ML20029D113
| ML20029D113 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1993 |
| From: | Hagan R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NA-94-0072, NA-94-72, NUDOCS 9405040047 | |
| Download: ML20029D113 (142) | |
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i J W4pLF CREEK NUCIEAR OPERATING CORPORATION Robert C. Hagan Vice President Nuclear Assurance April 28, 1994 NA 94-0072 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, D. C. 20555
Subject:
Docket No. 50-482: Annual Environmental Operating Report Gentlemen: Enclosed is the Annual Environmental Operating Report which is being submitted ' pursuant to Wolf Creck Generating Station (WCGS) Facility Operating License NPF-42, Appendix B. This report covers the operating of WCGS for the period of January 1, 1993 to December 31, 1993. Very truly your. Jr L .j '8b % \ // v obert C. Eagan RCII/j ad Enclosure
.c c : L. J. Callan (NRC), w/a G. A. Pick (NRC), w/a W. D. Reckley (NRC), w/a L. A. Vandell (NRC ) , w/a
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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 1993 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT a s Y.-' p.- t vg APRIL 15,1994
TABLE OF CONTENTS LIST OF TABLES li LIST OF FIGURES ill 1 INTRODUCTION
- 1. PROGRAM DESCRIPTION 2
- 11. DISCUSSION OF RESULTS S 111. ANNUAL LAND USE CENSUS RESULTS AND PROGRAM REVISIONS 9 IV. PROGRAM DEVIATIONS 10 V. EPA INTERLABORATORY COMPARISON RESULTS 13
6 LIST OF TABLES TABLE 1: 1993 Radiological Environmental Monitoring Program Sample Collection 14 TABLE 2: Sample Location Numbers, Distances, and Directions 20 TABLE 3: 1993 Airborne Particulate Gross Beta Analyses 21 TABLE 4: Airborne Particulate Quarterly Composite Gamma Isotopic Analyses 22 TABLE 5: 1993 First & Second Quarter TLD Results 23 TABLE 6: 1993 Third & Fourth Quarter TLD Results 24 TABLE 7: 1993 Drinking Water Radiological Analyses 25 TABLE 8: 1993 Surface Water Radiological Analyses 26 TABLE 9: 1993 Ground Water Radiological Analyses 27 TABLE 10: 1993 Aquatic Plants Radiological Analyses 27 TABLE 11: 1993 Shoreline Sediment Radiological Analyses 28 TABLE 12: 1993 Bottom Sediment Radiological Analyses 29 TABLE 13: 1C33 Broadleaf Vegetation Radiological Analyses 30 TABLE 14: 1993 Irrigated Crops Radiological Analyses 30 TABLE 15: 1993 Milk Radiological Analyses 31 TABLE 16: 1993 Fish Radiological Analyses 32 TABLE 17: 1993 Land Use Census Residence Data 33 TABLE 18: 1993 Land Use Census Milk and Garden Data 34 TABLE 19: 1993 US EPA Interlaboratory Comparison Program 35 ii
e h LIST OF FIGURES FIGURE 1: Airborne Pathway Sampling Locations 37 FIGURE 2: Direct Radiation Pathway Sampling Locations 38 FIGURE 3: Waterborne Pathway Sampling Locations 39 FIGURE 4: Ingestion Pathway Sampling Locations 40 FIGURE 5: Distant Sampling Locations 41 FIGURE 6: 1993 Airborne Gross Beta Weekly Results 42 FIG'JRE 7: Historical Location 40 (Control) Smoothed Gross Beta 43 FIGURE 8: Historical Gross Beta Smoothed Weekly Indicator to Control Ratio 44 FIGURE 9: Gross Beta Historical Weekly Indicator Average and Cmtrol 45 FIGURE 10: Variation of Nearsite TLD Averages 46 FIGURE 11: TLD Nearsite Average and Control Average, Historical 47 FIGURE 12: WCGS Surface Water and Cumulative Liquid Effluent Tritium Data 48 FIGURE 13: WCGS Surface Water and Quarterly Liquid Effluent Tritium Data 49 FIGURE 14: Drinking Water Gross Beta (Historical) 50 iii
e h INTRODUCTION The 1993 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS) covers the period from January 1 though December 31,1993. WCGS is located in Coffey County, Kansas, approximately five miles nortr,-;ast of Burlington, Kansas. Fuel loading commenced at WCGS on March 12,1985. The operational phase of the Radiological Environmental Monitoring Program (REMP) began on May 22,1985 with initial criticality and the first detectable quantities of radioactivity were reported in plar1 effluents in June 1985. This report contains a description of the REMP conducted by Woif Creek Nuclear Operating Corporation (WCNOC), results of sample analyses performed by Teledyne isotopes and WCNOC health physics technicians, a discussion of monitoring program results, a description of revisions to and deviations from the program, and comments on the results of the Environmental Protection Agency (EPA) Interlaboratory Comparison Program. Individual sample results and a summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Position specified format are included as appendices to the report. No radiological e' feds of plant operations were detected in airbome particulate and radiciodine filters, fish, irrigated crops, breadleaf vegetation, milk, ground water, or drinking water. During 1993, activation products were detected in aquatic plants and algae, shoreline soil, and bottom sediment samples. No measurable impact on human exposure due to plant operation was seen for the year. I I l I 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 1 of 50
- 1. PROGRAM DESCRIPTION Radiological environmental samples were collected according to the schedule in Section 5.0 and Table 5-1 of the WCGS Offsite Dose Calculation Manual (ODCM). All samples were collected by WCNOC's Environmental Management and Radiological Services groups. The samples were processed and analyzed by Teledyne isotopes of Westwood, New Jersey. Table 1 lists sampling pathways and frequencies of sampling and analysis. Table 2 lists each sample location's distance and direction from the plant. Samples in addition to those required by the WCGS ODCM were obtained in conjunction with the Kansas Department of Health and Environment (KDHE) and to monitor additional parameters.
The following is a description of the sampling and analysk program by individual pathways. Deviations are permitted from the required sampling schedule if specimens are not attainable due to hazardous conditions, seasonable unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. Deviations from the routine sampling schedule and other problems encountered during the year are described in Section IV, Program Deviations. A. Airborne Low volume air sampling pumps continuously collected particulate and radioiodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. Weekly, the filters and charcoal canisters are changed out, labeled, and then shipped to Teledyne Isotopes for analysis. The volume of air sampled was calculated from the average of initial and final flow rates and the total time of collection. Each pump is equipped with a time totalizer that is checked weekly against the elapsed time. Gross beta analysis of the air particulate samples were performed approximately 72 hours post collection to allow the radon and thoron daughter products to decay. Each filter was mounted on a stainless steel planchette and counted on an automatic alpha-beta counter. Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes on a Ge(Li) detector. Charcoal canisters were routinely counted in groups of five to determine the presence or absence of I-131. Positive indication of I-131 would have resulted in analysis of each individual charcoal canister. Air samples were collected from the three sectors with the highest ground level deposition constants (D/Q), the community of New Strawn, and a control location. Distances and directions to sampling locations from the plant site are listed in Table 2; locations are shown in Figure 1 (nearby locations) and Figure 5 (distant locations). B. Direct Radiation One type of thermoluminescent dosimeters (TLDs) used during 1993 were provided by Teledyne isotopes. The TLDs consisted of rectangular Teflon wafers impregnated with CaSO4:Dy. Prior to placement in the field, the dosimeters were annealed for at least one hour at 250 to 260 degrees Centigrade. The TLDs are then placed in polyethylene pouches and holders containing 0.093 inch thick copper shields to filter out low energy radiation. Freshly annealed dosimeters were exchanged with exposed dosimeters and the exposed dosimeters are shipped to Teledyne isotopes for analysis. Four freshly annealed TLDs are shipped as controls with the exposed TLDs to record any exposure received in transit. 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 2 of 50
- )
Gamma exposures are measured on a Teledyne Model 8300 TLD reader. Individual dosimeters are then exposed to a Cs-137 source to determine each dosimeter's calibration factor. Panasonic UD-814-AQ TLDs were also used during the third and fourth quarters of 1993. These TLDs consist of one lithium-borate element and three calcium sulfate elements in a plastic case. Each TLD is annealed and analyzed by Wolf Creek health physics technicians on a Panasonic UD-710A TLD reader. In general, TLDs are positioned roughly 3 to 4 feet above the ground on utility poles. They are contained in either plastic thermostat boxes or f3erglass air sample pump housings. The boxes and housings protect them from the elements and tampering. Two TLDs are placed at each designated location. TLD sample locations are illustrated in Figure 2 (nearby locations) and Figure 5 (distant locations). Table 2 provides the distance and direction of each location from the site. C. Waterborne All water samples are analyzed for gamma emitters on a Ge(Li) detector. Radiochemical analysis for 1-131 is performed on drinking water and ground water samples. Gross beta analysis is performed on drinking water samples. Tritium analysis is performed by liquid scintillation monthly for surface water and quarterly for drinking water. Tritium analysis is performed by gas proportional counter quarterly for ground water. All water sampling locationsare listed in Table 2 and shown in Figures 3 and 5. Drinking water is sampled at the water treatment facilities for the towns of Burlington and Leroy. The Burlington facility is located upstream and the Leroy facility is located downstream of the confluence of the effluent from Wolf Creek Cooling Lake (WCCL) and the Neosho River. Monthly, composite samples are obtained from automatic composite samplers at each location that draw approximately 10 ml samples hourly. Monthly, grab samples are drawn from each surface water location. Surface water is sampled at the outfall of John Redmond Reservoir (JRR) as a control and in the discharge cove and spillway of WCCL for indicator locations. ' Ground water samples are collected quarterly from four locations. One ground water well is hydrologically upgradient from the site (location B-12) and is used as a control location. Three additional samples (C-10, C-49, and D-65) are obtained from wells hydrologically downgradient from the site as indicator samples. Shoreline sediments are sampled semiannually for gamma analysis at the discharge cove (indicator, Figure 3) and at JRR (control, Figure 3). Bottom sediments are also collected semiannually. Samples are obtained for gamma analysis at the discharge cove (indicator, Figure 3) and at JRR (control, Figure 3). In addition, a sample was obtained in the area of the ultimate heat sink (UHS, Figure 3) Semiannual aquatic plant and algae samples are obtained for gamma analysis from the discharge cove area or from an attemate location near the discharge cove (DC and DC ALT, respectively on j Figure 3). 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 3 of 50
i l D. Ingestion Milk samples are collected semimonthly from April through November (while the animals are feeding on pasture grass) and monthly from December through March (while the animals are on stored feed). No sampling locations were identified within 5 miles of the plant that produced milk for human consumption during 1993. Therefore, only control samples were obtained. Radiochemical l-131 and gamma isotopic analyses were performed on each sample. The control location is illustrated on Figure 5. 1 Broadleaf vegetation samples were collected monthly during the growing season from four gardens. The three indicator gardens (two regular and one alternate) and a control garden were sampled (Figure 5). Gamma isotopic analysis was performed on all samples. Irrigated crops (soybeans and corn) were also sampled. Two samples were obtained from cropland downstream of the confluence of WCCL effluents and the Neosho River gadicator) and one sample was obtained upstream (control). However, due to high rainfall amounts in the region during 1993, no irrigation from the Neosho River occurred during 1993. The samples were still obtained to serve as baseline data and to continue contact with local landowners. Gamma isotopic analysis was performed on each sample. Fish are sampled from the tail waters of JRR (control) and from WCCL semiannually for gamma isotopic analysis (Figure 4). Several recreationally important species and rough species are sampled. Gamma isotopic analysis is performed on boneless meat portions of the fish. [ l Game animals and fowl are sampled annually in the immediate vicinity of the plant and at a control i locc.on that is remote from the site. Gamma isotopic analysis is performed on boneless meat portions of the game. All sampling locations listed in this section are outlined in Table 2. l l l l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 4 of 50 e- -
l II. DISCUSSION OF RESULTS l Analysis results for all pathways are summarized in Appendix A using the format described in NRC J Radiological Assessment Branch Technical Position, Revision 1, November 1979. Results for l individual samples are listed in Appendix B. i In this section, results are discussed by pathway and analysis type. Operational results are related to j controls, preoperational data, sources of radioactivity, and effluent releases when applicable. Trends ( or seasonal effects are discussed. Tables 3 through 16 illustrate results of interest for 1993. Associated errors for positive results may be obtained in Appendix B. l A. Airborne I 1 Results of the weekly gross beta analysis are summarized in Table 3. Figure 6 illustrates a plot of weekly gross beta results for 1993. Figure 8 illustrates a historical plot of the gross beta 1/C ratios and includes a smoothed average trend. Although the smoothed average has a very slight increasing trend, the gross beta values for the time period are consistent with expected background and suggest that the slightly increasing 1/C ratios are a result of changing ! environmental conditions. For instance, Figure 7 illustrates a slightly decreasing trend for location 40
, (airbome sample control location) since 1989. Decreasing control values would tend to increase the I/C ratio over time. In addition, no radiciodine has been detected since 1989. Therefore, the slight increase in gross beta l/C ratios is due to a slight decrease in control location gross beta values over time and is not due to plant operations. It is also interesting to note that the smoothed plot (Figure 7) shows a definite seasonal cyclic trend in which gross beta values peak in the winter months (December or January) and decrease to a low point in the spring months (May or June).
Figure 9 illustrates a historical plot of average weekly indicator and control gross beta values during plant operations. l Table 4 summarizes the gamma analyses of 1993 airborne particulate filter quarterly composites. The table shows that only natural radioisotopes Be-7 and K-40 were detected. No effects of plant operation were seen via air samples during 1993. B. Direct Radiation 1993 quarterly gamma exposures for each location are summarized in Tables 5 and 6. Values are normalized to a standard 90 day quarter. Figure 10 shows the nearsite TLD data expressed as a percentage of the control data. Results from TLDs located near the plant site (<3 miles distant) have been combined into quarterly averages. Note that nearsite TLD locations have historically trended higher than the control locations both prior to and after WCGS became operational. Figure 11 showa the historical quarterly average values expressed in mrem /std 90 day quarter for both nearsite and control locations Figure 11 also shows that the levels of direct radiation measured by thermoluminescent dosimeters near Wolf Creek have declined from 1980 to 1993. This decrease in measured radiation levels is suspected to be caused by a decline in TLD efficiency. Linaar regression analyses of the direct radiation levels expressed as averages for a standard 90-day quarter indicate that measured radiation levels have declined significantly at indicator locations (p is less than or equal to 0.05 and r-squared is 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 5 of 50
8 equal to 0.49) and at control locations (p is less than or equal to 0.05 and r-squared is equal to 0.45). This decrease in measured direct radiation levels is not believed to be caused by a decrease in environmental direct radiation levels because Kansas Department of Health and Environment direct radiation results for locations near Wolf Creek do not show a similar decrease in measured direct radiation levels (internal KDHE data). Despite the decline in direct radiation levels measured by Wolf Creek's TLDs, a comparison of indicator and control location results still indicates that the direct radiation levels are not related to plant operation As also shown in Figure 11, the ratio of the near-site indicator location results to the control location results has remained near 100 percent through 1993. The near-site indicator location results and the control location results exhibited significant correlation (p is less than or equal to 0.05 and R is equal to 0.93) and this indicates that fluctuations in direct radiation levels were measured with a high degree of certainty by both the indicator and controllocation TLDs. However, if measured direct radiation levels continue to decline, the TLD results will tall below the range of pre-operational averages for Wolf Creek and the range of direct radiation levels measured by the NRC (note 1) and KDHE (note 2). Panasonic UD-814-AQ TLDs were placed in the same locations as the Teledyne isotopes TLDs during the third and fourth quarters of 1993 as a cross-comparison measure and the Teledyne TLDs will be replaced with the Panasonic TLDs during 1994. Please note that the supplemental Panasonic TLD data were used for the third quarter of 1993 on Figure 11 because the third quarter Teledyne TLDs could not be accurately analyzed. Please refer to the program deviations section for more information about the third quarter TLDs. Notes:
- 1. United States Nuclear Regulatory Commission,1994. NRC TLD Direct Radiation Monitoring Network Progress Report, October-December 1993 (NUREG-0837, volume 13, number 4), pg.
309.
- 2. Kansas Department of Health and Environment,1992. Report of Results of the Radiological Environmental Monitoring Program Around the Wolf Creek Generating Station Between July 1, 1991 and June 30,1992 (SFY 1992), pg. 36.
C. Waterborne (1) Drinking Water Results of drinking water gamma isotopic analyses are summarized in Table 7. No tritium was detected in drinking water samples during 1993. Figure 14 illustrates the historical drinking water gross beta data through 1993. The comr site samples for May 4 through June 1 and August 3 through August 31 exhibited elevated gross beta results, especially in the duplicate sample results for indicator location LW-40 on both June 1 and August 31. The indicator and control location both displayed elevated values for June 1, which suggests that the elevated values are not related to plant operations. Comparing the error range for the indicator location gross beta results on June 1 and August 31 shows that the i.iitial results are within the error range of the duplicate results. No other nuclides were identified during 1993. No activity due to plant operations were evident in drinking water samples during 1993. 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 6 of 50
4 ) (2) Surface Water Surface water data is summarized in Table 8. Tritium was the only nuclide identified in surface water samples during 1993. Figure 12 illustrates smoothed tritium data for WCCL from startup in May 1985 through 1993 for locations DC and SP and the cumulatise curies of tritium released to WCCL. Tritium values have been declining recently and the declining trend may be due to high precipitation during 1993. Significant discharge from WCCL occurred during 1993 as a result of precipitation. The increased precipitation allowed some dilution or replacement (with nontritiated water) of the tritiated water inventory in WCCL. The region had experienced a prolonged drought during the previous 2 to 3 years. Little discharge from WCCL occurred during the dry period. Note that the tritium levels are well below the 20,000 pCi/ liter reporting limit for drinking water sources and the 30,000 pCi/ liter limit for other water sources. Figure 13 illustrates the same smoothed tritium data for WCCL exwpt quarterly tritium effluent discharges are plotted. (3) Ground Water No gamma emitters or tritium were detected in ground water samples during 1993. A summary of results is included in Table 9. (4) Shoreline Sediment Naturally occurring nuclides Ra-226, Th-228, and K-40 were detected in shoreline sediment samples during 1993. Co-60 and Cs-137 were detected in samples obtained from the discharge cove (DC) and Cs-137 was also detected in a control location sample collected from JRR. The Co-60 activity is attributable to plant operations but the Cs-137 activity is likely the result of increased atmospheric fallout. The levels of Cs-137 activity detected in the discharge cove and control location samples exceed the range of Cs-137 fallout measured during pre-operational studies (0.0131 to 0.0478 pCi/L). No Cs-134 was detected in the shoreline sediment samples, as would be expected if the source of the Cs-137 activity was plant operations. Cs-134 has a half-life of 2.05 years and it would be expected to be detected in a sample collected close to a source of both Cs-134 and Cs-137. Neither Cs-137 or Cs-134 were detected in monthly surface water samples collected at the discharge cove or JRR during 1993. Analysis results are summarized in Table 11. D. Ingestion (1) Milk No indicator locations for milk were available for sampling during 1993 (see Program Deviation section for explanation). A control sample was routinely obtained for analysis. All milk samples analyzed contained K-40 at levels consistent with preoperational data. The yearly average K-40 concentration was 1340 pCi/ liter. Table 15 summarizes milk analysis results for 1993. No other gamma emitters were detected. (2) Food and Garden Crops Gamma analyses of broadleaf vegetation samples during 1993 revealed naturally occurring gamma emitters K-40 and Be-7 at concentration consistent with preoperatiorial levels. Another naturally-occurring isotope, Th-228, was detected in one broadleaf vegetation sample during 1993 at 0.0606 pCi/ gram. Broadleaf vegetation results are summarized in Table 13. 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 7 of 50
c h No additional gamma emitters were detected in broadleaf vegetation samples during the remainder of l the year. l Crop samples were obtained from lands normally irrigated by the Neosho River below the outfall of WCCL. However, due to adequate precipitation during 1993, no irrigation was needed. The samples were still obtained to continue Wolf Creek's relationship with local landowners and to continue to establish baseline values. Results of crop analyses are summarized in Table 14. No nuclides attributable to plant operations were detected. (3) Fish Analysis results are illustrated in Table 16. Naturally occurring K-40 was detected in all fish samples with an average concentration of 3.33 pCi/ gram (wet weight). Th-228 was also detected in all fish samples. No other radionuclides were detected in fish during the year. E. Special Samples (not required by the WCGS ODCM) (1) Game Animals and Birds Naturally occurring K-40 was detected in all game animal and bird samples in concentrations consistent with preoperational levels. No other radionuclides were detected and no effects of plant operations were detected in this pathway. j I (2) Bottom Sediment Table 12 shows gamma emitters detected during 1993 in bottom sediment samples. Sampling locations include the Ultimate Heat Sink (UHS), DC, and JRR. Natural nuclides detected include i K-40, Ra-226, and Th-228. Several other nuclides were detected in bottom sediment samples. A portion of the Cs-137 activity detected in WCCL bottom sediments is probably attributable to fallout and a portion is due to plant operation The Cs-137 levels are only slightly higher than those reported prior to WCGS criticality and therr. ce a major portion of the activity is due to fallout. However, the Mn-54 and Co-60 activity shown in ie table are attributed to plant operations and are regularly identified in plant effluents. Be-7 was detected in one of five supplemer.tal samples collected in the discharge cove during 1993 as an attempt to determine the variation of activity levels in the discharge cove. The activity levels detected at the supplemental sample locations were consistent with the levels detected at location DC. (3) Aquatic Vegetation Table 10 shows gamma emitters detected during 1993 in aquatic plant samples. Be-7, K-40 and Ra-226 were detected in all samples collected. Th-228 was detected in one sample. An alga sample accumulated the most detectable activity. Mn-54, Co-58, Co-60, Cs-134, and Cs-137 were all detected in at least the alga sample and some were detected in the other aquatic plant samples as well. 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 8 of 50
i s .h j IIL ANNUAL LAND USE CENSUS RESULTS AND PROGRAM REVISIONS Section 5.2 of the WCGS ODCM directs that "A Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater that 500 square feet producing broadleaf vegetation in each of 16 meteorological sectors within five miles of the WCGS Site." The results shall also be included in the Annual Radiological Environmental { Operating Report. Table 5-1 of the WCGS ODCM states that garden (broadleaf) sampling locations will be "from two indicator locations with highest calculated annual average D/Q". Methodology 1 The 1993 Land Use Survey was completed in October. Information was collected using a i combination of mailed survey forms, telephone contacts, and door-to-door contacts. 1
- l
} Surveys were mailed to the rural residences within five rniles of WCGS during the second week of l l August 1993. - The survey excludes the residents of New Strawn, Burlington, and a trailer park just l ] north of Burlington. These locations are excluded because of the large number of households and the l ! low probability that information gained from these residences would affect the locations used for
- REMP sampling. A total of 137 surveys were mailed to rural locations, and 115 responses (83.9 l percent) were received or obtained by Wolf Creek personnel. Response rates for the last six years range from 85 to 90 percent. !
- \
4 Results ; l 1 The total population for the responding residences was 373 persons for an average of 2.63 persons ) per household. This average and the 137 known occupied residences are used to estimate the total rural population within five miles of the site (excluding New Strawn, Burlington, and the trailer park). . i ' The rural population is estimated at 384 persons. The population estimates were 466 in 1991 and 500 in 1992. The drop in rural population for 1993 is attributed to the change in survey methodology ;
- described above but not to an actual reduction in population. Results are summarized in Tables 17 i l and 18.
No milk animals that produced milk for human consumption were identifiec' within 5 miles of WCGS 7 again in 1993. i i Summay 1 On the basis of the data collected in the 1993 Land Use Census, no changes are required in the '
- REMP. )
i 1 a i i 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 9 of 50 l
< A IV. PRODRAM DEVIATIONS Airborne Location 37,8/3/93 to 8/10/93: No airborne particulate or radiciodine samples were collected from location 37 during this week because the air sample pump switch did not completely engage when the pump was turned on after changing sample filters on 8-3-03. The switch apparently turned the pump off as the pump fuse was not blown. The switch was checked and the pump functioned properly after it was restored to service.
