L-02-059, 2001 Annual Environmental Report, Radiological

2001 Annual Environmental Report, Radiological

ML021400502
Person / Time
Site:	Beaver Valley
Issue date:	05/15/2002
From:	Pearce L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-02-059
Download: ML021400502 (86)

Text

FENOC FENOCRoute 168 Beaver Valley Power Station PO. Box 4 FirstEnergyNuclear Operating Company Shippingport, PA 15077-0004 L. W. Pearce 724-682-5234 Site Vice President Fax: 724-643-8069 May 15, 2002 L-02-059 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 2001 Annual Environmental Report, Radiological The enclosed Year 2001 Annual Radiological Environmental Operating Report for Beaver Valley Power Station (BVPS) Units 1 and 2 is being forwarded, in accordance with BVPS Technical Specification 6.9.2. The report indicates that the Environmental Monitoring Program outlined in the BVPS Offsite Dose Calculation Manual for Units 1 and 2 was followed throughout 2001. The program results demonstrate the adequacy of radioactive effluent control at the Beaver Valley Power Station and that the operations of Units I and 2 did not adversely affect the surrounding environment.

The findings of this report are summarized in the Executive Summary which is presented at the beginning of the report. Some observations from the report include the following:

"* Based on the analytical results of environmental samples during 2001, the Beaver Valley Power Station reporting levels were not exceeded.

"* Year 2001 analytical results continue to be at or below the pre-operational (1974-75) baseline results.

"* Based on the estimated dose to individuals from the natural background radiation exposure, the incremental increase in total body dose to the 50-mile population (approximately 4 million) from the operation of BVPS Units 1 and 2, is less than 0.0001% of the annual background dose. /

Beaver Valley Power Station, Unit No. 1 and No. 2 2001 Annual Environmental Report, Radiological L-02-059 Page 2 If you have any questions regarding this submittal, please contact Mr. Larry R. Freeland, Manager, Regulatory Affairs/Corrective Action at 724-682-5284.

Sincerely, L. W. Pearce Enclosure c: Mr. D. S. Collins, Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator

FENOC Beaver Valley Power Station - Units 1 & 2 Annual Radiological Environmental Operating Report Calendar Year - 2001 S- 2 2 _N_

BEAVER VALLEY POWER STATION UNITS 1 AND 2 LICENSES DPR-66 AND NPF-73 2001 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report EXECUTIVE

SUMMARY

This document is a detailed report of the 2001 Beaver Valley Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels in the vicinity of Unit 1 and Unit 2 from January 1 through December 31, 2001 in air, water, shoreline sediment, milk, fish, food crops, vegetation, and direct radiation measurement have been analyzed, evaluated, and summarized. The results of the REMP are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurement and modeling of the environmental exposure pathways.

Radiation and radioactivity in the environment is monitored within a 10 mile radius of the site.

Two types of samples are taken. The first type, control samples, are collected from areas that are beyond measurable influence of Beaver Valley Power Station. These samples are used as reference data. Normal background radiation levels, or radiation present due to causes other than Beaver Valley Power Station, can thus be compared to the environment surrounding the nuclear power station. Indicator samples are the second sample type obtained. These samples show how much radiation is contributed to the environment by the site. Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration. In 2001, samples were taken from over 60 sites around Beaver Valley Power Station that included the aquatic, atmospheric and terrestrial environments. More than 2400 analyses were performed on these samples. The environmental program for 2001 is outlined in Table 2-1.

In 1974 and 1975, prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a "pre-operational baseline". Current analysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to determine if changes in radioactivity levels are attributable to station operations. The 2001 analytical results and pre-operational baseline results are summarized in Table 2-2 and Table 2-3.

A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in the Offsite Dose Calculation Manual (ODCM) when averaged over any calendar quarter. Also, when more than one of the radionuclides are detected in the sampling medium, this report shall be submitted if:

Cnetain()+

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

Based on the analytical results of environmental samples during 2001, the Beaver Valley Power Station reporting levels were not exceeded.

Positive results attributable to the Beaver Valley Power Station were consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license. 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).

ii

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report In 2001, the radioactivity releases from BVPS Units 1 and 2 did not exceed the effluent limits identified in the Beaver Valley Power Station Operating License Technical Specification/Offsite Dose Calculation Manual (ODCM). Based on the estimated dose to individuals from the natural background radiation exposure, the incremental increase in total body dose to the 50 mile population (approximately 4 million), from the operation of Beaver Valley Power Station Units 1 and 2, is less than 0.0001 % of the annual background dose. The National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) is an estimated average of 296 mrem per year.

Analytical results are divided into four ODCM required categories based on exposure pathways:

Airborne, direct radiation, ingestion and waterborne. Each of these pathways is described below:

" The airborne exposure pathway includes airborne iodine and airborne particulates. The 2001 results 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.

" The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have indicated a stable trend and compare well with previous years.

" The ingestion exposure pathway includes milk, fish, and food product (leafy vegetable) samples. For milk samples, strontium-90 (Sr-90), attributable to past atmospheric nuclear weapons testing, was detected at levels similar to the past five years. The gamma spectroscopy counting only indicated positive results for potassium-40 (K-40) at average environmental levels. lodine-131 (1-131) was detected in four (4) milk samples at slightly above LLD levels. No other radionuclides were identified.

" The fish samples taken indicated below LLD levels in each of the samples. Vegetation samples revealed naturally occurring K-40 at average environmental levels.

" The waterborne exposure pathway includes drinking water, surface (river) water, and river sediment. Water samples were analyzed for tritium and gamma-emitting radionuclides.

Tritium was identified in one of twenty samples. The positive result was near typical lower limit of detection for tritium (H-3) analysis. Gamma analysis of samples indicated no gamma-emitting radionuclides above detection limits except one sample had naturally occurring radium-226 (Ra-226) and another sample had thorium-228 (Th-228). 1-131 analysis of weekly samples (151 total) indicated 90 positive results. None of the positive results exceeded the reporting level. It was also noted that the surface water samples, which are upstream of the plant and considered outside the influence of the site had similar results to the downstream drinking water samples.

iii

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

" Sediment samples are taken from three locations, upstream of the site, at the discharge point of liquid releases and downstream of the site. Analysis of samples indicated naturally occurring radionuclides K-40 and Ra-226 in all results. Small amounts of cesium-1 37 (Cs-1 37) from previous nuclear weapons tests was also detected in five of the six samples (including the Control location) at levels consistent with previous years. The samples from the discharge point of the site also indicated small amounts of other radionuclides, including cobalt-58 (Co-58), and cobalt-60 (Co-60) which are consistent with authorized station liquid discharges.

"* In addition to the required samples discussed above, groundwater, precipitation, soil, and feedcrops were also taken. Results were consistent with previous years and no degrading trends were identified.

The environmental monitoring program outlined in the Beaver Valley Power Station ODCM for Units 1 and 2 was followed throughout 2001. The REMP results demonstrate the adequacy of radioactive effluent control at the Beaver Valley Power Station and that the operations of Units 1 and 2 did not adversely affect the surrounding environment.

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

It should also be noted that there was a change in REMP analysis lab vendors following first quarter. This was a common process activity for the BVPS REMP.

iv

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report TABLE OF CONTENTS EXECUTIVE

SUMMARY

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

1. Program Description ............................................................................ 2-1

2. Summary of Results ............................................................................ 2-7

3. Quality Control Program ...................................................................... 2-7

4. Program Changes ............................................................................... 2-7 B. Air Monitoring ............................................................................................. 2-21

1. Characterization of Air and Meteorology ............................................ 2-21

2. Air Sampling Program and Analytical Techniques ............................. 2-21

3. Results and Conclusions .................................................................. 2-23 C. Monitoring of Sediments and Soils ............................................................. 2-26

1. Characterization of Stream Sediments and Soils ............................... 2-26

2. Sampling Program and Analytical Techniques .................................. 2-26

3. Results and Conclusions ............ ................... 2-28 D. Monitoring of Feedcrops and Food Products ............................................. 2-29

1. Characterization of Farm Products .................................................... 2-29

2. Sampling Program and Analytical Techniques .................................. 2-29

3. Results and Conclusions ................................................................... 2-31 E. Monitoring of Local Cows Milk .................................................................... 2-32

1. Description - Milch Animal Locations ................................................. 2-32

2. Sampling Program and Analytical Techniques .................................. 2-32

3. Results and Conclusions ................................................................... 2-34 F. Environmental Radiation Monitoring ........................................................... 2-37

1. Description of Regional Background Radiation and Sources ............. 2-37

2. Locations and Analytical Procedures ................................................. 2-37

3. Results and Conclusions ................................................................... 2-38 G. Monitoring of Fish ...................................................................................... 2-41

1. Description ........................................................................................ 2-41

2. Sampling Program and Analytical Techniques ..................... 2-41

3. Results and Conclusions .................................................................... 2-41 v

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report TABLE OF CONTENTS (Continued)

SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM (continued)

H. Monitoring of Surface, Drinking, Ground Waters and Precipitation ............ 2-43

1. Description of Water Sources ............................................................ 2-43

2. Sampling and Analytical Techniques ................................................. 2-44

3. Results and Conclusions ................................................................... 2-47

1. Estimates of Radiation Dose to Man .......................................................... 2-49

1. Pathways to Man - Calculational Models ........................................... 2-49

2. Results of Calculated Radiation Dose to Man - Liquid Releases ....... 2-50

3. Results of Calculated Radiation Dose to Man Atmospheric Releases ...................................................................... 2-52

4. C onclusions ....................................................................................... 2-54 SECTION 3 - LAND USE CENSUS .......................................................................... 3-1 SECTION 4 - QUALITY CONTROL PROGRAM / INTERLABORATORY COMPARISON PROGRAM A. Quality Control Program ............................................................................... 4-1

1. Split Sample Program (Contractor Laboratory Q C Laboratory ) ................................................................................... 4-1

2. Duplicate Sample Program (Contractor Laboratory Q C Laboratory) ................................................................................... 4-2 B. Interlaboratory Comparison Program ........................................................... 4-3

1. C ontractor Lab .................................................................................... 4-3 C. Co nclusions ................................................................................................. 4-4 vi

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report LIST OF TABLES Table 2-1 - Operational Radiological Environmental Monitoring Program ............ 2-2 Table 2-2 - Environmental Monitoring Program Results ....................................... 2-8 Table 2-3 - Pre-Operational Environmental Radiological Monitoring Program Sum m ary ........................................................................... 2-18 Table 2-4 - Results of Calculated Individual and Population Radiation Dose to Man - Liquid Releases ....................................................... 2-51 Table 2-5 - Results of Calculated Radiation Dose to Man Atm ospheric Releases ..................................................................... 2-53 Table 3-1 - Location of Nearest Residence, Garden, and Milch Animal ............... 3-2 Table 4-1 - Quality Control Data Contractor/Quality Control Laboratory Comparison Split Surface Water Samples, Site 2.1 ......... 4-5 Table 4-2 - Quality Control Data Contractor/Quality Control Laboratory Comparison Split Drinking Water Samples, Site 4 ........... 4-6 Table 4-3 - Quality Control Data Contractor/Quality Control Laboratory Comparison Split Milk Samples, Site 25 ........................... 4-7 Table 4-4 - Quality Control Data Contractor/Quality Control Laboratory Comparison Split Feed, Food, Sediment and Soil Samples ............... 4-8 Table 4-5 - Quality Control Data Contractor/Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate and Charcoal Filter Samples, Sites 30 and 30A ............... 4-9 Table 4-6 - Quality Control Data Contractor/Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate Samples (Gamma) (pCi/Cu Meter) ................................. 4-10 Table 4-7 - Quality Control Data Contractor/Quality Control Laboratory Comparison Thermoluminescent Dosim eters - m R/day ....................................................................... 4-11 Table 4-8 - Interlaboratory Comparison Program Independent Laboratory/Contractor Laboratory Comparison Spiked Water S am ples (pC i/I) ................................................................................ 4-12 Table 4-9 - Interlaboratory Comparison Program Independent Laboratory/Contractor Laboratory Comparison Spiked Milk S am ples (pCi/I) ................................................................................ 4-14 Table 4 Interlaboratory Comparison Program Contractor/Quality Control Laboratory Comparison Spiked Air Particulate/Charcoal Filters ....... 4-16 vii

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report LIST OF FIGURES Figure 1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station ...................................... 1-3 Figure 2 Air Sampling Stations ..................................................................... 2-22 Figure 2 Average Concentration of Gross Beta in Air Particulates ................ 2-25 Figure 2 Environmental Monitoring Locations - Shoreline Sediments and Soil ......................................................................... 2-27 Figure 2 Environmental Monitoring Program - Feedcrop and Food Product Locations .................................................................. 2-30 Figure 2 Environmental Monitoring Locations - Milk ..................................... 2-33 Figure 2 T LD Locations ................................................................................ 2-39 Figure 2 Environmental Monitoring Program - Fish Sampling Locations ....... 2-42 Figure 2 Environmental Monitoring Stations Locations - Ground, Surface Water, Drinking Water and Precipitation ........................... 2-46 viii

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report SECTION 1 - INTRODUCTION A. Scope and Objectives of the Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. The Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the FirstEnergy Nuclear Operating Company in 2001.

B. Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land. The site is approximately one mile from Midland, Pennsylvania; five miles from East Liverpool, Ohio; and twenty-five miles from Pittsburgh, Pennsylvania. Figure 1-1 shows the site location in relation to the principal population centers. Population density in the immediate vicinity of the site is relatively low. The population within a five mile radius of the plant is approximately 18,000 and the only area within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,320.

The site lies in a valley along the Ohio River. It extends from the river (elevation 665 feet above sea level) to a ridge along the border south of the Beaver Valley Power Station at an elevation of 1,160 feet. Plant ground level is approximately 735 feet above sea level.

The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam. The Pennsylvania Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. For 2001, the flow ranged from a minimum monthly average of 9,100 cubic feet per second (CFS) to a maximum monthly average of 67,900 CFS. The mean flow for 2001 was 29,783 CFS.

Water temperature of the Ohio River varies from 32 0 F to 840 F, the minimum temperatures occur in January and/or February and maximum temperatures in July and August. Water quality in the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela and Beaver rivers.

The climate of the area may be classified as humid continental. Annual precipitation is approximately 36 inches, typical yearly temperatures vary from approximately -3 0 F to 95°F with an annual average temperature of 52.3 0 F. The predominant wind direction is typically from the southwest in summer and from the northwest in winter.

1-1

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below:

Beaver Valley Unit 1 Beaver Valley Unit 2 Maximum Power Level 2652 - megawatts thermal 2652 - megawatts thermal 2689 - megawatts thermal 2689 - megawatts thermal (upgraded in October) (upgraded in October)

Type of Power PWR PWR No. of Reactor Coolant Loops 3 3 No. of Steam Generators & Type 3 - Vertical 3 - Vertical Steam Used by Main Turbine Saturated Saturated The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system.

Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam/water cycle.

1-2

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station r

SATION 514I B0 ~isNCO 50SS WILKINSEUNC, AETONN- IVSUG E.~~M KEESPORTILAA

, o EUBEVLLE... WERO -N-UR 20 40 MILES 1-3

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Environmental Radioactivity Monitoring Program

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

2-B - Air Monitoring 2-C - Monitoring of Sediments and Soils 2-D - Monitoring of Feedcrops and Food Products 2-E - Monitoring of Local Cows Milk 2-F - Environmental Radiation Monitoring 2-G - Monitoring of Fish 2-H - Monitoring of Surface, Drinking, Ground Waters and Precipitation 2-1 - Estimates of Radiation Dose to Man 2-1

Type of Sample Sampleont Sector Miles Sample Point Description Sample Frequency Sample Preparation Analysis Air Particulate and 13 11 1.4 Meyer's Farm Continuous sampling Weekly AP Gross Beta (b)

Radiolodine 30 4 0.5 Shippingport (S.S.) with sample collection Weekly Charcoal 1-131 46.1 3 2.3 Industry, RI. 68 - Garage at least weekly Quarterly Composite (c) Gamma - scan 32 15 0.8 Midland (S.S.)

48(a) 10 16.3 Weirton, W.Va., - Weirton Water Tower, Collier Way 0 51 5 8.0 Allquippa (S.S.)

"0 K) 0 (D

47 14 4.9 East Liverpool, Oh. - Water 0

Treatment Plant 27 7 6.1 Brunton's Farm 0 28 1 8.6 Sherman's Farm 29B 3 8.0 Beaver Valley Geriatric Center o.>

2 Direct Radiation 30 4 0.5 Shippingport (S.S.) Continuous (TLO) Quarterly (i) Gamma Dose 13 11 1.4 Meyer's Farm om 46 3 2.5 Industry, Midway Dr. 0 -D 32 15 0.8 Midland (S.S.) (0 48(a) 10 16.3 Weirton, W.Va. - Weirton Water Tower, Collier Way 45.1 6 1.9 . Raccoon Twp., Kennedy's M 0<

Corners IN) 51 5 8.0 Aliqulppa (S.S.)

-I 47 14 4.9 East Liverpool, Oh. - Water N)

Treatment Plant 0 70 1 3.4 North of Western Beaver 20 School - Engle Rd.

(D 80 9 8.2 Raccoon Park Office (Rit. 18) 81 9 3.6 Millcreek United Pres. Church 03m (D 82 9 6.9 Hanover Municipal Bldg. ITI 83 10 4.2 735 Mill Creek Rd. (D 14 11 2.5 Hookstown 0

2 84 11 8.3 Hancock Parks & Recreation Complex 0 85 12 5.7 Rts. 8 & 30 Intersection 86 13 6.2 E. Liverpool, Oh.

(0 1090 Ohio Ave. (0 92 12 2.8 Georgetown Rd. (S.S.)

CD 0

Types of Sample Sample Sector Miles Sample Point Description Sample Frequency Sample Preparation Analysis Points 2 Direct Radiation 87 14 7.0 Calcutta, Oh. - Calcutta Continuous (TLD) Quarterly (i) Gamma-Dose (continued) Smith's Ferry Rd. & Valley Dr. 0 88 15 2.8 Midland Heights - 110 Summit 'a N, CD 0 Rd.

89 15 4.8 Ohioville, 488 Smith's Ferry Rd. 0 90 16 5.2 1 Opposite Fairview School 10 3 1.0 Shippingport Boro 45 5 2.2 Rt. 18 & Anderson St.

60 13 2.5 444 Hill Rd.

93 16 1.1 Midland, Sunrise Hills CL 95 10 2.3 832 McCleary Rd. 70 28 1 8.6 Sherman's Farm CD 71 2 6.0 Brighton Twp. First West.

0 <

e 72 3 3.3 Industry, Logan Park 29B 3 8.0 Beaver Valley Geriatric Center 73 4 2.5 618 Squirrel Run Rd. (a)

Co N, CD 74 4 7.0 CCBC - 137 Poplar Ave.

C') CD 75 5 4.1 117 Holt Road 0' 0C)

N, 76 6 3.8 Raccoon Elementary Scho-ol 77 6 5.6 3614 Green Garden Rd 59 6 1.0' 236 Green Hill Rd. w 0 0 78 7 2.7 Raccoon Mun. Bldg. 0 27 7 6.1 Brunton's Farm 0 3.-0.

CD U) 79 8 4.4 Rt. 151 & Pross Ln.

15 14 3.7 Georgetown Post Office 46.1 3 2.3 Industry, Rt. 168 - Garage 91 2 3.9 Pine Grove Rd and Doyle Rd 04.Q (0

"-I CD 94 8 2.2 McCleary Rd. &Pole Cat Hollow Rd. zo 3 Surface Water 49(a) 3 5.0 Upstream Side of Montgomery Weekly Grab Sample (h) Weekly Sample from 1-131 ,-o Dam Site 49 0 01 2.1 14 1.5 Downstream (Midland) J&L Weekly, Intermittent Monthly composite of Gamma-scan 0 Composite Sample (h) Weekly Sample (c) 5 14 4.9 East Liverpool, Oh. - Water Daily Grab Sample Treatment Plant (raw water) Only - Collected Weekly (h)

__________________________________________________"__ uarterly Composite (c) H-3

0 "a

(D Sample Sector Miles Sample Point Description Sample Frequency Sample Preparation Typ ofSamle Analysis PointsI "4 Groundwater 14 11 2.5 Hookstown Semi-Annual Semi-Annual Gamma-scan owL03 15 14 3.7 Georgetown 0)

H-3 0.

11 3 0.8 Shippingport Boro 5 Drinking 4 15 1.3 Midland, Water Intermittent (d) Sample Weekly Composite 1-131 Treatment Plant 0 Collected Weekly Monthly Composite (d) Gamma-scan 0 Quarterly Composite (d) H-3 to.

Om O -I 5 14 4.9 East Liverpool, Oh. 0 Water Treatment Plant -)

N) 6 Shoreline Sediment 2A 13 0.2 BVPS Outfall Discharge Semi-Annual Semi-Annual Gamma-scan 00 49(a) 3 5.0 Upstream side of Montgomery 0, Dam 0ITI ro CD 0

50 12 11.8 Upstream side of New Cumberland Dam CD 3.

7 Milk 25 10 2.1 Searight's Farm Weekly (e) Weekly sample from 1-131 CL oo Searight's only 1-1 (n Biweekly (f) when Biweekly (grazing) Gamma-scan 0 animals are on pasture; Monthly (indoors) Sr-89, Sr-90, 1-131 monthly at other times.

00 96(a) 10 10.4 Windsheimer's Farm 0 r-5 27 7 6.1 Brunton's Farm *1 0o BVPS ODCM, Appendix C, Table 3,12-1 requires three (3) dairies to be selected on basis of highest potential a-4 thyroid dose using milch census data. See Section 2-E for specific locations sampled. 0 "In

-5 OD 3

0 Type of Sample Sample Sector Miles Sample Point Description Sample Frequency Sample Preparation Analysis 0 Points "a) 8 Fish 2A 13 0.2 BVPS Outfall Discharge Semi-Annual Composite of edible Gamma-scan parts by species (g) 49(a) 3 5.0 Upstream side of Montgomery 5.

Dam 0 9 Food Crops Annual at harvest if Composite of each Gamma-scan (Shlpplngport) 10 3 1.0 Three locations within 5 miles available sample species 1-131 on green leafy 0.

CL (Georgetown) 15 14 3.7 selected by BVPS. vegetables (D (Industry) 46 3 2.5 0 tn.

48(a) 10 16.3 Welrton, W.Va. U 10 Foodstuff and 25 10 2.1 Searight's Farm Monthly Monthly Gamma-scan 0 Summer Forage m R) 11 Soil 13 11 1.4 Meyer's Farm Every 3 years (1994, 30 4 0.5 Shippingport (S.S.)

12 Core Samples Gamma-scan m

,,) 1997, etc.) 3" Deep (2" Dia. at each Cii 46 3 2.5 Industry, Midway Dr. location) (approx. 10' oD 0 0 C/)

32 15 0.8 Midland (SS.) radius) 0 a) 48A(a) 10 15.6 Welrton, W.Va. - Weirton 2 Water Tower, E. Belleview Dr.

51 5 8.0 Aliquippa (S.S.) 0 0 nD CL 47 14 4.9 E. Liverpool, Oh. - Water a.. M Treatment Plant (D 27 7 6.1 Brunton's Farm 22 8 0.3 South of BVPS Transmission Line 0 29A 3 8.3 Nicol's Farm 0 12 Precipitation 30 4 0.5 Shipplngport (S.S.) Weekly grab samples Quarterly Composite (c) Gamma-scan, H-3 0 47 14 4.9 East Liverpool, Oh. - Water when available Treatment Plant 48 10 16.3 Welrton, W.Va. - Weirton Water Tower, Collier Way 0

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 2 Notations Operational Radiological Environmental Monitoring Program (Continued)

Notes:

(a) Control sample station: These are locations which are presumed to be outside the influence of plant effluents.

