L-07-060, RTL A9.690E, 2006 Annual Radiological Environmental Operating Report.

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RTL A9.690E, 2006 Annual Radiological Environmental Operating Report.
ML071230118
Person / Time
Site: Beaver Valley
Issue date: 04/25/2007
From:
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
L-07-060 RTL A9.690E
Download: ML071230118 (85)


Text

RTL A9.690E Enclosure 3 Beaver Valley Power Station - Units 1 & 2 2006 Annual Radiological Environmental Operating Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station - Units 1 & 2 Unit I License No. DPR-66 Unit 2 License No. NPF-73

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX I This document provides a detailed report of the Beaver Valley Power Station (BVPS) i Radiological Environmental Monitoring Program (REMP). During the report period, samples of air, water, shoreline sediment, milk, fish, food crops, feed crops, vegetation, and direct radiation (in the vicinity of the BVPS site) have been measured, analyzed, evaluated, and summarized.

The results of the REMP are intended to verify that BVPS effluent releases, performed in accordance with the BVPS Radiological Effluent Technical Specification (RETS) program, do not impact the environment with measurable concentration of radioactive materials and/or levels of radiation that are higher than expected.

Pre-operational REMP (1974 - 1975): i A pre-operational REMP program was performed during the period 1974 through 1975. At that time, samples were collected and analyzed to determine the amount of radioactivity present in 3

the environment prior to BVPS operation. The resulting values are considered a "baseline" to which current sample analyses can be compared. A summary of the pre-operational data is summarized in Table 2-3 of this report.

Operational REMP (1976 - Present): 3 The operational REMP program was initiated during calendar year 1976 and continued through the report period. During the past thirty-one (31) years, radiation and radioactivity in the environment was monitored within a 10-mile radius of the site. A description of the operational REMP program is outlined in Table 2-1 of this report. In general, two (2) types of samples were collected during the report period, and are described as follows:

" Control Samples: These samples are collected from areas that are beyond measurable influence of BVPS operation, and are used as reference data. Normal background radiation levels, or radiation present due to causes other than BVPS operation, can thus be compared I

to the environment surrounding the BVPS site. During the report period, three-hundred-thirteen (313) analyses were performed on samples from the control locations. In addition, eight (8) analyses were completed for TLD's at the control locations. Results of the I

analyses from the control locations are summarized in Table 2-2 of this report.

" Indicator Samples: Indicator samples are collected to determine the radiological impact of BVPS operation in the environment. These samples are collected from various locations near the BVPS site. At a minimum, the samples are collected from areas where the BVPS contribution would indicate the most significant radiological impact. During the report period, one-thousand-three-hundred-ninety-two (1392) analyses were performed on samples collected from more than ninety (90) indicator locations. In addition, five-hundred-three (503) analyses were completed for TLD's at the indicator locations. Results of the analyses from the indicator locations are also summarized in Table 2-2 of this report.

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.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Special Report Requirements:

A Special Report shall be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-3.03, Attachment Q Table 3.12-2.

A Special Report shall also be submitted when the results of the following calculation are >1.0.

This calculation is performed when more than one radionuclide is detected in the sampling medium:

Concentration (1) + Concentration (2) + ... > 1.0 Limit Level (1) Limit Level (2)

Summary:

Based on the analytical results of environmental samples, the reporting levels were not exceeded during the report period.

Positive results attributable to the BVPS operation were consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license and the ODCM. Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, other man-made sources, and to the normal statistical fluctuation for activities near the Lower Limit of Detection (LLD).

During the report period, the radioactive effluent releases from the BVPS site did not exceed the limits identified in the BVPS Operating License Technical Specifications, and/or the ODCM.

The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) is an estimated average of 296 mrem per year. During the report period, the average individual population dose (for 4 million people) from BVPS operation was much less than <1 mrem. Therefore, the average individual population dose was not affected from BVPS operation.

Analytical results are divided into the following exposure pathways:

" Airborne Exposure Pathway: The airborne exposure pathway includes airborne radioiodine and airborne particulates. The results during this report period were similar to previous years. There was no notable increase in natural products and no detectable fission products or other radionuclides in the airborne particulate media during the year.

  • Direct Exposure Pathway: This pathway measures environmental radiation doses by use of Thermo-Luminescent Dosimeters (TLDs). The results of TLD processing have indicated a stable trend and compare well with previous years.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX I

" Ingestion Exposure Pathway: This pathway includes milk, fish, and food products (leafy vegetable) samples.

For milk samples, Strontium-90 (attributable to past atmospheric weapons testing, was detected at levels similar to the past five years). The gamma spectrometry analyses only indicated positive results for naturally occurring Potassium-40 at average environmental levels. No other radionuclides were identified.

The fish samples indicated below LLD levels in each of the sample analyses.

Vegetation samples indicated naturally occurring Potassium-40 at average environmental levels.

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" Waterborne Exposure Pathway: This pathway includes drinking water, ground (well) i water, surface (river) water, and river sediment.

Water samples were analyzed for tritium and gamma-emitting radionuclides. Tritium was identified in some of the water samples, but the values were consistent with tritium at the control location. Gamma spectrometry analysis of water samples indicated no radionuclides above detection capabilities. Iodine- 131 analysis showed several positive analyses, but the values were consistent with Iodine- 131 at the upstream control location.

Sediment samples were collected from upstream of the site, at the discharge point of BVPS liquid effluent releases, and downstream of the site. Analysis of samples indicated naturally occurring radionuclides Potassium-40, Thallium-208, Bismuth-214, Lead-212, Lead-214, Radium-226, and Actinium-228 in all results. The analyses also indicated Cesium-137, but the values were consistent with Cesium-137 at the control location. The Cesium-137 is most likely due from previous nuclear weapons tests. Cobalt-58 and Cobalt-60 were also identified in some of the samples that were obtained at the shore line of the main outfall facility. This is not unusual, because the BVPS site discharges Cobalt-58 and Cobalt-60 in liquid waste effluents. However, the activity detected at this sample location is consistent with discharge data of authorized liquid effluent releases. All liquid effluent releases during the report I

period did not exceed the release concentration limits set forth in the ODCM.

Other Exposure Pathways: In addition to the required samples collected from the above exposure pathways, precipitation, and feed crops were also collected. Results were consistent with previous years and no degrading trends were identified.

The BVPS operational REMP program was followed throughout the report period. The results demonstrate the adequacy of radioactive effluent control at the BVPS, and that plant operation i did not adversely affect the surrounding environment.

It should be noted that the REMP program includes sampling sites in addition to the required i sites set forth in the ODCM. These include five (5) air sampling sites, one (1) surface water site, three (3) ground water sites, three (3) precipitation sites, two (2) sediment sites, one (1) local large dairy, and one (1) milk animal feed site.

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I Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX I EXECUTIVE

SUMMARY

....................................................................... ii I SECTION 1 - INTRODUCTION A. Scope and Objectives of the Program ............................................... 1-1 B. Description of the Beaver Valley Site ................................................. 1-1 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I A. Environmental Radioactivity Monitoring Program ............................... 2-1

1. Program Description .......................................................... 2-1
2. Summary of Results .......................................................... 2-5 I 3.

4.

Quality Control Program ......................................................

Program Changes .............................................................

2-5 2-5 I B. Air Monitoring ....................................................................... 2-23

1. Characterization of Air and Meteorology ................................. 2-23 I 2.

3.

Air Sampling Program and Analytical Techniques ...................... 2-23 Results and Conclusions .................................................... 2-24 I C. Monitoring of Sediments and Soil ................................................. 2-27

1. Characterization of Stream Sediments and Soils ......................... 2-27 I 2.

3.

Sampling Program and Analytical Techniques .......................... 2-27 Results and Conclusions .................................................... 2-28 D. Monitoring of Feedcrops and Food Products .................................... 2-33 I 1. Characterization of Farm Products ......................................... 2-33

2. Sampling Program and Analytical Techniques ............................ 2-33 I 3. Results and Conclusions ..................................................... 2-35 E. Monitoring of Local Cow and Goat Milk ......................................... 2-38 I 1.

2.

Description - Milch Animal Locations .................................... 2-38 Sampling Program and Analytical Techniques ............................ 2-38

3. Results and Conclusions ..................................................... 2-40 I F. Environmental Radiation Monitoring ............................................ 2-44 I 1.

2.

Description of Regional Background Radiation and Sources .......

Locations and Analytical Techniques ...................................... 2-44 2-44

3. Results and Conclusions ..................................................... 2-44 I G. Monitoring of Fish ..................................................................
1. Description ....................................................................

2-49 2-49 I 2.

3.

Sampling Program and Analytical Techniques ...........................

Results and Conclusions ....................................................

2-49 2-49 I

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX TABLE OF CONTENTS (Continued)

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM (continued)

H. Monitoring of Surface, Drinking, Ground Waters and Precipitation ......... 2-52

1. Description of Water Sources.......................................2-52
2. Sampling and Analytical Techniques ............................... 2-52
3. Results and Conclusions........................................... 2-54 I. Estimates of Radiation Dose to Man....................................... 2-61
1. Pathways to Man - Calculational Models ........................... 2-61
2. Results of Calculated Population Dose to Man - Liquid Effluent Releases........................................................... 2-61I
3. Results of Calculated Population Dose to Man - Gaseous Effluent Releases........................................................... 2-61
4. Conclusions ....................................................... 2-62 SECTION 3 - LAND USE CENSUS................................................3-1 SECTION 4 - SPLIT SAMPLE AND SPIKE SAMPLE,U INTER-LABORATORY COMPARISON PROGRAM.............4-1 A. Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2)........... 4-1I B. Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2) ......... 4-1 C. Conclusions............................................................. 4-3 Vi

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX LIST OF TABLES Table 2-1, Operational Radiological Environmental Monitoring Program ......................... 2-2 Table 2-2, Environmental Monitoring Program Results ............................................... 2-6 Table 2-3, Pre-Operational Environmental Radiological Monitoring Program Summary . 2-20 Table 2-4, Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Liquid Effluent Releases ................................................ 2-63 Table 2-5, Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Gaseous Effluent Releases ............................................... 2-64 Table 3-1, Location of Nearest Residents, Gardens, Dairy Cows, Doe Goats and Beef Cattle. 3-3 Table 4-1, Inter-Laboratory Comparison Program, Spiked Samples - 1 t Quarter ................. 4-4 Table 4-2, Inter-Laboratory Comparison Program, Spiked Samples - 2nd Quarter ............... 4-5 Table 4-3, Inter-Laboratory Comparison Program, Spiked Samples - 32d Quarter ................ 4-6 Table 4-4, Inter-Laboratory Comparison Program, Spiked Samples - 4th Quarter ................ 4-7 vii

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX LIST OF FIGURES Figure 1-1, Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station ................................................................ 1-3 Figure 2-1, Environmental Monitoring Locations - Air Sampling Stations ...................... 2-25 Figure 2-2, Graph of Annual Average Concentration: Gross Beta in Air Particulates .......... 2-26 Figure 2-3, Environmental Monitoring Locations - Shoreline Sediments and Soil ............. 2-30 Figure 2-4, Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & 60 In Sedim ent ................................................................................... 2-31 Figure 2-5, Graph of Annual Average Concentration: Cesium-137 in Soil ....................... 2-32 Figure 2-6, Environmental Monitoring Locations - Feed Crop and Food Product .............. 2-36 Figure 2-7, Graph of Annual Average Concentration: Cesium-137 in Feed and Food ......... 2-37 Figure 2-8, Environmental Monitoring Locations - Milk ............................................ 2-42 Figure 2-9, Graph of Annual Average Concentration: Iodine-13 1 in Milk .......................... 2-43 Figure 2-10, Environmental Monitoring Locations - TLDs ........................................ 2-46 Figure 2-11, Graph of Annual Average Exposure: Direct Radiation in Environment ........... 2-48 Figure 2-12, Environmental Monitoring Locations - Fish ........................................... 2-50 Figure 2-13, Graph of Annual Average Concentration: Cesium- 137 in Fish ..................... 2-51 Figure 2-14, Environmental Monitoring Locations - Ground Water, Surface Water, Drinking W ater and Precipitation ........................................................ 2-56 Figure 2-15, Graph of Annual Average Concentration: Iodine-131 in Surface Water, and Drinking Water ......................................................................... 2-57 Figure 2-16, Graph of Annual Average Concentration: Tritium in Surface Water .............. 2-58 Figure 2-17, Graph of Annual Average Concentration: Tritium in Ground Water .............. 2-59 Figure 2-18, Graph of Annual Average Concentration: Tritium in Drinking Water ............. 2-60 viii

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 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 monitoring program conducted by the FirstEnergy Nuclear Operating Company during the report period.

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. The site is approximately one mile from Midland, Pennsylvania; five miles from East Liverpool, Ohio; and twenty-five miles from Pittsburgh, Pennsylvania. Figure 1-1 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 15,493 and the only area within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,321.

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 1,078 feet. Plant grade 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.

During the report period, the Ohio River flow (as obtained from the Corps of Engineers - Water Resources Engineering) at the Wheeling Dam ranged from 17,600 cubic feet per second (minimum monthly average) to 77,500 cubic feet per second (maximum monthly average). The mean flow during the report period was 42,192 cubic feet per second.

Water temperature of the Ohio River typically varies from 340 Fahrenheit to 75' Fahrenheit. The minimum temperatures occur in January and/or February and maximum temperatures in July and'or August. Water quality in the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela and Beaver rivers.

The climate of the area may be classified as humid continental. The National Climate Data Center (http://climnvis.ncdc.noaa.gov/cgi-bin/cag3/state-map-display.pl) indicates the total annual precipitation during the report period was 47.66 inches, and the average mean temperature during the report period was 50.70 Fahrenheit. The predominant wind direction is typically from the southwest in summer and from the west southwest in winter.

