ML20076N278
| ML20076N278 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1990 |
| From: | Rhodes F WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-91-0082, ET-91-82, NUDOCS 9105030301 | |
| Download: ML20076N278 (153) | |
Text
{{#Wiki_filter:_ l W$LF CREEK NUCLEAR OPERATING CORPORATION Foftest T Rhoden vu p. e t,,n nas 61**'aicw 6.wa April 30. 1991 ET 91-0082 U. S. Nuclear Regulatory Commission ATTH: Document Control Debk Mail Station P1 137 Vashington, D. C. 20$$5
Subject:
Docket No. 50 482: Annual Radiological Environmental Operating Report Gentlemen Attached le the /6nnual Radiological Environmental Operating Report which is being submit t.ed pursuant to Wolf Creek Generating Station (WCOS) Technical Specification 6.9.1.6. This report covers the operation of Wolf Creek Gener atir.g s t a t i'an (WCGS) for the period of January 1, 1990 through December 31, 1990. Very truly yours,
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f.ny' /_/tnb /i Forrest T. Rhoden Vice President Engineering E Technical Services FTR/sem Attachment ces L. L. Gundrum (NRC), w/a A. T. Howell (NRC), w/a R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a l
-O rn -, s POR fiDOCU O #3 0 0 0 4 2 : 3 Don 411/ Burnirgton. KS f4839 / Phone (316) 304 8831
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1 Attachment to ET 91-0082 e l VOLF CREEK NUCLEAR OPERATING CORPORATION VOLF CREEK GENERATING STATION
- - 1990 ANNUAL RADIOLOGICAL
- ENVIRONMENTAL OPERATING REPORT i j 1 APRIL 18, 1991
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l. TABLE OF CONTENTS J Page l I List of Tables ................................................... i List of Figures .................................................. 11 Introduction ..................................................... 1 I. Program Description ........................................ 2 II. Discussion of Results ...................................... 6 III. Annual Land Use Survey Results and Program Revisions ....... 12 IV. Monitoring Program Deviations .............................. 14 V. EPA Interlaboratory Comparison Program Results ............. 18 Tables ........................................................... 19 Figures .................... .................................... 40 Appendix At Summary tables sa format of HRC Radiological Assessment Branch Technical Position, Revision 1, November 1979 ........................... A-1 Appendix B Individual Sample Results ........................... B-1 Appendix C Environmental Honitoring Tritium Levels ............. C-1
t i I LIST OF TABLES Page Table 1: 1990 Radiological Environmental Monitoring Program Sample Collection ....................................... 19 Table 2: Sample Location Numbers, Distances (miles) and Directions .............................................. 25 Table 3: 1990 Air Particulate Samples Gross Beta Analysis Results ............................. 26 Table 4: Air Particulate Composite Samples Gamma Analysis Results .................................. 29 Taile 5: 1990 TLD Results ........................................ 30 Table 6: Drinking Vater samples Gross Beta Analysis Results ............................. 32 Table 6As Drinking Water Samples Tritium Analysis Results ................................ 32 Table 7: Surface Water Samples Tritium Analysis Results ................................ 33 Table 8: Bottom Sediment / Shoreline Soil Gamma Analysis Results .................................. 34 Table 9: Aquatic Vegetation From VCCL Discharge Cove Gamma Analysis Results .................................. 36 Table los Results of the 1990 Land Use Census ..................... 37 Table 11: Results of EPA Interlaboratory Comparison Tests ......... 3B - I l
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LIST OF FIGURES Page Figure 1: Airborne Pathway Sampling Locations ..................... 40 Figure 2: Direct Radiation Pathway Sampling Locations ............. 41 Figure 3: Waterborne Pathway Sampling Locations ................... 42 Figure 4: Ingestion Pathway Sampling Locations .................... 43 Figure 5: Distant Sampling Locations .............................. 44 Figure 6: 1990 Airborno Particulate Activity Weekly Gross Beta Analysis Results ...................... 45 Figure 7s 1990 Airborne Particulate Activity Incicator/ Control Comparison ............................ 46 Figure 8: Operational TLD Results Hearsite & Control Location Averages .................... 47 Figure 9: Variation of Nearsite TLD Averages I of control Location Values ............................ 48 Figure 10 1990 Drinking Water Analysis Gross Beta .............................................. 49 Figure 11: Operational Tritium Concentrations Wolf Creek Cooling Lake ................................. 50 i
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IwraonectIgg This is the 1990 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCOS) covering the period from January 1 to December 31, 1990. WCGS is located in Coffey County, Kansas, approximately five miles northeast of Burlington, Kansas. Puel loading began at WCOS 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 quantitles 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 (VCN00), results cf sample analyses performed by Teledyne Isotopes, a discussion of mtnitoring program results, a discussion of program deviations and revisions, and a discussion of the results of the Environmental Protection Agency (EPA) Interlsboratory Comparison Program. Individual sample results and a summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Position specified format are included as appendices to the report. No effects o.! plant operation were seen in air filters (particulate and charcoal), dicact radiation, broadleaf vegetation, irrigated crops, and ground water. Tritium from routine plant releases was detected in Wolf Creek Cooling Lake (WCCL) surface water samples throughout the year. Tritium was also detected in the third quarter drinking water composite samples at both the control (Burlington) and indicator (LeRoy) locations. _The activity measured at LeRoy was at the detection limit with a large measurement error. The activity measured at Burlington was two times the detection capability with a relatively small error. It is believed the tritium detected at both loe ' ions are from the same source but not attributable to Wolf Creek since ths activity detected upstream of WCCL discharge was greater than the activity detected downstream. There was one elevated gross beta measurement for drinking water in February. The cause for che elevated gross beta measurement hae not been identified and no other radionuclide analysis for thin sample had any elevated levels. All nuclide concentrations were below applicable reporting levels. Activation products (Co-58 and Co.60) were detected in WCCL bottom sediment and shoreline soil and in algae samples obtained in the VCCL discharge cove Mn-54 Co-58, and Co-60 were detected. Also, one fish sample from VCCL contained Cs-137 which is assumed to be due to VCGS operation, although fallout Cs-137 (which is regularly detected in other sampling media) is probaoly also partially reflected in the measured concentrations. All of the concentrations were below applicable reporting levels. No measurable impact on human exposure due to plant operation was seen for the year. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 1 0F 50
4 l l T. PROGRAM DESCRIPTION Radiological environmental samples were collected according to the schedule in the Offsite Dose Calculation Manual. Some additional sample collections were made to support a cooperative sampling program with the State of Kansas and plant activities. All samples were collected by WCNOC's Radiological Services, Emergency Planning, and Environmental Management Groups and sent to 1sledyne Isotopes of Westwood, New Jersey for analysis. Table 1 lists , sampling pathways and frequencies of sampling and analysis. Table 2 lists I the sample location direction and distances. The following is a description of the sampling and analysis program by individual pathways. Deviations are permitted from the required sampling . schedule if specimens are not obtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. Deviations from the routine sampling schedule and j other problems encountered during the year are described in Section IV
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Monitoring Program Deviations. Airbornet Low volume air sampling pumps continuously collected particulate samples on 47 mm glass fiber filters samples were then drawn through charcoal canisters to collect I.131. Filters and charcoal canisters were changed out weekly, labeled, and shipped to Teledyne Isotopes for analysis. Total sample volume used to calculate air concentrations was determined from the average of the initial and final sampling flow rate and the total time of collection. Gross beta analysis of the air particulate samples was performed after a period of at least 24 hours following filter collection to allow decay of redon and thoron daughter products. Each filter was mounted on a stainless steel planchet and counted on an automatic alpha-beta counter. If the gross beta activity for a sample would have been greater than 10 times the yearly mean of control samples, a gamma isotopic analysis would have been performed on the individual sample. Weekly air particulate filters were combined into quarterly composites for each location and analyzed for gamma emitting isotopes on a Ge(L1) detector. Charcoal canisters were routinely counted in groups of five to determine the presence or absence of I-131. Positive indication of airborne I.131 would have been supplemented by separate analysis of individual canisters for each location. Air samples vere collected from the three sectors with the highest ground level D/Q. the nearby community of New Strawn, and a control location. Distances and directions to sampling locations from the plant site are 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 2 0F 50
4 listed in Table 2: locations are shown in Figure 1 (nearby locations) and Figure $ (distant locations). Direct Radiation: The thermoluminescent dosimeter (TLDs) used during 1990 were provided by Teledyne Isotopes. The TLDs consisted of rectangular teflon wafers impregnated with CaSO4:Dy. Prior to placement in the field, the dosimeters were annealed for at least one hour at between 250 and 260 degrees centigrade, then placed in polyethylene pouches and holders containing 0.022 or 0.093 inches of copper shielding to filter out low energy radiation. New t'ield dosimeters were exchanged with the exposed dosimeters and the exposed dosimeters were returned to Teledyne Isotopes for analysis. Freshly annealed control dosimeters were sent with the exposed TLDs to record trsnsit exposures received during shipment as well as system background of the TLD reader. Gamma exposures were measured on a Teledyne Model 8300 TLD readers individual dosimeters were then re-irradiated with a known exposure from a Cs-137 source and read again to determine individual dosimeter 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 sampler housings to protect them from moisture and tampering. Two TLDs were placed at each location to provide duplicate measurements. TLD locations are,shown on Figura 2 (plant vicinity and Figure 5 (distant). Table 2 provides distances and directions of each location from the WCGS site. Veterbornet Drinking, Surface, and Ground Water Monthly composite samples of drinking water were obtained by collecting aliquots at one hour intervals. Grab samples of surface and ground water were collected on a monthly and quarterly basis, respectively. All samples were sent to Teledyne Isotopes for analysis. All water samples were analyzed on a Ge(Li) detector to determine if gamma emitters were present. In addition to gemma analysis, a radiochemical analysis for I-131 was performed on drinking water and ground water samples. Gross beta analysis was also performed on drinking water samples. Tritium analysis was performed by liquid scintillation counting on a quarterly basis for drinking water and on a monthly basis for surface water. Tritium analysis for ground water was performed quarterl/ by gas counting. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 3 0F 50
