ML20082T713
| ML20082T713 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1993 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20082T694 | List: |
| References | |
| NUDOCS 9505040142 | |
| Download: ML20082T713 (23) | |
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INTRODUCTION The 1993 Annual Radiological Environmental Operating Report for Wo!f Creek Generating Station (WCGS) covers the period from January 1 through December 31,1993. WCGS is located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas.
Fuel loading commenced at WCGS on March 12,1985. The operational phase of the Radiologica:
Environmental Monitoring Program (REMP) began on May 22,1985 with initial criticality and the first detectable quantities of radioactivity were reported in plant effluents in June 1985.
This report contains a description of the REMP conducted by Wolf 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 effects of plant operations were detected in airbome particulate and radiciodine filters, fish, irrigated crops, broadleaf vegetation, milk, ground water, or drinking water.
During 1993, activation products were detected in aquatic plants and algae, surface water, shoreline l sediment, and bottom sediment samples.
No measurable impact on human exposure due to plant operation was seen for the year.
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0 L PROGRAM DESCRIPTION Radiological environmental samples were collec'ed 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 campling 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 analysis 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 volurr,e 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 initia; =d $n01 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 was performed approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> post l 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 ;
l-131. Positive indication of I-131 would have resulted in analysis of each individual charcoal canister. I 1
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 was provided by Teledyne 1 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 l Centigrade. The TLDs are then placed in polyethylene pouches and holders containing 0.093 inch l thick copper shields to filter out low energy radiation. Freshly annealed dosimeters were exchanged i with exposed dosimeters and the exposed dosimeters are shipped to Teledyne isotopes for analysis. I Four freshly annealed TLDs are shipped as controls with the exposed TLDs to record any exposure received in transit.
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.: l 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. j i
Panasonic UD-814-AQ TLDs were also used during the third and fourth quarters of 1993. These l TLDS consist of one lithium-borate element and three calcium sulfate elements in a plastic case. Each ' i TLD is annealed and analyzed by Wolf Creek health physics technicians on a Panasonic UD-710A TLD reader. ;
in peneral, TLDs are positioned roughly 3 to 4 feet above the ground on utility poles. They are l co:,tained in either plastic thermostat boxes or fiberglass 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 l-131 is performed on drinking water and ground water samples. Gross beta analysis is performed on drinking water samples. Tritium analysis is performed monthly by liquid scintillation for surface water l and quarterly for drinking water. Tritium analysis is performed by gas proportional counter quarterly for ground water. All water sampling locations are listed in Table 2 and shown in Figures 3 and 5.
i 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 i mi 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). l 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 i Figure 3). i l
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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 that produced milk for human consumption were identified within 5 miles of the j ;
plant during 1993. Therefore, only control samples were obtained. Radiochemcal 1-131 and gamma >
isotopic analyses were performed on each sample. The control location is illustrated on Figure 5. !
Broadleaf vegetabon samples were collected monthly during the growing season from four gardens. ~ '
The three indicator gardens (two regular and one altemtfr) and a control garden were sampled (Figure 5). Gamma isotopc analysis was performed on all samples.
Irrigated crops (soybeans and com) were also sampled Two samples were obtained from cropland !
downstream of the confluence of WCCL effluents cnd the Neosho River (indcator) and two samples _;
were 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 l as baseline data and to continue contact with local landowners. Gamma isotopic analysis was :
performed on each sample. i
'i 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. j 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 f location that is remote from the site. Gamma isotopic analysis is performed on boneless meat !
portions of the game, j All sampling locations listed in this section are outlined in Table 2.
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IL DISCUSSION OF RESULTS Analysis results for all pathways are summarized in Appendix A using the format described in NRC Radiological Assessment Branch Technical Position, Revision 1, November 1979. Results for individual samples are listed in Appendix B. .
t in this section, results are discussed by pathway and analysis type. Operational results are related to 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. ;
A. Airborne 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 1/C ratio over time. In addition, no radiciodine has been detected since 1989. Therefore, the slight increase in gross beta 1/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 plaat operations.
Table 4 summarizes the gamma analyses of 1993 airbome 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 Quarterly 1993 gamma exposures for each location are summarized in Tables 5 and 6. Values are l 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 controllocations both prior to and after WCGS became operational. Figure 11 shows the historical quarterly average values expressed in mrem /std 90 day quarter for both nearsite and controllocations.
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 oecline in TLD efficiency. Linear 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 REV 4/93
. l 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 (intemal 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 controllocation results has remained near 100 percent through 1993. The near-sMe 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 control location TLDs.
However, if measured direct radiation levels continue to decline, the TLD results will fall 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. Because only one Panasonic TLD was used at each location and the Panasonic TLDs produce one less reading than the Teledyne TLDs, the third quarter average direct radiation values were based on fewer data points than the first, second and fourth quarter direct radiation results. 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 Menitoring 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 oeta data through 1993. The composite 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 i indicator location LW40 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 j August 31 shows that the initial results are within the error range of the duplicate results. No other j nuclides were identified during 1993. I l
No activity due to plant operations were evident in drinking water samples during 1993. )
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i (2) Surface Water Surface water data are sumrriarized in Table 8. Tritium was the only nuclide identified in surface l water samples during 1993. Fgure 12 41ustrates smoothed tritium data for WCCL from startup in May 1985 through 1993 for locations DC and SP and the cumulative curies of tritium released to WCCL.
