ML20095J385
| ML20095J385 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1991 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20095J381 | List: |
| References | |
| NUDOCS 9205010296 | |
| Download: ML20095J385 (162) | |
Text
n.-c DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNITS 1 AND-2 1991 ANNUAL ENVIRONMENTAL REPOR1 RADIOLOGICAL l
i 1
PDR -
PDR R'
.m_
Duquesre Light Company 1991 Anaual Radiological Environmental Report EXECUTIVE
SUMMARY
This report describes the Radiological Environmental Momtoring Program conducted during 1991 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 vicimty of the site. This report discusses the results of this monitoring during 1991.
Duquesne Light Company operates the Beaver Valley Power Station Umts 1 and 2 pressurized water reactors as part of the Central Area Power Coordination Group.
The Beaver Valley Power Station Unit 1 operated throughout 1991 except during the Eighth Refueling Outage April 12 through July 20, 1991, and dining three maintenance outages January 17 through January 31, Septerr ber iS through September 25, and October 22 through November 28, 1991. The highest average l
daily output generated during the year was 836 megawatts net in Decembr-
- 991, and the total gross eiectrical generation during the year was 3.921.000 megawatt-hours.
Beaver Valley Power Station Unit 2 operated throughout the year except for a brief j
outage, November 26 through November 28,1991. The highest average daily output generated during the year was 823 megawatts net in February,1991, and the total gross electrical generation during the year was 7,099,800 megawatt hours.
in 1991, 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 j
the Limiting Conditions for Operation identified m the Beaver Valley Power Station I
Operating License Technical Specifications for Units 1 and 2.
Based upon the estimated dose to individuals from the natural background radiation exposure, the incremental increase in total body dose to the 50-mile population (4 million people),
from the operation of Beaver Valley Power Station - Unit No.1 and No. 2, is less than 0.0001% of the annual background, See Section V.! for specific details. The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure includmg radon) is 296 mrem per year.
The environmental monitoring program outlined in the Beaver Valley Power Station Units 1 and 2 Technical Specifications was followed throughout 1991 The results for each media are contained in Section V of this report, Examination of effluents and environmental media show that it'e Beaver Valiey Power Station Units 1 and 2 operations have not adversely affected the surrounding environment.
II EXECUTIVE SuuMARY
Duquesne Light Company -
1991 Annual Radiological Environmental Report i
Table of Contents
- Section 1. INTRODUCTION 1-1 A.
Scope and Objectives of the Program 11 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 Quahty Control Programs 31 B.
Evaluation of the Quality Control (QC) Prograrn Data 3 17 C.
Standard Requirements and Limitations for Radiological and Other Effluents 3 D.
Reportmg Levels 3-13 Section 4. MONITORING EFFLUENTS 41 A.
Monitoring of Liquid Effluents 41
+
1.
Description of Liquid Ettluents at the Beaver Valley Power Station.
4-1 2.
Effluent Treatment. Sampling. and Analytical Procedures 41 3.
Results of Liquid Effluent Discharge to the Environment 41 8.
Monitoring of Atmospheric Effluents 4-8 1.
Description of Atmospheric Effluent Sources 48 2.
Atmospheric Effluent Treatment and Samphng 4-11 3.
Results 4-15 C,
Solid Waste Disposal at the Beaver '/alle, Power Station 4 15 Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-1 A.
Environmental Radioactivity Monitoring Frograrn 5-1 1.
Program Description 51 2.
Summar/ of Results 5-6
- 3. _ _ Quahty Control Program 56 8.
Air Monitoring 5-22
- 1.-
Characterization of Air and Meteorology 5-22 2.
Air Sampling Program and Aaalytical Techniques 5 22 3.
-Results and Conclusions 5-24 C.
Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was required in 1991) 5-26 1.
Characterization of Stream Sediments and Soils 5-26 2.
Samphng 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 Anirnal Locations 5-33
-2.
Sampling Program and Analytical Techniques 5 33 3.
Results and Conc usions 5-36 ranie of Contems lil
Duquesne Li ht Company 0
1991 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 5-45 1.
Description 5-45 2.
Sampling Program and Analytical Techniques 5-45 3.
Results and Conclusions 5-45 H.
Monitoring of Surface Drinking, Well Waters and Precipitation 5-47 1.
Description of Water Sources 5-47 2.
Sampling and Analytical Techniques 5-48 3.
Results and Conclusions 5-51 1.
Estimates of Radiation Dose to Man 5-54 1.
Pathways to Man - Calculational Models 5-54 S
2.
Results of Calculated Radiation Dose to Man - Liquid Releases 5 55 3.
Results of Calculated Radiation Dose to Man -
Almospheric Releases 5-53 4.
Conclusions - (Beaver Valley Power Station) 5 59 I
IV Taole of Contents
Duquesne Light Company 1991 Annual Radiological Environmental Report List of Tables 3-1.
Quality Control Data - Contractor /Quahty Control Laboratory Comparison Thermoluminescent Dosimeters - mR! day 3-2 3-2.
Quality Control Data - Co.. tractor /Quahty Control Laboratory Comparison Split Surface Water Samples 3-3 3-3.
Quality Control Data - Contractor /Quahty Control Laboratory Cornparison Split Drmking Water Samples 3-4 3-4 Quahty Control Data - Contractor /Quahty Control Laboratory Comparison Spht Milk Samples 35 3-5, Quahty Control Data - Contractor /Quahty Control Laboratory Comparison Split Feed. Food and Sediment Samples 3-6 3-6.
Quahty Contrcl Data - Contractor /Quahty Control Laboratory Comparison Spiked Water Samples 3-9 3-7.
Quality Control Data - Contractor /Quahty Control Laboratory Comparison Spiked Milk Samples 3-10 3-8.
Quahty Control Data - Contractor /Quahty Control Laboratory Comparison Split Air Particutate and Charcoal Filter Samples 3-11 3-9.
Quality Control Data - Contractor / Quality Controi Laboratory Comparison Split Air Particulate Samples (gamma) 3-13 3-10.
Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Sr 89,90 Composite Samples 3-14 3-11.
Ouclity Control Data - Independent Laboratory / Contractor /Quahty Control Laboratory Comparison Spiked Water Samples 3-15 3-12.
Quality Control Data - Independent Laboratory / Contractor /Quahty Control Laboratory Comparison Spiked Milk Samples 3-16 4-1.
Effluent Treatment. Sampling and Analytical Procedures - Beaver Valley 4-7 4-2.
Results of Liquid Effluent Discharges to the Environment - Beaver Valley 4-7 4-3.
Radioactive Gaseous Waste Samphng and Analysis Program 4-t3 5-1.
Radiological Environmental Momtoring Program 5-2 5-2.
Environmental Monitoring Program Results (1991) 5-7 5-3.
Pre-operational Environmental Radiological Monitormg Program i
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.
Pressurized 10n Chanbers - 1991 Results (mR/ day) 5-44 5-7.
Radiation Dose to Maximum Individual, mrem /yr, BVPS - Liquid Releases 5-56 5-8.
Results of Calculated Radiation Dose to Man BVPS - Liquid Releases 5-57 5-9.
Results of Calculated R.adiation Dose to Man (1991) BVPS -
Atmospheric Releases 5-60 Ust of toes v
r l.-
Duquesne Light Company 1991 Annual Radiological Environmental Report List of Figures t
-11. - View of the Beaver Valley Power Station (BVPS)-
1-2
-S 1-2.
Geographical Map and Principal Communities in 40-mile Radius of the Beaver Valley Power Station 13 4-1.
Liquid Discharge Points to Ohio River 42 4-2.
Unit 1 Water Flow Schematic 4-3 4-3.
Unit 2 Water Flow Schematic 44 44.
Unit 1 Liquid Waste System 4-5 4 5.
Unit-2 Liquid Waste System 4-6 4 0.
Units 1 and 2 Gaseous Radwaste System 49 7.
Units 1 and 2 Gaseous Release Points 4-10 4-8.
Solid Waste Disposal Diagram 4 16 5-1.
Air Sampling Stations 5 23 5-2.
Aver ge Concentration of Gross Beta in Air Particulates 1991 5 25 5-3.
Environmental Monitoring Locations - Shoreline Sediments and Soil 5-27 5 4.
Environrr. ental Monitoring Program - Feederop 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 Beaver Valley Power Station 5-39 5-8.
TLD Locations Northeast Quadrant Beaver Valley Power Station 5-40 5-9.
TLD Locations Southeast Quadrant Beaver Valley Power Station 5-41 5-10.
TLD Locations Southwest Quadrant Beaver Valley Power Station 5-42 11.
Environmental Monitoring Locations - Pressurized lon Chambers 5-43 5-12.
Environmental Monitoring Program - Fish Sampling Locations 5-46
. - 13.
Environmental Monitoring Stations Locations - Wells. Surface Water.
Drinking Water and Precipitation 5-50 s
vi - i.;st or rig #es
Duquesne Li h! _ Company 0
1991 Annual Radiological Environmental Report Section 1. INTRODUCTION A.
Scope and Objectives of the Program zThe environmental p cgram consists of environmental momtoring for radioactivity in -
the vicinity of the Beaver Valley Power Station.
Environmental sampiing and analyses included air. water, milk, soil, vegetation river sediments, fish, and ambient radiation levels in areas surroundmg'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 1991.
B.
Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River m the Borough of Shippingport, Beaver County, Penns,:vania on a 501 acre tract of
- land, Figure 11 is a view of the Beaver Valley Power Stahon.
The site is approximately one 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 principal population centers. Population density in the immediate vicinity of the site is relatively low. The population within a 5 mile radius
- of the plant is approximately 18,000 and the only area wit hin the radius of concentrated papulation is the Borough of Mir'
'd, Pennsylvania, with a population of approximately 3,300.
The site ties in a valley along the Ohio River. It extends from the river (elevation 665 feet above sea level) to a ridge along the border south of the Beaver Valley Power Station at an elevation of 1.160 feet, Diant ground level is approximately 735 feet above sea level The Beaver Valley Power Station is on the Ohio River at river mite 34.8. at a location on the New Cumberland Pool that is 3.3 river miles riownstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The Penns'ylvania-Ohio-West Virginia border is located 5.2 river miles downstream f.om the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny. Monongahela and Ohio Rivers and their tributaries. Flow ranges from a minimum of approximately 5000 cubic feet per second (CFS) to a maximurn 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 IN T RoouCTioN 11
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Duquesne Ls0ht Company 1991 Annual Radiological Environmental Report Figure 12 Geograchtc.il Map innd Principal Communities in 40-mile Rad 4us of the Beher Va' ley Power Stab 0n
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~
Duquesne Light Company.
- 1991 Annual Radiological Environmental Report
'The desi n ratings'and basic features of the Beaver Valley Power Station Units 1 0
and 2 are tabulated below:
Beaver Vallev Unit 1 Beaver Vallev Unit 2
' Therrnal & Elec, RatinD -
(Net MW,)
. 2660 MW,835 MW, 2660 MW,836 MW, Type of Power PWR PWR No. of Reactor Coolant
_ Loops--
3 3
No. of Steam Generators-
& Type 3 - Vertical 3 - Vertical Steam Used by Main-Turbine Saturated Saturated
- The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator).
1Because. 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 m the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps., Heat is given up from the prirnary system to the secondary system in the
-steam generators, where steam is formed and delivered to the main umt turbine.
- which drives; the: electrical generator.
The' steam is condensed after passing through f the turbine, and returned to the steam generators to begin another steam / water cycle.
NOTE:
MW,- megawatts thermal
-:MW, - megawatts electrical
~
71-4 :Secton 1. INTRCOUCTION -
Duquesne Light Company _
1991 Annual Radiological Environmental Report J
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 1991; The Beaver Valley Power Station Umt 1 operated throu0 out 1991, except during the h
Eighth Refueling Outage April 12 through July 20, 1991, and three maintenance outages January 17-31. September 18-25, and October 22 - November 28,1991. Umt 2 operated throughout the year except for a brief outage. November 26-28, 1991.
During the year, the radioactive releases were below the hmits of 10 CFR Part 50, Appendix 1.
The releases at Beaver Valley Power Station Umts 1 and 2 did not exceed the limiting conditions identified in the Beaver Valley Power Station Omts 1 and 2 Operating License Technical Specificahons.
The environmental piogram for 1991 was the same as in 1990 except for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications. (Refer to Table 5-1 for the 1991 Radiological Monitoring Program Outline).
The Beaver Valley Power Station Technicat Specifications require s. apling of three (3) dairies which have the highest calculated milk pathway potentia. and one large local dairy.
The three dairies are determined from calculations cased on the meteorological data and the latest milch animat survey. However, these dairies are frequently small, consisting of as few as one cow or goat. The availabihty of m:lk from single cow dairies 'and revisions due to updated calculations and surveys norrnally 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.
Sarnples from each of these. dairies are obtained in addition to the four dairies required -by the Environmental Technical Specifications.
The collection periods associated with each of the locations are provided in the detailed summary of the milk monitoring program of this report (Section 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 1991 Radiolo@al Environnsna
. Monitoring Program are contained in Sectir 7 5 of this report. A summary of the 1991 operational environmental data is found. in Table 5-2 and a summar / of f reoperational data (1974-1975) environmental data is found in Table 5-3.
Examination of effluenis from the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and Station Technical Specifications.
Section 2. RESu Ts AND CoNCluS!oNS 1
Duquesne Light Company 1991 Annual Radiological Environmental Report Section 3, ENVIRONMENTAL MONITORING CONSIDERATIONS A.
Environmental Quality Control Programs The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) elements. It should be noted that the comparisons made v.ere at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure.
- However, acceptable correlation was achievad in most instances as outhned in the dHcussions and tables which follow.
1.
TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and OC Laboratory)
Thirteen (13) TLDs from the Contractor Laboratory and OC Laboratory are co-located, replaced quarterly and results compared.
The average of the contractor laboratory and the average of the quahty control laboratory agree within 7.9% of the mean of all results. This is well within the 7 cision of typical TLD Systems.
Summary data of the TLD Monitoring Frograrn is provided in Table 3-1, 2.
Spht Sample Program (DLC Contractor Laboratory - DLC QC Laboratory)
Samples of surf ace (river) water and drinking water were routinely split and analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory. in addition, samples of other media, st.ch as milk, soil, sediment and feedcrop were also sp"t with the DLC QC Laboratory.
A summary of results of spht water sampias is provided in Table 3-2 and Table 3-3.
In 1989 and 1990 disagreement in surface and drinking gross beta water ramples had been noted. Changes in laboratory procedures were made and in 1.i91 seven of eight split gross beta's were in agreement and one was close to agreement. Six extra surface and drinking water samples were sphi and processed for gross beta. All meet agreement criteria. Summaries of milk, sediment and feed / food crop split samples is provided i1 Table 3.t and T1ble 3-5.
Some variation may be expected due to small variations in duplicate samples, variations in analytical procedures, and in calibration, source type, etc.
Sects.in 1 ENVIRONMENTAL MONITORING CONSIDERATIONS 3-1
Duquesne Light Company 1991 Annual. Radiological Environmental Report Table 3-L Ouahty Control Data
- Contractor 'Ouality Control Latrratory Comparison Thermoluminescent Oosimeters - m%f ay i
TABLE 31 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON THERMOLUMINESCENT DOSIMETERS mRIday SST QUARTER 2ND QUARTER DLC OLC - QC DLC DLC, CC Locat+on No Cont' actor Lab Location No Contrxtor -
Lao iCaSO. Dyl 10a504 Dy}
,Ca 50. Dy l 1CaSO4 Ovi 10 0.17 0.18 10 0.14 0.17 13 0.17 0.17 13 C.14 0.1 G 14 0 *6 0.18 14 0.14 0.17 15 0.14 0.16 15 Lost Lost 27 0.16 0.18 27 0.14 0.17 28 0.17 0.19 26 0.16 0.17 229 0.21 022 298 0.17 020 32 0.16 0.19 32 0.16 0.19 45 0.16 0.18 45 0.16 0.99 46 0.14 0.16 46 0,13 0.13 47 0.16 0.21 47 0.17 022 48 0.16 c.19 46 0.15 OAe 51 0.17 0.2 t 51 0.15 O6
_l 3RD QU ARTER 4Tri QU ARTER
.l DLC OLC-QC DLC l
Ox0-QC Locatron No.
Cont < actor -
Lac Locat.on No Contractor Lao (Ca504 Dy)
(CaSO4 Dy)
(CaSO4 Dy1
}
- CaSO4Do 10 0.14 0.18 10 0.16 0.19 13 0.t3 0.16 13 0.17 0.18 14 0.14 0.18 l
14 0.1t!
020 I
15 Lest Lost 15 0.13 0.15 27 0.15 0.16 27 0.16 020
- 25 0,16 0.18 28 0.11 0.20 298 0,18 0.23 298 0.20 023 32 0.16 0.18 32 0.t 7 0.21 -
45 0.17 0.18 45 0.16 023 46 0,14 0.t 6 46 0.15 0.15 47 0.11 0.20 47 0.19 023 48 0.15 0.19 48 0.17 0.21 51 0.16 0.19 51 0.17.
0.20 ANNUAL DLC DLC - QC Luation No-Coctractor Lao (CaSO4 Dy)
(CaSO4.Dy) to 0.15 0.18 13 0.14-0.17 14 0.15 0.17 15 Lost Lost 27 0.15 0.17 29 0.16 0.19 29B 0.19 0 21 32
'0.16 0.19 45 0.15 0.18 46 0.13 0.16 47 0.17 0.21 J
43 0.17 0.19
}
51 0.16 0.19 L
'32 Secton 1 ENVIRONMEN3L MONITORING CO+4SIDERATIONS
Duquesne Oght Company _-
_1991 Annual Radiological Environmental Report i
l Table; 3 2f Ocahty -Controt Data Contractor /Ovahty Control Laboratory Comparison Spht Surface
- Water Samples
'l A
.-i
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]
3 T ABd 3
- QU4ff Y CONTROL DAT A CONTR ACT OR QUALif Y CONT ROL (ASORATOR f COMP ARISQN $PLIT SJRFaCE WMf ? SWPLES 9mpug.
tst Contractor M L ' Q4 i
- u#2.a Malf*>*
umis per.,4
- up41,
. Lab t h
~ $ dace Water G*c n A Dha.
Ja%a3
$ LB 0.9J t C.$6 pC M A pnt
$ t=3 Li103
{
pC n Jsy su to i U pcm 1
Octotter i 1.9 f.$ 1 1.1 pM 6432.7 5.4105 p NI S#xe harer.
Grou Beta Ja%arr bra l
4.210.5 5.$ t c 6 pCm Juy 1.2113 5.$ t C.6 oCm Octater i t i 2' 6.3 : 0.6 oc./
4 5# ace Water.
Cp 60 Ja%ary
-$4
<j 2 pCm
- ,ont 5) s 4.2 pCi/t Jdy 5l
$ 4.4 I "to Oc+oter i3 54.3 l
pCW
~ S# ace Water
- Cs,t34 JaNary s4 5 i,4 pCm Avd
.s3 13,4 pCat JW,
$ 0.9 s 3.4 pCa
- OctoDer S4
$ 3.5 pCm 5# ace Water Cs-137 -
JaNag 5$
$ t.6 pCm -
.l Apro -
$3 5 4,t pCm 1,,
Ju* y 5.1 54.0 pCm
~
Octot4r 54 54.6 pCm
$# ace waier f ntwm IstQuaner 3000 g 100 3t% 2178 pOn Composite 3ra ovarter
[.
i30170
$ iso pcm
- Compayte
}
s# ace water.
sr-se 2nd Quarter 5 t.i s 0.6 pCW Composte -
' 4th Quarter
$ O.74
$ 0.5 ACm Cornpoute
$w face Water S r -90 2nd Quarter -
,S 0.35
. 5 0. 7 -
PCdt r
Composite 4tn Quarter 5 0.1L
$03 pCa-Cornoo9te S# ace Water Co-60 2nd Quar 1er
$ 1,0 5 f.8 pC*il f.h>gn Composte -
- 4th Quarter
- 5 0,,9
$ 2.0 pCW a
- ayl 58 5 #
g, i
Extra Sont sampees For Gross Beta Surface Water Gross Geta March ( A) 4.910.9 3.410.9 pCdt Mar;h (B) 5.610.8 2.110.9 pCai March (C) 4.410.0 3.110.9 pCm
. til - Uncerta#nt>es a'e based on counting s!atistics and are specified at the 95% cont.oence coe%cient jL seg section s.4 2 l
a Section 3. ENV;RONMENTAL MONITORING CONSDERAllONs 3-3
Duquesne Light Company _
1991 Annual Radiological Environmental Report Table 13-3 Quahty Controt Data - Cortractor/Ouahty' Control Laboratory Comparison Split Drinking Water Sa rtples i
T ABLE 3-3 quality CONTRot CATA CONTRAC!ORIOUAtttY CONTRO'% LABORAf 0Rf COMP ARiSON SP' '7 DRINK!NG W ATER $AMFLES '
S a ms"'N ote cont act:<
ote oc
. w3,.
.in.,g, s Pencyj Lacgh Lab ila Ct# s teg )%Jter C U137 Feteva)
$ (A S 4,2 t/iM May 5 40_
s ?.0 pCat V
Augu st s $.0
$ ti. 8 pC e 'l I
howemtwr s 4.0 S 4.0 pCd TJrd4:q Wret
- - Cs 04 fetirwJ7
< 4.0
$ 3.4 pCA 2
May 53.0 54.3 pCin Augu sf 550
$ ?.5 -
pCat '
Novemter
. $ 4.0 53.6 gl.M nnung Water C0 50
~ N%#wa9 56.0 54)
I PCM
- 68(SP"U u,y 33,o s4e pCA A ugu st f A,0
- 5,3 pCut
- Nov+mov 54.0 g 4.0 pCd Orimng Water -
Cross Arpaa -
March i 1.6 s 1.1 pCW Og,e,.
m ne s,.s s..i pCm August
- $ t,6
$ f,7 pCth i
Novemtef -
11.4 S 1,3 pCM Doeong wate*
Gross Beta Mrch 2910.9 2.110,8-pCv1
~
June ~
~ 2.01 10 l'110,5 PCW1 August-6.811,4 4,310,6 pCs/l 8
hovemt.ee.
6.210.8 4,7 t 0,4 pC.A
- De am eng water f eit,vm 2nd Quarter s 100 s 178 pCd s
4tn Quade s 100.
s 165 pC>n
. Emira Spo! Samotes Foe Gross Beta Dnning wate-
- Gross Beta varen IA}
3 t t 03 1520,8 pCm March tB) 3,0 + 03.
-2.0 t 0.8 pCui-March (C) 4.1 0.8 2.6 t 0.8
,DC+h (4 Uncenaint.es are baud on count *g statist cs and are spoofied at the 95% conficence coeft.caent See section 3-A 2
~
4 l
i
' 3-4 Sectioni ENVIRONMENTAL MONITORING CONSIDERATIONS e
e<
- rr,-
ge-e r-.---
,--me.'
we
~ Duquebe Light C'ompany-'
1991 Annual R~ jioiogical Environmental Report a-L Table. 3-4 Ouality Control Data + Contractor!Ouahty control Laboratory Comparison Soht Milk
~ Samples i
TABLE 3-4
- QU ALITY CONTROL DATA
.- CONTRACTORtQUAttTY CONTROL LABORATORY COVPARiSON SP IT WLK SAVPLES -
L Sammng '
O' IJits Anasysis
. F eriod Lao (1) tad p) u m (25) 31091 Sr-eo 51,3 s o.4
$n Sr 90 2J 10.3 2.0105
$4 Co 60 -
s 4,0 54.9 rCA t-131 5 0.45 50.2 Sh C5 134 54.0 53.9
$ 'l C5-13?
