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Annual Radiological Environ Rept,Radiological Environ Monitoring Program,Jan-Dec 1998
	ML20206S497
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Site:	Cooper
Issue date:	12/31/1998
From:	Guenther J; TELEDYNE BROWN ENGINEERING CO.
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i Cooper Nuclear Station Annual Radiological Environmental Report l

Radiological Environmental Monitoring Program )

January 1,1998 - December 31,1998 I 1

USNRC Docket Number 50-298 Nebraskgl H District Prepared by TELEDYNE BROWN ENGINEERING ENVIRONMENTALSERVICES c4ma. pes j

w REPORT TO NEBRASKA PUBLIC POWER DISTRICT COLUMBUS, NEBRASKA RADIATION ENVIRONMENTAL MONITORING PROGRAM COOPER NUCLEAR STATION NEMAHA COUNTY, NEBRASKA ANNUAL REPORT JANUARY 1 'lV DECEMBER 31,1998 PREPARED BY TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES 50 VAN BUREN AVENUE WESTWOOD, NEW JERSEY 07675-1235 REPORT APPROVED BY: t*

JEFFREY M. GUENTHER, TECHNICAL MANAGER ENVIRONMENTAL ANALYSIS DEPARTMENT l

.l ATTACHMENT 3 LIST OF NRC COMMITMENTS l Correspondence No: NLS990051 The .following table identifies those actions committed to by the District in this

-document. Any other actions discussed in the submittal represent intended or planned actions by the District. They are described to the NRC for the NRC's l information and are not regulatory commitments. Please notify the NLES Manager.at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None N/A I

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l l PROCEDURE NUMBER 0.42 l REVISION NUMBER 6 l PAGE 9 OF 13 l m

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' PREFACE This report covers the period of January 1 through December 31, t

1998. All sample collections were made by personnel of the Nebraska Public

, Power District. Analyses were performed and reports of analyses were i prepared by Teledyne Brown Engineering - Environmental Services and forwarded to Nebraska Public Power District.

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l TABLE OF CONTENTS i PAGE Ph......................................................................................................................... 11 IJstof'Ihbles.............................................................................................................. vi IlstofF1 gums........................................................................................................... vil I. I n tro d u c tio n .. .. .. .. .. .. . .. .... .. .. .... ... .... .. .. .. .. .. . .. .. ... . .. .. .. .. . .. .... .. ... . .. ... .. .... .. .. . ... .. . .. .. .... .. .. .. 1 II. Summary.......................................................................................................................2 III. Sampling and Analyses Program, Stations and Maps .................................. 3 l IV . Discussion . .. ... ... ...... . .. .. .. ... .. . ...... ..... . .. .. .. ... .. .. ..... ..... .. . .... .. . .. .. . .. .. .. ... . . .. ... .. . .... .. . .... .. . ... 1 1 i

A. Program Objectives and Data Interpretation 11 Atmospheric Nuclear Detonations V. Radiological Environmental Monitoring Program Summary Table 3...12 l REMPS TABLE 3 ANNUAL

SUMMARY

OF ALL STATIONS OF THE ............13 ISOTOPES OF IITTEREST WITH YEARLY AVERAGE

' ACTIVITY, NUMBER OF DETECTIONS PER 'IDTAL STATION WITH HIGHEST AVERAGE ACTIVITY, AVERAGE OF COlfrROL STATION AND INCLUSIVE l DATES OF ANALYSES vi.

l DISCUSSION, IMPACT ON THE ENVIRONMENT, GRAPHS OF .................. 25 I RESULTS AND STATISTICAL TABLES FOR EACH QUARTER l 1

I' A and B. AIR PARTICULATES - GROSS BETA - GROSS ALPHA .................... 26 C. CHARCOAL FILTER, 1-131..........................................................................41 ,

D. COMPOSITE OF AIR PARTICULATE FILTERS - GAMMA .............. 49 I 1

E. FISH.....................................................................................................................57 i

i F. MILK - NEAREST PRODU CER ................................................................. 63 G. MILK - OTHER PRODUCERS ..............................................................72 !

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TABLE OF CONTENTS PAGE H. GROUNDWATER ........................................................................................81 I. RIVER WATER ............................................................................................88 J. THERMOLUMINESCENT DOSIMETERS ..........................................96 K. FOOD - BROADLEAF VEGETATION ......................................................104 L SH O RE LI NE SEDIMENT ........ ........ .................. ........................................ 1 10 VII . COMPLETE DATA TABLES ................................................................................ 115 A.B,C. AIR PARTICULATE FILTERS - GROSS ALPHA. .........................116 GROSS BETA.1-131 D. COMPOSITE - AIR PARTICUI ATE FILTERS ...............................137 E. FISH.............................................................................................................148 F. MILK - NEAREST PRODUCER .......................................................... 151 G. MILK - OTHER PRODUCERS ............................................................. 158 H. G ROU NDWATER .................... ...................... ...... .................................... 182

1. RIVE R WATE R . . ... .. ... . .. ... . .. . ... ... ..... . .. ... . .. . .. . .. ... .... .. . .. . .. . .. . .. . .. . .. ... . .. ... .. . .. .. 165 J. THERMOLUMINESCENT DOSIMETERS .....................................172 K. FOOD - BROADLEAF VEGETATION .................................................177 L SHORELIN E SEDIMENT ..................................................................... 185 REFERENCES...................................................................................................................187 1V

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l l TABLE OF CONTENTS PAGE VIII. Appendix )

l A LAND U SE C E NSU S ............................................ ............. .................. . .... .A- 1 B INTERLABORATORY COMPARISON PROGRAM ...........................B-1 C STATI STI CAL NOTE S ................................... ..... .......1. .. ..... ..................C- 1 D. NOTIFI CATI O N LEVELS .................................................................... . ...D- 1 l l

1 E. C O NVE NTI O N S .. . . ..... ..... .. . .. ..... . ... .. . .. . . . .. . .. . .. . .. .. . . .. ... .. .. . .. . .. ... .. ... . .. . .. ... .. . .. .E- 1 1

E DE IECI1ON CAPABIIJHES.............. . .. .... ......... .................................. ..F- 1 l G. SAMPLE STATION LOCATION AND SAMPLE TYPES................G-1 l l

H.

SUMMARY

OF DOSES TO A MEMBER OF THE PUBLIC...........H-1 OFF-SITE l

I V

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IJST OF TABIJCS

)

TABLES TITLE .PAGE 1 Sampling schedule and analysis, 5 1998, Cooper Nuclear Station i

2 Sample Station Location with 7 Distance and Direction from the Elevated Release Point (ERP) 3 Summary of Radiological Monitoring 13 Program A to L Statistical Summary Tables - Section VI pages25-114 By Sample Type A to L Data Tables - Section VII pages 115-190 By Sample Type and Station I vi

LIST OF FIGURES I!A TEl.c P_ age

1. Maps of sampling stations, Cooper Nuclear Station.............................. 9.10 A-1 Air Particulate, Gross Beta - CNS....................................... 28,29,30,50,51,52 A-2 Air Particulates, Gross Beta - ERAMS........................................... 31,32,53,54 B-1 Air Particulates, Gross Alpha - CNS.................................. 28,29,30,50,51,52 C-1 Airborne - Iodine, CNS. . .. .. . . . . ...... ... . . .. .. . . .. . . .. .. . . . . .. . . .... . . . . ... .. ... . .. ... . .. .. . . .. .. . . . 42,43,44 D-1 Air Particulates - Ce- 144 - CNS........................................... 28.29,30,50,51,52 D-2 Air Particulates Ce-144 - EML................................................................ 50,51,52 E-1 Fish, Gross Beta, K-40, Sr-90 and Cs-137 - All Imcations.......... 58,59, 60 F-1 Milk - Nearest Producer, K-40,1-131 and Cs-137........................ 64,65,66 F-2 Milk - Nearest Producer, Sr-89, Sr-90 and Elem. Ca................... 67,68,69 l G-1 Milk - Commercial Producers, K-40. I-131 and Cs-137.............. 73,74,75 G-2 Milk - Commercial Producers, Sr-89, Sr-90 and Elem. Ca......... 76,77,78 H-1 Groundwater - All Locations, Gross Alpha, Beta and H-3............. 82,83,84 I-1 River Water - All locations, Gross Alpha, Beta................................. 88,89,90 I-2 River Water - All Locations, Sr-89 Sr-90 and H-3........................ 91,92,93 J-1 'Ihermoluminescent Dosimetry - All Imcations............................... 97,98,99 K-1 Food - Broadleaf Vestation - All Imcations........................................105,106 L-1 Shoreline Sediment K-40, I-131, Cs-134 and Cs-137...............111,112 l

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L INTRODUCTION This report contains a complete tabulation of data collected during the period January through December 1998, for the operational Radiological Environmental Monitoring Program performed for the Cooper Nuclear Station (CNS) of the Nebraska Public Power District (NPPD) by Teledyne Brown Engineering - Environmental Services.

