ML20209G547

Vol 2 of Annual Environ Rept,Radiological

ML20209G547
Person / Time
Site:	Beaver Valley
Issue date:	12/31/1986
From:	Seiber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705010012
Download: ML20209G547 (125)

Text

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1986 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL - VOLUME ir2 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION l

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8705010012 861231 ff DR ADOCK 05000334

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J DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report EXECUTIVE

SUMMARY

This report describes the Radiological Environmenta1' Monitoring Program conducted during 1986 in the vicinity of the Beaver Valley Power Station. The Radiological Environmental Program consists of off-site monitoring of water, air, river sediments, soils, food i

pathway samples, and radiation levels in the vicinity of the site.

This report discusses the results of this monitoring during 1966 Duquesne Light Company operates the Beaver Valley Power Station Unit 1 pressurized water reactor as part of the Central Area Power Coordination Group. Beaver Valley Power Station Unit 2 was under

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i construction in 1986 and is scheduled to start up in 1987.

The Beaver Valley Power Station Unit 1 operated throughout 1986 except for May 17 - August 26, 1986, when the unit was shutdown for the Fifth Refueling and Ten-Year Inservice Inspection Outage.

The highest average daily output generated during the year was 838 megawatts net in November, 1986, and the total gross electrical generation during the year was 5,091,830 megawatt-hours.

In prior years, Duquesne Light Company conducted a joint environmental monitoring program for the Beaver Valley Power Station and the Shippingport Atomic Power Station. However, following issuance of the 1985 Annual Radiological Environmental Report, the joint program was discontinued, thus reference to the Shippingport Station has been deleted. See Section I, page 1 for specific detail.

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report EXECUTIVE

SUMMARY

(continued)

On April 25, 1986, a serious accident occurred at the Chernobyl l

Nuclear Plant in the Soviet Union resulting in a release of radioactive materials to the atmosphere.

Subsequently measurable levels of activity attributable to the accident were detected in the environment throughoat the Northern Hemisphere. See Section V for details on fallout data in the Beaver Valley Power Station area and pages 69, 10, 87 and 107 for graphical depictions on selected radionuclides.

During the year, the radioactive releases from BVPS Unit I were below the limits of 10 CFR Part 50, Appendix I and did not exceed the Limiting Conditions for Operation identified in the Beaver Valley Power Station Unit 1

Operating License Technical Specifications.

The maximum total body dose calculated for an individual frora the Beaver Valley Power Station Unit I releases in 198o was less than 0.05 mrem which is less than 1*. of the BVPS Unit 1 Technical Specifications and 10 CFR Part 50, Appendix I annual limits.

See Section I for specific details. The Nr.lonal Academy of Sciences 1980 BEIR Report shows that the typical dose to an individual from natural radiation exposure is 101 mrem per year.

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report EXECUTIVE

SUMMARY

(continued)

The environmental monitoring program outlined in the Beaver Valley Power Station Unit 1 Technical Specifications was followed throughout 1986.

The results of the program are consistent with those of previous years with the exception of the observed f allout from the Chernobyl Nuclear Plant accident.

Examination of effluents and environmental media show that the Beaver Valley Power Station Unit 1 operations have not adversely affected the surrounding environment.

1 i

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report TABLE OF CONTENTS Page EXECUTIVE

SUMMARY

1 I.

INTRODUCTION-----------------------------------------------

1 A.

Scope and Objectives of the Program 2

B.

Description of the Beaver Valley Site 2

II.

RESULTS & CONCLUSIONS--------------------------------------

7 III. ENVIRONMENTAL MONITORING CONSIDERATIONS--------------------

9 A.

Environmental Quality Control Programs 9

B.

Evaluation of the Quality Control (QC) Program Data 25 C.

Standard Requirements and Limitations for Radiological and Other Effluents 25 D.

Reporting Levels 26 IV.

MONITORING EFFLUENTS---------------------------------------

27 A.

Monitoring of Liquid Effluents 27 1.

Effluent Treatment, Sampling, and Analytical Procedures 31 2.

Results 31 B.

Monitoring of Airborne Effluents 32 1.

Description of Airborne Ef fluent Sources 32 2.

Airborne Effluent Treatment and Sampling 35 3.

Analytical Procedures for Sampling Airborne Effluents 37 4.

Results 39 C.

Solid Waste Disposal 40

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report TABLE OF CONTENTS (Continued)

V.

ENVIRONMENTAL MONITORING PROGRAM Page A.

Environmental Radioactivity Monitoring Program 42 1.

Program Description 42 2.

Summary of Results 59 3.

Quality Control Program 59 B.

Air Monitoring e5 1.

Characterization of Air and Meteorology 65 2.

Air Sampling Program and Analytical Techniques 65 3.

Results and Conclusions 68 C.

Monitoring of Sediments and Soils 72 1.

Characterization of Stream Sediments and Soils 72 2.

Sampling Program and Analytical Techniques 72 i

3.

Results and Conclusions 74 D.

Monitoring of Feedcrops and Foodcrops 76 1.

Characterization of Vegetation and Foodcrops 76 2.

Sampling Program and Analytical Techniques 76 l

3.

Results and Conclusions 79 E.

Monitoring of Local Cow's Milk 81 1.

Description - Milch Animal Locations 81 l

2.

Sampling Program and Analytical Techniques 81 l

l 3.

Results and Conclusions 85

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report TABLE OF CONTENTS (continued)

V.

ENVIRONMENTAL MONITORING PROGRAM (continued)

Page F.

Environmental Radiation Monitoring 88 1.

Description of Regional Background Radiation Levels and -Sources 88 2.

Locations & Analytical Procedures 88 3.

Results and Conclusions 89 G.

Monitoring of Fish 96 1.

Description 96 2.

Sampling Program and Analytical Techniques 96 3.

Results and Conclusions 96 H.

Monitoring of Surface, Drinking, Well Waters, and Precipitation 98 1.

Description of Water Sources 98 2.

Sampling Program and Analytical Techniques 99 3.

Results and Conclusions 102 I.

Estimates of Radiation Dose to Man 108 1.

Pathways to Man - Calculational Models 108 2.

Results of Calculated Radiation Dose to Man - Liquid Releases 109 3.

Results of Calculated Radiation Dose to Man - Airborne Releases 112 4

Conclusions - Beaver Valley Power Station 112

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report LIST OF FIGURES Figure

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No.

Page 1.0 View of the Beaver Valley Site 4

1.1 Geographical Map - 40 Mile Radius 5

4.1 Liquid Discharge Points to Ohio River 28 4.2 Water Flow Schematic - Beaver Valley Power Station 29 4.3 Liquid Radwaste Systems - Beaver Valley Power Station 30-4.4 Gaseous Waste Processing - Beaver Valley Power Station 33 4.5 Gaseous Release Points - Beaver Valley Power Station 34 4 ~. 6 Solid Waste Disposal Diagram

-41 5.B.1 Environmental Monitoring Locations - Air Sampling Stations 67 5.B.2 Concentrations of Gross Beta in Air Particulates 69 5.B.3 Concentrations of Iodine-131 in Air Charcoal 71 S.C.1 Environmental Monitoring Locations - Sediments 73 5.D.1 Environmental Monitoring Locations - Feederop and Foodcrop 77 5.E.1 Dairy Farm Locations (August - September 1986 Survey) 83 5.E.2 Environmental Monitoring Locations - Milk 84 5.E.3 Concentrations of Iodine-131 in Milk 87 5.F.1 Environmental Monitoring Locations - TLDs 90 5.F.2 Environmental Monitoring Locations - TLDs 91 5.F.3 Environmental Monitoring Locations - TLDs 92 5.F.4 Environmental Monitoring Locations - TLDs 93 5.F.5 Environmental Monitoring Locations - PICS 94 5.G.1 Environmental Monitoring Locations - Fish 97 5.H.1 Surface Water and Wells - Locations 101 5.H.2 Average Concentrations of Gross Beta and Iodine-131 in Precipitation 107

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DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report LIST OF TABLES Table Number Page III.1 Quality Control Data - TLD Comparisons 10 III.2 Quality Control Data - Water Split Samples 11 III.3 Quality Control Data - Split Samples - Miscellaneous 13 III.4 Quality Control Data - Spiked Samples 17 Ill.5 Quality Control Data - Spiked Samples 18 III.6 Quality Control Data - Air Particulates and I-131 19 III.7 Quality Control Data - Milk and Water 23 IV.A.1 Effluent Treatment, Sampling'and Analytical Procedures Beaver Valley Power Station 31 IV.A.2 Results - Liquid Effluents - Beaver Valley Power Station 31 V.A.1 Environmental Monitoring Program Summary 43 V.A.2 Environmental Monitoring Program Results (1986) 49 V.A.3 Pre-Operational Monitoring Program Results (1974-1975) 60 V.A.4 Typical LLDs for Gamma Spectrometry - DLC Contractor 64 V.D.1 Closest Residence and Garden in Each Sector 78 V.F.1 Pressurized Ion Chambers Results 95 V.I.1 Radiation Dose to Maximum Individual -

Beaver Valley Power Station - Liquid Releases 110 V.I.2 Results of Calculated Radiation Dose to Man - Beaver Valley Power Station -

Liquid Releases 111 V.I.3 Results of Calculated Radiation Dose to Man -

Beaver Valley Power Station - Airborne Releases 113

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SECTION I DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report I.

INTRODUCTION The 1986 Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1986.

In prior years Duquesne Light Company conducted a joint environmental monitoring program for Beaver Valley Power Station and the Shippingport Atomic Power Station.

The Shippingport Atomic Power Station was permanently shutdown on October 1, 1982. Responsibility for the decommissioning of the Shippingport Atomic Power Station rests with the U.S. Department of Energy, Richland Operations Office.

General Electric was awarded the contract to conduct the decommissioning activity.

General Electric preselected Morrison-Knudsen as its integrated subcontractor.

General Electric assumed custody of the plant on September 6, 1984 and received permission to begin physical decommissioning on September 17, 1985. Following issue of the 1985 Annual Radiological

Report, the joint environmental monitoring program was discontinued. General Electric now conducts its own environmental monitoring program consistent with decommissioning requirements.

Therefore, reference to the Shippingport i".omic Power Station has been deleted from the 1986 annual report.

The Duquesne Light Company environmental monitoring program for Beaver Valley Power Station will remain otherwise unchanged.

L 1

SECTION I DUQUESNE LIGIIT COMPANY 1986 Annual Radiological Environmental Report I.

INTRODUCTION A.

Scope and Objectives of the Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, soil, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding the site.

B.

Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land.

Figure 1.0 is a view of the Beaver Valley Power Station.

The site is approximately one mile from Midland, Pennsylvania; 5 miles from East Liverpool, Ohio; and 25 miles from Pittsburgh, Pennsylvania. Figure 1.1 shows the site location in relation to the principal population centers. Population density in the immediate vicinity of the site is relatively low. The population within a 5 mile radius of the plant is approximately 18,000 and the only area within that radius of concentrated population is the Borough of

Midland, Pennsylvania, with a population of approximately 4,300.

The site lies in a valley along the Ohio River.

It extends from the river (elevation 665 feet above sea level) to a ridge along the border south of the Beaver Valley Power Station at an elevation of 1,160 feet.

Plant ground level is approximately 735 feet above sea level.

The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Da.n, and 19.4 miles upstream from New Cumberland Lock and Dam.

The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site.

The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries.

Flow ranges from a minimum of 5000 cubic feet per second (CFS) to a maximum of 100,000 CFS.

The mean annual flow is approximately 25,000 CFS. ',.

SECTION I DUQUESNE LIGHT COMPANY f

1986 Annual Radiological Environmental Report I.

INTRODUCTION B.

Description of the Beaver Valley Site (continued)

Water temperature of the Ohio River varies from 32 F to 84"F, the minimum temperatures occur in January and/or February and maximum temperatures in July and August. Water quality in the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela, and Beaver rivers.

The climate of the area may be classified as humid continental.

Annual precipitation is approximately 36 inches, typical yearly temperatures vary from approximately -

3'F to 95 F with an annual average temperature of 52.8 F.

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

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51 l,l < I O / Mc W PORT 3 STIUBCIVILLI / 2 2 ,,AsuntGTcN S 40 s L/ / / 40 azztn;G I J Roads aivers Ci:les GEOGRAPilICAL iL\\P AND PRINCIPAL COBEIUNITIES IN 40-MILE RADIUS OF TIIE BEAVER VALLEY POWER STATION FIGU?2 1.1...

l SECTION I DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report I. INTRODUCTION B. Description of the Beaver Valley Site (continued) The design ratings and basic features of the Beaver Valley l Power Station are tabulated below: Beaver Valley Thermal & Elec. Rating (Net NW ) 2660 MW 835 MW Type of Reactor PWR Number of Reactor. 3 Coolant Loops Number of Steam Generators 3 - Vertical and Type Steam Used by Main Turbine Saturated The station utilizes two separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The, steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam / water cycle. megawatts thermal NOTE: MW megawatts electrical MW 6-

I \\ SECTION II DUQUESNE LIGHT COMPANY I 1986 Annual Radiological Environmental Report II. 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 1986. Comparisons of pre-operational data with operational data indicates the ranges of values are in good agreement for both periods of time. The Beaver Valley Power Station operated throaghout 1986 except for May 17 - August 26, 1986 when the station was shutdown for the Fifth Refueling and Ten-Year Inservice Inspection. During the year, the radioactive releases were below the limits of 10 CFR Part 50, Appendix'I. The releases at Beaver Valley Power Station did not exceed the limiting conditions identified in the Beaver Valley Power Station Operating License Technical Specifications. The environmental program for 1986 was the same as in 1985 except for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications. (Refer to Table V.A.1 for the 1986 Radiological Monitoring Program Outline). The Beaver Valley Power Station Technical Specifications require sampling of three (3) dairies which have the highest calculated milk pathway potential and one large 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 dairies and revisions due to updated calculations and surveys normally result in sampling of several additional dairies during the year in different sampling periods. The Environmental Monitoring Program also includes two larger dairies 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 dairies required by the Environmental Technical Specifications. The collection periods associated with each of the locations are provided in the detailed s mmary of the milk monitoring program of this report (Section V-E). t -

SECTION II DUQUESNE LIGHT COMPANY 1986 Anndal Radiological Environmental Report II. RESULTS AND CONCLUSIONS (continued) On April 25, 1986 a serious accident occurred at the Chernobyl Nuclear Plant in the Soviet Union resulting in a release of radioactive materials to the atmosphere. The radioactive plume I dispersed throughout the Northern Hemisphere and subsequently measurable levels of radioactivity were detected in environmental media across the United States. Those levels of radioactivity attributable to the Chernobyl accident around the Beaver Valley Power Station were reported to the NRC in accordance with IE Information Notice No. 86-32, " Request for Collection of Licensee Radioactivity Measurements Attributed to the Chernobyl Nuclear Plant Accident" and are discussed in Section V of this report. The results of the 1986 Radiological Environmental Monitoring Program are consistent with those of previous years. The only radioactivity above normal ambient levels in the environs other than world-wide fallout from previous Nuclear weapons tests and the April 25, 1986 Chernobyl Nuclear Plant accident was detected in the Beaver Valley Power Station discharge area and resulted in negligible exposure to members of the public. A summary of the 1986 operational environmental data (ranges and means) for each sampling media is found in Table V.A.2. A summary of preoperational (1974 - 1975) environmental data is found in Table V.A.3. Examination of effluents from the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and Station Technical Specifications. -o-l o

SECTION III DUQUESNE LIGHT COMPANY 1986 Annual Radiological Ensironmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS A. Environmental Quality Control Programs The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) 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. 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, replaced quarterly and of th'se two results compared. The arithmetic mean e systems agrees within i 7%. This is well within the precision of typical TLD Systems. Summary data of the TLD Monitoring Program is provided in Table III.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, soil, sediment and feedcrop were also split with the DLC QC Laboratory. A summary of results of split water samples is provided in Table 111.2. A summary of milk, sediment and feed / food crop split samples is provided in Table III.3. Some variation is expected due to small variations in duplicate samples, variations in analytical procedures, and in calibration, source type, etc. There was one poor gross beta comparison for a March drinking water sample shown on Table III.2. The reason is not known; however, the Juno, August and November samples were in good agreement as were the June and December spiked gross beta water samples shown on Table III.4. Because of the overall uniformity of comparable

results, it is concluded that the two laboratories are consistent and in agreement.

