ML20217K489
| ML20217K489 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1997 |
| From: | Dubois A, Ewing E, Hood G ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-98-0084, W3F1-98-84, NUDOCS 9805010231 | |
| Download: ML20217K489 (99) | |
Text
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y EntIrgy Oper tions,Inc.
Kiliona. LA 70066 i Tel 504 739 6242 C. Ewing, til e
gety s acauy mans
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W3F1-98-0084 A4.05 PR l
I April 30,1998 !
4 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 l Annual Radiological Environmental Operating Report Gentlemen:
Attached is the subject 1997 annual report on radiological environmental monitoring which covers the period of January 1 through December 31,1997. This report is submitted per Section 6.9.1.7 of the Waterford 3 Technical Specifications (NUREG-1117).
If there are any questions, please contact Roy Prados at (504) 739-6632.
Very truly your l
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E.C. Ewing Director j l Nuclear Safety & Regulatory Affairs ,
ECE/RWP/rtk Attachment [
l cc: E.W. Merschoff, C.P. Patel, P.A. Harrell, A.L. Garibaldi, J.T. Wheelock - INPO Records Center, J. Smith, N.S. Reynolds, NRC Resident inspectors Office, Administrator l 9805010231 DR 971231 ADOCK 05000382 I PM
e h'ntergy Annual Radiological Environmental
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Oper~ating Report P 'Janpery!1W199FDecember3)$1997 e :l !
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Annual Radiological 1997 I Environmental Opercting Report Waterford 3 Steam Electric Station l
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I Originator: Ay. V, fug ]g[gjg 4,/ ? ';,/q8 Ann V. Dubois Chemistry Technician Date Waterford 3 SES I Reviewed By: Jggyf f,j%d y ,
Gregory L Ik>od ChenEst'ry Supervisor Date Waterford 3 SES j
Approved By: L,6,9,.
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Aaron S. Bergeron Chemistry Su"perintendent Date Waterford 3 SES I
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Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station l
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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 1997, 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 discernable impact on the levels of radioactivity in the environment during 1997.
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i Annual Radiological 1997 l Environmental Operating Report Waterford 3 Steam Electric Station TABL.i OF CONTENTS PAGE ABSTRACT . . . . . . . . . . . . . .... . . . . . . . . . . . ......i TABLE OF CONTENTS ... . . .. . . . . . . . . .. . . . . . . . . ... .. . . .. . . ii l
LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . .. .iv ,
i LIST OF FIGURES . . . . . . . . . .. . . . .. . . . . . . .. vi 9
1.0 INTRODUCTION
. . ... .. .. . . .. . .. . ............1 1.1 Program and Report Objectives..... . . ... . . . . . . .....1 1.2 Plant and Site Description . . . .. . . . . .. . .1 2.0 PROGRAM DESCRIPTION.. . . . . .. .. . . . . . . . . . . .. . . . ....2 2.1 History and Development. . . . . . . ... . . . . . . . . . . . .. . ...........2 i 2.2 Responsibilities... .. . . . . . . . . . . . . . . . . . . . . . . ....2 !
2.3 Sample Collection and Handling Procedures.. . .. . .. . . . . . . . . ... 2 ;
2.3.1 Direct Radiation Exposure Pathway Samples.. . . .. .. .........3 j 2.3.2 Airbome Exposure Pathway Samples.. .. ... . . . . . . . . . .3 l 2.3.3 Waterborne Exposure Pathway Samples... . ... . . . . . . . .. ...3 3 2.3.4 Ingestion Exposure Pathway Samples.. . . . . . . . . . . . ... 4 2.4 Analytical Procedures by Environmental Services Laboratory . . . .......5 2.4.1 Sample Handling and Treatment.. . . .. ... . .. .5 2.4.2 Sample Analysis. . . . .. . . . .. . .6 *
- 2.4.3 Data Reporting.. , , . ... . . ...7 l
l 2.5 Environmental Dosimetry . . .. . . .. . . . . . .8 l 2.6 Lower Limits of Detection (LLD). . .. . . . . . ... . . .. . 8 l
2.7 Laboratory Quality Assurance. . .. . . . . . .8 l
2.7.1 Environmental Service Laboratory . . . . . . . . . .8 l
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Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS Page 3.0 DISCUSSION OF RESULTS . . . .27 3.1 Direct Radiation Exposure Pathway.. .
.27 3.2 Airborne Exposure Pathway.. . . .27 3.2.1 Airborne Particulates. . . . .27 3.2.2 Airbome lodine . . . . . . . . . . ... 28 3.2.3 Gamma Isotopic Analysis. .
.28 3.3 Waterborne Exposure Pathway.. . .. 28 3.3.1 Drinking / Surface Water . . . . .28 3.3.2 Groundwater.. . .
.29 3.3.3 Shoreline Sediment. . . .30 3.4 Ingestion Exposure Pathway. . 30 3.4.1 Milk . . . . . . 30 3.4.2 Fish.. . .
. 30 3.4.3 Broad Leaf Vegetation . . . 30 3.5 Samples Following the Spent Fuel Pool Spill . . .. . 31 3.5.1 Groundwater.. . . . 31 3.5.2 Shoreline Sediment. . . . . . 31 3.6 Statistical Analyses . . . . . 31 3.6.1 Calculation of the Mean and Standard Deviation .. . . 31 3.6.2 Comparing Two Sample Population Means. .. . . . 32 3.6.3 TLD Measurements. . . . . . . 33 3.6.4 Gross Beta Activity on Air Particulate Filters. . .33 3.6.5 Gross Beta Activity in Monthly Drinking Water Composites., . . 33 3.7 Deviations from the REMP. . . . 33 3.7.1 Unavailable Samples.. . . 33 3.7.2 Lack of Sample Continuity.. . 34 3.7.3 Missed Lower Limits of Detection.. . 34 -
3.8 Land Use Census.. . . . 34 3.9 Sampling Schedule Change. . 34
4.0 CONCLUSION
S . . .46 APPENDIX A REMP DATA
SUMMARY
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1 APPENDIX B REMP DATA. . 54
f Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station .
