ML20210B506
| ML20210B506 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1986 |
| From: | Bailey J, Velma King WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ET-87-0165, ET-87-165, NUDOCS 8705050343 | |
| Download: ML20210B506 (127) | |
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l i l I i Prepared by Vincent A. King i May 1, 1987 i s 8705050343 57sfaf PDR ADOCK O O 0482 . R PDR
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l s s TABLE OF N Page List of Tables .................................................... 2 s s List of Figures ................................................... 3 I ntrCaduct i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 I. Program Description ......................................... 6 II. Discussion of Results ....................................... 9 III. Annual Land Use Survey Results and Program Revisions ........ 15 IV. Monitoring Program Deviations ............................... 16 V. EPA Interlaboratory Ccanparison Program Results . . . . . . . . . . . . . . 18 TABLES
...........s................................................ 19 FIGURES ........................................................... 38 Appendix A: Sumary tables in format of NRC Radiological Assessment Branch Technical Position, Revision 1, November 1979 ........................... A-1 '
Appendix B: Individual sample results ........................... A-9 i l 1986 ANNUAL RADIOLOGICAL ENVIRONMENI'AL OPERATING REPORT NOLF CREEK GENERATING STATION Page 1 of 50 3, 1 !\ t 1i
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LIST OF TABLES Page Table 1: 1986 Radiological Environmental Monitoring Program Sampling Schedule .................................... 19 Table 2: Sampling Location Numbers, Distances, and Directions ........................................... 22 Table 3: Gross Beta Analysis Results of Air Particulate Samples .............................................. 23 Table 4: Gantna Analysis Results of Air Particulate Composite Samples .............................................. 25 Table 5: Weekly Ganina Analysis of Air Particulate Samples Following the Chernobyl Accident ..................... 26 Table 6: I-131 Analysis of Charcoal Filters ................... 27 Table 7: 1986 TLD Results ..................................... 28 Table 8: Gross Beta Analysis Results of Drinking Water Samples .............................................. 29 Table 9: Tritium Analysis Results of Surface Water ............ 30 Table 10: Gamna Dnitters in Milk Samples . . . . . . . . . . . . . . . . . . . . . . . 31 Table 11: Ganma Analysis Results of Broadleaf Vegetation Samples .............................................. 32 Table 12: Ganma Analysis Results of Shoreline Sediment Samples .............................................. 33 Table 13: Gamma Analysis Results of Aquatic Vegetation Samples .............................................. 34 Table 14: Results of 1986 Land'Use Survey ...................... 35 Table 15: Results of EPA Interlaboratory Comparison Tests ...... 36 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 2 of 50
LIST OF FIGURES Page Figure 1: Airborne Particulate and Radioiodine Sampling Locations ............................................ 38 Figure 2: TLD Incations ........................................ 39 Figure 3: Wa ter Sanpling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 Figure 4: M i lk Sangl i ng Loca t i o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 Figure 5: Broadleaf Vegetation Sangling Locations . . . . . . . . . . . . . . 42 Figure 6: Fish, Shoreline Sediments, and Aquatic Ve Sanpling Locations . . . . . . . . . . . . . . . . . . . ..............
. .getation 43 Figure 7: Distant Sangling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . 44 Figure 8: 1986 Gross Beta Air Concentrations ................... 45 Figure 9: Nearsite Average vs. Control TLDs . . . . . . . . . . . . . . . . . . . . 46 Figure 10: Variation of Nearsite TID Results . . . . . . . . . . . . . . . . . . . . 47 Figure 11: 1986 TLD Results ..................................... 48 Figure 12: Drinking Water Gross Beta Analysis Results ........... 49 Figure 13: 1985-86 Tritium in Surface Water .................... 50 1
1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 3 of 50 1 1 1 l L__ J
Introduction This represents the 1986 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS), located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas. This report covers the period from January 1 to December 31, 1986. Fuel loading began at WCGS on March 12, 1985. The operational phase of the Radiological Environmental Monitoring Program began with initial criticality on May 22, 1985, with the first detectable quantities of radioactivity reported in plant effluents in June, 1985. This report contains a description of the Radiological Environmental Monitoring Program conducted by Wolf Creek Nuclear Operating Corporation (WCNOC), results of sample analyses performed by Teledyne Isotopes, a discussion of monitoring program results, a discussion of program deviations and revisions, and a discussion of 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. Tritium from routine plant releases was detected in Wolf Creek Cooling Lake (WCCL) throughout the year at concentrations well below the Technical Specification reporting levels. Additionally, several activation products were seen in aquatic vegetation, shoreline sediment, and surface water in the immediate vicinity of the discharge cove of WCCL. Maximum concentrations, which were below Technical Specification reporting levels, were seen following a maintenance outage in April. Releases during and following the outage were higher than normally seen due to: (1) increased solubility of these nuclides, leading to increased concentrations in reactor coolant and (2) demineralizer problems which reduced removal efficiency for the activation products. Several corrective steps have been implemented which have reduced subsequent releases, including releases during the refueling outage (mid-October through mid-December), to normal levels. No tritium or other plant related nuclides were detected at the nearest downstream sampling points with unrestricted access (drinking water sampling location LW-40 at LeRoy and shoreline sediment sampling location NR on the Neosho River). A significant occurrence during 1986 which had a notable impact on several environmental sampling pathways was the Chernobyl accident in the Soviet Union on April 26. Fallout fission products from the accident were seen by the WCGS monitoring program beginning on the week of May 6-13 and continuing through late June. Pathways affected were airborne, ingestion (garden crops and milk), waterborne, and direct external exposure. 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 4 of 50
r ., i Segregation of nuclides due to the Chernobyl accident from those due to plant operation was fairly straightforward based on the following:
- the nuclides detected were fission products, which were not consistent with effluent nuclides released from WCGS,
- the period during which the results were seen was consistent with-the time of the accident and subsequent transport through the northern hemisphere, and
- the nuclides and concentrations detected were area-wide rather than localized near WCGS (i.e. the same nuclides and similar concentrations were seen at control locations and, based on conversations with the analysis laboratory, at other nuclear facilities across the United States).
No measurable impact on human exposure due to plant operation was seen for the year. 1 i 1 l l 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l l WOLF CREEK GENERATING STATION Page 5 of 50 l
I. PROGRAM DE!ERIPTION Radiological enviromental smples were collected according to the schedule in Table 3.12-1 of the Wolf Creek Technical Specifications and Section 4.0 of the Offsite Dose Calculation Manual. All samples .were collected by ICNOC's Environnental Manage ent Group and sent to Teledyne Isotopes for analysis.
'Ihe following is a description of the sangling and analysis program by individual pathways.
Airborne Particulates and Iodine: Low voltne air supling ptmps continuously collected particulate samples on 47am glass fiber filters; sangles were then drawn through charcoal cannisters to collect I-131. Filters and charcoal cannisters were changed out weekly, labeled, and shipped to Teledyne Isotopes for analysis. Total sangle voltme used to calculate air- concentrations was determined from the average of the initial and final sanpling flowrate and the total tine of collection. Gross beta analysis of the air particulate smples was performed approxinately 72 hours following filter collection to allow decay of radon and thoron daughter products. 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 conposites for each location and analyzed for ganma emitting isotopes on a Ge(Li) detector. In addition, individual filters were analyzed weekly during the month following the Chernobyl accident in order to detect and track airborne nuclide concentrations. Charcoal cannisters were routinely counted in groups of five to determine the presence or absence of I-131. Positive indication'of airborne I-131, which occurred for several weeks after the Chernobyl accident, was followed by separate analysis of individual cannisters for each location. Air sanples were collected from the three sectors with the highest ground level D/0, the nearby cmmunity of New Strawn, and a control location. Distances and directions to sampling locations from the plant site are listed in Table 1; locations are shown in Figure 1 (nearby locations) and Figure 7 (distant locations) . TLD: The thermoltmeinescent dosimeters (TLDs) used during 1986 were provided by Teledyne Isotopes. The TLDs consisted of rectangular teflon wafers impregnated with CaSO 4
- Dy. Prior to placenent in the field, the dosinieters 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 6 of 50
were annealed for at least one _ hour at between 250 and 260 degrees centigrade then placed in polyethylene pouches and holders containing 0.093 inches of copper snielding to filter out low energy radiation. tW field dosineters were exchanged with exposed dosineters and the exposed dosineters were returned to Teledyne Isotopes for analysis. Freshly annealed control dosineters were sent with the exposed TLDs to record transit exposures received during shiptent as well as system background of the TLD reader. Ganaia exposures were neasured on a Teledyne Model 8300 TLD reader; individual dosineters were then re-irradiated with a known exposure femi a Cs-137 source and read again to determine individual dosineter calibration factors. In general, TLDs were located 3-4 feet above the ground on utility poles; they were placed inside either plastic thermostat boxes or fiberglass air particulate sangler housings to protect them frmi moisture and tampering. Two TLDs were placed at each location to provide duplicate neasursents. TLD locations are shown on Figure 2 (nearsite) and Figure 7 (distant) . Table 1 provides distances and directions of each location from the WCGS site. Water: Monthly conposite sangles of drinking water were collected by continuously drawirg aliquots at two hour intervals. Grab sanples of surface water and ground water were collected on a monthly and quarterly basis, respectively. All sangles were sent to Teledyne Isotopes for analysis. All water sangles were analyzed on a Ge(Li) detector to determine if 93new miitters were present. In addition to gataia analysis, a radiochemical analysis for I-131 was performed on drinking water and ground water sanples. Gross beta analysis was also perfornied on drinking water samples. Trititan analysis was perforned by liquid scintillation counting on a quarterly basis for drinking water and ground water and on a monthly basis for surface water. Drinking water sanpling locations are at the water treatment stations for the towns of Burlington (upstream control location) and teroy (downstreau indicator location) . Surface water sanpling locations are at the John Redtond Reservoir outfall (control) and the Wolf Creek Cooling Lake discharge cove (indicator) . Ground water is sampled from three wells located hydrologically downgradient frmi Wolf Creek Coolirn Lake and frmi an upgradient control well. All water sanpling locations are listed in Table 1 and shown in Figures 3 and 7. 1986 ANNUAL RADIOLOGICAL EtNIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 7 of 50 1
T-Ingestion: Milk sanples w'e re collected on a semi-monthly basis from April through November (while milk aninals-were on pasture grass) and on a monthly basis the reainder of the year (when animals were on stored - feed) . Sarteles were sent to Teledyne Isotopes where radiochemical analyses for I-131 and ganaa analyses were perforned on each sanple. Locations are shown in Figure 4. Broadleaf vegetation sangles were collected nionthly during the growing season. Occasionally alternate sanpling locations were used when quantities of vegetation were limited, such as early or late in the growing season or during dry periods. Additionally, a sample of crops irrigated with water from the Neosho River downstream of Wolf Creek Cooling Lake was collected during harvest. The crop was intended for animal consmption only. All vegetation sangles were sent to Teledyne Isotopes and analyzed by ganaa spectroscopy. Locations are shown in Figure 5. Fish sanples were collected semiannually with several recreationally important species being sanpled. Sanples of boneless meat portions were sent to Teledyne Isotopes and analyzed by gmaa spectroscopy. tocations are shown in Figure 6. All sanpling locations above are listed in Table 1; distant locations are shown in Figure 7. (Fish sangling locations may vary satewhat from Figure 6 according to sanple availability.) Shoreline Sediment & Aquatic Vegetation: Semiannual shoreline sediment sm ples were collected from the Neosho river below the Wolf Creek-Neosho confluence and from a more conservative location on Wolf Creek Cooling Lake. Galas analysis was perforned by Teledyne Isotopes on each sangle. Sanpling locations are listed in Table 1 and shown on Figures 6 and 7. Aquatic vegetation sanples composed of rooted aquatic plants and algae were collected from the discharge cove area (location DC on Figure 6) of Wolf 1 Creek Cooling Lake. Ganaa isotopic analysis was perforned on each sample. 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 8 of 50
f II. DI!EUSSION N RESULTS Analysis results for all pathways are smaiarized 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. In this section, results are discussed by pathway and analysis type. Operational results are related to control location results, preoperational values, sources of radioactivity, and effluent releases when applicable. Trends or seasonal effects seen in the data are also discussed. Airborne Particulates and Iodine: Gross beta analysis results of weekly air particulate filters are listed in Table 3. The four indicator locations are averaged and plotted graphically with the control location results in Figure 8. No difference in indicator and control results is evident in Figure 8, showing no plant-related increase in gross airborne radioactivity concentrations. However, a significant peak occurs durity the month of May (5/6 through 6/3) as a result of the Chernobyl accident on April 26. The maximmi gross airborne concentration seen during this period was 0.34 pCi/ cubic meter at locations 32 and 40, which is approximately. ten times normal concentrations. Results of gama analysis of air particulate filters are smearized in Tables 4 and 5. Table 4 shows the results of routine analysis of quarterly composites. In addition to the routine schedule, individual filters were analyzed on a weekly basis followirg the Chernobyl accident in order to track air concentrations in a timely manner. Results of weekly analyses (excluding Be-7 and K-40) are shown in Table 5. Table 4 shows that naturally occurring Be-7 'and K-40 were detected regularly, as was the case during preoperational monitoring. In addition, I-131, Ru-103, Cs-134, and Cs-137 were seen on air particulate filters during the month of May as a result of the Chernobyl accident. Ru-103, Cs-134, and Cs-137 appear to have reached peak concentrations during the week of May 13-20. Results of analysis of charcoal filters for I-131 are smatarized in Table 6. of the1-131 was detected Chernobyl accident.at all locations during the month of May ag a result The peak concentration of 0.482 pCi/m was seen during the week of May 13-20. In comparing the I-131 concentrations during 'the week of May 6-13 frcm Tables 5 and 6 (i.e. results of particulate filter analysis compared to charcoal filter analysis), it appears that approximately 10-20% of I-131 was removed by the particulate filter prior to reaching the charcoal filter. Actual peak I-131 concentrations may therefore have been 10-20% higher than those listed in Table 6. l 1986 ANNUAL RADIOLOGICAL E!WIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 9 of 50 l 1
I Measured concentrations of the nuclides above appear to have been increased by washout due to precipitation during May. Excluding naturally occurring radionuclides and those related to the Chernobyl accident, no effects of plant operation were seen on airborne radionuclide concentrations for the year. TLDs: Quarterly ganma exposures measured at each location for 1986 are shown in Table 7. Values are the average of results for two dosimeters at each location, normalized to a 90-day standard quarter. Results from TLDs located near the plant site (less than approximately three miles distant) , which would be most sensitive to changes due to plant operation, were ccubined into quarterly averages. These nearsite averages, using locations 1, 2, 7, 8, 9, 10, 11, 12, 13, 14, 18, 26, 27, 28, 29, 30, 37, and 38, are cmpared to control TLD results in Figure 9. In addition, variation of the nearsite averages from the control location results are plotted graphically in Figure 10. Figures 9 and 10 also include preoperational data for cmparison. In Figure 9, quarterly exposures are somewhat higher for the second quarter of 1986 than for previous quarters. The increase is evident at control locations as well as at nearsite locations (confirmed in Figure 10 since no significant change in the nearsite/ control ratio occurs), indicating that the effect was area wide rather than due to plant operation. The most likely cause of this increase, which appears to be on the order of 2 or 3 mR, is the Chernobyl accident, although natural background variation may also have contributed. (Airborne sampling results show that most of the effect of the Chernobyl accident was during May.) The average daily ganna exposure rate at each location was plotted along with the preoperational average and range in Figure 11. It can be seen that 1986 exposure rates are well within the preoperational range. 1986 average exposure rates appear to be slightly higher than preoperational averages due to the Chernobyl accident. No changes to area ganaa exposure rates as a result of plant operation were identified. Drinking Water: Results of gross beta analysis of drinking water samples are listed in Table 8; Figure 12 depicts these results graphically along with preoperational values for comparison. 1986 ANNUAL RADIOLOGICAL ENVIRONMEllI'AL OPERATING REPORT WOLF CREEK GENERATING STATION Page 10 of 50 e
No significant difference between the indicator and control locations was found. Additionally, no increase over preoperational concentrations was evident, as is seen in Figure 12. No effect due to plant operation is identified in drinking water samples by gross beta analysis. This' conclusion is confirmed by the results of I-131, tritiuni, and ganna isotopic analyses; no other radionuclides were seen at detectable levels. Surface Water: Following the detection of tritium in Wolf Creek Cooling Lake (WCCL) during the fourth quarter of 1985, the sampling frequency was changed from quarterly to monthly in 1986 in order to track tritimi concentrations niore closely. The concentrations of tritimi seen in WCCL during 1986 are shown in Table
- 9. These concentrations are also displayed graphically in Figure 13. No detectable tritium concentrations were seen at the control location. It is assumed, therefore, that all tritium concentrations neasured in WCCL are due to plant operation, although in reality some natural and fallout tritium are also present in surface water.
