Text

1998 Annual Radiological Environ Operating Rept. with
	ML20206A914
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1998
From:	Warren C; WOLF CREEK NUCLEAR OPERATING CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	WO-99-0030, WO-99-30, NUDOCS 9904290081
	Download: ML20206A914 (180)
	v • d • e

6 W8LF CREEK ' NUCLEAR OPERATING CORPORATION Clay C. Warren Vim President & Chief Operating Omcer APR 2 31999 WO 99-0030 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Utation P1-137 Washington, D. C. 20555

Subject:

Docket No. 50-482: Annual Radiological Environmental Operating Report Gentlemen:

Enclosed is the Annual Radiological Environmental Operating Report which is being submitted pursuant to Wolf Creek Generating Station (WCGS) Facility Technical Specification 6.9.1.6. This report covers operation of WCGS for the period of January 1, 1998 to December 31, 1998.

If you should have any questions regarding this submittal, please contact me at (316) 364-4048, or Michael J. Angus at (316) 364-4077.

Very truly your ,

C C. Warren CCW/rlr Enclosure !

cc: E. W. Merschoff (NRC), w/e W. D. Johnson (NRC), w/e K. M. Thomas (NRC), w/s Senior Resident Inspector (NRC), w/e hdf o

A-9904290081 981231 '.

PDR ADOCK 05000482 h R PDR P.O. Box 411/ Burhngton, KS 66839 / Phone: (316) 364 8831 An Equal opportunity Employer M'F NC YET -

WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION 1998 ANNUAL RADIOLOGICAL l

ENVIRONMENTAL OPERATING REPORT

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TABLE OF CONTENTS List of Tables 11 List of Figures 111 Introduction 1 I. Program Description 2 II. Discussion of Results 5 III. Annual Land Use Census Results and Program Revisions 9 IV. Program Deviations 10 V. Interlaboratory Comparison Program Results 12 VI. Comparison to the Radioactive Effluents Release Program 13 Tables 14 Figures 34 Appendix A A-1 Appendix B B-1 i

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LIST OF TABLES 1 1998 Radiological Environmental Monitoring Program Description 14 2 Sample Location Numbers, Distances and Directions 19 3 Airborne Particulate Gross Beta Analyses 20 4 Airborne Particulate Quarterly Composite Gamma Isotopic Analyses 21 5 First and Second Quarter TLD Results 22 6 Third and Fourth Quarter TLD Results 23 7 Drinking Water Radiological Analyses 24 8 Surface Water Radiological Analyses 25 9 Shoreline Sediment Radiological Analyses 26 10 Milk Radiological Analyses 26 11 Broadleaf Vegetation Radiological Analyses 26 12 Crop Radiological Analyses 27 13 Fish Radiological Analyses 27 14 Bottom Sediment Radiological Analyses 27 15 Aquatic Vegetation Radiological Analyses 28 16 Terrestrial Vegetation Radiological Analyses 28 17 Soil Radiological Analyses 28 18 1998 Land Use Census Data 29 19 Comparison of 1998 and 1997 Land Use Census Milk and Garden Data 30 l

20 EPA Interlaboratory Comparison Program 1998 31 21 An lytics Cross Check Comparison Program 1998 32 22 Dosimetry Performance Testing Results 33 l

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LIST OF FIGURES 1 Airborne Pathway Sampling Locations 34 2 Direct Radiation Pathway Samp1.4ng Locations 35 3 Waterborne Pathway Sampling Locations 36 4 Ingestion Pathway Sampling Locations 37 5 Distant Sampling Locations 38 6 1998 Airborne Gross Beta Weekly Results 39 7 Historical Airborne Smoothed Indicator and Control Gross Beta 40 8 TLD Nearsite Locations and Control Locations 41 9 Variation of Nearsite TLD Averages Expressed as a Ratio to Control 42 Values 10 Drinking Water Gross Beta, Historical 43 11 Wolf Creek Lake Surface Water Smoothed Tritium Data 44 l 12 Cumulative Liquid Effluent Tritium Data 45 13 Cs-137 in Shoreline Sediment (Location Discharge Cove) 46 14 Tritium in Wolf Creek Lake Fish 47 i

i 15 Tritium Dose in WCL Surface Water and Released Liquid Tritium 48 l Maximum Organ Dose lii a

INTRODUCTION Tho 1998 Annual Radiological Environmental Operating Report for Wolf Creek Generating Station (WCGS) covers the period from January 1 through December 31, 1998. WCGS is located in Cof fey County, Kansas, approximately five miles northeast of Burlington, Kansas.

Fuel loading commenced at h:GS on March 12, 1985. The operational phase of the Radiological Environmental Monitoring Program (REMP) began with initial criticality on May 22, 1985 and the first detectable quantities of radioactivity were reported in plant effluents in June 1985.

This report contains a description of the REMP conducted by Wolf Creek Nuclear Operating Corporation (WCNOC), results of sample analyses, a discussion of monitoring program results, a description of revisions to and deviations from the program, and the results of Interlaboratory Comparison Programs.

Indivinal sample results and c summary of results in the Nuclear Regulatory Commission (NRC) Branch Technical Position specified format are included as appendices.

Activation products were not detected during 1998 in airborne particulate and radiolodine filters, broadleaf vegetation, crops, ground water, soil, terrestrial vegetation, drinking water or shoreline sediment.

Activation products attributable to plant operation were detected during 1998 in aquatic vegetation, bottom sediment, surface water and fish samples.

Nuclides detected in REMP samples were below applicable NRC reporting levels.

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I l I. PROGRAM DESCRIPTION ,

Radiological environmental samples were collected according to the schedule in

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I Attachment A, Table 5-1 of the WCGS Of fsite Dose Calculation Manual (ODCM).

Samples were collected - by the WCGS Environmental Management group and were analyzed by Teledyne Brown Engineering Environmental Services of Westwood, New Jersey. Environmental TLDs were processed by Detroit Edison at the Enrico Fermi 2 plant. Table 1 lists sampling pathways and frequencies of sampling and analysis. Table 2 lists each sample location's distance and direction from the plant. Samples in addition to those required by the WCGS ODCM were also obtained.

l The following is a description of the sampling and analysis program by individual pathways.

{ A. Airborne Pathway Low volume air sampling pumps continually collected particulate and radiciodine samples on 47 mm glass fiber filters and charcoal canisters, respectively. Weekly, the filters and charcoal canisters were changed out, j

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labeled, and shipped to Teledyne Brown Engineering Environmental Services for analysis. The volume of air sampled was calculated from the average of initial and final flow rates and the total time of collection. Each pump was equipped with a time totalizer that was checked weekly against the elapsed time.

I Gross beta analysis of the air particulate samples was performed after 72 l hours post collection to allow the radon and thoron daughter products to decay.

Weekly air particulate filters were combined into quarterly . composites for i cach location and analyzed for gamma emitting isotopes.

Charcoal canisters were routinely counted in groups of five to determine the presence or absence of I-131. Positive indication of I-131 would have resulted in analysis of each incfividual charcoal canister.

l Air - samples were collected from the three sectors with the highest ground level deposition constants (D/Q) (locations 2, 3 and 37), the community of New Strawn (location 32), and a control location (location 40). Distances and directions to sampling locations from the plant are listed in Table 2, nearby locations are shown in Figure 1 and distant locations are shown in Figure 5. ;

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B. Direct Radiation Pathway l Panasonic UD-814-AQ TLDs were used during the 1998 sample year. The TLDs consist of one lithium-borate element and three calcium sulfate elements in a plastic case.

TLDs were typically positioned roughly 3 to 4 feet above the ground in plastic thermostat boxes. The thermostat boxes protect the TLDs from the elements and tampering. Two TLDs were placed at each designated location. Nearby TLD sample locations are illustrated in Figure 2 and distant locations are shown in Figure 5. Table 2 provides the distance and direction of each location from the plant.

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Fage 2 of 48

i C. Waterborne Pathway All water samples were analyzed to determine if gamma emitters were present.

In addition to gamma analysis, radiochemical analysis for I-131 was performed on drinking water and ground water samples. Gross beta analysis was also i performed on drinking water samples. Tritium analysis was performed raonthly by liquid scintillation for surface water and quarterly for drinking water.

Tritium analysis for ground water was performed quarterly by gas counting.