Location 32,8/10/93 to 8/17/93: No airbome particulates were collected during this week at location 32 because the particulate filter was not properly seated in the sample head. A small gap allowed air to be drawn around, rather than through, the filter. The sample head was examined for mechanical defects and none were found. The particulate filter was replaced and the pump returned to service. Air particulate gross beta results from the other four WCNOC sampling locations for this week are consistent with historical air particulate gross beta levels, as are the air particulate gross beta results for location 32 from the week of 8/17/93 to 8/24/93. These results indicate that the sampling equipment functioned properly when retumed to service. Drinking Water Location LW-40, 4-25-93 to 4-26-93: Approximately 210 milliliters of the 7,200 milliliter monthly composite sample were not collected on these days because the sample collector blew its fuse after routine maintenance was performed on 4-25-93. The tubing used to replace the tubing in the pump roller housing was too stiff for the pump motor to turn the roller easily. The resistance of the stiffer tubing caused the motor to blow the fuse. The sampler with the improper tubing was replaced with a back-up sampler and composite sampling mMinued. The water sampler maintenance procedure was revised to specify and require that only the sampler manufacturer's replacement tubing be used. The loss of the 210 millimeters of drinking water did not significantly affect the drinking water analysis results for April 1993 and the composite sampler functioned properly during May and June of 1993. Location BW-15, October 1993: The drinking water sample for October was not collected at Burlington because the tube from the sample pump to the collection container was not connected properly after the September sample was collected. An extra tubing connection was removed on 11-2-93 to prevent future mistakes of this type. The November sample was properly collected. Location LW-40, October 1993: The tube from the sample pump to the collection container was not connected properly after the September sample was collected and the sample was pumped into the sample container housn,g, instead of the sample container. One gallon of drinking water was collected from the container housing and the analysis results were consistent with results from previous months. An extra tubing connection was removed on 11-2-93 to prevent future mistakes of this type. The November sample was properly collected. Location BW-15, December 1993: The composite sampler was damaged during December and collected only half its normal monthly volume. The sampler case had been cracked and the electronic components interrupted the composite sampling program. Damage to the sampler was detected on 1-4-94 and the broken sampler replaced on 1-5-94. The replacement sampler functioned properly. 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 10 of 50
o } Direct Radiation Samplers (TLDs) All Locations, Second Quarter 1993: TLDs were collected from all sampling locations as required. l Even though the shipping container was clearly marked "DO NOT X-RAY", the shipping container was inadvertently x-rayed before leaving WCGS. The TLDs were shipped to Teledyne Isotopes and analyzed as per normal protocol. Four freshly annealed TLDs were included in the shipping package as per procedure to record transit exposure. The TLD results showed no adverse consequences due to the x-ray exposure and no abnormal readings resulted. The TLDs included to record transit exposure yielded exposures similar to what is normally experienced during shipment. l Location 9, Second Quarter 1993: The TLD housing cover was missing and thus the TLDs had been j exposed to the elements prior to collection. The cover was replaced after the TLDs were collected. j No abnormal readings resulted. ] Location 16, Second Quarter 1993: The tree to which the TLDs and protective housing were affixed ; was struck by lightning sometime during the second quarter. The TLD housing cover was missing and thus the TLDs had been exposed to the elements prior to collection. The cover was replaced , after the TLDs were collected. No abnormal readings resulted. J Location 29, Second Quarter 1993: The TLD housing cover was missing and thus the TLDs had been exposed to the elements prior to collection. The cover was replaced after the TLDs were collected. ) No abnormal readings resulted. All Locations, Third Quarter,1993: Abnormal and unusable results were produced when the third quarter TLDs were analyzed by Teledyne isotopes. Some locations has negative results while other results varied widely between locations and the transit dosimeters used to detect any dose absorbed during shipment indicated abnormally high exposures of 42.1 millirems to 56.3 millirems. Normal i transit TLD dose readings are three to five millirems. It appears as if the TLDs received significant dose from an unknown source during shipment but that could not be confirmed by Federal Express. In 1994, WCNOC will replace the Teledyne TLDs with Panasonic TLDs that can be analyzed on site, i which will reduce the potential of receiving abnormal transit dose. Location 5, Fourth Quarter 1993: The TLD housing cover was missing and thus the TLDs had been exposed to the elements prior to collection. The cover was replaced after the TLDs were collected. i No abnormal meings resulted. 1 Ingestion Milk There were no deviations in milk sampling. However, there are still no indicator sampling locations available within five miles of the plant. Refer to Section Ill, Annual Land Use Census Results and Program Revisions. l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 11 of 50
{
. s Broadleaf Vegetation l Broadleaf Vegetation is sampled when seasonably available. No broadleaf vegetation deviations l
occurred during 1993. Listed below are those sample locations and dates when the samples were not i collected due to seasonal unavailability. No corrective actions were necessary. Samples were collected at the secondary location G-1 when available. Sample locations A-1 and R-1 are the primary sample locations and S-4 is the controllocation. All locations (4/93) Samples unavailable Gardens not yet established A-1, G-1 (5/93) Sample not yet available. Garden at A-1 and G-1 not yet established All other gardens sampled A-1, G-1 (6/93) Sample not yet available. Garden at A-1 and G-1 not yet established All other gardens sampled G-1 (7/93) Sample not yet available. Garden at G-1 not yet established All other gardens sampled l l R-1, G-1 (8/93) Growing season complete for vegetation species selected by landowners. All other gardens sampled l R-1, G-1 (9/93) Growing season complete for vegetation 1 species selected by landowners. l l All other gardens sampled l R-1, G-1, S-4 (10/93) Growing season complete for vegetation species selected by landowners. A-1 sampled. l l l 1993 Annual Radiological Environmental Operating Report l Wolf Creek Generating Station Page 12 of 50 i i
c :b V. EPA INTERLABORATORY COMPARISON RESULTS Teledyne isotopes is contracted to perform radiological analysis of environmental samples for WCNOC.. Teledyne participated in the EPA Interlaboratory Comparison Program during 1993. i Table 19 shows intertaboratory comparison test results received during the year. The table lists the sample date, the sample media, the nuclide or analysis type, the known value reportod by the EPA, the measured value reported by Teledyne Isotopes (based upon triplicate analysis), and the normalized deviation from the known. Results are listed in the table for sample media and analysis types corresponding to those performed for WCNOC. Except for one measurement, all of the Teledyne isotopes results were within three standard deviations of the known EPA results. Only results exceeding three standard deviations require corrective action. In the case of the one exception, an investigation was performed as described in footnote (e) of Table 19. Three results were betweer, two and three standard deviations. Those three required investigation. The footnotes of Table 19 describe the results of the investigations. l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 13 of 50
4 M TABLE 1
- 1 1993 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- SAMPLE COLLECTION I EXPOSURE NUMBER OF SAMPLING AND TYPE AND PATHWAY / SAMPLES AND COLLECTION FREQUENCY FREQUENCY OF SAMPLE SAMPLE LOCATIONS ANALYSIS AIRBORNE Radiciodine Samples from five Continuous sampler operation Analyze radioiodine and locations with sample collection weekly, canister weekly for Particulates or more frequently if required 1-131 by dust loading.
Samples from locations Analyze particulate near the site boundary filter weekly for in three sectors having gross beta activity; 4 the highest calculated perform quarterly annual average D/O gamma isotopic (Locations 2,3, and 37 analysis composite on Figure 1) (by location) Sample from the vicinity of a community having the highest calculated
; annual average D/O (Location 32 on Figure 1, New Strawn) 9 Sample from a control
- location 10 - 20 miles distant in a low D/O 4 sector (Location 40 on Figure 5) t DIRECT RADIATION j 40 routine monitoring Quarterly Gamma dose j stations with two or quarterly more dosimeters measuring dose continuously placed as follows:
a 4 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 14 of 50
( e A. l l TABLE 1 (Cont'd) ! EXPOSURE NUMBER OF SAMPLING AND TYPE AND -, PATHWAY / SAMPLES AND COLLECTION FREQUENCY FREQUENCY OF SAMPLE SAMPLE LOCATIONS ANALYSIS DIRECT RADIATION (cont'd) l An inner ring of stations, one in each meteorological sector ! 0-3 mile range from the j site (Locations 1-14,18, ! 26-31, 37, and 38 on Figure 2) An outer ring of stations, one in each meteorological sector in l the 3-5 mile range from
- the site (Locations 15-
! 17,19-22, 24, 25, and 32-36 on Figure 2) The balance of the stations to be placed in specialinterest areas such as population centers (Locations 23 and 32), nearby residences (Many locations are near a local residence), schools (Location 23), and in one or two areas to serve as control stations 10-20 miles distant from the site (Locations 39 and 40 on Figures 2 and 5) Locations 41,42, and 43 are not required sampling stations but have been added as specialinterest sampling locations 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 15 of 50 i
)
4 4 l I TABLE 1 pont'd) l EXPOSURE NUMBER OF SAMPLING AND TYPE AND I PATHWAYI 3AMPLES AND COLLECTION FREQUENCY FREQUENCY OF SAMPLE SAMPLE LOCATIONS ANALYSIS WATERBORNE Surface One sample upstream Monthly grab sample Monthly gamma , (Location MUSH on isotopic analysis
- j. Figure 3) and two and composite for samples downstream tritium analysis (Locations DC and SP quarterly on Figure 3)
Ground Samples from one or Quarterly Quarterly gamma two sources only if isotopic and tritium : likely to be affected analysis Indicator samples at locations hydrologically downgradient of the site ; (Locations C-10, C-49, l and D-65 on Figure 3); I Control sample at a location hydrologically upgradient of the site l (Location B-12 on ! Figure 3) l Drinking Sample of municipal Monthly Composite Monthly gamma , j water supply at an isotopic analysis l indicator location and gross beta ! downstream of the site analysis of (Location LW-40 on composite sample. Figure 5); Control Quarterly tritium i sample from location analysis of upstream of the site composites. (Location BW-15 on Figure 3) Shoreline One sample from the Semiannually Semiannual gamma sediment vicinity of Wolf Creek isotopic analysis l Cooling Lake discharge cove and one sample from John Redmond Reservoir (Locations DC and JRR respectively on Figure 3). 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 16 of 50 l
a b TABLE 1 (Cont'd) EXPOSURE NUMBER OF SAMPLING AND TYPE AND PATHWAY / SAMPLES AND COLLECTION FREQUENCY FREQUENCY OF SAMPLE SAMPLE LOCATIONS ANALYSIS WATERBORNE (cont'd) Bottom One sample from the Semiannually Semiannual gamma sediment vicinity of Wolf Creek isotopic analysis Cooling Lake discharge cove and one sample from John Redmond l Reservoir (Locations DC and JRR respectively on Figure 3). Special samples were obtained from the vicinity of the Ultimate Heat Sink. Rooted One sample from the Semiannually Semiannual gamma Aquatics or vicinity of Wolf Creek isotopic analysis Algae Cooling Lake (Location DC on Figure 3). INGESTION , Milk Samples from milking Semimonthly while animals Gamma isotopic animals at three are on pasture (April to analysis and 1-131 I indicator locations November) and monthly analysis of each within five miles of the during the remainder of the sample j l site having the highest year (December to March) i i dose potential (currently there are no indicator locations producing milk l for human consumption , within five miles of the I site); one sample from a controllocation greater than 10 miles from the site (Location ! ! S-3 on Figure 5) l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 17 of 50
s 6- I l i TABLE 1 (Cont'd) EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND PATHWAY / AND SAMPLE COLLECTION FREQUENCY FREQUENCY OF SAMPLE LOCATIONS ANALYSIS T INGESTION (cont'd) Fish Indicator samples of 1-3 Semiannually . Gamma isotopic recreationally important analysis on edible species from Wolf Creek portions Cooling Lake; control samples of similar species from John Redmond Reservoir * (several sampling areas indicated on Figure 4) Broadleaf Samples of available Monthly when available Gamma isotopic analysis on edible l Vegetation broadleaf vegetation from two indicator locations portions with highest calculated annual average D/O (Locations A-1 and R-1 and alternate location G-1 on Figure 4); sample of similar broadleaf vegetation from a control l location greater than 10 l miles from the site in a low D/O sector (Location S-4 on Figure 5) Irrigated Crops Sample of crops irrigated At time of harvest Gamma isotopic with water from the analysis on edible Neosho River portions downstream of the Neosho River-Wolf Creek confluence (Location NR-D1 and NR-l D2 on Figure 5); control ! sample irrigated with water from the Neosho River upstream of the Neosho River-Wolf Creek confluence (Location NR-U1 on Figure 5)
- 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 18 of 50 l
m h ? ) TABLE 1 (Cont'd) i EXPOSURE NUMBER OF SAMPLING AND TYPE AND PATHWAY / SAMPLES AND COLLECTION FREQUENCY FREQUENCY OF j SAMPLE SAMPLE LOCATIONS ANALYSIS l INGESTION (cont'd)
- Game birds Indicator samples of Annually Gamma isotopic and animals region specific analysis on edible i recreationally important portions species from the vicinity of Wolf Creek Cooling Lake; controlsamples of similar species from locations about 15 miles northwest of WCGS.
) 1 i 4 i i s i i i l 3 l i 1 a 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 19 of 50 t
s . TABLE 2 SAMPLE LOCATION NUMBERS, DISTANCES (Miles), AND DIRECTIONS 1 Location Distance / Location Distance / Location Distance / Number Direction Number Direction Number Direction TLD and Air Particulates and Radiolodines 1 1.4/N 15 4.5/ESE 29 2.6/SSW 2 2.7/N 16 4.2/E 30 2.2/SW , 3 3.0/NNE 17 3.6/SE 31 3.0/WNW 4 4.0/NNE 18 3.2/SSE 32 3.2/WNW 5 4.0/NE 19 4.0/SSE 33 3.7/WNW 6 4.4/ENE 20 3.3/S 34 4.0/N W 7 1.9/NE 21 3.8/S 35 4.6/NNW 8 1.6/flNE 22 5.1/SSW 36 4.2/N 9 2.0/ENE 23 4.5/S W 37 2.1/NNW 10 2.4/ENE 24 4.1/WSW 38 1.2/NW 11 1.5/E 25 3.6/W 39 13.0/N 12 1.8/ESE 26 2.6/WSW 40 >15.0/WNW 13 1.5/SE 27 2.1/S W 41 0.8/NNW 14 2.8/SE 28 2.8/SW 42 0.8/SSE 43 0.8/WNW Ground water Drinking water Surface water B-12 2.2/NNE BW-15 3.9/S W MUSH 3.6/W C-10 2.8/W LW40 10.0/SSE DC 0.6/WNW C-49 2.9/S W SP 2.9/S D-65 3.9/S Milk Broadleaf vegetation irrigated Crops S-3 >15.0/WNW A-1 1.4/N NR-U1 4.2/S W _i R-1 2.1/NNW NR-D1 >10.0/S G-1 1.6/SE NR-D2 >10.0/S l S-4 >15.0/WNW I Fish Shoreline and Bottom Aquatic Vegetation / Sediments Algae WCCL 0.6/WNW DC 0.6/WNW DC 0.6/WNW JRR 4/W JRR 4/W l UHS 0.6/E Game Birds and Animals WCCL General Vicinity l l Beto Junction >15.0/NNW l l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 20 of 50