Tritium concentrations in WCCL are correlated to a total liquid tritium release of 380 curies for 1986. As seen in Figure 13, concentrations seen to have approached an equilibrium of around 3000-4000 pCi/ liter for the year. However, variations in tritimi release quantities (which depend on plant operating modes, outages, etc.) and lake characteristics (such as increased lake flow-through during periods of increased precipitation) nay prevent the existance of a true, constant equilibrium value. All tritium concentrations detected were well below the Technical Specification reporting level. In addition to tritimi, Co-59 was detected by gama analysis of the 4/15/86 ECL sample. The concentration neasured was 9.51 + 3.75 pCi/ liter, which is near detection limits (nornelly 3-6 pCi/ liter) . This occurrence was related to 1.1 curies of released Co-58 during April. No treM is indicated by either release data or surface water ganna analysis results for the year. No other ganna enitters were detected in surface water during 1986. A hypothetical dose calculation was performed using NCGS Offsite Dose Calculation Manual and Regulatory Guide 1.109 nethodology, assmiing ingestion of surface water by the maximum individual. The maximmi iMividual dose from ingestion of tritium for one year at the neasured concentrations was 0.37 mren (child whole body dose) . The maximmi organ dose fran ingestion of the neasured Co-58 concentration for one month was 0.0087 nirem (adult GI-LLI dose) . These doses are well below WCGS Technical Specification limits. Actual doses frmi the first downstream drinking water 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 11 of 50 L-
location at LeRoy would be significantly smaller than these values, due to the intermittent outflow of WCCL and the large dilution factor encountered when WCCL outflow enters the Neosho River. As discussed in the section on drinking water results, no neasurable concentrations of plant related nuclides and no increase in gross beta concentrations were seen in drinking water at IaRoy for 1986. Ground Water: I-131 was detected in the 5/20/86 ground water sangle collected at location D-65 on Figure 3. The concentration measured was 0.91 + 0.23 pCi/ liter. This occurrence is considered a result of the Chernobyl accident since I-131 related to Chernobyl was also found in rain water, milk, broadleaf , vegetation, and air sanples collected during May and since an additional sangle from location D-65 on 6/26/86 contained no detectable I-131 (less than 0.3 pCi/ liter) . Assming ingestion of water at the measured concentration for one month, the maximm resulting organ dose would be 0.35 mre to the infant thyroid. I No other gama siitters or tritim were detected during 1986. No effect on ground water due to plant operation was identified. 1 Milk: All milk sanples analyzed for 1986 contained naturally occurring K-40 at concentrations consistent with preoperational levels. Yearly average concentrations goat's milk. were 1150 pCi/ liter for cow's milk and 1680 pCi/ liter for I-131 was detected in milk sangles from 5/13/86 through 6/24/86 following the Chernobyl accident. Table 10 lists the concentrations neasured, which reached a maxim m of 45 pCi/ liter at location S-3 on 5/28/86. Using singlifying, conservative assmptions, the maxinium organ dose from ingesting milk during this period could have been as large as 12 mrem to an infant thyroid as a result of the Chernobyl accident. Finally, Cs-137 was detected in four milk samples from both indicator and control locations. Concentrations, shown in Table 10,' were consistent with preoperational values which were due to long lived weapons fallout. The Chernooyl accident probably .also contributed to the measureable concentrations, three of which occurred in May and June. No other ganma mitters were detected and no plant related effects were j identified during the year. 1986 ANNUAL RADIOCDGICAL ENVIRONMENTAL OPERATING REPORT i WOLF CREEK GENERATING STATION Page 12 of 50 i
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i Food & Garden Crops: Gannia analysis of broadleaf vegetation sanples revealed naturally occurring ganna emitters K-40 and Be-7 at concentrations conparable to preoperational background levels. Ru-103, I-131, Cs-134, and Cs-137 were detected in broadleaf vegetation saaples during May and June as a result of the Chernobyl accident. Measured concentrations are shown in Table 11. No other gmaa miitters were detected for the reainder of the year, and no effects of plant operation were identified. ' In addition to broadleaf vegetation, a sanple of corn was collected which was irrigated with water frmi the Neosho River below the Wolf Creek Cooling Lake outfall. he crop was intended for animal consmption only. Ganaa analysis revealed naturally occurring K-40 to be present in the sangle, with no nuclides detected due to plant operation. Fish: Naturally occuring K-40 was found in all fish sanples collected with an average concentration of 3.4 pCi/ gram (wet weight) for both Wolf Creek Cooling Lake and the control location. Wese concentrations were within the range seen during the preoperational period. , No other gancia siitters were detected and no effects related to plant operation were identified. Shoreline Sedinents: Table j 1986. 12 shows ganna siitters ' detected in shoreline sediment sanples during i ) , Cs-137 (as fallout from weapons tests and from the Chernobyl accident) atrl i naturally occurring K-40, Ra-226, and Th-228 were measured at both smpling locations. Concentrations were consistent with preoperational levels. ' In addition, Co-58 was detected in WCCL at location DC on Figure 6. The l measured concentrations, shown in Table 12, are related to the release of ; 1.1 Ci of Co-58 during the April outage and correlates with Co-58 detection ! in surface water and aquatic vegetation sanples frm WCCL. Although sme ! degree of variability exists in analysis results, the second saple t { (collected on 10/28/86) appears to have a significantly lower concentration than the first sm ple (collected on 5/20/86), reflecting the return to snialler release quantities following the peak in April. No Co-58 was detected at location NR on Figure 7, which is accessible to the public. 1 i 1986 ANNUAL RADIOIDGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 13 of 50 l
Aquatic Vegetation: Algae and rooted aquatic plant sanples were collected frmi Wolf Creek Cooling Lake during 1986. Results of ganca isotopic analysis are shown in 1 Table 13. As shown in the Table, a conibination of naturally occurring radionuclides, fission products, and activation products were seen. Fission products detected were Cs-137, at concentrations consistent with preoperational levels due to fallout, and Ru-103 as fallout from the . Chernobyl accident. Activation products detected were Cr-51, Mn-54, and Co-60 (seen in the algae 4 saniple on 6/16/86) and Co-58 (seen in all sangles) . Measurenent of these i radionuclides is attributed to releases to the cooling lake, nainly during the April outage. As was the case with shoreline sedinents, Co-58 concentrations were significantly snaller in the later sanple on 10/28/86, reflecting a return to smaller release quantities following the outage. All concentrations attributable to plant operation were low and were from the innediate area of the discharge cove of WCCL. , 1 i j l I i I . 1, i { 1986 ANNUAL RADIOIDGICAL EtNIRONME!UAL OPERATING REPORT WOLF CREEK GENERATING STATION Pago 14 of 50 i i I
- III. Annual Land Use Survey Results and Program Revisions The 1986 Annual Land Use Survey was completed in Noveber. Information was collected using a conbination of mailed survey forms,' telephone contacts, and door to door contacts. Results of the survey, showing the distances to the nearest residences, milk producing aninals, and vegetable gardens within five miles of the plant site, are smaarized in Table 14.
No changes were made to sampling locations during 1986 as a result of the Land Use Survey. The only potential change identified was a possible new vegetable garden location for 1987 at 1.6 miles from WCGS in the NNE section (sector B). If incorporated, the new location would have a higher average D/Q value than the current sampling location G-1,1.6 miles from EGS in the SE sector. No revision will be nade, however, until the actual addition of a garden at this location is confirmed in 1987.
- Although not a formal revision to the Radiological Environmental Monitoring
. Program, analysis of surface water for tritime was perforned on a monthly basis rather than on quarterly coniposites of monthly samples in order to track tritium levels in WCCL nore closely during the year. In conjunction with the Land Use Survey, distances to residence locations were updated using more accurate inforaation from aerial photographs and U.S. Geological Survey naps. All corrections identified were minor and are reflected in both Table 2 and Table 14. Asterisks in Table 14 indicate
; actual location changes rather than corrections due to raieasurmient.
It should be noted that dose calculations are perforned for airborne and liquid pathways for a hypothetical individual at the exclusion area boundary in the highest X/Q and D/Q sector (for airborne pathways) and at the circulating water discharge point (for liquid pathways) . Calculated doses are therefore conservative, and not affected by changes in residence, milk animal, and broadleaf vegetation locations identified by the Annual Land Use Survey. t 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLP CREEK GENERATING STATION Page 15 of 50 i
IV. POIITGlltC PlWGtAM DEVIATIOREi Airborne Particulates and Iodine: Location 3 (3/11/86 - 3/18/86): Air leakage around an improperly sealed charcoal particulate cannister gasket may have allowed some air to bypass the filter, potentially resulting in an erroneously low concentration. Any effect appears to have been small, however, when comparing airborne particulate results at all locations during the sanie week. Location 3 (7/2/86 - 7/8/86): A small hole in the particulate filter was discovered upon reoval of the filter at the end of the sampling period; no 1 effect on results was apparent. Location 2 (9/2/86 - 9/9/86): Deposition on the particulate filter appeared to be less than normal; this was also reflected in the neasured i concentration, which was analler than at other locations during the same week. Although no inniediate cause was determined, the sangling ptmp was raioved from service and subsequent results were nornal. The above were isolated occurrences which did not indicate systmatic probleus and which did not result in deviations from the sampling schedule. Caution personnel, in handling the sangling assably was remiphasized to appropriate and potentially nialfunctioning equipnent was rmioved for { naintenance. Drinking Water tocation EM-15 (6/3/86 - 7/1/86): The composite sangle volme collected at the control location was smaller than normal due to a crack in the sanple line. The sanple size was sufficient for all required analyses to be. con.pleted, and no effect on results was apparent.
- The sanple line was repaired on 7/2/86; in addition, a suppleiental grab sanple was collected on 7/2/86 and analyzed.
Milk Milk was unavailable for the following locations during the year: tocation F-1 (6/24/86 through 8/12/86) Location P-2 (1/14/86 and 12/9/86) Location 0-5 (entire year) 1 Such unavailability occurs frequently since there are few milk animals and aiarginal milk production at these locations. No corrective actions were taken because there are no other identified locations producing milk for haan consuncti6n within five miles of the plant site. 1986 ANhUAL PADIOIDGICAL ENVIRONME21TAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 16 of 50
Food and Garden Crops 'l No samples were available at any locations' for the -April or Novenber samplirx3 periods ' described in the ' schedule in Table 1. No corrective actions were necessary since these samples are to be collected "when available" during the growing season. 1 l l 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING RENRT WOLF CREEK GENERATING STATION Page 17 of 50 L
o V. EPR Interlaboratory ryrison Program Results Teledyne Isotopes, contracted to perform analysis of radiological envirormental sangles for WCNOC, participated in the EPA Interlaboratory Conparison Program during 1986. Table 15 shows interceirparison test results for the year, including 1985 results which were not available for the 1985 Annual Report. The table lists the sanple nunber and date, the sangle media, the nuclide or analysis type, the known value reported by the EPA, the neasured value reported by Teledyne Isotopes (based on triplicate analysis), and the nornalized deviation from the known. (The nornalized deviation is determined by the difference in the measured result from the EPA reported known, divided by the stardard error of the mean as a neasure of the degree of precision. A normalized deviation larger than + 3.0 prompts followup action to identify the cause of the discrepancy.)_ Results are listed in the table only for sangle nedia and analyses types performed for WCNOC. Of the intercomparison results listed, only two exceeded a nornalized deviation of 3.0. During gross beta analysis of sample #399, a low energy beta correction factor overcompensated because the sangle mixture contained only a snall amount of low beta activity. 1he I-131 analysis of sangle #421 was perforned by an inexperienced technician who subsequently received additional training. No major problen was identified for any sangle medium or specific analysis. Past experience shows that corrective actions have been initiated prongtly when necessary. Overall performance of the analysis laboratory, as seen in the interemparison results, indicates good control of quality of analyses. 1986 ANNUAL PADIOIDGICAL ENVIRONMENI'AL OPERATING REPORT WOLF CREEK GENERATING STATION Page 18 of 50 t-
TABfES i
_- _ - . _ _ _ . _ -- _ . _ . . __ = . . _ _ _ _ _ __ . - _ _ _ _ _ _ _ _ _ _ .- _ . .m . TABLE 1 5h be RhDEOEDGIGL IBfVIROISEBfEhL DEDIll1GtING Penmet SRfWLIIIG Saarmt O> - x>t' Ntmber of San.ples hy MO Exposure Pathway art 1/or Sanple and Sanple tocations Sanpling and Collection Frequency Type and Frequency of Analysis
$o
- l. AIRBORNE
[{ a m -Q Radioiodine and Five locations, Continuous operation Radioiodine cannister. g t' Particulates station ntabers 2, of sanpler with saaple Analyze weekly for 3m 3, 32, arri 37 on collection as required for I-131. 8}m Z Figure 1 and location 40 (control) on by dust loadirg but at least weekly. Analyze for gross beta Figure 7. radioactivity approxi-i
- p.
t' n.ately 72 hours following filter change. Perforna gana.a isotopic analysis _on each sanple when gross Q beta activity is greater m than 10 tines the yearly 5 nean of control san.ples. d Perforn gan.a isotopic
$ analysis on con.posite
, (by location) once per m quarter.
8 4 2. DIRECT RADIATION 38 TID locations within Quarterly at each Ganc.a dose quarterly. 5-mile radius of site location. (station neber 1-38 on 9 Figure 2) and two offsite
$* locations (station 39 and 40 on Figure 7); two G TID dosineters at each o location.
m Ln C) I z.
r -. I l i l bU 1hBEJC 1 (Cont'd) G$ ny BADImnmCAL IIBIVIRGSBbHAL IWIIITORIGIG Pentman gg SWWLitC N E9 P&mber of Sanples
@ c- Exposure Path e y arti Sanplin3 an] Type and Frequency Mh and/or Sanple Sanple tocations Collection Fregtm_'y sa H r' 3. ETERBORNE of Analysis z8 Oy a. Sur face One upstrean, location enthly grab sanele mnthly gan.a isotopic r, near the John Rahsond and tritiun analysis, gn kservoir spillway, one
@ ~g san.ple from. Wolf Creek
" Cooling take discharge cove (see Figure 3) .
- b. Ground "three locations at Quarterly C-10, C-49, D-65, Quarterly gana.a isotopic
, anl tritita. analysis.
t, one control location o 'at B-12 (see Fi(Jure 3). N g c. Drinkiny Municipal water Nnthly cmposite* Monthly gross beta and 3 supplies at BurlinJton gana.a isotopic analysis. g (upstrean.) and teRoy Quarterly tritim. analy-l (downstrean.) . sis of composite sanele. E (See Figures 3 and 7) . 8 = g d. Sedin.ent from. One sanple fron. Wolf Sen.iannually Smiannual gana.a isotopic Shoreline Creek Cooling take analysis, discharge cove (see
.o Figures 6 and 7). $e
- e. Aquatic One sanple fron. Wolf Smiannually Sen iannual gana.a isotopic u Vegetation Creek Coolin3 take analysis, dischatge cove (see
& Figure 6).
ve o
- Composite sanplin3 shall be perforn.ed by collectanj an aliquot at intervals not excealinj 2 hours, i
l l l l '
f. l
\
l fi$ TABut 1 (Cont'd)
@$ i ny RhDintnr3 CAL IBRf1R(ESEBfthL M(BBIt0It111G Penrmaag gg SifE L II s 3 3 m mra m mc
*$ Ntm.ber of Sanples Og Exposure Pathway ard Sanpling ard Type ard Fregtoncy Eo ard/or Sanple Sanple tocations Collection Frequercy of Analysis
$o 6 4. INGESTION E