TABLE OF CONTENTS l
Page LIST OF TABLES TABLE 2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING.. . . . . . . . . . . . . . .11 PROGRAM (REMP)
SUMMARY
TABLE
2.2 DESCRIPTION
OF REMP SAMPLING LOCATIONS.. . . . .. . . . . . . 12 TABLE 2.3 DETECTION CAPABILITIES FOR ENVIRONMENTAL . .. . ,. . .. .. 19 SAMPLE ANALYSIS, LOWER LIMIT OF DETECTION j l
(LLD) l TABLE 2.4 ANALYTICAL LABORATORY CROSS CHECK RESULTS . . . . . .20 TABLE 3.1 1997 DIRECT RADIATION DATA ORGANIZED BY . . . . 35 COMPASS DIRECTION AND DISTANCE FROM WATERFORD 3 SES 1 I
TABLE 3.2 STATISTICAL COMPARISON OF 1997 TLD . .. . .. . . . . . . . . . . . 36 MEASUREMENTS FROM STATIONS GROUPED BY .]
DISTANCE FROM WATERFORD 3 SES )
TABLE 3.3 STATISTICAL COMPARISON OF 1997 GROSS BETA .. . . . . . . . . . 37 ACTIVITY MEASURMENTS ON AIR PARTICULATE !
FILTERS FROM WATERFORD 3 SES i l
TABLE 3.4 STATISTICAL COMPARISON OF 1997 GROSS BETA . .. .. . 38 ACTIVITY MEASUREMENTS IN DRINKING / SURFACE j WATER SAMPLES FROM WATERFORD 3 SES l
TABLE 3.5
SUMMARY
OF 1997 REMP DEVIATIONS. . . . . . . . . .39 I
TABLE 3.6 1996 LAND USE CENSUS RESULTS. . . .. . .40 -
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! Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS Page LIST OF TABLES (continued)
TABLE
3.7 DESCRIPTION
OF RADIOLOGICAL ENVIRONMENTAL , . .. . .. . . 41 MONITORING PROGRAM SAMPLE SCHED'ULE CHANGE TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . .48 PROGRAM
SUMMARY
TABLE B-1 QUARTERLY TLD DOSE RATES. . . . . . . . . . . . . . . . .. .. .55 TABLE B-2 AIR PARTICULATE FILTERS AND CHARCOAL.. . . . . .. . . . . 56 CARTRIDGES: GROSS BETA AND LODINE-131 ANALYSES l
TABLE B-3 AIR PARTICULATE FILTERS: GAMMA ISOTOPIC . .. . . . . 60 l ANALYSES TABLE B-4 DRINKING / SURFACE WATER: LODINE-131 . .. . . . . . . . . . . . . 61 ANALYSES TABLE B-5 DRINKING / SURFACE WATER: GROSS BETA ... .. . . . . . . . . . . . . .. 64 1 ANALYSES TABLE B-6 DRINKING / SURFACE WATER: GAMMA ISOTOPIC . . . . . . . .67 l ANALYSES TABLE B-7 DRINKING / SURFACE WATER: TRITIUM ANALYSES . .. .. . . . . .. 70 TABLE B-8 GROUNDWATER: TRITIUM AND GAMMAISOTOPIC, . . . . 71 ANALYSES l
TABLE B-9 SHORELINE SOll: GAMMAISOTOPIC ANALYSES. . . . .72 TABLE B-10 MILK: LODINE-131 AND GAMMA ISOTOPIC ANALYSES .. .73 v j l I
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i Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station TABLE OF CONTENTS Page LIST OF TABLES (continued)
TABLE B-11 FISH: GAMMA ISOTOPIC ANALYSES. .. . .. ... . . .75 TABLE B-12 BROAD LEAF VEGETATION: LODINE-131 AND GAMMA. . . .77 ISOTOPIC ANALYSES TABLE R-13 GROUNDWATER SAMPLES FOLLOWING SPENT FUEL. . . . 80 POOL SPILL: TRITIUM AND GAMMAISOTOPIC ANALYSES TABLE B-14 SHORELINE SEDIMENT SAMPLES FOLLOWING SPENT.. . .85 FUEL POOL SPILL: GAMMA ISOTOPIC ANALYSES -
LIST OF FIGURES FIGURE 2.1 REMP SAMPLE LOCATIONS WITHIN 2 MILES OF . . . . . .. .. ..24 WATERFORD 3 FIGURE 2.2 REMP SAMPLE LOCATIONS WITHIN 10 MILES OF . . . . . ...25 WATERFORD 3 l
FIGURE 2.3 REMP SAMPLE LOCATIONS WITHIN 50 MILES OF . . . . . . . . 26 WATERFORD 3 FIGURE 3.1 DIRECT RADIATION DOSE COMPARISON .. . ... . . . . . . .42 FIGURE 3.2 GROSS BETA- AIR PARTICULATE COMPARISON. . .. .43 FIGURE 3.3 GROSS BETA- DRINKING / SURFACE WATER . .. . .. 44 .
COMPARISON FIGURE 3.4 SAMPLE LOCATIONS FOLLOWING SPENT FUEL . . .. 45 POOL SPILL VI i.
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Annu11 R:diological 1997 Environment:1 Operating R: port Wat:rford 3 Steam El ctric Station j l
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 l 1997. The results discussed in this report were used to evaluate the radiological environmental i 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 I impact of the plant. In order to conduct this evaluation, the data analyses and interpretations contained in this report fulfill the following specific objectives:
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. to identify any radioactive materials or radiation in the environment associated with l plant operation, I l
i . to compare the results obtained during the reporting period with past operational and pre-operational data and identify any trends associated with accumulation of radioactivity in the environment; and l
. to verify compliance with federal regulatory requirements.
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 fiow of water obtained !
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 northwestern section of St.
Charles Parish approximately 3 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 Ponchartrain, 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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I Annual Rrdiological 1997 Environrn ntal Operating Report Waterford 3 Steam Electric Station 2.0 PROGRAM DESCRIPTION !
