ML20023B760

Vol 2 to Annual Environ Rept,Radiological,1982

ML20023B760
Person / Time
Site:	Beaver Valley
Issue date:	04/25/1983
From:	DUQUESNE LIGHT CO.
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1982 ANNUAL ENVIRONMENTAL REPORT RADf0 LOGICAL - VOLUME #2 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION AND SHIPPINGPORT ATOMIC POWER STATION J

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DUQUESSE LIGHT COMPANY 1982 Annual Radiological Environmental Report ABSTRACT This report describes the Radiological Environmental Monitoring Program conducted during 1982 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous ef fluents and of f-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site.

This report discusses the results of this monitoring during 1982.

The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1982.

There were no radioactive liquid effluents released from the Shippingport Atomic Power Station since radioactive liquids are processed and re-cycled within the plant systems.

The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment.

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DUQUESNE LIGHT COMPANY 1982_ Annual Radiological Environmental Report

-TABLE OF CONTENTS Page Abstract-----------------------------------------------------------

1 I.

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

1 A.

Scope and Objectives of the Program i

B.

Description of the Shippingport and Beaver Valley Site 2

II.

kESULTS & CONCLUSIONS--------------------------------------

6 III. ENVIRONMENTAL MONITORING CONSIDERATIONS--------------------

8 4

A.

Environmental Quclity Contrcl Programs 8

B.

Evaluation of the Quality Control (QC) Program Data 24 C.

Standard Requiraments and Liaitations for Radiological and Other Effluents 24 D.

Significant Changes and Reporting Levels 25 IV.

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

27 4

A.

Monitoring of Liquid Effluents 27 1.

Effluent Treatment, Sanpling, and Analytical 33 Procedures i

2.

Results 34 I

B.

Monitoring of Airborne Effluents 35 1.

Description of Airborne Effluent Sources 35 2.

Airborne Effluent Treatment and Sampling 40 3.

Analytical Procedures for Sampling Airborne Effluents 44 4.

Results 47 C.

Solid Waste Disposal 49 _

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DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report TABLE OF CONTENTS (Continued)

V.

ENVIRONMENTAL MONITORING PROGRAM h

A.

Environmental Radioactivity Monitoring Program 51 1.

Program Description 51 2.

Summary of Results 69 3.

Quality Control Program 69 B.

Air Monitoring 75 1.

Characterization of Air and Meteorology 75 2.

Air Sampling Program and Analytical Techniques 75 3.

Results and Conclusions 78 C.

Monitoring of Sediments and Soils 81 1.

Characterization of Stream Sediments and Soils 81 2.

Sampling Program and Analytical Techniques 81 3.

Results and Conclusions 83 D.

Monitoring of Feederops and Foodcrops 85 1.

Characterization of Vegetation and Foodcrops 85 2.

Sampling Program and Analytical Techniques 85 3.

Results and Conclusions 87 E.

Monitoring of Local Cow's Milk 88 1.

Description - Milch Animal Locations 88 2.

Sampling Program and Analytical Techniques 88 3.

Results and Conclusions 92

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DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report i

TABLE OF CONTENTS (continued)

V.

ENVIRONMENTAL MONITORING PROGRAM (continued)

Page F.

Environmental Radiation Monitoring 93 1.

Description of Regional Background Radiation Levels and Sources 93 2.

Locations & Analytical Procedures 93 3.

Results and Conclusions 98 G.

Monitoring of Fish 100 1.

Description 100 2.

Sampling Program and Analytical Techniques 100 3.

Results and Conclusions 100 H.

Monitoring of Surface, Drinking, and Well Waters 102 1.

Description of Water Sources 102 j

2.

Sampling Program and Analytical Techniques 102 3.

Results and Conclusions 106 I.

Estimates of Radiation Dose to Man 109 1.

Pathways to Man - Beaver Valley Power Station 109 a.

Calculational Models - Beaver Valley Power Station 109 2.

Rasults of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases 110 e

3.

Airborne Pathway 113 4

Conclusions - Beaver Valley Power Station 113 5.

Dose Pathways to Man - Shippingport Atomic Power Station 115 a.

Calculational Model - Shippingport Atomic Power Station 115 6.

Results and Conclusions - Shippingport Atomic Power Station 116

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DUQUESNE LIGHT COMPANY l

1982 Annual Radiological Environmental Report l

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LIST OF FIGURES Figure i

No.

P, ajte 1.0 View of the Shippingport and Beaver Valley Site 3

1.1 Geographical Map - 40 Mile Radius 4

4.1 Liquid Discharge Points to Ohio River 28 l

4.2 Water Flow Schematic - Shippingport Atomic Power Station 29 4.3 Water Flow Schematic - Beaver Valley Power Station 30 4.4 Liquid Radwaste Systems - Shippingport Atomic Power Station 31 4.5 Liquid Radwaste Systems - Beaver Valley Power Station 32 4.6 Gaseous Waste Processing - Shippingport Atomic Power Station 37 4.7 Gaseous Waste Processing - Beaver Valley Power Station 39 4.8 Gaseous Release Points - Shippingport Atomic Power Station and Beaver Valley Power Station 41 4.9 Solid Waste Disposal Diagram 50 5.B.1 Environmental Monitoring Locations - Air Sampling Stations 77 5.B.2 Concentrations of Gross Beta in Air Particulates 79 l

5.C.1 Environmental Monitoring Locations - Sediments 82 5.D.1 Environmental Monitoring Locations - Feederop and Foodcrop 86 5.E.1 Dairy Farm Locations (August - September 1982 Survey) 90 5.E.2 Environmental Monitoring Locations - Milk 91 5.F.1 Environmental Monitoring Locations - Radiation Monitoring 94 5.F.2 Environmental Monitoring Locations - Radiation Monitoring 95 5.F.3 Environmental Monitoring Locations - Radiation Monitoring 96 5.F.4 Environmental Monitoring Locations - Radiation Monitoring 97 f

5.G.1 Environmental Monitoring Locations - Fish 101 1

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DUQUESNE LZGHT COMPAh'l 1982 Annual Radiological Environmental Report LIST OF TABLES Table Number P, age III.1 Quality Control Data - TLD Comparisons 9

III.2 Quality Control Data - Water Split Samples 10 III.3 Quality Control Data - Split Samples - Miscellaneous 12 III.4 Quality Control Data - Spiked Samples 16 III.5 Quality Control Data + Spiked Samples 17 III.6 Quality Control Data - Air Particulates and I-131 18 III.7 Quality Control Data - Milk and Water 22 III.8 Anomalous Measurements During 1982 26 IV.A.1 Effluent Treatment, Sampling and Analytical Procedures Shippingport Atomic Power Station 33 IV.A.2 Effluent Treatment, Sampling and Analytical Procedures Beaver Valley Power Station 33 IV.A.3 Results - Liquid Effluents - Shippingport Atomic Power Station 34 IV.A.4 Results - Liquid Effluents - Beaver Valley Power Station 34 l

V.A.1 Environmental Monitoring Program Summary 52 V.A.2 Environmental Monitoring Program Results (1982) 57 V.A.3 Pre-Operational Monitoring Program Results (1974-1975) 70 V.A.4 Typical LLDs for Gamma Spectrometry - DLC Contractor 74 V.I.1 Radiation Dose to Man - Beaver Valley Power Station -

l Liquid Releases 111 V.I.2 Radiation Dose to Man - Beaver Valley Power Station -

Airborne Releases 114 l

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SECTION I DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report I.

INTRODUCTION The 1982 Annual Radiological Environmental Report for the Beaver Valley Power Station and the Shippingport Atomic Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1982.

The Duquesne Light Company operates the Shippingport Atomic Power Station for the United States Department of Energy and the Beaver Valley Power Station pressurized water reactor -

Unit No. I as part of the Central Area Power Coordination group.

Beaver Valley No. 2 Unit was under construction in 1982 and is scheduled to start-up in 1986.

The Shippingport Atomic Power Station operated throughout 1982, until the final shutdown date of October 1st 1982, with the gross electrical generation during the year of 302,730 megawatthours. The plant has been in operation utilizing a light water breeder reactor (LWBR) core since September 21, t

1977.

The Shippingport Atomic Power Station was the first large-scale central station nuclear reactor in the United States.

,I Since initial power generation in December 1957, operation of the pressurized water reactor at the Shippingport plant has supplied power to the Duquesne Light Company system in l

addition to providing technology which has served as a bas is for the development of pressurized water reactors in the nuclear industry.

The highest average daily output generated at the Beaver Valley Power Station during the year was 827 megawatts net in November, 1982. The total gross electrical generation during the year was 2,862,200.

megawatt-hours.

A.

Scope and Objectives of the Program The environmental program consists of effluent and environmental monitoring for radioactivity.

Liquid and j

gaseous effluents from the Beaver Valley Power Station and g

gaseous effluents from the Shippingport Atomic Power Station were collected, processed, sampled, and analyzed to ensure conformance with the applicable regulations and permits prior to their release to the environment. Environmental sampling and analyses included air, water, milk, soil, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding both plants.

SECTION I DUQUESNE LIGHT COMP &MY 1982 Annual Radiological Environmental Report I.

INTRODUCTION B.

Description of the Shippingport and Beaver Valley Site The Shippingport Atomic Power Station and the Beaver Valley Power Station are located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 486.8 acre tract of land which is owned by the Duquesne Light Company.

Figure 1.0 is an artist's view of both stations. 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.

There are no residents within a 1/2 mile radius of either plant.

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 Shippingport and Beaver Valley Power Stations at an elevation of 1,160 feet.

Plant ground level at both stations is approximately 733 feet above sea level.

i The two (2) stations are situated on the Ohio River at river sile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberland Lock and Dam.

The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries.

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.

Water temperature of the Ohio ' River varies ficm 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

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rivers.

The climate of the area may be classified as humid

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continental.

Annual precipitation is approximately 33 h

inches, typical yearly temperatures vary from approximately -

l 3*F to 95 F with an annual average teeperature of 52.8 F.

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

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1982 Annual Radiological Environmental Report I.

INTRODUCTION B.

Description of the Shippingport and Beaver Valley Site (continued)

The design ratings and basic features of the Beaver Valley Power Station and the Shippingport Atomic Power Station are tabulated below:

i Beaver Valley Shippingport Thermal & 'Elec. Rating - 2660 MW 852 MW 236.6 MW 72 MW MW-Each Reactor Type of Reactor PWR PWR*

Number of Reactor 3

4 Coolant Loops i

Number of Steam Generators 3 - Vertical 4 - Horizontal and Type Steam Used by Main Turbine Saturated Saturated Both stations utilize two (2) 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 MW

- megawatts electrical

• Light Water Breeder Core

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SECTION II DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report II.

RESULTS AND CONCLUSIONS Plant operations at both the Beaver Valley Power Station and the Shippingport Atomic Power Station had no adverse effects on the environment as a result of activities at either of the stations during 1982. 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 throughout 1982, and the Shippingport Atomic Power Station operated throughout 1982 until the final shutdown date of October 1, 1982.

During the year, the radioactive releases from both stations were below the limits of 10 CFR Part 50, Appendix I and applicable permits for each station. 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 1982 was the same as in 1981 except for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications.

The results of the 1982 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 Nuclear weapons tests is noted in Table III.8.

This radioactivity was only detected near the Beaver Valley Power Station discharge and resulted in negligible exposure to members of the public. A summary of the 1982 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.

The Beaver Valley Power Station Technical Specifications require sampling of four (4) dairies which have the highest calculated milk pathway potential. These four 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 fcw as one cow or goat.

The availability of milk from single cow dairies and revisions due to updated calculations and surveys result in sampling of several additional dairies during the year in different sampling periods.

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SECTION II DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report II.

RESULTS AND CONCLUSIONS (continued)

In order to provide continuity in the sampling / analyses pregram, the Environmental Monitoring Program includes three larger dairies and in 1982 a fourth large dairy was added to the program. This dairy is 10.3 miles south-southwest from the Beaver Valley Perwer Station and is considered to be a control location. Sampics from each of these dairies are obtained each month in addition to the four dairies required by the Environmental Technical Specifications.

During some sampling periods, one or all of the additional dairies could be among the four required dairies. Thus, there will be at least five and possibly as many as eight dairies sampled in any sampling period. The collection periods associated with each of the locations are provided in the detailed summary of the milk monitoring program of this report (Section V-E).

Examination of effluents from the Shippingport Atomic Power Station and the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and Station Technical Specifications. Tnere.were t.o (2) surface water tritium values during the year which exceeded the reporting levels established in the BVPS technical specifications which were based on preoperational levels.

These values were well below the limits of 10CFR20 for discharge from an operating plant.

Shippingport Atomic Power Station did not release any liquid radioactive effluents during 1982.

SECTION III DUQUESSE LIGHT COMPANY 1982 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS A.

Environmental Quality Control Programs The Quality Control (QC) Program used for the Beaver Valley -

Shippingport 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.

Radiation Monitoring (Duquesne _ Light Company (DLC)

Contractor Laboratory - DLC QC Labogalory - Independent Laboratory)

An independent program of external radiation monitoring was conducted by the QC Laboratory using lithium fluoride TLDs sharing the same location as the DLC Contractor Laboratory TLDs and Independent Laboratory TLDs.

Summary data of the QC Laboratory program is provided in Table III.1.

Duplicate contractor TLD, QC TLD, Annual TLD, and Independent Lab TLD and continuous integrating monitoring by a Pressurized Ion Chamber (PIC) show generally good agreement and demonstrate acceptable performance by the DLC Contractor Laboratory.

The arithmetic mean of each laboratory agrees within 10% of the arithmetic mean of the three laboratories. This is well within the precision of a typic.s1 TLD system.

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 laboratory of the Department of Energy).

A summary of results of split water samples is provided in Table III.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.

Because of the overall uniformity of comparable results, it is concluded that the two laboratories are consistent and in agreement.

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$setion III DUQUESNE LIGHT COMPANT TABLE 111.1 1982 Annus1 Radiolcgical Environmental Report TABLE 11I.1 QUALITY CONTROL RESULTS TLD MONITORING mR/ Day let QUARTER 2nd QUARTER DLC DLC DLC QC Independent DLC DLC QC Independuct DLC Location Centractor Lab Lab f3 PDER PIC Contractor Lab Lab #3 PDER PIC No.

(CaSO tDv)

(LiF) (CaSO,tTs)

(2)

Q (CaSO :Dv)

(LiF) (CaSO Ts)

(2)

Q 10 0.16 0.21 0.18 0.27 0.23(1) 0.15 0.18 0.21 0.26 0.23 13 0.17 0.22 0.18 0.27 0.17 0.20 0.20 0.26 14 0.17 0.23 0.19 0.16 0,17 0.20 15 0.13 0.15 0.13 0.21 0.13 0,13 0.16 0.19 27 0.17 0.21 0.19 0.16 0.16 0.18 28 0.18 0.23 0.20 0.17 0.21 0.20 29 0.21 0.26 0.20 0.19 0.22 0.20 32 0.19 0.24 0.21 0.23 0.29 0.18 0.20 0.23 0.22 0.27 45 0.19 0.23 0.20 0.27 0.23(1) 0.18 0.21 0.21 0.28 0.24(1}

46 0.16 0.19 0.17 0.22 0.21 0.15 0.17 0.19 0.25 0.18 47 0.19 0.22 0.19 0.18 0.20 0.23 48 0.18 0.20 0.19 0.17 0.19 0.18 51 0.20 0.22 0.20 0.27 0.17 0.19 0.20 0.25 l

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3rd QUARTER 4th QUARTER DLC DLC DLC QC Independent DLC DLC QC Independent DLC I4 cation Contractor hb Lab #3 PDER PIC Contractor Lab Lab #1 PDER PIC l

No.

(CaSO tDv) 0.iF) (CaSO tTm)

(2)

Q (CaSO.tDy)

(LiF) (CaSO,tTm)

(2) M 10 0.17 0.18 0.23 0.23 0.23(1) 0.17 0.20 0.19 0.24 0.23 13 0.16 0.17 0.20 0.22 0.17 0.21 0.20 0.26 14 0.17 0.18 0.22 0.17 0.21 0.20 15 0.14 0.13 0.18 0.20 0.14 0.16 0.17 0.20 27 0.17 0.17 0.21 0.17 0.19 0.22 28 0.18 0.19 0.23 0.18 0.22 0.23 29 0.20 0.22 0.24 0.20 0.26 0.24 32 0.18 0.19 0.19 0.19 0.27 0.19 0.23 0.23 0.22 0.26 45 0.19 0.21 0.23 0.25 0.23 0.19 0.22 0.23 0.26 0.24(13 III 46 0.15 0.15 0.20 0.22 0.19(1) 0.16 0.17 0.18 0.24 0.20 47 0.18 0.19 0.21 0.19 0.23 0.22 j

48 0.16 0.17 0.21 0.16 0.20 0.19 51 0.17 0.18 0.22 0.26 0.18 0.19 0.21 0.28 i

(1) PIC Reading at Iocation 10 taken in D14 Substation in Shippingport Boro. Ircation 45 taken at Kennedy's Corners. Location 46 taken at Industry Tire Shop.

(2) NRC results from Pennsylvania Department of Environmental Resources.

(3) In this consolidated environmental program the pressurized ion chamber (PIC) continuous roattor readings tend to be slightly higher than the TLD readings due to the differences in the inherent physics of each system. No compensatory measures have been taken to make both systems agree exactly because both systems were installed to monitor relative radiation levels rather than absolute levels. Each system provides a reasooably accurate measure of the absolute radiation levels..