Water sampling locations are listed in Table 2 and are shown in Figures 3 and 5.

l Drinking water was sampled at the water treatment facilities for the towns of Burlington-(control location) and LeRoy (indicator location) . The Burlington facility is located upstream and the LeRoy facility is located downstream of the confluence of the discharge from Wolf Creek Lake (WCL) and the Neosho River. _ Composite samples were obtained monthly from automatic samplers at l each location that collected about 10 ml of drinking water each hour.

l Grab samples'were obtained from surface water locations each month. Surface water was sampled from the outfall- of John Redmond Reservoir (JRR) as a l control location and from the discharge cove and spillway of WCL as indicator locations.

I Ground water samples were collected quarterly from four locations. Location B-12 is hydrologically upgradient from the site and is used as a control location. Three additional samples, C-10, C-49 and D-65, were obtained from wells hydrologically downgradient from the site as indicator samples.

l Duplicate samples were obtained from location C-49 and were labeled L-49.

These duplicate samples served as a laboratory quality check.

Shoreline sediments were sampled semiannually for gamma analysis at the discharge cove and Make-up Water Discharge Structure (MUDS) indicator locations and at JRR as a control location.

Bottom sediment samples were collected semiannually for gamma analysis at the discharge cove indicator location and the JRR centrol location.

Aquatic vegetation was collected semiannually for gamma analysis from indicator locations at the discharge cove and discharge cove alternate location.

D. Ingestion Pathway Because no sampling locations that produce milk for human consumption were identified within five miles of the plant during 1998, milk was not collected during 1998.

Broadleaf vegetation samples were collected monthly during the growing season from three gardens. Three indicator gardens (Figure 4) and a control garden (Figure 5) were sampled. Gamma isotupic analyses were performed on all samples.

Three crop samples were . obtained from two indicator locations downstream of the confluence of Wolf Creek and the Neosho River and two control samples were obtained upstream. Due to the wet weather, only one control sample was irrigated with water from the Neosho River. Indicator samples were not j irrigated with water from the Neosho River. Gamma isotopic analysis was I performed on each sample. ,

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f-Fish were sampled semiannually from the tail waters of JRR (control, Figure 4) and from WCL (indicator, Figure 4) for gamma isotopic analysis. Several species of gamefish and roughfish were sampled. Gamma isotopic analysis was performed on boneless meat portions of the fish. Fish were also analyzed for l tritium.

' Soil was sampled semiannually from two locations, the MUDS and Environmental Education Area (EEA), for gamma isotopic analyses. These samples were collected as part of a cooperative sampling effort with the Kansas Department of Health and Environment (KDHE).

Terrestrial vegetation was also sampled semiannually from locations MUDS and EEA for gamma isotopic analyses. These samples were collected as part of a cooperative sampling effort with the KDHE.

j Sampling locations listed in this section are outlined in Table 2.

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! II. DISCUSSION OF RESULTS l

Analysis results for all pathways are summarized in Appendix A using the format described in Radiological Assessment Branch Technical. Position, Revision 1, November 1979 (NRC Generic Letter 79-065). Results for individual samples are listed in Appendix B.

In this section, results are discussed by pathway and analysis type.

l Monitoring results are compared with control data, preoperational values,

! sources of radioactivity, and effluent releases when applicable. Trends or l seasonal effects are discussed. Associated counting uncertainties for i detected activity. values contained in Tables 3 through 17 are shown in l Appendix B.

A. Airborne Pathway Results of the weekly gross beta analysis are summarized in Table 3. In addition, Figure 6 graphically illustrates weekly gross beta results for 1998.

l Figure 7 represents the historical smoothed averages of indicator and control gross beta data. -

Figures 6 and 7. demonstrate how closely the indicator and control locations tracked together. The elevated gross beta level at location 37 during the l sample period of 11-04-98 through 11-11-98 on Figure 6, was due to low sample l volume caused oy a sampling equipment malfunction (see Program Deviations l section, Performance Improvement Request 98-3337). Figure 7 reveals a l

seasonal cyclic trend in which gross beta values peak in the winter months (December or January) and decrease to a low point in the spring months (May or June).

~I-131 activity was not detected in the weekly analysis of charcoal filters.

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Results'of the quarterly gamma analysis of air particulate filter composite analyses are summarized in Table 4. Naturally occurring Be-7 and K-40 were the only nuclides detected.

1 Effects of plant operation were not seen via the airborne pathway for the year j and no unusual trends were noted. l l

B. Direct Radiation Pathway Quarterly gamma exposures measured at each location for 1998 are shown in Tables 5 and 6. Measured values have been converted to a standard 90-day quarter.

l The highest direct radiation levels of the year were detected at location 47.

l Location 47 also had the highest TLD measured activity in 1997 The close ;

i proximity of location 47 to the Radwaste Building was the reason direct l radiation levels were higher at this location.

Results from TLDs located near the plant (less than approximately three miles), which would be most affected by changes in plant operation, were combined into quarterly averages. These nearsite averages, using locations 1, 2, 7-14, 18, 26-30, 37 and 38, are compared to control location results (locations 39 and 40) in Figure 8. In addition, variation of the nearsite averages from the control location results is displayed graphically in Figure 9. These figures also include preoperational data for comparison. The i nearsite TLD locations have historically trended higher than the control locations both prior to and after WCGS became operational.

No unusual trends were noted in 1998.

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 5 of 48

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C. Waterborne Pathway (1) Drinking Water

-Results of drinking water radiological analyses are summarized in Table 7.

Figure 10 illustrates the hirtorical drinking water gross beta data through 1998.

Only gross beta activity was detected in drinking water and it was detected in all of the drinking water samples. The annual mean of the control location gross beta activity (6.0 pCi/ liter) was the same as the annual mean of the indicator location (6.0 pCi/ liter). Figure 10 illustrates how closely the gross beta results compared for the indicator and ccatrol locations.

Activity due to plant operation was not evident in drinking water samples and no unusual trends were noted during 1998.

(2) Surface Water Tritium, attributable to WCGS operation, was detected in all surface water samples collected from WCL in 1998. According to the Radioactive Effluents Release Program, a total of 839 curies of liquid tritium was released during the year. Measured concentrations are shown in Table 8. An adult drinking 1.5 liters per day of surface water cellected from the discharge cove, using the highest detected tritium activity (13,000 pCi/ liter), would receive a I calculated committed dose of 0.45 mrem per year. (According to the National Council on Radiation Protection and Measurements [NCRP Report No. 94], the l estimated total effective dose equivalent rate for a member of the population in the United States from various sources of natural background radiation is j 300 mrem per year.) Figure 11 illustrates smoothed tritium data for locations

DC and SP from startup~in May 1985 through 1998. The cumulative curies of l liquid tritium released to WCL is illustrated in Figure 12.

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! During 1998, the annual mean for detected tritium activity at the discharge I

cove was 9,150 pCi/ liter. This was lower than the annual mean for tritium activity detected in 1997, and was likely due to the heavy rainfall during i 1998. It can be seen in Figure 11 that monthly surface water tritium concentrations have increased since plant startup. This is expected until the tritium concentration of the lake reaches equilibrium, which has been estimated at 13,000 pCi/ liter.

Tritium was the only activity detected in surface water samples and no unusual trends were noted.

(3) Ground Water l .During 1998, radioactivity was not detected in ground water samples.

. 1 (4) Shoreline Sediment Naturally occurring nuclides (K-40, Ra-226 and Th-228) were detected in all shoreline sediment samples.

Cs-137 activity was detected (54.2 and 53.4 pCi/kg) in both samples obtained from the discharge cove indicator location. Since Cs-134 activity was not detected in these samples, this activity may indicate fallout as opposed to newly produced fission products. The presence of Cs-134 is expected if the occurrence of Cs-137 is related to plant operation. Since Cs-134 has a shorter half-life than Cs-137 (2 years versus 30 years), it is not expected to be found when the presence of Cs-137 is due to fallout. Cs-137 activity was also detected (183 pCi/kg) in a sample obtained from the JRR control location.

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 6 of 48

Figure 13 illustrates that Cs-137 activity was detected preoperationally and is. routinely detected at the discharge cove. However, Cs-137 activity was not dettcted in discharge cove samples in 1997. A linear trendline indicates that the level of Cs-137 activity detected in the discharge cove is trending down.

Analysis results are summarized in Table 9.

D. Ingestion Pathway (1) Milk Milk was not collected during 1998 since no indicator locations within five miles of the plant were identified during the Land Use Census.