y a. Milk Samples frm. F-1, P-2, S=m.ia.onthly when Cana.a isotopic and t Q-5, ard a control ania.als are on pasture; l-131 analysis of each gg sample from. S-3 (see n.onthly at other tia.es. sanple, gg
- c +-+
Figures 4 arul 7). o b. Fish One sanple frca. Wolf Sam.iannually Cana.a isotopic analysis ! 3 Creek Coolirg Lake, on edible portions, sin.ilar sanple fron. John Rahord Ibservoir I spillway as control ' o (see Figure 6). E
.E 4 c. Ebod products BroM leaf vegetation Monthly duriry harvest. Gma.a isotopic analysis g samples at locations A-1, on edible portions.
G-1, ard R-1 (alternate) M on Figure 5; control at 3
- o S-4 on Figure 7.
One sample of crops At tia.e of harvest. Gana.a isotopic analysis irrigated with Neosho on edible portions. River water fron. locations
$a downstrean of the Neosho-2 Wolf Creek confluence w (location NR-D1 on Figure 1 o 7) .
i U' O _ . . . _ _ . _ _ . r. ._, _
gg 1hBER 2: SIWELING IACRTICII IEDWIRS, DI.91RICitS (adles) AaB DIMHCTICIE r cn n cn Q$ mz TLD arx] Air Particulate m c-x> Imation Distance / Location o" Nta.oer Distance / tocation Distance / Location Distance / Direction Nun.ber Es Direction Ntm.ber Direction Nun.ber Direction gS 1 1.4/N 11 1.6/E 21 3.8/S bo 2 31 3.0/WNW 2.7/N 12 1.8/ESE 22 4.1/S W U" o 3 3.0/NNE 13 1.5/SE 32 3.2/WNW oS 23 4.5/ N 33 3.7/W m 4 4.0/W E 14 2.6/SE 24 4.1/W W wQ 5 4.0/NE 15 4.5/ESE 25 34 4.0/W g r- 6 3.6/W 35 4.6/N w 4.4/ENE 16 4.2/E 26 2.6/W N
--e m 7 36 4.2/N 1.9/NE 17 3.6/SE 27 2.1/N c5 C
8 1.6/wE 18 3.2/SSE 28 2.8/SW 37 38 2.1/NNW E 9 2.0/ENE 19 4.0/SSE 29 2.6/SW 39 1.2/w 9 10 2.4/ENE 20 3.3/S 30 13.0/N E m 2.2/W 40 15.0/W W r-Grourskater Drinking m ter Surface mter O B-12 ! 2.2/WE BW-15 3.9/N MLISil 3.6/W I m C-10 2.8/W IM-40 ; 10/SSE DC 0.6/WW l $ C-49 2.9/SW d D-65 3.9/S o m Milk arx] Food Products o y A-1 1.4/N 0-5 3. 4/W F-1 1.3/ESE R-1 2.1/N w t G-1 1.6/SE S-3 >15.0/WW ! P-2 2.9jww S-4 15.0/WIM m, n , o j (D Fish Shoreline Saliments Aquatic WJetation Irrigatal Crops l N N l DC 0.6/ MM LC 0.6 /MW DC 0.6/WIM NH-D1 9.2/S Q JRR 4/W JRH 4/W m o NR 6.5/S l l l l ' t \. , ,- -- - - - . -
Table 3: 1986 GROSS BETA ANALYSIS RESULTS FOR AIR PARTICU[ ATE SAMPLES (pCi/CU. METER) INDICATOR [DCATIONS CONTROL DATE IDC 2 LOC 3 LOC 32 LOC 37 AVERAGE IDC 40 12/31 - 01/08 0.027 0.022 0.023 0.024 0.024 0.025 01/08 - 01/14 0.025 0.017 0.023 0.031 0.024 0.026 01/14 - 01/21 0.033 0.030 0.034 0.036 0.033 0.034 01/21 - 01/28 0.020 0.019 0.018 0.020 0.019 0.018 01/28 - 02/04 0.029 0.024 0.033 0.038 0.031 0.034
; 02/04 - 02/11 0.020 0.021 0.019 0.022 0.021 0.022 02/11 - 02/18 0.053 0.051 0.052 0.047 0.051 0.054 02/18 - 02/25 0.031 0.030 0.028 0.037 0.032 0.031 02/25 - 03/04 0.018 0.020 0.020 0.021 0.020 0.015 03/04 - 03/11 0.021 0.019 0.024 0.023 0.022 0.019 03/11 - 03/18 0.012 0.010(1) 0.013 0.012 0.012 0.017
] 03/18 - 03/25 0.017 0.018 0.016 0.019 0.018 0.017 03/25 - 04/01 0.022 0.019 0.026 0.023 0.023 0.022 04/01 - 04/08 0.023 0.016 0.019 0.017 0.019 0.016 04/08 - 04/15 0.023 0.020 0.021 0.021 0.021 0.018 04/15 - 04/22 0.021 0.016 0.017 0.016 0.018 0.017 04/22 - 04/29 0.022 0.016 0.021 0.021 0.020 0.018 04/29 - 05/06 0.024 0.025 0.023 0.017 0.022 0.023 05/06 - 05/13 0.082 0.046 0.078 0.061 0.067 0.072 05/13 - 05/20 0.310 0.240 0.340 0.270 0.290 0.340 1 05/20 - 05/27 0.200 0.180 0.230 0.210 0.205 05/27 - 06/03 0.042 0.230 i 0.034 0.070 0.038 0.046 0.034 06/03 - 06/10 0.024 0.018 0.023 0.027 0.023 0.026 06/10 - 06/17 0.027 0.021 0.032 0.028 0.027 0.029 06/17 - 06/24 0.031 0.022 0.026 0.030 0.027 0.028 l 06/24 - 07/01(2) 0.019 0.021 0.023 0.023 0.022 0.023 07/01 - 07/08(2) 0.033 0.025 0.025 0.030 0.028 0.040 07/08 - 07/15 ' O.018 0.017 0.020 0.008 0.016 0.016 07/15 - 07/22 0.022 0.013 0.017 0.019 0.018 0.016 07/22 - 07/29 0.029 0.027 0.023 0.029 0.027 0.017 07/29 - 08/05 0.031 0.020 0.032 0.030 0.024 0.031 08/05 - 08/12 0.022 0.022 0.022 0.021 0.022 0.023 08/12 - 08/19 0.034 0.022 0.030 0.032 0.030 0.030 i 08/19 - 08/26 0.046 0.037 0.043 0.041 0.042 0.036 08/26 - 09/02 0.028 0.020 0.030 0.027 0.026 0.027 (1) Light deposition on filter due to improperly sealed charcoal cannister gasket (2) End date/ start date was 7/2/86 for locations 2 and 3 1986 ANNUAL RADIOthGICAL E.WIROtMEtiTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 23 of 50
F-Table 3: 1986 GROSS BETA ABRLYSIS RESULTS FOR AIR PARTICUEATE SAMPLES (Cont'd) (pCi/CU. METER) . INDICA'IOR [DCATIONS CONTROL DATE IDC 2 LOC 3 LOC 32 LOC 37 AVERAGE [DC 40 09/02 - 09/09 0.011(3) 0.020 0.028 0.027 0.022 0.027 09/09 - 09/16 0.041 0.038 0.040 0.035 0.039 0.031 09/16 - 09/23 0.018 0.022 0.020 0.018 0.020 0.018 09/23 - 09/30 0.014 0.014 0.013 0.015 0.014 0.015 ! 09/30 - 10/07 0.014 0.016 0.016 0.014 0.015 0.012 10/07 - 10/14 0.026 0.018 0.019 0.023 0.022 0.022
'10/14 - 10/21 0.048 0.040 0.052 0.052 0.048 0.044 10/21 - 10/28 0.035 0.034 0.037 0.036 0.036 0.030 10/28 - 11/04 0.028 0.023 0.028 0.029 0.027 0.021 11/04 - 11/11 0.023 0.028 0.025 0.023 0.025 0.023 11/11 - 11/18 0.038 0.023 0.044 0.039 0.036 0.036 11/18 - 11/25 0.022 0.027 0.039 0.034 0.031 0.033 11/25 - 12/02 0.028 0.028 0.024 0.025 0.026 0.023 12/02 - 12/09 0.023 0.022 0.022 0.021 0.022 0.027 12/09 - 12/16 0.031 0.033 0.031 0.033 0.032 0.029 12/16 - 12/23 0.026 0.040 0.040 0.036 0.036 0.035 12/23 - 12/30 0.031 0.032 0.033 0.033 0.032 0.030 (3) Light deposition on filter 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 24 of 50
TABLE 4: GIME Al& LYSIS RESULTS T AIR PARTICU[ ATE CGtPOSITE SAMPLES (pCi/m3) Incation: 2 3 (control) 32 37 40 Be-7 1 QTR 0.0811 0.0529 0.0759 0.0727 0.0740 2 QTR 0.0847 0.0750 0.0879 0.0968 0.102 3 QTR 0.100 0.0873 0.111 0.0993 0.0867 4 QTR 0.0513 0.0525 0.0664 0.0712 0.0582 K-40 1 QTR --- 0.00941 --- --- 0.0133 2 QTR --- --- --- --- --- 3 QTR 0.0115 --- 0.00868 --- --- 4 QTR --- 0.00361 --- --- 0.00912 Ru-103 1 QTR --- --- --- --- --- 2 QTR 0.0122 0.00705 0.0122 0.0110 3 QTR --- --- 0.0104 4 QTR --- --- --- --- --- Cs-134 1 QTR --- --- --- --- --- 2 QTR 0.00524 0.00483 0.00524 0.00583 3 QTR --- --- 0.00641 4 QTR --- --- ---
\
Cs-137 1 QTR --- --- --- --- --- 2 QTR 0.0128 0.0103 0.0146 0.0156 3 QTR --- --- 0.0144 4 QTR --- --- --- --- --- i l 4 1986 ANNUAL RADIOIDGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION l Page 25 of 50 l l l
TABLE 5: WEEKLY GAlem ANALYSIS OF AIR PARTICU[ ATE SAMPLES FOLI4 WING THE CHERNOBYL ACX:IDENT (pci/m3) (control) Incation: 2 3 32 37 40 I-131 May 06-13 0.0268 --
;0.0207 --- ---
May 13-20 --- --- --- --- --- May 20-27 --- Ru-103 May 06-13 --- 0.0170 0.0154 0.0227 0.0170 May 13-20 0.0885 0.0646 0.138 0.105 0.115 May 20-27 0.100 0.0687 0.0965 0.110 0.0543 Cs-134 May 06-14 --- --- 0.0100 -- May 13-20 0.0302 0.0213 0.0485 0.0306 --- May 20-27 0.0273 0.0246 0.0299 --- --- Cs-137 May 06-13 0 . 11 6 --- --- 0.0169 0.0149 May 13-20 0.0676 0.0603 0.0982 0.0870 0.121 May 20-27 0.0670 0.0558 0.0632 0.0766 0.0892 i l I 1986 ANNUAL RADIO [DGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 26 of 50
M BLE 6: I-131 ARLifSIS OF CHMCOLL FILTERS (pCIA 3) Incation: 2 3 32 37 May 06-13 0.140 0.0941 0.121 0.142 0.150 May 13-20 0.429 0.333 0.482 0.308 0.441 May 20-27 0.266 0.221 0.206 0.363 0.355 May 27 - June 3 0.0264 0.0583 0.0412 0.0632 --- e s s ( I
,i .5 4
t 4 i t 4 \ , s
%~
)
1986 ANNUAL RADIOIDGICAL ENVIR0tNENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 27 of 50 4
,6 . _ , . _ . . _ , _ .2 , f .,
+
~
'DUK.E 7: 1986 T[D RESULTS N
(mR/90 Dus) QTR 1 QTR 2 QTR 3 QTR 4 AVG SDEV AW SDEV AVG SDEV AVG SDEV LOCATION 1 18.9 0.4 22.6 0.7 18.0 0.5 16.2 0.6
- 2 16.5 0.9 19.3 1.1 18.2 0.7 15.7 1.5 3 ; 17.6 0.6 20.4 0.9 16.6 0.6 15.6 0.6 4s .' 17.9 0.9 23.2 1.0 17.9 0.7 16.3 0.6 5f 17.2 0.9 20.2 0.7 17.0 0.4 15.5 0.7 6 16.6 0.5 19.9 0.4 16.6 0.7 15.0 1.5 7 15.5 a.5 19.6 0.8 16.3 0.6 13.7 0.4 8 17.3 0.4 19.7 0.8 17.4 0.7 15.6 1. 3 9 17.2 0.6 19.6 0.9 16.5 0.7 14.5 0.6 10 18.0 0.5 22.2 0.6 20.1 0.8 16.1 0.6 11 '19.2 0.8 22.4 0.7' 19.7 0.4 17.5 0.4
.i 12 16.0 0.4 21.1 0.9 17.6 0.4 16.1 0.9 13 18.0 1.0 21.9 1.1 19.0 1.2 16.4 0.9 14 18.0 0.4
- 21.9 0.6 19.2 0.6 16.5 0.6 15 17.6 0.6 21'.1 0.6 18.0 0.7 16.1 0.5 16 18.3 0.6 23.1 1.1 19.1 1.0 16.4 0.6 17 17.8 0.5 20.6 0.5 17.8 0.9 16.1 0.8 18 18.8 0.6 22.0 0.7 18.0 0.6 16.4 0.8 19 13.5 0.9 -21.8 1.1 18.3
' 0.7 16.8 0.6 20 17.7 0.4 21.7 0.6 23.0 1.8 16.2 0.5 21 15.6 0.6 18.9 0.7 14.5 0.4 14.2 0.6 22 .17.4 0.5 20.5 0.6 16.2 0.9 14.9 0.4 23 '17.5 0.5 20.4 1.3 17.2 0.4 15.6 0.6 24 19.0L 0.4 20.9 0.8 17.2 0.8 15.8 0.3 25 14.2 0.4 16.7 0.7 14.3 0.6 13.6 0.8 26 16.7 0.3 21.4 0.9 16.8 0.5 15.0 0.6 27 17.6 0.6 20.9 0.5 17.2 0.7 16.2 0.4 28 15.0 0.5 17.8 0.4 15.1 0.4 13.8 0.4 29 15.2 0.6 18.0 0.6 15.2 1.3 13 5 0.2 30 16.3 0.6 19.8 0.6 17.1 0.8 15.2 0.4 31 17.0 0.3 20.5 0.6 18.2 0.4 15.3 0.6 32 16.8 0.5 18.9 0.8 16.7 0.6 15.1 0.3 33 18.3 0.7 22.7 0.6 18.6 0.6 16.0 0.6 34 20.1 1.6 22.5 0.7 18.8 10 . 8 16.8 0.6 35 17.1 0.5 19.1 ' l.6 17.3 0.7 15.4 0.5 36 18.1 0.4 21.1 0.4 18.1 0.8 15.9 0.8 37 16.3 0.4 20.2 1.3 16.3 0.3 15.2 0.5 38 19.1 0.6 22.5- 0. 9, , 19.2 0.7 17.5 0.7 39 18.9 0.5 21.6 2.0- 17.4 0.7 16.1 0.6 40 16.4 0.6 18.7 1.0 15.1 0.5 13.9 0.6 AVG = Average of two TIDs at each location SDEV = Cartbined counting error of TLDs at each location >
y x. 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 2'8 of 50 l l a L' \
'IRBLE 8: GOSS BETA ANPLLYSIS RESULTS OF DRINKING IGLTER SAMPLES (pci/m 3)
M0tml IACATION % 40 [DCATION IBi-15 (Indicator) (Control) January 4.7 1 1.2 4.2 1 1.2 February 4.9 1 1.6 3.911.0 March 4.0 1 1.6 3.4 1 1.5 April 4.6 1 1.5 5.2 i 1.2 May 3.8 1 1.3 3.1 1 1.1 June 3.6 1 1.0 5.5 1 1.2 July 4.5 1 1.0 4.8 1 1.0 August 4.7 1 1.2 5.2 1 1.2 Septetber 6.1 1 1.4 7.311.5 October 5.8 1 1.3 7.1 1 1.4 Noveiber 4.411.4 7.0 1 1.5 Decetber 6.2 1 1.3 7.7 1 1.4 Range of Preoperational Values: 4.1 - 10.0 pCi/ liter 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ! WOLF CREEK GENERATING STATION Page 29 of 50
TABLE 9: 'IRITILM ARLYSIS RESULTS OF 't SURFACE WATER
.(pCi/ liter)
DATE DC I4 CATION (%CCL) PflSH IACATION (control) 01/21/86 2500 + 600
- (All less than 900 pCi/ liter) 02/18/86 2900 + 600 03/18/86 3700 + 600 04/15/86 3100 + 600 05/20/86 2900 + 600 06/17/86 6400 + 600 07/15/86 3900 + 500 08/19/86 2700 + 500 4
09/16/86 3500 + 600 10/21/86 3800 + 600 11/18/86 3600 + 600 12/16/86 3800 + 600 . l l 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 30 of 50
BBLE 10: GPMR EMITTERS IN MILK SAMPLES (pCi/ liter) DATE LOCATION I-131 C0tCENTRATION(1) Cs-137 C0tCElfrRATION( } 05/13/86 F-1 6.5 + 1.1 -- S-3 2.2 + 0.9 05/19/86 P-2 4.5 + 0.5 -- 05/27/86 F-1 43 + 1 6.71 + 3.30 P-2 1.0 + 0.2 -- 05/28/86 S-3 45 + 1 7.20 + 3.62 06/10/86 F-1 3.1 + 0.4 P-2 0.90 + 0.28 -- S-3 12 + I -- 06/24/86 S-3 2.4 + 0.2 6.12 + 3.37 11/25/86 P-2 -- 7.88 + 4.09 (1) Due to fallout frcxn Chernobyl accident I ) Due to fallout frcxn previous weapons tests and/or Chernobyl accident 1986 ANNUAL RADIOLOGICAL ENVIROtEENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 31 of 50 o
i TABLE 11: GAf9E At& LYSIS RESULTS OF BRQ4DLEAF i VBGETTATION SAMPLES (pCi/ gram - wet weight) LOCATION DATE Ru-103 III I-131 III Cs-134 III Cs-134(2) A-1 05/28/86 0.0282+0.0150 0.203+0.100 - 0.0357+0.0108 R-1 05/28/86 0.0258+0.0104 - - 0.0261+0.0076 S-4 05/28/86 0.0379+0.0125 0.0204+0.0082 0.0251+0.0081 (control) G-1 06/24/86 - - - 0.0273+0.0149 (1) Due to fallout from Chernobyl accident II Due to fallout from previous weapons tests and/or Chernobyl accident 1986 ANNUAL RADIOWGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 32 of 50
MBLE 12: GM9R ANP1YSIS RESULTS OF SHORELIIE SEDIMElff SAMPLES (pCi/ gram - dry weight) IRTE IOCATION NIELIDE COtCENTRATION 05/20/86 DC K-40 13.0 + 1.9 Co-58 1.63 I 0.27 Th-228 2.0910.24 06/24/86 NR K-40 14.3 + 1.4 Cs-137 0.0537 + 0.0294 Ra-226 2.32 + 0.61 Th-228 1.3410.13 10/28/86 DC K-40 13.8 + 1.4 Co-58 0.262 + 0.053
~
Cs-137 0.220 ~ 0.039 Ra-226 1.99 + 0.58 Th-228 1.4510.15 11/17/86 NR K-40 16.4 + 1.6 Ra-226 2.17 I 0.60
~
Th-228 1.97 0.20 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 33 of 50 L
TABLE 13: GMem ANALYSIS RESULTS OF AQUATIC VEGE3RTION SAMPLES - [ocation DC of WJCL (pCi/ gram - wet weight) DATE VBGETATION NUCLIDE CONCENTRATION TYPE 05/20/86 Rooted Aquatic K-40 2.26 + 0.23 Plants Co-58 0.691 + 0.338 Cs-137 0.0207 + 0.0114 Th-228 0.109 + 0.022 06/16/86 Algae Be-7 0.49 + 0.17 K-40 1.0770.14 Cr-51 0.29 I 0.17 Mn-54 0.0591 + 0.0120 Co-58 2.18 + 0.22 Co-60 0.114 + 0.013 Ru-103 0.0344 + 0.0190 Cs-137 0.0589 I 0.0138 Ra-226 0.410 + 0.239 Th-228 0.186 _T 0.029 10/28/86 Rooted Aquatic K-40 1.30 + 0.13 Plants Co-58 0.0698 + 0.0094 i l 1986 ANNUAL RADIOIDGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 34 of 50 l
1RBLE 14: RESULTS OF 1986 IAIO USE SURVEY DIREETION DISTAtCE (MILES) TO NEAREST SEC'IOR FROM PLANT RESIDEtCE MILK ANIMAL GARDEN A N 1.4 None 1.4 8 NNE 1.8* None 3.1 C NE 1.9 None 1.9 D ENE 2.1 2.3- 2.1* E E 1.8 None 1.8 F ESE 1.6 1.3 1.6 G SE 1.6 None 1.6 H SSE 3.l* None 3.1 J S 3.3 None 3.3 K SSW 2.6* None 4.1 L SW 2.1 None 2.6* M WSN 2.4* None 2.4* N W 2.1 None 2.3 P WIM 2.9 2.9 2.9* Q NR 1.4 3.4 1.4 l R NNN 1.9** None 2.1 Indicates Change from 1985 Data.
** Part-tine residence.
l l l l l 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 35 of 50 l i j
'DLBLE 15: RESULTS T EER INTERIABORA'IORY COGERISON TEMS SAMPLE SA!!PLE EPA TELEDYNE NORMALIZED NUMBER DATE TYPE NUCLIDE RESULTS (+10) RESULTS (+10) DEVIATION 396 10/25/85 Milk I-131 42 + 6 36 + 2 -1.82 Cs-137 56 + 5 61 1 5 1.84 397 11/22/85 Water Gr. Beta 13 1 5 16 i 1 0.92 398 12/06/85 Water I-131 4516 47 1 2 0.58 399 10/21/85 Water Gr. Beta 75 + 5 96 + 3 7.27 Co-60 18 I 5 19 7 3 0.46 Cs-134 18 I 5 20 I 3 0.69 Cs-137 1815 18[2 0.00 402 01/24/86 Water Gr. Beta 7.0 + 5.0 7.3 1 0.6 0.11 405 02/14/86 Water H-3 5227 + 523 5266 1 58 0.13 406 02/07/86 Water Cr-51 38 + 5 <87 --
Co-60 18 7 5 19 + 1 0.23 Zn-65 40 I 5 46 7 6 2.19 Ru-106 0+5-
<40 --
Cs-134 30 + 5 26 + 4 -1.38 Cs-137 2215 22 I 5 -0.11 407 01/31/86 Food I-131 20 + 6 18 + 1 -0.58 Cs-137 15 1 5 19 I 1 1.38 408 02/28/86 Milk I-131 9+6 9+0 0.00 409 03/21//86 Water Gr. Beta 8+5 9+1 0.46 410 04/04/86 Water I-131 9+6 10 + 0 0.29 413 05/23/86 Water Gr. Beta 15 + 5 15 + 1 0.11 415 04/20/86 Water Gr. Beta 35 + 5 33 -0.81 Co-60 10 T 5 14 + 1 1.38 Cs-134 5+5 <6 - Cs-137 515 8+2 1.03 l 1986 ANNUAL RADIOIOGICAL ENVIRONMENTAL OPERATING REPORT ! WOLF CREEK GENERATING STATION Page 36 of 50 1 1 L
1RBLE 15: RESULTS OF EPA IlfrERIABORA't0RY COMPARISON TESFFS (Cont'd) SAMPLE SAMPLE SPA TELEDYNE NORMALIZED NUMBER DATE TYPE NLCLIDE RESULTS (+10) RESULTS (+10) DEVIATION 416 04/25/86 Air Gr. Beta 47 + 5 45 + 3 -0.81 Filter Cs-137 1015 1011 0.11 417 06/13/86 Water H-3 3125 + 360 3033 -0.44 418 06/06/86 Water Cr-51 0+5 <93 -- Co-60 66 + 5 67 + 1 0.23 Zn-65 86 + 5 88 + 8 0.58 Ru-106 50 + 5 <48 -- Cs-134 49 I 5 48 + 1
~
-0.46 Cs-137 1015 9+2 -0.23 420 07/18/86 Water Gr. Beta 18 + 5 15 + 5 -1.15 421 08/08/86 Water I-131 45 + 6
_ 27 + 1 -5.20 422 06/27/86 Milk I-131 41 + 6 41 + 1 0.00 Cs-137 3115 3912 2.77 424 07/25/86 Food I-131 30 + 6 26 + 1 -1.25 Cs-137 2015 2215 0.69 426 09/19/86 Water Gr. Beta 8+5 11 + 0 1.03 427 09/12/86 Air Gr. Beta 66 + 5 64 + 1 -0.58 Filter Cs-137 2215 2312 0.46 429 10/17/86 Water H-3 5973 + 597 _ 5900 + 100
-0.21 430 10/10/86 Water Cr-51 59 + 5 <113 --
Co-60 3175 30 + 1 -0.23 l Zn-65 8515 84 I 5 -0.34 Ru-106 { 74 + 5 <70 - Cs-134 28 I 5 27 + 3 -0.23 l Cs-137 44 _I 5 3.00 53 _7 1 l 432 11/21/86 Water Gr. Beta 20 + 5 21 + 2 0.34 I l 1 i l 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 37 of 50
FIGURES L- .
Figure 1: Airborne Particulate and .9adi:10 dine Sar.pling Locations E8LN P8 4061, REV 6/86 WILE 3[ I sNAare. Q
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\ ao G- AIRBCRNE PARTICULATES AND RADICIODINE SAMPLING LOCATIONS 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- WOLF CREEK GENERATING STATION Page 38 of 50 l
Figure 2: TLO Locatior.s tats pp.4c?-i, erv s/as
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.-TLD LOCATIONS 7-1986 ANNUAL RADIGLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 39 of 50
l Figure 3: Water Sampling Lc:ati:ns s EPLN 88-4C S-f REV 8/06
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6-ORINKING WATER E-SURFACE WATER A-GROUND WATER I 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 40 of 50
Figure 4: Milk Sampling Locations Eptespp.4gg.p, egy 4jg7 uskgs/ s SHAMPE/ Y AI f / \ NEW STR AWN. t uits [ g ~ I g '
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\ w 1986 ANNUAL RADIOLOGICAL EilVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 41 of 50
Figure 5: Broadleaf vegetation Sampling Locations f *LN PD 4 04 1. REV 4/ 0F WLES[ $ swAmpE / Q Y \ Al b / h NEW STaAWN. y . \ . :lN m // E
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Figure 6: Fish, Shoreline 3ediments, snd Aquatic Vegetation 3ar.;11ng L :ati:ns totw as-4n-i, =Ev e/es w$ss/ < l
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\ w AQUATIC PLANTS E-CONTROL LOCATION FOR FISH SAMPLING l
- 4-CONTROL LOCATION FOR SHORELINE SEDIMENT SAMPLING 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 43 of 50 L ___
Figure 7: Distant Sampling Locations c.a ....c3.... n .,..