( , Drinking water sampling locations are at the water treatment stations for the towns of Burlington (upstream control location) and LeRoy (downstream indicator location). Surface water sampling locations are at the John Redmond Reservoir outfall (control), Wolf Creek Cooling Lake discharge cove (indicator), and Wolf Creek Cooling Lake main dam (indicator). Ground water is sampled from three wells located hydrologically downgradient from Wolf Creek Cooling Lake and from an upgradient control well. All water sampling locations are listed in Table 2 and shown in Figures 3 and 5. Shoreline and Bottom Sadiment: Semiannual samples of shtteline and bottom sediment were collected from the discharge covo area (location 'DC' on Figure 3) of Volf Creek Cooling Lake. Control samples were added for shoreline and bottom sediment at John Redmond Reservoir during the last half of 1990. Also, special bottom sediment samples were obtained in the Ultimate Heat Sink (UHS). Gamma analysis was performed on each sample. Aquatic Vegetation / Algae Semiannual samples of aquatic vegetation / algae were collected from the discharge cove area (location 'DC' on Figure 3) of Wolf Creek Cooling Lake. Gamma analysis was performed on each sample. Incestiont Milk: Milk samples were collected on a semi-monthly basis from April through November (while milk animals were on pasture grass) and on a monthly basis the remainder of the year (when animals were on stored feed). Samples were sent to Teledyne Isotopes where radiochemical analyses for 1-131 and gamma analyses were performed on each sample. Locations are shown in Figures 4 . and 5. Broadicaf Vegetation and Irrigated Crops: Broadleaf vegetation samples were collected monthly during the growing season. Alternate sampling locations were also used when quantities of vegetation were limited, such as early or late in the growing season or during dry periods. Additionally, samples of crops irrigated with water from the Neosho River upstream and downstream of the discharge from Wolf Creek Cooling Lake were collected during harvest. All vegetation samples were sent to Teledyne Isotopes and analyzed by gamma spectroscopy. Locations are shown in Figures 4 and 5. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 4 0F 50
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Fish Fish samples were collected semi-annually from Wolf Creek Cooling Lake (indicator) and John Redmond Reservoir (control) with several important recreational species being sampled. Samples of boneless meat portions were sent to Teledyne Isotopes and analyzed by gamma spectroscopy. Locations are shown in Figure 4. Game Animals and Birds: Annual samples of endemic game animals and birds were obtained from the immediate vicinity of Wolf Creek Cooling Lake (indicator) and John Redmond Reservoir (control). Samples of boneless meat portions were sent to Teledyne Isotopes and analyzed by gamma spectroscopy, i I 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 5 0F 50 1-.-------.-. -
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II. DISCUSSION OF RESULTS Analysis results for all pathways are summarized in Appendix A using the form;. oescribed 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. Airbornet Results of gross beta analysis of weekly air particulate filters are shown in Table 3. In addition, the four indicator locations are averaged and plotted graphically with the control location in Figure 6. Finally, Figure 7 shows the percent of the indicator average to the control location measurement. Both of these figurse demonstrate how closely the indicator and control locations track together. Results from the weekly analysis of charcoal filters for I-131 showed no concentration above the detection limit during the year. Results of the quarterly gamma analysis of air particulate filter composites are summarized in Table 4, which shows that naturally occurring Be.7 and K. 40, were detected regularly, as was the case during preoperational monitoring. No effects of plant operation were seen via the airborne pathway for the year. Direct Radiation: Quarterly gamma exposures measured at each location for 1990 are shown in Table 5. Values are normalized to a standard 90-day quarter. Results from TLDs located near the plant site (less than approximately three mile cistant), which would be most sensitive to changes due to plant operation, were combined into quarterly averages. These nearsite averages, using locations 1, 2, 7, 8, 9, 10, 11, 12, 13, 14, 18, 25, 27, 28, 29, 30, 37, and 38, are compared to control TLD (locations 39 and 40) results in Figure 8. In addition, the percentage of the nearsite averages to the control locations results are displayed graphically in Figure 9. These figures also include preoperational data for comparison. A change has been made to the shielding thickness used with the TLDs. The 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 6 OF 50
old thickness (0.022 inches) was undercompensating for the over response to low energy gammass therefore, the proper shield (0.093 inches) was installed the fourth quarter of 1990. This has caused an average drop in the measurements of less than 2 mrem over the standard quarter when compared to measurements taken using the 0.022 inch shield during the same time period. This change is described fully in the program deviation section of this report ! at is mentioned here since the results have been affected slightly, but insignificant 1y. by the shielding change. No changes to area gamma exposure rates as a result of plant operation were identified. Waterborne Since tritium has been appearing in water samples surrounding Wolf Creek a uetailed evaluation of tritium monitoring and concentrations in the environment was performed during 1990. The results of this evaluation are in Appendix C. Drinking Waters Results of gross beta analysis of drinking water samples are listed in Table 6: Figure 10 depicts these results graphically along with preoperational values for comparison. There was an unusually high value for gross beta teen in the February sample at LeRoy (LV 40). This value was verified with a follow-up analysis for gross beta. The gamma isotopic analysis for the sample failed to show any detectable gamma emitters and a visual inspection of the residue used for the measurement did not show any abnormal colors or densities. Also the quarterly composite for tritium was less than detectable. In summary, the gross beta must be considered a valid result but none of the other testing supports the higher value obtained for February. Tritium was detected at both BW-15 (control) and LW-40 (indicator) in the , third quarter composite. At BW-15 the concentration was 1600 1 400 i pCi/11ter and et LV-40 the concentration was 800 1 340 pC1/11ter; the detection limit is 700-900 pCi/11ter. The tritium detected at these locations are not due to plant effluents nince the tritium was seen at the control location as well as the indicator location. Surface Water Tritium. attributable to WCGS operation was detected in all surface water l samples collected from WCCL in 1990. A total of $90 Curies were released to l WCCL during the year. Measured concentrations are shown in Table 7. In l 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 7 0F 50
i Figure 11, VCCL tritium concentrations are plotted since WCGS began operation. It can be seen in Figure 11 that monthly surface water tritium j concentrations appear to be slightly increasing since plant startup. This is expected until the lake concentration reaches equilibrium. (See discussion on equilibrium concentrations in Appendix C, page C-4.) I A peak concentration of 9,000 p01/11ter occurred in November when the monthly grab saeple was obtained shortly after the termination of a batch release. Since the sample point is just beyond the near field mixing aone, complete mixing had not occurred. The peak concentration is seen in Table 7 and Figure 11. All tritium concentrations measured were below applicable reporting levels. There were no gamma emitters related to plant operation detected in surface water for the year. An additional surface water location was added to the sample collections in August in preparation for moving the location along the VCCL Main Dam several yards east of the presset location. The new location is beside the auxiliary spillway which allows dischargen into Wolf Creek. The results obtained from August through December indicate moving the stmple location will not have any affect on the analysis results. Ground Water No tritium or gamma emitters were detected in any of the quarterly ground water samples in 1990. Shoreline Sediment: Table 8 shows gamma emitters detected in shoreline sediment collected from Wolf Creek _ Cooling Lake and John Redmond Reservoir during 1990. In addition to the naturally occurring nuclides (Be-7, K-40, Ra-226, and Th-228), two other radionuclides were detected. Co-60, an activation product, was detected in the sample collected on October 16, 1990. This activity is attributed to plant operations rather than fallout from nuclear weapons testing. The other nuclide, Cs-137, was detected in both samples but the activity measured-is considered to be primarily due to fallout rather than plant operations since the concentration is at or below preoperation concentrations. Also, Cs-134 was not detected, although it would be expected if the occurrence of Cs-137 was related to plant operation. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 8 0F 50
Bottom Sediment Table 8 shows gamma emitters detected in bottom sediment samples collected from Wolf Creek Cooling Lake and John Redmond Reservoir during 1990. In addition to the naturally occurring nuclides (K-40, Ra.226, and Th-228), I several other radionuclides were detected. l i Co.58 and Co.60 are activation products whose presence in the WCCL samples j is attributed to plant operation. The Cs.137 concentrations measured are considered to be primarily due to fallout rather than plant operation since they are at or below concentrations measured preoperationally and are comparable to the concentrations seen in the control sample from John Redmond Reservoir. Also, Cs.134 was not detected although it would be expected if the occurrence of Co.137 was related to plant operation. 1 Aquatic Vegetations A combination of naturally occurring nuclides, fission products, and activation products were detected in algae samples from the VCCL discharge cove during the year. Rooted aquatic vegetation was not available again this year. A summary of the concentrations measured is shown in Table 9. Naturally occurring nuclides measured were Be.7, K-40, Ra.226, and Th.228. - Activation products seen in *.he samples were Kn.54. Co.58, and Co.60s all of these are attributable to operational releases. Fission product Co.137 was detected in both algae samples while Cs.134 was only seen in the sample collected 9/18/90. The fission products seen in the algae samples are due to fallout and possibly plant effluents. The concentration of Cs.137 measured in both algae samples is within the range of concentrations measured during the preoperational phase of environmental monitoring but the detection of Co.134 implies a recent source of activity., Innestion: Milk There were no indicator samples available during 1990 (see Program Deviation section for explanation). A control sample was routinely obtained + for analysis. All milk samples analyzed contained naturally occurring K 40 at concentrations consistent with preoperational levels. The yearly average concentration was 1260 pCi/11ter. No other gamma emitters were detected. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 9 0F 50
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1 l l Broadleaf Vegetation: camma analysis of broadleaf vegetation samples revealed naturally occurring gamma emitters K 40 and be.7 at concentrations comparable to preoperational and background levels. Co.137 was also detected at Locations R.1 (indicator) and 5 4 (control) during May. The concentrations were 0.0175 pCilgm and 0.323 pCilgm q respectively. These concentrations for Co.137 are attributed to fallout for the following reasons: 1) The range of fallout Co.137 seen in preoperational samples was 0.0131 to 0.0478 pCilgm. 2) Co.137 was not detected in the airborne effluent releases from the plant during the second quarter of 1990. 3) Co.134 was not detected, although it would be expected it the occurrence of Cs.137 was related to plant operation (Cs.134 decays with a shorter halflife than Cs.137 detection of Co.137 alone indicates fallout as opposed to newly produced fission products). No other gamma emitters were detected for the remainder of the year, and no effects of plant operation were identified. trrigated Crops: Camma analysis revealed naturally occurring K.40 to be present in the samples, with no nuclides detected which could be attributable to plant operation. Fichi Naturally occurring K.40 was found in all fish samples collected with an average concentration of 4.05 pC1/gm (vet weight) for WCCL samples and 4.81 pC1/gm (vet weight) for the control samples. These concentrations are within the range seen during the preoperational period. In addition one sample from WCCL. collected on 10/2/90, contained detectable levels of Co.137 at 0.0404 ptilgm (vet weight). Although fallout Co.137 is regularly measured in other environmental media and is probably reflected in these values, it is assumed that these concentrations are attributable to WCGS operational releases since Co.137 was not detected 1 during the preoperational testing or in control samples. A dose calculation for a hypothetical individual, assuming a maximum ingestion rate (16 kg per year from Reg. Guide 1.109) at the measured Cs.137 concentration results in an annual dose of 0.096 mrem (critical age group - teen, critical organ = liver). No other radionuclides were detected in fish during the year. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 10 0F 50
t Came Animal and Bird Naturally occurring K-40 was measured in all game animal and bird samples at l concentrations consistent with preoperational levels. ! 4 !!o other radionuclides were detected and no effects of plant operation were seen for this pathway. I 4 , t i l l 1990 ANNUAL RADIOLOOICAL ENVIRONMENTAL OPERATING REPORT WOLF CREll', GENERATING STATION PAGE 11 0F 50
