Text

Annual Radiological Environmental Operating Report
	ML021410085
Person / Time
Site:	Cooper
Issue date:	05/15/2002
From:	Denise Wilson; Nebraska Public Power District (NPPD)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NLS2002054
	Download: ML021410085 (150)
	v • d • e

H Nebraska Public Power District Nebraska's Energy Leader NLS2002054 May 15, 2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Annual Radiological Environmental Operating Report Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 The purpose of this letter is to submit the Cooper Nuclear Station (CNS) Annual Radiological Environmental Operating Report for the period of January 1, 2001, through December 31, 200 1.

The enclosed report is being submitted in accordance with CNS Technical Specification 5.6.2.

Per 10 CFR 50.4(b)(1), we are enclosing one copy of the report for your use, one copy to the Regional Office and one copy to the NRC Senior Resident Inspector.

Should you have any questions regarding this submittal, please contact me at 402-825-2760 or Paul V. Fleming, Acting Risk and Regulatory Affairs Manager, at 402-825-2774.

Sincerely, David L. Wilson Vice President - Nuclear

/dnm Enclosure cc: Regional Administrator w/enclosure USNRC - Region IV Senior Project Manager w/enclosure USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/enclosure USNRC - Cooper Nuclear Station NPG Distribution w/o enclosure Records Cooper Nuclear Station P.O. Box 98/ Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 http://www.nppd.com

I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS Correspondence Number: NLS2002054 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 for information only and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE N/A None 4

.4 I PROCEDURE 0.42 1 REVISION 10 1 PAGE 11 OF 14 1

NEBRASKA PUBLICPOWER DISTRICT COOPER NUCLEAR STATION RadiologicalEnvironmentalMonitoringProgram 2001 Annual Report January1, 2001 to December 31, 2001 Approved by Keith Jeter 6 LaboratoryDirector Prepared by Teledyne Brown Engineering 2508 Quality Lane Knoxville. TN 3 7931-3133

TABLE OF CONTENTS SECTION TITLE PAGE Preface ....................................................................................................... 6 I. Introduction .......................................................................................... 7 II. Sum m ary ............................................................................................ 10 III. Sampling and Analyses Program ...................................................... 12 IV. Summary and Discussion of 2001 Analytical Results ........................ 16 A . A irborne Particulates ................................................................... 17 B. A irborne Iodine ............................................................................. 18 C. Fish ............................................................................................... 18 D . M ilk - N earest Producers ................................................................. 18 E. M ilk- Other producer ................................................................. 21 F. Ground W ater ............................................................................... 21 G . River W ater ................................................................................. 21 H . Therm olum inscent D osimeters .................................................... 29 I. Food - Broadleaf V egetation ...................................................... 29 J. Shoreline Sedim ent ...................................................................... 29 V. Conclusions ........................................................................................ 32 V I. Radiological Environm ental M onitoring ........................................... 34 Program Summary Table - 2001 V II. Com plete Data Tables ........................................................................ 41 V III. References ............................................................................................. 100 2

TABLE OF CONTENTS (Cont)

APPENDICES APPENDIX A - 2001 Land Use Census ...................................................... A-1 APPENDIX B - Summary of Interlaboratory Comparisons ......................... B-1 APPENDIX C - Synopsis of Analytical procedures ...................................... C-1 APPENDIX D- Detection Limits and Reporting Levels ................................ D-1 APPENDIX E - REMP Sampling and Analytical Exceptions ....................... E-1 APPENDIX F - Summary of Doses to a Member of the Public Offsite ...... F-1 APPENDIX G - REMP Sample Station Descriptions .................................. G-1 LIST OF FIGURES

1. M ap of Sam pling Stations ..................................................................... 15 3

TABLE OF CONTENTS (Cont)

LIST OF TRENDING GRAPHS

1. Gross Beta in Air Particulates - CNS .................................................... 19

2. C esium -137 in Fish ............................................................................... 20

3. Iodine-131 and Cesium-137 in Milk - Nearest Producer ..................... 22

4. Iodine-131 and Cesium-137 in Milk - Other Producers ....................... 23

5. Tritium in Ground Water ...................................................................... 24

6. Tritium in River W ater ........................................................................... 25

7. Thermolum inescent Dosimetry ............................................................. 26

8. Iodine- 131 and Cesium- 137 in Food - Broadleaf Vegetation ............... 27

9. Iodine-131, Cesium-134, and Cesium-137 in Shoreline Sediment ..... 31 4

TABLE OF CONTENTS (Cont)

LIST OF TABLES I Sampling Schedule and Analysis .................................................... 14 VII-1 Gross Beta In Air Particulates ......................................................... 42 Iodine in Charcoal Filters VII-2 Gamma Emitters in Quarterly ......................................................... 62 Air Particulate Samples V II-3 Gross Beta, Strontium .................................................................... 72 Gamma Emitters in Fish VII-4 Strontium, Iodine- 131, CA ............................................................ 74 Gamma Emitters in Milk - Nearest Producers VII-5 Strontium, Iodine- 131, CA ............................................................ 78 Gamma Emitters in Milk - Other Producers VII-6 Gross Alpha, Beta, Iodine-131 ........................................................ 80 Gamma Emitters in Ground Water VII-7 Gross Alpha, Beta, londine- 131 ...................................................... 82 Gamma Emitters in River Water VII-8 Direct Radiation Measurements ....................................................... 88 TLD Results VII-9 Gamma Emitters in Broadleaf Vegetation ....................................... 90 VII- 10 Gamma Emitters in Sediment ........................................................ 99 5

PREFACE This report covers the period of January 1 through December 31, 2001. Personnel of the Nebraska Public Power District made all sample collections. Analyses were performed and reports of analyses we prepared by Teledyne Brown Engineering Environmental Services and forwarded to Nebraska Public Power District.

6

I. INTRODUCTION 7

I. INTRODUCTION This report contains a complete tabulation of data collected during the period January through December 2001, 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 comer of Nebraska on the Missouri River. A portion of the site extends into Missouri. The reactor is a 778-megawatt (net electrical) boiling water reactor. Initial criticality was attained on February 21, 1974. The reactor reached 50 percent power on June 25, 1974 and 100 percent 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. All 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. NALCO 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, 2001.

The United States Nuclear Regulatory Commission (USNRC) regulations (I OCFR50.34a) require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as is reasonably achievable (ALARA). To ensure these criteria are met, the operating license for Nebraska Public Power District's Cooper Nuclear Station includes Technical Specifications which address the release of radioactive effluents. Inplant monitoring is used to ensure that these release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in NPPD's CNS Technical Specifications.

8

A. Atmospheric Nuclear Tests Three atmospheric nuclear detonations in the People's Republic of China influenced program results significantly in late 1976 and in 1977. Two of these detonations occurred in late 1976 (September 26 and November 17) and one in late 1977 (September 17). As a consequence of these tests elevated activities of gross beta in air particulate filters and 1-131 in milk were 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 atmosphere and worldwide fallout.

Following the explosion, elevated levels of gross beta activities in air particulates and Iodine-131 in charcoal filters and milk samples were measured. Additionally, in 1986, Cesium-137 and the short-lived isotopes Iodine-131, Ruthenium-106, and Cesium-134 were detected in broadleaf vegetation. Similar results occurred in other areas of the United States and the entire Northern Hemisphere.

B. Program Objectives and Data Interpretation The objective of the monitoring program is to detect and assess the impact of possible releases to the environs of radionuclides from the operations of the Cooper Nuclear Station. This objective requires measurements of low levels of radioactivity equal to or lower than pre-determined limits of detection. In addition the source of the environmental radiation must be established. Sources of environmental radiation include:

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

(2) Terrestrial, primordial radionuclides from the environment (potassium-40, Radium-226, Thorium-228).

(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 products).

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

(5) Fallout from the Chernobyl Nuclear Reactor Accident.

Radiation levels measured in the vicinity of an operating power station are compared with preoperational measurements at the same locations to distinguish power plant effects from other sources. Also, results of the monitoring program are related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations or abnormal plant releases.

9

II.

SUMMARY

10

II.

SUMMARY

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 2001.

A discussion of each type of sample analyzed and its impact, if any, on the environment is presented in Section IV. Included also are graphs of the isotopes of interest for the past several years and the statistical results for each quarter of the year.

Section VI is the Radiological Environmental Monitoring Program Summary. It contains the yearly summary of the program with the total number of samples of each type analyzed. It lists the yearly average and range for the control locations versus the indicator locations and the number of detections per total number of samples. It identifies the station with the highest yearly average, the distance and location of that station and provides the range of detection.

Section 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 the inclusive dates of the analyses.

Section 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 number.

11

III. SAMPLING AND ANALYSIS PROGRAM 12

III. SAMPLING AND ANALYSIS PROGRAM The 2001 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 2001 Intercomparison Program conducted by the Analytic's, Inc. and Environmental Resource Associates are contained in Appendix B.

Sampling locations are indicated in the map labeled Figure 1. The sample types collected at each location and the approximate distance and direction from the reactor elevated release point are specified.

The annual land use census for 2001 is described in Appendix A. There were no milk animals found within three miles of CNS in 2001 and no evidence of potable water use from the river. The nearest garden to CNS is in sector D, 1.7 miles from CNS.

Gardens were found in eight sectors during 1999, in nine sectors during 2000, and in nine sectors during 2001. The nearest resident to CNS is in sector Q, 0.9 miles from CNS.

All of the required 2001 environmental monitoring, including sampling and analysis, was conducted as specified in Table D4. 1-1 of the CNS Offsite Dose Assessment Manual (ODAM), except as noted in Appendix E, Exception Table.

13

TABLE 1 NEBRASKA PUBLIC POWER DISTRICT COOPERNUCLEAR STATION Environmental RadiationSurveillance Program Sampling Schedule andAnalysis Sample Type Station Frequency Analyses Airborne/ 1-10 Once per 7 days Gross alpha, beta. Gamma Isotopic Particulate on quarterly composite of each station, and on each sample in which gross beta activity is >10 times the yearly mean of control samples Airborne/Iodine 1-10 Once per 7 days 1-131 Milk / Nearest Producer peak 61 Once per 15 days 1-131 (low level), Gamma Isotopic pasture only Sr-89, Sr-90, elem. Ca. on monthly composite River Water 12,28 Once per 31 days Gross alpha, sus and dis Gross beta, sus and dis, Sr-89, Sr-90, Gamma Isotopic, Tritium on quarterly composite Milk/ Nearest Producer 61,99 Once per 31 days 1-131 (low level) Sr-89, Sr-90, elem. Ca.,

Non-peak pasture Gamma Isotopic Food Products / Broadleaf 28,35,96,101 Monthly when 1-131 (low level), Gamma Isotopic Vegetation available Background Radiation 1-10, 20,44,56,58,59, Once per 92 days TLD Readout Thermoluminescent 66,67,71,79-91,94 (gamma dose)

Dosimeters Groundwater 11,47 Once per 92 days Gross Alpha, Beta, Gamma Isotopic, Tritium Milk Other Producers 42,99,100 Once per 92 days 1-131 (low level) Sr-89, Sr-90, elem. Ca.,

Gamma Isotopic Fish (Summer and Fall) 28,35 Two times per year Gross Beta, Sr-89, Sr-90, Gamma Isotopic on edible portions Shoreline Sediment 28 Two times per year Gamma Isotopic 14

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(D-E W-g Station D istance* Direotion* Sample Number (miles) (deareasI Classification Type(s) 1 0.1 230 IND AP, C, TL 2 0.75 210 IND AP. C. TL 11 0.15 275 IND WG 12 0.1 355 CON WR WSW-(@ 20 0.96 315 IND TL 58 1.1 234 IND TL 59 1 170 IND TL 79 0.85 299 IND TL 80 0.75 280 IND TL 81 0.8 255 IND TL 82 0.8 185 IND TL

Approximate distance and direction with respect to reactor Elevated Release Point (ERP)

NOTE:

Environmental sampltfpe codes; AP = air porticulate filters; C = charcoal cartridges FI = fish; M = milk; H= shoreline sediment; TL = environmental themnolumInescent dosimeters; VT = broadleof vegetation; WG = groundwater; WR = river water.

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IV.

SUMMARY

AND DISCUSSION OF 2001 ANALYTICAL RESULTS 16

IV.

SUMMARY

AND DISCUSSION OF 2001 ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during 2001 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance manual and are explained in the Teledyne Brown Engineering Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix C. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in an Interlaboratory Comparison Program.

Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the Interlaboratory Comparison are provided in Appendix B.

Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated from each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, Radiological Monitoring Acceptable Program (November 1979, Revision 1).

Section C contains a discussion of the LLD formulas.

The following is a discussion and summary of the results of the environmental measurements taken during the 2001 reporting period A. Airborne Particulates Gross beta activity was observed in 480 of the 482 indicator samples collected during 2001. The average concentration was 0.025 pCi/m 3 and a range of 0.004 to 0.11 pCi/m 3. The results of the gross beta activities are presented in Section VII-l and Trending Graph 1. The gross beta activities for 2001 were comparable to levels measured in the previous several years. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing performed in other countries. The preoperational period of 1971 through 1974 averaged 0.098 pCi/m 3 gross beta.

Air particulate filters were collected weekly and composited by locations on a quarterly basis. They were analyzed by gamma ray spectroscopy. The results are presented in Section VII-2. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in 40 of 40 composite3 samples. The indicator locations had an average concentration of 0.104 pCi/m and a range of 0.029 to 0.154 pCi/m 3. During the preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Cobalt-60 was measured in one sample at a concentration of 0.003 pCi/m 3. Thorium-228 was measured in one sample at a concentration of 0.001 pCi/mi3. All other gamma emitters were below the detection limits. The Environmental Measurements Laboratory of the US Department of Energy no longer reports measurements of 17

cerium-144 because the artificial nuclides such as cerium-144 have reached the limits of detection by the analytical techniques now used.

B. Airborne Iodine Charcoal cartridges used to collect airborne iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. Stations 01 through 10 were monitored. The results are presented in Section VII-1. All results were below the required lower limit of detection. The preoperational period of 1971 through 1974 averaged less than 0.02 pCi/mi3 iodine- 131.

C. Fish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements, which have radioactive isotopes. The results are presented in Table VII-3 and Trending Graph 2. Nine samples of fish were collected during the summer and fall of 2001. A middle-top feeding fish (carp) and a bottom feeding fish (catfish) were collected in June and October. These samples were analyzed for gross beta, strontium-89/90 and by gamma ray spectroscopy. As expected naturally occurring potassium-40 was detected in all samples. The average concentration at the control location was 2878 pCi/kg (wet weight) and a range of 2380 to 3390 pCi/kg (wet weight). The average concentration for the five indicator samples was 2946 pCi/kg (wet weight) with a range of 2800 to 3090 pCi/kg (wet weight).

The preoperational period of 1971 through 1974 averaged 2400 pCi/ kg potassium-40.

The fission product cesium-137 was not measured in any samples for 2001.

Cobalt-60 was not measured in any samples for 2001. Strontium-89 was not detected during 2001. Strontium 90 was detected at a concentration of 7.75 pCi/kg (wet). The preoperational period averaged 0.075 pCi/gram strontium-90.

Naturally occurring thorium-228 was measured in one of the five indicator samples at a concentration of 7.37 pCi/kg (wet weight). All other gamma emitters were below their detection levels.

D. Milk - NearestProducer Milk samples are collected once every 15 days in peak pasture season and once every 31 days the rest of the year. The results are presented in Table VII-4 and Trending Graph 3. Nineteen samples were analyzed by gamma ray spectroscopy.

As expected, naturally occurring potassium-40 was measured in all samples with an average of 1196 pCi/liter and a range of 1070 to 1540 pCi/liter.

The fission product cesium-137 was not detected during 2001. The preoperational period of 1971 through 1974 averaged 7.33 pCi/liter cesium-137.

Srontium-89 was not detected in the 12 samples analyzed. Strontium-90 was detected in all samples monitored with an average level of 1.00 pCi/liter and a range of 0.66 to 2.8 pCi/liter. This is a normal environmental level. The 18

TRENDING GRAPH 1 GROSS BETA IN AIR PARTICULATES MONTHLY AVERAGE - ALL LOCATIONS 0.1 I,

co 0.01 0.001 0.0001

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-i-W- Gross Bet

TRENDING GRAPH 2 CESIUM-137 IN FISH ALL LOCATIONS 1000.0 100.0 t 10.0 1.0 0.1 p I I I I I oy cf cb 0C 0N 0 0Cf 0Cf 1-.-- Cs-137 -o---s-137 LLDI

preoperational period averaged 7.20 pCi/liter strontium-90. Elemental calcium was detected at an average concentration of 1.00 pCi/liter with a range of 0.21 to 1.93 pCi/liter. Naturally occurring radium-226 was measured in one of the nineteen samples analyzed at a concentration of 113 pCi/liter. All other gamma emitters were below their detection levels. The preoperational period averaged less than 0.2 pCi/liter iodine-131.

E. Milk - OtherProducers Eight milk samples were collected from two locations of other producers during 2001 and results are presented in Table VII-5 and Trending Graphs 5 and 6.

Station 99 and station 100 were sampled quarterly in 2001. Naturally occurring potassium-40 was detected in all eight samples analyzed with an average concentration of 1248 pCi/liter and a range of 1040 to 1470 pCi/liter. Strontium 89 was not detected during 2001. Strontium 90 was measured in seven of the eight samples with an average concentration of 1.10 pCi/liter with a range of 0.66 to 1.8 pCi/liter. Elemental calcium was measured in the eight samples with an average concentration of 1.10 pCi/liter and a range of 0.85 to 1.3 pCi/liter.

Naturally occurring thorium-228 was measured in one of the eight samples analyzed at a concentration of 5.94 pCi/liter. All other gamma emitters were below their detection levels.

The levels of radioactivity of the nuclides iodine- 131 and cesium- 137 are plotted on Trending Graph 4. A comparison of graph 3 and graph 4 indicate there was no appreciable difference between the levels of activity of the nearest producer and the commercial producers. This indicates there is no effect on milk samples from the operation of the Cooper Nuclear Station.

F. Ground Water Groundwater was collected from two stations quarterly and analyzed for gross beta and gross alpha activity, for tritium, and for gamma emitting radionuclides.

Station 11 is located 0.15 miles from the plant and station 47 is 25.8 miles from the plant. The results are presented in Table VII-6 and Trending Graph 5.

The gross beta activity for the eight indicator samples had an average concentration of 6.76 pCi/liter and a range of 4.0 to 9.0 pCi/liter. This is statistically similar to past years. The preoperational period of 1971 through 1974 averaged 9.33 pCi/liter gross beta. Gross alpha was detected in one of the eight samples with a concentration of 3.10 pCi/liter. The preoperational period averaged 9.33 pCi/liter gross beta. There were no other gamma emitters measured above their detection levels. Tritium levels have been plotted in Trending Graph 5. The graph indicates this activity has remained essentially unchanged. The preoperational period averaged 379 pCi/liter tritium.

G. River Water River water was collected monthly and monitored for gross beta and gross alpha, suspended and dissolved, strontium-89, strontium-90 plus gamma emitting 21

TRENDING GRAPH 3 IODINE-131 AND CESIUM-137 IN MILK - NEAREST PRODUCER STATION 61 100.0 10.0 0

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10.0 1.0 I It II II I I I H-3 -i-H-3 LLD

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10 1995 1995 1995 1995 1996 1996 1996 1996 1997 1997 1997 1997 1998 1998 1998 1998 1999 1999 1999 1999 2000 2000 2000 2000 2001 2001 2001 2001

-Exposure Pathway - Ambient Gamma Radiation: TLD Note: The anomaly observed during the 1 st quarter of 2001 was the result of a change in TLD vendor and a one time change in TLD badge type, which is known to read lower then those used previously or subsequently.

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isotopes. A quarterly composite was measured for tritium. The results are presented in table VII-7 and Trending Graph 6.

There was no detection of potassium-40 above the normal level of detection. In fact, no gamma emitters were detected above their detection limits. Strontium-89 was not measured in 2001. Strontium-90 was measured in one of the eleven indicator samples analyzed with a concentration of 0.32 pCi/liter. Gross alpha (Dissolved) was measured in three of the eleven control samples with an average concentration of 5.27 pCi/liter and a range of 3.9 to 6.7 pCi/liter. Gross Alpha (Dissolved) was measured in two of the eleven indicator samples with an average concentration of 3.75 pCi/liter and a range of 3.1 to 4.4 pCi/liter. The preoperational period of 1971 through 1974 averaged 2.35 pCi/liter gross alpha (Dissolved). Gross Alpha (Suspended) was measured in six of the eleven control samples with an average concentration of 15.1 pCi/liter and a range of 0.43 to 60 pCi/liter. Gross alpha (Suspended) was measured in two of the eleven indicator samples with an average concentration of 5.05 pCi/liter and a range of 2.7 to 7.4 pCi/liter. The preoperational period averaged 1.70 pCi/liter gross alpha (Suspended). All eleven of the control samples analyzed for gross beta (Dissolved) had measurable concentrations with an average of 8.96 pCi/liter and a range of 6.8 to 11 pCi/liter. All eleven indicator locations had an average concentration of 8.12 pCi/liter and a range of 6.9 to 9.6 pCi/liter. The preoperational period averaged 8.83 pCi/liter gross beta (Dissolved). Gross beta (Suspended) was measured in nine of the eleven control samples with an average concentration of 33.4 pCi/liter and a range of 1.0 to 120 pCi/liter. Gross beta (Suspended) was measured in eight of the eleven indicator samples with an average concentration of 4.55 pCi/liter and a range of 1.3 to 11 pCi/liter. The preoperational period averaged 5.67 pCi/liter gross beta (Suspended). Tritium was measured in one of the four control samples with a concentration of 96.0 pCi/liter. Tritium was measured in one of the four indicator samples with a concentration of 100 pCi/liter. The preoperational period averaged 338 pCi/liter tritium. Below are a comparison of the 2000 and 2001 results for gross alpha and gross beta. The average readings were similar to previous years but are within normal yearly fluctuations.

2000 2001 Average pCi/liter Average pCi/liter Gross Alpha Dissolved 3.21 4.66 Gross Alpha Suspended 1.47 12.6 Gross Beta Dissolved 8.21 8.54 Gross Beta Suspended 2.75 19.8 The levels of activity continued to rise and fall within statistical limits depending on water levels and turbulence and were probably due to naturally occurring isotopes. No fission or reactor activation products were detected. Trending Graph 6 illustrates the level of activity for tritium.

28

H. Thermoluminescent Dosimeters Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table VII-8 and Trending Graph 7. Ambient radiation was monitored at 32 locations within a 10 mile radius of the Cooper Nuclear Station and collected quarterly. The quarterly averages for the indicator locations was 14.9 milliRoentgen/quarter and a range from 0.1 to 43.3 milliRoentgen/quarter. The control station 44, which is located 10.5 miles, 270 degrees had an average of 17.3 milliRoentgen/quarter and a range from 5.5 to 37.9 milliRoentgen/quarter. The highest station was Station 85 with an average of 17.5 milliRoentgen/quarter and a range from 9.5 to 35.3 milliRoentgen/quarter.

The preoperational period of 1971 through 1974 averaged 7.0 milliRoentgen/quarter.

The gamma exposures monitored by thermoluminescent dosimeters from 1995 through 2001 are plotted. The data from year to year is in good agreement and indicates no adverse changes in radiation exposure to the population near the Cooper Nuclear Station.

L Food - BroadleafVegetation Thirteen food samples were collected from three locations. They were analyzed for iodine-131 by chemical separation and by gamma spectrometry. The results are presented in Table VII-9 and Trending Graph 8. Iodine- 131 was not measured above the detection limits in the thirteen samples analyzed. As expected, naturally occurring potassium-40 was monitored in three of three control samples with an average activity of 7983 pCi/kg (wet weight) and a range from 5170 to 9990 pCi/kg (wet weight). Potassium-40 was detected in ten of the ten indicator samples with an average concentration of 5425 pCi/kg (wet weight) and a range from 527 to 7830 pCi/kg (wet weight). The preoperational period of 1971 through 1974 averaged 3900 pCi/ kg potassium-40. Cosmogenic beryllium-7 was detected in three of the three control samples with an average concentration of 2616 pCi/kg (wet weight) and a range from 1540 to 3970 pCi/kg (wet weight).

The average at the indicator locations was 2298 pCi/kg (wet weight) and a range from 74.2 to 4130 pCi/kg (wet weight). All other gamma emitters were below the detection limits.

J. Shoreline Sediment Sediment samples were collected during May and October from Station 28 and were analyzed by gamma spectrometry. The results are presented in Table VII- 10 and Trending Graph 9. One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in one of two samples with an activity of 48.2 pCi/kg (dry weight). As expected, naturally 29

occurring potassium-40 was observed in the two samples with an average activity of 14150 pCi/kg (dry weight) and a range from 12900 to 15400 pCi/kg (dry weight). Radium-226 was measured in one of the two samples with a concentration of 1370 pCi/kg (dry weight). Naturally occurring, thorium-228 was observed in the two samples with an average concentration of 930 pCi/kg (dry weight) and a range from 819 to 1040 pCi/kg (dry weight). All other gamma emitters were below their detection limits.

The results of the analyses have been presented. Based on the evidence of the Radiological Environmental Monitoring Program, the Nebraska Public Power District, Cooper Nuclear Station is operating within regulatory limits.

30

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V. CONCLUSIONS 32

V. CONCLUSIONS The results of the 2001 Radiological Environmental Monitoring Program (REMP) for the Cooper Nuclear Station (CNS) of the Nebraska Public Power District (NPPD) have been presented. The report contains data tables, summaries, and discussions of the data and trending graphs.

Naturally occurring radioactivity was observed in sample media in the expected activity ranges. Occasional samples of a few media showed the presence of man-made isotopes. They have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence.

Section IV is a discussion of each type of sample analyzed and its impact, if any, on the environment. Included also are graphs of the isotopes of interest for the past several years.

Section VI presents the yearly summary of the program with the total number of samples of each type analyzed, the number of detection per total number of samples, the station with the highest average, the average of the control station, and the inclusive dates of the analyses. This is followed by a complete tabulation of the data by sample type and station number in Section VII.

The 2001 radiological environmental measurements for the Cooper Nuclear Station indicates that there has been no residual fallout resulting from the explosion and fire at Chernobyl Reactor in the Soviet Union which occurred on April 26, 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 the Cooper Nuclear Station.

33

SECTION VI.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

- 2001 34

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Coomer Nuclear Station Docket No. 50-298 Location of Facility Nemaha, Nebraska Reporting Period January 1, 2001 to December 31, 2001 (County, State)

Type & Lower Limit All Indicator Control Medium of Pathway Total No. of Locations Location with Highest Annual Mean Location No. of Sampled of Analyses Detection (1) Mean (2) Name Mean () (2) Mean () (2) Reportable (Unit of Measurement) Performed (LLD) Range (2) Range (2) Range (2) Occurrences Air Iodine 1-131 482 0.07 -(0/482) -(0/0) 0 (pCi/m 3)

Air Gross Beta 482 0.01 .025(480/482) Sta. 3 2.5 mi. .028(41/42) -(0/0) 0 Particulate (Weekly) (.004-0.110) (.004-0.110)

(pCi/rn3)

Gross Alpha 482 - .004(361/482) Sta. 4 3.0 mi. 0.005(31/46) -(0/0) 0 (Weekly) (0.001-0.038) (0.001-0.038)

Gamma 40 Be-7 40 0.104(40/40) Sta. 2 0.75 mi. 0.124(4/4) -(0/0) 0 (0.029-0.154) (0.103-0.140)

Co-60 40 0.003(1/40) Sta. 8 2.5 mi. 0.003(1/40) -(0/0) 0 Th-228 40 0.001(1/40) Sta. 8 2.5 mi. 0.001(1/40) -(0/0) 0 Fish Gr Beta 9 4120(5/5) Sta. 35 2.0 mi. 5325(4/4) 5325(4/4) 0 (pCi/kg wet) (2000-6600) (3100-6200) (3100-6200)

Sr-89 9 -(0/5) -(0/4) 0 (1) Nominal Lower Limit of Detection (LLD).

(2) Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location indicated in brackets ( ).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Coooer Nuclear Station Docket No. 50-298 Location of Facility Nemaha, Nebraska Reporting Period January 1,2001 to December 31, 2001 (County, State)

Type & Lower Limit All Indicator Control Medium of Pathway Total No. of Locations Location with Highest Annual Mean Location No. of Sampled of Analyses Detection (1) Mean (2) Name Mean () (2) Mean () (2) Reportable (Unit of Measurement) Performed (LLD) Range (2) Range (2) Range (2) Occurrences Fish Sr-90 9 7.75(4/5) Sta. 28 1.8 mi. 7.75(4/5) -(0/4) 0 (pCi/kg wet) (4.5-12) (4.5-12)

Gamma 9 K-40 9 2946(5/5) Sta. 28 1.8 mi. 2946(5/5) 2878(4/4) 0 (2800-3090) (2800-3090) (2380-3390)

Co-60 9 0.13 -(0/5) -(0/4) 0 Cs-137 9 0.15 -(0/5) -(0/4) 0 Th-228 9 7.37(1/5) Sta. 28 1.8 mi. 7.37(1/5) -(0/4) 0 Milk Sr-89 12 - -(0/12) -(0/0) 0 Nearest Producers (pCi/liter)

Sr-90 12 - 1.00(12/12) Sta. 61 3.5 mi. 1.00(12/12) -(0/0) 0 (0.66-2.8) (0.66-2.8)

Ca 12 - 1.00(12/12) Sta. 61 3.5 mi. 1.00(12/12) -(0/0) 0 (gm/liter) (0.213-1.93) (0.213-1.93)

(1) Nominal Lower Limit of Detection (LLD).

(2) Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location indicated in brackets ( ).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Cooper Nuclear Station Docket No. 50-298 Location of Facilit, Nemaha, Nebraska Reporting Period January 1,2001 to December 31, 2001 (County, State)

Type & Lower Limit All Indicator Control Medium of Pathway Total No. of Locations Location with Highest Annual Mean Location No. of Sampled of Analyses Detection (1) Mean (2) Name Mean () (2) Mean ( ) (2) Reportable (Unit of Measurement) Performed (LLD) Range (2) Range (2) Range (2) Occurrences Milk Gamma 19 Nearest Producers (pCi/liter) K-40 19 - 1196(19/19) Sta, 61 3.5 mi. 1196(19/19) -(0/0) 0 (1070-1540) (1070-1540)

Ra-226 19 113(1/19) Sta. 61 3.5 mi. 113(1/19) -(0/0) 0 Milk Sr-89 8 -(0/8) -(0/0) 0 Other Producers (pCi/liter)

Sr-90 8 1.10(7/8) Sta. 99 10,5 mi. 1.23(3/4) -(0/0) 0 (0.66-1.8) (0.78-1.5)

Ca 8 - 1.10(8/8) Sta. 99 10,5 mi, 1.18(4/4) -(0/0) 0 (gm/liter) (0.85-1.3) (1.10-1.2)

Milk Gamma 8 Other Producers (pCi/liter) K-40 8 1284(8/8) Sta. 100 11.5 mi. 1288(4/4) -(0/0) 0 (1040-1470) (1190-1400)

Th-228 8 - 5.94(1/8) Sta. 99 10.5 mi. 5.94(1/4) -(0/0) 0 (1) Nominal Lower Limit of Detection (LLD).

(2) Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location indicated in brackets ().