_ . ._ _= . __ ._ _ . _ _ _ _ _ _. _ __ _ __ l
. +
TABLE 3 1993 Airborne Particulate Gross Beta Analyses (pCl / cubic meter, analysis error reported in Appendix B) DATE Location WEEK Beginning Ending 2 3 32 37 40 j 1 12/29/92 1/5/93 0 034 0.034 0.031 0.034 0.031 2 1/5/93 1/12/93 0.033 0.033 0.036 0.040 0.037 3 1/12/93 1/19/93 0.046 0.046 0.059 0.048 0 056 4 1/19/93 1/26/93 0.023 0.023 0.035 0.023 0.025 5 1/26/93 2/2/93 0.029 0.029 0.030 0.026 0.028 6 2/2/93 2/9/93 0.029 0.029 0.035 0.024 0.031 7 2/9/93 2/16/93 0.027 0.027 0017 0.027 0.032 1 8 2/16/93 2/23/93 0 031 0.031 0.032 0.031 0.029 9 2/23/93 3/2/93 0.035 0.035 0.028 0.025 0.031 l 10 3/2/93 3/9/93 0.025 0.025 0.023 0.022 0.027 11 3/9/93 3/16/93 0.016 0.016 0.012 0.013 0.014 12 3/16/93 3/23/93 0.023 0.023 0.018 0.024 0.022 13 3/23/93 3/30/93 0.017 0.017 0.012 0.017 0.015 14 3/30/93 4/6/93 0.015 0.015 0.015 0.014 0.019 l 15 4/6/93 4/13/93 0.017 0.017 0.018 0.014 0.017 ! 16 4/13/93 4/20/93 0.016 0.016 0.017 0.015 0.016 17 4/20/93 4/27/93 0.027 0.027 0.028 0.030 0.029 18 4/27/93 5/4/93 0.019 0.019 0.014 0.014 0.018 19 5/4/93 5/11/93 0.021 0.021 0.014 0.015 0014 20 5/11/93 5/18/93 0.015 0.015 0.015 0.017 0.013 21 5/18/93 5/25/93 0.016 0.016 0.015 0.018 0.016 22 5/25/93 6/1/93 0 019 0 019 0.016 R016 0.018 23 6/1/93 6/8/93 0.019 0.019 0.017 0.017 0.021 24 6/8/93 6/15/93 0 022 0.022 0.018 0 018 0.019 25 6/15/93 6/22/93 0.018 0.018 0 015 0.017 0.016 26 6/22/93 6/29/93 0.015 0.015 0.013 0.016 0.017 27 6/29/93 7/6/93 0.024 0.024 0.020 0 022 0.019 28 7/6/93 7/13/93 0.020 0.020 0.018 0.020 0.021 _ 29 7/13/93 7/20/93 0.017 0.017 0.019 0.020 0.018 30 7/20/93 7/27/93 0.022 0 022 0.019 0.019 0.024 31 7/27/93 8/3/93 0 022 0.022 0.023 0.022 0.027 32 8/3/93 8/10/93 0 024 0.024 0.021 0 024 0.000 l 0.032 33 8/10/93 8/17/93 0 027 0.027 0.028 0.000 34 8/17/93 8/24/93 0 023 0.023 0.021 0.024 0 024 35 8/24/93 8/31/93 0.028 0.028 0.029 0.026 0.028 36 8/31/93 9/7/93 0.020 0.020 0.021 0.024 0.022 37 9/7/93 9/14/93 0.020 0.020 0.017 0.019 0.032 38 0/14/93 9/21/93 0.024 0.024 0.021 0.023 0.025 39 9/21/93 9/28/93 0.020 0.020 0.018 0.019 0 020 40 9/28/93 10/5/93 0.025 0 025 0.027 0.025 0.025 41 10/5/93 10/12/93 0.026 0.026 0.027 0.028 00?I 42 10/12/93 10/19/93 0.019 0.019 0.025 0 027 0.029 43 10/19/93 10/26/93 0 022 0.022 0.023 0.029 0 025 l 44 10/26/93 11/2/93 0.019 0.019 0.020 0 023 0.025 45 11/2/93 11/9/93 0 024 0.024 0.020 0.021 0.023 46 11/9/93 11/16/93 0.022 0.022 0.016 0 025 0.022 47 11/16/93 11/23/93 0.028 0.028 0.024 0.026 0.027 48 11/23/93 11/30/93 0.031 0.031 0 028 0 028 0.023 49 11/30/93 12/7/93 0.029 0.029 0.036 0.036 0 035 50 12/7/93 12/14/93 0.032 0 032 0.030 0.035 0 031 51 12/14/93 12/21/93 0 029 0.029 0.026 0.030 0 030 52 12/21/93 12/28/93 0.024 0 024 0.024 0 025 0.019 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 21 of 50
l e . TABLE 4 Airborne Particulate Quarterly Composite Gamma Isotopic Analyses (pCil cubic meter, analysis error reported in Appendix B) LOCATION YEAR QTR BE 7 B E-7 K-40 K-40 1-131 CS 134 CS 137 ERROR ERROR ) 2 1993 1 0.06 0.0073 < 0.01 < 0.002 < 0.0006 < 0.0006 l 2 1993 2 0.08 0.0075 < 0.01 < 0.003 < 0.0005 < 0.0004 i 2 1993 3 0.07 0.0077 < 0.01 < 0.002 < 0.0004 < 0.0005 2 1993 4 0.06 0.006 < 0.008 < 0.002 < 0.0003 < 0.0006 3 1993 1 0.04 0.0053 < 0.009 < 0.002 < 0.0005 < 0.0006 3 1993 2 0.06 0.0064 < 0.02 < 0.003 < 0.0006 < 0.0006 3 1993 3 0.06 0.0062 < 0.01 < 0.002 < 0.0005 < 0.0005 3 1993 4 0.06 0.0064 < 0.02 < 0.003 < 0.0006 < 0.0006 32 1993 1 0.05 0.0053 < 0.008 < 0.002 < 0.0005 < 0.0006 32 1993 2 0.08 0.0081 0.00601 0.00303 < 0.002 < 0.0004 < 0.0004 32 1993 3 0.08 0.0083 0.00794 0.00402 < 0.002 < 0.0005 < 0.0005 32 1993 4 0.07 0.0072 < 0.009 < 0.003 < 0.0005 < 0.0004 ! 37 1993 1 0.05 0.0063 < 0.02 < 0.002 < 0.0006 < 0.0006 37 1993 2 0.07 0.0074 0.00872 0.00408 < 0.003 < 0.0005 < 0.0005 37 1993 3 0.08 0.0079 < 0.007 < 0.002 < 0.0005 < 0.0005 37 1993 4 0.06 0.006 0.0104 0.0048 < 0.002 < 0.0005 < 0.0005 40 1993 1 0.05 0.0059 < 0.01 < 0.002 < 0.0005 < 0.0005 40 1993 2 0.08 0.0077 0.00663 0.00347 < 0.003 < 0.0005 < 0.0005 40 1993 3 0.06 0.0063 0.00597 0.00312 < 0.001 < 0.0004 < 0.0003 40 1993 4 0.06 0.006 < 0.007 < 0.002 < 0.0004 < 0.0004 l l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 22 of 50
s
- l I
TABLE 5 1993 First & Second Quarter TLD Results I (mr / 90 day qtr) First Quarter Second Quarter l DKYS 90 D AVG 90 D LOCATION DAYS 90 D AVG 90 D 1 LOCATION 2STV 2STV
~
91.0 13.9 1.9 1 92.3 15.0 1.8 1 2 91.0 13.5 0.7 2 92.3 14.8 2.7 91.0 13.4 1.2 3 92.2 14.2 1.4 3 I 4 91.0 13.2 0.8 4 92.2 15.6 2.3 5 91.0 12.9 - 1.0 5 92.2 14.1 2.0 l 6 91.0 13.4 2.2 6 92.1 13.8 1.3 f 0.8 7 92.2 14.0 1.5 ! 7 91.0 12.3 8 90.9 13.3 1.9 8 92.3 14.9 1.4 9 91.0 13.0 1.6 9 92.2 11.4 5.7 , 10 91.0 13.5 1.0 10 92.1 15.7 6.4 l 11 91.0 13.7 1.0 11 92.2 15.5 1.9 l 12 91.0 13.4 1.7 12 92.2 14.8 1.3 l 13 91.0 13.9 2.2 13 92.2 14.8 1.4 l 14 91.0 13.2 3.4 14 92.2 15.0 1.6 15 91.0 13.6 1.2 15 92.1 14.3 1.4 ! 16 91.0 13.0 0.8 16 92.1 14.3 2.3 17 91.0 13.2 1.7 17 92.1 14.2 1.8 18 91.0 15.0 1.6 18 92.1 14.6 1.5 _ 19 91.0 14.0 1.2 19 92.1 15.5 2.1 20 91.0 13.3 1.6 20 92.0 15.0 1.4 21 91.0 12.4 0.7 21 92.0 12.1 1.8 l 22 91.0 13.0 1.3 22 92.1 13.5 1.7 23 91.0 14.0 0.5 23 92.0 14.9 1.6 l 1.5 1 24 91.0 14.0 1.2 24 92.0 14.2 25 91.0 10.5 1.0 25 92.0 11.8 0.8 26 91.0 12.5 1.2 26 92.0 13.7 1.3 1 27 91.0 15.3 1.8 27- 92.0 14.7 1.3 28 91.0 12.1 1.2 28 92.0 12.6 1.8 29 91.0 11.1 0.6 29 92.0 11.8 1.7 1 j
- 30 91.0 13.1 0.9 30 92.0 13.6 1.5 1 31 91.0 13.2 1.5 31 92.0 14.1 1.2 l 32 91.0 12.8 1.7 32 92.0 13.3 1.1 33 91.0 15.0 2.0 33 92.0 14.7 1.3 l 34 91.0 14.7 1.2 34 92.0 14.8 1.8 35 90.9 14.2 1.3 35 92.2 15.1 2.0 36 90.9 12.5 2.0 36 92.2 14.3 0.8 37 91.0 12.4 1.1 37 92.0 14.4 2.3 38 91.0 14.2 1.1 38 92.0 15.4 2.9 39 91.0 13.6 0.9 39 92.1 13.9 1.5 40 90.7 12.8 2.2 40 92.4 12.8 3.1 41 91.0 11.8 1.1 41 92.3 12.1 1.0 42 91.0 9.4 0.7 42 92.3 8.8 1.8 43 91.0 10.4 2.5 43 92.1 9.8 1.2 l
l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 23 of 50
_. - - .. - =_ _ - _ _ _ _ _ .. s a o TABLE 6 1993 Third & Fourth Quarter TLD Results (mr / 90 day qtr) Fourth Quarter (Teledyne TLD data) Third Quarter (Panasonic TLD data) LOCATION DAYS 90 D AVG 90 D LOCATION DAYS 90 D AVG 90 0 2STV 2STV 1 97.9 17.5 1.0 1 83.0 15.6 2.3 2 97.8 15.6 1.9 2 83.1 14.7 1.7 3 97.9 14.9 0.8 3 83.1 14.8 1.5 4 97.9 16.0 0.6 4 83.1 15.4 3.3 - 5 97.9 14.9 1.0 5 83.0 13.9 1.1 6 97.9 13.7 1.1 6 83.1 14.7 1.5 7 97.9 14.6 1.1 7 83.1 13.8 0.9 8 97.9 16.1 1.6 8 83.0 16.2 1.0 9 97.9 13.9 1.1 3 83.1 14.2 1.1 10 98.0 15.8 1.4 10 83.1 15.7 1.9 11 97.9 17.5 2.9 .11 83.1 15.6 1.5 12 97.9 16.0 1.7 12 83.1 14.1 1.5 13 97.9 17.0 0.6 13 83.1 15.6 1.2 14 97.9 18.1 14 83.1 16.1 1.6 1.9 ~ 15 97.9 16.8 1.7 15 83.1 16.7 1.7 16 97.9 15.9 0.7 16 83.1 16.4 1.5 17 97.9 18.0 2.2 17 83.1 14.9 1.6 18 97.9 16.9 2.7 18 83.1 16.6 1.7 19 97.9 18.9 1.3 19 83.1 16.8 1.0 20 98.0 16.1 1.8 20 83.1 19.4 3.7 21 98.0 15.3 5.9 21 83.1 15.7 1.7 22 97.9 15.1 1.3 22 83.0 -16.0 1.6 23 98.0 14.8 2.1 23 83.1 16.5 1.7 24 98.0 15.0 0.8 24 83.1 16.4 1.1 25 98.0 12.1 0.8 _ 25 83.1 13.3 2.3 26 98.0 13.9 1.0 26 83.1 14.1- 0.7 27 98.0 15.2- 0.9 27 83.0 15.7 1.0 , l 28 98.0 13.7 0.3 28 83.0 16.7 1.2 29 98.0 13.2 1.1 29 83.0 14.1 1.0 30 98.0 15.3 1.5 30 83.1 15.5 1.5 31 98.0 15.8 0.5 31 83.1 16.4 1.3 32 98.0 15.5 1.9 32 83.0 15.5 0.7 33 98.0 17.2 0.3 33 83.1 16.4 2.1 34 98.0 17.4 1.0 34 83.0 16.5 1.2 35 97.9 19.4 2.3 35 83.1 15.4 0.9 36 97.9 18.7 1.7 36 83.1 15.3 1.9 37 98.0 17.3 2.2 37- 83.0 15.7 0.9 ! 38 98.0 18.8 2.1 38 83.0 16.9 1.6 i 39 98.0 16.8 0.8 39 83.1 14.8 2.6 i 40 98.0 16.2 2.4 40 83.0 14.3 1.0 41 97.9 15.5 1.4 41 83.0 15.3 1.2 42 97.9 12.5 1.6 42 83.0 11.8 0.6 43 97.9 11.2 2.2 43 83.0 10.3 0.5 I l
.1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station - Page 24 of 50
- 1 . +
a TABLE 7 1993 Drinking Water Radiological Analyses (pCilliter, analysis error reported in Appendix B) I l } SAMPLE LOCATION GR-B GR-B MN 54 FE-59 CO-68 CO-60 ZN-65 ZR- I131 CS 134 CS 137 I f COLLECTION ERROR NB-95 I START DATE l I 2/2/93 BW15 5 +/- 1.8 <3 <6 <3 <3 <7 <3 <1 <3 <3 l 2/2/93 BW15 5.1 +/- 1.8 <2 <5 <2 <2 <5 <2 <1 <3 <3 3/2/93 BW15 6.8 +/- 1.3 <2 <6 <3 <3 <6 <3 < 0.2 <3 <4 . 4/6/93 BW15 7.9 +/- 1.4 <3 <7 <3 <4 <6 <3 < 0.5 <4 <4 ! 5/4/93 BW15 5.9 +/- 1.1 <3 <6 <3 <4 <7 <4 < 0.2 <4 <4 6/1/93 BW15 9.4 +/- 1.7 <3 <7 <3 <3 <7 <3 < 0.2 <3 <4 d 7/6/93 BW15 68 +/- 1.2 <3 <6 <3 <3 <7 <4 < 0.5 <4 <4 8/3/93 BW15 6.2 +/- 1.3 <4 <7 <4 <4 <9 <4 <0.4 <4 <4 8/31/93 BW15 7.1 +/- 3.5 <3 <6 <3 <3 <6 <3 < 0.9 <3 <3 11/30/93 BW15 6.4 +/- 1.4 <3 <6 <3 <3 <7 <3 < 0.2 <3 <3 l 11/30/93 BW15 7.9 +/ 1.5 <3 <6' <3 <4 <6 <3 < 0.1 <3 <3 f 2/2/93 LW40 6.7 +/- 1.4 <3 <7 <3 <4 <8 <3 < 0.6 <4 <4 3/2/93 LW40 6.2 +/- 1.4 <3 <6 <3 <3 <6 <3 < 0.1 <3 <4 4/6/93 LW40 8.5 +/- 1.5 <4 <9 <4 <4 < 10 <5 < 0.5 <5 <5 5/4/93 LW40 6.4 +/- 1.3 <4 <8 <4 <4 <8 <4 < 0.2 <4 <4 6/1/93 LW40 6.7 +/- 2.2 <3 <6 <3 <3 <6 <3 <0.5 <3 <4 ' I 6/1/93 LW40 12 +/- 3 <3 <7 <3 <3 <7 <3 < 0.6 ' <3 <3 .l 7/6/93 LW40 6 +/- 1.3 <4 <9 <4 <4 <9 <4 < 0.4 <5 <5 j 8/3/93 LW40 5.3 +/- 1.4 <4 <7 <3 <4 <8 <4 < 0.4 <4 <4 8/31/93 LW40 13 +/- 4 <3 <6 <3 <4 <7 <3 <0.8 <3 <4 10/5/93 LW40 2.3 +/- 1.3 <4 <8 <4 <4 <8 <4 < 0.2 <4 <4 11/30/93 LW40 7.4 +/- 1.5 <3 <7 <3 <3 <8 <4 < 0.2 <3 <4 11/30/93 LW40 6.7 +/- 1.5 <4 <9 <4 <5 <8 <4 < 0.2 <5 <5 i
)
4 ) 4 i N t T l 9 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 25 of 50
- - . . - . ._- . _ - . =-
e , TABLE 8 1993 Surface Water Radiological Analyses ; (pCl / liter, analysis error reported in Appendix B) , 1 LOCATION DATE H-3 MN-54 FE-59 CO-58 CO-60 ZN-65 ZR- l-131 CS- CS- BA-LA- COMMENTS l NB-95 134 137 140 DC 1/19/93 6300 <3 <7 <3 <4 <8 <4 <6 c4 <4 <5 . DC 2/23/93 6400 <3 <8 <3 <4 <7 <4 < 10 <4 <4 <9 DC 2/23/93 6600 <3 <8 <3 <4 <7 <4 < 10 <3 <4 <7 DUPLICATE DC J DC 3/16/93 7800 . < 4 < 10 <4 <5 < 10 <5 <8 <5 <5 <6 DC 4/20/93 8900 <3 <6 <3 <3 <6 <3 <5 <3 <3 <4 J
<4 <7 <4 <4 <6 l DC 5/18/93 7300 <3 <7 <3 <4 (7 DC 6/15/93 7300 <3 <7 <4 <4 <8 <4 <6 <4 <4 <5 DC 7/20/93 5900 <3 <7 <3 <4 <6 <4 <6 <3 <4 <5 DC 8/17/93 6500 <3 <7 <3 <3 <6 <3 <7 <3 <3 <5 DC 8/17/93 6800 <3 <6 <3 <3 <5 <3 <7 <3 <4 <7 DUPLICATE ,
DC 9/21/93 6700 <3 <8 (4 <4 <8 <4 <8 <4 <4 <7 , DC 10/19/93 6700 <3 <7 <3 <3 <7 <3 < 10 <3 <3 < 10 l DC 11/16/93 6800 <3 <8 <3 <3 <6 <4 < 20 <3 <3 <9 l DC 12/21/93 6600 <3 <6 <3 <3 <6 <3. <7 <3 <4 <6 MUSH 1/19/93 <600 <3 <7 <3 <4 <7 <4 <6 <3 <5 <5 ; MUSH 2/23/93 < 100 <3 <8 <3 <3 <7 <3 < 10 <3' <5 <7 MUSH 3/16/93 <600 <3 <6 <3 <4 <7 <3 <6 <3 <5 <5-MUSH 4/20/93 < 400 <4 <9 <4 <4 <8 <4 <7 <4 <4 <6 MUSH 5/18/93 < 600 <3 <6 <3 <3 <6 <3 <4 <3 <3 <4 MUSH 6/15/93 < 600 <4 <9 <4 <5 < 10 <5 < 10 45 <5 <7 MUSH 7/20/93 < 700 <3 <6 <3 <3 <7 <3 <6 <3 <4 <4 MUSH 8/17/93 <700 <3 <7 <3 <3 <7 <3 <8 <3 <4 <6 MUSH 9/21/93 < 500 <3 <7 <3 <4 <7 <3 <7 <4 <4 <6 MUSH 10/19/93 < 400 <3 <8 <4 <4 <7 <3 < 10 <4 <4 <9 MUSH 11/16/93 < 400 <3 <7 <3 <3 <6 <3 < 20 <3 <3 <9 MUSH 12/21/93 < 300 <3 <7 <3 <3 <7 <4 <8 <3 <4 <8 SP 1/19/93 6400 <3 <6 <3 <4 <7 <3 <6 <4 <5 <6 SP 2/23/93 7000 <4 <8 <4 <3 <7 <4 < 10 <3 <4 <8 SP 3/16/93 8400 <3 <6 <3 <3 <7 <3 <6 <3 <4 <5 SP 4/20/93 8900 <4 <8 <4 <4 <8 <4 <8 <4 <4 <7 l SP 5/18/93 7400 <3 <7 <4 c4 <8 <4 <6 <4 <4 <6 SP 6/15/93 7500 <4 < 10 <5 <5 < 10 <5 <8 <5 <5 <6 SP 7/29/93 6000 <3 <7 <3 <3 <6 <3 <7 <4 <4 <6 SP 8/17/93 5600 <3 <7 <3 <3 <7 <3 <8 <3 <4 <6 SP 9/21/93 6500 <3 <7 <3 <4 <6 <3 <7 <3 <3 <6 SP 10/19/93 7100 <4 < 10 <4 <4 <8 <4 < 20 <4 <4 < 10 SP 11/16/93 6300 <3 <8 <3 <3 <7 <4 < 10 <3 <3 <9 SP 12/21/93 6500 <2 <6 <3 <3 <5 <3 <6 <3 <4 c5 i i
)
1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 26 of 50 ; 1 I _ _ _ _ ~ _ _ . _ . . . _ - _ , , ..
l l TABLE 9 1993 Ground Water Radiological Analyses (pCl / liter, analysis error reported in Appendix B) LOC DATE H-3 MN. FE- CO CO- ZN- ZR- I- CS- CS. BA-54 59 -58 60 65 NB- 131 134 137 LA-95 140 l B12 23-Feb-93 < 100 < 3< 8< 3< 4 < 8< 4 < 0.3 < 4 < 4 < 8 B12 18-May-93 < 200 < 3< 5< 3< 3< 6< 3< 0.1 < 3< 3< 4 B12 17 Aug-93 < 200 < 3< 7< 3< 3< 6< 4 < 0.1 < 3< 5< 7 B12 16-Nov-93 < 400 < 3< 8< 4 < 4 < 7 < 4 < 0.2 < 4 < 4 < 10 t C10 23-Feb-93 < 100 < 5< 10 < 5< 5< 10 < 5< 0.3 < 5< 5 < 9 C10 18-May-93 < 200 < 3< 6< 3< 3< 6< 3< 0.3 < 3< 3< 4 l C10 17-Aug-93 < 200 < 5< 10 < 5< 5< 10 < 6< 0.2 < 6< 6< 9 ( 0.2 < 3< 3< C10 16-Nov-93 < 400 < 3< 8< 3< 4 < 6< 3< 8 C49 23-Feb-93 < 100 < 4 < 8< 4 < 4 < 8< 4 < 0.2 < 4 < 4 < 7 C49 18-May 93 < 200 < 3< 7< 3< 3< 7< 3< 0.1 < 3< 4 < 5 C49 17-Aug-93 < 200 < 3< 6< 3< 3< 5< 3< 0.1 < 3< 4 < 5 C49 16-Nov-93 < 400 < 3< 7< 3< 3< 7< 3< 0.2 < 3< 3< 7 D65 23-Feb-93 < 100 < 4 < 10 < 4 < 4 < 9< 4 < 0.3 < 4 < 4 < 8 D65 18-May-93 < 200 < 4 < 7< 4 < 4 < 7< 4 < 0.3 < 4 < 4 < 6 D65 17-Aug-93 < 200 < 3< 7< 4 < 4 < 7< 4 < 0.1 < 3< 4 < 6 D65 16-Nov-93 < 400 < 3< 8< 3< 4 < 8< 4 < 0.2 < 3< 4 < 10 P65 05-May-93 < 200 < 2< 5 < 3< 3< 6< 3< 0.2 < 3< 4 < 4 TABLE 10 1993 Aquatic Plants Radiological Analyses (pCl / liter, analysis error reported in Appendix B) l
+
LOC TYPE DATE BE-T M-40 MN44 C048 CO40 CS 134 CS-137 RA226 TH-228 CR-61 85 125 DC ALGAE 6/2M3 619E41 1 ;)E@ 6 78e'.42 918E41 6.68E41 7.39E42 106E41 3 44E41 181E 41 2 35E41 4 59E-2 DC ROOTED AQUATIC Gr29/93 8 81E 02 191E<io 6 47E42 2 61E42 163E41 DC AM POND WEED 9/29/93 3 01E42 2 60E@ 7 28E43 1.62E42 ALT l l l i l I l l 1993 Annual Radiological Environmental Operating Report l Wolf Creek Generating Station Page 27 of 50
TABLE 11 1993 Shoreline Sediment Radiological Analyses (pCl / kg dry, analysis error reported in Appendix B) LOCATION DATE BE-7 K-40 CO 58 CO-60 CS 134 CS 137 RA-226 TH-228 RA 228 20-Apr 93 <05 9.77 <0.05 0 0928 < 0.06 0.174 1.91 1.09 < LLD DC 20-Apr-93 < 0.4 10.80 <0.03 < 0.03 <0.05 < 0.04 2.32 1.71 < LLD JRR DC 28-Sep-93 <0.3 7.50 < 0.03 < 0.03 < 0.04 0.0731 0.738 0 69 < LLD 09-Nov-93 <0.3 8.77 <0.03 < 0.03 < 0.04 0.108 1.55 1.01 < LLD JRR JRR 09-Nov-93 < 0.4 8.70 < 0.04- <0.03 < 0.05 0.139 2.36 1.16 < LLD Those numbers reported as <LLD are not normally tracked in WCNOC shorehne sedirnent databases unless activity is detected. 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 28 of 50
TABLE 12 1993 Bottom Sediment Radiological Analyses LOC DATE BE-7 K-40 MN-54 CO-58 CO-60 CS-134 CS-137 RA-226 TH-228 DC1 5/25/93 < LLD 12.8 +/- 1.3 <LLD <LLD 1.370 +/- 0.14 0.185 +/- 0.726 +/- 3.040 +/- 0.7 1.230 +/- 0.12 0.05 0.073 DC2 5/25/93 < LLD 4.3 +/- 0.5 <LLD <LLD 0.474 +/- <LLD 0.408 +/- 1.770 +/- 0.611 +/- t 0.054 0.047 0.75 0.061 DC3 5/25/93 0 454 +/- 4.9 +/- 0.49 0.077 +/- 0.324 +/- 0.793 +/- 0.139 +/- 0.222 +/- 1.660 +/- 0.586 +/- 0.239 0.0028 0.039 0.079 0.03 0.036 0 45 0.059 DC4 5/25/93 < LLD 13.2 +/- 1.3 <LLD <LLD 1.430 +/- 0.14 0.361 +/- 0.942 + /- 2.150 +/- 1.430 +/- 0.056 ~ 0.094 0.07 0.014 DCS 5/25/93 < LLD 13.1 +/- 1.3 <LLD <LLD 2.340 +/-0.23 0.293 +/- 0.840 +/- 2.530 +/- 1.530 +/- 0.15 0.049 0.084 0.68 DC 6/29/93 < LLD 14.1 +/- 1.4 <LLD <LLD 1.180 +/- 0.12 0.271 +/- 0.893 +/- 3.290 +/- 1.330 +/- 0.13 0.057 0 089 0.83 UHS 7/2/93 < LLD 13.7 +/- 1.4 <LLD <LLD <LLD <LLD 0.368 +/- 2.490 +/- 0.6 1.310 +/- 0.13 0.048 JRR 7/2/93 < LLD 17.1 +/- 1.7 <LLD <LLD <LLD <LLD 0.225 +/- 2.420 +/- 1.390 +/- 0.14 0 038 0.54 DC 9/28/93 < LLD 12.0 +/- 1.2 0.057 + /- <LLD 1.080 +/- 0.11 0 322 +/- 0.647 +/- 2.120 +/- 1.240 +/- 0.12 0.0325 0.046 0.065 0.59 JRR 11/9/1993 < LLD 10.9 +/- 1.1 <LLD <LLD (LLD <LLD 0.216 +/- 1.590 +/- 1.100 +/- 0.11 0.03 0.54 Those numbers reported as <LLD are not normally tracked in WCNOC bottom sediment databases unless activity is detected.