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

(c) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location.

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

(e) Weekly milk sample from Searight's Dairy is analyzed for 1-131 only.

(f) Milk samples are collected bi-weekly when animals are in pasture and monthly at other times.

(g) The fish samples will contain whatever species are available. If the available sample size permits, then the sample will be separated according to species and compositing will provide one sample of each species. If the available size is too small to make separation by species practical, then edible parts of all fish in the sample will be mixed to give one sample.

(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. A weekly grab sample is obtained from daily composited grab samples obtained by the water treatment plant operator at location 5. For location 49, a weekly grab sample is obtained by a field technician.

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

2-6

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

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 NRC Regulatory Guide 4.8 and in accordance with Beaver Valley Power Station Offsite Dose Calculation Manual. Summaries of results of analysis of each media are discussed in Sections 2-B through 2-H and an assessment of radiation doses are given in Section 2-1. Table 2-3 summarizes Beaver Valley Power Station preoperational ranges for the various sampling media during the years 1974 and 1975. Comparisons of preoperational data with operational data indicate the ranges of values are generally in good agreement for both periods of time.

Activity detected 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 the Beaver Valley Power Station has resulted in no significant changes to the environment.

3. Quality Control Program The Quality Control Program implemented by the Beaver Valley Power Station to assure reliable performance by the contractor and the supporting QC data are presented and discussed in Section 4 of this report.

4. Program Changes The following changes were implemented in the 2001 sampling program.

None 2-7

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

Type and Lower Limit Medium of Pathway Number of m Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean (M) Name *Mean (f) *Mean (f) Reported 0CD (Unit of Measurement) Performed * (LLD)

• Range Distance and Directions

• Range *Range Measurements*** -I IT!

Weirton, WV No. 48 0 Water Gammna (12)

Precipitation Mn-54 5 LLD CO (pCi/I) 0 Fe-59 10 LLD ...... 0 CD 0<

Co-58 5 LLD ...... 0 0'4 -I 0, Co-60 5 LLD ...... 3 0 0 M CD Z n -6 5 10 LL D -- .... 0 20 Zr/Nb-95 (a 5 LLD ...... 0 C s-134 5 LL D -- "" 0

"" 0 C s-13 7 5 LL D -- .... 0 o

Ba/La-140 10 LLD -.... 0 -I 11-3 (12) 200 410 (4/12) CD 30, Shippingport, (S.S.) 410 (4/4) LLD 0 (242-577) 0.5 mi ENE (242-577) (n to CD

• Nominal Lower Limit of Detection (LLD) -O "0

" Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations Is Indicated in parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

Type and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean (f) Name ** Mean (f) ** Mean (f) Reported (Unit of Measurement) Performed * (LLD*

• Range Distance and Directions **Range **Range Measurements***

a)

Georgetown, PA No. 15 m 0

Groundwater H-3 (6) 200 214 (1/4) 11. Shippingport Boro 214 (1/6) LLD 0 0 (pCi/I) 0,8 mi NE Gamma (6)

Mn-54 5 LLD ...... 0 Q -I E

C" 00 Fe-59 10 LLD ...... 0 0 (0 CD Co-58 5 LLD ...... 0 0

Co-60 5 LLD ..... 0 0

Zn-65 10 LLD ...... 0 34 CD 0-5M (D Zr/Nb-95 5 LLD ...... 0 CL "aD Cs-134 5 LLD ...... 0 Cs-137 5 Lid ...... 0 Ba/La-140 10 LLD ..... 0 CD 00 0,

14 Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

Type and 0 Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean (f) Name ** Mean (f) ** Mean (f) 0 CU Reported (Unit of Measurement) Performed * (LLD)

• Range Distance and Directions ** Range

• Range Measurements*** m Drinking Water 0 1-131 (100) 1.0/0.5 (1) 0.81 (58/100) 4, Midland 0.84 (29/50) 0 (pCi0) (0.20-1.90) Water Treatment Plant (0.40-1.90) 1.3 mi NNW (D H-3 (8) 200 R. --4 LLD LLD 0 r+ CD 0

N) Gamma (24) 0'--.

oow U)

Mn-54 5 LLD ...... 0 00 Fe-59 10 LLD ...... 0 0 0 Co-58 5 LLD ...... 0 Co CD Co-60 5 LLD ..... 0 Zn-65 30/10(1) LLD ...... (D 0

Zr/Nb-95 15/5(1) LLD ..... 0 2)

Cs- 134 5 LLD ... (D CD 0

Cs-137 5 LLD -0 0 U-Iq BaILa-140 15/10(1) LLD -- 0 "to 0

(1) LLD for first vendor (1 ' Quarter 2001) /LLD for second vendor (remainder of 2001).

• Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is Indicated In parentheses (f)

• • • Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit I and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

Type and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection

• Mean (f) Name ** Mean (f) ** Mean (f) Reported K)

(Unit of Measurement) Performed * (LLD) ** Range Distance and Directions

• Range ** Range Measurements*** 0 0

49, Upstream side of Montgomery Dam Surface Water 1-131 (51) 1.010.5 (1) 1.01 (32/51) One Sample Location One sample 0 (pCi/l) (0.30-3.70) location M E1, H-3 (12) 200 209(1/12) 2.1, Downstream 209(1/4) LLD 0 Midland - J&L 1.5 mi WNW Gamma (36) C.

0 Mn-54 5 LLD 0 -i Fe-59 15/100() LLD 0 0 0 (D 0

.. , Co-58 5 LLD 0 0 e

CD

.. L Co-60 5 LLD 0 0M 0 Zn-65 30/ 10(l) LLD 0 z4 Zr/Nb-95 15/5(l) LLD 0 -Il CD Cs-134 5 LLD 0 0 2D Cs-137 5 LLD 0 (D BaLa.-140 15 LLD 0 0O Ra-226 (a) 66 (1/12) 49, Upstream side, 66 (1/12) 66 (1/12) 0 of Montgomery Dam 5.0 mi NE Th-228 (a) 0.84 (1/12) 49. Upstream side, 0.84 (1/12) 0.84 (1/12) 0 of Montgomery Dam 5.0 mi NE (1) LLD for first vendor (I' Quarter 2001) / LLD for second vendor (remainder of 2001).

(a) LLD for this nuclide for water not required by ODCM.

• Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated In parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver. Pennsylvania Reporting Period Annual 2001 03 (County, State)

Type and Lower Limit Medium of Pathway Number of Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations m Nonroutine Sampled of Analysis Detection ** Mean (0 Name ** Mean (f)

• Mean (f) Reported M (Unit of Measurement) Performed * (LLD)

• Range Distance and Directions ** Range 0i.

• • Range Measurements***

Montgomery Dam No. 49 Sediment Gamma (6)

(pCi/g)

(dry weight) K-40 (a) 11,07 (6/6) 49, Upstream side of 14.20(2/2) Same as 0 (7.10-15.80) 0 Montgomery Dam (12.60-15.80) High Location 0 <

5.0 mi NE 0

Co-58 (a) 0.22 (2/6) 2A, BVPS Outfall 0.22 (2/2) None Detected 0 I?

N, (D (0.20-0.23) 0.2 ml W (0.20-0.23) N, Co-60 (a) 0.82 (2/6) 2A, BVPS Outfall 0.82 (2/6) None Detected N, 0 0 (0.70-0.93) 0.2 mi W CD (0.70-0.93) 0 0 M Cs- 134 0.06 -. .... None Detected 0

-I Cs-137 "Ca r.

0.08 0.13 (5/6) 2A, BVPS Outfall 0.15 (4/4) Same as 0 00 C CD (0.07-0.16) 0.2 ml W & 49, (0.14-0.16) High Location 0. .9 Upstream side of 3 Montgomery Dam 5.0 mi NE CD Ra-226 (a) 1.85(6/6) 49, Upstream side of 2.26(2/2) Same as 0 (1,21-2.35) Montgomery Dam (2.16-2.35) Hligh Location 00 5.0 mi NE (a) LLD for this nuclide for Sediment not required by ODCM "1M CD

• Nominal Lower Limit of Detection (LLD) O0

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations Is Indicated In parentheses (f)

• Nonroutine reported measurements are defined In Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver. Pennsylvania Reporting Period Annual 2001 (County, State)

Type and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean (f) Name ** Mean (f) ** Mean (f) Reported (Unit of Measurement) Performed * (LLD) ** Range Distance and Directions ** Range ** Range Measurements***

Windsheimer No. 96 m

0 Milk 1-131(146) 1.0/0.5 (1) 0.6(4/146) 27. Bmnton's Farm 0.7 (3/18) 0.4 (1/18) 0 (pCi/I) (0.4-0.8) 6.1 mi SE (0,5-0.8)

Sr-89 (126) 2.0 LLD Sr-90 (126) 0.7 1.9 (116/126) 69 Collins 3.5 (18/18) 1.6 (19/21) 0 0 (0.6-5.1) 3.5 mi SE (1.5-5.1) (0.6-4.6) 0

-I Gamma (126) C" 1 "CD N,, K-40 (a) 1429 (126/126) 69 Collins 1729 (18/18) 1484 (21/21) 0 00 (1079/2048) 3.5 mi SE (1350-2048) (1290-1608) ". CD 0 '10o v'4. CD Cs-134 5 LLD ...... 0 0

Cs-137 5 LLD ..... 0 0

-5 Cl C-0<

CDC (D

0D (0 W Ba/La-140 15/10(1) LLD ...... 0 -u

-I "CDCD Ou

D (1) LLD for first vendor (1I"Quarter 2001) / LLD for second vendor (remainder of 2001).

(a) LLD for this nuclide for Milk not required by ODCM

• Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated In parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

Type and Lower Limit Number of Medium of Pathway Total Number of AlU Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean (f) Name

• Mean (f) ** Mean (f) Reported (Unit of Measurement) Performed * (LLD)

• Range Distance and Directions

• Range ** Range Measurements***

m Weirton, WV No. 48 Food and Garden 1-131 (4) 0.06 LLD 0 (

0 Crops (pCilg) 0 (wet weight) Gamma (4) (D K-40 (a) 3.0(4/4) 46, Industry, 5.2(1/1) 2.6 (1/1) 0 '

(1.8-5.2) Midway Dr. "-I 2.5 mi NE C° 00 Cs- 134 0.06 LLD ....

rl 0 0 N)

Cs- 137 0.06 LLD

,a

.... 0 0

-4. 0 0

(D 05 CL 0.

e 0

(a) LLD for this nuclide for Food and Garden Crops not required by ODCM

• Nominal Lower Limit of Detection (LLD)

• Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated

• in parentheses (f)

Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit I and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

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

0 Sampled of Analysis Detection

• Mean (f) Name ** Mean (f) ** Mean (M) Reported (Unit of Measurement) Performed * (LLD) ** Range Distance and Directions ** Range

• Range Measurements*** 0 rn Upstream Montgomery Dam No. 49 Fish Gamma (8)

CD (pCi/g)

(wet weight) Mn-54 0.05 LLD ...... 0 Fe-59 0.10 LLD ...... 0 r3 0" Co-58 0.05 LLD ...... 0 ,a 0 (CD Co-60 0.05 LLD ..... 0 CL 2) 0 Zn-65 0.10 LLD .. 0 1-4 CD Cs-134 0.05 LLD ..... 0 (D) 0 Cn r+

Cs-137 0.06 LLD ...... 0 r-

'a 00

• Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver, Pennsylvania Reporting Period Annual 2001 (County, State)

Type and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean (f) Name ** Mean (f) ** Mean (1) Reported (Unit of Measurement) Performed * (LLD) ** Range Distance and Directions ** Range

