L-09-140, RTL A9.690E, 2008 Annual Radiological Environmental Operating Report, Enclosure 3

RTL A9.690E, 2008 Annual Radiological Environmental Operating Report, Enclosure 3

ML091890214
Person / Time
Site:	Beaver Valley
Issue date:	07/01/2009
From:	FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
L-09-140 RTL A9.690E
Download: ML091890214 (95)

Text

RTL A9.690E Enclosure 3 Beaver Valley Power Station - Units 1 & 2 2008 Annual Radiological Environmental Operating Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station - Units 1 & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX Report Preparation and Submittal Requirements: The Beaver Valley Power Station (BVPS)

Annual Radiological Environmental Operating Report (AREOR) was prepared and submitted in accordance with the requirements contained in the following documents:

• BVPS Integrated Technical Specifications, Administrative Control 5.6.1

" Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-3.03, Attachment T, Control 6.9.2, "Controlsfor RETS and REMP Programs"

• BVPS procedure 1/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications"

• BVPS procedure 1/2-ENV-02.01, "Description of Overall Radiological Environmental MonitoringProgram"

• NUREG-1301, "Offsite Dose CalculationManual Guidance: Standard RadiologicalEffluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No.], April 1991"

• BVPS SAP Order No. 200197646-0400 is associated with an evaluation of historical TLD trends.

• BVPS SAP Order No. 200197646-0440 is associated with documenting upstream (control location) surface water 1-131 analyses above the reporting level.

" BVPS SAP Order No. 200197646-0490 is associated with documenting the interruption of air particulate and iodine sampling.

" BVPS SAP Order No. 200197646-0610 is associated with documenting the adjustments made to the placement of TLDs in the field.

" BVPS SAP Order No. 200197646-0640 is associated with documenting unusual gross beta analysis results of air particulate filter media.

" BVPS SAP Order No. 200197646-0650 is associated with documenting interruption of goat milk sampling.

• BVPS SAP Order No. 200197646-0720 is associated with documenting a missed surface water sample.

Report Overview:

The AREOR provides a detailed summary of the BVPS 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. During the report period, the BVPS radioactive effluent releases (as performed in accordance with the Radiological Effluent Technical Specification (RETS) program), did not exceed the limits identified in the BVPS Operating License Technical Specifications, and/or the ODCM. The results of the REMP verify that the effluent releases did not impact the environment with measurable concentration of radioactive materials and/or levels of radiation that are higher than expected.

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and INDEX i Description of Pre-operational REMP (1974 - 1975): 1 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 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 I

summarized in Table 2-3 of this report.

Description of Operational REMP (1976 - Present):

The operational REMP program was initiated during calendar year 1976 and continued through i the report period. During the past thirty-three (33) 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 and compared during the report period, and are described as follows:

" Control Samples: These samples are collected from areas that are beyond measurable i 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 to the environment surrounding the BVPS site. During the report period, three hundred fifty five (355) analyses were performed on samples from the control locations. In addition, eight (8) analyses were completed for TLDs at the control locations. Results of the 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 four hundred eighty two (1482) analyses were performed on samples collected from eighty seven (87) indicator locations. In addition, five hundred three (503) analyses were completed for TLDs at the indicator locations. Results of the analyses from i the indicator locations are also summarized in Table 2-2 of this report.

• Comparisons: Current analysis results from the indicator samples were compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels were attributable to BVPS operation.

Determination of Environmental Impact

• 2008 Sample Media and Analyses: Results for drinking water, surface water, precipitation, groundwater, shoreline stream sediment, fish, cow milk, goat milk, feedstuff, foodcrops, air I

particulate and air radioiodine media remained consistent with previous data. Minor increases and decreases were noted in most sample media, and any positive results attributable to the BVPS operation were consistent with station data of authorized radioactive I

discharges, and were within limits permitted by the operating license and the ODCM. Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear iii I

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX weapons tests, other man-made sources, and to the normal statistical fluctuation for activities near the Lower Limit of Detection (LLD). The pre-operational values were not exceeded during the report period.

" Airborne Exposure Pathway: This ODCM required pathway was evaluated via sampling of 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 ODCM required pathway was evaluated via measurement of 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.

" Ingestion Exposure Pathway: This ODCM required pathway was evaluated via sampling of milk, fish, and foodcrops (leafy vegetables).

For milk samples, Strontium-90 (attributable to past atmospheric weapons testing), was detected at levels similar to those of previous 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.

Foodcrop (leafy vegetation) samples indicated naturally occurring Potassium-40 at average environmental levels.

• Waterborne Exposure Pathway: This ODCM pathway was evaluated via samples of drinking water, ground (well) water, surface (river) water and river sediment.

Water samples were analyzed for tritium and gamma-emitting radionuclides. Tritium was not identified in any of these water samples. Iodine-131 analysis of drinking water indicated positive analyses, but the values were consistent with Iodine-131 at the upstream surface (river) water control location, and was not due to liquid effluent releases from BVPS.

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, and most likely due from previous nuclear weapons tests. Cobalt-58 and Cobalt-60 were 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. The activity detected at this sample location is consistent with discharge data of authorized liquid iv

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I effluent releases, and all liquid effluent releases during the report period did not exceed the release concentration limits set forth in the ODCM. I

• Other Exposure Pathways: In addition to the samples collected from the exposure pathways described above, other media (i.e., precipitation, feedstuff and soil) were also collected. Results were consistent with previous years, with no degrading trends.

" Osite Groundwater Monitoring: A total of six (6) offsite groundwater samples were i collected and analyzed for Tritium and by gamma spectrometry during the report period.

The samples were collected on a semi-annual basis from three (3) locations within four (4) miles of the site. The locations included one (1) well in Shippingport PA, one (1) well in Hookstown PA, and one (1) well in Georgetown PA. No gamma-emitting radionuclides were detected in the analyses. All tritium results were less than the pre-operational value.

" Supplemental Sample Sites: The REMP program includes supplemental sampling sites in addition to the required sites set forth in the ODCM. The supplemental sites include five (5) air sampling sites, one (1) surface water site, three (3) groundwater sites, three (3) precipitation sites, two (2) sediment sites, ten (10) soil sites, one (1) local large dairy, and one (1) milk animal feedstuff site. The soil sites are on a triennial sample frequency. They were not sampled in 2008 and are scheduled to be sampled until 2009.

• Population Dose vs. Natural

Background:

During the report period, the total calculated 0- i 50 mile population dose was 402 man-mrem (liquid releases), and 144 man-mrem (gaseous releases). The average individual population dose from BVPS operation was much less than

<1 mrem. For information, the National Academy of Sciences 1990 BEIR Report shows that I the typical dose to an individual from background (natural radiation exposure including radon) is an estimated average of 296 mrem per year. The following graph illustrates that the average individual population dose was not affected from BVPS operation. I Figure i-1 Graph of Annual Average Population Dose: BVPS Dose and Natural Background Dose I 1000.000000 100.0000000 Average Population Dose7 10.0000000

• 1.00000000--

W 1.01000000 0.10010000 0.0001000 - __--._---_-- - 4_-

0.0000100 1. 1 1 Ne O Ne -15 Ie

• BVPS Average Population Dose (rnRem)

Background Population Dose (296 rrem) v!

_ _ _ _Natural

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Summary: During the report period, 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 BVPS operational REMP program was followed throughout the report period. The results demonstrate the adequacy of radioactive effluent control at BVPS, and that BVPS operation did not adversely affect the surrounding environment. Positive results attributable to 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).

Inter-laboratory Comparison Programs:

• Split Sample Program: BVPS shared split samples with the Pennsylvania Department of Environmental Protection (PADEP) in support of their nuclear power plant monitoring program. The shared media and number of locations were typically comprised of; milk (1),

surface water (3), river sediment (1), fish (1), foodcrops (2), co-located air particulate/air iodine (4), and TLD (24). The split sample program was coordinated by the state, and the results are not provided with this report.

" Spike Sample Program: Spiked samples were provided by an independent laboratory and then analyzed by the REMP contractor laboratory. The samples were provided throughout the report period and included water samples, milk samples, filter paper samples and charcoal cartridge samples. All one-hundred-sixteen (116) analyses performed by the contactor laboratory on the spiked samples met the NRC comparison criteria.

Special Reports:

SINCE no reporting levels were exceeded during 2008, THEN no Special Reports were required. For information, a Special Report shall be submitted to the NRC when (1) levels of radioactivity in an environmental sampling medium exceeds the limits specified in ODCM procedure 1/2-ODC-3.03, Attachment Q Table 3.12-2, and when (2) the results of the following calculation are >1.0 (for calculations performed when more than one radionuclide is detected in the sampling medium):

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

Land Use Census Results:

Highlights from the most recent Land Use Census are documented in letter NPD3NRE:0542, dated September 29, 2008 and are summarized as follows:

• Nearest Residence: The nearest residence has not changed since the previous census. The location remains at 211 Ferry Hill Road, Shippingport, PA (0.406 miles NE).

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I 9 Nearest Garden: The nearest garden >500 square feet has not changed since the previous census. The location remains at 238 State Route 168, Hookstown, PA (0.760 miles SSW). l

• Nearest Dairy Cow: The nearest dairy cow milked has not changed since the previous census.

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

e Nearest Doe Goat: The nearest doe goat milked has changed since the previous census.

However, SINCE this location cannot provide enough milk for sample analysis, THEN the location of the nearest doe goat will remain at the Collins Farm, 289 Calhoun Road, Aliquippa, PA (3.547 miles SE).

• PrevailingWinds: The prevailing wind direction for Ground Releases and Elevated Releasesn was identified by showing the highest deposition parameter (D/Q) in the East and ESE Sectors, respectively. The REMP properly monitors the environment with air particulate sampling stations in some sectors and with direct radiation TLDs in all sectors.

• 2009 Dairy Cow Sampling Locations: Using the results of the 2008 Land Use Census, the 2009 dairy cow milk sampling locations will remain at the same locations used in 2008. The locations are; Searight Dairy, 948 McCleary Road, RD1, Hookstown, PA (2.097 miles SSW),

I Halstead Dairy, 104 Tellish Drive, Hookstown PA (5.079 miles SSW), Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.158 miles SE), and Weindsheimer Dairy, RD 1 Burgettstown, PA (10.476 miles SSW).

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• 2009 Doe Goat Sampling Locations: Using the results of the 2008 Land Use Census, the i 2009 doe goat milk sampling location remain at the same location used in 2008. The location is at Collins Farm, 289 Calhoun Road, Aliquippa, PA (3.547 miles, SE).

• D/O for Milch Animal Locations: None of the 2008 milch animal sampling locations experienced a >20% increase in deposition parameter (D/Q).

• D/O for Offsite Dose Determination: There was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, a linear regression analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% more than the offsite dose previously calculated using current ODCM methodology.

• D/Q Historical Comparison: There was no adverse trend in D/Q when comparing data to the ODCM default D/Q values, which validates that there was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% more than the offsite dose previously calculated using current ODCM methodology. Therefore, a change in ODCM Receptor location and/or a change to meteorology at the current ODCM Receptor location were not required.

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX Deviations, Changes and Adjustments to the Normal Sampling Program

" Deviation from Normal Milk Sampling & Analysis Schedule: The Bi-weekly Doe Goat milk sampling was interrupted during the report period. Although the Doe Goats could not be sampled during that period, the minimum sampling and requirements were still met. This issue was documented in SAP Order 200197646-0650.

" Deviation from Normal Surface Water Sampling and Analysis Schedule: The automatic drinking water sampling station at Midland, PA was interrupted on one (1) occasion during the report period. This issue was documented in SAP Order 200197646-0720.

" Deviation from Normal Air Particulate & Iodine Sampling and Analysis Schedule: The air particulate and iodine sampling stations were interrupted on seven (7) separate occasions during the report period. This issue was documented in SAP Order 200197646-0490.

" Adjustments to TLD Placement: An evaluation of TLD placement was performed to ensure the intent of the criteria established in ANSI N545-1975 was met. As a result of this evaluation, several of the TLDs were lowered and/or relocated to adjacent/nearby sites. In summary, the reported exposure results of all previous BVPS TLD data for the sixty-four (64) TLD sites were considered valid and did not require adjustment. Results of the evaluation were documented in SAP Order 200197646-0610 and letter NPD3NRE:0538.

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and INDEX 3 EXECUTIVE

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3 Report Preparation and Submittal Requirements ............................................... ii R eport Overview ..................................................................................

Description of Pre-operational REMP (1974 - 1975) ........................................

Description of Operational REMP (1976 - Present) ..........................................

ii iii iii I

Determination of Environmental Impact .......................................................

Inter-laboratory Comparison Programs .........................................................

Special R eports ....................................................................................

iii vi vi 3

Land Use Census Results ......................................................................... vi Deviations, Changes and Adjustments to the Normal Sampling Program ................ vii SECTION 1 - INTRODUCTION A. Radiation Fundamentals .................................................................... 1-1 B.

C.

D.

Radiation and Radioactivity ...............................................................

Units of Measurement ......................................................................

Lower Limit of Detection ..................................................................

1-1 1-4 1-4 3

E. Scope and Objectives of the REMP Program ........................................... 1-5 F. Description of the Beaver Valley Site .................................................... 1-5 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Environmental Radioactivity Monitoring Program .....................................

