ML20217Q476
| ML20217Q476 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1997 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20217Q474 | List: |
| References | |
| NUDOCS 9805080136 | |
| Download: ML20217Q476 (124) | |
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ATTACHMENT 1 1997 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL l
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9905000136 980430 PDR ADOCK 05000334 R
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BEAVER VALLEY POWER STATION UNITS 1 AND 2 I
LICENSES DPR-66 AND NPF-73 1997 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL I
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Duqu3sno Light Company 1997 Annurl Radiologicri Environm:ntal Rtport EXECUTIVE
SUMMARY
l This document is a detailed report of the 1997 Beaver Valley Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels in the vicinity of Unit 1 and Unit 2 from January 1 through December 31,1997 in air, water, shoreline sediment, milk, fish, food crops, vegetation, soil, and direct radiation measurement have been analyzed, evaluated, and summarized. The results of the REMP are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentration of radioactive 1
materials and levels of radiation are not higher than expected on the basir of the effluent measurement and modeling of the environmental exposure pathways.
l Radiation and radioactivity in the environment is monitored within a 10 mile radius of the site.
Two types of samples are taken. The first type, control samples, are collected from areas that are beyond measurable influence of Beaver Valley Power Station. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than Beaver Valley Power Station, can thus be compared to the environment surrounding the i
nuclear power station. Indicator samples are the second sampM type obtained. These samples show how much radiation is contributed to the endronment by the site. Indicator samples are taken from areas close to the station where any plant contribution will be at the ~
highest concentration. In 1997, samples were taken from over 60 sites around Beaver Valley Power Station that included the aquatic, atmospheric and terrestrial environments. More than 2300 analyses were performed on these samples. The environmental program for 1997 is
)
outlined in Table 3-1.
In 1974 and 1975, prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a
" pre-operational baseline". Current analysis results from the indicator samples are compared to j
both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations. The analytical results are summarized in Table 3-2.
A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in the Offsite Dose Calculation Manual (ODCM) when averaged over any calendar quarter. Also, when more than one of the radionuclides are detected in the sampling medium, this report shall be submitted if.
Concentration (1)
Concentration (2)
+
21.0 Limit Level (1)
Limit Level (2)
Based on the analytical results of environmental samples during 1997, the Beaver Valley Power Station reporting levels were not exceeded.
Positive results attributable to the Beaver Valley Power Station were consistent with station l
data of authorized radioactive discharges and were within limits permitted by the NRC license.
Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, and to the normal statistical fluctuation for activities near the lower limit of detection (LLD).
1i
Duquesna Light Company g
1997 Annut! Radiological Environmsntal Report 5
in 1997, the radioactivity releases from BVPS Units 1 and 2 did not exceed the effluent limits 3
identified in the Beaver Valley Power Station Operating License Technical Specification /Offsite E
Dose Calculation Manual (ODCM). Based on 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), from the operation of Beaver Valley Power Station Units 1 and 2, is less than 0.0001% of the annual background. The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) in 296 mrem per year.
Analytical results are divided into four ODCM required categories based on exposure pathways:
E Airborne, direct radiation, ingestion and waterborne. Each of these pathways is described g
below:
The airborne exposure pathway includes airborne iodine and airborne particulates. The 1997 results were very similar to previous years. There was no notable increase in natural products and no detections of fission products or other radionuclides in the airborne particulate media during the year.
The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have indicated a stable trend and -
compare well with previous years.
The ingestion exposure pathway includes milk, fish, and food product (leafy vegetable) samples. lodine-131 was not detected in any 1997 milk samples. Strontium-90, attributable to past atmospheric nuclear weapons testing, was detected at levels similar to the past five years. Naturally occurring potassium-40 was detected at average environmentallevels. No other radionuclides were ider.tified.
The fish samples taken indicated only naturally occurring potassium-40 in each of the g
I samples at average environmentallevels. Vegetation samples revealed naturally occurring E
f potassium-40 at average environmental levels.
The waterborne expc sure pathway includes drinking water, surface (river) water, and river sediment. Water samples were analyzed for H-3, gamma-emitting radionuclides and 1-131.
H-3 was identified in one of twenty samples, and this was at the controllocation upstream from the site which is considered outside the influence of the site. Gamma analysis of samples indicated no gamma-emitting radionuclides.1-131 analysis of weekly samples (156 total) indicated 93 positive results. Only eight were above the required Lower Limit of Detection (LLD) and none exceeded the reporting level. It was also noted that the surface water samples, which are upstream cf the plant and considered outside the influence of the site had similar results to the downstream drinking water samples.
I l
ill
l Duquasne Light Company 1997 Annuni Radiologicti Environmsntal Rsport Sediment samples are taken from three locations, upstream of the site, at the die arge poirit ofliquid releases and downstream of the site. Analysis of samples indicated naturally occurring radionuclides K-40, Ra-226 and Th-228 in all results.
Small amounts of Cs-137 from previous nuclear weapons tests was also detected in all samples at levels consistent with previous years. The two samples from the discharge point of the site also indicated small amounts of Co-58, Co-60, and Cs-134 which are consistent with authorized station liquid discharges.
In addition to the required samples discussed above, groundwater, precipitation, feederops, and soil samples were also taken. Results were consistent with previous years and no degrading trends were identified.
The environmental ml:pitoring program outlined in the Beaver Valley Power Station ODCM for Units 1 and 2 was followed throughout 1997. The REMP results demonstra'e the adequacy of radioactive effluent control at the Beaver Valley Power Station and that the operations of Units 1 and 2 did not adversely affect the surrounding environment.
4 IV
Duquasna Light Compnny l
l 1997 Annual Rcdiological Environmnntal Raport TABLE OF CONTENTS EXECUTIVE
SUMMARY
. ii l
SECTION 1
'NTRODUCTION A.
Scope and Objectives of the Program......
.1-1
{
B.
Description of the Beaver Valley Site......
.1-1 C.
1997 Operation.............
.1-2 f
SECTION 2 - MONITurtlNG EFFLUENTS A.
Monitoring of Liquid Effluents.....
.2-1 1.
Description of Liquid Effluents at the Beaver Valley Power Statien.
.2-1 2.
Radioactive Liquid Waste Sampling and Analysis Program.
........ 2-1 3.
Results of Liquid Effluent Discharge to the Environment...
..........2-1 B.
Monitoring of Atmospheric Effluents.
.......... 2-10 1.
Description of Atmospheric Effluent Sources..............
........ 2-10 l
2.
Atmospheric Effluent Treatment and Sampling............
. 2-13 3.
Resuits..
........ 2-14 SECTION 3 - ENVIRONMENTAL MONITORING PROGRAM A.
Environmental Radioactivity Monitoring Program...................
.3-1 f
1.
Program Description........
.3-1 2.
Summary of Results..........
.... 3-6 3.
Quality Control Program..........
.3-6 4.
Program Changes..........
... 3-6 B.
Air Monitoring..
........... 3 -2 2
{
1.
Characterization of Air and Meteorology...........
...... 3-22 2.
Air Sampling Program and Analytical Techniques..
.3-22 3.
Results and Conclusions....
. 3-24
. 3-27 C.
Monitoring of Sediments and So"s.....
1.
Characterization of Stream Sediments and Soils..
...... 3-27 2.
Sampling Program and Analytical Techniques.
..... 3-27 3.
Results and Conclusions.......
.... 3-29 D.
Monitoring of Feederops and Fooderops.
....... 3-30 1.
Characterization of Vegetation and Foodcrops......
.. 3-30 2.
Sampling Program and Analytical Techniques..
... 3-30 3.
Results and Conclusions............
...3-32
(
v
Duqu sns Light Ccmp ny 1997 Annuti Rrdiologic:1 Environmsntal R3 port TABLE OF CONTENTS (Continued)
SECTION 3 - ENVIRONMENTAL MONITORING PROGRAM (continued)
E.
Monitoring of Local Cows Milk.
.3-33 1.
Description - Milch Animal Locations.
.3-33 2.
Sampling Program and AnalyticalTechniques.
.3-33 3.
Results and Conclusions..
.3-35 F.
Environmental Radiation Monitoring.
. 3-36 1.
Description of Regional Background Radiation and Sources.
. 3-36 2.
Locations and Analytical Procedures.
... 3-36 l
3.
Results and Conclusions....
.3-37 5
G.
Monitoring of Fish.
.3-40 1.
Description.
.. 3-40 2.
Sampling Program and Analytical, Techniques.
.. 3-40 3.
Results and Conclusions..
. 3.
H.
Monitoring of Surface, Drinking, Ground Waters and Precipitation..
.. 3-42 1.
Description of Water Sources..
..... 3-4 2 2.
Sampling and Analytical Techniques.
.3-43 3.
Results and Conclusions......
.3-46 1.
Estimates of Radiation Dose to Man...
.3-48 1.
Pathways to Man - Calculational Models.
.3-48 2.
Results of Calculated Radiation Dose to Man - Liquid Releases.
.3-49 3.
Results of Calculated Radiation Dose to Man -
l Atmospheric Releases.
.3-49
}
4.
Conclusions.
..3-52 l
{
SECTION 4 - LAND USE CENSUS.
..4-1 SECTION 5 - QUALITY CONTROL PROGRAM / INTERLABORATORY COMPARISON PROGRAM A.
Quality Control Program.
.5-1 l
1.
Split Sample Program (DLC Contractor Laboratory -
DLC 2C Laboratory).
.5-1 2.
Dupacate Sample Program (DLC Contractor Laboratory -
DLC QC Laboratory).
.5-2 B.
Interlaboratory Comparison Program.,.
.5-2 1.
Contractor Lab.
..5-2 l
2.
Quality Control Lab.
.5-3 C.
Conclusions.
... 5-3 I
I I
Duqu::n3 Light Comp:ny l
l 1997 Annuti Redi: logical Environm:ntal R:: port LIST OF TABLES Table 2 Radioactive Liquid Waste Sampling and Analysis Program.
.2-7 Table 2 Results of Liquid Effluent Discharges to the Environment.
... 2-9 Table 2 Radioactive Gaseous Waste Sampling and Analysis Program.
.2-15 Table 3 Radiological Environmental Monitoring Program.
.3-2 Environmental Monitoring Program Results.
.3-7 Table 3-2 Table 3 Pre-Operational Environmental Radiological Monitoring Program Summary.
... 3-18 Table 3 Typical Detection Sensitivities for Gamma Spectroscopy Detection by High Resolution Germanium.
.3-21 Table 3 Radiation Dose to an Individual, mrem /yr -
I Liquid Releases.
.3-50 Table 3 Results of Calculated Radiation Dose to Man -
Liquid Releases..
..3-51 Table 3 Results of Calculated Radiation Dose to Man -
Atmospheric Releases..
.3-53 Table 4 Location of Nearest Residence, Garden, and Milch Animal.
.4-2 Table 5 Quality Control Data Contractor / Quality Control Laboratory Comparison Split Surface Water Samples..
.5-4 Table 5 Quality Control Data Contractor / Quality Control Laboratory Comparison Split Drinking Water Samples.
.5-5 I
Quality Control Data Contractor / Quality Control Table 5-3 Laboratory Comparison Split Milk Samples.
..5-6 Table 5 Quality Control Data Contractor / Quality Control Laboratory Comparison Split Feed, Food and Sediment Samples... 5-7 Table 5 Quality Control Data Contractor / Quality Control I
Laboratory Comparison Duplicate (Co-located) Air Particulate and Charcoal Filter Samples..
... 5-8 Table 5 Quality Control Data Contactor/ Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate Samples (Gamma) (pCi/Cu Meter).
.5-9 Table 5 Quality Control Data Contractor / Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/ day..
... 5-10 I
Table 5 Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory Comparison Spiked Water Samples (pCi/l).
. 5-11
~
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Duquasna Light Company 1997 Annual Rrdiological Environmsntal Report LIST OF TABLES (Continued)
Table 5 Interlaboratory Comparison Program independent g
Laboratory / Contractor Laboratory Comparison Spiked Milk 3
.5-13 Samples (pCi/l).
Table 5 Interlaboratory Comparison Program Contractor / Quality Control Laboratory Comparison Spiked Air Particulate / Charcoal Filters.
.5-15 Table 5 Contractor EPA Interlaboratory Comparison Program 1996..
.5-16 E
Table 5 Contractor EPA Interlaboratory Comparison Program 1997.
.5-17 E
Table 5 QC Lab - EPA Interlaboratory Comparison Program 1996.
.. 5-35 Table 5 QC Lab - EPA Interlaboratory Comparison Program 1997.
. 5-36 I
I I
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viii
Duqusans Light CompIny 1997 Annual Radiological Environmantal Rsport LIST OF FIGURES View of the Beaver Valley Power Station.....
... 1 -3 Figure 1-1 Figure 1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station...
..1-4 Figure 2 Liquid Discharge Points to Ohio River.......
........ 2-2 Figure 2 Unit 1 Water Flow Schematic....................................... 2-3 Unit 2 Water Flow Schematic...
. 2-4 Figure 2-3 Unit 1 Liquid Waste System.....
.2-5 Figure 2-4 Figure 2 Unit 2 Liquid Waste System...
..... 2-6 Figure 2 Units 1 and 2 Gaseous Radwaste System.
..... 2-11 Units 1 and 2 Gaseous Release Points.......
.... 2-12 Figure 2-7 Figure 3-1
- Air Sampling Stations......
... 3-2 3 Figure 3 Average Concentration of Gross Beta in Air Particulates.......... 3 ~
Environmental Monitoring Locations - Shoreline Figure 3-3 Sediments and Soil...
.. 3-28 Environmental Monitoring Program - Feedcrop and Figure 3-4 Foodcrop Locations...
..3-31 Figure 3 Environmental Monitoring Locations - Milk........................ 3-34 TLD Locations....
...3-38 Figure 3-6 Figure 3 Environmental Monitoring Program - Fish Sampling Locations.. 3-41 Environmental Monitoring Stations Locations - Ground, Figure 3-8 Surface Water, Drinking Water and Precipitation.
.. 3-45 Figure 4-1 Milch Animal Census..
.......4-3 Contractor - EPA Cross Check Program Trending Graphs...
..5-20 Figure 5-1 IX
Duqussna Light Company
(
1997 Annuti R diologicti Environmsntal Rsport SECTION 1 - INTRODUCTION A.
Scope and Objectives of the Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, vegetation, river sediments, fish, soil and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. The Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1997.
B.
Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land. Figure 1-1 is a view of the Beaver Valley Power Station. The site is approximately 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 within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,500.
I The site lies in a valley along the Ohio River. It extends from the river (elevation 665 feet above sea level) to a ridge along tN border south of the Beaver Valley Power Station at an elevation of 1,160 feet. Plant gmund level is approximately 735 feet above sea level.
The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series or dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. For 1997, the flow ranged from a minimum monthly average of 10700 cubic feet per second (CFS) to a maximum monthly average of 104900 CFS. The mean flow for 1997 was 40792 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.
1-1
1 Duqunsnn Light Company 1997 Annurl Rtdiological Environmental R port The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below:
Beaver Valley Unit 1 Beaver Valley Unit 2 l
Maximum Power Level 2652 - megawatts thermal 2652 - megawatts thermal Type of Power PWR PWR i
No. of Reactor Coolant Loops 3
3 No. of Steam Generators & Type 3 - Vertical 3 - Vertical Steam Used by Main Turbine Saturated Saturated The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system.
Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is given up from the primary system -
E to the secondary system in the steam generators, where steam is formed and delivered to g
the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam / water cycle.
C.
1997 Operation The Beaver Valley Powe.- Station Unit 1 operated throughout 1997 except during a refueling outage from September 28 and continuing into 1998 and unscheduled outages from March 19 to April 14, June 28 to July 31, and August 7 to August 10. Unit 2 operated throughout 1997 except for unscheduled outages from January 6 to January 15, March 19 to March 30, July 10 to July 23, and December 16 continuing into 1998.
The maximum dependable capacity factor for 1997 were as follows: Unit 1 - 56.3% and Unit 2 - 85.7%.
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1-2 l
Duquesne Light Company 1997 Annual Radiological Environmental Report Figure 1-1 View of the Beaver Valley Power Station
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Duquesna Light Company 1997 Annual Rtdiological Environmental Report
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Figure 1-2 Geographical Map and Principal Communities g
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Duqu:sna Light Company 1997 Annual Radislogical Environmental Rsport
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SECTION 2 - MONITORING EFFLUENTS
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The Beaver Valley Power Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases are controlled to ensure that limits set by Federal or State governments are not exceeded. In addition,
(
self-imposed goals have been established to further limit discharges to the environment.
A. Monitoring of Liquid Effluents
[
1.
Description of Liquid Effluents at the Beaver Valley Power Station Most of the water required for the operation of the Beaver Valley station is taken from
[
the Ohio River, and returned to the river, used for makeup to various plant systems, or discharged via a sanitary waste system. In addition, liquid effluents are discharged to the Ohio River using discharge points shown in Figure 2-1. Schematic diagrams of liquid flow paths for the Beaver Valley Power Station are shown in Figure 2-2, Figure 2-3, Figure 2-4 and Figure 2-5.
2.
Radioactive Liquid Waste Sampling and Analysis Program See Table 2-1.
3.
Results of Liquid Effluent D.scharge to the Environment
(
See Table 2-2.
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2-1
Duqussno Light Company 3
1997 Annual Radiological Environm:ntil R: port E
Figure 2-1 Liquid Discharge Points to Ohio River
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Duqussna Light Company 1997 Annual Rtdiological Environmsntal Rzport j
Table 2-1 Radioactive Liquid Waste Sampling and Analysis Program MINIMUM LOWER LIMIT OF LlQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION (LLD)
TYPE FREQUENCY FREQUENCY ANALYSIS
( Ci/mi)*
P P
Principal Gamma Emitters' SE-7 Each Batch" Each Batch" l-131 1 E-6 P
Dissolved and Entrained ases( a a m ers)
One Batch /M.n Batch Waste Release Tanks P
M H-3 1 E-5 Each Batch" Composite
- Gross Alpha 1 E-7 P
Q Sr-89, Sr-90 SE-8 Each Batch" Composite
- Fe-55 1 E-6 s
W Principal Gamma Emitters' SE Grab Sample Composite
- l-131 1 E-6 ss Ive and ntrained Grab Sample' M
1 E-5 Gases (Gamma Emitters)
B.
Continuous Releases
- 8 s
M H-3 1E-5 Grab Sample Composite
- Gross Alpha 1 E-7 s
O Sr-89, Sr-90 SE-8 Grab Sample Composite
- Fe-55 1 E-6 Atleast once per 7 days W
At least once per 31 days M
At least once per 92 days Q
P Cortpleted prior to each release 2-7
Duquasna Light Company E
1997 Annu:1 Radiological Environmsntal Raport E
Table 2-1 Notation a.
The Lower Limit of Detection (LLD).
b.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released, To be representative of the quantities and concentrations of radioactive materials in liquid c.
effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
I d.
A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
e.
A continuous release exists when the discharge of liquid wastes is from a non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. Releases from the Turbine Building drains and the Auxiliary Feedwater Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd).
f.
The principal gamma emitters for whLh the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, g
Ce-141 and Ce-144. This list does not mean that only these nuclides are to be detected 5
and reported. Other peaks which are measurable and identifiable, together with the above i
nuclides, shall also be identified and reported. Nuclides which are below the LLD for the g
analyses should be reported as "less than" the nuclide's LLD, and should not be reported B
as being present at the LLD level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLDs higher g'
than required, the reasons shall be documented in the Annual Radioactive Effluent E
l Release Report.
g.
When radioactivity is identified in the secondary system, a discharge permit should be prepared on a monthly basis to account for the radioactivity that will eventual!f be discharged to the Ohio River.
h.
Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling will be perform *.a a means of a grab sample taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during pump operation.
I l
I 2-8
Duquasna Light Company 1997 Annual Radiolcgical Environmsntal Raport Table 2-2 Results of Liquid Effluent Discharges to the Environment Effluent Type Results for 1997 Steam System Blowdown The Steam System Blowdown was recycled when practicable.
Batch Radioactive Waste Routine planned releases of liquid effluents Liquids from the Beaver Valley Power Station were released in accordance with conditions noted in Section 6.8.6a of the Technical Specifications and Appendix C of the ODCM.
No limits were exceeded. These values have been reported in the Beaver Valley Power Station Annual Radioactive Effluent Release Report for 1997.
Continuous Radioactive Waste Radioactive waste liquids were not discharged Liquids in a continuous mode during 1997.
2-9
Ouqu:sns Light Company 3
1997 Annual Radiolog' cal Environmnntal Rsport E
B.
Monitoring of Atmospheric Effluents 1.
Description of Atmospheric Effluent Sources Beaver Vallev Power Station (Units 1 and 2)
The Beaver Valley Power Station identifies radionuclides according to Section 6.8.6a of the Technical Specifications, Appendix C of the ODCM and Regulatory Guide 1.21.
Prior to waste gas decay tank batch releases and containment purge releases, an analysis of the principal gamma emitters is performed. The principal gamma emitters include noble gases, iodines, and carticulates. Figure 2-6 shows the gaseous radwaste system at Beaver Valley Power Station.
The environmental continuous gaseous release points also require specific nuclide identification. These points include.
a.
Unit 1 Release Points:
- 1) The Venti!ation Vent located on top of the Unit 1 Primary Auxiliary Building.
- 2) The Supplementary Leak Collection and Release System (SLCRS) Vent a
located on top of the Unit 1 Containment Building.
b.
Unit 2 Release Points:
- 1) The Ventilation Vent located on top of the Unit 2 Primary Auxiliary Building.
- 2) The Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Unit 2 Containment Building.
I
- 3) The Decontamination Building Vent located on top of the Unit 2 Decontamination Building.
- 4) The Waste Gas Storage Vault Vent located on top of the Unit 2 Decontamination Building.
- 5) The Condensate Polishing Building Vent located on top of the Unit 2 Condensate Polishing Building.
c.
Unit 1 and Unit 2 shared Release Point:
- 1) The Process Vent located on top of the Unit 1 Cooling Tower.
These points are continuously monitored for particulates and gases. Grab samples are obtained on a weekly basis and are analyzed for noble gas gamma-emitting isotopes. Grab samples are obtained on a monthly basis and analyzed for tritium.
Weekly continuous samples are obtained on filter paper and charcoal cartridges. The filter papers are analyzed for particulate gamma-emitting radionuclides and gross E
alpha. Composites of the filter papers are analyzed monthly for Sr-89 and Sr-90. The E
charcoal cartridges are analyzed for I-121,1-133 and 1-135.
Figure 2-7 shows these gaseous release points.
2-10
Duquasna Light Comp 2ny 1997 Annual Rcdiological Environmsntal Raport Figure 2-6 Units 1 and 2 Gaseous Radwaste System PROM UNIT 2 CAS.EQUS WASTE SYSTEM 70 ATMOSPME.E (siMLA TO UNrf 1) ivf l
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Duque:ns Light Company g
1997 Annut! Radiologic 1 Environmental Report E
Figure 2-7 Units 1 and 2 Gaseous Release Points Ohio River Cl I
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Release Point & Description Elevation
- 1. Unit 1: Ventilation Vent 79 feet. 24 seters
- 2. Unit 1: Contatraent / sLCAS Vent 154 feet = 47 meters g
- 3. Unit 1121 Process vent 475 feet = 145 seters i
- 4. Unit 2: Ventilation Vent 85 feet = 26 enters
- 5. Unit 2: Contalrnent / sLCAs vent 154 feet = 47 meters 3 %j
- 6. Unit 2: Condensate Polishing Building Vent 80 feet = 24 enters 8
- 7. Unit 2: Uaste cas Storage vault Vent 80 feet. 24 meters
[I V
- 8. Unit 2 Decontamiration Sullding Vent 80 feet = 24 meters
' Ur. ' t 2: Turbine Building Vent 109 feet = 33 meters j
Note: The telease Point shom for the Unit 2 Turbine BJIlding Vent Is E
a representative exhaust point for the 10 roof exhaust outlets.
I I
2.,
Duquesns Light Comprny I
1997 Annurl Radiological Environmsntsi Rsport 2.
Atmospheric Effluent Treatment and Sampling i
l Gaseous Waste Disposal System (Units 1 and 2)
Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor. Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and radioisotopes consisting of noble gases, particulates and radiciodines are also present in this system.
The overhead gas compressor directs the radioactive gas stream to a gas surge tank.
I Gas is periodically transferred from the Unit 1 or Unit 2 surge tank to one of the three (3) storage tanks at Unit 1 or one of the seven (7) storage tanks at Unit 2. The tanks are then sampled and authorization obtained for discharge in accordance with I
the ODCM. The discharge of the waste gases from the decay tanks (2 scfm)is then diluted with about 1000 scfm of air. The gases are then combined with nitrogen purge from the oxygen analyzers, calibration gas from the oxygen analyzers, the main I
condenser air ejector exhaust, the containment vacuum system exhaust, aerated vents of the sweep gas system, discharge of the overhead gas compressor and the purge from the applicable multi sample point radiation monitor. The mixture is then filtered I
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 I
the Unit 1 cooling tower. The radioactivity levels of the stream are continuously monitored in accordance with the ODCM.
Should the radioactivity release concentration of the stream exceed the allowable I
setpoint, a signal from the radiation monitor will stop the discharge from the applicable Unit 1 or Unit 2 tanks.
Reactor Containment Purae (Units 1 and 2)
During a shutdown period after the Unit 1 or Unit 2 containment has been sampled and authorization for discharge determined in accordance with the ODCM, purging may commence through the Ventilation Vent located on top of the Auxiliary Building or the Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Reactor Containment Building or the Process Vent located on top of the Cooling Tower.
I
-l l
l
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l L
z 2-13
Duqussn3 Light Company 3
1997 Annual Radiological Environmsnt:1 R:: port E
Buildino Ventilation Systems (Units 1 and 2)
Most areas in the Unit 1 Auxiliary Building are monitored for radioactivity by individual radiation monitors which aid in identifying any sources of contaminated air. Tha normal exhaust is through the Ventilation Vent effluent pathway. This pathway is monitored continuously by several redundant channels of the Radiation Monitoring System (RMS)in accordance with the ODCM. Particulate and iodine samples are g
obtained continuously while grab noble gas samples are obtained weekly in g
accordance with the ODCM. Upon a upper activity alarm, automatic dampers divert the system's exhaust air stream hrough one of the main filter banks in the E l Supplementary Leak Collection and Release System (SLCRS) which exhausts through l'
the SLCRS Vent effluent pathway.
Areas in the Unit 2 Auxiliary Building (subject to radioactive contamination) are l
monitored for radioactivity prior to entering the filter banks in the Supplementary Leak Collection and Release System (SLCRS). This system is sampled continuously for particulates and iodines and is sampled weekly for noble gases, in accordance with the ODCM. This system is monitored continuously by the Digital Radiation Monitoring System (DRMS) in accordance with the ODCM.
Each Unit 1 and Unit 2 SLCRS filter bank consists of roughing filters, charcoal filters,
)
I and pleated glass fiber type HEPA filters. The roughing filters remove large particulates to prevent excessive pressure drop due to buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the HEPA filters remove particulates and charcoal fines.
These and other release points for Unit 1 and Unit 2 of the Beaver Valley Power Station are shown in Figure 2-7. Some of these release points discharge small amounts of radioisotopes consisting of noble gases, particulates and radiciodines.
See Table 2-3 for the Radioactive Gaseous Waste Sampling and Analysis Program.
This program is an excerpt of the requirements contained in the ODCM.
3.
Results Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 6.8.6a of the Technical Specifications and Appendix C of the ODCM. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Annual Radioactive Effluent Release Report for 1997.
Duqusens Light Company 1997 Annu11 Radiological Environmsntil Rspurt J
1 Table 2-3 Radioactive Gaseous Waste Sampling and Analysis Program MINIMUM LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION (LLD)
TYPE FREQUENCY FREQUENCY ANALYSIS
( Cl/cc)
P P
Principal Gamma Emitters' 1 x 10"
- 1. Waste Gas Each Tank Storage Tank Grab Sample Each Tank H-3 1 x 104 P
P l
Principal Gamma Emitters
- 1 x 10"
- 2. Containment Purge Each Purge
- Grab Sample Each Perge*
H3 1 x 10*
M*" Grab M
Principa! Gamma Emitters' 1 x 10" b
- 3. Ventilation Systems" Sample H-3 1 x 104
- a. Procest Vent yf i.131 1 x 10'i2
- b. Aux. Bldg. Vents Charcoal Sample 1-133 1 x 10*
- c. Containment V/
Principal Gamma Emitters 1 x 10'"
Vents Particulate Sample (1-131 Others)
- d. Decon. Bldg.
Continuous' M
Composite Gross alpha 1 x 10'"
Vent
- e. Waste Gas Particulate Sample Vault Vent Q
- f. Cond. Polish.
Composite Sr-89, Sr-90 1 x 10'"
Bldg. Vent Particulate Sample Noble Gases Gross Beta 4
Noble Gas Monitor 1 x 10 and Gamma W
At least once per 7 days At least once per 31 days M
O At least once per 92 days Completed prior to each release P
i 1
t 2-15
Duqu3sns Light Comp:ny 1997 Annual Rrdiologicci Environm nt:1 Rsport Table 2-3 Notation a.
The Lower Limit of Detection (LLD).
b.
Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a B
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. This requirement does not apply if (1) analysis shows that the DOSE g
EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
c.
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from the appropriate ventilation release path) when the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler. Sampling shall also be performed at least nnce per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and analyses shall be completed within -
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. 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 LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
Tritium grab samples shall be taken at least once per 7 days from the ventilation e.
exhaust from the spent ft.el pool area, whenever spent fuel is in the spent fuel pool.
f.
The average ratio of the sample flow rate to the samp!ed stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Appendix C CONTROLS 3.11.2.1,3.11.2.2 and 3.11.2.3.
1 g.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, l
Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not l
mean that only these nuclides are to be detected and reported. Other peaks which l
are measurable and identifiable, together with the above nuclides, shall also be I
identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLDs higher than required, the reasons shall be l
documented in the Annual Radioactive Effluent Release Report.
h.
Only when release path is in use.
2-16
Duquasnm Light Company 1997 Annu11 Radiol:gical Environmsntal Raport SECTION 3 - ENVIRONMENTAL MONITORING PROGRAM A.
Environmental Radioactivity Monitoring Program 1.
Program Description The program consists of monitoring water, air, soil, river bottoms, vegetation and foodcrops, cows milk, ambient radiation levels in areas surrounding the site, and aquatic life as summari7eJ 5 Table 3-1. Further description of each portion of the program (Sampling Methe
'timple Analysis, Discussion and Results) are included l
in Sections 3-B through 3-1 i..ns report.