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.
l 2.1 History and Development The Waterford 3 REMP evolved from the Pre-operational Environmental Radiological l Surveillance (PERS) prograrr (1978-1982) and was initiated in April of 1983. Equipment, l procedures, techniques, and sampling locations used during the pre-operational survey l 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, l were used to supplement the baseline established during the PERS Program.
2.2 Responsibilities l Waterforti 3 personnel are responsible for implementing and ensuring that the REMP l complies with federal regulatory, Technical Specification, and Offsite Dose Calculation l 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 analytical results l i
reports; and preparing and submitting the Annual Radiological Environmental Operating )
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Report and other relevant reports to the Nuclear Regulatory Commission.
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 results reports; and overseeing laboratory quality assurance j 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 Panasonic multi-element thermoluminescent dosimeters (TLDs) were analyzed by the TLD Process Laboratory at the Waterford 3 Nuclear Station.
I 2.3 Sample Collection and Handling Procedures l Sample types, location, collectiori frequency, and the analyses performed are j summarized in Tables 2.1 and 2.2. The information contained in these tables is based on
! requirements specified in Table 5.8-1 and Attachments 6.13 & 6.14 of the Waterford 3 l ODCM . Location maps of the sampling are illustrated in Figures 2.1 through 2.3. Any station deviations (i.e., unavailable samples and missed lower limits of detection) or changes made to the REMP during 1997 are discussed in Section 3.6.
The environmental samples collected are classified into four general categories according to exposure pathways: d rect radiation, airbome, waterborne, and ingestion. Sample collection and handling procedures are described in the following sections. The descriptions are intended to provide a concise procedural overview rather than a step-by-step description.
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I Annual Rtdiological 1997 Environmental Operating R:; port Watirford 3 St:am El ctric Station 2.3.1 Direct Radiation Exposure Pathway Samples Integrated external gamma exposure determined using Panasonic multi-element thermoluminescent desimeters (TLDs) was measured at thirty-one locations as follows:
e an inner ring of stations; one in each of the sixteen meteorological sectors in the general area of the site boundary; e an outer ring of stations; one in ten of the sixteen meteorological sectors in the six to eight kilometer range from the site; and
. the balance placed in areas of special interest (e.g., population centers, schools, etc.) with one area serving as a control.
The TLDs were exchanged quarterly by Waterford 3 personnel and were analyzed by the TLD Process Laboratory at the Waterford 3 Nuclear Station. '
Direct radiation exposure was also monitored by the Louisiana Radiation Protection Division (LRPD) during 1997. TLD locations that are the same for LRPD and Waterford 3 are noted on Table 2.2. Effective 1/1/98, the LRPD discontinued their monitoring for direct radiation exposure. q 2.3.2 Airborne Exposure Pathway Samples Samples of airborne particulates and radiciodines were collected at four indicator !
stations (APG-1, APO-1' APP-1, APC-1) and one control station (APE-30). Low-volume air pumps and flow totalizers in weather proof shelters provided l continuous air sampling.
Using the sampling devices described above, airborne particulate samples were ,
obtained on a filter and collected weekly (until March 31st) and then biweekly by l Waterford 3 personnel for shipment to the laboratory for gross beta analysis. The filters were composited quarterly oy the laboratory for isotopic analysis by gamma spectroscopy. i l
Airborne iodine sampling was done in conjunction with air particulate sampling using a charcoal cartridge to collect iodine. The cartridges were collected weekly .
(until March 31st) and then 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 surface 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.
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Annual Rrdiological 1997 Environmental Operating R: port Wat:rford 3 Stram Eltctric Station Composite drinking / surface water samples were obtained biweekly (until March 31st) and then 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 was added to each sample prior to shipment. The laboratory analyzed the biweekly /four week samples for lodine-131, composited them quarterly for gross beta, gamma spectroscopy and tritium analysis. ,
Groundwater:
Due to the high water table resulting from shallow aquifers in the vicinity of the site, drainage canal sampling represents groundwater discnarge. Groundwater was obtained quarterly by grab sampling from one sampling location (GWK-1).
Again, hydrochloric acid and sodium iodide was 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 shoreiine of the Mississippi River; 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 semi-monthly (until March 31st) and then monthly from one indicator location (MKO-5) and one control location (MKO-45).
Sampling of the control station was performed by Louisiana Radiation Protection Division personnel. Although one additional indicator location was identified (MKQ-1), no samples were available from this location during 1997 (see Section 3.6). Finally, formaldehyde and sodium iodide was added as a preservative to all milk samples. Upon arrival at the laboratory, lodine-131 and gamma spectroscopy analyses were performed.
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 analysis by gamma spectroscopy.
Broad leaf vegetation:
The Waterford 3 ODCM, Section 5.8.1, requires that broad leaf vegetation be sampled from 3 locations within 5 miles of the plant in the event milk samples are unavailable. Since milk samples were collected trem only one sampling location within five miles of Waterford 3, broad leaf vegetation was sampled monthly at 4
Annuil Radiological 1997 Environmental Operating Report Wat:rford 3 Steatr 'El:ctric Station two mdicator locations (BLO-1 and BLB-1) and ene control location (BLK-15).
The samples were shipped without further processing.
Food product:
Food product sampling was not required because no areas surrounding the plant were irrigated with water in which plant wastes are discharged. Effective March 31st, food product sampling was no longer required in accordance with the approved REMP reduction plan.
2.4 Analytical Procedures by Environmental Services Laboratory: j i
2.4.1 Sample Handling and Treatment '
The laboratory staff receipts and stores samples upon arrival. Environmental samples frequently require preparation prior to analysis, depending on media and analyses type.
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 refrigration until analysis can be performed.
Air Filters The laboratory handles air filters with care to avoid disturbing any 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 "
l 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 i 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.
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Annual R:diological 1997 Environm:ntal Operating R: port Wat:rford 3 Stram Elictric Station l 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 Air Sample Analysis The laboratory counts air filters for 100 minutes, or until required LLDs in ODCM Specification Table 6.12.1-3 are achieved, in a low-background alpha-beta l 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 isotope.'., such as radon and thoron daughters.