'Section III DUQUESNE LIGHT COMPANY TABLE III.2 1982 Annual Radiological Environmental Ripsrt (Pcg1 1 of 2)

TABLE III.2 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RISULTS Comparison of Contractor and DLC-0C fabs Dic Contractor DLC - QC Media

. Analysis Sampling Period Lab (1)

Lab (1)

Units Surface Water Cross Alpha January

.f 1.9 2.422.1 pCi/1 April f 0.72 3 1.1 pci/1 July g 0.97

$ 0.6 pC1/1 October 3 0.89 g 0.92 pC1/1 Surface Water Cross Beta January 6.5 2 1.3 6.3 2 2.2 pC1/1 April 4.0 2 1.2 3.6 2 1.9 pCi/1 July 6.1 2 1.3 3.7 2 1.5 pC1/1 October 4.2 2 1.4 5.6 2 2.2 pC1/1 Surface Water co-60 January

$3.0

$ 4.5 pC1/1 April 3 3.0

$ 3.9 pC1/1 July f 2.0

$4.0 pC1/1 October

< 2. 0 f 3.8 pC1/1 Surface Water Co-134 January

, g 3.0 55.0 pC1/1 April 3 3.0 f 4.6 pC1/1 July

$ 2.0 3 4.8 pC1/1 October j2.0 3 4.7 pC1/1 Surface Water Ca-137 January f 3.0 3 3.0 pC1/1 April

$ 3.0 3 4.3 pC1/1 July 32.0

$ 5.0 pCi?1 October

< 2.0

< 5.0 pC1/1 Surface Water Tritium Ist Quarter 790 2 70 560 2 210 pC1/1 Composite 3rd Quarter 140 g 100 Composite

-e 196 pC1/1 Surface Water Sr-89 2nd cuarter

< 1.6

< 0.36 pC1/1 Composite 4th Quarter

$ 1.9 1 0.6 pC1/1 Composite Surface Water Sr-90 2nd Quarter

$0.17 0.36 2 0.28 pC1/1 Composite 4th Quarter

$ 0.38 1 0.4 pC1/1 Composite Surface Water CoetG 2nd quarter

< 0.6 3 3.9 pC1/1 (high.

Composite g,f*I h

eter

$ 0.9 f 3.6 pC1/1 g

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

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Stetio's III DUQUESNE LIGHT COMPANY T2 bis III.2 1982 Annual Rtdiolegical Envir:nmentsi R2 port (P2gi 2 of 2)

TABLE III.2 (continued)

QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-OC tabs DLC Contractor DLC-QC Media Analysis

-Sampling Period Lab (1)

Lab (1)

I' nit s Drinking Water Cm=137 February g 2.0

$ 4.5 pCi/1 May g 2.0 g 4.7 pCi/L August

< 3.0

< 5.1 pC1/1 November

< 2.0

< 4.9 pC1/1 Drinking Water Cs-134 February

$ 3.0 f 4. 3, pC1/1 May g 2.0

< 4.5 pC1/1 August

< 3.0

< 4.9 pC1/1 November

< 2.0

< 5. 0 pCi/1 Drinking Water Co-60 Feburary

$ 2.0 f 3.6 pC1/1 May g 2.0

$ 3.9 pC1/1 August

< 3.0

< 4.2 pC1/1 November

< 2.0

< 4.6 pCi/1 Drinking Water Cross Alpha March i 0.60 f 1.3 pC1/1 June

< 0.52

< 1.6 pC1/1 August

.< 0.36

< 1.5 PC1/1 November g 0.42

< 1.4 pC1/1 crinking Water Cross Beta March 4.5 2 1.1 5.6 2 1.9 pCi/1 June 3.0 2 1.1 4.2 2 1.8 pC1/1 August 4.6 2 1.1 4.9 2 2.1 pC1/1 November 3.5 2 1.3 3.4 2 1,9 pC1/1 Drinking Water Tritium 2nd Quarter f 70 290 2 220 pC1/1 4th Quarter

< 70

< 190 pC1/1 (1)

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

F Section III DUQUESNE LIGHT COMFANT TABLE III.3 1982 Annual Radiological Environmental Report (Page 1 of 2)

TABLE III.3 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Cectractor and DLC-0C tabs DLC Contractor DLC-QC Media Analysis Sampling Period Lab (1)

Lab (1)

Units Milk I-131 3-16-82 g 0.11 f 1.2 PCi/l (Location 25)

Se-89 3-16-82 g 2.0 f 0.93 pCi/l Sr-90 3-16-82 1.2 2 0.5 3.1 2 0.8 pC1/1 Cs-134 3-16-82 g 2.0

$ 4.7 pC1/1 Cs-137 3-16-82 g 2.0 5.1 2 4.4 pC1/1 Co-60 3-16-82 1 2.0

< 3,9 pC1/1 K-40 3-16-82 1230 2 120 pC1/1 Milk I-131 6-16-82 5 0.14

< 0.22 pC1/1 (Location 25)

K-40 6-16-82 1030 2 120 pC1/1 Cs-134 6-16-82

< 3.0

< 4, e pC1/1 Cs-137 6-16-82 g 3.0 3 4,7 pC1/1 Co-60 6-16-82 g 3.0 3 4,o pC1/1 Feed Be-7 6-14-82 2.1 5 0.46 pC1/gm Dry (Location 25)

K-40 6-14-82 19.6 2 2 pCi/gm Dry Cs-134 6-14-82.

S 0.01 50.1.

pC1/ga Dry Cs-137 6-14-82 s (A03

$ 0.1 pCi/gs. Dry Co-60 6-14-82

< 0.02

< 0.1 pC1/gm Dry Food I-131 9-1-82

< 0.007

< 0.06 pC1/gm Dry (Cabbage)

K-40 9-1-82 1.13 2 0.14 pC1/gm Dry (Location 10)

Co-60 9-1-82 f 0.006 f0.04 pCi/ga Dry Cs-134 9-1-82 g 0.007 f 0.04 pCi/gs Dry Cs-137 9-1-82 f 0,007 g 0.04 pCi/gm Dry Food (Lettucs )

I-131 9-1-82 f 0.004 f 0.06 pCi/ga Wet (Location 10)

Be-7 9-1-82 0.30 2 0.21 pC1/gm Wet K-40 9-1-82 2.69,2 0.54 pci/gm Wet Co-60 9-1-82 f 0.01 f0.07 pCi/ga Wet Cs-134 9-1-82

< 0.01

< 0.07 pCi/gu Wet Cs-137 9-1-82

< 0.01

< 0.06-pC1/ps Wet Feed (Location 2ir)

Sr-90 9-20-82 0.06 2 0.01 0.19 2 0.12 pCi/gm Dry

{l) Uncertainties are based on counting statistics and are specified at the 952 confidence interval.

- - Analyses not performed nor required.

NctionIII DUQUESNE LIGHT COMPANY TABLE III.3 1983 Annual Radiological Environm64ts1 Ittport (Pass 2 of 2)

TABLE III.3 QUALITY CONTROL RESULTL l

-SPLIT SAMPLE ANALYSIS RTSt!LTS l

Comparison of Contractor and DLC-0C labs DLC Contractor DLC-QC Media Analysis Samplina Period 14b (1)

Lab (1) t%it s Milk Sr-89 9-20-82

$ 1.2 pC1/1

('ocation 25)

Sr-90 9-20-82 3.2 2 0.7 PCi/1 Co-60 9-20-82

$ 3.0

$4.2 Pci/1 l

Cs-134 9-20-82

,f3.0

$4.6 pC1/1 Cs-137 9-20-82.

f 3.0

$4.7 pC1/1 I-131 9-20-82 f 0.11

$0.6 pC1/1 K-40 9-20-82 1040 2 120 pC1/1 Sedimest Cr-A 10-21-82 11 h 8 15 2 6 pC1/gm Dry (Location 3)

Cr-a 10-21-82 51 2 3 29 2 7 pCi/sm Dry U-235 10-21-82

$ 0.01

$0.08 pci/sm Dry U-234 10-21-82 0.31 2 0.16 0.7 2 0.2 pCi/sm Dry U-238 10-21-82 0.18 2 0.01 0.31 2 0.13 pC1/gm Dry Sr-89 10-21-82

$0.2

$0.4 pCi/sm Dry Sr-90 10-21-82 f 0.05

$ 0.08 pCi/sm Dry K-40 10-21-82 13 2 1.3 pCi/gm Dry Co-60 10-21-82 0.08 2 0.03 0.20 2 0.10 pC1/sm Dry l

Cs-134 10-21-82 5 0.02

$ 0.07 pCi/gm Dry Cs-137 10-21-82 0.3520.05 0.16 2 0.12 pC1/gm Dry Ra-226 10-21-82 2.17 2 0.73 pC1/gm Dry l

Th-228 10-21-82 1.43 2 0.14 pC1/gm Dry 1

Milk I-131 12-21-82

$0.16

$7 pC1/1 (Locstion 25)

K-40 12-21-82 888 2 124 pCi/1 Cs-134 12-21-82

$3.0

$5.0 pC1/1 Cs-137 12-21-82

$, 3.0

$ 5.2 PC1/1 Co-60 12-21-82

$3.0

$ 4.4 pC1/1 l

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

- - Analysis not performed nor required.

Not analyzed due to late arrival of sample.

I.

SECTION III DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report A.

Environmental Quality Control Programs (continued) 3.

DLC QC Latypratory Program Spiked samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for analysis. Tables III.4 (water) and III.5 (milk) provide data from this portion of the QC Program.

The overall results demonstrate that the contractor performed acceptably in the program.

4.

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

Duplicate air particulate and charcoal filters (radioiodine) 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 for Sr-89 and Sr-90 activity for the second and third quarters 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 Contractor Laboratory maintained its own QC Program which included participation in the Environmental Protection Agency Environmental Monitoring Safety Laboratory (EPA EMSL)

Interlaboratory Cross Check Program.

This cross check program indicated that the Contractor results were in agreement with EPS 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. _

.... ~

SECTION III DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report A.

Environmental Quality Control Programs (continued) 6.

Special QC Program (DLC Contracter Laboratory Independent Laboratory - DLC QC Laboratory)

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 Laboratory. A summary of rescits of this portion of the QC program is provided in Table III.7.

The results show generally good agreement between the laboratories and demonstrate that the contractor performed acceptably in the program.

l Section III DUQUESNE LICHT COMPANT TABLE III. 4 1982 Annual Radiolsgicci Envircnaattal Ripstt TABLE III.4 QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS RESULTS Sample Type DLC and Contractor DLC - QC S uple Date Ident. No.

Analysis Lab (1) tab (1)

Units 3-30-82 53-46 Water Sr-89 17 2 4 18 2 4 pC1/1

$r-90 12 2 1 11 2 2 pC1/1 5-7-82 53-47 Water I-131 7.8 2 0.6 9.1 2 0.8 pCi/1 Mn-54 45.6 2 5.0 41 2 16 pC1/1 Co-60 40.6 2 5.1 47216 pC1/1 Co-137 28.2 2 4.7 31 t 16 pC1/1 Co-57 23.7 2 3.3 28 2 10 pC1/1 6-10-82 53-48 Water:

Cross Alpha 1.620.6*

12 2 2 pCi/1 l

Cross Beta 9.4 2 1.1 1422 pC1/1 9-22-82 53-49 Water Sr*39 22 2 3 18 2 2 pC1/1 Sr-90 12 2 1 12 2 2 pci/1 Cr-51 100 2 50 113 2 24 pCi/1 Ru-106 92.1 2 9.2 110 2 18 pCi/1 Cs-137 29.8 2 3 26 2 8 pC1/1 10-30-82 53-50 Water:

I-131 lost 3,6 2 3.5 pC1/1 Fe '9 26.1 2 10 18212 pC1/1 Co-60 26.6

• 5.8-30 2 7 P 1/1 C

Ru-106 187 2 49 250 2 65 pC1/1 Co-144 56.3 e 24.6 60 2 52 pCi/1 H-3 560 2 90 720 2 330 pC1/1 j

l 1-17-83 53-51 Water Cro.e Alpha 7.7 2 3.4*

21 2 8 pC1/1 Crous 8 eta 15 1 2.0 2024 pC1/1 1-17-83 53-48a Water:

I-121 3.0 2 0.4*

4.1 2 0.2 pC1/1 b

Water:

I-131 8.2 2 0.5 8.6 2 1.1 pC1/1 c

Water:

1-131 14 1 16 2 2 pC1/1 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.

Poor agreement between the Contractor Lab and the Q.C. Lab. The reason is still under investigation et the time of this report. The Contractor Lab and the EPA intercomparison Gross Alpha results v re within acceptable agreement.

l._

Sxtita III DUQUESNE LICHT COMPANY TABLE III.5 1982 Annual Radiological Environmental Report TABLE III.5 QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS Sample Type DLC and Contractor DLC - QC S+-pIm Date Ident. No.

Analysis Lab (1)

IJb (1)_

t' nit e 2-22-82 52-53 Milkt Sr-89 6.5 2 2.8 7.5 2 2.7 pCi/1 St-90 15 2 1.0 14 2 2.2 pC1/1 I-131 8.0 2 0.4 7.0 2 1.2 pci/1 pC1/1 K-40 1030 2 100 Cs-13 7 24.1 2 5.6 29 2 8 pC1/1 6-8-82 52-54 Milk:

I-131 3.6 2 0.2 4.1 2 1.1 pC1/1 pC1/1 K-40 1170 t 120 Co-60 54.8 2 7.1 5027 pCi/1 Cs-137 33.4 2 6.6 3328 pci/l Co-57 48.0 2 5.9 40 2 7 pC1/1 pCi/l 9-27-82 52-55 Milk Sr-89 13 2 1 20 e

pC1/1 Sr-90 12 2 1 12;5 I-131 1.9 2 0.2 3.2 2 0.7 pCi/1 PCi/l K-40 953 2 95 Cr=51 181 2 18 236 2 20 pC1/1 Ca-137 25s324.0 33 2 7 pC1/1 Ce-144 99.8 2 25 120 2 45 pCi/l I

10-30-82 52-56 Milk I-131 2.2 2 0.2 4.1 2 3.2 pC1/1 K-40 1310 2 130 pCi/l Cr-51 91.7 : 36.1 69 2 44 pC1/1 Fe-59 13.3 2 10 21 2 12 pC1/1 Co-60 28.1 2 5.3 25

• 9 pC1/1 Cs-137 20.3 2 5.4 13 2 8 pC1/1

(

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

Analyses not performed nor required.

QC analysis not available, since the QC laboratory inadvertantly disposed of the saeple prior to analysis.

Teledyne result compared acceptably to the known value using EPA acceptance criteria and EPA uncertainty for a single measurement. _-

4 Stetica III DUQCESNE LICHT COMPANT TABLE III.6 1982 Annual Radiological Environmental Raport (Pags I of 4)

TABLE III.6 QUALITY CONTROL REST lLTS AIR PARTICt*LATES AND CHARCOAL FILTER: COMPARABLE SAMP!.ES Air Particulates Air fodine pCi/Cu. Meter (Beta)

'pC1/Cu. Meter DLC DLC Contractor DLC - QC Contractor DLC - QC S+ role care Lab (1)

Lab (t)

Sample Date Lab (1)

Lab (1) 1/4/82 to 0.038 2 0.003 0.042 2 0.003 1/12/82 to dr 0.01

""< 0.015 1/12/82 1/18/82 1/18/82 to 0.042 2 0.004 0.043 2 0.003 1/25!82 to

<"" 0.01

""< 0.021 1/25/82 2/1/82 2/1/82 to 0.034 2 0.004 0.039 2 0.003 2/8/82 to 5 0.008

$0.017 2/8/87 2/16/82 2/16/82 to 0.020 2 0.003 0.025 2 0.003 2/22/82 to g 0.009 50.020 2/22/82 3/1/82 3/1/82 to 0.029 2 0.004 0.034 2 0.003 3/8/82 to sg 0.01

< 0.022 3/8/82 3/15/82 3/15/82 to 0.012 2 0.003 0.013 2 0.002 3/22/82 to

<"" 0.009

~< 0.022 3/22/82 3/29/82 3/29/82 0.026 2 0.003 0.027 + 0.002 4/5/62 to g 0.009

$0.020 4/5/82 4/12/82 4/12/82 to 0.023 2 0.003 0.030 2 0.003 4/19.82 to ec 0.01 40 0.022 4/19/82 4/26/82 4/26/82 to 0.026 2 0.003 0.029 2 0.002 5/3/82 to 5/3/82 5/10/82

• si 0.009

""< 0.010 5/10/82 to 0.028 2 0.003 0.038 2 0.003 5/17/82 to g 0.01 5/17/82 5/24/82

""< 0.015 5/24/82 to 0.020 2 0.003 0.027 2 0.002 6/1/82 to

=g 0.01

$0.028 6/1/82 6/7/82 6/7/82 to 0.020 2 0.003 0.028 2 0.002 6/14/82 to 6/14/82

""e 0.009

""< 0.028 6/21/82 6/21/82 to 0.027 2 0.003 0.029 2 0.002 6/28/82 to ac 6/28/82 7/6/82

"" 0.009

""< 0.016 7/6/82 to 0.025 2 0.004 0.025 2 0.003 7/12/82 to

"" 0.01

< 0.010 7/12/82 7/19/82 7/19/82 to 0.026 2 0.003 0.029 2 0.002 7/26/82 to

< 0.01

< 0.020 7/26/82 8/2/82 8/2/82 to 0.034 2 0.004 0.037 2 0.00s 8/9/82 to

< 0.01

< 0.019 8/9/82 8/16/82 8/16/82 to 0.021 2 0.003 0.027 2 0.002 8/23/82 to

"" 0.01

< 0.019 8/23/82 8/30/82

~

8/30/82 to 0.027 2 0.003 0.030 2 0.002 9/7/82 to

"' 0.01

< 0.040 9/7/82 9/13/82 (1) Uncertainties are based on ecusting statistics and are specified at the 95% confidence interval.. -

-_._.w----

.m Sectica III DUQUESNE LICHT COMPANT TABLE III.6 1982 Annual Radiolegical Envirennental kaport (Pags 2 cf 4 )

TABLE III.6 QUALITY CONTR0i., RESULTS AIR PARTICULATES AND CHARCOAL FtLTERr C,OMPARABLE SAMPLES Air Particulates Air todine pC1/Cu. Meter (Beta) pC1/Cu. Meter i

DM DM l

Contractor DLC - QC Contractor D14 - QC Srapte Date Lab (1) tab (1)

Sample Date 1.ab (1)

Lab (1) 9/13/82 to 0.018 2 0.003 0.020 2 0.002 9/20/82 to S 0.009

$0.018 9/20/82 9/;7/82 9/27/82 to 0.025 2 0.003 0.031 2 0.003 10/4/82 to

~< 0.009

~< 0.019 10/4/82 10/11/32 10/11/82 to 0.025 1 0.003 0.023 2 0.002 10/18/82 to

< 0.009

< 0.014

[

10/18/82 10/25/32 i

10/25/82 to 0 040 2 0.004 0.035 2 0.003 11/1/h2 to 1 0.01 50018 11/1/82 11/8/32 I

11/8/82 to 0.034 2 0.004 0.034 2 0.003 11/15/82 to

~i 0.006

~< 0.018 l

11/15/82 11/22/82 l

11/22/82 to 0.021 2 0.003 0.027 2 0.002 11/29/82 to

< 0.01

~< 0.023 11/29/82 12/6/82 12/6/82 to 0.027 2 0.003 0.030 2 0.003 12/13/82 to

-< 0.01

~< 0.023 12/13/82 12/20/02 12/20/82 to 0.020 2 0.003 0.026 2 0.002 12/27/82 to

< 0.01

~< 0.017

~

12/27/12 1/3/82 l

I l

(1) Uncertainties are based on counting statistics and are specified at the 951 confidence interval.

