ML20138C660

1996 Annual Environ Rept,Radiological, for Beaver Valley Power Station,Units 1 & 2

ML20138C660
Person / Time
Site:	Beaver Valley
Issue date:	12/31/1996
From:	DUQUESNE LIGHT CO.
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ML20138C640	List: ML20138C635 ML20138C660 ML20138C679
References
NUDOCS 9704300168
Download: ML20138C660 (137)

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i ATTACHMENT 1 1996 ANNUAL ENVIRONMENTAL REPORT l

RADIOLOGICAL i

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DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNITS 1 AND 2 LICENSES DPR-66 AND NPF-73 f.

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1996 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL t

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1996 Annual Radiological Environmental Report l

EXECUTIVE

SUMMARY

This document is a detailed report of the 1996 Beaver Valley Power Station l

Radiological Environmental Monitoring Program (REMP). Radioactivity levels in the vicinity of Unit i and Unit 2 from January 1 through December 31,1996 in air, water, shoreline sediment, milk, fish, food crops and vegetation, and direct radiation l

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.

J Radiation and radioactivity in the environment is constantly monitored within a 10 mile radius of the site. Two types of samples are taken. The first type, contro!

samples, are collected from areas that are beyond measurable influence of Beaver Valley Power Station.

These samples are used as reference data.

Normal background radiation levels, or radiation present due to causes other than Beaver Valley Power Station, can thus be compared to the environment surrounding the i

nuclear power station. Indicator samples are the second sample type obtained.

These samples show how mucil 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 1996, samples were taken from 60 sites around Beaver Valley Power Station that included the aquatic, atmospheric and terrestrial environments. More than 2300 analyses were performed on these samples.

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 basel!ne".

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 maximum dependable capacity factors for 1996 were as follows: Unit 1 - 80.0%

and Unit 2 - 66.2R in 1996, the radioactive 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 (4 million), from the operation of Beaver Valley Power Station Units 1 and 2, is less than 0.00015% of the annual background. The National Academy of Sciencies 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation j

exposure including radon) is 296 mrem per year.

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The environmental monitoring program outtued in the Beaver Valley Power Station Offsite Dose Calculation Manual for Units 1 and 2 was followed throughout 1996.

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.

ll EXECUTIVE

SUMMARY

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l Duquesne Light Company l

1996 Annuci Radiological Environmental Report l

Table of Contents l

Section 1. INTRODUCTION 1-1 4

l A.

Scope and Objectives of the Program 1-1 l

B.

Description of the Beaver Valley Site 1-1 l

Section 2. RESULTS AND CONCLUSIONS 2-1 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-1 A.

Environmental Quality Control Program 3-1 B.

Evaluation of the Quality Control Program Data' 3-16 C.

Standard Requirements and Limitations for Radiological and Other Effluents 3-18 D.

Reporting Levels 3-18 Section 4. MONITORING EFFLUENTS 4--1 A.

Monitoring of Liquid Effluents.

4-1 1.

Description of Liquid Effluents at the Beaver Valley Power Station.

4-1 2.

Radioactive Liquid Waste Sampling and Analysis Program 4-1 3.

Results of Liquid Effluent Discharge to the Environment 4-1 B.

Monitoring of Atmospheric Effluents 4-10 1.

Description of Atmospheric Effluent Sources 4-10 2.

Atmospheric Effluent Treatment and Sampling 4-13 3.

Results 4 14 Section 5. ENVIRONMENTAL MONITORING PROGRAM 51 A.

Environmental Radioactivity Monitoring Program 51 1.

Program Description 5-1 2.

Summary of Results 5-6 3.

Quality Control Program 5-6 4.

Program Changes 5-6

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8.

Air Monitoring 5-21 1.

Characterization of Air and Meteorology 5-21 2.

Air Sampling Program and Analytical Techniques 5-21 3.

Results and Conclusions 5-23 C.

Monitoring of Sediments and Soils 5-26 1.

Characterization of Stream Sediments and Soils 5-26 2.

Sampling Program and Analytical Techniques 5-26 3.

Results and Conclusions 5-28 D.

Monitoring of Feedcrops and Foodcrops 5-29 1.

Characterization of Vegetation and Foodcrops 5 29 2.

Sampling Program and Analytical Techniques 5-29 L

3.

Results and Conclusions 5-32

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Monitoring of Local Cows Milk 5-33 l

1.

Description - Milch Animal Locations 5-33 2.

Sampling Program and Analytical Techniques 5-33 3.

Results and Conclusions 5-36 Table of Contents ll1

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Duquesne Light Comp::ny 1996 Annual Radiological Environmental Report i

F.

Environmental Radiation Monitoring 5-37 1.

Description of Regional Background Radiation and Sources 5-37 2.

Locations and Analytical Procedures 5-37 3.

Results and Conclusions 5-38 l

G.

Monitoring of Fish 5-43 l

1.

Description 5-43 2.

Sampling Program and Analytical Techniques 5-43 3.

Results and Conclusions 5 43 H.

Monitoring of Surface, Drinking, Well Waters and Precipitation 5-45 1.-

Description of Water Sources 5-45 2.

Sampling and Analytical Techniques 5-46 3.

Results and Conclusions 5-49 Estimates of Radiation Dose to Man 5-52 1.

Pathways to Man - Calculational Models 5-52 2.

Results of Calculated Radiation Dose to Man - Liquid Releases 5-53 3.

Results of Calculated Radiation Dose to Man -

Atmospheric Releases 5-53 4.

Conclusions 5-56 Section 6. INTERLABORATORY COMPARISON PROGRAM 6-1 A.

Contractor Lab - Interlaboratory Comparison Program 6-1 B.

Quality Control Lab - Interlaboratory Comparison Program 6-1 i

iv Taue or contents

Duquesna Light Company 1996 Annual Radiological Environmental Report List of Tables 3-1.

Quality Control Data - Contractor Quality Control Laboratory Comparison Thermoluminescent Dosimeters - mR/ day 3-2 3-2.

Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Surface Water Samples 3-3 3 3.

Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Drinking Water Samples 3-4 3-4.

Quality Control Data - Contractor / Quality Control Laboratc,ry Comparison Split Milk Samples 3-5 3-5.

Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Feed, Food and Sediment Samples 3-6 5-6.

Quality Control Data - Contractor / Quality Control Laboratory Comparison Spiked Air Particulate / Charcoal Filters (pCl/Cu Meter) and Milk Samples (pCi/l) 3-8 3-7.

Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate and Charcoal Filter Samples 3-9 3-8.

Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/Cu Meter) 3-11 3-9.

Quality Control Data - Independent Laboratory / Contractor / Quality Control Laboratory Comparison Spiked Water Samples (pCi/l) 3-12 3-10.

Quality Control Data - Independent Laboratory / Contractor Laboratory Comparison Spiked Milk Samples (pCi/l) 3-14 4-1.

Radioactive Liquid Waste Sampling and Analysis Program 4-7 4-2.

Results of Liquid Effluent Discharges to the Environment 4-9 4-3.

Radioactive Gaseous Waste Sampling and Analysis Program 4-15 5-1.

Radiological Environmental Monitoring Program 5-2 5-2.

Environmentai Monitoring Program Results (1995) 5-7 5-3.

Pre-operational Environmental Radiological Monitoring Program Summary 5-17 5-4.

Typical Detection Sensitivities For Gamma Spectroscopy Detection By High Resolution Germanium 5-20 5-5.

Closest Residence and Garden in Each Sector 5-31 5-6.

Radiation Dose to Highest Individual, mrem /yr - Liquid Releases 5-54 5-7.

Results of Calculated Radiation Dose to Man - Liquid Releases 5-55 5-8.

Results of Calculated Radiation Dose to Man - Atmospheric Releases 5-57 6-1.

Contractor - EPA Interlaboratory Comparison Program 1995 6-2 6-2.

Contractor - EPA Interlaboratory Comparison Program 1996 6-3 6-3.

Contractor - EPA Cross Check Program Trending Graphs 6-5 6-4.

QC Lab - EPA Interlaboratory Comparison Program 1995 6-29 6-5.

QC Lab - EPA Interlaboratory Comparison Program 1996 6-30 Ust of Tables V

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Duquesna Light Company 1996 Annual Radiological Environmental Report List of Figures 1-1.

View of the Beaver Valley Power Station 1-3.

1-2.

Geographical Map and Principal Communities in 40-mile Radius of the Beaver Valley Power Station 1-4 4-1.

Liquid Discharge Points to Ohio River 4-2 4-2.

Unit 1 Water Flow Schematic 4-3 4-3.

Unit 2 Water Flow Schematic 4-4 4-4.

Unit 1 Liquid Waste System 4-5 4-5.

Unit 2 Liquid Waste System 4-6 l

4-6.

Units 1 and 2 Gaseous Radwaste System 4-11 4-7.

Units 1 and 2 Gaseous Release Points 4-12 5-1.

Air Sampling Stations 5-22 5-2.. Average Concentration of Gross Beta in Air Particulates 5-25 5-3.

Environmental Monitoring Locations - Shoreline Sediments and Soil 5-27 5-4.

Environmental Monitoring Program - Feedcrop and Foodcrop Locations 5-30 5-5.

Beaver Valley Power Station Milch Animal Census 5-34 5-6.

Environmental Monitoring Locations - Milk 5-35 5-7.

TLD Locations - Northwest Quadrant 5-39 5-8.

TLD Locations - Northeast Quadrant 5-40 5-9.

TLD Locations - Southeast Quadrant 5-41 5-10.

TLD Locations - Southwest Quadrant 5-42 5-11.

Environmental Monitoring Program - Fish Sampling Locations 5-44 5-12.

Environmental Monitoring Stations Locations - Wells, Surface Water, Drinking Water and Precipitation 5-48 VI ' Ust of Figures

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i Duquesne Light Company 1996 Annual Radiological Environmental Report Section 1. INTRODUCTION 1

A.

Scope and Objectives of the Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station.

Environmental sampling and analyses included air, water, milk, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. The Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1996.

B.

Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in 1

the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of j

land.

Figure 1-1 is a view of the Beaver Valley Power Station.

The site is approximately one mile from Midland, Pennsylvania; 5 miles from East Liverpool, j

Ohio; and 25 miles from Pittsburgh, Pennsylvania.

Figure 1-2 shows the site 1

location in relation to the principal population centers. Population density in, the immediate vicinity of the site is relatively low. The population within a 5 mile radius of the plant is approximately 18,000 and the only area within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,500.

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 1

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 Cumberlanc' 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 1996, the flow ranged from a minimum monthly average of 27300 cubic feet per second (CFS) to a maximum monthly average of 110000 CFS. The mean flow for 1996 was 65450 CFS.

Water temperature of the Ohio River varies from 32'F to 84 F, the minimum temperatures occur in January ar.d/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.

Section 1. INTRODUCTION 1-1

_.. _ =

Duquesne Light Company 1996 Annual Radiological Environmental Report The climate of the area may be classified as humid continental.

Annual precipitation is approximately 36 inches, typical yearly temperatures vary from approximately - 3*F to 95*F with an annual average temperature of 52.3*F. The l

predominant wind direction is typically from the southwest in summer and from the northwest in winter.

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Duquesne Light Company l

1996 Annual Radiological Environmental Report l

Figure 1-1. View of the Beaver Valley Power Station

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section 1. INTRODUCTION 1-3 i

1 Duquesne Light Compcny 1996 Annual Radiological Environmental Report 1

Figure 1-2. Geographical Map and Principal Communities in 40-mile Radius of the Beaver Valley Power Station m

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Cities CE0 GRAPHICAL IfAP AND PRINCIPAL C0tEIUNITIES IN 40-MILE RADIUS OF BIE i

BEAVER VALLEY POWER STATION FIGURE 1-2 4

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' 1-4 Section 1. INTRODUCTION

Duquesnn Light Company 1996 Annual Radiological Environmental Report 4

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

l Beaver Vallev Unit i Beaver Vallev Unit 2 d

4 Maximum Power Level 2652 - megawatts thermal 2652 - megawatts thermal Type of Power PWR PWR No. of Reactor Coolant i-Loops 3

3 No. of Steam Generators j

& Type 3 - Vertical 3 - Vertical

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Steam Used by Main Turbine Saturated Saturated i

The units utilize two separate systems (primary and secondary) for transferring heat i

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 j

isolated from the secondary system. Reactor coolant in the primary system is i

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 l

steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator.

The steam is condensed after passing i

through the turbine, and returned to the steam generators to begin another I

steam / water cycle.

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Section 1. INTRODUCTION 1-5

Duquesne Light Company 1996 Annual Radiological Environmentai Report Section 2. RESULTS AND CONCLUSIONS Plant operations at the Beaver Valley Power Station had no adverse effects on the environment as a result of activity at the station during 1996.

The Beaver Valley Power Station Unit 1 operated throughout 1996 except during a refueling outage March 22 through May 11,1996 and maintenance outages May 31 through June 2 and August 5 through August 22,1996. Unit 2 operated throughout the year except during a refueling outage August 30 through December 16, 1996.

During the year, the radioactive releases were below the limits of 10 CFR Part 50, Appendix 1.

The releases at Beaver Valley Power Station Units 1 and 2 did not i

exceed the limiting conditions identified in the Beaver Valley Power Station

'l Operating License Technical Specifications /Offsite Dose Calcu!ation Manual (ODCM) for Units 1 and 2.

The environmental program for 1996 is outlined in Table 5-1, Radiological

)

Environmental Monitoring Program.

Changes from 1995 are described in Section 5-A-4.

The Beaver Valley Power Station Technical Specifications /ODCM require sampling of three (3) dairies which have the highest calculated milk pathway potential and one largo local dairy. The three dairies are determined from calculations based on the meteorological data and the latest milch animal survey. However, these dairies are frequently small, consisting of as few as one cow or goat. The availability of milk from single cow dalries and revisions due to updated calculations and surveys normally result in sampling of several additional dalries during the year in different sampling periods.

The Environmental Monitoring Program also includes one other large dairy in order to provide continuity in the sampling / analyses program and a control location.

Samples from each of these dairies are obtained in addition to the four dairles required by the Technical Specifications /ODCM. The collection periods asscciated with each of the locations are provided in the detailed sumrnary of the milk monitoring program of this report (Section 5-E).

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, and to the normal statistical fluctuation for activities near the lower limit of detection (LLD).

The results and conclusions for each media of the 1996 Radiological Environmental Monitoring Program are contained in Section 5 of this report. A summary of the 1996 operational environmental data is found in Table 52 and a summary of preoperational data (1974-1975) environmental data is found in Table 5-3.

Evaluation of effluent release data from the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and Station Technical Specifications /ODCM.

section 2. RESuLTs ANo conclusions 2-1

Duquesne Light Company 1996 Annual Radiological Environmental Report Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS A.

Environmental Quality Control Program The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of six (6) elements. It should be noted that the comparisons made were at very low levels of radioactivity and consequently, the activities at these levels are difficult to measure. See Section 3-8 for discussion of comparison criteria for radiochemical determinations. Values in Table 3 2 through Table 3-10 identified with an asterisk (*) do not meet comparison criteria.

However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.

1. TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and QC Laboratory)

Thirteen (13) TLDs from the Contractor Laboratory and QC Laboratory are co-located and replaced quarterly, and the results are compared. The average of the Contractor Laboratory and the average of the QC Laboratory agree within i 5.0% of the mean of all results. This is well within the precision of typical

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j TLD Systems. Summary data of the TLD Monitoring Program is provided in Table 3-1.

2. Split Sample Program (DLC Contractor Laboratory - DLC QC Laboratory)

Samples of surface (river) water and drinking water were routinely split and analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory. In addition, samples of other media, such as milk, sediment, foodcrop and feederop were also split with the DLC QC Laboratory.

A summary of results of split water samples is provided in Table 3-2 and Table 3-3.

There were no non-comparisons in all of the surface water and drinking water analysis.

Summaries of milk, sediment and feed / food crop split samples are provided in Table 3-4 and Table 3-5. Good overall agreement was obtained with only one non--comparison observed of potassium-40 in feed. Some variation may be expected due to variations in duplicate samples, variations in analytical procedures and in calibration, source type, etc.

(Text continued on page 3-7)

Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-1

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1996 Annual Radiological Environmental Report l

Table 3-1. Quality Control Data Contractor Quality Control Laboratory Comparison i

Thermoluminescent Dosimeters mR/ day TABLE 3-1 a

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QUALITY CONTROL DATA CONTRACTOR QUALITY CONTROL LABORATORY j

COMPARISON THERMOLUMINESCENT DOSIMETERS - mR/ day 1ST QUARTER 2ND QUARTER

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DLC - QC DLC -

DLC. QC i

Location No.

Contractor Lab Location No.

Contractor Lab (CaSO4:Dy)

(CaSO4:Dy)

(CaSO4:Dy)

(CaSO4:Dy) j 10 0.187 0.141 10 0.170 0.169 13 0.176 0.135 13 0.163 0.170 14 0.186 0.134 14 0.169 0.164 4

15 0.176 0.157 15 0.162 0.169 27 0.178 0.136 27 0.170 0.181 i

28 0.180 0.135 28 0.175 0.184 29B 0.213 0.184 298 0202 0.222 32 0.203 0.171 32 0.185 0.181 45 0.199 0.158 45 0.185 0.190 46 0.177 0.143 46 0.175 0.168

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47 0.209 0.171

- 47 0.200 0.207 48 0.200 0.164 48 0.190 0.192

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51 0.192 0.167 51 0.187 0300 l

3RD QUARTER 4TH QUARTER l Contractor DLC -

DLC - QC DLC -

DLC - QC j

Location No.

Lab Location No.

Contractor Lab 4

(CaSO4:Dy)

(CaSO4:Dy)

(CaSO4:Dy)

(CaSO4:Dy) 10 0.186 0.151 10 0.182 0.169 4

13 0.177 0.149 13 0.172 0.169 14 0.181 0.149 14 0.177 0.166 15 0.179 0.166 15 0.173 0.181 27 0.184 0.147 27 0.173 0.182 28 0.191 0.160 28 0.184 0.188 298 0.221 0.193 293 0.219 0.221 32 0.198 0.476 32 0.197 0.174 45 0.193 0.173 45 0.184 0.189 48 0.170 0.156 48 0.172 0.178 47 0.202 0.173 47 0.204 0.210 48 0.196 0.1 64 48 0.193 0.191 51 0.192 0.167 51 0.183 0.185 3-2 secuan 3. ENvlRONMENTAL MONITORING CONSIDERATIONS

Duquesne Light Company 1996 Annual Radiological Environmantal Report Table 3 2. Quality Control Data - Contractor /Oua!.ty Control Laboratory Comparison Split Surface Water Samples TABLE 3 2 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT SURFACE WATER SAMPLES Media Analysis S8mPling DLC Contractor DLC - QC Units Period Lab (1)

Lab (1)

January

<3

< 1.8 pCi/l Surface Water Co-60 July

<5

< 2.7 pCl/l October

<3

< 3.6 pCi/l January

<3

< 1.9 pCi/l April

<3

< 7.5 pCe/l Surface Water Cs-134 f

July

<5

< 4.6 pCi/l October

<4

< 4.2 pCi/l January

<3

< 2.4 pCi/l Surface Water Cs-137 July

<5

< 4.9 pC11 October

<4

< 3.4 r41/1 Surface Water 1st Quarter

< 100

< 152 pCi/l (Quarterly Tritium j

Composite) 3rd Quarter

< 200

< 157 pCill Surface Water 1st Quarter

< 1.1

< 0.8 pCill (Quarterly Sr-89 Composite) 3rd Quarter

< 1.3

< 0.7 pCi/l Surface Water 1st Quarter

< 0.26 0.5 i 0.3 pCill (Quarterly Sr-90 Composite) 3rd Quarter

< 0.31

< 0.5 pCi/l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

Section 3. ENVIRONMENTAL MONITORING Cf,NSIDERATIONS 3-3

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Duriuesne Light Company 1996 Annual Radiological Environmental Report Table 3-3. Quality Control Data Contractor /Ouality Control Laboratory Comparison Split Drinking Water Samples TABLE 3-3 QUALITY CONTROL DATA CONTRACTORlQUALITY CONTROL LABORATORY COMPARISON SPLIT DRINKING WATER SAMPLES Sampi ng DLC Contrector DLC QC Media Analysis Um Period Lab (1)

Lab (1)

February

< 4.0

< 3.0 pCi/l Drinking Water May

< 4.0

< 2.9 pCi/l Composite)

August

< 4.0

< 4.2 pCi/l

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(Monthly Cs-137 November

< 3.0

< 2.2 pCi/l February

< 4.0

< 4.1 pCi/l Drinking Water May

< 3.0

< 2.4 pCill

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(Monthly Cs-134 Composite)

August

< 3.0

< 4.0 pCin November

< 2.0

< 4.6 pCiM February

< 4.0

< 5.0 pCill Drinking Water May

< 3.0

< 2.2 pCin (Monthly Co-60 Composite)

August

< 4.0

< 2.1 pCi/l November

< 2.0

< 2.2 pCi/l March 0.53 0.25

< 0.5 pCiM j

Drinking Water 1-131 (Weekly Split)

August 0.40 i 0.16

< 0.3 pCiM November

< 0.24

< 0.5 pCi/l Drinking Water 2nd Quarter

< 200

< 150 pCi/l (Quarterly Tritium

,i Composite) 4th Quarter

< 200

< 162 pCi/l 1st Quarter

< 1.5

< 0.9 pCid Dnn g Wa er 2nd Quarter

< 1.5

< 1.2 pCi/l Composite) 3rd Quarter

< 1.6

< 0.6 pCl/l 4th Quarter

< 1.7

< 0.9 pCi/l 1st Quarter

< 0.43 0.4 i 0.3 pCi/l Dr n ng Water 2nd Quarter

< 0.43

< 0.5 pCid Composite) 3rd Quarter

< 0.29

< 0.6 pCin 4th Quarter

< 0.27

< 0.8 pCi/l (1) Uncertainties are based on counting stantics and are specified et the 95% confidence coefficient.