Tritium values t ave been declining recently and the declining trend may be due to high precipitation durin; 1993. Sig$ cant 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 drr,ught during the previous 2 to 3 i 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 except quarterly l 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 1
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 j exceed the range of Cs-137 fallout measured during pre-operational studies (0.0131 to i 0.0478 pCi/ gram). No Cs-134 was detected in the shoreline sediment samples, as would be expected if the source of the Cs-137 activity was pla..t 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 l cove or JRR during 1993. Arialysis 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. Potassium-40 levels were l consistent with preoperational data. The yearly average K-40 concentration was 1392 pCi/ liter. I Table 15 summarizes milk analysis results for 1993.
No other gamma emitters were detected.
(2) Food and Garden Crops i
Gamma analyses of broadleaf vegetation samples during 1993 revealed naturally occurring gamma l emitters K-40 and Be-7 at concentrations consistent with preoperational levels. l Another naturally-occurring isotope, Th-228, was detected in one broadleaf vegetation sample during 1993 at 61 pCi / kilogram. Broadleaf vegetation results are summarized in Table 13. l 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station 1 Page 7 of 50 !
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.l No additional gamma emitters were detected in broadleaf vegetation samples during the remainder of [
the year, i
Crop samples were obtained from lands normally irrigated by the Neosho River below the outfall of f WCCL. However, due to adequate precipitation during 1993, no irrigation was needed The samples f 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. l 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 at an average concentration of 3.247 pCl / kilogram (wet weight). No other radionuclides were '
detected in fish during the year.
E. Special Samples (not required by the WCGS ODCM) l (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.
(2) Bottom Sedimer,t 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 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 operations. The Cs-137 levels are only slightly higher than those reported prior to WCGS criticality and therefore a major portion of the activity is due to fallout. However, the Mn-54, Co-58, Co-60 and Cs-134 activity shown in the table are attributed to plant operations and are regularly identified in plant effluents.
Be-7 was detected in one of five supplemental 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.
1 (3) Aquatic Vegetation l l
Table 10 shows gamma emitters detected during 1993 in aquatic plant samples. Naturally occurring i Be-7, K-40, Ra-226 and Th-228 were detected. An alga sample accumulated the most detectable l activity. Mn-54, Fe-59, Cr-51, Co-58, Fe-59, Co-60, Nb-95/Zr-95, Nb-95, Ru-103, Ru-106, Sb-125, 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.
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TABLE 1 (Cont'd) !
EXPOSURE NUMBER OF SAMPLING AND TYPE AND PATHWAY / SAMPLES AND COLLECTION FREQUENCY FREQUENCY OF SAMPLE SAMPLE LOCATIONS ANALYSIS DIRECT RADIATlON (cont'd)
An inner ring of stations, one in each i meteorological sector 0-3 mile range from the site (Locations 1,7-9, 11-13,18,26,27,29-31,37, and 38 on .
Figure 2) !
An outer ring of stations, one in each meteorological sector in the 3-5 mile range from the site (Locations 4-6, 15-17,19-25, and 33-i 36 on Figure 2) Five sectors contain an additional station (Locations 2,3,10,14 and 28).
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 j on Figures 2 and 5)
Locations 41,42, and 43 are not required samplin stations but 1 have been added as specialinterest sampling locations i
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TABLE 2 SAMPLE LOCATION NUMBERS, DISTANCES (Miles), AND DIRECTIONS i Location Distance I Location Distance / Location Distance i Number Direction Number Direction Number Direction TLD and Air Particulates and Radiciodine 1 1.4/N 15 4.5/ESE 29 2.6/SSW 2 2.7/N 16 4.2/E -30 2.2/W !
.l 3 3.0/NNE 17 3.6/SE 31 3.0/WNW - l 4 4.0/NNE 18 3.2/SSE 32 3.2/WNW i 5 4.0/NE 19 4.0/SSE 33 3.7/WNW ;
6 4 4/ENE 20 3.3/S 34 4.0/NW 7 1.9/NE 21 3.8/S 35 4.6/NNW l 8 1.6/NNE 22 4.1/SSW 36 4.2/N l 9 2.0/ENE 23 4.5/SW 37 2.1/NNW I 10 2.4/ENE 24 4.1/WSW 38 1.2/NW :
11 1.6/E 25 3.6/W 39 13.0/N l l i
12 1.8/ESE 26 2.6/WSW 40 >15.0/WNW . !
13 1.5/SE -27 2.1/SW 41 0.8/NNW !
14 2.6/SE 28 2.8/SW 42 0.8/SSE l :
43 0.8/WNW i Ground water Drinking water Surface water ;
B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 >10.0/SSE DC 0.6/WNW l C-49 2.9/SW SP 2.9/S -
D-65 3.9/S ;
Milk Broadleaf vegetation irrigated Crops 6 S-3 >15.0/WNW A-1 1.4/N NR-U1 4.2/S W l
R-1 2.1/NNW NR-D1 >10.0/S G-1 1.6/SE NR-D2 >10.0/S S4 >15.0/WNW Fish Shoreline and Bottom Aquatic Vegetation 1 -
Sediments Algae 1 WCCL 0.6/WNW DC 0.6/WNW DC 0.6/WNW JRR 4/W JRR 4/W UHS 0.6/E Game Birds and Animals WCCL GeneralVicinity Beto Junction >15.0/NNW 1993 Annual RadWical Environmental Operating Report Wolf Creek Generating Station Page 20 of 50 REV 4/95
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I TABLE 3 1993 Airtsorne Particulate Gross Beta Analyses ;
(pCil cubic meter, analysis error reported in Appendix B) '
DATE Looseon l WEEK Beginning Ending 2 3 32 37 40 l 1 12/29/92 1/5S3 0 034 0.031 0.034 0.031 0.031 2 1/5/93 1/12/93 0.033 0.036 0 040 0.037 0.027 i 3 1/12/93 1/19/93 0.046 0.059 0.048 0.056 0.048 l 4 1/19/93 1/26 S 3 0.023 0.035 0.023 0,025 0.021 !