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$-DRINKING WATER e-BRCADLEAF VEGETATICN, IRRIGATED CROPS T-SHORELINE SEDIMENTS S-TLD/ AIR PARTICULATES l 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION Page 44 of 50 l
l
l l l 1986 GROSS BETA AIR CONCENTRATIONS
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s 1985-86 TRITIUM IN SURFACE WATER Ra: n ,, WOIX CREEK COOLING LAKE DISCHARGE COVE gg 8000 - WM o" 10 to Ms 7000 - Na UN D "U 6000 - OE Um Sh 5000 - OM - MM z h $a E! R 4000 - r d a O O O w QQ M O O O
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O WCCL CONCENTRATION + DETECTION LIMIT
4 APPE30 ICES 1986 AIGERL RADIO [DGICAL ENVIROMENERL OPERATING REPORT WDLF CREEK GENERATING SIRTION l Prepared by TELEDYNE ISOTOPES 50 Van Buren Avenue Westwood, New Jersey Prepared for Wolf Creek Nuclear Operating Corporation l
TABLE OF C00ffDirS: APPEROICES Page Appendix A: Stumary tables in format of NBC Radiological Assessrtient Branch Technical Position, Revision 1, Noverbe r 19 79 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 Appendix B: Individual sa:tiple results Air Particulate and Charcoal Filters . . . . . . . . . . . . A-9 Composite Air Particulate Filters ............... A-19 Thermoltzninescent Dosimeters . . . . . . . . . . . . . . . . . . . . A-24 Irrigated Crops ................................. A-28 Fish ............................................ A-29 Food and Garden Crops ........................... A-32 Milk ............................................ A-38 Shoreline Sediments ............................. A-51 Aquatic Vegetation .............................. A-53 Drinking Water .................................. A-54 Ground Water .................................... A-60 Surface Water ................................... A-64 l A-ii
i l l l l l l 4 APPENDIX A:
SUMMARY
TABLES s-l 1 I 1 l l 1 i I I
- r. i i l I
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Nane of Facility Wolf Creek Nuclear Docket No. STN 50-482 Location of Facility Cof fey County, kansas Reporting Period Annual 1986 (County,5 tate) Analysis and Lower Limit Meditan or Pathway Number of Total Number of All Indicator Locations location with Highest Annual Mean Control Locations Nonroutine Sanpled of Analysis Detection ** Mean (f) Name **Mean ( f) **Mean (f) Reported (Unit of Measuremeat) Performed (LLD) ** Range Distance and Directions ** Range ** Range Measurements ** Station No. 40 - Air Gross (260) 3 35(208/208) 32 3.2 miles WNW 39(52/52) 37/(52/52) O Particulate Beta (8.0-340) (13-340) (X10-3 pCf/ (12-340)-
-T Cu.M.) 1-131 7 206(16/208) 40 15 miles WNW 315W/52) 315(3/52)
(26-482) (150-441) Gamma (20) (ISG;MI) N s
, a 5 -,_
Be-7 , 1 79(16/16) 44"3.2yh25 WNW
' 85(4/4) 80(4/4)
~ ~
0
- W
~ (50-110 /s ,
(66-111) (58-102) K-40 , 24 8(4/16) 02 2.7 miles N 12(1/4) 0 Y 11(2/4)
. (3.6-12) -
(9-13) 7 Ru-103 ,'1 11(4/16) X 3.2 miles WNW 12(1/4) 10(1/4) 0 (7-12) -- -- Cs-134 fD 5(4/16) '? -- 40 15 miles WNW 6(1/4) 6(1/4)
._ , (4.8-5.8) -- --
N Cs-137 0.5 1)(4/16) 37 2.1 miles WNW 16(1/4) 14(1/4) O p (10-16) -- -- Stations 39 and 40 External TLD (320) Radiation Quarterly 0.05 0.20(304/304) 11 1.6 miles E (mR/ day) 0.22(8/8) 0.19(16/16) 0 (0.16-0.22) (0.19-0.25) (0.18-0.21)
- t u
Nominal Lower Limit of Detection (LLD) ; Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) ^ _,, w e e a v -- - -m
- s - , ..w , . ~ . . s-
- 4. w g ,d ,f
- g. ,, Y
-f ENVIRONMENTAL RADIOLOGICAL MDNITORING PROGRAM
SUMMARY
Name of Facility Wolf Creek Nuclear Docket No. STN 50-482 Location of Facility Coffey County, Kansas Reportino Period Annua 0 1986 (County, State) Analysis and Lower Limit -- Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mcp . Control Locations , Nonroutine Sampled of Analysis Detection ** Mean (f) Name **Mean ifT "Mean (f) Reported (Unit of Measurement) Performed (LLD) ** Range Distance and Directions ** Range ** Range Measurements ** Irriaated Crop Gamma (1) NONE (pCl/a K-40 0.5 2.8(1/1) .NR-D1 9.2 miles 5 2.8(1/1) - 0 wet welaht) Y s f Nominal Lower Limit of Detection (LLD) Mean and rance based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) .
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Wolf Creek Nuclear Docket No. STN 50-482
-Location of Facility Coffey County, Kansas Reportina Period Annual 1986 (County,5 tate)
Analysis and Lower Limit Medium or Pathway Number of Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean ( f) Name **Mean ( fT **Mean ( f) Reported (linit of Measurement) Perfomed (LLD) ** Range Olstance and Directions ** Range ** Range Measurements ** J. Rednond Reservoir Fish Gamma (13) (pci/o) K-40 0.5 3.4(10/10) WCCL 3.4(10/10) 3.4(3/3) 0 (wet welaht) (2.5-3.8) (2.5-3.8) (3-3.7) , S-4 Food and Gamma (17) Garden Crops Be-7 0.1 0.5(11/11) 5-4 15 miles WNW (pci/q wet 0.7(6/6) 0.7(6/6) 0 (0.2-0.8) (0.3-1.4) (0.3-1.4) wetoht) K-40 0.5 4.0(10/11) R-1 2.1 miles NNW 4.3(1/1) 4(6/6) 0 (1.1-5.8) -- (2.8-6.5) > Ru-103 0.01 0.03(2/11) 5-4 15 milas WNW 0.04(1/6) 0.04(1/6) 0 L (0.026-0.028) -- -- I-131 0.1 0.2(1/11) A-1 1.4 miles N 0.2(1/11) -(0/6) O Cs-134 0.02 -(0/11) 5-4 15 miles WNW 0.02(1/6) 0.02(1/6) O Cs-137 0.02 0.03(3/11) A-1 1.4 miles N 0.04(1/5) 0.03(1/6) 0 (0.03-0.04) -- -- Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
r ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Wolf Creek Nuclear Docket No. STN 50-482 Location of Facility Cof fey County, Kansas Reportina Period Annual 1986 (County,5 tate) Analysis and Lower Limit Number of Medium or Pathway Total Ntmiber of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean ( f) Name **Mean ( f) **Mean ( f) Reported (linit of Measurement) Performed (LLD) **R ange ' Distance and Directions ** Range ** Range Measurements ** Station 5-3 Milk I-131 (54) 0.2 11(5/34) (pC1/t) 18(3/16) 15(4/20) 0 (0.9-43) F-1 1.3 miles ESE (3.1-43) (2-45) Gamma (54) K-40 100 1371(34/34) _1678(18/18) 0 1250(20/20) (656-1960) P-2 2.9 alles WNW (1310-l % 0) (1100-1490) 1-131 10 36(2/34) 48(2/20) 48(2/20) (9.8-62.5) S-3 15 miles WNW (20-76) (20-76) Cs-137 5 7(2/34) 8(1/18)
> 6.7(2/20) 0 (7-8) P-2 2.9 miles WNW --
(6-7) A Nominal Lower Limit of Detection (LLD) Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
.- . . _ . - _ -_. -. . - - . . . .. . _ _ . . ~ . - . _ - _ _. -
. --- -._. . . . ~ . . _ . . . - - . . - .
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Wolf Creek Nuclear Docket No. STN 50-482 Location of Facility Coffey County, Kansas Reporting Period Annual 1986 (County,5 tate) Analysis and Lower Limit Number of Medita or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine
,1.
Samplett of Analysis Detection ** Mean (f) Name **Mean ( f) **Mean (f) Reported (tinit of Measurement) Performed (LLD) ** Range Distance and Directions ** Range ** Range Measurements **~ Shoreline Sediment 4 (pCi/a (dry wetoht) Gamma (4) No Control K-40 0.5 14(4/4) 15(2/2) 0 (13-16) NR 6.5 miles 5 (14-16) -- Co-58 0.1 0.9(2/4) 0.9(2/2) 0 (0.3-1.6) DC 0.6 miles WNW (0.3-1.6) -- Cs-137 0.06 0.1(2/4) 0.2(1/2) '0 i (0.05-0.2) DC 0.6 miles WNW -- -- I m Ra-226 0.5 2.2(3/4) 2.2(2/2) O (2.0-2.3) NR 6.5 miles S (2.2-2.3) -- Th-228 0.04 1.7(4/4) 1.8(2/2) 0 (1.3-2,1) DC 0.6 alles WNW (1.5-2.1) -- 1 Nominal Lower Limit of Detection (LLD)
.Mean and range based upon detectable measurements only. Fraction of detectable measurements at specif fed locations is indicated in parentheses (f)
_ _ ~ _ i a ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
'i Name of Facility Wolf Creek Nuclear Docket No. STN 50-482 Location of Facility Cof fey County. Kansas Reporting Period Annual 1986 (County, State)
I Analysis and Lower Limit Medlun or Pathway Number of i Total Number of All Indicator Locations location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection *
- Me an ( f) Mane **Mean ( f) **Mean ( f) Reported (Unit of Measurement) Performed (LLD) ** Range Distance and Directions ** Range ** Range Measurements **
1 NO CONTROL ! Vegetation, Gauna (3) i Aouatic Be-7 0.1 0.5(1/3) DC 0.6 miles WNW ? (pC1/o wet -- 0.5(1/3) 0 ! weight) i K-40 0.5 i 1.5(3/3) DC 0.6 miles WNW l.5(3/3) 0 (1.1-2.3) (1.1-2.3) y Cr-51 0.1 0.3(1/3) DC 0.6 miles WNW 0.3(1/3) O Mn-54 0.01 0.06(1/3) DC 0.6 alles WNW 0.06(1/3) 0 Y Co-58 0.01 1.0(3/3) DC 0.6 miles WNW I.0(3/3) 0 m (0.07-2.2) } (0.07-2.2) Co-60 0.01 0.l(1/3) DC 0.6 alles WNW 0.l(1.3) 0 , Ru-103 0.01 0.03(1/3) DC 0.6 alles WNW 0.03(1/3) O Cs-137 0.01 0.04(2/3) DC 0.6 alles WNW 0.04(2/3) i 0 (0.02-0.06) (0.02-0.06) Ra-226 0.2 0.4(1/3) DC 0.6 miles WNW 0.4(1/3) 0 Th-228 0.02 0.l(2/3) DC 0.6 alles WNW 0.1(2/3) 0 (0.1-0.2) (0.1-0.2) ; 4 Naninal Lower Limit of Detection (LLD) Mean and rance based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
.t 4
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
Name of Facility Wolf Creek Nuclear Docket No. STN 50-482 i Location of Facility Coffey County, Kansas Reporting Period Annual 1986 (County,5 tate) 4 Analysis and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analysis Detection ** Mean ( f) Name **Mean (f) **Mean ( f) Reported (Unit of Measurement) Performed (LLD) **Ranoe Distance and Directions ** Range ** Range Measurements ** BW-15 Water I-131 (25) 0.5 -(0/12) N/A N/A -(0/13) 0 Drinkina - - (pCf/f) Gross (25) 2 4.8(12/12) BW-15 3.9 miles SW 5.4(12/12) 5.4(12/12) 0 1 Beta (3.6-6.1) (3.1-7.7) (3.1-7.7) Gamma (25) --
-(0/12) N/A N/A -(0/13) 0 k
> Triti m (8) 1000 -(0/4) N/A N/A -(0/4) 0 y - -
4 Water, 8-12 j Ground 1 (pC1/2) 1-131 (17) 0.5 0.9(1/13) D-65 3.9 miles 5 0.9(1/13) -(0/4) 0 Gamma (17) --
-(0/13) -- MA -(0/4)
Triti a (16) 1000 -(0/12) N/A N/A -(0/4) 0 i f I 4 Nominal Lower Limit of Detection (LLD)
** Mean and range based upon detectable menurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f) i
ENVIRONMENTAL RADIOLOGICAL MONIIC3ING PROGRAM
SUMMARY
Nme of Facility _ Wolf Creek Nucicar Docket No. STN 50-482 Location of Facility Cof fey County, Kansas Reporting Period Annual 1986 (County,5 tate) Analysis and Lower Limit Medfim or Pathway Total Number of All Indicator locations Number of Sampled of Analysis Detection Location with Highest Annual Mean Control Locations Nonroutine
** Mean ( f) Name
**Mean ( f) **Mean ( f) Reported (ifnit of Measurement) Performed (LLD) ** Range Distance and Directions ** Range ** Range Measurements **
Mush Water Surf ace Gama (24) (nCi/f) 00-58 5 9.5(1/12) DC 0.6 alles WNW 9.5(1/12) -- 0 Tritita (24) 1000 3570(12/12) DC 0.6 miles WNW 3570(12/12) -(0/9) 0 (?500-6400) (2500-6400) -- Y
=
Nominal Lower Limit of Detection (LLD)
** Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f)
APPENDIX B: DATA TABLES w.
WOLF CREEK NUCLEAR PPFRATING CORP FXPOSURE PATHWAY - Alp 00RNF AIP P AR TICUL ATE & CHAOCOAL FILTFRt STATI0'4 NUMRE* 02 COLL. TIME AP FILTER MID-COUNT CHA# COAL F ILTE R STADT STOP G705$ BETA TIME l-131 OATE DATE VOLUMF UNITS (PCI/CU. M l OAff TlWF IPCI/CU. M i 12/31 01/09 3.62F 08 CC 2.7 +-0. 3 E -62 01/10 L.T. 2. F-02 01/08 01/14 2.64E 08 CC 2.5 +-0.3 F-02 01/17 L.T. 3. E-02 01/14 01/21 3.15E 08 CC 3.7 +-0.4 F-02 01/25 L.T. 3. F-02 (a) 01/14 01/21 3.15E 08 CC 3.3 +.0.3 E.02 01/27 L.T. 4 F-02 01/21 01/26 2.99E OR CC 2.0 +-0 3 F-02 01/10 L.T. 3. E-02 01/29 02/04 2.9 3E OR CC 2.9 +-0.3 E-02 02/06 L.T. 3. E-02 02/04 02/11 2.9AE 08 CC 2.0 +-0.3 E-02 02/14 L.T. 2. E-02 02/11 02/1R 3.06E OP CC 5.3 +-0.4 E-0? 02/20 L.T. 2. E-02 02/15 02/25 2.925 08 CC 3.1 +-0.3 F-32 02/27 L.T. 3. E-02 02/29 03/04 3.06E 08 CC l.B +-0.3 E-02 03/06 L.T. 3. E-02 03/04 03/11 2.93E 08 CC 2.1 +-0.3 F-02 01/14 L.T. 3. E-02 01/11 03/18 2.9ff 08 CC 1.2 +-0.3 F-02 03/?G L.T. 3. E-02 03/19 03/25 2.98E 09 CC I.7 +-0.3 E-02 03/27 L.T. 3. E-02
'01/25 04/01 3.00E 05 CC 2.2 +-0.3 E-02 04/04 L.T. 3. F-02 04/01 04/08 3.02E 08 CC 2.3 +-0.4 E-02 04/11 L.T. 2. E-02 04/04 04/15 3.09E 08 CC 2.3 +-0.3 E-02 04/18 L.T. 2. E-02 l 04/15 04/22 2.94F 0* CC 2.1 +-0.3 E-02 04/29 L.T. 3. E-02 04/22 04/29 2.9tE 09 CC 2.2 +-0. 3 F- 02 05/01 L.T. 3. E-02 $* 04/29 05/06 2.998 09 CC 2.4 +-0.3 E-02 05/0P L.T. 3. E-02 l u) 05/06 05/13 2.94E 08 CC 4.? +-0.6 F-02 05/16 1.40+-0.46E-01
( 05/I3 05/20 3.03E 08 CC 3.1 +-0.1 E-01 05/22 4.29+-0.69E-01 , 05/20 05/27 3.23F 09 CC 2.0 +-0.1 E-01 09/31 2.66+-0.27E-01 ( 09/27 C6/03 3.15E 09 CC 4.2 +-3.4 E-02 06/09 2.64+-1.15E-02 l 06/03 06/10 2.90E 09 CC 2.4 +-0.4 E-02 06/17 L.T. 3. E-02 06/10 06/17 3.02E 08 CC 2.7 +-0.4 E-02 06/21 L.T. 5. F-02 06/17 06/24 2.92E 08 CC 3.1 +-3.4 E-02 06/27 L.T. 4. E-02 1 06/24 07/02 3.62E 08 CC 1.* +-0.2 E-02 07/03 L.T. 3. E-02 07/02 07/04 2.57F OP CC 3.4 *-0.5 E-02 07/11 L.T. 3. E-02 07/04 07/15 3.02E os CC I.8 +-0.3 E-02 07/10 L.T. 7. E-02 07/15 07/22 3.22E 08. CC 2.2 +-0.3 E-02 37/25 L.T. 4. E-02 07/22 07/29 3.23E 08 CC 3.2 +-0.4 E-02 09/02 L.T. 3. E-02 (a) 07/22 07/29 3.23F 08 CC 2.9 +-0,3 E-02 04/04 L.T. 5. E-02 07/29 08/0% 3.090 04 CC 31 + -0. 3 C -02 03/0* L.T. 2. E-02 09/05 09/12 3.0mE 08 CC 2. 2 + -0. 3 E- 02 09/14 L.T. 2. E-02 09/12 09/19 3.33F 08 CC 3.4 +-0.4 F-02 09/23 L.T. 2. E-02 04/19 08/26 3.lAE 08 CC 4.6 +-0.4 E-02 09/11 L.T. 2. E-02 05/26 09/02 3.16E 08 CC 2." +-0 3 C-02 09/05 L.T. 4. F-02 (a) Duplicate analysis.