(2) Food and Garden Crops Gamma analyses of broadleaf vegetation samples during 1998 detected naturally occurring gamma emitters Be-7 and K-40.

Cs-137 activity was detected (9.73 pCi/kg) in a sample from location G-1.

Since Cs-134 activity was not detected, this activity may indicate fallout as opposed to newly produced fission products. The presence of Cs-134 is expected if the occurrenca of Cs-137 is related to olant operation. Since Cs-134 has a shorter half-life than Cs-137 (2 years versus 30 years), it is not expected to be found when the presence of Cs-137 is due to fallout. 4 Activity attributable to plant operation was not detected. Table 11 shows the results of 1998 analyses, j

In addition to broadleaf vegetation, crop samples were collected. Two control i samples were obtained from cropland upstream of the confluence of Wolf Creek I and the ' Neosho River, and three indicator samples were obtained downstream.

One control sample location was irrigated with Neosho River water. Due to the wet summer, the other sample locations were not irrigated with Neosho River water. Gamma analysis detected naturally occurring K-40 to be present in all of the samples, with no nuclides detected due to plant operation. Results of crop analyses are summarized in Table 12.

(3) Fish Analysis results are illustrated in Table 13. Naturally occurring K-40 activity was detected in all fish samples.

During 1998, fish were also analyzed for tritium. All fish samples taken from WCL had tritium activity detected (6,600 pCi/kg annual mean) . The detected tritium activity was attributable to plant operation. An adult consuming 21 kilograms of. fish, at the maximum measured tritium concentration for 1998 (11,000 pCi/kg) would receive a calculated committeo dose of 0.015 mrem.

(According to the National Council on Radiation Protection and Measurements

[NCRP Report No. 94), the estimated total effective dose equivalent rate for a j member of the' population in the United States from various sources of natural background radiation is 300 mrem per year.) Figure 14 illustrates the tritium concentrations detected in fish from WCL. ,

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E. Special Samples (not required by the WCGS ODCM)

(1) Bottoa Sediment Table 14 shows gamma emitters detected during 1998 in bottom sediment samples.

Naturally occurring nuclides detected include Be ' K-40, Ra-226, and Th-228. i 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 7 of 48 c.

Co-60 activity (May 11, 1998, 1290 pC1/kg and September 29, 1$r98, 865 pCi/kg) was detected in both samples obtained from the WCL discharge cove. Co-60 l

activity is attributable to plant operation and is commonly identified in plant effluents.

Zn-65 activity (September 29, 1998, 96.4 pCi/kg) was detected in a sample obtained from the WCL discharge cove. This was the first detected activity of Zn-65 and it is not commonly identified in plant effluents. Zn-65 is an l

activation product, however, due to the relatively low activity detected and the high counting uncertainty, this result was considered to be an anomaly. A second analysis of this sample produced a Zn-65 result of L.T. 100 pCi/kg'.

Cs-137 (May 11, 1998, 477 pCi/kg and September 29, 1998, 394 pCi/kg) activity was detected in samples taken from indicator locations and in samples taken from the control location. Since Cs-134 was not present and Cs-137 activity was also detected from the control location samples, this activity was primarily due to fallout, and not to a newly produced fission product of plant origin.

No other radionuclides were detected.

(2) Aquatic Vegetation Table 15 lists gamma emitters detected in aquatic vegetation samples.

Naturally occurring Be-7, K-40, Ra-226 and Th-228 were detected. Other t- activity detected included Mn-54, Co-58, Co-60, Cs-134 and Cs-137. This activity was attributed to plant operation and is regularly identified in plant effluents.

(3) Terrestrial vegetation Pasturage samples were obtained from the EEA and MUDS. All samples had j naturally occurring Be-7 and K-40 activity detected. No other nuclides were '

detected. Table 16 reflects gamma emitters detected in terrestrial vegetation samples.

(4) soil 1

Soil samples were elso obtained from the EEA and MUDS. Naturally occurring Be-7, K-40, Ra-226 and Th-228 activity was detected. Cs-137 activity was detected in three of the four soil samples. The Cs-137 activity was l attributable to fallout since Cs-134 activity was not detected and the J activity levels for Cs-137 are well within the preoperational range (255 to 2,160 pCi/kg). Table 17 lists the activity detected in soil samples.

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III. ANNUAL IAND USE CENSUS RESULTS AND PROGRAM REVISIONS Summary The annual Land Use Census of rural residents within five miles of WCGS was completed for 1998. No changes were required in the REMP regarding broadleaf vegetation - sample locations. Location P2.0-16RD1150 had previously been identified as a potential sample location for broadleaf vegetation, however, efforts to contact the individuals at this address were unsuccessful. The land .use census results were re-evaluated ' and the D/O rankings were re-calculated with the omission of location P2.0-16RD1150 as a potential broadleaf vegetation sample location. The two locations with the highest calculated annual average D/Q rankings were G1.6-QURD1384 and F1.8-14RD7 730.

The ODCM ' specifies that an " alternate location may be used to provide l continued monitoring". Because the calculated D/O for the third-ranked garden 4 was not 20 percent greater.than the fourth-ranked garden, the garden at El.8-QULA1485 has been chosen as an alternate sampling location. The residents at G1.6-QURD1384, F1.8-14RD1730, and El.8-QULA1485 have agreed to allow sampling from their respective gardens during the 1999 growing season. The results and notable changes are summarized and illustrated in Tables 18 and 19.

Background

Section 5.2, Attachment A, of the ODCM procedure (AP 07B-004), directs that "a Land Use Census shall be condteted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater that 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site" and "the - results of the Land Use Census 'shall be included in the Annual Radiological Environmental Operating Report."

Table 5-1,- Attachment A, of the ODCM requires that broadleaf vegetation samples.be collected from "two indicator locations with the highest calculated annual average D/Q."

Table 5-1, Attachment A, of the ODCM also requires that milk samples be collected from "three indicator locations within 5 miles of the site having the highest dose potential."

Methodology Surveys were sent to the rural residents within five miles of WCGS during the third week of July 1998. A follow-up mailing was sent to residents who did not respond. The survey excluded the residents of New Strawn, Burlington and a trailer park just north of Burlington. These locations are excluded due to the large number of households and the low likelihood that information gained from these residences would affect the locations chosen for REMP sampling. Of the 173 surveys mailed to the rural residents, 153 were returned by mail or completed by conversing with the residents. Twenty surveys were partially completed with information collected from a visual observation of the location.

'Results Table 18 reflects the nearest residences, milk animals and broadleaf gardens.

Table 19 lists the changes as compared to the 1997 Land Use Census results for milk animals and gardens producing broadleaf vegetation.

Changes in the nearest ' residence occurred in one sector (N) and no milk locations were identified. Numerous location changes were noted for the nearest garden producing broadleaf vegetation, i

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IV. PROGRAM DEVIATIONS Airborne Pathway Location 32: On June 16, 1998, air sample pump 5967 was found inoperable.

Air particulates and radiciodine samples were not collected between 1035 and 1050 on the referenced date. Pump 5967 was removed from service, the blown fuse was replaced and a pump 5991 was installed and verified operable at the location. Electricians verified that wiring was not damaged on pump 5967.

The inoperability problem of pump 5967 could not be repeated. (Performance Improvement Request 98-1777)

Location 32: On June 30, 1998, both sample pumps (WCGS and KDHE) were found without power. Air particulates and radioiodine samples were not collected between the evening (p . m. ) of June 29, 1998, and the morning (a.m.) of July, 2, 1998. Electricians repaired damaged wiring, power was restored, and both sample pumps were verified operable. (Performance Improvement Request 98-1970)

Location 37: On July 21, 1998, a 3.56 percent discrepancy was identified between the actual time and the meter time. According to the elapsed time meter, air particulates and radioiodine samples were not collected for approximately five hours during the sample period starting July 15, 1998,'and ending July 21, 1998. The electric cooperative verified that a power outage was not experienced during the sample period. The pump was checked and ,

verified operable. (Performance Improvement Request 98-2116) '

Location 37: On July 28, 1998, a 29.95 percent discrepancy was identified between the actual time and the meter time. According to the elapsed time meter, air particulates and radioiodine samples were not collected for approximately 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months during the sample period starting July 21, 1998, and ending July 28, 1998. The electric cooperative verified that a power outage did not occur during the sample period. Electricians verified that wiring was not damaged. To trouble-shoot this problem, an additional pump was installed and the pumps ran side-by-side through August 25, 1998. Since no discrepancies were identified, the missed sample was likely due to an electrical power outage. (Performance Improvement Request 98-2165)

Location 37: On September 16, 1998, air sample pump 5974 was found )

inoperable. Air particulates and radiciodine samples were noc collected for approximately 122 hours0.00141 days 0.0339 hours 2.017196e-4 weeks 4.6421e-5 months between the sampling period starting September 10.