5 1/26/93 2/2/93 0.029 0 030 0.026 0.028 0.027 6 2/2/93 2/9/93 0.029 0.035 0 024 0.031 0.022 7 2/9/93 2/16/93 0.027 0.017 0.027 0.032 0.027 8 2/16/93 2/23/93 0.031 0.032 0.031 0.029 0.031 9 2/23/93 3/2/93 0.035 0.028 0.025 0.031 0.024 10 3/2/93 3/9/93 0.025 0.023 0.022 0.027 0.022 11 3/9/93 3/16/93 0.016 0.012 0.013 0.014 0.011 I 12 3/16/93 3/23/93 0.023 0.018 0.024 0.022 0.018 )
13 3/23/93 3/30/93 0.017 0.012 0.017 0 015 0.014 14 3/30/93 4/6S3 0.015 0.015 0,014 0.019 0.015 15 4/6/93 4/13/93 0.017 0.018 0.014 0.017 0.015 16 4/13/93 4/20/93 0.016 0.017 0.015 0.016 0.014 !
17 4/20/93 4/27/93 0 027 0 028 0.030 0 029 0.023 l 18 4/27/93 5/4/93 0.019 0.014 0.014 0.018 0.016 19 5/4/93 5/11/93 0.021 0.014 0.015 0.014 0.014 20 5/11/93 5/18/93 0 015 0.015 0.017 0.013 0.014 21 5/18/93 5/25/93 0.016 0.015 0.018 0.016 0.014 l
22 5/25/93 6/1/93 0.019 0 016 0.016 0.018 0.022 23 6/1/93 6/8/93 0 019 0.017 0.017 0.021 0.020 l 24 6/8/93 6/15/93 0.022 0.018 0.018 0.019 0.018 1 25 6/15/93 6/22/93 0.018 0.015 0 017 0.016 0.014 l 26 6/22/93 6/29/93 0 015 0.013 0 016 0.017 0.016 l 27 6/29/93 7/6/93 0.024 0.020 0.022 0.019 0.020 !
28 7/6/93 7/13/93 0 020 0.018 0.020 0 021 0.018 !
29 7/13/93 7/20/93 0.017 0.019 0 020 0.018 0.015 30 7/20/93 7/27/93 0.022 0.019 0.019 0.024 0.020 31 7/27/93 8/3/93 0.022 0.023 0.022 0.027 0.025 32 8/3/93 8/10/93 0.024 0.021 0.024 no data 0.024 33 8/10/93 8/17/93 0.027 0.028 no data 0.032 0.028 34 8/17/93 8/24/93 0.023 0.021 0.024 0.024 0.021 35 8/24/93 8/31/93 0.028 0.029 0.026 0.028 0.026 :
36 8/31/93 9/7/93 0.020 0 021 0 024 0.022 0.024 )
37 9/7/93 9/14/93 0 020 0.017 0 019 0.032 0.021 l 38 9/14/93 9/21/93 0.024 0.021 0 023 0.025 0.019 l 39 9/21/93 9/28/93 0.020 0 018 0.019 0.020 0.016 j 40 9/28/93 10/5/93 0.025 0 027 0 025 0.025 0.018 ,
41 10/5/93 10/12/93 0.026 0.027 0.028 0.031 0.031 l 42 10/12/93 10/19/93 0.019 0.025 0.027 0.029 0.024 j 43 10/19/93 10/26/93 0 022 0.023 0 029 0.025 0 023 '
44 10/26/93 11/2/93 0.019 0 020 0.023 0.025 0.021 45 11/2/93 11/9/93 0.024 0.020 0.021 0.023 0.021 46 11/W93 11/16/93 0 022 0.016 0 025 0.022 0.024 47 11/16 S3 11/23/93 0 028 0.024 0.026 0 027 0.024 48 11/23/93 11/30/93 0 031 0 028 0.028 0.023 0.026 49 11/30/93 12/7/93 0.029 0.036 0 036 0 035 0.028 50 12/7/93 12/14/93 0.032 0.030 0.035 0.031 0.028 51 12/14193 12/21/93 0 029 0 026 0 030 0.030 0.027 52 12/21/93 12/28/93 0 024 0 024 0.025 0.019 0.025 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 21 of 50 )
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TABLE 4
- Airborne Particulate Quarterly Composite Gamma lootopic Analyses (pCil cubic meter, analysis error reported in Appendix B)
LOCATION YEAR QTR BE-7 BE-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 >
2 1993 2 0.08 0.0075 < 0.01 < 0.003 < 0.0005 < 0.0005 -
2 1993 3 0.07 0.0077 < 0.01 < 0.002 < 0.0004 < 0.0005 l 2 1993 4 0.06 0.0060 < 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 0.0060 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 0.0060 < 0.007 < 0.002 < 0.0004 < 0.0004 l t
I 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 22 of 50 ,
REV 4/95 j
i l' .