-. -- . - _ . - - . _. .. . . . - - - . . - , . . . . .~, _ _ . _ . _ . _ _ - . . - - . . . _ _ .. - .~
4 WOLF CREEK NUCLEAD DPERATING CORP FXPOSURE PATHWAY - Al#?nRNE Alp PARTICULLTE % CHAOCOAL FILTEp5 q i STATION NUMBE# 02 I 1 COLL. TIME AP FILTER MI9-COUNT CHARCOAL FILTER START STOP GROSS SETA TIMF 1-131 DATE DATE VOLU4F UNITS (PC1/CU. M l DATF TIME (PCI/CU. M i 09/02 09/09 3.38E 08 CC 11 +-0.2 E-02 09/12 L.T. 1. E-02 09/09 09/16 2.99E 08 CC 4.1 +-0.4 E-02 09/20 L.T. 3. E-02 1 09/lA 09/23 1.02E DA CC 1.9 +-0.3 E-02 09/27 L.T. 3. E-02 a 09/23 09/10 3.03E 09 CC 1.4 +-0.3 E-02 10/04 L.T. 2. E-02 1 09/30 10/07 3.03E 08 CC 1.4 +-0. 3 F -02 10/12 L.T. 2. E-02 10/07 10/14 2.87E 08 CC 2.6 +-0.4 E-02 10/16 L.T. 4. E-02 j 10/14 10/21 2.96E 08 CC 4.9 +-0.4 E-02 10/25 L.T. 2. E-02 10/21 10/28 3.00E 08 CC 3.5 +-0.4 E-02 10/41 L.T. 3. E-02 10/28 11/04 2.93E 08 CC 2.8 + -0. 3 F -0 2 II/0P L.T. 3. F-02 11/04 11/11 3.04E 08 CC 2.3 +-0.3 T-02 11/15 L.T.. 2. E-02 11/11 11/I8 2.85E 08 CC 3.9 +-0.4 5-02 11/21 L.T. 3. E-02 11/18 11/25 2.94E 08 CC 2.2 +-0.3 E-02 12/01 L.T. 4 E-02 11/24 12/02 3.0TF 08 CC 2.8 +-0.3 E-02 12/05 L.T. 3. E-02 12/02 12/09 2.8AF 08 CC 2.3 +-0.3 E-02 12/12 L.T.- 3. E-02 12/09 12/16 3.06E 08 CC 3.1 +-0.3 E-02 12/1R L.T. 3. E-02 12/16 12/23 3 14F OA CC 2.6 +-0.3 E-02 12/11 L.T. 3. E-02 12/23 12/30 3.llE OR CC 3.1 +-0.3 F-02 01/06 L.T. 3. E-02
>e
>4 O
l 1 i 1
, t 4 i i
i
WOLF CREFK NUCLFAR OPERATING CORP FXPOSU4F PATHWAY - AIRB0pME AIP 84RTICUL4TE & CHADCOAL FILTER $ STATION NUM9F9 03 COLL. TIME AP FILTER "ID-COUNT CHARCOAL FILTFR STA*T STOP GSOSS META TIME I-131 OATE 04TE VOLUME UNITS IPC1/CU. M ) OATC T!*F IPC1/CU. N I 12/11 Ol/Ca 3.18E 04 CC 2.2 +-0.3 E-02 01/10 L.T. 2. E-02 01/04 01/14 2.39E 08 CC 1.7 +-0.3 E-02 01/17 L.T. 3. F-02 01/14 01/21 3.10F 04 CC 3.0 +-0.1 F-02 01/75 L.T. 3. E-02 01/21 01/29 2.89E 03 CC 1.9 +-0.3 F-02 01/10 L.T. 3. F-02 01/28 02/04 3.01E 09 CC 2.4 +-0.3 F-02 32/06 L.T. 3. f-02 02/04 02/11 3.03F 08 CC 2.3 +-1.3 E-02 02/14 L.T. 2. E-02 (a) 02/04 02/11 3.03E 08 CC 2.1 +-0.3 E-02 02/19 L.f. 4. E-02 02/11 02/18 3.04E 09 CC 5.1 +-0.4 E-02 02/20 L.T. 2. E-02 02/18 02/25 2.89E OR CC 5.0 +-0.3 F-02 07/27 L.T. 3. E-02 02/25 03/04 2.96E 09 CC 2. 0 +-0. 3 E- 02 03/06 L.T. 3. E-02 01/04 03/11 2.98E OR CC 1.9 +-0.3 E-02 03/14 L.T. 3. E-02 03/11 03/18 3.07F 08 CC 9.9 +-2.2 F-03 01/20 L.T. 3. E-02 03/1R 03/25 2.62E 08 CC 1.8 + -0. 3 E - 0 2 03/27 L.T. 3. E-02 03/25 04/01 1.20E 08 CC 1.* *-0.3 F-02 04/04 L.T. 3. E-02 04/01 04/08 3.13E 08 CC 1.6 +-0.3 C-02 04/11 L.T. 2. E-02 04/09 04/15 3.09F OR CC 2.0 +-0. 3 E -02 04/18 L.T. 2. E-02 04/15 04/22 2.94E 08 CC 1.6 +-0.3 F-02 04/25 L.T. 3. E-02 04/22 04/29 3.02E 04 CC 1.6 +-0.3 F-02 05/01 L.T. 3. F-02 3> 04/29 09/06 3.09E 04 CC 2.5 +-0.3 E-02 05/04 L.T. 3. E-02 j, 05/04 05/13 3.09E 08 CC 4.6 +-0.4 E-02 05/16 9.41+-3.96E-02
- r. 05/13 05/20 3.01F 08 CC 2.4 *-3.1 E-01 05/22 3.33*-0.56E-01 05/20 05/27 1 12E 08 CC !.9 +-0.1 E-01 05/31 2.2t+-0.24E-01 05/27 06/01 1 15F 08 CC 3.4 +-0.4 E-02 06/09 5.83+-2.13E-02 06/03 06/10 3.00E 08 CC 1.9 +-3. 3 E -02 06/17 L.T. 5. E-02 06/10 06/17 2.91E 08 CC 2.1 + -a. 3 E -0 2 06/21 L.T. 5. E-02 06/17 06/24 3 20F 09 CC 2.2 +-0.3 5-02 06/29 L.T. 2. E-02 06/24 07/02 3 33F OR CC 2.5 +-0.3 E-02 07/03 L.T. 1 E-02 07/02 07/08 2.61F 08 CC 2.4 +-0.4 E-02 07/10 L.T. 2. F-02 (a) 07/02 07/08 2.6tF 09 CC 2.5 +-0.4 E-02 07/11 L.T. 1 E-02 07/08 07/15 3.07E 08 CC 1. 7 +-0. 3 r.02 07/10 L.T. 6. F-02 07/15 07/22 3.026 09 CC 1.3 +-0.3 r-02 07/25 L.T. 4 F-02 07/22 07/29 3.07E 09 CC 2.7 +-0.3 E-02 08/02 L.T. 3. f-02 07/29 09/05 2.90E 09 CC 2.0 + -0. 3 E -0 2 OP/09 L.T. 3. F-02 08/05 08/12 3.02E 08 CC 2. 2 + -0. 3 E -02 08/14 L.T. 2. E-02 05/12 0e/19 3 11F 08 CC 2.2 +-0.3 F-02 04/23 L.T. 2. E-02 01/19 08/26 3.07E 08 CC 3.7 +-0.4 E-02 0F/31 L.T. 2. E-02 09/?6 09/02 3.01E 09 CC 2. 0 +-0. 3 E -02 09/05 L.T. 4. E-02 (a) Duplicate analysis
_ _ _ _ _ . _ _.m_... _ - . _ . _ , _ . . . , . _ _ _ _ _ _ _ . . _ . - , . . . . ~ . . _ _ _ . , _ . . . _ . . _ . - . . m___ _ ._-__-m h WOLF CREfK NUCLFAD ?Pf 0 AT ING COOP EEF05URE PATHWAY - AIRRORNr AIF PARTICULATF & rdARCOAL FILTF95 STATION NUNRF2 03 C OI. L . TIMF AP FILTER P19-count CHARCoat FILTER START ST38 C20%5 SFTA TIME l-1 31 OaTF DATF VOLUNF UNITS IPC1/fu. m i DATF TIPE IPC1/CU. M i 09/32 09/09 3.02E 08 CC 2.0 +-0 3 E-0? Ca/12 L.T. 2. F-02 09/09 09/16 3.03E 09 CC 3.P +-0.4 E-02 09/20 L.T. 3. E-02 09/16 09/23 3.01E 08 CC 2.2 +-0.3 T-07 09/27 L.T. 3. E-02 09/23 0*/30 3.03E 09 CC 14 +-0.3 F-02 10/04 L.T. 2. E-02 09/30 10/07 3.14E 08 CC l.6 *-0.1 F-02 10/12 L.T. 2. F-02 10/07 10/14 3.109 08 CC 1.8 +-0.3 E-02 10/16 L.T. 4. E-02 10/14 10/21 3.02F 09 CC 4.0 +-0.4 F-02 10/?5 L.T. 2. E-02 10/21 10/28 3 15F 05 CC 3.4 +-3.4 T-0? 10/11 L.T. 2. E-02 10/23 11/04 3.13F CR CC 2.3 +-0.3 E-02 11/0A L.T. 3. E-02 -> 18/04 11/11 3.19F 08 CC 2.P + -0. 3 F -0 ? II/IM L.T. 2. E-02 11/11 11/13 3.07E OS CC 2.4 + - 0. 3 F - 02 11/21 L.T. 2. E-02 (a) 11/11 11/19 3.0 TE 08 CC 2.3 +-0.3 E-02 11/24 L.T. 3. F-02 11/14 11/2% 3.07F 08 CC 2.7 +-0.4 T-02 17/01 L.T. 4. E-02 11/25 12/02 3.17F 08 CC 2.8 +-0.3 E-02 12/05 L.T. 3. F-02 12/02 12/09 3.24F 08 CC 2.2 +-0.3 E-02 12/12 .L.T. 3. F-02 12/09 12/14 2.80E 04 CC 3.3 +-0.4 F-02 12/19 L.T. 3.. E-02 12/16 12/23 2 84F 08 CC 4.0 +-0.4 E-02 12/31 L.T. 4. F-02 Y 12/23 12/30 2.90E 08 CC 3.2 +-0.4 E-02 01/06 L.T. 3. E-07 N (al Duplicate analysis. (
_ _ _ _ _ . = _ _ _ _ . _ . - . _ _ . _ - _ . _ __ _ _ . _ ._ _ . _ _ _ _ _ _ ___ _ .m_ , WOLF CREFK NUCLEAR 7PFDATING COOP EXPOSURE PATHWAT - AIR *0RNF Ale PARTICUL4TF & C4aeC0AL FILTFRS STATION NUM9E3 32 COLL. TIPE AP FILTER MID-COUNT CHARCOAL FILTER ST4RT ST3P CROSS META TIME l-131 04TF 04TE VOLUME UNIT 5 IPCI/CU. M I DATE TIME IPCI/CU. M i 12/11 01/04 1.74F 08 CC 23 +-0. 3 E -07 01/10 L.T. 2. E-02 OI/ca 01/14 2.79F 08 CC 2.3 +-0.3 F-02 01/17 L.T. 3. E-02 01/I4 01/21 1.35E 04 CC 3.4 +-0.1 F-02 01/75 L.T. 2. F-02 01/21 01/28 3.15E 08 CC 1.4 +-0.3 E-02 01/30 L.T. 3. E-02 01/28 02/04 3.20E 04 CC 3.3 * -0. 3 E - 02 02/06 L.T. 3. E-07 02/04 n2/II 3.20E OR CC 1.9 *-3.3 5-02 02/14 L.T. 2. E-02 02/11 02/18 1.21E 09 CC 5.2 *-3.4 E-0? 02/20 L.T. 2. f-02 02/l? 02/25 3.22E 08 CC 2.8 +-0.1 F-07 02/27 L.T. 2. E-02 02/25 03/04 1.33E 04 CC 2.0 +-0.3 E-02 01/06 L.T. 2. E-02 l 01/04 03/11 1.18F 04 CC 2.2 +-0.3 E-02 01/14 L.T. 2. F-02
- (a) 03/04 03/11 3.14E 08 CC 2.4 +-0.3 E-02 03/17 L.T. 4. E-02
! 01/11 03/19 1.27F on CC 1.3 +-0.1 E-02 03/20 L.T. 3. E-02 03/19 03/25 3.29F OR CC 1.6 +-0.2 E-02 01/27 L.T. 2. E-02 l 01/25 04/01 3.24E Oe CC 2.6 +-0.3 E-02 04/04 L.T. 3. E-02 l 04/01 04/09 3.09F 08 CC 1.9 +-0.3 F-02 04/11 L.T. 2. E-02 i 04/06 04/15 3.03E 09 CC 2.1 +-0.3 E-02 04/18 L.T. 2. F-02 04/19 04/22 2.94F 04 CC 1.7 +-0.3 E-02, 04/?5 L.T. 3. E-02 04/22 04/29 2.98E OR CC 2.1 +-0.3 F-02 05/38 L.T. 3. E-02 l >" 04/29 05/06 2.98E 09 CC 2.3 +-0.3 E-02 0*/09 L.T. 3. E-02 i
- d. 05/06 05/11 2.94E 08 CC 7.8 +-0.5 E-02 05/16 1.21+-0.33E-01 04 05/14 05/20 2.99F 09 CC 3.4 *-0.1 E-01 05/21 4.82+-0.7tE-01 05/20 05/27 2.95E OR CC 2.3 +-0.1 E-01 05/11 2.06+-0.?tF-01 (a) 05/27 06/03 4.02F 08 CC 6.7 +-0.5 F-02 06/08 L.T. 2. E-02 09/27 06/03 3.02E 09 CC 7.0 +-0.5 E-02 06/10 4.12+-1.70E-02 06/03 06/10 2.92E 08 CC 2.3 +-0.3 E-02 06/17 L.T. 3. E-02 06/10 06/17 2.97E Ca CC 1.7 +-0.4 E-02 06/21 L.T. 5 E-02 06/17 06/24 2 94E 08 CC 2.6 +-0.3 F-02 06/28 L.T. 2. E-02 06/24 07/0!4 2.90F 08 CC 2.1 +-0.3 E-02 07/03 L.T. 4. E-02 07/01 07/04 2.94E 08 CC 2.5 +-0.4 F-07 07/11 L.T. 3. E-02 07/09 07/15 2.99E DA CC 2.0 +-0. 3 E -02 07/10 L.T. 7. E-02 07/15 07/22 1.00E 04 CC 1.7 +-0.3 F-02 07/25 L.T. 4 F-02 07/22 07/29 3.02E 08 CC 2.1 +-0.3 E-02 08/02 L.T. 3. E-02 07/29 08/05 3.00E 08 CC 3. 2 *-0. 3 E -02 09/08 L.T. 3. E-02 OP/05 0R/12 2.99E 08 CC 2.2 +-0. 3 E - 02 09/14 L.T. 2. E-02 04/I2 08/19 3.05F 08 CC 3.0 *-0.4 F-02 08/23 L.T. 2. E-02 09/19 04/26 3.00F OR CC 4.3 +-3.4 E-02 09/11 L.T. 2. E-02 04/26 09/02 3.04E 08 CC 3.0 +-0.4 F-02 09/05 L.T. 4. E-02 (a) Duplicate analysis.
l - i
. _ . . - _ _ _ _ . . _ _ _ . _. _ . . _ . . _ . . _ _ _ __.____.m_. _ - . . _ . . . _ _ . _ _ _ . _ ___. , . . . _ _ _ . .__._....____ _ _ .
l WOL F CREEE MUCL E AR SPER ATING CORP EtPOSUer PAT 4WAY - 410RODNF AIF P4PTICUL4TF % CHARCOAL FILTrR$ STATION 4QMRFe 32 1 COLL. Tlaf Ap FILTFR M10-C7UNT CHARCO4L FILTER l STA9T STOP C#355 4f74 TIME l-131 DATF 04TF VOLUME UNITS f*Cl/CU. 9 5 34TF TIPE (PCl/CU. 9 I (a) n9/26 09/02 3.04F 08 CC 3,0 . 0.4 F-02 39/09 L.T. 4. F-02 ] C9/02 09/09 3.90F 08 CC 2.8 +-0. 3 E- 02 09/12 L.T. 2. E-02 09/09 01/16 4.05E 08 CC 4.0 *-4.4 F-02 99/20 L.T. 3.- E-02 2 09/16 09/23 3.00E 08 CC 2.0 *-0.3 E-02 09/27 L.T. 3. E-07 09/23 09/30 3.02E 08 CC 1.3 +-9.3 0-62 10/04 L.T. 2. E-02
- 0*/3e 10/07 3.05E n8 Cr 1.6 +-0.3 E-02 10/12 L.T. 2. F-02 r 10/07 10/14 3.OIF 08 CC 1.9 +-0.3 E-02 10/16 L.T. 4 E-02
, 10/14 10/21 3.03E 09 CC 5.2 +-0.4 F-02 10/25 L.T. 2. E-02 10/21 10/24 3.03E 08 CC 3.7 +-0.4 F-02 10/31 L.T. 3. F-02 10/2a 11/04 3.01E 08 CC 2.4 +-0.3 F-02 11/0* L.T. 3. E-02
- 11/04 11/11 3.10F 09 CC 2.5 + -0. 3 E - 02 11/15 L.T. 2. F-02 i 11/11 11/88 2.9FF 08 CC 4.4 +-0.4 E-02 11/21 L.T. 2. E-02 l- 11/14 11/25 3.02E 08 CC 3.9 +-0.4 E-02 12/01 L.T. 4 E-02 ,
11/2% 12/02 3.03E 08 CC 2.4 +-0.3 E-02 12/05 L.T. 3. E-02 j 12/02 12/09 2.91F 08 CC 2.2 +-0.3 E-02 12/12 L.T. 3. F-02 12/09 12/16 3.05E 08 CC 3.0 +-0.3 F-02 12/18 L.T. 3. E 1 (a) 12/09 12/16 3.05F 04 CC 3.1 +-0.3 E-02 12/70 L.T. 2. E-02 12/16 12/23 3.0IE 08 CC 4.0 +-0.4 E-02 12/11 L.T. 3. E-02
! }*- 12/21 12/39 3.07E 08 CC 3.4 *-C.4 C-02 01/06 L.T. 3. E-02 s
1 Sb 4 (a) Duplicate analysis. 1 ; 1 4 a
- -- _ - . - .- . - - - - - . . . . . - - . . . . - - - - - - - - . . ~ - - ..n. .~. - ~_ -. ..
( WOLF CRFEK NUCLsap 3PERAfl4G CORP e FEPOSUDE PATHW4Y - AIRRORNE Alp PARTICULATE & CHARCOAL FitTFR5 ! STAfl0N NtJMSER 37 5 COLL. TIMF MID-COUNT AP FILTE9 CHARCOAL FILTE4 l 574*T STOP GdO55 BETA flaF 1-131 DATF 04TF VOLUME UNITS l#CI/CU. M I 04TE TIME IPCl/CU. M i 12/31 01/04 1.47E 03 CC 2.4 +-0.3 F-0? 01/10 L.T. 2. E-02 01/09 01/14 2.60E 08 CC 3.1 +-0.4 E-02 01/17 L.T. 3. E-02 01/14 01/21 3.10E OR CC 3.6 +-0.3 F-02 01/25 L.T. 3. F-02 01/?! 01/78 2.95E 04 CC 2.0 +-0.3 5-02 01/10 L.T. 3. E-02 n1/24 02/04 2.98F 09 CC 3.9 +-0.4 E-02 02/06 L.T. 3. E-02 07/04 02/11 3.lRE 08 CC 2.2 +-0.1 E-02 02/14 L.T. 2. F-02 02/II 02/19 3.05E 08 CC 4.7 +-0.4 F-32 02/20 L.T. 2. F-02 02/18 02/29 2 91E 09 CC 3.7 +-0.4 E-02 02/27 L.T. 3. E-02 02/25 03/04 3.22F 04 CC 2.1 +-0.3 E-02 03/06 L.T. 3. E-02 03/04 01/11 2.938 04 CC 2.1 +-0.3 F-07 01/14 L.T. 3. E-02 03/11 03/84 2 87E os CC l.2 +-0.3 E-12 03/20 L.T. 3. E-02 01/14 03/25 2.83E 09 CC 1.9 +-0.3 E-02 01/27 L.T. 3. F-02 01/25 04/01 3.02E 0* CC 21 +-0.3 C-02 06#06 L.T. 3. F-02 04/01 04/05 2.94E OR CC 1.7 +-0.4 E-02 06/11 L.T. 2. E-02 (a) 04/01 04/08 2.94E 08 CC 2.0 +-0.4 E-02 04/14 L.T. 4 E-02 06/04 04/15 3.04E 09 CC 2.1 +-3.5 E-02 04/19 L.T. 2. F-02 04/1% C4/22 2.85E 09 CC 14 +-0.3 F-02 06/25 L.T. 3. E-02 04/?2 04/29 3 2tE 08 CC 2.1 +-0.3 E-02 04/01 L.T. 2. E-02 35 04/29 05/06 3.64E 09 CC 17 +-0.2 E-02 09/0e L.T. 2. E-02
- d. 04/06 05/13 3.69F OR CC 6.1 +-0.4 F-02 OC/le 1.42+-0.59E-01 ui esfg3 og/20 3.5RE 09 CC 2.7 +-0 1 E-01 0%/23 3.08+-0.94E-01 05/20 05/27 3.37F On CC 2.1 +-0.1 F-01 05/31 3.63+-0.36E-01 0%/27 c6/03 3.30F 08 CC 4.4 +-0.4 E-02 06/09 6.32+-2.37E-02 06/03 06/10 3.00E 09 CC 2.7 +-0.4 E-02 06/87 L.T. 6. E 0$/10 C6/17 3.02E 08 CC 2.9 +-0.4 E-02 06/21 L.T. 9 E-02 16/17 06/24 3.0*E 09 CC 3.0 +-0.4 F-02 06/24 L.T. 2. E-02 06/24 07/03 1.00E 08 CC 2.3 +-0.3 E-02 07/03 L.T. 4 E-02 07/01 07/08 2.75E 08 CC 3.0 +-0.4 E-02 07/11 L.T. 3. F-02 07/09 07/15 3.07E 09 CC 4.4 +-2.7 F-03 37/30 L.T. 6. F-02 07/15 07/22 3.07E 09 CC 1.9 +-0.3 E-02 07/2% L.T. 4 E-02 07/22 07/29 3.125 09 CC 2.9 +-0.3 E-07 09/42 L.T. 3. E-02 07/29 08/0% 2 95E 09 CC 3.0 +-0.1 F-02 OR/06 L.T. 3. E-02 09/0% 09/12 3.13F 04 CC 2.1 *-0.3 E-02 09/14 L.T. 2. E-02 08/12 09/19 3.03E 09 CC 3.2 +-0.4 E-0? 09/73 L.Y. 2. E-02 09/19 0R/26 2.92E 09 CC 4.1 *-0.4 E-02 09/31 L.T. 2. E-02 04/?6 09/02 2.95E 09 CC 2.7 +-0.4 c-02 09/05 L.T. 4 E-02 i 09/32 09/09 2.91F 08 CC 2.7 +-0.3 E-02 09/12 L.T. 2. F-02 09/09 09/16 2.94E 08 CC 3.5 *-0.4 E-07 09/20 L.T. 3 F-02 1
(a) Duplicate analysis, i
.. _._ m . . _ . _ . ,_._..__.._...-.._m. . .._._,_....._-.._...___,m .. . _ _ . . _ ~ _ _ _ , . _ _ . _ _ _ _ _ _ _ . . . . - . . _ . . _ ._. . _ . . ~ . . . . . . . . _ _ . _ . . . . .-. ..