3-B - Air Monitoring Sediments and Soils Monitoring 3-C i
i 3-D - Vegetation and Foodcrops 3-E Cows Milk 3-F -
Environmental Radiation Monitoring 3-G -
Fish 3-H -
Surface, Drinking, Well Waters and Precipitation 3-1 Estimates of Radiation Dose to Man 1
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Duqu:snn Light Company l
1997 Annual Radiological Envircnmsntal Rapsrt Table 3 Notations Radiological Environmental Monitoring Program (Continued)
Notes:
(a)
Control sample station: These are locations which are presumed to be outside the l
influence of plant effluents.
(b)
Typical detection sensitivities for gamma spectrometry are shown in Table 3-4.
(c)
Particulate samples are not counted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change. Perform gamma isotopic analysis on each 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 sample from Searight's Dairy is analyzed for 1-131 only.
(g)
Milk samples are collected bi-weekly when animals are in pasture and monthly at other times.
(h)
The fish samples will contain whatever species are available. If the available sample size permits, then the sample will be separated according to species and compositing will provide one sample of each species. If the available size is too small to make separation by species practical, then edible parts of all fish in the sample will be mixed to give one sample.
(i)
Composite samples are obtained by collecting an aliquot 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. A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5.
(j)
Two (2) TLDs are collected quarterly from each monitoring location.
(k)
Exact location may vary due to availability of food products.
Additional Notes:
l Sample points correspond to site numbers shown on maps.
1 o
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.
3-5
Duqucsne Light Comp:ny 1997 Annual Radiological Environmental R: port 2.
Summary of Results All results of this monitoring program are summarized in Table 3-2. This table is prepared in the format specified by NRC Regulatory Guide 4.8 and in accordance with a
Beaver Valley Power Station Opera License, (Appendix A, Technical l
Specifications /ODCM). Summaries o results of analysis of each media are discussed in Sections 3-8 through 3-H and an assessment of radiation doses are given in Section 3-1. Table 3-3 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 ranges of values are generally in good agreement for both periods of time.
Activity detected w'as attributed to naturally occurring radionuclides, BVPS effluents, medical procedures, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the lower limit of detection (LLD). Table 3-4 shows typical detection sensitivities for gamma spectroscopy detection by high resolution germanium detectors.
The conclusion from all program data is that the operation of the Beaver Valley Power Station has resulted in insignificant changes to the environment.
3.
Quality Control Program The Quality Control Program implemented by Duquesne Light Company to assure reliable performance by the DLC contractor and the supporting QC data are presented and discussed in Section 5 of this report.
I 4.
Program Changes The following changes were implemented in the 1997 sampling program.
Surface Water. deleted quarterly Sr 89/90 analysis.
I f
Groundwater: Meyers' Farm Site #13 deleted (site was abandoned).
I Drinking Water: deleted quarterly Sr 89/90 analysis.
l I
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Duqu:sns Light Comp:ny 1997 Annual Radiological Envircnm:ntil R port Table 3-3 Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver. Pennsvivania Reporting Level CY 1974 - 1975 (County)
(State)
Pre-Operational Program Summary (Combined 1974 - 1975)
Medium or Pathway Analysis and Total Lower Limit of AllIndicator Locations Sampled Number of Analysis Detection (LLD)
Mean, (f) Range (Unit of Measurement)
Performed g
Sediments Gross Alpha (0) g pCi/g (dry)
Gross Beta (33) 1 18 (33/03) 5 - 30 Sr-90 (0)
U-234, 235, 238 (0)
Gamma (33) 13 (33/33) 2 - 30 K-40 1.5 13 (33/33) 2 - 30 Cs-137 0.1 0.4 (21/33) 0.1-0.6 Zr/Nb-95 0.05 0.8 (12/33) 0.2 - 3.2 Ce-144 0.3 0.5 (3/33) 0.4 - 0.7 Ru-106(b) 0.3 1.5 (3/33) 1.3 - 1.8 E
Others
< LL Foodstuff Gamma (8)
E pCi/g (dry)
K-40 1
33 (8/8) 10-53 Cs-137 0.1 0.2 (1/8)
Zr/Nb-95 0.05 02 (1/8)
Ru-106(b) 0.3 0.8 (1/8)
Others
< LLD Feedstuff Gross Beta (80) 0.05 19 (80/80) 8 - 50 l
pCi/g (dry)
Sr-89 (81) 0.025 0.2 (33/81) 0.04 - 0.93 E
Sr-90 (81) 0.005 0.4 (78/81) 0.02 - 0.81 Gamma (81) l K-40 1
19 (75/81) 5-46 Cs-137 0.1 0.5 (6/81) 0.2 - 1.6 E
Ce-144 0.3 1.5 (5/81) 0.9 - 2.6 Zr/Nb-95 0.05 0.8 (13/81) 0.2 - 1.8 Ru-106(a) 0.3 1.4 (12/81) 0.6 - 2.3 Others
< LLD Soil Gross Alpha (0) l pCi/g (dry)
Gross Beta (64) 1 22 (64/64) 14 - 32 (Template Samples)
Sr-89 (64) 0.25 0.4 (1/64) m 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 - 6.8 Ce-144 0.3 1.1 (7/64) 0.2 - 3 g
Zr/Nb-95 0.05 0.3 (13/64) 0.1 - 2 g
Ru-106(b) 0.3 1.1 (3/64) 0.5 - 2 Others
< LLD (f)
Fraction of detectable measurements at specified location.
I 3-18 z
Duqusens Light CompIny 1997 Annu:1 Radici:gic l Environm:ntal Rapsrt Table 3-3 (Continued)
Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility Beaver Vallev Power Station Docket No. 50-334 Location of Facility _ Beaver. Pennsylvania Reporting Level CY 1974 - 1975 (County)
(State)
Pre-Operational Program Summary (Combined 1974 - 1975)
Medium or Pathway Analysis and Total Lower Limit of All Indicator Locations Sampled Number of Analysis Detection (LLD)
Mean, (f) Range (Unit of Measurement)
Performed Soil Gross Alpha (0) pCi/g (dry)
Gross Beta (8) 1 21 (8/8) 16-28 (Core Samples)
Sr-89 (8) 0.25
< LLD Sr-90 (8) 0.05 0.2 (5/8) 0.08 - 0.5 Gamma (8)
K-40 1.5 13 (8/8) 7-20 Cs-137 0.1 1.2 (7/8) 0.2 - 2.4 Co-60 0.1 0.2 (1/8)
Others
< LLD Surface Water Gross Alpha (40) 0.3 0.75 (5/40) 0.6 - 1.1 pCi/l Gross Beta (120) 0.6 4.4 (120/120) 2.5-11.4 Gamma (1) 10- 60
< LLD Tritium (121) 100 300 (120/121) 180- 800 Sr-89 (0)
Sr-90 (0)
C-14 (0)
Drinking Water I-131 (0) pCi/l Gross Alpha (50) 0.3 0.6 (4/50) 0.4 - 0.8 Gross Beta (208) 0.6 3.8 (208/208) 2.3 - 6.4 Gamma (0)
Tritium (211) 100 310 (211/211) 130-1000 C-14 (0)
Sr-89 (0)
Sr-90 (0)
Ground Water Gross Alpha (19) 0.3
< LLD pCi/l Gross Beta (76) 0.6 2.9 (73/75(b))
1.3 - 8.0 Tritium (81) 100 440 (77/81)80-800 Gamma (1) 10-60
< LLD Air Particulates Gross Alpha (188) 0.001 0.003 (35/188) 0.002 - 0.004 and Gaseous Gross Beta (927) 0.006 0.07 (927/927) 0.02 - 0.32 3
pCi/m Sr-89 (0)
Sr-90 (0) l-131 (816) 0.04 0.08 (2/816) 0.07- 0.08 Gamma (197)
Zr/Nb-95 0.005 0.04 (122/197) 0 01- 0.16 Ru-106 0.010 0.04 (50/197) 0.02 - 0.09 Ce-141 0.010 0.02 (3/197) 0.01 - 0.04 Ce-144 0.010 0.02 (44/197) 0.01 - 0.04 Others
< LLD (f)
Fraction of detectable measurements at specified location.
3-19
Duqueens Light Company 1997 Annual Rcdlologicri Environmental R: port Table 3-3 (Continued)
Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility BeaverValley Power Station Docket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 (County)
(State)
Pre-Operational Program Summary (Combined 1974 - 1975)
Medium or Pathway Analy sis and Total Lower Limit of AllIndicator Locations Sampled Numberof Analysis Detection (LLD)
Mean, (f) Range (Unit of Measurement)
Performed Milk l-131 (91) 0.25 0.6 (4/91) 0.3 - 0.8 pCi/l Sr-89 (134) 5 7
(4/134) 6-11 Sr-90 (134) 1 5.3 (132/134) 1.5-12.8 Gamma (134) l Cs-137 10 13 (19/134) 11 -16 Others
< LLD E
External Radia' ion y - Monthly (599) 0.5 mR*
0.20 (599/599) 0.08 - 0.51 mR/ day y - Quarterly (195) 0.5 mR*
0.20 (195/195) 0.11 - 0.38 -
g y-Annual (48) 0.5 mR*
0.19 (48/48) 0.11 - 0.30 g
Fish Gross Beta (17) 0.01 1.9 (15/17) 1.0 - 3.2 pCi/g (wet)
Sr-90 (17) 0.005 0.14 (17/17) 0.02- 0.50 g
Gamma (17) 0.5 E
K-40 2.4 (17/17) 1.0 - 3.7 Others
< LLD LLD in units of mR - Lower end of usefulintegrated exposure detectability range for a passive radiation detector (TLD).
(a) May include Ru-106, Ru-103, Be-7.
(b) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample).
(f)
Fraction of dett.dable measurements at specified location.
I I
3-20
Duquasna Light Comprny 1997 Annual Radiol::gical Envircnment:1 Report Table 3-4 Typical Detection Sensitivities for Gamma Spectroscopy Detection by High Resolution Germanium Milk Air Sediment Nuclide Water Particulates and Soll
( C/ g e)
( C Ig wet)
(pCl/ liter)
(pCl)
(pCilg wet)
Be-7 50 20 200 0.2 0.2 K-40 80 50 400 0.4 0.4 Mn-54 5
2 20 0.02 0.02 Co-58 5
2 20 0.02 0.02 Fe-59 10 3
40 0.04 0.04 Co-60 5
2 20 0.02 0.02 Zn-65 10 5
40 0.04 0.04 Zr/Nb-95 5
3 40 0.04 0.04 Ru-103 5
2 30 0.03 0.03 ~ ~
Ru-106 50 20 200 0.2 0.2 1-131 15 4
100 0.1 0.1 Cs-134 5
2 20 0.02 0.02 Cs-137 5
2 20 0.02 0.02 Ba/La 140 10 3
200 0.2 0.2 Ce-141 10 3
100 0.1 0.1 Ce-144 40 20 200 0.2 0.2 Ra-226 80 10 100 0.1 0.1 Th-228 10 10 20 0.02 0.02 3-21
Duquesna 1.!ght Company g
1997 Annu 1 R:diological Envir:nm:ntal Rsport g
B.
Air Monitoring 1.
Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is generally from the southwest in summer and from the northwest in the winter, 2.
Air Sampling Program and Analytical Techniques a.
Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10) offsite air sampling stations. The locations of these stations are listed in Table 3-1 and shown on a map in Figure 3-1.
Samples are collected at each of these stations by continuously drawing one cubic foot per minute of atmosphere air through a glass fiber filter and through a charcoal cartridge. The former collects airborne particulates; the latter is for radiciodine sampling. Samples are collected for analysis on a weekly basis.
g The charcoalis used in the weekly analysis of airborne I-131. The filters are 3
analyzed each week for gross beta, then composited by station for quarterly analysis by gamma spectrometry. In order to reduce interference from natural E
radon and thoron radioactivities, all filters are allowed to decay for a few days after E
collection prior to counting for beta in a low background counting system.
b.
Procedures Gross Beta analysis is performed by placing the filter paper from the weekly air sample in a 2" 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 quarter and scanning this composite on a high resolution germanium gamma spectrometer.
Radiciodine (I-131) analycis is performed by a gamma scan of the charcoalin a weekly charcoal cartridge. The activity is referenced to the mid-collection time.
I l
3-22
Duqustna Light Comp:ny 1997 Annual Radiclogict! Environmsntal Rsport Figure 3-1 Air Sampling Stations lun#
~
~
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(
artington j
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Me I
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^
, is Negley is I
b t
I 10 mile r$[ius (7
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g
,B aver alls
.n.
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/
- Marion W L
80 I
Willi, sport toi New B f
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- 29BS East Roches I
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e
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ile radius]
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g y
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ow Manches.er i
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g l
tt Weirton control she. #48 Sector 10,16.3 miles, not shownl,
/
/
New Cumberland l
q e
hh4TA o im Site Distance Site No.
Distance
+
3, gy Location 3,,,,,
Location No.
(miles)
- j.,
(miles) 13 11 14 Meyers' Farm
'/
32 15 08 Mid'and. PA 27 7
6i Brunton's Dairy Farm 46 1 3
23 tndustry PA (Garage) 28 1
86 Sherman's Farm 47 14 49 East Liverpool. OH 298 3
80 Beaver County Hospital l'd 48 10 16 3 Weirton. WV 30 4
05 Snappingport, PA (S S )
V 51 5
80 Abquippa. PA 30A 4
05 S.Nppingport. PA (S S )
J
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+
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m 3-23 F
____w
Duquasn3 Light Company 3
1997 Annual R diologicri Environmsntal R port E
3.
Results and Conclusions A summary of data is presented in Table 3-2.
a.
Airborne Radioactive Particulates A total of five hundred twenty (520) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years. Figure 3-2 illustrates the weekly average concentration of gross beta in air particulates.
Weeks 41,47, and 51 indicated a weekly average that was higher than the other weeks. Even though the average for these weeks was higher, weekly averages in previous years have been as high or higher. It was noted that the control station, Weirton, WV, also had similar elevated readings during these three weeks. This station is considered to be outside the influence of plant operations and indicates that the increase for that week was from natural causes (radon). Also, all air particulate samples are required to be counted by gamma spectroscopy if any gross beta result is greater than ten times the yearly control location average (10 x 0.0162 pCi/m = 0.162 pCi/m ). For weeks 41,47 and 51, none of the
~~
8 samples exceeded 0.040 pCi/m and individua! samples were not required to be counted for gamma spectroscopy because their gross beta results were not high enough to meet the gamn.a spectroscopy counting requirement.
The weekly air particulate samples were composited to forty (40) quarterly samples which were analyzed by gamma spectrometry. Naturally occurring Be-7 was present in all samples. Naturally occurring K-40 was detected in fifteen (15) l of the forty (40) monthly samples. Results are listed in the summary Table 3-2.
B Based on the analytical results, the operation of Beaver Valley Power Station did E
not contribute any measurable increase in air particu! ate radioactivity during 1997.
g b.
Radiciodine A total of five hundred twenty (520) weekly charcoal filter samples were analyzed for 1-131. No detectable concentrations were present at any locations.
I Based on analytical results, the operation of Beaver Valley Power Station did not contribute any measurable increase in airborne radioiodine during 1997.