9 o

t I i Section III DUQUE$NE LIGHT COMPANY TABLE !!!.1 1986 Annual Radiological Environmental Report TABLE !!!.1 QUALITY CONTROL RESULTS TLD MONITORING mR/ Day IST QtfARTER 2ND QUARTER DLC DLC DLC QC DLC QC t.ocation Contractor t.ab t.ocation Contractor I.ab No. (CaSO,tDy) (CaSO,tDy) No. (CaSO, toy) (CaSO tDy) 10 0.17 0.20 10 0.17 0.21 13 0.13 0.18 13 0.16 0.18 14 0.17 0.17 to 0.15 0.18 t$ 0.13 0.13 15 0.12 0.15 27 0.16 0.17 27 0.18 0.20 28 0.18 0.19 28 0.17 0.20 29 0.21 0.23 29 0.20 0.22 32 0.20 0.21 32 0.17 0.23 45 0.18 0.21 45 0.17 0.23 46 0.15 0.16 46 47 0.18 0.20 47 0.18 0.23 48 0.19 0.18 48 0.17 0.21 St 0.18 0.20 51 0.16 0.21 3RD QUARTER 4TH QUARTER DLC DLC DLC QC DLC QC Location Contractor Lab Location Contractor Lab No. (CaSO,sDy) (CaSO,tDy) No. (CaSO,iDy) (CaSO,tDy) to 0 16 0.21 to 0.16 0.20 13 0.16 0 19 13 0 16 0.17 14 0 17 0.20 14 0.15 0.17 15 0 14 0.15 15 0.13 0.14 27 0.16 0.19 27 0.17 0.18 28 0.18 0.22 28 0.16 0.19 29 0.21 0.25 29 0.19 0.21 32 0.18 0.22 32 0.18 0.20 41 0.18 0.21 43 0.13 0.21 46 46 0.16 0 14 47 0.18 0.22 47 0.t? 0.21 4a 0.18 0.21 48 0.18 0.20 $1 0.18 0.21 $1 0.17 0.19

• TLD Mtseing..

l Section !!! DUQUESNE LIGHT COMPANY TABLE !!!.2 1986 Annual Radiological Environmental Report (Page 1 of 2) l TABLE 111.2 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs DLC Contractor DLC - QC Melia Analysis Samplina Period Lab (1) Lab (1) Units Surface Water Gross Alpha January i 1.7 1 0.9 pCL/1 April i 1.9 1.3 0.8 pct /l July i 1.6 1 0.6 pC1/1 October i 1.7 0.9 0.9 pct /l Surface Water Gross Beta January 3.4 1.1 3.2 1 0.8 pct /l April 9.4 1 0.8 6.0 0.9 pct /l July 3.7 1.1 2.5 0.8 pCl/l October 7.1 1.6 3.3 0.7 pct /l 4.0 1 0.8 pct /l Surface Water Co 60 January i April i 5.0 1.2 pct /l .fuly i 4.0 i 1.8 nCL/l October 4.0 1.9 pCL/1 Surface Water Cs-134 January i 4.0 1 0.7 pCL/1 April 1 4.0 1.2 pct /l 3.0 i 1.6 pCL/1 July October i 3.0 l.7 pct /l Surface Water Cs-137 January i 3.0 1 0.7 pct /l 4.0 i 1.2 pCL/1 April July i 3.0 i 1.8 pct /l October i 3.0 i 1.8 pCL/I Surface Water Tritium ist Quarter 160 80 162 ; 89 pCL/1 Composite 3rd Quarter 670

• 70 538 : 114 pC1/1 Compostte Surface Water St-89 2nd Quarter e,

2.0 1 0.4 pC1/1 Composite 4th Quarter 2.0 1 0.8 pC1/1 Composite Surface Water Sr-90 2nd Quarter i 0.36 1 0.3 pCL/1 Composite 4th Quarter 1 0.5 1 0.7 pct /l Compostte Surface Water Co-60 2nd Quarter 8.85 + 2.31 I'2 1 2.0 pC1/1 (high Composite ~ i 0.7 4th Quarter g,g Composite (1) Uncertatnties are based on counting statistics and are spec tiled at the 957. confidence interval. -

l Section !!! DUQUESNE LIGHT COMPANY ' TABLE !!!.2 1986 Annual Radiological Environmental Report (Page 2 of 2) TABLE III.2 (Continued) QUALITY CONTROL RESULTS SPLIT 5 AMPLE ANALYSIS RESULTS Casparison of Contractor and DLC-0C Labs DLC Contractor DLC - QC thdk Analvsis Sasolina Period Lab (1) Lab (1) M Drinking water co-137 February e 4.0

• 0.9 pct /l W "kly Split)

May i S.O 1 0.7 pct /l August 1 4.0

• 0.9 pct /l
• 3.0 1 0.6 pCL/1 November 4.0 1 0.8 pC1/1 Ortnking Water Co.134 Febtuary 3

(Weekly Spttt) May i S.0 1 0.8 pC1/1 August

• 3.0
• 0.9 pCL/1 November
• 3.0 1 0.7 pct /l 3

Drinking Water Co.60 February < 4.0 1 0.9 pC1/1 (Weekly $plit) May

• 4.0 1 0.8 pC1/1 August i 4.0
• 0.8 pC1/1 November i 3.0 1 0.6 pCL/1 Drinking Water Gross Alpha March g 1.3
• 0.5 pct /l (Monthly Composite)

June i 1.6 1 1.0 pCL/I August i 1.6 e 0.9 pCL/l November g 2.0 1 0.8 pct /I Drinking Water Cross Beta Ma rch 3.5 1 0.5* 1.1 0.9 pcl/l (Itonthly Composite) June 3.6 1 1.2 3.6 f, 1. 4 pC1/1 August 4.9 g 1.7 1.9 g 1.0 pct /l November 4.6 g 1.3 2.1 1.1 pCill Ottaming Water Tritium 2nd Quarter 160 10 120 : 1,11 pull (Quarterly Composite) i 200 113 : 90 pC1/1 4th Quarter

• defer to Section !!!.A.2.

(1) Uncertainties are based on counting statistics and are specified at the 9$% confidence interval. l. t i j. Section III OUQUESNE LIGHT COMPANY 7A8LE !!!.3 1986 Annual Radio 10gical Environmental Report (Page 1 Of 2) TA8LE III.3 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs DLC Contractor DLC - QC g Analysis Samplina Period Lab (1) Lab (1) Uni.ts Milk t-131 3 18-86 1 0.18 1 0.16 pct /t

• • • • I'"

sr-89 3-18 86 e, 1.7 g 0.17 pct /t $r-90 3 18-86 3.0 0.8 2.66 0.50 pct /t Cs-134 3-18 86 1 4.0 1 1.3 pct /t ca.137 3 18 86 4.0 1.4 pct /t Co.60 3-18 86 S.0 1.3 pct /t K-40 3 18-86 1630 : 140 1370 + 70 pct /t Milk Cs.134 6 24-86 i 8.0 1 2.1 pct /t Rocation 23) Cs-137 6 24 86 7.0 2.6 pct /t Co-60 6-24 86 7.0 3.3 pct /l K-40 6-24-86 1280 130 1340 : 130 pct /t Feed Be.7 6 24 86 1.16 0.28 0.87

• 0.31 pC1/gm Dry ocation 25) x.40 6-24-86 15.2 + 1.5 10.9 : 0.6 pct /sm cry fal31 6-24-86 0.012 + 0.003

< 0.0t$ pct /gm Dry pct /gm Dry Co-60 62486 i O.03 1 0.008 Cs-134 6 24 86 g 0.03

0.010 PCs/gm Dry Cs 137 6-24 86 0.073 g 0.023 0.050 0.040 pct /sm Dry stu.103 6-24-86 0.0$

0.042 0.013 pCL/am Dry Feed Sr 90 4-21 86 to 0.12 0.01 0.16 0.03 pC1/gm Dry (Location 25) g Food I-131 9 03 86 1 0.011 1 0.018 pC1/gm Wet (Location 23) K-40 9 01-86 2.12 0.21 1.80 + 0.23 pct /sm Wet Co-60 9-03 86

• 0.00$

a, 0.006 pCL/sm Wet C5 134 9 03-86 1 0.005 1 0.006 pct /sm het Cn.137 9-03-n6 e 0.005 e 0.006 pct /gm Wet (1) Uncertainties 4re based on countsnm u atterics and are specifteJ at the 95 confidence interval...

Section !!! DUQUESNE LIGHT COMPANY TABLE !!!.3 1986 Annual Radiological Environmental Report (Page 2 Of 2) L TABLE III.3 (Continued) QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Marison of ContraMor and OLC-0C Labs DLC Contractor DLC - QC Media Analysis Samplina Period Lab (1) Lab (1) Units Milk I 111 9-22-86 < 0.28 1 0.27 pct /1 a cation 25) sr-89 9-22-86 1 1.3 1 0.28 pct /l $r 90 9-22-86 2.5 : 0.8 2.3 0.64 pCi/l Cs-134 9-22-86 0.4 3.2 pct /l Cs-137 9-22-86 1 0.5 4.3 pC1/1 Co-60 9-22-86 0.4 3.6 pC1/1 K-40 9-22 86 1230. 120 1350 90 pct /1 5ediment Cross Alpha 10-3N86 22 8 16.3 + 4.7 pct /gm Dry

• • 'I " '

Gross Beta 10-30-86 15 3 23.5 1.1 pct /gm Dry U-235 10-30-86 0.04 0.02 1 0.02 pC1/gm Cry U-234 10-30-86 0.68 0.07 0.83 0.16 pCL/gm Cry U-238 10-30-86 0.53 0.06 0.48 0.12 pC1/ m Dry 5 Sr-89 10-30-86 < 0.16

• 0.005 pC1/gm Dry Sr-90 10-30-86

< 0.054 0.021 0.006 pC1/gm Dry Co-58 10-30-86 0.09 0.01 0.17 0.01 pct /gm Dry Co 60 10-30-86 1.24 0.12 2.89 0.04 pCi/gm Dry Cs-134 10-30 86 0.11. 0.03 <0.008 pC1/gm Dry Cs-137 10-30-86 0.44 0.04 0.42 + 0.02 pC1/gm Cry Mn-54 10-30-86 1 0.03 1 0.03 pct /gm Dry K-40 10-30-86 15.7 1.6 12.6 0.3 pC1/gm Dry Milk i-ill 12-15-86 <0.26 = 0.15 pCL/1 (location 23) Cs-134 12-15-86 5 2.0 pct /1 Cs-137 12-15-86 6.41 3.67 2.3 pC1/1 Co-60 12-15 A6 1 4 1 2.4 pct /1 K-40 12-15-86 1330. 130 1250 120 oct/l (1) Uncertaint ies are based on count ing stae it'ic s and are specifted at the 95* confidence interval. i ? it SECTION III DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report III. Et.7IRONMENTAL MONITORING PROGRAMS A. Environmental Quality Control Programs (continued) 3I DLC QC Laboratory Program Spiked samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for 1 I analysis. Tables III.4 (water) and III.5 (milk) provide I data from this portion of the QC Program. The overall results demonstrate that the contractor performed 4 acceptably in the program. 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 monthly air particulate filters, composited from the weekly air particulate filters, were analyzed 6 months out of the year for gamma activity. Duplicate quarterly air particulate filters, composited from the weekly air particulate filters, were analyzed g for Sr-89 and Sr-90 actisity for each quarter of the year. Table III.6 provides data for this portion of the QC program. The results show generally good agreement / between the laboratories and demonstrate that the contractor performed acceptably in the program. 5. Contractor Internal QC Program The Contractar Lp5 oratory maintained its own QC Program which included participation in the Environmental Protect' ion. Agency, Environmental Monitoring Safety EMSL) Interlaboratory Cross Check f' Laboratory (EPA Program.- This cross check program indicated that the Contractor results were in agreement with EPA EMSL. DLC also audited the Contractor Laboratory and determined that internal QC practices were in effect and that procedures and laboratory analytical techniques conformed to approved DLC procedures. h / s L

=. ~- i Fs 9 J SECTION'III I DUQUESNE LIGHT COMPANY ' I' 1986 Annual Radiological Environmental Report i. f6 III. ENVIRON? FEN'"Af. MONITORING CONSIDERATIONS - A. Envirorimental Quality Control Programs (continued) 6. Special QC Program (DLC Contractor Laboratory Independent Laborstcry - DLC OC Leberstery) O Milk and water samples were prepared quarterly by an ' ' Independent Laboratory. This included low level spiking of specified nuclides. The prepared samples were split three ways and analyzed by the DLC-QC Laboratory and Independent Laboratory as well as the Contractor !.aboratory. A summary of results of this portion of the QC program is provided in Table III.7. The results show generally i good agreement between the laboratories and demonstrate that the contractor performed acceptably in the program. 3 f 4 4 4 r l 't 4 1 a j + f y 1 \\ i i; f i ) 'i L p u ,r t' > gl-3 y ,,v. m.- - -, -, -. ~. -.., - -, - -

~. - k g Section !!! DUQUESNE LIGHT COMPANY,.;i TABLE !!!.4 1986 Annual Radiological Enyf ronamtal Report TABLE 111.4 QUALITY CONTROL RESULTS L SP!KE SAMLE ANALYSIS RESULTS Sample Type DLC and Contractor DLC - QC Sample Date Ident. No. Analysis Lab (1L,, Lab (1) Units 12-31-85 W13 Water Gross Alpha t ?. [ t 10.6 0.6 pC1/1 '/ Cross Beta t o f, t 12.0 1.4 pC1/1 3-01-86 W-14 Waters Sr-89 1 1.9 1.6 0.4 pCi/t Sr 90 3.1 + 0.4 2.4 + 0.2 pct /t 4-28-86 W-15 Water: 1-131 40 : 1 44.9 + 2.4 pct /l K-40 f,, 60 =. 100 14 pC1/1 4 Co-60 9.22 + 3.24 10.6 + 1.7 pC1/1 Cs-134 24.9 + 5.5 30.2 + 2.4 pct /1 Cs-137 24.4 4.1 21.9 : 1.9 pct /t 6-11-86 W-16 Water Cross Alpha 104 3 16.2 + 0.7 pC1/1 Cross Beta - 35. 2 38.4.,3.5 pC1/1 t-9-30-86 W-18 Water: Cs-134 42.2 + 5.7, 34.7 5.6 pC1/1 Cs-137 46.0 + 4.9 51.1 7.0' pct /l I 10-28-86 W-19 ,t-68a t e r Sr-89 13.0 + t 13.6 : 4.1 pct /t 1 St-90 5.2 0.5 6.4 : 1.6 pC1/1 11-18-86 W-20 4s t e r: H-3 3500 + 100 7

3455 + 180 pct /l.

10131 86 W-21 Wbter: Co-60 '19.4 4.8 19.2 2.2 pCi/t Cs-134 32.1 + 4.7 31.7 + 5.2 pct /t Cs-137 23.4 + 4.1 23.8 : 1.0 pC1/1 y - i 4*^ g 4 d s w A Note - i W-17 wa s an internal spike used only by the DLC-QC Lab. (t) Uncertainties are based on counting statistics and are specified at the 95? confidence interval. '+. P 4

Section !!! DUQUESNE LIGHT COMPANY TA8LE !!!.5 1986 Annual Radiological Environmental Report h i j TA8LE III.5 r QUALITY CONTROL RESULTS ( SPIKE SAPPLE ANALYSIS Sample Type DLC and Contractor DLC - QC Seele Date Ident. No. Analysis Lab (1) Lab (1) Units 2-26-86 M1-6 Milk Sr-89 4.3 6.0 1.9 pCL/1 Sr-90 11 1 14.2 ; 1.7 pC1/1 1-131 30 : 1.0 34.2 3.8 pCL/1 Cs-134 31.9 : 5.4 32.0 : 1.8 pct /1 Cs-137 40.7 5.2 35.8 2.1 ' pC1/1 K-40 1320 130 1260 110 pc1/1 4-28-86 M1 7 Milk: 1-131 40 : 1 39.7 3.3 pct /l K-40 1320 130 1350 70 pct /l Cs-134 23.1 7.2 28.7 2.8 pct /t Cs-137 27.7 2.8 21.2 2.8 pC1/1 6-30-86 M1-9 Milk Sr-89 < t.9 e 1.0 pCL/1 Sr-90 13 1 12.6 1.8 pct /t 1-131 38 2 38.9 7.0 pC1/1 Cs-134 35.3 4.5 33.0 3.4 pC1/1 Cs-137 40.2 3 4.8 38.5 ; 2.8 pC1/1 K-40 369 : 48 380 30 pC1/1 10-28-86 MI-10 Milk: Sr-89 12.3 1.8 pCL/1 10-28-86 Mi-11 Milkt St-90 15.0 2 12.3 1.8 pC1/1 i NOTE - Mi-8 was an internal spike used only by the DI4-QC 1.ab.

• M1 Sample was not analysed. M1-il replaced Mi-10 (1) Uncertainties are based on counting st ttstics and are specified at the 957. confidence intervat. -

{ Section Ill DUQUESNE LIGHT COMPANY TABLE III.6 1946 Ann'4a1 Radiological Environmental Report (Page 1 of 4) TABLE III.6 QUALITY CONTROL RESULTS AIR FARTICULATES AND CHARCOAL FILTER: COMPARABLE SAMPLES Air Beta (pct /m ) Air lodine (pCi/m ) - DLC DLC Contractor DLC - QC contractor uLc - 4 Sample Date Lab (1). Lab (1) Sanele Date Lab (1) Lab- (1 ) 13-30-85 to 0.017 + 0.003 0.023 + 0.004 1-06-86 to < 0.02 1 0.03 1-06-86 1-13-86 0.03 ,0.0t 3 1-t3-86 to 0.016 0.004 0.020 0.003 1-20-86 eo 1-20 86 1-27-86 1-27-86 to 0.018 + 0.004 0.018 0.003 2-03-86 to 1 0.01 < 0.03 2-03-86 2-10-86 3-10-86 to 0.022 + 0.003 0.021 + 0.003 2-18-86 to e 0.01 < 0.03 2-18-86 2-24-86 ( 2-24-86 to 0.018 0.004 0.018 + 0.003 3-03-86 to e 0.01 < 0.03 3-03-86 3-10-86 3-10-86 to 0.014 + 0.003 0.015 + 0.002 3-17-86 to < 0.01 < 0.03 3 17-86 3-24-86 3-24-86 to 0.022 1 0.004 0.023 3 0.004 3-31-86 to 1 0.02 1 0.03 3-31-86 4-07-86 6-07-86 to 0.009 0.003 0.008 : 0.002 4-14-86 to < 0.02 1 0.03 4-14-86 4-21-86 4-21-86 to 0.019 + 0.003 0.025 + 0.004 4-28-86 to e 0.02 < 0.03 t 6-28-86 5-05-86 5-05-86 to 0.12 + 0.01 0.100 + 0.006 5-12-86 to 0.346 0.035 0.46 + 0.09 5-12-86 5-19-86 5 19-86 to 0.10 + 0.01 0.136 + 0.007 5-27-86 to < 0.06 < 0.04 5-27-86 6-02-86 G-02-86 to 0.095 0.006 0.099 + 0.006 6-09-86 to < 0.03 < 0.03 6-09-86 6-16-86 i I (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval. 1 ! ~ ,,_m

betion II2 DUQUESNE LIGHT COMPANY TABLE III.6 1986 Annual Radiological Environmental Report (Page 2 Of 4) TABLE I!!.6 (Continued) QUALITY CONTROL RESULTS AIR PARTICULATES AND CHARCOAL FILTER: COW ARABLE SAM LES Air Beta (oCt/m ) Air Iodine (pct /m ) Uu. LLC Contractor DLC - QC Contractor DLC - QC Sasele Date Lab (1) Lab (1) Sasele Date Lab (1) Lab (1)- 6-16-86 to 0.027 + 0.004 0.025 + 0.004 6-23-86 to < 0.02 < 0.03 4 ,6-23 86 6-30-86 6-30-86 to 0.022 0.003 0.022 + 0.003 7-08-86 to i 0.02 1 0.03 7-08-86 7-14-86 7-14-06 to 0.029 + 0.004 0.02) + 0.003 7-21-86 to < 0.02 < 0.03 7-21-86 7-28-86 7-28-86 to 0.023 + 0.004 0.019 + 0.003 8-04-86 to 1 0.02 1 0.03 8-04-86 8-11-86 d.02 < 0.03 8-11-86 to 0.026 + 0.004 0.024 + 0.004 8-18-86 to e 8-18-86 8-25-86 8-25-86 to 0.021 0.003 0.020 0.003 9-02-86 to 1002 1 0.03 9-02-86 9-08-86 9-08-86 to 0.027 0.003 0.029 0.004 9-15-86 to < 0.02 < 0.03 9-15-86 9-22-86 9-22-86 to 0.020 0.003 0.018 + 0.003 9-29-86 to i 0.02 1 0.03 9-29-86 10-06-86 10-06-86 to 0.018 + 0.003 0.019 + 0.003 10-13-86 to 1 0.02 1 0.03 10-13-86 10-20-86 10-20-86 to 0.032 0.004 0.043 + 0.004 10-27-86 to i 0.02 1 0.03 10-27-86 11-03-86 11-03-86 to 0.019 + 0.003 0.017 + 0.003 11-10-86 to < 0.02 < 0.03 11-10-86 11-17-86 11-t7-86 eo 0.026 + 0.004 0.026 + 0.004 11-24-86 eo 1 0.02 1 0.03 11-24-86 12-01-86 12-01-86 0.015 : 0.003 0.019 + 0.003 12-08-86 to < 0.02 < 0.03 12-08-86 12-15-66 12-15-86 0.027 + 0.004 0.036 0.004 12-22-86 to < 0.01 < 0.03 12-22-86 12-29-86 (1) Uncertainties are based on counting scattstics and are specified at the 957. confidence intervat., rm . -~ --,.--i---- -vr F ?---*--7-'-T-"*Pw -e*- r-v~ v

Section III DUQUESNE LIGHT COMPANY TABLE Ill.6 1986 Annual Radiological Environmental Report (Page 3 of 4) TABLE 111.6 I-QUALITY CONTROL 3 L AIR PARTICULATES (oC1/n ) DLC Contractor DLC - QC Sasele Date Nuclide Lab (1) Lab (1) January Be-7 0.102 + 0.019 0.112 + 0.011 Others LLD LLD March Be-7 0.121 + 0.018 0.104 0.013 Others LLD LLD May Be-7 0.140 0.020 0.121 0.024 Cs-134 0.014 + 0.002 0.013 + 0.003 Cs-137 0.027 + 0.003 0.028 + 0.004 Ru-103 0.027 0.003 0.021 + 0.003 Others LLD LLD July Be-7 0.148 + 0.026 0.168 + 0.027 Others LLD LLD ~ September Be-7 0.079 0.013 0.085 0.028 Others L1D LLD November Be-7 0.092 + 0.018 0.118 + 0.045 LLD LLD Y l 't 1 M 4 L-LLD - Lower Limit of Detectton (1) Uncertainties are based on counting statistics and rae specitted at the 95% confidence Interval.,,,,.