I j WOLF CREFE N'JCLF AR SPFRATING C09P 4 ! EXPOSURE PATHWAY - AI490RNr AIR #ARTIC9LATF & CHAOCOAL FILTERS STATION NUM9f4 3F COLL. Yl"E AP FILTER Min-COUNT CHA2C94L FILTEP j STL*T ST3P GROS 5 8FT4 TimF l-131
- OATF DATE WOLUMF UMITS (PCl/CU. M I 74T5 TIwc (PCl/CU. M I 7 2
l j 01/16 09/23 3.17E OS CC I.s +-9.3 E-02 09/27 L.T. 2. E-02 l i 09/23 09/30 3.OTE 08 CC 1.5 +-0.3 E-02 10/06 L.T. 2. E-02 07/13 10/07 2.98E OR CC 1.4 +-0.1 F-92 10/12 L.T. 2. E-02 l 10/07 10/14 3.12F 09 CC 2.3 +-0.3 E-32 10/16 t.T. 4. E-02 ' , 10/14 10/21 3.IIE 08 CC 5.2 +-0.4 F-02 10/?5 L.T. 2. E-02 (a) 10/14 10/21 3.llE 04 CC 5.2 +-0.4 E-02 10/27 L.T. 3. E-02 10/21 10/29 3.20E 08 CC 3.6 *-0.4 9-02 10/31 L.T. 2. F-02
) 10/24 11/04 3 18E 08 CC 2.9 +-0.3 E-02 11/09 L.T. 3. F-02 I'
11/04 11/11 3.20F 08 CC 2.3 +-3.3 F-0? 11/15 L.T. 2. f-02 11/11 11/14 1.14E 08 CC 3.9 +-0.4 E-02 11/?! L.T. 2. E-02 , 11/I4 11/25 1 14E 09 CC 3.4 +-1.4 E-02 12/PI L.T. 4. E-02 ! , 11/25 12/02 3.12E 04 CC 2.5 +-0.3 E-02 12/0? L.T. 3. E-02 ; 12/02 12/09 1.02E 08 CC 2.1 +-0.3 E-02 12/12 L.T. 3. E-02 ,
- j. 12/09 12/16 3.075 08 CC 3.3 +-3.3 E-02 12/19 L.T. 3. E-02 !
t 12/16 12/23 3.04E 04 CC 3.6 +-0.4 E-02 12/11 L.T. 3. F-02 12/23 12/30 3.01E 08 CC 3.3 +-0.4 E-02 01/06 L.T. 3. E-02 j $' Os l (a) Duplicate analysis. 1 1 l t
)
1
_.___._m______ _ . - _ _ _ _ . - - _ _ _ ._. ,I wolf CRFEE NUCLFAR SPERATING CORP FEPO5URE PATHWAY - AIRRORNF AIE PAeTICULATE 4 CHARCOAL FILTFR5 STATIO1 NUMPF" 40 COLL. Tl4F AP FILTER Pl9-COUNT CHARCOAL FILTER STAoT STOP Ct055 SETA TIMF I-131 DATF DATE VOLUME UNITS IPCI/CU. 9 5 3ATF TIFF IPCI/CU. 4 9 J 12/31 01/08 3.5 7E 08 CC 2.5 +-0.3 F-07 01/10 L.T. 1. E-02 01/09 01/14 2.44F 09 CC 2.6 *-0.4 E-02 01/17 L.T. 2. E-02 01/14 01/21 2.988 08 CC 3.4 .-0.3 F-02 01/25 L.T. 1. E-02 01/28 01/28 2.92E 08 CC 1.8 +-0.3 E-02 01/.40 L.T. 2. E-02 01/28 02/04 2.95E 09 CC 3.4 *-0.4 F-02 02/06 L.T. 2. E-02 02/04 02/11 3.02E 08 CC 2.2 +-0.3 F-02 02/14 L.T. 2. E-02 02/11 02/19 3.01E 09 CC 5.4 +-0.4 E-02 02/20 L.T. 3. E-02 02/l* 02/25 3.02E 08 CC 3.1 +-0.3 E-02 02/27 L.T. 2. F-02 02/25 03/04 3.12E 08 CC 15 +-0.3 E-02 03/66 L.T. 1. E-02 03/04 03/11 2.84E 08 CC 1.9 *-0.3 E-02 03/14 L.T. 1. F-02 r 03/11 03/18 2.84E 08 CC 1.7 +-0.3 E-02 03/20 L.T. 2. E-02 l 03/19 03/25 2.80F 09 CC 1.7 +-0.3 E-02 03/27 L.T. 2. F-02
! 01/25 04/01 3.0lf 08 CC 2.2 +-0.3 E-07 04/04 L.T. 2. E-02 04/01.04/08 2 79E 08 CC 1.6 +-0.4 E-02 04/11 L.T. 1. E-02 04/08 04/15 3.23E 08 CC 1.9 +-0.3 E-02 04/19 L.T. 1. F-02 C4/15 04/22 3.07F on CC 17 +-0.3 E-02 04/25 L.T. 2. E-02 04/22 04/29 3.lif 08 CC 1.R + ^.3 F-02 05/01 L.T. l. F-02
?" 04/29 05/06 3.15E na CC 2.3 +-0.1 F-02 05/06 L.T. 1. E-02 i d+ (a) 04/29 05/06 3.15F 08 CC 2.3 +-0.3 E-02 05/10 L.T. 2. E-02
'4 05/06 05/13 2.98F 04 CC 7.2 +-0.5 F-02 05/16 1.50+-0.54E-01 05/13 05/20 3.09F C8 CC 3.4 +-0.1 E-01 05/25 4.41+-0.66F-01 05/20 05/27 3.12E 08 CC 2.3 +-0.1 E-01 0 5/ 11 3.55+-0.36E-01 05/27 06/03 3.20E 09 CC 3.4 +-0.4 E-02 06/C' L.T. 4. F-02 06/03 06/10 3.05E 08 CC 2.6 +-0.4 F-02 06/14 L.T. 3. F-02 06/10 06/87 3.34E 08 CC 2.9 +-0.3 E-02 06/21 L.T. 2. t-02 06/17 06/24 3.19F 08 CC 2.8 +-0.3 F-02 06/2e L.T. 2. F-02 l 06/24 C7/01 3.03F 04 CC 2.3 +-0.3 E-02 07/04 L.T. 2. F-02 s 07/01 07/09 1.IIE 08 CC 4.0 +-0.4 F-02 07/11 L.T. 2. E-02 07/98 07/15 3.00E 08 CC 16 +-0. 3 E -02 07/30 L.T. %. F-02 07/l5 07/22 2.e9F 08 CC 1.6 +-0.3 F-02 17/25 L.T. 2. E-02 07/22 07/29 2.92F 08 CC 1.7 +-0. 3 E -02 08/02 L.T. 2. F-02 07/29 08/05 3.10E 08 CC 1.1 +-0.3 F-02 08/ne L.T. 2. F-02 08/05 08/12 2.88E 08 CC 2.3 +-0.3 E-02 OS/I' L.T. 1. E-02 09/12 08/19 1.09F 09 CC 3.0 +-0.4 E-02 09/23 L.T. 2. F-02 08/19 08/26 2.92E 08 CC 3.6 +-0.4 E-02 08/11 L.T. 1. E-02 08/26 09/02 2.9tE 08 CC 2.7 +-0.4 F-02 39/05 L.T. 2. E-02 C9/02 09/09 2.92E 08 CC 2.7 +-0.3 E-02 09/12 L.T. 1. F-02 (a) Duplicate analysis.
t
.~ _ . . . _ _ _ _ _ . .._._.--.-.._a._.. _ . _ . _ - . _ _ _ . _ . - . .ms _ . _ _ _ . _ . - . _.._...m..m_. ~. .
. ~ . ~ - . . . . . . . - - . . ~ .
4
- WOLF CBEEK NUCLEAR OPERATING CORP i
i EXPOSURE PATHWAY - AIRPORNE ATP
- ARTICULATE & CHAPCOAL FilTFR5 i
STATION NUMBER 40 i" COLL. TIME AP FILTER MI9-CnUNT CHARCDAL FILTER START STOP CROSS BETA TIMF I-131 OATF DATF VOLUME UNITS (PCI/CU. 9 9 04TF.TIMF (PCI/CU. 9 9 09/09 09/16 3.03F 09 CC 3.1 +-0.4 E-02 09/2C L.T. 2. E-02 09/16 09/23 2.97E 04 CC 1.8 +-0.3 E-02 01/27 L.T. 2. E-02 (a) 09/I6 09/23 2.97E 08 CC 1.8 +-0.3 E-02 09/29 L.T. 3. E-02 09/23 09/30 3.02E 09 CC I.9 +-0.3 E-02 10/04 L.T. 1. F-02 09/10 10/07 3.05E 08 CC I.2 +-0.3 F-02 10/12 L.T. 1. E-02 .i 10/07 10/14 3.02E 08 CC 2.2 +-0.5 E-02 10/16 L.T. 2. F-02 ' 4 10/I4 10/21 2.97E 08 CC 4.4 *-0.4 E-02 10/25 L.T. 1. E-02 10/21 10/28 3.05E 09 CC 3.0 +-0.4 E-02 10/31 L.T. 1. E-02 1*/28 11/04 2.93E 04 CC 21 *-0.3 E-02 II/0P L.T. 2. E-02 11/04 11/11 3.09F 08 CC 2.3 +-0.3 F-02 11/15 L.T. 1. E-02 11/I1 11/18 2.93E 04 CC 3.6 +-0.4 F-02 11/21 L.T. 1. C-02. II/le 11/25 3.06E 08 CC 3.3 *-0.4 E-02 12/01 L.T. 2. E-02 i 11/29 12/02 3.04E 08 CC 2.3 + -0. 3 E -02 12/09 L.T. 2. E-02 ' 12/02 12/09 2.94E OR CC 2.7 +-0. 3 E- 02 12/12 L.T. 2. E-02 . 12/39 12/16 3.03E 09 CC 2.9 *-0.3 F-02 12/la L.T. 3. E-02 12/16 12/23 3.00E 08 CC 3.5 +-0.4 E-02 12/31 L.T. 2'. E-02 l 12/24 12/30 3.02E 04 CC 3.0 +-0.3 E-02 01/06 L.T. 2. F-02 i w 03 a (a) Duplicate arealysis. i i 4 l 4 6 4 4 1 ( 4 4 i a
, __.__--._.-.m..-. . _ _ . _ _ - _ . WOLF CREEK NUCI E AR OPF4ATING CORP FIPOSU9E PATHWAY - AIRPOPNE COPPOSITF AI9 PAPTICULATE FILTERS ^ IPCI/CU. M i STATION NUMPE8 02 DATF COLLFCTFC 12/31-04/01 04/01-07/02 n7/02-09/10 09/30-12/30 GAMMA $PECTRU4 ANALVSIS
#E-7 4.ll*-1.10E-02 8.47*-l.9%E-02 1.00+-0.InF-01 5.13+-0.68E-02 r-40 L.T. 1 E-02 L.T. 2. F-02 1.19+-0.33F-02 L.T. 6. E-03 vi-% 4 L.T. 4 5-04 L.T. 7. f-04 L.T. 4. 5-04 L.T. 3. E-04 CO-54 1.T. 1. F-03 L.T. 9 E-04 L.T. 5. 8-04 L.T. 4. E-04 FF-59 L.T. 2. E-03 L.T. 3. E-03 L.T. 2. E-03 .L.T. 1. E-03 CO-60 L.T. a. 4-04 L.T. 9. E-04 L.T. 6. *-04 L.T. 4 E-04 2N-65 L.T. 2. E-03 L.T. 2. F-03 L.T. 1. F-03 L.T. 7. E-04 2e-95 L.T. 1. E-03 L.T. 1. F-03 t.T. 6.. r-O' L.T. 5. E-04 00-103 L.T. 1. E-03 1.22+-0.19F-02 L.f. 7. E-04 L.T. 7. E-04 RU-136 L.T. 7. E-03 L.T. 1. E-02 L.T.. 3. f-03 L.T. 3. E-03 I-131 L.T. 8. E-03 L.T. 2. f-02 L.T. 2. f-02 L.T. 1. E-02 CS-134 L.T. 9 E-04 9.24+-1.74F-03 L.T. 5. F-04 L.T. 4. E-04 C5-137 L.T. 9 5-04 1 28+-0 16E-02 t.T. 5. F-04 L.T. 3. E-04 PA-140 L.T. 4. F-03 L.T. 6. E-03 L.T. 4. E-03 L.T. 3. E-03 CE-141 L.T. 2. E-03 L.T. 3. C-03 L.T. 1 E-03 L.T. 1. E-03 CE-144 L.T. 5. F-03 L.T. 6. E-03 L.T. 3. F-03 L.T. 3. E-03 f 4A-226 L.T. 1. F-02 L.T. 2. E-02 L.T. 7. F-03 L.T. 8. E-03 >* TH-229 L.T. 1. E-03 L.T. 2. E-03 L.T. 8. E-04 L.T. 7. E-04 to A
- -. - , - - . - - - - - . - - - . - . . _ - . - . . - . _ _ - . . . - - - _ _ - . _ . . - . _ . - _ _ . . . . - . - -- . . - - . .~. ~
? a I t l WOLF CREFE NUCLE AR SPER ATING COPP ErrosuaE PATHWAY - AIRBORNF COPP35tTE AIR PARTITULATF FILTFPS 1 *C I /CU. ft I i STATION NUM9En 01 1 I . l DATE COLLFCTE9 12/31-04/01 04/01-07/02 cT/07-09/10 09/30-12/30 GAMMA $ PFC T Rttp ANALYSIS BE-7 %.29+-0.69E-02 7.50*-1.6nF-02 g.73. l.3tF-02 5.02+-0.60E-02 r-40 9.41*-4.10E-03 t.T. 2. F-02 t.r. 3 r-02 3.61+-2.06E-03
*N-54 L.T. 5. E-04 L.T. 1. E-01 L.T. 9 E-04 L.T. c-03 L.T. 3. E-04 00-58 L.T. 5. E-04 1. L.T. I. F-03 L.T. 4. E-04 FF-59 L.T. 1. F-03 L.T. 3. F-01 L r. 3. F-03 1.
CO-60 F-01 L.T. E-03 L.T. 6. F-04 L.T. 1. L.T. 9. E-04 L.T. 3. E-04 i ZN-65 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. t-03 L.T. 6. E-04 i 2R-95 L.T. 6. F-04 L.T. 1. E-04 L.T. 1. F-03 L.T. 5. E-04 a PU-101 L.T. 7 F-04 7.05*-2.00F-03 L.T. 2. F-03 L.T. 6. E-04 I DU-106 L.T. 4 E-03 L.T. 1. F-02 L.T. p. g-ni L.T. 3. E-03 I-131 L.T. 5 F-03 L.T. 2. F-02 L.T. 3. g-02 L.T. 1. E-02 C5-134 L.T. c. E-04 4.83*-1.32E-03 L.T. 9 F-04 L.T. 4. E-04 C5-137 L.T. 5. F-04 1.03*-0.18E-02 L.T. 9. F-04 L.T. 3. E-04 eA-140 L.T. 3. E-03 L.T. 4. E-03 L.T. 3. c-02 L.T. 2. E-03 CE-141 L.T. E-03 L.T. 2. E-03 L.T. E-03 CE-144 L.T. 1.
