Text

Annual Radiological Environmental Operating Report for 2001
	ML021330153
Person / Time
Site:	Cook
Issue date:	04/24/2002
From:	Greenlee S; Indiana Michigan Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	AEP:NRC:2691-07
	Download: ML021330153 (132)
	v • d • e

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1373 INDIANA MICHIGAN POWER April 24, 2002 AEP:NRC:2691-07 10 CFR 50, Appendix I Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Enclosed is the Donald C.

Cook Nuclear Plant Annual Radiological Environmental Operating Report. This report covers the period from January 1, 2001, through December 31, 2001, and it was prepared in accordance with the requirements of Technical Specification 6.9.1.6 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C.

There are no new commitments in this submittal. Should you have any questions, please contact Mr. Gordon P. Arent, Manager of Regulatory Affairs at (616) 697-5553.

Sincerely, Scot A. Greenlee Director, Nuclear Technical Services

/dmb Attachment c:

K. D. Curry, w/o attachment J. E. Dyer MDEQ - DW & RPD, w/o attachment NRC Resident Inspector R. Whale, w/o attachment

U. S. Nuclear Regulatory Commission AEP:NRC:2691-07 Page 2 bc:

G. P. Arent, w/o attachment A. C. Bakken J. P. Carlson/D. L. Noble/J. H. Harner P. B. Cowan, w/o attachment R. W. Gaston, w/o attachment S. A. Greenlee S. B. Haggerty, w/o attachment (Commitment #7923)

D. W. Jenkins, w/o attachment J. A. Kobyra, w/o attachment D. Minnaar J. E. Pollock, w/o attachment J. F. Stang, Jr., NRC - Washington, DC T. R. Stephens, w/o attachment

ATTACHMENT 1 TO AEP:NRC:2691-07 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

DONALD C. COOK NUCLEAR PLANT UNITS 1 & 2 Annual Radiological Environmental Operating Report January 1 to December 31, 2001 Prepared by Indiana Michigan Power Company and Teledyne Brown Engineering 1

TABLE OF CONTENTS SECTION TITLE PAGE Sum m ary................................................................................................................

6 I.

Introduction...............................................................................................................

8 II.

Changes......................................................................................................................

10 III.

Sam pling and Analysis Program.............................................................................

13 IV.

Sum m ary and Discussion of 2001 Analytical Results............................................

22 A.

Airborne Particulates.................................................................................

24 B.

Airborne Iodine........................................................................................

24 C.

Direct Radiation - TLDs............................................................................

24 D.

Surface W ater...........................................................................................

25 E.

Groundwater..............................................................................................

25 F.

Drinking W ater.........................................................................................

25 G.

Sedim ent..................................................................................................

26 H.

M ilk.........................................................................................................

26 I.

Broadleaf Vegetation.................................................................................

26 J.

Fish..........................................................................................................

26 K.

Food Products...........................................................................................

27 V.

Conclusions.........................................................................................................

34 VI.

References 37 2

TABLE OF CONTENTS (Cont)

APPENDICES APPENDIX A - Radiological Environmental Monitoring......................................................

39 Program Summary A PPEN D IX B - D ata Tables.........................................................................................................

45 APPENDIX C - Analytical Procedures Synopsis......................................................................

69 APPENDIX D - Summary of Interlaboratory Comparisons....................................................

78 APPENDIX E - REMP Sampling and Analytical Exceptions..................................................

96 APPENDIX F - Land Use Census - 2001...................................................................................

100 APPENDIX G - Summary of the Pre-operational Radiological.................................................

111 Monitoring Program APPENDIX H-Summary of the REMP Quality Control Program............................................

114 APPENDIX I - TLD Quality Control Program..........................................................................

128 3

TABLE OF CONTENTS (Cont)

LIST OF FIGURES

1.

Onsite REM P M onitoring Locations...........................................................................

20

2.

Offsite REM P M onitoring Locations..........................................................................

21

3.

M ilk Farm Survey Table.................................................................................................

103

4.

M ilk Farm Survey M ap...................................................................................................

106

5.

Land Use Survey Table..................................................................................................

109

6.

Residential Survey M ap..................................................................................................

110 LIST OF TRENDING GRAPHS

1.

Average M onthly Gross Beta in Air Particulates........................................................

28

2.

Direct Radiation - Quarterly TLD Results...................................................................

29

3.

Tritium in Groundwater................................................................................................

30

4.

Tritium in Drinking W ater...........................................................................................

33

5.

Interlaboratory Com parisons Program..........................................................................

84 4

LIST OF TABLES TABLE TITLE PAGE B-1 Concentrations of Gross Beta Emitters in Weekly...........................................................

46 Airborne Particulates B-2 Concentrations of Gamma Emitters in Quarterly.............................................................

50 Composites of Airborne Particulates B-3 Concentrations of Iodine-131 in Weekly Air Cartridge..................................................

52 Samples B-4 Direct Radiation Measurements - Quarterly TLD Results..............................................

54 B-5 Concentrations of Iodine, Tritium and Gamma Emitters.................................................... 55 in Surface Water B-6 Concentrations of Tritium and Gamma Emitters in.................................................... 56 Groundwater B-7 Concentrations of Gross Beta, Iodine, Tritium and...................................................... 58 Gamma Emitters in Drinking Water B-8 Concentrations of Gamma Emitters in Sediment...................................................

60 B-9 Concentrations of Iodine and Gamma Emitters in Milk..................................................

61 B-10 Concentrations of Gamma Emitters in Food/Vegetation..................................................

65 B-11 Concentrations of Gamma Emitters in Fish....................................................................

66 B-12 Gamma Spec LLDs and Reporting Levels......................................................... 67 5

SUMMARY

6

INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

SUMMARY

This report summarizes the collection and analysis of various environmental sample media in 2001 for the Radiological Environmental Monitoring Program for the Donald C. Cook Nuclear Plant.

The various analyses of most sample media suggest that there was no discernible impact of the Donald C. Cook Nuclear Plant on the environment. The analysis of air particulate filters, charcoal cartridges, direct radiation by thermoluminescent dosimeters, fish, water, milk, sediments from Lake Michigan, drinking water, and food products, either did not detect any radioactivity or measured only normal background levels of naturally occurring or normal background levels of ambient manmade radionuclides.

Tritium, measured at low levels in on-site wells, appears to be the only radionuclide attributable to the plant operations. However, the associated groundwater does not provide a direct dose pathway to humans.

7

I. INTRODUCTION 8

I.

INTRODUCTION The Donald C. Cook Nuclear Plant's Radiological Environmental Monitoring Program (REMP) is conducted in compliance with NRC Regulatory Guide 1.21 and 4.1, licensing commitments, and Technical Specifications. The REMP was developed in accordance with the NRC Radiological Assessment Branch Technical Position (BTP), Rev. 1, November 1979. A synopsis of the sampling program and maps can be found in Section III, Sampling and Analysis Program. This report represents the Annual Radiological Environmental Operating Report (AREOR) for Units 1 and 2 of theDonald C. Cook Nuclear Plant for the operating period from January 1, 2001 through December 31, 2001.

A.

The Donald C. Cook Nuclear Plant of Indiana Michigan Power Company is located on the southeastern shore of Lake Michigan approximately one mile northwest of Bridgman, Michigan. The plant consists of two pressurized water reactors, Unit 1, 1030 MWE and Unit 2, 1100 MWE. Unit 1 achieved initial criticality on January 18, 1975 and Unit 2 achieved initial criticality on March 10, 1978.

B.

Objectives The objectives of the operational radiological environmental monitoring program are:

1.

Identify and measure radiation and radioactivity in the plant environs for the calculation of potential dose to the population.

2.

Verify the effectiveness of in-plant measures used for controlling the release of radioactive materials.

3.

Provide reasonable assurance that the predicted doses, based on effluent data, have not been substantially underestimated and are consistent with applicable standards.

4.

Comply with regulatory requirements and Station Technical Specifications and provide records to document compliance.

9

II. CHANGES 10

II.

CHANGES REMP, PCP. and ODCM Procedure Changes for the AREOR Administrative corrections were performed on the below listed procedures for the following reasons: corrected procedure number format, added various words or phrases of clarification to steps with no change of method or intent to the step, corrected typos or information incorrectly referenced but referenced correctly elsewhere, placed statements in the form of IF/THEN statements, utilized standard notation, removing redundant information, and other minor editorial corrections.

REMP 12-THP-60 10-RPP-63 Rev 4a, "Collection of REMP Groundwater Samples" Administrative corrections only (as stated above).

12-THP-601 O-RPP-633 Rev 5, "Collection on Environmental Radiation Dosimeters" Removed instructions for the Member of Public (MOP) TLDs from this procedure, there is a separate procedure covering MOP TLDs.

Added a new step informing the user of where the TLDs may be obtained (storage location).

Added an equipment list, which indicates the materials needed for successful TLD deployment/retrieval.

Added the shipment of samples as a final condition.

Corrected a utility pole number on which a TLD is located.

Revised the map legend.

Updated map for clarity and to add consistency.

PCP PMP-6010-PCP-900 Rev 4a, "Radioactive Waste Process Control Program" Added statements that allow radwaste to be packaged and shipped to a processor for further processing.

Added clarification as to where filters may be shipped.

Added clarification for free standing water requirements for filters.

Added a reference to NRC commitment #1357.

ODCM PMP-6010-OSD-001 Rev 16, "Off-site Dose Calculation Manual" Added "and projected" to several steps to ensure the requirement for a 31 day projected dose is clear.

Changed wording from cow-milk-infant to child via the inhalation pathway to align with Tech Specs, GL 89-01 and NuReg 0472 (note: issue captured, no impact on dose to public).

Added "or used in the ESW system (Eberline)" to describe that the new monitors monitor the whole ESW system not just the portion associated with the CTS heat exchanger.

Added evaluation to step 3.10.5 in response to C/R 00-6882 to ensure the latest data is acceptable.

Added generator blowdown, blowdown treatment, and the ESW Eberline monitors since they are attendant monitors. Also modified action 3 for ESW for proper compensating actions.

Added the routing of attachment 3.17 to NS&A for impact evaluation.reference in Attachments 3.2 and 3.3 to the sample flow switches of the steam Changed a utility pole number from 152 to 99 onwhich a TLD is located. Changed the distance and direction of REMP wells W-8 and W-2 due to drilling new wells to upgrade well type and construction.

11

Also reformatted ONS-1 (T-1) for consistency and added location description information to SWL-2 and SWL-3 sample collection locations.

Deleted attachment 3.25 due to the low level contaminated blocks being shipped for permanent disposal.

PMP-6010-OSD-001 Rev 16, Cs-1, "Off-site Dose Calculation Manual" An action was divided by the monitor manufacturer and broken into two steps using the IF/THEN format.

Teledyne Brown Engineering Changes During the year 2001, Teledyne Brown Engineering updated their technical procedures to the EPA standardized format. These formatting changes were done without impact to the procedures.

12

III.

SAMPLING AND ANALYSIS PROGRAM 13

III.

SAMPLING AND ANALYSIS PROGRAM Table 1 summarizes the sampling and analysis program for the Donald C. Cook Nuclear Plant for 2001. For each sample medium, the table lists the sample locations, including distance and direction from the center of the two units, and the station identification. The station identifications for the sampling locations are shown on Figures 1 and 2. Also for each sample medium the sample collection frequency, type of analysis, and frequency of analysis are listed.

14

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TABLE I DONALD C. COOK NUCLEAR PLANT - 2001 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS COLLECTION LOCATION STATION DISTANCE DIRECTION DEGREES FREQUENCY ANALYSIS/FREQUENCY Environmental (TLDs)

ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 Rosemary Beach Radioactive Material Bldg.

Sewage Settling Pond 2nd U/2 transmission tower to the 765 yard Well W-01 SWell W -02 Ln New Buffalo South Bend Dowagiac Coloma Intersection of Red Arrow Hwy & Marquette Woods Rd., Pole

B294-44 Stevensville Substation Pole #B296-13 Pole #B350-72 Intersection of Shawnee & Cleveland, Pole #6387-32 Snow Rd., west of Landon Rd., Pole #B426-1 Bridgman Substation California Rd., Pole #B424-20 Ruggles Rd., Pole #B369-214 Intersection of Red Arrow Hwy. & Floral Rd., west of Red Arrow Hwy Pole #B422-99 Intersection of Snow Rd & Baldwin Rd., Pole #B423-12 (T-01)

(T-02)

(T-03)

(T-04)

(T-05)

(T-06)

(T-07)

(T-08)

(T-09)

(T-10)

(T-11)

(T-12)

(NBF)

(SBN)

(DOW)

(COL)

(OFT-l)

(OFT-2)

(OFT-3)

(OFT-4)

(OFT-5)

(OFT-6)

(OFT-7)

(OFT-8)

(OFT-9)

(OFT-10) 1945 ft.

2338 ft.

2407 ft.

1852 ft.

1895 ft.

1917 ft.

2103 ft.

2208 ft.

1368 ft.

1390 ft.

1969 ft.

2292 ft.

15.6 mi 26.2 mi 24.3 ml 18.9 ml 4.5 mi 3.6 mi 5.1 mi 4.1 mi 4.2 mi 4.9 mi 2.5 mi 4.0 mi 4.4 mi 3.8 mi 180 480 900 118&

189° 2100 36° 82° 1490 1270 110 630 Quarterly Direct Radiation/Quarterly SSW SE ENE NNE NE NE NE E

ESE SE S

S ESE S

(OFT-11) 3.8 mi S

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TABLE 1(cont)

DONALD C. COOK NUCLEAR PLANT - 2001 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS COLLECTION LOCATION STATION DISTANCE DIRECTION DEGREES FREQUENCY ANALYSIS/FREQUENCY lAir Charcoal Particulates (ONS-1)

(ONS-2)

(ONS-3)

(ONS-4)

(ONS-5)

(ONS-6)

(NBF)

(SBN)

(DOW)

(COL)

(W-1)

(W-2)

(W-3)

(W-4)

(W-5)

(W-6)

(W-7)

(W-8)

(W-9)

(W-10)

(W-11)

(W-12)

(W-13)

(W-14) 1945 ft.

2338 ft.

2407 ft.

1852 ft.

1895 ft.

1917 ft.

15.6 mi 26.2 mi 24.3 mi 18.9 mi 1969 ft.

2302 ft.

3279 ft.

418 ft.

404 ft.

424 ft.

1895 ft.

1274 ft.

1447 ft.

4216 ft.

3206 ft.

2631 ft.

2152 ft.

1780 ft.

180 485 90*

1180 1890 2100 Weekly Gross Beta/Weekly 1-131/Weekly Gamma Isotopic/

Quarterly Composite SSW SE ENE NNE 110 630 107' 3010 2900 2730 1890 540 220 1290 1530 1620 1820 164-Quarterly Gamma Isotopic/Quarterly Tritium/Quarterly ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 New Buffalo South Bend Dowagiac Coloma C)

FGroundwaterI Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite

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DONALD C. COOK NUCLEAR PLANT - 2001 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS COLLECTION LOCATION STATION DISTANCE DIRECTION DEGREES FREQUENCY ANALYSIS/FREQUENCY Steam Generator Groundwater Steam Generator Storage Facility Steam Generator Storage Facility Steam Generator Storage Facility Steam Generator Storage Facility (SG-1)

(SG-2)

(SG-4)

(SG-5) 0.8 mi 0.7 mi 0.7 ml 0.7 mi 9.0 mi 0.6 mi

[Drinking Water St. Joseph Public Intake Lake Township Public Intake Station (STJ)

(LTW) 950 92' 93' 920 NE S

Quarterly Gross Beta/Quarterly Gross Alpha/Quarterly Gamma Isotopic/Quarterly Daily

-L ISurface Water Condenser Circulating Water Intake Lake Michigan Shoreline Lake Michigan Shoreline SWL-1 SWL-2 SWL-3 500 ft.

South of Plant Centerline 500 ft.

North of Plant Centerline Daily Gross Beta/14 Day Composite Gamma Isotopic/14 Day Composite 1-131/14 Day Composite Tritium/Quarterly Composite Gamma Isotopic/Monthly Composite Tritium/Quarterly Composite ISediment Lake Michigan Shoreline Lake Michigan Shoreline SL-2 SL-3 500 ft.

500 ft.

S N

Semi-annually Gamma Isotopic/Semi-anually IMilk-Indicator Monroe Residence Schuler Farm Glen Troy Farm 5.0 mi 4.1 ml 7.0 mi SE SSE SSE Weekly 1-131/14 Day Gamma Isotopic/14 Day Baroda Baroda Buchanan I

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TABLE 1(cont)

DONALD C. COOK NUCLEAR PLANT - 2001 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS COLLECTION LOCATION STATION DISTANCE DIRECTION DEGREES FREQUENCY ANALYSISIFREQUENCY IMilk Background La Porte Dowagiac Livinghouse Wyant Farm IBroadleaf Vegetation Indicator Sample Indicator Sample Control Sample Sector-D ONS-V Sector J 20.0 mi 20.7 mi 8 mi.

8 mi.

15-25 mi.

S E

Highest D/Q Land Sector Highest D/Q Land Sector Weekly Monthly when available 1-131/14 Days Gamma Isotopic/14 Days Gamma IsotopiclMonthly 1-131 Monthly IFish L

Lake Michigan OD0 Lake Michigan Lake Michigan Lake Michigan ONS-N ONS-S OFS-N OFS-S 0:3 mi 0.4 mi 3.5 mi 5.0 mi N

S N

S 2/yr Gamma Isotopic/Twice a Year iGrapes/Broadleaf I

Sector D At time of harvest Gamma Isotopic at time of harvest Nearest Sample to Plant in highest /Q land sector containing media.

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DONALD C. COOK NUCLEAR PLANT - 2001 RADIOLOGICAL SAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS COLLECTION LOCATION STATION DISTANCE DIRECTION DEGREES, FREQUENCY ANALYSISIFREQUENCY lGrapes In a land sector containing grapes Sector J At time of Gamma Isotopic at time approximately 20 miles from the Plant in one of harvest of harvest the less prevelant D/Q land sectors

Composite samples of Drinking and Surface water shall be collected at least daily Particulate sample filters should be analyzed for gross beta activity 24 or more hours following filter removal. This will allow for radon and thoron daughter decay. If gross beta activity in air or water Is greater than 10 times the yearly mean of control samples for any medium, gamma isotopic analysis should be perfromed on the Individual samples.

Please note the following definitions:

Weekly at least once every seven (7) days Monthly Quarterly Semi-annually at least once every thirty-one (31) days at least once every ninety-two (92) days at least once every one hundred eighty-four (184) days

On-site REMP Monitoring Locations SURFACE WATER ISVWL3 SEOIM4ENT ISL WELL.

V, SWACt WATER ISMt-i WILLA. WI, SURIACE WAlER ISV4W; SEDIMENT ISL-21 20 LEGEND ONS ONS-6:

Air Sampling Stations T T-12:

TLD Sampling Stations W W-14:

REMP T/S Groundwater Wells SG-I, SG-2, SG-4, SG-5: REMP Non T/S Groundwater Wells SWL-1, 2, 3: Surface Water Sampling Stations SL-2, SL-3: Sediment Sampling Stations

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IV.

SUMMARY

AND DISCUSSION OF 2001 ANALYTICAL RESULTS 22

IV.

SUMMARY

AND DISCUSSION OF 2001 ANALYTICAL RESULTS A discussion of the data from the radiological analyses of environmental media collected during the report period is provided in this section. Samples for 2001 were analyzed by Teledyne Brown Engineering Environmental Services, Inc. in Knoxville, TN.

The procedures and specifications followed at Teledyne Brown Engineering are in accordance with the Teledyne Brown Engineering Quality Assurance Manual. 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 Brown Engineering, the laboratory also participates in Interlaboratory Comparison Programs. Participation in these programs 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 D.