• Range Measurements*** m Weirton, WV No. 48 CU External Radiation Gamma (174) 0.05 0.19 (174/174) 84, Hancock Co. Parks 0.23 (4/4) 0 0.21 (4/4) 0 (mR/day) (0.11-0.26) & Recreation Center (0.20-0.26) 8.3 mi SW (0.16-0.24) 3 Feed and Forage Gamma (12) oCD (pCi/g) 0<

(wet) (D 0

IF --. 3" 0*

Be-7 (a) 1.2 (7/12) One sample -- One sample 0 0

(0.8-2.3) location location

-u 0 0 0 K-40 (a)

(0 13.2 (12/12) One sample -- One sample 0 (9.0-17.5) location 1-1 location C

1-131 CDL (a) None Detected One sample -- One sample 0 location location 3 o

Cs-134 (a) None Detected One sample -- One sample 0 in a (0

location CD location (0 'a Cs-137 (a) None Detected One sample -- One sample 0 location location (a) LLD for this nuclide for Feed and Forage not required by ODCM 0

• Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Valley Power Station Unit 1 and 2 Docket No. 50-334/50-412 Location of Facility Beaver. Pennsylvania Reporting Period Annual 2001 (County, State) 0 Type and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine m Sampled of Analysis Detection **Mean (f) Name ** Mean (f) **Mean (0 Reported 0 (Unit of Measurement) Performed * (LLD) ** Range Distance and Directions ** Range

• Range Measurements***

0 mS" Weirton, WV No. 48 Air Particulate Gross Beta 2 23 (530/530) 32, Midland (S.S.) 24(53/53) 23 (53/53) 0 CD and Radioiodine (530) (8-56) 0.8 mi NW (11-50) (8-45) r-

-5. - C)

(XIO-3 pCi/Cu.M.) 1-131(530) 0.04 LLD 0 5 <

Gamma (40) 3 "4 Be-7 (a) 63 (40/40) 51, Aliquippa, 67 (4/4) 62 (4/4) 0 0 (37-87) Sub Station (48-87) (50-77) Q 0 o0 M 8.0 mi E Cs-134 0.8/0.5(l) LLD 0 0 r 00

'a Cs- 137 0.7/0.5(1) LLD 0 (a C Ci)

(D) to CD (I) LLD for first vendor (1" Quarter 2001) /LLD for second vendor (remainder of 2001). 0 (a) LLD for this nuclide for Air Particulate not required by ODCM

• Nominal Lower Limit of Detection (LLD)

• • Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

• Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975).

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility Beaver Valley Power Station Docket No. 50-334 Location of Facility Beaver, Pennsylvania Reporting Level CY 1974 - 1975 (County) (State)

Pre-Operational Program Summary (Combined 1974 - 1975)

Medium or Pathway Analysis and Total Lower Limit of All Indicator Locations Sampled Number of Analysis Detection (LLD) Mean, (f) Range (Unit of Measurement) Performed Sediments Gross Alpha (0) --..

pCi/g (dry) Gross Beta (33) 1 18 (33/33) 5- 30 Sr-90 (0) ....

U-234, 235, 238 (0) -

Gamma (33) -- 13 (33/33) 2 - 30 K-40 1.5 13 (33/33) 2-30 Cs-137 0.1 0.4 (21/33) 0.1 -0.6 Zr/Nb-95 0.05 0.8 (12/33) 0.2 - 3.2 Ce-1 44 0.3 0.5 (3/33) 0.4 - 0.7 Ru-106(a) 0.3 1.5 (3/33) 1.3-1.8 Others -- < LLD Foodstuff Gamma (8) ....

pCi/g (dry) K-40 1 33 (8/8) 10- 53 Cs-137 0.1 0.2 (1/8) -

Zr/Nb-95 0.05 0.2 (1/8) -

Ru-1 06(a) 0.3 0.8 (1/8) -

Others -- < LLD Feedstuff Gross Beta (80) 0.05 19 (80/80) 8 - 50 pCi/g (dry) Sr-89 (81) 0.025 0.2 (33/81) 0.04-0.93 Sr-90 (81) 0.005 0.4 (78/81) 0.02-0.81 Gamma (81) ....

K-40 1 19 (75/81) 5-46 Cs-1 37 0.1 0.5 (6/81) 0.2- 1.6 Ce-144 0.3 1.5 (5/81) 0.9-2.6 Zr/Nb-95 0.05 0.8 (13/81) 0.2- 1.8 Ru-106(a) 0.3 1.4 (12/81) 0.6-2.3 Others -- < LLD Soil Gross Alpha (0) --..

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

Sr-90 (64) 0.05 0.3 (48/64) 0.1 - 1.3 U-234, 235, 238 (0) --..

Gamma (64) ....

K-40 1.5 13 (63/64) 5-24 Cs-137 0.1 1.5 (56/64) 0.1-6.8 Ce-144 0.3 1.1 (7/64) 0.2-3 Zr/Nb-95 0.05 0.3 (13/64) 0.1 - 2 Ru-106(a) 0.3 1.1 (3/64) 0.5-2 Others -- < LLD (f) Fraction of detectable measurements at specified location.

2-18

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report 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, Pennsylvania Reporting Level CY 1974 - 1975 (County) (State)

Pre-Operational Program Summary (Combined 1974 - 1975)

Medium or Pathway Analysis and Total Lower Limit of All Indicator Locations Sampled Number of Analysis Detection (LLD) Mean, (f) Range (Unit of Measurement) Performed Soil Gross Alpha (0) ....

pCi/g (dry) Gross Beta (8) 1 21 (8/8) 16- 28 (Core Samples) Sr-89 (8) 0.25 < LLD Sr-90 (8) 0.05 0.2 (5/8) 0.08 - 0.5 Gamma (8) ....

K-40 1.5 13 (8/8) 7-20 Cs-137 0.1 1.2 (7/8) 0.2-2.4 Co-60 0.1 0.2 (1/8) -

Others -- < LLD Surface Water Gross Alpha (40) 0.3 0.75 (5/40) 0.6 - 1.1 pCi/I 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) ....

pCi/I Gross Alpha (50) 0.3 0.6 (4/50) 0.4 - 0.8 Gross Beta (208) 0.6 3.8 (208/208) 2.3 - 6.4 Gamma (0) --..

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

Sr-89 (0) -

Sr-90 (0) -

Ground Water Gross Alpha (19) 0.3 < LLD pCi/I Gross Beta (76) 0.6 2.9 (73/75)(b) 1.3 - 8.0 Tritium (81) 100 440 (77/81) 80 - 800 Gamma (1) 10-60 < LLD Air Particulates Gross Alpha (188) 0.001 0.003 (35/188) 0.002 - 0.004 and Gaseous Gross Beta (927) 0.006 0.07 (927/927) 0.02 - 0.32 pCi/m 3 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) 0.01 - 0.04 Others < LLD (f) Fraction of detectable measurements at specified location.

2-19

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report 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, Pennsylvania Reporting Level CY 1974 - 1975 (County) (State)

Pre-Operational Program Summary (Combined 1974 - 1975)

Medium or Pathway Analysis and Total Lower Limit of All Indicator Locations Sampled Number of Analysis Detection (LLD) Mean, (f) Range (Unit of Measurement) Performed Milk 1-131 (91) 0.25 0.6 (4/91) 0.3-0.8 pCi/I Sr-89 (134) 5 7 (4/134) 6- 11 Sr-90 (134) 1 5.3 (132/134) 1.5- 12.8 Gamma (134) ....

Cs-137 10 13 (19/134) 11-16 Others < LLD External Radiation y- Monthly (599) 0.5 mR* 0.20 (599/599) 0.08- 0.51 mR/day y- Quarterly (195) 0.5 mR* 0.20 (195/195) 0.11 -0.38 y - Annual (48) 0.5 mR* 0.19 (48/48) 0.11 - 0.30 Fish Gross Beta (17) 0.01 1.9 (15/17) 1.0-3.2 pCi/g (wet) Sr-90 (17) 0.005 0.14 (17/17) 0.02-0.50 Gamma (17) 0.5 K-40 2.4 (17/17) 1.0-3.7 Others < LLD LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD).

(a) May include Ru-1 06, Ru-1 03, Be-7.

(b) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample).

(f) Fraction of detectable measurements at specified location.

2-20

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report 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) off site air sampling stations. The locations of these stations are listed in Table 2-1 and shown on a map in Figure 2-1.

The air sample stations were upgraded during the year and as a result of the upgrade, sample flow was increased from one to two cubic feet per minute. The charcoal filters were changed in order to maintain collection efficiency at the higher flow rate.

Samples are collected at each of these stations by continuously drawing one to two cubic feet per minute of atmosphere air through a glass fiber filter and through a charcoal cartridge. The former collects airborne particulates; the latter is for radioiodine sampling. Samples are collected for analysis on a weekly basis.

The charcoal is used in the weekly analysis of airborne 1-131. The filters are analyzed each week for gross beta, then composited by station for quarterly analysis by gamma spectrometry. In order to reduce interference from natural radon and thoron radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.

b. Procedures Gross beta analysis is performed by placing the filter paper from the weekly air sample in a 2" p!anchet and counting it in a low background, gas flow proportional counter.

Gamma emitters are determined by stacking all the filter papers from each monitoring station collected during the quarter and scanning this composite on a high resolution germanium gamma spectrometer.

Radioiodine (1-131) analysis is performed by a gamma scan of the charcoal in a weekly charcoal cartridge.

2-21

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-1 Air Sampling Stations Site No. Distance Site No. Distance (miles) L n Sector (miles) Location 13 11 1.4 Meyer's Farm 32 15 0.8 Midland (S.S.)

27 7 6.1 Brunton's Farm 46_._1 3 2.3 Industry Rt. 68 - Garage 28 1 8.6 Sherman's Farm 47 14 4.9 East Liverpool, Oh. - Water

_____Treatment Plant 29B 3 8.0 Beaver Valley Geriatric Center 48 10 16.3 Weirton, W.Va. -Weirton 30 Water Tower, Collier Way 30 0.5 Shippingport (S.S.) 51 5 8.0 Aliluipga (S.S.)

30A 4 0.5 Shippingport (S.S.) 1

_,__7___I .

2-22

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

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

a. Airborne Radioactive Particulates A total of five hundred thirty (530) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years. Figure 2-2 illustrates the weekly average concentration of gross beta in air particulates.

For the week ending 11/19/01, the average for the air particulate gross beta counts were approximately double the results of the yearly average. The Control location, which is considered outside the influence of the Beaver Valley Power Station, also indicated the elevated readings that week. When the quarterly gamma spectroscopy analysis was performed, only naturally occurring isotopes were identified (see below). Three Mile Island, Limerick, Davis Besse, and the Pennsylvania Department of Environmental Protection (Pa. DEP) have also experienced elevated readings in the same range as BVPS. No evidence points to the elevated readings being the result of plant operations.

The weekly air particulate samples were composited to forty (40) quarterly samples which were analyzed by gamma spectrometry. Naturally occurring beryllium-7 (Be-7) was present in all samples. No other radionuclides were detected. Results are listed in the summary Table 2-2.

Based on the analytical results, the operation of Beaver Valley Power Station did not contribute any measurable increase in air particulate radioactivity during 2001.

b. Radioiodine A total of five hundred thirty (530) weekly charcoal filter samples were analyzed for 1-131. No detectable concentrations were present at any locations.

Based on analytical results, the operation of Beaver Valley Power Station did not contribute any measurable increase in airborne radioiodine during 2001.

2-23

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

c. Deviations from required sampling/analysis schedule

" CR 01-4411 was written because the vendor lost four of the thirteen weekly air particulate samples from site 13 in the first quarter. The weekly gross beta analysis was performed on all the weekly samples from site 13; however, when they were ready to perform the quarterly composite gamma spectroscopy analysis for site 13, only 9 of the 13 weeks could be located.

