ML20198A396
| ML20198A396 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1984 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20198A389 | List: |
| References | |
| NUDOCS 8511050012 | |
| Download: ML20198A396 (129) | |
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7 l-I 1984 ANNUAL ENVIRONMENTAL REPORT RADIOLOGICAL - VOLUME (/2 DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION AND SHIPPINGPORT ATOMIC POWER STATION 1
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.8511050012 850430
{DR ADOCK 05000334PDR
DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report ABSTRACT
[
This report describes the Radiological Environmental Monitoring
{ Program conducted during 1984 in the vicinity of the Beaver Valley l 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 1984.
[.-
The environmental' program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout' 1984.
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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r DUQUESNE LIGHT COMPANY L 1984 Annual Radiological Environmental Report
. TABLE OF CONTENTS i
j Abstract------------------------------------------------------------ 1 I. INTRODUCTION----------------------------------------------- 1 A. Scope and Objectives of the Program 2 B. Description of the Shippingport and Beaver Valley Site 2 II. RESULTS & CONCLUSIONS--------------------------------------
f 7 III. ENVIRONMENTAL MONITORING CONSIDERATIONS-------------------- 9 A. Environmental Quality Control Programs 9 B. Evaluation of the Quality Control (QC) Program Data 26 C. Standard Requirements and Limitations for Radiological .
a J 9ther Effluents 26 D. Reporting Levels 27 IV. MONITORING EFFLUENTS--------------------------------------- 28 A. Monitoring of Liquid Effluents 28
- 1. Effluent Treatment, Sampling, and Analytical Procedures 34
- 2. Results 35 B. Monitoring of Airborne Effluents 36
- 1. Description of Airborne Effluent Sources 36
- 2. Airborne Effluent Treatment and Sampling 41
- 3. Analytical Procedures for Sampling Airborne Effluents 45
- 4. Results 48 C. Solid Waste Disposal 52
[
r- DUQUESNE LIGHT COMPANY
( 1984 Annual Radiological Environmental' Report TABLE OF CONTENTS ~(Continued)
V. ENVIRONMENTAL MONITORING PROGRAM h
( A. Environmental Radioactivity Monitoring Program 54
- 1. Program Description 54
- 2. Summary of Results 69
- 3. Quality Control Program 69 B. Air Monitoring 75 l 1. Characterization of Air and Meteorology 75
- 2. Air Sampling Program and Analytical Techniques 75
- 3. Results and Conclusions 78 C Monitoring of Sediments 81
- 1. Characterization of Stream Sediments 81
- 2. Sampling Program and Analytical Techniques 81
- 3. Results and Conclusions 83 D. Monitoring of Feederops and Fooderops 85
- 1. Characterization of Vegetation and Fooderops 85
- 2. Sampling Program and Analytical Techniques 85
- 3. Results and Conclusions 88 E. Monitoring of Local Cow's Milk 89
- 1. Description - Milch Animal Locations 89
- 2. Sampling Program and Analytical Techniques 89
- 3. Results and Conclusions 93
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b DUQUESNE LIGHT COMPANY f 1984 Annual: Radiological Environmental Report TABLE OF CONTENTS (continued)
V. ENVIRONMENTAL MONITORING PROGRAM (continued) Page g F. Environmental Radiation Monitoring 94
- l. 1
- 1. Description of Regional Background Radiation '
Levels and Sources 94
- 2. Locations & Analytical Procedures 94
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(- 3. Results and Conclusions 99 l.
G. Monitoring o.f Fish 101
- 1. Description 101 h
- 2. Sampling Program and Analytical Techniques 101
]
- 3. Results and Conclusions 101 H. Monitoring of Surface, Drinking, and Well Waters 103
- 1. Description of Water Sources 103 ,
- 2. Sampling Program and Analytical Techniques 104
- 3. Results and Conclusions 107 I. Estimates of Radiation Dose to Man 110
- 1. Pathways to Man - Beaver Valley Power Station 110
- a. ~ Calculational Models - Beaver Valley Power Station 110
- 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases 111
- 3. Airborne Pathway 114
- 4. Conclusions - Beaver Valley Power Station 114
- 5. Dose Pathways to Man - Shippingport Atomic Power Station 116
- 6. Results and Conclusions - Shippingport Atomic Power Station 117
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DUQUESNE LEGHT COMPANY h 1984 Annual Radiological Environmental Report LIST OF FIGURES
( Figure No. Page f 1.0 View of the Shippingport and Beaver Valley Site 4 1.1 Geographical Map - 40 Mile Radius 5 4.1 Liquid Discharge Points to Ohio River 29 4.2 Water Flow Schematic - Shippingport Atomic Power Station 30 4.3 Water Flow Schematic - Beaver Valley Power Station 31
( 4.4 _ Liquid Radwaste Systems - Shippingport Atomic Power l Station 32 4.5 Liquid Radwaste Systems - Beaver Valley Power Station 33 4.6 Gaseous Waste Processing - Shippingport Atomic Power Station 38 4.7 Gaseous Waste Processing - Beaver Valley Power Station 40 4.8 Gaseous Release Points - Shippingport Atomic Power Station and Beaver Valley Power Station 42 4.9 Solid Wasta Disposal Diagram 53 5.B.1 Environmental Monitoring Locations - Air Sampling Stations 77 5.B.2 Concentrations of Gross Beta in Air Particulates 79 5.C.1 Environmental Monitoring Locations - Sediments 82 5.D.1 Environmental Monitoring Locations - Feederop and Foodcrop 86 5.E.1 Dairy Farm Locations (August - September 1984 Survey) 91 l 5.E.2 Environmental Monitoring Locations - Milk 92 5.F.1 Environmental Monitoring Locations - Radiation Monitoring 95 5.F.2 Environmental Monitoring Locations - Radiation Monitoring 96 5.F.3 Environmental Monitoring Locations - Radiation Monitoring 97.
5.F.4 Environmental Monitoring Locations - Radiation Monitoring 98 5.G.1 Environmental Monitoring Locations - Fish 102 5.H.1 Surface Water and Wells - Locations 106
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II DUQUESEE LIGHT COMPANY
(- '1964 Aanual Radiological Environmental Report.
LIST OF TABIIS Table Number P_aage III.1 Quality Control Data - TLD Comparisons 11 III.2 Quality Control Data - Water Split Samples 12 III.3 Quality Control Data - Split Samples - Miscellaneous 14
( III.4 Quality Control Data - Spiked Samples 18 III.5 Quality Control Data - Spiked Samples 19 III 6 Quality Control Data - Air Particulates and I-131 20 III.7 Quality Control Data - Milk and Water 24 IV.A.1 Effluent Treatment, Sampling and Analytical Procedures Shippingport Atomic Power Station 34 IV.A.2 Effluent Treatment, Sampling and Analytical Procedures Beaver Valley Power Station 34 IV.A.3 Results - Liquid Effluents - Shippingport Atomic Power Station 35 IV.A.4 Results - Liquid Effluents - Beaver Valley Power Station 35 V.A.1 Environmental'Honitoring Program Summary 55 V.A.2 Environmental Monitoring Program Results (1984) 60 V.A.3 Pre-Operational Monitoring Program Results (1974-1975) 70 V.A.4 Typical LLDs for Gamma Spectrometry - DLC Contractor 74 V.D.1 Closest Residence and Garden in Each Sector 87 V.I.1 Radiation Dose to Man - Beaver Valley Power Station - Liquid Releases 110 V.I.2 Radiation Dose to Man - Beaver Valley Power Station - Airborne Releases 113
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SECTION I DUQUESNE LIGIIT COMPANY
- h. 1984 Annual Radiological Envirrnmental Report I. INTRODUCTION The 1984 Annual Radiological Environmental Report for the Beaver Valley Power Station and the Shippingport Atomic Power Station summarizes the radiological environmental program conducted by the Duquesne Light Company in 1984.
The Duquesne Light Company operates the Shippingport Atomic Power Station for the United States Department of Energy and the Beaver Valley Power Station pressurized water reactor - Unit No. I as part of the Central Area Power Coordination group. Beaver Valley
[ No. 2 Unit was under construction in 1984 and is scheduled to l start-up in 1987.
The Shippingport Atomic Power Station was permanently shutdown on October 1, 1982. During 1984 the Shippingport Atomic Power Station nuclear reactor core was disassembled and shipped off-site for disposal. Responsibility for the Shippingport Atomic Power Station was assigned to the U.S. Department of Energy, Richland Operations Office for the purpose of decommissioning on September 6, 1984.
l- The Shippingport Atomic Power Station was the first large-scale central station nuclear reactor in the United States. Since initial pewer generation in December 1957, operation of the pressurized water reactor at the Shippingport plant has supplied power to the Duquesne Light Company system in addition to providing technology which has served as a basis for the development of pressurized water reactors in the nuclear industry.
The plant utilized a Light Water Breeder Reactor (LWBR) core from September 21, 1977 until final shutdown on October 1, 1982, pioneering light water breeder technology.
The highest average daily 'utput o generated at the Beaver Valley Power Station during the year was 830 megawatts . net in January, 1984. The total gross electrical generation during the year was 5,065,500 megawatt-hours.
t
( SECTION I DUQUESNE LIGHT COMPANY
( 1984 Annual Radiological Environmental Report I. INTRODUCTION A. Scope and Objectives of the Program
[ The environmental program consists of effluent and i environmental monitoring for radioactivity. Liquid and gaseous effluents from the Beaver Valley Power Station and I the Shippingport Atomic Power Station were collected, processed, sampled, and analyzed to ensure conformance with l the applicable regulations and permits prior to their release to the environment. Environmental sampling and analyses included air, water, milk, soil, vegetation, river sediments, fish, and ambient radiation levels in areas surrounding both plants.
f 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 l in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land. Figure 1.0 is an artist's view g of both stations. The site is approximately one mile from
[ Midland, Pennsylvania; 5 miles from East Liverpool, Ohio; and 25 miles from Pittsburgh, Pennsylvania. Figure 1.1 shows the site location in relation to the principal population centers. Population density in the immediate vici.41ty of the
{ site is relatively low. The population within a 5 mile radius of the plant is approximately 18,000 and the only area g within that radius of concentrated population is the Borough
[ of Midland, Pennsylvania, with a population of approximately 4,300.
The site lies in a valley along the Ohio River. It extends
{ from the river (elevation 665 feet above sea level) to a ridge along the border south of the Shippingport and Beaver Valley Power Stations at an elevation of 1,160 feet. Plant ground level at both stations is approximately 735 feet abore 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 l Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream frcm the site. The river flow is regulated by a series of dam:. 2nd reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. Flow ranges from a minimum of 5000 cubic feet per second (CFS) to a maximum of 100,000 CFS. The mean annual flow is approximately 25,000 CFS.
k SECTZON I DUQUESNE LIGitT COMPAFI 1984 Annual Radiological Environmental Report I. INTRODUCTION
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B. Description of the Shippingport and Beaver Valley Site (continued)
Water temperature of the Ohio River varies from 32*F to 84*F, the minimum temperatures occur in January and/or February and g maximum temperatures in July and August. Water quality in l the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela, and Beaver rivers.
The climate of the area may be classified as humid continental. Annual precipitation is approximately 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 typ'cally from the southwest in summer and from the northwest in winter.
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L DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report I
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L r SECTION I DUQUESNE LIGHT C0!!PANY L 1984 Annual Radiological Environmental Report I. INTRODUCTION B. Description of the Shippingport and Beaver Valley Site (continued)
I L
The design ratings and basic features of the Beaver Valley Power Station and the Shippingport Atocic Power Station are Beaver Valley Shippingport
( Thermal & Elec. Rating - 2660 We 835 W, 236.6 We 72 W e W-Each Reactor Type of Reactor PWR PWR( )
Number of Reactor 3 4 Coolant Loops Number of Steam Generators 3 - Vertical 4 - Horizontal and Type Steam Used by Main Turbine Saturated Saturated Both stations utilize two (2) separate systems (primary and secondary) for transferring heat from the source (the reactor) to the receiving component (turbine generator).
Because the two systems are isolated from each other, primary and secondary waters do not mix; therefore, radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and stean generators by means of reactor coolant pumps. Heat is given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after passing through the turbine, and returned to the se.eam generators to begin another steam / water cycle.
NOTE: Wg -
megawatts thermal W, - megawatts electrical (1) The Shippingport Atomic Power Station was not operated during 1984 (2) Light Water Breeder Core
( SECTION II DUQUESNE LIGHT COMPANT lL 1984 Annual Radiological Environmental Report II. RESULTS AND CONCLUSIONS
( Plant operations at both the E aver Valley Power Station and the Shippingport Atomic Power Station had no adverse effects on the
[ environment as a result of activities at either of the stations i during 1984. Comparisons of pre-operational data with operational data indicates the ranges of values are in good agreement for both I periods of time.
j The Beaver Valley Power Station operated throughout 1984. The
'Shippingport Atomic Power Station which was -shutdown in 1982 completed defueling in 1984. During the year, the radioactive
{ releases from both stations were below the limits of 10 CFR Part 50, Appendix I and applicable permits for each station. The releases at Beaver Valley Power Station did not exceed the h limiting conditions identified in the Beaver Valley Power Station Operating License Technical Specifications.
The environmental program for 1984 was the same as in 1983 except
{- for several changes in dairy locations which were revised as required by the Beaver Valley Technical Specifications. (Refer to Table V. A.1 for the 1984 Radiological Monitoring Program Outline).
The results of the 1984 Radiological Environmental Monitoring Program are consistent with those of previous years. The only radioactivity above normal ambient levels in the environs other
(- than.world-wide fallout from Nuclear weapons tests was detected in the Beaver Valley Power Station discharge area and resulted in y negligible exposure to members of the public. A summary of the
[ 1984 operational environmental data (ranges and means) for each sampling media is found in Table V.A.2. A summary of preoperational (1974 - 1975) environmental data is found in Table V.A.3.
~
The Beaver Valley Power Station Technical Specifications require p sampling of three (3) dairies which have the highest calculated
[ milk pathway potential and one large local dairy. The three dairies are- determined from calculations based on the meteorological data and the latest milch animal survey. However,
{ these dairies are frequently small, consisting of as few as one cow or goat. The availability of milk from single cow dairies and revisions due to updated calculations and surveys result in
[ sampling of several additional dairies during the year in t different sampling periods.
[
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SECTION II DUQUESNE LIGHT COMPANY
{ 1984 Annual Radiological Environmental Report II. RESULTS AND CONCLUSIONS (continued)
In addition, the Environmental Monitoring Program includes two larger dairies in order to provide continuity in the
{- sampling / analyses program and a control location. Samples from each of these dairies are obtained each month in addition to the four dairies required by the Environmental Technical
[ Specifications. During some sampling periods, one or all of the
( additional dairies could be among the required dairies. The collection periods associated with each of the locations are provided in the detailed summary of the milk monitoring program of
( this report (Section V-E).
Examination of effluents from the Shippingport Atomic Power
[ Station and the Beaver Valley Power Station and environmental i media demonstrated compliance with regulations and Station l Technical Specifications.
(
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p SECTIOM III DUQUESME LIGHT COMPANY
( 1984 Annual Radiological Environmental Report III.- ENVIRONMENTAL MONITORING CONSIDERATIONS A. Environmental Quality Control Programs
( The Quality Control (QC) Program used for the Beaver Valley -
i Shippingport Environmental Padioactivity Monitoring Program consisted of seven (7) elemeats. It should be noted that the comparisons made were at very low levels of radioactivity and
(: consequently, the activities at these levels are difficult to measure. However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.
- 1. Radiation Monitoring (Duquesne Light Company (DLC)
Contractor Laboratory: Two Independent Systems h (CaS0t:Dy and CaS0u:Tm) - DLC - QC Laboratory An independent program of externa) radiation monitoring was conducted by the QC Laboratory using lithium l1 fluoride TLDs sharing the same location as the DLC Contractor Leboratory TLDs. In 1984 a QC Laboratory was used in the first three quarters, prior to contracting a f new QC Laboratory. The new DLC QC Laboratory will begin external radiation monitorino in the first quarter of 1985. Summary data of the QC Laboratory program is provided in Table III.1.
Adequate quality control of TLDs was demonstrated by duplicate contractor TLD, QC TLD, Annual TLD, and continuous integrating monitoring by a Pressurized Ion Chamber (PIC) which show generally good agreement and demonstrate acceptable performance by the DLC Contractor Laboratory. The arithmetic mean of each TLD System agrees within i 10% of the arithmetic mean of the three TLD Systems. 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, F samples of other media, such as milk, soil, sediment and feederop were also split with the DLC QC Laboratory (a laboratory of tne Department of Energy).
k
[ SECTION III DUQUESNE LIGHT CO?!PANY L 1984 Annual Radiological Environmental Report III. ENVIRON'! ENTAL ?!ONITORING CONSIDERATIONS A. Environmental Quality Control Programs (cont inued)
- 2. Split Sample Program (DLC Contractor Laboratory - DLC QC
{ Laboratory (continued)
A summary of results of split water samples is provided in Table III.2. A summary of milk, sediment and feea/ food crop split samples is provided in Table III.3.
Some variation is expected due to, small variations in duplicate samples, variations in analytical procedures, and in calibration, source type, etc.
Because of the overall uniformity of comparable results, it is concluded that the two laboratories are consistent and in agreement.
'Section III CUQUESNE LIGHT CCMPAN7 TABLE III.1 1984 Ar.nual Radiological Environmental Report TABLE III.1 QUALITY CONTROL RESULTS TLD MONITORING
-9/2av 1ST 00ARTE9 250 QUARTER DLC OLC 1 OLC QC DLC DLC DLC QC . OLC DLC j Location Contractor Lab CONTRACTOR PIC Contractor Lab CCNTRACTOR PIC Mo. (Ca50.:Dv) (LtF) 1Q50 :Tm) 3 Hj, laS0pDy) (LiF) (#CaSO.:Tm) [21
{
to 0.16 0.21 0.18 0.21 0}
f 0.17 0.13.~ 0.17 0.22 III 13 0.15 0.21 0.21 0.16 0.18 0.19 14 0.15 0.21 0.19 0.17 0.16 0.19 15 0.14 0.16 0.14 0.13 0.13 0.15 27 0.15 0.21 0.18 0.17 0.17 0.16 28 0.16 0.22 0.21 0.17 0.18 0.18 298 0.18 0.26 0.18 0.20 0.21 0.21 32 0.19 0.25 0.18 0.23 0.19 0.19 0.22 0.22 45 0.16 0.24 0.18 0.25 UI 0.18 0.17 0.21 0.25 III 46 0.13 0.18 0.18 0.19 0.15 0.17 0.17 0.19 47 0.17 0.25 0.21 0.18 0.22 0.18 48 0.18 0.23 0.19 0.18 0.18 0.19 51 0.18 0.22 0.19 0.18 0.18 0.20 f 3RD QUARTER 4TH OUARTER DLC DLC
( DLC QC . DLC DLC DLC QC OLC CLC
[ Location Contractor (C450.:0v)
Lab Contractor (CaSO,:Tm)
PIC Contractor Lab Contractor FIC No. (L1F) 21 (C450.:Dv) (L1F) (CaSO,:Tm) to 0.14 El 0.15 0.20 0.21 0) 0.17
- 0.18 0.21 III L; 13 0.14 0.17 0.19 0.17
- 0.17 14 0.15 0.16 0.21 0.17
- 0.17 15 0.13 0.13 0.17 0.13
- 0.15 27 0.15 0.17 0.21 0.15
- 0.17
- 28 0.16 0.19 0.20 0.17
- 0.19 298 0.17 0.21 0.26 0.20
- 0.24 g 32 0.16 0.17 0.21 0.22 0.18
- 0.23 0.23 l 45 0.18 0.21 0.23 0.25 UI 0.19
- 0.21 0.25 0) 46 0.15 0.14 0.21 0.18 0.14
- 0.17 0.18 47 0.16 0.17 0.23 0.17
- 0.23 48 0.17 0.15 0.22 0.16
- 0.19 31 0.18 0.18 0.21 0.17
- 0.18 3 witched ;C :.acs in 4th Quarter. New QC *ao vill start "_Ds in ist Quarter 1995.
