ML20206G339
| ML20206G339 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1998 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20206G332 | List: |
| References | |
| NUDOCS 9905070177 | |
| Download: ML20206G339 (150) | |
Text
{{#Wiki_filter:- I l i DUQUESNE LIGHT COMPANY j BEAVER VALLEY POWER STATION i UNITS 1 AND 2 i LICENSES DPR-66 AND NPF-73 1998 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL ' 1 I
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9905070177 990430 PDR ADOCK 05000334 R PDR _
Duquans Light Company
- a. -
1998 Annual Radiclogical Environmtntal Rrport EXECUTIVE
SUMMARY
.This document is a detailed repod of the 1998 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 31,1998 in air, water, shoreline sediment, milk, fish, food crops, vegetation, 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 materials and levels of radiation are not higher than expected on the basis of the effluent measurement and modeling of the environmental exposure pathways.
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 nuclear power station. Indicator samples are the second sample type obtained. The.se samples show how much radiation is contributed to the environment by the site. Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration. In 1998, samples were taken from over 60 sites around Beaver Valley Power Station that included the aquatic, atmospheric and terrestrial environments. More than 2300 Enalyses were performed on these samples. The environmental program for 1998 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 both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations. The 1998 analytical results and pre-operational baseline results are summarized in Table 3-2 and Table 3-3.
' 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:
Concentiation(1) + Concentration (2) + . . 2 1.0 Limit Level (1) Limit Level (2) , Based on the analytical results of environmental samples during 1998, the Beaver Valley Power Station reporting levels were not exceeded. Positive results attributable to the Beaver Valley Power Station were consistent with station data i 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). il
Duquusn3 Light CompIny '
- 1998 Annual Radiological Environmtntal R: port In 1998, the radioactivity releases from BVPS Units 1 and 2 did not exceed the effluent limits identified in the Beaver Valley Power Station Operating License Technical Specification /Offsite 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 (approximately 4 million), from the operation of Beaver Valley Power Station Units 1 and 2,is less than 0.0001% of the annual background dose. The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) is 296 mrem per year.
Analytical results are divided into four ODCM required categories based on exposure pathways: Airborne, direct radiation, ingestion and waterborne. Each of these pathways is described below:
. The airborne exposure pathway includes airborne iodine and airborne particulates. The 1998 results were 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 1998 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 identified.
The fish samples taken indicated naturally occurring potassium-40 in each of the samples at average environmentallevels. One of the nine fish samples indicated trace amounts of cesium-137 near the typical detection sensitivities for gamma spectroscopy. Vegetation samples revealed naturally occurring potassium-40 and beryllium-7 at average environmental levels.
. The waterborne exposure pathway includes drinking water, surface (river) water, and river sediment. Water samples were analyzed for tritium and gamma-emitting radionuclides.
Tritium was identified in five of twenty-two samples, two upstream of the plant and three downstream. All five positive results were below typical lower limit of detection for H-3 analysis. Gamma analysis of samples indicated no gamma-emitting radionuclides above detection limits.1-131 analysis of weekly samples (156 total) indicated 61 positive results. Only five 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 of the plant and considered outside the influence of the site had similar results to the downstream drinking water samples. iii I
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- 4.
- Duquisna Light Company 1998 Annut! Radiological Envircnmsntal Rspart Sediment samples are taken from three locations, upstream of the site, at the discharge point of liquid 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-60 which are consistent with authorized station liquid discharges.
- In addition to the required samples discussed above, groundwater, precipitation, and feederops were also taken. Results were consistent with previous years and no degrading trends were identified.
. The environmental monitoring program outlined in the Beaver Valley Power Station ODCM for Units 1 and 2 was followed throughout 1998. The REMP results demonstrate 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.
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Duqunsna Light Ccmp:ny 1998 Annual Radiol:gical EnvircnmIntal R psrt TABLE OF CONTENTS EXEC U TI VE SU M M A RY . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii I SECTION 1 - INTRODUCTION A.. Scope and Objectives of the Progrant............... ...................... ................. .1-1 B. Description of the Beaver Valley Site.......... ..................................... .........1-1
- C. 1 99 8 Ope rati o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -2 SECTION 2 - MONITORING EFFLUENTS A. M onitoring of Liquid Effluents....... . ....... ..... .... . ................... ...... .......... ..... 2-1
- 1. Description of Liquid Effluents at the Beaver Valley Power Station..... 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
- 2. Atmospheric Effluent Treatment and Sampling........ .. ...... . ........... 2-13
- 3. Results.........................................................................................2-14 SECTION 3 - ENVIRONMENTAL MONITORING PROGRAM A. Environmental Radioactivity Monitoring Program........... ..... ...... .. ............. 3-1
- 1. Progra m De s cription. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 1
- 2. Sum m a ry of R es ults. . . . . . . . . . .. . . . . . . . . . . . ... . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . 3-7
- 3. Q uality Control Program. . .. .... .. . . . . ... . . . . .. . . . . . .. . . . ... .. .. .. ... ..... . .... . .. . . . .. . . . .. .. 3-7
- 4. Program C ha ng es . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . 3-7 B. A i r M onitori ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . . 3-22
- 1. Characterization of Air and Meteorology............................... ............ 3-22 !
- 2. Air Sampling Program and Analytical Techniques................ ............ 3-22 j
- 3. Results and Conclusions ... . . . ... .. . . . . . . . . . .. . . . . . . . ... . . . .... . .. . .. .... . . . .... . ... . . . .. 3-24 C. M onitoring of Sediments and Soils... ............... ....................... . ................... 3-27
- 1. Characterization of Strearn Sediments and Soils.................. .. .. ..... 3-27
- 2. Sampling Program and Analytical Techniques.................................. 3-27 ,
- 3. Results a nd Conclusions. . .. . . .. .. . ... . . .. . .. . . . . . . ..... .. .. ...... . . .. .. . . ... ... . . ... . .. . 3-2 9 D. Monitoring of Feederops and Food Products................ ............. ....... ... . 3-30 i
- 1. Characterization of Farm Products.................................................... 3-30
- 2. Sampling Program and Analytical Techniques....... ...... ............... ... 3-30
- 3. Re sults a nd Conclu sions. . .... . .. . .. . ... .. .. ... . ........ . ....... . .. . . . . . . . ... ....... . .. ... 3-32 l
l v
Duqusens Light Ccmptny -
' 1998 Annuil Radialegicti Environmsntal R port
' TABLE OF CONTENTS (Continued)
SECTION 3 - ENVIRONMENTAL MONITORING PROGRAM (continued). E. M onitoring of Local Cows M ilk............ ........ .... . . . ... ... ............ . .............. .... 3-33 1
- 1. Description - Milch Animal Locations...................... .. ....................... 3-33
- 2. Sampling Program and Analytical Techniques..... ... ........................ 3-33
- 3. Re s ults and Conclusions.. . . . . .... .. .... . . . ... . . .. . . . .. . .. .. . . . . .. .. . . . . . .. . ... . . .... 3 F. Environmental Radiation Monitoring...... . ........ ...... .. . ... ... ... .. .......... 3-36
- 1. Description of Regional Background Radiation and Sources........... . 3-36 1 2.
3. Locations and Analytical Procedures... ... ............... ... ........ ... ..... . 3-36 _ Re sults and Conclusions.... .... .. ... ...... .... . ........ .. ...... .. .. ... . . ...... ... . . . 3-37 G. M onitorin g of Fi s h . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-40
- 1. De s cri ption . . .. . . . . . . . . . . .. . .. . . . . . .. . ... . . . ...........................................3-40
- 2. Sampling Program and Analytical iechniques...... ....... .. ................ 3-40
- 3. Re s ults a nd Conclusions. . . .. . . . . . . . . . . . . .. . . . . . . .. . . . .. . . . . . . .. . . . . .. . ... . . . . . . . . .. .. .. 3-40 i H. Monitoring of Surface, Drinking, Ground Waters and Precipitation............ 3-42 j
- 1. Description of Water Sources... .... .... ..... . .. .... .. .. ................. ....... ..... 3-42
- 2. Sampling and Analytical Techniques................ ................ .. ............ 3-43 j
- 3. Re sults and Con clusions.. ... .. . ....... ......... ............ .. ............. .... ..... 3-46 i
- l. Estimates of Radiation Dose to M an..... . ... ...... .. ... ... ...................... ........ ... . 3-49 1
- 1. Pathways to hnan - Calculational Models.......... ......... ...................... 3-49 1
- 2. Results of Calculated Radiation Dose to Man - Liquid Releases....... 3-50
- 3. Results of Calculated Radiation Dose to Man -
Atmospheric Relea ses .. . . .. .. .. . . . .. . .. . . ... . . . . . .. . .. .. . . . . . .... .. ... . ... . . . . .. ..... .. .. 3-51
- 4. C o n cl u sio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-5 4 l l
SECTION 4 - LA N D U S E C EN SU S . .. . ....... . .. . . . . . . . . . . . .. ... . . . . .. . . .. . ...... .. . . .... . .. ... .. . . . . .. 4-1 l SECTION 5 - QUALITY CONTROL PROGRAM / INTERLABORATORY COMPARISON PROGRAM A. Q uality Control Program . . .. . . . .. .. . . . . . . . .. . . . . .. . . .. . .. . . . . . . . . . . . .. . . .. . . . .. . .. . .. . . . . .. 5- 1
- 1. Split Sample Program (DLC Contractor Laboratory - l DLC Q C La boratory) . . ...... ... . ..... .. . . ........ . ...... ............................5-1 i
- 2. Duplicate Sample Program (DLC Contractor Laboratory - J D LC Q C La bo ratory) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 l
- 3. Blind Split Program (DLC Contractor)................................................ . 5-2 B. Interlaboratory Comparison Program.. ....................... ... . ........... ............ 5-3
- 1. C o ntracto r Lab . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-3
- 2. Quali?y Control Lab. . . . . . . . . . ...........................................5-3 C. Conclusions. .... . .. ... . . . ...................................................5-3 j vi
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) ** Duquisn3 Light Company 1998 Annual Radiological Environmsntal Report i l
LIST OF TABLES Table 2 Radioactive Liquid Waste Sampling and Analysis Program.. .... ..... 2-7 J Table 2 Results of Liquid Effluent Discharges to the Environment............. .... 2-9
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Table 2 Radioactive Gaseous Waste Sampling and Analysis Program...... . 2-15 Table 3-1 -- Operational Radiological Environmental Monitoring Program.... ....... 3-2 Table 3 Environmental Monitorirm Program Results.. . . . .. .. ... ... ... ... .... 3-8 l Table 3 Pre-Operational Environmental Radiological Monitoring i Program Summary.. . .. .. . ... . . ..... . . . . . . . . . . .........................3-18 Table 3 Typical Detection Limits for Gamma Spectroscopy i Detection by High Resolution Germanium....... .. ...... ........ ... ..... 3-21 Table 3-5 Radiation Dose to an Individual, mrem /yr - Liq uid R elea s es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. .. . . . . . . . .. . . . . . . . .. . . . . . . . . . . 3-52 Table 3 Results of Calculated Radiation Dose to Man - Liquid R elea s e s . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 5 3 Table 3 Results of Calculated Radiation Dose to Man - Atmospheric Releases..... .......... ... .... ..............................3-55 l 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 Table 5 Quality Control Data Contractor / Quality Control 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 l Laboratory Comparison Duplicate (Co-located) Air Particulate and Charcoal Filter Samples... ..... .. ... ................. . ...... 5-8 . Table 5 Quality Control Data Contractor / 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 - m R/ day.... . .. ... .... .. .. . .. . .... .. . . . . . . . . . . . . . . . . . . . . . 5- 1 0 Table 5-8 - Quality Control Data Contractor Comparison of Blind Split Samples.... ... .... ... .... ... . ....... . .... . . . . . . . . . . . . . . . . . 5- 1 1 vli
Duqu:sna Light Company
- 1998 Annual Ridielegical Envir nmant:1 RIport
' LIST OF TABLES (Continued)
Table 5 Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory Comparison Spiked Water Sampies (pCi/l).... ... .. ....................................................5-12 Table 5 Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory Comparison Spiked Milk Sampies (pCl/l) ..... . .. .. . ........ ... ... .............................................5-14 Table 5 Interlaboratory Comparison Program Contractor / Quality Control Laboratory Comparison Spiked Air Particulate / Charcoal Filters....... 5-16 Table 5 Contractor EPA Interlaboratory Comparison Program 1998......... .. 5-17 Table 5 QC Lab - EPA Interlaboratory Comparison Program 1997.. ..... ... .. 5-34 Table 5 QC Lab - EPA Interlaboratory Comparison Program 199a....... ...... 5-35 vill
1 l Duquasnn Light Company l 1998 Annutl Rcdislogicd Envir:nmtntal Raport ] I LIST OF FIGURES l Figure 1 View of the Beaver Valley Power Station.......... ........... ...... . .. .. ...1-3 ' Figure 1-2 -- 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 Figure 2 Unit 2 Water Flow Schematic....... ........... ... ... .. . ... .. ... ........ ..... ...... 2-4 I Figure 2 Unit 1 Liquid Waste System .. ... . .. ........... ........ .. .. ... .. . .. ............ . . 2-5 l Figure 2 Unit 2 Liquid Waste System . ......... .... .. ... .... ....... .. .. . .. ... . .. .. .. .. ... 2-6 l Figure 2 Units 1 and 2 Gaseous Radwaste System............... ... ... ... ..........2-11 Figure 2 Units 1 and 2 Gaseous Release Points.. .... ........ ............ ... .. .... 2-12 Figure 3 Air Sam pling Stations . . .. . . .. ... . . . . . . . . . . . .. . . . .. . . . ... ... . . . . . . . .. . . ... . . . . .. .. .. . . . 3-23 Figure 3 Average Concentration of Gross Beta in Air Particulates.. . ....... . 3-26 Figure 3 Environmental Monitoring Locations - Shoreline S ed im ents a nd Soil . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2 8 Figure 3 Environmental Monitoring Program - Feederop and l Food Product Locations. ....................... .......... . . ............. . . .... 3-31 Figure 3 Environmental Monitoring Locations - Milk................... .... . .......... 3-34 j l Figure 3 TLD Locatio n s . . . .. . . . .. . . . . . . . . . . . . . . .. . .. . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-38 i Figure 3 Environmental Monitoring Program - Fish Sampling Locations....... 3-41 l Figure 3 Environmental Monitoring Stations Locations - Ground, i Surface Water, Drinking Water and Precipitation......................... . 3-45 Figure 4-1 M ilch A ni m al C e n s u s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-3 Figure 5 Contractor - EPA Cross Check Program Trending Graphs......... . . 5-19 i e 1 1 I 1 l I l lx
DuquIsna Light Company 1998 Annual Rrdiolsgicil Environmental Raport SECTION 1 '-INTRODUCTION A; Scope and Objectives of the Program - The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. The Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne Ught Company in 1998.' 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; five miles from East Liverpool, Ohio; and twenty-five 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 five 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 3,320. 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 the border south of the Beaver Valley Power Station at an elevation of 1,160 feet. Plant ground level is approximately 735 feet above sea level. The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. For 1998, the flow ranged from a minimum monthly 1 average of 7,500 cubic feet per second (CFS) to a maximum monthly average of l 89,500 CFS. The mean flow for 1998 was 36,367 CFS. ; 1 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 i 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 frcm the southwest in summer and from the northwest in winter.
