ML20206E589
| ML20206E589 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1998 |
| From: | Dubois A, Ewing E, Hood G ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-99-0063, W3F1-99-63, NUDOCS 9905050176 | |
| Download: ML20206E589 (200) | |
Text
.
y Ent: gy per ti:ns,inc.
Killona. LA 70066 Tel 504 739 6242 Er C. Ewing, lil JC Baf Sa ety & Regulatory Affaws W3F1-99-0063 A4.05 PR April 29,1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Annual Radiological Environmental Operating Report Gentlemen:
Attached is the Annual Radiological $nvironmental Operating Report for the period of January 1 through December 31,1998. This report is submitted pursuant to the requirements of Waterford 3 Technical Specification Section 6.9.1.7.
If there are any questions, please contact Roy Prados at (504) 739-6632.
Very truly yours,
)
E.C. Ewing i
u I ar Safety & Regulatory Affairs b
f ECE/RWP/rtk g,101 Attachment cc:
E.W. Merschoff, NRC Region IV, P. Patel, NRC-NRR, P.A. Harrell, NRC Region IV, A.L. Garibaldi, P. Lewis - INPO Records Center, J. Smith, N.S. Reynolds, NRC Resident inspectors Office, Administrator Radiation Protection Division (State of Louisiana) 9905050176 981231' ADOCK 05000382((
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= ~ Entergy Annual Radiological Environmental ~
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b Waterford 3 Steam Electric Station E.ntergy Operations, Inc.
' Docket Number 50-382 License Number NPF-38 l
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- AnnualRadiological 1998 Environmentd Operating Report Waterford 3 Steam Electric Station h
gpf 4/f9/99 Originator:
,n, V,1)Je Ann V. Dubois Chemistry Technician Date Waterford 3 SES Reviewed By:
b7 yj f. L l j
9/geg Gregory L. Hood Chendth Supervisor Date Waterford 3 SES Approved By:
jag V, 7&% /%
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Aaron S. Bergeron hemistry S'uperintendent Datel
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v Waterford 3 SES
r; Annual Radiological'
' Environmental Operating Report.
1998 Waterford 3 Steam Electric Station ABSTRACT This report is issued pursuant to Waterford 3 Technical Specification 6.9.1.7. Its purpose is to discuss the Waterford 3 Radiological Environmental Monitoring Program (REMP), present the results of the program for the year of 1998, and evaluate the radiological impact on the environment resulting from plant operation.
The Waterford 3 REMP collected data on environmental radioactivity levels around the Waterford 3 nuclear power plant. These levels were determined by analyzing samples of air, water, shoreline soil, fish, vegetation, and milk from various locations around the facility. Based on the evaluation of the environmental data collected,. the operation of Waterford 3 exhibited no discemable impact on the levels of radioactivity in the environment during 1998.
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Annual Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS Page ABSTRACT
....i TABLE OF CONTENTS..
. li LIST OF TABLES
.iv LIST OF FIGURES
.. vi
1.0 INTRODUCTION
..1 1.1 Program and Report Objectives.
.1 1.2 Plant and Site Description.......
.1 2.0 PROGRAM DESCR!PTION...
.. 2 l
2.1 History and Development....
.......2 2.2 Responsibilities...
.2
.)
2.3 Sample Collection and Handling Procedures..
.....2 2.3.1 Direct Radiation Exposure Pathway Samples.
.3 2.3.2 Airborne Exposure Pathway Samples......
.3 2.3.3 Waterborne Exposure Pathway Samples.......
.... 3 2.3.4 lagestion Exposure Pathway Samples.......
.4 2.4 Analytical Procedures by Environmental Services Laboratory...
.4 2.4.1 Sample Handling and Treatment....
..4 2.4.2 Sample Analysis.
.5 2.4.3 Data Reporting..
.7 j
2.5 Environmental Dosimetry.
..7 2.6 Lower Limits of Detection (LLD).
..7 2.7 Laboratory Quality Assurance......
.8 l
2.7.1 Environmental Service Laboratory.
...8 li
F Annual Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS (Continued)
Page 3.0 DISCUSSION OF RESULTS......
.. 25 3.1 '
Direct Radiation Exposure Pathway..
.. 25 3.2 Airbome Exposure Pathway.......
.25 3.2.1 Airborne Particulates..
.. 25 3.2.2 Airborne lodine...
.25 3.2.3 Gamma Isotopic Analysis.
.. 26 3.3 Waterborne Exposure Pathway...
. 26 3.3.1 Drinking / Surface Water.
. 26 3.3.2 Groundwater..
. 27 -
3.3.3 Shoreline Sediment.
. 27 3.4 Ingestion Exposure Pathway...
.28 3.4.1 Milk.
.28 i
3.4.2 Fish...
.28 3.4.3 Broad Leaf Vegetation.......
.28 3.5 Statistical Analyses.....
.28 3.5.1 Calculation of the Mean and Standard Deviation.
.28 3.5.2 Comparing Two Sample Population Means.....
.. 29 3.5.3 TLD Measurements......
. 30
)
3.5.4 Gross Beta Activity on Air Particulate Filters.
.. 30 3.5.5 Gross Beta Activity in Monthly Drinking Water Composites..
.. 30 3.6 Deviations from the REMP...
. 30 3.6.1 Unavailable Samples...
. 30 3.6.2 Lack of Sample Continuity.........
. 30 3.6.3 Missed Lower Limits of Detection.
. 30 3.7 1998 Land Use Census..
. 31
4.0 CONCLUSION
S......
. 41 APPENDIX A REMP DATA
SUMMARY
.42 i
APPENDIX B REMP DATA...
.49 iii
Annual Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station 1
TABLE OF CONTENTS (Continued)
Page i
LIST OF TABLES l
l TABLE 2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING....
.. 10 PROGRAM (REMP)
SUMMARY
4 TABLE
2.2 DESCRIPTION
OF REMP SAMPLING LOCATIONS.
.11 TABLE 2.3 DETECTION CAPABILITIES FOR ENVIRONMENTAL
.18 SAMPLE ANALYSIS, LOWER LIMIT OF DETECTION (LLD)
TABLE 2.4 ENVIRONMENTAL (CROSS CHECK) PROGRAM PARTICIPATION RESULTS.
.. ~19 TABLE 3.1 1998 DIRECT RADIATION DATA ORGANIZED BY
. 32 COMPASS DIRECTION AND DISTANCE FROM WATERFORD 3 SES TABLE 3.2 STATISTICAL COMPARISON OF 1998 TLD...