I L -

y.,-.,-.n-n-,

r_

---

,nyy

$1ction III DCQUESNE LIGHT COMPANT TABLE III.6 1982 Annual Radiological Environmental R port (P3;s 3 of 4)

TABLE III.6 QCALITY CONTROL 3

AIR PARTICULATES (pC1/m )

DLC Contractor DLC - OC 1+rple Date Nuclide Lab (1)

Lab (1)

J:nntry Be-7 0.105 2 0.016 0.081 2 0.008 (12/28/81 to 2/1/82) battis K-40 0.018 2 0.013 (12/28/81 to 2/1/82) Teledyne others LLD LLD March (3/1/82 to 3/29/82) Bettis Be-7 0.083 2 0.016 0.080 2 0.030 (3/1/82 to 3/29/82) Teledyne Others LLD LLD May (5/3/82 to 6/1/82) Bettis Be-7 0.113 t 0.011 0.18 2 0.03 (5/3/82 to 6/1/82) Teledyne Others LLD LLD July (6/28/82 to 7/26/82) Bettis Be-/

0.137 2 0.018 0.090 2 0.016 (6/28/82 to 8/2/82) Teledyne Others LLD LLD 5:ptember (8/30/82 to 9/27/82)

Be-7 0.076 2 0.029 0.045 2 0.018 Others LLD LLD November (11/1/82 to 11/19/82)

Be-7 0.086 2 0.019 0.057 2 0.016 Others LLD LLp LLD Lower limit of detector.

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

-- Analyses not performed nor required. __

$3ction III DUQUESNE LIGHT COMPANT TABLE III.6 1982 Annual Radiological L vironmental Report (Page 3 of 4)

TAELE III.6 QUALifT CCNTRCL 3

AIR PARTICULATES (pC1/m i DLC Contractor CLC - QC 3 eple Cate Nuclide Lab (1)

Lab (1)

Jcnu.try Be-7 0.105 2 0.016 0.081 2 0.008 (12/28/81 to 2/1/82) QC Lab K-40 0.018 2 0.013 (12/28/81 to 2/1/82) Contractor others LLD LLD Lab March (3/1/82 to 3/29/82) QC Lab Se-7 0.083 2 0.016 0.080 2 0.030 Others LLD LLD (3/1/82 to 3/29/82) Con {rgetor May (5/3/82 to 6/1/82) OC Lab Be-7 0.113 2 0.011 0.18 2 0.03 (5/3/82 to 6/1/82) Contractor others LLD LLD Lab July

{6/28/82 to 7/26/82) QC Lab Be-7 0.137 2 0.018 0.090 2 0.016 Others LLD LLD t1/28/82 to 8/2/82) Con {rgetor S:ptember (8/30/82 to 9/27/82) QC Lab Be-7 0.076 2 0.029 0.045 2 0.018 others LLD LLD (8/30/82to9/27/82) Con {rgetor November (11/1/82 to 11/29/82) QC Lab Be-7 0.086 2 0.019 0.057,2 0.016 others LLD LLD (11/1/82 tc 11/29/82) Con ((getor l

l l

l l

I i

LLD Lower limit of detector.

(1) Uncertainties are based on counting statistics and are specified at the 953 confidence interval.

-- Analyses not performed nor required..

Section III CCQUESNE L1CHT COMPANT TABLE III.6 1982 Anny l Radiological Environmental Repset (Ptss 4 of 4)

TABLE III.6 QUALITY CONTROL AIR PARTICUIATE AND CHARCCAL FILTER 3 COMPARABLE SAMPLES 1.0 CATION 30 - (pC1/s i DLC Contractor DLC - QC S+epte Date Nucitde tab (1)

Lab (1) ist Quarter Composite 12/28/81 to 3/29/82 St-89

< 0.0012

$ 0.0012 Sr-90 0.0002 2 0.0001 5 0.00019 3rd Quarter Composite Sr-89

$ 0.0014 50.00086 6/ 28/82 to 9/27/82)

Sr-90 0.0002 2 0.0001 5 0.00015 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval...

PW NN

==-Wrye=9

.y 9

-m%.w.-g

-.m.m,,

y

Section III DUQUESNE LIGRT COMPANY TABLE III.7 1982 Antual Radisisgical Envirrnmental R: port (P:gi 1 of 2)

TABLE III.7 QUALITT CONTROL DATA QC Sample Comparisons (All Analyses in pC1/1)_

Sample Type DI4 and Independent Contractor DLC - QC Sample Date Ident. No.

Analysis

__ lab (1)

Lab (1) la b 'O 2 24-82 53-239 Vater Sr-90 9.9 2 0.4 9.6 2 0.7 9.8 2 1.5 I-131 2.1 2 0.4 4.6 2 0.2 4.9 2 0.7 Co-60 1628 19.4 2 5.7 15 e 6' Cs-134 23210 19.3 2 6.3 17 2 5 Cs-137 35 9 34.3 2 6.2 30 2 6 2-24-82 53-240 Water H-3 1050 2 60 1210 2 100 1020 2 210 5-19-82 53-241 Water:

Sr-89 5.3 2 1.0 5.0 2 3.1 4.0 2 2.2 Sr-90 19.8 2 0.5 15 2 1 16 2 2 I-131 1622 18 2 1 16 2 1 Co-58 28

• 8 33 2 6 38 2 8 Co-60 19 2 8 19.1 2 5.5 20 2 7 Co-137 21 2 8 18.6 2 6.3 21 2 8 5-19-82 53-242 Water:

H-3 1230 2 60 1250 2 100 1600 t 230 25.4 2 0.6 21 2 1.0 2522 8-18-82 53-243 Water St-90 1-131 4.7 2 1.3 7.7 z'O.3 11 2 1 Fe-59 40 2 20 30.3 1 11.5 26 2 14 Co-60 29 2 9 28.6 2 2.9 3329 Cs-134 18 2 8 15.3 2 6.4 10 2 7 Co-137 23 2 7 27.6 2 6.1 28 2 8 8-18-82 53-244 Waters B-3 1260 2 60 1270 2 100*

1230 e 230 11-10-82 53-245 Water St-89 10 2 2 14 2 5 9.8 2 2.2 Sr-90 24 2 0.5 24 2 1 15 22 16 2 1 17.7 2 0.9 I-131 17 2 11,

' 35.6 2 5 30 2 8 Co-58 34 2 8 Co-60 2528 29.3 't 5.7 3127 Cs-137 27

• 8 38.5 2 5. 8 35 2 9 11-10-82 53-246 Water:

H-3 1260 2 60 1270 2 100 1360 2 280 (1) Uncertainties are based on counting statistics and are specified at the 95I confideoca interval.

• Based on reanalysis, the first.snalysis, although in general agreement with the QC Lab appeared to be biased high..

Ssetion III DUQUESNE LICHT CUMPANY TAELE III.7 1902 Annual '!adiological Environesntal Report (Pags 2 of 2)

TA3LE III.7 QUALITY CONTROL DATA QC Sanple Comparisona (All Analyses in pC1/1)

Sample Type DLC and Independent Contractor CLC - OC Sample rate Ident. No.

Analv$;s Lab (1)

La b (t) ta h (1) 2-24-82

$2-222 Milk:

St-89 9.3 2 1.5 10 t 4 9.72 2.2 Sr-90 14.1 2 0.6 13 2 1 14 2 2 1-131 19.8 2 0.4 2321 19 2 2 Cs-134 14 2 5 15.4 2 4.2 9.1 2 6.2 Cs-137 38 2 5 35.6 2 5.3 40 t 5 5.I).82 52-223 Milk:

Sr-89 5.0 2 2 4.0 2 1.7

$ 3.0 Sr-90 19.4 2 0.5 L6 21

• 19 2 2 I-131 5.2 2 1.0 5.8 2 0.2 3.52

1..?

~

Cs-134 19 2 4 19.6 2 4.9 IS : 7 Cs-137 24 2 4 29.5 2 5.2 33 2 8 S-IS-82 52-224 Milk:

Sr-89 5.0 2 2 6.1 2 2.9 3.8 2 2.6 Sr-90 21.0 t 0.6 15 t 1.0 20 2 2 1-131 3.4 2 0.4 4.3 2 0.2 5.920.7 Cs-134 22 2 4 11.7 2 6.3 16 : 9 Cs-137 25 2 4 26.3 r 6.3 32 : S l

11-M-3 2 52-225 Milk:

Sr-89 12 2 2 15 2 ee 7.1 2 2.5 St-90 20.3 2 0.6 16 2 2 15 2 2 I-131 13.5 2 1 12 2 1 12.6 2 1.4 Cs-134 21 2 7 18.6 2 5 15 2 7 Cs-137 34 2 4 4.125.7 34 7 l

r

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

3ased on reanalysis, the first analysis, although in general agreement witts the QC Lab appear 61 to be biased low.

s

• • Although the Contractor Lab and the Q.C. Lab results are not in good agreetnent, both the Q.C. Lab and the Contractor Lab are in good agreewn: vith the Independent Lab..

SECTION III DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report 7.

Nuclear Regulatory Commisssion (NRC) Program The Nuclear Regulatory Commission (NRC) 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.

The Commonwealth of Pennsylvania's radiological laboratory is utilized by the NRC for analyzing these samples. Comparison of results also indicated agreement between the NRC Laboratory and the Duquesne Light Company Contractor Laboratory.

B.

Evaluation of the Quality Control (QC) Program Data The split sample program indicates that the Contractor laboratory is performing satisfactorily.

In addition, three (3) independent laboratories are used to supplement the regular program.

Comparisons between the independent laboratories and the Contractor laboratory is acceptable, and demonstrates 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 l

Program, the Environmental Monitoring Program for 1982 is l

acceptable with respect to both accuracy and measurement.

C.

Standard Requirements and Limitations for Radiological and Other Effluents The Shippingport Atonic Power Station and Beaver Valley Power Station are governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. Effluent releases at both stations are controlled to ensure that limits set by Federal or State governments are not exceeded.

In addition, self-imposed limits have been established to l

further limit discharges to the environment.

Shippingport Atomic Power Station is operated in compliance l

with regulations and permits involving radioactive and - other effluents. Limits noted in Department of Energy (DOE) Orders 5484.1 and 5480.1, Ohio River Valley Water Sanitation Commission (ORSANCO)

Standards No.

1-70 and 2-70, Pennsylvania Department of Environmental Resources Industrial Waste Permit #1832, and Environmental Protection Agency (EPA) National Pollutant Discharge Elimination System I

(NPDES)

Permit

1. PA-0001589, Pennsylvania Department of Environmental Resources Industrial Waste Permit #0472205, and Pennsylvania Department of Environmental Resources Radioactive Gaseous Discharge Permit are observed and followed.

SECTION IZI DUQUESNE LTGHT COMPANY 1982 Annual Radiological Environmental Report C.

Standard Requirements and Limitations for Radiological and Other Effluents (continued)

Beaver Valley Power Station is subject to regulations which include the Code of Federal Regulations 10 CFR, Pennsylvania Department of Environmental Resources (PDER) Industrial Waste Permit #0473211, Sewage Treatment Facilities Permit #0479403, Gaseous Discharge Permit #04-306-001, PA Code - Title 24, j

Part I,

Ohio River Valley Water Sanitation Commission (ORSANCO)

Standards No.

1-70 and 2-70, Environmental l

Protection Agency (EPA),

National Pollution Discharge Elimination (NPDES) Permit #0025615, and the Beaver Valley Power Station Technical Specifications.

D.

Significant Changes and Reporting Levels Statistically significant changes in radiological l

environmental monitoring results are defined as the median value (M) plus two (2) times the 95% confidence interval (N),

or ten (10) times the lower limit of detection (LLD) for each sampling media analyzed during the preoperational period 1972

- 1975. Analytical results for sampling media noted in the Beaver Valley Power Station Environmental Technical Specifications, which were greater than the statistically significant values determined in the preoperational program (M + 2N or 10 x LLD), are values which require reporting as an anomalous measurement.

This report is forwarded to the Nuclear Regulatory Commission within 10 (ten) days after the completion of a confirming analysis.

There were two (2) analytical results of environmental samples during 1982 which exceeded Beaver Valley Power Station reporting levels and are summarized in Table III.8.

The surface water tritium results were attributable to Beaver Valley discharges; however, the releases were well below limits noted in 10 CFR20.

I i

v _

l SECTXON III DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report TABLE III.8 Anomalous Measurements

• During 1982 l

l Environmental Site Reporting Level Found Sample'Date Media Location Level (Analvt. Results) 3rd Quarter Tritium in Surface 2A 1390 pCi/1 1570 pCi/1 l

1982 Water (1) 4th Quarter Tritium in Surface 2A 1390 pCi/1 2580 pCi/1 1982 Water (1)

NOTE (1):

Attributable to BVPS releases.

(There were no releases which exceeded effluent limits for tritium as identified in 10 CFR 20),

t

• Measurements which exceed the reporting levels in the Beaver Valley Power Station Environmental Technical Specifications.

1 4

1 :

SECTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report IV.

MONITORING EFFLUENTS A.

Monitoring of Liquid Effluents Description of Liquid Effluents at the Shippingport Atomic Power Station and the Beaver Valley Power Station.

Most of the water required for the operation of the Beaver Valley and Shippingport stations is taken from the Ohio

River, and returned to the river, used for make2p to various plant systems, consumed by station personnel, or discharged to a septic systen.

In addition, small amounts of well water and liquid effluents are discharged to the Ohio River using discharge points shown in Figure 4 1 Figures 4.2 through 4.5 are schematic diagrams of liquid flow paths for Shippingport and Beaver Valley respectively. The following four (4) tables summarize radioactive liquid effluents at both the Shippingport and Beaver Valley Power Stations:

Table IV.A.1 - Effluent Treatment, Sampling, and Analytical Procedures - Shippingport Table IV.A.2 - Effluent Treatment, Sampling, and Analytical Procedures - Beaver Valley Table IV. A.3 - Results of Liquid Effluent Discharges to the Environment - Shippingport Table IV.A.4 - Results of Liquid Effluent Discharges to the Environment - Beaver Valley Y

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SECTION IV FIGURE 4,2 DUQUESNE LIGHT CGF N N 1982 Annual Radiological Environmental Peport SECTION IV FIGURE 4.2 m

CAPPED TO TREATED WATER PREVEhT

!!EAD TANK DISCHARCE PROCESSED RADWASTF TO OHIO RADWASTE

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. 3 EC UgM HGWH OO h 3 H@ pp CuH UQ OgO oWH MD4 Ogm 4W WadOtt er 3a OT N RI EA TR AD W DN. M E F E T S G S S T EM S R C AK E OE h E W RTA T O FST T A N W G I N G D I D I L W L O D O O L S C F , ~ 4 K NAT A' TSE T l g I OT K i MW %*C6I W D KL A E I T L l I C T T S C E E T R ~ ~ f ~ ~ ~ M ET S L Y , E E S EI V T V E S g E E L A O T L W T lg gj

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T RI R A I V L t UU - - DT L g I I GQ / FL F F II g j T IE. LA E gi(fI g t g l g ) V L B j ER A gI ) T g V R g A O E F B [ g g 4 j RO TA T R I E K D D N N IES N E A UTK D U G T QSN IES A I A A UTK I M N QSN A I LWT ILWT T R AA E A D I m" 7 e ) D S E I T N A A N R D I D NK M AN A N I T W s SS N O S P R 5 O D T M E N" C W N U WOI ( r E S OC^ t HE S S D D' V hyI i i i SECTION IV TABLE IV.A.1 TABLE IV.A.2 DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report TABLE IV.A.1 1. Effluent Treatment. Sampling and Analytical Procedures - Shioninaoort t Treatment. Sampling Standard and/or Effluent Tvoe and/or Monitoring Analytical Procedures (a) Steam System Directed to radwaste system if _ Secondary water is sampled for Blowdown radioactive. Normally directed any radioactive contamination. to discharge channel where it A 1000 mi sample counted in a is diluted by circulating cooling multichannel analyzer for 10 water. minutes for gross activity. The counter can measure a minimum detectable act N ty (MDA) of 8.4 x 10'8 uCf/ml. (b) Radioactive Collected, segregated and A 3000 m1 sample is counted for Waste Liquids processed as one of two types gross activity. The counter of liquid wastes: can measure a minimum detgetable activity (MDA) of 4 x 10- uCt/ml. a) special waste b) radioactive waste Sample taken of batch before processing to remove radio-activity and reuse in plant systems. See Figure 4.4. TABLE IV.A.2 1. Effluent Treatment. Samolino and Analvtical Procedures - Beaver Valley Treatment. Sampling Standard and/or Ufluent Type and/or Monitoring Analytical Procedures (a) Steam System Recycled or directed to Radwaste If discharged, procedures adhere Blowdown System for discharge. to Technical Specifications. (b) Radioactive Concentration of radioactive Procedures adhere to requirements Waste materials released in waste of Technical Specifications. effluents shall not exceed values specified in 10 CFR 20 Appendix B. Table II for unrestricted areas, and the Environmental Technical Specifications. f - SECTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report e TABLE IV.A.3 2. Results: Shippingport Effluent Type Results for 1982 (a) Steam System The boilers we e periodically blown down. Blowdown The boilers are sampled prior to each blowdown. There was no radioactive liquid discharged in 1982. l (b) Radioactive Since Shippingport first went into operation Waste Liquids in 1957, the total activity of liquid waste j discharged each year has decreased more or l less continuously from a high of 0.53 Ci in 1965 to a low of less than 0.001 Ci in the years 1974, 1975, 1976, and 1977. There was no radioactive liquid discharged in 1978, 1979, 19CO, 1981, or 1982. TABII IV.A.4 2. Results: Beaver Valley Effluent Type Results for 1982 (a) Steam System The Steam System Blowdown was recycled or Blowdown directed to the Radwaste System where it was monitored and discharged. Radioactivity was detected in the blowdown system during a primary to secondary steam generator tube leak ("C" Steam Generator: 7/22/82 to 8/27/82). l This liquid was released in accordance with conditions noted in the Environmental Technical Specifications (b) Radioactive Liquid effluents from the Beaver Valley Waste Liquids Power Station were released in accordance with conditions noted in the Environmental Technical Specifications. No limits were exceeded. These values have been reported i in the Beaver Valley Power Station Semiannual Effluent Reports for 1982. 1 _ SECTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents 1. Description of Airborne Effluents / Sources a. Shippingport Atomic Power Station The potential source of airborne radioactivity associated with the Shippingport station is the radioactivity contained in the reactor coolant system. This system contains the activated corrosion and wear products, activated impurities in reactor coolant, and small quantities of fission products originating from naturally-occurring uranium impurity. This material could become airborne from reactor coolant sampling operations and from maintenance and overhaul operations which require opening the system or working on contamina-ted' components removed from the system. Stringent radiologirsi controls which have been developed during 25 years of operations at Shippingport are exercised during these operations to prevent radioactivity from becoming airborne. Cobalt-60 is the nuclide of primary concern because of its long radioactive half-life and its concentration in reactor coolant. This radionuclide, present in the form of minute insoluble particles, could become airberne during maintenance operations on contaminated components removed from this system.

