ML20151Y647
| ML20151Y647 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ND3VPN:5448, NUDOCS 8805050060 | |
| Download: ML20151Y647 (126) | |
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1987 ANNUAL ENTIRON!! ENTAL REPORT RADIOLOGICAL - VOLU!!E n; DUQUESNE LIGliT C0!!PANY I
BEAVER VALLEY POWER STATION UNITS 1 AND 2 I
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DUQUESNE LIGHT COMPANY 1987 Annus1 Radiological Environmental Report
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EXECUTIVE
SUMMARY
This repert describes the Radiological Environmental Monitoring Program conducted during 1987 in the vicinity of the Beaver Valley Power Station Units 1 and 2.
The Radiological Environmental y
Program consists of off site monitoring of water,
- air, river sediments,
- soils, food pnhway samples, and radiation levels in the vicit.ity of the si-This report discusses the results of this monitoring durit I
Duquesne Light Company operates the Beaver Valley Power Station Units I and 2 pressurized wate-reactors as par-of the Central Area Power Coordination Group.
The beaver Valley Power Station Unit 1 operated throughout 1987 until the unit was shutdown on Decen.ber il, 1987 for the Sixth hefueling Outage.
The highest average daily output generated during the year was 629 rtegawatts net in July, 1967, and the total gross electrical generation during the year was 5,992,490 megawatt-hours.
I Eeaver Valley Powar Station Unit 2 achieved initial criticality on August 4,
19E*
with c ce.~ e r c i a l operation being declared on November 17, 1957 The highest average daily output generated during the year was 82e regawatts net in December, 1987, and the total gross electrical generation during the year was 782,200 megawatt-hours.
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DUQUESNE LIPHT COMPANY 1987 An..aal Radicalogical Environmental Report EXECUTIVE
SUMMARY
(continued)
In prior years, Duquesne Light Company conducted a joint environmental monitoring program for the Beaver Valley Power Station and the Shippingport Atomic Power Station. However, following issuance of the 1985 Annual Radiological Environmental
- Report, the joint program was discontinued, thus reference to the Shippingport Station has been deleted. See Section I, page 1 for specific detail.
Durang the year, the radioactive releases from BVPS Units 1 and 2 were below the limits of 10 CFR Part 50, Appendix I and did not exceed the Limiting Conditions for Operation identified in the Beceer Valley Power Station Operating License Technical
-1 Specifications for Units 1 and 2.
The maximum total body dose calculated for an individual from the Beaver Valley Power Station Units 1 and 2 releases in 1987 was less than 0.15 mrem which is less than l' of the BVPS Technical Specifications for Units 1 and 2 and 10 CFR Part 50, Appendix I annual limits.
See Section V.I for specific details. The NationaJ Academy of Sciences 1980 BEIR Report shows that the typical dose to an individual from natural
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radiation exposure is 101 mrem per year.
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DUQUESNE LIGHT COMPANY j
1987 Annual Radiological Environmental Report EXECUTIVE
SUMMARY
(continued)
The environmental monitoring program outlined in the Beaver Valley L
Power Station Units 1 and 2 Technical Specifications was followed throughout 1987.
The results for each media are contained in Section V of this report.
Examination of effluents and
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environmental media show that the Beaver Valley Power Station Units 1 and 2 operations have not adversely affected the surrounding environment.
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L DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report I
TABLE OF CONTENTS E
Page EXECUTIVE
SUMMARY
1 I.
INTRODUCTION-----------------------------------------------
1 I
A.
Scope and Objectives of the Program 2
B.
Description of the Beaver Valley Site 2
II.
RESULTS & CONCLUSIONS-------------------------------
7 I
III. ENVIRONMENTAL MONITORING CONSIDERATIONS--------------------
9 A.
Environmental Quality Control Programs 9
B.
Evaluation of the Quality Control (QC) Program Data 25 I
C.
Standard Requirements and Limitations for Radiological and Other Effluents 25 D.
Reporting Levels 26 IV.
MONITORING EFFLUENTS---------------------------------------
27 A.
Monitoring of Liquid Effluents 27 1.
Effluent Treatment, Sampling, and Analytical Procedures 33 2.
Results 33 B.
Monitoring of Airborne Effluents 34 1.
Description of Airborne Effluent S7urces 34 2.
Airborne Effluent Treatment and Sampling 38 3.
Results 42 I
C.
Solid Waste Disposal 43
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l DUQUESNE LIGHT COMPANY t
1987 Annual Radiological Environmental Report TABLE OF CONTENTS (Continued)
V.
ENVIRONMENTAL MONITORING PROGRAM Page
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A.
Environmental Radioactivity Monitoring Program 45 1.
Program Description 45 2.
Summary of Results 62 3.
Quality Control Program 62 B.
Air Monitoring 68 1.
Characterization of Air and Meteorology 68 2.
Air Sampling Program and Analytical Techniques 68 3.
Results and Conclusions 71 C.
Monitoring of Sediments and Soils 74 1.
Characterization of Stream Sediments and Soils 74 2.
Sampling Program and Analytical Techniques 74 3.
Results and Conclusions 76 D.
Monitoring of Feedcrops and Foodcrops 78 1.
Characterization of Vegetation and Foodcrops 78 2.
Sampling Program and Analytical Techniques 78 3.
Results and Conclusions 81 E.
Monitoring of Local Cow's Milk 83 1.
Description - Milch Animal Locations 83 2.
Sampling Program and Analytical Techniques 83 3.
Results and Conclusions 87 l
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DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
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TABLE OF CONTENTS (continued)
V.
ENVIRONMENTAL MONITORING PROGRAM (continued)
Page F.
Environmental Radiation Monitoring 89 1.
Description of Regional Background Radiation Levels and Sources 89 2.
Locations & Analytical Procedures 89 3.
Results and Conclusions 90 G.
Monitoring of Fish 97 1.
Description 97
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2.
Sampling Program and Analytical Techniques 97 3.
Results and Conclusions 97 H.
Monitoring of Surface, Drinking, Well Waters, and Precipitation 99 1.
Description of Water Sources 99 2.
Sa:r.pling Program and Analytical Technigres 100 3.
Results and Conclusions 103 I.
Estimates of Radiation Dose to Man 108 1.
Pathways to Man - Calculational Models 108 2.
Results of Calculated Radiation Dose to Man - Liquid Re'. cases 109 3.
Results of Calculated Radiation Dose to Man - Airborne Releases 112 4.
Conclusions - Beaver Valley Power Station 113 I
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DUQUESNE LIGHT C0!!PANY 1987 Annual Radiological Environmental Report
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LIST OF FIGURES Figure No.
Page i
1.0 View of the Beaver Valley Site 4
1.1 Geographical !!ap - 40 !!ile Radius 5
4.1 Liquid Discharge Points to Ohio River 28 1
4.2 Water Flow Schematic -
Beaver Valley Power Station Unit 1 29 4.3 Water Flow Schematic -
Beaver Valley Power Station Unit 2 30 4.4 Liquid Radwaste Systems Beaver Valley Power Station Unit 1 31 1
4.5 Liquid Radwaste Systems -
Beaver Valley Power Station Unit 2 32 4.6 Gaseous Waste Processing -
Beaver Valley Power Station Units 1 and 2 36 I
4.7 Gaseous Release Points -
Beaver Valley P..>wer Station Units 1 and 2 37 4.8 Solid Waste Disposal Diagram 44 5.B.1 Environmental ?!onitoring Locations - Air Sampling Stations 70 5.B.2 Concentrations of Gross Beta in Air Particulates 72 S.C.1 Environmental !!cnitoring Locations - Sediments 75 5.D.1 Environmental !!anitoring Locations - Feederop and Foodcrop 79 5.E.1 Dairy Farm Locations (August - September 1987 Survey) 85 5.E.2 Environmental ?!onitoring Locations - tillk 86 5.F.1 Environmental rionitoring Locations - TLDs 91 5.F.2 Environmental rionitoring Locations - TLDs 92 5.F.3 Environmental ifonitoring Locctions - TLDs 93 1
5.F.4 Environmental F!onitoring Locations - TLDs 94 5 F.5 Environmental Ficnitoring Locations - PICS 95 5.G.1 Environmental ?!onitoring Locations - Fish 96 5.H.1 Surface Water and Wells - Locations 102.
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L DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
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LIST OF TABLES Table F
Number Page III.1 Quality Control Data - TLD Comparicons 10 111.2 Quality Control Data - Watet Split Samples 11 III.3 Quality Control Data - Split Samples - Miscellaneous 13 III.4 Quality Control Data - Spikee Samples 17 III.5 Quality Control Data - Spike. Samples 18 III.6 Quality Control Data - Air Particulates and I-131 19 III.7 Quality Control Data - Milk and Water 23 IV.A.1 Ef fluent Treatmer.t, Sampling and Analytical Procedures Beaver Valley Power Station 33 IV.A.2 Results - Liquid Effluents - Beaver Valley Power Station 33 IV.B.1 Radioactive Gaseous Vaste Sampling and Analysis Program 40 V.A.1 Environmental Monitoring Program Summary 46 V.A.2 Environmental Monitoring Program Results (1987) 52 V.A.3 Pre-Operational Monitoring Program Results (1974-1975) 63 Y./.4 Typical LLDs for Gamma Spectrometry - DLC Contractor 67 V.D.1 Closest Residence and Garden in Each Sector 80 V.F.1 Pressurized Icn Chambers Results 96 V.I.1 Radiation Dose to Maximum Individual -
Beaver Valley Power Station - Liquid Releases 110 V.I.2 Results of Calculated Radiation Dose to Man - Beaver Valley Power Station -
Liquid Releases 111 V.I.3 Results of Calculated Radiation Dose to Man -
Beaver Valley Power Station - Airborne Releases 114 l
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N SECTION I DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report I.
INTRODUCTION The 1987 Annual Radiological Environmental Report for the Beaver Valley Power Station summarizes the radiological environmental e
L program conducted by the Duquesne Light Company in 1987.
In prior years Duquesne Light Company conducted a joint environmental monitoring progrcm for Beaver Valley Power Station and the Shippingport Atomic Power Station.
The Shippingport Atomic Power Station was permanently shutdown on October 1, 1982. Responsibility for the decommissioning of the I
Shippingport Atomic Power Station rests with the U.S. Department of Energy, Richland Operations Office.
General Electric was awarded the contract to conduct the decommissioning activity.
General Electric preselected Morrison-Knudsen as its integrated I
subcontractor.
General Electric assumed custody of the plant on September 6, 1984 and received permission to begin physical decommissioning on September 17, 1985.
Following issue of the 1985 Annual Radiological
- Report, the joint environmental
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monitoring program was discontinued. General Electric now conducts its own environmental monitoring program consistent with decommissioning requirements.
Therefore, reference to the I
Shippingport Atomic Power Station has been deleted from the 1987 annual report.
The Duquesne Light Company environmental monitoring program foe Beaver Valley Power Station will remain I
otherwise unchanged.
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StCT10s 1 DuqutSst ticar COMeAsv 1987 Annual Radiological Environmental Report I.
INTRODUCTION A.
Scope and Objectives of the Program The environmental program consists of environmental I
monitoring for radioactivity in the vicinity of the Beaver Valley Power Station. Environmental sampling and analyses included air, water, milk, soil, vegetation, river sediments,
- fish, and ambient radiation levels in areas surrounding the I
site.
B.
Description of the Beaver Valley Site The Beaver Valley Power Station is located on the south bank ef the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 501 acre tract of land.
Fig'tre i
1.0 is a view of the Beaver Valley Power Station.
The site is approximately one mile from Midland, Pennsylvania; 5 miles from East Liverpool, Ohio; and 25 miles from Pittsburgh, I
Figure 1.1 shows the site location in relation to the principal population centers.
Population density in the immediate vicinity of the site is relatively low. The i
population within a 5 mile radius of the plant is approximately 18,000 and the only area within that radius of concentrated population is the Borough of.
- Midland, Peinsylvania, 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 i
ridge along the border south of the Beaver Valley Power Station at an elevation of 1,160 feet.
Plant ground level is approximately 735 feet above sea level.
The Beaver Valley Power Station is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream f rom Montgomery Lock and Dam, and 1
19.4 miles upstream from New Cumberland Lock and Dam.
The Pennsylvania-Ohio-West Virginia border is located 5.2 river I
miles downstream from the site.
The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, p
Monongahela and Ohio Rivers and their tributaries.
Flow I
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.
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SECTION 1 DUQUESNE LIGHT CO.iPANY 1967 Annual Radiological Environmental Report
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I.
INTRODUCTION B.
Description of the Beaver Volley Site (continued)
Water temperature of the Ohio River varies f rom 32*F to 84*F, the minimum temperatures occur in January and/or February and roaximum temperatures in July and August. Water quality in the Ohio River at the site location is affected primarily by the water quality of the Allegheny, Monongahela, and Beaver rivers.
The climate of the area may be classified as humid continental.
Annual precipitation is approximately 36 inches, typical yearly temperatures vary from approximately -
3*F to 95 F with an annual average temperature of 52.8*F.
The predominant wind direction is typically from the southwest in summer and from the northwest in winter. -
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SECTION I DUQUESNE LIGHT CO>!PANY 1987 Annual Radiological Environmental Report I
1.
INTRODUCTION u
B.
Description of the Beaver Valley Site (continued)
IL The design ratings and basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below:
Beaver Valley Unit 1 Beaver Valley Unit 2 Thermal & Elec.
Rating (Net IN )
2660 FN 835 ?N 2660 IN 836 FN e
t e
t e
Type of Reactor FWR PWR No. of Reactor Coolant Loops 3
3 No. of Steam Generators 6 Type 3 - Vertical 3 - Vertical Steam Used by
?!ain Turbine Saturated Saturated I
The units utilize two separate systems (primary and secondary) for transferring heat from the source (the reactor:-
to the receiving component (turbine generator).
I 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 I
secondary system.
Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps.
Heat is given up from the primary I
system to the secondary system in the steara generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator.
The steam is condensed after passing through the turbine, and returned to the steam I
generators to begin another steam / water cycle.
megawatts thermal NOTE:
tN BN, megawatts electrical I
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L r-I SECTIOS II DUQUESSE LIGHT COMPANY 1987 Annual Radiological Environmental Report II.
RESULTS AND CONCLUSIONS Plant operations at the Beaver Valley Power Station had no adverse p
effects on the environment as a result of activity at the station L
during 1987.
The Beaver Valley Power Station Unit 1 operated throughout 1987 until the station was shutdown on December 11, 1987 for the Sixth Refueling Outage.
Beaver Valley Power Station Unit 2 achieved I
initial criticality on August 4, 1987 with commercial operation being declared on November 17, 1987.
During the year, the radioactive releases were below the limits of 10 CFR Part 50, I
Appendix 1.
The releases at Beaver Valley Power Station Units 1 and 2 did not exceed the limiting conditions identified in the Beaver Valley Power Station Units 1 and 2 Operating License Technical Specifications.
The environmental program for 1987 was the same as in 1986 except for several changes in dairy locations which were revised as I
required by the Beaver Valley Technical Specifications.
(Refer to Table V.A.1 for the 1987 Radiological Monitoring Program Outline).
I The Beaver Valley Power Station Technical Specifications require sampling of three (3) dairies which have the highest calculated milk pathway potential and one large local dairy. The three dairies are determined from calculations based on the I
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 I
revisions due to updated calculations and surveys normally result in sampling of several additional dairies during the year in different sampling periods.
The Environmental Monitoring Program also includes two larger dairies in order to provide continuity in the sampling / analyses program and a control location.
Samples from each of these I
dairies are obtained in addition to the four dairies required by the Environmental Technical Specifications.
The collection periods associated with each of the locations are provided in the I
detailed summary of the milk monitoring program of this report (Section V-E).
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i SECTION II DUQUESNE LIGHT C0!!PANY 1987 Annual Radiological Environmental Report II.
RESULTS AND CONCLUSIONS (continued)
Activity detected was attributable to naturally occurring
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radionuclides, CVPS effluents, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the lower limit of detection (LLD). The positive results attributable to the Beaver Valley Power Station were consistent with station data of authorized radioactive discharges and were within limits permitted by the NRC license.
The results and conclusions for each media of the 1987 Radiological Environmental !!onitoring Program are contained in I
Section V of this report.
A summary of the 1987 operational environmental data is four.d in Table V.A.2 and a summary of preoperational data (1974-1975) environmental data is found in Table V.A.3.
Examination of effluents from the Beaver Valley Power Station and environmental media demonstrated compliance with regulations and I
Station Technical Specifications.
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u SECTION III DUQUESNE LIGHT C0!!PANY 1987 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS A.
Environmental Quality Control Programs The Quality Control (QC) Program used for the Beaver Valley Environmental Radioactivity Monitoring Program consisted of seven (7) elements.
It should be noted that the comparisons made were at very low levels of radioactivity and consequently, the activities at these levels are difficult to I
measure. However, acceptable correlation was achieved in most instances as outlined in the discussions and tables which follow.
1.
TLD Monitoring (Duquesne Light Company (DLC) Contractor Laboratory and QC Laboratory)
Thirteen (13) TLDs from the Contractor Laboratory and QC Laboratory are co-located, replaced quarterly and results compared.
The average of the contractor I
laboratory and the average of the quality control laboratory agree within 6. l*.
of the mean of all results. This is well within the precision of typical TLD Systems.
Summary data of the TLD Monitoring Program is provided in Table 111.1.
2.
Split Sample Program (DLC Contractor Laboratory - DLC QC I
Laboratory)
Samples of surface (river) water and drinking water were I
routinely split and analyzed by the DLC Contractor Laboratory and the DLC QC Laboratory.
In addition, samples of other media, such as milk, soil, sediment and feedcrop were also split with the DLC QC Laboratory.
A summary of results of split water samples is provided in Table III.2.
A summary of milk, sediment and I
feed / food crop split samples is provided in Table 111.3.
Some variation is expected due to small variations in duplicate samples, variations in analytical procedures, and in calibration, source type, etc.
Because of the overall uniformity of comparable results, it is concluded that the two laboratories are consistent and in agreement.
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L, Section 111 DUQUESNE LIGHT COMPANY TABLE III.1 1987 Annual Radiological Environm2ntal Report L
TABLE !!!.1 E
QUALITY CONTROL RESULTS I
TLD MONITORING rnR/ Day IST OUARTER 2ND QUARTER DLC DLC OLC QC OLC QC Location Contractor Lab Location Centractor Lab No.
(CaS0 :0y)
(CaSO gDy) ho.
(C,50 g 0y)
(CaSO,:Dy) 3 10 0.18 0.20 10 0.16 0.2i 13 0.16 0.17 13 0.15 0.17 14 0.17 0.17 14 0.15 0.18 15 0.14 0.14 15 0.13 0.15 27 0.18 0.17 27 0.15 0.20 28 0.18 0.19 28 0.18 0.20 293 0.21 0.23 29B 0.19 0.23 32 0.19 0.21 32 0.15 0.21 I
45 0.17 0.20 45 0.19 0.23 46 0.16 0.15 46 0.14 0.14 47 0.20 0.20 47 0.18 0.23 I
48 0.18 0.18 48 0.17 0.21 51 0.19 0.18 51 0.18 0.20 I
3RD QUARTER 4TH QUARTER I
DLC DLC DLC OC DLC OC E
Location Contractor Lab Location Contractor Lab g
No.