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III. ANNUAL LAND USE SURVEY RESULTS AND PROGRAM REVISIONS The purpose of the Land Use Census is to identify within a distance of $ miles the location in each of the 16 meteorological sectors of the nearest residence, the nearest milk animal and the nearest garden of greater than 50 square meters producing broadleaf vegetation. The 1990 Annual Land Use Survey was completed in October. Information was collect >d using a combination of mailed survey forms, telephone contacts, and door to-door contacts. Comparing the 1989 census results to this year the nearest resident has changed in Sectors B and P. In Sector B the nearest resident is no longer 1.8 miles from the plant at location B-10: the new location (B.2) is further from the plant at 3.1 miles. In Sector P the distance to the nearest resident decreased from 2.9 to 2.8 miles. The nearest resident is at P.26 just south of New Strawn. The previous nearest resident was at P-2 just east of New Strawn. Several changes were noted in the distance to the nearest milk animal. Hilk animals were identified in Sectors A and B this year where they had not been identified in the 1989 Land Use Census. As in 1989, milk animals were identified in Sectors D. F, and H but the distance to the nearest milk animal in Sector D increased from 2.3 miles to 2.4 miles. Hilk animals are no longer present in Sector 0, specifically location 0 6. At location F.13, the resident has one female goat. The resident did not indicate whether the goat was producing milk but the owner did indicate any milk produced would not be used for human consumption. The milk from the cows in Sectors A and B is used only to nurse the young animals and will not be used for human consumption. Therefore as samples are unavailable, sampling at these locations is not possible. At location H-19, the cattle are for breeding purposes only and the milk will not be used for human consumption. This is a change from last year when the cattle were allowed to graze at that location until they were ready to prodsce milk, they were then transferred to a location near LeRoy and fed on stored feed during the lactatien period. Sampling at this location is not possible. In Sector D the nearest milk animal has moved frei D-2, where the resident indicated he no longer kept milk animals, to location D-3 which is slightly further from the plant. The resident at D-3 indicated he does occasionally drink the milk from these cows even though the milk is used primarily to nurse young calves. When asked to participate in the Radiological Environmental Honitoring Program the resident refused, therefore sampling at this location will not be possible. Several location changes were noted for the nearest garden in Sectors C, E. H. J. L, N, and Q. In all of these sectors (except N) the distance to the l 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 12 0F 50
f : l nearest garden either remained the same, even though the actual location changed, or increased. In sector N there are no gardens within five miles of the plant producing broadleaf vegetation. None of the existing broadleaf vegetation sampling locations are affected by the location changes in these sectors. Based on the data obtained from the 1990 Land Use Census no changes are 1 required for the Radiological Environmental Monitoring Program. As in the past, it should be noted that dose calculations are performed for airborne and liquid pathways for a hypothetical individual at the exclusion area boundary in the highest X/Q end D/Q sector (for airborne pathways) and at the circulating water aischarge point (for liquid pathways). Calculated doses are therefore not affected by changes in residence, milk animal, and broadleaf vegetation locations identified by the Annual Land Use survey. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 13 0F 50
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3 IV...MONI701130. PROGRAM DEVIATIONS Airborne , Location 37 (1/23/90 1/30/90): The charcoal canister was not seated properly on the gasket, allowing air leakage in the sampling train. Deposition on the filter was light and the measured gross beta concentration was approximately 60! lower than the average concentration for the four j other indicator locations. The reported value for location 37 during this week was therefore considered to be erroneously low. ; All personnel involved in sample collections were informed of this event and cautioned to check the air samplers for proper suction when performing air samples changeouts. l All Locations ( 6/26/90 7/10/90): When performing air sample changoouts on 7/3/90 air sample flows were determined incorrectly. The error occurred when the-calibration graph was misinterpreted. The graph reads Pump Flowmeter Reading vs Mass Flowmeter Reading (or indicated flow vs actual flow). The graphs were interpreted as actual vs indicated. This error caused total sample volumes calculated for two sample periods (6/26/90 - 7/3/90-and 7/3/90 7/10/90) to be erroneously high and consequently the sample activity per unit volume to be low. The high pump flows were noted when reviewed by the Program Coordinator on 7/9/90 but discussions with personnel involved did not ipdicate a problem with the sampler or sample techniques. It was not disec ered until 7/10/90, during another training session on air sampling, that the calibration graph had been interpreted incorrectly. All personnel involved in sample collections were informed of this event and assigned reouired reading for graph interpretation. The correct-volumes for those two weeks were determined and used to correct the sample analysis results for air particulate gross beta and charcoal filter radiolodine. Location 37 (10/16/90 - 10/23/90): The-air sample pump at this location was removed from service on 10/23/90 when a significant flow increase was noted for the week. The air sampler was examined and the calibration curve-was verified. The calibration curve was still valid but the seal around the charcoal filter was difficult to achieve. The charcoal filter holder was replaced to alleviate.this problem. .The sample activity results were reviewed for this week and the results at this location were consistent with the results at the other indicator locations. Direct Radiation Location 10 (First quarter): One of the TLDs at this location was 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION- PAGE 14 0F 50 L._ . ._ _ .a _ .. _ . _ _ _ . _ . _ . _ _ , -
I . . missing, probably due to an act of vandalism. The second TLD vas located on the ground at the sample location and sent in for analysis. Since vandalism is beyond the control of VCGS there were no corrective actions taken. Location 16 (First Quarter): One the of TLDs was missing, probably due to an act of vandalism. The second TLD vas still attached to the utility pole and sent in for analysis. Again, since vandalism is beyond the control of WCGS and appears to be an infrequent occurrence, there were no corrective actions taken. Location 21 (First Quarter): One of the TLD6 at this location was apparently not removed at the end of the fourth quarter of 1989 and left for two quarters. The results from the TLD in question were approximately two times higher than the second TLD at this location and the wrong color label was on the TLD. Also, as noted in the 1989 Annual Radiological Environmental Operating Report one of the TLDs at this location for the fourth quarter of 1989 was analyzed as having a negative dose and had the wrong color label, indicating the TLD had never been in the field. The value from the second TLD at this location was used as the recorded exposure at this location. Location 16 (Third Quarter): On one of the TLDs at this location half of the copper shield in the holder was missing. A review of the results did not show any significant difference between the two TLDs at this location therefore both TLDs were used in determining the recorded exposure. All Locations: During the reporting period, it was determined the TLD cases did not have the proper shield thickness to prevent the TLDs from over-responding to low energy gamma radiation. The VCGS program includes a requirement that the detection capabilities for thermoluminescent dosimeters used for environmental measurements to be in accordance with the reconnendations of Regulatory Guide 4.13, Revision 1. July 1977,
' Performance. Testing, and Procedural Specifications for Thermoluminescent Dosimetry: Environmental Applications
- and ANSI H545 1975, ' Performance.
Testing, and Procedural Specifications for Thermoluminescence Dosimetry (environmental applications)'. Vendor documentation indicates the copper shield thickness for the TLD cases necessary to meet the requirements for energy response in the Regulatory Guide and ANSI standard is 0.093 inches. Contrary to this requirement, the thickness of copper shields used was 0.022 inches. The 0.022 inch shields for the TLD cases were purchased prior to the issuance of the WCGS Technical Specifications and have been used since 1981. This deviation constitutes a program deviation since the TLDs did not fully meet the recommendations of Regulatory Guide 4.13. Since the discovery of this programmatic deviation, several corrective actions have taken place: Discussions with the vendor to determine the impact of the 0.022 inch shield on the TLD measurements have indicated the error associated with the shield variation would be in a conservative direction since the TLD would over 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 15 0F 50
I U . i i rerpond by up to 2.5 times depending on the gamma ray energy for that component of the gamma ray =nectrum. The vendor indicated that when exposed to cosmic rays and normal terrestrial background. TLDs, whether shielded by 0.022 inch or 0.093 inch copper, read the same dose. TLD results, when compared to TLD results of the Kansas Department of Health and Environment and Nuclear Regulatory Commission, measured for the past several years are at normal background exposure levels. ! New TLD cases with the 0.093 inch shield were placed in the field for the fourth quarter of 1990 along with the 0.022 inch shield to make an actual comparison of the exposure measurements. This will continue through the second quarter of 1991 to determine the magnitude of the difference. At this time the difference is not believed to be significant. WCGS has i acquired cases with 0.093 shields and will be using them in conjunction with the current TLD type in future measurements in order to meet the TLD response characteristics listed in Regulatory Guide 4.13. This program deviation was evaluated against the WCOS Technical . Specification reporting requirements for the Radiological Environmental Monitoring Program. It was determined that reporting this program deviation in the Annual Radiological Environmental Operating Report under monitoring program deviations would fulfill tae reporting requirements. Vaterbornet , Drinking Water Location LV.40 (2/90 - 3/90): A malfunction of the composite water sampler at LW-40 was discovered during a site visit on 2/26/90. The malfunction involved the submersion of electronic components of the sampler in water after a period of. time during which water was pumped into the sampling chamber but was not removed during the purge cycle. Once the water level reached the electronic components at the top of the chamber, the sampler ceased to function. Upon discovery of the problem the sampler was drained of the excess water that had accumulated and removed from the sample location. It is thought that the malfunction may have been due to construction activities at the water.tre?tment facility. '- sampler had been moved from its normal location by pid nters and, in t'.e process, the . sample line had been at least partially y. inched shut. The resulting restriction to flow may have prevented the sampler from completing the purge cycle properly. Another sampler could not be installed because of t construction activities where the sampler is located. Following the replacement of the electronic components of the sampler and the completion of construction activities, the sampler was reinstalled at LV-40 on 3/12/90. Due to the interruption of sampling caused by this l- malfunction. the February and March drinking water samples are not composite i samples for the entire month. 1990 ANNUAL RADIOLOGICAL ENVIRORMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 16 0F $0 -
-, .-, ,- ,-. ,m, . - . . , -.-.-,..,_m_ , , . , _ . . . . . , . . . . _ . , . _,-m.,,.,.c . _ . , , , . , , , , , ,
r . I. '
] .
Location LV.40 (12/90): During a routine check of the composite water sampler at LW-40 on December 16, 1990, it was noticed the i sampler was not functioning. The sampler was not receiving power due to a failed breaker in the electrical circuit supplying power to the outlet. 1 LeRoy city personnel repaired the breaker on 12/19/90 and the sampler was returned to service on 12/21/90. It is not known how long the sampler was out-of-service (the sampler was last checked 12/6/90) but the sampler
, container was half full on 12/10/90. This is normal after two weeks of operation and implies the out of service time was quite short. Since the root cause of the sampler malfunction was out of our control we have not taken any corrective actions to prevent-recurrence.