1998, and ending September 16, 1998. Pump 5974 was removed from service and pump 5972 was installed and verified operable. Pump 5974 was returned to the vendor where the defective motor was replaced. (Performance Improvement

Request 93-2826) The vendor lab was unable to meet the Lower Limit of Detection for I-131 on the charcoal filter due to the low sample volume.

(Performance Improvement Request 98-3410)

Location 40: On September 24, 1998, puinp 5965 was found inoperable and the l fuse was also blown. Air particulates and radioiodine samples were not l collected for approximately five hours on 09-24-98. Pump 5965 was removed

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from service and pump 5967 was installed and verified operable. Pump 5965 was returned to the vendor where the defective motor was replaced. (Performance Improvement Request 98-2921) 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 10 of 48

Location 37: On November 4, 1998, an 8.48 percent discrepancy was identified between the actual time and the meter time. According to the elapsed time meter, air particulates and radioiodine samples were not collected for approximately 13.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during the sample period starting October 28, 1998, and ending November 4, 1998. On November 11, 1998, a 67.54 percent discrepancy was identified between the actual time and the meter time.

According to the elapsed time meter, air particulates and radioiodine samples were not collected for approximately 113 hours0.00131 days 0.0314 hours 1.868386e-4 weeks 4.29965e-5 months during the sample period starting November 4, 1998 and ending November 11, 1998. pump 5972 was removed from service due to the defective elapsed time meter and a pump installed which was verified to be operable. (Performance Improvement Request 98-3337)

Location 32: On December 23, 1998, a 4.4 percent discrepancy was identified between the actual time and the meter time. According to the elapsed time meter, air particulates and radioiodine samples were not collected for approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months during the sample period starting December 16, 1998, and ending December 23, 1998. On December 29, 1998, a 6.87 percent discrepancy was identified between the actual time and the meter time. According to the elapsed time meter, air particulates and radioiodine samples were not collected for approximately 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months during the sample period starting December 23, 1998, and ending December 29, 1998. The pump was rechecked on January 6, 1999, and the elapsed time meter was found inoperable. At that time, Pump 5971 was removed from locatian 32 and pump 5969 was installed and verified to be operable. (Performance Improvement Request 98-3337)

The reason for the inconsistent performance of the pumps at locations 32 and 37 is not known at this time. Although brief periods of inoperability are permitted by the Offsite Dose Calculation Manual, the sporadic performance at locations 32 and 37 is being. tracked as part of WCNOC's corrective action program to determined if a trend is developing. In each case the specific problem was corrected and the pump at the location left in an operable condition.

Drinking Water Location BW-15 (Burlington): On January 28, 1998, the sampler was found operational, however, a review of sampler performance indicated that 70 samples were missed. During the week of January 20-23, 1998 the water department had drained the bay from which the samples are obtained for maintenance purposes. (Performance Improvement Request 98-0235)

Milk Indicator sample locations are still unavailable within five miles of the plant. Refer to Section III, Annual Land Use Census Results and Program Revisions.

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f V. INTEPtman*% TORY COMPARISON PROGRAM RESULTS l

l Teledyne Brown Engineering Environmental Services is under contract to perform l

radiological analysis of environmental samples for WCNOC. Teledyne

i. participated in the Environmental Protection Agency (EPA) Interlaboratory Comparison Program during 1998.

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( Table - 20 shows interlaboratory comparison test results received during the l year. The table lists the collection date, the sample medium, the nuclide or l analysis type, the known value reported by the EPA, the measured value reported by Teledyne Brown Engineering Environmental Services (based upon j triplicate analysis), and the normalized deviation from the known value.

Beginning with 1996, the EPA discontinued providing milk and air particulate filter samples. For replacements, Teledyne Brown Engineering Environmental Services purchased comparable spiked samples from Analytics, Incorporated (see Table 21).

Table 22 is a summary of statistical results of performance testing of TLDs processed at Enrico Fermi 2 by Detroit Edison which participated in the l

National Voluntary Laboratory Accre'ditation Program.

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! VI. COMPARISON TO THE RADIOACTIVE EFFLUENTS RELEASE PROGRAM l

.As described in the sections discussing radioisotopes found in the surface water from WCL, dose that may be received as a result of tritium released from WCGS is consistent with the theoretical doses as calculated by the Radioactive Effluent Release Program.

Figure 15 indicates that the dose to a man resulting from drinking surface water from WCL lake was within a reasonable expected value. Dose for the surface water was determined using the December tritium activity detected for each calendar year at the discharge cove. Released tritium maximum organ dose (mrem) values were obtained from Annual Radioactive Effluent Release Reports and are not cumulative (the values reflected are the totals for the respective years).

The tritium dose values are being compared on a qualitative basis. It is not expected that the annual doses, as calculated in the Radioactive Effluent Release Report, would compare directly to those calculated from the REMP. The Radioactive Effluent Release Report provides a ' snap shot' of potential dose resulting from the yea r's release. The REMP data indicate the accumulated result of releasing tritium into the cooling lake since the start of plant operation.

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l 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 13 of 48 1

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TABLE 1 .

1998 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM DESCRIPTION (SAMPLE COLLECTION REQUIRED BY ODQ4)

EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND PATHWAY / AND SAMPLE COLLECTION FREQUENCY FREQUENCY OF SAMPLE LOCATIONS ANALYSIS AIRBORNE Figures 1 & 5 Didioiodine Samples from five Continuous sampler Analyze

a. d locations operation with sample radiciodine Particulates collection weekly, or canister weekly more frequently if for I-131 required, by dust loading.

Samples from Analyze locations near the particulate site boundary in filter weekly three sectors for gross beta having the highest activity; calculated annual perform average D/O quarterly gamma (Locations 2, 3, isotopic and 37 on Figure 1) analysis composite (by location)

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 Figure 5) l l

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l 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 14 of 48 l

[ >

TABLE 1 (Cont)

EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND FREQUENCY PATHNAY/ AND SAMPLE LOCATIONS COLLECTION FREQUENCY OF ANALYSIS SAMPLE DIRECT RADIATION Figures 2 & 5 40 routine Quarterly Gamma dose monitoring stations quarterly with two or more dosimeters measuring dose continuously, placed as follows:

An inner ring of stations, one in each meteorological sector 0-3 mile range from the site (Locations 1, 7-9, 11-13, 18, 26, 27, 29-31, 37, 38 and 47 on Figure 2)

An outer ring of stations, one in each meteorological sector in the 3-5 mile range from the site (Locations 4-6, 15-17, 19-25, and 33-36 on Figure 2). Five sectors

[A, B, D, G, and L]

contain an additional station (Locations 2, 3, 10, 14 and 28)

The balance of the stations to be ;

placed in special i interest areas such !

as population l centers (Locations 23 and 32), nearby J residences l

l 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 15 of 48

TABLE 1 (Cont)

EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND PATHWAY / AND SAMPLE COLLECTION FREQUENCY FREQUENCY OF SAMPLE LOCATIONS ANALYSIS DIRECT RADIATION (cont)

(many locations are near a residence),

. schools (Location 23), and in one or two areas to serve as control stati'ons 10-20 miles distant from the site (Locations 39 and 40 on Figure 5)

WATERBORNE Figure 3 Surface One sample upstream Monthly grab sample Monthly gamma (Location MUSH on isotopic Figure 3) and one analysis and sample downstream composite for (Location DC on tritium analysis Figure 3), quarterly Ground Samples from one or Quarterly grab sample Quarterly gamma two sources only if isotopic and likely to be tritium analysis affected.

Indicator samples at locations hydrologically downgradient of the I site (Locations j i

C-10, C-49, and D-65 on Figure 3); i Control sample at a location hydrologically upgradient of the site (Location B-12 on Figure 3) 1 1998 Annual Radiological Environmental Operating Report Wolf-Creek Generating Station Page 16 of 48 t

TABLE 1 (Cont)

EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND PATHNAY/ AND SAMPLE COLLECTION FREQUENCY FREQUENCY OF SAMPLE LOCATIONS ANALYSIS WATERBORNE (cont)

Drinking Sample of municipal Monthly Composite Monthly gamma water supply at an isotopic indicator location analysis and i downstream of the gross beta i site (Location analysis of LW-40 on Figure 5); composite control sample from sample.

location upstream Quarterly of the site tritium analysis (Location BW-15 on of composites.