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1
. TABLE 6 1993 Third & Fourth Quarter TLD Results ,
(mr190 day qtr) l Third Quarter (Panasonic TLD data) Fourth Quarter (Teledyne TLD data)
LOCATION DAYS 90 D AVG 90 D LOCATION DAYS 90 D AVG 90 D i 2STV 2STV
{
1 97.9 17.5 1.0 1 83.0 15.4 3.3 2 97.8 15.6 1.9 2 83.1 14.4 2.7 ;
3 97.9 14.9 0.8 3 83.1 14.6 2.1 4 97.9 16.0 0.6 4 83.1 15.1 5.5 5 97.9 14.9 1.0 5 83.0 13.7 1.6 .
6 97.9 13.7 1.1 6 83.1 14.4 2.4 7 97.9 14.6 1.1 7 83.1 13.6 1.5 8 97.9 16.1 - 1.6 8 83.0 16.0 1.6 9 97.9 13.9 1.1 9 83.1 14.3 1.5 ,
10 98.0 15.8 1.4 10 83.1 15.5 2.9 11 97.9 17.5 2.9 11 83.1 17.7 2.2 12 97.9 16.0 1.7 12 83.1 15.5 2.2 ;
13 97.9 17.0 0.6 13 83.1 15.4 1.7 14 97.9 18.1 1.9 14 83.1 15.8 2.3 15 97.9 16.8 1.7 15 83.1 16.5 2.4 16 97.9 15.9 0.7 16 83.1 16.2 2.1 17 97.9 18.0 2.2 17 83.1 15.5 2.4 18 97.9 16.9 2.7 18 83.1 16.3 2.3 19 97.9 18.9 1.3 19 83.1 16.5 1.4 20 98.0 16.1 1.8 20 83.1 19.1 5.9 21 98.0 13.6 0.1 21 83.1 15.9 2.4 22 97.9 15.1 1.3 22 83.0 15.8 2.3 23 98.0 14.8 2.1 23 83.1 16.2 2.5 >
24 98.0 15.0 0.8 24 83.1 16.1 1.7 25 98.0 12.1 0.8 25 83.1 13.0 3.6 26 98.0 13.9 1.0 26 83.1 13.9 1.3 27 98.0 15.2 0.9 27 83.0 15.5 1.4 28 98.0 13.7 0.3 28 83.0 16.5 1.6 29 98.0 13.2 1.1 29 83.0 13.9 2.2 30 98.0 15.3 1.5 30 83.1 15.3 2.3 31 98.0 15.8 0.5 31 83.1 15.7 1.8 32 98.0 15.5 1.9 32 83.0 15.3 1.1 33 98.0 17.2 0.3 33 83.1 16.2 3.0 34 98.0 17.4 1.0 34 83.0 16.3 1.8 35 97.9 19.4 2.3 35 83.1 15.2 1.3 36 97.9 18.7 1.7 36 83.1 15.1 2.7 -
37 98.0 17.3 2.2 37 83.0 15.4 1.4 38 98.0 18.8 2.1 38 83.0 16.7 2.3 39 98.0 16.8 0.8 39 83.1 14.6 3.9 40 98.0 16.2 2.4 40 83.0 14.1 1.4 41 97.9 15.5 1.4 41 83.0 15.1 1.7 ,
42 97.9 12.5 1.6 42 83.0 11.2 1.0 43 97.9 11.2 2.2 43 83.0 10.2 0.8 i
r 1993 Annual Radiological Environmental Operating Report ,
Wolf Creek Generating Station Page 24 of 50 REV 4/95
TABLE 7 1993 Drinking Water Radiological Analyses (pCl / liter, analysis error reported in Appendix B)
SAMPLE LOCATION GR-B GR-B MN-54 FE-59 CO-58 CO-60 ZN-65 ZR- I-131 CS-134 CS-137 BA-LA COLLECTION ERROR NB-95 140 START DATE 1/5/93 BW15 7.2 +/- 1.4 <3 <7 <3 <3 <6 <3 < 0.2 <3 <3 <5 2/2/93 BW15 5.0 +/-1.8 <3 <6 <3 <3 <7 <3 <1 <3 <3 <4
- 2/2/93 BW15 5.1 +/- 1.8 <2 <5 <2 <2 <5 <2 <1 <3 <3 <3 3/2/93 BW15 6.8 +/- 1.3 <2 <6 <3 <3 <6 <3 < 0.2 <3 <4 <6 4/6/93 BW15 7.9 +/- 1.4 <3 <7 <3 <4 <6 <3 < 0.5 <4 <4 <6 5/4/93 BW15 5.9 +/- 1.1 <3 <6 <3 <4 <7 <4 < 0.2 <4 <4 <6 6/1/93 BW15 9.4 +/- 1.7 <3 <7 <3 <3 <7 <3 < 0.2 <3 <4 <6 7/6/93 BW15 6.8 +/- 1.2 <3 <6 <3 <3 <7 <4 < 0.5 <4 <4 <5 8/3/93 BW15 6.2 +/- 1.3 <4 <7 <4 <4 <9 <4 < 0.4 <4 <4 <5 8/31/93 BW15 7.1 +/- 3.5 <3 <6 <3 <3 <6 <3 < 0.9 <3 <3 <5 11/30/93 BW15 6.4 +/- 1.4 <3 <6 <3 <3 <7 <3 < 0.2 <3 <3 <5
- 11/30/93 BW15 7.9 +/- 1.5 <3 <6 <3 <4 <6 <3 < 0.1 <3 <3 <S 1/5/93 LW40 7.1 +/- 1.4 <3 <8 <3 <3 <8 <4 < 0.2 <4 <4 <6 2/2/93 LW40 6.7 +/- 1.4 <3 <7 <3 <4 <8 <3 < 0.6 <4 <4 <6 3/2/93 LW40 6.2 +/- 1.4 <3 <6 <3 <3 <6 <3 < 0.1 <3 <4 <6 i 4/6/93 LW40 8.5 +/- 1.5 <4 <9 <4 <4 < 10 <5 < 0.5 <5 <5 <6 5/4/93 LW40 6.4 +/- 1.3 <4 <8 <4 <4 <8 <4 < 0.2 <4 <4 <7 ,