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Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 1 - INTRODUCTION I

The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below:

Beaver Valley Unit 1 Beaver Valley Unit 2 I 2900 - megawatts thermal Licensed Power Level Type of Power 2900 - megawatts thermal PWR PWR I

No. of Reactor Coolant Loops 3 3 No. of Steam Generators & Type 3 - Vertical 3 - Vertical I

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 I

from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps.

I Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and returned to the steam generators to begin I

another steam/water cycle.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station SHENANG0 RIVF14 0 20 40 MILES 1-3

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Environmental Radioactivity Monitoring Program

1. Program Description The program consists of monitoring water, air, soil, river bottoms, vegetation and food crops, cows milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table 2-1. Further description of each portion of the program (Sampling Methods, Sample Analysis, Discussion and Results) are included in Sections 2-B through 2-I of this report.

2-B - Air Monitoring 2-C - Monitoring of Sediments and Soils 2-D - Monitoring of Feed Crops and Food Products 2-E - Monitoring of Local Cow and Goat Milk 2-F - Environmental Radiation Monitorin!

2-G - Monitoring of Fish 2-H - Monitoring of Surface Water, Drinking Water. Ground Water and Precipitation 2-I - Estimates of Radiation Dose to Man 2-1

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 Operational Radiological Environmental Monitoring Program Section Type of Sample Sample Point Sample Point Description Sample Frequency Sample Frequency/

AnalysisPreparation Analysis 1 Air 13 Hookstown, PA (Old Meyer Farm) Continuous Weekly - Air Gross Beta Particulate & 27 Aliquippa, PA (Brunton Farm) Sampling with Particulate (b)

Radionuclide 28 Sherman Farm Sample 29B Beaver, Pa (Friendship Ridge) Collection at least Weekly - Charcoal Iodine-131 30 Shippingport, PA (Cook's Ferry Substation) weekly 32 Midland, PA (North Substation) Quarterly Composite Gamma Scan 46.1 Industry, PA (McKeel's Service - Rt. 68) (c) 47 East Liverpool, OH (Water Department) 48 Weirton, WV (Water Tower - Collier Way) 511 Aliquippa, PA (Sheffield Substation) 10 Shippingport, PA (Post Office) 2 Direct 13 Hookstown, PA (Old Meyer Farm) Continuous (TLD) Quarterly (I) Gamma Dose Radiation 14 Hookstown, PA 15 Georgetown, PA (Post Office) 27 Aliquippa, PA (Brunton Farm) 28 Sherman Farm 29B Beaver, PA (Friendship Ridge) 30 Shippingport, PA (Cook's Ferry Substation) 32 Midland, PA (North Substation) 33-44 BVPS Site Perimeter Locations Raccoon Township, PA (Christian House 45 Baptist Chapel - Rt. 18) 45.1 Raccoon Township, PA (Kennedy's Corner) 46 Industry, PA (Midway Drive) 46.1 Industry, PA (McKeel's Service - Rt. 68) 47 East Liverpool, OH (Water Department) 48 Weirton, WV (Water Tower - Collier Way) 51 Aliquippa, PA (Sheffield Substation) 52-55 BVPS Site Perimeter Locations 59 236 Green Hill Road 60 Georgetown, PA (444 Hill Road) 70 Industry, PA (236 Engle Road) 71 Brighton Township, PA (First Western Bank) 72 Ohioview, PA (Luthem Church - Rear) 73 618 Squirrel Run Road 74 Monaca, PA (37 Poplar Avenue - CCBC) 75 Aliquippa, PA (117 Holt Road) 76 Raccoon Township, PA (Elementary School) 77 Aliquippa, PA (3614 Green Garden Road) 78 Raccoon Township, PA (Municipal Building) 79 106 Rt. 151 - Ted McWilliams Auto Body 80 Raccoon Township, PA (Park Office -Rt. 18) 81 Millcreek United Presby, Church 82 2697 Rt. 18 83 735 Mill Creek Road 84 Hancock County, WV (Senior Center) 85 2048 Rt. 30 86 East Liverpool, OH (1090 Ohio Avenue) 87 50103 Calcutta Smith's Ferry Road 88 Midland, PA (110 Summit Road) 89 Ohioville, PA (488 Smith Ferry Road) 90 Midland, PA (6286 Tuscarawras Road) 91 Pine Grove Road & Doyle Road Georgetown, PA (Georgetown Road 92 Substation) 93 104 Linden - Sunrise Hills 94 Hookstown, PA (832 McCLeary Road)

Hookstown, PA (McCleary & Pole Cat Hollow 95 Roads) 111-112 BVPS Site Perimeter Locations 2-2

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Table 2-1 Operational Radiological Environmental Monitoring Program I

Section 3

Type of Sample Surface Sample Point 49 (a)

Sample Point Description Industry, PA (Upstream of Montgomery Sample Frequency Weekly Grab Sample (h)

Sample Preparation Analysis Frequency Weekly Sample from Analysis I

Water Dam) Site49 only Iodine-131 2.1 Midland, PA (ATI Allegheny Ludlam)

Weekly Intermittent Composite Sample (h)

Monthly Composite of Weekly Sample (c)

Gamma Scan I

Daily Grab Sample 4 Groundwater 5

11 14a Ih East Liverpool, OH (Water Department)

Shippingport, PA (Upstream)

Hookstown, PA (Downstream)

Collected Weekly

()

Semi-Annual Quarterly Composite (c)

Semi-Annual Tritium (H-3)

Gamma Scan Tritium (H-3)

I (Downstream)

I 15b Georgetown, PA 5 Drinking 4 Midland, PA (Water Department) Weekly Composite of Water 5 East Liverpool, OH (Water Department) Intermittent (d) Daily sample (d) Iodine-131 Sample Collected Monthly Composite (d) Gamma Scan Weekly Quarterly Composite (d) Tritium (H-3) 6 Shoreline Sediment 2A 49a (a)

BVPS Outfall Vicinity Industry, PA (Upstream of Montgomery Dam)

Semi-Annual Semi-Annual Gamma Scan I 50 New Cumberland, WV (Upstream of 7 Milk 25 Dam)

Hookstown, PA (Searight Farm)

Weekly (e) Weekly Samples from Searight only Weekly Iodine-131 I

from Searight 27 (k) Aliquippa, PA (Brunton Farm) 69 (k) Aliquippa, PA (Collins Farm) Biweekly (f) When All other samples &

only Gamma Scan I

96 (a) Burgettstown, PA (Windsheimer Farm) animals are on analyses are Biweekly Iodine-131 113(a) Bgestown, PA (Halsteadhi Farm) pasture; monthly at during grazing, but Strontium-89 113 (k) Hookstown, PA (Halstead Farm) 114 (k) Hookstown, PA (Moore Farm) other times Monthly during other times Strontium-90 I

2A BVPS Outfall Vicinity Gamma Scan 8 Fish 49a 10a Industry, PA (Upstream of Montgomery Dam)

Shippingport, PA Semi-Annual Composite of edible parts by species (g) on edible parts Gamma Scan I

9 Food 15a Georgetown, PA Annual at Harvest Composite of each Iodine-131 on Products 46a Industry, PA ifavailable sample species green leafy 48a Weirton, WV vegetables I

Feedstuff & 25 Hookstown, PA (Searight Farm) Monthly Monthly Gamma Scan 10 11 Summer Soil Forage 13 22 Hookstown, PA (Old Meyer Farm)

South of BVPS, Transmission Lines Every Three (3) 12 Core Samples 3" Gamma Scan I

Years Deep (2" diameter at 27 29A 30a Aliquippa, PA (Brunton Farm)

Beaver, PA (Nicol Farm)

Shippingport, PA (Cook's Ferry Substation)

(1997, 2000, 2003) each location approx. 10' radius)

I 32a Midland, PA (North Substation) 46b 47a 48A Industry, PA (Willows Inn - Rt. 68)

East Liverpool, OH (Water Department)

Weirton WV (Water Tower - East I

Belleview Drive) 12 Precipitation 51a 30 47 Aliquippa, Substation)

PA (Sheffield Substation)

Shippingport, PA (Cook's Ferry East Liverpool, OH (Water Department)

I Weekly grab samples when available I

Quarterly Composite (c) Gamma Scan Tritium (H-3)

I 48 Weirton WV (WaterTower-Collier Way) 2-3 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 Operational Radiological Environmental Monitoring Program Notes for Table 2-1 (a) Control Sample Station: These Locations which are presumed to be outside the influence of plant effluents.

Particulate Samples are not counted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change. Perform Gamma (b) isotopic analysis on each sample when gross beta is greater than 10 times the yearly mean of control samples.

(c) Long-term composite samples are obtained from short-term composite samples at the specified locations.

(d) Composite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

(e) Weekly milk sample from the Searight Dairy is analyzed for lodine-131 only.

(f) Milk samples are collected bi-weekly when animals are grazing. The milk samples are collected monthly at other times.

(g) The fish samples contain whatever species are available.

IF adequate sample size is available, THEN the sample is separated according to species, and compositing will provide one sample of each species.

IF adequate sample size is not available, THEN separation by species is not practical. Therefore edible parts of all fish in the sample are mixed to provide one sample.

(h) Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at location 2.1. The water treatment plant operator at location 5 obtains the weekly grab sample from the daily composite grab samples. For location 49, the weekly grab sample is obtained by a field technician.

(i) Two (2) TLDs are collected quarterly from each monitoring location.

(k) Offsite Dose Calculation Manual procedure 1/2-ODC-3.03, Attachment Q, Table 3.12-1 requires three (3) dairies to be selected on basis of highest potential thyroid dose using milch census data. See Section 2-E of this report (Monitoring of Local Cows Milk) for specific locations sampled.

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Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

2. Summary of Results I All results of this monitoring program are summarized in Table 2-2. This table is prepared in the format specified by the NRC via the Branch Technical Position in NUREG-1301, and in accordance with Beaver Valley Power Station Offsite Dose Calculation Manual. Summaries of results of analysis of each media are discussed in Sections 2-B through 2-H and an assessment of radiation doses are given in Section 2-1. Table 2-3 summarizes Beaver Valley Power Station pre-operational ranges for the various sampling media during the years 1974 and 1975.

Comparisons of pre-operational data with operational data indicate the ranges of values are generally in good agreement for both periods of time.

Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the Lower Limit of Detection (LLD).

I The conclusion from all program data is that the operation of the Beaver Valley Power Station has resulted in no significant changes to the environment.

3. Quality Control Program The Quality Control Program implemented by the Beaver Valley Power Station to assure reliable performance by the contractor and the supporting QC data are presented and discussed in Section 4 of this report.
4. Program Changes There were no changes of significance to the sampling program during the report period. The only change of note was relocation of the soil sample Control location. Specifically, due to construction at the previous location, it was moved to the Collier Way Water Tower, which is also the current Control location for the air particulate sampler. Moving the Control location for soil samples does not adversely impact the accuracy or reliability of sample collection.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334/ 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Air Particulate and Radioiodine Unit of Measurement: (pico Curies / cubic meter)

Type and Lower Number of Total Number Limit of All Indicator Locatior Locations with Highest Annual Mean Control Location Nonroutine 0

of Analysis Detection Mean (fraction) () Name Mean (fraction)(b) Name Mean (fraction)0" Reported Performed LLD ' Range b) Distance and Direction Range N Distance and Direction Range (b) Measurements W Gross Beta 0.004 0.027 ( 468 / 468 ) No. 51 Alliquippa. PA 0.03 ( 52 / 52 ) No. 48 Weirton, WV 0.028 ( 52 / 52 0 520 0.01 - 0.093 Sheffield Substation 0.012 - 0.093 Water Tower 0.011 - 0.053 8.00 miles E Collier Way 16.40 miles SSW 1-131 <0.04 LLD( 0/468) LLD( 0/468 LLD( 0/52 0 520 Gamma 40 Be-7 NA 0.077 ( 36 / 36 ) No. 27 Alliquippa, PA 0.084 ( 4 /4 ) No. 48 Weirton, WV 0.076 ( 4 /4 NA 0.053 - 0.106 Brunton Farm 0.06 - 0.106 Water Tower 0.065 - 0.102 6.14 Miles SE Collier Way 16.40 miles SSW Co-60 0.0003 LLD( 0 /36) LLD( 0 /36) LLD( 0 /4 ) 0 Cs-134 0.0004 LLD( 0 / 36) LLD( 0 /36 ) LLD( 0 /4 ) 0 Cs-137 0.0004 LLD( 0 /36) LLD( 0 /36 ) LLD( 0 /4 ) 0 Ba-La-140 0.0005 LLD( 0 /36 ) LLD( 0 /36 ) LLD( 0 /4 ) 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-6

Beaver Valley Power Station RTL A9.690E I

2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Drinking Water Unit of Measurement: (pico Curies / liter)

I Type and Lower Number of Total Numbet Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine 51 t of Analysis Detection Mean (fraction) (b) Name Mean (fraction)t Name Mean (fraction)* Reported Performed LLD

  • Range () Distance and Direction Range (b) Distance and Direction Range (b) Measurements 0) 1-131 0.5 0.625 ( 49 / 102 ) No. 5 EAALivermol, OH 0.670 ( 23 / 52 ) No. 49 Industry, PA 0.819 ( 37 / 52 ) 0 0.3 - 1.2 Wotw Deplalment 0.3 1.2 Upstream of 0.3 - 2.1 154 4.90 miles WNW Montgomery Dam 1 4.92 miles NE I H-3 LLD( 0/8 ) LLD( 0/4 ) LLD( 0/4 ) 0 12 200 Gamma 36 Mn-54 5 LLD( 0 / 24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Fe-59 10 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 / 12) 0 Co-58 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Co-60 5 LLD( 0 / 24) LLD( 0 /24) LLD( 0 / 12) 0 Zn-65 10 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Zr-Nb-95 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Cs-134 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Cs-137 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Ba-La-140 15 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-7