.33 MEASUREMENTS FROM STATIONS GROUPED BY DISTANCE FROM WATERFORD 3 SES TABLE 3.3 STATISTICAL COMPARISON OF 1998 GROSS BETA
.. 34 ACTIVITY MEASURMENTS ON AIR PARTICULATE FILTERS FROM WATERFORD 3 SES I
TABLE 3.4 STATISTICAL COMPARISON OF 1998 GROSS BETA.
. 35 ACTIVITY MEASUREMENTS IN DRINKING / SURFACE WATER SAMPLES FROM WATERFORD 3 SES I
)
TABLE 3.5
SUMMARY
OF 1998 REMP DEVIATIONS..
. 36 l
TABLE 3.6 1998 LAND USE CENSUS RESULTS..
. 37 i
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Annual Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS (Continued)
Page 1
LIST OF TABLES (continued)
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING.
.43
)
PROGRAM
SUMMARY
{
TABLE B-1 QUARTERLY TLD DOSE RATES........
..50 TABLE B-2 AIR PARTICULATE FILTERS AND CHARCOAL..
.. 51 CARTRIDGES: GROSS BETA AND IODINE-131 ANALYSES TABLE B-3 AIR PARTICULATE FILTERS: GAMMA ISOTOPIC.
. 56 ANALYSES TABLE B-4 DRINKING / SURFACE WATER: IODINE-131.
. 57 ANALYSES TABLE B-5 DRINKING / SURFACE WATER: GROSS BETA.
.60 f
ANALYSES TABLE B-6 DRINKING / SURFACE WATER: GAMMA ISOTOPIC..
.. 63 ANALYSES TABLE B-7 DRINKING / SURFACE WATER: TRITIUM ANALYSES..
.66 TABLE B-8 GROUNDWATER: TRITIUM AND GAMMA ISOTOPIC.
.67 ANALYSES TABLE B-9 SHORELINE SOll: GAMMA ISOTOPIC ANALYSES..
.68 TABLE B-10 MILK: LODINE-131 AND GAMMAISOTOPIC ANALYSES.
.69 TABLE B-11 FISH: GAMMA ISOTOPIC ANALYSES......
... 71 TABLE B-12 BROAD LEAF VEGETATION: IODINE-131 AND GAMMA.
.. 73 ISOTOPIC ANALYSES 4
V
Annual Radiological 1998 l
Environrnental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS (Continued)
Page LIST OF FIGURES FIGURE 2.1 REMP SAMPLE LOCATIONS WITHIN 2 MILES OF.
.22 WATERFORD 3 FIGURE 2.2 REMP SAMPLE LOCATIONS WITHIN 10 MILES OF.
.23 WATERFORD 3 FIGURE 2.3 REMP SAMPLE LOCATIONS WITHIN 50 MILES OF.
.24 WATERFORD 3 FIGURE 3.1 DIRECT RADIATION DOSE COMPARISON.
.38 FIGURE 3.2 GROSS BETA-AIR PARTICULATE COMPARISON..
.39 FIGURE 3.3 GROSS BETA-DRINKING / SURFACE WATER.
.40 COMPARISON k
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Annu 1 Radiologic 1 1998 Environment:1 Operating R; port Waterford 3 Steam Electric Station
1.0 INTRODUCTION
This report describes the Radiological Environmental Monitoring Program (REMP) for the Waterford 3 Steam Electric Station and discusses the results obtained during the calendar year 1998. The results discussed in this report were used to evaluate the radiological environmental impact from the operation of Waterford 3. The submission of this report to the Nuclear Regulatory Commission (NRC) fulfills the requirements pursuant to Waterford 3 Technical Specification 6.9.1.7.
1.1 Program and Report Objectives The objective of the monitoring program is to evaluate the radiological environmental impact of the plant.
In order to conduct this evaluation, the data analyses and interpretations contained in this report fulfill the following specific objectives:
to identify any radioactive materials or radiation in the environment associated with e
plant operation, to compare the results obtained during the reporting period with past operational and e
pre-operational data and identify any trends associated with accumulation of radioactivity in the environment; and, to verify compliance with federal regulatory requirements e
1.2 Plant and Site Description Waterford 3 employs a pressurized water reactor for the production of approximately 1153 gross (1104 net) megawatts of electricity. The station uses a flow of water obtained i
from and discharged to the Mississippi River for condenser cooling. On March 4,1985,
{
the unit achieved initial criticality.
The plant is located on the west bank of the Mississippi River at River Mile 129.6 between Baton Rouge and New Orleans, Louisiana. The site is in the northwestem section of St.
Charles Parish, approximately three miles southeast of the St. John the Baptist Parish boundary, between Killona and Taft. The Mississippi River is the closest prominent natural feature; other features include Lac des Allemands, about 5.5 miles southwest of the site, and Lake Pontchartrain, about 7 miles northeast of the site.
Most of the man-made features are located on the narrow strip of land between the Mississippi River and the wetlands. Specifically, several industrial facilities including Waterford 1 and 2 Steam Electric Station (0.4 miles northwest), Little Gypsy Steam Electric Station (0.8 miles northeast), IMC Agrico, a fertilizer manufacturer (0.6 miles east southeast), Oxychem Chemical Company (0.8 miles east southeast), and Union Carbide, a chemical manufacturer (1.2 miles east southeast) are operating in the area.
Major urban centers in the region include New Orleans (approximately 25 miles east) and Baton Rouge (approximately 50 miles west-northwest). Communities near the site in St.
Charles Parish include Killona (0.9 miles west northwest), Montz (1.0 miles north), Norco (2.5 miles east), Hahnville (3.7 miles east southeast), and Destrehan (6.3 miles east southeast). Laplace (4.7 miles north)is located in St. John the Baptist Parish.
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Annu:1 Radiological 1998 Environmental Operating R: port Waterford 3 Steam Electric Station 2.0 PROGRAM DESCRIPTION i
A general summary of the REMP is given in Table 2.1. Brief descriptions and locations of the sampling stations are presented in Table 2.2.
In addition, station locations are illustrated in Figures 2.1 through 2.3. A more detailed description of the REMP is provided below.
2.1 History and Development The Waterford 3 REMP evolved from the Pre-Operational Environmental Radiological Surveillance (PERS) program (1978-1982) and was initiated in April of 1983. Equipment, procedures, techniques, and sampling locations used during the pre-operational survey were incorporated into the operational program.
Further, the environmental data collected during the first two years of the REMP (1983 and 1984), prior to initial criticality, were used to supplement the baseline established during the PERS Program.
2.2 Responsibilities Waterford 3 personnel are responsible for implementing and ensuring that the REMP complies with federal regulatory, Technical Specification, and Offsite Dose Calculation Manual (ODCM) requirements.