Intestiont Hilk There were no deviations in milk sampling however, there are still no indicator sampling locations available within five miles on the plant. This is detailed in the Annual Land Use Survey Results and Program Revisions. Broadleaf Vegetation: The growing season for broadleaf vegetation was extremely poor this year therefore, several of the monthly samples were not available. Adverse growing conditions such as a wet spring followed by a very dry summer caused a short growing season at our sample locations. All Locations (4/90): Samples were not available. Location A.1 and G-1 (5/90): Samples were not available. Location G-1 (8/90): Sample was not available. Location R 1 (8/90): Unable to obtain enough sample to meet LLD. Location S-4, R.1, and G.1 (9/90): Samples were not available. Location S-4 and R.1 (10/90): Samples were not available. Location S-4, R 1, and A-1 (11/90): Samples were not available. No corrective actions were necessary since the schedule directs these samples to be collected 'as available' during the growing season and when the primary sample locations A 1 and R-1 were unavailable the alternate location G-1 was available. l-1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERAT1HG STATION PAGE 17 0F $0
j V. EPA IWYKRI.ABORATORY C(MPARlSON PROGRAM RESUI.TS Teledyne Isotopes, contracted to perform analysis of radiological environmental samples for WCN00, participated in the EPA Interlaboratory Comparison Program during 1990. Table 11 shows interec.tparison test results received during the year. The table lists the collection date, the sample media, the nuclide or analysis type, the known value reported by the EPA and the measured value reported by Teledyne Isotopes (based on triplicate analysis). Results are listed in the table for the sample media and analysis types corresponding to those performed for WCNOC. Ru-106 result for the water sample with a collection date of 2/9/90 was lower than the EPA value. No apparent cause for the low result was found. Three aliquets of the sample were counted on three separate detectors. The results of all three were similar. The calibration curve fit was good (0.997). Ruthenium-106 was obtained from the EPA. Results of spikes were acceptable. Subsequent EPA cross. checks did not exceed two normalized standard deviations. No additional follow-up is necessary but monitoring of results will continue. Ba-133 result for the water sample with a collection date of 10/15/90 was lower than the EPA value. All other isotopes in the sample were measured accurately. The calculations were reconfirmed. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLP CREEK GENERATING STATION PAGE 18 0F 50
TABLE 1 1990 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND FREQUENCY PATHWAY / AND COLLECTION OF ANALYSIS SAMPLE S AMPLE LOCATIONS FREQUENCY AIRBORNE Iodine & Samples from five continuous sampler Analyze radiolodine particu- locations operation with canister weekly for lates sample collection I-131. Sauples from loca- weekly, or more tions near the site frequently if Analyze particulate boundary in three required by dust filter weekly for sectors having the loading. gross beta acti-highest calculated ivityl perform annual average D/Q quarterly ganma (Locations 2, 3 and isotopic analysis 37 on Figure 1): composite (by loca-tion). Sample from the vicinity of a community having the highest calculated annual average D/Q (Location 32 on Figure 1. New Strawn): Sample from a control location 10 - 20 miles distant in a low D/Q , sector (Location 40 on
'Fjgure 5).
DIRECT RADIATION 40 routine monitoring Quarterly Gamma dose stations with two or quarterly more dosimeters measur-ing dose continuously, placed as follows: 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT VOLF CREEK GENERATING STATION PAGE 19 0F 50-
TABLE 1 (cont'd) 1990 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND FREQUENCY PATHWAY / AND COLLECTION OF ANALYSIS SAMPLE jatiELE LO_CAJJ.QHj, _ FREQUENCY DIRECT RADIATION (cont'd) An inner ring of sta-tions, one in each meteorological sector 0 - 3 mile range from the site (Locations 1 - 14, 18, 26 - 31, 37, and 38 on Figure 2). An outer ring of sta-tions, one in each-meteorological sector 3 - 5 mile range from the site (Locations A$ 16, 17, 19 - 22, 24, 25 and 32 - 36 on Figuru 2). The balance of the sta-tions to be placed in special interest areas such as population cen-ters (Locations 23 end 3k) -nearby r6sidences (Many locations are near a residence), schools (Location 23), and in one or two areas to serve as control stations 10 - 20 miles distant from the site (Locations 39 and
- 40) (Locations are on Figures 2 and 5)
Locations 41, 42, and 43 on Figure 2 are not part of the required program but have been added as special inter-est locations. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 20 0F 50
-.- . _ . . - . . . - . . _ - -. ~ . - . - - . . . - . . .. ..-. - . - --
I TABLE 1 (cont'd) i 1990 RADIOLOGICAL ENVIRORMENTAL MONITORING PROGRAM SAMPLE COLLECTION EXPOSURE NUMBER OF SAMPLES SAMPLIPG AND TYPE AND FREQUENCY PATEWAY/ AND COLLT.CTION OF ANALYSIS SAMPLt SAMPLE LOCATIONS ,JJf4JENCY WATERBORNE Surface One sample upstream Monthly grab sample Honthly gamma iso. (Location MUSH on topic analysis and Figure 3) and two composite for samples downstream tritium = analysis (Locations DC and SP quarterly, on Figure 3) An additional. sample. SP(ALT),in the same vicinity as SP-has b6en-added in preparation
'for relocating SP.
Ground Samples from one or Quarterly Quarterly. gamma two sources only if isotopic and-likely to be affected. tritium analysis.. Indicator samples at
-locations hydrologi- ,
cally downgradient of the site (Locations
.C-10 C-49 and D-65 on Figure 3):: Control sample at a-location hydrologically upgra-dient'of~the. site (Location B-12 on Figure 3).
Drinking' : Sample of municipal Monthly composite Monthly gamma iso-water. supply at an topic analysis indicator location .and gross beta downstream of'the site analysis of compo-(Location LW-40 on ' site sample. _ Quar-Figure 5): control .terly tritium anal-sample.from.locatien .ysis of composite, upstream of the site (Location BW-15 on Figure 3). 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF-CREEK GENERATING STATION PAGE 21-OF 50
I TABLE 1 (cont'd) 1990 RADIOLOGICAL ENVIRONMEWTAL MONITORING PROGRAM SAMPLE COLLECTION-EXPOSURE RUMB."R OF SAMPLES SAMPLING AND TYPE AND FREQUENCY PATHWAY / AND- COLLECTION OF ANALYSIS
}611& L f.&tPLE LOCATIONS _ FREQUENCY VATERBORNE (cont'd)
Shoreline One sample from the Semiannually; Semiannual gamma - Sediment vicinity of Wolf isotopic analysis, Creek Cooling Lake discharge cove,(Loca-tion DC on: Figure 3) and one sample from John Redmond Reservoir-(Location JRR on Figure 3). Bottom One sample-from the_ Semiannually Semiannual gamma Sediment- vicinity of Wolf isotopic analysis. Creek Cooling Lake discharge cove (Loca-
. tion DC on Figure _3) and one sample from John Redmond Reservoir (Location -JRR on -
Figure 3). Special i samples were taken-in the vicinity of the Ultimate Heat Sink. Rooted, One sample from the Sem1 annually Semiannual gamma Aquatics vicinity of Wolf isotopic analysis, y oor Algae . Creek Cooling Lake discharge cove (Loca. tion DC on Figure 3). INGESTION Milk Samples from milking Semimonthly while Gamma isotopic animals at three animals are on analysis and indicator locations pasture (April to. I-131 analysis within 5 miles of the November): monthly of~each sample. site having the at other times highest dose poten- (December to March). tial (currently there l' l- 1990 ANNUAL RADIOLOGICAL. ENVIRONMENTAL OPERATING REPORT I EWOLF CREEK' GENERATING STATION PAGE 22 0F 50 1 O. .
TABLE 1 (dont'd) 1990 RADIOLOGICAL INVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION EXP03URE NUMBER OF SNdPLES SAMPLING AND TYPE AND FREQUENCY PATHWAY / AND COLLECTION OF ANALYSIS SAMPLE )RjPM._ LOCATIONS .,ZEf_QMENCY INGESTION (cont'd) Milk are no locations pro-(cont'4) ducing milk for human consumption within 5 miles of the site): one campic from a con-trol location greater than 10 miles f rom the site (Location S-3 on Figure 5). Fish Indicator camples of Semiannually Gamma isotopic 1 to 3 recreationally Analysis on edible important species from portions. Wolf Creek Cooling Lake (several sampling areas indicated on Figure 4): control samples of similar specie 6 from John Redmond Reservoir indicated on Figure 4). Broadleaf Samples of available Monthly when Gamma isotopic Vegetation broadleaf vegetation available analysis on edible from two indicator portions. locations with highest , calculated annual aver-age D/Q (Locations A-1 and R-1 and alternate Location G-1 on Figure 4): sample of similar broadleaf vegetation from a control location greater than 10 miles from the site in a low D/Q sector (Location S-4 on Figure 5). 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 23 0F 50
T TABLE 1 (cont'd) 1990 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION EXPOSURE NUMBER OF SAMPLES SAMPLING AND- TYPE AND FREQUENCY. PATNWAY/ AND COLLECTION OF ANALYSIS SAMPLE- SAMPLE LOCATIONS- FREOUENCY INGESTION (cont'd) Irrigated- Sample of crops irri. At time of harvest Gamma isotopic Crops - gated with water from analysis on edible the Neosho River down- portions. stream of the Neosho River - Wolf Creek con. fluence (Location NR-D2 on Figure 5). Control sample of crops irri - gated with water.from the Neosho River up-stream of the Neosho
' River - Wolf Creek con-fluence'(Location NR-U1 on Figure'5).