, -.. ~.... Section !!! DUQUESNE LIGHT COMPANY TABLE !!!.6 1986 Annual Radiological Environmental Report (Page 4 of 4) TABLE III.6 QUALITY CONTROL 1< AIR PARTICULATE AND CHARC0AL FILTER 3)OMPARABLE SAMPLES C LOCATION 30 - (nCf/m DLC (ontractor Di.C - QC Staple Date Nuclide Lab (1) Lab (1) ist Quarter Composite Sr-89 1 0.0012 1 0.0001 $r-90 1 0.0001 1 0.0001 2nd Quarter Comoosite Sr-89 1 0.0009 0.0003 0.0003 $r-90 1 0.0002 0.0002 + 0.0001 3rd Quarter Composite-St-89 1 0.0014 1 0.0002 l, Sr-90 10.0001 1 0.0001 4th Quarter Composite Sr-89 1 0.0008

0.0003 Sr-80 10.0001 3 0,0002 4

-l (1) Uncertainties are based on counting statistics and are specified at the 95*. confidence interval.

Section !!! DUQUESNE LIGHT COWANY TABLE III.7 1986 Annual Radiological Environmental Report (Page 1 of 2) TABLE III.7 QUALIW CONTROL DATA QC Sample Comparisons (All Analyses in oCU11 Sagle Type DLC .aA Inden.nd.nt enntractnr DLC - OC Sample Date Ident. No. Anaises La'b (1) Lab (1) Lab (1) ~ 2 05-66 53-271 Water: Sr-90 9.8 _+ 0.4 11 _+ 1 8.5 _+ 0.9 I-131 8.4 + 0.2 9.0 0.2 7.0 + 2.2 Hn-54 19 + 7 30.9 : 4.2 30.1 6.8 Cs-134 19 : 6 20.2 + 3.3 21.2 3 4.4 Cs-137 27 : 7 30 + 6.1 31.4 3.3 2-05-86 53-272 Water: H-3 1000 + 112 1200 : 100 1050 120. I. 5-07-86 53-273 Water: Sr-89 15 + 2 13 + 2 7.8 3.9 St-90 13.7 + 1.0 14 + 1 14.0 2.4 1-131 17.2 0.3 17 1 17.1 2.3 Co-58 20 + 3 25 5.2 29.4 8.8 2-65 18 + 6 25.2 7.9 20.6 : 6.4 5-07-86 53-274 Water: W-3 1533 : 100 1500 200 1450 + 150 6-05-86 53-A Water 1,131 7.4 + 0.2 7.2 3 0.3 6.9 : 1.2 1, 53-8 g.g3g 13.2 0.2 12 + 1 13.7 + 1.9 t 53-C I-131 25.1 : 0.3 22 1 22.9 2.4 8-21-86 53-275 Water: Sr-89 14 + 2 13 + 2 6.9 : 3.8 Sr-90 14.8 + 0.4 12 1 14.0 + 1.0 1-131 8.5 + 0.3 7.9 0.3 10.5 1.0 Cs-134 18 + 5 18.8 + 3.2 14.9 4.6 Cs-137 24 6 34.0 4.3 27.2 + 3.8 8 21-86 53-276 Water: H-3 2027 + 130 2100 + 100 2120 _+ 100 11-19-86 53-277 Water Sr-89 7 2 .5.8 + 1.6 6.6 + 6.1 Sr-90 12.1 0.5 10 + 1 8.7 2.8 I-131 11 + 0.4 14 1 16.4 + 2.2 Co-58 17 3 21.4 4.6 20.7 2.5 Co-60 64 5 70.2 7.0 64.9 + 0.5 11-19-86 53-278 H-3 880 150 1100 100 1047 + 30 i w (1) Uncertainties are based on counting statistics and are spectfted at the 95% confidence intervat.,

Section 111 DUQUESNE LIGHT COMPANY . TABLE III.7 1986 Annual Radiological Environmental Report (Page 2 of 2) y l TABLE III.7 L QUALITY CONTROL DATA 4 L QC Sample Comparisons (All Analyses in DC1/1) Sample Type DLC and Indeoendent contractor DLC - OC Seele Date Ident. No. Analyses Lab (1) Lab (1) Lab (1) 2-05-86 52-238 Milk Sr-89 to 2 to 3 8.4 3.6 Sr-90 17 2 17 1 15.2 : 1.6 1-131 17.3 3 21 1 14.1 : 1.9 Cs-134 14 + 3 16.8 + 3.5 12.8 + 3.6 Cs-137 23 4 28.1 6.4 26.9 2.8 K-40 1400 140 1300 140 5-07-86 52-239 Mitki Sr-89 5.2 + 1.0 2.3 4.1 : 1.7 Sr-90 11.6 + 0.4 12 1 11.7 1.1 1-131 14.5 + 0.2 17 1 12.5 3.2 Cs-134 17 to 13.9 3 3.7 12.5 3.4 Cs-137 38 12 34.2 + 4.6 30.1 + 3.4 K-40 1290 + 130 1250 100 6-05-86 52-A Milk: 1-131 10.9 0.2 13 1 9.1 : 1.0 52-5 I-131 16.9 _+ 0.3 18 _+ 1 14.7 _+ 2.2 52-C 1-131 35.0 0.5 31 1 24.6 z'2.8 8-21-85 52-240 Milk: S r-89 2.8 0.7 1.4 5.1 2.3 3r-90 12.2 0.4 13 1 12.4 1.4 1-131 14.8 0.5 17 + 1 19.6 + 1.0 Cs-134, 19 : 6 25.5 4.9 18.7 : 0.6 Cs-137 24 + 7 29.3 4.8 24.4 3.8 K 40 1440 t40 1180 : 140 11-19-86 52-241 Milk: Sr-89 23 + 3 14 2 13.2 ; 5.5 Sr-90 20.6 3 0.6 16 1 15.9 2.1 I-131 8.0 0.5 13 + 1 11.1,; 4.6 Cs-134 17 6 15.6 4.3 14.2 3 4.2 Cs-137 31 7 35.9 : 4.4 32.5 3.3 K 40 1300 + 200 1390 : 140 1260 + 20 Analysis not performed nor required. (1) Uncertainties are based on counting statistics and are specit ted at the 95% confidence interval. _.

SECTION III DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING PROGRAM ^ A. Environmental Quality Control Programs (continued) 7. Pennsylvania Department of Environmental Resources Program The Pennsylvania Department of Environmental Re;surces (PDER) 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. Comparison of results also indicated agreement between the PDER Laboratory and the Duquesne Light Company Contractor Laboratory. i B. Evaluation of the Quality Control (QC) Program Data The split and spiked sample program indicates that the Contractor and QC Laboratory are performing satisfactorily. In addition, an independent laboratory is used to supplement the regular program. Comparisons between the independent, QC and Contractor laboratories are acceptable and demonstrate a satisfactory performance by the DLC contractor. Based on all available QC data and the data from the Contractor's internal EPA Interlaboratory Cross Check Program, the Environmental Monitoring Program for 1986 is acceptable with respect to both accuracy and measurement. C. Standard Requirements and Limitations for Radiological and Other Effluents The Beaver Valley Power Station is governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases are controlled to ensure that limits set by Federal or State governments are not exceeded. In addition, self-imposed limits have been i established to further limit discharges to the environment.._

SECTION III DUQUESNE LIGHT COMPANY s 1986-Annual Radiological Environmental Report (. III. ENVIRONMENTAL MONITORING PROGRAM C. Standard Requirements and Limitations for Radiological and Other Effluents (continued) Beaver. Va.11ey Power. Station is subject to regulations which include the Code of Federal Regulations _ 10 CFM (t.nergy), Pennsylvania Department of Environmental Resources (PDER) / Industrial Waste Permit #0473211, Gaseous Discharge Permit i

1. 04-306-001, 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 #0025615, and the Beaver Valley. Power Station Technical Specifications. 1 D. Reporting Levels A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmer.tal sampling medium exceeds the limits specified in the Beaver Valley Power Station Technical Specifications when averaged over any calendar quarter. Also, when more than one of the rad.ionuclides are detected in the sampling medium, this report shall be submitted if: Concentration (1), Concentration (2), .2 1.0 k Limit Level (1) Limit Level (2) There were no analytical results of environmental samples during 1986 which exceeded Beaver Valley Power Station reporting levels. 1

.. t. 1 SECTION IV-DUQUESNE LIGHT COMPANY E 1986 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS A. Monitoring of Liquid Effluents Description of Liquid Effluents at the Beaver Valley Power Station. Most of the water required for the operation of the Beaver Valley station is taken from the Ohio River, and returned to the river, used for makeup to various plant systems, consumed by station personnel, or discharged via a sanitary waste system. In addition, small amounts of well water and liquid k effluents are discharged to the Ohio River using discharge points shown in Figure 4.1. Figures 4.2 and 4.3 are i schematic diagrams of liquid flow paths for the Beaver Valley Power Station. The following two (2) tables summarize radioactive liquid effluents at the Beaver Valley Power Station: Table IV.A.1 - Effluent Treatment, Sampling, and Analytical Procedures - Beaver Valley Table IV.A.2 - Results of Liquid Effluent Discharges to the Environment - Beaver Valley i-I

SECTION IV FIGURE 4.1 DUQUESNE LXGilT COMPANY s, 1986 Annual Radiological Environmental Report f 8 Bis FIGURE 4.1 s.p sg~ 5 g!n h WME .2 g.

33 na_

o a .<0 3348 E E h E e :m l

a.

= .m s a e >l =2 t. t.ygt g g y a a := y ,n,,,,,,~,,n,,~~,,,,,, ~,,,,,, ~,,,,,,,, ~,,,,,,,,,,, ~. h TW/W./3/00M/Nf l (83/ UN) MOVOUddY 3CO/ W um muuu s uu mum uu su m > u.susm umm uuu um / qs g" l t. g: g$t g ege { v-u.! 1 3 i u a p 5 "d* ll $50 5"$ n 5$ = = e a... s a-E- \\, g I -sa e g v:8 e 3" 4 5 d g. 8 8 E IE 9-E d C2 "d<~ 8 "1 25-2 b" 6. ) ex =52 : L sa

1. q t " ~, L s 83 /

3 2 / 1 e a d*s s W m' M " h E W$ G S s 5. 3 ~ m iE E n ~ >g = c ..8 8 e .= $3 W hs Q li! I k 5E O sg 1 } Ob= 3"8 .o-u _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1

FIGURE 4.2 SECTION TV DUQUESNE LIGHT C0!D%NY 1986 Annual Radiological Environmental Report SECTION IV EIGURE 4.2 EVAPORATION LOSSES 1 BEAVER VALLEY POWER STATION COOLING TOWER OM-PU:tPS -/ ) a

FLOWy,

) f I s j % L '\\ l PRIMARY AND MAIN SECOND.CY Y C UII'

L HL\\T jg CONI,ENSER E.\\CHAECCRS AND CHILLERS d b WATER 7

TR P.iTI!.C SYSTDI I I h 1P 9P REACTOR SERVICE PLANT go[LER gA;;t7Agy gg7;g SYSTCtS SYSir;t SYSTD1 SY3 TEM 74 wr ) \\ RADVASTE RADWASTE BLOWDOWN RECE!VI T, A PROC".SSING SYSTDI SYSTEM ST@t SCEEN VAIER VA3d w j g SYSTUt d b INTAKE PtHPS C m I AUX AUX e k Agg TEST SCREEN EFFLUENTS WASH INTAKE k PLHPS ^ ^ w f 1I [ ] f if BEA%ER BEAVER VALLEY BEAVER VALLEY BEAVER VALLEY BEAVER VALLEY BEAVER VALLEY yg y g VALLEY POWER STATION ' POWER STATION POWER STATION POWER STATION P74ER STATION POWER STATION POWER AUX. DISCHARGE AUX. DISCHARGE DISCHARGE (002) DISCHARGE (003) DISQiARG" (001) g, NTAK BEAVE?. VALLEY h. P0kTR bTATION WATER FLOW SCHEMATIC - BEAVER VALLEY PCWER STATION DISCHARG2 (004) lll UE HOZ H< mHOC w 3! T CC C ZM O O&FoDM wgC@ DhW OMO eOh MU5 o0 vO"n 3 1_, w 0 4 07 N R I EA TR ^ AD W _~ L DN. M E F F T S C S S Y EM S a CA E E OLh E W RTA T O PST S T A N W G N m_ N X D I D I I L W L O O O O L S C B C K N AT TSE T O l T K i M L '" ] W N D A E T L lg = C T Y S C = E E = = T R = = = ( = u'~ = = = y M F. T S E Y T S S g A O E l g T W T g A S D R .,A N I O R R 4W I N Q A T T t K U P E E ghl A R A I V L L l g DT L E I I ggy F F g l + jg g p I. Y F f l l A i ) V a K X ) p I y A Rf [ [ g [ s e RO L T E A M V R S R E L E K A t D E S N N LIUTK ED N Wv E5 V K E A s H c T KEK CQSN LIES A I AA UTK T M C CN M A IN ILWT wQSN AE A B RT oI AA E A LLWT T R S D A m" ) D S E N I TA A N R D D N I M A A N T m S S N S P R S O o M C T T E ( u w N L M E S V H s S ijg l l t ll i 1 I l

SECTION IV - DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report TABLE IV. A.1 1. Effluent Treatment, Sampling and Analytical Procedures - Beaver Valley i Treatment, Sampling Standard and/or Effluent Typc and/or Monitoring Analytical Procedures-(a) Steam System Recycled or directed to If discharged, procedures Blowdown Radwaste System for adhere to Technical discharge. Specifications. (b) Radioactive Effluents shall not exceed Procedures adhere to { Waste values specified in the requirements of } Technical Specifications. Technical Specifications. All discharges are performed in accordance with the Offsite Dose Calculation Manual (0DCM). TABLE IV.A.2 2. Results of Liquid E f fluent Discharges to the Environment - Beaver 7 Valley Effluent Type Results for 1986 (a) Steam System The Steam System Blowdown was recycled or Blowdown directed to the Radwaste System where it was monitored and discharged in accordance with conditions noted in Section 3/4.11.1 of the Technical Specifications (b) ' Radioactive Routine planned releases of liquid effluents Waste Liquids from the Beaver Valley Power Station were released in accordance with conditions noted in the Section 3/4.11.1 of the Technical Specifications and no limits were exceeded. These values have been reported in the Beaver Valley Power Station Semiannual Effluent Reports for 1986.

SECTION IV DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring'of Airborne Effluents k 1. Description of Airborne Effluent Sources Beaver Valley Power Station (BVPS) / The Beaver Valley Power Station identifies isotopes according to the' Environmental Technical Specifications and Regulatory Guide 1.21. Prior to waste gas decay tank batch releases and containment purge releases, an analysis of the pribcipal gamma emitters is performed. The principal gamma emitters include noble

gases, iodines, and particulates. Figure 4.4 shows the gaseous radwaste system at Beaver Valley Power Station.

