ML19309F816
| ML19309F816 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/29/1980 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML19309F815 | List: |
| References | |
| NUDOCS 8005010357 | |
| Download: ML19309F816 (113) | |
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I I 1979 ANNUAL ENVIRONENTAL REPORT RADIOLOGICAL - VOLUME #2 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION I AND SHIPPINGPORT ATOMIC POWER STATION I
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DUQUENSE LIGHT COMPIRY 1979 Annual Radiological Environmental Report I ABSTRACT This report describes the Radiological Environmental Monitoring Program conducted during 1979 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1979.
The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1979. There were no radioactive liquid effluents released from the Shippingport Atomic l Power Station since radioactive liquids are processed and re-cycled I within the plant systems.
The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment.
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I DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report TABLE OF CONTENTS Page Abstract i
- 1. INTRODUCTION 1 A. Scope and Objectives of the Program 1 B. Description of the Shippingport and Beaver Valley Site 2 II. RESULTS & CONCLUSIONS- 6 III. ENVIRONMENTAL MONITORING CONSIDERATIONS 8 A. Environmental Quality Control Programs 8 B. Evaluation of the Quality Control Program Data 23 C. Standard Requirements and Limitations for Radiological and Other Effluents 23 D. Significant Changes and Reporting Levels 24 I IV. MONITORING EFFLUENTS--- 26 A. Monitoring of Liquid Effluents 26
- 1. Effluent Treatment, Sampling, and Analytical Procedures 32
- 2. Results 33 B.
I Monitoring of Airborne Effluents 34
- 1. Description of Airborne Effluent Sources 34
- 2. Airborne Effluent Treatment and Sampling 38
- 3. Analytical Procedures for Sampling Airborne Effluents 41
- 4. Results 44 C. Solid Waste Disposal 46 l 11 lI
DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report TABLE OF CONTENTS (Continued)
Page V. ENVIRONMENTAL MONITORING PROGRAM A. Environmental Radioactivity Monitoring Program 48
- 1. Program Description 48
- 2. Summary of Results 65
- 3. Quality Control Program 65 B. Air Monitoring 71
- 1. Characterization of Air and Meteorology 71
- 2. Air Sampling Program and Analytical Techniques 71
- 3. Results and Conclusions 73 C. Monitoring of Sediments and Soils 76
- 1. Characterization of Stream Sediments and Soil 76
- 2. Sampling Program and Analytical Techniques 76
- 3. Results and Conclusions 78 D. >bnitoring of Feederops and Fooderops 80
- 1. Characterization of Vegetation and Foodcrops 80
- 2. Sampling Program and Analytical Techniques 80
- 3. Results and Conclusions 82 E. Monitoring of Local Cow's Milk 83
- 1. Description - Milch Animal Locations 83
- 2. Sampling Program and Analytical Techniques 83
- 3. Results and Conclusions 86 111 l
1 I DUQUEliSE LIGHT COMPANY 1979 Annual Radiological Environmental Report TABLE OF CONTENTS (continued)
Page V. ENVIRONMENTAL MONITORING PROGRAM (continued)
F. Environmental Radiation Monitoring 87
- 1. Description of Regional Background Radiation Levels I and Sources 87 (
- 2. Locations & Analytical Procedures 87
- 3. Results and Conclusions 89 G. Monitoring of Fish 90
- 1. Description 90
- 2. Sampling Program and Analytical Techniques 90
- 3. Results and Conclusions 90 H. Monitoring of Surface, Drinking, and Well Waters 92
- 1. Description of Water Sources 92
- 2. Sampling Program and Analytical Techniques 92
- 3. Results and Conclusions 96
- 1. Estimates of Radiation Dose to Man 99
- 1. Pathways to Man - Beaver Valley Power Station 99
- a. Calculational Models - Beaver Valley Power Station 99
- 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station 100
- 3. Airborne Pathway 103 I
- 4. Conclusions - Beaver Valley Power Station 103
- 5. Dose Pathways to Man - Shippingport Atomic Power Station 103
- a. Calculational Model - Shippingport Atomic Power Station 105
- 6. Results and Conclusions - Shirpingport Atomic Power Station 106 l
I DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report LIST OF FIGURES Figure No. Page 1.0 View of the Shippingport and Beaver Valley Site 3 1.1 Geographical Map - 40 Mile Rafius 4 4.1 Liquid Discharge Points to Ohio River 27 4.2 Water Flow Schematic - Shippingport Atomic Power Station 28 4.3 Water Flow Schematic - Beaver Valley Power Station 29 4.4 Liquid Radwaste Systems - Shippingport Atomic Power Station 30 4.5 Liquid Radwaste Systems - Beaver Valley Power Station 31 I 4.6 4.7 4.8 Gaseous Waste Processing - Shippingport Atomic Power Station Gaseous Waste Processing - Beaver Valley Power Station Caseous Release Points - Shippingport Atomic Power Station 35 37 and Beaver Valley Power Station 39 I 4.9 5.B.1 Solid Waste Disposal Diagram 47 Environmental Monitoring Locations - Air Sampling Stations 72 5.B.2 Concentrations of Gross Beta in Air Particulates 74 5.C.1 Environmental Monitoring Locations - Sediments 77 5.D.1 Environmental Monitoring Locations - Feederop and Foodcrop 81 5.E.1 Dairy Farm Locations (August - September 1978 Survey) 84 5.E.2 Environmental Monitoring Locations - Milk 85
- 5. F.1 Environmental Monitoring Locations - Radiatioc Monitoring 88 5.G.1 Environmental Monitoring Locations - Fish 91 5.H.1 Surface Water and Wells - Locations 94 I
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DUQUP'57 LIGHT COMPANY 1979 Annual Radiological Environmental Report I LIST OF TABLES I Table Number Page III.1 Quality Control Data - TLD Comparisons 9 III.2 Quality Control Data - Water Split Samples 10 III.3 Quality Control Data - Split Samples - Miscellaneous 12 III.4 Quality Control Data - Spiked Samples 15 I III.5 III.6 III.7 Quality Control Data - Spiked Samples Quality Control Data - Air Particulates and I-131 Quality Control Data - Milk and Water 16 17 21 III.8 Anomalous Measurements During 1979 25 IV.A.1 Effluent Treatment, Sampling and Analytical Procedures -
Shippingport Atomic Power Station 32 I IV.A.2 IV.A.3 Effluent Treatment, Sampling and Analytical Procedures -
Beaver Valley Power Station Results - Liquid Effluents - Shippingport Atomic Power 32 I IV.A.4 Station Results - Liquid Effluents - Beaver Valley Power Station 33 33 V.A.1 Environmental Monitoring Program Summary I V.A.2 V.A.3 V.A.4 Environmental Monitoring Program Results (1979)
Pre-Operational Monitoring Program Results (1974-1975) 49 52 66 Typical LLDs for Gamma Spectrometry - DLC Contractor 70 V. I.1 Radiation Dose to Man - Beaver Valley Power Station -
Liquid Releases V.I.2 13L Radiation Dose to Man - Beaver Valley Power Station -
Airborne Releases 104 I
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SECTION I DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report I
- 1. INTRODUCTION The 1979 Annual Radiological Environmental Report for the Beaver Valley Power Station and the Shippingport Atomic Power Station summarizes the I radiological environmental program conducted by the Duquesne Light Company in 1979.
The Duquesne Light Company operates the Shippingport Atomic Power I Station for the United States Department of Energy and the Beaver Valley Power Station pressurized water reactor - Unit No. 1 as part of the CAPCO pool. Beaver Valley No. 2 Unit was under construction in 1979 and is scheduled to start-up in 1986.
The Shippingport Atomic Power Station operated throughout 1979, with I the gross electrical generation during the year of 368,307 megawatt-hours. The plant has been in operation utilizing a light water breeder reactor (LWER) core since September 21, 1977.
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 highest average daily output generated at the Beaver Valley Power Station during the year was 829 megawatts net in January, 1979 The I total gross electrical generation during the year was 1,939,200 megawatt-hours.
A. Scope and Objectives of the Program The environmental program consists of e.ffluent and environmental I monitoring for radioactivity. Liquid and gaseous effluents from the Beaver Valley Power Station and gaseous effluents from the Shippingport Atomic Power Station were collected, processed, sampled, and analyzed to enst.re conformance with the applicable I regulations and permits prior to their release to the environment.
Environmental sampling and analyses included air, water, milk, soil, vegetation, ri"ar sediments, fish, and ambient radiation levels in areas surrounding both plants.
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I SECTION I DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report
.I I. INTRODUCTION B. Description of the Shippingport and Beaver Valley Site The Shippingport Atomic Power Station and the Beaver Valley Power Station are located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 486.8 acre tract of land which is owned by the Duquesne Light Company.
Figure 1.0 shows a view of both stations. The site is approximately one mile from Midland, Pennsylvania; 5 miles from East Liverpool, Ohio; and 25 miles from Pittsburgh, Pennsylvania. Figure 1.1 shows I 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 I of either plant. The population within a 5 mile radius of the plant is approximately 17,000 and the only area of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 5,000.
The site lies in a valley along the Ohio River. It extends from the river (elevation 665 feet above sea level) to a ridge along the border south of the Shippingport and Beaver Valley Power Stations at an elevation of 1,160 feet. Plant entrance 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 Cumberland Lock and Dam. The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated I by a series of dams and reservoirs on the Beaver, Allegheny, and Monongahela rivers and their tributaries. Flow ranges from a minimum of 5000 cubic feet per second (CFS) to a maximum of 100,000 CFS. The mean annual flow is approximately 25,000 CFS.
Water temperature of the Ohio River varies from a minimum of 32*F to 84*F, the minimum temperatures occur in January or l February and maximum temperatures in July and August. Water 5 quality in the Ohio River at the site location is affected
! primarily by the water quality of the Allegheny, Monongahela, 3 and Beaver rivers.
,E 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 I
in winter.
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8 SECTION I DUQUESNE LIGHT COMPANY FIGURE 1.0 1979 Annual Radiological Environmental Report I
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I SECTION I DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report I
- 1. INTRODUCTION B. Description of the Shippingport and Beaver Valley Site (continued)
The design ratings and basic features of the Beaver Valley I Power Station and the Shippingport Atomic Power Station are tabulated below:
Beaver Valley Shippingport Thermal & Elec. Rating - 2660 MW 852 MW 236.6 MW 72 MW MW-Each Reactor Type of Reactor PWR PWR*
Number of Reactor 3 4 Coolant Loops I Number of Steam Generators and Type 3 - Vertical 4 - Horizontal 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)
I 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 I 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 molant pumps. Heat is given up from the primary system to the I secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the The steam is condensed after passing electrical generator.
I through the turbine, and returned to the steam generators to begin another steam / water cycle.
I NOTE: MW - megawatts thermal I MW - megawatts electrical I
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I SECTION II DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report I II.
RESULTS AND CONCLUSIONS A review of plant operation at both the Beaver Valley Power Station and the Shippingport Atomic Power Station indicated that there were t no adverse effects on the environment as a result of activities at either of the stations during 1979.
The Shippingport Atomic Power Station operated throughout 1979; Beaver Valley Power Station experienced an extensive outage to verify seismic qualification of the plant. During the year, the radioactive releases from both stations were below the limits of I 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. These releases are summarized in Tables IV.A.2 and IV.A.3 of this report.
The environmental program for 1979 was the same as in 1978 except for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications.
I The results of the 1979 Radiological Environmental Monitoring Program are consistent with those of previous years. Radioactivity above normal ambient levels in the environs were detected in some analyses.
These anomalous results are noted in Table III.8 and summarized below.
I When detectable environmental radioactivity occurred, it was comparable to the national levels of radioactivity in the environment and/or result-ed in neglible exposure to members of the public. A summary of the 1979 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 and ranges is found in Table V.A.3.
I Examination of effluents from these stations and environmental media demonstrated compliance with regulations and Station Technical Specifi-cations. While there were three (3) rerults during the year which I exceeded the reporting levels of the Nuclear Regulatory Commission, all of the analyses after evaluation were below limits identified in the Code of Federal Regulations or the Beaver Valley Technical I Specifications. These included two (2) surface water tritium values at the outfall of the Beaver Valley Power Station and one (1) surface water gross beta at the outfall of the Shippingport Atomic Power Scation. The former resulted from small quantities of I tritium released from the Beaver Valley Power Station which were well below limits noted in 10CFR20, and the latter was attributable to natural radioactivity of suspended sediments. The high gross beta value of 26.0 pCi/ liter was for a March 1979 composite of surface water. This relatively high activity is attributed to the bottom sediments contained in the sample resulting from turbulent water conditions during sampling. The sediment concentration in this sample was 1.3 grams / liter.
If the gross beta activity of 26 pCi/ liter measured in the water sample is attributed entirely to I
I SECTION II DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report l
I II. RESULTS AND CONCLUSIONS (continued) the sediment, the activity of the sediments would be 20 pCi/ gram of I
dissolved solids. Since gross beta measurements of sediment samples obtained during 1978 have resulted in activities between 13 and 64 pCi/ gram, it is concluded that the unusually high surface water I activity was due to the solids from the river sediments and not from plant operation. To confirm this, part of the sample was l reanalyzed after filtering out the suspended solids. After filtering, (
the gross beta results for the water was 6.7 pCi/ liter, which is I within the range of activities normally found in surface water. j This is well below the reporting level noted in the Beaver Valley I Technical Specifications. Shippingport Atomic Power Station did not release any liquid radioactive effluents during 1979.
The Beaver Valley Power Station Technical Specifications require sampling of four (4) dairies which have the highest calculated milk pathway potential. These four dairies are determined from calculations based on the meteorological data and the latest milch animal survey.
However, these dairies are frequently small, consisting of as 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.
In order to provide continuity in the sampling / analyses program, the environmental monitoring program includes three larger dairies. Samples I 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 I be among the four required dairies. Thus, there will be at least four and possibly as many as seven dairies sampled in any sampling period.
The collection periods associated with each of the locations is provided in the detailed summary of the milk monitoring program of this report (Section V-E).
Lessons learned from the Three Mile Island incident indicated the need I for more radiation monitors in all sectors surrounding the plant.
Twenty-eight (28) new sites were identified in addition to the thirteer (13) locations monitored in previous years. Negotiations with property owners was completed by the end of the year for the installation of
' I radiation monitors beginning in 1980. Also, monthly pressurized ion chamber readings were taken during March - December 1979 at offsite thermoluminescent dosimeter locations. This was implemented to provide background data and quick data availability for emergency situations.
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SECT 10N III DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report I 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 eight (8) 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 I measure. However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.
- 1. Radiation Monitoring (Duqueste Light Company (DLC)
Contractor Laboratory - DLC QC Laboratory An independent program of external radiation monitoring I was conducted by the QC Laboratory using lithium fluoride TLDs at the same locations. Summary data of the QC Laboratory program is provided in Table III.l.
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 the 3 laboratories agrees within + 4% of each other. 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. Some variation may be expected due to small variations in duplicate samples, variations in analytical I procedures, and in calibration, source type, etc. A summary of milk, sediment, and feed / food crop split samples is provided in Table III.3.
Because of the overall uniformity of comparable results, it is concluded that the two laboratories are consistent t
and in agreement.
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I SECTION III DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environm2ntal Report TABLE III.1 I TABLE III.1 QUALITY CONTROL RESULTS I TLD MONITORING mR/ Day 2nd QUARTER let QUARTER DLC DLC DLC QC Independent DLC DLC QC Independent Di C Location Contractor Lab 1.ab # 3 PDER PIC Contractor Lab Lab 1'3 PDER PIC No. (CaSO4 :Dy) (LiF) (CaSO4 :Tm) (2) JQ (CaSO4 :Dy) (LiF) CaSOg:Tm) 1 (1)
I 10 13 0.17 k.18 0.18 0.20 0.18 0.19
.22
.21 0.23 0.24" I 0.19 0.20 0.18 0.20 0.22 0.25
.23
.24 0.23(3) 0.26 "
0.23 " 0.21 0.23 - 0.22 "
I 14 0.17 0.18 0.19 - 0.22 0.12 0.18 " 0.13 0.14 0.18 - 0.15 "
15 0.12 0.13 -
0.17 0.23 " 0.19 0.19 0.21 - 0.22 "
27 0.17 0.18 -
0.18 0.25 " 0.20 0.22 0.24 - 0.24 "
28 0.17 0.19 -
0.20 0.29 " 0.23 0.25 0.28 - 0.28 "
29 0.21 0.21 -
0.23 0.21 0.23 0.26 - 0.24 32 0.20 0.19 0.20 -
0.29" 0.28* 0.19 0.27 .25 0. 27" .