6/1/93 LW40 6.7 +/- 2.2 <3 <6 <3 <3 <6 <3 < 0.5 <3 <4 <5
'6/1/93 LW40 12 +/- 3 <3 <7 <3 <3 <7 <3 <0.6 <3 <3 <4 7/6/93 LW40 6.0 +/- 1.3 <4 <9 <4 <4 <0 <4 < 0.4 <5 <5 <6 8/3/93 LW40 5.3 +/- 1.4 <4 <7 <3 <4 <8 <4 < 0.4 <4 <4 <5 8/31/93 LW40 13 +/- 4 <3 <6 <3 <4 <7 <3 <0.8 <3 <4 <6 10/5/93 LW40 2.3 +/- 1.3 <4 <8 <4 <4 <8 <4 < 0.2 <4 <4 <7 11/30/93 LW40 7.4 +/- 1.5 <3 <7 <3 <3 <8 <4 < 0.2 <3 <4 <5
- 11/30/93 LW40 6.7 +/- 1.5 <4 <9 <4 <5 <8 <4 < 0.2 <5 <5 <7
- duplicate l
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i 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station ,
Page 25 of 50 REV 4/95 j i
TABLE 8 1993 Surface Water Radiological Analyses (pCi t liter, analysis error reported in Appendix B)
LOCATION DATE H-3 MN-54 FE-59 CO-58 CO-60 ZN-65 ZR- I-131 CS- CS- BA-LA- COMMENTS NB-95 134 137 140 DC 1/19/93 6300 <3 <7 <3 <4 <8 <4 <6 <4 <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 DUPUCATE DC 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 DC 5/18/93 7300 <3 <7 <3 <4 <7 <4 <7 <4 <4 <6 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 DUPUCATE 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 DC 11/16/93 6800 <3 <8 <3 <3 <6 <4 < 20 <3 <3 <9 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 2/25/93 <100 <3 <8 <3 <3 <7 <3 < 10 <3 <5 <7 l ,
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 <5 <5 <7 MUSH 7/20/93 < 700 <3 <6 <3 <3 <7 <3 <6 <3 <4 <4 i I
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 l 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 SP 5/18/93 7400 <3 <7 <4 <4 <8 <4 <6 <4 <4 <6 SP 6/15/93 7500 <4 < 10 <5 <5 < 10 <5 <6 <5 <S <6 SP 7/20/93 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 c5 <3 <6 <3 c4 <5 )
i i
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1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 26 of 50 REV 4/95
i TABLE 9 1993 Ground Water Radiological Analyses (pCilliter, 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-FotF93 < 100 < 3< 8< 3< 4 < 8< 4 < 0.3 < 4 < 4 < 8 i B12 18-May-93 < 200 < 3< 5< 3< 3< 6< 3< 0.1 < 3< 3< 4 B12 17-Au9-93 <200 < 3< 7< 3< 3< 6< 4< 0.1 < 3< 5< #
B12 16-Nov-93 < 400 < 3< 8< 4 < 44 7< 4< 0.2 < 4< 4< 10 C10 23-Fet>93 <100 < 5< 10 < 5< 5< 10 < 5< 0.3 < $< 5< 9 i C10 18-May 93 < 200 < 3< 6< 3< 3< 6< 3< 0.3 < 3< 3<. 4
- C10 18-May-93 < 200 < 4 < 7< 4< 4 < 7< 4< 0.3 < 4< 4 < 6 l
C10 17-Au9-93 < 200 < 5< 10 < 5< 5< 10 < 6< 0.2 < 6< 6< 9 [
C10 16-Nov-93 < 400 < 3< 8< 3< 4 < 6< 3< 0.2 < 3< 3< 8 C49 23-Fet>93 < 100 < 4 < B< 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-Fet>93 < 100 < 4 < 10 < 4 < 4 < 9< 4 < 0.3 < 4 < 4 < 8
{
D65 18-May-93 < 200 < 2< 5< 3< 3< 6< 3< 0.2 < 3< 4< 4 _l 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 e
- duplicate l TABLE 10 1993 Aquatic Plants Radiological Analyses (pCil g, wet, analysis error reported in Appendix B) l !
LOC TYPE DATE BE-7 K 40 MN-54 CO-58 FE-59 CO-60 RU-103 RU-106 CS-134 i
DC ALGAE 6/29/93 0.619 1.30 0.0678 0.918 0.0286 0.658 0.0122 0.153 0.0739 !