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b 3-4 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS

Duquesne Light Company 1996 Annual Radiological Environmental Report Table 3-4. Quality Cuntrol Data - Contractor / Quality Controi Laboratory Companson Split Milk Samples TABLE 3-4 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT MILK SAMPLES U

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Period Analysis Units Lab (1)

Lab (1)

Sr-89

< 0.67

< 1.2 pCi/l Sr-90 1.8 i 0.2 2.2 0.6 pCin 1-131

< 0.12

< 0.4 pCi/l Milk (25) 3 12-96 Co-60

<4

< 4.2 pCiM Cs-134

<4

< 3.5 pCi/l Cs-137

<4

< 3.2 pCin K-40 1310 i 130 1410 i 70 pCi/l Co-60

<4

< 6.4 pCIM l-131

< 0.22

< 0.3 pCin Milk (25) 6-17 96 Cs-134

<4

< 3.0 pCin Cs-137

<4

< 2.8 pCli.

K-40 1270 i 130 1320 6 120 pCi/l Sr-39

< 0.82

< 0.9 pCi/l Sr-90 2.7 i 0.2 3.1 i 0.6 pCi/l I131

< 0.16

< 0.5 pCin Milk (25) 9-10-96 Co 60

<4

< 4.2 pCi/l Cs 134

<4

< 6.6 pCih Cs-137

<4

< 8.3 pCih K-40 1370 140 1370 i 140 pCi/l Co-60

<4

< 3.4 pCiM l.131

< 0.28

< 0.6 pCi/l Milk (25) 12-16-96 Cs-134

<4

< 4.8 pCl/l Cs-137

<4

< 3.9 pCi/l K-40 1240 120 1420 i 100 pCl/l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

Sect.on 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-5 A

Duquesne Light Company 1996 Annual Radiological Environmental Report Table 3-5. Quality Control Data - Contractor / Quality Control Laboratory Comparison Split Feod, Food and Sediment Samples TABLE 3-5 QUALITY CONTROL DATA CONTRACTORIQUALITY CONTROL LABORATORY COMPARISON SPLIT FEED, FOOD AND SEDIMENT SAMPLES

"" I"8 D

Media Analysis Contr or Units p

d lab (1)

~

Be-7

< 0.2

< 0.13 pCi/gm (dry)

K-40 16.1 i 1.6*

5.48 i 0.4 pCi/gm (dry)

Co-60

< 0.03

< 0.019 pCi/gm (dry)

Feed (25) 6-17-96

< 0.04

< 0.014 pCi/gm (dry) 1131 Cs-134

< 0.03

< 0.010 pCi/gm (dry)

Cs-137

< 0.03

< 0.015 pCilgm (dry)

K-40 1.510.15 2.7 i 0.4 pCi/gm (wet)

Co-60

< 0.007

< 0.013 pCilgm (wet)

< 0.0079

< 0.024 pCl/gm (wet) '

Food (10) 9-27-96 1]1 Cs-134

< 0.007

< 0.017 pCilgm (wet)

Cs-137

< 0.007

< 0.014 pCl/gm (wet) l Co-58 0.840 i 0.084 0.75 i 0.08 pCi/gm (dry)

Co 60 0.2S7 i 0.052 0.2810.04 pCi/gm (dry)

Cs-134

< 0.06

< 0.047 pCi/gm (dry)

Sedirnont (2A) 11-6-96 Cs-137 0.154 i 0.038 0.173 i 0.07 pCi/gm (dry)

Ra-226 1.380 i 0.640 2.58 i 0.54 pCi/gm (dry)

K-40 11.000 i 1.100 12 31 i 0.73 pCi/gm (dry)

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

See Section 3.A.2 and 3.B.

3-6 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS

Duqcesne Light Company 1996 Annual Radiological Environmental Report 3.

DLC QC Laboratory Program Spiked air particulate and charcoal filters and milk samples prepared by DLC QC Laboratory were submitted to the Contractor Laboratory for analysis. The

" spiked to" values are used for calculating comparison acceptance criteria.

Table 3-6 provides the data for this portion of the QC Program. See Section 3-B for evaluation of the data.

4.

Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory)

Duplicate air particulate and charcoal filters (radiciodine) samples were collected at Location #30 and compared during the year on a weekly basis.

Comparison of particulate and charcoal samples alternated from week to week.

Duplicate quarterly air particulate filters, composited from the weekly air particulate filters, were analyzed for gamma activity for each quarter of the year. Table 3-7 and Table 3-8 provides data for this portion of the QC program.

See Section 3-B for evaluation of the data.

5.

Contractor and QC Laboratory - Internal QC Program The Contractor and QC Laboratory maintained their own QC program which included participation in the Environmental Protection Agency - Environmental Monitoring Safety Laboratory (EPA - EMSL) Interlaboratory Cross Check Program. This cross check program indicated that the Contractor and QC Laboratory results were in agreement with EPA EMSL. The Contractor data for 1995 and 1996 is presented with trending graphs from 1981. See Sections 6A and 6B.

6.

Special QC Program (DLC Contractor Laboratory - Independent Laboratory)

Low level spiked water and milk samples are prepared by a vendor noted for supplying quality primary standards with NIST traceability. The " spiked to" values are used for calculating comparison acceptance criteria. The prepared spiked samples are then sent to the DLC Contractor Laboratory. A summary of results of this portion of the QC program is provided in Table 3-9 and Table 3-10. See Section 3-B for evaluation of this data.

In addition to the DLC QC program, the Pennsylvania Department of Environmental Protection (PDEP) also conducted a surveillance program in the vicinity of the site. Samples of air, river water, drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program. Good comparison of the states quarterly results and DLC results was demonstrated in 1996.

(Text continued on page 3-16)

Section 3. ENVIRONMENTAL MONITORING CoNSIDERATloNs 3-7

~

Duquesne Light Company 1990 Annual Radiological Environmental Report Table 3-6. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Spiked Air Particulate /Charcoat Filters (pCi/Cu Meter) and Milk Samples (pCi/l) e TABLE 3-6 QUALITY CONTROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPIKED AIR PARTICULATE / CHARCOAL FILTERS (pCl/Cu MEER) AND MILK SAMPLES (pClll)

~

Sample Sample Type and Sample DLC - QC r

Date Identification No.

Analyses Lab (1) s

)

Air Particulate 2-7-96 Filter Gross Bcta 7.5010.31 7.99 i 0.80 pCi/m3 DQQC AP-1 i

Air Particulate 10-22 96 Filter Gross Beta 3.75 i 0.31 5.98 i 0.60 pCi/m3 DQQC AP-2 Air Charcoal 2-7-96 Filter I-131 0.359 i 0.036 0.261 i 0.026 pCi/m3 DQQC CH-1 Air Charcoal 10 22-96 Filter 1-131 0.850 i 0.085 0.530 i 0.053 pCl/m3

~

DQQC CH-2 1-131 35.0 i 1.0 40.4 i 6.0 pCl/l 6-26-96 s-134 32.4 i 4.3 31.3 t E0 pCi/l DQQC l-64 Cs-137 49.7 i 5.0 42.5 t 5.0 pCl/l (1) Uncertainties are based on counting statistics and are specified at the 95%

confidence coefficient.

o

.e I

0 3-8 section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS

TABLE 3-7 QUALITY CONTROL DATA

-4 CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES Air Particulates Air lodine 4

pC1/Cu Meter (Beta) pCl/Cu Meter mO DLC.

DLC -

5E Sample Date Contractor

~

Sample Date Contractor DLC - QC

{g Lab (1)

Lab (1)

Lab g

gg 8

1/2 - 1/8 0.020 i 0.004 0.022 i 0.003 1/8 - 1/15

< 0.01

< 0.010 o

gg 8

1/15 - 1/22 0.015 i 0.003 0.017 i 0.003 1/22 - 1/29

< 0.02

< 0.007 g

g$

1/29 - 2/5 0.021 1 0.003 0.025 i 0.003 2/5 - 2/12

< 0.01

< 0.007 8=

n> a 2/12 - 2/20 0.012 i 0.003 0.014 i 0.002 2/20 - 2/26

< 0.01

< 0.012 S.-

yc 2/26 - 3/4 0.019 i 0.003 0.016 i 0.003 3/4 - 3/11

< 0.01

< 0011 o

fp

$.,_g 3/11 - 3/18 0.016 i 0.003 0.021 1 0.003 3/18 - 3/25

< 0.01

< 0.009

{n f 3/25 - 4/1 0.010 i 0.003 0.014 i 0.003 4/1 - 4/8

< 0.01

< 0.007 jk

$- r-4/8 - 4/15 0.013 i 0.003 0.014 i 0.003 4/15 - 4/22

< 0.01

< 0.012 kh g

4/22 - 4/29 0.010 1 0.003 0.014 i 0.003 4/29 - 5/6

< 0 01

< 0.004

=

{Q g

5/6 - 5/13 0.008 i 0.003 0.009 i 0.002 5/13 - 5/20

< 0.01

< 0.011 g

y}

j 5/20 - 5/28 0.013 1 0.003 0.014 1 0.002 5/28 - 6/3

< 0.01

< 0.011 3$

O O T g

6/3 - 6/10 0.009 0.003 0.011 1 0.003 6/10 - 6/17

< 0.01

< 0.011 g

o E

6/17 - 6/24 0.015 i 0.003 0.015 i 0.003 6/24 - 7/1

< 0.01

< 0.012 (1) Uncertainties are based on counting statistics and are specified at the 95% confidenco coefficient.

s r

O o

o Q

3 4

o 8

8 iF 5

8

1. E 6

5 2

Y

=

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TABLE 3-7 (continued)

By QUALITY CONTROL DATA

.w CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE AND CHARCOAL FILTER SAMPLES m

p, Air Particulates Air lodine Q

pCl/Cu Meter (Beta) pCi/Cu Meter b

DLC -

DLC-3 Sample Date Contractar Sample Date Centractor E

• III Lab (1)

Lab (1) m C

u)

O 7/1 - 7/8 0.016 i 0.003 0.022 i 0.003 7/8 - 7/15

< 0.01

< 0.007 8

8 7/15 - 7/22 0.015 i 0.003 0.014 i 0.002 7/22 - 7/29

< 0.009

< 0.008 g

o E

7/29 - 8/5 0.016 i 0.003 0.017 1 0.003 S/5 - 8/12

< 0.01

< 0.007 E

8/12 - 8/19 0.016 1 0.003 0.021 1 0.003 8/19 - 8/26

< 0.01

< 0.006 E

$.g g

8/26 - 9/3 0.033 1 0.003 0.030 i 0.003 9/3 - 9/9

< 0.01

< 0.011 y

h 9/9 - 9/16 0.018 i 0.003 0.021 0.003 9/16 - 9/23

< 0.01

< 0.007 d

9/23 - 9/30 0.022 i 0.003 0.024 1 0.003 9/30 - 10/7

< 0.01

< 0.020

$g o

5 10/7 - 10/14 0.013 i 0.003 0.017 1 0.003 10/14 - 10/21

< 0.01

< 0.012 10/21 - 10/28 0.017 i 0 003 0.019 0.003 10/28 - 11/4

< 0.01

< 0.015

{Q 11/4 - 11/11 0.015 i 0.003 0.015 i 0.003 11/11 - 11/18

< 0.02

< 0.005 yj 11/18 - 11/25 0.021 1 0.003 0.021 1 0.003 11/25 - 12/2

< 0009

< 0.016 3$

(D x 12/2 - 12/9 0.017 i 0.003 0.021 1 0.003 12/9 - 12/16

< 0.01

< 0.014 y

12/16 - 12/23 0.022 0.004 0.019 i 0.003 12/23 - 12/30

< 0.01

< 0.018 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence coefficient.

1 l

~

Duquesne Light Compariy 1996 Annual Radiological Environmental Report Table 3-8. Quality Control Data - Contractor /Ouality Control Laboratory Comparison Split Air Particulate Samples (gamma) (pCi/Cu Meter)

TABLE 3-0 QUALITY COtO ROL DATA CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPLIT AIR PARTICULATE SAMPLES (GAMMA)(pCl/Cu Meter)

Sample Period Nuclide

~

Lab (1)

Lab (1)

Be-7 0.140 i 0.014' O.084 0.010 Co-60

< 0.0002

< 0.0008 1st Quarter Cs-134

< 0.0002

< 0.0008 Composite Cs-137

< 0.0002

< 0.0009 Ba-La-140

< 0.007

< 0.0017 K-40 0.004 i 0.002

< 0.0231 Be-7 0.144 I 0.014 0.110 i 0.016 Co-60

< 0.0003

< 0.0003 2nd Quarter Cs-134

< 0.0003

< 0.0003 Composite Cs-137

< 0.0003

< 0.0004 Ba-La-140

< 0.01

< 0.0008 K-40 0.004 i 0.002

< 0.0195 Be-7 0.144 i 0.014 0.089 i 0.011 Co-60

< 0.0002

< 0.0004 3rd Quarter Cs-134

< 0.0002

< 0.0008 Composite Cs-137

< 0.0002

< 0.0003 Ba-La-140

< 0.007

< 0.0011 K-40

< 0.005

< 0.018 Be-7 0.112 i 0.011*

0.055 I 0.009 Co-60

< 0.0003

< 0.0003 4th Quarter Cs-134

< 0.0002

< 0.0005 Composite Cs-137

< 0.0003

< 0.0003 Ba-La-140

< 0.008

< 0.0006 K-40 0.005 i 0.002

< 0.0177 (1)

Uncertainties are based on counting statistics and are specified at the 95%

confidence coefficient.

See Section 3.8 secnon 3. ENVIRONMENTAL MONITORING CONSIDERATIONS M11

Duquesne Light Company 1996 Annual Radiological Environmental Report Tr.ble 3-9. Quality Centrol Data - Independent Laboratory / Contractor /Ouality Control Lrboratory Comparison Spiked 'Nater Samples (pCi/l)

TABLE 3 0 QUALITY CONTROL DATA INDEPENDENT LABORATORY / CONTRACTOR / QUALITY CONTROL LABORATORY COMPARISON SPlKED WATER SAMPLES (pCIA)

I Sample Sample Type and Samp!a Independent Contractor Date

!.ientification No.

Analysen Lab (1)

Lab (1)

Sr-89 24.0 t 1.0 27 2 Sr-90 21.0 i 1.0 21 i 1 1-131 36.0 2.0 36 1

Ce-141 88.0 i 4.0 88 i 9 Cr-51 322.0 t 16.0 343 i 35 Water Cs-134 58.0 3.0 57 t 6 3-12-96 53-351 Cs-137 64.0 3.0 67 7 Co-58 48.012.0 48 i 5 Mn-54 31.0 2.0 38 i 4 Fe-59 83.0 4.0 91 9

Zn-65 97.0 i 5.0 103 10 Co-60 76.0 4.0 83 8 3-12-96 H-3 2982 14S 2800 200 3 52 Sr-89 10 i 1

<9 Sr-90 20 i 1 18 t 1 1-131 20 1 18 1

Ce-141 379 i 19 370 i 37 Cr 51 995 i 50 960 i 96 Water Cs-134 294 15 277 28 6 19-96 53-353 Cs-137 724 i 36 790 i 79 I

Co-58 164 8 182 i 18 Mn-54 530 27 582 i 58 Fe-59 137 i 7

56 i 16 Zn45 102 i 5 104 i 10 14' i 7 156 i 16 Co-60 i

6-19-96 H-3 1252 i 63 1200 200 53 l

(Table 3-9 continued on next page) 1 I

3-12 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS L__. _.

Duquesne Light Company 1996 Annual Radiological Environmental Reoort TABLE 3 9 (continueh QUALITY CONTROL DATA INDEPENDENT LABORATORY / CONTRACTOR / QUALITY CONTROL LABORATORY CCMPARISON SPIKED WATER SAMPLES (pC1/I)

I Sample Sample Type and Sample Independent Contractor Date Identification No.

Analyses l

Lab (1)

Lab (1)

Sr-89 40 2 32 i 2

$r-90 35 2 31 1

1-131 50 i 3 50 i 1 Ce-141 423 21 410 41 Cr-51 646 32 664 66 Water Cs-134 295 i 15 281 28 9-26-96 53-355 Cs-137 225 i 11 243 1 24 Co-58 174 9 177 i 18 M >54 239 i 12 257 26 Fe-59 50 i 5 54 i 8 Zn-65 93 i 5 99 10 Co-60 151 t 8 169 17 9-26-96 H-3 2259 113 1900 i 200 3

St-89 0

< 1.2 i

Sr-90 0

< 0.31 1-131 39 i 2 34 i 1 Ce-141 272 14 269 i 27 Cr 51 209 i 10 198 45 Water Cs-134 172 i 9 158 i '16 12-12 96 53-357 Cs-137 101 1 10 202 20 Co-58 119 6 122 i 12 Mn 54 202 i 10 226 6 23 Fe-59 48 2 62 i 10 Zn-66 31 5

101 i 12 Co-GO 108 5 110 11 12 12-96 HJ 2G86 i 134 2600 i 200 5 58 (1) Uncertainties are based on counting statistics and a7e specified at the 95% confidence coefficient.

Section.3. ENVIRONMENTAL UONITORING CONSIDERATIONS 3-13

i.

Duquesne Light Company 1996 Annual Radiologice' Environmental Repe,rt Table 3-10. Quality Control Data - independent Laboratory / Contractor Laboratory Cor'iparison Spiked Milk Samples (pCi/l)

TABLE 310 QUAUTY CONTROL DATA INDEPENDENT LABORATORY / CONTRACTOR LABORATORY COMPAR SON SplKED MILK SAMPLES (pCul)

.4 i

Sample Sampic Type and Sarnple independent Contractor

~,g Date Identification No.

Analyses Lab (1)

Lab (1) i

,.~-

Sr-89 31 i 2 34 2 St-00 16 i1 l

17 i 1 1 ' 31 13 i 1 13 i1 Ce-141 234 i 12 235 i 24 Cr-51 856 i 43 885 i 89 l

Cs-134 1

154 i e 146 14 l

Mdk L

3-12-06 S2-278 CS 137 170 i 9 182 i 19 Co-58 128 i 6 133 i 14 M n-54 84 i 4 88i9 Fe-59 223 i 11 246 i 25 Zn-65 260 i 13 281 i 28 Co-60 204 i 10 214 i 21 Sr-89 15 i 1 14 i 1 Sr-90 10 i 1 11 i 1 1-131 15 i 1 17 i i Ce-141 215 i 11 208 i 21 Cr-51 563 1 28 584 i 58 Mdk Cs-134 166 i 8 159 i *ld 6-19-96 52 279 Cs-137 410 i 21 449 i 45 Co-58 93 i 5 101 i 10 p-M n-54 300 i 15 331 i 33 Fe-59 77 i 4 89 i 11

.' 9 I'

[

Zn-65 54 i 3 66 i 8 Co-G0

&4 i 4 87 0 Sr49 50 i 3 43 i 2 Sr-90 22 i 1 19 i1 la31 24 i 1 27 i 1 l

Co-141 318 i 16 323 i 32 Cr-51 456 i 24 512 i 57 l^

g Mdk Cs-134 222 i 11 202 i 20 9-26-96 52-280 Cs 137 169 i 8 180 i 18 131 i 7 135 13 00-58 Y

Mn-54 180 i 9 194 i 19 Fe-59 37 i 2 41 i A zn-c5 70 i 4 84 i :2 Co-60 114 i 6 120 i 12

~

i (Table 3-10 continued On next page)

< b 1

3-14 Section 3 ENVIRONMEi4TAL MONITORING CONSIDERATIONS

• 'a

Duquesne Light Company 1996 Annual Radiological Environmental Report TABLE 3-10 (continued)

QuAUTY CONTROL DATA INDEPENDENT LABORATORY /CONTRt.CTOR LABORATORY COMPARISON SplKED MlWC SAMPMS (pCl/t)

Sample Suiple Type aid SanWe irm pendert Contrac'or Date identification No.