(CaSO.:0y)
(CaS0 :0y) ho.
(CaS0 :Dy)
(CaS0 :0y) 3 3
3 10 0.16 0.20 10 0.17 1
13 J.17 0.18 13 0.16 0.17 14 0.17 0.18 14 0.16 0.17 15 v.14 0.14 15 0.13 0.20 1
27 0.17 0.17 27 0.16 0.20 28 0.18 0.19 28 0.17 0.20 293 U.11 0.22 293 0.20 0.22 32 0.16 0.20 32 0.18 0.22 45 0.18 0.20 45 0.18 0.22 46 J.16 0.16 46 0.15 0.15 4'i v.ld 0.19 47 0.20 0.22 45 0.15 0.20 48 0.16 0.20 51 0.18 0.18 51 0.17 0.20 I
Lc:t er Damaged I I t
a Section 111 DUQUESNE LIGHT COMPANY TABLE Ill.2 1987 Annual Radiological Environmental Report (Page 1 of 2)
TABLE 111.2 QUALITY CONTROL RESULTS SPLIT SAMPLE MALYSIS RESULTS Comparison of Contractor and DLC-0C Labs s
DLC Contractor DLC - QC Media Analysis Samplina period Lab (1)
Lab-(l)
Units Surface Water Gross Alpha January I l.7 10.7 pC1/1 April 11.9 10.9 pCi/l July 11.7 1 0.6 pCi/l October 11.7 11.0 pCi/l Surface Water Gross Beta January 7.1 + 1.8 2.5 + 0.8 pCi/l April 5.2 + 1.4 4.2 + 1.2 pCi/1 JJly 8.4 + 1.5 3.3 + 0.9 pC1/1 Octcber 43 + 3 59.2 + 6.3 pCi/l 5;rface Water Co-60 January
< 4.0
< 0. 8 pCi/l April 15.0 10.7 pCi/l July 13.0 10.8 pti/l October 8.9 - 2.3 10.4 + 2.4 pCi/l i
Surface Water Cs-134 January 13.0 10.6 pCi/l April 16.0 10.8 pCi/l Jsly 13.0 10.8 pC1/1 i
October 1 4.0 1 1.7 pCi/l Sarface Water Cs-137 January 1 4.0 10.7 pCi/l April 16.0 1 0.7 pCi/l i
July 1 4.0 1 0.8 pCi/1 October 1 4.0 1 1.6 pCi/l l
Sarfste Water Tritium ist Quarter 3
Composite 440 + 220 128 + 82 p01/1 3rd Quarter Composite 14000 1 1000 14200 1 233 pC1/1 Sarface Water Sr-89 2nd Quarter Composite
< 2.0
< 0.3 pCi/1 4th Quarter I
Sarface Water Composite 5 2.0 10.2 pC1/1 Sr-90 2nd Quarter Composite 1 0.48 1 0.3 pC1/1 4tn Quarter I
Co posite
< 0.49 1 0.2 pCi/1 5;rface 'nater Co-50 2r.d Quarter (high Composite
< 0.9
< 0.8 pC1/1 I
sensitivit/
4th Quarter analysis)
Composite 3.19 _+ 0.94 3.72.+. 1.71 pCi/l I
(1) t.ncertairties are cased on counting statistics and are specified at the 95% confidence interval. !
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. TABLE !!!.2 L.
-1987 Annual Radiological Environmental Report (Page2of2) f 1ABLE 111.2 (Coatinued)
QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs lg DLC F
Contractor DLC - QC b.
Media Analysis Samplino Period Lab (1)
Lab (1)
Units Orinking Water Cs-137 february' 1 5.0 1~0.4 pC1/1 (weekly split)
May 1 5.0 1 0.8 pCi/1 August i 6.0 1 0.8 pC1/1 hovember 1 4.0 1-1.2 pCi/1 F
Drinking Water Cs-134 February 1 5.0 1 0.4 pC1/1 h
(weekly split)
Pay 1 5.0 1 0.8 pCi/1 August 1 5.0 1 0.8 pCi/1 November 1 4.0 1 1.1 pCi/1 Orinking Water Co 60 February 1 5.0 1 0.4 pCi/1
- (weekly split)
May 1 5.0 1 0.8 pC1/1 b
August 15.0 1 0.8 pCi/1 L
hovember 1 4.0 11.3 pCi/1 Orinking Water Gross Alpha March 1 1.6 1 0.5 pC1/1 (montnly composite)
June 1 1.4 1 0.5 pCi/1 August i 1.5 1 0.6 pCi/1 November 11.1 10.5 pCi/1 Drinking Water Gross Beta March 3.41 1
1.7 1 0.8 pC1/1 1
(monthly composite)
June 3.6 36 2.2 1 0.9 pC1/1 0
August 5.5 + 1.3 3.2 + 1.0 pC1/1 November 2.4 f 1.0 2.9 2 0.8 pCi/1 Orinking Water Tritium 2nd Quarter 1 100 1 65 pC1/1 4th Quarter 1 100 169 ; 74 pC1/1
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(1) Uncertateties are based en counting statistics and are specified at the 951 confidence interval. F
Section 111 DUQUESNE LIGHT COMPANY TABLE !!!.3 4
1987 Annual Radiological Environmental Report (Page 1 of 2)
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TABLE !!!.3 L
QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS P
Comparison of Contractor and OLC-0C Labs b
DLC Contractor DLC - QC r
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Media Sampling Period
' Analysis.
Lab (1)
Lab (1)
Units Milk 3-23 87 Sr-89 1 1.2 1 0.3 pC1/1 (Location 25) 3-23-87 Sr-90 2.1 + 0.6 2.8 + 0.6 pC1/1 3-23-87 1-131 1 0.28 1 0.1 pCi/1 3-23-87 K-40 1350 1 140 1300 1 50 pCi/1 J-23 87 Co-60 1 4.0 1 0.9 pCi/1 7
3-23-87 Cs-134 14.0 1 0.7 pCi/1 3-23-87 Cs-137 1 5.0 1 1.0 pCi/1 Milk 6-23-87 1-131 1 0.039 1 0.09 pCi /1 (Locatien 25) 6 23 87 Cs-134 1 0.06 1 0.9 pC1/1 6-23-87 Cs-137 1 0.04 1 0.9 pCi /1 6-23-87 Co 60 1 0.05 1 1.0 pCi/1 6-23 87 K 40 1290 + 130 1280 + 60 pC1/1 Feed 6-23-87 1-131 1 0.03 1 0.021 pCi/gm (dry)
(Location 25) 6 23 87 Be-7 1.85 + 0.41 1.47 0.33 pCi/gm (dry) 6-23 87 K-40 18.3 + 1.8 16.3 + 1.4 pCi/gm (dry) 6 23 87 Co 60 1 0.05 1 0.023 pCi/gm (dry) 6 23-87 Cs-134 1 0.06 1 0.021 pC1/gm (dry) 5 23 87 C5-137 1 0.05 1 0.021 pCi/gm (dry)
Feed 3 015 pCi/gm (dry)
(Location 25) 62387 Sr-90 0.181 02 0.038 0
0 Food 9 10-87 1-131 1 0.005 1 0.005 pCi/gm (wet)
(Location 10) 9 10 87 K-40 2.96 + 0.3 1.62 + 0.21 pCi/gm (wet) g.10 87 Co 60 1 0.01 1 0.006 pCi/gm (wet) 9 10-87 Cs-134 1 0.01 1 0.004 pC1/gm (wet) 9 10 87 Cs-137 1 0.01 1 0.004 pC1/gm (wet) 1 02 0.14 1 0.03 pCi/gm (dry)
J Feed 9 21-87 Sr-90 0.21 0
(Location 25)
M (1) Uncertainties are based on counting statistics and are specified at the 95% confidence interval.
E8"M F
n t
- Section til CUQUESNE LIGHT COMPAN7 TABLE !!I.3
[
1987 Annual Radiological Environmental Report (Page 2 of 2)
TABLE !!!.3 (Continued)
QUALITY CONTROL RESULTS SPLIT SAMPLE ANALYSIS RESULTS Comparison of Contractor and DLC-0C Labs 7
L-DLC Contractor DLC - QC Media Sartpling Period Analysis Lab (1)
Lab (1)
Units Milk 9-21 87 I-131 1 0.32 1 0.1 pct /1 (Lo:ation 25) 9-21 87 Sr-39 1 2.0 1 0.2 pC1/1 9 21-87 Sr-90 3.7 + 0.8 3.7 + 0.6 pCi/1 9 21-87 Cs-134 1 5.0 1 0.6 pCi/1 9-21-87 Cs-137 1 4.0 1 0.9 pCi/1 9-21-87 Co 60 1 4.0 1 0.9 pCi/1 9-21-87 K-40 1350 1 130 1260 + 60 pC1/1
~
Sediment 10-29-87 Gross Alpha 20 + 8 10.6 + 3.1 pCi/gm (dry)
(Location 2A) 10-29-87 Gross Beta 32 + 3 24.8 + 2.4 pCi/gm (dry) 10-29 87 Sr-89 1 0.19 1 0.01 pC1/ga (dry) 10 29 87 Sr 90 1 0.048 0.049 1 0.011 pC1/gm (dry)
~
10-29 87 Co-58 11.0
. ti/gm (dry) 11 10.9 + 0.2 1
p 10-29 87 Co-60 4.69 + 0.47 4.17 + 0.14 pCi/gm (dry)-
10 29-87
.Cs-134 1 0.1 1 0.04 pC1/gm (dry) t0 29 87 Cs 137 0.414 1 0.093 0.39 + 0.06 pC1/gm (dry) 1 09 1 0.03 pCi/ge (dry) 10 29 87 Mn 54 0.172 0
10 29 87 K-40 12.7 1 3
10.3 1 0.7 pC1/gm (dry) 1 10 29 87 Au 226 2.88 + 1.25 2.29 + 0.7 pCi/gm (dry) 1 13 0.44 1 0.06 pCi/ge (dry) 10 29-87 Th-228 1.26 0
Milk 12-14 87 I-131
< 0.24
< 0.1 pC1/1 (Location 25) 12-14 87 Cs 134 1 4.0 1 0.7 pCi/1 12-14 87 Cs-137 1 4.0 1 0.8 pC1/1 12 14 87 Co-60 1 4.0 1 0.8 pCi/1 12 14 87 K 40 1410 + 140 1259 + 57 pC1/1 (1) Uncertainties are based on Counting statistics and are specified at the 951 confidence interval, s
m M
N i r
SECTION III DUQUESNE LIGHT CO3!PANY 1987 Annual Radiological Environmental Report III.
ENVIRON!! ENTAL ?!ONITORING PROGRA>!S A.
Environmental Quality Control Programs (continued)
P 3.
DLC QC Laboratory Program Spiked samples prepared by DLC QC Laboratory were routinely submitted to the Contractor Laboratory for analysis. Tables III.4 (water) and III.5 (milk) provide I
data from this portion of the QC Program.
The overall results demonstrate that the contractor performed acceptably in the program.
I 4
Comparisons of Similar Samples (DLC Contractor Laboratory - DLC QC Laboratory]
Duplicate air particulate and charcoal filters (radioiodine) samples were collected at Location #30 and compared during the year on a weekly basis.
Comparison I
of particulate and charcoal samples alternated from week to week Duplicate monthly air particulate filters, composited from the weekly air particulate filters, were I
analyzed ti months out of the year for gamma activity.
Duplicate quarterly air particulate filters, composited from the weekly air particulate filters, were analyzed for Sr-69 and Sr-90 activity for each quarter of the I
year. Table III.6 provides data for this portion of the QC program. The results show generally good agreement between the laboratories and decanstrate that the contractor performed acceptably in the program.
5.
Contractor Internal QC Program The Contractor Laboratory maintained its own QC Program which included participation in the Environmental Environmental !!onitoring Safety Protection Agency i
Interlaboratory Cross Check Program.
This cross check program indicated that the Contractor results were in agreement with EPA E!!SL. DLC I
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.
I I
l SECTION III DUQUESNE LIGHT CO.'!PANY 1987 Annual Radiological Environmental Report III. ENVIRONMENTAL MONITORING CONSIDERATIONS A.
Environmental Quality Control Programs (continued) l l
6.
Special QC Program (DLC Contractor Laboratory -
Independent Laboratory - DLC QC Laboratory)
Milk and water samples were prepared quarterly by an Independent Laboratory. This included low leyel spiking of specified nuclides. The prepared samples were split three ways and analyzed by the DLC-QC Laboratory and Independent Laboratory as well as the Contractor Laboratory.
A summary of results of this portion of the QC program l
is provided in Table III.7.
The results show generally p
good agreement between the laboratories and demonstrate that the contractor performed acceptably in the program.
I l
l l
l l
I I
I I
Section !!!
DUQUESNE LIGHT COMPANY TABLE !!!.4 1987 Annual Radiological Environmental Report TABLE 111.4 QUALITY CONTROL RESULTS SPIKE SAMPLE ANALYSIS RESULTS Sample Type DLC and Contractor DLC - QC Sample Date Ident. No.
Aralysis Lab (1)
Lab (1)
Units 12-20-86 W 22 Water: Gross Alpha 17 1 2 9.8 1 1.4 pCi/1 Gross Beta 27 1 2 21.7 1 2.0 pCi/l 1-Ot-87 W-23 Water: 1-131 25 1 1 29.8 1 2.5 pCi/1 3 30-87 W-24 Water: Sr-89 21 + 3 24.7 + 3.6 pCi/l Sr-90 26 1 1 23.9 1 3.8 pCi/1 4-30-87 W-25 Water: 1-131 25 + 1 28.0 + 1.9 pCi/l 4-30-87 W-26 Water: Co-60 25.5 + 2.6 24.8
- 1.4 p01/1 Cs-137 22.5 + 2.3 21.2 + 0.5 pC1/1 H-3 2900 + 100 3422 + 100 pCi/I 6 30 87 W 27 Water: Gross Alpha 15 + 2 8.5 1 1.9 pCi/1 Gross Beta 26 + 2 22.5 + 1.9 pC1/1 6-30-87 W-28 Water: Gross Alpha 13 + 2 8.7 + 1.3 pC1/1 Gros Beta 13 + 1 12.2 + 5.2 pCi/1 6 30-87 W 29 Water: Gross Alpha 29 1 3 16.4 + 1.3 pC1/1 Gross Beta 16 + 1 15.9 + 4.0 pCi/l 9 30 87 W 30 Water: Sr-89 20 + 2 17.5 + 3.0 pCi/1 Sr-90 19 + 1 18'.4 + 2.2 pCi/1 10-26 S7 W-31 water: H-3 3100 + 100 2053 + 93 pC1/1 (1) Uncertainties are based en counting statistics and are specified at the 957 confidence interval.
M
~
17 I
Section !!!
DUQUESNE LIGHT COMPANY VA8LE III.5 7
1987 Annual Radiological Environmental Report
-).
TABLE 111.5 QUALITY CONTROL RESULTS SP!KE SAMPLE ANALYSIS Sample Type DLC m
and Contractor DLC - QC Sa-ple Date Ident. No.
Analysis Lab (1)
Lab (1)
Uni ts l_
1-05-87
- Ml-12 Milk: 1-131 30 + 1 36.5 + 1.3 pC1/1 K-40 1250 + 130 1330 + 120 pCi/1 F
Cs-137 29.9.+. 4.7 32.6.+. 4.2 pCi/1
. 1-09-87 Mi-13 Milk: Sr-89 10 + 5 10.4 + 2.1 pC1/1 Sr-90 15 + 1 14.6 + 1.6 pCi/1 K-40 1280 + 130 1390 + 20 pC1/1 1 131 39 + 2 49.5 + 1.2 pC1/1 Cs-137 32.1 + 4.9 33.3 + 0.6 pC1/1 4-30-87 M1-14 Milk: 1-131 22 + 1 25.0 + 2.2 pCi/1 K-40 1280 + 130 1250 + 50 pC1/1 Cs-137 26.1 + 4.3 34.2 + 2.0 pC1/1 7-02-87 Mi 15 Milk: Sr-90 21 + 1 19.4 1 6 pC1/1 1
K 40 1310 + 130 1220 + 80 pCi/1 1-131 49 + 2 43.5 + 0.7 pCi/1 12 pC1/1 Cs-134 21.1 2 3.3 17.9 2
Cs-137 31.9 + 4.6 25.4 + 1.8
.pci/1 E
E E
(1) Uncertainties are cased on counting statistics and are specified at the 951 confidence interval.
[
-18 F
l
Section til DUQUESNE LIGHT COMPANY TABLE 111.6 1987 Annual Radiological Environmental Report (Page 1 of 4)
TABLE 111.6 OVAllTY CONTROL RESULTS AIR PARTICULATES AND CHARCOAL FILTER: COMPARABLE SAMPLES Air Particulate, Air lodine pC1/Cu Meter (Beta)
PCi/Cu. Meter DLC DLC Contractor DLC - QC Contractor OLC - QC
~
Saaple Date Lab (1)
Lab (1)
Sample Date lab (1)
Lab (1) 12-29-86 to 0.023 + 0.003 0.033 + 0.004 1-05-87 to 1 0.02 1 0.03 1-05-87 1-12-87 1-12 87 to 0.020 + 0.004 0.022 + 0.003 1-19-87 to 1 0.02 1 0.03 1-19-87 1-26-87 g
1-26-87 to 0.022 + 0.003 0.026 + 0.004 2-02-87 to 1 0.02 1 0.03 m
2-02 87 2-09 87 0.02 1 0.03 2-17-87 0.021 + 0.003 2-17-87 to 2-03-87 to 0.022 + 0.003 2-23-87 2-23-87 to 0.015 + 0.003 0.017 + 0.004 3 02-87 to 1 0.02 1 0.03 3 02 67 3-09 87 3-09-87 to 0.019 + 0.003 0.022 + 0.003 3-16-87 to 1 0.02 1 0.03 3-16 87 3-23-87 3 23-87 to 0.017 + 0.003 0.012 + 0.003 3 30-87 to 1 0.02 1 0.03 3-30-87 4-06-87 4 06-87 to 0.012 + 0.003 0.012 + 0.003 4-13-87 to 1 0.02 1 0.03 4-13 87 4 20-87 0.02 1 0.03 4 20-87 to 0.013 + 0.003 0.021 + 0.004 4-27-87 to
(
4 27 87 5 04-87
~
5-11 87 0.013 + 0.004 5-11-87 to 1 0.02 1 0.03 5-04 87 to 0.019 + 0.004 5 18-87
~
5 18-87 to 0.011 + 0.003 0.014 + 0.003 5-26-87 to 1 0.02 1 0.03 5 26-87 6-01 8/
6 01-87 to 0.016 + 0.003 0.020 + 0.004 6-08-87 to 1 0.02 1 0.03 6-08-87 6-15-87 6-15 87 to 0.021 + 0.003 0.021 + 0.003 6-22-87 to 1 0.02 1 0.03 6 22 87 6-29 87 s
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Section !!!