However, strict radiological surveillance is maintained throughout the operating

plant, including continuous monitoring of airborne radioactivity in the operating spaces to ensure that concentrations are less than the uncontrolled area limits specified in DOE Order 5484.1.

In

addition, air exhausted from potentially contaminated areas, such as decontamination and maintenance

areas, is passed through high-efficiency particulate air filters. These filters are routinely serviced, changed, and tested in-place..

r 1 I i l SECTION IV DUQUESNE LIGHT COMPANY l 1982 Annual Radiological Environmental Report 1 The principle environmental release point for the Shippingport Atomic Power Station is the l containment ventilation exhaust. This point is continuously conitored, and analyses are. performed on charcoal cartridges weekly for I-131 and monthly for I-133 and I-135. Additionally, weekly i continuous air samples are obtained on fixed filter l papers which are analyzed weekly for gross beta, I and composited monthly to identify gamma emitting l isotopes. Composite of the particulate filters are also analyzed monthly for gross alpha determinations and quarterly for Sr-89 and Sr-90. A monthly gas sample is also obtained and analyzed for tritium. l I. SECTION IV FIGURE 4.6 DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report SURGE TANKS RESIN STCRAGE TA?;KS FLASH TANK SPRAY RECYCLE TANK 2' GAS STRIPAER T VENT GAS i CCMPRESSCRS iP P ap HYCRCGEN ANALYZER ANC CATALYTIC HYC90 GEN BURNER SYSTEM PRESSURE RECUCING r VALVE VENT GAS m 437C CUBIC FT (STP) SURGE CRUM GAS CECAY CRUMS 133 CU8tc FT EACH (TIP) i, .r 4> TEST TANKS CILUTICN CHEMICAL WASTE TANKS FANS Ion Exchangers l l STACX GAS MCNITCRS -- TO STACM Shipptr.g;crt At =le Pever Station Casecus Radicactive Vaste Precessir4 Sysi c FIGJRE 4.6 _ y c SECTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report l l IV. MONITORING EFFLUENTS a. Shippingport Atomic Power Station (continued) l Reactor plant exhausts from the Decontamination Room, Sample Preparation

Room, Radiochemistry Laboratory, Gaseous Waste System, and Compacting Station are continuously sampled with fixed filter samplers.

These samples are analyzed weekly for r j gross beta, cnd composited monthly to identify l gamma emitting isotopes. Processing of noble gases (predominantly short lived Xe-133) is accomplished by collecting and storing the gases in Shippingport RWP vent gas system. After sampling and analysis, the gases are released when the storage tanks are full. Figure 4.6 shows a schematic diagram of the gaseous waste system in the radioactive waste disposal system at Shippingport. b. 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 principal gamma emitters is performed. The principle gamma emitters include noble gases, iodines, and particulates. Figure 4.7 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 l the Cooling Tower, the Ventilation Vent located on the top of the Auxiliary

Building, and Supplementary Leak Collection 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 I-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 to identify particulate gamma emitting isotopes. Composites of the particulate samples are analyzed monthly for gross alpha determinations and quarterly for Sr-89 and Sr-90. 01OHHOZ H4 qMOCW3 >. N 33 7 7 E tH g O" g gCo.htZ o -@0N h aC4M "'U OH pO%M Mp4FNo ga Oqtr 0 ehM[>PQ N2" >a2 pu 8. [sSOE" $ y,RaE=5 $" GN IR LE OW OO CT R E l! f P S OH TA S 3 R O 0 T R R E E S T T E L L R I I f F F M E E O R R C P P AC =- Ks A D T E E L C C s R Y M U C 9! R 5 E g / R D R S O L B L r M A y O E C T R b A Y IC O g N = I $E T 3 C AK O CN R EA p R DT E [ g T g L g S I A D F E g B E g T y L S A ] A R L T O E U C C T C L I A R O A I T H F R 7 !p c A 4 lA L P j TAK A E l CN O EA C t R i U DT R C Q A I E H / F C AC T K \\ \\' N g O \\ f \\ s A 7 R E T W AK ( CN P EA LT V T C E F L R L IZ A L V I R H C g E V q A E R E T ?pr U FU S t O l H P c E K E n F E I t R o A I F P O r C T t T I 5 M C s S A U FE R A C f E 1 n C B E C E IT E ~ D A 3 V R N P O m-I T AI M R a_' A

r L

u R N 2 C N M O O Y O N s S T T 1 R3 I I N T A RT A ? T A r F 4 N ON Ml C r s D 1 A TA I A L rp u N D CI R E I O O 4 y AO FD D C s C R O EO RC bwI Ii SECTION TV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS 2. Airborne Effluent Treatment and Sampling a. Shippingport Atomic Power Station Gaseous wastes stripped from the reactor coolant at the Shippingport Station are circulated through a hydrogen analyzer and catalytic hydrogen burner system where the hydrogen is removed. The gases are initially stored in a vent gas surge drum, and subsequently compressed and transferred to one of four gas storage drums. The decayed gases are sampled prior to release. In addition, the exhaust from the containment is equipped with high efficiency particulate air filters and monitoring devices to prevent releases of radioactive particulates. Protective devices are utilized in the event of high airborne activity to automatically seal off the primary containment to prevent an inadvertent release of radioactivity. Reactor plant exhausts from the Decontamination

Room, Sample Preparation Room, Radiochemistry Laboratory, and Compacting Station are also equipped with high efficiency particulate air filters, and are continuously monitored for radioactive particulates by the use of fixed filter monitors. Exhausts from the Gaseous Waste System are filtered and sampled for radioactivity at the release point also. Continuous air monitors are located within the containers, and other plant areas to constantly monitor the condition of the air.

A stack release diagram is shown in Figure 4.8 identifying ventilation and gaseous release points for the Shippingport Atomic Power Station. b. Beaver Valley Power Station l Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor. Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and traces of the radioisotopes xenon, krypton, cobalt, and iodine are also present in the gaseous effluent. SECTION IV FIGURE 4.8 DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report SECTION IV DISCHARGE POINTS - CASEOUS WASTES Ventilation Vent \\ SLCRS Vent f g 1 / / / C C v / r-e [ Containment Ventilation System (Containment Air Nor ally recirc.-not vented) Auxiliary Building Ventilation System Exhausts Caseous wastes to Cooling Tower; Air Ejector CASEOUS RELEASE POIYr5 - BEAVER VALLEY POWER STATION Vaste Disposal Building .-Fuel Handling Building -Service Bldg. Exhausts (Filt ered) / j W Emerg. Filtration -Concrete Enclosure Exhaust Caseous Wast e Ventilation Exhaust (Filt ered) ; Release (Filtered) Air Ejector CASEOUS RELEASE POINTS - SHIPPINCPCRT ATOMIC PCUER STATION FIGURE 4.8 1 SECTION IV DUQUESNE LIGHT COMPANY l 1982 Annual Radiological Environmental Report l IV. MONITORING EFFLUENTS b. Beaver Valley Power Station (continued) The overhead gas compressor directs the radioactive gas stream to a gas surge tank. The system is designed to return most of the gas to the volume control tank in the Chemical and Volume Control System (CVC System). A quantity of gas is periodically 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, I the flow of the waste gases from the decay tanks is l recorded and rapidly diluted with about 1000 scfm of air in order to limit hydrogen concentration. The gases are then combined with the containment vacuum system exhaust, aerated vents of the vent and drain system, and the main air ejector effluent. 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 j the top of the cooling tower. The radioactivity levels of the stream are monitored continuously. Samples are also taken to determine the rate of activity released to the atmostphere. 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. l During a shutdown period after the containment has been sampled and the activity levels determined, the containment may be purged through the Supplementary Leak Collection Release System (SLCRS) Vent, or the ventilation vent located on top of the Auxiliary Building. 1 i SECTICP XV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report 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 and sampled periodically. Upon a high radiation 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 4.8 for the Beaver Valley Power Station... SECTION IV DUQUESME LIGHT COMPANY 1982 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS b. Beaver Valley Power Station (continued) Each filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type HEPA filters. The roughing filters remove large particulates to prevent excessive pressure drop 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. 3. Analytical Procedures for Sampling Airborne Effluents a. Shippingport Atomic Power Station The following tabulates the gaseous sampling and analysis schedule: Vent Gas Decay Tank Releases Sampling Type Of Detectable Sample Type Frequency Activity Analysis Concentration Gas From Prior to Gamma Ray Spectrum 3 x 10 -/ pCi/cc Decay Tank Discharge of Gas Sample

• Gas from Prior to H-3 2 x 10-7 pCi/cc Decay Tank Discharge Gas from Prior to C-14 1 x 10-7 pCi/cc Decay Tank Discharge A gas sample of measured volume is counted in a multi-channel analyzer for 10 minutes for gross activity.

The has activity (MDA)of3x10pcunter a minimum detectable uCi/cc for the predominant nuclide of Xe-133...

CTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiologicci Environmental Riport MONITORING EFFLUENTS 3.

Analvtical Procedures for Sameling Airborne Effluents (continued) Air Exhausts Sampling Type Of Samole Type Frequenev Activity Analvsis Dectectable Limits L) Air from the Plant Ventilation Ccatinuous Gross Gamma 1.2 x 10 uC1/cc (Gas, Exhan t Effluent Stream Channel 8 ORMS)* -10 5 x 10 uC1/cc (Particulate; CL2cael 12 ORMS)*

2) P1rticulate Filter in Plant Continuous Gross Beta 1 x 10 uC1/cc V:ntilation Effluent Stream Weekly Sample (Particulate)

~ Particulate Filter in Plant Continuous Principle Cac:ma 1 x 10 uCi/cc Vant11ation Effluent Stream Monthly Composite Particulate (Weekly if Gross Beta > 1 x 1013) -15 Pirticulate Filter in Plant Continuous Gross Alpha 2 x 10 pC1/cc Vcutilation Effluent Stream Monthly Particulate Pirticulate Filter in Plant Continuous Sr-89, Sr-90 5 x 10 pCi/ml (Sr-89) -14 Vcnt11ation Effluent Stream Quarterly y3 19 VCi/ml (Sr-90) Particulate (3) Charcoal Cartridge in Plant Continuous I-131 1 x 10 pCi/ml V:ntilation Effluent Stream Weekly 3 Chcrcoal Cartridge in Plant Monthly I-133 I-135 1 x 10 uC1/ml (I-131) Vcntilation Effluent Stream Monthly 1 x 10 pC1/ml (I-135) ~ (4) Ev:cuated Bomb Sample In Monthly H 2 x 10-uCi/mi Plant Ventilation Effluent Strsam (5) Ptreiculate Filter in Reactor Continuous Gross Beta ,1 x 10" pCi/cc Plant Exhaust from Decontami-Weekly Particulate tr. tion Room, Sample Preparation Roo], Radiochemistry Laboratory, Carrous Waste System. and Compacting Station. P2rticulate filter in Reactor Continuous Principal Gamma 1 x 10-DCi/cc Plant Exhaust from Decontami-Monthly Composite Particulate nntion Room Sample Preparation (Weekly if Gross Room, Radiochemistry Laboratory, Beta > 1 x 10 13) and Compacting Station. ORMS - Operational Radiation Monitoring System o Although the ORMS Channels have no specific function as far as effluent monitoring and reporting 19 concerned, these two (2) channels are being listed for information purposes. It is also noted clnt these channels provide alarm functions in the Main Control Room when levels of 1.2 x 10-6 uC1/cc are reached on Channel 8, or 1 x 10-9 uCi/cc on Channel 12. Additionally, they shut the v:ntilation system butterfly valves when levels of 1.2 x 10-0 uCi/cc are reached on Channel 8 or 1 x 10-7 pC1/cc on Channel 12. -. SECTION IV DUQUESNE LICHT COMPANY 1982 Annutl Radiclegicel Envircnmental Rtpsrt IV. MONITORING EFFLUENTS 3. Analytical Procedures for Sampling Airborne Effluents (continued) b. Beaver Valley Power Station The following tabulates the gaseous sampling and analysis schedule: Detectablo Gaseous Sampling Type Of Concentraticas Source Frequency Activity Analysis (uCi/ml)a b (1) Wasta Cas Decay Tank Each Tank Principal Gamma Emitters 10 4 Releases (2) Containment Purge Each Purge Principal Gamma Emitters 10-4c Releases -6 H-3 10 (3) Environmental Release Monthly Principal Gamma Emitters 10 Points (Gas Samples) ~0 H-3 10 -12 Weekly I-131 10 (Charcoal Sample) -10 Weekly I-133, I-135 10 (Charcoal Sample) ~11 Weekly Principal Gamma Emitters 10 (Particulates) (Ba-La-140, I-131, and others) 10" Monthly Gr ss a d Composite (Particulates) ~11 Quarterlyd Sr-90 and Sr-89 10 Composite (Particulates)

• The above detectability limits for activity analysis are based on technical feasibility and on For some nuclides, the potential significance in the environment of the quantities released.

lower detection limits may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported. For certain mixtures of gatr.:a emitters, it may not be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much-higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides which are measurable.

• Analyses shall also be performed following each refueling, startup, or similar operational occurrence which could alter the mixture of nuclides.