The transition of the laboratory from Westwood, New Jersey to Knoxville, Tennessee resulted in a longer than anticipated interruption in production. This interruption caused a backlog in the count room, which resulted in a delay of sample counting. As radionuclides with short half-lives decay, we are less able to detect their presence. This is reflected by an abnormally large decay correction factor in the activity calculation and elevated minimum detection levels. Consequently, there were a number of missed LLDs in the first half of 2001.

Routinely, radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. Under normal conditions, Teledyne Brown Engineering analytical methods meet or exceed the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position of Radiological Monitoring, Revision 1, November 1979, and PMP-6010-OSD-001, "Off-Site Dose Calculation Manual".

The following is a discussion and summary of the results of the environmental measurements performed during the reporting period. Comparison is made where possible with radioactivity concentrations measured in the preoperational period of August 1971 to the initial criticality of Unit I on January 18, 1975. A brief summary of the preoperational program is found in Appendix G.

23

A.

Airborne Particulates Airborne particulate samples are collected with an oil-less pump at approximately 56 LPM using a 47 mm particulate filter. Results of gross beta activities are presented in Table B-1.

The measurement of the gross beta activity on the weekly air particulate filters is a good indication of the levels of natural and/or manmade radioactivity in the environment.

The average gross beta concentration of the six indicator locations was 0.020 pCi/m3 with a range of individual values between 0.005 and 0.048 pCi/m 3. The average gross beta concentration of the four control locations was 0.020 pCi/m3 with a range between 0.006 and 0.047 pCi/m3. In Trending Graph 1 the monthly average gross beta concentrations for the indicator locations and for the control locations are plotted. The gross beta concentrations in air particulates filters in 2001 were lower than at the end of the preoperational period when the effects of recent atmospheric nuclear tests were being detected.

Air particulate filters were composited by location on a quarterly basis and were analyzed by gamma ray spectroscopy.

Results are presented in Table B-2.

Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in all forty samples. The average concentration for the control locations was 0.112 pCi/m3 and the values ranged from 0.087 to 0.138 pCi/m3. The average concentration for the indicator locations was 0.110 pCi/m3 with a range of 0.082 to 0.179 pCi/m3.

These values are typical of beryllium-7 measured at various locations throughout the United States. Naturally occurring potassium-40 was not measured in 2001. Thorium 228 was measured in one of the twenty-four indicator quarterly composites with a concentration of 0.0002 pCi/m 3. Thorium-228 was measured in two of the control quarterly composites with an average concentration of 0.0005 pCi/m3 and a range of 0.0004 to 0.0007 pCi/m3. No other gamma emitting radioactivity was detected.

B.

Airborne Iodine Airborne iodine samples are collected with an oil-less pump at approximately 56 LPM using a charcoal filter cartridge. Charcoal cartridges are installed downstream of the particulate filters and are used to collect airborne radioiodine. The results of the weekly analysis of the charcoal cartridges are presented in Table B-3. All results were below the lower level of detection of 0.30 pCi/m3 with no positive activity detected.

C.

Direct Radiation - Thermoluminescent Dosimeters Thermoluminescent dosimeters (TLDs) measure external radiation exposure from several sources including naturally occurring radionuclides in the air and soil, radiation from cosmic origin, fallout from atomic weapons testing, potential radioactive airborne releases from the power station and direct radiation from the power station. The TLDs record exposure from all of these potential sources.

The TLDs are deployed quarterly at 27 locations in the environs surrounding the D. C. Cook Nuclear Plant. The average value of the four areas of each dosimeter (calibrated individually after each field exposure period for response to a known exposure and for transit exposure) are presented in Table B-4.

Those exposure rates are quite typical of observed rates at many other locations in the country. The average annual measurement for the control samples was 3.13 mR/standard month with a range of 1.0 to 5.3 mR/standard month.

The annual accumulation of indicator samples had a measurement of 3.17 mR/standard month with a range of 1.1 to 5.9 mR/standard month. The 2001 annual average in the environs of the Donald C. Cook Nuclear Plant is at the low range of the exposure rates (1.0 to 2.0 mR/week) measured during the preoperational period. The results of the indicator and control TLDs are in good agreement and are plotted in Trending Graph 2.

24

D.

Surface Water Two 125 milliliter surface water samples were collected from the intake forebay and from two shoreline locations, all within 0.3 miles of the two reactors and were composited daily over a monthly period. The gamma isotopic sample is preserved with nitric acid. The thirty-six samples were analyzed for iodine-131 by gamma ray spectroscopy. All results were less than or equal to the lower limit of detection. The quarterly composite was analyzed for tritium by liquid scintillation method described on page 73. Results are presented in Table B-5. Tritium was detected in one of the four indicator samples with a concentration of 160 pCi/liter. Tritium was detected in three of the eight control samples with an average concentration of 207 pCi/liter and a range of 120 to 350 pCi/liter. During the preoperational period tritium was measured in surface water samples at concentrations of approximately 400 pCi/liter.

Naturally occurring potassium-40 was measured in one of the twenty-four control samples with a concentration of 476 pCi/liter. Potassium-40 was not detected in any of the indicator samples. Cesium 137 was not measured in any of the samples during 2001.

E.

Groundwater Water samples are collected quarterly from fourteen wells, all within 4300 feet of the reactors.

First, a static water elevation is determined and three well bore volumes are purged from the well using a groundwater pump, or equivalent Two 1-liter and one 125 mL samples are then obtained and the gamma isotopic samples are preserved with nitric acid. The samples are analyzed for gamma emitters and tritium. The results are presented in Table B-6. Naturally occurring potassium-40 was measured in six samples with an average concentration of 188 pCi/liter and a range of 77.2 to 369 pCi/liter. Thorium 228 was measured in seven samples with an average concentration of 13.3 pCi/liter and a range of 3.91 to 29.1 pCi/liter. There were no other gamma emitting isotopes measured. The groundwater wells W4, W 5, W-6, and W-14 had measurable tritium activity throughout 2001. Tritium was measured in 16 of the 56 samples at the locations with an average concentration of 548 pCi/liter and a range of 180 to 1700 pCi/liter. The annual concentrations of tritium in wells W-1 through W-7 are plotted in Trending Graph

3. Tritium concentration in groundwater wells during the preoperational period typically averaged 400 pCi/liter. Groundwater does not provide a dose pathway for the Cook plant environs.

F.

Drinking Water Daily samples are collected at the intake of the water purification plants for St. Joseph and Lake Township. The 1000 ml daily samples at each location are composited and analyzed for gross beta, iodine-131, and gamma emitters. These samples were composited and the gamma isotopic sample was preserved with nitric acid.

On a quarterly basis the daily samples are composited and analyzed for tritium. The results of analyses of drinking water samples are shown in Table B-7.

Gross beta activity was measured in nineteen of the twenty-six samples from the Lake Township intake with an average concentration of 2.59 pCi/liter and a range of 1.7 to 4.5 pCi/liter. Gross beta activity was measured in twenty-four of the twenty-six samples from the St. Joseph intake with an average concentration of 2.83 pCi/liter and a range of 2.1 to 4.0 pCi/liter. Naturally occurring potassium 40 was measured in one of the twenty-six samples from the Lake Township intake with a concentration of 192 pCi/liter. Naturally occurring potassium-40 was measured in one of the twenty-six samples from the St. Joseph intake with a concentration of 375 pCi/liter. Iodine-131 was measured in one of twenty-six samples from the Lake Township intake with a concentration of 0.93 pCi/liter. Iodine-13 1 activity was measured in one of the twenty-six samples from the St. Joseph intake with a concentration of 0.96 pCi/liter. No other gamma emitting isotopes were detected. Tritium was 25

measured in all four of the Lake Township intake sample with an average concentration of 153 pCi/liter and a range of 92.0 to 190 pCi/liter. Tritium was measured in all four of the St. Joseph intake samples with an average concentration of 138 pCi/liter and a range of 93.0 to 180 pCi/liter. Tritium (or LLD values) in drinking water are plotted in Trending Graph 4.

There were no drinking water analyses performed in the preoperational program.

G.

Sediment Sediment samples are collected semiannually along the shoreline of Lake Michigan at the same two locations as the surface water samples. Two liters of lake sediment are collected using a small dredge in an area covered part time by wave action. The sediment samples are analyzed by gamma ray spectroscopy, the results of which are shown in Table B-8. In March and October one sample was collected from location SL-2 and SL-3. Gamma ray spectroscopy detected naturally occurring potassium-40 in all four samples.

The average potassium-40 concentration was 7515 pCi/kg (dry weight) with a range of 7190 to 7960 pCi/kg (dry weight). Thorium-228, also naturally occurring, was measured in all four samples with-an average concentration of 89.8 pCi/kg (dry weight) and a range of 82.7 to 94.5 pCi/kg (dry weight). All other gamma emitters were below the lower limits of detection.

H.

Milk Milk samples of one gallon are collected from a 500 gallon bulk tank every fourteen days from four farms located between 4.1 miles and 20.7 miles from the site. The fifth farm is a goat farm located 5.0 miles from the plant site, where no bulk tank is used. Milk samples are preserved by adding 40 grams per gallon of sodium bisulfite when the samples are collected. The samples are analyzed for iodine-131 and other gamma emitters.

The results are shown in Table B-9.

Naturally occurring potassium-40 was measured in all of the fifty-two control samples with an average concentration of 1309 pCi/liter and a range of 1190 to 1470 pCi/liter. Potassium-40 was measured in all of the seventy eight indicator samples with an average concentration of 1414 pCi/liter and a range of 922 to 2000 pCi/liter. 1-131 was not measured in any of the 130 samples analyzed in 2001.

I.

Broadleaf Vegetation Broadleaf in lieu of milk collection was discontinued due to reimplementation of the milk sampling program in 2000.

J.

Fish Using gill nets in approximately twenty feet of water in Lake Michigan, 4.5 pounds of fish are collected 2 times per year from each of four locations. The samples were then analyzed by gamma ray spectroscopy. Results are presented in Table B-1l. Naturally occurring potassium-40 was measured in the four control samples with an average concentration of 3145 pCi/kg (wet weight) and a range of 2390 to 3920 pCi/kg (wet weight). Potassium-40 was measured in all four indicator samples with an average concentration of 2893 pCi/kg (wet weight) and a range of 2680 to 3130 pCi/kg (wet weight). Cesium 137 was measured in two control samples with an average concentration of 43.7 pCi/kg (wet weight) and a range of 32.3 to 55.0 pCi/kg (wet weight). Cesium-137 was measured in three of the four indicator samples with an average concentration of 20.9 pCi/kg (wet weight) and a range of 11.7 to 37.6 pCi/kg (wet weight). The level of cesium-137 found in these samples during 2001 are equivalent to the cesium-137 detected during the preoperational period.

26

K.

Food Products Food samples are collected annually at harvest, at three locations, as near the site boundary as possible, and approximately twenty miles from the plant. Each sample consists of greater than 300 grams of grapes and/or a large (12" x 15") zip lock bag moderately stuffed with broadleaves. Three vegetation samples and two grape samples were collected in 2001. The samples were analyzed by gamma ray spectroscopy. Results are presented in Table B-10. Cosmogenically produced beryllium-7 was measured in the control sample with a concentration of 1040 pCi/kg (wet weight). Beryllium-7 was measured in both indicator samples with an average concentration of 5020 pCi/kg (wet weight) and a range of 2800 to 7240 pCi/kg (wet weight). Naturally occurring potassium-40 was measured in the control sample with a concentration of 4000 pCi/kg (wet weight). Potassium-40 was measured in both indicator samples with an average concentration of 4865 pCi/kg (wet weight) and a range of 4490 to 5240 pCi/kg (wet weight). Cesium-137 was not measured during 2001. Two grape samples were collected in 2001. Beryllium-7 was measured in the control sample with a concentration of 115 pCi/kg (wet weight). Beryllium-7 was measured in the indicator sample with a concentration of 109 pCi/kg (wet weight). Naturally occurring potassium-40 was measured in the control sample with a concentration of 5300 pCi/kg (wet weight). Potassium-40 was measured in the indicator sample with a concentration of 2290 pCi/kg (wet weight). Cesium-137 was not measured during 2001.

27

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V. CONCLUSIONS 34
V.
CONCLUSIONS The results of the 2001 Radiological Environmental Monitoring Program for the Donald C.
Cook Nuclear Plant have been presented. The results were as expected for normal environmental samples. 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. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence. Specific examples of sample media with positive analysis results are discussed below.
Air particulate gross beta concentrations of all the indicator locations for 2001 appear to follow the gross beta concentrations at the control locations. The concentration levels are actually lower than during the preoperational period. Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). No man-made activity was found in the particulate media during 2001. No iodine-131 was detected in charcoal filters in 2001.
Thermoluminescent dosimeters (TLDs) measure external gamma radiation from naturally occurring radionuclides in the air and soil, radiation from cosmic origin and fallout from atmospheric nuclear weapons testing, and radioactive airborne releases and direct radiation from the power plant.
The average annual TLD results were at normal background exposure levels.
Surface water samples are collected daily from the intake forebay and two locations in Lake Michigan. The samples are analyzed quarterly for tritium, and monthly for gamma emitting isotopes.
Naturally occurring potassium-40 was the only gamma emitter detected during 2001.
Tritium was measured in three control samples and one indicator sample.
Groundwater samples were collected quarterly at fourteen wells, all within 4300 feet of the reactors. The three wells within 500 feet had measurable tritium, which is attributed to the operation of the plant. The highest concentration measured in 2001 was 1700 pCi/liter which compares closely with the lowest concentration measured during 2000 of 1700 pCi/liter. Potassium-40, a naturally occurring nuclide was detected in six of the fifty-six samples with an average concentration of 188 pCi/liter. No other gamma emitting isotopes were detected.
Samples are collected daily at the intakes of the drinking water purification plants for St. Joseph and Lake Township. Samples composited daily over a two week period are analyzed for iodine-131, gross beta, and measured for gamma emitting isotopes. Samples are also analyzed quarterly for tritium.
Naturally occurring potassium-40 was detected in two of the fifty-two samples with an average concentration of 284 pCi/liter. No other gamma emitting isotopes were detected. Iodine-131 was detected in two of the fifty-two samples with an average concentration of 0.95 pCi/liter, which is below the required LLD of 1.0 pCi/liter.
Gross beta was measured in all fifty-two samples at normal background concentrations. Tritium was measured in 2001 in the eight quarterly composite samples with an average concentration of 146 pCi/liter.
Sediment samples can be a sensitive indicator of discharges from nuclear power stations.
Sediment samples are collected semiannually along the shoreline of Lake Michigan at two locations in close proximity of the reactors. The samples were analyzed by gamma ray spectroscopy and only naturally occurring gamma emitters were detected. There is no evidence of station discharges affecting Lake Michigan, either in the sediments or in the water, as previously discussed.
35
The milk sampling program was reinstated in March of 2000. Milk samples are collected biweekly from five farms within the vicinity of the nuclear plant. Naturally occurring potassium-40 was detected in all of the one-hundred and thirty samples with an average concentration of 1372 pCi/liter.
No other gamma emitters were detected.
Broadleaf sampling in lieu of milk was discontinued due to the reimplementation of the milk collection program in 2000.
Fish samples collected in Lake Michigan in the vicinity of the nuclear plant were analyzed by gamma ray spectroscopy. Naturally occurring potassium-40 was detected in all eight samples. Cesium 137 was found in three of the four indicator samples with an average concentration of 20.9 pCi/kg (wet weight) and in two of the four control samples with an average concentration of 43.7 pCi/kg (wet weight). The level of cesium-137 found in these samples during 2001 are equivalent to the cesium-137 detected during the preoperational period.
Food products, consisting of grapes and broadleaf vegetation were collected and analyzed by gamma ray spectroscopy. Vegetation samples are collected annually from three locations and grapes are collected annually from two locations within the vicinity of the nuclear plant.
The samples were analyzed by gamma ray spectroscopy. Cosmogenically produced beryllium-7 was detected in all three vegetation samples with an average concentration of 3693 pC/kg (wet weight). Naturally occurring potassium-40 was detected in all three samples with an average concentration of 4577 pCi/kg (wet weight). Cosmogenically produced beryllium-7 was detected in both grape samples with an average concentration of 112 pC/kg (wet weight). Naturally occurring potassium-40 was detected in both grape samples with an average concentration of 3795 pCi/kg (wet weight).
The only gamma emitting isotopes measured during 2001 were beryllium-7 and potassiunm-40.
The results of the analyses have been presented. Based on the evidence of the Radiological Environmental Monitoring Program the Donald C. Cook Nuclear Plant is operating within regulatory limits. Tritium in four on-site wells appears to be the only radionuclide which can be directly correlated with the plant. However the associated groundwater does not provide a direct dose pathway to humans because these wells do not supply water to the local population.
36
VI. REFERENCES 37
VI.
REFERENCES
1.
Data Tables from 1985-1988 CEP-AEPSC Annual Radiological Environmental Monitoring Program Reports.
2.
Eberline Instrument Company. Indiana Michigan Power Company, "D. C. Cook Nuclear Plant Radiological Environmental Monitoring Program - 1974 Annual Report", May 1975.
3.
Donald C. Cook Nuclear Plant, PMP-601 O-OSD-001, "Offsite Dose Calculation Manual".
4.
United States Nuclear Regulatory Commission, Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", December 1975.
5.
United States Nuclear Regulatory Commission, Regulatory Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, June 1974.
6.
United States Nuclear Regulatory Commission, Regulatory Guide 4.1 "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants", April 1975.
7.
USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.
38
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
39
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLER PLANT DOCKET NO. 50-315/50-316 BERRIEN COUNTY JANUARY 1 TO DECEMBER 31, 2001 ANALYSIS AND NUMBER OF MEDIUM OR PATHYWAY TOTAL NUMBER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSIS MEAN (a/b)
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Air Iodine (pCi/m 3)
Airborne Particulates (pCi/m3) 1-131 Gross Beta Gamma Be-7 0P.
CD Direct Radiation (mR/Standard Dose Month)
K-40 Th-228 Gamma 529 529 40 40 40 40
-(0/317) 19.6(317/317)
(5.4-48) 110(24/24)
(82.4-179)
-(0/24) 0.22(1/24)
NA ONS-2 2338 ft.
48° 20.5(53/53) 19.6(212/212)
(6.7-47)
(5.7-47)
ONS-2 2338 ft.
480 123(4/4)
(87.7-179)
NA NBF 15.6 mi.
SSW 0.67(1/4) 107 Quarterly 107 3.17(91/91)
(1.1-5.9)
OFT-9 4.4 mi.
ESE 4.3(4/4)
(3.8-4.9)
(a/b) Ratio of samples with detectable activity to total number of samples analyzed.
-(0/212) 0 0
0 0
0 112(16/16)
(87.3-138)
-(0/16) 0.54(2/16)
(0.4-0.67) 3.13(16/16)
(1.0-5.3) 0 I
I I
I I
I I
[
I I
I I.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLER PLANT DOCKET NO. 50-315150-316 BERRIEN COUNTY JANUARY 1 TO DECEMBER 31, 2001 ANALYSIS AND NUMBER OF MEDIUM OR PATHYWAY TOTAL NUMBER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSIS MEAN (a/b)
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Surface Water (pCi/liter)
Gamma K-40 H-3 Groundwater (pCi/liter)
Drinking Water (pCi/liter)
Gamma K-40 Th-228 H-3 36 36 12 56 56 56 56
-(0/12) 160(1/12) 188(6/56)
(77.2-369) 13.3(7/56)
(3.91-29.1) 548(16/56)
(180-1700)
Gross Beta 52 2.73(43/52)
(1.7-4.5) 1-131 52 0.95(2/52)
(0.93-0.96)
SWL-3 North Comp SLW-2 South Comp 476(1/24) 250(2/4)
(150-350)
Well 7 1895 ft.
1890 274(1/4)
Well 11 3206 ft.
1530 29.1(1/4)
Well 6 424 ft.
273° 1180(4/4)
(420-1700)
St. Joseph 9.0 mi.
St. Joseph 9.0 mi.
NE NE 2.83(24/26)
(2.1-4.0) 0.96(1/26)
(a/b) Ratio of samples with detectable activity to total number of samples analyzed.
476(1/24) 207(3/8)
(120-350)
-(0/0)
-(0/0)
-(0/0)
-(0/0)
-(0/0) 0 0
0 0
0 0
.0
I.
[.
+
f
,.[
I I
f
-(
I.
I
[
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLER PLANT DOCKET NO. 50-315150-316 BERRIEN COUNTY JANUARY 1 TO DECEMBER 31, 2001 ANALYSIS AND NUMBER OF MEDIUM OR PATHYWAY TOTAL NUMBER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSIS MEAN (a/b)
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Drinking Water (pCi/liter)
Gamma K-40 H-3 Fish (pCi/kg wet)
I\\)
FoodNegetation Broadleaf (pCi/kg wet)
Gamma K-40 Cs-137 Gamma Be-7 K-40 Cs-1 37 52 52 8
8 8
8 3
3 3
3 284(2/52)
(192-375) 146(8/8)
(92-190) 2893(4/4)
(2680-3130) 20.9(3/4)
(11.7-37.6) 5020(2/2)
(2800-7240) 4865(2/2)
(4490-5240)
-(0/2)
St. Joseph 9.0 mi.
NE 375(1/26)
LTW 0.6 mi.
S 153(4/4)
(92-190)
-(0/0)
-(0/0)
OFS-N 3.5 mi.
N 3410(2/2) 3145(4/4)
(2900-3920)
(2390-3920)
OFS-N 3.5 mi.
N 32.3(1/2)
Sector D Sector D 7240(1/1) 5240(1/1)
NA NA 43.7(2/4)
(32.3-55.0) 1040(1/1) 4000(1/1)
-(0/1)
(a/b) Ratio of samples with detectable activity to total number of samples analyzed; 0
0 0
0 0
0 0
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLER PLANT DOCKET NO. 50-315150-316 BERRIEN COUNTY JANUARY 1 TO DECEMBER 31, 2001 ANALYSIS AND NUMBER OF MEDIUM OR PATHYWAY TOTAL NUMBER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSIS MEAN (a/b)
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS FoodNegetation Grapes (pCi/kg wet)
Sediment pCi/kg dry)
Gamma 2
Be-7 K-40 Cs-1 37 Gamma K-40 Cs-137 Ra-226 Th-228 2
2 2
4 4
4 4
4 109(1/1) 2290(1/1)
-(0/I) 7515(4/4)
(7190-7960)
-(0/4)
-(0/4) 89.8(4/4)
(82.7-94.5)
Sector J Sector J NA SL-2 NA NA SL-3 115(1/1) 5300(1/1 )
NA 500 ft.
S 7610(2/2)
(7260-7960)
NA NA 500 ft.
N 91.3(2/2)
(88.1-94.5)
(a/b) Ratio of samples with detectable activity to total number of samples analyzed.
115(1/1) 5300(1/1)
-(0/1) 0 0
0
-(0/0)
-(0/0)
-(0/0)
-(0/0) 0 0
0 0
f I
I I
I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLER PLANT DOCKET NO. 50-315/50-316 BERRIEN COUNTY JANUARY 1 TO DECEMBER 31, 2001 ANALYSIS AND NUMBER OF MEDIUM OR PATHYWAY TOTAL NUMBER ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSIS MEAN (a/b)
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Gamma Be-7 K-40 1-131 Cs-137 130 130
-(0/78) 130 1414(78/78)
(922-2000) 130 130
-(0/78)
-(0/78)
NA NA
-(0/52)
Monroe 5.0 mi.
SE 1604(26/26) 1309(52/52)
. (922-2000)
(1190-1470)
NA NA NA NA
-(0/52)
-(0/52)
(a/b) Ratio of samples with detectable activity to total number of samples analyzed.
Milk (pCi/L) 0 0
0 0
{ 2(
.1 I.
rT<{.
>