- Game birds Indicator samples of Annually Gamma isotopic analysis on edible-
~
and- region specific: animals- recreationally impor- portions. tant specine from the=
~ vicinity-of Wolf-Crech 4 Lakes control samples of similar species from the vicinity-of John Redmond--Reservoir.
q. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION- PAGE 24 ,0F 50 t
TABLE 2
-SAMPLE LOCATION NUMBERS DISTANCES (miles) AND DIRECTIONS Location Distance / Location Distance / Location Distance /
Number Direction Number Direction Number Direction TLD'and Air Particulate l' 1.4/N 15- 4.5/ESE 29 2.6/SSW 2 2.7/N 16 4.2/E 30 2.2/W
- 3. 3.0/NNE 17 3.6/SE 31 3.0/WNW ,
4 4.0/NNE 18 3.2/SSE 32 3.2/WNW 5 4.0/NE 19 4.0/SSE 33 3.7/WNW 6 4.4/ENE 20 3.3/S 34 4.0/NW 7 1.9/NE 21 3.8/S 35 4.6/NNW 8' 1.6/NNE 22 4.1/SSW 36 4.2/N 9 2.0/ENE 23 4.5/SW 37 2.1/NNW 10 2.4/ENE 24 4.1/WSW 38 1.2/NW 11 1. 5 / E . 25 3.6/W 39 13.0/N 12 1.8/ESE- 26 2.6/WSW 40 >15.0/WNW 13 1.5/SE 27 2.1/SW 41 0.8/NNW-14 2.6/SE 28 2.6/SW 42 0.8/SSE 43 0.8/WNW-Ground Water Drinkina Valet Surface Water B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 10/SSE DC 0.6/WNW ~ C-49 2.9/SW: SP .2.9/S D-65 -3.9/S SP(ALT) 2.9/S Hilh Broadleaf Venetation Irrinated crops S-3 >15.0/WNW- A-1 1.4/N :NR-U1- 4.2/SW R-1 2.1/NNW NR-D2 ;>10.0/S
.G-1 1.6/SE S-4 >15.0/WNW- ,
Elah Shoreline and Bottom ' Aquatic Vegetation Sediment' /Alnae WCCL 0.6/WNW. DC 0.6/WNW DC 0.6/WNW JRR- 4/W JRR 4/W UHS 0.6/E-Game Birds and Animals-WCCL. General Vicinity JRR General Vicinity 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 25 0F 50
TABLE 3 1990 AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS RESULTS (pC1/m ) INDICATOR LOCATIONS INDICATOR STANDARD CONTROL DATE LOC 2 LOC 3 LOC-32 LOC 37 AVERAGE DEVIATION LOC 40 1/2-1/9 .033 .038 .032 .034 .0343 .0026 .031 1/9-1/16 .024 .027 .023 .024 .0210 .0017 .021 1/16-1/23 .050 .047 .045 .050 .0480 .0024 .043 1/23-1/30 .026 .026 .026 .010 .0220 .0080 .024 1/30-2/6 .035 .036 .032 .034 .0343 .0017 .034 2/6-2/13 .032 .031 .034 .031 .0320 .0014 .032 2/13-2/20 .033 .031 .033 .033 .0325 .0010 .033 2/20-2/27 .026 .025 .028 .031 .0275 .0026 .029 2/27-3/6 .033 .029 .032 .033 .0318 .0019 .032 3/6-3/13 .023- .024 .026 .020 .0232 .0025 .023 3/13-3/20 .021 .019 .019 .023 .0205 .0019 .021 3/20-3/27 .025 .029 .032 .029 .0288 .0029 .030 3/27-4/3 .015 .017 .014 .025 .0178 .0050 .024 4/3-4/10 .027 .029 .024 .028 .0270 .0022 .029 4/10-4/17 .027 .025 .032 .034 .0295 .0042 .033 4/17-4/24' .026 .024 .027 .024 .0253 .0015 .024 4/24-5/1- .018 .015 .019 .020 .0180 .0022 .015 5/1-518 ;023. .022 .025 .023 .0232 .0013 .020 5/8-5/15 .019 .018 .020 .019 .0190 .0008 .019 5/15-5/22 .019 .021 .021 .024 .0213 .0021 .021 5/22 5/29 .027 .022 .029 .024 .0255 .0031 .024 5/29-6/5 .022 .022 .023 .022 .0222 .0005 .023 6/5-6/12 .021 .021. .020 .022 .0210 .0008 .024' 6/12-6/19 .019 .021 .019 .022 .0203 .0015 .021. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 26 0F 50
* : c. !
i TABLE 3 (cont'd) 1990-AIR PARTICULATE SAMPLES ( OROSS BETA ANALYSIS RESULTS (pCi/m )
-INDICATOR LOCATIONS INDICATOR STANDARD CONTROL DATE LOC 2 LOC 3 LOC 32 LOC 37 AVERAGE DEVIATION LOC 40-6/19-6/26 .026 .027 .028 .027 .0270 .0008- .028-6/26-7/3 .024 .026 .030 .029 .0272: .0028 .029 17/3-7/10 .026- 028 .0311 .028 .0283 .0021 .028 7/10 *//17 . 025 .028 .028 .027 .0270= .0014- .030
-7/17-7/24 .021' .024 .019 .020 .0210 .0022 .018 7/24-7/31 .0261 .028 .029 .032 .0288 .0025 .027
- 7/31-8/7 .019 1 020 .023 .022 .0210 .0018 .023
,8/7-8/14 1 026- .024 .025 .028 .0258 .0017- .023 8/14-8/21. .024= -.021 .021 .024 .0225 .0017 .024 8/21-8/28- .026 ,.024' .027 .029 .0265 .0021 .024
-8/28-9/4 .038 .035 .041 .040 .0385 .0026 .034 9/4'-9/11. .037- '.029 .032 .034 .0330 .0034 .027 9/11-9/18 .025 .023 .022 .023 .0232 .0013 .022
.9/18-9/25 .020' . 022 024 .025. .0227 .0022 .023 9/25-10/2 .035- .037 .04 .642 .-0385 .0031 .036
- 10/2-10/9; '0231. .025 .026 .023 .0243 .0015 .025 10/9a10/16):.036' .032 .034 .032- . 0335 .0019 .036-10/16-10/23 .~019 .026- .028 .022 .0238 .0040 : 027-L 10/23-10/30 .015 .025- .029 .029 .0245 .0066- .025 10/30-11/6 .032 .029 .034 - .030 .0312 .0022 .029' 11/6-11/13: .035 .037 .036 .042 .0375 .0031 .038 i'
R 11/13-11/20 .032' .032- .031 .035 .0325 .0017 .027-
- l. 11/20-11/27 .024 .021 .024 .025 .0235- .0017 .022
- 11/27-12/4 .028- .025' .025 .032 .0275 .0033 -.024 L:
1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
-WOLF CREEK GENERATING STATION PAGE 27 0F 50
TABLE 3 (cont'd) 1990 AIR PARTICULATE SAMPLES GROSS BETA ANALYSIS RESULTS (pCi/m ) INDICATOR LOCATIONS INDICATOR STANDARD CONTROL DATE LOC 2 LOC 3 LOC 32 LOC 37 AVERAGE DEVIATION LOC 40 l 12/4-12/11 .031 .024 .029 .032 .0290 .0036 .028 12/11-12/18 .039 .036 .040 .042 .0393 .0025 .038 , 12/18-12/26 .040 .042 .040 .046 .0420 .0028 .037 ' 12/26-1/2 .036 .041 .041 .039 .0393 .0024 .040 l l 1990-ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 28 0F 50 i
. . _ . _ , . . - _ . _ . . ~ . _ _ . . . _ . . - - . _ - ~ . _ , . _ . . m._..._ - _ - . . _ > _ _ . _ _ _ , _ . .
r= ..
~i TABLE 4 -!
AIR PARTICULATE COMPOSITE SAMPLES GAMMA ANALYSIS RESULTS-(pC1/m ) (CNTRL) ISOTOPE 2R W W LOC 32 LOC 37 LOC 40 Be ist- ,053'7 .0565 .0582 .0712- .0449 2nd _60493 .0414 .0133 .0168 .0668 3rd .0624 .0535 .0647 .0529 .0607 4th .0552 -.0484 .0489- .0553 .0530 K 1st -00883- .0130 ND ND ND'
- 2nd .00935 ND ND- .00795 ND 3rd ND ND ND ND ND 4th ND ND .00753 ND ND ND._--Not Detected
-No OTHER GAMMA EMITTERS DETECTED.
l
-i 4
i 1 [
~
-1990 ANNUAL' RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 29 0F 50--
s..