To be representative of the average quantities a-d concer trations of radioactive materials in d particulate form released in gaseous effluents, samples should be collected in proportion to the rate of flow of the effluent stream. SECTZON IV DUQUESNE LXGHT COMPANY 1982 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS 4. Results a. Shippingport Atomic Power Station Analyses for the particulate eirborne radioactivity in the plant effluents indicated that the gross alpha and beta activity concentrations were at or very near the Lower Limit of Detection (LLD). Analytical results of charcoal filter samples showed that there were no instances of radioiodine concentrations above LLD. Specific gamma analyses of weekly and monthly composite air filter samples were also performed. Results snowed naturally occurring radioactivity typical of "backgredad air" and nuclides attributable to worldwide fallout from nuclear weapons testing. During 1982, there were three instances where activity, attributable to plant operations, was measured. In the first instance, Cobalt-60 activity was measured in the Decontamination Room Waste Receiver Exhaust. The rotal amount of Co-60 activity released was 0.000000000663 curies at a 10-13 pCi/ml. In the concentration of 1.54 x second instance. 0.000000000157 curies of Co-60 activity was released from the Decontamination Room Waste Receiver Exhaust at a concentration of 10 -12 pCi/ml. In the third instance, 1.43 x Cobalt-60 activity was measured in-the Reactor Plant Main Ventilation Exhaust. The total amount of Co-60 activity released was 0.000000298 curies at a concentration of 4.76 x 1715 pCi/ml. Radiostrontium anslyses of quarterly composite air filter samples showed Sr-89 and Sr-90 concentrations in air which were at or near the 10 -14 minimumdetectableconggntrationsof 5 x uC1/m1, and 1 x 10-uC1/ml, respectively. The levels of Sr-89 and Sr-90 observed were extremely low and are typical of " background air" radiostrontium levels. Also tritium and carbon-14 gaseous releases in the effluents were estimated based on analyses of primary coolant and found to be below the predicted levels presented in the LWBR Program Environmental Impact Statement. There were thirteen (13) releases of gaseous radioactivity from the Shippingport Atomic Power Station during 1982. The total gaseous - SECTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report radioactivity released from the Shippingport Atomic Power Station during 1982 was approximately 0.00154 l curies of Xe-133. The amount of radioactivity released from the Shippingport Atomic Power Station during 1982 was extremely small. and had a negligible effect on the environment as shown in Section V.6. b. Beaver Valley Power Station Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in the Environmental Technical Specifications. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi-Annual Effluent Reports for 1982. i o _ SECTION IV DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report IV.' MONITORING EFFfUENTS C. Solid Waste Disposal at the Shippingport and Beaver Valley Power Stations During normal operations and periodic maintenance, Shippingport and Beaver Valley Power Station generated small quantities of radioactive solid waste materials such as evaporator concentrates, contaminated rags, paper, plastics, filters, spent ion-exchange resins, and miscellaneous tools and equipment. These were disposed of as solid radioactive waste. At Shippingport Atomic Power Station and the Beaver Valley Power Station, the compactable wastes were segregated and compressed in a 55 gallon compactor to minimize disposal volumes. The compressed waste, plus other drums of noncompactable waste, were then shipped offsite for disposal at a site owned by the Department of Energy or 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 buried at the Shippingport or 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 and the Nuclear Regulatory Commission. Shipments offsite were made in accordance with Department of Transportation regulations. Figure 4.9 depicts solid waste handling at the site. In 1982, the Shippingport plant disposed of a total of 6312 cubic feet of radioactive solid waste having a total radioactivity of about 0.217 curies. This included twelve (12) shipments of low level wastes. At Beaver Vuiley Power Station approximately 10,392 cubic feet of radioactive solid waste was shipped offsite in 1982. The actual burial volume of solid waste is slightly higher due to container size (11,052 cubic feet). The thirty-three (33) shipments contained a total activity of 383.4 curies. Industrial solid wastes from both plants were collected in portable bins, and removed to an approved offsite burial ground. No burning or burial of wastes was conducted at either the Beaver Valley or Shippingport plant. l l SECTION IV FIGURE 4.9 DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report SECTION IV SOLID WASTE DISPOSAL DIACRAM FIGURE 4.9 HADIOACTIVE SOf.D) WASTE DISPOSAL Radioactive Waste Sludge Druming a Disposal Evaporator Station i D h. 'on oo'oY 2 Misc. Radioactive Compactor and Solid Wastes 3 running Statica ); m I> -,m o Spent Radioactive I Special Shipping l, Q Resin -l Casks & Containers I g 2 - 00' Mo o' a l l INDUSTRIAL SOLID WASTE DISPOSAL DIACRAM Water Filtered; i Filt ers drummed---- .I A 6 9 r Sludge From Water _f ) Treatment Plant and j Sewage Treatment _ OO, 5 Planc (3VPS) c 0 Trash Basket - Beaver Vallev Debris and Trash Hoppar e Screenhouse Shippingport 3 From Screenhouse i I m o-a ? 8u Trash & Carbage Storage Bin g h o FIGURE 4.9 COI SECTION V - A DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program 1. Program Description The program consists of monitoring water, air, soil, river bottoms, v'egetation and foodcrops, cow's milk, ambient radiation. levels in areas surrounding the site, and aquatic ~ life as summarized in Table V.A.l. Further description of each portion of the program (Sampling, Methods of Sample Analysis, Discussion and Results) are included in parts V-B through V-I of this report. V-B - Air Monitoring V-C - Sediments and Soils Monitoring V-D - Vege'tation and Foodcrops V-E - Cow's Milk J. V-F - Environmental Radiation Monitoring sc V-G' Fish' V-H - Surface, Drinking and Well Waters V-I - Estimates of Radiation Dose to Man 4 i ! + 4 - ) m- TABLE V.A.1 g y C0;:SOLIDATED RADIOLoCICAL ENVIR2NME*;TAL MINITCRICC PRoGRAN <a e DLC Sakple Analysis (b) Type of Sample Points Sample Point DescrtMion Sample Frequency Preparation Frequency Analysis Sample ICI -131 Weekly Composite (d) Cross b I Farm Continous Sampilng 1. Air Particulate 13. Heier'sSh ppingport, PA. (S.S.) with sample collect-Monthly Composite (d) y -scan and Radiolodine 3046.1 Industry, PA (Tire Co.) tion at least 32 Midland,PA(5.5.) weekly. QuarterlyComposite(d) 48(a) Weirtoa, W (a? Sr-89, 90 51 Aliquippa PA (5.5.) 47 East Liverpool, Oil 27 Brunton's Farm G 28 Shernan's Farm 3 298 Beaver County llospital i Quar:erly (k)I "g y-Dose 2. Direct 30 S hippingport, PA (S.S.) Continous I Annually " Radiation 13 Meyer's Fun (TLD) (4 46 Industry,PA(Church) ph 32 Hidland,PA(S.S.) gg 48(a) Weirton, W (a)

, U 45.1 Raccoon Twp, PA Kennedy's Crnrs.

g i 51 Aliquippa, PA (S.S.) -h M 47 East liverpool. OH s E DLCf DLC# Quarterly (k) y-Dose ~0 Raccoon Park Continuous { 'O 8 ~ ~ - ~ West. Byr. School 70 (TLD) Annually gh 28 Shernan's Farm 81 Southside School i 71 Brighton Twp. School 82 llanover Municipal 81dg. g. 12 Logan School 8,3 Mill Creek Rd g 298 Beaver County llospital 14 llookstown 73 Potter Twp. School 84 llancock Co. Children Home F 74 Conn. Col-Center Twp. 85 Rts. 8 & 30 Intersection 3 75 lloit Road 86 E. Liverpool Cahills House 76 Raccoon Twp. School 92 Georgetown Rd. 77 GreenGardenRd(Wayne's) 87 Calcutta Road 59 Irons 88 Midland Heights 78 Raccoon Mun. Bldg. 89 Ohioville 27 Brunton's Farm 90 Fairview School 79 Rt.18 & Rt.151 10 Shippingport Boro, PA 15 Georgetown 45 Mt. Pleasant Church 46.llndustry PA Tire Co. 60 llaney's Fara 91 Pine Grove Rd and Doyle Rd. 93 Sunset Hills, Midland 94 McCleary Rd, Wilsoa 95 McCleary Rd, Hollie Williams .i D G <= S.S. - Substation b TABl.E U.A.! CONSOI,IDATED RADIGI.OGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) M DLC g Sdmple Sample Analysis (b) g Type of.Samp1.e. . Points.... Sample Point. Description, S mple Frequency. _, Preparation l'rt guency Analysi.s_ <= z 3. Surface 49.1 Arco Polymers (a) Intermittent Monthly Composite of Gross 8 8 Water 2.1 Dnunstream (!!idland) Crucible Coltosite Samples (j) Ucekly Sample (d) Gioss = 3 Shippingport Atomic Power Ucekly Grab Quarterly Composite..... ___. _, y -n an Collected Weekly Co-60. H.3 Station Dischan ge sareples Only Sr-89, Sr-90 49(a) Mont9tmiery Dam (Upstream) 2A Dnunstream BVPS.0ut fall 5 [ast i Iverpool '(r aw water) Daily Grab Sample Only - Collected Weekly (j) ~ %D Groalua ter 13 11 eyer's farin O 14 Hookstown, PA 15 Georgetorn, PA E 11 Shippingport Boro Quarterly Quarterly y-scan, Gross s ~ Gross a, H.3 5. Drirking 4 Midland, PA (Hidland Water) Intermittent ('} Ueekly Composite of y-scan, 1-131 & l3 Treatment Plant) Sample Collected Dally Sample _(d)__ PE Gross a, Gross e 2 "' IbnthlyComposite(d)) Hectly Quarterly Composite (d H-3, Co-60, Sr-89, 90 KC s S fast Liverpool, OH (East Live. pool Nater Treatmerit E9 Plant) __ g[ <O 6. Shoreline 2A Downstream BVPS Outfall Semlannual Semiannual y - scan, Gross 8 $4 Sedia.ent Gross a j h 3 Vicinity SAPS Discharge Uranluen Isotopic 49 Upstream Side of fluntgomery Sr-89, 90 g Dain (a) 50 Upstream side of New Cumtierland y Ud* ._ E III Seari ht's Dairy Weekly Weekly sample from I-131 1. Hilk 25 9 Searight'sonly-)-- 61* Allison Blweekly'(grazig 62*

r. yon 3 - scan 66*

Straight Monthly (Indoors) Sr-89, 90 69* Collins Binkly (g) 1-13], Cs-137 96ia) Wirmisteim r Wton animals are 97* in ylass on pasture; 98* Ibxall OLuuni) nont.hly at otler 99* t urpich t.ifnes. 27 Brunton's trairy pil Ptothly nmthly y - scan 29A Nicnl's niity th) Sr-89, 90 1-131, Cs-137 G

• Aklitional dairies repired tsy f>wi <

ntal Technical Siecification 3.2.1.D.2. In aklition to Searight's ISite 25), three dairies ase ~> i higtest detosition factors. Sites 27 arvi 29A are rerpired for tin Shi[pinq[ ort prtyram. selected wien milk is available ic TABl.E U.A.I CONSOLIDATED RADIOLOGICAL. ENVIRONMENTAL MONITORING PR(tr. RAM .9 (Continued) g 2 e DLC Sample Sample Analysis Analysis (b) ijpe of Sopple _ Poin.ts. _.Sm.ple Point Desc ription,._. Sap.ple f r equency,_Prepara tion,_ Frequency.,_ 8. Fish 2A Vicinity of BVPS #1 Semiannual Cose.posite of edible g-state on edible Station Olschange and parts by species (1) portions Shippingport Dis. Sta. 49(a) Upstream $1de of Montgomery Dam 9. N d Crops (Shipp. 10 (Three locations within Arinual at Conposite of each 1-scan (Georg. 15 5 miles Selected by harvest if saiiple species 1-131 on 9, een (Indus. 46 Coi.pany) available leafy veijetables g c= 4R(a), _):eir. ton, UV _( IG. Tecostuff and 25 Scarlyht's Dairy Farm Monthly __ _ _ _ _. Monthly _ __.. _ ___ _._._ __.__._ 3-scan _ _ ____g S*'er forage __ . _ _ _ _ ____ _._ _._,_ _ ___,,. ______. ___ __. Quar _ter k _ __ _ Quarterly Cuaposite Sr-90

11. Soil 13 Meyer's Farm Every 3 years 12 Core Sampics y-scan gg 30 Shippingport, Pa.

(1982, 1985, etc.) 3" Deep (3" Dia. Sr-90 go 46 Industry, Pa. at each location Gross e oh 32 (florth of Site) Hidland (approx.10' Gross a jg g 48(a) Heirton. W. Va. radius) Uranium Isotopic gn 51 Aliquippa, Pa. u ,., h f 47 E. Liverpool Oh. 27 Brunton's Dairy j 22 South of BVPS Site j o 29A Nic hol's Dai ry _ _ _ _e5 l a 1l' E i 4 h; SECT 10N V - A DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report TABLE V. A.1 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) In these cases a gamma isotopic analysis is done if the beta activity exceeds the reporting level of 0.53pCi/m3. gross i (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location. (e) Composite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (f) Weekly milk sample from Searight's Dairy is analyzed for 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 frte 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at locations 49.1 and 2.1. 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) TLD's are collected quarterly and annually from each monitoring location. - SECTION V - A DUQUESNE LIGilT C0}!PANY 1982 Annual Radiological Environmental Report Additional Notes: -- Sample points correspond to site numbers shown on maps. All Iodine I-131 analyses are performed within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of sample collection if possible. All Air samples are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for Gross Beta.._ m m ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAN SUMMAR1r o d Name of Facility Duquesne Light Company Docket No.56-334 OZ Pennsylvania Reporting Period Annual 1982 LocationofFacilityBeaver(County,5 fate) 1 Number of Analysis and Lower Limit Medium or Pathway Total Number of ~All Indicator Locations -location with Highest Quar. Mean Control Locations Monroutine Sampled of Analysis Detection

• • Mean (f)

Name

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

• • Range Distance and Directions ** Range

• • Range Measurements ***

5 co Welrton,WV M. 48 A,tr Particulate Gross (519) 2.5 26(519/519) Allautppt, PA No. 51 27(52/52) 27(51/51) O and Rgdlolodine Beta (10-49) 8.5 miles - ESE (11-42) (12-49) c$ (X10-3pC1/Cu. M.) Sr-89(40) 2 LLD E'. $" Sr-90 (40) 0.1 0.21(19/40) Sherman Dairy No. 28 0.30(2/4). 0.20(2/4) O p (0.12-0.36) (0.30-0.31) (0.16-0.24) E$ H m I-131($19) 10 LLD j g r* Be-7 20 106(120/120) East Liverpool No. 47 114(12/12) 112(12/12) 0 Y Gamma (120) g (45-215) 6.5 miles - W (63-200) (63-187) na 4 0 K-40 10 39(21/120) Meyer's Fara No. 13 81(2/12) 50(3/12) 0 (15-131) 1.6 miles - SW (31-131) ( 2',-88) $9 O Cs-137 0.6 1.9(4/120) Weirton, WV No. 48 1.9(1/12) Same as 0 (1.1-1.9) 20 miles - SW High Location @ M re Ra-226 10 29(1/120) Weirton, WV to. 48 29(1/12) Same as 0 8" 20 miles - SW High Location

xs Th-228 1

2.9(8/120) Midland, Pa. No. 32 4.3(1/12) LLD 0 $o (1.6-5.9) 0.9 mile - NNW N Others Table V.A. LLD H c beM t [ i. Nominal Lower Limit of Detection (LLD) g 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 B) ro ENVIR0fMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

I Nane of f acility Duquesne Light Company Docket No.

50-334 d

Location of Facility Beaver, Pennsylvania Reporting Period Annual 1982 (County,5 tate) 4 Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator locations location with Highest Quar. Mean fontrol locations knroutine Sanpfed of Analysis Detection

• 3 Mean (f)

Nane

• • Mean (f)'Miian (f)

Reported 5

ju_n i t o_f _M_ea_s_u_r_eme_nt ) Performed (LLD)

• • Range Distance and Directions ** Range _

• • Range Measurements ***

00 u

No, 49 g

Sediment Gross (8) 0.3 16(8/8)

BVPS' Discharge No. 02A 21(2/2) 16(2/2) 0

3c (pCl/g)

Alpha (9.0-21)

River Mlle -- 35.0 (20-21)

(11-20)

(dry weight)

Gross (8) 1.0 40(8/8)

BVPS Discharge No. 02A 49(2/2) 39(2/2)

O ts Beta (24-52)

River Mile -- 35.0 (46-52)

(35-43)

E$

o.

c:

73 Sr-89 (8) 0.2 LLD o- -:

Sr-90 (8)

O'.04 0.069(6/8)

BVPS Discharge No. 02A 0.082(2/2) 0.057(2/2) 0

$M (0.042-0.11)

River Mlle -- 35.0 (0.054-0.11)(0.057-0.057) r t-1 Ganna (8)

$n Be-7 0.2 1.8(2/8)

BVPS Discharge No. 02A 2.4(1/2)

LLD 0

(1.2-2.4)

River Mlle -- 35.0

$0 l

N n

K-40 0.5 13(8/8)

BVPS Discharge NO. 02A 16(2/2) 14(2/2) 0 h

0 (4.0-17)

River Mlle -- 35.0 (15-17)

(12-16) g4 Co-60 0.0; 0.58(4/8)

BVPS Discharge No. 02A 1.0(2/2)

LLD 0

N (0.082-1.9)

River Mile -- 35.0 (0.11-1.9)

Cs-131 0.02 0.37(8/8)

BVPS Discharge No. 02A 0.63(2/2) 0.37(2/2) 0 g

(0.045-0.78)

River Mile -- 35.0 (0.47-0.78) (0.32-0.42) m O

Ce-144 0.09 0.62(1/8) mntgomery Dam No. 49 0.62(1/2)

Same as 0

N High Location River Mlle -- 31.0 Ra-226 0.1 2.3(8/8)

BVPS Discharge No. 02A 3.5(2/2) 2.3(2/2) 0 (1.2-4.0)

River Mlle -- 35.0 (3.1-4.0)

(2.0-2.6)

H Th-228 0.02 1.5(8/8)

BVPS Discharge No. 02A 2.0(2/2) 1.5(2/2) 0 (0.66-2.4)

River Mile -- 35.0 (1.6-2.4)

(1. 3-1. 7) p Naninal tower Limit of Detection (LLD) g Mean and range based upon detectable measurements only. Fraction of detectable measurenents 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 B)

ENVIRONMENTAL RADIOLOGICAL ENITORING PROGRAM

SUMMARY

us 50-334 g

Name of Facility Duquesne Light Company Docket No.

H Penns Ivania Reporting Period Annual 1982 o

Location of facility Beaver(dounty,ftate)

Z Ninnber of Analysis and Lower Limit Medtima or Pathway Total Number of

-All Indicator locations Location with Highest Quar. Mean Control Locations Nonroutine Sanpled of Analysis Detection

• %an (f) 7ane HMean (f)'Hean (f)

Reported 5>

(tinit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range

• R ange be asurement s* *

• co

'4 Montgomery Dan No. 49 Sediment Others Table V.A.

LLD c

(pCi/9)

(dry weight)

U-233(8) 0.01 0.44(8/8)

Montgomery Dan No. 49 0.49(2/2)

Same as 0

4" (continued) and (0.13-0.74)

River Mile -- 31.0 (0.44-0.54)

High Location yg U-234 o.

D U-235 (8) 0.01 0.024(6/8)

BVPS Discharge No. 02A 0.034(2/2) 0.014(2/2) 0

• C (0.011-0.040)

River Mile -- 35.0 (0.028-0.040) (0.011-0.017)

O 2 U-238 (8) 0.01 0.34(8/8)

N. Cumberland D. No. 50 0.39(2/2) 0.36(2/2) 0

7. M (0.10-0.54)

River Mile -- 54.0 (0.37-0.40)

(0.32-0.40) g[

pa i

< n

>* Ok oB?

m 4

2 5e eli" H

be M

Nuninal Lower Limit of Detection (LLD)

Hean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) f Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications to (Appendix B)

L M

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SlMMARY Q

h Name of Facility Duquesne Light Company Docket No.

