ML20084L124

1983 Annual Environ Rept,Radiological Vol 2

ML20084L124
Person / Time
Site:	Beaver Valley
Issue date:	12/31/1983
From:	Carey J DUQUESNE LIGHT CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8405140346
Download: ML20084L124 (115)

Text

{{#Wiki_filter:.- - ~. 7 4 1983 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL - VOLUME #2 i: DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION AND SHIPPINGPORT ATOMIC POWER STATION i, e 8405140346 831231 f PDR ADOCK 05000334 h 7 R PDR t/ ~

1 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report ABSTRACT This report describes the Radiological Environmental Monitoring Program conducted during 1983 in the vicinity of the Beaver Valley Power Ststion and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-sita, 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 1983. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1983. 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. -i-

r DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report TABLE OF CONTENTS Page Abstract------------------------------------------------------------ 1 ^ I. INTRODUCTION----------------------------------------------- 1 A. Scope and Objectives of the Program 2 B. Description of the Shippingport and Beaver Valley Site 2 'II. RESULTS & CONCLUSIONS-------------------------------------- 7 III. ENVIRONMENTAL MONITORING CONSIDERATIONS-------------------- 9 A. Environmental Quality Control Programs 9 B. Evaluation of the Quality Control'(QC) Program Data 26 C. Standard Requirements and Limitations for Radiological and Other Effluents 26 D. Reporting Levels 27 IV. MONITORING EFFLUENTS--------------------------------------- 28 A. Monitoring of Liquid Effluents 28 1. Effluent Treatment, Sampling, and Analytical Procedures 34 2. Results 35 B. Monitoring of Airborne Effluents 36 1. Description of Airborne Effluent Sources 36 2. Airborne Effluent Treatment and Sampling 41 3. Analytical Procedures for Sampling Airborne Effluents 45 4 Results 48 C. Solid 'w'aste Disposal 50

.. = .~ DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report TABLE OF CONTENTS (Continued) V. ENVIRONMENTAL MONITORING PROGRAM Page A. Environmental Radioactivity Monitoring Program 52 1. Program Description 52 2. Summary of Results 68 3. Quality Control Program 68 B. ' Air Monitoring 74 1. Characterization of Air and Meteorology 74 2. Air Sampling Program and Analytical Techniques 74 3. Results and Conclusions 77 C. Monitoring of Sediments 80 1. Characterization of Stream Sediments 80 2. Sampling Program and Analytical Techniques 80 3. Results and Conclusions 82 D. Monitoring of Feederops and Foodcrops 84 1. Characterization of Vegetation and Fooderops 84 2. Sampling Program and Analytical Techniques 84 3. Results and Conclusions 86 E. Monitoring of Local Cow's Milk 87 1. Descriptica - Milch Animal Locations 87 2. Sampling Program and Analytical Techniques 87 2 3. Results and Conclusions 91 + r' f -lii-

DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report TABLE OF CONTENTS (continued) V. ENVIRONMENTAL MONITORING PROGRAM (continued) Page F. Environmental Radiation Monitoring 92 1. Description of Regional Background Radiation Levels and Sources 92 2. Locations & Analytical Procedures 92 3. Results and Conclusions 97 G. Monitoring of Fish 99 1. Description 99 2. Sampling Program and Analytical Techniques 99-3. Results and Conclusions 99 H. Monitoring of Surface, Drinking, and Well Waters 101 1. Description of Water Sources 101 2. Sampling Program and Analytical Techniques 101 3. Results and Conclusions 105 I. Estimates of Radiation Dose to Man 108 1. Pathways to Man - Beaver Valley Power Station 108 a. Calculational Models - Beaver Valley Power Station 108 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases 109 3. Airborne Pathway 112 4 Conclusions - Beaver Valley Power Station 112 5. Dose Pathways to Man - Shippingport Atomic Power Station 114 6. Results and Conclusions - Shippingport Atomic Power Station 115 -iv-

DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report LIST OF FIGURES Figure No. P_ age 1.0 View of the Shippingport and Beaver Valley Site 4 1.1 Geographical Map - 40 Mile Radius 5 4.1 Liquid Discharge Points to Ohio River 29 4.2 Water Flow Schematic - Shippingport Atomic Power Station 30 4.3 Water Flow Schematic - Beaver Valley Power Station 31 4.4 Liquid Radwaste Systems - Shippingport Atomic Power Station 32 4.5 Liquid Radwaste Systems - Beaver Valley Power Station 33 4.6 Gaseous Waste Processing - Shippingport Atomic Power Station 38 4.7 Gaseous Vaste Processing - Beaver Valley Power Statica 40 4.8 Gaseous Release Points - Shippingport Atomic Power Station and Beaver Valley Power Station 42-4.9 _ Solid Waste Disposal Diagram 51 5.B.1 Environmental Monitoring Locations - Air Sampling Stations 76 5.B.2 Concentrations of Gross Beta in Air Particulates 78 5.C.1 Environmental Monitoring Locations - Sediments 81 5.D.1 Environmental Monitoring Locations - Feedcrop and Foodcrop 85 5.E.1 Dairy Farm Locations (August - September 1983 Survey) 89 5.E.2 Environmental Monitoring Locations - Milk 90 5.F.1-Environmental Monitoring Locations - Radiation Monitoring 93 5.F.2 Environmental Monitoring Locations - Radiation Monitoring 94 5.F.3 Environmental Monitoring Locations - Radiation Monitoring 95 5.F.4 Environmental Monitoring Locations - Radiation Monitoring 96 5.G.1 Environmental Monitoring Locations - Fish 100 5.H.1 Surface Water and Wells - Locations 104 -v-

DUQUESNE LIGHT COMPAW 1983 Annual Radiological Enviro'nmental Report LIST OF TABLES Table Number h III.1 Quality Control Data - TLD Comparisons 11 III.2 Quality Control Data - Water Split Samples 12 III.3 Quality Control Data - Split Sampics - Miscellaneous 14 III.4 Quality Control Data - Spiked Samples 18 III.5 Quality Control Data - Spiked Samples 19 III.6 Quality Control Data - Air Particulates and I-131 20 III.7 Quality Control Data - Milk and Water 24 IV.A.1 Effluent Treatment, Sampling and Analytical Procedures Shippingport Atomic Power Station 34 IV.A.2 Effluent Treatment, Sampling and Analytical Procedures Beaver Valley Power Station 34 IV.A.3 .Results - Liquid Effluents - Shippingport Atomic Power Station 35 IV.A.4 Results - Liquid Effluents - Beaver Valley Power Station 35 V.A.1 Environmental Monitoring Program Summary 53 V.A.2 Environmental Monitoring Program Results (1983) 58 V.A.3 Pre-Operational Monitoring Program Results (1974-1975) 69 V.A.4 Typical LLDs for Gamma Spectrometry - DLC Contractor 73 V.I.1 Radiation Dose to Man - Beaver Valley Power Station - Liquid Releases 110 V.I.2 Radiation Dose to Man - Beaver Valley Power Station - Airborne Releases 113 -vi-

SECTION I DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report I. INTRODUCTION The 1983 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 1983. 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 Pcwer Coordination group. Beaver Valley No. 2 Unit was under construction in 1983 and is scheduled to start-up11n 1986. The Shippingport Atomic Power Station was permanently shutdown on October 1, 1982. During 1983 the Shippingport Atomic Power Station nuclear reactor core was disassembled for shipment off-site for disposal. The Shippingport Atomic Power Station was the first large-scale central station nuclear reactor in the United States. 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 addition to.providing technology which has served as a basis for the development of pressurized water reactors in the nuclear industry. The plant utilized a Light Water Breeder Reactor (LWBR) core from September 21, 1977 until final shutdown on October 1, 1982, pioneering light water breeder technology. The. highest average daily output generated at the Beaver Valley Power Station during the year was 817 megawatts not in

April, 1983.

The total gross electrical generation-during the year was 4,916,300 megawatt-hours. i

SECTION I DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report I. INTRODUCTION A. Scope and Objectives of the Program The environmental program consists of effluent and environmental monitoring for radioactivity. Liquid and gaseous effluents from the Beaver Valley Power Station and the Shippingport Atomic Power Station were collected, processed, s ampl ed, 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. B. Description of the Shippingport and Beaver Vallev 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 appt,ximately 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 alcng 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 735 feet above sea level. The two (2) stations are situated on the Ohio' River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from New Cumberl1nd 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. m. SECTION I DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report I. INTRODUCTION B. Descriotion of the Shiopingport and Beaver Valley Site (continued) Water temperature of the Ohio River varies from 32 F to 84 F, the minimum temperatures occur in January and/or February and maximum temperatures in July and August. Water quality in the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela, and Beaver j rivers. The climate of the area may be classified as humid continental. Annual precipitation is approximately 33 inches, typical yearly temperatures vary from approximately - 3'F to 95*F with an annual average temperature of 52.8'F. The predominant wind direction is typically from the southwest in summer and from the northwest in winter. t ( 4 - -- -.. _ ~ -.

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s SECTION I DUQUESNE LIGHT COMPANY 1983 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: Beaver Valley Shippingport(1) Thermal & Elec. Rating - 2660 SN 835 IN 236.6 ?N 72 IM g e t e MW-Each Reactor Type of Reactor PWR PWR( ) Number of Reactor 3 4 Coolant Loops 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. NOTE: MW megawatts thermal g MW - megawatts electrical e (1) The Shippingport Atomic Power Station was not operated during 1983. (2) Light Water Breeder Core 6-

SECTION II DUQUESNE LIGHT COMPANY 1983 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 1983. 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 1983, while the Shippingport Atomic Power Station was shutdown and defueled throughout 1983. 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 1983 was the same as in 1982 except for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications. (Refer to Table V.A.1 for the 1983 Radiological Monitoring Program Outline). The results of the 1983 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 was detected near the Beaver Valley Power Station discharge and resulted in negligible exposure to members of the public. A summary of the 1983 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 three (3) dairies which have the highest calculated milk pathway potential.and one large local dairy. The three dairies are determined from calculations based on the meteorological data and the latest milch animal survey. However, these dairies are frequently small, consisting of as few as one cow or goat. The availability of milk from single cow dairies and revisions due to updated calculations and surveys result in sampling of several additional dairies during the year in different sampling periods.

SECTION II DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report II. RESULTS AND CONCLUSIONS (continued) In addition, the Environmental Monitoring Program includes two larger dairies in order to provide continuity in the sampling / analyses program and a control location. Samples from each of these dairies are obtained 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 required dairies. 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. i r i l l l l -s-

~ SECTION III DUQUESNE LIGHT COMPANY 1983 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 (Duauesne Light Company (DLC) Contractor Laboratory - DLC QC Laboratory - 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 j 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 15?. of the arithmetic mean of the three laboratories. This is well within the precision of a typical 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. -..

SECTION III .DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report III. ENVIRONMENTAL !!3NITORING CONSIDERATIONS A. Environmental Quality Control Programs (continued) 2. Split Sample Program (DLC Contractor Laboratory - DLC QC I~5 oratory (continued) Because of the overall uniformity of ccmparable results, it is concluded that the two laboratories are consistent and in agreement, 1- + 6 4 9. i

Secti:n III DUQUESNE LIGHT COMPANY TABLE 111.1 1983 Annual Radiological Environmental Report TABLE III.1 QUALITY CONTROL RESULTS TLD MONITORING mR/ Day IST OUARTER 2ND OUARTER CLC DLC DLC QC Independent DLC DLC QC Independent CLC Location Contractor Lab Lab #3 PDER PIC Contractor Lab Lab #3 PDER PIC No. (CaSO.:Dy) (L1F) (CaSO :Tm) (2) 13), (CaSO.:Dy) (L1F)

1. CaSO.:Tm)

'(2)' (3) W 0) 0.17 0.19 0.19 0.27 0.21 10 0.18 0.22 0.21 0.26 0.21 13 0.1o 0.22 0.22 0.27 0.16 0.13 0.1. 0.29 14 0.17 0.22 0.20 0.19 13 0.14 0.16 0.13 0.22 0.13 0.13 0.lo 0.27 27 0.18 0.21' O 20 0.16 0.16 0.18 28 0.19 0.23 0.20 0.17 0.20 0.20 29 0.20 0.23 0.25 0.20 0.23 0.22 32 0.20 0.27 0.24 0.23 0.24 0.18 0.20 0.22 0.23 0.24 0) 45 0.13 0.2; u.25 0.29 0.26 0.19 0.21 0.20 0.29 0.250) W ao 0.h 0.20 0.20 0.25 0.19W 0.13 0.15 0.17 0.27 0.19 47 0.it . 44 0.23

0. 19 0.21 0.21 a4 0.20

).24 0.20 0.13 0.1$ 0.20 . 31 0.19 0.21 0.24 0.25 0.17 0.19 0.13 0.30 3RD OUARTER 4TH OUARTER DLC DLc Contractor *** DLC Otc contractor *** DLC OC Independent DLC CLC GC independent-CLC Location Contractor Lab Lao #3 PDER PIC Contractor Lao Lao #3 POER PIC No. (CaSO.:Dy) (LiF) (CaSO :Tm) (2) 1D, (CaSO.:Cv) (LiF) (CaSO :Tm) (2) M 10 0.13 0.16' O.16 0.25 0.26W' O.16 0.20 0.19 0.22 o, 3W 0.25 13 0.17 0.17 0.1o 0.25 0.16 0.17 0.17 14 0.13 0.13 0.18 0.16 0.20 0.21 15 0.14 0.12 0.13 0.21 o,g3 o,t; o,14 0.21 27 0.13 0 lo 0.17 0.16 0.13 0.13 28. 0.19 0.19 0.18 0.17 0.'21 0.20 29 0.21 0.22 0.20 0.18 0.23 0.21 32 0.20 0.13 0.19 0.23 0.16 0.21 0.20 0.19 43 ' O.19 0.13 0.17 0.26 0.25(1) 0.17 0.19 0.20 0.25 0.25(1) 46 0.15 0.15 0.17 0,22 0.19W 0.15 0.17 0.14 0.22 0.190) 47 0.21 0.19 0.20 0.20 0.20 0.21 48 0.13 0.16 0.17 0.20 0.19 0.20 31 0.21 0.19 0.18 0.26 0.19 0.20 0.19 0.27 (1) PIC Reading at Location 10 taken in DLC Substation in shippingport Soro. Location 45 taken at Kennedy's Corners. Location 46 taken at industry Tire Shop. (2) NRC results f rom Pennsylvania Departcent of Environmental Resources. (3) In this consolidated environeental program the pressurized ion chamber (PIC) continuous monitor 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 co ::iake both systems agree exactly because both systems were installed to monitor relative radiation levels rather than absolute levels. Each system provides a reasonably accurate measure of the abschte radiation levels. TLD missing from its posted location Stacian is out of service Jed and 4th quarter independent Laboratory equipment casen over by Contractor lab. Section III CUQUESNE LIGHT CC:4PArn TABLE III.2 1983 Annual Radiological Environmeatal Report (Page 1 of 2) TABLE !!!.2 OUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and OLC-0C Labs DLC i Contractor DLC - QC l Media Analysis Sarrolino Period Lab (1) Lao (1) Units Surface Water Gross Alpha January 2.6 : 1.3 2.9 2 2.5 pC1/1 April 5 0.71 g 1.0 pC1/1 1.1 S 1.2 pC1/1 July 5 October 5 1.4 {1.4 pC1/1 surface Water Gross am a January 11 2 2 9.0 2 2.2 pci/1 April 7.72 1.5 4.82 1.7 pC1/1 July 3.0 2 1.2 5.0

• 1.7 pCill October 6.62 1.4 5.9 2 2.5 pCi/1 Surfece Water Co-40 January 5 2.0 g 4.2 pC1/1 April 3 2.0 5 3.7 pC1/1 July s 3.0 s 3.9 pci/1 0ctober

1.0

3.7 pC1/1 P 1/1 Surface Water ca-134 January 5, 2.0 g 5.0 C

April g 3.0 g 4.4 pCi/1 f July 5 2.0 g 4.5 pC1/1 October s 1.J { 4.2 pC1/1 Surface Water Cs-137 January s 3.0 g 5.0 pC1/1 April g 3.0 g 4.7 pC1/1 July s 3.0 3 4.7 pct /1 pC1/1 October ,g 2.0 < 3.7 Surface Water Tritium ist Quarter 1030 2 100 900

• 320 pCi/1 Composite 3rd Quarter 2290 2 140 2610 2 280 pC1/1 Composite Surface Water Sr-49 2nd Quarter

$ 1.7 < 0.36 pC1/1 Composite 4th quarter < 1.2 3 3.0 pC1/1 Composite Surface Water Sr-90 2nd Quarter 5 0.29 5 0.36 pC1/1 Composite 4th Quarter Composite ""< 0.32 g 0.48 Surface Water Co-60 2nd Quarter 5 1.0 g 3.6 pCill (high Composite sensitivity analysis) 4th Q'uarter f 0.3 1 4.9 PC1/1 Compo site (1) Uncertainties are based on counting statistics and are specified at the 951 confidence level. I t f I

.... ~ DUQUESNELIGhTCOMPANY TABLE III.2 1983 Annual Radiological Environmental Report (Page 2 of 2) e 1 TABLE III.2 (Continued) OUALITY CONTROL RESULTS SPLIT SAMPLE ANALYS!$ RESULTS Comearison of Contractor and DLC-0C Labs DLC Contractor OLC - QC + Media Analysis Samolina Period Lab (1) Lab (1) Units Driabing Water Cs-137 February < 2.0 1 5.0 pC1/1 May g 3.0 1 5.0 pC1/1 August 5 2.0 1 5.4 pCi/1 November s 2.0 5 5.0 pC1/1 Drinbing Later Cs-134 February g 2.0 g 5.0 pC1/1 May s 3.0 s 5.0 pCi/1 August g 2.0 g 5.3 pC1/1 P ill November s 2.0 5 5.0 C i Drinking Water Co-60 February g 2.0 4.8 pC1/1 i hy g 3.0 g 4.0 pC1/1 August g 2.0 ., 4.6 pC1/1 Novemoer g 2.0 0 pCi/1 Driabing Water Gross Alpha March g 0.59 s 1.0 pC1/1 4 June 5 0.45 s 1.6 pCi/1 August 5 0.86 5 1.6 pCi/1 November g,0.46 g 1.9 pC1/1 Orinbing Water Cross Beta March 4.1 2 1.2 6.1 2 2.0 pC1/1 June 3.0 2 0.9 2.6 2 1.7 pC1/1 August 4.1 2 1.4 6.2 2 3.7 pC1/1 P ill C November 3.7 2 1.4 2.7 2 1.8 Drinking Water Tritium 2nd Quarter 270 2 80 1 200 pC1/1 4th Quarter < 70 f 170 P 1/1 C 1 l 1 i' l i 2 I (t) Uncertataties are based on counting statistics and are specifiad at the 95 confidence interval...