Responsibilities of Waterford 3 personnel include collecting (with the exception of fish samples), preparing, and shipping of environmental samples; conducting environmental dosimetry measurements; reviewing reports of analytical results; preparing and submitting the Annual Radiological Environmental Operating Report and other relevant reports to the NRC.
The Environmental Services Laboratory at the River Bend Nuclear Station located in St.
Francisville, Louisiana, is responsible for performing radiological analyses, conducting initial data review, preparing reports of analytical results, and overseeing laboratory quality assurance and control.
Additionally, a separate contractor, the Fisheries Co-Operative Extension Service of Louisiana State University, is responsible for the collection of fish samples. The TLD Process Laboratory at Waterford 3 analyzed the Panasonic multi-element thermoluminescent dosimeters (TLDs).
2.3 Sample Collection and Handling Procedures I
Sample type, location, collection frequency, and the analyses performed are summarized in Tables 2.1 and 2.2.
The information contained in these tables is based on requirements specified on Attachments 7.13 and 7.14 of the Waterford 3 ODCM.
Location maps of the sampling are illustrated in Figures 2.1 through 2.3.
Any station deviations during 1998 are discussed in Section 3.6 (i.e., unavailable samples and missed lower limits of detection).
1 The environmental samples collected are classified into four general categories according to exposure pathways: direct radiation exposure, airborne exposure, waterborne exposure, and ingestion. Sample collection and handling procedures are described in the I
following sections. The descriptions are intended to provide a concise procedural I
overview rather than a step-by-step description.
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fE Annuil Radiological 1998 Environmental Operiting R: port Waterford 3 Steam Electric Station i
2.3.1 Direct Radiation Exposure Pathway Samples Integrated external gamma exposure, determined by using Panasonic multi-element TLDs, was measured at thirty-one locations as follows:
an inner ring of stations; one in each of the sixteen meteorological e
sectors in the general area of the site boundary;
)
an outer ring of stations; one in ten of the sixteen meteorological e
sectors in the six to eight kilometer range from the site; and, the balance placed in areas of special interest (e.g., population e
centers, schools, etc.) with one area serving as a control.
I The TLDs were exchanged quarterly by Waterford 3 personnel and were analyzed by the TLD Process Laboratory at Waterford 3.
2.3.2 Airborne Exposure Pathway Samples Samples of airborne particulate and radioiodine were collected at four indicator stations (APG-1, APQ-1, APP-1, and APC-1) and one control station (APE-30).
Low-volume air pumps and flow totalizers in weatherproof shelters provided continuous air sampling.
Using the sampling devices described above, airborne particulate samples were obtained on a filter and collected biweekly by Waterford 3 personnel for shipment to the laboratory for gross beta analysis. The filters were composited quarterly by the laboratory for isotopic analysis by gamma spectroscopy.
Airbome iodine sampling was done in conjunction with air particulate sampling using a charcoal cartridge to collect iodine. The cartridges were collected bi-weekly by Waterford 3 personnel for shipment to the laboratory for lodine-131 analysis by gamma spectroscopy.
2.3.3 Waterborne Exposure Pathway Samples Drinking and Surfaco Water:
Because the plant discharges into the Mississippi River, the major source of drinking water in the vicinity of Waterford 3, water samples taken from the Mississippi River were designated as both drinking and surface water samples.
Composite drinking / surface water samples were obtained every four (4) weeks from the Mississippi River using automatic composite samplers placed at one upstream (DWP-7/SWP-7) and two downstream (DWG-2/SWG-2, DWE-5/SWE-
- 5) locations. Hydrochloric acid and sodium iodide were added to each sample prior to shipment. The laboratory analyzed the four week samples for lodine-131, l
composited them quarterly for gross beta, gamma spectroscopy and tritium analysis.
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Annu11 Radiological 1998
- Environmental Operating RIport Witirford 3 Stam El:ctric Station Groundwater:
Due to the high water table resulting from shallow aquifers in the vicinity of the site, drainage canal sampling represents groundwater discharge. Groundwater was obtained quarterly by grab sampling from one sampling location (GWK-1).
4 Again, hydrochloric acid and sodium lodide were added to the sample prior to shipment to the laboratory for tritium and gamma spectroscopy analyses.
Shoreline Sediment:
Samples were obtained semi-annually from a sampling station at each side of the plant discharge point. Station SHWE-3 is located downstream on the shoreline of the Mississippi River and station SHWK-1 is on the shoreline of the 40-Arpent canal. The samples were shipped without further processing.
2.3.4 Ingestion Exposure Pathway Samples Milk:
Milk samples were collected monthly from one indicator location (MKQ-5) and one control location (MKQ-45).
Louisiana Radiation Protection Division personnel performed sampling of the control station. Although one additional indicator location was identified (MKQ-1), no samples were available from this location during 1998 (see Section 3.6). Finally, formaldehyde and sodium iodide were added as a preservative to all milk samples. The lat oratory performed lodine-131 and gamma spectroscopy analyses.
Fish:
Fish samples were collected annually from the Mississippi River upstream (FH-1) and downstream (FH-2) from the plant. A contractor performed the sampling by netting. Subsequently, the fish were segregated by species and location prior to Waterford 3 receiving the samples. The samples were shipped frozen for gamma spectroscopy analysis.
Broad leaf vegetation:
The Technical Requirements Manual (TRM), Table 3.12-1, requires that broad leaf vegetation be sampled from three locations in the event milk samples are unavailable.. Since milk samples were collected from only one sampling location, broad leaf vegetation was sampled monthly at two indicator locations (BLQ-1 and BLB-1) and one control location (BLK-15). The samples were shipped without further processing.
2.4 Analytical Procedures by Environmental Services Laboratory:
2.4.1 Sample Handling and Treatment The laboratory staff receives and stores samples upon arrival. Environmental samples frequently require preparation prior to analysis, depending on media and analyses type.
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Annull Radiological 1998 l
Environmental Operating R: port Waterford 3 Steam Electric Station i
Water Samples Generally, field personnel acidify one-gallon water samples with concentrated hydrochloric acid when collected, unless otherwise directed by the analytical laboratory. Tritium samples are not acidified and are stored in glass bottles under refrigeration until analysis can be performed.
Air Filters The laboratory handles air filters with care to avoid disturbing any particulate deposition on the air particulate filter. They normally receive air filters in plastic petri dish containers that aid in transporting heavy dust loaded filters.
Milk The laboratory refrigerates milk samples until analyzed. They add a preservative (formaldehyde), if analyses are delayed for more than a few days to inhibit bacterial growth and retard spoilage. Unless frozen or shipped on ice, milk samples analyzed for lodine-131 require an addition of 100 mis of formaldehyde, of which field personnel normally add 40 mis prior to shipment, to avoid binding of the iodine that may occur with smaller levels of formaldehyde.