I 45 0.21 0.20 0.21 .24 46 0.16 0.16 0.16 .19 0.22" 0.17 0.17 0.21 .21 0.21" 0.24 0.21 0.26 " 0.21 0.19 0.26 - 0.26 "
47 0.20 -
0.22 " 0.23 0.19 0.23 - 0.24 "
I 0.18 0.16 0.17 -
48 0.26 " 0.20 0.19 0.26 - 0.25 "
51 0.19 0.20 0.19 -
3rd QUARTER 4th QUARTER I DLC DLC QC Lab Independent Lab I3 PDER DLC PIC DLC Contractor DLC QC Lab Independent Lab #3 PDER DLC PIC Location Contractor (2) JQ (LiF)
I No. CaSO4 :Dy) (LiF) (CaSO4 :Tm) 1 (1) (CaSO4 :Dy) (CaS0;:Tm) 0.19 0.17 0.19 .25 0.23 I3) 0.22 0.22 0.22 .23 0.26(3) 10 0.22 0.20 0.20 .27 0.25" 0.22 0.25 0.24 .24 0.26" 13 0.22 0.17 0.20 - 0.22 " 0.21 . 0.23 0.21 - 0.22 "
14 0.13 0.13 - 0.16 " ** ** ** - 0.15 "
15 0.16 0.18 0.18 - 0.23 0.20 ** 0.22 -
0.23 "
27 0.20 0.19 - 0.25" 0.22 0.23 0.24 - 0.24 "
28 0.23 0.22 0.25 0.22 0.23
- 0.29 " Q.24 0.25 0.26 - 0.29" 29 0.19 -
0.26 0.22 0.21 0.25 '- 0. 2E "
32 0.23 0.22 0.20 .28 0.26" 0.22 0.27 0.24 .25 0. 2E" 45 0.22 0.22 0.18 0.16 .23 0.22" 0.20 0.17 0.19 .21 0.22 "
46 0.17 0.22 0.18 -
0.27 " 0.24 0.23 0.25 - 0.27 "
47 0.21 48 0.19 0.17 0.17 -
0.23 " ** ** ** - 0.25 "
0 18 - ,0 25" 0.23 0.22 0.23 - 0.26 "
51 0. 31 + 0.20 (1) Pressurized ion chamber (FIC)
(2) NRC results from the Pennsylvania Department of Environmental Resources (3) PIC Reading taken in Shippingport Boro at DLC Substation There are 4 readings per contractor TLD location. In this case, one dosimeter reading was nigher than the others.
If high dosi=eter is deleted, low one averages 0.24 mR/ day.
xx Based on periodic rate checks rather than continuous monitoring
+
This reading was high relative to other TLDs at the same location and to other TLD data from the same laboratory.
The data was reviewed and no errors could be found. The result is considered anomalous since it does not agree with other comparable measurements
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I SECTION III DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environm:ntal Rsport TABLE III.2 (Pags 1 of 2)
TABLE III.2 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs DLC Contractor DLC - QC Media Analysis Sampling Period Lab (1) Lab (1) Units Surface Water Gross a January 1 1.4 3.2 1 2.9 pci/1 April 1.7 1 1.6 1 1.2 pci/1 July 1 1.2 1 1.1 pci/1
. October 1 0.9 2.3 1 1.0 pci/1 Surface Water Gross 8 January 4.6 1 1.1 7.9 1 2.2 pCi/1 April 5.0 1 1.2 4.1 1 3.1 pci/1 July 3.8 1 1.1 4.1 2.4 pci/1 I Tritium October 6.7 1 1.2 190 + 80 7.6 1 2.2
< 200 pci/1 pC1/1 Surface Water 1st Quarter Composite 3rd Quarter Composite
-< 110 -< 220 pC1/1 Surface Water Co-60 January 1 3.0 1 4.2 pci/1 April 1 3.0 16.9 pCi/1 July 1 3.0 1 5.0 pci/1 October 10 3 1 5.8 pC1/1 Surface Water Cs-137 January < 3.0 < 3.1 pC1/1 April < 3.0 < 5.1 pci/1 July 1 3.0 14.3 pC1/1 October s 3.0 3 3.3 pci/1 Surface Water C-14 2nd Quarter 1.05 1 0.25 i 9.1 pC1/1 Cornposite Surface Water Sr-89 2nd Quarter < 2.0 pC1/1 Composite -< 0.32 4th Quarter < 2.0 < 0.3 pC1/1 Composite Surface Water Sr-90 2nd Quarter 1.2 10.7 0.33 1 0.24 pC1/1 Composite pC1/1 I Surface Water Co-60 4th Quarter Composite 2nd Quarter 0.48 +- 0.37 i 1.0 0.5 '-+ 0.3 1 1.3 pC1/1 I (high sensitivity analysis)
Composite 4th Quarter Composite 1*0
~~ 1.2 pC1/1 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
l SECTION III DUQUENSE LIGHT COMPANY TABLE III.2 5 1979 Annual Radiological Environm:ntal R2 port (Pags 2 of 2)
TABLE III. 2 (Continued)
QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and OLC-0C Labs DLC Contractor Media Analysis Sampling Period Lab (1) OLCLab- QC(l) Units Orinking Water Cs-137 February < 3.0 < 4.3 pC1/1 i4ay 1 3.0 < 4.9 pC1/1 14.3 pC1/1 August 1 3.0
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- 1 3 pC1/1 Orinking Water Co-60 February 1 3.0 1 6.4 May 1 3.0 1 5.9 pC1/1 Auaust
< 4.0 < 5.9 pC1/1 november _7 3.0 7 4.5 pCi/1 Orinking Water Gross a March 0.95 1 0.47 1 1.0 pC1/1 June 1 0.56 11 1 pC1/1 August 1 0.57 1 0.7 pC1/1 November < 0.57 < 0.8* pC1/1 Orinking Water Gross 8 March 3.7 1 0.9 3.6 1 2.4 pCi/1 June 3.9 1.1 5.6 13.0 pCi/1 I August November 4.0 3.2 11.1 11.2 5.9 10.8 5.3 1 2.6*
pC1/1 pC1/1 Orinking Water Tritium 2nd Quarter 240 1 60 < 220 pCf/1 4th Quarter 140 1 70 < 200 pC1/1 I '* Analysis performed on weekly sample which was collected 12-4-79.
(1) Uncertainties are based on counting statistics and are specified at tne m confidenc. interval.
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SECTION III DUQUENSE LIGHT COMPANY TABLE III.3 1979 Annual Radiological Environm:ntal Report (Pags 1 of 2)
I TABLE 111.3 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS
, COMPARISON OF CONTRACTOR AND DLC-0C LAB DLC Contractor DLc - Qc Media Analysis Samplino Period Lab (1) tab (1) Units <
l Milk I-131 3 12-79 < 0.13 10.6 pci/1 1 (Loca*. ion 25) Sr-89 3-12-79 1.1 1 0.5 pci/1 Sr-90 3-12-79 3.4 + 0.5 3.8 1 0.4 pci/1 Cs-137 3-12-79 9.0 16.1 1 4*4 PC1/1 Co-60 pci/1 3-12-79 1 3.0 1 6.1 K4 3-12-79 999 1 140 1120 1 80 pci/1 Other 3-12 79 LLD LLD pci/1 Milk I-131 6-11-79 < 0.14 < 0.6 pC1/1 I (Location 25) Cs-137 Co-60 6-11-79 6-11-79 11.3 + 6.6
< 3.0 9.2 + 6.3
< 5.9 pC1/1 pC1/1 K-40 6-11-79 1160 + 70 1110 1 150 pC1/1 I Feed
[ Pasture Grass]
(Location 25)
Cs-137 6-11-79 < 0.03 < 0.02 pCf/gm (dry)
Co-60 6-11-79 < 0.03 < 0.02 pCi/gm (dry)
K-40 6-11-79 29.7 + 3.0 25.8 + 4.2 pCf/gm (dry)
Feed (Location PS) Sr-90 6-11-79 0.17 + 0.03 0.32 + 0.07 pCf/gm (dry)
Sediment Gross a 7-19-79 (Location 3) 14 ? 18 22.0 17 pCi/gm Gross 8 7-19-79 32.0 + 3 25.0 15 pCi/gm U-235 7-19-79 0.097 + 0.020 < 0.10 pC1/gm U-234 7-19-79 1.19 + 0.18 0.91 + 0.09 pCf/gm U-238 7-19-79 0.69 + 0.08 0.89 1 0.17 pCi/gm Sr-89 7-19-79 1 0.088 1 0.02 pCi/gm Sr-90 7-19-79 0.04 + 0.03 0.04 + 0.02 pCf/gm Cs-137 7-19-79' O.20 + 0.04 0.32 + 0.10 pCi/gm Co-60 7-19-79 < 0.04 < 0.09 pCi/gm K-40 7-19-79 12.9 + l.5 13.3 + 1.7 pCf/gm LLD = Lower Limit Dectection l
(1) = Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
1 SECTION III DUQUENSE LIGHT COMPANY TABLE III.3 i 1979 Annual Radiological Environm:ntal Raport (Paga 2 of 2)
TA8LE !!!.3 QUALITY CONTROL P.ESULTS SPLIT SAMPLE ANALYSIS RESULTS COMPARISON OF CONTRACTCR AND CLC-QC LAS DLC Sampling Contractor DLC - QC Media Analysis Period Lab (1) Lab (1) Units Soil Gross a 6-15-79 5.7 1 3.0 7.0 1 5.0 pC1/gm Gross s 6-15-79 21.0 + 2.0 24.0 + 6.0 pC1/gm ;
Sr-90 6-15-79 0.25 + 0.06 0.27 + 0.04 pC1/gm f
K-40 6-15-79 10.8 + 1.6 11.2 + 1.5 pCi/gm Cs-137 6-15-79 0.76 + 0.09 1.2 + 0.2 pC1/gm Co 60 6-15-79 < 0.03 < 0.08 pC1/gm U-235 6-15-79 <_ 0.02 1 0.10 pC1/gm U-234 6-15-79 0.28 + 0.07 0.38 + 0.05 pC1/gm U-238 6-15-79 0.28 1 0.07 0.32 1 0.05 pC1/gm Food I-131 8-07-79 < 0.011 < 0.10 pCf/gm (wet)
(Lettuce) pCf/gm (wet)
Cs-137 8-07-79 0.022 1 0.009 1 0.03 Co-60 8-07-79 < 0.008 < 0.03 pCf/gm (wet)
, K-40 8-07-79 2.9 + 0.3 2.6 + 0.5 pC1/gm (wet) l Other 8-07-79 LLD LLD pCi/gm (wet)
Food I-131 8-07-79 < 0.011 < 0.09 (Swiss Chard) Cs-137 8-07-79 0.031 1 0.021 1 0.04 pCi/sm (wet)
Co-60 8-07-79 < 0.01 < 0.04 pCi/gm (wet)
K-40 8-07-79 5.3 + 0.6 5.0 + 0.7 pct /gm (wet)
Others 8-07-79 LLD LLD pCf/gm (wet)
I Milk (Location 25)
I-1 31 Sr-89 9-18-79 9-18-79 1 0.14
< 1.9 0.5 0.9 pCi/1 pCi/1 Sr-90 9-18-79 4.3 + 0.6 3.1 + 0.9 pC1/1 Cs-137 9-18-79 < 3.0 < 4.4 pC1/1 Co-60 9-18-79 < 3.0 < 5.5 pC1/1 K-40 9-18-79 1270 + 130 880 + 100 pC1/1 Other 9-18-79 LLD LLD pC1/1 Milk (Location 25) I-1 31 12-11-79 < 0.15 < 0.4 pC1/1 Cs-137 12-11-79 < 0.3 < 7.4 pC1/1 Co-60 12-11-79 < 0.3 < 8.5 pC1/1 K-40 12-11-79 1360 1 140 1150 1 180 pC1/1 Others 12-11-79 LLD LLD pC1/1 LLD - Lower Limit of Detection (1) - Uncertainties are based on counting statistics and are specified at the 95t confidence interval.
SECTION III DUQUENSE LIGHT COMPANY 1979 Annuti Radiological Environm2ntal R: port l
III. ENVIRONMENTAL MONITORING CONSIDERATIONS
- 3. DLC QC Laboratory Program Samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for analysis.
These included " spike" samples. Tables III.4 (water) and III.5 (milk) provide data from this portion of the QC program. The results demonstrate that the contractor performed the program acceptably.
- 4. Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory)
Duplicate air particulate and charcoal filters (radioiodine) samples were collected at Location #30 and compared during the year on a weekly basis. These data are provided in Table III.6. Agreement was excellent.
- 5. Contractor Internal QC Program The Duquesne Light Company 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 I Contractor Laboratory results were in agreement with EPA -
EMSL. DLC also audited the Contractor Laboratory and determined that internal QC practices were in effect and that procedures and laboratory analytical techniques conformed to approved DLC procedures.
- 6. Special QC Program (DLC Contractor Laboratory -
Independent Laboratory - DLC QC Laboratory)
Milk and water samples were prepared quarterly by an I Independent Laboratory.
of specified nuclides.
This included low level spiking The prepared samples were split three ways and analyzed by the DLC-QC Laboratory and Independent Laboratory as well as the Contractor Laboratory. A summary of results of this portion of the QC program is provided in Table III.7. The results show generally good agreement between the laboratories and I demonstrate that the contractor performed the program acceptably.
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SECTION III DUQUENSE LIGHT COMPANY TABLE III.4 1979 Annual Radiological Environmsntal Report G
TABLE III.4 QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS RESULTS Sample Type DLC and Contractor OLC - QC Sample Date Ident No. Analysis Lab (1) Lab (1) Units I 3-26-79 53-25 Water: Sr-89 7.3 + 1.5 8.2 1 1.6 pC1/1 Sr-90 4.7 + 0.6 4.8 1 0.5 pCi/1 6-20-79 53-26 Water: 1-131 4.5 1 0.6 5.9 11.2 pC1/1 Co-60 9.18 + 6.61 15.9 + 5.2 pC1/1 l Cs-137 42.9 + 7. 7 37.2 1 5.9 pCf/1 Others LLD LLD pCi/1 I 6-20-79 53-27 Water: Gross a Gross s Water: Sr-89 3.2 10.4 16 11
+ 2 8.8 1 3.1 16.8 1 4.4 11.0 + 2.2 pC1/1 pC1/1 pC1/1 10-01-79 53-28 11 Sr-90 11 11 9.8 11.0 pCi/1 Cs-137 35.7 1 6.4 28.0 1 5.3 pCf/l Others LLD LLD pC1/1 11-26-79 53-29 Water: I-1 31 1.9 1 0.1 2.4 1 0.6 pCi/1 10.5 1 3.7 pC1/1 Co-60 16.7 1 4.8 Cs-137 8.9 + 4.8 12.6 + 6.4 pCf/1 Others LLD LLD pC1/1 Water: H-3 1330 1 270 pC1/1 11-26-79 53-30 1110 1 90 11-26-79 53- 31 Water: C-14 29.7 +_ 3.0 32.3 1 6.3 pCi/1 Water: Gross s 9.4 + 2.3 16 12 pC1/1 12-18-79 53-32 Gross a 26 12 27 16 pC1/1
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i (1) Uncertainties are based on c.ounting statistics and are specified at the 95 confidence interval.
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SECTION ZII DUQUENSE LZGHT COMPANY TABLE I12.5 1979 Annual Radiological Environmental Report TABLE I!!.5 QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS Sample Type DLC and Contractor OLC - QC Sample Date Ident. No. Analysis Lab (1) Lab (1) Units 3-26-79 52-41 Milk: Sr-89 8.0 1 1.5 8.9 1 1.8 pC1/1
$r-90 5.2 1 0.6 5.6 1 0.6 pCf/1 1-131 1 0.17 1 0.3 pC1/1 K-40 1090 + 140 -
pCf/1 Cs-137 24.7 1 5.3 30.0 15.8 pC1/1 Other I.LD 1.LD pC1/1 6-20-79 52-42 Milk: I-131 6.7 1 0.7 7.9 + 1.3 pC1/1 K-40 1370 + 160 -- pC1/1 Cs-137 30.6 + 7.3 22.5 + 6.0 pC1/1 Other LLD LLD pCi/1 7-30-79 52-43 Milk: Sr 89 < 1. 6
- 8.7 + 1.8
- pC1/1 Sr 90 8.1 + 0.7 5.4 + 0.7 pCi/l I-131 2.1 + 0.3 2.6 + 0.8 pCi/l l
Cs 137 12.0 1 7.4 13.7 1 5.2 pC1/1 Other LLD LLD pC1/1 11-26-79 52-44 Milk: I-131 3.0 1 0.1 4.3 11.0 pC1/1 K-40 1230 1 120 1380 1 210 pC1/1 Cs-137 26.9 + 5 20.6 + 6.5 pCf/1 Other LLD tLD pC1/1 l
l The Sr-89 results are not in good agreerert for this sample. The results of the analysis were reviewed and no errors could be found. Tht specific cause.of the differences could not be identified.
However, previous and subsequent analyses h.'ve yielded excellent agreement between the laboratory results.
(1) Uncertainties are based only on counting sta'.istics and are specified at the 955 confidence interval.