Analyses Lab (1)

Lab (1)

St 39 (2)

< 0.63 Sr-90 (2) 1.5 i 0.2 1 131 59 i 4

$9 i 1 j

Co 141 277 i 17 282 i 28 Cr 51 214 i 13 198 48 Mdk Cs-134 175 i 10 167 i 17 12-12-96 (52-281)

Cs-137 194 i 12 207 i 21 Co-58 121 i 7 124 i 12 un-54 208 i 12 228 i 23 Fe-59 49 i 3 51 i 11 Zn-65 93 i 6 99 i 13 Co40 110 i 7 116 i 12 (1) Uncertainties are based on counting statistics and are spectMed at the 95% contdence coefficient.

(2) No Sr-89 or Sr 00 was acced to this spiked samplu.

i 1

e.

Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-15

,,x

. s

Duquesne Light Company 1995 Annual Radiological Environmental Report B.

Fvaluation of the Quality Control Prograrn Data The split and spiked sample program indicates that the Contractor and QC Laboratory are generally performing satisfactorily in accordance with " Criteria for Comparing Analytical Measurements from NRC Compliance Office." Comparisons -

between the QC Laboratory and Contractor Laboratory are generally acceptable and demonstrate a satisfactory performance by the DLC contractor. All media were in agreernent in accordance with NRC criteria as listed in inspection Guidance 84750-03 dated 12/04/90 with the exception of those media in Table 3-2 through Table 3-10 identified with an asterisk (*).

~ Comparisons are obtained by dividing the comparison standard by its associated uncertainty to obtain the resolution. The standard value is multiplied by the ratio values obtained from the following table to find the acceptance band for the result to 2

be compared. Note that in the case where the counting precision of the standard yields a resolution of less than 4, a comparison cannot be calculated.

Resolution Ratio

<4 4-7 0.5-2.0 8 - 15 0.6 - 1.66 15 - 50 0.75 - 1.33 51 - 200

.8 - 1.25

> 200

.85 - 1.18 3-10 secuon 1 ENVIRONMENTAL MONITORING CONSIDERATIONS

~ _ _ _ _ _ _

Duquesne Light Company 1996 Annual Radiological Environmental Report j

B.

Evaluation of the Quality Control Program Data i

i

• Contractor Laboratory l

The Contractor Laboratory had a very satisfactory performance throughout the 1996 QC Laboratory Program. In the independent Laboratory Program, with reference to the high quality spikes as reported in Table 3-9 and Table 3-10, excellent comparisons were achieved for all milk and water spikes.

In the QC Laboratory spike sample program, as reported in Table 3-6 for air particulate and charcoal filters and milk. Good comparisons were achieved for i

all spike samples submitted by the QC Lab.

Within the Contractor /QC Lab split sample program samples for feed and 4

sediment are particularly subject to sample variability. One non-comparison was noted for potassium-40 in feed.

o The Contractor Laboratory had satisfactory performance within the EPA Interlaboratory Cross Check Program (See Section 6).

4 i

j in the Contractor /QC similar sample program, there was good agreement of both the air particulate and charcoal cartridge filters.

There was one (1)

)

non-comparison of the air particulate filter gamma count for Be-7 in the first quarter.

• Quality Control Laboratory e

The QC Laboratory had satisfactory performance within the EPA Interlaborr/ory Cross Check Program (See Section 6).

Based on all available QC program data, the data from the Contractor and QC Laboratory's internal EPA Interlaboratory Cross Check Program, and comparisons l

with the PDEP, the Environmental Monitoring Program for 1996 is acceptable with respect to both accuracy and measurement.

1 5

6 Section 3. ENVIRONMENTAL MONITORING CONSIDERATIONS 3-17

~_

Duquesne Light Campany 1996 Annual Radiolog!;al Environmental Report l

C.

Standard Requiremenf.s and Limitations for Radiological and other Effluents The Beaver Valley Fower Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases are controlled to ensure that limits set by Federal or State governments are not exceeded. In addition, se;f-imposed goals have been established to further limit discharges to the environment.

Beaver Valley Power Station is subject to regulations which include the Code of Federal Regulations 10 CFR (Energy), Gaseous Discharge Permits for auxiliary boilers and diesel generators, PA Code - Title 24, Part I, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No.1-70 and 2-70, Environmental Protection Agency (EPA), National Pollution Discharge Elimination (NPDES) Permit

1. 0025615, and the Beaver Valley Power Station Technical Specifications /ODCM.

D.

Reporting Levels A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an er'vironmental sampling medium exceeds the limits specified in the Beaver Valley Power Station Technical Specifications /ODCM when averaged over any calendar quarter. Also,'when more than one of the radionuclides are detected in the sampling rnedium, this report shall be submitted if:

Concentration (1)

Concentration (2)

+

+... >~ 1.0 Limit Level (1)

Limit Level (2)

Base:I on the analytical results of environmental samples during 1996 the Beaver Valley Power Station reporting levels were not exceeded.

l 1

l l

3-18 section 3. ENVIACNMENTAL MONITORING CONSIDERATIONS

Duquesne Light Company 1996 Annual Radiological Environmental Report Section 4. MONITORING EFFLUENTS A.

Monitoring of Liquid Effluents 1.

Description of Liquid Effluents at the Beaver Valley Power Station.

i j

Most of the water required for the operation of the Beaver Valley station is taken from the Ohio River, and returned to the river, used for makeup to various plant f

systems, consumed by station personnel, or discharged via a sanitary waste system. In addition, liquid effluents are discharged to the Ohio River using discharge points shown in Figure 4-1. Schematic diagrams of liquid flow paths for the Beaver. Valley Power Station are shown in Figure 4-2. Figure 4-3, a

Figure 4-4 and Figure 4-5 i

2.

Radioactive Liquid Waste Sampling and Analysis Program 1

See Tabte 4-1.

l 3.

Results of Liquid Effluent Discharge to the Environment See Table 4-2.

i l

i l

I section 4. MONITORING EFFLUENTS 4-1

Duquesne Light Company 1996 Annual Radiological Environmental Report Figure 41. Liquid Discharge Points to Ohio River I

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se if ir O

s 2

COOLINGTeg8ER BLOWOOWN. BWpS.g $g hf 4

~

O BVPS-1 & -2 COMB 8860 3

DISCNARGE POINT ZO Q

FIGURE 4 2 -UNIT 1 WATER FLOW SCHEMATIC E

m 2

-4 10 m

r*

b t

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2?

6L STREAM STREAM FLOW COLLECTION, TREATMENT E. DISCHARGE N o.

RATE eves-2 COOLING C

l.

CONT SUMP 400PD tower 2.

HtOH-LEVEL LIQUID E VAPOR ATOR BLOwbOwN

[

2.

AUX BLDG 50MP ZOOGPO W STE TEST DRAINS SO GPM C

ION EXCHANGER TANWS 2

.O 3.

LAS OftAINS 4000P3 b

OF a 10 S.000 G A L 3,000 C AL 4.

R.P. S A MPLE S 35GPD gypg,

,,COQLING g

a TOWER g

e 5.

MISC. SOURCES 660GPD SLOWDOWN e

i STEAM iSpOOGPM m

6.

usse. SOURCES 400PD CENERATOR

}

BIJDWDOWN 3

. SVPS-B En-2 F.

SG PRE FILTER IOGPD TAMKS 2 l

BACK WASH 30,000 CAL COM9GNED h

OISCHARGE

-U SO GPM POINT

U5 CL h SORON TEST o cn TANKS 2 oy

~

14.500 GAL O. p O o~

=

m -+

PURIFICATION CS 10N BORON 9040se kO 8.

CVCS LETDOWN 60GPM ION EXCMANGER SOO# EXCHANGEn RECOVER 1r EVAPOA ATORS 2

=;. O 18vP5-1)

OF 80 TANMS 2 IS GPal o3

==

/HR OF.10 195,000 105ALL EMCEPT I s T3 CAL lot y g

SVPS-1"I

$M PUHaflCAllON CS BON STEAM g

CYCS LETDOWN l

ION E XCH ANGER 500 # EXCHANGEp GENERATOR 9-(BVPS-2) 60 GPM DF IO

=+

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0F:10 EVAPORATOR g

m

/ He g

g 0-0 O

O 10.

BVPS-1 TURBINE 7,2 00GPO h

BLDG DHAtNS C

NOTgge DISCHARGES TO BVPS-l

[

ENVIRONMENT 9

1 CMUM MER t iNPuf TO aves-a sTEAu cENERATOR eVPs-i vARO a

stowoOwN EVAPORATOR is NOT usED onAiNAGE BLOWDOWN AND ENVIRONMENT DURING NORMAL BASE LOADED OPERATIONS DeSCHARGE POINT)

I h

2. IF RADICACTMTY iS DETECTED. TURBINE n

8tpLDING DRAINS CAN BE TRANSFERRED TO

?

THE CHEMICALWASTE SUMP AND TREATED AS S

EIOUID WASTE.

'i.

Y w

s h.

'I g

A Y

r

.m h

C 4

2.

o m

N STR AM 0

STR EA M COLLECTION, TREATMENT, G DISCHARGE gg

[

SVPS-t EVPS-I COOLIN G g

C EVAPORATOR TOWER BLOWOOWN as a

Q 1.

CONT SUMP 40 GPD FEED PUMPS ISpOO GPM d

m m

2.

AUX SLDG SUMP ZOO GPD WASTE LIQUID WASTE SVPS-2 k

k DRAINS WASTE TEST 100 GPM COOLING 3

3 3.

MISC SOURCES TOOGPD TANKS E ION EXCHANSER TANeiS g TOWER y

W BLOWDOWN

~U F,500 GAL OF e 80 C

18,000 GAL Q

4.

R.R SAMPLES 35GPO 03 9.CO STEAM OM S.

LAS DRAINS 4000PD 5 WD TANN5 2 O c~

BV P S-1 Tn -2 CONDENSATE DEMH NO 6.

RINSE WASTE 2,685 GPD COOLING 3 O i

70 g

7, 8vPS 2 TUR81NE NO COMCMN OR BWEM MRMM 7,200 GPO

- (gyp 3 2 YARD ORAINAGE 3$

ON BUILDING DRAINS DISCHARGE POINT)

GX 3

2 N OT ES:

[

1. NO STEAM GENERATOR SLOWDOWN IS DISCHARGED.

y h

2. TURBINC-8UILDING DRAINS ARE PROCESSED BY THE LicutD WASTE SYSTEM UPON HIGH ACitvlTY.

DISCHARGES TO BVPS-2 COOLING TOWER BLOWDOWN AND ENVIRONMENT t

i i.

_~-- -.

- - ~

i k

TABLE 4-1 5

Radioactive Liquid Waste Sampling and Analysis Program E

N OF LOWER M OF f

LIQUID SAMPLING ANA SIS A

ION (RD) g

-[

RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (s/Ci/ml) x Principal Gamma p

p SE-7 E-Emitteraf o

t Each Batchh Each Batchh I-131 1E-6 a-e p

Dissolved and c

M Entrained Gases 1 E o y

Batch Waste Release One Batch /Mh Tanksd (Gamma Emitters) k 3

g g

P M

H-3 1E-5 g

gg

[

j Each Batchh Compositeh Gross Alpha 1E-7 P

O Sr-89, Sr-90 SE-8 h$

-j u

-m I

Each Batchh Compositeb Fe-55 1E-6 5

8 to Principal Gamma W

SE-7 C

Grab Samplee

. Emitterst n

]E l-131 1E-6 Eh

[

i g

Dissolved and Qy B.

Continuous

?

3$

i Releases *.e

( amma mitters) g gx M

H-3 1 E-5 3"

I Grab Samplee m

x Compositec Gross Alpha 1 E-7 d

m u

5 O

Sr-89 Sr-90 SE-8 o

Grab Samples 3

Compositec Fe-55 1E-6 mo W - At least once per 7 days

}

M - At least once per 31 days O - At least once per 92 days

}

'g P - Completed prior to each release j

.ks 9

i

.a i

.Ys

Duquesne Light Company 1996 Annual Radiological Environmental Report 4

{

TABLE 4-1 NOTATION The Lower Limit of Detection (LLD).

a.

b.

A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

To be represer:ative of the quantities and concentrations of radioactive c.

materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the l

composite sample to be representative of the effluent release.

i d.

A batch release exists when the discharge of liquid wastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then j

thoroughly mixed to assure representative sampling.

A continuous release exists when the discharge of liquid wastes is from a e.

non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. Releases from the Turbine Building drains and the Auxiliary Feedwater Pump Bay Drain System and Chemical Waste Sump are considered continuous when the primary to secondary leak rate exceeds

]

0.1 gpm (142 gpd).

f.

The principal gamma emitters for which the LLD specification will apply are i

exclusively the following radionuclides: M n-54, Fe-59, Co-58, Co-60, Zn-65,

}

Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

g.

When radioactivity is identified in the secondary system, a discharge permit should be prepared on a monthly basis to account for the radioactivity that will eventually be discharged to the Ohio River.

h.

Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling will be performed by means of a grab sample taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during pump operation.

4-8 Section 4. MONITORING EFFLUENTS

-. - ~.

E Duquesne Light Company 1996 Annual Radiological Environmental Report Table 4 2. Results of Liquid Effluent Discharges to the Environment 4

TABLE 4-2 RESULTS OF LIQUID EFFLUENT DISCHARGES TO THE ENVIRONMENT 4

Effluent Type Results for 1996 Steam System The Steam System Blowdown was recycled when Blowdown practicable.

Batch Routine planned releases of liquid effluents from the Radioactive Beaver Valley Power Station were released in accordance l

Waste Liquids with conditions noted in Section 6.8.6a of the Technical Specifications and Appendix C of the ODCM. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Annual Radioactive Effluent Release Report for 1996.

Continuous Radioactive waste liquids were not discharged in a Radioactive continuous mode during 1996.

Waste Liquids j

l Section 4. MONITORING EFFLUENTS 4-9

,~

... - ~._

~

1 Duquesne Light Company l

1996 Annual Radiological Environmental Report B.

Monitoring of Atmospheric Effluents 4-j 1.

Description of Atmospheric Effluent Sources i

Beaver Valley Power Station (Units 1 and 2)

The Beaver Valley Power Station identifies radionuclides according to i

Section 6.8.6a of the Technical Specifications, Appendix C of the ODCM and Regulatory Guide 1.21.

Prior to waste gas decay tank batch releases and containment purge releases, an analysis of the principal gamma emitters is 1

performed. The principal gamma emitters include noble gases, iodines, and particulates. Figure 4-6 shows the gaseous radwaste system at Beaver Valley Power Station.

The environmental continuous gaseous release points also require specific i

nuclide identification. These points include:

j a.

Unit 1 Release Points:

3

1) The Ventilation Vent located on top of the Unit 1 Primary Auxillary Building.

2) The Supplementary Leak Collection and Release System (SLCRS)

Vent located on top of the Unit 1 Containment Building.

b.

Unit 2 Release Points;

1) The Ventilation Vent located on top of the Unit 2 Primary Auxiliary Building.

4

2) The Supplementary Leak Collection and Release System (SLCRS) l Vent located on top of the Unit 2 Containment Building.

3) The Decontamination Building Vent located on top of the Unit 2 l

Decontamination Building.

4) The Waste Gas Storage Vault Vent located on top of the Unit 2 j

Decontamination Building.

5) The Condensate Polishing Building Vent located on top of the Unit 2 Condensate Polishing Building.

i-

c. Unit 1 and Unit 2 shared release point;

1) The Process Vent located on top of the Unit 1 Cooling Tower.

These points are continuously monitored for particulates and gases.

G rab samples are obtained on a weekly basis and are analyzed for noble gas gamma emitting isotopes. Grab samples are obtained on a monthly basis and analyzed for tritium. Weekly continuous samples are obtained on filter paper and charcoal cartridges.

The filter papers are analyzed for particulate gamma emitting radionuclides and gross alpha. Composites of the filter papers are analyzed monthly for Sr-89 and Sr-90. The charcoal cartridges are analyzed for I-131,1-133 l

and 1-135.

Figure 4-7 shows these gaseous release points.

i 4-10 Secuon 4. MONITORING EFFLUENTS

4 Duquesne Light Company 1996 Annual Radiological Environmental Report Figure 4-6. Units 1 and 2 Gaseous Radwaste System 1

I"yMg%INgMit H5m is etn95NtXIsp i

t 4j l

on i mt:

ll CourtE5 son CoerM3508 I

f 4

(_, _)

(lua rnes lf(lumia= l ~

H pee e e IIGI I.E

(.._.)

t zi__i)-

l

(..._.)

4:_,_ip

(-- -)

qi_ _ip j

1

{lx= = lf flx=r=\\)-

I

)

FILTEE 8N f**

"" I '*

l 1

lx= team lnce,inl-o

>(

=

.c

....i. h,r-

$MEIP Ces k

==ma

.=na"*JfL-ca s=.isurano

.uri, n

,,J g.

=tma

>Q-mui

==

>C::2 FIGURE 4 UNITS 1 AND 2 GASEOUS RADWASTE SYSTEM Section 4. MONITORING EFFLUENTS 4-11

Duquesne Light Company 1996 Annual Radiological Environmental Report Figure 4-7. Units 1 and 2 Gaseous Release Points

--a - Ohio Ib **

• l

~

Cj l

I

+

i l

E h./

I

@N f

- 09

'N

]

1, 1

i D

a e

I J

m i

Unit 2 i

Uniti i

1 ]

4 e

s a

t IILIAR P0!If a DESCEPUCK fuftflot

1. Unit 1:

Ventilation fest 79 feet : 24 uters Q

2. telt 1:

Contaluseat / SLCI3 Test 151 fest 47 seters i

3. Dait 1 & 2: Process feet 475 feet : 145 meters

4. Unit 2:

fentilaties fest 85 feet: 26 seters a7 l

5. Deit 2:

Costainneet / Sitts feet 154 fut : 47 meters

5. Delt 2:

Coedessete Polishing Beilding fest 80fut: '24 setere pw

1. Unit 2:

fasta Gas Storage Taslt Vest 80 feet: 24 esters 1

5. Cait 2:

Decostasiaation Belldlag fest 80 feet : 21eeters FIGURE 4 UNITS I AND 2 GASEOUS RELEASE POINTS 4-12 secuon 4. MONITORING EFFLUENTS

I Duqucsno Light Company 1996 Annual Radiological Environmental Report l

2.

Atmospheric Effluent Treatment and Sampling Gaseous Waste Disoosal System (Units 1 and 2) l Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor. Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A small amount of l

nitrogen and radioisotopes consisting of noble gases, particulates and radiolodines are also present in this system.

1 The overhead gas compressor directs the radioactive gas stream to a gas surge tank. Gas is periodically transferred from the Unit 1 or Unit 2 surge tank to one of the three (3) storage tanks at Unit 1 or one of the seven (7) storage tanks at Unit 2. The tanks are then sampled and authorization obtained for discharge in accordance with the ODCM. The discharge of the waste gases from the decay tanks (2 scfm) is then diluted with about 1000 scfm of air. The gases are then combined with nitrogen purge from the oxygen analyzers, calibration gas from the oxygen analyzers, the main condenser air ejector exhaust, the containment vacuum system exhaust, aerated vents of the sweep gas system, discharge of the overhead gas compressor and the purge from the applicable multi sample point radiation monitor. The mixture is then filtered through one of the gaseous waste disposal filters, each of wh!ch consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the Unit 1 cooling tower. The radioac'.tvity levels cf the stream are continuously monitored in accordance with the ODOM.

Should the radioactivity release concentration of the stream exceed the allowable setpoint, a signal from the radiation monitor will stop the discharge from the applicable Unit 1 or Unit 2 tanks.

Reactor Containment Purce (Units 1 and 2)

During a shutdown period after the Unit 1 or Unit 2 containment has been sampled and authorization for discharge determined in accordance with the ODCM, purging may commence through the Ventilation Vent located on top of the Auxiliary Sullding or the Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Reactor Containment Building or the Process Vent located on top of the Cooling Tower.