54.0 5 4.9 pCv1 K,40 1183 123 1165 i 117 DCu!
H M A (25)
= 618 91 Co.60
< 3.5 pCiti f
i4 31-5 0.12
$ C.10 pCin C$-134
$ 3.4 pCdl s
Cs-137 5 42 l
cCvt K-40 1407 i 96 pCat Mck (25) 9 17-91' Sr 80 51,5 s 0.6 pCin Sr 90 -
2.010.4-2.8 i 0.5 pCat -
Co -60 54.0
$ 3.2 pCut I-131
$ n.09 50,3 pCin Os-134 54,0 54.9 oCut Cs 137
$ 4.0 56.5 pCut K-40 1300 i 130 1363 i 143 pCut Milk (25) 12-17-91 Co-60
$ 3.0
$ 7.4 pCdl
-1131 50,1 50,2 pCi/l.
Cs 134 53.0
$ 6.2 pCat Cs 137 53,0-5 7J PCat K +40 1390 i 140 1250 1 152 pCut
. O} Uncertamties are based on counting statistics and are speofM at the 95% confiaence coefficen*
See Section 3-8;
' Analysis cDiamed on $nerent sampre 0
k
. Section 3 ENVIRONMENTAL MONITORING CONSIDERATIONS 3-5' t.
. Duquesno L'ight Company 1991 Annual Radiological Er*vironmental Report 4
Table
'3 5 Ouahty Control Data _ Contractor!Ouakty Control Laboratory Companson Spht Feed food
'and Sediment Samples S
t T ABL ; 3 5 r
' QUAtt1ICONTROL DATA -
CONTR ACTOCQUAUTY CONTROL LABOR ATORY
. COMPAR SON SPLIT FEED. FOOD AND SEOtVENT SAMPLES l
r Sa P""9 Ve09 -
Ana4ysts Unds 9 eros Lao 11)
Lantie
-Fees 1256 61691 Be-7 50.4 5 0.23 PCoqm 10* y!-
K-40 32 1 3' 14.111.0 pCJgm icty) r Co 60 5 0.03
[
5 0.047 pCsgm tory) l 1 13 t 5 0.004 5 0.033 PCUgm teryl C5 134
.5 0.03
$ C,03 pCagm to y)
Cs 137 5 0.03
$ 0.033 pCagm idry) feed 125) '
61891.
Sr-90 _
0.061 i 0.007 0.040 1 0.007 pCagm tary)
[
Food (10) 82991
- ( 40 2.5910.26 1.91 10.2c pCegm-4 we:1 Co 63
$ C.005 5 0,011 pCogm tweti I
1 131
$ 0.02 5 0.011 pC gm twet)
-(
Cs,134 5 0.005 5 0.010 pCugm twet;
-l Cs.137 5 0.006 5 0.011 pCvgm twet)
- Seoiment (2A) 10-23 91 Gross A!pha
-14,016.0
- 16.40 t 4.42 pCu p tory)
Gross Deta 37.0 t 3,0 25.97 t 2f i pCvgm ict yt.
5r.89 -
. s 0.15 5 0,018 pCagm taryi I
Sr90
$ 0.029 -
$ 0.02210.007 PCvg m (dry)
Co 58 '
O.743 0.061 0.91 1 0.088 pCugm vary)
Co-60 :
2 42 i Co?4 2.80 0.14 pCagm tory)
CS 134
$ 0.07
$ 0.054'
' pCvgm toryr Cs-137 0.177 1 0.071 0.24 1 0.061 pCagm tory) 1 Ra 226 t.84 10.6 7
-3.3910.87 pC#gm tarY)
K 40.
12.7 t.1.3 17,66 i 0,85 pCdgm (cry)
'(11.
Uncertarnt4es are cased on countmg statistics and are specihed at the 95% conhcence coeffcent.
See sect;oo 3 8.
Analysis obta:ned on datterer.; sample.
L J
n 36' Section 3 ENVIRONMENTA!. MONITORING CONSIDERATIONS
. g. -
4
_-.. _ = _.. _. _ _.. _.. _.. -. __
-- Duquesne Light Company _
j 1991 Annual Radiological Environmental Report
-3L 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.
4 Comparisons of Similar - Samples (DLC Contractor Laboratory -' DLC QC 4
Laboratory)
Duplicate air particulate - and charcoal - fillers - (radiciodine) samples were collec%d at Location =30 and compared during the year on a weekly basis.
i-
. Comparison of particulate and charcoal samples alternated from week to week.
Duplicate monthly air' particulate filters, composited from the weekly, air oarticulate fiiters, were analyzed 6 months out of the year for gamma activity.
Duplicate' quarterly air-particulate filters, composited from the weekly ait' particulate filters, were analyzed for Sr-89 and St-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 OC Laboratory - Internal _ QC Program "The' Contractor and -QC Laboratory maintained their own QC Progr.am which included participation in the Environmental Protection Agency - Environrnental Monitorin0 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. See Appendix I and ll.
- DLC: also audited the Contractor and QC Laboratory and determined -that internal. QC practices were in effect and that procedures ~ and laboratory 1-analytical techniques conformed to approved DLC procedures.
6.
Speda! QC. Program (DLC Contractor Laboratory - Independent Laboratory -
DLC QC Laboratory)
~ Milk and water samples were prepared by an Indoendent Laboratory. This included-low level spiking of specified nuclides. - The prepared samples were split: three ways and analyzed. by the-DLC-QC ' Laboratory and Independent
~
- Laboratory as well as the Contractor Laboratory. A summary of results of this portion - of the QC program 'is provided in Table 3-11.
Contractor non-comparison with the Independent Laboratory for i+131 in water provided in Table 3-11 and Sr-89-90 in milk provided -in Table 3-12 is discussed in the following paragraphs; Section 3. ENVIRONMENT AL MONITORING CONSIDERATIONS 3.,
Duquesne Light Company 1991 Annual Radiological Environmental Report-i l^
The contractor _ laboratory 1-131 in water results were noted to have a low bias compared; to the independent' and the QC laboratory for sample _ spikes
~ produced by the independent laboratory. All laboratory work and calculations' for these 1-131 samples were verified by the contractor. This low bias had not i
j-
.been observed in the previous year and no known changes which could effect results had been inade in the laboratories or procedures. Essentially the same
_ procedure is _used by the contractor._for both milk and water samples and in.
1991-all' milk samples for 1131 produced by the independent laboratory and
- i analyzed by the contractor met agreement criteria. Also in 1991, agreement was obtained in spike samples produced by the QC laboratory for 1131 in water l
and milk with one exception where the contractor result was high rather than p
Llow. The most probable cause of the low bias in 1-131 results by the contractor is differences in the sample preservation of the independent laboratory prepared spike compared to routine samples and/or QC laboratory prepared spikes. Such a bias would not effect routine sample results. In 1992 a different vendor will supply the independent laboratory spike samples and the contractor has also re-issued (for other reasons) the analytical procedure for iodine in _
water. Results of iodine in water spikes will be followed closely m 1992 to obtain resolution of any corfinued bias, i
The contractor laboratory obtained background results for Strantium 89 and 90
_on;two spiked milk sant es (52-259 and 59-260) prepared by the independent l
l' laboratory. The. independent laboratory stated the split samples were'made from -or'e batch and that. no preservatives were used.
Although the _ split samples were not treated in the same manner as routine samples (bisulfite addition) no previous problems _had been observed. Gamma activities present in the sample were comparable between laboratorie. Although the contractor laboratory did 'not obtain comparison-for Sr 89-90 for the abcve samples provided by the independent laboratory, in the same time period comparisons
[
were obtamed for Sr 89-90 in milk on samples provided by the QC laboratory and also by. the EPA Interlaboratory Cross Check Program. Agreement was obtained between the contractor and independent: laboratories for Sr-89-90 in
. milk on the last scheduled sample of the year (52-261) and also on a specially arranged extra sample (52 261-A). It remains unclear whetrar the discrepancy in Sr 89-90 results were due to the sample provided on the analysis' performed.
In.the following year, a different vendor will supply _ the independent _ laboratory
_ spike samples'and the.-contractor has also made a procedure revision. The comparison of Strontium 89-90 in milk will be followed closely in 1992.
f l'
.3 Secnon 3' EN'/lRCNMENTAL MONIroRING CONSIDERATIONS
i Duquesne Light Company.
1991 Annual Radiological Environmental Report I
l Cuahty Control Data Contractot Ouakty Control Laboratory ' Comparison Spiked Water Table 3<6s Sampfes -
i TA3LE 3 6 '
QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPlKED WATER SAMPLES DLC l
Sample Identification Sample DLC - QC Ceam Units Date ~
N o.
Analysis Lab (1) 3 12-91 W 75 Sr-89 27 i 3 18.8 1.5 -
pCill 1
St-90 16 1
16.0 0.8 pCill 4-24 91
.W 76 l-131 56 t 1.0 56.5 i 1.7 pCiti 4-24-91 W-77 Co-60 15 2 2.1 16.4 2.2 pCill Cs-134 18.8 i 2.4 23.8 2.5 pCill C3-137 24.2 i 2.4 25.0 2.4 pCill 4-24-91 W-78 H3 4000 i 100 4027 i 188 pCill 1
6-28 W-79 Gross 5.2 i.1.2 7.4 0.7 pCill Alpha Gross 9.3 1.1 11.0 0.7 pCill Beta 10-22-91 W-80 St 26 a.
27A i 6.9 pCi/l Sr-90 15 i 1.0 11.7 1.4 pCill
'10-22-91
.W-81 1-131 18 1.0 19.1.
0.7
- pCill 10-22-91 W-82 Co-60 21.5 i 2.2 22.6 t 2,7 -
- pCill Cs 134 16.2 1.6 15.5 1.8 pCill Cs-137 18.7 1.9 17.5 2.1 pCill 10-22-91 W H-3 4900 100 4639 i 137.
pCill 12-19-91
- W-84 Gross 7.4 i 1.5 6.2 i 0.6 pCill
- Alpha pCill Gross 12.0 i 1.0 11.0 0.7 Beta '
(1) Uncertainties are based on counting statistics and are specified at the 95%
confidence coefficient.
Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 39
Duquesne Light Company 1991 Annual Radiological Environmental Report
- y Table i3 7. Ooahty-Control _ Oata Contiactor/Ouahty Controi Laboratory Comparison Spiked udk Samt45:
i TABLE 3 7-QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL
. LABORATORY COMPARISON SPlKED MILK SAMPLES Sample identification Sample DLC - QC D at e' N o.
Analysis Lab (1) 1 31-91 Mi 33 S r-89 20 i 5 20.7 3.3 pCill Sr-90 22 1
19.0 1.4 pCill Cs-134 17.4 4.0 22.2 1.7 pCill Cs-137 25.214.0 26.1 i 1.6 pCill K-40 '
1300 130 1280 40 pCill 2-11-91 Mi-34 l-131 36 1.0 40.7 1.8 pCill 4-24-91 Mi-35 1131 44 i 1.0 48.0 0.8 pCill Cs-134'
-17.7 i 4.2 19.212.0 pCi/l Cs-137 21 4,8 22.8 2.2 pCill K-40 1260 130 1320 57 pCill 7-31-91 Mi Sr-89 28.0 2.0 28.112.1 pCill Sr-90 11.0 1.0 11.6 i_0.7 pCill 1131 48.0 2.0*
14.4 1.9
' pCill Cs-134 53.0
$ 1.8 pCill Cs-137 33.6 i 4.0 34.3 i 3.0 pCill K 40 719 1 72 675 45 pCill -
10-22-91 Ml-37 l131 22 1.0 23.6 i 3.2 pCi/l Cs 134 19.7 5.0 22.8 2B pCill Cs-137 33.8 i 5.4 38.3 i 3.0 pCill K-40 1230 i~ 120.
1233 53 pCill (1)' Uncertainties are based on counting statistics and are specified at the 95%
confidence coefficient.
See Section 3 B 3 ' Section 3 ENVIRONMENTAL MONITORING CONSIDERATIONS
~ - _. _ _. _. _ _.... _. _ _ _ - _ _. _ _.... _ _ >
Duquesno Light Company 1991 Annual Radiological Environmental Report j
L Table 3 8 Ovahty Control Data. Contractor Qualdy CoNrol Lat> oratory Compans,on Split Air Particulato and Charc. cal rdter Samples i
B I
1 0 C.
O o.
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6 6
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6 6
6 4
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.t<8 v
z o m a
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5 5 E5 6, $ 0 5 6 l}
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i
- 7...
section 3. ENVmONMENTA1. MOMTOmHG CDNSIDERAT'ONs 3 11-l
...a
..-.-. z.--...........
Duquesno Light Company 1991 Annual Radiological Environmental Report 8
- e-. o.
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b*
8 o
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0 I 3 12: = sewi 3 - E sviRONMENT AL MOMTORING CONSIDERATIONS
_.... _ _. _., _.,, _. _ _., _ _,., _ _ _ _ _ _ _ _ _. -.. ~ _.. _. _ _. - - _, _ - ~.
Duquesno Light Company 1991 Ant;ual Radiological Environmental Report
= Table 3-9 Quahty Control Data. Contractor /Ouahty Control Laboratory Compamon Spht Air Parti ulate Sampler. (gamma's t
TABLE 3 9 i
QUALITY CONTROL DATA l
CONTRACTOR / QUALITY CONTROL LABORATORY 1
COMPARISON SPLIT AIR PARTICULATE SAMPLES (GAMMA)
-l
.A DLC + Contractor DLC - QC Sample Date Nuclide Ba 7 0.093 i 0.009 0.047 i 0.01' January Others LLD LLD l
Be 7 0,136 i 0.014 0.098 0.017 Others LLD LLO g
Be+7 0.074 1 0.007 0 086 i 0.024 May J
Others LLD LLD Be 7
_0.138 i 0.014 0.103 i 0.026 July Others LLO
-LLD j
Be 7 0.005 i 0.010 0.078 1 0.026 Othcts LLD LLD Be 7 0.100 0.010 0.075 1 0.031 Others LLD LLO (1) Uncertainties are based on counting statistics and are specified at the 95%
confidence coefficient, I
LLD + Lower Limit of Detection I
Section 3. ENVIRONMENTAL MONITORING CONSIDER ATtONs 3-13
- ~ -.
i Duquesne Light Company 1991 Annual Radiological Environtnental Report i
Table 310.Quahty Control Data Contrattr,e/Ouahty Control Laboratory Comparison Spht Sr49 90 Compo64tc Samples i
TABLE 310 QUALITY CONTROL DATA CCNTRACTORIQUALITY CONTROL LABORATORY COMPARISON SPLIT SR 89,90 COMPOSITE SAMPLES DLC - Contractor DLC - QC Sample Date Nuclide Lab (1)
Lab (1) ist Quarter Sr-89
$ 0.0001 5 0.0003 Cornposite St-90
$ 0 0001 5 0.0003 2nd Quarter Sr 89 5 0.0013
$ 0.0003 Composite Sr 90
$ 0.00014 5 0.0003 3rd Quarter Sr-89 5 0.00091
$ 0,0004 Composite Sr 90
$ 050016
$ 0.0002 4th Quarter Sr 89 5 0.00027 5 0 0004 Composite Sr 90
$ 0.00007 j
$ 0.0004 (1) Uncertainties are based on countiri0 statistics and are specified at the 95%
confidence coefficient.
L I
4 1
31'4-Section l' ENVIRONMENTAL MON'tTORING CONSIDERATiuNS
~ -. -....
Duquesr.e Light Company s
1991 Annual Radiological Environmental Report i
i Table 311. Quahty Control Data. Independent Laboratory / Contractor /Ouahty controt Laborainry l
Companson Spa.ed Water Samples i
1 ABLE 311 i
QUAlliY CONTROL DAT A i'
IND(P(NDfNT LABORATORY / CONTRACTOR /QUAlif Y CONTROL LABORATORY COMPARI5ON SpikfD WAf f R SAMPLES i
U S ample loentihcation Sampie independent DLC OC Date No Analysts L ab (1) lati(1) g Sr 89 2812 2211 12.3 i 2.5' S' 7) 18105 1911
.12.910.9' 2 + 91 53 311 1 131 7,110.2 5.010.2*
6J i 0.4 CS 134 161 3 k0.4 1 5.2 N.T i 2.2 -
C$.13?
$i3
' 6.5 t 4.0 13,0104 5
2-5 91-l 53 312 H3 1150 1 90 9200 i no 12M i 29 Sr-87 16.211.5 15.0 i 1.0 92.511.1 Sr.93 10.410.5 7.6 i 5.0*
10.310.2 l
43091 53 313 1131 13J i 0.2
?.i i 3.0*
'?.912 A Cs.137
- 0.013.0 17.214.3 14.411.2 Co-60 14.013.0 11.714.2 15.5 0.6 4-30 91.
53 314 H3 1643 1 90 21YJ i 100 1628 i 65
$r 89 18.611.3 14.014,0 9.611.3
.3 r
Sr 90 16.211.0 12.011.0 11512.3 8691-53 315 4 131 11.010.3 3.512.0*
9.510.2
- un.54 31.014.0 32.7 i 4,1 35.? i 3.6 j
Cs.131 1 T.01 3.0 17.114.0 21.6 i 1.6 6-6 91 53 316-H.3 -
1600 1 100 14001 17 1434 1 97 Sr.89 15.111.3 15.0 i 1.0 11.412.4 Sr-93 14.311,0 11.0 i 1.0 a.5 10.8 10 29 f 1
$3 317 1131 20.010.3 7.113.0*
12.710./*
Cs.137 14.013.0 ifA i 3 9 16.015.6 Co fio 10.0 1 340 6.012.1 12.7 i 5.5 10-29 91
$3 316 H.3 100 i 70 700 i W T60 i 80
~ (il uncertaat<es are Da$ed on counting statistics and are reported at the 95% conhoence coethc4ent.
See Sections 3 A 6 and 3 B.
e
'f
. Section 3 ENVIRONMENT AL MONITORtHG CONSIDERATIONS. 3 15
g-I g.
Duquesne Light Company 1991 Annual Radiological Environmental Report
,f, hte, ' '1 Ova 5ty Control Data Independent Latoratory Contractor'Ouahty Control L.iboratory p.
Comparison Spiked Milk Samples
=>
j?
1ADLE312 f
1' QUAllf Y CONTROL DATA IND(P[ND( Ni LABOR AT OR Y/ CON T R ACT OR/QU All1 Y CONTROL LABORATORY COMP ARISON SPIKED MILK SAMPLES Sample idenhfication Sample independent DLC.QC Date No Anafyses Lab (1)
Lab (1) g Sr-69 10.2 i 1.2 7.314.0 C.9 10.9 S' WJ 12.$ 1 0.6 13.0 i 1.0 13.010.6 t 131 19.010.3 17.0 ~+ 1.0 20.5 + 0.9 2591 52 25e Ci 134 29.014.0 is 6 i 6.3 N.1 1 3.1 C5 13?
23.014.0 23.314,4 20.210.7 K40 1420 1 90 1240 i 20 1257 i 04
$<-82 17.012 5 1.C*
16.912.6 Sr W 14.210.5 0.65 t 0.2' 13.311.2 0131 16210.3 17.710.0 i?.811.9 C s.134 10.013.0 t $.61 3,7 18.312.2 Cs 137 12.013.0 19.fi i 3.7' 18.1 i 1.6 K 40 1220 1 90 1250 i 130 1240 1 64
$r-69 9.$ i 1.3 5 0.84' 11.6 i 2.0 S' 90 it i 2.0 S 0.16*
12.410.6 S131 14.410.3 12.9 i 0.6 12.9 i 1.0 84 91
$2-260 Cs 134 12.313 12.113,7 1$ 711.5 Cs-137 10 i 3 17.113.9 12.212.0 i
K 40 1100 i 90 1230 1 120 1204 i f4 St 89 12.012.0 13.012.0 1.0 i 2,4 Sr 30 15.0 i 1.0 13.011.0 10.6 1 0.9 10-29 ~91 52-201 Cs 134 11.0 i 3.0 10.714.5 12.7 i 6.0 C5-137 13.013.0 10.C i 4.1 17.017,1 K.40 1230 i 120 1284 i 141 12 17-91 52-261 A -
Sr 90 10.310.7 12.0 t 1.0 10.7 i 0.2 (1) Unceriainties are based on counting statit,bcs and are bned on the 95% confioence cWfoent.
See Sections 3-A 6 and 3.B.
Not reportec 3 16 Section 3. ENVIRONMENT AL MONITORING CONSIDERATIONS
Duquesne Light Conipany 1991 Annual Radiological Environmental Report 7,
Pennsylvania Department of Environmental Resources Program The Pennsylvania Department of Environrnental Resourt es (PDER) also conducted a surseillance program in the vicmity of the site. Samples of an, river water. drmking water, sediment, milk, vegetation, hsh and radiahon rnonitoring. ire included in their program. Comparison of results also mdicated agreement Detween the PDER Laboratory and the Duquesne Light Company Contractor Laboratory.
D.
Evaluation of the Quality Control (QC) Program Data The spht and spiked sample program indicates that the Contractor and CC Laboratory are generally performing satisfactorsly m accordance with
- Criteria for Comparing Analytical Measurements from NRC Comphanc e Ufhce." In addition, an independent taboratory is used to supplement the regular program. Compansons between the mdependent, QC and Contrattor laboratories are generally acceptable and demonstrate a satisfactory performance by the DLC contractor All media were found to be in agrnement in accordance with NRC criteria as hsted in Inspechon Guidance 84750-03 dated 12/04/90 with the exception of those media m Table 3 2 through Table 312 identified with an asterisk (*).
Based on all available QC data and the data from the Contractor and QC Laboratory's internal EPA Intertaboratory Cross Check Program, the Environmental Monitoring Prograrn for 1991 is acceptable with respect to both accuracy and measurement.
C.
Standard Requirernents and Limitations for Radiological and Other Effluents The Beaver Valley Power Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania, Ettluent releases are controlled to ensure that hmits set by Federal or Stato governments are not exceeded, in addition, self-imposed hmits have been established to further hmit discharges to the environment.
Beaver Valley Power Station is subject to regulations which include the Code of
- Federal Regulations 10 CFR (Energy). Pennsylvania Department of Environmental Resources (PDER) Industr:al Waste Permit 1d473211, Gaseous Discharge Permit 904 306-001, PA Code Tit le 24, Part I, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No.170 and 2-70 Environrnental Protection Agency (EPA), National Pollution Discharge Elimmation (NPDES) Permit 1:0025615 F and the Beaver Valley Power Station Technical Specificahons.
1
/
e Section 3. [NVIRoWENT A1. McNIToRING CONCf der < ATQNs 3 17
1 Duquesne Light Company 1991 Annual Radiciogical Environmental Report D.
Reporting Levels A report is required to be submitted to the Nuclear Regulatory Conunission when the level of radioattivity in an environinental samplinD medium exceeds lho limits specified in the Beaver Valley Power Station Tect nical Specifications when averaged over any calendar quarter. Also, when more than one of the radionuclides are dOleCled in the sampling medium, this report Shall be Submitted it.
i l
Concentration (1)
Concentration i2)
+
+
> 1.0 Limit Level (1 >
Limit Level (2)
~
There were no analytical results of environtnental samples during 1931 which exceeded Beaver Valley Power Station reporting levels.