The vendor performed the gamma spectroscopy analysis with the 9 available weekly samples with the results indicating only naturally occurring Be-7 being identified. The DEP has an air sampling station co-located with BVPS at site

13. Results from the DEP first quarter composite was less than (L.T.)

1E-4 pCi/m 3 for both cesium-134 (Cs-134) and Cs-137. The weekly gross beta analysis results for the four weeks that were later lost were all within normal range with 3 of the 4 being below the Control location. This condition report also documents the vendors failure to meet the sensitivities for barium-140 (Ba-1 40) as stated in 1/2-ENV-02.01 for all ten air sampling sites during the quarterly gamma spectroscopy analysis. All other sensitivities for air sample analysis were met. It should be noted that Ba-1 40 does not have an ODCM required LLD to be met. This was the last report from this vendor.

Starting on 4/1/02, BVPS began using a new vendor and no other occurrences of this nature have resulted.

" CR 01-3637 was written to document BVPS response to OE 12361. OE 12361 concerned F&J holders used for air particulate/charcoal cartridge air sampling for a REMP program. The problem concerned the charcoal cartridge being loose -in the holder and air being allowed to bypass the charcoal cartridge instead of going through it. BVPS reviewed the holders used for REMP air sampling at BVPS. It was found that BVPS uses Model RVH-35 from Hi-Q Environmental Products Co. not the holders in question. Also, the holder used by BVPS was loaded with the air and charcoal filters and it was found that there was no indication that the charcoal cartridge was loose as described in the OE. In addition, BVPS has vacuum gauges that would indicate a leak (lowered resistance).

2-24

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-2 Average Concentration of Gross Beta in Air Particulates Ir Le IL se

_z o

F z

U. t UL 0.

0 0

U.

F 0

z4 L5LL 0

0 0

"*wno/lod 2-25

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report C. Monitoring of Sediments and Soils 1 Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.

2. Sampling Program and Analytical Techniques

a. Program River bottom sediments were collected semi-annually above the Montgomery Dam, in the vicinities of the Beaver Valley discharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 2-1 and are shown in Figure 2-3.

Soil samples were not required in 2001. The next year for sampling is 2003.

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

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

b. Analytical Procedures Gamma analysis of sediment or soil is performed in a 300 ml plastic bottle which is counted by a gamma spectrometer.

2-26

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-3 Environmental Monitoring Locations - Shoreline Sediments and Soil

.. I -:_- ,,, - -J f týt SOIL SAMPLING LOCATIONS Site Sector Distance D Location Site Sector Distance Location No. (miles) No. - (miles) Location 13 11 1.4 Meer s Farm 32 15 0.8 Midland (S.S.)

22 8 0.3 South of BVPS Transmissioný- 46 3 2.5 Industry, Midway Dr.

Line 27 7 6.1 Brunton's Farm 47 14 4.9 East Liverpool, Oh. - Water Treatment Plant 29A 3 8.3 Nicols Farm 48A 10 15.6 Weirton, W.Va. - Weirton Water I_ I Tower, E. Belleview Dr.

30 4 0.5 Shippingport (S.S.) . 51 5 8.0 Aliquippa (S.S.)

2-27

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

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

a. Sediment A total of six (6) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was detected in all six samples. Ra-226 was detected in six samples. Small amounts of Cs-1 37 from previous nuclear weapons tests were detected five of the six river sediment samples, including two upstream above Montgomery Dam, which is unaffected by plant effluents. Small amounts of Co-58 and Co-60 were detected in the Beaver Valley Power Station discharge area and are attributable to station releases. The activity detected in the station discharge area is consistent with station data of authorized radioactive discharges which were within limits permitted by the NRC license.

The positive results detected are attributable to authorized releases from the Beaver Valley Power Station and are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.

2-28

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report D. Monitoring of Feedcrops and Food Products

1. Characterization of Farm Products According to the latest data from the 1999 Statistical Summary and Pennsylvania Department of Agriculture Annual Report, there were approximately 650 farms in Beaver County. The cash receipts from the sale of agricultural crops and livestock was $16,199,000. The principal source of revenue was in dairy products which was estimated at $7,020,000. Revenues from other farm products were estimated as follows:

Field Crops $1,703,000 Fruits $291,000 Horticulture and Mushrooms $3,894,000 Vegetables and Potatoes $372,000 Poultry and Meat Products $2,919,000

2. Sampling Program and Analytical Techniques

a. Program Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 2-4. Each sample is analyzed by gamma spectrometry.

Food products (vegetables) were collected at garden locations during the summer of 2001. Leafy vegetables, i.e., cabbage, were obtained from Shippingport, Georgetown, Industry, PA, and Weirton, W.Va. All samples were analyzed for gamma emitters by gamma spectroscopy. Samples were also analyzed by radiochemical analysis for 1-131.

2-29

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-4 Environmental Monitoring Program - Feedcrop and Food Product Locations

[

Sample Type Site No. Location Food 10 Shippingport Food 15 Georgetown Food 46 Industry Food 48 Weirton, W.Va.

Feed 25 Searight's Dairy 2-30

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

b. Procedures Gamma emitters in feed are determined by scanning a dried, homogenized sample with the gamma spectroscopy system. A high resolution germanium detector is utilized with this system. Food samples are loaded into tared 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.

1-131 in food crops is determined by radiochemistry. Stable iodide carrier is first added to a chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and treated with sodium hypochlorite. The iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into toluene. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.

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

a. Feed A total of twelve (12) samples were analyzed by gamma spectroscopy. Only naturally occurring nuclides were identified, for example: K-40 in all the samples and Be-7 in seven (7).

CR 01-3132 was written for two monthly feed samples from site 25, January and February, because the vendor failed to achieve the procedurally required LLDs for 1-131. Feed sampling is not required by the BVPS ODCM and there are no licensing required LLDs. The other procedurally required LLDs for these samples were met. No positive 1-131 results were seen for the entire year from any of the 42 milk sample results obtained from this site. This vendor was replaced starting 4/1/01 and no other LLD occurrences have occurred for feed samples.

b. Food A total of four (4) samples were analyzed for 1-131. No detectable concentrations were present.

A total of four (4) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was present in all samples. No other nuclides were identified.

c. The data from food and feed analyses were consistent with previous data. Based on the analytical results, the operation of the Beaver Valley Power Station did not contribute any measurable increase in radioactivity in the foods and feeds in the vicinity of the site.

2-31

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report E. Monitoring of Local Cows Milk

1. Description - Milch Animal Locations Samples of fresh milk are obtained from milch animals at locations and frequencies noted in Table 2-1. This milk is analyzed for its radioiodine content, gamma emitters, and 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 Milk was collected from two (2) reference dairy farms (Searight's and Brunton's) within a 10-mile radius of the site and from one (1) control location (Windsheimer's) outside of the 10-mile radius. Additional dairies, which represent the highest potential milk pathway for radioiodine based on milch animal surveys and meteorological data, were selected and sampled. These dairies are subject to change based upon availability of milk or when more recent data (milch animal census) indicate other locations are more appropriate. The location of each is shown in Figure 2-5 and described below.

Approximate Direction and Distance from Collection Site Dair Number of Animals Midpoint of Unit 1 Reactor Period being Milked 25 Searight 51 Cows 2.1 miles SSW Jan. - Dec.

27 Brunton 94 Cows 6.1 miles SE Jan. - Dec.

69* Collins 6 Goats 3.5 miles SE Apr. - Dec.

96 Windsheimer 75 Cows 10.4 miles SSW Jan. - Dec.

103* Halstead 62 Cows 5.2 miles SSW Jan.- Apr.

105* Ambrose 32 Cows 3.9 miles WSW Jan. - Dec.

106* Conkle 32 Cows 3.7 miles WSW Jan. - Dec.

Highest potential pathway dairies The sample from Searight Dairy is collected and analyzed weekly for radioiodine using a procedure with a high sensitivity. Samples from each of the other selected dairies are collected monthly when cows are indoors, and bi-weekly when cows are grazing. This monthly or bi-weekly sample is analyzed for Sr-89, Sr-90, gamma emitters including Cs-1 37 (by high resolution germanium gamma spectroscopy) and 1-131 (high sensitivity analysis).

2-32

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-5 Environmental Monitoring Locations - Milk Site Sector Location Site Sector Distance Location No. (miles) No. (miles) 25 10 2.1 Seanght's Farm  : 103 10 5.2 Halstead Farm 27 7 6.1 Brunton's Farm 105 12 3.8 Ambrose Farm 69* 7 3.4 Collins 106' 12 3.7 Conkle Farm 96 10 10.4 Windsheimerns Farm , "

I Dairies selected based on highest deposition factors.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

b. Procedure Radioiodine (1-131) analysis in milk was performed using chemically prepared samples and analyzed with a low-level beta counting system.

Gamma emitters are determined by gamma spectroscopy of a 1 liter Marinelli container of milk.

Strontium milk samples are prepared by adding stable strontium carrier and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is purified in all samples by the Argonne method using 3 grams of extraction material in a chromatographic column. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for the ingrowth of yttrium-90 (Y-90). Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate.

The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Sr-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 gravimetrically.

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

a. A total of one hundred twenty-six (126) samples were analyzed for Sr-89 and Sr-90. No Sr-89 was detected. Sr-90 was detected in one hundred sixteen (116) samples at levels attributable to previous nuclear weapons tests and are within the normally expected range.

b. A total of one hundred twenty-six (126) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was present in all samples. No other radionuclides were identified.

c. A total of one hundred and forty-six (146) samples were analyzed for 1-131 during 2001. 1-131 activity was detected in four (4) samples below the required LLD. Three (3) were detected at the same location where the dairy farmer had obtained additional water from the Midland Water Plant (site 4) in 2001. This practice was noted to have also taken place in 1999.

The fourth positive reading was detected at the Control location and was below the required LLD. Additional information may be found in Section 3-d (CR 02-00428).

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

d. Five Condition Reports were written concerning milk sample analysis.

" CR 01 -3446 was written because one milk sample taken 1/30/01 at site 25 was not analyzed. The vendor did not ship sample to subcontracted vendor for analysis. Once discovered, it was too late to count due to half-life concerns since analysis was for I-131. This vendor has since been replaced.

" CR 01 -2177 was written for one sample from site 25 taken 4/10/01 that was lost in shipment. This sample was for 1-131 analysis only. This is the only sample lost in shipment for the year and this is not a recurring problem.

" CR 01 -2591 was written for twelve monthly milk samples taken in January and February because the vendor failed to achieve the procedurally required Lower Limit of Detection for Sr-89 (all 12 samples) and Ba-140 (1 sample). The twelve Sr-89 samples ranged from 3.9 to 4.5 pCi/liter, which is above the procedural requirement of 2 pCi/liter. The Ba-140 sample was 12 pCi/liter, which is above the procedural requirement of 10 pCi/liter. It should be noted that the Ba-1 40 result was within the required ODCM LLD value of 15 pCi/liter and that Sr-89 does not have a ODCM required LLD. At the time of analysis, the primary vendor was subcontracting out the work and did not effectively communicate the LLD requirements to the subcontracted vendor. Starting 4/1/01, a new primary vendor has been contracted and no LLD problems have been noted.

" CR 01-0827 was written because seven environmental milk samples analyzed by the vendor failed to meet the required Lower Limit of Detection (LLD) for Sr-89. The required limit is 2 pCi/liter. For these seven samples, the LLDs ranged from 3.0 to 9.1 pCi/liter.

Probable cause, as documented by the vendor, is "a longer than anticipated interruption in production" due to move to a new laboratory facility. Starting 4/1/01, a new primary vendor has been confirmed and no LLD problems have been noted.