1-1 D
1 Duquiene Light C:mpany l 1998 Annual R:di:Icgic'_I Envircnmtntal Rzp::rt The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below: Beaver Valley Unit 1 Beaver Valley Unit 2 Maximum Power Level 2652 - megawatts thermal 2652 - megawatts thermal Type of Power PWR PWR No. of Reactor Coolant Loops - 3 3 No. of Steam Generators & Type 3 - Vertical 3 -Vertical Steam Used by Main Turbine _ Saturated Saturated The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, j radioactivity in the primary system water is normally isolated from the secondary system. I Reactor coolant in the primary system is pumped through the reactor core and steam l generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and retumed to the steam generators to begin another steam / water cycle. C. 1998 Operation The Beaver Valley Power Station Unit 1 operated throughout 1998 except during a refueling outage that ended January 21 and unscheduled outages from January 31 to August 15. Unit 2 operated throughout 1998 except for unscheduled outages from January 1 to September 28 and November 1 to November 4. The maximum dependable capacity factor for 1998 were as follows: Unit 1 - 39.8% and Unit 2 - 24.4%. l 1-2
Duquesne Light Company . . 1998 Annual Radiological Environmental Report Figure 1 1 View of the Beaver Valley Power Station
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- Duqursnm Light Company 1998 Annual Radicingical Envircnm:ntal R: port Figure 12 Geographical Map and Principal Communities J in 50-mile Radius of the Beaver Valley Power Station l
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Duqussna Light Company 1998 Annual Rtdiological Environmnntal Rapsrt SECTION 2 - MONITORING EFFLUENTS
. The Beaver Valley Power Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases are controlled to ensure that limits set by Federal or State governments are not exceeded. In addition, self-imposed 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 Discharge to the Environment See Table 2-2.
4 2-1 4
e Duqunns Light C::mpEny ' 1998 Annu:1 Rtdiol:gical Environmtntal R;p:rt Figure 2-1 Liquid Discharge Points to Ohio River L 3 lif vl f_-
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- *- ]
1998 Annual Rrdiclogical Envircnm ntal Rrport Table 2-1 Radioactive Liquid Waste Sampling and Analysis Program MINIMUM LOWER LIMIT OF LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION (LLD) TYPE FREQUENCY FREQUENCY ANALYSIS ( Ci/ml)a P P Principal Gamma Emittersf SE-7 j Each Batchh Each Batchh I-131 1E-6 P Dissolved and Entrained M 1E-5 One Batch /Mh Gases (Gamma Emitters) Batch Waste Release Tanksd P M H-3 1E-5 Each Batchh Compositeb Gross Alpha 1E-7 j P Q Sr-89, Sr-90 SE-8 l Each Batchh Compositeb Fe-55 1 E-6 4 Grab Sampieg W Principal Gamma Emittersf ' 5E-7 Compositec l-131 1 E-6 Grab Sample 9 ** "" "" M 1E-5 l Gases (Gamma Emitters) ; B. Continuous 1 Releasese 9 M H-3 1 E-5 Grab Sampleg Compositec Gross Alpha 1E-7 Grab Sample 9 Q Sr-89, Sr-90 SE-8 Cr;mpositec Fe-55 1E-6 W - At least once per 7 days M - At least once per 31 days Q - At least oncp, per 92 days P - Complete (prior to each release j j
'l 1
l 2-7
Duqu::sna Light Ccmpiny *
- 1998 Annual Radiological Envircnmzntal Rrport 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. c.. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- d. A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior -
to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling. !
- e. A continuous release exists when the discharge of liquid wastes is from a non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. ,
Releases from the Turbine Building drains and the Auxiliary Feedwater Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd).
- f. .The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above {
nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
- g. When radioactivity is identified in the secondary system, a RWDA-L should be preparad on a monthly basis to account for the radioactivity that will eventually be discharged to the Ohio River,
- h. Whenever the BV-2 Recirculation Drain Pump (s) are discharging to Catch Basin 16, sampling will be performed by means of a grab sample taken every 4 hours during pump operation.
i 2-8
E DuquIsn3 Light C:mpany ] a 1998 Annual Radislogical Envir:nmsntal Rrpart l Table 2-2 Results of Liquid Effluent Discharges to the Environment Effluent Type Results for 1998 Steam System Blowdown The Steam System Blowdown was recycled. 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 j and Appendix C of the ODCM. No limits were exceeded. Values for all liquid releases have been reported in the Beaver Valley Power Station Annual Radioactive Effluent Release Report for 1998. Continuous Radioactive Waste Radioactive waste liquids were not discharged Liquids in a continuous mode during 1998. l l l 2-9
- Duqussna Light Campany, *
- i
' 1998 Annual Ridislogic:1 Envircnmtntal Ripsrt B. Monitoring of Atmospheric Effluents
- 1. Description of Atmospheric Effluent Sources
' Beaver Valley Power Station (Units 1 and 2)
The Beaver Valley Power Station identifies 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, lodines, and particulates. Tritium concentrations are estimated prior to release and followed up with a grab sample from the ventilation system used during release. Figure 2-6 shows the gaseous radwaste system at Beaver Valley Power Station.
)
The environmental continuous gaseous release points also require specific nuclide i identification. These points include: j
- a. Unit 1 Release Points: l
- 1) The Ventilation Vent located on top of the Unit 1 Primary Auxiliary Building.
- 2) The Supplementary Leak Collection and Release System (SLCRS) Vent j 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 I
located on top of the Unit 2 Containment Building._
- 3) The Decontamination Building Vent located on top of the Unit 2 Decontamination Building. ,
- 4) The Waste Gas Storage Vault Vent located on top of the Unit 2 Decontamination Building.
- 5) The Condensate Polishing Building Vent located on top of the Unit 2 I 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 weekly basis for the two SLCRS release points and on a monthly basis for the other six release points and analyzed for tritium. Continuous filter paper and charcoal cartridge samples are changed on a weekly basis. The filter papers are analyzed for particulate gamma-emitting radionuclides and gross alpha. Composites of the filter papers are analyzed monthly for Sr-89 and Sr-90. The charcoal cartridges are analyzed for radioactive iodine. Figure 2-7 shows these gaseous release points. 2-10
Duqu:isnn Light C::mpany l + 1998 Annurl Radiological Envir:nmInt:1 R;p rt Figure 2-6 1 l Units 1 and 2 Gaseous Radwaste System c
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Duqu ;sna Light Ccmpany *
- 1998 Annut! Radiolegical Environmental R5 port .
( Figure 2-7 Units 1 and 2 Gaseous Release Points
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- 1. Unit 1: Ventitation Vent 79 feet = 24 outers l
- 2. Unit is Contalrusent / SLCal Vent
- 3. Unit 112: Process Vent 134 fewt a 47 meters 475 feet = 145 seters g
- 4. Unf t 2: Ventitation Vent 83 feet a 24 meters i
- 3. Unit 2: Contalnnent / stca$ Vent 154 feet = 47 meters
- 6. Unit 2: Condensate Polishing Sullding Vent 80 feet a 24 meters Wj
- 7. Unit 2: Weste ces storage Vault vent
- 8. Unit 2: Deconteelnetton sulldins Vent 80 feet a 24 meters 80 feet = 24 meters [f
- 9. Unit 2: Turbine Suf tdine Vent 109 feet = 33 meters l Notes the telease Point shom for the Unit 2 Turbine Sullding Vent is l
' a representative exhaust point for the 10 roof exhaust outlets.
2-12
Duquama Light Company 1998 Annuil Radialogicil Environmsntal Rrport 1
- 2. Atmospheric Effluent Treatment and Sampling
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Gaseous Waste Disposal System (Units 1 and 2) l Radioactive gases enter the gaseous wasta 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 radioiodines are also present in this system.
The overheao gas compressor directs the radioactive gas sUeam to a gas surge tank. 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 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 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 through one of the gaseous waste disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the Unit 1 cooling tower. The radioactivity levels of the stream are continuously l monitored in accordance with the ODCM. l 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 Purge (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. 2-13
Duquicna Light C:mpany * *
)
'1998 Annu-l Radi.Ingicti Envir:nmsntal Riport Building 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 any3 :es of contaminated air. The normal exhaust is through the Ventilation Vent effluent patiway. This pathway is monitored continuously by several redundant channels of the Radiation Monitoring System (RMS) in accordance with the ODCM. Particulate and lodine samples are obtained continuously while grab noble gas samples are obtained weekly in accordance with the ] 1 ODCM. Upon a upper activity alarm, automatic dampers divert the system's exhaust I air stream through one of the main filter banks in the Supplementary Leak Collection ! and Release System (SLCRS) which exhausts through the SLCRS Vent effluent pathway. 1 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 i 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, 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 radioiodines.
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 1998.
2-14 l l
Duqussn3 Light Comp 2ny 1998 Annual Radi:Icgical Envircnm2ntal R! port Table 2-3 Radioactive Gaseous Waste Sampling and Analysis Program i I l MINIMUM LOWET( LlMIT OF GASEOUS RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION (LLD) TYPE FREQUENCY FREQUENCY ANALYSIS ( Cl/ce) P P ! Each Tank Principal Gamma Emitters 9 1 x 10-4 1 Waste Gas Grab Sample Each Tank Storage Tank Each Tank * { Grab Sample Each Tank
- H-3* i x 104 Principal Gamma Emitters 9 1 x 10-4
- 2. Containment Purge Each Purgeb Grab Sample . Each Purgeb H-3 1 x 10-6 Mb,c e Grab Mb Principal Gamma Emitters 9 1 x 10-4
'4. Ventilation Systemsh Sample H-3 1 x 10-6
- a. Process Vent wd 1-131 1 x 10-12
- b. Ventilation Vents Charcoal Sample I133 1 x 10-10
- c. Containment Wd Principal Gamma Emitters 9 1 x 10-11 Vents (SLCRS) Particulate Sample (1-131, Others)
- d. Decon. Bldg. Continuousf M Vent Gross alpha 1 x 10-11 l Composite
- e. Waste Gas Particulate Sample Vault Vent o i
- f. Cond. Polish. Composite Sr-89, Sr-90 1 x 10-11 Bldg. Vent Particulate Sample Noble Gases, Gross Beta Noble Gas Monitor 1 x 10-6 and Gamma W -
At least once per 7 days M - At least once per 31 days Q - At least once per 92 days P - Completed prior to each release The H-3 concentration shall be estimated prior to release and followed up with an H-3 grab sample from the Ventilation System during release. 2-15
. Duquasna Light Ccmp:ny 1998 Annuil Radiclegical Envircnmsntal R5 port 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 1 hour period. . This requirement does not apply if (1) analysis shows that the DOSE -
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 hours (from the appropriate ventilation release path) when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing or after removal from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- e. Tritium grab samples shall be taken at least once per 7 days (from the appropriate ventilation release path of the spent fuel pool area) whenever spent fuel is in the spent fuel pool.