The environmental gaseous release points also require specific nuclide identification. These points include the Process Vent located on top of the Unit 1 Cooling Tower, the Ventilation Vent located on the top of the Auxiliary Building, and Supplementary Leak Collection l and Release System (SLCRS) Vent located on top of the ) Containment. These points are continuously monitored. Principal gamma emitters and tritium are analyzed on a monthly basis. Analysis is also done on charcoal cartridges for 1-131, I-133, and I-135 that have continuously sampled the gas stream for a week. Weekly continuous samples are also obtained on filter paper for gross alpha determinations and to identify particulate gamma emitting isotopes. Composites of the particulate samples are analyzed monthly for Sr-89 and l Sr-90. . l

FIGURE 4.4 SECTION IV DUQUESNE LIGHT C0tiPANY 1986 Annual Radiological Environmental Report ) 1 / BEAVER VAL 1,EY FCMER STAT!"M MSE0t/S RADICACTIVE WASTt PROCES$!NG SYSTEM E

25 2

EE: N e 5 5 E E a r e u j = 5 s. o W l C (~- E 5 ./ i ( f O 1 L c 5 E M sr N e a $"w E 8f. 5 l g ( j ( I f 3 E. b N t a w = W se !22 g a 4 -3 a : = i u a 8 g l on a ,g 8% l g t \\ '/ 4 '/Xj i# 5 1 [ 4 a e-o = 9 q e m 5 m 3 a a b 4 l l W i6 ^ b w . e4 = 3 ~ = m E M = = 3 5 a E E s I a m r = 4 h P 4 g g N u. E E E f su 35 5 i ? Os c a 3 v 38 w u e 0 i --- -.. - - - - _

SECTION IV DUQUESNE LIGHT COMP M FIGUP2 4.5 1986 Annual Radiological Environmental Report SECTION IV DISCHARGE POINTS - GASEOUS t/ASTES FIGUTE 4.5 \\ Ventilation Vent SLCRS Vent J / I / N C V / Containment Ventilation System (Containment Air Normally recirc.-not vented) Auxiliary Building Ventilation System Exhausts Oaseous wast es to Cooling Tower; Air Ejector CASEOUS RELEASE POINTS - BEAVER VALLEY POWER STATION I

SECTION XV DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued) 2. Airborne Effluent Treatment and Sampling Beaver Valley Power Station 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 subsysten upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor. Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and radioisotopes of xenon, krypton, tritium, cobalt, cesium, manganese, iodine, chromium and strontium are also present in the three continuous ventilation system pathways. The overhead gas compressor directs the radioactive gas stream to a gas surge tank. Gas is periodically l discharged from the surge tank to one of the three (3) ) decay tanks for eventual release to the atmosphere via the process vent on top of the cooling tower. After the decay tanks are sampled and authorization obtained for discharge, the flow of the waste gases from the decay tanks (2 scfm) is recorded and rapidly diluted with about 1000 scfm of air in order to dilute hydrogen and i radioactive effluent concentration. The gases are then combined with nitrogen purge from the decay tank radiation monitor and oxygen analyzers, calibration. gas from the oxygen analyzers, the main condenser air ejector exhaust, the containment vacuum system exhaust, aerated vents of the vent and drain system, discharge of the overhead gas compressor and the purge from the multi sample point radiation monitor. The mixture is then filtered through one of the gaseous waste disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the cooling tower. The radioactivity levels of the stream are monitored continuously. SECTION IV DUQUESNE LIGHT COMPANY ( b 1986 Annual Radiological Environmental Report I IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued) (. 2. Airborne Effluent Treatment and Sampling (continued) Beaver Valley Power Station (continued) Should the radioactivity release concentration of the stream go above the allowable setpoint, a signal from the radiation monitor will stop all flow from the decay tanks. y During a shutdown period after the containment has been sampled and the activity levels determined, the f containment may be purged through the Ventilation Vent }. located on top of the Auxiliary Building or the Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Reactor Containment Building or the Process Vent located on top of the Cooling Tower. Areas in the Auxiliary Building subject to radioactive' contamination are monitored for radioactivity prior to entering the common Ventilation Vent. These individual radiation monitors aid in identifying any sources of contaminated air. The Ventilation Vent is also monitored continuously by several redundant systems and sampled periodically. Upon a high activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the Supplementary Leak Collection and Release System (SLCRS) and to the SLCRS Vent. Release points are shown in Figure 4.5 for the Beaver Valley Power Station. 1 Each filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type HEPA filters. The l roughing filters remove large particulates to prevent excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the HEPA filters remove particulates and charcoal fines. SECTION IV DUQUESNE LIGHT COMPANY t 1936 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS 3. Analytical Procedures for Sampling Airborne Effluents t Beaver Valley Power Station The following tabulates the gaseous sampling and analysis schedule: Minimum lower Limit of Sampling Analyste Type of Detection (LLD) Caseous Belease Type Frequency Frequency Activity Analyste Cao C1/mi)* A. Weste Cae Storage F F 8 1 x 10" Tank Each Task Ea:h Tank Principal Comme Easttere Crek Sample H-1 1 a 10" I

8. Contetnaent Furge Each Purge E4.:h Purge Principal Camma Emittere 1 x 10 Crab 4

66 - 1 1 m to Sample I C. Venstletion Systems M '"I* H Principal Camme Ealttere 1 a 10" -6

1. Process Vent g

g }

2. Containment Vent

1. Aus. Bldg. Vent 1 x 10'I Continuous W

I-13L Chercoat -10 Sample t-til i x 10 I Belease free BaJto-Continuous W' Frtncipet Camme Emittere todine and Ferticulates Pasticulate (1-t31. Othere) 1 a 10 (Airborne) may be S.asple Continuoue H Crose alphe 1 x 10' I I I I* Particulate Sample Continuous q Sr-69. St-90 1 x 10' I I compne i t e Fa r t icule t e Samate Continuous' thible das thih t e C.aees 1 x 10" thei t t o r Crome Bete and Camma

SECTION IV DUQUESNE LIGHT COMPANY s 1986 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS L B. Monitoring of Airborne Effluents (continued) 3. Analytical Procedures for Sampling Airborne Effluents (continued) TABLE NOTATION a. The Lower Limit of Detection (LLD). b. When reactor coolant system activity exceeds the limits stated in the BVPS Technical Specification, analyses shall be performed once every 24 hours during startup, shutdown and 25% load changes and 72 hours after achieving the maximum steady state power operation unless continuous monitoring is provided. c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours f after changing (or after removal from sampler). Sampling and analyses shall also be performed at least once per 24 hours, during startup, shutdown and 25% load changes and 72 hours after achieving the maximum steady state power operation when RCS activity exceeds the limits stated in the Technical Specification unless continuous monitoring is provided. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. e. Tritium grab samples shall be tak'en at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. f. The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with the BVPS Technical Specification. _ _ _ _ _.

? SECTION IV DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report I IV. MONITORING EFFLUENTS L B. Monitoring of Airborne Ef fluents (continued) ( 3. Analytical Procedures for Sampling Airborne Effluents (continued) f g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report. 4. Results I Beaver Valley Power Station Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 3/4.11.2 of the Technical Specifications. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi-Annual Effluent Reports for 1986., _.,,,.....

h / c SECTION IV DUQUESNE LIGHT COMPANY L 1986 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS i C. Solid Waste Disposal at the Beaver Valley Power Station During Beaver Valley Power Station normal operations and periodic maintenance, small quantities of solid radioactive waste materials were generated such as evaporator f' concentrates, contaminated rags, paper, plastics, filters, spent ion-exchange resins, and miscellaneous tools and equipment. These were disposed of as solid radioactive waste. At the Beaver Valley Power Station, the compactable wastes are segregated and compressed in 55 gallon drums to minimize disposal volumes. The compressed waste, plus other drums of noncompactable waste, were then shipped offsite for disposal at a commercial radioactive material burial site licensed by the Nuclear Regulatory Commission (NRC) or a state under agreement with the NRC. No radioactive waste material was I buried at the Beaver Valley Power Station site. All containers used for packaging, transport, and disposal of radioactive materials met the requirements of the United States Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Shipments offsite were made in accordance with DOT and NRC regulations. Figure 4.6 depicts solid waste handling at the site. At Beaver Valley Power Station approximately 3,347 cubic feet of radioactive solid waste was shipped offsite in 1986. This is the actual burial volume. The eleven (11) shipments contained a total activity of 445.5 curies. Industrial solid wastes were collected in portable bins, and removed to an approved offsite burial ground. No burning or burial of wastes was conducted at the Beaver Valley Power Station site.,

SECTZON IV FIGURE 4.6 1 DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report SOLID WASTE DISPOSAL DIACRAM SECTION IV FICURE 4.6 WADIDACTIVE Sul.ut WASTE DISPOSAL Misc. Radioactive Compactor and Solid Wastes Dru= ming Station ] D o 'on notTch 3 Sludge Solidify-Radioactive Waste m. j Msansal Evnaorator ina Station ?> i-,- o Spent Radioactive Special ShippLng u Q I. ) Resin Casks & Containers ( 7 ) 00' twoo-g ( l INDUSTRIAL SOLID WASTE DISPOSAL DIACRAM i Water Filtered; FLIters drummed---- .f 9 Sludge From Water m g Treatment Plant, _ r 3 i 3 Sevage Treatment Plant, and Cooling D Cf 'n d 2 Tower 5 Trash Basket - Beaver Valley U Debris and Trash d From Screenhouse \\ ~ a I c = "T 0' e ? 8 ~ Trash & Garbage Storage Bin g C OO @CU _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _. _.. _ _ _. _ _ _. _. _ _

l i SECTION V - A DUQUESNE LTGHT COMPANY l 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING s A. Environmental Radioactivity Monitoring Program 1. Program Description l The program consists of monitoring water, air, soil, f river bottoms, vegetation and foodcrops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table V.A.1. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are i included in parts V-B through V-I of this report. ~ V-B - Air Monitoring V-C - Sediments and Soils Monitoring V-D - Vegetation and Foodcrops V-E - Cow's Milk V-F - Environmental Radiation Monitoring V-G - Fish V-H - Surface, Drinking, Well Waters and Precipitation V-I - Estimates of Radiation Dose to Man I., ,1 _ _... _.....

-m-c- c- ? ~ ... g ;- TABLE V.A.1 y, n M < CONSOLIDATED RADIOLOGICAL ENVIROMENTAL MONITORING PROGRAM g ~ g e' DLc % Sample Analysis ~ Sample Analysis (b) b;. ;A Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Frequency .o I' Gross Seta. ICI -131 I 1. Air Particulate 13. Il 1 Meyer's Farm Continuous Samp1 fag Weekly Composite and Radiciodine 30 4 0.6 Shippingport. PA. (S.S.) with sample collec- -- g Gasum -scan 46.1 3 2.4 Industry. PA tion at least Monthly Composite s weekly 32 15 0.8 Midland. PA (S.S.) Quarterly composite Jd)x 48(a) 10 16.5 Weirton. WV (a) Sr-89.90 51 5 8.0 Aliquippa. PA (S.S.) 47 14 4.8 East Liverpool. OH I i 27 7 6.2 Brunton's Fare 1 28 1 8.7 Sherman's Fara 298 3 8.1 8eaver County Hospital E ~ c I E 2. Direct 30 4 0.6 - St.iopingport. PA (S.S.) Continuous Quarterly ) Gesum-Oose E' Radiation 13 Il s i;6 Payer's Farm (TLD) Annually

e. I 46 3

2.5 Industry. PA(Church) .3 5O l w s 32 15 0.8 Midlano. PA (S.S.) Y 48 (a) 10 16.5 Weirton, WV (a) y K g 45.1 6 2.0 Raccoon Twp. PA Kennedy's crnrs. g l 51 5 8.0 Allquippa. PA (S.S.) jw m w 47 _ 14 4.8 East Liverpool. 0H e 3 r* l 70 1 3.0 West. 8vr. School ? k l 80 9 8.4 Raccoon Park 3 I l 81 J 3.9 Southside School 2 E 82 9 7.1 Hanover Nnicipal 81dg._ j' l 83 10 4.5 Mill Creek Rd l 14 11 2.6 Hookstown i 84 11 8.5 Hancock Co. Children Home 85 12 5.8 Rts. 8 & 30 Intersection k 86 13 6.5 E. Liverpool Cahills House 92 12 3.0 Georgetown Rd. 87 14 7.0 Calcutta Road 88 15 3.1 Midland Heights 89 15 4.7 Ohiov111e 90 16 5.2 Fairview School 10 4 0.8 Shippingport Boro. PA 45 5 2.2 Mt. Pleasant Church 60 13 3.7 Haney's Farm 93 16 1.3 Sunset Hills. Midland 95 10 2.4 McCleary Rd. Hollie Williams E o m ?* .m S.S. - Substation f --. _,s. .s

~ 1---, ~ .m -{ - TABLE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIROINENTAL MONITORING PROGRAM w (Continued) 6 DLC 9 Sample Sample Analysis Type of Sample Points Sector Miles Sample Point Description-Sample Frequency Preparation Frequsacy Analysis (b) 2. Direct 28 1 - 8.7 Shenman's Farm, Continuous Quarterly Gamma-Dose Radiation 71 2 5.6 Brighton Twp. School (TLD) Annually (Continued) 72 3 3.2 Logan School 'f 298 3 8.1 Beaver County Hospital 73 4 2.2 Potter Twp. School ~ ' ' ' ~ ~ ^ ' 74 4 6.8 Comm. Col-Center Twp. 75 5 4.3 Holt Road 76 6 3.8 Raccoon Twp. School 77 5.8 Green Garden Rd { Wayne's) + 3 59 7-1.1 Irons 78 7 2.3 " Ratto6A Mun. Bldg. \\ 27 7 6.2 'Bruntan's Farm N', Y 79 8 4.6 Rt. 15 8 Rt. 151 E 15 14 3.3 Georgetown I. 46.1* 3 2.1 Industry PA g

o 2

3.7 Pine Grove Rd and Doyle Rd E g 91 8 2.4 McCleary Rd. Wilson { g 94 '* I 2 l i w 3-r- m d l 3. Surface 49.1 4 5.0 Arco Polymers (a) Intermittent Monthly Composite of Gross 8 eta 0 ;-. Water 2.1 14 1.3 Downstream (Myland) J s L Composite Samples.(j) Weekly Sample (d) Gross Alpha 5-Collected Weekly Ganna-scan S' n 3 13 0.2 Shippingport Atomic Power Weekly Grab Quarterly Composite Co-60. H-3 i 9 Statisn Discharne Samples Only Sr-89. Sr-90 2 ) '^ 49 (a) J 'f3.% Montgomery Dam j = (Upstream)

s

.I '\\>V " M 2A 13 0.2 Downstream 8vPS Outfall ~ 5 14~ 4.8 East Liverpool (raw water) c ally Grab Sample r ,f Only - Collected Weekly (j) E' y* E ) l ~ 4. Groundwater 13 11 1.6 .- Meyer's Fara 14 'll 2.6 Hookstossit PA -l L1 Georgetbn. PA 15 ^+15 11 3 ?.8 Shippingport Boro Quarterly - Quarterly ' Gamma-scan, Gross l } Beta. Gross Alpha. ^ ~ H-3 l or 5. Drinking 4 14 1.3 Midland. PA (Midland Water ' Intermittent (*} Weekly Composite of ., Gamma-scan, 1-131:. 3 p. I Treatment Plant) Sample (oliecteG Daily Sample (d) Weekly Monthly Composite (d) Gross Alp aha Gross Beta,

• ~

~14 4.8 East Liverpool. ON (Cast Quarterly Composite (d) H-3.Co-60. Sr79. 90 5 Liverpool Water Treatment '4 1, T. Plant) s m l s 6 0.5 DLC New Trainin4 Ido. Weekly Grab Sample. ~ a \\ 3 [w / W A

m am s-w ), % h W h Q s r_ t

ci '

q "'q TABLE'V.'A k i, 3 g C08450LIDAIED RADIOLOGICAL ENVIRONMENTAL MONITOR!NCPROGRAft ' \\ ( Continued ) y i a 3 " ?. Y ~ DLC Sample'~ Sample \\ Adelssis Type of Sample iPoints 7 57 tor _ Miles Sample VWint Description 58S'M,5qv.* L y Preparation Frequency Analysis (b) 7~ 4DiQ,.s 6. Shoreline 2A 13 0.2 Downstream BVPS OutfaII ScQS iWil.tA Semiannual' Gamma-scan.,40ssBeta Sediment ai Gross Alphe 4 3 13 0.2 Vicinity SAPS Discharge 'N Ufantum Isetopic' j 49 3 3.2 Upstream side of Montgomery Sr-::9. 90 i Dam (a) 50 13 8.2 Upstream side of New Cumberland Das IN 7. Milk 25 10 2.1 Searight's Dairy Weekly Weekly sample from I-131 Searight's only Biweekly (g) Blueekly (grazing) Gamma-scan When animals are Monthly (indoors) Sr-89. 90 F ~ on pasture; I-131. Cs-137 a-96(a) % 10 10.3 Windsheimer monthly at other 27 7 6.2 Brunton's Dairy (b) tiu s. . g 29 3 8.3 Nicol's Dairy (h) Monthly Monthly Gamma-scan Sr-89. 90. E&g I-131. Cs-137 g C= I 8. Fish 2A 13 0.2 Vicinity of 8vPS #1 Semiannual Composite of edible Gamma-scan on edible O,". Station Discharge and parts by species (f) portions ~g i Shippingport Dis. Sta. 5 49(a) 3 4.7 Upstream Side of s T Montgomary~ Dam 1~' O 9. Food Crops (Shipp.) 10 4 0.8 (Three locations within Annual at Composite of each Gassia-scan k5 (Georg.) 15 14 3.3 5 miles Selected by harvest if sample species 1-131 on green 3 (Indus.) 46 3 2.5 Company) available leafy vegetabits N^ 48(a) 10 16.5 Weirton WV ~ m g

10. Feedstuff and 25 10 2.1 b.<right's Dairy Farm Monthly Monthly Gasmia-scan _ d Summer Forage Quarterly Quarterly Composite 2

SrGU 7% ~ ~7,

11. Soll 13 11 1.6 Meyer's Farm Every 3 years 12 Core Samplev Ga84 -scan 30 4

0.6 Shippingport. Pa. (1982.1985,etc.) 3" Deep (3" Dia'. Sr-90 46 3 2.6 Industry. Pa. at each locaticn Gross Beta 32 15 0.8 (NorthofSite) Midland (approx. 10' Gross Alpha 48(a) 10 16.5 Weirton, W. Va. radius) Uranium Isotopic $1 5 8.0 Aliquippa. Pa. 47 14 4.8 E. Liverpool. Oh. s 27 7 - ' 6.2 Brunton's Dairy 22 8 0.3 South of EVPS Site 29A 3 8.3 Nichol's Dairy g = BVPS Technical Specification Table 3.12-1 re<uires three(3) dairies be selected on basis of highest potential thyroid dose using m milch census data. See Section V.E. for specific locations sampled.

• =c
• z.

w

i'f TAetE V.A.1 CollSOLIDATED RADIOLOGICAL EIIVIROIIECTAL MONITORIIIG Pancean 6 (Continued) 5 DLC Sample Analysis gg Sample Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Frequency Analysis 12. Precipitation 30 4 0.6 Shippingport, PA Weekly grab 'fonthly Composite Cross 8 47 14 4.8 East Liverpool, OH samples when of arsb samples y-scan 48 to 16.5 Weirton, W available Quarterly Composite H-3, Sr-89 Sr-93 . G R F ? 'g 8 l g 1

a. $ C

.E. A I C s~ e e Z l M3 nO .e 4 -*a 3 4 1 e. ? E a 2 m a 1 4

SECTION V - A DUQUESNE LIGHT COMPANY 1936 Annual Radiological Environmental Report TABLE V. A.1 L CONSOLIDATED 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 LLD's for Gamma Spectrometry are shown in Table V.A.4. (c) Particulate samples are not counted for 2 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is > 10 times the yearly mean of control samples. (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location. (e) Composite samples are collected at intervals not exceeding 2 hours. (f) Weekly milk sample from Searight's Dairy is analyzea.ior I-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 milk samples from Brunton's and Nicol's are collected once per month. (i) 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. (j) Composite samples are collected at intervals not exceeding 2 hours at locations 49.1 and 2.1. Weekly grab samples are obtained at location 3, 49 and 2A. A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5. (k) Two (2) TLDs are collected quarterly and annually from each monitoring location..

SECTION V - A DUQUESNE LIGHT COMPANY s 1986 Annual Radiological Environ = ental Report TABLE V. A.1 CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Additional Notes: Sample points correspond to site numbers shown on maps. All Iodine I-131 analyses are performed within 40 hours of sample collection if possible. All Air samples are decayed for 72 hours before analyzing for Gross Beta. T-.