50-334 4 I location of Facility Beaver, Pennsylvania Reporting Period Annual 1982 I

(County,5t at e)

>i Analysis and lower Limit Number of Medium or Pathway Total Number of All Indicator locations location with Highest Quar. Mean Control Locations Nonroutine Sampled of Analysis Detection

• FMean ( f )

hame

• • Mean (f)

• • Mean (f)

Reported e

(t> nit of Meas:acnent) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurement s"*

[9 Weirton WV No. 48 g

c Soil Gross (10) 0.3 15(10/10)

5. of Site BVPS No. 22 28(1/1) 12(1/1)

O (pCi/g )

Alpha (8.7-28) s (dry weight)

Gross (10) 1.0 37(10/10)

5. of Site BVPS No. 22 51(1/1) 32(1/1)

O Eg c:

Beta (30-51) gQ O M Sr-90 (10) 0.05 0.12(9/10).

East Liverpool No. 47 0.21(1/1) 0.061(1/1) 0 gy l (0.049-0.21) og pi Gamma (10)

@ [

e c7 o

Be.1 0.2 0.26(2/10)

Nicol Dairy No. 29A 0.31(1/1)

LLD 0

m (0.21-0.31)

D K-40 0.5 13(10/10)

5. of Site BVPS No. 22 17(1/1) 13(1/1) 0 (10-17) 9 i

Cs-137 0.02 0.68(10/10)

Midland No. 32 1.0(1/1) 0.28(1/l) 0 (0.28-1.0) r, l

ra" Ce-141 0.03 0.13(1/10)

Aliquippa No. 51 0.13(1/1)

LLD 0

g o

Ra-226 0.1 2.2(10/10)

Meyer Farm No.13 3.2(1/1) 1.4(1/1) 0 0

(1.4-3.2j N

f H i br.

M Nominal Lower Limit of Detection (LLD)

• • Meap 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 B)

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O ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SIM SRY 5

z Nee of Facility Duquesne Light Company Docket No.

50_7 u Location of Facility Beaver Pennsylvania Reporting Period Annual 1982 t

I (County State) c e=W Number of p

Analysis and Lower Limit Medium or Pathway Total Number of All Indicator locations Location with Highest Quar. Mean Control Locations Nonroutine o

Sampled of Analysis Detection

• • Mean (f)

Nme

• • Mean (f) M an (f)

Reported (Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurements ***

m C

e Feed and Forage Sr-90 (5) 0.003 0.047(5/5)

Searight Dairy No. 25 --

One sample 0

n (pC1/g)

(0.018-0.075) 2.4 miles - SW location g,

r (dry weight)

O O

Gamma (13)

E 0

o Be-7 0.3 1.2(9/13) g oo (0.46-2.5) a w

O m

2 K-40 0.5 16(13/13)

" M (8.0-32)

M ta Cs-137 0.03 0.062(1/13) 0 r m e

d Th-228 0.05 0.20(3/13) 0 5

g Q

(0.13-0.26)

N e

x Others Table V.A.

LLD p

'u caW N

2 C

e e

H b

e-M f

N Nominal Lower Limit of [htection (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 B)

-- Searight's Dairy is the only Feed and Forage sample location, therefore, all of the data for this locatid is listed under All Indicator 1.ocations.

'i ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

un}

Name of facility Duquesne Light Company Docket No.

50-334 Location of Facility Beaver. Pennsylvania Reporting Periot Annual 1982 oZ (County,5 tate) l Number of Analysis and Lower Limit Medtime or Pathway Total Number of All Indicator Locations Location with Highest Quar. Mea' Control Locations Nonreutine 5

03 Sanpled of Analysis Detection

• • Mean (f)

Name

• • Mean (f) 7 Mean (f)

Reported junitofMeasurement) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurements ***

Weirton, WV g

h. M o

Food and Garden 1-131.(8) 0.006 LLD C

Crops (pCl/g)

(wet weight)

Gamna (8)

Be-7 0.3 0.30(1/8)

Shippingport, PA 0.30(1/1)

LLD 0

f E-No. 10 gg O M K-40 0.5 3.2(8/8)

Weirton, WV No. 48 6.l(1/2)

Same as 0

e us (1.1-6.1) 20 miles - SW High Location Cs-137 0.01 0.044(1/8)

Industry, PA No. 46 0.044(1/2) LLD 0

@ [

1m 2.0 miles -- NME e n y

Others TABLE V. A.

E< n e ok O

0 E-5 3

3 l

H b

e 4

M f

4 pominal Lower Limit of Detection (LLD) b l

Mean and range based upon detectable measurements only. Fraction cf 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 4

(Appendix 8) i t

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM StMIARY CA Nme of Facility Duquesne Light Company Docket No.

50-334 E!

w Location of Facility Beaver, Pennsylvania Reporting Period Annual 1982 oZ (County,$t ate) 1 Analysis and Lower Limit Nasuber of Meditsa or Pathway Total Number of All Indicator Locations location with Highest Quar. Mean Control Locations Nonroutine e

e

$mpled of Analysis Detection

• • Mean (f) 7me

• • Mean (f) 7 'Mean (f)

Reported (Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurements ***

Brunton Dairy y

No. 27

s Milk I-131(152) 0.2 LLD C

b (PCi/l)

Sr-89 (119) 2 LL D hg C Sr-90 (119) 1 4.7(119/119)

Collins No. 69 9.9(18/18) 2.l(12/12) 0 A-C S

(0.67-14)

(3.0-14)

(1.6-4.0) o w in Gauna (119)

$y K-40 100 1360(119/119)

Douglas No., 97 1650(10/10) 1260(12/12) 0 w

p (860-1900)

(1120-1900)

(1100-1540)

$[

e e o g

Cs-137 5

7.l(22/119)

Straight No. 66 10(1/2)

LLD 0

m (4.2-11) g Others Table V.A.

LLD a

b i

F l

E 3

l i

Naninal 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)

.-3 Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendix B) eM

?

i

~

cn ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Duquesne Light Company Docket No.

50-334 g

o"4 location of Facility Beaver, Pennsylvania Reporting Period Annual 1982 (County, State) 1 Nimber of 5

Analysis and Lower Limit Medium or Pathway Total Nisaber of All Indicator Locations Location with Highest Quar. Mean Control locations Nonroutine o0 S mpled of Analysis Detection

• • Mean (T)

Name

• • Mean(f) **Mean (f)

Reported

[UnitofMeasurement) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurements ***

P Weirton,WV M. 48 C4W External Radiation (176) 0.05 0.18(176/176)

Raccoon Mun. Bldg.

0.20(4/4) 0.11(4/4) 0 (mR/ day) quarterly)

(0.13-0.21)

No. 78 (0.20-0.21) (0.16-0.18) f@

c..o (44 annual) 0.05 0.17(44/44)

Raccoon Mun. Bldg.

0.20(1/1) 0.17(1/1) 0 y@

(0.13-0.20)

No. 78 e en O

• 4 09 m td D -

H a 5

i. 8 24

s U

Montgomery Das g

h. 49 n

D Fish Gamma (4)

(pCl/g)

K-40 0.5 2.4(4/4)

BVPS Discharge No. 02A 2.9(2/2) 1.9(2/2) 0 (wet weight)

(1.7-3.3)

River Mile -- 35.0 (2.6-3.3)

(1.7-2.2) g r

"O Cs-137 0.01 0.029(1/4)

Montgomery Dam No. 49 0.029(1/2) Same as o

o River Mile -- 31.0 High Location N

i Othe"5 Table V.A.

LLD l

H br m

ta Naminal 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 B)

mn ENVIRONMENTAL RADIOLOGICAL MONIT CING PROGRAM

SUMMARY

dox N me of Facility Duquesne Light Company Docket No.

50-334 Location of Facility 8eaver, Pennsylvania Reporting Period Annual 1982 (County,5 tate) p Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator tocations Location with Highest Quar. Mean Control Locations Nonroutine l

Sampled of Analysis Detection

• • Mein (f)

Name

• • Mean (f) **Mean (f)

Reported (Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurements ***

,e Montgomery Das No. 49 Surface Water Gross (72) 1 1.6(1/72)

BVPS Discharge No. 02A 1.6(1/12)

LLD g

(pC1/d)

Alpha F.tver Mlle -- 35.0 oc Gross (72) 1 5.l(72/12)

BVPS Discharge No. 02A 6.7(12/12) 5.2(12/12) 0 Beta (2.3-9.5)

River Mlle -- 35.0 (4.7-9.5)

(4.1-6.9) e if c

Ganna (72) g Q

o m

Ra-226 100 120(1/72)

Crucible Steel No. 2.1 120(1/12)

LLD 0

g y

p m

[

b Others TABLE V.A.

LLD w

a d

Sr-89 (24) 1.5 LLD mc Sr-90(24) 0.4 LLD 4

Co-60 (24)(a) 1 LLD El

/

Tritium (24) 100 420(22/24)

BVFS Discharge No. 02A 1420(4/4) 150(3/4) 2 (10-2580)

River Mlle -- 35.0 (220-2580)

(110-210) g w

N

?

3 (a) Co-60 analyzed by high sensitivity method.

• -1 b

Nominal Lower Limit of Detection (LLD) e Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)

M

• • • Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the 8eaver Valley Power Station Technical Specifications (Appendix 8) b

i ENVIRONMENTAL RADIOLOGICAL MONIT0k!NG PROGRAM StM4ARY g

M Name of Facility Duquesne Light Company Docket No.

50-334 g

W Location of Facility Beaver, Pennsylvania Reporting Period Annual 1982 (County,5 tate) 9 Number of

~

I Analysis and Lower Limit Medium or Pathway Total Number of All Indicator tocations Location with Highest Quar. Mean Control Locations Nonroutine y

5mpled of Analysis Detection

• • Mean (f)

Name

• • Mean(f)

• • Mean (f)

Reported to lunitofMeasurement) Performed (ttD)

• • Range Distance and Directions ** Range

• • Range Measurnments***

I Drinking Water I-131(104) 0.2 0.25(1/104)

Midland Pa. No. 04 0.25(1/52) --

0 o

River Mlle -- 36.3 (pCl/f) i Gross (24) 0.6 LLD W

E-Alpha 5n 0

Gross (24) 1 4.7(24/24)

Midland Pa. No. 04 5.0(12/12) o us Beta (2.9-6.5)

River Mile -- 36.3 (3.0-6.0)

W :4 Gamma (104)

Table V.A.

LLD S$b Sr-89 (8) 1.5 LLD m o G

W Sr-90(8) 0.4 LLD m

n o a Co-60 (8)(a) 1 LLD dOk n

O$

Tritium (8) 100 160(6/8)

East Liverpool No. 5 175(4/4)

(110-270)

River Mlle -- 41.2 (110-270) g4 anmW

?

o O

n i

H (a) 00-60 analyzed by high sensitivity method.

g eM fkuninal lower Limit of Detection (LLD) 4 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 f

(Appendix 8) w l

?

M t

en MO ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SIMtARY H

N me of Facility Duquesne Light Company Docket No.

50-334 g

t 4

Location of Facility Beaver, Pennsylvania Reporting Period Annual 1982 i

(County,5 tate)

Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator locations location with Highest Quar. Mean Control Locations Nonroutine S mpled of Analysis Detection

.rHean (f)

Hme

• • Mean (f) ' Mean (f)

Reported G

(Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range

• • Range Measurements ***

g Ground Water Gross (16) 2 LLD g

Georgetown AIS t

a (pCi/I)

Alpha g

pct /I G'oss (16) 1 3.0(15/16)

Hookstown Pa. No. 14 4.4(4/4) 1.8(4/4)

O Beta (1.2-5.3) 3 miles -- WSW (3.6-5.0)

(1.4-2.5) fE

c. c 7%

Gama (16)

Table V.A.

LLD w en Tritium (16) 70 150(11/16)

Georgetown,Pa. No. 15 160(4/4)

S ee as 0

j y i

(90-210) 4.6 miles -- WNW (110-210) Hioh Location r

2:

i 5

<0 m ok oo B

too E-N o

O F1" t

s$

Nominal Lower Limit of Detection (LLD)

M Hean 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 (Decenber 1975) and the Beaver Valley Power Station Technical Specifications (Appendix B) f N

t

SECTXON V - A DUQUESNE L8GHT COMPAMY 1982 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 B,

Environmental 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 date indicate the ranges of values are in good agreement for both periods of time.

In a few cases where activity was detected, some of the activity was attributable to previous nuclear weapons tests and the 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 Shippingport and Beaver Valley Power Station has not resulted in any detectable changes to the environment attributable to either station.

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 SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1982 Annual Radiological Environmtntal R port (Page 1 of 4)

TABLE V. A. 3 (Page 1 of 4)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMARY Name of Tacility Shiseingport Atesic Power Station Docket No.

Not Arslicable Name of Tacility Beaver vallev Pever station Docket No.

50-334 Location of Tacility Saaver. 7ennsvivania Reportin8 Period CT 1974 - 1975 (County, StateJ P1t!-OPutATICNAL PROC 1 TAM SCMMARY (CCMBUCD 1974 - 1975)

Media or Fathway Lower Limit Sampled Analysis and Total Number of All Indicator 14 cations (Unit of Measurement) of Analvsis Performed Detection U2 Maan. (f) fante 5/

Surface Water

' Cross Alpha (40) 0.J 0.75 40 0.6 - 1.1 Gross Seta (120) 0.6 4.4

/120 2.5 - 11.4 Gama (1) 10 - 60

< LLD Tritium (1:1) 100 300

• /121 180 - 500

$r-89 (0)

$r-90 (0)

C-14 (0)

Driski=g Vater I-131 (0)

Cross Alpha (50) 0.3 0.6

'/ 0 0.4 - 0.8 5

Gross Sata (208) 0.6 3.8 208/ 208 2.3 - 6.4 Gamma (0)

IU/211 130 - 10U0 Tritium (211) 1C0 310 C-14 (0)

St-49 (0)

Sr-90 (0)

Ground Water Gross Alpha (19) 0.3

< Lia 73/75 *I 1.3 - 8.0 I

Cross Beta (76) 0.6 2.9 II Tritium (81) 100 440

/81 80 - 800 Cama (1) 10 - 60

< Ua 35/188 0.002 - 0.004 Air Particulates Cross Alpha (188) 0.001 0.003 and Gaseous PC1/d Cross Seca (927) 0.006 0.07 I27/927 0.02 - 0.32 Sr-89 (0) l l

$r-90 (0) 2/

I-13 1 (816) 0.04 0.08 516 0.07 - 0.08 Gamma (197)

I/

2r.%-95 0.005 0.04 197 0.01 - 0.16 50/197 0.02 - 0.09 Ru-106 0.010 0.04 Ca-141 0.010 0.02

/197 0.01 - 0.04 Ca-144 0.010 0.02

/197 0.01 - 0.04 Others < um

__,__.,ama-~

SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 L982 Annual Radiological Environ =en:al Report (Page 2 of 4)

TABLE V.A.3 (Page 2 of 4)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRE! SUE!ARY 54.e of Facility ThinirTrert At-mi: ?m? T e s tier. Occhet No.

Net Anliesble Na=a of Fac O ty leaver '.'allev iover ses:::s Oceket No.

x-n.

locatien of Facility 1es'rer. Pear.svi m ia Raporti=g Pericd C* 1971 - 1973 (County, State)

PRZ-CPI 2ATICNAL PROCVM SMJLIT (COM3I:C 1974 - 1973)

Madi m or Pat hay icver 11=it Sa= pled Analysis a d Total Nunber of All Indicator 14 cations (rsi: of Measure:asti of A=.alvsis Perfer:ed Oetectien *D Maas. (fi ?lrt=2e

!cti Gross Alpha (0)

PCi/3 (dry) 64/4 14 - 3:

(Tamplace Sa= piss)

Grose 3 eta (64) 1 22 6

1/4 6

St=89 (64) 0.*3 0.4 Sr-90 (64) 0.05 0.3.s

/64 0.1 - 1.3 U-224,233,233 (0)

Cama (64) 63 E-40 1.3 13

/64 3 - 24 Cs-137 0.1 1.3 36/ 64 0.1 - 6,3 I/4 0.2 - 3 C4-144 0.3 1.1 6

U /4 0.1 - 2 6

ZrNb-95 0.05 0.3 3/64 0.3 - 2 Ru-106(D) 0.3 1.1 Others

< II.D Soil Gross Alpha (0)

PC1/3 (dry) 8 (Core Sa=ples)

Cross Beta (8) 1 21

/8 16 - 23 Sr-89 (8) 0.23

< LD Sr-90 (8) 0.05 0.2

/8 0.03 - 0.5 casma (a)

E-40 1.3 13 sla 7 - 20 Ca-137 0.:.

1.2 7/s 0.

- 2.4 1

Co-40 0.1 0.2

/8 Others

< I.13 _

i-

SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1982 Annual Radiological Environmental Report (Page 3 of 4)

TABLE V. A.3 (Page 3 of 4)

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

3ema of Facility Thian hecer? Aramie Fever festieg Dotket io. fee esitenhia Name of Tacility seaver Valle, PoweQty113, Dogket No.

30-)J6 Loc ation of Tacility 8eaver. Penasvivan -_ 'sportia. avel CT 1974 - 1975 (County State)

FRE-OFERATIONAL F10 CRAN SC@lALT(CCMBa~s 1974 - 1975) t!adium or Fachway Im ' '.

Sampled Analysis and Total Number f

All laditator locations (tait of %asurement) of Analvois Performed

, Detee _ *; - S Meas. (f) Ranae Sediments Cross Alpha (0) pC1/8 (dry) 33/

Crose Beta (33) 1 18 33 3 - 30 8r-90 (0)

U-234.235, 238 (0)

Gamma (33) 13 33/33 2 - 30 E-40 1.5 13

/33 2 - 30 1/33 0.1 - 0.6 Ca-137 0.1 0.4 22Nb-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 113 Foodstuff Comma (8) 8 1-40 1

33

/8 10 - 33 1/8 Ca-137 0.1 0.2 1

rNb-95 0.05 0.2

/8 0I 1

nu-106 0.3 0.8

/8 Othera e 113 80 Feedstuff Cross seca (80) 0.05 19

/80 8 - 30 33/81 0.04 - 0.93 Sr-89 (81) 0.023 02 "l81 0.02 - 0.81 3r-90 (81) 0.005 0.4 Camas (81) 3 E-40 1

19

/81 5 - 46 Co-137 0.1 0.5

'/81 0.2 - 1.6 Co-144 0.3 1.5

/81 0.9 - 2.6 U/81 0.2 - 1.8 ZrNb-95 0.05 0.8

'/81 0.6 - 2.3 0I Eu-106 0.3 1.4 Others e 113 -

e

SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1982 Annual Radiological Environmantal Rzport (Page 4 of 4)

TABLE V.A.3 (Page 4 of 4)

" ENVIRONMENTAL PADICLOGICAL MONITORING PROGRMI

SUMMARY

Name of Facility Shippintport Atoale Power Station Docket No.