Cooper Nuclear Station is located in Nemaha County in the southeast corner of Nebraska on the Missouri River. A portion of the site extends into Missouri. The reactor is a 778 megawatt boiling water reactor. Initial criticality was attained on February 21, 1974. The reactor reacl'.ed 50%

power on June 25,1974 and 100% power on November 20,1974.

Radiological environmental monitoring began in 1971 before the plant became operational and has continued to the present. The program monitors radiation levels in air, terrestrial and aquatic environments. Most samples are collected by NPPD personnel. All are shipped for analysis to a contractor's laboratory where there exists special facilities required for measurements of extremely low levels of radioactivity. From 1971 through 1976 the contractor was Teledyne Isotopes, Westwood, New Jersey. ?!ALCO Environmental Sciences: assumed responsibility for the analyses effective January 1,1977.

On November 1,1978 Hazelton Environmental Sciences Corporation

-(HESC) assumed responsibility for the program. Prior to November 1,1978 Hazelton Environmental Sciences operated as NALCO Environmental Sciences. Teledyne Isotopes (now trading as Teledyne Brown Engineering -

Environmental Services) again assumed responsibility for the analyses effective January 1,1979 through December 31,1998.

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SUMMARY

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Presented in this report are summaries and discussions of the data generated for the Radiological Environmental Monitoring Program (REMP) for the Cooper Nuclear Station (CNS) of the Nebraska Public Power District (NPPD) for 1998. 1 Part V, Table 3 presents the yearly summary of the program with the total number of samples of each type analyzed, the yearly average for all samples, the number of detections per total number of samples, the station with.the highest average, the average of the control station, and th: inclusive dates of the analyses.

Part VI is a discussion of each type of sample analyzed and its impact, if any, on the environment. Included also is a graph of the isotopes of interest since 1977 and the statistical results for each quarter of the year. This is followed by a complete tabulation of the data by sample type and station l number.

The -1998 radiological environmental measurements for CNS indicates that there has been no residual fallout resulting from the explosion and fire at the Chernobyl Reactor in the Soviet Union which occurred on April 26, l

! 1986. It may be concluded from all measurements taken that the operations of CNS had no detectable impact on the environment in the vicinity of CNS.

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III. SAMPLING AND ANALYSES PROGRAM. STATIONS AND MAPS The 1998 sampling and analysis program is described in Table 1.

'teledyne Brown Engineering - Environmental Services has a comprehensive

. quality assurance / quality control program designed to assure the reliability of data obtained. The results for the 1998 Intercomparison Program conducted by the EPA Environmental Monitoring Systems Laboratory in Las Vegas, Nevada and Analytic *s, Inc., are contained in Appendix B.

Sampling locations are summarized in Table 2. The type or status of each location and its distance and direction from the reactor elevated re-Jease point are specified. A map of locations follows (Figure 1). Complete descriptions of active sampling locations are given in Appendix G.

The annual land use census for 1998 is described in Appendix A.

There were no milk animals found within three miles of CNS in 1998 and no evidence of potable water use from the river. The nearest garden to CNS is in sector L,1.3 miles from CNS. Gardens were found in 9 sectors during i1997 and in 8 sectors during1998. The nearest resident to CNS is in sector Q, 0.9 miles from CNS.

All of the required 1998 environmental monitoring, including sam-pling and analysis, was conducted as specified in Table D4.1-1 of the CNS Offsite Dose Assessment Manual (ODAM), except as noted below:

COLLECTION STATION PATHWAY SAMPLE PERIOD REASON 11 Waterborne Groundwater 01/20 Unable to collect due to I frozen valve on well 1-10 Airborne Air Particulate & 03/03-03/.10 Unable to collect due to Charcoal Filters severe weather conditions 59 Ambient TLD 01/07-04/01 Sample destroyed by fire Gamma 07 Airborne Air Particulate & 04/07-04/14 Pump failure Charcoal Filter 07 Airborne Air Particulate & 04/14-04/21 Pump failure Charcoal Filter 07 Airborne Air Particulate & 04/21-04/28 Pump failure !

Charcoal Filter 28,35, Ingestion Broadleaf 05/26 Vegetation not available 81,101 Vegetation 03 Airborne Air Particulate & 06/09-06/16 Unabk to obtain sample ;

Charcoal due to llood water i 28,35. Ingestion Broadleaf 06/16 Unable to obtain due to ;

Vegetation flood (28,35): insuincient 101 vegetation (101) 1 3 l l

i-COLLECTION STATION PATHWAY SAMPLE PERIOD REASON

03' Airborne Air Particulate & 06/23-06/30. Pump failure Charcoal Filter 71 Ambient TLD 04/01-07/01 Sample missing Gamma 28,35, Ingestion Broadleaf 07/14 Vegetation not available 101 Vegetation - (35); partial sample due to insufficient vegetation (28, 101) 35 Ingestion Broadleaf 08/11 Vegetation not available Vegetation 03 trborne Air Particulate & 08/11-08/18 Pump failure Charcoal Filter 28,35 Ingestion Broadleaf 09/17 Sample unavailable (35, 101 Vegetation 101); partial sample due to insufficient veg. (28) 99 Ingestion Milk - Nearest 09/23 Sample not available Producer 02,06 Airborne Air Particulate & 09/23-09/29 Power failure resulted in )

Charcoal Filter low air volume; samples i did not meet spec.

28,35 Ingestion Broadleaf 10/22 Sample not available due 101 Vegetation to death of vegetation 59,71.82 Ambient 'ILD 10/27 Samples missing Gamma 07 Airborne Air Particulate & 11/03-11/10 Pump failure Charcoal Filter 07 Airborne Air Particulate & 11/10-11/17 Pump failure Charcoal Filter 07 Airborne Air Particulate & 11/17-11/24 Insufficient sample volume Charcoal Filter 07 Airborne Air Particulate & 12/08-12/15. Pump failure l Charcoal Filter 20,59, Ambient TLD 10/27/98- Samples not availabh 82 Gamma 01/26/99

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i COLLECTION STATION PAm .WAY SAMPLE PERIOD REASON 61 Ingestion Milk - Nearest 02/98-12/98 Station 61 listed in ODAM Producer not used because dairy out j of business; replacement '

samples obtained at Station 99 96 Ingestion Broadleaf 05/98-10/98 Station 96 listed in ODAM Vegetation not used because it was not predicted to have the highest annual average ground-level D/Q: j replacement samples obtained at Station 28 i

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l TABLE 1 l

NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION ENVIRONMENTAL RADIATION SURVEILLANCE PROGRAM SAMPLING SCHEDULE AND ANALYSIS l ONCE PER 7 DAYS l Sample Tvoe Station Nos. Analyses Airborne - Particulate 1 - 10 Gross alpha, beta. Gam-ma isotopic on quarterly composite of each sta- l tion and on each sample in which gross beta ac- i tivity is > 10 times the yearly mean of control ;

samples Airborne - Iodine 1-10 1-131 l ONCE PER 15 DAYS l Sample Tyne Station Nos. Analyses Milk - Nearest Producer 99 I-131 (low level)

(peak pasture only) Gamma isotopic Sr-89, Sr-90, Elem.