1. Program Description ..................................................................

2-1 2-1 3

2. Summary of Results .................................................................... 2-5

3. Quality Control Program .............................................................. 2-5 I

4. Program Changes ...................................................................... 2-5 B . A ir M onitoring ............................................................................... 2-23

1. Characterization of Air and Meteorology ..........................................

2. Air Sampling Program and Analytical Techniques ...............................

2-23 2-23 I

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

C. Monitoring of Shoreline Stream Sediment and Soil ....................................

1. Characterization of Shoreline Stream Sediment and Soil .........................

2-24 2-28 2-28 I

2. Sampling Program and Analytical Techniques .................................... 2-28

3. Results and Conclusions .............................................................. 2-29 2-34 I

D. Monitoring of Feedstuff and Foodcrops ..................................................

1. Characterization of Farm Products ................................................... 2-34

2. Sampling Program and Analytical Techniques .................................... 2-34 l

3. Results and Conclusions .............................................................. 2-36 E. Monitoring of Local Cow and Goat Milk ................................................. 2-39

1. Description - Milch Animal Locations ............................................. 2-39

2. Sampling Program and Analytical Techniques .................................... 2-39

3. Results and Conclusions .............................................................. 2-41 F. Environmental Radiation Monitoring ..................................................... 2-45

1. Description of Regional Background Radiation and Sources .................... 2-45

2. Locations and Analytical Techniques ............................................... 2-45

3. Results and Conclusions .............................................................. 2-45 ix I

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and INDEX G . M onitoring of Fish ............................. .............................................. 2-50

1. D escription .............................................................................. 2-50

2. Sampling Program and Analytical Techniques ........................ 2-50

3. Results and Conclusions ....... ................................ 2-50 H. Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation .... 2-53

1. Description of Water Sources ................................... ............. ,..... ...... 2-53

2. ' Sampling and Analytical Techniques .............................. 2-54

3. Results and Conclusions ....................................... 2-56 I. Estimates of Radiation Does to Man .................... 1.................................. 2-63

1. Pathways to Man - Calculational Models ............... 2-63

2. Results of Calculated Population Dose to Man - Liquid Effluent Releases.., 2-63

3. Results of Calculated Population Dose to Man - Gaseous Effluent Releases. 2-63

4. Conclusions .................................... .................................... 2-64 SECTION 3 - LAND USE CENSUS A. Land Use Census Overview .............................................................. 3-1 B. N earest Residence ................................................................ ........... 3-1 C. N earest G arden >500 sqft ................................................................. 3-1 D. Nearest Dairy Cow Milked ................................................................. 3-1 E. Nearest Doe Goat Milked ..... *............................................................ 3-1 F. Projections for 2009 Dairy Cow Sampling Locations .................... ............ .3-1 G. Projections for 2009 Doe Goat Sampling Locations ................................... 3-2 H. D/Q for Milch Animal Locations ........................................................ 3-2 I. D/Q for Offsite Dose Determination ................................. . 3-2 J. D/Q Historical Comparison ........... ..................................................... 3-2 SECTION 4 - SPLIT SAMPLE AND SPIKE SAMPLE, INTER-LABORATORY COMPARISON PROGRAM A. Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2) .................... .4-1 B. Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2) .................. 4-1 C. C onclusion s ................................................................................... 4-3 x

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX U AREOR 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 ............................................ 2-65 Table 2-5 Comparison of Natural Background Exposure Versus Calculated Population Dose to Man - Gaseous Effluent Releases ............................................... 2-66 Table 3-1 Location of Nearest Residents, Gardens, Dairy Cows, Doe Goats and Beef C attle ............................................................. ......................................................... 3-3 Table 4-1 Inter-Laboratory Comparison Program, Spiked Samples - 1st Quarter .............. 4-4 Table 4-2 Inter-Laboratory Comparison Program, Spiked Samples - 2 nd Quarter ............. 4-5 Table 4-3 Inter-Laboratory Comparison Program, Spiked Samples - 3rd Quarter ............. 4-6 1 Table 4-4 Inter-Laboratory Comparison Program, Spiked Samples - 4th Quarter .............. 4-7 I

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX AREOR FIGURES Figure i-1 Graph of Annual Average Population Dose: BVPS Dose and Natural B ackground D ose ........................................................................... v Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver V alley Pow er Station ........................................................................ 1-7 Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations ........................ 2-26 Figure 2-2 Graph of Annual Average Concentration: Gross Beta in Air Particulates ........... 2-27 Figure 2-3 Environmental Monitoring Locations - Shoreline Sediments and Soil ............... 2-31 Figure 2-4 Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & 60 in S edim ent ...................................................................................... 2-32 Figure 2-5 Graph of Annual Average Concentration: Cesium-137 in Soil ........................ 2-33 Figure 2-6 Environmental Monitoring Locations - Feedstuff and Foodcrops .................... 2-37 Figure 2-7 Graph of Annual Average Concentration: Cesium-137 in Feedstuff and Foodcrops ..................................................................................... 2-38 Figure 2-8 Environmental Monitoring Locations - Milk ............................................ 2-43 Figure 2-9 Graph of Annual Average Concentration: Iodine-131 & Sr-90 in Milk .............. 2-44 Figure 2-10 Environmental Monitoring Locations - TLDs .......................................... 2-47 Figure 2-11 Graph of Annual Average Exposure: Direct Radiation in Environment ............. 2-49 Figure 2-12 Environmental Monitoring Locations - Fish ............................................. 2-51 Figure 2-13 Graph of Annual Average Concentration: Cesium-137 in Fish ....................... 2-52 Figure 2-14 Environmental Monitoring Locations - Ground Water, Surface Water, Drinking W ater and Precipitation ..................................................................... 2-58 Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water, and D rinking W ater .............................................................................. 2-59 Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water ................. 2-60 Figure 2-17 Graph of Annual Average Concentration: Tritium in Ground Water ................. 2-61 Figure 2-18 Graph of Annual Average Concentration: Tritium in Drinking Water ............... 2-62 xii

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION A. Radiation Fundamentals Radiation is the conveyance of energy through space. For example, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. All matter consists of atoms, which are comprised of positively charged particles (protons), negatively charged particles (electrons), and non-charged/neutral particles (neutrons). The relatively large particles (protons and neutrons) are packed tightly together in a cluster at the center of the atom called the nucleus, while the smaller particles (electrons) orbit around the nucleus. In an electrically neutral atom, the negative charges of the electrons are balanced by the positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together. Other attractive forces between the protons and neutrons keep the densely packed protons from repelling each other, and prevent the nucleus from breaking apart.

B. Radiation and Radioactivity The following provides an alphabetical glossary of terms associated with radiation, radioactivity, and the radioactive decay process. The terms discussed include Alpha Particles, Beta Particles, Gamma Rays, Genetic Effects, Half-life, Ionization, Isotopes, Neutrons, Radiation, Radioactive Decay, Radionuclides and Somatic Effects.

Alpha Particles: Particulate and electromagnetic radiation each travel through matter differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and interactions with other atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles.

Beta Particles: Beta Particles: Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either +1 or -1. Because they are so small and have a low, charge, they do not collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel, through several meters of air, but may be stopped by a thin piece of metal or wood.

Gamma Rays: Gamma rays are pure energy and'travel at the speed of light. They. have no measurable charge or mass, and generally travel much farther than alpha or beta particles before

'being absorbed. After repeated interactions, the gamma ray loses its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high-energy gamma radiation can travel a considerable distance, where as, low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of Lead or concrete may be needed to effectively shield gamma rays.

Genetic Effects: The effects of ionizing radiation which are observed in the offspring of the exposed individual that could occur as a result of ionizing radiation interacting With the genes in the human cells.

Half-life: The length of time an atom remains radioactive is defined in terms of half-life, which is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Radionuclides that have infrequent emissions have a long half-life, where as, radionuclides. that have more frequent emissions have a short half-life.

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION U Ionization: Through interactions with atoms, alpha, beta, and gamma radiation lose their energy.

When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same I

number of protons as electrons, thus, the number of positive and negative charges cancel, in which the atom is electrically neutral. When one or more electrons are removed, an ion is formed.

Ionization is one of the processes that may result in damage to biological systems.

Isotopes: A group of identical atoms containing the same number of protons make up an element.

In fact, the number of protons an atom contains determines its chemical identity. For instance, all 3

atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms.

However, the number of neutrons in the nucleus of an element may vary. Atoms with the same number of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or deficit in the number of neutrons in the nucleus. Radionuclides such as Uranium-238, Berylium-7 and Potassium-40 occur naturally. Others are man-made, such as Iodine-131, Cesium-137, and Cobalt-60.

Neutrons: Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, neutrons are not of environmental concern since the neutron source at' nuclear power stations, is sealed within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slowly as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they,travel.

Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons.

Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as Cadmium, to absorb-the now thermal neutrons. 'Concrete is also used to form an effective neutron shield because it contains water molecules and can be easily molded around odd shapes.

I Radiation: This is the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation is I another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and particulate radiation. Electromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space.

Included in this category are gamma rays and X-rays. Particulate radiation consists of tiny, fast moving particles which, if unhindered, travel in a straight line through space. The three types of particulate radiation of concern to us are alpha particles, which are made up of 2 protons and 2 neutrons; beta particles, which are essentially free electrons; and neutrons. The properties of these I

types of radiation will be described more fully in the Range and Shielding section. .

I 1-2 'i

Beaver Valley Power Station *RTLA9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION Radioactive Decay: Radioactive atoms, over time, will reach a stable, non-radioactive state through a process known as radioactive decay,.which is the release of energy from'an atom through the emission of ionizing radiation. Radioactive atoms may decay directly to a stable state'or' may go through a series of decay stages, called a radioactive decay series, and produce several daughter products that eventually result in a stable atom. The loss Of energy through'radioactive decay may transform the atom into a chemically different element. For example, when Uranium-238 decays, it' emits an alpha particle and, as a result, the atomlses 2 protons and 2 neutrons. Since'the number of protons in the nucleus of an atom determines its' chemical identity, then when the Uranium-238 atom loses the '2 protons and 2 neutrons, it is transformed into an 'atom of Thorium-234. 'Thorium-234 is one of the 14 successive daughter products of Uranium-238. Radon is. another daughter product, and the decay -series ends with stable Lead-206. The following example is part of a known radioactive decay series, called the Uranium series, which begins with Uranium-238 and ends with Lead-206& The information provided.in *theupper portion of each block is the isotope name, while the information provided in the lower portion of each block is the half-life.

2 38 2 34 u

U 4.5E+9 Yr , 2.5E+5 Yr 1.2 2 K mp

'4

' 2 34 Th , 230 T 8.OE+4 Yr 24 d Beta Decay Alpha Decay 226 Ra I 1600 Yr 222R 3.82 d 2 18 214P 0 pO 21Op0 3.05 min 1.6E-4 s

• 138.4 d.

214'

~'(1 9.7 min 4.0 ~ d 20 6 Pb 21OPb Pb 26.8 min 23 Yr stable Radionuclides: See description for "isotopes".

Somatic Effects: The effects of ionizing radiation which developin the directly exposed individual, including an unborn child. Somatic effects can be divided further into acute and chronic effects.

Acute effects develop shortly after exposure to large amount of radiation. Chronic effects are a result of exposure to radiation over an extended period of time.:

1-3

Beaver Valley Power Station RTL A9.690E I 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION I C. Units of Measurement Activity.(Curie): This relates the number of atoms in a sample that disintegrate (decay) per unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci),isthe unit used to describe the activity of a material and indicates the rate at which the atoms of a radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. A smaller unit of the curie is used when discussing the low concentrations of radioactivity detected in environmental samples. For instance, the picocurie (pCi) represents one I

trillionth of a curie.

Absorbed Dose (rad): This is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and electromagnetic radiation.

The rad is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material (1 rad = 100 erg/gm). The rate of absorbed dose ,

is usually. given in rad/hr. The rad is not used to quantify biological damage caused by ionizing radiation.

Dose Equivalent (rem): Biological damage due to alpha, beta, gamma and neutron radiation may result from ionizing radiation. Some types of radiation, especially alpha particles which cause dense local ionization, can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or X-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing radiation. When the quality factor is multiplied by the absorbed dose (Rad), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radiation. The dose equivalent is measured in rem. An example of this conversion from absorbed dose (rad) to dose equivalent (rem) uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 Rad of alpha radiation = 20 rem. Since beta and gamma radiation each have a quality factor of 1, then 1 Rad of either beta or gamma radiation = 1 rem. Neutrons have a quality factor ranging from 2 to 10.

I In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the millirem, is often used, where as, one millirem (mrem) is equal to 1/1000 of a rem.

D. Lower Limit of Detection The Lower Limit of Detection (LLD) for environmental samples is a calculated value that represents an a-priori (before-the-fact) limit for the smallest concentration (i.e.; pCi per unit mass or volume) of radioactive material in a sample that will be detected with 95% probability, and with 5%

probability of falsely concluding that a blank observation represents a real signal. A calculated LLD must consider such analytical variables as standard deviation of the background counting rate, the counting efficiency, the sample size, the fractional radiochemical yield, the radioactive decay constant, and the elapsed time between sample collection and time of counting. 3 I

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION E. Scope and Objectives of the REMP Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of BVPS. Environmental sampling and analyses include 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 Operating Report (AREOR) for BVPS summarizes the Radiological Environmental Monitoring Program (REMP) conducted by the FirstEnergy Nuclear Operating Company during the report period.

F. Description of the Beaver Valley Site BVPS is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 453 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.

BVPS 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 8,800 cubic feet per second (minimum monthly average) to 107,400 cubic feet per second (maximum monthly average). The mean flow during the report period was 45,342 cubic feet per second.

Water temperature of the Ohio River typically varies from 34' Fahrenheit to 750 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 predominant wind direction is typically from the southwest in summer and from the west southwest in winter. The National Climate Data Center (http://www.ncdc.noaa.gov/oa/climate/research/cag3/v4.html) indicates the following data for the Pittsburgh, PA area:

• The total annual precipitation during the report period was 39.248 inches

• The average mean temperature during the report period was 50.9' Fahrenheit 1-5

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 U

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

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

No. of Reactor Coolant Loops No. of Steam Generators & Type 3

3 - Vertical 3

3 - Vertical I

Steam Used by Main Turbine Saturated Saturated I The BVPS units utilize two separate systems (primary.and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the I primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam I generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam/water cycle. I I

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Beaver Valley Power Station RTL A9.690E 2008 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 I

SHENANGO AIVEM DAM & RESERVOIR 20 40 MILES 1-7

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosureý 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM, A. Environmental Radioactivity Monitoring 'Program

1. Program Description The program consists of monitoring water, air, soil, river bottoms (sediment), feedstuff, vegetation, foodcrops, cow's 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 Sediment and Soil 2-D Monitoring of Feedstuff and Foodcrops 2-E Monitoring of Local Cow and Goat Milk

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

Beaver Valley Power Station 2008. Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Table 2-1 I Onerational Radiological Environmental Monitoring: Program Section Sample Type Sample Site No.