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Cooper Nuclear Station Docket No. 50-298 Location of Facility Nemaha, Nebraska Reporting Period January 1, 2001 to December 31, 2001 (County, State)

Type & Lower Limit All Indicator Control Medium of Pathway Total No. of Locations Location with Highest Annual Mean Location No. of Sampled of Analyses Detection (1) Mean (2) Name Mean () (2) Mean ( ) (2) Reportable (Unit of Measurement) Performed (LLD) Range (2) Range (2) Range (2) Occurrences Groundwater Gross Alpha 8 3.10(1/8) Sta. 47 25.8 mi. 3.10(1/8) -(0/0) 0 (pCi/liter)

Gross Beta 8 4 6.76(8/8) Sta. 11 0.15 mi. 7.10(4/4) -(0/0) 0 (4.0-9,0) (5.4-8.3)

H-3 8 2000 -(0/8) -(0/8) -(0/0) 0 Gamma 8 00 K-40 8 -(0/8) -(0/8) -(0/0) 0 River Water Gross Alpha 22 3.75(2/11) Sta. 35 2.0 mi. 6.7(1/2) 5.27(3/11) 0 (pCi/liter) (Dissolved) (3.1-4.4) (1.4-1.9) (3.9-6.7)

Gross Alpha 22 5.05(2/11) Sta. 35 2.0 mi. 17.8(4/8) 15,1(6/11) 0 (Suspended) (2.7-7.4) (1.4-60) (0.43-60)

Gross Beta 22 4 8.12(11/11) Sta. 35 2.0 mi. 9.85(2/2) 8.96(11/11) 0 (Dissolved) (6.9-9.6) (9.70-10) (6.8-11)

Gross Beta 22 4.55(8/11) Sta. 12 0.10mi 36.8(7/9) 33.4(9/11) 0 (Suspended) (1.3-11) (2.8-120) (1.0-120)

(1) Nominal Lower Limit of Detection (LLD).

(2) Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location indicated in brackets ().

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Cooper Nuclear Station Docket No. 50-298 Location of Facility Nemaha, Nebraska Reporting Period January 1, 2001 to December 31, 2001 (County, State)

Type & Lower Limit All Indicator Control Medium of Pathway Total No. of Locations Location with Highest Annual Mean Location No. of Sampled of Analyses Detection (1) Mean (2) Name Mean ( ) (2) Mean () (2) Reportable (Unit of Measurement) Performed (LLD) Range (2) Range (2) Range (2) Occurrences River Water 1-131 22 0.46(1/11) Sta. 12 0.10mi 0.48(1/9) 0.48(1/11) 0 (pCi/liter)

Gamma 22 K-40 22 -(0/11) -(0/11) 0 H-3 8 2000 100(1/4) Sta. 28 1.8 mi. 100(1/4) 96.0(1/4) 0 Sr-89 22 -(0/11) -(0/1 1) 0 Sr-90 22 0.32(1/11) Sta. 28 1.8 mi. 0.32(1/11) -(0/11) 0 Direct Radiation Gamma 126 10.6(122/122) Sta, 85 3.1 mi. 13,4(4/4) 13.3(4/4) 0 (mR/Standard Month) Dose (0.00-27.1) (9.5-19.2) (5.5-21.8)

Quarterly Broadleaf/Vegetation Gamma 13 (pCi/kg wet)

Be-7 13 2298(10/10) Sta. 35 2.0 mi. 2616(3/3) 2616(3/3) 0 (74.2-4130) (1540-3970) (1540-3970)

K-40 13 5425(10/10) Sta. 35 2.0 mi. 7983(3/3) 7983(3/3) 0 (527-7830) (5170-9990) (5170-9990)

(1) Nominal Lower Limit of Detection (LLD).

(2) Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location indicated in brackets ( ).

ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Cooper Nuclear Station Docket No. 50-298 Location of Facility Nemaha, Nebraska Reporting Period January 1, 2001 to December 31, 2001 (County, State)

Type & Lower Limit All Indicator Control Medium of Pathway Total No. of Locations Location with Highest Annual Mean Location No. of Sampled of Analyses Detection (1) Mean (2) Name Mean () (2) Mean () (2) Reportable (Unit of Measurement) Performed (LLD) Range (2) Range (2) Range (2) Occurrences Broadleaf/Vegetation Cs-137 13 0.08 -(0/10) -(0/3) 0 (pCi/kg wet) 1-131 13 0.06 -(0/10) -(0/3) 0 Shoreline Sediment Gamma 2 (pCi/kg dry)

Be-7 2 428(1/2) Sta. 28 1.8 mi. 428(1/2) -(0/0) 0 40 K-40 2 14150(2/2) Sta. 28 1.8 mi, 14150(2/2) -(0/0) 0 (12900-15400) (12900-15400)

Cs-137 2 0.18 48.2(1/2) Sta. 28 1.8 mi. 48.2(1/2) -(0/0) 0 Ra-226 2 1370(1/2) Sta. 28 1.8 mi. 1370(1/2) -(0/0) 0 Th-228 2 930(2/2) Sta. 28 1.8 mi. 930(2/2) -(0/0) 0 (819-1040) (819-1040)

(1) Nominal Lower Limit of Detection (LLD).

(2) Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location indicated in brackets ( ).