2-35

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report CR 02-00428 was written to document the positive 1-131 results found at site 27. Three of the eighteen milk samples from one of the indicator dairies (site 27) indicated positive for 1-131 in 2001. All three were below the reporting level of 3 pCi/I and were also below the ODCM required Lower Level of Detection of 1.0 pCi/I (the range of the results were 0.5 to 0.8 pCi/I). This was seen in 1999 when we had seven positive 1-131 results at this same dairy. The investigation in 1999 concluded that it was because the dairy had run out of water at the farm and was getting water from the Midland Water Dept. Again this year, the dairy needed to supplement their water with water from the Midland Water Dept. from July to end of December. BVPS has for many years seen positive 1-131 results both upstream and downstream of the plant at low levels (including the Midland Water Plant). Evidence indicates that the positive milk results are likely from the cows drinking water from the Midland Water Plant. Brunton's was contacted and they confirmed that they still do not pasture their milk cows and there feed is from storage. This feed is stored from 2 to 10 months. All weekly iodine air samples at site 27 indicated < MDA.

e. Based on all the analytical results and the above investigation, the operation of the Beaver Valley Power Station did not contribute any measurable increase in radioactivity in the milk in the vicinity of the site.

2-36

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report F. Environmental Radiation Monitoring

1. Description of Regional Background Radiation and Sources The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300-400 feet. Most of the land is wooded.

The principal geologic features of the region are nearly flat-laying sedimentary beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams.

Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 ýtR/hr. Results for 2001 indicated that background radiation continued in this range.

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

In 2001 there were a total of forty-four (44) offsite environmental TLD locations.

The locations of the TLDs are shown in Figure 2-6.

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 in a special environmental holder.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

3. Results and Conclusions Data obtained with the contractor TLD during 2001 are summarized in Table 2-2.

The annual exposure rate of all offsite TLDs averaged 0.190 mR/day in 2001.

As in previous years, there was some variation among locations and seasons as would be expected. In 2001, ionizing radiation dose determinations from TLDs averaged 69.4 mR for the year. This is comparable to previous years.

There was no evidence of anomalies that could be attributed to the operation of the Beaver Valiey Power Station. The TLDs confirm that changes from natural radiation levels, if any, are negligible.

In 2001, two TLD results were lost due to vandalism: [Ref: CR 01-7051 and CR 02-00428]

"* Site No. 71 - 1st quarter

"* Site No. 86 - 3rd quarter 2-38

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-6 TLD Locations 2-39

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-6 (Continued)

TLD Locations SOUTHEAST Site Sector Distance Location Site Sector DistanceLocation No. (miles) __ No. (miles) 27 7 6.1 Brunton's Farm" 78 7 2.7 Raccoon Municipal Bldg 45.1 6 1.9 Raccoon Twp., Kennedy's . 79 8 4.4 Rt. 151 and Pross Ln.

Corners 51 5 8.0 Aliquippa (S.S.) 80 9 8.2 Raccoon Park 59 6 1.0 236 Green Hill Rd* 82 9 6.9 Hanover Municipal Building 76 6 3.8 Raccoon Elementary 94 8 2.2 McCleary Road & Pole Cat School

_ Hollow Rd.

77 6 5.6 Raccoon Twp. (Green

_______ ________Garden Road)___________________________

NORTHEAST N. Distance Site Distance No.

Site Sector (miles) Location No. Sector (miles) Location 10 3 1.0 Shippingport Boro 70 1 3.4 North of Western Beaver School - Engle Rd.

28 1 8.6 Sherman's Farm 71 2 6.0 Brighton Twp., First Western Bank 29B 3 8.0 Beaver Valley Geriatric 72 3 3.3 Industry, Logan Park Center 30 4 0.5 Shippingport (S.S.) 73 4 2.5 618 Squirrel Run Rd.

45 5 2.2 Rt. 18 & Anderson St. 74 4 7.0 CCBC, 137 Poplar Ave.

46 3 2.5 Industry Midway Dr. 75 5 4.1 117 Holt Road 46.1 3 2.3 Industry, Rt. 68 & Garage 91 2 3.9 Pine Grove Road & Doyle

_________Road SOUTHWEST Site Sector Location St Sector Distance Location No. (miles) No. (miles) 13 11 1.4 Meyer's Farm 84 11 8.3 Hancock Co. Parks &

I Recreation Complex 14 11 2.5 Hookstown 85 12 5.7 Routes 8 & 30 Intersection 48 10 16.3 Weirton, W.Va. - Weirton 92 12 2.8 Georgetown Road (S.S.)

Water Tower, Collier Way 81 9 3.6 Millcreek United Pres. - 95 10 2.3 832 McCleary Road Church 83 10 4.2 735 Mill Creek Road -i

• 2-40

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report G. Monitoring of Fish

1. Description During 2001, fish collected for the radiological monitoring program included carp, hybrid bass, sauger, and catfish.

2. Sampling Program and Analytical Techniques

a. Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectroscopy. Fish sampling locations are shown in Figure 2-7.

b. Procedure A sample is prepared in a standard tared 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a high resolution germanium detector.

3. Results and Conclusions A summary of the results of the fish monitoring data is provided in Table 2-2.

A total of eight (8) samples were analyzed by gamma spectroscopy. No gamma emitting radionuclides were detected.

Based on the analytical results, the operation of the Beaver Valley Power Station did not contribute any measurable increase in radioactivity in the Ohio River fish population.

2-41

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-7 Environmental Monitoring Program - Fish Sampling Locations Site Sector Distance No. (miles) 2A 13 0.2 BVPS Outfall Discharge 49 3 5.0 Upstream side of Montgomery Dam 2-42

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report H. Monitoring of Surface, Drinking, Ground Waters and Precipitation

1. Description of Water Sources The Ohio River is the main body of water in the area. It is used by the Beaver Valley Power Station for plant make-up for the cooling tower and for receiving plant liquid effluents.

Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site. It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water Authority. The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river. The next downstream user is East Liverpool, Ohio which is approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream use river water for cooling purposes.

Groundwater occurs in large volumes in the gravel terraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm.

In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The average annual precipitation for the area is 36.23 inches based on 1941 to 1970 data collected at the Pittsburgh International Airport.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

2. Sampling and Analytical Techniques

a. Surface (Raw River) Water The sampling program of river water includes three (3) sampling points along the Ohio River. Raw water samples are normally collected at the East Liverpool (Ohio) Water Treatment Plant [River Mile 41.2] daily and composited into a weekly sample. One automatic river water sampler is located at J&L Steel's river water intake [River Mile 36.2]. The automatic sampler takes a 20-40 ml sample every 15 minutes and samples are collected on a weekly basis. A weekly grab sample is taken upstream of the Montgomery Dam [River Mile 29.6]. The weekly grab sample and automatic water sample are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point.

The weekly grab samples upstream of the Montgomery Dam are analyzed for 1-131.

The monthly composites are analyzed for gamma emitters. The quarterly composites are analyzed for H-3.

Locations of each sample point are shown in Figure 2-8.

b. Drinking Water (Public Supplies)

Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Water Treating Plants. An automatic sampler at each location collects 20-40 ml every 20 minutes which is composited into a weekly sample. The weekly sample from each location is analyzed for 1-131.

Monthly composites of the weekly samples are analyzed by gamma spectrometry, Quarterly composites are analyzed for H-3. Locations of each sample point are shown in Figure 2-8.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

c. Groundwater Semi-annual grab samples were collected from three (3) locations (see Figure 2-8) within four (4) miles of the site. These locations are:

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

d. Precipitation Precipitation is collected at Shippingport, Pa., East Liverpool, Oh. and Weirton, W.Va. Precipitation, when available, is collected each week and then composited into quarterly samples. The quarterly composites are analyzed for H-3 and gamma emitters. Locations of each sample point are shown in Figure 2-8.

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

Tritium is determined in water samples by liquid scintillation counting.

Radioiodine (1-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.

2-45

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Figure 2-8 Environmental Monitoring Stations Locations Ground, Surface Water, Drinking Water and Precipitation Sample Site Distance Sample Site Distance D Type No. (miles) Dsi Type No. Sector (miles) Description Surface 2.1 14 1.5 Downstream Midland- Ground 14 11 2.5 Hookstown AJ&L Surface 5 14 4.9 E. Liverpool, Oh. -Water Ground 15 14 3.7 Georgetown Treatment Plant Surface 49 3 5.0 Upstream side of Precipitation 30 4 0.5 Shippingport (S.S.)

Montgomery Dam 4 Drnking 4 15 1.3 Midland -Water ' Precipitation 47 14 4.9 E. Liverpool, Oh.,

Treatment Plant _ _Water Treatment Plant Drinking 5 14 4.9 E. Liverpool, Oh. - Water Precipitation 48 10 16.3 Weirton, W.Va.

Treatment Plant Weirton Water Tower, G round 11 3 0.8 S hippingport Boro - .-l , .j-a y 2-46

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

3. Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, ground and precipitation) are provided by sample type and analysis in Table 2-2. These are discussed below.

a. Surface Water A total of twelve (12) samples were analyzed quarterly for H-3. One of the twelve was positive with a value of 209 pCi/liter. This level is well below the required LLD of 2000 pCi/liter.

A total of thirty-six (36) samples were analyzed by gamma spectrometry.

One of thirty-six indicated naturally occurring Ra-226. Another one of the thirty-six (36) samples indicated naturally occurring Th-228. Both samples were from the Control location.

A total of fifty-one (51) samples were analyzed for 1-131 using a radiochemical method. Positive levels of 1-131 were measured in thirty-two (32) of the weekly samples. The positive results ranged in values from 0.30 to 3.70 pCi/liter. This is similar to previous years. These positive results were detected at a Control location five miles upstream of BVPS and is considered outside the influence of BVPS operation.

b. Drinking Water A total of eight (8) samples were analyzed for H-3. All results were below the LLD.

A total of twenty-four (24) samples were analyzed by gamma spectrometry.

No gamma-emitting radionuclides were detected.

A total of one hundred (100) samples were analyzed for 1-131 using a radiochemical method. Positive levels of 1-131 were measured in fifty-eight (58) of the weekly samples. Thirty-nine (39) of the positive values were below the required LLD. The nineteen (19) at or above the required LLD were below reportable levels. The positive results were detected at both the Midland and East Liverpool plants at similar concentrations. Also, calculations were performed in the year 2000 to predict the 1-131 concentrations at the Midland Water Treatment Plant from liquid effluent releases at the Beaver Valley Power Station during 2000. These calculations show that the predicted concentrations (less than detectable level) at the Midland Water Treatment Plant are well below the values being detected. Releases of 1-131 for the year 2001 were at or below those for the year 2000. This calculation and the fact that 1-131 is also being detected at the upstream surface water Control station at similar concentrations indicates that the positive results detected at the Midland Water Treatment Plant are not a result of plant releases.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

c. Groundwater A total of six (6) samples were each analyzed for H-3 and by gamma spectrometry. No gamma-emitting radionuclides were detected. All six tritium results were less than LLD except 1, which was 214 pCi/I, which is slightly above the LLD of 200 pCi/I.

d. Precipitation A total of twelve (12) samples were analyzed for H-3 and by gamma spectrometry. Four (4) positive tritium results detected were within normal levels. No gamma emitting radionuclides were detected.

e. Deviations from required sampling schedule and analysis CR 01-3189 was written for four (4) weekly drinking water, two weekly surface water and two weekly milk samples, that were collected, shipped and received by the vendor analysis lab for 1-131 analysis.

BVPS was notified by the vendor on 5/30/01 that the samples had not been analyzed. Due to the short half-life of 1-131, it was too late to analyze the samples at that time. This vendor analysis lab has been replaced and this problem has not reoccurred.

f. Summary The data from water analyses demonstrates that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in local river, drinking, well waters or precipitation. The analytical results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.

2-48

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Estimates of Radiation Dose to Man

1. Pathways to Man - Calculational Models The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using codes for the ARERAS/MIDAS computer system equivalent to NRC computer codes XOQDOQ2, GASPAR, and LADTAP. Dose factors listed in the ODCM were used to calculate doses to maximum individuals from radioactive noble gases in discharge plumes. Beaver Valley effluent data, based on sample analysis were used as the radionuclide activity input.