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Surface Water Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine 1

of Analysis Detection Mean (fraction) b) Name Mean (fraction)(b) Name Mean (fraction) Reported Performed LLD

  • Range (M) Distance and Direction Range N Distance and Direction Range W Measurements 1-131 0.5 No. 49 Industry, PA 0.819 ( 37 /52 ) 0 52 Upstream of 0.3 - 2.1 Montgomery Dam 4.9 miles NE H-3 200 LLD( 0 /8 ) LLD( 0 /4 ) LLD( 0 /4 0 12 Gamma 36 Mn-54 5 LLD( 0 /24 LLD( 0 /24) LLD( 0 /12 0 Fe-59 10 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0 / 12) 0 Co-58 5 LLD( 0 /24 LLD( 0 /24) LLD( 0 /12) 0 Co-60 5 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0 /12) 0 Zn-65 10 LLD( 0 /24 LLD( 0 /24 ) LLD( 0 / 12) 0 Zr-Nb-95 5 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0 /12) 0 Cs-134 5 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0 /12) 0 Cs-137 5 LLD( 0 /24 LLD( 0 /24 ) LLD( 0 /12) 0 Ba-La-140 is LLDI( 0 /24 LLD( 0 /24 ) LLD( 0 /12) 0 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-8

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Ground Water Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Numbei Limit of All Indicator Locatio. Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)() Name Mean (fraction)(") Name Mean (fraction)(') Reported Performed LLD ' RanMe ( Distance and Direction Range M Distance and Direction Range () Measurements H-3 200 LLD ( 0 /4 ) LLD ( 0 /4 ) No.ll Shippingport, PA LLD ( 0 /2 ) 0 6

Gamma Upstream 0.94 miles NE No. 11 Shippingport, PA I

6 Mn-54 5 LLD( 0 /4 ) LLD ( 0 /4 Upstream 0.94 miles NE LLD ( 0 /2) 0 I

Fe-59 10 LLD( 0 /4 ) LLD ( 0 /4 LLD ( 0 /2) 0 Co-58 5 LLD( 0 /4 ) LLD ( 0 /4 LLD ( 0 /2) 0 Co-60 5 LLD( 0 /4 ) LLD ( 0 /4 LLD ( 0 /2 ) 0 Zn-65 10 LLD( 0 /4 ) LLD ( 0 /4 LLD ( 0 /2) 0 Zr-Nb-95 5 LLD( 0 /4 ) LLD ( 0 /4 LLD( 0 /2) 0 Cs-134 5 LLD( 0 /4 ) LLD ( 0 /4 LLD( 0 /2) 0 Cs-137 5 LLD( 0 /4 ) LLD ( 0 /4 LLD( 0 /2) 0 Ba-La-140 15 LLD( 0/4 ) LLD( 0/4 LLD( 0/2) 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-9

I Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

  • Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Precipitation Water Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Number Limit of All Indicator Locatiot Locations with Hilhest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) ('t Name Mean (fraction) () Name Mean (fraction)() Reported Performed LLD (' Range () Distance and Direction Range (b) Distance and Direction Range O) Measurements (C)

H-3 200 239 ( 3 /8 ) No. 30 Shippingport, PA 239 ( 3 /4 ) No. 48 Weirton, WV LLD ( 0 /4 ) 0 12 197 - 286 Cook's Ferry Substation 197 - 286 Water Tower 0.43 miles ENE Collier Way 16.40 miles SSW Gamma 12 Mn-54 5 LLD( 0 / ) LLD( 0 /8 LLD( 0 /4 ) 0 Fe-59 10 LLD( 0 /8 ) LLD( 0 /8 LLD( 0 /4 ) 0 Co-58 5 LLD( 0 / 8 ) LLD( 0 /8 LLD( 0 /4 ) 0 Co-60 5 LLD( 0 / 8 ) LLD( 0 /8 LLD( 0 /4) 0 Zn-65 10 LLD( 0 / 8 ) LLD( 0 /8 LLD( 0 /4) 0 Zr-Nb-95 5 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0 /4 ) 0 Cs-134 5 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0 /4) 0 Cs-137 5 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0 /4) 0 Ba-La-140 15 LLD( 0 /8 ) LLD( 0 /8 LLD( 0 /4 ) 0 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-10

Beaver Valley Power Station RTL A9.690E I

2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Milk Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Numbei Limit of All Indicator Locatior Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) () Name Mean (fraction)(h) Name Mean (fraction)(") Reported Performed LLD ( Range (b) Distance and Direction Range N Distance and Direction Range N Measurements

  • 1-131 0.5 LLD( 0 /118 LLD( 0/118 ) No. 96BurgettstownPA LLD( 0/21 ) 0 139 Windsheimer Farm 10.48 miles SSW Sr-89 2.0 LLD( 0 /87 ) LLD ( 0 /87 ) No. 96Burgettatown.PA LLD ( 0 /21 ) 0 108 Windsheimer Farm 10.48 miles SSW Sr-90 07 1.73( 82 /87 ) No.69 Alliquippa, PA 2.85 (12 /12 ) No. 96 Burgettstown, PA 1.16 ( 21 /21 ) 0 108 0.6 - 4.4 Collings Farm 1.8 -4.4 Windsheimer Farm 0.6 -2.7 3.55 miles SE 10.48 miles SSW Gamma 108 K-40 NA 1428 ( 87 /87 ) No. 114 HooikwnPA 1615 ( 12 /12 ) No. 96 Burgettstown, PA 1374 (21 / 21) NA 995 - 2013 Moore Farm 1325 - 2013 Windsheimer Farm 1261 - 1528 Mn-54 5 LLD( 0 /87 )

2,12 miles SW LLD( 0 /87 )

10.48 miles SSW LLD( 0 /21) 0 I

Fe-59 10 LLD( 0 /87 ) LLD( 0 /87 ) LLD( 0 /21) 0 I Co-58 5 LLD( 0 /87) LLD( 0 /87) LLD( 0 /21) 0 Co-60 5 LLD( 0 /87 ) LLD( 0 /87 ) LLD( 0 /21) 0 Zn-65 10 LLD( 0/87 ) LLD( 0/87 ) LLD( 0/21) 0 Zr-Nb-95 5 LLD( 0 /87 ) LLD( 0 /87 ) LLD( 0 /21) 0 Cs-134 5 LLD( 0 /87 ) LLD( 0 /87 ) LLD( 0 /21) 0 Cs-137 5 LLD( 0 /87 ) LLD( 0 /87 ) LLD( 0 /21) 0 Ba-La-140 15 LLD( 0 /87 ) LLD( 0 /87 ) LLD( 0 /21) 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-11

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver Countvy Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Fish Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total NumberLimit of All Indicator Locatior Locations with H-ighest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)*") Name Mean (fraction) () Name Mean (fraction)(b) Reported Performed LLD ( Range (b) Distance and Direction Range (b) Distance and Direction Range N Measurements Gamma Mn-54 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0 / ) 0 Fe-59 0.10 LLD( 0 / ) LLD( 0 / ) LLD( 0 / ) 0 Co-58 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0 / ) 0 Co-60 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0 / ) 0 Zn-65 0ý10 LLD( 0 / ) LLD( 0 / ) LLD( 0 / 0 Zr-Nb-95 0.03 LLD( 0 / ) LLD( 0 / ) LLD( 0 / 0 Cs-134 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0 / 0 Cs-137 0.05 LLD( 0 / LLD( 0 / ) LLD( 0 / 0 Ba-La-140 0.07 LLD( 0 / ) LLD( 0 / ) LLD( 0 / 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-12

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RAflIOI.OGAI.A ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2006 I

Medium: Foodcrops Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total Number Limit of All Indicator Locatior Locations with Highest Annual Mean Control Location Nonroutine 1

of Analysis Detection Mean (fraction)(b) Name Mean (fraction)0" Name Mean (fraction)() Reported Performed LLD , Range N Distance and Direction Range Distance and Direction Range (,) Measurements 1-131 0.06 LLD ( 0 /3 ) LLD( 0 /3 ) LLD( 0 /1 ) 0 4

Gamma 4

K-40 NA 2.14 ( 3/3 ) No. 15 Hookstown, PA 2.18( i /I ) To. 4aWeirton,WV 1.70( 1 /1 ) NA 2.08 - 2.18 321 Third Street 2.18 - 2.18 Weirton Area 1.70 - 1.70 3.7 miles WSW 16.54 miles SSW Mn-54 0.05 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Fe-59 0.10 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Co-58 0.05 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Co-60 0.05 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Zn-65 0.10 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Zr-Nb-95 0.03 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Cs-134 0.05 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Cs-137 0.05 LLD( 0 /3 ) LLD( 0 /3 LLD( 0 /1 ) 0 Ba-La-140 0.07 LLD( 0 /3 ) LLD( 0 /3 ) LLD( 0 /1 ) 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-13

I I Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

  • Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania I Reporting Period: Calendar Year - 2006 Medium: Feedstuff Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total Numbei Limit of All Indicator Locatior Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction)(b) Name Mean (fraction) () Reported Performed LLD ( Range M Distance and Direction Range (b) Distance and Direction Range (b) Measurements Gamma 12 Be-7 NA 2.05 ( 7/ 12 ) No. 25 Searight Farm 2.05 ( 7/12 ) No.25 SearightFarm 2.05 ( 7/12) NA 0.48 - 4.65 948 McCleary Road 0.48 - 4.65 948 McCleary Road 0.48 - 4.65 Hookstown, PA Hookstown, PA 2.1 miles SSW 2.1 miles SSW K-40 NA 8.94( 12 / 12 ) No. 25 SearightFarm 8.94 ( 12/12 ) No. 25 SearighitFarm 8.94 ( 12/12) NA 0.27 - 20.16 948 McCleary Road 0.27 - 20.16 948 McCleary Road 0.27 - 20.16 Hookstown, PA Hookstown, PA 2.1 miles SSW 2.1 miles SSW Mn-54 0.05 LLD( 0 / 12 ) LLD( 0 /12) LLD( 0 /12 0 Fe-59 0.10 LLD( 0 / 12) LLD( 0 /12) LLD( 0 / 12 0 Co-58 0.05 LLD( 0 / 12 ) LLD( 0 /12) LLD( 0 / 12 0 Co-60 0.05 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 / 12 0 Zn-65 0.10 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 /12 0 Zr-Nb-95 0.03 LLD( 0 / 12 ) LLD( 0 / 12 ) LLD( 0 / 12 0 Cs-134 0.05 LLD( 0 / 12 ) LLD( 0 / 12 ) LLD( 0 /12 0 Cs-137 0.05 LLD( 0 / 12) LLD( 0 /12) LLD( 0 / 12 0 Ba-La-140 0.07 LLD( 0 / 12) LLD( 0 /12) LLD( 0 /12 0 Ru-103 0.04 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 /12 Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-14

Beaver Valley Power Station RTL A9.690E I

2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania I

Reporting Period: Calendar Year - 2006 Medium: Sediment (page 1 of 2)

I Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Locatio Locations with Highest Annual Mean of Analysis Detection Mean (fraction)01 Name Distance and Direction Mean (fraction) ')

Range M')

Control Location Name Distance and Direction Nonroutine Mean (fraction) (b) Reported lRange (b) Measurements W I

i Performed LLD () Range (b)

Gamma 6

K-40 NA 1.4 (

10.02-4/4 12.01

) No. 2A BVPS Outfoll Vicinity 0.31 miles WSW 11.13(

10.25-2 / 2 12.01

) No. 49a Industry, PA Upstream of Montgomery Dam 9.81(

8.62-2/2 10.99

) NA I 4.93 miles NE Mn-54 0.05 LLD ( 0/4 0/4

)

)

LLD( 0/4 ) LLD 0/2 ) 0 I Fe-59 0.10 LLD LLD( 0 /4 ) LLD 0/2 ) 0 Co-58 0.05 0.22 0.22- 0. 22 1/4 ) No. 2A BVPS Outfall Vicinity 0.31 miles WSW 0.22( 1/2 0.22 - 0.22

) Fo .49a Industry, PA Upstream of Montgomery Dam LLD 0/2 ) 0 I

4.93 miles NE Co-60 0.05 0.51 114 ) No. 2A BVPS 0.51 ( 1/2 \*o. 49a Industry, PA LLD( 0/2 ) 0 I

0.51 - 0.5 Outfwl Vicinity 0.51 - 0.51 Upsh-eam of Zn-65 0.10 LLD ( 0/4 )

0.31 miles WSW LLD( 0 /4 Montgomery Dam 4.93 miles NE LLD( 0/2 ) 0 I

Zr-95 Nb-95 0.03 0.03 LLD LLD (

0/4 0/4

)

)

LLD(

LLD(

0 /4 0 /4 LLD(

LLD(

0/2 0/2

)

)

0 0

I

)

I Cs-134 0.05 LLD ( 0/4 LLD( 0 /4 LLD( 0/2 ) 0 Cs-137 0.05 0.08( 3/4 ) No. 2A BVPS 0,08 ( 2 /2 14o, 49a Industry, PA 0.07( 2/2 ) 0 09 0.08- 0. Ouffall Vicinity 0.08 - 0.09 Upstream of 0.06- 0.09 0.31 miles WSW Montgomery Dam No. 50 New Cumberland, WV Upst=m of 0.08 (