I I
I I
l I
3-24
Duquienn Light Ccmptny 1997 Annuti Rcdiclegical Environm:ntil Rsport c.
Deviations from required sampling / analysis schedule ODCM reauired sites:
Site 48, Weirton, WV air sampling station was inoperable from 1/18/971742 to 1/20/971653 due to vacuum pump motor failure. The vacuum pump was replaced and the station was returned to service.
Site 13, Meyers Farm air sampling station was inoperable from 1/29/971115 to 1/30/97 0715 due to blown fuse. The fuse was replaced and the station was returned to service.
Site 13, Meyers Farm air sampling station was inoperable from 6/16/97 0858 to 6/18/971306 due to blown fuse. The fuse was replaced and the station was returned to service.
Site 13, Meyers Farm air sampling station was inoperable from 8/2/97 0831 to 8/5/971120 due to worn and weathered fuse box. The fuse box was replaced and the station was returned to service.
Site 30, Shippingport SS air sampling station was inoperable from 9/29/971224 to 9/29/971653 due to burnt contact causing the vacuum pump motor to fail. The vacuum pump was replaced and the station was returned to service.
l
.Non-ODCM reauired sites:
Site 30A, Shippingport SS QC air sampling station was inoperable from 4/19/97 0816 to 4/21/971203 due to defective on/off switch. The defective switch was replaced and the station was returned to service.
Site 28, Shermans Dairy Farm air sampling station was inoperable from 9/19/97 0320 to 9/22/97 2006 due to timer switch failure. The timer switch was replaced and the station was returned to service.
3-25
__ o
Duqussne Light Company g
1997 Annual Radiological Environmental Report a
Figure 3-2 Average Concentration of Gross Beta in Air Particulates I
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'IN n3/ lod 3-26
Duqusens Light Ccmpany 1997 Annut! Radiological Environmsntil Rsport C.
Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was required in 1997) l 1.
Characterization of Stream Sediments and Soils l
The stream sediments consist largely of sand and silt. Soil samples may vary from l
sand and silt to a heavy clay with variable amounts of organic material.
l 2.
Sampling Program and Analytical Techniques l
a.
Program l
River bottom sediments were collected semi-annually above the Montgomery i
Dam, in the vicinities of ths Beaver Valley discharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 3-1 and are shown in Figure 3-3.
Soil samples were collected at each of ten (10) locations during 1997. At 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 assure representative undisturbed samples.
Sampling locations are listed in Table 3-1 and are shown in Figure 3-3.
Bottom sediments and soils are analyzed for gamma-emitting radionuclides.
b.
Analytical Procedures Gamma analysis of sediment or soil is performed in a 300 ml plastic bottle which is counted by a gamma spectrometer.
1 l
3-27 l
Duquasns Light Company 3
1997 Annual Radiological Environmsntal Raport E
Figure 3-3 Environmental Monitoring Locations - Shoreline Sediments and Soil I
N h
urs A
s,
)
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)
'N D
4 m
, Beaver alls on Heights es Marion si -
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"3 East Rochester
,Fairview egg 4 Freedom f
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\\(Weirt n Control Site # 48A, Sector 10,15.6 miles, not shownl Q@
,/
C1 tion New Cumberland linton nio 3
s C'
SOIL SAMPLING LOCATIONS f-8'
- D tance b
D nce Sector Location Sector Location N
N 32 15 08 Midland. PA 3
13 11 14 Meyers' Farm f;
46 3
25 industry Church Area 22 8
03 South of BVPS (Onsite) 47 14 49 East Liverpool, OH
- 'g{.
27 7
61 Brunton's Dairy Farm j
18A 10 15 6 Werdon. VN 29A 3
83 Nicois 30 4
05 Shippingoort PA (S S )
'M 51 5
80 Ahquipoa. PA SEDIMENT SAMPLING LOCATIONS S' '
D tance b'
D nce
[
Sector Location Sector Location N
N Upstream. New Cumbedand W
2A 13 02 BVPS Discharge 50 12 11 8 Dam 49 3
50 Upstream - Montgomery Dam
. N :a s
e; % :n t<w,
.n o. u; I
I 3.=
I Duqusann Light Company 1997 Annut! Redislogical Environmantil R:psrt 3.
Results and Conclusions A summary of sediment analysis is presented in Table 3-2.
a.
Sediment A total of six (6) samples were analyzed by gamma spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was detected in every sample. Be-7 was detected in two samples. Small amounts of Cs-137 from previous nuclear weapons tests were detected in five river sediment samples. The average Cs-137 activity for the two downstream sites was lower than the upstream control location samples, which are unaffected by plant effluents. Small amounts of Co-58, Co-60, Cs-134 and Sb-125 were detected in the Beaver Valley Power Station discharge l
area and are attributable to station releases. The activity detected in the station l
discharge area is consistent with station data of authorized radioactive discharges which were within limits permitted by the NRC license.
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 disch rgEs,'
are adequate and that the environmental monitoring program is sufficiently sensitive.
b.
Soil A total of ten (10) samples were analyzed by gamma spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was detected in every sample. Small i
amounts of Cs-137 from previous nuclear weapons tests were detected in all ten l
samples including the control station (Weirton, WV). When compared against pre-operational values and previous samples, the Cs-137 is trending down.
l l
l i
3-29
Duqu:sna Light Company g
1997 Annur.1 Radiological Environm:ntsi Report E
D.
Monitoring of Feedcrops and Foodcrops 1.
Characterization of Vegetation and Foodcrops According to the 199G statistical summary of the Pennsylvania Department of Agriculture, there were approximately 575 farms in Beaver County. The total value of farm crops and livestock was $16,793,000. The principal source of revenue was in dairy products which was estimated at $6,849,000. Revenues from other farm products were estimated as follows:
Field Crops
$1,794,000 Fruits
$239,000 Horticulture and Mushrooms
$3,859,000 Meat and Animal Products
$3,442,000 Vegetables and Potatoes
$497,000 Poultry Products
$113,000 The totalland in Beaver County is 279,020 acres. Approximatel; 147,900 acres are forested land and 57,960 acres are pasture and crop land.
2.
Sampling Program and AnalyticalTechniques a.
Program Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 3-4. Each sample is analyzed by gamma spectrometry.
Foodcrops (vegetables) were collected at garden locations during the summer of 1997. Leafy vegetables, i.e., cabbage, were obtained from Shippingport, Georgetown, and Industry, PA, and Weirton, WV. All samples were analyzed for E
gamma emitters by gamma spectroscopy. The samples were also analyzed by E
radiochemical analysis for I-131.
I I
I 33o
Duquesno Light CcmpIny 199~ Annurl Rrdi:l:gical Environm:ntil R: port Figure 3-4 Environmental Monitoring Program - Feedcrop and Foodcrop Locations
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1 irton Control Site 48, Sector 10,16.5 mifg not shok g
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Sample Type Site No.
Location Food 10 Shippingport Food 15 Georgetown Food 46 Industry Food 48 Weirton. WV Feed 25 Seanght s Dairy 3-31
Duqu:sns Light Comp ny 1997 Annual Radiologic l Environmsnt:1 R port b.
Procedures Gamma emitters in feed are determined by scanning a dried, homogenized sample with the gamma spectroscopy system. A high resolution germanium detector is utilized with this system. Food samples are loaded into tarred 300 or 150 ml plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters.
Radiciodine (I-131) in food crops is determined by radiochemistry. Stable iodide carrier is first added to a chopped sample which is then leached with sodium hydroxide solu' ion, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and treated with sodium hypochlorite. Tae iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into toluene, it is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
3.
Results and Conclusions A summary of data is presented in Table 3-2.
a.
Feed A total of twelve (12) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was present in all samples and Th-228 was present in five (5) samples. Be-7 was detected in nine (9) samples.
b.
Food A total of four (4) samples were analyzed for 1-131. No detectable concentrations were present.
A total of four (4) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was present in all samples. No other nuclides were identified.
c.
The data from food and feed analyses were consistent with previous data. Based on the anahtical results, the operation of the Beaver Valley Power Station did not contribe : any measurable increase in radioactivity in the foods and feeds in the vicinity of the site.
I 3-32
[
1 Duqussns Light Company 1997 Annual Radiclogical Environmsntil Rsport E.
Monitoring of Local Cows Milk 1.
Description - Milch Animal Locations Samples of fresh milk are obtained from milch animals at locations and frequencies
]
noted in Table 3-1. This milk is analyzed for its radiciodine content, calculated as lodine-131, gamma emitters, and strontuim-89 and strontuim-90.
j Detailed field surveys are performed during the grazing season to locate and enumerate milch animals within a five (5) mile radius of the site. Survey data for the most recent survey conducted is shown in Section 4, Land Use Census.
2.
Sampling Program and Analytical Techniques a.
Program Milk was collected from these (2) reference dairy farms (Searight's and Brunton's) within a 10-mile radius of the site and from one (1) controllocation (WindsMimer's) outside of the 10-mile radius. Additional dairies, which represent the highest potential milk pathway for radiciodine based on milch animal surveys' '
and meteorological data, weie selected ano sampled. These dairies are subject to l
change based upon availability of milk or when more recent data (milch animal census) indicate other locations are more appropriate. The location of each is shown in Figure 3-5 and described below.
Number of Direction and Distance from Collection Site Dalry Milch Animals Midpoint of Unit 1 Reactor Period 25 Searight 54 Cows 2.1 miles SSW Jan. - Dec.
l 27 Brunton 93 Cows 6.1 miles SE Jan. - Dec.
69*
Collins 4 Goats 3.4 miles SE Jun. - Oct.
96 Wiiidsheimer UCows 10.4 mile'ISW Jan. - Dec.
j s
109*
Soissen 24 Cows 3.7 miles WSW Jan. - Dec.
[ElDe$
105*
Ambrose 28 Cows 3.8 miles WSW 106*
Conkle 46 Cows 3.7 miles WSW Jan. - Dec.
Highest potential pathway dairies The sample from Searight Dairy is collected ano analyzed weekly for radiciodine l
using a procedure with a high sensitivity. Samples from each of the other l
selected dairies are collected monthly when cows are indoors, and bi-weekly when cows are grazing. This monthly or bi-weekly sample is analyzed for Sr-89, i
Sr-90, gamma emitters including Cs-137 (by high resolution germanium gamma spectroscopy) and 1-131 (high sensitivity analysis).
l l
l 3-33
Duqusann Light Company 1997 Annu 1 R diological Environm ntal Report Figure 3 5 Environmental Monitoring Locations - Milk
('
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l,fiF~ {
gsa-
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G n.o
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'\\ ' '
, is Negleyy Eastv t
2r i
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is*-
, (
Willidqsport
'1 New Brg Mn T Fredericktown O'
- .4 East Rochest
[
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2 i wille alcutta Ise 1
L' 10 mj'e ra&J
/
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L N #lEE*+
U Mdla ipp g l
y PowerStati g
o r
Hon,wn
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$#96 j
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6' Di ce Location M
0 D tance Sector Location Sector No N
25 10 21 Seangnt s Davy
-j 105*
12 38 Ambrose Dairy 27 7
61 Brunton's Dairy Farm (p
106*
12 37 Conkle Dairy 96 10 10 4 Windsheimer Dairy 7;
109*
12 37 Soisson Dairy ous-g., v4stu vtU. at< sw r 4 9pm --
2 69*
7 34 Colkns m
,;, y p. e -
.o e c e
- Darries selected based on hegnest deposition factors 3-34
l Duquasna Light Ccmptny l
1997 Annual Radiological Environmnntil R3 port I
b.
Procedure Radiciodine (1-131) analysis in milk was performed using chemically prepared samptes and analyzed with a low-level beta counting system.
Gamma emitters are determined by gamma spectroscopy of a 1 liter Marinelli container of milk.
Strontium milk samples are prepared by adding stable strontium carrier l
and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is purified in all samples by the Argonne method using 3 grams of extraction materialin a chromatographic column. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for the ingrowth of Y-90. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitatir'g SrCO from the sample after yttrium 3
separation. This precipitate is mounted on a nylon planchet and is covered 2
with an 80 mg/cm aluminum absorber for low level beta counting, Chemical yields of strontium and yttrium are determined gravimetrically.
3.
Results and Conclusions A summary of data is presented in Table 3-2.
A total of one hundred fifty-one (151) samples were analyzed for 1-131 during 1997. All 1-131 activities in milk were below the minimum detectable level.
I A total of one hundred twenty (120) samples were analyzed for Sr-89 and Sr-90. No Sr-89 was detected. Sr-90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the normally expected range.
At total of one hundred twenty (120) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was present in al! samples. No other radionuclides were identified.
All results were consistent with (or lower than) those obtained in the preoperational program. Based on the analytical results, the operation of the Beaver Valley Power Station did not contribute any measurable increase in radioactivity in the milk in the vicinity of the site.
i l
3-35
Duquasn3 Light Company 1997 Annual Radiological Environmrnt:1 R port F.
Environmental Radiation Monitoring 1.
Description of Regional Background Radiation and Sources The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300-400 feet. Most of the land is wooded.
l The principal geologic features of the region are nearly flat-laying sedimentary g
beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and 3
shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sanostone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major g
tributary streams.
g Based on surveys reported in previous annual reports, exposure rates ranged _
from 6-12 R/hr. Results for 1997 indicated that background radiation continued in this range.
2.
Locations and Analytical Procedure.=
Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLCa).
In 1997 there were a total of forty-four (44) offsite environmental TLD locations.
The locations of the TLDs are shown in Figure 3-6. Thirteen (13) locations also have QC Laboratory TLDs. Both laboratories use calcium sulfate dysprosium, (CaSOiDy)in Teflon matrix.
The calcium sulfate dysprosium (CaSO4Dy) TLDs were annealed at the Contractor Central Laboratory shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit between the Central E
Laboratory, the field location, and the Central Laboratory was corrected by E
transit controls maintained in lead shields at both the Central Laboratory and the field office. All dosimeters were exposed in the field in a special E
environmental holder. The dosimetry system was calibrated by reading g
calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation field.
3-36
Duqussne Light Comp:ny 1997 Annual Radiological Environmental Rrport l
l 3.
Results and Conclusions Data obtained with the contractor TLD (CaSO(Dy in Teflon) during 1997 are l
summarized in Table 3-2, and the quality control TLD results are listed in Table 5-7.
The annual exposure ~ rate of all offsite TLDs averaged 0.181 mR/ day in 1997.
As in previous years, there was some variation among locations and seasons as would be expected. In 1997, ionizing radiation dose determinations from TLDs averaged approximately 66.1 mR for the year. This is comparable to previous years. There was no evidence of aromalies that could be attributed to i
the operation of the Beaver Valley Power Station. The TLDs confirm that I
changes from natural radiation levels, if any, are negligible.
1 l
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3-37
Duqussno Light Company 1997 Annu:1 Radiological Environmsntal Report Figure 3-6 TLD Locations b
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3-38
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Duquesne Light Company 1997 Annual Radiological Environmsntal Rsport w
Figure 3-6 (Continued)
TLD Locations u
SOUTHEAST Site Distance Sector Location p Site
~
Sector Distance Location N o.
(miles) g N o.