Ca. on monthly composite l ONCE PER 31 DAYS l Samole Tyne Station Nos. Analyses River Water 12,28 Gross alpha - sus and dis Gross beta - sus and dis, Sr-89, Sr-90 Gamma isotopic Tritium on quarterly composite 5

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' TABLE 1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION ENVIRONMENTAL RADIATION SURVEILLANCE PROGRAM SAMPLING SCHEDULE AND ANALYSIS l ONCE PER 31 DAYS l Sample Tvoe Station Nos. Analyses Milk - Nearest Producer 61,99 l-131 (low level)

(non-peak pasture Sr-89, Sr-90 season)

Elem. Ca Gamma isotopic Food Products - Broad- 28,35,81,101, 1-131 leaf Vegetation (when 96 Gamma isotopic available) 1 ONCE PER 92 DAYS l Samole Tvoe Station Nos. Analyses Background Radiation 1 - 10, 20, 44, TLD Readout 56,58,59,66, (gamma dose) 67, 71, 79 - 91, 94 ,

I Groundwater 11,47 Gross alpha, beta I Gamma isotopic Tritium Milk - Commercial and 42, 100 1-131 (Iow level) j Other Milk Producers Sr-89, Sr-90 Elem. Ca Gamma isotopic l 2 TIMES / YEAR l Samole Tvoe Station Nos. Analyses Fish (Summer and Fall) 28,35 Gross beta Sr-89, Sr-90 Gamma isotopic l Shoreline Sediment 28 Gamma isotopic l

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l TABLE 2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STA' HON BROWNVILLE, NEBRASKA DISTANCE AND DIRECTION FROM THE ELEVATED RELEASE POINT (ERP)

TO THE SAMPLE STATION LOCATIONS STATION" DISTANCED DIRECTIOND SAMPLED NUMBER (MILES) (DEGREES) CLASSIFICATIONC TYPES 1 0.10 225 IND AP,C,TL 2 0.75 225 IND AP,C,TL 3 2.5 338 IND AP,C TL 4 3.0 43 IND AP,C,TL 5 3.5 102 IND AP,C,TL i 6 3.0 165 IND AP,C TL I 7 2.5 230 IND AP,C,TL 8 2.5 260 IND AP, C, 'IL 9 7.3 335 IND AP,C,TL 10 10.0 160 IND AP,C,TL 11 0.15 225 IND WG j 12 0.10 360 CON WR i 20 0.96 315 IND TL 28 1.8 150 IND WR, FI, SH, VT l 35 2.0 350 CON VT, FI, WR l 42 12,9 156 IND M (Other) l 44 10.3 270 CON TL 47 25.8 154 IND WG 56 1.9 118 IND TL 58 1.1 219 IND TL 59 1.0 189 IND TL 61 3.5 326 IND M (Nearest) 66 4.5 200 IND TL 67 4.8 325 IND TL 71 4.3 71 IND TL 79 0.85 299 IND TL 80 0.75 284 IND TL 81 0.80 265 IND TL,VT 82 0.80 176 IND TL 83 4.4 189 IND TL 84 4.4 297 IND TL 85 3.1 3 IND TL 86 4.6 16 IND TL 87 1.75 20 IND TL 88 1.75 63 IND TL 89 2.0 86 IND TL 90 2.25 134 IND TL 91 6.9 54 IND TL 7

l TABLE 2 i NEBRASKA PUBLIC POWER DISTRICT l COOPER NUCLEAR STATION BROWNVILLE, NEBRASKA l

DISTANCE AND DIRECTION FROM THE ELEVATED RELEASE POINT (ERP) l TO THE SAMPLE STATION LOCATIONS STATION" DISTANCE D DIRECTION D SAMPLE d

-NUMBER (MILES) (DEGREES) CLASSIFICATION C TYPES 94 3.6 108 IND TL 96 1.2 334 IND VT 99 10.5 189 IND M (Nearest) 100 11.5 197 IND M (Other) 101 13.3 73 IND VT a Only Sample Stations active for the reporting period are listed. Sample i Station numbers missing from the sequence are for inactive or discontinued locations.

b Approximate distance and direction are specified with respect to the re-actor Elevated Release Point (ERP).

C - Classification codes: IND = indicator: CON = control.

d Environmental sample type codes: AP = air particulate filters: C = char-coal cartridges: FI = fish: M = milk; SH = shoreline sediment: TL = envi-ronmental thermoluminescent dosimeters: VT = broadleaf vegetation: WG i

= groundwater: WR = river water. l l

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I IV.' DISCUSSION A. Program Obtectives and Data Internretation l The objective of the monitoring program is to detect and assess the im-pact of possible releases to the environs of radionuclides from the operations of the Cooper Nuclear Station. 'Ihis objective requires measurements of low levels of radioactivity equal to or lower than pre-determined limits of detec-tion. In addition the source of the environmental radiation must be estab-lished. Sources of environmental radiation include:

(1) Natural background radiation from cosmic rays (Be-7).

, (2) Terrestrial, primordial radionuclides from the environment (K-40,

! Ra-226. Th-228).

l (3) Fallout from atmospheric nuclear tests such as the September 1977 detonation by the Peoples' Republic of China and the atmospheric weapons test of October 16,1980 (fission products and fusion prod-t ucts).

(4) Releases from nuclear power plants such as CNS (fission products l and neutron activation products).

(5) Fallout from the Chernobyl Nuclear Reactor Accident.

Radiation levels measured in the vicinity of an operating power station j are compared with preoperational measurements at the same locations to '

distinguish power plant effects from other sources. Also, results of the moni- i toring program are related to events known to cause elevated levels of radia- 1 tion in the environment, e.g., atmospheric nuclear detonations or abnormal plant releases.

H Atmosoheric Nuclear Tests Three atmospheric nuclear detonations in the People's Republic of China j j influenced program results significantly in late 1976 and in 1977. Two of l these detonations occurred in late 1976 (September 26 and November 17) and one in late 1977 (Septembe'r 17). As a consequence of these tests ele-vated activities of gross beta in air particulate filters and I-131 in milk were l observed throughout most of the United States.

No atmospheric nuclear tests have been conducted since 1977, thus no short-lived fission products were detected in air particulate samples. Also no 1-131 was detected from radiogases from any sources.

On April 26,1986 the fire and explosion of Chernobyl Reactor No. 4 in the Soviet Union resulted in the release of fission products to the atmo-sphere and worldwide fallout. Following the explosion, elevated levels of gross beta activities in air particulates and I-131 in charcoal filters and milk samples were measured. Additionally, in 1986, Cs-137 and the short-lived isotopes I-131, Ru-106, and Cs-134 were detected in broadleaf vegetation.

Similar results occurred in other areas of the United States and the entire Northern Hemisphere.

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l l V. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLES Presented in Table 3 are the radiological environmental monitoring pro-gram summaries (REMPS) generated from the reports of analyses performed l during 1998 for the NPPD sampling and analyses program. The REMPS ta-l bles conform to the requirements of Table 1 in Regulatory Guide 4.8 (Reference 6).

l The average activity level for all samples collected for the year for each sample type are smnmarized in this table. The mean, range and fraction of detections to total samples assayed are presented. The station location and station number with the highest annual mean is also tabulated. If a control station is specified the comparable results of the control are listed.

From the REMPS table it is possible to determine the total number of each type of sample analyzed and the average activity of all samples from all stations of each nuclide. If there were no positive detections the maximum of the lowest levels of detection is listed. The station having the highest level of activity is specified. From this data it is possible to determine any high levels of activity and the source. The dose impact on the population can thus be evaluated.

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l TABIE 3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMARIES (REMP) 1998 13

1!

T C D 8 I

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VL DISCUSSION, IMPACT ON THE ENVIRONMENT l

GRAPHS OF RESULTS FROM 1977-- 1998 AND STATISTICAL TABLES PCR l EACH QUARTER l

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25

A and B. AIR PARTICUIATE SAMPLES - GROSS BETA AND GROSS ALPH4 (See Tables A A-4. B B-4)

STATIONS 01 to 10 Air particulates were collected on membrane filters at ten locations (01-10). The filters were changed weekly and analyzed for gross beta and gross alpha activities. Quarterly composites are analyzed for gamma emitting iso-topes.

The average gross beta activity of all stations for each quarter of 1997 and 1998 is summarized below:

1997 First Quarter 0.020 pCi/Cu. M.

Second Quarter 0.015 pCi/Cu. M.

Third Quarter 0.025 pCf/Cu. M.

Fourth Quarter 0.025 pC1/Cu. M.

Average 1997 0.021 pCi/Cu. M.

1998 First Quarter 0.024 pCi/Cu. M.

Second Quarter 0.017 pCi/Cu. M.

Third Quarter 0.025 pC1/Cu. M.

Fourth Quarter 0.018 pCi/Cu. M.

Average 1998 0.021 pCi/Cu. M.

The level of beta activity was at normal environmental levels in 1998 showing the natural seasonal variations. There was a slight increase in the level of gross beta activity during the first quarter; the second quarter of 1997 was slightly lower than 1998. The third quarter of 1998 was the same as in 1997. Here was a slight decrease in the fourth quarter of 1998. he increase and decline in activity often occurs and is attributed to natural phenomena.

The gross alpha activity continued low and close to the limits of detec-tion. Gross alpha activity is probably due to the alpha emitters found in soil and particulates drawn into the filters.

No effect attributable to the Cooper Nuclear Station was observed in the results of monitoring air particulates.

26

A and B. AIR PARTICULATE SAMPLES - GROSS BETA AND GROSS ALPHA (See Tables A A-4. B B-4)

STATIONS 01 to 10 Figure A1, B1 shows the gross beta, gross alpha and Cc-144 activity in the environs of CNS. The results for 1986 through 1998 are on the second and third pages of Figure A-1, B-1. The gross beta activity in 1998 was simi-lar to previous years in which there were no nuclear atmospheric weapons tests or nuclear accidents. he gross alpha activity remained low and near the normal detection level. Cerium-144 was below the level of detection.