0.08- 0.08

/2 4.93 miles NE I

Dam 11.77 mile WSW 0/4 )

Ba-La-140 0.07 LLD ( LLD( 0/4 LLD( 0/2 ) 0 4/4 )

TI-208 NA 0.37 ( 39 No. 2A BVPS 0.39 ( 2 /2 qo. 49a Industry, PA 0.31 ( 2 /2 NA 0.33 - 0.3 Outfall Vicinity 0.38 - 0.39 Upstream of 0.28 - 0.34 0.31 miles WSW Montgomery Dam 4.93 miles NE 2-15

RTL A9.690E I 2006 Beaver Annual ValleyRadiological Power Station Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

  • Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Sediment (page 2 of 2)

Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Locatio Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)(") Name Mean (fraction) () Name Mean (fraction)

  • Reported Performed LLD
  • Range (b) Distance and Direction Range (6) Distance and Direction Range (b) Measurements )

Bi-214 NA 0.903 ( 4 /4 ) No. 50 New Cumsberland, WV 0.94 ( 2 /2 ) o. 49a Industry, PA 0.84 ( 2 /2 ) NA 0.74 - 0.99 Upstream of 0.89- 0.99 Upstream of 0.30 - 0.88 Dam Montgomery Dam 11.77 miles WSW 4.93 miles NE Pb-212 NA 1.09 ( 4 /4 ) No. 50 NewCumberland, WV 1.11 ( 2 / 2 ) o. 49a Industry, PA 0.91 ( 2 /2 ) NA 1.03 - 1.19 Upstream of 1.03 - 1,19 Upstream of 0.76- 1.05 Dam Montgomery Dam 11.77 miles WSW 5 miles NE Pb-214 NA 1.028 ( 4 /4 ) No. 50 New Cumbeland, WV 1.07 ( 2 / 2 ) o. 49a Industlry, PA 0.95 ( 212 ) NA 0.86 - 1.12 Upstream of 1.04 - 1.09 Upstream of 0.85 - 1.05 Dam Montgomery Dam 11.77 miles WSW 5 miles NE Ra-226 NA 2.01 ( 4 /4 ) No. 2ABVPS 2.04 ( 2 /2 ) o. 49a Industry, PA 1.95 ( 2/2 ) NA 1.93 - 2.06 Outfall Vicinsty 2.02- 2.06 Upstream of 1.64 - 2.26 0.31 miles WSW Montgomery Dam 5 miles NE Ac-228 NA 1.16 ( 4 /4 ) No. 2ABVPS 1.24 ( 2 /2 ) o. 49aIndustry, PA 1.02 ( 2 /2 ) NA 0.98 - 1.34 Outfall Vicinity 1.13 - 1.34 Upstream of 0.88 - 1.15 0.31 miles WSW Montgomery Dam 5 miles NE

  • Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 112-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-16

I Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-413 I

Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2006 Medium: Soil (page 1 of 2)

I Unit of Measurement: (pico Curies / gram) Dry Type and Lower Total Number Limit of All Indicator Locatio Locations with Highest Annual Mean Control Location Number of Nonroutine I

of Analysis Detection Mean (fraction) (b) Name Mean (fraction)co) Name Mean (fraction)(o) Reported Performed Gamma LLD ( Range (b) Distance and Direction Range N Distance and Direction Range N Measurements I

10 K-40 12.54 ( 9/ 9 9.75 - 16.14

) No. 29A Beaver, PA Nichol Farm 16.14 ( I/1 16.14 - 16.14

) No. 48 Weirton, WV Water Tower 14.20 ( 1/1 14.20 - 14.2 N/A I 8.09 miles NE Collier Way Mn-54 LLD( 0 / 9 ) LLD( 0/I )

16.40 miles SSW LLD (0/ 1) 0 I

9 ) LLD( 0 /1 ) LLD (0/ 1) 0 I

Fe-59 LLD( 0/

Co-58 LLD( 0/ 9 ) LLD( 0 /1 ) LLD (0/ 1) 0 Co-60 LLD( 0/ 9 ) LLD( 0 /1 ) LLD (0/ 1) 0 Zn-65 Zr-95 LLD(

LLD(

0/ 9 0/ 9

)

)

LLD(

LLD(

0 /1 0 /1

)

)

LLD LLD (0/

(0/ 1) 1 )

0 0

I Nb-95 Cs-134 LLD(

LLD(

0/

0/

9) 9 )

LLD(

LLD(

0 /1 0/1

)

)

LLD LLD (0/

(0/ 1) 1 )

0 0

I Cs-137 0.20 (

0.13 - 0.27 9/ 9 ) No. 13 Hookstowo, PA Old Meyer Farm 1.49 miles SW 0.27 ( 1 / 1 0.27 - 0.27

) No. 48 Weirton, WV Water Tower Collier Way 16.40 miles SSW 0.28 ( I / 1 )

0.28 - 0.28 0

I No. 46b Industry,PA Willows Inn, Route 68 2.66 miles NE 0.27 (

0.27 - 0.27

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2-17 I

RTL A9.690E I 2006 Beaver Annual ValleyRadiological Power Station Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50413 Location of Facility: Beaver County, Pennsylvania Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Medium: Soil (page 2 of 2)

Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Total Numbe Limit of All Indicator Locatior Locations with H-ighest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (5) Name Mean (fraction)(b) Name Mean (fraction) ") Reported Performed LLD Range W , Distance and Direction Range () Distance and Direction Range (,) Measurements W Ba-La-140 LLD( 0 / 9 ) LLD( 0 /1 ) LLD (0 / 1 ) 0 TI-208 0.36( 9/9 ) No. 29A Beaver, PA 0.47 ( IlI ) No. 48 Weirton, WV 0.38 ( 1 / I 0.24 - 0.47 Nichol Farm 0.47 - 0.47 Water Tower 0.38 - 0.38 8.09 miles NE Collier Way 16.40 miles SSW Bi-214 0.86( 9/ 9 ) No. 29A Beaver, PA 1.31( 11 ) No. 48 Weirton, WV 1.10 ( 1 / I ) N/A 0.51 - 1.31 Nichol Farm 1.31 - 1.31 Water Tower 1.10 - 1.10 8.09 miles NE Collier Way 16.40 miles SSW Pb-212 1.19 ( 9/ 9 ) No. 51a Alliquippa, PA 1.61 ( /1/ ) No. 48 Weirton, WV 1.16 ( 1 / I ) N/A 0.78 - 1.61 Sheflield Substation 1.61 - 161 WaterTower 1.16 - 1.16 7.99 miles E Collier Way 16.40 miles SSW Pb-214 0.98( 9/ 9 ) No. 29A Beaver, PA 1.45( I/ ) No. 48 Weirton, WV 1.26 ( 1 / I ) N/A 0.72 - 1.45 Nichol Farm 1.45 - 145 Water Tower 1.26 - 1.26 8.09 miles NE Collier Way 16.40 miles SSW Ra-226 2.20( 9/ 9 ) No. 29A Beaver, PA 3.02 ( I / I ) No. 48 Weirton, WV 2.83 ( I / 1 ) N/A 1.61 - 3.02 Nichol Farm 3.02 -3.02 Water Tower 2.83 - 2.83 8.09 miles NE Collier Way 16.40 miles SSW Ac-228 1.12 ( 9 / 9 ) No. 22 South of BVPS 1.53 ( Ill ) No. 48 Weirton, WV 1.30 ( I / I N/A 0.79 - 1.53 Transmission Line 1.53 - 1.53 Water Tower 1,30 - 1.30 0.3 miles SSE Collier Way 16.40 miles SSW Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-18

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-413 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2006 Medium: External Radiation Unit of Measurement: (mR / Quarter)

Type and Lower Number of Total Numbei Limit of All Indicator Locatior Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) () Name Mean (fraction) () Name Mean (fraction) () Reported Performed LLD - Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements W Gamma 511 4.6 18.1 (492-12.9 - 23.1 492) No. 112 BVPS Site Perimeter Location 22.3 ( 8 /8 216 - 2311

) No.43 Weirton, WV WaterTower Cother Way 19.4( 8/8 18.8 -20.5

) 0 I

16.40 miles SSW I

' Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

I Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)

NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) 2-19 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement) Performed (LLD)

Sediments Gross Alpha (0) ....

(pico Curie /gram) dry Gross Beta (33) 1 18 (33/33) 5 - 30 Sr-90 (0) ....

U-234, 235, 238 (0) --

Gamma (33) -- 13 (33/33) 2-30 K-40 1.5 13 (33/33) 2-30 Cs-137 0.1 0.4 (21/33) 0.1 - 0.6 Zr/Nb-95 0.05 0.8 (12/33) 0.2 - 3.2 Ce-144 0.3 0.5 (3/33) 0.4 - 0.7 Ru-106(a) 0.3 1.5 (3/33) 1.3- 1.8 Others < LLD Foodstuff Gamma (8) ....

(pico Curie /gram) 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 (pico Curie/gram) 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) ....

- Template Samples - Gross Beta (64) 1 22 (64/64) 14 - 32 Sr-89 (64) 0.25 0.4 (1/64) --

(pico Curie /gram) dry 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.

2-20 El

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Table 2-3 (Continued) I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations I

Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement) Performed (LLD)

Soil Gross Alpha (0) ....

- Core Samples - Gross Beta (8) 1 21 (8/8) 16 -28 (pico Curie /gram) dry 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 (pico Curie / liter) Gross Beta (120) 0.6 4.4 (120/120) 2.5 - 11.4 Gamma (1) 10-60 < LLD Tritium (121) 100 300 (120/121) 180-800 Sr-89 (0) ....

Sr-90 (0)

C-14 (0)

Drinking Water 1-131 (0) ....

(pico Curie / liter) Gross Alpha (50) 0.3 0.6 (4/50) 0.4 - 0.8 Gross Beta Gamma Tritium (208)

(0)

(211) 100 0.6 3.8 310 (208/208)

(211/211) 2.3 - 6.4 130- 1000 I

C-14 Sr-89 Sr-90 (0)

(0)

(0)

I Ground Water (pico Curie / liter)

Gross Alpha Gross Beta Tritium (19)

(76)

(81) 100 0.3 0.6 2.9 440

< LLD (73/75)(b)

(77/81) 1.3 - 8.0 80 - 800 I

Gamma (1) 10-60 < LLD Air Particulates and Gaseous Gross Alpha Gross Beta (188)

(927) 0.001 0.006 0.003 0.07 (35/188)

(927/927) 0.002 - 0.004 0.02 - 0.32 I

(pico Curie /cubic meter) Sr-89 (0) ....

Sr-90 1-131 Gamma (0)

(816)

(197) 0.04 0.08 (2/816) 0.07-0.08 I Zr/Nb-95 Ru-106 Ce-141 0.005 0.010 0.010 0.04 0.04 0.02 (122/197)

(50/197)

(3/197) 0.01 0.02 0.01

-0.16

- 0.09

-0.04 I

Ce-144 0.010 0.02 (44/197) 0.01 -0.04 (f)

Others Fraction of detectable measurements at specified location.

< LLD I

2-21 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 (Continued)

Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement) Performed (LLD)

Milk 1-131 (91) 0.25 0.6 (4/91) 0.3-0.8 (pico Curie / liter) Sr-89 (134) 5 7 (4/134) 6 - 11 Sr-90 (134) 1 5.3 (132/134) 1.5 - 12.8 Gamma (134) ....

Cs-137 10 13 (19/134) 11 - 16 Others < LLD External Radiation y - Monthly (599) 0.5 mR* 0.20 (599/599) 0.08 - 0.51 (milli Roentgen / 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 (pico Curie / gram) 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 outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample).

(f) Fraction of detectable measurements at specified location.

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Beaver Valley Power Station RTL A9.690E Enclosure 3 I

2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I B. Air Monitorin,

1. Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is i generally from the southwest in summer and from the northwest in the winter.
2. Air Sampling Program and Analytical Techniques 3
a. Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10) offsite air sampling stations. The locations of these stations are listed in Table 2-1 and shown on a map in Figure 2-1.

Samples are collected at each of these stations by continuously drawing two cubic feet per minute of atmosphere air through a glass fiber filter paper and a charcoal cartridge. The glass fiber filter paper is used for collection of airborne particulates, while the charcoal cartridge is used for collection of radioiodine. Samples are collected for analysis on a weekly basis. 3 The charcoal cartridge is used in the weekly analysis of airborne Iodine- 131. The glass fiber filter papers are analyzed each week for gross beta, then composited by station each quarter for gamma spectrometry analysis. In order to reduce interference from short-lived I naturally occurring radioactivity (e.g.; radon and thoron), the glass fiber filter papers are decayed prior to performing beta analysis in a low background counting system.

b. Procedures Gross Beta Analysis of Filter Paper: Analysis is performed by placing the glass fiber filter paper from the weekly air sample in a 2 inch planchet and analyzing it in a low background, gas flow proportional counter.

Gamma Emitter Analysis of Filter Paper: Analysis is performed by stacking all of the glass i fiber filter papers collected from each monitoring station during the quarter and scanning this composite on a high resolution germanium gamma spectrometer. 3 Iodine-131 Analysis of Charcoal Cartridge: Analysis is performed by a gamma scan of each charcoal cartridge. 3 3

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions A summary of data is presented in Table 2-2.
a. Airborne Radioactive Particulates Gross Beta: 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 2-2 indicates the weekly average concentration of gross beta in air particulates.

Gamma Spectrometry: The weekly air particulate samples were composited into forty (40) quarterly samples which were analyzed by gamma spectrometry. Naturally occurring Beryllium-7 was identified in thirty-six of thirty-six (36 of 36) indicator samples, and four of four (4 of 4) control samples. No other radionuclides were detected. A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-2.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required airborne particulate sampling and analysis schedule during the report period.