- 3. E-03 L.T. 5. E-03
- 2. L.T. 1. E-03 L.T. 5. F-33 L.T. 2. E-03 4A-226 L.T. 9. E-03 L.T. 2. E-02 L.T. 1. E-02 L.T. 7. E-03 1 7 t8-22 8 L.T. 5. F-04 L.T. 2. E-03 L.T. 1. F-03 L.T. 7. E-04 e
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_ _ . _ _ . . _ _ _ _ . . ..___.___..__m_._ _ _ ____. _ ___..__ ___m__..-._ . . . _ _ _ . _ _ _ _ _ _ _ _ _ _ . . . . . . m_-. _ _ _ . __m.. . . .- . _ _ .. . . . . 4 WOLF CREEK NUCLEAR 3*ERATING CORP EIPrituRE P 4THW4Y - AIRRORNE 1 COM*3 SITE AIR P ARTICUL ATE FILTE*5 I I PC I /CIf. M* I j ST4710% NUM4F4 32 1 t DATE COLLECTED 12/31-04/01 04/01-07/02 07/01-09/30 09/30-12/30 CamMA SPFCT4J= ANALYSIS as-7 7.59*-0.76E-02 8.79*-2 536-02 J, r-40 L.T. 6. E-03 1.ll*-0.IIE-01 6.64+-1.12E-02 J L.T. 4. E-02 4.68*-4.74E-03 L.T. 2. E-02 un-54 L.T. 4. F-04 L.T. 1. E-03 L.T. 5 E-04 L.T. 6. E-04 ! CD-59 L.T. 4. E-04 L.T. 2. E-03 L.T. 6. E-04 L.T. 8. E-04 i FE-99 L.T. 1. E-03 L.T. 5. E-03 L.T. 2. E-03 L.T. 2. E-03 i C'l- 6 0 L.T. 3. E-04 L.T. E-03
' 2. L.T. 5 E-04 L.T. 6 E-04 2N-65 L.T. 8. E-04 L.T. 4 E-03 L.T. 1. E-03 L.T. 1. E-03
) 2R-95 L.T. 5. E-04 L.T. 2. E-03 L.T. F. E-04 L.T. 9 E-04
#U-103 L.T. 9. E-04 1. 22 +-0. 3 35-02 L.T. 1. E-03 L.T. 1. E-03
#U-106 L.T. 3. F-03 L.T. 2. E-02 L.T. 4 E-03 L.T. 7. E-03 1-131 L.T. 4 E-03 L.T. 3. E-02 L.T. 2. E-02 L.T. 2. E-02 Cs-134 L.T. 3. E-04 5.24*-1.92E-03 L.T. 6. E-04 L.T. 7. E-04 (5-137 L.T. 3. E-04 1.46*-0.25E-02 L.T. 5. E-04 L.T. 8. E-04
=A-14n L.T. 2. E-03 L.T. 6. E-03 L.T. 5 E-03 L.T. 5. E-03 j CE-141 L.T. s-03 L.T. 3. E-03
- 1. L.T. 2. E-03 L.T. 2. E-03 i CF-144 L.T. 3. E-03 L.T. 9. E-03 L.T. 3. E-03 L.T. 5. E-03 J cA-226 L.T. P. E-03 L.T. 2. F-02 L.T. 1. E-02 L.T. 1. E-02
! TH-279 L.T. 8. E-04 L.T. 3. E-03 L.T. 9. E-04 L.T. 2. E-03 1
4 e i PJ l >* l i e t f 1
_ _ _ _ - ._ _ .m_..._ __ . . _ _ __ _ -. . _ _ _ _ _ . _ _ _ _ _ . ~ _ _ _ ____--._..______ _ _. . . _ _ . . _ _ _ _ _ WOLF CRFEE NUCL84R 7PERATING TO9p ftFSSU4F P4THWAY - alam0PNr Cor*351TE 48' PAPTICULATE FILTFRS i I*CI/CU. P 1 l STATION NUM8Ft 17 1 1 DaTF COLLFCTED 12/31-04/01 04/01-3T/02 07/01-09/30 09/30-12/30 GAMMA SPFCT8UM ANALYSIS as-7 7.27+-0.73E-02 9.68+-l.9tE-02 9.91+-0.99F-02 n-so 7.12+-0.87E-02 L.T. 7. F-03 1.T. 3. F-02 L.T. 7. E-03 L.T. 1. E-02 MN-54 L.T. 4. E-04 L.T. 9. e-04 L.T. 4 En-99 L.T. 4 E-04 E-04 L.T. 6. E-04 L.T. l. E-03 L.T. 6. F-04 L.T. 7. E-04 FF-%9 L.T. 1 E-04 L.T. 2. F-03 L.T. CO-60 L.T. E-04
- 2. 8-03 L.T. 2. E-03
- 3. L.T. 6. E-04 L.T. 4 E-04 L.T. 7. E-04 ZN-6% L.T. 6. 8-04 L.T. E-03
] ZR-95 L.T. E-04
- 2. L.T. 4. F-04 L.T. 1. E-03
- 4. L.T. 1. E-03 L.T. 6. E-04 L.T. 3. E-04 i 20-103 L.T. 6. E-04 1.10*-0.17F-02 L.T. M. E-04 D0-104 L.T. 1. E-03 L.T. 1. E-03 L.T. 8. F-Oi L.T. 4 E-03 L.T. 6. E-03 I-131 L.T. 4. 5-03 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 w CS-It4 L.T. 4 E-04 5.83+-1.34F-03 L.T. 5. E-04 L.T. 6. E-04 r$-137 L.T. 4 E-04 1.56+-0.18F-02 L.T. 4. F-04 L.T. 8. E-04 94-140 L.T. 2. F-03 L.T. 5 F-03 L.T. 5 F-03 L.T. 5. E-03 CF-141 L.T. 1. 8-03 L.T. 2. E-03 L.T. 2. E-05 2.
CF-144 L.T. E-03 1.T. 3. 5-03 L.T. 5. E-04 L.T. 3. E-03 L.T. 3. E-03 j CA-226 L.T. 8. F-03 L.T. 1. E-02 L.T. 9. E-03 TH-22A F-04 L.T. 1. E-02 L.T. 8. L.T. 2. E-03 L.T. 9 *-04 L.T. 1. E-03 e DJ l 1 1 1 i 4 I
_ . . . _ . ., . _ - _ _ . - , . _ _ . - _ = _ _ _ _ , . _ _ -
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1, WOLF CREFK NUCLFAR OPERATIMC CORP FIPOSURE PATHWAY - AIR 90RNF COMPOSITE 4I9 P4RTICUL4TF FILTFR5 j . IPCI/CU. M I STATinN NUMBER 40 1 04TF CnLLECTF0 12/31-04/01 .p4/01-07/01 07/01-09/30 09/30-12/30 CAMMA 5prCTRUM ANALYSIS s , RF-7 7.40+-1.09E-02 1.02+-0.22F-01 9.67*-0.96F-02 5.82+-0.71E-02 E-40 1 33+-0.5aE-02 L.T. 4. 5-02 L.T. R. 5-03 9.12+-3.26E-03 "N 54 L.T. 7 E-04 L.T. 1. E-On L.T. 4 F-04 L.T. 4. E-04 C0-98 L.T. 9 F-04 L.T. 2. F-n3 L.T. 5. F-04 L.T. 5. E-04 F5-49 L.T. 2. E-c3 L.T. 6. F-0) L.T. 1. E-03 L.T, 1. E-03
! CO-60 L.T. 7. F-04 L.T. 2. F-03 L.T. 5. f-04 L.T. 4. E-04 2N-65 L.T. 2. E=O3 L.T. 4. E-03 L.T. 9. F-04 L.T. 1. E-03 IR-95 L.T'. 1. E-03 L.T. 2. E-03 L.T. 5. r-04 L.T. 6. E-04 20-103 L.T. 1. E-03 1 04+-0.30E-02 L.T. 8. E-04 L.T. 7. E-04 ; RU-In6 L.T. 7. E-03 L.T. 2. E-02 L.T. 3. F-03 L.T. 4 E-03 I-131 L.Y. 1. E-02 L.T. 3. F-02 L.T. 2. F-02 L.T. 1. E-02 l -
j C5-134 L.T. '7 E-94 6.41+-l.93E-03 L.T. 4. E-04 - L.T. 4. E-04 '
, CS-137 LaT. .9 F-04 1 44+-0.24E-02 L.T. 5. 5-04 L.T. 4. E-04 94-140 L.T. _3. s-o3 t.T, g. F-03 L.T. 4. F-03 L.T. 4. E-03 j CE-141 L.T. 2. 5-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 1. E-03 , CE-144 L.T. 6. F-03 L.T. 8. E-03 L.T. 3. E-03 L.T. 2. E ! RA-226 L.T. 2. E-02 L.T. 2. E-02 L.T. 9. E-03 L.T. 7. E-03 T '4- 2 2 ' L.T.' 2. E-0) L.T. 2. E-03 L.T. 9. E-04 L.T. 7. E-04 ] >
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WOLF CREEK NUCLEAR OPERATING CORPORATION EXPOSURE PATHWAY - AIR 80RNE THERM 0 LUMINESCENT DOSIMETERS (net mR/ day) STATION FIRST GUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER NUMPER 01/08/86-04/01/86 04/01/86-07/01/86 07/01/86-10/01/86 10/01/86-01/02/87 STA-01 0.211 2 0.002 0.261 t 0.0.007 0.197 2 0.004 0.176
- 0.004 STA-02 0.185 t 0.007 0.217 i 0.01 0.185 t 0.002 0.178 2 0.008 STA-03 0.197 2 0.005 0.226 1 0.009 0.186 i 0.002 0.168 2 0.005 STA-04 0.202 2 0.003 0.271 2 0. 038 0.201 2 0.006 0.176 2 0.004 STA-05 0.198 2 0.01 0.224 t 0.002 0.191 1 0.003 0.164
- 0.006 STA-06 0.182 t 0.004 0.218 2 0.003 0.187 t 0.006 0.163 2 0.02 STA-07 0.167 2 0.003 0.227
- 0.005 0.190 1 0.005 0.151 2 0.004 STA-08 0.203 t 0.003 0.220 t 0.003 0.193 2 0.006 0.171 t 0.015 STA-09 0.193 2 0.006 0.212 2 0.007 0.185 t 0.007 0.161 1 0.005 STA-10 0.200 t 0.003 0.244 2 0.005 0.236 t 0.008 0.176
- 0.005 STA-11 0.215 t 0.008 0.250 t 0.004 0.217 1 0.005 0.191 1 0.003 STA-12 0.201 2 0.002 0.238 t 0.004 0.193 2 0.003 0.173 t 0.002 STA-13 0.199 1 0.002 0.245 2 0.009 0.218 1 0.01 0.174 t 0.004 STA-14 0.200 2 0.004 0.247 2 0.006 0.211 t 0.006 0.175 t 0.003 STA-15 0.194 t 0.003 0.238 1 0.004 0.200 t 0.006 0.175 t 0.003 STA-16 0.208
- 0.005 0.261 t 0.008 0.205 t 0.005 0.178 t 0.006 STA-17 0.194 t 0.007 0.229 1 0.003 0.202 1 0.007 0.177 i 0.005 STA-18 0.207 2 0.006 6.244 t 0.001 0.200 t 0.006 0.181 t 0.006 STA-19 0.210 t 0.008 0.236 2 0.008 0.201 t 0.001 0.184
- 0.003 STA-20 0.200 t 0.004 0.240 t 0.006 0.224 t 0.002 0.181 1 0.003
.- __m. _ . _ _ _ . _ _ . ._ _ _ , . _ _ _ _ . _ . _ . _ _ _ _ _ _ . _ , . _ _ . _ ..m.___._ ..___ ___m.._.. _ __ .m_ _ . - _ _._ _ _ _ _.
j WOLF CREEK NUCLEAR OPERATING CORPORATIONM i i EXPOSURE PATHWAY - AIRBORNE THERM 0 LUMINESCENT DOSIMETERS (net mR/ day) i i STATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER NUMBER 01/08/86-04/01/86 04/01/86-07/01/86 07/02/85-10/01/85 10/01/85-01/08/86 i STA-21 0.177 2 0.008 0.194 t 0.002 0.162 t 0.002 0.162 t 0.008 STA-22 0.191 t 0.006 0.223 2 0.002 0.182 t 0.009 0.158 2 0.002 STA-23 0.196 t 0.007 0.232 2 0.012 0.189 1 0.001 0.172 2 0.007 STA-24 0.197 2 0.003 0.234 t 0.008 0.191 t 0.006 0.171 2 0.002
~
STA-25 0.158 t 0.005 0.188 t G.007 0.156 t 0.004 0.161 2-0.004 STA-26 0.192 2 0.003 0.214 2 0.008 0.186 1 0.003 0.162 2 0.002 d) 4 STA-27 0.197 2 0.005 0.228 2 0.005 0.190 1 0.005 0.180 t 0.004 STA-28 0.173 2 0.003 0.196 t 0.005 0.168 t 0.005 0.151 2 0.005 STA-29 0.173 2 0.004 0.205 t 0.005 0.172 t 0.012 0.152 2 0.002
; STA-30 0.182 2 0.004 0.214 i 0.005 0.184 i 0.008 0.170 t 0.003
! Y STA-31 0.196 t 0.002 0'225 2 0.004
. 0.212 t 0.005 0.168 2 0.004 STA-32 0.194 2 0.004 0.205 t 0.007 0.184
- 0.003 0.167 2 0.002 1
j STA-33 0.214 2 0.008 0.258 t 0.005 0.205 t 0.005 0.182 2 0.005 STA-34 0.199 i 0.005 0.240 t 0.008 0.205 1 0.004 0.194 i 0.006 i
. STA-35 0.193 2 0.001 0.207 t 0.016 0.190 2 0.004 0.172 1 0.004 STA-36 0.200 2 0.002 0.230 t 0.005 0.200
- 0.002 0.175 t 0.006 l
, STA-37 0.184 i 0.004 0.219 2 0.004 0.175 t 0.003 0.166 2 0.003 l
STA-38 0.217 2 0.005 0.238 t 0.009 0.208 1 0.004 0.194 1 0.004 STA-39 0.223 t 0.004 0.231 1 0.004 0.191 t 0.007 0.177 1 0.003 ' STA-40 0.184 t 0.007 0.199 2 0.01 0.166 2 0.005 0.154 i 0.005 i 4 i
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WOLF CREEK NUCLEAR OPERATING CORPORATION EXPOSURE PATHWAY - AIRBORNE THERM 0 LUMINESCENT DOSIMETERS (net mR/ day) STATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER-NUMRER 01/08/86-04/01/86 04/01/86-07/01/86 07/01/86-10/01/86 10/01/86-01/02/87 STA-01 0.209 i 0.005 0.243 i 0.005 0.204 2 0.004 0.183 i 0.006 STA-02 0.180 t 0.008 0.211 2 0.005 0.219 t 0.008 0.173 2 0.014 STA-03 0.193 2 0.006 0.228 t 0.005 0.182 1 0.007 0.180 t 0.005 STA-04 0.196
- 0.01 0.245 1 0.007 0.196 t 0.005 0.185 i 0.006 STA-05 0.185 t 0.005 0.224 2 0.008 0.187 i 0.005 0.181 1 0.004 STA-06 0.186 1 0.005 0.223 0.003 0.183 1 0.005 0.172 2 0.017 STA-07 0.178 2 0.006 0.208 t 0.006 0.172 2 0.004 0.155 t 0.002 STA-08 0.181 2 0.002 0.216 t 0.008 0.193 2 0.003 0.175 t 0.002 STA-09 0.189 2 0.004 0.223 i 0.008 0.182 2 0.004 0.161 i 0.003
.p STA-10 0.200 2 0.006 0.250 t 0.005 0.208 i 0.005 0.183 2 0.005 $ STA-II 0.212 1 0.004 0.247 1 0.007 0.221 1 0.002 0.199 1 0.003 STA-12 0.199 2 0.005 0.229 i 0.009 0.198 t 0.003 0.185 t 0.01 STA-13 0.200 t 0.012 0.242 2 0.009 0.205 t 0.009 0.190 i 0.009 STA-14 0.200 t 0.002 0.239 2 0.004 0.215 t 0.004 0.191 t 0.005 STA-15 0.197
- 0.007 0.230 t 0.005 0.201 i 0.006 0.183 t 0.006 STA-16 0.197 2 0.005 0.253 t 0.009 0.219 t 0.01 0.185 t 0.004 STA-17 0.201 t 0.002 0.228 t 0.005 0.194 t 0.007 0.182 t 0.007 STA-18 0.210 t 0.007 0.244 2 0.008 0.201 1 0.004 0.185 1 0.007 STA-19 0.202 2 0.007 0.248 1 0.01 0.206 2 0.008 0.190 t 0.006 STA-20 0.194 2 0.003 0.243 t 0.003 0.288 t 0.02 0.178 t 0.005 w _ _ _
._ __ - _ _.. _ _ ____._. _ __ _ __ . ._ _ _ _ ___- _ __ .- _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . ~ _ _ _ _ .. _. . __
WOLF CREEK NUCLEAR OPERATING CORPORATION
! .2 4
EXPOSURE PATHWAY - AIRBORNE - THERM 0 LUMINESCENT DOSIMETERS - (net mR/ day) j STATION FIRST OUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER
- NUMBER 01/08/86-04/01/86 04/01/86-07/01/86 07/01/86-10/01/86 10/01/86-01/02/87 1
1 STA-21 0.168 2 0.003 0.226 t 0.007 0.161 t 0.004 0.153 2 0.002 STA-22 0.196 1 0.003 - 0.233 1 0.007 0.178
- 0.004
{ 0.173 1 0.003 STA-23 0.192 2 0.002 0.221 0.007 ' 0.192 t 0.004 0.174 1 0.003 STA-24 0.225 t 0.015 0.231 t 0.004 0.193 t 0.006 0.181 1 0.002 STA-25 0.156
- 0.003 0.183 2 0.004 0.162 1 0.005 '
s 0.140 t 0.008 STA-26 0.180 t ~0.003 0.262 t 0.006 /7 +0.187 t 0.005 0.173 1 0.007 STA-27 -0.195 t 0.007 0.237 2 0.004 0.192 t 0.007 0.180 t 0.003 - STA-28 0.160 t 0.005 0.199 t 0.002 0.167 2 0.003 ' ~' ~ 0.156 1 0.002 STA-29 0.163 t 0. 0 0 7... 0.194 2 0.004 0.164 2 0.006 0.150't 0.002 , , i STA-30 0,}80 i 0.006 0.225 t 0.005 0.196 1 0.003 _ ~ 0.167 t 0.0d5 O STA-31 0.181 t 0.002 0,232 1 0.006 0.192 t 0.0C3 , 0.173 2 6.UO4 STAI32 0.179 t.0.005 0.215 2 0.007 0.187 2 0.007 0.169 t 0.004 , STA-33 0.192 2 0.003 0.246 i 0.004 0.207 i 0.006 0.173 1 0.004 STA-34 0.247 t 0.018 0.259 i 0.003 0.214 t 0.008
~
0.181 i 0.005 i STA-35 0.186 2 0.006 0.217 t 0.008 0.193 i 0.006 0;170 t 0.004 STA-36 0.202 t 0.005 0.238 2 0.002 ' 0.202 1 0.008 0.177 1 0.006 1 i STA-37 0.179 2 0.003 0.231 t 0.014 # 0,187 2 0.003 0.172 t 0.004 STA-38 0.207.t 0.005 0.262 t 0.004 0.218 1 0.007 0.195 t 0.007 , ! STA-39 0.196 2 0.005 ' O.249 t 0.022 0.195 t 0.002 0.181 t 0.007 STA-40 0.181 2 0.004 0,216 t*0.005 0.170.2 0.002 0.156 t 0.006 A
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l WOLF CREEE NUCLFAe DPERATING Copp EXPO $URE PATHWAY - INCESTION IRRICATED CROP fpCI/CM WET I STATION NUMSFe N'DI DATF COLLECTED 10/03 , l CAMMA SPECTRUM ANALYSIS BE-T L.T. 1. E-01 t W-40 2.79*-0.28E 00 , MN-54 L.T.' l. E-02 CD-98 L.T. 1. E-02 FE-59 L.T. 3. E-02 CO-60 L.T. 1. E-02 ZN-65 L.T. 3. E-02 29-95 L.T. 1. E-02
- RU-103 L.T. 1. E-02 ,
, RU-106 L.T. 1. E-01 I-131 L.T. 5. E-02 CS-134 L.T. 1. F-02 CS-137 L.T. 1. E-02 64-140 L.T. 3. E-02 CF-141 L.T. 3. E-02 CE-144 L.T. 8. E,02 44-226 L.T. 2. F-01 , , _
TM-228 L.T. 2. F-02 - a i , y - i
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a % s WMF C EEK NUCLFAR OPFPATING (ORP EXPG3040 PATHWAY - INCESTION
-A F I 5H 1*CI/GM WET I STATION NUMBEE , dCCL
+
DOTE COLLECTED 03/20 03/20 06/13 16/I3 10/08 CAME FISil (W ril) GAME FISII (BCR/ CAME FISit (LMB) CAME FISit (CitC) ROUGH FISil (BMB/SMB) GAMMA $PECTPUM A'l AL Y S I S WCR) BE-7 1.T. M. 8-02 L.T. 6 E-02 L.T. l. E-01 L.T. 3. E-01 L.T. 2. E-01