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

d' Name of f acility Duquesne Light Company Docket No. 50-334 ~ o* Location of Facility Beaver, Pennsylvania Reporting Period Annual 1986 4 (County,5 tate) 8-Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Smpled of Analysis Detection a Mean (r) name "Mean (f) "Mean (f) Reported (Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range
• *R ange Measurements ***

'D Welrton,WV No. 48 Air Particulate Gross (520) 2.5 27(520/520) Shippingport, PA 29(52/52) 26(52/52) 0 and R diolodine Beta (6.9-170) No. 30 (9.1-170) (9.4-130) u (X10-JpC1/Cu. M.) Sr-89 (40) 5 LLD Hg ['O Sr-90 (40) 0.2 LLD S U! I-131 (520) 40 249(37/520) Weirton, WV No. 48 296(4/52) Same as High 0 o :2: (39-561) (121-561) Location yM 00 t~ Gamma (120) p5 Be-7 40 124(120/120) Sherman Dairy No. 28 140(12/12) 110(12/12) O pm f (79-192) (88-176) (89-172) HH o mn K-40 20 37(10/120) Sherman Dairy No. 28 56(1/12) 48(2/12) 0 0.Q (12-73) (23-73) r 83 M> Ru-103 2 16(20/120) Shippingport, PA 20(2/12) 15(2/12) 0% (6.2-30) No. 30 (12-28) (10-20) g n Cs-134 1 9.1(15/120) Industry, PA 13(1/12) 8.5(2/12) 0 n (2.4-14) No. 46 (4.3-13) Cs-137 1 17(20/120) Industry, PA 20(2/12) 17(2/12) 0 [ (4.7-32) No. 46 (8.9-32) (8.9-25) g I-131 70 66(1/120) Aliquippa, PA 66(1/12) 0 N No. 51 Others Table V.A. 3 LLO H Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) t* M Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specificationt (Appendix B) fw

y ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

g Name of Facility Duquesne Light Company Docket No. 50-334 Location of Facility Beaver. Pennsylvania Reporting Period Annual 1986 (county,5 tate) Analysis and Lower Limit Number of j Medita or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations honroutine Sampled of Analysis Detection

• • Mean (f)

Name

• • Mean (r)
  • Mean (t)

Reported 1 (Unit of Measurement) Performed (LLD)

• • Range

~ Distance and Directions ** Range

• • Range Measurements ***

, Montgomery Dam y No. 49 m a os Sediment Gross (8) 0.3 15(8/8) SAPS Olscharge No. 3 20(2/2) 13(2/2) 0 (pCl/g) Alpha (7.0-22) River Mlle -- 34.8 (17-22) (12-13) D l (dry weight) i Gross (8) 1.0 31(8/8) SAPS Discharge No. 3 35(2/2) 31(2/2) 0 p 4 Beta (17-40) River Mile --34.8 (30-40) (29-32) h Sr-89 (8) 0.2 LLD p, $ i

• • to j

Sr-90 (8) 0.04 LLD Sy o Ganma (8) %[ u o c1 y Be-7 0.2 1.l(2/a) Cumberland Dam No. 50 1.4(1/2) LLO O (0.85-1.4) mn K-40 0.5 13(8/8) SAPS Discharge No. 3 15(2/2) 13(2/2) 0 @A (7.7-17) River Mile -- 34.8 (13-17) (12-13) p@ 1 O Co-58 0.2 0.091(1/8) BVPS Discharge No. 02A 0.16(1/2) LLD 0 D 4 River Mlle -- 35 D Co-60 c.2 1.3(3/8) BVPS Discharge No. 02A 1.9(2/2) LLD 0 E (0.12-2.5) River Mile -- 35 (1.2-2.5) H Cs-134 0.02 0.090(2/8) BVPS Discharge No. 02A 0.!!(1/2) LLD 0 h (0.073-0.11) River Mile -- 35 'o et Cs-137 0.02 0.32(8/8) BVPS Discharge No. 02A 0.44(2/2) 0.32(2/2) 0 (0.095-0.46) River Mile -- 35 (0.43-0.44) (0.28-0.36) Ra-226 0.1 2.5(8/8) SAPS Discharge No. 3 3.4(2/2) 2.4(2/2) 0 N (1.0-3.7) River Mile --34.8 (3.0-3.7) (2.2-2.6) m Th-228 0.02 1.4(8/8) SAPS Olscharge No. 03 1.7(2/2) 1.2(2/2) 0 (0.72-2.0) River Mile -- 34.8 (1.3-2.0) (1.2-1.3) Others Table V.A. 3 LLD ia i P i

.m. m r, ._?-- vs ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

H N me of facility Duquesse Light Company Docket No. 50-334 2: Location of facility Beaver, Pennsylvania Reporting Period Annual 1986 4 (County,5 tate) Analysis and Lower Limit Number of p Medium or Pathway Total Number of All Indicator Locations Location with Mighest Annual Mean Control Locations Nonroutine $mpled of Analysis Detection

• • Mean (f)

Name

• *Me an ( f) **Mean ( f)

Reported (Unit of Me#surement) Performed (LLD)

• • R ange Distance and Directions ** Range
  • R ange Measurements ***

Montgomery Dam o No. 49 g Sediment U-233 (8) 0.01 0.52(8/8) BVPS Dicharge No. 02A 0.73(2/2) 0.49(2/2) 0 k (pCl/g) and (0.23-0.77) River Mile -- 35 (0.68-0.77) (0.43-0.54) E. (dry weight) U-234 mHC u-235(8) 0.01 0.022(7/8) BVPS Discharge No. 02A 0.029(2/2) 0.021(2/2) 0 go ,p (0.0046-0.038) River Mile -- 35 (0.019-0.038) (0.015-0.026) W Un u-238 (8) 0.01 0.51(8/8) SAPS Discharge No. 03 0.71(2/2) 0.55(2/2) O c, g (0.16-0.85) River Mile -- 34.8 -(0.56-0.85)(0.34-0.76) c oc t* M' M s t ::: HH u t11 O o9

s. e S

5 1 l r i b-s. .-l ~ b trs ? ? N Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendix 8) ~

m r-- + 1 CA ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Duquesne Light Company Docket No. 50-334 2: Location of f acility Beaver, Pennsylvania Reporting Period Annual 1986 (County,5 tate) l> Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection

• • Mean (f)

Name

• *Me an ( f )
  • Mean (f)

Reported r (Unit of Measurement) Performed (LLD)

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

e, Welrton,WV g No. 48 h External Radiation Gamma 0.05 0.17(170/170) Beaver County Hosp. 0.20(4/4) 0.18(4/4) 0 o (mR/ day) (170 quarterly) (0.11-0.22) No. 298 (0.19-0.21) (0.17-0.18) g H C; Gamma 0.05 0.17(42/42) Calcutta, OH 0.23(1/1) 0.17(1/1) 0 j (42 annual) (0.13-0.23) No. 87 h c: n tn Feed and Forage I-131 (12) 0.01 0.l(2/12) Searight Dairy One Sample (pCirq) (0.01-0.27) No. 25 Location 0 e to Op (dry weight)

e. H 4

Sr-90 (4) 0.003 0.15(4/4) @9 HE (0.09-0.2) ea 8 mo l Be-7 0.3 1.5(8/12) $,q p Gamma (12) 0 q N g (0.6-4.3) 84 O a K-40 0.5 21(12/12) (10.1-40.6) Ru-103 0.05 0.22(1/12) O lE 0 o I-1 31 0.1 0.64(1/12) R tt Cs-134 0.06 0.08(1/12) 0 g Cs-137 0.04 0.13(7/12) 0 (0.07-0.22) p Others Table V.A. 3 LLD 0 t,a Nominal Lower Limit of Detection (LLD) Mean and rance based upon de.cctable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) s Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendix B)

n r-- r ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

H Mme of f acility Duquesne Light Company Docket No. 50-334 E z. Location of Facility Beaver, Pennsylvania Reporting Period Annual 1986 4 (county.5t ate) Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sepled of Analysis Detection

• • Mean (f)

Name

• • Mean (f)
  • Mean (f)

Reported e (Unit of Measurement) Performed (LLD)

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

g Montgomery k Das No. 49 u hME Fish G ama (9) (pC1/g) K-40 0.5 3.3(9/9) Montgomery Dam 3.6(4/4) Same as O p 4@) (wet weight) (2.4-4.9) No. 49 (3.2-4.0) 'High Location an tn ,\\ gy O ~ ' Others Table V.A. 3 LLD S td Weirton, WV No. 48 .i I 8 Food and Garden 1-131 (5) 0.006 LLD pO Crops (pC1/g) H (wet weight) oD Gamma (5) gR Be-7 0.1 0.66(1/5) Industry, PA No. 46 0.66(1/2) LLD 0 ec K-40 0.5 3.4(5/5) Industry, PA No. 46 4.9(2/2) 3.l(1/1) 0 (2.0-6.8) (3.1-6.8) H Cs-131 0.08 0.016(1/5) Industry, PA No. 46 0.016(1/2) LLD 0 o et Others Table V.A. 3 LLD H brM 4 b , Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) Nonroutine reDorted measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications ( Appendix E'

.r-ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

H Name of Facility Duquesne Light Company Docket No. 50-334 ~ Location of Facility Beaver, Pennsylvania Reporting Period Annual 1986 (County,5 tate) I Analysis and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection

• • Mean (f)

Name

• • Mean (f) * *Me an ( f )

Reported l (Unit of Measurement) Performed (LLD)

• • Range Olstance and Directions ** Range
  • Range Measurements ***

m Brunton Dalry p

h. 27 a

i o Milk I-131 (174) 0.5 11.5(34/174) Nichols Dairy No. 29A 18.9(5/20) 0.9(3/20) 0 (pC1/t) (0.4-48) (1.3-45) (0.4-1.3) H Sr-89 (138) 2 LLO E# C - vi Sr-90 (138) 1 3.l(138/138) Telesz No. 101 7.2(3/3) 2.3(19/19) 0 0 ZM (1.1-12) (4.4-12) (1.4-3.2) o oo t-Gamma (145) 7$ m :r b K-40 100 1412(145/145) Telesz No. 101 1753(3/3) 1324(20/20) 0 "H 7 (994-1950) (1540-1950) (1210-1540) n1 n D 52 1-131 10 31(15/145) Collins Dairy No. 69 66(2/7) LLD 0 h9 (1.2-95) (37-95) E *$ 0 A Cs-137 5 8.9(24/145) Collins Dairy No. 69 14(2/13) 9.0(2/20) 0 (5.5-19.9) (8.7-19.9) (8-10) c Others Table V.A. 3 LLO b !? l et t rv Y= t" M l .L Nominal Lower Limit of Detection (LLD) i Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

• • • Nonroutine reported measurements ace defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendia B) l l

L

n .c ~, _. r. us [Nv!R0sMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

g H Nme of Facility Duquesne Light Company Docket No. 50-334 g z Location of Facility Beaver. Pennsylvania Reporting Period Annual 1986 (county,5 tate) 1 Analysis and Lower Limit Number of Meditse or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Septed of Analysis Detection

• • Mean (f)

Name "Rean (f) "Mean (f) Reported (Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range
  • R ange Measurements ***

e 4 Montgomery Dan No. 49 Surf ace Water Gross (72) 2 LLD (pCi/f) Alpha D E Gross (72) 1 5.5(71/72) SAPS Discharge No. 03 7.l(12/12) 4.8(12/12) 0 eo Beta (1.5-17) (2.7-16) (2.3-6.1) pE >c G ama (72) - $ p3 o :: Co-60 5 15(1/72) SAPS Discharge No. 03 15(1/72) LLD 0 7M d. Sb-125 10 44(1/72) SAPS Discharge No. 03 44(1/12) LLD 0 0O v. wH mn fS D Others Table V.A. 3 LLD 80 Sr-89 (24) 2 LLD M > Sr-90 (24) 0.5 LLD bl k l3 g Co-60 (24)(a) 2 LLD w Tritium (24) 100 2012(14/24) BVPS Discharge No. 02A 6364(4/4) 208(2/4) 0 (84-17000) (84-17000) (86-330) Eo O rt i H b (a) Co-60 analyzed by high sensitivity method. g l A. l { Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) w Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the 8eaver Valley Power Station Technical Specifications l (Appendix 8) l l

_m n_ _ r---- w. m ENVIRONMENTAL RADIOLOGICAL MONITDRING PROGRAM Sipewty g. As Nme of Facility Duquesne Light Company Docket No. 50-334 O* Location of Facility Beaver, Pennsylvania Reporting Period Annual 1986 4 .(County,5 tate) 4 Number of "j Analysis and Lower Limit. Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Monroutine r Sampled of Analysis Detection

• • Mean (f)

Name

• • Mean (f)
• Nan (f)

Reported e (Unit of Measurement) Performed (LLD)

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

0 y Drinking Water I-131 (156) 0.5 0.5(4/156) Midland PA No. 04 0.5(4/156) o (oct/f) (0.3-0.6) River Mlle -- 36.3 (0.3-0.6) a rc Gross (36) 0.6 LLD C Alpha hb QQ Gross (36) 1 3.7(35/36) E. Liverpool, OH No. 05 4.l(12/12) Beta (1.4-6.1) River Mile -- 41.2 (2.2-6.1) o2 wm Sr Gamma (156) Table V. A. 3 LLD Sr-89 (12) 1.5 LLD mn 8 Sr-90 (12) 0.5 LLD

s 9 1

$Q l Co-60 (12)(a) 2 LLD n 0 Tritium (12) 100 171(7/12) DLC Training Bldg. 207(3/4) (130-310) No. 6 (150-310) h l a ? ? '8 a 9 P m (a) Co-60 analyzed by high sensitivity method. 4 ~> Nominal Lower Limit of Detection (LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (f) Mean and range based upon detectable measurements only. Nonroutine repot ted measu ements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical. Specifications (Appendia B) I

~ v m_ _% -- y tn ENVIRONMENTAL RADIOLOGICAL MONITORING PR0 wast SisetARY g H Nme of Facility Duouesne Light Campany Docket me. 50-334 g Z Location of Facility Beaver. Pennsylvania Reporting Period Annual 1986 (County state) 8 .I Analysis and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Monroutine S apled of Analysis Deta: tion

• • Rean (f)

Nme

==Rean (f)

• • Rean (f)

Reported (Unit of Measurement) Performed (LLD)

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

e Georgetown, Pa. No. 15 g S Ground Water Gross (16) 2 LLD (pct / liter) Alpha %ec Gross (16) 1 4.0(11/16) Shippingport, PA 4.6(3/4) 2.8(3/4) 0 yg Beta (1.7-6.6) No. 11 (3.2-5.9) (1.8-3.8) o. Gamma (16) Table V.A. 3 LLD r$ o Tritium (16) 90 187(11/16) Meyer Fars No. 13 220(2/4) 183(3/4) 0 %[ 'l (130-280) (160-280) (130-250) gg ,y wH EO $ sa a it 84 9 tkc etnW 2 3 9. 'r in N No6ainal Lower Limit of Detectiori (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

• • • Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendia B)

~ ~ ~ m v en ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SLNMARY r1 O N me of Facility Duquesne Licht Company Docket No. 50-334 s S ~ Location of Facility Beaver, Pennsylvania Reporting Period Annual 1986 (County,5t ate) t Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Septed of Analysis Detection

• • Mean (f)

Name

• • Mean (f)
  • Mean (f)

Reported c (Unit of Measurement) Performed (LLD)

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

Weirton, WV No. 48 Precipitation Gross (40) 2 8.2(38/40) Weirton, WV 10(12/12) Same as High 0 y (pC1/f) Beta (0.7-31) No. 48 (1.7-31) location p E Gama (49) gg Be-7 40 111(19/49) E. Liverpool, OH 134(5/16) 109(12/15) 0 I y l (59-269) No. 47 (87-269) (66-230) 0 $r K-40 20 ' 72(1/49) E. Liverpool, OH 72(1/16) 0 No. 47 a= w HH 8 Pu-103 2 8.5(3/49) Shippingport, PA 8.9(1/18) 8.3(2/15) O (7.38-9.15) No. 30 (7.4-9.2) pg k3G 1-131 10 48(10/49) Shippingport, PA 59(4/18) 43(3/15) 0 (8.8-95) No. 30 (13-95) (14.62) 0 Cs-137 1 8.8(4/49) Weirton, WV 10(4/15) Same as High (6.8-13.6) No. 48 (6.8-13.6) Location a Others Table V.A. 3 LLD Sr-89 (3) 2 LLD E ? Sr-90 (3) 0.5 LLD r1 rt H-3 100 130(1/3) Shippingport, PA 130(1/1) LLD 0 No. 30 Ywr t1 1 Nominal Lower Limit of Detection (LLD) N Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) Nonroutine r(ported measurements are defined in Regulatory Guide 4.8 (MARCH 1975) and the Beaver Valley Power Station Technical Specifications (Appendix B) E.