DC ROOTED 6/29/93 0.088 1.91 0.065 0.026 i AQ8JATIC DC AM POND 9/28/93 0.301 2.60 ALT WEED l LOC TYPE DATE CS-137 RA-226 TH-228 CR-51 NS-95/ZR-95 NS-95 SB-125 DC ALGAE 6/29/93 0.106 0.344 0.181 0.235 0.063 0.121 0.0459 0.163 I DC ROOTED AQUATIC 6/29/93 DC ALT AM POND WEED 9/28/93 0.007 0.162 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 27 of 50 REV 4/95
TABLE 11 1993 Shoreline Sediment Radiological Analyses ,.
(pCil kg, dry, analysis error reported in Appendix B) 'j LOCATION DATE BE-7 K-40 CO-58 CO-60 CS-134 CS-137 RA-226 TH-228 DC 20-Apr-93 (500 9770 < 50 93 < 60 174 1910 1090 JRR 20-Apr-93 <400 10800 < 30 < 30 < 50 < 40 2320 1710 ,
DC 28-Sep-93 < 300 7500 < 30 < 30 < 40 73 738 690 ,
JRR 09-Nov-93 < 300 8770 < 30 < 30 < 40 108 1550 1010 i
JRR* 09-Nov-93 < 400 8700 < 40 < 30 < 50 139 2360 1160
- Duplicate Analysis ,
t i
1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 28 of 50 REV 4/95 .
I
TABLE 12 1993 Bottom Sediment Radiological Analyses (pCiI kg, dry, analysis error reported in Appendix B)
LOC DATE BE-7 K-40 MN-54 CO-58 CO-60 CS-134 CS-137 RA-226 TH-228 DC1 5/25/93 < 400 12800 +/- 1300 < 50 < 50 1370 +/- 140 185 +/- 50 726 +/- 73 3040 +/- 700 1230 +/- 120 DC2 5/25/93 < 400 4300 +/- 500 < 40 < SO 474 +/- 54 < 60 408 +/- 47 1770 +/- 750 611 +/- 61 DC3 5/25/93 454 +/- 239 4900 +/- 490 77 +/- 28 324 +/- 39 793 +/- 79 139 +/- 30 222 +/- 36 1660 +/- 450 586 +/- 59 DC4 5/25/93 < 400 13200 +/- 1300 < 60 < 50 1430 +/- 140 361 +/- 56 942 +/- 94 2150 +/- 700 1430 +/- 140 DCS 5/25/93 < 400 13100 +/- 1300 < 60 < 50 2340 +/- 230 293 +/- 49 840 +/- 84 2530 +/- 680 1530 +/- 150 DC 6/29/93 < 500 14100 +/- 1400 < 60 < 50 1180 +/- 120 271 +/- 57 893 +/- 89 3290 +/- 830 1330 +/- 130 UHS 7/2/93 < 400 13700 +/- 1400 < 40 < 40 < 50 < 50 368 +/- 48 2490 +/- 600 1310 +/- 130 JRR 7/2/93 < 400 17100 +/- 1700 < 40 < 30 < 30 < 50 225 +/- 38 2420 +/- 540 1390 +/- 140 DC 9/28/93 < 400 12000 +/- 1200 57 +/- 33 < 50 1080 +/- 110 322 +/- 46 647 +/- 65 2120 +/- 590 1240 +/- 120 JRR 11/9/93 < 400 10900 +/- 1100 < 40 < 30 < 40 < 40 216 +/- 30 1590 +/- 540 1100 +/- 110 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 29 of 50
-REV 4/95 l . - .-..- .- -.- .- - . .- - . - _
. I TABLE 13 1993 Broadleaf Vegetation Radiological Analyses (pCl / kg, wet, 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 27-May-93 LETTUCE S4 570 116 5400 540 < 10 < 20 < 20 < 20 < 300 < 20 25-May-93 LETTUCE R1 931 115 5460 550 < 10 < 20 < 10 < 10 < 200 < 20 224un-93 CABBAGE S-4 367 66 3450 340 <9 < 10 <9 <9 < 200 < 20 "
294un-93 LETTUCE R-1 852 85 8480 850 <8 < 10 <8 <9 < 100 < 10 274ul-93 CABBAGE S-4 1490 150 3750 370 < 10 < 20 <9 <9 < 200 < 10 274ul-93 CABBAGE R-1 1100 110 3400 340 < 10 < 20 < 10 < 10 < 200 < 20 27-Jul-93 SWISS A-1 689 99 4240 420 < 10 < 20 < 10 < 10 < 200 < 20 i CHARD 17-Aug-93 SWISS A-1 242 58 6280 630 <8 < 10 <9 < 10 < 200 < 10 CHARD
- 17-Aug-93 SWISS A-1 310 67 6190 620 <9 < 10 < 10 <9 < 200 < 10 CHARD ,
24-Aug-93 CABBAGE S-4 330 88 3960 400 < 10 < 20 < 10 < 10 < 200 < 20 21-Sep-93 SWISS A-1 527 84 3890 390 < 10 < 20 < 10 < 10 < 200 61 CHARD 21-Sep-93 CABBAGE S4 626 100 4150 410 < 20 < 30 < 10 < 10 < 200 < 20 3 26-Oct-93 SWISS A-1 557 72 2670 270 <9 < 20 <9 <9 < 200 < 10 CHARD ,
- Duplicate Analysis 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- I-131 CS- CS-137 RA- TH-ERROR ERROR 103 134 226 228 19-Oct-93 SOYBEANS NR4J1 < 60 N/A 13100 1300 <8 <9 <9 <9 < 100 10 19-Oct-93 CORN NR-U1 < 80 N/A 2720 270 < 10 < 10 < 10 < 10 < 200 20 i 19-Oct-93 SOYBEANS NR-D1 < 90 N/A 14700 1500 < 10 < 20 < 10 < 10 < 200 < 20 19-Oct-93 CORN NR-D2 < 60 N/A 2900 290 <7 < 10 <8 <8 < 100 < 10 i
1993 Annual Radiological Environmental Operating Report i Wolf Creek Generating Station Page 30 of 50 REV 4/95 I
L d
'4 TABLE 15 1993 Milk Radiological Analyses (pCl / liter, analysis error reported in Appendix B) 5-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 DUPUCATE COW 2/10/93 <0.4 1340 +/- 130 <4 <5 <7 COW 2/10/93 < 0.4 1510 +/- 150 <5 <5 <7 DUPUCATE COW 3/9/93 <0.2 1390 +/- 140 <4 <5 <5 COW 4/13/93 < 0.2 1370 +/- 140 <4 <5 <5 COW 4/28/93 < 0.2 1470 +/- 150 <3 <3 <4 !