DUQUESNE LIGHT COMPANY TABLE !!I.6 1987 Annual Radiological Environmental Report (Page 2 of 4)
TABLE 111.6 (Continued)
L QUALITY CONTROL RESULTS AIR PARTICULATES AND CHARC0AL FILTl[R: COMPARABLE SAMPLES Air Particulate, Air lodine pC1/Cu. Meter (Beta) pCi/Cu. Meter I
DLC OLC Contractor DLC - OC Contractor OLC - QC Sample Date Lab (1)
Lab (1)
Sarole Date lab (1)
Lab (1)
I 0.03 0.02 6-79-87 to 0.017 + 0.003 0.015 + 0.003 7-06-87 to 7-06-87 7-13-87 7-13-87 to 0.019 + 0.002 0.024 + 0.003 7-20-87 to 10.02 1 0.03 I
7-20 87 7-27-87 8-03-87 0.025 + 0.004 8-03-87 to 10.U2 1 0.03 7-27-87 to 0.027 + 0.003 8 10-87 I
8-10-87 to 0.C20 + 0.003 0.026 + 0.004 8-17-87 to 10.02 1 0.03 8-17 87 8-24-87 8-24-87 to 0.017 + 0.003 0.019 + 0.003 8-31-87 to 10.02 1 0.05 B 31-87 9-08-87 I
9-08-87 to 0.030 + 0.004 0.033 + 0.003 9-14-87 to 1 0.02 1 0.01 9 14-87 9-21-87 9-21-87 to 0.022 + 0.003 0.026 + 0.003 9-28-87 to 10.02 1 0.04 I
9 28-87 10-05-87 10-05-87 to 0.015 + 0.003 0.020 + 0.003 10 13 87 to 10.02 1 0.01 10 13-87 10-19 87 10-19-87 to 0.026 + 0.004 0.029 + 0.004 10-26-87 to 1 0.02 1 0.01 10-26 87 11-02 87 11-02 87 to 0.040 + 0.004 0.040 + 0.004 11-09-87 to 1 0.02 1 0.01 11-09 87 11 16-87 1
11-16-87 to 0.019 + 0.003 0.019 + 0.003 11 23-87 to 10.01 1 0.01 11-23 87 11-30 87 11-30-87 to 0.011 + 0.003 0.016 + 0.003 12-07 87 to
< 0.02
' O.01 1
12 07-87 12 14-87 12-I4 87 to 0.015 + 0.003 0.014 + 0.003 12-21 87 to 0.01 0.01 12 21 87 12 29 87 I
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l I
Section Ill DUQUESNE LIGHT COMPANY TABLE III.6 1987 Annual Radiological Environmental Report (Page 3 of 4)
TABLE !!t.6 0UALITY CON 1ROL 3
AIR PARTICULATES (DCi/r )
OLC Contractor OLC - QC 5.mple Date Nuclide Lab (1)
Lab (1)
January Be-7 0.107 1 0.014 0.081 1 0.015 e,
K-40 0.011 1 0.006 LLO
~
Otners LLD LLD M.rch Be-7 0.163 + 0.019 0.125 + 0.022
- Cther, LLD LLD May Be-7 0.176 + 0.021 0.100 + 0.018
- Other, LLD LLD Septener Ee-7 0.140 1 0.018 0.128 + 0.067
- Otrer, LLO LLO Acvember Be-7 0.101 1 0.014 0.172 1 0.045
- Other, LLD LLD
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Section !!!
00')UESNE LIGHT COMPANY TABLE 111.6 1987 Annual Radiological Environtnental Report (Page 4 of 4)
TABLE 111.6 QUALITY CONTROL AIR PARTICULATE AND CHARC0AL FILTER 3)OMPARABLE SAMPLCS C
LOCATION 30 - (DC1/e OLC Contractor DLC - OC Sample Date hu:lide Lab (1)
_L,,,.3,,( 1,1 I
1.t 0;.rter Corpe,ite Sr 89 1 0.0012 1 0.0001 Sr 90 1 0.0003 1 0.0001 2r4 Quarter Cerca,ite Sr 89 1 0.0013 1 0.0002 Sr-90 1 0.0002 1 0.0002 3rd Quarter Co.mpo,ite Sr-89 1 0.0014 1 0.0002 g
g Sr-9) 1 0.0002 1 0.0002 4tn Qu.rter Corpe,ite Sr-89 1 0.0009 1 's.0003 Sr-90 1 0.0002 1 0.0003 1
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Section !!!
DUQ'JESNE LIGHT COMPANY TABLE !!!.7 l
1987 Annual Radiological Environ:nental Report (Page 1 of 2) s e
TABLE !!!.7 L
QUAllW CONTROL DATA QC Sample Comparisons (All Analyses in DCi/1)
Sample Type DLC and independent Contractor DLC - Q*
Sample Cate Ident. No.
Analyses y _(1)
Lab (1)
Lab (1) 2-05-87 53 279 Water: br 89 23 + 2 21 + 2 23.1 + 2.7 Sr 90 18.7 + 0.5 16 + 1 16.3 + 2.0 1-131 20 + 1 15 + 1 23.7 + 1.2 Mn-54 16 + 3 22.2 + 4.7 21.7 + 1.8 Cs 137 29.9 + 1.4 25.5 + 4.9 33.3 + 1.3 2-06-87 53-280 Water:
H-3 1440 + 140 1440 + 100 1460 + 120 5-05-87 53-261 Water: Sr-89 19.9 + 1.2 17 + 2 11.6 + 1.1 Sr-90 12.8 + 0.4 15 + 1 10.9 + 1.2 2.8 + 0.2 3.5 + 0.6 1-131 Co-58 14.3 + 5.4 15.1 + 4.4 16.0 + 2.3 Co 60 10.7 ; 5.5 13.2 + 4.5 10.6 + 2.0 2 27 1100 2 100 1170 3 170 1
5 05 87 53 282 Water:
H-3 947 8-05 27 53-283 Water: Sc-89 25 + 2 18 + 1 17.1 + 6.9 Sr-90 23.7 + 0. 6 21 + 1 19.8 + 2.9 27 1
l-131 10.8 1 0.6 11 2 1 11.3 Cs 134 19 + 3 18.5 + 2.6 18.3 + 3.4 Cs-13i 19 + 3 18.5 + 3.9 19.7 + 4.0 2-07-87 53-284 Water: H-3 520 + 110 480 + 100 538 + 29 11-30-87 53-285 Water: Sr-89 11 + 2 11 + 2 9.7 + 1.7 Sr 90 12.5 + 0.6 11 + 2 9.7 + 0.6 1-131 18 + 4 22 + 1 23.2 + 1.4 Co E0 14 + 3 18.1 + 4.0 16.6 + 2.7 Cs-137 11 2 3 18.5 2 3.7 18.3 2 0.9 11-30-87 53-285 Water: H-3 3580 + 140 4800 + 1000 4068 + 84
- l-131 wet lest in cre-istry (11 U.certairties are based en ccanting statistics and are specified at the 951 conficence interval.
.'3-i
Section til DJOUESNE LIGHT COMPANY TABLE 111.7 1987 Annual Radiological Environmental Report (Page2of2)
TABLE !!!.7 00ALITY CONTROL DATA QC Sample Comparisons (AllAnalysesinDCif,,1,1 s
l Sample Type DLC B
and Independent Contractor OLC - OC S rple Date Ident. No.
Analyses Lab (1)
Lab (1)
Lat fil 2-05 87 52-242 Milk: Sr-89 12 + 2 6.2 + 1.5 5.2 + 3.0 Sr-90 11.2 + 0.5 9.7 + 1.2 14.4 + 4.1 1-131 13 + 1 12 + 1 15.0 + 0.8 16[8 11.4+5.0 9.9 3.4 Cs-134 Cs-137 16 1 4 14.6 1 6.6 14.6 + 0.2 K 40 1200 + B0 1260 + 130 1280 + 40 I
E-05-87 52-243 Milk: Sr-89 17.9 + 1.2 20 + 2 24.9 + 1.5 Sr-90 15.5 + 0.4 28 + 2 20.9 + 4.9 4.0 + 0.2 5.4 + 0.3 1-131
+
Cs-134 17.1 + 3.0 17.9 + 4.5 15.6 + 2.3 Cs-137 17.4 + 3.1 19.1 + 4.0 21.1 + 3.3 K-40 1260 + 80 1200 + 120 1250 + 70 8-05-87 52-244 Milk: Sr-89 16 + 4 10 + 3 8.6 + 1.6 Sr-90 17.9 + 0.5 16 + 1 16.1 + 1.1 I
1-131 9+2 10 + 1 10.7 + 2.2 Cs 134 18 + 3 16.9 + 5.1 20.7 + 4.6 I
Cs-137 23 1 3 16.81 5
22.0 1 2.0 4
K 40 1150 + 80 1170 + 120 1190 + 90 11 30-87 52-245 Milk: Sr-89 15 + 3 13 + 1 10.5 + 2.2 13f1 12.3[0.4
$r-90 16.8 + 0.6 1-131 16 + 5 17 + 1 Cs-134 10 + ;
8.0 + 0.5 8.9 + 1.9 I
Cs-137 14 + 3 17.2 + 4.6 17.6 + 1.3 K 40 1120 + 80 1250 + 130 1225 + 37 l
l l-131 =as lost in chemistry
" Not analyzed - insufficient sa ple for both strontium and iodine analyses.
(1) Uncertainties are based on coseting statistics and are specified at the 95% conficence interval. _
SECTIOS III DUQUESSE LIGHT COMPANY 1987 Annual Radiological Environmental Report 111. ENVIRONMENTAL MONITORING PROGRAM A.
Environmental Quality Control Programs (continued) e 7.
Pennsylvania Department of Environmental Resources Program The Pennsylvania Department of Environmental Resources (PDER) also conducted a surveillance program in the I
vicinity of the site.
Samples of air, river water, drinking water, sediment, milk, vegetation, fish and radiation monitoring are included in their program.
Comparison of results also indicated agreement between the PDER Laboratory and the Duquesne Ligit Company Contractor Laboratory.
B.
Evaluation of the Quality Control (QC) Program Data The split and spiked sample program indicates that the I
Contractor and QC Laboratory are generally performing satisfactorily in accordance with "Criteria for Comparing Analytical Measurements from SRC Compliance Office."
In I
addition, an independent laboratory is used to supplement the regular program.
Comparisons between the independent, QC and Contractor laboratories are acceptable and demonstrate a satisfactory performance by the DLC contractor.
Based on all available QC data and the data from the Contractor's internal EPA Interlaboratory Cross Check Program, the Environmental Monitoring Program for 1967 is acceptable with respect to both accuracy and measurement.
C.
Standard Reauirements and Limitations for Radiological and I
Other Effluents The Beaver Valley Power Station is governed by rules and I
regulations of the Federal C-overnment and the Commonwealth of fennsylvania.
Effluent releases are controlled to ensure that limits set by Federal or State governments are not I
exceeded.
In
- addition, self-imposed limits have been established to further limit discharges to the environment. _______ __-__
l SECTION III DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report III. E_SVIRONMENTAL MONITORING PROGRAM C.
Standard Requirements and Limitations for Radiological and Other Effluents (continued) l Beaver Valley Power Station is subject to regulations which I
include the Code of Federal Regulations 10 CFR (Energy),
Pennsylvania Department of Environmental Resources (PDER)
Industrial Waste Permit 90473211, Gaseous Discharge Permit I
(204-306 001, PA Code - Title 24, Part I, Ohio River Valley Water Sanitation Commission (ORSANCO) Standards No. 1-70 and 2-70, Environmenti.1 Protection Agency (EPA), National Pollution Discharge Elimination (NPDES) Permit (t0025615, and the Beaver Valley Power Station Technical Specificar. ions.
D.
Reporting Levels a
report is required to be submitted to the Nuclear Regulatory Commission when the level of radioactivity in an i
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 I
of the radionuclides are detected in the sampling medium, this report shall be submitted if:
Concentration (1)
Concentration (2)
.2 1.0 I
Limit Level (1)
Limit Level (2)
There were no analytical results of environmental samples I
during 1987 which exceeded Beaver Valley Power Station reporting levels.
2e-
~
l SECTION IV DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report IV.
MONITORING EFFLUENTS A.
Monitoring of Liquid Effluents Description of Liquid Effluents at the Beaver Val'ey Power Station.
Most of the water required for the operation of the Beaver Valley station is taken from the Ohio River, and returned to the river, used for makeup to various plant systems, consumed by station personnel, or discharged via a sanitary waste system.
In addition, small amounts of well water and liquid effluents are discharged to the Ohio River using discharge points shown in Figure 4.1.
Figures 4.2, 4.3, 4.4 and 4.5 are schematic diagrams of liquid flow paths for the Beaver Valley Power Station. The following two (2) tables summarize radioactive liquid effluents at the Beaver Valley Power Station:
Table IV.A.1 - Effluent Treatment, Sampling, and Analytical Procedures - Beaver Valley Table IV.A.2 - Results of Liquid Effluent Discharges to the Environment - Beaver Valley I
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1" SECTION IV FIGURE 4.3 DUQUESNE LIGHT COMPANY
[
1987 Annual Radiological Environmental Report
~l ja!! %)
FIGURE 4.3
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FIGURE 4.5 BVPS-2 1.10VID WASTE SYSTEM u,
l 6
SECTION IV DUQUESNE LIGHT C051PANY 1987 Annual Radiological Environmental Report TABLE IV.A.1 L_
l.
Effluent Treatment, Sampling and Analytical Procedures - Beaver Valley Treatment, Sampling Standard and/or Effluent Tyg and/or ?!cnitoring Analytical Procedures (a) Steam System Recycled or directed to If discharged, procedures Blowdown Radwaste System for adhere to Technical discharge.
Specifications.
(b) Radioactive Effluents shall not exceed Procedures adhere to Vaste values specified in the requirements of I
Technical Specifications.
Technical Specifications.
All dis;harges are performed in accordance with the Offsite Dose Calculation
?!anual (ODC51).
TABLE IV. A.2 2.
Results of Liquid Effluent Discharges to the Environment - Beaver Valley Effluent Type Results for 1987 (a) Steam System The Steam System Blowdown was recycled or Blowdown directed to the Radwaste System where it was I
monitored and discharged in accordance with conditions noted in Section 3/4.11.1 of the Technical Specifications for Units 1 and 2.
(b) Radioactive Routine planned releases of liquid efiluents Waste Liquids from the Beaver Valley Power Station were released in accordance with conditions noted I
in the Section 3/4.11.1 of the Technical Specifications for Units 1 and 2 and no limits were exceeded. These values have been reported in the Beaver Valley Power Station Semiannual Effluent Reports for 1987.
SECTION IV DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
[
IV.
MONITORING EFFLUENTS B.
Monitoring of Airborne Effluents 1.
Description of Airborne Effluent Sources Beaver Valley Power Station (Units 1 and 2)
The Beaver Valley Power Station identifies isotopes according to the Environmental Technical Specifications
{
Prior to waste gas decay tank batch releases and containment purge releases, an analysis of the principal gamma emitters is performed.
The principal gamma emitters include noble
- gases, iodines, and particulates.
Figure 4.6 shows the gaseous radwaste system at Beaver Valley Power Station.
The environmental gaseous release points also require specific nuclide identification. These points include:
a.
Unit 1 Release Points; I
1)
The Ventilation Vent located on top of the Unit 1 Primary Auxiliary Building.
2)
The Supplementary Leak Collection and Release I
System (SLCRS) Vent located on top of the Unit 1 Containment Building.
b.
Unit 2 Release Poin5s; 1)
The Ventilation Vent located on top of the Unit 2 Primary Auxiliary Building.
2)
The Supplementary Leak Collection and Release System (SLCRS) Vent located on top of the Unit I
2 Containment Building.
3)
The Condensate Polishing Building Vent located I
on top of the Unit 2 Condensate Polishing Building.
4)
The Waste Gas Storage Vault Vent located on I
top of the Unit 2 Decontamination Building.
5)
The Decontamination Building Vent located on top of the Unit 2 Decontamination Building.
c.
Unit 1 and Unit 2 shared release points; 1)
The Process Vent located on top of the Unit 1 Cooling Tower. _- __ _ - _ _ _ _ _ _ _ _ _.
lL SECTION IV DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
{
IV.
MONITORING EFFLUENTS B.
Monitoring of Airborne Effluents (continued) 1.
Description of Airborne Effluent Sources (continued) 1 Beaver Valley Power Station (Units 1 and 2) (continued)
These points are continuously roonitored for particulates I
and gases. Grab samples are obtained on a weekly basis and are analyzed for noble gas gattma emitting isotopes and tritium. Weekly continuous samples are obtained on I
filter paper e.nd charcoal cartridges. The filter papers are analyzed for particulate gamma emitting isotopes and gross alpha.
Composites of the filter papers are analyzed monthly for Sr-89 and Sr-90.
The charcoal I
cartridges are analyzed for 1-131. 1-133 and 1-135.
Figure 4.7 shows these gaseous release points.
I I
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CTI0tt IV FIGU2E 4.6 DUQUESNE LIGHT C0tiPAt1Y 1987 Annual Radiological Environmental Report F
FIGURE 4*6 c (H04 UNIT 2 G4EOUS TASTE SYSTEM SildlAt TO Tmi SHQ!i FOR UilT 1)
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SECTION IV FIGURE 4.7 DUQUESNE LIGHT COMPANY
{
1987 Annual Radiological Environmental Report w Ohio River FIGURE 4.7 7/~' %
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- 1. Ventilation Vent-thit 1 79 I
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- 2. Cmtairrent Vent (SLCRS)-01it 1 153
- 3. Process Vent-01it 1 & 2 475
- 4. Ymtilatim Vent - thit 2 85 l
S. Cmtairrent Vent (SLCRS)-01it 2 153 i,
- 6. Ccnimsate Fblishirg &;ildirg 85 hi Vent-Olit 2
- 7. Waste Cas Stora y Vault Vent-Dait 2 W
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- 8. Dturitaminatim &Jildirg Vent-bait 2 W
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- Elevatim atom piant grace, in fwt FIGURE 4.7 GASEOUS RELEASE POINTS - BEAVER VALLEY POWER STATION UNil I & 2 _______ _ _ _ _ _ _ _ _
SECTIOM IV DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
{
IV.
MONITORING EFFLUENTS B.
Monitoring of Airborne Effluents (continued) 2.
Airborne Effluent Treatment and Sampiing Beaver Valley Power Station (Units 1 and 2)
Radioactive gases enter the gaseous waste disposal I
system from the degasifier vent chiller of the boron recovery system, and are directed to the gaseous waste charcoal delay subsystem upstream of the overhead gas compressor where the gas is chilled to condense most of the water vapor.
Gases from the degasifier vent chillers contain primarily hydrogen and water vapor. A I
small amount of nitrogen and radioisotopes of xenon,
- krypton, tritium, cobalt, cesium, manganese, iodine, chromium and strontium are also present in the eight continuous ventilation system pathways.
The overhead gas compressor directs the radioactive gas stream to a gas surge tank.
Gas is periodically I
discharged from the Unit 1 or Unit 2 surge tank to one of the three (3) decay tanks at Unit 1 or one of the seven (7) decay tanks at Unit 2.