(
APPENDIX B DATA TABLES 45
I I
I 4
[
I I
I TABLE B-1 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10-3 pCi/m 3 +/- 2 sigma COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW COL Average DATES
+/-+ 2s.d.
JANUARY 2001 17 2
19 2
21 +2 30 +3 16 2
20 +/-2 22 +2 31 +2 26 +2 18 +/- 2 15 +/- 2 16+/- 2 14+/- 2 17+/-2 17+/-2 16+/-2 17+/-2 15+/-2 15+/-2 15+/-2 16+/-2 15+/-2 22 +/- 2 24 +/- 2 22 +/- 2 20 +/- 2 19 +/- 2 22 +/- 2 24 +/- 2 28 +/- 2 22 +/- 2 22+/-2 23+/-2 21 +/-2 19+/-2 19+/-2' 21 +/-2 21 +/-2 23+/-2 21 +/-2 30+/-3 31 +/-3 33-+/-3 30+/-2 28+/-2 27_+/-3 27_+/-2 31 +/-2 30+/-3 18+/-2 19+/-2 16+/-2 17+/-2 15+/-2 17+/-2 18+/-2 19+/-2 14_+/-2 25_+/-2 24_+/-2 25+/-2 21 +/-_2 23+/-2 21 +/-_2 21 +/-_2 23+/-2 23_+/-2 18+/-2 18_+/-2 22_+/-2 23_+/-2 19+/-2 21 +/-_2 21 +/-2 22_+/-2 21 +/-_2 31 +/-2 33_+/-3 31 +/-_2 29_+/-2 30_+/-2 30_+/-2 31 +/-_3 30+/-2 33+/-3 18 +/- 2 24 +/- 2 23 +/- 2 24 +/- 2 23 +/- 2 22 +/- 2 24 +/- 2 26 +/- 2 22 +/- 2 19-+/-2 18-+/-2 18_+/-2 18+/-2 15_+/-2 17_+/-2 19+/-2 20+/-2 19-+/-2 14+/-2 14+/-2 13+/-2 12+/-2 13+/-2 11 +/-_2 12+/-2 15_+/-2 14_+/-2 17+/-2 15_+/-2 17+/-2 17_+/-2 15+/-2 17_+/-2 18+/-2 17_+/-2 18+/-2 17+/-2 12+/-2 17_+/-2 15+/-2 16+/-2 15+/-2 17+/-+2 15+/-2 16+/-2 Quarter Avg.
20 +/- 11 21 +/- 10 21 +/- 13 21 +/- 12 20 +/- 10 19 +/- 11 20 +/- 10 21 +/- 10 22 +/- 11 21 +/- 12 16+/- 2 22 +5 21 +/-+3 30 +/-4 17-3 23 +/-+4 21 +/-4 31 +/-3 23 -+5 18+/- 3 13+/- 3 17 2
15+/- 3 21 --11 (a)
Sample not received.
01/03/01 01/10/01 01/17/01 01/24/01 01/31/01 FEBRUARY 02/07/01 02/14/01 02/21/01 02/28/01 MARCH 03/07/01 03/14/01 03/21/01 03/28/01
TABLE B-1 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW COL Average DATES
+ 2s.d.
APRIL 04/04/01 04/11/01 04/18/01 04/25/01 17 2
12 2
15 2
19 2
MAY 05/02/01 05/09/01 05/16/01 05/23/01 05/30/01 18 2
18 2
17 2
12 2
7.5 +/- 1.6 16+/-2 16_+/-2 16+/-2 16+/-2 15+/-2 18+/-2 17+/-2 17+/-2 11 +/-2 15+/-2 13+/-2 13+/-2 13+/-2 14+/-2 15+/-2 13+/-2 13+/-2 13+/-2 12+/-2 12+/-2 13+/-2 21 +/-2 18+/-2 16++/-2 19+/-2 17+/-2 17+/-2 17+/-2 20+/-2 19+/-2 22+/-2 22+/-2 20+/-2 21 +/-2 20+/-2 18+/-2 16+/-2 15+/-2 20+/-2 18 +/-12 17+/-2 21 2
17+/-2 14_+/-2 18+/-2 18+/-2 15+/-+2 19+/-2 17+/-2 12+/-2 10+/-2 11 +/-2 12++/-2 11 +/-2 13+/-2 11 2
11+/-2 8.0+/-1.7 8.2+/-1.6 9.3+/-1.5 8.3 +/-1.6 11 +/-2 10+/-+2 17+/-2 20+/-2 14+/-2 14+/-2 13+/-2 14+/-2 18+/-2 19+/-2 21 +/-2 20+/-2 17+/-2 19+/-+2 17_+/-2 18+/-2 13+/-2 13+/-2 9.4+/-1.6 9.9+/-1.8 JUNE 06/06/01 06/13/01 06/20/01 06/27/01 Quarter Avg.
6.8 +/- 1.6 6.7 +/- 1.6 6.7 +/- 1.7 7.1 +/- 1.5 7.3 +/- 1.5 5.4 +/- 1.4 5.7 +/- 1.6 7.4 +/- 1.7 6.1 +/- 1.5 6.7 +/- 1.7 18+/-2 16+/-2 15+/-2 16+/-2 12+/-2 13+/-3 15+/-2 15+/-2 13+/-2 15+/-2 19+/-2 22+/-2 18:+/-!2 19+/-+2 16+/-2 15+/-2 20+/-2 22_+/-2 20+/-+2 19+/-2 15 +/- 2 16 +/- 2 14 +/- 2 13 +/- 2 15 +/- 2 12 +/-+2 15 +/- 2 15 +/- 2 13 +/- 2 14 +/- 2 15 +/- 8.3 16 +/- 8.4 14 +/- 7.8 15 +/- 8.3 15 +/- 8.5 13 +/- 7.9 15 +/- 8.4 15 +/- 8.6 15 +/- 8.3 16 +/- 8.3 (a)
Sample not received.
17 3
14 3
13 2
18 3
20 +/-3 18 4
17 3
12 2
9-2 7+1 15 4
19 5
14 2
15 -+8.3 I
I I
I I
4 1
1 1
[
[
TABLE B-I (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10-3 pCi/M3+/- 2 sigma COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW COL Average DATES
+/- 2 s.d.
JULY 17 +/- 2 18 +/- 2 (a) 24 +/- 2 21 +2 23 +/-2 17+/- 2 18 2
23 +/-+2 SEPTEMBER 17+/- 2 15 2
20 +/-+2 17+/- 2 18+/-2 17+/-2 16+/-2 19+/-2 16+/-2 17+/-2 18+/-2 17+/-2 19_+/-2 17 +/-2 17+/-2 20+/-2 19+/-2 18+/-2 20+/-2 18+/-2 16_+/-2 17-+/-2 16-+/-2 17-+/-2 16 +/-2 14 +/-2 13+/-2 14+/-2 26 +/- 2 27 +/- 2 25 +/- 2 23 +/- 2 24 +/- 2 25 +/- 2 26 +/- 2 23 2
21 +/-_2 24_+/-2 19 +/-2 22_+/-2 20+/-2 20_+/-2 24+/-2 22+/-2 24 +/- 2 22 +/- 2 23 +/- 2 25 +/- 2 23 +/- 2 22 +/- 2 24 +/- 2 25+/- 2 17_+/-2 15+/-2 15_+/-2 16+/-2 15 +/-2 16+/-2 16+/-2 17+/-2 17 +/-2 16_+/-2 15_+/-2 16+/-2 17+/-2 16-+/-2 17+/-2 17-+/-2 19-+/-2 19_+/-2 19 +/-2 19+/-2 20 +/-2 21 +/-2 20_+/-2 17+/-2 19_+/-2 16_+/-2 16_+/-2 17+/-2 16_+/-2 18_+/-2 17+/-2 18 +/-2 17_+/-2 15+/-2 13 +/-2 16 +/-2 14_+/-2 14_+/-2 15+/-2 14_+/-2 21 +/-2 16 +/-2 17+/-2 19_+/-2 18 +/-2 18_+/-2 18 +/-2 19+/-2 20_+/-2 18+/-2 18+/-2 24+/-5 23+/-6 19 +/-2 20 +/-2 16 +/-2 19 +/- 2 19 +/- 2 16 +/- 2 25 +/- 2 21 +/-2 22 +/- 2 18 +/- 2 17 +/- 2 18 +/- 2 16 +/- 2 14 +/- 2 19 +/- 2 17 +/- 2 17 +/- 2 19 +/- 2 15 +/- 3 25 +/- 3 21 +/- 3 23 +/- 2 16+/- 2 17+/- 2 20 +/-+3 17+/- 2 15+/- 2 19+/- 3 19 5
Quarter Avg.
19 +/- 5.9 20 +/- 5.8 18 +/- 7.4 18 +/- 6.6 19 +/- 6.3 19 +/- 6.6 18 +/- 6.3 19 +/- 7.6 18 +/- 6.6 19 +/- 5.8 19 +/- 6.3 (a) Sample not received.
07/04/01 07/11/01 07/18/01 07/25/01 AUGUST 08/01/01 08/08/01
ý-*
08/15/01 08/22/01 08/29/01 09/05/01 09/12/01 09/19/01 09/26/01
I f F" 1
-4
I
.1
'if I
I t
TABLE B-1 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results In Units of 10-3 pCi/m3 +/- 2 sigma COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW COL Average DATES
+/- 2 s.d.
OCTOBER 10/03/01 10/10/01 10/17/01 10/24/01 10/31/01 22 +/- 2 20 +/- 2 13_+/-2 23 +/-+2 14 +/-+2 22 +/- 2 24 +/- 2 12 +/- 2 24 +/- 2 13 +/- 2 NOVEMBER 11/07/01 11/14/01 11/21/01 11/28/01 18 +/- 2 23 +/- 2
,43 +/- 3 25 +/- 2 20 +/-+2 27 +2 47 +/-+3 28 +/-+2 20 +/-+2 17 +/-_2 22 +/-_2 21 +/-_2 12 +/-2 12 2
21 +/-+2 24+/-2 13 +/-+2 12 2
17 +/-2 17 2
22 +/-2 25 2
43 +/-+3 44 3
25 +/--2 26 2
21 +/-2 21 +/--2 20+/-+2 21 +/-2 23+/-2 23+/-2 13 +/-2 11 +/-2 12 +/-2 21 +/--2 24-+/-2 24+/-2 14 +/-+2 14 +/-_2 14 +/-2 18 +/--2 17 +/-2 18 2
26 +/-+2 24 +/- 2 23 2
47 +/- 3 48 +/- 3 47 3
24 +/-2 26 +/--2 29 2
22+/-2 202 27+/-2 23+/-2 9.5 +/- 1.6 13 2
24 +/- 2 22 2
13 +/-2 11 2
17+/-+2 18_+/-2 24+/-+2 23_+/-2 40 +/- 3 45 +/- 3 23+/-2 26-+/-2 18_+/-2 20_+/-3 19_+/-2 22+/-+5 12_+/-2 12+/-+2 21 +/-+2 23 +/-3 12+/-+2 13_+/-2 18+/-+2 18+/-+2 23 +/- 2 24 +/- 3 40 +/- 3 44 +/- 6 24_+/-2 26+/-+4 DECEMBER 12/05/01 12/12/01 12/19/01 12/26/01 01/02/02 Quarter Avg.
25 +/- 2 30 +/- 2 28 +/-2 24 +/-+2 18+2 30 +/- 2 33 +/- 3 30 +/- 2 27 +/- 2 19 +/- 2 28 +/-+2 27 +/-+2 28 +/-_2 31 +/-+2 30 +/-+2 28 +/-2 23 +/-2 24 +/-2 18 +/--2 21 +/-2 23 +/- 15 25 +/- 18 23 +/- 16 24 +/- 16 AnnualAvg.
20 +/- 12 21 +/- 13 19 +/- 13 19 +/- 13 30-+/-2 31 +/-2 25+/-2 36+/-3 33-+/-3 32_+/-2 33_+/-3 29+/-+2 27+/-2 29 +/-_2 23 +/-+2 28 2
22 +/-+2 21 +/-_2 22 2
25 +/- 18 25 +/- 18 25 17 20 +/- 14 19 +/- 12 19 13 24 +/-+2 28 2
32 +/--2 30 2
31 +/--2 29 2
27+/-+2 25+/-2 23 +/- 2 24 2
24 +/- 15 24 +/- 16 20 +/- 13 20 +/- 13 25+/-+2 27+/-5 27_+/-2 31 +/-5 32-+/-2 30-+/-4 24 +/- 2 25 +/- 4 19 +/-_2 21 +/-_4 22 +/- 15 24 +/- 16 19 +/- 12 20 +/- 13 (a)
Sample not received.
r-77f
TABLE B-2 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results in Units of 10-3 pCi/m 3 +/- 2 sigma Stations Nuclides First Quarter Second Quarter Third Quarter Fourth Quarter Average 12/27100 - 03/28/01 03/28/01 - 06/27/01 06/27/01 09/26/01 09/26/01. 12/26/01
+ 2 s.d.
ONS-1 Be-7 82.4 + 5.7 115 + 6.2 128 + 9.6 100 +/- 11 106 + 20 K-40
< 6
<4
< 9
< 6 Cs-134
< 0.4
< 0.3
< 0.3
< 0.3 Cs-137
< 0.3
< 0.3
< 0.3
< 0.3 Th-228
< 0.4
< 0.4
< 0.4
< 3 ONS-2 Be-7 87.7 +/- 5.9 179 +/- 11 124 +/- 8.7 99.5 +/- 9.5 123 +/- 41 K-40
< 5
< 6
< 4
< 5 Cs-134
< 0.3
< 0.5
< 0.2
< 0.3 Cs-137
< 0.3
< 0.4
< 0.3
< 0.3 Th-228
< 0.3
< 0.7
< 0.3
< 3 ONS-3 Be-7 100 +/- 6.9 115 +/- 6.6 118 +/- 9.1 85.5 +/- 10 105 + 15 K-40
< 4
< 5
< 6
< 9 Cs-134
< 0.4
< 0.4
< 0.3
< 0.4 Cs-137
< 0.4
< 0.3
< 0.3
< 0.3 Th-228
< 0.6
< 0.5
< 0.4
< 3 ONS-4 Be-7 93.1 +/- 6.4 135 +/- 7.3 121 +/- 9.7 87.0 +/- 8.2 109 +/- 23 K-40
< 3
< 4
< 7
<5 Cs-134
< 0.4
< 0.3
< 0.3
< 0.4 Cs-137
< 0.4
< 0.2
< 0.4
< 0.3 Th-228
< 0.6
< 0.2
< 0.4
<3 ONS-5 Be-7 83.2 +/- 7.1 129 +/- 7.7 121 t 6.6 102 +/- 10 109 +/- 20 K-40
< 3
< 3
<4
<6 Cs-134
< 0.4
< 0.3
< 0.2
< 0.5 Cs-137
< 0.4
< 0.3
< 0.2
< 0.4 Th-228
< 0.6
< 0.4 0.22 +/- 0.10
< 3 0.22 +/-0.10 ONS-6 Be-7 102 +/- 7.6 121 +/- 7.3 112 +/- 7.4 96.0 +/- 9.8 108+/- 11 K-40
< 3
< 3
< 6
< 7 Cs-134
< 0.4
< 0.4
< 0.4
< 0.6 Cs-137
< 0.3
< 0.4
< 0.4
< 0.5 Th-228
< 0.6
< 0.5
< 0.4
< 3 50
TABLE B-2 (cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS* IN QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results in Units of 10-3 pCi/m 3 +/- 2 sigma Stations Nuclides First Quarter Second Quarter Third Quarter Fourth Quarter Average 12/27/00 - 03/28/01 03/28/01 - 06/27/01 06/27/01 09/26/01 09/26/01 -12/26101
_ 2 s.d.
NBF Be-7 93.3 + 6.2 128 + 6.6 118 + 7.1 94.1 +/- 9.9 108 +/- 17 K-40
< 5
< 3
< 4
< 8 Cs-134
< 0.3
< 0.3
< 0.2
< 0.3 Cs-137
< 0.3
< 0.3
< 0.2
< 0.3 Th-228
< 0.3 0.67 +/- 0.19
< 0.3
< 3 0.67 +/- 0.19 0
SBN Be-7 97.7 +/- 6.5 138 +/- 7.4 132 +/- 8.0 83.2 +/- 9 113 +/- 27 K-40
< 6
< 4
< 5
< 5 Cs-134
< 0.4
< 0.3
< 0.2
< 0.3 Cs-137
< 0.3
< 0.2
< 0.3
< 0.3 Th-228
< 0.3
< 0.4 0.40 +/- 0.13
< 2 0.40 +/- 0.13 DOW Be-7 87.3 +/- 5.8 126 +/- 7.2 119 +/- 6.7 102 +/- 11 109 +/- 17 K-40
< 5
< 3
< 3
< 5 Cs-134
< 0.4
< 0.3
< 0.2
< 0.3 Cs-137
< 0.3
< 0.2
< 0.2
< 0.3 Th-228
< 0.4
< 0.4
< 0.2
< 2 COL Be-7 131 +/- 8.9 134 +/- 7.9 115 +/- 6.8 89.4 +/- 10 117 20 K-40
< 8
< 7
< 5
< 5 Cs-134
< 0.5
< 0.4
< 0.2
< 0.3 Cs-137
< 0.4
< 0.4
< 0.2
< 0.3 Th-228
< 0.5
< 0.4
< 0.2
< 2 51
TABLE B-3 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10-3 pCi 3 +
+/- 2 sigma COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW COL DATES JANUARY 2001
< 10
< 10
< 10
< 30
< 20
< 10
< 30
< 20
<9
<9
<9
<9
< 10
< 10
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 30
< 20
< 30
< 20
< 20
< 30
< 30
< 20
< 20
< 20
< 20
< 20
< 30
< 20
< 20
< 40
< 20
< 10
< 10
< 20
< 20
< 20
< 20
< 10
< 10
< 10
< 10
< 9
< 10
< 10
< 10
< 20
< 20
< 20
< 20
< 30
< 20
< 10
< 20
< 30
< 20
< 10
< 20
<3
<2
<3
<4
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 10
< 10
< 20
< 10
< 3
< 10
< 20
< 20
< 10
< 10
< 10
< 10
< 20
< 20
< 20
< 30
< 20
< 20
< 20
< 20
< 20
< 40
< 40
< 20
< 10
< 10
<5
< 20
< 20
< 30
< 20
< 20
< 20
< 20
< 20
< 10
< 10
< 20
< 20
< 10
<4
< 20
< 20
< 20
< 10
< 20
< 10
< 30
< 20
< 40
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 10
< 10
< 10
< 10
< 10
< 20
< 20
< 20
< 20
< 30
< 30
< 20
< 30
< 40
< 40
< 30
< 20
< 20
< 20
< 20
< 30
< 30
< 30
< 20
< 30
< 20
< 30
< 20
< 20
< 20
< 50
< 40
< 30
< 30
< 30
< 10
< 30
<8
<10
<9
<10
< 10
< 20
< 10
< 20
< 40
< 40
< 30
< 40
< 20
< 20
< 20
< 20
< 40
< 40
< 10
< 20
<5
<5
<4
<5
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 20
< 20
< 20
< 20
< 30
< 30
< 30
< 30
< 20
< 20
< 10
< 20
< 30
< 30
< 30
< 30
< 30
< 30
< 10
< 20
< 30
< 30
< 30
< 30 (a)
Sample not received.
52 01/03/01 01/10/01 01/17/01 01/24/01 01/31/01
< 10
< 20
<6
< 10
< 30 FEBRUARY 02/07/01 02/14/01 02/21/01 02/28/01 MARCH 03/07/01 03/14/01 03/21/01 03/28/01 APRIL 04/04/01 04/11/01 04/18/01 04/25/01
< 20
< 20
< 30
< 20
< 30
30
< 10
<8
< 30
< 10
< 30
<3 MAY 05/02/01 05/09/01 05/16/01 05/23/01 05/30/01
< 10
< 10
< 20
< 10
< 20 June 06/06/01 06/13/01 06/20/01 06/27/01
< 20
< 20
< 20
< 20
TABLE B-3 (cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-1 31 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10.3 pCi/m 3 +/- 2 sigma COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW COL DATES July
< 20
< 30
< 20
< 20
< 30
< 40
< 20
< 30
< 10
< 20
< 10
< 10
< 30
< 30
< 30
< 30
< 40
< 40
< 40
< 60
< 20
< 20
< 20
< 20
< 30
< 30
< 30
< 40
< 30
< 30
< 30
< 30
< 20
< 10
< 20
< 10
< 20
< 20
< 30
< 30
< 10
< 10
< 10
< 10
< 10
< 10
< 10
< 10
< 10
< 10
< 10
< 40
<10
< 9
<10
< 10
< 20
< 20
<10
< 10
< 30
< 30
< 20
< 20
< 20
< 20
< 20
< 20
< 60
< 60
< 60
< 40
< 30
< 30
< 30
< 30
< 30
< 30
< 20
< 30
< 50
< 50
< 50
< 60
<10
<10
< 8
< 10
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 20
< 30
< 30
< 30
< 30
< 50
< 50
< 50
< 30
< 20
< 20
< 30
< 30
< 20
< 30
< 40
< 30
< 30
< 40
< 10
< 20
< 20
< 20
< 30
< 30
< 60
< 50
< 50
< 20
< 20
< 20
< 40
< 20
< 20
< 30
< 30
< 30
< 20
< 20
< 20
< 30
< 20
< 20
< 10
< 10
< 10
< 20
< 10
< 10
< 30
< 20
< 20
<10
< 20
< 20
< 10
< 10
< 10
< 20
< 20
< 20
< 20
< 20
< 20
< 40
< 50
< 40
< 20
< 30
< 30
< 20
< 30
< 30
< 40
< 30
< 30
< 10
< 20
< 10
< 30
< 30
< 30
< 20
< 20
< 20
< 30
< 30
< 30
< 30
< 40
< 40
< 30
< 20
< 20 (a)
Sample not received.
53 07/04/01 07/11/01 07/18/01 07/25/01 August 08/01/01 08/08/01 08/15/01 08/22/01 08/29/01 September 09/05/01 09/12/01 09/19/01 09/26/01 October 10/03/01 10/10/01 10/17/01 10124/01 10/31/01 November 11/07/01 11/14/01 11/21/01 11/28/01 December 12/05/01 12/12/01 12/19/01 12/26/01 01/02/02
<20
< 50 (a)
< 20
< 40
< 20
< 30
< 30
< 20
< 20
< 10
< 10
< 10
<10
< 20
< 30
< 20
< 60
< 20
< 20
< 20
< 20
< 30
< 30
< 30
< 50
< 20
< 30
< 20
< 10
< 30
< 50
< 20
<20
< 20
< 20
< 20
< 10
< 10
< 20
< 20
<10
< 20
< 20
< 50
< 30
< 30
< 30
< 20
< 30
< 20
< 30
< 30
< 20
< 40
< 50
< 10
< 30
< 50
< 20
< 20
< 30
< 20
< 20
< 10
< 10
< 20
< 20
<20
< 30
< 20
< 50
< 30
< 30
< 30
< 20
< 30
< 20
< 30
< 40
< 20
'74..
SI
(
(
I.
I4 TABLE B-4 INDIANA MICHIGFAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results in Units of mR/standard month STATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER AVERAGE CODES 12128/00 - 03129/01 03/29/01 - 06128/01 06/28101 - 09127/01 09/27101 - 01102/02 1 2 s.d.
T-01 T-02 T-03 T-04 T-05 T-06 T-07 T-08 T-09 T-10 T-1 1 T-12 OFT-1 OFT-2 OFT-3 OFT-4 OFT-5 OFT-6 OFT-7 OFT-8 OFT-9 OFT-10 OFT-1I NBF SBN DOW COL Average : 2 s.d.