Sample Frequency Sample Preparation /

Analysis Frequency I 1 Air 13 Hookstown, PA (Old Meyer Farm) Continuous Weekly - Air Gross Beta Particulate &

Radionuclide

?7 28 29B 30 Aliquippa, PA (Brunton Farm)

Sherman Farm Beaver, Pa (Friendship Ridge)

Shippingport, PA (Cook's Ferry Substation)

Sampling with Sample Collection at least weekly Particulate Weekly - Charcoal (b)

Iodine-i 31 I

I 32 Midland, PA (North Substation) Quarterly Composite Gamma Scan 46.1 Industry, PA (McKeel's Service - Rt. 68) (c) 47 East Liverpool, OH (WaterDepartment) 48 (a) Weirton, WV (Water Tower - Collier Way) 1 1 51 Aliquippa, PA (Sheffield Substation) 2 Direct Radiation 10 13 14 Shippingport, PA (Post Office)

Hookstown, PA (Old Meyer Farm)

Hookstown, PA Continuous (TLD) Quarterly (I) Gamma Dose I 15 Georgetown, PA (Post Office) 27 28 29B Aliquippa, PA (Brunton Farm)

Sherman Farm Beaver, PA (Friendship Rid6ge)

U 30 Shippingport, PA (Cook's Ferry Substation) 32 33-44 45 Midland, PA (North Substation)

BVPS Site Perimeter Locations Raccoon Township, PA (Christian House Baptist Chapel - Rt. 18)

I 45.1 I

Raccoon Township, PA (Kennedys Corner) 46 Industry,.PA (Midway Drive) ,

46.1 Industry, PA (McKeel's Service - Rt. 68) 47 East Liverpool, OH (Water Department) 48 (a) Weirton, WV (Water Tower'- Collier Way) 51 52-56 59 Aliquippa, PA (Sheffield Substation)

BVPS Site Perimeter Locations 236 Green Hill Road I

60 Georgetown, PA (444 Hill Road) 70 71 72 73 Industry, PA (236 Engle Road)

Brighton Township, PA (First Western Bank)

Ohioview, PA (Lutheran Church - Rear) 618 Squirrel Run Road I

I 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 80 81 106 Rt. 151 - Ted McWilliams Auto Body Raccoon Township, PA (Park Office -Rt. 18)

Millcreek United Presbyterian, Church I

82 2697 Rt. 18 83 84 85 86 735 Mill Creek Road Hancock County, WV (Senior Center) 2048 Rt. 30 I

East Liverpool, OH (1090 Ohio Avenue) 87 88 89 90 50103 Calcutta Smith's Ferry Road Midland, PA (110 Summit Road)

Ohioville, PA (488 Smith Ferry Road)

Midland, PA (6286 Tuscarawras Road)

I 91 Pine Grove Road & Doyle Road 92 93 Georgetown, PA (Georgetown Road Substation) 104 Linden - Sunrise Hills I

Hookstown, PA (McCleary'& Pole Cat 94 95 111-112 Hollow Roads)

Hookstown, PA (832 McCLeary Road)

BVPS Site Perimeter Locations I

2-2

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 perational Radiological Environmental Monitoring Program Sample Sample Sample Preparation /

Section Type Site Sample Location Sample Frequency Analysis Frequency Analysis Tp No.

49a Weekly Grab 3 Surface a Industry, PA (Upstream of Montgomery Sample (h) Weekly Sample from Water (a) Dam) Site49 only Iodine-131 Weekly Intermittent Midland, PA (ATI Allegheny Ludlam) Composite Sample Monthly Composite Of 2.1 (h) Weekly Sample (c)

Gamma Scan Daily Grab Sample 5 East Liverpool, OH (Water Department) Collected Weekly Quarterly Composite (c)

(h) Tritium (H-3) 11 (a) Shippingport, PA (Upstream) Gamma Scan 4 Groundwater 14a Hookstown, PA (Downstream) Semi-Annual Semi-Annual Tritium (H-3) 15b Georgetown, PA (Downstream) 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) 2A BVPS Outfall Vicinity 6 Shoreline 49a Industry, PA (Upstream of Montgomery Semi-Annual Semi-Annual Gamma Scan Sediment (a) Dam)

New Cumberland, WV (Upstream of 50 Dam) 7 Milk Weekly (e) Weekly Samples from Weekly 25 Hookstown, PA (Searight Farm) . Searight only Iodine-131 from Searight only 27a (k) Aliquippa, PA (Brunton Farm) 69 (k) Aliquippa, PA (Collins Farm) Biweekly (f) When All other samples & Gamma Scan 96 (a) Burgettstown, PA (Windsheimer Farm) animals are on analyses are Biweekly Iodine-131 113 (k) Hookstown, PA (Halstead Farm) pasture; monthly at during grazing, but Strontium-89 other times Monthly during other Strontium-g9 114 (k) Hookstown, PA (Moore Farm) times 2A BVPS Outfall Vicinity Gamma Scan 8 Fish Industry, PA (Upstream of Montgomery Semi-Annual Composite of edible. on edible 49a Dam) parts by species (g) parts 10a Shippingport, PA Gamma Scan 9 Food 15a Georgetown, PA Annual at Harvest Composite of each Iodine-131 on Pr c s4 Products d 46aa Industry, Idsry PAPA if available sample species green v g tleafy be 48a Weirton, WV vegetables Feedstuff & 25 Hookstown, PA (Searight Farm) Monthly Monthly Gamma Scan 10 Summer Forage 13a Hookstown, PA (Old Meyer Farm) 11 Soil 22 South of BVPS, Transmission Lines Every Three (3) 12 Core Samples 3" Gamma Scan 27b Aliquippa, PA (Brunton Farm) Years Deep (2" diameter at (1997, 2000, 2003) each location approx. 10' 29A Beaver, PA (Nicol Farm) radius) 30a Shippingport, PA (Cook's Ferry Substation) 32a Midland, PA (North Substation) 46b Industry, PA (Willows Inn - Rt. 68) 47a East Liverpool, OH (Water Department) 48 (a) Weirton WV (Water Tower - Collier Way) 51a Aliquippa, PA (Sheffield Substation) 30 Shippingport, PA (Cook's Ferry Weekly grab 12 Precipitation Substation) samples when Quarterly Composite (c) Gamma Scan 47 East Liverpool, OH (Water Department) available Tritium (H-3) 48 (a) Weirton WV (Water Tower-Collier Way) 2-3

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Table 2-1 I Operational Radiological Environmental Monitoring Program Notes for Table 2-1 I

(a) Control Sample Station: These Locations which are presumed to be outside the influence of I

plant effluents.

(b)

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

control samples.

(c) Long-term composite samples are obtained from short-term composite samples at the specified I 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 />. I (e) Weekly milk sample from the Searight Dairy is analyzed for Iodine-1 31 only.

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

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

IF adequate sample size is available, THEN the sample is separated according to species, and I

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. I (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 49a, the weekly grab sample is obtained by I

a field technician.

(i) Two (2) TLDs are collected quarterly from each monitoring location. I (k) ODCM 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 RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

2. Summary of Results 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-I. Table 2-3 summarizes BVPS 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).

The conclusion from all program data is that the operation of BVPS has resulted in no significant changes to the environment.

3. Quality Control Program The Quality Control Program implemented by BVPS 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.

2-5

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I I

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Air Particulate and Radioiodine Unit of Measurement: (pico Curies / cubic meter)

I I

Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) ýb' Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (' Range 1b) Distance and Direction Range (h) Distance and Direction Range (b) Measurements Gross Beta 510

< 0.004 0.025 ( 459 / 459) 0.011 -0.051 No. 47 East Liverpool, OH Water Department 4.88 miles WNW 0.026 ( 51 / 51 0.013 - 0.045

) No. 48 Weirton, WV Water Tower Collier Way 0.025 ( 51 / 51 )

0.014 -0.048 0

I 16.40 miles SSW 1-131 510

<0.04 LLD( 0 /459 LLD( 0/459 LLD( 0/51 0 I

Gamma 40 I

Be-7 NA 0.081 ( 36 / 36 0.550 - 0.101

) No. 32 North Substation Midland 0.75 Miles NW 0.085 ( 4 / 4 0.068 *0.100

) No. 48 Weirton, WV Water Tower Collier Way 16.40 miles SSW 0.081 ( 4 / 4 0.067 - 0.098 NA I

Co-60 Cs-134

<0.0003

< 0.0004 LLD(

LLD(

0 / 36 0 / 36

)

)

LLD(

LLD(

0 /36 0 /36

)

)

LLD(

LLD(

0/4 0 /4

)

)

0 0

I Cs-137 Ba-La-140

< 0.0004

<0.0005 LLD(

LLD(

0 / 36) 0 / 36 )

LLD(

LLD(

0 /36) 0/36 )

LLD(

LLD(

0 /4 0/4

)

)

0 0

I 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)

I

'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) I I

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Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Drinking 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 of Analysis Detection Mean (fraction) IbI Name Mean (fraction) (bl Name Mean (fraction) (b) Reported (5)g DitneadDrcin neMaumns Measurement(b)

Performed LLD (" Range 'b Distance and Direction RanIt (b) Distance and Direction Range )

1-131 < 0.5 0.650 ( 58 / 104 ) No. 5 East Liverpool, OH 0.700 ( 33 / 52 ) No. 49 Industry. PA 0.900 ( 42 / 52 ) 0 156 0,300 - 2.000 Water Department 0.300 - 2,000 Upstream of 0.200 - 2.600 4.90 miles WNW Montgomery Dam 4.92 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 < 15 LLDI( 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 I

Enclosure 3 I

2008 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I I

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Surface Water Unit of Measurement: (pico Curies / liter)

I Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine 15 1 of Analysis Detection Mean (fraction) W Name Mean (fraction) Name Mean (fraction) (bl Reported Performed LLD "' Range N Distance and Direction Range M Distance and Direction Range Nj MeasurementsM 1-131 < 0.5 No. 49 Industry, PA 0.900 ( 42 / 52 0 52 Upstream of 0,200 2.600 Montgomery Dam 4.92 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 < 15 LLD( 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 2008 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 / 50-412 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Ground 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 of Analysis Detection Mean (fraction) IbI Name Mean (fraction) (b Name Mean (fraction) (b) Reported Performed LLD) ~ Range (b) Distance and Direction Range (b) Distance and Direction . Range (b) Measurements.W H-3 <200. LLD( 0 /4 ) LLD( 0/4 ) No.Il Shippingport, PA LLD( 0/2 ) 0 6 Upstream'

' 0.94 miles NE Gamma No. 11 Shippingport, PA 6  : Upstream 0.94 ýniles NE Mn-54. <5 LLD( 0/4 ) LLD( 0/4 ) LLD,( 0/2 0 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 LLD (0/2) 0

) . LLD(0/4 )

Ba-La'-140 <15 LLD( 0/4 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).

2-9

Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Precipitation Water Unit of Measurement: (pico Curies / liter)

I Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) b) Name Mean (fraction)(b) Name Mean (fraction)co) Reported Performed LLD W Range (b) Distance and Direction Range (b) Distance and Direction Range ) Measurements H-3 < 200 486 ( 2 / 8 ) No. 47 East Liverpool, OH 790 ( 1 /4 ) No. 48 Weirton, WV LLD ( 0 /4 ) 0 12 182 - 790 Water Department 790 -790 Water Tower 4.88 miles WNW Collier Way 16.40 miles SSW Gamma 12 Mn-54 <5 LLD( 0/8 ) 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 Zr-Nb-95

< 10

< 5 LLD(

LLD(

0/8 0 / 8

)

)

LLD(

LLD(

0/8 0 /8

)

)

LLD(

LLD(

0/4 0 /4

)

)

0 0

I Cs-134 Cs-137

<5

< 5 LLD(

LLD(

0/8 0 / 8

)

)

LLD(

LLD(

0/8 0 /8

)

)

LLD(

LLD(

0/4 0 /4

)

)

0 0

I Ba-La-140 < 15 LLD( 0 / 8 Nominal Lower Limit of Detection

) LLD( 0 /8 ) LLD( 0/4 ) 0 I

bMean 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)

I 2-10 I

Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Milk Unit of Measurement: (pico Curies / liter)

Type and Lower Number of Total Number Limit of All Indicator Locatiom Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) b) Name Mean (fraction) (" Name Mean (fraction) N Reported Performed LLD 4') Range (,) Distance and Direction Range (b) Distance and Direction Range (b) Measurements 1-131 < 0.5 LLD ( 0 / 104) LLD ( 0 / 104 No, 96Burgettstown, PA LLD( 0 /20 ) 0 124 Windsheimer Farm 10.48 miles SSW Sr-89 < 2.0 LLD( 0 /72 ) LLD( 0/72 No.96Burgettstown, PA LLD( 0/20) 0 92 Windsheimer Farm 10.48 miles SSW Sr-90 < 0.7 1.379 ( 66 / 72 ) No. 25 Hookstown, PA 1.845 ( 20 / 20 No. 96 Burgettstown, PA 0.995 ( 19 / 20 ) 0 92 0.600 -2.6 Searight Farm 1.300 - 2.500 Windsheimer Farm 0.600 - 1.900 2.10 miles SSW 10.48 miles SSW Gamma 92 K-40 < NA 1416 ( 72/ 72 ) No. 69 Alliquippa, PA 1630 ( 12 / 12 ) No. 96 Burgettstown, PA 1361 ( 20 / 20 NA 1067 - 1746 Collings Farm 1489 - 1746 Windsheimer Farm 1300 - 1507 3.55 miles SE 10.48 miles SSW Mn-54 <5 LLD( 0 / 72 ) LLD( 0 /72 ) LLD( 0 /20 0 Fe-59 < 10 LLD( 0 /72 ) LLD( 0 /72 LLD( 0/20 0 Co-58 < 5 LLD( 0 / 72 ) LLD( 0 /72 ) LLD( 0 /20 0 Co-60 < 5 LLD( 0 /72 ) LLD( 0 /72 ) LLD( 0 /20 0 Zn-65 < 10 LLD( 0 / 72 ) LLD( 0 /72 ) LLD( 0 /20 0 Zr-Nb-95 < 5 LLD( 0 /72 ) LLD( 0 /72 ) LLD( 0 /20) 0 Cs-134 <5 LLD( 0/72 ) LLD( 0/72 ) LLD( 0/20) 0 Cs-137 < 5 LLD( 0 / 72 ) LLD( 0 /72 ) LLD( 0 /20) 0 Ba-La-140 < 15 LLD( 0 /72 ) LLD( 0 /72 ) LLD( 0/20 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 I