SECTION VII. COMPLETE DATA TABLES 41

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 01 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 9.95E+03 CU. FT. 3.9 +/- 0.4 E-02 4.1 +/- 1.9 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 3.2 +/- 1.7 E-03 01/17 L.T. 2. E-02 01/09 01/16 1.OOE+04 CU. FT. 3.2 +/- 0.3 E-02 4.5 +/- 1.8 E-03 01/19 L.T. 2. E-02 01/16 01/23 1.01 E+04 CU. FT. 3.3 +/- 0.4 E-02 2.5 +/- 1.2 E-03 01/29 L.T. 3. E-02 01/23 01/30 1.OOE+04 CU. FT. 1.6 +/- 0.3 E-02 1.6 +/- 1.0 E-03 02/06 L.T. 2. E-02 01/30 02/06 1.01 E+04 CU. FT. 2.2 +/- 0.3 E-02 2.7 +/- 1.4 E-03 02/12 L.T. 4. E-02 02/06 02/12 8.69E+03 CU. FT. 2.3 +/- 0.3 E-02 2.3 +/- 1.5 E-03 02/21 L.T. 7. E-02 02/12 02/20 (a) (a) (a) 02/20 02/28 (b) 1.6 +/-0.1 E01 1.1 +/-0.5 E 00 03/05 L.T. 6. E+00 02/28 03/06 8.48E+03 CU. FT. 2.6 +/- 0.4 E-02 2.6 +/- 1.4 E-03 03/14 L.T. 3. E-02 03/06 03/13 1.01 E+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 1. E-03 03/21 L.T. 4. E-02 03/13 03/21 1.12E+04 CU. FT. 4.1 +/- 0.4 E-02 2.2 +/- 0.3 E-02 03/26 L.T. 4. E-02 03/21 03/27 8.72E+03 CU. FT. 1.3 +/- 0.3 E-02 L.T. 1. E-03 04/03 L.T. 5. E-02 03/27 04/03 1.02E+04 CU. FT. 1.1 +/-+0.2 E-02 L.T. 1. E-03 04/06 L.T. 1. E-02 04/03 04/10 9.27E+03 CU. FT. 1.6 +/- 0.3 E-02 1.8 +/- 1.3 E-03 04/13 L.T. 2. E-02 04/10 04/17 1.02E+04 CU. FT. 1.2 +/- 0.2 E-02 1.4 +/- 1.0 E-03 04/23 L.T. 1. E-02 04/17 04/23 9.04E+03 CU. FT. 1.3 +/- 0.3 E-02 L.T. 1. E-03 05/01 L.T. 5. E-02 04/24 05/01 1.10E+04 CU. FT. 1.1 +/-+0.2 E-02 1.9 +/- 1.1 E-03 05/08 L.T. 2. E-02 05/01 05/08 1.02E+04 CU. FT. 1.2 +/-+0.2 E-02 1.9 +/- 1.1 E-03 05/10 L.T. 3. E-02 05/08 05/15 1.OOE+04 CU. FT. 2.5 +/- 0.3 E-02 5.0 +/- 1.7 E-03 05/17 L.T. 2. E-02 05/15 05/22 1.01 E+04 CU. FT. 1.7 +/- 0.3 E-02 2.5 +/- 1.5 E-03 05/24 L.T. 2. E-02 05/22 05/29 1.01 E+04 CU. FT. 1.0 +/- 0.3 E-02 L.T. 2. E-03 06/01 L.T. 3. E-02 05/29 06/05 1.02E+04 CU. FT. 1.1 +/- 0.2 E-02 L.T. 2. E-03 06/08 L.T. 2. E-02 06/05 06/12 9.86E+03 CU. FT. 2.2 +/- 0.3 E-02 2.4+/-1.4 E-03 06/19 L.T. 2. E-02 06/12 06/19 1.02E+04 CU. FT. 2.1 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 5. E-02 06/19 06/26 9.54E+03 CU. FT. 4.0 +/- 0.4 E-02 1.9 +/- 0.3 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 01 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 8.96E+03 CU. FT. 3.2 +/- 0.4 E-02 5.6 +/- 1.9 E-03 07/09 L.T. 4. E-02 07/03 07/10 1.OOE+04 CU. FT. 2.1 +/- 0.3 E-02 L.T. 2. E-03 07/12 L.T. 5. E-02 07/10 07/17 1.02E+04 CU. FT. 2.7 +/- 0.3 E-02 7.1 +/-2.0 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.91 E+03 CU. FT. 2.3 +/- 0.3 E-02 2.3 +/- 1.3 E-03 07/27 L.T. 3. E-02 07/24 07/31 1.01 E+04 CU. FT. 1.8 +/- 0.3 E-02 1.7 +/- 1.2 E-03 08/08 L.T. 3. E-02 07/31 08/07 9.26E+03 CU. FT. 2.7 +/- 0.3 E-02 1.4 +/- 1.2 E-03 08/19 L.T. 3. E-02 08/07 08/14 9.31 E+03 CU. FT. 2.7 +/- 0.3 E-02 2.9 +/- 1.5 E-03 08/22 L.T. 4. E-02 08/14 08/21 1.01E+04 CU. FT. 2.6 +/- 0.3 E-02 2.1 +/- 1.4 E-03 08/29 L.T. 5. E-02 08/21 08/28 1.01E+04 CU. FT. 2.1 +/-+-0.3 E-02 2.1 +/- 1.2 E-03 08/30 L.T. 2. E-02 08/28 09/04 9.94E+03 CU. FT. 2.9 +/- 0.3 E-02 1.6 +/- 1.3 E-03 09/06 L.T. 1. E-02 09/04 09/11 9.16E+03 CU. FT. 2.5 +/- 0.3 E-02 2.6 +/- 1.7 E-03 09/19 L.T. 3. E-02 09/11 09/18 1.OOE+04 CU. FT. 2.6 +/- 0.3 E-02 L.T. 1. E-03 09/21 L.T, 3. E-02 09/18 09/25 1.OOE+04 CU. FT. 2.4 +/- 0.3 E-02 2.7 +/- 1.5 E-03 09/28 L.T. 4. E-02 09/25 10/02 9.78E+03 CU. FT. 2.2 +/- 0.3 E-02 2.4 +/- 1.3 E-03 10/05 L.T. 3. E-02 10/02 10/09 9.97E+03 CU. FT. 2.8 +/- 0.3 E-02 4.3 +/- 1.9 E-03 10/12 L.T. 1. E-02 10/09 10/16 9.91 E+03 CU. FT. 1.7 +/- 0.3 E-02 L.T. 1. E-03 10/23 L.T. 3. E-02 10/16 10/23 1.03E+04 CU. FT. 1.8 +/- 0.3 E-02 2.5+/-1.3 E-03 10/30 L.T. 3. E-02 10/23 10/30 9.97E+03 CU. FT. 2.9 +/- 0.3 E-02 3.1 +/- 1.7 E-03 11/08 L.T. 3. E-02 10/30 11/06 1.OOE+04 CU. FT. 2.3 +/-+0.3 E-02 3.4+/-1.4 E-03 11/15 L.T. 3. E-02 11/06 11/13 1.03E+04 CU. FT. 3.6 +/- 0.4 E-02 2.7+/-1.3 E-03 11/20 L.T. 4. E-02 11/13 11/20 1.01 E+04 CU. FT. 4.5 +/- 0.4 E-02 3.8+/- 1.6 E-03 12/06 L.T. 4. E-02 11/20 11/27 1.02E+04 CU. FT. 3.0 +/- 0.3 E-02 2.6+/- 1.6 E-03 12/11 L.T. 4. E-02 11/27 12/04 9.92E+03 CU. FT. 1.3 +/- 0.2 E-02 L.T. 1. E-03 12/13 L.T. 2. E-02 12/04 12/11 1.02E+04 CU. FT. 2.4 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 4. E-02 12/11 12/18 9.87E+03 CU. FT. 4.6 +/- 0.4 E-02 3.4+/-1.5 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.16E+04 CU. FT. 2.4 +/- 0.3 E-02 3.6+/-1.4 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 02 COLL. TIME APEFILTER APFILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 9.95E+03 CU. FT. 7.5 +/- 0.5 E-02 7.2 +/- 2.3 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01 E+04 CU. FT. 1.7 +/- 0.3 E-02 2.0 +/- 1.4 E-03 01/17 L.T. 2. E-02 01/09 01/16 9.10E+03 CU. FT. 3.3 +/- 0.4 E-02 2.6+/-1.6 E-03 01/19 L.T. 2. E-02 01/16 01/23 1.01 E+04 CU. FT. 4.5 +/- 0.4 E-02 3.5+/-1.4 E-03 01/29 L.T. 3. E-02 01/23 01/30 (a) (a) (a) 01/30 02/06 (a) (a) (a) 02/06 02/12 (a) (a) (a) 02/12 02/20 (a) (a) (a) 02/20 02/28 (a) (a) (a) 02/28 03/06 (b) 2.7 +/- 0.2 E 01 4.6 +/- 0.8 E 00 03/14 L.T. 6. E+00 03/06 03/14 (a) (a) (a) 03/14 03/21 (b) 1.6 +/-+0.1 E01 8.4 +/- 1.2 E 00 03/26 L.T. 1. E+01 03/21 03/27 8.71 E+03 CU. FT. 8.3 +/- 2.9 E-03 L.T. 1. E-03 04/03 L.T. 5. E-02 03/27 04/03 (a) (a) (a) 04/03 04/10 (b) 8.8 +/- 1.0 E 00 1.0 +/- 0.4 E 00 04/13 L.T. 7. E+00 04/10 04/17 1.02E+04 CU. FT. 1.1 +/-+0.2 E-02 2.2 +/- 1.2 E-03 04/23 L.T. 1. E-02 04/17 04/24 9.84E+03 CU. FT. 1.5 +/- 0.3 E-02 1.3 +/- 1.1 E-03 05/01 L.T. 4. E-02 04/24 05/01 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 3.8 +/- 1.5 E-03 05/08 L.T. 2. E-02 05/01 05/08 1.02E+04 CU. FT. 1.7 +/- 0.3 E-02 2.6 +/- 1.3 E-03 05/10 L.T. 3. E-02 05/08 05/15 9.99E+03 CU. FT. 2.3 +/- 0.3 E-02 4.8 +/- 1.7 E-03 05/17 L.T. 2. E-02 05/15 05/22 1.01E+04 CU. FT. 1.5 +/- 0.3 E-02 1.8 +/- 1.4 E-03 05/24 L.T. 2. E-02 05/22 05/29 1.01E+04 CU. FT. 6.1 +/- 2.3 E-03 L.T. 2. E-03 06/01 L.T. 3. E-02 05/29 06/05 (a) (a) (a) 06/05 06/12 (b) 6.3 +/-+0.8 E 00 4.8 +/- 3.6 E-01 06/19 L.T. 2. E+01 06/12 06/19 1.02E+04 CU. FT. 1.0 +/- 0.2 E-02 L.T. 2. E-03 06/17 L.T. 5. E-02 06/19 06/26 1.01E+04 CU. FT. 4.3 +/- 0.4 E-02 2.1 +/-0.3 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 02 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.97E+03 CU. FT. 3.0 +/-+0.3 E-02 5.9 +/- 1.9 E-03 07/09 L.T. 3. E-02 07/03 07/10 9.93E+03 CU. FT. 2.2 +/- 0.3 E-02 L.T. 2. E-03 07/12 L.T. 5. E-02 07/10 07/17 8.97E+03 CU. FT. 2.7 +/- 0.4 E-02 5.8 +/- 2.0 E-03 07/23 L.T. 4. E-02 07/17 07/24 9.66E+03 CU. FT. 2.5 +/- 0.3 E-02 1.8+/-1.2 E-03 07/27 L.T. 3. E-02 07/24 07/31 1.01 E+04 CU. FT. 1.9 +/- 0.3 E-02 L.T. 1. E-03 08/08 L.T. 3. E-02 07/31 08/07 9.94E+03 CU. FT. 2.5 +/- 0.3 E-02 2.4 +/- 1.3 E-03 08/19 L.T. 3. E-02 08/07 08/14 9.87E+03 CU. FT. 2.4 +/- 0.3 E-02 2.6 +/- 1.3 E-03 08/22 L.T. 4. E-02 08/14 08/21 9.98E+03 CU. FT. 2.4 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 5. E-02 08/21 08/28 9.88E+03 CU. FT. 2.1 +/- 0.3 E-02 1.7+/-1.2 E-03 08/30 L.T. 2. E-02 08/28 09/04 9.76E+03 CU. FT. 3.1 +/- 0.3 E-02 3.0+/-1.6 E-03 09/06 L.T. 2. E-02 09/04 09/11 9.10E+03 CU. FT. 2.6 +/- 0.3 E-02 2.2+/-1.6 E-03 09/19 L.T. 3. E-02 09/11 09/18 9.86E+03 CU. FT. 3.1 +/- 0.3 E-02 2.4+/-1.4 E-03 09/21 L.T. 3. E-02 09/18 09/25 1.OOE+04 CU. FT. 2.7 +/- 0.3 E-02 3.3+/-1.6 E-03 09/28 L.T. 4. E-02 09/25 10/02 9.67E+03 CU. FT. 2.4 +/- 0.3 E-02 L.T. 1. E-03 10/05 L.T. 3. E-02 10/02 10/09 1.01 E+04 CU. FT. 1.9 +/- 0.3 E-02 2.1 +/- 1,4 E-03 10/12 L.T. 2. E-02 10/09 10/16 1.03E+04 CU. FT. 2.0 +/- 0.3 E-02 L.T. 1. E-03 10/23 L.T. 3. E-02 10/16 10/23 9.98E+03 CU. FT. 2.9 +/- 0.3 E-02 3.3 +/- 1.5 E-03 10/30 L.T. 3. E-02 10/23 10/30 9.91 E+03 CU. FT. 3.3 +/- 0.3 E-02 3.1 +/- 1.8 E-03 11/08 L.T. 3. E-02 10/30 11/06 9.99E+03 CU. FT. 2.9 +/- 0.3 E-02 2.9 +/- 1.3 E-03 11/15 L.T. 3. E-02 11/06 11/13 1.03E+04 CU. FT. 3.6 +/- 0.4 E-02 3.1 +/- 1.3 E-03 11/20 L.T. 4. E-02 11/13 11/20 1.01E+04 CU. FT. 4.5 +/-+0.4 E-02 4.1 +/- 1.7 E-03 12/06 L.T. 4. E-02 11/20 11/27 1.02E+04 CU. FT. 1.6 +/- 0.3 E-02 L.T. 2. E-03 12/11 L.T. 2. E-02 11/27 12/04 9.93E+03 CU. FT. 2.2 +/- 0.3 E-02 L.T. 1. E-03 12/13 L.T. 2. E-02 12/04 12/11 9.94E+03 CU. FT. 2.8 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 3. E-02 12/11 12/18 9.88E+03 CU. FT. 4.3 +/- 0.4 E-02 2.7 +/- 1.4 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.16E+04 CU. FT. 2.7 +/- 0.3 E-02 1.8 +/- 1.1 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 03 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 8.64E+03 CU. FT. 1.1 +/-+0.1 E-01 9.5 +/- 2.8 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 3.2 +/- 1.7 E-03 01/17 L.T. 2. E-02 01/09 01/16 9.78E+03 CU. FT. 4.2 +/- 0.4 E-02 5.2+/- 1.9 E-03 01/19 L.T. 2. E-02 01/16 01/23 (a) (a) (a) 01/23 01/30 (a) (a) (a) 01/30 02/06 9.91 E+03 CU. FT. 2.4 +/- 0.3 E-02 1.5+/-1.1 E-03 02/12 L.T. 4. E-02 02/06 02/12 9.43E+03 CU. FT. 2.7 +/- 0.3 E-02 4.4+/-1.8 E-03 02/21 L.T. 3. E-02 02/12 02/20 (a) (a) (a) 02/20 02/28 (a) (a) (a) 02/28 03/06 (b) 2.5 +/- 0.2 E 01 3.2 +/- 0.7 E 00 03/14 L.T. 7. E+00 0-1 03/06 03/14 1.13E+04 CU. FT. 3.0 +/- 0.3 E-02 3.0+/-1.3 E-03 03/21 L.T. 3. E-02 03/14 03/21 7.26E+03 CU. FT. 5.7 +/- 0.5 E-02 2.3 +/- 0.4 E-02 03/26 L.T. 3. E-02 03/21 03/27 (d) (d) (d) 03/27 04/03 (d) (d) (d) 04/03 04/10 (d) (d) (d) 04/10 04/17 (d) (d) (d) 04/17 04/24 (b) L.T. 8. E-01 L.T. 3. E-01 05/01 L.T. 7. E+00 04/24 05/01 9.96E+03 CU. FT. L.T. 3. E-03 L.T. 9. E-04 05/08 L.T. 2. E-02 05/01 05/08 1.01 E+04 CU, FT. 4.0 +/- 1.9 E-03 L.T. 9. E-04 05/10 L.T. 1. E-02 05/08 05/15 9.10E+03 CU. FT. 2,7 t+/-0.3 E-02 6.2 +/- 2.0 E-03 05/17 L.T. 2. E-02 05/15 05/22 1.01E+04 CU. FT. 1.4 +/- 0.3 E-02 L.T. 2. E-03 05/24 L.T. 2. E-02 05/22 05/29 1.OOE+04 CU. FT. 1.0 +/- 0.3 E-02 L.T. 2. E-03 06/01 L.T. 2. E-02 05/29 06/05 1.03E+04 CU. FT. 1.2 +/- 0.2 E-02 L.T. 2. E-03 06/08 L.T. 2. E-02 06/05 06/12 9.84E+03 CU. FT. 2.0 +/- 0.3 E-02 1.6 +/- 1.2 E-03 06/19 L.T. 2. E-02 06/12 06/19 9.52E+03 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 5. E-02 06/19 06/26 1.07E+04 CU. FT. 4.8 +/- 0.4 E-02 2.2 +/- 0.3 E-02 06/29 L.T. 1. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 03 COLL. TIME APEFILTER APEFILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 8.78E+03 CU. FT. 3.2 +/- 0.4 E-02 4.5 +/- 1.8 E-03 07/09 L.T. 2. E-02 07/03 07/10 1.01 E+04 CU. FT. 2.5 +/- 0.3 E-02 L.T. 2. E-03 07/12 L.T. 3. E-02 07/10 07/17 1.04E+04 CU. FT. 2.6+/-0.3E-02 5.4 +/- 1.8 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.66E+03 CU. FT. 2.0 +/- 0.3 E-02 1.8 +/- 1.2 E-03 07/27 L.T. 2. E-02 07/24 07/31 9.93E+03 CU. FT. 2.2 +/- 0.3 E-02 1.5+/-1.2 E-03 08/08 L.T. 3. E-02 07/31 08/07 1.OOE+04 CU. FT. 1.9 +/-0.3 E-02 1.3 +/- 1.1 E-03 08/19 L.T. 3. E-02 08/07 08/14 8.80E+03 CU. FT. 3.3 +/- 0.4 E-02 3.1 +/-1.5 E-03 08/22 L.T. 4. E-02 08/14 08/21 1.07E+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 4. E-02 08/21 08/28 1.OOE+04 CU. FT. 1.9 +/- 0.3 E-02 1.2 +/- 1.0 E-03 08/30 L.T. 2. E-02 08/28 09/04 1.01 E+04 CU. FT. 2.2 +/- 0.3 E-02 L.T. 1. E-03 09/06 L.T. 2. E-02 09/04 09/11 9.64E+03 CU. FT. 2.1 +/- 0.3 E-02 2.3 +/- 1.6 E-03 09/19 L.T. 3. E-02 09/11 09/18 1.07E+04 CU. FT. 3.0 +/- 0.3 E-02 2.1 +/-1.2 E-03 09/21 L.T. 2. E-02 09/18 09/25 9.92E+03 CU. FT. 2.3 +/- 0.3 E-02 2.6 +/- 1.5 E-03 09/28 L.T. 4. E-02 09/25 10/02 1.02E+04 CU. FT. 1.3 +/- 0.3 E-02 L.T. 1. E-03 10/05 L.T. 2. E-02 10/02 10/09 1.01 E+04 CU. FT. 2.4 +/- 0.3 E-02 2.4 +/- 1.6 E-03 10/12 L.T. 2. E-02 10/09 10/16 9.89E+03 CU. FT. 2.2+/-0.3E-02 1.5 +/- 1.2 E-03 10/23 L.T. 4. E-02 10/16 10/23 1.02E+04 CU. FT. 3.2+/-0.3E-02 3.2 +/- 1.5 E-03 10/30 L.T. 3. E-02 10/23 10/30 1.OOE+04 CU. FT. 2.6 +/- 0.3 E-02 2.3 +/- 1.6 E-03 11/08 L.T. 3. E-02 10/30 11/06 8.53E+03 CU. FT. 3.5 +/- 0.4 E-02 3.5 +/- 1.6 E-03 11/15 L.T. 3. E-02 11/06 11/13 1.03E+04 CU. FT. 4.3 +/- 0.4 E-02 4.1 +/-1.5 E-03 11/20 L.T. 4. E-02 11/13 11/20 1.OOE+04 CU. FT. 2.4 +/- 0.3 E-02 2,4 +/- 1.4 E-03 12/06 L.T. 4. E-02 11/20 11/27 1.03E+04 CU. FT. 2,8 +/- 0.3 E-02 L.T. 2. E-03 12/11 L.T. 4. E-02 11/27 12/04 9.93E+03 CU. FT. 2.1 +/- 0.3 E-02 1.6 +/- 1.3 E-03 12/13 L.T. 2. E-02 12/04 12/11 1.01E+04 CU. FT. 1.4 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 4. E-02 12/11 12/18 9.86E+03 CU. FT. 4.0 +/- 0.4 E-02 3,3 +/- 1.5 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.15E+04 CU. FT. 1.8 +/-0.3 E-02 2.3 +/- 1.2 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 04 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 1.OOE+04 CU. FT. 6.0 +/- 0.4 E-02 5.5 +/- 2.1 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01 E+04 CU. FT. 1.4+/- 0.3 E-02 2.7+/-1.6 E-03 01/17 L.T. 2. E-02 01/09 01/16 1.02E+04 CU. FT. 3.6 +/- 0.3 E-02 4.0 +/- 1.7 E-03 01/19 L.T. 1. E-02 01/16 01/23 9.85E+03 CU. FT. 2.9 +/- 0.3 E-02 1.7+/-1.1 E-03 01/29 L.T. 2. E-02 01/23 01/30 1.02E+04 CU. FT. 7.2 +/- 2.1 E-03 1.8 +/- 1.1 E-03 02/06 L.T. 3. E-02 01/30 02/06 1.01 E+04 CU. FT. 2.2 +/- 0.3 E-02 2.5+/-1.4 E-03 02/12 L.T. 3. E-02 02/06 02/12 8.23E+03 CU. FT. 1.8 +/- 0.3 E-02 L.T. 2. E-03 02/21 L.T. 4. E-02 02/12 02/20 (a) (a) (a) 02/20 02/28 (b) 1.7+/-0.1Ei01 1.5 +/- 0.6 E 00 03/05 L.T. 7. E+00 02/28 03/06 8.42E+03 CU. FT. 1.8 +/- 0.3 E-02 3.3+/- 1.6 E-03 03/14 L.T. 3. E-02 00 03/06 03/14 1.13E+04 CU. FT. 2.1 +/- 0.3 E-02 1.5+/-1.0 E-03 03/21 L.T. 2. E-02 03/14 03/21 9.32E+03 CU. FT. 5.5 +/- 0.5 E-02 3.1 +/-0.4 E-02 03/26 L.T. 2. E-02 03/21 03/27 8.98E+03 CU. FT. 5.6 +/- 2.6 E-03 L.T. 1. E-03 04/03 L.T. 3. E-02 03/27 04/03 1.OOE+04 CU. FT. 1.2 +/- 0.2 E-02 L.T. 1. E-03 04/06 L.T. 2. E-02 04/03 04/10 9.82E+03 CU. FT. 1.8 +/- 0.3 E-02 L.TI.1. E-03 04/13 L.T. 1. E-02 04/10 04/17 1.04E+04 CU. FT. 1.6 +/- 0.3 E-02 2.9+/- 1.4 E-03 04/23 L.T. 2. E-02 04/17 04/24 1.01 E+04 CU. FT. 1.8 +/- 0.3 E-02 2.9+/-1.4 E-03 05/01 L.T. 5. E-02 04/24 05/01 (d) (d) (d) 05/01 05/08 (d) (d) (d) 05/08 05/15 (d) (d) (d) 05/15 05/22 (b) 2.6 +/- 0.7 E 00 L.T. 5. E-01 05/24 L.T. 6. E+00 05/22 05/29 1.01 E+04 CU. FT. 1.1 +/-0.3E-02 L.T. 2. E-03 06/01 L.T. 3. E-02 05/29 06/05 1.01 E+04 CU. FT. 1.2 +/- 0.2 E-02 L.T. 2. E-03 06/08 L.T. 2. E-02 06/05 06/12 9.86E+03 CU. FT. 2.0 +/- 0.3 E-02 L.T. 1. E-03 06/19 L.T. 9. E-03 06/12 06/19 1.02E+04 CU. FT. 1.5 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 5. E-02 06/19 06/26 1.01 E+04 CU. FT. 6.5 +/- 0.5 E-02 3.8 +/- 0.4 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE &CHARCOAL FILTERS STATION NUMBER 04 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.90E+03 CU. FT. L.T. 3. E-03 1.3 +/- 1.1 E-03 07/09 L.T. 3. E-02 07/03 07/10 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 L.T. 2. E-03 07/12 L.T. 3. E-02 07/10 07/17 1.02E+04 CU. FT. 3.1 +/- 0.3 E-02 8.6 +/- 2.2 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.67E+03 CU. FT. 2.4 +/- 0.3 E-02 2.0 +/- 1.3 E-03 07/27 L.T. 4. E-02 07/24 07/31 9.92E+03 CU. FT. 2.2 +/- 0.3 E-02 L.T. 1. E-03 08/08 L.T. 3. E-02 07/31 08/07 9.02E+03 CU. FT. 2.3 +/- 0.3 E-02 L.T. 1. E-03 08/19 L.T. 3. E-02 08/07 08/14 8.90E+03 CU. FT. 2.7 +/- 0.4 E-02 1.6 +/- 1.2 E-03 08/22 L.T. 4. E-02 08/14 08/21 1.OOE+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 5. E-02 08/21 08/28 9.92E+03 CU. FT. 2.2 +/- 0.3 E-02 1.7+/-1.2 E-03 08/30 L.T. 3. E-02 08/28 09/04 9.76E+03 CU. FT. 2.8 +/- 0.3 E-02 L.T. 2. E-03 09/06 L.T. 1. E-02 09/04 09/11 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 2.8 +/- 1.6 E-03 09/19 L.T. 3. E-02 09/11 09/18 9.93E+03 CU. FT. 2.8 +/- 0.3 E-02 1.5 +/- 1.1 E-03 09/21 L.T. 2. E-02 09/18 09/25 9.37E+03 CU. FT. 2.4 +/- 0.3 E-02 3.0 +/- 1.6 E-03 09/28 L.T. 2. E-02 09/25 10/02 9.74E+03 CU. FT. 2.3 +/- 0.3 E-02 1.7 +/- 1.2 E-03 10/05 L.T. 3. E-02 10/02 10/09 1.02E+04 CU. FT. 2.5 +/- 0.3 E-02 2.5 +/- 1.6 E-03 10/12 L.T. 2. E-02 10/09 10/16 9.88E+03 CU. FT. 1.9 +/- 0.3 E-02 2.0 +/- 1.3 E-03 10/23 L.T. 3. E-02 10/16 10/23 1.02E+04 CU. FT. 3.0 +/- 0.3 E-02 3.1 +/- 1.5 E-03 10/30 L.T. 3. E-02 10/23 10/30 9.99E+03 CU. FT. 2.8 +/- 0.3 E-02 3.8 +/- 1.9 E-03 11/08 L.T. 3. E-02 10/30 11/06 9.94E+03 CU. FT. 2.8 +/- 0.3 E-02 2.5+/-1.3 E-03 11/15 L.T. 3. E-02 11/06 11/13 1.03E+04 CU. FT. 3.8 +/- 0.4 E-02 2.3 +/- 1.2 E-03 11/20 L.T. 4. E-02 11/13 11/20 1.OOE+04 CU. FT. 3.6 +/- 0.4 E-02 2.9 +/- 1.5 E-03 12/06 L.T. 4. E-02 11/20 11/27 1.02E+04 CU. FT. 2.7 +/- 0.3 E-02 L.T. 2. E-03 12/11 L.T. 4. E-02 11/27 12/04 9.98E+03 CU. FT. 2.6 +/- 0.3 E-02 2.5 +/- 1.5 E-03 12/13 L.T. 2. E-02 12/04 12/11 1.01 E+04 CU. FT. 1.7 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 4. E-02 12/11 12/18 9.84E+03 CU. FT. 3.3 +/- 0.4 E-02 4.6 +/- 1.7 E-03 12/26 L.T. 3. E-02 12/18 12/26 1.16E+04 CU. FT. 2.6 +/- 0.3 E-02 1.2 +/- 0.9 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 05 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 9.96E+03 CU. FT. 7.3 +/- 0.5 E-02 7.1 +/-2.3 E-03 01/08 L.T. 2. E-02 01/02 01/09 1.01 E+04 CU. FT. 3.2 +/- 0.3 E-02 3.6 +/- 1.7 E-03 01/17 L.T. 1. E-02 01/09 01/16 9.92E+03 CU. FT. 3.5 +/- 0.3 E-02 3.7 +/- 1.7 E-03 01/19 L.T. 1. E-02 01/16 01/23 9,91E+03 CU. FT. 4.6 +/- 0.4 E-02 2.0 +/- 1.2 E-03 01/29 L.T. 2. E-02 01/23 01/30 1.02E+04 CU. FT. 2.0 +/- 0,3 E-02 1.3 +/- 1.0 E-03 02/06 L.T. 3. E-02 01/30 02/06 1.01 E+04 CU. FT. 2.7 +/- 0.4 E-02 3.0 +/- 1.5 E-03 02/12 L.T. 3. E-02 02/06 02/12 8.23E+03 CU. FT. 2.5 +/- 0.4 E-02 1.9 +/- 1.5 E-03 02/21 L.T. 5. E-02 02/12 02/20 1.14E+04 CU. FT. 3.8 +/- 0.3 E-02 1.3 +/- 1.0 E-03 02/23 L.T. 3. E-02 02/20 02/28 1.17E+04 CU. FT. 2.6 +/- 0.3 E-02 2.2 +/- 1.4 E-03 03/05 L.T. 1. E-02 02/28 03/06 8.26E+03 CU. FT. 3.8 +/- 0.4 E-02 3.8 +/- 1.7 E-03 03/14 L.T. 3. E-02 03/06 03/14 1.13E+04 CU. FT. 2.2 +/- 0.3 E-02 2.0 +/- 1.1 E-03 03/21 L.T. 2. E-02 03/14 03/21 9.76E+03 CU. FT. 4.1 +/- 0.4 E-02 2.0 +/- 0.4 E-02 03/26 L.T. 3. E-02 03/21 03/27 8.93E+03 CU. FT. 2.0 +/- 0.4 E-02 2.5+/-1.6 E-03 04/03 L.T. 3. E-02 03/27 04/03 1.OOE+04 CU. FT. 1.7 +/- 0.3 E-02 1.7 +/- 1.2 E-03 04/06 L.T. 2. E-02 04/03 04/10 9.82E+03 CU. FT. 1.9 +/- 0.3 E-02 2.9 +/- 1.5 E-03 04/13 L.T. 1. E-02 04/10 04/17 1.03E+03 CU. FT. 1.7 +/- 0.3 E-02 2.6 +/- 1.3 E-03 04/23 L.T. 1. E-02 04/17 04/24 1.02E+04 CU. FT. 1.8 +/- 0.3 E-02 3.3+/-1.5 E-03 05/01 L.T. 5. E-02 04/24 05/01 9.52E+03 CU. FT. 2.5 +/- 0.3 E-02 3.3+/-1.5 E-03 05/08 L.T. 3. E-02 05/01 05/08 1.02E+04 CU. FT. 1.7 +/- 0.3 E-02 1.9 +/- 1.1 E-03 05/10 L.T. 2. E-02 05/08 05/15 9.10E+03 CU. FT. 2.7 +/- 0.3 E-02 5.9 +/- 1.9 E-03 05/17 L.T. 2. E-02 05/15 05/22 1.01 E+04 CU. FT. 1.6 +/- 0.3 E-02 1.7 +/- 1.4 E-03 05/24 L.T. 2. E-02 05/22 05/29 1.01 E+04 CU. FT. 8.1 +/- 2.4 E-03 L.T. 2. E-03 06/01 L.T. 3. E-02 05/29 06/05 1.03E+04 CU. FT. 1.0 +/- 0.2 E-02 L.T. 2. E-03 06/08 L.T. 2. E-02 06/05 06/12 9.86E+03 CU. FT. 1.8 +/- 0.3 E-02 1.9+/-1.3 E-03 06/19 L.T. 1. E-02 06/12 06/19 1.02E+04 CU. FT. 1.9 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 3. E-02 06/19 06/26 1.01 E+04 CU. FT. 5.4 +/- 0.4 E-02 2.3 +/- 0.4 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 05 COLL. TIME APEFILTER APFILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.91 E+03 CU. FT. 3.1 +/- 0.3 E-02 4.6 +/- 1.7 E-03 07/09 L.T. 3. E-02 07/03 07/10 1.01 E+04 CU. FT. 2.4 +/- 0.3 E-02 L.T. 2. E-03 07/12 L.T. 2. E-02 07/10 07/17 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 6.6 +/- 2.0 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.70E+03 CU. FT. 1.9 +/- 0.3 E-02 1.7+/-1.2 E-03 07/27 L.T. 3. E-02 07/24 07/31 1.01 E+04 CU. FT. 1.9 +/- 0.3 E-02 L.T. 1. E-03 08/08 L.T. 2. E-02 07/31 08/07 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 1.3 +/- 1.1 E-03 08/19 L.T. 3. E-02 08/07 08/14 1.OOE+04 CU. FT. 2.0 +/- 0.3 E-02 1.7 +/- 1.1 E-03 08/22 L.T. 2. E-02 08/14 08/21 1.01 E+04 CU. FT. 1.8 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 4. E-02 08/21 08/28 1.01 E+04 CU. FT. 1.6 +/- 0.3 E-02 1.4 +/- 1.1 E-03 08/30 L.T. 3. E-02 08/28 09/04 1.01 E+04 CU. FT. 2.2 +/- 0.3 E-02 1.8 +/- 1.3 E-03 09/06 L.T. 2. E-02 09/04 09/11 1.01 E+04 CU. FT. 1.9 +/- 0.3 E-02 L.T. 2. E-03 09/19 L.T. 3. E-02 09/11 09/18 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 1.9 +/- 1.2 E-03 09/21 L.T. 2. E-02 09/18 09/25 9.94E+03 CU. FT. 2.3 +/- 0.3 E-02 L.T. 1. E-03 09/28 L.T. 2. E-02 09/25 10/02 1.OOE+04 CU. FT. 1.7 +/- 0.3 E-02 2.0 +/- 1.2 E-03 10/05 L.T. 2. E-02 10/02 10/09 9.99E+03 CU. FT. 2.2 +/- 0.3 E-02 3.4 +/- 1.7 E-03 10/12 L.T. 2. E-02 10/09 10/16 9.88E+03 CU, FT. 1.5 +/- 0.3 E-02 2.3 +/- 1.3 E-03 10/23 L.T. 4. E-02 10/16 10/23 1.04E+04 CU. FT. 2.5 +/- 0.3 E-02 2.9 +/- 1.4 E-03 10/30 L.T. 2. E-02 10/23 10/30 9.84E+03 CU. FT. 2.3 +/- 0.3 E-02 2.6 +/- 1.7 E-03 11/08 L.T. 2. E-02 10/30 11/06 9.94E+03 CU, FT. 2.3 +/- 0.3 E-02 2.1 +/- 1.2 E-03 11/15 L.T. 1. E-02 11/06 11/13 1.03E+04 CU. FT. 3.3 +/- 0.3 E-02 3.3 +/- 1.4 E-03 11/20 L.T. 2. E-02 11/13 11/20 1.OOE+04 CU. FT. 3.9 +/- 0.4 E-02 3.4 +/- 1.6 E-03 12/06 L.T. 2. E-02 11/20 11/27 1.03E+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 12/11 L.T. 4. E-02 11/27 12/04 9.91 E+03 CU. FT. 2.2 +/- 0.3 E-02 L.T. 1. E-03 12/13 L.T. 2. E-02 12/04 12/11 1.02E+04 CU. FT. 2.8 +/- 0.3 E-02 2.5+/-1.7 E-03 12/18 L.T. 4. E-02 12/11 12/18 9,84E+03 CU. FT. 3.8 +/- 0.4 E-02 3.6 +/- 1.5 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.16E+04 CU. FT. 2.7 +/- 0.3 E-02 2.8 +/- 1.3 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 06 COLL. TIME APEFILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 9.76E+03 CU. FT. 6.4 +/- 0.5 E-02 7.5 +/- 2.4 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 4.1 +/- 1.8 E-03 01/17 L.T. 2. E-02 01/09 01/16 1.02E+04 CU. FT. 2.8 +/- 0.3 E-02 3.2 +/- 1.5 E-03 01/19 L.T. 1. E-02 01/16 01/23 9.91 E+03 CU. FT. 4.7 +/-+0.4 E-02 3.6 +/- 1.5 E-03 01/29 L.T. 3. E-02 01/23 01/30 1.02E+04 CU. FT. 1.7 +/-+0.3 E-02 2.2 +/- 1.2 E-03 02/06 L.T. 2. E-02 01/30 02/06 1.01 E+04 CU. FT. 1.7 +/- 0.3 E-02 2.3 +/- 1.3 E-03 02/12 L.T. 3. E-02 02/06 02/12 8.22E+03 CU. FT. 2.6 +/- 0.4 E-02 L.T. 2. E-03 02/21 L.T. 4. E-02 02/12 02/20 1.14E+04 CU. FT. 4.5 +/- 0.4 E-02 3.0 +/- 1.3 E-03 02/23 L.T. 2. E-02 02/20 02/28 1.14E+04 CU. FT. 2.8 +/- 0.3 E-02 1.8 +/- 1.3 E-03 03/05 L.T. 3. E-02 02/28 03/06 8.41 E+03 CU. FT. 2.1 +/- 0.3 E-02 2.0 +/- 1.3 E-03 03/14 L.T. 5. E-02 03/06 03/14 1.13E+04 CU. FT. 1.6 +/- 0.3 E-02 L.T. 9. E-04 03/21 L.T. 2. E-02 03/14 03/21 1.02E+04 CU. FT. 4.2 +/- 0.4 E-02 2.2 +/- 0.4 E-02 03/26 L.T. 3. E-02 03/21 03/27 8.93E+03 CU. FT. 1.3 +/- 0.3 E-02 L.T. 1. E-03 04/03 L.T. 4. E-02 03/27 04/03 1.OOE+04 CU. FT. 1.9 +/- 0.3 E-02 2.7 +/- 1.4 E-03 04/06 L.T. 1. E-02 04/03 04/10 9.82E+03 CU. FT. 9.4 +/- 2.3 E-03 L.T. 1. E-03 04/13 L.T. 1. E-02 04/10 04/17 1.03E+03 CU. FT. 9.3 +/- 2.2 E-03 1.9 +/- 1.2 E-03 04/23 L.T. 5. E-02 04/17 04/24 1.02E+04 CU. FT. 1.8 +/- 0.3 E-02 1.5 +/- 1.1 E-03 05/01 L.T. 3. E-02 04/24 05/01 9.88E+03 CU. FT. 1.8 +/- 0.3 E-02 3.7 +/- 1.5 E-03 05/08 L.T. 2. E-02 05/01 05/08 9.96E+03 CU. FT. 1.2 +/- 0.2 E-02 1.4 +/- 1.0 E-03 05/10 L.T. 2. E-02 05/08 05/15 9.10E+03 CU. FT. 2.7 +/- 0.3 E-02 6.8 +/- 2.1 E-03 05/17 L.T. 2. E-02 05/15 05/22 1.OIE+04 CU. FT. 1.4 +/-0.3 E-02 2.7 +/- 1.6 E-03 05/24 L.T. 2. E-02 05/22 05/29 1.01 E+04 CU. FT. 1.0 +/- 0.3 E-02 L.T. 2. E-03 06/01 L.T. 3. E-02 05/29 06/05 1.03E+04 CU. FT. 8.2 +/- 2.2 E-03 L.T. 2. E-03 06/08 L.T. 4. E-02 06/05 06/12 9.86E+03 CU. FT. 1.5 +/- 0.3 E-02 L.T. 1. E-03 06/19 L.T. 1. E-02 06/12 06/19 1.02E+04 CU. FT. 1.9 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 3. E-02 06/19 06/26 1.01 E+04 CU. FT. 4.4 +/- 0.4 E-02 1.6 +/- 0.3 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 06 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.91 E+03 CU. FT. 3.0 +/- 0.3 E-02 5.8 +/- 1.9 E-03 07/09 L.T. 2. E-02 07/03 07/10 1.01 E+04 CU. FT. 2.3 +/- 0.3 E-02 2.2 +/- 1.6 E-03 07/12 L.T. 2. E-02 07/10 07/17 1.04E+04 CU. FT. 2.5 +/- 0.3 E-02 5.0 +/- 1.7 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.70E+03 CU. FT. 1.4 +/- 0.3 E-02 1.3+/- 1.1 E E-03 07/27 L.T. 3. E-02 07/24 07/31 1.01E+04 CU. FT. 1.9 +/-+0.3 E-02 1.6 +/- 1.2 E-03 08/08 L.T. 3. E-02 07/31 08/07 9.88E+03 CU. FT. 2.6 +/- 0.3 E-02 2.6 +/- 1.4 E-03 08/19 L.T. 3. E-02 08/07 08/14 9.64E+03 CU. FT. 3.0 +/- 0.3 E-02 1.8 +/- 1.2 E-03 08/22 L.T. 4. E-02 08/14 08/21 1.01E+04 CU. FT. 2.5 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 4. E-02 08/21 08/28 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 2.2 +/- 1.2 E-03 08/30 L.T. 3. E-02 08/28 09/04 1.01E+04 CU. FT. 2.7 +/- 0.3 E-02 1.6+/-1.3 E-03 09/06 L.T. 2. E-02 09/04 09/11 1.02E+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 09/19 L.T. 3. E-02 09/11 09/18 1.01 E+04 CU. FT. 3.1 +/- 0.3 E-02 L.T. 1. E-03 09/21 L.T. 2. E-02 09/18 09/25 9,94E+03 CU. FT. 2.5 +/- 0.3 E-02 L.T. 1. E-03 09/28 L.T. 3. E-02 09/25 10/02 1.02E+04 CU. FT. 2.4 +/- 0.3 E-02 1.7+/-1.1 E-03 10/05 L.T. 2. E-02 10/02 10/09 1.02E+04 CU. FT. 2.4 +/- 0.3 E-02 3.6 +/- 1.8 E-03 10/12 L.T. 2. E-02 10/09 10/16 9.88E+03 CU. FT. 1.9 +/- 0.3 E-02 2.0 +/- 1.3 E-03 10/23 L.T. 3. E-02 10/16 10/23 1.04E+04 CU. FT. 1.0 +/- 0.2 E-02 2.0 +/- 1.2 E-03 10/30 L.T. 3. E-02 10/23 10/30 1.OOE+04 CU. FT. 2.6 +/- 0.3 E-02 L.T. 2. E-03 11/08 L.T. 3. E-02 10/30 11/06 9.96E+03 CU. FT. 2.5 +/- 0.3 E-02 2.9+/- 1.3 E-03 11/15 L.T. 2. E-02 11/06 11/13 1.03E+04 CU. FT. 4.1 +/- 0.4 E-02 3.7+/- 1.5 E-03 11/20 L.T. 2. E-02 11/13 11/20 1.OOE+04 CU. FT. 3.8 +/- 0.4 E-02 5.5+/-1.9 E-03 12/07 L.T. 3. E-02 11/20 11/27 1.03E+04 CU. FT. 1.0 +/- 0.2 E-02 L.T. 2. E-03 12/11 L.T. 4. E-02 11/27 12/04 9.91 E+03 CU. FT. 2.8 +/- 0.3 E-02 2.4+/-1.5 E-03 12/13 L.T. 5. E-02 12/04 12/11 1.02E+04 CU. FT. 2.6 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 5. E-02 12/11 12/18 9.84E+03 CU. FT. 4.7 +/- 0.4 E-02 3.4+/-1.5 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.16E+04 CU. FT. 2.8 +/- 0.3 E-02 1.9 +/- 1.1 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 07 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 9.31 E+03 CU. FT. 8.0 +/- 0.5 E-02 6.1 +/-2.2 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01E+04 CU. FT. 2.2 +/- 0.3 E-02 L.T. 2. E-03 01/17 L.T. 2. E-02 01/09 01/16 9.10E+03 CU. FT. 5.2 +/- 0.4 E-02 5.7 +/- 2.1 E-03 01/19 L.T. 2. E-02 01/16 01/23 1.01 E+04 CU. FT. 5.8 +/- 0.4 E-02 2.7 +/- 1.3 E-03 01/29 L.T. 3. E-02 01/23 01/30 1.01 E+04 CU. FT. 1.9 + 0.3 E-02 1.6 +/- 1.0 E-03 02/06 L.T. 3. E-02 01/30 02/06 1.01 E+04 CU. FT. 3.0 + 0.4 E-02 1.8+/- 1.2 E-03 02/12 L.T. 4. E-02 02/06 02/12 5.80E+03 CU. FT. 4.6 + 0.6 E-02 2.9 +/- 2.2 E-03 02/21 L.T. 6. E-02 02/12 02/20 1.15E+04 CU. FT. 5.1 + 0.4 E-02 4.1 +/- 1.5 E-03 02/23 L.T. 2. E-02 02/20 02/28 1.12E+04 CU. FT. 2.8 + 0.3 E-02 2.7+/-1.5 E-03 03/05 L.T. 3. E-02 02/28 03/06 6.26E+03 CU. FT. 4.7 _ 0.5 E-02 8.4 +/- 2.8 E-03 03/14 L.T. 5. E-02 03/06 03/13 1.01 E+04 CU. FT. 1.8 + 0.3 E-02 1.3 +/- 1.0 E-03 03/21 L.T. 3. E-02 03/13 03/21 1.07E+04 CU. FT. 4.1 + 0.4 E-02 2.1 +/- 0.3 E-02 03/26 L.T. 3. E-02 03/21 03/27 8.72E+03 CU. FT. 2.4 + 0.4 E-02 1.9 +/- 1.4 E-03 04/03 L.T. 4. E-02 03/27 04/03 1.02E+04 CU. FT. 1.0 + 0.2 E-02 1.8 +/- 1.2 E-03 04/06 L.T. 1. E-02 04/03 04/10 9.84E+03 CU. FT. 2.3 + 0.3 E-02 3.0 +/- 1.5 E-03 04/13 L.T. 2. E-02 04/10 04/17 1.02E+02 CU. FT. 1.6 + 0.3 E-02 2.2 +/- 1.2 E-03 04/23 L.T. 2. E-02 04/17 04/24 9.88E+03 CU. FT. 9.9 + 2.5 E-03 2.0+/-1.2 E-03 05/01 L.T. 4. E-02 04/24 05/01 9.92E+03 CU. FT. 2.8 0.3 E-02 2.9 +/- 1.3 E-03 05/08 L.T. 2. E-02 05/01 05/08 1.01E+04 CU. FT. 1.7 + 0.3 E-02 2.6 +/- 1.3 E-03 05/10 L.T. 2. E-02 05/08 05/15 9.96E+03 CU. FT. 3.3 + 0.4 E-02 7.0 +/- 2.0 E-03 05/17 L.T. 8. E-03 05/15 05/22 1.01 E+04 CU. FT. 2.5 + 0.3 E-02 2.4 +/- 1.5 E-03 05/24 L.T. 2. E-02 05/22 05/29 1.01 E+04 CU. FT. 1.1 + 0.3 E-02 L.T. 2. E-03 06/01 L.T. 2. E-02 05/29 06/05 1.03E+04 CU. FT. 1.1 + 0.2 E-02 L.T. 2. E-03 06/08 L.T. 3. E-02 06/05 06/12 9.81 E+03 CU. FT. 2.2 +/- 0.3 E-02 2.1 +/- 1.4 E-03 06/19 L.T. 1. E-02 06/12 06/19 1.02E+04 CU. FT. 1.7 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 4. E-02 06/19 06/26 1.01 E+04 CU. FT. 2.8 +/- 0.3 E-02 1.1 +/-0.2 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 07 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.97E+03 CU. FT. 2.4 +/- 0.3 E-02 5.1 +/- 1.8 E-03 07/09 L.T. 1. E-02 07/03 07/10 1.OOE+04 CU. FT. 2.2 +/-+0.3 E-02 L.T. 2. E-03 07/12 L.T. 2. E-02 07/10 07/17 9.80E+03 CU. FT. 2.1 +/- 0.3 E-02 4.5 +/- 1.7 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.90E+03 CU. FT. 2.0 +/- 0.3 E-02 2.3 +/- 1.3 E-03 07/27 L.T. 2. E-02 07/24 07/31 1.01E+04 CU. FT. 1.4 +/- 0.3 E-02 2.3 +/- 1.4 E-03 08/08 L.T. 3. E-02 07/31 08/07 1.01 E+04 CU. FT. 2.5 +/- 0.3 E-02 1.3 +/- 1.1 E-03 08/19 L.T. 3. E-02 08/07 08/14 1.02E+04 CU. FT. 2.3 +/- 0.3 E-02 2.4+/-1.3 E-03 08/22 L.T. 3. E-02 08/14 08/21 1.01E+04 CU. FT. 2.0 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 4. E-02 08/21 08/28 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 2.2+/-1.2 E-03 08/30 L.T. 3. E-02 08/28 09/04 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 1.8 +/- 1.3 E-03 09/06 L.T. 2. E-02 09/04 09/11 1.01 E+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 09/19 L.T. 4. E-02 09/11 09/18 1.OOE+04 CU. FT. 2.8 +/- 0.3 E-02 2.7+/-1.4 E-03 09/21 L.T. 2. E-02 09/18 09/25 1.OOE+04 CU. FT. 2.6 +/- 0.3 E-02 2.0+/-1.3 E-03 09/28 L.T. 3. E-02 09/25 10/02 9.98E+03 CU. FT. 2.1 +/- 0.3 E-02 1.2+/-1.0 E-03 10/05 L.T. 2. E-02 10/02 10/09 1.02E+04 CU. FT. 2.1 +/- 0.3 E-02 2.4+/-1.5 E-03 10/12 L.T. 2. E-02 10/09 10/16 9.90E+03 CU. FT. 1.5 +/- 0.3 E-02 2.5+/-1.4 E-03 10/23 L.T. 3. E-02 10/16 10/23 1.04E+04 CU. FT. 9.7 +/- 2.3 E-03 1.9 +/- 1.2 E-03 10/30 L.T. 3. E-02 10/23 10/30 9.79E+03 CU. FT. 2.6 +/- 0.3 E-02 3.5 +/- 1.8 E-03 11/08 L.T. 3. E-02 10/30 11/06 9.66E+03 CU. FT. 2.8 +/- 0.3 E-02 3.0 +/- 1.4 E-03 11/15 L.T. 2. E-02 11/06 11/13 9.80E+03 CU. FT. 3.3 +/- 0.4 E-02 3.3 +/- 1.4 E-03 11/20 L.T. 2. E-02 11/13 11/20 9.89E+03 CU. FT. 2.4 +/- 0.3 E-02 2.8 +/- 1.5 E-03 12/07 L.T. 3. E-02 11/20 11/27 1.02E+04 CU. FT. 3.0 +/--0.3 E-0 2.5 +/- 1.6 E-03 12/11 L.T. 4. E-02 11/27 12/04 9.93E+03 CU. FT. 1.5 +/-+0.3 E-02 2,1 +/- 1.4 E-03 12/13 L.T. 5. E-02 12/04 12/11 9.94E+03 CU. FT. 1.9 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 5. E-02 12/11 12/18 9.88E+03 CU. FT. 2.1 +/- 0.3 E-02 1.3+/-1.0 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.16E+04 CU. FT. 2.7 +/- 0.3 E-02 2.1 +/- 1.1 E-03 01/04 L.T. 4. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 08 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 1.OOE+04 CU. FT. 2.7 +/- 0.3 E-02 2.4+/- 1.6 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01 E+04 CU. FT. 2.4 +/- 0.3 E-02 3.4+/-1.7 E-03 01/17 L.T. 2. E-02 01/09 01/16 9.96E+03 CU. FT. 1.7 +/- 0.3 E-02 2.7+/-1.5 E-03 01/19 L.T. 2. E-02 01/16 01/23 1.01 E+04 CU. FT. 1.4 +/- 0.3 E-02 1.9 +/- 1.1 E-03 01/29 L.T. 3. E-02 01/23 01/30 (a) (a) (a) 01/30 02/06 (a) (a) (a) 02/06 02/12 (a) (a) (a) 02/12 02/20 (b) (b) (c) (c) 02/20 02/28 1.14E+04 CU. FT. 8.5 +/- 2.5 E-03 L.T. 1. E-03 03/05 L.T. 3. E-02 02/28 03/06 8.56E+03 CU. FT. 8.9 +/- 2.6 E-03 1.5 +/- 1.1 E-03 03/14 L.T. 5. E-02 03/06 03/14 1.14E+04 CU. FT. 6.7 +/- 1.9 E-03 L.T. 9. E-04 03/21 L.T. 2. E-02 03/14 03/21 1.02E+04 CU. FT. 1.5 +/-+0.3 E-02 4.4 +/- 1.8 E-03 03/26 L.T. 3. E-02 03/21 03/27 8.93E+03 CU. FT. 5.3 +/- 2.6 E-03 1.3+/-1.3 E-03 04/03 L.T. 4. E-02 03/27 04/03 (a) (a) (a) 04/03 04/10 (b) 3.3 +/- 0.7 E 00 4.8 +/- 3.4 E-01 04/13 04/10 04/17 1.01E+01 CU. FT. 5.3 +/- 2.0 E-03 L.T. 9. E-04 04/23 L.T. 2. E-02 04/17 04/24 1.01E+04 CU. FT. 4.2 +/- 2.1 E-03 L.T. 1. E-03 05/01 L.T. 4. E-02 04/24 05/01 1.03E+04 CU. FT. 2.7 +/- 0.3 E-02 1.5+/-1.0 E-03 05/08 L.T. 2. E-02 05/01 05/08 9.70E+03 CU. FT. 1.7 +/- 0.3 E-02 2.0+/- 1.2 E-03 05/10 L.T. 2. E-02 05/08 05/15 1.OOE+04 CU. FT. 2.4 +/- 0.3 E-02 3.4+/-1.4 E-03 05/17 L.T. 7. E-03 05/15 05/22 9.90E+03 CU. FT. 1.8 +/- 0.3 E-02 2.0+/-1.5 E-03 05/24 L.T. 3. E-02 05/22 05/29 1.01 E+04 CU. FT. 6.4 +/- 2.3 E-03 L.T. 2. E-03 06/01 L.T. 4. E-02 05/29 06/05 (a) (a) (a) 06/05 06/12 (b) 8.1 +/- 0.9 E 00 L.T. 4. E-01 06/19 L.T. 1. E+01 06/12 06/19 1.02E+04 CU. FT. 1.8 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 3. E-02 06/19 06/26 1.01 E+04 CU. FT. 4.4 +/- 0.4 E-02 1.8 +/- 0.3 E-02 06/29 L.T. 1. E+01 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 08 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.34E+03 CU. FT. 2.0 +/- 0.3 E-02 3.2 +/- 1.5 E-03 07/09 L.T. 1. E-02 07/03 07/10 1.OOE+04 CU. FT. 2.3 +/- 0.3 E-02 2.0 +/- 1.6 E-03 07/12 L.T. 2. E-02 07/10 07/17 8.56E+03 CU. FT. 2.5 +/- 0.4 E-02 2.4+/-1.5 E-03 07/23 L.T. 4. E-02 07/17 07/24 9.94E+03 CU. FT. 2.5 +/- 0.3 E-02 4.6+/-1.8 E-03 07/27 L.T. 3. E-02 07/24 07/31 1.OOE+04 CU. FT. 2.2 +/- 0.3 E-02 2.1 +/- 1.3 E-03 08/08 L.T. 3. E-02 07/31 08/07 9.63E+03 CU. FT. 2.7 +/- 0.3 E-02 1.6 +/- 1.2 E-03 08/19 L.T. 3. E-02 08/07 08/14 1.OOE+04 CU. FT. 2.4 +/- 0.3 E-02 3.1 +/- 1.4 E-03 08/22 L.T. 3. E-02 08/14 08/21 1.01E+04 CU. FT. 2.4 +/- 0.3 E-02 1.9 +/- 1.4 E-03 08/29 L.T. 4. E-02 08/21 08/28 1.01E+04 CU. FT. 2.1 +/- 0.3 E-02 1.2 +/- 1.0 E-03 08/30 L.T. 2. E-02 08/28 09/04 9.91 E+03 CU. FT. 2.5 +/- 0.3 E-02 1.7+/-1.3 E-03 09/06 L.T. 2. E-02 09/04 09/11 9.51 E+03 CU. FT. 2.4 +/- 0.3 E-02 3.1 +/- 1.8 E-03 09/19 L.T. 4. E-02 09/11 09/18 1.01 E+04 CU. FT. 2.6 +/- 0,3 E-02 2.5 +/- 1.3 E-03 09/21 L.T. 1. E-02 09/18 09/25 1.OOE+04 CU. FT. 2.8 +/- 0.3 E-02 1.8+/-1.3 E-03 09/28 LT. 3. E-02 09/25 10/02 9.41 E+03 CU. FT. 2.5 +/- 0.3 E-02 2.1 +/- 1.3 E-03 10/05 L.T. 2. E-02 10/02 10/09 9.78E+03" CU. FT. 2.6 +/- 0.3 E-02 2.2 +/- 1.6 E-03 10/12 L.T. 2. E-02 10/09 10/16 1.02E+04 CU. FT. 1.8 +/- 0.3 E-02 2.3 +/- 1.3 E-03 10/23 L.T. 3. E-02 10/16 10/23 9.97E+03 CU. FT. 2.4 +/- 0.3 E-02 1.8 +/- 1.2 E-03 10/30 L.T. 4. E-02 10/23 10/30 1.02E+04 CU. FT. 2.7 +/-+0.3 E-02 3.6 +/- 1.8 E-03 11/08 L.T. 3. E-02 10/30 11/06 9.76E+03 CU. FT. 1.8 +/- 0.3 E-02 1.3+/-1.0 E-03 11/15 L.T. 2. E-02 11/06 11/13 1.01 E+04 CU. FT, 3.6 +/- 0.4 E-02 4.3 +/- 1.6 E-03 11/20 L.T. 2. E-02 11/13 11/20 1.01 E+04 CU. FT. 4.4 +/- 0.4 E-02 5.7+/- 1.9 E-03 12/07 L.T. 3. E-02 11/20 11/27 1.01 E+04 CU. FT. 2.6 +/- 0.3 E-02 2.5 +/- 1.6 E-03 12/11 L.T. 4. E-02 11/27 12/04 1.OOE+04 CU. FT. 2.9 +/- 0.3 E-02 L.T. 1. E-03 12/13 L.T. 5. E-02 12/04 12/11 1.OOE+04 CU. FT. 2.3 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 5. E-02 12/11 12/18 9.80E+03 CU. FT. 4.4 +/- 0.4 E-02 5.8 +/- 1.9 E-03 12/26 L.T. 3. E-02 12118 12/26 1.14E+04 CU. FT. 2.0 +/- 0.3 E-02 1.6 +/- 1.0 E-03 01/04 L.T. 5. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 09 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 9.80E+03 CU. FT. 6.1 +/- 0.5 E-02 8.8 +/- 2.5 E-03 01/08 L.T. 3. E-02 01/02 01/09 1.01E+04 CU. FT. 2.5 +/- 0.3 E-02 L.T. 2. E-03 01/17 L.T. 2. E-02 01/09 01/16 1.01 E+04 CU. FT. 3.4 +/- 0.3 E-02 5.2+/-1.9 E-03 01/19 L.T. 1. E-02 01/16 01/23 1.00E+04 CU. FT. 4.3 +/- 0.4 E-02 3.0 +/- 1.4 E-03 01/29 L.T. 3. E-02 01/23 01/30 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 1.6+/- 1.0 E-03 02/06 L.T. 2. E-02 01/30 02/06 1.OOE+04 CU. FT. 2.2 +/- 0.3 E-02 2.0+/-1.3 E-03 02/12 L.T. 4. E-02 02/06 02/12 8.36E+03 CU. FT. 2.5 +/- 0.4 E-02 L.T. 2. E-03 02/21 L.T. 5. E-02 02/12 02/20 1.12E+04 CU. FT. 2.9 +/- 0.3 E-02 2.2+/-1.2 E-03 02/23 L.T. 2. E-02 02/20 02/28 1.12E+03 CU. FT. 3.1 +/- 0.4 E-02 2.4 +/- 1.5 E-03 03/05 L.T. 3. E-02 02/28 03/06 6.32E+03 CU. FT. 4.1 +/- 0.5 E-02 4.6 +/- 2.1 E-03 03/14 L.T. 5. E-02 00 03/06 03/14 1.14E+04 CU. FT. 2.2 +/- 0.3 E-02 1.0 +/- 0.9 E-03 03/21 L.T. 5. E-02 03/14 03/21 9.86E+03 CU. FT. 2.4 +/- 0.3 E-02 7.0 +/- 2.2 E-03 03/26 L.T. 4. E-02 03/21 03/27 8.94E+03 CU. FT. 1.9 +/- 0.3 E-02 L.T. 1. E-03 04/03 L.T. 4. E-02 03/27 04/03 1.OOE+04 CU. FT. 1.5 +/- 0.3 E-02 1.8 +/- 1.2 E-03 04/06 L.T. 1. E-02 04/03 04/10 9.85E+03 CU. FT. 1.7 +/- 0.3 E-02 2.3 +/- 1.3 E-03 04/13 L.T. 2. E-02 04/10 04/17 9.94E+03 CU. FT. 1.3 +/- 0.2 E-02 L.T. 9. E-04 04/23 L.T. 3. E-02 04/17 04/24 1.02E+04 CU. FT. 1.7 +/-+0.3 E-02 3.5 +/- 1.5 E-03 05/01 L.T. 3. E-02 04/24 05/01 1.01E+04 CU. FT. 2.3 +/- 0.3 E-02 2.5 +/- 1.2 E-03 05/08 L.T. 2. E-02 05/01 05/08 9.72E+03 CU. FT. 1.2 +/-+0.3 E-02 1.2 +/- 1.0 E-03 05/10 L.T. 2. E-02 05/08 05/15 9.99E+03 CU. FT. 2.3 +/-+0.3 E-02 3.1 +/- 1.4 E-03 05/17 L.T. 8. E-03 05/15 05/22 1.OOE+04 CU. FT. 1.7 +/- 0.3 E-02 1.7 +/- 1.4 E-03 05/24 L.T. 2. E-02 05/22 05/29 1.01 E+04 CU. FT. 8.3 +/- 2.5 E-03 L.T. 2. E-03 06/01 L.T. 2. E-02 05/29 06/05 1.03E+04 CU. FT. 1.1 +/- 0.2 E-02 L.T. 2. E-03 06/08 L.T. 3. E-02 06/05 06/12 9.82E+03 CU. FT. 1.6 +/- 0.3 E-02 L.T. 1. E-03 06/19 L.T. 1. E-02 06/12 06/19 1.02E+04 CU. FT. 1.7 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 4. E-02 06/19 06/26 1.01 E+04 CU. FT. 3.5 +/- 0.4 E-02 1.1 +/-0.2 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE &CHARCOAL FILTERS STATION NUMBER 09 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.97E+03 CU. FT. 2.4 +/- 0.3 E-02 5.0 +/- 1.7 E-03 07/09 L.T. 1. E-02 07/03 07/10 1.01 E+04 CU. FT. 2.4 +/- 0.3 E-02 2.0+/-1.6 E-03 07/12 L.T. 2. E-02 07/10 07/17 1.02E+04 CU. FT. 2.2 +/- 0.3 E-02 2.7+/-1.4 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.93E+03 CU. FT. 2.0 +/- 0.3 E-02 L.T. 1. E-03 07/27 L.T. 3. E-02 07/24 07/31 9.84E+03 CU. FT. 2.3 +/- 0.3 E-02 L.T. 1. E-03 08/08 L.T. 3. E-02 07/31 08/07 1.01 E+04 CU. FT. 2.3 +/- 0.3 E-02 2.3 +/- 1.3 E-03 08/19 L.T. 4. E-02 08/07 08/14 9.81 E+03 CU. FT. 2.1 +/- 0.3 E-02 2.0 +/- 1.2 E-03 08/22 L.T. 4. E-02 08/14 08/21 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 L.T. 2. E-03 08/29 L.T. 5. E-02 08/21 08/28 1.01 E+04 CU. FT. 2.2 +/- 0.3 E-02 L.T. 1. E-03 08/30 L.T. 1. E-02 08/28 09/04 1.01 E+04 CU. FT. 2.5 +/- 0.3 E-02 1.7 +/- 1.3 E-03 09/06 L.T. 3. E-02 09/04 09/11 1.02E+04 CU. FT. 2.4 +/- 0.3 E-02 L.T. 2. E-03 09/19 L.T. 3. E-02 09/11 09/18 1.01 E+04 CU. FT. 2.5 +/- 0.3 E-02 2.9 +/- 1.4 E-03 09/21 L.T. 1. E-02 09/18 09/25 1.OOE+04 CU. FT. 2.2 +/- 0.3 E-02 L.T. 1. E-03 09/28 L.T. 3. E-02 09/25 10/02 1.02E+04 CU. FT. 2.4 +/- 0.3 E-02 2.2 +/- 1.2 E-03 10/05 L.T. 2. E-02 10/02 10/09 1.02E+04 CU. FT. 2.5 +/- 0.3 E-02 1.9 +/- 1.5 E-03 10/12 L.T. 3. E-02 10/09 10/16 9.98E+03 CU. FT. 1.7 +/-0.3 E-02 2.0 +/- 1.3 E-03 10/23 L.T. 2. E-02 10/16 10/23 1.04E+04 CU. FT. 8.6 +/- 2.2 E-03 L.T. 1. E-03 10/30 L.T. 3. E-02 10/23 10/30 1.01 E+04 CU. FT. 2.4 +/- 0.3 E-02 L.T. 2. E-03 11/08 L.T. 3. E-02 10/30 11/06 9.82E+03 CU. FT. 2.3 +/- 0.3 E-02 2.5 +/- 1.3 E-03 11/15 L.T. 2. E-02 11/06 11/13 1.03E+04 CU. FT. 3.0+/-0.3E-02 1.8 +/- 1.1 E-03 11/20 L.T. 2. E-02 11/13 11/20 1.02E+04 CU. FT. 3.8 +/- 0.4 E-02 4.2 +/- 1.7 E-03 12/07 L.T. 3. E-02 11/20 11/27 1.01 E+04 CU. FT. 3.2 +/- 0.3 E-02 2.1 +/- 1.6 E-03 12/11 L.T. 3. E-02 11/27 12/04 1.OOE+04 CU. FT. 3.1 +/- 0.3 E-02 2.1 +/- 1.4 E-03 12/13 L.T. 5. E-02 12/04 12/11 1.OOE+04 CU. FT. 2.2 +/- 0.3 E-02 2.1 +/- 1.7 E-03 12/18 L.T. 4. E-02 12/11 12/18 9.94E+03 CU. FT. 3.6 +/- 0.4 E-02 2.8+/-1.4 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.14E+04 CU. FT. 2.3 +/- 0.3 E-02 2.4+/-1.2 E-03 01/04 L.T. 5. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VIl-i NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 10 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

