Co-60 84.8 i 6.4 79.9 4.0 77.9 i 27.6 I 115-7B LiF-100 Chips Jun,1984 Seventh IntemationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of Lab, Cs-137 78.8 1.6 75.0 3.8 73.0 i 22.2 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory I Commission, and the U.S. Environmental Protection Agency. 7th International Intercomparison 115-7C CaSO.: Dy Jun,19M Field 76.812.7 75.8 6.0 75.1 i 29.8 I Cards Lab, Co-60 115-7C CaSO.: Dy Jun,19M 82.513.7 79.9 i 4.0 77.9127.6 Cards I 115-7C ,CaSO.: Dy Cards Jun,19M Lab, Cs-137 79.0 i 3.2 75.0 3.8 73.0 i 22.2 Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of I 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. 8th International Intercomparison I 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.Sil.4 29.7i l.5 28.9i l2.4 115-8A LiF-100 Chips Jan,1986 Field, Site 2 11.3 i 0.8 10.410.5 10.1 9.1 115-8A LiF-100 Chips Jan,1986 Lab, Cs-137 13.7 i 0.9 17.2 i 0.9 16.2 i 6.8 Eighth Intemational Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy. 8th International Intercomparison 115-8B LiF-100 Chips Jan,1986 Field, Site 1 32.311.2 29.7 1.5 28.9112.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.011.0 10.4 i 0.5 10.li 9.0 I 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 Eighth Intemational intercomparison of Environmental Dosimeters conducted in the fall and winter of 15.8 0.9 17.210.9 16.2 i 6.8 l 1985-19S6 at New York, New York, and sponsored by the U.S. Department of Energy. I 8th InternationalIntercomoarison l 115-8C CaSO.: Dy Jan,1986 Field, Site 1 32.2 0.7 29.7 1.5 28.9112.4 Cards 1 A2 2
o Table A-2. Crosscheck program results;hermoluminescent Dosimeters. (TLDs). Lab Teledyne Results Known Average i2 Sigma Code TLD Type Da te Measurement i 2 Sigma Valuei2 Sigma (All Participants) 115-8C CaSOg Dy Jan,1986 Field, Site 2 10.6 0.6 10.4 0.5 10.119.0 Cards 115-8C Lab, Cs-137 ( CaSOg Dy Jan,1986 18.1 i 0.8 17.2 0.9 16.2'i 6.8 Cards 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. <9th International Intercomparison 115-9 The Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory. 10th Internation,al Intercomparison 115-10A LiF-100 Chips Aug,1993 Field 25.711.4 27.0 1.6 26.4110.2 ' 115-10A LiF-100 Chips Aug,1993 Lab,1 22.7 t l.6 25.9 1.3 25.0 9.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.7 2.6 72.7 t l.9 69.8 i 20.3 g The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State E University and sponsored by the U.S. Department of Energy and the Idaho State University. 10th International Intercomparison g1 115-10B CaSOg Dy Aug,1993 Field 26.0 2.3 27.0 1.6 26.4 i 10.2 E j Cards 1 115-10B CaSOg Dy Aug,1993 Lab,1 24.lil.7 25.911.3 25.0 9.4 Cards l 115-10B CaSOg Dy Aug,1993 Lab,2 69.2 i 3.0 72.7 i 1.9 69.8 i 20.3 Cards The Tenth International Intercomparison of Er,vironmental Dosimeters conducted in 1993 at Idaho Stat University and sponsored by the U.S. Department of Energy and the Idaho Stat University. Teledyne Testing 89-1 LiF-100 Chips Sep,1989 Lab 21.0i0.4 22.4 ND i ND = No Data; Teledyne Testing was only performed by Teledyne. , Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in September,1989. Teledyne Testine 89-2 Teledyne Nov,1989 Lab 20.9 1.0 20.3 ND CaSop Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990 A2-3
\ ,
Table A 2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs). mR f Lab _ Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement 2 Sigma Value i 2 Sigma (All Participants) Teledyne Testing 90-1 Teledyne Jun,1990 Lab 20.6 1.4 ND ( 19.6 CaSo.: Dy Cards ND = No Data, Teledyne Testing was only performed by Teledyne. Cards were irraciated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990. Teledyne Testing 90-2 Triedyne Jun,1990 Lab 100.8 4.3 100.0 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990. Teledyne Testing { 91-1 Teledyne Oct,1990 Lab,1 33.4 i 2.0 32.0 ND CaSo.: Dy Cards { 91-1 Oct,1990 Lab,2 Teledyne 55.214.7 58.8 ND CaSo.: Dy Cards 91-1 Teledyne Oct,1990 Lab,3 87.8 i 6.2 85.5 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991. Teledyne Testing { 92-1 LIF-100 Chips Feb,1992 Lab,1 .11.110.2 10.7 ND 92-1 LiF-100 Chips Feb,1992 Lab,2 25.610.5 25.4 ND Lab,3 ( 92 1 LiF-100 Chips Feb,1992 46.4 0.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992. ( Teledyne Testing 92-2 Teledyne Apr,1992 Reader 1, #1 20.1 0.1 20.1 ND CaSo.: Dy [ Cards 92-2 Teledyne Apr,1992 Reader 1, #2 40.6 i 0.1 40.0 ND CaSo.: Dy [ Cards { r A2-4 L r
, l Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
Lab Teledyne Results Known Average i2 Sigma I Code TLD Type Date Measurement 2 Sigma Value i 2 Sigma (All Participants) 92-2 Teledyne Apr,1992 Reader 1, #3 60.011.3 60.3 ND CaSo.: Dy Cards - 92-2 Teledyne Apr,1992 Reader 2, #1 20.3 i 0.3 20.1 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #2 39.2 0.3 40.0 ND CaSo.: Dy Cards 92-2 Teledyne Apr,1992 Reader 2, #3 60.7 0.4 60.3 ND CaSo.: Dy Cards ND = No Data; Teledyne Testing was only performed by Tcledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in April,1992. Teledyne Testing 93-1 Teledyne Mar,1993 Lab,1 10.011.0 10.2 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,2 25.2 2.2 25.5 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,3 42.7i 5.7 45.9 ND LiF-100 Chips ND = No Data; Teledyne Testing was only performed by Teledyne. Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1993. Due to a potential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is available upon request. Teledyne Testing 94-1 Teledyne Nov,1994 Lab,1 15.6 i 0.4 14.9 ND g LiF 100 Chips g 94-1 Teledyne Nov,1994 Lab,2 30.2 0.4 29.8 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,3 59.210.3 59.7 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Reader 1, #1 '4.910.1
. 14.9 ND CaSo.: Dy Cards 94-1 Tcledyne Nov,1994 Reader 1, #2 30.8 0.1 29.8 ND CaSo.: Dy Cards A2-5 l
3 Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (T1.Ds). mR Lab Teledyne Results Known Average 2 Sigma Ccde TLD Type Date Measurement 2 Sigma Value 2 Sigma (All Participants)- 94 1 Teledyne Nov,1994 Reader 1, #3 58.9 0.3 59.7 ND CaSo.: Dy Cards (' 94-1 Teledyne Nov,1994 Reader 2, #1 15.4 0.2 14.9 ND CaSo.: Dy Cards 94-1 Teledyne Nov,1994 Reader 2, #2 31.4 0.2 29.8 ND CaSo.: Dy Cards 94-1 Teledyne Nov,1994 Reader 2, #3 60.110.3 59.7 ND CaSo.: Dy Cards ND = No Data; Tc!cdyne Testing was only performed by Teledyne. Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in November,1994. A2-6
1
- l
\
Table A-3. In-house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1' Activity Limits SPW-7569 WATER Jul,1995 H-3 25806.9 447.7 26669.0 21335.2 - 32002.8 SPAP-109,6,7 AIR FILTER Nov,1995 Gr. Beta 7.3 0.0 8.0 0.0 - 18.0 SPAP-2513 AIR FILTER Apr,1995 Gr. Beta 7.5 i 0.0 8.1 0.0 - 18.1 , SPAP-2542 AIR FILTER Apr,1995 Cs-137 2.3 2.1 1.9 1.2 - 2.7 SPAP-284 AIR FILTER Jan,1995 Cs-137 2.2 i 0.0 1.9 1.2 - 2.7 SPAP-284 AIR FILTER Jan,1995 I-131(g) 2.2 0.0 1.9 1.2 - 2.7 SPAP-408 AIR FILTER Jan,1995 Gr. Beta 7.5 0.0 8.1 0.0 - 18.1 SPAP-7554 AIR FILTER Jul,1995 Gr. Beta 7.310.0 8.1 0.0 - 18.1 SPAP-7557 AlR F1LTER Jul,1995 Cs-137 2.3 0.0 1.9 1.2 - 2.7 SPCH-11238 CHARCOAL Oct,1995 I-131(g) 0.8 0.0 0.8 0.5 - 1.1 E CANISTER g SPCH-5964 CHARCOAL Jun,1995 I-131(g) 2.2 0.1 2.3 1.4 - 3.3 CANISTER SPCH-717 CHARCOAL Jan,1995 1-131(g) 2.9 0.1 CANISTER 2.5 1.5 - 3.4 l 3 SPF-10921 FISH Oct,1995 Co-60 0.7 0.0 0.8 0.5 - 1.1 SPF-10921 FISH Oct,1995 Cs-134 0.5 0.0 0.6 0.3 - 0.8 SPF-10921 FISH Oct,1995 Cs-137 0.9 0.1 0.9 0.5 - 1.2 - SPF-3708 FISH May,1995 Cs-134 0.1 0.0 0.1 0.1 - 0.2 SPF-3708 FISH May,1995 Cs-137 0.2 0.0 0.2 0.1 - 0.2 SPMI-205 M1LK Jan,1995 Cs-137 51.2 7.5 49.4 39.4 - 59.4 SPMI-205 MILK Jan,1995 Sr-89 19.413.4 MILK 23.1 13.1 - 33.1 g SPMI-205 Jan,1995 Sr-90 26.2 1.3 28.1 18.1 - 38.1 = SPMI-2988 MILK Apr,1995 Cs-134 37.0 1.8 30.7 - 50.7 40.7, SPMI-2988 MILK Apr,1995 Cs-137 62.4 3.1 54.5 44.5 - 64.5 SPMI-2988 MILK Apr,1995 Sr-89 32.6 i 3.3 36.5 26.5 - 46.5 SPMI-2988 MILK Apr,1995 Sr-90 25.6 1.6 24.9 14.9 - 34.9 g SPMI-6838 MILK Jun,1995 I-131 38.5 0.5 39.6 27.6 - 51.6 E SPMI-707 MILK Jan,1995 I-131 80.3 1.4 86.0 68.8 - 103.2 SPMI-707 MILK Jan,1995 I-131(g) 84.8 i 10.4 86.0 51.6 - 96.0 ) SPMI-7525 MILK Jul,1995 Cs-134 31.512.5 34.4 24.4 - 44.4 SPMI-7525 MII.K Jul,1995 Cs-137 50.2 4.0 43.4 33.4 - 53.4 SPMI-7525 ie ILK Jul,1995 1-131(g) 44.7 i 5.4 45.6 27.4 - 55.6 SPMI-7525 ?.!!LK Jul,1995 Sr-90 28.0 i 1.4 27.9 17.9 - 37.9 SPSO-5130 50'l May,1995 Cs-134 0.3 0.0 0.3 0.2 - 0.4 SPSO-5130 SOIL May,1995 Cs-137 0.5 0.0 0.5 0.3 - 0.7 A3-1
Table A-3. In house " spike" samples. Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1' Activity Limits SPVE-6006 VEGETATION Jun,1995 I-131(g) 0.6 0.0 0.5 0.3 - 0.8 SPVE-7190 VEGETATION Jul,1995 I-131(g) 1.1 0.0 1.0 0.6 - 1.4 SPVE-729 VEGETATION Feb,1995 I-131(g) 1.9i 0.1 1.9 1.1-2.6 SPW-1204 WATER Feb,1995 Ra-226 6.910.1 6.9 4.8 - 9.0 SPW-12079 WATER Nov,1995 H-3 27963.4 445.5 29315.0 23452.0 - 35178.0 SPW-12084 WATER Nov,1995 Gr. Alpha 75.3 i 3.2 82.8 41.4 - 124.2 SPW 12084 WATER Nov,1995 Gr. Beta 86.912.5 86.3 76.3 - 96.3 I SPW 1790 WATER Mar,1995 Sr-89 0.9 3.9 42.7 The raw data was reviewed and found to be free of errors. The sample was repeated with similar 32.7 - 52.7 results.An Investigation was conducted to determine the cause of this deviation. No apparent cause was I found for this discrepancy. It was determined the " spike" was prepared improperly. Another " spike" was prepared and analyzed (See SPW-63SS). No further action is planned. SPW-1790 WATER Mar,1995 Sr-90 31.4 i l .8 39.1 31.3 - 46.9 I The raw data was reviewed and found to be free of errors. The sample was repeated with similar results.An Investigation was conducted to determine the cause of this deviation. No apparent cause was found for this discrepancy. It was determined the " spike" was prepared improperly. Another " spike" was prepared and analyzed (See SPW-63S8). No further action is planned. SPW-2544 WATER Apr,1995 H-3 9656.2 291.8 9333.0 7466.4 - 11199.6 SPW-2652 WATER Apr,1995 Co-60 23.8 i 2.4 24.8 14.8 - 34.8 i SPW-2652 WATER WATER Apr,1995 Cs-134 29.312.3 30.8 20.8 - 40.8 SPW-2652 Apt,1995 Cs-137 42.3i 3.9 40.9 30.9 - 50.9 SPW-286 WATER Jan,1995 H-3 10929.9 i 5594.5 40871.0 32696.8 - 49045.2 SPW-289 WATER Jan,1995 Co-60 G0.5 14.1 247.5 222.8 - 272.3 SPW-289 WATER Jan,1995 Cs-134 290.5 14.4 321.3 289.2 - 353.4 I SPW-289 WATER WATER Jan,1995 Cs-137 387.71 21.2 394.3 354.9 - 433.7 SPW-3051 Mar,1995 Gr. Alpha 88.5 3.7 82.9 41.5 - 124.4 WATER I SPW-3051 SPW-3051 WATER Apr,1995 Gr. Alpha Mar,1995 Gr. Beta 88.0 3.8 83.012.3 82.9 87.2 41.5 - 124.4 77.2 - 97.2 SPW-3051 WATER Apr,1995 Gr. Beta 79.6 i 2.3 87.2 77.2 - 97.2 SPW-3589 WATER May,1995 Fe-55 2033.7 t S00.2 2274.0 1819.2 - 2728.8 SPW-5608 WATER Jun,1995 I-131 78.812.3 85.5 68.4 - 102.6 l WATER Jun,1995 I-131 I SPW-6005 SPW-6008 WATER May,1995 Gr. Alpha 48.2 i l.9 17.3i 1.4 46.8 20.7 34.8 - 58.8 10.4 - 31.1 SPW-6008 WATER May,1995 Gr. Beta 21.211.0 21.8 11.8 - 31.8 SPW-6388 WATER May,1995 Sr-89 18.712.4 21.2 11.2 - 31.2 SPW-6388 WATER May,1995 St-90 21.211.1 23.2 13.2 - 33.2 l l ~ A3-2
1
. I Table A-3. In-house " spike" samples.
Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1' Activity Limits SPW-6398 WATER May,1995 Sr-89 18.7 i 2.4 21.2 11.2 - 31.2 SPW-6398 WATER May,1995 St-90 21.2 1.1 23.2 13.2 - 33.2 SPW-6839 WATER Jun,1995 I-131 34.9 i 0.5 39.5 27.5 - 51.5 SPW-8179 WATER Jul,1995 Fe-55 2.3 0.4 2.1 0.0 - 22.1 SPW-9981 WATER Sep,1995 St-89 34.6 4.9 39.0 29.0 - 49.0 SPW-9981 WATER Sep,1995 Sr-90 20.311.3 20.0 10.0 - 30.0 All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/ Filter; and food products, which are in mg/kg. ' All samples are the results of single determinations.
- Control limits are based on Attachment A, page A2 of this report.
NO'IE: For fish, Jello is used for the spike matrix. For vegetation, Sawdust is used for the spike matrix. I A3-3 i
Table A-4. In house " blank" samples. Concentration pCi/L*.
, Teledyne Result 5 Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma)
SPAP-10968 AIR FILTER Novl995 Gr. Beta < 0. 4 0.61 0.26 < 3.2 SPAP-2514 AIR FILTER Apr1995 Gr. Beta <0.3 0.03 0.25 <3.2 I. l SPAP-2543 AIR FILTER Apr1995 Co-60 <4.4 0.39 2.20 < 10.0 SPAP-2543 AIR FILTER Apr1995 Cs 134 < 1.9 0.05 2.11 < 10.0 SPAP-2543 AIR FILTER Apr1995 Cs 137 < 1.1 -1.24 1.83 < 10.0 SPAP-283 AIR FILTER Jan 1995 Co-60 <2.7 -0.36 1.40 < 10.0 SPAP-283 AIR FILTER Jan 1995 Cs-134 <1.5 -0.6711.33 < 10.0 l SPAP 283 AIR FILTER Jan 1995 Cs 137 <2.4 0.46 1.33 < 10.0 SPAP-409 AIR FILTER Jan 1995 Gr. Beta <0.5 0.0210.28 < 3.2 SPAP-7556 AIR FILTER Jul1995 Gr. Beta < 1.0 0.06 0.55 < 3.2 SPAP-7558 AIR FILTER Jul1995 Co-60 <4.2 0.39 i 3.06 < 10.0 SPAP-7558 AIR FILTER Jul1995 Co-60 <4.2 0.0413.07 < 10.0 l SPAP-7558 AIR FILTER Jul1995 Cs 134 <3.0 -1.2312.45 < 10.0 SPAP-7558 AIR FILTER Jul1995 Cs-137 <3.5 1.18 2.04 < 10.0 SPCH-11238 CHARCOAL Oct 1995 I-131(g) < 1.9 -0.0010.01 < 9.6 l CANISTER SPCH-287 CHARCOAL Jan 1995 I-131(g) <2.3 -1.9813.12 < 9.6 CANISTER SPCH-5975 CHARCOAL Jun1995 I-131(g) <3.0 -0.71 2.68 < 9.6 CANISTER SPF-10922 FISH Oct 1995 Co-60 <5.4 5.74 4.70 < 10.0 SPF-10922 FISH Oct 1995 Cs-134 <8.9 2.47 5.44 < 10.0 SPF-10922 FISH Oct 1995 Cs-137 <5.4 -2.4415.08 < 10.0 l SPF-3709 FISH May1995 Co-60 <8.4 2.21 i 5.97 < 10.0 SPF-3709 FISH May1995 Cs-134 < 1.3 6.79 8.55 < 10.0 SPF-3709 FISH May1995 Cs-137 <1.3 3.6117.81 < 10.0 SPM-204 MILK Jan 1995 Co-60 <5.3 0.4113.48 < 10.0 SPM-204 MILK Jan 1995 Cs-134 <4.4 -0.07 2.05 < 10.0 l SPM-204 MILK Jan 1995 Cs-137 <4.3 1.32 2.53 < 10.0 SPM-204 MILK Jan 1995 I-131 <0.5 -0.0310.22 < 0.5 SPM 204 MILK Jan 1995 Sr-89 <0.8 0.1411.08 < 5.0 SPM-204 MILK Jan 1995 Sr-90 N/A 1.4610.48 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. I SPMI-10920 MILK Oct 1995 Co-60 <3.8 -0.4515.05 < 10.0 SPMI-10920 MILK Oct 1995 Cs-134 <3.5 -2.7914.35 < 10.0 I L A4-1
.~..--.u.. . . .
1 Table A-4. In-house " blank" samples. Concentration pCi/L*. Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria l Code Type Date Analysis LLD Activity" (4.66 Sigma) , SPMI-10920 MILK Oct 1995 Cs-137 <6.0 1.55 i 4.13 < 10.0 SPMI-2987 MILK Apr1995 Cs-134 <3.4 0.37 1.d9 < 10.0 SPMI-2987 MILK Apr 1995 Cs-137 <3.3 1.29 1.75 < 10.0 SPMI-2987 MILK Apr1995 Sr-89 <0.4 0.0610.62 <5.0 SPMI-2987 MILK Apr1995 Sr-90 N/A 1.47 0.38 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPMI-7526 MILK Jul1995 Co-60 <5.8 1.19 i 3.34 < 10.0 SPMI-7526 MILK Jul1995 Cs-134 < 5.1 0.4S 1 2.76 < 10.0 SPMI-7526 MILK Jul1995 Cs-137 <3.7 0.98 2.39 < 10.0 SPMI-7526 MILK Jul1995 I-131 <0.5 0.00 i 0.23 <0.5 SPMI-7526 MILK Jul1995 Sr-89 <0.6 -0.19 i 0.82 < 5.0 SPMI-7526 MILK Jul1995 Sr-90 N/A 1.35 0.36 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. SPSO-11225 SOIL Oct 1995 Cs-134 <0.034 0.00 0.02 < 10.0 SPSO-11225 SOIL Oct 1995 Cs-137 <0.019 -0.0010.01 < 10.0 SPSO-5131 SOIL May1995 Cs-134 <0.034 0.01 0.01 < 10.0 SPSO-5131 SOIL May 1995 Cs-137 <0.012 0.00 i 0.01 < 10.0 SPVE-6007 VEGETATION Jun1995 I-131(g) <0.009 0.0010.01 < 20.0 SPVE-7191 VEGETATION Jul1995 I131(g) <0.005 -0.00 i 0.00 < 20.0 SPVE-728 VEGETATION Jan1995 I-131(g) <12.0 2.33 i 7.54 < 20.0 SPW-1106 WATER Feb l995 Ni-63 <12.0 0.25 6.31 < 20.0 SPW-12080 WATER Nov 1995 H-3 <149 23.01 74.94 < 200.0 SPW-12082 WATER Nov1995 Co-60 <2.1 0.62 i 1.13 < 10.0 SPW-12082 WATER Novl995 Cs-134 < 1.9 0.02 1.28 < 10.0 SPW-12082 WATER Nov1995 Cs-137 <2.4 1.53 i l.22 < 10.0 SPW-12082 WATER Novl995 Gr. Alpha <0.6 0.19 i 0.43 < 1.0 SPW-12082 WATER Nov i995 Gr. Beta < 1.7 0.0611.11 < 3.2 SPW-2545 WATER Apr1995 H-3 <169 97.76 i 88.37 < 200.0 SPW-2651 WATER Apr1995 Co-60 <3.17 -1.08 i 2.45 < 10.0 SPW-2651 WATER Apr1995 Cs-134 <3.32 0.29 2.57 < 10.0 < SPW-2651 WATER Apr 1995 Cs-137 <3.56 -0.92 2.64 < 10.0 SPW-285 WATER Jan 1995 H-3 <165.0 -48.53 i 84.76 < 200.0 SPW 288 WATER Jan 1995 Co-60 <2.3 -0.11 2.02 < 10.0 SPW-288 WATER Jan 1995 Cs-134 <3.5 -0.19 2.61 < 10.0 A4-2
Table A-4. In-house " blank" samples. Concentration pCi/L'. Teledyne Results Acceptance Lab Sample , ample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma) SPW-288 WATER Jan 1995 Cs-137 <4.7 0.98 2.54 < 10.0 SPW-3052 WATER Mar 1995 Gr. Alpha 40.6 0.49 0.43 < 1.0 SPW-3052 WATER Apr1995 Gr. Alpha <0. 7 0.23 i 0.47 < 1.0 SPW-3052 WATER Mar 1995 Gr. Beta < 1.4 3.05 0.98 <3.2 SPW-3052 WATER Apr 1995 Gr. Beta < 1.7 -0.02 1.09 <3.2 SPW-3590 WATER May 1995 Fe-55 <602.0 0.00 365.40 < 1000.0 SPW-6011 WATER Jun 1995 I-131 <0.4 -0.03 0.19 <0.5 SPW-7570 WATER Jul1995 H-3 <164 51.58 83.71 < 200.0 SPW-8180 WATER Ju11995 Fe-55 <0.4 0.00 0.27 < 1000.0 SPW-8931 WATER Aug1995 Ra-228 < 1.0 0.58 0.61 < 1.0 SPW-957 WATER Feb l995 Co-60 <3.7 -1.25 3.02 < 10.0 SPW-957 WATER Feb l995 Cs-134 <5.2 0.76 2.77 < 10.0 SPW-957 WATER Feb l995 Cs-137 <3.6 -1.38 2.65 < 10.0 SPW-9982 WATER Sep 1995 Sr-89 <0.8 0.52 i 0.76 < 5.0 SPW-9982 WATER Sep 1995 Sr-90 <0.4 0.21 0.21 < 1.0
- Liquid sample results are reported in pCi/ Liter, air filter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.
- The activity reported is the net activity result.
A4-3
e Table A-5. In-house " duplicate" samples. E Concentration in pCi/L' Lab Sample First Second Averaged I Codes
- Date Analysis Result Result Result WW-62, 63 Jan,1995 Gr. Beta 1.4160 0.4220 1.2900 0.4000 1.3530 0.2907 l WW-62, 63 Jan,1995 H3 22.5635 i 80.8891 18.8029 80.7140 20.6832 57.1354 l WW-41, 42 Jan,1995 Gr. Alpha I - 5.0970 1 2.5260 2.4790 2.1920 3.7880 1.6722 WW-41, 42 Jan,1995 Gr. Beta 4.6720 0.8260 4.9650 0.8770 4.8185 1 0.6024 l WW-41, 42 Jan,1995 H-3 30.0800 81.2250 -47.0000 77.7750 -8.4600 56.2282 WW-41, 42 Jan,1995 K-40 1.3840 1 0.2076 1.7300 i 0.2595 1.5570 i 0.1662 WW-41, 42 Jan,1995 Sr-89 -0.3474 0.5730 -0.0685 0.5382 -0.2079 0.3931 WW-41, 42 $r-90 0.2017 i 0.2519 0.1389 0.2174 0.1703 0.1664 Jan,1995 g CF-20, 21 Jan,1995 Be-7 0.4327 i 0.1200 0.4741 1 0.1250 0.4534 0.0866 m CF-20, 21 Jan,1995 Gr. Beta 2.9120 i 0.0930 2.9920 t 0.0920 2.9520 0.0654 CF-20, 21 Jan,1995 K-40 4.0808 i 0.3060 3.7714 i 0.3050 3.9261 0.2160 CF-20, 21 Jan,1995 Sr-89 0.0013 1 0.0043 0.0000 0.0058 0.0007 i 0.0036 CF-20, 21 Jan,1995 Sr-90 0.0017 0.0011 0.0026 1 0.0015 0.0021 i 0.0009 CW-105,106 Jan,1995 Gr. Beta 5.4370 0.9970 6.1900 i 1.0260 5.8135 i 0.7153 CW-105,106 Jan, ly. 5 Gr. Beta 0.0490 1 0.4360 0.0590 1 0.4360 0.0540 1 0.30S3 MI-83, 84 Jan,1995 Co-60 -0.3330 2.5300 0.6530 2.1700 0.1600 1.6666 MI-83, 84 Jan,1995 Cs-137 -1.1400 2.2700 0.0761 1.8700 -0.5320 1 1.4705 MI-83, 84 Jan,1995 1-131(G) -1.9100 3.2000 1.4700 2.4700 -0.2200 2.0212 MI-187,188 Jan,1995 I-131 0.1496 i 0.2574 0.2682 0.3828 0.2089 i 0.2306 Mi-187,188 Jan,1995 K-40 1,573.0000 138.0000 1,426.0000 177.0000 1,499.5000 112.2197 SW-213, 214 Jan,1995 H-3 5,939.6340 1 241.2390 6,091.2412 232.8063 6,015.4376 i 167.6269 WW-240, 241 Jan,1995 H-3 39.8030 80.3410 9.9510 78.9420 24.8770 i S6.3172 WW-316, 317 Jan,1995 H-3 17,618.0000 377.0000 17,390.0000 381.0000 17,504.0000 267.9972 MI-295, 296 Jan,1995 Co-60 -1.0900 i 2.3700 0.2510 2.8000 -0.4195 i 1.8342 Mi-295, 296 Jan,1995 Cs-134 -0.6360 i 1.8100 0.7830 2.4400 0.0735 1.5190 MI-295, 296 Jan,1995 Cs-137 0.5200 1.8200 1.2900 2.6800 0.9050 1.6193 l Mi-295, 296 Jan,1995 1-131 0.1300 0.2600 0.2300 0.3400 0.1800 0.2140 !