Af ter the decay tanks are sampled and authorization obtained for discharge, I
the flow of the waste gases from the decay tanks (2 scfm) is recorded and rapidly diluted with about 1000 scfm of air in order to dilute hydrogen and radioactive effluent concentration. The gases are then combined with nitrogen purge from the decay tank radiation monitor and oxygen analyzers, calibration gas from the I
oxygen analyzers, the main condenser air ejector exhaust, the containment vacuum system exhaust, aerated vents of the vent and drain system, discharge of the overhead gas compressor and the purge from the multi I
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 I
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 Unit I cooling tower. The radioactivity levels of I
the stream are monitored continuously.
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 Unit 1 or Unit 2 decay tanks being discharged.
i FL SECTION IV DUQUESNE LIGHT C0!!PANY 1987 Annual Radiological Environmental Report IV.
MONITonlNG EFFLUENTS h
B.
Monitoring of Airborne Effluents (continued) 2.
Airborne Effluent Treatment and Sampling (continued)
Beaver Valley Power Station (continued)
J During a shutdown period after the Unit 1 or Unit 2 I
containment has been sampled and the activity levels determined, purging may commence through the Ventilation Vent located on top of the Auxiliary Building or the I
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 Unit 1 Auxiliary Building (subject to radioactive contamination) are monitored for radioactivity prior to entering the common Ventilation i
Vent.
These individual radiation monitors aid in identifying any sources of contaminated air.
The Vertilation Vent is also monitored continuously by several redundant channels of the Radiation Monitoring System (RMS) and is sampled periodically.
Upon a high activity alarm, automatic dampers divert the system's exhaust air stream through one of the main filter banks I
in the Supplementary Leak Collection and Release System (SLCRS) and to the SLCRS Vent.
Areas in the Unit 2 Auxiliary Building (subject to radioactive contamination) are monitored for radioactivity prior to entering the filter banks for the I
Supplementary Leak Collection and Release System (SLCRS)
Vent.
This system is sampled periodically for determination of radioactive material and is monitored continuously by other channels of the Digital Radiation I
Monitor.ing System (DAMS).
Each Unit 1 and Unit 2 filter bank consists of roughing I
filters, charcoal filters, and pleated glass fiber type HEPA filters.
The roughing filters remove large particulates to prevent excessive presst.re 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, kelease points for Unit 1 and Unit 2 of the Beaver Valley Power Gtation are shown in Figure 4.7.
See Table IV.B.1 for Radioactive Gaseous Vaste Sampling and Analysis Program. l
M' M '~ M M
M M
M M
M M
M M
M~
TABLE IV.B.1 Radioactive Gaseous Waste Scmpling cnd Analysis Progrrm
!!IN1!1UM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LI.D)
O GASEOUS RELEASE TYPE FREQUENCY FREQUE!!CY ACTIVITY ANALYSIS (pC1/ml)"
h
?.. Vaste Cas Storage Tank P
P
_4 g
Each Tank Each Tank Principal Camma Emitters 1 x 10 Grab
-6 Sample H-3 1x 10 g
O I
B. Containment Purge P
P Each Purge Each Purge Principal Camma Emitters 1 x 10-g l
E g
Crab
_ g, Sample li-3 1 x 10 m
b b
E WE C. Ventilation Systems M.c.c g
Principal Camma Emitters 1 x 10 SO Grab oE
- 1. Process Vent Sample 11 - 3 1 x 10 w.:
- 2. ' cntainment Vents gm J
1 re gg
- 3. Aux. Bldg. Vents g
~
[5
- 4. Cond. Polish.
Continuous W
1-131 1 x 10 EO Bldg. Vent Charcoal
-10 amp e x 0 yq
- 5. Decon. Bldg. Vent f
d g
o 'g y4 n nu us W
Principal Camma M tters
_gg
- 6. Waste Cas Vault Particulate (I-131, Others) 1 x 10 g
Sample g
y
~
f Continuous M
Gross alpha 1 x 10-11 Composite 4
~
o Particulate Sample 1 x 10'I Continuous Q
Sr-89 Sr-90 Composite
~
Particulate g
Sample g
-6 f
M Continuous Noble Gas Noble Cases 1 x 10 Monitor Cross Beta and Canma y
'en
t
~
SECTION IV DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
[~
IV. MONITORING EFFLUENTS L
TABLE NOTATION I
a.
The Lower Limit of Detection (LLD).
l s
b.
When reactor coolant system activity exceeds the limits stated in the BVPS Technical Specification, analyses shall be 7
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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving the maximum i
[~
steady state power operation unless continuous monitoring is L
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 /> (from the approp iate entilation release path) when the refueling canal is tloodeo, d.
Samples shell 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 p
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, L
shutdown and 2 5*.
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 activity exceeds the limits stated in the Technical Specificatio, 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.
f~L e.
Tritium grab namples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
L f.
The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered
{
by each dose or dose rate calculation made in accordance with the BVPS Technical Specification.
f g.
The principal gamma emitters for which the LLD specification L
will apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Kn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-
[
~
[
134 Cs-137, Ce-141, and Ce-144 for particulate emissions.
l This list does not mean that only these nuclides are to be l
detected and reported. Other peaks which are measurable and l
F identifiable, together with the above nuclides, shall also be k
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 7
result in LLD's higher than required, the reasons shall be L
documented in the semi-annual effluent report.
I~
h.
Only when release path is in use.
L r~
L.
IL SECTION IV DUQUESNE LIGilT COMPANY 1987 Annual Radiological Environmental Report IV.
MONITORING EFFLUENTS B.
Monitoring of Airborne Effluents (continued) l 3.
Results
+
e Beaver Valley Power Station l^
Gaseous effluents from the Beaver Valley Power Station were released in accordance with conditions noted in a
l Section 3/4.11.2 of the Technical Specifications. No limits were exceeded. These values have been reported in the Beaver Valley Power Station Semi-Annual Effluent p
Reports for 1987.
l L
l l
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E E
E L
E
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m m..
SECTION IV DUQUESNE LIGHT C0!!PANY 19E7 Annual Radiological Environmental Report
[
IV, rioNITORING EFFLUENTS C.
Solid Vaste Disposal at the Beaver Valley Power Station
~
During Beaver Valley Power Station normal operations and I
periodic maintenance, small quantities of solid radioactive waste materials were generated such as evaporator concentrates, contaminated rags, paper, plastics, filters.
spent lon-exchange resins, and miscellaneous tools and I
equipment. These were disposed of as solid radioactive waste.
At the Beaver Valley Power Station, the compactable wastes are segregated and compressed in 55 gallon drums to minimize disposal volumes. The compressed waste, plus other drums of I
noncompactable waste, were then shipped offsite for disposal at a commercial radioactive material burial site licensed by the Nuclear Regulatory Commission (NRC) or a state under agreement with the NRC.
No radioactive waste material was I
buried at the Beaver Valley Power Station site.
All containers used for packaging, transport, and disposal of I
radioactive materials met the requirements of the United States Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC).
Shipments offsite were made in accordance with DOT and NRC regulations.
Figure 4.8 depicts I
solid waste handling at the site.
At Beaver Valley Power Station approximately 2,600 cubic feet I
of radioactive solid waste was shipped offsite in 1987. The six (6) shipments contained a total activity of 35 cur.es.
I Industrial solid wastes were collected in portable bins, and removed to an approved offsite burial ground.
No burning or burial of wastes was conducted at the beaver Valley Power Station site.
I I
I FIGURE 4.8 SECTION IV l
DUQUESNE LIGHT COMPANY I
1987 Annual Radiological Environmental Report l
l 11 I
SOLD VASTE DISPOSAL DIACRAM SECTION IV w ADIDACTIvr sof.tn W ASTE DISPOSAL I
.v.isc. Radioactive Compactor and g
Solid Wastes Drumming Station
]
I D
5
\\
5
'On notrer Dadioactive Waste Sludge Solidify-I j
Discos 31 Fvsror9 tor ino Station 1
8 Q
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Spent Radioactive Special Shipping n
Resin Casks & Containers i
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L SECTION Y - A DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING
~
A.
Environmental Radiosctivity Monitoring Program 1.
Progran Description The program consists of monitoring water, air, soil, river bottoms, vegetation and fwderops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Yable V.A.I.
Further description of each portion of the program (Sampling Methods of Sample Analysis, Discussion and Results) are I
included in parts V-E through V-1 of this report.
V-B - Air Monitoring Y-C - Sediments and Soils Monitoring V-D - Vegetation and Foodcrops V-E - Cow's Milk V-F - Environmental Radiation Monitoring V-G - Fish I
V-H - Surface, Drinking, Well Waters and Precipitation I
Y-I - Estimates of Radiation Dose to Man i
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1ABLE V.A.1 M
n C0!s50t1 PAT [0 C.DIOLOGICIL EMIPO$mt Ti.L M0mif0R!MG PeoGram
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DtC Sample Anafysis Sample Type of Sample Points Sector Miles Sample Point Description Sample Frequency Preparation Freoveccy Analysts IdI Gross tete. ICI 1 131 1.
Air Particulate 13.
11 1.6 Meyer's farm Continuous Sampling Weekly Composite sad Radiciodine 30 4
0.6 Shippingport. PA. (5.5.)
with sample coller..
46.1 3
2.4 Industry. PA tion at least Monthly Comcosite Gamma -scen weekly 32 15 0.8 Midland. PA (5.5.)
gg) 48(a) 10 16.5 bie t rton WV (a)
Owarterly Composite Sr-89.90 51 5
8.0 Allqvfppa. PA (5.5.)
~
47 14 4.8 test Liverpnol. OH
,c 27 7
6.2 Brunton's Farm 5
28 1
8.7 Sherman's Far.
298 3
8.1 Scaver County Hospital 5
E Quarterly (4' 2.
Direct 30 4
0.6 Shippingport. PA {$.5.)
Continuous 99 Gama-Dose y {
- sdfation 13 11 1.6 Meyer's farm (1LD)
Annually S c 46 3
2.5 Indestry. PA(Church) 8 O
32 15 0.8 Midland. PA (5.5.)
2 A 48 (a) 10 16.5 Watrton, WV (a)
I r-45.1 6
2.0 Raccoon Twp. PA tennedy's Crnrs.
E e
51 5
8.0 Aligvippa. PA (5.5.)
5 e
m f
47 14 4.8 fast Liverpool. OH i
n 70 1
3.0 West. 8vr. School 80 9
8.4 Raccoon Part o
81 9
3.9 Southside School 4 5 82 9
7.1 Hanover Municipal Bldg.
83 10 4.5 Mill Creek Rd "f
14 11 2.6 Hookstown 84 11 8.5 Hancock Co. Children Home 4
j US 12 5.8 Ets. 8 & 30 Intersection R
i l
86 13 6.5
[. Liverpool Cahills House 92 12 3.0 Georgetown Rd.
l 87 14 7.0 Calcutta Road 88 15 3.1 Midland Heights 89 15 4.7 Chloville 90 16 5.2 Fairview School 10 4
0.8
$hippingport Boro. PA 45 5
2.2 Mt. Pleasant Church 60 13 3.7 Haney's Farm 93 16
.3 Sunset Hills. Midland 95 10 2.4 McCleary Rd. :allte W111 tams E
"m 5.5. - Substation
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f T T T I
Tastt v.A.1 C0450LIDATED RADIOLOGICAL C M IRomsEGTAL Mou!TORING PROGRAM g
(Conttaved) g
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DLC Samle Analysts g
$saple Type of Seagle Points sector Miles Sample Point Description semple frequency Preparatton Frequency Aaalysis 2.
Direct 28 1
8.7 Sherman's Form Conttavous Ovarterly Ga w -Dose Radiation 7?
2 5.5 Brighton Twp. School (TLD)
Annually (Continued) 72 3
3.2 Logan School 298 3
8.1 Beaver Covaty Hospital 73 4
2.2 Potter Twp. 5-hool 74 4
6.8 Comm. Col-Center Twp.
75 5
4,3 Holt Road 76 6
3.8 Raccoon Two. School 77 6
5.8 Green Garden Rd (Wayne's) 3 59 7
1.1 frons
~
78 7
2.3 Raccoon Mun. 81dg.
F 27 7
6.2 Brunton's Farm 79 8
4.6 Rt. 18 & Rt. 151 E.
i 15 14 3.3 Georgetown 46.1 3
2.1 Industry PA g
a 91 2
3.7 Ptee Grove ad and Doyle 8d T
l 94 8
2.4 McCleery ad, aft 1 son 5K 3.
1sefece 49.1(a) 4 5.0 Arco Polymers Intermittent Monthly Compostte of Gross Beta 0-
),
Water 2.1 14 1.3 Downstream (Midland) J s 1.
Composite 5emples (j) Weekly Sample (d)
Gross Alpha I.
Collected Weekly Gessne-sca n 7
o 8
3 13 0.2 shipelagport Atomic Power tieetly Grab Quarterly Comoostte Co-60. H-3 i
-4 g
Statten Discherge 5supies only 3r-89. $r-90 49 (a) 3 3.2 Montgomery Den (Upstream)
C 2A 13 0.2 Downstream SVP5 Outfall
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5 14 4.8 test Liverpool (row water)
Detly Grab Saaple Only - Collected Weekly (j)
-F 3
3 4.
Groundweter 13 11 1.6 mcyar's Farm 34 11 2.6 Hookstown. PA 15 15 3.3 Georgetown, PA l
11 3
0.8 shippingport soro Overterly Quarterly Ge=ne-scan. Cross i
Beta. Gross Alpha.
M-3 1
5.
Drinking 4
14 1.3 Midland. PA (Mid1 sad Water Intermitter.t (#}
Weekly CoNotite of Ge w -scan. 1-131 h
Treatment Plant)
Sample Collected Daily Searle (d) g Jeekly Monthly Composite (d)
Gross Alphe Gross Sete 5
14 4.8 tast Liverpool. CH (East Quarterly Cogostte (d) st-3.Co-60. Sr-89, 90 Civerpool Water Treatment Plant) 6 5
0.5 DLC new Tratatag 81de.
Weenly Grah Sample
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TABLE V.A.1 h
C0%CLIDAftD REDIOLOGICAL ENflPOM;TAL MOUTO#f ts PPC02AM
'j
( Continved )
PLC Sagle Analysis gg)
Type of sample Points Sector Miles Sample Point Description Sample Freovency Preparation frequeacy Analysis Sagt e 6.
Shoreline 2A 13 0.2 Downstream 87P5 Outfall Seefaaaual Semfannual Ga<aa-scan. Gross Beta Gross Alpha Urantua Isotesic sediment 3
13 02 victatty SAPS Discharge Sr-89. 90 49 3
3.2 Upstream side of Montgomery D?m (a) 50 13 8.2 U3 stream side of New Comt.erland Dam 7.
Milk 25 10 2.1 Searight's Dafry Weekly Weekly sample from 1-1 31 oc Searight's only Bfweekly (g)
Itweekly (grazing)
Gama-s c a n When animals are Monthly (ta eors)
Sr-89, 93 y
1-131. (s-137 g
on pasture; 96fa) 10 10.3 Wladsheimar monthly at other
- 3. p 27 7
6.2 trunton's Dairy (h) times.
29 3
8.3 Nico1*s Dairy (h) tbethly Ponthly Gama-scan Sr-89. 90 g
8.
Fish 2A 13 0.2 Vicinity of BVP5 n semiar.nual Co-posite of edible Cama-scan ca edible parts by species (t) portions 0h 5tation Discharge and "z
[
Shippingport Dfs. Sta.
- [
o, a
49(a) 3 a.7 Upstream Side of o
, 4 Montgomery Dam
>5 9,
Food Crops (Shipp.) 10 4
0.8 (Three locations within Annual at Composite of each Gama-scan (Georg.) 15 14 3.3 5 stics selected by harvest if sa gte species 1-131 os green leafy vecetables (Indus.) 46 3
2.5 Company) available 44ta) 10 16.5 Weirton. VV k
Ga ma-scan
- 10. Feedstuff and 25 10 2.1 Searight's Dairy Farm Monthly Mnnthly Sr-93 Quarterly Quarterly Composite Su mer Forage
- 11. Soft 13 11 1.6 Meyer's farm Every 3 years 12 Core Sa-ples Ga ma-scan 30 4
0.6 Shippineart. I's.
(1982. IMS. etc. )
3" Deep ( 3 Dia.
$r-90 at each location Gross teta 46 3
2.6 Industry. Pa.
(appron. 10*
Gross Alpha 32 15 0.8 (morth of Site) Midland radius)
Uranium Isotopic a8(a) 10 16.5 Weirton. W. Va.
51 5
8.0 Altquippa. Pa.
47 14 4.3 E. Liverpool. 0%.
27 7
6.2 Brunton's Dairy 22 A
0.3 South of BVP5 Site 2M 3
A.3 utchot's Dairy g
E.
pateattal ebyeal.8.iaae atar.
3YP5 Technical 5perificit taa T.shle 1.32-3 retalrce t;.recO) Jairice i.e aciert ed a.e ; aat e af ht p4.e=t utich cenown state.
See f.ect f aa V.f'. f or specif se lae nt tana maaptcJ.
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E SECTION V - A DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report EL 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 10 times the year.y mean of sample when gross beta is >
control samples.
(d) Analysis composites are well mixed actual samples prepared of equal portions from each shorter term samples from each locat ion.
(c) Composite samples are colli ed 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 />.
p (f) Weekiy milk sample from Searight's Dairv is analysed for I-L I?1 only.
(g) Milk samples are collected bi-weekly whea animals are in pasture and monthl', at other times.
[ Assume April - October for grazing season (pasture).]
)
I (h) The milk samples from Brunton's and Nicol's are collected once per month.
(i) The fish sampics 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 I
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 I
sample.
(j) Composite samples are collected at intervals not exceeding 2 I
hours at locations 49.1 and 2.1.
Weekly grab samples are obtained at location 3, 49 and 2A.
A weekly grab sartple is also obtained from daily composited grab samples obtained by the water treatment plant operator at location,.
(k) Two (2) TLDs are collected quarterly and annually from each monitoring location.
.,e.
L F
L SECTION V - A DUQUESNE LIGHT COMPANY 1987 Annual Radiolagical Environmental Report TABLE V.A.1 CONSOLIDATED RADIOLOGICAL ENVIRONMENTAL ?!ONITORING PROGRAM (Continued)
L
~
Additional Notes:
Sample points correspond te 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.
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-- All Air samples are decayed for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before analyzing for Gross Beta.
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INVIRONMf NI AL RADIOLOGILAL HONITORING PROGRAM SLMMARY H
O Nee of Facility Be wcr Valley Power Station Unit I and 2 Docket No. 50-334/50-412 4
Locat ton of f actitty Beaver, Pennsylvant e Reportino Perlod Annual 1987 (C6iiMM2e)
Number of Analysis and Lower Limit Medissa or Pathway Total Number of All Indicator Ivatto.
-Location with Hichest Annual Mean Control Locat tons Nonroutine Ca
~
Septed of Analysis Detection
'M Mean' Nee
- 'Mean (f) NHean (f)
Reported (tinit of Measurement) Performed (LLD)
- R an9?_,,
Distance and Directions ** Range
- R ange Me asurment s* *
- g WeIrton.WV 3
No. 48 cW" Air Particulate Gross (520) 2.5 19(519/520)
Midland, PA 20(51/52) 18($2/52) 0 and Radiotodine Beta (8.4-43)
No. 37 (11-38)
(8.e-32) gg ao (X10-3 pct /Cu. M.)