(1) PIC Reading at Location 10 taken in DLC Substation in Shippingport Boro. Location 45 caken at Kennedy's Corners Location 46 tacan at Industry Iire S{.op.
G) , _ ,
In this consolidated environnental progras the p.essurizes ion chambee (PIC):entinuous monitor readings tend system. to be slightly higher than the ILD readings due to the differences in the inherent physics of each No cc pensatory measures have been taken to make both syste=s agree exactly because both systems were installed to waitor relative radiation levels rather than absolute levels. 7.ach system provides
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-a reascnaoly accurate =easure of the absolute radiatten levels.
1984 Annual Radiological Environmental Report (Page 1 of 2)
L TABLE III.2 OUALITY CONTROL RESULTS SPLIT !AvP'.E INAlv!!S 2E!ULTS Comearison of Contractor ind OLC-0C Labs L
DLC Contractor DLC - QC Media Analysis Samoling Deriod Lab (1) Lab (1) Units Surface Water Gross Alpha January 1 1.1 2.9 2 2.0 pCi/l April 1 0.8 1 2.6 PC1/1 July i 1.2 3.3 2 3.1 pC1/1 October 1 0.97.
2.7 2 1.9 pC1/1 Surface Water Gross Beta January 4.5 2 1.6 5.4 2 1.8 pC1/1 April 7.3 : 0.7 7.9 2 1.9 pC1/1 July 8.3 2 0.7 7.4 2 2.0 pCi/1 October 8.S 0.8 6.1 1.8 pC1/1 Surface Water Co-60 January 12.0 13.3 pC1/1 April 12.0 4.9 2 3.5 (2) pC1/1 July < 1.0 < 3.4 pCi/l October < 1.0 < 0.9 pC1/1 Surface Water Ca-134 Januarv < 2.0 < 4.5 pC1/1 April < 2.0 < 3.0 pC1/1 July < 1.0 < 2.5 pC1/1 October < 1.0 < 0.9 pC1/1 Surface Water Cs-137 January < 2.0 < 4.8 pC1/1
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-- Kp rii < 2.0 1.7 pC1/1 July < 1.0 < 2.6 pC1/1
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October < 1.0 < 1.0 pC1/1 Surface Water Tritium ist Quarter 1290 2 100 1700 2 250 pC1/1 Composite 3rd Quarter 2000 2 200* 1150 2 120 pC1/1 Composite Surface Water Sr-89 2nd Quarter Composite i 1.1 1 0.70 pC1/1 4th Quarter < 1.9 10.5 pC1/1 Composite
/
Surface Water Sr-90 2nd Quarter Composite 15 0 10.24 pC1/1 4th Quarter -< 0.3 10.2 pC1/1 Composite Surface Water Co-60 2nd Quarter < 0.8 ~< a.S pCi/l (high Composite -
sensitivity analysis) 4th Quarter < 1.0 11.4 pC1/1 Composite (1) L*ncertainties are based cn counting statist'.cs and are specified at the 93* confidence interial.
Five of six Tritius analyses in water are in good agreement. See Tables !!!.2 and !!!.7.
(2) The activity was due to suspenned solids fr:s river bottom sedi-ents.
L Section III DUQUE5hE LIGriT COMPANY IABLE III 2 1984 Annual Raciological Environmer.tal Report (Page 2 of 2) f L
TABLE !!!.2 (Continued)
OUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULT 5 L
Moarison of Contesctor and DLC-00 Labs r DLC contractor OLC - QC Media An_al ysis Sampling Period Lab (1) Lab (1) Units Drinking Water Cs-i3 7 Tebruary I
i 3.0 15.0 pCL/1 May i 3.0 < 2.5 pC1/1 August i 3.0 1 2.7 pC1/1 November i 3.0 1 2.I pC1/1 Drinking Water Cs-134 February < 3.0 < 5.0 pC1/1 May 1 2.0 1 2.6 pCi/1 August i 3.0 pct /1 1 2.6 Noverber < 3.0 < t.8 pC1/1 Drinking Water Co-60 February i 3.0 < 4.4 pCi/1
, May 12.0 1 2.4 pC1/1 August i 3.0 1 2.2 pC1/1 November 12.0 pCL/1 1 1.9 Drinking Water Cros. .\1pha M reh 0.29 . l.1 pC1/1 June 1041 1 2.0 pCi/1 August '
- 1.41 2.8 2 2.5 pCL/1 November < 0.36 0.37 pCL/1 Drinkitg Water Cr' ass Beta M. tech 5.1 1.4 2.4 2 1.9 pC1/1 June 3 . fi t 1.4 6.0 !.3 pC1/1 August 4.6 2 1.5 4.7 2 1.7 pC1/1 November 4.2 2 t.6 L.972 0.55 pC1/1 Orinking Water Tritium 2nd Quarter 2 70 t 70 1 210 pC1/1 4th Quarter 260 190 ; 109 pC1/1
'!)
Unc e rtain t ie s are based 2n counting .tatistics and are specified at the 951 cantidence interval.
'Section !!! DUQUESNE LIGHT COMPANY TA8LE 111.3 1984 Annual Radiological Environmental Report (Pagt 1 of 2)
TA8LE !!!.3 QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and CLC-0C Labs DLC Contractor DLC - QC f g Analysis Samplina Period Lab (1) Lab (1) Units
!- Kilk I-131 3-19-84 < 0.1 < 0.25 pC1/1 (Location 23) Sr-89 3-19-84 11.1 1 0.92 pCi/l Sr-90 3-19-64 2.120.7 2.820.87 pC1/1 Cs-134 3-l9-84 L
12.0 14.8 pC1/1 Cs-137 3-19-84
,(Location 25) Cs-134 6-19-84
(
12.0 14.8 pC1/1 Cs-137 6-19-84 12.0 14.7 pC1/1 Co-60 6-19 84 12.0 14.1 pC1/1 Feed Co-60 6-19-84 < 0.02 1 0.066 pCI/gm Dry (Location 23) Cs-134 6-l9-84 1 002 1 0.075 pCi/gm Dry Cs-137 6-19-84 1 0.02 1 0.074 pC1/ga Dry Faed St-90 6-19-84 0.17 2 0.01 1 0.037 pct /gm Dry (Location 25)
Food I-L31 8-29-84 < 0.013 < 0.077 pC1/gm Wet
- (Location 10)
(Cabbage) Co-60 3-29-84 < 0.004 < 0.013 pC1/gs tJet Cs-134- 8-29-84 < 0.005 e 0.013 pct /gm Wet Cs-137. 8-29-84 < 0.005 < 0.013 pC1/gm Wet (1) Uncertainties are based on councing statistics 2nd are specified at the 952 ccnfidence interval.
t Section !!!' DUQUESNE LIGHT COMPAN7 TABLE !!!.3 1584 Annual Radiological Environmental Report (Page 2 of 2)
TABLE III.3 (Continued)
QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs DLC Contractor DLC - QC Media Analysis Samplino Period Lab (1) Lab (1) Units S:diment Cross Alpha 9-4-84 5.6 2 3.9 17 2 6 pC1/gm Dry (Location 3) Gross Beta 9-4-84 34 2 3.0 34 2 4.1 pC1/gm Dry I U-235 9-4-84 0.022 2 0.01 1 0.11 pCi/gm Dry U-234 9-4-84 0.79 1 0.06 1.1 1 0.38 pCi/gm Dry U-238 9-4-84 0.58 2 0.05 0.56 1 0.26 pri/gm Dry Sr-89 9-4-84 1 0.049 1 0.14 pCi/gm Dry Sr-96 9-4-84 0.044 1 0.023 ; 0.53 pC1/gm Dry Co-60 9-4-84 0.339 2 0.097 0.22 2 0.007 pCi/gm Dry Cs-134 9-4-84 1 0.04 1 0.049 pC1/gm Dry Cs-137 9-4-84 0.423 2 0.086 0.58 2 0.08 pC1/gm Dry Milk I-131 9-25-64 ; 0.I g 0.2 pC1/1 (Location 25) Sr-89 9-25-84 ; 1.3 pCi/1 1 0.4
$r-90 9-25-84 2.9 1 1.0 2.7
- 0.6 pC1/1 Cs-134 9-25-84 ,3.0 g 1.9 pC1/1 Cs-137 9-25-84 1 3.0 1 2.0 pC1/1 K-40 9-25-84 1190 t 120 L280 t 130 pC1/1 Milk I-131 12-10-84
[ 1 0.L 1 0.2 pCi/1
( (Locetton 25) Cs-134 12-10-84 1 2.0 1 2.8 pC1/1 Cs-137 12-10-84 1 2.0 ; 3.0 pci/1 K-40 12-l0-84 1130 t 130 1260 t 160 pC1/1 l
(
(1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
t
[ SECTION III DUQUESNE LIGHT COMPANY L 1984 Annual Radiological Environmental Report III. ENVIRONMFNTAL MONITORING PROGRAMS A. Environmental Quality Control Programs (continued)
- 3. DLC QC Laboratory Program Spiked samples prepared by DLC QC Iaboratory were routinely submitted to the Contractor Laboratory for analysis. Tables III.4 (water) and III.5 (milk) provide data from this portion of the QC Program. The overall results demonstrate that the contractor performea acceptably in the program.
- 4. Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory)
Duplicate air particulate and charcoal filters (radioiodine) samples were collectad at Location #30 and compared during the year on a weekly basis. Comparison of particulate and charcoal samples alternated from week to week. Duplicate monthly air particulate filters, r
composited from the weekly air particulate filters, were L analyzed 6 months out of the year for gamma activity.
Duplicate quarterly air particulate filters, composited from the weekly air particulate filters, were analyzed I
for Sr-89 and Sr-90 activity for the first and third quarters of the year. Table III.6 provides data for this portion of the QC program. The results show
[ generally good agreement between the laboratories and L demonstrate that the contractor performed acceptably in
. the program.
[ which included participation in the Environmental L Protection Agency -
Environmental Monitoring Safety Laboratory (EPA - EMSL) Interlaboratory Cross Check Program. This cross check program indicated that the
[ Contractor results were in agreement with 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.
1 l
SECTION III DUQUESNE LIGHT COMPANY l 1984 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS 1
l A. Environmental Quality Control Programs (continued)
- 6. Special QC Program (DLC Contractor Laboratory -
1 Independent Laboratory - DLC QC Laboratory)
Milk and water samples were prepared quarterly by an Independent Laboratory. This included low level spiking l
I of specified nuclides. The prepared samples were split three ways and analyzed by the DLC-QC Laboratory and Independent Laboratory as well as the Contractor iaboratory. A summary of results of this portion of the CC program is provided in Table III.7. The results show
- enerally good agreement between the laboratories and l 1emonstrate that the contractor performed acceptably in the program, l
t I
i l
l l
(L Section !!! DUQUESNE LIGHT COMPANY TABLE !!I.4
.1984 Annual itadiological Environmental Report TA8LE :11.4 QUALITY CONTROL RES'.1TS Epir !>o'.! MAL?t!! 2TrJt.*!
!a:le *g;e 10 and Contractor CLC - QC
- Samole Date Ident. No. Analysis Lab (1) Lab (1) Units
?
4-23-84 53-58 Vater Sr-89 81
- 4 94
- 5.3 pC1/1 St-90 31 2 1 37 2 3.5 pC1/1 7-5-44 53-59 Water: Co-58 18.6 2 4 19 2 7.8 pci/1 Co-60 24.8 2 5.3 29 2 7.4 pCi/1 1-131 3.6 2 0.2 4.4 2 0.83 pC1/1 Ca-134 24.724.8 16 2 7.7 pC1/1 8-7-44 A/8-1 Water Cross Alpha pC1/1
$ 1.1 1 3.5 Cross 3 eta i 1.5 1 3.0 pC1/1 A/8-2 Water Cross Alpha 4.8 2 1.8 2.3 2 2.3 pCi/1 Cross Seta 6.2 2 1.9 1 3.0 pC1/1 A/8-3 Water: Cross Alpha 9.1 2 2.3 9.2 e 3.1 pci/1 l Gross Seta 15 t 2.0 11 2 4.2 pC1/1 A/8-4 Waters Cross Alpha 14 2 3.0 19 2 4.0 pC1/1 Gross Beta 24 2 3.0 29 2 5.1 pC1/1 A/8-5 Waters Cross Alpha 43 2 5.0 39 2 5.5 pCi/1' Gross Beta 45 2 3.0 50
- 5.5 pci/1 10-19-64 W-1 Water: H-3 4550 2 500 4490 2 560 pCi/1 9-30-44 W-2 Water Sr-89 38 2 5 43.7 2 5.1 pC1/1 St-90 54 2 2.0 53.4 2 6.2* pct /1 Cs-137 79.1 2 7.9 . 62.7
- 8.0 pC1/1 10-28-84 W-3 Water Cs-137 84.9 2 8.5 68.1 8.7 pC1/1
(
L (1) L'ncertainties are based on countin8 statistics and are specified at the 95% confidence interval.
Section Ill DUQUE$NE LIGHT COMPANY TABLE III.5 1924 Annual Radislogical Environmental R: port t
k TABLE !!!.5 QUALITY CONTROL RESULTS
$P!KE SAMPLE ANALYS!$
Sample Type DLC and Contractor OLC - QC Sample Date Ident. No, Analysis Lab (1) Lab (1) Units 4-23-85 52-61 Milk: Sr-89 1322 14 2 1.8 pC1/1
$r-90 11 2 1 17 2 2.6 pC1/1 I-131 6.8 2 0.3 6.5 2 0.46 pC1/1 Co-58 16.6 2 4.9 12 2 7 pC1/1 Ru-106 359 2 63 320 2 72 pC1/1
$b-125 18.7 2 10.7 20 2 18 pC1/1 Ca-144 66.1230 54 2 44 pCL/1 7-5-84 52-62 Milk: 1-131 30 t t* 36 2 1.9 pC1/1 Cs-134 35 : %.6 39 2 7.6 pC1/1 Cs-137 12.9 2 4.2 1627.7 pC1/1 10-16-14 52-63 Milk Sr-89 6.2 2 1.1 ** 13 2 4.4 pCi/1 St-90 8.9 1 0.9 *** 13 2 2.7 pC1/1 1-l31 35 2 1 36 2 .9 pC1/1 Cs-137 31.8 2 4.8 31 2 7 pC1/1 (0-28-84 MI-L Milk I-131 120 t 10 127 2 17 pC1/1 Cs-137 232 2 23 184 2 l9 pC1/1 e
Seven of eight I-131 spiked milk samples are in good agreement. See Tables III.5 & III.7.
Four of six St-89 spikalmilk samples sre in good agreenent. See Tables III.5 & III.7.
- e rty, af et t St-90 spiked silk samples are in good agreement. See I4bles III.5 & III.7.
(15 Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
l l
section III OUQUESNE LIGHT COMPANY TA8LE III.6 1984 Annual Radiological Environmental Report (Page 1 of 4)
I 1
L TABLE III.6 0UALITY CONTROL RESULTS AIR 9 ARTICULATES AND WCOAL MLTEh +C90aoAstE P os_E5 Air P3rtic'J14tes Air Iodine pC1/Cu. Meter (Beta) pC1/Cu. Meter I DLC DLC L Contractor OLC - QC Contractor CLC - QC Sample Cate Lab (1) Lab (1) Samle Date Lab (1) Lab (1) 1/3/84 to 0.024 2 0.004 0.032 2 0.003 1/9/84 to < 0.018 1/9/84 ~< 0.008 1/16/84 ~
1/16/84 to 0.031 2 0.004 0.039 2 0.003 1/23/84 to < 0.008 1/23/84 2.0.011 1/30/84 1/30/94 to 0.016 2 0.003 0.026 2 0.002 2/6/84 to 2/6/84 -< 0.01 1 0.027 2/13/84 2/13/84 to 0.016 2 0.003 0.021 2 0.002 2/21/84 to 2/21/34 ~< 0.008 1 0.025 2/27/84 2/27/84 to 0.011 2 0.003 0.018 2 0.002 3/</84 to 3/5/84 ~< 0.0' 1 0.016 3/12/84 3/12/84 to 0.014 2 0.003 0.029 2 0.002 3/19/84 to 3/19/84 -< 0.008 1 0.012 3/26/84 3/26/84 to 0.012 2 0.003 0.015 2 0.002 4/2/84 to 1 0.019 4/2/24 ~< 0.006 4/10/84 4/10/8* o 0.012 2 0.004 0.017 2 0.002 4/16/84 to 1 0.021 4/16/84 ~< 0.007 4/23/84 4/23/84 tc 0.017 2 0.003 0.022 2 0.002 4/30/84 to 4/30/84 -<0.007 1 0.014 5/7/84 5/7/84 to 0.012 2 0.003 0.015 2 0.002 5/14/84 to 1 0.013 5/14/84 -< 0.008 5/21/84 5/21/84 to 0.017 2 0.003 0.024 2 0.002 5/29/84 to 5/19/84 ~< 0.01 1 0.011, 6/4/84 6/4/84 to 0.030 2 0.004 0.040 2 0.003 6/11/84 to 1 0.010 6/11/84
~< 0.006 6/18/84 6/18/84 to 0.018 2 0.003 0.023 2 0.002 6/25/84 to 1 0.017 6/25/84 ~<0.008 7/2/84 7/2/84 to 0.013 2 0.003 0.022 2 0.002 7/9/84 to 1 0.029 7/9/84 ~<0.008 7/16/84 (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
[-
Section !!! DUQUESNE LIGHT COMPANY TA8LE !!!.6 1994 Annual Radislogical Environmental Report (Page 2 of 4)
TABLE !!!.6 (Continued)
QUALITY CONTROL RESULTS AIR PARTICULATES AND CHARC0AL FILTER: COMPARABLE SAMPLES
{ .
Air Particulates Air fodine PC1/Cu. Meter (Beta) pC1/Cu. Meter
Seele Date Lab (1) Lab (1) Sassle Date Lab (1) Lab (1) '
( '7-16-84 to 0.017 2 0.003 0.022 2 0.003 7-23-84co 7-23-84 -< 0.007 < 0,007
(. 7-30-84 -
7-30-84 to- 0.018 2 0.003 0.027 2 0.002 8-6-84 to 8-6-84 8-13-84
~< 0.007 ~< 0.016 8-13-84 to 0.028
- 0.004 0.032 2 0.003 8-20-84 to <
8-20-84 8-27-84
~< 0.005 ~ 0.006 8-27-84 to 0.032 2 0.003 0.033 2 0.002 9-4-84 to <
9-4-84 9-10-84
~< 0.00 7 ~ 0.005 9-10-84 to 0.018 2 0.003 0.023 2 0.003 9-17-84 to 9-17-84 -e 0.005 ~
< 0.03 9-24-84 9-24-84 to 0.014 2 0.003 0.020 2 0.003 10-1-84 to 10-1-84
- 0.005 < 0.03 10-8-84 10-8-84 to 0.021 2 0.004 0.030 2 0.003 10-15-84 to LO-15-84 10-22-84
-< 0.004 -< 0.03 in 27 s4 to 0.024 2 0.004 0.027 2 0.004 to-29-84 to <. 0.005 <, 0.03 10-29-84 (1-5-84
!!-5-84 to 0.021 2 0.004 0.022 2 0.004 11-12-84 to 11-12-84 ~
- 0.004 <
~ 0.03 11-l9-84 11-L9-84 to 0.026
- 0.004 0.032 2 0.004 11-26-84 to
. 11-26-44 12-3-84
-< 0.006 -< 0.03
.2-3-84 to 0.022 2 0.004 0.028 2 0.004 12-10-84 to < 0.006 12-10-84 ~ ~< 0.03 12-17-84 12-17-84 to 0.025 2 0.004 0.030 2 0.004 12-24-84 to 62-24-84 12-31-84
~< 0.006 ~<
0.03
( .