Figure A-2 shows the gross beta activity in air samples through April 1989 at Jefferson City, Missouri as reported by the Environmental Radiation Monitoring System (ERAMS) of the US Environmental Protection Agency.

No more recent data was available. His data was taken from Environmental Radiation Da.ta distributed by the Eastern Environmental Radiation Facility, Montgomery, Alabama. The measurements by ERAMS were made after a waiting period which may explain the somewhat lower results because of decay of the isotopes having a shorter half-life. Measurements of Cc-144 were no longer reported because the activity has approached the limit of de-tection by the analytical techniques now used.

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C. AIR RADIOIODINE - CHARCOAL FILTERS (See Tables C-1 throuah C-4)

STATIONS 01 m 10 Charcoal filters used in series with air particulate filters were collected weekly during 1998 at stations 01 through 10 and monitored for radioiodine.

l Tables C-1 through C-4 show the average monthly and quarterly results for each station and the average of all 10 stations. Airborne I-131 levels were '

below the limits of detection for all of 1998.

Figure C-1 plots the results ofI-131 as monitored in charcoal filters and summarized monthly in 1998 compared with previous years. Results for 1998 were generally below the normal limits of detection indicating no atmospheric effect from the operations of CNS.

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STATIONS 01 TO 10 Air Particulate Filters, which were collected weekly, were composited for each station for a quarterly gamma spectral analysis during the four quar-ters of 1998.

Beryllium-7, a naturally occurring cosmogenic nuclide, was detected in 40 of 40 samples at a level of 0.10 pCi per cubic meter which is similar to the levels of past years. Potassium-40, also a naturally occurring nuclide, was detected in the first quarter at a level of 0.02 pCi per cubic meter for Station

8. Potassium-40 was not detected for the remaining 39 samples.

Figure D-1 graphs the gross beta, gross alpha and Ce-144 activity as measured on air particulate filters collected weekly at CNS. (This is the same as Figure A-1, B-1). The plot illustrates that there were no detections of Ce-144 above the normal level of detection as measured by the quarterly gamma scan of samples from CNS.

Figure D-2 shows that measurements of Ce-144 are no longer reported by the Environmental Measurements Laboratory of the US Department of Energy because the artificial nuclides such as Ce-144, have reached the lim-its of detection by the analytical techniques now used.

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E. FISH (See Tables E-1. E-2)

STATIONS 28. 35 l

Fish samples were collected during the summer and fall at the above stations and analyzed for gross beta, Sr-89, Sr-90, and Jamma emitting iso-topes. A midole-top feeding fish (carp) and a bottom jeeding fish (catfish) '

were collected in July and September.

The gross beta and Sr-90 activities were similar to the levels of previous years. Strontium-90 was generally below the normal level of detection. One sample for catfish at Station 28 collected in September had a Sr-90 value of 0.007 cC1/gm, wet, and a Cs-137 value of 0.02 pCi/gm, wet. 'Ihere were no detections of Sr-89. Naturally occurring K-40 was detected in all samples at an average level of 2.93 pCi/gm, wet.

Plotted in Figure E-1 are the radionuclides gross beta, K-40, Sr-90 and '

Cs-137 monitored in fish samples which show no appreciable change from 1977 through 1998. The plot of the nuclides shows that most of the gross beta activity is due to the terrestrial nuclide K-40. j as ;

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l F. uTTX iSee Tables F-1. F-21 STATIONS 61. 99 fMEAREST PRODUCER)

One sample from Station 61, 3.5 miles, 326 degrees from the elevated release point of CNS, were collected in January as the nearest producer.

Samples from Station 99,10.5 miles from the plant, was collected from February through December as the nearest producer. Samples are collected once every 15 days in peak pasture season and once every 31 days the rest of the year.

The monthly samples collected January through May and October through December were analyzed for I-131 by chemical separation, for elemental calcium and strontium 89 and 90. In addition they were analyzed for gamma emitting isotopes on a high resolution gamma spectrometer. The

! samples collected every 15 days during peak pasture season were analyzed !

upon receipt for I-131 and gamma emitting isotopes. A monthly composite I was prepared and analyzed as described above.

There were no detections of I-131 in the twenty samples analyzed by chemical separation. There were no detections of Sr-89 in the samples ana-lyzed. Strontium-90 was detected at an average level of 1.4 pCi/ liter, which is a normal environmental level. Elemental calcium was found at an average level of 1.4 mg/ liter. Potassium-40, a naturally occurring isotope, was ,

detected at an average level of 1280 pCi/ liter. '

1 Cesium-137 was not detected in any of the samples analyzed. There was no indication of an effect on the milk of the producer nearest the plant from ,

the operations of CNS.

Shown in Figure F-1 and F-2 are the plots of radionuclides monitored from 1977 through 1998 in milk samples from producers nearest the reac-tor. The levels of K-40, elemental calcium and Sr-90 remained stable.

There were no detections of I-131, Sr-89 or Cs-137. This indicates no effect on milk samples from the operations of CNS.

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l G. MILK (SEE TABLES G-1. G-21 l

STATIONS 42. 99.100 (OTHER PRODUCERS) l Milk samples were collected in the first quarter from other producers, Station 99,10.5 miles from the plant and Station 100 which is 11.5 miles from the plant during January. Samples were collected from Stations 100 l and 42, which is 12.9 miles from the plant, during the rest of the year. The samples were analyzed for I-131 by chemical separation, for elemental calcium, for Sr-89 and 90 and for gamma emitting isotopes. There were no detections of I-131 in the eight samples monitored.

There were no detections of Sr-89. Strontium-90 was found at an aver-age level of 0.84 pCi/ liter. There were 1.6 mg of calcium per liter of milk.

Potassium-40 was detected at an average level of 1370. pCi/ liter. The stron-tium-90 K-40 and elemental calcium were at normal environmental levels and were similar to the results obtained from analyses of milk from the near-est producer. Strontium-90 results were slightly lower for other producers which may be attributed to the change in sampling locations. There were no detections of Cs-137 in the samples collected. It can be concluded that the operations of CNS had no efiect on milk samples and thus no dose impact on the population.

The levels of radioactivities of the nuclides K-40,1-131 and Cs-137 are plotted on Figure G-1. Potassium-40 was at normal environmental levels as in previous years. There were no detections of I-131 or Cs-137. Figure G-2 shows that Sr-90 and elemental calcium are at a level comparable to previous years and tiiere were no detections of Sr 89. These graphs indicate that there was no appreciable difference between the levels of activity of the nearest producer and the commercial producers. This indicated no effect on milk samples from the operations of CNS.

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l H. GROUNDWATER ISee Tables H-1 and H-2) l STATIONS 11. 47 l

l l

Groundwater was collected from two stations quarterly and analyzed for l

gross beta and gross alpha activity, for tritium and for gamma emitting ra-dionuclides. Station 11 is 0.15 miles from the plant and station 47 is 25.8 miles from the plant.

The gross beta activity averaged 7.5 pCi/ liter which is statistically similar to past years. There was no detection of gross alpha above the normal level

.of detection There were no detections of gamma emitters above the normal level of detection. The tritium level averaged 100 pCi/ liter for the year which is the normal environmental level.

l There was no difference in levels of beta activity or tritium for the sta-

tion close to the plant as compared with the more distant station. It may be i

! -concluded that there was no impact from the operations of CNS on the envi- i' l

ronment as shown by measurements of radionuclides in groundwater.

l Shown in Figure H-1 are the gross alpha, gross beta and tritium levels in ,

groundwater. The levels of these activities have remained essentially un- !

changed. ;

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L RIVER WATER ISee Table I-1 and I-2)

STATIONS 12. 28 River water was collected monthly and monitored for gross beta and gross alpha, suspended and dissolved, Sr-89 and Sr-90 plus gamma emitting isotopes. A quarterly composite was measured for tritium.

There were no detections of potassium-40 above the normal level of de-tection and no detections of Sr-89 or Sr-90.

The average gross alpha and gross beta readings were similar to or slightly higher than the previous years as indicated in the summary of 1997 {

and 1998 averages below but are within normal yearly fluctuations.