- f. The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Appendix C CONTROLS 3.11.2.1, 3.11.2.2 and 3.11.2.3.
- g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
- h. Only when release path is in use.
2-16
E Duquezna Light C:mpany 1998 Annual RadiologicEl Environmsntal R: port 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 summarized in Table 3-1. Further description of each portion of the program (Sampling Methods, Sample Analysis, Discussion and Results) are included in Sections 3-8 through 3-1 of this report.
3-B - Air Monitoring 3-C - Monitoring of Sediments and Soils 3-D - Monitoring of Feederops and Food Products j 3-E - Monitoring of Local Cows Milk 3-F - Environmental Radiation Monitoring 3-G - Monitoring of Fish 3-H - Monitoring of Surface, Drinking, Ground Waters and Precipitation 3-1 - Estimates of Radiation Dose to Man I 3-1
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~ Duqussna Light Ccmpany 1998 Annual Radislogical Envir nmIntal R2 pert
- Table 3 Notations Operational Radiological Environmental Monitoring Program (Continued)
Notes: (a) Control sample station: These are locations which are presumed to be outside the influence of plant effluents.
. ('b)' Typical detection sensitivities for gamma spectrometry are shown in Table 3-4.
(c) Pa'rticulat'e samples are not counted within 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is > 10 times the yearly mean of control samples. (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location.
.(e) Composite samples are collected at intervals not exceeding 2 hours.
(f) Weekly milk sample from Searight's Dairy is analyzed for 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 hours 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:
. Sample points correspond to site numbers shown on maps. l . All air samples are decayed for 72 hours before analyzing for gross beta.
l l 3 I
Duquisn) Light Ccmptny 1998 Annual Radigingical Environmsntal R:rp:rt
- 2. Summary of Rasults ,
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 Beaver Valley Power Station Operating License, (Appendix A, Technical Specifications /ODCM). Summaries of results of analysis of each media are discussed - in Sections 3-B 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 j preoperational data with operational data indicate the ranges of values are generally in good agreement for both periods of time. Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, j 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 l and discussed in Section 5 of this report. I i
- 4. Program Changes l The following changes were implemented in the 1998 sampling program, a Added site 49.1 as an alternate surface water sampling site (not used in 1998).
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- 1998 Annual Radi:logicci Envir:nm;ntal R p3rt 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, Pennsylvania Reporting Level CY 1974 - 1975 (County) (State)
Pre-Operational Program Summary (Combined 1974 - 1975) Medium or Pathway Analysis and Total AllIndicator Locations Lower Limit of Sampled Number of Analysis Mean,(f) Range Detection (LLD) (Unit of Measurement) Performed Sediments Gross Alpha (0) -- - pCi/g (dry) Gross Beta (33) 1 18 g33/33) 5-30 Sr-90 (0) - - U-234, 235, 238 (0) - - Gamma (33) - 13 (33/33) 2- 30 K-40 1.o 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(a) 0.3 1.5 (3/33) 1.3 - 1.8 Others - < LLD i Foodstuff Gamma (8) - - pCi/g (dry) K-40 1 33 (8/8) 10 - 53 Cs 137 0.1 0.2 (1/8) - Zr/Nb-95 0.05 0.2 (1/8) - Ru-106(a) 0.3 0.8 (1/8) - Others - < LLD Feedstuff Gross Beta (80) 0.05 19 (80/80) 8 - 50 pCilg (dry) Sr-89 (81) 0.025 0.2 (33/81) 0.04 - 0.93 Sr-90 (81) 0.005 0.4 (78/81) 0.02 - 0.81 Gamma (81) - - K-40 1 19 (75/81) 5-46 Cs-137 0.1 0.5 (6/81) 0.2 - 1.6 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) - - pCi/g (dry) Gross Beta (64) 1 22 (64/64) 14 - 32 (Template Samples) Sr-89 (64) 0.25 0.4 (1/64) - Sr-90 (64) 0.05 0.3 (48!64) 0.1 - 1.3 ! U-234, 235, 238 (0) - - Gamma (64) - - K-40 1.5 13 (63/64) 5-24 Cs-137 0.1 1.5 (56/64) 0.1 - 6.8 Ce-144 0.3 1.1 (7/64) 0.2 - 3 Zr/Nb-95 0.05 0.3 (13/64) 0.1 - 2 Ru-106(a) 0.3 1.1 (3/64) 0.5 - 2 Others - < LLD (f) Fraction of detectable measurements at specified location. 3-18 __ _ _ _ _ _ _ _ _ _ __ _ ___ n
Duqu:sn2 Light Cump:ny
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1998 Annual Radiclogic:l Envir:nmIntal R psrt Table 3-3 (Continued) Pre Operational Environmental Radiological Monitoring Program Summary Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver, Pennsylvania Reporting Level CY 1974 - 1975 (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 ; Soil Gross Alpha (0) - - j pCl/g (dry) Gross Beta (8) 1 21 (8/8) 16 -28 ,j
. (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 l Sr-89 (0) - -
l Sr-90 (0) - - < C-14 (0) - - Drinking Water 1-131 (0) - - pCl/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 pCi/m3 Sr-89 (0) - - Sr-90 (0) - - l131 (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
I Duqurns Light Ccmpany
- 1998 Annut! Radici:gic;l Envirsnm:ntal R::p::rt
- Table 3-3 (Continued)
Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver, Pennsylvania Reporting Level CY 1974 - 1975 ] (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 Mean,(f) Range Detection (LLD) (Unit of Measurement) Performed Milk l-131 (91) 0.25 0.6 (4/91) 0.3 - 0.8 pCl/l Sr-89 (134) 5 7 (4/134) 6 -11 Sr-90 (134) 1 5.3 (132/134) 1.5-12.8 Gamma (134) - - Cs-137 10 13 (19/134) 11 - 16 Others < LLD Extemal Radiation 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 y- Annual (48) 0.5 mR* 0.19 (48/48) 0.11 - 0.30 Fish Gross Beta (17) 0.01 1.9 (15/17) 1.0 - 3.2 pCl/g (wet) Sr-90 (17) 0.005 0.14 (17/17) 0.02 - 0.50 Gamma (17) 0.5 K-40 - 2.4 (17/17) 1.0 - 3.7 Others - < LLD LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD). (a) May include Ru-106, Ru-103, Be-7. (b) One outfier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample). (f) Fraction of detectable measurements at specified location. 3-20
E Duqu:cna Light C mp:ny l 1998 Annu 1 Radi:l:gicci Envir:nm:ntal R: port l Table 3-4 Typical Detection Limits for Gamma Spectroscopy Detection oy High Resolution Germanium Milk Air "
- Sediment Nuclide Water Particulates and Soil
{ C /kg ) (pC /g wet) (pCilliter) (pCl) (pCilg wet) l 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 I Co-60 5 2 20 0.02 0.02 Zn-65 10 5 40 0.04 0.04 i 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
Duquisna Light C:mpany *
- 1998 Annual Radielegicci EnvircnmIntal R; port 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 radiciodine 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 radioiodine sampling. Samples are collected for analysis on a weekly basis. The charcoal is used in the weekly analysis of airbome 1-131. The filters are analyzed each week for gross beta, then composited by station for quarterly analysis by gamma spectrometry. In order to reduce interference from natural radon and thoron radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.
- b. Procedures Gross beta analysis is performed by placing the filter paper from the weekly air sample in a 2" 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. i i Radiciodine (1-131) analysis is performed by a gamma scan of the charcoalin a weekly charcoal cartridge. The activity is referenced to the mid-collection time. i 3 22
Duquisn3 Light C:mp ny 1 l - + 1998 Annu 1 Rtdiclogicri Environmsntil Report Figure 3-1 Air Sampling Stations F . f ta , y ( artington j \/
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"* ' Sector 8'"
Location Sector Location No. (rniles) (miles) 13 11 14 Meyef's Farrn M 32 15 0.8 Midland (S.S.) 27 7 6.1 Brunton's Farm E 46.1 3 2.3 Industry Rt. 58 - Garage 28 1 8.6 Sherman's Farm 47 14 4.9 East Liverpool, Oh. . Water Treatinent Plant 29B 3 8.0 Beaver Valley Geriatric Center .. 48 to 16.3 Werton, W.Va. - Weirton Water Tower, Collier Way 30 4 05 Shopingport (S.S.) 51 5 8.0 Aliquippa (S.S.) 3GA 4 0.5 Shppingport (S.S.) ;[ff,;i L J l r' . L.iff.C 3-23
DuquIsna Light Company
~
1998 Annusi Radicingical Envircnmtntal Rrport . l
- 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 29,38, 44, and 46 indicated a weekly average that was higher than the other week's. - 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, W.Va., also had similar elevated readings during these four 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). I Also, all air particulate samples are required to be counted by gamma spectroscopy l if any gross beta result is greater than ten times the yearly control location average l
'(10 x 0.0162 pCi/m = 0.162 pCi/m 3). For these four weeks, none of the samples exceeded 0.031 pCl/m and individual samples were not required to be counted for gamma spectroscopy because their gross beta results were not high enough to -
, meet the gamma 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 ten (10) of the forty (40) monthly samples. No other radionuclides were detected. Results are listed in the summary Table 3-2. Based on the analytical results, the operation of Beaver Valley Power Station did ! not contribute any measurable increase in air particulate radioactivity during 1998.
- b. Radioiodine A total of five hundred twenty (520) weekly charcoal filter samples were analyzed for 1-131. No detectable concentrations were present at any locations.
Based on analytical results, the operation of Beaver Valley Power Station did not j contribute any measurable increase in airborne radiciodine during 1998. s i
)
3-24 Y 5-
Duqu;cns Light Ccmpany 1998 Annual Radici:gic"_I Environmtntal R; port
- c. D;vittions from r:quir:d si:mpling/en*Jysis schedule ODCM required sites:
The following sites had a power loss during week of 6/29/98 to 7/6/98 caused by a severe storm on 6/30/98. Below are the sites and down time.
. Site 13, Meyer's Farm -
31.3 hours
. Site 30, Shippingport (S.S.) -
27.9 hours Non-ODCM required sites: Site 27, Brunton's Farm air sampling station was inoperable from 3/26/981634 to 3/30/981606 due to power switch failure. The defective switch was replaced with upgraded switch and retumed to service. The following sites all had a power loss during week of 6/29/98 to 7/6/98 caused by a severe storm on 6/30/98. Below are the sites and down times.
. Site 27, Brunton Farm -
60.5 hours l
. Site 30A, Shippingport (S.S.) QC -
27.9 hours
. Site 51, Aliculppa (S.S.) -
7.6 hours l l l 4 3-25
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Duquisna Light C:mpany 1998 Annu 1 Radi: logical Envir:nmsntal R; port C. Menitsring cf Sedim:nts and Soils (Soil Monitoring is required every 3 years and was not required in 1998)
- 1. Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt. Soil samples may vary from ;
sand and sitt to a heavy clay with variable amounts of organic material. I
- 2. Sampling Program and Analytical Techniques
- a. Program River bottom sediments were collected semi-annually above the Montgomery Dam, i in the vicinities of the Beaver Valley discharge and above the New Cumberland ;
Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling l locations are also listed in Table 3-1 and are shown in Figure 2-3. Soil samples were not required in 1998. Next year of sampling will be 2000. 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 1
3-27
1 Duqui:sna Light C mp:ny , , { 1998 Annutl Radisingical Envir nm:ntal R port l Figure 3-3 Environmental Monitoring Locations - Shoreline Sediments and Soil h rs b
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. y SOfL SAMPLING LOCATIONS Sector tame 8 ",' Dt e N Location Sector Location N
! 13 11 1.4 Meyer's Farm M 32 15 08 Midland (S.S.) 22 8 0.3 South of BVPS Transmission . 46 3 2.5 Industry, Mdway Dr. l Line j 27 7 8.1 Brunton's Farm 47 14 4.9 East Liverpool, Oh. - Water j , Treatment Plant 1 29A 3 8.3 Nicots Farm . 48A 10 15.6 Werton, W.Va. . Weirton Water j ' Tower, E. Belleview Dr. 30 4 0.5 Shippingpoet (S S.) M 51 5 8.0 Aliquippa (S.S .) , SEDIMENT SAMPLING LOCATIONS . Distame 3"' Distance l
'No" ' . Sector (miles)
Location No. Sector (mi'es) l Location 2A 13 0.2 BVPS Outfan Discharge l UpstreamSdeof New 50 l 12 l 11.8 ( l l Cumberland Dam l l l 3-28 l
E .. Duquasna Light Ccmprny 1998 Annuil Radicingical EnvironmIntil R; port
'3. Results and Conclusions l o
A summary of sediment analysis is presented in Table 3-2. , 1
= 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 three samples. Small amounts of Cs-137 from previous nuclear -
L weapons tests were detected in all of the river sediment samples, including two i upstream above Montgomery Dam, which is unaffected by plant effluents. Small - l amounts of Co-60 were detected in the Beaver Valley Power Station discharge area and are attributable to station releases. The activity detected in the station discharge area is consistent with station data of authorized radioactive discharges which were within limits permitted by the NRC license.