1 i
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Duquesne Light Company 1901 A'tual Radiological Environmental Report Section 4. MONITORING EFFLUENTS A.
Monitoring of Liquid Effluents 1.
Descriptson of Liquid Effluents at tho Beaver Valley Power Station.
Most of the water required for the operation of the Beaver Valley station is taken from the Ohio River. and returned to the river, used for make ip to various p; ant systems, consumed by statien personnel, or discharged via a sanitary waste system.
in addition, small amounts of well water and hquid effluents are discharged to the Ohio River using discharge points shown m Figure 41.
Figure 4-2 Figure 4-3. Figure 4-4 and Figure 4 5 are schematic diagrams of liquid flow paths for the Beaver Valley Power Station.
2.
Effluent Treatment. Sampling, and Analytical Procedures See Tab!e 4 t 3.
Results of Liquid Elfluent Discharge to the Environment See Table 4 2.
vototor tsa Errtuens 41 see.on4 u
Duquesne Light Company 1991 Annual Radiological Enveronnwnf al Report 5
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H to 46 secon 4 vomicaiNo EFFLUENTS
i Duquesne Light Company 1991 Annual Radiological Environmental Report Tabte 41 Effluent Treatment, Samphng and Analytical Procedures Beaver Valley i
I TABLE 41 EFFLUENT TREATMENT, SAMPLING AND ANALYTICAL PROCEDURES - BEAVER VALLEY 4
Treatment, Sampling and/or Standard and/or Analytical
"'"' YE' Monitoring Procedures Steam Recycled or dirActed to if discharged, procedures System Radwaste System for adhere to Technical Blowdown discharDe-Specifications-Radioactive Effluents shall not exceed Procedures adhere to Waste values specified in the requirements of Technical Technical Specifications. All Specifications.
dischar0es are performed in accordance with the Offsite Dose Calculation Manual (ODCM).
Table 4 2. Results of t.iquid Effluent Dir, charges to the Environment Beaver Vat!ey TABLE 4 2 RESULTS OF LIQUID EFFLUENT DISCHARGES TO THE CNVIRONMENT BEAVER VALLEY Effluent Type Results for 1991 Steam System The Steam System Blowdown was recycled.
Blowdown Radioactive Routine planned releases of liquid eftfuents from the Waste Liquids Beaver Valley Power Station were released in accordance with conditions noted in Section 3/4.11.1 of the Technical Specifications for Units 1 and 2 and no limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi-annual Radioactive Effluent Release Reports for 1991, section t MON!TORING EFFLUENTS 4*7
I Duquesne Light Company 1991 Annual Radiological Environmentat Report
)
B.
Monitoring of Atmospheric Effluents 1.
Description of Atmospheric Effluent sources Beaver Valley Power Station (Umts 1 and 2)
The Beaver Valley Power Station identities isotopes according to the Technical Specifications and Regulatory Guide 1.21. Prior to waste gas decay tank batch releases and containment purge releases, an analysis 'of the principal gamma l
emitters is performed.
The principal gamma etnitters include noble gases, iodines, and particulates. Figure 4-6 shows the gaseous radwaste sustem at Beaver Valley Power Station.
The environmental gaseous release points also require specific nuclide identification. These points include:
a.
Unit 1 Release Points:
1)- The Ventilation Vent located on top of the Unit 1 Primary Auxiliary Building.
- 2) The Supplementary Leak Collection and Release System (SLCRS)
Vent located on top of the Unit 1 Containment Building.
b.
Unit 2 Release Points:
- 1) The Ventilation Vent located on top of the Unit 2 Primary Ausiliary f
Building..
- 2) The Supplementary Leak Collection and Release System (SLCRS)
Vent located on top of the Unit 2 Containment Buildmg.
- 3) The Condensate Polishing Building Vent located on top of the Umt 2 Condensate Polishing Buildmg.
- 4) The Waste Gas Storage Vault Vent located on top of the Unit 2 Decontamination Buitding.
- 5) The Decontamination Building Vent located on top of the Unit 2 Decontamination Building, c.
Unit 1_ and Unit 2 shared release points;
- 1) The _ Process Vent located on top of the Unit 1 Cooling Tower.-
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 isotepes and tritium, Weekly continuous samples are obtained on fitter paper and charcoal-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 1-131,1133 and 1135.
Figure _4 7 shows these gaseous release points.
48 secton4 ucNITokiNG EFFLUENTS '
Duquesne Light Company 1991 Annual Ractiological Environmental Report Figur e 4 6 Units 1 and 2 Caseous Rad 4aste System e
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MONdORING EFFtupas 49 u.
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- 3. Osit 1 & 2: Process fest 475 fut : 145 meters
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VasteGasStoragefanitfeat 80 feet: 24 meters 6.Usit2:
k contaaliation h ilding Test 50 feet: 24 noter FIGURE 4 UNITS 1 AND 2 GASE0US RELEASC POINT 5 4 10 secon 4 vomtomso ruwtsts -
..__-..____..__m._._.__._.____________..
Duquesne Light Company 1991 Annual Radiological Environmental Report 2.
Atmospheric Effluent Treatment and Sampling
. Beavet Valley Power Station (Umts 1 and 2)
Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor. Gases from the degasiber vent chillers contain primardy hydrogen and water vapor. A small amount of nitrogen - and radioisotopes consisting of noble. gases, particulates and radiciodmos are also present in the eight continuous ventilation system pathways.
The overhead gas compressor directs the radioactive gas stream to a gas surge tank. Gas is periodically transferred from the Unit 1 or Unit 2 surge tank to one of the three (3) decay tanks at Umt 1 or one of the seven (7) decay tanks at Umt
- 2. After the decay tanks are sampled and authoritation obtained for discharge.
the flow of the waste gast' from the decay tanks (2 sctm) is recorded and tapidly diluted with about 1000 scfm of air in order to dilute hydrogen and radioactive effluent concentration. The gases are then combmed with nitrogen purge from the oxygen analyters, cahbration gas from the oxygen analyters, the main condenser air ejeclor exhaust, the containment vLcuum 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 mnnitor. The mixture is then fjltered 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 th'e stream are monitored continuously.
Should the radioactivity release concentration of the stream go at:ove the allawable 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 Umt 2 containment has been sampled and the activity levels determined, purging may commente through the Ventilation Vent located on top of the Auxiliary Building or the Supplementary l
Leak Collection and Releaso' System (SLCRS) Vent located on top of the Reactor 6
Containment BuHding or the Process Vent located on top of the Cooling Tower.
Areas in the Unit 1 Auxiliary Building (subject to radioactive contamination) are mc.mtored for radioactivity prior to entering the common Ventilation Vent. These individual radiation monitors aid in identifying any sources of contaminated air.
I The Ventilanon Vent is also monitored continuously by' several redundant channels of the Radiation Monitoring System (RMS) and is sampled periodically.
Upon a high activity Plarm, 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.
sect.on 4-voNiromNs Urtuu4Ts "4 11-
Duquesne Ught Company 1991 Annual Radiological Environmental Report Areas in the Unit 2 Auxihary Building (subject to radioactive contamination) are
- monitored for 'ad,Jactivity prior to entering the filter banks for the
. Supplementary Leak Collection and Release System (SLCRS) Fant. Tins system is samp?9d penodically for determination of radioactive material and is monitored coot;nuously by other channels of the Digital Radiabon Monitcrmg System (DRM.5 ).
Each Unit 1 and Unit 2 futer bank consists of roughing filters, charcoal fdters.and c
pleated p' ass liber type HEPA filters.
The roughing hiters remove targo particulates to prevent excessive pressure drop buildup on the charcoal and tiEPA litters The chaiccol filters are effective for radioactive iodino removal and the HEP A fdters remove particulates ano e.harcoal fines.
Release poir-ts f or Uni! 1 and Unit 2 of the Beaver Valley Power-Station are
- showr, in Fqturc A 7.
See Table 4 3 for Radioactive Gaseous Wasto Sampling anu Analysis Program.
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Duquesne Light Company 1991 Annual Radiological Environmental Report T_AILLE NOT ATION a.
The Lower Limit of Detect;on lLLD),
b.
When reactor coolant system activity exceeds the hmits stated in the BVPS Technical Specification, analyses shall be performed once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during startup. shutdown and 25'e load changes and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving the maximum steady state power operation unless continuous momtormg is I
provided.
c.
Tritiurn grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from the appropriate ventilabon release path) when the refuehng canal is flooded.
d.
Samples shall be changed at least once per 7 days ar'd analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing tor af ter removal from samples).
Sampling and analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, during startup, shutdown and 25% load changes and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving the maximum steady state power operation when RCS activity exceeds the hnlits stated in the Technical Specification unless continuous monitoring is provided.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a f actor of 10.
e.
Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel oool area, whenever spent fuel is m the spent fuel pool, f.
The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the tirne period covered by each dose or dose rate calculation riade in acreardance with the BVPS Technical Specification.
l-g.
The principal gamma emitters for which the LLD cpecification will apply are l
exclusively the following radionuclider: Kr 87, Kr-88, Xe-123, Xe 133mc Xe 135, and Xe 138 for gaseous emissions and Mn $4, Fe 59, Co 58, Co 60, 2n-65.
Mo-99, Cs 134 Cs 137, Ce 141, and Ce 144 tor particulate emissions. This list does not mean that only these nuchdes are to be detected and reported Other t
peaks which are meacurable and identitiable, together with the above nuchdes, shall also be identified and reported. Nuttides which are below the LLD for the analyses should rot be reported as being present at the LLD level for that euchde. - When unusual circumstances result in LLD's higher than required the reasons shall be documented in the semi-annual effluent report.
h.
Only when release path is in use.
t 444 - Secdon d VONIToR:No EFFLUENTS
Duquesna Light Company 1991 Annual Radbo0ical Environmental Report 3..
Results Beaver Valley Power Station Gaseous effluents from the Beaver Valley Power Station were released in
- accordance with conditions noted in Section 3/4112 of the Technical Specifications. No limits were exceeded. These values have been reported in l
the Beaver Valley Power Stahon Semi Annual Radioactive Effluent Release Reports for 1991.
t C.
Solid Waste Disposal at the Beaver Valley Power Station During Beaver Valley Power Station normal operations and periodic maintenance.
small quantities of sohd radioactive waste materials were generated such as contaminated rags, paper, plastics, litters, spent non-exchange resms, and misce!!aneous tools and equipment. These were disposed of as sohd radioactive waste.
-The services of offsite vendors were used Ic se0regate. incinerate, and super compact the waste.. At the Beaver Valley Power Station, the compactabln i
wastes are segregated and the capabihty exists to cornpress the waste m SS gallon drums to minimize disposal volumes.
The waste is sinpped for disposal at a commercial radioactive material burial site licensed by the Nuclear Regulatory l'
Cormnission (NRC) or a state under agreement with the NRC. No radioactive waste rnaierial is buried at the Beaver Valley Power Station site.
t All containers used for packaging, transport, and disposal of radioactive materials met the reqmrements of the United States Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC).
Shipments offsite were made m accordance with DOT and NRC reculations. Figure 4-8 depicts solid waste handling at the site.
At Beaver Valley Power Station approximately 6,155 cubic feet of radioactive solid waste was' buried offsite in 1991. The forty-sin (46) shipments contained a total activity of 1080 curies.
Industrial solid wastes were collected in portable bins, and removed in an approved offsite burial ground. No burning or burial of wastes was conducted at the Beaver Valley Power Station site, E
- 5. con 4. NoNITorvWo UFLUENis : 4 15 -
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i Duquesne L%et Company 1991 Annual Radiological Environmental Report Figure 43 Solid Wwe Disposal Osagram i
N A010ACT Ivr stRID wa sTit U 1S I'05 A L i
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Duquesne Light Company 1991 Annual Radiological Environmental Report Section 5. ENVIRONMENTAL MONITORING PROGRAM A.
Environmental Radioactivity Monitoring Program 1.
Program Description 1 he program consists of monitoring water. air, soil, river bottoms, vegetation and foodcrops, cows milk, ambient radiation levels in areas surrounding the site, and
'quatic life as summarized in Table 51. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are included in parts 5-8 through 5-1 of this report.
5 Air Monitoring 5 C - Sediments and Soils Monitoring 5-D - Vegetation and Foodcrops 5-E - Cows Milk 5-F - Environmental Radiattor, Monitoring 5-G - Fish 5 H - Surface, Drinking, Well Waters and Precipitation 5 Estimates of Radiation Dose to h 'n sem 5 ENVIRONMENTAL MONITORING PROGR Av 51
t Duquesne Light Company l
1991 Annual Radiological Environmental Report t
i Tablo 51. Radiological Environmental Monitoring Program
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,. p TABLE 5-1
' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGR AM (continued)
Notes
- 1 (a) Control sample station: These are locations which are presumed to be outside-I e
the influence of plant effluents.
'(b) Typical LLD's for Gamtra Spectrometry are shown in Table-5-4.
(c) Particulate samples are not counted for 2: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after filter change. Perform-
-l gamma isotopic analyais 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(f)
Weekly milk carspie from Searight's Dairy is analyzed for I 131 only.
1 (g) Milk samples are collected b;-weekly when animals are in pasture and monthly l
at other times, [ Assume Ap el October for grazing season (pesture);
1
--(h) ' The milk samples from Brunton's and Nicol's are collected once per month.
j (i). The fish samples will~contain whatever species are available. If :the available-sample size permits; then the sample will be separated according so. species.
i and compositing -will provide one sample of each species, if the available size is too small to make separation by species practical, then edible parts of all-fish in the sample will be mixed to give one sample.
(j)
Composite ~ samples'.are collected at - intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at
. locations 49.1 and 2,1. Weekly grab samples are.obtained at locations 49 and
- 2 A,-
' A weekly grab ~- sample'is also obtained from daily composited grab
- samples obtamed by the water treatment plant operator at location 5, (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 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of ' sample-collection if possible.-
- : All Air samples'are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for Gross Beta.
J
- Secben 5-EhV!RoNuENTAL MotCTORING PROGRAM 5 -
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Duquesno Light Company 1991: Annual Radiological Environmental Report-2.
- Sun 3 mary of _Results '
i
' All results of this monitoring program are summarized-in Table 5-2. This table is prepared. in the_ formal specified by: NRC Regulatory Guide 4.8 and in accordance with Beaver Valley Power Station Operating License, (Appendix A, Technical Specifications). Summaries of results of analysis of each media are discussed in Sections 5-8 through 5-H and an assessment of radiation doces are found in Section 5-l.
Table 5-3' summarizes Beaver Valley Power Station
- preoperational ranges for the various sampling media during the years 1974 and 1975. -Comparisons-of preoperational data with operational data indicate the l
ranges.of values are generally in good _ agreement for both pericds of time.
1 Activity detected was attributed to _ naturally occurrir'0 radionuclides. - BVPS effluents, medical procedures, previous nuclear weapons tests or to the normal
- statistical fluctuatior, for activities near the lower limit of detection (LLD).
- The conclusion from all program-data is that the operation of the Beaver Valley Power Station has resulted in insignificant changes to the environment.
l 3.
- Quahty Control Program L
The Quality Control Program implemented by Duquesne Light Company to i;
_ assure reliable performance by the DLC contractor and the supporting QC data l
are prcsented and discussed m-Section 3 of this report. The lower timits of detection for.various analysis for each media monitored by this program by-the L
DLC Contractor Laboratory are provided in Table 5-2 and in '.'able 5 4.
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ENVIRONMENTAL RADIOLOC1 CAL MONITOFJNG PINXiRAM
SUMMARY
Name of Fictitty Beaver Vallev Power Statioinfrut I and 2 Dwket No. 50 311/50/412 t.,
location of Fart:1ty Beaver. Penn$ vivant.t. Hegwasting Ihkal Arinual liFJ1 E-(County. State,,
Y O
r\\)
Analysts azul Lower Limit N uu.iscs of Mesisum of Pathway Total Number of All Indicator locations Ix(ation with flichest Autmalhbm Control Lt.a3 hnh Noen oe stine t
Sampled of Analyons Detection
" Mean if)
Name
- ?Mean (0
- Mean to Hepors ed (Unit of Measurement) Performed (LLD)
"Ha nge -.
Distance asal Directiom**Ranrr
- Ha nne Mr.n us eme n t s * **
Montgomery Daen No. 49 oo Fish Gamma (9)
I (pCl/g)
K 40 0.05 3.0(9/9) 2A. IIVPS Descharge 3.0(5/ 5) 3 0(4/4) o iwet weight)
(2.3 3.7) 0.2 ma W (2.3 3.7)
('t.3 3 36 3
C*_o Otheis Table V.A.
IlD ME' e
c.
9G O w
-3 o m to6C E S-m~
g 3 O g
5O 3
6-O --
2 3C v,
3 L m
@Q z
U S
E~
$z
?
e m
m V
z O
~
i r-C O
E O
Pz O
n 13OO Mentrwal lamer Limes of Detevikm (LLD) v E
Mean arut range bawd ugon detertable measurements only Free thwi ed st. see tat,1c en casierement< at sg, til..I l.
.it.
.s as tout' ted tn gene rithes. s 10
~
- *
- Nonrteottne regwerted measuremertts are deftswd in itegulatory (.uhle 4 M (t he ue twr 19751 arut abc lica et V tle y INw. r St swwe Sp eitu inee,s.
Y w
s.
C ENVIRONMENTAL RAD 1QLOGICAL MONTTORING PROGRAM $UMMARY Name of Facality Beaver Vallev Ibwer Station Untt 1 and 2 Docket NoE11/50/112 3
-4 locanon of Factitty Deaver. Pennsvivanta Heporting Perkxl Annual 11731 1
(County. Statel
- E,.
m-o 5
vi o"
sb Ana is armt Lcwer IJmit Nimitser ut Meditim of Pathway Tota Number cf All Iriditator Imattern laatton with Ifichest AIrtisal Med.n CuntidliL!?hnt) None outinc Sampled ofAnalysts Detection
" Mean (f)
Name "Mean (1)
"Mean (Il Hep. e teel p
(Unit of Measurement) Perfarened (LLD)
- H a nge Distance a<wt Dirert>>ns "Hanne "Ra nge Me.assie rn.rn t."*
r-Weirton. WV No. 4H L
Food arwi Garden I-131 (4) 0.006 IJD to '
9 Crops (pCl/g) 3' g
(wet weight))
Gamsca (4) y m
3 3
K-40 0.5
. 2.014 /4)
- 10. Shippingport Horo 2.6(1/11 1.6t l /11 o
g c
(I.4-2.61 0 8 mi ENE o, O m
D5
$ g.
Others Table V.A.
11D E
Es
.3*
ac eo.
7 m~
3 O 5,e 0 3 3 V 3N e,2 3
C Dc U
Nominal Lamer 1.tm:t of Deteruon (UD)
Mean and range t>ased upore detectable measurements only. Frat than of detc< talJe mear*>rrenents at spre tiled lim athan is La.!!< aeed en pare endae ws til
- *
- Nonroutine reported measurements are deftswd in llegulatory Cusde 4 8 (IWemt.es 19751 and etw iteavrr Valley timer Statuwe Sgwe sia twwi,
3
~
O5.5ug CM"m~ DkO332_r xDt?-
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r a
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2 ee r r at n
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l
.h ENVIItONMEMI AL ItADIOLOGICAL MONf f OltlNG IHOGl{AM SUMMAltY y.
t o
Name d Fadlity Beaver Vallev Ibwer Sratlan Unn I and 2 Dot het No. 50 331/501412 6
I U_
O laratkm of Fac1111y litarer I'rnnsvivania Reporting Ivetal Armual 19'31 m
g ICamney. Statel t.=i to a
humler..I Analysts arut tower Limit c
Medium of I*athway Total Number of All f aultrator IA.athms LLaLaMon wfitt litchest Annual.Fbs.f3 Dall!!'l imiift12 Naur**"s t w Sampled of Analysis Dettetton
- Mean If)
Name
- Mean II) -
"Mean til ifeg*w1ed m
(Unit of Measurement) Performed (LLDI
- Ha nge IMstanre avul lMrettsoen
- ld a r$ge
- Mang '
Mc a w es t ene-eit s*"
w
[
Monagennery Dam N, 49 49 l
o Sediment Cross (6) 0.3 21(6/6l
- 50. Upstream 2 712 /2) 20(2/2) o to r
~
l E
(pCI/g)
Alpha (14 37)
New Cumbertarvl Dam (46 37) 114 - 2'*)
8 2 mt W g
8 g..
3-(dry weight) 2 Crnas W 0I
.3916/61 2A. ItVis IMw harge 4 l12 /23 3 412 /23 o
c lieta (33 45) 0.2 ml. W (31 45) 133-358 E r)
(
C m
g Sr Ef9 (6) 0.2 IlD e p.-
m
?o m
0 038(2/63
- 49. Upstream 0 050(I/2)
Same as e
o to Sr-90 16) 0 04 C
(0.025 0 050)
- Managwnery Dam high im atum oj
~
to 4.7 sra NE 8C I
Camma 16}
fle 7 02 1,5!2 /63 2A. IIVIS DIsrharge 1 9(l / 23 ljD o
E 8Q l
E (1.0 1.9) 0 2 mt. W
^
m 3 O K-40 0.5 1316/6)
- 50. Upstream 14(2/2) 12(2/21 o
5o
{j3 141 New Cumberl.stul Dam (13 5-13 71 (11-83)
,y3 ft 2 mi W
=U3i Mn-54 0 05 0 083(1/63 2A. IIVis Otw harge 0 o**311 / 23 IJD u
oy 3
0 2 ml. W N
Co 58 0.2 0 6 912 / 61 2A. IlVis Discharge o 69(2/2)
IJn u
,e" 10.64-0 74) 02mtW to 64 0 741 Co CD 02.
15(2/6) 2A. IIVl3 Otw harge 15(2/2) ljD o
O l
(0672.41 0.2 ml W to 67-2 48 Co337 0 02 0 2 716 / 61
- 49. Upstream O 3 012 /23 Nenn as n
ha:filia ath.n (O88036)
Montgos sery Dam (024036) s 4.7 mi NE Ha 226 0.1 2.2(6 / 61
- 50. Upstream 23(2/2!
22(2/2) o (18251 New Cumtmiasui Dam 12025' 12 2 2.21 ft.2 mt W T4228 0 02 1 216/6) 2A. ItVis tNw herge 8.312 / 21 I It2/2) o (1. 1 -8. 51 02mlW l1.1 I Si 11.1-3.2)
Others Table V A.
IJD i'
Normn.el 14swer IJmte of Detet16cn (1J Dj Mean asw! range based upon detestable nwasurem*nts oudy. Frai slon of detes t Able MCa%nfemenIS JI % ft S $th el Is 3 alhaf M 9% $1MIh.tle el en gusf e64tlW?.8 % lI)
- *
- Nonremtine reported measurements are defined in Hegulatury Guide 4 ts (Des emtwa 1975) armi the fle.ever Valtry 1%e r Mathes Sg.sth ad
.n,
^d
n z.
gd' 5 < [ Cc ~n 2 5 r.am
_ o3 paaCa]sa o6O Rc f"."kS a.m3.D N c],~
s u.
a 4 r c6 mb 7
e "s
tne e
f nl in o
I.
r t6 e r
(
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bns e O
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0 o
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s s
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c e
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an I
1
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.[ea
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1) 1
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ENVIRONMENTAL HADIOLOGICAL MONITOHING PROGRAM
SUMMARY
8
-k'
- Name of Facthty Braver Vallev Power Station Unit I and 2 ' Docket No. 50 33 gjg/412
'4' v.
w Locauon of Factiety Beaver. IVnnsvivania Heporting Italad Annual 1991 1E-m ICounty. State) z 9
, s.
n
N' Oz.