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g SECTION III DUQUENSE LIGHT COMPANY TABLE III.6 m 1979 Annual Radiological Environm:ntal Report (Pagt 1 of 4)
E TABLE III.6 QUALITY CONTROL RESULTS AIR PARTICULATES At:0 CHARCOAL FILTER: COMPARABLE SAMPLES I Air Particulates pCi/Cu. Meter (Beta)
Air lodine pC1/Cu. Meter DLC DLC I Contractpr DLC ,QC Contractor OLC - CC Sample Date lab tl) Lab (1) Sample Date Lab (1) Lab (1) 1/9/79 to 0.044 + 0.004 0.044 + 0.003 1/2/79 to < 0.007 < 0.019 1/16/79 1/9/79 1/23/79 to 0.027 + 0.004 0.027 + 0.002 1/16/79 to 1 0.007 1 0.029 1/30/79 1/23/79 2/6/79 to 0.044 + 0.004 0.045 + 0.003 1/30/70 to 1 0.007 1 0.020 2/13/79 2/6/79
< 0.007 I 2/20/79 to 2/27/79 0.036 + 0.004 0.034 + 0.003 2/13/79 to 2/20/79 2/27/79 to < 0.006 1 0.022
< 0.023 3/6/79 to 0.047 + 0.004 0.045 + 0.003 3/13/79 3/6/79 3/20/79 to 0.032 + 0.004 0.032 + 0.003 3/13/79 to < 0.008 < 0.019 3/27/79 3/20/79 4/3/79 to 0.040 1 0.004 0.042 1 0.003 3/27/79 to < 0.007 < 0.020 4/10/79 4/3/79 4/17/79 to 0.055 + 0.005 0.049 + 0.003 4/10/79 to < 0.006 < 0.020 I 4/24/79 5/1/79 to 5/8/79 0.041 + 0.004 0.046 + 0.003 4/17/79 4/24/79 to 5/1/79
< 0.008 < 0.020 I 5/15/79 to 5/22/79 0.035 1 0.004 0.037 1 0.003 5/18/79 to 5/15/79
< 0.007 < 0.020 5/29/79 to 0.035 1 0.004 0.044 1 0.002 5/22/79 to 6/5/79 ~< 0.010 ~< 0.019 5/29/79 6/17/79 to 0.050 + 0.004 0.045 + 0.003 6/5/79 to 1 0.02 < 0.029 6/19/79 6/12/79 6/26/79 to 0.048 + 0.005 0.046 + 0.003 6/19/79 < 0.01 < 0.020 7/2/79 6/26/79 7/9/79 to 0.028 ~ + 0.003 0.035 ~ + 0.003 7/2/79 to 1 0.007 -< 0,019 7/16/79 7/9/79 7/23/79 to 0.029 1 0.004 0.033 -+ 0.003 7/19/79 to 1 0.02 , 0,034 7/30/79 7/23/79 l = 8/6/79 to 0.045 0.004 0.03s + 0.003 7/30/79 to 1 0.01 < 0.025 8/13/79 8/6/79 l
8/20/79 to 0.030 1 0.004 0.030 1 0.003 8/13/79 to 1 0.007 1 0.021 8/27/79 8/20/79 9/4/79 to 0.034 1 0.004 0.032 1 0.003 8/27/79 to < 0.020 9/10/79 1 0.016 9/4/79 9/17/79 to 0.034 i G.004 0.032 1 0.003 9/10179 to 9/24/79 < 0.007 < 0.017
?/17/.'9 I I-
SECTION III DUQULTSE LIGHT COMPANY TABLE III.6 1979 Annual Radiological Environm:ntal Report (Page 2 of 4) i l I TABLE III.6 OUALITY CONTROL RESULTS AIR PARTICULATES AND CHARCCAL FILTER: COMPARABLE SAMPLES Air Particulates Air lodine l
pC1/Cu. Meter (Beta) pC1/Cu. Meter I -
OLC OLC Contractqr OLC - QC Contractor DLC - QC Sample Date Lab LI) Sample Date Lab (1) Lab (1) Lab (1) 10/01/79 to 0.030 -+ 0.004 0.030 +- 0.003 9/24/79 to < 0.006 < 0.020 10/08/79 10/01/79
' 10/16/79 to 0.036 +~ 0.005 0.041 ~+ 0.003 10/08/79 to < 0.003 < 0.021 10/22/79 10/16/79 I 10/30/79 to 11/05/79 11/12/79 to 0.029 +~ 0.004 0.040 +- 0.004 0.032 ~+ 0.003 0.042 +- 0 303 10/22/79 to 10/30/79 11/5/79 to
< 0.007
~< 0.01
< 0.018 11/19/79 11/12/79
~< 0.024 11/26/79 to 0.025 +- 0.004 11/19/79 to 12/03/79 0.031 ~+ 0.003 ~< 0.01 -< 0.020 11/26/79 I 12/10/79 to 12/17/79 12/24/79 to 0.025 1 0.003 0.020 + 0.003 0.028 + 0.002 0.020 + 0.002 12/03/79 to 12/10/79 12/17/79 to <
< 0.01 0.01
< 0.021
< 0.023 12/31/79 12/24/79 I
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Uncertainties are based only on counting statistics and are specified at the 95% confidence interval.
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SECTION III DUQUENSE LIGHT COMPANY TABLE III.6 1979 Annual Radiological Environmental Raport (Page 3 of 4)
TABLE III.6 QUALITY CONTROL AIR PARTICULATES (oCi/m3)
I' Sample Date Nuclide DLC Contractor Lab (1)
DLC - QC Lab (1)
January Be-7 0.045 + 0.010 0.071 + 0.031 O/20 - 1/30/79 Zr/NB-95 < 0.001 0.012 + 0.012 K 40 0.087 + 0.042 IID I March Others Be-7 11D 0.154 + 0.018 0.14 m
+ 0.004.
( /27 - 4/3/79) cs-137 0.0017 1 0.0014 IID I May Others Be-7 0.15 11D 1 0.02 0.13 11D 1 0.03 (5/1 - 5/29/79)
I cs-137 0.001P + 0.0011 0.0033 1 0.0023 Others I1D 11D Be-7 0.119 1 0.017 0.13 1 0.05 I
July (7/2 - 7/30/79) Cs-137 1 0.0007 0.0045 1 0.0027 Others LLD LLD I September Be-7 0.085 1 0.014 0.12 1 0.03 (9/4 - 10/1/79) Others LLD LLD i
E November Be-7 0.105 + 0.026 0.076 + J.024 g (10/30 - 12/3/79) Cs-137 0.0017 1 0.0013 -
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I (1) Uncertainties are based only on counting statistics and are specified at +.he 951 confidence interval.
1 SECTION III DUQUENSE LIGHT COMPANY TABLE III.6 1979 Annual Radiological Environmental Report (Page 4 of 4)
I TABLE 111.6 Quality Control I Air Particulate and Charcoal Filter-gomparable Samples location 30 - (pCi/m )
I Sample Data Nuclide DLC Contractor lab @
DLC - QC Lab (1) ist Quarter Composite: Alpha 0.0040 + 0.0013 0.0045 + 0.0005 l Air Filter Sr-89 < 0.0011 < 0.0012 i Sr-90 0.00029 1 0.00008 0.00039 1 0.00017 3rd Quarter Composite: Alpha 0.0031 1 0.0011 0.0053 1 0.0007 Air Filter Sr-89 1 0.0017 1 0.00057 ;
Sr-90 0.00031 1 0.00016 0.00045 1 0.00028 I
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I I (1) Uncertainties are based only on counting statistics and are specified at the 95% confidence interval.
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SECTION III DUQUESNE LIGHT COMPANY TABLE III.7 l 1979 Annual Radiologi, cal Environmental Report (Page 1 of 2)
TA8tE !!I.7 .
QUALITY CONTROL DATA I QC Sample Comparisons (All Analyses in DCf/1)
I Sample Date Ident No.
Sample Type and Anal yses Independent Lab (11 DLC Contractor Lab (1)
DLC - QC Lab (I) 2-14-79 52-21 0 Milk: Sr-89 7.5 11.4 3.8 1 0.9 6.6 11.4 Sr-90 15.0 1 0.6 12 11 12.7 11.2 I-131 8.0 + 0.2 8.0 + 0.2 6.4 1 0.7 Cs-137 47 + 2 50 + 7 39 + 4 I 5-23-79 52-211 Milk: Sr-89 Sr-90 1 12 15.9 + 0.7 1 1.1 14 +,, 1 11.0 14.6 1 1.2 1-131 4.9 1 0.2 8.8 1 0.4 5.0 1 0.9 Cs-12/ 13.0 + 6 28.9 + 6.9 25.6 + 6.6 Cs-134 22.0 11 28.9 + 7.5 30.7 1 6.4 I
K-40 ---
1250 1 150 8-15-79 52-212 Milk: 'Sr 89 6 12 3.3 11.4 9.1 + 1.8 Sr 90 19.2 11.2 11 11 12.9 11.3 jI l
Cs 134 Cs 137 25.0 1 7.0 21.0 14 24.9 + 7.0 28.1 + 6.7 21.4 + 8.4 23.7 + 7.9 l I-131 5.7 1 0.6 4.9 + 0.3 7.8 + 1.1 11-14-79 52-213 Milk: Sr-89 12 13 9.1 11.5 8.1 11.6 Sr-90 14.0 1 0.5 13 11 14.1 11.4 I I-131 8.3 11.2 3.7 + 0.2 4.4 10.7 K.40 --- 1260 + 120 ---
Cs-134 23.0 + 7.0 19.5 1 5.1 17.1 18.6 j
Cs-137 20.0 +, 4.0 19.7 14.7 23.5 1 8.4
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'I (1) Uncertainties are based only on counting statistics and are specified at the 95% confidence interval.
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SECTION III DUQUESNE LIGHT COMPANY TABLE III.7 1979 Annual Radiolog6 cal. Environmental Report (Page 2 of 2)
I TABLE III.7 QUALITY CONTROL DATA QC Sample comparisons (All Analyses in pCi/1 I Sample Date Ident. No.
Sample Type and Analyses.
Independent Lab (1)
OLC Contractor lab (1)
OLC - QC lab (1)
I Water: Sr-90 2-14-79 53-215 17.7 + 0.4 14 + 1 13.8 + 1.8 Cs-137 34.2 + 0.7 42 + 8 30 + 7 Co-58 21 16 27 18 23 15 Co-60 18 + 6 28 16 21 16 2-14-79 53-216 Water: H-3 1400 1 50 1550 1 100 1200 1 250 5-23-79 53-217 Water: Cs-134 9 16 11.4 + 6.8 11.5 1 6.7 Cs-137 13 + 6 19.2 1 5.4 22.6 18.7 I Sr-89 0.3 1 0.8 < 1.9 ---
Sr-90 33.6 1 0.7 25.0 11 30.0 1 1.5 Co-58 22 16 30.1 1 7.2 28.6 +, 8.9 Mn-54 52 + 9 55.4 + 7.8 65 1 10 5-23-79 53-218 Water: C-14 -- < 0.2 1 6.1 I 8-15-79 53-219 H-3 Water: Sr 90 Mn 54 1400 + 50 35.2 1 0.6 52.0 18 1290 1 110 26.0 +,, 1 60.0 + 7.2 1350 1 230 29.7 11.5 48.5 + 9.6 Co 58 14.0 + 5 27.0 + 7 26.6 + 9.1 15.2 + 5.8 <
Co 60 < 6 7.9 Cs 134 12.0 19 15.8 1 6.0 21.6 1 8.5 Cs 137 16.0 13 30.5 + 6.7 19.1 1 9.1 8-15-79 53-220 Water: C-14 --- 54.0 + 5.4
- 14.4 + 5.0
- H-3 1260 1 50 1280 +,, 90 1460 1 270 I 11-14-79 53-221 "Eter: Mn 54 Cs 137 18 + 6 16 13 54.6 1 5.5 20.2 + 5.0 48.7 1 10.7 28.7 1 8.1 36.4 + 0.7 I Sr 90 30 + 1 30.3 11.7 Co 58 18 + 6 22.1 + 4.4 12.8 + 10.6 Cs 134 15 18 11.4 + 4.3 1 7.5 l
Co 60 --- 27.4 + 4.9 26.2 1 10.5 11-14-79 53-222 Water: H-3 1000 1 70 1170 1 110 1100 1 270 C-14 ---
9.2 1 0.9 14.0 1 7.1 I
(1) Uncertainties are based only on counting statistics and are specified at the 95% confidence interval.
I
- The C-14 results for sample #53-220 are not as good as would be expected. The data were reviewed and and the specific cause could not be identified. However, subsequent analyses of samples53-222 and 53-31 were in excellent agreement (See Table 111.4 for sample 53-31 results).
I SECTION III DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report I
III. ENVIRONMENTAL MONITORING CONSIDERATIONS
- 7. Nuclear Regulatory Commission (NRC) Program The Nuclear Regulatory Commission (NRC) also conducted a I surveillance program in the vicinity of the site. Samples of air, river water, drinking water, milk, vegetation, ffsh, and radiation monitoring are included in their I 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 I Contractor laboratory.
B. Evaluation of the Quality Control (QC) Program Data I The split sample programs indicated that the Contractor laboratory was performing satisfactorily. In addition, three (3) independent laboratories were used to supplement the regular program. Comparisons I between the independent laboratories and the Contractor laboratory were acceptable, and demonstrate a satisfactory performance by the DLC contractor.
The results of the Quality Control Program give assurance that the radioanalytical data obtained by the DLC Contractor laboratory I in the Environmental Monitoring Program for 1979 is acceptable with respect to both accuracy and prec sion of measurement.
Standard Requirements and Limitations for Radiological and I
C.
Other Effluents The Shippingport and Beaver Valley Power Stations are governed I by rules and regulations of the Federal Gov'rnment and the Commonwealth of Pennsylvania. Effluent rele fses at both stations are controlled to ensure that limits set by Federal or State governments are not exceeded. In addition, self-I imposed limits aa e been established to further limit discharges to the environ:tenu.
I Shippingport Atomic Power Station is operated in compliance with regulations and perr i ts involving radioactive and other effluents.
Limits noted in De, 'ent of Energy (D.O.E.) Manual Chapters 0513 g and 0524, Ohio Rivet ._11ey Water Sanitation Commission (ORSANCO)
Standards No.1-70 and 2-70, Pennsylvania Department of Environmental
- 3 Resources - Industrial Waste Permit #1832, and Environmental Protection Agency (EPA) National Pollutant Discharge Elimination I System (NPDES) Permit #PA-0001589 are observed and followed.
I SECTION III DU M SE LIGHT COMPANY 1979 Annual m.,liological Environmental Report !
III. E_NVIRONMENTAL MONITORING CONSIDERATIONS I C. Standard Requirements and Limitations For Radiological and Other Effluents (continued)
Beaver Valley Power Station is subject to regulations which I include the Code of Federal Regulations 10 CFR, Pennsylvania Department of Environmental Resources (PDER) Industrial Waste Permit #0473211, Sewage Treatment Facilities Permit #0472411, I Gaseous Discharge Permit #04-336-001, 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 I Pollution Discharge Elimination System (NPDES) Permit #0025615, and the Beaver Valley Power Station Technical Specifications.
D. Significant Changes and Reporting Levels Statistically significant changes in radiological environmental monitoring results are defined as the median value (M) plus two I (2) times the 95% confidence interval (N), or ten (10) times the lower limit of detection (LLD) for each sampling media analyzed during the preoperational period 1972 - 1975. Analytical results for sampling media noted in the Beaver Valley Power Station I Environmental Technical Specifications, which were greater than than the statistically significant values determined in the pre-operational program (M + 2N or 10 x LLD), are values which require I reporting as an anomalous measurement. This report is forwarded to the Nuclear Regulatory Ct,mmission within ten (10) days after the completion of a confirming analysis.
I There were three (3) analytical results of environmental samples during 1979 which exceeded Beaver Valley Power Station reporting levels and are summarized in Table III.8. The surface water I tritium results were attributable to Beaver Valley discharges; however, all releases were well below limits noted in 10 CFR 20.
The high gross beta value of 26.0 pCi/ liter was for a March 1979 I composite of surface water. This relatively high activity is attributed to the bottom sediments contained in the sample result-ing from turbulent water conditions during sampling. The sediment j concentrations in this sample was 1.3 grams per liter. If the 5 gross beta activity of 26 pCi/ liter measured in the water sample is attributable entirely to sediments, the activity of the sediments would be 20 pCi/ gram of dissolved solids. Since gross beta measure-I ments of sediment sampled obtained during 1978 have resulted in activities between 13 and 64 pCi/ gram, it is concluded that the unusually high surface water activity was due to the solids from l
I the river sediments ant!. not from plant operation. To confirm this, part solids.
of the sample was reanalyzed af ter filtering out the suspended After filtering, the gross 8 result in the water was 6.7 pC1/ liter, which is within the range of activities normally found in surface water.
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SECTION III DUQUESNE LIGHT COMPANY TABLE III.8 1979 Annual Radiological Environm:ntal Report I
l TABLE III.8 Anomalous Measurements
- During 1979_
I l
Sample Date Environmental Media Site Location Reporting Level Level Found (Analytical Results) 1st Quarter is90 pC1/1 I
Tritium in Surface 2 1390 pCi/l 1979 Water (1) ist Quarter Gross S in Surface 3 18.3 pC1/1 26 pCi/1 l 1979 Water (2) l 4th Quarter Tritium in Surface 2 1390 pCi/l 4240 pCi/l 1979 Wat.ar (1)
I NOTE (1): Attributable to BVPS releases. (There were no releases which exceeded effluent limits for tritium as identified in 10 CFR 20).
(2): Attributable to natural radioactivity associated with large amounts i of suspended sediments in sample. When the sample was reanalyzed, I the activity in the sample containing only dissolved solids was less than 7 pCi/1, which is well below the Beaver Valley reporting level for surface waters. Sampling Site #3 is located below the Shippingport Atomic Power Station discharge structure. Shippingport Atomic Power Station did not release radioactive liquids in 1979. i l
Measurements which exceed the reporting levels in the Beaver Valley Power Station Environmental Technical Specifications.
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SECTION IV DUQUESNE LICHT COMPANY 1979 Annual Radiological Environmental Report )
.m IV. MONITORING EFFLUENTS
,5 Monitoring of Liquid Effluents A.