I Section 4. MONITORING EFFLUENTS 4-13

Duquasne Light Company -

i 1996 Annual Radiological Environmental Report j

L I'

I i

Buildino Ventilation Systems (Units 1 and 2)

E l

Most areas in the Unit 1 Auxiliary Building'are monitored for radioactivity by individual radiation monitors which aid in identifying _any sources of l

contaminated air. The normal exhaust is through the Ventilation Vent effluent pathway.

This pathway -is monitored continuously by several redundant L

channels of the Radiation. Monitoring System (RMS) in accordance with the ODCM. Particulate and iodine samples are obtained continuously while grab j

l noble gas samples are obtained weekly in accordance with the.ODCM. Upon a upper activity alarm, automatic dampers divert the system's exhaust air stream' j

through one of the main filter banks in the Supplementary Leak Collection ~and l

Release System (SLCRS) which exhausts through the SLCRS Vent effluent j

pathway.

5 Areat in the Unit 2 Auxiliary Building (subject to radioactive contamination) are monitored for radioactivity prior to entering the filter banks in the Supplementary Leak Collection and Release System. (SLCRS).

This system is sampled l

continuously for particulates and lodines and is sampled weekly for noble gases,-

in accordance with the ODCM. This system is monitored continuously by the '

Digital Radiation Monitoring System (DRMS) in accordance with the ODCM.

Each Unit 1 and Unit 2 SLCRS filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type HEPA filters. The roughing filters remove large particulates to prevent excessive pressure drop due to buildup on the charcoal..and HEPA filters.

The. charcoal filters are effective for radioactive j

iodine removal and the HEPA filters remove particulates and charcoal fines.

i These and other release points for Unit i and Unit 2 of the Beaver Valley Power l

Station are shown in Figure 4-7. Some of these release points discharge small l

amounts of radioisotopes consisting of noble gases, particulates and radiolodines.

L See - Table'4-3 for the. Radioactive Gaseous Waste Sampling and Analysis

[

Program..This program is an excerpt of the requirements contained in the j

ODCM.

i

- 3.

- Results l

Gaseous effluents from the Beaver Valley Power Station were. released in accordance with conditions noted in S' ction 6.8.6a of the Technical e

Specifications and Appendix C of the ODCM. No limits were exceeded. These values have been reported in the Baaver Valley Power Station Annual

(

Radioactive Effluent Release Report for 1996.

i i

' 4-14 secuon 4. MONITORING EFFLUENTS

~.

TABLE 4-3 Radioactive Gaseous Waste Sampling and Analysis Program E

t GASEOUS SAMPLING

^

I b

RELEASE TYPE FREQUENCY I

FREOUENCY ANALYSIS

( Ci/cc)

o i

Principal Gamma 1.

Waste Gas P

P 1 x 104 s

Emitterse o

Storage Tank Each Tank Grab Sample Each Tank H-3 1 x 10-e a

u)

F P

Principal Gamma

2. Containment P

1 x 10-4 Emitterso Purge Each Purgeb Grab k

Each Purgeb Sample H-3 1 x 104 c.

32 g

3. Ventilation Principal Gamma h

0 1 x 104 t

Systemsh Mb.c.e Grab Sample Mb Emitterso n

,3 m i

0 C

p h$

i a.

Process Vent H-3 1 x 104

{

[5 5

b. Aux. Bldg.

Wd 1-131 1 x 10-12 ents Charcoal Sample 1-133 1 x 50 to d

kh a

ontainmW I

Vents Wo Principal Gamma m -+

59

[

Emitterso (1-131, 1 x 10-11 d.

Decon. Eidg.

Particulate Sample Others)

[

[g Vent x

3V M

$~

$ x$

3 i

e.

Waste Gas Continuousf Composite Particulate Gross alpha 1 x 1011 y

Vault Vent Sample k

E g"'

f. Cond. Polish.

I O

3-Bldg. Vent Composite Particulate Sr-89. Sr-90 1 x 10-11 o

A Sample C

k Noble Gas Monitor 1 x 104 w

Beta and Gamma oy W-At least once per 7 days o

M - At least once per 31 days Q

O - At least once per 92 days

{

P - Completed prior to each release E

a f

a M

Duquesne Light Company 1996 Annual Radiological Environmental Report TAa!.E 4-3 NOT ATION a.

The Lower Limit of Detection (LLD).

b.

Sampling and analysis shall also be perfcrmed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a i hour period. This requirement does not apply if (1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased mere than a factor of 3.

c.

Tritium grab samples shall be taken at ceast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from the appropriate ventilation release path) when the refueling canal is flooded.

d.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampier.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15%

of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant nas not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

e.

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pt:al area, whenever spent fuel is in the spent fuel pool.

f.

The reerage ratio of the sample flow rt.e to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Appe ndix C CDNTROLS 3.11.2.1, 3.11.2.2 and 3.11.2.3.

g.

The principal gamma emitters for which the LLD specification will apply are exclusively the followir:g radionuclidos: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissicns and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-154, Cs-137, Ce-141, and Ce-144 fcr particulate emissions. This list does not mean that only these nuclides are tes be detected and reported. Other peaks which are rneasurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclidos which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstareces resuit in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

h.

Only when release path is in use.

4-16 secuon 4. po'flToRING EFFLUENTS

Duquesne Light Company 1996 Annual Radiological Environmental Report Section 5. ENVIRONMENTAL MONITORING PROGRAM A.

Environmental Radioactivity Monitoring Program 1.

Program Description The program consists of rnonitoring 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 5-1.

Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are included in sections 5-B through 5-1 of this report.

5-B - Air Monitoring SC - Sediments and Soils Monitoring 5 D - Vegetatiori and Foodcrops 5-E - Cows Milk 5-F - Environmental Radiation Monitoring 5-G - Fish 5-H - Surface, Drinking, Well Waters and Precipitation 5 Estimates of Radiation Dose to Man i

f l

l Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-1

m._..

Y n

TABLE 5-1 r

i g-RADIOLOOtCAL ENVIRONMENTAL MONITORING PROGRAM

-1 m

asE l

DLC e

m g,,,,,

g Type of 3emple Sample Sector Mllas Sample Point Description Sample Frtal-sacy Analysis (b)

Pointe Y

z 1.

Air Particulate 53 11 18 Meyer's Farm Continuous Sampling Weekly Composite (d)

Gross Beta. (c)133; and Radio!adine 33 4

0e SNppingport. PA (S S.)

with sa a,,le Ouarterly Composite (d)

Gamma -scan f

2 48 1 3

24 industry PA collection at least c.

y 32 15 08 Midland. !" A (S S )

weekly 6

P 48(a) to 18.5

.Wirten. WV (a)

J

$1 5

89 A;tquippa PA (S S.)

E y

y 6

4' 14 4S East Livatpool. OH E.

to z4 17.

7 82 Brunion's Farm m

G 28 1

87 Sherman's Ferm

[

_ Q 3

g 298 3

89 Beaver County Hospital 3

h 2.

Direct Radiation 30 4

08 Ehlppingport. PA (S S.)

Continuous (TID)

Quarterly 0)

Gamma-Oose x

13 11 18 Meyer's Farm

-O h

( 48 3

2.5 Industry, PA (Chure!

h~

a 32 15 08 Midland, PA (S S.)

C g$

e k

48(a) 10 18 5 Weirton, WV (a)

E g

45 1 8

20 Raccc & Twp.PA O

Kennedy s Crnrs.

[

O @3 81 5

80 Aliquippa, PA (S.S )

3.

6[

47 14 48 East Uverpool, OH 12 e3 70 1

30 West t3vr, School u

m I

j sg 80 9

84 Raccoon Park

$. o 81 9

39

$cuthside School 82

. G 7.1 Hanover Municipal Badg y

83

{

83 10 45 Mill Creek Rd 3 T3 3$

14 11 28 Hookstown 84 11 85 Hancock Co. Children Home G X 83 12 58 Rts. 8 & 30 intersection U.,

l 86 13 85 E. Uverpool Cahl:Is House E

i 92 82 30 Georgetown Rd.

m j

87 to 7.0 Calcutta Read G

88 15 31 Midfind Heights

]

89 15

4. 7 '

C%!outle 3

90 18 52 Fairv6ew School to 4

08 Shippingpart Boro, PA 45 5

2. 2 Mt. P1easant Church 80 13 37 Haney's Farm l

93 18 53 Sunset Hills. Midland t

t J.

I

TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DLC

=,, ;;,:';,

Anal-sie)

T,,. o, 8.m.t.

8egie

. ecto, Mi...

..mp,.,oint D.s=,po.n Sam.,e4ue,.ey 2

D6 rect Radiation 95 10 24 McCleary Rd, HotHe Williams Continuous (TLD)

QuartertyC)

Gamma-Dose (continuec) 28 I

87 Shermen's Farm 71 2

58 Brighton Twp School 72 3

32 Site of Former Logan School 2GO 3

81 Beaver County Hospital 73 4

22 Potter Twp Schooi Q

74 4

88 Cu.nm College-Center Twp (o

75 5

43 Holt Road G

78 8

36 Raccoon Twp. School 77 8

58 Green Garden Rd 3

59 7

1.1 frons 3c 78 7

23 Raccoon Mun Bldg 1g 27 7

82 Brunton's Farm C

78 8

48 Rt.19 & Rt.15t y

c3 y 15 14 33 Georgetowri Post Offtce Q- (D 48.1 3

2.1 Industry PA O CA 81 2

37 Pine Grove Rd and Doyle Rd O5

~

84 8

24 McCreary Rd, Witson 3.

Surface Water 49 i;a) 4 50 NOVA Chemicals (formerty Weekly, intermt! tent WeaMy Sample from I-131 0_3 C Arco Polymers)

Composite Samples (t)

NOVA only m3 2.1 14 1.3 Downstream (Midland) J&L r

ca 5

14 48 East Liverpoot (raw water) d Gmem*

UO 5O d

Weekly Sample (d)

Daily Grab Sample g

y Only - Collected 3V weeMyo) 0"'"*"Y C** * '"*

"-3, Sr-89, Sr 90 gg Og 4.

Groundwater 13 il 18 besyer's Farm Semi-Annual Same Annual Gamma-scan H-3 3

m 2

14 11 28 Hookstown, PA f

D3 15 15 33 Georgetown, PA 11 3

08 shippingport Boro g

C 5

DHnking 4

14 13 Midland, PA (Midland Water Intermittent (e) Sample Weekty Composite of I-131

]

Treatment Plant)

Collected Weekly Daily Sample id) 3

, y Monthly Composite (d)

Gamma-scan, I-5 14 48 East Liverpool, OH (East E

Uverpool Water Treatment Quaderly Composite (d)

H-3, Sr-89 Sr-90 h

PIant) a O

m 8.

Shoreline 2A 13 02 Downstream BVPS Outfall Semi-Annuai Semi-Annual Gamma-scan 2

Sediment O

43 3

32 Upstream Side of 3

Montgomery Dam (a)

Q 50 13 82 Upstream side of m

New Cumberland Dam DE Yw

to TABLE 51 ky RADIOLOGICAL ENVIRONMENTAL MONIYORING PROGRAM

$a Type of Semple Sa le Sector Miles Sample Point Description Sample Frequency Analvsis(b) 3 Pointe p

?

Milk 25 10 2.1 Seartght's Dalry Weekly (f)

Weekly sample from 1-138 C

Searight's only Biweekly (GI when B weekly (grattag)

Gamma-scan y

animals are on Monthly (Indoort i Sr-89 Sr-90,1-131 r-pasture, monthly at 96(a) to 13 3 Wtndsheimer's Diary other times.

Q z

27 7

82 Brunton's Dalry (o

h C)

BVPS OOCM, Appendix C, Table 3.121 requires three (3) datries to be selected on basis of highest potential thyroid dose using milch census data See Section 5-E for specific 2

locations sampled.

y 2

s 0

8.

Fish 2A 13 02 Vicinity of BVPS Samt-Annual Composite of edible

'3amma-scan C

3

]

Station Discharge parts by species (h) on Mible M_O 49(a) 3

4. 7 Upstream Side of portions y(C Montgomery Dam m

(

8 Food Crops Annual at harvest if Composite of each Gamma-scan O

(Sh!pp )

to 4

00 Three locations within available samp:e species 1-131 on green

~U O

(Georg )

15 14 33 5 miles so! acted by DLCo.

teafy vegetables e

O (indus.)

48 3

25 Waltton, WV 6[

48(a) to 18 5 NO 7

10 Feedstuff and 25 to 2.1 Seartcht's Datry Farm Monthly Monthly Gamma. scan ITI ~

Summer Forage h

11 Soll 13 11 I8 Meyer's Farm Every 3 yeats (1994, 12 Core Samples Gamma-scan o' 3 30 4

08 Shippingport, PA 1937. etc )

3* Deep (3' Dia 3V 44 3

28 Industry, PA at each location 3$

32 15 08 (North of Site) Midland (approw 10' OM 4g(a) to 18 5 Wetrton, WV radius) 51 5

80 Aliquippa. PA 47 14 48 E. Uverpool, OH 2

27 7

82 Brunton's Dairy G

22 8

03 South of OvPS Site 2'A 3

83 Nicol's Dairy 3

12 Precipitation 30 4

06 Shippingport, PA Weekly grab samples Quarterly Composite y-scan, H 3 47 14 48 East L!verpool, CH when evallable 48 to 18 5 Weltton, WV l

[

t

Duquesne Light Company 1996 Annual Radiological Environmental Report TABLE 5-1 NOTATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (continued)

Notes:

(a) Control sample station: These are locations which are presumed to be outside

.the influence of plant effluents.

(b) Typical detection sensitivities for gamrna spectrometry are shown In Table 5-4.

(c) Particulate samples are not counted for 2: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change. Perfoim gamma isotopic analysis on each sample when gross beta is > 10 times the yearly mean of control samples.

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

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

(f)

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

(g) Milk samples are collected bi-weekly when animals are in pasture and monthly at other times. [ Assume April-October for grazing season (pasture).]

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

(i)

Composite samples are 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 /> at locations 49.1 and 2.1.

A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5.

(J)

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

i Additional Notes:

Sample points correspond to site numbers shown on maps.

All 1-131 analyses are performed within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of sample collection if possible.

All air samples are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for Gross Beta.

Section S. ENVIRONMENTAL MONITORING PROGRAM 5-5

Duquesne Light Company 1996 Annual Radiological Environmental Repori i

2.

' Summary of Results All results of this rnonitoring progiam are summarized in Table 5-2. This table is prepared in the format specified by NRC Regulatory Guide 4.8 and in accordance with Beaver Valley Power Station Operating License, (Appendix A, Technical Specifications /ODCM).

Summaries of results of ana!ysis of each.

)

media are discussed in Sections 5-B through 5-H and an assessment of radiation -

j doses are given in Section 5-l.

Table' 5-3 summarizes Beaver Valley Power l

Station preoperational ranges ior the var!ous sampling media during the years i

1974' and 1975.

Comparisons of preoperational data with operational data

.l l

Indicate the ranges of values are generally in good agreement for both periods l

of time.

Activity detected was. attributed to naturally occurring radionuclides, BVPS effluents, medical procedures, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the lower limit of detection (LLD).

j The conclusion from all program data is that the operation of the Beaver Valley Power Station has resulted in insignificant changes to the environment.

j j

3.

Quality Control Program l

The Quality Control Program implemented by Duquesne Light Company to assure reliable performance by the DLC contractor and the supporting QC data are presented ar.d discussed in Section 3 of this report.

i 4.

Program Changes

)

l The following changes were implemented in the 1996 sampling program.

• Air Particulate: gamma spectrometry analysis changed from monthly to quarterly; quarterly Sr-89/90 analysis deleted.

• Direct Radiation (TLDs): deleted annual TLDs.

c l

1 l'

• Su: face Water: deleted sites 2.0 BVPS Station Discharge and 2A j

Downstream BVPS Outfall; deleted gross alpha / beta and high sensitivity l.

. Co-60 analysis.

• Groundwater: changed sampling frequency from quarterly to semi-annual; deleted gross alpha / beta analysis.

• Drinking Water: gamma spectrometry analysis changed from weekly to monthly; deleted gross alpha / beta and high sensitivity Co-60 analysis.

• Shoreline Sediment: deleted gross alpha / beta and Sr-89/90 analysis.

• Feedstuff and Summer Forage: deleted quarterly Sr-90 analysis.

• Soll: deleted Sr-90, gross alpha / beta and uranium isotopic analysis.

l

• Precipitation: gamma spectrometry analysis changed from monthly to quarterly; deleted gross beta and Sr-89/90 analysis.

• Milk: deleted site 29 Nichol's Dairy.

5 section s. ENVIRONMENTAL MONITORING PROGRAM

-4 e) tr ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

iii Name of Facility Beaver Vallev Power Station Unit 1 and 2 Docket No. 50-334/50-412 g

Location of Facility Beaver. Pensavivania Reporting Perioil Annual 1996 N

(County, State) gi i

h Analyals med Imwer Limit Number of Medless ofFathway Total Number of AllIndicator Lecitisas Locatloe with Highest Anesel, Mese ' Control Locations Nearestias 3

l 2

Sampled ofAmelysis Detecties

• • Mesa (Q Name

• • Mean (f)

• • Mean (f)

Reported (Unit of Measurement) Performed

• (LLD)

• • Ramqe Distance and Directions ** Range

• • Range Eleasurements**

• g h

Weirtog WV No. 48

{

y 0

3 Water Gamma (12) 2.

Precipitation Be-7 (a) 63 9 (5/12)

30. Shippingport. Pa.

74.9(t/4) 65.)(3/4) 0 to-O (pCVt)

(48 8-7L9) 0.6 mi E!E (333-726) 3-e c

M Ma-54 3

LLD 0

7 c$.n5 3

ww I's-$9 10 LLD O

g 6g 3

e5' C co-5s 5

LLD o

.o tu e i

ee r

Co 60 5

LLD 0

G.

m~

3 I

E j.O m

Zn 65 to LLD 0

O O

d 3

e 0

3$

5 Zr/Nb.93 LI.D 0

~u 3

3

$M L

Cs-134 5

LLD 0

E iii 5

Cs-137 3

LLD 0

mo

o e

2 Ba/La-140 10 LLD 0

k oO II-3 (12) 200 335 (2/12) 30, Shippingpan Pa.

470 (l!4)

LLD 0

3 (200-470) 66 miENE t~

EO L

2 (a) LLD for this nucible for Water Precipitation not required by ODCM

-AO t

Bg Nomleet Lemer Limit of Detecteen (L1D) y Mean and range based spea detectable measure:=ents only. Fraction of detectable measurements et specified locations is is Jicated La parenthenee (f; Noarentine reperled measurements are defleed le Reguletory Guide 4.0 (December 1975) and tbs Beaver Valley rewer Station Specificaties.

m 8

m>C Y

-4 m

V' es t.

D" L9 s

O f*

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

g g

5 Name of Faculty Beaver Vallev Power Station Unit I andl Docket No. 50-334/50-412

(.

d Locattom of Faculty Beaver. Penasvlvania Reporting Period Annual 1996 8

(County, State)

}

3 I

3 E-Amelyste and Lower IJsli Number of f

Mediam ef Pethway TetetNamber of AB ledketee locations Emetice with ilighest Aeeuet, Mees Controllmatka; Nosraetime O

S*8P ed ofAeolysis Desecties

" Mese (f)

Nease

• • Mese(f)

" Met n (f)

Reported q

to l

2 (Uelt of Messerement) Performed

• (LLD)

• • Range Dietence end Directions ** Rsnee

• • Rasse Mmurce:ents*"

h*

y Georgetown,PA No.15 g

y G

a

?

2 Groundwater H-3 (6) 200 LLD O

m a

_O Q

Gaanes(6) y mj D) c m

Ma-54 5

t.t.D 0

Q

{

h Fe-59 10 LLD O

r-n 00-58 5

LtJ) 0 g

gu 6 m

r 3

{

0 Co-60 5

LLD i

{o Za45 16 LLD 0

g au 2r/Hb-95 5

LLD O

g 03 h

Cs-134 5

LLD 0

02 Cs-137 5

LLD 0

X Be/La-140 10 tip 0

0 A

r i

Needeel Lewer Limit of Detertes (LLD)

Mese and reage based spee detectable seemserements nely. Fractise of detectable seesserements et specified locations is ledicated in parentheses (f)

• • • Noorouties reported messeresseets are defleed to Itegulatory Guide 4A (Deccesber 1975) and the Beaver VeBey Fewer Station Specirweties

..~.-..