12/26 01/02 1.OOE+04 CU. FT. 5.1 +/- 0.4 E-02 4.8 +/- 2.0 E-03 01/08 L.T. 2. E-02 01/02 01/09 1.OOE+04 CU. FT. 2.4 +/- 0.3 E-02 2.5 +/- 1.5 E-03 01/17 L.T. 2. E-02 01/09 01/16 9.99E+03 CU. FT. 2.3 +/- 0.3 E-02 2.0 +/- 1.3 E-03 01/19 L.T. 1. E-02 01/16 01/23 1.01 E+04 CU. FT. 3.2 +/- 0.3 E-02 2.7+/-1.3 E-03 01/29 L.T. 2. E-02 01/23 01/30 1.01 E+04 CU. FT. 1.2 +/- 0.2 E-02 1.2 +/- 0.9 E-03 02/06 L.T. 2. E-02 01/30 02/06 1.01 E+04 CU. FT. 1.3 +/- 0.3 E-02 2.3 +/- 1.3 E-03 02/12 L.T. 4. E-02 02106 02/12 6.93E+03 CU. FT. 1.5 +/- 0.3 E-02 L.T. 2. E-03 02/21 L.T. 5. E-02 02/12 02/20 1.15E+04 CU. FT. 3.5 +/- 0.3 E-02 2.8 +/- 1.3 E-03 02/23 L.T. 2. E-02 02/20 02/28 1.15E+04 CU. FT. 1.9 +/- 0.3 E-02 2.0 +/- 1.4 E-03 03/05 L.T. 2. E-02 02/28 03/06 8.56E+03 CU. FT. 2.4 +/- 0.3 E-02 2.8 +/- 1.4 E-03 03/14 L.T. 4. E-02 03/06 03/14 1.14E+04 CU. FT. 1.3 +/- 0.2 E-02 L.T. 9. E-04 03/21 L.T. 4. E-02 03/14 03/21 1.02E+04 CU. FT. 2.0 +/- 0.3 E-02 7.3 +/- 2.2 E-03 03/26 L.T. 4. E-02 03/21 03/27 8.95E+03 CU. FT. 1.4 +/- 0.3 E-02 3.0 +/- 1.7 E-03 04/03 L.T. 4. E-02 03/27 04/03 1.OOE+04 CU. FT. 9.7 +/- 2.3 E-03 L.T. 1. E-03 04/06 L.T. 1. E-02 04/03 04/10 9.84E+03 CU. FT. 1.3 +/-0.3 E-02 2.4 +/- 1.4 E-03 04/13 L.T. 2. E-02 04/10 04/17 1.02E+04 CU. FT. 1.3 +/-0.2 E-02 9.7 +/- 9.2 E-04 04/23 L.T. 2. E-02 04/17 04/24 9.90E+03 CU. FT. 1.1 +/-0.3E-02 1.6 +/- 1.1 E-03 05/01 L.T. 2. E-02 04/24 05/01 1.02E+04 CU. FT. 2.2 +/- 0.3 E-02 3.1 +/- 1.4 E-03 05/08 L.T. 2. E-02 05/01 05/08 1.01 E+04 CU. FT. 1.7 +/- 0.3 E-02 1.0 +/- 0.9 E-03 05/10 L.T. 1. E-02 05/08 05/15 9.97E+03 CU. FT. 1.9 +/- 0.3 E-02 2.0 +/- 1.1 E-03 05/17 L.T. 9. E-03 05/15 05/22 I.OOE+04 CU. FT. 1.3 +/- 0.3 E-02 1.8 +/- 1.4 E-03 05/24 L.T. 2. E-02 05/22 05129 1.01E+04 CU. FT. 7.9 +/- 2.4 E-03 L.T. 2. E-03 06/01 L.T. 4. E-02 05/29 06/05 1.03E+04 CU. FT. 9.5 +/- 2.3 E-03 L.T. 2. E-03 06/08 L.T. 3. E-02 06/05 06/12 9.81 E+03 CU. FT. 2.1 +/- 0.3 E-02 L.T. 1. E-03 06/19 L.T. 1. E-02 06/12 06/19 1.02E+04 CU. FT. 1.4 +/- 0.3 E-02 L.T. 2. E-03 06/27 L.T. 4. E-02 06/19 06/26 1.01E+04 CU. FT. 3.4 +/- 0.3 E-02 1.1 +/-0.2 E-02 06/29 L.T. 2. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-1 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE AIR PARTICULATE & CHARCOAL FILTERS STATION NUMBER 10 COLL. TIME AP FILTER AP FILTER CHARCOAL FILTER START STOP SAMPLE GROSS BETA GROSS ALPHA MID-COUNT 1-131 DATE DATE VOLUME UNITS (PCI/CU.M.) (PCI/CU.M.) DATE (PCI/CU.M.)

06/26 07/03 9.96E+03 CU. FT. 2.9 +/- 0.3 E-02 6.3 +/- 1.9 E-03 07/09 L.T. 1. E-02 07/03 07/10 1.01 E+04 CU. FT. 2.0 + 0.3 E-02 3.3 +/- 1.8 E-03 07/12 L.T. 2. E-02 07/10 07/17 1.03E+04 CU. FT. 2.0 +/- 0.3 E-02 2.9+/- 1.4 E-03 07/23 L.T. 3. E-02 07/17 07/24 9.80E+03 CU. FT. 2.0 +/- 0.3 E-02 2.7+/-1.4 E-03 07/27 L.T. 2. E-02 07/24 07/31 1.01 E+04 CU. FT. 2.0 +/- 0.3 E-02 1.7+/- 1.2 E-03 08/08 L.T. 2. E-02 07/31 08/07 1.01 E+04 CU. FT. 3.0 +/- 0.3 E-02 2.6 +/- 1.4 E-03 08/19 L.T. 4. E-02 08/07 08/14 1.OOE+04 CU. FT. 2.7 +/- 0.3 E-02 3.3 +/- 1.5 E-03 08/22 L.T. 2. E-02 08/14 08/21 1.01 E+04 CU. FT. 2.7 +/- 0.3 E-02 2.9+/- 1.6 E-03 08/29 L.T. 5. E-02 08/21 08/28 1.01 E+04 CU. FT. 2.1 +/- 0.3 E-02 2.5+/-1.3 E-03 08/30 L.T. 2. E-02 08/28 09/04 1.01 E+04 CU. FT. 2.4 +/- 0.3 E-02 L.T. 1. E-03 09/06 L.T. 2. E-02 09/04 09/11 1.02E+04 CU. FT. 1.6 +/- 0.3 E-02 L.T. 2. E-03 09/19 L.T. 3. E-02 09/11 09/18 1.01 E+04 CU. FT. 2.8 +/- 0.3 E-02 2.2+/-1.3 E-03 09/21 L.T. 1. E-02 09/18 09/25 9.97E+03 CU. FT. 2.4 +/- 0.3 E-02 3.0+/-1.5 E-03 09/28 L.T. 2. E-02 09/25 10/02 1.02E+04 CU. FT. 1.9 +/- 0.3 E-02 2.2+/-1.2 E-03 10/05 L.T. 2. E-02 10/02 10/09 1.02E+04 CU. FT. 3.0 +/- 0.3 E-02 2.1 +/- 1.5 E-03 10/12 L.T. 2. E-02 10/09 10/16 9.91 E+03 CU. FT. 2.0 +/- 0.3 E-02 1.5+/-1.2 E-03 10/23 L.T. 2. E-02 10/16 10/23 1.03E+04 CU. FT. 1.7 +/- 0.3 E-02 2.7+/-1.4 E-03 10/30 L.T. 2. E-02 10/23 10/30 9.99E+03 CU. FT. 2.1 +/- 0.3 E-02 L.T. 2. E-03 11/08 L.T. 2. E-02 10/30 11/06 9.96E+03 CU. FT. 1.8 +/- 0.3 E-02 L.T. 9. E-04 11/15 L.T. 2. E-02 11/06 11/13 1.03E+04 CU. FT. 1.9 +/- 0.3 E-02 2.7 +/- 1.3 E-03 11/20 L.T. 1. E-02 11/13 11/20 1.02E+04 CU. FT. 3.0 +/- 0.3 E-02 3.7+/-1.6 E-03 12/07 L.T. 2. E-02 11/20 11/27 1.01 E+04 CU. FT. 2.6 +/- 0.3 E-02 L.T. 2. E-03 12/11 L.T. 4. E-02 11/27 12/04 9.93E+03 CU. FT. 1.9 +/- 0.3 E-02 L.T. 1. E-03 12/13 L.T. 4. E-02 12/04 12/11 1.01 E+04 CU. FT. 2.0 +/- 0.3 E-02 L.T. 2. E-03 12/18 L.T. 5. E-02 12/11 12/18 1.OOE+04 CU. FT. 3.5 +/- 0.4 E-02 4.1 +/- 1.6 E-03 12/26 L.T. 5. E-02 12/18 12/26 1.13E+04 CU. FT. 2.7 +/- 0.3 E-02 3.4 +/- 1.4 E-03 01/04 L.T. 5. E-02 (a) Sample not collected due to adverse weather conditions.

(b) Sample volume not provided. Results are in total pCi.

(c) Sample not analyzed per client request.

(d) Sample not available due to pump/power failure.

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 01 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 7.08 +/- 0.66 E-02 1.09 +/- 0.08 E-01 1.43 +/- 0.09 E-01 9.50 +/- 1.04 E-02 K-40 L.T. 8. E-03 L.T. 6. E-03 L.T. 1. E-02 L.T. 1. E-02 MN-54 L.T. 6. E-04 L.T. 7. E-04 L.T. 5. E-04 L.T. 1. E-03 CO-58 L.T. 1. E-03 L.T. 1. E-03 L.T. 8. E-04 L.T. 2. E-03 FE-59 L.T. 4. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 5. E-03 CO-60 L.T. 6. E-04 L.T. 6. E-04 L.T. 5. E-04 L.T. 9. E-04 ZN-65 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 3. E-03 ZR-95 L.T. 1. E-03 L.T. 1. E-03 L.T. 8. E-04 L.T. 2. E-03 RU-103 L.T. 3. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 3. E-03 RU-106 LT. 5. E-03 L.T. 6. E-03 L.T. 4. E-03 L.T. 7. E-03 1-131 L.T. 3. E+00 L.T. 2. E-01 L.T. 1. E-01 L.T. 8. E-01 CS-1 34 L.T. 6. E-04 L.T. 7. E-04 L.T. 4. E-04 L.T. 9. E-04 CS-137 L.T. 6. E-04 L.T. 6. E-04 L.T. 4. E-04 L.T. 5. E-04 BA-140 L.T. 1. E-01 L.T. 3. E-02 L.T. 2. E-02 L.T. 8. E-02 CE-141 L.T. 4. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 4. E-03 CE-144 L.T. 3. E-03 L.T. 4. E-03 L.T. 2. E-03 L.T. 4. E-03 RA-226 L.T. 5. E-03 L.T. 1. E-02 L.T. 1. E-02 L.T. 2. E-02 TH-228 L.T. 8. E-04 L.T. 7. E-04 L.T. 3. E-03 L.T. 5. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 02 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 1.40+/-0.15 E-01 1.38+/-0.09 E-01 1.03+/-0.07 E-01 1.13+/-0.13 E-01 K-40 L.T. 2. E-02 L.T. 1. E-02 L.T. 7. E-03 L.T. 1. E-02 MN-54 L.T. 1. E-03 L.T. 8. E-04 L.T. 6. E-04 L.T. 1. E-03 CO-58 LT. 3. E-03 L.T. 1. E-03 L.T. 9. E-04 L.T. 2. E-03 FE-59 L.T. 1. E-02 L.T. 3. E-03 L.T. 2. E-03 L.T. 5. E-03 CO-60 L.T. 1. E-03 L.T. 7. E-04 L.T. 5. E-04 L.T. 8. E-04 ZN-65 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 3. E-03 ZR-95 L.T. 3. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-103 L.T. 6. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 3. E-03 RU-1i06 L.T. 1. E-02 L.T. 7. E-03 L.T. 5. E-03 L.T. 8. E-03 1-131 L.T. 7. E+00 L.T. 2. E-01 L.T. 1. E-01 L.T. 9. E-01 CS-1 34 L.T. 1. E-03 L.T. 8. E-04 L.T. 6. E-04 L.T. 1. E-03 CS-1 37 L.T. 1. E-03 L.T. 7. E-04 L.T. 5. E-04 L.T. 8. E-04 BA-140 L.T. 4. E-01 L.T. 3. E-02 L.T. 2. E-02 L.T. 8. E-02 CE-141 L.T. 1. E-02 L.T. 3. E-03 L.T. 2. E-03 L.T. 4. E-03 CE-144 L.T. 6. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 4. E-03 RA-226 L.T. 2. E-02 L.T. 9. E-03 L.T. 5. E-03 L.T. 2. E-02 TH-228 L.T. 2. E-03 L.T. 1. E-03 L.T. 5. E-04 L.T. 6. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 03 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 9.80+/- 1.12 E-02 1.16 +/-+0.09 E-01 9.69 +/-+0.69 E-02 1.00 +/-+0.13 E-01 K-40 L.T. 1. E-02 L.T. 1. E-02 L.T. 7. E-03 L.T. 1. E-02 MN-54 L.T. 1. E-03 L.T. 9. E-04 L.T. 6. E-04 L.T. 1. E-03 CO-58 L.T. 2. E-03 L.T. 1. E-03 L.T. 9. E-04 L.T. 2. E-03 FE-59 L.T. 8. E-03 L.T. 4. E-03 L.T. 3. E-03 L.T. 5. E-03 CO-60 L.T. 9. E-04 L.T. 8. E-04 L.T. 5. E-04 L.T. 9. E-04 ZN-65 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 3. E-03 ZR-95 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-103 L.T. 5. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 3. E-03 RU-106 L.T. 9. E-03 L.T. 8. E-03 L.T. 5. E-03 L.T. 9. E-03 1-131 L.T. 5. E+00 L.T. 2. E-01 L.T. 2. E-01 L.T. 9. E-01 CS-1 34 L.T. 1. E-03 L.T. 9. E-04 L.T. 6. E-04 L.T. 1. E-03 CS-137 L.T. 9. E-04 L.T. 8. E-04 L.T. 5. E-04 L.T. 9. E-04 BA-140 L.T. 3. E-01 L.T. 4. E-02 L.T. 2. E-02 L.T. 9. E-02 CE-141 L.T. 7. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 4. E-03 CE-144 L.T. 4. E-03 L.T. 4. E-03 L.T. 2. E-03 L.T. 4. E-03 RA-226 L.T. 2. E-02 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. E-02 TH-228 L.T. 9. E-04 L.T. 1. E-03 L.T. 5. E-04 L.T. 7. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 04 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 6.62 +/-+0.84 1E-02 1.09 +/-+0.08 E-01 1.30+/-0.09 E-01 1.08 +/-+0.15 E-01 K-40 L.T. 1. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 2. E-02 MN-54 L.T. 9. E-04 L.T. 8. E-04 L.T. 8. E-04 L.T. 1. E-03 CO-58 L.T. 2. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 FE-59 L.T. 6. E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 7. E-03 CO-60 L.T. 7. E-04 L.T. 7. E-04 L.T. 7. E-04 L.T. 1. E-03 ZN-65 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 3. E-03 ZR-95 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 3. E-03 RU-103 L.T. 4. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 4. E-03 RU-1i06 L.T. 7. E-03 L.T. 6. E-03 L.T. 6. E-03 L.T. 1. E-02 1-131 L.T. 4. E+00 L.T. 2. E-01 L.T. 2. E-01 L.T. 1. E+00 CS-134 L.T. 8. E-04 L.T. 8. E-04 L.T. 8. E-04 L.T. 1. E-03 CS-1i37 L.T. 7. E-04 L.T. 6. E-04 L.T. 7. E-04 L.T. 1. E-03 BA-140 L.T. 2. E-01 L.T. 3. E-02 L.T. 3. E-02 L.T. 9. E-02 CE-141 L.T. 6. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 6. E-03 CE-144 L.T. 4. E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 6. E-03 RA-226 L.T. 2. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 1. E-02 TH-228 L.T. 1. E-03 L.T. 1. E-03 L.T. 6. E-04 L.T. 8. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 05 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 8.83 +/-+0.76 IE-02 1.23 +/- 0.08 E-01 1.17 +/- 0.08 E-01 9.41 +-1.19E E-02 K-40 L.T. 8. E-03 L.T. 7. E-03 L.T. 9. E-03 L.T. 2. E-02 MN-54 L.T. 7. E-04 L.T. 4. E-04 L.T. 7. E-04 L.T. 1. E-03 CO-58 L.T. 1. E-03 L.T. 6. E-04 L.T. 1. E-03 L.T. 2. E-03 FE-59 L.T. 5. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 6. E-03 CO-60 L.T. 5. E-04 L.T. 4. E-04 L.T. 6. E-04 L.T. 1. E-03 C)

OC, ZN-65 L.T. 2. E-03 L.T. 9. E-04 L.T. 2. E-03 L.T. 3. E-03 ZR-95 L.T. 1. E-03 L.T. 7. E-04 L.T. 2. E-03 L.T. 2. E-03 RU-103 L.T. 3. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 4. E-03 RU-1i06 L.T. 5. E-03 L.T. 3. E-03 L.T. 5. E-03 L.T. 1. E-02 1-131 L.T. 3. E+00 L.T. 1. E-01 L.T. 1. E-01 L.T. 1. E+00 CS-1i34 L.T. 6. E-04 L.T. 3. E-04 L.T. 7. E-04 L.T. 1. E-03 CS-1i37 L.T. 7. E-04 L.T. 4. E-04 L.T. 6. E-04 L.T. 1. E-03 BA-140 L.T. 2. E-01 L.T. 2. E-02 L.T. 2. E-02 L.T. 1. E-01 CE-1i41 L.T. 4. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 5. E-03 CE-144 L.T. 3. E-03 L.T. 2. E-03 L.T. 3, E-03 L.T. 5. E-03 RA-226 L.T. 6. E-03 L.T. 9. E-03 L.T. 1. E-02 L.T. 2. E-02 TH-228 L.T. 7. E-04 L.T. 5. E-04 L.T. 6. E-04 L.T. 8. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 06 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 8.52_+/-+0.96 E-02 1.16_+/-0.08 E-01 1.03_+/-0.08 E-01 1.12_+/-0.13 E-01 K-40 L.T. 1. E-02 L.T. 8. E-03 L.T. 9. E-03 L.T. 2. E-02 MN-54 L.T. 9. E-04 L.T. 4. E-04 L.T. 7. E-04 L.T. 9. E-04 CO-58 L.T. 2. E-03 L.T. 7. E-04 L.T. 1. E-03 L.T. 1. E-03 FE-59 L.T. 7. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 4. E-03 CO-60 L.T. 8. E-04 L.T. 4. E-04 L.T. 6. E-04 L.T. 7. E-04 ZN-65 L.T. 2. E-03 L.T. 9. E-04 L.T. 2. E-03 L.T. 2. E-03 ZR-95 L.T. 2. E-03 L.T. 6. E-04 L.T. 2. E-03 L.T. 2. E-03 RU-1i03 L.T. 4. E-03 L.T. 9. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-106 L.T. 8. E-03 L.T. 3. E-03 L.T. 6. E-03 L.T. 6. E-03 1-131 L.T. 5. E+00 L.T. 9. E-02 L.T. 1. E-01 L.T. 6. E-01 CS-1i34 L.T. 9. E-04 L.T. 3. E-04 L.T. 7. E-04 L.T. 6. E-04 CS-137 L.T. 8. E-04 L.T. 4. E-04 L.T. 6. E-04 L.T. 7. E-04 BA-140 L.T. 2. E-01 L.T. 2. E-02 L.T. 2. E-02 L.T. 7. E-02 CE-1i41 L.T. 6. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 4. E-03 CE-144 L.T. 4. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 4. E-03 RA-226 L.T. 2. E-02 L.T. 1. E-02 L.T. 8. E-03 L.T. 1. E-02 TH-228 L.T. 1. E-03 L.T. 7. E-04 L.T. 6. E-04 L.T. 5. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 07 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 9.18 +/-+0.85 E-02 1.20 +/-+0.08 E-01 1.22 +/-+0.08 E-01 6.98 +/-_0.92 E-02 K-40 L.T. 9. E-03 L.T. 1. E-02 L.T. 1. E-02 L.T. 1. E-02 MN-54 L.T. 7. E-04 L.T. 5. E-04 L.T. 7. E-04 L.T. 7. E-04 CO-58 L.T. 2. E-03 L.T. 8. E-04 L.T. 1. E-03 L.T. 1. E-03 FE-59 L.T. 5. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 4. E-03 CO-60 L.T. 6. E-04 L.T. 4. E-04 L.T. 6. E-04 L.T. 8. E-04 ZN-65 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 ZR-95 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 RU-103 L.T. 3. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-106 L.T. 6. E-03 L.T. 4. E-03 L.T. 6. E-03 L.T. 5. E-03 1-131 L.T. 4. E+00 L.T. 1. E-01 L.T. 1. E-01 L.T. 5. E-01 CS-134 L.T. 7. E-04 L.T. 4. E-04 L.T. 7. E-04 L.T. 5. E-04 CS-137 L.T. 6. E-04 L.T. 4. E-04 L.T. 6. E-04 L.T. 6. E-04 BA-1i40 L.T. 2. E-01 L.T. 5. E-02 L.T. 3. E-02 L.T. 5. E-02 CE-141 L.T. 5. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 3. E-03 CE-144 L.T. 3. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 3. E-03 RA-226 L.T. 1. E-02 L.T. 1. E-03 L.T. 1. E-02 L.T. 1. E-02 TH-228 LT. 5. E-04 L.T. 7. E-04 L.T. 6. E-04 L.T. 4. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 08 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 2.91 B365 0 E-02 1.54 +/-+0.11 E-01 1.27 +/-+0.08 E-01 1.02 +/-+0.13 E-01 K-40 L.T. 1. E-02 L.T. 1. E-02 L.T. 8. E-03 L.T. 2. E-02 MN-54 L.T. 9. E-04 L.T. 6. E-04 L.T. 6. E-04 L.T. 1. E-03 CO-58 L.T. 2. E-03 L.T. 9. E-04 L.T. 9. E-04 L.T. 2. E-03 FE-59 L.T. 6. E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 6. E-03 CO-60 3.09 +/- 0.28 E-03 L.T. 5. E-04 L.T. 5. E-04 L.T. 1. E-03 ZN-65 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 3. E-03 ZR-95 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-1i03 L.T. 4. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 4. E-03 RU-106 L.T. 7. E-03 L.T. 5. E-03 L.T. 5. E-03 L.T. 1. E-02 1-131 L.T. 4. E+00 L.T. 2. E-01 L.T. 2. E-01 L.T. 1. E+00 CS-1i34 L.T. 8. E-04 L.T. 5. E-04 L.T. 6. E-04 L.T. 1. E-03 CS-1i37 L.T. 7. E-04 L.T. 5. E-04 L.T. 5. E-04 L.T. 1. E-03 BA-140 L.T. 2. E-01 L.T. 2. E-02 L.T. 2. E-02 L.T. 1. E-01 CE-141 L.T. 5. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 6. E-03 CE-1i44 L.T. 3. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 5. E-03 RA-226 L.T. 9. E-03 L.T. 2. E-02 L.T. 1. E-02 L.T. 2. E-02 TH-228 1.35 +/- 2.21 E-03 L.T. 8. E-04 L.T. 5. E-04 L.T. 8. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 09 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 7.79 +/- 0.72 E-02 1.21 +/- 0.08 E-01 1.14 +/-+0.06 E-01 1.01 +/- 0.12 E-01 K-40 L.T. 7. E-03 L.T. 1. E-02 L.T. 6. E-03 L.T. 1. E-02 MN-54 L.T. 4. E-04 L.T. 5. E-04 L.T. 4, E-04 L.T. 1. E-03 CO-58 L.T. 9. E-04 L.T. 7. E-04 L.T. 6. E-04 L.T. 2. E-03 FE-59 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 6. E-03 CO-60 L.T. 4. E-04 L.T. 4. E-04 L.T. 3. E-04 L.T. 8. E-04 o ZN-65 L.T. 9. E-04 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 ZR-95 L.T. 1. E-03 L.T. 7. E-04 L.T. 7. E-04 L.T. 2. E-03 RU-103 L.T. 2. E-03 L.T. 1. E-03 L.T. 9. E-04 L.T. 3. E-03 RU-106 L.T. 4. E-03 L.T. 4. E-03 L.T. 3. E-03 L.T. 8. E-03 1-131 L.T. 2. E+00 L.T. 1. E-01 L.T. 9. E-02 L.T. 9. E-01 CS-134 L.T. 4. E-04 L.T. 4. E-04 L.T. 4. E-04 L.T. 1. E-03 CS-1i37 L.T. 4. E-04 L.T. 5. E-04 L.T. 4. E-04 L.T. 9. E-04 BA-140 L.T. 1. E-01 L.T. 2. E-02 L.T. 1. E-02 L.T. 9. E-02 CE-141 L.T. 3. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 4. E-03 CE-144 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 4. E-03 RA-226 L.T. 8. E-03 L.T. 1. E-02 L.T. 1. E-02 L.T. 2. E-02 TH-228 L.T. 4. E-04 L.T. 7. E-04 L.T. 3. E-03 L.T. 7. E-03

VII-2 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AIRBORNE COMPOSITE AIR PARTICULATE FILTERS (PCI/CU. M.)