Figure 3)

Shoreline One sample from the Semiannually Semiannual gamma sediment vicinity of Wolf isotopic Creek Lake analysis discharge cove; control sample from John Redmond Reservoir (Locations DC and JRR respectively on Figure 3)

INGESTION Figures 4 & 5 Milk Samples from Semimonthly April to Gamma isotopic milking animals at November; monthly analysis and three indicator December-March I-131 analysis locations within of each sample five miles of the site having the highest dose potential (currently there are no locations producing milk for human consumption within five miles of the site); one sample from a control location greater than 10 miles from the site ,

if indicator locations are sampled.

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 17 of 48

TABLE 1 (Cont)

EXPOSURE NUMBER OF SAMPLES SAMPLING AND TYPE AND PATHWAY / AND SAMPLE COLLECTION FREQUENCY FREQUENCY OF SAMPLE LOCATIONS ANALYSIS INGESTION (cont)

Fish Indicator samples Semiannually Gamma isotopic of 1-3 analysis on recreationally edible portions important species from Wolf Creek Lake; control samples of similar species from John Redmond Reservoir spillway (Figure 4)

Broadleaf Samples of Monthly when Gamma isotopic Vegetation available broadleaf available analysis on vegetation from two edible portions indicator locations with highest calculated annual average D/0 (Locations G-1 and F-1 and alternate location E-1);

sample of similar broadleaf vegetation from a control location greater than 10 miles from the site in a low D/0 sector (Location S-4 on Figure 5)

Irrigated Sample of crops At time of harvest Gamma isotopic Crops irrigated with analysis on water from the edible portions Neosho River downstream of the Neosho River - Wolf Creek confluence (Location NR-D1 and NR-D2 on Figure 5) 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 18 of 48

TABLE 2 SAMPLE LOCATION NtS4BERS, DISTANCES (Miles) AND DIRECTIONS ,

Location Distance / Location Distance / Location Number Distance 7 Number Direction Number Direction Direction Air Particulates and Radiciodines 2 2.7/N 3 3.0/NNE 32 3.2/WNW 37 2.1/NNW 40 >15.0/WNW TLDs 1 1.4/N 17 3.6/SE 33 3.7/WNW 2 2.7/N 18 3.0/SSE 34 4.0/NW 3 3.0/NNE 19 4.0/SSE 35 4.6/NNW 4 4.0/NNE 20 3.3/S 36 4.2/N 5 4.0/NE 21 3.8/S 37 2.1/NNW 6 4.4/ENE 22 4.1/SSW 38 1.2/NW 7 1.9/NE 23 4.5/SW 39 13.0/N 8 1.6/NNE 24 4.1/WSW 40 >15.0/WNW 9 2.0/ENE 25 3.6/W 41 0.8/NNW 10 2.4/ENE 26 2.6/WSW 42 0.8/SSE 11 1.6/E 27 2.1/SW 43 0.8/WNW 12 1.8/ESE 28 2.8/SW 44 3.0/NNW 13 1.5/SE 29 2.6/SSW 45 1.6/WNW 14 2.6/SE 30 2.2/W 46 1.5/WNW 15 4.5/ESE 31- 3.0/WNW 47 .16/S

~

16 4.2/E 32 3.2/WNW Ground water Drinking water Surface water B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 >10.0/SSE DC 0.6/WNW C-49/L-49 2.9/SW SP 2.9/S D-65 3.9/S Milk Broadleaf vegetation Irrigated Crops F-1 1.8/ESE NR-U1 4.2/SW G-1 1.6/SE NR-D1 9.2/S E-1 1.8/E NR-D2 >10.0/S S-4 >15.0/WNW Fish Shoreline Soil Aquatic Vegetation / Algae WCL 0.6/WNW DC 0.6/WNW DC 0.6/WNW JRR 4.0/W JRR 4.0/W DC ALT 1.5/NW MUDS 1.5/WNW Terrestrial Vegetation & Soil Botton Sediment EEA 3.0/NNW DC 0.6/WNW MUDS 1.5/WNW JRR 4.0/W l

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1998 Annual Radiological Environmental Operating Report l Page 19 of 48 Wolf Creek Generating Station

TABI2 3 Airborne Particulate Gross Beta Analyses (pC1/ cubic ascer, analysis counting uncertainties reported in Appendix B)

Date Location Beginning Ending 2 3 32 37 40 (Control) 12/31/97 01/06/98 0.019 0.016 0.017 0.018 0.023 01/06/98 01/14/98 0.041 0.034 0.037 0.037 0.036 01/14/98 01/20/98 0.038 0.030 0.033 0.035 0.033 01/20/98 01/27/98 0.029 0.033 0.029 0.030 0.031 01/27/98 02/03/98 0.026 0.028 0.029 0.029 0.029 02/03/98 02/10/98 0.022 0.025 0.023 0.0/3 0.021 02/10/98 02/17/98 0.028 0.026 0.027 0.030- 0.029 02/17/98 02/24/98 0.025 0.026 0.025 0.025 0.023 02/24/98 03/03/98 0.019 0.020 0.017 0.018 0.016 03/03/98 03/10/98 0.015 0.015 0.018 0.018 0.016 03/10/98 03/17/98 0.022 0.024 0.026 0.026 0.025 l 03/17/98 03/24/98 0.022 0.021 0.020 0.020 0.020 J 03/24/98 03/31/98 0.023 0.020 0.024 0.022 0.021 03/31/98 04/07/98 0.015 0.016 0.016 0.015 0.015 04/07/98 04/15/98 0.021 0.020 0.026 0.022 0.024 04/15/98 04/21/98 0.019 0.015 0.021 0.019 0.022 04/21/98 04/29/98 0.023 0.027 0.025 0.021 0.026 04/29/98 05/06/98 0.017 0.020 0.019 0.018 0.017 05/06/98 05/12/98 0.018 0.020 0.019 0.020 0.017 05/12/98 05/19/98 0.025 0.023 0.024 0.022 0.023 05/19/98 05/26/98 0.029 0.031 0.032 0.031 0.031 05/26/98 06/02/98 0.021 0.024 0.025 0.022 0.023 06/02/98 06/10/98 0.018 0.014 0.018 0.016 0.016 06/10/98 06/16/98 0.018 0.018 0.013 0.021 0.019 06/16/98 06/23/98 0.016 0.016 0.019 0.016 0.015 06/23/98 06/30/98 0.013 0.013 0.014 0.013 0.014 06/30/98 07/07/98 0.019 0.020 0.022 0.018 0.019 07/07/98 07/15/98 0.021 0.016 0.021 0.019 0.016 07/15/98 07/21/98 0.026 0.026 0.029 0.029 0.026 07/21/98 07/28/98 0.020 0.018 0.021 0.027 0.018 07/28/98 08/04/98 0.018 0.017 0.021 0.022 0.020 08/04/98 08/11/98 0.029 0.027 0.031 0.028 0.028 08/11/98 08/18/98 0.032 0.035 0.039 0.034 0.033 08/18/98 08/25/98 0.029 0.030 0.031 0.035 0.028 08/25/98 09/01/98 0.032 0.031 0.038 0.032 0.037 09/01/98 09/10/98 0.039 0.036 0.041 0.042 0.038 09/10/98 09/16/98 0.020 0.025 0.022 0.012 0.023 09/16/98 09/24/98 0.018 0.019 0.020 0.017 0.016 09/24/98 09/30/98 0.026 0.025 0.024 0.023 0.028 09/30/98 10/07/98 0.015 0.016 0.017 0.014 0.016 10/07/98 10/15/98 0.020 0.023 0.024 0.028 0.024 10/15/98 10/22/98 0.025 0.025 0.023 0.022 0.021 10/22/98 10/28/98 0.022 0.024 0.020 0.024 0.024 10/28/98 11/04/98 0.016 0.017 0.015 0.018 0.013 j 11/04/98 11/11/98 0.018 0.020 0.019 0.058 0.023 '

11/11/98 11/18/98 0.033 0.030 0.032 0.029 0.029 !

l 11/18/53 11/24/98 0.025 0.023 0.025 0.028 0.025 !