Soll and Bottom Sediment The laboratory dries, grinds, and sieves soil and sediment samples before analysis. The lab then mixes the samples to ensure a homogeneous mixture.
Other Samples The laboratory preserves perishable samples by refrigeration or freezing.
Vegetation and other samples may require drying, pulverizing or ashing before or after analysis for long-term storage.
2.4.2 Sample Analysis Gross Beta Analysis:
Air Samples The laboratory counts air filters for 100 minutes, or until the required LLDs in TRM Table 4.12-1 are achieved. This analysis was performed with a low-background alpha-beta counter at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after collection to allow for the decay of short-lived isotopes, such as radon and thoron daughters.
Water Samples This analysis measures overall beta radionuclides in water samples. It involves evaporating a suitable aliquot of sample (usually 100 mis) in a beaker and then drying the beaker residue in a 47mm stainless steel planchet under heat lamps or on a hot plate. The lab counts the plancheted samples for 200 minutes, or until the required LLDs are achieved, in a low-background alpha-beta counting system. Activity calculation includes a self-absorption attenuation factor (referred to as a salt density curve) for counter efficiency based on weight of residue on each planchet.
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. Annu 1 Radiological 1998 Environmental Operating RIport Waterford 3 Steam Electric Station i
Tritium Analysis:
' Water Samples i.
The laboratory typically adds six mis of water to 12 mis of liquid scintillation l
cocktail in a 20 mi vial and inserts the vial into a liquid scintillation spectrometer for a 200 minute count, or until the required LLDs are achieved.
lodine-131 Analysis:
Water Samples L
The laboratory mixes four liters or more of the sample with a stable iodine carrier solution and then stirs the sample with an anion exchange resin to remove iodine from the sample. The resin is then transferred to a 250 mi micro-marinelli beaker and counted in a shielded intrinsic Germanium detector until the required LLDs are achieved.
Gamma lootopic Analysis:
Milk and Water Samples The laboratory fills a 3.7 liter marinelli beaker with a representative aliquot of the sample and counts for a minimum of 60 minutes, or until the required LLDs are achieved, in a shielded. intrinsic Germanium detector coupled to a computer-based data acquisition system which performs a pulse height analysis.
A computer software program defines peaks by certain changes in slope of the spectrum. The program also compares the energy of each peak with a library of peaks for radionuclide identification and then performs a calculation using 4
appropriate fractional gamma ray abundance, half-life, detector efficiency and net counts in the peak region.
Vegetation and Fish Samples The laboratory loads a maximum quantity of undried vegetation, food or garden crop sample into a tared i liter marinelli beaker and weighs it. The sample is then counted for 30 minutes, or until the required LLDs are achieved, in a shielded intrinsic Germanium detector as described above. The laboratory loads as much as possible (up to the total sample) of the dried edible portion of a fish sample into a tarred 0.5 liter marinelli beaker, or a lab-tech petri dish, depending on fish quantity, and weighs. The sampie is then counted for a minimum of 30 minutes in a shielded intrinsic Germanium detector as described above.
Soil and Sediment Samples The laboratory dries soil and sediment at a low temperature (110-135'C) in a convection oven, then loads the sample into a tarred 1.0 liter marinelli beaker and weighs it. The sample is then counted for 30 minutes, or until the required LLDs are achieved, in a shielded intrinsic Germanium detector as described above.
Chamoal Cartridge Samples The laboratory counts each charcoal cartridge separately by positioning each on the face of the detector in a converted one-half liter marinelli used as a holder.
Each sample is counted for a minimum of 30 minutes or until LLDs are achieved.
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Annurl Radiological 1998 Environmental Operating Rrport Waterford 3 Steam Electric Station Air Particulate Samples The laboratory stacks 13 air particulate filters, for a quarterly composite for each field station, one on top of another in a covered plastic petri dish. The composite 1
sample is counted for 30 minutes, or until the required LLDs are achieved, in a shielded intrinsic Germanium detector as described above.
2.4.3 Data Reporting The laboratory calculates the mean of analytical results as follows:
X = Xil n where; i
X Mean
=
Xi
=
Individual sample results Number of sample results n
=
The lab rounds off calculated values by inspection of digits to the right of the third reported significant digit, with values less than five rounded down and values equal to or greater than five rounded up.
I The laboratory reports gross beta and tritium analytical results, less than a two sigma counting error, as less-than-LLD value for that sample. The lab reports analytical'results, greater than the two sigma counting error, along with asaociated two sigma counting error, as a plus or minus (+) term.
The laboratory considers calendar quarters and a quarterly composite to be composed of six to seven bi-weekly aliquots or samples, such as for air particulate filters, or three to four monthly aliquots or samples, such as for drinking water, 2.5 -
Environmental Dosimetry Panasonic Model UD-814 TLDs that contain one lithium borate and three calcium sulfate phosphor elements are used for environmental dosimetry. However, only the calcium sulfate phosphor elements are used for analysis. For placement in the field, two annealed dosimeters are placed inside a plastic bag and mounted in an aluminum frame.
The dosimeters are checked monthly and exchanged for analysis each quarter using a Panasonic Automatic TLD Reader Model UD-710A.
2.6 Lower Limits of Detection (LLD)
The minimum sensitivities for the analytical procedures are reflected by the LLD values presented in Table 4.12-1 of the TRM. The LLD's are a priori estimates based on assumed sample volumes, counting times, detector efficiencies, etc. Analyses that could not achieve these lower limits of detection are discussed in Section 3.6.
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Annual Radiological 1998 Environmental Operating RIport Waterford 3 Steam Electric Station 2.7 Laboratory Quality Assurance 2.7.1 Environmental Service Laboratory During 1998, the Environmental Service Laboratory at the River Bend Station (RBS) participated in a Radiological Interlaboratory Comparison i
Cross Check Program. This program satisfies the requirements of the f
Waterford 3 ODCM, Section 5.7.2, for participation in an interlaboratory comparison program. The program performs analyses on various sample media typically found in the REMP. As a result of participation in the program, an objective measure of analytical precision and accuracy was obtained. In the event that results obtained were not within control limits (three standard deviations), an investigation was conducted to determine the cause, and corrective action was taken to prevent a recurrence. Table 2.4 lists the 1998 results of the laboratory's participation in the cross-check program.
Results of the investigation of Out of Control Limits Explanation and Corrective Actions:
The Environmental Service Laboratory at the RBS conducted an investigation of the cross-check results that were outside the control limits as defined in note "d" on Table 2.4.