- i l The positive results detected are attributable to authorized releases from the l Beaver Valley Power Station and are characteristic of the effluent. These results l confirm that the station assessments, prior to authorizing radioactive discharges, l are adequate and that the environmental monitoring program is sufficiently ;
sensitive. l l k 3 29 l:
wm ,- Duqu:sna Light Comprny . . 1998 Annual Radiolegicil Environmsntil R: port D. Monitoring of Feederops and Food Products
'1, . Characterization of Farm Products According to the latest data from the 1996-1997 Statistical Summary and Pennsylvania Department of Agriculture Annual Report, there were approximately 565 farms in Beaver County. The total value from the sale of agricultural crops and livestock was
$16,677,000. The principal source of revenue was in dairy products which was estimated at $6,828,000. Revenues from other farm products were estimated as follows:
Field Crops $2,264,000 Fruits $281,000 Horticulture and Mushrooms S3,886,000 Meat and Animal Products $2,868,000 Vegetables and Potatoes $433,000 Poultry Products $117,000 The totalland in Beaver County is 279,020 acres. Approximately 147,900 acres are forested land and 62,000 acres are pasture and crop land.
- 2. Sampling Program and Analytical Techniques
- a. Program Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 3-4. Each sample is analyzed by gamma spectrometry.
Food products (vegetables) were collected at garden locations during the summer of 1998. Leafy vegetables, i.e., cabbage and lettuce, were obtained from Shippingport, Georgetown, and Industry, PA, and Weirton, W.Va. All samples were analyzed for gamma emitters by gamma spectroscopy. Samples were also analyzed by radiochemical analysis for 1-131. 1 l 4 3-30
Duqu:sn3 Light Company 1998 Annual Radielegict.1 Envir:nmsntal R: port Figure 3-4 Environmental Monitoring Program - Feederop and Food Product Locations Uw A -- e j
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.__2N 3 Sample Type Site No. Location N
Food 10 Shippingport Food 15 Georgetown Food 46 Industry Food 44 Weirton, W.Va. Feed 25 Searight's Dairy 3-31
Duqu;sna Light Ccmpany , , 1998 Annu:1 Radiol:gical Envircnmsnt:1 R port i b Procedures Gamma emitters in feed are determined by scanning a dried, homogenized sample with the gamma spectroscopy system. A high resolution germr.nium detector is utilized with this system. Food samples are loaded into tarred 300 or 150 mi plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters. Radiciodine (1-131) in food crops is determined by radiochemistry. Stable lodide carrier is first added to a chopped sample which is thsn leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle fumace. The melt is dissolved in water, filtered and treated with sodium hypochlorite. The 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 four (4) samples. Be-7 was detected in eight (8) samples.
- b. Food A total of five (5) samples were analyzed for 1-131. No detectable concentrations were present.
A total of six (6) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was present in all samples. Naturally occurring Be-7 was found in one (1) sample. No other nuclides were identified.
- c. The data from food and feed analyses were ',onsistent with previous data. Based on the analytical results, the operation of the Beaver Valley Power Station did not contribute any measurable increase in rr.dioactivity in the foods and feeds in the vicinity of the site.
3-32 _ _o
Duqussna Light Ccmpany 1998 Annut! Radislogical Environmsntal Rrpert 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 radioiodine content, calculated as - iodine-131, gamma emitters, and strontuim-89 and strontuim-90. 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. I
- 2. Sampling Program and Analytical Techniques -j l
- a. Program
{ l Milk was collected from these (2) reference dairy farms (Searight's and Brunton's) within a 10-mile radius of the site and fro-rr one (1) controllocation (Windsheimer's) outside of the 10-mile radius. Additional Gairies, which represent the highest potential milk pathway for radioiodine based on milch animal surveys and meteorological data, were selected and sampled. These dairies are subject to change based upon availability of milk or when more recent data (milch animal census) indicate other locations are more appropriate. The location of each is shown in Figure 3-5 and described below. Number of Direction and Distance from Collection i Site Dairy Milch Animals Midpoint of Unit 1 Reactor Period 25 ' Searight 54 Cows 2.1 miles SSW Jan. - Dec. 27 Brunton P3 Cows 6.1 miles SE Jan. - Dec. 69* Collins 4 Goats 3.4 miles SE Jul. - Dec. 96 Windsheimer 53 Cows 10.4 miles SSW Jan. - Dec. 103* Halstead 60 Cows - 5.2 miles SSW July 109* Soissen 24 Cows 3.7 miles WSW Jan. - Jun" 105* Ambrose 28 Cows 3.8 miles WSW Jan. - Dec. 106* Conkle 46 Cows 3.7 miles WSW Jan. - Dec.
- Highest potential pathway dairies
** Ceased dairy operations in July ,
The sample from Searight Dairy is collected and analyzed weekly for radiolodine using a procedure with a high sensitivity. Samples from each of the other 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, Sr-90, gamma emitters including Cs-137 (by high resolution germanium gamma . spectroscopy)' and 1-131 (high sensitivity analysis). l I I i 3 Duquasna Light C mpany
- 1998 Annual Rrdiological Environm::ntal Report Figure 3-5 Environmental Monitoring Locations - Milk
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- N Sector .O Location Sector , ","y Location 25 10 2.1 Searight's Farm W 103* 10 5.2 Maistead Fann 27 7 6.1 Brunton's Farm M 10$* 12 3.8 Ambrose Farm 69* 7 3.4 Colhns W 106* 12 3.7 Conkle Farm 96 10 10.4 Windsheimers Farm W 109* 12 3.7 Somson Farm
- Deiries selected based on highest depositen factors.
3-34
Duqunsna Ll0ht Ccmp:ny 1998 Annuil Ridislogicil Environmsntal RIpert
- b. Procedure Radiciodine (1-131) analysis in milk was performed using chemically prepared samples 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 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 material in a chromatographic column. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for the ingrowth of Y-90. Yttrium is then precipitated as hydroxide,is dissolved and re-precipitated as oxalate. The yttrium oxalate_ is mounted on a nylon planchet and is counted in a low-level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCOs from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Chemical yields of strontium and yttrium are determined pravimetrically.
- 3. Results and Conclusions A summary of data is presented in Table 3-2.
A total of one hundred fifty-two (152) samples were analyzed for 1-131_ during 1998. All 1-131 activities in milk were below the minimum detectable level. A total of one hundre i twenty (120) samples were analyzed for Sr-89 and Sr-90. No Sr-89 was detectei . Sr-90 levels attributable to previous nuclear weapons tests were detected in one hundred nineteen (119) of the 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 all 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, 3-35
Duqu=ne Light Campany 1998 Annual Radi: logical Envirsnm:ntal Rrpert 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.
The principal geologic features of the region are nearly flat-laying sedimentary j beds of the Pennsylvania Age. Beds of limestone altemate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial depcsits partially cover the older sedimentary deposits in the northwest. Most of the j region is underlain by shale, sandstone, and some coal beds of the Conemaugh ' Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams. l l Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 pR/hr. Results for 1998 indicated that background radiation continued in this range. l 1
- 2. Locations and Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).
In 1998 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, (CaSOgDy)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 { Laboratory, the field location, and the Central Laboratory was corrected by ] transit controls maintained in lead shields at both the Central Laboratory and the field office. All dosimeters were exposed in the field in a special environmental holder. The dosimetry system was calibrated by reading calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation I field. 1 1 I 3-36 l l
Duqu;enn Light Ccmpiny 1998 Annurol Radiclagicci Envircnm:ntal R: port
- 3. Results and Conclusions Data obtained with the contractor TLD (CaSOgDy in Teflon) during 1998 are 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 0.172 mR/ day in 1998. As in previous years, there was some variation among locations and seasons as would be expected. In 1998, ionizing radiation dose determinations from TLDs averaged approximately 62.9 mR for the year. This is comparable to previous years. There was no evidence of anomalies that could be attributed to the operation of the Beaver Valley Power Station. The TLDs confirm that changes from natural radiation levels, if any, are negligible. I l i i I 1 l i l 3-37 I . 1 ! < )
Duquesnm Light Company 1998 Annual R;diologicil Environmental R: port Figure 3-6 TLD Locations j Tii~ { '
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1 Duqunn3 Light Company 1998 Annual Radiological Environm:ntal R': port Figure 3-6 (Continued) TLD Locations SOUTHEAST 8N' Distance Distance No. Sector Location b 8N' I Sector Location l (miles) n No. ) (miles) I 27 7 6.1 Brunton's Farm E 78 l 7 2.7 Raccoon Municipal Bldg 45.1 6 1.9 Raccoon Twp., Kennedy's 79 8 4.4 Rt.151 and Pross Ln. Corners 51 5 8.0 { 'quippa (S.S.) Fi 80 l 9 8.2 Raccoon Park 59 6 1.0 236 Green Hill Rd. F 82 l 9 6.9 Hanover Municipal Building 76 6 3.8 Raccoon Elementary 94 8 2.2 McCleary Road & Pole Cat School Hollow Rd. Ga de R d) ; NORTHWEST l Site Distance 8d' Distance Sector Location Sector Location No. (miks) No. (miles) l 15 14 3.7 Georgetown Post Office -q 87 14 7.0 Calcutta, Oh. - Calcutta l 4 Smiths Ferry Rd. & Valley Dr. 32 15 0.8 Midland (S S.) 88 15 2.8 Midland Heights - 110 Summit Rd. 47 14 4.9 E. Liverpool, Oh. Water 89 15 4.8 Ohioville,488 Smith Ferry Treatment Plant Rd. 60 13 2.5 444 Hill Rd. 90 16 5.2 Opposite Fairview School 86 13 6.2 E. Liverpool. Oh. - 1090 --- 93 16 1.1 Midland Sunrise Hills Ohio Ave. l NORTHEAST Sector D tance Location 8N Sector D tance Location
, N ,
10 3 1.0 Shippingport Boro 70 1 3.4 North of Westem Beaver School-Engle Rd. 28 1 8.6 Sherman's Farm .: 71 2 6.0 Brighton Twp., First Westem Bank 29B 3 8.0 Beaver Valley Gerlatric l 72 3 3.3 Industry, Logan Park Center 30 4 0.5 Shippingport (S.S.) 73 4 2.5 618 Squirrel Run Rd. 45 5 2.2 Rt.18 & Anderson St. 74 4 7.0 CCBC,137 Poplar Ave. 46 3 2.5 Industry Midway Dr. M 75 5 4.1 117 Holt Road 46.1 3 2.3 Industry, Rt. 68 & Garage ( 91 2 3.9 Pine Grove Road & Doyle Road SOUTHWEST Site Sector Distance Location 8N' Sector Distance Location No. (miles) : l No. (miles) 13 11 1.4 Meyer's Farm 4 84 11 8.3 Hancock Co. Parks & ' i i Recreation Complex 14 11 2.5 Hookstown M 85 12 5.7 Routes 8 8 30 Intersection 48 10 16.3 Weirton, W.Va. Weltton L: 92 12 2.8 Georgetown Road (S.S.) Water Tower, Collier Way E. 81 9 3.6 Millcreek United Pres. 95 10 2.3 832 McCleary Road 83 10 4.2 511 f., XM ?. d s E C 5 G E ?.1 D 3-39
. . j Duqu2sn3 Light C:mpany ,
1998 AnnuIl Radi:l:gic 1 Envir2nm:ntal R: port G. Monitoring of Fish
- 1. Description During 1998, fish collected for the radiological monitoring program included carp, bass, sheepshead, and catfish. l l
- 2. Sampling Program and Analytical Techniques 1
- a. Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectroscopy. Fish sampling locations are shown in Figure 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
. A summary of the results of the fish monitoring data is provided in Table 3-2.
A total of nine (9) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was detected in all samples. One of the nine samples indicated trace amounts of Cs-137 near the typical detection sensitivities for gamma spectroscopy. This sample was one of the five samples taken at the BVPS outfall discharge site. 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. 3-40
Duqu2sna Light Company 1998 Annual Radiclogical Environmsntal R: port 1 Figure 3-7 - Environmental Monitoring Program - Fish Sampling Locations
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E Duquszn3 Light Ccmpany 1998 Annual Ridi:: logical Envir nmsntal R:p;rt 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 downstream of the Beaver Valley Power Station site. It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water
, Authority. The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river. The next downstream useris East Liverpool, Ohio which is approximately 6 miles downstream. The heavy.