Summary: Based on the analytical results, the operation of Beaver Valley Power Station did not contribute any measurable increase in air particulate radioactivity during the report period.

b. Airborne Radioiodine Iodine- 131: A total of five-hundred-twenty (520) weekly charcoal filter samples were analyzed for Iodine- 131. No detectable concentrations were present at any locations.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required airborne radioiodine sampling and analysis schedule during the report period.

Summar: Based on analytical results, the operation of BVPS did not contribute any measurable increase in airborne radioiodine during the report period.

2-24

Beaver Valley Power Station RTL A9.690E Enclosure 3 I

2006 Annual Radiological Environmental Operating Report I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-1 I

Environmental Monitoring Locations - Air Sampling Stations I

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Site Distance Sample Type No. Sector (miles) 1.49 Sample Point Description Hookstown, PA (Old Meyer Farm)

I 13 27 28 11 -SW 7-SE 1-N 6.16 8.60 Aliquippa, Pa (Brunton Farm)

Sherman Farm I

Air Particulate

& RadioIodine 29B 30 32 3-NE 4-ENE 15-NW 7.97 0.43 0.75 Beaver, PA (Friendship Ridge)

Shippingport, PA (Cook's Ferry Substation)

Midland, PA (North Substation - Rt. 68)

I 46.1 47 48 3-NE 14-WNW 10-SSW 2.28 4.88 16.40 Industry, PA (McKeels Service - Rt. 68)

East Liverpool, OH (Water Department)

Weirton, WV ( Water Tower, Collier Way)

I 51 5-E 8.00 Aliquippa, PA (Sheffield Substation)

I 2-25

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-2 Graph of Annual Average Concentration: Gross Beta in Air Particulates Beaver Valley Power Station REMP Environmental Air Particulate Samples - Gross Beta 0.20 0.18_....


Average of 9 Indicator Locations E 0.16

  • -. -- A--- Control Location Pre-Operational value (0.07 pCi / cubic neter) 0.12

- Required LLD (0.01 pC I liter)

-No Reporting Level for Gross Beta 0.10 0 0.08 A0 0.06 _4-~

0.04 0.02- U~W U7 0.00

ýb ýb 1 1<3 0 * -CP 1410 le 2-26

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM 1 C. Monitoring of Sediments and Soils

1. Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt. Soil samples may vary from sand and silt I to a heavy clay with variable amounts of organic material.
2. Sampling Program and Analytical Techniques I
a. Program River bottom sediments were collected semi-annually above the Montgomery Dam, in the vicinities of the Beaver Valley discharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 2-1 and are shown in Figure 2-3.

Soil samples are collected every three years. They were collected at each often (10) locations during 2006 and are not due to be collected again until 2009. At each location, twelve (12) core samples (3" diameter by 2" deep) are gathered at prescribed points on a 10 foot radius circle. Each location is permanently marked with reference pins. Each set of samples is systematically selected by moving along the radius in such a manner as to assure representative undisturbed samples. Sampling locations are listed in Table 2-1 and are shown in Figure 2-3.

Bottom sediments and soils are analyzed for gamma-emitting radionuclides.

b. Analytical Procedures I Gamma Emitter Analysis of Sediment or Soil: Analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry.

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I 2-27

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-4 and Figure 2-5.
a. Sediment Gamma Spectrometry: A total of six (6) sediment samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40, Thalium-208, Lead-212, Lead-214, Bismuth-214, Ra-226 and Ac-228, was detected in four of four (4 of
4) indicator samples and two of two (2 of 2) control samples.

Cesium-137: This radionuclide was identified in three of four (3 of 4) indicator samples and two of two (2 of 2) control samples. The results were similar to previous years (current years range = 0.08 to 0.09 pico Curie / gram), and less than the pre-operational level of 0.4 pico Curie / gram. Also, SINCE Cesium-137 was identified at the indicator locations (downstream) and at the control location (upstream), THEN it was not due to plant effluent releases and is most likely residual contamination due from previous nuclear weapons tests.

Cobalt-58: Radionuclide Cobalt-58 was identified in one of four (1 of 4) indicator samples and zero of two (0 of 2) control samples. The samples that indicated Cobalt-58 were obtained at the shore line of the main outfall facility. The results were similar to previous years (current years range = 022 to 0.22 pico Curie / gram), even though this data is greater than the pre-operational level of 0.098 pico Curie / gram.

Cobalt-60: Radionuclide Cobalt-60 was identified in one of four (1 of 4) indicator samples and zero of two (0 of 2) control samples. The samples that indicated Cobalt-60 were obtained at the shore line of the main outfall facility. The results were similar to previous years (current years range = 0.51 to 0.51 pico Curie / gram), even though this data is slightly greater than the pre-operational level of 0.4 pico Curie / gram Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required sediment sampling and analysis schedule during the report period.

Summary: The identification of Cobalt-58 and Cobalt-60 at the shore line of the main outfall facility is not unusual, because the plant discharges these radionuclides in liquid waste effluents. The analyses are consistent with discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report period did not exceed the release limits set forth in the Offsite Dose Calculation Manual.

2-28

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

__ I

b. Soil Gamma Spectrometr: A total often (10) soil samples were analyzed by gamma spectrometry. Naturally occurring Potassium-40, Thalium-208, Lead-212, Lead-214, Bismuth-214, Ra-226 and Ac-228, was detected in nine of nine (9 of 9) indicator samples and one of one (1 of 1) control samples.

Cesium- 137: This radionuclide was identified in nine of nine (9 of 9) indicator samples and one of one (1 of 1) control samples. The results were similar to previous years (current years range = 0.13 to 0.27 pico Curie / gram), and less than the pre-operational level of 1.2 pico Curie / gram.

c. Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required soil sampling and analysis schedule during the report period. However, the sample site for the Control location was re-located during the report period. Specifically, due to construction at the previous location, the sample site was moved to the Collier Way Water Tower, which is also the current Control location for the air particulate sampler.

Moving the Control location for soil samples does not adversely impact the accuracy or reliability of sample collection.

d. Summary: SINCE Cesium-137 was identified at the indicator locations and at the control location, THEN it was not due to plant effluent releases, and is most likely residual contamination due from previous nuclear weapons tests.

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2-29 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-3 Environmental Monitoring Locations - Shoreline Sediments and Soil Sample Site Distance Type No. Sector (miles) Sample Point Description 13 11-SSW 1.49 Hookstown, PA (Old Meyer Farm) 22 8-SSE 0.28 South of BVPS, Transmission Lines 27 7-SE 6.19 Aliquippa, PA (Brunton Farm) 29A 3-NE 8.09 Beaver, PA (Nicol Farm)

Soil 30a 4-ENE 0.43 Shippingport, PA (Cooks Ferry Substation) 32a 15-NW 0.74 Midland, PA (North Substation) 46b 3-NE 2.66 Industry, PA (Willows Inn - Rt. 68) 47a 14-WNW 4.89 East Liverpool, OH (Water Department) 48a 10-SSW 15.56 Weirton, WV (Collier Way Water Tower) 51a 5-E 7.99 Aliquippa, PA (Sheffield Substation) 2A 13-W 0.31 BVPS Outfall Vicinity Sediment 49a 3-NE 4.93 Industry, PA (Upstream Montgomery Dam) 50 12-WSW 11.77 New Cumberland, WV (Upstream of Dam 2-30

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-4 I

Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & Cobalt-60 in Sediment U

Beaver Valley Power Station REMP Cs-I37 Sediment Trends - Outfall Vicinity I 1000.00 I

100.00 ---- ----------------- -----.- Cs-137

- ~ Control Location Cs-137 Pre-Operational Cs-137 (0.4 pCi / gram)

,00-,---------Cs-137 Required LLD (180 pCi/gm) --

I 1000-----~----- - - iNo Reporting Level for Sediment E

I 0

CL 0.0 0.10 - - - - - - - - - - - - - - - - - --

I 0.01 I Beaver Valley Power Station REMP I

100.00 Co-58 & Co-60 Sediment Trends - Outfall VicinityI RU- Co-58 I

- Unit 2 Pre-Operational Mean: Co-58 (0.098 pcVgm)

II -

a

-No Co-60 Unit 2 Pre-Operational Mean: Co-60 (0.40 pCi/gram)

Required LLD for Co-58 or Co-60 No Reproting Lirrit for Co-58 or Co-60 I

E10.00------- -- -- -- -- -- -- -- -- -- -- -- -A--------Ttl-- ----------------------- I la\. '

AA

/ I"' a I 1.00------------- .1 41 4 4P 0. 4 4 A4 In I

I

.*01 * ." . .* .

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2-31

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-5 Graph of Annual Average Concentration: Cesium-137 in Soil Beaver Cs-137Valley Soil Power Station REMP Trends (Tri-Ennial) 124 S1.0 ----------------------------------------------------------------. ~~o~cLo

  • " ---<v-Cs- 137

.m 1.0 1 Control Location-CP Re-operational Cs-1 37 (1.2 pCi / gram)

E 0.8 --------------------- ------------------------- Reporting Level for Soil W-No E

0 0.2 0.0

, ,-40 '

2-32

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM D. Monitoring of Feed Crops and Food Products I

1. Characterization of Farm Products According to the 2002 Census of Agriculture (1), there were 645 farms in Beaver County. Total market value of production (Crops and Livestock) was $10,828,000.00. Some of the principal I

sources of revenue (>$50,000.00) are as follows:

Milk and Other Dairy Products from Cows $4,719,000.00 Cattle and Calves $1,387,000.00 I

Nursery, Greenhouse, Floriculture and Sod $1,129,000.00 I

Other Crops and Hay $893,000.00 Vegetables, Melons, Potatoes and Sweet Potatoes $843,000.00 I Grains, Oil Seeds, Dry Beans and Dry Peas $567,000.00 Poultry and Eggs $523,000.00 I Cut Christmas Trees, and Short Rotation Woody Crops $285,000.00 Fruits, Tree Nuts and Berries $198,000.00

$85,000.00 I

Other Animals and Other Animal Products Horses, Ponies, Mules, Burros, and Donkeys Sheep, Goats and their Products

$81,000.00

$60,000.00 U

Hogs & Pigs Aquaculture Undisclosed Amount Undisclosed Amount I

2. Sampling Program and Analytical Techniques I
a. Program I

Representative samples of Feed Crops (cattle feed) are collected monthly from the nearest dairy farm (Searight Dairy). See Figure 2-6. Each sample is analyzed by gamma spectrometry. I Food products (vegetables) are collected at garden locations during the growing season.

Leafy vegetables, (e.g.; cabbage) are obtained from Shippingport, Georgetown, and Industry, Pennsylvania. Samples are also obtained from the control location in Weirton, I

West Virginia. All samples are analyzed for gamma emitters by gamma spectranetry.

Samples are also analyzed by radiochemical analysis for Iodine- 131. I

() http:/lwww.nass.usda.govlcensus/censusO2/profilesupalcp42007.PDF I

I 2-33

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b. Procedures Gamma Emitter Analysis of Feed: Analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high resolution germanium detector is utilized with this system. Food samples are loaded into tare weight 300 or 150 ml plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters.

Iodine-131 Analysis of Food Crops: Analysis is performed by radiochemistry. A stable iodide carrier is added to a chopped sample, which is then leached with a sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. 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.

2-34

I Beaver Valley Power Station RTL A9.690E Enclosure 3 I

2006 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM i

3. Results and Conclusions 3 A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-7.
a. Feed Gamma Spectrometry: A total of twelve (12) samples were analyzed by gamma spectrometry. Naturally occurring Potassium-40 was identified in twelve of twelve (12 of
12) samples. Naturally occurring Beryllium-7 was found in seven of twelve (7 of 12) samples.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required feedstuff sampling and analysis schedule during the report period.

Summary: The data from the feedstuff analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the feedstuff in the vicinity of the site during the report period

b. Food Iodine- 131: A total of four (4) samples were analyzed for Iodine- 131. No detectable concentrations were present in the three (3) indicator samples or the one (1) control sample.

Gamma Spectrometry: A total of four (4) samples were analyzed by gamma spectrometry.

Naturally occurring Potassium-40 was identified in three of three (3 of 3) indicator samples and one of one (lof 1) control samples. No other radionuclides were identified.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required foodstuff sampling and analysis schedule during the report period.

Summary: The data from the foodstuff analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the foodstuff in the vicinity of the site during the report period.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-6 Environmental Monitoring Locations - Feed Crop and Food Product Sample Site Distance Type No. Sector (miles) Sample Point Description Feed 25 10-SSW 2.10 Hookstown, PA (Searight Farm) 10a 4-ENE 1.02 Shippingport, PA Food 15a 14-WNW 3.55 Georgetown, PA 46a 3-NE 3.39 Industry, PA 48a 10-SSW 16.54 Weirton, WV 2-36

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-7 Graph of Annual Average Concentration: Cesium-137 in Feed and Food Beaver Valley Power Station REM P Cs-137 Feed and Food Product Trends 100 e--.-Cs-137 (Feed)

- Cs-137 (Food)

Cs-137 Pre-operational Results 10------------------------------- Cs- 137 Required LLD (80 pCi/kg) Wet---------

No Reporting Level for Feed of Food C.)

E

.4 0,01

,4AQ,I , *

"q*b , * , * , *&*,* ,

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM E. Monitoring of Local Cow and Goat Milk

1. Description - Milch Animal Locations Samples of fresh milk are obtained from milch animals at locations and frequencies noted in Table 2-1. The milk is analyzed for its radioiodine content, gamma emitters, strontium-89 and strontium-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 3, Land Use Census.