2.6 + 3.5 3.4 +/- 1.1 3.1 +/- 0.03 3.8 +/- 0.6 3.6 +/- 0.2 3.3 +/- 0.3 3.4 +/- 0.2 3.1 +/- 0.1 3.1 +/- 0.2 3.4 +/- 0.6 2.9 +/- 0.5 2.8 +/- 0.1 3.3 +/- 0.03 2.2 +/- 0.3 3.5 +/- 0.1 3.5 +/- 0.2 3.6 +/- 0.2 3.9 +/- 0.8 3.1 +/-0.3 3.2 +/- 0.1 3.8 +/- 0.4 3.4 +/- 0.2 4.6 +/- 0.5 2.9 +/- 0.1 3.6 +/- 0.0 3.2 +/- 0.4 4.0 +/- 1.3 3.3 +/- 0.5 1.3 +/- 1.7 2.2 +/- 0.7 1.1 +/-0.6 2.8 +/- 3.7 1.9 +/- 3.0 2.8 +/- 1.1 2.1 +/- 0.2 2.4 +/- 0.8 2.6 +/- 2.1 2.8 +/- 1.9 1.9 +/- 1.7 1.7 +/- 0.1 2.1 +/- 1.4 2.3 +/- 2.1 2.3 +/- 1.0 3.3 +/- 0.3 1.4 +/- 0.4 2.3 +/- 0.5 1.7 +/- 0.1 2.9 +/- 0.8 4.5 +/- 2.7 2.4 +/- 0.8 3.5 +/- 3.8 1.9 +/- 1.9 2.8 +/- 2.3 2.0 +/- 0.6 1.0 +/- 0.2 2.3 +/- 0.8 3.9 +/- 1.8 4.0 +/- 0.6 2.6 +/- 0.5 3.3 +/- 0.2 2.9 +/- 0.9 2.6 +/- 0.8 3.1 +/- 0.1 2.9 +/- 0.9 3.4 +/- 0.8 2.9 +/- 0.6 2.8 +/- 0.2 3.6 +/- 0.07 3.3 +/- 1.3 2.9 +/- 0.5 3.2 +/- 0.1 3.0 +/- 1.4 3.8 +/- 0.7 5.9 +/- 1.2 4.0 +/- 0.1 4.4 +/- 1.1 4.9 +/- 0.5 2.9 +/- 0.5 4.1 +/- 0.9 3.7 +/- 0.3 5.3 +/- 1.7 2.3 +/- 0.7 3.0 +/- 1.9 3.5 +/- 0.9 3.2 +/- 1.6 2.9 +/- 2.0 3.3 +/- 0.8 4.0 +/- 2.4 3.8 +/- 1.3 3.1 +/- 0.4 3.2 +/- 1.1 3.1 +/- 0.1 3.5 +/- 0.4 4.0 +/- 1.8 3.6 +/- 1.1 2.9 +/- 1.1 3.8 +/- 0.2 3.2 +/- 0.5 3.5 +/- 0.03 3.7 +/- 1.2 3.2 +/- 1.6 4.4 +/- 0.5 3.0 +/- 1.6 3.7 +/- 0.3 4.1 +/- 0.8 (a) 3.9 +/- 0.8 3.7 +/- 1.2 4.1 +/- 0.1 3.6 +/- 1.2 3.0 +/- 0.8 3.5 +/- 0.4 2.8 +/- 2.2 3.1 +/- 1.5 2.5 +/- 2.0 3.5 +/- 1.1 3.1 +/- 1.7 3.0 +/- 0.6 3.0 +/- 1.2 2.9 - 0.7 3.2 + 0.8 3.3 + 1.1 2.8 +/- 1.4 2.8 - 1.6 3.1 + 1.4 2.7 +/- 1.0 3.1 +/- 1.1 3.4 +/- 0.6 3.0 +/- 2.2 4.1 +/- 3.0 3.0 +/- 1.9 3.6 +/- 1.3 4.3 + 1.0 2.9 +/- 1.0 4.0 +/- 0.9 3.1 + 1.7 4.0 +/- 2.1 2.8 +/- 1.5 2.8 +/- 2.5 3.2 +/- 0.8 (a) TLD was missing during collection. See Appendix E.
01
TABLE B-5 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITTERS-IN SURFACE WATER Results in Units of pCi/liter +/- 2 sigma Station Collection Date 1-131 **
K-40 Tritium SWL-1 (Condenser Circ.)
SWL-2 (South Comp)
SWL-3 (North Comp) 01/31/01 02/28/01 03/31/01 04/30/01 05/31/01 06/30/01 07/31/01 08/31/01 09/30/01 10/31/01 11/30/01 12/31/01 01/31/01 02/28/01 03/31/01 04/30/01 05/31/01 06/30/01 07/31/01 08/31/01 09/30/01 10/31/01 11/30/01 12/31/01 01/31/01 02/28/01 03/31/01 04/30/01 05/31/01
.06/30/01 07/31/01 08/31/01 09/30/01 10/31101 11/30/01 12/31/01
< 20
< 250
< 50
<5
<20
< 30
< 50
< 30
<6
<6
< 20
< 10 (a)
(a)
< 60
< 10
< 30
< 30
< 60
< 20
<6
<7
<20
< 10 (a)
(a)
< 40
< 10
< 30
< 30
< 40
< 20
<5
<8
< 20
< 10
< 90
< 60
< 80
< 50
< 50
< 50
< 80
< 70
< 70
< 60
< 120
< 50 (a)
(a)
<110
< 90
< 60
< 50
< 90
< 80
< 80
< 70
< 50
< 50 (a)
(a)
< 70
< 80
< 70
< 50
< 60 476 +/- 44
< 70
< 90
< 80
< 80
< 100
< 100 160 +/- 60
< 100
< 100
< 100 150 +/- 50 350 +/- 70
< 100
< 100 120 +/- 60
< 100 (a) Sample not collected.
Typical LLDs are found in Table B-12.
1-131 is not a required isotope for analysis of surface water samples.
55
TABLE B-6 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS* IN GROUND WATER Results in Units of pCi/liter t 2 sigma Collection Date Well W-1 Well W-2 Well W-3 Well W-4 Well W-5 Well W-6 Well W-7
< 50 77.2 +/- 35.8
< 50
< 60 80 70 60 70 90 130 100 80 01/25/01 04/26/01 07/27/01 10/25/01 01/25/01 04/26/01 07/27/01 10/26/01 01/25/01 04/26/01 07/26/01 10/25/01 01/29/01 04/27/01 07/31/01 10/25/01 01/29/01 04/27/01 07/31/01 10/26/01 01/29/01 04/27/01 07/31/01 10/25/01 01/25/01 04/26/01 07/27/01 10/26/01 369 +/- 45
< 70 150 +/- 36
< 80
< 80 188 +/- 49 69.6 +/- 37.8
< 60
< 80 274 +/- 26
< 50
< 70
<3
<4
<2
<3
<4
<4
<3
<5
<4
<5
<3
<5
<6
<5
<4
<6
<5
<4
<2
<5
<5
<4
<3
<4
<5
<3
<2
<5
<4
<4
<3
<3
<4
<4
<3
<5
<4
<5
<3
<6
<7
<4
<4
<7
<6
<4
<3
<6
<6
<4
<5
<5
<6
<3
<2
<5 Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
56 K-40 Co-60 Cs-137 Station
< 100
< 60
< 50
< 100 Th-228 3.91 +/- 3.63 5
4 14.2 +/- 2.7 10.9 +/- 3.5
<6
<5
<10
<7
<6
<8
<7 14.3 +/- 5.3
<5
<4
< 10
<8
<6
<6
<6
<9
<5
<4
<4
<9
<5
<3
<10 Tritium 100 100 100 100 100 100 100 100
< 100
< 100
< 100
< 100 540 +/- 90 480 +/- 80 460 +/- 80 460 +/- 70 300 +/- 110 320 +/- 90 220 +/- 90 350 +/- 80 1700 +/- 100 1.600 +/- 100 1000 +/- 100 420 +/- 70
< 100
< 100
< 100
< 100 Station Collection Date
TABLE B-6 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS* IN GROUND WATER Results in Units of pCi/liter +/- 2 sigma Collection Date K-40 Well W-8 Well W-9 Well W-10 Well W-1l Well W-12 Well W-13 Well W-14 01/25/01 04/26/01 07/27/01 10/25/01 01/26/01 04/26/01 07/27/01 10/26/01 01/26/01 04/26/01 07/26/01 10/26/01 01/25/01 04/26/01 07/26/01 10/26/01 01/25/01 04/27/01 07/27/01 10/26/01 01/25/01 04/26/01 07/27/01 10/26/01 01125/01 04/26/01 07/26/01 10/26/01
< 90
< 80
< 60
< 70
< 120
< 80
< 60
< 80
< 80
< 80
< 50
< 120
< 70
< 70
< 60
< 70
<110
< 70
< 50
< 70
< 90
< 100
< 90
< 80
< 90
< 70
< 60
< 80 Co-60 Cs-137
<7
<4
<2
<5
<5
<5
<3
<6
<4
<5
<3
< 5
<7
<5
<3
<5
<6
<6
<4
<5
<4
<4
<3
<4
<4
<5
<4
<4 Average +/- 2 s.d.
188 +/- 233 15.2 +/- 17 548 +/- 944 Typical LLDs are found in Table B-1 2. All other gamma emitters were <LLD.
57 Station
<7
<4
<2
<6
<6
<6
<4
<7
<4
<5
<4
<5
<8
<5
<3
<6
<6
<6
<5
<5
<4
<7
<4
<4
<5
<5
<4
<4 Th-228
< 10
<7
< 4
< 10
<9
< 10 22.7 +/- 6.5
<10
<7
<8
<6
<5 29.1 +/- 9.0
<10
<4
<10
<9
<10
<10
<6 11.3 +/- 3.6
< 10
<7
<5 Tritium 100 100 100 100 100 100 100 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
< 100
+/- 80
+/- 70
+/- 70
+/- 70
<7
<10
<5
<5 180 250 230 260 Station Collection Date
TABLE B-7 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, TRITIUM AND GAMMA EMITTERS* IN DRINKING WATER Results in Units of pCi/liter + 2 sigma CO3LLE*CTION DATE:
eGrn;* R~ta Gamma Snec Iodine 1-131 Tritium LTW 01/10/01 01/24/01 02/07/01 02/21/01 03/07/01 03/21/01 04/04/01 04/18/01 05/02/01 05/16/01 05/30/01 06/13/01 06/27/01 07/11/01 07/25/01 08/08/01 08/22/01 09105/01 09/19/01 10/03/01 10/17/01 10/31101 11/14/01 11/28101 12/12/01 12/26/01 Average +/- 2 s.d.
<4 3.4 +/- 2.0
<2
<3 3.5 +/- 1.1
<3 4.5 +/- 2.2 2.3 +/- 0.9 3.0 +/- 0.9
<2 1.9 +/- 0.9 2.0 +/- 0.9 2.3 +/- 0.9 1.7 +/- 1.0 2.0 +/- 0.9
<2
<2 3.0 +/- 0.8 2.1 +/- 1.1 2.7 +/- 0.9 2.5 +/- 0.9 2.7 +/- 0.9 2.0 +/- 0.9 3.2 +/- 0.9 2.1 +/- 0.9 2.4 +/- 0.9 2.6 +/- 1.4
"< LLD
"< LLD
"< LLD
"< LLD
.< LLD 192 +/- 29 K-40
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 192 +/- 29 K-40
< 5 (a)
< 2 (a)
<1
<1
< 2 (a)
<1
< 0.6
< 0.7
< 0.8
<1
<0.5
<0.5
< 0.4
< 0.7 0.93 +/- 0.55
< 0.5
<1
< 0.7
< 0.4
<1
< 0.7
<1
< 0.3
< 0.4
<1
<1 0.93 t 0.55 190 +/- 70 190 +/- 70 190 +/- 70 190 +/- 70 190 +/- 70 190 +/- 70 160 +/- 70 160 +/- 70 160 +/- 70 160 +/- 70 160 +/- 70 160 +/- 70 160 +/- 70 92 +/- 59 92 +/- 59 92 +/- 59 92 +/- 59 92 +/- 59 92 +/- 59 170 +/- 60 170 +/- 60 170 +/- 60 170 +/- 60 170 +/- 60 170 +/- 60 170 +/- 60 153 +/- 85 (a) Due to delay in analysis and interfering radioactivity, LLDs were not met.
Typical LLDs are found in Table B-12.
58 COLLECTION DATE Iodine 1-131
TABLE B-7 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, TRITIUM AND GAMMA EMITTERS* IN DRINKING WATER Results in Units of pCi/liter + 2 sigma m1 I I::TIl'AN I'lATI G*amma Snec Iodine 1-131 Tritium STJ 01/10/01 01/24101 02/07/01 02/21/01 03/07/01 03/21101 04/04/01 04/18/01 05/02/01 05/16/01 05/30/01 06/13/01 06/27/01 07/11/01 07/25/01 08/08/01 08/22/01 09/05/01 09/19/01 10/03/01 10/17/01 10/31/01 11/14/01 11/28/01 12/12/01 12/26/01 Average + 2 s.d.
<4
<3 2.4 +/- 1.1 4.0 +/- 2.1 2.8 +/- 1.2 3.6 +/- 2.1 3.4 +/- 2.2 2.4 +/- 1.0 2.5 +/- 0.9 2.1 +/- 1.1 2.9 +/- 1.0 2.3 +/- 0.9 2.5 +/- 0.9 2.4 +/- 1.0 3.4 +/- 1.0 3.5 +/- 1.3 2.9 +/- 1.1 2.9 +/- 0.9 2.5 +/- 1.1 3.1 +/-0.9 3.3 +/- 0.9 2.4 +/- 0.9 2.7 +/- 0.9 2.7 +/- 0.9 2.5 +/- 0.9 2.8 +/- 0.9 2.8 +/- 1.0
"< LLD
"< LLD
"< LLD
"< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD 375 +/- 37 K-40
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD.
< LLD
< LLD
< LLD 375 +/- 37 K-40
<5 (a)
<2 (a)
<1
<1
<1
<1
< 0.5 0.96
0.32
<0.7
<1
< 0.9
< 0.4
< 0.4
< 0.8
<1
< 0.5
<1
<0.7
< 0.4
<1
< 0.8
< 0.5
< 0.3
< 0.7
< 0.6
<1 0.96 -+ 0.32 180 +/- 70 180 +/- 70 180 +/- 70 180 +/- 70 180 +/- 70 180 +/- 70 140 +/- 70 140 +/- 70 140 +/- 70 140 +/- 70 140 +/- 70 140 +/- 70 140 +/- 70 93 +/- 57 93 +/- 57 93 +/- 57 93 +/- 57 93 +/- 57 93 +/- 57 140 +/- 60 140 +/- 60 140 +/- 60 140 +/- 60 140 +/- 60 140 +/- 60 140 +/- 60 138 +/- 71 (a) Due to delay in analysis and interfering radioactivity, LLDs were not met.
Typical LLDs are found in Table B-12.
59 Pril I r-f-Tinki DATE Iodine 1-131
ollectio 04/12 04/12 10/11 10/11/
2 s.d.
TABLE B-8 INDIANA MICHIGAN COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS* IN SEDIMENT Results in Units of pCilkg (dry) +/- 2 sigma n Date Be-7 K-40 Cs-137 Ra-226
/01
< 100 7960 +/- 325
< 10
< 200 101
< 100 7190 +/- 257
< 20
< 300
/01
< 200 7260 +/- 374
< 20
< 400
/01
< 100 7650 +/- 301
< 20
< 500 7515 +/- 718 Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
60 Station C SL-2 SL-3 SL-2 SL-3 Average +/-
Th-228 94.0 +/- 7.9 88.1 +/- 6.8 82.7 +/- 10.3 94.5 +/- 8.6 89.8 +/- 11.1
TABLE B-9 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA* EMITTERS IN MILK Results in Units of pCi/liter +/- 2 sigma STATION CODES COLLECTION DATES Station Be-7 K-40 1-131 Cs-137 Ba-140 01/03/01 Glen Troy Farm
< 40 1400 +/- 79
< 3 (a)
< 4
< 40 Monroe Rsid
< 50 1700 +/- 94
< 4 (a)
< 5
< 40 Shuler Farm
< 50 1410 +/- 92
< 4 (a)
< 5
< 40 Living House Farm < 40 1370 +/- 73
< 4 (a)
< 3
< 30 Wyant Farm
< 40 1280 +/- 82
< 6 (a)
< 4
< 40 01/17/01 Glen Troy Farm
< 50 1300 +/- 84
< 0.8
< 6
< 30 Monroe Rsid
< 60 1490 +/- 92
< 0.7
< 7
< 30 Shuler Farm
< 40 1430 +/- 81
< 0.6
< 5
< 20 Living House Farm < 50 1270 +/- 85
< 0.8
< 7
< 30 Wyant Farm
< 50 1250 +/- 77
< 0.6
< 6
< 30 01/31/01 Glen Troy Farm
< 30 1470 +/- 86
< 0.6
< 4
< 20 Monroe Rsid
< 30 1600 +/- 92
< 0.6
< 4
< 20 Shuler Farm
< 50 1510 +/- 121
< 0.6
< 6
< 30 Living House Farm < 30 1280 +/- 76
< 0.9
< 4
< 20 Wyant Farm
< 40 1310 +/- 83
< 0.5
< 4
< 20 02/14/01 Glen Troy Farm
< 50 1640 +/- 79
< 0.3
< 6
< 30 Monroe Rsid
< 50 1520 +/- 83
< 0.3
< 6
< 30 Shuler Farm
< 60 1250 +/- 93
< 0.4
< 7
< 40 Living House Farm < 40 1470 +/- 86
< 0.4
< 4
< 20 Wyant Farm
< 40 1200 +/- 83
< 0.4
< 4
< 20 02/28/01 Glen Troy Farm
< 30" 1370 +/- 85
< 0.3
< 4
< 20 Monroe Rsid
< 30 1660 +/- 97
< 0.2
< 5
< 20 Shuler Farm
< 50 1420 +/- 124
< 0.2
< 6
< 20 Living House Farm < 30 1420 +/- 84
< 0.3
< 6
< 20 Wyant Farm
< 40 1310+/-85
< 0.3
< 4
< 20 03/14/01 Glen Troy Farm
< 30 1300 +/- 83
< 0.3
< 4
< 20 Monroe Rsid
< 30 1700 +/- 92
< 0.4
< 4
< 20 Shuler Farm
< 50 1470 +/- 118
< 0.6
< 6
< 30 Living House Farm < 30 1290 +/- 77
< 0.3
< 4
< 20 Wyant Farm
< 40 1250 +/- 80
< 0.3
< 4
< 20 03/28/01 Glen Troy Farm
< 50 1240 +/- 77
< 0.4
< 6
< 30 Monroe Rsid
< 30 922 +/- 52
< 0.5
< 4
< 20 Shuler Farm
< 50 1200 +/- 79
< 0.6
< 6
< 30 Living House Farm < 60 1260 +/- 97
< 0.3
< 7
,< 30 Wyant Farm
< 40 1260 +/- 71
< 0.3
< 7
< 20 (a) Due to delay in counting, the LLD was missed. See Appendix E.
Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
61
TABLE B-9 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA* EMITTERS IN MILK Results in Units of pCi/liter +/- 2 sigma STATION CODES COLLECTION DATES Station Be-7 K-40 1-131 Cs-137 Ba-140 04/11/01 Glen Troy Farm
< 50 1230 +/- 77
< 0.3
< 6
< 20 Monroe Rsid
< 40 1430 +/- 83
< 0.4
< 5
< 8 Shuler Farm
< 60 1210 +/- 97
< 0.3
< 7
< 30 Living House Farm < 40 1320 +/- 75
< 0.3
< 6
< 20 Wyant Farm
< 50 1250 +/- 81
< 0.4
< 6
< 20 04/25/01 Glen Troy Farm
< 40 1350 +/- 82
< 0.6 4.50 +/- 1.77
< 20 Monroe Rsid
< 30 1600 +/- 92
< 0.3
< 4
< 20 Shuler Farm
< 50 1240 +/- 110
< 0.3
< 6
< 30 Living House Farm < 30 1300 +/- 76
< 0.4
< 5
< 20 Wyant Farm
< 40 1380 +/- 82
< 0.3
< 4
< 20 05/09/01 Glen Troy Farm
< 40 1370 +/- 70
< 0.4
< 5
< 20 Monroe Rsid
< 50 1560 +/- 85
< 0.6
< 6
< 30 Shuler Farm
< 50 1270 +/- 80
< 0.3
< 6
< 30 Living House Farm < 30 1370 +/- 79
< 0.3
< 5
< 20 Wyant Farm
< 30 1260 +/- 78
< 0.3
< 4
< 20 05/23/01 Glen Troy Farm
< 30 1310 +/- 78
< 0.2
< 4
< 20 Monroe Rsid
< 30 1620 +/- 90
< 0.4
< 4
< 20 Shuler Farm
< 50 1290 +/- 106
< 0.3
< 6
< 30 Living House Farm < 30 1340 +/- 76
< 0.3
< 5
< 20 Wyant Farm
< 30 1450 +/- 81
< 0.2
< 4
< 20 06/06/01 Glen Troy Farm
< 70 1230 +/- 101
< 0.4
< 8
< 40 Monroe Rsid
< 50 1710 +/- 86
< 0.3
< 6
< 30 Shuler Farm
< 50 1220 +/- 81
< 0.3
< 6
< 30 Living House Farm < 50 1430 +/- 88
< 0.2
< 6
< 30 Wyant Farm
< 50 1310 +/- 80
< 0.3
< 6
< 30 06/20/01 Glen Troy Farm
< 50 1230 +/- 81
< 0.2
< 6
< 30 Monroe Rsid
< 60 1570 +/- 95
< 0.4
< 7
< 30 Shuler Farm
< 50 1320 +/- 77
< 0.3
< 6
< 20 Living House Farm < 50 1270 +/- 77
< 0.3
< 5
< 30 Wyant Farm
< 30 1280 +/- 68
< 0.3
< 2
< 10 07/04/01 Glen Troy Farm
< 30 1420 +/- 85
< 0.3
< 4
< 20 Monroe Rsid
< 30 1440 +/- 88
< 0.4
< 4
< 20 Shuler Farm
< 30 1180 +/- 72
< 0.4
< 6
< 20 Living House Farm < 40 1340 +/- 90
< 0.4
< 6
< 20 Wyant Farm
< 30 1280 +/- 73
< 0.3
< 3
< 20 (a) Due to delay in counting, the LLD was missed. See Appendix E.
Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
62
TABLE B-9 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA* EMITTERS IN MILK Results in Units of pCi/liter +/- 2 sigma STATION CODES COLLECTION DATES Station Be-7 K-40 1-131 Cs-137 Ba-140 07/18/01 Glen Troy Farm
< 40 1230 + 74
< 0.4
< 5
< 20 Monroe Rsid
< 50 1510 +/- 85
< 0.2
< 6
< 20 Shuler Farm
< 50 1210 +/- 81
< 0.3
< 6
< 20 Living House Farm < 60 1320 +/- 98
< 0.4
< 8
< 30 Wyant Farm
< 50 1260 +/- 76
< 0.4
< 7
< 20 08/01/01 Glen Troy Farm
< 30 1340 +/- 78
< 0.3
< 5
< 20 Monroe Rsid
< 40 1670 +/- 91
< 0.4
< 4
< 20 Shuler Farm
< 40 1250 +/- 89
< 0.3
< 6
< 20 Living House Farm < 30 1350 +/- 69
< 0.3
< 3
< 20 Wyant Farm
< 30 1320 +/- 81
< 0.3
< 4
< 20 08/15/01 Glen Troy Farm
< 50 1300 +/- 77
< 0.4
< 6
< 30 Monroe Rsid
< 50 1500 +/- 83
< 0.4
< 6
< 30 Shuler Farm
< 40 1280 +/- 78
< 0.4
< 6
< 30 Living House Farm < 50 1270 +/- 74
< 0.4
< 7
< 30 Wyant Farm
< 50 1350 +/- 77
< 0.4
< 6
< 30 08/29/01 Glen Troy Farm
< 40 1430 +/- 74
< 0.4
< 5
< 20 Monroe Rsid
< 50 1910 +/- 97
< 0.4
< 6