STATION NUMBER 10 DATE COLLECTED 12/26-03/27 03/27-07/03 07/03-09/25 09/25-12/26 GAMMA SPECTRUM ANALYSIS:

BE-7 5.78 +/- 0.68 E-02 9.88 +/- 0.65 E-02 1.32 +/- 0.07 E-01 8.34 +/- 1.12 E-02 K-40 L.T. 8. E-03 L.T. 6. E-03 L.T. 6. E-03 L.T. 1. E-02 MN-54 L.T. 5. E-04 L.T. 4. E-04 L.T. 5. E-04 L.T. 8. E-04 CO-58 L.T. 9. E-04 L.T. 6. E-04 L.T. 7. E-04 L.T. 1. E-03 FE-59 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 4. E-03 CO-60 L.T. 4. E-04 L.T. 4. E-04 L.T. 4. E-04 L.T. 6. E-04 ZN-65 L.T. 1. E-03 L.T. 8. E-04 L.T. 1. E-03 L.T. 2. E-03 ZR-95 L.T. 1. E-03 L.T. 6. E-04 L.T. 7. E-04 L.T. 2. E-03 RU-1i03 L.T. 2. E-03 L.T. 9. E-04 L.T. 1. E-03 L.T. 2. E-03 RU-1i06 L.T. 4. E-03 L.T. 3. E-03 L.T, 4. E-03 L.T. 7. E-03 1-131 L.T. 2. E+00 L.T. 9. E-02 L.T. 1. E-01 L.T. 7. E-01 CS-134 L.T. 3. E-04 L.T. 3. E-04 L.T. 5. E-04 L.T. 7. E-04 CS-1i37 L.T. 5. E-04 L.T. 3. E-04 L.T. 4. E-04 L.T. 7. E-04 BA-140 L.T. 1. E-01 L.T. 1. E-02 L.T. 2. E-02 L.T. 7. E-02 CE-141 L.T. 3. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 4. E-03 CE-144 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 4. E-03 RA-226 L.T. 8. E-03 L.T. 8. E-03 L.T. 5. E-03 L.T. 1. E-02 TH-228 L.T. 6. E-04 L.T. 4. E-04 L.T. 2. E-03 L.T. 5. E-03

VII-3 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION FISH (PCI/KG WET)

STATION NUMBER 28 DATE COLLECTED: 06/20 06/20 06/20 09/26 09/26 CATFISH CARP QA CARP CATFISH RADIOCHEMICAL ANALYSIS:

GR-B 4.4 +/- 0.2 E+03 6.6 +/- 0.3 E+03 5.2 +/- 0.3 E+03 2.4 +/- 0.1 E+03 2.0 +/- 0.1 E+03 SR-89 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 L.T. 5. E 00 L.T. 3. E 00 SR-90 4.5 +/- 2.5 E 00 L.T. 3. E 00 6.7 +/- 3.0 E 00 1.2 +/- 0.1 E+01 7.8 +/- 1.0 E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 3. E+01 L.T. 7. E+01 L.T. 3. E+01 L.T. 2. E+02 L.T. 2. E+02 K-40 2.80 +/- 0.1: E+03 3.09 +/- 0.1!E+03 2.95 +/- 0.1: E+03 3.06 +/- 0.2, E+03 2.83 +/- 0.2: E+03 MN-54 L.T. 4. E 00 L.T. 6. E 00 L.T. 4. E 00 L.T. 2. E+01 L.T. 2. E+01 CO-58 L.T. 4. E 00 L.T. 8. E 00 L.T. 4. E 00 L.T. 2. E+01 L.T. 2. E+01 FE-59 L.T. 9. E 00 L.T. 2. E+01 L.T. 9. E 00 L.T. 5. E+01 L.T. 5. E+01 CO-60 L.T. 4. E 00 L.T. 5. E 00 L.T. 4. E 00 L.T. 2. E+01 L.T. 2. E+01 ZN-65 L.T. 8. EQ00 L.T. 1. E+01 L.T. 9. E 00 L.T. 5. E+01 L.T. 5. E+01 ZR-95 L.T. 7. E 00 L.T. 8. E 00 L.T. 6. E 00 L.T. 2. E+01 L.T. 2. E+01 RU-1i03 L.T. 4. E 00 L.T. 1. E+01 L.T. 4. E 00 L.T. 2. E+01 L.T. 2. E+01 RU-106 L.T. 3. E+01 L.T. 5. E+01 L.T. 3. E+01 L.T. 2. E+02 L.T. 2. E+02 1-131 L.T. 1. E+01 L.T. 3. E+02 L.T. 1. E+01 L.T. 5. E+01 L.T. 6. E+01 CS-134 L.T. 4. E 00 L.T. 5. E 00 L.T. 4. E 00 L.T. 2. E+01 L.T. 2. E+01 CS-137 L.T. 4. E 00 L.T. 5. E 00 L.T. 4. E 00 L.T. 2. E+01 L.T. 2. E+01 BA-140 L.T. 3. E+01 L.T. 6. E+01 L.T. 3. E+01 L.T, 4. E+01 L.T. 4. E+01 CE-141 L.T. 7. E 00 L.T. 1. E+01 L.T. 6. E 00 L.T. 3. E+01 L.T. 3. E+01 CE-144 L.T. 2. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 1. E+02 L.T. 1. E+02 RA-226 L.T. 1. E+02 L.T. 2. E+02 L.T. 1. E+02 L.T. 3. E+02 L.T. 4. E+02 TH-228 L.T. 5. EQ00 L.T. 7. E 00 7.37 +/- 2.8'E 00 L.T. 2. E+01 L.T. 2. E+01

VII-3 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION FISH (PCI/KG WET)

STATION NUMBER 35 DATE COLLECTED: 06/21/2001 06/21/2001 09/26 09/26 CARP CATFISH CARP CATFISH RADIOCHEMICAL ANALYSIS:

GR-B 5.9 +/- 0.3 E+03 6.1 +/-0.2 E+03 6.2 +/- 0.2 E+03 3.1 +/- 0.1 E+03 SR-89 L.T. 1. E+01 L.T. 1. E+01 L.T. 9. E 00 L.T. 3. E 00 SR-90 L.T. 6. E 00 L.T. 4. E 00 L.T. 5. E 00 L.T. 1. E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 3. E+01 L.T. 4. E+01 L.T. 3. E+02 L.T. 2. E+02 K-40 2.61 +/-+0.11 E+03 3.39 +/- 0.1 E+03 2.38 +/- 0.41 E+03 3.13 +/- 0.2! E+03 MN-54 L.T. 3. E 00 L.T. 5. E 00 L.T. 4. E+01 L.T. 2. E+01 CO-58 L.T. 4. E 00 L.T. 5. E 00 L.T. 4. E+01 L.T. 2. E+01 FE-59 L.T. 8. E 00 L.T. 1. E+01 L.T. 8. E+01 L.T. 5. E+01 CO-60 L.T. 6. E 00 L.T. 4. E 00 L.T. 3. E+01 L.T. 2. E+01 ZN-65 L.T. 7. E 00 L.T. 1. E+01 L.T. 9. E+01 L.T. 5. E+01 ZR-95 L.T. 3. E 00 L.T. 5. E 00 L.T. 4. E+01 L.T. 2. E+01 RU-103 L.T. 4. E 00 L.T. 5. E 00 L.T. 4. E+01 L.T. 3. E+01 RU-106 L.T. 3. E+01 L.T. 4. E+01 L.T. 3. E+02 L.T. 2. E+02 1-131 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+02 L.T. 6. E+01 CS-134 L.T. 3. E 00 L.T. 4. E 00 L.T. 4. E+01 L.T. 3. E+01 CS-1i37 L.T. 5. E 00 L.T. 4. E 00 L.T. 4. E+01 L.T. 2. E+01 BA-140 L.T. 7. E 00 L.T. 1. E+01 L.T. 8. E+01 L.T. 5. E+01 CE-141 L.T. 5. E00 L.T. 8. E 00 L.T. 6. E+01 L.T. 3. E+01 CE-144 L.T. 2. E+01 L.T. 3. E+01 L.T. 2. E+02 L.T. 1. E+02 RA-226 L.T. 8. E+01 L.T. 1. E+02 L.T. 1. E+03 L.T. 4. E+02 TH-228 L.T. 4. E 00 L.T. 1. E+01 L.T. 7. E+01 L.T. 4. E+01

VII-4 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION MILK NEAREST PRODUCER (PCI/LITER)

STATION NUMBER 61 DATE COLLECTED: 01/09/2001 02/06/2001 03/06/2001 03/06/2001 04/03/2001 QA RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 6. E 00 L.T. 2. E 00 L.T. 2. E 00 L.T. 2. E 00 SR-90 2.8 +/-+0.4 EQ00 8.3 +/-_2.1 E-01 1.0 +/-+0.2 E00 7.7+/- 1.6 E-01 1-131 L.T. 7. E-01 L.T. 9. E-01 (a) (a) L.T. 1. E-01 CA(gm/liter) 6.3 +/- 0.9 E-01 8.0 +/- 1.2 E-01 8.6 +/- 1.3 E-01 2.1 +/- 0.2 E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 4. E+01 L.T. 7. E+01 L.T. 4. E+01 L.T. 5. E+01 L.T. 3. E+01 K-40 1.27+/-0.08 E+03 1.30+/-0.10 E+03 1.18++/-0.08 E+03 1.21++/- 0.09 E+03 1.22+/-0.07 E+03 MN-54 L.T. 4. E+00 L.T. 8. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 3. E+00 CO-58 L.T. 5. E+00 L.T. 8. E+00 L.T. 4. E+00 L.T. 6. E+00 L.T. 3. E+00 FE-59 L.T. 1. E+01 L.T. 2. E+01 L.T. 1. E+01 L.T. 1. E+01 L.T. 7. E+00 CO-60 L.T. 5. E+00 L.T. 7. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 4. E+00 ZN-65 L.T. 9. E+00 L.T. 2. E+01 L.T. 8. E+00 L.T. 1. E+01 L.T. 7. E+00 ZR-95 L.T. 7. E+00 L.T. 1. E+01 L.T. 5. E+00 L.T. 1. E+01 L.T. 4. E+00 RU-103 L.T. 5. E+00 L.T. 8. E+00 L.T. 5. E+00 L.T. 6. E+00 L.T. 3. E+00 RU-106 L.T. 4. E+01 L.T. 7. E+01 L.T. 3. E+01 L.T. 4. E+01 L.T. 3. E+01 1-131 L.T. 1. E+01 L.T. 2. E+01 L.T. 2. E+01 L.T. 3. E+01 L.T. 8. E+00 CS-1i34 L.T. 4. E+00 L.T. 8. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 3. E+00 CS-1i37 L.T. 4. E+00 L.T. 8. E+00 L.T. 3. E+00 L.T. 5. E+00 L.T. 3. E+00 BA-140 L.T. 3. E+01 L.T. 4. E+01 L.T. 1. E+01 L.T. 5. E+01 L.T. 7. E+00 CE-141 L.T. 7. E+00 L.T. 1. E+01 L.T. 8. E+00 L.T. 9. E+00 L.T. 5. E+00 CE-144 L.T. 2. E+01 L.T. 4. E+01 L.T. 2. E+01 L.T. 3. E+01 L.T. 2. E+01 RA-226 L.T. 1. E+01 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 L.T. 9. E+01 TH-228 L.T. 7. E+00 L.T. 1. E+01 L.T. 9. E+00 L.T. 8. E+00 L.T. 6. E+00 (a) Data not reported. Declared invalid due to sample mount not decaying properly.

(b) Monthly composite.

VII-4 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION MILK NEAREST PRODUCER (PCI/LITER)

STATION NUMBER 61 DATE COLLECTED: 05/01/2001 05/29/2001 06/12/2001 06/12/2001 06/26/2001 QA RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 1. E 00 (b) L.T. 9. E-01 (b)

SR-90 7.5 +/- 1.8 E-01 (b) 8.7 +/-+1.8 E-01 (b) 1-131 L.T. 1. E-01 L.T. 1. E-01 L.T. 1. E-01 L.T. 2. E-01 L.T. 2. E-01 CA(gm/liter) 6.5 +/- 0.7 E-01 (b) 5.5 +/- 0.6 E-01 (b)

GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 5. E+01 L.T. 2. E+01 L.T. 5. E+01 L.T. 4. E+01 L.T. 5. E+01 K-40 1.30 +/- 0.07 E+03 1.23 +/- 0.05 E+03 1.11 +/- 0.08 E+03 1.09 +/- 0.07 E+03 1.11 +/- 0.07 E+03 MN-54 L.T. 5. E+00 L.T. 2. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 6. E+00 CO-58 L.T. 6. E+00 L.T. 2. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 6. E+00 FE-59 L.T. 1. E+01 L.T. 5. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 CO-60 L.T. 5. E+00 L.T. 2. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 5. E+00 ZN-65 L.T. 1. E+01 L.T. 4. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 ZR-95 L.T. 5. E+00 L.T. 4. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 5. E+00 RU-103 L.T. 6. E+00 L.T. 3. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 RU-106 L.T. 5. E+01 L.T. 2. E+01 L.T. 5. E+01 L.T. 5. E+01 L.T. 5. E+01 1-131 L.T. 1. E+01 L.T. 2. E+01 L.T. 1. E+01 L.T. 1. E+01 L.T. 8. E+00 CS-134 L.T. 5. E+00 L.T. 2. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 6. E+00 CS-137 L.T. 5. E+00 L.T. 2. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 BA-140 L.T. 1. E+01 L.T. 3. E+01 L.T. 9. E+00 L.T. 8. E+00 L.T. 7. E+00 CE-141 L.T. 8. E+00 L.T. 4. E+00 L.T. 9. E+00 L.T. 6. E+00 L.T. 8. E+00 CE-144 L.T. 3. E+01 L.T. 1. E+01 L.T. 4. E+01 L.T, 3. E+01 L.T. 3. E+01 RA-226 L.T. 9. E+01 L.T. 7. E+01 L.T. 1. E+02 L.T. 9. E+01 L.T. 9. E+01 TH-228 L.T. 1. E+01 L.T. 3. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 (a) Data not reported. Declared invalid due to sample mount not decaying properly.

(b) Monthly composite.

VII-4 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION MILK NEAREST PRODUCER (PCI/LITER)

STATION NUMBER 61 DATE COLLECTED: 07/10/2001 07/24/2001 08/07/2001 08/21/2001 09/04/2001 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 2. E 00 (b) L.T. 2. E 00 (b)

SR-90 1.1 +/-+0.2 E0(b) 7.1 +/-+1.6 E-01 (b) 1-131 L.T. 3. E-01 L.T. 2. E-01 L.T. 1. E-01 L.T. 2. E-01 L.T. 2. E-01 CA(gm/liter) 1.40+/-+0.14 E00(b) 1.92 +/- 0.19 E 00 (b)

GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 3. E+01 L.T. 5. E+01 L.T. 5. E+01 L.T. 3. E+01 L.T. 4. E+01 ON K-40 1.13 +/- 0.08 E+03 1.54 +/-+0.08 IE+03 1.22 +/- 0.07 IE+03 1.17 + 0.07 E+03 1.08 +/- 0.07 E+03 MN-54 L.T. 4. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 3. E+00 L.T. 5. E+00 CO-58 L.T. 4. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 3. E+00 L.T. 5. E+00 FE-59 L.T. 9. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 8. E+00 L.T. 1. E+01 CO-60 L.T. 4. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 3. E+00 L.T. 5. E+00 ZN-65 L.T. 9. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 8. E+00 L.T. 1. E+01 ZR-95 L.T. 4. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 4. E+00 L.T. 5. E+00 RU-103 L.T. 4. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 5. E+00 RU-106 L.T. 3. E+01 L.T. 5. E+01 L.T. 5. E+01 L.T. 3. E+01 L.T. 5. E+01 1-131 L.T. 4. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 6. E+00 L.T. 6. E+00 CS-134 L.T. 4. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 3. E+00 L.T. 6. E+00 CS-137 L.T. 5. E+00 L.T. 6. E+00 L.T. 7. E+00 L.T. 4. E+00 L.T. 5. E+00 BA-140 L.T. 5. E+00 L.T. 9. E+00 L.T. 8. E+00 L.T. 6. E+00 L.T. 6. E+00 CE-141 L.T. 6. E+00 L.T. 9. E+00 L.T. 8. E+00 L.T. 6. E+00 L.T. 7. E+00 CE-1i44 L.T. 2. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 3. E+01 RA-226 L.T. 1. E+02 LT. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 L.T. 9. E+01 TH-228 L.T. 9. E+00 L.T. 1. E+01 L.T. 1. E+01 L.T. 7. E+00 L.T. 1. E+01 (a) Data not reported. Declared invalid due to sample mount not decaying properly.

(b) Monthly composite.

VII-4 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION MILK NEAREST PRODUCER (PCI/LITER)

STATION NUMBER 61 DATE COLLECTED: 09/18/2001 10/09/2001 11/06/2001 12/04/2001 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 1. E 00 (b) L.T. 2. E 00 L.T. 2. E 00 L.T. 1. E 00 SR-90 7.4 +/- 2.3 E-01 (b) 9.6 +/- 2.2 E-01 6.6 +/- 2.2 E-01 8.1 +/- 1.7 E-01 1-131 L.T. 2. E-01 L.T. 2. E-01 L.T. 2. E-01 L.T. 1. E-01 CA(gm/liter) 1.93+/-0.19 E00(b) 1.10+/-0.11 E00 7.90+/-0.79 E00 1.10+/-0.11 E00 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 4. E+01 L.T. 5. E+01 L.T. 4. E+01 L.T. 5. E+01 K-40 1.09 +/-+0.07 E+03 1.07 +/-+0.07 E+03 1.26 +/-+0.08 E+03 1.15 +/-+0.08 E+03 MN-54 L.T. 5. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 6. E+00 CO-58 L.T. 5. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 6. E+00 FE-59 L.T. 1. E+01 L.T. 1. E+01 L.T. 9. E+00 L.T. 1. E+01 CO-60 L.T. 5. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 6. E+00 ZN-65 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 ZR-95 L.T. 5. E+00 L.T. 5. E+00 L.T. 4. E+00 L.T. 6. E+00 RU-103 L.T. 5. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 6. E+00 RU-106 L.T. 4. E+01 L.T. 5. E+01 L.T. 4. E+01 L.T. 5. E+01 1-131 L.T. 9. E+00 L.T. 9. E+00 L.T. 7. E+00 L.T. 1. E+01 CS-1i34 L.T. 6. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 6. E+00 CS-137 L.T. 5. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 6. E+00 BA-140 L.T. 7. E+00 L.T. 9. E+00 L.T. 6. E+00 L.T. 9. E+00 CE-141 L.T. 7. E+00 L.T. 8. E+00 L.T. 5. E+00 L.T. 9. E+00 CE-144 L.T. 3. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 3. E+01 RA-226 L.T, 9. E+01 1.13 +/- 0.49 E+02 L.T. 1. E+02 L.T. 1. E+02 TH-228 L.T. 1. E+01 L.T. 9. E+00 L.T. 6. E+00 L.T. 1. E+01 (a) Data not reported. Declared invalid due to sample mount not decaying properly.

(b) Monthly composite.

VII-5 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION MILK OTHER PRODUCER (PCI/LITER)

STATION NUMBER 99 DATE COLLECTED: 01/09/2001 04/10/2001 07/10/2001 10/09/2001 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 1. E 00 L.T. 2. E 00 L.T. 5. E-01 L.T. 1. E 00 SR-90 1.5 +/- 0.3 E 00 L.T. 6. E-01 7.8 +/- 1.5 E-01 1.4 +/- 0.4 E 00 1-131 (a) L.T. 1. E-01 L.T. 2. E-01 L.T. 2. E-01 CA(gm/liter) 1.2 +/-_0.1 E+00 1.2 +/-+0.1 E00 1.1 +/-+0.1 E00 1.20 +/-+0.12 EO00 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 4. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 6. E+01 "K-40 1.26_+/- 0.08 E+03 1.47+/- 0.10 E+03 1.35 +/- 0.08 E+03 1.04 +/- 0.09 E+03 MN-54 L.T. 4. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 7. E+00 CO-58 L.T. 5. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 8. E+00 FE-59 L.T. 1. E+01 L.T. 1. E+01 L.T. 8. E+00 L.T. 2. E+01 CO-60 L.T. 4. E+00 L.T. 5. E+00 L.T. 4. E+00 L.T. 7. E+00 ZN-65 L.T. 9. E+00 L.T. 1. E+01 L.T. 8. E+00 L.T. 2. E+01 ZR-95 L.T. 8. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 8. E+00 RU-103 L.T. 5. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 8. E+00 RU-106 L.T. 4. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 6. E+01 1-131 L.T. 1. E+01 L.T. 7. E+00 L.T. 4. E+00 L.T. 1. E+01 CS-1i34 L.T. 4. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 8. E+00 CS-1i37 L.T. 4. E+00 L.T. 7. E+00 L.T. 4. E+00 L.T. 7. E+00 BA-140 L.T. 3. E+01 L.T. 7. E+00 L.T. 5. E+00 L.T. 1. E+01 CE-141 L.T. 8. E+00 L.T. 7. E+00 L.T. 5. E+00 L.T. 1. E+01 CE-144 L.T. 3. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 4. E+01 RA-226 L.T. 1. E+01 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 TH-228 L.T. 7. E+00 L.T. 1. E+01 5.94 +/- 2.62 E+00 L.T. 1. E+01 (a) Due to delay in analysis, the sample value was declared invalid.

VII-5 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION MILK OTHER PRODUCER (PCI/LITER)

STATION NUMBER 100 DATE COLLECTED: 01/09/2001 04/10/2001 07/10/2001 10/09/2001 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 8. E-01 L.T. 8. E-01 L.T. 5. E-01 L.T. 8. E-01 SR-90 6.6 +/-1.8 E-01 7.9 +/- 2.2 E-01 7.6 +/- 1.4 E-01 1.8 +/- 0.3 E 00 1-131 (a) L.T. 1. E-01 L.T. 2. E-01 L.T. 2. E-01 CA(gm/liter) 1.0+/-0.1 E+00 9.6+/-0.1 E-01 0.85 +/- 0.08 E+00 1.30 +/- 0.13 E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 5. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 4. E+01 I--l 1.0 K-40 1.40 +/- 0.11 E+03 1.36 +/- 0.08 E+03 1.19 +/- 0.08 IE+03 1.20 +/- 0.07 E+03 MN-54 L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 CO-58 L.T. 7. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 FE-59 L.T. 2. E+01 L.T. 9. E+00 L.T. 8. E+00 L.T. 1. E+01 CO-60 L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 ZN-65 L.T. 1. E+01 L.T. 9. E+00 L.T. 8. E+00 L.T. 1. E+01 ZR-95 L.T. 1. E+01 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 RU-103 L.T. 7. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 6. E+00 RU-1i06 L.T. 5. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 5. E+01 1-131 L.T. 2. E+01 L.T. 7. E+00 L.T. 5. E+00 L.T. 9. E+00 CS-134 L.T. 5. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 6. E+00 CS-1i37 L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 7. E+00 BA-140 L.T. 4. E+01 L.T. 6. E+00 L.T. 5. E+00 L.T. 7. E+00 CE-141 L.T. 1. E+01 L.T. 7. E+00 L.T. 6. E+00 L.T. 5. E+00 CE-144 L.T. 3. E+01 L.T. 3. E+01 L.T. 3. E+01 L.T. 3. E+01 RA-226 L.T. 2. E+01 L.T. 1. E+02 L.T. 1. E+02 L.T. 9. E+01 TH-228 L.T. 8. E+00 L.T. 9. E+00 L.T. 9. E+00 L.T. 1. E+01 (a) Due to delay in analysis, the sample value was declared invalid.

VII-6 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - GROUND (PCI/LITER)

STATION NUMBER 11 DATE COLLECTED: 01/16/01 04/17/01 07/17/01 10/16/01 RADIOCHEMICAL ANALYSIS:

GR-A L.T. 3. E 00 L.T. 2. E+00 L.T. 6. E+00 L.T. 4. E+00 GR-B 7.8+/-1.8 E 00 5.4 +/- 1.6 E+00 6.9 +/- 2.9 E+00 8.3 +/- 3.0 E+00 1-131 L.T. 7. E-01 L.T. 2. E-01 L.T. 3. E-01 L.T. 3. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 2. E+02 L.T. 5. E+01 L.T. 5. E+01 L.T. 4. E+01 00 K-40 L.T. 4. E+02 L.T. 9. E+01 L.T. 9. E+01 L.T. 1. E+02 CD MN-54 L.T. 2. E+01 (a) L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 CO-58 L.T. 2. E+01 (a) L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 FE-59 L.T. 4. E+01 (a) L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 CO-60 L.T. 2. E+01 (a) L.T. 5. E+00 L.T. 6. E+00 L.T. 5. E+00 ZN-65 L.T. 4. E+01 (a) L.T. 1. E+01 L.T. 1. E+01 L.T. 1. E+01 ZR-95 L.T. 4. E+01 (a) L.T. 5. E+00 L.T. 6. E+00 L.T. 5. E+00 RU-103 L.T. 2. E+01 L.T. 6. E+00 L.T. 6. E+00 L.T. 6. E+00 RU-1i06 L.T. 2. E+02 L.T. 5. E+01 L.T. 5. E+01 L.T. 5. E+01 1-131 L.T. 4. E+01 L.T. 9. E+00 L.T. 1. E+01 L.T. 8. E+00 CS-134 L.T. 2. E+01 (a) L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 CS-137 L.T. 2. E+01 (a) L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 BA-140 L.T. 1. E+02 (a) L.T. 9. E+00 L.T. 9. E+00 L.T. 8. E+00 CE-141 L.T. 3. E+01 L.T. 8. E+00 L.T. 9. E+00 L.T. 7. E+00 CE-144 L.T. 1. E+02 L.T. 3. E+01 L.T. 4. E+01 L.T. 3. E+01 RA-226 L.T. 6. E+01 L.T. 9. E+01 L.T. 1. E+02 L.T. 2. E+02 TH-228 L.T. 5. E+01 L.T. 1. E+01 L.T. 1. E+01 L.T. 7. E+00 TRITIUM ANALYSIS:

H-3 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 (a) Due to limited sample volume, the LLD was missed.

VII-6 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - GROUND (PCI/LITER)

STATION NUMBER 47 DATE COLLECTED: 01/16/01 04/17/01 07/17/01 10/16/01 RADIOCHEMICAL ANALYSIS:

GR-A 3.1 +/-2.9 E 00 L.T. 3. E 00 L.T. 6. E 00 L.T. 4. E 00 GR-B 9.0+/-1.9 E 00 4.0 +/- 2.0 E 00 7.2 +/- 2.8 E 00 5.5 +/- 2.8 E 00 1-131 L.T. 4. E-01 L.T. 5. E-01 L.T. 2. E-01 L.T. 2. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 1. E+02 L.T. 3. E+01 L.T. 6. E+01 L.T. 3. E+01 K-40 L.T. 2. E+02 L.T. 8. E+01 L.T. 1. E+02 L.T. 8. E+01 00 MN-54 L.T. 2. E+01 (a) L.T. 4. E+00 L.T. 7. E+00 L.T. 3. E+00 CO-58 L.T. 2. E+01 (a) L.T. 4. E+00 L.T. 7. E+00 L.T. 3. E+00 FE-59 L.T. 3. 'E+01 L.T. 7. E+00 L.T. 1. E+01 L.T. 7. E+00 CO-60 L.T. 1. E+01 L.T. 3. E+00 L.T. 6. E+00 L.T. 6. E+00 ZN-65 L.T. 4. E+01 (a) L.T. 8. E+00 L.T. 2. E+01 L.T. 7. E+00 ZR-95 L.T. 3. E+01 L.T. 3. E+00 L.T. 7. E+00 L.T. 4. E+00 RU-103 L.T. 2. E+01 L.T. 4. E+00 L.T. 7. E+00 L.T. 3. E+00 RU-106 L.T. 1. E+02 L.T. 3. E+01 L.T. 6. E+01 L.T. 3. E+01 1-131 L.T. 3. E+01 L.T. 5. E+00 L.T. 9. E+00 L.T. 5. E+00 CS-134 L.T. 2. E+01 (a) L.T. 4. E+00 L.T. 8. E+00 L.T. 3. E+00 CS-137 L.T. 2. E+01 (a) L.T. 4. E+00 L.T. 7. E+00 L.T. 5. E+00 BA-140 L.T. 7. E+01 (a) L.T. 5. E+00 L.T. 9. E+00 L.T. 5. E+00 CE-141 L.T. 2. E+01 L.T. 5. E+00 L.T. 1. E+01 L.T. 5. E+00 CE-144 L.T. 8. E+01 L.T. 2. E+01 L.T. 4. E+01 L.T. 2. E+01 RA-226 L.T. 4. E+01 L.T. 8. E+01 L.T. 2. E+02 L.T. 1. E+02 TH-228 L.T. 2. E+01 L.T. 7. E+00 L.T. 1. E+01 L.T. 5. E+00 TRITIUM ANALYSIS:

H-3 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 (a) Due to limited sample volume, the LLD was missed.