. _ . _ . - . _ _ _ _ .. _ _._ . _ _ _ _ _ .- _ _ _ . _ _ _ _ , . _ .__.m 6
TABLE 5 1990 TLD RESULTS (mR/ Standard Quarter *) [ IST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER LOCATION. AVG 1pff, M M M 1pE E 1pE 1- 18.0 0.6 15.3 0.4 15.6 0.3 16.4 0.1 2 .14 . 9 - 0.2 13.6 0.7 13.9 0.2 15.4 0.6 3 16.1 0.3 14.7 0.2 15.2 0.4 15.2. 0.8. 4 18.0 0.3 15.3 0.3 17.0 0.8 15.4 0.8
-5 15.4 0.3- 14.9 0.2 14.8- 0.5 15.1 0.4 6 15.7 0.3 14.4 0.3 14.4 0.4 13.8 0.7 7 15.3 0.3 13.8 0.3 14.0 0.6 14.5 10 . 7 8 17.4 0.4 14.5 0.8- 16.0 0.5 17.2 1.2 9 17.1 10 . 6 14.7 0.5 14.1 0.3 11 6 . 6 - 1.0 10 17.9L 0.3 15.7 0.3- 15.7 0.2 16.4 0.3
-11 .19.2 1.0 117.1 0.4' 17.4 0.9 18.3 0. 8' 12 17.8 0.5- 15.3 0.3 '15.4 0.4 16.4' O.5 13 17.5 0.3 15.7 0.4 1.5 9 0.3~ 16.7 0.5 14 17.2 0.5 -15.8 0.2 15.9- 0.4 16.4 0.4 15 16.7L 0.3 R15.5 0.3 16.8 0.5 15.4 0 ~. 4 16 16.9 0.6 16.1 0.6 17.6- 0.2' 14.9 2.8 17: 16.7 0.9: '15.1 0.3 - 14.2 1.0 15-1 . 1.2 18~ .17.9 0.7 16.5' O.5 16.7' 0.5 16.7 :3.2 19 20.1 1.0'- 16.2 0.4. 17.0 0.4 114.3- 0. 9' 20 17.5- 0.5 15.4 - 0. 2 - 15'.2 0.7 15. 8 -- -0.7 21- 15.1** 0.1 13.5 0.4 14.0 0.4: 13.11 -- 1. .- 22' 17.3 '0.6 14.8 -0.2 15.5 0.3 14.1 1.2 J23 117.3 0.2 14.9 0.3 15.5 0.3 14.7 0.9 24 '16.6 0.3 15.3. 0.3- 18.8 1.0 15.4 0.9
'
- 90 days per Standard Quarter lj **' Based on the results-of one TLD l
s l-1990-ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF lCREEKLGENERATING STATION PAGE 30 0F.50 o
~n . _ _ _ , , _ . _ . . . . . . _ _ __ _
TABLE 5 (cont'd) 1990 TLD RESULTS (mR/ Standard Quarter *) IST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER LOCATION AVG SDEV AVG SDEV AVG SDEV AVG SDEV 25 15.3 1.2 12.0 0.3 13.7 1.1 11.8 0.9 26 15.6 0.5 13.8 0.4 14.3 0.3 13.7 1.1 27 17.5 0.5 15.3 0.6 16.2 0.2 15.6 0.4 28 15.7 0.2 14.9 0.2 13.6 0.5 13.0 0.5 29 14.1 0.2 13.3 0.5 13.8 0.4 13.2 0.3 30 15.6 0.3 14.6 0.3 15.2 0.2 13.6 1.2 31 15,9 0.9 14.6 0.4 14.9 1.0 15.1 0.5 32 14.9 0.4 13.6 0.6 14.4 0.5 14.9 0.3 33 17.9 0.2 15.8 0.3 17.2 0.2 16.0 0.6 34 17.6 0.5 14.6 0.9 16.3 0.4 14.9 1.8 35 17.5 0.4 16.4 0.2 15.7 0.6 15.6 0.3 36 16.1 0.4 14.9 0.4 16.5 0.3 15.8 0.6 37 16.1 0.1 13.6 0.3 14.8 0.1 15.2 0.8 38 17.3 1.0 17.0 0.5 17.4 0.3 16.1 0.6 39 15.9 0.3 15.3 0.7 15.8 0.3 15.6 0.5 40 15.5 0.7 12.8 0.2 12.8 0.5 14.2 0.4 41 16.9 0.3 11.6 1.4 15.3 0.3 16.4 0.6 42 10.8 0.7 10.1 0.2 10.0 0.2 11.1 0.5 43 9.9 0.2 8.9 0.3 9.0 0.2 9.7 0.4
- 90 days per Standard Quarter 1
1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 31 0F 50
4 TABLE 6 DRINKING WATER SAHPLES GROSS BETA ANALYSIS RESULTS (pCi/11ter) MONTH INDICATOR CONTROL LV-40 BW-15 JAN 6.2 i 1.2 7.1 1 1.3 FEB 50 1 3.0 8.3 1 1.6 MAR 6.4 1 1.3 6. 5 i 1. 3 APR 5.6 i 1.4 6.0 1 1.4 MAY 5.4 1 1.2 6.3 1 1.2 JUN 7.211.4 5.1 1 1.2 JUL 4.8 1 1.3 6.3 1 1.4 AUG 4.8 1 1.2 6.5 1 1.3 SEP 4.0 1 1.2 6.3 i 1.3 OCT 7.2 1 1.4 13 1 7.0 NOV 7.3 1 1.5 6.1 1 1.3 DEC 6.2 1 1.5 7.5 i 1.4 s TABLE 6A DRINKING WATER SAMPLES TRITIUM ANALYSIS RESULTS* (pCi/11ter) QUARTER INDICATOR CONTROL LW-40 BW-15 let < 200 < 900 2nd < 900 < 900 3rd 860 1 340 1600 1 400 4th < 700 < 700
- Deteccion Limit - 700-900 pCi/11ter Reporting Level - 20000 pCi/11ter 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l WOLF CREEK GENERATING STATION PAGE 32 0F 50
A l n.. TABLE 7 SURFACE WATER SAMPLES TRITIUM ANALYSIS RESULTS -
. (pci/ liter)
DC . SP .SP(ALT) MUSH p.611 ' (INDICATOR)- (INDICATOR) (INDICATOR) (CONTROL) 1/16/90 7000 1 500 6800 1 500 N/A- .< 500 2/20/90~ 7500 1.700 8100 1 700 N/A < 900 3/20/90 .7900 1 600 7700 1 600 N/A_ < 800 4/17/90~ - 7800 1 600 7500 1 600 N/A < 900 5/15/90 7400 1 600 7100 1 600- N/A < 800 6/19/90 6600 1 600 7600 1 600 N/A . <.800 7/17/90' 6200 i 1400 6600 i;1400 N/A < 900~ 8/21/90- 5600 1 500 5600 1 500- 5600 1 500 < 600 ~ 6200 +'500 6100 + 500
'9/18/90- ..5800 + 500 < 600
- 10/16/90:
5300 1.600 5100 1 600 5500 1 600 <.900
- 11/20/.90 9000 + 600 ;5600 + 500 ,5900 1 500 < 600 ,
o - 12/18/90; - 5500 i'500.~ 5300-i 500- ;5400;i 500 .<-600-i f 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
' WOLF = CREEK GENERATING l STATION PAGE.33 0F 50_
,v-- -- , --
TABLE 8 BOTTOM SEDIMENT / SHORELINE SOIL GAMMA ANALYSIS RESULTS (pC1/ gram - dry weight) INDICATOR CONTROL WCCL JRR DATE SAMPLE TYPE NUCLIDE CONCENTRATION CONCENTRATION 4/17/90 Shoreline Soil K-40 9.96 i 1.00 N/A Discharge Cove Co-60 0.177 1 0.029 N/A Ra-226 1.58 1 0.51 N/A Th-228 1.14 1 0.11 N/A 6/26/90 Bottom Sedbment K-40 12.2 1 1.2 N/A Discharge Cove Co-58 0.0686 1 0.0402 N/A Co-60 0.345 1 0.054 N/A Cs-137 0.411 1 0.047 N/A Ra-226 1.57 1.0.55 N/A Th-228 1.32 1 0.13 N/A 6/27/90 Bottom Sediment K-40 12.5 1 1.3 N/A Ultimate Heat Co-60 0.082 1 0.0266 N/A Sink Canal Co-137 0.311 1 0.031 N/A Ra-226 2.05 1 0.36 N/A Th-228 1.11 1 0.11 N/A 6/27/90 Bottom Sediment K-40 12.3 1 1.2 N/A Ultimate Heat Co-60 0.0728 1 0.0323 N/A Sink Dam Area Cs-137 0.555 1 0.056 N/A Ra-226 2.66 1 0.6 N/A Th-228 1.51 1 0.15 N/A 9/25/90 Bottom Sediment K-40 11.3 i 1.1 N/A Discharge Cove Co-60 0.253 1 0.049 N/A Cs 137 0.280 1 0.034 N/A Ra-226 1.37 1 0.75 N/A Th-228 1.12 1 0.11 N/A 10/1/90 Bottom Sediment K-40 N/A 4.7 1 1.5 John Redmond Cs-137 N/A 0.188 1 0.019 Reservoir Ra-226 N/A 1.82 1 0.37 Th-228 N/A 1.46 1 0.15 l 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 34 0F 50
TABLE 8 BOTTOM SEDIMENT / SHORELINE SOIL GAMMA ANALYSIS RESULTS (pci/ gram - dry weight) INDICATOR CONTROL WCCL JRR DATE SAHPLE TYPE NUCLIDE CONCENTRATION CONCENTRATION 10/16/90 Shoreline Soil K-40 10.5 i 1.1 N/A Discharge Cove Co-60 0.151 1 0.027 N/A Cs-137 0.0958 1 0.0282 N/A Ra-226 2.13 1 0.47 N/A Th-228 1.13 1 0.11 N/A 10/15/90 Shoreline Soil K-40 N/A 10.7 1 1.1 John Redmond Ra-226 N/A 1.96 1 0.73 Reservoir Th-228 N/A 1.40 1 0.14 e 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 35 0F 50
..~ !? ,
Q,; TABLE 9
-AQUATIC VE0ETATION FROM WCCL DISCRARGE COVE GAMHA ANALYSIS RESULTS (pci/ gram - wet weight)
DAIX VEGETATION TYPE NUCLIDE CONCENTRATION
-i '
6/26/90- . Algae Be-7 1.13 1 0.11 K-40 1.85 1 0.18 Co-58 0.0444 1 0.0083 7 Co-60 0.0488 1 0.0086 Cs-137 0.0589 1 0.000 Ra-226 0.215 1 0.125 Th-228 0.119 -i 0.012 9/18/90 . Algae Be-7 0.750 1 0.088 K-40_. 1.88 1 0.19 < Mn-54 0.0121 1 0.0053 Co-58 'O.0433 1 0.0072 Co-60 -0.118 1 0.012 i:t Os-134 0.0416 1 0.0071-Co-137 0.113 1 0 011 Ra-226 0.45 1 0.119 Th-228 -0.201 1 0.020-1 e-I t
^
l.- i l 1990-ANNUAL RADIOLOGICAL. ENVIRONMENTAL OPERATING REPORT l :VOLF CREEK GENERATING STATION PAGE 36 0F 50
TABLE 10 RESULTS OF THE 1990 LAND USE CENSUS DIRECTION DISTANCE (MILES) TO NEAREST: SECTOR- FROM PLANT RESIDENCE MILK ANIMAL GARDEN A N 1.4, 4.5, 1.4 B NNE 3.1 4.1 3.1, C NE 1.9 NON{ 2.2 D ENE 2.1 -2.4 2.1 E E 1.8 NONE_ 1.8 F ESE- 1.6 4.7 , 1.6 G SE 1.6 NONE 1.6, N SSE 3.1 NONE 4.3, J S 3.3 NONE 3.8 K SSW 2.6 NONE 4.1, L SW 2.1 NONE 3.1 M WSW 1.6 1.6 2.4 , N W 2 .1, - NONE HONE P WNW 2.8 NONE 2.0, Q NW- 1.4 NONE 3.2 R 'NNW 1.9 NONE 2.1 Indicates-a change from 1989 data. 1990 ANNUAL ILADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 37 0F 50
TABLE 11 RESULT 9 0F EPA INTERLABORATORY COMPARISON TESTS COLLECTION EPA TELEDYNE DATE MEDTA NUCLIDE RESULTS(a) RESULTSfb) 10/31/90 Water Gr. Beta 32.00 1 5.00 30.33 1 0.58 Cs-134 5.00 1 5.00 5.33 1 1.15 Cs-137 5.00 1 5.00 7.00 1 0.00 1/26/90 Water Gr. Beta 12.0 1 5.0 12.33 1 1.73 2/9/90 Water C0-60 15.00 1 5.00 15.00 1 3.46 2n-65 139.00 1 14.00 131.33 1 9.07 Ru-106 139.00 1 14.00 113.67 1 4.04 (c) Cs-134 18.00 1 5.00 15.33 1 2.31 Cs-137 18.00 1 5.00 19.33 1 3.21 Ba 133 74.00 1 7.00 66.00 1 3.46 2/23/90 Water H-3 4976.00 1 498.00 4900.00 1 100.00 3/30/90 Air Gr. Beta 31.0 1 5.0 31.67 1 0.58 Filter. Os-137 10.0 1 5.0 10.67 1 1.15 4/17/90 Water Gr. Beta 52.0 1 5.0 53.33 1 1,53 Cs-134 15.0 1 5.0 12.67 1 1.53 Co-137 15.0 1 5.0 16.33 1 1.15 l 4/27/90 Milk I-131 99.0 1 10.0 89.67 1 3.21 Cs-137 24.0 1 5.0 27.33 1 2.52 K 1550.0'i 78.0 1483.33 1 75.06 5/11/90 Water Gr. Beta 15.0 1 5.0 17.00 1 1.00 , 6/8/90 Water Co-60 24.0 1 5.0 25.33 1 2.52 i L Zn-65 148.0 1 15.0 148.67 1 3.06 Ru-106 210.0 1 21.0 196.00 1 20.66 i Cs-134 24.0 1 5.0 23.67 1 2.89 Cs-137 25.0 i 5.0 24.67 1 2.08 Ba 133 99.0 1 10.0 93.00 1 6.08. 6/22/90 Water H-3 2933.0 1 358.0 2900 1 100.00 8/10/90 Water I-131 39.0 1 6.0 36.00 1 3.00 8/31/90 Water Gr. Beta 62.0 1 5.0 63.33 1 1.53 Co-137 20.0 1 5.0 18.33 1 3.21 Footnotes at end of table. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 38 0F 50
TABLE 11 (cont'd) RESULTS OF EPA INTERLADORATORY COMPARISON TESTS COLLECTION EPA TELEDYNE DATE MEDIA NUCLIDE RESULTS(a) RESULTS(b) 9/21/90 Water Gr. Beta 10.0 1 5.0 11.00 1 1.00 9/28/90 Milk I-131 58.0 1 6.0 54.67 1 1.53 Cs-137 20.0 1 5.0 23.00 1 1.73 K 1700 0 1 85.0 1710.00 1 65.51 10/15/90 Water Co-60 20.0 1 5.0 21.00 1 1.00 Zn-65 115.0 1 12.0 115.00 1 11.53 Ru-106 151.0 1 15.0 142.00 1 8.66 Cs-134 12.0 1 5.0 11.00 1 0.00 Cs-137 12.0 1 5.0 16.33 1 2.52 Ba-133 110.0 1 11.0 94.67 1 5.13 (d) 10/19/90 Water H-3 7203.0 1 720.0 7133.33 1 251.66 10/30/90 Water Gr. Beta 53.0 + 5.0 51.00 + 2.31 Cs-134 7.0 + 5.0 9.00 + 0.00 Cs-137 5.0 + 5.0 7.67 + 1.15 FOOTNOTES: (a) EPA Results - Expected laboratory precision (1 sigta). Units are pCi/11ter for water, and milk except K (total) is in mg/ liter. Units are total pC1 for air particulate filters. (b) Teledyne Results - Average +/- one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pC1 for air particulate filters. (c) No apparent cause for the low results were found. Three aliquots of the sample were counted on three separate detectors. The results of all three were similar. The calibration curve fit is good (0.997). Ruthenium-106 was obtained from the EPA. Results of spikes were acceptable. Subsequent cross-checks from the EPA did not exceed two normalized standard deviations. No additional follow-up is necessary, but Teledyne will continue to monitor the results. New calibrations were completed in March, 1991.