Sr-89 (40) 5 LLO rCbN Sr-90 (40) 0.2 LLD g
w d
1-131 (520) 40 LLD n
t-*
mH "O
ta k
Gamma (120)
Be-7 40 125(120/120)
Shippingport, PA 140(12/12) 111(12/12) 0 (51-204)
No. 30 (73-177)
($1-151)
Eo np K-40 20 40(10/120)
Midland, PA 57(3/12)
LLD 0
yy (11-86)
No. 32 (36-86) g Others Table V.A. 4 LLD E
W e
- o O
N Hb E
'ro Nominal Lower Limit of Detection (LLD)
Mean and rance based upon detectable r.casurczents only. fraction of detectable measurements at specified locations is indicated in parentheses (f)
Monroutine reported measurements are defined in Reculatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendix A)
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l.
I us INVIRONMEliTAL RADIOLOGICAL MONITORING PROGRAM 5tNMARY H
Nec of f acility Beaver Valley Pow 7r Station Unit I and 2 Docket No. 50-134/50-412 y
Z Pet.nsy v ani a Reportina Period Annual 1987 4
l Location of f acility Feaver,ty.St ate)
(Coun Number of Analysis and Lower limit Medium or Pathway Total Number of All Indicator locations location with Hlahest Annual Mean Control loc at ions Nonroutine S epled of Analys1s Detection 83 Nes if; Yame a'Mean (T) 74 Fad-(f)
Reported G
(Unit of Measurement) Performed (LtD)
- % r,ge Olstance and Direct tons ** Range
- *R ange Me asur ement s* *
- Q" N5Tdgomery Dam No. 49 g
' Sediment Gross (8) 0.3 22(8/8)
SADS Discharge No. 03 25(2/2) 21(2/2) 0 (pct /c)
Alpha (18-26)
River Mile - 34.8 (24-?6)
(18-24) gg Gross (8) 1.0 37(8/8)
SAPS Discharge No. 03 4?(2/2) 39(2/2) 0 (dry wetoht)
Beta (31-44)
River Mlle --34.8 (40-44)
(38-40)
- o. o F C:
Sr-89 (8) 0.2 LLD O @
Sr-90 (8) 0.04 Ltc 0* g o
W rne
%y w
Y Gamma (8) en k Be-7 6.2
- 0. D(4/8)
SAPS Discharge No. 03 0.93(1/2) 0.76(2/2)
O (0.43-0.98)
(0.53-0.98)
$n rp K-40 0.5 II!Aial Cumberland Dam No. 50 14(2/2) 13(2/2) 0 Qd
(%16)
(13-16)
(12-14) g P%-54 0.2 0.17( 4 8)
BVPS Discharge No. 02A 0.17(1/2)
LLD 0
River Mlle -- 35.0 g
e*
Co-58 0.2 S.5(2/8)
BVPS Discharge No. 02A 11(1/2)
LLD 0
E (0.097-11)
River Mlle -- 35.0 o
0 Co-60 0.2 3.2(3/9)
BVP5 Discharge N,.
02A 4.7(2/2)
Lt c 0
re (0.15-4 8)
River Mlle -- 35.0 (4. 7-4.8 )
C5-137 0.02 0.45(8/8)
C eberland D e No. 50 0.75(2/2) 0.29(2/2) 0 (0.24-1.2)
(0.29-1.2)
(0.24-0.35)
Ra-226 0.1 2.l(8/8)
Cabcriand Dam No. 50 2.5(2/2) 1.6(2/2)
O s
(l.3-2.9)
(2.1-2.9)
(1.3-1.9) g t~
Th-228 0.02 1.2(8/8)
Ceberland Dam No. 50 1.3(2/2) 1.?(2/2) 0 rn (1.2-1.4)
(1.1-1.2)
(0.99-1.4)
Ra-228 1.G 1.2(1/8)
Cumberland Das No. 50 1.2(I/2)
LtD 0
Others Table V.A. 4 LLD
MUR l l l 1 T
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(NVIRONMENTAt RADIOLOGICAL PONITORisG PROGRAM SLNMARY g
H Mame of Facility Beaver Valley Power Station Unli. I and 2 Docket No. 50-334/50 412 Location of Facility Beaver, Pennsylvania Reportino Period Annual 1987 f.
(County,5 tate)
Number of Analysis and lower Limit Pedium er Pathway Total Number of All Indicator locations to<.ation with Hinh2st Annual Mean Control locations Nonroutine Sampled of Analysts Detection
- Mean (f)
Name "Me an ( f) NMe an ( f )
Reported (Unit of Measurement) Per fumed (LLD)
- Renee Distance and Directions ** Range
- Range Measurements ***
M Montgomery Dam y
No. 49 bu Sediment U-233 (8) 0.01 0.59(8/8)
Cumberland Dam No. 50 0.81(2/2) 0.39(2/2) 0 H
(pCf/c) and (0.28-1.0)
(0.62-1.0)
(0.28-0.50) mc (dry wetoht)
U-234 b c:
U-235 (R) 0.01 0.018(8/8)
SAPS Olscharoe No. 03 0.024(2/2) 0.01(2/2) 0 (0.0063-0.029)
(0.018-0.029) (0.0063-0.014) og oS h U-238 (8) 0.01 0.4 h*8/8)
Cumberland Dam No. 50 0.58(2/2) 0.31(2/2) 0 (0.24-0.69)
(0.47-0.69)
(0.24-0.38) np mH wO I
Ds
<O r '
no8g ac rt>
H ko O
- 1 rt H>
tu t*
t1 Nominal Lower Limit of Detection (LLD)
Fraciton of docctable measurements at specified locations is indicated in parentheses (f) g Mean and rance based upon detectable measurements only.
Nonroutine reported measurements are defined in Renulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications m
(Appendix Al
y_- _ _
tn t9 O
[NVIR0f.?t[NI AL EADIGiOGICAL Pt*110 RING PROGRAM SLMMARY Name of Facility Beaver valley Power Station Unit I and 2 Docket No. 50-334/50-412 g
location of Fartlity Beaver, Pennylvania Reporting Period Annual 1987 4
{ Count y,51 ale)
[.
j i
Number of foalysis and Lower Limit Meditsu or Pathway Total Number of All Ind!cator locat ions location with Highest Annual Mean Control locat ions Nonroutine Sept ed of Analysis Detectton
"' ret 7 f)
Nme 3*Mean (f) nWean (f)
Reported d
(Unit of Measurement) Performed (LLD)
' * *R anoe Dist ance and Direct ions **Ranoe
- Range Me asur ewent s ** *
~
Weirton,WV k
%. 48 3c External Radiation Gmma 0.05 0.17(176/176)
Hancock County 0.21(4/4) 0.17(4/4) 0 l
(mR/ day)
(176 ouarterly)
(0.12-0.22)
Children's Home No. 84 (0.20-0.22)
(0.15-0.19) g
$c 1
l Gamma 0.05 0.17(43/43)
Haney's Fara 0.20(1/l) 0.17(1/1) 0 09 oM (43 annual)
(0.12-0.21)
No. 60 w tis I
r u
Feed and forace I-131 (12) 0.01 LLD
$caright Dairy One Sag le
$[
Y (pC1/o)
No. 25 Locat ion 0
HO (dry wetoht)
Sr-90 (4) 0.003 0.17(4/4) 0
< 0 (0.06-0.23) n O
Gamma (12) 0 Be-7 0.3 1.9(9/12)
@ @R to (C.41-4.22)
D, r
K-40 0.5 24(12/12) 0 m
H (1.9-48.0)
W Cs-137 0.04 0.055(1/12)
O p
O M"
Th-228 0.1 0.27(1/12) 0 Others fable V.A. 4 lid 0
H b
c E9 M ominal Lower Limit of Detection (LLD)
N Mean and rance based upon detectable measus ements only. Traction of detectable measurements at specified locations is indicated in parentheses (f)
Nonroutine reported measurements are defined la Recuiats,iy Guide 4.8 (December 1975) and the Beaver Valley Power $tation TechntCal Specifications (Appendix A)
A S
7 F U 'l.f U 'l F L_f 7 W1.
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ENVIRONMENTAL RAJIOLOGICAL MONITORING PROGRAM SLNMARY g
>4 Name of f acility Beaver Valley Power Station Unit I and 2 Docket No. 50-334/50-412 g
4 location of f acility Beaver, Pennsv1vania Reportino Period Annual 1997 d.
(County.5(M e; G
Number of Analysis and Lower Limit Medium or Pathway Total Number of All Indicator locations Location with Highest Annual Mean Control Locations Nonrout ine Sampled of Analysis Detectfon
- 3%an (T)
Name
Mean (f) ' * *Mean ( f)
Reported (tin d
,1 Measurement) Performed (LLD)
- *R ange Distance and Directions ** Range
- *R ange Measurements ***
y Montgomery g
W Dam No. 49 gg
- 0. D fish Ganna (8)
/4)
K-40 0.5 3.?(8/8)
BVP5 - Shippingport 3.4(5/5)
- 2. 7(3/3) 0 we oht)
(7,7,4,9)
No. 02A (2.2-4.9)
(2.5-2.8) o Co-58 0.03 0.05(1/8)
BVP5 - Shippingport 0.05(1/S)
LLD 0
Mg 4
No. 02A r
b ed y
Others Table V. A. 4 LLD ro h
4O Weirton WV No. 48 food and Garden 1-131 (4) 0.006
- LD g
Crops (pC1/q)
(wetweight) n.
n Gamma (4)
W K-40 0.5 2.4(4/4)
Industry, PA No. 46 3.5(1/1) 1.3(1/1) 0 W
(1.3-3.5) 4 Others Table V. A. 4 LLD 0
y H
r-L4 g
Nominal Lower Limit of Detection (LLD)
Traction of detectable measurements at specified locations is indicated in parentheses (f)
Mean and rance based upon detectable meascenents only.
Nonroutine reported measurements are defined in Regulatory Guide 4.8 (5fPTEMBER 1975) and the Beaver Valley Power Station Technical Specifications (Appendix A)
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[NVIP0 MENTAL RADIOLOGICAL M0hlTORING PROGRAM SlMMARY O
l Mme of f acility Beaver valley Power Station Unit I and 2 Docket No. 50-334/50-412
- r.
4 e
I Location of f acility Beaver Penns Ivania Reporting Period Annual 1987
~~{dly.St a e) i Number of Analysis and Lower Limit Median or Pathway Total Number of All Indicator locations Location with Hiohest Annual Mean Control Locations Nonroutine G
Septed of Analysis Detection
- Mean (f)
Name
- Mean (f) T*Mean (f)
Report ed
~
(Unit of Measurement) Performed (LLD)
- R ange Distance and Directions ** Range
- *R anoe Measurements ***
g Erunton Dairy y
- h. 27 CD f
yh
(
Milk I-131 (167) 0.5 ttD Sr-89 (135) 2 ILD o.d (pCl/t)
O
)
Sr-90(135) 1 4.2(132/135)
Ferry No. 102 9.6(16/16) 2.5(18/19) 0 r
i (1.1-14)
(5.6-14)
(1. 5-4.0) gg 1
a O ta Gauna (136) hO l
K-40 100 1360(136/136) romall No. 98 1580(14/14) 1310(19/19) 0 g
(970-1790)
(1380-1780)
(1070-1520) ym Cs-137 5
7.7f 15/136) lijndsheimer No. %
9.2(2/19) 6.l(2/19)
O M
(5.6-11)
(7.5-11)
(5.6-6.6)
E.
Others Table V. A. 4 LLD 0
%w b
=0 O
rt I
1 g
b 4
r-I M
i 1
y Nominal Lower Limit of Detection (LLD)
Traction of detectabl6' measurements at specified locations is indicated in parentheses (f) 1 Mean and rance based upon detectable measurements only.
l Nonroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications (Appendix A) i
m E NVIRONME N IAL RADICLOGICAL MONITORING PROGRAM SLNMARY g
O Nee of Facility 8 caver Valley Power Station Unit I and 2 Docket No. 50-334/50 412 d
i O
1 Penns Reporting Period Annual 1987 l
7EounE%ylvania Location of Factitty Beaver g
4 i
te)
Number of Analysis and 1ower Limit Medium or Pathway Total Neber of All teedicatur Locations location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection
- ~ @ H Nee
Mean (f) NHean (Q Reported (linit of Measurement) Perfomed (LLD)
- *R ance_
Distance and Directions **Ranoe "R ange Measurements ***
y N
Montgomery Dam No. 49 Surf ace Water 1-131 (52) 0.5 0.5(2/52)
Arco Polymers No. 49.1 0.5(2/52) 0 (pCi/f)
(0.4-0.5)
(0.4-0.5)
@p Gross (72) 0.6 LLO E'
ps y Alpha
>c Gross (72) 1 7.7(72/72)
BVPS Discharge No. 02A 14(:2/12) 5.7(12/12) 0 Bet a (2.9-57)
River Mlle -- 35.0 (3.o-57)
(3.5-9.0) og Oh G ama (77)
N b
K-40 20 92.5(1/77)
J and L 5 teel No. 2.1 9.5(1/12)
LLD 0
e-* ok C) 00-58 5
128(4/77)
BVP5 Discharge No. 02A 228(2/12)
LLD 0
(6.9-303)
River Mlle -- 35.0 (153-303)
$0 n0 Co-60 5
18.8(3/77)
Shippinoport, PA No. 03 30.8(1/12)
LLD 0
S (8.9-30.8) a ev Others Table V. A. 4 LLD Sr-89 (24) 2 LLD E
.oo Co-58 (24)(a) ?
54(2/24)
BVPS Discharge No. 02A 54(2/4)
Ll D 0
"v r
(23-85)
River Mlle -- 35.0 (23-85)
Co-60 (24)(a) 2 5.47(3/24)
Shippingport, PA No. 03
- 8. 5(1/4 )
LLO 0
(3.2-8.5)
Tritte (24) 100 3900(16/24)
BVPS Discharae ho. 02A 16000(3/4) 270(4/4) 0 (IM-35000)
River Mlle -- 35.0 (440-35000)
(130-460) h (a) Co-58 and Co-60 analyzed by high sensitivity method and were performed on quarterly composited samples.
Nominal Lower Limit of Detection (LLD)
Fraction of detectable measurements at specified locations is indicated in parentheses (f)
Mean and range based upon detectable measurements only.
Nonroutine reported measurements are defined in Regulatcry Guide 4.8 (December.1975) and the Beaver Valley Power Station TechntCal Specif tCations (Append 1x A )
0
q p---
, y -- -
y--- -)
7 z y z g
y z
y sn N
INVIRONMf MTAL RADIOLOGICAL MONITORING PROGRAM StMMARY 2
Nec of Factitty Beaver Vallef Power Station Unit I and 2 Docket No. 50-334/50-412 g
location of Facittty B* aver, Pennsylvanta Report ing Period Annual 1987 4
(County,5 tate) j, Number of Analysis and Lower limit Medium or Pathway Total Naber of All Indicator locations Location with Highest Annual Mean Control locations Nonroutine Sampled of Analysis Detection
- W an (f)
Name
- Mfean (f)
- Rean (f)
Reported (tintt of Measurement) Performed (lLD)
- R anoe Distance and Directions ** Range
- Range Me asur egnent s* *
- d Drinkino biater 1-131 (155) 0.5 0.8(2/155)
Midland. PA No. 04 0.4(2/52) 0 (pct /t)
(0.39-0.4)
River Mlle -- 36.3 (0.39-0.4) g.
Gross (36) 0.6 LLD Alpha b
Gross (36) 1 4A(35/36)
E. Liverpool, OH No. 05 4.9(12/12) 0 04 O Beta (2.1-9.0)
River Mile -- 41.2 (3.6 9.0) o5 wM%
Gama (156)
K-40 20 195(1/156)
DLC New Training Bldg.
195(1/52) 0 Q[
5g No. 06 ro Others Table V.A. 4 LLD E
Sr-89 (12) 1.5 LLD 7o Sr-90 (12) 0.5 LLD
@D e3 Co-60 (12)(a) 2 LLD on" Tritte (12) 100 240(8/12)
Midland. PA No. 04 330(2/4) 0 (140-380)
River Mlle -- 36.3 (270-380) p Rre H
(a) Co-60 asalyzed by high sensitivity method.
be tn Nominal Lower Limit of Detection (LLD)
Fraction of detectable measurements at specified locations is indicated in parentheses (f)
Mean and rance based upon detectable measurements only.
Monroutine reported measurements are defined in Regulatory Guide 4.8 (December 1975) and the Beaver Valley Power Station Technical Specifications w
(Appendia A)
M' ' M M
M M
M M
W m
i t4 h
f NVIRONMf MTAL RADIOLOGICAL MONITORING PROGRAM StrMARY H
O Name of Facilit y Beaver Valley Power Station tinit I and 2 Docket No. 50-334/50-412 f
tucation of Fac titty ~ Beaver, Penns Ivania Reporting Period Annual 1987
{CoTETy~,5{ e)
-e Number of W
Analysis and tower Limit Medium or Pathway Total Number of All ledicator locations location with Highest Annual Mean Control locations Nonroutine 5mpled of Analysts Detertion
- 3 Me an ( f)
Name
- 3Mean (T) mKean (f)
Reported g
(tinit of Measurement) Performed (LLD)
- *R ance Distance and Directions ** Range
- *R ange Measurements ***
3 Georgetown, PA No. 15 g
w Ground Wat er Grots (16) 2 LLD
[h (pC1/Itter)
Alpha
- o. c Gross (16) 1 3.8(12/16)
Shippingport, PA 5.0(4/4) 2.7(3/4) 0 7C pb Beta (1.3-6.6)
No. 11 (2.1-6.6)
(2.5-3.1) 0h r
Gama (16) o t*
K-40 103(1/16)
Georgetown, PA 108(1/4) Same as high 0
o No. 15 loc ation g
U Others Table V.A 4 LLD
<n Trttlum (16) 90 250(6/16)
Shippingport, PA 360(2/4) 130(2/4) 0 o
(110-410)
No. 11 (310-410)
(110-150) g aoremW 7J a
~o O
r1 re H
be t1 h
Nominal Lower Limit of Detection (LLD)
Traction of detectable measurements at specified locations is indicated in parentheses (f)
Mean and rance based upon detectable meesurements only.
Monroutine reported measurements are defined in RequIatory Guide 4.8 (December.1975) and the Beaver valley Power Station Technical Specifications (Appendix A)
M M
M
,M M
M M
M M
i V O O tn M
O E NVIR0tet NT *8_ RAbl08 OGICAL MONITORING PROGRAM SlNNARY N
g O
Nme of f acility Beaver Valley Power St ation Unit I and 2 Docket No. 50-334/50-412 Z
<3 location of Facility Beave, Pennsylvania Reporting Period Annual 1987
[
76uM y,Lt e) 5 Analysis and Lower Limit Number of 8
Medium or Pathway Total Number of All Indicator locations location with Highest Annual Mean Control tocations Nonrout ine
$mpled of Analysis Detection
- %B f}
Nw
- % an (f)
- Me o (f)
Reported k
(Unit of Measurrecat) Performed (LLD)
- Renge Distance and Directions ** Range
- R ange Measurements ***
D
~
Weirton, WV No. 48 hw w at er -
pc Precipitation Gross (33)
?