Radionuclides contained in the Annual Radioactive Effluent Release Report (noble gases, particulates, radioiodines and tritium) were included as source terms when they were detected above the LLD values. All LLD values reported by Beaver Valley Power Station are equal to or lower than those required by the ODCM.

All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to code equivalent to XOQDOQ2 which in turn provided input for the GASPAR equivalent. Except when more recent or specific data was available, all inputs were the same as used in the Beaver Valley Power Station Environmental Statements or in Regulatory Guide 1.109.

The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the "cow-milk-child", and other ingestion pathways.

All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using intrinsic germanium detectors. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0). The actual data from these analyses are tabulated and used as the radionuclide activity input term in code equivalent to LADTAP. A hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is available, all other input are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109. Pathways, which were evaluated, are drinking water, fish consumption, and shoreline recreation.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

2. Results of Calculated Radiation Dose to Man - Liquid Releases

a. Individual Dose The doses which are calculated by the model described above are to the likely most exposed real individual located at Midland since this is the nearest location where significant exposure of a member of the general population could potentially occur. A breakdown of doses by total body by age group and highest organ by age group is provided in Table 2-4 for the likely most exposed individual. Included in this table is a breakdown of a typical dose to individuals from natural radiation exposure.

b. Population Dose The 2001 calculated dose to the entire population of almost 4 million people within 50 miles of the plant is presented in Table 2-4.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 2-4 Results of Calculated Individual and Population Radiation Dose to Man - Liquid Releases Organ IndividualmeExposure (a) mrem TOTAL BODY Adult 0.0010 Teen 0.0007 Child 0.0010 Infant 0.0010 ANY ORGAN Adult 0.0011 (Liver)

Teen 0.0009 (Liver)

Child 0.0013 (Liver)

Infant 0.0010 (Liver)

TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE(b)

Ambient Gamma Radiation 58 Radionuclides in Body  : 40 Global Fallout <1 Radon  : 198 TOTAL mRem/year . 296 (a) Likely most exposed member of general population located at Midland drinking water intake.

(b) National Academy of Sciences, 'The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 Population Organ Man-Millirems Largest Isotope Contributor Total Body 71 H-3 69 Man-Millirems GI-LLI 73 H-3 69 Man-Millirems 2-51

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

3. Results of Calculated Radiation Dose to Man - Atmospheric Releases The results of calculated radiation dose to the maximum exposed individuals for BVPS airborne radioactive effluents during 2001 are provided in Table 2-5.

The doses include the contribution of all pathways. A 50-mile population dose was also calculated and is provided.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 2-5 Results of Calculated Radiation Dose to Man - Atmospheric Releases Maximum Exposed Organ Individual mrem TOTAL BODY 0.301 SKIN 0.302 LUNG 0.302 THYROID 0.304 50-Mile Organ Population Dose man-rem TOTAL BODY 0.730 THYROID 0.730 2-53

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

4. Conclusions Based upon the estimated dose to individuals from the natural background radiation exposure in Table 2-5, the incremental increase in total body dose to the 50-mile population (approximately 4 million people), from the operation of Beaver Valley Power Station - Unit 1 and 2, is less than 0.0001% of the annual background dose.

The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report SECTION 3 - LAND USE CENSUS A land use census was conducted July 30 through August 17, 2001 to comply with BV-1 and BV-2 Technical Specification 6.8.6b Item 2 and the ODCM Appendix C CONTROL 3.12.2. The census results are summarized in Table 3-1.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 3-1 Location of Nearest Residence, Garden, and Milch Animal SECTOR RESIDENCE (miles) GARDEN (miles) (1) MILCH ANIMALS (miles) (2)

N 1.58 2.00 None NNE 1.59 1.62 None NE 0.39 2.62 None ENE 0.54 1.01 None E 0.40 1.93 2.62 ESE 0.89 1.71 None SE 1.10 2.44 2.31 SSE 1.12 2.35 3.16 S 1.42 2.29 3.83 SSW 0.81 2.10 1.93 SW 1.55 1.55 2.16 WSW 1.44 2.56 3.38 W 2.25 2.25 None WNW 2.75 None 4.83 NW 0.89 0.92 4.92 NNW 0.91 1.19 2.38 (1) Gardens greater than 500 square feet producing fresh leafy vegetables (2) Within five miles 3-2

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report SECTION 4 - QUALITY CONTROL PROGRAM / INTERLABORATORY COMPARISON PROGRAM A. Quality Control Program The Quality Control (QC) Program for the Beaver Valley Radiological Environmental Monitoring Program involves the analysis of split samples at a QC laboratory and the analysis of high quality (NIST traceable) spiked samples (results are discussed in the Interlaboratory Comparison Program section). This testing provides a means to ensure independent checks are performed on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices. It should be noted that the comparisons for split and duplicate samples were at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure.

The NRC criteria listed in NRC Inspection Procedure 84750, 12/4/90, Inspection Guidance 84750-03 is used as the acceptance criteria for comparisons of results of split and spike samples between the Contractor Lab and the QC Lab/Independent Lab. These comparisons are performed by dividing the comparison standard (the QC Lab or 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. Note that in the case where the counting precision of the standard yields a resolution of less than 4, a valid comparison cannot be made. Values identified with an '*' in Tables 4-1 through 4-10 do not meet acceptance criteria.

Resolution Ratio

<4 -

4-7 0.5-2.0 8-15 0.6-1.66 16-50 0.75-1.33 51 -200 0.8-1.25

> 200 0.85-1.18

1. Split Sample Program (Contractor Laboratory - QC Laboratory)

Routine environmental samples of surface (river) water, drinking water, milk, sediment, food crops, and feed crops were routinely split and analyzed by the Contractor Laboratory and the QC Laboratory.

A summary of results of split water samples is provided in Table 4-1 and Table 4-2.

There were no non-comparisons in all the surface water and drinking water analysis for gamma spec, 1-131, and tritium analysis. Three (3) weekly drinking water 1-131 results showed positive values for the Contractor Lab and less than values for the QC Lab. Comparison of results could not be made. Review of the Interlaboratory Comparison Program results (Table 4-8) indicates that the Contractor Laboratory performed well with 1-131 analysis in water.

Summaries of milk, sediment, and feed/food crop split samples are provided in Table 4-3 and Table 4-4. Good overall agreement was obtained in all samples except for non-comparison for Co-58 and Co-60 in the sediment sample.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report

2. Duplicate Sample Program (Contractor Laboratory - QC Laboratory)

Twenty-eight (28) duplicate (co-located) air particulate and charcoal filters samples were collected at Location #30 and compared (gross beta for particulate filters and radioiodine for charcoal filters) during the year. For the first quarter, the particulate filters were composited and analyzed for gamma activity. Results are presented in Table 4-5 and Table 4-6. There was good agreement of both the air particulate (beta) and charcoal cartridge filters. The first quarter composite of the air particulate filters (gamma) showed good comparisons.

For the first quarter, thirteen (13) duplicate (co-located) TLDs from the QC Laboratory were placed with thirteen (13) "routine" TLDs from the contractor laboratory, and the results were compared. The average of the Contractor Laboratory and the average of the QC Laboratory agree within +/- 4.1% of the mean of all results. This is well within the precision of typical TLD systems. Summary data of the TLD monitoring program is provided in Table 4-7.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report B. Interlaboratory Comparison Program Participation in an Interlaboratory Comparison Program is required by BV-1 and BV-2 Technical Specification 6.8.6b, Item 3. In the first quarter of 2001 this requirement was fulfilled by the Contractor Lab (Teledyne Brown Engineering Environmental Services Westwood N.J.) analyzing high quality (NIST traceable) spiked samples supplied by two Beaver Valley Power Station contracted vendors for the first quarter. For the remainder of the year, this requirement was fulfilled by the Contractor Lab (Environmental, Inc.

Northbrook, IL) and the spiked samples provided by one contracted vendor.

1. Contractor Lab The high quality (NIST traceable) spiked samples include air particulate, charcoal filters water, and milk. The samples were submitted to the Contractor Lab for analysis. The "spiked to" values are used for calculating comparison acceptance criteria. Values identified with an '*' do not meet acceptance criteria explained above.

Comparison of results of the spiked milk and water samples showed good results.

As part of the offsite radiological environmental monitoring program spiked water and milk QC samples are prepared by a vendor and are sent to the vendor lab BVPS uses for sample analysis. The analysis lab does not know the concentration of the radionuclides in the milk and water sample (there are 12 radionuclides in each spike) prior to analysis. For the first quarter, the milk sample results for Sr-89 and Sr-90 did not meet the criteria used at BVPS for acceptable results (they were low by about 35%). For the water, Sr-89 was reported as

< 1.5 pCi/I and the vendor supplying the sample reported 74 pCi/I. Also, for 1-131 in water the analysis lab reported < 0.32 pCi/I while the vendor supplying the spike reported 90 pCi/I. CR 01-3531 was written in response to these non-comparisons.

The vendor provided BVPS with the documentation of this situation (TBE Nonconformance Report Form 01-35). The vendor concluded that this appears to be an isolated event. There review of the analytical logbooks and worksheets for these samples did not uncover any abnormalities. No calculational errors were found. Other analyses for these radionuclides and matrix were reviewed for the same time frame and were determined to be acceptable. They conclude that a recurrence is not anticipated. It should be noted that this vendor is no longer used by BVPS effective 4/1/01.

The vendor (Analytics) supplying the spiked samples were contacted to determine if they have any reason to believe that the "spiked to" values provided to BVPS were in error. Analytics believes that the values are accurate.

As noted in last year's report, the new vendor used by BVPS as of 4/1/01 was to be tracked for Fe-59 analysis of spiked samples. No problems have been observed during the last three quarters of 2001.

Comparison of results of the spiked air particulate filters and charcoal cartridge filters showed good results. Both results are reported in Table 4-10.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report C. Conclusions Based on all available Quality Control data and Interlaboratory Comparison data the Environmental Monitoring Program for 2001 is acceptable with respect to both accuracy and measurement.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-1 Quality Control Data Contractor/Quality Control Laboratory Comparison Split Surface Water Samples Site 2.1 Media Analysis Sampling Contractor QC Lab (1) Units Period Lab (1) _ C Lab (1) Unit Surface January <4 < 2.3 pCi/I Water Co-60 May < 1.8 (Monthly < 4.3 pCi/I Cormrosite) December < 3.5 < 1.5 pCi/I Surface January <4 < 2.1 pCi/I Water Cs-1 34 May < 3.2 (Monthly < 4.5 pCi/I Composite) December < 2.7 < 1.4 pCi/I Surface January <4 < 2.6 pCi/I Water Cs-137 May < 1.9 (Monthly < 3.6 pCi/I Composite) December < 4.3 < 1.2 pCi/I Surface Water (Quarterly Tritium 2 nd Quarter < 146 < 200 pCi/I Composite _ I (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-2 Quality Control Data Contractor/Quality Control Laboratory Comparison Split Drinking Water Samples Site 4 Media Analysis Sampling Contractor QC Lab (1) Units Period Lab (1)

Drinking February <4 < 3.4 pCi/I Water June < 2.2 < 3.3 pCi/I (Monthly Cs-137 October < 2.5 < 0.7 pCi/I Composite) November < 2.7 < 0.8 pCi/I Drinking February <4 < 2.7 pCi/I Water June < 3.9 < 3.5 pCi/I (Monthly Cs-134 October < 2.5 < 0.8 pCi/I Composite) November < 3.8 < 1.0 pCi/I Drinking February <4 < 1.7 pCi/I Water June < 1.9 < 2.8 pCi/I (Monthly Co-60 October < 3.2 < 0.7 pCi/I Composite) November < 2.5 < 0.8 pCi/I Drinking 3/5 to 3/12 1.9 +/- 0.06 < 0.4 pCi/I Water 8/7 to 8/14 0.6 +/- 0.2 < 0.2 pCi/I (Weekly 11/6 to 11/13 1.8 0.2 < 0.68 pCi/I Split) 11/27 to 12/4 < 0.4 < 0.85 pCi/I Drinking Water Tritium 3rd Quarter < 162 < 210 pCi/I (Quarterly Composite I (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-3 Quality Control Data Contractor/Quality Control Laboratory Comparison Split Milk Samples Site 25 Media Sampling Analysis Contractor QC Lab (1) Units Period Lab (1)