< 30 Shuler Farm
< 50 1220 +/- 76
< 0.4
< 6
< 30 Living House Farm < 60 1340 +/- 99
< 0.3
< 8
< 40 Wyant Farm
< 50 1200 +/- 73
< 0.5
< 7
< 20 09/12/01 Glen Troy Farm
< 40 1350 +/- 73
< 0.2
< 5
< 20 Monroe Rsid
< 40 1650 +/- 81
< 0.3
< 5
< 20 Shuler Farm
< 60 1090 +/- 84
< 0.2
< 7
< 30 Living House Farm < 40 1330 +/- 67
< 0.2
< 5
< 20 Wyant Farm
< 40 1190 +/- 69
< 0.2
< 5
< 20 09/26/01 Glen Troy Farm
< 30 1320 +/- 79
< 0.4
< 3
< 20 Monroe Rsid
< 30 1640 +/- 91
< 0.4
< 5
< 20 Shuler Farm
< 50 1360 +/- 112
< 0.4
< 6
< 30 Living House Farm < 30 1290 +/- 73
< 0.4
< 4
< 20 Wyant Farm
< 40 1190 +/- 75
< 0.4
< 4
< 20 10/10/01 Glen Troy Farm
< 30 1320 +/- 78
< 0.3
< 4
< 20 Monroe Rsid
< 50 1880 +/- 122
< 0.3
< 6
< 30 Shuler Farm
< 30 1390 +/- 77
< 0.4
< 4
< 20 Living House Farm < 40 1300 +/- 77
< 0.4
< 4
< 20 Wyant Farm
< 40 1280 +/- 89
< 0.3
< 6
< 20 (a) Due to delay in counting, the LLD was missed. See Appendix E.
Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
63
TABLE B-9 (Cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA* EMITTERS IN MILK Results in Units of pCI/liter +/- 2 sigma STATION CODES COLLECTION DATES Station Be-7 K-40 1-131 Cs-137 Ba-140 Glen Troy Farm
< 20 Monroe Rsid
< 30 Shuler Farm
< 30 Living House Farm < 40 Wyant Farm
< 30 Glen Troy Farm
< 40 Monroe Rsid
< 50 Shuler Farm
< 30 Living House Farm < 40 Wyant Farm
< 40 Glen Troy Farm Monroe Rsid Shuler Farm Living House Farm Wyant Farm Glen Troy Farm Monroe Rsid Shuler Farm Living House Farm Wyant Farm Glen Troy Farm Monroe Rsid Shuler Farm Living House Farm Wyant Farm Average +/- 2 s.d.
< 30
< 20
< 40
< 40
< 20
< 60
< 50
< 40
< 50
< 30
< 50
< 50
< 50
< 30
< 40 1460 +/- 55 1770 +/- 64 1340 +/- 55 1330 +/- 66 1300 +/- 52 1320 +/- 81 2000 +/- 125 1370 +/- 75 1310 +/- 77 1360 +/- 90 1300 +/- 60 985 +/- 44.9 1310 +/- 72 1290 +/- 66 1280 +/- 63 1210 +/- 88 1720 +/- 81 1320 +/- 81 1450 +/- 104 1330 +/- 71 1320 +/- 76 1950 + 91 1250 +/- 103 1310 +/- 71 1300 +/- 76 1372 + 349
< 0.4
< 0.6
< 0.6
< 0.5
< 0.5
< 0.2
< 0.2
< 0.3
< 0.3
< 0.3
<1
<1
<1
< 0.9
<1
< 0.3
< 0.2
< 0.2
< 0.2
-< 0.2
< 0.6
< 0.3
<1
< 0.4
< 0.4
<3
<3
<3
<4
<5
<4
<6
<4
<5
<5
<5
<3
<5
<4
<4
<7
<6
<4
<5
<4
<6
<7
<5
<3
<4
<10
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 10
< 20
< 20
<10
< 30
< 30
< 20
< 30
< 20
< 30
< 30
< 30
< 20
< 20 (a) Due to delay in counting, the LLD was missed. See Appendix E.
Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
64 10/24/01 11/07/01 11/21/01 12/05/01 12/19/01
TABLE B-10 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS* IN FOODNEGETATION Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION COLLECTION DATE 09/12/2001 09/12/2001 09/12/2001 09/12/2001 09/19/2001 Station Sector-J Sector-D Sector-J Sector-D ONS-V Description Grapes Grapes Broadleaf Broadleaf Broadleaf Be-7 115 +/- 39 109 +/- 20 1040 +/- 79 7240 +/- 367 2800 +/- 189 K-40 5300 +/- 239 2290 +/- 114 4000 +/- 224 5240 +/- 332 4490 +/- 339 Average +/- 2 s.d.
2261 +/- 5984 4264 +/- 2458 Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
65 1-131
< 10
<8
< 20
< 30
< 40 Cs-137
<8
<5
< 10
< 20
< 20
TABLE B-1I INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS* IN FISH Results in Units of pCi/kg (wet) +/- 2 sigma Collection Date Station 06/08/2001 OFS-N 06/08/2001 ONS-N 06/08/2001 ONS-S 06/08/2001 OFS-S 10102/2001 OFS-N 10/02/2001 ONS-N 10/02/2001 ONS-S 10/02/2001 OFS-S Average +/- 2 s.d.
Description Lake Michigan Lake Michigan Lake Michigan Lake Michigan Lake Michigan Lake Michigan Lake Michigan Lake Michigan Be-7
< 60
< 80
< 100
< 80
< 100
< 100
< 100
< 100 K-40 2900 +/- 119 2680 +/- 188 2880 +/- 144 2390 +/- 122 3920 +/- 254 2880 +/- 276 3130 +/- 266 3370 +/- 262 3019 +/- 929 Co-60
<6
<8
<9
<7
< 20
< 20
< 10
< 20 Cs-137 32.3
3.25 13.5 +/- 2.73 11.7 +/- 3.14
<8
< 20 37.6 +/- 7.39
< 20 55 +/- 9.81 30.0 +/- 36.0 Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.
66 Ra-226
< 100
< 100
< 200
< 100
< 400
< 500
< 500
< 500 Th-228
<10
<10
<10
< 10
< 20
< 20
< 20
< 20
TABLE B-12 INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DETECTION AND REPORTING LEVELS Isotope TI LLD ODCM LLD Rept Level TI LLD ODCM LLD Rept Level Vegetation - pCi/kcq-wet Water - pCi/liter Cerium-144 60 N/A N/A 30 N/A N/A Barium/La-140 10 N/A N/A 50/10 60/15 200 Cesium-134 10 60 1000 7
15 30 Ru,Rh-106 80 N/A N/A 50 N/A N/A Cesium-137 10 60 2000 6
18 50 Zr,Nb-95 10 N/A N/A 10/15 30/15 400 Manganese-54 10 N/A N/A 5
15 1000 Iron-59 15 N/A N/A 15 30 400 Zinc-65 20 N/A N/A 10 30 300 Colbalt-60 10 N/A N/A 5
15 300 Cobalt-58 10 N/A N/A 5
15 1000 Iodine-131 20 60 100 10 1
2 Iodine-131 (a) 1 1
Milk - oCilliter Air Filter - pCilm3 Cerium-144 30 N/A N/A 0.007 N/A N/A Barium/La-140 50/10 60/15 300 0.005 N/A N/A Cesium-134 7
15 60 0.002 0.06 10 Ru,Rh-106 50 N/A N/A 0.010 N/A N/A Cesium-1 37 6
18 70 0.002 0.06 20 Zr,Nb-95 20 N/A N/A 0.002 N/A N/A Manganese-54 5
N/A N/A 0.002 N/A N/A Iron-59 15 N/A N/A 0.002 N/A N/A Zinc-65 10 N/A N/A 0.002 NIA N/A Colbalt-60 5
N/A N/A 0.002 N/A N/A Cobalt-58 5
N/A N/A 0.002 N/A N/A Iodine-131 10 1
3 0.040 0.07 0.9 Iodine-131 (a) 1 1
(a) Analysis by radiochemistry and based on the assumptions in Procedure PRO-032-1 1.
(b) Based on the assumptions in PRO-042-5.
67
TABLE B-12 (cont.)
INDIANA MICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DETECTION AND REPORTING LEVELS Isotope TI LLD ODCM LLD Rept Level TI LLD ODCM LLD Rept Level Fish-pCi/kg - wet (b)
SedimentlSoil -pCil/k-drv Cerium-144 Barium/La-140 Cesium-134 Ru,Rh-106 Cesium-1 37 Zr,Nb-95 Manganese-54 1ron-59 Zinc-65 Colbalt-60 Cobalt-58 Iodine-131 lGross BetalTritium LLDs and Reportin Levels Gross Beta Air Particulates Drinking Water Surface Water Ground Water Drinking Water 0.01 pCi/m 3 2.0 pCi/L 0.01 pCi/m3 4.0 pCi/L Tritium - pCi/L 200 200 200 2000 2000 2000 (a) Analysis by radiochemistry and based on the assumptions in Procedure PRO-032-1 1.
(b)
Based on the assumptions in PRO-042-5.
68 200 200 20 200 20 40 20 40 40 20 20 100 N/A N/A' 130 N/A 150 N/A 130 260 260 130 130 N/A NIA N/A 1000 N/A 2000 N/A 30000 10000 20000 10000 30000 N/A 150 5
30 200 30 40 9
50 60 20 20 30 N/A N/A 150 N/A 180 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NIA N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 20000 20000 20000
APPENDIX C ANALYTICAL PROCEDURES SYNOPSIS 69
ANALYTICAL PROCEDURES SYNOPSIS Appendix C is a synopsis of the analytical procedures performed during 2001 on samples collected for the Donald C. Cook Nuclear Plant's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by American Electric Power 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 Samples............................................................................................
71 Determination of Gross Beta Activity in Water Samples....................................................
72 Analysis of Samples for Tritium (Liquid Scintillation).........................................................
73 Analysis Samples for Iodine-131..........................................................................................
74 Gamma Spectrometry of Samples.........................................................................................
75 M ilk and W ater..........................................................................................................
75 Dried Solids other than Soils and Sediment..............................................................
75 F ish.................................................................................................................................
75 Soils and Sediments...................................................................................................
75 Charcoal Cartridges (Air Iodine)...............................................................................
75 Airborne Particulates................................................................................................
75 Environmental Dosimetry.....................................................................................................
77 70
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/m3)
=
((S/T) - (B/t))/(2.22 V E)
TWO SIGMA ERROR (pCi/m3)
=
2((S/T2 ) + (B/t2 ))l/2/(2.22 V E)
LLD (pCi/m3)
=
4.66 (B1/ 2 )/(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) 71
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.
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 1/2 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.
72
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)
TWO SIGMA ERROR
=
2((N + B)/At) 2/(2.22 V E)
LLD
=
4.66 (B/At)12/(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 73
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) 1/2 TWO SIGMA ERROR
=
2((N/At+B)/At)
/(2.22 E V Y DF)
I/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-0.0061M)/(exp-0.0061 Ms)
E
=
efficiency of the counter determined from an 1-131 standard mount Ms
=
mass of Pdl2 on the standard mount, mg M
=
mass of PDI2 on the sample mount, mg 74
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 c6 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.
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:
75
=
(S-B)/(2.22 t E V F DF)
TWO SIGMA ERROR
=
2(S+B)"2/(2.22 t E V F DF)
LLD
=
4.66(B)" 2/(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 76 RESULT
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 thermoluminescent 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 2nB 4O7-Cu Thin plastic 2
CaSo4-Tm Plastic 3
CaSo4-Tm/Pb Lead 4
CaSo4-Tm/Pb 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 1 0ARreader, 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
(E3
+ E41 + E32 + E42 ]-
[(E3tran2+Ee4trans.
All dose is reported as "mR/standard month" using the following equation to calculate:
Net Exposure + 90 Days X 30.44 Days + Net Exposure/Standard Month 77
APPENDIX D
SUMMARY
OF INTERLABORATORY COMPARISONS 78
EPA Interlaboratory Comparison Program 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 USEPA EMSL-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.
All DOEiEML total uranium analyzed in air filter, water, and soil failed their criteria.
The total uranium results were reported in incorrect units. When converted to the correct units, the results were in agreement and acceptable.
Trending graphs are provided in this section for Analytics and ERA when there were at least two data points to plot.
79
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 TBEFAnalytics Evaluation E2584-93 Milk 2707 2708 2709 Charcoal Charcoal Charcoal March, 2001 June, 2001 August, 2001 August, 2001 1-131 Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 1-131 1-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-137 Ce-141 Ce-141 Cr-51 Cs-34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 75 166 433 212 165 81 172 151 314 254 pCi 104.5 pCi 84.8 pCi 99.6 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 131 68 53 134 172 76 141 126 72 79 100 109 140 72 161 51 200 148 August, 2001 E2756A-396 Charcoal September, 2001 A14734-148 Liquid September, 2001 A14735-148 Gas 1-131 Sr-89 Sr-90 pCi 87 93 0.94 Total uCi 1.30E-03 1.55E-03 Total uCi 1.00E-04 1.12E-04 Xe-1 33 Total uCi 0.606 0.585 Kr-85 Total uCi 8.53 8.42 0.84 0.89 1.04 1.01 80 E2755-396 Milk E2757-396 AP Filter 77 162 418 223 176 82 175 146 322 254 81 72 92 124 68 50 132 162 86 128 120 76 74 90 125 116 66 134 49 158 128 0.97 1.03 1.04 0.95 0.94 0.99 0.98 1.03 0.98 1
1.29 1.18 1.08 1.06 1.00 1.06 1.02 1.06 0.88 1.10 1.05 0.95 1.07 1.11 0.87 1.21 1.09 1.20 1.04 1.27 1.16 A
A A
A A
A A
A A
A W
A A
A A
A A
A A
A A
A A
A A
W A
A A
W A
A A
A A
A
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 September, 2001 A14736-148 Charcoal September, 2001 A14737-148 Air Filter September, 2001 A14738-148 Liquid September, 2001 A14286-148 Liquid September, 2001 E2772-396 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Total uCi 0.483 Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi 4.99E-02 1.68E-01 2.47E-02 5.18E-02 4.60E-02 3.96E-02 2.99E-02 5.22E-02 4.71 E-02 0.495 5.25E-02 1.85E-01 2.97E-02 5.73E-02 4.75E-02 4.02E-02 2.92E-02 5.12E-02 4.83E-02 Gr-Alpha Total uCi 5.80E-04 4.67E-04 Gr-Alpha uCi/cc 1.70E-04 1.45E-04 H-3 uCi/cc 2.92E-03 1.77E-03 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 100 126 349 147 321 190 205 85 246 261 91 121 366 160 319 177 205 86 254 266 September, 2001 E2773-396 Charcoal 1-131 pCi 68.6 67 1.02 81 A
A A
A A
A A
A A
A A
0.98 0.95 0.91 0.83 0.90 0.97 0.99 1.02 1.02 0.98 1.24 1.17 1.65 1.10 1.04 0.95 0.92 1.01 1.07 1.00 0.99 0.98 0.98 A
A A
A A
A A
A A
A A
A A
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 E2774-396 Air Filter December, 2001 E2980-396 Milk December, 2001 E-2981-396 Milk December, 2001 E-2983-396 Air Filter Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Sr-89 Sr-90 Fe-55 1-131 Ce-141 Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 118 362 135 350 184 230 100 305 267 75 44 108 50 352 468 173 312 92 148 101 192 322 185 190 74 163 46 80 57 119 165 116 351 153 307 170 197 82 244 255 85 59 99 61 379 497 199 318 90 149 102 "206 353 181 237 95 152 43 71 49 99 169 1.02 1.03 0.88 1.14 1.08 1.17 1.22 1.25 1.05 0.96 1.27 1.09 0.82 0.93 0.94 0.87 0.98 1.02 0.99 0.99 0.93 0.93 1.02 0.80 0.78 1.07 1.07 1.13 1.16 1.2 0.98 71 December, 2001 E-2982-396 Charcoal 1-131 pCi 89 92 0.93 82 A
ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)