(miles) 27 7
6.1 Brunten's Farm 78 7
2.7 Raccoon Municipal Bldg 45.1 6
1.9 Raccoon Twp.
79 3
4,4 Raccoon Twp. (Routes 18 (Kennedy's Corners) t
& 151) 51 5
8.0 Aliquippa f
80 9
8.2 Raccoon Park 59 6
1.0 Irons' Farm i
82 9
6.9 Hanover Township Municipal Building 76 6
3.8 Raccoon Twp. School I
94 8
2.2 Raccoon 1wp. (McCleary Road)
Ra TP(
77 6
5.6 a den R d$
[
NORTHWEST Site Distance Location gy Site Distance Sector Sector Location N o.
(miles)
N o.
(miles) g
^
15 14 3.7 Georgetown s
87 14 7.0 Calcutta. OH -
%{.
88 15 2.8 Midland Heights
~
32 15 0.8 Midland, PA (S.S )
47 14 4.9 E. Liverpool, OH 89 15 4.8 Ohioville (Water Company) gi 60 13 2.5 Haney's Farm 90 16 5.2 Fairview School 86 13 6.2 E. Liverpool, OH
!S 93 16 1.1 Midland (Sunset Hills)
~
(Croxall's) n 3
NORTHEAST Site Distance Location gl Site Sector Location Distance Sector No.
(miles) p.
No.
(miles) 10 3
1.0 Shippingport Boro 70 1
3.4 Western Beaver School L
28 1
8.6 Sherman's Farm P
71 2
6.0 Brighton Twp. School
@i 29B 3
8.0 Beaver County 72 3
3.3 Site of Former Logan Hospitai i
School 30 4
0.5 Shippingport, PA Ni 73 4
2.5 Potter Twp. School (S.S.)
q Mt Pleasant Church 45 5
2.2 74 4
7.0 Com. College Ctr. Twp.
I 46 3
2.5 Industry Church Area g
75 5
4.1 Holt Road 46.1 3
2.3 Industry, PA (Garage)
E 91 2
3.9 Pine Grove Road / Doyle E
Road L
SOUTHWEST
[
Site Distance Location Fq Sector Location Site Distance Sector No.
(miles)
No.
(miles)
L 13 11 1.4 Meyers' Farm i
84 11 8.3 Hancock Cty., WV t
(Childrens Home) 14 11 2.5 Hookstown S
85 12 5.7 Hancock Cty., WV
{
(Routes 8 & 30) 48 10 16.3 Weirton, WV (Water O
92 12 2.8 Greene Twp.
p L_
Co.)
E (Georgetown Road) 81 9
3.6 Southside School (h'
95 10 2.3 McCleary Road (Hollie Williams)
J re p (Min j
[
83 10 4.2 3-39 L
Duqu:;sns Light Company 1997 Annurl Radiologic:l Environmsntal Report G.
Monitoring of Fish j
1.
Descriotion During 1997, fish collected for the radiological monitoring program included I
carp and catfish.
2.
Sampling Program ano Analytical Techniques a.
Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley affluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caJght is analyzed by gamma spectroscopy. Fish sampling locations are shown in Figure 3-7.
b.
Procedure A sample is prepared in a standard tared 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a high resolution germanium detector.
3.
Results and Conclusions l
A summary of the results of the fish monitoring data is provided in Table 3-2.
A total of eight (8) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was detected in all samples. No other gamma emitting radionuclides were detected.
Based on the analytical results, the operation of the Beaver Valley Power Station did not contribute any measurable increase in radioactivity in the Ohio River fish population.
l l
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3-40
Duqunsna Light CcmpIny
{
1997 Annual Radiological Environmnntal Raport Figure 3 7 Environmental Monitoring Program - Fish Sampling Locations
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Sector Location 2A 13 02 BVPS Discharge 49 3
50 Upstream Montgomey Oam L
3-41
Duqussn3 Light Comp;ny 1997 Annual Radiologicti Environm*ntil R: port H.
Monitoring of Surface, Drinking, Ground Waters and Precipitation 1.
Description of Water Sources The Ohio River is the main body of water in the area. It is used by the Beaver Valley Power Station for plant make-up for the cooling tower and for receiving plant liquid effluents.
Ohio River water is a source of water for some towns both upstream and a
downstream of the Beaver Valley Power Station site. It is used by several g
mi'"palities and industries downstream of the site. The nearest user of the
'iver as a potable water source is Midland Borough Municipal Water
- y. The intake of the treatment plant is approximately 1.5 miles sam and on the opposite side of the river. The next downstream user is cast Liverpool, Ohio which is approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream use river water for cooling purposes.
Groundwater occurs in large volumes in the gravel terraces which lie along the-river, and diminishes considerably in the bedrock underlying the site. Normal wel! 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 me'n annual preci,nitation for the area is 36.43 inches based on 1965 to 1994 data collected at the Pittsburgh International Airport.
I I
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1 3-42 I
l Duqu;sno Light Ccmprny 1997 Annurl Ridiological Environmtntal Report 2.
Sampling and AnalyticalTechniques I
a.
Surface (Raw River) Water The sampling program of river water includes three (3) sampling points along the Ohio River. Raw water samples are normally collected at the East Liverpool (Ohio) Water Treatment Plant [ River Mile 41.2) daily and composited into a weekly sample. Two automatic river water samplers are at the following locations: Upstream of Montgomery Dam [ River Mile 29.6];
and at J&L Steel's river water intake [ River Mile 36.2]. The automatic sampler takes a 20-40 mi sample every 15 minutes and samples are l
collected on a weekly basis. The weekly grab sample and automatic water i
sample are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point.
The weekly composites from the automatic river water sampler upstream at Montgomery Dam are analyzed for 1131.
The monthly composites are analyzed for gamma emitters. The quarterly-composites are analyzed for H-3.
i Locations of each sample peint are shown in Figure 3-8.
i b.
Drinking Water (Public Supplies)
Drinking (treated) water is collected at both Midland (PA) and East l
Liverpool (OH) Water Treating Plants. An automatic sampler at each location collects 20-40 mil every 20 minutes. These intermittent samples are then composited into a weekly sample. The weekly sample from each j
location is analyzed for 1-131.
Monthly composites of the weekly samples are analyzed by gamma l
spectrometry. Quarterly composites are analyzed for H-3. Locations of i
each sample point are shown in Figure 3-8.
l l
(
3-43 1
Duqu!.sne Light Company 1997 Annu:1 Radiologic:l Environm:ntal Report c.
Groundwater Semi-annual grab samples were collected from three (3) locations (see g
Figure 3-8) within four (4) miles of the site. These locations are:
E l
One (1) wellin Shippingport, PA g
l 3
l One (1) wellin Hookstown, PA One (1) wellin Georgetown, PA Each ground water sample is analyzed for tritium and by gamma spectroscopy.
d.
Precipitation l
l Precipitation is collected at Shippingport, PA, East Liverpool, OH and Weirton, WV. Precipitation, when available, is collected each week and then composited into quarterly samples. The quarterly composites are analyzed for H-3 and gamma emitters. Locations of each sample point are shown in Figure 3-8.
e.
Procedures Gamma analysis is performed on water samples by placing one liter of the l
sample into a Marinelli container and counting the sample on a high resolution germanium gamma spectrometry system.
Tritium is determined in water samples by liquid scintillation counting.
Radiciodine (1-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
l l
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3-44
1 I
Duqu:sn3 Light Company 1997 Annual Radiclogicti Envir nm:ntal Rap:rt Figure 3-8 I
Environmental Monitoring Stations Locations -
Ground, Surface Water, Drinking Water and Precipitation I*
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I Sample Site Disunce Sector Description Sample Site Distrance Sector Description Type No, (miles) 7;q Type No.
(miles)
'.;$f "8"'8* W'88%
Surface 2.1 14 1.5 Ground 14 11 2.5 Hookstown. PA Surface 5
14 49 E. Liverpool. OH
-9l.
Ground 15 14 37 Georgetown, PA I
^
"[
Precipitation 30 4
05 Shippingport, PA (S S }
Surface 491 4
5.3 er ept_ -
.l Precipitation 47 14 49 E. Uvorpool. OH Dnnking 4
15 1.3 hifn" ' #'
Precipitation 48 10 16.3 Weirton. WV Dnnking 5
14 49 Ground 11 3
0R Shipoengport PA Gut us rm-n J + we.4 e bA:he sergq.rN6 eaw/ Sim -4ch wa I
3-45 I
l
Duqu:sna Light Company 1997 Annu:1 Radiological Environmsnt:1 Raport 3.
Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, gi ground and precipitation) are provided by sample type and analysis in El Table 3-2. These are discussed below.
a.
Surface Water A total of twelve (12) samples were analyzed quarterly for H-3. One of the g
twelve was positive for H-3, just slightly above detectable levels and was E
located upstream of the plant (NOVA Chemical) and could not be attributed to plant releases.
A total of thirty-six (36) samples were analyzed by gamma spectrometry.
No gamma-emitting radionuclides were detected.
A total of fifty-two (52) samples were analyzed for 1-131 using a highly sensitive technique. Trace levels of I-131 were measured in twenty-one (21) of the weekly samples. All the positive results but two were below the~
required LLD. The two above the required LLD were below reportable levels. These positive results were detected at a controllocation above the BVPS discharge and could not be attributed to plant releases.
b.
Drinking Water A total of eight (8) samples were analyzed for H-3. No H-3 was detected.
A total of twenty-four (24) samples were analyzed by gamma spectrometry. No gamma-emitting radionuclides were detected.
A total of one hundred four (104) samples were analyzed for 1-131 using a g
highly sensitive technique. Positive levels of I-131 were measured in E
seventy-two (72) of the weekly samples. All the positive results except six were below the required LLD. The six above the required LLD were below reportable levels and could not be attributed to plant releases. The positive results were detected at both the Midland and East Liverpool plants. As noted under Surface Water above,1-131 has been observed upstream of the site.
c.
Groundwater A total of six (6) samples were each analyzed for H-3 and by gamma spectrometry. No H-3 or gamma-emitting radionuclides were detected.
I 3-46
Duquisna Light Comp:ny 1997 Annu 1 Rrdiological Envir:nm:ntti R: port d.
Precipita'. ion A total of twelve (12) samples were analyzed for H-3 and by gamma spectrometry. Two (2) positive tritium results detected were within normal leveh. Naturally occurring Be-7 was detected in five (5) samples.
Naturally occurring K-40 was detected in two (2) samples. No other ga:nma emitting radionuclides were detected.
e.
Summary The data from water analyses demonstrates that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in local river, drinking, well waters or precipitation. The analytical results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.
Further, the actual detected concentration (averaged over the total batch I
discharge period during the year) attributable to Beaver Valley Power
^
Station, was only 0.109% of the limits set forth in Appendix C of the ODCM for water discharged to the Ohio River. The Ohio River further reduced I
this concentration by a factor of approximately 600 prior to its potential use.
f.
Deviations from ODCM required sampling schedule Site 5, East Liverpool drinking water was found with collection vessel valve open between 3/18/971141 to 3/20/971133. Valve was closed and I
sample collection continued from 3/20/97 to 3/25/97. New collection vessels were installed 5/30/97 with valve location on top so that even if left open they would not drain down.
Site 2.1, Downstream J&L surface water sampler was taken out of service for 34.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> between 9/25/97 0730 to 9/26/971800 due to maintenance performed by J&L personnel on related system.
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u 3-47
Duquun3 Light Company 1997 Annuri Radiological Environm:ntal R: port 1.
Estimates of Radiation Dose to Man 1.
Pathways to Man - Calculational Models The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using codes for the E
ARERAS/ MIDAS computer system equivalent to NRC computer codes g
XOQDOQ2, GASPAR, and LADTAP. Dose factors listed in the ODCM were used to calculate doses to maximum individuals from radioactive noble gases g
in discharge plumes. Beaver Valley effluent data, based on sample analysis in g
accordance with Tables 2-1 and 2-3, were used as the radionuclide activity input.
I Radionuclides contained in the Annual Radioactive Effluent Release Report (noble gases, particulates, radiuiodines 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 ODCM.
All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to code equivalent to XOQDOQ2 which in turn provided input for the GASPAR equivalent. Except when more recent or specific data was available, all inputs were the same as used in the Beaver Valley Power Station Environmental Statements or in Regulatory Guide 1.109.
The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, de " cow-milk-child", and other ingestion pathways.
All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using E
intrinsic germanium detectors. Each batch is diluted by cooling tower 5
blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall(River Mile 35.0). The actual data from these analyses E
are tabulated and used as the radionuclide activity input term in code 3
equivalent to LADTAP. A hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is available, all other input are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109. Pathways, which were evaluated, are drinking water, fish consumption, and shoreline recreation.
I g
Duqu ens Light Ccmpany 1997 Annual Rrdi: logic;l Environm:mt:;l Rsport 2.
Results of Calculated Radiation Dose to Man - Liquid Releases a.
Individual Dose The doses which are calculated by the model described above are to the likely most exposed realindividuallocated at Midland since this is the nearest location where significant exposure of a member of the general population could potentially occur. A breakdown of doses by pathway and organ is provided in Table 3-5 for the likely most exposed individual.
I included in this table is a breakdown of a typical dose to individuals from natural radiation exposure. The results of calculated radiation dose to the likely most exposed real individual are compared to BVPS annual limits in Table 3-6.
b.
Upon implementation of the Unit 2 Technical Specifications and inception of the liquid discharge procedures at Unit 2 on July 24,1987, the discharge limits were clarified to be reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annual site limits listed in Table 3-6 are specific ~
to this report only, and were derived by inultiplying the individual Technical Specification reactor limits by a factor of two (2).
c.
Population Dose The 1997 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was:
Organ Man-Millirems Largest Isotope Contributor I
Total Body 129 H-3 125 Man-Millirems Thyroid 138 H-3 125 Man-Millirems 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 1997 are provided in Table 3-7.
The doses include the contribution of all pathways. A 50-mile population dose is also calculated and provided in Table 3-7. H-3 is the primary radionuclide contributions to these doses.
The results are compared to the BVPS annua l limits in Table 3-7. As in the liquid discharge limits, the gaseous effluent limits are reactor specific; i.e.,
Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annuallimits listed in Table 3-7 are specific to this report only, and were derived by multiplying the individual I
Technical Specification reactor limits by a factor of two (2). The reeults show compliance with the BVPS annual limits.
I 3-49 I
I
Duquasna Light Company 1997 Annual R diol:gical Environmental Report Table 3-5 Radiation Dose to an Individual (a), mremlyr - Liquid Releases (b)
Pathway Skin Highest Organ Thyroid Bone Whole Body 0.00071 0.00008 0.00050 0.00053 Fish N/A Consumption (Teen)(Liver)
(Adult)
(Child)
(Adult) 0.00210 0.00210 0.00003 0.00176 Drinking N/A (Infant)(Thyroid)
(Infant)
(Child)
(Child)
Water Shoreline 0.00003 0.00003 0.00003 0.00003 0.00003 Activities (Teen)
(Teen) (Skin)
(Teen)
(Teen)
(Teen) mrem 0.00003 0.00240 0.00210 0.00054 0.00191 Highest (Teen)
(Child)(Liver)
(Infant)
(Child)
(Child)
Individual TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (c)
Ambient Gamma 58 Radiation Radionuclides in Body 40 Global Fallout
<1 Radon 198 TOTAL mrem / year 296 (a)
Likely most exposed member of general population -located at Midland drinking water intake (b)
Total liquid releases are from Site (combined Units 1 and 2)
(c)
National Academy of Sciences,"The Effects on Populations of Exposure to Low Levels of lonizing Radiation," BEIR Report,1990 I
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3-50 I
Duquasna Light CcmpIny 1997 Annual Redislogicti Environm:ntal Rrp rt Table 3-6 Results of Calculated Radiation Dose to Man - Liquid Releases individual BVPS Annual Percent of Organ Exposure (a)
Limits Annual Limit mrem mrem TOTAL BODY Adult 0.0018 6.0 0.03 Teen 0.0013 ^
6.0 0.02 Child 0.0019 6.0 0.03 Infant 0.0017 6.0 0.03 ANY ORGAN Adult 0.0020 (Liver) 20.0 0.01 Teen 0.0017 (Liver) 20.0 0.01 Child 0.0024 (Liver) 20.0 0.01 Infant 0.0021 (Thyroid) 20.0 0.01 (a)
Likely most exposed member of general population -located at Midland drinking water intake 3-51
?