Sectica III CUCCESNE LIGHT CCMPANY TABLE III.3 1983 Annual Radiological Environrnental Report (Page 1 of 2) TABLE !!I.3 QUALITY CONTROL RESULTS SPLIT ! AMPLE ANALYSIS RESULTS Comoarison of Centractor and CLC-0C Labs DLC Contractor DLC - QC Media Analysis Sarnalino Paried Lab (1) Lab (1) Units Milk

-131 3-29-83

< 0.13 < 0.3 pCill (Location 23) 1-131 6-21-83 1 0.03 s 0.25 pCill K-40 6-21-83 1260 130 pC1/1 Cs-13; 6-21-83 g 3.0 $ 5.0 pC1/1 Cs-137 6-21-83 < 3.0 e 3.0 pC1/1 ~ Co-60 6-21-83 < 3.0 < 4.3 pct /l Fasd K-40 6-21-83 12.3 _* 1.2 pC1/gm Dry (Lecation 25) Co-60 6-21-83 g 0.01 g 0.0 48 pC1/gm Dry = Cs-134 6-21-83 < 0.0L .e 0.050 pC1/gm Dry C4-137 6-21-83 g 0.02 g 0.072 pC1/gm Dr/ rn-228 6-21-43 0.09 : 0.0) pC1/;m 2ry Feed Sr-90 6-21-43 0.% 3 =0.000 0.21 : 1.12 rCi/ m Pr7 (Location 25) Food I-131 9-1-d 3 g 0.005 PCi/gm Wet (Cabbage) K-40 9-1-83 1.38 20.19 PC1/gm Wet (Location 10) Co-60 9-1-83 1 0.004 1 0.12 pC1/gm 7ec Cs-134 9-1-83 c 0.003 g 0.12 pCi/gm Wat Cs-137 9-1-43 g 0.00 3 g 0.13 pC1/gm Wet Food 9-1-43 pCi/4m Wt (Swiss chard) I-131 9-1-43 0.163 : 0.064 pC1/gm Wet (Location 10) g-;o 9-1-43 $.69 0.57 pCUgmet Co-60 9-1-a 3 < 0.003 < 0.11 P i' ' Cs-134 9-1-93 [0.004 2 0.13 E i#3" "' Cs-137 9-1-43 0.02 1 0.007 0.12 (1) 1:ncertainties are based on counting statistics and are specified at the 952 confidence level. Analyses not performed nor required. Section III DUQUESNE LIGHT COMPANf TABLE III.3 1983 Annual Radioltgical Environmental R;p:rt (Page 2 of 2) TABLE III.3 (Continued) QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs DLC Contractor DLC - QC Media Analysis Samplino Period Lab (1) Lab (li_ Units Sediment Gross Alpha 10-25-83 '+ 14 e 7 12 2 6.5 pci/gm Dry (1.oc tion 3) Cross Beta 10-25-83 29 2 3 29 2 7.8 pCi/gm Dry U-235 10-25-83 0.015 2 0.004 0.23 2 0.06 pCi/gm Dry U-234 10-25-83 0.83 2 0.08 0.80 2 0.13 pC1/gm Dry U-238 10-25-83 0.62 2 0.06 0.53 2 0.10 pCi/gm Dry Sr-89 10-25-83 < 0.14 60.22 pCi/gm Dry Sr-90 10-25-83 0.041 2 0.025 g 0.11 pCi/gm Dry K-40 10-25-83 15.7 2 1.6 pCi/gm Dry Co-60 10-25-83 0.239 2 0.07 0.30 2 0.21 pCi/gm Dry Cs-134 10-25-83 f 0.03 < 0.16 pCi/gm Dry Cs-137 10-25-83 0.497 2 0.065 0.42 2 0.097 pCi/gm Dry Ra-226 10-25-83 2.78

• 1.01 pCi/gm Dry Th-228 10-25-83 1.56 2 0.16 pCi/gm Dry Milk Sr-89 12-11-83 1 1.0 f 0.92 pC1/1 (1.ocetion 25)

Sr-90 12-11-83 1.420.5 2.4 2 0.78 pCi/1 Co-60 12-11-83 $ 2.0 g 4.4 pCi/1

• Cs-134 12-11-83 i 3.0

< 5.0 pCi/1 Cs-137 12-11-83 g 2.0 f 5.0 pCi/1, K-40 12-11-83 1270 130 pCi/1 I-131 12-11-83 $_0.24 f 0.28 pCi/1 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence level. Analyses not performed nor required.

SECTION III DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report A. Environmental Quality Control Programs (continued) 3. DLC QC Laboratory 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 (radiciodine) samples were collected at Location #30 and compared during the year on a weekly basis. Comparison of particulato 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 first 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 1983 Annual Radiological Environmental Report A. Environmental Quality Control Programs (continued) 6. Special QC Program (DLC Contractor 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 i three ways and analyzed by the DLC-QC Laboratory and Independent Laboratory as well as the Contractor Laboratory. A summary of results 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. 1 i 4 -

4 ClfME"NE LIGHT CCMPAM TABLE !!I.4 Section III 1983. Annual R diclogical Envirofeental Repnet \\ ~ TABLE III.8-i~ .iALITY CONTROL RCIULT! 'c_ R i SA.cotf ANALYSIS RESULTS Sancia Type DLC ant Contractor DLC - QC Analysh Lab (1) Lab (1) Units Sasele Data ident. No. 1 4-1-d3 53-52 Water sr-89 6.6' t 1.6 5.8 r 1.3 pct /1 Sc 90 3 0.4 3 0.4 pC1/1 4-1-MJ $3-52 Water: I-131 13 22 12 2 6 pC1/1 Cr-51 25.5 2 5.2 27.0 t 6.0 pggf g C2-134 26 2 6.9 19 27 pCin Ce-144 83.2 t'41.3 66-t 46 g pCL/1 .7-29-83 J53-54 W.ter: Cross Alpha 8.6 2 1.4 12 t 1.7 pCi/1 Cro s Beta 25 12

• e 41 2 2.8 pC1/1

.9-1-83 33-55 Water: Sr-89 i LLD

• 11 2 2.4 pCi/1 Sr-90 6.320.9*

~15 t 1.6 pCi/1 Co-58 35.7 t 8.7 39 e 9 pet /t I Co-60 14.0 2 4s4 it-6e pet /1 10-20-93 53-56 tiatur: 1-131 _ 20 1 M: 2.3 pCL/1 ~ Co-58 119 2 12 99 9.6 pC1/1 .Co-60 57.1 2 5.9 58 2 8.8 pC1/1 Ce-144 232 29 170 2 64 pC1/1 s 16 3 2050 2 13D. 2000 2 280 pC1/1 1 24-84 53-57 Water: Gross Alpha 2.5 1 b.9** 23 2 3.7 pC1/1 l. Gross Beta 32 2 ; 40 2 2.9 pCI/[ , 15-64~ '53-A Water; S e-8 9, 7.9 r_ 1.7 11 ).3 pC1/1 $r-40 11 2 1 8.2 e 1.4 pCL/1 53-8 Water t, 9t-19 '2123 22 2 2.8 pCL/1 ~ Sr-9J 23 2 1 20 2 2.1 pC1/1 53-C - , hear Sr-89 3122f '30 2 3.3 pC1/1 -T sr-90 30 t'2' 30 2 2.4 pC1/1 s .a ~ N 4 a-' g_ ] ~ ' (1) Uncertainties are based on counting statistics and are specifiei at the 9M c:nf uente level. '. U.3 1.over limit of detector.

• Four of five spiked samples ~ are in good agreement.

s ~ ,8* While these sampids are not in pod agreer.est with the Qualit*/ Control Laboratory, the Contractor Laboratory did agree with nine EPA Interccmparison Laboratory _results ranging f rom 10 pC1/1 to 150 pC1/1. i 4 t - 18 ~ +, - .v.- ._,.p.m, ,~n _.ny -.,n ,mm m,, nen,.,n__.nn,,,,y_.,, ,e. m 7y,,

Sectiin III DUQUESNE LIGHT COMPANY TABLE 111.5 1983 Annual Radiological Environmental R: port TABLE III.5 QUALITY CCitTROL RESULTS SPIKE SAMPLE ANALYSIS Sample Type DLC and Contractor DLC - QC Sample Date Ident. No. Analysis Lab (1) Lab (1) Units 1-17-83 52-57 Milk: Sr-89 s 3.0 7.4 : 5.2 pC1/1 St-90 6.6 2 0.9 6.3 2 3.5 pC1/1 Mn-54 42.1 2 6.5 41 7 pC1/1 .Cs-134 18.2 2 7 11

• 6 pC1/1 Cs-137 29.1 : 6 31 2 9 pC1/1 1-131 4.5
• 0.3 6.8 2 1.2 pC1/1 6-4-43 52-58 ~

Milk: I-131 10 1 7.6 2 1.0 pC1/1 Fe-59 31 2 10.8 29 2 18 pC1/1 Cs-134 53 2 5.3 48 2 11 pCi/1 10-20-83 52-60 Milk: 1-131 8.3 2 1.5 12 : 1.4 pC1/1 Ma-54 40.5

• 4.4 39 11 pC1/1 Co-60 33.6 5.1 24 2 8.6 pC1/1 Cs-137 72 t,.7.2 59
• 9 pCi/1 L

i t j (1) Uncertainties are based on counting statistics and are specified at the 951 confidence level. i _

c. Section III DUQUESNE LIGHT COMPANY TABLE III.6 1983 Annual Radiological Environmental Report (Pag 2 1 of 4) TABLE III.6 CUALITY CONTROL RESULTS AIR PARTICULATES AND CHARCCAL FILTER: COMPARABLE SAMPLES Air Particulates Air fodine pCi/Cu. Meter (Beta) pCi/Cu. Meter DLC DLC Contractor DLC - QC Contractor DLC - OC Sample Date Lab (1) Lab (1) Sample Date Lab (1) Lab (1) 1-4-83 to 0.022 0.003 0.030 2 0.0032 1/10/83 to 5 0.01 50.027 1-10-e3 1-17-83 1-17-83 to 0.013 2 0.003 0.013 2 0.002 1-24-83 to 50.009 < 0.027 1-31-83 1 3 to 0.015 2 0.003 0.023 2 0.003 2-7-83 to g 0,01 < 0.017 2-14-83 2-14-83 to' O.022 0.004 0.037 2 0.003 2-22-83 to S 0.01

0.017 2-21-83 2-28-83 2-28-83 to 0.023 2 0.003 0.029 2 0.003 3-7-83 to

< 0.01 s 0.021 3-7-83 3-14-83 3-14-83 to 0.009 0.003 0.014 2 0.002 3-21-83 to C 0.01 5 0.013 3-21-83 3-23-83 3-28-83 to J.312 : J.JJ4 0.022 : 0.002 4-4-33 to 5 0.009 s 0.013 4-4-83 4-11-83 4-11-83 to 0.011 2 0.003 0.015 2 0.005 4-18-83 to S 0.009 s 0.012 4-18-83 4-23-83 4-25-83 to 0.017 0.003 0.023 2 0.002 5-2-83 to. e 0.01 e 0.010 ^ 5-2-83 5-9-83 5-16-83 ' 0.011 0.003 0.019 2 0.002 3-16-83 to < 0.005 e 0.019 5-9-83 to ~ ~ 5-23-83 5-23-83 to 0.010 t o 43 0.015 : 0.002 5-31-83 to < 0.01 < 0.014 5-31-83 6-6-83 ~ (1) Uncertainties are based en counting statistics and are specified at the 95:; confidence level.,

= Section III DUQUESNE LIGHT COMPANY TABLE III.6 1983 '. Annual Radislogical Environ antal Paport '(Page 2 of 4) TABLE III.6 (Continued) OUALITY CONTROL RESULTS AIR PARTICULATES AND CHARCCAL FILTER: COMPARABLE SAMPLES Air Particulates Air Iodine pC1/Cu. Meter (Beta) pC1/Cu. Meter DLC CLC Contractor DLC - QC Contractor DLC - QC Sarole Date Lab (1) Lab (1) Samole Date Lab (1) Lab (1) 6-6-83 to 0.023 2 0.004 0.030 2 0.002 6-13-83 to ~e 0.01 ~< 0.013 6-13-33 6-21-d3 l 6-21-d3 to =0.015': 0.004' O.025 : 0.003 6-27-43 to / 0.009 < 0.015 6-27-33 7-3-33 7-5-8 3 to 0.014 2 0.004 0.018 : 0.002 7-11-43 to < 0.009 i 0.013 7-11-83 7-id-d 3 '7-18-83 to 0.017 2 0.003 0.024 2 0.002 7-25-83 to 4'O.01 ~< 0.015 7-25-83 8-1-d3 ~ S-1-83 to 0.023 2 0.003 0.0322 0.003 8-4-d3 to g 0.01 6 0.022 3-3-83 3-15-43 d-15-43 to 0.033 : 0.004 0.042 2 0.003 d-22-43 to ' 0.01 J-22-d3 d-23-33 e~ 0.016 i-29-43 to 0.026 : 0.003 0.036 : 0.002 9-+-4 3 to 9-8-43 9-12-33 ~< 't.01 ~< 0,013 9-12-83 to 0.018 : 0.003 0.029 : 0.002 9-19-83 to ( 9-19-43 9-26-43 ~ 0.01 < 0.010 ~ 9-26-43 to 0.034 2 0.004 0.042 : 0.003 10-J-o3 to ~ 0.01 c 0.012 10-3-d3 10-10-83 ~ 10-10-43 to 0.019 2 0.003 0.022 0.002 10-17-d3 to 10-17-d3 10-23-83 -( 0.01 < 0.016 - ~ 10-24-43 to 0.013 2 0.003 0.019 : 0.002 10-31-d3 ta ( 0.J03 10-31-d3 11-7-d3 ~ ~< 0.020 11-7-33 to 0.023 : 0.003 0.027 : 0.002 11-la-33 to n 0.003 -- 0.020 11-14-d3 11-21-83 11-21-d3 to 0.027 : 0.004 0.037 : 0.003~ 12-3-d3 ~s 0.018 L1-29-d3 to 3 0.003 11-28, 12-5-83 to 0.027 : 0.003 0.024 0.002 12 13 -83 to -< 0.007 < 0.028 12-13-53 12-13-83 ~ 12-19-83 to 0.020 2 0.003 0.0 21 : 0.002 12-27 83 to < 0.009 ~ 12-27-83 1-3-84 4 0.011 f J t (1) ' L'ncertatacias are based an counting statistics and are specified at the 95's confidence interval. * .. = - -, _,

.~ 'Section III DUQUESNE LIGHT COMPANY TA?LE III.6 1983 Annual Radiological Environmental R1 port (Page 3 of 4) TABLE III.6 0UALITY CONTROL 3 AIR PARTICULATES (cCi/m ) DLC Contractor DLC - OC Sample Date !!!di.lMi Lao (1) Lab (1) January (1/3/83.to 1/31/83) Se-7 0.057 : 0.018 0.051 2 0.011 Others LLD LLa March (2/28/83 to 3/38/83). se-7 0.082 2 0.027 0.066 : 0.011 Othets LLD LLD May (5/2/83 to 5/31/83) Be-7 0.102 2 0.021 0.075 : 0.014 Others LLD LLD ' July (6/27/83 to 3/1/S3) Be-7 0,143 : 0,0;o o,;co o,co; K40 0.027 : 0.013 LLD Others LL3 LLp S$p t ember (8/29/83 to 9/26/83) Be-7 0.118 : -0.027 0.086 0.015 Others LLD LLD Novemzer (10/31/33 ta 11/23/33) 2e-7 0.094 : 0.22 0.063 2 0.008 0thers LLD LLD (1) - t'acertainties are based on councing statistics ar d are specified at the 95*, confidence interval. LLD. Lower limit of detector. L:

Section III' 000UESNE LIGHT CCMPANY TA3LE III.6 1983 Annual Radiological Environmental Report (Page 4 of 4) TABLE III.6 QUALITY CONTROL AIR PARTICULATE AND CHARCOAL FILTER 3)OMPARABLE SAMPLES C LOCATION 30 - foC1/m OLC Contractor DLC - QC Sasele Date Nuclide Lab (1) Lab (1) ist Quarter Composite Sr-89 5 0.0009 3 0.00029 12/27/83 to 3/23/83 ~ Sr-90 g 0.0003 1 0.00014 3rd Quarter Composite Sr-89 < 0.0004 < 0.0015 6/27/83 to 9/26/83 Sr-90 $ 0.0001 5 0.00015 4 (1) I*ncertainties are based on counting statistics and are specified at the 95% confidence interval. Sectiin III DUQUESNE LIGHT COMPANY TABLE III.7 1983 Annual Radiological Environmental Report (Page 1 of 2) - TABLE III.7 QUALITY CONTROL DATA QC Sample Comparisons (All Analyses in DCi/1) Sample Type DLC and Independent Contractor DLC - QC Samole Date Ident. No. Analyses Lab (1) Lab (1) Lab (1) 2-16-83 53-247 Water Sr-90 14.6 2 0.6 15 2 1 15 2 2 I-131 16.1 2 0.3 13 2 1 13 2 2 Co-60 18 2 8 21.9 2 6.7 18 2 6 Cs-134 22 2 8 19.4 2 6.9 16 2 6 Cs-137 25 8 18.5 2 5.8 2426 2-16-83 53-248 Water: H-3 1170 2 60 1160 2 100 1320 2 330 5-25-83 53-249 Water: Sr-90 22.4 2 0.6 20 2 1 21 2 1.3 1-131 23.3 2 1.4 2121 13 2 1.3 Mn-54 38 2 5 29.8 2 4 29 2 8.6 Cs-134 15 2 4 16.5 2 4.1 19 e 11 Cs-137 16 2 3 19.6 2 4.4 19 2 8.2 5-25-83 53-250 Water: H-3 580 2 70 630 2 80 560 2 250 8-17-83 53-251 Water: Sr-90 11.8 2 0.5 14 2 1* 10 2 0.8 1-131 13.5 2 0.8 16 2 1 1722.1 Cs-137 30 2 8 34.1 2 8.1 31 2 7.8 8-17-83 53-252, Water: H -3 1750 2 60 1890 2 130 1600 2 270 11-30-83 53-253 Water: Sr-89 12 2 LLD LLD Sr-90 26.7 2 6 27.0 2 1.0 24 2 5.4 I-131 19 8 8.0 2 0.4 11 2 1.5 Co-60 30 2 5 28.9 2 4.8 35 2 7.8 Cs-134 20 4 16.1 2 4.1 15 2 8.0 Cs-137 22 2 4 23.9 2 5.0 22 2 8.4 11-30-83 53-254 Water: H-3 1500 2 200 1450 2 100 1630 2 290 i l Based on reanalysis, the first analysis, although in general agreement with the QC Lab appeared to be biased high. l (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval. I LLD Lower Limit of Detector. --.

Section 181 DUQUESNE LIGHT COMPANY TABLE III.7 1983 Annual Radiological Environmental Repor2 (Page 2 of 2) TABLE III.7 QUALITY CONTROL DATA QC Sample Comparisons (All Analyses in DC1/1) Sample Type DLC and Independent Contractor OLC -.QC Sample Date Ident. No. Analyses lab (1) Lab (1) Lab (1) 3-16-83 52-226 Milk: Sr-89 9: 2 11 : 1 9.2 : 2.8 Sr-90 18.6 2 0.5 18 1 13 2 2 I-131 16.120.3 12 1 13 2 2 Cs-134 1726 12.5 : 6.3 11 : 6 Cs-137 20 2 6 21.6 2 6.5 21 : 7 S-25-83 52-227 Milk: St-89 622 5.6 1.4 5.7 2.9 St-90 10.4 : 0.5 8.6 2 0.8 9.2 2 1.5 1-131 21.4 2 1.3 12 1 11 2 1.6 Cs-134 1126 11 : 0.2 8.0 2 7.4 Cs-137 2124 22.2 : 3.1 22 2 9.6 8-17-83 52-22S Milk: -Sr-89 1422 16 : 2

7 e it Sr-90 21.0 2 0.5 18

1 14 : 2.7 1-131 7: 0.7 3.8 : 0.2 7.4 1.0 Cs-134 40

• 5 34 : 3.1 25 : 9.0 Cs-137 48 2 5 46.6 9.2 39 8.4 11-30-83 52-229 Milk: I-131 2726 23.0 10 22 2 2.3 Cs-134 13 2 4 7.5 2 4.1 13 2 4.6 Cs-137 1524 13.0 2 3.8 11 2 8.2 (1)

Uncertainties are based on counting statistics and are specified at the 952 confidence interval. -.

~ SECTION III DUQUESNE LIGHT COMPANY 1983 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 Labo ratory. 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 da'ta and the data from the Contractor's internal EPA Interlaboratory Cross Check Program, the Environmental Monitoring Program for 1983 is acceptable with respect to both accuracy and measurement. C. Standard Requirements and Limitations for Radiological and Other Fffluents The Shippingport Atomic 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 further limit discharges to the environment. Shippingport Atomic Power Station is operated in compliance 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 Eesources Industrial Waste Permit #1832, and Environmental Protection Agency (EPA) National Pollutant Discharge Elimination System (SPDES) Permit

1. PA-0001589, Pennsylvania Department of Environmental Resources Industrial Waste Permi+ #0472205, and Pennsylvania Department of Environmental Resources Radioact'.ve Gaseous Discharge Permit are observed and followed.

SECTION III DUQUESNE LIGHT CO.'!PANY 1983 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 (Energy), 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, Part I, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No. 1-70 and 2-70, Environmental Protection Agency (EPA), National Pollution Discharge Elimination (NPDES) Permit #0025615, and the Beaver Valley Power Station Technical Specifications. D. Reporting Levels A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in the Beaver Valley Power Station Technical Specifications when averaged over any calendar quarter. Also, when more than one of the radionuclides are detected in the sampling medium, this report shall be submitted if: Concentration (1), Concentration (2). .2 1.0 Limit Level (1) Limit Level (2) There were no analytical results of environmental samples during 1983 which exceeded Beaver Valley Power Station reporting levels.... -

SECTION IV DUQUESNE LIGHT COMPANY 1983 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 tor the operation of the Beaver Valley and Shippingport stations is taken from the Ohio River, and returned to the river, used for makeup to various plant systems, consumed by station personnel, or discharged to a septic system. 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, Samplin'g, 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

SECTION IV FIGURE 4.1 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report .. E. seS 2 : FIGURE 4.1 s s sut .3 l d-b; E e i

=-

t >G sGE -!s z .c M 550s 2 l g.

3 n aj sg6 o

c ggegl 48 E a4 .<w m 3"W# o E sEOS a<=~ =mu a==- a .5 E"Eb S$8% 5 et .= s -me. a e

== t.y0 kg S s g 2.. ..=- 5 ~ m iae swoa m i m wssua*> nneme-soorwe 4 .i u n u s u iun i n i mmmm ' m m u n n, m u m m m msini w p M E M 1 E a $y "ok

1. gM s

.g a

l 8 50 _== o x.< N d u "d D 5 $[: % 5 5 333 ~ = = $. 5 _d E 58 d E. b "8 1 .5 E 8 5. es us. g n re$ E _i E5 k dB 28 d 4 t 7 1 e J d4 s. W h g g e- \\ i 2 n ~ a $3 o ~ O %=g n E ..=e .= +

1. . 2 f

g p_ _, _

h. j!

,h W E w -s s 2: w= u (s\\J Ed k bg .e E-E E %, e. : i (\\ d g=~ = El % '$; i C !2 2:

ai c a mi c..

l i ii " i ) ~ 11 52- \\ t h; 4 M g 52i 25-SECTION IV FIGURE 42 DUQUESNE LIGHT COTNE 1983 Annual Radiological Envncesital Peport SECTION IV pjggg{ q,2 O TREATED WATER 11EAD TANK PROCESSED RADVASTF PUMPS RADWASTE I PROCESSING SYSTDt g b RADWASTE W REACTOR I RECYCLE RECEIVING] PLANT yp sys;cg TANXS SYSTDtS 1r WATER NEUTRALI-SOFTENERS ZER TANK g FILTERS y. N DEMIDER-WATER i.-4 BOILER ~ ALIZERS STORACE SYSTEM M N I ME tu wa SERVICE 'd d WATER O SYSTEM Al SANITARY WATER SYSTEM ^ n CLEARWELt. RECYCLE SYSTEM l DMM PUMPS - - R.P. AIR HANDLING ~ UNITS DEEPVELL u R. P. COMPONENT s r COCLERS T RIVER WATER l C l T. P. C0!1PONENT s. COOLERS l I 8 SHIPPINGPORT P.S. s HAIN DMIT CONDENSER e.. I SCREEN WASH CIRC. WATER PUMPS PLHPS 70 FIRE PROTECTION SYSTEM FIRE PUMP q, l TRAVELING DE3RIS l SCRIENS \\ d' STitAINER m OH10 RIVER 3, e SHIPPINCPORT P.S. INTAKE / SHIPP NCNRT P.S. (FLW % DISCHARGE l WATER FLOW SCHE!4ATIC - S!1IPPINCPORT ATCttIC PCWER STATIC!I t 1

SECTION IV FIGURE 4.3 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report SECTICN IV FIGUE 4.3 EVAPORATION LOSSES I I BEAVE2 VALLEY FO*aT.R STATION COOLING TOWER PCIPS y N ?m f l s j 'sk 'R

'2L'uRY A

;L

',\\... m m 5:00::0ARY t '". y, "..]{.3 I 'b CC'OE::S ER AND C1;ILLE2S db l W/.TER TR.i!I';G SYSTi;i I I h 4P 1P REACTOR SERVIC:: PIX.*T E0tLF1 SA':ITARY kA!;R SYST::!S SY3Hl! SYSTO! SYSTE:t 1 m 1 i if wp / k NAU

• II RAWASTE RECE!VI:;G M

0 3 Si S.s., ! ( A T.);'J! WATER S C,%,, VASH j( SYSTP>t INTAKE PL'MPS t E i AUX AUX e k AUX TEST SCREEN EPFLUENT! WASH INTAKI ( PCtPS ^ p w if y }f ] P SEA \\ER BEAVER VALLEY BEAVER VALLEY REAVER VALLEY 3CAV2 VALLU 3EAVER VALLEY VALLEY POWER STATION POWER STATION POWER STATION ?OWER STATIO;; PWER STATION A PCWER AUX. DISCHARGE AUX. DISCHARGE DISCHARGE (002) DISCILCGE (00 3) OISCHARO: (001) l STA. AUX. (007) (006) l INTAKE 3 EAVE 2 VALLEY h POWER STATION BEAVER VALLEY PCWE2 STATI0t; DISC;WtCE (004) WATOR FLOW SCHEMATIC

f + a 44OlHO: (I e 2 H4 gOaNM yeV 5 cMt eHG31 O o 2 n t b CcW h3hp aO rOWM MU e mg rD W( ] 1 m Ig" r.- I g 0g I 7g g R E TL I TR F NE EF US LNy AE fag g EN FRg LA ETp CT RE \\ C-T E L I i Ne F A R H A NCI OXO I EC M E H T U S P S Y S M S R Sg L E Ey T R F Cg S E S Oy Y T N k S A A P W E R E NK T T Y AN S R TA A A T W T E R I GE M R E E N RT E E E T V T L I A US T A-R L I T S SA S I I F C W Y O S H F A C TL CS N O A E X t L O I EC T EeR A R D NI S RN C A IM A NLi II I R LE W OO I F H H IC D D EC L O R I I A C U U T& C S Q4 I E I + t S T L4 3E R S H E A

• E O

T W m L N t T D O c I I I I F U T F Q A I T L S P R t L a P 1W l tP R E C D EES TL T t S e AES O lES l

• VTK I TK O

GE t [NTAA CSN R NM A I SN n[( $ LAA UA NCWT PWT ST T P k A M o U P. P A t E I a] M P A P T I S H NE S I G AR RU DS E" N E T I M S A A Y R T S S D N S N E I n T S F I E T A o N N YH A N S E T E I TU R A A D C V M R RR A IS D T W U E O E E R L E T D D T T WT D I e T S E T E N S C D H A C( A M C c I A Y U R i W Y AO I U A i V E S D O S R FR L R R P A M E t T E O I S D O S R A G ; e K LV T NN T iB T G T R f P t mD EI A OI S I E S & A i mI CA I A 6 I E t L t t 1 a s C t e E D R k e N C c P S J 4 k V A A S M P A ( A R DD D t T I I I I I A K A e S S 8 I R P W 4 LD K A T P t D S k A t t 4 t t f N S W C i A S PN L

h. t A A A

A

• S T T 1

h N N H A t t R T C L - ( A A E t I OI O A M T N t 't C SI P T I N L I s t C 1 N c t R A S K A t A S e t M t A s P t or V E t C f L au i S l k t a t h B C C 6 PN t T V = 7 i [ 4 W g ] 4 l! l

SECTION IV FIGURE 4.5 DUQUESNE f.IGHT COM2ANY 1983 Annual Radiological Environmental Report rtcces 6.s i.i s is n a a.i i = [0 i il O I E-A g g 53g cB3; ~ E ,i t 4 l 4 a es = s= in _a ul.- aj n .,.,g-3 i -e s. m + + = i. .. ~------ !~ i O O O O iu 2.i e,. g $ = a3i

a a3 a a a

o o I E A o e ! 3 E l lia = 2

TABLE IV.A.1 .A.2 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report TABLE IV.A.1 1. Effluent Treatment. Samplino and Analytical Procedures - Shicoinacort Treatment. Sampling Standard and/or Effluent Type and/or Monitorino Analytical Procedures (a) Steam System Directed to redweste system if Secondary water is sampled for 810wdown rsdioactive. Normally directed any radioactive contamination. to discharge channel where it A 1000 m1 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 activity (MOA) of 8.4 x 10'g uC1/ml. (b) Radioactive Collected, segregated and A 3000 mi sample is counted for Waste Liquids processed as one of two types gross gama activity. its counter of liquid wastes: can measure a minimum detgetable activity (MOA) of a x 10~ uC1/ml. (a) special waste Also, a 100ml sanple is evaporated (b) radioactive waste and countad for gress beta activity. This counter can measure a mini. nan a Sample taken of batch before r'otoc*&le activity otAl of 1 x 10-3'uCi/ml. processing to remove radio-activity and reuse in plant systems. See Figure 4.4 TABLE IV.A.2 1. Effluent Treatment. $4molina and Analytical Procedures - Beaver Valler Treatment. Sampling Standard and/or Effluent Tvee and/or Monitorina Analytical Procedures (s) Steam System Recycled or directed to Radweste If discharged, procedures adhere Blowdown System for discharge, to Tecnnical Specifications. .(b) Radioactive Concentration of radioactive Procedures adhere to requirements Waste materials released in waste of Tecnnical Specifications, effluents shall not exceed values specified in 10 CFR 20. Appendix B, Table !! for unrestricted areas, and the Environmental Technical Specifications. + ) SECTION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report TABLE IV. A.3 2. Results: Shippingport Effluent Type Results for 1983 (a) Steam System Because of final plant shutdown on October 1, Blowdown 1982, there were no boiler blowdowns during 1983. (b) Radioactive Since Shippingport first went into operation Waste Liquids in 1957, the total activity of liquid waste discharged each year has decreased more or less continuously. For example, radioactivity exclusive of tritium decreased 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, 1980, 1981, or 1982. Discharging of radioactive liquid waste resumed in 1983, with a total activity, exclusive of Tritium, of less than 0.0001 Ci being released. The total Tritium released was approximately 0.672 C1. TABLE IV.A.4 2. Results: Beaver Valley Effluent Type Results for 1983 (a) Steam System The Steam System Blowdown was recycled or Blowdown directed to the Radwaste System where it was monitored and discharged in accordance with conditions noted in 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 in the Beaver Valley Power Station Semiannual Effluent Reports for 1983..

l SECTION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents 1. Description of Airborne Effluent 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 and canal systems. These systems contain the activated corro. ion and we;r 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 and canal sampling opecations, defueling operation, maintenance and overhaul operations, or working on contaminated components removed from these systems. Stringent radiological controls which have been developed during 26 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 airborne during operations on contaminated components removed from these systems.