2. Sampling Program and Analytical Techniques
a. Program Cow milk was collected from the two (2) reference dairy farms within a 10-mile radius of the BVPS. These milk samples were obtained at the Searight Dairy Farm (2.097 miles SSW) and the Brunton Dairy Farm (6.158 miles SE).

Cow milk and goat milk were collected from three (3) other dairy farms within a 10-mile radius of the BVPS site. These milk samples were obtained at the Moore Farm (2.120 miles SW), the Collins Dairy Farm (3.547 miles SE) and the Halstead Dairy Farm (5.097 miles SSW), and were selected based on milch animal surveys and evaluations of meteorological data (i.e.; deposition parameters). They were added to the sampling program to ensure the highest potential milk pathway for radioiodine uptake is evaluated. The dairies are subject to change based upon availability of milk or when more recent data (milch animal census, and/or change in meteorological conditions) indicate other locations are more appropriate.

Cow milk was also collected from the one (1) control location dairy farm outside of the 10-mile radius. These milk samples were obtained at the Windsheimer Dairy Farm (10.476 miles SSW).

The milk sample from the Searight Dairy Farm is collected and analyzed weekly for Iodine-131 using a method that ensures 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. The monthly and/or bi-weekly sample is analyzed for Strontium-89, Strontium-90, principle gamma emitters (including Cesium-137 by high resolution germanium gamma spectrometry), and Iodine-131 high sensitivity analysis The location of each is shown in Figure 2-8 and described below.

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2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Approximate Distance and Direction Collection Site Dairy Number of Animals from Midpoint between Period I 25* Searight Dairy being Milked 46 Cows Unit 1 and Unit 2 Reactor 2.097 miles SSW January thru I

948 McCleary Road December Hookstown, PA I 27 Brunton Dairy 88 Cows 6.158 miles SE January thru 3681 Ridge Road Aliquippa, PA December I

69 Collins Dairy 289 Calhoun Road 4 Goats 3.547 miles SE January, and June thru October I

Aliquippa, PA 96 Windsheimer Dairy 74 Cows 10.476 miles SSW January thru December I

RD #11 Burgettstown, PA Halstead Dairy January thru I

5.097 miles SSW December 113 104 Tellish Drive Hookstown, PA 64 Cows I

114* Moore Farm 10 Goats 2.120 miles SW April thru 982 State Route 168 September I Hookstown, PA

  • Highest potential pathway dairies based on evaluation of deposition parameters I

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b. Procedure Iodine-131 Analysis of Milk: The milk samples are chemically prepared, and then analyzed with a low-level beta counting system.

Gamma Emitter Analysis of Milk: This is determined by gamma spectrometry analysis of a I liter Marinelli container of milk.

Strontium-90 Analysis of Milk: The milk samples are prepared by adding a 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 in-growth of yttrium-90 (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 Strontium-90 activity.

Strontium-89 Analysis of Milk: The Strontium-89 activity is determined by precipitating strontium carbonate (SrCO 3) 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 by gravimetric means.

3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-9.
a. Strontium-89: A total of one-hundred-eight (108) milk samples were analyzed for Strontium-89 during the report period. Strontium-89 was not detected in any of the eighty seven (87) indicator samples, nor was it detected in any of the twenty-one (21) control samples.
b. Strontium-90: A total of one-hundred-eight (108) milk samples were analyzed for Strontium-90 during the report period. Strontium-90 was detected in eighty-two of eighty-seven (82 of 87) indicator samples and twenty-one of twenty-one (21 of 21) control samples. The levels detected were attributable to previous nuclear weapons tests and are within the normally expected range.
c. Gamma Spectrometry: A total of one one-hundred-eight (108) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40 was present in eighty-seven of eighty-seven (87 of 87) indicator samples and twenty-one of twenty-one (21 of 21) control samples. No other gamma-emitting radionuclides were identified during analysis.

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2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

d. Iodine- 131: A total of one-hundred-thirty-nine (139) milk samples were analyzed for I Iodine- 131 during the report period. Iodine- 13 1 was not detected in any of the one-hundred-eighteen (118) indicator samples, nor was it detected in any of the twenty one (21) control samples. All analyses were less than the 0.5 pico Curie / liter LLD value.
e. Deviations from Required Sampling and Analysis: The Bi-weekly Doe Goat milk sampling was interrupted during the report period. Specifically, the Doe Goats ceased production of milk during the winter months but was re-established in the spring and summer months (after breeding was completed). Although the Doe Goats could not be sampled during that period, the minimum Bi-weekly milk sampling requirements were still met. SINCE only four (4) Bi-weekly Dairy Cow locations (or Doe Goat locations) are required to be sampled, THEN the minimum requirements were met with the four (4) Dairy Cow milk samples. This condition and Associated Corrective Actions are documented in Condition Report No. CR06-01028-01, CR06-9984 and SAP Order 200197646-0170.
f. Summary: Based on all the analytical results and the comparison to pre-operational levels, the operation of BVPS did not contribute any measurable increase in radioactivity in the milk in the vicinity of the site during the report period.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-8 Environmental Monitoring Locations - Milk Site Distance Sample Type No. Sector (miles) Sample Point Description 25* 10-SSW 2.097 Hookstown, PA (Searight Farm) 27 7-SE 6.158 Aliquippa, PA (Brunton Farm)

Milk 69 7-SE 3.547 Aliquippa, PA (Collins Farm) 96 10-SSW 10.476 Burgettstown, PA (Windsheimer Farm) 113 10-SSW 5.079 Hookstown, PA (Halstead Farm) 114" 11-SW 2.120 Hookstown, PA (Moore Farm)

  • Dairies selected based on evaluation of deposition parameters 2-42

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-9 Graph of Annual Average Concentration: Iodine-131 in Milk I Beaver Valley Power Station REMP 1-131 Concentrations in Milk 14.0 4

Chernobyl Accident 12.0.-'

10.01970 WeaponsTesting ---

. 10. 0 .. . . . . . .

8.0 --. . . . .. -- - Average at the Indicator Location - - -

A---,---

Control Location S.. Re-Operational value (0.6 pCi / liter) 60- - - --- Required LLD (1 p /liter)

. -- Reporting Level (3 pO/ liter) 4.0-..

4 --.-- -- .

2.0 &  % ----------- ----------------------------------------------

No le k 'Icea& 141 lea-a0** 1400 le 41 le 14P k 2-43

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM 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 beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams.

Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 pR/hr.

2. Locations and Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).

During the report period, there were a total of sixty-three (63) environmental TLD locations.

This is comprised of forty-four (44) offsite locations, along with nineteen (19) fence perimeter locations. The offsite TLD locations are plotted on Figure 2-10, but the fence perimeter locations are not plotted due to the large scale of the figure.

The 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 for a calendar quarter, in a specific holder that contains two (2) TLDs at each location.

3. Results and Conclusions A summary of the TLD results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-11.

TLD Analysis: During the report period, the average quarterly external exposure rate (as measured from TLD) was 18.1 mR at the sixty-three (63) indicator locations, and 19.4 mR at the Control location. This external exposure rate is comparable to previous years. As expected, there was some variation in external exposure rate among locations and seasons.

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2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required sampling schedule (i.e.; TLD placement) and analysis schedule (i.e.; TLD processing) during the report period.

Summary: The quarterly TLD external exposure rates are comparable to those of previous years. There was no evidence of anomalies that could be attributed to the operation of 3

BVPS. It should also be noted that the average external exposure rate at the indicator locations was less than average external exposure rate at the Control location. Based on all the analytical results and the comparison to pre-operational levels, the operation of BVPS did not contribute any measurable increase in external exposure in the vicinity of the site during the report period. The TLD exposure rates also confirm that changes from natural I radiation levels, if any, are negligible.

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I I Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Figure 2-10 Environmental Monitoring Locations - TLDs I

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RTL A9.690E I

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Figure 2-10 (Continued)

TLD Locations Site Distance SOUTHEAST QUADRANT Site Distance I

Sector Location Sector Location I

No. (miles) No. (miles) 27 7-SE 6.14 Brunton Dairy Farm 78 7-SE 2.72 Racoon Twsp Municipal Building Aliquippa, PA Raccoon Township, PA 45.1 6-ESE 1.92 Kennedy's Comers 79 8-SSE 4.46 106 State Route 151 Ted McWilliams Auto Body I

Raccoon Township, PA 51 5-E 8.00 Sheffield Substation 80 9-S 8.27 Park Office, State Route 18 Aliquippa, PA Raccoon Township, PA 59 6-ESE 0.99 236 Green Hill Road 82 9-S 6.99 2697 State Route 18 Aliquippa, PA Aliquippa, PA 76 77 6-ESE 6-ESE 3.80 5.52 Raccoon Elementary School Raccoon Township, PA 3614 Green Garden Road 94 8-SSE 2.25 McCleary & Pole Cat Hollow Road Hookstown, PA I Aliquippa, PA Site No.

Sector Distance (miles)

NORTHWEST Location QUADRANT Site No.

Sector Distance (miles)

Location I I

15 14-WNW 3.75 Post Office 87 14- 7.04 50103 Calcutta Smith's Ferry Road Georgetown, PA WNW 32 15-NW 0.75 North Substation 88 15-NW 2.74 110 Summit Road Midland, PA Midland, PA 47 14-WNW 4.88 Water Department 89 15-NW 4.72 488 Smith's Ferry Road 60 13-W 2.51 I East Liverpool, OH 444 Hill Road Georgetown, PA 90 16-NNW 5.20 Ohioville, PA 6286 Tuscarawras Road Midland, PA I

86 13-W 6.18 1090 Ohio Avenue 93 16-NNW 1.10 104 Linden - Sunrise Hills Site Sector Distance East Liverpool, OH NORTHEAST QUADRANT Location Site Sector Distance Midland, PA Location I

I No. (miles) No. (miles) 10 3-NE 0.94 Post Office 70 1-N 3.36 236 Engle Road 4-ENE Shippingport, PA Industry, PA 28 1-N 8.60 Sherman Farm 71 2-NNE 6.01 First Western Bank Beaver Falls, PA Brighton Township, PA 29B 30 3-NE 4-ENE 7.97 0.43 Friendship Ridge Beaver, PA Cook's Ferry Substation 72 73 3-NE 4-ENE 3.25 2.48 Ohioview Lutheran Church - Rear Industry, PA 618 Squirrel Run Road I

Shippingport, PA Industry, PA 45 46 5-E 3-NE 2.19 2.49 Christian House Baptist Chapel, State Rte 18 Raccoon Township, PA Midway Drive 74 75 4-ENE 5-E 6.92 4.08 137 Poplar Avenue (CCBC)

Monaca, PA 117 Holt Road I

Industry, PA Aliquippa, PA 46.1 2-NNE 3-NE 2.28 McKeel's Service, State Route 68 Industry, PA SOUTHWEST QUADRANT 91 2-NNE 3.89 Pine Grove Road & Doyle Road I

I Site Distance Site Distance Sector Location Sector Location No. (miles) No. (miles) 13 11-SW 1.49 Old Meyer Farm 84 11-SW 8.35 Senior Center Hookstown, PA Hancock County, WV 85 12- 5.73 2048 State Route 30 I

14 11-SW 2.53 Hookstown, PA WSW 48 10-SSW 16.40 Collier Way Water Tower 92 12- 2.81 Georgetown Road Substation Weirton, WV WSW Georgetown, PA 3.69 Millcreek United Presbyterian Church 95 10-SSW 2.37 832 McCleary Road I

81 9-S Hookstown, PA 83 10-SSW 4.26 735 Mill Creek Road 2-47 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-11 Graph of Annual Average Exposure: Direct Radiation in Environment Beaver Valley Power Station REMP Environmental TLD Trends I 0.22------------------------------------------------------------- ------------

0.20 0.16 A. ---- Al A & "k

'U E 0.14 _________-_________________

S 0.16 ..............................-- 'A' -----------------

01 Average of 63 Indicator Locations 1 0.12 --- -A-- .Control Location (Weirton WV)

R0e-Operational Value (0.2 mrrem / day) 0.et210 ,

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I Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM G. Monitoring of Fish N

1. Description During the report period, fish collected for the radiological monitoring program included carp, channel catfish, brown bullhead, freshwater drum and red horse.
2. Sampling Program and Analytical Techniques
a. Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectroscopy. Fish sampling locations are shown in Figure 2-12.
b. Procedure A sample is prepared in a standard tare weight 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 I A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-13.

I Gamma Spectrometry: A total of twelve (12) fish samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in 3

any of the six (6) indicator samples, nor were they detected in any of the six (6) control samples.

Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required fish sampling and analysis schedule during the report period.

Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the Ohio River fish population during the report period.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-12 Environmental Monitoring Locations - Fish Site Distance Sample Type No. Sector (miles) Sample Point Description 2A 13 0.2 BVPS Outfall Vicinity Fish 49a 3 5.0 Industry, PA (Upstream Montgomery I I _ I_ IDam) 2-50

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-13 Graph of Annual Average Concentration: Cesium-137 in Fish Beaver Valley Power Station REMP Cs-137 Concentrations - Fish 10000.000 1000.000 100.0 00 -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

E .-..-... Cs-137

-

  • Control Location - Ibntgomery Dam 2 Reoperational (0.014 pai/ gm)

CL 10.000-----------------Unit t*E - Required LLD (150 p / gm) 1! 1.000 - ---------------- Reporting Level (2000 pCi / gi o*0P 0.100 000---t "---4a "---l""I--I--4-f-------- "l------I---I" -- I--I----I--I*-

0.001 4..` .0:

  • 00 P 0PAl 0 Aý 2-51

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM 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 user is East Liverpool, Ohio which is approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream use river water for cooling purposes.