8.0(33/33)
I. Liverpool, OH 8.5(11/11) 8.4(11/11) 0 mC (pC6/t)
Beta (2.1-20)
No. 47 (2.1-15)
(5.3-14)
G y
Gama (33) oo $
e Be-7 40 32(17/33)
E. Liverpool, OH 97(8/11) 72(7/11)
O pp (50-195)
No. 47 (50-195)
(56-92) ps 7
wo Others Table V. A. 4 LLD m%
D Sr-89 (12)
?
LLG
$0{
Shippingport, PA 260(3/4)
O (170-400)
No. 30 (170-400) np w
5:1 en
=0 O
etn H
t-*
l 19
<=
Nominal tower Limit of Detection (LLD)
Mean and rance 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 (MARCH 1975) and the Beaver Valley Power Station Technical Specitications (Appendix A)
l SECTION V - A DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENV!RONMENTAL MONITORING A.
Environmental Radioactivity Monitoring Program (continued) 2.
Summary of Results All results of this monitoring program are summarized in Table V.A.2.
This table is prepared in the format specified by NRC Regulatory Guide 4.8 and in accordance m
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 thrcugh 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 fcr the various sampling media during the years 1974 and 1975.
Comparisons of pre-operational data with
,~
operational data indicate the ranges of values are generally in good agreement for both periods of time.
f Activity detected was attributed to naturally occurring L
radionuclides, BVPS effluents, previous nuclear weapons tests or to the normal statistical fluctuation for sctivities near the lower limit of detection (LLD).
The concit sion from all program data is that the operation of the Beaver Valley Power Station has
~
resulted in insignificant changes to the environment.
3.
Quality Control Program The Quality Control Program implemented by Duquesne Light Company to assure reliable performance by the DLC contractor and the supporting QC data are presented and discussed in Section III of this report.
The lower limits of detection for various analysis for each media monitored by this program by the DLC Contractor Laboratory are provided in Table V.A.4.
s M
W _
F
SECTION'V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 (Page 1 of 4) 1987 Annual Radiological Environm:ntal Rsport TABLE V.A.3 (Page 1 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Tacility Beaver Vallev Power Station Docket No.
50-334 14 cation of Tacility Beaver. ?ex svivania Reporting Period CT 1974 - 1975 (County, State)
PRZ-0PERATIONAL PROCMM SDMARY (CCMBINED 1974 - 1975) lower Limit Nadium or Pathway Sampled Analysis and Total Number of All Indicator locations (Unit of Measurement) of Analysis Performed Detection 13 Maan. (f) Ranae
/40 0.6 - 1.1 s
Surface Water Cross Alpha (40) 0.3 0.75 PC1/1 120/120 2.5 - 11.4 Cross seta (120) 0.6 4.4 Cama (1) 10 - 60 e 1.13 0/ 21 180 - 800 1
Tritis (121) 100 300
$r-89 (0)
I St-90 (0)
C-14 (0)
IL Drinki=4 Vater I-131 (0)
Gross Alpha (50) 0.3 0.6
'/30 0.4 - 0.8 208/208 2.3 - 6.4 Cross Beta (208) 0.6 3.8 Camma (0) 211 tricium (211) 100 310
/211 130 - 1000 C-14 (0)
H St-89 (0)
I" St-90 (0)
I Cround Vater Cross Alpha (19) 0.3 e 11D 3/75 'I 1.3 - 8.0 I
Cecss Beta (76) 0.6 2.9 II Tritium (81) 100 440
/81 80 - 800 Casmaa (1) 10 - 60 eID 30/188 0.002 - 0.004 Air Particulates Cross Alpha (188) 0.001 0.003 and Caseous 927/927 0.02 - 0 32 pC1/=3 Cross seta (927) 0.006 0.07 Sr-89 (0)
Sr-90 (0) 2/816 0.07 - 0.08 I-131 (816) 0.04 0.08 Camma (197) 2/197 0.01 - 0.16 Ir.%-95 0.005 0.04 0
Ru-106 0.010 0.04
/197 0.02 - 0.09 3
Ce-141 0.010 0.02
/197 0.01 - 0.04 C4-144 0.010 0.02
"/197 0.01 - 0.04 Others e 11D F
-w 1
SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.Ae3 1987 Annutl Radiological Envirotuntntal R: port (Page 2 of 4)
~
TABLE V.A.3 (Page 2 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Beaver Vallev Power Station Docket No.
50-334 Location of Tacility leaver. Penne?1vania taporting Period CT 1974 - 1975, (County, State)
PRE-CPERATIONAL PROGRAM $UMMART (CCMBINE 1974 - 1975)
Medium or Pathnsey Lower Limit
$supled Analysis and Total Number of All Indicator 14 cations (Unit of NaasurementJ of Analveis Perforv i Detection Lt.D Mean. (f) Ennae
~
Soil Gross Alpha (0)
PC1/g (dry) 64/4 14 - 32 6
(Template samples)
Gross Beta (64) 1 22 1
Sr-89 (64) 0.25 0.4
/64
'8 sr-90 (64) 0.05 0.3
/64 0.1 - 1.3 U-234,235,238 (0)
Gamma (64) 83 E-40 1.5 13
/64 5 - 24 56/64 c.1 - 6,8 Cs-137 0.1 1.5 I
[
Ce-144 0.3 1.1
/64 0.2 - 3 U
ZrNb-95 0.35 0.3
/64 0.1 - 2 En-106(b) 0.3 1.1
/64 0.5 - 2 others
< L1.D Soil Gross Alpha (0)
PC1/g (dry)
(Core Samples)
Gross Beta (8) 1 21 g/8 16 - 28 Sr-89 (8) 0.25
< L1D 3/8 0.08 - 0.5 St-90 (8) 0.05 0.2 I
camma (8) 8/8 7 - 20 E-40 1.5 13
'ce-137 0.1 1.2 7/8 0.2 - 2.4 1/8 Co-60 0.1 0.2 Others
< LLD F
SECTION V - A DUQUESNE LIGHT COMPANY TABLE V. A.3 1987 Annual Radiological Environmental Report (Page 3 of 4) l 1
TABLE V. A.3 (Page 3 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Mame of Tacility leaver fallet Power Station Dockat No.
50-334 location of Tacility leaver. Pennevivania Reporting Leni CT 1974 - 1975 (County. State)
FR2-0FEIATICEAL PROGRMt StlMMART(COM3DD 1974 - 1975)
Medium er Pathway lower Limit sampled Analysis and Total skanber of All Indicator locations (Unit of Measurement) of Amalvois Performed Detection 112 Maan. (f) Rante PC1/g (dry)
(0) sediments Cross Alpha Gross Seta (33) 1 18 33j33 5 - 30
$r-90 (0)
U-234.235, 233 (0) 33/33 2 - 30 Cam (33) 13 33 E-40 1.5 L3
/33 2 - 30 21/33 0.1 - 0.6 Ca-1.37 0.1 0.4 1rNb-95 0.05 0.8
/33 0.2 - 3.2 3/33 0.4 - 0.7 Ce-144 0.3 0.5 0)
Ru-106 0.3 1.5
/33 1.3 - 1.8 Others e LLD F%
Toodstd f Caama (8) 8 E-40 1
33
/8 10 - 33 1/8 Ca-137 0.1 0.2 1
Erine-95 0.05 0.2
/6 0)
I tu-106 0.3 0.8
/8
_r.
.m 00 Teod stuf f Cross Beta (80) 0.05 19
/80 0 - 50 33 Sr-89 (81) 0.023 0.2
/81 0.04 - 0.93
- 8/81 0.02 - 0.81 St-90 (81) 0.005 0.4 Cm (8?.)
II E-40 1
19
/bi 3 - 46 6
Ce-137 0.1 0.3
/81 0.2 - 1.6 Co-144 0.3 1.3
/81 0.9 - 2.4 U/81 0.2 - 1.8 1 rub-95 0.05 0.8 0)
U/81 0.6 - 2.3 au-106 0.3 1.4 Others e L13 E F
l'w SECTION V - A DUQUESNE LIGHT COMPANY TABLE V.A.3 1987 Annusi Radiological EnvironmIntsl Rsport (Page 4 of 4)
TABLE V.A.3 (Page 4 of 4)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SbHMARY Name of Facility Beaver Valley Power Station Docket No.
50-334 locatics of Tacility Beaver Pennsvivania Reporting Level CT 1974 - 1975 (County, State)
FRE-OFT 2ATICMAL PROCRAM SCW. ART (CNBDito 1974 - 1975)
[
Medium or Fathway Imer Limit sampled Analysis and Total Ikeber of All Indicator tocations (Unit of Measurement) of Analysis Forformed Detection 11D Mean. (f) Ranne Milk I-131 (91) 0.25 0.6
'/91 0.3 - 0.8 fL PC1/1 4/134 6 - 11 Sr-89 (134) 5 7
132/134 1.5 - 12.8 Sr-90 (134) 1 5.3 Camme (134) 19/ 34 11 - 16 ca-137 10 13 1
Others e 113 3"/
Istanal Radiation y - Monthly (399) 0.5 a1
- 0.20 399 0.08 - 0.51 ma/ day 195 y - Quarterly (195)
- 0. 5 mA
- 0.20
/195 0.11 - 0.38
'0 y - Annual (48) 0.5 37.*
0.19
/48 0.11 - 0.30 U/17 1.0 - 3.2 Fish Cross Beca (17) 0.01 1.9 PC1/2 (wet) s r-90 (17) 0.035 0.14 p/17 0.02 - 0.50 Gamma (17) 17 1-40 0.5 2.4
/17 1.0 - 3.7 other e LLD Lib in units of MR - Lower end of useful integrated exposure detectability range for a passive radiation detector (712).
One outlier act includsd in maan. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample.)
May include tu-104, Re-103, Be-7. F
u n
n
.F7 F W l F ~
m tnn H
H Oz DUQUESNE LIGHT C01'fANY TABLE V.A.4 TYPICAL LLDs
- FOR GAMMA SPECTROMETRY Sediment Milk Water Ait Pajticulages Vegetation G Soil Fish G
- pCi/r )
(pCi/kg dry)
(pCi/g dry)
(pC1/g wet)
Nuclide (pCi/ liter)
(10 Be-7 30 20 50 0.03 0.05 g
n-40 60 20 g
Cr-51 40 10 100 0.05 0.1 E
l Mn-54 3
0.5 30 0.02 0.03 ko Co-58 3
0.5 30 0.02 0.03 gg O
re-59 6
2 60 0.03 0.06 gy Co-60 3
0.6 30 0.02 0.03
$M C
- n-65 8
1 70 0.04 0.07 ob uo Ir/Nb-95 5
2 50 0.03 0.05 P' %
i Ru-103 3
2 40 0.03 0.04
$g hO Ru-106 30 5
30 0.02 0.03 n i5 Ag-IICM S
3 30 0.02 0.03 0
1-131 4
2 30 0.02 0.03 Te-132 4
2 20 0.01 0.02 5
9 I-133 4
2 20 0.01 0.02 ed Cs-134 4
0.6 30 0.02 0.03 g
Cs-136 6
0.6 50 0.03 0.05 3
Cs-137 4
0.6 20 0.02 0.03 N
82/La-140 10 6
40 0.02 0.04 Cc-I'l 6
2 60 0.03 0.06 H
Cc-144 30 5
200 0.1 0.2 D>
to Ra-226 60 6
600 0.3 0.6 t<
Th-223 10 1
60 0.03 0.06 4
At time of analysis (DL.C Contractor Lab).
Activity detected in all sampics.
1.ower Level of Octection is defined in Beaver Valley Power Station Technical Specificat wns.
NOTE
l L
~
SECTION V - B DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING B.
Air Menitoring 1.
Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area.
Air flow is generally from the Southwest in summer and from the orthvest in the winter.
2.
Air Sampling Program and Analytical Techniques a.
Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10) 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 atmospherr air through a glass fiber filter and t;. augh a charcoal cartridge.
The former collects a rborn particulates; the latter is for radiciodine sampling.
Samples are collected for analysis on a weekly basis.
The charcoal is used in the weekly analysis of airborne I-131.
The filters are analyzed each week for gress beta, then composited by station for monthly analysis by gamma spectrometty.
They are further composited ir a quarterly sample from each station for Sr-89 and Sr-90 analysis.
In order to reduce interference from natural radon and thoron radioactivities, all filters are a'. lowed 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. _-
SECTION V - B DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING L.,
B.
Air Monitoring (continued) 2.
Air Sampling Program and Analytical Techniques (continued) b.
Procedures (continued)
Gamma emitters are determined by stacking all the p
filter papers from each monitoring station L
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-L collection time.
[
J l
i I
l I
I I
l s
SECTION V - B FIGURE 5.B.1 r
l DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report FIGURE 5.B.1 ENVIRONWENTAL WONITORING LDCATIONS-AIR SRPLif0 LOCATiryg N
LA'aou cary alH S'MU6 STATIrf6 T
7, J
j er.4 o couvry SM M
1 Q...
13 MEYER'S b!RY f#lM j.,
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27 BRtiiton's b !RY fM P.
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L SECTION V - B DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
{
V.
ENVIRONMENTAL MONITORING B.
Air Monitoring (continued) 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 filtrate is taken for strontium analysis and is reduced in volume by evaporation. Strontium is precipitated as Sr(NO ):
using fuming
( 9 0'. )
3 nitric acid.
An iron (ferric hydroxide) scavenge is performed, followed by addition of stable I
yttrium carrier and a 5 to 7 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re precipitated as oxalate. The I
yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity.
Sr-89 activity is determined by from the sample after yttrium precipitating SrC03 I
separation. This precipitate is mounted on a nylon 2
planchet and is covered with 80 mg/cm aluminum absorber for icvel beta counting.
3.
Resclu and Conclusions
.t suamar; of data is presented in Table V.A.2.
a.
/irborne 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 I
5.B.2 illustrates the average concentration of gross beta in air particulates.
I I
I I
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D.E:. <
eECMCE-gu!e,? YO d s
a
=
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SECTION V - B DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING B.
Air Monitoring (continued)
[
3.
Results and Conclusions (continued) a.
Airborne Radioactive Particulatas (continued)
The weekly air particulate samples were composited to one hundred twenty (120) monthly samples which I
p were analyzed by gamma spectrometry.
Naturally L
occurring Be-7 was present in every sample.
Occasional traces above detection levels of other naturally occurring nuclides such as K-40 were
(
present. These are listed in the summary Table V.A.2.
Examination of effluent data from the Beaver Valley Power Station demonstrated that none i
F of the slightly elevated results are attributable L
to the operation of the power station.
A total of forty (40) quarterly samples were each l
7 L
analyzed for Sr-89 and Sr-90.
No Sr-89 or Sr-90
)
was detected.
l i
I Based on the analy'.ical results, the operation of Beaver Valley Power Station did not contribute to any increase in air particulatt radioactivity during CY 1987.
l l
b.
Radiolodine A
total of five hundred twenty (520) weekly i
charcoal filter samples were analyzed for I-131.
l d
No detectable concentrat.ons were found at any f
l oca t ion s..
4 u
Based on analytical results, che opet rat ion of j
Beaver Valley Power Station did not contribute to any increase ir.
airborne radioiodine during CY j
y 1987.
l i
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i i
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i i
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SECTION V - C DUQUESNE LIGHT COMPANY
~
1987 Annual Radiological Environmental Report
~
V.
ENVIRONMENTAL MONITORING C.
Monitoring of Sediments and Soils (Soil Monitoring is required every 3 years was not required in 1987)
Characterization of Stream Sediments and Soils 1.
s The stream sediments consist largely of sand and silt.
Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material.
2.
Sampling Program and Analytical Techniques a.
Program River bottom sediments were collected semi-annually above the Montgomery Dam in the vicinities of the Beaver Valley discharge and Shippingport discharge and above the New Cumberland Dam.
A Ponar or Eckman dredge is used to collect the sample. The
~
sampling locations are also listed in Table V.A.1 and are shown in Figure 5.C.1.
Bottom sediments are analyzed for gross alpha and l~~
beta activity, strontium, uranium, and the gamma-emmitting radionuclides, b.
Analytical Procedures Gross beta - sediments and soils are analyzed for gros's beta by nounting a i gram portion of dried i
sediment in a 2" planchet. The sample is counted in a iow background, gas flow proportional counter.
Self absorption corrections are made on the basis of sample weight.
,ross algha activity of sediment or soil is G
analyzed in the same manner as gross beta except
~~
that the counter is sat up to count only alpha.
Gamma analysis of sediment or soil is performed in a 300 ml plastic bottle which is counted by a gamma spectrometer.
E E
[:
24 f~
SECTION V - C FIGURE 5.C.1 DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report SEDTI:ENTS AND SOTLS p
L FIGURE 5.C.1 EPMRONMENTAL WONITOfuNG LOCATIONS-SFUEllT SEDl?DTS & Soll E
y L4wnoe.c own
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Of WA 3**'h'W *.
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SECTION V - C DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
~
V.
ENVIRONMENTAL MONITORING C.
Monitoring of Sedinents and Soils (Soil Monitoring is required every 3 years and was not required in 1987)
~
(continued) 2.
Sampling Program and Analytical Techniques (continued) l l
b.
Analytical Procedures (continued)
~
Strontium 89 and 90 are determined by 1
radiochemistry. A weighed sample of sediment or soil is leached with Nitric Acid HNO. A stable 3
carrier is added for determination of recovery.
Strontium concentration and purification is ultimately realized by precipitations of strontium nitrate in fuming nitric acid.
Additional hydroxide precipitations and barium chromate separations are also used. The purified strontium is converted to a carbonate for weighing and counting.
Samples are counted soon after
~
separation (5 -
7 days is allowed for yttrium ingrowth).
Activities are calculated on the basis of appropriate Sr-89 decay and Y-90.
Separate 8
mounts covered with a 80 mg/cm aluminum absorber are used for counting in a low backgrornd beta counter.
Uranium isotopic analysis of cediment and soil samples were performed by alpha spectrometry after r
leaching and isolation of the uranium by en ion exchange chromatography plus mercury cathode electrclysis, then electroplated onto a planchet.
I 3.
Rer.ults and Conclusions A summary of data is presented in Table V. A.2, 1
L_
a.
Eediment A total of (8) samples were analyzed for gross
[
alpha and gross beta.
Results were comparable to previous years.
A total of eight (8) samples were analyzed for Sr-
{
89 and Sr-90.
No Sr-89 or Sr-90 was detected.
M F
l SECTION V - C DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
{
V.
ENVIRONMENTAL MONITORING C.
Monitoring of Sediments and Soils (Soil Monitoring is E
required every 3 years and was not required in 1987)
L_
(continued) 3.
Results and Conclusion (continued) a.
Sediment (continued)
E A total of eight (8) samples were analyzed by gamma L
spectrometry. Naturally occurring K-40, Ra-226 and Th-228 was found in every sample and Be-7 was found r
in four samples.
Small amounts of Cs-137 from L
previcus nuclear weapons tests were found in all river sediment samples including upstream above Montgomery Dam which are unaffected by plant effluents. A small amount of Co-58 was detected in one sample downstream of the plant at New Cumberland Dam.