MI-295, 296 Jan,1995 1-131(g) -0.3970 2.3600 -0.0386 i 4.3000 -0.2178 2.4525 i M!-295, 296 Jan,1995 K-40 1,449.1000 91.2000 1,311.8000 1 108.0000 1,380.4500 70.6779 l MI-295, 296 Jan,1995 La-140 0.6220 i l.6900 -1.1800 2.5000 -0.2790 1.50SS MI-295, 296 Jan,1995 Sr-89 0.2267 1 0.7985 0.1552 1 0.9326 0.1909 i 0.6139 MI-295, 296 Jan,1995 Sr-90 1.3813 i 0.3839 1.6174 i 0.4296 1.4993 1 0.2881 ) LW-609, 610 Jan,1995 Gr. Beta 2.6380 i 0.7310 1.6940 i 0.6930 2.1660 i 0.5036 LW-344, 345 Jan,1995 Co-60 -0.1680 1 1.8700 1.5200 i 3.1100 0.6760 1.8145 LW-344, 345 Jan,1995 Cs-137 0.3820 1 1.9200 -0.1570 i 2.9500 0.1125 i 1.7599 LW-344, 345 Jan,1995 Gr. Beta 3.2810 1 0.9440 3.3500 0.9390 3.3155 0.6657 i A5-1
l l Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result MI-374, 375 Jan,1995 I-131 -0.0572 0.2162 -0.0743 0.2780 -0.0658 1 0.1761 MI-374,375 Jan,1995 K-40 1,250.0000 i 150.0000 1,286.5000 141.0000 1,268.2500 1 102.9332 kJan,1995 Gr. Beta 1.8970 0.5970 1.9470 0.6020 1.9220 0.4239 i SW-463,464 SW-463, 464 . Jan,1995 H-3 35.5580 1 80.3070 7.4860 78.9880 21.5220 56.3212 WWU-860, 861 Jan,1995 Gr. Alpha 0.3000 0.6000 0.2000 0.3000 0.2500 0.3354 WWU-860, 861 Jan,1995 Gr. Beta 0.8450 1.3200 1.7600 1.3500 1.3025 0.9440 WWU-860, 861 Jan,1995 K-40 61.8050 32.9000 70.9860 36.2000 66.3955 24.45S4 Jan,1995 Co-60 -2.1600 2.2900 1.9400 1 2.7500 -0.1100 i 1.7893 i SW-586,587 SW-586, 587 Jan,1995 Cs-137 0.5590 2.3400 1.5000 2.8800 1.0295 1.8554 WW-547, 548 Jan,1995 H-3 602.5630 i 102.9290 619.5980 103.5540 611.0805 73.0031 SWT-715, 716 Jan,1995 Gr. Beta 2.3000 1 0.6000 2.3000 0.5000 2.3000 i 0.3905 SW-694, 695 Feb,1995 Gr. Beta 3.9100 1 0.7450 4.1790 0.7550 4.0445 i 0.5303 Feb,1995 H-3 9,951.8722 284.2655 10,200.7626 287.5238 10,076.3174 202.1613 I WW-736,737 WW-763, 764 Feb,1995 H-3 584.4290 101.0550 707.1020 105.5380 645.7655 73.0589 MI-881, 882 Feb,1995 I-131 0.1760 0.2567 0.1552 0.2852 0.1656 0.1919 MI-881, 882 Feb,1995 K-40 1,340.4000 i 164.0000 1,492.0000 i 101.0000 1,416.2000 96.3029 MI-838, 839 Feb,1995 Co-60 0.9670 i 2.6500 -0.4760 3.8100 0.2455 2.3205 MI-838, 839 Feb,1995 Cs-134 -0.0557 2.2800 -1.4200 i 3.0900 -0.7379 1.9201 I MI-838,839 Feb,1995 Cs-137 -0.4380 i 2.5500 -0.4370 i 3.0900 -0.4375 i 2.0032 MI-838, 839 Feb,1995 I-131 0.1283 i 0.1951 0.0880 i 0.1984 0.1081 0.1391 MI-838, 839 Feb,1995 I-131(g) -0.2560 i 2.5800 -0.5630 i 3.1800 -0.4095 i 2.0475 MI-838,839 Feb,1995 K-40 1,298.6000 i 99.4000 1,232.5000 1 125.0000 1,265.5500 i 79.8520 Feb,1995 Sr-89 0.5302 0.5774 0.5000 1 0.6000 0.5151 1 0.4164 I Mi-S38,839 Ml-838,839 Feb,1995 Sr-90 0.8186 1 0.2809 0.8000 1 0.?900 0.8093 0.2055 MI-937., 938 Feb,1995 I-131 -0.0083 0.1800 -0.0270 1 0.1800 -0.0177 1 0.1273 MI-937,938 Feb,1995 K-40 1,451.8000 i 69.6000 1,456.6000 1 141.0000 1,454.2000 78.6212 SW-904, 905 Feb,1995 H-3 640.3425 i 104.5679 597.4040 i 103.0233 618.8733 73.3966 Feb,1995 I-131 0.2640 i 0.2740 0.1160 i 0.2600 0.1900 0.1889 I MI-1216,1217 MI-1216,1217 Feb,1995 K-40 1,583.0000 i 131.0000 1,493.6000 i 174.0000 1,538.3000 108.9002 SW-1237,1238 Feb,1995 H-3 55.3942 i 97.3964 4.8591 i 95.3581 30.1267 i 68.1528 SW-1264,1265 Feb,1995 H-3 67.0910 1 81.1760 109.2630 1 83.1440 88.1770 58.1001 G-1343,1344 Feb,1995 Be-7 11.4490 i 0.2850 11.8800 i 0.2560 11.6645 t 0.1915 j G-1343,1344 Feb,1995 K-40 2.9844 0.2420 3.0269 0.2250 3.0057 i 0.1652 B SW-1494,1495 Feb,1995 Co-60 -2.1900 i 4.1200 0.0565 i 3.4400 -1.0668 t 2.6837 SW-1494,1495 Feb,1995 Cs-137 3.4500 3.6600 0.2430 1 3.5700 1.8465 t 2.5564 SW-1367,1368 Feb,1995 H-3 560.3183 1 103.1109 606.1104 i 104.7919 583.2144 i 73.5072 A5-2
I Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Cedes
- Date Analysis Result Result Result WW-1394,1395 Feb,1995 H-3 47.8310 80.1790 -24.8930 76.6250 11.4940 55.4528 SWT-1515,1516 Feb,1995 Gr. Beta 2.4460 0.5250 1.6920 0.5000 2.0690 1 0.3625 I WW-1536,1537 Feb,1995 H-3 2,874.3025 i 167.5000 2,924.0574 168.6330 2,899.1800 118.8416 WW-1563,1564 Mar,1995 H-3 33.5160 1 82.6640 39.5490 82.9570 36.5325 i 58.5560 WW-1618,1619 Mar,1995 Co-60 2.8000 1.5000 2.2000 4.6000 2.5000 2.4192 WW-1618,1619 Mar,1995 Cs-137 -0.9000 1.7000 -2.5000 i 3.2000 -1.7000 1.8118 WW-1618,1619 Mar,1995 H-3 4,333.0000 204.0000 4,457.0000 206.0000 4,395.0000 144.9586 MI-1663,1664 Mar,1995 Co-60 1.9500 3.2400 -1.5300 i 2.7200 0.2100 2.1152 MI-1663,1664 Mar,1995 Cs-134 0.1690 2.7700 -1.1300 2.0500 -0.4805 1.7230 MI-1663,1664 Mar,1995 Cs-137 -0.0737 2.7400 0.9210 i 2.4100 0.4237 1.8245 MI-1663,1664 Mar,1995 I-131 0.1226 0.2720 0.2261 0.3010 0.1744 0.2028 MI-1663,1664 Mar,1995 I-131(g) -0.4090 1 3.7100 0.1220 1 3.4200 -0.1435 2.5229 MI-1663,1664 Mar,1995 K-40 1,592.1000 124.0000 1,555.6000 t 118.0000 1,573.8500 85.5862 MI-1663,1664 Mar,1995 1.a-140 -1.6500 1 3.1000 g
-0.2240 2.6800 -0.9370 2.0489 m MI-1663,1664 Mar,1995 Sr-89 0.59S4 0.6672 0.5889 1 0.7467 0.5937 1 0.5007 MI-1663,1664 Mar,1995 Sr-90 1.3624 1 0.3718 1.5034 0.4517 1.4329 0.2925 WW-1684,1685 Mar,1995 Gr. Beta 4.9280 0.7420 5.0100 0.7400 4.9690 1 0.5240 WW-1684,1685 Mar,1995 H-3 81.7160 i 84.9140 85.7340 i 85.1040 83.7250 60.1105 LW-1707,1708 Mar,1995 Co-58 0.4070 3.0300 0.0486 2.8500 0.2278 i 2.0799 LW-1707,1708 Mar,1995 Co-60 1.0600 i 2.8900 1.5000 2.7000 1.2800 i 1.9775 LW-1707,1708 Mar,1995 Cs-134 -1.8600 1 3.0500 -1.5400 2.8300 -1.7000 i 2.0803 LW-1707,1708 Mar,1995 Cs-137 2.5900 i 2.9600 -1.3700 2.5100 0.6100 1.9405 LW-1707,1708 Mar,1995 Fe-59 5.5200 i 6.1500 -6.6900 1 6.1500 -0.5850 4.3487 LW-1707,1708 Mar,1995 Gr. Deta 1.9570 1 0.4850 2.1270 0.4760 2.0420 1 0.3398 LW-1707,1708 Mar,1995 I-131 0.2350 i 0.2925 -0.0500 0.2859 0.0925 i 0.2045 LW-1707,1708 Mar,1995 I-131(g) -0.6900 i 6.6800 -0.6210 1 6.2000 -0.6555 i 4.5569 LW-1707,1708 Mar,1995 K-40 79.3000 42.8000 75.3000 39.2000 77.3000 29.0193 LW-1707,1708 Mar,1995 La-140 -3.5900 i 5.0900 1.2800 i 4.5800 -1.1550 i 3.4236 LW-1707,1708 Mar,1995 Mn-54 -1.9300 i 3.1200 0.7640 2.5200 -0.5830 1 2.0053 LW-1707,1708 Mar,1995 Ru-103 -0.1320 i 3.3400 -0.7770 2.9700 -0.4545 2.2348 LW-1707,1708 Mar,1995 Zn-65 -2.6700 6.4700 -1.7400 1 5.7700 -2.2050 i 4.3346 LW-1707,1708 Mar,1995 Zr-Nb-95 -0.2680 1 3.0600 -3.2400 1 2.7200 -1.7540 1 2.0471 SW-1762,1763 Mar,1995 H-3 104.4150 1 89.3960 92.2110 i 88.8390 98.3130 1 63.0159 S O-1861, 1862 Mar,1995 Cs-137 0.2587 1 0.0414 0.2481 0.0248 0.2534 i 0.0241 S O-1861, 1862 Mar,1995 K-40 11.7290 1 0.5530 11.2500 i 0.4990 11.4895 i 0.3724 S O-1861, 1862 Mar,1995 Ra-226 1.6890 0.3970 1.5274 U.2730 1.6082 i 0.2409 A5-3
i 7 se Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Ana?ysis Result Result Result SW 1919,1920 Mar,1995 H-3 -9.1230 1 85.2000 66.6680 88.8670 28.7725 1 61.5556 SW-1919,1920 Mar,1995 H-3 -9.1230 85.2005 66.6679 88.8672 28.7725 61.5559 Mar,1995 Gr. Alpha 1.9830 2.2510 3.0330 2.4400 2.5080 1.6599 IWWU-2031, 2032 WWU-2031, 2032 Mar,1995 Gr. Deta 1.2540 1.9270 2.1120 1.9680 1.6830 1 1.3772 CW-1997,1998 Mar,1995 Gr. Beta 2.6670 0.9880 2.3100 1.3570 2.4S85 i 0.8393 CW-1997,1998 Mar,1995 Gr. Beta -0.5301 0.9521 0.6351 1 1.1355 0.0525 0.7409 AP-2784, 2785 Mar,1995 Co-60 -0.0004 1 0.0006 -0.0003 0.0005 -0.0003 0.0004 Mar,1995 Cs-137 -0.0003 0.0006 0.0001 0.0004 -0.0001 0.0004 i AP-2784,2785 MI-2083, 2084 Mar,1995 I-131 0.0210 0.1920 0.0150 1 0.1850 0.0180 1 0.1333 MI 2083,20S4 Mar,1995 K-40 1,273.9000 69.7000 1,328.9000 59.8000 1,301.4000 1 45.9188 MI 2083,2084 Mar,1995 Sr-90 1.5850 1 0.4530 1.8040 0.5520 1.6945 0.3570 SW-2104, 2105 Mar,1995 Gr. Deta 1.6690 i 0.5320 1.7090 i 0.5640 1.6890 i 0.3877 SW-2200, 2201 Mar,1995 H3 33.7710 85.6270 54.0340 86.5810 43.9025 i 60.8857 ISW-2355,2356Mar,1995 Co-60 0.6430 i 1.5100 0.8670 1.5800 0.7550 i 1.0928 SW-2355, 2356 Mar,1995 Cs-137 2.2000 i 1.5400 0.0533 i 1.8500 1.1267 1 1.2035 AP-2453, 2454 Mar,1995 Sr-89 0.0002 1 0.0006 -0.0001 0.0006 0.0000 0.0004 AP-2453, 2454 Mar,1995 St-90 0.0000 1 0.0002 0.0001 0.0003 0.0001 0.0002 AP-2805, 2806 Mar,1995 Co-60 -0.0001 i 0.0004 0.0002 0.0003 0.0000 i 0.0002 I AP-2805,2806 Mar,1995 Cs-137 0.0002 0.0004 0.0000 0.0004 0.0001 0.0003 SW-2221, 2222 Mar,1995 K-40 149.6900 1 74.4000 119.3800 46.7000 134.5350 43.9211 PW-2248, 2249 Mar,1995 H-3 154.6240 i 91.0610 164.7520 91.5110 159.6880 1 64.5491 PW-2271, 2272 Mar,1995 Co-60 -0.4760 1.9800 -1.2100 2.8900 -0.8430 1.7516 Mar,1995 Cs-137 0.9590 2.0500 0.8750 i 3.4600 0.9170 1 2.0109 IPW-2271,2272 M1-2149,2150 Apr,1995 Co-60 -1.2100 1 2.2200 0.6560 2.6900 -0.2770 i 1.7439 Mi-2149,2150 Apr,1995 Cs-137 0.1650 i 2.0400 2.3100 i 2.2200 1.2375 i 1.5075 Mi-2149,2150 Apr,1995 I-131(G) 0.0888 i 2.2200 0.3000 2.5100 0.1944 1.6754 WW-2313, 2314 Apr,1995 G r. Beta 0.5850 1 0.4990 0.9810 i 0.5230 0.7830 i 0.3614 CW-2401, 2402 Apr,1995 Gr. Deta 1.7069 i 1.2973 3.4661 1.4515 2.5865 i 0.9734 ICW-2401,2402 Apr,1995 Gr. Beta 0.0096 i l.1238 0.4760 1.1031 0.2428 i 0.7874 SL-2567, 2568 Apr,1995 K-40 1.4123 0.4360 1.7225 0.3760 1.5674 0.2879 WW-2432, 2433 Apr,1995 H-3 -21.5803 i 82.7489 2.6975 i 83.9276 -9.4414 i 58.9305 WW-2659, 2660 Apr,1995 Gr. Beta 0.5450 1 0.6040 0.3970 0.4440 0.47101 0.3748 WW-2659, 2660 Apr,1995 H-3 38.3900 i 87.4520 133.3540 1 91.7350 85.8720 i 63.3703 IMl 2713,2714 Apr,1995 I131 0.3870 1 0.5277 0.1686 i 0.2430 0.2778 i 0.2905 Mi-2713, 2714 Apr,1995 K-40 1,420.9000 i 137.0000 1,420.0000 137.0000 1,420.4500 1 96.8736 CW-2739, 2740 Apr,1995 Gr. Beta 13.7987 1 2.0770 14.3132 1 2-1038 14.0560 1.4782 AS-4