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m L ..ct.1.t1.. .t. ... 8 .. . _ tm 8 .t.ti.tio. _8 .t. ... 1,1 8 .t t,. ,,, _ ,18 _ . 1.t.c 1.
Section !!! DUQUESNE LIGHT COMPANY TABLE III.6 1984 Annual Radiological Environmental Report (Page 3 of 4)
L TABLE !!!.6 QUALITY CONTROL AIR PARTIC'.:LATES f eCf /n31 DLC Contractor OLC - QC
$ ample Date Nuclide L&D (I) Lab (1)
January (12/27/83 to 1/30/84) Se-7 0.098 2 0.011 0.12 2 0.026 Others LLD IJ.D March (2/27/84 to 4/2/84) Be-7 0.117 2 0.015 0.074 2 0.015 Others LLS LLD May (4/30/84 to 5/19/94) Be-7 0.140 2 0.021
' 0.110 2 0.020 Others LID LLD July (7/2/84 to 7/30/84) Se-7 0.126 2 0.026 0.22 2 0.032 Others LLD LLD September *
(8/27/84 to 10/1/84) Be-7 0.119 2 0.015 0.100 2 0.02 Cs-137 0.0012 2 0.0010 10.0004 Others LLD
, LLD November (10/29/84 to 12/3/84) Se-7
( others 0.117 2 0.012 LLD 0 094 2 0.010 LLD '
l (1) *.*ncertaisties are based on asunting statistics and are specified at the 932 confidence interval.
LLD Lover limit af detection.
f k
Section !!! DUQUESNE LIGHT COMPANY TABLE III.6 1934 Annual Radiological Enutronmental RGport (Page 4 of 4)
TABLE III.6 QUALITY CCNTROL C
AIR PARTICULATE LOCATION AND CHARC0AL FILTEk 3)CMPARABLE SAMPLES 30 - (DC1/m 1
DLC Contractor DLC - QC
( Sample Date Nuclide Lab (1) Lab (1)
Ist Quarter Composite Sr-89 1 000099 1 0.00068 Sr-90 < 0.00012 < 0.00017 3rd Quartet Composite Sr-89 1 000090 2 0.0008 St-90 < 0.00011 <0.0002
(
(
(
l
{ .
{
l
{
(1) Uncertainties are based on counting statistics and are specified at the )$% confidence interval.
h Section !!! Ou0UE3NE LIGHT COMPANY TABLE III.7 1984 Annual Radio 1cgical Environmental Report (Pagt 1 of 2)
TABLE 111.7-QUALITY CONTROL DATA QC Sample Comparisons l
(All Analyses in oCf/1)
Sample Type DLC and Independent Contractor OLC - QC Ident. No. Analyses Lab (1) Lab (1) Lab (1)
(. Sample Date 2-29-84 53-255 Water Sr-90 16 2 0.7 16 2 1.0 14 1.6
. I-131 5.2 2 0.2 5 2 0.2 6.5 2 1.1-1t1-54 24
- 7 30.3 2 4.8 22 2 11 Cs-134 24 2 8 18.1 2 4.2 18211 Cs-137 33 2 8 37.6 2 6.9 26 2 12 2-29-84 53-256 Water: H-3 1100 2 200 1340 2 90 1300 2 250 J 3-9-84 53-257 Waters Sr-39 to 2 2 8.8 2 1.3 8.5 t 2.5 St 10.4 2 0.6 10 2 1.0 10 2 1.6
. I-131 18 2 1 14 2 1.0 17 2 1.7 Co-58 21 2 7 21.4 2 4.2 24 2 8.8 Co-60 24 2 8 24.9 2 4.2 24 2 7.2 3-9-84 53-258 Waters !!-3 1240 2 110 1720 2 110 1100 2 210 8-8-84 53-259 Waters Sr-90 22.2 2 0.7 21 2 1 22 2 1.3 1-131 8.7 1 0.4 9.720.3 11 2 1 Fe-59 28 5 41.1 2 8.6 46 2 16 ,
Cs-134 18 2
- 16.9 2 3.% 17 2 6.4 Co-137 26 2 4 26.2 2 4.4 22 2 6.1 8-8-84 53-260 Water H-3 955 t 70 1200 2 100 1510 2 520 11-7-84 53-261 Waters $r-89 16 2 2 11 2 1 13.7 2 1.3 l Sr-90 20.1 2 0.6 14 2 1 14.0 2 1.2 1-131 8.9 2 1.1- 16 2 1 12.5 2 0.6 Co-58 29 2 8 30.1 2 6.4 32.326.7 Co-60 33 2 8 34.8 2 7.3 39.3 2 7.3 11-7-84 53-262 Water H-3 1600 2 200 1700 2 100 1651 2 350 l
{
{
l l.
(1) Uncertainties are based on countin$ statistics and are based at the 95% confidence interval.
L Section III DUQUESNE LIGHT COMPANY TABLE III 7 1984 Annual Radioltgical Envirormental Report (Page 2 of 2) f'L- TABLE !!!.7 QUALITY CONTROL DATA OC 04 mole Ocmpartscns F- (All Analyses in DCf/l) k Sample Type DLC and Independe Contractor DLC - QC Sample Date Ident. No. Analyses Lab (1) Lab (1) Lab (1) 2 29-84 52-230 Milk Sr-89 to 2 2 7.6 2 1.1 8.7 2 4.6 d Sr-90 12.3 2 0.8 12 2 1.0 13 1 2.5 I-131 25
- 4 21 2 1.0 18 2 1.4 Cs-134 18 2 4 13.9 2 6.1 13 2 7.6 Cs-137 31 2 4 34.2 2 5.3 30 2 8.6 5-9-84 52-231 Milk: $r-89 522 5.2 2 1.4 5.0
- 3.1 St-90 13.8 2 0.6 9.9
- 1.0 12.0
- 1.6 I-131 9.4
- 0:5 9.0 2 0.2 9.0
- 1.9 Cs-134 16 2 4 13.4 2 4.5 14 2 7.7 Cs-137 2924 30.4 2 5.5 27
- 8.0 8-8-84 52-232 Milk Sr-89 10 2 2 7.5 2 1.1 12 2 3.4
( 3r-90 16.4 2 0.6 14 2 1 15 1.9 I-131 13.4 2 0.3 13 2 1 13 2 0.9 Cs-134 1524 21.425.5 16 2 7.5
'Cs-137 20 ,2 4 28.6 2 5.5 21 2 9.1, 11-7-84 52-233 Milk: Sr-89 10.2 2 1.4 3.0 2 1.5
- 9.8 2 1.3 Sr-90 22.2 2 0.7 11 2 1 11.7 2 0.9 I-131 8.0 2 0.8 8.3 2 0.5 6.3 2 0.2 Cs-134 19 2 4 21.7 2 4.5 14.5 2 3.9 Cs-137 2924 33.8 2 4.6 29.0 2 6.9
(
( .
{
l five of six 3r-40 spiked stik samples are in pod agreement. See I4bles !!:.5 an$ III.*.
(1) t*ncertainties are based on the counting statistics and are based at the 95: confidence interval.
p-s SECTION III DUQUESME LIGHT COMPA.W
{ 1984 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING PROGRAM A. Environmental Quality Control Programs (continued)
- 7. Nuclear Regulatory Commisssion (NRC) Program
{
The Nuclear Regulatory Commission (NRC) also conducted a j I
surveillance program in the vicinity of the site.
Samples of air, river water, drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program. The Commonwealth of
{. Pennsylvania's radiological laboratory is utilized by the NRC for analyzing these samples. Comparison of results also indicated agreement between the NRC Laboratory and the Duquesne Light Company Contractor
( Laboratory.
B. Evaluation of the Quality Control (QC) Program Data The split sample program indicates that the Contractor laboratory is performing satisfactorily. In addition, three
( (3) independent laboratories are used to supplement the l regular program. Comparisons between" the independent laboratories and the Contractor laboratory is acceptable, and demonstrates a satisfactory performance by the DLC
( contractor.
Based on all available QC data and the data from the ,
[ Contractor's internal EPA Interlaboratory Cross Check l Program, the Environmental Monitoring Program for 1984 is acceptable with respect to both accuracy and measurement.
f C. Standard Requirements and Limitations for Radiological and Other Effluents
[ The Shippingport Atomic Power Station and Beaver Valley Power L
Station are governed by rules and regulations of the Federal Government and the Commonwealth of Pennsylvania. E f fluent releases at both stations are controlled to ensure that f limits set by Federal or State governments are not exceeded.
In addition, self-imposed limits have been established to further limit discharges to the environment.
l
(
(
b SECTION IV DUQUESNE LIGHT COMPANY
{ 1984 Annual Radiological Environmental Report-IV. MONITORING EFFLUENTS h
A. Monitoring of Liquid Effluents Description of Liquid Effluents at the Shippingport Atomic
[' Power Station and the Beaver Valley Power Station, r Most of the water required for the operation of the Beaver
( Valley and Shippingport stations is taken from the Ohio River, and returned to the river, used for makeup to various plant systems, consumed by station personnel, or discharged
( to a septic system. In addition, small amounts of well water and liquid effluents are discharged to the Ohio River using l discharge points shown in Figure 4.1. Figures 4.2 through
- r. 4.5 are schematic diagrams of liquid flow paths for
( Shippingport and Beaver Valley respectively. The following four (4) tables summarize radioactive liquid effluents at both the Shippingport and Beaver Valley Power Stations:
( Table IV.A.1 - Effluent Treatment, Sampling, and Analytical Procedures - Shippingport
( Table IV.A.2 - Effluent Treatment, Sampling, and Analytical Procedures - Beaver Valley
(- Table IV.A.3 - Results of Liquid Effluent Discharges to the Environment - Shippingport
( Table IV. A.4 - Results of Liquid Effluent Discharges to the l Environment - Beaver Valley
(
[
{
l
SECTION IIf
( DUQUESNE LIGHT C0!!PANY 1984 Annual Radiological Environmental Report III. ENVIRON!! ENTAL ?!ONITORING PROGRA>!
C. Standard Requirements and Limitations for Radiological and Other Effluents (continued)
Shippingport Atomic Power Station is operated in compliance with regulations and permits involving radioactive and other effluents. Limits noted in Department of Energy (DOE) Orders
(- 5484.1 and 5480.1, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No. 1-70 and 2-70, Pennsylvania Department of Environmental Resources -
( Industrial Vaste Permit #1832, and Environmental Protection Agency (EPA) National Pollutant Discharge Elimination System (NPDES) Permit #PA-0001589, Pennsylvania Department of
[ Environmental Resources Industrial Waste Permit #0472205, and i Pennsylvania Department of Environmental Resources Radioactive Gaseous Discharge Permit are observed and followed.
l Beaver Valley Power Station is subject to regulations which include the Code of Federal Regulations 10 CFR (Energy),
( Pennsylvania Department of Environmental Resources (PDER)
L Industrial Vaste Permit #0473211, Sewage' Treatment Facilities Permit #0479403, Gaseous Discharge Permit #04-306-001, PA Code - Title 24, Part I, Ohio River Valley Water Sanitation
( Commission (ORSANCO) Standards No. 1-70 and Environmental Protection Agency (EPA), National Pollution 2-70, Discharge Elimination (NPDES) Permit #0025615, and the Beaver Valley Power Station Technical Specifications.
{
D. Reporting Levels f A report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an environmental sampling medium exceeds the limits specified in the Beaver Valley Power Station Technical Specifications when
( averaged over any calendar quarter. Also, when more than one of the radionuclides are detected in the sampling medium, this report shall be submitt.ed if:
Concentration (1) , Concentration (2) , . . .2 1.0 Limit Level (1) Limit Level (2)
There were no analytical results of environmental samples during 1984 which exceeded Beaver Valley Power Station reporting levels.
{
l L
SECTION TV FIGURE 4.1
( 1984 Annual Radiological Environmental Report DUQUESNE LIGHT COMPANY 2
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SECTION IV FIGURE 6.2 0000ESiE LIGHT CCITIM 1984 Annual Padiological EnvizcrTaental Peport sECTIoN IV
{ FIGURE 4.2 m
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L SECTION ZV FIGURE 4.3 DUQUESNE LIGHT COMPAlff s 1984 Annual Radiological Environ::: ental Report
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/ DUQUESNE LIGHT COMPANY L 1984 Annual Radiological Environmental Report r
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w SECTION IV TABLE IV.A.1 TABLE IV.A.2 DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report TABLE IV.A.1
- 1. Effluent Treatment. Samplino and Analytical Procedures - Shiccincoort i Treatment. Sampling Standard and/or Effluent Tvoe and/or Monitorino Analytical Procedures s
I Radioactive Collected, segregated and A 3000 m1 sample was counted for gross garran activity. h counter Waste Liquids processed as one of two types (i of liquid wastis: can measure a minimum detgetable activity (MDA) of 4 x 10' uC1/ml.
(a) special waste Also, a 100ml sanple is evaoorated (b) radioactive waste and counted for g ess beta activity.
'!his counter can measure a minirum Sample taken of batch before detectable activity (MDM of 1 x 10 pCi/ml.
processing to remove radio- t activity and reuse in plant systems. See Figure 4.4.
TABLE IV.A.2
- 1. Effluent Treatment. Samp11no and Analytical Procedures - Beaver Valley Treatment. Sampling Standard and/or Effluent Type and/or Monitorino Arplytical Procedures (a) Steam System Recycled or directed to Radwaste If discharged, procedures adhere Blowdown System for discharge, to Technical Specifications.
l (b) Radioactive Effluents shall not exceed Procedures adhere to requirements Weste values specified in the Technical of Technical Specifications.
Specifications. All discharges are perfomed in accordance with the Offsite Dose Calculation Manual (00CM).
(
l,
SECTION IV DUQUESNE LIGHT COMPANY
{- - 1984 Annual Radiological. Environmental Report TABLE IV.A.3
- 2. Results: Shippingport
(-
. Effluent Type Results for 1984 (a) Steam System Because of final plant shutdown on October 1, Blowdown 1982, there were no boiler blowdowns during 1984.
(b) Radioactive Since Shippingport first went into operation l
Waste Liquids in 1957, the total activity of liquid waste l discharged each year has decreased more or less continuously. For example, radioactivity i exclusive of tritium decreased from a high of l 0.53 Ci in 1965 to a low of less than 0.001 C1 in the years 1974, 1975, 1976, and 1977.
(t There was no radioactive liquid discharged in 1978, 1979, 1980, 1981, or 1982.
~
Discharging of radioactive liquid waste resumed in 1983 to support defueling operations and to prepare the Station for decommissioning.
During 1984, a total activity, exclusive of Tritium, of less than 0.000009 Ci was released.
The total Tritium released was approximately 0.120 Ci.
TABLE IV.A.4
- 2. Results: Beaver Valley Effluent Type Results for 1984 (a) Steam System The Steam System Blowdown was recycled or Blowdown directed to the Radwaste System where it was monitored and discharged in accordance with I
conditions noted in Section 3/4.11.1 of the Technical Specifications f (b) Radioactive Liquid effluents from the Beaver Valley Waste Liquids Power Station were released in accordance with conditions noted in the Section 3/4.11.1 of the Technical Specifications. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semiannual Effluent Reports for 1984.
w.
SECTION IV. DUQUESNE LIGHT COMPANY
( 1984 Annual Radiological Environmental Raport IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluente
- 1. Description of Airborne Effluent Sources
( a. Shippingport Atomic Power Station The potential scurce of airborne radioactivity l associated with the Shippingport station is the radioactivity contained in the reactor coolant and canal systems. These systems contain the activated corrosion and wear products, activated impurities in reactor coolant, and small quantities of fission products originating from naturally occurring uranium impurity. This material could become airborne from reactor coolant and cansl sampling operations, defueling operation, maintenance and overhaul operations, or working on contaminated components removed from these systems. Stringent radiological controls which have been developed during 27 years of operations at Shipping-port are exercised during these operations to prevent radioactivity from becoming airborne. Cobalt-60 is the nuclide of primary concern because of its long radioactive half-life and its concentration in reactor coolant. This radionuclide, present in the form of minute insoluble particles, could become airborne during operations on contaminated components removed from these systems.-
However, strict radiological surveillance is maintained throughout the plant, including continuous monitoring of airborne radioactivity in the operating spaces to ensure that concentrations are less than the uncontrolled area limits specified in DOE Order 5480.1. In addition, s air exhat.ated from potentially contaminated areas, such as decontamination and maintenance areas, is passed through high-efficiency particulate air filters. These filters
- f. are routinely serviced, changed, and tested in-place.
l t
I 1.
k' SECTION IV DUQUESNE LIGHT COMPANY
(~._ 1984 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS
{. .B. Monitoring of Airborne Effluents (continued) j
, 1. Description of Airborne Effluent Sources (continued)
The principle environmental release points for the Shippingport Atomic Power Station are the containment
( ventilation exhaust and the Radioactive Waste Processing System exhaust. These points were con-L '
tinously monitored, and analyses were performed on charcoal cartridges weekly for I-131 and monthly for I-133 and I-135 until September 6, 1984, when respon-sibility was turned over to the decommissioning agency.
Additionally, weekly continuous air samples are obtained
( on fixad filter papers which are analyzed weekly for ;
gross beta, and composited monthly to identify gamma i emitting isotopes. Composite of the particulate filters l
[ are also analyzed monthly for gross alpha meterminations
(- and quarterly for Sr-89 and Sr-90. A monthly gas sample is also obtained and ana'yzed for tritium for each release point.
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i b SECTION IV FIGURE 4.6 DUQUESNE LIGHT COMPANY -
1984 Annual Radiological Environmental Report SURCE TANKS RESLN STCAaGE TANKS -
FLASH TANE :
SPRAY RECYCLE TANK 2
[ GAS STRIPPER r T
VENT GAS CCMPRESSCRS ,
ir ,
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c GAS DECAT ORUMS 133 CU8tc FT EACM (sTF) i' ,, ,, ,,
' TEST TANKS -
O!LUTICN CHEMICAL WASTE TANKS 1 FANS Ion Exchangers
(
-s l l STACX GAS MCNITCRS i "
5 - TO STACx f Shippinr; ort Atssic Pever Statica Caseous L
Radioactive vaste Pr: cessing Syste=
f FIGURE 4.6
, l
L SECTION IV DUQUESNE LIGHT COMPANY
{ 1984 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS L B. Monitoring of Airborne Effluents (continued)
- 1. Description of Airborne Effluent Sources (continued)
- a. Shippingport Atomic Power Station (continued) f Reactor plant exhausts from the Decontamination Room, Sample Preparation Room, Radiochemistry Laboratory, Gaseous Waste System, Compacting
[ Station, and Decontamination Waste Drain Receiver
( Tank were continuously sampled with fixed filter i samplers. These samples were analyzed weekly for l gross beta, and composited monthly to identify h gamma emitting isotopes. These exhaust points were secured, therefore, these samples were discontinued by the Richland'Oper~tions a Office.
(.
( 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. Figura 4.6 shows a schematic diagram of the gaseous waste system in the radioactive waste disposal system at Shippingport.
- b. Beaver Valley Power Station (BVPS)
The Beaver Valley Power Station identifies isotopes according to the Environmental Technical.
f.' Specifications and Regulatory Guide 1.21. Prior to
$ waste gas decay tank batch releases and containment purge releases, an analysis of the principal garama emitters is performed. The principle gamma emitters include noble gases, lodines, and particulates. Figure 4.7 shows the gaseous radwaste system at Beaver Valley Power Station.
The environmental gaseous release points also require specific nuclide identification. These points include the Process Vent located on top of the Cooling Tower, the Ventilation Vent located on the top of the Auxiliary Building, and Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Containment.
These points are continuously monitored. Principal gamma emitters and tritium are 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.