]

1997 1998 Average pCi/ liter Average poi / liter i

Gross Alpha 3.1 4.5 (dissolved)

Gross Alpha 1.7 2.7 (suspended)

Gross Beta 9.8 9.4 (dissolved)

Gross Beta 4.6 7.6 (suspended)

Figure I-1, which follows, is a plot of the gross alpha and gross beta of suspended and dissolved particles. The levels of activity continued to rise ,

and fall within statistical limits depending on water levels and turbulence l and were probably due to naturally occurring isotopes. No fission or reactor ;

activation products were detected. Figure I-2 illustrates the level of activity '

for tritium, Sr-89 and Sr-90. ;

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l J. AMBIENT RADIATION - THERMOLUMINESCENT DOSIMETERS (TLDs - See Tables J-1 AND J-2)

STATIONS 01-10, 20.44. 56. 58. 59. 66. 67. 71.79-91. 94 Ambient radiation was monitored at 32 locations within a 10 mile ra-dius of CNS and collected quarterly. The quarterly averages for all stations of ambient net gamma radiation ranged from 17.0 milliroentgen / quarter to 21.0 milliroentgen / quarter. The highest exposure during each of the four quarters was at Station 66 (4.4 miles, 297 degrees) and averaged 20.5 mR/ quarter. The lowest exposure was at Station 91 (2.5 miles, 338 degrees) averaging 16.6 milliroentgen / quarter.

The radiation at station 44, (10.5 miles, 270 degrees) which is the control station, was an average of 20.0 mR/ quarter. This was similar to other stations and to the average of all stations which was 18.3 mR/ quarter.

The relationship between milliroentgen (mR) and millirems (mr) is approximately one for the exposure conditions encountered. No plant effect from CNS was indicated.

The gamma exposures monitored by thermoluminescent dosimeters from 1977 through 1998 are plotted on Figure J-1. The data from year to year is in good agreement and indicates no adverse changes in radiation ex-posure to the population near CNS.

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Broadleaf vegetation was collected each month from July through September for Station 28 and from July through August for Stations 81 and 101. No samples were available for Station 35. The samples were tested for i

' I-131 by chemical separation and for gamma emitting isotopes by high resolution spectrometry.

The naturally occurring isotopes Be-7 and K-40 were detected in the l samples at normal environmental levels. No I-131 was detected in any of the 20 samples. No Cs-137 was detected. Cesium-137 is detected in other areas l of the United States and is attributed to fallout from previous atomic weapons i testing.

See Figure K-1 for the levels of activities in food samples as repre-sented in broadleaf vegetation in 1998.

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L SHORELINE SEDIMENT STATIQH_16 Shoreline sediment samples were collected in the spring and fall from Station 28,1.8 miles,150 degrees downstream of the release point of CNS.

hey were analyzed for gamma emitters by means of a high resolution gamma spectrometer. In the samples collected the naturally occurring isotopes Be-7, K-40, Ra-226 and Th-228 were detected at normal environmental levels.

Cesium-137, a fission product, was detected at an average level of 0.027 l

PCi/gm, dry, i Potassium-40 was detected at 14.4 pCi/gm, dry in the second quarter and 9.9 pCi/gm dry in the fourth quarter. Radium-226 was detected at about the same level in the fourth as in the second quarter. Thorium-228 had an average level of 0.63 pCi/gm dry for the year. Beryllium-7 was detected at a level of 0.19 pCi/gm dry for the year. Manganese-54, an activation product, was detected at a level of 0.013 pCi/gm dry in the second quarter, but was below the detection limit in the fourth quarter. All other nuclides were below the detection limit for both the spring and fall.

Presented in Figure L-1 are the plots of the radionuclides K-40, I-131, Cs-134 and Os-137 in shoreline sediment since 1985. No detections of I-131 nor Cs-134 were seen and K-40 was at a normal environmental level.

He Cs-137 was at a low level which is found in many areas and media. Since sediment tends to trap and retain any elements in the water pathway, it acts as a good indicator of the effects on the water pathway of any reactor efflu-ents.

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REFERENCES

1. Nebraska Public Power District, Cooper Nuclear Station Environmental Radiation Monitoring Program, Annual Report, January 1, 1982-December 31,1982 (prepared by Teledyne Isotopes).

2. Nebraska Public Power District, Cooper Nuclear Station Environmental )

Radiation- Monitoring Program, Annual Report, January 1, 1983-December 31,1983 (prepared by Teledyne Isotopes).

1

3. Nebraska Public Power District Cooper Nuclear Station, Environmental I Monitoring Program, Annual Report, January 1,1984 to December 31, 1984. (Prepared by Teledyne Isotopes).

4. U.S. Department of Energy; EML 440 March 1985; EML-444 April 1989; Environmental Measurements Laboratory, US Department of Energy, New York, New York 10014.

5. U.S. Environmental Protection Agency; Environmental Radiation Data, Report 35, July -- September 1983, Report 39, July -- September 1985; Report 40, October -- December 1984; Report 41, January -- March 1985. Report 42, April -- June 1985: Report 43, July-September 1985, Report 44-45 October-March 1986; Report 46 April-June 1986; Report 47, July-September 1986; Report 48, October-December 1986; Report 49, January-March 1987. Environmental Radiation Facility, Montgomery, Alabama.

6. U.S. Department of Energy; EML 460. October 1,1986; Environmental Measurements Laboratory, US Department of Energy, New York, New l York 10014.

7. U.S. Nuclear Regulatory Commission,1975. Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants.

187

APPENDIX i

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l APPENDZX A Y OY W USE CENSUB 1

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y

)

CNS ANNUAL LAND USE CENSUS July 29,1998 0-3 Miles l

l The Cooper Nuclear Station (CNS) Offsite Dose Assessment Manual (ODAM) requires that an annual land use census be conducted. This census identifies the location of the nearest garden that is greater than 500 square feet in area and yields leafy green vegetables, the nearest milk animal, and the location of the nearest resident in each of the 16 meteorological sectors within three miles of CNS.

In accordance with CNS ODAM, a land use census was performed on July 29,1998. The nearest residence to CNS is in sector 'Q',0.9 miles from CNS. The nearest garden to CNS is in sector l

'L',1.3 miles from CNS.

No milk animals were found within 3 miles of CNS in 1998, and there was no evidence of potable water use noted from the Missouri River within three miles downstream of CNS.

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A-1 l

1 CNS ANNUAL LAND USE CENSUS July 29,1998 0-3 Miles SECTOR NEAREST RESIDENT DIRECTION NEAREST GARDEN DIRECTION MII.K ANIMAL A 3.0 Miles 1.0* 3.0 Miles 1.0* NONE B 2.7 Miles 13.0* NONE --

NONE C NONE --

NONE --

NONE D 1.7 Miles 62.0* 2.8 Miles 69.0* NONE E 1.8 Miles 94.0* 1.8 Miles 94.0* NONE F 2.3 Miles 112.0* 2.3 Miles 112.0* NONE G NONE --

NONE --

NONE H NONE --

NONE --

NONE J NONE --

NONE --

NONE K 2.2 Miles 210.0* NONE --

NONE L 1.3 Miles 221.0* 1.3 Miles 221.0* NONE M 1.2 Miles 253.0* NONE --

NONE

'N 1.0 Miles 267.0* NONE --

NONE P 1.6 Miles 294.0* 2.8 Miles 298.0* NONE Q. 0.9 Miles 307.0* 2.9 Miles 314.0* NONE R J.3 Miles 338.0* 1.9 Miles 338.0* NONE A-2 l

\

APPENDIX 3 I E M ORATORY COMPARISON PROGRAM l

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e B-1

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r 1998 A summary of the Results of the Analyses by Teledyne Brown Engineering -

Environmental Services of the EPA and Analytics, Inc. Cross Check Samples Compared with the Known Activity as reported by the Environmental !

Monitoring Systems Laboratory, las Vegas, Nevada and Analytics, Inc.

All results which exceed three sigma deviation from the known are ap-pended with a note giving the possible cause of the deviation and corrective action taken.