-i ke Y'P ENVIRONMENTAI, RADIOLOGICAL MONITORING PROGRAM

SUMMARY

5' Name of Facility Beaver Va8!ev Power Station Unit I and 2 Docket No. 50-334/50-412 w

o Location of Facility Beaver. Pennsvivania ReportingPeriod A;p3al1996 g

(County, State) to3 81 Analys6s and lawer Limit Number of g

Medium of Pethway Tete! Number of AII!adicator Lees. ions Imaties with Highest Asnual, Mesa Centrol Locations Neareutine o

a Sampled ofAmelysis Detection

• • Mesa (f)

Namie

" Mean (t)

" Mesa (t)

Reported (Unit of Measurement) Performed

• (LLD)

• • Range Distance and Directient ** Range

• • Itange Measurements ***

O CD I

c

=

Ddaking Water I-13t (104) 0.5 0 51(39/I04) 04, Malland Pa.

0.55 (22/52) 0 7

(pCill)

(0.28-2.2) 1.3 mi WNW (0.32 2.2) su g as C

y Gamsna (24) 3 ga p

o c go Ma-$4 5

LLD 0

6 to Fe 59 10 LLD 0

E-~

(5 Co-58 5

LLD 0

[

Co-60 5

LLD O

e tu to e

r Zn45 30 LLD 0

m~

m Zre 95 5

LLD 0

[h g

Cs-134 5

LLD 0

3

.O g

Cs-131 5

LLD 0

]

p Ba/La 140 10 LLD O

mM Sr-89 (8) 2 LLD O

aO Sr-90 (8) 0.5 tJD 0

m V

g 18-3 (8) 200 LLD 0

h

-e>

r-E O

E

-40

[

Nemissi Lawer Lismit of Detectice (LLD)

Mese and roege based spee detectable sneeseressents only. Fracties of detectable measureusents et specified locations le ladkated la parentheses (f) 2

• • • Nearentine reported messarements are defined la Rer.satory Guide 4.8 (Deceeuber 1975) and the Beaver Valley Power Statias Specification.

8 sc Y

e

V.a' -

.o

.!m

[-

ls v

N l6 ENVIRONMENTAL RADIOLOGICAL. MONITORING PROGRAM

SUMMARY

rp t

! Q Naame of Facility Beaver Valley Power Station Unit I and 2 Docket No. 50-334/50-412 '

j.

Location of Facility Beaver. Penmayhania Reporting Period Annual 19%

3

[

(County, State)

.l 5

E y

Amelysis and 14wer IJait Number of

{

r-Medium of Pathway Total Number of Att ledicator tacetions Location with Highest Annual Mean Control 14caeleas Neareutine o

_a g

Sempted ofAnalysis Detection

" Mees (4 Name

• • Mees (f)

" Mean (f)

Reported.

2.

z

@ sit of Messarement) Perferened

• (LLD)

• • Range Distance and Directions " Range

" Range Measurements *"

o cn 4

Upstream-NOVA Chemical No. 49,1 5'

3>

Q U3 3

E Surface Weser 1131($2) 0.5 0.67(7/52) 49.1, Upstream, NOVA 0 67 (7/52)

One sampic 0

?

5 O

(pCill)

(0.22-l.2)

Chemical 5 0 mi ENE (0.22 - 1.2) location S

to g j

Sr-89(12) 2 LLD 0

D

]e-c 8

3 m

Sr-90(12) 0.5 LLD O

m Q. m 3>

Om E

H-3 (28) 200 160 (1/21) 49.1, Updream, NOVA 160 (I/21)

Some as high 0

E o$

~

Chemical 5.0 mi ENE location E

80. C o

O "U

Gamma (36)

-y 2

m -*

3 O Mn-54 5

LLD 0

g 0a Fe-59 10 II.D 0

ya a

Co-50 LLD 0

mM 3

Co-60 LLD

-0

{

[

Zn45 le LLD 0

T3

{

Zr/Nb-95 5

LLD 0

Cs-l)4 5-LLD 0

Cs-137 5

ILD 0

Ba4a-840 10 ll.D 0

Nemmel 14wer Limit of Detection (LLD)

Mees and range based spea detectobee --

.. ;ts sely. Frectles of detectable aseasuressents et speciRed locations is ledicated in perenthesee (1)

"* Neeroselee reported onessurements are defined la Regulatory Guide 4.8 (December 1975) med the Beaver YnWey Power Staties Specinceties.

t

l

~. -,

.~ _

Yro

.1 7

W ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

g' Naine of Facility Beaver Valley Power Station Unit I and 2 Docket No. 50-334/50-412

(-

Location of Facility Beaver. Penastivania Reporting Period Annual 1996 8

(County, State) j a

G i

Amelyons and 14wer timet Number of

{

[

i Medium of Fathway Total Number of Allledicatee Locations Laceden wkb Illghest Aneust, Mess Centrollacelless Nearentlee o

a i

Sempted ofAnalysis Detectise

• • Mees (f)

Name

• • Mesa (f)

• • Mesa (f)

Reported g.

{

(Unit of Messaremees) Performed

• (LLD)

" Range Dissance med Directises ** Reage

• • Isange Measuremenes* **

O m

Montgomery Dem No. 49 5'

C 3

Sedireest Gamme (6)

?

5 (pCi/s)

~

S fu-- g (dry weiglu)

Be-7 (a)

I.20(64)

49. Upstream, 8.41(2/2) 1.4. l(2/2) 0 g

%.g.-

(0 62-1.84)

Mnagmry Dare (0 971-1 81)

(0 971-1.84) g o

o. g 4.7 mi NE) y K-40 (a) 13(6/6)

49. Upstream, 14.6(2/2) 14 6(2/2) 0 0 (A (11-16)

Mutgmry Dare (13.1-16)

(13.1-16)

E.

o@

4.7 ml. NE E

O

- - r-o~

Co-58 (a) 0.84(t/6) 2A, BVPS Outfe!!

0.54(t/2)

(e) 0 G

su cr 0.2 mi. W g

Co 60 (a) 0 35(2/6) 2A, BVPS Outfalt 0.35(2/2)

(a) 0 sn l

g (0.267-0.442) 0.2 mi. W (0.267-0.442)

5. o 3

9-Cs-134 0.06 LLD 0

0 a u 3y Sa Cs-137 0.08 0.20(6 4) 49,Upstrsam.

0.24(2/2) 0.24(2/2) 0 (0.125M44)

Mntgary Darn (0.240-0 244)

(0 24-0.24)

(D x m

4.7 mi NE 3

y is Ra 226 (a) 2.15(6/6)

50. Upstream.

2.46(2/2) 2.39(2/2)

'O h

(1.38-2.96)

N.Cumberland Dem (1.94-2.95)

(2.85-2 63) x K

8.2 mi. W (D

O mz Th-228 (e) 1.19(6/6) 49 Upsircam, 1.39(2/2) 1.39(2/2) 0 0

(a93-1.63)

Mntamry Dare (1.14-1.63)

(l.14-l.63) 3 r

4.7 mi. NE E

f O3 O

(a) Lil.) for this nuclade for Sedimens not required by ODCM

+

g Nominal 14wer Umst of Detecties (l LD)

]

Mese and reage based spes detectable usesserements sely. Fracties of det-ctable measurements et speciEed leeetions is ladiesled le pareatheses (f)

Q Nearestime reported messerements are densed le Regulatory Golde 4.8 (December 1975) med the Beaver Valley Power Stalien Specification.

l 5e i

Y' i

a f

O r

i i..

m

. ~._..... _

V' an e'

~

t tn i

?

Y U

m ENVIRONMENTAL RA9tOLOGICAL MONITGRING PROGRAM

SUMMARY

g m

h Nanae of Facility Brayer variev rower station voit.na 2 nocket No,50-334/$0-412 '

l o

Locaties of Facility Beaver.Pennsylvestia Reporting Period Annual 1996 3

(Courity, State)

E!

c Aestysts and Raoer tamir Nember of h

[

F Medium of Pathnsy TotalNumber of A3 Indiretor Emcations locaties with liighest Anneal. Mean Centrol Lecatsoes Nearestine 0

^

{

Sampled of Amelysis Detecties

• • Mesa (f)

Name

• • Mean(f)

" Mene (f)

. Reported E

3 2

(Unit of Messerement) Farformed

• (LLD)

• • Rasse Distsace sad Directions ** Range

• • h uge Measurencets***

O Ch.

t T4 O

Windshctmer No. 96 3'

to a

t Milk 3-138(148) 0.4 LLD O

(pCL/I) 0 7

EO

[.0 Sr-A9 (Il5) 2.5 LLD a

St-90 (I t 5) 0.7 2.3 (ll5/tll) 105 Amtwose Dsi.y 3 0 (19/19) 1.6 (19/19) 0 O

m 6

t;:

C (I.2-3.0) 3 86 mi WSW (2.4-3 91 (l 2-3.2) g 6y a

C Gamme(I t5)

O EC

[

co 03 O to K-40 (a) 1329 (115/115) 104 Conkle Dany 135t (19/19) 136t (19/19) 0 S

mA (1020-1550) 3.75adWSW (1020-153c)

(1880.t55c) 3 ()

5. O i

Os-134 5

LLD 0

o3

[

2 'o e$

Cs-137 3

LLD 0

3 x BafLa-140 80 LLD 0

3 I

E

o -

tD T5 O

b

1 t

(a) LLD for tids nuclide for MIIk not required by 00CM i

f%cmleal temer IJett of Detectten (11D)

Mese and range based useo detectable messeroments only. I'ractice of detectable sereserements et specified lacastems is Indicated la parentheses (f)

Nooradies reported measurements are dehad in Regalesery Guide 4.8 (Decesaber 1975) end the Beaver Valley Pewer Station Specificattee.

6 m

m m

. - _. ~

i

-4 m

!Io Tm ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

E' Name of Fadlity Beaver Vallev Power Station Unit I and2 Docket No. 50-334/50-417

[

Location of Facility lleaver. Pennsvliamia Reporting Period Annual 1996 g

i (County, State) e E

Aeolysissed LemerIJait Number of g

Medium of Pothway Total Number af All lodicator RAcations IAceties wkh Iligbest Anesel, Mean Control tacations Neareselse o

i Sempted ofAmelysis Delettise

" Mene (f)

Neree

• • Maen (f)

• • Meae if)

Reported S-(Unit of Messerement) Performed

• (LLD)

• • Reage IHsf ence end Directions ** Range

• • Range Meesurements**

• Q Weirton, WV No. 48 E

C 2

f Food end Garden t-131 (4) 0.06 LLD O

?

8 Oops (pCds)

S 8D_c (wet wcW)

Gemme(4)

U c

l y

3 tu -O K.40 (e) 1.9(4/4) 45 Wcutan 2.0(111 )

2 (4til) 0 (t.5-2.0) 1605 unics SSW Cs-134 0.04 LLD O

c.

oy e

m Os-137 0 G6 Lt.D O

g- [

DJ c 5

~E i

mao

5. O 8-

,o 3 r

t

$ *s 3

i m

5 g

s O

2) i 2

(D E

O z

O j

-4 3

r-C O

t h

(a) LLD for this omtide for Food and Gerdce Oops not rcquired by ODCM i

O2 8

Nemiset 14wer Umia of Detectise (IlR).

m Mese med range besed spes detectable meessrements only. Fracties ofdetectable measurements et specirmed locations is indicated is pareetbases (f) t 8"

Neerenties repersed oneesereneets are defseed is Regelstery Caide 4.3 (December 1975) and the Beaver Volley Power Steeles Specthceties.

i s

c Y

W

i l

I V' a*

l Y1 t

u,

!5 V'P i

'm ENVIRONMENTAL RADIOI OGICAL MONITORING PROGRAM

SUMMARY

m m

o 2

Name of Facility Besver Vallev Power Station Unit I and 2 Docket No. 50-334/50-412.

1 l=

Location of Facility Beaver. Pennsylvania ReportingPeriod Annual 1996 g

(County, State) 3

,z i r a

! m 3

Aestysis sod IAwer Liste Nusrter of f

Medium of Fathway Totet Number of Altlediceter 14cetiens Leceties with liighest Aneusl. Meae Centrol tatations Neevestiac E

Sampled of Ametysis Detection

" Mene (f)

Name

• • Meae (f)

• • Mese (f)

Reported g

._ Unit of Measurement) Performed

• (LLD)

" Reage Distance and Directices " Raete

• • Range Musu emenes*"

w to

(

O e

Montgomevy Dare No. 49 2

4 3

O Fish Camma(t) 2 (pCi/g) k'

'" O c

(wet weight)

K-40 (a) 3 42 (8/8) 49 Upstream 3 61 (4/4)

Same as 0

m (168-391)

Montgomery Dam (1.19-3.91) high tocation m

C a$

Q 4.7 mi NE 3

tu x

an

=y Me-54 0.05 LLD 0

O, 'j O

9. m 2

Fc-59 0.8 11D O

m O

O C Co-58 0.05 LID 0

7 3

m~

3

$. C)

Ca60 0.05 LLD 0

O ze45 0.:

LLD 0

o3 3 o 3

Cs-134 0.0S LLD 0

3 e x 3

C>l37 0.06 LLD O

g

'O (D

T30

'l (a) LLD for this nuclide for Fish not seguired by ODCM Naratest Lower 4Jett of Deteestem (1.1E)

Mene end reage based spoe detectable scenerements sely. Frection of detectable asessurements et specified locations isledicated is parentheses (f)

• " Neereuttee reported aseaserements are deGeed la Regulatory Guide 4A (December 1975) sed the Beever Valley Power Staties Specilicetles.

a1ze

?

ENVIRONMENTAL RADIOLOGICAL MONITORINGlROGRAM

SUMMARY

F Namne ot' Facility Beaver Vallev Power Station Unit I and 2 Docket No. 50-334/50-412 T

Location of Facility Beaver. Pennsylvania Reporting Period Annual 1996 h

(Countys State) a 3

Aestysis and Lower IJamit Nember of g

Medium of Pathway Total Number of AllIndicator Imations Imation with Highest Annual, Mesa Centret 14 cations Noorcstine Sampled ofAastpis Detection

• • Mesa (0 Name

" Mesa (f)

" Mesa (O Repe<ted h

a (tfait of Measuressent) Perferened

• (LIM

• • Range Distance and Directions ** Reage

" Range Measuremenes*"

2.

to Wesrton, WV No. 48 Q

5 Externet Radiation Gamma (43) 0.05 0.19 (173/173) 54 ItancockCounty 0.22(4/4) 0.20(4/4) 0 C

s (asR/ day)

(180 quarterty)

(0.13424)

Childreasllome (0.22 4.24)

(0.19 4.20)

?

j t.$ mi SW S,

gu-o

%5 3

N 2

D. C o' m ta e

-o Feed and Forage 1-138 (12) 0.06 LLD One sample One sampic 0

d O_ C (pCi/g) location location O

(1 (dry weight)

" C7 21 m -*

cn omnma (12) 3 b

p W 3 6

De-7 (a) 1.84 (5/12)

One sampic One sample 0

0

.{

(0 63-4.81) location location 3E 3a g

K-40 (a) 14.91 (12/I2)

One sample One sample 0

y (4.0-23.5) locarion location E

m O

Th-228 (a) 0.33 (2/12)

One sample One sample 0

C (0.I3-0.I6) location location u

1 z

O y

Cs 114 0.04 II.D One sample One sample e

3 r-location location E

O Cs137 0.06 ll.D One semple One sample 0

Q locasion location Oa2 (a) LLD for this macitde for Feed and Forage not required by ODCM O

]

Nrelaat 14wer IJmit of Detecome (LI.4 g

Mess and range bened spes detectable messarements sely. Fraction of detectable measurements at spectned locations h ladkated In parentheses (f)

• • • Nourentine reported messeressents are deGeed la Regulatory Guide 4.0 (Denmber 1975) and the Beaver Valley Pswer Station Speci& cation.

m>E Y

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ENVIRONMENTAL RADIOLOGICAL MONITORING PHOGRAM

SUMMARY

rn f

Nasue of Facility Beaver Valley Power Station Unk 1 and 2 Docket No. 50-334/50-412

[

g Locatloa of Facility Beaver. Pennsvivania Reporting Period Annual 1996 y

(County, State) 3 z

C O

Z-4 k

Aestysis sed Lemur Unit Number of f

g Medlem of Pathway 1stsINumber of AllIndirst4r 14 cations 14 cation with liighest Amasal, Mean Centrol f.ecations Nearentlee 3

e O

Sampled of Analysis Detecties

• • Mesa (f)

Name

" Mese (f)

• • Mene (f)

Reported g

y 3

(Unit of Messerement) Performed

• (LLD)

• • Range Distance and Directions ** Range

• • Range Meassremeets* **

2.

O Weirtoa, WV No. 48 f

a o

y Air Particulate Gruss Beta 0 002 16 (520/520)

32. Mu!IanA Pa, 17(52/52) 16 (52/52) 0 C

emiRadmiodme (320)

(6 33) 0.8 sni NW (9 33)

(7-33) m_ g ya M

C y

h (X10-3 pCUCtLM.)

1-131(520) 0.04 LLD 0

2 m

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&m Garnma(40) 0-o$

e

=

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32. Midlan4 Pa.

147(4/4) 133(4/4) 0 1

r-(99-186) 0 & mi NW (108-186)

(101-857) g m6 us r

K-40 (a) 4 (13/40)

St. Ahqwppa, Pa 7(2/4)

S (t/4) 0 m*

(4-10)

O a mi E (4-10) h

'3 Cs-134 0.0003 1.1D 0

03 o 3*

Cs-137 0.0003 11D O

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m m

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t 3

(a)11D for tids nuclide for Air Particulate not requimi by ODCM Nominal Lower Unit of Detecties (LLD)

Mees and range based spaa detectable measurements saly. Fracties of detectable measuremeets at spec 16ed fecations is ladicated la parentbenes (!)

"* Noarentine reperted measuremsets are densed im Engelatory Gelde 4.8 (December 1975) and the Beaver Valley Pewer Station Speciscation.

Duquasna Light Company 1996 Annual Radiological Environmental Report Table 5-3. Pre-operational Environmental Radiological Monitoring Program Summary TABLE 5-3 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 i

1 (County, State)

PRE OPERATIONAL PROGRAM

SUMMARY

(COMBINED 1974 1975)

Medium or Pathway sis W Tel hmW WM M Wim Wm of Analysis Performed of Detection LLD Mean, (f) Range (Unit of a rement)

Sediments Gross Alpha (0) pCl/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 Co-144 0.3 0.5 (3/33) 0.4 - 0.7 Ru-106(b) 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 i

Cs-137 0.1 0.2 (1/8)

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

Ru-106(b) 0.3 0.8 (1/8)

Others

< LLD Feedstuff Gross Beta (80) 0.05 19 (80/80) 8 - 50 pCilg (dry)

Sr-89 (81) 0.025 0.2 (33/81) 0.04 - 0.93 Sr-90 (81) 0.005 0.4 (78/81) 0.02 0.81 Gamma (81)

K 40 1

19 (75/81) 5 - 46 Cs-137 0.1 0.5 (6/81) 0.2-1.6 Ce-144 0.3 1.5 (5/81) 0.9-2.6 Zr/Nb-95 0.05 0.8 (13/81) 0.2 - 1.8 Ru-106(b) 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 Co 144 0.3 1.1 (7/64) 0.2 - 3 Zr/Nb-95 0.05 0.3 (13/64) 0.1 - 2 j

Ru-106(b) 0.3 1.1 (3/64) 0.5 - 2 l

Others

< LLD (f)

Fraction of detectable measurements at specified location.