Gross Beta Water Sample Analysis This analysis measures overall beta radionuclides in water samples. It involves evaporating a suitable aliquote of sample (usually 100 mis.) in a beaker and then drying the beaker re.sidue 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 required LLDs in ODCM Specification Table 5.8-3 are achieved, in a low-background alpha-teta counting system. Activity calculation includes a self-absorption attenuauon factor (referred to as a salt density curve) for counter efficiency based on weight of residue on each planchet.
l Tritium Water Sample Analysis The laboratory typically adds six mis of water to 12 mis of liquid scintillation cocktail in a 20 mi vial, and then inserts the vial into a liquid scintillation l spectrometer for a 200 minute count, or until required LLDs in ODCM Specification Table 5.8-3 are achieved.
l l lodine-131 Sample Analysis I
The laboratory mixes four liters or more of the sample with a stable iodine carrier l solution and then stirs the sample with an anion exchange re.in 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 in ODCM Specification Table 5.8-3 are achieved.
Gamma Isotopic Sample Analysis Milk and Water
! 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 required LLDs in ODCM Specification Table 5.8-3 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 energy of each 6
Annual Rcdiological 1997 l Environmental Operating Rrport Waterford 3 Steam El:ctric Station l l
peak with a library of peaks for radionuclide identification and then performs a calculation using appropriate fractional gamma ray abundance, half life, detector i efficiency and net counts in the peak region.
Vegetation, Food and Garden Crops, and Fish The laboratory loads a maximum quantity of undried vegetation, food or garden I crop sample into a tared 1-liter marinelli beaker and weighs. The sample is then counted for 30 minutes, or until required LLDs in ODCM Specification Table 5.8-3 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 tared 0.5-liter marinelli beaker, or a lab-tech petri dish, depending on fish quantity, and weighs. The sample is then counted for a minimum of 30 minutes in a shielded intrinsic Germanium detector as described above.
Soils and Sediments The laboratory dries soil and sediment at a low temperature (110-135'C) in a convection oven, then loads into a tared 1.0-liter marinelli beaker and weighs.
The sample is then counted for 30 minutes, or until required LLDs in ODCM Specification Table 5.8-3 are achieved in a shielded intrinsic Germanium detector as described above.
Charcoal Cartridges 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 in ODCM Specification Table 5.8-3 are achieved.
l Air Particulate The laboratory stacks 13 air particulate filters, for a quarterly composite for each field station, one on top of another in a plastic petri dish and cover. The composite sample is counted for 30 minutes, or until required LLDs in ODCM Specification Table 5.8-3 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:
2 = XII n where:
X = Mean Xi = Individual sample results n = Number of sample results 7
l Annual R:diological 1997 Environmental Operating R: port Wat:rford 3 St:am El ctric Station The lab rounds calculated values by inspection of digits to the right of the third reported significant digit, with values less than 5 rounded down and values equal to or greater than 5 rounded up.
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 associated two sigma counting error, as a plus or minus (+) term.
1 The laboratory considers calendar quarters and a quarterly composite to be composed of 6 to 7 bi-weekly aliquots, or samples, such as for air particulate filters, or 3 to 4 monthly aliquots, or samples, such as for drinking water. ,
2.5 Environmental Dosimetry Panasonic Model UD-814 thermoluminescent dosimeters (TLDs) that contain one lithium borate and three calcium sulfate phosphor elements were used for environmental dosimetry. However, only the calcium sulfate phosphor elements were used for analysis. i 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.
l 2.6 Lower Limits of Detection (LLD) l The minimum sensitivities for the analytical procedures are reflected by the Lower Limits l of Detection (LLD) values presented in Table 2.3 from Table 5.8-3 of the Waterford 3 )
ODCM. 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.
2.7 Laboratory Quality Assurance l 2.7.1 Environmental Service Laboratory :
During 1997, the Environmental Service Laboratory at the River Bend Station participated in a Radiological interlaboratory Comparison (cross-l check) Program. This program satisfies the requirements of the Waterford 3 ODCM, Section 5.8.2, for participation in an interlaboratory comparison program. The program involved 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 (3 standard deviations), an l investigation was conducted to determine the cause, and corrective action was taken to prevent a recurrence. Table 2.4 lists the 1997 results of the laboratory's participation in the cross-check program.
Results of the Investigation of Out of Control Limits Explanation and Corrective Actions:
An investigation was conducted by the Environmental Service Laboratory at the River Bend Station into the cross-check analysis results which were outside the control limits as defined in note *d" in Table 2.4. In the 1997 I
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Annual Radiological 1997 i
Environmental Operating Rrport Wat rford 3 Steam Elsctric Station Cross-Check program, eight sample analysis results (from a total of one hundred and six sample results) were outside the control limits. These eight sample results are for the:
Second Quarter e E1034-125 (Analytics) of 4/07/97 Fe-59 E1036-125 (Analytics) of 4/07/97 Cs-137
- E1053-125 (Analytics) of 6/19/97 Cs-137 l
j Third Quarter
- E1147-125 (Analytics) of 09/18/97 Cs-134
. E1147-125(Analytics)of 09/18/97 Ce-141 Fourth Quarter
. E1228-125 (Analytics) of 12/11/97 Mn-54
. E1228-125 (Analytics) of 12/11/97 Fe-59 .
- E1229-125 (Analytics) of 12/11/97 Cr-51 l Program Exceptions:
There were eight results out of control limits (3 sigma) for the 1997 cross check program. Of these eight out of control limit results, all were analyzed by gamma spectroscopy (6 nuclides in two matrices). Five of the results in question were in liquid cross check samples, three in the sediment samples. -
There was a single result for Mn-54 in water out of control limits. Review of the cross check results for the year indicated a high bias for Fe-59 and Cs-137 in water, even though there were only two instances each out of control limits.
Investigation of this bias 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 in the energy region in j question, we will add two additional nuclides (Mn-54 and Zn-65) to the next set of l l liquid calibration sources purchased. The addition of these nuclides to the I calibration source should bring the results for the three nuclides in question within control limits.
Review of the three out of control limit results in the sediment samples did not indicate a trend or bias. Given the limited data for sediment cross check samples (4 samples) to date, it was not possible to establish a trend. The three out of :
control limit results were each for a different nuclide (Cr-51, Cs-134, and Ce-141). No corrective action due to these results will be taken at this time. If, after collection of additional data a trend or bias is established, corrective action will be taken at that time.