Industries in Midland, as well as others downstream use river water for cooling purposes. Groundwater occurs in large volumes'in the gravel t'erraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm. In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The average annual precipitation for the area is 36.23 inches based on 1941 to 1970 data collected at the Pittsburgh International Airport. 1 3-42
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Duquigna Light Cnmpany 1998 Annual Radiol:gicti Envir:nmtntil R:psrt ;
- 2. Sampling and Analytical Techniques l a. Surface (Raw River) Water The sampling program of river water includes three (3) sampling points f 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]; I and at J&L Steel's river water intake [ River Mile 36.2]. The automatic sampler takes a 20-40 ml sample every 15 minutes and samples are collected on a weekly basis. The weekly grab sample and automatic water
- sample are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point.
i Tne weekly composite from the automatic river water sampler upstream of i the Montgomery Dam are analyzed for 1-131. l The monthly composites are analyzed for gamma emitters. The quarterly composites are analyzed for H-3. Locations of each sample point are shown in Figure 3-8. l l b. Drinking Water (Public Supplies) , Drinking (treated) water is collected at both Midland (Pa) and East Liverpool (Oh) Water Treating Plants. An automatic sampler at each location collects 20-40 mi every 20 minutes. These intermittent samples are then composited into a weekly sample. The weekly sample from each location is analyzed for 1-131. Monthly composites of the weekly samples are analyzed by gamma spectrometry. Quarterly composites are analyzed for H-3. Locations of each sample point are shown in Figure 3-8. 3-43
Duquisne Light Ccmpany
- 1998 Annu 1 Radirlagicil Envir nmIntal Ripsrt
- c. Groundwater Semi-annual grab samples were collected from three (3) locations (see Figure 3-8) within four (4) miles of the site. These locations are:
One (1) wellin Shippingport, PA One (1) wellin Hookstown, PA One (1) wellin Georgetown, PA i Each ground water sample is analyzed for tritium and by gamma spectroscopy. . I
- d. Precipitation i
Precipitation is collected at Shippingport, Pa., East Liverpool, Oh. and Weirton, W.Va. 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 i shown in Figure 3-8.
- e. Procedures Gamma analysis is performed on water samples by placing one liter of the 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 scintillatiCn counting. Radioiodine (1-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
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3-44 _ _ _____ - -_ - -__________-__________ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - - _ - _ _ _ _ _ _ - _ _ _ _ - - - _ _ _ ~
Duquasna Light Company 1998 Annu-.I Radiolcgical Envir:nm:ntal R: port Figure 3-8 Environmental Monitoring Stations Locations - , Ground, Surface Water, Drinking Water and Precipitation !
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Surface 2.1 14 1.5 Downstream Mediand - Ground 14 11 2.5 Hookstown Surface 5 14 4.9 E. Uverpool. Oh. - Water Ground 15 14 3.7 Georgetown Treatrnent Plant Surface 49.1 4 5.3 Upstream NOVA Precipitation 30 4 0.5 Shippingport (S.S.) Chernicals Drinking 4 15 1.3 Msdiand - Water Precipitation 47 14 4.9 E, Uverpool, Oh., . Treatment Plant Water Treattnent Plant Drinking 5 14 4.9 E. Uverpool, Oh. - Water Precipitation 48 10 16.3 Werton, W.Va. - Treatrnent Plant Weirton Water Tower, Ground 3 0.8 ,Shippingpeut Boro .h . . ,. l3 . .~c' '.?: , 3-45
' Duquisn2 Light Company
- 1998 Annual Rrdi:Ingical Envir:nmantti R: port
- 3.L Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, ground and precipitation) are provided by sample type and analysis in Table 3 2. These are discussed below.
- a. Surface Water A total of fourteen (14) samples were analyzed quarterly for H-3. Three of
< the fourteen were positive for H-3, ranging from 140 to 160 pCi/ liter (the normal LLD is 200 pCl/ liter). Two were located upstream of the plant
- (NOVA Chemical) and one was located 4.9 miles downstream at -
East Liverpool, Ohio. 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 seventeen (17) of the weekly samples. All the positive results but one were below the required LLD. The one above the required LLD was below reportable levels. These positive results were detected at a control location 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. Two of the samples were positive, both indicating 130 pCi/ liter (the normal LLD is 200 pCi/ liter).
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 highly sensitive technique. Positive levels of I-131 were measured in forty-four (44) of the weekly samples. All the positive results except four were below the required LLD. The four 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. Also, twenty of the forty-four positive results were detected during the 1st; 2nd, and 3rd quarter even though no 1-131 was released because of extended outage and the short half-life (8.05 days) of I-131. I 3-46 I _ - - - . )
Duqunna Light Ccmp:ny 1998 Annual Radicicgical Envircnm:ntal RIport
- c. Groundwater l
A total of sixj6) samples were each analyzed for H-3 and by gamma spectrometry. No gamma-emitting radionuclides were detected. One of the I six samples indicated a positive H-3 value of 140 pCi/ liter. This result was ! below the calculated Lower Limit of Detection (LLD) for water samples ) (200 pCi/ liter) but statistically indicated a ' positive' result. It should be noted j that the required LLD for H-3 in water is 2000 pCi/ liter, j l
- d. Precipitation 4 A total of twelve (12) samples were analyzed for H-3 and by gamma spectrometry. Two (2) positive tritium results detected were within normal levels. Naturally occurring Be-7 was detected in five (5) samples. Naturally !
. occurring K-40 was detected in one (1) sample. No other gamma 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.
- i Further, the actual detected concentration (averaged over the total batch i discharge period during the year) attributable to Beaver Valley Power )
Station; was only 0.144% of the limits set forth in Appendix C of the ODCM for water discharged to the Ohio River. The Ohio River further reduced this j concentration by a factor of approximately 600 prior to its potential use, j i l i f 3-47
, Duquicna Light Campany
- 1998 Annual Radi:ligical Envir:nm2ntal R! port f.. Deviations from ODCM required' sampling schedule
. Site 49.1, Upstream Nova Chemical surface water was found with the delivery tube outside of collection vessel on 1/8/98. Delivery tube was inserted in collection vessel and sampling resumed. Approximately 50 hours were lost.--[Ref: Condition Report #990909]
Site 4, Midland Water Treatment Plant drinking water was found with
' delivery tube outside of collection vessel on 2/26/98 at 0800. Delivery tube was inserted in collection vessel and sampling resumed. Total of 44.8 hours were lost. - (Ref: Condition Report #990909]
Site 2.1, Midland - J&L surface water was found with delivery tube outside i of collection vessel on 3/10/98. Entire week's sample was lost.= Sampling station was enclosed in a lockable cabinet. No further problems occurred this year. [Ref: Condition Report #990909] Site 4, Midland Water Treatment Plant drinking water was found with delivery tube outside of collection vessel on 7/17/98. Delivery tube was inserted in collection vessel and sampling resumed. Total of 72.9 hours werelost. [Ref: Condition Report #990909] ; Site 49.1, Upstream Nova Chemical surface water lost power for 65.9 hours
' during week of 11/27/98 to 12/1/98. Discussed with NOVA Chemical personnel. Nova Chemical was performing maint. nance in area and did not know that sampler would be effected. No further incidents occurred this year.
3-48
-.a
7
. Duqu:sna. Light Ccmpany 1998 Annual Ridiclegic:l Envircnmantal R: port l
. l. 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 l ARERAS/ MIDAS computer system equivalent to NRC computer codes - XOODOQ2, GASPAR, and LADTAP. Dose factors listed in the ODCM were
. used to calculate doses to maximum individuals from radioactive noble gases in dischargo plumes. Beaver Valley effluent data, based on sample analysis in accordance with Tables 2-1 and 2-3, were used as the radionuclide activity input.
. Radionuclides contained in the Annual Radioactive Effluent Release Report (noble gases, particulates, radioiodines 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. l The airborne pathways evaluated were beta and gamma doses from noble gas !
. plumes inhalation, the " cow-milk-child", and other ingestion pathways. '
All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using intrinsic germanium detectors. Each batch is diluted by cooling tower blowdown ' water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0). The actual data from these analyses are tabulated and used as the radionuclide activity input term in code equivalent to LADTAP. A hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is svailable, 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. 3-49
Duqusana Light Ccmp:ny 1998 Annual Radi:Icgical Enviranm:ntil Rtport
- 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 real individual located at Midland since this is the nearest location where significant exposure of a member of the general j population could potentially occur. A breakdown of doses by pathway and j organ !s provided in Table 3-5 for the likely most exposed individual, j 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 i 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, l
- Appendix 1. Therefore, the annual site limits listed in Table 3-6 are specific to this report only, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2).
- c. Population Dose The 1998 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was:
Organ Man-Millirems Largest Isotope Contributor Total Body 176 H-3' 167 Man-Millirems 1 Thyroid 175 H-3 167 Man-Millirems l-1 1 ! i i l 1, 3-50
Duqusans Light Campsny. 1998 Annual R diclogical Envircnmnntal Rrport l l 3. Results.of Calculated Radiation Dose to Man - Atmospheric Releases l The results of calculated radiation dose to the maximum exposed individuals for BVPS airborne radioactive effluents during 1998 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. The results are compared to the'BVPS annual 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 annual limits listed in Tabie 3-7 are i
specific to this report only, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2). The results show
. compliance with the BVPS annual limits.
NOTE: During the performance of a QA Audit in 1998, discovery was made regarding inadequate calibration frequency for wind speed and wind direction meteorological sensors. This violation of Technical Specification 3.3.3.4, Table 4.3-5 was previously reported in Beaver Valley Power Station, Unit No.1 Licensee Event Report No. LER 98-029-00 dated January 18,1999. As stated in the LER, there is no reason to suspect that the meteorological instruments were indicating inaccurately, just that the methodology used to perform their calibrations was not fully adequate to ensure the calibration frequency was met. Thus, these instruments remained functional and provided continuous data on the local meteorological conditions. There are also redundant sensors which would help indicate any potential anomaly, if one was present, even though these instrument's calibration periodicity may have been exceeded. A daily channel check is routinely performed on the primary and redundant sensors. The doses calculated from the meteorological data (see Table 3-7) are considered to be accurate. Further description of this situation and associated Corrective Actions are detailed in NRC Inspection Report l 50-334/98-11, 50-412/98-11 and the Notice of Violation. l 3-51
DuquIsne Light C:mpiny 1998 Annual Radiolegical Envirrnmsntti Rrptrt Table 3-5 Radiation Dose to an Individual (a), mremlyr - Liquid Releases (b) Pathway Skin Highest Organ Thyroid Bone Whole Body Fish N/A 0.00187 0.00007 0.00136 0.00136 ConsumptJon (Teen) (Liver) (Adult) (Child) (Adult) Drinking N/A 0.00251 0.00251 0.00007 0.00235 Water (Infant) (Thyroid) (Infant) (Child) (Child) Shoreline 0.00004 0.00004 0.00003 0.00003 0.00003 Activities (Teen) (Teen) (Skin) (Teen) (Teen) (Teen) i mrem 0.00004 0.00404 0.00254 0.00144 0.00311 H hest (Teen) (hild) (Liver) (Child) (Child) (Adult) 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) Totalliquid 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 3-52
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Duqu ena Light Ccmpany 1998 Annuil Rr.ditingic l Envir:nm:ntal R: port { I Table 3 6 l Results of Calculated Radiation Dose to Man - Liquid Releases 1 Individua! BVPS Annual Organ Percent of Exposure (a) Limits (b) ' Annual Limit mrem mrem TOTAL BODY 4 Adult 0.0031 6.0 0.05 Teen 0.0021 6.0 0.04 0.0027
)
Child 6.0 0.05 l Infant 0.0023 6.0 0.04 ANY ORGAN Adult 0.0036 (Liver) 20.0 0.02 Teen 0.0032 (Liver) 20.0 0.02 Child 0.0040 (Liver) 20.0 0.02 , infant 0.0025 (Thyroid) 20.0 0.01 (a) Likely most exposed member of general population - located at Midland drinking water intake. (b) Limits are based on 3 mrem / year total body per unit and 10 mrem / year for any organ per unit. I 3-53 l
v-
. . i Duqu:cna Light C:mp ny 1998 Annual Radini:gical Envir:nm2ntal 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 (approximately 4 million people), from the operation of
- Beaver Valley Power Station - Unit 1 and 2, is less than 0.0001% of the annual '
background dose. The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public. ,
)
3-54
i Duquasna Light C:mp;ny i 1998 Annuil R di::legicri EnvironmIntal R:p:rt l l Table 3-7 3 l l Results of Calculated Radiation i Dose to Man - Atmospheric Releases MAXIMUM BVPS EXPOSURE ANNUAL PERCENT OF ORGAN INDIVIDUAL LIMIT (a) mrem mrem LIMIT TOTAL BODY 0.233 30 0.78 SKIN 0.235 30 0.78 LUNG 0.236 30 0.79 THYROID 0.233 30 0.78 (a) Limit is based on 15 mrem per unit. l l 50-MILE ; I ORGAN POPULATION DOSE man-rem TOTAL BODY 0.514 SKIN 0.021 LUNG 0.516 THYROID 0.514 3-55
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Duquuna Light C:mpany 1998 Annull Ridinlogic:l Envir nmnntil R: port SECTION 4 - LAND USE CENSUS A land use census was conducted July 27 through July 31,1998 to comply with BV-1 and BV-2 Technical Specification 6.8.6b ltem 2 and the ODCM Appendix C CONTROL 3.12.2. The census results are summarized in Table 4-1. The locations of the milch animals are shown on Figure 4-1. 4 4-1
Duquisn3 Light C:mpany , , 1998 Annual Radislegical EnvirsnmIntal RHport Table 4-1 Location of Nearest Residence, Garden, and Milch Animal SECTOR RESIDENCE (miles) GARDEN (miles) (U MILCH ANIMALS (miles)<23 N 1.55 2.01 None NNE 1.59 1.61 None NE 0.42 2.65 None ENE 0.56 0.95 None E 0.40- 1.14 2.62 ESE 0.87 1.60 4.51 SE 1.10 2.44 2.31 SSE 1.10 2.16 3.14 S 1.40 2.31 3.83 SSW 0.80 1,53 1.93 SW 1.60 1.72 2.16 WSW 1.46 2.39 3.41 W 2.27 2.27 None WNW 2.77 2.77 4.83 NW 0.91 0.92 None NNW 0.91 1.17 None (1) Gardens greater than 500 square feet producing fresh leafy vegetables ! (2) Within five miles 1 l I i 4-2
- Duqusens Light Company l 1998 Annu11 Radiological Environmental Rtport l
l Figure 4-1 i Milch Animal Census
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Duquisnn Light Company 1998 Annual R diclegical Environmtntal Rsport SECTION 5 - QUALITY CONTROL PROGRAM / lNTERLABORATORY COMPARISON PROGRAM A. Quailty Control Program
-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 j the Interleboratory Comparison Program section). This testing provides a means to ensure j indspendent checks are performed on the precision and accuracy of 1:.e measurements of 1 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 spilt and spike samples between the Contractor Lab and the QC Lab / Independent Lab. These comparisons are performed by dividing the comparison standard (the QC Lab or , Independent Lab result) by its associated uncertainty to obtain Le resolution. The i comparison 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 valid comparison cannot be made. Values identified with an '*'in Tables 5-1 through 5-10 do not meet , acceptance criteria. i Resolution Ratio
<4 ' -- l 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, 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, and feed / food crop split samples are provided in Table 5-3 and Table 5-4. Good overall agreement was ob; .J ied with only feed having a non-comparison. Naturally occuring beryllium was the orny non-comparison. As noted above, some variation may be expected at these low levels of radioactivity. 5-1
Duqunna Light Ccmptny *
- 1998 Annual R dicl:gical Enviranmtntal RIport l
- 2. Duplicate Sample Program (DLC Contractor Laboratory - DLC QC Laboratory) j 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 Table 5-5 and Table 5-6. There was good agreement of both the air particulate (beta) and charcoal cartridge filters. Quarterly composites of the air particulate filters (gamma) showed good comparisons except for one Be-7 result in the fourth quarter. Thirteen (13) duplicate (co-located) TLDs from the Contractor Laboratory and OC Laboratory are replaced quarterly, and the results are compared. The average of the Contractor Laboratory and the average of the QC Laboratory agree within i 3% of the i 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.