In the 1998 cross-check program, six sample analysis results were outside the control limits. These six sample results are for the:
Second Quarter i
E1400-125 (Analytics) of 6/11/98 Cs-137 e
Third Quarter I
E1512-125 (Analytics) of 09/24/98 Cr-51 e
E1516-125 (Analytics) of 09/24/98 Cr-51 E1516-125 (Analytics) of 09/24/98 Cs-134 E1513-125 (Analytics) of 09/24/98 Mn-54 Fourth Quarter E1601-125 (Analytics) of 12/10/98 Fe-59 e
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k Annu11 Radiological 1998 Environmental Oper; ting Rrport Waterford 3 Steam Electric Station Program Exceptions:
There were six results outside the control limits (three sigma) for accuracy in the 1998 cross check program.. Of these six out-of-control limit results, all were analyzed by gamma spectroscopy (five nuclides in two matrices). Five of the results in question were in liquid cross check samples, one in a sediment sample.
. All six results in question were bias high.
There was a single result for Mn-54 in sediment out-of-control limits, with a slight
- high bias (+1.68) trend indicated after review of only six results in the past three years. Review of the cross check results for three years (23 results) indicated a low bias (-1.11) for Cr-51 in water, even though there were only two results out- -
of-control limits. The review also indicated a slight high bias (+1.91) for Fe-59 in water over the same three-year period. Cs-134 and.Cs-137 results in water indicate no trends over the three year period.
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Investigation of high bias results in the past indicated it was due to coincidence -
summing effects of Y-88 and Co-60 on the efficiency curve in the effected
. region. To minimize the coincidence summing effects on the efficiency curve, RBS added two additional nuclides (Mn-54 and Zn-65) to the set of liquid calibration sources Cross check samples for 1998 were not analyzed using the new nuclide mix since the new sources were not purchased until the end of l
1998. New gamma efficiency curves have been established using the new nuclide mix sources; however, they will be used to analyze cross check samples in 1999.
Impact Statement:
l j
inere was no impact on past data indicated by these cross check program j
exceptions. Environmental samples are analyzed and reported with a 95%
confidence level that the analytical result with its associated error encompasses the "true" value. Ninety-seven percent of RBS environmental cross check results are within control limits for accuracy and precision.
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Annual Radiological 1998 Environmental Oper ting Report Wat:rford 3 St;;m Electric Station TABLE 2.4 ENVIRONMENTAL (CROSS-CHECK) PROGRAM PARTICIPATION RESULTS 1
gT pe Study Date Analysis f
"Kr.own" Value' Va N EV" N-GE' gg E1514-125 9/24/98 Beta 62117.3 55.1
-1.19 0.063 E1599-125 12/10/98 Beta 52 i 17.3 49.9
-0.36 0.012 gg E1367-125 3/12/98 l-131 134 1 23.2 135 0.17 0.176 (pCl/ cartridge) i E1401 125 6/11/98 l-131 62 i 10.7 60.4
-0.44 0.219 E1515-125 9/24/98 l-131 85 i 14.7 86.2 0.25 0.535 E1600-125 12/10/98 l-131 79 i 13.7 78.7
-0.07 0.179 g
E1364-125 3/12/98 Beta 269 1 69.9 254
-0.63 0.337 J
E1365-125 3/12/98 H-3 2398 1 608.6 2405 0.03 0.442 E1366-125 3/12/98 Cr-51 167 i 14.5 157
-2.14 1.415 Mn-54 111 i 9.61 115 1.25 0.213 Fe-59 79 i 8.66 83.9 1.71 0.780 Co60 71 i 8 66 73.4 0.83 0.118 l
Zn-65 118 i 20.4 122 0.64 0.400 1-131 90 i 15.6 93.3 0.64 0.348 Cs-134 70 i 8.66 70.0 0.31 0.224 Cs-137 134 i 11.6 134 0.09 0.088 i
Ce-141 58 i 8.66 59.1 0.39 0.543 E1368-125 3/12/98 Cr-51 167 i 14.5 158
-1.94 1.839 (duplicate)
Mn-54 111 1 9.61 118 2.29 0.532 I
j Fe-59 79 i 8.66 78.8
-0.06 0.473 Co-60 71 i 8.66 74.1 1.07 0.508 Zn-65 118 i 20.4 120 0.34 0.100 i
1-131 90115.6 103 2.44 0.912 I
Cs-134 70 i 8.66 70.5 0.17 0.083 i
Cs-137 134111.6 137 0.78 0.176 I
Ce-141 58 i 8.66 52.6
-1.88 1.689 E1398-125 6/11/98 Beta 243 1 63.1 224
-0.90 0.292 E1399-125 6/11/98 H-3 6007*1041 5830
-0.51 0.146 E1400-125 6/11/98 Cr-51 150 i 13.0 157 1.62 0.945 Mn-54 121 1 10.5 127 1.62 0.195 Fe-59 52 i 8.66 58.0 2.08 1.016 l
Co-60 164 1 14.2 174 2.04 0.504 Zn45 139 t 24.1 151 1.54 0.297 l-131 62 i 10.7 64.6 0.74 0.200 Cs-134 108 1 9.35 117 2.89 0.438 Cs-137 80 8.66 89.0 3.12' O.177 i
Ce-141 113 i 9.79 111 0.51 0.105 19 i
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Annuri Radiological 1998
{
Environmental Oper: ting R: port Wat:rford 3 Stiam Electric Station TABLE 2.4 (continued)
^"
n "Known" Value' Va N EV6 N
NGE' Water (pCalliter)
E1402-125 6/11/97 Cr-51 150 1 13.0 148
-0.46 2.678 (duplicate)
Mn-54 121 1 10.5 129 2.39 0.293 Fe-59 5218.66 52.8 0.29 0.898 Co-60 164 i 14.2 171 1.55 0.288 Zn-65 139 i 24.1 147 1.00 0.382 1-131 62 i 10.7 65.8 1.07 0.343 Cs-134 108 i 9.35 113 1.60 0.766 Cs-137 80 i 8.66 84.3 1.50 0.106 Ce-141 113 i 9.79 115 0.72 0.627 E1512-125 9/24/98 Cr 51 165 i 14.3 139
-5.4 68 0.716 Mn-54 66 i 8.66 66.6 0.22 0.732 Fe-59 5518.66 57.2 0.76 1.146 Co-60 131 1 11.4 133 0.44 0.451 Zn-65 173i30 178 0.50 0.068
?131 79113.7 79.5 0.10 1.622 Cs-134 73 i 8.66 69.3
-1.28 1.087 Cs-137 119 1 10.3 114 1.36 0.099
~
Ce-141 129 1 11.2 129 0.00 0.733 E1516-125 9/24/98 Cr-51 165 i 14.3 144
-4.4 88 1.933 (duplicate)
Mn-54 66 i 8.66 64.5
-0.51 0.154 Fe-59 55 i 8.66 63.0 2.78 0.543 Co-60 131 1 11.4 130
-0.35 0.631 Zn-65 173 i 30 173