COW 5/11/93 < 0.2 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 6/22/93 < 0.2 1400 +/- 140 <4 <4 <4 COW 7/13/93 < 0.2 1270 +/- 130 <4 <4 <6 COW 7/27/93 < 0.2 1390 +/- 140 <4 <4 <5 !
COW 8/10/93 < 0.3 1480 +/- 150 <4 <4 <7 COW 8/24/93 < 0.2 <100 <4 <4 <5 K-40 <100 l
COW 9/7/93 < 0.2 1360 +/- 140 <4 <4 <6 i
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 j 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 i
1 1993 Annual Radiological Envir onmental Operating Report Wolf Creek Generating Station Page 31 of 50 REV 4/95
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TABLE 16 1993 Fish Radiological Analyses !
(pCil kg, wet, analysis error reported in Appendix B) l i
DATE SPECIES Location K-40 MN-54 FE-59 CO-58 CO-60 ZN-85 CS-134 CS-137 TH-228 :
30-Apr-93 CHANNEL WCCL 3590 < 10 < 30 < 10 < 10 < 30 < 20 < 20 < 20 CATFISH 30-Apr-93 WIPER WCCL 3710 < 10 < 30 < 20 < 10 < 30 < 20 < 20 < 30 30-Apr-93 CARP WCCL 3070 < 20 < 30 < 20 < 10 < 30 < 20 < 20 < 30 18-May-93 WHITE BASS JRR 3570 < 30 < 60 < 30 < 30 < 50 < 30 < 30 < 60 f 18-May-93 CARP JRR 3270 < 30 < 60 < 20 < 30 < 50 < 30 < 20 < 40 05-Oct-93 SM BASS / WIPER WCCL 2700 < 10 < 30 < 10 < 10 < 30 < 10 < 10 < 20 i 05-Oct-93 CHANNEL WCCL 2800 < 20 < 50 < 20 < 20 < 40 < 20 < 20 < 40 l CATFISH l 05-Oct-93 CARP WCCL 3230 < 20 < 40 < 20 < 20 < 40 < 20 < 20 < 40 1 09-Nov-93 CARP JRR 3280 < 10 < 30 < 10 < 10 < 30 < 10 < 10 < 20 t
t
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1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 32 of 50 REV 4/95
$t
'e.
s.
TABLE 19 '
l 1993 US EPA interlaboratory Comparison Program .
e ransrem T- ,.. '
Date blache hchde EPA Manullie) laa8aram Resultib) Dermuonicl
- 01/15/93 Wasar Sr-89 ISD 2 54 12.67 2 1.15 -0.81 ~ '
3r-90 10.0 1 SD 8.33 2 1.15 0.56 01/29/93 Water Gr-Alpha 34D1 9D 17.33 2 1.15 -321 hD r Gr-Bata 44.0
- SD 52201 1h0 2.77 tel j 02/05/93 Water I-131 100D1 10D 106.67 2 5.77 1.15 05/05/93 Weser Re.226 941 1.5 7.67 i O.12 -2.46 (0 Ra-228 1852 4.6 19.33 3 2 31 031 04/20/93 Water Gr. Alpha 95.0 1 24D 94.33 2 1.15 4 06 Ra-226 24.9 2 17 19.00 t 120 -276 (0 ,
Ra-228 19.0 1 4A 18.33 1 0.58 4.24 ,
Gr-Bata 177.0 2 27D 180.0
- ODO .l.73 Sr.89 41.0 t ED 35.33 2 1.53 -IA6 Er.90 29D1 5D 27.33 2 0.58 0.58 Co40 30.0 t SD 40.67 2 151 0.58 Ca 134 27Dt 5D 23A7 2 1.53 1.15 Co-837 3202 54 34332 2D8 0A1 06/04/93 Water H-3 9844D t 984D 9386.67 1 152.75 0A4 r 06/11/93 Water Co40 15D t SD 16.33 1 1.53 0.46 Zn-65 105.0 t 10D 121.33 1 20D0 3.18 (d Ru-106 !!9.0 2 12D 106.33 2 15.80 -!A3 Ca 134 5Dt 5D 5.67 * - 0.58 023 Ca-137 SD 2 SD SD72 0.58 0.58 Ba-133 90D1 10D 104.33 2 9.29 0.92 07/16/93 Water Sr.89 34D 2 ED 31E72 2.52 4 81 Sr-90 25.0 t ED 24.00 t ODO 4 35 i
07/23/93 Wasar Gr Alpha 15D t SD R&672 2D8 127 Gr-Beta 43D 2 669 42.67
- 2.52 0D8 08/27/93 Air riitar Or. Alpha 19.0 t SD 1720t ODO 029 Gr-Beta 47D 2 EO 40.00 1 1.73 0.m 5r-90 19.0 2 SD 17.67 1 0.58 4 46 Ca-837 9.02 SD 9A72 0.58 023
~
09/09/93 Water Ra.226 14.9 2 22 15.33 2 0.56 034 Ra-228 20.4 2 Sul 20.67 2 1.15 0D9 09/24/93 hink Sr.49 30.0 t SD 35.67 1 331 136 Sr-90 25.0 2 SD 24.00 1 1.73 0.35 I-131 120D 2 12D 126.67 2 5.77 036 Ca.137 49D 2 SD 50.67 1 1.15 0.58 K 1679D1 44D 1820.00 2 17.32 -1.22 10/08/93 Water I-131 117.0 1 12D 105.33 2 5.77 137 10/19/93 Water Gr-Beta 58D 2 10D 51.33 2 321 .l.15 Sr-89 15.0 2 SD 15.00 t 120 0.00 Sr-90 10.0 1 SD 10.00 t 0.00 0D0 C040 IOD 1 SD 12.00 2 120 OAD Ca 134 12D 2 54 9.00 2 IDO -1D4 Ca 137 IOD 2 ED 12.67 2 2.52 OA2 Gr. Alpha 40.0 1 10D 39.67 1 0.58 4"3B Ra-226 9.92 13 10.10 2 0.79 0.23 Ra 228 12.5 2 11 14.67 2 1.15 1.21 10/29/93 Water Gr Alpha 20.0 2 5D 20.33 1 2.08 0.12 Gr-Bata 15D 2 ED 15.67 2 2D8 0.23