9
f l
Annu11 RIdiological 1997
! Environmental Operating Rtport Wat:rford 3 Stram Electric Station impact Statement:
There is no impact on past data indicated by these cross-check program 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-five percent of RBS environmental cross-check results are within control limits for accuracy and precision. .
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Annu:1 Radiological 1997 Environmental Operating Rrport Watsrford 3 Stram El:ctric Station TABLE 2.4 ENVIRONMENTAL (CROSS-CHECK) PROGRAM PARTICIPATION RESULTS Sa pgT pe Study Date Analysis "Known" Value' VaYue N DEV" N N GE' gFg,r E1148-125 9/18/97 Beta 108 1 17.3 109 0.17 0.000 E1230-125 12/11/97 Beta } 39.01 8.7 40.3 ) 0.46 0.272 Charcoal Cartridge E1035-125 4a/97 l-131 89.0115.4 89.6 0.11 0.106 l (pCi/ cartridge) . .
E1052-125 6/19/97 l-131 l 86 i 14.9 86.0 -0.01 0.048 E1149-125 9/18/97 l-131 611 10.6 63.4 l 0.67 0.426 E1231-125 12/11/97 ' l-131 30.0 i 10.4 } 31.5 ) 0.44 0.384 gtg E1032-125 4/7/97 Beta 144 i 37.4 168 1.95 0.438 E1033-125 4/7/97 H-3 3397i 629 l 3285 -0.53 0.186 E1034-125 4R/97 Cr-51 267 1 23.1 264 -0.43
} 1.549 )
l Mn-54 183 1 15.8 190 1.33 0.129 Co-58 72.01 8.7 l 67.8 ) -1.44 0.851 Fe-59 117 i 10.1
) 133 l 4 1.313 Co-60 189 i 16.4 j 191 0.31 0.188 Zn-65 170 i 29.4 181 1.09 0.069
~
Cs-134 152 1 13.2 153 0.30 0.389 Cs-137 123 i 10.7 123 -0.09 0.288 Ce-141 }~ 1711 14.8 168
-0.54 0.069 E1036-125 4/7/97 Cr-51 } 267 1 23.1 264 -0.39 0.841
+
(duplicate) Mn-54 1831 15.5 188 1.01 0.129
~
Co-58 72 i 8.7 69 -1.03 0 378
~
Fe-59 117 i 10.1 127 2.96 0.606 Co-60 189 i 16.4 189 -0.06 0.250 .
- ~
Zn-65 170 1 29.4 190 2.04 0.382
, }
I Cs 134 152 i 13.2
~
155 0.61 0.233 Cs-137 123 1 10.7 134 kg; 0.480 j Ce-141 171 i 14.8 173 0.41 0.691 E1049-125 6/19/97 Beta 139 i 36.1 137 -0.19 0.368 E1050-125 6/19/97 H-3 1313i 575 1317 0.02 0.197 E1051-125 6/19/97 Cr-51 288 i 24.9 272 -1.92 1.436 Mr44 123 1 10.7 128 1.50 0.288 l
^
Co-58 1121 9.7 115 1.03 0.105 Fe-59 110 i 9.5- } 114 1.26 2.148
~
Co 60 151 1 13.1 155 0.84 0.704 Zn-65 203 1 35.2 224 1.82 0.029
~
l-131 61.0 i 10.6 64.2 0.90 0.571 Cs-134 118 i 10.2 123 1.37 0.100 Cs-137 167 1 14.5 181 2.83 0.212
} l Ce-141 l 192 1 16.6 197 l 0.84 0.369 20
Annual Radiologic:l 1997 Environrnental Operating R: port Wat:rford 3 St:am Electric Station ENVIRONMENTAL (CROSS-CHECK) PROGRAM PARTICIPATION RESULTS Sa p e T pe Study Date Analysis
Known" Value' Va NNV6 N GE' Water (pCi/ liter) E1053-125 6/19/97 Cr-51 288 1 24.9 282 -0.68 1.395
^
(duplicate) Mn-54 123 1 10.7 132 2.44 0.480 i
Co-58 112 i 9.7 114 0.62 0.316 l
Fe-59 1101 9.5 118 2.52 0.215 Co40 f 151 i 'i3.1 157 1.30 O.469 Zn-65 203
- 35.2 228 2.10 0.145 '
i 1-131 61.0 i 10.6 60.0 -0.29 0.455 Cs-134 f 118 i 10.2 121 0.78 f a1M Cs-137 } ,
167 1 14.5 182 .~_ 0.495 Ce-141 192 1 16.6 l 193 0.24 0.308 E1146-125 9/18/97 C7-51 239 i 20.7 226 -1.84 0.840 Mn-54 69.0 i 8.7 71.0 0.68 0.319 Co-58 47.01 8.7 f 48.0 0.36 0.118 Fe-59 94.0 i 8 7 102 2.77 1.181 f
Co40' 155 1 13.4 l 155 0.00 0.229 Zn45 154 1 26.7 153 -0.07 0.384 l-131 94.0 i 16.3 96.9 [ 0.54 0.283
- I Cs-134 80.0 i 8.7 f* 79.0 f -0.36 0.177 Cs-137 84.0 t 8.7 85.9 0.65 O.248 l Ce-141 60.01 8.7 57.8 -0.75 0.520 )
E1150-125 9/18/97 Cr-51 } 239 1 20.7 243 0.53 } 1.730 (duplicate) Mn-54 69.0 i 8.7 72.4 1.18 0.118
}
Co-58 47.0 i 8.7 48.6 0.57 0.461 Fe-59 94.01 8.7 102 2.7T ~~ 1.181 Co40 155 i 13.4 } 160 1.04 0.762 Zn45 154 1 26.7 164 1.16 0.345 l-131 94.01 16.3 94.1 0.02 0.798 J I
Cs-134 80.01 8.7 75.5 -1.57 0.390 Cs-137 84.01 8.7 33.5 -0.16 } 0.449 Ce-141 60.0 i 8.7 54.4 -1.94 0.449 E1228-125 12/11/97 Cr-51 334 1 28.9 336 0.24 1.768 Mn-54 f 137 i 11.9 89.01 8.7 149
( 0.172 Co-58 } 94.9 2.04 l 0.295 Fe-59 f 97.0 i 8.7 ,
106 h [ 0.236 Co40 l 161 1 13.9 160 0.14 0 220 Zn-65 } 2411 41.7 257 1.15
^
0.319 l-131 f 454i 1a4 48.9 1.12 a315 Cs-134 171 1 14.8 173 0.34 0.138
}'
Cs-137 l 177 i 15.3 182 0.91 0.200 Ce-141 f 167 1 14.5 i 167 0.07 0.637 21
l l.