C
. Analysts and Lower Limit
' Nemaleer of 5
.7
! Medium of I%thway ' Total Nureher of All Indicator locahons Isation with flaaliest AnnUNU Control foratims Nouroutine.
_y Sampled
..'ofAna W Detection
~ Mean to.
Name-
"Mean (0 -
- Mean 10 Repor te.1 r
(Unit'of Measurement) Pesformed (LLD)
"Hange D6 stance and Directions "Hange "Ra nge
- Mc.asurements"* -
=,
I w-g O
eo z
I-131 (157)'
0.5
. O.48(47/157)
- 04. Midland. PA.
0.5012fi/52)
O, y-Drtnidng
.g t
m Water.
10.1 6-1.01-1.3 mi WNW 10.20 1.0) 3-2 IpC1/11 '
'i
(.
Groes (36) 0.6 llD y7 3
Alpha z>
c 8
. e, D "
y
]
m Cross 136) 1 4.9(36/36)
- 04. Midland. PA 5.3(12/121 o
a 5i
' i Beta '
12.0 9. 4 1.3 mi WNW (2.0 9.61 o, in Oo
- Gamma (157)
Table V.A.
IlD r-4 Sr-89 (121 1.5 11D ta c '
a
. rn ~
Sr-90 (12).
0.5 11.D k3 a.
-8 Co 60 (12) (a) i 11D _
- Of
'I
. g c,.
oQ 11-3 (1 2) 100 133(3/12)-
- 05. E. It~rpool. Oli 140( t / 4) o 4
(130 140) 4.8 mt WNW
?.
y-t 3
- tD
-y.
'O' 2
b.
~!
l (a) Co 60 analyzed Isy high sensittvity medmd.
Nominal foiwer l_imit of Detettson (U.D)
Mean and range based upon detestatale meneurements only Fras thm d detes talJe measuremerts at $$"'lfh *I l'a *thwn* Is 8s'dw ated ses parreetiscws (f)
- ' Nonruutine reported measurements are deftswd in f{cgulatory Cuhie 4 ft ilks emter 1975) asul ti.e lleaver Valiry Ibwer Statkun spe,sticath.ew,
1 m
4 b
ald1 e-
'v-'.
w
2 a 5'm m r-e2~no3t54 G3 >a@
ho oyu m358a3c" E yOVk*-
yhEo ub s
e "s
tn e
e o inl m f
f
}
(
e e r tus o
o 0
er s
Sor w
c u
c.
mngms t
r a
t s
e i
uoc!
c e NNIM e w e >
s,.
t p
a.
st te ol 6i, i l
5 s
s 1
t.
e b I e o.
cp a
. n ngN
)51
- i. S e an 4
n u s
ea A
/7 i.
l tn""
25 D
D t kt t
4 i
MI P
19 1
1 o
s.
st 2
n 4 (2 I
J iS 1
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4 o
w se r
/
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1
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1 4
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15 R
1 A
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3 1
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(
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Duquesne Light Company 1991 Annual Radiological Environmental Report
- Table 5-3 Pre-operational Environmental Radiological Monitonng Program Summary TABLE 5 3
' PNE OPERATIONAL ENVIRONMEt TAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Valley Power Station Docket No. 50-334 -
Location of Facihty Beaver; Pennsylvania Reporting Level CY 1974 - 1975 (County. State)
PRE OPERATION L PROGRAM
SUMMARY
(COMBINED 1974 1975)
Medium or Pathway Analysis and Total Number Lower Limit AllIndicator Locations
' " I *
- "9' (Unit of a u ement)
Sediments Grors A!pna (0) pCi'g (dry)
Gross Beta (33)_
1 18 33/33 5 30 Sr-90 (0)
U-234,235 238 (0)
Gamma (33) 13 33'33 2 - 30 K 40 15 13 33/33 2 - 30 Cs-137 0.1 04 21/33 0.1 - 0 6 e
3 ZrNb-95 0 05 0.8 12'33 0.2-32 Ce 144 03 05 3/33 04-07 Ru-106 m.
- 0.3 1.5' 3t33 1.3-18 Others-
< LLD Y:
- Foodstuff Gamma (8) pCi'g (dry)
K-40 1
33 848 10 53
- - C s-137 01 02 1/8 ZrNb-95 0 05 02 1/8 4
Ru-1064 -
0.3 08 1/8
- Others
< LLD Feedstuff Cross Beta (80) 0.05 19 80180 8 50 pCUg (dry).
Sr 89
-(81) 0 025 0.2 33/81 004-093-Sr 90
~(81) 0 005 04 78/81 002 081 Gamma
.(81).
K 40 1
19 75/81 5 46 Cs 137 01 0.5 - 6t81 02 Cc-144 03 1,5 5181 0.9 - 2 6 ZrNb-95 _
0 05 08 13/81 0.21.8-Ru 106:e>
03 14 12/81
'O.6-23 Others
< LLD Soilf Gross Alpha (0) pCilg (dry)
~ Gross Beta (64) 1 22 64/64 14 - 32 (Template Samples)
_ St 89 (64) 0 25 04 1/64 Sr-90 (64) 0.05 0.3 48/64 0.1 - 1.3 -
U-234, 235, 238
_ (0)
- Gamma (64)
K 40 1.5 13 63/64 - 5 24 Cs-137
- 0.1 1.5 56/64 0.1-68 Ce-144 03 1.1 7/64 0.2 - 3 ZrNb 95 0 05 03 13/64 0.1 2
Ru 106'b>
03 1.1 3/64 0.5-2 Others
< LLD 5-18 Section S. ENVIRONMENTAL MONITORING PROGRAM
~
Duquesne Light Company 1991 Annual Radiological Environmental Repor!.
TABLE 5 3 I
PRE OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Bewer Va' ley Power Station Docket No. 50 334
' Location of Facility Beaver Pennsylvania Reporting Level CY 1974 -197_5 iCounty. Statei PRE OPERATIONAL PROGRAM SUMM ARY (COMBINED 1574 1975)
Medium or _Dathway
- Analysis and Total Number Lower Limit AllIndicator Locations
- (Unit of a u ement)'
- "9"
. Scil Grons Alpha (0) pCilg tdry)
Gross Beta (8) 1 21 8<8
~16 28 (Cos e Samples)
Sr-89 (8) 0 25
0 05
-02 58 008-05 Gamma (8)
K 40 15 13 8'8 7 - 20 Cs 137 -
01 12 7/8 02 24 Co 01 02 1/8 Others
< LLD
[
--1 Surf ace Water ;
Gross Alpha-(40) 03 0 75 5 40 0 6 - 1.1 pO!!
. Gross Beta (120) 06
.44 120'120 25 114 Gamma (1)-
10 60
< LLD Tritium (121) 100 300 120/121 180 - 800-Sr 89 (0)
~ Sr-90 (0)
C-14 (0)
Drinking Water
-I131 (0) pOil :
Gross Alpha -
(50)'
03 06 4 50 04 Od Gross Beta (208) 06 38 208'208 23-64 Gamma (0) l
. Tritium (211) 100 310 ?11/211 130 1000 C-14 (0)
' Sr-89 (0)
Sr-90 (0)
Ground Water Gross Alpha (19) 03
< LLD
.j pCill Gross Beta' (76) 06 2.9 73!75f a) - 13'-80 e-f Tritium (81) 100 440 77/81 80 - 800 Gamma (1) -
10 60
< LLD j
Air Particulates Gross Alph.t
--(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 St 89 (0)
Sr-90 (0) l131 (816) 0 04 0 08 2/816
.007 008 Gamma (197)
ZrNb-95 0 005 0 04 122/197 0 01 0 16 Ru-106 0 010 0 04 ~ $0/197 002 009 Ce-141 0.010 0 02 3/197 001 004 Ce-144 0 010 0 02 44/197 0.01 - 0 04-Others
< LLD Milk l-131 (91) 0 25 06 4/91 0,3-08 pCill Sr89 (134) 5 7
4/134 6-11 j
Sr 90 (134) 1 53 132/134 1.5 - 12 8 j
Gamma (134) j Cs-137 10 13 19/134 11 - 16 Others
{
< LLD o
Section 5. ENVIRONVENTAL MONITORING PROGRAM 5-19
Duquesne Light Company -
- 1991' Annual Radiological Environmental Report TABLE 5 3 PRE OPERATIONAL ENVIRONMENTAL R ADIOLOGICAL MONITORING PROGRAM SUMM ARY
- Name of Tacihty Beaver Vanev Power Station Docket No. 50-334
' Location of Facility Beaver Pennsylvania Reporting Level CY 197.1.- 1975 (County. State)
PRE OPERATIONAL PR0 CRAM SUMM ARY (COMBINED 1974 1975)
Medium or Pathway Analysis and Total Number Lower Limit All Indicator Locations
"*'Y**
(Unit of a u ement)
""9' External Radiation y - Monthly (599) 0 5 mR' O 20 599/599 008 051-mR! day y - Quarterly (195) 0 $ mR*
O 20 _195'195 011 0 3B y - Annual (48) 0 5 mR*
O 19 48448 011 030 Fish Cross Beta (17) 0 01 19 15/17 1.0 32 pCvg (wet) '
Sr.90 (17) 0 005 0 14 17/17 002 050 Gamma-(17) 0.5 K-40 24 17/17 10-37 Otaers
. < LLD LLD in units of MR --Lower end of useful integrated exposure detectabihty 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)
(til.. may include Ru;106, Ru 103. Be-7J Y
e 5-20 Section 5 ENVIRONMENTAL MONITORING PROGRAM
X Duquesne Light Company
.1991 Annual Radiological Environmental Report
< Table 5-t Typ cal LLDs For Gamma Spectrometry TABLE 5-4 TYPICAL LLDs
- FOR GAMMA SPECTROSCOPY
^ ' ' "' ' "'#
- 9#'
Nuclide a er
& So I (10 3 pCi/m))
(pCilkg dry)
(pCilg wet)-
(pCilliter)
(pCilg dry)
Be-7 30 20 50 0.03 0.05 K 60 20 Cr-51 40 10 100 0.05 0.1 fo,-54 3
0.5 30 0,02 0.03 Co-58 3
0.6 30 0.02-0,03 Fe-59 6
1 60 0.03 0.06
. Co-60 3
0.6 30 0.02 0.03 Zn 65 8
-1 70 0.04 0.07 Zr/Nb-95 5
2 50 0.03 0.05 Ru 103
'3 2
40 0.03 0.04 Ru-106 30 5
30 0.02 0.03 Ag 110M 5
3 90 0.02 0.03 l-131 4
2 30
.0.02 0.03 Te-132 4
2
-20 0.01 0.02 1133 4-2-
20 0.01 0.02 Cs-134 4
0.6 30 0.02 -
0.03 Cs 136-6 0.6 50 0.03 0.05
- Cs-137 4
0.6 20 0.02 0.03 Ba-La 140 10 6-40 0.02 0.N
- Cc-141 6
2-60
-0.03 0 06 Ce-144 30 5
-200 0.1 0.2 Ra-226 60 6
600-0.3 '
O.6 '
l Th-228 -
10 1
60 0.03 j.
0.06 At time of analysis (DLC Contractor Lab).
Activity detected in all samples.
NOTE: Lower Level of Detection is defined in Beaver Valley Power Station Technical
. Specifications.
seenor 5. ENVIRONVENTAL McNfTORING PROGR Au 5-21
. Duquesne Light Company
~
1991 Annual Radiciogical Environmental Report B
Air Monitoring y>
-1, Charatterization of Air and Meteorology The air in the vicinity.of the site contains pollutants typical for an industrial area.
Air flow is generally from the Southwest m scmmer and from the Northwest in the winter.
. 2. -
. Air Samplin0 Program and Analytical Techniques a; Program The air is sampled for gaseous radiciodine and radioactive particulates at each of ten (1) offsite air sampling stations. The locations of these stations are listed in Table 5-1 and shown on a map in Figure 5-1.
Samples are collected at each of these s,tations 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 > adiciodine sampling. Samples are collected for analysis-on a weekly basis.
The charcoal is used in the weekly analysis of airborne I-131. The filters are 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 frorn 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 papar 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.
1
_5-22 sect,on 5 ENVIRONMiNTAL MONITORING PROGRAM 2
i
Duquesne Light Company 1991 Annuai Radictogica! Environmental Report Figure 51 Air Samphng Stat.ons
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Section 5 ENVIRONMENTAL MONITOR.NG pr,0GRAu G-23
i P
Duquesne Light Company 1991 Annual Radiol _ogical Erivironmental Report l Strontium-89 andi Stry.ctium-90 activities are determined in quarterly.
_com_ posited air particulo s filters. Stable strontium carrier is added to the sample and it is leached in nitric acid to bring' deposits into sobtion. The
- mixture is then filtered. Half of the filtrate is taken for strontium analysis und is reduced in volume by evsporation. Strl, tium is precipitated as
' Sr(NO )3. using fummg (90%) nitric acid, An iron (ferric - hyoroxide) 3 scaven0e is performed, followed by addition of stable yttriurn carrier and a 5 to 7 day period for. yttrium in0rowth. 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 m a low level beta counter to infer. -Sr-90 activity. St-89 activity is determined by precioitating SrCO 3
from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered wi'h 80 mg/cm? aluminum absorber for 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 t'venty (520) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years.
Figure 5-2 illustrates the average concentration of gross beta in air
- particulates.
The-weekly. air particulate samples were composited to one hundred twenty (120) monthly samples which were analyzed by Gamma i
- spectrometry.
Naturally occurring-Be-7 was present in every sample.
Occasional traces above detection' levels of other naturally occurring nuclides such as K-40 were present. These are listed in the summary Tabte ' 5-2.
..1 A total of forty (40) quarterly samples were Mach analyzed for Sr-S9 and
~
St-90. No Sr 39 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 CY 1991, b.
Radiciodine -
A total of five hundred twenty (520) weekly charcoal filter samples were analyzed -for 1-131.
No--detectable concentrations were found at any locations.
Based on analytical results, the operation of Beaver Valley Power Station-did not contribute to any increase in airborne radiciodine during CY 1991.
5-24 Shu.on 5 EW!RoNMENTAL MONToRING PROGRAM
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<1 Io Duquesne Light Company -
1991 Annual Radiological Environmental Report m
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a-C.
Monitoring _of _ Sediments and Soils (Soil Monitoring is required every 3 years and was R
required in 1991)
E L
ti Characterization of Stream Sediments and Soits l.
l.
The stream sediments consist largely of sand and silt. Soil samples may vary l
from sand and sitt to a heav/ clay with variable amounts of organic material.
i i
2.
_ Sampling Program and Analytical Techniques a.
Program -
River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and l
above the New Cumberland Dam. A Ponar_ or Eckman dredge is used to L
collect the sample. The sampling locations are also listed in Table 5-1 and are_shown in Figure 5-3.
l Soil samples were collected at each of ten (10) locations during 1991. At-1, each location 12 core samples (3~ diameter by 2~ deep) are gathered at prescribed points on a 10 foot radius circle. Each location is permanently marked with reference pins.
Each set of samples is systematically
. selected by moving along the radius in such a manner as to ast,ure representative undisturbed samples.
Sampling locations are listed in Table 5-1 and are shown in Figure 5-3.
Bottam sediments and soils are analyzed for gross alpha and beta activity.
strontium, and the gamma-emitting radionuclides.
b.
Analytical Procedures Gross beta - sediments and soils are analyzed for gross beta by mounting
(.
a 1= gram portion-of dried sediment in a 2" planchet.
The sample is l
counted in a low background, gas flow proportional counter.
Self absorption corrections are made on the basis of sample weight.
Gross alnha activity of sediment or soil is analyzed in thp 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 mi plastic bottle which is counted by a gamma spectrometer, s
i 5-26 Seaon 5. ENVIRONMENTAL MONITORING PROGRAM
I Duquesne Light Company 1991 Annual Radiological Environmental Report Figure-53 Enytronmental Momforing Locations - Shorehne Sediments and Soil N
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I section 5. ENVIRONMENTAL MONITORING DROGRAv 5 27
.~.
T Duquesne Light Company-1991 Annual Radiological Environmental Report
- Strontium 89 and 90 are determined by radiochemistry A wei hed sample 0
of sediment or boil is leached with Nitric' Acid'HNOp A~ stable carrier is added for determination of - recovery.
Strontium. concentration and purification is ultimately realized by precipitations of strontium nitrate in-
. fuming nitric acid.
Additional hydroxide precipitations and - barium chromate separations are also used. The purified strontium is converted to a carbonate for weighing and counting. Samples are counted soon after j
separation (5 - 7 days is allowed for yttrium ingrowth).
Activities are calculated on the bass of appropriate Sr-89 decay and Y-90.
Separate mounts covered with a 80 mg/cm2 aluminum absorber are used for counting in a low background beta counter.
3.
Results and Conclusions 1
A summary of sediment and soil analysis is presented in Table 5-2.
a.
Sediment A total of six (6)-samples were analyzed for gross alpha and gross beta.
Results were comparable to previous years.
. A total of six (6) samples were analyzed for Sr 89 and St 90. No Sr-89 or -
Sr+90 was detected.
A total of six (6) sample were analyzed by gamma spectrometry. Naturally occurring K-40.- Ra-226, and Th-228 was found in every sample ano. Be-7 was found in two samples.
Small-amounts of Cs-137 from previous nuclear weapons test,were found in all river sediment samples ' including
. upstream above Montgomery Dam, which are unaffected by plant effluents.
- Small amounts of Mn-54, Co-58, Co-60 and Cs 137 were detected in the
~
Beaver Valley Power Station discharge area and are attributable to station
- releases. The-activity found in the station discharge area is consistent j
with station data of authorized radioactive discharges. which were within limits permitted by the NRC license.
The analyses demonstrate that the Beaver Valley Power Station did not contribute = a significant - increase - of radioactivity in the Ohio River sediment. The positive results detected are attributable to authorized releases from the Beaver Valley-Power Station and-are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate -and' that the environmental monitoring program is sufficiently sensitive.
b.
Soil i
Results of soil analysis are comparable to preoperational data.
a 5-28 sectm 5 ENV1RoNMENTAl. McNtTORING PROGRAM
Duquesne Light Company 1991 Annual Radiological Environmental Report D.
Monitorir.g of Feederops and Foodcrops 1.
Characle'rization of Vegetation and Foodcrops According to the 1990-1991 statistical summary of the Pennsylvania Department of Agriculture, there were approximately 570 farms in Beaver County. The total value of farm crops and livestock was $17.093,000. The principal source of revenue was in dairy products which were estimated at 57.386.000. Revenues from other farm products were estimated as follows:
Field Crops l
51,478.000 Fruits
$222.000 Horticulture and Mushrooms S3.533.000 Meat and Animal Products 53.384.000 Vegetables and Potatoes
$592.000 Poultry Products S132.000 The total land in Beaver County is 279.020 acres. Approximately 147,900 acres are forested land an 59,063 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. August,1991 to locate the nearest residence and nearest garden of greater than 500 square feet producing fresh leafy vegetables within a five (5) mile radius of the site _
See Table 5-5 for results.
Foodcrops (vegetables) were collected at garden locations during the summer of 1991, Leafy vegetables, i.e., cabbage were obtained from St.ippingport. Georgetown, industry, PA and Weirton. WV.
Atl samples were analyzed for gamma emitters (including 1-131 by gamma spectroscopy).
Section 5 ENVIRONMENTAL MoNITokiNG PROGRAM 5-29
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1991 Annual. Radiological Environniental Report
. Table 5-5.. Closest Residence and Garden in Each Sector e
- TABLE S-5 Clo est Residence and Garden in Each Sector
--S ector Closest Residence * -
Closest Garden
- 1 1I55 mi N 2.01 mi N.
'2 1.59 mi NNE 1.61 mi NNE 3 __
0.42 mi NE 0.53 mi NE
.j 4.
0.38 mi ENE 0.93 mi ENE 5
0.42 mi E 1.93 mi E 6
0.87 mi ESE 1.00 mi ESE 7
1.40 mi S
. 2,16 mi S 1
10-0.80 mi SSW-1.55 mi SSW t
11 1,46 mi SW--
-1.67 mi SW 12
'1.46 mi WSW 1.46 mi WSW 13 2.27 mi W
- 2.27 mi W 14-2.77 mi WNW 2.96 mi WNW 15 -'
O.91 mi NW -
0.92 mi NW 16-
- 0.91 mi NMW 1.29 mi NNW
<
- Direction and Distance from Midpoint between Reactors-
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Section 5. ENVIRONMENTAL MONITORING PROGRAM 5 31
l' Duquesne Light Company 1991 Annual Radiological Environmental Report l
- b..' Procedures L
Gamrpa emitters, including 1131, are determitied by scanning a dried, i
homogenized sample with the gamma spectroscopy system.
A high resolution german'Jm detector is utilized with this system.
Strontium 90 analysis for feedstuff is performed by a procedure similar to that described in 5-C.2.
L L
Radiciodine (1-13] is determined by radiochemistry. Stable iodide carrier is first added -to a chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace.
The melt is dissolved in water. filtered and treated with sodium p
hypochlorite. The iodate is then reduced to iodine with hydroxylamine l
hydrochloride and is extracted into chloroform. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium l-iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
I l
3.
Results and Conclusions n
I i
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 taal of four (4) samples were analyzed for Sr-00. Small amounts of Sr-90 from previous nuclear weapons tests were found in all samples.
A total of twelve (12) samples were analyzed by gamma spectroscopy.
Naturally occurring K-40 was found in all semples and Be-7 was detected in four (4) samples.
b, Food A total of four (4) samples were analyzed for 1-131.
No detectable l --
concentrations were found.
l; j_
A total of four (4) samples were analyzed by gamma spectrometry.
j Naturally occurring K-40 was found in all samples.
l
- c. The data from food and feed analyses were consistent with (or lower than) those obtained in the preoperational program. These data confirm that the Beaver Valley Power St$ tion did not contribute to radioactivity in foods and feeds in the vicinity of the site.
l l
i:
l 5-32' sw,n 5. ENW4oNMENTAL MONITORING PROGRAM
~_..
Duquesne Light Company 1991 Annual Radiological Environmental Report E.
Monitoring of Local Cows Milk 1.
Description - Milch Animal Locations 1
g During the seasons that animals producing milk (tmich arumats) for human consumption are on pasture, samples of fresh mil are obtained train these ammals at locations and frequencies noted in Table 5-1 This nulk is analyzed for its radiosodiae tentent calculated as lodine-131. The ana!yres are prforrned within e'ght (3) dayF of sampling Detailed ficid surveys are performed during the grating season to locate and enurnerate nutch animals Within a five (S) nulo radius of the site. Goat herd locations out to !!!!een (15) miles are identified. Survey data for the most recent survey conducted in August,1991 is shown in Figuro 5 5.
-2.
Sampling Program and Analytical Techniques a.
Program Milk was collected from these (3) reference dairy farms (Searight's, Brunton's and Nicol's) within a 10 mile radius of the site and frorn one (1) control location (Windsheimer's) outsido of the 10. mite radius. Additional datries, which represent the highest potential rmik pathway for radiotodme based on milch atumal surveys and meteorological data were selected and sampled. These dairies are subject to change based upon availabihty of milk or when more recent data (milch animal census) Indicate other locations are more appropriate.