I Description of Liquid Effluents at the Shippingport Atomic Power Station and the Beaver Valley Power Station.
g Most of the water required for the operation of the Beaver valicy and Shippingport stations is taken from the Ohio
~5 River, and returned to the river, evaporated, consumed by station personnel, or discharged to a septic system. In addition, a smali cmount of well water and liquid effluents
_I is discharged to the Ohio River using discharge points shown in Figure 4.1. Figures 4.2 through 4.5 are schematic diagrams
- g 9 liquid flow paths for Shippingport and Beaver Valley g respectively. The following four (4) tables summarize '
radioactive liquid effluents at both the 'ihippingport and Beavcc Valley Power Stations:
= Table IV.A.1 - Effluent Treatment, Samt,2ing, and Analytical Procedures - Shippingport l
Table IV.A.2 - Effluent Treatment, Sampling, and Analytical Procedures - Beaver Valley Table IV.A.3 - Results of Liquid Effluent Discharges to the Environment - Shippingport Table IV.A.4 - Results of Liquid Effluent Discharges to the I Environment - Beaver Valley I
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l SECTION IV DUQUESNE LIGHT C0ZIPANY FIGURELI.3 1979 Annual Radiological Environmental Report EVAPORATION LOSSES h 1
BEAVER VALLEY POWER STATION COOLING Tob7.R OVER-PC:!PS7 FLOW 7
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wqmst um cum TABLE IV.A.1 SECTION IV 1979 Annual Radiological Environ = ental kport gy TABLE IV.A.1
- 1. Effluent 1reatment. Samoling, and Analytical Procedures - Shippingport Treatrent, Sampling, Standard and/or Effinent Type and/or Monitoring Analytical Procedures (a) Steam System Directed to radwaste system if Secondary water is sampled for Blowdown radioactive. Normally directed any radioactive contamination.
to discharge channel where it A 1000 mi sample counted in a is diluted by circulating cooling multichannel anaiyzer for 10 water. minutes for gross activity.
The counter can measure a minimum detectable activity (MDA) of 8.4 x 10-8 uCi/ml.
(b) Radioactive Collected, segregated, and A 3000 mi sample is counted for Waste Liquids processed as one of two types Co60 gamma activity. The counter of liquid wastes: can measure a minimum detectable I (a) special waste (b) radioactive waste activity (MDA) of 3 x 10-8 uCi/ml.
Sample taken of batch before processing to remove radio-activity and reuse in plant systems. See Figure 4.4.
TABLE IV.A.2
- 1. Effluent Treatment. Sampling, and Analytical Procedures - Beaver Valley Treatment, Sampling, Standard and/or Effluent Type and/or Monitoring Analytical Procedures Recycled or directed to Radwaste If discharged, procedures adhere (a) Steam System Blowdown System for discharge. to Technical Specifications.
(b) Radioactive Concentration of radioactive Procedures adhere to requirements Waste materials released in waste of Technical Specifications.
effluents shall not exceed values specified in 10 CFR20, Appendix 8. Table II for unrestricted areas, and the Environmental Technical Specifications.
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SECTION IV DUQUENSE LIGHT COMPANY TABLE IV.A.3 1979 Annual Radiological Environmental Report TABLE XV.A.4 l l
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TABLE IV.A.3
- 2. Results: Shippingport Effluent Type Results for 1979 (a) Steam System The boilers were periodically blown-down.
Blowdown The boilers are sampled prior to each blowdown. l There was no radioactive liquid discharged in J 1979.
(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 I less continuously from a high of 0.53 Ci in 1965 to a low of less than 0.001 Ci in the years 1974, 1975, 1976 and 1977. There was no radioactive liquid discharged in 1978 and 1979.
I
- 2. Results: Beaver Valley Effluent Type Results for 1979 (a) Steam System The Steam System Blowdown was recycled or Blowdown directed to the Radwaste System where it was monitored and discharged. No radioactivity was found in the water.
I (b) Radioactive Waste Liquids Liquid effluents from the Beaver Valley Power Station were released in accordance with conditions noted in the Environmental I Technical Specifications. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semiannual Effluent Report for 1979.
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SECTION IV DUQUENSE LIGHT COMPANY !
1979 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents
- 1. Description of Airborne Effluents
- a. Shippingport Atomic Power Station The potential source of airborne radioactivity associated with the Shippingport station is the radioactivity contained in the reactor coolant system. This system contains the activated corrosion and wear products, activated impurities in reactor coolant, and small quantities of fission products originated from naturally occurring uranium impurity and could become airborne from reactor coolant, sampling operations, and maintenance and overhaul operations which require opening the system or working on contaminated components removed from the system.
Stringent radiological controls which have been developed during 22 years of operations at Shippingport are exercised during the:m operations to prevent radio-activity from becoming airborne. Cobalt-60 is the nuclide of primary concern because of its long radio-active half-life and its concentration in reactor coolant. This radionuclide, present in the form of minute insoluble particles, cocid become airborne I during maintenance operations on contaminated components removed from this system. However, strict radiological surveillance is maintained throughout the operating I 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 Manual Chapter 0524. In I addition, air exhausted from potentially contaminated areas, such as decontamination and maintenance areas, is passed through high-efficiency particulate air I filters. These filters are routinely serviced, changed, and tested in-place.
The principle environmental release point for the Shippingport Atomic Power Station is the containment ventilation exhaust. This point is 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 I 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.
SECTION IV DUQUESNE LIGHT COMPANY FIGURE 4.6 I 1979 Annual Radiological Environmental Report SURGE TANKS RESIN STCRACE tat;KS FLASH TANK g SPRAY RECYCLE TANK I t0 u g
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FIGURE 4.6 SECTION IV DUQUENSE LIGHT CrdPANY 1979 Annuti Radiological Environmental Rsport IV. MONITORING EFFLUENTS
- a. Shippingport Atomic Power Station (continued)
Reactor plant exhausts from the Decontamination Room, Sample Preparation Room, Laundry Room, Radiochemistry Laboratory, Gascous Waste System, and Compacting Station are continuously sampled with fixed filter samplers.
These samples are analyzed weekly for gross beta, and composited monthly to identify gamma emicting isotopes.
Processing of noble gases (predominantly short lived Xe-133) is accomplished by collecting and storing the gases in Shippingport RWP vent gas system. After sampling and analysis, the gases are released when the storage tanks are full. Figure 4.6 shows a schematic diagram of the gaseous waste system in the radioactive waste disposal system ac Shippingport.
- b. Beaver Valley Power Station (BVPS)
The Beaver Valley Power Station identifies certain 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 principal gamma emitters I include noble gases, iodines, and particulates.
Figure 4.7 shows the gaseous radwaste system at Beaver Valley Power Station.
The environmental 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 the Elevated Release Point located on top of the Containment. These points are continuously monitored. Principal gamma emitters and tritium are analyzed on a monthly basis. Analysis is also done on charcoal cartridges for I-131, I-133, and I-135 that have continuously sampled the gas stream for a week.
I Weekly continuous samples are also obtained on filter paper to identify the particulates gamma emitting isotopes. Composites of the particulate samples are analyzed monthly for gross alpha determinations and quarterly for Sr-89 and Sr-90.
l I SECTION IV DUQUESNE LIGHT COMP m 1979 Annual Radiological Environmental Report FIGURE 6.7 I SEAftX VALLEY F0WER STATICN CASEQUS 1ADICACT!vt WA$TE FROC1351NG SYSTEM E
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SECTION IV DUQUESNE LIGHT COMPANT l
m 197 9 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS
- 2. Airborne Effluent Treatment and Sampling
- a. Shippingport Atomic Power Station Gaueous wastes stripped from the reactor coolant at the Shippingport Station are circulated through a n ydrogen analyzer and catalytic hydrogen burner system where the hydrogen is removed. The gases are I initially stored in a vent gas surge drum, and subsequently compressed and transferred to one of four gas storage drums. The decayed gases are sampled prior to release. In addition, the exhaust from the containment is equipped with high efficiency particulate air filters and monitoring devices to prevent releases of radioactive particulates. Protective devices are utilized in the event of high airborne activity to automatically seal off the primary containment to prevent an inadvertent release of radioactivity.
Reactor plant exhausts from the Decontamination Room, Sample Preparation Room, Laundry Room, Radiochemistry Laboratory, and Compacting Station are also equipped with high efficiency particulate air filters, and are continuously monitored for radioactive particulates by the use of fixed filter monitors. Exhausts from the Gaseous Waste System are filtered and sampled for radioactivity at the release point also. Continuous I 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 both Beaver Valley Power Station and Shippingport Atomic Power Station.
- b. Beaver Valley Power Station Radioactive gases enter the gaseous waste disposal I system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most l of the water vapor. Radioactive gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and l
traces of xenon, krypton, and iodine are also present in the gaseous effluent.
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,l 5 SECTION IV DUQUENSE LIGHT COMPANY FIGURE 4.8 1979 Annual Radiological Environ:nental Report l
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l SECTION IV - FIGJRE 4.8 DISCHARCE PotNTS - CASECUS VASTIS Vent 11ation Vent \
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Containment ventilation System (Containment Air I '
Normally recirc.-not vented Aux 11 Lacy Building Ventilation System Exhausts Caseous vastes to Cooling Tower; and Air Ejector I -
CASEOUS RELEASF POUCS - BEAVER VALLEY PCWER STATICM p
I Waste Disposal Building
=
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. Service Bldg. Edausts (Filtered)
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Caseous Waste Release (Filtered) Air Ejector cAsteUS PELEAst 'oncs SMI??IycPcRT ATcMic ocurR STATrew i !
FIGlRE 4.8 I D** * 'T
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SECTION IV DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmrntal 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 I 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 I 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 I discharge, the flow of the waste gases from the decay tanks is recorded and rapidly diluted with about 1100 scfm of air in order to limit hydrogen concen-tration. The gases are then combined with the containment vacuum system exhaust, aerated vents of the vent and drain system, and the main air ejector effluent. The mixture is then filtered through one of the gaseous waste disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the cooling tower. The radioactivity levels of the stream are monitored continuously. Samples are also taken periodically to determine the rate of activity released to the atmosphere. Should the radioactivity release concentration of the stream I by above the allowable setpoint, a signal from the radiation monitor will stop all flow from the decay tanks.
During a shutdown period after the containment has been sampled and the activity levels determined, the I containment may be purged through the elevated release or, if the activity is low level, through the vent 11a-tion vent located on top of the Auxiliary Building.
!g Areas in the Auxiliary Building subject to radioactive l E cont *=iancloa are =onteored for radioactivity prior to entering the common ventilation vent. These individi'al I radiation monitors aid in identifying any sources of contaminated air. The ventilation vent is also monitored continuously and sampled periodically. Upon a high radiation alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the supplementary leak collection and release system and to the elevated release point.
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SECTION IV DUQUESNE LIGHT COMPANY I 1979 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS
- b. Beaver Valley Power Station (continued)
Each filter tank consists of roughing filters, charcoal filters, and pleated glass fibre type HEPA filters. The roughing filters remove large particulates to prevent I excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the HEPA filters remove particulates and charcoal fines.
- 3. Analytical Procedures for Sampling Airborne Effluents
- a. Shippingport Atomic Power Station The following tabulates the gaseous sampling and analysis schedule:
Vent Gas Decay Tank Releases Sampling Type Of Detectable Sample Type Frequency Activity Analysis Concentration I Gas from Decay Tank Prior to Discharge Gamma Ray Spectrum of Gas Sample
- 1 x 10
~0 pCi/cc Gas from Prior to H-3 2 x 10~ pCi/cc Decay Tank Discharge Gas from Prior to C-14 1 x 10~ uCi/cc Decay Tank Discharge I
- A gas sample of measured volume is counted in a multi-channel analyzer for 10 minutes for gross activity. The counter has a minimum detectable activity (MDA) of 1 x 10-8 uCi/cc for the predominant nuclide of Xe-133.
l
1 DUQUENSE LICHT COMPANY l 3ECTION IV 1979 Annual Radiological Environmental Report IV. HONITORING EFFLUENTS 3 Analytical Proce.fures for Sampline Airborne Ef fluents (continued)
Air Exhausts I Sample Type Sampling Frequency Type of Activity Analysis continuous Cross Camma Detectable Limits 1.2 x 10 pCi/cc (Cas, (1) Air from the Plant Ventilation I Exhaust Effluent Stream Channel 8 ORMS)*
5 x 10-10 ,cgjc, (Particulates Channel 12 ORMS)*
Continuous Cross Beta 1 x 10~I' pCi/cc (2) Particulate Filter in Plant Weekly Sample (Particulate)
Ventilation Effluent Stream 1 x 10 ,,C1/cc Particulate Filter in Plant Continuous Principal Camma I Ventilation Effluent Stream Monthly Composite
- (Weekly if Cross Beta 11 x 10-13)
Particulate I
~
Particulate Filter in Plant Continuous Cross Alpha 2 x 10 " uC1/cc Ventilation Effluent Stream Monthly Particulate Particulate Filter in Plant continuous Sr-89, Sr-90 $ x 10 ~I4 uci/ml (Sr-89)
I Ventilation Effluent Stream (3) Charcoal Cartridge in Plant Continuous Quarterly I-131 1 x 10 Particulate
~
1 x 10 " uci/mi uCi/ml (Sr-90)
I Ventilation Effluent Stream Charcoal Cartridge in Plant Ventilation Effluent Stream Monthly Weekly 1-133. I-135 Monthly 1 x 10~I 1 x 10" pCi/ml (I-133) uci/ml (I-135)
(4) Evacuated Bomb Sample In Monthly H 2 x 10 (H )
Plant Ventilation Ef fluent Stream I (5) Particulate Filter in Reactor Plant Exhaust from Decontami-nation Room, Sample Preparation Room, Laundry Room, Radio-Continuous Cross Beta Weekly 1 x 10~I' uCi/cc Particulate chemistry Laboratory, Caseous
.I Waste System, and Compacting Station.
Continuous Principal Camma 1 x 10 uCi/cc I
Particulate filter in Reactor Plant Exhaust from Decontam4- Monthly Composite Particulate nation FMom, Sample Prep % ation (Weekly if Cross Room, Laundry ? ~ %dio- Beta 1 1 x 10'13) l chemistry Laboratory, Caseous i
Waste System, and Compacting Station.
ORMS - Operational Radiation Monitoring System I
e Although the ORMS Channels have no specific function as far as ef fluent monitoring and reporting is concerned, these two (2) channels are being listed for information purposes. It is also n d that these channels provide alarm functions in the Main Control Room when levels of 1.2 x 10'gte uC1/cc are reached on Channel 8, or 1 x 10' uCi/cc on Chann Additionally, they shut the ventilation system butterfly valves when levels of 1.2 x 10'g1 12. are reached on Channel 8 or uC1/cc 1 x 10~7 uC1/cc on Channel 12.
1 DUQUENSE LIGHT COMPANY SECTION IV 1979 Annual Radiological Environmental Report I IV. MONITORING EFFLUENTS
- 3. Analytical Procedures for Sampling Airborne Ef fluents (continued)
- b. Beaver Valley Power Station The following tabulates the gaseous sampling and analysis schedules Detectable Sampling Type of Concentrations Gaseous I Source (1) Waste Gas Decay Tank Frequency Each Tank Activity Analysis Principal Gamma Emitters (uci/ml)a 10 6
Releases Principal Camma Emitters 10 (2) Containment Purge Each Purge Releases 10 H-3 I
Principal Gamma Emitters 10 (3) Environmental Release Monthly Points (Gas Samples)
E-3 10-6 Weekly I-131 10 (Charcoal Sample)
-10 Weekly I-133. I-135 10 I (Charcoal Sample)
Weekly (Particulates)
Principal Gamma Emitters (Ba-La-140, 1-131, and 10
~11 I
others)
~11 Monthly Composite Gross a 10 (Particulates)
-11 I
d 10 Quarterly Composite Sr-90 and Sr-89 (Particulates)
I
- The above detectability limits for activity analysis are based on technicalFor the potential significance in the environment of the quantities released.
lower detection limitr. may be readily achievable, and when nuclides are measured below the stated limits, they a tould also be reported.
feasibility and on some nuclides, For certain mixtures oi 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 mw h hayher levels. Under tt.ese circumstances, it will be more appropriate to calculate the I les da of such radionuclices using observed ratios with those radionuclides which are measurable.
- Analyses shall also be performed following each refueling, startup, or similar operational occurrence which could alter the mixture of nuclides.
d To be representative of the average quantities and concentrations of radioactive materials in particulate form released in gaseous effluents, samples should be collected in proportion to the rate of flow of the effluent stream.
SECTION IV DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report i
i IV. MONITORING EFFLUENTS
- 4. Results
- a. Shippingport Atomic Power Station Analyses for r% particulate airborne radioactivity in the plant effluents indicated that the gross alpha and gross beta activity concentrations were at or very near the min'. mum detectable a '.vities (MDA). Analytical results of charcoal filte samples showed that there was one instance of radioioJine concentrations above MDA. This instance occurred u N- *he period between September 24 to October 1, 1979, .. attributed to a small primary coolant leak. The co centration I observed at this time was 8.8 + 2.90 x 10-14 pCi/cc.
The measured level of radioiodine was less than 0.1%
of the permissible concentration outlined in 10 CFR 20 Appendix B and resulted in a total release of 0.0000011 I curies.
The total releases of gaseous radioactivity from the Shippingport Atomic Power Station were approximately 0.008 curies of Xe-133 activity and .00009 curies of Kr-85 activity. These amounts of radioactivity released from the Shippingport Atomic Power Station during 1979 are extremely small and had a negligible effect on the environment.
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l SECTION IV DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report
- 4. Results (continued)
- 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 i the Beaver Valley Power Station Semi-Annual Effluent i Reports for 1979.
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1 ll 11 I -
SECTION IV DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS C. Solid Waste Disposal at the Shippingport and Beaver Valley Power I Stations During normal operations and periodic maintenance, Shippingport and Beaver Valley Power Stations generated small quantities of radioactive solid waste materials such as evaporator concentrates contaminated rags, paper, plastics, filters, spent ion-exchange resins, and miscellaneous tools and equipment. These were disposed of as solid radioactive waste.
At Shippingport Atomic Power Station and the Beaver Valley Power Station, the compactable wastes were segregated and compressed in a 55-gallon compactor to minimize disposal volumes. The compressed waste, plus other drums of noncompactable waste, were then shipped l offsite for disposal at a commercial radioactive material burial l site licensed by the Nuclear Regulatory Commission (NRC) or a state under agreement with the NRC. No radioactive waste material was buried at the Shippingport or Beaver Valley Power Station site.