-0.03 0.376 l-131 79 i 13.7 83.7 1.04 0.965 Cs-134 7318.66 64.2
-3. 06*
1.051 Cs-137 119 i 10.3 111
-2.33 0.298 Ce-141 129 i 11.2 128
-0.18 1.557 E1597-125 12/10/98 Cr-51 1020 i 88.3 1009 0.66 0.556 Mn-54 147 t 12.7 156 2.12 0.643 Fe-59 153 1 13.3 164 2.41 0.849 Co-60 185 2 16.0 191 1.19 0.255 Zn-65 145 1 25.1 143
-0.20 0.041 1-131 64 t 11.1 62.0
-0.53 0.803 Cs-134 228 1 19.8 232 0.56 0.259 Cs-137 190 i 16.5 198 1.40 0.062 Ce-141 774 i 67.0 798 1.09 0 336 f
20
g-Annu:1 Radiological 1998 EnvironmentalOper: ting R port Witirford 3 Stram Electric St: tion l
TABLE 2.4 (continued)
L kn
^ " * *
"Known" Value' Va ue N EV6 N-NGE' Water (pCl/ liter)
E1601 125 12/10/98 Cr-51 1020 i 88.3 1063 1.47 0.208 (duplicate)
Mn-54 147 i 12.7 157 2.36 0.402 Fe-59 153 i 13.3 182 6.5 78 1.235 Co-60 185 1 16.0 192 1.25 0.639 Zn-65 145 1 25.1 149 0.48 1.141 1-131 641 11.1 69.7 1.55 0.535 Cs-134 228 1 19.8 246 2.79 0.311 Cs-137 190 1 16.5 197 1.28 0.870 Ce-141 774 i 67.0 796 1.00 0.412 gng E1513-125 9/24/98 Cr-51 0.352 i 0.030 0.344
-0.79 1.054 Mn-54 0.140 1 0.012 0.154 3.41' O.894 Fe-59 0.119 i 0.010 0.118 0.42 1.003 Co.60 0.281 i 0.024 0.291 1.25 0.555 Zn45 0.369 1 0.064 0.383 0.64 0.311 Cs-134 0.156 1 0.014 0.149
-1.61 1.128 Cs-137 0.381 1 0.033 0.371
-091 0.353 Ce-141 0.275 i 0.024 0.279 0.51 0.872 E1598-125 12/10/98 Cr-51 1.78 1 0.154 1.680
-1.95 0.604 Mn-54 0.259 i 0.022 0.273 1.90 1.086 Fe-59 0.269 i 0.023 0.263
-0.75 0.580 Co-60 0.324 i 0.028 0.332 0.86 0.620 Zn-65 0.255 i 0.044
' O.267 0.82 0.896 Cs-134 0.400 i 0.035 0.371
-2.54 0.372 Cs-137 0.460 1 0.040 0.484 1.84 0.452 Ce-141 1.360 1 0.118 1.356
-0.10 0.903 NOTES:
(a) The "known" values are listed with a range reflechng control (3 sigma) hmits.
(b) The normalized deviation from the "known" value is computed from the deviation and the standard error of the rnean,12 000 is the warning limit and 13.000 is the control hmit. This is a measure of accuracy of the analytical methods.
(c) The normalized range is computed from the mean range. the controllimit, and the standard error of the range; +2.000 is the waming Ilmat and +3.000 is the cor** 94 limit. This is a measure of precision of the analytical methods.
(d) Tt. results reported were out of the controllimits; refer to the discussion on program exceptions.
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Annual Radiological 1998 EnvironmentalOper ting R: port Waterford 3 Steam Electric Station 3.0 DISCUSSION OF RESULTS Analytical results for the year 1998 are discussed in this section by exposure pathway, sample type, and analysis performed. Analytical results focusing only on man-made radioactivity are summarized in Appendix A and data for the individual analyses are presented in the tables of Appendix B.
3.1 Direct Radiation Exposure Pathway The average exposure rates measured by TLDs at both control and indicator stations were 13,12, 11, and 11 mrem / standard quarter for the first, second, third, and fourth quarters of 1998, respectively. The average exposure rate of the 120 indicator TLD locations was 12 mrem / standard quarter compared to 10 mrem / standard quarter average exposure rate at the control location. The lowest and highest individual exposure rates were eight mrem / standard quarter (C-1,1*-4*
quarters) and 25 mrem / standard quarter (D-2,1" quarter) for all locations. Table 3.1 compares the indicator TLD results by directional sector and distance from the facility. A comparison of directional sectors indicates the highest average exposure rate in 1998 to be 14 mrem / standard quarter in Sector L.
The average exposure rates during 1998 are consistent with those from the pre-operational program and the previous five years of operation (Figure 3.1). In particular, the pre-operational survey indicates that exposure rates ranged between 11 and 33 mrem / standard quarter with an average of 20 mrem / standard quarter. Similarly, the range indicated during the previous five years of operation was 7.0 to 23 mrem / standard quarter with an average exposure rate of 13 mrem / standard quarter.
3.2 Airborne Exposure Pathway 3.2.1 Airborne Particulate
{
3 Gross beta activity ranged from 0.009 pCi/m (APG-1,APQ-1, APC-1: 09/14-09/29) to 0.029 8
2 pCi/m (APC-1, APP-1: 05/11-05/26) with an average of 0.018 pCi/m for 126 measurements from all five locations. The average gross beta activity for the indicator (APG-1, APQ-1, APP-1, APC-1) locations was 0.018 pCi/m compared to 0.019 pCi/m at the controllocation (APE-30).
The airborne gross beta activity results obtained during 1998 are consistent with the results from the pre-operational program and the previous years of operation (Figure 3.2). In the period from 1984 to 1997, the average gross beta activity per year for the indicator locations ranged from 0 006 to 0.049 pCi/m with an average of 0.019 pCi/m compared to 0.020 pCi/m' at the control location. Also, the pre-operational survey indicates that in periods not significantly influenced by nuclear weapons testir.g, the gross beta activity ranged between 0.007 and 0.480 pCi/m with an average of 0.080 pCi/m.
3.2.2 Airborne lodine All of the 126 airbome lodine-131 results were below the calculated lower limit of detection 3
(LLD) which varied from 0.009 to 0.047 pCi/m and were below the required LLD (0.7 8
pCl/m ) required by the Waterford 3 TRM. The sample Lt.D variability was due primarily to the difference in air sample volumes.