- Duplicate Sample 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 29 of 50 0
I TABLE 13 j 1993 Broadleaf Vegetation Radiological Analyses ! (pCil kg dry, analysis error reported in Appendix B) l l DATE TYPE LOC BE 7 BE 7 K 40 K-40 RU-103 l *31 CS-134 CS-137 RA 226 TH-228 ERROR ERROR ,
- 27-May-93 LETTUCE S4 0.57 0.116 5.4 0.54 < 0.01 < 0.02 < 0.02 < 0.02 < 0.3 < 0.02 l 25-May-93 LETTUCE R1 0.931 0.115 5.46 0.55 < 0.01 < 0.02 < 0.01 <0.01 <0.2 < 0.02 22-Jun-93 CABBAGE S-4 0.367 0.066 3.45 0.34 -<0.009 < 0.01 <0.009 < 0.009 < 0.02 < 0.02 29-Jun-93 LETTUCE R-1 0.852 0 085 8.48 0.85 <0,008 < 0.01 <0.008 <0009 < 0.1 < 0.01 27-Jul-93 CABBAGE S-4 1.49 0.150 3.75 0.37 < 0.01 <0.02 < 0.009 < 0.009 < 0.2 < 0.01 27-Jul-93 CABBAGE P .1 0.110 34 0.34 < 0.01 < 0.02 < 0.01 < 0.01 <02 < 0.f 2 27-Jul-93 SWISS 1 0 689 0.099 4.24 0.42 < 0.01 <0.02 < 0.01 < 0.01 < 0.2 < 0.J2 CHARD 17-Aug-93 SWISS 4 0.242 0.058 6.28 0.63 <0.008 < 0.01 < 0.009 <0.01 < 0.2 <001 CHARD 17 Aug-93 SWISS A- 0.31 0.067 6.19 0.62 < 0.009 <0.01 < 0.01 < 0.009 <0.2 < 0.01 CHARD 24-Aug-93 CABBAGE S-4 0.33 0.088 3.96 0.4 < 0.01 <0.02 <001 < 0.01 < 0.2 < 0.02 21-Sep-93 SWISS A-1 0.527 0.840 3.89 0.39 <0.01 < 0.02 < 0.01 < 0.01 < 0.2 0.0606 CHARD 21 Sep-93 CABBAGE S-4 0.626 0.100 4.15 0.41 <0.02 <0.03 < 0.01 < 0.01 <0.2 < 0.02 26-Oct-93 SWISS A-1 0.557 0.072 2.67 0.27 < 0.009 < 0.02 < 0.009 < 0.009 <0.2 < 0.01 CHARD TABLE 14 1993 Irrigated Crops Radiological Analyses (pCl / kg dry, analysis error reported in Appendix B)
DATE TYPE LOC BE-7 BE-7 K-40 K-40 RU-103 1-131 CS-134 CS 137 RA-226 TH-228 ERROR ERROR 19-Oct-93 SOYBEANS NR-U1 <0.06 N/A 13.1 1.3 < 0.008 < 0.009 < 0.009 < 0.009 < 0.1 0.01 19-Oct-93 CORN NR-U1 <0.08 N/A 2.72 0.27 < 0.01 < 0.01 < 0.01 <0.01 < 0.2 0.02 19-Oct-93 SOYBEANS NR-D1 <0.09 N/A 14.7 1.5 < 0.01 < 0.02 < 0.01 < 0.01 < 0.2 < 0.02 19-Oct-93 CORN NR-D2 < 0.06 N/A 2.9 0.29 < 0.007 < 0.01 < 0.008 < 0.008 < 0.1 < 0.01 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 30 of 50
m o TABLE 15 1993 Milk Radiological Analyses (pCil kg dry, analysis error reported in Appendix B) TYPE DATE l-131 K-40 K-40 CS-134 CS-137 BA-LA- COMMENTS ERROR 140 COW 1/12/93 < 0.2 1350 +/- 140 <4 <4 <6 COW 1/12/93 < 0.2 1390 +/- 140 <4 <5 <6 DUPLICATE COW 2/10/93 < 0.4 1340 +/- 130 <4 <5 <7 COW 2/10/93 < 0.4 1510 +/- 150 <5 <5 <7 DUPLICATE COW 3/9/93 < 0.6 1390 +/- 140 <4 <5 <5 COW 4/13/93 < 0.02 1370 +/- 140 <4 <5 <5 COW 4/28/93 < 0.02 -1470 +/- 150 <3 <3 <4 COW 5/11/93 < 0.02 1360 +/- 140 <4 <4 <5 COW 5/25/93 < 0.1 1400 +/- 140 <4 <4 <6 COW 6/8/93 < 0.1 1410 +/- 140 <4 <4 <4 COW 7/13/93 <0.02 1270 +/- 130 <4 <4 <6 COW 7/27/93 <0.02 1390 +/- 140 <4 <4 <5 COW 8/10/93 < 0.3 1480 +/- 150 <4 <4 <7 COW 8/24/93 < 0.02 <100 <4 <4 <5 K 40 <100 COW 9/7/93 < 0.2 1360 +/- 140 <4 <4 <6 COW 9/21/93 < 0.3 1320 +/- 130 <4 <4 <6 COW' 10/12/93 < 0.3 1420 +/- 140 <4 <4 <7 COW 10/26/93 < 0.7 1540 +/- 150 <4 <4 <6 COW 11/9/93 < 0.2 1370 +/- 140 <5 <5 <6 COW 11/23/93 < 0.3 1390 +/- 140 <5 <5 <6 COW 12/7/93 <0.2 1410 +/- 140 <3 <4 <5 l l t l l 1993 Annual Radiological Environmental Operating Report. Wolf Creek Generating Station Page 31 of 50 l
j . . l l ! ! TABLE 16 I i 1993 Fish Radiological Analyses ! (pCil kg dry, analysis error reported in Appendix B) DATE SPECIES Location K-40 MN-64 FE-59 CO-58 CO-60 ZN-65 CS-134 CS 137 TH-228 I l 30-Apr-93 CHAM 7/, d WCCL 3.59 < 0.01 < 0.03 < 0.01 < 0.01 <0.03 < 0.02 < 0.02 0.02 CAT 4 30-Apr-93 WI ..< WCCL 3.71 < 0.01 < 0.03 < 0.02 <0.01 < 0.03 < 0.02 <0.02 0.03 J 30-Apr-93 CARP WCCL 3.07 <0.02 <0.03 < 0.02 < 0.01 < 0.03 < 0.02 <0.02 0.03 l 18-May-93 WHITE BASS JRR 3.57 < 0.03 < 0.06 <0.03 <0.03 < 0 05 <003 <0.03 0.06 18-May-93 COMMON CARP JRR 3.27 < 0.03 < 0 06 < 0.02 <0.03 < 0.05 < 0.03 < 0.02 0.04 09-Nov-93 CARP JRR 3.28 < 0.01 <0.03 < 0.01 < 0.01 <0.03 <0.01 < 0.01 0.02 j 05-Oct-93 SM BASS / WIPER WCCL 2.70 < 0.01 <0.03 < 0.01 < 0.01 <0.03 < 0.01 < 0.01 0.02 ! 05-Oct-93 CHANNEL WCCL 2.80 < 0.02 <0.05 < 0.02 < 0.02 < 0.04 <002 < 0.02 0.04 CATFISH 05-Oct-93 CARP WCCL 3.23 < 0.02 <0.04 < 0.02 < 0.02 <0.04 < 0.02 < 0.02 0.04 I l l l l l l l l l 1993 Annual Radiological Environmental Operating Report i Wolf Creek Generating Station
\
1 l Page 32 of 50 l
TABLE 17 1993 Land Use Census Residence Data 1992 1993 TOTAL NO.OF DISTANCE (MI) DISTANCE (MI) POPULATION RESPONSES / / CLOSEST ICLOSEST SECTOR FOR SECTOR HOUSEHOLDS RESIDENCE RESIDENCE A 13 6/6 1.4/A1.4 1.4/A1.4 B 16 6/6 3.1/B3.1 3.1/B3.1 C 23 9/9 2.0/C2.0 1.9/C1.9 D. 12 5/5 2.1/D2.1 2.1/D2.1 l E 10 4/4 1.8/E1.8 1.8/E1.8 F 43 15/15 1.8/F1.8 1.6/F1.6 G 23 9/9 1.6/G1.6 1.6,F1.6 H 13 4/4 3.1/H3.1 3.1/H3.1 i J 21 7/8 3.3/J3.3 3.3/J3.3 K 7 4/4 2.6/K2.6 2.6/K2.6 L 43 14/15 2.1/L2.1 2.1/L2.1 M 28 15/16 1.6/M1.6 1.6/M1.6 N 15 6/6 2.1/N2.1 2.1/N2.1 P 74 24/25 2.9/P2.9 2.8/P2.8 l 1 Q 25 10/10 1.4/Q1.4 1.4/Q1.4 R 7 4/4 1.9/R1.9 2.1/R2.1 NOTE: Entries shown in bold indicate changes from the 1992 land use census. I i 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 33 of 50
i l i I TABLE 18 1993 Land Use Census Milk and Garden Data i 1992 1993 1992 1993 DlQ DISTANCE DISTANCE DISTANCE DISTANCE (DEPOSITION (MI)/ MILK (MI)/ MILK (MI)/ CLOSEST (MI)/ CLOSEST CONSTANT)/ I SECTOR ANIMAL ANIMAL GARDEN GARDEN RANKING A none none 1.4/A-01 1.4/A1.4 4.70E-09/1 4, I B 4.9/B4.9 4.9/B4.9 3.1/B-02 4.2/B4.2 4.41 E-10/11 i C none none 2.0/C-01 2.6/C2.6 5.13E-10/10 -]
- D none none 2.1/D-01 2.1/D2.1 - 2.54E-10/15 E none none 1.8/E-01 1.8/E1.8 5.80E-10/7 l f
F none 4.9/F4.9 1.6/F-07 1.8/F1.8 LDjE-10/4 G none 3.6/G3.6 1.6/G-01 1.6/G1.6 1.82E-09/3 ) H none 4.9/H4.9 3.1/H-02 4.9/H4.9 7.66E-10/14 I i . j J none none- 3.3/J-01 4.0/J4.0 4.07E-10/12 l K none none 2.6/K-06 4.1/K4.1 3.61E-10/13 l L none none 2.6/L-39 2.6/L2.6 5.55E-10/9 I I i M 1.6/M1.6 none 1.6/N 19 2&M2d 5.60E-10/8 a 1 N none none 2.6/N-03 2.6/N2.6 5.86E-10/6 ]; P none none 2.8/P-26 4.3/P4.3 2.31E-10/16 Q none none 2.3/Q-03 19/Q3.9 6.24E-10/5
; R none none 2.1/R-01 2.1/R2.1 2.11E-99/2 )
j NOTE: underlined and bold entries indicate changes from the 1992 land use census, i i-I 1 4 1993 Annual Radiological Environmental Operating Report Wolf Craek Generating Station Page 34 of 50
O
- TABLE 19 1993 US EPA Interlaboratory Cornparison Program t
Collection Teledyne Date Media Nuclide EPA Result (a) Isotopes Result (b) Deviation (c) 01/29/93 Water Gr Beta 44.0 5.0 52.00 1.00 2.77 (d) 02/05/93 Water I131 100.0 10.0 106.67 - 5.77 1.15 04/20/93 Water Gr-Beta 177.0 27.0 150.0 0.00 -1.73
' Co-60 39.0 5.0 40.67 3.51 0.58 Cs 134 27.0 5.0 . 23.67 1.53 -1.15 Cs-137 32.0 5.0 34.33 2.08 0.81 06/04/93 Water H3 9844.0 984.0 9366.67 152.75 -0.84 06/11/93 Water Co-60 15.0 5.0 16.33 1.53 0.46 Zn-65 103.0 10.0 -121.33 20.09 3.18 (e)
Ru-106 119.0 12.0- 106.33 15.89 -1.83
^ '
Cs 134 5.0 5.0 5.67 'O.58 0.23 Cs-137 5.0 5.0 6.67 0.58 0.58
. _ _ Ba-133 99.0 10.0 104.33 9.29 0.92 07/23/93 Water Gr-Beta 43.0 6.9 42.67 2.52 -0.08 08/27/93 Air Filter Gr Beta 47.0 5.0 49.00 1.73 0.69 Cs-137 9.0 5.0 9.67. 0.58 0.23 09/24/93 Milk I-131 120.0 12.0 126.67 5.77 0.96 Cs 137 49.0 5.0 50.67 1.15 0.58 K 1679.0 84.0 1620.00 17.32 -1.22 10/08/93 Water I 131 117.0 12.0 103.33 5.77 -1.97 10/29/93 Water Gr-Beta 15.0 5.0 15.67 2.08 0.23 11/5/93 Water H-3 7398.0 740.0 6900.00 100.00 -1.17 11/12/93 Water Co-60 30.0 5.0 28.67 2.89 -0.46 Zn 65 150.0 15.0 152.00 9.17 0.23 Ru-106 201.0 20.0 177.33 5.51 -2.05 (O Cs-134 59.0 5.0 53.33 4.93 -1.96 -
Cs-137 40.0 5.0 41.33 3.06 0.46 Ba-133 79.0 8.0 69.33 3.06 -2.09 (0 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 35 of 50
o , i l l TABLE 19 (cont'd) ! 1993 US EPA Interlaboratory Comparison Program Collecuon Teledyne l Date Media Nuclide EPA Resultfa) Isotopes Result (b) l Foottmi n j (a) EPA Results Expected laboratory precision (1 sigma). Units are pCi/ liter for water and milk except K l 1s in mg/ liter. Units are total pCi for air particulate filters. 1 (b) Teledyne Results - Average one sigma. Units are pC1/ liter for water and milk except K is in mg/ liter. Units are total pC1 for air particulate filters. (c) Normalized deviation from the known. (d) By oversight, we did not use the special self-absorption curve which we had previously derived using EPA water and Cs-137 standard. We will use the EPA curve in the future. We may also re-derive this cun e using a water sample which the EPA has agreed to send us. (e) The calculations were checked and found to be correct. The results of six gamma emitting isotopes were reported to the EPA. The results of four were within 1 normalized deviation; a fifth, within 2 l normalized deviations. Only the Zn-65 average was outside the controllimits. There is no obvious l reason why one isotope should be outside the control limits, while five other isotopes were within control limits. ' (f) An investigation is being conducted; the results will be available shortly. l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 36 of 50
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*-TLD a-DRINKING WATER i A-MILK *-BROADLEAF VEGETATION /
4 IRRIGATED CROPS 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 41 of 50
FIGURE 6 l t l ; Gross Beta Results 1993 6.00E-02 * ! l ! t w ^ j l l !
! $ 5.00E-02 _. I__ __ _l ~
---~T lE '
u p l3
! 4.00E-02 _o ,_ .
7 i :2 o' i l2 c .t . a
^ ^
l2a 3.00E-02 -, Lq' r l_. c ,.S g b A n- * ' E
! 2.00E-02 __
a _ _ e. . a. - " im . , , ,.: p ie s > v .
,m __ _ i u g
! 8 1.00E-02 _. _.
L_ i- l O i I j 0.00E+00 j 0 4 8 12 16 20 24 28 32 36 40 44 48 52 Week Number o LOC 2 + LOC 3 o LOC 32 A LOC 37 : LOC 40
; L__.___
1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 42 of 50 A
. . - . . . . . _ _ , _ . , _ - - _ , . , . . _ . . , , .. . - , _ . , . . . , . . . . _ _ _ _ . . _ . . . . . . . _ _ - - - . . _ , . _ . . ~ , _ , _ - , . . , - _ . , - . . . . . . . , . . . - - _ _ , - , ~ - . , , _ . - , - , - _ - . - , . , - - - - . . . - - - . . , . , - - -,_
FIGURE 7 Smoothed (Avg of 20) Indicator and Control Gross Beta, Historical u 0.060 p __ __4__ j _t y l3 8 l' i .____ 4 ~} 4__ TChernobyl accidentL
^
~ ~ ~ ~ ~ ~
! i !
3 0.050 b
~ - - ~~--
I~ _ __. . g h__ _ _ _- l ! J _-_ _ 4
,m H--F __i
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--y I3 !
e ' r_ .+ __._____ l
. _4_ .I__. !
A ~
'I !
--~-
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R! o ZZ [_____a[Ih.Z a - b_- _-r}__ 4 M_._-__._a l
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a .._ p p __ _ __ _ __.__ _ _._____.. p _ K_ __ __ _ q _ j_ _ __4_ _ _ _____ .
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g _______f...__ ._ _
, ____.._y___-__._____ _ _ _ _ _ _.______7 p y . . . _ _ _ _.._____..y p._.____ +...-_.____q ._f _9 { .__7._ _ h__ .._______._]
; _ _ _ _ i__ __ .j __ _ _ ._ _ _ _ _ j 7, }.___._t_._.._ _ _ .__.__._j..______.__}______._
._.____7___ 4___ . . _ . . _ _ _ _ . _ _ _ _ ..__ __
O _[_]l[_T_._-[] __ ))][_ i_ _ _ __.__, } [_ ((_[ _][_~__ _] -))l _ __4[_1._ _. --"[___]_. [-~ ~
,y, 0.000 . _1.__..___.______p__..._.._j_________4_____ t 4 _ ______ y l* 1-Jan-85 1-Jan-86 1-Jan-87 1-Jan-88 1-Jan-89 1-Jan-90 1-Jan-91 1-Jan-92 1-Jan-93 1-Jan-94 i
Smoothed Average Location 40 - - Smoothed Average hdicator Locations 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 43 of 50 s
FIGURE 8 i Airborne Particulate Indicator Weekly Average to Control Ratio (Historical) j 1 x 180.0 2 b l. 2 160.0 l I i ! ,3 i ie j - 1 i - Io 140.0 - t-1 - 3 - - . b
.l_" -
5 120.0 - o
~
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.o. l 8 40.0 i l E l.
E i o 20.0 a 1-Jan-85 1-Jan-86 1-Jan-87 1-Jan-88 1-Jan-89 1-Jan-90 1-Jan-91 1-Jan-92 1-Jan-93 1-Jan-94 E q l Smoothed Ratio (Aw) of 20) - Weekly Ratio
! I
- t. .
1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 44 of 50 (
FIGURE 9 T I Control (LOC 40) and Indicator location average, Historical. '
, L
. 3.60E01 l, j _.
..__-__y__._.- Chernobyl i 7_
_t -- l.
--._ H -{=_=_g- ;
i _ = _ _l_ i E - - " - - - Accident - - t -t l -- -) 3.10E01 F'-~ I -~--- ' i i - LOC 40 -i ( j$o w ._ __ t : i _ __; __2 4 _ [__ _ _ _J ._J r _ .___.___ L_ n _ I ___T 4_ _ 1 indicator Average _. l ! E 2.60s-01 1
--------i--- --
4 ' 4-- --- jo - - __p___.. 4 l 4
,o __{
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+ j
---i O 2.10E-01 i f l .3 t-- ,
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.- _ _ __ _ __ _ y .
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j .__ p.____q _ y -_ t -_- y __- .. _ _ g t ----
----t--------t 7-._-.--_~
M
.r -- -t---------T---
-S-- 1.60E01 - t- --
m L [ - _ -- - . _ . . _----- _-__--._-.t--------]-___t___-__---..___._____# I. i _. ! _ _. _ _ . . _ p
-M_.---- - - H- l----- b--------- - _ _4 _ ._ __._--- - ._ a-4 . --
7 1 -Q L__- -______-}__ ---y____._...___J__.____{. _ _ _ . _ . . . lm 1.j os01 f -- ---- --- - H t ---- -- --- -- b --- ------ t --- 4._ __ t-------- ___
$ ___+_ _.t_________
_._ pp. _ _ _ ____ _ q _ _ . . ._ _ _ 4__ . . _ __ y p__ } _4___ _ _ . __ j o u _._._--__% r_ _
-_-..+-__.___.,__-.-___._m-.-- _9______ _ _ - - - _ . _
_4_._ _gq 4.- -
~~~d-~~~' ~ - ~ E- -- ~ ~~~ + - - - -- i O 6.00602 --t----- t - --- - j t
i.-~ [;t. _ ~ 1_. i T T _ _ _ _ . . ,__ _ _ _ _
,_..___L _ _ _
l ' r ___-__ p__-___ __p ___._ _!,
~
l 1.00602 ,__--___i,_-____% g__.___.-_.._ , 4 __, 1-Jan-85 1-Jan-86 1-Jan-87 1-Jan-88 1-Jan-89 1-Jan-90 1-Jan-91 1-Jan-92 1-Jan-93 1-Jan-94 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 45 of 50 4
. - - . , , , , - , . _ - , , , _ . . . , - , - . . , . , _ , , - . - . . - - . _ , , - - - . . . . . , _ . , , , - - - . _ _ _-..,,. _ -,_,- .._,. _,... . ._ ,,,..-,...-~..----- ,,,._.,.- , , _ . _ . , _ . - -
Figure 10 5
, - . _-_ _ ___.m. _ . . _ _ _ _ _ _ _ - _ _ . _ _ _ . _ _._ _ _ _ __ __.._ _._._.._ _ . .-__. - _ . --
f Variation of Nearsite TLD Averages Expressed as a Ratio to Control Values 1 1 115.0 8 y 110.0 ___ _ _ _ ___ ia + , . + +
+ * * * ** *
$ 105.0 _ _ , _ . . _ , _ , , ,.,
, v o + * * * + 4 100.0 .
IE + ' o + o uC 95.0 . _ _ _ O O 90.0 jg _ . _ . _ _ _ _ _ _ _ _+ _ _
!I
'S 85.0 _ _ _ _ _ _ . _ _ . _ _
8 E C 80.0 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993
+ Nearsite Avg (<3 mi distant) to Control Avg. Reference (Ratio of 1:1 expressed as percentage) expressed as percentage L . . _ . _ _ _ _ . _
1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 46 of 50
FIGURE 11 i Nearsite Locations, Control Locations, and Nearsite incicator to Control I Ratios 140,0 26.0 20 24.0 --- - - - - - - - 120.0 22.0 - - - - - - - - - - - - - 110.0
- - - -~
100.0 20.0 - e e 90.0 18.0 g ;,- # -- e __g , _ _., __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
^,eA A n 3 8
# ^
'^
,e oe8s l en*e ' S e_ ,__o, , , _ _ __ s "a -
80.0 16.0 g---- =^ e 3 g7 B gn - ^-c - e m
,eA, *e o m0 3 eo m,A A" A
s An A3 fr, A o s n - -*" e _ 60.0 14.0 -A A a g 4 12.0 50.0 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 8 Average d Nearsite Locdions A Average d Control Locdions Necrsiteto Cordrol Rdio(in f percent) t-. . - - _ _ _ _ - - _ - _ _ - _ _ - _ _ _ _ _ _. l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 47 of 50 J
FIGURE 12 l l i WCCL Smoothed (avg of 10) Surface Water and Cumulative Liquid Effluent Tritium Data i i 10000 . . 10000 v._____.____.__.__._ __ g j 9000 6 - - - - -- - --- -
-l 9000 a i
, w - -.. . . - - - - _
8000 - Z
~
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e+ e Z~At- 8000 b C r : .: - : === . --- _-.__r-~ _=
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i
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8 -
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- V 7000 h
$?=: = r: Y ,_ , #$* $
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l {: } [ l l .z_3,% - e' 9_ i:: ?E=hFE==E+3Ye%ie -_fe -**W-
- 2 6*% _== ** ~~ ~ T E[
- - - -- M --H {
5000 '-~ ~ - -- 5000
,y . . _ = - - = = r- = : =r- __
***y f " _ _ :======rr == =: -
=) Q 2 2 5 4000 - 2 --- ' " ^ ^ ~_ ~ - _
~~~~~ - --- - -- T~ ~ - --- E- l 4000 E
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a
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s: EEE I}E-E}E-E.E qI- E -- E -I:Es = 2 3000 i8 3000 o _ - =neer===== i I2 e 2 1 1==- -
= - -
= --
n:E:Er l: : : : : : : i
- i i i : i i g =21t2000 :
!b ,000 ggg I..jd5N?rf555- = r[h-?BEb!55;! !!!I!!555f 1000 t
0 i=w.3. IyHil lil I!III!I I!I I Illil I!I III!I!I Ill!I I I I It 0 I 01-Jan-85 01-Jan-86 01-Jan-87 02-Jan-88 01-Jan-89 01-Jan-90 01-Jan-91 02-Jan-92 01-Jan-93 01-Jan-94
; e Smoothed DC (as of 10)
- Smoothed SP (as of 10) Cumulatie Tritium Curies Released i l _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ . - __
1 _. __ _ _ _ _ . _ - _ _ _ t 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 48 of 50 o
. . . . . . - . , . , _ _ , _ - . . , . . . _ , _ , . . . . _ . , , _ _ - . , _ _ . . . . . _ . , . . _ ~ , . . . . . . - . . . - , . . , . . , , , - . , . . , _ . - . _ _ - , . - _ . . _ _ , . , , _ - _ , . .,. _..,_._ _.,_ _._._ ---. _ . .- - . - . ,. . . . . . _ . , , , _ _
I l FIGURE 13 l 1 -
; WCCL Smoothed (avg of 10) Surface Water and Quarterly Liquid Effluent Tritium Data i
i { 10000 500 9000 *- E ' 450 j 1---- -
, -g _-j g l 8000
~ ~~ ~
-*M me EW 1 ! 400 E j- __
g- e, ___ e __j c
-eN, 7.
j !$ 7000 'q - %8%t g 7 7 350 :n 6000
= [ -
300 is 5000 r es . s
-e-Eq2 eg liFla-250 3 lo 4000 ege __
.- . 5.ame.
a ~
- B U
_ _ ___ a 200 of - i g i _ _ 8 **nz se# E- - _-E : __ _ _1 $ o 3000 I' E E- -m- E E: - -E- - 150 = E E 5 . 100 2000 - - E. -M : 7 E 50 1000 E.!IIlli.lilililaililillililiI!I!II!.I!Iililil.TIil!I.I!Ile.0 l; 0 , l 01-Jan-85 01-Jan-86 01-Jan-87 02-Jan-88 01-Jan-89 01-Jan-90 01-Jan-91 02-Jan-92 01-Jan-93 01-Jan-94 3 ! l e Sm oothed DC (avg of 10) o Smoothed SP (avg of 10) g Tritium Curies Released per Quarter l L -- _ i 1993 Annual Radiological Environmental Operating Report ! Wolf Creek Generating Station Page 49 of 50
-,-m, -, -,-- ---,, n , n .. ,-,r~,-----,.~..n- -,mm-,r. ,nn,,e,--.-.----.------,-,,,.-,-- . - - - , , ,,-~-.-,---,n. ,..c,--,n- > - - - .- - --- ,, ,..--w
I , t , 1 l f r l FIGURE 14 l r Drinking Water Gross Beta, Historical' i 20.0 .._____m.__ . i !
- l l { r Feb 90 'valuen L
._ l 4 4 J
~ .
7 l l 18.0 .. _ _ _ . . _ . _ _ _ __ i l 50 pCl/liteg __, i __ l _.._._l____. . _ L. _ I 4_ { _ j __ j 16.0 . . _ - _ _ _ _ _ __ ___ ___. __1 . _ _ _ . _ _ . _ .
; 9 i
14.0 .._ _ .4 )___ _ _4_ , L_ l,y_$ I _ _ _._ _ _I _ _ _ I _-. __ ._, _ , , .I_ i 7
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~
+ ,l , - .! , +
a ,i. _+ j ,y 80 __ _ _ _ __ _ _ _ _
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+
o I + j 4- + f4ge, , g+ , j,- - , _ _ _ r o+ **
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3 + 2.0 .. _ __ _1,_ _ _ _ j . _ _ __. _ i ___ _ ._ { __ _ _ _h* __ _ _ _7_ _ ._ _.i _. _ _ __ q_
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- p..___. e 0.0 .e .
n o i e a l 1-Jan-85 1-Jan-86 1-Jan-87 2-Jan-88 1-Jan-89 1-Jan-90 1-Jan-91 2-Jan-92 1-Jan-93 1-Jan-94 1-Jan-95 i j 1 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 50 of 50 o
. 1 o .