2008 Annual Radiological Enviromnental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Enclosure 3 I

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 / 50-412 Location of Facility: Beaver County. Pennsylvania I

Reporting Period: Calendar Year - 2008 Medium: Fish I

Unit of Measurement: (pico Curies / gram) Wet Type and Lower Total Numbei Limit of of Analysis All Indicator Location Locations with Highest Annual N Detection Mean (fraction) Nb) Name I I Performed Gamma LLD "' Range N Distance and Direction I

Mn-54 Fe-59

< 0.05

< 0.10 LLD (

LLD(

0o 0/

LLD(

LLD(

0/

0/

0/

0/ 0 I

Co-58 Co-60

< 0.05

< 0.05 LLD (

LLD(

0/

0/

LLD(

LLD(

0/

0/

0/

0/

0 I

Zn-65 < 0.10 LLD ( 0/ LLD( 0/ 0/ 0 Zr-Nb-95 < 0.03 LLD 0/ LLD( 0/ 0/ I Cs-134 < 0.05 LLD 0/ LLD( 0/ 0/ 0 Cs-137 Ba-La-140

< 0.05

< 0.07 LLD(

LLD(

0/

0/

LLD(

LLD (

0/

0/

0/

01 0

I

' Nominal Lower Limit of Detection 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)

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

I I

I I

I 2-12 I

Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 Location of Facility: Beaver Countv. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Foodcrops Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) b) Name Mean (fraction) (b) Reported Performed LLD "' Range 'b) Distance and Direction Range (b) Distance and Direction Range (b Measurements 1-131 < 0.06 LLD ( 0 / 4 ) LLD ( 0 4 ) LLD( 0/ 1 0 5

Gamma 5

K-40 NA 2.160( 4/ 4 ) No. 15 Georgetown, PA 2.300 ( 1 / 1 ) No. 48a Weirton, WV 2.130 ( 1/1 ) NA 1.970 - 2.300 321 Third Street 2.300 - 2.300 Weirton Area 2.130 - 2.130 3.7 miles WSW 16.54 miles SSW Mn-54 < 0.05 LLD( 0 / 4 ) LLD( 0 /4 ) LLD 0 /1 ) 0 Fe-59 <0.10 LLD( 0 4 ) LLD( 0/4 ) LLD( 0/1 ) 0 Co-58 < 0.05 LLD( 0 /4 ) LLD( 0 /4 LLD( 0 /1 ) 0 Co-60 < 0.05 LLD( 0 /4 LLD( 0 /4 LLD( 0 / 1 0 Zn-65 < 0.10 LLD( 0 /4 LLD( 0 /4 ) LLD( 0 /1 0 Zr-Nb-95 < 0.03 LLD( 0 /4 LLD( 0 /4 LLD( 0/1) 0 Cs-134 < 0.05 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /1 ) 0 Cs-137 < 0.05 LLD( 0 /4 3 LLD( 0 /4 3 LLD( 0 /1 0 Ba-La-140 < 0.07 LLD( 0 / 4 ) LLD( 0 /4 ) LLD( 0 /1 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) 2-13

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I 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 / 50-412 Location of Facility: Beaver Countvy Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Feedstuff Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total Number Limit of AlI Indicator Location.Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) Wb) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD " Range (bl Distance and Direction Range (b) Distance and Direction Range (bW Measurements (0 Gamma 12 Be-7 <NA 1190( 5 / 12 ) No. 25 Searigbt Farm 1.190 ( 5 / 12 ) No. 25 Searight Farm 1.190 ( 5 / 12 NA 0.320 - 21550 948 McCleary Road 0.320 - 2,550 948 McCleary Road 0.320 - 2.550 Hookstown, PA Hookstown, PA 2110 miles SSW 2.10 miles SSW K-40 <NA 11.04( 12/ 12 ) No. 25 Searight Farm 11.04 ( 12/ 12 ) No. 25 Searight Farm 11,04 ( 12/ 12 ) NA 7.38 - 15.05 948 McCleary Road 7.38 - 15.05 948 McCleary Road 7.38 - 15.05 Hookstown, PA Hookstown, PA 2,10 miles SSW 2.10 miles SSW Mn-54 < 0.05 LLD( 0 / 12 ) LLD( 0 / 12 ) LLD 0 /12 0 Fe-59 Co-58

< 0.10

< 0.05 LLD(

LLD(

0 / 12 0 / 12

)

)

LLD(

LLD(

0 / 12 0 / 12

)

)

LLD(

LLD(

0 /12) 0 /12) 0 0

I Co-60 Zn-65

< 0.05

< 0.10 LLD(

LLD (

0 / 12) 0 / 12 )

LLD(

LLD (

0 /12) 0 /12 )

LLD( 0 /12)

LLD ( 0 /12 )

0 0 I

)

I Zr-Nb-95 < 0.03 LLD( 0 / 12 ) LLD( 0 /12 LLD( 0 /12) 0 Ru-103 < 0.04 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0/ 12) 1-131 < 0.06 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 13a-1.a-140 < 0.07 LLD ( 0 / 12 ) LLD ( 0 / 12 ) 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) I c 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) I I

2-14 I

Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Sediment (page I of 2)

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

Performed LLD

• Range ]

Name Distance and Direction Mean (fraction) N

]Range Name

.lDistance and Direction Mean (fraction) (b) Reported Range (b) Measurements Gamma 6

K-40 NA 9.40( 4/ 4 ) No. 2A BVPS 10.14( 2 /2 No. 49a Industry, PA 9.48 ( 2/ 2 7.29- 11,37 Outfall Vicinity 8.90- 11.37 Upstream of 9.77 - 9.91 0.31 miles WSW Montgomery Dam 4.93 miles NE Mn-54

• 0.05 LLD( 0/4 4 LLD ( 0/4 ) LLD ( 0/2 Fe-59 < 0.10 LLD( 0/4 ) LLD( 0/4 LLD ( 0/2 )

)

Co-58 < 0.05 0.08 ( 2/ 4 No, 2A BVPS 0.08( 2 / 2 No. 49a Industry, PA LLD ( 0/2 0,08 - 008 Outfall Vicinity 0.08 - 0.08 Upstream of 0.31 miles WSW Montgomery Dam 4.93 miles NE Co-60 < 0.05 0.15( 2/ 4 No. 2A BVPS 0,15( 2/2 No. 49a Industry, PA LLD( 0/22 0.11 - 0,19 Outfall Vicinity 0.11- 0.19 Upstream of 0.31 miles WSW Montgomery Dam 4.93 miles NE Zn-65 < 0.10 LLD( 0/4 ) LLD ( 0 / 4 ) LLD( 0/22 Zr-95

• 0.03 LLD 0/4 ) LLD 0/4 ) LLD ( 0/2 )

0/4 ) ) )

Nb-95 < 0.03 LLD LLD 0/4 LLD ( 0/2

)

Cs-134 < 0.05 LLD ( 0 / 4 ) LLD ( 0/4 ) LLD ( 0/2 Cs-137 < 0.05 0,10 ( 2 / 4 ) No. 2A BVPS 0.10 ( 2 /2 No. 49a Industry, PA 0.081 2 /2 0.06- 0.13 Outfall Vicinity 0,06- 0,13 Upstream of 0.08 - 0.08 0.31 miles WSW Montgomery Dam 4.93 miles NE Ba-La-140 < 0.07 LLD( 0/ 4 LLD ( 0 / 4 LLD( 0/2 TI-208 NA 0,31( 4/4 ) No. 2A BVPS 0.34 ( 2 /2 No. 49a Industry, PA 0.28( 2 /2 0.23 - 0.39 Outfall Vicinity 0,29- 0.39 Upstream of 0.28 - 0.28 0.31 miles WSW Montgomery Dam 4.93 miles NE 2-15

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Enclosure 3 I

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 / 50-412 Location of Facility: Beaver County, Pennsylvania I

Reporting Period: Calendar Year - 2008 Medium: Sediment (page 2 of 2)

I Unit of Measurement: (pico Curies / gram) Dry Type and of Analysis Lower Total Number Limit of AlUIndicator Location. Locations with Highest Annual Mean Detection Mean (fraction) W'i Name Mean (fraction) 0" Control Location Name Mean (fraction)

Number of Nonroutine Reported I

Performed Bi-214 LLD 1)

NA Range 0.78 (

Ib) 0.58- 0.89 4 / 4 )

Distance and Direction No. 2A BVPS Outfall Vicinity Range 0.83 ( 2 /2 0.77 - 0.89 Distance and Direction No. 49a industry, PA Upstream of Range (b) 0.72 ( 2 / 2 0.69 - 0.75

)

Measurements 1 NA I 0.31 miles WSW Montgomery Dam Pb-212 NA 1.17 ( 4 /4 ) No, 2A BVPS 1.28 ( 2/ 2 4.93 miles NE

) No. 49aIndustry, PA 1.02 ( 2/2 ) NA I

0.94- 1.34 Outfall Vicinity 1.21- 1.34 Upstream of 0.89- 1.15 Pb-214 NA 0.81 ( 4 /4 )

0.31 miles WSW No. 2A BVPS 0.87 2 / 2 Montgomery Dam 5 miles NE No. 49a Industry, PA 0.79 ( 2 /2 ) NA I

0.59- 0.93 Outfall Vicinity 0.81- 0.93 Upstream of 0.74- 0.84 0.31 miles WSW Montgomery Dam 5 miles NE I Ra-226 NA 1.67 ( 4 /4 1 No. 2A BVPS 1.92 ( /2 ) No. 49a Industry, PA 1.67 ( 2 /2 ) NA 1.09- 2.12 Outfall Vicinity 0.31 miles WSW 1.71- 2.12 Upstreamof Montgomery Dam 5 miles NE 1.43 - 1.91 I

Ac-228 NA 0.98 ( 4 /4 ) No. 2A BVPS 1.07 ( 2 / 2 ) No. 49a Industry, PA 0.96 ( 2 /2 ) NA 0.75- 1.19 Outfall Vicinity 0.31 miles WSW 0.95- 1.19 Upstream of Montgomery Dam 5 miles NE 0.90- 1.01 I

Nominal Lower Limit of Detection I

I 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)

I I

I I

2-16 I

Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Soil (page 1 of 2)

Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) Name Mean (fraction) Name Mean (fraction) N Reported Performed LLD ( Range 1b) Distance and Direction Range (b) Distance and Direction Range N Measurements W Gama Note: Soil Sampling peformed every three (3) years. Sampling was performed in 2006, and is next due in 2009.

K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 2-17

Beaver Valley Power Station RTL A9.690E I

2008 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 / 50-412 Location of Facility: Beaver County. Pennsylvania Reporting Period: Calendar Year - 2008 Medium: Soil (page 2 of 2)

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

Name Mean (fraction) (b) Reported Performed LLD (') Range (b) Distance and Direction Range Distance and Direction Range (b) Measurements W Note: Soil Sampling performed every three (3) years. Sampling was performed in 2006, and is next due in 2009.

Ba-La-140 TI-208 Bi-214 I

Pb-212 I

Pb-214 Ra-226 Ac-228 I

a Nominal Lower Limit of Detection I

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 1J2-ODC-3.03, Attachment Q, Control 3.12.1)

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

I 2-18 I

Beaver Valley Power Station RTL A9.690E 2008 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 / 50-412 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 Number Limit of All Indicator Location, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD "R Range M Distance and Direction pRange (b) Distance and Direction Range

• Measurements Gamma 4.6 18.4( 503 / 503 ) No, 112 BVPSSite 23.0 ( 8 /8 ) No. 48 Weirton, WV 20M5( 8/8 ) 0 511 11.4 - 26.0 Perimeter 20,0 - 25.4 Water Tower 18&7- 24.0 Location 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) 2-19

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary I Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 I

Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled (Unit of Measurement)

Number of Analysis Performed of Detection (LLD)

Mean, (f) Range I

Sediments (pico Curie /gram) dry Gross Alpha Gross Beta Sr-90 (0)

(33)-

(0) 1 18 (33/33) 5 - 30 I U-234, 235,238 (0) --

Gamma K-40 Cs-137 (33) --

1.5 0.1 13 13 0.4 (33/33)

(33/33)

(21/33) 2 - 30 2-30 0.1 - 0.6 I

Zr/Nb-95 Ce-144 Ru-106(a) 0.05 0.3 0.3 0.8 0.5 1.5 (12/33)

(3/33).

(3/33) 0.2 - 3.2 0.4- 0.7 1.3 - 1.8 I

Others < LLD I

Foodcrops Gamma (8) --..

(pico Curie/gram) dry K-40 1 33 (8/8) 10 - 53 Cs-137 0.1 012 (1/8) --

Zr/Nb-95 Ru-106(a) 0.05 0.3 0.2 0.8 (1/8)

(1/8)

-- I Others -- < LLD Feedstuff (pico Curie/gram) dry Gross Beta Sr-89 Sr-90 (80)

(81)

(81) 0.05 0.025 0.005 19 0.2 0.4 (80/80)

(33/81)

(78/81) 8 - 50 0.04 - 0.93 0.02 - 0.81 I

Gamma K-40 Cs-137 (81) --

1 0.1 19 0.5 (75/81)

(6/81) 5-46 0.2- 1.6 I

Ce-144 0.3 1.5 (5/81) 0.9-2.6 Zr/Nb-95 Ru-106(a) 0.05 0.3 0.8 1.4 (13/81)

(12/81) 0.2-1.8 0.6-2.3 I

Others -- < LLD Soil Template Samples -

Gross Alpha Gross Beta Sr-89 (0)

(64)

(64) 1 0.25 22 0.4 (64/64)

(1/64) 14 - 32 I

I (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 Ce- 144 0.1 0.3 1.5 1.1 (56/64)

(7/64) 0.1 - 6.8 0.2 - 3 I

Zr/Nb-95 0.05 0.3 (13/64) 0.1 - 2 Ru-106(a)

Others 0.3 1.1 (3/64),

< LLD 0.5 - 2 U

(f) Fraction of detectable measurements at specified location.