11/24/98 12/03/98 0.029 0.028 0.028 0.028 0.030 f j 12/03/98 12/10/98 0.025 0.024 0.025 0.023 0.024 !

12/10/98 12/16/98 0.030 0.031 0.033 0.030 0.037 i l 12/16/98 12/23/98 0.021 0.023 0.021 0.020 0.019 l' 12/23/98 12/29/98 0.030 0.031 0.031 0.030 0.031 12/29/98 01/06/99 0.029 0.030 0.029 0.031 0.031 l

1998 Annual Radiological Environmental Operating keport Wolf Creek Generating Station Page 20 of 18

TABIZ 4 Airborne Particulate Quarterly Composite Gamma Isotopic Analyses .

(pCi/ cubic meter, analysis counting uncertainties reported in Appendix B)

Location Quarter Be-7 K-40 2 1 0.0709 3 1 0.05e9 32 1 0.0729 37 1 0.0622 0.00616 40 1 0.0658 2 2 0.0864 3 2 0.0788 0.00781 32 2 0.0888 37 2 0.103 40 2 0.0863 2 3 0.0849 3 3 0.0774 32 3 0.1010 37 3 0.0765 40 3 0.0755 2 4 0.0711 3 4 0.0717 32 4 0.0636 0.00637 37 4 0.0718 40 4 0.0699 0.00728 l

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1 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 21 of 48

TABLE 5 First and Second Quarter TLD Results (ar/90 day qtr)

First Quarter Second Quarter Location Days 90 Day 2 std dev Location Days 90 Day 2 std dev Average Average 1 91.8 15.6 0.9 1 83.1 16.6 0.9 2 91.1 14.4 1.0 2 83.0 14.6 1.5 3 91.8 14.9 1.1 3 82.3 15.2 1.2 4 91.8 14.9 0.9 4 83.0 16.1 1.9 5 91.8 14.3 1.4 5 83.0 14.9 1.1 6 91.8 13.9 1.0 6 83.0 14.7 0.6 7 91.9 13.6 0.5 7 83.0 14.3 1.0 8 91.9 15.5 1.0 8 83.0 16.3 0.9 9 91.9 13.6 0.9 9 82.9 14.2 1.2 10 91.9 14.9 0.7 10 82.9 16.0 0.5 l 11 91.9 16.5 0.7 11 82.9 17.0 1.1 12 91.8 14.7 0.9 12 83.0 l'.7 0.5 13 91.8 15.4 1.5 13 82.9 16.4 1.3 l 14 91.8 16.0 1.3 14 83.0 16.5 1.4 l 15 91.8 15.2 0.7 15 83.0 15.7 1.5 16 91.8 14.6 1.1 16 83.0 15.4 0.4 17 91.8 14.3 0.8 17 83.0 15.5 1.6 18 91.9 15.7 1.1 18 83.0 16.7 1.4 19 91.9 16.4 1.0 19 83.0 16.9 1.3 20 91.9 15.6 0.9 20 83.0 16.1 1.1 21 91.9 12.8 1.1 21 83.0 13.5 1.0 22 91.9 15.3 0.7 22 83.1 16.0 0.9 23 91.8 14.8 1.0 23 83.0 15.6 0.7 24 91.8 14.6 1.0 24 83.0 15.3 1.3 25 91.0 12.2 1.8 25 83.0 12.5 1.0 26 91.9 14.1 0.7 26 83.0 14.3 0.7 l 27 91.9 15.2 1.1 27 83.0 15.5 0.8 28 91.9 12.9 1.3 28 83.0 13.2 0.5 1 29 91.9 12.6 1. 0 29 83.0 12.8 0.6 l 30 91.0 16.5 1.4 30 83.9 16.2 1.0 l 31 91.8 14.6 0.9 31 83.1 14.8 1.1 32 91.0 14.3 0.7 32 83.0 14.6 0.4 33 91.0 15.8 1.4 33 83.0 17.4 1.2 l 34 92.0 16.2 1.1 34 83.1 16.2 1.3 35 91.8 15.2 0.7 35 83.0 15.8 1.2 36 91.1 15.1 0.7 36 83.7 15.6 0.2 37 91.1 14.5 1.3 37 83.0 14.4 0.9 38 91.1 16.8 1.0 38 83.8 17.4 0.6 39 91.1 15.1 1.3 39 84.0 15.2 1.1 l 40 91.1 13.1 1.0 40 83.0 13.2 0.7 41 91.8 13.5 0.6 41 83.1 14.1 0.3 42 91.7 10.0 1.3 42 83.1 10.1 0.9 43 91.7 9.0 0.6 43 83.1 9.2 0.9 44 91.1 15.5 0.7 44 83.8 15.4 1.3 l 45 91.0 17.0 0.8 45 83.9 16.9 0.6 46 91.9 15.2 1.1 46 83.0 15.2 1.1 47 91.7 38.0 1.6 47 83.1 27.0 2.3 1998 Annual Radiological Environmental Operating Report

~ Wolf Creek Generating Station Page 22 of 48 l

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TABI.E 6 Third and Fourth Quarter TLD Results (ar/90 day qtr)

Third Quarter Fourth Quarter Location Days 90 Day 2 std dev Location Days 90 Day 2 std dev Average Average 1 90.9 16.0 1.4 1 90.2 17.7 1.3 2 91.8 14.0 1.3 2 90.1 15.8 1.6 3 91.8 14.7 1.2 3 90.2 16.6 1.5 4 91.1 14.9 1.2 4 90.2 17.8 1.7 5 91.1 14.3 0.5 5 90.2 15.6 1.1 6 91.0 13.8 0.8 6 90.2 16.0 1.5 7 91.0 13.5 0.7 7 90.2 14.9 1.3 8 91.0 15.1 1.8 8 90.2 17.4 0.8 9 91.0 13.9 1.9 9 90.3 15.1 0.7 10 91.0 15.5 0.9 10 90.3 17.2 0.6 11 91.0 16.6 0.8 11 90.3 18.7 0.9 12 91.0 15.3 1.2 12 90.3 17.2 1.3 13 91.0 15.7 1.8 13 90.3 17.7 1.4 14 91.0 15.6 0.8 14 90.3 17.6 1.4 15 91.0 15.2 0.3 15 90.2 17.1 1.5 16 91.0 14.9 0.6 16 90.2 16.5 1.9 17 91.0 14.2 1.2 17 90.2 17.2 1.2 ]

18 91.0 15.9 0.8 18 90.1 18.9 0.9 19 91.0 15.4 1.2 19 90.1 18.1 0.9 20 91.0 15.3 0.7 20 90.1 17.5 0.8 21 91.0 13.2 0.7 21 90.1 14.8 1.0 22 91.0 15.5 1.0 22 90.0 17.5 0.8 23 91.1 15.1 0.6 23 90.9 16.8 1.1 24 91.1 14.9 0.9 24 90.9 16.8 1.3 25 92.0 12.1 0.6 25 90.9 13.3 1.4 26 91.0 13.9 0.9 26 90.9 15.4 1.6 27 91.0 15.2 0.9 27 90.9 16.6 1.0 28 91.0 12.6 0.5 28 90.9 14.7 1.7 29 91.0 11.9 0.7 29 90.9 14.2 0.5 30 91.0 15.3 0.6 30 90.9 17.6 1.2 31 91.0 14.1 0.7 31 90.9 16.0 0.4 32 92.0 13.5 1.5 32 90.9 15.9 0.9 33 92.0 16.1 1.0 33 90.9 16.7 0.8 34 91.0 15.2 1.6 34 90.9 17.1 1.4 35 91.1 15.4 0.9 35 90.1 17.1 1.1 36 91.1 14.8 0.9 36 90.1 16.3 0.8 37 92.0 13.8 1.4 37 90.0 16.2 1.2 38 91.2 16.5 1.2 38 90.0 19.0 1.1 39 90.9 14.6 1.5 39 91.1 17.1 1.0 40 91.9 11.6 1.1 40 91.0 14.2 0.9 41 90.9 12.5 0.9 41 90.2 14.1 0.5 42 91.0 9.7 0.8 42 91.2 11.0 1.4 43 90.9 9.0 0.7 43 91.2 10.4 1.3 44 91.0 14.9 0.7 44 90.1 17.1 0.9 i 45 91.0 16.1 1.3 45 90.9 17.7 1.7 46 91.0 14.5 1.3 46 90.9 17.4 1.2 47 91.0 18.1 1.7 47 91.2 21.2 1.7 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 23 of 48 l