- 3. Blind Split Program (DLC Contractor) i The blind split program consisted of unscheduled unannounced split samples of water, sediment and milk from normal environmental locations. The ' normal' and blind split samples were sent to the DLC Contractor along with other samples of the same media.
The lab had no knowledge of the location of the blind split sample or that it was even a split. A summary of the results are provided on Table 5-8. The sediment and milk samples showed good agreement. Overall good agreement was seen with the water 1-131 analysis. One of the three 1-131 comparison samples indicated a positive and a "less than". The positive value was near the lower level of detection and some variation may be expected at these low levels of radioactivity, l I l l l S-2
Duqussna Light Company 1998 Annual Radioingical Environmnntal R; pert B. Interlaboratory Comparison Program Participation in an Interlaboratory Comparison Program is required by BV-1 and BV-2 : Technical Specification 6.8.6b, item 3. In 1998 this requirement was fulfilled by the ! Contractor Lab (Teledyne Brown Engineering Environmental Services - Westwood N.J.) analyzing high quality (NIST traceable) spiked samples supplied by two Duquesne Light !
. Company contracted vendors. In addition, the Contractor Lab participated in the US EPA Interlaboratory Comparison Program.
- 1. Contractor Lab The high quality (NIST traceable) spiked samples include air particulate and charcoal filters (prepared by the DLC QC Laboratory) and water and milk (prepared by the 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.
. Comparison of results of the spiked water and milk samples showed good results with no non-comparisons in 1998. These results are presented in Tables 5-9 '
through 5-10.
. Comparison of results of the spiked air particulate filters and charcoal cartridge filters showed good results Both results are reported in Table 5-11. '
The US EPA Interlaboratory Comparison Program results for 1998 are presented in Table 5-12. 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 'TI'. This program indicated that the Contractor Laboratory results were in agreement with the EPA except as noted in the footnotes. The footnotes on the tables discuss investigation of problems encountered and the steps taken to prevent reoccurrence. The Contractor Laboratory 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 1997 that were not available for publication for the 1997 report are presented in Table 5-13. The available results for 1998 are presented in Table 5-14. This program indicated that the QC Laboratory results were in agreement with the EPA ,
except as noted in the remarks within the table. The remarks within Tables 513 and 5-14 discuss investigation of problems encountered in a few cases and the steps taken to prevent reoccurrence. The QC Laboratory had satisfactea performance within the EPA Interlaboratory Cross Check Program. C. Conclusions Based on all available Quality Control data and Interlaboratory Comparison data the Environmental Monitoring Program for 1998 is acceptable with respect to both accuracy and measurement. 5-3
7_ Duqu;2na Light CampIny '
- 1998 Annu 1 Ridisl:gical Envir:nmIntal Rip:rt Table 5-1 Quality Control Data Contractor / Quality Control Laboratory Comparison Split Surface Water Samples Media Analysis Sampling DLC - Contractor DLC - QC Units Period Lab (1) Lab (1)
Surface January <3 < 4.2 pCi/l Water Co-60 April <3 < 1.8 pCi/l (Monthly July <4 < 3.5 pCi/l Composite) October <4 < 5.0 pCi/l Surface January <3 < 4.5 pCi/l Water Cs-134 April <3 < 2.5 pCi/l (Monthly July <4 < 4.3 pCi/l Composite) October <5 < 5.0 pCi/l Surface January <3 < 3.8 pCill Water Cs-137 April <4 < 4.2 pCill (Monthly July <4 < 5.0 pCi/l Composite) October <5 < 7.7 pCi/l ist Quarter < 100 < 163 pCi/l er Tritium aey 3rd Quarter < 100 < 163 pCi/l g e (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. 5-4
Duquisn3 Light Ccmpany 1998 Annual Ridi:l gical Envircnmsntal R:p rt l Table 5-2 l l Quality Control Data l Contractor / Quality Control Laboratory Comparison Split Drinking Water Samples . I Media Analysis Sampling DLC - Contractor DLC - QC Units Period Lab (1) Lab (1) Drinking February <4 < 2.9 pCill Water Cs-137 May <3 < 4.3 pCi/l l l (Monthly August <3 < 1.7 pCi/l Composite) November <4 < 3,7 pCi/l I Drinking - February <3 < 2.3 pCi/l . Water Cs-134 May <3 < 2.1 pCi/l (Monthly August <3 < 5.2 pCl/l Composite) November <3 < 3.4 pCi/l I Drinking February <3 < 2.6 pCill Water Co-60 May <3 < 3.5 pCill (Monthly August <3 < 1.8 pCi/l Composite) November <3 < 2.8 pCi/l Drinking 3/10 to 3/17 0.45 i 0.16 < 0.5" pCill Water 1-131 6/9 to 6/16 < 0.27 < 0.5 pCi/l (Weekly 8/11 to 8/18 0.32 i 0.20 < 0.4 pCill Split) 11/10 to 11/1'7 0.41 i 0.19 0.50 0.20 pCi/l 2nd Quarter < 100 < 180 pCi/l ar Tritin
"* 4th Quarter 130i70 < 154 pCill pos te (1) Uncedainties are based on counting statistics and are specified at the 95% confidence l coefficient.
Resolution < 4, see Section SA. l 5-5
Duqu:sro Light C mpany ' ' 1998 Annual R di:l:gical Envir:nm:ntal R;p rt l Table 5 3 Quality Control Data Contractor / Quality Control Laboratory Comparison Split Milk Samples Sampling DLC - Contractor DLC - QC Units Media Analysis oeriod Lab (1) Lab (1) Sr-89 < 1.3 < 0.6 pCi/l Sr-90 2.4 i 0.3 2.0 i 0.4 pCi/l Milk l-131 < 0.26 < 0.4 pCi/l (Weekly Split) 3/17/98 Co-60 <3 < 3.0 pCi/l Cs-134 <3 < 6.4 pCi/l Cs-137 <3 < 5.9 pCi/l K-40 1420 i 140 1410 130 pCi/l Co-60 <4 < 2.4 pCi/l Milk l-131 < 0.24 < 0.4 pCi/l i (Weekly Split) 6/16/98 Cs-134 <4 < 2.6 pCi/l Cs-137 <4 < 6.9 pCi/l K-40 1210 i 120 1350 i 180 pCi/l Sr-89 < 0.92 < 0.7 pCill Sr-90 2.6 i 0.2 2.4 i 0.5 pCi/l Milk l-131 < 0.28 < 0.5 pCi/l (Weekly Split) 9/21/98 Co-60 <4 < 6.5 pCi/l Cs-134 <4 < 3.8 pCill Cs-137 <4 < 8.3 pCi/l K-40 1230 120 1340 160 pCi/l Co-60 <3 < 5.5 pCi/l ! Milk l-131 < 0.24 < 0.7 pCi/l ! (Weekly Split) 12/14/98 Cs-134 <4 < 3.5 pCi/l { Cs-137 <4 < 4.5 pCill ) K-40 1310 130 1340 i 120 pCill (1) Uncertainties are based on counting statistics and are at the 95% confidence level. I I 5-6
Duqu:sna Light Ccmpany
-1998 Annual Radigingical Envir:nmsntal Riport )
,- Table 5-4 L-Quality Control Data Contractor / Quality Control Laboratory { Comparison Split Feed, Food and Sediment Samples , DLC - Media Sampling Analysis Contractor DLC - QC Units Period Lab (1) Lab (1) Be-7 *3.96 i 0.40 2.38 i 0.23 pCi/gm (dry) ! K-40 17.0 i 1.7 17.44 i 0.56 pCi/gm (dry) l Feed 9/21/98 Co-60 < 0.04 < 0.021 pCi/gm (dry) l (25) 1-131 < 0.06 < 0.033 pCi/gm (dry) Cs-134 < 0.04 < 0.023 pCilgm (dry) Cs-137 < 0.04 < 0.019 pCi/gm (dry) K-40 2.44 0.24 3.06 0.27 pCl/gm (wet) Co-60 < 0.008 < 0.012 pCi/gm (wet) Food 10/2/98 l-131 < 0.015 < 0.017 pCi/gm (wet) (10) Cs-134 < 0.008 < 0.006 pCl/gm (wet) Cs-137 < 0.008 < 0.010 pCi/gm (wet) Co-58 < 0.04 < 0.03 pCi/gm (dry) l Co-60 0.133 i 0.041 0.140 i 0.015 pCi/gm (dry) Sediment 10/16/98 Cs-134 < 0.05 <0.05 pCi/gm (dry) (2A) Cs-137 0.113 i 0.039 0.100 i 0.015 pCi/gm (dry) Ra-226 1.99 0.66 1.84 i 0.29 pCi/gm (dry) K-40 9.39 i 0.94 9.96 i 0.35 pCl/gm (dry) (1) Uncertainties are based on counting statistics and are specified at the 95% confidence ; coefficient. See Section 5-A. 57
Duqus2n3 Light C mptny
- I 1998 Annual Rrdirlagical Envirrnm ntal RIport j Table 5-5 l Quality Control Data Contractor / Quality Control Laboratory Comparison l Duplicate (Co-located) Air Particulate and Charcoal Filter Samples Air Particulates Air lodine pCl/Cu Meter (Beta) pCl/Cu Meter DLC - Contractor DLC - QC Sample Date DLC - Contractor DLC - QC Sample Date Lab (1) - Lab (1) Lab Lab 12/29-1/5 0.014 1 0.003 0.014 i 0.003 1/5-1/12 < 0.01 < 0.008 1/12-1/19 0.026 i O.004 0.024 i O.003 1/19-1/26 <0.01 < 0.006 1/26 -2/2 0.014 i 0.003- 0.018 1 0.003 2/2 - 2/9 < 0.01 < 0.011 2/9 -2/17 0.019 1 0.003 0.023 i 0.003 2/17 - 2/23 < 0.01 < 0.011 2/23-3/2 0.016 i 0.003 0.019 1 0.003 3/2 - 3/9 < 0.01 <0.015 3/9 -3/16 0.019 i 0.003 0.020 i 0.003 3/16 - 3/23 < 0.01 < 0.004 l
3/23-3/30- 0.017 i 0.003 0.025 1 0.004 3/30-4/6 < 0.01 < 0.009 4/6 -4/13 0.014 i 0.003 0.020 1 0.003 4/13-4/20 < 0.01 < 0.008 4/20 4/27 0.016 1 0.003 0.022 1 0.003 N27 - 5/4 < 0.01 < 0.007 5/4 - 5/11 0.010 1 0.003 0.015 t 0.003 5/11 - 5/18 < 0.01 < 0.008 5/18 -5/26 0.012 1 0.003 0.019 i 0.003 5/26 - 6/1 < 0.01 <0.015 6/1 - 6/8 0.009 i 0.003 0.012 i 0.003 6/8-6/15 <0.01 < 0.032 6/15 - 6/22 0.013 1 0.003 0.014 i 0.003 6/22 - 6/29 < 0.01 < 0.009 6/29-7/6 0.013 i 0.003 0.018 i 0.003 7/6-7/13 < 0.01 < 0.007 7/13 7/20 0.023 1 0.003 0.023 1 0.003 7/20- 7/27 < 0.01 < 0.018 7/27-8/3 0.020 i 0.003 0.020 i 0.C03 8/3-8/10 < 0.01 < 0.005 8/10 - 8n7 0.021 i 0.003 0.029 i 0.004 8/17 - 8/24 < 0.01 < 0.011 8/24 - 8/31 0.019 i 0.003 0.029 i 0.004 8/31 - 9/8 < 0.01 < 0.009 9/7 -9/14 0.023 1 0.004 0.024 i 0.004 9/14 - 9/21 <0.01 < 0.008 9/21 -9/28 0.018 i 0.003 0.026 i 0.004 9/28-10/5 < 0.01 < 0.004 10/5-10/12 0.009 i 0.003 0.016 i 0.003 10/12-10/19 < 0.01 < 0.007 10/19-10/26 0.017 1 0.003 0.026 1 0.003 10/26- 11/2 < 0.01 < 0.013 11/2 -11/9 0.010 i 0.003 0.015 i 0.003 11/9-11/16 < 0.01 < 0.008 11/16-11/23 0.019 i 0.003 0 927 i 0.004 11/23-11/30 < 0.01 < 0.016 11/30-12/7 0.020 i 0.003 0.027 i 0.004 12R - 12/14 < 0.01 <0.004 12/14-12/21 0.016 1 0.003 0.022 1 0.003 12/21-12/28 < 0.01 < 0.007 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. 5-8
Duqu2sna Light Ccmpany I
'1998 Annutl Radiclegical EnvircnmIntal Rrp::rt Table 5-6 Quality Control Data Contractor / Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate Samples (Gamma)(pCi/Cu Meter).