1 2-20 I

Beaver Valley Power Station RTL A9.690E 2008 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) M " ,

Soil Gross Alpha (0) -- -

-Core Samples - Gross Beta (8) 1 21 (8/8) 16728 (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) 77-20 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 Alpht (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* (208) ,0.6 3.8, (208/208) , 2.3- 6.4 Gamma (0) ....

Tritium (211) 100 310 (211/211) 130- 1000 C-14 (0) -- -

Sr-89 (0)

Sr-90 (0)

Ground Water Gross Alpha (19) 0.3 < LLD (pico Curie./liter) Gross Beta (76) 0.6 *2.9 (73/75)(b) 1.3.- 8.0 Tritium (81) 100 440 (77/81) 80 - 800 Gamma (1) 10-60 < LLD Air Particulates Gross Alpha (188) 0.001 0.003 (35/188) 0.002 -.0.004 and Gaseous Gross Beta (927) 0.006 0.07 (927/927) 0.02- 0.32 (pico Curie /cubic meter) Sr-89 (0) -- -

Sr-90 (0) -- --

1-131 (816) 0.04 0.08 (2/816) 0.07 - 0.08 Gamma (197) -- --

Zr/Nb-95 0.005 0.04 (122/197) 0.01 -0.16 Ru-106 .0.010 0.04 (50/197) 0.02- 0.09 Ce-141 0.010 0.02 (3/197) 0.01 - 0.04 Ce-144 0.010 0.02 (44/197) 0.0i - 0.04 Others < LLD (f) Fraction of detectable measurements at specified location.

2-21

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Table 2-3 (Continued)

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

Number of Analysis Performed of Detection (LLD)

Mean, (f) Range U Milk (pico Curie / liter) 1-131 Sr-89 Sr-90 (91)

(134)

(134) 0.25 5

1 0.6 7

5.3 (4/91)

(4/134)

(132/134) 0.3 - 0.8 6 - 11 1.5 - 12.8 I

Gamma Cs-137 Others (134) ....

10 13 (19/134)

< LLD 11 - 16 I External Radiation (milli Roentgen / day) y - Monthly y - Quarterly (599)

(195) 0.5 mR*

0.5 mR*

0.20 0.20 (599/599)

(195/195) 0.08 - 0.51 0.11 -0.38 I

_y - Annual (48) 0.5 mR* 0.19 (48/48) 0.11 -0.30 Fish (pico Curie /gram) wet Gross Beta Sr-90 (17)

(17) 0.01 0.005 1.9, 0.14 (15/17)

(17/17) 1.0 - 3.2 0.02-0.50 I

Gamma (17) 0.5 K-40 2.4 (17/17) 1.0-3.7 I

Others < LLD LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive U

radiation detector (TLD).

(a) May include Ru-106, Ru-103, Be-7. I (b) One outlier not included in mean. (Water taken from dried-up spring with high sediment and (f) potassium content. Not considered typical groundwater sample). -

Fraction of detectable measurements at specified location.

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1 U

2-22 I

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM B. Air Monitoring

1. Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is generally from the southwest in summer and from the northwest in the winter.

2. Air Sampling Program and Analytical Techniques

a. Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10) offsite air sampling stations. The locations of these stations are listed in Table 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 on a weekly basis.

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 naturally occurring radioactivity (e.g.; radon and thorium), 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 fiber filter papers collected from each monitoring station during the quarter and scanning this composite on a high resolution germanium gamma spectrometer.

Iodine-131 Analysis of Charcoal Cartridge: Analysis is performed by a gamma scan of each charcoal cartridge.

.2-23

Beaver Valley Power Station RTL A9.690E i 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM R

3. Results and Conclusions 3 A summary of data is presented in Table 2-2.

a. Airborne Radioactive Particulates i Gross Beta: A total of five-hundred-ten (510) 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.

3 During the period 05/19/08 - 05/27/08, the Gross Beta Results were unusually low.

Specifically, the Gross Beta results for the ten (10) air particulate sample stations ranged from i 0.011 - 0.014 pCi/cubic meter, where as the cumulative average ranged from 0.022 to 0.025 pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the one (1) control location. This issue was discussed with the REMP Administrators at the other two FENOC sites (i.e.; Davis-Besse Nuclear Power Plant and the Perry Nuclear Power Plant),

and they also noted similar decreases in Gross Beta results during this period. There is no consequence to unusually low sample results at the indicator and control locations. The cause is most likely due to cosmic phenomenon. This issue is documented in SAP Order 200197646-0640. 3 During the period 11/02/08 - 11/10/08, the Gross Beta Results were unusually high.

Specifically, the Gross Beta results for all ten (10) air particulate sample stations ranged from 0.034 - 0.051 pCi/cubic meter, where as the cumulative average ranged from 0.024 to 0.026 I pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the one (1) control location. This issue was discussed with the REMP Administrators at the other two FENOC sites (i.e.; Davis-Besse Nuclear Power Plant and the Perry Nuclear Power Plant),

and they also noted similar increases in Gross Beta results during this period. There is no consequence to unusually high sample results at the indicator and control locations. The cause is most likely due to cosmic phenomenon. This issue is documented in SAP Order 200197646-0640.

I Gamma Spectrometry: The weekly air particulate samples were composited into forty (40) i 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 some deviations from i the required airborne particulate sampling and analysis schedule during the report period.

Specifically, during the sampling period of 02/25/08 - 03/03/08, the Air Particulate and Iodine Sampling Station at the Shippingport, PA Cooks Ferry Substation (Site No. 30, 0.43 miles ENE) was interrupted for 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> due to an undeterminable power loss. During the sampling period of 03/24/08 - 03/31/08, the Air Particulate and Iodine Sampling Station at East Liverpool, OH Water Department (Site No. 47, 4.88 miles WNW) was interrupted for 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> due to shattered vanes in the sample pump. During the sampling periods of 06/02/08 -

3 06/09/08, 06/16/08 - 06/23/08, and 06/30/08 - 07/05/08, the Air Particulate and Iodine Sampling Station at Hookstown, PA (Site No. 13, 1.49 miles SW) was interrupted for 23 l hours, 58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br /> and 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, respectively due to power losses from blown fuses. After each 2-24 1

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM of the power losses, the fuses were replaced and the sample pumps were successfully restarted. The power loss condition was resolved on 07/07/08 by removing an extension cord not associated with BVPS-REMP air sampling equipment. During the sampling period of 09/02/08 - 09/08/08, the Air Particulate and Iodine Sampling Station at the Shippingport, PA Cooks Ferry Substation (Site No. 30, 0.43 miles ENE) was interrupted for 114 hours0.00132 days <br />0.0317 hours <br />1.884921e-4 weeks <br />4.3377e-5 months <br /> due to shattered vanes in the sample pump. All Air Particulate and Iodine Samples obtained for the sampling period of 09/02/08 - 09/08/08 were discarded by the shipper, because they were damaged during shipment. Although these are not missed samples (i.e., the samples were obtained), no sample analyses are available for this sample period. During the sampling periods 09/08/08 - 09/15/08, and 09/15/08 - 09/22/08, the nine (9) Air Particulate and Iodine Sampling Stations (Indicator Locations) were interrupted for various periods of time. The interruptions were all related to power outages caused by hurricane Ike thunderstorms that entered the area on 09/14/08. During this period, sampling was interrupted for periods from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. During the sampling period of 11/17/08 - 11/24/08, the Air Particulate and Iodine Sampling Station at the Midland, PA North Substation (Site No. 32, 0.75 miles NW) was interrupted for 93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br /> due to shattered vanes in the sample pump. SINCE BVPS uses ten (10) airborne particulate sample stations versus five (5) required by the ODCM, THEN there was no consequence to interruption of sample collection during these periods.

This condition is documented in SAP order 200197646-0490.

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

b. Airborne Radioiodine Iodine-13 1: A total of five-hundred-ten (510) weekly charcoal filter samples were analyzed for Iodine-131. No detectable concentrations were present at any locations.

Deviations from Required Sampling and Analysis Schedule: The deviations are the same as described above for airborne particulates.

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

2-25

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Figure 2-1 I Environmental Monitoring Locations - Air Sampling Stations U

U I

I I

I I

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I I

Sample Type Site No. Sector Distance (miles) Sample Point Description I 13 11-SW 1.49 Hookstown, PA (Old Meyer Farm) 27 28 29B 7-SE 1-N 3-NE 6.14 8.60 7.97 Aliquippa, Pa (Brunton Farm)

Beaver Falls, PA (Sherman Farm)

Beaver, PA (Friendship Ridge)

I Air Particulate 30 4-ENE 0.43 Shippingport, PA (Cook's Ferry Substation)

& Radioiodine 32 46.1 15-NW 2-NNE 3-NE 0.75 2.28 4.88 Midland, PA (North Substation - Rt. 68)

Industry, PA (McKeels Service - Rt. 68)

East Liverpool, OH (Water Department)

I 47 14-WNW 48 51 10-SSW 5-E 16.40 8.00 Weirton, WV (Water Tower, Collier Way)

Aliquippa, PA (Sheffield Substation) U 2-26 I

Beaver Valley Power Station RTL A9.690E 2008 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 REM P Environmental Air Particulate Samples - Gross Betaj 0.20 0.18-E - Average of 9 Indicator Locations 0.16

... A -- Control Location 0.14- -.

. - - -Pre-Operational value (0.07 p0 / cubic meter) 0.12 - - Required LLD (0.01 p0 / liter)

E 0.10 -

- No Reporting Level for Gross Beta 0.08 0

0.06 ----------

0.04--

0 "5

0.02 -

0 .00 1 1 ý 1 i i 1 i i i 1 ! i  ! , 1 1 i i i i i i  : i i i i i i

,*0 ,Nq,4 *", * *. .". ,03, ,* 91 *

• 5 2-27

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM C. Monitoring of Shoreline Stream Sediment and Soil 3

1. Characterization of Shoreline Stream Sediment and Soil The stream sediment (river bottoms) consists largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.

3

2. Sampling Program and Analytical Techniques 3

a. Program Shoreline stream sediment were collected semi-annually above the Montgomery Dam, in the vicinity of the BVPS outfall structure, 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.

Although not required by the ODCM, soil samples are collected every three years. They were collected at each of ten (10) locations during 2006 and are not due to be collected I 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.

I Sampling locations are listed in Table 2-1 and are shown in Figure 2-3.

Shoreline stream sediment and soil are analyzed for gamma-emitting radionuclides.

b. Analytical Procedures 1 Gamma Emitter Analysis of Stream Sediment: Analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry. i Gamma Emitter Analysis of Soil: Although not required by the ODCM, analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry i I

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I 2-28 i

Beaver Valley Power Station RTL A9.690E 2008 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. Shoreline Stream 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, Radium-226 and Actinum-228, were 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 two of four (2 of 4) indicator samples and two of two (2 of 2) control samples. The results were similar to previous years (current years range = 0.06 to 0.13 pico Curie / gram), and less than the pre-operational level of 0.4 pico Curie / gram. Also, SINCE Cesium-137 was identified 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 two of four (2 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 = 0.08 to 0.08 pico Curie / gram), and this data is currently less than the pre-operational level of 0.098 pico Curie / gram.

Cobalt-60: Radionuclide Cobalt-60 was identified in two of four (2 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 = 0.11 to 0.19 pico Curie / gram), and this data is currently less 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 in the shoreline stream sediment near the main outfall facility is not unusual, because the plant discharges these radionuclides in liquid effluent releases. 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 ODCM.

2-29

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b. Soil Although not required by the ODCM, soil is sampled every three years and was sampled in 2006. Soil sampling will be performed during calendar year 2009.

2-30

Beaver Valley Power Station RTL A9.690E 2008 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 13a 11-SW 1.49 Hookstown, PA (Old Meyer Farm) 22 8-SSE 0.28 South of BVPS, Transmission Lines 27b 7-SE 6.19 Aliquippa, PA (Brunton Farm) 29A 3-NE 8.09 Beaver, PA (Nicol Farm)

Shippingport, PA (Cooks Ferry Soil 30a 4-ENE 0.43 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) 48 10-SSW 16.40 Weirton, WV (Collier Way Water Tower) 51a 5-E 7.99 Aliquippa, PA (Sheffield Substation) 2A 12-WSW 0.31 Shippingport, PA (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 2-31

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Figure 2-4 I Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & Cobalt-60 in Sediment Beaver Valley Power Station REM P I

1000.00 Cs-137 Sediment Trends - Outfall Vicinity I I

100.00 I

E S 10.00

• j 1 .oM

- - -Control Cs-137 Location Cs-137 Cs-137 Pre-operational Results (0.4 pCVgrrm Cs- 137 Required LLD (180 pCVgm)

I E

I

a. No Reporting Level for Sediment ff

-a 1.00 0 . . .. .. . .. .. .. . . . . ." " "" " - -- . * -o-i "-

I

0. 0.10, 0.01 bq` 14" Nq~ 11 le *@ 1411

.4.1 14,1P 1P 19 pe e e 1ý I

Beaver Valley Power Station REM P Co-58 & Co-60 Sediment Trends - Outfall VicinityI I

-- 3-- Co-58 UUnit 2 Pre-Operational Mean: Co-58 (0.098 pcVgm) a Co-60 I

Unit 2 Pre-Operational Mean: Co-60 (0.40 pC/gram)

-No Required LLD for Co-58 or Co-60 10.00 -------- - - No Reproting Limit for Co-58 or Co-60 i------------------------

I

'I""

E 1.00 I

4A I

AA A A A

AA P A' I 0 / l 7'\ a A ' \ A I "

a. 0.10 1-G/"-. / \ U I ~ -

I I I/ V %I ft-1l 0.01 N 4NP I'll, N 1119 11 10" 46, 140 144 144 14" 1 4 I

I 2-32 I

Beaver Valley Power Station RTL A9.690E 2008 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 Valley Power Station REM P Cs-1 37 Soil Trends (Tri-Ennial) 1.4 L.

1.2

• - Cs-137 1.0 -A-- Control Location

-N Pre-operational Cs- 137 Reporting Level (1.2 pCi / gram) for Soil E 0.8 0.6 ...............................