However, strict radiological surveillance is maintained throughout the

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.,

SECTION IV DUQUESNE LIGHT CO.'!PANY 1983 Annual Radiological Environmental Report f The principle environmental release points for the Shippingport Atomic Power Station are the containment ventilation exhaust and the Radioactive Waste Processing System exhaust. These points cre continuously monitored, and analyses are performed on charcoal cartridges weekly for I-131 and monthly for I-133 and I-135. Additionally, weekly continuous air samples are obtained on fixed filter papers which are analyzed weekly for gross beta, and composited monthly to identify gamma emitting 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 for each release point. t 1 5 -

SECTION IV FIGURE 4.6 DUQUESNE LIGHT COMPANY ) 1983 Annual Radiclogical EnvironmenCal Report l SURGE TANMS r REStN STCR GE istaS FLASM TANT = SPRAY RECYCLE TANK 1 GAS STRIPRER r T VENT CAS COMPRES3CRS it o HsCRCCEN ANA4,Y2 ER ANO CATALYflC H1CRCGEN SURNER SYSTEM PRESSURE REDUCWG r 4 VALVE j ~ VENT CAS m 4870 CUDC FT (STP) SURGE CRUM ^ I I ,P OAS DECAT CRUMS 133 Ct8tc FT EACH (STP) 1, i, it TEST TANKS O!LUTICN CHEMICAL WASTE TANK 5 FANS lon Exchangers I l l ' l STACK GAS McNITORS - TO STACM Shipping; ort Ateste Power Stattori Caseous Radicactive '.'este Processir.g Systes FICURE 4.6 38 -

i SECTION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS a. Shippingport Atomic Power Station (continued) Reactor plant exhausts from the Decontamination Room, Sample Preparation

Room, Radiochemistry Laboratory, Gaseous Waste System, Compacting Station, and Decontamination Waste Drain Receiver Tank are continuously sampled with fixed filter samplers. These samples are analyzed weekly for gross beta, and composited monthly to identify 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. Af ter 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 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 analysed 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 monthly for Sr-89 and Sr-90. SECTION IV FIGURE 4.7 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report SUVtt VALLET PWtt $TAf!CM CAf tlX$ SACICACTIVE WASTE Fir 0CtfS!M !YfitM 'I3: MrX = p -- e E i ~ ~ s s. a g u = 3 s' o W b i 8 / sf 8 5 ( 5 n a 5 ir e a s b l h 48% 0 y g = s .e r h h Sr

== "2 3 g $.*5 l 1 e 8s a \\ $~/,,/,. '//, 5 1 5 2: e g 'EG iP k dk a di j .L iL j6 w I b y Jk h ,F F, a e h ( ^ i 1 t 3 b, ?- I ) P i i 1P 4 I e n ? 4 r, x 3 SW ft E t ga. c.: 5 ? e. a SECTION IV DUQUESSE LIGHT COMPANY 1983 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS 2. Airborne Effluent Traatment 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 airborno activity to automatically seal off the primary containment to prevent an inadvartent release of radioactivity. Reactor plant exhausts trom the Decontamination

Room, Sample Preparation Room, Radiochemistry Laboratory, Compacting Station, and Decontamination Waste Drain Receiver Tank are also equipped with high efficiency particulate air filters, and are continuously monitored for radioactive particulates by the use of fixed filter menitors. 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 Radioactive gases enter the gaseous waste disposal system from the degasifier vont 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, cosium, manganese and iodine are also present in the gaseous affluent. -41

SECTION IV FIGURE 4.8 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report SECTION IV DISCHARCE POI?.'TS - CASECUS WASTES i Ventilation Vent k SLCRS Vent f J / / / O C v I r Containment Vencilacien System (Containment Air Normally recirc.-not vented) Auxiliary Building 7entilation System Exhausts Caseous vastes to Cooling Tower; Air Ejector l GASECUS RELEASE POIvrS - BEAVER VALLEY PCWER STATICN l l 5 l ( Waste Disposal Building Fuel Handling Building Service Bldg. Exhausts + (Filt ered) / -Concrete Enclosure l Y d Emerg. Filtration Exhaust I.- Ca s ecu s Wa s t e ventilation Exhaust (Filt ered) ; Release (Filtered) Air Ejector CASECUS PELEASE POI!rTS - SMI????tGPcRT ATC?iIC ?PirR STATTC?* FIGURE 4.8 SECTION IV DUQUESNE LIGIIT COMPANY 1983 Annual Radiological Environmental Report 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, the flow of the waste gases from the decay tanks (2 scfm) is recorded and rapidly diluted with about 1000 scfm of air in order to 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 procese vent on the top of the cooling tower. The radioactivity levels of the stream are monitored continuously. Samples are also taken to determine the rate of l activity released to th'e 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 {- Ventilation Vent located on top of the Auxiliary l Building or the Supplementary Leak Collection and i Release System (SLCRS) Vent located on top of the l Reactor Containment Building or the Process Vent i located-on top of the Cooling Tower. I-i l J

)

SECTION IV DUQUESNE LIGHT COB 1PANY 1983 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 activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the supplementary leak collection and release system (SLCRS) and to the SLCRS Vent. Release points are shown in Figure 4.8 for the Beaver Valley Power Station. + b 1 1 a l l SECTION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report i 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 Decaf 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 counter has a mininum detectable activity (!!DA) of 3 x 10-7 pCi/cc for the predominant nuclide of Xe-133. ]

~~ A-3,4 ' t SEC? ION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Envircr.nental Report IV. MONITORINC ETTI.tET!S 3. AnalvticsU Procedures f or SamtliEt Af rgerne Uflueng (continued) Air 13hausts Samplias Type 0f Seele N Freeuen g Activit @ lveis Doctectable Limits 1.2 x 10-6,ggf,, gg,,, (1) Air frota the Fiant Ventilation Continuous Gross Casma Channel 8 ORMS)e Estaust Effluent Stream 5 x 10-10 uC1/cc (Particulates Channel 12 ORMS)* 1 x 10*I' uC1/cc

12) Particulate' Filter in Flant contina,as Gross Beta

• /encilation Ef fluent Stream weekly Sample (Particulate) and Casew s 11aste Systen T.ataust 1 x 10 g3 uct/cc Facticulate Filter in flant Continuous Frtaciple Casna Ventilation Effluent Streas.

Morthly Coopcsite Particulate (Weekly if Cro Seta 1 1 x 10*gs*3) and Caseous Weste Systes Exhaust 2 x 10-15 uci/cc Particulate Filter 1r Plar.t Continuous Cross Alpha vestilation Effluent $tream Monthly Particulate ~ .g4 and Caseous Weeta System Exhaust Fatticulate Tilter in Flaat Continuous $r-89. Sr-90 3 x to uC1/ml ($r-89) Vent 11stion Effluent Stream Quarterly 1 x 10*I' uC1/ml ($r-90) 4:4 Caesous Waste System Exhaust Particulate

• I3 (3) Charcoal Cartridge in Flant Continuous 1-131 1 x 10 uC1/mi ventilatica Ifflueet Stream f.eekly.

1 x to.g3 uC1/a1 (1-133) and Caseous Waste Syaren Exhaust Charcoal Cartridst in Plant Monthly I-133. :-133 Ventilatics fffluens Seteaa renthly 1 x 10-12,ggj,1 gg,g33,' and Caseous Waste System Exhaust H' 2 x 10* uC1/ml (4) Evacuated Bomb Sampio In' Monthly Flant Ventilation Effluent Strees and Gaseous Waste Systes Exhaust ! x 10*I' WC1/cc D) Particulasa Filter in Reactor continucus Cross seta kaakly Particulate Plant Ev.haust from Decontasi-nation Race. Sample Preparatica Room. Radiochemistry Laboratory. Compactine Station..ind Desen-tamination kaste Drain flatelver Taft. ! x 10*II MC1/cc Particulate filter in teactor Continu'aus Principal Camma Plant 14heust fram Decentami-Monthly Composite Particulate nation Ro'ra. Senple 1reparatioe (Weekly if Crges Beta 1 1 x 10 13) Roce. Radiochemistry Labctatery. Compattf rit Statin. and to: ort. tac 1*ta tion vaste Drain Receiver Tank. 00'5 = Operational Radiation Monitoricg Sy*tes

• Althoud ti.e OMt3 Channels have no spesific function as f ar as ef ?!uent wui:t rug aad reporting Jt is also noted is coyca rne d. *.hese tw (*) channels are bete? listed f or inf erration sucpotas.these :ha that 4* /cc sie reached on Channel S. er ! x 10*7.C1/ec ce Channel 1;. Additiona p. they shut the i

vautila p n ayat o butterfly valves when levels of 1

• x 10** act/et are resched on Charnel 1 or 1 < 10 d,i/cc on Chavel 12. -

SECTION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS 3. Analycical 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 Concentrations Source Frequency Activity Analysis (uCi/al)a (1) Weste Gas Decay Tank Each Tank Principal Gamma Emitters 10-'D Releases ~0 H-3 10 (2) Containment Purge' Each Purge Principal Gamma Emitters 10~'" Releases -6 H-3 10 (3) Environmental Release Monthly Principal Gamma Emitters 10' Points (Gas Samples) -6 H-3 10 Weekly I-131 10-12 (Charcoal Sample) -10 Weekly, I-133, I-135 10 (Charcoal Sample) d Weekly Principal Camma Emitters 10 (Particulates) (Ba-La-140, I-131, and others) ~11 Monthly Cross a 10 d Composite (Particulates) Quarterlyd Sr-90 and St-89 10 Composite (Particulates) O The above detectability limits for activity analysis are based on technical feasibility and o., the potential significance in the environment of the quantities released. Por some nuclidct. lower detection limits may be readily achievable, and when nuclides are seasured below the stated limits, they should also be reported. For certain mixtures of gamma 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 measur:.

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

d To be representative of the average quantities and concentrations of radioactive materials D. particulate form released in gaseous effluents, samples should be collected in proportion to the rate of flow of the affluent streas. _ 47 _

SECTION IV DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS 4. Results a. Shippingport Atomic Power Station Anslyses for the particulate airborne 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 showed naturally occurring radioactivity typical of " background air" and nuclides attributable to worldwide fallout from nuclear weapons testing. During 1983,.there were six (6) instances where activity attributable to. plant operations was measured. In each of these instances, Cobalt-60 activity was measured in the Decontamination Room Vaste Receiver Exhaust. The total amount of Cobalt-60 activity released was 0.000000008330 Ci with concentrations ranging from 2.10 x 10-15pCi/cc to 1.51 x 10-13pCi/cc/ These concentrations are all well below Faderal limits. Radiostrontium analyses of quarterly composite air filter samples showed Sr-89 and Sr-90 concentrations in air which 'were at or near the minimum detectable concentrations of 5 x 10 -14 pCi/ml, and 1 x 10 -14 pCi/ml, respectively. The levels of Sr-89 and Sr-90 observed were extremely low and are ' typical of " background air" radiostrontium levels. Also, Carbon-14 activities in gaseous effluent releases were estimated based on analysis of primary coolant and analysis of l Radiocctive Waste Processing System vent gas and l tritium activities in gaseous effluents were estimated based on canal water tritium levels. These activity levels were/ consistent with past reported levels considering plant operations during 1983. There were five (5) releases of gaseous radioactivity from the Shippingport Atomic Power Station during 1983. The total gaseous radioactivity released from'the Shippingport Atomic 1 L l

( SECTION'IV. DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report Power Station during 1983 was approximately 0.0000205 curies of Xe-133. The amount of radioactivity released from the Shippingport Atomic Power Station during 1983 was extremely small and had a negligible effect on the environment as shown in Section V.I.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 1983. 1 L P l. 4 I 4 .-.. + - ,r,--, r - - ~, -,. - - ,,,-,e -7 r,m ,c-- ,,-,i.m-r v-v.w y --, m.,, --.,e

SECTION IV DUQUESNE LIGHT C0}!PANY 1983 Annual Radiological Environmental Report IV. ?!ONITORING EFFLUENTS C. Solid Waste Disposal at the Shippingport and Beaver Valley Power Stations During the Shippingport Atomic Power Station defueling efforts and Beaver Valley Power Station normal operations and pericdic maintenance, small quantities of solid radioactive waste materials were generated 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 drum 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 Begulatory Commission. Shipments offsite were made in accordance with Department of Transportation regulations. Figure 4.9 depicts solid waste handling at the site. In 1983, the Shippingport plant disposed of a total of 14,130.5 cubic feet of radioactive solid waste having a total radioactivity of about 15.334 curies. This included twenty (20) shipments of low level wastes. At Beaver Valley Power Station approximately 7,417 cubic feet of radioactive solid waste was shipped offsite in 1983. The actual burial volume of solid waste is slightly higher due to container size (8127 cubic feet). The thirty (30) shipments contained a total activity of 475.1 curies. l l 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.

SECTION IV FIGURE 4.9 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report SECrlCN IV SOLD AST? DISPCsAL DIAcnAM y:Grag 4,9 NADIDACTIVi? SOf,0) WASTE DISPOSAL Misc. Radioactive Compactor and Solid Wastes Drummf ng Station ] D k 'on oo'oM 2 Wadioactive Waste Sludge Solidify-Disnnsal Evaenrator ina Station j ~3 o Spent Radioactive Special Shipping a o Resin Casks & Containers

• Ji 00'

'crfo o-g INDUSTRIAL SOLID WASTE DISPOSAL DIAGRAM l l t Water Filtered; Filt ers drummed---- --.4 9 Sludge From Water f Treatment Plant and ) Sewage Treat =ent g ]e Planc (3VPS) 8 Trash Basket - Beaver Valley ] Debris and Trash Hopper [at Screenhouse Shippingport From Screenhouse \\ I w Q x P I g c e 'O n a j m ~3 $w Trash & Garbage Storage 31n Ct 5 c FIGURE 4.9 U i 1.

SECTION V - A DUQUESNE LIGHT COMPANY 1983 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, vegetation and foodcrops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table V.A.1. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are included in parts V-B through V-I of this report. V-B - Air Monitoring V-C - Sediments and Soils Monitoring V-D - Vegetation and Foodcrops V-E - Cow's Milk V-F - Environmental Radiation Monitoring V-G - Fish V-H - Surface, Drinking and Well Waters V-I - Estimates of Radiation Dose to Man TABLE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM h29 Dt C Sample Sample Analysis ' Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Frequency Analysis (b) 1. Air Particulate 13. 11 1.6 Heyer's Farm Continuous Sampling Weekly Composite (d) Gross Beta ICI -131 I and Radiolodine 30 4 0.6 Shippingport PA. (S.S.) with sample collec-46.1 3 2.4 Industry PA (Tire Co.) tion at least Monthly Composite (d) Gamma -scan weekly 32 15 0.8 Midland, PA (S.S.) 48(a) 10 16.5 Weirton, WV (a) Quarterly Composite (d) 51 5 8.0 Aliquippa, PA (S.S.) Sr-89.90 47 14 4.8 East Liverpool, OH 27 7 6.2 Brunton's Farm 28 1 8.7 Sherman's Farm ca 298 3 8.1 Beaver County Hospital [ g I 2. Direct 30 4 0.6 Shippingport, PA (S.S.) Continuous Quarterly ) Radiation 13 Il 1.6 Meyer's Farm (TLD) Annually Gasmia-Dose y 8 46 3 2.5 Industry,PA(Church) 51 8 32 15 0.8 Midland, PA (S.S.) ?., G 48 (a) 10 16.5 Weirton, WV (a) 3 $ 8 45.1 6 2.0 Raccoon Twp, PA Kennedy's Crnrs. g r-to 51 5 8.0 Aliquippa, PA (S.S.) E w 47 14 4.8 East Liverpool, OH 4 I 70 1 3.0 West. Byr. School = n 80 9 8.4 Raccoon Park !g 81 9 3.9 Southside School 82 9 7.1 Hanover Municipal Bldg. 2 5 83 10 4.5 Mill Creek Rd s. 14 11 2.6 Hookstown 84 11 8.5 Ilancock Co. Children Home [ 85 12 5.8 Rts. 8 8 30 Intersection 86 13 6.5 E. Liverpool Cahills House Q 92 12 3.0 Georgetown Rd. 87 14 7.0 Calcutta Road 88 IS 3.1 Midland Heights 89 15 4.7 Ohioville 90 16 5.2 Fairview School 10 4 0.8 Shippingport Boro PA 45 5 2.2 Ht. Pleasant Church 60 13 3.7 Haney's Farm 93 16 1.3 Sur. set Hills, Midland 95 10 2.4 McCleary Rd Hollie Williams C r"- S.S. - Substation