All containers used for packaging, transport, and disposal of radioactive materials met the requirements of the United States Department of Transportation and the Nuclear Regulatory Commission.
Shipments offsite were made in accordance with Department of Transportation regulations. Figure 4.9 depicts solid waste handling at the site.
In 1979, the Shippingport plant generated a total of 3072 cubic feet of radioactive solid waste having a total radioactivity of I 4255.19 curies. This included three (3) shipments of low level wastes, three (3) shipments of irradiated components and one shipment of radioactive sources.
At Beaver Valley Power Station approximately 8626 cubic feet of radioactive waste were shipped offsite. The nineteen (19) shipments contained a total activity of 242.2 curies.
Industrial solid wastes from both plants were collected in portable bins, and removed to an approved offsite burial ground. No burning or burial of wastes was conducted at either the Beaver Valley or Shippingport plant.
I DUQUESNE LIGHT COMPANY FIGURE 4.9 SECTION IV 1979 Annual Radiological Environmental Report SOLID WASTE DISPCSAL DIACRAM FIGURE 4.9 SECTION IV RADIOACTIVE SOLID WASTE DISPOSAL Sludge Dru ming- .
Radioactivt? Waste % .
Disposal Evaporator Station 3
,P s a
'on an'cicY -
Misc. Radioactive . Cc=pactor and .
Solid Wastes Druu=ing Station $
sa
?>
9 8 Spent Radioactive Special Shipping _
Q c.
Resin Casks & Containers ,, ,
( E
__go' ryto o- g INDUSTRIAL SOLD VASTE DISPOSAL DT.ACRAM Water Filtered; i Filt ers dru=med----
1 3
d9 Sludge Frem Water f, ) .
Treatment Plant and g gt zg , j Sevage Treat =ent g Planc (3VPS) w Trash Basket - Beaver Valley u Debris and Trash Hopper t Screenheuse Shippingporg 3 From Screenhcuse , g
'O Q O
E m
?
TrasT'. Carbage Storage 3tn g o
FIcupe 4.9 CO M U D**D w] ~TYM
'D
.co 1. .NinLa
SECTION V-A DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. E_WIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program j
- 1. Program Description The program consists of monitoring water, air, soil, river bottoms, vegetation and fooderops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table V.A.l. Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are included in parts V-B through V-I of this report.
V-B - Air Monitoring V-C - Sediments and Soil 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 m m m M m M TABLE V. A.1 $
'l COtiSOLIDATED ItADIOLOGICAL ENVIRolciENTAL H0hlTORING PROGRAM Ez e
Sample Sar:p12 Analysis Sanple Point Descriptioi Sac:pling Frequency Preparation Frequency Analyses Type of Sample Points Cross 8
- 1. Surface 1 Outfall of Peggs Run Intermittent Monthly Composite nf Wekly Cross =
Station discharge (BVPS) Sample v - scan Vater 2 Shippinc. port station discharge Quarterly Composite H-3, St-89, St-90 3
5 East Liverpool water plant Co-60 C-14 _,
(raw water) E 49(a) Upstream side of Montgomery Dam N
E a*
i?8
- 2. Drinking 4 M Hland water plant (created Intermittent Weekly Co:nposite of Daily o.g s
neer) Sar.ple y - sean, T-131 og
$ Honthly Couposite Cross =1 Cross 6 oa 3
5 East Liverpool water plant quarterly Corposite 11-3. Sr-3 D r *.,0, (created water)
Co40, C-14 0,h
- m'i en Station Discharge (BVPS) Semi-annual Composite of edible parts y - scan on edible partions d
- 3. Fish 2 by species (d) pg 3 Shippingport Station Discharge Mi 49(a) Upstream side of Montgomery Dam f,
g 6Y Semi-Annual - y - scan B Q Q 4. Sediment 2,493(*) Station discharges St-89 (except for sediment), 3 Upstream side of Montgomery Dan b Sr-90 h Cross 8, Cross =
50 Upstress side of New Cu=terland Dua Uranium isotopic on-Site W 11 Quarterly - y - scan u 5. Groundwater 9 H-3 y 11 Shippingport, PA g 13 Heyers Farm Crosa 8 Cross = p b y, 14 Ilookstown, PA 15 Georgetown, PA b
b
M i m
TABLE V.A.1 g CONSOLIDATED RADIO 1DCICAL ENVIRONMEM AL HONITORING PROGRAM d (ContinueJ) g e
Sample Sample Analysis ,
Type of Sample Points Sample Peint Description Sampling Frequtncy Preparation Frequency Analyses Meyers Fara Every Three Years 12 core samples - y - scan
- 6. Soil 13 22 South of Site 2" Deep (3" Sr-90 27 Brunton's Dairy Diameter) at each Cross 6 29A Nichols Dairy Fara location. Approx. Cross =
30 Shippingport 10' radius. L'ranium Isotopic 32 HiJland, PA 46 Industry, PA 47 East Liverpool, Oli g w
48(a) Wei r t on , WV e 51 Aliquippa, PA N
- 7. Hilk 25 Searight Dairy Weekly Weekly sample from Searight's Only 1-131 {
y - Scan g 25 27 Searight Dairy Brunton Dairy Monthly Monthly sample when milk is available. Sr-89, Sr-90, 1-131 gj i 29A Nichols Dairy OJ y 36 Bertuvic (g) (h) g-m 57 Bailes 3
59 60 Irons llaney bo 61 Allison 62 Lyons g 35
- 8. Air 13 Heyers Farm Continuous Weekly Composite Cross 8. 1-131 27 Brunton Dairy Monthly Composite (b) y - scan E 28 Sherman Dairy Farm Quarterly Composite (b) Sr-89, Sr-90, [
298 Beaver County liospital Cross = q Shippingport o 30 32 Midland, PA 46 Industry, PA 47 East Liverpool, 011
{} 48(a) Weirton, WV
% 51 A11gulppa, PA
- 9. Direct 10 Shippingport, PA Continuous Quarterly (* y - Dose Radiation 13 Heyers Dairy Farm (TLD) Ar'""*l(e) 14 Ilookstown, PA 15 Ceorgetown, PA 27 Brunton's Dairy b ch 28 Sherman Dairy Farm g i i 298 Beaver County llospital p m
g 32 45
- lidland, PA Mt. Pleasant Church <
2= '
46 Industry, PA i 47 East liverpool, OH b 48(a) Weirton, WV 51 Aliquippa, PA Other locations are sampled based on n. ilk Pow r Vallana((ses.er Station's Technical Specifications identify sample points 25, 27, and 29A.
- Be0150ay pa
M M M m g
TABLE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL. MONITORING PROGRAM Q (Continued) d z
Sample Sample ,
Sampling Frequency Preparation Analyses p Type of Sample Points Sample Point Description Searight's Dairy Monthly Monthly v - scan
- 10. Feedstuff and 25 b"""*' '*E* Quarterly Composite Sr-90 Fruit and Vegetables grown Annual at harvest Composite of edible y - scan
- 11. Food Crops --
I-131 on green within 5 miles of site if available parts (one sample from Shippingport leafy vegetables g when available).
y E.
n
~
NOTFS (a) Control sample station: These are stations which are presumed to be outside the influence of plant effluents.
_ EE In cases in which the sampling frequency is periodic, a composite sample is a grab sample taken from Sg (b) Corposite samples o, p the well mixed total of the equal-sized periodic samples. For instance, a quarterly composite sample of monthly samples is a portion of the mixture of three, equal-sized monthly samples. y 4 n a-(c) In these cases, a y - isotopic analysis is done if the gross 8 value is higher than the high 95 percentile value determined tg 1
from previous values.
mg En (d) The fish samples contain whatever species are available, if the available sample size permits, then the sample is separated "Q 3 "U according to species and compositing will provide one sample of each species. If the available size is too small to make separation by species practical, then edible parts of all fish in the sample are mixed to give one sample. hk f+
(e) Two (2) TLDs are collected quarterly and annually from each monitoring location. Several TLDs were lost or stolen dgring i the year, O
o, (f) Hidland Only. r, (g) Dairies selected in conformance with BVPS-ETS which requires sampling at datries with highest potentic.1 dose pathway.
(h) Milk obtained from goats.
ADDITIONAL NOTES: - Sample points correspond to site numbers shown on maps.
- All Iodine-131 analyses are Performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sample collection if possible.
- All air samples are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for gross Alpha and Beta.
N R
m
M M M M M M m
TABLE V.A.2 h a
td 4
ENV!m4: ENTAL RADIOLOGICAL DONITORING PROGRAM StMIARY 1 p
Name of Facility Duquesne Light Company Docket No.
Location of Facility Beaver, Pennsylvania Reporting Period Annual 1979 (County, State)
Number of 5 Analysis & Lower Limit .
Location with liighest Quar. Mean Control Locations Nontoutine j Medium or Pathway Total Number of All Indicator Locations * % an(f,) **Mean(f) Reported of Analysis Detection ** Hean (Tj Name Measuremerts*"
Sampled Distance 4 Directions ** Range - ** Range Perforised (LLD) **Rance (Unit of Measurement) Weirton,WV848 P
36 (520/520) Heyer Dairy 813 37(52/52) 37(52/52) 0*
Airborne Particulate Gross (520) and Radioiodine 8 eta 2.5 (16-87) 1.6 antes - SW (23 64) (16-87) faE (a 10-3pC1/Cu.M)
Aliquippa, Pa851 4.4(4/4) 4.1(4/4) 0 $
o Gross (40) 1 3.6 (40/40) (2.8-5.4)
Alpha (1.9-6.3) 8.5 miles - LSE (2.7-5.8) g O tus Brunton Dairy s27 2.l(1/4) LLD 0 %p y $r-89(40) 1 2.1 (1/40)
- 7.3 miles - SE -
ns Beaver County Hospitals 298 0.62(3/4) 0.54(3/4) 0 Sr-90(40) 0.2 0.48(33/40) 8 miles - ENE (0.32-0.78) (0.25-0.76) pn (0.16-0.91) <: o 10 Lt.D
- - - - Q%
O I 131(520)
$pd te Casima(120) East Liverpool,OH847 120(12/12) 116(12/12) 0 Be-7 20 111(320/120) S (45-162) 6.5 attes - W (82-162) (102-161) >
59(2/12) 34 (1/12) 0 L-40 20 41(12/120) Shippingport.PA 830 g (13-87) 0.3 mile - ESE (32-87) -
'u 0
Midland pas 32 to (1/12) LLD 0 Ru-106 5 10(1/120) -
e et 5$
%G g4
- Nominal Lower Limit of Detection (LLD) Fraction of detectable measurements et specified locations is indicated in parentheses (f)
Hean and range based upon detectable measurements only.Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 19 kI e.a (Appendis 8) D
M M M M M M M M M M M un TABLE V.A.2 M O
E
$4 ENVIRONMENTAL RADIOLDCICAL MONITORING PROCant Stas 4AaY Name of Facility Duquesne Light Company Docket No.
Location of Facility Beaver. Pe'nnsylvania Reporting Period Annual 1979 (County, State)
W w
Analysis 4 Lower Limit Number of
- Medium or Pathway Total Number of All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine Sampled of Analysis Detection ' Mean (f) Name * % an(f) "Mean(f) Reported g (Unit of Measurement) Performed (LLD) " Range Distance & Directions ** Range " Range Measurements *** p h
Airtorne Particulate and Radiolodine Cs-137 0.6 1.7 (45/120)
(0.68 3.0)
InJustry, PA846 2.0 miles - NNE 2.1 (5/12)
(1.3-3.0) 1.4 (5/12)
(0.95-1.7) 0 "o C (a 10~3 PC i/Cu.M)
(con't) p ge$j g
Co-141 2 2.1 (2/120) Sherman Dairy.828 2.1 (1/12) LLD 0 mv I
M (2.0-2.3) 9.4 miles - N -
Me t*
W H I D. O Co-144 5 4.7 (21/120) Sherman Dairy.828 6.3 (2/12)
(2.9-9.8) 4.5 (4/12)
(1.0-8.8) 0'
- rg (1.0-9.8) 9.4 miles - N m DO Th-228 1 3.6 (4/120) East LLverpool, 011847 5.0 (1/12) 2.4 (1/12) 0 g9 (2.4-5.0) 6.5 miles - N - -
g 0
Others V.A.5 LLD - - - -
y H
o O
- 1 at
^H
$b o.o r*t'l Nominal Lower Limit of Detection (LLD) .
" Mean and range based upon Jetectable measurements only. fraction of Jetectable measurements at specified locations is indicated in parentheses (f) ",
0 Da
- Nonroutine reported measurements are defined in Regulatory Guide 4.8 (Decer.ber 1975) and the leaver Valley Power Station Technical, Specifications n (Appendia B) H v
E E l in M
l TABLE V.A.2 Q i
8 z
ENi1RONMENTAL RADIOLOGICAL HONITCHNG PROGRAM SibNARY 4 i
Name of facility Duquesne Light Company Docket No. p Location of Facility Seaver, Pennsylvania Reporting Period Annual 1979 (County, State)
Analysis 4 Lower Lialt Number of 5 Medium on Pathway Total Number of All Indicator Locations Location with liighest Quar. Mean Control Locations Konroutlas y Sampled of Analysis Detection ** Hean (f) Name "Mean(f) "Mean(f) Reported (Unit of Measurement) Performed (LLD) " Range Distance 4 Directions " Range " Range Measurements ***
Montgomery Das #49 g Sediment Cross (8) 5 16 (7/8) SAPS Discharge 803 24 (2/2) 13 (2/2) 0 e (pci/ge) Alpha (9.1-33) River Mile 34.8 (14-33) (9.1-16) y (dry weight) ko Gross (8) 1 28 (8/8) SAPS Discharge d33 River Mile 34.8 34 (2/2)
(32-36) 31 (2/2)
(28-33) 0 $%
o en Sota (13-36) 8 0.1 !
5h 00 U Sr-89 (8) LLD - - -
i EC Sr-90 (8) 0.03 0.06l (3/8) >bntgomery Dam 849 0.073 (2/2) Same as 0 k9 H
(0.038-0.081) River Mile 31.0 (0.065-0.081) lingh Location 7]
Camma (8)
NO
<o Be-7 0.3 1.5 (6/8) SVPS Discharge 802A 2.5 (2/2) 0.65 (2/2) 0 y@
(0.63-2.5) River Nile 35.0 (2.4-2.5) (0.64-0.67) o K-40 0.5 12 (8/8) 8vPS Discharge 802A 15 (2/2) 11 (2/2) 0 (5.4-16) River Mile 35.0 (15-15) (10-12) %
H Co-60 0.04 0.48 (2/8) SVPS Discharge 802A 0.48 (2/2) Same as 0 (0.20-0.76) River Mile 35.0 (0.20-0.76) liigh 1.ocation g Cs-137 0.02 0.29 (7/8) 8vPS Discharge 802A 0.41 (2/2) 0.26 (2/2) 0 E (0.067-0.45) River Mile 35.0 (0.38-0.45) (0.24-0.28) Q Co-144 0.2 0.61 (l'/8) SAPS Dischargo 803 0.61 (1/2) LLD 0
- River Mlle 34.8 -
Ra-226 0.6 2.6 (7/8) hvPS Disch.irge 802A 3.7 (2/2) 2.5 (2/2) 0 (I.1-4.2) River Mile 35.0 (3.2-4.2) (2.4-2.6)
Nominal Lower Limit of Detection (LLD) u
" Hean and range based upon detectable measurements only. Fraction of detectable sessurements 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 O >
m (Appendia 8) u H
U M M -
un t's TABLE V.A.2 g H
o 2:
<1 g
ENVIR0lolENTAL RADIOLOCICAL HON 11DRING PROGRAM SLS$1ARY Docket No.
Name of Facility n. men, t1.hr re.nnny tacation of Facility n,,,,, p,nnsyiv,nt. Reporting Period Annual 1979 (County, State) e w
Analysis & Lower Limit Number of
- McJium or Pathway Total Number of All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine Sampled of Analysis Detection ** Hean (f) Name *
- Nea n (f) - * % anif) Reported g Performed (LLD) **Rance Distance & Directions ** Range ** Range Measurements *** g3 (Unit of Hessurement) h H
SVPS Discharge 802A 1.9 (2/2) 1.3 (2/2) 0 n 1.3 (8/8)
Sediment Th-228 0.02 (pCL/gn) (0.48-1.9) River Nile 35.0 (1.9-1.9) (1.3-1.4) ~ ga.
ggc:
(Jry weight) - - - -
gg (con't) Others TrSle V.A.5 LLD rg i
j l'3
$ Uranium Analysis M **
1 U-233*U-234 0.01 1.0 (8/8) BVPS Discharge 802A 1.5 (2/2) 0.72 (2/2) 0 QH e
(0.40-1.6) River Nile 35.0 (1.5-1,6) (.66-0.79)
U-235 0.01 0.053 (7/8) SAPS Discharge 803 0.083 (2/2) 0.035 (2/2) 0 $n (0.020-0.097) River Mile 34.8 (0.070-0.097) (0.050-0.035) $S80
- 1 0.67 ($/8) BVPS Discharge 802A 1.0 (2/2) 0.50 (2/2) 0 0D U-238 0.01 (0.29-1.1) River Mile 35.0 (0.87-1.1) (0.41-0.60) $M o
D S
e-5 2+1 re
^ *4 5$
00 r*
. ~ - . a g,t
- Nominal Lower Limit of Detection (LLD) f
- Nean anJ range based upon detectable measurements only. Fraction of detectable measurements at specified locations is inJicated in parentheses (f) O >
- Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications w (AppenJim 8)' s v
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TABLE V.A.2 g 8z LNVIROEVTAL RADIOLOGICAL FONITORING FROGRAM StMARY l Name of Facility Dmuesne Lieht Company Docket No. p Location of Fac!!!ty . Beaver. Pennsylvania Reporting Period Annual 1979 (County. State)
Number of 5 Analysis &
Total Number Lower Limit All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine y Medium or Pathway of "Mean(f) Reported Sampled of Analysis Detection " Mean (f) .%ame "Nean(f)
Distance 4 Directions " Range ** Range Measureme nt s***
Performed (LLD) " Range (thit of Measuremeet)
Searight Dairy 825 - One Sample 0 Feed & Forage Sr-96(4) 0.003 t1 (pCi/gs) 2.4 miles - Sit loc tion 5.b ywg 0
+
Camma(14)
- - 0 EN di Be-7 0.3 1.4 (8/14) -
e ao g,,,
y (0.88-3.1) 0" H
- - 0 K-40 0.5 19 (14/14) -
(4.8-44) p!