Duqu:sn3 Light Company 1997 Annual Rcdiological Environmsnt:1 R: port 4.
Conclusions Based upon the estimated dose to individuals from the natural background radiation exposure in Table 3-6, the incremental increase in total body dose to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit 1 and 2, is less than 0.0001% of the annual background.
The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a g
small incremental dose to that which area residents already received as a E
result of natural background. The doses constituted no meaningful risk to the public.
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Duqussna Light Ccmp:ny
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1997 Annual Radi logical Envircnmsnt:1 Rsport Table 3-7 Results of Calculated Radiation Dose to Man - Atmospheric Releases MAXIMUM BVPS PERCENT OF
(
EXPOSURE ANNUAL
^
ANNUAL INDIVIDUAL LIMIT miem mrem TOTAL BODY 0.406 30 1.35 SKIN 0.406 30 1.35 LUNG 0.405 30 1.35 THYROID 0.430 30 1.43 50-MILE
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POPULATION ORGAN DOSE man rem TOTAL BODY 0.734 SKIN 0.244
(
LUNG 0.737 THYROID 0.760
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Duqurans Light Ccmptny
~ 1997 Annu:1 Ridicingicti Environm:ntal Raport SECTION 4 - LAND USE CENSUS A land use census was conducted July 28 through August 1,1997 to comply with BV-1 and BV-2 Technical Specification 6.8.6b Item 2 and the ODCM Appendix C CONTROL 3.12.2. The census results are summarized in Table 4-1. The lacations of the milch animals are shown on
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Figure 4-1.
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Duqusens Light CcmpIny 3
1997 Annurl Radiological Environm ntal R port E,
Table 4-1 Location of Nearest Residence, Garden, ar.d Milch Animal SECTOR RESIDENCE (miles)
GARDEN (miles)")
MILCH ANIMALS (milesf2)
N 1.55 1.55 None NNE 1.59 1.61 None NE 0.42 2.65 None ENE 0.38 0.95 1.36 E
0.42 1.14 2.62 ESE 0.87 1.60 None l
SE 1.10 1.25 2.31 SSE 1.10 2.16 3.14 S
1.40 2.31 3.83 SSW 0.80 1.53 1.93 SW 1.67 1.67 1.90 WSW 1.46 2.39 3.41 W
2.27 2.27 None WNW 2.84 3.18 4.83 NW 0.91 0.92 4.28 NNW 0.91 1.17 None (1)
Gardens greater than 500 square feet producing fresh leafy vegetables (2)
Within five miles I
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1997 Annu 1 R diological Environmsntal Rnport Figure 4-1 Milch Animal Census
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Duqussn3 Light Comptny 1997 Annuti Rrdiologicti Environm:ntal Rsport SECTION 5 - QUALITY CONTROL PROGRAM / INTERLABORATORY COMPARISON PROGRAM j
A.
Quality Control Progr?.m The Quality Control (QC) Program for the Beaver Valley Radiological Environmental Monitoring Program involves the analysis of split and duplicate samples at a QC laboratory and the analysis of high quality (NIST traceable) spiked samples (results are discussed in the Interlaboratory Comparison Program section). This testing provides a means to ensure independent checks are performed on the precision and accuracy of the measurements of l
radioactive materials in environmental sample matrices. It should be noted that the comparisons for split and duplicate samples were at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure.
The NRC criteria listed in NRC Inspection Procedure 84750,12/4/90, inspection Guidance 84750-03 is used as the acceptance criteria for comparisons of results of split and spike samples between the Contractor Lab and the QC Lab / Independent Lab. These comparisons are performed by dividing the comparison standard by its associated I
uncertainty to obtain the resolution. The standard value is multiplied by the ratio values obtained from the following table to find the acceptance band for the result to be compared:
Note that in the case where the counting precision of the standard yields a resolution of less than 4, a comparison cannot be calculated. Values identified with an '*' in Tables 5-1 I
through 5-10 do not meet acceptance criteria.
Resolution Ratio
<4 4-7 0.5 - 2.0 8-15 0.6 -1.66 16 - 50 0.75 -1.33 51 - 200 0.8 - 1.25
> 200 0.85-1.18 1.
Split Sample Program (DLC Contractor Laboratory - DLC QC Laboratory)
Routine environmental samples of surface (river) water, drinking water, milk, sediment, soil, food crops, and feed crops were routinely split and analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory.
A summary of results of split water samples is provided in Table 5-1 and Table 5-2.
There were no non-comparisons in all the surface water and drinking water analysis.
Summaries of milk, sediment, soil and feed / food crop split samples are provided in Table 5-3 and Table 5-4. Good overall agreement was obtained with only feed having any non-comparisons. Naturally occuring potassium and beryllium were the only non-comparisons. Some variation may be expected due to variations in duplicate samples, and variations in analytical procedures and in calibration, source type, etc.
l 5-1
Duqu:2n3 Light Company 1997 Annual RIdiological Environm:ntil Report Duplicate Sample Program (DLC Contractor Laboratory - DLC QC Laboratory) ml 2.
lI Duplicate (co-located) air particulate and charcoal filters samples were collected at Location #30 and compared (gross beta for particulate filters and radiciodine for charcoal filters) during the year on a weekly basis. Comparison of particulate and charcoal samples alternated from week to week. For each quarter the particulate filters were composited and analyzed for gamma activity. Results are presented in i
Table 5-5 and Table 5-6. There was good agreement of both the air particulate (beta) j and charcoal cartridge filters. Quarterly composites of the air particulate filters j
(gamma) showed good comparisons in all four quarters.
Thirteen (13) duplicate (co-located) TLDs from the Contractor Laboratory and QC Laboratory are replaced quarterly, and the results are compared. The average of the Centmetor Laboratory and the average of the QC Laboratory agree within 6% of the mean of all results. This is well within the precision of typical TLD systems. Summary data of the TLD monitoring program is provided in Table 5-7.
B.
Interlaboratory Comparison Program Participation in an Interlaboratory Comparison Program is required by BV-1 and BV g E
Technical Specification 6.8.6b, Itcm 3. In 1997 this requirement was fulfilled by the Contractor Lab (Teledyne Brown Engineering Environmental Services - Westwood N.J.)
participating in the US EPA Interlaboratory Comparison Program (spiked water samples g
only) and by analyzing high quality (NIST traceable) spiked samples supplied by two E
Duquesne Light Company contracted vendors.
1.
Contractor Lab The high quality (NIST traceable) spiked samples include air particulate and charcoal g
i filters (prepared by the DLC QC Laboratory) and water and milk (prepared by the E
independent Laboratory). The samples were submitted to the Contractor Lab for analysis. The " spiked to" values are used for calculating comparison acceptance criteria. Values identified with an '*' do not meet acceptance criteria explained above.
These results are presented in Tables 5-8 through 5-10.
Comparison of results of the spiked water and milk samples showed good results except for the Sr-89 in milk for each of the samples in the first and second quarter.
It was determined that the sample preparer was not rinsing the strontium extraction column correctly. This was corrected and samples from the third and fourth quarters showed excellent comparisons.
Comparison of results of the spiked air particulate fiuers and charcoal cartridge filters showed good results. One of the charcoal cartridge samples required a recount because the initial count was skewed high by failing to reverse the sample at mid-count. Both results are reported in Table 5-10.
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5-2
Duqussne Light Comprny l
1997 Annuri R di: logical Envircnmsntil R: port The US EPA Interlaboratory Comparison Program results for 1996, that were not available for publication in the 1996 report, are presented in Table 5-11. Table 5-12
{
contains the available results for 1997. Figure 5-1 contains the trending graphs for the water analysis performed back to 1981. Teledyne Brown Engineering Environmental Services results are denoted on Figure 5-1 as 'Tl'. This program indicated that the
{
Contractor I aboratory results wf.,re in agreement with the EPA except as noted in the footnote's. The footnotes on the tables discuss investigation of problems encountered in a few cases and the steps taken to prevent reoccurrence. The Contractor
[
Laboratoiy had satisfactory performance within the US EPA Interlaboratory Cross Check Program.
2.
Quality Control Lab The Quality Control Lab (Teledyne Brown Engineering - Midwest Lab) participated in the US EPA Interlaboratory Comparison Program (spiked water samples only). The
[
results for 1996 that were not available for publication for the 1996 report are presented in Table 5-13. The ava!!able results for 1997 are presented in Table 5-14.
r This program indicated that the QC Laboratory results were in agreement with the EPA L
except as noted in the remarks within the table. The remarks within Tables 5-13 and 5-14 discuss investigation of problems encountered in a few cases and the steps taken' to prevent reoccurrence. The QC Laboratory had satisfactory performance within the
[
EPA Interlaboratory Cross Check Program.
C.
Conclusions
[
Based cn all available Quality Control data and Interlaboratory Comparison data the Environmental Monitoring Program for 1997 is acceptable with respect to both accuracy
[
and measurement.
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L 5-3 r
Duqu:;;;ns Light CampIny 1997 Annu 1 Rrdiolsgicti Environm:ntrl R:p:rt Table 5-1 Quality Control Data ContractorlQuality Control Laboratory Comparison Split Surface Water Samples Sampling DLC - Contractor DLC - QC Units Media Analysis Period Lab (1)
Lab (1)
Surface January
<3
< 4.2 pCi/l Water Co-60 April
<3
< 2.8 pCill (Monthly
.uly
<3
< 2.3 pCi/l Composite)
October
<3
< 3.7 pCill Surface January
<3
< 2.9 pCi/l Water Cs-134 April
<3
< 6.4 pCi/l (Monthly July
<4
< 2.6 pCi/l Composite)
October
<4
< 4.2 pCi/l Surface January
<4
< 3.1 pCi/l
~
Water Cs-137 April
<4
< 6.3 pCill (Monthly July
<3
< 2.5 pCi/l Composite)
October
<4
< 2.3 pCill ist Quarter
< 200
< 153 pCill er Tritium a e ly 3rd Quarter
< 200
< 166 pCill e
(1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
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Duquisna Light Ccmpany 1997 Annurl Rrdicl:giccl Envir:nm:ntil Repart Table 5-2 Quality Control Data Contractor / Quality Control Laboratory Comparison Split Drinking Water Samples Media Analysis Sampling DLC - Contractor DLC - QC Units Period Lab (1)
Lab (1)
Drinking February
<3
< 6.3 pCi/l Water Cs-137 May
<3
< 5.9 pCi/l (Monthly August
<5
< 1.6 pCi/l Composite)
November
<4
< 2.4 pCi/l Drinking February
<3
< 7.1 pCi/l Water Cs-134 May
<3
< 3.1 pCi/l (Monthly August
<4
< 1.2 pCi/l
' Composite)
November
<3
< 2.5 pCill Drinking February
<3
< 4.8 pCill Water Co-60 May
<3
< 5.1 pCi/l ~
(Monthly August
<4
< 2.5 pCi/l Composite)
November
<3
< 2.3 pCi/l Drinking March
< 0.27
< 0.4 pCi/l Water 1-131 June 0.48 i 0.22
< 0.5 pCi/l (Weekly August 1.20 i 0.20
< 0.3 pCill Split)
November
< 0.35
< 0.2 pCi/l 2nd Quarter
< 200
< 163 pCill ar Ritim 4th Quarter
< 200
< 164 pCi/l mpos te (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
t 5-5
Duqus::no Light Comptny 1997 Annual Radi logical Envircnm:ntil R: port Table 5 3 Quality Control Data ContractorlQuality Control Laboratory la Comparison Split Milk Samples DLC - Ob DLC - Contractor Sampling Analysis Units Media Penod Lab (1)
Lab (1)
Sr-89
< 0.77
< 0.7 pCi/l l
Sr-90 1.6 t 0.2 1.7 i 0.4 pCi/l E
Milk l-131
<0.23
< 0.4 pCi/l (Weekly Split) 3/24/97 Co-60
<4
< 3.5 pCill Cs-134
<3
< 3.3 pCill Cs-137
<4
< 4.7 pCi/l K-40 1330 i 130 1420i100 pCi/l Co-60
<4
< 3.8 pCi/l Milk l-131
< 0.27
< 0.3 pCi/l (Weekly Split) 6/16/97 Cs-134
<4
< 3.7 pCill Cs-137
<4
< 3.6 pCi/l K-40 1280 i 130 1310i90 pCill Sr-89
< 1.4
< 0.7 pCill Sr-90 1.8 0.3 2.4 0.5 pCill Milk l-131
< 0.26
< 0.3 pCi/l E
(Weekly Split) 9/22/97 Co-60
<3
< 6.1 pCi/l E
Cs-134
<3
< 5.1 pCi/l Cs-137
<3
< 5.1 pCi/l E
K-40 1220 i 120 1190i150 pCi/l 3
<3
< 6.1 pCill Milk l-131
< 0.32
< 0.4 pCi/l g
(Weekly Split) 12/15/97 Cs-134
<3
< 3.5 pCi/l E
<3
< 4.2 pCi/l K-40 1150 i 120 1240 i 160 pCi/l l
(1)
Uncertainties are based on counting statistics and are at the 95% confidence level.
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5-6
Duquisna Light C:mp::ny 1997 Annurl Radioicgical Environmantal Rip:rt Table 5-4
[
Quality Control Data Contractor / Quality Control Laboratory Comparison Split Feed, Food and Sediment Samples DLC -
Media Samplin9 Analysis Contractor DLC - QC Units Period Lab (1)
Lab (1)
Be-7
- 0.218 1 0.027 0.6110.14 pCi/gm (dry)
- 2.18 i 0.22 6.0110.37 pCi/gm (dry)
Feed 6/16/97 Co-60
< 0.004
< 0.015 pCi/gm (dry)
(25) 1-131
< 0.006
< 0.019 pCilgm (dry)
I Cs-134
< 0.004
< 0.006, pCi/gm (dry)
< 0.004
< 0.013 pCi/gm (dry)
K-40 1.51 i 0.15 2.09 i 0.29 pCi/gm (wet) j L
< 0.009
< 0.014 pCi/gm (wet)
Food 9/16/97 l-131
< 0.013
<0.023 pCi/gm (wet)
(10)
Cs-134
< 0.009
< 0.011 pCi/gm (wet)
< 0.008
<0.007 pCi/gm (wet)
Co-58 0.546 1 0.058 0.498 i 0.038 pCi/gm (dry)
Co-60 0.393 1 0.055 0.344 1 0.029 pCilgm (dry)
Sediment 10/15/97 Cs-134 0.136 1 0.040
< 0.062 pCi/gm (dry)
(2A)
Cs-137 0.162 1 0.048 0.166 i 0.026 pCilgm (dry)
Ra-226 1.930 1 0.640 2.289 0.376 pCi/gm (dry)
K-40 9.830 i 0.980 10.680 0.560 pCi/gm (dry)
K-40 10.4 i 1.0 10.810.2 pCi/gm (dry)
[
Soil Co-60
< 0.03
< 0.007 pCi/gm (dry)
(30) 8/6/97 Cs-134
< 0.03
< 0.012 pCi/gm (dry)
Cs-137 0.343 i 0.034 0.35 i 0.01 pCi/gm (dry) f Ra-226 1,79 i 0.45 1.69 0.18 pCi/gm (dry)
(1)
Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
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See Section 5-A.