SECTION IV FIGU'RE 4.7
/
DUQUESNE LIGHT COMPANY i
t 1984 Annual Radiological Environmental Report r !
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s c SECTION IV DUQUESNE LIGHT COMPANY b 1984 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued)
- 1. Description of Airborne Effluent Sources (continued)
- b. Beaver Valley Power Station (BVPS) (continued) I h Weekly continuous . samples are also obtained on filter paper to identify particulate gamma emitting isotopes. Composites of the particulate samples are analyzed monthly for gross alpha determinations
( and monthly for Sr-89 and Sr-90.
- 2. Airborne Effluent Treatment and Sampling
- a. Shippingport Atomic Power Station During defueling operations prior to the turnover of the plant to the decommissioning agency, gaseous wastes stripped from the reactor coolant at the Shippingport Station were circulated through a hydrogen analyzer and catalytic hydrogen burner system where the hydrogen was removed. The gases were initially stored in a vent gas surge drum, and subsequently compressed and transferred to one of four gas storage drums. The decayed gases were 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 were utilized in the event of high airborne activity to
{e automatically seal off the primary containment to prevent an inadvertent release of radioactivity.
( Reactor plant exhausts from the Decontamination
( Room, Sample Preparation Room, Radiochemistry Laboratory, Compacting Station, and Decontamination Waste Drain Receiver Tank are also equipped with nigh efficiency particulate al.r filters, and were f continuously monitored for radioactive particulates by the use of fixed filter monitors. Exhausts from ~
the Gaseous Waste System, which'was vented and ,
secured in January, 1984, we W filtered and aampled for radioactivity nt the release point also. Con-f t
tinuous' air monitors are located within the contain-
= ers, and other plant areas to constantly monitor the condition of the air. A stack release diagram is shown in Figure 4.8 identifying ventilation and gaseous release points for the Shippingport Atomic Power Station.
SECTION IV FIGURE 4.8 DUQUESNE LIGHT COMPANY 1984 Annus1 Radiological Environm:ntal Report L
SECION IV DISCHARGE POINTS - CASEOUS WASTES Ventilation Vent \
SLCRS Vent g
/
. /
/
.f_. C v f Containment Ventilation System (Containment Air Normally recirc.-not vented Auxiliary Buildin;;
Ventilation System Exl.auses Caseous wastes to Cooling Tower; Air Ejector CASEOUS RELEASE POINTS - BEAVER VALLEY PCWER STATICN Waste Disposal Building + Fuel Handling Building Serricu Bldg. E h usts (Filt ered)
/ -Concrete Enclosure
- I d Emerg. Filtration
/ / Exhaust t.-Caseous Wast e Ventilation Exhaust (Filt ered) ;
Release Air Ejector CASEOUS RELEASE ?OI'CS - SWI??TGPCRT ATCMIC ?CUER S*ATICN FIGURE 4.8
[ SECTION IV DUQUESNE LIGHT COMPANY
( 1984 Annual Radiclogical Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued)
- 2. Airborne Effluent Treatment and Sampling (continued)
- b. Beaver Valley Power Station f Radioactive gases enter the gaseous waste disposal system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor. Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A small amount of nitrogen and radioisotopes of xenon, krypton, cobalt, cesium, manganese, iodine, chromium and strontium are also present in the three continuous
. ventilation system pathways.
The overhead gas compressor directs the radioactive gas stream to a gas surge tank. The system is designed to return most of the gas to the volume control tank in the Chemical and Volume Control Sptem (CVC System). A quantity of gas is periodically discharged from the surge tank to one of the three (3) decay tanks for eventual release to the atmosphere via the process vent on top of the cooling tower. After the decay tanks are sampled and authorization obtained for discharge, the flow of the waste gases from the decay tanks (2 scfm) is recorded and rapidly diluted with about 1000 scfm of air in order to limit hydrogen concentration. The gases are then combined with nitrogen purge from the decay tank radiation monitor and oxygen analyzers, calibration gas from the oxygen. analyzers, the main condenser air l ejector exhaust, the containment vacuum nystem exhaust, aerated vents of the vent and drain system, discharge of the overhead gas compressor and the purge from the multi sample point radiation monitor. The mixture is then filtered through one of the gaseous waste disposal filters, each of which consists of a charcoal bed and a high efficiency filter. The filtered gases are then discharged by one of the gaseous waste disposal blowers to the atmosphere via the process vent on the top of the cooling tower. The radioactivity levels of the stream are monitored continuously.
Samples are also taken to determine the rate of activity released to the atmosphere.
(.
SECTION IV~ DUQUESNE LIGHT COMPANY
{ 1984 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS l B. Monitoring of Airborne Effluents (continued)
- 2. Airborne Effluent Treatment and Samoling (continued)
- b. Beaver Valley Power Station (continued) l Should the radioactivity release concentration of the stream go above the allowable setpoint, a signal from the radiation monitor will stop all flow from the decay tanks.
(
During a shutdown period after the containment has j been sampled and the activity levels determined, t the containment may be purged through the l Ventilation Vent located on top of the Auxiliary ;
Building or the Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the
{ Reactor Containment Building or the Process Vent located on top of the Cooling Tower.
(- Areas in the Auxiliary Building subject to radioactive contamination are monitored for radioactivity prior to entering the common ventilation vent. These individual radiation monitors aid in identifying any sources of contaminated air. The ventilation vent is also monitored continuously and sampled periodically.
Upon a high activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks in the supplementary leak collection and release system (SLCRS) and to the SLCRS Vent. Release points are shown in Figure 4.8 for the Beaver Valley Power Station.
SECTION IV' DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued)
- 2. Airborne Effluent Treatment and Sampling (continued)
- b. Beaver Valley Power Station (continued)
Each filter bank consists of roughing filters, charcoal filters, and pleated glass fiber type HEPA filters. The roughing filters remove large particulatrs to prevent excessive pressure drop buildup on the charcoal and HEPA filters. The charcoal filters are effective for radioactive iodine removal and the HEPA filters remove particulates and charcoal fines.
- 3. Analytical Procedures for Sampling Airborne Effluents
- c. Shippingport Atomic Power Station The following tabulates the gaseous sampling and analysis schedule prior to turnover to the decom-missioning agency:
Vent Gas Decay Tank Releases Sampling Type Of Detectable Sample Type Frequency Activity Analysis Concentration Gas From Prior to Gamma Ray Spectrum 3 x 104 uCi/cc Decay Tank Discharge of Gas Sample
- Gas from Prior to H-3 2 x 104 Ci/cc Decay Tank Discharge Gas from Prior to C-14 1 x 104 uCi/cc Decay Tank Discharge
- A gas sample of measured volume is counted in a multi-channel analyzer for 10 minutes for gross activity. The counter has a minimum detectable activity (MDA) of 3 x 10*7 uCi/cc for the predominant nuclide of Xe-133.
SECTION IV DUQUESNE LIGHT COMPANY 1984 Annual R:diological Environmental Report IV. MONITORINC EFFLUENTS
- 3. Analvtical Procedures for Samelina Airborne Effluents (continued)
Air Exhausts Sampling Type Of Sample Tvne Frequenev Activity Analvsis Dectactable 1.inits (1) Air from the Plant ventilation continuous Cross Casuna 1.2 x ION uCi/cc (Gas.
Exhaust Effluent Stream Channel 8 ORMS)*
~
5 x 10 UC1/cc (Particulate; Channel 12 f~
' ORMS)*
Continuous Gross Beta 1 x 10~ ' pC1/cc (2) Particulate Filter in Plant Weekly Sample (! articulate)
[ Ventilation Effluent Stream
( and Caseous Waste System Exhaust .g3 Particulate Filter in Plant Continuous Principle Gamma 1 x 10 uCi/cc ventilation Effluent Stream Monthly Composite Particulate and Gaseous Wasta System Exhaust (Weekly if Gross Beta 1 1 x 10~13)
Particulate Filter in Plant Continuous Gross Alpha 2 x 10-15 uci/cc Ventilation Effluent Stream Monthly Particulate and Gaseous Waste Systen Exhaust -14 Particulate Filter in Plant Continuous $r-89, Sr-90 5 x 10 uCi/al (Sr-89)
Ventilation Effluent Stream Quarterly 1 x 10# uCi/ml (Sr-90) and Caseous Weste Systen Exhaust Particulate 3
(3) Charcoal Cartridge in Plant Continuous I-131 1 x 10 uCi/a1 Ventilation Effluent Stream Weekly and Gaseous vaste System Exhaust 1 x 10'g3 uC1/al (I-133)
Charcoal Cartridge in Plant Monthly I-133, 1-135
. Ventilation Effluent Stream Monthly -2
[ 1 x 10 uci/a1 (I-135) and Gaseous Waste Systes Exhaust
}
(4)~ Evacuated Bomb bample In Monthly B 2 x 10 uC1/a1 Plant Ventilation Effluent Stream and Gaseous Weste System Exhaust ,gg Continuous Cross Beta 1 x 10 uCi/cc (5) Particulate Filter in Reactor Weekly Particulate Plant Exhaust from Decontami-nation Room, Sample Preparation Room, Radiochemistry I.aboratory, f.
t Compacting Station, and Decon-tamination Waste Drain Receiver Tank.
Particulate filter in Reactor Continuous Principal Gasma 1 x 10~I3 uC1/cc Plant Exhaust from Decontani- Monthly Composite Particulate nation Room. Sample Preparation (Weekly if Cross ~
Room, Radiochemistry 1.aboratory. Beta 1 1 x 10 13)
Compacting Station, and Decon-
..canination Waste Drain Receiver Tank.
ORMS - Operational Radiation Monitoring System
- Although the ORMS Channels have no specific function as far as affluent acnitoring and reporting is concerned, these two (2) channels are being listed for information purposes. It is also noted 4
' that these channels provide alara functions in the Main Control Room when levels of 1.2 x 10 Wi/cc are reached on Channel 8, or 1 x 10-9 uci/cc on Channel 12. Additionally, they shut the ventila; ion syste:n butterfly valves when levels of 1.2 x 10** uC1/cc are reached on Channel 8 or 1 x 10~' Wisce an Channel 11.
L SECTION IV DUQUESWE LIGHT COMPANY
[ 1984 Annual Radiological Environmental Report
( IV. MONITORING EFFLUENTS
- 3. Analytical Procedures for Sampling Airborne Effluents (continued)
- b. Beaver Valley Power Station The following tabulates the gaseous sampling and analysis schedule:
Mieluun I m r Limit of Sampling Analyste Type of Detecties (LLD)
Caseous Release Type Fregisency Frequency Activity Amelyste (,eC1/el)"
A. Weste Ces Storage F F l Tank Each Tank Crab Es:h Tank Francipal Comes Entttere8 1 a 10' Semele H-3_
1 a 10 -4
- 8. Containeemt Purge Each Purge Each Purge Principal Cemen Emittere8 1 u 10 ~4 Crab Sample -6 N-3 1 a 10 I C. Vens tletion Systems ~4 M **I* H Principal Jones telttera s 1 a 10
- 1. Process Vent 3,'*p m le n-3 1 x 10'
- 2. Containment Vent
- 3. Aus. Olds. Vant Continuoese I
W I-13e -12 1 s 10 Charcoat
~
88*FI* t-133 I a 10 -10 Beteeee from Radiu- Coetineene W Principal Comme Beittere 8 todine and Particulates Petticulate (I-131. Othere) 1 x 10 (Airborne) may be Sam p le
- EI*" "*
eti . Fe huay only* Composite Particulate Sample Continuove Q Sr-89. Sr-90 1 a 10'II Composite Perticulete Sama t e Continuove' Pbble Gee Nobie Ceoas 1 a 10' Hmii tor Crowe 24ta and Comme
SECTION IV DUQUESSE LIGHT COMPANY 1984 Annual Radiological Environmental Report IV. MONITORING EFFLUENTS
( B. Monitoring of Airborne Effluents (continued)
- 3. Analytical Procedures for Sampling Airborne Effluents
[ (continued)
TABLE NOTATION
- a. The Lower Limit of Detection (LLD).
- b. When reactor coolant system activity exceeds the
{- limits stated in the BVPS Technical Specification, I
analyses shall be performed once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during startup, shutdown and 25% load changes and l f 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving the maximum steady state power operation unless continuous monitoring is provided.
- c. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
f d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
~
Sampling and analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, during startup, shutdown and 25% load changes and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving
[ the maximum steady state power operation when RCS t activity exceeds the limits stated in the Technical Specification unless continuous monitoring is provided. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased
{ by a factor of 10.
[ e. Tritium grab samples shall be taken at least once i per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool
- f. The average ratio of the sample flow rate to the sampled stream flow rate shall be known for Ae j time period covered by each dose or dose rate i calculation made in accordance with the BVPS Technical Specification.
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SECTf0N IV DUQUESNE LIGHT COMPANY
[4 1984 Annual Radiological Erjvironmental Report -
IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued)
- 3. Analytical Procedures for Sampling Airborne Effluents
( (continued)
- g. The principal gamma emitters for which the LLD
{ specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134,
[l Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only thsse nuclides are to be detected and reported. Other
[ peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below
(- the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.
When unusual circumstances result in LLD's higher
[ than required, the reasons shall be documented in L' the semi-annual effluent report.
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SECTZON IV DUQUESNE LIGHT COMPANY
{ .
1984 Annual Radiological Environmental Report IV. HONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued)
- 4. Results
{
- a. Shippingport Atomic Power Station Analyses for the particulate airborne radioactivity
~
in the plant effluents indicated that the gross alpha and beta activity concentrations were at or
{ very near the Lower Limit of Detection' (LLD).
Analytical results of charcoal filter samples showed that there were no instances of radioiodine concentrations above LLD.
Specific gamma analyses of weekly and monthly composite air filter samples were also performed.
(' Results showed naturally occurring radioactivity typical of " background air" and nuclides attributable to worldwide falleut from nuclear weapons testing.
During 1984, there were eight (8) instances where Cobalt-60 activity attributable to plant operations was measured. The total amount of Cobalt-60 activity released was 0.00000005966 Ci with concentrations ranging from 1.54 x 10' " pCi/cc to 6.80 x 10"" pCi/cc. These concentrations are all well below Federal limits.
Radiostrontium analyses of quarterly composite air h filter samples showed Sr-89 and Sr-90 concentrations in air which were at or near the minimum detectable concentrations of 5 x 10-1"
[ pCi/ml, and 1 x 10-1" pCi/ml, respectively. The I- levels of Sr-89 and Sr-90 observed were extremely low and are typical of " background air" radiostrontium levels. Also, Carbon-14 activities
- f. in gaseous effluent releases were estimated based on analysis of canal water and analysis of the water processed through the IHIN Film Evaporator, which is vented to the Radioactive waste exhaust stack. Tritium activities in gaseous effluents were estimated based on canal water tritium levels.
These activity levels were consistent with past reported levels considering plant operations during 1984.
c r..' SECTION IV DUQUESNE LIGHT COMPANY L 1984 Annual Radiological Environmental Report-
. IV. MONITORING EFFLUENTS B. Monitoring of Airborne Effluents (continued)
- 4. Results (continued)
- a. Shippingport Atomic Power Station (continued)
( - -.
There was one release of gaseous radioactivity from the Shippingport Atomic Power Station during 1984.
In support of defueling operatione at the Shippingport Atomic Power Station, the Radioactive
( Waste Processing Vent Gas System was deactivated whereby the contents of the system were released to the atmosphere.
('c_ __
Samples taken prior to the release revealed only a small concentration of Carbon-14 in the Vent Gas System. Approximately 0.0065 curies of Carbon-14
[. activity was released to the environment in association with this release. Because of the extent of radioactive decay, no gamma-emitting
(. <
fission gas activity (i.e. Xenon-133) was released.
The total amount of radioactivity released to the atmosphere from the Shippingport Atomic Power l'- Station during 1984 was extremely small and had a negligible effect on the environment as shown in
.Section V.S.6.
- b. Beaver Valley Power Station Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in Section 3/4.11.2 of the Technical '
Specifications. No limits were exceeded. These l-. values have been reported in the Beaver Valley Power Station Semi-Annual Effluent Reports for 1984.
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( SECTION IV DUQUESNE LIGliT COMPANY
( 1984 Annual Radiological Environmental Report
.W. MONITORING EFFLUENTS C. Solid Waste Disposal at the Shippingport and Beaver Valley Power Stations
( During the Shippingport Atomic Power Station defueling efforts and Beaver Valley Power Statioa normal operations and periodic maintenance, small quantities of solid radioactive
[. - waste materials were generated such as evaporator concentrates, contaminated rags, paper, plastics, filters, spent ion-exchange resins, and miscellaneous tools and equipment. These were disposed of as solid radioactive
[' waste.
At Shippingport Atomic Power Station and the Beaver Valley
- l. Power Station, the compactable wastes were segregated and compressed in a 55-gallon drum to minimize disposal volumes.
The compressed waste, plus .other drums of noncompactable waste, were then shipped offsite for disposal at a site owned
{--
by the Department of Energy or a commercial radioactive material burial site licensed by the Nuclear Regulatory
[ Commission (NRC) or a state under agreement with the NRC. No
( radioactive waste material was buried at the Shippingport or Beaver Valley Power Station site.
All containers used for packaging, transport, and disposal of radioactive materials met the requirements of the United States Department of Transportation and the Nuclear
( Regulatory Commission. Shipments offsite were made in
[ accordance with Department of Transportatita regulations. -
Figure 4.9 depicts solid waste handling at the uite.
In 1984, the Shippingport plant disposed of a total of f- 9,094.3 cubic feet of radioactive solid waste having a total radioactivity of about 10.670 curies. This included twenty-
[ six (26) shipments of low level wastes. In addition, the t irradiated PWR Core 2 Lower Core barrel estimated to contain 2.048 X 10" curies of radioactivity was shipped offsite for disposal at a site owned by Department of Energy.
At Beaver Valley Power Station approximately 5,493.5 cubic feet of radioactive solid waste was shipped offsite in 1984.
[ This is the actual burial volume. The twenty-two (22) l shipments contained a total activity of 710.8 curies.
Industrial solid wastes from both plants were collected in portable bins, and removed to an approved offsite burial f ground. No burning or burial of wastes was conducted at either the Beaver Valley or Shippingport plant.
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L SECTION IV FIGURE 4.9
[
DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report I
SECTION IV SOLID WASTE DISPOSAL DIACRAM FIGURE 4.9 NADIDACTIVE SOf.U) WASTE DISPOSA L Misc. Radioactive g Compactor and
[- Solid Wastes Drurming Station i
".-- D h
[
Radioactive Waste Sludge Solidify-
'on cobM Msrosal Evner, tor ino Station
}
g I'
Spent Radioactive o Resin
- Special Shipping Casks & Containers u
I~-Q .
(
I 00' -Mo o- g INDUSTRIAL SOLID WASTE DISPOSAL DIACLLM i
Water Filtered; _
Filters drummed---- _
- y -f O
[
Sludge From Vater - '
[ f 1
Treat:nent Plant and _ ,
} ,
Sevage Treat::ent g gi ]
Flanc (37PS) g w
Trash Basket - Beaver Valley C Debris and Trash Hopper t Screenhouse shippingport From Screenhcuse 3
y
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m g us
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Trash & Garbage Storage Sin d g E o
- 31 cure ,. 9 oo mi o -
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SECTION V - A DUQUESNE LIGHT COMPANY
{- 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING A. Environmental Radioactivity Monitoring Program
(- 1. Program Description The' program consists of monitoring water, air, soil,
[ river bottoms, vegetation and foodcrops, cow's milk, L ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table V.A.1. Further description of each portion of the program (Sampling
(- Methods of Sample Analysis, Discussion and Results) are included in parts V-B through V-I of this report.
V-B - Air Monitoring V-C - Sediments and Soils Monitoring V-D - Vegetation and Foodcrops V-E - Cow's Milk V-F - Environmental Radiation Monitoring V-G - Fish
( V-H - Surface, Drinking and Well Waters V-I - Estimates of Radiation Dose to Man
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TABLE V.A.1 N.
CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM d
.2 DLC
- Sample Sample Analysis Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Frequency -, Analysis IbI *
- 1. Air Particulate 13. 11 1.6 Meyer's Farm Continuous Sampling Weekly Composite.IdI Gross Beta, IC} I-131 and Radiolodine 30 4 0.6 Shippingport, PA. (S.S.) with sample collec .
46.1 3 2.4 Industry, PA (Tire Co.) tion at least - MonthlyCompositejdI Gamma -scan .
weekly 32 15 0.8 Midland, PA (S.S.)
48(a) 10 16.5 Weirton, WV (a) Quarterly composite Idl I 51 5 8.0 Aliquippa, PA (S.S.) Sr-89.90 47 14 4.8 East Liverpool, OH 27 7 6.2 Brunton's Fara 'G 28 1 8.7 Sherman's Farm 2 298 3 8.1 Beaver County Hospital p {
- 2. Direct 30 4 0.6 Shippingport, PA (S.S.) Continuous Quarterly I y
Radiation 13 11 1.6 Meyer's Fara . (TLD) Annually Gesuna-Dose g' 8 46 3 2.5 Industry,PA(Church) &'8 32 15 0.8 Midland, PA (S.S.) o C 8
48 (a) 10 16.5 Weirton, WV (a) 3E-u 45.1 6 2.0 Raccoon Twp, PA Kennedy's Crnrs. g r-51 5 8.0 Aliquippa, PA (S.S.) i E
'I 47 14 4.8 East Liverpool, OH m 4 70 1 3.0 West. 8vr. School 3 n 80 9 8.4 Raccoon Park ; $
l 81 9 3.9 Southside School 2 >
82 9 7.1 Hanover Municipal Bldg. 3 5 83 10 4.5' Mill Creek Rd j',
14 11 2. 6 . Hookstown i 84 11 8.5 Hancock Co. Children Home ,
85 12 5.8 Rts. 8 8 30 Intersection 3 86 13 6.5 E. Liverpool Cahills House Q 92 12 3.0 Georgetown Rd.
- 87 14 7.0 Calcutta Road 88 15 3.1 Midland Heights 89 15 4.7 Ohioville 90 16 5.2 Fairview School 10 4 0.8 Shippingport Soro, PA 45 5 2.2 Mt. Pleasant Church 60 13 3.7 Haney's Fara 93 16 1.3 Sunset Hills, Midland 95 13 2.4 McCleary Rd, Hollte Williams y
M m
S.S. - Substation *
- .. - m .~_ m. .v __r .
r~m .
r- m r- r-x gm m r T BLE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. y, (Continued) E DLC d
Sample :8 Sample Analysis Type of Sample Points Analysis IbI Sector Miles Sample Point Description Sample Frequency ' Preparation Frequency
- 2. Direct 28 8.7 k 1 Sherman's Farm Continuous Quarterlyfgf Gamma-Dose Radiation 71 2 5.6 Brighton Twp. School (TLD) Annually (Continued) 72 3 3.2 Logan School 298 3 8.1 Beaver County Hospital 13 4 2.2 Potter Twp. School 74 4 6.8 Conn. Col-Center Twp.
75 5 4.3 Holt Road 76 6 3.8 Raccoon Twp. School 77 6 5.8 Green Garden Rd (Wayne's) g
$9 7 1.1 frons a 78 7 2.3 Raccoon Mun. Bldg.
- 27 7 6.2 Brunton's Farm 3" 79 8 4.6 Rt. 18 & Rt. 151 E 15 14 3.3 Georgetown S 46.1 3 2.1 Industry PA Tire Co.
91 2 3.7 Pine Grove Rd and Doyle Rd 1g x,
, 94 8 2.4 McCleary Rd, Wilson {gg w _ . _ . _
m ,g E.
- 3. Surface 49.1 4 5.0 Arco Polymers (a) Intermittent Monthly Composite of r-I Water 2.1 14 1.3 Gross Beta O g Downstream (Midland) Crucible Composite Samples (j) Weekly Sample (d) Gross Alpha ~
Collected Weekly Gamma-scan T n 3 13 0.2 Shippingport Atomic Power,
~
Weekly Grab Quarterly Composite Co-60. H-3 i g Station Discharge Samples Only Sr-89. Sr-90 49 (a) 3 3.2 Montgomery Dam 3 3 (Upstream) j g 3
2A 13 0.2 Downstream BVPS Outfall C 5 14 4.8 East Liverpool traw water) Daily Grab Sample ~
Only - Collected Weekly (J) F 8
- 4. Groundwater 13 11 1.6 Meyer's Fars 1
14 11 2.6 Hookstown, PA 15 15 3.3 Georgetown, PA 11 3 0.8 Shippingport Boro Quarterly Quarterly Gamma-scan, Gross Beta, Gross Alpha.
- 5. Drinking 4 14 1.3 Midland, PA (Midland Water Intermittent I*I Weekly Composite of ' Gamma-scan, 1-131 3 Treatment Plant) Sample Collected Daily Sample (d) F; Weekly Monthly Composite (d) Gross Alpha, Gross Beta .,
5 14 4.8 East Liberpool, OH (East Quarterly Composite (d) H-3.Co-f>0, Sr-89, 90 Liverpool Water Treatment i Plant)
m - _m - - m _m m- U TABLE V.A.I y CON 3OLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
( Contitued )
'y Dtc
- Sample Sample Analysis
- Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Frequency Analysis g)
- 6. Shoreline 2A 13 0.2 Downstream BVPS Outfall Semiannual Semiannual Gamma-scan. Gross Beta Sediment Gross Alpha 3 13 0.2 Vicinity SAPS Discharge Uranium Isotopic 49 3 3.2 Upstream Side of Montgomery Sr-89. 90 Dam (a) 50 13 8.2 Upstream side of New Cumberland .
Dam 7 Milk 25 10 2.1 Searight's Dairy Weekly Weekly sample from I-131 -
Searight's only 8 61* 12 3.2 Allison Biweekly (g) Biweekly (grazing) Gamma-scan
- 69* 7 3.6 Collins When animals are Monthly (Indoors) Sr-89. 90 y 96(a) 10 10.3 Windsheimer on pasture; I-131. Cs-137 98* Foxall E 5 2.9 monthly at other
100* 14 2.8 Dcughty times.
62* 12 3.3 Lyon y8 ,
99* 6 4.1 L ampich at S 27 7 6.2 Brunton's Dairy (h) Monthly Monthly ?O 29 3 8.3 Nicol's Dairy (h). Gamma-scan Sr-89. 90 gM 8
8.
1-131. Cs-137 gg e,
Iish 2A 13 0.2 Vicinity of BVPS #1 Sealannual Composite of edible on
" Station Discharge and parts by species (1)
Gamma-scan on edible portions
[oh
= n Shippingport Dis. Sta. -
49(a) 4.7 Upstream Side of j $>
4 3
Montgomery Dam 35 s
- 9. food Crops (Shipp.) 10 4 0.8 (Three locations within Annual at e, (Georg.) 15 Composite of each Gamma-scan -
14 3.3 5 miles Selected by harvest if sample species (indus.) 46 3 2.5 Company) 1-131 on green y available leafy vegetables 48(a) 10 16.5 Weirton. WV 3
- 10. Feedstuff and 25 10 2.1 Searight's Dairy Fara Monthly Summer forage Monthly Gamma-scan Quarterly Quarterly Composite S r-90
- 11. Soil 13 11 1.6 Meyer's Farm Every 3 years 30 12 Core Samples Gamma-scan 4 0.6 Shippingport. Pa. (1982.1985, etc. ) 3" Deep (3" Dia.
46 3 2.6 Industry. Pa. Sr-90 32 15 0.8 at each location Gross Beta (North of Site) Midland (approx. 10' Gross Alpha 48(a) 10 16.5 Weirton, W. Va.
51 5 8.0 Aliquippa. Pa. radius) Uranium isotopic 47 14 4.8 E. Liverpool. Oh.
27 7 6.2 Brunton's Dairy 22 8 0.3 South of BVPS Site W 294 3 8.3 Nichol's Dairy E f our (4) dairies are required by the BVPS ?
lechnical Specification lable 3.12-1. In addition to one local large dairy (Searight's dairy).
three (3) datries are selected on basis of highest potential thyroid dose using allch census data. $
SECTION V - A DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report TABLE V.A.1
(. CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)
Notes:
( (a) Control sample station: These are locations which are presumed to be outside the influence of plant effluents.
( (b) Typical LLD's for Gamma Spectrometry are shown in Table V.A.4.
(c) Particulate samples are not counted for 2: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ,
filter change. Perform gamma isotopic analysis on each l sample when gross beta is > 10 times the yearly mean of !
control samples.
h (d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each location.
(e) Composite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(f) Weekly milk sample from Searight's Dairy is analyzed for I-131 only.
(g) Mil: samples are collected oi-weekly when animals are in pastare and monthly at other times. [ Assume April - October for grazing season (pasture).]
(h) The milk samples from Brunton's and Nicol's are collected once per month.
(i) The fish samples will contain whatever species are available.
If the available sample size permits, then the sample will be separated according to species and compositing will provide one sample of each species. If the available size is too small to make separation by species practical, then edible parts of all fish in the sample will be mixed to give one sample.
(j) Ccmposite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at locations 49.1 and 2.1. Weekly grab samples are obtained at location 3, 49 and 2A. A weekly grab sample is also obtained from daily composited grab samples obtained by the water treatment plant operator at location 5.
(k) Two (2) TLD's are collected quarterly and annually from each monitoring location.
L
( SECTZON V - A DUQUESNE LIGHT C0t!PANY 1984 Annual Radiological Environmental Report TABLE V.A.1
[ CONSOLIDATED RADIOLOGICAL ENVIRON!! ENTAL !!0NITORING PROGRAh!
(Continued)
[
Additional Notes:
Sample points correspond to site numbers shown on maps.
All Iodine I-131 analyses are performed within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of
[ sample collection if possible.
All Air sampics are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for Gross Beta.
{
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r- r- _r ..m r-m .rm ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY Name of Facility Duquesne Light Company , m Docket No. 50-334 , y, H Location of Facility Beaver, Pennsylvanta Reporting Period Annual 1984 (County,5 tate) y#
g Analysis and Lower Limit <
Meditan or Pathway Number of Total Number of All Indicator locations Location with Highest Quar. Mean Control Locations Monroutine I Senpled of Analysis Detect ion ** Mean (f) Name Junit o @ asurement) Performed (LLD) ** Range amean (f)
- mean (f) Reported p. l Distance and Directions ** Range * *R ange Measurements *** '
Celrton,WV - -
No. 48 Air Particulate . Gross (520) 2.5 18(520/520) Allquippa, PA No. 51 20(52/52) 18(52/52) O 5
co and R diolodine Beta (5.5-58) *
(Xtr9pC1/Cu. M.) (7.5-58) (8.0-36)
Sr-89 (40) 2 LLD -- -- -- -
g y
0.1 e Sr-90 (40) LLD -- -- -- -
% cs I-131 (520) 10 LLD -- -- -- -
U
- p. c:
Sb-125(520) 30 LLD -- -- -- -
oN rZ om a Ganna (120)
Be-1 20 $ t-*
o 112(120/120)
(63-169)
Midland, PA No. 32 126(12/12)
(89-161) 115(12/12) 0 (' y (63-152) e :z:
' H K-40 10 34(20/120)
(8.5-111)
Sherman Dairy No. 28 68(2/12)
(26-111) 28(4/12)
(13-49)
O Eo
$0 nk Cs-137 1 2.l(3/120) Brunton Dairy No. 27 2.5(1/12) LLD -
0 0 (1.2-2.5) @P:M to $
Ra-226 10 49(1/170) E. Liverpool, OH 49(1/12) LLD 0 $
No. 47 --
Th-228 3.3(3/120) Beaver Co. Hospital 1
(1.6-4.3) No. 298 4.3(1/12)
LLD 0 g
, .o o
Others Table V.A. 4 LLD -- -- -- -
S H
b t<
- . . . _ M H uninal Lower Limit of Detection (LLD) ^ .-
p
- flean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) .
lionroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Statton Technical Specifications N (Appendix B) -
-. - .~ ~ . .w m . m. .e _ r-m .?~ .r rm r; 3 ENVIRONMLNTAL RADIOLOGICAL MONITORING PROGRAM SUfetARY -
Name of Facility Duquesne Light Company Docket No. 50-334 O Location of Facility Beaver, Pennsylvania Reporting Period Annual 1984 4 (County,5t at e) I Analysis and Lower Limit Number of Medium or Pathway Total Munber of . All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine Sampled of Analysis Detectton ** Mean (f) Name **Mean (f) **Mean If) Reported (Unit of Measurement) Performed (LLD) * *R ange Distance and Directions ** Range * *R ange Measurement s**
- G Montgomery Dam Cn No. 49 #
Sediment Gross (10) 0.3 11(10/10) 8VPS Outf all Area No. 02 15(2/2) 13(2/2) 0 g l (pCl/g) Alpha (5.6 23) River Mlle -- 35.0 (7.6-23) (10-16) p (dry weight) <
c Gross (10) 1.0 35(10/10) 8VPS Outfall Area No. 02 40(2/2) 35(2/2 0 $
Beta (23-42) River Mlle --35.0 (39-42) (32-38 Sr-89(10) 0.2 LLD -- -- -- -
$E Sr-90(10) 0.04 0.048(6/10) Montgomery Dam No. 49 0.070(1/2) Same as O oS rM
, (0.019-0.089) River Mlle -- 31.0 --
High Location j jj rM
$ Gansna (10) @g
' wH Be-7 0.2 1.2(7/10)
(0.54-2.0)
BVPS Outf all Area No. 02 2.0(1/2)
River Mlle -- 35.0 0.58(1/2) 0 mQ ga K-40 0.5 15(10/10) SAPS Ds. Vc. SW No. 03A 18(1/1) 12(2/2 0 $O (8.6-18) River Mlle -- 34.8 --
(12-13) ) @[$
0 Co-58 0.03 0.16(1/10) SAPS Discharge No. 03 0.16(1/2) LLD 0 @ s River Mlle -- 34.8 -- --
g Co-60 0.03 "
0.44(6/10) SAPS Ds. Vc. SW No. 03A 0.7)(1/1) LLD 0 (0.17-0.71) River Mile -- 34.8 -- --
7
'o Cs-134 0.02 0.13(4/10) SAPS Ds. Vc. SW No. 038 0.16(1/1) LLD 0 River Mlle -- 34.8 @
(0.078-0.16) -- --
rt Cs-137 0.02 0.42(10/10) SAPS Ds. Vc. SW No. 03A 0.62(1/1) 0.27(2/2) 0 (0.17-0.62) River Mlle -- 34.8 --
(0.25-0.29) g Ra-226 0.1 2.8(10/10) SAPS Ds. Vc. SW No. 03A 4.4(1/1) 2.l(2/2) 0 b (1.7-4.4) niver Mlle --34.8 --
(1.9-2.3) O Th-228 0.02 1.5(10/10) SAPS Ds. Vc. SW No. 03A 2.0(1/1) 1.2(2/2) 0 $
(1.0-2.0) River Mlle -- 34.8 --
(1.2-1.3) >'
PJ
- - .- -m .- - .m m m r-- m ,
ENVIRONMENIAL RADIOLOGICAL MONITORING PROGRAM SUP9tARY Nme of Facility Duquesne Light Company Docket No. 50-334 m m
Location of Facility Beaver, Pennsylvania Reporting Period Annual 1984 h (County,5t ate) o Analysis and Lower Limit Z Medium or Pathway Number of Total Number of All Indicator t,ocations Location with Highest Quar. Mean Control Locations Monroutine 4 S upled of Analysis Detect ion junitofMeasurement) Performed '5 % an (f) Mme **Mean (f) 7Maan (f) Reported 8 (LLD)' ** Range Distance and Directions ** Range ** Range Measurements *** >
Montgomery Das
~' No. 49 Sediment Others Table V.A. 4 LLO fpCl/g) -
idry weight) U-233 (10) 0.01 SAPS Ds. Vs. SW Mo. 3A oo Icnntinued) and 0.65(10/10) 0.91(1/1) 0.38(2/2) 0 (0.29-0.91) River Mile -- 34.8 --
(0.32-0.43)
U-234 g y
U-235(10) 0.01 c 0.022(8/10) SA*S Discharge No. 03 0.031(1/2) 0.011(1/1) 0 (0.011-0.031) River Mlle -- 34.8 -- -- $ cs to c U-238(10) 0.01 0.47(10/10) SA85 Ds. Vs. SW No. 3A 0.64(1/1) 0.26(2/2) 0 $.S (0.24-0.64) River Mlle -- 34.8 --
(0.24-0.27) gy
. .~2 Om 8 oQ l ^
D
~
NC p o
-g Wa
<o Nk i.!i O
rt 5 8' g
!?
?c1 rt H
__ b a
g flominal Lower Limit of Detection (LLD)
Hean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) 4 flonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Dower Station Technical Specifications (Appendix 8) ?
N e
- - - - - n n m ,- ,- w --
i
. 1 ENVIR0lMENfAL RADIOLOGICAL MONITORING PROGRAM SLMMRY
]
Name of Facility Duquesne Light Company Docket No. 50 ',34 m m
Location of Facility Beaver, Pennsylvania Reporting Period Annual 1984 -4 l
(County,St ate)
=ll s
Analysis and Lower Limit Number of Medluni or Pathway Total Number of All Indicator Locations y Location with Highest Quar. Mean Control Locations Monroutine Sampled of Analysis Detcrtion ** Mean (f) Name **Mean (f)
(Unit of Heasurement) Performed (LLD) * *R ange Distance and Directions ** Range
- Mean (f)
- Range Repos teil Measurements ***
co
, Weirton WV External Radiation Gamma 0.05 Calcutta No. 85 (mR/diy) (170 quarterly) 0.17(170/170') 0.19(4/4) b. (4/4) 0 (0.11-0.21) 7.0 miles - W (0.18-0.20) (0.17-0.18) c
.-s l Gannia 0.05 0.16(43/43) Calcutta, No. 87 0.1';(1/1) 0.17(1/1) 0 l
, (43 annual) (0.13-0.19) 7.0 miles - W -- --
g Feed and forage M::
(pC1/q)
Sr-90 (4) 0.003 0.12(4/4)
(0.026-0.18)
Searight Dairy No. 25 --
2.4 miles - SW One sample O ES
, (dry weiglit) locatfon SQ
-2 cn y Gamma (12)
Be-7 0.3 1.9(6/12) -- -- --
0 gm w r-(0.59-4.1) mE ax K-40 0.5 16(12/12) -- -- --
0 <H (7.1-25) sn oo Es-131 0.02 0.04(1/12) -- -- --
0 3%
gg Ra-226 c+ -<
0.03 0.80(2/12) -- -- --
0 m, (0.54-1.1) -- -- -- -
- =
Th-228 0.03 0.18(1/12) -- -- --
0 -@
-- -- -- .- - o Others Table V.A.4 LLD -- -- -- -
thainal Lower Limit of Detection (LLD) y llean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) >
- Honroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the 8eaver Valley Power Station Technical Specifications "
(Argendix 8) :-
I m
?