Appendix A Summary Tables in the format of NRC Radiological Assessment Branch Technical Position Revision 1, November 1979 ; i l l l l l l l l l l 1 l l I l l I l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 1 of 11 Appendix A
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>3 S(a3 K@ ENVIRONMEfRAL RADIOLOGICAL MONTIORING PROGRAM
SUMMARY
@ [_
O Name of Facility Wolf Creek Nuclcu Docket No.S1N 50-482 to a
@ 5' location of Facility Cofrey County. Kansas Reporting Period Annual 1993 y 6" (County. State)
(Q 3-f.O h) hb o@ Medium of Pathway Analysis and lower Limit Total Number of Number of All Indicator IAcations location with Iltchest Annual. Mean Control locationg Nonruutine 3 =r Sampled of Analysis Detection " Mean (1) Name "Mean (!) "Mean (1) Reported
@ (Unit of Measurement) Performed (LLD) "Ra nge Distance and Directions " Range "Ra n ge Measurements" 3 Station No. JRR (D
h Sediment / Silt (pct /g Gamma (10) O dry weight) BE-7 0.3 0.45(1/8) DC4 0.45(1/l) -(0/2) 0 g U JRR 4 miles W e K-40 0.5 11(8/8) 14(2/2) 14(2/2) O c3 (4.3- 14) (11-17) (Il-17) 23 to Co-58 0.02 0.32(1/8) DC-3 0.32(1/l) -(0/2) 0 ba Mn-54 0.03 0.067(2/8) . DC-3 0.077(1/1) -(0/2) 0 (0.057-0.077) -- -- Co-60 0.02 1.2(7/8) DC-5 2.3tI/1) -(0/2) 0 (0.47-2.3) - -- Cs-134 0.06 0.26(6/8) DC-4 0.36(l/1) -(0/2) 0 (0.14-0.36) -- - Cs-137 0.06 0.63(8/8) DC-4 0.94(1/l) 0.22(2/2) 0 (0.22-0.94) -- (0.22-0.23) Ra-226 0.5 2.4(8/8) DC-1 3.0(1/1) 2.0(2/2) 0 (l.7-3.3) -- (l.6-2.4)
"U uc$ Th-228 0.04 1.2(8/8) DC-5 1.5(I/1) 1.3(2/2) 0 V u (0.59- 1.5) --
(l.1-1.4) @m aO R' ] >m Nominal lower IJmit of Detection (LLD)
** Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled locations is Indicated in parentheses (f)
e b
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83 (D 3 5 ENVIRONMENTAL RADIOLOGICAL MONTIORING PROGRAM
SUMMARY
E[ oa Name of Facility Wolf Creek Nuclear Docket No.STN 50-482 k5 locauon of Facility Coffev County. Kansas Reposting Period Armual 1993
- iS.
go (County. State) m8 Analysis arul lower IJmit Number of
@ <, Medlurn of Pathway Total Number of All Irxlicator locatl9nt location with litchest Annual. Mean Control locations Nonroutine Sampled ofAnalysis Detection a Mean (0 Name "Mean (0 **Mean (O Reported 8 (LLD) "Ra nge Distance and Directions " Range "Ra n ge Measu rement s**
3 (Unit of Measurement) Performed Station No.JRR h 3 Ei- Shoreline Soll Camma (4) (pCl/g 0 dry weight) K-40 0.5 8.6(2/2) JRR 4.0 miles W 9.8(2/2) 9.8(2/ . t o (8.8- 11) (8.8- 11) g (7.5 9.8)
$. -(0/2) 0 g Co-60 0.03 0.09(1/2) DC 0.6 miles WNW 0.09(1/2) m (D
E Cs-137 0.06 0.12(2/2) DC 0.6 miles WNW 0.12(2/2) O. I 1(I /2) 0 A (0.07-0.17) (0.07-0.17) -- Ra-226 0.5 1.3(2/2) JRR 4.0 miles W l .9(2/2) 1.9(2/2) 0 (0.74- 1.9) (1.6-2.3) (1.6-2.3) Th-228 0.04 0.89(2/2) JRR 4.0 miles W l.4(2/2) 1.4(2/2) 0 (0.69- 1.1) (l.0-1.7) (l.0-1.7)
>2 E'S 8m aO W ,*
.i
>m Nominal lower Limit of Detecuon (LLD)
" Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations se indicated in parentheses (0
6
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i-
i3 3 m3 E_ ENVIRONMENTAL RADIOIDGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Wolf Creek Nuclear Docket No.STN 50-482 c a[ kE Incation of Facility Coffev County. Kansas ReportingIVrtod Annual 1993 (County, State) i8 e _.. f.O 0 Analysis and Lower Limit Number of sr@- tt. All Indicator locations location with flichest Annual. Mean Control locations Nonroutine 8< Medium of Pathway Sampled Total Number ofAnalysts of Detection " Mean (0 Name "Mean IQ "Mean (f) Reported 8 ** Range Distance and Directions " Range " Range Measurements" 3 (Unit of Measurement) Performed (LLD) No control h 3 Gi Soll Camma (1) tpCl/g dry weight) Be-7 0.3 0.6(l /1) A1 1.4 miles N 0.6(l/11 -- O u to .. U
$ AI 1.4 miles N C K-40 0.5 9.0(l/1) 9.0(l/1) --
O
~D .. ..
to E Al 1.4 miles N o, gog g / g) o 3 Cs-137 0.06 0.10(1/1) .. Ra-226 0.5 1.6(l/1) Ai 1.4 miles N 1.6(l/1) -- 0 Th-228 0.04 0.8(l/1) Al 1.4 miles N O.8(l/1) -- 0 >T uo to A 3 % ao R] Nominal Inver Limit of Detection (LLD)
' Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled locations is indicated in parentheses II)
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O >3 (D U ENVIRONMENTAL RADIOLOGICAL MONTIORING PROGRAM
SUMMARY
7 5_
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Name of Facility Wolf Creek Nuclear Docket No.STN 50-482 location of Facility Coffev County. Kansas - Reporting Period Annual 1993 kO (County. State) e,8
=r -
6 M sr - Analysts and Lower Umst Number of et @ Medium of Pathway Total Nueaber of All Indicator laations location with litchest Annual. Mean Control laations Nonroutine
@ g.
Sampled ofAnalysis Detection " Mean (f) Name "Mean (f) **Mean (f) Reported 3 (LLD) "Ra nge Distance and Directions " Range " Range Measu rements" 3 (Unit of Measurement) Performed 3 BW-15 m l 3 I Ei Water 1-131 (23) 0.5 -(0/12) NA NA -(0/11) O
- t Drinking 2 '6.9(12/12) HWI5 3.9 miles SW 7,og137g3) 7,ogggfgg) o n (pCl/l) Gross (23)
$ Heta (2.3- 13) (5.0-9.4) (5.0-9.4) t cu E Gamma (23) --
-(0/12) NA NA -(0/11) O o
h Trttlum (8) 1000 -(0/4) NA NA -(0/4) O ; y .. .. .. i a B-12 Water. 1-131 (16) 0.5 -(0/12) NA NA -(0/4) O Ground -- -- (pCl/I) Gamma (16) K-40 100 -(0/12) NA NA -(0/4) O Tritium (16) 1000 -(0/12) NA NA -(0/4) O i T
>csu vw
^ i 3 O Q O, x.
>A
. Nominal lower IJmit of Detection (ll.D)
' Mean and rargge based upon detectable measurements only. Frection of detectable measurements at specified locations is indicated in parentheses (f)
e a to o 30 S >3 e3 k ENVIRONMENTAL RADIOLOGICAL MONTIORING PROGRAM
SUMMARY
$h u o.
Name of Facility Wolf Creek Nuclear Docket No.S1N 50-482 hE 3M locauon of Facility Coffer County. Kansas Reporting Period Annual 1993 (County. State) go . (O g- ^~ g$ Analysis and lower Limit Number of 3 i Medium of Pathway Total Number of All Indicator locations location with Illahest Annual. Mean Control locations Nonroutine 8 Sampled of Analysis Detection " Mean (0 Name "Mean (Q "Mean (O Reported 3 (Unit of Measurement) Performed (LLD) "Ra nge Distance and Directions " Range "Ra n ge Measurements" Munh h 3 E Water 6 Surf. ice (pCl/I) Gamma (36)
, K-40 60 136(1/24) DC 136(1/12) -(0/12) 0 3
- Tritium (36) 1000 6950(24/24) SP 6967(12/12) -(0/12) O
[ (5600-8900) (5600-8900) -- E 2 1
'V w V a E
i Nominal tower Limit of Detection (11D)
" Mean and range based upon detectable measurements only. Fraction of detectable measurements at spectfled locations is indicated in parentheses (f)
Appendix B i 1993 Individual Sample Results i 1 d j l .i 4 1 i 4 4 J l l l l l l l 1 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 1 of 77 Appendix B
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E 1 ) 2 2 2 2 2 2 2 2 2 2 2 2 LI 2 2 2 2 2 F M. 0 0 - 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L3C 1 u E E E E E E E E E E E E E E E E E A1 t O./ 3. 3 3 2 2 2 2 1 2 2 1
. 2 2 2 2 2 2 CIC R (p T. T. T. T. T. T. T. T.
T. T. T. T. T. T. T. T. T. l i A L L L L L L L L L L L L L L L L L _ C T N .
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2 O 1 1
/ /1 / / /1 / 2/ 2/ 2/ 2/3 /3 /3 / / / / /3 CMT I A 1 I 3 4 4 4 4 DTD I
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M N 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 O A 0 0 0 0 0 0 0 0 0 0 -0 0 0 0 0 0 0 I T S R T )- - E E E E E E E E E E E E E E E E E A R E E M. R E T D 3 3 4 3 3 3 3 3 3 4 3 3 3 3 3 3 3 O T LSu 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 P L I I FSC Ol/ i 1 1 1 1 i i t 1 1 1 i 1 1 1 i 1 R F PRC 4 3 6 3 9 9 7 1 2 5 5 6 3 7 5 7 6 O L A G (p 3-3 4 2 2 2 2 3 3 3 2 1 2 1 1 1 1 C G O 0 A 2 - N C 1 R R T A A EB l R l E C MU P D N O N T R A N N U 5 2 8 5 0 9 3 1 3 31 2 8 8 5 3 8 A E E T OI OEE 1 2 2 0 2 0 0 1 1 4 2 0 0 1 1 2 2 L T CMTA / / 1 / /I / / / / / / / / / / / / / C A AT I 1 2 2 2 2 3 3 3 3 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 4 4 4 U I DTD N CU S I M < K E m l E A R P C R X I IA O S W T : C I N C C C O O O I ( C C OCO O C O C C X(: X(: OCC C O C C C CO - U E 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 < U E 3 5 E E 8 E 8E E8 E4 E 0E7 E 7 E E4 E 2E8 E 2 2 E E 1 8 0 L _ O 1 2 0 2 0 2 1 2 2 0 0 0 9 9 9 0 9 V 3 3 3 3 3 3 7 3 3 3 3 3 2 2 2 3 2 _ EPE 5 2 9 6 22 09 06 3 3 2 292 60 03 0 6 3 02 1 1 3 0 1 2 . 0 1 1 TOT ATA
/ / 1 / /1 / 1 / / / / / / / / 2/ /3 /
2 2 2 2 3
/ 3 3 3 4 4 4 s DSD 1
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t s ly a n N A 0 1 t e 1 a C
- c ET LRE 9 5 2 9 62 20 09 6 6 3 2 92 60 03 0 6 3 1 1 2 3 0 1 i
lp 2 0 1 1 1 u LAI A / / / / / / / /2 / 2/ /2 / 2/ /2 3/ 3/ / 3 3 3 4 4 D 2 t I 1 I OCST'D 1 0 O 0 0 0 0 0 0 0 0 0 0 0 0 0 0
- s > S E,_ h a E S gW k 5
f@ = r S Bm y O 3 g k h 3 2 _ r D ^ u $*toO[N h ok{$ek= O Ck5" 3 d 3 aR' 0 L
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tw o. AIR pal (IlCULATE AND CilARCOAL FILTERS i 5E STATION NUMBER 02 58 ga __. U)O kb 5' 3 COLLEC110N DATE START STOP MID COUfG TlME A P FILTER GROSS DETA MID COUfR TIME CilARCOAL FIL1ER 1131 3 k- DATE DA1E VOLUME UNITS DATE (pCl/Cu.M.) DNIE (pC1/Cu.M.) O m 2.7 i 0.3 E 02. 04/20 04/27 2.91E 08 05/04 05/01 LT. 1. E-02 g 04/27 05/04 2.83E 08 CC 05/11 1.9 i 0.3 E-02 05/08 LT. 3. E-02 0 05/04 05/11 2.92E 08 CU 05/24 2.110.3 E-02 05/15 LT. 2. E-02 g 1.510.3 E-02 05/25 g 05/11 05/18 2.92E 08 CC 05/25 LT. 3. E-02 e 2 05/18 05/25 2.93E 08 (E 06/02 1.6 i O.3 E-02 05/29 LT. 2. E-02 ; L e k 05/25 06/01 2.84E 08 T 06/08 1.9 i 0.4 E.02 06/05 LT. 2. E-02 i
$ 06/01 06/08 2.85E 08 CC 06/16 1.9 i 0.3 E-02 06/11 LT. 3. E-02 06/08 06/15 2.87E 08 (E 06/29 2.210.3 E-02 06/19 LT. 2. E-02 06/15 06/22 2.87E 08 OC' 06/30 1.8 i 0.3 E-02 06/26 LT. 2. E-02 2
06/22 06/29 2.87E 08 CC 07/08 1.510.3 E41 07/03 LT. 2. E-02 l 06/29 07/06 2.86E 08 OC 07/16 2.410.3 E 12 07/11 LT. 1. E-02 07/06 07/13 2.88E 08 CC 07/21 2.010.3 E-02 07/18 LT. 2. E-02 07/13 07/20 3 06E 08 OC 07/27 1.7 i 0.3 E-02 07/24 LT. 2. E-02 07/20 07/27 2.90E 08 OC 08/06 2.210.3 E-02 07/30 LT. 1. E-02 13 M D u 07/27 08/03 2.80E 08 OC 08/12 2.210.3 E-02 08/07 LT. 2. E-02 08/03 08/10 2.80E 08 OC 08/19 2.4 i O.3 E-02 *
- @ ca Q. O EQ 08/10 08/17 2.90E 08 OC 08/26 2.7. i 0.3 E.02 08/22- LT. 2. E-02 03 N 08/17 08/24 3.10E 08 OC 08/30 .2.3 i 0.3 E-02 08/28 LT. 2. E-02 08/24 08/31 2.90E 08 OC 09/10 2.8 i 0.3 E-02 09/04 LT. 2. E-02 08/31 09/07 3.00E 08 OC 09/15 2.010.3 E-02 09/11 LT. 1. E-02
- Sample not received.
i t e n n n n n n n n n n n n n n n p o o o o o o o o o o o o o o o o 3 5 Q 6 5 6 6 6 O aO U & O 5 6 0 22 - r ( n Du= O~y u- ad ad d ad J d ad d aaaa ' 3- a 9 sssssssssssssss aaaa aaa aaa aaaaa c W j u* 2 a s 8 e a 8 s n.a s 8 2. n s 8wN<&&223&&>>>nnAsa> aso o o - - - --- - - ----o i 5 s s s s s s 8.8 8 s s s s 8 8 8 A x6e e e e e e e e- c w 2. 2 eeeee aE W=2 nnnnnnnnnnn nnnnn d y o o o o o o-o o- o o o o e o o o -
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E 28U SE882 N8s: N$ a o s&&&2 2222AAss z o 5"s g o < & s: aa8eeas8sa8s: a v e o '8 '8 o&Eo &&2 22 3>AAN 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 4 of 77 Appendix B
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y 88888888888888888 l g w w w w w w w-w w w w w w a w w w 1 o E n n$n?n ?n E n n? n? nE.n o o E ? ? E 5. ? $. n n nn n n n -
$'s aU 2 8882 N882 NN880 8 '
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v c - o oo o o o o e o o o o.o o 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 5 of 77 Appendix B
R E l ) - L' 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 FI M. 0- 0 0 - - 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L 1 u E E E E E E E E E E E E E E E E E E E E A3C 1 . O/ CIC l 1 . 3 2 2 1 2
- 3. 2 2 2 1
2 2 1 2 2 2 2 2 1 R (p T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T T. A T. T. l l L L L L L L L L L L L L L L L L L L L L C T N U 1 8 5 15 9 5 1 9 6 3 I 8 4 0 7 5 21 8 4 OEE 0 0 2 2 0 1 1 2 0 1 1 2 3 0 2 2 0 1 1 CMT I A / 5 5 5/ / / / / 5 5
/ / / / / / / /
6 6 6 6 7 7 7 7 7 8 8 8 8 9 9
/ / / / / /
DTD I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M N 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 O A 0 0 0 0 0 0 I T S RXJ E E E E E E E E 0E 0E0 E0 E0 E
- - - - - - - - - - 0 0 0 0 0 0 0 0 0 E E E E E E E A
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1 R9 E/4 8 2 1 4 5 95 7 9 627 3 0 911 629 I 3 01 1 1 0 1 0 2 1 1 2 2 3 1 1 0 0 R0 0 0 0 0 0 0 0 0 0 0 0 000 0 0 0 0 0 A/ 00 000O00 0 0 0 000 00000 U10 1 i 1 i 1 i 1 i 1 1 i 1 i 1 1 i 1 t 1 Q. 1 9 8 9671 7 1 0 1 37 92 2 4 1 4 e 3 c l l 9 4 5 6 8 4 6 76 8 8 67675 5 621 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 r u i/ R3 00 00 00 000 0 0 0000 0 00 0 o s 1 U/ n O0 w F1 o n k n u n a _ m N o 0 R f r _ 1 T E I s A R e s - R S A o V R U d EE I _ R NT Q s O RE u _ D io C OMBI R! r u . G RSO i l s p _ N T IAD I A - )y l' d e R YT f a d i v E Al / e P WEC R ce _ O 1 m r R 1S T e A AE t e R 39 v E PN n a L EM I ( E/ h I8 C U ULRU R0 A/ 5 7 1 1 6 2 0 81 5 4 7 3 3 6 57 9 2 0 0 1 1 1 1 00 1 1 1 0 21 1 1 0 1 1 y a N SO U70 0 00 0 0 0 0 0 0 00 0 0 0 0 00 0 0 m K E VM I Q-3 0 0 0 00 0 0 00 0 0 0 000 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 e y E XR R EE 1 D9 N/ 8 4 6 995 5 2 4 4 6 8 9298 2 00 25 6 3 25 55 66 6 5 6 75 230 11 1 1 1 1 1 1 ht C 1 T O7 0 1 I. 1 1 1 1 1 1 1 1 1 00 0000 0 00 00 0 0000000 I. e C/ s u _ E I E4 a O S0 c e W b c ib a 3 s 9 u R 7/ n E0 u _ I/ 1 8 1 05 5 4 5 1 7 21 2 97 31 4 1 e . R4 1 0 1 1 0 0 1 1 1 01 2 1 0 0 2 1 01 r e _ A0 - 0 0 00 0 0 0000 000 00 0000 U3 w _ 00 0 0 00 000 0 000 00 0 0 00 4' Q9/ 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 7 5 2 8 3 61 6 4 91 4 605 5 2 3 s t _ T6 1 3 8 31 4 4 4 67 4 4 3 5 5 5 31 1 l u S0 1 I. 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 s e R/ I 1 0 0 0 000 00 0 0 00 0 00 000 0 r F0 D. 1 1 r e t r _ a u q d NR ir OE 5 67 8 90 1 2 3 4 5 67 8901 23 ht IB T 22 2 2 2 3 3 3 3 3 3 3 3 3 3 4 4 4 4
- - - - - - - - - - - - - - - - - - - e AM TU AAAAAAAAAAAAAAAAAAA h TTTTTTTTTTTTTTTTTTT T SN SSSSSSSSSSSSSSSSSSS
- e 8 >sE m [a5' y k $O33gE O3hS ;$$ U EeoBRa@.Byot n 3 y M= O ~
L' o3acR m _' 1 '
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0> es 3 3 hk WOI.F CREEK NUCLEAR OPERATING CORPORATION
$h9: EXPOSURE PATilWAY - AIRDORNE TilERMOLUMINESCENT DOS! METERS l'l % 9 (net mR/ day) en8 k f5k STATION FIRST QUAIGER SECOND QUAIGER TillRD QUAR 1ER FOURUI QUARIER NUMI!ER 01/06/93-04/07/93 04/07/93-07/08/93 10/13/93-01/04/94
(( 8 0.13410.008
- 0.149 i 0.012 3 STA-25 '.12110.003 STA 26 0.139' n.011 0.15110.013 0.149 i 0.014 0.16110.008 0.178 1 0.011 h STA-27 0.15510.016 0.I78 1 0.012 0.13810.009 0.14110.016 h STA-28 0.13410.010 0.164 1 0.020 3 STA-29 0.12910.004 0.14710.011 0.173 1 0.023 B STA-30 0.14810.009 STA-31 0.14910.009 0.15810.0 t o 0.178 i 0.013 y STA-32 0.14410.011 0.14410.009 0.174 i O.010
$ STA-33 0.17010.020 0.16210.008 0.179 i 0.016 STA-34 0.15410.011 0.16610.013 0.183 1 0.010 S
STA-35 0.16810.009 0.17010.016 0.177 1 0.008 STA-36 0.13610.004 0.16010.007 0.162 1 0.013 STA-37 0.I4010.004 0.I5210.011 0.177i 0.008 STA-38 0.16010.000 0.16910.030 0.193 1 0.015 STA-39 0.15110.008 0.15110.005 0.172 i O.018 STA-40 0.13210.008 0.15910.031 0.16I i 0.011 STA-41 0.12710.007 0.13810.009 0.171 1 0.010 STA 42 0.09910.007 0.09610.003 0.127 1 0.011 STA-43 0.11810.025 0.10910.007 0.113 10.002
*The third quarter TLD results were unusable because they may have received spurious doses from an unknown source.
Nu u m N CL O YG co ~
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P. 3 a3
*E WOLF CREEK NUCLEAR OPERATING CORPORATION h~m EXPOSURE PAT 1tWAY -INGESTION 8a g g- ANIMALS /OAME c-S *og- (pCi/GM WET) v> tu $h 5o STATION NUMBER NESR a$
8 3 DATE COLLECTED: 10/14 1O/14
$ WlIITE TAIL DEER WilrIE TAIL DEER *
{ CAMMA SI'ECTRUM ANALYSIS: O BE-7 LT. 8. E-02 LT.9. E-02
] 3.7510.38 E 00 B K-4 0 4.0310.40 F ru
$ MN-54 LT. 5 E-03 LT.6. E-03 g CO-58 LT 8. E-03 LT.9. E-03
.g FE-59 LT. 2. E-02 LT.3. E-02 Q CO-60 LT. 5. E.03 LT.6. E-03 ZN-65 LT. 1. E-02 LT. 1. E-02 ND-95/ZR-95 LT. 8. E-03 LT. 9. E-03 RU-103 LT. 1. E-02 LT. 1. E-02 RU-106 LT.5. E-02 LT. 5. E-02 1-131 LT. 5. E-01 LT.6. E-01 CS-134 LT. 5. E-03 LT.6. E-03 CS-137 LT. 5. E-03 LT. 6. E-03 1A-140/BA-140 LT. 8. E-02 LT. 1. E-01 CE- 141 LT. 2. E-02 LT.2. E-02 CE-144 LT.4. E-02 LT.4. E-02 RA-226 LT. 9. E-02 LT. 1. E-01 cw Til-228 LT. 1. E-02 LT. 1. E.02 Dto to y
So
- Duplicate Analysis R[
u
e Qa s O> 83 tt 3 K WOEX CREEK NUCI2AR OPERATING CORPORATION t C)E-e XI EXPOSURE PKI11WAY - INGES110N 5$ ANIMAIS/ GAME B 5' gg (pCl/GM WE1) oh y) STATION NUMBER CTRL EE 5' 3 3 S. o DATE COLLECTED: - QUAll 3 11/18
'h a GAMMA SPECTRUM ANALYSIS:
BE-7 LT. 1. E-01 h K-40 3.1510.31 E 00 y MN-54 LT. 1. E-02 y_ CO-58 LT. 1. E-02 O FE-59 LT.3. E-02 , ! k CO-60 LT.9. E-03 i 3 ZN.65 LT.2. E-02 NB-95/ZR-95 LT. 1. E-02 , RU- 103 LT.2. E-02 RU.106 LT. 9. - E-02 l-131 LT.2. E-Ol CS-134 LT. 1. E-02 CS-137 LT. 1. E-02
- IA-140/BA- 140 LT. 6. E-02 4
CE-141 LT.2. E-02 CE-144 LT.6. E-02 RA-226 LT.2. E-01 Til-228 LT.2. E-02
> e[
v sa D PQ g o c Q. O - WG w~ i
e a o
- o>
e4 e s
*E WOlE CREEK NUCl2AR OPERATING CORPORATION p~ EXPOSURE PATilWAY - INGFEllON
** $ ANIMALS / GAME B 5'
$y (pCl/GM WEll e
g STAllON NUMBER SCIU O E o Of. DATE COLLECTED- 12/08 j QUAIL e GAMMA SPECTRUM ANALYSIS: R
- E-01 BE-7 LT.2.
K-40 2.9910.30 E 00 g MN-54 LT.2. E-02
@ CO-58 LT.2. .E-02.
- FE-59 LT.4. E-02 h CO LT.2. E-02 3 ZN-65 LT.4. E-02 NB-95/ZR-95 LT.2. E-02 RU-103 LT.2. E-02 RU-106 LT.2. E-01 I-131 LT.8. E-02 CS-134 LT.2. E-02 CS-137 LT.2. E-02' LA-140/BA 140 LT.4. E-02 CE-141 LT.3. E-02 CE-144 LT.9. E-02 RA-226 LT.3. E-01 Tll-228 LT.3. E-02 i %"2 3w-o OO E']
, m~ _ _ _ _ _ . _ _ - _ - _ _ . - _ - - _ - _ _ _ - - _ - - - _ _~ _ -_ ..
4 -e o> c3 3 ox a g WOIX CREEK NUCLEAR OPERATING CORPORATION ce W EXPOSURE PA111WAY - INCESI1ON
' S $. ANIMAIS/CAME g 5-cz o-
@ig. (pct /GM WET)
'N- STATION NUMBER SCTR
$E 3 _ f.