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5-7
Duqu:sn3 Light Company 1997 Annu:1 Rtdiological Envircnm:ntal R: pert Table 5-5 Quality Control Data Contractor / Quality Control Laboratory Comparison ga Duplicate (Co-located) Air Particulate and Charcoal Filter Samples Air Particulates Air lodine pCl/Cu Meter (Beta) pCi/Cu Meter DLC - Conkactor DW - QC DLC - Contractor DLC - QC E
Sample Date g
Sample Date Lab (1)
Lab (1)
Lab Lab 12/30 -1/6 0.023 i 0.003 0.022 1 0.003 1/6 - 1 /13
< 0.01
< 0.013 1/13-1/20 0.021 1 0.003 0.022 1 0.003 1/20-1/27
< 0.01
< 0.008 1/27-2/3 0.018 1 0.003 0.024 1 0.003 2/3 -2/10
<0.01
< 0.020 2/10-2/18 0.018 i 0.003 0.017 i 0.002 2/18 - 2/24
< 0.01
< 0.011 2/24 - 3/3 0.010 1 0.003 0.011 i 0.002 3/3-3/10
< 0.01
< 0.012 3/10-3/17 0.014 1 0.003 0.018 i 0.003 3/17 - 3/24
< 0.01
< 0.01_5 3/24 - 3/31 0.012 1 0.003 0.012 i 0.003 3/31 - 4/7
<0.01
< 0.004 4/7 - 4/14 0.013 i 0.003 0.015 i 0.003 4/14 - 4/21
< 0.01
< 0.015 j
4/21 - 4/28 0.009 i 0.003 0.011 1 0.002 4/28-5/5
< 0.01
< 0.006 5/5-5/12 0.012 1 0.003 0.013 1 0.002 5/12 - 5/19
< 0.01
< 0.023 5/19-5/27 0.007 i 0.002 0.010 i 0.002 5/27-6/2
< 0.01
< 0.011 6/2 - 6/9 0.007 1 0.003 0.009 i 0.003 6/9 - 6/16
< 0.01
< 0.007 g
6/16 - 6/23 0.018 1 0.003 0.021 i 0.003 6/23 - 6/30
< 0.01
<0.007 6/30 - 7/7 0.012 i 0.003 0.013 0.004 7/7 - 7/14
< 0.01
<0.015 5
7/14 - 7/21 0.023 1 0.003 0.022 1 0.003 7/21 - 7/28
< 0.01
< 0.009 l
7/28-8/4 0.017 i 0.003 0.021 1 0.003 8/4 - 8/11
< 0.01
< 0.017 8/11 - 8/18 0.014 1 0.003 0.017 i 0.003 8/18 -8/25
<0.01
< 0.015 8/25-9/2 0.023 i 0.003 0.024 1 0.003 9/2 - 9/8
< 0.01
< 0.004 9/8-9/15 0.017 t 0.003 0.020 1 0.003 9/15 9/22
< 0.01
< 0.004 9/22 - 9/29 0.016 1 0.003 0.020 i 0.003 9/29 10/6
< 0.01
< 0.015 10/6-10/13 0.035 1 0.004 0.037 0.004 10/13 10/20
< 0.02
< 0.005 10/20-10/27 0.011 1 0.003 0.017 1 0.003 10/27-11/3
< 0.02
< 0.007 11/3 - 11/10 0.014 1 0.003 0.016 0.003 11/17 -11/24
< 0.02
< 0.009
=
11/17 -11/24 0.032 i 0.004 0.031 1 0.004 11/24-12/1
< 0.01
< 0.006 12/1 - 12/8 0.017 1 0.003 0.018 i 0.003 12/8-12/15
< 0.01
< 0.013 12/15 12/22 0.033 1 0.004 0.036 1 0.004 12/22-12/29
< 0.02
< 0.010 (1)
Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
5-8
Duquesne Light Company 1997 Annual Radiological Environmental Report Table 5 6 Quality Control Data Contractor / Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate Samples (Gamma)(pCl/Cu Meter)
DLC - Contractor DLC - QC Sample Period Nuclide Lab (1)
Lab (1)
Be-7 0.110 i 0.011 0.071 1 0.013 Co-60
< 0.0003
< 0.0004 Cs-134
< 0.0003
<0.0006 1st Quarter
< 0.0003
< 0.0006 Composite Cs-137 Ba-La-140
< 0.007
< 0.0017 K-40
< 0.006
< 0.025 Be-7 0.166 1 0.017 0.095 i 0.016 Co-60
< 0.0001
< 0.0008 2nd Quarter Cs-134
< 0.0001
< 0.0005 Composite Cs-137
< 0.0001
< 0.0005 -
Ba-La-140
< 0.01
<0.0008 K-40 0.003 0.001
<0.025 Be-7 0.141 0.014 0.085 i 0.011 Co-60
< 0.0002
< 0.0010 3rd Quarter Cs-134
<0.0002
< 0.0017 Composite Cs-137
< 0.0002
< 0.0005 Ba-La-140
< 0.006
< 0.0008 K-40
< 0.005
< 0.025 Be-7 0.093 0.009 0.061 1 0.012 Co-60
< 0.0002
< 0.0010 4th Quarter Cs-134
< 0.0002
< 0.0016 Composite Cs-137
< 0.0002
< 0.0006 Ba-La-140
< 0.010
< 0.0008 K-40
< 0.005
< 0.0231 (1)
Uncertainties are based on counting statistics and are spec fied at the 95% confidence coefficient.
5-9
Duqussn3 Light Company 1997 Annual Radislogical Environmsntal Report Table 5-7 Quality Control Data Contractor / Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/ day 1ST QUARTER 2ND QUARTER DLC QC Lab fC L cation No.
Co tr ctor Location No.
Co tr ctor Dy (CaSO :Dy)
(CaSO :Dy) 4 4
10 0.174 0.141 10 0.173 0.167 13 0.163 0.130 13 0.162 0.167 14 0.158 0.140 14 0.163 0.165 15 0.161 0.141 15 0.159 0.169 27 0.171 0.131 27 0.172 0.171 28 0.171 0.144 28 0.177 0.169 298 0.202 0.169 29B 0.205 0.199 32 0.187 0.158 32 0.174 0.154 45 0.162 0.163 45 0.177 0.173 46 0.177 0.144 46 0.160 0.164 47 0.198 0.164 47 0.194 0.191 48 0.183 0.158 48 0.170 0.179 51 0.180 0.159 51 0.164 0.179 3RD QUARTER 4TH QUARTER DLC C Lab DLC QC Lab Location No.
Co tr ctor Location No.
Co tr ctor
(
I (CaSO :Dy)
(CaSO :Dy) 4 4
10 0.174 0.130 10 0.197 0.162 13 0.166 0.136 13 0.176 0.163 l
14 0.189 0.135 14 0.178 0.169 15 0.175 0.148 15 0.176 0.171 27 0.183 0.135 27 0.180 0.176 28 0.186 0.138 28 0.189 0.177 298 0.216 0.175 29B 0.232 0.210 32 0.195 0.151 32 0.200 0.162 45 0.183 0.157 45 0.188 0.184 46 0.167 0.135 46 0.173 0.156 47 0.208 0.156 47 0.204 0.190 48 0.187 0.159 48 0.196 0.185 51 0.185 0.149 51 0.193 0.184 5 10
Duquesne Light Company 1997 Annual Radiological Environmental Report
[
Table 5-8
(
interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory Comparison Spiked Water Samples (pCill)
Sample Type and independent Contractor l Sample Date Identification No.
Sample Analyses Lab (1)
Lab (1)
Sr-89 15 i 1 1411 Sr-90 20 i 1 2111 1-131 2511 2311 Ce-141 251i13 275128 3/20/97 Water Cr-51 419121 459i46 53-359 Cs-134 15518 144 i 14
~
Cs-1c 12316 136 i 14 C&S8 8614 91 i 9
~
Mn-54 190 10 205 1 21 Fe-59 15518 198 i 20 Zn-65 17919 200 i 20 Co-60 190110 189i19 3/20/97 H-3 853143 11001200 5-Sr-89 2011 17 i 1 Sr-90 10 i 1 1111 l-131 6113 6111 Ce-141 192 1 10 198i20 6/19/97 Water Cr-51 288 1 14 296 i 39 53-361 Cs-134 118 i 6 111111 Cs-137 16718 187 19
~
C&58 11216 121112 Mn-54 123 i 6 129 1 13 Fe-59 11016 116i12 Zn-65 203 1 10 230 1 23 Co-60 15118 156 i 16 6/19/97 H-3 1310170 15001200 5-2 (Table 5-8 continued on next page) 6 5-11
Duqu:snn Light C:mp:ny 1997 Annual Radiologic:1 Envircnm:ntal Report Table 5-8 (Continued)
Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory l
m Comparison Spiked Water Samples (pCill)
Sample Type and independent Contractor Sample Date identification No.
Sample Analyses Lab (1)
Lab (1)
Sr-89 15 i 1 16 i 1 Sr-90 15 i 1 13 i 1 5
l-131 9415 93 t 1 Ce-141 6013 5817 Cr-51 239i12 301 i 39 9/18/97 Water 53-363 Cs-134 80 4 73 i 7 Cs-137 84i4 91 9 Co-58 4712 54i5 Mn-54 69 i 3 73 i 7 Fe-59 9415 99 i 10 I
Zn-65 154i8 170 i 17 E
C&60 15518 158 i 16 9/18/97 H-3 778140 9401200 53 Sr-89 31i2 3011 Sr-90 1011 12 i 1 1-131 4512 4711 Ce-141 167 i 8 161116 12/11/97 Water Cr 51 334i17 373i 37 53-365 Cs 134 171 i 9 170 1 17 Cs-137 177 9 190 i 19 C&58 8914 102110 Mn-54 137i7 144 i 14 Fe-59 97i5 107111 l
Zn-65 241112 268127 Co-60 16118 168 1 17 12/11/97 H-3 1076154 1200i200 53 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
I 5-12
i Duqussna Light Ccmp:ny 1997 Annual Radinlegic:1 Environmsnt.I R p:rt Table 5-9 Interlaboratory Comparison Program l
Independent Laboratory / Contractor Laboratory l
Comparison Spiked Milk Samples (pCl/l) l Sample Type and Independent Contractor Sample Date identification No.
Sample Analyses Lab (1)
Lab (1)
Sr-89 25 i 1 14i1 Sr-90 1911 15 i 1 1131 2011 1911 Ce-141 232i 12 227 123 3/20/97 Milk Cr-51 387 i19 377i38 52-282 Cs-134 143 i 7 124i12 l
l Cs-137 114i6 122112 l
Co-58 79i4 75 i 8 Mn-54 176i9 189 1 19 Fe-59 144 i 7 156 116 Zn-65 16518 159 1 16 Co-60 176 i 9 168 i 17 St-89 25 i 1 1212 Sr-90 10 i 1 1011 1
i 1-131 6113 3311
]
I Ce-141 213 1 11 213121 6/19/97 Milk Cr-51 319116 338i41 52-283 Cs-134 13127 121112 l
Cs-137 18519 207121 Co-58 12416 126i13 Mn 54 137 i 7 145i15 Fe-59 122i6 127 i 14 Zn-65 225 11 254125 Co-60 168 i 8 177118
- See Section 5-A.
(Table 5-9 continued on next page) i 5-13
Duqu:sna Light Ccmp:ny 1997 Annual Rrdio.'ogical Environm:ntal R: port Table 5-9 (Continued)
Interlaboratory Comparison Program independent Laboratory / Contractor Laboratory Comparison Spiked Milk Samples (pCill)
Sample Type and independent Contractor Sample Date Identification No.
Sample Analyses Lab (1)
Lab (1)
Sr-89 15 i 1 14 i 1 Sr-90 14 i 1 14 i 1 1-131 87 i 4 80 i 1 Ce-141 77 i 4 7217 9/18/97 Milk Cr-51 304 i 15 313136 52-284 Cs-134 10215 98 i 10 Cs-137 10715 119112 Co-58 60 i 3 6d i 7 Mn-54 88 i 4 97i10 Fe-59 11916 136i14 Zn-65 196 i 10 216 i 22 Co-60 197 i 10 205i21 Sr-89 19 i 1 1812 Sr-90 1011 12 1 1-131 3912 43 i 1 Ce-141 98 i 5 104 i 10 12/11/97 Milk Cr-51 195 i 10 202 i 40 52-285 Cs-134 100i5 102 i 10 Cs-137 10315 119i12 Co-58 5213 6016 Mn-54 80 i 4 91i9 Fe-59 5713 67111 Zn-65 14117 164 i16 Co-60 9415 107111 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.
~
5-14
Duqu2cna Light Compiny 1997 Annu11 Rcdirl:gic l Envircnmental Raport
[
Table 5-10
(
Interlaboratory Comparison Program Contractor / Quality Control Laboratory Comparison Spiked Air Particulate / Charcoal Filters Sample Type and Sample DLC - Contractor DLC-QC Sample Date Units identification No.
Analyses Lab (1)
Lab (1)
^
2/12/97 Gross Beta 6.25 0.31 5.74i0.60 pCi/m*
DO A 3
^
10/14/97 Gross Beta 2.7210.63 3.04 i 0.30 pCi/m' DQ A
(
^
2/12/97 l-131 1.14 0.11 1.08 0.11 pCi/m*
DQ C C Ar rcoal mer 10/14/97 1-131 0.44 i 0.04 pCi/m*
DQQC CH4 0.53 i 0.053m (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. '
(2) Recount performed 10/22/97.
See Section 5-A and 5-B.
[
[
[
{
F L
5-15
Duqu:sno Light Company 3
1997 Annu 1 R diologicti Environm3ntal R:ptrt E
Table 5-11 Contractor EPA interlaboratory Comparison Program 1996 Deviation (c)
Media Nuclide EPA Results (a)
Engineer ng s I (b)
Gr-Alpha 59.1 14.8 55.671 5.03
-0.40 Ra-226 9.9 1 1.5 10.00 1 0.00 0.12 Ra-228 5.1 1.3 5.47 i 0.31 0.49 Gr-Beta 111.8 1 16.8 110.0 0.00
-0.19 10/15/96 Water Sr-89 10.0 5.0 9.00 i 0.00
-0.35 Sr-90 25.015.0 26.00 1.00 0.35 Co-60 15.015.0 14.67 i 1.53
-0.12 Cs-134 20.015.0 19.67 1.15
-0.12 Cs-137 30.0 i 5.0 29.33 1.15
-0.23 10/25/96 Water Gr-Alpha 10.3 5.0 9.03 0.72
-0.44 Gr-Beta 34.6 5.0 39.67 i 0.58 1.76 Co-60 44.0 5.0 44.67 0.58 0.23 Zn-65 35.0 5.0 38.67 0.58 1.27 11/08/96 Water Cs-134 11.0 5.0 12.00 i 0.00 0.35 Cs-137 19.015.0 20.67 1.15 0.58 Ba-133 64.0 6.0 56.67 i 3.21
-2.12 (d) 12/06/96 Water Ra-226 20.1 3.0 20.33 0.58 0.13 Ra-228 10.2 2.6 10.33 1 0.58 0.09 Footnotes:
(a)
EPA Results - Expected laboratory precision (1 sigma). Units are pCi/ liter for water.