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I TABLE 7 Drinking Water Radiological Analyses (pCi/litar, analysis counting uncertainties reported in Appendix B))

Location Start Date Gr-B BW15 01/06/98 4.5 LW40 01/06/98 5.9 BW15 02/04/98 4.8 LW40 02/04/98 3.2 BW15 03/03/98 4.4 LW40 03/03/98 4.9 BW15 04/07/98 5.0 LW40 04/07/98 5.4 BW15 05/06/98 5.1 LW40 05/06/98 5.1 BW15 06/04/98 5.4

~

LW40 06/04/98 5.3 BW15 07/07/98 5.4 LW40 07/07/98 5.3 BW15 08/04/98 5.1 LW40 08/04/98 5.4 BW15 09/01/98 11.0 LW40 09/01/98 11.0 BW15 10/07/98 13.0 LW40 10/07/98 12.0 BW15 11/04/98 2.7 LW40 11/04/98 3.9 BW15 12/02/98 6.2 LW40 12/02/98 6.0 l

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1998 Annual Radiological Environmental Operating Report ;

Wolf Creek Generating Station Page 24 of 48 ;

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TABLE 8 Surfaos Water Radiological Analyses ,

(pCi/ liter, analysis counting uncertainties reported in Appendix B)

Location Date H-3 DC ~

01/20/98 11000 SP 01/20/98 11000 DC 02/17/98 13000 SP 02/17/98 12000 DC 03/17/98 8700 SP 03/17/98 8800 DC 04/21/98 8700 SP 04/21/98 9000 DC 05/19/98 8600 SP 05/19/98 8900 DC 06/16/98 8200 SP 06/16/98 8700 DC 07/21/98 8000 SP 07/21/98 8100 DC 08/20/98 7500 SP 08/20/98 7600 DC 09/24/98 9900 SP 09/24/98 8300 DC 10/22/98 8500 SP 10/22/98 9100 DC 11/19/98 8700 SP 11/19/98 8300 j DC 12/17/98 9000 SP 12/17/98 9000 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 25 of 48

TABLE 9 Shoreline Sediment Radiological Analyses (pCi/kg, dry, analysis counting uncertainties reported in Appendix B)

Location Date K-40 Cs-137 Ra-226 Th-228 MUDS 04/24/98 5960 3370 1310 DC 05/11/98 7240 54.2 1150 703 JBR 05/11/98 9830 183 1970 1110 DC 09/29/98 6820 53.4 934 733 JRR 10/29/98 9950 3130 1410 TABLE 10 Milk Radiological Analyses (pCi/ liter, analysis counting uncertainties reported in Appendix B)

Milk was not collected during 1998.

TABLE 11 Broadleaf Vegetation Radiological Analyses (pCi/kg, wet, analysis counting uncertainties reported in Appendix B)

Type Location Date l Be-7 K-40 Cs-137 CABBAGE S-4 05/26/98 210 2680 CABBAGE E-1 06/30/98 318 3180 HORSERADISH LEAVES F-1 06/30/98 371 3620 CABBAGE G-1 06/30/98 209 3350 9.73 CABBAGE S-4 06/30/98 261 3240 CABBAGE E-1 07/28/98 672 3500 HORSERADISH LEAVES F-1 07/28/98 757 3800 CABBAGE G-1 07/28/98 1410 3050 CABBAGE S-4 07/28/98 1050 2940 HORSERADISH LEAVES F-1 08/25/98 375 5400 CABBAGE G-1 08/25/98 188 2900 RHUBARB LEAVES S-4 08/25/98 2940 HORSERADISH LEAVES F-1 09/30/98 503 4150 hHUBARB LEAVES S-4 09/30/98 767 2130 RHUBARB LEAVES S-4 10/28/98 201 4230 HORSERADISH LEAVES F-1 10/29/98 683 4530 TURNIP GREENS G-1 10/29/98 4730 1998 Annual Radiological Environmental Operating Report

! Wolf Creek Generating Station Page 26 of 48 l~

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i f TABI2 12 Crop Radiological Analyses (pCi/kg, wet, analysis counting uncertainties reported in Appendix B)

Type Location Date K-40 CORN (irrigated) NR-U1 11/13/98 3280 SOYBEANS (not irrigated) NR-U1 11/13/98 16500 CORN (not irrigated) NR-D2 11/13/98 3240 SOYBEANS (not irrigated) NR-D2 11/13/98 15400 SOYBEANS (not irrigated) NR-D1 11/13/98 18500 l

l TABLE 13 Fish Radiological Analyses (pci/kg, wet, analysis counting uncertainties reported in Appendix B)

Species Location Date K-40 H-3 WHITE CRAPPIE JRR 05/11/98 3530 COMMON CARP JRR 05/11/98 3400 FW DRUM WCL 05/13/98 3290 6100 SM BASS WCL 05/13/98 3710 6800 COMMON CARP WCL (DC) 05/13/98 3280 3900 CHANNEL CATFISH WCL (DC) 05/13/98 3330 3200 SM BUFFALO WCL (UHS) 05/13/98 3120 5400 COMMON CARP JRR 09/29/98 3620 WH1TE CRAPPIE JRR 09/29/98 3590 WHITE BASS WCL (DC) 10/14/98 3390 11000 WALLEYE WCL (MAIN BODY) 10/14/98 3960 7200 WIPER WCL (URS) 10/14/98 3620 7600 SM BUFFALO WCL (UHS) 10/14/98 1810 7500 CHANNEL CATFISH WCL (URS) 10/14/98 3200 7300 TABLE 14 Botton Sediment Radiological Analyses (pCi/kg, dry, analysis counting uncertainties reported in Appendix B)

Location Date Be-7 K-40 Co-60 Zn-65 Cs-137 Ra-226 Th-228 DC 05/11/98 12500 1290 477 2810 1120 t JRR 05/11/98 406 15600 168 2110 1120 l JRR 09/29/98 16900 193 1780 1290

! DC 09/29/98 11800 865 96.4 394 1830 1180 I

I 1998 Annual Radiological Environmental Operating Report )

Wolf Creek Generating Station Page 27 of 48 l l- j

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TABLE 15 Aquatic Vegetation Radiological Analyses .

(pCi/kg, wet, analysis counting uncertainties reported in Appendix B) ;

Location Type Date Be- K- Mn- Co- Co- Cs- Cs- Ra- Th-7 '40 54 58 60 J34 137 226 228 l 1

DC ALT AM LOTUS 06/11/98 165 3470 1

DC ALT AM LOTUS 09/29/98 692 1860 l DC ALGAE 10/14/98 714 2270 25.5 77.3 198 3.78 34.0 250 88.0 i

l TABLE 16 Terrestrial Vegetation Radiological Analyses (pCi/kg, wet, analysis counting uncertainties reported in Appendix B)

Type Location Date Be-7 K-40 GRASS MUDS 06/30/98 2040 S480 GRASS EEA 06/30/98 1730 5350 GRASS EEA 11/20/98 7160 5560 GRASS MUDS 11/20/98 11900 4050 TABLE 17 Soil Radiological Analyses (pCi/kg, dry, analysis counting uncertainties reported in Appendix B) I Location Date Be-7 K-40 Cs-137 Ra-226 Th-228 EEA 04/24/98 694 11300 254 1860 1540 MUDS 04/24/98 804 11300 3440 1170 EEA 11/20/98 400 10900 153 2070 879 MUDS 11/20/98 12100 59.9 2140 1030 1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 28 of 48

TABLE 18 1998 Land Use Census Data .

Location of Nearest:

Sector Residence Milk Animal Broadleaf Garden A A2.6-17TE1520 None None B B3.1-QURD1712 None B3.6-QURD1755 C C1.9-16RD1655 None C1.9-16RD1655 D D2.1-QULA1571 None D2.1-QULA1571 E El.8-QULA1485 None El.8-QULA1485 F F1 6-14RD1711 None F1.8-14RD1730 G Gl.6-QURD1384 None Gl.6-QURD1384 H H3.1-12RD1711 None H4.85-10RD1698 l J J2.0-11RD1549 None J3.8-11RD1535 K K2.6-12LA1439 None K4.1-NARD 1120 L L2.4-NARD 1339 None L2.6-NARD 1309 M M2.3-14RD1322 None M2.6-HW751423 N N2.1-15RD1350 None N3.1-HW751434 l P P2.0-16RD1150 None P4.7-KARD1675 l

l Q Ol.4-NALA1574 None Q3.2-17RD1310 i

! R R2.1-NALA1650 None None Locations are identified based upon the following protocol: I EXAMPLE: A1.4-16RD1525 First letter is based upon sector, thus "A" designates this residence is in sector A.

i The number immediately following the first letter designates the distance (in miles) from the powerblock.