25
m i
Annuit Radiological 1998 Environmental Oper-ting RIport Waterford 3 Steam Electric Station 3.2.3 Gamma Isotopic Analysis Gamma spectroscopy results of the twenty air sample quarterly composites indicate that no man-made radionuclides were detected above their respective lower limits of detection.
3.3 Waterborne Exposure Pathway 3.3.1 Drinking / Surface Water i
As mentioned previously, drinking water samples also serve as surface water samples for Waterford 3. Therefore, monthly and quarterly gamma spectroscopy analyses of drinking water and quarterly tritium analyses also satisfy the surface water sampling requirement.
Thirty-nine composite drinking / surface water samples were analyzed by gamma spectroscopy for lodine-131 (Table B-4). All of the 39 composite sample lodine-131 results were below the calculated LLD.
Gross beta activity was detected in eleven of the twelve composites with a range of 2.8 (DWP-7: 10/12-12/07) to 6.3 (DWG-2: 07/20-09/14) pCi/l and an average activity of 4.4 pCi/l. The average activity for the control location, DWP-7, was 3.8 pCi/l compared to the averages of 5.1 and 3.9 pCi/l for indicator stations DWG-2 and DWE-5, respectively.
Analyses for gross beta in drinking / surface water were not performed during the pre-operational survey. However, in order to fulfill comparison requirements,1998 data was compared to data from the 1983 report and the previous years of operation.
The gross beta activity results obtained during 1998 are consistent with those from the 1983 reporting period and the previous years of operation (Figure 3.3). In particular, the period from 1984 to 1997, the average gross beta activity per year for the indicator locations ranged from 1.1 to 60.0 pCill with an average of 5.4 pCi/l compared to 4.8 pCi/l at the control location. Similarly, the 1983 survey indicates that in periods not significantly influenced by nuclear weapons testing the gross beta activity ranged between 2.9 and 14.0 pCi/lwith an average of 7.0 pCill.
Twelve composite drinking / surface water samples were analyzed by gamma spectroscopy.
Results indicate that all measurements were below the calculated LLDs.
Tritium analyses of drinking / surface water samples indicate that eleven of the twelve measurements were below the calculated LLD. Tritium was detected in one sample from the control location DWP-7,333+207 pCill. The detected activity in this sample was considerably below the LLD (2000 pCi/ liter) required by the Waterford 3 TRM and have a very high level of statistical uncertainty associated with it.
The tritium concentration detected in 1998 is consistent with those from the pre-operational program and the previous years of operation. In particular, the pre-operational survey indicates that tritium concentrations in drinking water samples ranged between 70 and 180 pCill with an average of 116 pCill. Similarly, the range indicated in the previous years of operation was from 170 to 545 pCi/l.
26
- AnnuciRadiological 1998 Environmental Operating RCport Waterford 3 Steam Electric Station 3.3.2 Groundwater Five groundwater samples were collected from one sampling location, GWK-1, and analyzed for tritium and gamma emitters. Tritium was detected in all five of the groundwater samples. The detected tritium activities in these samples ranged between 386 and 7224 pCi/l with an average activity of 2908 pCi/1.
The tritium concentrations detected in 1998 are slightly higher than those are from the pre-operational program and the previous years of operation. In particular, the pre-operational survey indicates that tritium concentration in groundwater samples ranged between 60 and 180 pCill with an average of 121 pCi/l. Similarly, the range indicated in the previous years of operation was from 249 to 4097 pCi/l.
While the tritium concentrations detected in 1998 are slightly higher than from the pre-operational program and the previous years of operation, they are consistent with observed effluent release data via this pathway. Variations in rainfall will affect the observed results since dilution of plant effluents with rainfall occurs at this monitoring station. Dry periods will cause higher levels of tritium to be observed.
The plant is making efforts to reduce the quantity of radioactive effluent released via this pathway. Design Change DC-3521 will reroute effluents from the Dry Cooling Tower Sumps to the Circulating Water System and ultimately to the Mississippi River. This will result in the Turbine Building industrial Waste Sump as being the only routine radioactive effluent release point for this pathway.
Tritium concentrations in samples at this location will continue to be carefully monitored in the future. If the levels approach 10,000 pCi/l (50% of the reporting levels in tritium in water), increased monitoring will be implemented.
3.3.3 Shoreline Sediment Four shoreline soil samples were collected from the following sampling locations: two samples from the Mississippi River shoreline downriver of the plant (SHWE-3) and two samples from the shoreline of a drainage canal (SHWK 1).
Cesium-137, a man-made nuclide, was detected in the sample from station SHWK-1 with the highest concentration at 51 +/- 14 pCi/kg (dry). Cesium-137 was also detected in the sample from station SHWE-3 with the highest concentration at 50 +/- 13 pCi/kg (dry) which is less than the required LLD (180 pCl/kg dry). No other man-made radionuclides were detected in any of the samples.
The Cesium-137 results obtained during 1998 are consistent with those from the pre-operational program and the previous years of operation. In particular, the pre-operational survey indicates that Cesium-137 was detected in 9 of 14 soil samples at concentrations ranging between 30 and 890 pCi/kg(dry) with an average concentration of 164 pCi/kg (dry).
Similarly, the range indicated during the previous years of operation was from 18 to 142 pCi/kg (dry) with an average activity of 52 pCi/kg (dry). Further, studies in Louisiana indicate that Cesium-137 is commonly found in soils and sediments as a result of atmospheric weapon testing. Because the Cesium-137 levels are consistent with pre-operational values, the Cesium-137 level detected in 1998 is more than likely attributable to weapon testing fallout.
27
" Annual Radiological -
1998 Environmental Operating RIport Waterford 3 Steam Electric Station 3.4 Ingestion Exposure Pathway
.3.4.1 Milk Twenty milk camples were collected from two sampling locations and analyzed by gamma spectroscopy end a radiochemical procedure for lodine-131. Results from these analyses indicate that all measurements were below the calculated LLD, 3.4.2 Fish Eight fish samples, four upstream and four downstream of the plant were collected and the edible portions analyzed by gamma spectroscopy. No man-made radionuclides were detected above their LLD in any of the samples.
3.4.3 Broad Leaf Vegetation Thirty-nine broad leaf vegetation samples were collected and analyzed by gamma spectroscopy and a radiochemical procedure for lodine-131. No man-made radionuclides were detected in any of the collected samples above their calculated LLDs.
3.5 Statistical Analyses 3.5.1 Calculation of the Mean and Standard Deviation The mean and standard deviation for different groups of analyses are calculated using the following equations:
X-i,.;5 n
and
_, 8 03
([,, (X -Xf S=
(n -1) where:
X = mean of sample population, S = standard deviation of sample population, n = number of samples in sample population, and X, = value of the l'th sample.