TABLE V.A.] CONSOLIDATED RADIOLOGICAL ENVIRONENTAL MONITORING PROGRAM y, (Cor.tinued) h DLC N Sample-Sample Analysis Type of sample Points Sector Miles Sample Point Description Sample frequency Preparation Frequency Analysis (b) 2. Direct 28 I 8.7 Sherman's Farm Continuous Quarterly Gamma-Dose Radiation 71 2 5.6 Brighton Twp. School (TLD) Annually (Continued) 72 3 3.2 Logan School 298 3 8.1 Beaver County Hospital 73 4 2.2 Potter Twp. School 74 4 6.8 Conn. Col-Cent' r Twp. e 75 5 4.3 Holt Road 76 6 3.8 Raccoon Twp. School 77 6 5.8 Green Garden Rd (Wayne's) 59 7 1.1 Irons 3 18 7 2.3 Raccoon Mun. Bldg. 27 7 6.2 Brunton's Farm 79 8 4.6 Rt. 18 & pt. 15I E 15 14 3.3 Georgetown 46.1 3 '2.1 Industry PA Tire Co. g

=

91 2 , 3.7 Pine Grove Rd and Doyle Rd E g 94 8 2.4 McCleary Rd, Wilson y a Ni . Surface 49.1 4 5.0 Arco Polymers (a) Intermittent Monthly Composite of Gross Beta bh Water 2.1 14 1.3 Downstream (Midland) Crucible Composite Samples (j) Weekly Sample (d) Gross Alpha ~$ 3 Collected Weekly Gamma-scan E' 3 13 0.2 Shippingport Atomic Power Weekly' Grab Quarterly Composite Co-60. H-3 i on Station Discharge Samples Only Sr-89. Sr-90 3 ) 49 (a) 3 3.2 Montgomery Dam (Upstream) j $ s 2A 13 0.2 Downstream BVPS Outfall 5 14 4.8 East Liverpool (raw water) Daily Grab Sample ~ Only - Collected Weekly (j) F uo 4. Groundwater 13 11 1.6 Meyer's Farm 14 11 2.6 Hookstown, PA 15 15 3.3 Georgetown, PA 11 3 0.8 Shippingport Buro Quarterly Quarterly Ganna-scan, Gruss Beta, Gross Alpha. H-3 5. Drinking 4 14 1.3 Midland, PA (Midland Water Intermittent Weekly Composite of Gamma-scan,1-131 h Treatment Plant) Sample Collected Da_i_1y Sampi d d) g; Weekly Monthly, Composite (d) Gross Alpha Gross Beta 5 14 4.8 East Liverpool, OH (East Quarterly Composite (d) H-3,Co-60 Sr-89. 90 3 Liverpool Water 1reatment Plant)

v. TABLE V.A.1 R CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM E3 (Continued) [ DLC Sample Sample Analysis Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Frequency Analysis (b) 6. Shoreline 2A 13 0.2 Downstream BVPS Outfall Semiannual Semiannual Gaamia-scan, Gross Beta Sediment Gross Alpha 3 13 0.2 Vicinity SAPS Discharge Uranium Isotopic 49 3 3.2 Upstream Side of Montgomery Sr-89, 90 Dam (a) 50 13 8.2 Upstream side of New Cumberland Dam 7. Milk 25 10 2.1 Searight*S Dairy Weekly Weekly sample from I-131 Searight's only 3 61* 12 3.2 Allison Biweekly (g) Biweekly (grazing) Gasmia-scan 6* 69* 7 3.6 Collins When animals are Monthly (Indoors) Sr-89, 90 y 96(a) 10 ?C.3 Windsheimer on pasture; I-131 Cs-137 8 98* 5 2.9 Foxall monthly at other 100* 14 2.8 Doughty times. 1 g 27 7 6.2 Brunton's Dairy (h) Monthly Monthly Gasmia-scan Sr-89, 90 gg 29(a) 3 8.3 Nicol's Dairy (h) 1-131, Cs-137 gg ,g 8. Fish 2A 13 0.2 Vicinity of BVPS fl Semiannual Composite of edible Gamma-scan on edible i Station Discharge and parts by species (1) portions O C y, Shippingport Dis. Sta. ~E vi 49(a) 3 4.7 Upstream Side of T n Montgomery Dam i g E o 9. Food Crops (Shipp.) 10 4 0.8 (three locations within Annual at Composite of each Gasmia-scan ki (Georg.) 15 14 3.3 5 miles Selected by harvest if sample species 1-131 on green 3 (Indus.) 46 3 2.5 Company) available leafy vegetal,les i 48(a) 10 16.5 Weirton, WV m ~

10. Feedstuff and 25 10 2.1 Searight's Dairy Farm Monthly Monthly Gaemia-scan Q

Suusner forage ()uarterly Quarterly Composite Sr-90

11. Soil 13 11 1.6 Meyer's Farm Every 3 years 12 Core Samples Gannia-scan 30 4

0.6 Shippingport, Pa. (1982,1985, etc. ) 3" Deep (3" Dia. Sr-90 46 3 2.6 Industry, Pa. at each location Gross Beta 32 15 0.8 (North of Site) Midland (approx. 10' Gross Alpha 48(a) 10 16.5 Weirton, W. Va. radius) Uranium Isotopic SI 5 8.0 Aliquippa, Pa. 47 14 4.8 E. Liverpool, Oh. 2/ 7 6.2 Bruntnn's Dairy 22 8 0.3 South of BVPS Site 29A 3 8.3 Nichol's Dairy g

• Additional dairies required by Invironmental Technical Specification 3.2.1.D.2.

In addition to Searight*: (Site 25), three dairies are selected E when milk is available tused on highest deposition f actors. Sites 27 and 294 are required for the Shippingport program.

SECTION V - A DUQUESNE LIGHT COMPANY 1983 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 (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location. (e) Composite samples are collected at intervals not exceeding 2 hours. (f). Weekly milk sample from Searight's Dairy is 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).] 4 (h) The milk samples from Brunton's and N'icol'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 separatien by species practical, then edible parts of all fish in the sample will be mixed to give one sample. (j) Composite samples are collected at intervals not exceeding 2 hours at locations 49.1 and 2.1. Weekly grab samples are obtained at location 3, 49 and 2A. A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5. (k) TVo (2) TLD's are collected quarterly and annually from each monitorint location. _=

SECTION V - A DUQUESNE. LIGHT COMPANY 1983 Annual Radiological Environmental Report Additional Notes: -- Sample points correspond to site numbers shown on maps. All Iodine I-131 analyses are performed within 40 hours of sample collection if possible. All Air samples are decayed for 72 hours before analyzing for Gross Beta. 1- ,l r i e l i s-8 i

[NVIRONMENTAL RADIOLOGICAL MONiiORING PROGRAM SUPNARY Name of facility Duquesne Light Company Docket No. 50-334 Location of f acility Beaver, Pennsylvania Reporting Period Annual 1983 (County,5 tate) [o Analysis and Lower Limit Number of Z Medium or Pathway Total Number of All Indicator locations Location with Highest Quar. Mean Control Locations Nonroutine Sampled of Analysis Detection

• • Mean (f)

Name

• • Mean (f) **Mean (f)

Reported (Unit of Measurement) Performed (LLD)

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

Walrton,WV No. 48 w Air Particulate Gross (520) '2.5 18(520/520) Sherman Dairy No. 28 19(52/52) 18(52/52) 0 and R lolodine Beta (X10pCi/Cu.M.) (6.1-44) (8.3-44) (6.9-38) D-p ,c $r-89(40) 2 LLD Dw $r-90 (40) 0.1 0.13(3/40) Sherman Dairy No. 28 0.15(1/12) 0.12(1/12) 0 (0.12-0.15) 'g % o, r.o 1-131 (520) 10 LLD O@ go us Gamuna(120)_ K% Be-7 20 % (120/120) Sherman Dairy No. 28 104(12/12) 98(12/12) 0 o (31-151) (67-151) (49-147) $[o e K-40 10 31(23/120) Industry, Pa No. 46 70(2/12) 23(1/12) 0 o, (12-87) 2.0 miles - NNE (54-87) y% g Ra-226 10 13(1/120) Beaver Co. H. No. 298 13(1/12) LLD 0 o 8 miles--[NE y m Others Table V.A. 4 fiD S b af E a ] i H 7' Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of* detectable measurements at specified locations is indicated in parentheses (f) Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendix B) y .~

EEVIRONMENTAL RAul0 LOGICAL MCITORING PROSRAM SUINARY Name of f acility Duquesne Light Company Docket No. 50-334 t.n Location of f actitty Beaver, Pennsylvania Reporting Period Annual 1983 g i { County, State) g Analysis and Lower Limit Number of Medium or Pathway Tot al Nunber of All Indicator locations location with Highest Quar. Mean Control tocations Nonroutine ~ 4 Saupled of Analysis Detection

• • Mean(f)

Name

• htean (f)~**heTn TTT-Reported (Unit of Measurement) Performed (LLD)
  • Range Distance and Directions ** Range
• *R ang e Measurements ***

I Montgomery 7 am ~p No. 49 e Sediment Gross (8) 0.3 17(8/8) Montgomery Dan No. 49 22(2/2) Same as 0 (pCi/g) Alpha (9.7-34) River Mile -- 31.0 (9.7-34) liigh Location (dry weight) Gross (8) 1.0 30(8/8) SAPS Discharge No. 03 33(2/2) 27(2/2) 0 o Beta (23-38) River Mlle --34.8 (29-38) (23-31) e-* Sr-89(8) 0.2 LLD ga 4 + bc i Sr-90 (8) 0.04 0.076(5/8) Mont90mery Dan No. 49 0.099(1/2) Same as 0 (0.041-0.11) River Mile -- 31.0 High Location og Gamma (8) S$ Be-7 0.2 0.51(3/8) BVPS Discharge No. 02 0.69(1/2) 0.32(1/2) 0 C (0.32-0.69) River Mile -- 35.0 Hy tn H tn K-40 0.5 12(8/8) SAPS Discharge No. 03 13(2/2) 12(2/2) 0 yn (8.9-16)- River Mile -- 34.8 (11-16) (11-14) ro od Co-60 0.03 0.44(4/8) BVPS Discharge No. 02 0.65(2/2) LLD 0 g $g (0.22-0.88) River Mile -- 35.0 (0.42-0.88) ,p Cs-137 0.02 0.33(8/8) SAPS Discharge No. 03 0.40(2/2) 0.28(2/2) 0 g l (0.19-0.50) River Mile -- 34.8 (0.31-0.50)(0.26-0.29) e Ra-226 0.1 2.3(8/8) BVPS Discharge No. 02 3.0(2/2) 2.2(2/2) 0 E (1.4-4.1) River Mlle -- 35.0 (1.9-4.1) (2.1-2.3) '8 et i Th-228 0.02 1.3(8/8) 8VPS Discharge Nu. 02 1.7(2/2) 1.2(2/2) 0 rt (1.0-1.8) River Mile -- 35.0 (1.6-1.8) (1.1-1.2) i J l H b Nuuinal Lower Limit of Detection (LLD) "ri t 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 Specificatfors (Appendix B) to i 1

m ENVIRONIENTAL RADIOLOGICAL POIITORING PROGRAM Supet4RY Name nf Facility Dues.esne Light Company Dcckst No. 50-334 $fl - Location of Facility 8eaver. Pennsylvania Reporting Period Annual 1983 s (County.5t ate) Q Analysis and Lower Limit Nimber of 4 Medium or Pathway Total Number of All Indicator Locations tocation with-Highest Quar. Mean Control Locations llonroutine Sampled of Analysis Detection

• • Mean (f)

Name

• • Mean(f) **Mean (f)

Reported (Unit of Measurement) Performed (LLD)

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

p Montgomery Das No. 49 Sediment Others Table V.A. 4 LLD o (pC1/g) (Cry weight) U-233(8) 0.01 0.63(8/8) BVPS Dis &arge No. 2A 0.71(2/2) 0.51(2/2) 0 (continued) and (0.38-0.%) River Mile -- 34.8 (0.54-0.90) (0.48-0.55) U-234 Sc U-235(8) 0.01 0.020(8/8) N.Cupberland Den No. 50 0.026(2/2) 0.017(2/2) 0 (0.011-0.040) River Mlle - 54.0 (0.011-0.040) (0.013-0.020) ye >c U-238 (8) 0.01 0.31(8/8) SAPS Disdurge No. 3 0.50(2/2) 0.37(2/2) o Q (0.033-0.62) River Mile -- 34.8 (0.38-0.62) (0.35-0.38) om o$ gm Ob g 4 -g I 1 i

i. 8 2E5 n*

F ? H be

• Nominal Lowe-Limit of Detection (LLD)

M Mean and rar.ge 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 8eaver Valley Power Station Technical Specifications (Appendix 8) to

~. En m OH ENVIRONHLNIAL RAD 10t6GILAL MtOI10 RING PROGkAH 50V+WV o= Name of facility Duquesne Light Cumpany Docket No. 50-3 M Location of facility Beaver, Pennsylvania Reporting Period Annual 1983 8 (Inunty, Stat -) Analysis and tower Limit Medluin or Pathway ' Total msuber of Number of All Indicator tocations Location with Highest Quar. Mean ' Control Locations Nooroutine Sampled of Analysis Detection

• Glean ( f)

Name

• • Mean (f)'liean (f)

Reported e junit of Measurunent) Performed (LLD)

• • Range Distance and Hirations ** Range
  • Range Hessurement s* *
• leed and forage Sr-90(4) 0.003 0.075(4/4)

Searight Daisy Na. 25 -- One sample 0 g (pC1/g) (0.020-0.20) 2.4 miles -.5W location n (dry weight) Gausna (l2) H Be-7 0.3 0.76(6/12) 0 (0.45-0.91) Eoc

c. c e c:

K-40 0.5 12(12/12) (4.3-23) 0 o m 7y ao m Es-137 0.03 0.045($/12) 0 y t-* (0.015-0.083) m H H a Ra-226 0.03 0.72(1/12) O mN g gn

e. O I

Th-228 0.05 0.064(2/12) + -- 0 y@ (0.037 0.090) c :> 25 Others Table V. A. 4 LLD p remW t O Pt rt H N Nominal tower Limit of Detection (LtD) t-* Mean and range based upon detectable measurunents only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) M Nonroutine reported measuranents are defined in Regulatory Guide 4.8 (Decamber 1975) and the Beaver Valley Power Station Technical Specifications (Appendix B) ( L> L

Egtm$ [$dnOk>g Hbetn 4.>,N n t.?do* 4 p n! $w $D$H g$O oo$p" $Nr O B.cE $?? s o ) f s (n o si et sa ec hi tf s ni t ec e n re f n e O 0 0 0 ap oidm pS t ee rut r nl eoru ia bros c mnpa di uoee en NNRM thac ce n iT o s i d n 8 nn o 4 t io i) a i tf so ia c st a ( o c eh aL 't o ng s5 a n'W D mg D or W eh n L ea l MR L ai L ie o** n L SH L t w r ** o ao t t cP n r o o i l y C e ) e ) W ) 1 dl 3 f 2 )) / el 8 ( / 32 1 i a 9 .n e 1 /1 ( fV 1 a ng ( 3 - G i e an 7 (4 2 cr M ea 1

9. 3 0

ee la MR pv u 0 - 5( 0 - sa n r ** e Y n a tB R 4 A u s 0 a A 3 Q n 1 5 e H 1 d o 1 sh P o S 5 i t i tt U 0 s t o ed n r e c N 8 a e h e 4 NW mn M P H A g ig ir A A1 r R i P 1 ea G o n l D oW P u) t NS s5 O N i h r n-a7 R t t d o V - w e9 P t r i n p W os m1 e o w a g s t e G k p ip ti em bB n ne el eR N c e n e ol gi lE o R o ec I D i nn ip ie0 e cI rm r aM C t aa o6 tf T a Nt h I c is S W2 G4 eP N o tE O y L D eS M n d( a L p a s f8 A m C o i) n o n e o 4 I C at i n G va t oe U t i t. a i d g. cJ ti L h 0 g s of ) cu. 1 i n y l ( -) 8 aG D l n t 8 )) / r A e n r ne / 82 1 F y R e P u o ag 1 /1 ( r n o t en ( 8 - 0 o L s ,C aMa 7 (9. 0 p ya 2 .t icI R D A e r( 1 6.1 e T u e L ll L N q v d L 0 - 4( 0 - I nu E u a n og D, M e I e B sR NO l t R y l nn I t y A ei V i t 4 m N l i ed E i l re A. un c i t a c si f a i n V af m F i o ee md f L i) 6 e ) o f tD 0 1 l D o rf ct 0 3 5 0 b L ee e eoet a Ll r m n w t( 0 0 0 0 T (ba a o o e a N i L D nt s t oct a ien c drs tt e o nei cem L absd ) ede sye ) 8 t r sul m 8 ( enu iMar ( Dos s no 7 s pa ylAf 1 a 3 r f ue l a r 3 m7 0 1 e o m atf e 1 m-4 h d nooP ae s t t ed AT GB K C O se I imat ) ibr t L o n ep) e rgeB y m enr a e wa x w r n orei h u e L nd t s d) din a a rg) l nt e P e a/t aaup dM Gih n op re Cg inrA olf d pi man ( po n( e oeo mn a w NMN uat s iSi d pt d n ooe e U orw M ( FC( I mN

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM $UpstARY to Mame of Facility Duquesne Light Company Docket No. 50-334 H E Location of Facility Beaver. Pennsylvania Reporting Period Annual 1983 2: (County,5 tate) 1 Analysis and Lower Limit Nueer of Medium or Pathway Total Nueer of All Indicator tocations location with Highest Quar. Mean Control locations Nonroutine Sampled of Analysis Detection H Mean (f) Name