Groundwater occurs in large volumes in the gravel terraces which 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 National Climate Data Center (http://climvis.ncdc.noaa.gov/cgi-bin/cag3/state-map-display.pl) indicates the total annual precipitation during the report period was 47.66 inches.

2. Sampling and Analytical Techniques
a. Surface (Raw River) Water The sampling program of river water includes three (3) sampling points along the Ohio River. Raw water samples are collected daily at the East Liverpool (Ohio) Water Treatment Plant [River Mile 41.2], and the made into weekly composite sample. One automatic river water sampler is located at the ATI-Allegheny Ludlam (formerly J&L Steel) 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. A weekly grab sample is taken upstream of the Montgomery Dam [River Mile 29.6]. The weekly grab sample and automatic water sample are then made into a monthly composite sample from each location. In addition, a quarterly composite sample is prepared for each sample point.

The weekly grab samples upstream of the Montgomery Dam are analyzed for bdine-131.

The monthly composites are analyzed for gamma emitters. The quarterly composites are analyzed for tritium.

Locations of each sample point are shown in Figure 2-14.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b. Drinking Water (Public Supplies)

Drinking water (i.e.; treated water) is collected at both the Midland, PA and East Liverpool, OH Water Treating Plants. An automatic sampler at each location collects 20-40 ml every 20 minutes, and then made into a weekly composite sample. The weekly composite sample from each location is analyzed for Iodine- 131.

Monthly composites are made from the weekly samples, and are analyzed by gamma spectrometry. Quarterly composites are analyzed for tritium. Locations of each sample point are shown in Figure 2-14.

c. Groundwater Semi-annual grab samples were collected from three (3) locations within four (4) miles of the site (see Figure 2-14). These locations are:

One (1) well in Shippingport, PA One (1) well in Hookstown, PA One (1) well in Georgetown, PA Each ground water sample is analyzed for tritium and by gamma spectrcnetry.

d. Precipitation Precipitation is collected at Shippingport, PA, East Liverpool, OH, and Weirton, WV.

Precipitation, when available, is collected each week and then made into quarterly composite samples. The quarterly composites are analyzed for tritium and gamma emitters. Locations of each sample point are shown in Figure 2-14.

e. Procedures Gamma Analysis of Groundwater: The analysis is performed on water samples by placing one liter of the sample into a Marinelli container and analyzing the sample on a high resolution germanium gamma spectrometry system.

Tritium Analysis of Groundwater: The tritium is determined in water samples by liquid scintillation analysis.

Iodine-131 Analysis of Groundwater: The sample is chemically prepared, and analyzed with a low-level beta counting system.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions A summary of the analysis results of water samples (surface water, drinking water, ground water and precipitation) during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-15.
a. Surface Water Tritium: A total of twelve (12) surface water samples were analyzed for Hydrogen-3 (Tritium) during the report period. Tritium was not detected in any of the eight (8) indicator samples, nor was it detected in any of the four (4) control samples.

Gamma Spectrometry: A total of thirty-six (36) surface water samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples.

Iodine-1 31: A total of fifty-two (52) surface water control samples were analyzed for Iodine-131 using radiochemical methods during the report period. Iodinel31 was detected in thirty-seven of fifty-two (37 of 52) weekly control samples, of which two (2) analyses exceeded the reporting level of 2 pico Curie / liter. The results were similar to previous years, (current years range = 0.3 to 2.1 pico Curie / liter). The positive results were detected at the Control location, which is five (5) miles upstream (not influenced by BVPS operation). Identification of Iodine- 131 during the report period was most likely due to medical diagnostic and treatment procedures. (

Reference:

CR07-12344 and SAP Order 200197646-0190).

b. Drinking Water Tritium: A total of twelve (12) drinking water samples were analyzed for Tritium during the report period. Tritium was not detected in any of the eight (8) indicator samples, nor was it detected in any of the four (4) control samples.

Gamma Spectrometry: A total of thirty-six (36) drinking water samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides Aere not detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples.

Iodine-13 1: A total of one hundred-fifty-six (154) drinking water samples were analyzed for Iodine-131 (using radiochemical methods) during the report period.

Iodine- 131 was detected in forty-nine of one-hundred-two (49 of 102) indicator samples and thirty-seven of fifty-two (37 of 52) control samples. SINCE all of the positive results at the downstream location did not exceed the positive results from the upstream surface water Control location, THEN the positive results were not influenced by BVPS operation, and were most likely due to medical diagnostic and treatment procedures.

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Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

c. Groundwater 3 Tritium: A total of six (6) groundwater samples were analyzed for Tritium during the report period. Tritium was not detected in any of the four (4) indicator samples, nor was it detected in any of the two (2) control samples.

Gamma Spectrometry: A total of six (6) groundwater samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the (4) indicator samples, nor were they detected in any of the two (2) control I

samples.

d. Precipitation Tritium: A total of twelve (12) precipitation samples were analyzed for Tritium during the report period. Tritium was detected in three of eight (3 of 8) indicator samples, but was not detected in any of the four (4) control samples. The positive results are consistent with previous years data (current range = 197 - 286 pico Curie / liter, with an LLD of 200 pico Curie / liter), which is less than the pre-operational level of 300 pico I Curie / liter. Identification of Tritium at this location is not unusual, because the plant discharges tritium in gaseous waste effluents. Specifically, the tritium activity is consistent with discharge data of authorized gaseous effluent releases. All gaseous effluent releases during the report period did not exceed the release limits set forth in the Offsite Dose Calculation Manual.

Gamma Spectrometry: A total of twelve (12) precipitation samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides werenot detected in any of the eight (8) indicator samples, nor were they detected in any of the four (4) control samples.

I

e. Deviations from Required Sampling and Analysis Schedule: During November 2006, I the automatic drinking water sampling station at Midland, PA (Site No. 4) was found to have an unusually low volume in the collection vessel on two (2) separate occasions.

The sampling apparatus was repaired, but SINCE the sampling volume was not adequate for the period October 31, 2006 thru November 14, 2006, THEN the analyses from these samples were not considered valid. Therefore, the Iodine-131 analysis data for this period was adjusted to represent an average of the previous week and the following week analysis. This condition and associated Corrective Actions are described in Condition Report CR06-9951, and SAP Order 200197646-0160.

f. Summary: Data from the water sample analyses demonstrate that BVPS did not I contribute a significant increase of radioactivity in the local river, in the drinking water, in the well water, or in the 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 2-55

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-14 Environmental Monitoring Locations -

Ground Water, Surface Water, Drinking Water and Precipitation Site Distance Sample Type No. Sector (miles) Sample Point Description Drinking 4 15 1.3 Midland, PA (Water Departmen)

Water 5 14 4.9 East Liverpool, OH (Water Department) 2.1 14 1.5 Midland, PA (ATI Allegheny Ludlam)

Surface Water 5 14 4.9 East Liverpool, OH (Water Department) 49a 3 5.0 Industry, PA (Upstream Montgomery Dam) 11 3 0.8 Shippingport, PA Ground Water 14a 11 2.5 Hookstown, PA 15a 14 3.7 Georgetown, PA 30 4 0.5 Shippingport, PA (Cook's Ferry Substation)

Precipitation 47 14 4.9 East Liverpool, OH ( Water Department) 48 10 16.3 Weirton WV (Water Tower, Collier Way) 2-56

I Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water & Drinking Water I Beaver Valley Power Station REMP U

2.5 1-131 Surface Water& Drinking Water Trendsl I 2.0

-- Down Stream Dinldng Water - lVidland I

U 1.5 x Down Stream Drinldng Water - East Liverpool Control Location - Up Stream Surface Water Unit 2 DW reoperational p

-Required LLD (1pa0/ liter)

(0.23 pa liter)

I Z- Reporting Level (2 p/ liter)

I U=1.0 0.

I I

CL0.5 A

I 0.0 &i A NC~'AIVl" I

I I

I I

2-57 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water Beaver Valley Power Station REMP Tritium Trends - Surface Water 100000

.-. Indicator Mean (pa/ I

-a -Control Location (pCi /I)

- 10000 Pre- Operational (300 pCi/I) ." "_-_

, , Required LLD (2,000 pC/I)

CL.

  • Reporting Level Surface Water (30,000 pCi/I) o "6 10 0 - -..---..-.

0 -.-.--. .-..- -.-

00 100 2-58

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-17 Graph of Annual Average Concentration: Tritium in Ground Water Beaver Valley Power Station REMP Tritium Trends - Ground Water I 1o0 8

101i.oIIl . ý ý I j ý .

10N01 "" Ný-

1 1 ,01 o" 1 1, 0,3 01 4,0 e l 2-59

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-18 Graph of Annual Average Concentration: Tritium in Drinking Water Beaver Valley Power Station REMP Tritium Trends - Drinking Water 100000

- -- Indicator Mean A Control Location (pai / I)

Pre- Operational (300 pCi/l) 10000 - Required LLD (2,000 pCi/I-

.,,,,.,,- Reporting Level Drinking Water (20, 000 pCi/I)

C.)

100.

10 -O---- -- -'----- -- --

100 -

101,1; qz 4ý p ý40

  • e 1§ e 'i 0 e 2-60

Beaver Valley Power Station RTL A9.690E I

2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM i

I. Estimates of Radiation Dose to Man

1. Pathways to Man - Calculational Models i The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using computer codes for the ARERAS/MIDAS computer system. These computer codes are equivalent to NRC I

computer codes XOQDOQ2, GASPAR, and LADTAP. Dose factors listed in the Offsite Dose Calculation Manual are used to calculate doses from radioactive noble gases in discharge plumes. Beaver Valley effluent data, based on sample analysis were i

used as the radionuclide activity input.

All liquid and gaseous effluent radionuclides listed in the Annual Radioactive Effluent Release Report were input as source terms to the computer codes.

All batch and continuous gaseous effluent releases were included in the dose assessment calculations. The release activities are based on laboratory analysis.

Meteorological data collected by the Beaver Valley Power Station Meteorology System was also used as input to the computer codes. Except when more recent or specific data was available, the usage factors were obtained from the BVPS Final Environmental Statements or Regulatory Guide 1.109. The airborne effluent pathways evaluated provided population doses out to 50 miles.

All radioactive liquid effluents are released by batch mode after analysis by gamma spectrometry. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River via the main outfall (River Mile 35.0). The actual data I

from these analyses are tabulated and used as the radionuclide source term input to the computer code. Except when more recent or specific data was available, the usage factors were obtained from the BVPS Final Environmental Statements or Regulatory I

Guide 1.109. The liquid effluent pathways evaluated provided population doses out to 50 miles. I

2. Results of Calculated Population Dose to Man - Liquid Effluent Releases During the report period, the calculated dose to the entire population (-4 million people) within 50 miles of the plant is presented in Table 2-4 for BVPS liquid effluent releases. Also shown in this table is a comparison to natural radiation exposure.
3. Results of Calculated Population Dose to Man - Gaseous Effluent Releases During the report period, the calculated dose to the entire population (-4 million i people) within 50 miles of the plant is presented in Table 2-5 for BVPS airborne effluent releases. Also shown in this table is a comparison to natural radiation exposure. The doses include the contribution of all pathways.

2-61

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

4. Conclusions Based upon the estimated dose to individuals from the natural background radiation exposure in Tables 2-4 and 2-5, 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 0.00006% 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.

2-62

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-4 Comparison of Natural Radiation Exposure Versus Calculated Population Dose to Man - Liquid Effluent Releases TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (a)

Ambient Gamma Radiation 58 millirem / year Radionuclides in Body 40 millirem / year Global Fallout < 1 millirem /year Radon 198 millirem / year Average Individual 296 millirem / year (Total from all sources shown above)

(a) National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 0-50 mile Population Dose from BVPS Liquid Effluent Releases Man-millirem Largest Isotope Contributor Total Dose 552 Tritium Average Dose Tritium (per Individual)

Comparison of Individual Dose BVPS Liquid Effluent Releases Versus Natural Background Radiation millirem BVPS Liquid Effluent Release Dose 0.0001380 Natural Radiation Exposure 296 2-63

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-5 Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Gaseous Effluent Releases TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (a)

Ambient Gamma Radiation = 58 millirem / year Radionuclides in Body = 40 millirem / year Global Fallout < 1 millirem / year Radon 198 millirem / year Average Individual = 296 millirem / year (Total from all sources shown above)

(b)

National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 0-50 mile Population Dose from BVPS Gaseous Effluent Releases Man-millirem Largest Isotope Contributor Total 103 Tritium Average 0.0000258 Tritium (per Individual) 0 T Comparison of Individual Dose BVPS Gaseous Effluent Releases Versus Natural Background Radiation millirem BVPS Gaseous Effluent Release Dose 0.0000258 Natural Radiation Exposure 296 2-64

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 3 - LAND USE CENSUS i A Land Use Census was conducted August 31 through September 22, 2006 to comply with:

" Unit 1 and Unit 2 Technical Specification 6.8.6b, Item I

" BVPS REMP procedure 1/2-ENV-04.02, "Milch Animal Sampling Location Determination & ODCMProcedure 1/2-ODC-3.03, Control 3.12.2 Action Statements a and b Compliance Determination" The Land Use census indicates that no changes were required in the current sampling locations, and no changes were required to the methodology used for determination of offsite dose from plant releases. A numerical summary of the Land Use Census results are provided in Table 3-1.

The following information is also provided to clarify the Land Use Census as documented in letter NPD3NRE:0381, dated September 26, 2006:

" Nearest Resident:

The current location has not changed since the previous census.