The characters following the dash represent a unique identifier based upon location address.

The example is in sector A, 1.4 miles from the plant, at 1525 16th Road.

l 1998 Annual Radiological Environmental Operating Report 1 Wolf Creek Generating Station Page 29 of 48 l l

l

TABLE 19 Comparison of 1998 and 1997 Land Use Census Milk and Garden Data i

SECTOR 1997 1998 1997 CLOSEST 1998 CLOSEST D/O MILK MILK GARDEN GARDEN PRODUCING RANKING ANIMAL ANIMAL PRODUCING BROADLEAF BROADLEAF VEGETATION VEGETATION A none none none none B none none B3.6-QURD1755 B3.6-QURD1755 5 C none none C2.2-16RD1670 C1.9-16RD1655 3 D none none D2.1-QULA1571 D2.1-QULA1571 10 E none none E1.8-QULA1485 E1.8-QULA1485 4 F none none F1.8-14RD1730 F1.8-14RD1730 2 G none none G1.6-QURD1384 G1.6-QURD1384 1 H none none H4.85-10RD1698 H4.85-10RD1698 13 J none none J3.8-11RD1535 J3.8-11RD1535 9 K none none K3.8-11RD1499 K4.1-NARD 1120 12 L none none L2. 6-NARD 1.~,0 9 L2.6-NARD 1309 8 ,

1 M none none M2.4-14RD1321 M2.6-HW751423 6 N none none N2.8-HW751480 N3.1-HW751434 11 P none none P4.5-KARD1630 P4.7-KARD1675 14 0 none none Q3.2-17RD1310 03.2-17RD1310 6 R none none none none NOTE: Underlined entries indicate changes from the 1997 Land Use Census.

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 30 of 48

l 1

4 TABLE 20 i

EPA Interlaboratory Comparison Program 1998 l Environmental Collection Medium Nuclide EPA Result (a) Telodyne Brown Deviation Date Engineering (c)

Result (b) i

01/16/98 Water Sr-89 8.0+ 5.0 5.00+ 1.73 -1.04 l Sr-90 32.01 5.0 31.671 0.58 -0.12 i 01/30/98 Water Gr-Alpha 30.51 7.6 33.001 2.65 0.57 Gr-Beta 3.91 5.0 5.601 0.90 0.59 02/06/98 Water I-131 104.91 10.5 110.001 0.00 0.84 02/13/98 Water- Ra-226 16.01 2.4 14.671 0.58 -0.96 Ra-228 33.3+ 8.3 32.001 2.00 -0.27 03/13/98 Water H-3 2155.01 348.0 1833.331 57.74 -1.60 l 04/21/98 Water Gr-Alpha 54.41 13.6 50.001 1.73 -0.56 Ra-226 15.0+ 2.3 15.00+ 0.00 0.00 Ra-228 9.37 2.3 8.50I 0.20 -0.60 Gr-Beta 94.77 10.0 102.00I 6.56 1.26 l Sr-89 6.07 5.0 4.67I 1.15 -0.46 l Sr-90 18.01 5.0 21.675 1.15 1.27 Co-60 50.0+ 5.0 52.33+ 1.53 0.81 Cs-134 22.07 5.0 21.007 1.00 -0.35 l Cs-137 10.01 5.0 11.675 0.58 0.58 l 06/05/98 Water Co-60 12.01 5.0 13.001 1.00 0.35 l Zn-65 104.0+ 10.0 111.67+ 2.52 1.33 Cs-134 31.0I 5.0 32.33I 0.58 0.46 Cs-137 35.0I 5.0 37.67I -

2.08 0.92 Ba-133 40.01 5.0 35.001 2.65 -1.73

( 06/12/98 Water Ra-226 4.91 0.7 4.471 0.85 -1.07 Ra-228 2.1_+ 0.5 1. 9 3_+ 0.21 -0.58 07/17/98 Water Sr-89 21.0+~ 5.0 21.00+ 1.00 0.00 Sr-90 7.01 5.0 6.331 0.58 -0.23 07/24/98 Water Gr-Alpha 7.21 5.0 5.431 0.64 -0.61 Gr-Beta 12.8+ 5.0 14.67+ 2.08 0.65 l

09/11/98 Water I-131 6.11 2.0 5.931 0.55 -0.14 l

09/18/98 Water Ra-226 1.71 0.3 1.531 0.46 -0.96 Ra-228 5.71 1.4 6.701 0.35 1.24 Footnotes:

a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ liter for water, b) Teledyne Results - Average i one sigma. Units are pCi/ liter for water.

c) Normalized deviation from the known.

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 31 of 48 i

l l

)

TABLE 21 Analytics Cross Check Comparison Program 1998 Sample Medium Nuclide Telodyne Analytics Ratio ID/ Date Brown Result (b)

Engineering Result (a)

E1346-396 Milk 1-131 87+ 9 82+ 4 1.06 '

TI#71657 Ce-141 66[ 7 701 4 0.94 03/12/98 Cr-51 220+ 30 201+ 10 1.09 l Cs-134 857 9 847 4 1.01 )

Cs-137 1807 20 1617 8 1.12 Mn-54 1307 10 1337 7 0.98 Fe-59 1107 10 957 5 1.16 Zn-65 1607 20 1427 7 1.13 Co-60 821 8 85[ 4 0.96 E1460-396 Milk I-131 68+ 7 67+ 3 1.01 TI#78921 Ce-141 947 9 997 5 0.95 06/11/98 Cr-51 977 31 1327 7 0.73 Cs-134 1017 10 957 5 1.06 Cs-137 797 8 707 4 1.13 Mn-54 1127 11 1067 5 1.06 Fe-59 58I 9 457 2 1.29 i Zn-65 1437 14 1227 6 1.17 Co-60 1571 16 1431 7 1.10 Footnotes:

a) T.piedyne Results - counting uncertainty is two standard deviations. Units ty* pCi/ liter for milk. For gamma results, if two standard deviations are lean than 10%, then a 10% counting uncertainty is reported.

b) Ratio of Teledyne Brown Engineering to Analytics results.

l l

I I

1998 Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 32 of 48 l

j

l l

' TABLE 22 Dosimetry Performance Testing Results .

NATIONAL VOLUNTARY LABORATORY ACCREDITATION PROGRAM PERSONNEL DOSIMETRY PERFORMANCE TESTING

SUMMARY

OF STATISTICAL RESULTS PROCESSOR NAME: DETROIT EDISON COMPANY PROCESSOR CODE: 100529 B DOSIMETER DESCRIPTION: PANASONIC UD-802AS/ISA 820 I TEST RESULTS FOR QUARTER: 199804 {

TESTING STATUS: RENEWAL 1 TYPE OF DOSIMETER WHOLEBODY REPORT PRINTED: 28 January 1999 i

SHALLOW DEPTH DEEP DEPTH CATEGORY B S lB l + S L D S lB l + S L j 01 NO TEST 0.025 0.092 0.117 0.30 02 NO TEST -0.013 0.123 0.136 0.30 3A 0.060 0.114 0.173 0.50 0.070 0.085 0.155 0.50

)

3B 04 NO TEST 0.029 0.110 0.139 0.50 SA NO TEST l

SB NO TEST SC 0.043 0.086 0.129 0.50 NO TEST 06 0.007 0.083 0.170 0.50 0.109 0.123 0.232 0.50 07 -0.038 0.087 0.125 0.50 -0.053 0.095 0.148 0.50 08-TOTAL NO TEST -0.017 0.086 0.103 0.50 08-NEUTRON NO TEST -0.036 0.088 0.124 0.50 l

09 I l

~

- - - PROCESSOR DID NOT PARTICIPATE IN THIS CATEGORY B = Bias i S = Standard Deviation j

! L = Limit I

l 1998' Annual Radiological Environmental Operating Report Wolf Creek Generating Station Page 33 of 48 i

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ML20206A914

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