Sample Period Nuclide DLC - Contractor DLC - QC Lab (1) Lab (1) Be-7 0.130 i 0.013 0.069 i 0.012 Co-60 < 0.0003 < 0.0004 1st Quarter Cs-134 < 0.0003 < 0.0004 Composite Cs-137 < 0.0003 < 0.0003 Ba-La-140 < 0.008 < 0.0012 K-40 < 0.005 < 0.024 Be-7 0.143 i 0.014 0.085 i 0.014 Co-60 < 0.0003 < 0.0014 2nd Quarter Cs-134 < 0.0003 < 0.0015 Composite Cs-137 < 0.0003 < 0.0009 Ba-La-140 < 0.008 < 0.0012 K-40 < 0.009 < 0.025 Be-7 0.150 i 0.015 0.107 i 0.013 Co-60 < 0.0003 < 0.0004 3rd Quarter Cs-134 < 0.0003 < 0.0005 Composite Cs-137 < 0.0003 < 0.0007-Ba-La-140 < 0.008 < 0.0015 4 K-40 < 0.005 < 0.030 Be-7 *0.135 0.013 0.065 i 0.015 Co-60 < 0.0002 < 0.0004 4th Quarter Cs-134 < 0.0003 < 0.0008 Composite Cs-137 < 0.0003 < 0.0009 Ba-La-140 < 0.010 < 0.0008 K-40 < 0.005 < 0.0324 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. See Section SA. i 5-9
r Duqu sn3 Light C:mpany '
- 1998 Annuil Rtdiol:gical Envir:nm:ntal R:psrt Table 5 7 Quality Control Data Contractor / Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/ day 1ST QUARTER 2ND QUARTER
~ * ~
- Location No. Co tr ctor Location No. Co tr ctor (CaSO4:Dy)
(CaSO4:Dy) I* 4 Y (CaSO4:Dy) 10 0.180 0.151 10 0.176 0.173 13 0.167. 0.152 13 0.157 0 166
- 14. 0.175 0.153 14 0.156 0.167 15 0.164 0.158 15 0.159 0.170 27 0.171 0.149 27 0.158 0.173 28 0.178 0.156 28 0.168 0.168 29B 0.209 0.189 29B 0.183 0.108 32 0.192 0.178 32 0.194 0.173 45 0.174 0.167 45 0.171 0.138 46 0.162 0.153 46 0.158 0.155 47 0.184 0.177 47 0.184 0.181 48 0.186 0.174 48 0.185 0.184 51 0.184 0.167 51 0.177 0.174 l
I 3RD QUARTER 4TH QUARTER
~ * ~
Location No. Co tr ctor (CaSo4:Dy) Location No. Co tr ctor (CaSO4:Dy) (CaSO4:Dy) (CaSO4:Dy) 10 0.167 0.146 10 0.175 0.158 13 0.153 0.146 13 0.164 0.155 14 0.160 0.153 14 0.167 0.160 15 0.159 0.165 15 0.167 0.168 l 27 0.166 0.145 27 0.169 0.167 l 28 0.175 0.157 28 0.174 0.162 i 298 0.189 0.181 298 0.199 0.188 32 0.172 0.164 32 0.188 0.162 45 0.177 0.168 45 0.177 0.167 46 0.160 0.151 46 0.153 0.144 47 0.192 0.178 47 0.189 0.186 48 0.179 0.164 48 0.183 0.166 51 0.162 0.162 51 0.173 0.166 5 10
Duqu:sna Light Company 1998 Annual Rcdisingicti Envircnm:;ntal R: port Table 5-8 Quality Control Data Contractor Comparison of Blind Split Samples 1 Sampling Contractor Lab Contractor Lab Media . Site A"8IY8 8 Units Period Routine Result
- Split Result
"" 4 1/12 - 1/20 1131 0.49 i 0.19 < 0.2 pCi/ liter ar n
5 1/20 - 1/27 l-131 < 0.29 < 0.26 pCl/ liter ar 49.1 1/27 - 2/3 1-131 < 0.35 < 0.27 pCi/ liter e-Co-58 < 0.06 <0.05 pCl/g (dry) Co-60 0.1210.04 0.08 i 0.04 " pCi/g (dry) Cs-134 ' <0.07 < 0.05 pCl/g (dry) Sediment 2A 4/24/98 Cs-137 0.19 i 0.06 0.19 i 0.04 pCl/g (dry) Ra-226 1.97 i 0.75 2.29 i 0.86" pCl/g (dry) Th-228 1.33 i 0.13 1.35 i 0.14 pCl/g (dry) K-40 13.50 i 1.40 15.00
- 1.50 pCi/g (dry)
Sr-89 < 0.88 < 1.4 pCi/ liter Sr-90 2.2 i 0.2 1.7
- 0.2 pCi/ liter Co-60 <3 <3 pCl/ liter Milk 25 12/15/98 l-131 <0.24 < 0. 4 pCi/ liter Cs-134 <4 <3 pCl/ liter Cs-137 <4 <4 pCl/ liter K-40 1310i130 1420
- 140 pCl/ liter Indicates non-comparison
- Resolution < 4, see Section SA.
5-11
tr DuquIsn2 Light Ccmpany ,
'1998 Annutl Radi: logical Envirsnmsntal RIport i
Table 5-9 Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory Comparison Spiked Water Samples (pCl/l) Sample Type and independent Contractor Sample Date - Sample Analyses Identification No. Lab (1) Lab (1) i l Sr-89 10415 9512 Sr-90 4112 45 i 1 l l-131 9015 89 i 1 Ce-141 58 i 3 65 t 7 i 3/12/98 Water Cr-51 167i8 169 i 34 53-366-- Cs-134 7014 69 i 7 Cs-137 134 i7 146 i 15 ) Mn-54 111 16 129 i 13 Fe-59 79 i4 91i10 l l Zn-65 118 i 6 143i14
]
Co-60 71 14 70i7 3/12/98 H-3 2398 i120 1800 i 200 5 37 St-89 69 i 3 65 i 2 Sr-90 71i4 66i1 1-131 62 i 3 61 i 1 Ce-141 113 i 6 117 i 12 6/11/98 Water Cr-51 150 i 8 102 i 36 53-368 Cs-134 108i5 113 i 11 Cs-137 8014 88i9 Mn-54 121 i6 126i13 Fe-59 52 i 3 62i9 Zn45 139 i7 157 i16 Co-60 164i8 170i17 6/11/98 H-3 6007i300 5100 200 539 (Table 5-9 continued on next page) 5-12
Duqu:Isn3 Light C:mp:ny
.1998 Annual R:diclagical Envircnmi:ntal RIpsrt l
Table 5-9 (Continued) Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory l Comparison Spiked Water Samples (pCl/l) i Sample Type and independent Contractor Sample Date Sample Analyses Identification No. Lab (1) Lab (1) Sr-89 84 i 4 7612 I
' Sr-90 51 i 3 49 i 1 1-131 79i.4 79 i 1 Ce-141 129 i6 128 i13 9/24/98 Water Cr-51 165i8 187 i 30 53-370 Cs-134 73 i 4 73 i 7 Cs-137 119 i 6 127 113 Mn-54 66i3 73 i 7 Fe-59 5513 66 i 9 Zn45 17319 187 19 Co-60 131 i 7 129 i 13 9/24/98 H-3 3530 i177 3500 i 200 5 31 Sr-89 5213 48 i 3 Sr-90 71 4 73 i 1 1-131 64 i 3 60 i 1 1
Ce-141 774i39 788 i 79 12/10/98 Water Cr-51 1015i51 1020 100 53-372 Cs-134 228 i11 235 i 24 Cs-137 - 190 110 209121 Mn-54 147i7 164 t 16 Fe-59 153i8 177 i 18 Zn-65 145 i 7 164 i16 Co40 185i9 193 i 19 12/10/98 [33 H-3 5985 1299 58001200 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficier.t 5 13
Duqurni Light C:mpany , 1998 Annu:1 Ridi:l:gict) Envir nm2ntil R port Table 5-10 Interlaboratory Comparison Program Independent Laboratory / Contractor Laboratory Comparison Spiked Milk Samples (pCl/l) Sample Type and Independent Contractor Sample Date Identification No. Sample Analyses ' Lab (1) Lab (1) Sr-89 53 i 3 46 i2 Sr-90 44 i2 45 i 1 1-131 82 i4 85 i 1 Ce-141 70 i 4 7317 3/12/98 Milk Cr-51 201 i 10 218 1 27 52-286 Cs-134 84 i 4 82 i 8 Cs-137 161 i 8 174 ii7 142i14 Mn-54 133 i 7 Fe-59 95 i 5 106 i 11 Zn-65 142 i7 149 i 15 Co-60 85 i 4 89 i 9 Sr-89 77 i 4 62 i 2 Sr-90 6013 5511 1-131 67 i 3 73 i 1 Ce-141 99 i 5 98 i 10 6/11/98 Milk Cr-51 132 i 7 113 34 52-287 Cs-134 95 i 5 98110 Cs-137 70 i 4 78 i 8 Mn-54 106i5 115 i 12 Fe-59 45 i 2 51 i 9 Zn-65 122 i G 128 i 13 Co40 14317 156 i 16 (Table 5-10 continued on next page) 5-14
Duque:ns Light C:mpany 1998 Annu 1 Radici:gical Environmtntil rip:rt Table 5-10 (Continued) ! Interlaboratory Comparison Program ] Independent Laboratory / Contractor Laboratory Comparison Spiked Milk Samples (pCill) Sample Tyr and independent Contractor Sample Date Sarspie Analyses identificativ, .o. Lab (1) Lab (1) Sr-89 51 i3 4513 i l Sr-90 81 i4 80 i 1 1-131 90 t 5 93 i 1 Ce-141 146 i7 139 114 9/24/98 Milk Cr-51 186 19 200 136 52-288 Cs-134 82 i 4 82 i 8 Cs-137 134 i 7 143 14 Mn-54 74 i 4 78i'8 1 Fe-59 63 t 3 72 i 10 i Zn-65 195 i10 193 i 19 Co-60 148 i 7 145 i 15 Sr-89 68 i 3 57i2 Sr-90 41 2 43 i 1 1-131 71 i4 67 i 1 Ce-141 746 i37 743 i 74 12/10/98 Milk Cr-51 979 i 49 995 i 99 52-289 Cs-134 220 111 217i22 Cs 137 183 i 9 197120 Mn-54 142 i7 155 i 16 Fe-59 148 i 7 165 t 17 Zn-65 140 i 7 152 i 15 Co-60 178 i 9 184 i18 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient 5-15
Duqurna Light C mpany , , 1998 Annu 1 Rrdi:Irgicil Envir:nm:ntal R: port Table 5-11 I interlaboratory Comparison Program j Contractor / Quality Control Laboratory j Comparison Spiked Air Particulate / Charcoal Filters Sample Type and Sample DLC - Contractor DLC - QC Sample Date Units i Identification No. Analyses Lab (1) Lab (1) 3/24/98
^
DQ A -6 Gross Beta 8.44 i 0.31 7.98 i 0.80 pCl/m8 9/18/98
^
Gross Beta 5.63 i 0.31 6.77 i 0.68 pCl/m3 DQ A -7 2/19/s8 l-131 2.40 i 0.24 2.03 i 0.20 pCl/m8 DQ C 7/8/98
^
l-131 0.42
- 0.04 0.57 i 0.06 pCl/m*
DQ C (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient. I i i I l 1 1 4 5-16
Duquesn3 Light C:mpany 1998 Annual Radi:ltgical Environmsntal R: port 4 Table 5-12 Contractor EPA Interlaboratory Comparison Program 1998 l Co e on
, Media Nuclide EPA Results (a) Deviation (c)