I Section 5. ENVIRONMENTAL. MONITORING PROGRAM 5-17

Duquesne Light Company 1996 Annual Radiological Environmental Report 1

TABLE 5 3 PRE-OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

4 1

Name of Facility Beaver Vallev Power Station Docket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Level CY 1974 - 1975 4

(County, State)

PRE OPERATIONAL PROGRAM

SUMMARY

(COMBINED 1974 - 1975)

Medium or Pathway Analysis and Total Number Lower Limit All Indicator Locations f Ana e e e rme f etection @

Mean,m Range (Unit of u ement) j Soil Gross Alpha (0) l 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 i

Cs-137 0.1 1.2 (7/8) 0.2 - 2.4 i

Co-60 0.1 0.2 (1/8) i Others LLD f

Surface Water Gross Alpha (40) 0.3 0.75 (5/40) 0.6 - 1.1 pCill 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 j

Sr-89 (0)

Sr-90 (0)

C-14 (0)

Drir,kng Water 1131 (0) pCi/l Gross Alpha (50) 0.3 0.6 (4/50) 0.4-0.8 Gross Beta (208) 0.6 3.8 (208/208) 2.3 6.4 Gamma (0)

Tritium (211) 100 310 (211/211) 130 1000

)

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

Sr-90 (0)

Ground Water Gross Alpha (19) 0.3

< LU) pCill Gross Beta (76) 0.6 2.9 (73/75(a)) 1.3 - 8.0 1

Tritium (81) 100 440 (77/81) 80 - 800 Gamma (1) 10 - 60

< LLD Air Particu ates Gross Alpha (188) 0.001 0.003 (35/188) 0.002 - 0.004 and Gaseous Gross Beta (927) 0.006 0.07 (927/927) 0.02 - 0.32 pCi/m3 Sr-89 (0)

Sr-90 (0) 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 Co-141 0.010 0.02 (3/197) 0.01 - 0.04 Co-144 0.010 0.02 (44/197) 0.01 - 0.04 Others

< LLD (f)

Fraction of detectable measurements at specified location.

l 5-18 Secuon S. ENVIRONMENTAL MONITORING PROGRAM

i Duquesne Light Company 1996 Annual Radiological Environmental Report TABLE 5 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 Number Lower Limit All Indicator Locations

" ' ^ " *

""9' (Unit of a u ement)

Milk l-131 (91) 0.25 0.6 (4/91) 0.3 - 0.8 pCl/l Sr-89 (134) 5 7

(4/134) 6 - 11 Sr-90 (134) 1 5.3 (132/134) 1.5 - 12.8 Gamma (134)

Cs-137 10 13 (19/134) 11 - 16 Others

< LLD External Radiation y - Monthly (599) 0.5 mR*

0.20 (599/599) 0.08 - 0.51 mR/ day y - Quarterly (195) 0.5 mR' O.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) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample).

(b) May include Ru-106, Ru-103, Bo-7.

(f)

Fraction of detectable measurements at specified location.

Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-19

Duquesne Light Company 1996 Annual Radiological Environmental Report i

Table S 4. Typical Detection Sensitivities For Gamma Spectroscopy Detection By High Resolution Germanium TABLE 5-4 TYPICAL DETECTION SENSITIVITIES FOR GAMMA i

SPECTROSCOPY DETECTION BY HIGH RESOLUTION GERMANIUM Air Particulates Vegetation Fish (PCI)

(pCilkg dry)

(PCilg wet)

(p i i 7) pCilg Be-7 50 20 200 0.2 0.02 i

4 K-40 80 50 400 0.4 0.4 M n-54 5

2 20 0.02 0.02 Co-58 5

2 20 0.02 0.02 4

Fe.59 10 3

40 0.04 0.04 Co-60 5

2 20 0.02 0.02 Zn-65 10 5

40 0.04 0.04 l

Zr/Nb-95 5

3 40 0.04 0.04 Ru-103 5

2 30 0.03 ~

0.03 Ru-106 50 20 200 0.2 0.2 1-131 15 4

100 0.1 0.1 1

Cs-134 5

2 20 0.02 0.02 Cs-137 5

2 20 0.02 0.02 Ba/La-140 10 3

200 0.2 0.02 Ce-141 10 3

100 0.1 0.1 Ce-144 40 20 200 0.2 0.2 Ra-226 80 10 100 0.1 0.1 Th-228 10 10 20 0.02 0.02 5-20 Secuon 5. ENVIRONMENTAL MONITORING PROC. RAM

Duquesne Light Company 1996 Annual Radiological Environmental Report l

i 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.adiciodine and radioactive particulates at each of ten (10) offsite air sampling stations. The locations of these stations are listed in Table 5-1 and shown on a map in Figure 5-1.

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

l 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" planchet and counting it in a low background, gas flow proportional counter.

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

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

The activity is referenced to the mid-collection time.

a Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-21

_m

.~

Duquesne Light Company 1996 Annual Radiological Environmental Report 1

Figure 5-1. Air Sampling Stations N

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5-22 Section 5. ENVIRONMENTAL MONITORING PROGRAM

l Duquesne Light Comp::ny 1996 Annual Radiological Environmental Report

)

i i

3.

Results and Conclusions A summary of data is presented in Table 5-2.

a. Airborne Radioactive Particulates A total of five hundred twenty (520) weekly samples from ten (10) locations l

were analyzed for gross beta. Results were comparable to previous years.

[

Figure 5-2 illustrates the average concentration of gross beta in air particulates.

Week 35 indicated a weekly average that was higher than the other weeks.

Even through the average for week 35 was higher, weekly averages in previous years have been as high or higher. It was noted that the control i

station, Weirton, WV, was the highest of all the stations that week. This station is considered to be outside the influence of plant operations and indicates that the increase for that week was from natural causes (radon).

Also, all air particulate samples are required to be counted by gamma spectroscopy if any gross beta result is greater than ten times the yearly control location average (10 x 0.0164 pCl/m = 0.164 pCl/m'). For week 8

35, none of the samples exceeded 0.033 pCi/m' and were not required to be counted for gamma spectroscopy because their gross beta results were not high enough to meet the gamma spectroscopy counting requirement.

The weekly air particulate samples were composited to forty (40) quarterly samples which were analyzed by gamma spectrometry.

Naturally ccct:rring Be-7 was present in all samples. Naturally occurring K-40 was detected in thirteen (13) of the forty (40) monthly samples. Results are listed in the summary Table 5-2.

Based on the analytical results, the operation of Beaver Valley Power Station did not contribute any' measurable increase in air particulate radioactivity during 1996.

b.

Radiolodine A total of five hundred twenty (520) weekly charcoal filter samples were analyzed for 1-131.

No detectable concentrations were present at any locations.

Based on analytical results, the operation of Beave.- Valley Power Station did not contribute any measurable increase in airborne radiciodine during 1996.

c.

Deviations from required sampling / analysis schedule ODCM reauired sites:

Site 32, Midland PA (SS) air sampling station was inoperable from 3-3-96 0621 to 3-5-961207 due to a loose wire to vacuum pump. The loose wire was repaired and station was returned to service.

Site 46.1, Industry PA air sampling station was inoperable from 3-5-96 0345 to 3-6-961537 due to a burned wire at the vacuum pump. The burned wire was replaced and station was returned to service.

section 5. ENVIRONMENTAL MONITORING PROGRAM 5-23 j

Duquesne Light Company 1996 Annual Radiological Environmental Report Site 46.1, industry PA air sampling station was inoperable from 3-13-96 0414 to 3-14-961113 due to a shorted wire at the vacuum pump.

The vacuum pump was replaced and station was returned to service.

Site 13, Meyers Farm air sampling station was inoperable from 7-17-96 0440 to 7-18-96 0955 due to blown fuse. The blown fuse was replaced and station was returned to service.

Site 30, Shippingport PA air sampling station was inoperable from 11-11-96 1545 to 11-14-961213 due to vacuum pump failure. The vacuum pump was repaired and E.tation was returned to service.

Non ODCM reouired sites:

Site 28, Shermans Farm air sampling station was inoperable from 5-18-96 1434 to 5-20-961618 due to short circuit in timer box. The timer box replaced and station was returned to service.

Site 298, Beaver County Hotgual particulate air samp.le for the week 8-26-96 to 9-3-96 was not collected or analyzed. Sample appeared to have been eaten by a rodent or insects. No other cases of this nature occurred in 1996.

l 1

5 24 section 5. ENVIRONMENTAL MONITORING PROGRAM

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Duquesna Light Company 1996 Annual Radiological Environmontal Report C.

Monitoring of Sedin'. ants and Soils (Soli Monitoring is required every 3 years and is required in 1997)

I 1.

Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt. Soil samples may vary 2

from sand and silt to a heavy clay with variable amounts of organic material.

l 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 4

above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also ilsted in Table 5-1 and are shown in Figure 5-3.

Bottom sediments are analyzed for gamma-emitting radionuclides.

b.

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

4 8

l 1

5-26 section 5. EdVIRONMENTAL MONITORING PROGRAM

1 Duquesne Light Company 1996 Annual Radiological Environmental Report Figure 5-3. Environmental Monitoring locations - Shoreline Sediments and Soil l

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i Section S. ENVIRCNMENTAL MONITORING PROGRAM 5-27

q 1

Duquesne Light Company 1996 Annual Radiological Environmental Report 3.

Results and Conclusions I

A summary of sediment analysis is presented in Table 5-2.

j a.

Sediment A total of six (6) cample were analyzed by gamma spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was found in every sample. Be-7 was found in six samples. Small amounts of Cs-137 from previous nuclear weapons test were found in all six river sediment samples including two upstream above Montgomery Dam, which are 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 j

activity found 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 j

monitoring pregram is sufGelently sensitive.

i 1

4 a

5 28 Section S. ENVIRONMENTAL MONITORING PROGRAM

1 Duquesne Light Company 1996 Annual Rcdlological Environmenta! Report j

u D.

Monitoring of Feederops and Foodcrops 1

1.

Characterization of Vegetation and Foodcrops I

l According to the 1996 st:atistical summary of the Pennsylvania Department of Agriculture, there were approximately 575 farms in Beaver County. The total i

value of farm crops and livestock was $16,793,000. The principal source of revenue was in dairy products which were erstimated at $6,849,0C0. Revenues from other farm products were estimated as follows:

1 Field Crops

$1,794,000 Fruits

$239,000 l

Horticulture and Mushrooms

$3,859,000 i

Meat and Animal Products

$3,442,000 Vegetables and Potatoes

$497,000 Poultry Products

$113,000 The total land in Beaver County is 279,020 acres. Approximately 147,900 acres are forested land and 57,960 acres are pasture and crop land.

2.

Sampling Program and Analytical Techniques a.

Program Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 5-4.

Each sample is analyzed by gamma spectrometry.

A land use census was performed July / August 1996 to locate the nearest residence and nearest garden of greater than 500 square feet producing fresh leafy vegetables within a five (5) mile radius of the site.

See

{

Table 5-5 for results.

Foodcrops (vegetables) were collected at garden locations during the summer of 1996. Leafy vegetables, i.e., cabbage, were obtained from Shippingport, Georgetown, and Industry, PA, and Weirton, WV.

All samples were analyzed for gamma emitters (including 1-131 by gamma

]

spectroscopy).

i section 5. ENVIRONMENTAL MONITORING PROGRAM 5 29

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Duquesne Light Company 1996 Annual Radiological Environmental Report Table 5-5. Closest Residence and Garden in Each Sector l

TABLE 5-5 Closest Residence and Garden in Each Sector Sector Closest Residence

• Closest Garden

• l 1

1.55 mi N 1.76 mi N 2

1.59 mi NNE 1.61 mi NNE 3

0.42 mi NE 2.65 mi NE 4

0.38 mi ENE 0.98 mi ENE 5

0.42 mi E 2.00 mi E 6

0.87 mi ESE 1.63 mi ESE 7

1.10 mi SE 1.78 ml SE 8

1.10 mi SSE 2.16 mi SSE 9

1.40 mi S 2.31 mi S 10 0.80 mi SSW 1.55 mi SSW 11 1,67 mi SW 1.67 mi SW 12 1.46 mi WSW 1.55 mi WSW 13 2.27 mi W 2.27 ml W 14 2.84 mi WNW 3.18 mi WNW 15 0.91 mi NW 0.92 mi NW 16 0.91 mi NNW 1.36 mi NNW

" Direction and Distance from Midpoint between Reactors l

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l Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-31

Duquesne Light Company 1996 Annual R:diological Environmental Report 1

b.

Procedures Gamma emitters are determined by scanning a dried, homogenized sample with the gamma spectroscopy system.

A high resolution germanium detector is utilized with this system.

Radiolodine (1-131) is determined by radiochemistry. Stable lodide 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 lodide 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 S-2.

a.

Feed A total of twelve (12) samples were analyzed by gamma spectroscopy.

Naturally occurring K-40 was present in all samples and Th-228 was present in two (2) samples. Be-7 was detected in five (5) samples, b.

Food A total of four (4) samples were analyzed for I-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.

i

.O 5-32 secuon 5. ENVIRONMENTAL MONITORING PROGRAM

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Duquesne Light Company 1996 Annual Radiological Ervironmental Report i

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Monitoring of Local Cows Milk 4

1.

Description - Milch Animal Locations Samples of fresh milk are obtained frorn milch animals at locations and frequencies noted in Table 5-1. This milk is analyzed for its radiciodine content calculated as lodine-131. The analyses are performed within eight (8) days of sampling.

Detailed field surveys are performed during the grazing season to locate and enumerate milch animals within a five (5) mile radius of the site. Goat herd locations out to fifteen (15) miles are identified. Survey data for the most recent survey conducted in is shown in Figure 5-5.

l 2.

Sampling Program and Analytical Techniques a.

Program Milk was collected from these (2) reference dairy farms (Searight's and l

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 dairles, which represent the highest potential milk pathway for radiolodine 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 i

locations are more appropriate.

The location of each is shown in i

Figure 5-6 and described below.

4 Direction and Distance from Collection Midpoint between Reactors Period i

25 Searight 47 Cows 2.16 miles SSW Jan. - Dec.

27 Brunton 93 Cows 7.3 miles SE Jan. - Dec.

t' 96 Windsheimer 58 Cows 10.3 miles SSW Jan. - Dec.

109*

Soissen 30 Cows 3.83 miles WSW Jan. - Dec.

105*

Ambrose 25 Cows 3.86 miles WSW Jan. - Dec.

106*

Conkle 32 Cows 3.75 miles WSW Jan. - Dec.

Highest potential pathway dairies.

i Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-33

Duquesne Light Company 1996 Annual Radiological Environmental Report Figure 5-5. Beaver Valley Power Station Milch Animal Census i

BEAVER VALLEY POWER STATION MILCH ANIMAL CENSUS 1

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5-34 Section 5. ENV!F C)NMENTAL MONITORING PROGRAM

Duquesne Light Company J

1996 Annual Radiological Environmental Report i

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Duquesne Light Company 1996 Annu:1 Redlological Environmental Report The sample from Searight Dairy is collected and analyzed weekly for radiciodine using a procedure with a high sensitivity. Samples from each of the other selected dairies are collected monthly when cows are indoors, and bi-weekly when cows are grazing. This monthly or bi-weekly sample is analyzed for Sr-89, Sr-90, gamma emitters including Cs-137 (by high resolution germanium gamma spectroscopy) and 1-131 (high sensitivity analysis).

b.

Procedure Radiolodine (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 one 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

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precipitating phosphates.

Strontium is purified in all samples by the Argonne method using three grams of extraction material in a chromatographic column. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for the ingrowth of Y-90.

Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCOs from the sample after yttrium separation.

This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm' aluminum absorber for low level beta counting.

Chemical yields of strontium and yttrium are determined gravimetrically.

3.

Results and Conclusions A summary of data is presented in Table 5-2.

A total of one hundred forty-eight (148) samples were analyzed for I-131 during 1996. All 1-131 activities in milk were below the minimum detectable level.

A total of one hundred fifteen (115) samples were analyzed for Sr-89 and Sr-90.

No Sr-89 was detected. Sr-90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the normally expected range.

A total of one hundred fifteen (115) sa'mples were analyzed by gamma spectroscopy. Naturally occurring K-40 was present in all samples. No other nuclides were identified.

All results were consistent with (or lower than) those obtained in the preoperational program. Based on the analytical resultF, the operation of the Beaver Valley Pewer Station did not contribute any measurable increase in radioactivity in the milk in the vicinity of the site.

5-36 Secuen 5. ENVIRONMENTAL MONITORING PROGRAM

Duquesne Light Company 1996 Annual Radiological Environmenial 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.

1 The principal geologic feature

• of the region are nearly flat-laying sedimentary i

beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and 4

shale,ith abundant interbedded coal layers.

Pleistocene glacial deposits parti y cover the older sedimentary deposits in the northwest. Most of the re. ;, - 1 is underlain by shale, sandstone, and some coal beds of the Conemaugh l

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 R/hr. Results for 1996 indicated that background radiation continued i

in this range.

2 3

2.

Locations and Analytical Procedures i

Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs).

l in 1996 there were a total of forty-four (44) off-site environmental TLD locations.

j i

The locations of the TLDs are shown in Figure 5-7 through Figure 5-10. Thirteen j

(13) locations also have QC Laboratory TLDs. Both laboratories use calcium sulfate dysprosium, (CaSO :Dy) in Teflon raatrix.

4 2

The calcium sulfate dysprosium (C4SO :Dy) TLDs were annealed at the 4

Contractor Central Laboratory shortly before placing the TLDs in their field i

locations.

The radiation dose accumulated in-transit between the Central j

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 j

holder.

The dosimetry system was calibrated by reading calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation field.

Section S. ENVIRONMENTAL MONITORING PROGRAM 5-37

Duquesne Light Company 1996 Annual Radiological Environmental Report 3.

Results and Conclusions Data obtained with the contractor TLD (CaSO(:Cy in Teflon) during 1996 are summarized in Table 5-2, and the quality contml TLD results are listed in Table 3-1.

The annual exposure rate of all offsite TLDs averaged 0.185 mR/ day in 1996. AL in previous years, there was some variation among locations and seasons as would be expected.

Three TLDs were lost in the field during the year at Station 71. The TLD at this station was moved to a less conspicuous location to prevent theft.

In 1996, lonizing radiation dose determinations from TLDs averaged approximately 67.7 mR for the year. This is comparable to previous years.. There was no evidence of anomalies that could be attributed to the operation of the Beaver Valley Power Station. The TLDs confirm that changes from natural radiation levels, if any, are negligible.

e 3

5-38 Section 5. ENVIRONMENTAL MONITORING PROGRAM -

l Duquesne Light Company 1996 Annual Radiological Environmental Report Figure S-7. TLD Locations Northwest Quadrant l

FIGURE 5 7 - TLD LOCATIONS I

NORTHWEST QUADRANT BEAVER VALLEY POWER STATION I

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SectorLe t.ocatton l 1 70 Western Beaver t' i 28 Sherman's Farm 13 86 East uverpool 13 60 Haney's Farm 14 15 Georgetown 14 87 Calcutta 14 47 E. Uverpool Water Co. 15 32 Midland S.S. 15 88 Midlanc Heignts i 15 89 Ohiovi;le i 16 90 Fairview School 16 93 Sunset Hills Midland a s ? Section 5. ENVIRONMENTAL MONITORING PROGRAM S.39 4

Duquesne Light Company 1996 Annual Radiological Environmental Report i Figure 5-8. TLD Locations - Northeast Quadrant FIGURE 5 TLD LOCATIONS NORTHEAST QUADRANT i ..s,,,,,.__ BEAVER VALLEY POWER STATION ~* i \\, i i b / -'/ \\~ f ) N' ( ~- / t j r .,. ~. f 3 g ) *, / 't.. s....... x [ \\., ~ ~ ~ ' p D \\ l I ~ ,j l.. 'l \\, :, / '\\ ..v e g, g q. . 'x l / .;f a t H i (, '/ e ...f. ; y \\ ~ s. p g s /* < .i ( S', g3 i_ ,X-

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Duquesne Light Company 1996 Annual Radiological Environmental Report l .i Figure 5-9. TLD Locations - Southeast Quadrant 3 .N. N. /,,5 . Q* - } a <<o 4 ,\\ g ,[ , r '....,, 4 .i i [, N. / g ,J. 4 t, --J 4 j s s '- ,gg ---N U d ,\\ i i 4 A 1-i.