I Ill Table A-5. In-house " duplicate" samples. Iii Concentration in pCi/L' ) Lab Sample First Second Averaged 6 Codes Date Analysis Result Result Result I CW-2739, 2740 Apr,1995 Gr. Beta 5.0526 1.5206 2.2742 1.3431 3.6634 i 1.0144 SW-2686, 2687 Apr,1995 H-3 52.6753 1 86.9675 2.0260 84.5748 27.3506 60.6552 WW 3447, 3448 Apr,1995 Gr. Alpha -0.2920 i l.6860 -1.4650 1.6480 -0.8785 i 1.1788 - WW-3447, 3448 Apr,1995 Gr. Beta 1.2340 1.7000 3.1840 1 1.8140 2.2090 1 1.2430 CW-2835, 2836 Apr,1995 Gr. Beta 1.9571 1.4080 2.7378 1.4641 2.3474 1 1.0157 CW-2835, 2836 .Apr,1995 Gr. Beta 0.1817 1.1916 0.8185 1.2403 0.5001 0.8600 CW-2918, 2919 Apr,1995 Gr. Beta 5.3065 1.6254 4.2821 1 1.5611 4.7943 1.1268 CW-2918, 2919 Apr,1995 Gr. Beta 2.0988 1.3349 0.7752 1 1.2404 1.4370 0.9111 F-3552, 3553 Apr,1995 K-40 3.1142 0.4410 2.8860 i 0.2410 3.0001 1 0.2513 ! F-3552, 3553 Apr,1995 Sr-89 -0.0061 1 0.0064 0.0011 0.0080 -0.0025 0.0051 F-3552,3553 Apr,1995 Sr-90 0.0023 0.0029 0.0005 0.0036 0.0014 i 0.0023 SWT-3343, 3344 Apr,1995 Gr. Beta 2.3310 0.5190 2.9 8.30 0.4800 2.6570 0.3535 G-3133,3134 Apr,1995 K-40 6.5000 0.1740 6.0532 i 0.3120 6.2766 i 0.1786 SW-3403, 3404 Apr,1995 H-3 159.5512 90.5914 72.7069 86.6327 116.1290 62.6738 WW-3424, 3425 Apr,1995 H-3 442.5093 116.7309 430.4409 i 116.3142 436.4751 82.3940 LW-3682, 3683 Apr,1995 Gr. Beta 2.0500 0.5760 1.5240 0.5500 1.7870 0.3982 LW-3682, 3683 Apr,1995 Gr. Deta 2.0501 i 0.6760 1.5244 0.5500 1.7872 i 0.4358 LW-3682, 3683 Apr,1995 H-3 139.9350 i 91.1490 75.0380 88.2140 107.4865 63.4229 g LW-3682, 3683 Apr,1995 H-3 75.0378 88.2143 139.9353 1 91.1494 107.4865 i 63.4231 3 S 0-3531, 3532 May,1995 Cs-137 0.1624 0.0246 0.1418 i 0.0306 0.1521 0.0196 S O-3531, 3532 May,1995 Gr. Alpha 6.8662 3.5751 9.2164 i 3.8687 8.0413 i 2.6338 S 0-3531, 3532 May,1995 Gr. Beta 17.0973 i 3.0829 18.8034 i 3.1329 17.9503 i 2.1977 S O-3531, 3532 May,1995 K-40 25.03SOi 0.7710 23.8180 i 0.6600 24.4280 0.5075 S 0-3531, 3532 May,1995 Sr-89 -0.0129 0.0215 0.0014 i 0.0202 -0.0057 i 0.0147 S O-3531, 3532 May,1995 Sr-90 0.0261 0.0109 0.0122 1 0.0093 0.0191 i 0.0072 WW-3577, 3578 May,1995 Co-60 -0.2530 2.2200 0.5410 2.5800 0.1440 1.7018 , WW-3577, 3578 May,1995 Cs-137 1.1500 2.2000 -1.6400 2.9200 -0.2450 i 1.8280
)
WW-3577, 3578 May,1995 H-3 33.5750 90.9827 58.7563 i 92.0487 46.1657 64.7125 1 MI-3598,3599 May,1995 I-131 0.2288 i 0.3515 0.2122 1 0.3043 0.2205 0.2324 ) MI-3598,3599 May,1995 K-40 1,349.0000 i 112.0000 1,297.4000 i 151.0000 1,323.2000 1 94.0013 ! MI 3809,3810 May,1995 Co-60 -0.3700 i 2.9600 0.1820 i 2.9600 -0.0940 1 2.0930 M1-3809,3810 May,1995 Cs-137 0.9060 2.5000 0.1380 1 2.3600 0.5220 i 1.7190 l M1-3809,3810 May,1995 I-131 0.1445 i 0.1573 0.1738 i 0.2057 0.1592 i 0.1295 ) l CW-3838, 3839 May,1995 Gr. Beta 1.9922 1 1.3549 3.4291 1.4650 2.7106 0.9977 CW-3838, 3839 May,1995 Gr. Beta -0.7347 1 1.2274 -1.0782 1.2004 -0.9064 1 0.8584 F-4309, 4310 May,1995 Co-60 -0.0017 0.0093 -0.0032 0.0166 -0.0024 i 0.0095 l l l AS-5 l 1 I
Table A-5. In-house duplicate" sarnples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result F-4309, 4310 May,1995 Cs-137 0.0028 0.0089 0.0012 0.0133 0.0020 i 0.0080 F-4288, 4289 May,1995 Co-60 0.0038 1 0.0097 0.0012 0.0088 0.0025 i 0.0065 F-4288, 4289 May,1995 Cs-137 0.0002 0.0067 0.0022 0.0062 -
0.0012 0.0045 F-4330, 4331 May,1995 Co-60 0.0018 0.0046 0.0031 0.0050 0.0024 1 0.0034 F-4330, 4331 May,1995 Cs-137 0.0001 1 0.0042 -0.0007 0.0038 -0.0003 0.0028 MI-4377,4378 May,1995 Co-60 0.9480 1.7400 2.2200 2.6600 1.5840 1 1.5893 MI-4377,4378 May,1995 Cs-134 0.7830 1.4900 -0.2080 2.3000 0.2875 i 1.3702 MI-4377,4378 May,1995 Cs-137 0.8740 i l.3800 0.6430 1 2.1400 0.7585 1.2732 MI-4377,4378 May,1995 I-131 -0.07851 0.1490 -0.0420 0.1498 -0.0602 0.1056 MI-4377,4378 May,1995 I-131(g) 0.1700 1.3000 -1.1200 2.6200 -0.4750 1A624 MI-4377,4378 May,1995 K-40 1,385.1000 63.2000 1,344.3000 92.5000 1,364.7000 1 56.0145
! MI-4377,4378 May,1995 Sr-89 -0.0069 1 0.7313 0.0069 i l.1490 0.0000 0.6810 MI-4377, 4378 May,1995 Sr-90 1.2729 i 0.4414 1.3229 1 0.6414 1.2979 1 0.3893 Ml-4544,4545 May,1995 I-131 0.0524 0.2867 0.0574 0.2367 0.0549 i 0.1859 MI-4544, 4545 May,1995 K-40 1,410.0000 1 72.3000 1,359.0000 i 65.7000 1,384.5000 1 48.8461 MI-4544,4545 May,1995 Sr-90 2.1444 0.5153 1.2741 0.4112 1.7093 1 0.3296 G-4604,4605 May,1995 Be-7 1.9338 i 0.3520 1.7467 0.3580 1.8403 0.2510 G-4604,4605 May,1995 Co-60 -0.0112 0.0217 -0.0175 0.0189 -0.0144 i 0.0144 G-4604,4605 May,1995 Cs-134 0.0076 0.0165 0.0079 0.0163 0.0078 0.0116 G-4604,4605 May,1995 Cs-137 0.1303 i 0.0332 0.1283 0.0420 0.1293 i 0.0268 G-4604,4605 May,1995 Gr. Beta 3.9523 0.1425 3.9500 0.1562 3.9512 1 0.1057 G-4604,4605 May,1995 I-131(g) 0.0101 1 0.0227 0.0055 0.0263 0.0078 0.0174 G-4604,4605 May,1995 K-40 5.1487 0.6580 5.1002 0.6970 5.1245 0.4793 CW-4575, 4576 May,1995 Gr. Beta 1.9783 1 1.1888 2.8278 1.2558 2.403010.8M6 CW-4575, 4576 May,1995 Gr. Beta -0.2059 1 1.0000 -0.5589 0.9721 -0.3824 0.6973 MI-4695,4696 May,1995 1-131 0.1049 0.1737 0.0942 0.1607 0.0995 0.1183 MI-4695,4696 May,1995 K-40 1,568.8000 1 114.0000 1,573.1000 i 50.1000 1,570.9500 i 62.2616 May,1995 Sr-89 -0.2701 i 0.7584 -0.0499 0.8752 -0.1600 1 0.5790 I MI-4716,4717 MI-4716, 4717 May,1995 Sr-90 1.1720 i 0.4391 1.6280 i 0.4432 1.4000 1 0.3119 G-4814,4815 May,1995 Be-7 0.6081 i 0.2520 0.5837 1 0.1750 0.5959 i 0.1534 G-4814,4815 May,1995 K-40 5.8319 i o.6100 5.1295 0.5050 5.4807 i 0.3960 WW-4784, 4785 May,1995 H-3 18,665.3086 390.2155 18,274.9314 1 386.3294 18,470.1200 274.5535 SW-4759, 4760 May,1995 H-3 3,679.8217 1 213.9409 3,817.7847 217.0401 3,748.8032 i l52.3787 S 0-5178, 5179 May,1995 Cs-137 0.8481 0.0691 0.8110 i 0.0710 0.8296 0.0495 S O-5178, 5179 May,1995 K-40 19.9200il.0S00 22.0860 1.1800 21.0030 0.7998 SWU-5663, 5664 May,1995 Gr. Beta 2.4654 1 0.6199 2.5106 1 0.6258 2.4880 1 0.4404 l
AS-6
i 1 s e Table A-5. In house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result SWU-5663, 5664 May,1995 H-3 867.2182 i 104.9067 865.5032 104.8506 866.3607 74.1604 BS - 6983,6984 May,1995 Gr. Beta 7.3555 1 1.2333 8.0347 1.4183 7.6951 0.9397 US - 6983, 6984 May,1995 Gr. Deta 7.3555 i 1.2333 I & O347 1.4183 7.6951 0.9397 BS - 6983,69&4 K-40 E
May,1995 8.3490 1 0.3090 8.5309 0.0683 8.4400 1 0.1582 m BS - 6983,6984 May,1995 K-40 8.3490 0.3090 8.5309 1 0.0683 8.4400 1 0.1582 BS-6983, 6984 May,1995 Cs-137 0.0074 i 0.0008 0.0094 0.0024 0.0084 i 0.0013 BS-6983, 6984 May,1995 Gr. Beta 7.3555 1 1.2333 8.0347 1.4183 7.6951 0.9397 BS-6983, 6984 May,1995 K-40 8.3490 0.3090 8.5309 0.0683 8.4400 1 0.1582 BS - 5494,5495 May,1995 Cs-137 0.5929 i 0.0319 0.5876 0.0378 0.5903 i 0.0247 BS - 5494,5495 May,1995 Cs-137 0.5929 i 0.0319 0.5876 1 0.0378 0.5903 i 0.0247 BS - 5494,5495 May,1995 K-40 21.0920 0.6570 21.3050 0.7070 21.1985 0.4826 BS - 5494,5495 M3y,1995 K-40 21.0920 0.6570 21.3050 i 0.7070 21.1985 i 0.4826 BS-5494, 5495 May,1995 Cs-137 0.5929 i 0.0319 0.5876 0.0378 0.5903 i 0.0247 BS-5494, 5495 May,1995 K-40 21.0920 0.6570 21.3050 0.7070 21.1985 0.4826 F-5025,5026 May,1995 Co-60 0.0024 0.0064 0.0028 0.0077 0.0026 i 0.0050 F-5025,5026 May,1995 Cs-137 -0.0006 i 0.0050 -0.0038 i 0.0063 -0.0022 i 0.0040 F-5385,5386 May,1995 K-40 2.5044 0.3450 2.5992 1 0.3830 2.5518 1 0.2577 F-5046, 5047 May,1995 Co-60 0.0012 0.0067 -0.0021 0.0073 -0.0004 i 0.0049 F-5046,5047 May,1995 Cs-137 0.0018 0.0053 -0.0003 0.0046 0.0007 i 0.0035 WW-5244, 5245 May,1995 H-3 608.3574 96.3200 463.5639 91.1176 535.9606 66.2947 SW-6013, 6014 May,1995 Co-60 0.8080 i 2.2000 1.5300 3.0300 1.1690 i 1.8722 SW-6013, 6014 May,1995 Cs-137 -0.6750 2.3000 0.4560 1 2.3200 -0.1095 1.6334 MI-5620,5621 May,1995 I-131 0.1589 0.1736 0.0147 i 0.1644 0.0868 i 0.1196 MI-5620, 5621 May,1995 K-40 1,526.2000 119.0000 1,449.3000 162.0000 1,487.7500 100.5050 WW - 5642,5643 May,1995 Gr. Alpha 2.3120 2.3250 2.3120 i 2.3250 2.3120 i l.6440 WW - 5642,5643 May,1995 Gr. Beta 2.3120 i 3.2540 2.3120 3.2540 2.3120 1 2.3009 WW - 5642,5643 May,1995 K-40 94.3550 19.8000 58.9910 29.5000 76.6730 i 17.7644 DW-5738, 5739 May,1995 Gr. Beta 2.5151 i l.1685 3.5614 i l.2103 3 0333 1 0.8411 DW-5738, 5739 May,1995 I-131 -0.0458 0.1650 -0.0284 0.1486 -0.0371 0.1110 LW-6327, 6328 May,1995 Gr. Beta 6.4501 1.0293 6.6100 1.0327 6.5300 0.7290 W-6398, 6399 May,1995 Sr-89 15.1044 i 3.8169 18.1475 2.7239 16.6259 1 2.3446 W-6398, 6399 May,1995 Sr-90 25.0828 i 1.8532 24.4207 i 1.3058 24.7518 i 1.1335 WW-6184, 6185 Jun,1995 Gr. Beta 6.0148 i l.1147 7.4613 i l.3560 6.7380 i 0.8777 WW-6184, 6185 Jun,1995 H-3 86.1439 78.3469 106.9572 79.2631 96.5505 1 55.7245 MI-5684,5685 Jun,1995 Co-60 0.0976 2.9600 0.4260 1 4.6300 0.2618 2.7477 MI-5684,5685 -- Jun,1995 Cs-137 1.8400 i 2.6500 -0.9210 t 3.2400 0.4595 1 2.0929 i F 1 AS 7
4' Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lib Sample First Second Averaged Codes
- Da te Analysis Result Result Result MI-5684,5685 Jun,1995 I-131 0.0829 i 0.1477 -0.0025 0.1466 0.0402 1 0.1041 CW-5713,5714 Jun,1995 Gr. Beta 3.1068 1 1.4397 3.2557 i l.4487 3.1812 1 1.0212 CW-5713,5714 Jun,1995 Gr. Beta d.0491 1.4849 0.3925 1.5076 0.2208 i l.0580 SL-5832,5833 Jun,1995 Co-60 0.0410 i 0.0114 0.0585 0.0182 0.0498 0.0107 SL-5832,5833 Jun,1995 Cs-137 0.0550 0.0124 0.0499 i 0.0215 0.0525 i 0.0124 SL-5832,5833 Jun,1995 Gr. Beta 4.6S00 1 0.4800 4.6800 0.4800 4.6800 0.3394
( SL-5832,5833 Jun,1995 K-40 2.9035 0.2750 2.4429 0.3290 2.6732 1 0.2144 SL-5832,5833 Jun,1995 Sr-89 0.0106 1 0.0261 0.0048 0.0336 0.0077 i 0.0213 Jun,1995 Sr-90 0.0102 1 0.0114 0.0164 0.0148 0.0133 i 0.0093 [ SL-5832,5833 WW-5992, 5993 Jun,1995 Co-60 0.3950 i 1.2200 0.9060 2.6500 0.6505 1.4587 WW-5992, 5993 Jun,1995 Cs-137 -1.4000 i 1.3800 -1.4400 3.0300 -1.4200 i 1.6647 ( WW-5992,5993 Jun,1995 H-3 67.0084 1 76.1576 94.0370 77.3473 80.5227 54.2738 SL-6205, 6206 Jun,1995 Co-60 0.0029 0.0088 0.0111 i 0.0120 0.0070 0.0074 SL-6205, 6206 Jun,1995 Cs-134 0.0033 1 0.0070 0.0002 0.0096 0.0018 i 0.0059 SL-6205, 6206 Jun,1995 Cs-137 0.0138 0.0091 0.0174 0.0104 0.0156 i 0.0069
. SL-6205,6206 Jun,1995 Gr. Beta 3.3400 i 0.1000 3.3400 i 0.1000 3.3400 1 0.0707 SL-6205,6206 Jun,1995 I-131(g) -0.0060 0.0135 -0.0003 0 0197 -0.0031 0.0119 SL-6205, 6206 Jun,1995 K-40 3.3386 1 0.3100 3.3294 0.3780 3.3340 0.2444 SW-6256, 6257 Jun,1995 H-3 423.9034 i 92.0134 585.0329 t 97.8935 504.4682 i 67.1744 MI-6277,6278 Jun,1995 I-131 0.0926 i 0.1619 0.0532 0.2284 0.0729 i 0.1400 MI-6277,6278 Jun,1995 K-40 1,285.5000 i 152.0000 1,355.2000 114.0000 1,320.3500 i 95.0000
{ SW-6232,6233 Jun,1995 H-3 68.3732 79.46S0 136.7465 32.4296 102.5599 i 57.2490 VE-6348, 6349 Jun,1995 Gr. Alpha 0.3230 i 0.0990 0.1780 0.0520 0.2505 0.0559 VE-6348, 6349 Jun,1995 Gr. Beta 3.2970 i 0.1410 3.4170 0.0920 3.3570 i 0.0842 VE-6348,6349 Jun,1995 K-40 3.1425 0.3310 2.9775 0.3350 3.0600 i 0.2355 MI-6419,6420 Jun,1995 I-131 0.1154 i 0.1633 0.1197 0.1806 0.1175 0.1217 { MI-6419,6420 Jun,1995 K-40 1,457.2000 175.0000 1,339.3000 150.0000 1,398.2500 i 115.2443 MI-6521,6522 Jun,1995 I131 0.0534 0.1511 0.0344 i 0.1784 0.0439 1 0.1169 MI-6521, 6522 Jun,1995 K-40 1,475.4000 123.0000 1,274.6000 160.0000 1,375.0000 1 100.9071 [ SL-6500,6501 Jun,1995 K-40 1.8001 1 0.4550 2.1667 0.5460 1.9834 0.3554 MI-6446,6447 Jun,1995 Co-60 0.1640 1 4.8700 0.4440 2.8200 0.3040 i 2.S138 MI-6446,6447 Jun,1995 Cs-137 1.3000 3.3600 0.0563 2.1800 0.6782 1 2.0026 { M1-6446,6447 Jun,1995 I-131 -0.0433 i 0.2077 0.0000 i 0.2377 -0.0217 i 0.1578 CW-6474,6475 Jun,1995 Gr. Beta 2.8423 i l.4039 3.1674 1 1.4145 3.0049 i 0.9965 ( CW-6474,6475 Jun,1995 Gr. Beta 0.0000 i 1.1519 0.0909 1.1588 0.0455 i 0.8170 Mi-6564,6565 Jun,1995 I-131 0.2460 i 0.2607 0.0948 1 0.2353 0.1704 i 0.1756 e AS-8
Y Table A-5. In house " duplicate" samples. Concentration in pCi/L' Lib Sample First Second Averaged Ccdes* Date An.,1ysis Result Result Result BS-6960, 6961 Jun,1995 Cs-137 0.0752 0.0292 0.0475 0.0274 0.0613 i 0.0200 BS-6960, 6961 Jun,1995 K 40 17.6680 0.8700 17.0190 i 1.0600 17.3435 i 0.6857 WW-6861, 6862 Jun,199b H-3 1,422.4460 1 128.0232 1,505.1361 130.2761 1,463.7910 i 91.3261 MI-6S40,6841 Jun,1995 I-131 0.1583 0.2131 0.0509 0.1801 0.1046 0.1395 LW-6889, 6890 Jun,1995 Co-60 -2.4000 i 3.4100 1.4300 1.7400 -0.4850 i 1.9141 LW-6889, 6890 Jun,1995 Cs-137 -0.5210 3.0300 0.1410 2.1900 -0.1900 1 1.8693 LW-6889, 6890 Jun,1995 Gr. Beta 3.0131 1 0.8315 3.0285 1 0.8358 3.0208 i 0.5895 SW-7053, 7054 Jun,1995 H-3 73.2226 75.6858 126.8001 1 78.1734 100.0114 54.4046 SW-7011, 7012 Jun,1995 H-3 203.5633 81.5943 226.7766 i 82.6041 215.1699 1 58.0540 MI-7032,7033 Jun,1995 I-131 0.2720 i 0.2879 -0.0925 i 0.2629 0.0897 i 0.1949 MI-7032,7033 Jun,1995 K-40 1,577.6000 127.0000 1,522.8000 i 164.0000 1,550.2000 103.7123 SWU-7101, 7102 Jun,1995 Gr. Beta 1.9679 i 0.4592 2.1339 i 0.5061 2.0509 i 0.3417 SWU-7101, 7102 Jun,1995 H-3 118.5873 i 85.7967 92.6463 i 84.6688 105.6168 1 60.2700 SWU - 7828,7829 Jun,1995 Sr-89 0.5896 1 0.7987 0.0977 i 0.6691 0.3436 1 0.5210 SWU - 7828,7829 Jun,1995 Sr-90 0.2398 i 0.3028 0.1937 0.2742 0.2168 1 0.2042 3WU - 7828,7829 Jun,1995 Sr-90 0.2398 i 0.3028 0.19371 0.2742 0.216S i 0.2042 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 1 0.7987 0.0977 i 0.6691 0.3436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 i 0.7987 0.0977 0.6691 0.3436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 0.7987 0.0977 0.6691 0.3436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-89 0.5896 i 0.7987 0.0977 i 0.6691 0.3436 i 0.5210 SWU-7828, 7829 Jun,1995 Sr-90 0.2398 0.3028 0.1937 0.2742 0.2168 0.2042 SWU-7828, 7829 Jun,1995 Sr-90 0.2398 i 0.3028 0.1937 0.2742 0.2168 i 0.2042 SWU-7828, 7829 Jun,1995 Sr-90 0.2398 i 0.3028 0.1937 i 0.2742 0.2168 i 0.2042 SWU-7828, 7829 Jun,1995 Sr-90 0.239S i 0.3028 0.1937 0.2742 0.2168 i 0.2042 AP-8111, 8112 Jun,1995 Co-60 -0.0002 i 0.0007 0.0004 1 0.0007 0.0001 0.0005 AP-8111, 8112 Jun,1995 Cs-137 -0.0002 1 0.0007 0.0004 i 0.0005 0.0001 1 0.0004 SW-7080, 7081 Jun,1995 Gr. Beta 2.3011 0.5921 2.6708 0.6113 2.4860 i 0.4255 SW-7080, 7081 Jun,1995 K-40 61.2620 28.3000 95.4390 26.0000 78.3505 i 19.2152 WWT-7122, 7123 Jun,1995 H-3 3.8386 i 81.4299 -13.4353 i 80.6115 -4.7983 i 57.2910 LW-7239, 7240 Jun,1995 Gr. Beta 2.5177 i 0.0580 2.4081 i 0.6061 2.4629 i 0.3044 ) WW-7143, 7144 Jun,1995 H-3 539.1386 1 103.3228 436.4159 99.5398 487.7772 i 71.7352 PW-7174, 7175 Jun,1995 H-3 144.0732 1 84.2861 121.4242 83.2655 132.7487 i S9.2395 l SW-7216, 7217 Jun,1995 H-3 20.3728 i 81.4069 62.9704 i 83.3227 41.6716 i 58.2446 WW-7281, 7282 Jun,1995 Gr. Beta 1.8051 i 0.3271 2.1056 i 0.5796 1.9553 1 0.3328 WW-7281, 7282 Jun,1995 H-3 -24.3250 1 75.1716 10.3381 i 76.8357 -6.9934 i 53.7459 SW-7387, 7388 Jul,1995 Co-60 1.0200 1.9000 0.1530 1.6700 0.5865 1.2648 A5-9
Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result SW-7387, 7388 Jul,1995 Cs-137 0.5600 2.3400 -0.8650 1 2.0400 -0.1525 i 1.5522 AP-8133, 8134 Jul,1995 Co-60 -0.0000 1 0.0005 0.0003 0.0006 0.0001 0.0004 Jul,1995 Cs 137 -0.0001 0.0004 0.0000 i 0.0005 l AP-81b3,8134 AP-7600,7601
-0.0001 i 0.0003 Jul,1995 St-89 0.000S i 0.0008 0.0010 0.0008 0.0009 0.0005 AP-7600,7601 Jul,1995 St-90 -0.0001 0.0003 0.0005 0.0003 0.0002 0.0002 M1 7260,7261 Jul,1995 Co-60 0.3390 2.9100 0.5630 5.2400 0.4510 2.9969 MI-7260,7261 Jul,1995 Cs-137 1.6600 2.5900 -1.4600 3.3700 0.1000 2.1251 Jul,1995 I-131 0.1745 i 0.1944 0.1004 0.1792 0.1374 0.1322 1 MI-7260,7261 WW-7454, 7455 Jul,1995 H-3 7,142.7529 243.6211 6,985.4236 241.2186 7,064.0882 171.4188 LW - 7487,7488 Jul,1995 K-40 48.0000 14.4000 95.7520 39.9000 71.8760 21.2095 LW - 7487,7488 Jul,1995 K 40 48.0000 i 14.4000 95.7320 i 39.9000 71.8760 21.2095 LW-7487, 7488 Jul,1995 Co-60 0.4460 i 1.0700 0.3830 i 3.0000 0.4145 i 1.5926 LW-7487, 7488 Jul,1995 Cs-134 0.1230 i 1.0600 -2.3900 3.0100 i LW-7487,7488 Jul,1995 Cs-137 0.4920 1.1000 -2.2200 1 2.8400
-1.1335 i 1.59 %