Identification Reported Known Month/Year Number Media Nuclide Units Value Value Ratio TBE/EML Evaluation February, 2001 Rad-29 Liquid Co-60 Cs-134 Cs-137 September, 2001 Rad-38 Liquid Ba-1 33 Co-60 Cs-1 34 Cs-137 Zn-65 August, 2001 Rad-39 Liquid Total U Ra-226 September, 2001 Rad-40 Liquid Sr-89 Sr-90 August, 2001 Rad-41 Liquid Gr-Alpha Gr-Beta September, 2001 Rad-42 Liquid H-3 December, 2001 12130109 Liquid 1-131 pCi/L 95.5 pCi/L 60.5 pCi/L 48 pCi/L 35.5 pCi/L 47.6 pCi/L 15.5 pCi/L 206 pCi/L 35.4 pCi/L 60.3 pCi/L 14.7 pCi/L 26.4 pCi/L 28.2 pCi/L 15.2 pCi/L 52.0 pCi/L 2370 pCi/L 3.77 83 91.1 59.8 45 36 46.8 15.9 197 36.2 52.9 15.4 31.2 25.9 17.8 53.0 2730 4.38 1.05 1.01 1.07 0.99 1.02 0.97 1.05 0.98 1.14 0.95 0.85 1.09 0.85 0.98 0.87 0.86 A
A A
A A
A A
A A
A A
A A
A A
A
Cr.51 IN MILK C- 07 I
120 100 80 P--k 60 40 20 0
Jun-97 Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-Ol Ný-Ol F*TBE mAnalytics]
9 9
a I
May-02 800 700 600 500 400 300 20D 100 0 T Jun-97 Jan.98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-oo F* TBE m AnaNtics]
Apr-Ol Nov-01 May-02 1200 im 600 400 200 800 0
Juný97 Jan-98 Jul,98 Fb-99 Aug-99 Mar-00 I*
TBE a Analytics 9
9 Oct-00 Aprr-Ol Nov-01 May-02 84 1-131 IN MILK Ce-141 IN MILK
300 200 100 0
Jun-97 Jan-98 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01 Nov-01 May-02 F- -TBE Analvbcs n-97 jaý98 350 3GO 250 200 150 100 50 0
Ju Apr-01 No,01 Juý98 Feb-99 Aug-99 Mar-00 Oct-Go May-02 F*TBE mAnalylicsý 85 C-oe Cs-134 IN MILK Cs-137 IN MILK
Fe-IS IN MILK 180 140!
120 t 804 60p 40 20 itd-PB Feb-99 AUg-99 Mar-DO Oct-DO F*TBE mAnalytics Jun-97 Jan-9Z Apr-Gl Nov-01 Mawý02 Zn-65 IN MILK n-97 Jan-98 JuI-96 feb-99 Aug-99 Niar-OC Oct-00 Apr-01 Nov-01 Uay-02 r*TBE EAnaWytc~s Co-SO IN MILK 400 350 300 250 200 150 100 50 0
May-02 Apr-01 Nov-Cl Jun-97 Jan-98 Jul-98 elSE m Analytics Feb-99 Aug-99 Mar-GO Oct00O 86 350 300 250 200 150 100 50 0
Ju.
p II T
U a
a
Co-58 in Milk 200 150 100 50 0
Jul-01 Sep-01 Nov-01 Dec-01 4 TBE iAnalcs Fe-59 in Milk 180 160 140 120 100 80 60 40 20 Jun-01 Mar-97 Sep-97 Apr-98 Nov-98 May-99 Dec-99 Jun-00 Jan-01 Jul-01 Feb-02 Sep-02 F*TBE m Analytics 87 6--Jo Sr-90 IN MILK 70 60 U
50 30 20
0.
Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01 Nov-01 May-02 F*lT E mAnalytics 0
a U
a=
(U B
Jan-01 Fel-01 Apt-01 87
Cr-51 IN FILTERS 900 800 7001 600 500 400 100 Jul-98 Feb-99 Aug-99 Mar-co Oct-00 Apr-01 Nov-01 May-02 e.TBE --Analytics Cs-134 IN FILTERS 180 160 140 120 100 80 U
20 Jul-98 Feb-99 A.9-99 Mar-00 Oct-0o Apr-01 Nov-01 May-02 F 9TBE EAnalytics 88 8-1/
Ce-141 IN FILTERS 600 500 400 300 200 100 p
0 Jul-98 Feb-99 Aug-99 Mar-00 Oct-00 Apr-01 Nov-01 May-02
TBE mAnalvticsl
Cs-137 IN FILTERS Fe-59 IN FILTERS Mn-54 IN FILTERS 160 120 80 40 0
Jul-98 Feb-99 Aug-99 Mar-00 Oct-oo Apr-01 Nov-01 Mayý02 F*-TBE MAnalytics].
450 300 150 JU3-98 0
1 FeM9 Augý99 Mar-00 Oct-Do Apr-01 Nov-01 May-02 F*-TBE mAna"cs 200 150 100 50 Jul-98 0
No,01 May-02 Feb-99 Aug-99 Mar-00 Oct-oo Apr-01
[ý-TýBENAnalvýbcs 89
Zn-65 IN FILTERS 250 200 150 100 50 0
Feb-99 Aug-99 Mar-00 Oct-cc Apr-01 Nov-01 May-02 FlTBE mAnalyticsl Co-60 IN FILTERS Feb-99 Aug-99 Mar-00 Oct-O0
TBE m Analytics 90 Jul-98 4
U-4m U
U.*
t 250 200 150 100 50 A3 IS a
p.
U Jul-98 Apr-O1 Nov-01 May-02 Co-58 IN FILTERS 80 60 40 20 0*-U Jul-Cl Jul-0l Aug-01 Sep-01 Sep-01 Oct-Cl Nov-01 Nov-01 Dec-01
TBE U Analytics]
c -/3
91 H-3 IN WATER 1.00E-02 9.OOE-03 8.OOE-03 7.OOE-03 6.OOE-03 5.00E-03 4.OOE-03 3.OOE-03 2.OOE-03 1.00E-03 Dec-99 Mar-00 Jun-00 Oct-oo Jan-01 Apr-Ol Jul-ol Nov-01
TBE 0 Analytics
1-131 IN CHARCOAL CARTRIDGE U
U maI 120 100 80 60 40 20 0
Ma Jul-01 Nov-0l Feb-02 92 Jan-01 Apr-01
eTBE EIAnlalytjcs arC00 Jun-00 Oct-O0 t
Co-60 IN WATER Feb-01 ApT-01 Jun-01 Jul*l eTBE m ERA]
Cs-1 34 IN WATER 30 20 10 0,
Jan-01 FePb-01 Apr-01 Jun 01 e TBE m ERAI 93 0
120 100 80 60 40 20 0
Jan-01 Sep-01 70 60 50 40 p
U Jul-o0 Seo-0l c -(;
Sr-89 IN WATER Cs-1 37 IN WATER 250 200 150 100 50 o 4-Jan-01 Feb-Ol AprýOl Jun-01 Jul-01 FOTBE a ERA Sep4l Zn-65 IN WATER Sep-13 May-27 Jan-41 Oot-54 Juný68 Feb-82 Oct-95 Jul-09 r#TBE W ERA 40 35 30 25 20 Jan-00 40 35 30 25 20 Jan-00 Sep-13 Mayý27 Jan-41 OCt-54 Jun-68 Feý82 Oct-95 Jul-09
-4TBE a
ERA]
94
40 35 30 25 20 15 la Janýoo Sep-13 May-27 Jan-41 OCt-54 Jun-68 Feb-82 Oct-95 Jul-09 F*-TBE OFRA Gr-ALPHA IN WATER 41 35 30 25 20 15 10 Jan-00 Sep-13 Map27 Jan-41 Oct-54 Jun-68 Febý82 Oct-95 Jul-09
.r*TBE a
ERA.
30 20 lo 1
Jan-00 Sep-13 May-27 Jan-41 OCt-54 Jun-68 Feb-82 octý95 Jul-09 TBE a ERA]
95
(ý-ll Sr-90 IN WATER F
50 4060 F-Gr-BETA IN WATER
APPENDIX E REMP SAMPLING AND ANALYTICAL EXCEPTIONS 96
REMP SAMPLING AND ANALYTICAL EXCEPTIONS Air Particulates The majority of air particulate gross beta results exceeded the ODCM LLD of 0.01 pCi/m3 (sample results which were at or below the LLD values include: ONS-3 for the period of 05/16/01 to 05/23/01; ONS-1, ONS-3, ONS-4, ONS-5, ONS-6, DOW, SBN, and COL for 05/23/01 to 05/30/01; all air sample stations for 11/14/01 to 11/21/01; SBN for 10/10/01 to 10/17/01.) Having the majority of the air sample results greater than the OCDM LLD is consistent with historical data. All of the results were.
lessthan the 0.033 pCi/m 3.
Due to an electrical power interruption samples from air stations ONS-iwere not continuous from 04/04/01 to 04/11/01. The air sample station was without power for approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> (C/R 01109087). Storms caused electrical power interruptions of samples from air stations ONS-5 and ONS 6 for the date for 06/06/01 to 06/13/01, 08/15/01 to 08/22/01, and 09/19/01 to 09/26/01. These power interruptions caused the samples to be of insufficient volume to provide data points. Severe electrical storms occurred in June, August, and September. Where it was possible, samples were collected and analyzed. Corrective actions for these events were captured by the Cook Nuclear Plant corrective actions system in C/R #01165045 and C/R #01235017.
The sample media for ONS-1 (particulate and iodine) for the period of 07/11/01 to 07/18/01 was lost during the shipping process. This condition was captured in C/R #01249063.
Surface Water Surface water samples were not obtained from beach locations SWL-2 and SWL-3 between 01/01/01 and 03/05/01 then again from 03/07/01 to 03/13/01 due to hazardous environmental conditions (i.e. heavy ice build up).
Due to challenges faced by Teledyne Brown Engineering, LLD's were not met for Ba-140 (60pCi/l) and La-140 (15pCi/l) for SWL-1 for the February monthly composite sample. The LLDs reported by Teledyne was 162 and 53.4, respectively. Required LLDs were missed for SWL-1, SWL-2, and SWL-3 for the samples composited for March. The LLDs for these samples were Ba-140, 68.3, 85, and 61.4 pCi/l and La-140, 22.9,26.4, and 19.5 pCi/l, respectively. This event was captured by the Cook Nuclear Plant corrective actions system under C/R # 01110029.
The March monthly composite sample did not meet the required LLD for La-140 (15 pCi/L) for the SWL-3 location. The LLD reported by Teledyne was 15.3 pCi/l. No NCR or C/R was written due to the closeness of this sample to the limit and the limit being an a priori limit.
The monthly composited surface water samples for the month of July for the locations SWL-1, and SWL-2 did not meet the LLDs for La-140 (15 pCi/I) and Ba-140 (60 pCi/l). The reported LLDs were 22.4 and 25 pCi/l for La-140 and 68.7 and 71.0 pCi/L for Ba-140, respectively.
Thermoluminescent Dosimeters (TLDs)
There was an outstanding issue from the 2000 AREOR concerning the discrepancy between the 4th quarter TLD results and the 3rd quarter TLD results. This issue was captured by the Cook Nuclear Plant corrective actions system under C/R D#01 089057. The cause of this condition was the inconsistent use of 'pig' TLDs used to calculate net exposures from gross exposures. Pig TLDs are now used consistently in this process.
97
The 4 th quarter 2001 environmental dosimeter (TLD) at OFT-10 was found to be missing.
The ground surrounding the utility pole was searched and the cage was located; however, the TLD could not be found. This condition was documented on condition report C/R #01325021.
This TLD is located offsite on the comer of Red Arrow Hwy and Floral Road.
Groundwater Gross beta result for groundwater wells SG-1, SG-2, SG-4, and SG-5 measured 5.1 pci/l, 5.2 pCi/1, 7.8 pCi/l and 6.9 pCi/l, respectively, for samples drawn on 01/26/01. These results exceeded the ODCM LLD level of 4.0 pCi/l, however this maximum LLD level is applicable to drinking water only. The gross beta and gross alpha levels recorded were consistent with historical data.
Due to challenges faced by Teledyne Brown Engineering, the LLD was not met for La 140 (15 pCi/1) for W-I 1 for the 1st quarter well samples. The LLD reported by Teledyne was 15.2 pCi/l. The duplicate count for W-1 missed the LLDs for Fe-59 (30 pCi/l), Ba-140 (60 pCi/1),
and La-140 (15 pCi/l). The actual LLDs were 33.9, 1110, and 377 pCi/l, respectively. Teledyne documented this condition on NCR #01-31. This condition was also documented on Cook Plant Condition Report #01110029.
The collection of groundwater samples from W-4, W-5, and W-6 were delayed until 01/29/01 from 01/26/01. This was due to training new technicians on the process of collecting groundwater. Extra time was required and the sampling period extended to 95 days which is within the 25% allowable extension period as per the ODCM.
All results for groundwater sampling were less than the required LLD of 2000 pCi/l and far less than the reporting level of 20000 pCi/1. However, W-6 result yielded 1.6 E+03 pCi/I with an actual LLD of 1.0 E+02 pCi/l. This gives a positive indication of tritium in the groundwater at W-6. This is consistent with historical data and the data indicates the tritium level is declining.
Gross beta result for groundwater wells SG-4 and S/G-5 measured 9.0 pCi/l and 5.2 pCi/l, respectively, for samples drawn on 04/27/01. These results exceeded the ODCM LLD level of 4.0 pCi/I, however, this maximum LLD level is applicable to drinking water only. The gross beta and gross alpha levels recorded were consistent with historical data.
The collection of groundwater samples for W4, W-5, and W-6 were delayed until 07/31/01 from 07/27/01. The sampling period extended to 95 days which is within the 25%
allowable extension period as per the ODCM. This was due to high winds during the sampling period.
Drinking Water Due to challenges faced by Teledyne Brown Engineering, LLDs were not met for Fe-59 (30 pCi/1), Ba-140 (60 pCi/1), and La-140 (15 pCi/1) for the STJ and LTW composite samples for the period of 12/28/00 to 01/10/01. The LLDs reported by Teledyne were, for STJ 30.1, 1300, and 433 pCi/l; for LTW 39.6, 1340, and 454 pCi/l.
The ODCM LLDs were also not met for Ba-140 and La-140 for the STJ and LTW composite samples for the period of 01/25/01 to 02/07/01. The reported LLDs were, for STJ 1030 and 342 pCi/l; for LTW 1020 and 301 pCi/l.
98
Due to challenges faced by Teledyne Brown Engineering, LLDs were not met for 1-131 (1.0 pCi/l) for the STJ and LTW composite samples for the periods of 12/28/00 to 01/10/0 1 and 01/11/01 to 01/24/01. The LLDs reported by Teledyne were 5.0 pCi/l for the first period for both facilities and 2.0 pCi/1 for the second period for both facilities. The LLD was also not met for I 131 (1.0 pCi/1) for the LTW composite sample for the period of 02/22/01 to 03/07/01. The reported LLD for this sample was 2.0 pCi/l.
The ODCM LLD for La-140 (15 pCi/1) was not met for the LTW composite samples for the period of 06/28/01 to 08/08/01. The reported LLDs were 17.0 (06/28/01 to 07/11/01), 15.8 (07/11/01 to 07/25/01), and 15.4 pCi/l (07/25/01 to 08/02/01) during this period.
The above issues were captured by the Cook Nuclear Plant corrective actions system under C/R #01110029 and Teledyne's system under NCR 01-31.
The Lake Township water treatment facility (LTW) gross beta composite sample of the period from 03/22/01 to 04/04/01 was 4.5 pCi/1. This result exceeded the ODCM LLD level of 4.0 pCi/L. This result, however, is consistent with historical data.
Milk Samplin2 None of the milk samples collected on 01/03/01 met the ODCM LLD for 1-131 (1.0 pCi/1). The sample reported LLDs were Glen Troy 3.0, Monroe 4.0, Livinghouse 4.0, and Wyant 6.0 pCi/l. Teledyne initiated NCR #01-30. Cook Nuclear Plant C/R #01110029 captured this condition.
99
APPENDIX F 2001 LAND USE CENSUS 100
SUMMARY
OF THE 2001 LAND USE CENSUS The Land Use Census is performed to identify any significant changes in land usage in the area immediately surrounding the plant, which could affect exposure pathways. Any identified changes are evaluated to determine whether modifications should be made to the REMP or other related programs.
See the attachments and the table that summarize the census results. The following is a narrative summary of the 2001 census.
Dairy Farm Survey (See attachments 1L2, and 3)
The dairy farm survey was performed to update the list of dairy farms located in the plant area (Berrien County), to identify the nearest animal whose milk is used for human consumption. The milk farm survey for the Cook Plant was conducted on September 20, 24, and 27, 2001.
There were no changes in the dairy farm list from the Michigan Department of Agriculture between July 1, 2000 and July 1, 2001. Two new dairy farms (goats for private milk consumption) were located in the County during this year's door-to-door survey.