l Annual Radiological 1997 Environm:ntal Operating Rsport Wat rford 3 Steam Electric Station ENVIRONMENTAL (CROSS-CHECK) PROGRAM PARTICIPATION RESULTS Sa pie T pe Study Date Analysis "Known" Value' Va NYEV" N N GE' Water (pCi/hter) E1232-125 12/11/97 Cr-51 334 1 28.9 345 1.11 1.839 (duplicate) Mn-54 137 1 11.9 145 2.11 0.345
~
f Co-58 89.0 i 8.7 95 2.iO 0.473
( Fe-59 97.01 8.7 105 2.89 , 0.118 Co-60 161 1 13.9 162 0.22 }~ ').293
~
- 2411 41.7 267 1.84 0.a1 Zn-65 [
1131 45.01 10.4 43.5 -0.43 0.3%
{ , ,
Cs-134 171 1 14.8 168 -0.68 0.138 -
Cs-137 177 i 15.3 182 1.04 0.133 Ce-141 167 1 14.5 165 -0.48 0.210
~
ggn E1147-125 9/18/97 Cr-51 0.709 i 0.061 0.697 -0.58 0.236 Mn-54 0.206 i 0.017 0.209 0.46 0.118 Co-58 , 0.141 1 0.012 0.143 0.41 } 0.591 Fe-59 0.278 i 0.024 0.278 -0.04 0.127 Co-60 0.460 1 0.04 } 0.455 -0.38 0.051 Zn-65 0.458i 0.08 } 0.461 0.13 0.141
~
Cs-134 0.239 1 0.021 f 0.218 .I[.? ..; jh 0.098 Cs-137 0.377 i 0.033 -1.34 0.031
, f 0.362 l l Ce-141 0.178 i 0.015 0.194 0.265
~
l E1229-125 12/1197 } Cr-51 0.491 1 0.043 0.444 1.299
[ Mn-54 0.202 i 0.017 0.215 2.31 0.354 Co-58 0.136 1.49 0.506 f 0.13010.012 Fe-59 0.142 1 0.012 0.140 -0.41 0.084 Co-60 0.237 i 0.021 0.238 0.14 0.148 Zn-65 0.355 1 0.062 0.370 0.72 0.164 Cs-134 0.251 1 0.023 0.242 -1.24 0.091 O.380 -0.64 0.342
[ Cs-137 } 0.387i 0.033 l
l Ce-141 1 0.246 i 0.021 0.258 1.73 0.984 NOTES:
i (a) The "known" values are listed with a range reflecting control (3 sigma) limits.
l (b) The normalized deviation from the "known" value is computed from the deviation and the standard error of the mean; 12.000 is l the waming limit and 13.000 is the controllimit. This is a measure of accuracy of the analytical rrethods.
! (c) The normalized range is computed from the mean range, the control limit, and the standard error of the range; +2 000 is the
, waming limit and +1000 is the control hmit. This is a measure of precision of the anaYtical methods.
l (d) The results reported were out of the controllimits; refer to the discussion on program exceptions.
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Annu:1 R*diological 1997 Environmental Oper ting R: port \Nat:rford 3 Stram El ctric Station 3.0 DISCUSSION OF RESULTS Analytical results for the year 1997 are discussed in this section by exposure pathway, sample type, and analysis performed. Further, analytical results focusing only on man-made radioactivity are summarized in Appendix A; data for the individual analyses are prosented in the tables of Appendix B.
3.1 Direct Radiation Exposure Pathway The average exposure rates measured by thermoluminscent dosimeters (TLDs) at both control and indicator stations were 12,13,12, and 13 mrem / standard quarter for the first, second, third, and fourth quarters of 1997, respectively.
The average exposure rate of the 120 indicator TLD locations was 13 mrem / standard quarter compared to 11 mrem / standard quarter average exposure rate at the control location. The lowest and highest individual exposure rates were 4 mrem / standard quarter (M-1,1st quarter) and 21 mrem / standard quarter (N-1,2nd 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 l 1997 to be 15 mrem / standard quarter in Sector N. '
The average exposure rates during 1997 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 to 23 mrem / standard quarter with an average exposure rate of 13 mrem / standard quarter. ,
3.2 Airborne Exposure Pathway 3.2.1 Airborne Particulates Gross beta activity ranged from 0.001 pCi/m' (APC-1, 9/29 -10/13) to 0.036 pCi/m* (APG-1,1/6 -1/13) with an average of 0.019 pCi/m for 160 measurements from all five locations. The average gross beta activity for the indicator (APG-1, APQ-1, APP-1, APC-1) locations was 0.019 pCi/m' compared to 0.020 pCi/m3 at the control location (APE-30).
The airborne gross beta activity results obtained during 1997 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 1995, the average gross beta activity per year for the indicator 8
, locations ranged from 0.014 to 0.027 pCi/m with an average of 0.019 l pCi/m* compared to 0.020 pCi/m* at the control location. Also, the pre-l operational survey indicates that in periods not significantly influenced l by nuclear weapons testing, the gross beta activity ranged between 0.007 and 0.480 pCi/m with an average of 0.080 pCi/m .