- 8 eg Cs-137 0.03 0.11 (6/14) - - - 0 gD o
(0.067-0.17) (a 4 p
- - - 0 E Co-141 0.05 0.31 (1/14) H E
0.2 0.64 (2/14) - - - 0 3e1 Co-144 j
i (0.62-0.67) *
(
- - 0 1h-228 0.04 0.12 (2/14) -
(0.13-0.32)
Others Table V.A.5 LLD ed b
N
- 4 .
- Noet -I Lower Lisle of Detection (LLD)
- Mean and range based upon detectable measurements orly, fraction of detectable measurements at specified locations is indicated in parentheses (f) 0
"* Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the 8eaver Valley Power Station Technical Specifications p (Appendia B) U
M m M M M M m m m m m
tg TABLE V.A.2 Q 0
=
4 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SLANARY ,
Name of Facility Duquesne Light Company Docket No.
tocation of Facility Beaver. Pennsylvania Reporting Period Mnumi 1979 (County, State)
Analysis & Lower Limit Number of 8 Medium or Pathway Total Number of All Indicator locations Location with Highest Quar. Mean Control Locations Nontoutine SampleJ of Analysis Detection " Mean (f) Name **Mean(f) **Mean(f)
- Range Reported Mea surement s"*
g (tinit of Measurement) Performed (LLD) " Range Distance 4 Directions ** Range p C
k M
CarJen Crops I-131(5) 0.004 LLD - - - - g (pci/ga) . :o c2 M4 (wat weight) Camma(5) gh Be-7 0.27(2/5) Georgetown PAst5 0.40(1/3) - 0 **
0.02 O (0.13-0.40) 4.6 miles - WNW - r$
o td 8
y g
K-40 0.5 4.2(5/5)
(2.9-5.3)
Shippingport.PA810 0.3 miles - ESE 5.3(1/1)
- 0 $e gH H
Cs-137 0.009 0.027(2/5) Shippingport.PAa10 0.032(1/1) - 0 (0.022-0.032) 0.3 miles - ESE - En
<o Th-228 0.02 0.056(1/5) Shippingport.PAa10 0.056(1/1) - 0 $k
- 0.3 miles - ESE -
Others Table V.A.5 LLD - - . - g r,
b t c if l O I
e1 l rs a +4 5$
'll E; Nominal Lower Limit of Detectir.n (LLD) M4* *
- Mean and range based upon detectable measurements only. fraction of detectable measurements at specified locations is indicated in parentheses (f) o>
en *
- " Nonroutine reported measurements are defined in Regulatory Culde 4.8 (December 1975) and the Seaver Valley Power Station Technical Specifications g (Apper41x 8) g d
l
- Ift a okg%
NhO*2 44 o:cc%si nt "
4 $o@ $ SH N 2 ;;
I
" & d H$* g"y>$oE8$e8 s M 1
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t t m t
- - 0 0 0 0 -
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a NN d c M
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- r 4.1 2(
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' TABLE V.A.2 Q a
- 4 ENVIRONMENTAL RADIOLOGICAL Dil1titRING PROGRAM StH4ARY a Name of Facility Duquesne Light Company Docket No. >
Location of Facility Seaver, Pennsylvania Reporting Period Annual 1979 (County. State) v Number of
- Analysis & Lower Limit Location with Highest Quar. Mean Control Locations Nontoutine e Medium or Pathway Total Number of All Indicator Locations Saepted of Analysis Detection " Hean (f) hame "Mcan(f) "Mean(f) Reported Performed (LLD) " Range Distance 8 Directions " Range "Ra ng e Mea su rement s"*
(Unit of Measurement) tfeirton. WV 848 5 t3 External Radiation TLD-t(50 Quarterly) 0.05 0.20 (M n o) Beaver County Hosp.8298 0.23(4/4) 0.20(3/3)(a) 0 gg (mR/ Jay) (0.12s . 4) 8 miles - ENE (0.21-0.25) (0.81-0.22) o.g o en rx g TLD-y(11 Annual) 0.05 0.20(11/11) Beaver County ttosp.8298 0.23(1/1) , (a) 0 $M o (0.17-0.23) 8 m!!ss - ENE -
p[
>n t vy Nn 40 k
a ?:
il. 4 V.
e
?
o O
et rs (a) The annual and fourth quarter TLDs were missing at station.84S on date of exchange with new year.
% 5; e <3
- No.inas Lower Limit of Detection (LLD) *
" Haan and range basoJ upon detectable measurements only. fraction of detectable measurements at specifieJ focations is indicated in parentheses (f) o>
- " Numroutine reported measureacnts are defined in Regulatory Guide 4.8 (Deccaber 1975) and the Beaver Valley Power Station Technical Specifications g p
(APpendia B)
D
E40u$ yle OOkp.4 s t5 r h 4.> n M umO 5 z :* a >
s a5 $ go ovnW gey :e cL 5 O$o S Q N<&oB.Os>W 5 inte r
M )
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9 4
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TABLE V.A.2 O
8 z
~
4 E.W1RONMENTAL RADIOLOGICAL MONITORING PROGRAM SGNARY 8
Name of Facility DW uesne Light Company Docket No. p Location of Facility Beaver. Pennsylvania Reporting Period Annual 1979 (County, State)
H Number of e Analysis & Lower Limit g" Medium or Pathway Total Number of All Indicator Locations Imcation with Highest Quar. Mean Control Locations Nonroutine of Analysis Detection ** Pean (f) Name * % am(f) **Mean(f) Reported Sampled Performed ** Range Distance & Directions ** Range ** Range Measurements ***
(Unit of Measurement) (LLD)
Georgetown. Pas 15 g Heyers Dairy 813 1.3(1/4) LLD 0 g Ground Water Gross (20) I 1.2 (2/20)
(pC1/2) Alpha (1,1-1,3) 1.6 miles - SW -
o.
Gross (20) . 2.5(19/20) Heyers Dairy al3 3.l(4/4) 1.6(3/4) 0 @
m :a; l Beta (1.1-5.3) 1.6 elles - SW (1.5-5.3) {1.11.9) OM e
Tritium (20) 200 340(19/20) BVPSa9 430(4/4) 350(4/4) 0 E t*
f (120-720) On-Site (190-590) (180-720) $H H O
' N Cama (20) Table v.A.5 LLD - -
O ns O
B.:iy D
h H
- o O
et rt
- g4n.
- Nominal Lower Limit of Detection (LLD) u.
- Hean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
- Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications oI mN (Appendix B)
' W
SECTION V - A DUQUENSE LIGHT COMTANY 1979 Annual Radiological Environmintal' R: port I V. ENVIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program (continued)
- 2. Summary of Results l l
All results of this monitoring program are summarized in Table V. A.2. .'his table is prepared in the format specified by NRC Itegulatory 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 summaries 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 the few cases where activity was detected, it was near the lower limit of its detection (LLD) and are attributable to the statistical nature of the LLD.
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 with the exception of those listed in Table III.8.
- 3. Quality Control Program The Quality Control Program implemented by Duquesne Light Company to assure reliable performance by contractor and the supporting QC data are presented and discussed in Section III of this report. The lower limits of detection for vsrious analysis for each media monitored by this program by the DLC Contractor Laboratory are provided in Table V.A.4.
DUQUESNE LIGHT COMPANY TABLE V.A.3 SECTION V - A (Page 1 of 4) 1979 Annual Radiological Environmental Report TABLE V.A.3 (Page 1 of 4)
ENVIRONMEN~. RADIOLOGICAL MONITORINC PROGRAM SUMMA 11 E se of Facility thtsetsr-eft At:==Je ?arsef Itsttes Decast No. Net A9911cmDIe same of Fac;.1Ary Seaver kallev Pue ? 5 ta n n 00cset yo. m Lacation of Facility leaver. Fetsevivasta taperting Parted CT 1974 - 1973 (Ca n t7 states rtr-ot DAtt: MAL Fte:1AM mot (mtND 197& - 1975) wh er fatterer tower Limit sampled Analysis and Total Embar of All ladicatar tacations Mate of Mamourement) of Analvets ?,rf ened teeeettss t:3 Maan. ff1 tance Surface sater Crees Alpha (40) 0.3 0.73 3/ 40 0.6 - 1.1 Crees seca (120) 0.4 4.4 /120 1.3 *.1.4 Camma (1) 10 - 60 4 IJ$
Trician (121) 100 300 */ 21 1 130 - 800 3r-49 (0) = =
$r-90 (0) -
b C-14 (0) -
Drinktas Vater 1- 131~ (0) --
pC1/1 4 Crees Alpha (30) 0.3 ' O.6 /30 0.4 - 0.8 Crees leta (208) 0.4 3.4 204/208 1.3 - 6.4
-=
Comma (0) -
Tritian (211) 100 310 /211 130 - 1000 C-14 (0) - --
se-49 (0) - -.
Sr-90 (0) - ==
Cromed vatar Cross Alpha (19) 0.3 4 122 Croce Beta (76) 0.6 2.9 I3/73I *I 1.3 - 8.0 Tritium 440 U /81 80 - 800 G1) 100 Comma (1) 10 - 60 4 123 Air Ferticulates Crose Alpha (188) 0.001 0.003 3/138 0.0C2 - 0.004 and Gaaeone pC1/m3 Crose seca (927) 0.006 0.07 927/927 0.02 - 0.32 3r-49 (0) -
se-90 , (0) -
1-121 (816) 0.04 0.08 2/ 814 0.07 - 0.08 I Camme 2rn-93 tu-106
)$1) 0.CCS 0.010 0.04 0.04 D/ 197 0.01 - c.14 30
/197 0.02 - 0.09 3
Ca-141 0.010 0.02 /197 0.01 - 0.04 Co-144 0.010 0.02 /197 0.01 - 0.04 Othere 4 113 SECTION V - A DUQUESNE LIGHT COMPANY TABLE V. A.3 1979 Annual Radiological Environmental Report (Page 2 of 4)
{
l TABLt V.A.) (Fase 2 of 4)
ENVIRONMDrIAL RADIOLDGICAL }0NITORING FROGRAM SLHMARY Not Anglicable Same of Tacilit7 Shiestareert Atomie Fever Statien_ Docket No.
Name of Tac.uAty 5eaver Vallev Power station Docket No. 30-33 I
E Location of Tacility saaver. Founsvivania Reporting Period CT 1974 - 1975 (County, Scace)
I PRE-CFEIATIONAL PEDCIAN StlMMAJtr (CCM5IND 1974 - 1975)
Medium or Fat!nsey Lower Limit Analysis and Total Number of All Tadte=cor Locations sempled Mean. (f) Yante I of Analveis Performed Detection t.LD (Unit of Measurement)
Soil Gross Alpha (0)
PC1/g (dry) 1 22 64/64 16 - 32 Grose Beta (64)
I (Templace samplae) 1 0.25 0.4 /64 -
Sr-89 (64)
Sr-90 (64) 0.05 0.3 /64 0.1 - 1.3 U-234,235.238 (0)
Cames (64) 63 K-40 1.5 13 /64 5-24 0.1 1.5 6/ 64 0 1 - 6,8 Cs-137 Co-144 0.3 1.1 7/64 0.2 - 3 IrNb-95 0.05 0.3 /64 0.1 Ra-106 0) 0.3 1.1 /64 0.5 - 2 Others < LD Soil Grose Alpha (0) -
j pC1/5 (dry) 21 g/8 16 - 23 (Cora Samplae) Grose Beta (8) 1 ,
Sr-49 (8) 0.25 < LID I
sr-90 (a) 0.05 0.2 ls 0.0a - 0.5 l
caema (s)
K-40 1.5 13 8/s 7 - 20 Co-137 0.1 1.2 7/s 0.2 - 2.4 1
Co-60 0.1 0.2 /s -
Others <LD l I ;
I l
TABLE V. A. 3 SECTION V - A DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report (Page 3 of 4)
I TABLE V.A.3 (Page J of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SCC".ARY Nema of Facility shineimor- Arme rever seation Docket No. We50-334.Aselfeebla Name of Facility Beaver Vallev Power Station Dockat No.
I 14 cation of Tacility seaver. Pennevivania Reportins Level CT 1974 - 1975 (Coiancy, Stata)
FRX-CFEBADMEAL FloGRAM St20t&II(COMBI 3ED 1974 - 1975)
I *di - or Fathumy sampled Analysis and Total Number of Analysis Performed Iower Limit of Decoction 11D All Indicator Incations Mean. (f) tanee (Unie of Measurement)
I sad t-es pcils (dry)
Gross ~
Alpha Gross seca (0)
(33) 1 1s 33f 33 5 - 30 i
I 1
sr-90 (c) l U-234,235, 238 (0) 13 3/33 2 - 30 1 camma (33) 33 2 - 30 1.5 13 /33 l E-40 0.1 c.4 U/33 0.1 - 0.6 cs-U7 0.05 0.8 /33 0.2 - 3.2 trmb-95 0.3 0.5 3/33 0.4 - 0.7 Co-144 3 1.3 - 1.s 0.3 1.3 /33 Ru-lo6 0I
< LI.D others I Foodstuff Pci/s (dry) t' (a) 1 33 a/s 10 - 33 K-40 I co- u7 nub-95 0.1 0.05 0.2 0.2 1
1
/s
/s 1
0I 0.3 c.a /s -
sm-106
< I13 others I reedscaff cross seta (80) 0.05 0.025 19 c.2 80 /80 33
/s1 8 - so 0.04 - 0.93 sr-49 (81)
I se-90 camma (81)
(si) 0.005 0.4 7s/s1 0.02 - c.s1 73 1 19 /s1 5 - 46 E-40 0.1 0.5 'Is1 0.2 - 1.6 C -u7 3
0.3 1.3 /s1 0.9 - 2.6 C.-144 0.05 .o.s u/s1 c.2 - 1.s .
nub-95 1 0.3 14 12/s1 c.6 - 2.3 so-106 0)
I others
< 113 SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 197 9 Annual Radiological Environmental Report (Page 4 of 4)
TABI.E V.A.3 (Page 4 of 4)
ENVIRONMENTAL RADIOLOGICAI. MONITORING PROGR,Ut SLS ARY I 3ame of Facility Shipotsrport Atomic rever Station Docket No. Not Aeoliesble same of Facility seaver valle, Fever station Cockat No. 50-334 Location of Tacility Saaver. Pennsvivania taporting Level CT 197t. - 1973 (County, Stata)
PRE 4FEIAENt P30 GRAM St20'.AI! (CctGINC 1974 - 1975)
W t = or Path sy Lnser limit Samplad Analysis and Total Nummer of All Indicator locations of Analysis Performed Detection LL3 Mesa. (f) Ranae (Unit of t'- -E -- t)
I-ul (91) 0.25 0.6 '/91 0.3 - 0.8 milk.
I $r-49 se-90 (ue)
(ur) 5 1
7 5.3 132/ua
/134 6 - 11 1.5 - 12.8 Gemme (u4) 18 co-u7 10 u /u4 11 - 16 Others < z.ls I Excarnal Radiatica" y - Monthly (399) 0.3 31 0.20 3I'/399 0.08 - 0.31 0.20 "3 /195 0.11 - 0.38 y - Quarterly (195) 0.5 na 48 g,3g ,g,3a y - Ananal (48) 0.3 na 0.19 f43
^
Fish Grose Beta (17) 0.01 1.9 117 1.0 - 3.2 PC1/8 (w*C) 0.005 0.14 7/17 0.01 - 0.30 Sr-90 (17)
I Cm L-40 (17) 0.l, 2.4 17
/17 1.0 - 3.7 1
co-u7 0.08 0.03 /17 -
< IIn Other I .
I
(* Cae outliar not included in mean. (Watar ralama from dried-up sprist with high sediment and potassium content. Not considered typical groundwater sample.)
OI May taclude Ru-104, Ru-103, Se-7.
I l
m m m m m m M M DUQUENSE LIGHT COMPANY TABLE V.A.4 TYPICAL LLDs* FOR CAMMA SPECTROMETRY n
Sediment d o
Hilk Vegetation & Soll Fish Z Water AirPagticulates (pC1/kg dry) (pCi/g dry) (pC1/g wet)
Nuclide (pCi/ liter) (10' pCi/m') <
50 0.05 0.05 i Be-7 30 20 K-40 60 20 0.05 0.I 10 100 Cr-51 40 3 0.5 30 0.02 0.03 $
Hn-54 0.03 0.6 30 0.02 >
Co-58 3 60 0.03 0.06 o 6 1 D Fe-59 0.03 g 0.6 30 0.02 Co-60 3
- 70 0.04 0.07 In-65 8 2
1 50 0.03 0.05 $E Zr/Nb-95 5 2 40 0.03 0.04 hk o tn Ru-103 3 I 5 30 0.02 0.03 yg y Ru-106 30 3 30 0.02 0.03 % E9 i 5 Ag-Il0H 2 30 0.02 ?.03 0[
l-131 4 2 20 0.01 0.02 b rn +-l To-132 4 0.01 0.02 D 4 2 20 <n 1-133 Cs-134 4 0.6 30 0.02 0.03 7S 50 0.03 0.05 l 6 0.6 Cs-136 0.03 2 0.6 20 0.02 0 Cs-137 4 0.04 re 6 40 0.02 N Ba/t.a-140 10 W 60 0.03 0.06 6 2 Ce-141 5 200 0.1 0.2 $
Ce-144 30 600 0.3 0.6 E 60 6 Ra-226 0.06 N 60 0.03 Th-228 to 1 N
08
- At time of analysis (Dtf Contractor I.ab).