At the present time, there are five farm/residence with dairy animals used for milk consumption within eight miles of the plant (Shuler, Monroe, Glen-Troy, Waldo, and Jerry Warmbein). The milk sampling program was restarted on March 29, 2000 and has continued to date. Therefore, the collection of monthly broadleaf samples (in lieu of milk sample) has been discontinued (as per 12-THP-6010-RPP 635).
The closest milk-producing animals (for human consumption) are milk cows at the Shuler &
Son Farm located at 2791 Snow Road in Baroda at a distance of 21,648 feet from the plant center line.
Residential Survey (see Attachments 3 and 4)
From June 1, 2000 through June 1, 2001, eight (8) residential building permits were issued for new construction in Lake Township for Sections 5, 6, 7 and 8. These sections border the Cook Plant property. None of the permits change which residence in each sector is closest to the Cook Plant. In addition, none of these permits were issued to the residences, which are the closest in each sector.
Therefore, none of the construction permits will affect the Plant's radiological evaluation of residential households.
Grave and Broadleaf Survey In accordance with the Offsite Dose Calculation Manual PMP-6010-OSD-001 and the grape and broadleaf collection procedure 12-THP-6010-RPP-638, broadleaf vegetation sampling is performed in lieu of a garden census. Broadleaf sampling is performed to monitor for plant impact on the environment. The samples were obtained as close to the site boundary as possible in a land sector, with sample media, with the highest average deposition factor (D/Q). Control samples were also obtained in a less prevalent sector approximately 21 miles from the site boundary. These locations were the B.
Kunde vineyard at 3316 Linco road in Stevensville, onsite broadleaves (ONS-V) were collected by Well
W-1 in sector A, and the Eldridge residence at 6156 Fail road in LaPorte, Indiana, respectively. The analytical results for the grape and broadleaf samples obtained on September 12 and 16, 2001 were less than ODCM lower limits of detection (LLDs) (60 Pico-curies/kg for Cs-134, Cs-137 and 1-131) specified in Att. 3.20 Maximum Values for LLDs - REMP of the ODCM.
101
Conclusion The 2001 REMP Land Use Census verified that no change is required to the Annual Radiological Effluents Release Report or the REMP. This was demonstrated by the performance of the dairy farm survey, the residential survey, and the grape and broadleaf survey. There were no significant changes in the usage of the land immediately surrounding the plant.
102
2001 Land Use Census - Operating Dairy Farms in Name and Address Township Section Andrews University Oronoko 12 Dairy Road Berrien Springs, 49103 Brohman Farm Oronoko 29 1637 Mt Tabor Rd.
Berrien Ssprings, 49103 Glen Troy Farm Weesaw 10 Mel Freehling 2221 Glendora Rd.
Buchanan, 49107 Koebel Farm Three Oaks 36 16318 Avery Rd.
Three Oaks, 49128 Dean Lozmack Weesaw 23 14843 Cleveland Rd.
Galien, 49218 Paul Lozmack Weesaw 30 4193 Elm Valley Three Oaks, 49128 William Nimtz Pipestone 07 3445 Park Rd.
Eau Claire, 49111 Howard Payne Weesaw 31 RFD 2 Box 148 Three Oaks, 49218 Powers Farm Buchanan 31 16402 Wells Rd.
Buchanan, 49107 Shuler Farm Lake 28 2791 Snow Rd.
Baroda, 49101 Wagner Farms Berrien 35 Carl Wagner, Jr.
8523 Chapel Rd.
Carl Wagner, Sr.
Berrien 26 11215 Pucker St.
Niles, 49120 John Warmbein Weesaw 19 RFD 2 Box 180 (Old Mill Rd.)
Three Oaks, 49128 Milton Preston This dairy farm is not located in 57643 Indian Lk Rd.
Berrien County. It is in Cass County Dowagiac, 49047 The above farms arc Michigan Department of Agriculture Grade A approved.
Berrien County Sector/Distance E / 10.5 miles (55,440 ft)
F / 8.5 miles (44,880 ft)
H / 7.0 miles (36,960 ft)
J / 10.6 miles (55,970 ft)
H / 9.2 miles (48,580 fi)
J I 10.3 miles (54,390 ft)
D/ 13.5 miles (71,280 ft)
J / 10.9 miles (57,552 ft)
H / 12.7 miles (67,060 ft)
G & H / 4.1 miles (21,648 ft)
F/ 16.5 miles (87,120 ft)
F/ 17.0 miles (89,760 ft)
J / 8.5 miles (44,880 ft)
E/ 18.4 miles (97,152 ft) 103
2001 Land Use Census - Operating Dairy Farms in Berrien County - Continued The farms listed below are not MI Department of Agriculture approved Farms.
Name and Address Township Section Sector/Distance Arvon Arent 463-6546 Bainbridge 3
C/ 19.2 miles (101,380 ft) 2300 Angling Rd.
Watervliet, MI 49098 Harvey Hoffman Watervielt 35 C / 203 miles (107,180 ft) 2533 N M-140 Hwy.
Watervliet, 49098 Jeff Monroe Lake 27 G /5.0 miles (26,400 ft) 10627 Miller Rd..
Baroda, 49101 Dr. Ken Siefert Niles 12 F / 19.3 miles (101,900 ft)
Town & Country (Vet Clinic) 3127 N, Fifth St. (M-5 1).
Niles, 49120 Tony Waldo Chikaming 13 J / 7.8 miles (41,180 ft) 14255 Minnich Rd.
Sawyer, 49125 Jerry Warmbein Weesaw 18 J / 7.7 miles (40,660 fIt) 14143 Mill Road.
Three dOaks, 49128 Robert Zebell Three Oaks 33 & 34 K/ 12.0 miles (63,360 ft) 7819 Kruger Road Three Oaks, 49128 Zieger Farm Three Oaks 25 J / 9.4 miles (49,630 ft) 5692 Warren Woods Rd.
Three Oaks, 49128 The following farms/residences have steer/cows (Holstein or Jersey)/goats which are not used for milking at this time but should be verified annually.
Devrie Weesaw 10 G/7.8 miles (41,180 ft) 1847 Gardner Rd..
Buchanan, 49107 William Haase Lake 27 G /4.5 miles (23,760 it) 10276 Miller Rd Baroda, 49101 Richard Leneway Bertrand 14 G /17.1 miles (90,290 ft) 2650 Red Bud Tr.
Niles, 49120 Patyno Weesaw 10 H / 7.2 miles (38,020 ft) 2629 Glendora Rd.
Buchanan, 49107 104
2001 Land Use Census - Operating Dairy Farms in Berrien County - Continued The following farms/residences have steer/cows (Holstein or Jersey)/goats which are not used for milking at this time but should be verified annually.
Name and Address Township Section Sector/Distance Arthur Phillips Bainbridge 31 D /14.0 miles (73,920 ft) 2414 Park Rd.
Eau Claire, 49111 Nelson Farm Oronoko 14 F / 10.5 miles (55,440 ft)
Shawnee Rd.
Berrien Springs, 49103 Roger Tumbleson Bertrand 19 G/ 19.0 miles (100,320 fR) 3120 Mayflower Rd.
Niles, 49120 Chad While Lake 14 F / 4.5 miles (23,760 ift) 1558 W. Shawnee Rd.
Baroda, 49101 105
Landuse 2001 ns of I nis symooi marKs locations or cows milked for human I fls symroo marks locations of loats and dairy steers, visual Streets98 Copyright © 1988-1997. Microsoft Corporation and/or its suppliers All rights reserved. Please visit our web site at htpt lmaps expedia.corn A Ltachrnent I Page I oF 3 106 0mi 2
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APPENDIX G
SUMMARY
OF THE PRE-OPERATIONAL RADIOLOGICAL MONITORING PROGRAM 111
SUMMARY
OF THE PREOPERATIONAL RADIOLOGICAL MONITORING PROGRAM A preoperational radiological environmental monitoring program was performed for the Donald C. Cook Nuclear Plant from August 1971 until the initial criticality of Unit 1 on January 18, 1975. The analyses of samples collected in the vicinity of the Donald C. Cook Nuclear Plant were performed by Eberline Instrument Corporation.
The summary of the preoperational program presented in this appendix is based on the seven semi-annual reports covering the period. The purpose of this summary is to provide a comparison of the radioactivity measured in the environs of the Donald C. Cook Nuclear Plant during the pre-start up of Unit 1 and the radioactivity measured in 2001.
As stated in the report for the period of July 1 to December 31, 1971, the purposes of a preoperational radiological monitoring program include:
(a)
"To yield average values of radiation levels and concentrations of radioactive material in various media of the environment.
(b)
To identify sample locations and/or types of samples that deviate from the averages.
(c)
To document seasonal variations that could be erroneously interpreted when the power station is operating.
(d)
To indicate the range of values that should be considered "background" for various types of samples.
(e)
To "proof test" the environmental monitoring equipment and procedures prior to operation of the nuclear power station.
(h)
To provide baseline information that will yield estimates of the dose to man, if any, which will result from plant operation."
The discussion that follows is for the various sample media collected and analyzed in both the preoperational period and during 2001. Analyses performed during the preoperational but not required in 2001, are not discussed.
The gross beta activity in air particulate filters ranged from 0.01 to 0.17 pCi/m3 from the middle of 1971 to the middle of 1973. In June of 1973 and in June of 1974 the People's Republic of China detonated atmospheric nuclear tests. As a result there were periods during which the gross beta results were elevated to as high as 0.45 pCi/m 3 with no statistically significant differences between indicator and background stations. By the end of the preoperational period the values were approximately 0.06 pCi/m3.
The gamma ray analyses of composited air particulate filters showed "trace amounts" of fission products, Ce-144, Ru-106, Ru-103, Zr-95, and Nb-95, the results of fallout from previous atmospheric nuclear tests. Cosmogenically produced beryllium-7 was also detected.
The direct radiation background as measured by thermoluminescent dosimeters (TLD) ranged between 1.0 and 2.0 mRern/week during the three and one-half years period.
112
Milk samples during the preoperational period were analyzed for iodine-131 and by gamma ray spectroscopy (and for strontium-89 and strontium-90). All samples had naturally occurring potassium 40 with values ranging between 520 and 2310 pCi/liter. Cesiurn-137 was measured in many samples after the two atmospheric nuclear tests mentioned above. The cesium-137 activity ranged from 8 to 33 pCi/liter. Iodine-131 was measured in four milk samples collected July 9, 1974. The values ranged between 0.2 and 0.9 pCi/liter.
Lake water samples were collected and analyzed for tritium and by gamma ray spectroscopy.
Tritium activities were below 1000 pCi/liter and typically averaged about 400 pCi/liter.
No.
radionuclides were detected by gamma ray spectroscopy.
Gamma ray spectroscopy analyses of lake sediment detected natural abundances of potassium 40, uranium and thorium daughters, and traces of cesium-137 below 0.1 pCi/g which is attributed to fallout.
Gamma spectroscopy analyses of fish detected natural abundance of potassium-40 and traces of cesium-137; the latter attributed to fallout.
Drinking water analysis was not part of the preoperational program.
113
APPENDIX H
SUMMARY
OF THE REMP QUALITY CONTROL PROGRAM 114
Teledyne Brown Engineering Quality Control Summary 2001 The quality assurance program at Teledyne Brown Engineering - Environmental Services (TBE-ES) is designed to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, measurement and reporting of data, as well as the record keeping of the final results. Quality control, as part of the quality assurance program, provides a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements.
TBE-ES laboratory employs a comprehensive quality assurance program designed to monitor the quality of analytical processing to ensure reliable environmental monitoring data. The program includes the use of controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits by external groups, a laboratory quality control program which include regular Quality Control (QC) samples to include blanks, Laboratory Control Samples (LCS) and duplicates, and a staff training program. Monitoring programs also include the Interlaboratory Quality Control Program administered by the Laboratory Quality Assurance Manager (used in conjunction with the National Institute of Standards and Technology's Measurement Assurance Program, NIST MAP) and a third party interlaboratory program administered by Analytics, Inc. and Environmental Resource Associates. Together these programs are targeted to supply QA/QC sources at 5% of the client sample analysis load. In addition the Laboratory Quality Control Audit Committee administers a blind duplicate program conducted through client environmental monitoring programs.
The TBE Quality Assurance Program meets or exceeds all requirements specified in Reg. Guide 4.15, Quality Assurance for Radiological Monitoring Programs.
This summary reports QC sample data and interlaboratory known values or interlaboratory results analyzed or received by TBE-ES during the year 2001. Any problems that are identified during the course of these studies are investigated by means of the TBE Corrective Action Process.
Blanks Laboratory blanks were analyzed on water.
These blanks were analyzed for gross alpha, gross beta, iodine-13 1, strontium-89, and strontium-90. A total of 351 blanks were analyzed. The analytical are presented in the attached table.
Suikes Laboratory spikes or laboratory control samples were analyzed for the following matrices:
Water, Milk, and Other Liquid. These spikes were analyzed for gross alpha, gross beta, tritium, iodine 13 1, strontium-89, and strontium-90. A total of 351 spikes were analyzed. The analytical are presented in the attached table.
115
Duplicates Duplicate samples were analyzed for the following matrices: Air Particulates, Charcoal Filters, Ground Water, and Milk. These duplicates were analyzed for gross beta, iodine-131, potassium-40, and tritium. A total of 42 duplicate sets were analyzed. The analytical results are presented in the attached table.
Intercomparison Data The intercomparsion tables and graphs are includes in Appendix D.
116
GROSS ALPHA, GROSS BETA IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 1 of 4)
Gross Alpha, Total pCi Gross Beta, Total pCi Spike Spike Spike