The current location is at 211 Ferry Hill Road, Shippingport, PA (0.406 miles NE).

" Nearest Garden >500 sqft:

The current location has not changed since the previous census.

The current location is at 238 State Route 168, Hookstown, PA (0.760 miles SSW).

" Nearest Dairy Cow Milked:

The current location has not changed since the previous census.

The current location is at Searight Dairy, 948 McCleary Road, RD 1, Hookstown, PA (2.097 miles SSW).

" Nearest Doe Goat Milked:

The current location has not changed since the previous census.

The current location is at 982 State Route 168, Hookstown, PA (2.120 miles SW).

NOTE: this is not the nearest location, but it is the nearest location providing samples.

" Nearest Beef Cattle:

The current location has not changed since the previous census.

The current location is at 105 Shippingport Road, Shippingport, PA (1.405 miles ENE).

I 3-1 i

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 - LAND USE CENSUS

" Proiection for 2007 Dairy Cow Sampline Locations:

Using a linear regression analysis of deposition parameters (D/Q), Dairy Cow sampling locations were determined to remain at the same locations used in 2006:

- Searight Dairy, 948 McCleary Road, RDI, Hookstown, PA (2.097 miles SSW)

- Halstead Dairy, 104 Tellish Drive, Hookstown, PA (5.079 miles SSW)

- Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.158 miles SE)

- Windsheimer Dairy, RD 1 Burgettstown, PA (10.476 miles SSW).

" Projection for 2007 Doe Goat Sampling Locations:

The linear regression analysis also indicated that the Doe Goat sampling locations will remain at the same locations used in 2006:

- Moore Farm, 982 State Route 168, Hookstown, PA (2.120 miles SW)

- Collins Farm, 289 Calhoun Road, Aliquippa, PA (3.547 miles, SE).

3-2

I Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 5 SECTION 3 - LAND US E CENSUS Table 3-1 Location of Nearest Resi lents, Gardens, Dairy Cows, Doe Goats and Beef Cattle I

DAIRY DOE BEEF RESIDENTS GARDENS COWS GOATS CATTLE SECTOR 0 to 5 miles 0 to 5 miles (mile.l 0 to 5 miles (mniles) 0 to 5 miles (milesl 0 to 5 miles (miles)I 5

(miles)

N 1.584 2.899 None None 3.461 NNE 1.661 None None None 3.110 NE 0.406 2.711 None None 4.869 ENE 0.598 1.028 None None 1.405 E 0.429 1.979 None 3.402 2.620 ESE 0.476 1.713 None 4.285 2.952 SE 1.583 1.802 None 3.547 1.974 SSE 1.102 2.127 None None 4.573 S 1.399 2.276 3.851 None 2.337 SSW 0.760 0.760 2.097 1.818 1.832 SW 1.453 1.453 None 2.120 1.452 WSW 1.394 2.832 None 3.849 1.544 W 2.204 None 2.701 None 3.176 WNW 2.742 None None None None NW 0.885 1.033 None 5.125 4.277 NNW 0.902 1.353 2.442 None 2.416 NOTE: Distances shown in Bold print are the nearest location for that receptor I

3-3 I

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM A. Split Sample Program (Inter-Laboratory Comparison, Part I of 2): BVPS participates in a split sample program with the Pennsylvania Department of Environmental Protection (PADEP) in support of their nuclear power plant monitoring program.

  • BVPS provided split samples to PADEP throughout the report period. The shared media and number of locations were typically comprised of; milk (1), surface water (3), sediment (1), fish (1), and food crops (2).

" PADEP has co-located continuous air particulate & air iodine sample stations with four (4) of the BVPS locations.

" PADEP has co-located TLDs with twenty-four (24) of the BVPS TLDs.

B. Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2): BVPS participates in a spike sample program with an Independent Laboratory. This program is used to independently verify sample analyses performed by the BVPS Contractor Laboratory.

  • Acceptance Criteria 1: The NRC criteria listed in NRC Inspection Procedure 84750, 12/4/90, Inspection Guidance 84750-03 is used as acceptance criteria for comparisons of results of spiked samples between the Contractor Lab and the Independent Lab. These comparisons are performed by dividing the comparison standard (Independent Lab result) by its associated uncertainty to obtain the resolution. The 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. However, in such cases where the counting precision of the standard yields a resolution of less than 4, a valid comparison is not practical, and therefore, not performed.

NRC Criteria Resolution Ratio

<4 --

4-7 0.50-2.00 8- 15 0.60-1.66 16-50 0.75-1.33 51-200 0.80-1.25

> 200 0.85-1.18 Acceptance Criteria 2: BVPS also has self imposed acceptance criteria. That criteria requires the percent difference between the Contractor Lab Activity and the Independent Lab Calculated Activity to agree by + 20%.

4-1

Beaver Valley Power Station 2006 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE U INTER-LABORATORY COMPARISON PROGRAM Participation in an Inter-Laboratory Comparison Program is required by BVPS Unit 1 and 2 Technical Specification 6.8.6b, Item 3. For the report period, the requirement was met by the Contractor Lab analyzing NIST traceable spiked samples supplied by an Independent Lab.

During the report period, BVPS used (Environmental, Inc., Midwest Laboratory - Northbrook, IL) as the Contractor Laboratory, and (Analytics- Atlanta, GA) as the Independent Laboratory.

The spiked samples included air particulate filter papers, charcoal cartridges, water samples, i and milk samples. The samples were submitted by the Independent Laboratory to the Contractor Laboratory for analysis. The "spiked to" values were used for calculating comparison Acceptance Criteria.

  • Spiked Milk & Water Samples: The spiked sample results (i.e.; the BVPS criteria) for each calendar quarter are reported in Table 4-1 through Table 4-4, respectively. The following summary is provided:

- A total of forty-eight (48) gamma spectrometry radionuclide analyses were I performed by the Contractor Laboratory on four (4) milk samples.

- A total of forty-eight (48) gamma spectrometry radionuclide analyses were i performed by the Contractor Laboratory on four (4) water samples.

- A total of four (4) chemical analyses for 1-131 were performed by the Contractor I Laboratory on four (4) milk samples.

- A total of four (4) chemical analyses for 1-131 analyses were performed by the I Contractor Laboratory on four (4) water samples.

- A total of four (4) tritium analyses were performed by the Contractor Laboratory on I four (4) water samples.

- Comparison of results of the spiked milk and water samples showed acceptable i agreement with the NRC acceptance criteria. All one-hundred-eight (108) analyses met the NRC acceptance criteria

- Comparison of results of the spiked milk and water samples showed acceptable agreement with BVPS acceptance criteria. All but one (1) of the one-hundred-eight (108) analyses met the BVPS acceptance criteria.

I I

I 4-2

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM

'Spiked Filter Paper and Charcoal Cartridge Samples: The spiked sample results for each calendar quarter are also reported in Table 4-1 through Table 4-4, respectively. The following summary is provided:

- Gross Beta (Cesium- 137) analyses were performed by the Contractor Laboratory on two (2) filter paper samples.

- Iodine- 131 analyses were performed by the Contractor Laboratory on two (2) charcoal cartridge samples.

- Comparison of results of the spiked filter paper and charcoal cartridge samples showed acceptable agreement with the NRC acceptance criteria. All four (4) analyses performed by the Contractor Laboratory met the NRC acceptance criteria.

- Comparison of results of the spiked filter paper and charcoal cartridge samples showed acceptable agreement with the BVPS acceptance criteria. All four (4) analyses performed by the Contractor Laboratory met the BVPS acceptance criteria C. Conclusions

" Results of Split Sample Program:

The split sample program is coordinated by the state, and the results are not provided with this report.

" Results of Spike Sample Program:

Based on the Inter-Laboratory comparison data, BVPS considers all analyses provided throughout the report period by the Contractor Laboratory to be acceptable with respect to both accuracy and measurement. A comparison of the data, to the BVPS Acceptance Criteria, is provided in the following tables.

4-3

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I Table 4-1 Inter-Laboratory Comparison Program I Spiked Samples - 1 st Quarter Sample Type and Percent Difference Between Contractor Lab Activity and I

Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity Sr-89 (Contr. Lab - Ind. Lab) / Ind. Lab

-7.68%

I Sr-90 1-131 (Chemical) 1-131 1.82%

-2.84%

3.13%

I 03/23/2006 Water Ind Lab: E4947-93 Ce-141 Cr-51 Cs-134 2.99%

3.76%

-6.73%

I Con. Lab: SPW-1566 Cs-I 37 Co-58 1.76%

0.68% I Mn-54 2.82%

Fe-59 Zn-65 8.33%

0.34%

I Co-60 -1.96%

03/23/2006 Water Ind. Lab: E4946-93 H-3 8.55%

I Con. Lab: SPW-1567 Sr-89 Sr-90

-11.82%

-4.55% I Milk 1-131 (Chemical) 1-131 Ce-141

-7.05%

-4.23%

2.31%

I 03/23/2006 Ind. Lab: E4948-93 Con. Lab: SPMI-1568 Cr-51 Cs-134 Cs-137

-4.04%

-11.07%

-1.24%

I Co-58 Mn-54

-5.62%

1.51% I Fe-59 -0.11%

Zn-65 Co-60

-2.16%

-7.11% I Filter Paper 03/23/2006 Ind. Lab: E4949-93 Con. Lab: SPAP-1569 Cs-137 (Gross Beta) 15.83% I Charcoal Cartridge 03/23/2006 Ind. Lab: E4950-93 1-131 -11.65% I Con. Lab: SPCH-1570 I

4-4

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-2 Inter-Laboratory Comparison Program Spiked Samples - 2 nd Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) I Ind. Lab Sr-89 -3.05%

Sr-90 -18.00%

1-131 (Chemical) -2.13%

1-131 -0.80%

Ce-141 4.70%

Water Cr-51 2.38%

06/0812006 Ind. Lab: E5011-93 Cs-1 34 -3.11%

Cs-1 37 2.63%

Con. Lab: SPW-3846 Co-58 6.17%

Mn-54 3.53%

Fe-59 7.63%

Zn-65 6.33%

Co-60 0.38%

Water 06/08/2006 Ind. Lab: E5010-93 H-3 -9.53%

Con. Lab: SPW-3847 Sr-89 -8.68%

Sr-90 -19.00%

1-131 (Chemical) 4.60%

1-131 -2.86%

Milk Ce-141 -2.45%

Cr-51 -7.57%

06/08/2006 Ind. Lab: E5012-93 Cs-1 34 -11.65%

Cs-137 0.26%

Con. Lab: SPMI-3848 Co-58 -0.80%

Mn-54 2.53%

Fe-59 6.60%

Zn-65 -0.59%

Co-60 -3.02%

4-5

Beaver Valley Power Station RTL A9.690E I 2006 Annual Radiological Environmental Operating Report Enclosure 3 I

SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I Table 4-3 Inter-Laboratory Comparison Program I

Spiked Samples - 3 rd Quarter Percent Difference Between I

Sample Type and Contractor Lab Activity and Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) / Ind. Lab I Sr-89 -9.33%

Sr-90 1-131 (Chemical) 0.77%

18.5%

I 1-131 1.00%

Water Ce-141 Cr-51 3.52%

-3.23%

I 09/14/2006 Ind. Lab: E5086-93 Con. Lab: SPW-6271 Cs-134 Cs-137 Co-58

-8.16%

1.56%

-0.63%

I Mn-54 Fe-59 4.35%

6.67% I Zn-65 1.55%

Water Co-60 -2.92%

I 09/14/2006 Ind. Lab: E5085-93 H-3 -2.91%

Con. Lab: SPW-6270 Sr-89 -9.55%

I Sr-90 1-131 (Chemical) 1-131

-7.50%

21.76%

8.51%

I 09/14/2006 Milk Ind. Lab: E5087-93 Ce-141 Cr-51 Cs-134

-1.63%

-5.82%

-7.18%

I Con. Lab: SPMI-6272 Cs-137 Co-58 Mn-54

-1.20%

-0.46%

0.09%

I Fe-59 Zn-65 Co-60 7.73%

2.41%

-3.21%

I 09/14/2006 Filter Paper Ind. Lab: E5088-93 Cs-i137 8.28%

I Con. Lab: SPAP-6273 (Gross Beta) 09/14/2006 Charcoal Cartridge Ind. Lab: E5089-93 1-131 -6.63%

I Con. Lab: SPCH-6274 I 4-6

Beaver Valley Power Station RTL A9.690E 2006 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-4 Inter-Laboratory Comparison Program Spiked Samples - 4h Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) fInd. Lab Sr-89 -4.11%

Sr-90 -1.67%

1-131 (Chemical) 7.43%

1-131 0.43%

Ce-141 -0.28%

Water Cr-51 -0.69%

12/07/2006 Ind. Lab: E5167-93 Cs-134 -9.72%

Cs-i137 1.83%

C o-58 2.3%

Con. Lab: SPW-8748 Co-58 2.35%

Mn-54 3.61%

Fe-59 9.09%

Zn-65 5.35%

Co-60 -1.54%

Water 12/07/2006 Ind. Lab: E5166-93 H-3 -1.92%

Con. Lab: SPW-8747 Sr-89 -12.22%

Sr-90 5.00%

1-131 (Chemical) 13.94%

1-131 1.83%

Ce-141 -1.60%

Milk Cr-51 -0.39%

12/07/2006 Ind. Lab: E5168-93 Cs-134 -13.74%

Cs- 137 0.80%

C o-58 0.8%

Con. Lab: SPMI-8751 Co-58 -0.48%

Mn-54 5.14%

Fe-59 8.13%

Zn-65 4.45%

Co-60 -2.67%

4-7