!!/5/93 Weser H-3 7308D 2 740D 8000.00 2 100.00 1.17 11/12/93 Water CW 30.0 1 SD 28.67 1 2A9 0.46 Zn45 150.0 2 ISD 152.00 2 9.17 0.23 ,
Ru-306 201D 2 20D 177.33 2 5.51 -2D5 D4 ;
Ca 134 50.0 2 SD 53.33 2 433 .lA6 1 Ca-137 40.0 2 SD 41.33 2 3D6 0.46 1 Be-133 79.0 2 SD 89.33 2 3DB -2D0 to 1993 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 35 of 50 REV 4/95
.. :: 1 g "
,m ;
l4' )
oe .
1 TABLE 19(contd) .
toes us EPA Intertaboratory Comparison Program l l
\
t
- m. .
lol EPA Resuks-Pad laboratory precision (1 sigmal. Unme are pct /Iner for water and snelk enoopt K is in sag /litar. Units are total PCI for air particulate Gleurs. ,
M Telodyne Mosults . Aserage t one Units are pct /hter for water and estik encept K asin neg/hter. Unsas are p0 for air particulmas Akers. -
lei Normehead doutation front the known.
kg 1he EPA outtched from Am-241 to D-230 alpha spike. We cakhrated with 3-230.
using medium nitrate to generate a selfeboorption cusve. De EPA water. honover has minerals which have greater self-absorption than the medium nitrate motets.1he !
EPA has agreed to mend us a gallon of their water whidt we een use to prepare a self- ,
ahoorpuon cuswe with h-230, l
Id By overstput, we did not use the spealal self-absorption curve which we had .k a -i dortved useng EPA weser and Co-137 standard. We udi use the EPA curve ;
an the future. We may also re<lertve this curve usmag a water semple whicts the EPA l has apsed to send us. ;
10 The =insens data and backsnnands were vert 8ed. Possibly some adaceanre== used I were arrensously hips. causing leur values. A less Rhely emuse is an error in dilution.
Near Ra-236 atandards wel be prepared. Closer anonttortng of out of control !
an- wel be done and astra are in preparation of the sampie wul be j maernmenant- ;
W The calculations were checked and found to be correct.1he results of etz pasana emitting *===ap== were reported to the EPA. The results of four were within I a
normahmud devenuon: a Alth. wahen 2 nonneksed deviations. Only the Ends average
- was outmode the control hausts. Dare is no strvious reeman why one testope should ne outande the control kmeta, sendte Ave other Isotopes wuse within control asusta.
f N Althoups the 11 average (177.31 was 2.tB deutsuons leur comspared to the EPA value. ,
the & was good with the svarege (175.21 of 173 paranvanaa he data was -(
reviewed for accuracy induding halfIIIe and brnncheny inteissey used. No preideums l were found. No corrocove action anunpeted because of the good agreement wah the !
average of sa partscapensa. ,
No problems were found with the Al=Hana 1hyee other tectopes were within I h W
- deviation, so its unilhely that a general problem estata. If compared to the average of I
all perucepanta, the 11 reauks would urM*=my be wettun 2 desteuens.1be an.
137 reauks were within +1 devantson for the past two muss chadia, thus there is not i
+
a trend. No correcove acuan anucepated at this time. ,
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1993 Annual Radiological Environmental Operating Report !
Wolf Creek Generating Station l Page 36 of 60 i REV'4/95
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