I L.--

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l EPA INTERLABORATORY COMPARISON PROGRAM 1998 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) 01/16/98 Water Sr-89 8.0 2 5.0 5.00 1.73 -1.04 Sr-90 32.0 2 5.0 31.67 0.58 -0.12 01/30/98 Water Gr-Alpha 30.5 2 7.6 33.00 2 2.65 0.57 Gr-Beta 3.9 5.0 5.60 2 0.90 0.59 02/06/98 Water I-131 104.9 2 10.5 110.00 e 0.00 0.84 02/13/98 Water Ra-226 16.0 2.4 14.67 0.58 -0.96 Ra-228 33.3 8.3 32.00 2.00 -0.27 03/13/98 Water H-3 2155.0 348.0 1833.33 57.74 -1.60 04/21/98 Water Gr-Alpha 54.4

13.6 50.00 2 1.73 -0.56 Ra-226 15.0 2 2.3 15.00 0.00 0.00 Ra-228 9.3 2 2.3 8.50 z 0.20 -0.60 Gr-Beta 94.7 10.0 102.00 2 6.56 1.26 Sr-89 6.0 5.0 4.67 T.15 -0.46 Sr-90 18.0 z 5.0 21.67 1.15 1.27 Co 60 50.0 z 5.0 52.33 z 1.53 0.81 Cs-134 22.0 2 5.0 21.00 1.00 -0.35 Cs-137 10.0 5.0 11.67 2 0.58 0.58 06/05/98 Water Co-60 12.0 z 5.0 13.00 1.00 0.35 Zn-65 104.0 2 10.0 111.67 2.52 1.33 Cs-134 31.0 5.0 32.33 0.58 0.46 Cs-137 35.0 2 5.0 37.67 2.08 0.92 Ba-133 40.0 2 5.0 35.00 2.65 -1.73 06/12/98 Water Ra-226 4.9 0.7 4.47 0.85 -1.07 Ra-228 2.1 0.5 1.93 0.21 -0.58 07/17/98 Water Sr-89 21.0 5.0 21.00 1.00 0.00 Sr-90 7.0 2 5.0 6.33 2 0.58 -0.23 07/24/98 Water Gr-Alpha 7.2 z 5.0 5.43 0.64 -0.61 Gr-Beta 12.8 2 5.0 14.67 2.08 0.65 08/07/98 Water H-3 17996.0 e 1800.0 16000.00 0.00 -1.92 09/11/98 Water 1-131 6.1 2 2.0 5.93 0.55 -0.14 09/18/98 Water Ra-226 1.7 0.3 1.53 2 0.46 -0.96 Ra 228 5.7 2 1.4 6.70 z 0.35 1.24 10/20/98 Water Gr-Beta 94.0 2 10.0 74.67 2 7.64 -3.35 (d)

Sr-89 19.0 5.0 18.33 2 1.53 -0.23 Sr-90 8.0 5.0 8.33 1.15 0.12 Co-60 21.0 2 5.0 22.33 2 1.15 0.46 l Cs-134 6.0 5.0 6.67 0.58 0.23 Cs-137 50.0 2 5.0 56.33 3.79 2.19 (e)

EPA INTERLABORATORY COMPARISON PROGRAM 1998 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) 10/20/98 Gr-Alpha 30.1 7.5 21.67 2.31 -1.95 Ra-226 4.5 0.7 4.67 e 0.25 0.41 Ra-228 1.5 2 0.4 1.9 0.20 1.73 11/11/98 Water Co-60 38.0 2 5.0 39.67

2.52 0.58 Zn-65 131.0 13.0 140.67 e 10.97 1.29 Cs-134 105.0 2 5.0 103.00 e 2.00 -0.69 Cs-137 111.0 6.0 115.33 2 1.53 1.25 Ba-133 56.0 6.0 46.33 e 2.52 -2.79 (d)

Footnotes:

(a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters.

(b) Teledyne Results - Average 2 one sigma. Units are pCi/ liter for water ano milk except K is in mg/ liter. Units are total pCi for air particulate filters.

(c) Normalized deviation from the known.

(d) The special EPA instructions concerning multiple evaporation with concentrated nitric acid (to purge chlorides derived from hcl preservative) were omitted by oversight. The chlorides cause greater self absorption and lead to lower results. Two additional aliquots using two evaporations with concentrated nitric acid were analyzed. The results, when corrected for decay of Sr-89, were 87 and 83 pC1/ liter which compare favorably with the EPA result.

(e) An investigation is being conducted; results will be available shortly.

l ANALYTICS CROSS CHECK COMPARISON PROGRAM 1998 !

! Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a) Result Ratio (b) ,

E1346-396 Milk I-131 87 9 82 4 1.06 TI#71657 Ce-141 66 2 7 70 4 0.94 03/12/98 Cr-51 220 30 201 10 1.09 Cs-134 85 9 84 2 4 1.01 Cs-137 180e 20 1612 8 1.12 Mn-54 130 10 133 7 0.98 Fe-59 110e 10 95 5 1.16 Zn-65 160 20 1422 7 1.13 CO-60 82 2 8 85 4 0.96 E1460-396 Milk I-131 68 m 7 67 2 3 1.01 TI#78921 Ce-141 94 1 9 99 5 0.95 06/11/98 Cr-51 97 31 132 7 0.73 Cs-134 101 10 95 2 5 1.06 Cs-137 79 8 70 4 1.13 Mn-54 112 11 106 2 5 1.06 Fe-59 58 2 9 45

2 1.29 Zn-65 143 14 122 6 1.17 CO-60 157 16 143 7 1.10 E1630-396 Milk I-131 65 2 1 71 4 0.92 TI#94881 Cc-141 647 65 746 37 0.87 12/14/98 Cr-51 900 90 9792 49 0.92 Cs-134 200 20 220 11 0.91 Cs-137 177 18 183 9 0.97 l Mn-54 136 14 1422 7 0.96 Fe-59 1562 16 1482 7 1.05 Zn-65 132 14 140 7 0.94 CO-60 169 17 178 9 0.95 Sr-89 20 2 69 3 0.29 (c)

Sr 90 16 2 1 41 2 0.39 (c)

E1631-396 Filter Ce-141 5662 57 524 26 1.08 TI#94882 Cr-51 8002 80 687 49 1.16 12/14/98 Cs-134 1472 15 154 8 0.95 Cs-137 1582 16 128 6 1.23 Mn 54 122 12 100 5 1.22 Fe-59 134 13 104 5 1.29 Zn-65 129m 13 98 2 5 1,32 CO-60 134 13 125 6 1.07 E1632-396 Water H-3 5500 200 5980 299 0.92 TI#94883 12/14/98 E1633-396 Water Am-241 8.3 2 1.5 7.9 e 0.4 1.05 T1#94884 Pu-239 9.8 2 1.8 8.9 0.4 1.10 12/14/98

Footnotes:

-(a) Teledyne Results - counting error is two standard deviations. Units are pCi/ liter for water and milk. For gamma results, if two standard deviations are less than 10%, then a 10% error is reported. Units are total pCi for air particulate filters.

(b) Ratio of Teledyne Brown Engineering to Analytics results. Acceptance criteria are based on USNRC acceptance criteria described in USNRC Procedure 84750 dated March 15,1994.

(c) An investigation is being conducted; results will be available shortly.

i

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APPENDIX C l l

i STATISTICAL NOTES l 1

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APPENDIX C STATISTICAL NOTES

1. Each activity is' reported in one of two forms:

x i s or l

<L, where x = value of measurement; s = counting error at the 95%

confidence level (2 sigma error);

L = detection limit based on 4.66 sigma error for counter background l 2. All activities are corrected to collection time except for gross alpha and gross beta.

3. Computation of means:

(a) In any statistical table, the values are entered as xis or <L where x = sample mean = Ex; n

n = number of data points averaged; s = average of the 2 sigma counting errors = Is n

(b) For gross beta ana gross alpha results in air particulates, averaging includes values which are less than the lower limits of detection.

, The detection limit is used as the sample activity in these cases.

1 (c) In all cases, if all values in an averaging group are below detec-tion limits, the highest of the detection limits is reported as a "less than" value without an associated tolerance. If some values are above detection limits and some are below, then:

C-1

1 l

l i

(1) The mean of the positive results is reported and the number l l of positives is listed in parentheses.

(d) Means are reported on a quarterly basis except for air particulate l and airborne iodine data which are reported monthly. For air i i

particulate and charcoal filters, data for samples collected on the 1

i Ist, 2nd, and 3rd day of a month are assigned to the previous month.

(e) In rounding off, numbers followed by a 5 or higher digit are rounded ;

upwards.

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Appendix 0 Notification Levels 9

NEBRASEA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION ENVIRONMENTAL RADIATION SURVEILIANCE PROGRAM NOTIFICATION LEVELS l

l Media and Nuclide Notification Level Air Gross Alpha . . . . . . . . . .

Gross Beta. ... .. . . . . . ........... 0.1 pCi/m 3 I-131 . . . ..... . . . . .

........... 1.0 pCi/m 3 Cs-134 . . ..... . . . . . ........... 0.31 pCi/m 3 Cs-137 . . .. . . . . . . . . ........... 3.3 pCi/m 3

........... 6.7 pCi/m 3 Milk I-131 (low level) .. . . . . . 1.09 pCi/1 Sr-89 . . . .... . . . . . . ...........

Sr-90 . .. ... . . . . . . . ........ ........... 6.04 pCi/1 Cs-134 ..... . . .. . . . ... 14.82 pCi/1 Cs-137 ........... 20.0 pCi/1

.. .... . . . . . . ........... 23.0 pCi/1 Croundwater Cross Alpha . . . . . . . . . .

Cross Beta. .. . .. . . . . . ........... 12.0 pCi/1

{

H-3 . . .. ... .. . . . . . ............ 33.8 pCi/1 Mn-54 . .......... 6700 pCi/1 !