The location of each is shown in Figure 5-6 and described below.
Direction and Dislam from Collettson Madpomt between 4 <,tters Period
--4
?f, Searight 43 Cows 2.2 moes Stu Jan Dec
' 2T Brurton 03 Cows 7.3 moes SE Jan t.
20A Ncoi 70 Cows -
8.0 m ies NE J.m Dec j
90 Wmet he nier
$3 Cows 10.3 moes SSW Jai oet.
301 "
Teres:
1 Goat' 2.6 Wes E May sept tc?'
F erry 4 Goats' 3.3 maes sE F en
- Oct
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131 Vosen iCow 0.98 moes ESE 1DM*
fordyce 2 Goats' 2,50 mues NNW 10$"
Ambrose 38 cows 3.86 mees wbW Nov 1
s/
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1 Conrta 33 Cows 3J5 moes wSW gg j
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2 Goats 4.28 moes Nw M4 Osage + Nome Oniy.
Negr+est po'ertal namway da4 ries Section 5 i NVIRONMENT A'. MONITORING PROGRAM
Duquesne Light Company 1991 Annual Radiological Environmental Report figure 5,5 Bem er Vaney ro.er si.. tion Milc h Animal (engyg s
I BE AV E R VA L LE Y P OW E RS TAT I O N MILCH ANIMAL CENSUS--
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MILK sec: ion s ENVIRONMENTAL MONITORING PROGRAM 5-35
.Duquesne Light Company 1991 Annual Radiological Environmenta' Report The sample from Searight Dairy was collected and analytod weekly for radiciodine using a procedure with a high rensitivity. Samples from each of the other selected dairies were collected monthly when cows are indoors, and bi woekly when cows aro grazing. This monthly or bi weekly sample is analyzed for St 89, Sr 90, gamma emitters including Cs-137 (by high resolution germanium gamma spectroscopy) and 1-131 (lugh sensitivity analysis),
b.
Procedure Radiciodine ' (1131) analyshi in milk was normally performed usmg chemically prepared samples and analyzed with a low-level beta counting system.
Qam,ma emitters are determined by gainma spectroscopy of a one liter Marinelli container of milk.
Strontium analysis of milk is similar to that of other foods (refer to 5-C 2) except that rnilk samples are prepared by addition of Trichloracetic Acid (TCA) to produce a curd which is removed by filtration and discarded. An oxalate precipitale is ashed for counting.
3.
Results and Cone!usions A summary of data is presented in Table S-2.
A total of one hundred sixty-six (166) samples were analyzed for I 131 during 1991. All 1131 activities in milk were below the minimum detectable level.
A total of one hundred thirty four (134) samples were analyzed for St-89 and Sr-90, - No St 89 was detected. Sr 90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the normally expected range.
A total of one hundred thirty-four (134) samples were analyzed by gamma spectroscopy. The predominate isotope detected was naturally occurring K 40 and was found in all samples. Cs 137 was detected in one (1) sample.
It was r'oted that the dalries with the highest annual mean activities were goal 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 ra'dioactivity in mi!k in the vicimty of the site.
5 36 ; Senon 5. ENv1RONMENTAL MoNiTo4ING PROGRAM
Duquesne Light Company 1991 Annual Radiological Environmental Report F.
Environmental Radir.tlon Monitoring 1.
DescriplIon of Regional Background Radiation and Sources The tetrain in the vicmity of the Beaver Valley Power Stahon generally consists of rough fulls with altitude varbrtions of 300 400 feet. Most of the land is woodnt The princ$al geotogic features of the region are nearly flat faying sedimentary t>eds of the Penrsylvania Age, Beds of nmestone alternate with sandstone ar'd shale with-abundant interbedded coa! layer s.
Pleistocene glacial deposits partially cover the older sedimentary deposets in the northwest. Most of the region is underlain by shate, sandstone, and r.ome coal beds of the Conemaugh i
Formation.
Outcrops of sandstone. shale, and li;nestone of the Allegheny Formation exist withm the Ohio River Valley and along major tributary streams.
)
Based on surveys. reported in previous annual reports, exposure rates ranged-from G-12 pR/hr Results for 1991 inuicated that background radwfinn contmued in this range 2.
. Locations and Analytical Procedures j
Ambient enternal radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).
i In 1991 there were a total of forty-four (44) off site environmental TLD locations, j
The locations of the TLDs are shown in Figure 5 7 through Figure 510. Thirteen (13) locations also have QC Laboratory TLDs. Both laboratories use calcium sulfato dysprosium. (CaSOgDy) in Teflon matrix.
The catc;Jm sulfate (CaSOjDy) TLDs were annealed shortly belore placing the TLDS in their field locations. The radiat'on dose accumulated in transit between the field IMation and the laboratory was corrected by annealing control dosimeters shortly before the field dosimeters were removed from the field location, when shipping the freshly _ annealed control dosimeters with the exposed field dosimeters to the laboratory 'nr readout at the same time. All dosimeters were exposed in the field in a special environmental holder..The dosimetry system was calibrated by reading calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation field, in addition to' TLDs. Pressurized lon Chambers (PIC) provide continuous integrating monitoring. Sixteen PICS (Sites' 116) are part of the Sentri 1011 Radiation Monitoring System which is a microcomputer based data acquisition system.
Data from the stat ons are'sent at regular intervals to the Central Processing Unit were integrated doses are calculated. In addition there are four.
PICS.which are AC. Radiation Monitors.
These are inspected weekly for i
integrator readings. The locations of the PICS are shown in Figure 511.
t Sectmo $ ENVIRONMENTAL MONITORING * : 54 Av 5 37
Duquesne Light Company 1991 Annual Radiolo0ical Environmental Report i
3.
Results and Conclusions Data obtair ed with the contractor TLD (CaSO :Dy in Teflon) during 1991 are i
4 summarized in lable 5-2, and the quahty control TLD results are listed in Table 31. Results for the PICS are hsted m Tablo 5 6.
The annual exposure rate of all off site TLDs averaged 0.16 rnR/ day in 1991. As in previous years, there was some variation among locations and seasons as would be expected Two TLDs were lost in the field during the year.
In 1991, loniting radiation dose determinations from TLDs averaged approximately 58 mR for the year. This is comparable to prev >ous years. There I
was no evidence of anomalies that could be attributed to the operation of the Beaver Valley Power Station.
The TLDs confarrn that changes from natural
~
radiation invels. il any, are negligible.
i I
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Duquesne Light Company 1991 Annual Radiological Environrt1 ental Report l
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Duquesne Lrght Company 1991 Annual Radiological Environmental Report r,gwe f.s TLD Locatont Nmtbeav' Ou;drani beaver vailey Power statiae, 5
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Duquesne Light Company 1991 Annual Radiological Environmental Renert Figure 510 TLO torat.ons South *e4 C iadrant Oeaver Valley Io*e* Station i
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'S-42 section s-ENVIRONMENT L MONITORING PROGRAM
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Duquesne Light Company 1991 Annual Radiological Environmental Repcrt T$e 5 6 Pressuri;cd lon Cha abets.1941 Results imR' day)
TABLE 5-6 Pressurized toLGhambers 1991 Results (mR/ dam Distance and Direction Average Site Location from Midpoint (mR/ day)
Between Reactors 1
industry Hill 0.5 mi N.
0.188 2
Industry Rt. 68 0.9 mi NNE 0200 3
Industry 2.25 mi NE 0.104 4
Cooks Ferry 0.5 mi ENE 0,199
-5 Shipoingport Bridge South 0.45 mi E 0.221 6
BVPS Entrance 0.4 ml ESE 0.216 7
Unit 2 Laydown 0.3 mi SE 0.210
.8 Birdhill Road 0.9 mi SSE 0.222 9
Past DLCO Microwave 0.35 m. S 0.209 10 OLCO Microwave 0.35 mi SSW 0.206-11
.Meyer's Furm 1.45 mi SW 0.228 12 J&L Steel Tie 0.75 mi WSW 0.216 13 F. P. Microwave 1.5 mi W 0.182 14 Midland Substation South
. 0.6 mi WNW 0.212 15 Midland Substation North 0.75 mi NW 0228-16 Sunrise Hills 1.1 mi NNW 0.202-t AC-201 Raccoon Municipal Building
- 2.4 mi S E O252 AC-202 Kennedy's Corners 2.0 mi NE O240 Z 054-Hookstown Substation 2.9 mi WSW 0.254 Y-028 J&L-1.3 mi NW 0.166 i
5-44 Section $ Et4VIRONMENTAL 40NITORING _PROGR Au
)
Duquesne Li0ht Company 1991 Annual Radiological Environmertal Report G.
Monitoring of Fist.
l 1.
Description During 1991. fish collected for the radio:ogical monitoring program included l
bass. carp. catfish. sheephead and shad.
2.
Sampling Pro 0 ram and Analytical Techniques a.
Program Fish samples are collected semi _-annually in the New Cumberlar'd pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the ' Montgomery Dam. The edible portion of each diffrront species
.l caught is analyzed by 9 mma spectroscopy. Fish sampling locations are shown in Figure 512.
b.
Procedure t
A sample is prepared in a standard ta'ud 300 ml clastic bottle and scanned for gamma emitting nuclidas with gamma spectrometry system which utilizes a high resolution germanium detector.
3.
Results and Conclusions A sumtnary of the results of the fish monitoring data is provided in Table 5-2.
)
A total of nine (9) samples were analyzed by garnma spectroscopy. Naturally occurring K 40 was found in all samples.
Tho' analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River fish population E
4 4
1 4
i sea:on 5 tavlRONMEN1 AL MONITCRING PROGRAv 5 45
. -.. - =. -
Duquestie Light Lornparty 1991 Annual Radiological Environmental Report i
Figure 5 12 Environmentai Mon tonng Program. Fisn Sampling Locatic,ns s
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1991 Annual Radiological Enveronmental Report H.
Monitoring of Surface, Drinking, Well Waters and Precipitation i
1.
Description of Water Sources The Ohio River is the main body of water in the area. It is used by the Beaver Valley Power Station for plant make up for the cooling tower and for receiving plant liquid effluents.
i Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site. It is used by several municipahties and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Mumcipal Water Authority.
The intake of the treatment plant is approximately 1.5 rulles 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. Some of these plants also have private treatment facilities for plant
- sanitary water.
Ground water occurs in large volumes in the gravel terraces which lie alon0 the river, and diminishes considerably in the bedrock underlying the site. Norrial well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm.
In General, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year.
The record mean annual precipitation for the area is 36.40 inches based on 1972 to 1990 data collected at the Pittsburgh international Airport, t
e Lect on 5 ENVIRONVENTAL MONITORING PROGR AU 5 m,
__.m Duquesne Light Company 1991 Annual Radiclogical 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 412] daily and composited into a monthly sample. Weekly grab samples are taken from the Ohio River at the followmg 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 l'
following locations: Upstream of Mont0cmery Dam ',; River Mile 29.6); and at J&L Steel's river water intake [ River Mile 36.2]. The automatic sampier takes a 20-40 mi sample every 15 minutes and is collet.ted on a weekly basis..
The weekly grab samples and automatic water samples are i
composited into monthly samples from c1ch location.
In addition, o quarterly composite sample is prepared for each sample point.
Tne weekly composites from the automatic river watbr sampler upstream i
at Montgomery Dam are analyzed for 1131.
+
The monthly composites are analytod for gross alpha, gross beta, and gamma emitters. The quarterly composites are analited for H 3. Sr 89.
)
Sr 90, and Co-60 (high sensitivity).
)
Locations of each sample point are shown in Figure 5-13 b.
Drinking Water (Public Supplies)
Drinking (treated) water is collected at bnth Midland (PA) and East Liverpool (OH) Water Treating Plants, An automatic sampler at each location collects 20-40 ml every 20 minutes. These intermittent samples i
are then composited into a weekly sample. A weekiy grab sample is also taken at the DLC Training Building in Shippingport, PA.
The weekly sample from'each location is analyzed by gamma spectroscopy.
The weekly samples are also analyzed for 1131.
Monthly composites of the weekly samples are analyzed for gross alpha.
gro.3 beta, and by gamma spectrometr/.
Quarterly ccmposites are analyzed for H 3, St 89, Sr 90 and Co 60 (high sensitivity). Locations of each sample point are shown in Figure 513.
t p
. 5-4 8 ' Secon 5. ENVIRONMENTAL MONI10R4NG PROGRAM
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Duquesne Light Cornpany l
10')1 Annual Radiologicat F,nvironmental Report
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c, Ground Water Grqb samples ' ware collected each quarter from each of four (4) well locations (see Figure 513) within four (4) miles of the site.
Theso iutations are:
I 000 (1) well at Shippingport, PA' l
t One (1) well at Meyer s Farm (Hookstown, PA) f One (1) well in Hookstown, PA
[
i Or o (1) well in Georgetown, PA Each ground water m.mple is analyzed for Dross alpha, gross beta, tritium, and by gamma spectroscopy.
d.
Precipitation
?recipitition is collected at Shippingport, PA. East Liverpoot OH_ and
['
'Weirton, WV. Precipitation when available is collected each week and then cornpesited into monthly and quarterly sarnples, The monthly samples are analyzed for gross bola and gamma emitters and the quarterly composites
^
are anal zed for H 3, St-89 and St 90. Locations of each sample point are
/
chown in Figure 513, i
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WELLS, SURFACE WATER, DRINKIT6 WATER, y
T AND PRECIPITATION 6
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.. - _. _. _.m Duquesne Light Company
'j 1991 Annual Radiolo0 cal Environmental Report i
e.
Procedures i
Gross afgha and cross _twta 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 f!ow proportional counter. Self absorption corrections are made on the basis Of sample weight.
Qamma anaty.Rs is performed on water sample by loading one hter of sample into a one liter Marinelli container and countmg a GetLi) gamma spectrometry system.
Strontium-80 and 9Q are determmed on water samples by a procedure
- simitar ' to that described m 5-C.2 except that the leaching step is eliminated.
i
_C_gpalt 60 is determined with a sensitivity of 1 pCuhter by evaporatmg 2 hters.of sample on a hutplate and transferrmg the residue to a 2-mch planchet. The planchet is counted on a high resolution germaniur" Damma spectrometry syaterm i
Tritium is determined in water sampkts by converting 2 ml of the sample to hydrogen and counting the activity in a 1 liter low level gas counter which is operated in the proportional range in anti-coincidence rnode.
Radicioding (1131) analysis in water was normally perfmmed using chemically prepared samples and analyzed with a low-level beta countmg system.
'3.
Results and Conclusions i
i A summary of results of all analyses of water samples (surf ace, 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 in one of the samples at a level comparable ' to preoperational values.
Positivo beta results above preoperational levels were detected in the OVPS discharge area and are attributable to station releases.- The beta activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were,within limits permitted by the NRC license.
A total of sixteen (16) samples were analyzed for H 3, Sr 89 and Sr-90 as I
well as a high sensitivity analysis for Co-58 and Co 60. Positive Co-58 and-tritium results were detected in the BVPS discharge area and are attributable to station releases, All other samples taken-upstream and downstream were within '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, e
L se: bons ENVIRONMENTAL McNif0 RING PROGR Au 5-51
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i Duquesne 1.ight Company 1991 Annual Radiological Environmental Report
)
A total of forty eight (48) samples were analyzed by gamma spectrometry.
Positive Co 58 results were detected m the BVPS discharge area and are attribstable to station releases. The Co 5B activity found i, the station discharge area is consistent with station data c' authurized radioactive discharges and were within limits perrnitted by the NRC license. No other gamma emitting radionuclides were detected.
A tota, of fifty two (52) samples were analyzed for l 131 using a highly sensitive technique. Trace levels of I 131 were rueasured in eighteen (18) of the weekly samples. Th9 results were slightly above the minimum detectable activity. The positive results were detected at a contre' location above the BVPS discharge and could not be attributed to plant releases.
The results may be attributed to medical procedures and the exported i
variabihty in the analyses results of very low levels of activity.
b.
Drinking Water A total of thirty six (36) samples were analyzed for gross alpha and gross beta. All results were within a normal range, A total of twelve (12) samples were analyzed for H 3, St 89 and St 90 as
~ well as a high sensitivity analysis for Co-60. No Sr 89. Sr-90, or Co-60 were detected.
The H 3 data were withm the preoperational range indicative of normal environmental levels.
A total of another one hundred hfty-seven (157) samples were analyzeo by gamrna spectrometry. No gamma emitting radionuclides were detected.
A total of one hundred fifty-seven (157) samples were analyzed for 1131 using a highly sensitive technique. Trace levels cf I 131 were measured in forty seven (47) of the weekly samples. The results were slightly above the minimum detectable activity. The positive results were detected at Midland and East Liverpool and could not be attributed to plant releases.
As noted under Surface Water above,1131 has been observed upstrean' of the site, The results may be attributed to medical procedures and the expected variability in the analyses results of very' low levels of activity, c.
Ground Water A total of sixteen (16) samples were each analyzed for gross alpha, gross beta, H 3 and by gamma spectrometry. No alpha activity was detected in any of the sampics. The gross beta and H 3 results are comparable to preoperational ranges. K 40 was the only gamma emitting radionuclide detected.
I d.
Precipitation A total of twenty seven (27) samples were analyzed for gross beta. All results were within a normal range.
A total of twelve (12) samples were analyzed for H 3, St-89 and Sr-90. Two l-(2) positive tritium results detected were within normal levels. No St-89 or Sr 90 was detected, A to1al of twenty seven (27) samples were analyzed by gamma i
l-spectrometry.
Naturally occurring Be-7 was detected in eighteen (18)
. samples.
l
- 5-52 setion 5. ENVIRONMENTAL MONITORING PROGRAM a
2.
J
. - -. _.. ~ _ _ _ _..
Duquesne Light Company 1931 Annual Radiological Environmental Report e.
Summary The data from water analyses demonstrates that the Beaver Valley Power Sta'tlon did not contribute a si nificant increast of radioactivity in iocal 0
river, drinking, well waters or precipitation. The few positive results which could be attributable to authorized releases from the Beaver Valley Power I
Station are characteristic of the effluent. These results contrm that the station assessments, prior to authorizing radioactive dischar0HS. are adequate and that the environmental monitoring program is sutficiently j
sensitive.
Further, the actual detected concentration (averaged over the total batch j
discharge period during the year) attributable to Beaver Valley Power l
Station. was only 0.360*o of the Maximurn Permissible Concentration 1
allowed by the Federal Regulations for water discharged to the Ohio River.
[
The Ohio River further reduced this concentration by a factor of ~ 600 prior to its potentjal use by members of the public.
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Duquesne Light Company 1991 Annual Radiological Ensironmental Report t.
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listimates of Radiation Dose to Man
[
t, Pathways to Man Calculational Models i
The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using NRC computer codes XOODOQ2 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 ot the BVPS license. were used as the idionuclide activity input.
Each radionuclide contained in the Semi-Annual Radioactive Effluent Release Report (noble gases, particulates, radiciodines and tritium) were included as source terms when they were detected above the LLD values. All LLD values reported by Beaver Valley Power Station are equal to or lower than those required by the Technical Specifications.
All gaseous effluent r > leases, including Auxiliary Building Ventilation, were Lincluded in dose assessments. The release activities are based on laboratory analysis. When the activity of noble gas was below detection sencitivity, either the inventory based on its MDL or an appropriate but conservative ratio to either rneasured activity of Kr-85 or Xe 133 was used. Meteorological data collected by the Beaver Valley Power Station Meteorolo0y System was used as input to XOOOOQ2 which in turn provided input for GASPAR. Except when more recent or specific data was available, all inputs were the same as used in tae Beaver Vsliey Power Station Environmental Statements or in Regulatory Guide 1.109.
Tb3 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 rnode 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 Wion outtall (River Mile 35.0), The actual data from these analyses are tabulated and used as the radionuclide activity input term in LADTAP. A hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specille data for the period is available, all other input to LADTAP are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1109.
Pathways, which were evaluated, are drinking water, fish consernpuon, shoreline recreation, swimming, and boating.
l 5-54'. section 5. ENVIRONMENTAL MONITORING PROGR AM
_ _.. ~
-. _ -.. -- - - - - -. _ - - - - - - - - ~.. _. - - -
I wuquesne Light Company -
3 1991 Annual Wadiological Environmental Report i
2.
Results of Calculated Radiation Dor.e to t,iar. Liquid Releases l
i l
- a. Individual Dose l
i The doses which are calculated by the model described above are to a j
i hypef.<ctical real individual located at Midland since this is the nearest j
location where significant exposure of a member of-the pubhc could j
j potentially occur; therefore, this location is use to calculate the maximum i
exposure. A breakdown of doses by pathway and organ is'provided in l
l Table 5-7 for the maximum individual.
Included in this table is a I
breakdown of a typical dose to individuals from natural radiation exposure.
The results of calculated radiation dose to the hypothetical real individual j
h are compared to BVPS annual limits m Table 5 8.
t l
b.
Upon implementation of the Unit 2 Technjcal Specifications and inception of the liquid discharge procedures at 'Jnit 2 on July 24.1987, the discharge j-hmits -were clarified to be reactor specific; i.e., Unit 1 and Unit 2 have l
reactor specific dose limits that are equal to the limits in 10 CFR Part 50.
I
. Appendix.l.
. Therefore, the annual site limits listed in Table 5 9 are specific to this report only, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2).
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6-Duquesne Light Company l
1991 Annual Radiological Environmental Report L
Table 5 8 Results of Calcutated Radiation Dose to Man BVPS Liquid Releases i-TABLE 5-8 Results of Calculated Radiation Dose to Man Beaver Valley Power Station Liquid Releases j
l BVPS Annual Percent of t il R I Organ mi s Annual j
Individual mrem Limit t
TOTAL-B_OQY '
- Adult -
0.00195 6.0 0.033 j
Teen 0.00111 S.O
_ 0.019
{
Child 0.00105 0.0 0.033
' infant 0.00282 6.0 0.047=
{
- ANY ORGAN l
Adult -
0.00223 (GI LLI) 20.0 0.011 i
Toen 0,00133 (Liver) 20.0 0.0067 Child 0.00200 (Liver) 20.0 0.010 l
Infant 0.00288 (Liver) 20.0 0.014 t
Maximum Total Body Dose Capsule Summary r
mrom 1991 Calculated 0.00282 Final Environmental Statement 3.5 -
I r
li!ghest Ornan Dose r
1991 Calculated
.0.00288 Final Environmental _ Statement 4,7 s
3 Y
9 9
b t
i Section 5, ENVIRONMENTAL MONITORING PROGRAu
_5 57_
. Duquesne Light Company 1991 Annual Radiological Environmental Report 1
c.
Population Dose The 1991 calculated dose to the entire population of almost 4 million i
people within 50 miles of the plant was:
"'U'
' E' Organ "f.:.o Millirems Contributors TOTAL BODY 96.7 H3 94.5 mrem Fe-55 1.0 mrom THYRO!D-94.6 H-3 94.5 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 1991 are provided in Table 5-9. The doses include the contribution of all pathways. A 50 mile population dose is also calculated and provided in Table 5 9.
H-3 is the primary radionuclide contributions to these doses.
The results are compared to the BVPS annual limits in Table 5-9.
As in the i
ilquid 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 9 are specific to this report only, and were derived by multiplying the individual Technical
- Specification reactor limits by a factor of two (2). The results show comphance with the BVPS annual limits.
i
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5 58 Swon 5. ENVIRONMENTAL MONITORING PROGRAM.