- -. - .m_ m e,m m , _ _ r- e ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRMI SUMARY Mane of f acility Duquesne Light Company Docket No. 50-334 g Location of f acility Beaver, Pennsylvania n Reporting Period Annual 1984 H (County,5t ate) $
2:
Analysis and Lower Limit Number of 8 Medium or Pathway Total Nuder of All Indicator locations Location with Highest Quar. Mean Control Locations Nonroutine >
Sampled of Analysis Detection ** Mean (f) Name **Mean (f) **Mean (f) Reported (Unit p W asurement) Performed (LLD) * *R ange Distance and Directions ** Range * *R ange Measurements ***
Montgomery e Dam No. 49 $
Fish (pCl/g)
Gansna(8) k K-40 0.5 3.0(8/8) BVPS Outful Area 3.l(4/4) 2.8((4/4) 0 $
(wet weight) (2.2-3.1) No. 02 (2.6-3.7) (2.2-3.3) m ts Cs-131 0.02 0.028(2/8) 8vPS Outfl Area 0.028(2/4) LLD 0 gc (0.008-0.048) No. 02 (0.008-0.048) d H. M Others Table V.A.4 LI D -- -- -- - 0 y OM M
m oH
& Weirton, WV No. 48 8 t
Q H
Food and Gar den Crops (pCl/g) 1-131 (8) 0.006 LLD -- -- -- -
pn
<: o (wet w ight) p %,
l Gansna (8) 0.04 op l Be-7 0.39(3/8) Georgetown PA No. 15 0.55(1/2) 0.20(1/3) 0 gd l (0.20-0.55) -- -- -
m o
K-40 0.5 4.0(8/8) Industry, PA No. 46 6.5(2/2) 3.4(3/3) 0 E
! (1.8-11.1) 2.0 miles - NNE (1.9-11.1) (2.3-4.1) H I
-- No. 10 --
o
'1 l l Th-228 0.01 0.016(1/8) Weirton, WV No. 48 0.016(1/3) Same as 0 "
l -- -- High Location i H i Others Table V. A.4 LLD -- -- -- - >
$M j _ _ .-
I l Hmalnal Lower Limit of Detection (LLD) l 11ean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) f i
- Nonroutine reported measurements are def fned in Regulatory Guide 4.3 (December 1975) and the Beaver Valley Power Stattor. Technical Specifications to (Appendix B) l l
-. - - m - _m m ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY Name of Fact 11ty Duquesne Light Company Docket No. 50-334 Location of Facility Beaver, Pennsylvania Reporting Period Annual 1984 $
o (County,5t ate)
.H
'A
' Analysis and Lower Limit <:
Mellum or Pathway Total Number of Number of All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine ,
Sampled of Analysis Detection ** Mean.lf) pinlD I Measurement) Performed (LLD) **R ange Name .
- Mean(f) **Mean (T) Reported >
Distance and Directions ** Range **R ange Measurement s**
- Mlik Brunton Dairy No. 27 y
l-131 (152) 0.2 LLD co (ra/f) -. -- -- -- **
Sr-89 (120) 2 LLD -- -- -- --
Sr-90(120) 1 3.6(120/120) Doughty No. 100 c.
i 8.3(3/3) 2.0(12/12) 0 (0.89-11) (6.5-11) (0.98-2.1) % es P2 c Gamma (120)
K-40 1460(120/120) Lampich flo. 99 $$
(1090-1970) 1750(11/11)
(1510-1920) 1420(12/12)
(1320-1580) o yy r-e o gr}
' Cs-137 7.0(11/120) Doughty No. 100
! 9.5(1/3) LLD 9 % t-*
(4.0-12)
Others gg Table V.A.4 LLD -- -- --
~x H.
ko I 4 is l$
a
\ E i n H
b 5;
- i Nominal Lower Limit of Detection (LLD)
- I
- " Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) N Nonroutine (Appendixreported B) measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Simcifications 4
O 9 s
- - - - -- -m - - ~ _m_ m _m r- ry
' ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Sup9tARY Name of Facility Duquesne Light Company Docket No. 50-334 un Location of f acility Beaver Penns.ylvania Reporting Period Annual 1984 $
flounty,5(ate) e Analysis and Lower Limit <:
Number of Medluis or Pathway Total Nunter of All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine '
Sampled of Analysis Detect ion ** Mean (T) Name **Mean (f) **Mean (f) Reported >
junit of fleasurement) Performed (LLD) * *R ange Distance and Directions ** Range * *R ange Measurement s* *
- Montgomery Dam No. 49 [
co Surf ace Water Gross (72) 2 LLD -- -- -- - *
(pCl/f) Alpha -- --
g Gross (72) 1 5.6(72/72) 8VPS Discharge No. 02A 7.7(12/12) 5.3(12/12) 0 S Beta (1.7-12) River Mlle -- 35.0 (4.3-9.6) (4.1-6.9) $ ts Ganua(12) Table V.A. 4 LLD -- -- -- -
fj
- o. c l Sr-89 (24) 2 LLD -- -- -- -
p@ ]
wz ;
jM i i I r ta !
l *
@Q r 3:
]
Tritium (24) 70 2040(24/24) BVPS Discharge No. 02A 8530(4/4) 273(4/4) 0 g H
(110-17000) River Mlle -- 35.0 (440-17000) (110-410) -
p n
<o
$k i!i 0
H W
(a) 0o-60 analyzed by high sensitivity method. .@
O ct H-b r*
- M Nominal Lower Limit of Detection (LLD) 11ean 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
- p (Appendix B) .
w
m ~ w_.~ ~ r ~ r- _.
r- ..
r- r-m .r-m r-m r~m _ r, _ .r-m r-n r~m _m r ENVIROINENTAL RADIOLOGICAL MONITORING PROGRAM SUpglARY l
1
- Name of Facility Duquesne Light Company Docket No. 50-334 Location of Facility Beaver, Pennsylvania Reporting Period Annual 1984 us i (County,5 tate)
-Q
H O
2:
Analysis and Lower Limit Number of Medius or Pathway Total Number of All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine 4 ,
Sampimi of Analysis Detection ** Mean (f) Name . *mean (f) **Mean (f) Reported 8 (Unit of Heasurement) Performed (LLD) * *R ange Distance and Directions ** Range * *R ange Measurements ***. p.
DrirAing Water (pCl/t)
I-131(104) 0.2 0.29(11/104) E. Lvpl, OH No. 05 River Mlle -- 41.2 0.30(2/52). -- 0 $
(0.19-0.44) (0.19-0.41) y.
l Gross (24) 0.6 LLD -- -- -- -
g l Alpha p 1
g.
Gross (24)
Beta 1 .4.l(24/24) Midland Pa. No. 04 River Mlle -- 36.3 4.3(12/12) -- 0 $
l (2.2-6.1) (3.4-5.7)
E.g o i Gansna(104) Table V.A.4 LLD -- -- -- -
g Q.
O V) py Sr-89 (8) 1.5 LLD -- -- -- -
i i oo
, Sr-90 (8) 0.5 LLD -- -- -- -
p[
w N o
, Co-60 (8)(a) 1 LLD -- -- -- -
Pg M
Tritium (8) 100 210(8/8) E. Lvpl. OH No. 05 215(4/4) -- 0 D0 (180-380) River Mlle -- 41.2 (180-380) $S n 50 w
N W
5 2
a (a) 8:o-60 analyzed by high sensitivity method. H b
t-*
M Nominal Lower Limit of Detection (LLD) f Mean and range based upon detectable measurements only. Fraction of detectable measu.ements at specified locations is indicated in parentheses (f) 3 Monroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications
- g (Appendix 8)
- . .- -m .m v - r- ,
r-m. v e-m _ r-, rm m m -
I ENVIRONMENTAL RADIOLOGICAL MDNITORING PROGRAM SUIMARY Name of Facility Duquesne Light Company Docket No. 50-334 Location of Facility 8eaver, Pennsylvania Reporting Period Annual 1984 (County,5 tate) Q s
O Analysis and Lower Limit <
Medium or Pathway Total Munber of Munber of All Indicator Locations Location with Highest Quar. Mean Control Locations Nonroutine g
Sampled of Analysts Detection ** Mean (f) Name #
jlfnit of Measurement) Performed (LLD) * *R ange **Mean(f) **Mean (f) Reported Distance and Directions ** Range * *R ange Measurements *** j Georgetown, Pa. No.15 Ground W ater g l Gross (16) 2 LLD --
(pC1/ liter) Alpha p
Gross (16) 1 3.5(13/16) Hookstown Pa. No.14 4.8(4/4)
Beta 2.6(3/4) 0 g (1.1-5.6) 3 miles -- WSW (4.2-5.4) (2.2-3.2) -
H Ganesa (16) Table V.A. 4 LLD -- -- -- -
EM Tritium (16) 90 220(13/16) Georgetown Pa No.15 270(3/4) Same as 0 h
$ cn (100-370) 4.6 alles -- WNW (230-330) High Location yy
' $ t*
a to 05 em
' H So E4 8$
S E
i?
2 3
H b
t-trj Nominal Lower Limit of vetection (LLD)
Mean and range based upon detectable measurements only.
Fraction of detectable measurements at specified locattoos is indicated in parentheses '(f)
Nonroutine (Appendixreported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications
- B) g e
SECTION V - A DUQUESNE LIGHT COMPANY L 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
~
A. Environmental Radioactivity Monitoring Program (continued)
- 2. Summary of Results
{
All results of this monitoring program are summarized in r Table V.A.2. This table is prepared in the format
( s,pecified by NRC Regulatory Guide 4.8 and in accordance with Beaver Valley Power Station Operating License, (Appendix A, Technical Specifications). Summaries of results of analysis of each media are discussed in Sections V-B through V-H and an assessment of radiation doses are found in Section V-I. Table V.A.3 summarizes Beaver Valley Power Station pre-operational ranges for the various sampling media during the years 1974 and 1975. Comparisons of pre-operational data with operational data indicate the ranges of values are in good agreement for both periods of time.
In a few cases where activity was detected, some of the activity was attributable to previous nuclear weapons tests and the remaining detected activities were near the lower limit of their detection (LLD) and are attributable to the normal statistical fluctuation near
( the LLD level.
The conclusio1. from all program data is that the
[ operation of the Shippingport and Beaver Valley ?ower
( Station has not rest.lted in any detectable changes to the environment attributable to either station.
3.
( Quality Control Program The Quality Control Program implemented by Duquesne
[ Light Company to assure reliable performance by the DLC
( contractor and the supporting QC data are presented and discussed in Section III of this report. The lower limits of detection for various analysis for each media
( monitored by this program by the Laboratory are provided in Table V.A.4.
DLC Contractor
{
SECTION V - A DUQUESNE LIGHT COMPANY' TABLE V.A.3 1984 Annu21 Radiological Environm:ntal Rzport (Page 1 of 4)
TABLE V.A.3 (Page 1 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Tacility Shiteistport Atemic Power Station Docket No.
Not Aceticable Nana of Tacey 3eaver '.'a nev ?ever station Occicat No. 50 Location of Tacility 3eaver Pennsvivania Reporting Period CT 1974 - 1975 (County, State)
PRE-OP!IATICMAL PROCRAM SQ0LARY (COM5I'C 1974 - 1975)
Medius or Fat.Way tower Limit Sampled Analysis and 2ocal Number C*nie of Measurement) of All Indicator Locations of Analvsis ?arformed Detection t1D Mean. (f) Ranae Surface "Jacer Cross Alpha (40) 0.3 0.75 5/40 0.6 - 1.1 pC1/1 Cross seca (120) 0.6 4.4 120
/120 2.3 - 11.4 Gemma (1) 10 - 60 < TD 2riti m (121) 100 300 U/121 130 - 800 St-49 (0) - -
St-90 (0) - -
C-14 (0) - -
Drissing "Jacer 2-131 (0) -
Cross Alpha (50) 0.3 0.6 '/50 0.4 - 0.8 Cross Beta (208) 0.6 3.8 208/208 2.3 - 6.4 Camma (0) - -
2ritium (211) 100 310 /211 130 - 1000 C-14 (0) - -
Sr-49 (0) - -
i St-90 (0) - -
Gemed water Cross Alpha (19) 0.3 PC1/1
- f.Ia Crose Beta (76) 0.6 2.9 73/ 75I *I 1.3 - 8.0 Tritim (81) 100 440 I
/81 80 - Sr*
Comma (1) 10 - 60 < ILD Air Particulates Cross Alpha (188) 0.001 0.003 and Caseous 33/138 0.002 - 0.C04 pC1/a3 Crose 3eca (927) 0.QM 0.07 927/ 927 0.02 - 0.32 Sr-49 (0) -
$r-90 (0) -
I-131 (816) 0.04 0.08 2/ 316 0.07 - 0.08 Camma (197) 2r h 95 0.003 0.04 /197 0.01 - 0.15 Ru-106 0.010 0.04 50/197 0.02 - 0.09 Ca-141 0.010 0.02 /197 0.01 - 3.04 Ca-144 0.010 0.02 /197 3.01 - 0.04 Others < '.m
_ 79 _
5-f SECTION V - A DUQUESNE LIGHT COMPANY TABLE VeA.3 1984 Annuni Radiological Environmental Raport (Page 2 of 4)
TABLE V.A.3 (Page 2 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
r b
Name of Facility Shiset m ert Ae mie Pever Station Docket No. Not Apolicable Name of Tacility 3eaver Vallev Power scacica Docket No. N-m Location of racility Peaver. Penasvivania Importing Period CT 1974 - 1975 (County state) {
PRE-CPERATIONAL PROGRAM SQtfARY (CCHBINED 1974 - 1975)
Media or Pattasny Lount Limit Sampled Analysis and Total E mber of All Indicator 14 cations (Unie of Measurements of w 'vois Perfonned Detection LLD Mean. (f) r Soil Grose Alpha (0) - -
PC1/g (dry)
(T m place Samples) Grose Beta (64) 1 22 g/ 64 14 - 32 1
Sr-49 (M) 0.25 0.4 /M -
l Sr-90 (M) 0.05 0.3 & 8/M 0.1 - 1.3 l U-234,235,238 (0) - -
Gama (M)
E-40 1.5 63 13 /64 5 - 24 Co-137 0.1 1.5 56/ 64 0.1 - 6,8 Co-14 7 0.3 1.1 /4 6 0.2 - 3 Zrsb-95 0.05 0.3 U /46 0.1 - 2 In-106 0) 0.3 1.1 3/64 0.5 - 2 f others < LLD Scil Gross Alpha (b) =
{ PC1/g (dry)
=
(Core Samples) Grose seca (8) 1 8
/8 21 16 - 28 Sr-49 (8) 0.25 < Lla Sr-90 (8) 0.05 0.2 5/8 0.04 'O.5 Gasma (8)
E-40 1.5 13 8/ 8 7 - 20 C*-137 0.1 1.2 7/ 8 0.2 - 2.4
( CHO 0.1 0.2 1
/8 -
Others < 113 71 -
1 b -
DUQUESNE LIGHT COMPANY TABLE V. A.3 (SECTIONV-A 1984 - Annual Radiological Environn:ntal R2 port (Page 3 of 4)
( TABLE V. A.3 (Page 3 of 4)
(. ENVIRON'IENTAL RADIOLOGICAL >10NITORING PROGRA21 SU101ARY
[ sa a of ract u:7 fuw- -ee- e--i- ? ve- its-t m acket No. "e e
- 1 f "" *
( Name of Tacility 3eaver '.'eliev Pever its-tes Occs.et No. 50-33*
tacac*ca of Tac 111:7 Seaver. ?ennsvLvania 14porti.sg 'avel c' !??? - 1975 (Count 7. state) )
FRE-OFEIAIIONAI. PSDGRAM SN(C:2GL'E31974 - 1975)
F.asiasm or Factuay '.auer t.init Sampled Analysis and Total Number of All Indicator Locations (tait of M asuremmat? of Analvsts ?ardo ned *etection O Meaa. (f) taase Sam h ts Cross ~
Alpha (0) -
PCU g (dry) 33f 33 I
Cross 3 eta (33) 1 13 3 - 30 3r-90 (0) - -
U-234.233. 238 (0) - -
Gamma (33) 13 33/ 33 2 - 30 33 E-40 1.3 13 /33 2 - 30 Cs-L37 0.1 0.4 /33 0.1 - 0.6 19 3rsb-95 0.05 0.8 **/33 0.2 - 3.2 Co-La4 0.3 0.3 /33 0.4 - 0.7 tv.-106 0I 3
0.3 1.3 /33 1.3 - 1.3 Others eC l
(. Foodses!!
pcus (d.7)
Cama (3) 5 i E-40 1 33 /3 10 - 33 Ca-L37 0.1 0.2 /$ -
1
- rsh-95 0.05 0.2 /5 -
In-LQ4 0I 1
0.3 0.3 /8 -
( _s .m I0 /50 Feedstuff Crose 3 eta (30) 0.05 19 S - 50 3r-49 (81) 0.0 3 3.2 33/51 0.04 - 3.13 3r-90 3.003 3.4 I/ 31 0.02 - 0.31 (31)
Gamma (51)
II E-*C L 19 /81 3 - 44 Co-L37 0.1 0.3 /S1 0.2 - 1.6 Co-144 0.3 1.3 3/51 0.9 - 2.6 rsb-95 0.03 3.3 /$1 0.2 - 1.3 lu-106 0.3 1.4 Ill 0.6 - 2.3 others e !.;.3
SECTION V - A DUQUESNE LIGHT COMPANY TABLE VeA.3 1984 Annual Radiological Environs:ntal Raport (Page 4 of 4)
$ ~
TABLE V.A.3 (Page 4 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
F Name of Tacility Shionistoere Atomic Power Station Oocket No. Not Aeolicable
( Naas of Facility 3eaver valle, Power itseies Occkat No. 50-334 Location of Tacility 3eaver. Pennsvivania Reportiss Level Cy 1977. - 19 N (County, Stata)
PEZ-4FERATIONAL PROGRAM SIDeWir (CCMBINED 1974 - 1975) l Medi a or Pathway Immer Limit 5 g led Analysis and Total Number of All Indicator I4 cations (thLit of w--- r - t) of Analvsis Performed Detection II.D Mean. (f) Ramme Milk I-131 (91) 0.25 C.6 '/91 0.3 - 0.8 Sr-49 (134) 5
~
/134 6 - 11 se-90 132 (134) 1 /134 1.5 - 12.s Gammer (134)
Co-137 10 18 13 /134 11 - 16 Others < U.D 1 sternal Radiation y - Monthly (599) 0.5 at
- 0.20 599/599 0.08 - 0.51 ma/ day y - Quarterly (195) 0.5 mE
- 195 0.20 /195 0.11 - 0.38 y - Ammaal '8 (44) 0.5 mE* 0.19 /48 0.11 - 0.30 Fish Gross Beta (17) 041 pC1/g (wet) 1.9 U/17 1.0 - 3.2
( Sr-90 (17) 0.005 0.14 17/17 0.02 - 0.50 Games (17)
~
( E-40 0.5 2.4 17
/71 1.0 - 3.7 Othat e LLD
(
l f
- t 11D in units of MR - Lower and of useful integrated exposure detectability range for a passive radiation detector (TLD).
(8 Osa outlier not included in saan. (Water taken from dried-up spring with high sediment and potasetum content. Not considered typical groundwater sample.)
May faciude Eu-106, au-103, 3e-7.
.. +
SECTION V - A TABLE V. A.4
('_ DUQUESNE LIGHT COMPANY
( --f
. 1984 Annual Radiological Environmental Report m
- se y
.= m M ee o se 5 e .P en M M me *a M m M w a o
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74 -
( !
i SECTION V - B DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING B. Air Monitoring
- 1. Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is generally h from the Southwest in summer and from the Northwest in
,, the winter. I
- 2. Air Sampling Program and Analytical Techniques
- a. Program -
The air is sampled for gaseous radiciodine and radioactive particulates at each of ten (10) off-site air sampling stations. The locations of these stations are listed in Table V.A.1 and shown on a map in Figure 5.B.1.
Samples are collected at each of these stations,by continuously drawing about one cubic foot per minute of atmosphere air through a glass fiber filter and through a charcoal cartridge. The former collects airborne particulates; the latter
(.- '
is for radioiodine sampling. Samples are collected for analysis on a weekly basis.
f- The charcoal is used in the weekly analysis of airborne I-131. The fi:.ters are analyzed each week for gross beta, then composited by station for monthly analysis by gamma spectrometry. They are
{ further composited in a quarterly sample from each station for Sr-89/90 analysis. In order to reduce interference from natural radon and thoron
(- radioactivities, all filters are allowed to decay for a few days after collection prior to counting for beta in a low background counting system.