" Activity detected in all samples. Es "a t.ower 1.evel of Detection is defined in Beaver Valley Power Station Technical Specifications. <
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SECTION V - B DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING B. Air Monitoring
- 1. Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical I for an industrial area. Air flow is generally from the South-west in sumraer and from the Northwest in the winter.
- 2. Air Sampling Program and Analytical Techniques
- a. Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10) of f-site air sampling stations. The locations of these stations are listed in Table V.A.1 and shown on a map in Figure 5.B.1.
Samples are collected at each of these stations by continuously drawing about one cubic feet per minute I of atmosphere air through a glass fiber filter and through a charcoal cartridge. The former collects airborne particulates; the latter is for radioiodine sampling. Samples are collected for analysis on a weekly basis.
I The charcoal is used in the weekly analysis of airborne I-131. The filters are analyzed each week for gross beta, then composited by station for monthly analysis by gamma spectrometry. They are further composited in a quarterly I sample from each station for alpha analysis and for Sr-89/
90 analysis. In order to reduce interference from natural radon and thoron radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.
- b. Procedures I Gross be g analysis is performed by placing the filter paper from t.e F weekly air sample in a 2" x 1/4 planchet and counting it in a low background, gas flow proportional counter.
Gamma emitters are determined by stacking all the filter papers from each monitoring station collected during the I month and scanning this composite on a lithium drifted germanium (Ge(Li)) gamma spectrometer.
I Radiciodine (I-131) analysis is performed by a gamma scan of the charcoal in a weekly charcoal cartridge. The activity is referenced to the mid-collection time.
I SECTION V - B DUQUESNE LIGHT COMPANY FIGURE 5.B.1 1979 Arotual Radiological Environmental Report Fiq. 5.B.1 ENVIRONMENTAL MONITORWG L.0(.ATIONS AIR 5Agt'if. 5f Af t015 N Ain SAMPL. INCL LOCATIONS StA. 40. LOC A!!ON _,
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SECTION V-A DUQUENSE LIGHT COMPANY L979 annual Radiological Environmental Report V. ENVIRONMEN';AL MONITORING
- b. Procedures (continued)
Strontium-89 and Strontium-90 activities are determined in quarterly composited air particulate filters. Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution.
The mixture is then filtered. Half of the filtrate 17 taken for s-.rontium analysia Phe remainder bef.ng saved for gross alpha analysis) and is reduced in volume by evaporation. Strontium is precipitated as Sr(NO3)2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable I yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttriur. is then precipitated as hydroxide, is dissolved and re precipitated as oxalate. The yttrium oxalate is mourced cn a nylon planchet and is counted in a low level br.ca counter to infer strontium-90 activity.
Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mouncei on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting.
I Gross alpha activity is determined from the remaining half of solution prepared during the strontium analysis.
The solution is filtered and then evaporated onto a 2-inch stainless steel planchet. The sample is counted on a I Beckman-Sharp Wide Beta II automatic counter for alpha activity.
- 3. Results and Conclusions A summary of data is presented in Table V.A.1,
- a. Airborne Radioactive Particulates I A total of five hundred twenty (520) weekly samples from ten (10) locations was analyzed for gross beta.
Results were comparable to previous years; however, unlike previous years, there were no significant I short-term increases due to nuclear weapons testing by China. Figure 5.B.2 illustrates the average concentration of gross beta in air particulates.
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i SECTION V - A DUQUESNE LIGHT COMPANY FIGURE 5.B.2
. 1979 Annual Radiological Environmental Report I
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'M*n3/ gad 5 I SECTION V-B DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- a. Airborne Radioac:ive Particulates (continued)
I The weekly air particulate samples were composited to one hundred and twenty (120) monthly samples which were analyzed by gamma spectrometry. Naturally occurring l
l Be-7 was present in every sample. Occasional traces I
l i
above detection levels of other nuclides were present.
Some were natural; others were residuals from previous nuclear weapons' tests. None were attributable to either Beaver Valley Power Station or Shippingport Atomic Power Station.
A total of forty (40) quarterly samples were each analyzed I for gross alpha, Sr-89, and Sr-90. Results were comparable to those in previous years, including pre-operational years.
Based on the analytical results, the operation of Beaver Valley Power Station and Shippingport Atomic Power Station I
did not contribute to any increase in air particulate radioactivity during 1979.
- b. Radioiodine A total of five hundred and twenty (520) weekly 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 radioiodine during CY 1979.
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l SECTION V - C DUQUENSE LIGHT COMPANY E 1979 Annual Radiological Environm:ntal R2 port V. ENVIRONMENTAL MONIT0 KING C. Monitoring of Sediments and Soils
- 1. Characterization of Stream Sediments and Soils I 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.
- 2. Sampling Program and Analytical Techniques
- a. Program River bottom sediments were collected quarterly above the Montgomery Dam in the vicinities of the Beaver Valley discharge and Shippingport discharge and above I the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table V.A.1 and are shown in Figure 5.C.1.
Soil samples were collected at each of ten (10) locations during CY 1979. At each location 12 care samples (3" diameter by 2" deep) are gathered at prescribed points on I a 10 foot radius circle. Each location is permanently marked with reference pins. Each set of samples is systematically selected by moving along the radius in I such a manner as to assure representative undisturbed samples. Sampling locations are listed in Table V.A.1 and are shown in Figure 5.C.l.
Bottom sediments and soils are analyzed for gross alpha and beta activity, strontium, uranium and the gamma-emitting radionuclides.
B. Analytical Procedures I 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 ;
l are made on the basis of sample weight.
Gross alpha activity of sediment or soil is analyzed in l
I the same manner as gross beta except that the counter is set up to count only alpha.
l Gamma analysis of sediment or soil is performed in a 100 ml plastic bottle which is counted by a gamma spectrometer.
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SECTION V - C DUQUESNE LIGHT COMPANY FIGURE 5.C.1 1979 Annual Radiological Environmental Report I SEDUfENTS AND SOIL FIGURE 5.C.1 I
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SECTION V - C DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report I V. ENVIRONMENTAL MONITORING
- b. Analytical Procedures (continued)
Strontium 89 and 90 are determined by radiochemistry. A I weighed sample of sediment or soil is leached with HNO '3 A stable carrier is added for determination of recovery.
Strontium concentra, tion and purification is ultimately realized by precipitations of strontium nitrate in fuming I nitric acid. Additional hydroxide precipitations and barium chromate separations are also used. The purified strontium is converted to a carbonate for weighing and I counting. Samples are counted soon after separation (5 - 7 days is allowed for yttrium ingrowth). Activities arecalculatedonthebasisofappropriateSr-g9decayand Separate mounts covered with a 80 mg/cm aluminum I Y-90.
absorber are used for counting in a low background beta counter.
I Uranium isotopic analysis of sediment or soil samples were performed by alpha spectrometry after leaching and isolation of the uranium by anion exchange chromato-I graphy plys mercury cathode electrolysis, then electroplated onto a planchet.
- 3. Results and Conclusions I a. Results I The results of sediment and soil analysis are summarized in Table V.A.2.
There were no significant differences between these current levels and those previously detected in both upstream and downstream sediment samples. Results from gross alpha analysis tend to vary significantly as is characteristic of this type of analysis, but all results were within the range anticipated.
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SECTION V - C DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 3. Results and Cor.clusions (continued)
I a. Results (continued)
I 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 I Other than a very small amount of Co-60, at the outfall of Beaver Valley Power Station, the sediment analysis do not indicate any increased radioactivity attributable to Beaver Valley Power Station. Since Shippingport Atomic I Power Station did not release any radioactive liquid waste during 1979, it did not contribute to any changes in river sediment radioactivity. Small amount of Cs-137 from I fallout was found in all river sediment samples including those upstream above Montgomery Dam which are unaffecced by plant effluents.
I Results of soil analysis are comparable to preoperational data.
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l SECTION V - D DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report l V. ENVIRONMENTAL MONITORING D. Monitoring of Feederops and Foodcrops
- 1. Characterization of Vegetation and Foodcrops According to a survey made in 1975, there were approximateP' 700 farms in Beaver County. The principle source of revenu, for the farms was in dairy products which amounted to nearly l $3,200,000.00. Revenues from other farm products were as follows:
l Crops $1,400,000.00 Horticulture $ 565,000.00 Meat S 831,000.00 I Poultry $ 760,000.00 The percentage of crop land in Beaver County is approximately 17%, pasture land - 6.5%, forest land - 47.8%, and other land uses - 28.7%.
- 2. Sampling Program and Analvtical Techniques
- a. Program I Representative samples of cattle feed are collected monthly from the nearest dairy (Searight) . See Figure 5.D.l.
sample is analyzed by gamma spectrometry. The monthly Each samples are composited into a quarterly sample which is analyzed for Sr-90.
Foodcrops (vegetables) were collected at garden locations
, during the summer of 1979. Swiss chard and lettuce were
! obtained from a garden in Shippingport, PA; lettuce was sampled from gardens in Industry and Georgetown, PA. All l samples were analyzed for gamma emitters (including I-131 l by gamma spectrometry),
i b. Procedures Gamma emitters, including I-131, are determined by scanning a dried, homogenized sample with the gamma E =Pectro=etry 87=ce=- ^ ce('t) detector le utiitzed 1 3 with this system.
Strontium 90 analysis for feedstuff is p erformed by a I procedure similar to that described in V.C.2.
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SECTION V - D DUQUENSE LIGHT COMPANY l
g 1979 Annual Radiological Environmantal Report ,
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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 radienuclides. All results were consistent with (or lower than) tht,2e obtained in the pre-operational program. These data cenfirm 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.
I I
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SECTION V - E DUQUESNE LIGHT COMPANY I 197 9 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.l. This milk is analyzed for its radio-iodine content calculated as Iodine-131. The analyses are I performed within eight (8) days of sampling.
Detailed field surveys were performed twice 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 were identified. Survey data for the most recent survey conducted in August - September, 1978 is shown in Figure 5.E.1.
- 2. Sampling Program and Analytical Techniques
- a. Program l
Milk was collected from three (3) reference dairy farms I within a 10-mile radius of the site. Additional dairies, which represent the highest potential milk pathway for radioiodine based on milch animal surveys and meteorological data were selected and sampled. These dairies are subject to change when more recent data (including census) indicate other locations are more appropriate. The location of each is shown in Figure 5.E.2 and described below.
Number of Milch Distance and Direction Collection Site Dairy Animals From Site Period 25 Searight 5 1 Cr.y s 2.2 miles-southwest Jan. - Dec.
27 Brunton 80 Cows 7.3 miles-southeast Jan. - Dec.
l 29A Nichol 45 Cows 8.0 miles-northeast Jan. - Dec.
56 Bertovic 3 Goats
- 3.7 miles-north Apr. - Sept.
57 Bailes 1 Cow
- 3.1 miles-west / northwest Apr. - May 59 Irons 1 Cow
- 2.3 miles-south Apr. - Dec.
60 Haney 2 Cows
- 2.6 miles-west Jan. - Mar.,
Jun. - Dec.
61 Allison 45 Cows 3.3 miles-west / southwest Apr. - Dec.
62 Lyon 25 Cows 3.4 miles-west / southwest Apr. - Dec.
Milk usage - home only.
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SECTION V - E DUQUENSE LIGHT COMPANY FIGURE 5.E.1 1979 Annual Radiological Environmental Report FIGURE 5.E.1 COW a GOAT SURVEY- sui /1MER,1979 I e
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SECTION V - E DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environm:ntal R: port V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk (continued)
- a. Program (continued)
The sample from Searight Dairy was collected and analyzed weekly for radioiodine using a procedure with a high sensitivity. Samples from each of the other selected dairies were collected monthly.
This monthly sample is analyzed for Sr-89, Sr-90, gamma emitters including Cs-137 (by spectrometry),
and I-131 (high sensitivity analysis).
- b. Procedure Radiciodine (I-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a betagated, gamma coincidence counting system.
Gamma emitters are determined by gamma spectrometry of a one liter marinelli container of milk.
Strontium analysis of milk is similar to that of other foods (Refer to V.C.2) except that milk samples are prepared by addition of Trichloracetic Acid (TCA) to produce a curd which is removed by filtration and discarded. An oxalate precipitate is ashed for counting.
- 3. Results and Conclusions A total of one hundred thirteen (113) samples were analyzed for I-131 during 1979. All I-131 activities in milk were I below the minimum detectable level (0.3 pC1/1).
A total of seventy-three (73) samples were analyzed by gamma spectrometry and for strontium. Both the Cs-137 and Sr-90 levels were within the normally expected range. The higher levels from China's nuclear tests which were experienced in the last several years were notably absent. this year. Such tests were not performed during 1979.
SECTION U - F DUQUENSE L1GHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring
- 1. Description of Regional Background Radiation Levels and Sources The terrain in the vicinity of the Shippingport and Beaver Valley Power Station generally consists of rough hills with altitude variations of 300 to 400 feet. Most of the land is wooded.
The principal geologic features of the region are nearly flat-lying sedimentary beds of the Pennsylvania Age. Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposite partially cover the older sedimentary deposits in the northwest.
Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley, and along major tributary streams.
Based on surveys reported in previous annual reports, exposure rates ranged from 6 to 12 pR/hr. Results for 1979 indicated that background radiation continued in this range.
- 2. Locations & Analytical Procedures Ambient external radiation levels at the site were measured I using thermoluminescent dosimeters (TLDs). There were three (3) types used in the Duquesne Light Company Radiological Environmental Monitoring Program. They are calcium sulphate dysprosium, [CaSO 4 (Dy) in teflon matrix], lithium fluoride (LiF), and thulium activated calcium sulfate (CaSO ;Tm).4 The lithium fluoride TLDs have been posted and analyzed by a laboratory of the Department of Energy (DOE) as an independent check of environmental radioactivity levels. The CaSO :Tm 4
were used as a back-up and as a QC program. The locations of the TLDs are shown in Figure 5.F.1. Comparisons of TLD results are presented in Section III, Table III.1.
l l
1 SECTION V - F DUQUESNE LIGHT COMPANY FIGURE 5.F.1 1979 Annual Radiological Enviroanental Report I ENVIRONMENTAL McNITORINC i LOCATIONS FiquRE 5.F.I L n OFFSITE RADIATION 00SIMEIt.RS (TLDU I ,#0#55linG
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l I SECTION V - F DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environm:ntal R: port I
V. ENVIRONMENTAL MONITORING
- 2. Locations & Analytical Procedures (continued)
I The lithium fluoride (LiF) TLD were annealled at least ten (10) days before scheduled use. Calibration with Cesium-137 exposure was performed within a few days of annealing. Readout of the calibration set was delayed for ten (10) days to allow for the decay of unstable, low temperature peaks in the glow curve. Radiation dose accumulated from time of analysis to posting was corrected utilizing background readings of ten (10) TLD chips within a few days of posting (the average of these backgrounds at I posting time was then subtracted from the gross readings of each TLD). Thus net reading reflects the radiation dose received by the TLD during the time it was posted in the environment only. All LiF TLDs were read quarterly.
The calcium sulfate (CaSO4:Dy) TLDs were annealled shortly before placing the TLDs in their field locations. The I 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.
I 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 4
- Dy in teflon) during 1979 is summarized in Tables V.A.2 and III.1.
The annual exposure races averaged .21 mR/ day in 1979.
I As in previous years, there was some variation among locations and seasons as would be expected.
In 1979, ionizing radiation dose determinations averaged approximately 75 mR for the year. This is comparable to previous years. There was no evidence of anomalies that could be attributed to operation of Beaver Valley Power Station or Shippingport Atomic Power Station. Based on the results of Table III.1, the erratic data experience in 1978, appear to have been eliminated. Three sets of TLDs of different g types, each provided and analyzed by a separate laboratory, g demonstrate good agreement and confirm that changes from natural radiation levele rif any, are neglible, l
i l I
SECTION V - C DUQUENSE LIGHT COMPANY l 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING G. Monitoring of Fish
- 1. Description Fish collected near the site are generally scrap fish.
During 1979, fish collected for the radiological monitoring program included carp and catfish.
- 2. Sampling Program and Analvtical Techniques
- a. Progrtm Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley I and Shippingporc. effluent discharge points and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectrometry.
Fish sampling locations are shown in Figure 5.G.I.
- b. Procedure A sample is prepared in a standard cared 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a Ge(L1) detector.
I 3. Results and Conclusions I A summary of the results of the fish monitoring data is provided in Table V.A.2. Sixteen (16) fish were caught in May. Six (6) more samples were caught during October -
November. No fish samples were available from above the I Montgomery Dam during the second half of the year despite ten (10) attempts to collect them. Except for naturally occurring K-40, the only gamma emitter which was detected in any sample was a trace of Cs-137 in one sample. This was attributable to nuclear weapons testings of previous years. This isotope, as well as other fission and corrosion activation nuclides, were not found in fish san.ples from the Beaver Valley Power Station discharge location. Shippingport Atomic Power Station released no radioactive liquids during CY 1979. This indicates that the operation of the Shipping-l port Atomic Power Station and the Beaver Valley Power Station i
has not resulted in radioactivity in fish in the Ohio River.