0) 0.4 0.2 0.0 2-33

Beaver Valley Power Station RTL A9.690E I 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I D. Monitorin2 of Feedstuff and Foodcrops I

1. Characterization of Farm Products According to the 2007 Census of Agriculture (1), there were 824 farms in Beaver County. Total I market value of production (Crops and Livestock) was $15,187,000.00. Some of the principal sources of revenue (>$50,000.00) are as follows: I Milk and Other Dairy Products from Cows $5,647,000.00 Nursery, Greenhouse, Floriculture and Sod $2,813,000.00 Grains, Oil Seeds, Dry Beans and Dry Peas $1,243,000.00 Other Crops and Hay $1,120,000.00 I Vegetables, Melons, Potatoes and Sweet Potatoes $989,000.00 I Fruits, Tree Nuts and Berries $449,000.00 Poultry and Eggs $327,000.00 Cut Christmas Trees, and Short Rotation Woody Crops $204,000.00 Horses, Ponies, Mules, Burros, and Donkeys $182,000.00 Sheep, Goats and their Products $90,000.00 3 Hogs & Pigs Undisclosed Amount Aquaculture Undisclosed Amount I Cattle and Calves Undisclosed Amount Other Animals and Other Animal Products Undisclosed Amount I

(1) ht:wwagesssdgvPuictns27/nieHgigt/unyPf-ePenyvnandxapI 2-34

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

2. Sampling Program and Analytical Techniqlues

a. Program Feedstuff: Although not required by the ODCM, representative samples of Feedstuff (cattle feed) are collected monthly from the nearest dairy farm (Searight Dairy). See Figure 2-6. Each sample is analyzed by gamma spectrometry.

Foodcrops (leafy vegetables): Foodcrops are collected at garden locations during the growing Iseason. Leafy vegetables, (e.g.; cabbage) are obtained from Shippingport, Georgetown, and Industry, Pennsylvania. Samples are also obtained from the control location in Weirton, West Virginia. All samples are analyzed for gamma emitters by gamma spectrometry. Samples are also analyzed by radiochemical analysis for Iodine- 131.

b. Procedures Gamma Emitter Analysis of Foodcrops: Analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high resolution germanium detector is utilized with this system. Samples of feedstuff and foodcrops 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.

Gamma Emitter Analysis of Feedstuff: Although not required by the ODCM, analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system.

A high resolution germanium detector is utilized with this system. Samples of feedstuff and foodcrops 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 Foodcrops: 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 hypochiorite. 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.

2-35

Beaver Valley Power Station RTL A9.690E I 2008 Annual Radiological Environmental Operating Report Enclosure 3 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. Feedstuff Gamma Spectrometry: Although not required by the ODCM, 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 five of twelve (5 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 3

b. Foodcrops 3 Iodine-131: A total of five (5) samples were analyzed for Iodine-131. No detectable concentrations were present in the four (4) indicator samples or the one (1) control sample.

Gamma Spectrometry: A total of five (5) samples were analyzed by gamma spectrometry.

Naturally occurring Potassium-40 was identified in four of four (4 of 4) indicator samples and one of one (lof 1) control samples. No other radionuclides were identified. i Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required foodstuff sampling and analysis schedule during the report period. 3 Summary: The data from the foodcrops 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 foodcrops in the vicinity of the site during the report period.

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I 2-36 1

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2- ENVIRONMENTAL MONITORING PROGRAM*

Figure 2-6 Environmental Monitoring Locations - Feedstuff and Foodcrops 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-S W 16.54 Weirton, WV 2-37

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-7 Graph of Annual Average Concentration: Cesium-137 in Feedstuff and Foodcrops Beaver Valley Power Station REMP Cs-137 Feedstuff and Foodcrops Trends 100

--- Cs-137 (Feedstuff)

-Cs s-137 (Foodcrops)

Cs-i137 Pre-operational ResuIs 10- -- -------------------------- Cs-137RequiredLLD (80pCikg)Wet-

-lb Reporting Level for Feed of Food 0E I.m0 o 0.

0 0.

0.01 2-38

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM E. Monitoring of Local Cow and Goat Milk I. 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 (2.10 miles SSW) and the Brunton Dairy Farm (6.16 miles SE).

Cow milk and goat milk were also collected from two (2) other dairy farms within a 10-mile radius of the BVPS site. The goat milk samples obtained at the Collins Dairy Farm (3.55 miles SE) and the cow milk samples obtained at the Halstead Dairy Farm (5.08 miles SSW) 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 (10.48 miles SSW).

The cow milk sample from the Searight Dairy Farm (2.10 miles SSW) is collected and analyzed weekly for Iodine-131 using a method that ensures a high sensitivity. Samples from each of the other 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 principle gamma emitters (including Cesium-137 by high resolution germanium gamma spectrometry), and Iodine-131 high sensitivity analysis. Although not required by the ODCM, the monthly and/or bi-weekly sample is also analyzed for Strontium-89, Strontium-90.

During the 2008 Land Use Census, it was determined that a new heard of doe goats is located at the Sullivan Farm (4.285 miles ESE), and the Ferry Farm (3.32 miles SE) has again obtained a doe goat. No goat milk samples were available from either of these locations during 2008, because, the goats were already dry at time of the Land Use Census.

However, both locations may provide goat milk samples during 2009.

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RTL A9.690E I

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM The location of each is shown in Figure 2-8 and described below.

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Site Dairy Approximate Number of Animals being Milked Distance and Direction and Unit 2between Unit 1 Midpoint from Reactor Collection Period I 25 Searight Dairy 948 McCleary Road 38 Cows 2.10 miles SSW January thru December I Hookstown, PA 27a Brunton Dairy 108 Cows 6.16 miles SE January thru December I

3681 Ridge Road 69*

Aliquippa, PA Collins Dairy 1 Goats 3.55 miles SE March thru I

289 Calhoun Road Aliquippa, PA August U

96 Windsheimer Dairy 75 Cows 10.48 miles SSW January thru RD #11 December I Burgettstown, PA 113*

Halstead Dairy 104 Tellish Drive 60 Cows 5.08 miles SSW January thru December I

Hookstown, PA Ferry Farm 1 Goat 3.32 miles SE Not Applicable:

I No goat milk 227 Calhoun Rd 102 Aliquippa, PA available during 2008 I Sullivan Farm 5 Goats 4.29 miles ESE Not Applicable:

115 198 Wilson Lane No goat milk available I Aliquippa, PA during 2008

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

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Beaver Valley Power Station RTL A9.690E 2008 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 1 liter Marinelli container of milk.

Strontium-90 Analysis of Milk: Although not required by the ODCM, 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 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: Although not required by the ODCM, 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/cm 2 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 Iodine-131 and Strontium-90 analyses (including the pre-operational period through the report period) is shown on Figure 2-9.

a. Strontium-89: Although not required by the ODCM, a total of ninety-two (92) milk samples were analyzed for Strontium-89 during the report period. Strontium-89 was not detected in any of the seventy-two (72) indicator samples, nor was it detected in any of the twenty (20) control samples.

b. Strontium-90: Although not required by the ODCM, a total of ninety-two (92) milk samples were analyzed for Strontium-90 during the report period. Strontium-90 was detected in sixty-six of seventy-two (66 of 72) indicator samples and nineteen of twenty (19 of 20) 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 ninety-two (92) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40 was present in seventy-two of seventy-two (72 of 72) indicator samples and twenty of twenty (20 of 20) control samples. No other gamma-emitting radionuclides were identified during analysis.

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Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

d. Iodine-131: A total of one hundred twenty-four (124) milk samples were analyzed for I Iodine-131 during the report period. Iodine-131 was not detected in any of the one hundred four (104) indicator samples, nor was it detected in any of the twenty (20) 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 at the only Doe Goat Location (Site No. 69, 3.547 miles SE), as identified in the Land Use Census, were interrupted during 2008. Specifically, the Doe Goats at this location ceased production of milk in September 2008. Although the Doe Goats could not be sampled during that period, the minimum Bi-weekly milk sampling requirements of ODCM procedure 1/2-ODC-3.03, Attachment Q, Table 3.12-1 were still met. Specifically, SINCE only 4 Bi-Weekly Dairy Cow and/or Doe Goat locations are required to be sampled, THEN the minimum requirement was met with 4 Dairy Cow milk samples.

Also, two (2) of the four (4) Bi-weekly milk samples obtained on 09/08/08 were discarded by the shipper, because they were damaged during shipment. Although the samples were obtained, no sample analyses for the Brunton Dairy (Site No. 27a, 6.16 miles SE) and the Windsheimer Dairy (Site No. 96, 10.48 miles SSW) were available for this Bi-weekly sample period. This condition is documented in SAP Order 200197646-0650.

f. Summy: 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 U

milk in the vicinity of the site during the report period.

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-8 Environmental Monitoring Locations - Milk Point DescriDtion Hookstown, PA (Searight Farm)

Aliquippa, PA (Brunton Farm)

Aliquippa, PA (Collins Farm)

Burgettstown, PA (Windsheimer Farm)

Hookstowri, PA (Halstead Farm)

Hookstown, PA (Moore Farm)

• Dairies selected based on evaluation of deposition parameters 2-43

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-9 Graph of Annual Average Concentration: Iodine-131 & Sr-90 in Milk Beaver Valley Power Station REMP 14.0 1-131 Concentrations in Milk 14.0 I 12.0-----------... ......--.. .. .. . .Chernobyl.. Accient 10--- -- - 1970sWeaponls TestingI-S 8.0----------

---

-- -- -- -- -- -- -- -- -I- - - - - - - - ------ - 0 Average at the Indiator Location---

Z -..--.- Control Location 4P re-Operational value (0.6 pO liter)

S6.0 --- -- -- -- -- -- -- -- ---- ------------- ------ -- -- -- ------- Required LLD(11 pa/liter)---

S, Reporting Level (3 pi/ liter)

.20 0.0 ,

Beaver Valley Power Station REM P Sr-90 Concentrations in Milk 10 9----------------------------------------------- ---- Avg. of Indicator Locations ---

8--- A- -- Control Location Pre-Operational value (5.3 p /liter)

N -- -------------------- ----- ---- ----- ---- ----- ---- ----- ----

0._

0 2D&

CL~ AA-A 0j 2-44

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM F. Environmental Radiation Monitoring

1. Description of Regional Background Radiation and Sources Historical information for regional background was obtained from Reuter-Stokes instruments that were previously located within a five (5) mile radius of the BVPS site. Data is no longer available from these instruments, but historical data indicated that the background exposure rates ranged from 6 ýtR/hr to 12 ýtR/hr.

The sources of background radiation are affected by the terrain in the vicinity of BVPS, where as, the local hills (i.e., with altitude variations of 300-400 feet) and densely wooded areas contribute to differences in background radiation level. Other sources (e.g., Radon) are affected by the geological features of the region, which are characterized by nearly flat-laying sedimentary beds of the Pennsylvania Age. For information, the local sedimentary 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.

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-four (64) environmental TLD locations.

This is comprised of forty-four (44) offsite locations, along with twenty (20) 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 18.4 mR at the sixty-four (64) indicator locations, and 20.5 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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Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Adjustments to TLD Placement: In regards to operating experience at Clinton Power Station i (OE26003), BVPS TLD sites were evaluated during 2008 against criteria established in ANSI N545-1975 (Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry). As a result of this evaluation, several of the TLD sites were lowered and/or relocated to adjacent/nearby sites. For TLD sites that were relocated; (1) no changes were I

necessary to the distances specified in this and previous reports, and (2) no changes were necessary to the distances specified in the Offsite Dose Calculation Manual. In summary, the reported exposure results of all previous BVPS TLD data for the sixty-four (64) TLD sites are I

considered valid and do not require adjustment. Results of the evaluation were documented in SAP Order 200197646-0610 and letter NPD3NRE:0538.

TLD Trend Evaluation: As discussed in the 2007 report, the trends of the environmental TLD data during the period 2001 thru 2007 showed a small increase for the indicator locations, and a step (level) increase for the Control location. The increase was traced to a change made in late 2001 with regards to the environmental TLD field holders, which resulted in an increased sensitivity to natural background beta radiation. In summary, the increase in TLD data was consistent at all locations (including the control location), was most likely due to increased sensitivity to natural background beta radiation, and was not a consequence of BVPS gaseous effluent releases. This issue is documented in SAP Order No. 200197646-0400.

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

Summary: The quarterly TLD external exposure rates are comparable to those of previous years, except for the increase described above in the TLD Trend Evaluation. There was no evidence of anomalies that could be attributed to the operation of BVPS. It should also be I

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 I

increase in external exposure in the vicinity of the site during the report period. The TLD exposure rates also confirm that changes from natural radiation levels, if any, are negligible.

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Beaver Valley Power Station. RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3..

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

.'Figure 2-10 Environmental Monitoring Locations - TLDs 2-47

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Figure 2-10 (Continued) I TLD Locations Site No.

Sector Distance (miles)

SOUTHEAST QUADRANT Location Site No.

sector Distance (miles)

Location I

27 45.1 7-SE 6-ESE 6.14 1.92 Brunton Dairy Farm Aliquippa, PA Kennedy's Corners Raccoon Township, PA 78 79 7-SE 8-SSE 2.72 4.46 Racoon Twsp Municipal Building Raccoon Township, PA 106 State Route 151 Ted McWilliams Auto Body I

51 59 5-E 6-ESE 8.00 0.99 Sheffield Substation Aliquippa, PA 236 Green Hill Road Aliquippa, PA 80 82 9-S 9-S 8.27 6.99 Park Office, State Route 18 Raccoon Township, PA 2697 State Route 18 Aliquippa, PA I

U 76 6-ESE 3.80 Raccoon Elementary School 94 .8-SSE 2.25 McCleary & Pole Cat Hollow Road Raccoon Township, PA Hookstown, PA 77 6-ESE 5.52 3614 Green Garden Road Aliquippa, PA Site No.