Fe-59 . .. . . ... . . . . . . . .. ......... 330 pci/1

... . . . . . . . ......... 130 Co-58 . . . ... . . . . . . . ........... .. pCi/1 Co-60 . .. ... .. . . . . . 330 pCi/1 2n-65 . . . ... . . . . . . .

........... 100 pCi/1 l

Zr-Nb-95 . .. . . . . . . . . ........ ... 100 pCi/1 ;

I-131 . . . ... . . . . . . .

........... 67 pCi/1 Cs-134 . .... . . . . . . . .........

........... 0.67 pCi/1 Cs-137 .........

.. 10 pCi/1

. . . . .......... 17 pC1/1 Ba -La - 140 .

... .. . . . . . . ........ .. 67 pCi/1 Food Products I-131 ..

Cs-134 . . ...

. . .... .. .. ... .. .. .. . . . . . . . . . . . 0.1 pCi/g vet Cs-137 .. ....... . . . .

.......... 0.33 pCi/g vet

.......... 0.66 pCi/g vet Fish Cross Beta. ....... . . . .

Sr-89 . . . ....... . . . .

.......... 10.8 pCi/g vet

.......... 3.3 pCi/g vet Sr-90 . . . . . . ... . . . . . .

Mn-54 . . ......... ........ 1.2 pCi/g wet

. . . .......... 10 pCi/g wet D-1

Media and Nuclide Notification 1.evel Fish (Continued)

Fe-59 . . . . . . . . . . . . . . . . . . . . . . . .

Co-58 .

3.3 pCi/g vet Co-60 .

....................... 10 pCi/g vet En-65 . ....................... 3.3 pCi/g wet Cs-134

....................... 6.7 pCi/g vet Cs-137

....................... 0.33 pCi/g vet

....................... 0.67 pCi/g vet.

River Vater Cross Alpha sus . .

Cross Alpha Dis . .................. 22.0 pCi/1 Cross Beta Sus. ..... 27.6 pCi/1

............. 58.8 pCi/1 Gross Beta Dis. ................... 88.6 Sr-89 . pCi/1 Sr-90 .

....................... 1000.0 pCi/1 H-3 . ......... 100.0 pci/1

...........s . . . . 6700 pCi/1 Mn-54 . .....

............... . . . 330 pCi/1 Fe-59 . .................... 130 Co-58 . .....................

. . . pCi/1

. . 330 pCi/1 Co-60 . .................... .. . 100 pCi/1 Zn-65 . ............... . . . .. . . . 100 pCi/1 Zr-Nb-95 ...............

67 pCi/1 I-131 . . . . . . . . . . . . . . . . . .. .. ... .. .. .. .

Cs-134 0.67 pCi/1 Cs-137

....................... 10 pCi/1 Ba-14-140 .

17 pCi/1

..................... 67 pCi/1 Shoreline Sediment

I I

Co-60 . .......................

Cs-134 0.1 pCi/g dry

............... . . . .. . . . 0.75 pCi/g dry Cs-137 ................. . .. . .. 0.75 pCi/g dry ,

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l APPENDIX E i

CONVENTIONS USED !

i IN l

DATA TREND GRAPHS l

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[

APPENDIX E Conventions used in Data Trend Graphs

1. The data trend plots are based on statistical summaries of Section VI.

2. Monthly or quarterly averages are plotted.

3. The conventions used to determine if a "less than" (<).value or detectable result is plotted are those given in Appendix C.

4. Lowest levels of detection (LLD) are noted by a straight line on the graphs.

5. A typical less-than value arising from delayed counting of short-

-lived isotopes (such as I-131 or Ba-140) or reduced sample size are omitted.

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APPENDII F DETECT 10tl CAPABILITIES N-

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n on ca e o u s i dq m s st n u '

t a ud ct ue

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dn gs n L w i oe g g 5 ki cl M e rV 0 - a s P

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h da Cp o e t oe ol ( h ef l p

Fd a td e e m s o f i a a r of s e B r nc i e c oe h t

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n l S

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2 3 3

u a ei S Y ( m f lpys E Ls oi -

0 0 0 0 - -

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T No t t r 8 0 d

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s na L P ae Ee t t p v n I

B LMe F D r s i e ia A

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A RAa o D hn c a i f C F ci OS L t u t Lm t L o n p5 N

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i t

. t . t l c p n yll afc i t i t W t W 9 0 t 1 i t aade e n n 8 9 n 3 et m eiit hh ccebn i a h a h - - a 1 3 Dt ge e p p sl d u s

u s r r u - -

L i h r y yi l o Q A 'a p Q A S S Q I H Lf eThTTLi I

" o wb t* d

wr 7

'LLD = lower limit of detection based on 4.66sw & where sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as apprdpriate (as counts per minute). The LLD is at counting time and must be corrected to collection time. The LLDs given above are based on the quantities indicated and the background count rate in the absence of any radionuclides in the sample. In calculating the LLD for a radionuclide determined by I

gamma-ray spectrometry, the background shall include the !

typical contributions of other radio-nuclides normally present in the samples (e.g., potassium-40 in milk samples). !

l l

Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachlevable. In such cases, the contributing factors will be identified and described in the Environmental Radiation Monitoring Program Annual Report. ,

Note:All LLD's which we require are listed in this table for Ge(Li) Gamma Spectroscopy. If any nuclide is detected, it shall be reported quantitatively whether or not it is ;

one of the 20 nuclides listed above. {

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1 l

APPENDIZ G l SAMPLE STATIOM LOCATIONS AND SAMPLE TYPES l

1 1

COOPER NUCLEAR STATION LIST OF ACTIVE SAMPLE STATIONS 1998 Sample Station" Samole Descriotion -- Tvoe and Location No.1 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Outside the nonhwest edge of fence, east of the gate to the LLRW storage pad l on the CNS site, NWl/4, S32, T5N, R16E, Nemaha County, Nebraska. l No. 2 Type: (1) Air Particulate and Charcoal Filters 3

(2) Environmental Thermoluminescent Dosimetry l Location: North side of county road access to the south portion of CNS site approximately 275 feet west of the former Jefferson Broady farmstead, SWl/4, S32, T5N, R16E, Nemaha County, NE.

No. 3 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Located on the nonh side of the Brownville State Recreation Park access road near water gauging station, SEl/4, S18, T5N, R16E, Nemaha County, Nebraska.

1 No. 4 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thennoluminescent Dosimetry Location: Located 1/2 mile south of Phelps City, Missouri, on west side of Highway "U", NEl/4, S2, T64N, R42W, Atchison County, Missouri.

No. 5 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Located 1/4 mile south and 1/4 mile east of Langdon, Missouri, on north side of road, west of railroad tracks, SWl/4, S18, T64N, R41 W, Atchison County, Missouri.

G-1

E 1 l

Sample Station Samole Descriotion -- Tvoc and Location

)

No. 6 Type: (1) Air Particulate and Charcoal Filters I (2) Environmental Thermoluminescent Dosimetry Location: One mile west of the end ofMissouri State Highway "U", south side of road, SW corner of the intersection,NW1/4, S34, T64N, R42 W, Atchison County, Missouri.

No. 7 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: 300 yards east of Highway 67 on north side of road, west of Nemaha elevator, i SWl/4, S6, T4N, R16E, Nemaha County, Nebraska.

1 No. 8 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: 1/2 mile north,3/4 mile west and 3/4 mile north of Nemaha, on west side of

{

road adjacent to Mark T. Moore Transmission Line, NEl/4, S35, T5N, R1 SE, Nemaha County, Nebraska.

No. 9 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry l Location: Four miles north of Highway 136, on Highway 67. Then 1 mile east of Highway 67 and 1/2 mile north on west side of road, SWl/4, S26, T6N, RI5E, Nemaha County, Nebraska.

i No.10 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry '

Location: One mile north of Barada, Nebraska, in SW corner ofintersection, NEl/4, S14, T3N, R16E, Richardson County, NE.

No. I1 Type: (1) Water - Ground Location: Plant well water supply header at well pits, NWl/4, S32, T5N, R16E, Nemaha County, Nebraska.

l l

G-2

1 l Sample Station Samole Descriotion -- Tvoe and Location No.12 Type: (1) Water - River Location: Sample (1) is taken from the Missouri River immediately upstream from the Plant Intake Structure (River Mile 532.5). (During periods when unsafe l conditions warrant, Station 35 may be used as an alternate upstream i

collection site.)