_.m._.._.____....-._
Duquesno tight Codipany 1991 Annual Radiolo0lcal Environmental Repor(
4 4.
Conclnsions. (Beaver Valley Power Station)
Based upon the estimated dose to individuals from the natural background radiation exposure m Table $ 7, the incremental increase in total body dose to the 50amle population (4 million people), from tho operation of Beaver Valley Power Station Umt 1 and 2, is less than 0.0001'. of the annual background.
The calculat(.. doses to the pt.blic from the operation of Beaver Valley Power Station iUnit 1 and 2, are below BVPS annual hmits and resulted in only a small incremental dobe to that which area residents already received as a result of natural backgrouni The doses constituted no rneaningful risk to the pubbc.
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t seci,cn 5. ENVIRONMENT AL MONITORING FROGRAM -- 5 59
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r" Duquesno Light Company 091-Annual Radiological Environmental Report Table 5 9 Resutes of Cateviated Rat tion Dese to Man (1991 ?VPS Atmosv.ene Releases i
TABLE 5-9 Results of Calculated Radiation Dose to Man (1991)
Beaver Variey hwer Station - Atmospheric Releases MAXIMUM 50 MILE gygg N
A lON ORGAN ANNUAL LIMIT INDIVIDUAL ANNUAL LIMIT DOSE-mrem man rem TOTAL BODY 0.0971 30 0.32 1.24 SKIN 0.106 30 0.35 1.55 LUNG 0.0973 30 0.32 1.26 THYROID 0.171 30 0.57 1.82 6
(
_ 5-60 Section 5. ENVIRONMENTAL MONITORING PROGRAM
APPENDIX l
Contractor Laboratory 1
EPA Interlaboratory
]
1
-Comparison Program Al-1
.4 4
, -- m k
DUQUESNE LIGHT COMPANY 1991'
~
s'u"
- US fiPA IffilD *.*a'itATORY COMPARISON PitOGRAM 'lWI -
m..-c I of 3)
EPA.
Dese TI MeHed - - ; Deee EPA '
EPA Tl
' Norm llev.
- Wareleg ;
' Preperstlee Results lessed Results Media j
Nesult:(a)
Nesults(h)
(Knowe)
- *
- A c a les w
. C1/1181 03M781-
-04/1581
' Waser "
Sr89 501-50 5 ou i 0 00 0 oo Sr-90 5.0 t..
50
- 5.00 1 0 00 0007 01/25St 02/2181 03/1881 Weser <
Gross Alpha
-50i.
. 5.0 9 00 i L 1.00 :
139 Gross Beta 5.0 e
'5.0 7.00 1 0 00 0 69 02J08SI 03/22/91 04/19/91 Waser
. Ca60 4001 5.0 39.33 1 - 3 06.
-4)23 Zn45' 149 0 i 15 0 147.00 1 1.00 0 24-Ru-106 186 0 i 19 0 176 67 i 17.56 -
-0 85 Cs.134 80i
' 5.0 7.33 1 0.58-
-0.23 Cs-137 801 5.0 7.67 i '
3.21
-0 12 Be 133 75.0 i 8.0..
75.67 i 5.51 0.14 02/15/91 03/1SSI 0543/91 Weser I 131 75.0 i 80 80 00 i 5.29 I Os 02/22/91 03/22 S 1 04/1581
' Weser 11-3 4418.0 i. 442.0 4500 i o I73.21 0 32 0328/91 0546/91 05/3181 Weser Ra-226' 3181 4.8 28.33 1 4.73 1.25 Ra-228 21.1 1 5.3 16.67 1 2.03
-1.45 03/29/91 0646/91 0742S!
As fileer Grus Alphs 2501 60 42.67 1 0.55 5 10
-"n)
Gross Beta 124.0 1 6.0 12667 :a 5 77 0.77 Sr-90 40.0 1 50 37.00 i 1.00
.s 04 CaI37 4001 5.0 43001 5.29 I 04' 04/16/91 07/2581 Waser Cnoss Alpha 5401 14 0 59 67 i 4 04 0 70 Ra-226 8.0 i.
l.2 7331 0 81
-0 w, Ra-228 15.21 38 10001 0 00
-2 47
- %1)
Gross Beta
' 115 0 t 17.0 110 00 1 0 00 0 51 Sr-89 2801 50 31 00 i 1 00 1.04 Sr-90 26 0.1 5.0 21.00 1 0 00
-1.71 Cs-134 2401 50' 25001 1 00 0 35 Cs 137 2501 5.0 24 00 i 1.73
.-0 35 04/26/91 06."28 S 1 07/3181 Mak Sr 89 3201 50 24001 3 00 2 77
" (cI Sr.90 3201 5.0 26311 2.08
. l.9e.
1 131 6001 6.0 53.33 1 231 1.92 Cs.137 49.0 1 50 52 67 i. I.53 1.27 K
'1650 0 1 83.0 1590 00 1 81.85
-I 25 l
Nsswiscs are Immic41 sa crxl of taNc.
=
DUQUESNE LIGHT, COMPANY. - 1991 US EPA lifiutLABG'2NIICY COMPARISON PROGRAM 1991 (Page 2 of 3)
EPA Date Tl Malled '
Date EFA EPA.
~ TI-Noren De
- War eleg
' PreparatM Resulte leseed Reseks
- Media NucIlde Resulte(e)
Nesules(h)
( K now n) '
- *
- A c t io n
- 05/10/9i1 05#36/91 05/1991 Wakr -
Sr-89.
3901
- 5.0 38671.
4.51
-012
~
- Sr-90 24.0 1 5.0 22 00 i 1.73
-Ofn 05/17NI
' 06/13/91 07A18/91 Wake :
Onuss Alges 2401 60 24.33 1 '
2.52' O.10 Cnoss Beta -
4601 5.0 50331 1.53 1.50 06417M1 07/1881 08/12 S 1 Wassr
' Co-60 1001 5.0 10.33 1 0 58 0 12
- 7s 65 108.0 i '
. I 1.0 106 00 1 2.65
-o 31 Ru-106 149.0 1 15.0 136 67 i - 3 79
-I42
'Cs-134 15.0 1 50 13 67 i 1.53 4)46 Cs-137 14.0 1 5.0 13671 1.53
-0.12 Be-133 62.0 1 60 56331 1.53
-1.64 06/21 S 1 07/18/91 08/12/91 Weser
. II-3 '
124801 1248.0 12833.33 1 115.50 049 07/12N1 100R/91.
09A)6/91.
Weser Re-226 1591 2.4 15.0 i 1.0e
-0 65 Ra-228 16.7 i 4.2 14.33 1-2.31
-0.98 08AN/91 1308/91 09/04/91 W eser 1-131 20 0 i '
60 19.33 i C.58
-0 19 Oc.10/91
'10/25/91 12AN/91 Air fileer On-Alpha 2501 60 27.00 1 2.00 0 58 Cn Beta 92.0 i 10 0 100 00 1 0 00 I.39 St-90 3001 5.0
.27.67 1 2.89
-0 s1 Cs-I37 30.0 1 5.0 33.3) i 3.21 1.15 1
09/13/91 10/25/91' 12/12/91 Wseer Sr-89 4901 5.0
.50671' 2.89 0.58 Sr-90 25.0 1 5.0 26 00 i 1.00 0.35 09/2091 10/17BI I1A)4/91 Waser Gr-Alpha ~
1001.
50 1: 67 i' O.58 '
03M Gr-Beta 2001 5.0 21.00.1.
0 00 0.35 j
09/27 MI 12536/91 12/23/91 MA Sr-89 2501 5.0 21001 2 65
-1.39 Sr90 2501 5.0 19.00 1 0 00
-2 08
- *( c )
1-131 108 0 i-li 0 113 33 1 5 77 o 84 Cs-137 30.0 1 50 29001 3 61
-0 35 K
1740.0 1 87.0 1503.33 i. 75 06
-4.71
~ (f) r liars >tes are locaicd an end of tabic, 3
a
b s
UUQUESNE LIUllT COMPANY - 1991 IIS ITA INT 11RI ADC?.ATORY COMPARISON IROGRAM 1991 (Page 3 of 3)
EPA Date TI Mailed Date EPA EPA TI
. Norm Dev.
" Warning Premration Results issued Results Media Nuclide Result:(a)
Results(h)
(Known!
"* A c tion IMH/91 11/15N1 12/12SI Wascr Co60 29.0 1 5.0 30.33 1 2 0x 0 46 2n 65 7301 70 72.67 1 7.09 0 08 Ro-106 IW 01 20 0 197.67 1 7 51
-0.12 Cs-134 10.0 t 50 10.33 1 0 58 0 12 Cs-137 1001 50 Il.331 0 58 046 Da-I33 98.0 1 10 0 97.00 i N.72
-0 17 IWI8SI I1/15/91 12D4/91 Waar II-3 24540 1 353 0 2333 33 1 57.74 4 59 10/22N1 OIA)2N2 Ol/21N2 Wara Onuss Aloha 8201 21.0 55001 4 36
-2 23
~ (gi Ra-226 2201 3.3 21001 2.65
-0 52 Ra-228 22.2 1 5.6 18001 1.00
-13)
Gruss Beta 65 0 i 10 0 56 00 i 1.00
-I 56 St-89 to 01 50 10.67 1 2 08 0 23 Sr-90 10 0 i 50 9331 0 58
-0 23 C#60 2001 50 19671 0 58
-0.12 Cs-134 1001 50 10331 2 08 0 12 Cs-137 11.0 1 50 13.67 1 0.58 0.92 II A)a>91 OIK12N2 Ol/21N2 Waser Ra-226 6.5 i 1.0 5 37 t 0 32 I%
Ra-228 8.1 1 2.0 7.90 i 1.20
-0 17 (2)
Average i czpmmental sigma.
(b)
Expected laboranary precisim (I sigma. I desciminatum).
(d) ne lowest three results out d nine analyses were ehcaen. Other results in the group were close to the given value. He posess fiw acceptwg data is currenely ualer review (2)
Tbc cause far the deviation is lelieved to be errincously high strtetium yacids, probably caused by inavnplaic separazion ef calcium 'Ihe lat=wakwy has invesargaaed carner concentrations sod pipeting acchnigees, and have found them to te corrett Further aspects of analysts' techniques are being sessed 'Ibe tal=sas.ey has ret esved a new stnerium extractim material devek at Arganne Naexmal I Axwaiory. Expenmects with this meth=1 ao actueve bener separatam ci aaburn were awnpleted and pnsedure IHO O 42 lm was impicmented un 2/f-.
(f) here is no apparent cause ka the km K-40 resuits. Two other isotspes spaed in the sample ere in g<xai agreement with I PA values 11nd umverwms were resiewed anJ found to be cswrectly.W Ibssible background errtws in ge4:netry were anwesus sicJ and found to have an trisignifs arit c f fett (g)
ISteable failure to transfer all sample residue to the counting plaru.het. Analysts are being tested using in imuse and other ITA spacs
=US EPA CROSS: CHECK l PROGRAM GROSS BETAIN AIR PARTICUIATES 160 140 -
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100 -
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APPENDIX ll QC Laboratory r
EPA Interlaboratory
-Comparison Program AII-1
J.
i APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
TIML participates in intercomparison studies administered by U.S. EPA Environmen, Monitoring Systems Laboratory,.Las Vegas, Nevada. The results are reported in Appendixi Also reported are results of in-house spikes and blanks. Appendix A is updated twice a year; ;
complete Appendix is. included in January and July monthly reports only. Please refer to Janu; and July reports for information. -
, January,1992
- AII '
Appendix A Interlaboratory Comparison Procram Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated i interlabordory comperison (crosscheck) programs since the formulation of its quality control program in December 1971, These programs are operated by agencies which supply environmental type sam milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories, The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
Participant laboratories' measure the concentration of specified radion alldes and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environmental wmple crosscheck program for milk, water, air filters, and food samples during the period January 1988 through November 1991. This program has been 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 dosimeters (TLDs) during the period 1976, 1977,1979,1980,1984, and 1985-86 through participation in the Second, Third, Fourth, Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed.
Table A-3 lists results of the analyses on in house spiked samples.
Table A-4 lists results of the analyses on in-house " blank" samples.
Attachment B lists acceptance criteria for " spiked" samples.
Addendum to Appendix A provides explanation for out of-limit results.
AII-3
Table A 1. U.S. Environmental Protection Agency's crmscheck program, comparison of EPA and Telt - '
Isotopes Midwest Laboratory results for mil, water, air filters, cnd focd samples,1988 throu IW1.a Concentration inaf[L(b EPA Resultd Lab Fample Ebte TIML Result Control Ccdc Type Collected Analysis 12aC is, N= 1 Limits 3TW 521 Water Jan 1988 Sr-89 27.315.0 30.015.0 21.3-38.7 Sr 90 15.311.2 15.011.5 12.4 17.6 STW 523 Water Jan 1988 Cr. alpha 2311.2 4.015.0 0.0-12.7 Cr. beta 7.711.2 8.015.0 0.0 16.7 STW 524 Food Jan 1988 Gr 89 44.014.0 46.015.0 373-54.7 Sr 90 53.0t2.0 55.012.8 50.2 59.8 1131 102.314.2 102.0110.2 M 3 119.;
Cs-137 95.716.4 91.015.0 82.3-99.7
~
K 10111158 1230162 1124 1336 s
STW 525 Water Feb l988 Co-60 69.3 :2.3 69.015.0 60 3-77.7 Zn-65 99.013.4 94.019.4 77.7 110.1 Ru 106 92.7114.4 105.0110.5 86.8-123.:
Cs-134 61.713.0 64.015.0 55.3-72.7 Cs 137 99.713.0 94.015.0 85 3-102.7 STW 526 Water
't b l988 H3 34531103 33271362 2700-3954 e
STW 527 Water Feb 1968 Uranium 3.010.0 3.016.0 0.0 13.4 STW 528 Milk Feb 1988 1 131 4.711.2 4.010.4 33-4.7 STVJ 529 Water mar 1988 Ra 226 7.110.6
611.1 5,6-9.6 Ra 228 nae 7.711.2 5.79.7 STW 530 Water Mar 1988 Cr. alpha 4311.2 6.015.0 0.0 14.7 Cr. beta 13 .13 13.015.0 43 21.7 STAF-531 Air Filter Mar 1988 Cr. alpha 21.012.0 20.015.0 11.3-28.7
' Gr. beta 48.010.0 50.015.0 413 58
Sr 90 16.711.2 17.011.5 14.4-19.6 Cs 137 18.7113 16 Di5.0 7.3-24.7 STW 532 Water Apr 1988 I-131 9 012.0 7.5f0.8 62-88_
All-4'
Table A 1. (continued)
~
Concentration in t<i/Lb ETA Resultd Lab Sample Date TIML Result
. Control Code Type Collected Analysis t2ac 1s, N=1 Limits STW 533 Water Apr 1988 SM (Blind)
Sample A Cr. alpha NDI 46.0111.0 27.0-65.0 Ra 226 ND 6.411.0 4.78.1 Ra 228 ND 5.610.8 4.27.0 Uranium 6.016.0 6.016.0 0.0-16.4 Sample B Gr. beta ND 57.015.0 48.3-65.7 Sr89 3311.2 5.015.0 0.0 13.7 Sr 90 5.311.2 5.011.5 2.47.6 Co60 63.3113 50.015.0 41.3-58.7 Cs 134 7.7tl.2 7.015.0 0.0-15.7 Cs 137 8311.2 7.015.0 0.0-15 7 STU 415 Urine Apr 1988 H3 64831155 62021620 5128-7276 STW 536 Water Apr 1988 Sr 89 14.711 3 20.015.0 11.3 28.7 Sr 90 20.0+ 2.0 20.011.5 17.4-22.6 STW 538 Water Jun 1988 Cr 51 331.7113.0 302.0130.0 250.0 354.0 Co40 16.012.0 15.015.0 63 23.7 Zn 65 107.7111.4 101.0110.0 83.7 1183 Ru 106 191.3111.0 195.0120.0 160.4-229.6 CS-134 18314.6 20.015.0 11.3-28.7 Cs-137 26311.2 25.015.0 16.3-33.7 STW 539 Water Jun 1988 H3 5586192 55651557 4600-6530 STW-541 Milk Jun 1988 Sr 89 33.7111.4 40.015.0 31.3-48.7 Sr 90 55315.8 60.013.0 54.8-65.2 1131 103.713.1 94.019.0 78.4 109.6 Cs 137 52.713.1 51.015.0 42.3 59.7 K
1587123 1600180 1461 1739 STW 542 Water Jul1988 Cr, alpha 8.7i4.2 15.015.0 6.3 23.7 Gr. beta 5311.2 4.015.0 0.0 12.7 STF 543 Food Jul 1988 St 89 NDI 33.0i5.0 24.3-41.7 Sr 90 ND 30.012.0 30.5-37.5 I131 115.0153 1c"' 0111.0 88.0 126.0 Cs-137 52.716.4 49.015.0 40.2.-57.7 K
1190166 1240162 1133-1347 All-5
Table A 1. (continued)
Concentration in r<i/Lb FPA Resultd lab Sample Date TIML Result Control Code Type Collected Analysis 12csc Is. N=1 Limits ETW 544 Water Aug 1958 I131 80.010.0 76.018.0 62.1 89.9 STW 545 Water Aug 1988 Pu 239 11.010.!
10.211.0 8.511.9 j STW 346 Water Aug 1988 Uranium 6.010 0 6.016.0 0.0-16.4 STAF 547 Air Filter Aug 1988 Gr. alpha 8.010.0 8.0:.3.0 0.0-16.7 l Gr. beta 26.311.2 29.015.0 20.3-37.7 i St-90 8.012.0 8.011.5 5.4-10 6 Cs-137 13.012.0 12.015.0 3.3207-STW 548 Water Sep 1988 Ra 226 9.310.5 8.412.6 6.0 10.6 Ra 228 5.810.4 3.411.6 4.06.8 STW 549 Water Sep 5988 Gr. alpha 7.012.0 8.015.0 0.0-16.7i Cr. beta 11.311.2 10.0i5.0 1.3-18.7:
STW 550 Water Oct 1988 Cr 51 252.0114.0 251.0A25.0 207.7 294.3 Co-60 26.012.0 25.015.0 16.3 33.7 Zn-65 158.3110.2 151.0115.0 125.0 177.0 Ru 106 153.019.2 152.0115.0 126.0 178.0 Cs u4 28.715.0
.25.015.0 16.3-33.7 C5137 16.311.2 15.015.0 6.3-23.7,
l STW 551 Water Oct 1988 H.3 2333i127 23161350 1710-2927 STW 552
. Water Oct 1988 553 (Blind)
Sample A' Cr. alpha 38.318.0 41.0110.0 23.7 58.3:
Ra 226 4.510.5 5.0i0.8 3.6-6.4 Ra 228 4.410.6 5.210.8 3.6-6.4 Urantum 4.7tl.2 5.016.0 0.0 15.4 Sample B Gr. beta 51.313.0 54.0iS:0 45.3-62.7!
- Sr-89 3.711.2 11.015.0 2.3 19.7' Sr 90 10.711.2 10.011.5 7.4-12.6 C5134 15.312.3 15.0t5.0 6.3-23.7i C5137 16.711.2 15.015.0 6.3-23.7!
-A11-6
Table A 1.- (continued)
Concentration in nCi/Lb
~
d FPA Resull _
lab Sample Date TIML Result Control Code' Type Collected Analysis 12cc is, N=1 Limits STM 554 Milk Oct 1988 Sr89 40.317.0 40.015.0 31.3 48.7 Sr 90 51.012.0 60.013.0 54.8 65.2 1131 94.0 3.4 91.019.0 75.4-106.6 C3-137 45.014.0 50.015.0 41.5 4 7 K
1500145 1600180 q.,i 1739 STU 555 Urine Nov 1988 H3 30301209 30251359 2403 3647 STW 556-Water Nov 088 Gr. alpha 9.013.5 9.015.0 0 3-17.7 Cr. beta 9.711.2 9.015.0 0 3-17.7 STW 557 Water Dec 1988 1131 108.713.0 115.0112.0 94.2 135.8 STW 559 Water Jan '.989 Sr-89 40.018.7 40.015.0 31.3 48.7 Sr 90 24.313.1 25.011.5 22.4-27.6 STW 560 Water Jan 1989 Pu 239 5.811.1 4.210.4 3.5-4.9 STW 561 Water fan 1989 Gr. alpha 7.311.2 8.015.0 0.0 16.7 Gr. beta 5.311.2 4.015.0 0.0-12.7 STW 562 Water
' mb 1989 Cr 51 245146 235124 193.4-276.6 Co 60 10.912.0 10.015.0 1 3-18.7 Zn-65 170110 159116 139.2 186.7 Ru 106 18117.6 178118 146.8-2W.2 Cs-134 9.713.0 10.015.0 1.3 18.7 Cs 137 11.711.2 10 015.0 1,3 18.7 STW 563 Water Feb l989 I131 109.014.0 106.0111.0 86.9 125.1 STW 564 Water Feb 1989 H3 2820i20 27541356 2137 3371 STW 565 Water Mar 1989 Ra 226 4.210 3 4.9 0.7 3.7-6.1 Ra 223 1.911.0 1.710 3 1.22.2 STW 566 Water Mar 1989
,U 5.010.0 5.016.0 0.0 15.4 STAF 567 Air Filter Mar 1989 Gr. alpha 21.711.2 21.015.0 12.3 29,7 Cr. beta 68314.2 62.015.0 53.3 70.7 Sr 90 20.012.0 20.011.5 17.4 22.6 Cs-137 21.311.2 20.0i5.0 1?3-28.7 AII-7
Table A 1. (continued)
Concentration in r$Ci/Lb E 'Aghd 12b Sample Date TIML Result Control Ccde -
Type Collected Analysis 12aC is. N=1 Limits STW 568 Water Apr 1989 569 (B!ind)
Sample A Cr. alpha 22.712.3 29.017.0 16.9-41.2 Ra 226 3.610.6 3.510.5 2.6-4.4 Ra 228 2.611.0 3.610.5 2.7-45 U
3.010.0 3.016.0 0.0 13.4 Sample B Gr beta 52.316.1 57.015.0 433-651 Sr 89 9.315.4 8 015.0 0.0 161 St 90 7.010.0 8.011.5 5.4 10.6 C3134 21.015.2 20.015.0 11.3-28J Cs 137 3.012.0 20.0.15.0 11.3-28J STM 570 Milk Apr 1989 St-89 26.0110.0 39.015.0 30.3-47.7 Sr-90 45.714.2 55.013.0 49.S 60.2 Cs 137 54.016.9 50 HA0 41.3-58J K-40 15211208 1600130 1461 173s STW-5718 Water May 1989 Sr-89
<0.7 6.015.0 0.0 143 Sr 90 5.011.0 6.011.5 34-8.6 STW 572 Water May 1989 Cr. alpha 24.012.0 30.018.0 16.1 43.9 Gr. beta 49.3115.6 50.015.0 41.3 583 STW-573 Water Jun 1989 Ba 133 50.711.2 49.015.0 40.3-57; Co-60 31.312.3 31.015.0 22.3-39.5 Zn 65 167i10 165117 135.6-194 Ru 106 12319.2 123113 105.5-150 Cs-134 40.311.2 3915 30.3-47.'