• • Mean (f) **Mean (f)

Reported illnit of Measuronent) Performed (lLD)

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

er Brunton Dairy No. 27 Milk I-131(153) LLD (pCl/f) o Sr-89(123) LLD w Sr-90 (123) 4.6(123/123) Collins No. 69 10.l(19/19) 0 (0.43-18.0) (3.9-18.0) Ets

o. c:

Ganssa(124) 70 Hb K-40 1340(124/124) foxall No. 98 1710(8/8) 1330(12/1?) O (686-2060) (1270-2060) (1070-15%) S$ n tn Cs-137 7.4(16/124) Nichols No. 29% 10.9(1/12) LLD 0 0t* - (4.0-13.6) Hg m a: Others Table V.A.4 LLD DH I $o 8i5 P R k~ u H ? E a Nominal Lower Limit of Detection (LLD) Me.m and range based upon detectable measuremerts 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 8eaver Valley Power Station Technical Specifications (Appendix 8) gg t* tM I~

.q [NVIRONMENfAL RADIOLOGICAL MC]IICING PROGRAM SUN 4ARY Name of f acility Duquesne Light Company Docket No. 50-334 Q Location of Facility Beaver (CEnty,$ tate) H Penn31vania Reporting Period Annual 1983 o* I Analysis and Lower L lait Nunber of Medium or Pathway Total Number of All Indicator tocations Location with liighest Quar. Mean Control Locations Nonroutine Sampled of Analysis Detection

• FMean (l)

Nme

• • Mean(f) **Mean (f)

Reported 5 (Unit of Measurenent) Performed (LLD)

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

m k Weirton,WV W No. 48 g External Radiation (175) 0.05 0.18(175/175) No. 87 0.20(4/4) 0.19(4/4) 0 (nR/ day) (quarterly) (0.12-0.22) (0.19-0.21) (0.18-0.20) (44 annual) 0.05 0.17(44/44) No. 88 0.20(1/1) 0.18(1/1) 0 fe (0.13-0.20) SE o tn N Be 1 E'fi hg I Montgomery D a No. 49 t ish Gannia (8) s (pC1/g) K-40 0.5 2.l(8/8) Montgomery Das Nc. 49 2.2(3/3) Same as O (wet weight) (0.43-3.2) River Mile -- 31.0 (0.62-3.0) High Location n Cs-137 0.01 0.039(1/8) BVPS Discharge No. 02A 0.039(1/2) LLD 0 g River Mlle -- 35.0 .oo Others Table V.A.4 LLD N H Nominal tower Limit of Detection (LLD) N Mean and range based upon detectable measurements only, Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Statio e tn (Appendix B) 4 ~

ENVIRONtf NTAL RADIOLOGICAL MONITORING Ps0 GRAM SUP9MRY M 4 Name of Facility Duquesne Light Company Docket No. 50- m location of facility beaver. Pennsylvania Reporting Period Annual 1983 (County, State) l Analysis and Lower l'imit Namber of Medium or Pathway Total Nudeer of All Indicator locations Location with Highest Quar. Mean Control locations Monroutine Sangiled of Analysis Detection

• • Mean (f)

Name nMean(f) **Mean (f) Reported y (Unit of Measurteent ) Performed (llD)

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

e Montgomery Das No. 49 8 Surf ace Water Gross (72) 2 9.l(1/72) Arco Polymers No. 49.1 9.l(1/12) LLD (pct /t) Alpha y u Gross (72) 1 5.3(71/72) BVPS Discharge No. 32A 6.7(12/12) 5.2(12/12) O M Bet a (1.2-15) River Mile -- 35.0 (3.9-11) (3.6-6.9) .xsto ts Gamma (72) Table V.A. 4 LLD M O c: Sr-89(24) 2 LLD oo z Sr-90(24) 0.5 LLD p trs p r' Co-60 (24)(a) 1 LLD HQ M :z: I (120-24100) River Mlle -- 35.0 (920-24100) (130-290) $H Tritium (24) 100 2900(20/24) BVPS Discharge No. 02A 11100(4/4) 190(4/4) 0 en r1 o Ok O g w

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

Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations es indicated in parentheses (f) Nonroutine reported measurements are defined in Regulatory Guide 4.8 (Deces6er 1975) and the Beaver Valley Power Station Technical Specifications g (Appendix B) g M U~

tn LNVIRui4 d ral At RAD!ul0LICAL HitlTORING PRt4RAll $lllHARY g H Name of f acility agguessee Light Company Docket No. 50-334 g* Location of f acility Beaver Penns Ivania Reporting Period Annual 1983 , 4 7 County, GtTJ 1 Analysis and lower Lisit Number of Medium or Pathway Total Number of All Ira 28catus tccat taas Location with ligi hest Quar. Mean Control locations Monroutine Sampled of Analysis Detection

• Hean [t ) --

N ahm. ~

• • fican(f)
  • Mean (f)

Reported ~ JunitofMeasurement) Performed {ttD)

• • Range

_ _ Distance and Directions * %,.gc

• • Rang Measurements ***

G oo Drinking Water I-131 (103) 0.2 0.34(3/103) Midland Pa. No. 04 0.34(3/51) -- G (pCi/t) (0.23-0.48) River Mile -- 36.3 (0.23-0.48) g .O Gross (24) 0.6 LLD C Alpha Gross (24) 1 4.l(?4/z4) Midland Pa. No. 4 4.5(12/12) -- 0 E t3 Beta (1.4-9.0) River Hile -- 30.3 (1.1-9.0) Q O c: Gamaa (103) Table V.A. 4 LID py oo 2 Sr-69(8) 1.5 tid p tn > t* Sr-90 (8) 0.5 LID t-4 g m Co-60(8)(a) I tlD Nk fritium (8) 100 200(f,/8) Midland Pa. No. 04 220(2/4)- 0 O (100-390) River Mile -- 36.3 (170-270) @i$ . a w ? ? ? (a) Co-60 analyzed by high sensitivity method. H Nominal Lower Limit of Detection (LLD) g Mean and range based upoa detectable measurements only. fraction of detectable measurements at specified locations is indicated in parentheses (f) ta Nonroutine reported measurements are defined in Regulatory Guide 4.8 (Decendier 1975) and the Beaver Valley Power Station Technical Specifications en (Appendia B) 5* 'N

_m [NVIRONMENTAL RNllOLOGICAL HCll0NING PRELRAM SUH4ARY M' .4 + Nme of f acility Duquesne Ligt1 Company Docket (40 50-334 .oz tocation of f acility Beaver,. Pennsylvania Reporting Period _ Annual 1983 (County,$t at e). 4 t Analysis and Lower Lielt Nimber of Medium or Pathway Total Nmber of. All Indicator tocations location with liic t.est Quar. Mean Control Locations Nonroutine S apled of Analysis Detection 7

• Mean (f)

Name

• • Mean (f) M an (f)

Reportel 5 (Unit of Measurement) Performed (LLD)

• • Range Distance and Directions ** Range

' ** Range Measurements *** 08 9 Georgetown, Pa. No.15 Ground Water Gross (16) 2 LLD (pC1/ liter) Alpha 3 5W Gross (16) 1 3.0(16/16) ilookstown Pa. No. 14 4.3(4/4) 2.4(4/4) 0 Bet a (1.0-5.8) 3 miles -- W5W (3.4-S.8) (1.4-3.6) ggg Gamma (16) Table V.A.4 LLD fO ec Tritium (16) 90 170(13/16) Shippingport Pa fio.11 190(4/4) 140(4/4) 0 00 m O M (90-260) 0.8 mile -- IJ (110-260) (90-190) m W C* 8 m hd N nn O O l E6 - P, $ ~- i r", H@ Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in pare Nunroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) askt the Beaver Valley Power Station Tectenical Specific 4 (Appendix B) ta

SECTION V - A DUQUESNE LIGHT COMPANY 1983 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 fo rmat 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 data 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.Ae3 1983 Annual Radiological EnvironmIntel Rsport (Page 1 of 4) TABLE V. A.3 (Page 1 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

same of rac.111ty shiseimt or: Ateste ?-ver Seseien Oceket :ro. Noe Aesti:sbie Name of Factisty 3eaver 7a nev ?:ver status Oceket No. 50-32 Locacian of Tacility 3eaver. ?eensrivania Reporti:s 7eri d C" 19*4 - 19?$ (Caunty statej _ PRE-0FERA*IC'uL PRCCRAM SIM8ARY (COM5t? C 1974 - 1973) !$sdhms or Fathway Lower Limit Sempied Analysis and Total Neber of All Indicator Locatione (Unit of % asurosame) of Analvsts Performed Oateetica LI3 Mean. If) Ranee 3/ Surfaae 'Jeter Gross Alpha (40) 0.3 0.75 40 0.6 - 1.1 pC1/1 Gross Beta (1:0) 0.6 4.4

• /120 2.5 - 11.4 Gemma (1) 10 - 60

< t.:3 0/ :1 130 - 500 Triti m (1:1) 100 300 1 Sr-49 (0) Sr-90 (0) C-16 (0) DrinJsing Water I-131 (0) /0 0.4 - 0.8 Gross Alpha (30) 03 0.6 3 D8 *08 2.3 - 6.4 / Groes Beta (208) 0.6 3.8 Gamma (0) I /211 130 - 1000 Tritium (211) 100 310 C-14 (0) ~ Sr-49 (0) l Sr-90 (0) Crom d unter Grose Alpha (19) 0.3 < 1:3 I3/ I 73 *I 1.3 - 3.0 Grose 3 eta (76) 0.6

• 9 l

I Tritium (31) 100 440 /81 30 - 500 Gemma (1) 10 - 60 < L:3 Air Ferticulates Cross Alpha (188) 0.001 0.003 35/188 0.002 - 0.Cc4 and Gaseous 927/927 0.02 - O.

G1/M Gross Beta (927) 0.006 0.07 Sr-89 (0)

Sr-90 (0)

-13 1 (816) 0.04 0.08

/S15 0.07 - 0.08 i l Oames (197) r I r2-95 0.005 0.04

• • • /197 0.01 - 3.15 30/197 0.0: - 0.cr au-10s 0.010 0.04 3

Cs=141 0.010 0.0: /197 0.01 - 0.0, 04-144 0.010 0.02 /197 0.01 - 0.04 Others < L:3

l SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1983 Annual Radiological Environmental Raport (Page 2 of 4) i 1 TABLE V. A.3 (Page 2 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

1 Name of Tacility Shieeter ort At _ic Pever Statien Docket No. Not Aeolicable Name of Taca. lacy 3eaver V411ev Power station ::ccket No. 30 !acation of Tacility Beaver. Pennsvivenia Reporting Period CT 1974 - 1975 (County, scate) FREM FEIATIONAL PROCEAM St29 FAIT (COMBI 3ED 1974 - 1975) i Mediin or Pattuny ! aver Limit Sampled Analysis and Total Number of All Tdfemeer Iacations (Unit of Measurements of Analysis Performed Detection t.LD h. (f) Kinnae Seil Gross Alpha (0) PC1/3 (dry) (Temp 1ste semples) Grose Beta (M) 1 22 g/ 4 14 - 32 6 1 Sr-49 (M) 0.25 0.4 /M Sr-90 (M) 0.05 0.3 a '8/64 0.1 - 1.3 U-234,233,238 (0) Games (M) 63 Er-40 1.5 13 /M 5 - 24 Co-137 0.1 1.3 36/M 0.1 - 6,8 I/M 0.2 - 3 co-144 0.3 1.1 U Zrsh-95 0.05 0.3 /4 0.1 - 2 0) Em=106 0.3 1.1 3/64 0.5 - 2 Others < I.ID I Soil Gross Alpha (0) PC1/g (dry) (Core Seeples) Grose Beta (8) 1 21 g/8 16 - 28 Se-49 (8) 0.25 < LIJ 3 Sr-90 (8) 0.05 0.2 /8 0.08 - c. Genes (8) 8/ E-40 1.5 13 8 7 - 20 7/ C.-137 0.1 1.2 8 0.2 - :. ' 1 Co-60 0.1 0.2 /8 ( Others < IID l 1 I l 1 -

i SECTION V - A DUQUESNE LIGHT COMPANY TABLE W.A.3 1983 Annual Radiological Environmental Report (Page 3,of 4) TABLE V. A.3 (Page 3 of 4) ENVIRON}! ENTAL RADIOLOGICAL MONITORING PROGRAM SUSDLARY 3eme of Tacility !Mes t-eser? Ae-nie ?wer teme* ~a "ocket No. W e Aestia nia Name of Facility Seaver Va.11ev Fever Statics Cochet 50. 50-33* fe artas of Facility leaver. Pennevivenia Reportir.g Level CT 1971 - 1975 (County. state) Ft2-OFEIATICE4L FROGRAM $CIMART(COMBI llRD 1374 - 1973) Medium er PatJmay lauer 11mit Sampled Analysis and Total smeber of All ?=dirator locations ean. (f) Ranee Mait of weesurement) of Analvois Perferned tee.eeto.i t13 w Sediasata Cross Alpha (0) pC1/3 (dry) 33.f Cross Seca (33) 1 13 33 3 - 30 Sr-90 (0) U-234.233. 238 (0) 33/ 33 2 - 30 Cams (33) 13 33 E-40 1.5 13 /33 2 - 30 21/33 0.1 - 0.6 Ca-137 0.1 0.4 U

rsb-93 0.05 0.8

/33 0.2 - 3.2 Co-144 0.3 0.3 3/33 0.4 - 0.7 OI 3/33 1.3 - 1.5 to-104 0.3 1.3 others e 12.3 I Foodstuff Gamma (8) PC1/s (dry) 4/6 10 - 33 l E-40 1 33 1 Ca-137 0.1 0.2 /8 1 Zrsb-93 0.05 0.2 /8 0) En-104 0.3 0.3 /8 Others e 113 30 Feedecuff Crose 3 eta (80) 0.03 19 /80 3 - 30 l PC1/g (dry) 33/81 0.04 - 0.93 l St-49 (81) 0.023 0.2 II/ 81 0.02 - 0.31 3r-90 (51) 0.C03 0.4 l Camma (SI) II E-40 1 19 /81 3 - 44 6/1 0.2 - 1.6 Cs-137 0.1 0.3 3 3 I co-144 0.3 1.3 /81 0.9 - 2.6 rNb-93 0.03 0.5 /t1 0.2 - 1.3 Ru-106 0.3 1.4 /31 0.6 - 2.3 CtherJ < '.*3 t t l -_

SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1983 Annunl Radiological Environmtntal Report (Page 4 of 4) TABLE V.A.3 (Page 4 of 4) ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Tacility Shitoimevert Atomic Power Station Ocekat No. Not Aeolicable Name of Tacility 3eaver vallev Pever Station Ocekst No. 50-3 3 t. locatics of Tacility !aaver, Pennsvivania Reporting Level Cy 1974 - 1975 (County, Stata) FRZ-OFEIATIONAL PROC 2AM SQGfA2r (COMBINED 1974 - 1975) t l Mediam or Fathuay Immer Limit Samplad Analysis and Total N eber of All Indicator tocations l (Unit of F-- c) of Analysis Performed Detectica TJ.D Mesa. (f) Raate Milk I-131 (91) 0.25 0.6 '/91 0.3 - 0.3 PCill 4/134 6 - 11 i Sr-89 (134) 5 7 U2 $r-90 (134) 1 5.3 /134,1.5 - 12.0 Gemme (134) II Co-137 10 13 /134 11 - 16

• Others e IJ.D External Radistica y

.!hathly (399) 0.3 mR

• 0.20 II/599 0.08 - 0.51 ma/ day 195 y - Quarterly (195) 0.5 mE
• 0.20

/195 0.11 - 0.38 '8 y - Ananal (48) 0.3 mR* 0.19 /48 0.11 - 0.30 U/17 1.0 - 3.2 Fish Grose Beta (17) 0.01 1.9 PC1/5 (wet) g7/17 0.02 - 0.50 I Sr-90 (17) 0.005 0.14 Games (17) l 17/17 1.0 - 3., E-40 0.3 2.4 other e LLD l [ I ILD in units of MR - Lower and of useful integrated exposure detectability range for a l passive radiation detector (TLD). One outlier not included is maan. Gater taken from dried-up spring with high sediment and potassium content. Not considered typical groundvatar sample.) May include Ru-1C6 Zu-103 Be-7. _n_

l MMoHHO:a

• H >> t g s*

3 a 8Dg b n* aa gDC$ $gOg$$ $hN0 SDF g3N ) tew h 5 3 3 6 3 7 5 4 3 3 3 2 2 3 5 3 4 6 6 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 6 0 s g 0 i/ Fi 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Cp ( ) t y nt r eid mo 3 5 2 2 3 2 4 3 3 2 2 2 1 1 2 3 2 2 3 3 iSg 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 3 0 d / e4i 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S Cp ( YR s T n E o M i t O a R c T i f C ) i E ny c Y P or e N S id p t S A ag 0