The result was slightly above the p
minimum detectable activity and may be attributed L
to station releases or from expected variability in the analyses results of very low activity.
Small amounts of Co-58, Co-60, Mn-54 and Cs-137 were
~
[
detected in the Beaver Valley Power Stacion discharge area and are attributable to station releases.
The activity found in the station
[
discharge area is consistent with station data of L
authorized radioactive discharges which were within limits permitted by the NRC license, r
L A total of eight (8) samples were analyzed by alpha spectroscopy for uranium.
Naturally occurring uranium was found in all samples.
l' The analyses demenstrace that the Beaver Valley Power Stat t or. did not contribute a significant p
increase of radioactivity in the Ohio River L
sediment.
The positive results detected are attributeble tc authorized releases from the Beaver Valley Power Station and are charccteristic of the effluent.
These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental
{
monitoring program is sufficiently sensitive.
E E
[
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L SECTION Y - D DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING D.
Monitoring of Feederops and Foodcrops r
L 1.
Character 1zation of vegetation end roadcrons J
According to a survey made in 1985, there were approximately 610 farms in Beaver County. The principal source of revenue for the farms was in dairy products I
which amounted to nearly $5,998,000.
Revenees from other farm products were as follows:
Field Crops.
$2,013,000 Fruits 169,000 Horticulture and I
Mushrooms
$ 994,000 Meat and Animal Products.
$1,638,000 Vegetables and I
Potatoes.
S 266,000 Foultry Products S 426,000 I
The total land in Beaver County is 218,600 acres.
Approximately 134,592 acres are forested land and 61,116 acres are pasture and crop land.
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.I.
Each sample is analyzed by gamma i
spectrometry. The monthly samples are composited quarterly sample which is analyzed for Sr-into a 90.
A land use census was performed August, 1987 to locate the nearest residence and nearest garden of I
greater than 500 square feet producing fresh leafy vegetables within a five (5) mile radius of the site.
See Table V.D.1 for results.
Foodcrops (vegetables) were collected at garden locations during the sumer of 1987.
Leafy vegetables, i.e.,
cabbage were obtained from Shippingport, Georgetown,
- Industry, PA, and
- Weirton, WV.
All samples were analyzed for gamma emitters (including I-131 by gamma spectrometry). - - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _
a S
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FEEDCROP AND FOODCROP LOCATIONS FIGUE 5.D.1 e
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L SECT 1os v - o nuocESSE L1GitT c0xersy 1987 Annual Radiological Environmental Report TABLE V.D.1 Closest Residence and Garden in Each Sector Sector Closest Residence
- Closest Garden
- 1 1.55 mi S 1,55 mi N 2
1.59 mi SSE 1.59 mi NSE 3
0.42 mi SE 0.57 mi NE 4
0.38 mi ENE 0.98 mi ENE 5
0.42 mi E 1.84 mi E 6
0.87 mi ESE 1.00 mi ESE 7
1.40 mi S 1.97 mi S 10 0.80 mi SSW 1.55 mi SSV 11 1.46 mi SW 1.72 mi SW 12 1.46 mi WSW 1.46 mi WSW I
13 2.27 mi V 2.27 mi W 14 2.77 mi WSW 2.77 mi WNW 15 0.91 mi NW 0.92 mi NW 16 0.91 mi SSW 1.10 mi NSW I
- 1 ~ " " -e "" "" "
"1er 1= --" E--
5 - - _ - _ _ _ _ _ _ _ _ _
FL SECTION v - D DUQUESNE LIGHT C0h!PANY 1987 Annual Radiological Environmental Report V.
ENYlRON!! ENTAL !!ONITORING D.
?!onitoring of Feederops and Fooderops (continued) 2.
Sampling Program and Analytical Techniques (continued) b.
Procedures Gam:aa emitters, including I-131, are determined by I
scanning a dried, homogenized sample with the gamma spectrometry system.
A Ge(Li) detector is utilized with this system.
I Strontium 90 analysis for feedstuff is performed by a procedure similar to that described in V.C.2.
Radiciodine (I-131) is determined by radiochemistry.
Stable iodide carrier is first added to a chopped sample which is then leached g
g with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and treated with I
sodium hypochlorite.
The iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into chloroform.
It is then back-extracted as iodide into sodium bisulfite solution I
and is precipitated as palladium iodide.
The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
3.
Results and Conclusions A summary of data is presented in Table V.A.2.
2 a.
Feed A total of twelve (12) samples were analyzed for I-131.
No detectable concentrations were found.
A total of four (4) samples were analyzed for Sr-90.
Small amounts of Sr-90 from previous nuclear weapons tests were found in all samples.
A total of twelve (12) samples were analyzed by gamma spectrometry.
Naturally occurring K-40 was found in all samples and Be-7 was detected in nine (9) samples. Cs-137 which was found in one (1) sample is attributable to previous nuclear weapons tests.
l SECTION Y - D DUQUESNE ~.IGHT COMPANY 1987 Annual Radiological Environmental Report I
V.
ENVIRONMENTAL MONITORING D.
Monitoring of Feedcrops and Foodcrops (continued) 3.
Results and Conclusions (continued)
~
b.
Food A total of four (4) samples were analyzed for I-I 131. No det(ctable concentrations were'found.
A total of four (4) samples were analyzed by gamma spectrometry.
Naturally occurring K-40 was found in all samples.
c.
The data from food and feed analyses were I
consistent with (or lower than) those obtained in the pre-operational program.
These data confirm that the Beaver Valley Fower Station did not I
contribute to radioactivity in foods and feeds in the vicinity of the site.
I I
I I
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1 I
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SECTION Y - E DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING E.
1 Monitoring of Local Cow's Milk 1.
Description - Milch Animal Locations L
During the seasons that animals producing milk (milch animals) for human consumption are on pasture, samples of fresh milk are obtained from these animals at locations and frequencies noted in Table V.A l.
This milk is analyzed for its radiolodine content calculated as Iodine-131. The analyses are performed within eight (8) days of sampling.
Detailed field surveys are performed during the grazing season to locate and enumerate milch animals within a five (5) mile radius of the site.
Goat herd locations out to fifteen (15) miles are identified.
Survey data for the most recent survey conducted in August, 1987 is I
showr in Figure 5.E.1.
2.
Sampling Program and Analytical Techniques a.
Program Milk was collected from three (3) reference dairy i
farms (Searights, Brunton and Nicol's) within a 10-mile radius of the site and from one (1) control location (Windsheimer's) outside of the 10-mile I
radius.
Additional dairies, which represent the highest potential milk pathway for radiciodine based on milch animal surveys and meteorological I
data were selected and sampled. These dairies are subject to change based upon availability of milk or when more recent data (milch animal census) indicate other locations are more appropriate. The I
location of each is shown in Figure 5.E.2 and described below.
I Number of Milch Direction and Distance from Collection Site Dairy Animals Midpoint between Reactors Period 25 Searight 46 Cows 2.2 miles SSW Jan. - Dec.
27 Brunton 115 Cows 7.3 miles SE Jan. - Dec.
29A Nichol 130 Cows 8.0 miles NE Jan. - Dec.
I 96 Windsheimer 100 Cows 10.3 miles SSW Jan. - Dec.
61**
Allison 36 Cows 3.3 miles WSW Jan. - Apr.
I I
I l
SECTION Y - E DUQUESNE LIGHT C0liPANY 1987 Annual Radiological Environmental Report V.
ENVIRON 51 ENTAL MONITORING E.
Monitoring of Local Cow's Milk (continued) 2.
Sampling Program and Analytical Techniques (continued) a.
Program (continued)
Number g
3 of Milch Direction and Distance from Collection Site Dairy Animals Midpoint between Reactors Period 69*
Collins 8 Goats
- 3.5 miles SE Feb. - Apr.
62**
Lyon 21 Cows 3.A miles WSW Jan. - Apr.
96**
Foxall (Hammond) 4 Goats
- 3.0 miles ESE May - Dec.
I 10l*'
Teless 10 Goats
- 2.6 miles E May - Dec.
102*
Ferry 10 Goats
- 3.3 miles SE May - Dec.
- Milk Usage - Home Only.
- Highest potential pathway dairies.
I I
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FIGURE 3,E,1 DLQUEShE LIGHT CO.iPAa7 SECTIO'; V - 2 1987 Annual dadiological Environmental iseport BE AVER VAL LEY MILCH ANIM AL CE NSUS vou mu s
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FIGURE 5.E.2 SECTION V - E DUQUESNE LIGHT COITANY 1987 Annual Radiological Environmental Report i
FIGURE 5.E.2 f
ENVIRONWENTAL WONtTORlW LOCATIONS-MilX
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flGIE 5. E. 2 SECTION V - E DUQUESSE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING E.
Monitoring of Local Cow's Milk (continued) 2.
Sampling Program and Analytical Techniques (continued) a.
Program (continmed)
The sample from Searight Dairy was collected and analyzed weekly for radiciodine using a procedure with a high sensitivity.
Samples from each of the other selected dairies were collected monthly when cows are indoors, and bi-weekly when cows are grazing.
This monthly or bi-weekly sample is analyzed for Sr-89, Sr-90, gamma emitters including Cs-137 (by Spectrometry) and I-131 (high sensitivity analysis).
b.
Procedure Radiolodine (1-131) analysis in milk was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
Gamma emitters are determined by gamma spectrometry of a one litet Marinelli container of milk.
Strontium analysis of milk is similar to that of other foods (refer to V.C.2) except that milk I
samples are prepared by addition of Trichloracetic Acid (TCA) to produce a curd which is removed by filtration and discarded. An oxalate precipitate is ashed for counting.
3.
Results and Conclusions A summary of data is presented in Table V.A.2.
A total of one hundred sixty-seven (167) samples were analyzed for 1-131 during 1987. All I-131 activities in milk were below the minimum detectable level.
A total of one hundred thirty-five (135) samples were analyzed for Sr-69 and Sr-90.
No Sr-89 was detected.
Sr-90 levels attributable to previous nuclear weapons tests were detected in one hundred thirty-two (132) samples and were within the normally expected range. -
SECTION V - E DUQUESNE LIGilT COMPANY 1987 Annual Radiological Environmental Report V.
ENV RONMENTAL MONITORING E.
Monitoring of Local Cow's Milk (continued) iL 3.
Results and Conclusions (continued)
A total of one hundred forty-two (142) samples were analyzed by gamma spectrometry. The predominant isotope naturally occurring K-40 and wa,s found in detected was all samples. Cs-137 which is attributable to previous nuclear weapons tests was detected in eighteen (18) samples.
All results were consistent with (or lower than) those obtained in the preoperational program.
These data confirm that the Beaver Valley Power Station did not contribute to radioactivity in milk in the vicinity of the site. >
L, SECTION V - F DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
[
V.
ENVIRONMENTAL MONITORING F.
Environmental Radiation Monitoring 1.
Description of Regional Background Radiation Levels ap Sources j
The terrain in the vicinity of the Beaver Valley Power Station generally consists of rough hills with altitude variations of 300-400 feet. Most of the land is wooded.
The principal geologic features of the region are nearly flat-laying sedimentary beds of the Pennsylvania Age.
Beds of limestone alternate with sandstone and shale with abundant interbedded coal layers.
Pleistocene glacial deposits partially cover the older sedimentary deposits in the northwest.
Most of the region is
[
underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams.
u Based on surveys reported in previous annual reports, exposure rates ranged from 6-12 ttR/hr. Results for 1987 indicated that background radiation continued in this range.
2.
Locations & Analvtical Procedures Ambient external radiation levels around the site were i
1 measured using thermoluminescent dosimeters (TLDs).
In 1987 there were a total of forty four (44) off-site
~
environmental TLD locations. The locations of the TLDs are shown in Figures 5.F.1 thru 4.
Thirteen (13) locations also have QC Laboratory TLDs.
Both laboratories use calcium sulphate dysprosium, CaSO. (Dy) in teflon matrix.
E E
M
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i
.J SECTION Y - F DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING F.
Environmental Raaistion Monitoring (continued) 2.
Locations & Analytical Procedures (continued)
~
The calciun sulfate (CaSO.:Dy) TLDs were annealed shortly before placing the TLDs in their field locations.
The radiation dose accumulated in-transit between the field location and the laboratory was corrected by annealing control dosimeters shortly before the field dosimeters were removed from the field location, when shipping the freshly annealed control dosimeters with the exposed field dosimeters to the laboratory for readout at the same time.
All dosimeters were exposed in the field in a special environmental holder.
The dosimetry system was calibrated by reading calcium sulfate dosimeters which have been exposed in an accurately known gamma radiation field.
In addition to TLDs, Pressurized lon Chambers (PIC) provide continuous integrating monitoring.
Sixteen PICS (Sites 1-16) are part of the Sentri 1011 Radiation Monitoring System which is a microcomputer-based data acquisition system. Data from the stations are sent at regular intervals to the Central Processing Unit where integrated doses are calculated.
In addition 1here are four PICS which are AC Radiation Monitors.
These are inspected weekly for integrator readings. The locations of the PICS are shown in Figure S.T.5.
3.
Results and Ccnclusions Data obtained with the contractor TLD (CaSO.:Dy in I
teflen) during 1GS7 are summarized in Table V.A.2, and the quality control TLD results are listed in Table 111.1.
Results for the PICS are listed in Table V.F.1.
I The annual exposure rate of all off-site TLDs averaged 0.17 mR/ day in 1967.
As in previous years, there was l
some variation among locations and seasons as would be y
expected.
in 1957, ionizing radiation dose determinations from I
TLDs averaged approximately 62 mR for the year. This is comparable to previous years.
There was no evidence of anomalies that could be attributed to the operation of I
the beaver Valley Power Station. The TLDs confirm that changes from natural radiation levels, if any, are neglible.
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DUQUESNE LIGilT C01'PANY 1987 Annual Radiological Environmental Report MontHEAsi euAtwiAN,T u
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L SECTION Y - F DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report TABLC Y.F.1
{
Pressurized Ion Chambers - Results Distance I
and Direction from ?!idpoint AWrage jpM[ day]
R Site Location Between Reactors 1
Industry Hill 0.5 mi N 0.210 2
Industry - Rt. 68 0.9 mi NNE 0.218 3
Industry 2.25 mi NE 0.192 4
Cooks Ferry 0.5 mi ENE 0.217 5
Shippingport Bridge South 0.45 mi E 0.222 6
BVPS Entrance 0.4 mi ESE 0.231 7
Unit #2 Laydown 0.3 mi SE 0.219 8
Birdhill Road 0.9 mi SSE 0.247 9
Past DLCO Microwave 0.35 mi S 0.252 10 DLCO Microwave 0.35 mi SSV 0.216 11
?! eyer's Farm
- 1. 5 +1 SV 0.236 12 J 6 L Steel Tie 0.75 mi VSV 0.220 13 F. P. Microwave 1.5 mi V 0.176 14 Midland Substation South 0.6 mi WNV 0.228 15
!!idland Substation North 0.75 mi NV 0.235 16 Sunrise Hills 1.1 mi NNV 0.221 AC-201 Raccoon r!unicipal Building 2.4 mi SE 0.251 AC-202 Kennedy's Corners 2.0 mi NE 0.253 Z-054 Hookstown Substation 2.9 mi VSW 0.232 Y-028 J6L 1.3 mi NW 0.218 1
b SECTION Y - G DUQUESNE LIGirr COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING G.
Monitoring of Fish 1.
Description Fish collected near the site are generally scrap fish.
During 1987, fish collected for the radiological monitoring program included carp, catfish, smallmouth I
bass, sheephead and walleye.
2.
Sampling Program and Analytical Techniques I
a.
Program Tish samples are collected semi-annually in the New I
Cumberland pool of the Ohio River at the beaver Valley effluent discharge point and upstream of the Montgomery Dam.
The edible portion of each I
different species caught is analyzed by gamma spectrometry.
Fish sampling locations are shown in Figure 5.G.I.
b.
Procedure A saeple is prepared in a standard tared 300 ml i
plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a Ge(Li) detector.
I 3.
Results and Conclusions A summary of the results of the fish monitoring data is I
provided in Table V.A.2.
A total of eight (8) samples were analyzed by gamma I
spectrometry.
Naturally occurring K-40 was found in all saeples.
A trace amount of Co-56 was detected in one sample and is attributable to station releases.
The I
activity found is consistent with station data of authorized radioactive discharges which were well within the limits permitted by the NRC license.
The analyses demonstrate that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in the Ohio River fish population.
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ENVIRONMENTAL MONITORING PROGRAM y
FISil SAMPLING LOCATIONS 7
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SECTION V - H DUQUESNE LfGHT COMPANY 1987 Annual Radiological Environmental Report
{
V.
ENVIRONMENTAL MONITORING H.
Menitoring of
- Surface, Drinking, Well Vaters and 7
Precipitation 1.
Description of Vater Sources The Ohio River is the main body of water in the area.
It is used by the Beaver Valley Power Station for plant make up for the cooling tower and for receiving plant
{
liquid effluents.
Ohio River water is a source of water for some towns both upstream and downstream of the Beaver Valley Power 7
L Station site.
It is used by several municipalities and industries downstream of the site. The nearest user of the Ohio River as a potable water source is Midland l
Borough Municipal Water Authority. The intake of the L
treatment plant is approximately 1.5 miles downstream and on the opposite side of the river.
The next r
downstream user is East Liverpool, Ohio which is L
approximately 6 miles downstream. The heavy industries in Midland, as well as others downstream use river water for cooling purposes.
Some of these plants also have
[
private treatment facilities for plant sanitary water.
Ground water occurs in large volumes in the gravel F
terraces which lie along the river, and diminishes L
considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) with occasional wells yielding up to 60 gPm.
In general, the BVPS site experiences cool winters and
{
moderately warm summers with ample annual precipitation evenly distributed throughout the year. Normal annual precipitation for the area is 36.29 inches based on 1951 r
to 1980 data collected at the Pittsburgh International L
Airport.
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SECTION V - H DUQUESNE LIGHT CO.'!PANY 1987 Annual Radiological Environmental Report l
Y.
ENVIRON!! ENTAL ?!ONITORING (centinued)
H.
Monitoring of
- Surface, Drinking, Well
- Vaters, and l
Precipitation (continued) 2.
Sampling and Analvtical Techniques
{
a.
Surface (Raw River) Vater The sampling program of river water Includes six l
(6) sampling points along the Ohio River.
Raw i
water samples are normally collected at the East i
Liverpool (Ohio) Vater Treatment Plant [ River Mile 41.2]
daily and composited into a monthly sample.
[
Weekly grab samples are taken from the Ohio River at the discharge following locations: upstream of Montgomery Dam [ River Mile 31.6]; from Shippingport
[~
Station Decommissioning Project [ River Mile 34.8);
L 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 g
at J5L Steel's river water intake [ River Mile 36.2].
The automatic sampler takes a 20-40 ml F
sample every 15 minutes and is collected on a L
weekly basis.
The weekly grab samples and automatic water samples are composited into monthly I
f c-samples from each location.
In addition, a L
quarterly composite sample is prepared for each sample point.
The monthly composites are analyzed for gross alpha, gross beta, and gamma emitters.