-0.8640 1.5228 LW-7487, 7488 Jul,1995 Gr. Beta 2.1095 0.4725 1.8520 1 0.4810 1.9807 0.3371 LW-7487, 7488 Jul,1995 I-131 0.2323 i 0.2677 -0.0343 0.2508 0.0990 i 0.1834 LW-7487, 7488 Jul,1995 I-131(g) 0.3390 2.4400 0.9230 10.5000 0.6310 5.3899 LW-7487, 7488 Jul,1995 K-40 48.0000 14.4000 95.7520 i 39.9000 71.8760 21.2095 I LW-7487,7488 Jul,1995 K-40 48.0000 1 14.4000 95.7520 i 39.9000 71.8760 i 21.2095 LW-7487, 7488 Jul,1995 K-40 48.0000 t 14.4000 95.7520 39.9000 71.8760 21.2095 LW-7487,7488 Jul,1995 K-40 48.0000 i 14.4000 95.7520 1 39.9000 71.8760 21.2095 SW 7323,7324 Jul,1995 Gr. Beta 2.3224 i 0.7511 2.5774 0.7631 2.4499 i 0.5354 Jul,1995 H3 77.8879 1 83.9931 48.4345 82.6045 63.1612 i S8.9032 I SW-7323,7324 T 7366,7367 Jul,1995 Co-60 0.0092 i 0.0141 0.0061 i 0.0119 0.0076 0.0092 F-7366,7367 Jul,1995 Cs-137 0.0115 i 0.0108 0.0019 i 0.0111 0.0067 1 0.0077 MI-7510,7511 Jul,1995 I131 0.3443 0.3987 0.1361 i 0.3508 0.2402 i 0.2655 F-7344, 7345 Jul,1995 Co-60 0.0037 i 0.0077 -0.0071 0.0119 -0.0017 0.0071 F-7344, 7345 Jul,1995 Cs-137 0.0023 i 0.0057 0.0024 0.0097 0.0023 i 0.0056 1 MI-7429,7430 Jul,1995 I131 -0.1525 i 0.3171 0.1594 i 0.2283 0.0035 i 0.1953 F-8154,8155 Jul,1995 Gr. Beta 2.3081 1 0.0743 2.2522 1 0.0730 2.2802 0.0521 F-8154, 8155 Jul,1995 K-40 2.2313 i 0.2640 2.1161 0.4420 2.1737 i 0.2574 MI-7575,7576 Jul,1995 Co40 -1.0000 f 2.8600 1.6000 i 3.1700 0.3000 i 2.1347 MI-7575,7576 Jul,1995 Cs-134 1.7300 i 2.4200 -0.6220 i 2.3600 0.5540 i 1.6901 I MI-7575,7576 Jul,1995 Cs-137 -0.7550 t 2.5100 1.2800 i 2.3800 0.2625 1.7295 MI-7575,7576 Jul,1995 I-131 0.1795 i 0.2309 0.0704 i 0.2260 0.1250 0.1616 MI-7575,7576 Jul,1995 I-131(g) 0.8570 2.2400 0.8540 2.4400 0.8555 1 1.6561 A5-10
Table A-5. In-house " duplicate" samples. ll\ Concentration in pCi/L' Lib Sample First Second Averaged Codes
- Date Analysis Result Result Result Ml 7575,7576 Jul,1995 K-40 1,481.9000 i 111.0000 1,398.8000 i 106.0000 1,440.3500 t 76.7414 MI7575,7576 Jul,1995 Sr-89 0.6192 i 0.9862 -0.5435 0.9244 0.0378 0.6758 MI-7575,7576 Jul,1995 Sr-90 1.2363 1 0.4155 1.7902 0.4124 1.5133 0.2927 WWT-7621,7622 Jul,1995 1-131 0.0940 0.2062 0.0628 i 0.2223 0.0784 i 0.1516 MI-7739,7740 Jul,1995 Co-60 0.8900 4.9100 -0.5720 1 4.5800 0.1590 3.3572 l M1-7739,7740 Jul,1995 Cs-137 0.8600 3.7300 -0.4130 1 3.1400 0.2235 1 2.4379 i MI-7739,7740 Jul,1995 1-131 0.1928 i 0.2674 -0.0475 0.2351 0.0727 1 0.1780 i G-7805,7806 Jul,1995 Co-60 -0.0049 0.0159 0.0015 i 0.0156 -0.0017 0.0111 I G-7805,7806 Jul,1995 Cs-134 -0.0076 i 0.0157 0.0025 1 0.0094 -0.0025 1 0.0091 G-7805,7806 Jul,1995 Cs-137 0.0045 1 0.0140 0.0006 0.0118 0.0026 0.0092 I G-7805,7806 Jul,1995 Gr. Deta 5.0973 i 0.1994 5.1127 0.2103 5.1050 0.1449 ,
G-7805,7806 Jul,1995 I-131(g) -0.0048 0.0205 -0.0183 1 0.0205 -0.0115 i 0.0145 ) G-7805,7806 Jul,1995 K-40 6.0481 0.5610 5.8484 0.5100 5.9483 0.3791 l CW-7648, 7649 Jul,1995 Gr. Deta 6.68S3 1.7265 6.7478 1.7419 6.7181 1.2263 I CW-7648, 7649 Jul,1995 Gr. Beta 0.7444 i 1.2623 0.2325 i 1.2230 0.4885 i 0.8788 CW-7648, 7649 Jul,1995 H-3 -64.4182 i 97.4643 -70.1870 97.2364 -67.3026 i 68.8371 WW-7673, 7674 Jul,1995 Gr. Beta 14.1451 2.2254 14.2212 2.2315 14.1831 1 1.5757 WW-7673, 7674 Jul,1995 H-3 15.3145 t 81.7571 36.3720 82.7373 25.M32158.1586 M1-7896,7897 Jul,1995 Sr-89 0.3508 0.9697 0.1856 0.8702 0.2682 i 0.6514 MI-7896,7897 Jul,1995 Sr-90 1.7110 0.4271 1.2961 i 0.3929 1.5036 i 0.2902 WW-7967, 7968 Jul,1995 H-3 109.4679 i 84.6270 70.8322 i 82.8444 90.1500 59.2134 MI-7922, 7923 Jul,1995 Co-60 0.5680 3.1300 -1.0500 i 4.4600 -0.2410 i 2.7244 MI-7922,7923 Jul,1995 Cs-137 1.2100 2.8600 -0.5040 3.4200 0.3530 2.2291 MI-7922,7923 Jul,1995 I-131 0.0502 i 0.1932 0.0416 0.2336 0.0459 0.1516 LW 7944,7945 Jul,1995 Co-60 0.0830 2.2000 1.3000 i 1.8900 0.6915 i 1.4502 LW-7944, 7945 Jul,1995 Cs-137 0.6400 2.2200 -1.3800 1.8200 -0.3700 1 1.4353 LW-7944,7945 Jul,1995 Gr. Beta 4.1332 0.9251 3.9971 i 0.9393 4.0652 1 0.6592 SW-8704, 8705 Jul,1995 Co-60 0.1830 i 2.4900 0.9840 i l.7900 0.5835 i 1.5333 SW-8704, 8705 Jul,1995 Cs-137 0.2640 i 3.4500 -0.6630 i 1.9100 -0.1995 i 1.9717 WW-8196, 8197 Jul,1995 H-3 51.4226 87.9172 176.0234 i 93.3551 113.7230 i 64.1183 SWU-8318, 8319 Jul,1995 Gr. Beta 1.9584 i 0.4714 1.9228 0.4731 1.9406 1 0.3340 SWU-8318, 8319 Jul,1995 H-3 102.7030 1 103.6806 35.5141 i 101.1620 69.1086 72.4283 SWU-8318, 8319 Jul,1995 K-40 93.2530 39.7000 99.7420 49.1000 96.4975 1 31.5710 SP-8540, 8541 Jul,1995 Gr. Alpha 5.1903 i 1.3072 3.8567 1 1.0701 4.5235 i 0.8447 SP-8540, 8541 Jul,1995 Sr-89 1,443.0886 42.0809 1,419.4750 1 35.3491 1,431.2818 27.4789 SP-8540,8541 Jul,1995 Sr-90 15.7496 i 3.7553 19.4328 i 4.1309 - 17.5912 i 2.7914 A5-11
Table A-5. In house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Cedes
- Date Ar aly. sis Result Result Result VE-8090,8091 Jul,1995 Gr. Deta 2.3S19 1 0.0781 2.3059 ! 0.0779 2.3439 1 0.0552 VE-8090,8091 Jul,1995 K 40 2.8208 0.1170 2.7639 0.1330 t
2.7924 0.0886 SW-8175, 8176 Jul,1995 Gr. Alpha 0.5000 1 0.6000 0.65S3 i 0.8198 0.5791 1 0.5080 SW-8175, 8176 Jul,1995 Gr. Beta 0.8100 1.1000 0.8265 1.0847 0.8182 0.7724 SW-8175, 8176 Jul,1995 K-40 89.8150 i 23.8000 67.3590 1 39.3000 78.5870 22.9724 SW-8251, 8252 Jul,1995 H-3 86.7932 78.8856 43.9921 76.9259 65.3937 55.0921 SW 8606,8607 Jul,1995 Co-60 0.1320 1.7100 -0.2180 : 2.6000 -0.0430 1.5560 SW-8606, 8607 Jul,1995 Cs-137 1.0400 1 2.0400 -0.65S0 2.2400 -0.8490 1 1.5149 G - 8272,8273 Aug,1995 K-40 6.7487i 0 4490 6.6636 0.9730 6.7062 1 0.5848 G - 8272,8273 Aug,1995 Sr-89 0.0014 1 0.0091 -0.0007 1 0.0029 0.0004 0.0048 G - 8272,8273 Aug,1995 Sr-90 0.0053 1 0.0029 0.0016 1 0.0012 0.0034 1 0.0016 G-8272,8273 Aug,1995 Gr. Deta 6.2167 i 0.2594 5.9667 0.2551 6.0917 0.1819 MI-8293,8294 Aug,1995 I-131 -0.1058 i 0.1908 0.0093 1 0.2009 -0.0483 1 0.1385 MI-8389,8390 Aug,1995 I-131 -0.0127 1 0.1267 0.1W : 31318 0.0513 0.0914 MI-8389,8390 Aug,1995 K 40 1,543.8000 120.0000 1,369 9 v l62.0000 1,456.7000 100.8018 Mi-8413, 8414 Aug,1995 Co-60 0.2940 i 3.1400 -1.3500 1 5.2200 -1.0280 1 3.0458 MI-8413,8414 Aug,1995 Cs-137 -0.7370 1 2.8900 -1.3600 1 3.3100 -1.0485 1 2.1971 MI-8413,8414 Aug,1995 I-131 0.1142 1 0.2124 0.0598 0.2344 0.0870 1 0.1581 LW-8440, 8441 Aug,1995 Co-60 0.1030 i 2.3800 1.0300 1 1.8100 0.5665 i 1.4950 LW-8440, 8441 Aug,1995 Cs-137 0.7760 1.9900 -0.3890 2.0500 0.1935 1.4285 LW-8440, 8441 Aug,1995 Gr. Beta 3.3064 i 1.1388 4.6623 1.2154 3.9844 1 0.8327 WW-8518, 8519 Aug,1995 Co-60 1.4700 1 3.1400 -1.8100 1 2.9800 -0.1700 2.1645 WW-8518, 8519 Aug,1995 Cs-137 1.7100 1 2.8700 0.4430 2.7700 1.0765 1 1.9944 WW-8518, 8519 Aug,1995 H-3 10.6795 1 74.0469 -19.5791 1 72.5777 -4.4498 1 51.8422 VE-9564, 8565 Aug,1995 Co-60 0.0053 1 0.0122 0.0054 0.0128 0.0053 1 0.0088
- VE 1564,8565 Aug,1995 Cs-137 0.0038 1 0.0093 -0.0003 1 0.0082 0.0018 1 0.0062 MI- 1585, 8586 Aug,1995 Co-60 -0.4S10 1 4.0600 1.8S00 1 2.5900 0.6995 1 2.4079 M1-8E85,8586 Aug,1995 Cs-134 0.1220 3.5000 0.9370 1 2.2700 0.5295 1 2.0858 Mi-8585,8586 Aug,1995 Cs-137 1.7700 1 3.6400 0.2160 i 2.0700 0.9930 1 2.0937 M1-8585,85S6 Aug,1995 I-131 -0.2002 i 0.2079 0.0732 0.1900 -0.0635 i 0.1408 M1-8585,85S6 Aug,1995 1-131(g) 0.1360 1 9.0300 2.4300 1 6.8100 1.2830 1 5.6550 MI-8585,8586 Aug,1995 K-40 1,454.6000 1 150.0000 1,478.2000 104.0000 1,466.4000 i 91.2634 MI-8585,8586 Aug,1995 Sr-89 0.1158 1 1.1111 -0.0833 0.9491 0.0162 i 0.7306 MI-8585,8586 Aug,1995 Sr-90 1.9078 1 0.4296 1.6029 1 0.3807 1.7553 1 0.2870 MI-8674, 8675 Aug,1995 Co-60 -0.7910 1 3.2300 0.4890 3.3400 -0.1510 1 2.3232 MI-8674, 8675 Aug,1995 Cs-137 0.7690 1 2.4300 -
0.4160 1 2.4000 0.5925 i 1.7077 A512 ,
Table A-5. In-house " dup;icate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result MI-8674, 8675 Aug,1995 I-131 0.1471 0.2525 -0.0869 0.2167 0.0301 0.1664 SW-8648, 8649 Aug,1995 H-3 35 5546 i 75.1429 21.3328 74.4670 28.4437 i S2.8956 F-8754, 8755 Aug,1995 Co-60 0.0039 A O.0110 0.0031 0.0106 F-8754, 8755 0.0020 0.0076 g Aug,1995 Cs-134 -0.0026 0.0090 -0.0022 0.0087 -0.0024 0.0063 =
F-8754, 8755 Aug,I?95 Cs-137 0.0528 i 0.0207 0.0563 0.0171 0.0546 i 0.0134 F-8754, 8755 Aug,1995 Cr. Beta 13.1178 i 0.3041 12.6488 0.2780 12.8833 i 0.2060 F-8754, 8755 Aug,19M F131(g) 0.0026 0.0139 0.0013 0.0121 0.0019i U.0092 F-8754, 8755 Aug,1995 K-40 2.8119 i o.3670 3.2605 0.3670 3.0362 0.2595 VE-8946, 8947 Aug,1995 Gr. Alpha 0.2000 0.0300 0.2018 0.0786 0.2009 0.0561 VE-8946, 8947 Aug.1995 Gr. Beta 4.3000 i 0.1500 4.3179 0.1511 4.30S9 i 0.1065 VE-8946, 8947 Aug,1995 K-40 3.9615 0.2670 4.0418 0.3300 4.0017 0.2122 VE - 8802, 8803 Aug,1995 Sr-89 -0.0001 1 0.0018 -0.0004 0.0022 -0.0002 i 0.0014 VE - 8802,8803 Aug,1995 Sr-90 0.0011 1 0.0006 0.0013 0.0007 0.0012 0.0005 VE-8802, 8803 Aug,1995 K-40 2.3052 1 0.2360 2.3039 0.3070 2.3046 0.1936 MI-8845,8846 Aug,1995 1-131 0.0098 0.1785 0.0835 0.1740 0.0467 1 0.1246 CW-8873, 8874 Aug,1995 Gr. Bc.a 1.8586 i 1.3992 4.2592 i 1.5511 3.0589 i 1.0445 CW-8873, 8874 Aug,1995 Gr. l' eta 0.6043 1.1348 -0.0465 1.1799 -0.3254 i 0.8185 Mi-8902,8903 Aug,1995 I-131 -0.0387 0.2325 0.1320 1 0.3198 0.0466 0.1977 VE-9035, 9036 Aug,1995 K-40 2.1934 1 0.2790 2.3847 0.3380 2.2891 1 0.2191 SW-9056, 9057 Aug,1995 H-3 140.7425 79.5937 55.2281 75.6687 97.9853 1 54.9111 Mi-9113,9114 Aug,1995 I-131 0.2205 0.3289 0.2711 0.2835 0.2458 1 0.2171 LW-9079, 9080 Aug,1995 Co-60 0.8410 2.8400 0.1630 2.9900 0.5020 1 2.0619 LW-9079, 9080 Aug,1995 Cs-137 0.7700 2.7700 -0.5330 i 2.6700 LW-9079, 9080 0.1185 i 1.9237 g Aug,1995 Gr. Beta 2.7566 0.8607 2.6961 0.8549 2.7264 i 0.6065 E SW-9183, 9184 Aug,1995 Co-60 -0.3280 1 3.0000 2.2200 4.0400 0.9460 1 2.5160 SW-9183, 9184 Aug,1995 Cs-137 0.8200 1 3.4400 0.2580 4.3700 0.5390 i 2.7808 SWU-9162, 9163 Aug,1995 Gr. Beta 2.5000 1 0.5000 2.5094 0.5480 2.50471 0.3709 SWU-9162, 9163 Aug,1995 H-3 152.0000 i 88.0000 157.4341 83.7394 154.7170 1 60.7377 WW-9276, 9277 Aug.1995 H-3 1,636.0299 130.9904 1,680.8118 132.2095 1,658.4209 i 93.0562 VE-9210, 9211 Aug,1995 Gr. Deta 4.1000 i 0.2000 4.0920 1 0.1675 4.0960 1 0.1304 VE-9210, 9211 Aug,1995 K-40 4.6449 1 0.1090 4.6203 0.1150 4.6326 0.0792 DW-9371, 9372 Aug,1995 Gr. Beta 4.9900 1 1.1960 4.53271 1.1679 4.7613 1 0.8358 DW-9371, 9372 Aug,1995 I-131 0.1312 0.2093 0.1381 1 0.1961 0.1346 i 0.1434 MI-9297,9298 Aug,1995 I-131 g 0.0434 i 0.1996 0.0510 1 0.2134 0.0472 i 0.1461 g MI-9297,9298 Aug,1995 K-40 1,727.8000 180.0000 1,602.7000 172.0000 1,665.2500 124.4829 WW-9252, 9253 Sep,1995 H-3 -530.8948 1 98.7085 538.0449 i 98.9671 534.4698 1 69.8889 Ae.,3 g