%-40 1.63+-0.36' 00 4.67+-0.3FF 0.9 3 59+-0.36F 00 3.2t+-0.32E 00 2.49*-0 25E 00 MN-54 L.T. 9. E-0) L.T. 6. E-03 L.T. 1. E-02 L.T. 3. E-02 L.T. 1. E-02 C0-59 L.T. l. E-02 L.I. 6. F-03 t.T. 1. F-02 L.T. 3. E-02 L.T. 2. E-02 FF-59 L.T. 2. E 12 L.T. 1. E-02 1.T. 4. E-02 L.T. 7. E-02 L.T. 4. F-02 CO-60 L.T. 1. T-02 L.T. 7. F-03 L.T. 2. F-02 L.T. 3. E-02 L.T. 2. F-02 2N-65 L.T. 2. 8-01 L.T. 2. F-02 L.T. 3. F-02 L.T. 6. E-02 - L.T. 4. F-02 24-9% L.T. I. E-02 L.T. 7. F-09 L.T. 2. F-02 L.T. 3. E-02 L.T. 2. E-02 R0-10 3 L.T. I. E-02 L.T. 7. E-0! L.T. 2. F-02 L.T. 4. E-02 L.T. 2. E-02 PU-IC6 L.T. 8. E-02 L.T. 5 E-02 L.T. 1. F-01 L.T. 2. F-01 L.T. 1. E-01 1-til L.T. 3. F-02 L.T. 2. F-02 L.T. 8. (-02 L.T. 2. E-01 L.T. 1. E-On 9
CS-134 L.T. 9 '-C3 L.T. 7. E-03 L.T. 1. F-02 t.T. 3. E-02 L.T. 2. E-02
. CS-137 L.T. 1. E-02 L.T. 7 E-03 L.T. 2. E-02 L.T. 3. E-02 L.T. 2. E-02 7
8tA-140 L.T. 1. f=02 L.T. 1. E-02 L.T. 4. F-02 L.T. 7. E-02 L.T. 6. E-02 y CF-141 L.T. 2. F-02 L.T. l. E-02 L.T. 4. E-02 L.T. 5. F-02 L.T. 3. E-02
- CE-344 L.T. 7. 5-02 L.T. 5. E-02 t.T. 1. E-01 t.T. 2. E-01 L.T. ^9 E-02
- y. RA-226 L.T. 2. F-01 't.T. 1. f-01 L.T. 3. E-01 L.T. 5 E-01 L.T. 3. E-01 TH-229 L . T . , 2, E-02 L.T. 1. F-02 L.T. 3. f-02 L.T. 5. F-02 L.T. 3. E-02 mu N __
N
WOLF CREEK NUCLEA9 3PF1 ATl4G CORP EXP05Ud? PATHWAY - INGFSTION F I 5H (*Cf/Ga WFT I STATION NUMRER WCCL DATF COLLFCTFD 17/09 10/09 10/09 10/21 10/21 CAME FISH (NE) GAME FISH (WHB) GAME FISH (BLC/ CAME FISH (STB) CAMMA SPFCTRUM ANALYSIS ROUGH FISH (CP) CHC) RF-7 L.T. 2. F-01 L.T. 2. E-ol L.T. 2. F-01 L.T. l. E-01 L.T. 1. E-01 E-40 3.53+-0.355 00 3.64+-o.34E 00 3.07+-0.31E 00 3.80+-0.3PE 00 3.l?+-0.32E 00 MN-54 L.T. 2. E-n2 L.T. 2. E-02 L.T. 2. E-02 L.T. 1. F-02 L.T. 1. E-02 rn-SP L.T. 2. F-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 1. F-02 L.T. l. E-02 FF-49 L.T. 4. F-02 L.T. 6. E-02 L.T. 5. E-02 L.T. 3. E-02 L.T. 3. E-02 C3-60 L.T. 2. E-02 L.T. 2. F-07 L.T. 2. F-42 L.T. 1. F-02 L.T. 1. E-02 ZN-6% L.T. 4. F-02 L.T. 5. E-02 L.T. 4. 8-02 L.T. 3. E-02 L.T. 3. E-02 2R-95 L.T. 2. E-02 L.T. 3. F-02 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. F-02 RU-103 L.T. 2. E-02 L.T. 3. E-02 L.T. 3. F-02 L.T. 2. E-02 L.T. 2. E-02 FU-106 L.T. 2. E-01 L.T. 2. E-01 t.T. 2. E-01 L.T. 9 E-02 L.T. 9. E-02 1-131 L.Te 9 E-02 L.T. I. F-01 L.T. I. F-01 L.T. 2. F-01 L.T. 2. F-01 C5-134 L.T. 2. F-02 L.T. 2. E-02 L.T. 2. F-02 L.T. 1. E-02 L.T. 1. F-C2 C5-137 L.T. 2. F-02 L.T. 2. E-02 L.T. 2. F-02 L.T. 1. F-02 L.T. 1. F-02 e4-140 L.T. 4. E-02 L.T. 7. E-02 L.T. 7. E-02 L.T. 6. E-02 L.T. 7. E-02 CE-141 L.T. 4 E-02 L.T. 5. F-02 L.T. 5. F-02 L.T. 4 F-02 L.T. 4. F-02 CE-144 t.T. I. c-01 L.T. 2. E-01 L.T. 1. F-01 L.T. P. E-02 L.T. 9. F-02
}" 9A-276 L.T. 3. E-01 L.T. 4. F-01 L.T. 3. F-01 L.T. 2. E-01 L.T. 2. E-Ol 04 TH-225 L.T. 4 E-02 L.T. 4. E-02 L.T. 3. E-02 L.T. 2. E-02 L.T. 2. E-02 o
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WOLF CRFFK NUCLEAP OPERATING COPP EXPOSURF *ATHway - INCESTION F 1 5 H (PCI/GM WET I STATION NOMRFR JRR DATE COLLECTED 06/24 !!/26 11/26 ROUGil FISit (SMB) CAME FISit (BCR) ROllGil FISil (CP) RADIOCHFMICAL ANALYSIS SAMPLE NR NR NR GAMMA SPECTRUM ANAL YSIS RF-7 L.T. 2. E-01 L.T. 2. F-01 L.T. 1. E-01 K-40 3.02+-0.30E 00 3.52+-0 35F 00 3.70+-0.37E 00 "N-54 L.T. 2. E-02 L.T. 2. -E-02 L.T. 2. E-02 CO-5R L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 FF-59 L.T. 5. E-02 L.T. 5. E-02 L.T. 4. E-02 CO-60 L.T. 2. E-02 L.T. 2. F-02 L.T. 2. E-02 2N-65 L.T. 4 E-02 L.T. 4. F-02 L.T. 3. E-02 29-95 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. F-02 RU-103 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. F-02 RU-ICS L.T. 2. F-01 L.T. 2. E-01 L.T. 1. E-01 I-131 L.T. 1. E-01 L.T. m. E-02 L.T. 6. E-02 C$-134 L.T. 2. F-02 L.T. 2. E-02 L.T. 2. F-02 C5-137 L.T. 2. C-02 4.7. 2. E-02 L.T. 2. E-02 aA-140 L.T. 5. E-02 L.T.' 3. F-02 L.T. 4.. E-02 CE-14I L.T. 4 E-02 L.T. 5 F-02 L.T. 3. E-02 CE-144 L.T. 1. E-01 L.T. 1. F-01 L.T. R. F-02 7 RA-226 L.T. 3. E-01 L.T. 4. F-01 L.T. 3. E-01 g TH-228 L.T. .3. E-02 L.T. 4 E-02 L.T. 3. E-02 4
WOL F CRFEK NUCLEAR OPERATING CORP EXPOSURL PATHWAY - INGESTION - FOOD /GRDN CROPS f*Cl/GM WET I STATION NUMBER 4-1 LETTUCE SWISS CHARD CABBAGE SWISS CHARD SWISS CHARD DATE CnLLECTFD 05/28 06/24 07/24 08/26 10/01 CAPMA SperTRUM ANALYSIS AE-7 5.52+-1.15E-01 5.51+-1.14E-01 4.39+-0.90F-01 4.01+-0.86E-01 8.42+-0.93E-01 r-40 L.T. 5. E-01 5.09+-0.5tF 03 2.a4+-0.28F 00 3.63+-0.36E 00 2.60+-0 26E 00 MN-54 L.T. 1. E-02 L.T. 1. E-02 L.T. 1. F-02 L.T. 9. F-03 L.T. 7. E-01 C9-94 L.T. 1. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 4 E-03 L.T. 9. E-03 FE-59 L.T. 3. F-02 L.T. 3. E-02 L.T. 2. F-02 L.T. 2. E-02 L.T. 2. E-02 CO-60 L.T. 1. E-02 L.T. 1. F-02 t.T. 1. E-02 L.T. 1. E-01 L.T. 8. E-03 2N-65 L.T. 3. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 2R-95 L.T. 2. E-02 L.T. 1. E-02 L.T. l. E-02 L.T. 1. E-02 L.T. R. E-03
#U-103 2.82+-1.50E-02 L.T. 2. F-02 L.T. 1. E-02 L.T. l. E-02 L.T. 1. F-02 RU-106 L.T. 1. F-01 L.T. 1. E-01 L.T. 9 E-02 L.T. 8. E-02 L.T. 7 F-02 1-131 2.03+-1.00E-01 L.T. 1. F-01 L.T. 2. F-02 L.T. 4 E-02 L.T. 5. E-02 CS-134 L.T. 1. E-02 L.T. 1. F-02 t.T. 1. F-02 L.T. 1. E-02 L.T. T. E-03 CS-13T 3.57+-1.08E-02 L.T. 1. E-02 L.T. 1. F-02 L.T. 1. E-02 L.T. 8. E-03 04-140 L.T. 4. E-02 L.T. 5 E-02 L.T. 1. F-02 L.T. 2. E-02 L.T. 2. E-02 CE-141 L.T. 3. E-02 L.T. 1. E-02 L.T. 2. F-02 L.T. 2. E-02 L.T. 2 E-02 CE-144 L.T. 9. E-02 L.T. M. F-02 L.T. 4 F-02 L.T. 6. F-02 L.T. 6. E-02 RA-226 L.T. 2. F-01 L.T. 2. E-01 L.T. 3. F-01 L.T. 2. E-01 L.T. 2. E-01 TH-228 L.T. 2. F-02 L.T. 2. F-02 L.T. 2. F-02 L.T. 2. E-02 L.T. 2. E-02 s
Cr4 N
i WOL F CREEK NUCLEAR OPERATING CORP EXPOSURE PATHWAY INGESTION - FOOD /GRDN CROPS ( PCl/GM TdE T I ST A TIT 8 NUMBE8 G-1 DATF COLLFCTFD 06/24 07/79 08/26 10/01 10/01 ENDIVE SWISS CHARD SWISS CHARD SWISS CHARD SWISS CHARD C&MMA SPFCTRUM AN4LYS15 PC-7 6.47+-2.llE-01 6 25+-1.02E-01 3.69+-1.ORF-01 6.45+-0.79E-01 5.37+-0.7sE-Ol(a) r-40 4.21*-0.4?E 00 5.72+-0.5fE 03 9.81+-3.58r 00 3.48+-0.35E 00 1.le+-0.32E 00 MN-54 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 7. E-03 L.T. 7. E-03 CO-58 L.T. 2. E-02 L.T. 9. E-03 L.T. 1. E-02 L.T. 8. E-03 L.T. e. F-03 FF-49 L.T. 6. F-02 L.T. 2. E-02 L.T. 3. E-02 L.T. 2. E-02 L.T. 2. E-02 CD-60 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. F-02 L.T. 8. E-03 L.T. T. E-03 FN-65 L.T. 4. E-02 L.T. 3. E-02 L.T. 3. E-02 L.T. 2. E-02 L.T. 2. F-02 2R-95 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. F-02 L.T. 8. E-03 L.T. 9. E-03 RU-103 L.T. 3. E-02 L.T. 1. F-02 L.T. 1. F-02 L.T. 1. E-02 L.T. 1. E-02 RU-106 L.T. 2. e-01 L.T. P. C-02 L.T. 9 E-02 L.T. 7. E-02 L.T. 6. E-02 1-131 L.T. 3. E-OI L.T. 3. E-02 L.T. 4 F-02 L.T. 5. E-02 L.T. 5. E-02 CS-134 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 8. E-03 L.T. *. F-03 CS-137 2 73+-1.49E-02 L.T. 1. E-07 L.T. 1. E-02 L.T. 8. E-03 L.T. 8. E-03 PA-140 L.T. 9 E-02 L.T. l. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 CE-141 L.T. 6. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 CE-144 L.T. 2. F-01 L.T. 9.- E-02 L.T. 5. E-02 L.T. 6. E-02 L.T. 6. E-02 RA-226 L.T. 4. E-01 L.T. 2. E-01 L.T. 2. F-01 L.T. 2. E-01 L.T. 2. E-01 TH-228 L.T. 4 F-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 s u u (a) Duplicate analysis.
WOLF CREEK NUCLEAR OPERATING CORP EXPOSURE PATHWAY - INGESTION- FOOD /GRDN CROPS (PCl/0M WET I 4 STATinte NUM8Fe C-1 DATE COLLFCTFD 10/29 GAMaA SPECTRUM ANALT5!$ GE-7 1.82+-0.67E-01 E-40 1.10+-0.lle no MN-54 L.T. 6. E-03 CO-54 L.T. 6. E-03 FE-99 L.T. 2. F-02 CO-60 L.T. 6. E-03 ZN-69 L.T. 2. E-02 2R-95 L.T. 7.. F-04 4 RU-103 L.T. 9. F-03 00-106 L.T. 6. E-02 I-131 L.T. 2. 8-02 CS-134 L.T. 6. E-03 C5-137 L.T. 6 E-03 PA-143 L.T. 1. F-02 CE-141 L.T. 1. E.02 CF-144 L.T. 9 E-02 PA-226 L.T. 1. E-01 TH-224 L.T. 1. E-02
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I . WOLF CREEK NUCL844 OPERATING COPP EXPOSURE PATHWAY - INGESTION - FOOD /GRDN CROPS (PCI/GM WET I STATION NUMBER R-1 04TE COLLFCTED 05/28 SAVDV CABBAGE GAMMA $ P E C TQljM ANALy${$ PF-7 2.82+-0.43E-01 E-40 4.26+-0.43F 00 MN-54 L.T. 8. F-03 CO-59 L.T. 9 E-03 FF-99 L.T. 3. E-02 CO-60 L.T. 6. F-03 7N-69 L.T. 2. F-02 2R-49 L.T. 1. E-02 00-103 2.sn.-l.04E-02 RU-104 L.T. 7. F-02 I-131 L.T. 1. f-01 CS-134 L.T. 1. E-02 CS-137 2.61+-0.76E-02 RA-140 L.T. 4. F-02 CE-141 L.T. 2. E-02 CF-144 L.T. 6. E-02 RA-?26 L.T. 2. F-01 TH-229 L.T. 2. E-02
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WOLF CREFK NUCLFAP 9PERATING CORP EXPOSURE PATHWAY - INGESTION - FOOD /GRDN CROPS IPC1/GM WFT I STATION NUNRER $-4 OATE COLLECTED 05/28 06/?4 07/7a Od/26 10/01 CABBAGE CABBAGE SWISS CHARD CABBAGE CABBAGE GAMMA SPFCTRUM ANALYSIS 9F-7 3.19+-0.94E-Ol 2.79+-l.64E-01 7.R6+-1.0?F-01 1.36+-0.14E 00 1.03*-0.10E 00 K-40 2.96+-0.30E 00 5.05+-0.91E OS- 6.4A+-0.65F 00 3.73+-0.37E 00 3 17*-0.32E 00
*N-54 L.T. 9 E-03 L.T. 2. F-0? L.T. 1. r-02 L.T. 1. E-02 L.T. 9. E-03 CO-59 L.T. 1. E-02 L.T. 2. E-02 L.T. I. E-0? L.T. 1. E-02 L.T. 9. E-03 FF-99 L.T. 3. E-02 L.T. 5. E-02 L.T. 3. E-07 L.T. 3. E-02 L.T. 2. E-03 CO-60 L.T. 1. E-02 L.T. 2. F-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 9. E-03 2N-65 L.T. 2. E-02 L.T. 3. F-02 L.T. 3. E-02 L.T. 2. E-02 L.T. 2. E-02 ZR-15 L.T. 1. E-02 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. F-02 L.T. 9. E-03 PU-103 3.79+-1 2SE-0? L.T. 2. E-0? L.T. 1. F-02 L.T. 7. F-02 L.T. l. E-07 RU-106 L.T.. 8. F-02 L.T. 1. E-01 L.T. a. F-02 L.T. 1. E-01 L.T. 7. E-02 I-131 L.T. 1. E-On L.T. 2. E-01 L.T. 2. F-02 L.T. 5. E-02 L.T. 9 E-02 CS-134 2.04+-0.82E-02 L.T. 1. E-02 L.T. 1. ?-02. L.T. 1. E-02 L.T. 6. E-03 C5-137 2.51+-0.81E-02 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 8. E-03 AA-160 L.T. 4 F-02 L.T. 6. E-02 L.T. 1. F-02 L.T. 2. E-02 L.T. 2. F-02 CE-141 L.T. 3. E-02 L.T. 5. E-02 L.T. 2. F-02 L.T. 3. F-02 L.T. 2. E-02 CE-144 L.T. 7 F-02 L.T. 1. F-01 L.1. S. F-02 L.T. 9 F-02 L.T. 6. E-02 RA-726 L.T. 2. E-01 L.T. 3. E-01 L.T. 3. E-01 L.T. 3. E-01 L.T. . 2. E-01 TH-228 L.T. 2. E-02 L.T. 3. F-07 L.T. 2. E-02 L.T. 3. E-02 L.T. 2. E-02
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t W1LF CREEK NUCLEAR 3PERATING CORP EXPOSURE PATHWAY - INGESTION - FOOD / GARDEN CROPS ; (PC1/GM WFT l ' STATION NUPSFR $-4 4 DATF COLLFCTED 10/29 CABBAGE CAMMA SPFCTOUP ANALYSIS i BE-7 5.44+-l.45E-01 K-40 2.79*-0.23F 00 MN-54 L.T. 2. F-02 ' CO-58 L.T. 2. E-02 FE-59 'L.T. 4 5-02 CD-60 L.T. 2. E-02 1N-65 L.T. 3. E-02 ' TR-95 L.T. 2. E-02 RU-103 L.T. 2. E-02 RU-106 L.T. 2. E-01 I-131 L.T. 5. F-02 CS-134 L.T. 2. F-02 CS-137 i ~ L.T. 2. F-02 BA-140 L.T. 3. E-02 CE-141 L.T. 3. E-02 CE-144 L.T. l.. F-01 9A-226 L.T. 3. F-01 TH-229 L.T. 3. E-02 4
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! IR-95 L.T. 3. E 00 No t.T. 3. E 00 L.T. 4. E 00 L.T. 4 E 00 RU-103 L.T. 3. E 00 No L.T. 3. E 00 L.T. 5. E 00 L.T. 5. E 00 RU-106 L.T. 3. F 01 NR L.T. 3. 5 01 L.T. 4 E 01 L.T. 3. F 01 I-131 L.T. 4. F 00 NR L.T. 5. E 00 L.T. 6. E 00 L.T. 1. F 01 CS-134 L.T. 3. F 00 NR L.T. 3. F 00 L.T. 4. E 00 L.T. 4. E 00 CS-137 L.T. 3. E 00 Ne L.T. 3. E 00 L.T. 4 E 00 L.T. 4. E 00 9A-140 L.T. 4. E 00 NR L.T. 4. E 00 L.T. 5. E 00 L.T. 8. E 00 CE-141 L.T. 6. F 00 Ne L.T. 7. E 00 L.T. 7. F 00 L.T. 9. E 00 CE-144 t.T. 2. F 01 NR t.T. 3. E 01 L.T. 3. E 01 L.T. 3. E 01 R4-226 L.T. 7. r 01 NR L.T. 8. E 01 L.T. 8. E 01 L.T. 8. F 01 Y TH-22a L.T. 6. E 00 NR L.T. 7. E 00 L.T. 7 Ei, 00 L.T. 7. E 00 Ch TRITIUM ANALYSIS H-3 2.5 +-0.6 E 01 3.3 +-0.6 E 03 2.9 +-0.6 E.03 3.7 +-0.6 E 03 3.1 +-6.6 E 03 (a) Quarterly composite duplicate analysis.
*A second aliquot was counted and the Co-58 was confirmed: Co-58 = 7.73+-3.78 pCi/1.
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nae NUCLEAR OPERATING CORPORATION May 1, 1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Letter: ET 87-0165 Re: Docket No. 50-482 Subj: Annual Radiological Environmental Operating Report
Dear Mr. Martin:
Enclosed is the Annual Radiological Environmental Operating Report which is being submitted pursuant to Wolf Creek Generating Station Technical Specification 6.9.1.6. This report covers the operation of Wolf Creek Generating Station for the period of January 1, 1986, through December 31, 1986. Very truly yours, John A. Bailey Vice-President Engineering i and Technical Services JAB:jad l Enclosure l cc: PO'Connor (2) RMartin j JCummins l
\
PO. Box 411/ Burlington, KS 66839 / Phone: (316) 364 8831 An Equal Opporturvty Egoyer M F HCNET}}