/ s SECTION V - A DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report ( ( V. ENVIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program (continued) 2. Summary of Results All results of this monitoring program are summarized in ( ( Table V.A.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). Summaries of results of analysis of each media are discussed in Sections V-B through V-H and an assessment of radiation doses are found in Section V-I. Table V.A.3 summarizes Beaver Valley Power Station pre-operational ranges for the various sampling media during the years 1974 and 1975. Comparisons of pre-operational data with operational data indicate the ranges of values are in i good agreement for both periods of time. Activity detected was attributed to naturally occurring radionuclides. BVPS effluents, previous nuclear weapons tests and the Chernobyl Nuclear Plant accident in the Soviet Union on April 25, 1986. Remaining detected activities were near the lower limit of their detection (LLD) and are attributable to the normal statistical fluctuation near the LLD level. The conclusion from all program data is that the operation of the Beaver Valley Power Station has resulted in insignificant changes to the environment. 3. Quality Control Program The Quality Control Program implemented by Duquesne Light Company to assure reliable performance by the DLC contractor and the supporting QC data are presented and discussed in Section III of this report. The lower limits of detection for various analysis for each media monitored by this program by the DLC Contractor Laboratory are provided in Table V.A.4.

k SECTION Y - A DUQUESNE LIGHT COMPANY TABLE V.Ae3 1986 Annual Radiologicci Environmental R: port (Page 1 of 4) L TABLE V.A.3 (Page 1 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

I Name of Facility Beaver vallev Power Station Docket No. 50-334 Incation of Facility leaver. Penasv1vania Reporting Period CT 1974 - 1975 (County. State) FRE-CPJLATIONAL PROGRAN SQ9 TART (COMBINED 1974 - 1975) Medium or Fathway taver Limit $septed Analysis and Total Number of All Indicator tocations t (Unit of " 2ement) of Analysis Performed Detection 1.1D Meaa. (f) Ranae F 3/40 0.6 - 1.1 Serface unter Crose Alpha (40) 0.3 0.75 Grose Beta (120) 0.6 4.4 /120 2.5 - 11.4 Comma (1) 10 - 60 < 11D Tritius (121) 100 300 /121 180 - 800 $r-89 (0) St-90 (0) C-14 (0) Drinking unter I-131 (0) Cross Alpha (30) 0.3 0.6 '/50 0.4 - 0.8 08/208 2.3 - 6.4 Crose Beta (208) 0.6 3.8 Comma (0) Tritium (211) 100 310 /211 130 - 1000 C-14 (0) $r-89 (0) Sr-90 (0) Cround Water Cross Alpha (19) 0.3

• 11D I

I3/75 *I 1.3 - 8.0 Cross seta (76) 0.6 2.9 II Triti m (81) 100 440 /81 80 - 800 Ceema (1) 10 - 60 < 11D 35/ 188 0.002 - 0.004 Air Particulates Cross Alpha (188) 0.001 0.003 and Caseous 927/927 0.02 - 0.32 pC1/m3 Crose Beta (927) 0.006 0.07 3r-89 (0) Sr-40 (0) 2/816 0.07 - 0.08 1-131 (816) 0.04 0.08 Comma (197) 122/197 0.01 - 0.16 ZrNb-95 0.005 0.04 $0 Ra-106 0.010 0.04 /197 0.02 - 0.09 Co-141 0.010 0.02 /197 0.01 - 0.04 co-144 0.010 0.02 "/197 0.01 - 0.04 Others e 11D SECTION V --A DUQUESNE LIGHT COMPANY TABLE VeA.3 1986 Annual Radiological Environn ntal R;part (Page 2 of 4) TABLE V.A.3 (Page 2 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

s L Name of Facility Beaver Valley Power Station Docket No. 50-334 I Location of Tacility Beaver. Pennsylvania Reporting Period CT 1974 - 1975 [ (County. State) PRE-OPERATIONAL PROGRAM SI2etART (COMBINED 1974 - 1975) Media or Factusey !auer Limit Sampled Analysis and Total Weber of All Indfi.ator Locations (Unit of Measurements of Analysis Performed Detection LID Mean. (f) Yanne Soil Groes A1Pha (0) PCi/g (dry) (Template Samples) Grose Beta (64) 1 22 64/C 14 - 32 1 St-89 (64) 0.25 0.4 /64 Sr-90 (64) 0.05 0.3 A /64 0.1 - 1.3 U-234,235.238 (0) Game (64) 03 K-40 1.5 13 /64 5 - 24 56/ Cs-137 0.1 1.5 64 0.1 - 6,8 I/4 0.2 - 3 Co-144 0.3 1.1 6 U /4 0.1 - 2 ZrNb-95 0.05 0.3 6 Em-106 0.3 1.1 /64 0.5 - 2 Others < LID Soil Cross Alpha (0) PC1/g (dry) (Core Samples) Grose Beta (8) 1 21 'g/8 16 - 28 St-89 (8) 0.25 < LLD 5/8 0.08 - 0.5 Sr-90 (8) 0.05 0.2 Geemma (8) K-40 1.5 13 8/8 7 - 20 Cs-137 0.1 1.2 7/8 0.2 - 2.4 1 Co-60 0.1 0.2 /8 Others < LLD s r SECTION V - A DUQUESNE LIGHT COMPANY TABLE Ve A.3 1986 Annual Radiological Environmental Report (Page 3 of 4) ( [ b TABLE V. A.3 (Page 3 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Beaver Vallev Power Station Docket No. M 14 cation of Tacility leaver. Penaativania Reportin8 Level CT 1974 - 1975 (County. State) FRE-OPESATICEAL PROGRAM SDetART(COMBINED 1974 - 1973) tandium w rethuey Zeuer Limit sampled Analysis and Total Ikeber of All Indicator 14 cations (Unit of Measurement) of Analveio Performed Detection 1.12 Neae. (f) Rasse pC1/8 (dry) ~ (0) Sediments Croce Alpha 33f33 3 - 30 Cross seta (33) 1 18 3r-90 (0) U-234.235, 238 (0) Camas (33) 13 33/33 2 - 30 33 E-40 1.$ 13 /33 2 - 30 21/3 0.1 - 0.6 Ca-L37 0.1 0.4 3 ZrNb-95 0.05 0.8 /33 0.2 - 3.2 Ce-144 0.3 0.3 /33 0.4 - 0.7 0I Ru-106 0.3 1.3 /33 1.3 - 1.8 Others e 11D Foodstuff Ceema (8) 0 E-40 1 33 /8 10 - $3 1/8 Ca-137 0.1 0.2 1 trNb-95 0.05 0.2 /8 0I Ru-106 0.3 0.8 /4 others e 113 80 Feedstuff Crose Beta (80) 0.05 19 /80 8 - 30 3 /81 0.04 - 0.93 $r-89 (81) 0.023 0.2 8/81 0.02 - 0.81 $r-90 (41) 0.00$ 0.4 Camas (81) 15 E-40 1 19 /81 $. 44 Cs-131 0.1 0.$ '/ 81 0.2 - 1.6 I/81 0.9 - 2.6 Co-144 0.3 1.3 2Nb-95 0.05 0.8 /81 0.2 - 1.8 Ru-106(b) 0.3 1.4 /81 0.6 2 2.3 others a 1.12.

m-L SECTION V - A DUQUESNE LIGHT COMPANY TABLE VeAe3 1986 Annuni Radiologicsl Envir nmental Rsp rt (Pago 4 of 4) TABLE V.A.3 (Page 4 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

L Name of Facility Beaver Valley Power Station Docket tio. 50-334 te.u tion of Facility Beaver. Pennsylvania Reporting Level CT 1974 - 1975 (County, State) FRE-OFERATIONAf. PROCRAM SI29 TART (COMBINED 1974 - 1975) mat = or Pattuny teuer Limit { Sampled Analysis and Total thaber of All Indicator 14 cations (Unit of Measurement) of Analysis Performed Detection 11D Mean. (f) Ranae Milk I-131 (91) 0.25 0.6 'lJ1 0.3 - 0.8 '/ Sr-89 (134) 5 7 134 6 - 11 U2 Sr-90 (134) 1 5.3 /134 1.5 - 12.8 i Casmar (134) D Co-137 10 13 /134 11 - 16 Others e 11D External Radiation y - Monthly (599) 0.5 mR

• 0.20 SM/599 0.08 - 0.31 ma/ day 193 y - Quarterly (195) 0.5 mA
• 0.20

/195 0.11 - 0.38 '8 y - Annual (48) 0.5 m1

• 0.19

/48 0.11 - 0.30 Fish Crose Beta (17) 0.01 1.9 U/17 1.0 - 3.2 17/7 0.02 - 0.50 Sr-90 (17) 0.005 0.14 1 Camma (17) 1 E-40 0.5 2.4 /17 1.0 - 3.7 Other e 11D );. 4 11D in units of MR - Lower and of useful integrated exposure detectability range for a paselve radiation detector (TLD). ("I One outlier not included la mean. (Vater taken from dried-up spring with high sediment and potaesium content. !!at considered typical groundwater sample.) OI May include au-106 Ru-103, se-7. _., I

ta MoH ee O DUQUESNE LIGHT COMPANY z TABLE V.A.4 TYPICAL LLDs

• FOR GAMMA SPECTROMETRY Milk Sediment Water AirPa3ticulages Vegetation

& Soil Fish 5 'I Nuclide (pC1/ liter) (10' pCl/m ) (pCi/kg dry) (pCi/g dry) (pCi/g wet) g Be-7 30 20 50 0.03 0.05 g n-40 60 20 g Cr-51 40 10 100 0.05 0.1 Mn-54 3 0.5 30 0.02 0.03 g Co-58 3 0.6 30 0.02 0.03 0.g Fe-59 6 1 60 0.03 0.06 Co-60 3 0.6 30 0.02 0.03 In-65 8 1 70 0.04 0.07 Y Zr/Nb-95 5 2 50 0.03 0.05 Ru-103 3 2 40 0.03 'O.04 E Ru-106 30 5 30 0.02 0.03 k at m Ag-110M S 3 30 0.02 0.03 o I-131 4 2 30 0.02 0.03 l Te-132 4 2 20 0.01 0.02 $e I-133 4 2 20 0.01 0,02 ed Cs-134 4 0.6 30 0.02 0.03 g Cs-136 6 0.6 50 0.03 0.05 3 Cs-137 4 0.6 20 0.02 0.03 N Ba/La-140 10 6 40 0.02 0.04 Cc-141 6 2 60 0.03 0.06 +4 cc-144 30 5 200 0.1 0.2 Ra-226 60 6 600 ' O.3 0.6 Th-228 10 1 60 0.03 0.06

• At time of analysis (DLC Contractor Lab).

Activity detected in all sampics. NOTE 1.on.er Level of Detection is defined in Beaver Valley Power Station Technical Specifications.

s t L SECTION V - B DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report I ( V. ENVIRONMENTAL MONITORING B. Air Monitoring 1. Characterization of Air and Meteorology ( The air in the vicinity of the site contains pollutants t 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 I a. Program The air is sampled for gaseous radiciodine and radioactive particulates at each of ten (10) off-site air sampling stations. The locations of these stations are listed in Table V.A.1 and shown on a. map in Figure 5.B.1. Samples are collected at each of these stations by continuously drawing about 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 radiciodine sampling. Samples are. collected for analysis on a weekly bas is. The charcoal is used in lhe weekly analysis of airborne I-131. The filters are analyzed each week for gross beta, then composited by station for monthly analysis by gamma spectrometry. They are further composited in a quarterly sample from each station for Sr-89 and Sr-90 analysis. In order to reduce interference from natural radon and thoron rndioactivities, 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" x 1/4" planchet and counting it in a low background, gas flow proportional counter.

4 SECTION V - B DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING B. Air Monitoring (continued', L 2. Air Sampling Program and Analytical Techniques (continued) ( b. Procedures (continued) Gamma emittels are determined by stacking all the filter papets from each monitoring station collected during the month and scanning this composite on a lithium drifted germanium (Ge(L1)) gamma spectrometer. I Radiciodine (I-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. t i

SECTION V - B FIGURE 5.B.1 DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report L FIGuttE 5.B.1 DMRONMENTAL WODSTOWNB LOCATIONS-AIR St#UfG LOCATICF6 N vaa'eea com AIR SNf1_IMi STATICf6 f ( SDLEL LDC8IlW 13 finR's Dain FARM h. I

• dever

'p, #" 27 B M ON'S On! W F W 28 S a n's Dar n j f, ~' ,, L * ** '3 ' 29B BEAVER OMTV lbSPITAt. [^~

• i 30 SHIPP!NGRAT ibRO fe

( l N'4 ? '\\ - - '~ 32 Mituto e6 ) e-46 ImTw gg 47 EAST LIWRRJOL, Oi!O h.. r,' 48 WIRTcm Wsr VIRGIN!A S ~M "D p 51 A.rQUIPPA O N / .) l 'l ,3. k.._\\

• • i

~-- s ..c. 1 + \\ u,,,,, n I .t, /,, 's 4,, m i ][ [ O*'***/ lj g 4" 4 4 / - ~ ~ ~ +' c 'h w, f eu~ [., .,.r' 1 K: A\\ ,. /.r a ~@M I: '1,1 wJ / .c w g;lE l{ j/ 44w== g'5 ~, - #'F' hi y /esavs=coum y = 5-s. \\ I 's N f j 's .'t* s We4+rs %. see. e (Y%,,,, AIRS /&Llf6STATI0fG i w.. I FIGif 5.B.1 6 i.

i SECTION V - B DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report ( l V. ENVIRONMENTAL MONITORING s B. Air Monitoring (continued) 2. Air Sampling Program and Analytical Techniques (continued) f b. Procedures (continued) Strontium-89 and Strontium-90 activities are determined in quarterly composited air particulate filters. Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered. Half of the filtrate is taken for strontium analysis and is reduced in volume by evaporation. Strontium is precipitated as Sr(NO ): using fuming (90%) 3 nitric acid. An iron (ferric hydroxide) sravenge is performed, followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Sr-89 activity is determined by precipitating SrCO from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm aluminum absorber for level beta counting. 3. Results and Conclusions A summary of data is presented in Table V.A.2. a. Airborne Radioactive Particulates A total of five hundr'ed twenty (520) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years with the exception of short-term increases due to the Chernobyl Nuclear Plant accident in the Soviet Union on April 25, 1986. Figure 3.b.2 illustrates the average concentration of gross beta in air particulates. 68-

l 1I v $ <1 o s 's9M P F" t ESCh COH ng! i i - m. 005~ ?RSSS-msli= g a _f CED v ^ V ON ~ 689 \\ 1 n / T v C O SE TA L P A U E C S v I TR A P m G R UA I A N I ue A t v T Js EB v S N e SO N R U \\ J1 g G l-) F0, t. I n A S a6 Y N l8 A O P9 N I I 1 l r TA 1 e, R w5 i o2 T P N l R E y ri P C ar A N ep O lA c C u l N - E R G l A yt A R b n N E oe V nd ri A i N ec h c CA BEF N = AJ = 1 a 1 e 2 s s 8 s. j g3' ,mf l { l1 ii li {l\\I,

f L I ( SECTION V - B DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report ( V. ENVIRONMENTAL MONITORING B. Air Monitoring (continued) N 3. Results and Conclusions (continued) a. Airborne Radioactive Particulates (continued). The weekly air particulate samples were composited to one hundred twenty (120) monthly s amples which were analyzed by gamma spectrometry. Naturally occurring Be-7 was present in every sample. Occasional traces above detection levels of other .r. naturally occurring nuclides such as K-40 were present. Radionuclides attributable to the ( Chernobyl Nuclear Plant accident are Cs-134, Cs-137 pq and Ru-103. These are listed in the summary Table V.A.2. Examination of effluent data from the Beaver Valley Power Station demonstrated that none of the slightly elevated results are attributable to the operation of the power station. A total of forty (40) quarterly samples were each analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 was detected. Based on the analytical results, the operation of Beaver Valley Power Station did not contribute to any increase in air particulate radioactivity during CY 1986. b. Radiciodine A total of five hundred twenty (520) weekly charcoal filter samples were analyzed for I-131. No detectable concentrations were found at any locations with the exception of short-term increases due to the Chernobyl Nuclear Plant accident. Figure 5.B.3 illustrates the average concentration of I-131 in charcoal filter samples. ) Based on analytical results, the operation of Beaver Valley Power Station did not contribute to any increase in airborne radiciodine during CY

1986, t

rwa J { .noitceteD fo timiL ravoL 5=E 8 9 1 CED VON TCO PES GUA .LUJ NUJ YAM MPA MAM BEF NAJ 1s. w 6891 52 lirpA b' tnediccA .tnalP rewoP raelcuN lybonrehC r 1 r 1r l P Ir i P r 9 r 1 ri r r 1 r3 r i w y 11r1yf r ' lr 1r 1r1r <r 1r i r 1 ri r 1r3 r1r1r 1r1 r3 r 1 r 1 r 1r 1 r3r 1 r 1 r ir 1r 1r 9 /... ? o 1 O \\r1 - N - es. a S 2 \\ dO T y sr 2 1 L 8r ee t 9E i N l 1 8 I am u, bS E on C%o

• Z o iC 2m*

sc w \\/ E I a re 'C m. m- \\, l so 1 l 1 z l e e a SRETLIF LADCRAHC NI 131-I FO SNOITARTNECNOC EGAREVA \\ E nu m ~

4') SECTION V - C DUQUESNE LIGHT COMPANY s 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING ( 5 s C. Monitoring of Sediments aad Soils (Soil Monitoring is f required every 3 years was not requ. ired in 1986) l y,' 1. Characterization of Stream Sediments and Soils f The stream sediments consist largely of sand and silt. Soil samples may vary from sand and silt toia heavy clay with variable amounts of organic matefial. .( k l 2. Sampling Program and Analytical'Techniqu q a. Program. t River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and Shippingport disdharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table V.A.1 and are shown in Figure 5.C.1. .t Bottom sediments are analyzed for gross alpha ar.d 4 beta activity, strontium, uranium, and the gamma- \\ emmitting radionuclides. f j b. Inalytical Procedures fG_ross beta -sedimentsandsoilsareanalyzed[fo'r gioss beta by mounting a 1 gram portion of dried sediment in a 2" planchet. The sample is counted in af ow background, gas flow proportional counter. l Selt absorption correctior.s are made on the basis of sample weight. Gross alpha activity of sediment or soil is analyzed in the same manner as gross beta except that the counter is set up to count onl:t alpha. Gamma analysis of sediment or soil is performed in a 300 ml plastic bottle which is corated by a gamma spectrometer. . I

SECTION V - C FIGURE 5.C.1 DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report SEDIliENTS AND SOILS FIGURE 5.C.1 s DMitDNedGSTA4. WO84TONNB LOCATIONS-SH0ELIE SEDIENTS & S0ll N La"*** 8"'af f 3.AwmCOWIE, l. )b\\ 9GEIN SFDITN'T-l ] g ( k *ar'*' 84, ' " W'. M 2A Downstrears R@S OAfall \\ 3 Vicinity SAPS Dischat.e l %,, L... l 's. 49 Upstran Side of ftmtgwery i 50 L trurg Side of tes )'I Ifa ,t. t. w=" ~ Wa,v, M-s p,pe.e ) r* 8I ponrr mCATICH \\ W %'s Farr's j-(. l 21 South of BVPS Site 27 Brmtzm's Daizy g

• • -j Abe Je.weesy 29A Nichol's Dairy

/,# 7 l 30 Shimitancrt, PA g N h* 32 Midlard I ~. g 46 Irdustry, PA [ 47 E. Liverpool, O! 4l

• /

i e- / 48 Weirton, W.VA. 51 Aliquippa, PA chew //e f ,,...?'E ^ '~h'

)

m

• * ~ ~ ~ ~ ~ ~ -

r.; f e a

u...,

.) g Q b ~A

• Mj',

/* ,a / -, E.i

n -

c' > E7 i f a.a , f,'.**\\ y *s ' r ~/' J i o ,.,s:~/ 51 R, O,a \\ W \\ l 5' 9 2 W Jye4***'**,/ E i /,,,. n,a, ^'w' y a y g 5 CDo, s. 1 .~ \\ l Weir ks %. 9 ! s s 4 O* Ju/e of Hees

• - ~ ~

p.. - \\ ~ _ _l 88., o, %s l

SECTION V - C DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report { V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was not required in 1986) (continued) 2. Sampling Program and Analytical Techniques (continued) b. Analytical Procedures (continued) Strontium 89 and 90 are determined by radiochemistry. A weighed sample of sediment or soil is leached with Nitric Acid RN0. A stable 3 carrier.is added for determination of recovery. Strontium concentration and purification is ultimately realized by precipitations of strontium nitrate in fuming nitric acid. Additional hydroxide precipitations and barium chromate separations are also used. The purified strontium is converted to a carbonate for weighing and counting. Samples are counted soon after separation (5 - 7 days is allowed for yttrium ingrowth'). Activities are calculated on the basis of appropriate Sr-89 decay and Y-90. Separate 2 mounts covered with a 80 mg/cm aluminum absorber are used for counting in a low background beta counter. Uranium isotopic analysis of sediment and soil samples were performed by alpha spectrometry after leaching and isolation of the uranium by an ion exchange chromatography plus mercury cathode electrolysis, then electroplated onto a planchet. 3. Results and Conclusions A summary of data is presented in Table V.A.2. a. Sediment A total of (8) samples were analyzed for gross alpha and gross beta. Results were comparable to previous years. A total of eight (8) samples were analyzed for Sr-89 and Sr-90. No Sr-89 or Sr-90 was detected. j

r SECTION V - C DUQUESNE LIGHT COMPANY u 1986 Annual Radiological Environmental Report ( V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was not required in 1986.) (continued) 3. Results and Conclusion (continued) a. Sediment (continued) A total of eight (8) samples were analyzed by gamma spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was found in every sample and Be-7 was found in two. samples. Small amounts of Cs-137 from previous nuclear weapons tests were found in all river sediment samples including upstream above Montgomery Dam which are unaffected by plant effluents. Small amounts.of Co-58, Co-60, Cs-134 and Cs-137 were detected in the Beaver Valley Power Station discharge area and are attributable to station releases. The 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. A total of eight (8) samples were analyzed by alpha spectroscopy for uranium. Naturally occurring uranium was found in all samples. The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River sediment. The positive results detected are attributable to authorized releases from the Beaver Valley Power Station and are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive. -

SECTION V - D DUQUESNE LIGHT COMPANY { 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING l D. Monitoring of Feedcrops and Foodcrops r; 1. Characterization of Vegetation and Foodcrops According to a survey made in 1985, there were approximately 610 farms in Beaver County. The principal source of revenue for the farms was in dairy products which amounted to nearly $5,998,000. Revenues from ( other farm products were as follows: l Field Crops. $2,013,000 Fruits. $ 169,000 . Horticulture and Mushrooms. $ 994,000 Meat and Animal i Products. $1,638,000 Vegetables and Potatoes. S 266,000 Poultry Products $ 426,000 The total land in Beaver County is 218,600 acres. Approximately 134,592 acres are forested land and 61,176 acres are pasture and crop land. 2. Sampling Program and Analvtical Techniques a. Program Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 5.D.1. Each sample is analyzed by gamma spectrometry. The monthly samples are composited quarterly sample which is analyzed for Sr-into a 90. A land use census was performed August, 1986 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 V.D.1 for results. Foodcrops (vegetables) were collected at garden locations during the summer of 1986. Leafy vegetables, i.e., cabbage were obtained from Shippingport, Georgetown,

Industry, PA, and

Weirton, WV.