• 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 P

A tk 5

• 0 3 3 6 3 7 5 4 3 3 3 2 2 3 5 2 4 6 0 0 6 l

f M e/ 1 2 6 a t0 4 M gi c eC i A Vp n ' C A. G ( h T ce H V R T G O I E F n L L o i B t E A a N T s t S S D E L r U L s e Q e) w g o U L aa P D A l/ C ui 5 6 6 6 6 6 y cC e I i p 0 0 0 0 0 1 0 1 2 2 5 3 2 2 2 0 0 0 6 2 5 6 I l P t 2 2 1 l Y g a a~ V T P0 1 r r( e i v A a . e ) B b a_ n l i r d o e t ,n csi aef rl e pd tnm ) oas r C si e t rt Cl n Ll o l ei l t l 0 0 0 3 3 6 3 8 5 3 0 S 4 4 4 4 6 4 0 6 0 0 o Dai ia/ 3 6 4 3 1 3 6 t ( t MWi nc C sie p i t ( sde yeD l t acf neo at el fde o v ye et l mi 0 i vr 5 4 ti e e 9 M 1 t w 7 1 4 6 8 t co d 3 6 0 2 4 h3 a 4 4 2 2 AAl i i 4 8 9 0 5 b 0 0 l 1 3 3 3 l 7 0 S 5 5 5 t 6 N 1 1 I 3 1 3 1 t 1 t 1 1 2 2 1 - - - / - - - - c 4 - - - - - - / - - - 1 e - s s s a e c a h E "u u e - r a o e o n r u u g - r C C C B C C R 1 N B K C H C r C 2 Z R R A T I 1 t 'U8

7 ~~~ r \\?'\\ , ym SECTf0N'V --B DUQUESNE LIGIIT COMPANY 1983 Annual Radiological Environmental Report le ~ V. ENVIRON'! ENTAL 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 fron the -Southwest in summer and from the Northwest in the' winter. 2. Air Samuling Progra'n. and 'Analvtical Technioues 'a. Program The air iss dampled for gaseous radiciodine and rayloactive particulates atteach of ten (10) off-site air sampling, stations. The, locations of these stations are listed la Table V A.1 and shown on a map in Figure 5.B.l. Samples are collected at each of these stations by i continuously drawing about one cubic footf per minute of atnosphere air through a glass fiber filter and thiough a charcoal cartridge. The former collects cirborne particulates; the latter 4 is for ra'diciodine sampling. Samples are collected for analysis en a. weekly basis. The charcoal' is used in the weekly anslysis of l airbop.e I-131. The filteFs are analyzed each week l for gross beta, thenicompoyited by station for monthly analysis by gamme. >Rectrometry. They are i i further-composited in a quart,erly 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, aftericollection prior to counting m fc; beta in a l'ow background counting system. ~ s s, i b.x; Procedures' I ^ j Gross Beta analysis is performed by ple;cing the s filter paper from the weekly air sample in a 2" x - 1/ 4 planchet and counting it in a low background, s s gas' flow proportional counter. N, 'M ( N w. I 3 i \\ ( -e "M s

=. SECTf0N V - B DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report i b. Procedures (continued) 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 germanium (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. 4 l. om.. d 4, r,m1 y.,

e.. +

w> w m- .,<m. ,.-.---g

SECTION V - B FIGURE 5.B.1 DUQUESNE LIGHT CO}TANY 1983 Annual Ridiological Environmental Report FIGURE 5.B.1 ENVIRONMENTAI. W0teTORING LDCATIONS-AIR 3;iRI'li LOCATICf6 N um amm AIR SAIR!'E STATMS SIL.lE l0RE13 f i B ftYER'S lh!RY FM 27 Pauran's IhrRY FW , Never- ' p,- ^ 28 SHER N 'S DAIRY j\\ ~ 2c3 EEA M M b !TE [* A ,, L ' "* i i 30 SHIPP!NGPCRT30R0 l a 32 Minc $US h ~ " "~~ l ,s i a, ) e-46 IfCUSTRY 2$ @y s 47 Dsf Lim Gro I j.. (- N k!RTCN, %ST VIRGIN!A 9 ~V ,e ' I' 51 AuGUIPPA O N,, b ) h I e ,~' ' '7~j m i n ..:...""*"sg .,.f,' s., ,w s ,5y Q- .f s30 /fl'.g*. 6

j'f'

__..\\ m m~. i s s -t (puer,e .T ( {: 7E l

• h>,4 ^4

'"~ i @hA.-Q 7 d if W= * / r Z .s: e t 3 /_ _ t[ # -A s l y l m-s. d N N ';;x. 'r / gw v.. u.: c -- ( _ _ f \\ )% '~ w m_------------.,,s

SECTION V - B DUQUESNE LIGHT C0?!PANY 1983 Annual Radiological Environmental Report V. ENVIRON!! ENTAL ?!0NITORING b. Procedures (continued) Strontium-89 and Strontium-90 activities are determined in quarterly composited air particulate filters. Stable strontium carrier is added to the sample and it t-leached in nitric acid to bring deposits into solution. The mixture is then filtered. Half of the filtrate is taken for strontium analysis and is reduced in volume by evaporation. Strontium is precipitated as Sr(NO ) using fuming (90%) nitric acid. An iron (ferr c hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounced on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrC0 fr m the sample after yttrium 3 separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting. 3. Results and Conclusions A summary of data is presented in Table V.A.2. a. Airborne Radioactive Particulates l "A total of five hundred twenty (520) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years. Figure S.B.2 illustrates the average concentration of gross beta in air particulates. f L i. (

= AVERAGE CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES -- 1983 0 8 2 l .DS a \\ Al' x /\\ A i A /@ t\\ v v / gs n v ~ n y

d>

Eg a r a. g 8gg . mas i: il? E n .mai JAN FEB HAR APR MAY JUN JUL AUG SEP OCT NOV DEC

l 1983 P

!"u

SECTION V - B DUQUESNE LIGifT COMPANY 1983 Annual Radiological Environmental Report 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 Power Station did not contribute to any increase in air particulate radioactivity during CY 1983. 4 b. Radiciodine A total of five hundred and twenty (520) weekij charcoal filter samples were analyzed for I-131. 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 radiolodine during CY 1983..

,m -r A M. SECTION V - C DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report V. . ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was not required in 1983.) 1. Characterization of Stream Sediments The stream sediments consist largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material. 2. Sampling-Program and Analytical Techniques a. Program River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and 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. Bottom sediments are analyzed for gross alpha and beta activity, strontium, uranium, and the gamma-emmitting radionuclides. b. Analytical Procedures 1 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. j Gamma analysis of sediment or soil is performed in i a 100 ml plastic bottle which is counted by a gamma j spectrometer. l i l, 1 ~ r -,.... ~,.,,

SECTION V - C FIGURE 5.C.1 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report SEDII'ENTS AND SOTLS FIGURE 5.C.1 ENVIRONMENTA1. WONITORING l.CCATIONS- $H::EU.*E $3Tl[$ g $g N uwneus amn l b SC L!T EIPfrS I -,b, 1 I gy n _1 2A toestreara SVPS outfall l f 49 Cpstre m Side of.L v - i A. s kE,,L... l 3 Vicanity SAPS Dischage l b ,'g. Ce %s l l i 50 Cpstrum Side of New CNM De ,,,,1, h,e,M ver-I v m,.e 3,. m. PCb?" DCA721 E .'leyer's far-i l .[,, 22 South of BWS Site j-(, 27 Snatcm's Dair/ g .l A Je er/ry 29A Nichol's Dairf }N ',/ e 30 shippin; port, PA O 32 Mi11arsi I m 46 Lthistry, PA I g 4 %, t 47 E. Lbv.rinol, Of a '\\' / 48 Weartcm, W.G. 5

a. <

51 Aliquippa, PA Olsew#e

• s;;, ~ ;

c----- . 1 Sik, 's i 4 S& O@ - ~ ~. / m /

,.e..m~i/.1 m er e

,( OMem9 3 / _ y ') '\\&' .s e.,, / t o l hl i. 6'\\\\ 7 j== @A%/ i /r*4* * * *, s I 5 l \\. tc/ ^W

• 4 &

y; havan eauan g ,.m s. \\ \\ i We/ l . s. ,O* Jsete C/ Mons \\ = ~* f.. - m -._.

SECTION V - C .DUQUESNE LIGHT COMPANT 1983 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 HN0. A stable of recovery. carrier is added for determination 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 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 spe-trometry after leaching and isolation of the uranium by an ion exchange chromatography plus mercury cathode electrolysis, then electroplated onto a planchet. 3. Results and Conclusions a. Results The results of sediment 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. I l

SECTION V - C DUQUESNE LIGIIT COMPANY 1983 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING 3. Results and Conclusions (continued) a. Results (continued) Uranium isotopic analyses were performed by alpha 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 trace amounts of Co-60 which have been detected since 1977, the sediment analyses do not indicate any ' radioactivity attributable to Beaver Valley Power Station and Shippingport Atomic Power Station liquid discharge. 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. l i i l i i ! l

SECTION V - D DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report - V. ENVIRONMENTAL MONITORING D. Monitoring of Feederops and Foodcrops 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 Analytical Techniones a. Program Representative samples of cattle feed are collected monthly from the nearest dairy (Searight). See Figure 5.D.1. Each sample is analyzed by gamma spectrometry..The monthly samples are composited i into a quarterly sample which is analyzed for Sr-l 90. Foodcrops (vegetables) were collected at garden locations during the summer of 1983. Leafy vegetables, i.e., cabbage, spinach, and lettuce were obtained from Shippingport, Georgetown,

Industry, PA, and from Weirton, WV.

All samples i were analyzed for gamma emitters (including I-131 by gamma spectrometry). t 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 simil c to that described in V.C.2. l j ! 4 --,-,y,# y -.,c-- -r---3 7 .--.--,-v

o FIGURE 5.n.1 x y ffoM Yq u+tE*R Y.D4+1 I ~ ~l e I- -- -- -- -] (,b Ca,.da,, ? l OHlo s lhDLAMD g to cp@QEonqcrowat b,o __ _ ( i O airpineraar \\ st'Er at> col. R ~ 4-g. o 5b R g ./ g \\ l Ga a ns l f it ni = ,wesr! O psuusytvana @ s ~'y ?C ~tj ~8 ovbegiprA ,( vi m K }?EACTOR $o l N 8'". 4 I6 \\ (~ # 0$4 Nf a OW 1.EG Et4D : L 8 l (V) - Vegetable Garden h-Searight'sDairyFarm Feede rop Aedero@p ~y I c ENVIRONMEN'TAL MONITORING PROGRAM FEEDCROP AND FOODCROP LOCATIONS u FIGUE 5.D.1 e' ~ ~

h' SECTION V - D DUQUESNE LIGilT CO.'!PANY ( 1983-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. 9 _ _ _ _ _ _ _ -)

i SECTION V - E-DUQUESNE LIGHT COMPANY 1983 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 1 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. j 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 l highest potential milk pathway for radioiodine l 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 a 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. l 61 Allison 33 Cows 3.2 miles-west /sw. Jan.-June,Dec. 69 Collins 9 Goats, 1 Cow

• 3.6 miles-southeast Feb. - Dec.

l t

l l r SECTION V - E DUQUESNE LIGHT COMPANY l 1983 Annual Radiological Environmental Report I Number I of Milch Distance and Direction Collection Site Dairy . Animals From Site Period ) 98 Foxall l (Hammond) 2 Goats

• 2.9 miles-east July - Nov.

100 Doughty 1 Cow

• 2.8 miles-west /nw.

April - Dec.

• Milk Usage - Home Only.

f SECTION V - E DUQUESNE LIGHT COMPANY FIGURE 5.E.1 1983 Annual Radiological Environmental Report FIGURE 5.E.1 ENVIRONMENTAt. MONITORING LDCATIONS-Cow and Goat Survey i N imaa : anwrr MAM M .y Q* % j e ~ ,,J r-. (~"- ~. o -~lQt}.j i "*b*f. {

• • 4h

~

• =x bg.

l 1 \\,- s. ,_1..-- -- p,' K ,i N \\ e( t / O '~ s,. *.y, med.pi/ /H f - -l l a,,. N ic ,c s l /bs s Odd,% l , /.. [ 's",~- 's I, / -y., '. N ' Qls4 ,g O s s ~.

s. -

_,1..{ 's N, o /.% c.' q x t %*/ 'N a Y N./. l \\ i gg \\ 4. N. A l-sm g' ~ j' /, 'Y l / ....... a .- lsy/ .s .o-t h. 7 %c,. s .h. T *(. o 3 'a N. g *;. --4.. 6 y " **vt \\1 .Y c' _c,lC- " * 'r mw W' V**' fI:s{-{,;_a., %,C/. r T bgk.t"& d . ',\\., . [.; ; ',1 .I I t .t T E. I i u N,e a I, l.-] /; Mj ,p-s.g,4 y z.,N ,L... ] . ;g _ _v w,s-i ,o ['. ,,e"A.a'jo,/ /4 t 'j-g.e' - t . 4,. l

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SECTION V - E FIGURE 5.E.2 DUQUESNE LIGHT CO R ANY 1983 Annum 1 Radiological Environm?.ntal Report FIGURE 5.E.2 ENVIRONMENTAL. MONITORING LOCATIONS- 'TJ' N um owrY seawn cadre i 1 J MILK i Q,, ~ Site Location

• h 'k

/ W: 7. we 25 Searight -( /7 I h ', 27 Brunton

p. _,

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• ~ -.

~. - f' SECTION V - E DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report l-V. ENVIRONMENTAL MONITORING E. Monitoring of Local. cow's Milk (continued) a. Program (continued) J 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 f 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 j 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 3 samples are prepared by addition of Trichloracetic i Acid (TCA) to produce a curd which is removed by-i 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 1983. All I-131 activities in milk were below the minimum detectable level f (0.3 pCi/1). A total of one hundred and twenty-three (123) samples were analyzed by gamma spectrometry and for strontium. i l 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 1983. 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 in CY 1983. l t,

II SECTION V - F DUQUESNE' LIGHT COMPANY o - 1983 Annual Radiological Environmental Report -V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring -1. Description of Regional Background Radiation Levels and Sources k. 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, 4 exposure rates ranged'from 6 to 12 pR/hr. Results for 1983 indicated that background radiation continued in this range. 2. Locations & Analytical Procedures i. Ambient external radiation levels at the site were measured using thermoluminescent dosimeters (TLDs). .There were three (3) types used in the Duquesne Light l . Company Radiological Environmental Monitoring Program. They are eticium sulphate dysprosium, CaSO4 (Dy) in teflon matrix, lithium fluoride (LIF), and thulium activated calcium sulfate (CaSO :Tm). 4 The lithium fluoride TLDs were posted and analyzed by a laboratory of the Department of Energy (DOE) as an l independent check of environmental radioactivity levels. The CaSO :Tm TLDs were used as a back-up and as a QC l 4 program. In 1983 there were a total of forty-four (44) i 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.1.

i

SECTION V - F FIGURE 5.F.1 DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report A NORTHwtST QUADRANT W Breven Vau.sv F%cn Stanos .e is N ..e., 9 m..,, I

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SECTION V - F FIGURE 5.F.2 DUQUESNE LIGHT CODA 1:Y 1983 Annual Radiological Environmental Report rammar samun.t w~ - ~ Y 9 N s..ver i it 2 i u.i !00:';li!;.':"?' i 't l" 'UJ0"*" 92* I f 3

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.\\ l y j gN s i. i,.... ro. se ? paaeoen manLateel BLis. '. l t 3? Stuaton's Oesty =lecleary Rea.d ~^ B at. 's and t. L 51 0 't i 9 03 Sauta.n P.rt Dadece tdo Scfteel 11 9 $2 Hanovet # A 64 4 941 91d9 4 4 / ' 8 / ~ ~. W TH W T @ QRANT s' 9 6- 'u tus en.a.cv pc.,v.= 3.mtio.4 SECTION V - F FIGURE 5.F.4 DUQUESNE LIGHT COMPAW 1983 Annual Radiological Environmental Report k / \\ \\ l* ' '} ' ? / \\ x/ " ' ~ ' ~ ~7 .,A> r.- ~ i 'N: 31 o* ~. ?s *'$ ~' / ~ h, s y ~ Sy"~.. o ~ ~ g-(gG \\ \\ \\ \\ mpeu-= I f,, / a / f e W ,1 N i !\\ ) I[ \\g Nh)' >g i x f / \\ y / g \\ } m s 3 ~ / o I \\ \\ b f / -~ I i l \\ f L f \\ ik 4 i l [ 5 / . s,- g........ k !,I/ \\ \\ \\ g -[-., '\\ ; / 1 l il l a,s .....a..a.. o.i 11 / ..~. s .i "=g". .2 a.nover muntesp.i.itg. Jj \\[ b" I 's Ei 'c5.U'Ed"*' I C' w-tl / 40 ON%' it is noe n stown s'

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SECTION V - F DUQUESNE LIGHT COMPANY 1983 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 7 accumulated from the anneal date to the date of posting is accounted for by utilizing background readings from five (5) TLD chips in conjunction with an average background correction factor. The calibration of the TLD reader is performed within 24 hours 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 Data obtained with the contractor TLD (CaSO :Dy in 4 teflon) during 1983 are summarized in Table V.A.2, and the quality control TLD results are listed in Table III.1. The annual exposure rate of all off-site TLD's averaged 0.17 mR/ day in 1983. As in previous years, there was some variation cmong locations and seasons as would be expected. I u SECTION V - F DUQUESNE LIGHT COMPAST 1983 Annual Radiological Environmental Report 3. Results and Conclusions (continued) L In 1983, ionizing radiation dose determinations averaged approximately 62 mR for the year..This is comparable to previous years. There was no evidence of anomalies that could be attributed to the operation of 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. Lessons learned from the Three Mile Island incident indicated the need for more radiation monitors in all sectors surrounding the-plant. Sixteen (16) Reuter-Stokes Pressurized Ion Chamber environmental radiation monitors were installed in 1982, one in each of the 16 sectors. Installation of the central processing controller into the Emergency Response Facility was expected to be completed in 1983 but is now expected to be completed in 1984 which will permit the monitors to be read out at a central location. Engineering is also in progress te ' 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 which were scheduled to be operational by December 1983 are now expected to be operational by the end of the. fourth BVPS

1. 1 refueling outage.