15 Sector 14-WNW Distance (miles) 3.75 Post Office NORTHWEST QUADRANT Location Site No.

87 Sector 14-Distance (miles) 7.04 Location 50103 Calcutta Smith's Ferry Road I

32 47 15-NW 14-WNW 0.75 4.88 Georgetown, PA North Substation Midland, PA Water Department 88 89 WNW 15-NW 15-NW 2.74 4.72 110 Summit Road Midland, PA 488 Smith's Ferry Road N

I East Liverpool, OH Ohioville, PA 60 13-W 2.51 444 Hill Road 90 16-NNW 5.20 6286 Tuscarawras Road Georgetown, PA _ _ _ Midland, PA 86 13-W 6.18 1090 Ohio Avenue 93 16-NNW 1.10 104 Linden - Sunrise Hills East Liverpool, OH I

__Midland, PA NORTHEAST QUADRANT Site Sector Distance Location Site Sector DistanceLocation (miles) No. (miles)

No.

10 28 3-NE 4-ENE 1-N 0.94 8.60 Post Office Shippingport, PA Sherman Farm Beaver Falls, PA 70 71 1-N 2-NNE 3.36 6.01 236 Engle Road Industry, PA First Western Bank Brighton Township, PA I

I 29B 3-NE 7.97 Friendship Ridge 72 3-NE 3.25 Ohioview Lutheran Church - Rear Beaver, PA Industry, PA 30 4-ENE 0.43 Cook's Ferry Substation 73 4-ENE 2.48 618 Squirrel Run Road Shippingport, PA Industry, PA I

45 5-E 2.19 Christian House Baptist Chapel, State Rte 18 74 4-ENE 6.92 137 Poplar Avenue (CCBC)

Raccoon Township, PA Monaca, PA 46 3-NE 2.49 Midway Drive 75 5-E 4.08 117 Holt Road Industry, PA Aliquippa, PA 46.1 2-NNE 2.28 McKeel's Service, State Route 68 91 2-NNE 3.89 Pine Grove Road & Doyle Road Site 3-NE Distance Industry, PA SOUTHWEST QUADRANT Site Distance I

Sector Location Sector Location No.

13 14 11-SW 11-SW (miles) 1.49 2.53 Old Meyer Farm Hookstown, PA Hookstown, PA No.

84 85 11-SW 12-(miles) 8.35 5.73 Senior Center Hancock County, WV 2048 State Route 30 I

I WSW 48 10-SSW 16.40 Collier Way Water Tower 92 12- 2.81 Georgetown Road Substation Weirton, WV WSW Georgetown, PA 81 9-S 3.69 Millcreek United Presbyterian Church 95 10-SSW 2.37 832 McCleary Road Hookstown, PA 83 10-SSW 4.26 735 Mill Creek Road I

2-48 I

Beaver Valley Power Station RTL A9.690E 2008 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 REMPI Environmental TLD Trends I 0.22- -- -- -- -- ---- -- - -- ------ --- --- --

0.20 0.18 1' 11-E 2, 0 .16 .. . .. . . . . . . .. . . A -- - - - -A E 0.14

-0 Average of 63 Indicator Locations

--- - Control Location (Weirton WV) 0.12 Pre-Operational Value (0.2 rmrem/day)-------------- ---- ---- --- - - -...

0.10

,le * , * , * . * , * ** o 2-49

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 1

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM G. Monitoring of Fish

1. Description During the report period, fish collected for the radiological monitoring program included carp, channel catfish, quillback, red horse and smallmouth bass.

I

2. Sampling Program and Analytical Techniques m

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.

I

b. Procedure 3 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 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.

Gamma Spectrometry: A total of nine (9) fish samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the four (4) indicator samples, nor were they detected in any of the five (5) control samples.

I Deviations from Required Sampling and Analysis Schedule: There were no deviations from the m 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 2008 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 12-WSW 0.31 BVPS Outfall Vicinity Fish 49 Industry, PA (Upstream Montgomery 49a 3-NE 493 Dam) 2-51

Beaver Valley Power Station RTL A9.690E 2008 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 REMPI Cs-137 Concentrations - Fish 10000.000 1000M000--------------------- ----------------------

,g- 100.000 ------------------------------------------------------------ ----------------------------

---.-- Cs-137 10.000------------ - - ---------------- Control Location - Montgomery Dam -

E 0Unit 2 Preoperational (0.014 pCi / gn)

E i..iRequired LLD (150 pCi / gr)

E1 1.000---- -- -- -- -- -- -- --------- Reporting Level(2000 pCl /gm)-----------------------

1 .000 U> 01 0.Oc~O .10-------------------------------------------

0.001 -S 4--44..44- 4 44 4 2-52

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM H. Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation

1. Description of Water Sources The Ohio River is the main body of water in the area. It is the main surface water supply for generation of drinking water in the area. The Beaver Valley Power Station obtains water from the Ohio River for plant make-up water and discharges water to the Ohio River via NPDES discharge points (e.g. cooling tower blowdown, liquid effluent releases, etc).

The Ohio River is the main surface water supply source for towns, municipalities and industries both upstream and downstream of the BVPS 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, also 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://www.ncdc.noaa.gov/oa/climate/research/cag3/v4.html) indicates the total annual precipitation during the report period for the Pittsburgh, PA area was 39.24 inches.

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2008 Annual Radiological Environmental'Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

2. Sampling and Analytical Techniques 5

a. Surface (Raw River) Water The sampling program of river water includes three (3) sampling points along the Ohio i River.

Raw water samples are collected daily at the East Liverpool (Ohio).Water Treatment Plant, sample location 5, [River Mile 41.2], and the made into a weekly composite sample. One automatic river water sampler is located at the ATI-Allegheny Ludlam (formerly J&L Steel) river water intake, sample location 2.1, [River Mile 36.2]. The automatic sampler I takes a 20-40 ml sample every 15 minutes and samples are collected on a weekly basis.

The weekly samples are then made into a monthly composite sample for each location.

The monthly composite samples are analyzed for gamma emitters. In addition, a quarterly composite sample is prepared for each sample point from the monthly composites.

Quarterly composites are analyzed for Hydrogen-3 (Tritium).

A weekly grab sample is taken upstream of the Montgomery Dam, sample location 49

[River Mile 29.6]. This upstream sample at the Montgomery Dam is the control sample.

The weekly grab samples upstream of the Montgomery Dam are analyzed for Iodine- 131.5 Weekly grab samples are then made into monthly composites are analyzed for gamma emitters. Quarterly composite are prepared from each of the monthly composites. The quarterly composites are analyzed for Tritium..5 Locations of each sample point are shown in Figure 2-14.

b. Drinking Water (Public Supplies) i Drinking water (i.e.; treated water) is collected at both the Midland, PA Water Treating Plant, sample location 4, and East Liverpool, OH Water Treating Plant, sample location 5.

An automatic sampler at each location collects 20-40 ml every 20 minutes, which is 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. In addition, a quarterly composite sample is I

prepared for each sample point from the monthly composites. Quarterly composites are analyzed for Tritium.

A weekly grab sample is taken upstream of the Montgomery Dam, sample location 49

[River Mile 29.6]. This upstream sample at the Montgomery Dam is the control sample. i The weekly grab samples upstream of the Montgomery Dam are analyzed for Iodine-13 1.

Weekly grab samples are then made into monthly composites are analyzed by gamma spectrometry. Quarterly composite are prepared from each of the monthly composites.

The quarterly composites are analyzed for Tritium.

Locations of each sample point are shown in Figure 2-14. 1 2-54

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental OperatingReport Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

c. Groundwater Although not required by the ODCM, 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 is analyzed by gamma spectrometry.

d. Precipitation Although not required by the ODCM, precipitation is collected in Shippingport PA, East Liverpool OH, and Weirton WV. Precipitation, when. available, is collected each week and then, made into quarterly composite samples from the weekly samples. The, quarterly composites are analyzed for Tritium and gamma emitters., Locations of each of the sample points are shown in Figure 2-14.

e. Procedures Gamma Analysis of Drinking Water and Surface Water: 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. Although not required by the ODCM, this analysis is also performed on Groundwater and Precipitation.

Tritium Analysis of Drinking Water and Surface Water: The Tritium is determined in water samples by liquid scintillation analysis. Although not required by the ODCM, this

.analysis is also, performed on Surface Water, Groundwater and Precipitation; Iodine-131 Analysis of Drinking Water: The sample is chemically prepared and analyzed with a low-level beta counting system. Although not required by the ODCM, this analysis is also performed on Surface Water.

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2008 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 Figures U

2-15 through 2-18.

a. Surface Water Tritium: A total of twelve (12) surface 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.

I 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 I

detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples.

Iodine-131: Although not required by the ODCM, 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 forty-two of fifty-two (42 of 52) weekly control I

samples, of which three (3) analysis exceeded the reporting level of 2 pico Curie / liter.

The results were similar to previous years, (current years range = 0.2 to 2.6 pico Curie /

liter). The positive results were detected at the Control location, which is five (5) miles I

upstream (not influenced by BVPS operation). Identification of Iodine-131 during the report period was most likely due to medical diagnostic and treatment procedures from upstream facilities. This issue is documented in SAP Order 200197646-0440.

b. Drinking Water 3 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 were not detected in any of the twenty-four (24) indicator samples, nor were they detected in any of I

the twelve (12) control samples.

Iodine-131: A total of one hundred-fifty-six (156) drinking water samples were analyzed for Iodine-131 (using radiochemical methods) during the report period. Iodine-131 was detected in fifty-eight of one hundred four (58 of 104) indicator samples and forty-two of fifty-two (42 of 52) control samples. Some of the positive results at the downstream 3

location exceeded the positive results from the upstream surface water Control location, but none of these analyses exceeded the reporting level of 2 pico Curie / liter. Also, SINCE all of the liquid effluent discharges during the report period from BVPS did not have detectable Iodine- 131, THEN the positive results were not influenced by BVPS operation, and were most likely due to medical diagnostic and treatment procedures from upstream facilities.

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Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

c. Groundwater Tritium: Although not required by ODCM, 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: Although not required by ODCM, 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 four (4) indicator samples, nor were they detected in any of the two (2) control samples.

d. Precipitation Tritium: Although not required by ODCM, a total of twelve (12) precipitation samples were analyzed for Tritium during the report period. Tritium was detected in two of eight (2 of 8) indicator samples, but was not detected in any of the four (4) control samples.

Some of the positive results at the Cooks Ferry Substation in Shippingport, PA (current range = 182 pico Curie / liter, with an LLD of 133 pico Curie / liter) and the East Liverpool Water Department, in East Liverpool, OH (current range = 790 pico Curie / liter, with an LLD of 143 pico Curie / liter), are greater than the pre-operational level of 300 pico Curie / liter, but is consistent with washout of tritium (from gaseous releases) during precipitation events. Specifically, identification of tritium at this location is not unusual, because the plant discharges tritium in gaseous waste effluents, and washout does occur during precipitation. Also, the liquid tritium activity is less than the tritium 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: Although not required by ODCM, a total of twelve (12) precipitation samples were analyzed by gamma spectrometry during the report period.

Gamma emitting radionuclides were not detected in any of the eight (8) indicator samples, nor were they detected in any of the four (4) control samples.

e. Deviations from Required Sampling and Analysis Schedule: The weekly surface water sample at ATI-Allegheny Ludlam in Midland, PA (Site No. 2.1, 1.43 miles WNW) was not collected for the week of 4/22/08 to 04/29/08. Although this weekly downstream surface water sample was missed, the minimum weekly surface water sampling requirements of ODCM procedure 1/2-ODC-3.03, Attachment Q, Table 3.12-1 were still met. Specifically, SINCE the ODCM only requires one (1) upstream sample and one (1) downstream sample, THEN the minimum requirements were met with the upstream sample from Industry, PA (Site No. 49a, 4.93 miles NE), and the downstream sample from East Liverpool, OH (Site No. 5, 4.90 miles WNW). This condition is documented in SAP Order 200197646-0720.

f. Sumnary: Data from the water sample analyses demonstrate that BVPS did not 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.

2-57

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 U SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-14 I

Environmental Monitoring Locations -

Ground Water, Surface Water, Drinking Water and Precipitation I

I I

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U I

I Sample Type Drinking Site No.

4 Sector 15-NW Distance (miles) 1.26 Sample Point Description Midland, PA (Water Department)

I Water 5 14-WNW 4.90 East Liverpool, OH (Water Department)

Surface 2.1 14-WNW 1.43 Midland, PA (ATI Allegheny Ludlam)

I Water 5 14-WNW 4.90 East Liverpool, OH ( Water Department) 49a 3-NE 4.93 Industry, PA (Upstream Montgomery Dam)

Ground Water 11 14a 3-NE 11 -SW 0.94 2.61 Shippingport, PA Hookstown, PA I Precipitation 15b 30 47 14-WNW 4-ENE 14-WNW 3.75 0.43 4.88 Georgetown, PA Shippingport, PA (Cook's Ferry Substation)

East Liverpool, OH ( Water Department)

I 48 10-SSW 16.40 Weirton WV (Water Tower, Collier Way)

I 2-58 I

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water & Drinking Water Beaver Valley Power Station REMP 1-131 Surface Water & Drinking Water Trends

2. 5-

2. 0-

-a-- Dow n Stream Drinking Water - Mdland

- Down Stream Drinking Water - East Liverpool D---

a Control Location - Up Stream Surf ace Water

1. 5 Unit 2 DW Preoperational (0.23 pCi / liter)

A

- Reqluired LLD (1 pa / liter)

0. - Reporting Level (2 p() / liter)

1. 0

0. 5

0. 0 -. rr r \(  : /A Vi 1 , V ii

,e 14ý 411 1" 4,1 141Pe 4P 41,42 le e e e e e e 2-59

Beaver Valley Power Station RTL A9.690E 2008 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 REMPI Tritium Trends - Surface Water I Ilnnnnn Indicator Mean --(pa-/ -)-*

0Control Location (pa / 1)

Pre- Operational (300 pGi/I)

,.-,,,,*Required LLD (2,000 pCi/I)

Reporting Level Surface Water (30,000 pCi/I) "-

10000 c3 0.

1000 C., e--- - -- - -- - -- - - - -- - - --

0 C.)

0.