No. 20 Type: (1) Environmental Thermoluminescent Dosimetry Location: On NNW boundary of NPPD property, approximately 20 yards east of county road, SEl/4, S30, T5N, R16E, Nemaha County, NE. ,

1 l

No. 28 Type: (1) Water- River I (2) Fish (3) Sediment from Shoreline (4) Food Products - Broadleaf Vegetation Location: Samples (1) and (3) are taken from the Missouri River or its shore, below the Plant Discharge Flume near River Mile 530. Sample (2) is taken from the l

Missouri River 1/2 to 3 miles downstream of the plant site.

No. 3S Type: (1) Fish (2) Water- River (Alternate Site)

(3) Food Products - Broadleaf Vegetation i Location: Sample (1) is taken from the Missouri River about I to 3 miles above the CNS intake structure. Sample (3) is taken about 1/4 mile south of the Brownville State Recreation Area in Sector A. During periods when unsafe conditions warrant, Station 35 may be used as an alternate to Station 12 for sample type (2).

No. 42 Type: (1) Milk-Other Producer Location: One mile south,1-1/4 miles east of Barada, Nebraska, south side of county ,

road, NWl/4, S30, T3N, R17E, Richardson County, Nebraska.

No. 44 Type: (1) Environmental Thermoluminescent Dosimetry Location: Two miles south of Auburn stoplight and 1/4 mile south of Auburn Country Club on Highway 75, then 1/2 mile east of Highway 75 at fence line north of county road, SEl/4, S27, T5N, R14E, Nemaha County, Nebraska.

l l

G-3 i

u

Sample Station Samole Description -- Tvoc and Location No. 47 Type: (1) Water - Ground Location: At Falls City municipal water supply well south of Rulo, Nebraska, out of main header flow meter, SWl/4, S20, TIN, R18E, Richardson County, Nebraska.

No. 56 Type: (1) Environmental Thermoluminescent Dosimetry Location: 1-1/4 miles SW of Langdon, Missouri, on Highway "U", on the right side of the highway (Bill Gebheart farm), NWl/4, S23, T64N, R42W, Atchison County, Missouri.

No. 58 Type: (1) Environmental Thermoluminescent Dosimetry Location: Three miles south of Brownville, Nebraska, on county road, at the SE corner of the intersection with the farm road leading to Sample Station No. 2, SEl/4, S31, T5N, R16E, Nemaha County, Nebraska.

No. 59 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile SSE of the CNS Elevated Release Point,50 ya:ds west of the levee at the south boundary of NPPD property, SEl/4, S32, T5N, R16E, Nemaha County, Nebraska.

No. 61 Type: (1) Milk - Nearest Producer l Location: One mile west of Brownville, Nebraska, on Highway 136, then 1 mile north on the county road, turn right and proceed approximately 1/2 mile east, on south side of road (Raymond Gentert dairy), NWl/4, S13, T5N, RISE, Nemaha County, Nebraska. l l l l No. 66 Type: (1) Environmental Thermoluminescent Dosimetry l Location: Two miles south of Nemaha, Nebraska, on Highway 67 - east side of road l l (Mrs. Lola Kennedy farm), NWl/4, S19, T4N, R16E, Nemaha County, !

Nebraska.

l No. 67 Type: (1) Environmental Thermolominescent L 3simetry Location: 2 miles west of Brownville, Nebra3Ka, on Highway 136, then north 1-1/2 l miles on county road and east 1/2 mile, on north side of road (Walter Parkhurst farm), NEl/4, S11, T5N, RISE, Nemaha County, Nebraska. l G-4

Sample Station Samole Description -- Tvoc and Location i 'No.71 Type: (1) Environmental Thermoluminescent Dosimetry Location: Two miles east of Phelps City, Missouri, on Highway 136, then south 1-1/2 l

' miles on county road and west 1/4 mile (Tom Boatman farm), SEl/4, S6, T64N, R41W, Atchison County, Missouri.

No. 79 Type: (1) Environmental Thermoluminescent Dosimetry Location: 1-7/8 miles south of Brownville, NE, on east side of paved road, NPPD-propetty, SEl/4, S30, T5N, R16E, Nemaha County, NE.

No. 80 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2-1/8 miles south of Brownville, east side of paved road, NPPD property, NEl/4, S31, T5N, R16E, Nemaha County, Nebraska.

No. 81 Type: (1) Environmental Thermoluminescent Dosimetry (2) Food Products - Broadleaf Vegetation (extra site)

Location: 2-3/8 miles south of Brownville, Nebraska, in the NE corner of the intersection of the paved county road and CNS access road, NPPD property, NEl/4, S31, T5N, R16E, Nemaha County, Nebraska.

i No. 82 Type: (1) Environmental Thermoluminescent Dosimetry 1

Location: 7/8 mile south of CNS in a field, on NPPD property, SWl/4, S32, T5N,

, R16E, Nemaha County, Nebraska.

No. 83 Type: (1) Environmental Thermoluminescent Dosimetry i

Location: 2-1/4 miles south of Nemaha, Nebraska, on Highway 67, then east 1 mile to the junction of the driveway and county road (east side of drive, Leroy

' Kennedy), NEl/4, S19, T4N, R16E, Nemaha County, Nebraska.

No. 84 Type: (1) Environmental Thermoluminescent Dosimetry l

Location: 2-1/2 miles west of Brownville, Nebraska, south side of Highway 136 west of Locust Grove School (Bruce L. Solie), NWl/4, S22, T5N, R1 SE, Nemaha County, Nebraska.

No. 85 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile east of Brownville, Nebraska, on Highway 136, then north 1/4 mile on the east side of the county road (Scott Leseburg), NEl/4, S33, T65N, R42W, Atchison County, Missouri.

G-5 I

Sample Station Sample Description -- Tyne and Location No. 86 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile west of Phelps City, Missouri, on liighway 136, then north 1-1/2 miles on liighway "D" on west side (Mrs. Olin Harmes), SEl/4, S22, T65N, R43W, Atchison County, Missouri.

No. 87 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile west of Phelps City, Missouri, on liighway 136, south 1/2 mile on county road and 3/4 mile west on county road (to end of road, Robert Graf),

SWl/4, S3, T64N, R42W, Atchison County, Missouri.

No. 88 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile west of Phelps City, Missouri,on liighway 136, then south 2 miles at the end of the county road (David Meyerkorth), NWl/4, Sll, T64N, R42W, Atchison County, Missouri.

No. 89 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2-1/2 miles south of Phelps City, Missouri, on liighway "U", then 1/2 mile west in the SE corner of the county road intersection (Gertrude Rosenbohm), l NEl/4, S14, T64N, R42W, Atchison County, Missouri. I No. 90 Type: (1) Environmental Thermoluminescent Dosimetry Location: 1-1/2 miles west and 3/4 mile south of Langdon, Missouri,on liighway "U", ,

then 1/4 mile west (Garth Green), SWl/4, S23, T64N, R42W, Atcluson !

County, Missouri. I No. 91 Type: (1) Environmental Thermoluminescent Dosimetry Location: 1/2 mile west of Rock Port, Missouri, on the south side of the intersection of liwy.136 and IIwy. 275, at the water tower (Richard II. and Vicki Cook),

NWl/4, S28, T65N, R41W, Atchison County, Missouri.

No.94 Type: (1) Environmental Thermoluminescent Dosimetry Location: 1/4 mile south of Langdon, Missouri, on the west side of the road (Max Peeler), NEl/4, S24, T64N, R42W, Atchison County, Missouri.

G-6

I Sample l Station Samnie Description -- Type and Location i

No. 96 Type: (1) Food Products - Broadleaf Vegetation Location: Approximately 1 mile south of Brownville, Nebraska, along the paved road, in the road ditch in Sector R, SWl/4, S19, T5N, R16E, Nemaha County, Nebraska.

No. 99 Type: (1) Milk (Nearest and Other Producer) l Location: 1 -1/4 miles south of Shubert, Nebraska, west side of Hwy. 67 (James Zentner dairy), NEl/4, S24. T3N, R15E, Richardson County, Nebraska.

No.100 Type: (1) Milk (Other Producer)

Location: Two miles south and 1 mile west of Shubert, Nebraska (Dick James daity),

SWl/4, S23 T3N, R15E, Richardson County, Nebraska.

No.101 Type: (1) Food Products - Broadleaf Vegetation Location: 5-1/2 miles east and 1/2 mile north of Rock Port, Missouri, near thejunction of Highway 136 and Highway 59, in Sector D, encompasses portions of S19 and S30, T65N, R41W, Atchison County, Missouri.

NOTES: N Sample Station numbers missing from the sequence are inactive or discontinued Sample Stations.

l l

l 1

l l

G-7 a

1 i

APPENDIX H

SUMMARY

OF DOSES TO A MEMBER OF THE PUBLIC OFF-SITE j i

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ML20206S497

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