e Table A-5. In-house " duplicate" sarnples. Concentration in pCi/L' Lib Sample First Second Averaged Codes
- Date Analysis Result Result Result l MI-9327,9328 Sep,1995 I-131 0.1442 i 0.1680 0.0972 0.1575 0.1207 0.1151 WW-9396, 9397 Sep,1995 Co-60 2.0600 1 2.4700 0.6870 2.9500 1.3735 i 1.9238 W W 9396,9397 Sep,1995 Cs-137 2.6700 2.7300 0.779b 2.5900 1.7245 t l.8816 W W-9396,9397 Sep,1995 Gr. Beta 0.6947 i 1.3597 1.7640 1.3095 1.2293 1 0.9439 WW-9396, 9397 Sep,1995 H-3 14.9063 76.6085 48.8927 78.1795 31.8995 54.7287 I SW - 10075,10076 Sep,1995 H-3 262.0954 87.9940 265.6857 88.1404 '263.8905 i 62.2730 SW - 10075,10076 Sep,1995 Sr-89 -1.1140 0.9865 0.7627 1 0.9505 -0.1756 0.6849 SW - 10075,10076 Sep,1995 Sr-90 0.6409 1 0.2630 0.3425 i 0.2113 0.49171 0.1687 MI-9350,9351 Sep,1995 I-131 -0.0990 0.1565 0.0745 1 0.1638 -0.0123 0.1133 MI9350,9351 Sep,1995 K-40 1,335.3000 1 163.0000 1,521.4000 179.0000 1,428.3500 i 121.0475 1 MI- 9463,9464 Sep,1995 I-131 0.1059 0.1889 0.0550 i 0.1695 0.0SO4 0.1269 MI-9463,9464 Sep,1995 K-40 1,814.9000 139.0000 1,743.1000 i 180.0000 1,779.0000 i 113.7113 B5 - 9710,9711 Sep,1905 K-40 8.3415 1 0.3S90 8.7853 1 0.3190 8.5634 i 0.2515 CW - 9486,9487 Sep,1995 Gr. Beta 0.3695 1 1.1728 -0.88271 1.4122 -0.2566 0.9179 CW-9486, 9487 Sep,1995 Gr. Beta 3.1540 i 1.5156 3.4306 1.5908 3.2923 1.09S6 ISO - 9562,9563 Sep,1995 Cs-137 0.4189 0.0216 0.4786 i 0.0443 0.4488 i 0.0246 S O - 9562,9563 Sep,1995 K-40 14.9730 i 0.4070 15.6780 i 0.6540 15.3255 i 0.3852 VE-9515,9516 Sep,1995 Co-60 -0.0018 1 0.0107 -0.0046 1 0.0074 -0.0032 1 0.0065 VE-9515,9516 Sep,1995 Cs-137 -0.0003 1 0.00SO -0.0017 1 0.0071 -0.0010 i 0.0054 MI-9611,9612 Sep,1995 I-131 0.1395 0.2011 0.0905 i 0.2020 0.1150 1 0.1425 MI-9611,9612 Sep,1995 K-40 1,463.6000 i 163.0000 1,381.6000 i 117.0000 1,422.6000 i 100.3220 SW-9583, 9584 Sep,1995 H-3 191.7867 i 84.3836 59.5611 78.5845 125.6739 i 57.6544 Sep,1995 Gr. Beta 4.9397 i 0.8738 4.1679 1 0.7956 ILW - 9632,9633 4.5538 i 0.5909 LW-9632,9633 Sep,1995 Co-60 0.2420 i 2.5400 0.6900 1.8800 0.4660 i 1.5800 LW-9632, 9633 Sep,1995 Cs-134 -0.9850 2.5000 0.2670 1 2.3000 -0.3590 1.6985 LW-9632, 9633 Sep,1995 Cs-137 0.7330 i 2.7300 1.9600 2.0000 1.3465 1.6921 LW-9632, 9633 Sep,1995 I-131 -0.0233 i 0.1923 0.1754 1 0.2465 0.0761 i 0.1563 LW-9632, 9633 Sep,1995 I-131(g) -1.2000 i 7.8600 -1.7800 6.9200 -1.4900 5.2361 iLW 9632 9633
, Sep,1995 K-40 73.2000 1 35.1000 84.4840 i 38.9000 78.8420 26.1974 MI-9677,9678 Sep,1995 I-131 0.1492 i 0.1575 -0.0782 1 0.2124 0.0355 1 0.1322 Mi-9677,9Gd Sep,1995 K-40 1,579.6000 i 149.0000 1,387.5000 i l50.0000 1,483.5500 1 105.7131 CW-9654, 9655 Sep,1995 Gr. Beta 3.8956 i 1.4702 4.0324 i t.4561 3.96401 1.0346 CW-965 4, 9655 Sep,1995 G r. Deta -0.4258 i 1.0721 0.1637 1 1.0778 -0.1311 i 0.7601 iMI9738 9759Sep,1995
, Co-60 0.0531 i 2.3000 -1.0600 i 5.6200 -0.5035 3.0362 Mi-9758,9759 Sep,1995 Cs-137 0.1530 2.1000 3.3300 4.1300 1.7415 2.3166 MI-9758,9759 Sep,1995 I-131 0.0357
- 0.1262 0.1303 1 0.1374 0.0830 1 0.0933 A5-14
Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Codes
- Date Analysis Result Result Result VE-9781, 9782 Sep,1995 K-40 3.6858 1 0.3040 3.8621 0.3830 3.7740 1 0.2445 WW - 9917,9918 Sep,1995 Gr. Alpha 1.0000 1.2000 0.1895 1.3470 0.5948 1 0.9020 WW - 9917,9918 Sep,1995 Gr. Deta 2.0000 1 \1.6000 1.4626 1.5372 1.7313 t l.1094 WW - 9917,9918 Sep,1995 K-40 61.5990 1 27.2000 5F3580 30.1000 58.5285 1 20.2845 SWU - 10054,10055 Sep,1995 Gr. Beta 2.8699 1 0.6506 2.9815 0.6273 2.9257 1 0.4519 SWU - 10054,10055 Sep,1995 H-3 272.2258 i 86.5578 186.8216 82.9725 229.5237 i 59.9514 CW-9848, 9849 Sep,1995 Gr. Beta 10.095S 1 2.0529 10.6091 i 2.0035 10.3525 1.4343 CW-9848, 9849 Sep,1995 Gr. Beta 0.6483 i 1.1139 0.0874 1.0548 CW-9848, 9849 0.3678 i 0.7670 g Sep,1995 H-3 2.3592 i 75.6414 -2.9490 75.3926 -0.2949 i 53.3987 E MI-9873,9874 Sep,1995 I-131 0.1317 1 0.1666 0.2502 0.2503 0.1909 0.1503 SW - 10174,10175 Sep,1995 Co-60 -0.2100 1.9300 0.0995 i 3.2500 -0.0553 1.8899 SW - 10174,10175 Sep,1995 Cs-137 -0.0756 2.9100 -0.1070 2.8500 -0.0913 i 2.0366 WW-9988, 9989 Sep,1995 H-3 126.1391 81.1795 18.2725 i 76.3358 72.2056 1 55.7164 g SWT- 10033,10034 Sep,1995 Gr. Deta 1.7710 0.4680 1.9280 0.4610 1.8495 0.3285 m P-10216,10217 Sep,1995 H3 76.4356 78.6697 74.6580 1 78.5893 75.5468 1 55.5994 SW-10261,10262 Sep,1995 H-3 279.1447 i 88.4376 300.6173 89.3N3 289.8810 1 62.8413 VE - 10012,10013 Sep,1995 Gr. Beta 5.6577 i 0.3023 5.0000 i 0.4415 5.3288 0.2675 MI-10120,10121 Sep,1995 I-131 0.1055 0.1292 0.0027 i 0.1196 MI-10120,10121 0.0541 1 0.0880 g
Sep,1995 K-40 1,446.6000 163.0000 1,300.9000 14r.0000 1,373.7500 i 109.0802 3 SW-10195,10196 Sep,1995 H-3 -19.5632 1 74.6957 103.1512 i 80.3270 41.7940 i 54.8450 CW - 10240,10241 Sep,1995 Gr. Deta 2.7919 i 1.4430 3.6514 i 1.5144 3.2216 i 1.0459 : CW - 10240,10241 Sep,1995 Gr. Beta 0.5909 i l.1545 2.4180 1 1.3151 1.5045 i 0.8750 SW-10150,10151 Sep,1995 H-3 119.120S i 81.0078 129.7884 i 81.4747 124.4546 i 57.4465 SW - 10282,10283 Oct,1993 Gr. Beta 2.1771 i 0.4791 1.8939 0.4661 2.0355 1 0.3342 I WW - 10349,10350 Oct,1995 H-3 64.9002 i 80.1767 47.3596 79.4055 56.1299 i 56.4215 WW-10349,10350 Oct,1995 Co-60 0.0850 i 1.2400 1.4900 1 2.0900 0.7875 i 1.2151 WW-10349,10350 Oct,1995 Cs-137 0.7540 1.1500 0.0703 1 2.2400 0.4122 i 1.2590 VE-10370,10371 Oct,1995 K-40 3.3443 1 0.4620 3.2897 0.4770 3.3170 0.3320 F-10491,10492 Oct,1995 Co-60 -0.0087 1 0.0120 0.0051 0.0078 -0.0018 1 0.0072 F-10491,10492 Oct,1995 Cs-137 -0.0053 i 0.0105 -0.0009 i 0.0056 -0.0031 i 0.0059 AP - 10752,10753 Oct,1995 Co-60 -0.0006 1 0.0006 -0.0007 1 0.0005 -0.0007 1 0.0004 g AP - 10752,10753 Oct,1995 Cs-134 0.00071 0.0004 0.0003 0.0007 0.0005 1 0.0004 "! AP - 10752,10753 Oct,1995 Cs-137 -0.0004 1 0.0005 0.0000 1 0.0005 -0.0002 1 0.0003 AP- 10752,10753 Oct,1995 I-131(g) 0.0016 i 0.0034 -0.0005 0.0047 0.0005 1 0.0027 l AP - 10752,10753 Oct,1995 K-40 0.0344 0.0103 0.0436 i 0.0113 0.0390 i 0.0076 AE- 11141,11142 Oct,1995 Co-60 0.0001 0.0004 0.0002 1 0.0002 0.0001 i 0.0002 A5-15
Table A-5. In-house duplicate" samples. Concentration in pCi/L' Lib Sample First Second Averaged Codes' Date Analysis Result Result Result AP - 11141,11142 Oct,1995 Cs-137 0.0000 0.0003 0.0003 0.0004 0.0002 0.0002 MI- 10324,10325 Oct,1995 Co-60 0.3420 2.2000 -1.0200 1 3.2000 -0.3390 1.9416 11- 10324, 10325 Oct,1995 Cd 134 1.4400 1.9300 -1.0300 t 2.5800 0.2050 1 1.6110 il-10324,10325 Oct,1995 Cs-137 0.3320 2.0800 0.9930 i 2.5600 0.6625 i 1.6492 II- 10324,10325 Oct,1995 I-131 0.1255 0.1379 0.0629 t 0.2061 0.0942 0.1240