-(d) There is no apparent reason for the deviation between the EPA and Teledyne Isotoper, values. Other isotopes in the semple were measured accurately. The calculations vers reviewed and activities calculated from other Ba-133 gamma rays. Results were reproduced as reported.
1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 39 0F 50
FZGURE 1 4
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~---- - h ~~~~
I R , ,, B /
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*- AIRBORNE PARTICULATE AND RADIOIODINE 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 40 0F SO
FIGURE 2
\ iA h N 0 I j[ / ___ _ d ! __
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1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 41 0F 50
FIGURE 3
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*- DRINKING WATER A-SURFACE WATER m-GROUND WATER v-SHORELINE SED l MENT BOTTOM SEDIMENT AQU ATIC VEG'ETATION ,
1990 ANNUAL RADIOLOGICAL ENVIR0tatENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 42 0F 50
FIGURE 4
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FIGURE 5
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*-TLD s-DR!NKING WATER A-MILK *-BROADLEAF VEGETATION /
IRRIGATED CROPS 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT WOLF CREEK GENERATING STATION PAGE 44 0F 50 l- _ - - _ - _ - _ _ - _ _ _ _ - _ _ - _ - _ _ _ _ _ - . _ _ _ _
.l e-l 03 1990 AIRBORNE PARTICULATE ACTIVITY og
! gg aOs WEEKLY GROSS BETA ANALYSIS RESULTS l !:!g Og jg 0.07 -
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9 -r"5. 9 !E OPERATIONAL TLD RESULTS y@5 -tNEARSITE & CONTROL LOCATION AVERAES) 24 - 0C 22 - C"85 o gr . g8 20 ' '- w9 ' gc m_ \ ME ce
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8% E;a OE 1990 DRNKiNG WATER ANALYSIS m5
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GROSS BETA E 00
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Appendix A Sumary tables in format of NRC Radiological Assessment Branch Technical Ptssition Revision 1, November 1919
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. , _ 30M CRyyK GENERATING STATION APPENDIX A
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ENVIRONMENTAL RAD!OLOGICAL MONITORING IHOGRAM
SUMMARY
O so Name of Facshty Wol1 Creek Nuclear Docket No STN 50-462 Q
> 14auon of Facility Coffev County. Kansas RegwntingIYrk=1 Annual 1990 Q2 m2 (County. Statel m <=
7c > r-c) Number of 2p Ana}ysts an.J Lower IJmat mo Medium of Pathway Total Number of AILIrxilcator_lacauuna Imf hn with Itwhest Anr= == l Mean Controllocations "Mean to Nonroutine Reported Sampled of Analysis Detection " Menn (0 Name "Mean 10 y5 (LLD) " Range Distance armi Dirceuons "Hange " Range Meneurements"
-ar- ~O (Unit of Measurement) Performe( Munh z cn c) -
O w> Water NA 0 NA gr-
-orn Surface (pCl/I)
Gamma (41) -10/2 9)
-(O / 1 23 -z O< DC O.6 miles WNW 6800(12/I2) -10 /1 21 O z- Triuum (41) 1000 6500(29/29)
(5100-9000) (5300-9000) -- O z 3 ro 2 '
-4 r
O m m N
.-.4 2
O
- .W l m m
O N
-t >m 7> *U O m ra z
o
- CD >O 9 C)
- N,marsal temer tamet ed lxterswm (1L171
** Mran arwt range taasnt upme detettatale meauwemenas only Frartum of detettatJe meestwements at spenbrd I,=ratmwn is ee=fsrascef en parerisheses (f)
i Appendix B Individual Sample Results
o g i e N N N N N N N N N N N N N N N N N N s = 0 0 0 0 0 0 C O O O O O O O O O O O m e e e 0 6 0 6 I o e 6 6 0 4 6 6 e o e E E i W W W W W W W W W W W W W W W W W W
= ei amDi gewi e e e e e e e e e e e e e e o e e e O t % N N mm N N N N N N N N N N N N N N Wmm u W e t i e e e e e e ~ > >ee e
e e e e e a e e e e 2 w i > > > > > > > > k >e > > > > > >a w e o e e e e e e e o e e e e e a e d a & M e a a e d & d a e a a a e t
> I OWW e m a h e O N *
- O 4
- P h N = 4 e a WEk l m N N O = = N C = = N N O N N ime6 % % %
= O =
Obot = = a N N N N m m m m m e * *
- e e
*- 4 C O O O O O O O O O O O O O O O O C E 1 1
1 4 4 I I t e I a w N N N N N N N N A N N N N N N N N N C > C C O O O C C O O O O O O O O O O O w d i e e i e i I e o e I t e e t t t W = = W u- W W W W W W W W h W W t OF W W W W m m me e 2e W> T m e e m 9 m e m m m e m N a m e e e =t & >W e e o e e e e e e e e e o e o e e e e >& 4 d@D O C O O O O O O O O O O O O O O O C et O N = wt I e a e I I i 1 6 t t a t t t t um w O he% 9 + o e + + + 6 e e e 4 + + + + t e a e o We a P= 1 L e a LOui m
- O 4 e N P 4 m w =e e e c >e > @ g m Qt Z W sk i e e e e e e e e e o e e e e e w e 4Ww m N e N e m P N e N N N = N N N = N Ek E ee 4 D W 3 E d 2 W W> > g a 3e e C 6 RE a a e D > 0 mW w e > 0 W W m > 3 4 W D > e D 1 P P e O e h N e e m O h e e e e e &
W e W CWW 4 = N N = N O e = N e O = N N O m wok e VE> l %- ' a 6 eme l = N N N m a m m m e e e e e e 9 WM O>Of O O O O O O O O O O dW h = O O O O O O t C = g 4 3 4 e . w t
=i 2 4 U el W W W W W W W W W W W W W W W W De w i w w w w w w w w w w v v v w w w j e , e e e e e e e e e e e e e e e e O O O O O O O O O O O O O O O O O O h
E W W W W W W W u W W W W W W W W W W D e > P W > N N e N m e = 0 C e e a e d = P e O P O O P W m C O O O m a e N C e e e e e o e e e e e e e o e e e e
> m N N m N mm N N N mm e m e m m v l'
I t 1 9 4 m O @ P O M d e O k m O > d m e W A h- l O = N m o a N N O = N N O m a N C O
>C> l % % % % % % % % % % % % % % % % % %
e>e a a o e N N N N 9 m 9 m 4 e e 4 9 e Cec O O O O O O O O O O O O O O O O O O E I O I
= 1
>> I N e e= m O 4 m O > 4 m e h m O N + =
veW h C C N m o a e A L = % N e a m N O u d > l % % % % % % % % % % % % % % % % % % d> e i m = o e m N N h N
- a m p weC C C C O C O g 4 4 e c i
C C O C O O O O O O O C O l ' V i 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 1 0F 72 WOLF CREEK GENERATING STATION APPENDIX B
l' _ . 4 4 4 r 5 Unt F C'd E E E NUCLE AR' OPFr a f t sc ConP < .* ~ *
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-WOLF CREEK GENERATING STATION APPENDIX B
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h 1990-ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 25 =0F 72
- WOLF. CREEK GENERATING STATION APPENDIX'B
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WO1E CREEK NUC1. EAR OPERA ~IING CORPORA'110N EXPOSURE PA'111WAY - AIRBOHNE
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pe* T11ERMOI.UMINESCENT DOSIMETERS mo het mR/ day) n an E5 STATION FIRST QUARIER SECOND QUAxtER 'IlllRD QUAKIER FOURI11 QUAIGER 01/03/90-04/04/90 04/04/90-07/02/90 07/02/90-10/03/90 10/03/90-01/03/91 g NUMBER 5b STA-25 0.17310.049 0.13010.011 0.15610.009 0.15510.008 gg 0.15210.008 0.16210.010 0.17710.011 d5 STA-26 0.17210.021 0.19910.000 0.16910.011 0.18010.004 0.19210.013
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1 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 29 0F 72 WOLF CREEK GENERATING STATION APPENDIX B
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l APPENDIX C ENVIRONMENTAL MONITORING TRITIUM LEVELS
ENVIROIMENTAL WONITORING TRITIIM LEVELS c Tritium is monitored in the environment around the plant through drinking, surface, and ground water samples. Table C-1 summarines the characteristics of these samples. TABLE C-1 SAMPLE FREQUENCY REQUIRED ACHIEVED REPORTING CURRENT LLD LLD LEVEL LEVEL (pC1/1)- (pci/1) (pci/1) (pci/1) Surface Monthly 3000 700-900 30,000 7000 - 8000 i Ground Quarterly 2000 100-200 20,000 <200 Drinking Quarterly 2000 700-900 20,000 <900 , Before looking at tritium levels in the environment a knowledge of the quantity of. tritium released from the plant is required. That information is shown on Table-C-2 and Figure C-1. This information was taken from the
. Semi-annual Radiological Effluent Reports (1985-1990) submitted to the NRC.