- b. Procedures
[. Gross Beta analysis is performed by placing the
(' filter paper from the weekly air sample in a 2" x 1/4" planchet and counting it in a low background, >
gas flow proportional counter.
k I
f.
SECTION V - B DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING B. Air Monitoring (continued)
- 2. Air Sampling Program ' and Analytical
( (continued)
Techniques
- b. Procedures (continued)
Gamma emitters are determined by star. king all the filter papers from each monitoring station collected during the month and scanning this composite on a lithium drifted germanium (Ge(Li))
gamma spectrometer.
, Radiciodine (I-131) analysis is performed by a gamma scan of the charcoal in a weekly charcoal cartridge. The activity is referenced to the mid-collection time.
(
(
l v
SECTION V - B FIGURE 5.B.1 F
DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report i
L FIGURE 5.B.1 ENVIRt3MdENTAL. WCeGTORMS LOCATIONS- A[R epptIm tryy{yg
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SECTION V - B. DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING B. Air Monitoring
- 2. Air Sampling Program and Analytical Techniques
[. (continued)
- 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 filtrato is taken for strontium analysis and is reduced in volume by evaporation. Strontium is precipitated as SrG0 J2 3 using fuming (90%) nitric acid. An iron
[ (ferric hydroxide) scavenge is performed, followed
( by addition of stable yttrium carrier and a 5 to 7 -
-4 day period for yttrium ingrowth. Yttrium is then precipitated as, hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylen planchet and is counted.in a low level beta counter to infer strontium-90 activity.
Strontium-89 activity is determined by precipitating SrC0 s from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is coverad with 80 mg/cm 2 aluminum f absorber for level beta counting.
- 3. Results and Conclusions
{. A summary of data is presented in Table V. A.2.
- a. Airborne Radioactive Particulates A total of five hundred twenty (520) weekly samples
.from ten (10) locations were analyzed for gross beta. Results were comparable to previous years.
Figure 5.B.2 illustrates the average concentration p of gross beta in air particulates.
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SECTION V - B DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING B. Air Monitoring (continued)
- 3. Results and Conclusions (continued)
- a. Airborne Radioactive Particulates (continued)
, The weekly air particulate samples were composited to one hundred and twenty (120) monthly samples which were analyzed by gamma spectrometry.
Naturally occurring Be-7 was present in every sample. Occasional traces above detection levels of other nuclides were present. Some were natural, others were residual from previous nuclear weapons tests. These are listed in the summary Table V.A.2. Examination of effluent data from the Beaver Valley Power Station and the Shippingport Atomic Power Station demonstrated that none of the slightly elevated results are attributable to the operation of either power station. -
A total of forty (40) quarterly samples were each analyzed for Sr-89, and Sr-90. Results were comparable to previous years.
Based on the analytical results, the operation of Beaver Valley Power Station and Shippingport Atomic Power Feation did not contribute to any increase in air particulate radioactivity during CY 1984.
- b. Radiciodine 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.
L 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 1984.
(
(
h SECTION V - C DUQUESNE LZGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was not required in 1984.)
- 1. Characterization of Stream Sediments The stream sediments consist largely of sand and silt.
Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.
- 2. Sampling Program and Analytical Techniques
- a. Program River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and Shippingport discharge and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table V.A.1 and are shown in Figure S.C.1.
Bottom sediments are analyzed for gross alpha and <
beta activity, strontium, uranium, and the gamma-emmitting radionuclides.
- b. Analytical Procedures
( Gross bet'a - sediments and soils are analyzed for gross beta by mounting a 1 gram portien of dried sediment in a 2" planchet. The sample is counted
[ in a low background, gas flow proportional counter. j l Self absorption corrections are made on the basis of sample weight, f Gross alpha activity of sediment or soil is l analyzed in the same manner as gross beta except l that the counter is set up to count only alpha.
Gamma analysis of sediment or soil is performed in a 300 ml plastic bottle which is countsd by a gamma spectrometer.
(
Y SECTION V -C FIGURE 5.C.1 r DUQUESNE LIGHT COMPANY i
s 1984 Annual Radiological Environmental Report S E D I *.'E N T S AND S O II. S c
l FIGURE 5.C.1 L
ENVIRONMENTAL. WC0GT0fUMB LOCATIONS- SHCrTU E SEDIBDTS & S0IL N uwness couvrr
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SECTION V - C DUQUESNB LIGHT CO)1PANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL ?!0NITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was not required in 1984)
(continued) l
- 2. Sampling Program and Analytical Techniques (continued)
- b. Analytical Procedures (continued)
(
Strontium 89 and 90 are determined by
( radiochemistry. A weighed sample of sediment or
( soil is leached with Nitric Acid HNO3 . A stable carrier is added for determination of recovery.
Strontium concentration and purification is
( ultimately realized by precipitations of strontium nitrate in fuming nitric acid. Additional hydroxide precipitations and barium chromate separations are also used. The purified strontium is converted to a carbonate for weighing and counting. Samples are counted soon after separation (5 - 7 days is allowed for yttrium ingrowth). Activities are calculated on the basis l of appropriate Sr-89 decay and Y-90. Separate ,
mounts covered with a 80 mg/cm 2 aluminum absorber are used for counting in a low background beta counter.
Uranium isotopic analysis of sediment and soil
( samples were performed by alpha sp4ctrometry after leaching and isolation of the uranium by an ion exchange chromatography plus mercury . cathode
_ electrolysis, then electroplated onto a planchet.
- 3. Results and Conclusions
( a. Results The results of sediment analysis are summarized in Table V.A.2.
There were no significant differences between these current levels and those previously detected in f both upstream and downstream sediment samples.
I
f.-
SECTION V - C DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING C. Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years and was not required in 1984J (continued)
- 3. Results and Conclusions (continued)
- a. Results (continued)
Uranium isotopic analyses were performed by alpha spectroscopy. The results suggest that only naturally occurring U-234 and U-238 were present since the activities were nearly always the same in each sample and the levels are within the expected l range of natural uranium activities. In equilibrium, U-234 and U-238 have the same activity.
l l
- b. Conclusion Other than trace amounts of Co-58, Co-60 and Cs-134, the sediment analyses do not indicate any radioactivity attributable to Beaver Valley Power Station and Shippingport Atomic Power Station liquid discharges. Small amounts of Cs-137 from weapons testing fallout was found in all river sediment samples including those upstream above
[ Montgomery Dam which are unaffected by plant
} effluents.
f
f L
SECTION V - D DUQUESNE LIGHT COMPANY
( 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING D. 'donitoring of Feedcrops and Fooderops l 1. Characteri=ation of Vegetation and Foodcrops According to a survey made in 1981, there were approximately 650 farms in Beaver County. The principle
( source of revenue for the farms was in dairy products which amounted to nearly $4,659,000.00. Revenues from other farm products were as follows:
(' Crops $2,143,000.00 Horticulture $ 551,000.00 Meat $1,274,000.00 Poultry.
( $ 392,000.00 The percentage of crop land in !seaver County is approximately 17%, pasture land - 6.5%, forest land -
47.8%, and other land uses - 28.7%.
- 2. Sampling Program and Analytical Techniques
- a. Program
( Representative samples of cattle feed are collected
( monthly from the nearest dairy (Searight). See Figure 5.D.1. Each sample is analyzed by gamma spectrometry. The monthly semples are composited
( :
into a quarterly sample t.nich is analyzed for Sr-90.
A land use census was performed August, 1984 to
( locate the nearest residence and nearest garden of greater than 500 square feet producing fresh leafy vegatables within a five (5) mile radius of the
( site. See Table V.D.1 for results.
Foodcrops (vegetables) were collected at garden
[ locations during the summer of 1984. Leafy
( vegetables, i.e., cabbage, lettuce, and endive were obtained from Shippingport, Georgetown, Industry, PA, and from Weirton, WV. All samples were f analyzed for gamma emitters (including I-131 by gamma spectrometry).
- b. Procedures Gamma emitters, including I-131, are determined by scanning a dried, homogenized sample with the gamma spectrometry system. A Ge(Li) detector is utilized with this system.
)
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A ederop a ENVIRONMENTAL MONITORING PROGRAM FEEDCROP AND FOODCROP LOCATIONS v.
FIWE 5.D.1 h
SECTION V --D DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report Table V.D.1 Closest Residence and Garden in Each Sector Sector Closest Residence
- Closest Garden
- 1 1.59 mi N 1.63 mi N
( 2 1.64 mi NNE 1.68 mi NNE 3 0.44 mi NE 0.62 mi NE 4 0.44 mi ENE 1.04 mi ENE 5 0.47 mi.E 1.23 mi E 6 0.98 mi ESE 0.98 mi ESE 7 1.14 mi SE 1,63 mi SE 8 1.08 mi SSE 1.09 mi SSE f 9 1.36 mi S 1.36 mi S 10 0.76 mi SSW 1,48 mi SSW
(- 11 1.38 mi SW 1.53 mi SW 12 1.42 mi WSW 1.43 mi WSW 13 2.21 mi W 2.21 mi W 14 2.24 mi WNW 2.24 mi WNW
(
15 0.89 mi NW 0.91 mi NW f 16 0.71 mi NNW 1.02 mi NNW
- Distance and Direction from Reactor
{
(
(
s SECTION V - D CUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING D. Monitoring of Feederops and Foodcrops (continued)
- 2. Sampling Program and Analytical Techniques (continued)
- b. Procedures (continued) s g Strontium 90 analysis for feedstuff is performed by
.'a procedure similar to that described in V.C.2.
1
- 3. Result's and Conclusions A summary of results is provided in Table V.A.2. The predominant isotope detected was naturally occurring X-40 in both food and feed. Other activity is attributable to residuals from previous nuclear weapons tests or naturally occurring radionuclides. All results were consistent with (or lower than) those obtained in the pre-operational program. These data confirm that Shippingport Atomic Power Station and Beaver Valley Power Station did not contribute to radioactivity in foods and feeds in the vicinity of the site.
N P
k s
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L SECT 80N V - E DUQUESNE LfGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING E. Monitoring of Local Cow's Milk
- 1. Description - Milch Animal Locations During the seasons that animals producing milk (milch animals) for human consumption are on pasture, samples
( of fresh milk are obtained from these animals at locations and frequencies noted in Table V.A.1. This -
milk is analyzed for its radiciodine content calculated as Iodine-131. The analyses are performed within eight
( (8) days of sampling.
Detailed field surveys are performed during the grazing-( season to locate and enumerate milch animals within a five (5) mile radius of the site. Goat herd locations i out to fifteen (15) miles are identified. Survey data l
[ for the most recent survey conducted in August, 1984 is
( shown in Figure 5.E.1.
- 2. Sampling Program and Analytical Techniques
- a. Program
[ Hilk was collected from three (3) reference dairy L farms within a 10-mile radius of the site and from one (1) control location outside of the 10-mile radius. Additional dairies, which represent the
( highest potential milk pathway for radioiodine based on milch animal surveys and uteorological data were selected and sa= pled. 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 52 Cows 2.1 miles-south /sw. Jan. - Dec.
27 Brunton 105 Cows 7.3 miles-southeast Jan. - Dec.
29A dichol 55 Cows 8.0 miles-northeast Jan. - Dec.
96 Windsheimer 50 Cows 10.3 miles-southisw. Jan. - Dec.
61 Allison 23 Cows 3.2 miles-west /sw. Jan. - May 69 Collins 8 Goats, 1 Cow
- 3.6 miles-southeast Jan. - Dec.
62 Lyon 20 Cows 3.3 miles-west /sw. Feb. - May
(
SECTION V - E DUQUESNE LEGHT COMPANY 1984 Annual Radiological Environmental Report l
V. ENVIRONMENTAL MONITORING
[' E. Monitoring of Local Cow's Milk (continued)
- 2. Sampling Program and Analytical Techniques (continued)
- a. Program (continued)
{
< Number of Milch Distance and Direction Collection'
[ Site Dairy Animals' From Site Period 98 Foxall
( 100 Y (Hammond)
Doughty
- 2. Goats
- 2.9 miles-east May - Dec.
1 Cow
- 2.8 miles-west /nw. Jan.,May-June 99 Lampich 14 Goats
- 4.1 miles-ESE June - Nov. l
- Milk Usage - Home Only.
s
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P SECTION V - E DUQUESNE LIGHT COMPANY FIGURE 5.E.1 s
1984 Annual Radiological Environmental Report L
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. SECTION V - E FIGURE 5.E.2 DUQUESNE LIGHT CO ?ANY r 1984 Annual Radiological Environmental Report 5.E.2 l
( FIGURE ENVIRCNMENTAL WODSTOfuMB LOCATIONS- Pill.
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L L SECTION V - E DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report
- V. ENVIRONMENTAL MONITORING b
E. Monitoring of Local Cow's Milk (continued)
- a. Program (continued)
{
The sample from Searight Dairy was collected and analyzed weel:1y for radioiodine using a procedure
[- with a high sensitivity. Samples from each of the other selected dairies were collected monthly when cows are indoors, and bi-weekly when cows are
( grazing.
analyzed for Sr-89, Sr-90, gamma emitters including This monthly or bi-weekly sample is Cs-137 (by Spectrometry) and I-131 (high sensitivity analysis),
- b. Procedure
( Radioiodine (I-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
Gamma emitters are determined by ga:ama spectrometry of a one liter Marinelli container of milk.
( Strontium analysis of milk is similar to that of other foods (refer to V.C.2) except that milk samples are prepared by addition of Trichloracetic Acid (TCA) to produce a curd which is removed by
[-. filtration and discarded. An oxalate precipitate is ashed for counting.
( 3. Results and Conclusions A total of one hundred and fifty-two (152) samples were analyzed for I-131 during 1984. All I-131 activities in milk were below the minimum detectable level (0.3 pCi/1).
( A total of one analyzed by gamma spectrometry and for strontium.
hundred and twenty (120) samples were Both the Cs-137 and Sr-90 levels were within the normally expected range. The higher levels from China's nuclear
( tests which were experienced in other years were absent this year. Such tests were not performed during 1984.
r 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 in CY 1984.
[
L SECTZON V - F
[ DUQUESNE LIGHT COMPANY 1964 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING F. Environmental Radiation Monitoring l
)
{. , 1. Description of Regional Background Radiation Levels and Sources The terrain in the vicinity of the Shippingport and
[. B,eaver Valley Power Station generally consists of rough l hills with altitude variations of 300 to 400 feet. Most of the land is wooded.
The principal geologic features of the region are nearly flat-lying sedimentary beds of the Pennsylvania Age.
Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams.
Based on surveys reported in IJ;evious annual reports, exposure rates ranged from 6 to 12 pR/hr. Results for
( 1984 indicated that background radiation continued in this range.
- 2. Locations & Analytical Procedures Ambient external radiation levels at the site were measured using thermoluminescent dosimeters (TLDs).
There were three (3) types used in the Duquesne Light Company Radiological Environmental Monitoring Program.
They are calcium sulphate dysprosium, CaSOg (Dy) in teflon matrix, lithium fluoride (LiF), and thulium activated calcium sulfate (CaS0g:Tm).
The lithium fluoride TLDs were posted and analyzed by a laboratory of the Department of Energy (DOE) as an independent check of environmental radioactivity levels.
The CaSog:Tm TLDs were used as a back-up and as a QC
[ program. In 1984 there were a total of forty-four (44)
( off-site environmental TLD locations. The locations of
, the TLDs are shown in Figures 5.F.1 thru 4. Comparisons of TLD results are presented in Table III.1.
e L
SECTZON V -F FIGURE 5.F.1 DUQUESNE LIGHT COMPANY p 1984 Annual Radiological Environmental Report L
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DUQUESNE LIGHT CCITE.T b 1984 Annual Radiological Environmental Report
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DUQUESNE LIGHT COMPANY j 1984 Annual Radiological Environmental Report
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l SECTf0N V - F DUQUESNE LIGHT C011PANY j 1984 Annual Radiological Environmental Report V. ENVIRON >1 ENTAL MONITORING F. Environmental Radiation Monitoring (continued)
- 2. Locations & Analytical Procedures (continued)
{.
The lithium fluoride (LiF) TLDs used for environmental j purposes are pre-selected and annealed at least 5 working days prior to use. The radiation dose accumulated from the anneal date to the date of posting is accounted for by utilizing background readings from five (5) TLD chips in conjunction with an average background correction factor. The calibration of the l TLD reader is performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of processing i the posted environmental TLDs. The environmental TLDs
( are processed after retrieval and a background correction is made to account for the background radiation accumulated from the date of retrieval to the date of processing.
The calcium sulfate (CaSOg :Dy) TLDs were annealed shortly before placing the TLDs in their field locations. The radiation dose-accumulated in-transit between the field location and the laborat'ory was corrected by annealing control dosimeters shortly before
(
the field dosimeters were removed from the field location, then shipping the freshly annealed control cosimeters with the exposed field dosimeters to the
[ laborator,r for readout at the same tine. All dosimeters h were expotad in the field in a special environmental holder. '"he dosimetry system was calibrated by reading calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation field.
- 3. Results and Conclusions Data obtained with the contractor TLD (CaSO :Dy g in teflon) during 1984 are summarized in Table V.A.2, and the quality control TLD results are listed in Table
[ III.1.
t The annual exposure rate of all off-site TLD's averaged 0.16 mR/ day in 1984. As in previous years, there was some variation among locations and seasons as would be expected.
L l
V
SECTION V - F DUQUESME LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
[.
F. Environmental Radiation Monitoring (continued)
- 3. Results and Conclusions (continued)
In 1984, ionizing radiation dose determinations averaged approximately 58 mR for the year. This is comparable to previous years. There was no evidence of anomalies that could be attributed to the operation of either Beaver Valley Power Station or Shippingport Atomic Power Station. Three sets of TLDs of different types ,
demonstrate good agreement and confirm that changes from l natural radiation levels, if any, are neg11ble.
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-100-
l SECTION V - G DUQUESNE LIGHT COMPANY 5 1984 Annual Radiological Environmental Report.
V. ENVIRONMENTAL MONITORING G. Monitoring of Fish
- 1. Description Fish collected near the site are generally scrap fish.
During 1984, fish collected for the radiological monitoring program included carp and catfish.
- 2. Sampling Program and Analvtical Techniques
- a. Program Fish samples are collected semi-annually in the New
{ Cumberland pool of the Ohio River at the Beaver Valley and Shippingport effluent discharge points and upstream of the Montgomery Dam. The edible
(. portion of each different species caught is analyzed by gamma spectrometry. Fish sampling locations are shown in Figure 5.G.I.
- b. Procedure A sample is prepared in a standard tared 300 ml
( plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a Ge(Li) detector.
- 3. Results and Conclusions A summary of the results of the fish monitoring data is provided in Table V.A.2. Seven (7) fish were caught in May. Three (3) more samples were caught in November.
Except for naturally occurring K-40, the only gamma emitter which was detected in any samples was a trace of
( Cs-137 in two samples. Cesium-137 is a long lived fission product and some residual activity persists from previous weapons testing programs. This indicates that
{ the operation of the Shippingport Atomic Power Station and the Beaver Valley Power Station has not resulted in radioactivity in fish in the Ohio River.
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SECTION V - H DUQUESNE LIGHT COMPANY q 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING H. Monitoring of Surface, Drinking, and Well Waters
~
- 1. Description of Water Sources The Ohio River is the main body of water in the area.
It is used by both the Beaver Valley and Shippingport plants for water make-up and receiving plant liquid effluents. In addition, river water is used for cooling purposes at the Shippingport Atomic Power Station and make-up for the cooling tower at the Beaver Valley Power Station.
Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley and Shippingport 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- autaority.