Sr-89 < 0.98 < 0.5 pCi/I Sr-90 1.7 +/- 0.2 2.5 +/- 0.5 pCi/I Milk 1-131 < 0.23 < 0.3 pCi/I (Weekly Split) 3/27/01 Co-60 < 5.6 < 7.4 pCi/I Cs-134 < 5.7 < 4.4 pCi/l Cs-137 < 5.8 < 5.7 pCi/I K-40 1310 +/- 82 1394 +/- 178 pCi/I Co-60 < 3.3 < 8.9 pCi/I 1-131 < 0.3 < 1.5 pCi/I Milk 9/18/01 Cs-134 < 2.6 < 10 pCi/I (Weekly Split) Cs-137 < 3.0 < 9.1 pCi/I Sr-89 < 0.9 < 0.9 pCi/I Sr-90 1.6 +/- 0.4 1.34 +/- 0.24 pCi/I 1-131 < 0.2 < 0.27 pCi/I Milk 11/13/01 Co-60 < 2.4 < 8.3 pCi/I (Weekly Split) Cs-1 34 < 2.9 < 9.4 pCi/I Cs-137 < 4.0 < 7.6 pCi/I (1) Uncertainties are based on counting statistics and are at the 95% confidence level.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-4 Quality Control Data Contractor/Quality Control Laboratory Comparison Split Feed, Food, Sediment and Soil Samples Contractor Media Sampling Analysis Lab (1) QC Lab (1) Units Period Co-60 < 0.010 < 0.014 pCi/gm (wet)

Food 8/29/01 1-131 < 0.011 < 0.059 pCi/gm (wet)

Site 10 Cs-1 34 < 0.007 < 0.013 pCi/gm (wet)

Cs-1 37 < 0.008 < 0.012 pCi/gm (wet)

Co-58 0.20 +/- 0.03* 0.11 +/- 0.01 pCi/gm (dry)

Sediment 12/5/01 Co-60 0.93 +/- 0.04* 0.49 _0.01 pCi/gm (dry)

Site 2A Cs-1 34 < 0.05 < 0.02 pCi/gm (dry)

Cs-1 37 0.14 +/- 0.02 0.07 +/- 0.01 pCi/gm (dry)

(1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

• See Section 4A.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-5 Quality Control Data Contractor/Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate and Charcoal Filter Samples Sites 30 and 30A Air Particulates Air Iodine pCi/Cu Meter (Beta) pCi/Cu Meter Collection Contractor QC Lab (1) Collection Contractor Lab QC Lab Date Lab (1) Date 1/15 0.035 +/- 0.005 0.027 0.003 1/8 < 0.07 < 0.007 1/29 0.038 + 0.006 0.026 +/- 0.003 1/22 < 0.06 < 0.005 2/12 0.027 +/- 0.005 0.019 + 0.003 2/5 < 0.06 < 0.005 2/26 0.029 + 0.003 0.026 0.003 2/19 < 0.04 < 0.004 3/12 0.011 + 0.002 0.012 +/- 0.003 3/5 < 0.04 < 0.005 3/26 0.015 +/- 0.003 0.017 0.003 3/19 < 0.03 < 0.006 4/9 0.021 +0.003 0.019 0.003 4/9 < 0.04 < 0.012 5/7 0.024 0.004 0.032 +/-0.004 5/7 < 0.04 < 0.015 6/14 0.016 0.003 0.018 +/-0.002 6/14 < 0.04 < 0.007 7/9 0.017 0.003 0.020 0.002 7/9 < 0.04 < 0.005 8/13 0.030 +/- 0.004 0.032 _ 0.003 8/13 < 0.04 < 0.015 9/17 0.025 +/- 0.003 0.020 + 0.002 9/17 < 0.04 < 0.013 10/18 0.033 +/-0.004 0.030 0.002 10/18 < 0.04 < 0.016 11/12 0.023 0.004 0.021 +/-0.003 11/12 < 0.04 <0.008 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-6 Quality Control Data Contractor/Quality Control Laboratory Comparison Duplicate (Co-located) Air Particulate Samples (Gamma) (pCi/Cu Meter)

Sample Period Nuclide Contractor Lab (1) - QC Lab (1)

Site 30 Site 30A Be-7 0.050 +/- 0.005 0.066 +/- 0.02*

Co-60 < 0.0003 < 0.0007 CompQuate Cs-1 34 < 0.0003 < 0.0006 Composite Cs-1 37 < 0.0003 < 0.0004 Ba-La-1 40 < 0.030 < 0.0025 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

• Resolution < 4, see Section 4A.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-7 Quality Control Data Contractor/Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/day 1ST QUARTER Location No. Contractor QC Lab 10 0.142 0.148 13 0.149 0.151 14 0.142 0.159 15 0.137 0.152 27 0.147 0.148 28 0.126 0.143 29B 0.170 0.167 32 0.160 0.164 45 0.157 0.163 46 0.139 0.144 47 0.147 0.164 48 0.165 0.170 51 0.155 0.158 4-11

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-8 Interlaboratory Comparison Program Independent Laboratory/Contractor Laboratory Comparison Spiked Water Samples (pCi/I)

Sample Type and Independent Contractor Sample Date Identification No. Sample Analyses Lab (1) Lab (1)

Sr-89 74 +/- 4 < LLD

• Sr-90 69 +/- 3 61 +/- 1 1-131 90 +/- 5 < LLD

• Ce-141 94 +/- 5 90 +/- 5 Cr-51 242 +/- 12 227+/- 24 129 +/- 6 111 4 3/22/01 Water Cs-134 E2583-93 Cs-137 102 +/- 5 96 5 Co-58 48 2 49 4 Mn-54 101 5 98 5 Fe-59 84 4 87 6 Zn-65 186 9 193 11 Co-60 147 7 143 5 Water 3/22/01 E2582-93 H-3 3114 +/- 156 2700+/- 100 Sr-89 70 +/- 4 58 2 Sr-90 37 2 38 1 1-131 74 4 72 1 Ce-141 234 12 234 8 Cr-51 322 16 332+/- 47 193 7 177 3 6/14/01 Water Cs-134 E2683-93 Cs-137 174 9 185 6 Co-58 139 7 141 6 Mn-54 216 11 229 6 Fe-59 126 6 127 7 Zn-65 261 +/-13 269 9 Co-60 194 10 198 4 Water 6/14/01 E2682-93 H-3 7494 +/- 375 7203 +/- 243 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

• See Section 4-B.

(Table 4-8 continued on next page) 4-12

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-8 (Continued)

Interlaboratory Comparison Program Independent Laboratory/Contractor Laboratory Comparison Spiked Water Samples (pCi/l)

Sample Type and Independent Contractor Sample Date Identification No. Sample Analyses Lab (1) Lab (1)

Sr-89 85 +/- 4 79 + 5 Sr-90 59 +/- 3 60 -, 2 1-131 60 +/- 3 66 5 Ce-141 88+/-4 90 3 Cr-51 265 +/- 13 277 21 Water Cs-134 116 - 6 107+2 9/20/01 E2797-93 Cs-137 232+ 12 236 +/- 3 Co-58 128+/- 6 133 +/- 3 Mn-54 149 +/- 7 155 2 Fe-59 62+/-3 68 6 Zn-65 184 9 193+/- 7 Co-60 193 10 196 3 Water 9/20/01 E2796-93 H-3 4580 +/-230 4523 +/-114 Sr-89 71 +/- 4 63 7 Sr-90 43 +/- 2 44+ 2 1-131 93+/-5 90 2 Ce-141 224+/- 11 225 +/-2 Cr-51 293 +/- 15 303+/-9 1216/01 Water Cs-134 117 _+6 ill +1 E2985-93 Cs-137 188 +/- 9 194 5 Co-58 53 3 56 1 Mn-54 88 4 93 1 Fe-59 60 +3 67 4 Zn-65 122+6 136 5 Co-60 209+/- 10 211 1 Water 12/6/01 E2984-93 H-3 14060 +/-703 14664 +/-181 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-9 Interlaboratory Comparison Program Independent Laboratory/Contractor Laboratory Comparison Spiked Milk Samples (pCi/I)

Sample Type and Independent Contractor Sample Date Identification No. Sample Analyses Lab (1) Lab (1)

Sr-89 88 +/- 4 56 +/-3*

Sr-90 51 +/- 3 35+/-1*

1-131 77+/-4 64 1 Ce-141 162 8 146 7 Cr-51 418 21 392 31 3/22/01 Milk Cs-134 223 11 188 6 E2584-93 Cs-137 176 9 160 9 Co-58 82 4 77 5 Mn-54 175 9 168 8 Fe-59 146 7 144 9 Zn-65 322 16 323 16 Co-60 254 13 231 7 Sr-89 79 4 67 +/- 2 Sr-90 30 +/-2 28 +/- 1 1-131 69 3 65 +/- 0 Ce-141 163 8 160 +/- 7 Cr-51 224 11 239 +/- 7 Cs-134 134 7 125 +/-1 6/14/01 Milk E2684-93 Cs-137 121 6 128 +/-1 Co-58 96 +/-5 98+/- 4 Mn-54 150 8 158 3 Fe-59 88 4 93 6 Zn-65 182 9 187 1 Co-60 135 7 137 3 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

• See Section 4-B.

(Table 4-9 continued on next page) 4-14

Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-9 (Continued)

Interlaboratory Comparison Program Independent Laboratory/Contractor Laboratory Comparison Spiked Milk Samples (pCi/I)

Sample Type and Independent Contractor Sample Date Identification No. Sample Analyses Lab (1) Lab (1)

Sr-89 75+/-4 62+/-1 Sr-90 50 +/- 3 49-1 1-131 91 +/- 5 80 1 Ce-141 121 +6 121 _3 Cr-51 366 18 378 10 9/20/01 Milk Cs-134 160+/-8 148 3 E2798-93 Cs-137 319+/-16 327+2 Co-58 177+/-9 181 t2 Mn-54 205 10 213+/-2 Fe-59 86 4 91 +/-1 Zn-65 254 +13 270+ 2 Co-60 266+/-13 269 1 Sr-89 85+/-4 73+9 Sr-90 59 + 3 55+4 1-131 61 +3 58+/-0 Ce-141 379 +/- 19 364 7 Cr-51 497 +/-25 511 16 12/6/01 Milk Cs-134 199 +/- 10 184 5 E2986-93 Cs-137 318 +/- 16 325+/-3 Co-58 90 +/- 5 97 1 Mn-54 149 7 156 2 Fe-59 102+/-5 111 -3 Zn-65 206 10 224 9 Co-60 353 18 351 2 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

• See Section 4-B.

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Beaver Valley Power Station 2001 Annual Radiological Environmental Operating Report Table 4-10 Interlaboratory Comparison Program Contractor/Quality Control Laboratory Comparison Spiked Air Particulate/Charcoal Filters Sample Date Sample Type and Sample Analyses Contractor Lab (1) Independent Lab (1) Units Identification No.

3 4/25/01 Particulate Filter Air DQQC Gross Beta 0.78 0.08 0.77 +/- 0.02 pCi/r AP-15 9/20/01 E2799-93 Filter Air Particulate Gross Beta 81 4 81 +/- 0.9 pCi/sample 9/20/01 Air Charcoal Filter 1-131 E2800-93 68 +/- 3 72 +/- 3 pCi/sample 12/21/01 Air Charcoal Filter 1-131 63.2 + 1.8 61.0 +/- 3.0 pCi/sample E3002-93 I (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

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