VII-7 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - RIVER (PCI/LITER)

STATION NUMBER 12 DATE COLLECTED: 02/06/01 04/03/01 05/01/01 06/05/01 07/03/01 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 7. E-01 L.T. 8. E-01 L.T. 7. E-01 L.T. 5. E-01 L.T. 5. E-01 SR-90 L.T. 4. E-01 L.T. 3. E-01 L.T. 9. E-01 L.T. 1. E+00 L.T. 6. E-01 GR-A (Dissolved) 6.7 +/- 2.9 E+00 5.2 +/- 3.7 E+00 L.T. 3. E+00 L.T. 6. E+00 L.T. 4. E+00 GR-A (Suspended) 4.3 +/- 3.0 E-01 3.0 +/- 1.9 E+00 6.0 +/- 2.3 E+01 6.7 +/- 4.9 E+00 L.T. 2. E+00 GR-B (Dissolved) 9.7 +/- 1.6 E+00 8.8 +/- 2.9 E+00 6.8 +/- 3.3 E+00 7.9 +/- 3.0 E+00 9.6 +/- 2.9 E+00 GR-B (Suspended) 1.0 +/- 0.5 E+00 3.9 +/- 2.0 E+00 1.2 +/- 0.1 E+02 2.2 +/- 0.4 E+01 6.1 +/- 2.2 E+00 1-131 L.T. 6. E-01 L.T. 8. E-01 L.T. 1. E-01 4.8 +/- 1.2 E-01 L.T. 3. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 5. E+01 L.T. 3. E+01 L.T. 3. E+01 L.T. 4. E+01 L.T. 4. E+01 0K-40 L.T. 9. E+01 L.T. 6. E+01 L.T. 7. E+01 L.T. 1. E+02 L.T. 8. E+01 MN-54 L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 5. E+00 CO-58 L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+01 L.T. 5. E+00 L.T. 5. E+00 FE-59 L.T. 1. E+01 L.T. 8. E+00 L.T. 7. E+00 L.T. 1. E+01 L.T. 9. E+00 CO-60 L.T. 5. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 5. E+00 ZN-65 L.T. 1. E+01 L.T. 9. E+00 L.T. 7. E+00 L.T. 1. E+01 L.T. 1. E+01 ZR-95 L.T. 1. E+01 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 5. E+00 RU-1i03 L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 5. E+00 RU-106 L.T. 5. E+01 L.T. 3. E+01 L.T. 3. E+01 L.T. 4. E+01 L.T. 5. E+01 1-131 L.T. 1. E+01 L.T. 9. E+00 L.T. 7. E+00 L.T. 7. E+00 L.T. 7. E+00 CS-1i34 L.T. 6. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 5. E+00 L.T. 6. E+00 CS-1i37 L.T. 6. E+00 L.T, 5. E+00 L.T. 3. E+00 L.T. 5. E+00 L.T. 5. E+00 BA-140 L.T. 3. E+01 L.T. 7. E+00 L.T. 6. E+00 L.T. 7. E+00 L.T. 7. E+00 CE-141 L.T. 9. E+00 L.T. 7. E+00 L.T. 6. E+00 L.T. 7. E+00 L.T. 7. E+00 CE-144 L.T. 3. E+01 L.T. 2. E+01 L.T. 2. E+01 L.T. 3. E+01 L.T. 3. E+01 RA-226 L.T. 1. E+02 L.T. 2. E+02 L.T. 1. E+02 L.T. 2. E+02 L.T. 9. E+01 TH-228 L.T. 9. E+00 L.T, 9. E+00 L.T. 6. E+00 L.T. 7. E+00 L.T. 9. E+00 TRITIUM ANALYSIS: 04/03-06/05 H-3 L.T. 1. E+02 (a) Sample not collected.

(b) Data not reported. Declared invalid due to sample mount not decaying properly.

VII-7 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - RIVER (PCI/LITER)

STATION NUMBER 12 DATE COLLECTED: 08/07/01 09/04/01 10/02/01 11/06/01 12/04/01 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 8. E-01 L.T. 5. E-01 L.T. 4. E-01 L.T. 5. E-01 L.T. 6. E-01 SR-90 L.T. 7. E-01 L.T. 8. E-01 L.T. 6. E-01 L.T. 7. E-01 L.T. 3. E-01 GR-A (Dissolved) 3.9 +/- 3.3 E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 6. E+00 GR-A (Suspended) L.T. 1. E+00 L.T. 1. E+00 1.4+/-1.2 E+00 L.T. 2. E+00 L.T. 1. E+01 GR-B (Dissolved) 8.8 +/- 2.8 E+00 9.5 +/- 2.8 E+00 1.1 +/-0.3 E+01 7.0 +/- 2.7 E+00 9.4 +/- 2.9 E+00 GR-B (Suspended) 3.7 +/- 1.8 E+00 L.T. 2. E+00 2.8 +/- 1.7 E+00 L.T. 3. E+00 9.9 +/- 0.9 E+01 1-131 L.T. 2. E-01 L.T. 2. E-01 L.T. 3. E-01 L.T. 4. E-01 L.T. 2. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 4. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 3. E+01 L.T. 2. E+01 K-40 L.T. 9. E+01 L.T. 7. E+01 L.T. 6. E+01 L.T. 6. E+01 L.T. 6. E+01 00 MN-54 L.T. 4. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 CO-58 L.T. 5. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 FE-59 L.T. 1. E+01 L.T. 7. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 6. E+00 CO-60 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 ZN-65 L.T. 9. E+00 L.T. 7. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 6. E+00 ZR-95 L.T. 5. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 RU-103 L.T. 5. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 RU-1i06 L.T. 4. E+01 L.T. 3. E+01 L.T. 3. E+01 L.T. 3. E+01 L.T. 2. E+01 1-131 L.T. 1. E+01 L.T. 5. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 7. E+00 CS-134 L.T. 4. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 CS-137 L.T. 5. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 3. E+00 L.T. 3. E+00 BA-140 L.T. 9. E+00 L.T. 5. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 6. E+00 CE-1i41 L.T. 7. E+00 L.T. 6. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 5. E+00 CE-144 L.T. 3. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 2. E+01 L.T. 2. E+01 RA-226 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 L.T. 1. E+02 TH-228 L.T. 6. E+00 L.T. 9. E+00 L.T. 5. E+00 L.T. 5. E+00 L.T. 4. E+00 TRITIUM ANALYSIS: 07/03-09/04 10/02-12/04 H-3 L.T. 9. E+01 9.6 +/-+6.1 E+01 (a) Sample not collected.

(b) Data not reported. Declared invalid due to sample mount not decaying properly.

VII-7 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - RIVER (PCI/LITER)

STATION NUMBER 28 DATE COLLECTED: 01/02/01 02/06/01 03/06/01 04/03/01 05/01/01 RADIOCHEMICAL ANALYSIS:

SR-89 (a) L.T. 7. E-01 L.T. 2. E+00 L.T. 7. E-01 L.T. 7. E-01 SR-90 (a) L.T, 7. E-01 L.T. 6. E-01 3.2 +/- 1.6 E-01 L.T. 3. E+00 GR-A (Dissolved) (a) 3.1 +/- 1.8 E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 3. E+00 GR-A (Suspended) (a) L.T. 3. E-01 L.T. 4. E+00 L.T. 1. E+00 7.4 +/- 3.9 E+00 GR-B (Dissolved) (a) 7.4 +/- 1.3 E+00 9.6 +/- 2.6 E+00 8.3 +/- 2.9 E+00 7.9 +/- 3.3 E+00 GR-B (Suspended) (a) 1.3 +/- 0.5 E+00 L.T. 4. E+00 L.T. 3. E+00 1.1 +/- 0.3 E+01 1-131 (a) L.T. 4. E-01 (b) L.T. 7. E-01 L.T. 1. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 (a) L.T. 6. E+01 L.T. 4. E+01 L.T. 4. E+01 L.T. 4. E+01 00 K-40 (a) L.T. 1. E+02 L.T. 7. E+01 L.T. 8. E+01 L.T. 8. E+01 "MN-54 (a) L.T. 6. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 4. E+00 CO-58 (a) L.T. 7. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 4. E+00 FE-59 (a) L.T. 1. E+01 L.T. 8. E+00 L.T. 9. E+00 L.T. 8. E+00 CO-60 (a) L.T. 6. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 4. E+00 ZN-65 (a) L.T. 1. E+01 L.T. 7. E+00 L.T. 1. E+01 L.T. 8. E+00 ZR-95 (a) L.T. 1. E+01 L.T. 7. E+00 L.T. 4. E+00 L.T. 4. E+00 RU-103 (a) L.T. 7. E+00 L.T. 5. E+00 L.T. 5. E+00 L.T. 4. E+00 RU-106 (a) L.T. 6. E+01 L.T. 3. E+01 L.T. 4. E+01 L.T. 4. E+01 1-131 (a) L.T. 1. E+01 L.T. 2. E+01 L.T. 1. E+01 L.T. 8. E+00 CS-134 (a) L.T. 7. E+00 L.T. 3. E+00 L.T. 5. E+00 L.T. 4. E+00 CS-137 (a) L.T. 6. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 4. E+00 BA-140 (a) L.T. 3. E+01 L.T. 4. E+01 L.T. 9. E+00 L.T. 7. E+00 CE-141 (a) L.T. 1. E+01 L.T. 8. E+00 L.T. 8. E+00 L.T. 7. E+00 CE-144 (a) L.T. 4. E+01 L.T. 2. E+01 L.T. 3. E+01 L.T. 3. E+01 RA-226 (a) L.T. 1. E+02 L.T. 1. E+02 L.T. 8. E+01 L.T. 1. E+02 TH-228 (a) L.T. 9. E+00 L.T. 9. E+00 L.T. 8. E+00 L.T. 6. E+00 TRITIUM ANALYSIS: 01/02-03/06 H-3 L.T.,1. E 02 (a) Sample not collected.

(b) Data not reported. Declared invalid due to sample mount not decaying properly.

VII-7 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - RIVER (PCI/LITER)

STATION NUMBER 28 DATE COLLECTED: 06/05/01 07/03/01 08/07/01 09/04/01 10/02/01 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 5. E-01 L.T. 4. E-01 L.T. 6. E-01 L.T. 8. E-01 L.T. 4. E-01 SR-90 L.T. 6. E-01 L.T. 7. E-01 L.T. 6. E-01 L.T. 1. E+00 L.T. 7. E-01 GR-A (Dissolved) L.T. 6. E+00 4.4 +/- 3.7 E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 3. E+00 GR-A (Suspended) L.T. 3. E+00 L.T. 2. E+00 L.T. 1. E+00 L.T. 2. E+00 2.7 +/- 1.6 E+00 GR-B (Dissolved) 9.2 +/- 3.0 E+00 8.5 +/- 2.8 E+00 9.1 +/- 2.9 E+00 7.4 +/- 2.6 E+00 6.9 +/- 2.6 E+00 GR-B (Suspended) 3.8 +/- 2.1 E+00 4.2 +/- 1.9 E+00 L.T. 2. E+00 3.7 +/- 1.8 E+00 4.8 +/- 1.9 E+00 1-131 4.6 +/- 1.4 E-01 L.T. 4. E-01 L.T. 4. E-01 L.T. 2. E-01 L.T. 4. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 2. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 4. E+01 L.T. 5. E+01 00 K-40 L.T. 7. E+01 L.T. 8. E+01 L.T. 7. E+01 L.T. 1. E+02 L.T. 8. E+01 MN-54 L.T. 3. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 6. E+00 CO-58 L.T. 3. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 6. E+00 FE-59 L.T. 5. E+00 L.T. 9. E+00 L.T. 7. E+00 L.T. 8. E+00 L.T. 1. E+01 CO-60 L.T. 3. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 5. E+00 ZN-65 L.T. 6. E+00 L.T. 1. E+01 L.T. 6. E+00 L.T. 9. E+00 L.T. 1. E+01 ZR-95 L.T. 3. E+00 L.T. 4. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 5. E+00 RU-1i03 L.T. 3. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 4. E+00 L.T. 6. E+00 RU-106 L.T. 3. E+01 L.T. 4. E+01 L.T. 3. E+01 L.T. 4. E+01 L.T. 5. E+01 1-131 L.T. 4. E+00 L.T. 6. E+00 L.T. 8. E+00 L.T. 5. E+00 L.T. 9. E+00 CS-1i34 L.T. 3. E+00 L.T. 5. E+00 L.T. 3. E+00 L.T. 4. E+00 L.T. 6. E+00 CS-1i37 L.T. 3. E+00 L.T. 5. E+00 L.T. 3. E+00 L.T. 5. E+00 L.T. 6. E+00 BA-140 L.T. 4. E+00 L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 8. E+00 CE-141 L.T. 4. E+00 L.T. 4. E+00 L.T. 5. E+00 L.T. 6. E+00 L.T. 8. E+00 CE-144 L.T. 2. E+01 L.T. 3. E+01 L.T. 2. E+01 L.T. 3. E+01 L.T. 3. E+01 RA-226 L.T. 1. E+02 L.T. 9. E+01 L.T. 9. E+01 L.T. 2. E+02 L.T. 9. E+01 TH-228 L.T. 6. E+00 L.T. 6. E+00 L.T. 5. E+00 L.T. 8. E+00 L.T. 1. E+01 TRITIUM ANALYSIS: 04/03-06/05 07/03-09/04 H-3 L.T. 1. E+02 L.T. 9. E+01 (a) Sample not collected.

(b) Data not reported. Declared invalid due to sample mount not decaying properly.

VII-7 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - RIVER (PCI/LITER)

STATION NUMBER 28 DATE COLLECTED: 11/06/01 12/04/01 RADIOCHEMICAL ANALYSIS:

SR-89 L.T. 5. E-01 L.T. 6. E-01 SR-90 L.T. 6. E-01 L.T. 3. E-01 GR-A (Dissolved) L.T. 4. E+00 L.T. 5. E+00 GR-A (Suspended) L.T. 2. E+00 L.T. 3. E+00 GR-B (Dissolved) 7.1 +/-2.8 E+00 7.9+-2.8 E+00 GR-B (Suspended) 3.9 +/- 2.0 E+00 3.7+-2.0 E+00 1-131 L.T. 4. E-01 L.T. 2. E-01 GAMMA SPECTRUM ANALYSIS:

BE-7 L.T. 3. E+01 L.T. 4. E+01 00 K-40 L.T. 7. E+01 L.T. 1. E+02 MN-54 L.T. 4. E+00 L.T. 4. E+00 CO-58 L.T. 4. E+00 L.T. 5. E+00 FE-59 L.T. 8. E+00 L.T. 9. E+00 CO-60 L.T. 4. E+00 L.T. 4. E+00 ZN-65 L.T. 8. E+00 L.T. 9. E+00 ZR-95 L.T. 4. E+00 L.T. 4. E+00 RU-103 L.T. 4. E+00 L.T. 5. E+00 RU-106 L.T. 3. E+01 L.T. 4. E+01 1-131 L.T. 6. E+00 L.T. 1. E+01 CS-134 L.T. 3. E+00 L.T. 4. E+00 CS-137 L.T. 4. E+00 L.T. 4. E+00 BA- 140 L.T. 6. E+00 L.T. 8. E+00 CE-141 L.T. 6. E+00 L.T. 6. E+00 CE-144 L.T. 2. E+01 L.T. 2. E+01 RA-226 L.T. 1. E+02 L.T. 1. E+02 TH-228 L.T. 6. E+00 L.T. 9. E+00 TRITIUM ANALYSIS: 10/02-12/04 H-3 1.0 +/- 0.6 E+02 (a) Sample not collected.

(b) Data not reported. Declared invalid due to sample mount not decaying properly.

VII-7 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION WATER - RIVER (PCI/LITER)

STATION NUMBER 35 DATE COLLECTED: 01/02/01 03/06/01 RADIOCHEMICAL ANALYSIS:

SR-89 (a) L.T. 2. E+00 SR-90 (a) L.T. 7. E-01 GR-A (Dissolved) (a) L.T. 4. E+00 GR-A (Suspended) (a) 1.9 +/- 0.7 E+01 GR-B (Dissolved) (a) 1.0 +/- 0.3 E+01 GR-B (Suspended) (a) 4.2 +/- 0.4 E+01 1-131 (a) (b)

GAMMA SPECTRUM ANALYSIS:

BE-7 (a) L.T. 3. E+01 00 K-40 (a) L.T. 6. E+01 MN-54 (a) L.T. 3. E+00 CO-58 (a) L.T. 3. E+00 FE-59 (a) L.T. 8. E+00 CO-60 (a) L.T. 6. E+00 ZN-65 (a) L.T. 6. E+00 ZR-95 (a) L.T. 6. E+00 RU-103 (a) L.T. 4. E+00 RU-106 (a) L.T. 3. E+01 1-131 (a) L.T. 2. E+01 CS-1i34 (a) L.T. 3. E+00 CS-137 (a) L.T. 4. E+00 BA-140 (a) L.T. 3. E+01 CE-141 (a) L.T. 6. E+00 CE-144 (a) L.T. 2. E+01 RA-226 (a) L.T. 9. E+01 TH-228 (a) L.T. 7. E+00 TRITIUM ANALYSIS: 01/02-03/06 H-3 L.T. 1. E+02 (a) Sample not collected.

(b) Data not reported. Declared invalid due to sample mount not decaying properly.

VII-8 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AMBIENT GAMMA RADIATION: TLD milliRoentgen/Quarter Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Quarter Average Nuclide Number 01/01-04/01 04/16-07/05 07/05-10/03 10/03-01/03 + 1 std dev.

TLD 01 3.5 +/- 0.3 18.7 +/- 1.0 8.2 +/- 1.0 0.3 +/- 1.7 7.7 +/- 8.0 02 0.8 +/- 1.4 20.7 +/- 1.0 7.1 +/- 1.8 8.4 +/- 1.1 9.3 +/- 8.3 03 0.1 +/- 0.1 17.9 +/- 1.0 11.2 +/- 2.5 8.9 +/- 0.4 9.5 +/- 7.4 04 0.3 +/- 0.6 20.6 +/- 1.7 10.6 +/- 0.6 9.0 +/- 2.3 10.1 +/- 8.3 05 2.3 +/- 0.3 17.0 +/- 3.1 7.7 +/- 0.6 8.3 +/- 0.5 8.8 +/- 6.1 06 8.4 +/- 3.6 22.5 +/- 2.3 8.6 +/- 0.1 9.2 +/- 1.6 12.2 +/- 6.9 07 0.0 +/- 0.0 18.7 +/- 1.7 9.9 +/- 2.3 7.0 +/- 0.3 8.9 +/- 7.7 08 0.1 +/- 0.2 16.6 +/- 0.7 11.7 +/- 2.2 7.6 +/- 2.7 9.0 +/- 7.0 09 2.4 +/- 0.2 15.4 +/- 1.0 9.1 +/- 0.9 6.0 +/- 2.6 8.2 +/- 5.5 10 1.8 +/- 0.0 17.8 +/- 2.2 9.3 +/- 0.0 7.1 +/- 1.7 9.0 +/- 6.7 20 5.4 +/- 0.4 19.0 +/- 4.0 10.5 +/- 1.9 9.3 +/- 2.1 11.1 +/- 5.7 00 44 5.5 +/- 1.1 21.8 +/- 3.5 14.4 +/- 2.4 11.4 +/- 0.9 13.3 +/- 6.8 56 1.6 +/- 0.1 19.7 +/- 2.6 11.4 +/- 2,6 8.3 +/- 1.3 10.3 +/- 7.5 58 1.2 +/- 0.3 15.6 +/- 1.9 11.7 +/- 2.3 9.8 +/- 1.6 9.6 +/- 6.1 59 14.3 +/- 1.6 17.2 +/- 1.5 10.6 +/- 0.7 7.4 +/- 0.5 12.4 +/- 4.3 66 2.2 +/- 0.2 21.6 +/- 6.0 13.9 +/- 0.7 11.4 +/- 0.5 12.3 +/- 8.0 67 5.5 +/- 0.1 17.7 +/- 3.1 11.9 +/- 1.3 9.5 +/- 1.5 11.2 +/- 5.1 71 1.6 +/-+1.2 20.4 +/- 1.8 11.1 +/- 0.0 8.4 +/- 2.3 10.4 +/- 7.8 79 4.7 +/- 0.5 27.1 +/- 5.7 10.7 +/- 0.2 8.4 +/- 0.8 12.7 +/- 9.9 80 3.3 +/- 0.8 21.1 +/- 2.5 11.0 +/- 0.6 8.3 +/- 0.5 10.9 +/- 7.5 81 3.9 +/- 0.1 19.9 +/- 7.3 11.6 +/- 1.3 9.0 +/- 3.0 11.1 +/- 6.7 82 3.7 +/- 0.0 22.8 +/- 2.7 13.6 +/- 0.4 10.4 +/- 3.3 12.6 +/- 7.9 83 3.8 +/- 0.5 18.4 +/- 3.1 12.1 +/- 0.8 9.8 +/- 1.1 11.0 +/- 6.0 84 0.9 +/- 0.7 20.8 +/- 1.4 13.0 +/- 1.9 11.9 +/- 0.6 11.7 +/- 8.2 85 12.4 +/- 0.8 19.2 +/- 2.2 12.6 +/- 1.5 9.5 +/- 0.0 13.4 +/- 4.1 (a) Sample could not be located at site.

VII-8 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - AMBIENT GAMMA RADIATION: TLD milliRoentgen/Quarter Sample Station First Quarter Second Quarter Third Quarter Fourth Quarter Quarter Average Nuclide Number 01/01-04/01 04/16-07/05 07/05-10/03 10/03-01/03 +/- 1 std dev.

TLD 86 1.8 +/- 0.5 20.2 +/- 1.1 12.6 +/- 4.0 8.8 +/- 0.0 10.9 +/- 7.7 87 0.0 +/- 0.9 20.6 +/- 2.2 12.1 +/- 1.0 7.0 +/- 1.1 9.9 +/- 8.7 88 0.0 +/- 0.6 18.5 t 1.7 13.9 +/- 0.0 9.8 +/- 0.8 10.6 +/- 7.9 89 (a) (a) 12.8 +/- 1.4 9.3 +/- 0.4 11.1 +/-+2.5 90 2.1 +/- 0.3 17.8 +/- 1.5 11.3 +/- 0.9 6.9 +/- 2.1 9.5 +/- 6.7 91 7.4 +/- 0.9 20.3 +/- 2.7 10.5 +/- 1.0 9.5 +/- 1.6 11.9 +/- 5.7 94 1.9 +/- 0.5 19.5 +/- 2.8 13.4 +/- 2.7 9.8 +/- 1.2 11.2 +/- 7.4 Average/Quarter 3.2 +/- 3.5 mR/90 days 19.4 2.3 mR/80 days 11.2 1.8 mR/90 days 8.5 2.0 mR/92 days Average/Day 0.036 +/- 0.04 mR/day 0.24 0.03 mR/day 0.13 0.02 mR/day 0.10 0.02 mR/day 00 Range (0.0-14.3) mR/90 days (15.4-27.1) mR/80 days (7.1-13.9) mR/90 days (0.3-11.9) mR/92 days

\,C Detection/Total 27/30 30/30 31/31 31/31 (a) Sample could not be located at site.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 35 DATE COLLECTED 05/22/01 05/22/01 05/22/01 06/12/01 06/12/01 06/12/01 06/12/01 QA RADIOCHEMICAL ANALYSIS:

1-131 (a) (a) (a) (a) (a) (a) (a)

GAMMA SPECTRUM ANALYSIS:

BE-7 (a) (a) (a) (a) (a) (a) (a)

K-40 (a) (a) (a) (a) (a) (a) (a)

MN-54 (a) (a) (a) (a) (a) (a) (a)

CO-58 (a) (a) (a) (a) (a) (a) (a)

FE-59 (a) (a) (a) (a) (a) (a) (a)

CO-60 (a) (a) (a) (a) (a) (a) (a)

ZN-65 (a) (a) (a) (a) (a) (a) (a)

ZR-95 (a) (a) (a) (a) (a) (a) (a)

RU-103 (a) (a) (a) (a) (a) (a) (a)

RU-106 (a) (a) (a) (a) (a) (a) (a) 1-131 (a) (a) (a) (a) (a) (a) (a)

CS-1 34 (a) (a) (a) (a) (a) (a) (a)

CS-1 37 (a) (a) (a) (a) (a) (a) (a)

BA-1 40 (a) (a) (a) (a) (a) (a) (a)

CE-141 (a) (a) (a) (a) (a) (a) (a)

CE-144 (a) (a) (a) (a) (a) (a) (a)

RA-226 (a) (a) (a) (a) (a) (a) (a)

TH-228 (a) (a) (a) (a) (a) (a) (a)

(a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 35 DATE COLLECTED 07/17/01 07/17/01 07/17/01 08/14/01 08/14/01 08/14/01 09/11/01 RADIOCHEMICAL ANALYSIS:

1-131 (a) (a) (a) L.T. 1. E+01 (a) (a) L.T. 7. E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 (a) (a) (a) 1.54 +/- 0. E+03 (a) (a) 2.34 +/- 0. E+03 K-40 (a) (a) (a) 9.99 +/- 0. E+03 (a) (a) 5.17 +/- 0. E+03 MN-54 (a) (a) (a) L.T. 2. E+01 (a) (a) L.T. 1. E+01 CO-58 (a) (a) (a) L.T. 3. E+01 (a) (a) L.T. 1. E+01 FE-59 (a) (a) (a) L.T. 6. E+01 (a) (a) L.T. 2. E+01 CO-60 (a) (a) (a) L.T. 2. E+01 (a) (a) L.T. 2. E+01 ZN-65 (a) (a) (a) L.T. 5. E+01 (a) (a) L.T. 2. E+01 ZR-95 (a) (a) (a) L.T. 2. E+01 (a) (a) L.T. 1. E+01 RU-103 (a) (a) (a) L.T. 3. E+01 (a) (a) L.T. 1. E+01 RU-1i06 (a) (a) (a) L.T. 2. E+02 (a) (a) L.T. 1. E+02 1-131 (a) (a) (a) L.T. 1. E+02 (a) (a) L.T. 2. E+01 CS-134 (a) (a) (a) L.T. 2. E+01 (a) (a) L.T. 1. E+01 CS-137 (a) (a) (a) L.T. 2. E+01 (a) (a) L.T. 1. E+01 BA-140 (a) (a) (a) L.T. 6. E+01 (a) (a) L.T. 2. E+01 CE-141 (a) (a) (a) L.T. 4. E+01 (a) (a) L.T. 2. E+01 CE-144 (a) (a) (a) L.T. 1. E+02 (a) (a) L.T. 6. E+01 RA-226 (a) (a) (a) L.T. 6. E+02 (a) (a) L.T. 3. E+02 TH-228 (a) (a) (a) L.T. 4. E+01 (a) (a) L.T. 2. E+01 (a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 35 DATE COLLECTED 09/11/01 09/11/01 RADIOCHEMICAL ANALYSIS: (a) 1-131 L.T. 1. E+01 GAMMA SPECTRUM ANALYSIS:

BE-7 3.97 +/- 0. E+03 (a)

K-40 8.79 +/- 0. E+03 (a)

MN-54 L.T. 2. E+01 (a)

CO-58 L.T. 2. E+01 (a)

FE-59 L.T. 3. E+01 (a)

CO-60 L.T. 2. E+01 (a)

ZN-65 L.T. 4. E+01 (a)

ZR-95 L.T. 2. E+01 (a)

RU-103 L.T. 2. E+01 (a)

RU-106 L.T. 1. E+02 (a) 1-131 L.T. 3. E+01 (a)

CS-1 34 L.T. 1. E+01 (a)

CS-1 37 L.T. 2. E+01 (a)

BA-140 L.T. 2. E+01 (a)

CE-141 L.T. 3. E+01 (a)

CE-144 L.T. 1. E+02 (a)

RA-226 L.T. 5. E+02 (a)

TH-228 L.T. 3. E+01 (a)

(a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 96 DATE COLLECTED 05/22/01 05/22/01 05/22/01 06/12/01 06/12/01 06/12/01 07/17/01 RADIOCHEMICAL ANALYSIS:

1-131 (a) (a) (a) L.T. 6. E00 L.T. 8. E 00 (a) (a)

GAMMA SPECTRUM ANALYSIS:

BE-7 (a) (a) (a) 2.50 +/- 0. E+03 2.12 +/- 0. E+03 (a) (a)

K-40 (a) (a) (a) 4.58 +/- 0. E+03 5.91 +/- 0. E+03 (a) (a)

MN-54 (a) (a) (a) L.T. 2. E+01 L.T. 9. E 00 (a) (a)

CO-58 (a) (a) (a) L.T. 2. E+01 L.T. 9. E 00 (a) (a)

FE-59 (a) (a) (a) LT. 4. E+01 L.T. 2. E+01 (a) (a)

CO-60 (a) (a) (a) L.T. 2. E+01 L.T. 8. E 00 (a) (a)

ZN-65 (a) (a) (a) L.T. 4. E+01 L.T. 2. E+01 (a) (a)

ZR-95 (a) (a) (a) L.T. 2. E+01 L.T. 2. E+01 (a) (a)

RU-103 (a) (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) (a)

RU-106 (a) (a) (a) L.T. 2. E+02 L.T. 8. E+01 (a) (a) 1-131 (a) (a) (a) L.T. 5. E+01 L.T. 3. E+01 (a) (a)

CS-1i34 (a) (a) (a) L.T. 2. E+01 L.T. 8. E 00a (a) (a)

CS-1i37 (a) (a) (a) L.T. 2. E+01 L.T. 9. E 00 (a) (a)

BA-140 (a) (a) (a) L.T. 4. E+01 L.T. 6. E+01 (a) (a)

CE-1i41 (a) (a) (a) L.T. 3. E+01 L.T. 2. E+01 (a) (a)

CE-1i44 (a) (a) (a) L.T. 1. E+02 L.T. 6. E+01 (a) (a)

RA-226 (a) (a) (a) L.T. 6. E+02 L.T. 3. E+02 (a) (a)

TH-228 (a) (a) (a) L.T. 2. E+01 L.T. 2. E+01 (a) (a)

(a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 96 DATE COLLECTED 07/17/01 07/17/01 08/14/01 08/14/01 08/14/01 08/14/01 09/11/01 QA RADIOCHEMICAL ANALYSIS:

1-131 (a) (a) (a) (a) (a) (a) L.T. 6. E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 (a) (a) (a) (a) (a) (a) 2.34 +/- 0. E+03 K-40 (a) (a) (a) (a) (a) (a) 7.83 +/- 0. E+03 MN-54 (a) (a) (a) (a) (a) (a) L.T. 1, E+01 CO-58 (a) (a) (a) (a) (a) (a) L.T. 2. E+01 FE-59 (a) (a) (a) (a) (a) (a) L.T. 3. E+01 CO-60 (a) (a) (a) (a) (a) (a) L.T. 1. E+01 ZN-65 (a) (a) (a) (a) (a) (a) L.T. 3. E+01 ZR-95 (a) (a) (a) (a) (a) (a) L.T. 1. E+01 RU-103 (a) (a) (a) (a) (a) (a) L.T. 1. E+01 RU-106 (a) (a) (a) (a) (a) (a) L.T. 1. E+02 1-131 (a) (a) (a) (a) (a) (a) L.T. 3. E+01 CS-1 34 (a) (a) (a) (a) (a) (a) L.T. 1. E+01 CS-1 37 (a) (a) (a) (a) (a) (a) L.T. 1. E+01 BA-140 (a) (a) (a) (a) (a) (a) L.T. 2. E+01 CE-141 (a) (a) (a) (a) (a) (a) L.T. 3. E+01 CE-1 44 (a) (a) (a) (a) (a) (a) L.T. 8. E+01 RA-226 (a) (a) (a) (a) (a) (a) L.T. 4. E+02 TH-228 (a) (a) (a) (a) (a) (a) L.T. 3. E+01 (a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 96 DATE COLLECTED 09/11/01 09/11/01 RADIOCHEMICAL ANALYSIS:

1-131 L.T. 9. E 00 (a)

GAMMA SPECTRUM ANALYSIS:

BE-7 2.93 +/- 0. E+03 (a)

K-40 6.08 +/- 0. E+03 (a)

MN-54 L.T. 1. E+01 (a)

CO-58 L.T. 2. E+01 (a)

FE-59 L.T. 3. E+01 (a)

CO-60 L.T. 1. E+01 (a)

ZN-65 L.T. 3. E+01 (a)

ZR-95 L.T. 1. E+01 (a)

RU-103 L.T. 2. E+01 (a)

RU-106 L.T. 1. E+02 (a) 1-131 L.T. 3. E+01 (a)

CS-134 L.T. 1. E+01 (a)

CS-137 L.T. 1. E+01 (a)

BA-140 L.T. 2. E+01 (a)

CE-141 L.T. 2. E+01 (a)

CE-144 L.T. 9. E+01 (a)

RA-226 L.T. 5. E+02 (a)

TH-228 L.T. 3. E+01 (a)

(a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 101 DATE COLLECTED 05/22/01 05/22/01 05/22/01 06/12/01 06/12/01 06/12/01 07/17/01 RADIOCHEMICAL ANALYSIS:

1-131 (a) (a) (a) (a) (a) (a) L.T. 6. E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 (a) (a) (a) (a) (a) (a) 7.42 +/- 0. E+01 K-40 (a) (a) (a) (a) (a) (a) 5.27 +/-+0. E+02 MN-54 (a) (a) (a) (a) (a) (a) L.T. 9. E-01 CO-58 (a) (a) (a) (a) (a) (a) L.T. 9. E-01 FE-59 (a) (a) (a) (a) (a) (a) L.T. 2. E 00 CO-60 (a) (a) (a) (a) (a) (a) L.T. 8. E-01 ZN-65 (a) (a) (a) (a) (a) (a) L.T. 2. E 00 ZR-95 (a) (a) (a) (a) (a) (a) L.T. 9. E-01 RU-103 (a) (a) (a) (a) (a) (a) L.T. 9. E-01 RU-106 (a) (a) (a) (a) (a) (a) L.T. 8. E 00 1-131 (a) (a) (a) (a) (a) (a) L.T. 1. E 00 CS-134 (a) (a) (a) (a) (a) (a) L.T. 1. E 00 CS-1i37 (a) (a) (a) (a) (a) (a) L.T. 1. E 00 BA-140 (a) (a) (a) (a) (a) (a) L.T. 1. E 00 CE-141 (a) (a) (a) (a) (a) (a) L.T. 1. E 00 CE-144 (a) (a) (a) (a) (a) (a) L.T. 6. E 00 RA-226 (a) (a) (a) (a) (a) (a) L.T. 4. E+01 TH-228 (a) (a) (a) (a) (a) (a) L.T. 2. E 00 (a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 101 DATE COLLECTED 07/17/01 07/17/01 08/14/01 08/14/01 08/14/01 09/11/01 09/11/01 QA RADIOCHEMICAL ANALYSIS:

1-131 (a) (a) L.T. 1. E+01 L.T. 1. E+01 (a) L.T. 1. E+01 L.T. 7. E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 (a) (a) 2.14 +/- 0. E+03 1.50 +/-+0. E+03 (a) 3.52 +/- 0. E+03 4.13 +/- 0. E+03 K-40 (a) (a) 6.44 +/- 0. E+03 6.08 +/- 0. E+03 (a) 4.33 +/- 0. E+03 6.32 +/- 0. E+03 MN-54 (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) L.T. 2. E+01 L.T. 2. E+01 CO-58 (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) L.T. 2. E+01 L.T. 2. E+01 FE-59 (a) (a) L.T. 4. E+01 L.T. 2. E+01 (a) L.T. 4. E+01 L.T. 4. E+01 CO-60 (a) (a) L.T. 1. E+01 L.T. 1. E+01 (a) L.T. 2. E+01 L.T. 2. E+01 ZN-65 (a) (a) L.T. 4. E+01 L.T. 2. E+01 (a) L.T. 4. E+01 L.T. 4. E+01 ZR-95 (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) L.T. 2. E+01 L.T. 2. E+01 RU-103 (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) L.T. 2. E+01 L.T. 2. E+01 RU-106 (a) (a) L.T. 1. E+02 L.T. 9. E+01 (a) L.T. 2. E+02 L.T. 1. E+02 1-131 (a) (a) L.T. 3. E+01 L.T. 2. E+01 (a) L.T. 4. E+01 L.T. 3. E+01 CS-1i34 (a) (a) L.T. 1. E+01 L.T. 9. E 00 (a) L.T. 2. E+01 L.T. 2. E+01 CS-137 (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) L.T. 2. E+01 L.T. 2. E+01 BA-1i40 (a) (a) L.T. 2. E+01 L.T. 1. E+01 (a) L.T. 3. E+01 L.T. 2. E+01 CE-141 (a) (a) L.T. 3. E+01 L.T. 2. E+01 (a) L.T. 3. E+01 L.T. 2. E+01 CE-1i44 (a) (a) L.T. 8. E+01 L.T. 6. E+01 (a) L.T. 1. E+02 L.T. 1. E+02 RA-226 (a) (a) L.T. 5. E+02 L.T. 3. E+02 (a) L.T. 6. E+02 L.T. 5. E+02 TH-228 (a) (a) L.T. 2. E+01 L.T. 2. E+01 (a) L.T. 3. E+01 L.T. 3. E+01 (a) Vegetation sample not available.