The quarterly composites are analyzed for H-3. Sr-89, Sr-90, and Co-60 (high sensitivity).
Locations of each sample point are shown in Figure 5.H.1.
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b.
Drinking Vater (Public Supplies)
{
Drinking (treated) water is collected at both Midland (PA) and East Liverpool (OH) Vater Treatiug Plants.
An automatic sampler at each location collects 20-40 ml every 20 minutes.
These p
intermittent samples are then composited into a a
weekly sample.
A weekly grab sample is also taken at the DLC Training Building in Shippingport, PA.
l The weekly sample from each location is analyzed by gamma spectrometry.
The weekly samples are also analyzed for I-131.
i
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-100 F
[
SECTION V H
DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
[~
V.
ENVIRONMENTAL MONITORING L
H.
Monitoring of
- Surface, Drinking, Well
- Waters, and Precipitation (continued) 2.
Sampling and Analytical Techniques (continued)
{
b.
Drinking Water (Public Supplies) (continued)
Honthly 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.i.
c.
Ground Water Grab samples were collected each quarter from each of four (4) well locations (see Figure 5.H.1) within four (4) miles of the site. These locations are:
One (1) well at Shippingport, PA one (1) well at Meyer's Farm (Hookstown, PA)
~
One (1) well in Hookstown, PA One (1) well in Georgetown, PA Each ground water sample is analyzed for gross alpha, gross
- beta, tritium, and by gamma s
spectrometry.
d.
Precipitation p
Precipitation is collected at Shippingport (PA),
L East Liverpnol (OH) and Weirton (WV).
Precipitstion when available is collected each week and then composited into mon.hly and quarterly a
I
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saeples.
The monthly samples are analyzed for gross beta and gamma emitters and the quarterly composites are analyzed for H-3 Sr-89 and Sr-90.
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Locations of each sample point are shown in Figure 5.H.1.
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SECTION Y - H DUQUESNE LIGHT COMPANY
^
1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL HONITORING L
H.
Monitoring of
- Surface, Drinking, Well
- Vaters, and Precipitation (continued)
~
2.
Sampling and Analvtical Techniques (continued)
[
e.
Procedures Gross alpha and gross beta activities are I
determined first by evaporating one liter of the L
sample on a hotplate. The residue is mounted and dried on a 2 inch stainless steel planchet.
The sample is counted in a low background, gas flow L
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 ellt?inated.
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 s a:cples by converting 2 ml of the sample to hydrogen and
{
counting the activity in a 1 liter low level gas counter which is operated in the proportional range in anti-coincidence mode.
Radiciodine (I-131) analysis in water was normally performed using chemically prepared samples and analyzed with a low-level beta counting system.
3.
Results and Conclusions
~
A summary of results of all analyses of water samples (surface, drinking, ground and precipitatiou) are provided by sample type and analysis in Table V.A.2.
These are discussed below.
m-n
-103-l F
L SECTION V H
DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING
~
H.
Monitoring of
- Surface, Drinking, Vell
- Vaters, and Precipitation (continued) 3.
Results and Conclusions (continued)
~
a.
Surface Vater A total of seventy-two (72) samples were analyzed for gross alpha and gross beta.
All alpha results were within the normal range.
Positive beta results above preoperational levels were detected in the BVPS discharge area and are attributable to station releases. The beta activity found in the station discharge area is consistent with station data of authorized radioactive dischstges and were within limits permitted by the NRC license.
A total of twenty-four (24) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity analysis for Co 60.
Positive tritium and Co 60 results were detected in the BVPS discharge area and are attributable to station releases.
Tritium samples taken upstream and downstrcum weta within pre opera *.ional levels. No Sr-89, Sr-90 or Co 60 (analyzed by the high sensitivity method) were detected.
The tritium activity found in the station discharge area is consistent with statien data of authorized radioactive discharges and were within limits permitted by the NRC license.
A total of seventy-seven (77) samples were analyzed by gar.ma spectrometry.
Positive Co-58 and Co-60 results were detected in the BVPS discharge area and are attributable to station releases. The Co-SS and Co 60 activity found in the station discharge area is consiatent with station data of authorized radioactive discharges and were within limits permitted by the NRC license.
Naturally occurring K-40 was detected in one sample collected from J5L Steel.
No other gamma emitting radionuclides were detected.
-104-
I SECTION Y - H DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report E
V.
ENVIRONMENTAL MONITORING L
H.
Monitorint of
- Surface, Drinking, Velt
- Vaters, and Precipitation (continued) l^
3.
Results and Conclusions (continued)
{
a.
Surface Water (continued)
A positive beta and Co 60 result above preoperational levels was detected in one sample
~
L taken from the Shippingport Station Decommissioning discharge area.
A review of the Beaver Valley Power Station discharge permits was made as the
[
BVPS discharge area is adjacent to tha 3hippingport discharge area. The review showed no releases from the BVPS site were being conducted at the time of saepling.
The concentrations seen are consistent with those reported by the Shippingport Station Decommissioning Project for 1987 and are hundreds of times below the concentrations permitted by DOE
- Orders, b.
Drinking Water L
A total of thirty six (36) samples were analyzed for gross alpha and gross beta. All results were r
within a normal range.
L A total of twelve (12) samples were analyzed for H-3, Sr-89 and Sr-90 as well as a high sensitivity
-[
analysis for Co 60.
- detected, The H3 data were within the pre-operational range indicative of normal environmental levels.
A total of another one hundred fifty six (156) samples were analyzed by gamma spectrometry.
Naturally occurring K 40 was detected in one sample.
{
A total of one hundred fifty-six (156) samples were analyzed for I-131 using a highly sensitive technique.
Trace levels of Io131 were measured in two of the weekly samples.
The results were slightly above the minimum detectable activity.
n The positive results could not be attributed to station discharges. The results may be attributed
{
to expected variability in the analyses results of very low levels of activity or other scurces such as from medical.
m
-105-j r
SECTION V - H DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING (continued)
H.
Monitoring of
- Surface, Drinking, Well
- Waters, and Precipitation (continued) 3, Results and Conclusions (continued) c.
Well Water A total of sixteen (16) samples were ea'ch analyzed for gross alpha, gross beta, H-3 and by gamma A.
spectrometry.
No alpha activity was detected in N
any of the samples. The gross beta and H-3 data i
are within pre-operational ranges.
Naturally occuring K-40 was detected in one sample.
d.
Precipitation A total of thirty-three (33) samples were cnalyzed for gross beta.
All results were within a normal range.
A total of twelve (12) samples were analyzed for H-3 Sr-89 and Sr-90.
Four positive tritium results were detected which were within normal levels and no Sr-89 or Sr-90 was detected.
A total of thirty-three (33) samples were analyzed by gamma spectrometry.
Naturally occurring Be-7 was detected in seventeen (17) samples.
J 1
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1 1
I
-106-1
SECTION V - H DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING (continued)
H.
Monitoring of
- Surface, Drinki,g, Well
- Waters, and Precipitation (continued) 7L 3.
Results and Conclusions (continued) e.
Summary The data from water snalyses demonstrates that the Beaver Valley Power Station did not contribute a significant increase of radioactivity in local river, drinking, well waters or precipitation.
The few positive results which could be attributable to authorized releases from the Beaver Valley Power Station are characteristic of the effluent. These results confirm that the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.
- Further, the actual detected concentration
]
(averaged over a year) attributable to Beaver Valley Power Station, was only 1.027% of the Maximum Permissible Concentration allowed by the
~
Federal Regulations for kater discharged to the Ohio River. The Ohio River further reduced this concentration by a factor of ~ 600 prior to its potential use by members of the public.
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L SECTION V - I DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
[
V.
ENVIRONMENTAL MONITORING 1.
Estimates of Radiation Dose to Man F
L 1.
eathways to Man - calculational Models The radiation doses to man as a result of Beaver Valley operations were csiculated for both gaseous and liquid effluent pathways using NRC computer codes X0QD0Q2, GASPAR, and LADTAP. Dose factors listed in the ODCM were used to calculate doses to maximum individuals from radioactive noble gases in discharge plumes.
Beaver Valley effluent data, based on sample analysis in accordance with the schedule set forth in Appendix A of the BVPS license, were used as the radionuclide activity input.
Each radionuclide contained in the Semi-Annual Radioactive Effluent Release Report (noble
- gases, particulates, radioiodines and tritium) were included as source terms when they were detected above the LLD values.
All LLD values reported by Beaver Valley Power Station are equal to or lower than those required by the Technical Specifications.
All gaseous 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 to either measured
~
appropriate but conservative ratio activity of Kr-85 or Xe-133 was used. Meteorological data collected by the Beaver Valley Power Station Meteorology System was used as input to X0QD0Q2 which in turn provided input for GASPAR. Except when more recent or specific data was available, all inputs were the same as used in the Beaver Valley Power Station Environmental in Regulatory Guide 1.109.
The airborne Statements or pathways evaluated were beta and gamma doses from noble gas plumes inhalation, the "cow-milk-child", and other ingestion pathways.
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-108-r a
SECTION V - I DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report V.
ENVIRONMENTAL MONITORING I.
Estimates of Radiation Dose to Man (continued) 1.
Pathways to Man - Calculational Models (continued)
All potentially radioactive liquid effluents, including steam generator blowdown, are released by batch mode after analysis by gamma spectrometry using Intrinsic I
Germanium detectors.
Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River at the Beaver Valley Power Station outfc11 (River i
Mile 35.0)
The actual data f ro 1 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 i
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 I
Pathways, which were evaluated, are drinking
- water, fish consumption, shoreline recreation, swimming, and boating.
2.
Results of Calculated Radiation Dose to Man - Liquid Releases a.
Individual Dose The doses which are calculated by the model I
described above are to a
hypothetical real individual located at Midland since this is the nearest location where significant exposure of a member of the public could potentially occur; I
therefore, this location is used to calculate the maximum exposure. A breakdown of doses by pathway and organ is provided in Table V.I.1 for the I
maximum individual.
Included in this table is a breakdown of a typical dose to individuals from natural radiation exposure.
The results of I
calculated radiatien dose to the hypothetical real individual are compared to BVPS annual limits in Table V.I.2.
b.
Upon implementation of the Unit 2 Technical Specifications and inception of the liquid discharge procedures at Unit 2 on July 24, 1987, I
the discharge limits were clarified to be reactor specific; i.e.,
Unit 1 and Unit 2 have individual (not combined) dose limits. Therefore, the annual limits listed in Table V.I.2 were derived by I
multiplying the individual Technical Specification reactor limits by a factor of two (2).
I
-109-I
D 1
U I
h C
i J
t m
o m
EUU 7 1
TABLE V.I.1 Radiation Dose to Maximum Individual" mrem /yr.
b Beaver Valley Power Station - Liquid Releases un MAXIMUM USAGE WlIOLE E
GROUP FACTOR SKIN ORGAN THYROID BONE BODY PTMY Z
l Fish Consumption" Adult 21.0 kg N/A 0.000792 0.000701 0.000242 0.000380 (GI-LLI)
Drinking Water Infant 510 liter N/A 0.00570 0.0139 0.000141 0.00569 (GI-LLI) u Shoreline Activities Teen 67 hr.
0.00016 0.00014 5
1 l
U es TOTAL MREM 0.00016 0.00570 0.0139 0.000373 0.00569
- o E b
MAXIMUM (Teen)
(Infant)
(Infant)
(Child)
(Infant)
$. EE o
INDIVIDUAL (GI-LLI) o "3 ym s
oo t-TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE
? ?i d
Ambient Camma Radiation:
69 gg
{4 28" g
Radionuclides in Body :
o.',
4*
S Global Fallout
?
4 TOTAL mrem 101 H
E
^ Located at Midland Drinking Water Intake g
b Total liquid releases are from Site (combined Units 1 and 2)
Child is the critical group for bone with a dose of 0.000304 mrem /yr.
h d
M Pre-operational average ambient gamma radiation j
" National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1980 l
lL SECTIOS V - I DUQUESSE LIGHT COMPANY 1987 Annual Radiological Environmental Report TABLE V.I.2 Results of Calculated Radiation Dose to Man Beaver Valley Power Station - Liquid Releases i
Maximum Exposure Hypothetical BVPS Annual Percent of Real Individual Limits Annual I
mrem mrem Limit TOTAL BODY Adult 0.00386 6.0 0.064 Teen 0.00219 6.0 0.037 Child 0.00392 6.0 0.065 I
Infant 0.00569 6.0 0.095 ANT ORGAN Adult 0.00575 20.0 0.029 (Thyroid)
Teen 0.00387 20.0 0.019 (Thyroid)
Child 0.00775 20.0 0.039 (Thyroid)
I Infant 0.0139 20.0 0.070 (Thyroid)
Maximum Total Body Dose - Capsule Summary mrem i
1987 Calculated 0.00569 Final Environmental Statement 3.5 Highest Organ Dose 1987 Calculated 0.0139 Final Envircsnmental Statement 4.7
-111-
SECTION V - I DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
[
V.
ENVIRONMENTAL MONITORING I.
Estimates of Radiation Dose to Man (continued) 2.
Results of Calculated Radiation Dose to Men - Liquid Releases (continued)
Population Dose c.
The 1987 calculated dose to the entire population
{
of almost 4 million people within 50 miles of the plant was:
Largest Isotom
[L Man-Millirem Contributo1 TOTAL BODY 192 H-3 188 mrem Co-58 2.78 mrem Co-60 0.74 mrem THYROID 268 H-3 188 mrem I-131 67.9 mrem i
I-133 12.4 mrem 3.
Results of Calculated Radiation Dose to Man - Airborne Releases The results of calculated radiation dose to the maximum exposed individual for BVPS airborne radioactive
~
effluents during 1987 are provided in Table V.I.3.
The doses include the contribution of all pathways.
A 50-mile population dose is also calculated and provided in Table V.I.3.
H-3 is the primary radionuclide
[
contributions to these doses.
The results are compared to the BVPS annual limits in Table V.I.3.
As in the liquid discharge limits, the
{
gaseous effluent limits are reactor specific; i.e.,
Unit 1 and Unit 2 have individual (not combined) dose limits.
Therefore, the annual limits listed in Table V.I.3 were derived by multiplying the individual Technical Specification reactor limits by a factor of two (2).
The results show compliance with the BVPS annual limits.
m E
-112-F
F L
SECTION V - I DUQUESNE LIGHT COMPANY 1987 Annual Radiological Environmental Report
{
V.
ENVIRONMENTAL MONITORING I.
Estimates of Radiation Dose to Man (continued) 4.
Conclusions - (Beaver Valley Power Station)
Based upon the estimated dose to individuals from the natural background radiation exposure in Table V.I.1.,
the incremental increase in total body dose to the 50-mile population (4 million people), from the operation
{
of Beaver Valley Power Station - Unit No. 1 and No. 2, 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. 1 and No. 2, are below BVPS annual limits and resulted in only a small incremental dose to that which area residents already
(
received as a result of natural background. The doses constituted no meaningful risk to the public.
[
[
immuni E
E umune W
-113-F
M'M M
M M
M M
\\
m V-L___J 1
I TABLE V.I.3 Results of Calculated Radiation Dose to Man (1987)
O Beaver Valley Power Station - Airborne Radioactivity O
t m
50-MILE MAXIMUM EXPOSURE BVPS ANNUAL LIMIT PERCENT OF POPULATION DOSE ORGAN INDIVIDUAL, mrem mrem ANNUAL LIMIT man rem G
O TOTAL BODY 0.121 30 0.40 0.708 E
SKIN 0.158 30 0.53 1.10
$e
- n E LUNG 0.122 30 0.41 0.721
$.E
-m TilYROID 0.202 30 0.67 1.79 ilC ge
~1 E9
- ii6 2B B*
8 2"
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G Uw I
I L
DISTRIBUTION LIST r
l United States Nuclear Regulatory Commission (18 copies)
Attn:
Mr. Peter Tam, Project Manager Operating Reactors Branch No. 1
[
Division of Licensing L
c/o Document Control Desk Washington, DC 20555 United States Nuclear Regulatory Commission (2 copies)
Office of Inspection and Enforcement Attn: Regional Administrator, Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. A. A. Davis, Secretary Department of Environmental Resources Commonwealth of Pennsylvania 9th Floor, Fulton Building Third and Locust Streets Box 2063 Harrisburg, PA 17120 United States Department of Energy Technical Information Center Post Office Box 62 p
L Oak Ridge, TN 37830 Mr. J. G. Yusko
(
Department of Environmental Resources Bureau of Radiation Protection 121 South Highland Avenue Pittsburgh, PA 15206 W. W. von Schack, Chairman of the Board and President Duquesne Light Co:cpany
[
One Oxford' Centre 301 Grant Street Pittsburgh, PA 15279 J. J. Carey, Executive Vice President Operations p
Duquesne Light Company L
One Oxford Centre 301 Grant Street Pittsburgh, PA 15279 J. D. Sieber, Vice President Nuclear Group Duquesne Light Company
[
P.O. Box 4 Shippingport, PA 15077 E
F
DISTRIBLTION LIST (continued)
L W. S. Lacey, General Manager Nuclear Operations
{
Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 J. O. Crockett, General Manager Corporate Nuclear Services
(
Duquesne Light Company P.O. Box -
Shippingport, PA 15077 N. R. Tonet, Manager Nuclear Engineering Duquesne Light Company p
L P.O. Box 4 Shippingport, PA 15077
{
S. L. Pernick, Manager Environmental Afrairs Duquesne Light Company One Oxford Centre
[L 301 Grant Street Pittsburgh, PA 15279 r
C. E. Ewing, Manager Quality Assurance I
Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 J. A. Kosmal, Manager Radiological Control Duquesne Light Company I
P.O. Box 4 Shippingport, PA 15077 W. F. Wirth, Director Effluent Control and Environmental Monitoring i
Duquesne Light Company P.O. Box 4 Shippingport, PA 15077 B. P. Jones Memorial Library 663 Franklin Avenue Aliquippa, PA 15001 I
I I
p
=
A
"! pT A
Tetephone (412) 393-6000 b,
.O.
x4
~
SNppmgport, PA 15077-0004 April 25, 1988 ND3VPN:5448 United States Nuclear Regulatory Commission Document-Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station Unit No. 1 Docket No. 50-334, License No. DRP-66 Beaver Valley Power Station Unit No. 2 Docket-No..50-412, License No. NPS-73 1987 Annual Environmental Report Radiological - Volume #2
,n h
Gentlemen:
Under the Beaver Valley Power Station Unit No.1 License DRP-66, Beaver Valley Power Station Unit No. 2 License NPS-73 and in accordance with the requirements of Specifications 6.9.1.10 for the Technical Specifications, the 1987 Annual Radiological Environmental Report is hereby submitted.
Very truly yours, b
3 J. D. Sieber Vice President, Nuclear
..JWM :mb Enclosure United States Nuclear Regulatory Commission cc:
Regional Administrator, Region 1 i
631 Park Avenue i
King of Prussia, PA 19406 United States Nuclear Regulatory Commission
(
Resident Inspector Beaver Valley Power Station l
Dottie Sherman-f American Nuclear insurer's Library b
l The Exchange Suite 245 f
L 270 Farmington Avenue l~
Farmington, CT 06032
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