28 l
m Annuil Radiological 1998.
Environmental Oper; ting RIport Waterford 3 Steam Electric Station 3.5.2 Comparing Two Sample Population Means The means of two sample populations are compared for statistical difference using the standard "t" test. The use of the test requires the assumption that the data within the populations are normally distributed and that the true standard deviations of the mean are equal for both populations. The standard "t" test tests the hypothesis that the true means of both populations are equal. The "t" value can be calculated from the equation below (obtained from the CRC Standard Mathematical Tables,26th Edition (1981)):
X-Y 2
23 03 f(H -1)S +fM -1)S r
30.5 1
1
{
y
-+-
H,+Hy-1
< H, H, >
g i
where:
)
t = calculated "t" value, X = mean of first data set, i
Y = mean of second data set, y, = number of variables in first data set, S, = standard deviation of first data set, y y = number of variables in second data set, and S, = standard deviation of second data set.
The calculated "t" value is used to test the hypothesis that the true mean of the first population (m,) is equal to the true mean of the second population (m,) assuming that the true standard deviations of both populations are equal (m, = m,). The calculated "t" value is compared to a tabular "t" value such that:
a
.if t > t p,n then reject the hypothesis when m, > m,,
b.
if t < -t p,n then reject the hypothesis when m, < m,,
c.
if t > t pa,n then reject the hypothesis when m, = m,
y where t pm,n and t p,n are the tabular "t" values, with a preselected error (5%), confidence level (1 - p) or (1-p/2), and degrees of freedom n =n,+n,-2. Tabular values of the "t" were obtained from the CRC Standard Mathematical Tables,26th Edition (1981).
29
l Annu 1 Radiological 1998 Environmental Operating R: port Witirford 3 Steam Electric Station 3.5.3 TLD Measurements TLD stations were categorized by distance into three groups: 0-2 miles,2-5 miles, and >5 miles from the plant. A statistical analysis using the standard "t" test (described above) was performed comparing average exposure rates from 0-2 miles and 2-5 miles to the average exposure rate at >5 miles. In short, results indicate that the average exposure rates at 0-2 miles and 2-5 miles are statistically the same as the rates at >5 miles. Table 3.2 summarizes the results of this analysis.
3.5.4 Gross Beta Activity on Air Particulate Filters Additionally, the standard "t" test was used to compare average gross beta activity from each indicator station to the average gross beta activity at the control station. The results -
from this test show average activity detected at all indicator stations (APG-1, APQ-1, APC-1, and APP-1) to be statistically the same as the activity detected at the control-station.
Table 3.3 summarizes the results of this analysis.
3.5.5 Gross Beta Activity in Monthly Drinking Water Composites Finally, the standard "t" test was used to compare average gross beta activity from the two indicator stations to the average gross beta activity from the control station. The results from this test show average activity at indicator stations DWG-2 and DWE-5 are statistically the same as the average activity detected at the control station, DWP-7. Table 3.4 summarizes the results of this analysis, s
' 3.6 Deviations from the REMP 3.6.1 Unavailable Samples Four milk samples from location MKQ-5 were unavailable during the 1998 reporting period.
The milk samples were unavailable due to cows not producing enough milk. This is summarized in Table 3.5.
Milk samples were not available during 1998 from the animal owners at location MKQ-1 since the cows are not currently producing milk for human consumption. With the absence of milk samples at these locations, broad leaf vegetation sampling was performed.
3.6.2 Lack of Sample Continuity Seven air samples failed to meet the requirement for sample continuity as explained in Table 3.5.
3.6.3 Missed Lower Limits of Detection All lower limit of detection requirements were met for 1998.
30
Annual Radiological 1998 Environmental Operating R: port Waterford 3 Steam Electric S'ation 3.7 1998 Land Use Census l
In compliance with the Waterford 3 ODCM and TRM, the land use census was conducted on l
October 6 and 7,1998. The nearest residence, garden, and milk animal in each sector within a five mile radius of the plant was located by visualinspection and verbal inquiry.
l While residence and garden locations remained unchanged for 1998, one location of beef cows in l
Sector Q and two locations of goats in Sectors A and F have been removed. One new location for milk cows (Sector A), four new locations for beef cows (Sectors A and F), and four new locations for goats (Sector A and Q) were identified; however, in all cases it was determined that the milk animals are not currently producing milk for human consumption. This information was ascertained by verbal inquiry with the owners of the animals. As a result of the interviews, Waterford 3 personnel obtained a verbal agreement that the animal owners will sell milk samples to Waterford 3 l
in the event of a radiological emergency to provide additional data for analysis of environmental' impact.
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Annual Radiologic-1 1998 Environmentil Operating R port W:tirford 3 Ctram Electric Station TABLE 3.1 l
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Annu:1 Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station TABLE 3.6 1998 Bi-Annual Land Use Census Results Distance from Plant in Miles Sector Direction Milk Beef Food Residence Garden Cows Cows Goats Products A
N 1.3 1.7 4.6*
4.6 3.5*
4.1 B
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- Animals were located at this distance frr Waterford 3, but the milk is not currently used for human consumption
- Samples are being obtained from animals at this location (MKQ-5) for the REMP 37
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r Annual Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station
4.0 CONCLUSION
S -
The radiological environmental data collected during 1998 is consistent with the data obtained during the previous years of plant operation (1985-97), the first two years of the REMP prior to Waterford 3 initial criticality (1983-84), and the Pre-operational Environmental Radiological Surveillance (PERS) Program (1978-82). The only r.1an-made radionuclide detected in the routine environmental samples analyzed during 1998 was Cesium-137,
. Cesium-137 was detected in three shoreline soil samples. Studies in Louisiana indicate that Cesium-137 is commonly found in soils and sediments as a result of fallout from nuclear weapons testing. In addition, the detected concentration was consistent with pre-operational levels and the levels detected in the previous years of operation.
Further,' the concentration detected was lower than the required LLD and well below levels requiring notification.
Tritium was' detected in one control location surface / drinking water sample. The detected activity in the surface / drinking water sample was below the required LLD. The tritium concentration detected in 1998 was consistent with those from the pre-operational program and the previous years of operation.
Tritium was also detected in five ground water samples. Even though values observed were greater than the required LLD in four of the five samples, tritium is routinely released as measured in effluent sampling analysis via this pathway. Those levels i
observed are consistent with effluent sampling and analysis results.
In conclusion, based on the evaluation of the REMP data collected during 1998 the operation of Waterford 3 had no discernable radiological impact on the environment.
i 41
Annual Radiological 1998 Environmental Operating Report Waterford 3 Steam Electric Station APPENDIX A REMP DATA
SUMMARY
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