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- SECTION V - H DUQUESNE LIGHT COMPANY 197 9 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.
I 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 I plant sites. It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water Authority. The intake of the treatment plant I 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 I approximately 6 and 7 miles downstream, respectively. The heavy industries in Midland, as well as others downstream use ri':er water for cooling purposes. Some of these plants also have private treatment facilities for plant sanitary I water.
Ground. water occurs in large volumes in the gravel terraces I 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 five (5) sampling points along the Ohio River. Raw water samples I are normally collected at the East Liverpool (Ohio)
Water Treating Plant (River Mile 41.2) daily and composited into a monthly sample. Weekly grab samples I 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];
I near the discharge from Beaver Valley Power Station (River Mile 35.0]; and at the outfall of Pegg's Run, a stream which passes through the site upstream of the plants (River Mile 34.5]. The weekly reab samples are I composited into monthly samples from -2ch location.
In addition, a quarterly composite sample is prepared for each sample point.
l
i I SECTION V - H DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 2. Sampling and Analvtical Techniques (Continued)
- a. Surface (Raw River) Water (Continued)
The monthly composites are analyzed for gross alpha, I gross beta, and gamma emitters. The quarterly composites are analyzed for tritium (H-3), carbon 14 (C-14),
strontium 89 (Sr-89), strontium 90 (Sr-90), and cobalt 60 (high sensitivity).
Locations of each sample point are shown in Figure 5.H.l.
- b. Drinking Water (Public Supplies)
Drinking (treated) water is ?.ollected at both Midland (PA)
I and East Liverpool (OH) Water Treating Plants. An automatic sampler at each location collicts 20-50 milliliters every 20 minutes. These intermitteat samples are then composited into a weekly sample. The waekly sample from each location I is analyzed by gamma spectrometry. The weekly sample from Midland is also analyzed for radioiodine (I-131) .
Monthly composites of the weekly samples are analyzed for gross alpha, gross beta, and by gamma spectrometry.
Quarterly composites are analyzed for H-3, C-14, Sr-89, Sr-90, and Co-60 (high sensitivity). Locations of each I sample point are shown in Figure 5.H.l.
- c. Ground Water Grab sampics were collected each quarter from each of five (5) well locations (see Figure V.H.1) within four (4) miles of the site. These locations are:
One (1) Beaver Valley Power Station well One (1) well at Shippingport, PA One (1) well at Meyer's Farm (Hookstown, PA)
One (1) well in Hookstown, PA I One (1) well in Georgetown, PA Each groundwater sample is analyzed for gross alpha, I gross beta, tritium, and by gamma spectrometry.
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SECTION V - H DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 2. Sampling anc 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 sample is counted in a low background, gas flow proportional counter. Self-absorption corrections are made on the basis of sample weight.
Gamma analysts is performed on water sample by loading one liter of sample into a one liter marinelli container and counting on a Ge(L1) gamma spectrometry system Strontium-89 and 90 are determined on water samples by a procedure similar to that described in V.C.2 except that the leaching step is eliminated.
Cobalt-60 is determined with a sensitivity of 1 pC1/1 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) spectrometer system.
Tritium is determined in water samples by converting 2 ml of the sample to hydrogen and counting the activity in a 1 liter low level gas counter which is operated in the proportional range in anti-coincidence mode.
Carbon-14 is determined in water samples by adding a sodium carbonate carrier and evaporating i liter of neutral solution. The residue is burned to produce CO, which is purified first by forming a I barium car 5onate, releasing the carbon as CO second time and finally by gas chromatography.2
- The CO2 is counted in 100 cc low level gas counter which is operated in the proportional range in the anti-coincidence mode.
l I
SECTION V - H DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmrntal Rzport l
V. ENVIRONMENTAL MONITORING
- 3. Results and Conclusions A summary of results of all analyses of water samples (surface, drinking, and ground) are provided by sample type and analysis in Table V.A.2. These are discussed below.
- a. Surface Water A total of sixty (60) samples were each analyzed for gross alpha, gross beta, and gamma activity.
Twenty (20) quarterly composited samples were analyzed for tritium (H-3), radiostrontium (Sr-89 and Sr-90),
and Carbon-14 (C-14) as well as a high sensitivity analysis for Co-60.
No alpha, Sr-89 or Co-60 were detected in surface water during 1979. All beta activities were within normal range. The only gamma emitter detacted was Cs-137 at 4.3 + 3.3 pC1/1 in a East Liverpool sample '
composited for February. None was detected in the drinking water samples for the same period or near station discharge locations. This is a very low-level result near the minimum detectable activity and could be caused either by expected variability in analyses results or to fallout from historical weapons testing.
It is not attributable to either station operations.
The tritium levels in Beaver Valley Power Station outfall were elevated above preoperational levels during the first and fourth quarters, but none of these data suggest detectable increases over preoperational levels downstream of the station.
The tritium activity at the Beaver Valley Power Station outfall is consistent with station data of authorized radioactive discharges from Beaver Valley Power Station and were within limits permitted by NRC license.
Trace amounts of Sr-90 above the lower limit of I detection (LLD) were found at all locations in the second quarter (both upstream and downstream of the site). The LLD used in the Duquesne Light Company program is below that required by the Technical Specifications and accounts for analytical variability.
I I I i
i ___
SECTION V - H DUQUENSE LIGHT COMPANY 1979 Annual Radiological Environmrntal Rsport V. ENVIRONMENTAL MONITORING
- 3. Results and Conclusions (continued)
- a. Surface Water (ccutinued)
The results ranged from 0.42 + 0.39 pC1/ liter to 1.2 +
0.7 pC1/ liter. These are low levels and are near the typical lower limit of detection of 0.5 pCi/ liter.
TF se results may be attributed to expected variability L analysis results or to fallout from historical weapons testing being leached from the surrounding soil and into the river. Since there were positive results both above and below the stations, the results could not be attributed to station operations.
Carbon 14, above the lower limits of detection was reported in both upstream and downstream samples during the second and third quarters. The presence of C-14 in samples upstream of the site above the Montogomery Dam indicated that it is not attributable to either of these stations.
No detectable increase in radioactivity in the Ohio River can be attributed to Shippingport Atomic Power Station since it did not discharge radioactive liquids during 1979.
- b. Drinking Water A total of twenty-four (24) samples were analyzed for gross alphs and gross beta. All results were within preoperational data ranges.
A total of eight (8) samples were analyzed for tritium (H-3), carbon 14 (C-14), radiostrontium l (Sr-89 and Sr-90), and cobalt 60 (Co-60). No Sr-90, Sr-89, Co-60 or C-14 were detected. The tritium data were within the preoperational range indicative of normal environmental levels.
A total of another one-hundred and four (104) samples were analyzed by gamma spectrometry. No gamma emitting radionuclides were detected by these analysis.
SECTION V - H DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environs:ntal Report j V. ENVIRONMENTAL MONITORING
- b. Drinking Water (continued)
A total of fifty-two (52) samples were analyzed for radioiodine (I-131) using a highly sensitive technique.
Detectable levels of I-131 were determined in the two I (2) weekly samples collected on January 22 and July 17, 1979. The results of 0.29 pCi/ liter and 0.51 pC1/ liter for these samples are only slightly above the minimum I detectable activity of 0.2 pCi/ liter and are not consis-tent with surface water samples. Neither result could be attributed to station discharges. The results may be attributed to expected variability in the analyses results I of very low levels of activity. In addition, surface water analysis for the same periods did not indicate the presence of (1-131).
- c. Well Water A total of twenty (20) samples were each analyzed for gross alpha, gross beta, tritium and by gamma spectrom-etry. No alpha activity was detected. The gross beta and tritium data are within preoperational ranges.
One gamma emitting radionuclide was detected near the lower limit of detection in a single sample. Based on a review of effluent data and environmental data, neither Beaver Valley Power Station nor Shippingport Atomic Power Station contributed activity te e;aund water
, 3 during CY 1979. In addition, underground water flow in the Beaver Valley area is from the steep slopes to the i
E river. There is no apparent pathway for radioactive liquid sources to enter local wells.
- d. Summary The data from water analysis demonstrate that neither Beaver Valley Power Station nor Shippingport Atomic Power Station contributed a significant increase of radioactivity in local river, drinking or well waters.
The few positive results which could be attributable to authorized releases from Beaver Valley Power Station are characteristic of the effluent and confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.
Further, the maximum detected activity attributable to Beaver Valley Power Station was only a small fraction
(<0.2%) of the concentration (averaged over a year)
I permitted by the Federal Regalations for water consumed by the public. The Ohio River further reduced this concentration prior to its potential use by members of the public.
SECTION V - I DUQUESNE LIGHT COMPANY 197 9 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 1. Estimates of Radiation Dose to Man
- 1. Pathways to Man - Beaver Valley Power Station
- a. Calculational Models - Beaver Valley Power Station l
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 X0QD0Q, 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 I gases in discharge plumes. Beaver Valley effluent data, based on sample analysis in accordance with the schedule set forth in Appendix B of the BVPS license, were used as the radionuclide activity input.
Each radionuclide contained in the semi-annual effluent report format of Regulatory Guide 1.21 was considered. Certain radionuclides which were not detected in the effluents were not included in dose calculations when the inventory of such nuclides available for discharge was judged to be negligible.
As a result, only noble gases, radioiodines, strontium, and tritium were included as source terms based on the lower detectable limits of analysis (all sensi-tivities for analysis at Beaver Valley were equal to or better than required by the Beaver Valley license).
All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assess-ments. The release activities are based on laboratory analysis. When the activity of noble gas was below I 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.
I Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to X0QD0Q which in turn provided input for GASPAR.
Except when more recent or specific data was available, I all inputs were the same as used in the Beaver Valley Power Station Environmental Statements or in Regu a tory Guide 1.109. The airborne pathways evaluated were beta and gamma doses from noble gas plumes, inhalation, the " cow-milk child", and other ingestion pathways.
I 1
l l
SECTION V - I DUQUESNE LIGHT COMPANY 197 9 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- a. Calculational Models - Beaver Valley Power Station (continued)
All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using a GeLi detector. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0). The actual datr.
from these analyses are tabulated and used as the.
radionuclide activity input term in LADTAP. '"ae maximum individual for liquid pathways is located I at Midland. Except when more recent % 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 I The doses which are calculated, based on the model presented above in V.I.1, are summarized and compared to Beaver Valley Power Station license limits below.
An additional breakdown of these doses by pathway and organ is provided in Table V.I.l. For these calcula-tions, 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.
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SECTION V - I DUQUESdE LIGHT COMPANY 1979 Annual Radiological Environmsntal Report l I V. ENVIRONMENTAL MONITORING l
1
- 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued)
Actual Doses (mrem /yr.) - Calculated Using Site Effluents I Appendix I
- Analysis Dose - Calculated Using NRC Model Effluents Regulatory Limit Doses - NRC Staff Guidelines RM50-2 Appendix I Calculated Report (Con- Rh50-2 (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 0.081 2.78 5.0 0.019 Teen 0.054 0.712 5.0 0.011 I Child Infant 0.051 0.058 Not Reported Not Reported 5.0 5.0 0.006 0.004 ANY ORGAN Adult 0.099 Not Reported 5.0 0.026 (Liver)
Teen 0.091 Not Reported 5.0 0.025 (Liver)
Child 0.095 Not Reported 5.0 0.024 (Liver)
I Infant 0.077 (Thyroid)
Not Reported 5.0 0.026 Maximum Total Body Dose - Capsule Summary mrem 1979 Calculated 0.081 Appendix I Estimated 2.78 Final Environmental Statement 0.112 I Thyroid Dose - (Largest Expected Orgar. Dose) 1979 Calculated 0.077 Final Environmental Statement 0.96 t
, I
-102-
1 SECTION V - I DUQUESNE LIGHT COMPANY l 1979 Annual Radiological Environmtntal Raport V. ENVIRONMENTAL MONITORING
- 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued) l
- b. Population Doses The 1979 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 430 H-3 396 mrem Co-60 2 mrem Cs-137 6 mrem I THYROID 463 H-3 I-131 396 mrem 55 mrem The estimated quarterly dose in the NRC Final Environmental Statement is 104 Man-Millirem. The Calculated Dose is less than the background annual dose received by five (5) people of the 4 million people evaluated. The increased dose to this population is less than 0.0001% of normal background dose already received.
- 3. Airborne Pathway - (Beaver Valley Power Station)
The doses to the public for Beaver Valley Power Station I airborne radioactive effluents during 1979 are provided in Table V.I.2. They include the contribution all pathways.
Tritium is the primary radionuclide contribution to these doses. The data demonstrate compliance with 10CFR, Appendix I design objective limits.
- 4. Conclusions - (Beaver Valley Power Station)
The calculated doses to the public from the operation of Beaver Valley Power Station - Unit NO. 1 are below 10CFR50, I Appendix I design objectives, and resulted in only a sr211 incremental dose to that which area residents already received as a result of natural background the doses constirated no meaningful risk to the public.
- 5. Dose Pcthways to Man - Shippingport Atomic Power Station The radiation doses to man as a result of operations at the Shippingport Atomic Power Station during 1979 were calculated j for the liquid and gaseous effluent pathways. There were l no radioactive liquid discharges from the Shippingport Atomic I
Power Station during 1979.
-103-
M M M M M M M m
5 TABLE V.I.2 Results of Calculated Radiation Dose to Man (1979) "h Beaver Valley Power Station - Airborne Radioactivity @
I
- s APPENDIX I 50-MILE MAXIMUM EXPOSURE DESIGN OBJECTIVE PERCENT OF POPULATION DOSE ORGAN INDIVIDUAL, mrem mrem APPENDIX I man rem G
a TOTAL BODY .5259 5 10.5% 1.24 E
u SKIN 1.556 15 10.4% 5.86 ""
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Ris a 1.35 SQ y -- --
LUNG e?
Er TilYROID -- -- -- 1.27 $g mN SU
- 10CFR50, t.ppendix I h9 S
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SECTION V - I DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 5. Dose Pathways to Man - Shippingport Atomic Power Station (continued)
Effluent monitoring at the Shippingport Station during 1979 has shown that the radioactivity releases were substantially below the Federal radioactivity concentration guides. The environmental monitoring program has demonstrated that the radiation exposure to the general public from the Shippingport Station operations was too low to measure and could only be estimated with the calculational models described below using measured or estimated effluent radioactivity data.
- a. Calculational Models - Shippingport Atomic Power Station The radiation doses to man from Shippingport Atomic Power Station operations were estimated using calculational l
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- models recommended by the International Commission on Radiological Protection (ICRP Publ. 2, 1959) and employ the general guidelines of the Nuclear Regulatory Commission (Regulatory Guide 1.109) established to maintain compliance with 10CFR50 Appendix I.
The air dose pathways considered were inhalation, immersion in gaseous and suspended particulate activity, and the ingestion of food and milk produced in the Shippingport It was conservatively assumed that food products I vicinity.
consumed by the public were produced in the Shippingport area throughout CY 1979 The maximum potentially exposed individual for the air pathways was located at the site I boundary. It was conservatively assumed that the maximum individual resides continually at the site boundary.
I Modeling parameters and usage factot used in the pathway calculations were consistent with values recommended by the Nuclear Regulatory Commission (NRC Regulatory Guide 1.109). The population distribution within 50 miles of I the site was based on census data projected for 1979 as provided in the LWBR Program Environmental Impact Statement (ERDA 1541). Furthermore, the air pathway calculation employed site-specific meteorological and I wind direction data.
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I SECTION V - I I DUQUESNE LIGHT COMPANY 1979 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 6. Results and Conclusions - Shippingport Atomic Power Station Evaluation of the radiation dose-to-man calculations for the airborne effluents show that the maximum annual radiation exposure potentially received by an individual residing at the site boundary is less than 0.5 mrem. The maximum dose to an individual is well below the 10CFR50 Appendix I dose limits. Furthermore, the radiation exposure to the entire population of 4 million persons within 50 miles of the Shippingport Station was less than one (1) person-rem.
This dose is negligible compared to the typical general dose of more than 360,000 person-rem received by all individuals from typical background radiation.
In conclusion, the radiation exposure received from the
,d Shippingport Station during CY 1979 by any member of the 5 general public is a very small fraction of the background radiation and has, therefore, no significant effect on the general public.
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DISTRIBUTION LIST Director of Nuclear Reactor Regulation (17 copies)
United States Nuclear Regulatory Commission Attention: A. Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors c/o Distribution Services Branch, DDC, ADM Washington, DC 20555 Mr. Boyce H. Grier (2 copies)
Director of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Clifford L. Jones, Secretary Department of Environmental Resources Commonwealth of Pennsylvania South Office Building Harrisburg, PA 17105 Carl K. Gaddis, Manager United States Department of Energy Pittsburgh Naval Reactors Office Post Office Box 109 West Mifflin, PA 15122 Admiral H. G. Rickover Director, Naval Reactors United States Department of Energy Washington, DC 20013 George P. Dix, 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 United States Department of Energy Technical Information Center l Post Office Box 62 l Oak Ridge, TN 37830
DISTRIBUTION LIST (continued)
I J. M. Arthur Chairman of the Board I Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 S. G. Schaffer President Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 C. N. Dunn Vice President - Operations Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 E. J. Woolever I
Vice President, Engineering & Construction Division Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 H. A. VanWassen Project Manager, Beaver Valley Power Station Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 G. W. Moore General Superintendent - Power Stations Department Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 S. L. Fernick Manager of Environmental Affairs Duquesne Light Company 435 Sixth Avenue Pittsburgh, PA 15219 R. J. Washabaugh I Manager, Quality Assurance Duquesne Light Company Beaver Valley Power Station I P. O. Box 186 Shippingport, PA 15077 i
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