27 l
_. s
l
- Annual Rtdiological 1997 Environmental Operating Rrport Wat
- rford 3 Stram El ctric Station
! 3.2.2 Airborne lodine All of the 160 airborne lodine-131 results were below the calculated lower limit of detection (LLD) which varied from 0.003 to 0.046 pCi/m' and were below the required LLD (0.7 pCi/m* ) required by the Waterford 3 ODCM. The sample LLD variability was due primarily to the difference in air sample volumes.
l 3.2.3 Gamma Isotopic Analysis Gamma spectroscopy results of the twenty air sample quarterly ;
composites indicate that no man-made radionuclides were detected I above their respective lower limits of detection.
i 3.2 Waterborne Exposure Pathway 3.3.1 Drinking / Surface Water
)
j As mentioned previously, drinking water samples also serve as surface l water samples for Waterford 3. Therefore, monthly and quarter!y gamma spectroscopy analyses of drinking water and quarterly tritium j analyses also satisfy the surface water sampling requirement.
! Forty-eight composite drinking / surface water samples were analyzed by l
gamma spectroscopy for lodine-131 (Table B-4). All of the 48 composite sample iodine-131 results were below the calculated lower -
limit of detection (LLD).
Gross beta activity was detected in eighteen of the eighteen composites with a range of 2.5 (DWE 5,2/17 - 3/31) to 6.5 (DWG-5, 7/21-9/15) pCi/l and an average activity of 4.9 pCi/l. The average activity for the control location, DWP-7, was 4.2 pCill compared to the averages of 5.5 and 4.2 pCi/l for indicator stations DWG-2 and DWE-5, l respectively.
Analyses for gross beta in drinking / surface water were not performed during the pre-operational survey. However, in order to fulfill comparison requirements,1997 data will be compared to data from the 1983 report and the previous years of operation.
l The gross beta activity results obtained during 1997 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 1996, the average gross beta activity per year for the indicator locations ranged from 2.4 to 16.3 pCi/l 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/l with an average ,
of 7.0 pCi/l.
28
i Annu:1 R:diological 1997
! Environmental Operating R: port Wat:rford 3 Stram Electric Station Twenty-one composite drinking / surface water samples were analyzed by gamma spectroscopy. Results indicate that all measurements were below the calculated LLDs.
Tritium analysis of drinking / surface water samples indicate that six of the i twelve measurements were below the calculated LLD. Tritium was l detected in two samples from the indicator location DWG-2 (4261201
- pCill,1/1-3/31 and 3391200 pCi/l,4/28-6/23), three samples from the indicator location DWE-5 (4081201,1/1 - 3/31, 2451198, 4/28 - 6/23 and 2091201,7/21 - 9/15) and in one control sample DWP-7 (5441205 l- pCi/l, 1/1-3/31). The detected activities in these samples were considerably below the LLD (2000 pCi/ liter) required by the Waterford 3 ODCM and have a very high level of statistical uncertainty associated
! with them.
l The tritium concentrations detected in 1997 are 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 pCi/l with an average of 116 pCi/l. Similarly, the range indicated in the l previous years of operation was from 170 to 545 pCi/l.
l 3.3.2 Groundwater l -
Five groundwater samples were collected from one sampling location,
. GWK-1, and analyzed for tritium and gamma emitters. Tritium was
! detected in four of the five groundwater samples. The detected tritium l activities in these samples ranged between 516 and 4097 pCill with an
[ average activity of 1945 pCi/l.
l The tritium concentrations detected in 1997 are slightly higher than l those from the pre-operational program and the previous years of l operation. In particular, the pre-operational survey indicates that tritium concentrations in groundwater samples ranged between 50 and 180 pCi/l with an average of 121 pCi/l. Similarly, the range indicated in the i previous years of operation was from 249 to 650 pCi/l.
l l While the tritium concentrations detected in 1997 are slightly higher l than from the pre-operatioral program and the previous years of l operation, they are consistent with observed effluent release data via l 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 29
Annu 1R:diological 1997 Environmental Operating R: port Wat:rford 3 St:am El:ctric Station (50% of the reporting levels in tritium in water), increased monitoring will be implemented.
3.3.3 Shoreline Sediment Five shoreline soil samples were collected from the following sampling locations: two samples from the Mississippi River shoreline downriver of the plant (SHWE-3) and three 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 70 +/- 16 pCi/kg (dry).
Cesium-137 was also detected in the sample from station SHWE-3 with the highest concentration at 59 +/- 11 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 1997 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 1997 is more than likely attributable to weapon testing fallout.
3.4 Ingestion Exposure Pathway 3.4.1 Milk Thirty milk samples were collected from two sampling locations and analyzed by gamma spectroscopy and a radiochemical procedure for lodine-131. Results from these analyses indicate that all measurements were below the calculated LLD.
3.4.2 Fish Eleven fish samples, six upstream and five downstream of the plant were collected and the edible portions analyzed by gamma spectroscopy, No man-made radionuclides were detected above their lower limit of detection in any of the samples.
3.4.3 Broad Leaf Vegetation Thirty-six 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.
30
Annut! Radiological 1997 Environmental Operating R: port Wat rford 3 Steam El:ctric Station No man-made radionuclides wore detected in any of the collected samples above their calculated LLDs.
3.5 - Samples Following the Spent Fuel Pool Spill immediately following the spent fuel pool spill which occurred on 05/21/97 groundwater and shoreline sediment samples were taken by Waterford 3 and analyzed by the Environmental Services Laboratory. Five sample locations were chosen as illustrated in Figure 3.4. Samples were collected from each of the five locations from May through December.
- 3.5.1 Groundwater Groundwater samples were analyzed for tritium and gamma emitters.
Resul;s from the gamma analyses indicate that all measurements were below the calculated LLDs as illiustrated in Table B-13. Tritium was detected in 34 of the 40 samples taken. The detected tritium activity in these samples ranged between 253 and 4033 pCi/ liter with an average activity of 1149 pCi/ liter.
3.5.2 Shoreline Sediment Sediment samples were analyzed for gamma emitters. Results from the gamma analyses indicated the presence of Co-58, Co-60, and Cs-134 and Cs-137. The average activity of Co-58 was 407 pCi/kg (dry) with a range of 22 to 995 pCi/kg (dry). Co-60 was detected in only one sample with a result of 41 pCi/kg (dry). The average Cs-134 activity was 165 pCi/kg (dry) with a range of 14 to 563 pCi/kg (dry). The average Cs-137 activity was 113 pCi/kg (dry) with a range of 19 to 887 pCl/kg (dry). These results are indicated in Table B-14.