Since the beginning of plant operation through July 1990 a total of 2,186 Ci of tritium han-been released to Wolf Creek Cooling Lake-(WCCL). Some of the released tritium has decayed or been removed from the lake through other mechanisms such as evaporation, percolation to ground water,-and discharges E to Wolf Creek. The rest of the tritium has remained in WCCL. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 1 0F 14 WOLF. CREEK GENERATING STATION APPENDIX C
. . _ . .._. ,_ ._ _ _ .._ . .- _ . ._. . _ _ _ m . . . _ . _ _ _ _ . _ _ _ . - - .x ,,.
TABLE C-2 Semi Annual' Effluent Release Report Data YEAR -QUARTER ' CURIES . YEARLY DILUTION RELEASED TOTAL VOLUME (1) & 1985 1 , 2 0.137 5.22E09 3 50.8 4.20E10 - . 132.0 2.28E10- I 4 (182.94) ' 1986 1 129 2.35E10 2 -108 2.10E10 3 84.0 .. l'.64E10 4 $6.3 (377.3) 1.20E10 1987 1 88.5 9.84E09 2 115 1.30E10 3 102 -2.40E10 4 11.1 (316,60) :3.21E09 1 1988 1- 38' L7.61E09 2 -166 6.93E09 1 3 ~137 8.25E09 4 64.7 (405.70) 3.70E09 -j 1989 1 9.23 2.54E09 ' 2 119 3.22E09- - '; 3- 186 3.82E09 7'
-4 274 (588.23) 2.45E09 1990 1 293 8.93E09 .
2 22.1 1.11E10 3: 14'
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; WOLF' CREEK GENERATING STATION APPENDIX C
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q* , SURFACE WATER SAMPLIAG Surface water has been sampled at three locations: 1) John Redmond Reservoir below the gates-(FDSH), 2) WCCL Discharge-Cove (DC), and 3) WCCL Main Dam by the Auxiliary Spillway (SP). Location SP(ALT) had not been added when this_ study was performed. Prior to plant operations the tritium concentration in WCCL was less than the lower limit of detection. Analysis results from. monthly samples obtained ac sample locations DC-and SP reflect the builduplof tritium in WCCL due to plant effluents. The analysis results for DC and SP are displayed graphically _in Figures C-2 and C-3 respectively. This tritium buildup in WCCL will reach an equilibrium value which is dependent _upon Curies of H-3 released,- WCCL makeup and discharge, and radioisotopic decay. The USAR equilibrium value, taken from USAR Table ,
- 11.2 3 CALCULATED LIQUID EFFLUENT DISCRARGE CONCENTRATIONS FROM ROUTINE-OPERATION, is 23,400 pCi/1, The USAR value takes into consideration buildup or reconcentration of tritium in the cooling lake and the circulating water discharge over a 40 year plant life expectancy. The last five of these years are considered to be during a drought.
Using_a simplistic model for calculating nuclide buildup taken from NUREG/CR-3332 Radiological Assessment - A Textbook-on Environmental Dose Analysis, an approximation of the--current _ concentration as well as the equilibrium concentration expected in WCCL has been calculated. Using an average tritium release of 437 Ci/ year and an average dilution volume of-4.93E10 1/ year,'the current tritium concentration in WCCL should'be-approximately 7200 pCill and the equilibrium concentration will approach 9400 pC1/1 in seven more years. These figures are based on. average release rates, dilution-flows, lake discharge / makeup flow,-and does not account for periods of drought or-increasing; tritium releases from the~ plant. Current, tritium concentrations.in samples obtained from WCCL discharge cove and.at-the main dam vary from 7000 - 8000 pC1/1. Occasionally, a higher than normal tritium concentration will-be detected in the discharge cove when' sampling is coincidental:with a radioactive release from the. plant. I L 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 4- 0F 14 l~ WOLF CREEK GENERATING STATION APPENDIX C n>-e. --i s*p-e.--+w,.>mt-su-- . .g.
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I GROUND WATER SAMPLING Ground water is obtained from four locations around the plant, a control location (B-12) and three indicator locations, (C-10, C-49, D-65). Figure 4 shows the actual sample locations. Since February 1988 tritium activities of 150 to 300 pCill have been detected routinely in ground water s.mples. Occasionally activities as high as 600 - 800 pCill H-3 have been detected. Figures C-5 through C-8 show the detection limits achieved as well as the positive tritium activities measured at the same locations. Figures C-5 through C-8 also show how ground water tritium is more difficult to compare to preoperational data because the lower limit of detection has decreased since the initiation of the environmental sampling program. Initially the LLD was 2000 pCi/1. This was reduced to 2000 pCill in October 1981 and reduced again in February 1988 to 100 - 200 pCi/1 by changing the analysis method (Reflected on Figures 5-8). This means the levels we are currently detecting were not seen prior to operation because of the higher detection limit. Therefore, looking as WCGS data alone, does not allow a conclusion about the source of tritium to be made. However, a comparison of Wolf Creek data to that obtained by the State of Kansas at these same sample locations indicate the tritium is due to plant operations. Prior to plant operation to the tritium activity measured by the State of Kansas was
< 100 pCill (samples obtained from June 1983 through May 1985). Following plant start-up, tritium activities were occasionally detected above 500 pCill at all the indicator locations. See Table C-4 for actual State of Kansas data.
Since the tritium activity in the ground water is most likely due to plant effluents, dose projections have been made from the activity levels detected. Using the highest detected activity at all of the sample locations, 810 pC1/1, and the drinking water pathway doses were calculated for all the age groups, see Table C-3. TABLE C-3 TOTAL BODY AND ORGAN DOSE FROM GROUND WATER TRITIUM AGE GROUP HAXIMUM AVERAGE INDIVIDUAL INDIVIDUAL Adult 0.062 mremlyr 0.032 mremlyr Teen 0.044 0.022 Child 0.084 0.043 Infant 0.082 The dose limits from liquid effluents for any member of the general public are less than or equal to 1.5 mrem /qtr total body and less than or equal to 5 mrem /qtr to any organ and less than or equal to 3 mremlyr total body and less than or equal to 10 mremlyr to any organ. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 7 0F 14 WOLF CREEK GENERATING STATION APPENDIX C
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l 1 1 , y ,- i i TABLE C-4. KDHE Groundwater H-3 Measurements DATE B-12 C-12 C-49 D-65 pCill pCill pCill- pC1/1 05/16/89 246 241 177 255 02/21/89 -254 -230 61 -116 11/15/88' 99 '242 96 269 08/16/88 225- 226 327 281 aci/1 nC1/1 nC1/1 nC1/1 05/17/88 0.2-t 0.3 0.1 1 0.3 0.1 t 0.3 0.210'3 . 02/16/88 0.1 1 0.2 0.0 1 0.2 0.0 t 0.2 0.1 1 0.2 11/17/97 0.0 1 0.2_ 0.2 1 0.2 0.0 t 0.2 0.2 1 0.2 08/18/87- - 0.0 t 0.5 -0.0 t 0.5 0.0 t 0.7 0.0 1 0.5 05/19/87 0.0 t 0.4 0.0 t 0.3 0.6 1 0.3 0.8 1 0.4 02/17/87 . 0.0 t_0.4 0.7 t 0.4 0.9 t 0.4 0.0 t'O.4 i 11/18/86- 0.2 1 0.3 10.0 t 0.3 0.7 t 0.7- 0.2 1 0.3-08/19/86 - 0.0 t-0.3 0.2 tL0.3 0.9 1 0.3 0.0 1 0.3 05/20/86 0.4 t 0.3 0.5 1 0.2_ 0.3 1 0.3 0.5 t 0.3 02/18/86 0.0 t 0.3 0.0 1 0.2 0.1 t 0.3 0.3 1 0.3 11/19/85- 0.0 t 0.3 0.6't 0.3 0.0 t 0.2 .0.1 t 0.2 08/20/85 0.2 t 0.2 0.2 1 0.2 0.1 1 0.2 0.1 1 0.2 05/21/85 _0.0 1 0.2 0.0 t.0.2 0.0 t 0.2 0.0 t 0.2 l
-02/19/85 0.1 t-0.2' O.0 1 0.3- 0.1 t 0.2 0.1 t 0.2 >
11/19/84 0.1 t_0.2_ 0.0 t_0.3 0.0 1 0.3 0.0 t 0.3 , 08/14/84- ~ 0.0-t 0.2 0.0 t 0.2 0.1 t 0.2 0.0 t 0.2 i y' 05/22/84- 1 0.0 t 0.2 0.0't-0.2 0.0 1 0.2 0.0 t 0.2 102/14/84 ;0.0 1 0.3 0.3't 0.3 0.0 1 0.3 0.0 t 0.3 '
.11/08/83 - 0.0 1 0.3_ 0.1 1;0.'3- 0.0 t 0.3 0.0 t 0.3 08/17/83 0.2 t-0.3- 0.2 1 0.3 0.1 1 0.3 0.0 1 0.2 06/17/83 N/A .0.1 1 0.2 10.111 0.2. 0.1 1 0.2 ;
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- l. 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 13 0F 14 l WOLF. CREEK GENERATING STATION APPENDIX C i I
f 's , l DRINKING WATER SAMPLING Drinking water samples are monthly composite samples taken from the water treatment facilities at Burlington (control sample) and LeRoy (indicator sample). Tritium was detected at both of these sample locations during the third quarter composite for 1990. The tritium concentration at the control location (BW.15) was 1600 pC1/1 and at the indicator location (LV-40) was 860 pC1/1. The activity measured at LeRoy was at the detection limit (700 to 900 pC1/1) with a large measurement error. The activity measured at Burlington was two times the detection capability with a relatively small error. It is believed the tritium detected at both locations are from the same source but not attributable to Wolf Creek since the activity detected upstream of WCCL discharge was greater than the activity detected downstream. i 1990 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PAGE 14 0F 14 WOLF CREEK GENERATING STATION APPENDIX C _ _ _ __ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ __ _}}