VII-9 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY - INGESTION VEGETATION-TERRESTRIAL, BROADLEAF (PCI/KG WET)

STATION NUMBER 101 DATE COLLECTED 09/11/01 RADIOCHEMICAL ANALYSIS:

1-131 L.T. 8. E 00 GAMMA SPECTRUM ANALYSIS:

BE-7 1.73 +/-+0. E+03 K-40 6.15 +/-+0. E+03 MN-54 L.T. 2. E+01 CO-58 L.T. 2. E+01 00 FE-59 L.T. 4. E+01 CO-60 L.T. 2. E+01 ZN-65 L.T. 4. E+01 ZR-95 L.T. 2. E+01 RU-103 L.T. 2. E+01 RU-1i06 L.T. 2. E+02 1-131 L.T. 3. E+01 CS-134 L.T. 2. E+01 CS-137 L.T. 2. E+01 BA-140 L.T. 3. E+01 CE-141 L.T. 4. E+01 CE-144 L.T. 1. E+02 RA-226 L.T. 3. E+02 TH-228 L.T. 3. E+01 (a) Vegetation sample not available.

VI1-10 NEBRASKA PUBLIC POSWER DISTRICT COOPER NUCLEAR STATION EXPOSURE PATHWAY-AIRBORNE SHORELINE SEDIMENT (PCI/KG DRY)

STATION NUMBER 28 DATE COLLECTED: 05/01/01 10/02/01 GAMMA SPECTRUM ANALYSIS:

BE-7 4.28 +/- 2.81 E+02 L.T. 2. E+02 K-40 1.54 +/- 0.06 E+04 1.29 +/- 0.04 I E+04 MN-54 L.T. 2. E+01 L.T. 1. E+01 CO-58 L.T. 3. E+01 L.T. 2. E+01 FE-59 L.T. 7. E+01 L.T. 4. E+01 CO-60 L.T. 3. E+01 L.T. 2. E+01 ZN-65 L.T. 9. E+01 L.T. 6. E+01 ZR-95 L.T. 4. E+01 L.T. 4. E+01 RU-1i03 L.T. 3. E+01 L.T. 2. E+01 RU-1i06 L.T. 3. E+02 L.T. 2. E+02 1-131 L.T. 1. E+02 L.T. 4. E+01 CS-134 L.T. 4. E+01 L.T. 3. E+01 CS-1i37 4.82 +/- 1.05 E+01 L.T. 2. E+01 BA-140 L.T. 7. E+01 L.T. 3. E+01 CE-141 L.T. 4. E+01 L.T. 2. E+01 CE-144 L.T. 2. E+02 L.T. 1. E+02 RA-226 1.37 +/- 0.91 E+03 L.T. 6. E+02 TH-228 8.19 +/-+0.30 E+02 1.04 +/-+0.03 E+03

VIII. REFERENCES 100

VIII. 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).

3. Nebraska Public Power District Cooper Nuclear Station, Environmental 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 York 10014.

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

8. U.S. Regulatory Commission, Branch Technical Position, Radiological Monitoring Acceptable Program (November, 1979, Revision 1).

101

APPENDIX A LAND USE CENSUS A-1

ANNUAL CNS LAND USE CENSUS Conducted July 31, 2001 0-3 miles Cooper Nuclear Station (CNS) Offsite Dose Assessment Manual (ODAM) requires an annual land use census. 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 3 miles of CNS.

In accordance with the CNS ODAM, a land use census was performed on July 31, 2001. The nearest residence was found in sector Q, 0.9 miles from CNS, and the nearest garden was found in sector L, 1.3 miles from CNS.

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

A-2

ANNUAL CNS LAND USE CENSUS July 31, 2001 0-3 Miles SECTOR NEAREST RESIDENT Direction NEAREST GARDEN Direction NEAREST in Degrees in Degrees MILK Distance Distance ANIMAL A/N 3.0 Miles 1.00 3.0 Miles 1.00 NONE B/NNE NONE -- NONE -- NONE C/NE NONE -- NONE NONE D/ENE 1.7 Miles 62.00 NONE -- NONE E/E 1.8 Miles 92.00 2.0 Miles 85.00 NONE F/ESE 2.3 Miles 112.00 2.3 Miles 112.00 NONE G/SE NONE -- NONE -- NONE H/SSE NONE -. NONE -- NONE J/S NONE -- NONE -- NONE K/SSW 2.2 Miles 210.00 NONE -- NONE L/SW 1.3 Miles 231.00 1.3 Miles 219.00 NONE M/WSW 1.2 Miles 252.00 1.9 Miles 241.00 NONE N/W 1.0 Miles 265.00 NONE -- NONE P/WNW 1.7 Miles 294.00 2.4 Miles 293.00 NONE Q/NW 0.9 Miles 307.00 2.9 Miles 314.00 NONE R/NNW 1.9 Miles 336.00 1.9 Miles 336.00 NONE A-3

APPENDIX B

SUMMARY

OF INTERLABORATORY COMPARISONS B-I

INTERLABORA TORY COMPARISION PROGRAM A review of the 1999 Interlaboratory Comparison Program verified that Teledyne Brown Engineering did not perform iodine- 131, strontium-89, strontium-90, or gamma analyses on milk samples. TBE presumed, erroneously, that we were meeting client contract requirements. The 2001 Interlaboratory Comparison Program includes all contractually required analyses with the exception of iodine- 131 in water. This has been included in our blanket purchase order for Analytics and Environmental Resource Associates ERA for the year 2002.

The EPA discontinued their performance evaluation program in 1998. Although Teledyne Brown Engineering participated in the EPA program, there was a lapse in time between the period of the closure of the EPA program and the commencement of the ERA program. We have objective evidence that Teledyne Brown Engineering participates in these commercial ICP programs as well as documentation that we are continuing to do so.

For the year 2001 and forward, the determinations in TBE's ICP program are equivalent to or exceed the NRC requirements. This has been verified for all the Nuclear Utility clients.

However, in order to ensure this information has been communicated to all the utilities, a copy of this letter is being included in all 2001 annual reports for all utility clients.

The US Environmental Protection Agency (EPA) discontinued their Interlaboratory Comparison Program in December 1998. However, on May 1, 2001, accreditation was granted to Environmental Resource Associates' RadCheM Proficiency Testing Program to complete the process of replacing the USEEPA-LV Nuclear Radiation Assessment Division program. Teledyne Brown Engineering participates in the Analytics, Inc. and Environmental Resource Associates (ERA) programs to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability.

The National Institute of Standards and Technology (NIST) is the approval authority for laboratory providers participating in Intercomparison Study Programs; however, at this time, there are no approved laboratories for environmental and/or radiochemical isotope analyses.

Trending graphs are provided in this section for the EPA Program and for Analytics when there were at least two sets of data points to plot.

B-2

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio Month/Year Number Matrix Nuclide Units Value Value TBE/Analytics Evaluation March, 2001 E2584-93 Milk 1-131 pCi/L 75 77 0.97 A Ce-141 pCi/L 166 162 1.03 A Cr-51 pCi/L 433 418 1.04 A Cs-1 34 pCi/L 212 223 0.95 A Cs-1 37 pCi/L 165 176 0.94 A Co-58 pCi/L 81 82 0.99 A Mn-54 pCi/L 172 175 0.98 A Fe-59 pCi/L 151 146 1.03 A Zn-65 pCi/L 314 322 0.98 A Co-60 pCi/L 254 254 1 A May, 2001 A14428-55 Water Sr-89 uCi/mL 2.50E-03 2.95E-03 0.85 A Sr-90 uCi/mL 2.OOE-04 2.27E-04 0.88 A A14429-55 Water Gr-Alpha uCi/mL 1.70E-04 1.45E-04 1.17 A A14434-55 Water Fe-55 uCi/mL 2.40E-04 2.53E-04 0.95 A June, 2001 2707 Charcoal 1-131 pCi 104.5 81 1.29 W 2708 Charcoal 1-131 pCi 84.8 72 1.18 A 2709 Charcoal 1-131 pCi 99.6 92 1.08 A August, 2001 E2755-396 Milk Mn-54 pCi/L 131 124 1.06 A Co-58 pCi/L 68 68 1.00 A Fe-59 pCi/L 53 50 1.06 A Co-60 pCi/L 134 132 1.02 A Zn-65 pCi/L 172 162 1.06 A 1-131 pCi/L 76 86 0.88 A Cs-1 34 pCi/L 141 128 1.10 A Cs-1 37 pCi/L 126 120 1.05 A Ce-141 pCi/L 72 76 0.95 A August, 2001 E2757-396 AP Filter Ce-141 pCi 79 74 1.07 A Cr-51 pCi 100 90 1.11 A Cs-1 34 pCi 109 125 0.87 A Cs-1 37 pCi 140 116 1.21 W Co-58 pCi 72 66 1.09 A Mn-54 pCi 161 134 1.20 A Fe-59 pCi 51 49 1.04 A Zn-65 pCi 200 158 1.27 W Co-60 pCi 148 128 1.16 A B-3

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio Month/Year Number Matrix Nuclide Units Value Value TBE/Analytics Evaluation August, 2001 E2756A-396 Charcoal 1-131 pCi 87 93 0.94 A September, 2001 A14734-148 Liquid Sr-89 Total uCi 1.30E-03 1.55E-03 0.84 A Sr-90 Total uCi 1.OOE-04 1.12E-04 0.89 A September, 2001 A14735-148 Gas Xe-133 Total uCi 0.606 0.585 1.04 A Kr-85 Total uCi 8.53 8.42 1.01 A September, 2001 A14736-148 Charcoal 1-131 Total uCi 0.483 0.495 0.98 A September, 2001 A14737-148 Air Filter Ce-141 Total uCi 4.99E-02 5.25E-02 0.95 A Cr-51 Total uCi 1.68E-01 1.85E-01 0.91 A Cs-1 34 Total uCi 2.47E-02 2.97E-02 0.83 A Cs-137 Total uCi 5.18E-02 5.73E-02 0.90 A Co-58 Total uCi 4.60E-02 4.75E-02 0.97 A Mn-54 Total uCi 3.96E-02 4.02E-02 0.99 A Fe-59 Total uCi 2.99E-02 2.92E-02 1.02 A Zn-65 Total uCi 5.22E-02 5.12E-02 1.02 A Co-60 Total uCi 4.71 E-02 4.83E-02 0.98 A September, 2001 A14738-148 Liquid Gr-Alpha Total uCi 5.80E-04 4.67E-04 1.24 A September, 2001 A14286-148 Liquid Gr-Alpha uCi/cc 1.70E-04 1.45E-04 1.17 A H-3 uCi/cc 2.92E-03 1.77E-03 1.65 A September, 2001 E2772-396 Milk 1-131 pCi/L 100 91 1.10 A Ce-141 pCi/L 126 121 1.04 A Cr-51 pCi/L 349 366 0.95 A Cs- 134 pCi/L 147 160 0.92 A Cs- 137 pCi/L 321 319 1.01 A Co-58 pCi/L 190 177 1.07 A Mn-54 pCi/L 205 205 1.00 A Fe-59 pCi/L 85 86 0.99 A Zn-65 pCi/L 246 254 0.98 A Co-60 pCi/L 261 266 0.98 A B-4

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Ratio Month/Year Number Matrix Nuclide Units Value Value TBE/Analytics Evaluation September, 2001 E2773-396 Charcoal 1-131 68.6 68.6 67 1.02 A September, 2001 E2774-396 Air Filter Ce-141 pCi 118 116 1.02 A Cr-51 pCi 362 351 1.03 A Cs-1 34 pCi 135 153 0.88 A Cs-1 37 pCi 350 307 1.14 A Co-58 pCi 184 170 1.08 A Mn-54 pCi 230 197 1.17 A Fe-59 pCi 100 82 1.22 W Zn-65 pCi 305 244 1.25 W Co-60 pCi 267 255 1.05 A December, 2001 E2980-396 Milk Sr-89 pCi/L 75 85 0.96 A Sr-90 pCi/L 44 59 1.27 W Fe-55 pCi/L 108 99 1.09 A December, 2001 E-2981-396 Milk 1-131 pCi/L 50 61 0.82 A Ce-141 pCi/L 352 379 0.93 A Cr-51 pCi/L 468 497 0.94 A Cs-1 34 pCi/L 173 i99 0.87 A Cs-137 pCi/L 312 318 0.98 A Co-58 pCi/L 92 90 1.02 A Mn-54 pCi/L 148 149 0.99 A Fe-59 pCi/L 101 102 0.99 A Zn-65 pCi/L 192 206 0.93 A Co-60 pCi/L 322 353 0.93 A December, 2001 E-2983-396 Air Filter Ce-141 pCi 185 181 1.02 A Cr-51 pCi 190 237 0.80 A Cs-1 34 pCi 74 95 0.78 W Cs-1 37 pCi 163 152 1.07 A Co-58 pCi 46 43 1.07 A Mn-54 pCi 80 71 1.13 A Fe-59 pCi 57 49 1.16 A Zn-65 pCi 119 99 1.2 A Co-60 pCi 165 169 0.98 A B-5

DOE/EML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio Month/Year Number Media Nuclide Units Value Value TBE/EML Evaluation December, 2001 E-2982-396 Charcoal 1-131 pCi 89 92 0.93 A March, 2001 QAP 103 Air Filter Mn-54 Bq/filter 6.96 6.52 1.07 A Co-60 Bq/filter 19.4 19.44 1.00 A Cs-134 Bq/filter 2.59 2.83 0.92 A Cs- 137 Bq/filter 9.52 8.76 1.09 A Gr-Alpha Bq/filter 3.33 3.97 0.84 A Gr-Beta Bq/filter 2.26 2.58 0.88 W Sr-90 Bq/filter 7.46 7.1 1.05 A March, 2001 QAP 103 Water Co-60 Bq/L 100.3 98.2 1.02 A Cs-1 37 Bq/L 75.8 73 1.04 A Gr-Alpha Bq/L 1600 1900 0.84 A Gr-Beta Bq/L 1200 1297 0.93 A May, 2001 Sr-90 Bq/L 4.57 4.4 1.04 A H-3 Bq/L 61.0 79.3 0.77 W June, 2001 QAP 2009 Air Filters Mn-54 Bq/filter 49.5 43.2 1.15 A Co-57 Bq/filter 15.2 14.5 1.05 A Co-60 Bq/filter 8.79 8.43 1.04 A Cs-1 37 Bq/filter 8.26 7.41 1.11 A Gr-Alpha Bq/filter 2.31 2.35 0.98 A Gr-Beta Bq/filter 1.79 1.52 1.18 A June, 2001 QAP 2009 Water Co-60 Bq/L 75.7 73.7 1.03 A Cs-1 37 Bq/L 69.3 67.0 1.03 A September, 2001 QAP 0109 Air Filters Mn-54 Bq/filter 97.1 81.15 1.197 A Co-60 Bq/filter 18.8 17.5 1.074 A Cs-1 34 Bq/filter 12.7 12.95 0.981 A Cs-1 37 Bq/filter 20.8 17.1 1.216 W Gr-Alpha Bq/filter 5.42 5.362 1.011 A Gr-Beta Bq/filter 12.0 12.77 0.94 A Sr-90 Bq/filter 2.56 3.481 0.735 W September, 2001 QAP 0109 Water Co-60 Bq/L 207.3 209.0 0.992 A Cs-137 Bq/L 47.7 45.133 1.057 A Gr-Alpha Bq/L 1333.0 1150.0 1.159 W Gr-Beta Bq/L 8533.0 7970.0 1.071 A Sr-90 Bq/L 4.76 3.729 1.276 W H-3 Bq/L 212.3 207.0 1.026 A B-6

ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Ratio Month/Year Number Media Nuclide Units Value Value TBE/EML Evaluation February, 2001 Rad-29 Water Co-60 pCi/L 95.5 91.1 1.05 A Cs-1 34 pCi/L 60.5 59.8 1.01 A Cs-1 37 pCi/L 48 45 1.07 A September, 2001 Rad-38 Water Ba-1 33 pCi/L 35.5 36 0.99 A Co-60 pCi/L 47.6 46.8 1.02 A Cs-134 pCi/L 15.5 15.9 0.97 A Cs-1 37 pCi/L 206 197 1.05 A Zn-65 pCi/L 35.4 36.2 0.98 A August, 2001 Rad-39 Water Total U pCi/L 60.3 52.9 1.14 A Ra-226 pCi/L 14.7 15.4 0.95 A September, 2001 Rad-40 Water Sr-89 pCi/L 26.4 31.2 0.85 A Sr-90 pCiIL 28.2 25.9 1.09 A August, 2001 Rad-41 Water Gr-Alpha pCi/L 15.2 17.8 0.85 A Gr-Beta pCi/L 52.0 53.0 0.98 A September, 2001 Rad-42 Water H-3 pCi/L 2370 2730 0.87 A December, 2001 12130109 Water 1-131 pCi/L 3.77 4.38 0.86 A B-7

APPENDIX C SYNOPSIS OF ANALYTICAL PROCEDURES C-I

ANALYTICAL PROCEDURES SYNOPSIS Appendix C is a synopsis of the analytical procedures performed during 2001 on samples collected for the Nebraska Public Power Nuclear Plant's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by Nebraska Public Power District and Teledyne Brown Engineering and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979.

ANALYSIS TITLE PAGE Gross Beta Analysis of Sam ples ............................................................................................ C-3 A ir Particulates .......................................................................................................... C-3 Determ ination of Gross Beta A ctivity in W ater Sam ples .......................................... C-4 A nalysis of Samples for Tritium (Liquid Scintillation) ......................................................... C-5 A nalysis of Samples for Strontium -89 and -90 ...................................................................... C-6 Total W ater ................................................................................................................ C-6 M ilk ............................................................................................................................ C-6 Soil and Sedim ent ...................................................................................................... C-6 Organic Solids ............................................................................................................ C-6 A ir Particulates .......................................................................................................... C-7 Analysis of Samples for Iodine-I131 ...................................................................................... C-9 M ilk or W ater ............................................................................................................. C-9 Gam m a Spectrom etry of Samples ................................................................................... C-10 M ilk or Water ............................................................................................................. C-10 Dried Solids other than Soils and Sedim ent .............................................................. C-10 Fish ........................................................................................................................... C-10 Soils and Sedim ents .............................................................................................. C-10 Charcoal Cartridges (A ir Iodine) ......................................................................... C-10 A irborne Particulates ........................................................................................... C- 10 Environm ental Dosim etry ...................................................................................................... C-13 Low er Lim it of D etection Form ulas ................................................................................. C- 14 C-2

GROSS BETA ANALYSIS OF SAMPLES Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by the customer, is counted as the blank.

Calculations of the results, the two sigma error and the lower limit of detection (LLD):

RESULT (pCi/m)3 - ((S/T) - (B/t))/(2.22 V E) 2 TWO SIGMA ERROR (pCi/mi) 2((S/T ) + (B/t 2 ))l/ 2 /(2.22 V E) 1/2 LLD (pCi/m 3) - 4.66(B )/(2.22 V E t) where:

S Gross counts of sample including blank B Counts of blank E Counting efficiency T Number of minutes sample was counted t Number of minutes blank was counted V Sample aliquot size (cubic meters)

C-3

DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES Introduction The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.

One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.

After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchette which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.

Residue mass is determined by weighing the planchette before and after mounting the sample. The planchette is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass.

Detection Capability Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time.

The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/L at the 2.83 sigma level), assuming that 1 liter of sample is used and that 1/22 gram of sample residue is mounted on the planchette. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38.

C-4

ANALYSIS OF SAMPLES FOR TRITIUM (Liquid Scintillation)

Water Ten milliliters of water are mixed with 10 ml of a liquid scintillation "cocktail" and then the mixture is counted in an automatic liquid scintillator.

Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/L:

RESULT (N-B)/(2.22 V E) 1/2 TWO SIGMA ERROR 2((N + B)/At) / (2.22 V E) 1/2 LLD 4.66(B/At) /(2.22 V E )

where: N - the gross cpm of the sample B = the background of the detector in cpm 2.22 = conversion factor changing dpm to pCi V = volume of the sample in ml E efficiency of the detector At = counting time for the sample C-5

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added to I liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(N0 3)2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrNO 3 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and then re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrCO 3 from the sample after yttrium separation. 2 This precipitate is mounted on a nylon absorber for low level beta counting.planchette and is covered with an 80 mg/cm aluminum Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrochloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N0 3)2 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth.

Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrCO 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

Organic Solids A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N0 3) 2 using fuming (90%) nitric acid. An iron (ferric hydroxide)

C-6

scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrCO 3 from the sample after yttrium separation.

2 This precipitate is counted on a nylon planchette and is covered with an 80 mg/cm aluminum absorber for low level beta counting.

Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N0 3) 2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity.

Strontium-89 activity is determined by precipitating SrCO 3 from the sample after yttrium separation. This precipitate is counted on a nylon planchette and is covered with 80 mg/cm 2 aluminum absorber for low level beta counting.

Calculations of the result, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass:

RESULT Sr-89 = (N/At-Bc-BA)/(2.22 V Ys DFsR-89EsR-89)

TWO SIGMA ERROR Sr-89 - 2(N/At+Bc+BA)/At)" 2/(2.22 V YsDFsR-89EsR-89)

LLD Sr-89 = 4.66(Bc+BA)/At)"/ 2 /(2.22 V YsDFsR-89ESR-89)

RESULT Sr-90 = (N/At-B)/(2.22 V YI Y 2 DF IF E)

TWO SIGMA ERROR Sr-90 = 2(N/At+B)/At)" 2 /(2.22 V YI Y 2 DF E IF)

LLD Sr-90 4.66(B/At) " 2/(2.22 V Y 1 Y2 IF DF E)

Where N = total counts from sample At = counting time for sample (min)

Bc background rate of counter (cpm) using absorber configuration 2.22 dpm/pCi V volume or weight of sample analyzed BA = background addition from Sr-90 and ingrowth of Y-90 Bc = 0.016(K) + (K) EY/abs)(IGy- 9o)

Ys = chemical yield of strontium C-7

ESR-89 efficiency of the counter for Sr-89 with the 80 mg/cm. q.

aluminum absorber K (NAt-Bc)y- 90)/Ey-90 IFy-90 DF- 90Y1 )

DFy-90 the decay factor for Y-90 from the "milk" time to the mid count time Ey-9o efficiency of the counter for Y-90 IF. 90o ingrowth factor for Y-90 from scavenge time to milking time IGy_90 the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 0.016 the efficiency of measuring Sr-90 through a No. 6 absorber EY/abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm)

Y, chemical yield of yttrium Y2 = chemical yield of strontium DF = decay factor of yttrium from the radiochemical milking time to the mid count time IF ingrowth factor for Y-90 from scavenge time to the radiochemical milking time C-8

ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide.

The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.

Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/L:

RESULT = (N/At-B)/(2.22 E V Y DF)

TWO SIGMA ERROR 2((N/At+B)/At) /(2.22 E V Y DF) 1/2 LLD = 4.66(B/At) /(2.22 E V Y DF) where: N = total counts from sample (counts)

At = counting time for sample (min)

B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efficiency of the counter for 1-131, corrected for self absorption effects by the formula E = Es(exp-0.0061 M)/(exp-0.0061 Ms)

Es = efficiency of the counter determined from an 1-131 standard mount Ms = mass of Pdl 2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg C-9

GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample.

The sample is then counted for approximately 1000 minutes with a shielded high purity germanium (HPGe) detector coupled to a personal computer (PC)-based data acquisition system which performs pulse height analysis.

Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature, less than 100 0C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis.

Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis.

Soils and Sediments Soils and sediments are dried at a low temperature, less than 100°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height and analysis.

Charcoal Cartridges (Air Iodine)

Charcoal cartridges are counted up to five at a time, with one positioned on the face of a HPGe detector and up to four on the side of the HPGe detector. Each HPGe detector is calibrated for both positions. The detection limit for 1-131 of each charcoal cartridge can be determined (assuming no positive 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded HPGe detector coupled to a PC-based data acquisition system which performs pulse height analysis.

C-10

A PC software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region.

The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume of pCi/mass:

RESULT (S-B)/(2.22 t E V F DF) 1/2 TWO SIGMA ERROR - 2(S+B) /(2.22 t E V F DF) 1/2 LLD = 4.66(B) /(2.22 t E V F DF) where: S = Area, in counts, of sample peak and background (region of spectrum of interest)

B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)

F = fractional gamma abundance (specific for each emitted gamma)

DF = decay factor from the mid-collection date to the counting date C-1I

ADDENDUM TO GAMMA SPEC PROCEDURE Ba-140 (half-life =-12.8d) decays to LA-140 (half-life -40 hrs) and the daughter radionuclide, La-140 approaches .90 % of the Ba-140 activity within - 6 days. The La 140 photon energy at 1596 KeV is used to quantify the Ba-140 activity due to its high photon emission probability yield (96%) producing a higher count rate when present and therefore, a smaller associated counting error.

Zr-95 (half-life = -65d) decays to Nb-95 (half-life - -35d). The photon energy of Nb-95 (-765 KeV) is used to quantify Zr-95 because of the high photon emission probability yield (-100%) yielding a higher count rate and an associated lower counting error. The daughter radionuclide, Nb-95 approaches the Zr-95 activity after a time period of-65 days, an estimated time interval occurring between sample exposure, collection and shipping, and analysis.

C-12

Environmental Dosimetry Teledyne Brown Engineering out-sources its environmental Dosimetry services to Proxtronics Dosimetry LLC, a Wholly Owned Subsidiary of Proxtronics, Inc.

Proxtronics uses a thermo luminescent dosimeter (TLD) manufactured by Panasonic, Inc.

Panasonic identifies it as an UD-814 TLD. The TLD has four elements, numbered 1-4.

Elements and their filtration are composed of:

ELEMENT MATERIAL FILTRATION 1 nLi 2nB40 7-Cu Thin plastic 2 CaSo 4-Tm Plastic 3 CaSo 4-TmiPb Lead 4 CaSo 4-TmiPb Lead This material has a high light output, negligible thermally induced signal loss (fading) and negligible self-dosing. The energy response curve (as well as other features) satisfies NRC Regulatory Guide 4.13. Transit doses are accounted for by use of separate TLDs.

Prior to being sent to Teledyne brown, the Proxtronics badges are exposed to Cs 137, to a known dose and read in the Panasonic UD-7 1OARreader, with reference badges to establish an element response level for each badge. Badges are then re-annealed for assignment and distribution to Teledyne Brown.

Following the field exposure the badges are returned to Proxtronics for processing in a Panasonic UD-710 Reader. Each element is heated and the measured light emission is recorded. The transit controls are read in the same manner.

Transit Controls are calculated using the following equation:

TRANSDOSE= -

r(E3

_+E4 1 1 + E3 4

E4,) 7(E3trans_+/-Ee4trans)]

_.2 All dose is reported as "mR/standard month" using the following equation to calculate:

Net Exposure + 90 Days X 30.44 Days + Net Exposwe/S,,ndard Month C-13

LLD FORMULAS The LLD formulas in Section C are consistent with the LLD discussion in the ODAM. The term Sb in the ODAM equals 41B/t by Poisson statistics, where B = blank counts and t = blank counting intervals. The decay factor term e-XAI in the ODAM is the same as the DF terms in Section C, but does not appear in certain analyses such as gross beta because decay does not apply. In the tritium analysis, decay is not considered because of the relatively long half-life.

Efficiencies and volumes are consistent between the two documents, Chemical yields appear in Section C where applicable but do not apply to other analyses such as tritium and gross beta.