Not Applicable Name of.'acility Beaver Vallev Pever Station Dotkat No.

50-334 Location of Facility 3eaver, Pennsv1vania Reporting Level CT 1974 - 1975 (County, State)

FRZ-0FERATIONAL PROC 3UL4

SUMMARY

(COMBINED 1974 - 1975)

Mediam or Pativay Imme Limit sampled Analysis and Total Number of All Indicator locations (Unit of Measurement) of Amalvete Performed Detection LID Mean. (f) Ranee Milk I-13 1 (91) 0.23 0.6

'/91 0.3 - 0.8 Sr-89 (134) 5 7

'/134 6 - 11 132 St-90 (134) 1 5.3

/134 1.5 - 12.8 Gamune (134) 18 Ca-137 10 13

/134 11 - 16 Others ein SH/599 0.08 - 0.51 Extarnal Radiation y - Monthly (599) 0.5 mR

• 0.20 mR/ day 195 y - Quarterly (195) 0.5 at

• 0.20

/195 0.11 - 0.38 48 y - Annual (48) 0.3 mR

• 0.19

/48 0.11 - 0.30 13/17 1.0 - 3.2 Fish Cross Beta (17) 0.01 1.9 17 3r-90 (17) 0.C05 0.14

/17 0.02 - 0.50 Gaema (17)

E-4C 0.5 2.4

/17 1.0 - 3.7 other eIn LLD in units of MR - Lower and of useful integrated exposure detectability range for a passive radiation detector (TLD).

I*I Coe outlier not included in mean. CJater taken from dried-up spring with high sediment and potassium contant. Not considered typical groundwater sanple.)

OI May include Ru-106, Ra-103, Se-7. -

l tn Mo H

H O

2:

DUQUESNE LICJIT COMPANY TABLE V'.A.

4 8

i TYPICAL LLDs

• FOR C#iMA SPECTROMETRY Sediment i

Milk Water AirPagticulages Vegetation 5 Soil Fish 5

Nuclide (pCi/ liter)

(10' pC1/m )

(pCi/kg dry)

(pCi/g dry)

(pC1/g wet) ge-7 30 20 50 0.03 0.05 g

K-40 60 20 Cr-51 40 10 100 0.05 0.1 3

t3 Hn-54 3

0.5 30 0.02 0.03 gg Co-58 3

0.6 30 0.02 0.03 gQ Sy Fe-59 6

1 60 0.03 0.06 Co-60 3

0.6 30 0.02 0.03 e r*

n-65 8

1 70 0.04 0.07 oHHb Zr/Nb-95 5

2 50 0.03 0.05 g

g Ru-103 3

2 40 0.03 0.04 En s

i 5

Ru-106 30 5

30 0.02 0.03 r _r i

et 9 l

Ag-Il0M 5

3 30 0.02 0.03 0

1-131 4

2 30 0.02 0.03 l

Te-132 4

2 20 0.01 0.02 N

I-153 4

2 20 0.01 0.02 h

Cs-134 4

0.6 30 0.02 0.03 g

Cs-136 6

0.6 50 0.03 0.05 3

l 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 Cc-144 30 5

200 0.1 0.2 h

Ra-226 60 6

600 0.3 0.6 i

Th-228 10 1

60 0.03 0.06 4

At time of analysis (DLC Contractor Lab).

h Activity detectcJ in all samples.

NOTE lower Level of Detection is defined in Beaver Valley Power Station Technical Specifications.

SECTION V - B DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING B.

Air Monitoring 1.

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

2.

Air Sampling Program and Analytical Techniques a.

Program The air is sampled for gaseous radiciodine and radioactive particulates at each of ten (10) off-site air sampling stations. The locations ef these stations are listed in Table V.A.1 and shown on a map in Figure 5.B.l.

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 basis.

The charcoal is used in the 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-89/90 analysis.

In order to reduce interference from natural radon and thoron radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.

b.

Procedures Gross Beta analysis is performed by placing the filter paper from the weekly air sample in a 2"

x 1/4" planchet and counting it in a low background, gas flow proportional counter.

i.

L.

SECTION V - B DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report Gamma emitters are determined by stacking all the filter papers from each monitoring station collected during the month and scanning this composite on a lithium drifted getmanium (Ge(Li))

gamma spectrometer.

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.

l k

1

(.

SECTION V - B FIGURE 5.B.1 DUQUESNE LIGHT COMPMiY 1982 Annual Radiological Environmental Report FIGURE 5.B.1 ENVIRONMENTAL WO9GTORING LOCATIONS-AIR S/JPLUG NTIGS N

- mary AIR %'RI'6 STATirys f

h

~"

SILllL LTATl21 i

13 ltYER'S [ AIRY fW L.

27 BRLMON'S DAIRY FARM

/seser

'V ' ' ~

28 Se's DAIRY i

2ss su o ca =v w !Te r~ '

l 30 SHIPPINGPORTBORO I

, (.

2 muc h%

)

?^l\\,

~~

m

)

r-frousTRY gg I47 EAST LIVERPOOL, @ !O j.

r,'

4 WEIRTON, WEST VIRGIN!A 9

,,, - ~,,J' N,, _, /

51 Atlau! PPA O

e i

M' n.. l i

)

~

.s ', A 'r,,

..e.

1 l

i.%

46 e

us.n,G 1

l g

f

/,<

n

\\

w~w l

.5Y

)

l\\ 6-4

/

l 7,

~~ D,

.,.r' 4,

s d\\

,. /.r o

E ][ '! /

g o

I ;

'@n

• = -

/

E We ce /

l 3

z!'gd 4

/

l A c-5 9

)l

./

y 6

f,ava m

^ *w *

--k y

v s.

,4

\\

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SECTION V - B DUQUESSE LIGHT COMPANY 1982 Annual Radiological Environmental Report s

V.

ENVIRONMENTAL MONITORING

w.

b.

Procedures (continued) e Strontium-89 and Strentium-90 activities are determined in quarterly composited aira 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 )2 3

using fuming (90*4) nitric acid. An iron (ferric l' ss pp,erformed,- folicyed by hydroxide) scavenge addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth.

Yttrium is then precipitated as hydroxide, is diss)1ved and re-precipitated as oxalate. The yttrium ' oxalate is mounted on a nylon planchet and is contted in a. low

\\

level beta counter to infer strontiu'qqQO activity'.

s Strontium-89 activity is detArmined by y

precipitating Src 3 from the sample after yttrium separation. This precipitate is mounted'La a nylon 2

planchet and is covered with 80 mg/cm aluminum absorber for level beta counting.

3.

Results and Conclusions

• N N

A summary of data is presented in Table,V.A.2.

a.

Airborne Radioactive Particulates*'

A total of five hundred nineteen (519) weekly sam 4

ples from ten (10) locations was analyzed for gross peta.

One sample was:not obtained due to chart of air monitoring. equipment. Results were comparable to previous years.- Figure 5.B.2 illustrates the atarage concentration of gross beta in air particu-lates.

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SECTION V - B DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report t

V.

ENVIRONMENTAL MONITORING a.

Airborne Radioactive Particulates (continued)

The weekly air particulate samples were composited to one hundred and twenty (120) monthly samples which were analyzed by gamma spectrometry.

Naturally occurring Be-7 was present in every sample.

Occasional traces above detection levels of other nuclides were present.

Some were natural, others were residual from previous nuclear weapons tests. These are listed in the summary Table V.A.2.

Examination of effluent data from the Beaver Valley Power Station and the Shippingport Atomic Power Station demonstrated that none of the slightly elevated results are attributable to the operation of either power station.

A total of forty (40) quarterly samples were each analyzed for Sr-89, and Sr-90.

Based on the analytical results, the operation of Beaver Valley Power Station and Shippingport Atomic 4

Power Station did not contribute to any increase in air particulate radioactivity during CY 1982.

E b.

Radioiodine A total of five hundred and nineteen (519) weekly charcoal filter samples were analyzed for I-131.

One sample was not obtained due to theft of air monitoring equipment. No detectable concentrations were found at any locations.

Based on analytical results, the operation of Beaver Valley Power Station and Shippingport Atomic Power Station did not contribute to any increase in airborne radiciodine during CY.1982.

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SECTION V - C DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING C.

Monitoring of Sediments and Soils 1.

Characterization of Stream Sediments and Soils The stream sediments consist largely of sand and silt.

Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.

2.

Sampling Program and Analytical Techniques a.

Program River bottom sediments were collected quarterly above the Montgomery Dam in the vicinities of the Beaver Valley discharge and Shippingport discharge and above the New Cumberland Dam.

A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table V.A.1 and are shown in Figure 5.C.1.

Soil samples wera collected at each of ten (10) locations during CY 1982. At each location 12 cere samples (3"

diameter by 2" deep) are gathered at prescribed points on a 10 foot radius circle. Each location is permanently marked with reference pins.

Each set of samples is systematically selected by moving along the radius in such a manner as to assure representative undisturbed s amples.

Sampling locations are listed in Table V.A.1 and are shown in Figure 5.C.l.

Bottom sediments and soils are analyzed for gross alpha and beta activity, strontium, uranium, and the gamma-emmitting radionuclides.

b.

Analytical Procedures Gross beta - sediments and soils are analyzed for gross beta by mounting a 1 gram portion of dried sediment in a 2" planchet. The sample is counted in a low background, gas flow proportional counter.

Self absorption corrections 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 only alpha.

Gamma analysis of sediment or soil is performed in a 100 ml plastic bottle which is counted by a gamma spectrometer.

SECTION V - C FIGURE 5.C.1-DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report SEDIMENTS AND SOILS FIGURE 5.C.1 ENVWNMENTAL WONITORING LOCATIONS-SHOEUfE SEDIENTS & S0ll N

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SECTION V - C DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING b.

Analytical Procedures (continued)

Strontium 89 and 90 are determined by radiochemistry. A weighed sample of sediment or soil is leached with Nitric Acid HNO.

A stable 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 i

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 anion exchange chromatography plus mercury cathode electrolysis, then electroplated onto a planchet.

3.

Results and Conclusions a.

Results The results of sediment and soil analysis are summarized in Table V.A.2.

There were no significant differences between these current levels and those previously detected in both upstream and downstream sediment samples.

SECTION V - C DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 3.

Results and Conclusions (continued) a.

Results (continued)

Uranium isotopic analyses were performed by aloha spectroscopy.

The results suggest that only naturally occurring U-234 and U-238 were present since the activities were nearly always the same in each sample and the levels are within the expected range of natural uranium activities.

In equilibrium, U-234 and U-238 have the same

activity, b.

Conclusion Other than a very small amount of Co-60 at the outfall of Beaver Valley Power

Station, the sediment analyses do not indicate any increased radioactivity attributable to Beaver Valley Power Station.

Since Shippingport Atomic Power Station did not release any radioactive liquid waste during 1982, it did not contribute to any changes in river sediment radioactivity. Small amounts of Cs-137 from weapons testing fallout was found in all river sediment samples including those upstream above Montgomery Dam which are unaffected by plant effluents.

Results of soil analysis are comparable to preoperational data. _

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SECTION V - D DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING D.

Monitoring of Feedcrops and Fooderops 1.

Characterization of Vegetation and Foodcrops According to a survey made in 1981, there were approximately 650 farms in Beaver County. The principle source of revenue for the farms was in dairy products which amounted to nearly $4,659,000.00.

Revenues from other farm products were as follows:

Crops

$2,143,000.00 Horticulture

$ 551,000.00 Meat

$1,274,000.00 Poultry

$ 392,000.00 The percentage of crop land in Beaver County is approximately 17%, pasture land - 6.5%,

forest land -

47.8%, and other land uses - 28.7%.

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.l.

Each sample is analyzed by gamma spectrometry. The monthly samples are composited into a quarterly sample which is analyzed for Sr-90.

Foodcrops (vegetables) were collected at garden locations during the summer of 1982.

Cabbage and lettuce were obtained from Shippingport, Georgetown and Industry, PA, and from Weirton, WV.

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

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.,

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SECTION V - D DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 3.

Results and Conclusions A summary of results is provided in Table V.A.2.

The predominant isotope detected was naturally occurring K-40 in both food and feed.

Other activity is attributable to residuals from previous nuclear weapons tests or naturally occurring radionuclides. All results were consistent with (or lower than) those obtained in the pre-operational program.

These data confirm that Shippingport Atomic Power Station and Beaver Valley Power Station did not contribute to radioactivity in foods and feeds in the vicinity of the site.._

SECTION V - E DUQUESNE LIGHT COMPANY 1982 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 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 milk is analyzed for its radiciodine content calculated as Iodine-131. The analyses are performed within eight (8) days of sampling.

Detailed field surveys are performed during the grazing season to locate and enumerate milch animals within a five (5) mile radius of the site. Goat herd locations out to fifteen (15) miles are identified.

Survey data for the most recent survey conducted in July, 1982 is shown in Figure 5.E.1.

2.

Sampling Program and Analytical Techniques a.

Program Milk was collected from three (3) reference dairy farms within a 10-mile radius of the site and from one (1) control location outside of the 10-mile radius. Additional dairies, which represent the highest potential milk pathway for radioiodine based on milch animal surveys and meteorological data were selected and sampled. These dairies are subject to change when more recent data (including census) indicate other locations are more appropriate. The location of each is shown in Figure 5.E.2 and described below.

Number of Milch Distance and Direction Collection Site Dairy Animals From Site Period 25 Searight 41 Cows 2.1 miles-south /sw.

Jan. - Dec.

27 Brunton 105 Cows 7.3 miles-southeast Jan. - Dec.

29A Nichol 55 Cows 8.0 miles-northeast Jan. - Dec.

96 Windsheimer 50 Cows 10.3 miles-south /sw.

Jan. - Dec.

61 Allison 33 Cows 3.2 miles-west /sw.

Jan.-June,Dec.

62 Lyon 20 Cows 3.3 miles-west /sw.

Jan. - Mar.

66 Straight 1 Cow

• 3.1 miles-south /se.

Jan. - Feb.

69 Collins 9 Goats, 1 Cow

• 3.6 miles-southeast Feb. - Dec. _

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SECTION V - E DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report Number of Milch Distance and Direction Collection Site Dairy Animals From Site Period 97 Douglass 2 Goats

• 1.9 miles-southwest April - Aug.

98 Foxall (Hammond) 2 Goats

• 2.9 miles-east July - Nov.

99 Lampich 7 Goats 4.1 miles-east /se.

Aug. - Dec.

• Milk Usage - Home Only.

SECfICN V-E FIGURE 5.E.1 CUOUFSiE LIGff CCHPANY 1982 Annual Radiological Environmental Peport FIGURE 5.E.1 Cow & Goat Survey - Sumer,1982 N

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SECTION V - E DUQUESNE LIGHT COMPANY 1982 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 Radiciodine (I-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a beta-gamma coincidence counting system.

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 total of one hundred and fifty-two (152) samples were analyzed for I-131 during 1982. All I-131 activities in milk were below the minimum detectable level (0.3 pCi/1).

A total of one hundred and nineteen (119) samples were analyzed by gamma spectrometry and for strontium.

Both the Cs-137 and Sr-90 levels were within the normally expected range. The higher levels from China's nuclear tests which were experienced in other years were absent this year. Such tests were not performed during 1982.

Based on analytical results, the operation of Beaver Valley Power Station and Shippingport Atomic Power Station die not contribute to any increase in airborne radioiodine in CY 1982.

SECTION V - F DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING F.

Environmental Radiation Monitoring 1.

Description of Regional Background Radiation Levels and Sources The terrain in. the vicinity of the Shippingport and Beaver Valley Power Station generally consists of rough hills with altitude variations of 300 to 400 feet.

Most of the land is wooded.

The principal geologic features of the region are nearly flat-lying 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 to 12 pR/hr.

Results for 1982 indicated that background radiation continued in this range.

2.

Locations & Analvtical Procedures Ambient external radiation levels at the site were measured using thermoluminescent dosimeters (TLDs).

There were three (3) types used in the Duquesne Light Company Radiological Environmental Monitoring Program.

They are calcium sulphate dysprosium, CaSo4 (Dy) in teflon matrix, lithium fluoride (LiF), and thulium activated calcium sulfate (CaSo4:Tm).

The lithium fluoride TLDs were posted and analyzed by a laboratory of the Department of Energy (DOE) as an independent check of environmental radioactivity levels.

The CaSO :Tm TLDs were used'as a back-up and as a QC 4

program.

In 1982 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.

Comparisons of TLD results are presented in Table III.l. J

SECTION V - F FIGURE 5.F.1 DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report A NORTHWEST QUACRANT

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SECTION V - F DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 2.

Locations & Analytical Procedures (continued)

The lithium fluoride (LiF) TLDs used for environmental purposes are pre-selected and annealed at least 5 working days prior to use.

The radiation dose accumulated from the anneal date to the date of posting is accounted for utilizing background readings from five (5) TLD chips which are processed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the posting date.

The calibration of the TLD reader is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of processing the posted environmental TLDs.

The environmental TLDs are processed after retrieval and a background correction is made to account for the background radiation accumulated from the date of retrieval to the date of processing.

The calcium sulfate (CaSO4 :Dy) TLDs were annealed shortly before placing the TLDs in their field locations.