(b)
Teledyne Results - Average one sigma. Units are pCi/ liter for water.
(c)
Normalized deviation from the known.
l (d)
The cause for the deviation could not be specifically determined. Samples were analyzed in triplicate on three different HPGe detectors providing results with good precision (less than 11%
deviation). The values calculated by the software for each discrete energy line of Ba-133 were also j
in agreement indicating an excellent efficiency versus energy calibration fit. Use of a valid branching ratio in the calculation was verified. The initial aliquot was verified and the Co-60, Cs-134, and Cs-137 values were in excellent agreement with the known. A specific trend over time l
was not apparent in the data; however, the normalized deviation calculated from the EPA appears to decrease as the known activity increases. No corrective actions are anticipated at this time. Future analyses will be monitored to identify any potential trend toward an "out of contror condition.
5-16
Duqurens Light Company 1997 Annu11 Radiologicri Environm3ntil Report Table 5-12 Contractor EPA Interlaboratory Comparison Program 1997 Co e on Media Nuclide EPA Results (a)
Deviation (c)
Engineer ng R s I (b) 01/17/97 Water Sr-89 12.0 5.0 10.00 i 1.00
-0.69 Sr-90 25.015.0 25.00 1.00 0.00 01/31/97 Water Gross Alpha 5.2 5.0 8.1010.89 1.00 Gross Beta 14.7 i 5.0 15.00 1 1.00 0.10 02/07/97 Water 1-131 86.0 9.0 106.00 4.36 3.85 (d) 02/14/97 Water Ra-226 5.9 1 0.9 5.27 0.23
-1.22 Ra-228 8.2 2.1 8.40 i 0.30 0.16 03/07/97 Water H-3 7900.0 i 790.0 7366.67 378.59
-1.17 I
Gr-Beta 102.1 1 15.3 103.33 5.77 0.14-Sr-89 24.0 i 5.0 23.00 1.00
-0.35 Sr-90 13.0 i 5.0 12.67 1.15
-0.12 i
Co-60 21.015.0 22.67 0.58 0.58 04/15/97 Water Cs-134 31.0 5.0 28.67 0.58
-0.81 Cs-137 22.015.0 24.67 1 1.53 0.92 Gr-Alpha 48.0 12.0 54.67 1.53 0.96 Ra-226 13.0 2.0 13.00 1.00 0.00 Ra-228 3.1 0.8 4.87 0.12 3.82 (e)
Co-60 18.0 5.0 19.00 0.00 0.35 Zn-65 100.0 i 10.0 99.33 1.15
-0.12 06/06/97 Water Cs-134 22.0 5.0 18.67 1.15
-1.15 Cs-137 49.015.0 48.67 0.58
-0.12 Ba-133 25.015.0 22.33 2.52
-0.92 06/13/97 Water Ra-226 3.0 0.5 3.43 0.49 1.50 Ra-228 3.1 0.8 3.43 0.23 0.72 06/18/97 Water Gr-Alpha 3.1 5.0 2.9310.25
-0.06 Gr-Beta 15.115.0 14.00 1 1.00 0.38 l
(Table 5-12 continued on next page)
F 5-17 A
Duqu:sn3 Light Comp:ny 1997 Annual Radial gical Environm:ntal R: pert
{
Table 5-12 (Continued)
Contractor EPA Interlaboratory Comparison Program 1997
- I" Media Nuclide EPA Results (a)
Dwiation (c)
Engineer ng s I (b) 07/11/97 Water Sr-89 44.015.0 38.33 i 1.53
-1.96 Sr-90 16.0 5.0 25.00 1 0.00 3.12 (f) 08/08/97 Water H-3 11010 1101.0 12000.00 1 0.00 1.56 09/12/97 Water Ra-226 20.0 3.0 20.00 1.73 0.00 Ra-228 8.0 2.0 7.40 0.17
-0.52 09/19/97 Water I-131 10.0 i 6.0 11.00 1 0.00 0.29 Gr-Beta 143.4 21.5 136.67 5.77
-0.54 Sr-89 36.0 5.0 36.00 i 1.00 0.00 Sr-90 22.015.0 21.67 2.08
-0.12' Co-60 10.015.0 10.67 i 0.58 0.23 10/21/97 Water Cs-134 41.0 5.0 41.33 1 0.58 0.12 Cs-137 34.0 5.0 36.00 i 1.00 0.69 Gr-Alpha 49.9 12.5 45.67 1.15
-0.59 Ra-226 5.0 0.8 5.90 i 0.10 1.95 Ra-228 5.0 1.3 4.27 0.12
-0.98 10/31/97 Water Gr-Alpha 14.7 i 5.0 19.67 i 1.53 1.72 Gr-Beta 48.9 5.0 50.67 3.51 0 61 (Table 5-12 continued on next page) 1 I
g 61e
1 Duqu sn3 Light C:mpiny 1997 Annuil Redi: logic l Envir nmant:1 R:psrt r
l Table 5-12 (Continued)
Contractor EPA Interlaboratory Comparison Program 1997 L
Co e ion Media Nuclido EPA Results (a)
Devladon (c)
Engineer ng s I (b)
^
Co-60 27.015.0 25.00 1 1.00
-0.69 L
Zn-65 75.0 i 8.0 71.00 1 3.61
-0.87 11/07/97 Water Cs-134 10.0 i 5.0 10.67 1 0.58 0.23 j
I Cs-137 74.0 5.0 76.00 1.00 0.69 Ba-133 99.0110.0 78.67 1 0.58
-3.52 (g)
I (a) EPA Results - Expected laboratory precision (1 sigma). Units are pCi/ liter for wr.ter.
(b) Teledyne Results - Average i one sigma. Units are pCi/ liter for water.
c (c) Normalized deviation from the known.
(d) Erroneously high reading of the stable iodine content by ion specific electrode occurred, causing an erroneously low chemical yield. If the electrode reading is ignored, the average I-131 result becomes 90 pCi/l, in good agreement with the given value. An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulfide. We will investigate suspiciously high electrode readings by performing a gravimetric yield on the sample without the addition of iodine I
carrier or the I-131 content of active samples can also be verified by performing a gamma spectral analysis.
(e) An investigation discovered a low chemical yield on one sample and the loss of another during analysis. In the future, we will repeat analyses of samples with yields less than 85%
(f) The strontium separation chemistry was performed on 7/22/97. Initial results for the three samples did not agree well, so all were remilked by a senior analyst. This was insufficient to correct the I
problem. In-house QC samples showed satisfactory results at this time. There was additional qualification of analysts on in-house blanks and spikes. Analysis performed after retraining has been acceptable.
(g) An investigation was conducted and no apparent cause for the discrepancy could be identified.
I I
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b Duqunna Light Compxny 1997 Annu:1 Rtdislogical Environmentil Rsport Table 5-13
[
QC Lab - EPA Interlaboratory Comparison Program 1996 U.S. Environmental Protection Agency's crosscheck program, comparison sif EPA and Teledyne's Midwest Laboratory results'.
Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result' Control Code Type
' Collected Analysis 12 Sigma' Is. N=1 Limits STW-775 WATER Oct 1996 I131 26.7 2.3 27.0 6.0 16.6 - 37.4 STW 776 WATER Oct.1996 Gr. Alpha 55.8 t 2.4 59.1 14.8 33.4 84.8 STW 776 WATER Oct,1996 Ra 226 7.610.3 9.911.5 7.3 12.5 Analysis was repeated with technician being observed by the lab supervisor. Result of repeat is 10.11 0.29 pCi/L The technician performed the analysis in compliance with the procedure. The original raw data was reviewed and no errors where found. The suspected reason for the low results is a slight error during dilution of the sample. No further action is planned at this time.
STW 776 WATER Oct,1996 Ra 228 4.710.3 5.111.3 2.87.4 STW 776 WATER Qct,1996 Uranium 31.911.1 40.9 4.1 33.8 48.0 All raw data was reviewed for errors and calculations where checked. No errors where found. The analysis was repeated with the technician being observed by the lab supervisor, ne procedure was performed with no discrepencies. De result of the repeat is 39.4 0.17 pCi/L The suspected cause of the low result is a dilution error. No further action is planned at this tirne.
STW 777 WATER Oct,1996 Co-60 15.7 i o.6 15.015.0 6.3 23.7 STW 777 WATER Oct,1996 Cs 134 18.310.6 20015.0 11.3 28.7 STW 777 WATER Oct,1996 Cs-137 30.3 i 1.5 30.015.0
, 21.3 - 38.7 STW 777 WATER Oct,1996 Gr. Beta 99.416.9 111.8 1 16.8 82.7 - 140.9 STW 777 WATER Oct,1996 Sr89 7.0 t l.0 100 5.0 1.3 18.7 STW-777 WATER Oct,1996 St-90 23.711.2 25.015.0 16.3 33.7 STW 778 WATER Oct.1996 Gr. Alpha 10.212.1 10.3 5.0 1.6 19.0 STW 778 WATER Oct,1996 Gr. Beta 32.0 1.6 34.615.0 25.9 - 43.3 STW-779 WATER Nov,1996 Ba 133 60.3 2.5 64.016.0 53.6 - 74.4
{
STW 779 WATER Nov,1996 Co-60 45.310.6 44.0 5.0 35.3 - 52.7 STW 779 WATER Nov,1996 Cs 134 11.711.2 11.0 5.0 2.3 19.7 STW 779 WATER Nov,1996 Cs 137 19.7 2.3 19.015.0 103 27.7
[
STW 779 WATER Nov,1996 Zn-65 37.012.7 35.015.0 26.3 - 43.7 STW-781 WATER Dee,1996 Ra 226 20.210.0 20.113.0 14.9 - 25.3 ST1W781 WATER Dec,1996 Ra 228 9.5 t 0.8 10.2 t 2.6 5.7 - 14.7
.STW 781 WATER Dee,1996 Uranium 5.2 0.1 5.03.0 0.0 - 10.2
{
' Results obtained by Teledyne Brown Engineering Environmentd Services Midwest Laboratory as a participant in the environmental sarnple crosscheck program operated by the Intercornparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
[
Environmental Protection Agency (EPA), Las Vegas, Nevada.
- All results are in pCi/L, except for elemental potasslum (K) data in milk, which are in mg/L: air filter samples, which are in pCi/ Filter.
- Unless otherwise Indicated, the TBEESM1 results art given as the mean 2 standard deviations for three determinations.
- USEPA results are presented as the known values and expected laboratory precision (1s, I determination) and controllimits as defined by the EPA.
{
[
r L
5-35 g
Duqu:sn3 Light Comp:ny 1997 Annu:1 Radiological Environmsntal Rnport 4
Table 5-14 QC Lab - EPA Interlaboratory Comparison Program 1997 U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Tcledyne's Midwest Laboratory results'.
[,
r Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result
- Control Code Type Collected Analysis 2 Sigma'
- 15. N=1 Limits STW 782 WATER Jan,1997 Sr89 9.710.6 12.015.0 3.3 - 20.7 STW 782 WATER Jan,1997 Sr90 24.011.0 25.0 5.0 16.3 - 33.7 STW-783 WATER Jan,1997 Gr. Alpha 10.0i l.4 5.2 i 5.0 0.0 13.9 l
STW-783 WATER Jan,1997 Gr. Beta 15.812.0 14.718.0 6.0 - 23.4 STW-784 WATER Feb,1997 1131 86.0 2.0 86019.0 70.4 - 101.6 g
STW 784 WATER Feb,1997 I131 79.312.0 66.019.0 70.4 - 101.6 STWW 786 WATER Feb,1997 Ra 226 6.710.2 5.910.9 4.3 - 7.5 STWW 786 WATER Feb,1997 Ra 228 8.4 i l.1 8.2 2.1 4.6 11.8 STWW-786 WATER Feb,1997 Uranium 26.5 1.3 27.013.0 21.8 - 32.3 5TW 787 WATER Mar,1997 H-3 7,594.0 1 279.7 7,900.0 i 790.0 6,529.4 - 9,270.6 STW-794 WATER Apr,1997 Gr. Alpha 44.311.6 48.0 ! 12.0 27.2 68.8 STW-794 WATER Apr,1997 Ra 226 10.710.9 13.012.0 9.5 - 16.5 WATER Apr,1997 Ra 228 4.7 0.4 3.1f0.8 1.7 4.5 STW 794 All raw data and calculations were reviewed for errors. The analysis was repeated with the technician observed by the lab supervisor; the result of the reanalysis 3.It0.5 pCi/L. The suspected cause of the higher result was the lower than expected recovery of barium tracer. No further action is planned at this time.
STW 794 WATER Apr,1997 Uranium 26.810.3 24.0 t 3.0 18.8 - 29.2 STW 795 WATER Apr.1997 Co-60 21.710.6 21.0 i 5.0 12.3 29.7 STW 795 WATER Apr,1997 Cs 134 27.311.2 31.015.0 22.3 39.7 STW 795 WATER
,Apr,1997 Cs 137 217i l.5 22.015.0 13.3 30.7 STW 795 WATER Apt,1997 Gr. Beta 93.212.1 102.1 1 15.3 75.6 128.6 STW-795 WATER Apr.1997 Sr 89 21.311.2 24.015.0 15.3 - 32.7 STW 795 WATER Apr,1997 St-90 12.710.6 13.0 5.0 4.3 - 21.7 STW 796 WATER Jun,1997 Ba 133 24.711.2 25.015.0 16.3 33.7 STW 796 WATER Jun1997 Co-60 18.710.6 18.015.0 9.3 26.7 STW 796 WATER Jun,1997 Cs 134 19.710.6 22.015.0 13.3 - 30.7 STW 796 WATER Jun,1997 Cs-137 52.012.0 49.015.0 40.3-57.7 STW 796 WATER Just1997 Zn-65 101.0 i 2.0 100.01 10.0 82.7 - 117.3 STW 797 WATER Jun,1997 Ra-226 2.7 i 0.1 3.0 i 0.5 2.1 - 3.9 STW-797 WATER Jun,1997 Ra 228 2.310.3 3.110.8 1.7 - 4.5 STW 797 WATER Jun,1997 Uranium 38.111.0 40.3 i 4.0 33.4 - 47.2 l'
STW 800 WATER Jul.1997 Gr. Alpha 3.110.3 3.115.0 0.0.11.8 STW-800 WATER Jul,1997 Gr. Beta 13.910.2 15.115.0 6.4 - 23.8 E
STW-801 WATER Aug,1997 H3 11,348.7
- 241.4 11.010.0 1 1,101.0 9,099.8 - 12,920.2 3
- Results obtained by Teledyne Brown Engineering Environrnental Services M!dwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and g
Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
l Environmental Protection Agency (EP A), Las Vegas, Nevada.
E
- All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter E
samples, which are in pCi/ Filter.
- Unless otherwise indicated, the TBEESML results are given as the mean i 2 standard deviations for three determinations.
- USEPA results are presented as the known values and expected laboratory precision (15, I determination) and controllimits as defined by the EPA.
5-36
-