All samples were analyzed for gamma emitters (including I-131 by gamma spectrometry). - - - - -. -

[ m FIGURE 5.D.1 Monrn oncay. dan Af I - -l L -- _. __ _ c,.s,,, OHIO S l f 1* Mint.Aun u 8 "~ oyIo RW% l o l [ / / f . Bono ac \\ E MS I O &/PPINGPoRr \\ g.Qeongerowa R a~ we oot. n E' 0 \\ / y ./ g Gaden l f ? 81 / \\ iE 4 i wasr! O musyuan,, gaw.y ig w egin a ~n./ N to N REACTOR $0 SM 24 N N g 8g i N / j f G u 1 OW j LEGEND: L 8 hs - Vegetable Garden h Feedcrop Searight's Dairy Farm Aedero@p ~y I ENVIRONMENTAL MONITORING PROGRAM FEEDCROP AND FOODCROP LOCATIONS w FIGUE 5.D.1 o ~ ~

SECTION V - D DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report I TABIE V.D.1 Closest Residence and Garden in Each Sector Sector Closest Residence

• Closest Garden
• 1 1.59 mi N

.1.63 mi N 2 1.64 mi NNE 1.68 mi NNE 3 0.45 mi NE 0.62 mi NE 4 O.44 mi ENE 1.04 mi ENE 5 0.47 mi E 1.90 mi E 6 0.98 mi ESE 1.04 mi ESE 7 1.14 mi SE 1.63 mi SE 8 1.08 mi SSE 1.08 mi SSE 9 1.36 mi S 1.93 mi S 10 0.76 mi SSW 1.48 mi SSW 11 1.38 mi SW 1.53 mi SW 12 1.42 mi WSW 2.25 mi WSW 13 2.21 mi W 2.21 mi W 14 2.24 mi WNW 2.24 mi WNW 15 0.89 mi NW 0.92 mi NW 16 0.71 mi NNW 1.02 mi NSW

• Distance and Direction from Reactor..

f SECTION V - D DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING D. Monitoring of Feederops and Foodcrops (continued) 2. Sampling Program and Analytical Techniques (continued) b. Procedures Gamma emitters, including I-131, are determined by scanning a dried, homogenized sample with the gamma spectrometry _ system. A Ge(Li) detector is utilized with this system. Strontium 90 analysis for feedstuff is performed by a procedure similar to that described in V.C.2. A Radiciodine (I-131) is determined by radiochemistry. Stable iodide carrier is first added to a chopped sample which is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and treated with sodium hypochlorite. The iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into chloroform. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is nylon planchette for low level beta mounted on a counting. 3. Results and Conclusions A summary of data is presented in Table V.A.2. a. Feed I A total of twelve (12) samples were analyzed for I-131. Small amounts of I-131 were found in two samples and are attributable to the Chernobyl Nuclear Plant accident. A total of four (4) samples were analyzed for Sr-90. Small amounts of Sr-90 from previous nuclear weapons tests were found in all samples. 'l -SECTION V - D DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING D. Monitoring of Feederops and Foodcrops (continued) 3. Results and Conclusions (continued) a. Feed (continued) A total of twelve (12) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was found in all samples and Be-7 was detected in eight (8) samples. Small amounts of Ru-103, I-131, Cs-134 and Cs-137 were found in one (1) sample and are attributable to the Chernobyl Nuclear Plant accidcut. Cs-137 which was found in seven (7) i sdmples is attributable to previous nuclear weapons

tests, b.

Food-l A total of five (5) samples were analyzed for I-131. No I-131 was detected. i A total of five (5) samples were analyzed by gamma spectrometry. Naturally occurring K-40 was found in all samples and Be-7 was detected in one (1) sample. Cs-137 was found in one (1) sampl'e and is l attributable to previous nuclear weapons tests. t c. The data from food and feed analyses with the exception of fallout from Chernobyl were consistent-with (or lower than) those obtained in the pre-operational program. These data confirm that the Beaver Valley Power Station did not contribute to-radioactivity in foods and feeds in the vicinity of the site. t 1 i l E l 2 SECTION V - E DUQUESNE LIGHT COMPANY. L 1986 Annual. Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk 1. Description - Milch Animal Locations .During the seasons that animals producing milk (milch f. animals) for human consumption are on pasture, samples of fresh milk are obtained from these animals at locations and frequencies noted in Table V.A.1. This l milk is analyzed.for its radioiodine content calculated I as Iodine-131. The analysas 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 location.s out to fifteen (15) miles are identified. Survey data for the most recent survey c nducted in August, 1986 is shown in Figure 5.E~1. 2. Sampling Program and Analy ical Techniques a. Program Milk was collected from three (3) reference dairy farms (Searights, Brunton and Nicol's) within a 10-mile radius of the site and from one (1) control location (Windshimer's) outside of the 10-mile radius. Additional dairies, which represent the highest potential milk pathway for radiciodine based on milch animal surveys and meteorological data were selected and sampled. These dairies are subject to change based upon availability of milk or when more recent data (milch animal census) indicate other locations are more appropriate. The location of each is shown in Figure 5.E.2 and described beles. Number l of Milch Distance and Direction Collection t Site Dairy Animals From Site Period l 25 Searight 40 Cows 2.1 miles-south /sw. Jan. - Dec. 27 Brunton 85 Cows 7.3 miles-southeast Jan. - Dec'. 29A Nichol 50 Cows 8.0 miles-northeast Jan. - Dec. 96 Windsheimer 50 Cows 10.3 miles-south /sw. Jan. - Dec. [. 61** Allison 36 Cows 3.2 miles-west /sw. Jan. - Dec. l l l l -

SECTION V - E DUQUESNE LIGHT COMPANY s 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued) 2. Sampling Program and Analytical Techniques (continued) a. Program (continued) Number of Milch Distance and Direction Collection Site Dairy Animals From Site Period 69** Collins 8 Goats, 1 Cow

• 3.6 miles-southeast Jan. - Dec.

62** Lyon 16 Cows 3.3 miles-west /sw. Jan. - June 98** Foxall (Hammond) 1 Goat

• 2.9 miles-east June - Dec.

10l** Telesz 2 Goats

• 2.7 miles-east Aug. - Dec.

10?.** Ferry 4 Goats

• 3.2 miles-southeast Aug. - Dec.
• Milk Usage - Home Only.
  • Highest potential pathway dairies.

i.

SECTION V - E FIGURE 5.E 1 DUQUESNE LIGHT C051PAhT 1986 Annual Radiological Environmental Report ~ FL URE BEAVER VALLEY MILCH AND BEEF ANIMAL' S'URVEY' N u=ou ** nu s I &~~ as 1 ~w a s,s V y ^ j d. /> \\< ,.m V;.a / [ . '~ l 1,,A, s

y. r

/ = ~ a )' 4 M ,I $..L'.~.l -e---- t t' n.$ 1.." g~.p W [*,.r, ' a 3,

1. "f' p,y j.,

n-- r m [ '" 'apr a- \\ w / .1 . \\- T7 ? e ar i. b i >e s a t' A ' ?** Q an. u 7 i w s l- /s ~s f 3 ~ W'w' e e a a + +< .s i. a C,- - J- ~ ~ ~ ~ sGOATS 's -.s,;3

• COWS SUMMER 1986.

SECTION V - E FIGURE 5.E.2 DUQUESNE LIGHT C0!TANY j 1986 Annual Radiological Environmental Report FIGURE 5.E.2 EMYlR00 MENTAL MONITORING LOCATIONS-MilX N a.awwoes omwry } j suwacodrr 1; ) MILK W( I ] ).. a,a>+ s, m s my. v ' { m i-Site Location sa..e-i 25 Searight [ j [ ,'8' ~,, ' ' 27 Brunton [' " 29A Nicol j 61 Allison gg 62 Lyon c-d*9*"## 69 Collins e A. r' 96 Windshiemer i 101 Telesz E l 98 Foxall +,r. my o .g 0 4 102 Ferry i -i d \\ N e I ,s . y. ' ~ . 1 O

• • j q

4,4erry 1 t l

• 'T *

'*[. Ecever.af ,/ t,_ p,. - Mg t I p' j / 1 --..e i. 01 **' (n Q ~flb r' ne s 4 g .....j -. ;) ('E 69- / kk ii'# h 62 + m, + l l !=> 27 A W v s. -= hk*"* / 4 E z I 1 h' } I Ar w C, DEAVER COUNTY )v 3: s, te9eNGTON COUMTY \\, d N x x k j N Wei, hus %, p i a s + O* J< ale W MoA,s \\ -I Mll.V UTMlff6 Nh' FIGUPE S. E. 2 -

? SECTYON V - E DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report ( V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued) a. Program (continued) The sample from Searight Dairy was collected and analyzed weekly for radiciodine using a procedure with a high sensitivity. Samples from each of the other selected dairies were 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 Spectrometry) and I-131 (high sensitivity analysis). b. Procedure Radioiodine (I-131) analysis in milk was normally l performed using chemically prepared samples and analyzed with a low-level beta counting system. I Gamma emitters are determined by gamma spectrometry of a one liter Marinelli container of milk. Strontium analysis of milk is similar to that of other foods '(refer to V.C.2) except that milk samples are prepared by addition of Trichloracetic Acid (TCA) to produce a curd which is removed by filtration and discarded. An oxalate precipitate is ashed for counting. 3. Results and Conclusions A summary of data is presented in Table V. A.2. A total of one hundred seventy-four (174) samples were analyzed for I-131 during 1986. All I-131 activities in milk were below the minimum detectable level (0.5) with the exception of short-term increases due to the Chernobyl Nuclear Power accident. Figure 5.E.3 illustrates the average concentration of I-131 in the milk samples. A total of one hundred thirty-eight (138) samples were analyzed for Sr-89 and Sr-90. Sr-90 levels attributable to previous nuclear weapons tests were detected in all samples and were within the normally expected range.,

f-(= SECTION V - E DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued) 3. Results and Conclusions (continued) A total of one hundred forty-five (145) samples were analyzed by gamma spectrometry. The predominant isotope detected was naturally occurring K-40. Cs-137 and I-131 attributable to previous nuclear weapons tests and the Chernobyl Nuclear Plant accident were also detected. All results with the exception of fallout from Chernobyl were consistent with (or lower than) those obtained in the preoperational program. These data confirm taat the Beaver Valley Power Station did not contribute to radioactivity in milk in the vicinity of the site.

N El 0 AVERAGE CONCEN,TRATIONS OF I-131,IN MILK --1986 = ISS I M sm G m \\ g Ec 25 wn <\\ Eh s E= k \\ Em EC ( 88 -s h 98 2 As 2 n> 85 'l fx fi A x a .s H \\ M r a / A AA / \\/ \\/ \\/ \\ / v \\ A M y N F, /)\\ fv Vs, v v v' v " y s,sr y" " y,, y' i" s, q-g e A ,r s, [Y i NV ,y 3r 3r 3,. 3r i' t s 3, 3, < r 3, 3, Q if i' 3r .2 rt .25 y H 8 s Chernobyl l'uclear Poger Plant ? Acl ent - April 23, 1936 I id i I I .ex JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1888 fLowerLimitofDetection O

SECTTON V - F DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report t V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring 1. Description of Regional Background Radiation Levels and Sources The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude L variations of 300-400 feet. Most of the land is wooded. The principal geologic features of the region are nearly flat-laying sedimentary beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams. Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 pR/hr. Results for 1986 indicated that background radiation continued in this rcnge. 2. Locations & Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs). In 1986 there were a total of forty-four (44) off-site environmental TLD locations. The locations of the TLDs are shown in Figures 5.F.1 thru 4. Thirteen (13) locations also have QC Laboratory TLDs. Both laboratories use calcium sulphate dysprosium, CaSO. (Dy) in teflon matrix..

l l L SECTION V - F DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring (continued) 2. Locations & Analytical Procedures (continued) The calcium sulfate (Ca30.:Dy) TLDs were annealed shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit = l between the field location and the laboratory was ) corrected by annealing control dosimeters shortly before the field dosimeters were removed from the field location, when shipping the freshly annealed control dosimeters with the exposed field dosimeters to the laboratory for readout at the same time. All dosimeters c-were exposed in the field in a special environmental holder. The dosimetry system was calibrated by reading calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation field. l In addition to TLDs, Pressurized Ion Chambers (PIC) provide continuous integrating monitoring. Sixteen PICS (Sites 1-16) are part of the Sentri 1011 Radiation Monitoring System which is a microcomputer-based data acquisition system. Data from the stations are sent at regular intervals to the Central Processing Unit where integrated doses are calculated. In addition there are 4 four PICS which are AC Radiation Monitors. These are inspected weekly for integrator readings. The locations of the PICS are shown in Figure 5.F.5. 3. Results and Conclusions Data obtained with the contractor TLD (CaSO.:Dy in teflon) during 1986 are summarized in Table V.A.2, and the quality control TLD results are listed in Table III.1. Results for the PICS are listed in Table V.F.1. The annual exposure rate of all off-site TLDs averaged 0.17 mR/ day in 1986. As in previous years, there was some variation among locations and seasons as would be expected. In 1986, ionizing radiation dose determinations from TLDs averaged approximately 62 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 neglible. -

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SECTION V - F DUQUESNE LIGHT COMPANY 1986 Annual' Radiological Environmental Report TABLE V.F.1 Pressurized Ion Chambers - Results Distance and Average Site Location Direction from Site (mR/ day) 1 Industry Hill 0.5 mi N 0.209 2 Industry - Rt. 68 0.9 mi NNE 0.228 3 Industry 2.25 mi NE 0.202 4 Cooks Ferry 0.5 mi ENE 0.218 5 Shippingport Bridge South 0.45 mi E 0.223 6 BVPS Entrance 0.4 mi ESE 0.240 7 Unit #2 Laydown 0.3 mi SE 0.218 8 Birdhill Road 0.9 mi SSE 0.250 9 Past DLCO Microwave 0.35 mi S 0.233 10 DLCO Microwave 0.35 mi SSW 0.216 11 Meyer's Farm 1.45 mi SW 0.240 12 J & L Steel Tie 0.75 mi WSW 0.223 13 F. P. Microwave 1.5 mi W 0.175 14 Midland Substation South 0.6 mi WNW 0.221 15 Midland Substation North 0.75 mi NW 0.233 16 Sunrise Hills 1.1 mi NNW 0.221 AC-201 Raccoon Municipal Building 2.4 mi SE 0.256 AC-202 Kennedy's Corners 2.0 mi NE 0.250 Z-054 Hookstown Substation 2.9 mi WSW 0.229 Y-028 LTV 1.3 mi NW 0.220

SECTION V - G DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING G. Monitoring of Fish 1. Description Fish collected near the site are general,1y scrap fish. During 1986, fish collected for the i radiological monitoring program included carp, catfrbh and small mouth bass. 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 ef fluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by ganma spectrometry. Fish sampling locations are shown in Figure 5.G.1. 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 Ge(Li) detector. 3. Results and Conclusions A summary of the results of the fish monitoring data is provided in Table V.A.2. A total of nine (9) samples were analyzed by gamma spectrometry. The only gamma emitter detected was the naturally occurring K-40 which was found in all samples. This indicates that the operation of the Beaver Valley Power Station has not resulted in radioactivity in fish in the Ohio River. -

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l SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Monitoring of

Surface, 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 plant liquid effluents. Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power Station site. It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water Authority. The intake of the treatment plant is approximately 1.5 miles downstream and oa the opposite side of the river. The next downstream user is East Liverpool, Ohio which is approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream use river water for cooling purposes. Some of these plants also have private treatment facilities for plant sanitary water. Ground water occurs in large volumes in the gravel terraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm. In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. Normal annual precipitation for the. area is 36.29 inches based on 1951 to 1980 data collected at the Pittsburgh International Airport. V p ( SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING (continued) H. Monitoring of

Surface, Drinking, Well

Waters, and Precipitation { continued) 2.

Sampling and Analytical Techniques a. Surface (Raw River) Water The sampling program of river water includes five (5) sampling points along the Ohio River. Raw water samples are normally collected at the East Liverpool (Ohio) Water Treatment Plant (River Mile 41.2] daily and composited into a monthly sample. Weekly grab samples are taken from the Ohio River at the discharge from Shippingport Station Decommissioning Project (River Mile 34.8); and near the discharge from the Beaver Valley Power Station [ River Mile 35.0]. 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 Mile 36.2]. The automatic sampler takes a 20-40 m1 sample every 15 minutes and is collected on a weekly basis. The weekly grab sampics and automatic water samples are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point. The monthly composites are analyzed for gross alpha, gross beta, and gamma emitters. The quarterly composites are analyzed for H-3, Sr-89, Sr-90, and Co-60 (high sensitivity). Locations of each sample point are shown in Figure 5.H.1. 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 m1 every 20 minutes. These intermittent samples are then composited into a weekly sample. A weekly grab sample is also taken at the DLC Training Building in Shippingport, PA. The weekly sample from each location is analyzed by gamma spectrometry. The weekly samples are also analyzed for I-131. -,

SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Monitoring of

Surface, Drinking, Well

Waters, and Precipitation (continued) 2.