O DATE COLIECIED- 12/08 3 QUAll
$ GAMMA SPECTRUM ANALYSIS:
EI h UE-7 LT.2. E-01 3 K-40 4.0810.41 E 00
$ MN-54 LT.2. E-02 i g CO-58 LT.2. E-02 m FE-59 LT. 5. E-02
$ CO-60 LT.2. E-02' S ZN-65 LT. 5. E-02 NB-95/ZR-95 LT.2. E-02' HU-103 L r. 2. E-02 RU 106 LT.2. E-01 1-131 LT.6. E-02 CS-134 LT.2. E-02 CS-137 LT.2. E-02 IA-140/BA-140 LT.4. E-02 CE-141 LT.3. E-02 CE-144 LT. 1. E-01 y RA-226 LT.3. E.01 pg Til-228 LT.3. E-02 u.
U a-il O i R'] m~
t k$ O_ e
-w 9>
8a
#k' WOLF CREEK NUCLEAR OPERATING CORPORATION hO EXPOSURE PADlWAY -INGESTION '
aa
@ 5' FISil u3 - (pCi/GM WET) u)8
' k bk STADON NUMBER WCCL 5a 3 S.
f 8 3 DKIE COllECIED: 04/30 04/30 04/30
$ CATFISII (CAME) . WIPER CARP (ROUGil)
ET-
. GAMMA SPECTRUM ANALYSIS:
E E-0I LT. 1. E.01 LT. 1. E-01 g BE-7 LT. 1. 3.5910.36 E 00 3.7110.37 E 00 3.0710.31 E 00
$ K.4 0 LT.2. E-02 MN-54 LT. 1. E-02 LT. 1. E-02 )
e CO-58 LT. 1. E-02 LT. 2. E-02 LT.2. E' FE-59 LT.3. E.02 LT.3. E-02 LT.3. F r> CO-GO LT. 1. E-02 LT. 1. E-02 LT. 1. 1 ZN-65 - LT. 3. E-02 LT.3. E-02 LT.3. E-02 LT.2. E-02 LT.2. E.02 LT.2. E.02 , NB-95/ZR-95 RU- 103 LT. 1. E.02 LT. 2. E-02 LT.2. E-02 RU.106 LT. 1. E-OI LT. 1. E.01 - LT. 1. E-01 1.I31 LT.3. E.02 LT.4. E-02 LT,4. E 02 CS.134 - LT.2. E-02 LT.2. E.02 LT.2. E-02 CS-137 LT.2. E-02 LT. 2. - E-02 LT.2. E-02 IA-140/BA-140 LT.2. E.02 LT.3. E-02 LT.3. E-02 CE-141 LT.2. E-02 LT.2. E.02 LT.2 E-02 E-02 8 CE.144 LT.7. E.02 LT.7. E.02 LT.8. N RA-226 LT.2. E-01 E.02 LT.3. LT.3. E-01 E-02 LT.3. LT.3. E.01 E-02
$ Til-228 LT.2.
!! E ,
CD N s
' Duplicate Analysis
T i h $-
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I
'h>S i WOIE CREEK NUCIE.AR OPERATING CORPORATION
@Eg EXPOSURE PKDfWAY - INCEST 10N
*$ FIS!!
B 5' *
$8g-D (PC1/CM WET)
Cf) s_p STAT 10N NUMBER WCCL G
&E c
3 Q. Q DATE COLLECTED- 10/05 10/05 10/05 g SM MOLTDI BASS / WIPER CIIANNEL CATF1Sil COMMON CARP e CAMMA SPECTRUM ANAINSIS: a G- E-01 LT.2. E-Ol LT.2. E-01 DE-7 LT. 1. O 2.7010.27 E 00 2.8010.28 E 00 3.2310.32 E 00 v K-40 h MN-54 LT. 1. E-02 LT.2. E-02 LT.2. E-02
$ CO-58 LT. 1. E-02 LT.2. E-02 LT.2. E-02 '
, FE.59 LT.3. E-02 LT.5. C-02 LT.4. E-02 g CO-60 LT. 1. E-02 LT.2. E-02 LT. 2. ' 'E-02 g ZN-65 LT.3. E-02 LT.4. E-02 LT.4. E-02 NB-95/ZR-95 LT. 1. E-02 LT.2. E-02 LT. 1. E-02 RU-103 LT. 1. E-02 LT. 2. E-02 LT. 2.. E-02 RU-106 LT. 1. E-01 LT.2. E-0I LT 1. E-01 1-131 LT.3. E-02 LT.5. E-02 LT.4. E-02 >
CS- 134 LT. 1. E-02 LT.2. E-02 LT.2. E-02 CS-137 LT. 1. E-02 LT.2. E-02 LT.2. E-02 IA-140/BA-140 LT.2. E-02 LT.4. E-02 . LT. 3. . E-02 , CE-141 LT.2. E-02 LT.4. E-02 LT.3. E-02 CE-144 LT.7. E-02 LT. 1. E-01 LT. 1.' E-0I RA-226 LT.2. E-01 LT.4. E-01 ' LT. 3. E-OI
>o-8 Til-228 LT.2. E.02 LT.4. E-02 LT.4. E-02 uu
.,w.
}U m:
4
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i3 3
$h G) -
WOLF CREEK NUCLEAR OPERATING CORPORATION EXPOSURE PATIlWAY -INGESTION S@ e 9- FISil R O_ (pCi/GM WET) d@S. V) gg STAT 10N NUMBER JRR 5a w 6-8 3 DATE COLLECTED 05/18 05/18 11/09 e WilBASS ROUGII F1SII COM CARP Calf CAMMA SPECIRUM ANALYSIS: O BE-7 LT.2. E-01 LT.2. E-01 E-Ol n LT. 1. y K-4 0 3.5710.47 E 00 3.2710.44 E 00 3.2810.33 E 00 g MN-54 LT.3. E-02 LT.3. E-02 LT. 1. E.02 O CO-58 E-02 LT. 2. E-02 LT. 3. LT. 1. E-02 h FE-59 LT.6. E-02 LT. 6. E-02 LT.3. E-02 3# CO-60 LT.3. E-02 LT.3. E-02 LT. 1. E-02 ZN-65 LT. 5. E-02 LT.5. E-02 LT.3. E-02 NB-95/ZR-95 LT.3. E-02 LT.3. E-02 LT. 1. E-02 RU.103 LT.3. E-02 LT. 3. E-02 LT. 1. E-02 RU-106 LT.2. E-01 LT. 2. E.01 LT. 1. E-01 1-131 LT.6. E-02 LT. 5. E-02 LT. 5. E-02 CS.134 LT. 3. E-02 LT.3. E-02 LT. 1. E-02 CS-137 LT.3. E LT.2. E-02 LT. 1. E-02 IA-140/BA-140 LT. 5. E-02 LT. 4. E-02 LT. 3. E.02 CE.141 LT.6. E-02 LT. 3. E-02 LT.2. E-02 CE- 144 LT.2. E-01 LT. 1. E-01 LT.6. E-02 RA-226 LT. 6. E-0I LT.4. E-0I LT.2. E-0i b *[ .o , Tl!-228 LT. 6. . E-02 LT. 4. E-02 LT.2. E-02 Ru o* . O. O X'] m~
._ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ m _ - _ . . - . -
. i i f a
t a e 40 l 0>
$5 xg WOLF CREEK NUCl2AR OPERATING CORPORATION EXPOSURE PADfWAY - INCES110N O ~D e .
S$ FEED & FORACE B 5-
- c. o (pCl/CM DRY)
$ C.
y3@ STAT 10N NUMBER EA-1 EE 5o ' aS 8 3 DA'IE COI1ECIED: 09/21 Mild k GAMMA SPECTRUM ANALYSIS:
=.
9! BE-7 4.9610.56 E-01 h* K-40 MN-54 2.4910.25 E 00 , LT. 6. E-03
$. CO-58 LT.7. E-03 3
0 FE-59 LT. 2. E-02 [ CO-60 LT.7. E-03 3A ZN-65 LT.2. E-02 NB-95/ZR-95 LT.7. E-03 RU-103 LT.7. E-03 RU-106 LT. 6. E-02 1-131 LT. 1. E-02 CS-134 LT.7. E-03 CS-137 LT.7. E-03 IA-140/BA-140 LT.9. E-03 CE-141 LT. 1. E-02 CE-144 t T. s. E-02 RA-226 LT 1. F-01
>g T11-228 LT. 1. E-02 ow Ex e. y WN
_ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ __ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . . _ . _ - ~. ., ~ . ___ , _ . - - ~ . _
.i i
I r s h8
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id 3 ! to 3
#5 WOIX CREEK NUCtJtAR OPERATING CORPORATION h]
3 as EXPOSURE PA11IWAY - INGESVON Q B. FEED & IVRAGE ! 5J o __. (pct /CM DRY)
$k Rm STATION NUMBER NR-UI o
c- Q. 3
@ DATE COLLECIED: 10/19 10/19 ;
CORN g SOYDEANS m CAMMA SPECTRUM ANALYSIS: BE-7 LT.6. E-02 LT. 8. E-02 i
}
u K.40 1.31*0.13 E 01 2.7210.27 E 00 < h MN 54 LT. 8. E-03 LT. 9. E-03 CO-58 LT. 8. E-03 LT. 9. E-03 FE 59 LT. 2. E-02 LT.2. E-02 g CO-60 LT. 1. E-02 LT. 1. E-02 ; I g ZN-65 LT. 3. E-02 LT. 2- E-02 NH 95/ZR-95 LT. 8. E-03 LT.9. E-03 RU-103 LT. 8. E.03 LT. 1. E-02 RU-106 LT. 8. E-02 LT.7. E-02 I-131 LT.9. E-03 LT. 1. E-02 CS 134 LT.9. E-03 LT. 1. E-02 CS-137 LT.9. E.03 LT. 1. E-02 IA-140/DA-140 LT.6. E-03 LT. 1. E-02 CE-14 I LT. l. -E-02 LT.2. E-02 CE-144 LT. 5. E-02 LT.7. E-02 RA-226 LT. 1. E-G1 LT.2. E.01 2 Til-228 LT. 1. E-02 LT.2. E.02 kW 2, ~, o O_ , m :i
'. Y
.e e
4, me o> 53
@3 a
;K- @- WOtX CREEK NUCtJtAR OPERATING CORPORATION EXPOSURE PAT 1tWAY - INGESTION G) re W e3 $ FEED & FORAGE 6
.i g
@ g' (pCl/GM DRY) c e@
U) sr STATION NUMBER NR-D1
.EE 2 5.
8 3 DATE COLLECTED: 10/19 SOYBEANS , h CAMMA SPECTRUM ANALYSIS: a b D E-7 LT.9. E ' h* K-40 MN-54 1.4710.15 E 01 LT. 1. E-02 3 CO-58 LT. 1. E-02 O FE-59 LT.3. . E-02 [ CO-60 LT. 1. E-02 3N ZN-65 LT. 3. E-02 NB-95/ZR-95 LT. 1. E-02 RU-103 LT. 1. E-02 RU-106 LT. 1. E-01 I-131 LT.2. E-02 CS-134 LT. 1. E-02 CS-137 LT. 1. E-02
- LA-140/BA-140 . LT. 1. E-02 a CE- 141 LT. 2. E-02~
CE-144 LT. 6. E.02 'I RA-226 LT.2. E-01 g T11-228 LT.2. E-02
>e o es D Cd j ..$N Q. O W
ms
e l I T l l I
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K5 O~ WOLF CREEK NUCMAR OPERATING CORPORATION EXPOSURE PA'IllWAY - INCEST 10N m% 5 $_ FEED & FORAGE B6 y (pCI/GM DRY) eEi [O to STATION NUMBER NR-D2 E' 5 m o(. DAIE COLLECIED 10/19 y CORN m CAMMA SPECHtUM ANALYSIS: a BE-7 LT. G. E-02 O K-40 2.9010.29 E 00 o y MN-54 LT. 7. E-03 g- CO-58 LT. 7. E-03 C FE-59 LT.2. E-02 h CO-60 LT.8. E-03 E ZN-65 LT.2. E-02 NB-95/ZR-95 LT. 8. E-03 RU-103 LT.7. E.03 RU- 106 LT.7. E-02 I-131 L f. 1. E-02 CS-134 LT.8. E-03 CS-137 LT. 8. E-03 IA-140/BA-140 LT. 1. E-02 CE-141 LT. 1. E-02 CE-144 LT.4. E-02 RA-226 LT. 1. E-01
>e2 Til-228 LT. 1. E-02 'o w a=
CL O WG m~
1 0 3 3 2 3 2 3 3 2 2 3 3 2 2 2 1 2 D 0 0 C -0 0 0 0- - 0 0 0 0 0 0 0 0 R EEEEEEEEEEEEEEEEEE l A l 2 7 C 7 2 6S 0 to 8- 8 28 29 9 7 .2991 . . ..1 5 2 1 . . . 2S 7 7
/I 0W 5 6 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T.
1S 52LLLLLLLLLLLLLLLL 1 03 3 2 2 23 2 2 2 22 2 2 2 1 2 D 00 - 0 0- -0 0 00- -0 0 0 0 0- -000 0 R A EEEEEEEEEEEEEEEEEE II 4 9 9 C 8 3 0 1S 2S 01 10 9 . 9 2 1 2 91 8 21. . 2. 2 8 2 1 I 1
/ 7 9 G 9WI 2 8 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. 0 0S 5 3 LLLLLLLLLLLLLLL6 N
OI 1 0 3 3 2 2 2 3 3 2 2 2 3 2 2 2 1 2 _ T D 0- 0 0 - 000 0 0 0 0 0 0 0 0 0- 0 0 A R EEEEEEEEEEEEEEEEEE R A I ON l 7 2 C 66 P R10
- O1 7S 1S 0 1 10 8 . .9. 21 . . 29981
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NN O A 0S 3 6LLLLLLLLLLLLLLLL II R T l l R _ A. C E E _ RY EA E N W BM _ PW D O( M U 1 03 32 3 2 3 3 22 3 222 2 I 2 _ R 1 R A C/ N D R 0 00 0- 00
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t a C 4 /3 6 4 7 0 1 4 6 8 c M E 7 0 -5 5 8-5 0 6- 9-5 -15 0 1 0 1 33 4 1 14 14 22 22 i l M p T - 4 3 -- 1 1 u A D A C E - N CZNRR1 BKMCF OEONBUU1 CCL - SSAEEAI CCRT I D 3U@ U" . $5~g O5aQoyoR9L O D ( $5 gy3 ao>8Dx o!Ot!Bgo uE5n (
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e a o> S3 eo j KE WOIE CREEK NUCIE.AR OPERA 11NG CORPORATION EXPOSURE PAlllWAY - INCEST 10N O3
** 2 3 ![
e FOOD /CARDEN CROIS i B 5' gy e -. (PC1/GM WET) i j gO_ STATION NUMBER R-1 ,
$1 m
- 5' 3 3 S.
O DATE COLLECTED 05/25 06/29 07/27 . i LETTUCE LETTUCE CABBAGE y k8 GAMMA SPECTRUM ANALYSIS: O BE-7 9.3111.15 E-01 8.5210.85 E-01 1.1010.11 E 00 3 K-4 0 5.46to.55 E 00 8.4810.85 E 00 3.4010.34 E 00 5 k MN-54 LT. 1. E-02 LT.8. E-03 LT. 1. E-02 d CO-58 LT. 1. E-02 LT.8. E-03 LT. I. E-02 E-02 O FE-59 LT.3. E-02 LT.2. E-02 LT.2.
$o CO-60 LT. 1. E-02 LT.9. E-03 LT. 1. E-02 a ZN.65 LT.3. E-02. LT. 2. E-02 LT.2. E-02 NB-95/ZR-95 LT. 1. E-02 LT.8. E-03 LT. 1. E.02 RU- 103 LT. 1. E-02 LT.8. E-03 LT. 1. E-02 RU-106 ' LT. 1. E-01 LT.7. E-02 LT.9. E-02' 1-131 LT.2. E-02 LT. 1. E-02 LT.2. E-02 CS-134 LT. 1. E-02 LT. 8. E-03 LT. 1. E-02 ,
CS-137 LT. 1. E-02 LT.9. E-03 LT. 1. E-02 1A-140/BA-140 LT. 2. : E-02 LT. I. E-02 LT.2. E-02 CE-141 LT.2. 'E-02 LT. 1. E-02 LT.2. E-02 CE-144 LT.8. E-02 LT.4. E-02 LT.6. E-02 , .m RA-226 LT.2. E-Ol LT. 1. E-01 LT.2. E-01 '
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. 21
$$ MILK S 5'-
c'. o WI/LITEM i 5 9. a , .g g STN110N NUMBER S-3 ' 9L m , 5' 3 g DKIE COLLECTED- 0I/12 01/12* 02/10 02/I0* 03/09 RADIOCllEMICAL ANALYSIS: i_ii l-131 LT.2 E-01 LT.2 E-01 LT. 4. E-01 . LT. 4. E-01 LT. 2. E-01 O CAMMA SPECTRUM ANALYSIS: , .n k
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BE-7 LT.3. E 01 LT. 3. E 01 LT.4. E 01 LT.5. E 01 LT. 3. E 01 5 K.4 0 1.3510.14 E 03 1.3910.14 E 0"l 1.3410.13 E 03 1.5110.15 E 03 1.3910.14 E 03 23 MN-54 LT. 3. E 00 LT.4. E 00 LT.4. E 00 LT.5. E 00 LT. 3. E 00 I CO-58 LT. 't. E 00 LT.4. E 00 LT.4. E 00 LT. 5. E 00 LT. 3. E 00 3 FE-59 LT.8. E 00 LT.9. E 00 LT. 3. E 00 LT. 1. E 01 LT. 8. E 00 < CO-60 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT. 5. E 00 LT. 4. E 00 ZN-65 LT. 9. E 00 LT. 9. E 00 LT.9. E 00 . LT. 1. . E 01 LT. 8. E 00 ' ND-95/ZR-95 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.5. E 00 LT.4. E 00 i RU-103 LT.4. E 00 LT.4. E 00 LT. 5. E 00 LT.6. E 00 LT. 4. E 00 j RU-106 LT. 3. E 01 LT.3. E 01 LT.4. E 01 LT.4. E 01 LT. 3. E 01 I-131 LT.7. E 00 LT.7. E 00 LT. 9. E 00 LT. 1. E 01 LT. 6. E 00 CS 134 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.5. E 00 LT.4. E 00 i CS-137 LT.4. E 00 LT.5. E 00 LT. 5. E 00 LT. 5. E 00 LT. 5. E 00 IA-140/BA-140 LT.6. E 00 LT.6. E 00 LT. 7. E 00 LT.7. E 00 LT. 5. E 00 u CE-141 LT. 7. E 00 LT.7. E 00 LT.9. E 00 LT.8. E 00 LT. G. E 00
>5 CE-144 LT. 3. E 01 LT. 3. E 01 LT.4. E 01 LT. 3. E 01 LT.2. E 01 l
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S XE O-WOLF CREEK NUCLEAR OPERATING CORPORATION EXPOSURE PAT 11WAY - INCEST 10N 3h ea MILK t B 5'- EJ (PCI/IJIER) oh (n STATION NUMBER S-3 i EE 63 , 3 (. O DA'IE COLLECIED- 06/22 07/13 07/27 08/10 08/24 h RADIOCIIEMICAL ANALYSIS: 1 131 LT. 2. E.01 LT.2. E-01 LT.2. E-01 LT.3. E.01 LT. 2. E-01 o g GAMMA SPECIRUM ANALYSIS: S E 01 E 01 LT.3. E 01 - LT.3. E 01 g BE-7 LT.3. E 01 LT.3. LT.3. 7 C K.40 1.4010.14 E 03 1.2710.13 E 03 1.3910.14 E 03 1.4810.15 E 03 LT. 1. E 02 h MN.54 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 3* CO.58 LT. ' 4. E 00 LT.4. E 00 LT.3. E 00 LT.3. E 00 LT.4. E 00 ' FE-59 LT.9. E 00 LT.9. E 00 LT.9. E 00 LT.9. E 00 LT.9. E 00 CO-60 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 ZN.65 . LT.9. E 00 LT. 1. E 01 LT.9. E 00 LT.9. E 00 LT.9. E 00 . NB-95/ZR-95 LT.4. E 00 LT.4. - E 00 LT.4. ' E 00 LT.4. . E 00 LT.4. E 00 RU- 103 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 RU-106 LT.3. E 01 LT.3. E 01 LT.3. E 01 LT.3. E 01 LT.3. E 01 1-131 LT.6. E 00 LT.7. E 00 LT.7. E 00 LT.8. E 00 LT.7. . E 00 CS-134 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 CS-137 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 IA.140/BA.140 LT.4. E 00 LT.6. E 00 LT. 5. E 00 LT.7. E 00 LT. 5. E 00 CE-141 LT.7. E 00 LT. 7. E 00 LT. 7. E 00 LT. 8. E 00 LT. 6. E 00 D} CE-144 LT.3. E 01 E 01 LT.3. E 01 E 01 LT.3. E 01 E 01 LT.3.
' LT. 8.
E 01 E 01 LT.2. LT.7. E 01 E 01
]A RA-226 LT.8. LT.8.
E 00 LT.8. E 00 LT.7. E 00 LT.7. E 00 "a h TH.228 LT.7. E 00 LT.7. LT.7. sr 03 N a . t
s a a> a 83
@3 x WOIE CREEK MUCLEAR OPERA 11NG CORPORATION
_3 C)g- EXPOSURE PADIWAY - INCEST 10N r
** "U S $. MILK B6 go (PCI/ LITER) o.
gO STADON NUMBER S-3 ;
$.m O 3 a 5.
o a DATE COLLEC1ED: 09/07 09/21 10/12 10/26 11/09 RADIOCilEMICAL ANALYSIS: E I-131 LT. 2. E-0I LT.3. E-01~ LT. 3. E-OI LT.7. ~ E-01 LT. 2. ' E-01 t o GAMMA SPECIRUM ANALYSIS: e ' B e BE.7 LT. 4. E 01 LT.3. E 01 LT.4. E 01 LT.4. E 01 LT.4. E 01 S K-40 1.3610.14 E 03 1.3210.13 E 93 1.4210.14 E 03 1.54 0.15 E 03 1.3710.14 E 03 [ MN-54 LT.4. E 00 LT.4. E 00 LT.3. E 00 LT.4. E 00 LT. 5. E 00
-3 CO-58 LT.4. E 00 _ LT. 4. E 00 ' LT. 4. E 00 LT.4. E 00 LT.5. E 00 A FE.59 LT. 9. E 00 LT.9. E 00 LT. 1. E 01 LT. 9. E 00 LT. 1. E 01 CO-60 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT. 5. E 00 ZN-65 LT. 1. E 01 LT. 1. E 01 LT.9. E 00 LT.9. E 00 LT. 1. E 01 l
NB-95/ZR-95 LT. 4. E 00 LT.4. E 00 - LT.4. E 00 LT.4. E 00 LT.5. E 00 RU.103 LT.4. E 00 LT. 4. E 00 LT.4. E 00 LT.4. E 00 LT.5. E 00 RU- 106 LT. 3. E 01 LT. 3. E 01 LT. 3. . E 01 LT.3. E 01 LT. 4. E 01 1-131 LT.8. E 00 - LT.7. E 00 ~ LT. 1. E 01 LT.9. E 00 LT.8. E 00 CS.134 LT. 4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00. LT.5. E 00 CS.137 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT. 5. E 00 1A.140/BA-140 LT.6. E 00 LT.6. E 00 . LT. 7. E 00 LT.6. E 00 LT.6. E 00 I y CE.14 I LT. 6. ' E 00 LT.6. E 00 LT.7. E 00 LT.8. E 00 LT.8. E 00 gC CE.144 LT.2. E 01 LT.2. E 01 LT.2. E 01 LT.3. ~ E 01 LT.3. E 01 ;
]A RA-226 LT. 7. E 01 ' LT.7. E 01 LT.7. E 01 LT. 9. E 01 LT.9. E 01 ,
&o* Til-228 LT. 7. E 00 LT. 7. E 00 LT.7. E 00 LT. 7. E 00 LT. 8. E 00 sr co ~
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S wogE CREEK NUCl2AR OPERATING CORPORATION x"c EXI'OSURE PKnIWAY - INCES~nON C) x-a S$ MILK B5 g g- (PCl/ LITER) eh gj iir - STATION NUMBER S-3 5 a s. 8 DATE COLLECIED- 11/23 12/07 3 RADIOCIIEMICAL ANALYSIS: iii I-131 LT. 3. E-0! LT.2. E-01 CAMMA SPECIRUM ANALYSIS: h.