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/'s J a 1 ,M~Q * \\, z 7-K ... f...e '... ?' \\ s s. i 3 z f a FIGURE 5 TLD LOCATIONS s-SOUTHEASE QUADRANT '~~~6-~... 34 BEAVER VALLEY POWER STATION i Sector Site,, Location 5 51 Allquippa 5 75 Holt Road i 1 S 45 Mt. Pleasant Church 6 45.1 Raccoon Twp. 6 76 fraccoon Twp. School i 6 77 Green Garden Road 7 59 Iron's Farm i 7 78 Raccoon Municipal Bldg. 7 27 Brunton's Dairy 8 94 McCleary Road i 8 79 Rt.18 and Rt.151 9 80 Raccoon Park 9 81 Southside School 9 82 Hanover Municipal Bldg. ) 1 Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-41 1

Duquesne Light Company 1996 Annual Radiological Environmental Report i Figure 5-10. TLD Locations - Southwest Quadrant j l l '[ / \\ '%. ,. -m[ ' / .t-K* a g [ j s% ' s, ~ %..... Wk ~ '~ j "*"",~~l . h. _ p ' ~ ~.. N i,..... s s., g "f s s W ~j%..$.x ! b. /,, 'y e ~?p \\ ~~~ lF ' l ,1 ! t \\,/@,, ls ;.N. s / 1 . -,( G],,,,.. 1 .. 4 N ( d s \\ t. s x , N. ,/ } J-g ,b { \\ ^ a .s ') Y i) ~ \\ 'k ..,,, ai /' 4 &........ & :=. & -.lb ~ \\ ) / ....// r g tT j&.- l s ~ i m ( l '/ / i....... A II/ / \\ \\\\ .i / ,1 'w-y\\ \\1 ll Il L f +l : 8 ..... p' r y, y y

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\\ FIGURE 5 TLD LOCATIONS Qw-<w ~ F ~- ~ ~... - SOUTHWEST QUADRANT ~~ a BEAVER VALLEY POWER STATION Sector Sg Location 9 80 Raccoon Park 9 81 Southside School 9 82 Hanover Municipal Bldg. 10 48 Weltton Water Company 10 83 Mill Creek Road 10 95 McCleary Road 11 13 Meyer's Farm 11 14 Hookstown 11 84 Hancock Children's Home 12 92 Georgetowr Road 12 85 Rt. 8 and Rt. 30 13 86 E. Uverpool 13 60 Haney's Farm 542 Section S. ENVIRONMENTAL MONITORING PROGRAM

Duquesne Light Company 1996 Annual Radiological Environmental Report G. Monitoring of Fish 1. Descriptiori During 1996, fish collected for the radiological monitoring program included caip 4 and catfish, i 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 5-11. 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 reaolution germanium detector. 3. Results and Conclusions A summary of the results of the fish monitoring data is provided in Table 5-2. A total of eight (8) samples were analyzed by gamma spectroscopy. Naturally occurring K-40 was found in all samples. No other gamma emitting radionuclides were detected. Based on the analytical results, the operation of the Beaver Valley Power Station did not contribute any measurable increase in radioactivity in the Ohio River fish population. 1 Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-43

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Duquesne Light Company 1996 Annual Radiological Env!ronmental Report j H. Monitoring of Surfaca, Drinking, Well 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 i 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 municipalitics and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipel 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 Midiand, as well as others downstream use river water for cooling purposes. Groundwater occurs in large volumes in the gravel terraces which lie along the i river, and diminishes considerably Ir 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 record mean annual precipitation for the area is 36.43 inches based on 1965 to 1994 data collected at the Pittsburgh International Airport. Section 5. ENVIRONMENTAL McMTORING PROGRAM 5-45

Duquesne Light Company j 1996 Annual Radiological Environmental 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 Mlle 41.2] daily and composited into a weekly sample. Two automatic river water samplers are at the following locations: Upstream of Montgomery Dam [ River Mile 29.6]; and at J&L Steel's river water intake [ River Mlle 36.2]. The automatic sampler takes a 20-40 mi sample every 15 minutes and samples are collected on a weekly basis. The weekly grab sample and automatic water sample are composited into monthly samples from each location. in addition, a quarterly composite sample is prepared for each sample point. The weekly composites from the automatic river water sampler upstream at Montgomery Dam are analyzed for 1-131. The monthly composites are analyzed for gamma emitters. The quarterly composites are analyzed for H-3, Sr-89 and Sr-90. Locations of each sample point are shown in Figure 5-12. b. Drinking Water (Public Supplies) Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Water Treating Plants. An automatic sampler at each location collects 20-40 mi every 20 minutes. These intermittent samples are then composited into a weekly sample. The weekly sample from each location is analyzed for I-131. Monthly composites of the weekly samples are analyzed by gamma spectrometry. Quarterly composites are analyzed for H-3, Sr-89, anu Sr-90. Locations of each sample point are shown in Figure 5-12. 5-46 secdon 5. ENVIRONMENTAL MONITORING PROGRAM

= Duquusne Light Company 1996 Annual Radiological Environmental Report c. Groundwater Semi-annual grab samples were collected from three (3) of four (4) well locations (see Figure.5-12) 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 Meyer's Farm was abandoned this year and groundwater samples could - not be obtained. This site will be rernoved from the program in 1997. 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, WV. Precipitation, when available, is collected each week and then composited into quarterly samples. The quarterly composites are i analyzed for H-3 and gamma emitters. Locations of each sample point are shown in Figure 5-12. t

Duquesne Light Company 1996 Annual Radiological Environmental Report i Figure 5-12. Environrnental Monitoring Stations Locations - Wells, Surface Water, Drinking Water and Precipitation \\,9 ) g </ j s % *.= * ~ %, M - r 6 s 9-4 5 B1 x 7 I \\ e e a 6 %9 { N. e i ci l I-b } b o s e s %sW'm 1 88 2 O O 9 t Z k b / E $c / r a g 3 h "a 3 n$. 5i = i s =e / / Sd h3 r- ' -( ,/ "d 5 -! Q<3 53 l V 1 3 4' I 2 J t d /(v i 9O L 4% e( 1 a im 3 1 M t: 91 !1 ~ jeg i g ll,p D ' 3ie i y }'ila}a!Iabl s ;- e j oJ t. i 2 L3,. 03: DI i'._. j 8 0\\'. $,E la!! !! li ! O -Q l l S-48 Section S. ENVIRONMENTAL MONITORING PROGRAM

Duquesne Light Company 1996 Annual Radiological Environmental Report 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. Strontium-89 and 90 are determined on quarterly composites of the water samples. Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation (other sample volumes may be used). Strontium is separated by precipitating Sr(NOs): using nitric acid. A barium scavenge is performed to remove radium and other natural nuclides. Final purification of strontium is accomplished by precipitating SrSO4 An iron scavenge is performed, followed by addition of stable yttrium carrier and a minimum 5-day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as 4 oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCOs from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm aluminum absorber for low level beta counting. 8 Tritium is determined in water samples by liquid scintillation counting. Radiolodine (1-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system. 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 5-2. These are discussed below,

a. Surface Water A total of twelve (12) samples were analyzed quarterly for H-3, Sr-89 and Sr-90. No H-3, Sr-89, or Sr-90 was detected in these samples. In addition, for the first quarter of the year, nine (9) additional monthly composite samples were analyzed for H-3. One of the nine was positive for H-3, just slightly above detectable levels and was located upstream of the plant (NOVA Chemical) and could not be attributed to plant releases.

A total of thirty-six (36) samples were analyzed by gamma spectrometry. No gamma emitting radlonuclides were detected. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-49

Duquesne Light Company 1996 Annual Radiological Environmental Report A total of fifty-two (52) samples were analyzed for 1-131 using a highly sensitive technique. Trace levels of I-131 were measured in seven (7) of the weekly samples. The results were slightly above the minimum detectable activity. The positive results were detected at a control location above the BVPS discharge and could not be attributed to plant releases, b. Drinking Water A total of eight (8) samples were analyzed for H-3, Sr-89 and Sr-90. No H-3, Sr-89, or Sr-90 was detected. A total of twenty-four (24) samples were analyzed by gamma spectrometry. No gamma emitting radionuclides were detected. A total of one hundred four (104) samples were analyzed for 1-131 using a highly sensitive technique. Positive levels of I-131 were measured in thirty-nine (39) of the weekly samples. All the positive results except two were below the required LLD The two above LLD were below reportable levels and could not be attributed to plant releases. The positive results were detected at both the Midland and East Liverpool plants. As noted under Surface Water above,1-131 has been observed upstream of the site. c. Groundwater A total of six (6) samples were each analyzed for H-3 and by gamma spectrometry. No samples were obtained at Meyer Farm because the farm was abandoned for the entire year. No H-3 or gamma emitting radionuclides were detected. d. Precipitation A total of twelve (12) samples were analyzed for H-3 and by gamma spectrometry. Two (2) positive tritium results detected were within normal levels. Naturally occurring Be-7 was detected in five (5) samples. l l i t 5-50 section 5. ENVIRONMENTAL MONITORING PROGRAM

Duquesne Light Company 1996 Annual Radiological Environmental Report

e. Summary The data from water analyses demonstrates that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in local river, drinking, well waters or precipitation. The few positive results which could be attributable to authorized releases from the Beaver Valley Power Station are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environments! monitoring program is sufficiently sensitive.

Further, the actual detected concentration (averaged over the total batch discharge period during the year) attributable to Beaver Valley Power Station, was only 0.428% of the limits set forth in Appendix C of the ODCM i for water discharged to the Ohio River. The Ohio River further reduced this concentration by a factor of ~ 600 prior to its potential use by { members of the public. f. Deviations from ODCM required sampling schedule Site 49.1, NOVA Chemical surface water automatic sampler was out of service from 1-20-97 2027 to 1-26-96 1402 due to flooding of NOVA Chemical pump house basement caused by flooding of Ohio River and river pump maintenance being performed by NOVA Chemical personnel. Site 2.1, Downstream J&L surface water automatic sampler was found with sampling hose not in collection vessel during the week of 5-21-96, only 1.5 gallons were collected instead of normal 2 gallons. The hose was replaced after sample collection. Site 2.1, Downstream J&L surface water automatic sampler had a valve open on collection bottle between 6-18-961027 to 6-21-971430. The valve was closed and no further incidents occurred in 1996, section 5. ENVIRONMENTAL MONITORING PROGRAM S-51

4 Duquesne Light Company 1996 Annual Radiological Environmental Report l. Estimates of Radiation Dose to Man j 1. Pathways to Man - Calculational Models i 3 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 in accordance l with the schedule set forth in Appendix A of the BVPS license, were used as the radionuclide activity input. Each radionuclide contained in the Annual Radioactive Effluent Release Report (noble gases, particulates, radioicdines and tritium) were included as source j 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 l ODCM. All gaseous. effluent releases, including Anxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. Meteorological data collected by the Beaver Valley Power Station 6 Meteorology System was used as input to code equivalent to XOQDOQ2 which in turn provided input for the GASPAR equivalent. Except when more recent or specific data was available, all inputs were the same as used in the Beaver Valley Power Station Environmental Statements or in Regulatory Guide 1.109. l The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the " cow-milk-child", and other ingestion pathways. [ All potentially radioactive liquid effluents, including steam generator blowdown, aie released by batch mode after analysis by gamma spectrometry using i intrinsic Germanium detectors. Each batch is diluted by cooling tower b'owdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mlle 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 Environ.1 ental Statement or Regulatory Guide 1.109. Pathways, which were evaluated, are drinking water, fish consumption, and shoreline recreation. 5-52 Secuon 5. ENVIRONMENTAL MONITORING PROGRAM

Duquesn3 Light Company 1996 Annual RadiologicIl Environmental Report I 2. Results of Calculated Radiation Dose to Man - Liquid Releases . a. Ind!vidual Dose The doses which are calculated by the model described above are to the likelv most exposed real individual located at Midland since this is the nearest location where significcnt exposure of a member of the publ!c could potentially occur. A breakdown of doses by pathway and organ is provided in Table 5-6 for the maximum individual. Included in this table is a breakdown of a typical dose to individuals from natural radiation exposure. The results of calculated radiation dose to the likely most exposed real individual are cornpared to BVPS annual limits in Table 5-7.

b. Upon implementation of the Unit 2 Technical Specifications and inception of the liquid discharge procedures at Unit 2 on July 24,1987, the discharge limits were clarified to be reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1.

Therefore, the annual site limits listed in Table 5-8 are specific to this report on!y, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2). I c. Population Dose 4 The 1996 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was: Organ Man-Millirems Largest isotope Contributor TOTAL BODY 500.5 H-3 492 mrem THYROID 552.7 H-3 492 mrem 3. Results of Calculated Radiation Dose to Man - Atmospheric Releases The results of calculated radiation dose te, the maximum exposed individuals for BVPS airborne radioactive effluents during 1996 are provided in Table 5-8. The doses include the contribution of all pathways. A 50-mile population dose is also calculated and provided in Table 5-0. H-3 is the primary radionuclide contributions to these doses. The results are compared to the BVPS ennual limits in Table 5-8. As in the liquid discharge limits, the gasecus effluent limits are reactor specific; i.e., Unit 1 and Unit 2 have reactor specific dose limits that are equal to the limits in 10 CFR Part 50, Appendix 1. Therefore, the annual limits listed in Table S-8 are specific to this report only, and were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2). The results show compliance with the BVPS annual limits. Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-53

Y E TABLE 5-6 I g Radiation Dose to Highest Individual *, mromlyr - Liquid Releases * ~ g er i m FAT!!?!AY SKIN THYROID BONE j ORGAN BODY b 0.00172 0.000366 0.00133 0.00124 Fish Consumption N/A TM NM ply AW %N k z gr { 02853 O M 962 O M 88 Drinking Water N/A c (infant) (Thyroid) (Infant) (Child) (Child) o o O o Shoreline Activities (Teen) (Teen) (Skin) (Teen) (Teen) (Teen) o m i Lr 0.000107 0.00853 0.00853 0.00144 0.00726 k EO (Teen) (Infant) (Thyroid) (infant) (Child) (Child) N TYPICAL DOSE TO INDIVIDUALS FROM NATL >RAL RADIATION EXPOSUREc k -h c c BL oC Ambient Gamma Radiation 58 'g Eo

i; m~

Radiont ! ides in Body 40 1 $.9 4 a o b E Global Fallout <1 g E od is a Radon 198 si x 1 .iii

D TOTAL mrem 296 j

e O a Located at Midland Drinking Water intake 3 b Total liquid releases are from Site (combined Units 1 and 2) c National Academy of Sciences. "The Effects on Populations of Exposure to Low Levels of lonizing Radiation", BEIR Report, 1990 +

l Duquesne Light Company 1996 Annual Radiological Environmental Report Table 5-7. Results of Calculated Radiation Dose to Man Liquid Releases i 1 l TABLE 5-7 Results of Calculated Radiation Dose to Man - Liquid Releases 8 ** '"

• E #*

Organ L mi s Annual mrem Limit TOTAL BODY l Adult 0.00634 6.0 0.106 Teen 0.00442 6.0 0.074 i Child 0.00726 6.0 0.121 1 Infant 0.00676 6.0 0.113 ANY ORGAN Adult 0.00682 (Liver) 20.0 0.034 Teen 0.00542 (Liver) 20.0 0.027 Child 0.00846 (Liver) 20.0 0.042 Infant 0.00853 (Thyroid) 20.0 0.043 (a) Located at Midland Drinking Water intake Maximum Total Body Dose - Caosule Summary 1 mrem 1996 Calculated 0.00726 Unit 2 Updated Final Safety Analysis Report 3.5 Hiahest Oroan Dose 1996 Calculated 0.00853 Unit 2 Updated Final Safety Analysis Report 4.7 secuon 5. ENVIRONMENTAL MONITORING PROGPAM 5-55

.. _ _, ~.. _ 4 i Duquesne Light Company } 1996 Annual Radiological Environmental Report i d 4 4. Conclusions Based upon the estimated dose to individuals from the natural background e radiation exposure in Table 5-6, the incremental increase in total body doce to i the 50-mile population S million people), from the operation of Beaver Valley Power Station - Unit 1 and 2, is less than 0.00015% of the annual background. The calculated doses to the public from the operation of Beaver Valley Power Station - Unit 1 and 2, are below BVPS annual limits and resulted in only a small }- Incremental dose to that which area residents already received as a result of j natural background. The doses constituted no meaningful risk to the public. 1 l 1 4 e I I 5-56 Section 5. ErM3oNMENTAL MONITORING PROGRAM

\\ 1 Duquusna Light Company 1996 Annual Radiological Environmental Report Table 5-8. Results of Ca:culated Radiation Dose to Man - Atmospheric Releases TABLE 5-8 4 Results of Calculated Radiation Dose to Man - Atmospheric Releases MAXIMUM BVPS OF PONTION ORGAN ANNUAL LIMIT INDIVIDUAL ANNUAL LIMIT DOSE mrem man rem TOTAL BODY 0.379 30 1.26 1.23 SKIN 0.300 30 1.27 0.44 LUNG 0.380 30 1.27 1.36 THYROID 0.620 30 2.07 1.48 i i I I l Section 5. ENVIRONMENTAL MONITORING PROGRAM 5-57

Duquesna Light Company 1996 Annual Radiological Environmental Report Section 6. INTERLABORATORY COMPARISON PROGRAM A. Contractor Lab - Interfaboratory Comparison Program The US EPA Interlaboratory Comparison Program was modified at the end of 1995. In 1996 the EPA only provided water spiked samples to Teledyne Brown Engineering for analysis. Duquesne Light Company contracted with two vendors to supply Teledyne Brown Eng. with high quality spiked samples te fulfill the requirement of the Offsite Dose Calculation Manual (ODCM) Appendix C, Control 3.12.3. The results of these spiked samples are located in Tables 3-6, 3-9, and 3-10. These results showed good comparisons with the spiked values and all were within the criteria established in Section 3-B. The Contractor Lab (Teledyne Brown Engineering Environmental Services) participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, they participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. Table 6-1 contains the results for 1995 that were not available for publication in the 1995 report. Table 6-2 contains the available results for 1996. Table 6-3 contains trending graphs of results back to 1981. The footnotes on the tables discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence. B. Quality Control Lab - Interlaboratory Comparison Program The Quality Control Lab (Teladyne Midwest Laboratory) participates in the US EPA Interlaboratory Comparison Program. Table 6-4 contains the results for 1995 that were not available for publication in the 1995 report. Table 6-5 contains the results of the available data for 1996. section 6. INTERLABORATORY COMPARISON PROGRAM 6-1

Duque.sne Light Company 1996 Annual Radiological Environmental Report Table 6-1. Contractor - EPA Interlaboratory Comparison Program 1995 EPA INTERLABORATORY COMPAPJSON PROGRAM 1995 Environmental Collection Teledyne Brown Data Media Nuclide EPA Results(a) Engineering Result (b) Deviation (c) 11/03/95 Water Co60 60.0 5.0 58.00 0.58 -0.69 Zn-65 125.0 1 13.0 131.33 19.14 0.84 C5134 40.0 1 5.0 36.33 2.08 -1.27 Cs-137 49.0 i 5.0 50.33 4.62 0.46 Ba-133 99.0 ! 10.0 91.33 3.06 -1.33 1 Footnotes: (a) EPA Results-Expected laboratory prectsion (1 sigma). Units are pCi/ liter for water. (b) Teledyne Results - Average 1 one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters. (c) Statistical promulgation based on EPA-600/4-81-004. 62 secuon 8. INTERLABORATORY COMPARISON PROGRAM

i Duquesne Light Company 1996 Annual Radiological Environmental Report Table 6-2. Contractor - EPA Interlaboratory Cornparison Program 1996 l 1 EPA INTERLABORATORY COMPARISON PROGRAM 1996 Environmental j Collection Tcledyne Drown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviatiorde) 01/23/96 Water Sr-89 73.0 1 5.0 73.67 3.21 0.23 Sr-90 5.0 5.0 5.00 0.00 0.00 01/26/96 Water Gr-Alpha 12.1 5.0 19.00 1 1.00 2.39 (d) Gr Beta 7.0 5.0 7.13 0.21 0.05 i 02/02/96 Water 1131 67.0 i 7.0 71.67 3.06 1.15 03/08/96 Water H3 22002.0 1 2200.0 22000.00 0.00 0.00 04/16/96 Water Gr-Beta 166.9 i 25.0 160.00 0.00 -0.48 St-89 43.0 1 5.0 41.33 2.31 -0.58 Sr-90 16.0 1 5.0 15.33 i 0.58 -0.23 Co-60 31.0 1 5.0 31.67 i 1.15 0.23 Cs-134 46.0i 5.0 42.33 1.53 -1.27 Cs 137 50.0 i 5.0 52.33 1.53 0.81 Gr-Alpha 74.8 1 18.7 63.67 2.89 -1.03 Ra 226 3.0 1 0.5 3.40 i 0.00 1.39 i Ra 228 5.0 i 1.3 3.63 0.61 1.82 06/07/96 Water Co-60 99.0 i 5.0 99.00 i 1.73 0.00 Zn-65 300.0 30.0 309.33 2.08 0.54 ) Cs-134 79.0 1 5.0 69.67 i 1.53 3.23 (e) Cs-137 197.0 i 10.0 202.00 i 2.65 0.87 Ba 133 745.0 i 75.0 711.00 71.42 -0.79 06/21/96 Water Ra-226 4.9 1 0.7 5.50 i 0.26 1.48 Ra 228 9.0 1 2.3 9.73 1 0.46 0.55 07/12/96 Water Sr89 25.0 5.0 22.67 1.53 -0.81 St-90 12.0 1 5.0 12.33 i 1.15 0.12 07/19/96 Water Gr-Alpha 24.4 1 6.1 22.67 0.58 -0.49 Gr Beta 44.8 i 5.0 45.33 1 2.08 0.18 08/09/96 Water H3 10879.0 t 1088.0 9800.00 1 346.41 -1.72 10/02/96 Water 1-131 27.0 6.0 26.33 2.31 -0.19 Section 6. INTERLABORATORY COMPAR! SON PROGRAu 6-3

Duquesne Light Company 1996 Annual Radiological Environmental Report Table 6-2. Contractor - EPA Interlaboratory Cornparison Program 1996 l EPA INTERLABORATORY COMPARISON PROGRAM 1996 Environmental Collection Teledyne Brown Data Media Nuc!]de EPA Results(a) Engineering Result (b) Devistion(c) Footnotes: (a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ liter for ws:er. (b) Teledyne Results-Average one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters. (c) Statistical promulgation based on EPA-600/4-81-004. (d) The variation was due to self-absorption properties of the EPA sample matnx. On future EPA w:ter samples of this type, we will determine the overall alpha enunting efficiency by spiking the matrix with Tb-230 in accordance with their recent advisory. (c) An investigation is being conducted. 4 l l r I l l l l l s s 6-4 Section 6. INTERLABORATORY COMPARISON PROGRAM

.._.m. m EPA CROSS CHECK PROGRAM $e GROSS ALPHA IN AIR PARTICULATES (pg.1 of 1) 9 .d, = o m <n 60 - 3 e 5 2 _5 a 9 $5 8 6' 5 40 - [ [ m [ [ j eo o a 4 o a at p 7 3 a L i I s i m 3 L T T 7 . i -t m -+ S 3 0 0 20 - l g %C o f, 1,g J j { 8 vi a ed 4f ' 3' g {"L E [ g 1 g g 5 0-8 x t i l e g g O. 2 8c 2o 3 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 2 oz 3 o Ti i 3 Sigma o EPA i 3 Sigma 8 The US EPA discontinued air parbculate fdier sampfes m 1996. T r.n

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m 20 - o 'l 0 1981 1982 1983 1984 1985 1986 1G87 1988 1989 1990 1991 1992 1993 1994 1995 1996 i c Tl 13 Sigma o EPA i 3 Sigma The US EPA discontinued air particulate filter samples in 1996. I

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7 3 6m o C. $ I d O g r g 30 - o o 9 gg h i i 10 - 1i g e4 1 f 1 s -4 E 5 0-5 O d A t da -20 g 1981 1982 1983 1984 1935 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 e Oz j u Tl i 3 Sigma o EPA i 3 Sigma 8-Tne US EPA discontirmed air particulate feter samaples in 1996. c

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g. s as [ '(jin[4 j f I" ] + s 'O o g, a,- gji 1 o 3 tu 1 0-l 'o O 3 -20 1981 1982 1983 1984 1985 1986 1987 1988 1989 199u 1991 1992 1993 1994. 1995 1996 r o T12 3 Sigma o EPA 2 3 Ssma I The US EPA discontinued alt partio.date hiler samples in 1996. m.