Cs-137 22.3.t).2 20i5 11.328.:
STW 574 Water Jun 1989 H3 45131136 45031450 3724-52S STW 575 Water Jul1989 Ra-226 16.8i3.1 17.712.7 13.0 22.s Ra-228 13.813.7 18.312.7 13.6 231 STW-576 Water Jul 1989 U
40.311.2 41.016.0 30.6151 STW V7 Water Aug 1989 I131 S4.715.8 83.0 8.0 69.1 96.*
y STAF 579 A.ir Filter Aug 1989 Gr. alpha 6.0i0.0 6.015.0 0.0-14.:
Cs-137 10.312.3 10.015.0 1.3-18.:
A11-8 l
l Table A 1. (continued) i Concentration in rCi/1.b FPA Resultd le Sample Date TIML Result Control Code Type Collected Analysis 12 oC is, N=1 Limits STW 5S0 Watei Sep 1989 Sr 89 14.711.2 14 01.5.0 5322.7 St 90 9.711.2 10.011.5 7.4-12.6 STW 581 Water Sep 1989 Gr. alpha 5 010.0 4.015 0 0.0 12.7 Gr. beta 8.712.3 6.015.0 0.0-14.7 STW 583 Water Oct 1989 Ba 133 (0.3110.0 59.016.0 48.6-69.4 Co 60 29.014.0 30.015 0 21.1 38.7 Zn 65 132.316.0 129.0113.0 106.5 151.5 Ru 1" 155.316.1 161.0116.0 133.3 188.7 G :.h 6.'.' +6.1 29.015.0 20.3-37.7 Cs.37
-11 59.015.0 50.3 67.7 STW 584 Water Oct 1989 H3 uJ71r30 3496t.364 286614126 STW 585 Water Oct 1989 586 (Blind)
Sample A Gr. alpha 41.719.4 49.0112.0 28.2-69,8 Ra 226 7.910.4 8.411.3 6.2-10.6 Ra 228 4.41 0.8 4.110.6 3.15.1 U
12.010.0 12.016.0 1.6 22.4 Sample B Gr. beta 31.712.3 32.015.0 23.3-40.7 Sr 89 13.314.2 15.0 5.0 6.3-23.7 St 90 7.012.0 7.013.0 4.4-9.6 Cs 134 5.0.to.0 5.015.0 0.0-13.7 Cs-13
7.0io.0 5.015.0 0.0-13.7 STW-587 Water Nov 1989 R 226 7.910.4 8.711.3 6.4 11.0 Ra 228 b.9il.2 9.311.2 6.9 11.7 STW 588 Water Nov 1989 U
15.0do.08 15.016.0 4.6-25.4 STW 589 Water Jan 1990 Sr 89 22.715.0 25.015.0 16.3 33.7
' Sr 90 17.311.2 20.011.5 17.4-22.6 STW 591 Water Jan 1990 Gr. alpha 10.313.0 12.015.0 3.3-20.7 Gr. beta 12.311.2 12.015.0 3.3-20.7 i
Al1-9
I Table A 1. (continued)
)
Qncentration in t<i/Lb
]
FPA Resultd
]
Lib Sample Date TIML Result Control l Ccde Type Collected Analysis 12aC 1s, N=1 Limits STW 592 Water Jan 1990 CcHO 14.712.3 1515.0 6323.7 Zn-65 135.016.9 139.0114.0 114.8 163 2' Ru 106 133.3 13.4 139.0114.0 114.8 163.2 Cs-1M 17.311.2 18 015.0 9.3 26.7 Cs 137 19.311.2 18.015.0 9.3 26.7 :
Ba 133 78.010 0 74 017.0 61.9-S6.1 STW-593 Water Feb l990 H3 4827183 49761498 4113-5839 STW 594 Water Abr 1990 Ra-226 5.010.2 4.910.7 4.157 Ra-228 13.510.7 12.711.9 9.4 16.0 STW-595 Water Mar 1990 U
400.0 4.016.0 0.0-14.4 STAF 596 Air Filter Mar 1990 Gr. alpha 7.311.2 5.015.0 0.0-13.7 Cr. beta 34 010.0 31.015.0 22.3-39.7
$r 90 10.010.0 10.011.5 7.4 12.6 CS-137 9.311.2 10.015.0 1.3-18.7 STW-597 Water Apr 1990 598 (Blind)
Sample A Cr. alpha 81.013.5 90.0123.0 50.1 129.7 Ra 226 4.910.4 5.010.8 3.6-6.4 Ra-228 10.610.3 10.211.5 7.6-12.8 U
18.713.0 20.016.0 9.6-30.4 Sampie B Gr. beta 51.0110.1 52.01.5.0 43.3 60.7 Sr-89 9.311.2 10.015.0 1.3-18.7 Sr 90 10.313.1 10.011.5 8.3-11.7 Cs-134 16.010.0 15.015.0 6.3-23.7 C3-137 19.012.0 15.015.0 6.3 23.7 STM-599 Milk Apr 1990 Sr 89 21.713.1 23.015.0 14.3-31.7 br 90 21.017.0 23.015.0 14.3 31.7
.1-131 98.711.2 99.0110.0 81.7 1163 CS 137 26.016.0 24.015.0 15.3-32.7 K
1300.0169.2 1550.0178.0 1414.7 16S5 STW-600 Water May 1990 Sr 89 6.012 0 7.015.0 0.0-15.7 Sr 90 6.711.2 7.015.0 0.0-15.7 STW-601 Waier May 1990 Gr. alpha 11.012.0 22.016.0 11.6-32.4 Cr. beta 12.311 2 15 0150 63-237 AII-10
Table A 1. (continued Concentration in nCi/Lb FPA Resultd Lab Sample Date TIML Result
o n t rol Code Type Collected Analysis 12oC 1s, N=1 Lirnits STW 602 Water Jun 1990 Co-60 253123 24.015.0 153 32.7 Zn 65 155.0110.6 148.0 15.0 130.6-165.4 Ru 106 202.7117.2 210.0121.0 173.6-246.4 C3-134 23.711.2 24.015.0 18.2-29.8 Cs-137 27.7t3.1 25 015.0 163 33.7 Ba 133 100.718.1 990 10.0 8171163 STW 603 Water Jun 1990 H3 29271306 29331358 2312 3554 STW 604 Water Jul1990 Ra 226 11.810.9 12.111.8 9.0 15.2 Ra 228 4.111.4 5.111.3 2.S7.4 STW 605 Water Jul '990 U
20.311.7 20.813.0 15.6 26.0 STW 606 Water Aug 1990 1131 43.011.2 39.016.0 28.6149.4 STW 607 Water Aug 1990 Pu 239 10.011.7 9.110.9 7.5-10.7 STAF 608 Air Filter Aug 1990 Cr. alpha 14.010.0 10.015.0 13-18.7 Cr. beta 65.311.2 62.015.0 533-70.7 Sr 90 19.0i6.9 20.0 5.0 11 3-28.7 Cs-137 19.012.0 20.015.0 11.3 28.7 STW 609 Water Sep 1990 Sr 89 9.012.0 10.015.0 1 3-18.7 Sr 90 9.012.0 9.015.0 03 17.7 STW 610 Water Sap 1990 Cr. alpha 8311.2 10.015.0 1.3-18.7 Cr beta 10.311.2 10.015.0 13-18.7 STM 611 Milk Sep 1990 Sr 89 11.713.1 16.015.0 73 24.7 Sr-90
- 5.010.0 20.0 5.0 11 3-28.7 1131 63.016.0 58.016.0 47.6-68.4 Cs-137 20.012.0 20.015.0 11.3-28.7 K
1673.3170.2 1700.0185 0 1552.5-1847.5 STW-612 Water Oct 1990 Co-60 20313.1 20.015.0 11 3-28.7
- Zn-65 1153112.2 115.0112.0 94.2 135.8 Ru 106 152.013.0 151.0115.0 125.0-177.0 Cs 134 11.010.0 12.015.0 3 3-20.7 Cs-137 14.012.0 12.015.0 3 3-20.7 Ba 133 116.719.9 110.0111.0 90.9 129.
STW 613 Water Oct 1990 H3 7167i330 72031720 5954-8452 A!!-11
Tabl2 A 1, (continued)
Concentration in pCl/Lb EPA Resultd Lab Sample Date TIML Result Control -
Code Type Collected Analysis 12ac is, N=1 Limits STW 614 Water Oct 1990 615 Sample A Gr. alpha 68.717.2 62.0116.0 34.2 89.8 l Ra 226 12.910 3 13.612.0 10.1 17.1 Ra 228 4.210.6 5.011.3 2.7 73.
U 10.410.6-10.213.0 5.0 15.4 ;
Sample B -
Cr beta 55.018.7 53.015.0 44.3-61.7 -
Sr 89 15.712.9 20.01.5.0 113 28.7, St 90 12.012.0 15.015.0-63 23.7 Cs 134 9.011.7 7.015.0 0.0 15.7 i Cs 137 -
7.711.2 5.015.0 0.0 13.7 '
- STW 616 Water Nov 1990 Ra 226 6.811.0 7.411.1 5.593 Ra 228 5.311.7 7.711.9 4,4-11.0 :
. STW 6178 Water Nov 1990 U
35.0f0.4 35.513.6 29.3141.7!
STW 618 Water
- Jan 1991 Sr 89 4311.2 5.015.0 0.0 13.7 '
Sr 90 4.711.2 5.015.0 0.0 13.7 i STW-619 Water Jan 1991 I % 239 3.620.2 3310.3 2.83.8 STW 620
- Water.
Jan 1991 Cr. alpha 6.713.0 5.015.0 0.0 U.7-Cr. beta 6311.2 5.015.0 0.0 13.7 STW-621 Water Feb l991 Co 60 41318.4 40.015.0 31 3-48.7 Zn 65 166.7119.7-149.0il5.0 123.0-175.0-Ru-106 209.7118.6 186.0i19.0 153.0 219.0; Cs-134 9.012.0 8.015.0' O.046.7 J Csr137 9.711.2 8.015.0 0.0-16.7-Ba-133 85.7d9.2 75.0i8.0 61.1 88.9 STW 622 Water Feb 1991 1131
- 813k6.1 75.018.0 61.1 88.9 STW-623 Water Feb 1991 H3 4 10.01144.2 4418,01442.0 3651.2 5184 STW 624
' Water Mar 1991 Ra-226 31.4i3.2 31.814.8 23.5-40.1 Ra-228 NDh 21.115.3 11.9 30.3 STW 625.
Water Mar 1991 U
6.710.4 7.613.0 2.4-12.8:
' f i
- AII-12 1
'r tw.
-m-
-,r-reve.-.~
s-
~
v
,~,,,e-N,--ve,,ve
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.e.,m---edw,
-w---ee~v-a,c----e
,w, r+-,-
-wvme-
l Table A 1. (continued) l Concentration in rCi/Lb EPA R6ultd lab Sample Ebte TIML Result Control Cade Type Collected Analysis 12ac is, N=1 Limits STAF-626 Filter Mar 1991 Gr. alpha 38.711.2 25.016.0 146-354 Gr. beta 130.014.0 124.016.0 113.6 134 4 Sr 90 35.711.2 40.015.0 31.3-487 Cs-137 33714.2 40.015.0 31.3-487 STW 627 Water Apr 1991 628 Sample A Gr. alpha 51.016.0 54 0114.0 297 78.3 Ra 226 7.00.8 8.011.2 5.9 10.1 Ra 228 9.711.9 15.213.8 8.6 21.5 U
27.712.4 29.813.0 24.6 35.0 Sample B Gr. beta 93.316.4 115.0117.0 85.5-144.5 Sr 89 21.013.5 28.015.0 19336.7 Sr 90 23.010.0 26.015.0 173 347 Cs 134 27.311.2 24.015.0 15.3 32.7 C3137 29.012.0 25.015.0 16333.7 STM 629 Milk Apr 195il St 89 24.018.7 32.015.0 23.3 407 St 90 28.012.0 32.015.0 23.3 40.7 1131 65.3114.7 60.016.0 49.6 70.4 Cs 137 54 1111.0 49.0.t3.0 40.3-57.7 K
1591.71180.1 1650.0183.0 1506.0 1794.0 5TW-630 Water May 1991 Sr-89 40.712.3 39.015 0 30.3-47.7 Sr-90 23.711.2 24.015.0 15.3 32.7 STW 631 Water May 1991 Gr. alpha 27.715.8 24.016.0 134 34.4 Gr. beta 46.0d0.0 46.015.0 37.3 54.7 STW-632 Water Jun 1991 Co60 11.311.2 10.015.0 1.3-18 7 Zn 65 119,3116.3 108.0111.0 88.9 127.1 Ru 106 162.3119.0 149.0115.0 123.0 175.0 Cs 134 15.311.2 15.015.0 6.3-23.7 Cs-137 16.311.2 14.015.0 5.3-227 Ba 133 74.016.9 62.016.0 51 6-72.4 STW-633 Water Jun 1991 H3 13470.01385.8 12480.011248.0 10314.8-14645.2 STW 634
. Water Jul 1991 Ra 226 14.910.4 15.912.4 11.7 20.1 Ra-228 17.611.8 16.714.2 9.4 24.0 l
A!!-13
(
Table A 1 (continued)
Concentration in t'Cl/lb FPA Reiultd lab Sarnple Date TIML Result lontrol Ccde Type Collected Analysis 12cc 15, N=1 Limits STW 635 Water Jul 1991 U
12.810.1 14.213.0 9.0 19.4 STW 636 Water Aug 1991 1 111 19.311.2 20.016.0 9.6304 STW-637 Water Aug 1991 Pu 239 21.410.5 19.4i1.9 16.1 22.7 STW-638 Filter Aug 1991 Gr. alpha 33.012.0 25.016.0 14.6-35.4 Gr. beta 88.71).2 92.0110.0 80.4-103.ti Sr 90 27.0i4.0 30.015 0 21 3-38.7 Cs-137 26311.2 30.015.0 21 3-38.7 STW-639 Water Sep 1991 Sr 89 47.0110.4 49.015.0 403 57.7 Sr 90 24.012.0 25.015.0 163-33.7 STW 640 Water Sep 1991 Gr. alpha 12.014.0 10.015.0 1 3-18.7 Cr. beta 20.311.2 20.015.0 11 3-28.7 STM 641 Milk Sep 1991 St-89 20315.0 25.015.0 163-33.7 Sr 90 19.713.1 25.015.0 163 33.7 I131 130.7116.8 108.0111.0 88.9 127.1 C3-137 33.713.2 30.015.0 21 3-38.7 K
1743.31340.8 1740.0187.0 1589.1 1890 STW 642 Water Oct 1991 CcH50 29.711.2 29.015.0 203 37.7 Zn-65 75.713 3 73.017.0 60.9 85.1 Ru 106 1 %.3115.1 199.0120.0 164 3-233.:
CS 134 9.711.2 10.015.0 1 3-18.7 C3-137 11.012.0 10.01S.0 13 18.7 Ba 133 94.713.1 98.0110.0 80.7 115.2 STW-643 Water Oct 1991 H3 2640.01156.2 2454.01352.0 1843 3 3061 STW 644 Water Oct 1991 645 Sample A Gr. alpha 73.0113.1 82.0121.0 45.6 118..I Ra-226 20.912.0 22.013 3 163-27.7 Ra 228 19.6123 22.215.6 12.5 31.9
'U 13.510.6 13.513.0 8 3-18.7 Sample B Gr. beta 55.313.1 65.0110.0 47.7 823 St 89 9.713.1 10.0i5.0 13 18.7 Sr 90 8.711.2 10.015.0 1 3-18.7 Co40 20.3i1.2 20.015.0 11.3-28.7 Cs 134 9.015 3 10.015.0 1 3-18.7 Cs-137 14.715.0 11.015.0 2 3-19.7 1
i Al1-14
Table A 1, (continued) l C.grgnJ. ration in rCl/Lb FPA Resultd lab Sample Ebte TIML Result Control Ccde Type Collected Analysis 12 00 1s, N=1 Limits STW 646 Water Nov 1991 Ra 226 5.611.2 6.511.0 4.88.2 Ra 228 9.60.5 8.112.0 4.6 11.6 STW.647 Water Nov 1991 U
24.712.3 24.9 3.0 19.740.1 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support laboratory, U.S. Environmental Protection Agency (EPA), Las Vegas, Nevada, b All results are in pCi/1, except for elemental potassium (K) data in milk, which are in mg/1; air filter samples, which are in pCl/ filter; and food, which is in mg/kg.
c Unless otherwise indicatal, the TIML results are given as the mean i 2 standard deviations for three determinations, d USEPA results are presented as the known values and expected laboratory precision (1s,1 determinationi and control limits as defined by EPA.
e NA = Not analyzed.
I ND = No data; not analyzed due to relocation of lab.
5 Sample was analyzed but the results not submitted to EPA because deadline was missed (all data on file).
h ND = No data; sample lost during analyses.
AII-IS
Table A 2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR Teledyne Average 12e lab Result Known (All Code TLD Type Measurement 12ca Valuec Participants) 2nd International Intercomparisonb 115-2 CaF :Mn Field 17.011.9 17.1 16.417.7 2
Bulb lab 20.814.1 21.3 18.817.6 3rd International Intercomparisone 115-3 CaF :Mn Field 30.713.2 34.914.8 31.513.0 2
Bulb lab 89.616 4 91.7114.6 66.2124.0 4th International Intercompmitonf 115-4 CaF :Mn Field 14.111.1 14.111.4 16.0 9.0 2
Bulb Lab (low) 9.311.3 12.212.4 12.017.4 12b (High) 40.411.4 45.819.2 43.9113.2 Sh International Intercomparison8 115-5A CaF :Mn Field 31.411.8 30.016.0 30.2114.6 2
Bulb lab at beginning 77.415.8 75.217.6 75.8140.4 Lab at the end 96.615.8 88.418.8 90.7131.2 115-5B LiF-100 Field 30314.8 30.016.0 30.2114.6 Chips Field at beginning 81.117.4 75.217.6 75.8140.4 Lab at the end 85.4111.7 88.413.8 90.7131.2 E
7th International Comnarisonh 115-7A LIF-100 Field 75.412.6 75.816.0 75.li29.8 Chips Lab (Co40) 80.013.5 79.914.0 77.9127.6 Lab (C3137) 66.612.5 75.013.8 73.012 All-16.
Table A 3. Cross. check program results, thermolumir c.= cent dosimeters (TLDs).
mR Teledyne
. Average 12cd Lb Result Know (All Code TLDType Measurement 1203 Valuec Participants) 115 7B CaF :Mn Field 71.512.6 75.816.0 75.1129.8 2
Bulbs bb (Co-60)
M.816.4 79.914.0 77.9127.6 bb (Cs-137) 78.811.6 75.013.8 73.0+ M 2 115 7C CaSO :Dy Field 76.8 2.7 75.816.0 75.1129.8 4
Cards Lb (Co40) 82.513.7 79.9i4.0 77.9127.6 Lab (C5137) 79.013.2 75.013.8 73.0122.2 L
8th Interrational intercomparisoni 115-8A LIF-100 Field Site 1 29.511.4 29.711.5 28.9112.4 Chips Field Site 2 11.310.8 10.410.5 10.1 9.06 bb(Cs 137) 13.710.9 17.210.9 16.216.8 115-8B CaF :Mn Field Site 1 32.311.2 29,711.5 28.9112.4 2
Bulbs Field Site 2 9.011.0 10.410.5 10.119.0 Lab (Cs 137) 15.8 0.9 17.210.9 16.216.8 115-8C CaSO :Dy Field Site 1 32.210.7 29.711.5 28.9112.4 4
Cards Field Site 2 10.610.6 10.410.5 10.li9.0 bb (Cs-137) 18.110.8 17.210.9 16.216.8 Teledyne TestlD&I 89 1 LIF-100 bb-21.010.4 22.4 Chips 89-2 Teledyne bb 20.911.0 20.3 CaSO :Dy 4
Canis All-17
Table A 2. (continued) mR Teledyne Avera ge.t2 c' lab Result Known (All Code TLD Type Measurement A2ca Valuec Participants)
Teledyne Testingi 90 ik Teledyne lab 20.611.4 19.6 Ca50 4 4
Cards 90-11 Teledyne lab 100.814.3 100.0 CaSO Dy 4
Canis 91 im Teledyne lab 33.412.0 32.0 CaSO Dy 55.214.7 58.8 4
Cards 87.816.2 85.5 a Lab result given is the mean i2 standard deviations of three determinations.
b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by tl Health and Safety laboratory (HASL), New York, New York, and the School of Public Health of t}'
University of Texas, Houston, Texas.
c Value determined by sponsor of the intercomparison using continuously operated pressurized ic
- chamber, d Mean 12 standard deviations of results obtained by all laboratories participating in the program.
e Third International Intercompadson of Environmental Dosimeters conducted in summer of 19771:
Oak Ridge National laboratory and the School of Public Health of the Unircrsity of Texas, Housto Texas.
I Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 19791:
the School of Public Health of the University of Texas Houston, Texas.
5 Fifth International Intercomparison of Environmental Dosimeters conducted in fall of 1980 at Idal-Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texn ar Environmental Measurements l2boratory, New York, New York, US. Department of Energy.
h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring ar summer of 1984 at I.as Vegas, Nevada, and sponsored by the U.S. Department of Energy, The U.;
Nuclear Regulator */ Comrnission, and the US. Environmental Protection Agency.
I Elgiith Internat;onal Intercomparison cf Environmental Dosimeters conducted in the fall and winte: )
1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.
} Chips were submitted in Sepiember 1989 and cards were submitted in Isotopes, Inc., Westwood, NJ for irradiation.
k Cards were irradiated by Teledyne Isotopes, Inc., Westwood, NJ on June 19,1990.
1 Cards were irradiated by Dosimetry Ass <>ciates, Inc., Northville, MI on Octcber 30,1993.
m Irradiated cards were provided by Teledyne Isotopes, INC., Westwood, NJ. Irradiated on October 8,1991;
, AII-18
Table A 3. In house spiked sarnples.