- h. BE-7 LT.4. E 01 LT.3. E 01 r8 K-40 1.3910.14 E 03 1.4110.14 E 03 g MN-54 LT.4. E 00 LT.3. E 00
'g CO-58 LT.5. E 00 LT.3. E 00 A FE-59 LT. 1. E 01 LT.7. E 00 CO-60 LT.4. E 00 LT.3. E 00 ZN-65 LT. 1. E 01 LT.7. E 00 NB-95/ZR-95 LT.5. . E 00 LT.3. E 00 RU-103 LT. 5. E 00 LT.3. E 00 RU.106 LT.4. E 01 LT.3. . E 01 1-131 LT. 1. E 01 LT.5. E 00 CS-134 -
LT. 5. E 00 LT.3. E 00 CS-137 LT.5. E 00 LT.4. E 00 LA-140/BA-140 LT.6. E 00 LT. 5. E 00 7 CE-141 LT.8. E 00 LT. 6. E 00 De CE-144 ' LT.3. E 01 LT.3. E 01
$ RA-226 LT.9. E 01 LT.7. E 01 g[ TH-228 LT.8. E 00 LT.6 E 00 wa ms
_ - - _ _ _ - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - _ _ . . . - . - _ _ _ _ _ _ _ _ ~
+
+
h$ M8- , Oy B3 a3 WOLF CREEK NUCLEAR OPERATING CORPORATION . hE_ ax EXPOSURE PAT 11WAY - AQUAT1C 3 m tD k B 5' SEDIMENT / SILT
- c. o- '
5h en e (pCiKiM DRY) k hk5 STATION NUMBER DC 5' 3 3 k. 8 DKIE COLLECTED: 06/29 09/28 i l_ii CAMMA SPECIRUM ANALYSIS: 7 O . BE-7 E-01 LT.4. E-01 3 LT. 5. B K-40 1.4110.14 E 01 1.2010.12 E 01 E MN-54 LT.6. E-02 5.6813.25 E-02 m CO-58 LT.5. E-02 LT. 5. E-02
$ FE-59 LT. 1. E-01 LT. 1. E-01
$ CO-60 1.1810.12 E 00 1.0810.11 E 00 !
ZN-65 . LT. 1. E-01 LT. 1. E-O! NB-95/ZR-95 LT. 6. E-02 LT. 5. E-02 RU-103 LT.7. E.02 LT.5. E-02 RU-lO6 LT.4. E 01 LT.4. E.01 , I-131 LT.2. E-01 LT.2. E-01 CS-134 2.7110.57 E-01 3.2210.46 E-01 , CS-137 8.9310.89 E-01 6.4710.65 E-01 : IA-140/BA- 140 LT. 1. E-01 LT. 1. E-01 , CE.141 LT. 1. E-01 LT.8. E-02 CE-144 LT. 3. . E-01 LT.3. E.01 , y
- yg RA-226 3.2920.83 E 00 2.1210.59 E 00 V
- Tii-228 1.3310.13 E 00 1.2410.12 E 00 !
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S xC WOLF CREEK NUCLEAR OPERATING CORPORATION g 98 EXPOSUREPAT1tWAY- AQUATIC t* 2)
$. SEDIMENT / SILT Q 5.,
*8 5'
g' (gCi/GM DRY) STATION NUMBER DC-1
.J
(. 8 DATE COLLECIED: 05/25 E GAMMA SPEC 111UM ANALYSIS: O E-01 3 BE-7 LT.4. k K-4 0 1.2810.13 E 01 LT.5. E-02 S MN-54 21 CO-58 LT. 5. E-02
$ FE-59 LT. 1. E-01 S CO-60 1.3710.14 E 00 ZN-65 LT. 1. E-01 ND-95/ZR-95 LT. 5. E-02 RU- 103 LT. S. E-02 RU-106 LT.4. E-OI l-131 LT.9. E-02 CS-134 1.8510.50 E-OI CS-137 7.2610.73 E-01 LA-140/BA-140 LT.8. E-02 CE-141 LT.7. E-02 CE-144 LT.3. E-OI g
y$ RA-226 3.0410.70 E 00 1.2310.12 E 00
$ Til.228 a=
a2::
e a o S>3 M WOLF CREEK NUCLEAR OPERATING CORPORA ~I1ON hj EXPOSURE PATHWAY - AQUA *I1C . m. h $- SEDIMENT / SILT to (pCiSM DRY)
- w. .
$5 53 STATION NUMBER DC-2 3 Q.
8 g DATE COLLEC1ED 05/25 ' k CAMMA SPECTRUM ANALYSIS: O g BE-7 LT.4. E-01
@ K-40 4.2510.50 E 00 E MN-54 LT.4. E-02 7 CO-58 LT. 5. E-02 (D FE-59 LT.9. E-02 j CO-60 4.7410.54 E-01 ZN-65 LT. 8. E-02 NB-95/ZR-95 LT. 5. E-02 i RU-103 LT.4. E-02 l RU- 106 LT. 4. E-01 I I
I-131 LT. 9. E-02 CS-134 LT. 6. E-02 ~ CS-137 4.0810.47 E 01 , I LA-140/BA-140 LT. 8. E-02' CE-141 LT.9. E-02 CE-144 LT.3. E-01 i' RA-226 1.7710.75 E 00 o Til-228 6.1110.61 E-01 ywe a CL O E'] ms s
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k5 x5 WOLF CREEK NUCLEAR OPERATING CORPORA 110N h~ s tu g EXPOSUREPATilWAY- AQUA 11C yoB SEDIMENT / SILT c?- o~ iS 9. (pCWM DRY) i vs8
$M co STA110N NUMBER DC-3 ,
3 f. 8 g DATE COLLECIED 05/25 I GAMMA SPECTRUM ANALYSIS: h- ! O 4.5412.39 E-01 g BE-7 t B K-4 0 4.8710.49 E 00
$ MN-54 7.6812.80 E-02 CO-58 3.2410.39 E-01 g FE-59 LT.8. E-02 g CO-60 7.9310.79 E O1 ZN-65 LT.7. E-02 NB-95/ZR-95 LT.4. E-02 RU-103 LT.4. E-02 RU-106 LT.3. E.01 j 1-131 LT. 7. E-02 1 CS-134 1.3910.30 E O1 CS-137 2.2210.36 E-01 LA-140/BA-140 LT.5. E-02 CE-141 LT.5. E-02 CE-144 LT.2. E-Ol i
8 RA-226 1.6610.45 E 00 NS Til-228 5.8610.59 E.OI 38 ea w ::
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$ 05/25 "g DATE COLLECTED:
GAMMA SPECIRUM ANALYSIS:
- h. .
LT.4. E-01 h BE-7 1.3210.13 E 01 S K 40 E-02 LT.6. g MN-54 LT.5. E-02 e CO-58
]A FE-59 LT. 1. E-01 CO-60 1.4310.14 E 00 i
LT. 1. E-01 ZN 65 NB,95/ZR 95 LT.6. E-02 LT.5. E-02 RU.103 LT.4. E-01 RU-106 LT. 1. E-01 t l-131 CS-134 3.6110 f4 E-01 CS- 137 9.4210.94 E-01 LT.9. E-02 IA 140/ IIA-140 LT.7. E-02 m CE-141 E-01
>$ CE- 144 LT.3.
2.1510.70 E 00 h RA-226 1.4310.14 E 00
' g[ Til-228 ,
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#5 WOlX CREEK NUCLEAR OPERATING CORPORATION EXi'OSURE l'AlllWAY - AQUA' llc h]
am 4 9- SEDIMENT / SILT R 9- (pCl/GM DRY) 5j (O
@ g-WL STAT 10N NUMBER DC-5 gm O 3 "3
h.
@ DA'IE COLLECTED: 05/25 CAMMA SPECTRUM ANALYSIS:
o ET- DE 7 LT.4. E-01 K-40 1.3110.13 E 01 MN-54 LT.6. E-02 h
$ CO-58 LT. 5. E-02
- FE-59 LT. 1. E-01 g CO 60 2.3410.23 E 00 E-01 g ZN-65 LT. 1.
NB-95/ZR 95 LT.5. E-02 RU-103 LT.5. E-02 RU-106 LT.4. E-01 1-131 LT.9. E-02 CS-134 2.9310.49 E 01 CS-137 8.4010.84 E-01 LA.140/BA.140 LT.7. E-02 CE-141 LT.7. E-02 CE- 144 LT.3. E-01 RA-226 2.5310.68 E 00 Til-228 1.5310.15 E 00
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h@S X C) - WOIE CREEK NUCI2AR OPEstA11NG CORPORATION EXi'OSURE PAT 11WAY - AQUATIC l wI 5*a SEDIMENT SILT B 6' y g- (pct /GM DRY) oh(n STATION NUMBER UllS E5 O 3 oS O DKIE COLIECIED- 07/01 a h GAMMA SPECIRUM ANALYSIS: 2 a t
"- BE-7 LT.4. E-01 O K-40 1.3710.14 E 01 o
$ MN-54 LT. 4. E-02
- h. CO-58 LT. 4. E-02 O FE-59 LT.9. E-02
[ CO-60 LT. 5. E-02
'8 ZN-65 LT. 1. E-01 3 LT.5. E-02 NB-95/ZR-95 RU-103 LT.5. E-02 RU- 106 LT. 3. E-01 I-131 LT. 1. E-Ol ,
CS-134 LT. 5. E-02 l CS-137 3.6810.48 E-01 LA-140/BA-140 LT.7. E-02 i CE-141 LT.8. .E-02 CE-144 LT.3. E-OI RA-22G 2.4910.60 E 00 ; Til-228 1.3110.13 E 00
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@] EXPOSURE PA'n!WAY - AQUATIC k $. SEDIMENT SILT E 9- (pCl/GM DRY) o:sS
$Q k STATION NUMBER JRR am O 3 s ;;.
8 DATE COI1EclED: 07/02 II/09 GAMMA SPECI' RUM ANALYSIS: a Si E-OI E-01 g BE-7 LT.4. LT.4. 1.0910.11 E 01 m K-40 1.7110.17 E 01 h MN-54 LT.4. E-O'2 LT.4. E-02 s CO-58 LT. 3. E-02 LT.3. E-02 FE-59 LT. 9. E-02 LT. 9. E-02 g CO 60 LT.3. E-02 LT.4. E-02 g ZN-65 LT.9. E-02 LT.9. E-02 NB-95/ZR-95 LT. 4. E-02 LT. 5. E-02 RU- 103 LT. 4. E-02 LT. 4. E 02 RU-lO6 LT.3. E-01 LT. 3. E-01 1-131 LT. 1. E-01 LT. 1. E-01 CS-134 LT. 5. E-02 LT.4. E-02 CS- 137 2.2510.38 E-Ol 2.1610.30 E-01 LA-140/BA-140 LT.8. E-02 LT. 6. E-02 CE-141 LT.6. E-02 LT. 7. E-02 CE-144 LT. 2. E-01 LT. 2. E.OI RA-226 2.4210.54 E 00 1.5910.54 E 00 8 Til-228 1.3910.14 E 00 1.1010.1I E 00
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- Duplicate Analysis
=
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#5 WOI.Ir CREEK NUCLEAR OPERAT1NC CORPORATION h%
=.
EXPOSURE PA11tWAY- AQUA'IIC
!* 9: SIIOREl.INE SOIL to,8-5~ (pCl/CM DRY)
' CD STA110N NUMBER DC I3 5' f.
Q DATE COLlE~N: 04/20 09/28 3 m GAMMA SPECIRUM ANALYSIS: a lii BE-7 LT. 5. E-01 LT. 3. E-Ol { g K 40 9.7710.98 E 00 7.5010.75 E 00 g MN-54 LT.4. E-02 LT.2. E-02
$ CO-58 LT. 5- E-02 LT. 3. E-02
' FE-59 LT. 1. E-01 LT. 6. E-02 g CO-60 9.2813.47 E-02 LT. 3. E-02 ZN-65 LT.9. E-02 . E-02 3 LT. 5. i NB-95/ZR-95 LT. 5. E-02 LT. 3. E-02 RU-103 LT. 6. E-02 LT. 3. E-02 RU-106 LT.4. E-01 LT.2. E-01 I-131 LT.3. E-01 LT. 1. E-01 CS-134 LT.6. E-02 LT.4. E-02 CS-137 1.7410.40 E-01 7.3112.51 E-02 IA-140/BA-140 LT.2. E-01 LT. 6. E-02 CE-141 LT. 1. E-01 LT. 5. E-02 CE-144 LT.4. E-01 LT.2. E-01 RA-226 1.9110.68 E 00 7.3813.41 E-01 g8 TII-228 1.091011 E 00 6.9010.69 E-01
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- Duplicate Analysis
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ts b 7@ WOIE CREEK MUC12AR OPERATING CORPORATION O- EXIMURE PA111WAY - AQUA 11C o 23 S 0$. SIIORELINE SOIL a a-gg (pCl/CM DRY) oh (n STA110N NUMBER JRR
!! Ei 53 3 $.
g DATE COLLECTED: 04/20 11/09 11/09* CAMMA SPEC 111UM ANALYSIS: BE-7 LT.4. E-01 LT. 3. E-01 LT.4. E-01 h K-40 1.0810.11 E 01 E-02 8.7710.88 E 00 E-02 8.7010.87 E 00 y MN-54 LT.3. LT.3. LT.4. E.02 g CO-58 LT. 3. E-02 LT. 3. E-02 LT.4. E-02 C FE-59 LT. 8. E-02 LT.6. E-02 LT. 1. E-01 k CO-60 LT.3. E-02 LT. 3. E-02 LT.3. E-02 3 ZN-65 LT.7. E-02 LT.7. E-02 LT.9. E-02 NB 95/ZR-95 LT.4. E-02 LT.4. E-02 LT. S- E-02 RU- 103 LT.4. E-02 LT.4. E-02 LT.5. E-02 RU- 106 LT.3. E-01 LT.3. E-01 LT.3. E-01 1-131 LT.2. E-01 LT.9. E-02 LT.3. E-01 CS- 134 LT. 5. E-02 LT.4. E-02 LT.5. E-02 CS-137 LT.4. E-02 1.0810.29 E-01 1.3910.35 E-01 IA- 140/BA- 140 LT. 1. E-Ol LT. 7. E-02 LT. 1. E-01 CE-141 LT. 8. E-02 LT. 6. E-02 LT.9. E-02 CE- 144 LT.2. E-Ol LT. 2- E-01 LT.2. E-01 RA-226 2.3210.58 E 00 1.5510.47 E 00 2.3610.58 E 00 Til.228 1.7110.17 E 00 1.0110.10 E 00 1.1610.12 E 00 - %a u o, h 0) m ::
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O> - H pt- C 0 WOLF CREEK NUC1 EAR OPERA 11NG CORPORATION g8 EXPOSURE l'AT1tWAY - TERRESTRIAL { tv % 3 as 11 9 : SOIL
% 9-J 8, - (pC1/CM DRY) @k Rm STA110N NUMBER A-1 53 3
f. O DATE Coll.ECIED 06/I5 3
$ CAMMA SPECTRUM ANALYSIS:
E_ BE-7 5.5212.41 E-01 o 8.9510.90 E 00 3 K-40 E-02 0 e MN.54 LT.3. j CO-58 LT.3. E-02 FE-59 LT.8. E-02 n CO-60 LT.4. E-02 ZN-65 LT.7. E-02 a NB-95/ZR-95 LT.4. E-02 RU-103 LT.4. E-02 RU- 106 LT. 3. E-01 I 131 LT.7. E-02 CS-134 LT.4. E-02 CS-137 9.4913.25 E-02 1A-140/BA- 140 LT. G. E-02 CE-141 LT.6. E-02 CE-144 LT. 2. E-01 RA-226 1.6410.48 E 00 y yj Til-228 7.9710.80 E-0I v. QO YG m~
o a o> 83
!) 5E Wol.tr CREEK NUCMAR OPERAT1NG CORPORATION O EXPOSURE PA111WAY - AQUATIC ty y VEGETATION - AQUKnC hh~
ct. O g8 9. (pct /CM WE'll STK110N NUMBER DC g5'. h aQ 09/28 O DATE COllECIED 06/29 06/29 A14AE ROUIED AQUA 11CS l'OND WEED ROO1ED g k GAMMA SPEC 111UM ANALYSIS: O 6.1910.62 E-01 8.8113.79 E-02 3.0110.43 E-01 TJ BE.7 1.3010.I3 E 00 1.9110.19 E 00 2.6010.26 E 00 h K-40 6.7810.68 E-02 LT.6. E-03 LT. 5. E-03
$ MN 54 6.4710.65 E-02 LT. 6. E-03 CO-58 9.1810.92 E-01 2.8611.00 E-02 ' LT. 1. E-02 LT 1. E-02 g FE-59 LT.7. E-03 g CO-60 6.5810.66 E-01 2,6110.53 E-02 LT.2. E-02 LT. 1. E-02 LT. 1. E-02 ZN.65 6.3210.91 E-02 LT. 6. E-03 LT. 6. E-03 NB-95/ZR-95 1.2210.53 E-02 LT.6. E-03 LT. 6. E-03 '
RU-103 1.5310.48 E-02 LT.5. E-02 LT.4. E-02 RU-106 E-02 LT. 1. E-02 LT.2. E-02 l-131 LT. 1. 7.3910.74 E-02 LT.6. E.03 LT.6. E-03 CS-134 1.0610.11 E-01 LT. 6. E-03 7.2813.72 E-03 CS-137 LT. 8. E-03 LT. 8. E-03 LT.9. E-03 LA 140/BA-140 LT. 1. E-02 LT.9. E.03 LT.9. E-03 CE-141 LT.4. E-02 LT.4. E-02' LT.3. E-02 CE.144 1.6310.80 E-01 1.6210.67 E-01 2 RA 226 3.4410.90 E-01 E-02 LT.9. E-03 d$ Tll.228 1.8110.18 E-01 2.3510.45 E-01 LT. 1. 3m a 08 CR 51 SB-125 4.5911.38 E-02 9 O, N B-95 1.2110.12 E-01 d
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53 m! x WOlJ CREEK NUCLEAR OPERAT1NG CORPORATION {g -- EXPOSURE PK111WAY - WATERBORNE 5$ DRINKING WKIER B 6' i' Q (PCI/ LITER) ok(n STA110N NUMBER LW40 E in 53 i 3 k O DATE COLLECIED 06/01-07/06 06/01 07/06* 07/0G-08/03 08/03-08/31 08/31-10/05 y RADIOCllEMICAL ANALYSIS: m 3 GR-B 6.7 1 2.2 E 00 1.210.3 ' E 01 6.0 i 1.3 E 00 5.3 i 1.4 E 00 1.3 1 0.4 E 01 -t E I-131 LT. 5. E-01 LT.6. E-01 LT. 4. E.01 LT. 4. E-01 LT.8. E-01 o GAMMA SPECTRUM ANALYSIS: g
~
B g BE-7 LT. 1 E 01 LT 3. E O1 LT. 4. E OI LT.4. E 01 LT.3. E 01 o K.40 LT.5. E 01 LT. 7. E 01 LT. 1. E O2 LT. 6. E 01 LT.6. E 01 [ MN-54 LT. 3. E 00 LT.3. E 00 LT. 4. E 00 LT.4. E 00 LT.3. E 00 -l '
'8 CO-58 LT.3. E 00 LT. 3. E 00 LT.4. E 00 LT.3. E 00 LT.3. E 00
# FE.59 LT. 6. E 00 LT. 7. E 00 LT.9. E 00 - LT. 7. E 00 LT.6. E 00 CO 60 LT.3. . E 00 ~
LT.3. E 00 LT. 4. E 00 LT.4. E 00 LT.4. E 00 ZN.65 LT.6. _ E 00 - LT. 7. E 00 LT. 9.' E 00 LT.8. E 00 LT. 7.' E 00 NB-95/ZR-95 LT.1 E 00 LT.3. E 00 LT.4. E 00 LT.4. E 00 - LT. 3. E 00 RU-103 LT.3. E 00 LT.4. E 00 LT. 5. E 00 LT.4. E 00 LT.4. E 00 , l RU.106 LT. 3. E 01 LT. 3. E 01 LT. 4. E 01 LT.3. E 01 LT. - 3. E 01 1-131 LT.6. E 00 LT,6. E 00 LT.8. E 00 LT. 6. E 00 LT.7. E 00 CS.134 LT. 1 E 00 LT.1 E 00 LT.5. E 00 LT.4. E 00 LT. 3. E 00 CS-137 LT. 4. E 00 LT. 3.- E 00 - LT. 5. E 00 LT.4. E 00 LT.4. E 00 1A-140/BA-140 LT.5 E 00 LT.4. E 00 - LT. 6. E 00 LT. 5. E 00 LT. 6. E 00 [ CE-141 LT. 6. E 00 LT. 5. E 00 LT,8. E 00 LT.9. E 00 LT. 7. E 00 d$ CE.144 LT.2. E 01 LT. 2. E 01 LT.3. E OI LT.4. E 01 - .LT.1 E O1 j (n RA-226 LT.7. E 01 LT.6. E 00 LT. 8. E 01 LT. 1. E 02 LT.8. E OI
$. $ T11-228 LT.6. E 00 LT. 5. E 00 LT. 7. E 00 LT.9. E 00 . LT. 6. E 00 2
my TRrnUM ANALYSIS: 04/06-07/06 11 3 LT. 6. E 02
*Dupilmte Analysts
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!! B "E WOlE CREEK NUCLEAR OPERATING CORPORATION o 'D ta EXIDSURE PAlllWAY WATERDORNE S$
B 6' DRINKING WATER g-- (PCI/ LITER) mh STN110N NUMilER LW40 3 ,S. O 11/30 1I/30 01/04 DATE COLLEC1ED: 10/05-1I/02 g
$ RADIOClIEMICAL ANALYSIS:
6i 7.4 i 1.5 E 00 6.7 i 1.5 E 00 G R-H 2.3 i 1.3 E 00 E.01 LT.2. E-01 f LT.2. E.01 LT.2. y 1-131 m GAMMA SPECI11UM ANALYSIS: h LT.4. E OI LT.4. E O1 LT.3. E O1 BE-7 LT.8. E OI f.T. 6. E 01 LT. 5. E O1 K 40 J MN-54 LT.4. E 00 LT. 3. E 00 LT.4. E 00 3 LT. 3. E 00 LT.4. E 00 LT.4. E 00 CO-58 E 00 LT.9. E 00 LT. 8. E 00 LT.7. FE-59 E 00 LT.5. E 00 LT.4. E 00 LT.3. CO-GO LT.8. E 00 LT. 8. E 00 LT.8. E 00 ZN-65 E 00 LT.4. E 00 LT.4. E 00 LT.4. NB-95/ZR-95 E 00 LT. 5. E 00 LT. 5. E 00 LT.4. RU-103 E 01 LT.4. E 01 LT.3. E 01 LT.3. RU- 106 E 00 LT.9. E 00 LT. 9. E 00 LT.7. 1-131 E 00 LT. 5. E 00 LT.4. E 00 LT.3. CS.134 E 00 LT. 5. E 00 LT.4. E 00 LT.4. CS-137 E 00 LT.7. E 00 LT.7. E 00 LT. 5. LA-140/BA-140 E 00 LT. 1. E O1 LT.8. E 00 LT.7. u CE-14 I E 01 LT.4. E 01 LT.3. E 01 LT.3.