The intake of the treatment plant is approximately 1.5 miles downstream and on the opposite side of the river.
s The next downstream users are East Liverpool, Ohio, and Chester, West Virginia, which are approximately 6 and 7 miles downstream, respectively. The heavy industries in Midland, as well as others downstream use river water for cooling purposes. Some of these plants also have prive.te treatment facilities for plant sanitary water.
Ground water occurs in large volumes in the gravel terraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gpm.
)
/
-103-s
SECTION V - H DUQUESNE LIGHT COMPANY
, 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING (continued)
H. Monitoring of Surface, Drinking, and Well Waters (continued)
- 2. Sampling and Analytical Techniques
- a. Surface (Raw River) Water The sampling program of river water includes six (6) sampling points along the Ohio River. Raw water samples are normally collected at the East Liverpool (Ohio) Water Treatment Plant [ River Mile 41.2] daily and composited into a monthly sample.
Weekly grab samples are taken from the Ohio River at the following locations: Upstream of Montgomery Dam [ River Mile 31.8]; at discharge from Shippingport Atomic Power Station [ River Mile 34.8]; and near the discharge from the Beaver Valley Power Station [ River Mile 35.0]. Two automatic river water samplers are at the following locations: Upstream of Montgomery Dam [ River Mile 29.6]; and at LTV Steel's river water intake [ River Mile 36.2]. The automatic sampler takes a 20 ml to 40 m1 sample every 15 minutes and is collected on a weekly basis. The weekly grab s amples and automatic water samples are composited into monthly samples from each location. In addition, a quarterly composite sample is prepared for each sample point.
The monthly composites are analyzed for gross alpha, gross beta, and gamma emitters. The quarterly composites are analyzed for tritium (H-3), strontium 89 (Sr-89), strontium 90 (Sr-90), and cobalt 60 (Co-60) (high sensitivity).
7 Locations of each sample point are shown in Figure 5.H.1.
- b. Drinking Water (Public Supplics)
Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Water Treating Plants. An automatic sampler at each location collects 20-40 milliliters every 20 minutes. These intermittent samples are then composited into a weekly sample. The weekly s ample from each location is analyzed by gamma spectrometry. The weekly samples are also analyzed for radiciodine (I-131).
-104-
SECTION V - H DUQUESNE LIGHT COMPANY
$ 1984 Annual Radiological Environmental Report f V. ENVIRONMENTAL MONITORING L
H. Monitoring of Surface, Drinking, and Well Waters (continued)
- 2. Sampling and Analytical Techniques (continued)
- b. Drinking Water (Public Supplies) (continued)
Monthly composites of the weekly samples are analyzed for gross alpha, gross beta, and by gamma spectrometry. Quarterly composites are analyzed
( for H-3, Sr-89, Sr-90 and Co-60 (high sensitivity).
Locations of each sample point are shown in Figure 5.H.1.
- c. Ground Water Grab samples were collected each quarter from each of four (4) well locations (see Figure 5.H.1)
- within four (4) miles of the site. These locations are
(
L: :One (1) well at Shippingport, PA One (1) well at Meyer's Farm (Hookstown, PA)
One (1) well in Hookstown, PA L One (1) well in Georgetown, PA Each groundwater sample is analyzed for gross alpha, gross beta, tritium, and by gamma spectrometry.
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x
SECTION V - H DUQUESNE LIGHT COMPANY 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 2. Sampling and Analytical Techniques (continued)
- d. Procedure Gross alpha and gross beta activities are determined first by evaporating one liter of the sample on a hotplate. The residue is mounted and
) dried on a 2-inch stainless steel planchet. The J sample is counted in a low background, gas flow proportional counter. Self-absorption corrections are made on the basis of sample weight.
Gamma analysis is performed on water sample by loading one liter of sample into a one liter marinelli container and counting on a Ge(Li) gamma spectrometry system.
Strontium-89 and 90 are determined on water samples by a procedure similar to that described in V.C.2 except that the leaching step is eliminated.
Cobalt-60 is determined with a sensitivity of 1 pCi/1 by evaporating 2 liters of sample on a hotplate and transferring the residue to a 2-inch planchet. The planchet is counted on a Ge(Li) spectrometry system.
Tritium is determined in water samples by converting 2 ml of the s ample to hydrogen and counting the activity in a 1 liter low level gas counter which is operated in the proportional range in anti-coincidence mode.
- 3. Results and Conclusions 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 s
A total of seventy-two (72) samples were each analyzed for gross alpha, gross beta, and gamma activity. Twenty-four (24) quarterly composited
) samples were analyzed for tritium (H-3) and
) radiostrontium (Sr-89 and Sr-90) as well as a high sensitivity analysis for Co-60, i
-107-I
SECTION V - H DUQUESNE LIGIIT COMPANY 1984 Annus1 Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 3. Results and Conclusions (continued)
[- No Sr-90, Sr-89, Co-60, or gamma emitters were L,
detected in surface water during CY 1984. All alpha and beta activities were within ncrmal range.
( The tritium levels in Beaver Valley Power Station and Shippingport Atomic Power Station outfall were elevated above preoperational levels in 1984, but none of these data suggests detectable increases over preoperational levels downstream of the station. The tritium activity is consistent with y station data of authorized radioactive discharges
(- and were well within limits permitted by NRC license and DOE Order 5480.1.
- b. Drinking Water A total of twenty-four (24) samples were analyzed for gross alpha and gross beta. All results wers
.- within a normal range.
A total of eight (8) samples were analyzed for tritium (H-3), radiostrontium (Sr-89 and Sr-90),
and cobalt (Co-60). No Sr-89, Sr-90, or Co-60 were detected. The tritium data were within the preoper2tional range indicative of nounal envirar. ental levels.
A total of another one-hundred and four (104) samples were analyzed by gamma spectrometry. No gamma emitting radionuclides were detected by these analyses.
l
{
l 3
-108-
)
SECTION V~- H DUQUESNE LIGHT COMPANY 1984 Annual. Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 3. Results and Conclusions (continued)
A total of one hundred and four (104) samples were
( '
analyzed for radiciodine (I-131) using a highly sensitive technique. Trace levels of I-131 were measured in some .of the weekly samples. The
( results were slightly above the minimum detectable activity of 0.2 pC1/ liter. The positive results could not be attributed to station discharges. The
[l results may be attributed to expected variability
( in the analyses results of very low levels of activity, f- c. Well Water A total of sixteen (16) samples were each analyzed for gross. alpha, gross beta, tritium and by gamma
[L '
spectrometry. No alpha activity was detected in.
any of the samples. The gross beta and tritium data are within preoperational ranges.
l d. Summary -
[: The data from water analyses demonstrate that k neither Beaver Valley- Power Station nor L. Shippingport Atomic Power Station contributed a significant increase of radioactivity in local river, drinking or well waters. The few pcsitive results which could be attributable to authorized
- releases from Beaver Valley Power Station and Shippingport Atomic Power Station are characteristic of the affluent. These results L 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, (excluding tritium and . dissolved gases) which was attributable to Beaver Valley Power Station, was only a small fraction (0.31%) of the concentration (averaged over a year) permitted by the Federal l ~. Regulations for water consumed by the public. The l Ohio River further reduced this concentration prior to its potential use by members of the public.
F.
V
-109-
[ SECTION V - I DUQUESNE LIGHT COMPANY L, 1984 Annual Radiological Environmental Report r V. ENVIRONMENTAL MONITORING l
5 I. Estimates of Radiation Dose to Man f 1. Pathways to Man - Beaver Valley Power Station L
- a. Calculational Models - Beaver Valley Power Station The radiation doses to man as a result of Beaver I Valley operations were calculated for both gaseous J and liquid effluent pathways using hTC computer codes X0QD0Q2, GASPAR, and LADTAP. Dose factors listed in Beaver Valley Power Station Environmental Technical Specifications were used to calculate
- doses to maximum individuals from radioactive noble L 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 f
license, were used as the radionuclide activity input.
Each radionuclide contained in the Semi-Annual Radioactive Effluent Release Report (noble gases, particulates, radiciodines and tritium) were included as source terms when they were detected above the LLD values. All LLD values at Beaver Valley Power Station are equal to or better than those required by the Technical Specifications.
All gaseous effluent releases, including Auxiliary Building Ventilation, were included in dose assessments. The release activities are based on laboratory analysis. When the activity of noble gas was below detection sensitivity, either the inventory based on its MDL or an appropriate but
[ conservative ratio to either measured activity of L Kr-85 or Xe-133 was used. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to X0QD0Q2 which in turn provided input for GASPAR. Except when more recent or specific data was available, all inputs were the same as used in the Beaver
[ Valley Power Station Environmental Statements or in l Regulatory Guide 1.109. The airborne pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the " cow-milk child", and other ingestion pathways.
-110-
s SECTION V - I DUQUESNE LIGHT COMPANY 3 1984 Annual Radiological Environmental Report r V. ENVIRON'! ENTAL MONITORING L
- a. Calculational Models - Beaver Valley Power Station (continued)
All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry
( using a GeLi detector. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfall (River Mile 35.0) The actual data i from these analyses are tabulated and used as the radionuclide activity input term in LADTAP. A hypothetical real individual for liquid pathways is located at Midland. Except when more recent or specific data for the period is available, all other input to LADTAP are obtained from the Beaver Valley Power Station Environmental Statement or
) Regulatory Guide 1.109. Pathways, which were j 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 - Real Individual The doses which are calculated, based on the model presented above in V.I.1, are summarized and compared to Beaver Valley Power Station license limits below. The doses calculated reflect a change in the far-field dilution factor in
) accordance with Technical Specifications, Appendix
} A and the Offsite Dose Calculations Manual. An additional breakdown of these doses by pathway and organ is provided in Table V.I.l. For these calculations, a hypothetical real individual (s) was located at Midland since this is the nearest location which significant exposure of a member of the public could potentially occur.
-111-
- ~ ~ w-TABLE V.I.1 Radiatien Dost to Maximum Individual", crer1/yr.
Beaver Vallny Power Station - Liquid Rtleasts CRITICAL USAGE WHOLE .y .
PATHWAY GROUP FACTOR SKIN ORGAN THYROID BONE BODY =
Fish Consumptionb Adult 21.0 kg N/A 0.00463 0.000114 0.00275. 0.00329 (Liver)- -
Drinking Waterc Infant 510 1 N/A 0.0040 0.00423 0.000287 0.00371 -
(Liver) y j Shorline Activities Teen 67 hr. 0.00025 - - -
0.00021 TOTAL MREM 0.00025 0.00701 0.00423 0.00357 0.00562 l CRITICAL (Teen) (Adult) (Infant) (Child) (Adult) mg l INDIVIDUAL (Liver) 8.g l Cp l gxm un b DOSE TO INDIVIDUALS DURING 1981 FROM NATURAL RADIATION EXPOSURE kE
? -' z Ambient Gamma Radiation:
Radionuclides in Body:
69d 18e I[
g 2g E
Global Fallout: 4e o Gi
~
TOTAL mrem 91 F
a Located at Midland Drinking Water Intake !
b Child - Usage Factor 6.9 kg/yr.
c Adult - Usage Factor 7301/yr.
d Pre-operational average ambient gamma radiation e National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation", BEIR Report, 1972.
F SECTION V - I DU',dESNE LIGHT COMPANY q 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued)
Actual Doses (mrem /yr.) -
Calculated Using Site Effluents Appendix I
- Analysis Dose - Calculated Using NRC Model Effluents Regulatory Limit Doses - NRC Staff Guidelines RM50-2 Appendix I Calcu eted Report (Con- RM50-2 (Re. Ratio of (1.21 Re- servative Limit w/o Calculated ported Re- Non-accident Cost / Benefit Dose vs.
leases Doses) Analysis) Reg. Limit TOTAL BODY Adult 0.00562 2.78 5.0 0.001124 Teen 0.00314 0.712 5.0 0.000623 Child 0.00320 Not Reported 5.0 0.00064 Infant 0.00371 Not Reported 5.0 0.000742 ANY ORGAN Adult 0.00701 Not Reported 5.0 0.001402 (Liver)
Teen 0.00595 Not Reported 5.0 0.00119 r (Liver) l Child 0.00655 Not Reported 5.0 0.00131 j (Liver)
Infant 0.00423 Not Reported 5.0 0.000846 (Thyroid)
Maximum Total Body Dose - Capsule Summary mrem 1984 Calculated 0.00562 Appendix I Estimated 2.78 Final Environmental Statement 0.112 Thyroid Dose - (Largest Expected Organ Dose)
, 1984 Calculated 0.00701 Final Environmental Statement 0.96
-113-I
5 r SECTION V - I DUQUESNE LIGHT COMPANY
( 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL MONITORING
- 2. Results of Calculated Radiation Dose to Man - Beaver Valley Power Station Liquid Releases (continued)
- b. Population Doses The- 1984 calculated dose to the entire population of almost 4 million people within 50 miles of the (i plant was:
Largest Isotope Man-Millirem Contributors TOTAL BODY 201 H-3 192 mrem Cs-60 3.23 mrem Cs-137 2.39 mrem THYROID 205 H-3 192 mrem I-131 11.7 mrem f 3. Airborne Pathway - (Beaver Valley Power Station)
The doses to the public for Beaver Valley Power Station airborne radioactive effluents during 1984 are provided in Table V.I.2. They include the contribution of all pathways. Tritium is the primary radionuclide contribution to these doses. The data demonstrate 1 compliance with 10CFR50, Appendix I design objectives.
- 4. Conclusions - (Beaver Valley Power Station)
Based upon the estimated dose to individuals from the natural background radiation exposure in Table V.I.l.,
the incremental increase in total body dose to the 50-mile population (4 million people), from the operation of Beaver Valley Power Station - Unit No. 1, is less than 0.0003% of the annual background.
The calculated doses to the public from the operation of Beaver Valley Power Station - Unit No. I are below 10CFR50, Appendix I design objectives, and resulted in only a small incremental dose to that which area residents. already received as a result of natural background. The doses constituted no meaningful risk to the public.
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-- w. ,
TABLE V.I.2 R::sults of Calculated Radiatten Dose to Man (1984)
Beav:tr Valley Power Station - Airborns Radioactivity
~
- v. .
E.
M \
E APPENDIX I* 50-MILE <
MAXIMUM EXPOSURE DESIGN OBJECTIVE- PERCENT.0F POPULATION DOSE e ORGAN INDIVIDUAL, mrem mrem APPENDIX I man rem -
TOTAL BODY 0.106 5 2.12 0.806 g co SKIN G.263 15 1.75 2.67 [
o LUNG 0.100 -- -----
0.863 ;
THYROID 0.143 -- -----
1.27 :o8
$f5 o
-* l2 2
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-' x m H bS
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s e SECTION V - I DUQUESNE LIGHT C0t!PANY L 1984 Annual Radiological Environmental Report V. ENVIRONMENTAL ?!0NITORING
- 5. Dose Pathways to ?!an - Shippingport Atomic Power Station The radiation doses to man as a result of operations at
{ the Shippingport Atomic Power Station during 1984 were calculated for gaseous effluent pathways and liquid effluent pathways.
Effluent monitoring at the Shippingport Station during 1984 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 f operations' was too low to measure and could only be estimated with the calculational model described below using measured or estimated effluent radioactivity data.
~
- a. Calculational t!odels -
Shippingport Atomic Power Station f The radiation doses to man from Shippingport Atomic Power Station operations were estimated using calculational models recommended by the International Commission on Radiological Protection (ICRP Publ. 2, 1959) and employ the general guidelines of the Nuclear Regulatory Commission (Regulator Guide 1.109) established to maintain compliance with 10CFR50 Appendix I.
The air dose pathways considered were inhalation, immersion in gaseous and suspended particulate activity, and the ingestion of food and milk produced in the Shippingport vicinity. It was conservatively assumed that food products consumed by the public were produced in the Shippingport area thrcughout CY 1984. The maximum potentially exposed individual for the air pathways was located at the site boundary. It was conservatively assumed that the maximum individual resides continually at the site boundary.
A hypothetical individual was located at Midland, PA since this is the nearest location which significant exposure of a member of the public could potentially occur. The liquid dose pathways considered were drinking water, fish consumption, shoreline recreation, swimming and boating.
l
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SECTION V - I DUQUESNE LIGHT COMPANY 1984-Annual Radiological Environmental Report
- 5. Dose Pathways to Man - Shippingport Atomic Power Station (continued)
Modeling parameters and usage factors used in the pathway calculations were consistent with values recommended by the Nuclear Regulatory Commission (NRC Regulatory Guide 1.109). The population distribution within 50 miles of the site was based f on census data as provided in the IMBR Program Environmental Impact Statement (ERDA 1541).
Furthermore, the air pathway calculation employed
[ site-specific meteorological and wind direction i data.
- 6. Results and Conclusions - Shippingport Atomic Power
- f. Station Evaluation of the radiation dose-to-man calculations for
[ the effluents show that the maximum annual radiation l exposure potentially received by an individual residing at the site boundary is less than 0.1 mrem. The maximum dose to an. individual is well below the 10CFR50 Appendix f I dose limits. Furthermore, the radiation exposure to the entire population of 4 million persons within 50 miles of the Shippingport Station was less than 1 person-rem.
This dose is negligible compared to the typical- annual dose of approximately 360,000 person-rem received by all individuals from typical oackground radiation.
f In conclusion, the radiation exposure received from the Shippingport Station during CY 1984 by any member of the general public is a very small fraction of the
{ background radiation and has, therefore, no significant effect on the general public.
1
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( DISTRIBUTION LIST .
United States Nuclear Regulatory Commission (18 copies)
Attn: Mr. Peter Tam, Project Manager
{- Operating Reactors Branch No. 1 Division of Licensing c/o Document Control Desk Washington, DC 20555 United States Nuclear Regulatory Commission (2 copies)
Office of Inspection and Enforcement Atta: Dr. Thomas E. Merley, Regional Administrator 631 Park Avenue King of Prussia, PA 19406 Mr. Nicholas DeBenedictis, Secretary Department of Environmental Resources f Commonwealth of Pennsylvania 9th Floor, Fulton Building Third and Locust Streets Box 2063
{ Harrisburg, PA 17120 Mr. C. K. Gaddis, Manager f Pittsburgh Naval Reactors Office Post Office Box 109 Pittsburgh, PA 15122-0109' Admiral K. R. McKee Deputy Assistant Secretary for Naval Reactors United States Department of Energy f Washington, DC 20585 Mr. D. E. Patterson, Director Division of Operational and Environmental Safety United States Department of Energy Washington, DC 20013
- f. Mr. J. J. Schrieber, Project Manager Shippingport Station Decommissioning Project Office U.S. Department of Energy P.O. Box 335 Shippingport, PA 15077 United States Department of Energy Headquarters Library Washington, DC 20013 United States Department of Energy Technical Information Center Post Office Box 62 Oak Ridge, TN 37830 s
DISTRIBUTION LIST (continued) .
'C. E. Ewing Manager, Quality Assurance l Duquesne Light Company Beaver Valley Power Station P.O. Box 186 i Shippingport, PA 15077 W. F. Wirth Director Radiological Safety Programs Duquesne Light Company ,
Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 4
i r
9
+
l 1
h s DISTRIBUTION LIST (continued)
_Mr. J. G. Yusko '
f Department of Environmental Resources Bureau of Radiation Protection 121 South Highland Avenue Pittsburgh, PA 15206 J.M. Arthur, Chairman of the Board and Chief Executive Officer f One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 J. J. Carey Vice President - Nuclear Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 E. J. Woolever Vice President, Nuclear Construction Division i Duquesne Light Company l One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 F. A. Cavalier Project Manager, Beaver Valley Power Station Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 J. D. Sisaer Manager, Nuclear Safety & Licensing Department P.O. Box 4 Shippingport, PA 15077 T..D. Jones
., Manager, Nuclear Operations Duquesne Light Company P.O. Box 4' Shippingport, PA 15077 ,
- i. S. L. Pernick Manager of Environmental Affairs Duquesne Light Company One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 W
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