The radiation dose accumulated in-transit between the field location and the laboratory was corrected by annealing control dosimeters shortly before the field dosimeters were removed from the field location, then shipping the freshly annealed control dosimeters with the exposed field dosimeters to the laboratory for readout at the same time. All dosimeters 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.

3.

Results and Conclusions (CaSO :Dy in Data obtained with the contractor TLD 4

teflon) during 1982 are summarized in Table V.A.2, and the quality control TLD results are listed in Table III.l.

The annual exposure rate of all off-site TLD's averaged 0.18 mR/ day in 1982. As in previous years, there was some variation among locations and seasons as would be expected.

f In 1982, ionizing radiation dose determinations averaged approximately 66 mR for the year. This is comparable to previous years. There was no evidence of anomalies that could be attributed to the operation of either Beaver Valley Power Station or Shippingport Atomic Power Station. Three sets of TLDs of different types, each provided and analyzed by a separate laboratory, demonstrate good agreement and confirm that changes from natural radiation levels, if any, are neglible. _

SECTION V - F DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report Lessons learned from the Three Mile Island incident indicated the need for more radiation monitors in all sectors surrounding the plant.

Engineering and procurement are in progress for 16 Reuter-Stokes Pressurized Ion Chamber environmental radiation mcnitors to be used to circle the plant site, one in each of the 16 sectors.

Installation of the remote monitors for system operation which was begun in 1981 was completed in 1982 and the monitors were placed in service.

Installation of the central processing controller into the Emergency Response Facility is expected to be completed in 1983 which will permit the monitors to be read out at a central location. Engineering is also in progress to upgrade and modify the BVPS meteorological system to meet requirements in U.S. NRC Regulatory Guide 1.23, Rev. 1, and U.S.

NUREG-0654, Appendix 2.

The Reuter Stokes radiation monitors and the upgraded meteorological system will be tied into a new computer network to help meet some of the requirements set forth in U.S.

NRC NUREG-0654 (Criteria for Preparational Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants) and U.S. NRC NUREG-0737 (TMI Action Plan Requirements). The complete meteorological system modifications and new computer network are currently scheduled to be operational by December 1983. _

SECTION V - G DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING G.

Monitoring of Fish 1.

Description Fish collected near the site are generally scrap fish.

During 1982, fish collected for the radiological monitoring program included carp, catfish, and crapple bass.

2.

Sampling Program and Analvtical Techniques a.

Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley and Shippingport effluent discharge points and upstream of the Montgomery Dam.

The edible portion of each different species caught is analyzed by gamma spectrometry.

Fish sampling locations are shown in Figure 5.G.I.

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.

Three (3) fish were caught in April and May.

Two (2) more samples were caught in October. Except for naturally occurring K-40, the only gamma emitter which was detected in any samples was a trace of Cs-137 in one sample.

Cesium-137 is a long lived fission product and some residual activity persists from previous weapons testing programs.

This indicates that the operation of the Shippingport Atomic Power Station and the Beaver Valley Power Station has not resulted in radioactivity in fish in the Ohio River.

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SECTION V - H DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING H.

Monitoring of Surface, Drinking, and Well Waters 1.

Description of Water Sources The Ohio River is the main body of watbr in the area.

It is used by both the Beaver Valley and Shippingport plants for water make-up and receiving plant liquid effluents.

In addition, river water is used for cooling purposes at the Shippingport Atomic Power Station and make-up for the cooling tower at the Beaver Valley Power Station.

Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley and Shippingport plant sites.

It is used by several municipalities and industries downstream of the site.

The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water Authority.

The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river.

The next downstream users are East Liverpool, Ohio, and Chester, West Virginia, which are approximately 6 and 7 miles downstream, respectively. 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.

2.

Sampling and Analytical Techniques a.

Surface (Raw River) Water The sampling program of river water includes six (6) 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 following locations: Upstream of Montgomery Dam [ River Mile 31.8];

at discharge from Shippingport Atomic Power Station [ 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

-102-(

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SECTION V - H DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report 29.6]; and at Crucible Steel's river water intake (River Mile 36.2].

The automatic sampler takes a 20 ml to 40 mi sample every 15 minutes and is collected on a weekly basis.

The weekly grab samples 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 tritium (H-3), strontium 89 (Sr-89), strontium 90 (Sr-90), and cobalt 60 (Co-60) (high sensitivity).

Locations of each sample point are shown in Figure 5.H.1.

l 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 20-50 milliliters every 20 minutes. These intermittent samples are then composited into a weekly sample.

The weekly sample from each location is analyzed by gamma spectrometry. The weekly samples are also analyzed for radioiodine (I-131).

Monthly composites of the weekly samples are analyzed for gross alpha, gross beta, and by gamma spectrometry.

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.

-103-

SECTION V - H DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report 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 SMppingport, PA One (1) well at Meyer's Farm (Hookstown, PA)

One (1) well in Hookstown, PA One (1) tiell in Georgetown, PA Each groundwater sample is analyzed for gross alpha, gross

beta, tritium, and by gamma spectrometry.

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-104-

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ENVIRONMENTAL MONITORING

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2.

Sampling and Analytical Techniques ( ontinued) "

N '.

S d.

Procedure Gross alpha and gross beta activities'~are determined first by evaporating one liter of the sample' on a hotplate. The residue is mounted and.

dried on a 2-inch stainless steel planch e't..

The sample is counted-in a low background, gas flow proportional counter.

Self-absorption co: rections are made on the basis of sample weight.

i Gamma analysis is performed on' water samp'-s by loading one liter of sample

.into, a one liter marinelli centainer and counting on a Ge(Li) gamma spectrometry system.

j 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 p01/1 by evaporating ~ 2 liters.of sample on a hotplate and transferring the residue to a 2-inch planchet. The planchet is counted on a Ge(Li) spectrometry system.

Tritium is determined in water samples by converting 2 ml of the sample to hydrogen.and counting the activity in a 1 liter low level gas counter which is operated in the proportion..1 range in anti-coincidence mode.

3.

Results and Conclusions A summary of results of all analyses of water n,arples (surface, drinking, and ground) are provided by sample j

type and analysis in Table V.A.2.

These are discussed s

below, h

a.

Surface Water

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t.

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A total of - seventy-two (72) samp;lys were each analyzed for gross alpha, gross, be,t a, and gamare activity.

Twenty-four (24) quartsrly composited samples were analyzed for tritium ^ (H-3) andU radiostrontium (Sr-89 and Sr-90) as well as a high' sensitivity analysis for Co-60.

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SECTION V - H DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING

\\c' 3.

Results and Conclusions (continued)

No Sr-90, Sr-89, or Co-60 were detected in surface water duEjng CY 1982.

All alpha and beta activities were within normal range.

The only s

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The tritium lesels in Beaver Valley Power Station outfall were elevated above preoperational levels during the third and fourth quarters, but none of t --

these data suggests detectable increases over preoperational levels downstream of the station.

The tritium activity at the Beaver Valley Power

\\

Station outfall is consistent with station data of s

authorized radioactive discharges from Beaver s,

Valley Power Station and were well within limits N

permitted by NRC license.

No detectable increase in radioactivity in the Ohio River can be attributed to Shippingport Atomic Power Station since it did not discharge radioactive liquids during 1982.

7 b.

Drinking Water 7;;-.

A total of JLwenty-four (24) samples were analyzed for gross alpha and gross beta.

All results were within preoperational data ranges.

A total of eight (8) samples were analyzed for tritium (H-3)' radiostrentium (Sr-89 and Sr-90),

and cobalt (Cc-60).

No Sr-89, Sr-90, or Co-60 were detected.

The tritium data were within the preoperational range indicative of normal I

environmental levels.

E il A total of another one-handred and four (104)

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SECTION V - H DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 3.

Results and Conclusions (continued)

A total of one hundred and four (104) samples were analysed for radiciodine (I-131) using a highly i

sensitive technique.

A detectable level of I-131 was measured in one (1) weekly sample collected on May 11, 1982, at Midland.

The result of 0.25 pCi/ liter for this sample is only slightly above the minimum detectable activity of 0.2 pCi/ liter.

This positive result could not be attributed to station discharges.

The result may be attributed to expected variability in the analyses results of very low levels of activity.

In addition, surface water analysis for the same period did not indicate the presence of I-131.

c.

Well Water A total of sixteen (16) samples were each analyzed for gross alpha, gross beta, tritium and by gamma spectrometry.

No alpha activity was detected in any of the samples. The gross beta and tritium data are within preoperational ranges.

d.

Summary The data from water analyses demonstrate that neither Beaver Valley Power Station nor Shippingport Atomic Power Station contributed a significant increase of radioactivity in local river, drinking or well waters. The few positive results which could be attributable to authorized releases from 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 maximum detected activity attributable to Beaver Valley Power Station was only a small fraction ( 1. 26*.)

of the concentration (averaged over a year) permitted by the Federal Regulations for water consumed by the public. The Ohio River further reduced this concentration prior to its potential use by members of the public.

-108-

SECTION V - I DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING I.

Estimates of Radiation Dose to Man 1.

Pathways to Man - Beaver Valley Power Station a.

Calculational Models - Beaver Valley Power Station 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 Beaver Valley Pcwer Station Environmental Technical Specifications 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 B of the BVPS license, were used as the radionuclide activity input.

Each radionuclide contained in the semi-annual effluent report format of Regulatory Guide 1.21 was considered.

Certain radionuclides which were not detected in the effluents were not included in dose calculations when the inventory of such nuclides available for discharge was judged to be negligible.

As a result, only noble gases, radiciodines, strontium, and tritium were included as source terms based on the lower detectable limits of analysis (all sensitivities for analysis at Beaver Valley were equal to or better than required by the Beaver Valley license).

All gaseous effluent 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 as used in the Beaver

)

Valley Power Station Environmental Statements or in l

Regulatory Guide 1.109.

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

-109-

SECTION V - I DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING a.

Calculational Models - Beaver Valley Power Station (continued)

All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using a GeLi detector. 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. The maximum o dividual for liquid pathways is located at Mid 1...d.

Sxcept 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 - Beaver Valley Power Station Liquid Releases 9.

Liquid Pathway - Maximum Individual The doses which are calculated, based on the model presented above in V.I.1, are summarized and compared to Beaver Valley Power Station license limits below. An additional breakdown of these doses by pathway and organ is provided in Table V.I.1.

For these calculations, a hypothetical maximum individual (s) was located at Midland since this is the nearest location which significant l

exposure of a

member of the public could potenzially occur.

I t

-110-

TABLE V.I.1 y

1982 Radiation Dose to lbximum Individuala, mrem /yr.

Q Beaver Valley Power Station - Liquid Releases 5z CRITICAL USAGE W110LE PATilWAY GROUP FACTOR SKIN ORGAN TilYROID BONE BODY g

b Adult 21.0 kg N/A 0.0409 0.00451 0.0239 0.0301 Fish Consumption (Liver)

C Drinking Water Infant 510 1 N/A 0.0235 0.0684 0.00252 0.0212 (Liver)

G IS Shoreline Activities Teen 67 hr.

0.0027 0.0023 5

5" TOTAL MREM 0.0027 0.0542 0.0684 0.0312 0.0433 CRITICAL (Teen)

(Adult)

(Infant)

(Child) (Adult)

EE l

INDIVIDUAL (Liver) 0:f$

1

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O Z I

DOSE TO INDIVIDUALS DURING 1982 FROM NATURAL RADIATION EXPOSURE ilM 2C Ambient Camma Radiation:

69d E' "

Radionuclides in Body :

18e 4g l

o@

l Clobal Fallout 4*

@g a

TOTAL mrem 91 g

a Located at Midland Drinking Water Intake O

b Child - Usage Factor 6.9 kg/yr.

?

C Adult - Usage Factor 730 1/yr.

d Pre-operational average ambient gamma radiation H

e National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of h!

Ionizing Radiation:, BEIR Report, 1972.

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SECTION V - I DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 2.

Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued) l Actual Doses (mrem /yr.)

Calculated Using Site l

Effluents Appendix I

• Analysis Dose - Calculated Using l

NRC Model Effluents Regulatory Limit Doses - NRC Staff Guidelines RM50-2 Appendix I Calculated Report (Con-RM50-2 (Re.

Ratio of (1.21 Re-servative Limit w/o Calculated ported Re-Non-accident Cost / Benefit Dose vs.

leases Doses)

Analysis)

Reg. Limit TOTAL BODY Adult 0.0433 2.78 5.0 0.00866 Teen 0.0243 0.712 5.0 0.00486 Child 0.0208 Not Reported 5.0 0.00416 Infant 0.0212 Not Reported 5.0 0.00424 ANY ORGAN Adult 0.0542 Not Reported 5.0 0.01084 (Liver)

Teen 0.0486 Not Reported 5.0 0.00972 (Liver)

Child 0.0505 Not Reported 5.0 0.0101 (Liver)

Infant 0.0684 Not Reported 5.0 0.01368 (Thyroid)

Maximum Total Body Dose - Capsule Surnary mrem 1982 Calculated 0.0433 Appendix I Estimated 2.78 Final Environmental Statement 0.112 Thyroid Dose - (Largest Expected Organ Dose) 1982 Calculated 0.0684 Final Environmental Statement 0.96

• 10 CFR 50 Appendix I

-112-

SECTION V - I DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 2.

Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued) b.

Population Doses The 1982 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 159.0 H-3 148 mrem Co-60 5.14 mrem Cs-134 2.69 mrem THYROID 281.0 H-3 148 mrem I-131 130 mrem 3.

Airborne Pathway - (Beaver Valley Power Station)

The doses to the public for Beaver Valley Power Station airborne radioactive effluents during 1982 are provided in Table V.I.2.

They include the contribution of all pathways.

Tritium is the primary radionuclide contribution to these doses.

The data demonstrate compliance with 10CFR50, Appendix I design objective 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 to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit No.

1, is less than 0.000l* of the annual background.

The calculated doses to the public from the operation of Beaver Valley Power Station Unit NO.

1 are below 10CFR50, Appendix I design objectives, and resulted in only a small incremer..a1 dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public.

(

[

-113-

El TABLE V.I.2 P

2 Results of Calculated Radiation Dose to Man (1982)

Beaver Valley Power Station - Airborne Radioactivity M

l 5

l 03 1

APPENDIX I*

50-MILE N

l MAXIMUM EXPOSURE DESIGN OBJECTIVE PERCENT OF POPULATION DOSE g

ORGAN INDIVIDUAL, mrem mrem APPENDIX I man rem ts W @*

TOTAL BODY 0.0625 5

1.25%

0.135 ao$

i

-z 4

SKIN 0.160 15 1,07%

0.472 2M Z

EC i

DO LUNG 0.0654 O.149

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E8 TilYROID 1.760 0.430 pi@

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SECTION V I

DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRON'! ENTAL MONITORING 5.

Dose Pathways to Man - Shippingport Atomic Power Station i

l The radiation doses to man as a result of operations at the Shippingport Atomic Power Station during 1982 were calculated for gaseous effluent pathways. There were no radioactive liquid discharges from the Shippingport Atomic Power Station during 1982.

Effluent monitoring at the Shippingport Station during 1982 has shown that the radioactivity releases were substantially below the Federal radioactivity concentration guides.

The environmental monitoring l

program has demonstrated that the radiation exposure to the general public from the Shippingport Station operations was too low to measure and could only be estimated with the calculational models described below using measured or estimated effluent radioactivity data.

a.

Calculational Models - Shippingport Atomic Power Station The radiation doses to man from Shippingport Atomic Power Station operations were estimated using calculational models recommended by the International Commission on Radiological Protection (ICRP Publ.

2, 1959) and employ the general guidelines of the Nuclear Regulatory Commission (Regulatory Guide 1.109) established to maintain compliance with 10CFR50 Appendix I.

The air dose pathways considered were inhalation, immersion in gaseous and suspended particulate activity, and the inges+ ion of food and milk produced in the Shippingport vicinity.

It was conservatively assumed that food eroducts consumed by the public were produced in the Shippingport I

l area throughout CY 1982. The maximum potentially l

exposed individual for the air pathways was located at the site boundary.

It was conservatively assumed that the maximum individual resides continually at the site boundary.

l

[

(

-115-

l SECTION V - I DUQUESNE LIGHT COMPANY 1982 Annual Radiological Environmental Report V.

ENVIRONMENTAL MONITORING 5.

Dose Pathways to Man - Shippingport Atomic Power Station (continued)

Modeling parameters and usage factors used in the pathway calculations were consistent with values recommended by the Nuclear Regulatory Commission (NRC Regulatory Guide 1.109).

The population distribution within 50 miles of the site was based on census data as provided in the LWBR Program Environmental Impact Statement (ERDA 1541).

Furthermore, the air pathway calculation employed site-specific meteorological and wind direction data.

6.

Results and Conclusions Shippingport Atomic Power Station Evaluation of the radiation dose-to-man calculations for the airborne effluents show that the maximum annual radiation exposure potentially received by an individual residing at the site boundary is less than 0.1 mrem.

The maximum dose to an individual is well below the 10CFR50 Appendix I dose limits.

Furthermore, the radiation exposure to the entire population of 4 million persons within 50 miles of the Shippingport Station was less than 1 person-rem.

This dose is negligible compared to the typical general use of approximately 360,000 person-rem received by all individuals from typi-cal background radiation.

In conclusion, the radiation exposure received from the Shippingport Station during CY 1982 by any member of the general public is a very small fraction of the background radiation and has, therefore, no significant effect on the general public.

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West Mifflin, PA 15122-0109 Admiral K. R. McKee Deputy Assistant Secretary for Naval Reactors United States Department of Energy Washington, DC 20585 Mr. D. E. Patterson, Director Division of Operational and Environmental Safety United States Department of Energy Washington, DC 20013 United States Department of Energy Headquarters Library Washington, DC 20013 >

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Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 T. D. Jones Manager, Nuclear Operations Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 S. L. Fernick Manager of Environmental Affairs Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 C. E. Ewing Manager Quality Assurance Duquesne Light Company Beaver Valley Pcwer Station P.O. Box 186 Shippingport, PA 15077 r

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