C .z EPA CROSS CHECK PROGRAM N n. O STRONTIUM-89 IN MILK (pg.1 of 1) { 100 k Q l M-o T r = 8 5 4 1O i t i l u g' ,2 C 60 - a S Eb l 3 oa o@

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The US EPA discontinued anik samples in 1996. Te

T$ s' z t m '.8 EPA CROSS CHECK PROGRAM 4 IE k y STRONTIUM-90 IN MILK (pg.1 of 1) g 9 80 - ~ - 6 8 7 E m 8 m 8 l g 60 - u n k 5 5 ?* 1 E x 0 m -O 2 "o j x_g O I D) 6 L s

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c D N 1800 - C na Be 3 3 OM ,,o o l f) h if ', Ib Oh ~ r i o o o 3 1600 - o jf i > < >(f i n 5- [ 2 l l j l l} k 'g = l di gj 3 { '8 'l 3-MC il e o c ]E R E 1400 - I t ? s

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~ T an d w E* Aa =b EPA CROSS CHECK PROGRAM = n E o -4 3 g IODINE-131 IN MILK (pg.1 of 1) l 5: 8 5 O 140 - m N Q O 8 N 8 o E 120 - o o 'p r 3 = 8 8 m x 100 - 0 ' l, 7 h y, ,ji 5 o l S. hD l m o b @c O,,, g m 80 - 11 r 0 g 9m 3 C u r E BE 60 - g a-U 15 m -+ U S. C fl b O I. 3 o3 40 - if' it E' j '<i o a t3 ~v i 3m fI i, m x 20 - 1 a i m b { El E si g i-0- 0 1 c O 3 -20 6 1981 198J isd3 1984 '.985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 n Tli 3 Sigma o EPA 13 Sigma The US EPA dscstinued milk samples in 1996. 3 m

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1 T a [ -4 E u, b h EPA CROSS CHECK PROGRAM 0 h GROSS ALPHA IN WATER (pg.1 of 1) a 5 180 k t 8 E 9 a 160 0 9 b 4 8 8 140 g y y r 3 3 2 C O y iTi 120 m,,, g y c Z D 8, D m 02 c 2 too as 9: (D h l

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t i s' E I m4 EPA CROSS CHECK PROGRAM p GROSS BETA IN WATER (pg.1 of 2) { [ 6 i 220 t 9* 200 Q w 2 8 180 o> a si r 3 160 ~ A E E. o Y f 5 %.E 34o B 28 3 OM 4 = 120 9 r@- l 5' n .H, 2 3 E i 'M ~ w m 6 Q !O g M 7 g go i. 1 I J 8d i a o 2 M 3$ i M ' ;g s E* [ s 2 E l 40 'I l h' 8 ? o l x h h 20 3 ' I o [ l f or -20 y 1981 1982 1983 1984 1985 1986 9 v g o Tli 3 sigma o EPA i 3 sigma 5 l

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-1 l E i k I' S ?) [ Y ln g EPA CROSS CHECK PROGRAM ? m 9 m i5 TRITIUM IN WATER (pg.1 of 2) h 8 ig 5000 ln m O d Q 8 2 8 5 4000 m = m g 3 m c x EO 'O t, y g z o i, o m 3000 6 m 'fT < i r c Q 2 3" Em -i. la Og i ll t il 1 3 f Om e E '" ' h 5 n g r-g j ag 2000 1 , n T , h m~ o. 8 a oa O 5 io 1000 f 3 o3 33 Bo 0* 0 y u O3 -1000 [ 1981 1982 1983 1984 1985 l lD Tlt 3 si ma o EPA 13 sigma D I t

4 4.6 m J.%--. = A-a-a ,.*sS hae-. m--. ,i.%- a 6 -e .4- -.4 de 4..-4m+ EPA CROSS CHECK PROGRAM I 9 TRITIUM IN WATER (pg. 2 of 2) g aoom 7 25000 Q $g o O k g <= x o _o 20000 p gj B e-8 3 0 09 o5 a e w s C ga = d O l 9 3 E &*0 03 a 7 1 10000 E z M 'g 3 o-32 L gx h eh 'O g eg E o f h h .g O g 1985 1988 198/ 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 9 M h a Ti i 3 Sigma o EPA t 3 Sigma e e u a ?

95 du t7 m e-d6 ? P i EPA CROSS CHECK PROGRAM p. <l COBALT-60 IN WATER (pg 1 of 2) h 8 y 100 m m 8 r a Q 8 E i 8 - r g n I f 1 3 A E e x w m ? ~2 k kE !g 3 m a u-m 3 Om I w og 's = c o e C E EE i 2 40 3-m_ c c d O O an m n ( O j <o i d [ d i .[ h 7 0 3 [ ,f i f h f fu 20 a,, h l 3 i i e ( l i i e x a , g ,l F ,l g

D i

0 - 0 0 o m t) O I A i e [ 1981 1982 1983 1984 1985 1986 1987 1988 o Tl13 sigma o EPA 13 sigma f

y 4 4 A.m z o EPA CROSS CHECK PROGRAM E O COBALT-60 IN WATER (pg. 2 of 2) E a 120 9~ R "U i l a f g 100 i,qi-cn o

r 3

C so x o -O[5 o c 1 ll U O 3 o to 60 "{7 g og o -i o $e, T a g o g c a o 4 3 c I m-U 40 on o,, j Y u y alp o 8 I 3 -a sm onou o of = mo o g n 3$ 5 in o g 7 ni' f M 20 f E* og o o o I E l ,,I uI. 5 o n oi og g o m 0 -4 0 A O Q 'l 8e p J -20 1988 1969 1990 1991 .1992 1993 1994 1995 199F 1997 o l z T M o Tl 13 Sigma o EPA t 0 Sigrna' >C i i 0 1

T s' l = 8s e ? EPA CROSS CHECK PROGRAM I? IODINE-131 IN WATER (pg.1 of 1) x 5 o 8 7 s I;; y 180 Q Q W 8 2 8 I T n 140 { j J I i @P x 9 7 E Cn ,= o a ag o 8 3 E cn s

l 65 y

'll 100 a ii g -r C O tE 3 f-o b d a f 1 o n m Ii o an o E d' I f ir g4 m a 4.i i <i i of, o g o n ,i i n.. o j g m 20 g a o e o .,l 15 V Ik n c e aa a 5 hi i -20 1981 1G33 1985 1987 1989 1991 1993 1995 1997 1 o EPA i 3 Sgma m Tl13 Sgma w -w

o if ? .t 68 EPA CROSS CHECK PROGRAM y l CESIUM-134 IN WATER (pg.1 of 2) g 100 g j Q 2 8 M n r 3 S E Eo (' ~ se 80 3 0m he y g3 i l 3 o* d 6C ( 5'

• C 40 c

7 m O < i h< d [ Q O 8 r m <o o f i A [3 8 s 20 [' i i ]a] i L q i [, j g f s < i I 1 R m i s f 5 E ~ L f O M 'D S 8 c -20 j 1981 1982 1983 1984 1985 1986 1987 1988 2 0z g a Tli 3 shma o EPA 13 sham 8 ss ? N t ~.

T W d us er-B e 5 EPA CROSS CHECK PROGRAM 0 .a O e 2_i CESIUM-134 IN WATER (pg. 2 of 2) 3 0 ma 5 100 ng 1 8 7 s e 0 x a 0 to n 80 i, - 5 8 O E O b a o h c 60 k "O d 2 'O ii j "U E. 2 18 W C E Q. m i h 3 Om 05 l l 3, E 8 - r-lu 9. 05 l r 40 it' ii it = S

r i.

o~ <, o o m-6 3 O i n a 'i 11 I g

j. o e

ir o3 < i si i,- l l

r e

oo 20 o n n on o, 3g .{ gx i, o g ,p l }' g o<. i> e g, i, a o x 0 [ o 3 l O s s a s a 4 s 1988 1989 1990 1991 1992 1993 1Gid 1995 1996 1997 e Ti 13 Sigma o EPA i 3 Sgma 4 u. m - -...u-.m -m

Y SEo a P' EPA CROSS CHECK PROGRAM 9 CESIUM-137 IN WATER (pg.1 of 2) 80 O N 60 o w a R 3c x Eo l m j of c y y S3 = 40 Ty f i=i- = ou a a C T C. r"- t 1 a n 5-c3 o' m o J 4 o 1 3 t a r g i m~ 7 a ' t <r 6 B E.O a 20 r x O I u -i a as o ..r, g o3 au E 3E is 'l t mg -- [. jir g 0 x a D e O VO 3 8e -20 3 1981 1982 1983 1984 1985 1986 1987 e oz ,= a Tli3 sigma o EPA 13 sigma 8 se 4p m N

92 m ze f EPA CROSS CHECK PROGRAM 0 O O CESIUM-137 IN WATER (pg. 2 of 2) y 9 120 n o 8 7 o m E 8 h 100 e* o c a m o I9 8 5 h M ( EO E 5 DE $g$ D T T 3 g 60 4i 0m C 4 O h Ii lI 'd EC

i. h o_

g EC l o o o c 7 m* j h _( gO 5 40 c il y' n oI a.. 3 gg gi ), {'. ,a II y o o i y e o o,, 20 iilD i 3 h i t it I ti eq, ,f '. .I >i ol. j [ og o 0 - y O 'I -20 19P8 1989 1990 1991 1992 1993 1994 1995 1996 1997 a Tl13 Sigma o EPA i 3 Sigma

l l l Duquesne Light Company l 1996 Annual Radiological Environmental Report Table 6-4. OC Lab - EPA interlaboratory Comparison Program 1995 U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'. Concentration in pCi/L" Lab Sample Date Teledge Results EPA Result' Control Code Type Collected Analysis i2 Sigma' Is. N=1 Limits STW 746 WATER Oct,1995 I-131 121.3 i 1.2 148.0 i 15.0 122.0 - 174.0 All data was verified. No errors where found. Samples where counted on two separate days. The average of the samples counted on the other day (not reported) was low, but, would have passed. Teledyne has no explanation for the low values. Normally Teledyne would reanalyze the sample. In this instance, j approximately 18 halflives have transpired since collection, Teledyne felt preparing an in-house spike would be more advantageous. An In house spike was prepared on 02-08-% (see SPW-621 results). These results where acceptable. The technician was observed performing this analysis with no problems noted. i Since this is the first instance of poor performance in this analysis, no further action is planned. Teledyne will monitor this analysis for future problems. ) STW 747 WATER Oct,1995 Gr. Alpha 1073 i 15.2 99.4 t 24.9 56.2 142.6 STW 747 WATER Oct 1995 Ra-226 24.5f 03 24.8 3.7 18.4 - 31.2 STW-747 WATER Oct,1995 Ra-228 20.111.2 20.7 5.2 11.7 - 29.7 STW 747 WATER Oct,1995 Uranium 25.8 i 0.9 27.013.0 21.8 - 32.2 STW 748 WATER Oct.1995 Co-60 50311.2 49.015.0 403 57.7 STW-748 WATER Oct.1995 Cs 134 36.3 1.2 40.0 5.0 31.3 48.7 STW 748 WATER Oct,1995 Cs-137 31.311.5 30.0 i 5.0 213 38.7 STW 748 WATER Oct,1995 Gr. Beta 115.4133 123.5 1 18.5 91.4 - 155.6 ) STW-748 WATER Oct.1995 St-89 19.0 1.7 20.0 5.0 113 28.7 STW-748 WATER Oct,1995 Sr-90 10.710.6 10.015.0 13 18.7 STW-749 WATER Oct,1995 Gr. Alpha 36.9 i 3.0 51.2112.8 29.0 73.4 STW 749 WATER Oct,1995 Gr. Beta 24.3 t 1.6 24.8 t 5.0 16.1 33.5 STW-750 WATER Nov,1995 Ba 133 99 3 i 3.2 99.0 10.0 81.7 - 116 3 STW 750 WATER Nov,1995 Co-60 62.0 3.0 60.0 5.0 51.3 68.7 STW-750 WATER Nov,1995 Cs-134 37.710.6 40.015.0 31.3 - 48.7 STW-750 WATER Nov,1995 Cs 137 51.7 20.8 49.0 5.0 403 - 57.7 STW 750 WATER Nov,1995 Zn-65 127.3il.5 125.0 13.0 102.4 147.6

• Results obtained by Teledyne Brown Engineering Environmental Services Midwest laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitormg and Support Laboratory, U.S.

Environmental Protection Agency (EPA), Las Vegas, Neveda.

• All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/ Filter.
• Unless otherwise indicated, the TBEESML results are given as the mean i 2 standard deviations for three determinations.
• USEPA results are presented as the known values and expected laboratory precision (1s, I determination) and control limits as defined by the EPA.

l l l Section 6. INTERLABORATORY COMPARISON PROGRAu 6-29

Duquesne Light Company 1996 Annual Radiological Environmental Report Table 6-5. OC Lab - EPA Interlaboratory Comparison Program 1996 U.S. Environmental T&uan Agency's crosecheck program, comparison of EPA and Teledyne's Midwest laboratory results for various sample media *. Concentrationin pCl/t

• 1ab Sample Date Teledyne Raults EPA Resuit' Control Code Type Collected Analysis i2 Sigma' 1s, N-1 1.!mits STW 752 WATER Jan,1996 Gr. Alpha 19.511.5 12.115.0 3.4-20.8 STW-752 WATER Jan,1996 Cr. Beta 7.910.7 7.015.0 0.0- 15.7 STW-753 WATER Feb,1996 I131 7b.711.5 67.017.0 54.9 - 79.1 STW-761 WATER Mar,1996 H-3 22,776.71185D 22,002.0 i 2,200.0 18,185.1 25,818.9 i

Results where indavertently not reported due to administrative error in laboratory. STW 762 WATER Apt,1996 Cr. Alpha 63.812.4 74.8118J 42.4 - 107.2 STW-762 WATER Apr,1996 Ra.226 2.910.1 3.0i O5 2.1 - 3.9 STW 762 WATER Apr,1996 Ra-228 4.610.2 5.0113 2.7 - 7.3 STW-762 WATER Apr,1996 Uranium 57.9i 0.5 58.4

• 5.8 48.3 - 68.5 STW 763 WATER Apt,1996 Co-60 32.710.6 31.015.0 22.3 - 39J STW-763 WATER Apr,1996 Cs.134 43.011.0 46.015.0 373 - 54.7 STW-763 WATER Apr,1996 Cs-137 52312.1 50.015.0 41.3-587 STW-763 WATER Apt,1996 Gr. Beta 154.916.8 166.9 i 25.0 123.5 - 210 3 STW 763 WATER Apr,1996 St-89 42.013.6 434154 34.3 - 51J STW-763 WATER Apr,1996 Sr-90 15312.9 16,0154 7.3-24.7 S'1W-764 WATER Jun,1996 Ba-133 7454119.5 745.0 1 75.0 614.9 875.1 STW-764 WATER Jun,1996 Co.60 97.013.6 99.0154 90.3-107.7 STW-764 WATER Jun,1996 Cs-134 72 3 i 1.2 79.0 i 5.0 70.3-873 STW 764 WATER Jun,1996 Cs 137 2013 12.3 197.0 1 10.0 179J - 214.3 STW-764 WATER Jun,1996 Zn.65 298.016.2 300.0 1 30.0 248.0 - 352.0 STW-765 WATER Jun,1996 Ra 226 4.810.1 4.9105 33-6.1 STW-765 WATER Jun1996 Ra 228 8.710.5 9.0i23 5.0 13.0 STW-765 WATER Jun1996 Urmium 20.4 i 0.8 20.213D 15.0 - 25.4 STW-767 WATER Jul,1996 Sr-89 24212.0 25.0154 163 335 STW 767 WATER Jul,1996 St-90 11311.2 12.015.0 3.3 20J STW-768 WATER Jul,1996 Gr. Alpha 20.112.0 24.4 t 6.1 13.8 - 35.0 STW-768 WATER Jul,1996 Cr. Beta 40.413.2 44.815.0 36.1-53.5 STW-774 WATER Sep,1996 Ra-226 13.610.4 14.012.1 10.4 - 17.6 STW-774 WATER Sep,1996 Ra-228 5.410.4 4.7i l.2 2.6 - 6.8 STW-774 WATER Sep,1996 Uranium 10410.2 10.113.0 4.9 - 15 3 STW-775 WATER Oct,1996 I-131 26512.3 27.0i 6.0 16.6 37.4 STW-778 WATER Oct,1996 Gr. Alpha 10.212.1 10315.0 1.6-19.0 1

STW-778 WATER Ott,1996 Gr. Beta 32.011.6 34.615.0 25.9 - 43 3 6-30 Secdon 6. INTERLABORATORY COMPARISON PROGRAM

Duquesne Light Company 1996 Annual Radiological Environmental Report Table 6 5. OC Lab EPA interlaboratory Comparison Program 1998 I 1 1 US Environmental Protectxm Agency's crosscheck program, comparison of EPA and Teledyne's Midwest laboratory results for various sample media'. ) Concentration in pO/L' Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analysis 12 Sigma' Is, N=1 Limits i

• Results obtained by Teledyne Brown lingmeering Environmental Services Midwest laboratory as a i

participant in the environmental sample crosechedr. program operated by the Intercomparison and j Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support laboratory, US Environrnental Protection Agency (EPA), Las Vegas, Neweda. i-

• All results are in pCl/t. except for elemental potassium (K) data in milk, which are in mg/14 alt filter samples, which are in pCl/Pilter.

i

• Unless otherwise indkated, the TBEESML results are given as the rnen i 2 standard deviations for three determinations.
• USEPA results are presented as the known values and expected laboratorf precision (1s,1 determination) 1 and control limits as defined by the EPA.

i l i 1 1 l l p 4 Section 6. INTERLABORATORY COMPARISON PROGRAM 6 31}}