Sampling and Analytical Techniques (continued) b. Drinking Water (Public Supplies) (continued) Monthly composites of the weekly samples are analyzed for gross alpha, gross beta, and by gamma spectr6 metry. Quarterly composites are analyzed for H-3, Sr-89, Sr-90 and Co-60 (high sensitivity). Locations of each sample point are shown in Figure 5.H.1. c. Ground Water Grab samples were collected each quarter from each of four (4) well locations (see Figure 5.H.1) within four (4) miles of the site. These locations are: One (1) well at Shippingport, PA One (1) well at' Meyer's Farm (Hookstown, PA) One (1) well in Hookstown, PA One (1) well in Georgetown, PA Each ground water sample is analyzed for gross alpha, gross

beta, tritium, and by gamma spectrometry.

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 monthly and quarterly samples. The monthly samples are analyzed for i gross beta and gamma emitters and the quarterly composites are analyzed for H-3, Sr-89 and Sr-90. Locations of each sample point are shown in Figure 5.H.1. -100-1 -.___,_m._ - ~... _. ._m- ...-x

tn M O Ez 4 (! ). Mc.vrsourny DAA f-E l F - -l I i_____ _ _ s OHJO l (b ? MIDLAbfD ? y I 'I l 4 I ~~ g 5 l .Bo.eo Op \\ US yv Q,.qcongerm up O saimucponr\\ ?: 0 coi. \\ / l H A 4 ~ / 18 $e l \\ l e rs / SO l 8 l j v'""'t"* MJNSYL. VAN /A / $h ( ~4 g- ' g y \\ SA!!PLE SKIPLE SAMPa,ING POINT 8EACTOS2 U i \\ TYPE POilfT DESCRIPTION ( 8/y f" SUdFACE 2A DOWHSTREKI - BVPS \\ p rt l WATER 2.1 DOWNST2EMI - J $ L INTAKE ) ($ D 1 3 SillPPItCPORT STATION DISCHARGE \\ } W 5 EAST LIVG:. POOL WATEP, PLAW \\ g', c I (RAW WAT G) g) V J Pg9 49,t U'PSTREKI - ARCO POLYttERS INTAKE yo 1 M r DEII. KING [^ i WATER 4 M10aAND WATEA PIANT ] rt 5 EAST LIVERPOOL WATER PLAW o 6 DLC NIM TRAINIlc BUILDING g QQg g C WLLL II SHIPPINCPORT BORO M l WATER 13

tEYERS FAI:ll WELL WATER 14 HOOKSTOW'i, PA y

CE0!!GETOWN, PA SURFACE WATER, DRINKING, WATER AND PRECIFITATION I PJEf!PI-33 SHIPPINCPORT, PA gg3 ggg m, TATION 47 EAST LIV S P00L, OH j [NV/Rl0A!AfEAf7ML StrOquty &47swg LOCATIONS - WELLS, SURFACE WATER, DRINKING WATER AND FRECIFITATION i, I l

t> SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Monitoring of

Surface, Drinking, Well

Waters, and Precipitation (continued) 2.

Sampling and Analytical Techniques (continued) e. Procedures Gross alpha and gross beta activities 'are determined first by evaporating one liter of the sample on a hotplate. The residue is mounted and I dried on a 2-inch stainless steel planchet. The sample.is counted in a low background, gas flow proportional counter. Self-absorption corrections are made on the basis of sample weight. Gamma analysis is performed on water sample by loading one liter of sample into a one liter marinelli container and counting on a Ge(Li) gamma spectrometry system. Strontium-89 and 90 are determined on water samples by a procedure similar to that described in V.C.2 except that the leaching step is eliminated. Cobalt-60 is determined-with a sensitivity of 1 pCi/l by evaporating 2 liters of sample on a hotplate and transferring the residue to a 2-inch i planchet. The planchet is counted on a Ge(Li) spectrometry system. Tritium is determined in water samplen by I converting 2 ml of the sample to hydrogen and counting the activity in a 1 liter low level gas I counter which is operated in the proportional range in anti-coincidence mode. Radiciodine (I-131) analysis it. water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system. 3. Results and Conclusions l A summary of results of all analyses of water samples 1 (surface, drinking, ground and precipitation) are provided by sample type and analysis in Table V.A.2. These are discussed below. -102-t 1 -. - ~ ~ ~ _ _. _. - - _. - - - - - - ~ - - _, - -

SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Monitoring of

Surface, Drinking, Well

Waters, and Precipitation (continued) 3.

Results and Conclusions (continued) a. Surface Water A total of seventy-two (72) samples were analyzed for gross alpha and gross beta. All results were within the normal range. A total of twenty-four (24) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co-60. Positive tritium results were detected in the BVPS discharge area and are attributable to station releases. Tritium samples taken upstream and downstream were within pre-operational levels. No Sr-89, Sr-90 or Co-60 (analyzed by the high sensitivity method) were detected. The tritium activity found in the station discharge area is consistent with station data of authorized radioactive discharges and were i within limits permitted by the NRC license. A total of seventy-five (75) samples were analyzed by gamma spectrometry. Co-60 and Sb-125 were detected in one sample taken from the Shippingport Station Decommissioning discharge area. A review of the Beaver Valley Power Station discharge permits was made as the BVPS discharge area is adjacent to the Shippingport discharge area. The review showed no releases from the BVPS site were being conducted at the time of saepling. The concentrations seen are consistent with those reported by the Shippingport Station Decommissioning Project for 1986 and are hundreds of times below the concentrations permitted by DOE 4 i Orders. No other gamma emitting radionuclides were detected. b. Drinking Watcr A total of thirty-six (36) samples were analyzed for gross alpha and gross beta. All results were within a normal range. -103- .m.

a z .3 SECTION V - H-DUQUESNE LIGHT COMPANY-1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Monitoring of

Surface, Drinking, Well

Waters, and Precipitation (continued) 3.

Results and Conclusions (continued) b. Dris. king Water (continued) A total of twelve (12) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity-analysis for Co-60. No Sr-89, Sr-90, or Co-60 were ' detected. The H-3 data were within the preoperational range indicative of normal environmental levels. A total of another one hundred fifty-six (156) samples were analyzed.by gamma spectrometry. No gamma emitting radionuclides were detected by these analyses. A total of one hundred fifty-six (156) samples were analyzed for I-131 using a highly sensitive technique. Trace levels of I-131 were measured in some of the weekly samples. The. results were slightly above the minimum detectable activity of 0.5 pCi/ liter. The positive results could not be attributed to station discharges. The results may be attributed to expected variability in the analyses results of very low levels of activity or other sources such as from medical. c. Well Water A total of sixteen (16) samples were each analyzed for gross alpha, gross beta, H-3 and by gamma spectrometry. No alpha activity was detected in any of the samples. The gross beta and H-3 data are within pre-operational ranges. No gamma emitting radionuclides were detected by these analyses. -104-

SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report .V. ENVIRONMENTAL MONITORING (continued) H. Monitoring of-

Surface, Drinking, Well

Waters, and Precipitation (continued) 3.

Results and Conclusions (continued) d. Precipitation-In previous years precipitation was not normally sampled, however, following the Chernobyl Nuclear Plant accident in the Soviet Union on April 25, 1986 a sampling program was initiated to provide data to the Nuclear Regulatory Commission and appropriate. agencies in Pennsylvania, West Virginia and Ohio. During the weeks immediately after the Chernobyl accident samples were _ analyzed as soon as possible following precipitation, however, as the level of fallout activity decreased to near background the samples were collected in accordance with the schedule described in Section H.2.d. A total of forty (40) semples were analyzed for gross beta. Figure 5.H.2 illustrates the average concentration of gross beta in precipitation. Note the short-term increase due to the Chernobyl Nuclear Plant accident. A total of three (3) samples were analyzed for H-3, Sr-89 and Sr-90. -One positive tritium result was detected which was within normal levels and no Sr-69 or Sr-90 was detected. A total of forty-nine (49) samples were analyzed by gamma spectrometry. Naturally occurring radionuclides detected were Be-7 and K-40. Radionuclides attributable to the Chernobyl Nuclear Plant accident are Ru-103, I-131 and Cs-137. Figure 5.H.2 illustrates the average concentration of Iodine-131 in precipitaticn. Note the short-term increase due to the Chernobyl Nuclear Plant accident. Examination of effluent data from Beaver Valley Power Station demonstrated that none of the elevated results are attributable to the operation of the power station. -105-

~.. . s -.a.. 1 'SECTION V - H DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. . ENVIRONMENTAL MONITORING (continued) H. Monitoring-of

Surface,

-Drinking, Well -Waters, and Precipitation (continued) 3. Results and Conclusions (continued) 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 environmental monitoring program is sufficiently sensitive.

Further, the actual detected concentration (averaged over a year) attributable to Beaver Valley Power Station, was only 0.32% of the Maximum Permissible Concentration allowed by

'he Federal Regulations for water discnarged 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. -106-

U3 H H AVERAGE GROSS BETA AVERAGE I-131 e c c c ? x..........&..........n..........M <~ 199 m a i E "T 58 I e t E I [', - E g p .2 x, I I, l,'s / \\ "E ,r u ', gg .se, J,,so, 10 x'- _ oz ^ ^^ T M W H t-1 ' ( /\\ .' l O%[ iif \\U / \\ \\ / \\ n o 5 m :: a 1 / \\ -e I M E' S g 'N \\ \\ o7 ya y-anm 1 H n o .s n m o si m Chernobyl Nuclear Power Plant u Accident - Aplril 25, 1986 L l I r- .1 w. 'JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 19 8 E 5 PRECIPITATION AVERAGE CONCENTRATIONS OF GROSS BETA AND I-131

T SECTION V - 1 DUQUESNE LIGHT COMPANY ~ 1986 Annual Radiological Environmental Report. V. ENVIRONMENTAL MONITORING I. Estimates of Radiation bose to Man 1. Pathways to Man - Calculational Models The radiation doses to man as a result of Beaver Valley operations were calculated for both gaseous and liquid effluent pathways using NRC computer codes X0QD0Q2, GASPAR, and LADTAP. Dose factors listed ~in the ODCM l 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 with the schedule set forth in Appendix A of I' the BVPS license, were used as the radionuclide activity input. Each radionuclide contained in the Semi-Annual Radioactive Effluent Release Report (noble

gases, particulates, radioiodines and tritium) were included as source terms when they were detected above the LLD values.

All LLD values reported by Beaver Valley Power Station are equal to or lower than those required by the Technical Specifications. All gaseous offluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. When the activity of noble gas was below detection sensitivity, either the inventory based on its MDL or an appropriate but conservative ratio to either measured activity of Kr-85 or Xe-133 was used. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to X0QD0Q2 which in turn provided input for GASPAR. Except when more recent or specific data was available, all inputs were the same l as used in the Beaver Valley Power Station Environmental Sta'tements or in Eegulatory Guide 1.109. The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the " cow-milk-child", and other ingestion pathways. 5 T l I -108-1

SECTION V - I DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING I. Estimates of Radiation Dose to Man (continued) 1. Pathways to Man - Calculational Models (continued) All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using Intrinsic Germanium detectors. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0) The actual data from these analyses are tabulated and used as the radionuclide activity input term in 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 to LADTAP are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109. Pathways, which were evaluated, are drinking

water, fish consumption, shoreline recreation, swimming, and boating.

2. Results of Calculated Radiation Dose to Man - Liquid Releases a. Individual Dose The doses which are calculated by the model described above are to a hypothetical real individual located at Midland since this is the nearest location where significant exposure of a member of the public could potentially occur; therefore, this location is used to calculate the maximum exposure. A breakdown of doses by pathway and organ is provided in Table V.I.1 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 hypothetical real individual are compared to the BVPS #1 annual Technical Specifications limits in Table V.I.2. -109-

TABLE V.I.1 Radiation Dore to Maximum Individual" crir/yr. Beaver Valley Power Station - Liquid Releases MAXIMUM USAGE WHOLE PATHWAY CROUP FACTOR SKIN ORGAN THYROID BONE BODY m M O Fish Consumption Adult 21.0 kg N/A 0.00107 0.0000409 0.000632 0.000703 (Liver) 8 Drinking Water Infant 510 liter N/A 0.00246 0.00235 0.000114 0.00238 (Lung) Shoreline Activities Teen 67 hr. 0.00014 0.00012 G" k TOTAL MREM 0.00014 0.00258 0.00235 0.000676 0.00238 MAXIMUn (Teen) (Adult) (Infant) (Adult) (Infant) 5 INDIVIDUAL (Liver) e e- ? TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE o' TLC {h Ambient Gamma Radiation: 69 d Radionuclides in Body : 28 yg d$ d { Global Fallout 4 TOTAL mrem 101 Located at Midland Drinking Water Intake E o Child is the critical group for bone with a dose of 0.000759 mrem /yr.

1. Pre-operational average ambient gamma radiation d National Academy of Sciences, 'The Effects on Populations of Exposure to Low Levels of h

Ionizing Radiation," BEIR Report, 1980, n

SECTION V - I DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report TABLE V.I.2 Results'of Calculated Radiation. Dose to Man Beaver Valley Power Station - Liquid Releases Maximum Exposure BVPS #1 Percent of Hypothetical Annual Tech. Annual Real Individual Spec. Limits Tech. Spec. mrem mrem Limit TOTAL 90DY Adult 0.00218 3.0 0.073 Teen 0.00123 3.0 0.041 Child 0.00175 3.0 0.058 infant 0.00238 3.0 0.079 ANY ORGAN Adult 0.00258 10.0 0.026 (Liver) Teen 0.00187 10.0 0.019 (Liver) Child 0.00245 10.0 0.025 (Liver) Infant 0.00246 10.0 0.025 (Lung) Maximum Total Body Dose - Capsule Summary mrem 1986 Calculated 0.00238 Final Environmental Statement 0.112 Thyroid' Dose - (Largest Expected Organ Dose) 1986 Calculated 0.00235 Final Environmental Statement 0.96 -111- ~

SECTION V - I DUQUESNE LIGHT COMPANY 1986 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING 2. Results of Calculated Radiation Dose to Man - Liquid Releases (centinued) b. Population Dose The 1986 calculated dose to the entire population of almost 4 million people within 50 miles of the plant was: Largest Isotope Man-Millirem __ Contributors TOTAL BODY 81.6 H-3 79.8 mrem Fe-55 0.68 mrem Co-60 0.75 mrem THYROID 79.7 H-3 79.2 mrem I-131 0.52 mrem 3. Results of Calculated Radiatioa Dose to Man - Airborne Releases The results of caldulated radiation dose to the maximum exposed individual for BVPS airborne rac.ioactive effluents during 1986 are compared to the BVPS annual Technical Specifications limits in Table V.I.3. The doses include the contribution of all pathwavn. A 50-mile population dose is also calculated and provided in Table V.I.3. H-3 is the primary radionuclide contributions to these doses. The results show compliance with the BVPS #1 Technical Specifications limits. 4. Conclusions - (Beaver Valley Power Station) Based upon the estimated dose to individuals from the natural background radiation exposure in Table V.I.1., the incremental increase in total body dose t.o the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit No. L, is less than 0.0001* of the annual background. The calculated doses to the public from the operation of Beaver Valley Power Station - Unit No. I are below BVPS

1. 1 annual Technical Specifications limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public.

-112-

3. TABLE V.I.3 Results of Calculated Radiation Dose to Man (1986) Beaver Valley Power Station - Airborne Radioactivity N El E' = <= BVPS #1 ANNUAL PERCENT OF 50-MILE MAXIMUM EXPOSURE TECH. SPEC. LIMIT ANNUAL TECH. POPULATION DOSE g ORGAN INDIVIDUAL, mrem mrem SPEC. LIMIT man rea 5 8: TOTAL BODY 0.0239 15 0.16 0.258' g a E-e ,1, SKIN 0.0406 15 0.27 0.754 3 c

a. fi l

$9 LUNG 0.0258 15 0.17 0.282 yM me

• h i

THYROID 0.0460 15 0.31 0.408 H EO

14 1,

E$ g a E i n j i a n j i s b M i M 1 w

DISTRIBUTION LIST United States Nuclear Regulatory Commission (18 copies) Attn: Mr. Peter Tam, Project Manager Operating Reactors Branch No. I Division of Licensing c/o Document Control Desk Washington, DC 20555 United States Nuclear Regulatory Commission (2 copies) Office of Inspection and Enforcement Attn: Regional Administrator, Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. A. A. Davis, Secretary Department of Environmental Resources Commonwealth of Pennsylvania 9th Floor, Fulton Building Third and Locust Streets Box 2063 Harrisburg, PA 17120 United States Department of Energy Technical Information Center Post Office Box 62 Oak Ridge, TN 37830 Mr. J. G. Yusko Department of Environmental Resources Bureau of Radiation Protection 121 South Highland Avenue Pittsburgh, PA 15206 J.M. Arthur, Chairman of the Board Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 W. W. von Schack, President and Chief Executive Officer Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 J. J. Carey Senior Vice President - Nuclear Group Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 J. D. Sieber Vice President - Nuclear Group Duquesne Light Company P.O. Box 4 Shippingport, PA 15077

DISTRIBUTION LIST (continutd) J. O. Crockett Senior Manager, Nuclear Operations Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 N. R. Tonet General Manager, N2 clear Engineering and Records Duquesne Light Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 R. E. Martin Manager, Regulatory Affairs Duquesne Light Company Regulatory Affairs Department P.O. Box 328 SEG Building Shippingport, PA 15077 S. L. Pernick Manager, Envircnmental Affairs Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 C. E. Ewing Manager, Quality Assurance Duquesne Light Company Beaver Valley Power Station P.O. Box 186 Shippingport, PA 15077 J. A. Kosmal Manager, Radiological Control Duquesne Light Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 W. F. Wirth Director, Effluent Control and Envirormental Monitoring Duquesne Light Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 B. F. Jones Memorial Library 663 Franklin Avenue Aliquippa, PA 15001

V Telephone (412) 393-6000 Nuclear Group P O Box 4 Shippingport. PA 15077M4 April 23, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station Unit No. 1 Docket No. 50-334, License No. DRP-66 1986 Annual Environmental Report Radiological - Volume #2 Gentlemen: Under the Beaver Valley Power Station Unit No. 1 License DRP-66, and in accordance with the requirements of Specifications 6.9.1.10 of the Technical Specifications, the Annual Radiological Environmental Report is hereby sumbitted. Very truly yours, J. D. Seiber Vice President, Nuclear JWM mb Enclosure cc: United States Nuclear Regulatory Commission Regional Administrator, Region 1 631 Park Avenue King of Prussia, PA 19406 United States Nuclear Regulatory Commission Resident Inpsector Beaver Valley Power Station Dottle Sherman American Nuclear Insurers Library The Exchange Suite 245 g 270 Farmington Avenue i \\ Farmington, CT 06032 %}}