.11- 10324, 10325 Oct,1995 I-131(g) -0.8920 1 2.6900 1.1700 1 3.2900 0.1390 2.1249 MI- 10324,10325 Oct,1995 K-40 1,440.7000 i 88.9000 1,432.5000 i 120.0000 1,436.6000 74.6713 il- 10324,10325 Oct,1995 Sr-89 -0.4912 i 0.9456 -1.3268 i 0.8323 -0.9090 i 0.6466 "MI- 10324, b325 Oct,1995 Sr-90 1.6952 1 0.3864 1.7252 0.3803 1.7102 i 0.2711 WWU-10392,10393 Oct,1995 I-131 0.0442 1 0.1674 0.0223 i 0.1698 0.0333 i 0.1192 F-10470,10471 Oct,1995 Co-60 0.0049 1 0.0063 0.0037 0.0052 0.0043 i 0.0041 F-10470,10471 Oct,1995 Cs-137 0.0003 0.0050 0.0020 1 0.0037 0.0011 0.0031 10413,10414 Oct,1995 H-3 41.1376 77.3777 62.2941 78.3358 51.7159 55.0541 FW WW -10437, IC438 Oct,1995 H-3 81.6446 78.1486 -10.6493 i 73.8374 35.4977 53.7568 MI- 10512,10513 Oct,1995 I-131 0.0662 0.1335 0.0996 0.1517 0.0829 0.1010 SO - 10577, 10578 Oct,1995 Co-60 0.0033 1 0.0117 0.0032 1 0.0142 0.0033 i 0.0092 S O - 10577,10578 Oct,1995 Cs-134 0.0204 i 0.0110 0.0277 0.0128 0.0241 i 0.0084 SO - 10577,1057P, Oct,1995 Cs-137 0.1528 i 0.0249 0.16S7 i 0.0241 0.1608 i 0.0173 ISO- 10577,10578 Oct,1995 Gr. Beta 18.4120 3.0030 20.0560 i 3.0020 19.2340 1 2.1249 S O - 10577,10578 Oct,1995 K-40 19.0300 1 0.5920 18.4690 0.6160 18.7495 1 0.4272 MI- 10598,10599 Oct,1995 I-131 0.0233 i 0.1528 -0.1143 0.1290 -0.0455 1 0.1000 F - 106%,10667 Oct,1995 Co-60 -0.0011 0.0149 0.0022 0.0134 0.0005 i 0.0100 F - 10666,10667 Oct,1995 Cs-137 0.0062 0.0109 0.0088 0.0102 0.0075 1 0.0075 WW - 11206,11207 Oct,1995 H-3 144.1480 1 82.0522 298.7082 i 106.1128 221.4281 67.0681 F - 106S7,10688 Oct,1995 Co-60 -0.0056 i 0.0092 0.0052 1 0.0111 -0.0002 i 0.0072 F- 10687,10688 Oct,1995 Cs-137 0.0051 0.0081 -0.0007 0.0102 0.0022 i 0.0065 M1 - 10710,10711 Oct,1995 I-131 -0.0702 i 0.1760 0.0060 0.1746 -0.0321 1 0.1240 10797,10798 Oct,1995 H-3 255.73S8 i 88.0244 190.9283 85.4061 223.3336 61.3239 IWWF 10 882,10883 Oct,1995 K-40 2.4355 i 0.2770 2.3158 i 0.4530 2.3757 i 0.2655 CW - 10826,10827 Oct,1995 Gr. Deta 1.9841 1.3273 1.1082 i 1.2551 1.5461 i 0.9134 SWU - 10923,10924 Oct,1995 Gr. Beta 2.3790 0.5752 2.7204 0.5897 2.54971 0.4119 SWU - 10923,10924 Oct,1995 H-3 903.5097 1 108.7289 878.3050 i 107.7372 893.4074 i 76.5331 F - 10969,10970 Oct,1995 Cs-137 0.0391 0.0173 0.0589 i 0.0281 0.0490 i 0.0165 F - 10969,10970 Oct,1995 Cr. Beta 2.3088 1 0.0750 2.1970 1 0.0758 2.2529 i 0.0533 F - 10969,10970 Oct,1995 K-40 2.1279 i 0.3500 1.8750 1 0.4010 2.0015 0.2661 CW - 10773,10774 Oct,1995 Gr. Beta 8.4208 1.8580 9.9060 ?.0352 9.1634 i l.3779 I
A5 l Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sample First Second Averaged Ccdes' Date Analysis Result Result Result CW - 10773,10774 Oct,1995 Gr. Beta -0.266S 1.0986 0.8745 i 1.1142 0.3039 0.7824 CW - 10773,10774 Oct,1995 H-3 51.6603 i 77.7745 67.51 % i 78.4891 59.5854 55.2481 CW - 10858,1Q8.59 Oct,1995 Gr. Beta 3.8461 i 1.5209 5.5313 1.6346 4.6887 1.1163 CW - 10858,10859 Oct,1995 Gr. Beta 0.1646 1.1055 -0.2698 1.0572 -0.0526 0.7648 BS - 11056,11057 Oct,1995 Cs-137 0.3037 0.0214 0.3183 i 0.0167 0.3110 i 0.0136 BS - 11056,11057 Oct,1995 K-40 18.5050 1 0.4060 18.2S90 0.3850 18.3970 0.2798 F - 11078,11079 Oct,1995 K-40 2.6694 0.1700 2.7062 0.1140 2.6878 0.1023 CW - 11261,11262 Oct,1995 Gr. Beta 3.4182 i 1.5101 3.8050 1.4573 3.6116 1 1.0493 CW - 11261,11262 Oct,1995 Gr. Beta -0.9607 1 0.9909 -0.1199 1.1241 -0.5403 1 0.7492 MI- 11162,11163 Oct,1995 I-131 0.2163 0.2174 0.0872 0.2019 0.1517 0.1483 LW - 11185,11186 Oct,1995 Co-60 0.2560 2.0000 0.0639 3.9000 0.1600 2.1915 LW - 11185,11186 Oct,1995 Cs-137 0.9690 1 1.9600 1.3800 3.2600 1.1745 1.9019 LW - 11185,11186 Oct,1995 Gr. Beta 7.9276 i 1.3579 6.7150 1 1.2839 7.3213 1 0.9344 MI- 11284,11285 Oct,1995 I-131 0.1805 01626 0.1868 1 0.2352 0.1837 0.1763 MI- 11284,11285 Oct,1995 K-40 1,759.4000 182.0000 1,581.9000 164.0000 1,670.6500 122.4949 i DW - 11565,11566 Oct,1995 Gr.15 eta 2.3356 0.4715 2.6159 1 0.5003 2.5008 1 0.3437 DW - 11565,11566 Oct,1995 1-131 -0.1047i 0.M70 0.1835 1 0.2833 0.0394 i 0.2126 SW - 11309,11310 Oct,1995 Gr. Alpha 0.5829 0.5262 1.1580 0.6097 0.8705 1 0.4027 SW - 11309,11310 Oct,1995 Gr. Deta 3.1323 i 0.6596 2.5628 0.6351 2.8475 0.4579 MI- 11351,11352 Oct,1995 I-131 0.0319 i 0.2455 0.0097 0.2195 0.0208 1 0.1647 MI- 11351,11352 Oct,1995 K-40 1,492.6000 i 166.0000 1,431.8000 160.0000 1,462.2000 i 115.2779 SW - 11330,11331 Oct,1995 H-3 83.4709 i 77.8239 106.3960 i 78.8560 94.9335 1 55.3959 M1 - 11407,11408 Oct,1995 1-131 -0.1272 i 0.1871 0.1059 i 0.1876 -0.0106 0.1325 MI- 11433,11434 Nov,1995 I-131 -0.0607 0.1789 0.1317 1 0.1462 0.0355 i 0.1155 Mi- 11433,11434 Nov,1995 K-40 1,446.0000 1 167.0000 1,450.8000 119.0000 .,448.4000 1 102.5305 MI- 11433,11434 Nov,1995 St-89 -0.0542 1.2560 -0.0961 1.1700 -0.0752 i 0.8583 MI- 11433,11434 Nov,1995 Sr-90 1.9383 0.4889 1.8933 i 0.4555 1.9158 0.3341 l BS - 11453,11454 Nov,1995 Gr. Beta 8.3022 i 1.4598 7.0981 i 1.3963 7.7002 1.0100 BS - 11453,11454 Nov,1995 K-40 13.4130 1 0.6950 14.3840 i 1.0200 13.8985 i 0.6171 l MI - 11476,114.77 Nov,1995 1-131 -0.0379 0.1804 0.0878 i 0.2013 0.0250 1 0.1352 MI- 11476,11477 Nov,1995 K-40 1,425.6000 1 155.0000 1,379.5000 93.1000 1,402.5500 90.4055 MI 11476,11477 Nov,1995 Sr-89 0.1529 i 1.5801 0.6656 i 1.1518 0.4092 0.9777 MI- 11476,11477 Nov,1995 Sr-90 1.5845 0.6297 0.7492 0.4308 1.1668 0.3815 WW - 11657,1165S Nov,1995 Gr. Beta 0.3756 i 0.4690 0.4697 i 0.5060 0.4226 0.3450 WW - 11657,11658 Nov,1995 H-3 110.2042 i 79.0344 172.1940 i 81.6909 141.1991 i 56.8327 SW - 11519,11520 Nov,1995 H-3 86.0705 1 77.9529 10.3285 i 74.5326 48.1995 i 53.9253 A5-17
V l Tcble A-5. In-house " duplicate" samples. Concentration in pCi/L' Lab Sarnple First Second Averaged Codes
- Date Analysis Result Result Result WW - 11837,11838 Nov,1995 Co-60 0.6630 1.5100 0.0996 3.2500 0.3813 1.7918 WW - 11837,11838 Nov,1995 Cs-137 0.0SS2 1.6800 -0.5360 2.9800 -0.2239 1.7105 MI- 11588,115S9 Nov,1995 K-40 1,282.9000 161.0000 1,390.4000 145.0000 1,336.6500 108.3351 MI- 11611,11612 Noy,1995 I-131 0.0368 1 0.2007 0.1136 0.2056 0.0752 0.1437 MI- 11611,11612 Nov,1995 K-40 1,368.1000 1 112.0000 1,291.1000 158.0000 1,329.6000 96.8349 CW - 11678,11679 Nov.1995 Gr. Deta 2.6565 1.5123 2.0599 1.3520 2.3582i LO143 MI- 11786,11787 Nov,1995 1-231 0.0519 0.1914 -0.0830 0.1791 -0.0156 0.1311 MI- 11786,11787 Nov,1995 K-40 1,493.0000 i 100.0000 1,459.1000 170.0000 1,476.0500 i 98.6154 CW '- 11865,11866 Nov,1995 Gr. Beta 1.9S03i l.4093 1.1128 1.3439 1.5466 0.9737 4LW - 11926,11927 Nov,1995 Co-60 -0.6990 2.1700 -1.3700 1 3.3200 -1.0345 i 1.9831 jLW - 11926,11927 Nov,1995 Cs-137 1.3600 2.0100 1.6800 2.6S00 1.5200 i 1.6750 LW - 11926,11927 Nov,1995 Gr. Beta 3.5794 0.9059 4.2705 1 0.9513 3.9250 0.6568 Nov,1995 Co-60 0.1370 i l.6200 1.5900 2.0000 0.8635 1 1.2869 IPW -12451 12452 PW - 12451,12452 Nov,1995 Cs-137 -1.0900 1.7200 0.8750 2.5000 -0.1075 i 1.5173 WW - 12659,12660 Nov,1995 H-3 10,454.1364 283.5019 10,315.0095 1 281.7458 10,384.5729 199.8462 G - 12184,12185 Nov,1995 K-40 7.1257 0.4820 7.2496 0.5540 7.1877 i 0.3672 DW - 12229,12230 Nov,1995 Gr. Beta 1.4868 0.4353 1.5192 0.4562 1.5030 0.3153 DW - 12229,12230 Nov,1995 H-3 48.3898 76.5630 70.8565 77.5707 59.6232 54.4957 ISO- 12430,12431 Dec,1995 Cs-137 0.2060 1 0.0696 0.1746 0.0629 0.1903 i 0.0469 S O -12430,12431 Dec,1995 Gr. Alpha 15.7026 i 4.4545 10.9075 4.1010 13.3051 i 3.0274 SO -12430,12431 Dec,1995 Gr. Beta 22.3778 i 2.8536 23.0769 i 2.9630 22.7273 1 2.0568 S O -12430,12431 Dec,1995 K-40 16.6990 1 1.3000 17.6620 1.3500 17.1805 0.9371 Dec,1995 Co-60 1.4300 3.3200 3.3S00 i 2.1000 gLW - 12152,12153 2.4050 1.9642 ILW - 12152,12153 Dec,1995 Cs-137 -0.1400 i 3.1900 0.3640 i 2.8500 0.1120 i 2.1388 LW - 12152,12153 Dec,1995 Gr. Beta 5.1509 i 1.3079 4.8804 i 1.1924 5.0157 i 0.8849 22 12250,12251 Dec,1995 I-131 0.1190 1 0.1943 0.1981 0.2178 0.1586 1 0.1460 MI- 12250,12251 Dec,1995 K-40 1,470.3000 i 163.0000 1,386.6000 i 126.0000 1,428.4500 i 103.0109 WW - 12298,12299 Dec,1995 Co-60 0.4210 2.3800 0.1770 4.0900 0.2990 i 2.3660 WW - 12298,12299 Dec,1995 Cs-137 0.1580 i 2.0500 1.5200 2.7700 0.8390 i 1.7230 WW - 12298,12299 Dee,1995 H3 42.7622 i 77.9643 99.7786 80.5282 71.2704 i 56.0429 LW - 12380,12381 Dec,1995 Co-60 1.2700 2.4400 2.2300 2.2300 1.7500 1 1.6528 LW - 12380,12381 Dec,1995 Cs-134 0.5120 1 2.1300 1.9500 2.2200 1.2310 i 1.5383 LW - 12380,12381 Dec,1995 Cs-137 0.8060 1 2.5100 1.2200 2.4400 1.0130 i 1.7503 LW - 12380,12381 Dec,1995 I-131 0.0861 i 0.1243 0.1222 1 0.2055 0.1041 0.1201 LW - 12380,12381 Dec,1995 I-131(g) -7.3600 13.8000 4.7100 1 13.4000 -1.3250 1 9.6177 t.W - 12380,12381 Dec,1995 K-40 129.0000 i 41.2000 133.0000 1 34.7000 131.0000 i 26.9329 l
t A5-18
Table A-5. In-house " duplicate" samples. Concentration in pCi/L' Leb Sample First Second Averaged Codes
- Date Analysis Result Result Result MI- 12325,12326 Dec,1995 I-131 -0.1263 1 0.2456 0.1598 0.2063 0.0167 0.1604 MI- 12325,12326 Dec,1995 K-40 1,409.0000 1 172.0000 1,438.6000 169.0000 1,423.8000 120.5664 WW - 12347,12348 Dec,1995 H-3 77.2534 78.8630 87.6308 79.3168 82.4421 1 55.9252 F - 12688,12689 Dec,1995 Co-60 0.0009 i 0.0117 0.0011 1 0.0141 0.0010 0.0092 F - 12688,12689 Dec,1995 Cs-134 0.0044 0.0094 -0.0069 0.0138 -0.0013 0.0084 F - 12688,12689 Dec,1995 Cs-137 0.0366 0.0179 0.0266 0.0149 0.0316 0.0116 F - 12688,12689 Dec,1995 I-131(g) -0.0050 1 0.0244 0.0254 1 0.0422 0.0102 0.0244 F - 12688,12689 Dec,1995 K-40 2.4139 0.3400 2.5180 i 0.3700 2.4660 i 0.2512 PW - 12945,12946 Dec,1995 Co-60 0.2950 2.7700 1.4000 i 1.9600 0.8475 i 1.6967 PW - 12945,12946 Dec,1995 Cs-137 1.4900 2.5600 0.1240 1 2.1900 0.8070 i 1.6S45 All concentrations are reported in pCi/ liter, except solid samples, which are reported in pCi/ gram.
- Lab codes are comprised of the sample media and the sample numbers. Client codes have been eliminated to protect client anonytnity.
I i I i AS-19}}