3.6 Statistical Analyses 3.6.1 Calculation of the Mean and Standard Deviation The mean and standard deviation for different groups of analyses are calculated using the following equations:
X=fE l*l and 31 .
I J
l Annual Radiologic l 1997 Environ.nental Operating Raport Wattrford 3 Stsim Elrctric Station ,
r ,, m 03
[ (Xs - X)'
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.
3.6.2 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 f
2 / \23 03 r 3 0.5 fil,-I)S,+(liy~I)Sy 1 1
_+_
g 11x *lly ~ 1 , < 11, fly) where:
t = calculated "t" value, X = mean of first data set, Y = mean of second data set, y, = number of variables in first data set, S , = standard deviation of first data set, n, = 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 y) 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 , > my, 32 I .
i l Annual Rrdiological 1997 Environmental Operating R: port Wat:rford 3 Stsam Electric Station
! b. if t < -t p,n then reject the hypothesis when m , < my,
- c. if t > t pa,n then reject the hypothesis when m , = m y, where t pa,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 y-2. Tabular values of the "t" were obtained from the CRC Standard Mathematical Tables,26th Edition (1981).
3.6.3 TLD Measurements l
l . l TLD stations were categorized by distance into three groups: 0-2 m"es, 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 l the rates at >5 miles. Table 3.2 summarizes the results of this analysis.
3.6.4 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 l
APP-1) to be statistically the same as the activity detected at the control station. Table 3.3 summarizes the results of this analysis.
3.6.5 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 l 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. Table 3.4 summarizes the results of this analysis. j i
3.7 Deviations from the REMP i l
3.7.1 Unavailable Samples One milk sample from location MKQ-5 and three milk samples from location MKQ-45 were unavailable during the 1997 reporting pe"ici l The milk samples were unavailable due to cows not producing enough j milk and the owner of the dairy selling his business. This is summarized in Table 3.5 1 Milk samples were not available during 1997 from the tiiiiir.c! owners at location MKQ-1 since the cows are not currently producing milk for human consumption. With the absence of milk samples at these I locations, broad leaf vegetation sampling was performed. I 33
Annual Radiological 1997 Environmental Operating RIport Watirford 3 Stum Electric Station 3.7.2 Lack of Sample Continuity Four air samples and one water sample failed to meet the requirement for sample continuity as explained in Table 3.5.
3.7.3 Missed Lower Limits of Detection All lower limit of detection requirements were met for 1997.
3.8 Land Use Census The revised sampling schedule presented in Table 3.7 reflects that the land use census is performed biennially instead of annually. A land use census was not performed in 1997. The results of the land use census in this report are from the census performed on October 2nd and 3rd of 1996. These results can be found on Table 3.6. The land use census will be performed again in 1998. '
3.9 Sampling Schedule Change Based on Waterford 3 operational historical data, the REMP sampling frequency schedule was revised below what is defined in the NRC Branch Technical Position, Revision 1, November 1979 as documented in Radiation Protection calculation file # HP-CALC-96-005. Also, food product sampling was deleted based on the historical data and no areas surrounding the plant are irrigated with water in which plant wastes are discharged. The revised sen.pling schedule is presented in Table 3.7. This change has been covered in the Offsite Dose Calculation Manual (ODCM) and the Technical Requirements Manual (TRM).
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nn AE l, l 1 1 I 1 Annual Radiological 1997 I Environmental Operating Report Waterford 3 Steam Electric Station Sample Locations Following spent Fuel pool 3pijg Flgure 3.4 ~~~ ~! GW84 SHWS4 W+ , / 1 l - ,6 -[ s 1 \, ,pt w y Y- i ' ,/ THB GWS.5 'j .. { i, SHWS4 { i l ses ' i M8 i 1 f \ k* ! . 1 i' I ) / i . 1. g y l I't
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y cWS.1 SHWS-1 GWSJ SHWSJ ) LA 3127 45 I 1 Annual Radiological 1997 l Environmental Operating Report Waterford 3 Steam Electric Station l
4.0 CONCLUSION
S The radiological environmental data collected during 1997 is consistent with the data obtained during the previous years of plant operation (1985-96), 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 man- I made radionuclide detected in the routine environmental samples analyzed during 1997 was Cesium-137. Special environmental sampling performed after the spent fuel pool i spill (all located on site property) indicated additional man-made radionuclid. as discussed below. l Cesium-137 was detected in five 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. j Tritium was detected in surface / drinking water samples (five indicator samples and one control sample). The detected activities in the surface / drinking water samples were below the LLD required by the Waterford 3 ODCM. The tritium concentrations detected in 1997 are consistent with those from the pre-operational program and the previous years of operation. l Tritium was also detected in four ground water samples. Even though values observed were greater than the required LLD, tritium is routinely released as measured in effluent ,
sampling analysis via this pathway. Those levels observed are consistent with effluent sampling and analysis results.
Groundwater and sediment samples were taken following the spent fuel pool spill.
Tritium was detected in 34 of the 40 groundwater samples taken. Even though values observed were greater than the required LLD, tritium is routinely released as measured in effluent sampling analysis via this pathway. While the levels detected were above what is normally observed, these levels observed are consistent with effluent sampling and analysis results. Sediment samples indicated the presence of Co-58, Co-60, Cs-134 and Cs-137.
In conclusion, based on the evaluation of the REMP data collected during 1997 the operation of Waterford 3 had no discernable radiological impact on the environment.
i 46
Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station l
l l
APPENDIX A REMP DATA
SUMMARY
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Annual Radiological 1997 Environmental Operating Report Waterford 3 Steam Electric Station APPENDIX B 1
REMP DATA 1
l l
l 1
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7 n 9 io 9t 1 at k 8479587724533882062967956241 73 867898487975565807465474446888 382 060 S 000001 1 0000000001 1 000043000000 201 c
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t o
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