Eng neer ng R s I (b) 01/16/98 Water Sr-89 8.0 1 5.0 5.00 i 1.73 -1.04 Sr-90 32.0 t 5.0 31.67 i 0.58 -0.12 01/30/98 Water Gross Alpha 30.S i 7.6 33.00 2.65 0.57 Gross Beta 8.9 i 5.0 5.6010.90 0.59 02/06/98 Water 1-131 104.9 i 10.5 110.00 1 0.00 0.84 02/13/98 Water Ra-226 16.0 i 2.4 14.67 i 0.58 -0.96 Ra-228 33.3 8.3 32.00 i 2.00 -0.27 03/13/98 Water H-3 2155.0 i 348 1833.33 i 57.74 -1.60 Gr-Beta 94.7 i 10.0 102.00 i 6.56 1.26 Sr-89 6.0 i 5.0 4.67 i 1.15 -0.46 Sr-90 18.0 i 5.0 21.67 i 1.15 1.27 Co-60 50.015.0 52.33 i 1.53 0.81 04/21/98 Water Cs-134 22.0 i 5.0 21.00 i 1.00 -0.35 Cs-137 10.0 i 5.0 11.67 i 0.58 0.58 Gr-Alpha 54.4 i 13.6 50.00 i 1,73 -0.56 Ra-226 15.0 i 2.3 15.00 0.00 0.00 Ra-228 9.3 i 2.3 8.50 0.20 -0.60 Co-60 12.0 i 5.0 13.00 i 1.00 0.35 Zn-65 104.0 1 10.0 111.67 2.52 1.33 i 06/05/98 Water Cs-134 31.0 i 5.0 32.33 i 0.58 0.46 Cs 137 35.0 i 5.0 37.67 i 2.08 0.92 Ba-133 40.0 i 5.0 35.00 i 2.65 1.73 ' 06/12/98 Water Ra 226 4.9 i 0.7 4.47 i 0.85 -1.07 Ra-228 2.1 i 0.5 1.93 i 0.21 -0.58 07/17/98 Water Sr-89 21.0 i 5.0 21.0 i 1.00 0.00 Sr-90 7.0 i 5.0 6.33 0.58 -0.23 (Table 5-12 continued on next page) 5-17
. Duquisna Light Osmp:ny , ,
l 1998 Annual R dislogical Envirsnm2ntil R: port ) Table 512 (Continued) i Contractor EPA Interlaboratory Comparison Program 1998 Co e " Media Nuclide EPA Results (a) Deviation (c) a Engineer ng R s I (b) 07/24/98 Water Gr-Alpha 7.2 i 5.0 5.43i0.64 -0.61 Gr-Beta 12.8 i 5.0 14.67 i 2.08 0.65 08/07.98 Water H-3 17996.0 i 1800.0 16000.00 i 0.00 -1.92 ; 09/11/98 Water I-131 6.1 i 2.0 5.93i0.55 -0.14 09/18/98 Water Ra-226 1.7 i 0.3 1.53 i 0.46 -0.96 ! Ra-228 5.7 i 1.4 6.7010.35 1.24 Co-60 38.0 i 5.0 39.67 i 2.52 0.58 Zn-65 131.0 i 13.0 140.67 i 10.97 1.29 11/11/98 Water Cs-134 105.015.0 103.00 i 2.00 -0.69 Cs-137 111.0 i 6.0 115.33 i 1.53 1.25 Ba-133 56.0 i 6.0 46.33 1 2.52 -2.79 (d) (a) EPA Results - Expected laboratory precision (one sigma). Units are pCl/ liter for water. (b) Teledyne Results - Average one sigma. Units are pCl/ liter for water. (c) Normalized deviation from the known, as defined in EPA document EPA-600/4-81004, Feb.1981. (d) An investigation is being c.onducted for the higher than expected deviation; results will be included in next year's report. 5-18 l
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Duqu:;sn3 Light Ccmpany , , 1998 Annu11 RLdiolzgical Envir:nmsntal R! port Table 5-13 i QC Lab - EPA Interlaboratory Comparison Program 1997 U. - svironmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Brown Enguering Environmental Services, Midwest Laboratory results'. q j Concentrationin pCi/L l Lab Sample Da te EPA Result' Control TBEESML Results Code Type Collected Analysis ' 1s, N=1 Limits 2 Siena' STW-803 Water Sep,1997 Ra .228 8.012.0 4.5 - 11.5 7.0i 0.1:0.7 STW-803 Water Sep,1997 Uranium 5.l i 3.0 0.0 10.3 5.010.1;0.5 STW-812 Water Oct,1997 Gr. Alpha 49.9 i 12.5 35.4 - 64.4 61.8 i 6.3;9.8 STW-812 Water Oct,1997 Ra-226 5.0i 0.8 4.1 - 5.9 4.510.2;0.5 1 STW-812 Water Oct,1997 Ra-228 5.011.3 3.5 - 6.5 3.810.6;0.7 STW-812 Water Oct,1997 U 31.013.0 25.8 - 36.2 25.111.9;3.2 The presence of U-232 in the sample interfered with the recovery calculation. Result of recalculation; 31.311.1 pCi/L STW-813 ' Water Oct,1997 Co-60 10.0 i 5.0 4.2 - 15.8 10.0i 1.2;1.8 STW-813 Water Oct,1997 Cs-134 41.015.0 35.2 - 46.8 37.311.5;5.6 STW 813 Water Oct,1997 Cs-137 34.015.0 28.2 39.8 35.3 t o.6;5.1 STW-813 Water Oct,1997 Gr. Beta 143.4 t 21.5 118.5 - 168.3 157.1 1 6.9;25.2 STW-813 Water Oct,1997 Sr-89 36.0 i 5.0 27.3 - 41.8 30.7 i 2.1:3.7 STW-813 Water Oct,1997 St-90 22.0 i 5.0 16.2 - 27.8 20.0 i 1.0;2.2 STW-811 Water Nov,1997 Ba 133 99.0110.0 81.7 - 116.3 97.3 i 5.0;14.9 STW-811 Water Nov,1997 Co-60 27.0 i 5.0 18.3 - 35.7 28.311.7;4.4 STW-811 Water Nov,1997 Cs-134 10.015.0 1.3- 18.7 9.7 1.0;1.7 STW-811 Water Nov,1997 Cs-137 74.015.0 65.3 - 82.7 78.0 3.5;11.8 STW-811 Water Nov,1997 Zn-65 75.0i8.0 61.1 88.9 76.7 i 2.1;11.2
' Results obtained by Teledyne Brown Engineering Environmental Servicts Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the U.S. Environmental Protection Agency Office of Research and Developement National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.
- USEPA results are presented as the known values and expected laboratory precision (1 sigma,1 determination) and controllimits as defined by the EPA.
- Unless otherwise indicated, the TBEESML results are given as the mean 2 standard deviations for three determinations. "Ihe numbers after the semi-colon are the Total Propagated Uncertainty of the result.
5-34 1
Duqussna Light C:mpany 1998 Annual R di:lcgical EnvironmIntal Rcp:rt Table 5-14 QC Lab - EPA Interlaboratory Comparison Program 1998 U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'. Concentration in pCi/I 6 Lab Sample Date Teledyne Results d EPA Result Control Code Type Collected Analysis f2 Sigma
- 1s, N=1 ' Limits STW 815 WATER Jan,1998 Sr-89 6.0i t.0 8.015.0 2.2 - 13.8 STW-815 WATER Jan,1998 Sr 90 27Sil.2- 32.0 i 5.0 26.2 - 37.8 STW-816 WATER Jan,1998 Gr. Alpha. 31.212.3 30.5i 7.6 21.7 - 39.3 STW-816 WATER Jan,1998 Gr. Beta 6.610.6 3.915.0 0.0 - 9.7 STW-817 WATER Feb,1998 I-131 111.110.9 104.9 i 10.5 86.7 - 123.1 STW-818 WATER Feb,1998 Ra-226 14.9 i 1.3 16.0 i 2.4 11.8 - 20.2 STW-818 WATER Feb,1998 Ra-228 30.911.9 33.3 i 8.3 18.9 - 47.7 STW-818 WATER Feb,1998 U 25.8 i 1.1 32.0 i 3.0 26.8 - 37.2 The presence of U 232 in the sample interfered with the recovery calculation. Result of recalculation; 28.211.2 pCi/L.
STW-823 WATER Mar,1998 H3 2,151.0 i 75.2 1,551.2 - 2,758.8 2,155.0,i 348.0 STW-824 WATER . Apr,1998 Gr. Alpha 48.3 t l.5 54.4 i 13.6 30.8 - 70.8 STW-824 WATER Apr,1998 Ra-226 15.3 t 0.9 15.0 i 2.3 11.0 - 19.0 STW-824 WATER Apr,1998 Ra 228 7.811.0 9.3 i 2.3 5.3 - 13.3 STW-824 WATER Apr,1998 Uranium 5.1 i 0.1 5.0 i 3.0 0.0 - 10.2 STW-825 WATER Apr,1998 Co-60 50.0i l.7 50.0i5.0 41.3 - 58.7 STW 825 WATER Apr,1998 Cs-134 20.7 1.2 22.0 i 5.0 13.3 - 30.7 STW-825 - WATER Apr,1998 Cs-137 9.0i t.0 10.0 i 5.0 1.3 18.7 STW-825 WATER Apr,1998 Gr. Beta 92.li 3.2 94.7
- 10.0 77.4 - 112.0 STW-825 WATER Apr,1998 Sr-89 5.3i l.5 6.0i5.0 0.0 - 14.7 STW-825 WATER Apt,1998 Sr-90 17.3il.5 18.0 i 5.0 9.3 - 26.7 STW-826 WATER Jun,1998 Ba-133 36.0i l.0 40.0 i 5.0 31.3 - 48.7 STW-826 WATER Jun,1998 Co-60 14.0 i 1.0 12.015.0 3.3 - 20.7 STW-826 WATER Jun,1998 Cs 134 26.7 i 1.2 31.0i5.0 22.3 - 39.7 STW-826 WATER Jun,1998 Cs-137 32.7t 3.8 35.015.0 26.3 43.7 STW-826 WATER Jun,1998 Zn.65 99.0 11.8 104.0 i 10.0 86.7 - 121.3 STW-827 WATER Jun,1998 Ra-226 4.7 0.4 4.9 i 0.7 3.7 - 6.1' STW-827 WATER Jun,1998 Ra-228 2.6i0.7 2.110.5 1.2 - 3.0 STW 827 WATER Jun,1998 Uranium 3.0 0.1 3.013.0 0.0 ,8.2 STW-831 WATER Jul,1998 Sr-89 19.0 3.0 21.0 i 5.0 12.3 - 29.7 STW-831 WATER Jul,1998 Sr-90 7.0i0.0 7.015.0 0.0 - 15.7 STW-832 WATER Jul,1998 Gr. Alpha 5.8 i 0.4 7.2 i 5.0 0.0 15.9 STW-832 WATER Jul,1998 Gr. Beta 12.4 i 0.4 12.8 i 5.0 4.1 - 21.5 STW 833 WATER Aug,1998 H3 17,732.0 i 31.0 17,996.0 1 1,800.0 14,873.0 - 21,119.0 STW-840 WATER Sep,1998 I-131 5.9 0.1 6.1 i 2.0 2.6 - 9.6 STW-841 WATER Sep,1998 Ra-226 1.7i 0.1 1.7i 0.3 1.2 - 2.2 STW-841 WATER Sep,1998 Ra 228 6.li 0.6 5.7 t l.4 3.3 - 8'.1 l
l 5-35 l
E 1 Duqurna Light C:mpany 1998 Annu;l Radirlogical Envir nm:ntal R p:rt Table 5-14 (Continued) QC Lab - EPA Interlaboratory Comparison Program 1998 4 U.S. Enviroranental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'. Concentrationin pCi/L' Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analysis i2 Sigma' ' 1s, N=1 Limits STW 841 WATER 'Sep,1998 Uranium 8.2 i 0.5 9.113.0 3.9 - 14.3 1
- Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental Protection Agency (EPA), Las Vegas, Nevada.
- All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/ Filter.
- Unless otherwise indicated, the TBEESML results are given as the meani 2 standard deviations for three determinations.
' USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and controllimits as defined by the EPA. j l
5-36
ATTACHMENT 2 1998 ANNUAL ENVIRONMENTAL REPORT NON-RADIOLOGICAL i 1 I h .}}