C-14

APPENDIX D DETECTION LIMITS AND REPORTING LEVELS D-1

NEBRASKA PUBLIC POWER - COOPER NUCLEAR STATION DETECTION LIMITS AND REPORTING LEVELS Isotope ODAM LLD Rept. Level Water - pCilliter Gross beta 4 H-3 2000 6700 Mn-54 15 330 Fe-59 30 130 Co-58 15 330 Co-60 15 100 Zn-65 30 100 Zr-95 30 130 Nb-95 15 130 1-131 1(c) 1 Cs-134 15 15 Cs-137 18 18 Ba-140 60 67 La-140 15 67 3

Air Filter - pCilm Gross Beta 0.01 N/A 1-131 0.07 0.3 Cs-1 34 0.05 3.3 Cs-1 37 0.06 6.7 Fish - pCilkq-wet Mn-54 130 10000 Fe-59 260 3300 Co-58 130 10000 Co-60 130 3300 Zn-65 260 6700 Cs-1 34 130 330 Cs-1 37 150 670 Milk - pCilliter 1-131 1 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 D-2

NEBRASKA PUBLIC POWER - COOPER NUCLEAR STATION DETECTION LIMITS AND REPORTING LEVELS Isotope ODAM LLD Rept. Level Vegetation - pCi/kq-wet 1-131 60 Cs-134 60 Cs-137 80 Sediment - pCi/kg-dry Cs-134 150 Cs-1 37 180 D-3

APPENDIX E REMP SAMPLING AND ANALYTICAL EXCEPTIONS E-1

EXCEPTIONS Appendix E contains the exceptions to the 2001 REMP Program. Where possible, causes of the deviation have been corrected to prevent recurrence. Several samples were unavailable due to seasonal unavailability. A number of samples were held by the laboratory for a long period of time before they were analyzed. NRC Regulatory Guide 4.1 Section C., Subsection b., states, "When a radionuclide with an intermediate half-life (weeks to months) is released continuously or frequently, sampling and analysis of environmental media in the associated pathway should generally be carried out at intervals no greater than two or three half-lives of the nuclide." In some cases in this report, laboratory results that were invalid due to an excessive delay in analysis do not appear in the data tables or on the corresponding trending graphs.

All deviations from the sampling schedule have been documented on the data tables. Data Tables are in Section VII.

E-2

Exceptions for Scheduled REMP Sampling and Analysis During 2001, NPPD Cooper Nuclear Station Station(s) Pathway Sample Collection Period Exception/Reason Actions Taken and Replacement Samples, Where Applicable 3 Airborne Air particulate & 03/21/01-04/24/01 Sample not available; pump Equipment repaired and returned to Charcoal Filter out of service, normal service; no further action necessary 1 Airborne Air particulate & 02/12/01-02/28/01 Station not accessible due to Regular sampling resumed when Charcoal Filter poor road conditions. conditions allowed; no further action necessary 2 Airborne Air particulate & 01/23/01-3/21/01 Station not accessible due to Regular sampling resumed when Charcoal Filter 03/27/01-0410/01 poor road conditions. conditions allowed; no further 05/29/01-06/12/01 action necessary 3 Airborne Air particulate & 01/16/01-01/30/01 Station not accessible due to Regular sampling resumed when t'rj Charcoal Filter 02/12/01-03/06/01 poor road conditions, conditions allowed; no further action necessary 4 Airborne Air particulate & 04/24/01-05/22/01 Sample not available; pump Equipment repaired and returned to Charcoal Filter out of service. normal service; no further action necessary 4 Airborne Air particulate & 02/12/01-02/28/01 Station not accessible due to Regular sampling resumed when Charcoal Filter poor road conditions. conditions allowed; no further action necessary 8 Airborne Air particulate & 01/23/01-02/20/01 Station not accessible due to Regular sampling resumed when Charcoal Filter 03/27/01-04/10/01 poor road conditions. conditions allowed; no further 05/29/01-06/12/01 action necessary 61 Ingestion Milk-Nearest 03/06/01 Declared invalid due to Laboratory provided Producer sample mount not decaying documentation; no further action I properly. required.

Station(s) Pathway Sample Collection Period Exception/Reason Actions Taken and Replacement Samples, Where Applicable 100 Ingestion Milk-Other 01/09/01 Due to delay in analysis, Laboratory provided Producer LLD's not met. documentation; no further action necessary.

11, 47 Aquatic Ground Water 01/16/01 Due to limited sample Laboratory provided volume; LLD's were not documentation; no further action met. necessary.

28, 35 Aquatic River Water 01/02/01 Sample not taken due ice Regular sampling resumed when conditions on the river, conditions allowed; no further action necessary.

28, 35 Aquatic River Water 03/06/01 Declared invalid due to Laboratory provided sample mount not decaying documentation; no further action properly. required 89 Ambient TLD 01/01/01-04/16/01 Sample badge missing. TLD's for next sampling period Gamma 04/16/01-07/05/01 were placed at sites; no further action necessary.

35 Ingestion Broadleaf 05/22/01 Insufficient vegetation; no Attributable to natural seasonal Vegetation 06/12/01 sample taken. variations and mowing; no further 07/17/01 action necessary.

08/14/01 09/11/01 96 Ingestion Broadleaf 05/22/01 Insufficient vegetation; no Attributable to natural seasonal Vegetation 06/12/01 sample taken. variations and mowing; no further 07/17/01 action necessary.

08/14/01 09/11/01

Station(s) Pathway Sample Collection Period Exception/Reason Actions Taken and Replacement Samples, Where Applicable 101 Ingestion Broadleaf 05/22/01 Insufficient vegetation; no Attributable to natural seasonal Vegetation 06/12/01 sample taken. variations and mowing; no further 07/17/01 action necessary.

08/14/01 1 1 I'

kn

APPENDIX F

SUMMARY

OF DOSES TO A MEMBER OF THE PUBLIC OFF-SITE F-I

Summary of Doses to Maximum Individual at the Site Boundary, Resulting from Exposure to Radioactivity Discharged in Liquid Effluents, January-December 2001, Cooper Nuclear Station Dose to Individual, mrem Period and Total Pathway Skin Bone Liver Thyroid Kidney Lung GI-LLI 1st 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Quarter 2nd Quarter 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 3rd Quarter 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 4th Quarter 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Totals for 2001 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+0@ 0.00 E+00 0.00 E+00

Sutmar of Gaseous Effluent Dose Calculations DOSES TO MAXIMUM INDIVIDUAL (MREM), JANUARY-DECEMBER 2001 SPECIAL LOCATION NO. 1 A Site Boundary AT .69 MILES NNW ANNUAL BETA AIR DOSE = 9.64E-03 MILLRADS ANNUAL GAM4A AIR DOSE - 1.14E-02 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

...- +..---------------..--------------+--- ------------------------------ +-----------+-----------. .

PLUME 7.61E-03 : 7.61E-03 : 7.61E-03 : 7.61E-03 : 7.61E-03 : 7.61E-03 : 7.71E-03 : 1.71E-02

... --------.. +---------------

..- +......----------- +-----------.--------------------+---------------+-------------

GROUND ; 9.26E-02 : 9.26E-02 : 9.26E-02 : 9.26E-02 : 9.26E-02 : 9.26E-02 : 9.26E-02 : 1.06-01

-+-------+------------+---------------+---------------+-----------+---------------+----------------0----------------+

VEGET ADULT 1.06Z-01 3.30E+00 1,61E+00 3.39E-03 1.18E-03 6.60E-03 1.31E-03 0.00E+00

-.. ..----------------.--------------- +---------------. . +..-------- -+---------------+-------------

TEEN : 1.65E-01 : 3.921+00 : 2,55E+00 : 5.32E-03 : 1.85E-03 : 8.89E-03 : 2.38Z-03 : 0.00E+00

+-------+--------------+--------------+-----------+---------------+---------------+---------------+---------------+

CHILD : 3.52E-01 : 3.05E+00 ; 6.02E+00 : 9.05E-03 : 3.01E-03 : 1.70E-02 : 3,58E-03 : 0.00E+00

-+-------------------+--------------+---------------+-----------+---------------+---------------4---------------+

HEAT ADULT 4.05E-03 1.25E-01 6.08E-02 1.88E-04 6.45E-05 1.78E-04 5.62E-05 0.00E+00

+---------------+-----------+-----------+---------------+---------------+-----------+---------------+

TEEN : 3.26E-03 : 7.74E-02 : 5.03E-02 : 1.52E-04 : 5.21E-05 : 1.29E-04 : 5.32E-05 0.00E+00

+

CHILD ; 5.42E-03 : 4.69E-02 : 9.28E-02 : 2.01E-04 : 6.61E-05 : 1.94E-04 : 6.23E-05 : 0.00E+00

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

COW MILK :

ADULT : 4.34E-03 1,17E-01 5.75E-02 1.03E-03 3.69E-04 4,94E-03 1.47E-04 O.00E+00

+4--- - +-

+ ----------------- +---------------+---------------+------------------------------------- +

TEEN : 7.20E-03 : 1.58E-01 : 1.04E-01 : 1.81E-03 : 6.53E-04 : 7,82E-03 : 3.04E-04 : 0.00E+00

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

CHILD : 1.49E-02 : 1.25E-01 : 2,51E-01 : 3.14E-03 : 1.08E-03 : 1.55E-02 : 4.66E-04 : 0.00R+00

-+-------+-----------+---------------+---------------+---------------+---------------+---------------+---------------+

INFANT : 2.67E-02 : 1.25E-01 ; 5.14E-01 : 6.23E-03 : 1.76E-03 : 3.76E-02 ; 9.22E-04 : 0.00E+00

-+-------+-------------+---------------+---------------+---------------+---------------+-----------+---------------+

GOATMILK :

ADULT : 2,31E-03 1.41E-02 9.04E-03 2.85E-03 9.91E-04 5.93E-03 3.23E-04 O.00E+00

-++---------------------------+--------------- +--------------------------------------------------+

TEEN : 2.55E-03 : 1.91E-02 : 1.63E-02 : 5.02E-03 : 1.75E-03 : 9.39E-03 : 6.67E-04 : 0.00E+00

-+ + ++--------- --------------

4-------------------------------+---------------+---------------

CHILD : 3.06E-03 : 1.51E-02 : 3.94E-02 : 8.70E-03 : 2.91E-03 : 1.86E-02 : 1.03E-03 : 0.001+00 +/-

-+-------+-------------+---------------+---------------+-----------+---------------+---------------+---------------+

INFANT : 4.44E-03 ; 1.51E-02 : 7.69E-02 : 1.70E-02 : 4.69E-03 : 4.51E-02 : 1.87E-03 : 0,00E+00

-+-------+--------------4---------------+-----------+---------------+------------- '-4---------------+---------------+

INHAL ADULT 2.26E-04 1.90E-02 3.39E-03 9.19E-06 4.61E-06 4.28E-05 1.10E-01 0.00E+00

-++

+ - - --------------------------------------------------------------------------- +

TEEN ; 3.09E-04 : 1,99E-02 : 4.75E-03 : 1,26E-05 : 6.33E-06 : 5.38E-05 ; 1.76E-01 : 0.00E+00

-+-----------------------+--------------+---------------+-----------+---------------+---------------+-----------+

CHILD : 3.79E-04 : 8.90E-03 : 6.43E-03 : 1,22E-05 ; 5.90E-06 : 6,23E-05 ; 1.51E-01 : 0.00E+00

-- - +-----------+---------------+---------------+---------------4---------------4---------------+---------------+

INFANT . 2.54E-04 : 3.39E-03 ; 4.87E-03 ; 1.05E-05 : 3.80E-06

5.69E-05 : 1,39E-01 : 0.OOE+00

-- - +-----------+---------------+---------------4---------------+---------------+---------------+---------------+

Summary of Gaseous Effluent Dose Calculations DOSES TO MAXIMUM INDIVIDUAL (MREM), JANUARY-DECEMBER 2001 (CONTINUED)

SPECIAL LOCATION NO. 2 A Site Boundary AT .67 MILES N ANNUAL BETA AIR DOSE = 1.04E-02 MILLRADS ANNUAL GAMMA AIR DOSE = 1.24E-02 MILLRADS PATHWAY T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

...... +--------------+-.---------------.---------------.---------------.---------------.---------------+-----------+

PLUME : 8.30E-03 : 8.30E-03

8.30E-03 ; 8.30E-03 : 8.30E-03 : 8.30E-03 ; 8.41E-03 : 1.85E-02

..... +.---------------+-.---------------.....----------------+-----------------------------------

GROUND : 1.07E-01 : 1.07E-01 : 1.07E-01 : 1.07E-01 : 1.07E-01 : 1.07E-01 : 1.07E-01 : 1.22E-01

4---------------+---------------+---------------+---------------+-----------+----------+

VEGET :

ADULT 1.22E-01 3.80E+00 1.85E+00 3.92E-03 1.37E-03 9.63E-03 1.50E-03 : O.00E+00

-+-------+-----------+---------------4---------------+---------------+---------------4---------------+---------------4 TEEN : 1.90E-01 : 4.51E+00 : 2.93E+00 : 6.14E-03 : 2.15E-03 : 1.30E-02 : 2.74E-03 : O.00E+00

+---------------+---------------.---------------4---------------4---------------+---------------4 CHILD : 4.05E-01 : 3.51E+00 : 6.94E+00 : 1.04E-02 : 3.50E-03 : 2.49E-02 : 4.12E-03 : O.00E+00

+-------------4---------------4---------------+---------------+---------------.$-----------+---------------4 HEAT ADULT 4.66E-03 1.441-01 7.00E-02 2.17E-04 7.47E-05 2.59E-04 6.47E-05 :0.OOE+00

...... +.---------------+------------+--+---------------+---------------..+.------- -.--------------- +---------------+

TEEN : 3.76E-03 : 8.91E-02 : 5.79E-02 : 1.75E-04 : 6.03E-05 : 1.88E-04 : 6.13E-05 : O.00E+00

...... ---------------.....--------------- 4.--------------- +.-------..---------------..---------------..-----------..

CHILD : 6.25E-03 : 5.40Z-02 : 1.07E-01 : 2.31E-04 : 7.65E-05 : 2.84E-04 : 7.18E-05 : 0.00E+00

+----------.+---------------+.---------------+---------------.---------------.---------------+---------------+

COW MILK :

ADULT : 5.01Z-03 1.35E-01 6.63E-02 1.19E-03 4.34E-04 7.22E-03 1.69E-04 :0.OOE+00

.... ...---------------+-------------.---------------..---------------. . +..------------------------.---------------4.

TEEN ; 8.29E-03 : 1.82E-01 : 1.20E-01 : 2.10E-03 : 7.68E-04 : 1.14E-02 : 3.50E-04 : O.00E+00

. ...---------------+-- . .. --------------- +---------------+.------- .--------------- +---------------+

CHILD ; 1.72E-02 : 1.44E-01 : 2.89E-01 : 3.63E-03 : 1,27E-03 : 2.26E-02 : 5.37E-04 : 0.00E+00

..... +--- -- ----------------- +---------------..-----+---------------------------------------------+

INFANT : 3.08E-02 : 1.44E-01 : 5.93E-01 : 7.22E-03 : 2.07E-03 : 5.49E-02 : 1.06E-03 : O.00E+00

.. .+.-------------------------------------------------..-------- -.------------------------------

GOATMILK :

ADULT : 2.67E-03 1.63E-02 1.05E-02 3.291-03 1.15E-03 8.66E-03 3.73E-04 0.OOE+00

.... .+.---------------.+--- . ------------------------------ +.------- ------------------------------

TEEN : 2.95E-03 : 2.20E-02 : 1.90E-02 : 5.80Z-03 : 2.04E-03 : 1.37E-02 : 7.70E-04 : 0.00E+00

. .. -4......+

÷----------------------+---------------..+.-------- -+---------------+---------------. .

CHILD : 3.54E-03 : 1.74E-02 : 4.58E-02 : 1.01E-02 : 3.39E-03 : 2.71E-02 : 1.18E-03 : 0.00E+00

.+..---------------4.----------------------------------------------------------------------------+

INFANT : 5.153-03 1.74E-02 ; 8.92E-02 : 1.97E-02 : 5.46E-03 : 6.59E-02 : 2.15E-03 : O.OOE+00

-+-----------4---------------4---------------+---------------+---------------+---------------4---------------4 INHAL ADULT 2.43E-04 2.04E-02 3.65E-03 9.82E-06 4.91E-06 4.52E-05 1.19E-01 O.00E+00

- +-----------------+---------------4---------------4---------------+--------------- .4---------------4---------------+

TEEN : 3.32E-04 : 2.14E-02 : 5.12E-03 : 1.35E-05 : 6.73E-06 : 5.69E-05 : 1.90E-01 : 0.001E00

-.----------- 4---------------4---------------4---------------+---------------4---------------4---------------+

CHILD : 4.08E-04 : 9.58E-03 : 6.92E-03 : 1.31E-05 : 6.28E-06 : 6.58E-05 : 1.63E-01 : O.00E+00

-+-------+-----------4---------------4---------------4---------------+---------------4---------------4---------------4 INFANT : 2.73E-04 : 3.65E-03 : 5.24E 1.13E-05 ; 4.05E-06 ; 6.01E-05 : 1.49E-01 : 0.00E+00

.......-------------------------------------- +---------------..------- -+---------------+.---------------.

Summary of Gaseous Effluent Dose Calculations DOSES TO MAXIMUM INDIVIDUAL (HREM), JANUARY-DECEMBER 2001 (CONTINUED)

SPECIAL LOCATION NO. 3 A Nearest Res AT .90 MILES NW ANNUAL BETA AIR DOSE = 3.57E-02 MILLRADS ANNUAL GAMMA AIR DOSE - 3.83E-02 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN

...---------------.- +-.------------------------------.. +..------- .---------------.

+--------------

PLUME ; 2.56E-02 ; 2.561-02 : 2.56E-02 ; 2.56E-02 : 2.56E-02 : 2,56E-02 : 2.60E-02 : 6.17E-02

- 4-----------------------+---------------4---------------+---------------+-----------+-----------.4---------------4 GROUND : 6.89Z-02 : 6.89E-02 : 6.89E-02 ; 6.89E-02 : 6.89E-02 : 6,89E-02 : 6.89E-02 : 7.88E-02

-+------------..---------------..---------------.+- -..--------------- +---------------.+-----------..--------------. .

VEGET ADULT 7.87E-02 2.45E+00 1.19E+00 2.55E-03 9.12E-04 1.11E-02 9.71E-04 0.00E+00

.-----------+---------------+--------------- .4---------------4--------------- .4---------------.4---------------4 TEEN : 1.22Z-01 ; 2.91Z+00 : 1.89E+00 : 3.99E-03 1.43E-03 : 1.49z-02 : 1.77B-03 : 0.00E+00 S+-------4----------+---------------+---------------4---------------------------------4---------------+---------------4 CHILD : 2.61E-01 : 2.26E+00 : 4.48E÷00 : 6.79E-03 2.33E-03 : 2.86E-02 : 2.66E-03 : 0.00E+00

.-----------+---------------+---------------+--------------- .4---------------+---------------.---------------4 MEAT : :: ::

ADULT 3.01E-03 9.28E-02 4.52E-02 1.41E-04 4.90E-05 2.98Z-04 4.18E-05 :0.00E+00

....... +.....---+-.......-+..---------------+---------------+.---------------+----+---------------..--------------. .

TEEN ; 2.42F-03 : 5.753-02 : 3.739-02 ; 1.14E-04 : 3.96E-05 : 2.16E-04 : 3.96E-05 ; 0.00Z+00

... .--------------- +---------------..---------------+..------------....--------------- ...---------. +---------------.

CHILD : 4.03E-03 : 3.48E-02

6.89E-02 1.50Z-04 ; 5.02E-05 t 3,25E-04 : 4.63E-05 : 0.001400

ý--------------..

-+--------------+--------------..----.---------.. ---------.----.. ------------.-..--------------.4+-------------

COW MILK ADULT 3.24E-03 8.68E-02 4.28E-02 7.82E-04 3.01E-04 8.30E-03 1.10E-04 0.00E+00 S4----------+--------------+---------------4---------------+---------------.~---- 4---------------+---------------4 TEEN : 5.37E-03 : 1.17E-01 : 7.73E-02 : 1.38E-03 : 5.33E-04 : 1.31E-02 : 2.27E-04 ; 0,00E+00

.4-------------------4---------------4---------------4---------------+-------------------------------4---------------4 CHILD : 1.11E-02 : 9.31E-02 : 1,87E-01 : 2.39E-03 : 8.84E-04 : 2.60E-02 : 3.48E-04 : 0.00E+00 S+-------+-----------+---------------+---------------+---------------+---------------4---------------4---------------4 INFANT ; 1.99E-02 : 9.28E-02 : 3.83E-01 : 4.77E-03 : 1.44E-03 : 6.31E-02 : 6.88E-04 : 0.00E+00 S+-------4-----------4---------------4---------------+---------------4---------------.----------------4---------------4 GOATMILK :

ADULT : 1,74E-03 1.05E-02 6.95E-03 2.15E-03 7,72E-04 9.96E-03 2.42E-04 :0.00E+00

+--.-..---------------+---------------+---------------+---------------

. 4.---------------+--------------.

TEEN ; 1.93E-03 : 1,42E-02 : 1.26E-02 : 3.79E-03 ; 1.37Z-03 : 1.58E-02 : 5.00E-04 : 0.00E+00

......---- -4... -... ---.---------------..--------------- 4 .. ..----

CHILD : 2.33E-03 ; 1.139-02 : 3.04E-02 : 6.57E-03 : 2.27E-03 : 3.12E-02 : 7.68E-04 : 0.001E00

.+ 4......+---...---------------..--------------- 4.---------------+--------------- 4.---------------..--------------.

INFANT : 3.41E-03 , 1.12E-02 : 5,91E-02 : 1.29E-02 : 3.66E-03 : 7.58E-02 : 1.40E-03 : 0.00E+00

..... ---------------....---.. ..---------------..---------------. +--.---------------.. ...----------..---------------.

INHAL :

ADULT 4.39E-04 3.65Z-02 6.53E-03 2.69E-05 1.63E-05 1.79E-04 2.12E-01 0.00E+00

4---------------4---------------4---------------4---------------+-----------+-----------+---------------4 TEEN : 6.00E-04 : 3.82E-02 ; 9.15E-03 : 3.69E-05 ; 2.24E-05 ; 2.26E-04 : 3.39E-01 : 0.00E+00

+--------.-------------+---------------+---------------4---------------+-----------+---------------4---------------4 CHILD : 7.37E-04 : 1.73E-02 : 1.24E-02 : 3.60E-05 : 2.10E-05 : 2.64E-04 ; 2.91E-01 : 0.00E+00

+--------.-----------4---------------.4---------------4---------------4---------------4---------------4---------------4 INFANT ; 4.94E-04 : 6.69E-03 : 9.37E-03 : 3.19E-05 : 1.37E-05 : 2.41E-04 : 2.66E-01 : 0.00E÷00

+-+-..-------------------------------.---------------------------------------------+-------------.

APPENDIX G REMP SAMPLE STATION DESCRIPTIONS G-1

REMP SAMPLE STATION DESCRIPTIONS The following pages contain descriptions of the CNS REMP Sample Stations that were active or were used for part or all of 2001. There were no changes to the CNS REMP Sample Stations from the previous year.

G-2

REMP SAMPLE STATION DESCRIPTIONS SAMPLE TYPES AND SAMPLE LOCATIONS Sample Station (a) Sample Description - Type and Location No. 1 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Outside the northwest edge offence, east of the gate to the LLRW storage pad on the CNS site, NW 1/4, S32, T5N, R 16E, Nemaha County, Nebraska.

No. 2 Type: (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: North side of county road to the south portion of CNS site, SW 1/4, S32, T5N, R I6E, Nemaha County, Nebraska.

No. 3 Type (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Located on the north side of the Brownsville State Recreation Park access road near water gauging station, SE 1/4, S 18, T5N, R I6E, Nemaha County, Nebraska.

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

No. 5 Type (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Located /4 mile south and 1/4 mile east of Langdon, Missouri, on north side of road, west of railroad tracks, SW 1/4, T64N, R41W, Atchison County, Missouri.

No. 6 Type (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: One mile west of the end of Missouri State Highway "U", SW comer of the intersection, NW 1/4, S34, T64N, R42W, Atchison County, Missouri G-3

Sample Station Sample Description - Type and Location 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, SW 1/4, S6, T4N, RI 6E, Nemaha, Nebraska.

No. 8 Type (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: /2 mile north, 3/4 mile west and 3/4 mile north of Nemaha, on west side of road adjacent to transmission line, NE 1/4, S35, T5N, R15E, Nemaha County, Nebraska.

No. 9 Type (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: Four miles north of Highway 136, on Highway 67.

Then I mile east of Highway 67 and 1/2 mile north on west side of road, SW 11/4, S26, T6N, R15E, Nemaha County, Nebraska.

No. 10 Type (1) Air Particulate and Charcoal Filters (2) Environmental Thermoluminescent Dosimetry Location: One mile north of Barada, Nebraska, in SW corner of intersection, NE 1/4, S 14, T3N, RI6E, Richardson County, Nebraska.

No. 11 Type: (1) Water-Ground Location: Plant well water supply header at well pits, NW 1/4, S32, T5N, R16E, Nemaha County, Nebraska.

No. 12 Type: (1) Water- River Location: Sample (1) taken from the Missouri River immediately upstream form the Plant Intake Structure (River Mile 532.5). During periods when unsafe conditions warrant, Station 35 may be used as an alternate upstream collection site.

G-4

Sample Station Sample Description - Type and Location No. 20 Type: (1) Environmental Thermoluminescent Dosimetry Location: On NNW boundary of NPPD property, east side of county road, SE, S30, T5N, RI 6E, Nemaha County, Nebraska.

No. 28 Type (1) Water - River, (2) Fish (3) Sediment from Shoreline (4) Food Products - Broadleaf Vegetation Location: Samples (1), (3), and (4) are taken from the Missouri River or its shore downstream near River Mile 530, Sample (2) is taken from the Missouri River 1/2/2 to 3 miles downstream of the plant site.

No. 35 Type (1) Fish (2) Water - River (Alternate Site)

(3) Food Products - Broadleaf Vegetation Location: Sample (1) will be taken from the Missouri River about 1 to 3 miles above the CNS intake structure. During periods when unsafe conditions warrant, Station 35 may be used as an alternate to Station 12 (upstream collection site) for sample type (2). Sample (3) is taken about '/

mile south of the Brownville State Recreation Area in Sector A.

No. 42 Type: (1) Milk - Other Producer Location: One mile south, 1 1/4/miles east of Barada, Nebraska, south side of county road, NW 1/4, S30, T3N, R17E, Richardson County, Nebraska.

No. 44 Type: (1) Environmental Thermoluminescent Dosimetry Location: /4 mile south of Auburn Country Club on Highway 75, then 2 mile east of Highway 75 at fence line north of county road, SE1/4, S27, T5N, R14E, Nemaha County, Nebraska.

No. 47 Type: (1) Water -Ground Location: At Falls City Municipal water supply well NOTES:

(a) Sample station numbers missing from the sequence are for inactive or discontinued sampling locations.

G-5

Sample Station Sample Description - Type and Location 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, NW 1/4, $23, 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, SE 1/4, S31, T5N, Ri 6E, Nemaha County, Nebraska.

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

No. 61 Type (1) Milk - Nearest Producer Location: One mile west of Brownville, Nebraska, on Highway 136, then I mile north on the county road, turn right and proceed approximately /2mile east on south side of road, NW1/4, S13, T5N, RI5E, Nemaha County, Nebraska.

No. 66 Type: (1) Environmental Thermoluminescent Dosimetry Location: Two miles south of Nemaha, Nebraska, on Highway 67

- east side of road, NW 1/4, S19, T4N, RI 6E, Nemaha County, Nebraska.

No. 67 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2 miles west of Brownville, Nebraska, on Highway 136, then north 1 1/2 miles on county road and east 1/2 mile, on north side of road, NE1/4, S11, T5N, RI5E, Nemaha County, Nebraska.Sample NOTES:

(a) Sample station numbers missing from the sequence are for inactive or discontinued sampling stations.

G-6

Sample Station Sample Description - Type and Location No. 71 Type: (1) Environmental Thermoluminescent Dosimetry Location: Two miles east of Phelps City, Missouri, on Highway 36, then south 1 1/4/miles on county road and west 1/4 mile, SE1/4, 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 property, SE1/4, S30, T5N, R16E, Nemaha County, Nebraska.

No. 80 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2 1/8 miles south of Brownville, on east side of paved road, NPPD property, NE 1/4, S31, T5N, RI 6E, Nemaha County, Nebraska.

No. 81 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2 3/8 miles south of Brownville, Nebraska, in the NE comer of the intersection of the paved county road and CNS access road, NPPD property, NE 1/4, S31, T5N, R16E, Nemaha County, Nebraska.

No. 82 Type: (1) Environmental Thermoluminescent Dosimetry Location: 7/8 mile south of CNS in a field, on NPPD property, SW1/4, S32, T5N, R16E, Nemaha County, Nebraska.

No. 83 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2 t1/4 miles south of Nemaha, Nebraska, on Highway 67, then east I mile to the junction of the driveway and county road (east side of drive), NEI/4, S19, T4N, RI6E, Nemaha County, Nebraska.

No. 84 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2 1/2A miles west of Brownville, NE, south side of Highway 136 west of Locust Grove School, NW 1/4, S22, T5N, R15E, Nemaha County, Nebraska.Sample NOTES:

(a) Sample station numbers missing from the sequence are for inactive or discontinued sampling stations.

G-7

Sample Station Sample Description - Type and Location 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, NEI/4, S33, T65N, R42W, Atchison County, Missouri.

No. 86 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile west of Phelps City, Missouri, on Highway 136, then north 1 /2 miles on Highway "D" on west side, SE1/4, S22, T65N, R42W, Atchison County, Missouri.

No. 87 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile west of Phelps City, Missouri, on Highway 136, then south 2 mile on county road and 3/4 mile west on county road to the end of the road, NW1/4, S3, T64N, R42W, Atchison County, Missouri.

No. 88 Type: (1) Environmental Thermoluminescent Dosimetry Location: One mile west of Phelps City, Missouri, on Highway 136, then south 2 miles at the end of the county road, NW 1/4, S 11, T64N, R42W, Atchison County, Missouri.

No. 89 Type: (1) Environmental Thermoluminescent Dosimetry Location: 2 V2 miles south of Phelps City, Missouri, on Highway "U", then 1/2/2 mile west in the SE comer of the county road intersection, NE 1/4, S 14, T64N, R42W, Atchison County, Missouri.

No. 90 Type: (1) Environmental Thermoluminescent Dosimetry Location: 1 /2 miles west and 3/4 mile south of Langdon, Missouri, on Highway "U", then /4mile west, SW 1/4, S23, T64N, R42W, Atchison County, Missouri.Sample NOTES:

(a) Sample station numbers missing from the sequence are for inactive or discontinued sampling stations.

G-8

Sample Station Sample Description - Type and Location No. 91 Type: (1) Environmental Thermoluminescent Dosimetry Location: /2 mile west of Rockport, Missouri,on the south side of the intersection of U.S. Highway 136 and U.S.

Highway 275, at the south side of the water tower, NW1/4, S28, T65N, R41W, Atchison County, Missouri.

No. 94 Type: (1) Environmental Thermoluminescent Dosimetry Location: /4mile of Langdon, Missouri, on the west side of the road, NE1/4, S24, T64N, R42W, Atchison County, Missouri.

No. 96 Type: (1) Food products - Broadleaf Vegetation Location: Approximately I mile south of Brownville, Nebraska, along the paved road, in the road ditch in Sector R, SW 1/4, S 19, T5N, RI 6E, Nemaha County, Nebraska.

No. 99 Type: (1) Milk (Nearest and Other Producer)

Location: 1 1/4 mile south of Shubert, Nebraska, on the west side of Highway 67, NE 1/4, S24, T3N, R I5E, Richardson County, Nebraska.

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

Location: Two miles south and I mile west of Shubert, Nebraska, SW1/4, S23, T3N, R15E, Richardson County, Nebraska.

No. 101 Type: (1) Food Products - Broadleaf Vegetation Location: 5 /2 miles east and 1/2A mile north of Rock Port, Missouri, near the junction of Highway 136 and Highway 59, in Sector D, encompasses portions of several sections, Athison County, Missouri.

NOTES:

(a) Sample station numbers missing from the sequence are for inactive or discontinued sampling stations.

G-9

NLS2002054, Annual Radiological Environmental Operating Report

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