$ CE- 144 LT.9. E 01 LT.8. E 01 LT. 1. E 02 RA-226 g0, LT.7. E 00 LT.7. E 00 LT. 1. E 01 my Til.228 07/06 10/05 10/05-01/04 TRTI1UM ANALYSIS:
LT.4. E O2 LT.4. E 02 11 3
! , !i! , , e' . y l I h t , &
n t o I 1 1 0 0 0 0 0 00 0 - 0 0 0 0 0 0 0 0 01 0 1 0 01 0 1 1 0 0 000 00 0 0 2 0 E EEEEEEEEEEEEEEEEEE E 6 1 2 4. 634 8. 4 7. 4 5 324. 4. 1. .827 . . . 6 4
/
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1 2 35 3 3 8 4 6 3 4 31 3 3 8. 8 377. 4
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1 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T T,T. T. T. T. 1 L LLLLLLLLLLLLLLLLLL L 1 1 2 0 0 1 01 0 01 1 00 0 1 1 21 2 0- 0 0 0 0 0 0 0 0 0 0 0 00 0 0 000 0 E EEEEEEEEEEEEEEEEEE E 7 1 2 51 5 5. 1. 5 1 6 751 66. 91. 52
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8 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. 0 L LLLLLLLLLLLLLLLLLL L N O 1 1 1 00 0 00 0 01 0 000 01 1 0 2 I T 0- 00 0 0 0000 0 0 0 0 0 00 0 0 0 0 A E EEEEEEEEEEEEEEEEES E RE ON PR * . RO 8 3 3 64. 4. 74 7. 4 4 37 4. 4. 67. 38. 8 2 OB I CR 0 1
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5 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. GE 0 L LLLLLLLLLLLLLLLLLL L NT 1A R C TW E A T A R
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E R R- E B EY PA W 1 M 1 D L U 1 OW Rt N /I N 0- 1 1 00 0 0 0 0 0 1 00 00 01 1 0 0 0 000 0 00 0 0 0 0 0 0 00 0 0 2 0 1 U C E AT EA OR P N O( EEEEEEEEEEEEEEEEEE E I P I CE G T . . . . . . . . . . . . . . . . . UR A 8 3 363363 6313 4 3 34 7397 2 T 1 NU S / T. T. T. T. T,T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. KS 5 0 L LLLLLLLLLLLLLLLLLL L - EO' Ei RX _ CE _ X l
' . O 1 1 20 01 01 0 01 1 00 001 1 0 2 0- 0O 0 0 0 0 0 0 0 0 0 000 0 00 0 0 W
, E EEEEEEEEEEEEEEEEEE E 3
2 3 5 . 55 1. 5. 1. . 56 1 4 1 5599398 1
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2 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. 0 L LLLLLLLLLLLLLLLLLL L S: I
- S S
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- A I s D L U S t s
E A l H 0 Y ly I L a C C I C 5 4 A n E M E 9 1 N A L E P - A A L l S R B t e O i Z M a C CO A / 3 6 / 4 7 0 1 4 6 8 c M 4 U 7 0 -5 5 8-56-90 5 5 0 0 3 3 4 14 14 22 2 2 i E I 1 3 M 6 91 1 1 3 1 1 1 1 1 lp T D 4 - - - - - - - - - - I 3- u A A D R 1 1 A G E - NOEONBUU1 CCI BKMCFCZNRR1 SSAEEAi CCRT l R T I I D
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l 1 1 00 000 001 1 0 0 00 1 1 0 2 _ O- 0 000 0 0 00 0 0000 000 00 O _ E EEEEEEEEEEEEEEEEEE E _ 6 1 2 373373 734 31 33762 66. 4
/
1 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. 1 L LLLLLLLLLLLLLLLLLL L _ N _ O 1 1 1 0 00000 01 0 0000 1 1 0 2 I T 0 0 00 00 00 00 000000000 0 . A _ RE E EEEEEEEEEEEEEEEEEE E _ ON PR R . _ 35 3. .3635 OBO 7 1 1 3 33734. 56276. 2 _ CR 9 / ~ 4- 8 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. GE 0 L LLLLLLLLLLLLLLLLLL L Nl IA R C _ TW E R A I K R) E R-EY PA W ET BM I OW DN L/ U N 1 1 0 1 1 0000 0 00 1 00 000 1 1 000 0 0 00 00000 0 000 0 0 0 2 O Rll U CP EEEEEEEEEEEEEEEEEE AI O N E E EPK R ( O l I CE C T . . . . . . . . . . . . . . . . . . . . A 8 1 383373 7333434 55 276 2 UR T 1 MU S / 5 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. KS 0 L LLLLLLLLLLLLLLLLLL L EO _ EP RX _ CE . X I _ O 1 0-1 1 0000 00 01 1 00001 1 0 2 _ n W 0 00 0 000 0 00 000 0 0 0 00 0 _ E EEEEEEEEEEEEEEEEEE E 3 2 4 94 4 84 84 531 4 477276 1 2
/
2 T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. T. 0 L LLLLLLLLLLLLLLLLLL L S I
- S S
I Y S L Y A L N A A N M S A I D U S E AL I R T 0 Y L C C I C 5 4 A E M E 9 1
- N 1 E P -
A A I I S R B O I A Z / M C CO / 3 6 70 I 4 6 8 0 1 4 U 4 E I 1 M 7 0 - 5 58 59 60 655 9- 0 1 1 3 3 14 14 14 22 2 2 I T D 3 MA - - - - 3 1 1
- - - - - T 3 E 4 N CZNRR1 OEONBUU1CCI SSAEEAi I
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$ >5CEW$5 . T58 hao X gn5g c N$- 2 U$hyaN r
'> gsG
t i e a 4 9> < 88 x Wolf CREEK NUCLEAR OPERATING CORPORATION EXIOSURE PA~nIWAY . WATERDORNE C)@1 e2 i
'S $ GROUND WATER B 5' y g- . (PCI/ LITER) u2 g3O STNDON NUMBER D-65 si
&T
= s.
DKIE COLI.ECTED 02/23 05/18 08/17 11/16 h RADIOCllEMICAL ANALYSIS: h_ I-131 LT.3. E-01 LT.2. E-01 LT. 1. E-01 LT.2. E-0I h GAMMA SPECTRUM ANALYSIS: e . t
$. BE.7 LT.4. E 01 LT.2. . E 01 LT.3. E 01 LT.4. E 01 S K-4 0 LT. 5. E 01 LT.5. E 01 LT.9. E 01 LT.6. E 01
[ MN-54 LT 4. E 00 LT.2. E 00 LT. 3. E 00 LT. 3. E 00 ; 33 CO-58 LT.4. E 00 LT.3. - E 00 LT.4. E 00 LT.3. E 00 FE-59 LT. 1. E 01 LT. 5. E 00 LT.7. E 00 LT.8. E 00 CO-60 LT. 4. E 00 LT.3. E 00 LT.4. E 00 LT.4. E 00 ZN-65 LT.9. E 00 LT. 6. E 00 LT.7. E 00 LT. 8. E 00 NB.95/ZR.95 LT. 4. E 00 LT.3. E 00 - LT. 4. E 00 LT.4. E 00 RU.103 LT. 5. E 00 LT. 3. E 00 LT.4. E 00 LT. 5. E 00 RU 106 LT. - 4. E 01 LT.3. E 01 LT. 3. E 01 LT.3. E 01 I.131 LT. 1. E 01 LT.4. E 00 LT. 8. E 00 LT.2. E 01 CS.134 LT.4. E 00 LT.3. E 00 LT.3. E 00 LT.3. E 00 CS-137 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT 4. E 00 ! 1A.140/BA-140 LT. 8. . E 00 LT. 4. - . E 00 .LT 6. E 00 LT. 1. E 01 "U CE.141 LT.9. ' E 00 LT. 5. E 00 LT. 6. E 00 LT.9. E 00
">$ CE.144 LT.3. - E 01 LT.2. E 01 LT. 2. E 01 LT. 3. E 01
. $ RA-226 LT.9. E 01 LT.6. E 01 LT. 7. E 01 LT. 8. E 01
- g[ Til-228 LT. 8. E 00 LT. 5. 1 E 00 LT.7. E 00 LT. 7. E 00 E'Q GN i
TRrnUM ANALYSIS: 11 3 LT. 1. E 02 LT.2. E 02 LT.2. E 02 LT.4. E O2 i 4
. t
~
2 a o> h5 WOfX Camar NUC12AR OPE 5tATING CORPORATION h, t m b_._ EXPOSURE PKIHWAY - WATERBORNE 3 as h g" SURFACE WATER i8 (PCI/IIIER)
$- STATION NUMBER MUSil am O 3 a Q.
., O DNIE COLLECIED: 01/19 02/25 03/16 04/20 05/18 3
@ GAMMA SPECTRUM ANALYSIS:
Ei E 01 LT.3. E 01 LT.3. E 01 LT. 4. E 01 LT.3. E 01 6 BE.7 LT.3. E 01 LT. 5. E 01 LT.6. E 01 LT.8. E 01 3 K-4 0 LT. 6. LT.3. E 00 LT. 6. . E 01 LT. 3. E 00 LT. 3. E 00 ' LT. 4. E 00 LT.3. E 00
@ MN 54 LT.3. E 00 LT. 3. E 00 LT. 3. E 00 LT. 4. E 00 LT.3. E 00
[ CO-58 FE-59 LT.7. E 00 LT.8. E 00 LT.6. E 00 LT.9. E 00 LT.6 E 00 m CO-60 - LT. 4. E 00 LT.3. E 00 LT.4. E 00 LT.4. E 00 LT.3. E 00 ZN-65 LT. 7. E 00 LT.7. E 00 LT.7. E 00 LT. 8. E 00 LT.6. E 00 g LT.4. E 00 LT.3. E 00 LT.3. E 00 LT.4. E 00 LT.3. E 00 NB.95/ZR.95 RU 103 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT. 3. E 00 RU.106 LT.3. E 01 LT.3. E 01 LT.3. E 01 LT. 3. E 01 LT.3. E 01 1 131 LT.6. E 00 ' LT. 1. E 01 LT.6. E 00 LT. 7. ' E 00 LT.4. E 00 CS.134 LT. 3. E 00 LT. 3. E 00 LT.3. E 00 LT.4. E 00 LT. 3. E 00 CS.137 LT.5. E 00 LT. 5. - E 00 LT.5. E 00 LT.4. E 00 LT.3. E 00 LT.5. E 00 . LT. 7. E 00 LT.5. E 00 LT.6. E 00 LT.4. E 00 IA-140/BA-140 CE.14 I LT. 6. E 00 LT. 7. E 00 LT.6. E 00 LT.8. E 00 LT.4. E 00 CE.144 LT.2. E 01 LT. 2.- E 01 LT.2. E 01 LT.3. E 01 LT.2. E 01 RA-226 LT.7. E 01 LT. 7. E 01 LT.7. E 01 LT.9. E 01 LT. 6. E 01 LT. 6. E 00 LT.6. E 00 LT. 6. E 00 LT. 7. E 00 LT. 6. E 00 Q uo Tii-228
$ TR111UM ANALYSIS:
aO W* gy LT. 6. E 02 LT. 1. E 02 LT.6. E 02 LT.4. E 02 LT. 6. E 02 11 3
'i 4 ,
4
) r
-a o>
's 3
*E WOIE CREEK MUCLEAR OPERATING CORPORA 110N EXFOSURE PA"DIWAY - WATERBORNE h.-
o
$ 9. SURFACE WATER R 9-ij ua -
(PCl/ LITER) r CD O_ STA110N NUMBER MUSil l Z' . s (. O DATE COLT.ECTED 06/15 07/20 08/17 09/21 10/19 h a GAMMA SPECIRUM ANALYSIS- I i
.EI- !
BE.7 LT.4. E 01 LT. 3. E 01 LT. 3. E 01 LT. 3. E O1 LT.3. E O1 K-40 LT.7. E 01 LT 5. E 01 LT. 6. E 01 LT. 6. E 01 LT. 5. E 01 I g MN.54 LT.4. E 00 LT.3. E 00 LT.3. E 00 LT.3. E 00 LT.3. E 00 CO-58 LT.4. E 00 LT. 3. . E 00 LT.3. E 00 LT. 3. E 00 LT.4. E 00 , FE-59 LT. 9. E 00 LT.6. E 00 LT. 7. E 00 LT.7. E 00 LT.8. E 00 k CO-60 LT. 5. E 00 LT. 3. E 00 LT. 3. E 00 LT.4. E 00 LT.4. E 00 E ZN-65 LT. 1. E 01 LT. 7. E 00 LT. 7. E 00 LT.7. E 00 LT.7. E 00 NB-95/ZR-95 LT. 5. E 00 LT. 3. E 00 LT.3. E 00 LT.3. E 00 LT.3. E 00 RU-103 LT. 5. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 RU-106 LT.4. E 01 LT. 3. - E 01 LT. 3. E OI LT.3. E 01 LT. 3. E 01 1 131 LT. 1. E 01 LT. 6. E 00 - LT.8. E 00 LT.7. E 00 LT. 1. E 01 CS-134 LT. 5. E 00 LT. 3. E 00 ' LT. 3. E 00 LT.4. E 00 LT.4. E 00 CS-137 LT.5. E 00 LT. 4. E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LA-140/BA-140 LT.7. E 00 LT.4. E 00 LT. 6. E 00 LT. 6. E 00 LT.9. E 00 CE.141 LT. 1. E 01 LT. 7. E 00 - LT. /. E 00 LT. 6. . E 00 LT. 7. E 00 CE-144 LT. 5. E 01 LT. 3. E 01 LT. 3. E 01 LT. 2. E 01 LT.2. E 01 RA-226 LT. 1. E 02 ' LT. 8. E 01 LT. 8. E 01 LT.7. E 01 LT. 7. E 01 Tli-228 LT. 1. E 01 LT. 7. E 00 . LT. 7. E 00 LT. 6. E 00 LT.6. E 00 4 V se 3y TR!11UM ANALYSIS: 5O EO 03 N H.3 LT. 6. E 02 LT.7. E O2 LT.7. E 02 LT.5. E 02 LT.4. E 02 ; 4
1 A s l l l ho a o> 6 5 xC WOlX CREEK NUCIZAR OPERATING CORPORATION Q"- se x EXPOSURE PA111WAY- WATERBORNE OE SURFACE WATER E5 gg (PCI/ LITER) sa(cn E STA110N NUMBER MUSII EE oS 82 DATE COLLECIED: 11/16 12/21 h GAMMA SPECTRUM ANALYSIS: a E-- BE-7 LT.3. E 01 LT.3. E OI ' O g.40 LT.5. E 01 LT. 6. E 01 MN 54 LT.3. E 00 - LT.3. E 00 E. CO-58 LT.3. E 00 LT.3. E 00 S FE-59 . LT. 7. E 00 . LT. 7. E 00 [ CO-60 LT.3. E 00 LT.3. E 00 , 3A ZN-65 LT.6. E 00 - LT.7. E 00 NB-95/ZR-95 LT.3. E 00 LT.4. E 00 RU-103 LT.4. E 00 LT.4. ' E 00 RU-106 LT. 3. E 01 LT.3. ' E 01 I-13I LT.2. E OI LT.8. - E 00 CS-134 LT.3. E 00 LT.3. E 00 l CS-137 LT.3. E 00 LT.4. E 00 IA-140/BA-140 LT.9. E 00 ' LT.8. E 00 CE-141 LT.8. E 00 LT.8. E 00 CE-144 LT.3. E 01 LT.3. E 01 RA-226 LT.7. E 01 LT. 1. - E 02 . TH-228 LT.6. E 00 LT.8. E 00
@'g 8 -] y TRTHUM ANALYSIS:
So
'EQ III N 11 3 LT.4. E O2 LT.3. E O2 ;
+
__ _ _ . - _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ , _ _ w - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _
(
)
I$ e8 O Pe >3
%SS wOtr CREEK NUCIE.AR OPERATING CORPORATION g EXIOSURE PA'IIIWAY - WKIERBORNE nm 3g SURFACE WATER 5.h o (PCI/ LITER)
*o gQ STATION NUMBER SP Em 5' 3 3 6.
8 DATE COLLECTED 01/19 02/23 03/16 04/20 05/18 a y CAMMA SPECTRUM ANALYSIS: BE.7 LT. 3. E 01 LT.4. E 01 LT. 3. E 01 LT. 4. E 01 LT. 3. E 01 O K-4 0 LT. 6. E 01 LT. 6. E 01 LT. 6. E 01 LT. 6. E 01 LT.9. E O!
$ MN.54 LT. 3. E 00 LT.4. E 00 LT.3. E 00 LT.4. E 00 LT. 3. E 00
% CO-58 LT.3. E 00 LT.4. E 00 LT.3. E 00 LT. 4. E 00 LT.4. E 00 S FE-59 LT.6. E 00 LT. 8. E 00 LT. 6. E 00 LT.8. E 00 LT. 7. E 00 g CO-60 LT.4. E 00 LT. 3. E 00 LT.3. E 00 LT.4. E 00 LT.4 E 00
]A ZN.65 LT. 7. E 00 LT. 7. E 00 LT. 7. E 00 LT. 8. E 00 LT. 8. E 00 ND-95/ZR-95 LT. 3. E 00 LT.4. E 00 LT. 3. E 00 LT. 4. E 00 LT. 4. E 00 RU- 103 LT. 4. E 00 LT. 4. E 00 LT.4. E 00 LT. 5. E 00 LT.4. E 00 RU- 106 LT.3. E 01 LT.3. E 01 LT. 3. E 01 LT.4. E 01 LT. 3. E 01 I-131 LT. 6. E 00 LT. 1. E 01 LT.6. E 00 LT. 8. E 00 LT. 6. E 00 CS-134 LT.4. E 00 LT. 3. E 00 LT.3. E 00 LT.4. E 00 LT.4. E 00 CS-137 LT. 5. E 00 LT.4. E 00 LT.4. E 00 LT. 4. E 00 LT. 4. E 00 LA.140/BA-140 LT. G. E 00 LT.8. E 00 LT. 5. E 00 LT. 7. E 00 LT. 6. E 00 CE.141 LT.6. E 00 LT.9. E 00 LT. 6. E 00 LT. 9. E 00 LT. 6. E 00 CE- 144 LT.2. E 01 LT.3. E 01 LT. 2. E 01 LT.4. E 01 LT. 2. E 01 RA-226 LT. 7. E 01 LT. 8. E 01 LT.7. E 01 LT.9. E 01 LT. 7. E 01 c Til-228 LT. 6. E 00 LT. 7. E 00 LT. 5. E 00 LT. 9. E 00 LT 6. E 00 M(
8" T!UT1UM ANALYSIS: h-* 11-3 6.4 1 0.5 E 03 7.0 1 0.2 E 03 8.4 1 0.6 E 03 8.9 i 0.5 E 03 7.410.6 E 03 cn d
L !
~
's o
a o R> 3 fc E o*- WOIX CREEK NUCLEAR OPERA 11NG CORPORATION EXIUSURE PADIWAY - WKIERDORNE tj g hh c1 o-SURFACE WATER S 9. (PCI/ LITER) in 8 STATION NUMBER SP gg 5' a m ,S. O 09/21 10/19 DATE COLLECTED- 06/15 07/20 08/17 y
$ GAMMA SPECIRUM ANALYSIS:
iii E 01 LT.4. E 01 LT.4. E 01 LT.3. E 01 LT.3. E 01 LT.3. O BE-7 E 01 E 01 LT. 1. E 02 E 01 LT.9. E 01 LT.6. LT. 6. A K.40 LT. 6. LT.3. E 00 LT.4. E 00 E 00 LT.3. E 00 LT.3. ~ E 00 h MN-54 LT.4. LT.5. E 00 LT. 3. E 00 LT.3. E 00 LT.3. E 00 LT.4. E 00 S OG.58 E 00 E 00 LT. 7. E 00 LT. 1. E 01
'O FE-59 LT. 1. E 01 LT. 7. LT.7.
E 00 E 00 LT.4. E 00 LT.4. E 00
$ CO-60 LT.5. E 00 LT.3. LT.3.
E 00 LT.6. E 00 LT. 8. E 00 S ZN-65 LT. 1. E 01 LT. 6. E 00 LT.7. LT. 5. E 00 LT.3. E 00 LT.3. E 00 LT. 3. E 00 LT.4. E 00 NB-95/ZR-95 E 00 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.5. E 00 RU-103 LT.5. ' LT.4. E 01 LT.3. E 01 LT.3. E 01 LT.3. E 01 LT. 3. E 01 RU. lO6 E 00 LT.7. E 00 LT.8. E 00 LT.7. E 00 LT.2. E 01 I.131 LT.8. E 00 LT.4. E 00 LT.3. E 00 LT. 3. E 00 LT.4. E 00 CS-134 LT.5. LT. 5. E 00 LT.4. E 00 LT. 4. E 00 LT.3. E 00 LT.4. E 00 CS-137 LT.6. E 00 LT. 6. E 00 LT.6. E 00 LT. 6. E 00 LT. 1. E 01 LA-140/BA.140 E 00 LT.8. E 00 LT. 7. E 00 LT.6. E 00 LT.7. E 00 LT. 9. CE-141 LT.3. E 01 LT.3. E 01 LT.2. E 01 LT.3. E 01 LT.3. E 01 CE-144 LT.8. E 01 LT.6. E 01 LT.7. E 01 LT. 8. E O1
- a RA-226 LT.8. E 01 E 00 E 00 E 00 LT. 7. E 00 mo
>$ TH.228 LT.8. E 00 LT.7. LT.6. LT. 6.
'3N ay TRIBUM ANALYSIS:
sr CD N a 7.5 i 0.6 E 03 6.0 1 0.6 E 03 5.6 i 0.6 E 03 6.5 i 0.5 E 03 7.1 1 0.4 E 03 11-3 1 i 1
- i. ;
I 6 l )
}
h* a O> 2E K WOIE CREEK NUC12AP. OPERATING CORPORATION '
@Eg EXi'OSURE PA111WAY - WNIERBORNE to $ SURFACE WA1ER B 5'~
$J (PCI/LTIER) um to h STA110N NUMBER SP
!i! m 5' 3 3 <
y DNIE COLLECTED- 11/16 12/21 h 3 CAMMA SPECTRUM ANALYSIS: ' EI- BE-7 LT.3. E 01 LT. 2. ' E 01 l h K-40 LT.8. E 01 LT. 5. E 01 MN 54 LT.3. E 00 LT. 2. - E 00 h E 00 , s CO-58 LT. 3. E 00 LT.3. LT.6. E 00 FE-59 LT.8. E 00 D LT.3. E 00 LT.3. E 00 e CO-60 E ZN-65 LT.7. E 00 LT.5. E 00 2 E 00 LT.3. E 00 NB-95/ZR-95 LT.4. RU-103 LT.4. E 00 LT. 3. - E 00 , 1 RU-106 LT.3. E 01 LT. 2. ' E 01 I-131 LT. 1. E 01 LT 6. E 00 CS-134 LT.3. E 00 LT.3. E 00 CS-137 LT.3. E 00 LT.4. E 00 ; IA-140/BA-140 LT.9. E 00 LT. 5. . E 00 CE-141 LT.7. E 00 LT. 6. E 00 4 CE-144 LT.2. . E 01 ' LT. 2. . E 01 RA-226 LT. 6. E 01 LT. 6. E 01 E 00 E 00
>e8 TH-228 LT.6. LT. 5.
'O te 3g 3
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(PCI/IJTER) o5' _.8 50 _O STATION NUMBER DC h9 a s. y DATE COLI.ECTED- 01/19 02/23 02/23* 03/16 04/20 i h a CAMMA SPECTRUM ANALYSIS: iii- BE-7 LT.3. E 01 LT.4. E 01 E 01 E 01 LT. 3. LT. 4. LT.3. E 01
- h K-4 0 1.3610.27 E 02 LT. 7. E 01 LT.6. E 01 LT. 1. E 02 LT. 8. E 01 ,
h MN.54 LT.3. E 00 LT. 3. ' E 00 LT. 3. - E 00 LT.4. E 00 . LT. 3. E 00 I y CO-58 LT.3. E 00 - LT. 3. E 00 LT.3. E 00 LT.4. E 00 LT. 3. E 00 ' C FE-59 LT.7. E 00 LT. 8. E 00 LT.8. E 00 LT. 1. E O1 LT. 6. E 00 h CO-60 LT.4. E 00 ' LT. 4. E 00 LT.4. E 00 LT. 5. E 00 LT. 3. E 00 l , 3# ZN 65 LT.8. E 00 LT.7. E 00 LT.7. E 00 LT. 1. E 01 LT.6. E 00 l NB-95/ZR-95 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT. 5. E 00 LT. 3. E 00 RU-103 LT.4. E 00 LT. 5. E 00 . LT. 4. E 00 LT. 5. E 00 LT. 3. E 00 i RU.106 LT. 3. E 01 LT. 3. E 01 LT.3. E 01 LT.4. E 01 LT.3. E 01 I-131 LT. 6. E 00 LT. 1. E 01 LT. 1. E 01 LT.8. E 00 LT. 5. E 00 CS.134 LT.4. E 00 LT.4. E 00 LT 3. - E 00 LT. 5. E 00 LT. 3. E 00 CS-137 LT.4. E 00 LT.4. E 00 LT.4. E 00 LT.5. E 00 LT.3. E 00 IA-140/BA-140 LT. 5. E 00 LT.9. E 00 LT.7. E 00 LT. 6. E 00 LT.4. E 00 ' t ! CE.141 LT.6. E 00 LT. l. E 01 LT. 7. E 00 LT.8. E 00 LT. 5.' E 00 CE-144 LT.2. E OI LT.4. E 01 LT.3. E 01 LT.3. E 01 LT.2. E 01 RA-226 LT.7. E 01 LT. 1. E 02 LT.7. E O1 LT.8. E 01 LT.6. E 01 ! TH-228 LT.6. E 00 LT.9. E 00 LT.6. E 00 LT.8. E 00 LT. 5 E 00 -
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