Concentration in pCl/L Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=1 Activity 1s,n=13 QC MI 16 M11k Feb 1988 St 89 31.814.7 31,716.0 8.7 Sr 90 25.512.7 27.813.5 5.2 1131 26.410.5 23.2 5.0 10.4 C3-134 23.812.3 24.216.0 8.7 C3137 26.510.8 25.116.0 8.7 QC MI 17 Milk Feb 1988 l131 10.611.2 14.311.6 10.4 QC W 35 Water Feb 1988 l131 9.711.1 11.611.1 10.4 QC-W 36
. Wa ter Mar 1988 1131 10.511.3 11.611.0 10.4 QC W 37 Waier Mar 1988 Sr 89 17.112.0 19.818.0 8.7 St 90 18.710.9 17.315.0 5.2 QC-MI 18 Milk Mar 1988 I131 33.212.3 26.715.0 10.4 Cs-134 31.3i2.1 30.215.0 8.7 Cs 137 29.911.4 26.215.0 8.7 QC-W 38 Water
- Apr 1988 1131 17.111.1 14.215.0 10,4 QC W 39 Water Apr 1988 H3 4439131 41761500 724 QC W-40 Water Apr 1988 Co-60 23.710.5 26.114.0 8.7 Cs-134 25.4i2.6 29.214.5 8.7 C3137 26.612.3 26.214.0 8.7 QC-W-41 Water Jun 1988 Gr. alpha 12.310.4 13.115.0 8.7 Gr. beta 22.611.0 20.115.0 8.7 QC-MI 19 Milk Jul 1988 89 15.111.6 16.415.0 8.7 r
Sr-90 18.0 0.6 18.315.0 5.2 I131 88.414.9 86.618.0 10.4 Cs-137 22.710.8 20.816.0 8.7 QC-W-42
- Wa ter Sep 1988 Sr 89 48.513.3 50.818.0 8.7 Sr-90 10.911.0 11.413.5 5.2 OC-W-43 Water Oct 1988 Co60 20.913.2 21.413.5 8.7 Cs-134 38.711.6 38.016.0 8.7 Cs-137 19.012.4 21.013.5 8.7
- QC-W-44 Water Oct 1988 I-131 22.210.6 23.313.5 10.4 AII-19
Table A 3. In-house spiked sarnples(continued)
Cencentratiqn in tsCi/L Iab Sample Date TBil Expected Code Type Collected Analysis Result Known Precision n=1 Activity 13, n=l a QC-W-45 Water Oct 1988 H-3 4109143 41531500 724 QC MI-20 Milk Oct 1988 1-131 59.810.9 60 619.0 10 4 C3-134 49.611.8 48.617.5 8.7 Cs-137 25.814.6 24.714.0 8.7 QC W-16 Water Dec 1988 Cr alpha 11.512.3 15.215.0 8.7 Cr. beta 26.512.0 25 715.0 8.7 QC M1-21 Milk Jan 1989 Sr-89 25.5110.3 34 0110.0 8.7 Sr 90 28.313.2 27.1 3.0 5.2 1131 540113 550120 10.4 Cs-134 24.512.6 22.615.5 8.7 Cs-137 24.010.6 20.515.0 8.7 QC W-47 Water Mar 1989 St-89 15.213.8 16.115.0 8.7 Sr-90 16.411.7 16.9 3.0 5.2 QC-MI 22 M11k Apr 1989 l131 36.311.1 37.215.0 10.4 Cs-134 20.812.8 20.718.0 8.7 Cs-137 22.212.4 20.418.0 8.7 QC W-48 Water Apr 1989 Co-60 23.512.0 25.118.0 8.7 Cs-134 24.211.1 25.918.0 8.7 Cs-137 23.611.2 23.018.0 8.7 QC-W-49 Water Apr 1989 I131 37.2i3.7 37.215.0 10.4 QC-W-50 Water Apr 1989 H-3 3011159 30891500 724 QC-W-51 Water Jun 1989 Gr. alpha 13.011.8 15.015.0 8.7 Gr. beta 26.0 1.2 25.518.0 8.7 QC MI 23 Mlik Jul1989 St-89 19.416.5 22.0110.0 8.7 Sr 90 27.613.5 28.613.0 5.2 1-131 46.813.2 43.415.0 10.4 Cs-134 27.411.8 28.316.0 8.7 Cs-137 24.111.8 20.816.0 8.7 QC-MI-24 M11k Aug 1989 Sr-39 25.412.7 27.2110.0 8.7 Sr-90 46.011.1 47.819.6 8.3 l
QC W-52 Water Sep 1989 l-131 9.610.3 9.711.9 10.4 1
1 All-20
Table A 3. In house spiked samples (continued)
Concentration in rC1/L Lab Sample Date TIML
~
F.spected Code Type Collected Analysis Result Known Precision
"*I Activity 15, n= 3 a QC W 53 Water Sep 1989 1131 19.010.2 20.914 2 10.4 QC W 54 Water Sep 1989 St 89 25 814 6 24.714.0 8.7 Sr 90 26.515.3 29.715.0 5.2 QC MI 25 Milk Oct 1989 I-131 70.013.3 73.5 20.0 10.4 Cs 134 22.112.6 22.618.0 8.7 Cs-137 29.411.5 27.518.0 8.7 QC-W 55 Water Oct 1989 l131 33.311.3 35.3110.0 10.4 QC W 56 Water Oct 1989 Co-60 15.210.9 17.415.0 0.7 Cs 134 22.114.4 18.913.0 8.7 Cs-137 27.211.2 22.933.0 8.7 QC W 57 Water Oct 1989 H3 3334122 33791500 724 QC W 58 Water Nov 1989 St 89 10.911.4d 11.111.0d 8.7 Sr-90 10.411.0d t o,31),od 5.2 QC W 59 Water Nov 1989 Sr 89 101.016 Cd 104.1110.5d 17.5 Sr 90 98.013.0d 95.0110.0d 17.0 QC W-60 Water Dec 1989 Gr. alpha 10.811.1 10.614.0 8.7 Cr, beta 11.610.5 11.414.0 8.7 QC MI 26 Milk Jan 1990 CF134 19.311.0 20.818.0 8.7 C3-137 25.211.2 22.818.0 8.7 QC MI 27 Milk Feb 1990 Sr 90 18.011.6 18.815.0 5.2 QC hD 28 Milk Mar 1990 I131 63.812.2 62.616.0 6.3 QC hu-61 Water Apr 1990 Sr-89 17.92.5.5 23.118.7 8.7
. St 90 19.412.5 23.515.2 5.2
_ QC hu 29 M11k Apr1990 1131 90.719.2 82.518.5 10.4
~
Cs-134 18.311.0 19.715.0 8.7 Ce137 20.311.0 18.2t3.0 8.7 QC-W-62 Water Apr 1990 Co-60 8.710.4 9.415.0 8.7 Cs-134 20.010.2 19.715.0 8.7 Cs 137 28.711.4 22.715 0 8.7 All-21
Table A 3. In house spiked samples (continued)
Concentration in to/L lab Sample
!>te TIML Expected Ccde Type Collected Analysis Result Known Precision
""I Activity 1s,n=la QC W43 W ater Apr 1990 1131 63.518.0 66.016.7 6.6 QC W.44 Water Apr 1990 H3 19411130 1826.01350.0 724 QC W45 Water Jun 1990 Ra 226 6.410.2 6.911.0 1.0 QC W-66 Water Jun 1990 U
6.210.2 6.016.0 6.0 QC hu 30 M11k Jul 1990 Sr-89 12.810.4 18.4110.0 8.7 Sr 90 18.211.4 18.716.0 5.2 Cs 134 46.011.3 49.0 5.0 8.7 Cs-137 27.611.3 25.315.0 8.7 QC W-68 Water Jun 1990 Cr. alpha 9.810.3 10.616.0 8.7 Gr. beta 11.4 0.6 11.317.0 8.7 QC hu 31 Mlik Aug 1990 1-131 68.811.6 61.4112.3 10.4 QC W-69 Water Sep 1990 Sr 89 17.711.6 19.2110.0 8.7 Sr-90 13.911.6 17 4110.0 5.2 QC AU-32 Milk Oct 1990 1-131 34.810.2 32.416.5 8.7 Cs 134 25.811.2
- 273 110.0 8.7 Cs-137 25312.0 22.4110.0 8.7 QC W 70 Water Oct 1990 H3 2355159 22761455 605 QC W 71 Water Oct 1990 1-131 55.9i0.9 51.8110.4 10.4 QC-W 73 Water Oct 1990 Co-60 18312.7 16.815.0 8.7 Cs 134 283123 27.0t5.0 8.7 Cs-137 22.7tl.3 22.415.0 8.7 QC W-74 Water Dec 1990 Cr. alpha 21.411.0 26.116.5 11 3 Gr. beta 25.911.0 22.315.6 9.7 QC hu 33 Milk Jan 1991
' Sr-89 20.713.3 21.613.0 5.0 Sr 90 19.0il.4 23.013.0 3.0 Cs 134 22.211.7 19.615.0 5.0 Cs-137 26.1il.6 22.315.0 5.0 QC-hE-34 Milk Feb 1991 1-131 40.7tl.8 40.116.0 6.0 QC W 75 Water Mar 1991 Sr-89 18.811.5 23.315.0 5.0 Sr-90 16.010.8 17.213.0 3.0 i
AII-22
Table A 3. In house spiked samples (continued)
{
Concentration in rCi/L lab Sample Date TIML Expected Code Type CouectM Analysis Result Known Precision n=1 Activity is,n=la QC W 76 Water Apr 1991 1-131 56.511.7 59.015.9 5.9 QC W 77 Water Apr 1991 Co-(0 16.412.2 15115.0 50 Cs-1M 23 812.5 22.615.0 5.0 Cs 137 25.012.4 21.1 5.0 5.0 QC W 78 Water Apr 1991 H3 40271188 40801408 408 QC hU-35 Milk Apr 1991 1131 48.010.8 49.216.0 60 C51M 19.212.0 22.615.0 50 Cs-137 22.812.2 22.115.0 5.0 QC W 79 Water Jun 1991 Cr. alpha 7.410.7 7.815.0 5.0 Cr. beta 11.010.7 11.0 5.0 5.0 QC M136 Milk Jul 1991 Sr 89 28.112.1 34.0110.0 10.0 Sr-90 11.6tJ.7 11.5 3.0 3.0 1131 14.411.9 18.315.0 5.0 Cs 137 34.313.0 35.!i5.0 50 QC W-80 Water Oct 1991 Sr 89 27.416.9 24 A15.0 50 Sr 90 11.711.4 14.115.0 5.0 QC W 81 Water Oct 1991 1 131 19.1t0.7 20.614.2 4.2 QC W 82 Water Oct 1991 Co40 22.612.7 22.115.0 5.0 Cs-134 15.511.8 17.6. 5.0 5.0 Cs-137 17.512.1 17.615.0 5.0 QC W-83 Water Oct 1991 H3 46391137 43821438 4M QC MI-37 M11k Oct 1991 1 131 23.613.2 25.815.0 5.0 Cs-134 22.712.8 22.115.0 5.0 C3-137 38.313.0 35.115.0 5.0 QC-W-84 Wa te.
Dec 1991
' Gr. alpha 6.210.6 7.815.0 5.0 Cr. beta 11.010.7 11.015.0 5.0 a n=3 unless noted otherwise.
b n=2 unless noted otherwise.
c n=1 unless noted otherwise, d Concentration in pCi/ml.
I i
All-23
Table A 4 In houw '%nk" samples.
Concentration (t{t/ u Acceptance 13 Sample Date Results Cnteria Code Type
(
Iected Analysis (4.66 c)
(4 66 c)
SPS-5386 Milk Jan 1988 1131
< 0.1
<1 SPW 5448
" Dead" Water Jan 1988 H3
<177
<300 SPS-5615 Milk Mar 1968 Cs 134
< 2. 4
<10 C3-137
< 2. 5 (10 1131
<0.3
<1 Sr 89
<0. 4 c5 St-90 2.410.5 a
<3 SPS 5650 D.I. Water Mar 1988 Th 228
< 0. 3
<1 Th 230
<0.04
<1 Th 232
<0.05
<1 U 234 (0.03
<1 U 235
<0.03
<1 U 238
<0.03
<1 Am 241
<0.06
<1 Cm 241
<0.01
<1 Pu-238 (0.08
<1 Pu-240
<0.02
<1 STS4090 Milk Jul 1988 Sr-89
< 0. 5
<1 Sr 90 1.810.5
<1 1 131
<0. 4
<1 Cs-137
< 0. 4
<10 SPW 6209 Water Jul 1988 Fe 55
< 0. 8
<1 SPW-6292 Water Sep 1988 Sr-89
<0.7
<1 Sr-90
<0.7
<1 SPS-6477 Milk Oct 1988 1131
<0.2
<1 C3-134
< 6.1
<10 Cs-137
<5.9
<10 SPW-6478 Water Oct 1980 1131
<0.2
<1 SPW-6479 Water Oct 1988 Co-60
<5.7
<10 C3-134
<3.7
<10 Cs-137
<4.3
<10 SPW-6480 Water Oct 1988 H-3
<170
<300 All-24
i Table A 4. In hoase " blank" samples (continued) j 1
Concentration (pCl/l.)
l Acceptance i
lab,
Sample Date Results Criteria Code Type Collected Analysis (4.66 o)
(4.66 o) t i
SPW 6625 -
Water Dec 1988 Gr. alpha -
<0.7
<1 Cr. beta
< 1.9
<4 j
SPS-6723 Milk Jan 1989 Sr 89
<0. 6
<5 i
St 90 1.910.3a
<j
[
1131
<0.2
<1 Cs 134
<4.3
<10 Cs-137
<4.4
<10 SPW 6877 Water Mar 1989 Sr 89
<0.4
<5 St 90
<0.6
<1 I
- SPS4963 -
Milk Apr 1989 l131
<0.3
<1 Cs-134
<5.9 (10 Cs-137
<6.2
<10 SPW 7561.
Water Apr 1989 H3
<)50
<300
..SPW 7207:
Water Jun 1989 Ra 226
<0.2
<1 Ra 228
<0.6
<1 SPS 7308
' Milk' Jun 1989 Sr-89
<0.6
<5 i
Sr 90 2.110.5a
<3 1131
<0.3
<1 Cs 134
< 6.4
<10 Cs 137 -
<7.2
<10
~
SPW-7588 Water.
Jun 1989 Gr. alpha
<0.2
<1
~ Gr. beta '
<1.0
<4
~ SPS 7322 Milk Aug 1989.
Sr 89
<1.4
<5 Sr-90 4.811.0a
<1 1131 -
<0.2
<1 Cs-134
< 6.9
<10 Cs-137
<8.2
<10
' SPW 7559 -
-. Water Sep 1989 Sr 89
' <2.0
<5 i
<0.7
<1 SPW 7560 Water Oct 1989 l131
<0.1
<1
^ SPW-7562.
- Water Oct 1989 H3
<140
<300
-AII-25 se w e k -er
, -,,.e+---ee,-,,re,4-w
.-m,,.
--y-
,w--,-
-y,wv,.-,,-,.,.,
w,wy-v-,-.-w.---,----,-,,4,-i
,,,,w,.9 y
, y n,q
.r-wm a--- -, = -, -. *., y w w.-
Table A 4. in house " blank" samples (continued)
Concentration (r'Ci/t)
Acceptance Lab Sa,mple Date Results Cnteria Code Type Collected Analysis (4.66 c)
(4.66 o)
SPS 7605 Milk Nov 1989 l-131
< 0. 2
<1 Cs-1M
< 8. 6
<10 Cs 137
<10
<10 SPW 7971 Water Dec 1989 Cr. alpha
< 0. 4
<1 Gr. beta
<0.8
<4 SPW 8039 Water Jan 1990 Ra 226
< 0.2
<1 SPS-8040 Milk Jan 1990 Sr 89
<0. 8
<5 Sr 90
< 1.0
<1 SPS-8208 Milk Jan 1990 Sr 89
<0. 8
<5 Sr 90 1.610.5a
<g Cs-134
<3. 6
<10 Cs-137
<4.7
<10 SPS-8312 Milk Feb 1990 Sr-89
<0.3
<5 Sr 90 1.210.3a
<j SPW 8312A Water Feb 1990 Sr 89
<0.6
<5 Sr 90
<0.7
<5 SPS-8314 Milk Mar 1990 1 131
<0.3
<1 SPS-8510 Milk May 1990 1-131
<0.2
<1 C31M
<4.6
<10 Cs-137
<4.8
<10 SPW 8511 A Water May 1990 H3
<200
<300 SPS-8600 Milk Jul 1990 Sr 89
<0. 8
<5 Sr 90 1.7i0.6a
<3 1131
<0.3
<1 Cs 134
<5.0
<10 Cs-137
< 7,0
<10 SPM-8877 Milk Aug 1990 I131
<0.2
<1 SPW 8925 Water Aug 1990 H3
<200
<300 AlI-26
Table A-4. In house " blank" samples (continued)
Concentration (rCi/D Acceptance 14 -
Sample Date Results Criteria Code Type Collected Analysis (4.66 c)
(4.66 c)
SPW 8926 Water Aug 1990 Cr. alpha
< 0.3
<1 Cr. beta
<0.7
<4 SPW-8927 Water Aug 1990 U 234
<0.01
<1 U-235
<0.02
<1 U 238
<0.01
<1 SPW-8928 Water Aug 1990 Mn 54
<4.0
<5 Co 58
< 4.1
<5 Co 60
< 2.4
<5 Cs-134
<3.3
<5-Cs-137
<3.7
<5 SPW-8929 Water Aug 1990 Sr 89
<1.4
<5 Sr 90
< 0.6
<1 SPW 69 Water Sep 1990 Sr 89
< 1.8
<5 Sr 90
<0.8
<1 SPW-106 Water Oct 1990 H-3
<180
<300 I131
<0.3
<1 SPM 107 Milk Oct 1990 1131
<0.4
<1 Cs-134
<3.3
<5 Cs 137
<4.3
<5 SPW 370 Water Oct 199t-Mn 54
< 1.7
<5 Co.58
<2. 6
<5 Co-60
<1.6
<5 Cs-134
< 1.7
<5 Cs-137
< 1.8
<5
. SPW 372 Water Dec 1990 Gr. alpha
<0.3
<1 Gr. beta
<0.8
<4 SPS-406 Milk Jan 1991' Sr89
<0.4
<5 Sr 90 1.810.48
<1 Cs-134
<3.7
<5 Cs-137
<5.2
<5 SPS-421 Milk Feb l991 I131
<0.3
<1 SPW 451' Water Feb 1991 Ra 226
<0.1
<1 Ra-228
<0.9
<1 AII.27
Table A-4. In-house " blank" samples (continued)
Concentration (rCi/ U Acceptance lab Sample Date Results Critena Ccde Type Collected Analysis (4.66 o)
(4 M a)
SPW 514 Water Mar 1991 St 89
<1.1
<5 Sr-90
< 0.9 c1 SPW 586 Water Apr 1991 1 131
<0.2
<1 Co-60
< 2. 5
<5 C5-134
< 2. 4
<5 Cs 137
< 2. 2
<5 SPS-587 Milk Apr 1991 1131
< 0. 2
<1 CS-134
< 1.7 (5
< 1. 9 c.5 SPW-837 Water Jun 1991 Cr. alpha
< 0. 6
<1 Gr. beta
<1.1
<4 SPM 053 Milk Jul1991 Sr 89
< 0.7
<5 Sr-90 0 410.3a
<1 1-131
<0.2
<1 i
< 4.9
<5 SPM-1236 Milk Oct 1991 1-131
<0. 2
<1 Cs-134
<3.7
<5 CS-137
<4.6 (5
SPW-1254 Water Oct 1991 Sr-89
<2. 8
<5 Sr-90
<0.7
<1 SPW 1256 Water Oct 1991 1-131
<0. 4
<1 Co60
<3.6
<5 Cs-134
<4.0
<5 Cs-137
<3.6 di SPW-1259 Water Oct 1991 H-3
<160
<300 SPW 1444 Water Dec 1991-Gr. alpha
<0. 4
<1 Gr. heta
<0. 8
<4 a Low level of Sr-90 concentration in milk (1 - 5 Ki/L) is not unuseal AII-28
TIML BLIND-01 Revision 0,12 2946 ATTACHMENT B ACCEPTAN?E CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR \\ neuOUS ANALYSES 3 One Standard Deviation Analysis Level for Single Determination Camma Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium.' 90 5 to 50 pCl/ liter or Lg S pCi/ liter o
>50 pCl/ liter or kg 10% of known value Strontium 90b 2 to 30 pCi/ liter or kg 3.0 pCi/ liter -
>30 pCl/ liter or kg 10% of known value Pottssium
>0.1 g/ liter or kg 5% of known value Cross alpha
<20 pC1/ Uter 5 pCi/ liter
>20 pCi/ liter 25% of known value Cross beta
<100 pCi/ liter 5 pCi/ liter
>100 pCi/ liter 5% of knowm value
. Tritium
<4,000 pC1/ liter is = (pCi/ liter) =
169.85 x anown).0933
>4,000 pCi/ liter 10% of known value Radium 226,.228
<0.1 pCl/ liter 15% of knowm value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value
. Iodine 131,
<55 pCi/ liter 6 pCi/ liter Iodine-129b
>55 pCi/ liter 10% of known value Uranium 238,
<35 pCi/ liter 6 pCi/ liter b
Nickel-64,
>35 pC1/ liter 15% of known value Technetium.99b Iron 55b 50 to 100 pCl/ liter 10 pCi/ liter
>100 pCi/ liter 10% of known value
.a From EPA publication, " Environmental Radioactivity Laboratory Interenmparison Studies Program, Fiscal Year,1981-1982, EPA-600/4-814K)4.
b TIML limit.
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ALDDINDUM IOREh'QLLA The following is an explanation of the reasons why certain samples were outside the controllimit specifi, by the Environmental Protection Agency for the Interlaboratory Comparions Program starting Janua 19M.
EPA TLML Control Result Limit Lab Code Analysis (pCi/L)a (pCi/L)a Bxplenation STF 524 K
1010.71158.5b M 23.5-1336.5b Error in transference of data. Correct da was 1105133 mg/kg. Results in the pc have been within the limits and Tik will monitor the situation in the future.
STW-532 1-131 9.012.0 6.28.8 Samp:e recounted after 12 days.
Tl average result was 8.Sil.7 pCi/L (withl EPA control limits).
The sample w.
recounted in order to check the decc Results in the past have been within tl limits and TIML will continue to monit.
the situation in the future.
STW 534 CM4 63.311.3 41.2 58.7 High level of Co-60 was oue i contamination of beaker.
Deaker w.
discarded upon discovery e
contamination and sample wass recounte Recount results were 53.213.6 and 50.912 pCi/L STM-554 Sr 90 51.012.0 54.8-65.2 The cause of low result was due to vei high fat content of milk.
It should 1 noted that 63% of all participants faih this test.
Also, the average for c participants was 54.6 pCi/L before tt Crubb and 55.8 pCi/L after the Grubb.
STW-560 Pu-239 5.811.1 3.5-4.9 The cause of high results is not know though it is suspected that the standar was not properly calibrated by suppi and is under investigation. New Pu-2, standard was obtained and will be used 9 the next test.
STW-568 Ra-228 2.611.0 2.7-4.5 The cause of low results is not know Next EPA cross check results were with the control imits. No furthcr action planned.
l All-30
ADDFNDUM TO APPENDIX A (continued)
SPA TIML Comrol Result Limit lab Code Analysis (pCi/L)a (pCi/L)a Explanation
- STM 570 Sr 89 26.0110.0 30.3-47.7 The cause of low results was falsely high Sr 90 45.714.2 49.8-60.2 recovery due to suspected incomplete calcium removal. Since EPA sample was used up, internal spike was prepared and analyzed. The results were within control limits (See table A 3, sample QC MI.24).
No further action is planned.
STW-589 Sr 90 17.311.2 17.4-22.6 Sample was reanalyzed in triplicate:
results of reanalyses were 18.81LS pCi/L No further action is planned.
STM-599 K
1300.0i69.2c 1414.7-1685.3C Sample was reanalyzed in triplicate.
Results of reanalyses were 1421.7195.3 mg/L.
The cause of low results is unknown.
STW-601 Gr. alpha 11.012.0 11.6-32.4 Sample was reanalyzed in triplicate.
Results of reanalyses were 13.411.0 pCi/L STAF 626 Gr. alpha 38.711.2 14.6 35.4' The cause of high results is the difference in geometery between standard used in the TIML lab and EPA filter.
STW 632 Ba 133 74.016.9 51.6 72.4 wmple was reanalyzed. Results of the reanalyses were 63.816.9 pCi/L within EPA limit.
STW-641 1-131 130.7116.8 88.9 127.1 The cause of high result is unknown. In-house spike sample was prepared with.
activity of I 131 68.316.8 pCi/L. Result of the analysis was 69.119.7 pCi/L a Reported in pCi/L unless otherwise noted, b Concentrations are reported in mg/kg.
c Concentrations are reported in mg/L.
Al!-31
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