1000 10-I-2-60

Beaver Valley Power Station RTL A9.690E 2008 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 REM PI Tritium Trends - Groundwater 100000

-a-.-.. Indicator Mean (pa / I) 10000 -*--* Control Location (pa /I)

Pre- Operational (440 pG/I)

-A Required LLD (2,000 pCi/I)

-3 Reporting Level Groundwater (30,000 pCi/I)

- 1000 0

lO0 lO

,0. °,** ,~*," ,** , c * ,~c" ,bc o ccc *

• q** q*

2-61

Beaver Valley Power Station RTL A9.690E 2008 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 REM PI Tritium Trends - Drinking Water 100000

--a-- -- indicator W~lan Control Location (pQi / 1)

Pre- Operational (310 pCi/I) 10000 - - Required LLD (2,000 pC--I)

-- ,--,Reporting Level Drinidng Water (20,000 pCO.)

0 0 C-,

1 0 -- -_--- - -- -_ _- - - - - - - - - - - - - - -

10- ,

,4A( i. ,bA" ,*! , 4 ,0 ,41 ,4P ,o0 ,4 ,,

2-62

Beaver Valley-Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I. Estimates of Radiation Dose to Man 1 Pathways to Manh- Calculational Models The radiation doses to man as a result of BVPS 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 computer codes XOQDOQ2, GASPAR,, and LADTAP. Dose factors listed in the ODCM are used to calculate doses from radioactive noble gases in discharge plumes. BVPS effluent data, based on sample analysis were 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 BVPS 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.

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 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 Guide 1.109.

The total population doses were evaluated for all liquid and gaseous effluent pathways out to.

50 miles. For these evaluations, a total population of -4 million people was used. An-estimate of the populations are listed in the BVPS-2 UFSAR Section 2.1.3.1 for 0-10 miles and Section 2.1.3.2 for 10-50 miles.

2. Results of Calculated Population Dose to Man - Liquid Effluent Releases During the report period, the calculated dose to the entire population 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 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.

2-63

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

4. Conclusions 3 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 from the operation of BVPS - Unit 1 and 2, is less than 0.00005% of the annual background dose.

The calculated doses to the public from the operation of BVPS - Unit 1 and 2, are below ODCM 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.

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I 2-64 3

Beaver Valley Power Station RTL A9.690E 2008 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 402 Tritium Average Dose 0.0001005 Tritium (per Individual)

Comparison of Individual Dose BVPS Liquid Effluent Releases Versus Natural Background Radiation millirem BVPS Liquid Effluent Release Dose 0.0001005 Natural Radiation Exposure 296 2-65

Beaver Valley Power Station RTL A9.690E I

2008 Annual Radiological Environmental Operating Report Enclosure 3 U SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I

Table 2-5 Comparison of Natural Background Exposure Versus I Calculated Population Dose to Man - Gaseous Effluent Releases I

TYPICAL DOSE TO INDIVIDUALS I FROM NATURAL RADIATION EXPOSURE (a)

Ambient Gamma Radiation = 58 millirem / year I

Radionuclides in Body Global Fallout

=

=

40 millirem / year

< 1 millirem / year I

Radon 198 millirem / year Average Individual

=

= 296 millirem /year I (Total from all sources shown above)

(b) National Academy of Sciences, "The Effects on Populations of I Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 I

0-50 mile Population Dose from BVPS Gaseous Effluent Releases Man-millirem Largest Isotope Contributor I

Total Average 144 0.0000359 Tritium Tritium I

(per Individual)

I Comparison of Individual Dose BVPS Gaseous Effluent Releases U Versus Natural Background Radiation millirem i

BVPS Gaseous Effluent Release Dose Natural Radiation Exposure 0.0000359 296 I

I 2-66 I

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 - LAND USE CENSUS A. Land Use Census Overview: A Land Use Census was conducted September 4 through September 24, 2008 to comply with:

• Offsite Dose Calculation Manual procedure 1/2-ODC-3.03, "Controlsfor RETS and REMP Programs", Attachment R, Control 3.12.2, and Surveillance Requirement 4.12.2.1

" BVPS REMP procedure 1/2-ENV-04.02, "Milch Animal Sampling Location Determination & ODCM Procedure 1/2-ODC-3.03, Control 3.12.2 Action Statements a and b Compliance Determination" The Land Use census indicated 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:0542, dated September 29, 2008:

B. Nearest Residence:

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).

C. 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).

D. Nearest Dairy Cow:

The current location has not changed since the previous census.

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

E. Nearest Doe Goat:

The nearest location has changed since the previous census. However, SINCE the new location at 227 Calhoun Road, Aliquippa, PA (3.320 miles SE) cannot provide enough milk for sample analysis, THEN the location of the nearest Doe Goat milked will remain at 289 Calhoun Road, Aliquippa, PA (3.547 miles SE).

F. Projection for 2009 Dairy Cow Sampling 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 2008:

- Searight Dairy, 948 McCleary Road, RD1, 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).

3-1

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 3

SECTION 3 - LAND USE CENSUS G. Projection for 2009 Doe Goat Sampling Locations:

The linear regression analysis also indicated that there may be up to two (2) Doe Goat sampling location in 2009. The Doe Goat sampling location for 2009 may be as follows:

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

- Sullivan Farm, 198 Wilson Drive, Aliquippa, PA (4.285 miles ESE).

H. D/O for Milch Animal Locations:

None of the 2008 milch animal sampling locations experienced a >20% increase in D/Q.

Therefore, a Special Report per ODCM procedure 1/2-ODC-3.03, Attachment R, Control 3.12.2 Action "a" and/or Action "b" was not required. 3 I. D/O for Offsite Dose Determination:

There was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, a linear regression analysis of D/Q did not 3

yield any valid locations where the offsite dose could have increased >20% more than the offsite dose previously calculated using current ODCM methodology. Therefore, a Special Report per ODCM procedure 1/2-ODC-3.03, Attachment R, Control 3.12.2 Action "a" and/or Action "b" was not required.

J. D/O Historical Comparison:

There was no adverse trend in D/Q when comparing 1997 to 2008 data to the ODCM default D/Q values. This validates that there was no adverse effect on the current ODCM I methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased

>20% more than the offsite dose previously calculated using current ODCM methodology.

Therefore, a change in ODCM Receptor location and/or a change to meteorology at the current ODCM Receptor location was not required. i I

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I 3-2 3

Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 - LAND USE CENSUS Table 3-1 Location of Nearest Residences, Gardens, Dairy Cows and Doe Goats DAIRY RESIDENCES GARDENS COWS DOE GOATS SECTOR 0 to 5 miles 0 to 5 miles 0 to 5 miles 0 to 5 miles (miles) (miles) (miles) (miles)

N 1.584 None None None NNE 1.661 None None None NE 0.406 (2) None None None ENE 0.603 1.047 None None E 0.429 2.252 None 3.402 ESE 0.476 1.713 None 4.285 SE 1.583 1.802 None (1) 3.320 (2)

SSE 1.102 1.983 None None S 1.399 2.276 3.851 None SSW 0.760 0.760 (2) 2.097 (2) None SW 1.453 1.453 None None WSW 1.394 2.832 None None W 2.204 None None None WNW 2.742 None None None NW 0.885 1.033 None None NNW 0.902 2.413 2.442 None (1) Although there are no Dairy Cows within 5 miles in this sector, a large local dairy located at 6.158 miles is included in the milk sampling program.

(2) Distances shown in Bold print are the nearest location for that receptor.

3-3

Beaver Valley Power Station RTL A9.690E 2008 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 RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE 3 INTER-LABORATORY COMPARISON PROGRAM Participation in an Inter-Laboratory Comparison Program is required by BVPS Unit 1 and 2 Offsite Dose Calculation Manual procedure 1/2-ODC-3.03 Attachment S Control 3.12.3. For 1

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 3

following summary is provided:

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

U A total of forty-eight (48) gamma spectrometry radionuclide analyses were 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 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 four (4) water samples.

Comparison of results of the spiked milk and water samples showed acceptable agreement with the NRC acceptance criteria. All one-hundred-eight (108) analyses met the NRC acceptance criteria. 3 Comparison of results of the spiked milk and water samples showed acceptable agreement with BVPS acceptance criteria. All but two (2) of the one-hundred-eight (108) analyses met the BVPS acceptance criteria.

4-2 1

Beaver Valley Power Station RTL A9.690E 2008 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. The two samples that are not within the BVPS Acceptance Criteria are in the same sample type and are for two different sample analyses. Although these sample analyses are not within the BVPS Acceptance Criteria, they are within the NRC Acceptance Criteria. The BVPS acceptance criteria are self imposed and can be considered stringent compared to the NRC acceptance criteria. The first of the two deviations occurred in the second quarter for milk for Sr-90 (-20.89%).

The second occurred in the third quarter, also for milk, but for Sr-89 (-21.79%).

4-3

Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM U

Table 4-1 I Inter-Laboratory Comparison Program Spiked Samples - Ist Quarter Percent Difference Between I

Sample Date Sample Type and Identification No. Sample Analyses Contractor Lab Activity and Independent Lab Calculated Activity (Contr. Lab - Ind. Lab) I Ind. Lab I

Sr-89 Sr-90

-5.84%

15.75% I 1-131 (Chemical) 4.69%

1-131 Ce-141 4.83%

-0.15%

I Water Cr-51 0.77%

03/20/2008 Ind Lab: E5862-93 Con. Lab: SPW-1093 Cs-134 Cs- 37

-7.92%

2.24%

I 4.26%

I Co-58 Mn-54 4.40%

Fe-59 5.65%

Water Zn-65 Co-60 5.32%

-0.05% I 03/20/2008 Ind. Lab: E5861-93 Con. Lab: SPW-1092 H-3 3.57%

I Sr-89 -4.38%

Sr-90 1-131 (Chemical)

-5.43%

-1.67%

I 1-131 5.00%

Milk Ce-141 Cr-51

-0.48%

1.64%

I 03/20/2008 Ind. Lab: E5863-93 Cs-134 -6.24%

Con. Lab: SPMI-1094 Cs-137 Co-58 0.62%

2.40%

I Mn-54 5.31%

Fe-59 Zn-65 1.76%

6.64%

I Co-60 2.16%

Filter Paper Cs-137 I 03/20/2008 Ind. Lab: E5864-93 10.81%

Con. Lab: SPAP-1095 Charcoal Cartridge (Gross Beta)

U 03/20/2008 Ind. Lab: E5865-93 Con. Lab: SPCH-1096 1-131 -8.04%

I 4-4 I

Beaver Valley Power Station RTL A9.690E 2008 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) Ind. Lab Sr-89 -0.46%

Sr-90 17.50%

1-131 (Chemical) -5.74%

1-131 3.75%

Ce-141 -0.68%

Water Cr-51 9.04%

06/19/2008 Ind. Lab: E5937-93 Cs-134 -5.10%

Cs- 137 0.95%

o-58 CCo-58 2.02%

Con. Lab: SPW -3057 -2.02%

Mn-54 6.14%

Fe-59 5.84%

Zn-65 5.70%

Co-60 0.49%

Water 06/19/2008 Ind. Lab: E5936-93 H-3 1.94%

Con. Lab: SPW-3056 Sr-89 -5.65%

Sr-90 -20.89%

1-131 (Chemical) -0.56%

1-131 0.98%

Milk Ce-141 2.76%

Cr-51 7.68%

06/19/2008 Ind. Lab: E5938-93 Cs-134 -6.52%

Cs-137 1.29%

Con. Lab: SPMI-3058 Co-58 -1.94%

Mn-54 5.70%

Fe-59 6.54%

Zn-65 5.28%

Co-60 2.31%

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Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I

SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE I

INTER-LABORATORY COMPARISON PROGRAM Table 4-3 I

Inter-Laboratory Comparison Program Spiked Samples - 3 rd Quarter I

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

-3.46%

I Sr-90 9.15%

1-131 (Chemical) 1-131 6.10%

1.24%

I Ce-141 6.36%

09/18/2008 Water Ind. Lab: E6304-93 Cr-51 Cs-i134 5.09%

-7.40%

I Con. Lab: SPW-5026 Cs-137 Co-58 2.71%

0.00% I Mn-54 7.64%

Fe-59 Zn-65 6.80%

1.56%

I Co-60 1.03%

09/18/2008 Water Ind. Lab: E6303-93 H-3 3.96%

U Con. Lab: SPW-5025 Sr-89 Sr-90

-21.79%

-17.27%

I 1-131 (Chemical) 1-131 Ce-141 1.91%

-3.39%

1.12%

I 09/18/2008 Milk Ind. Lab: E6305-93 Cr-51 Cs-134 Cs-i137

-2.99%

-10.65%

-2.28%

I C o-1B -4.25%

Con. Lab: SPMI-5027 Co-58 -4.25%

Mn-54 Fe-59 3.61%

2.43%

I Zn-65 Co-60

-0.13%

-4.27% I Filter Paper Cs- 137 09/18/2008 Ind. Lab: E6306-93 Con. Lab: SPAP-5028 (Gross Beta) 5.38% I 09/18/2008 Charcoal Cartridge Ind. Lab: E6307-93 1-131 -14.75%

I Con. Lab: SPCH-5029 4-6 I

Beaver Valley Power Station RTL A9.690E 2008 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 - 4 th 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) / Ind. Lab Sr-89 6.35%

Sr-90 -0.75%

1-131 (Chemical) -5.30%

1-131 -1.25%

Ce-141 1.34%

Water Cr-51 3.37%

12/11/2008 Ind. Lab: E6370-93 Cs-134 -8.28%

Cs-137 0.71%

Con. Lab: SPW-6982 Co-58 -3.11%

Mn-54 0.73%

Fe-59 4.36%

Zn-65 2.57%

Co-60 1.41%

Water 12/11/2008 Ind. Lab: E6369-93 H-3 4.16%

Con. Lab: SPW-6981 Sr-89 -11.64%

Sr-90 -1.59%

1-131 (Chemical) -5.26%

1-131 -1.25%

Ce-141 1.41%

Milk Cr-51 -0.65%

12/11/2008 Ind. Lab: E6371-93 Cs-1 34 -8.88%

Cs- 137 0.33%

Co-58 1.63%

Con. Lab: SPMI-6983 Co-58 -1.63%

Mn-54 1.38%

Fe-59 7.60%

Zn-65 0.44%

Co-60 0.83%

4-7