2 l l 1 i f l ' i 4

SECTION V - G DUQUESNE LIGHT COMPANY 1980 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING G. Monitoring of Fish 1. Description L. Fish collected near the site are generally scrap fish. During 1983, fish collected for the radiological monitoring program included carp, catfish, crappie bass, gizzard shad and bass. 1 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 4 analyzed by gamma spectrometry. Fish sampling locations are shown in Figure 5.G.I. b. Procedure A sample is prepared in a standard cared 300 ml I 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. Five (5) fish were caught in April. Seven (7) more samples were caught in October. 2 Except for naturally occurring K-40, the only gamma 2 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 i previous weapons testing programs. This indicates that l. and the Beaver Valley Power Station has not resulted in the operation cf the Shippingport Atomic Power Station i radioactivity in fish in the Ohio River. en .y On [f FIGIEE 5.G.1 y

C t.

Monr90nrRY Dan k t eg, L. _ _ _ o h h

ygg t..

$ a) 0 } h .Baco 0.c \\ 0 s~~r \\ g y =.m -,- \\ '^ l t / ta 5 4 ,f go ~ a i / WM' Gj~ m ,V/Rqty!A N /, PENh/SYLVAhl!A s WG ( Y.y N Re^cron y, O ,9/ Y2 i <: o s g' R 36 / N ? C') Hooxsrown FISH L E s1re k8 LEGEtID no. weavion 2A ricar neaver valley Power Stat. ion ut scharge Fish Sampling Locations y m s 49 Upstreane - tiontgomery Dam I / c: c: EINIRONMENTAL MONITORING PROGRAM FISil SAMPLIt3G LOCATIONS I l L P j e f

SECTION V - H DUQUESNE LIGHT COMPANY 1983 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 water 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 plaat 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 t (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 -101-

~..

t P SECTION V - H. LUQUESNE LIGHT CnMPA.W 1983 Annual Radiological Environmental Report locations: Upstream of Montgomery Dam (River Mile 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 s ~ collected on a weekly basis. The weekly grab l; ' ' ; samples and automatic water samples are conposited into monthly samples from each. location. In ' addition,.a quarterly composite sample is prepared for each sample point.- t ,The monthly composites are analyzed for gross culpha, 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). Lecations of's.tch sample point are shown in'ligure 5.H.l. N b. . Drinking Water (Public Supplies) i hobh ' Drinking' (tren:ed)\\ vater is collected at Midland (PA) and East, Liverpool (OH) Water Treating Plants. A.7 automacic saryle_r 'a t each location c,011edji 20-40 millillt'ers-eytry 20 minutes. These s intercitteat samples are 'then composited into a weekly % sm ' The weekly sample \\sfrom' each locacion h'.ple. s inalyzed by gamiia spectrometry. The .s weekly sampl3s tra.glso analyzed 'for r'adioiodine (I.331)/. V-9 rf Monthly composites of the weakly su:ples are analyzed for gross alpha, gross beta, cud by gamma spectrometry. Quarterly compos ti.es are cualyzed for H-3, Sr-89, Sr-90 and Co-60.J(high sens itivity). ~ 'tocations of each saiple' point are rhown in Figure .i. ;t. l. \\\\o 8 s;. -~ -. _, x s 5 \\ ? g --y s .. e d \\.. h k + k '\\ 102-s~, \\ 4 't I k g 2 u.

SECTZON V'- H DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report c. Ground Water ' Grab samples were collected each quarter from each of four (4) well locations (see Figure S.H.1) within four (4) miles of the site. These locations are: i 4 ^ One (1) well at Shippingport, PA i One (1) well at Meyer's Farm (Hookstown, PA) One (1) well iri Hookstown, PA 4 One (1) well in Georgetown, PA Each groundwater sample is analyzed for gross alpha, gross

beta, critium, and by gamma j

spectrometry. i I l-i I I l i -103-l r

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SECTION V - H DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING 2. Sampling and Analytical Techniques (continued) 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 planchet. The s ample is counted in a low background, gas flow proportional counter. Self-absorption corrections are made on the basis of sample weight. Gamma analysis is performed on water sample by loading one liter of sample into a one liter marinelli container and counting on a Ge(Li) gamma spectrometry system. ~ Strontium-89 and 90 are determined on water samples by a procedure similar to that described in V.C.2 except that the leaching step is eliminated. i Cobalt-60 is determined with a sensitivity of 1 4 pCi/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 j converting 2 al of the sample to hydrogen and counting the activity in a 1 liter low level gas counter which is operated in the proportional range in anti-coincidence mode.

3.~

Results and Conclusions i A summary of results of all analyses of water samples (surface, drinking, and ground) are provided by sample l type and. analysis in Table V.A.2. These are discussed below. a. Surface Water A total of seventy-two (72) samples were each analyzed for gross alpha, gross beta, and gamma activity. Twenty-four (24) quarterly composited L samples were analyzed for tritium (H-3) and radiostrontium (Sr-89 and Sr-90) as well as a high sensitivity analysis for Co-60. l -105- 't-h g mv -wm-by,r. - - ,,,n v-, ,-w -,,er-y y w r-- .-,e, --w. %e%s w. w- -m,,-w--rw=

SECTION V - H DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING 3. Results and Conclusions (continued) No Sr-90, Sr-89, Co-60, or gamma emitters were detected in surface water during CY 1983. All alpha and beta activities were within normal range. The tritium levels in Beaver Valley Power Station and Shippingport Atomic Power Station outfall were elevated above preoperational levels in 1983, but none of these data suggests detectable increases over preoperational levels downstream of the station. The tritium activity is consistent with station data of authorized radioactive discharges and were well within limits permitted by NRC and NR license. b. Drinking Water A total of twenty-four (24) samples were analyzed for gross alpha and gross beta. All results were within a normal range. A total of eight (8) samples were analyzed for tritium (H-3), radiostrontium (Sr-89 and Sr-90), and cobalt (Co-60). No Sr-89, Sr-90, or Co-60 were detected. The tritium data were within the preoperational range indicative of normal environmental levels. A total of another one-hundred and three (103) samples were analyzed by gamma spectrometry. No gamma emitting radionuclides were detected by these analyses. I l r l -106-

SECTZON V - H DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING 3. Results and Conclusions (continued) A total of one hundred and four (104) samples were l analyzed for radioiodine (I-131) using a highly sensitive technique. Trace levels of I-131 were measured in three (3) weekly samples collected at Midland. The results were slightly above the minimum detectable activity of 0.2 pCi/ liter. The positive results could not be attributed to station discharges. The results may be attributed to expected variability in the analyses results of very low levels of activity. 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 Shippingpert 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 and Shippingport Atomic 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, which was attributable to Beaver Valley Power Station, was l caly a small fraction (0.52%) of the concentration l (averaged over a year) permitted by the Federal l Regulations for water consumed by the public. The Ohio River further reduced this concentration prior to its potential use by members of the public, t -107- -= -

SECTION V - I DUQUESNE LIGHT COMPANY 1983 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 Power 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 samp12 analysis in accordance with the schedule set forth in Appendix B of the BVPS license, were used as the radionaclide 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, radioiodines, strontium, and tritium were included as source terms based on the' lower detectable limits of analysis (all sensitivities for analysis 't 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 i 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 Regulatory Guide 1.103. The airborne pathways evaluated were beta and gamma doses from nobla gas plumes inhalation, the " cow-milk child", and other ingestion pathwa,s. -108-i

} SECTION V - I DUQUESNE LIGHT COMPANY 1983 Annual Radiologi* cal Environme2 cal 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 individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is available, all other input to LADTAP are obtained from the Beaver Valley Power Station Environmental Statement or Regulatory Guide 1.109.

Pathways, which were evaluated, are drinking

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

2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases a. Liquid Pathway - Maximum Individual The doses which are calculated, based on the model presented above in V.I.1, are summarized and t 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.l. For these calculations, a hypothetical maximum individual (s) was located at Midland since this is the nearest location which significant exposure of a member of the public could potentially occur. I i i i -109-

.'R:diation Dore to Maximum Individual", :;rea/yr. Bcaver Valley Pow:r Strtien - Liquid Role m a CRITICAL USAGE Wil0LE PATilWAY GROUP FACTOR SKIN ORGAN THYROID BONE BODY Fish Consumption Adult 21.0 kg N/A 0.0604 0.00227 0.0197 0.0276 (Liver) M O Drinking Water" Infant 510 1 N/A 0.0558 0.0696 0.00197 0.0535 h (Liver) a Shoraline Activities Teen 67 hr 0.00062 0.00057 H E T0k'AL oo MREM 0.00062 0.0702 0.0696 0.0254 0.0613 CRITICAL (Teen) (Adult) * (Infant) (Child) (Adult) f INDIVIDUAL (Liver) g e E c'f! DOSE TO INDIVIDUALS DURING 1983 FROM NATURAL RADIATION EXPOSURE hh gm f d

• e Ambient Gamma Radiation:

69 gg Radionuclides in Body 18 Yo Global Fallout 4" N$ l o{ h TOTAL mrem

• 91

" Located at Midland Drinking Water Intake Child - Usage Factor 6.9 kg/yr. [ O

1. Adult - Usage Factor 730 1/yr.

d Pre-operational average ambient gamma radiation " National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of g Ionizing Radiation", BEIR Report, 1972. 4 s

SECTION V - I DUQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued) Actual Doses (mrem /yr.) - Calculated Using Site Effluents Appendix I

• Analysis Dose - Calculated Using 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 0.0613 2.78 5.0 0.01226 Teen 0.0341 0.712 5.0 0.00682 Child 0.0416 Not Reported 5.0 0.00832 Infant 0.0535 Not Reported 5.0 0.01070 ANY ORGAN Adult 0.0702 Not Reported 5.0 0.01404 (Liver) Teen 0.0551 Not Reported 5.0 0.01102 (Liver) Child 0.0676 Not Reported 5.0 0.01352 (Liver) Infant 0.0696 Not Reported 5.0 0.01392 (Thyroid) Maximum Total Body Dose - Capsule Summary mrem l. 1983 Calculated 0.0613 l Appendix I Estimated 2.78 Final Environmental Statement 0.112 Thyroid Dose - (Largest Expected Organ Dose) 1983 Calculated 0.0702 Final Environmental Statement 0.96 l 10 CFR 50 Appendix I l -111-l

SECTION V - I DUQUESNE' LIGHT COMPANY 1983 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 1983 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 398.0 H3 392 mrem Cs134 3.03 mrem Cs137 1.81 mrem THYROID 437.0 H 392 mrem I 31 42.9 mrem 3. Airborne Pathway - (Beaver Valley Power Station) The doses to the public for Beaver Valley Power Station airborne radioactive effluents during 1983 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 Voiley 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 0.0002?; of the annual background. l The calculated doses to the public from the oper3 tion of Beaver Valley Power Station Unit No. 1 cre balow 10CFR50, Appendix I design objectives, and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no meaningful risk to the public. -112-

TABLE V.I.2 Results of Calculated Radiation Dose to Man (1983) Beaver Valley Power Station - Airborne Radioactivity p O Ez APPENDIX I* 50-MILE MAXIMUM EXPSOURE DESIGN OBJECTIVE PERCENT OF POPULATION DOSE ORGAN INDIVIDUAL, mrem mrem APPENDIX I man rem G R TOTAL BODY 0.0428 5 0.86% 0.158

s 5

SKIN 0.108 15 0.72% 0.492 "E ES LUNG 0.0416 0.171 SE C SN TilYROID 2.88 4.24 Se $5 bEi 99

ii5 k

e

• 10CFR50, Appendix I Et S

F ? 3 s b N Y* l

SECTION V - I DUQUESNE LIGHT COMPANY-1983 Annual Radiological Ervironmental Report V. ENVIRONMENTAL MONITORING 5. Dose Pathways to Man - Shippingport Atomic Power Station The radiation doses to man as a result of operations at the Shippingport Atomic Power Station during 1983 were calculated for gaseous effluent pathways and liquid effluent pathways. Effluent monitoring at the Shippingport Station during 1983 has shown that the radioactivity releases were f substantially below the Federal radioactivity concentration guides. The environmental monitoring program has demonstrated that the radiation exposure to the general public form the Shippingport Station operations was too low to measure and could only be estimated with the calculational model described below using measured or estimated effluent radioactivity data. a. Calcualtional 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 (Regulator Guide 1.109) established to maintain, compliance with 10CFR50 Appendix I. The air does pathways considered were inhalation, immersion in gaseous and suspended particulate activity, and the ingestion of food and milk produced in the Shippingport vicinity. It was conservatively assumed that food products consumed by the public were produced in the Shippingport area throughout CY 1983. The maximum potentially exposed individual for the air pathways was located i at the site boundary. It was constr*7atively assumed that the maximum individual resides continually at the site boundary. The maximum potentially exposed individual for liquid pathways was located at Midland, PA. The liquid dose pathways considered were drinking

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

l -114-l

SECTION V - Z DCQUESNE LIGHT COMPANY 1983 Annual Radiological Environmental Report 5. Dose Pathways to Man - Shippingport Atomic Power Station (continued) Modelit:q parameters and usage factors used in the pathway calculations were consistent with values recommented 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 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 with 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 perron-rem received by all individuals from typical background radiation. In conclusion, the radiation exposure received from the Shippingport Station during CY 1983 by any member of the general public is a very small fraction of the backgrcund radiation and has, therefore, no significant effect on the general public. t t -115- . ~

DISTRIBUTION LI' United States Nuclear Regulatory Commission (18 copies) Attn: Mr. Peter Tam, Project Manager Operating Reactors Branch No. 1 Divisica of Licensing c/o Document Control Desk Washington, DC 20555 United States Nuclear Regulatory Commission (2 copies) Office of Inspection and Enforcement Attn: Dr. Thomas E. Merley, Regional Administrator 631 Park Avenue King of Prussia, PA 19406 Mr. Nicholas DeBenedictis, Secretary Department of Environmental Resources Commonwealth of Pennsylvania 9th Floor, Fulton Building Third and Locust Streets Box 2063 Harrisburg, PA 17120 Mr. C. K. Gaddis, Manager Pittsburgh Nava? Reactors Office Post Office Box 109 Pittsburgh, PA 15122-0109 Admiral K. R. McKee Deputy Assistant Secretary for Naval Reacters 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 I l United States Departmant of Energy Technical Information Center Post Office Box 62 Oak Ridge, TN 37830 Mr. J. G. Yusko Department of Environmental Resources Bureau of Radiation Protection 121 South Highland Avenue Pittsburgh, PA 15206

F DISTRIBUTION LIST (continued) J.M. Arthur, Chairman of the Board and Chief Executive Officer One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 J. J. Carey Vice President - Nuclear Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 E. J. k'oolever Vice President, Nuclear Construction Division Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 F. A. Cavalier Project Manager, Beaver Valley Power Station Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 J. D. Sieber Manager, Nuclear Safety & Licensing Department 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. Pernick Manager of Environmental Affairs Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 C. E. Ewing i Manager, Quality Assurance Duquesne Light Company Beaver Valley Power Station P.O. Box 186 Shippingport, PA 15077

DISTRIBUTION LIST (continued) W. F. Wirth Director Radiological Safety Programs Duquesne Light Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077

P Bo Shippngport, PA 15077 6 JOHN J. CAREY (412) 643-5255 Vee Prescent-Nuclear Divison April 30, 1984 1983 Annual Environmental Report Radiological - Volume #2 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Dr. Thomas E. Murley, Regional Administrator Region I 631 Park Avenue King of Prussia, PA 19406

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334

Dear Mr. Murley:

Enclosed are two (2) copies of the 1983 Annual Environmental Report Radiological - Volume #2 for the Beaver Valley Power Station. Eighteen (18) copies have been provided to the Document Control Desk. The number of copies provided your office is in accordance with the distribution noted in Regulatory Guide 10.1. Very tr y yours, . Carey JJC/smf Enclosure l}}