.Spike Count date Blank (pCi)
Found (pCi)
In (pCi)
Blank (pCi) Found (pCi)
In (pCi) 02/0912001 02/09/2001 02/09/2001 02/16/2001 02/20/2001 02/20/2001 02/20/2001 02/22/2001 02/28/2001 03/02/2001 03/02/2001 03/02/2001 03/06/2001 03/08/2001 03/15/2001 03/15/2001 03/21/2001 03/22/2001 03/26/2001 03/27/2001 03/27/2001 03/29/2001 04/03/2001 04/12/2001 04/17/2001 04/18/2001 04/26/2001 04/30/2001 04/30/2001 04/30/2001
< 0.001
< 0.002
< 0.001
< 0.010
< 0.001
< 0.001
< 0.001
< 0.100
< 0.200
< 0.090
< 0.090
< 0.300
< 0.300
< 0.500
< 0.200
< 0.200
< 0.200
< 0.500
< 0.500
< 0.200
< 0.200
< 0.400
< 0.600
< 0.400
< 0.400
< 0.300
< 0.600
< 0.600
< 0.600
< 0.700 9.7 9.1 9.7 1.9 0.026 0.027 0.025 10 10 3.3 1.7
.6.9 9.4 13 7.4 11 14 14 13 13 11 12 12 12 10 11 8.8 12 11 11 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2
< 0.002
< 0.002
< 0.002
< 0.020
< 0.002
< 0.002
< 0.002
< 0.200
< 0.600
< 0.200
< 0.200
< 0.900
< 0.001
< 1.000
< 0.700
< 0.700
< 0.800
< 1.000
< 1.000
< 0.700
< 0.700
< 1.000
< 1.000
< 0.700
< 0.900
< 0.700
< 0.800
< 1.000
< 1.000
< 1.000 22.0 22.0 21.0 5.1 0.069 0.065 0.076 21.0 22.0 5.7 5.4 20.0 19.0 22.0 22.0 22.0 22.0 20.0 20.0 24.0 23.0 23.0 23.0 22.0 20.0 23.0 22.0 21.0 21.0 19.0 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 (a) Spike plated out on the side of the container. Retraining was conducted. Client samples were not affected.
117 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
GROSS ALPHA, GROSS BETA IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 4)
Gross Alpha, Total pCi Gross Beta, Total pCi Spike Spike Spike Spike Count date Blank Found pCi In pCi Blank (pCi) Found (pCi)
In (pCi) 05/04/2001 05/09/2001 05/10/2001 05/10/2001 05/10/2001 05/17/2001 05/17/2001 05/22/2001 05/23/2001 05/23/2001 05/30/2001 06/07/2001 06/08/2001 06/15/2001 06/19/2001 06/22/2001 06/27/2001 07/03/2001 07/10/2001 07/17/2001 07/20/2001 07/31/2001 07/31/2001 08/06/2001 08/14/2001 08/16/2001 08/16/2001 08/17/2001 08/27/2001 08/28/2001 08/29/2001
< 0.400
< 0.700
< 0.300
< 0.300
< 0.300
< 0.001
< 0.001
< 0.0008
< 0.070
< 0.001
< 0.300
< 0.400
< 0.100
< 0.300
< 0.600
< 0.400
< 0.700
< 0.400
< 0.400
< 0.200
< 0.500
< 0.300
< 0.300
< 0.001
< 0.300
< 0.400
< 0.400
< 0.400
< 0.800
< 0.600
< 0.500 11 8.2 9.9 8.9 10 8.8 10 9.8 14 8.6 9.7 10
< 0.6 8.1 8.8 10 12 9.7 8.7 11 12 12 12 15 13 14 13 11 11 13 12 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 11.2 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7
< 0.700
< 1.000
< 1.000
< 1.000
< 1.000
< 0.003
< 0.003
< 0.002
< 0.100
< 0.002
< 0.800
< 0.700
< 0.200
< 0.700
< 0.600
< 0.700
< 1.000
< 0.700
< 0.700
< 0.800
< 0.800
< 0.700
< 0.700
< 0.001
< 0.700
< 0.800
< 0.800
< 0.700
< 1.000
< 1.000
< 0.700 22.0 22.0 22.0 22.0 22.0 22.0 23.0 22.0 21.0 21.0 22.0 22.0 20.0 23.0 22.0 23.0 22.0 23.0 22.0 25.0 26.0 26.0 24.0 26.0 26.0 25.0 25.0 26.0 26.0 28.0 24.0 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 22.1 25.3 25.3 25.3 25.3 25.3 25.3 23.3 25.3 25.3 25.3 25.3 (a) Spike plated out on the side of the container. Retraining was conducted.
118 (a)
(a)
(a)
(a)
(a)
(a)
(a)
(a)
GROSS ALPHA, GROSS BETA IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of 4)
Gross Alpha, Total pCi Gross Beta, Total pCi Spike Spike Spike Spike Count date Blank Found pCi In pCi Blank (pCi) Found (pCi)
In (pCI) 09/10/2001 09/12/2001 09/19/2001 09/19/2001 09/24/2001 09/27/2001 10/01/2001 10/02/2001 10/04/2001 10/05/2001 10/0912001 10/10/2001 10/11/2001 10/11/2001 10/12/2001 10/12/2001 10/16/2001 10/19/2001 10/23/2001 10/26/2001 10/26/2001 10/31/2001 10/31/2001 11/07/2001 11/09/2001 11/12/2001 11/14/2001 11/16/2001 11/20/2001 11/21/2001 11/21/2001
< 0.700
< 0.200
< 0.300
< 0.300
< 0.600
< 0.300
< 0.300
< 0.400
< 0.600
< 0.400
< 0.300
< 0.700
< 0.400
< 0.300
< 0.500
< 0.500
< 0.400
< 1.000
< 0.300
< 0.400
< 0.400
< 0.900
< 0.500
< 0.300
< 0.500
< 0.400
< 0.300
< 0.700
< 0.400
< 0.800
< 0.700 15 22 26 23 31 28 30 25 25 23 27 34 28 29 32 27 27 35 29 29 26 28 28 27 27 25 24 30 27 33 29 14.7 29.3 29.3 29.3 29.3 29.35 29.3 29.4 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3 29.3
< 1.000
< 0.600
< 0.800
< 0.800
< 1.000
< 0.700
< 0.800
< 0.700
< 1.000
< 0.700
< 0.700
< 1.000
< 0.800
< 0.700
< 0.700
< 0.700
< 0.700
< 1.000
< 0.700
< 0.600
< 0.600
< 0.800
< 0.700
< 0.900
< 1.000
< 0.800
< 0.700
< 1.000
< 0.700
< 1.000
< 0.700 28.0 25.0 23.0 25.0 26.0 24.0 24.0 25.0 25.0 24.0 24.0 23.0 24.0 26.0 25.0 25.0 24.0 22.0 24.0 24.0 24.0 25.0 25.0 25.0 23.0 23.0 25.0 25.0 26.0 22.0 23.0 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 25.3 119
GROSS ALPHA, GROSS BETA IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 4 of 4)
Gross Alpha, Total pCi Gross Beta, Total pCi Spike Spike Spike Spike Count date Blank Found pCi In pCi Blank (pCi) Found (pCi)
In (pCi) 12/05/2001 12/06/2001 12/10/2001 12/17/2001 12/19/2001 12/19/2001 12/21/2001
< 0.400
< 0.700
< 0.200
< 0.300
'< 0.500
< 0.500
< 0.500 31 30 32 25 27 32 31 29.3 29.3 29.3 29.3 29.3 29.3 29.3
< 0.700
< 1.000
< 0.800
< 0.700
< 0.800
< 0.800
< 0.900 28.0 23.0 28.0 24.0 25.0 25.0 25.0 25.3 25.3 25.3 25.3 25.3 25.3 25.3 120
H-3 IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 1 of 2)
Spike Spike Count date Blank (pCi)
Found (pCi)
In (pCi) 01/12/2001 01/20/2001 01/22/2001 01/23/2001 01/26/2001 01/27/2001 01/31/2001 02/01/2001 02/06/2001 02/07/2001 02/08/2001 02/0912001 03/01/2001 03/03/2001 03/06/2001 03/12/2001 03/15/2001 03/20/2001 03121/2001 03/23/2001 03/24/2001 03/26/2001 03/30/2001 03/31/2001 04/07/2001 04/11/2001 04/11/2001 04/12/2001 04/13/2001 04/14/2001 04/16/2001 04/17/2001 04/19/2001 04/22/2001 04/25/2001
< 2.0
< 1.0
< 1.0
< 1.0
< 1.0
< 1.0
< 1.0
< 0.8
< 1.0
< 1.0
< 1.0
< 1.0
<0.1
< 0.1
< 0.2
< 0.1
< 0.1
< 1.0
< 1.0
< 0.1
< 1.0
< 0.1
< 0.1
< 1.0
<0.1
< 1.0
< 0.1
< 0.3
<0.1
< 0.3
< 1.0
< 0.9
< 1.0
< 1.0
<0.1 1200 1300 1300 1300 1300 1300 1300 2300 1300 1300 1300 1400 1200 1200 1300 1200 1200 1400 1300 1200 1300 1200 1100 1300 1100 1200 1100 1400 1100 1300 910 920 1200 1300 1100 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 1127 (a) Sample was double spiked.
121 (a)
H-3 IN-HOUSE BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 2)
Spike Spike Count date Blank (pCi)
Found (pCi)
In (pCi) 05/01/2001
< 0.10 1100 1127 05/04/2001
< 1.00 1200 1127 05/05/2001
< 1.00 1100 1127 05/08(2001
< 1.00 920 1127 05/08/2001
< 1.00 920 1127 06/16/2001
< 0.20 1100 1127 06/18/2001
< 0.10 1100 1127 06/19/2001
< 0.90 910 1127 06/20/2001
< 0.10 1100 1127 06/27/2001
< 1.00 1200 1127 06/29/2001
< 0.10 1100 1127 06/29/2001
< 1.00 1300 1127 07/13/2001
< 0.10 1100 1127 08/01/2001
< 0.10 1100 1127 08/08/2001
< 0.10 1100 1127 08/11/2001
< 1.00 1300 1127 08/11/2001
< 1.00 1300 1127 08/19/2001
< 1.00 1200 1127 08/20/2001
< 0.10 1100 1127 08/25/2001
< 1.00 950 1127 09/01/2001
< 0.09 1100 1127 09/16/2001
< 0.10 1100 1127 10/03/2001 0.55 1100 1127 10/08/2001
< 0.10 1100 1127 10/08/2001
< 0.90 1200 1127 10/25/2001
< 0.09 1100 1127 10/25/2001
< 0.09 1100 1127 10/25/2001
< 1.00 1200 1127 11/02/2001 0.99 1100 1127 11/13/2001
< 0.10 1100 1127 11/13/2001 0.13 1100 1127 11/13/2001
< 1.00 1100 1127 11/16/2001
< 1.00 1100 1127 11/30/2001
< 1.00 1100 1127 12/04/2001
< 1.00 1200 1127 12/08/2001
< 2.00 1100 1127 122
1-131 IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page I of 1)
Spike Spike Count date Blank (pCi0 Found (pCi)
In (pCi) 02/15/2001 03/0912001 04/04/2001 05/15/2001 09/17(2001 09/28/2001
< 0.2
< 0.4
< 0.3
< 0.2
< 0.4
< 1.0 27 2.9 0.4
<0.1 17.00 3.5 32.30 4.85 0.52 21.00 4.09 (a) 1-131 spike solution was too old. When replaced, the spike results were acceptable.
123 (a)
(a)
(a)
Sr-89, Sr-90 IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 1 of 2)
Sr-89 Sr-90 Spike Spike Spike Spike Count date Blank (pCi)
Found (pCi)
In (pCi)
Blank (pCi) Found (pCI)
In (pCi) 02/19/2001 02/28/2001 02/23/2001 03/05/2001 03/10/2001 03/16/2001 03/20/2001 03/28/2001 04/05/2001 04/12/2001 04/12/2001 04/13/2001 04/20/2001 04/26/2001 04/30/2001 05/17/2001 05/25/2001 06/01/2001 0610112001 06/15/2001 06/19/2001 06/27/2001 07/05/2001 07/10/2001 07/17/2001 08/02/2001 08/10/2001 08/23/2001 08/23/2001 08/2412001
< 0.05
< 0.2
<1
<2
<2
<8
<3
<2
<2
<2
<2
<3
<1
<2
<1
<3
<2
<1 53 100 61.7 49.4 33.1 41.59 121.66 65.89 47.41 43.07 35 35.55 34.4 33 34.1 30.8 21.5 28.3 24.4 15.0 30.5 11.9 11.9 25.1 34.23 30.60 39.30 36.36 26.08 24.97 23.45 14.72 33.24 11.681 12.91 27.43
< 0.5
< 0.001
< 0.2
< 6.8
< 2.0
< 2.0
< 0.5
< 1.0
< 0.8
< 0.0008
< 1.0
< 0.3
< 1.0
< 3.0
< 0.8
< 1.0
< 1.0
< 1.0
< 1.0
< 2.0
< 1.0
< 2.0
< 0.8
< 0.6
<1.0
< 0.7
< 2.0
< 1.0
< 1.0 15.5 0.074 28 30.2 31.1 34.0 137.0 27.5 22.9 14.6 11.0 15.5 29.2 17 16 42 26.4 43.7 13.7 36.4 43.7 35.5 13.6 34.5 37.2 23.6 32.7 38.1 22.7 16.09 16.07 30.15 32.07 31.55 31.59 12.77 32.02 32.00 15.34 16.06 15.99 31.97 15.00 15.53 44.80 31.93 41.55 15.48 38.14 50.40 39.05 15.45 46.54 44.95 27.07 40.18 43.05 27.04 (a) Incorrect reference date was being used. Client samples were not affected.
124 (a)
(b)
(b)
Sr-89, Sr-90 IN-HOUSE WATER BLANK AND SPIKE PROGRAM TELEDYNE QC PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 2)
Sr-89 Sr-90 Spike Spike Spike Spike Count date Blank (pCi)
Found (pCi)
In (pCi)
Blank (pCi) Found (pCi)
In (pCi) 09/06/2001 09/06/2001 09/1212001 09120/2001 09/26/2001 10/03/2001 10/08/2001 10/12/2001 10/23/2001 10/24/2001 10/25/2001 11/13/2001 12/04/2001 12/11/2001 12/19/2001
<2
<2
<2
<1
<4
<2
<3
<1
<2
<1
<2
<2
<1
<2 13.7 12.8 8.6 33.8 11 31 17 54 17 54 20 30 74 26 15.6 13.7 11.5 43.6 9.9 37.0 17.4 60.2 19.5 60.2 22.7 34.4 76.9 29.6
< 0.3
< 0.9
< 0.6
< 0.9
< 0.6
< 0.9
< 1.0
< 0.7
< 0.8
< 1.0
< 0.8
< 0.7
< 0.7
< 0.6
< 0.8 45.4 51.7 24.5 47.0 23.0 50 26 31 24 42 24 41 30 44 35 51.6 58.0 24.5 49.2 27.1 54.1 27.1 35.3 27.1 45.6 27.1 45.9 33.6 54.2 36.0 125
Results of Duplicate Analyses for 2001 Sample Type Analysis Date First Analysis Second Analysis Air Particulates Results in Units of pCilm3 Air Particulates/
Charcoal Filters Results in Units of pCitm3 Gr-Beta 01/10/01 "01/24/01 "02/07/01 "9
02/21/01 "03/07/01 "9,
03/21/01 "9
04/04/01 "04118/01 "9
05/02/01 "9
05/23/01 "I,
06/06/01 "9
06/20/01 "I,
07/04/01 "9,
07/18/01 "9,
08/08/01 "9
08/22/01 "9,
09/05/01 "9
09/19/01
""10/03/02
".9 10/17/01 "69 10/31/02
".9 12/05/02 1-131 01/10/01 01/24/01 02/07/01 02/21/01 03/21/01 04/04/01 04/18/01 05/02/01 05/23/01 06/06/01 06/20/01 07/04/01 07/18/01 08/08/01 08/22/01 09/05/01 09/19/01 10/03/01 10/17/01 10/31/01 2.4E-02 3.3E-02 2.1 E-02 3.OE-02 1.7E-02 1.8E-02 1.7E-02 I.4E-02 1.8E-02 1.2E-02 6.7E-03 1.9E-02 1.9E-02 1.6E-02 2.4E-02 I.7E-02 1.6E-02 2.0E-02 2.2E-02 1.2E-02 1.3E-02 3.1 E-02 2.OE-03 3.OE-03 2.OE-03 2.OE-03 2.0E-03 2.0E-03 2.0E-03 2.OE-03 2.0E-03 2.0E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 1.7E-03 3.OE-03
"< 2.E-02
"< 2.E-02
"< 3.E-02
"< 2.E-02
"< 1.E-02
"< 1.E-02 I.E-02
"< 1.E-02
"< 2.E-02
"< 3.E-02
"< 2.E-02
"< 2.E-02
"< 1.E-02
"< 1.E-02
"< 2.E-02
"< 2.E-02
"< 1.E-02
"< 2.E-02
"< 3.E-02
"< 3.E-02 (a) All other gamma results were less than the detection limits (LLD).
126 2.6E-02 3.3E-02 2.1 E-02 3.0E-02 1.7E-02 1.7E-02 1.4E-02 1.3E-02 1.9E-02 1.2E-02 7.5E-03 1.9E-02 1.9E-02 1.5E-02 2.5E-02 1.9E-02 1.6E-02 2.1 E-02 2.3E-02 1.2E-02 1.3E-02 2.8E-02 2.0E-03 3.OE-03 2.OE-03 2.OE-03 2.0E-03 2.OE-03 2.0E-03 2.0E-03 2.OE-03 2.0E-03 1.7E-03 2.0E-03 2.0E-03 2.OE-03 2.0E-03 2.0E-03 2.OE-03 2.OE-03 2.0E-03 2.OE-03 2.OE-03 2.0E-03
"< 1.E-02
"< 7E-03
"< 2.E-02
"< 2.E-02
"< 1.E-02
"< 1.E-02
"< 2.E-02
"< 7.E-03
"< 2.E-02
"< 4.E-02
"< 2.E-02
"< 3.E-02
"< 2.E-02
"< 1.E-02
"< 3.E-02
"< 2.E-02
"< 1.E-02
"< 1.E-02
"< 2.E-02
"< 2.E-02
Results of Duplicate Analyses for 2001 (Cont.)
Sample Type Analysis First Analysis Second Analysis Ground Water Results in Units of pCi/liter Milks Results in Units of pCi/liter K-40 (a) 01/25/01 "of 07/27/01 H-3 1-131 01/25/01 07/27/01 02/28/01 04/25/01 07/04/01 09/26/01 10124/01 K-40 (a) 02/28/01 "04/25/01 "07/04/01 "09/26/01 "10/24/01 1.4E+03 1.4E+03 1.4E+03 1.6E+03 1.3E+03
+/-
+
+/-
+
+/-
8.4E+01 8.2E+01 8.5E+01 9.1 E+01 5.5E+01 (a) All other gamma results were less than the detection limits (LLD).
127
"< 5.E+01
"< 6.E+01
"< 1.E+02
"< 1.E+02
"< 3.E-01
"< 3.E-01
"< 3.E-01
"< 4.E-01
"< 6.E-01
"< 1.E+02
"< 7.E+01
"< 1.E+02
"< 1.E+02
"< 4.E-01
"< 3.E-01
"< 4.E-01
"< 4.E-01
"< 4.E-01 1.3E+03 1.4E+03 1.3E+03 1.6E+03 1.4E+03
+/-
+
+/-
+/-
+/-
7.5E+01 8.2E+01 7.3E+01 9.OE+01 5.6E+01 of
APPENDIX I TLD QUALITY CONTROL PROGRAM 128
Per Regulatory Guide 4.13, Section C.4 and ANSI N545-1975, thermoluminesent dosimeters (TLDs) are required to undergo performance testing as specified in the ANSI Standard. The results of the sub contractor supplied performance testing are summarized in this section.
Specific testing procedures were followed, and all tests were conducted in the manner requested by the standard.
Sixteen TLD badges were tested for Dependence of Exposure Interpretation on the Length of the Field Cycle, twelve TLD badges were tested for Uniformity, Reproducibility, and Direct Dependence, ten TLD badges were tested for Energy Dependence and Moisture Dependence, eight TLD badges were tested for Light Dependence, and four TLD badges were tested for Self Irradiation.
Panasonic TLD models UD-801 and UD 814AS 11 containing CaSO4:Tm phosphors conform to the performance testing requirements for Environmental Dosimetry stated in ANSI Standard N-545 1975. All the tests were adequately completed in compliance with this standard.
129

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