ML17334B767

Annual Environ Operating Rept for 970101-1231 for DC Cook Nuclear Plant,Units 1 & 2. W/980427 Ltr

ML17334B767
Person / Time
Site:	Cook
Issue date:	12/31/1997
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0806R, AEP:NRC:806R, NUDOCS 9805180427
Download: ML17334B767 (308)

Text

CATEGORY 1 9'EGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCE8810% NER: 9805180427 DOC.DATE: 97/12/31

~ NOTARIZED: NO DOCKET PACIL:50-f15 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana N 05000315 50-f9.6 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.E ~ Indiana Michigan Power Co. (formerly Indiana

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SUBJECT:

"Annual Environ Operating Rept for 970101-1231 for DC Cook C Nuclear Plant, Units 1 a 2." W 8U427 A

DISTRIBUTION CODE: C001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Licensing Submittal: Environmental Rept Amdt E Related Correspondenceg NOTES: E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL STANG,J 1 1 INTERNAL ~ E C C/HDS3 1

1 1

0 NUDOCS-ABSTRACT RGN3 DRS/RSB 1

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1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

N NOTE TO ALL ERZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL 6

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I Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 491071395 April 27, 1998 AEP:NRC:0806R Nos.: 'ocket 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop 0-P1-17 Washington, D.C. 20SSS-0001 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 ANNUAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 1997 TO DECEMBER 31I 1997 Attached is the Cook Nuclear Plant Annual Environmental Operating Report for the year 1997. This report was prepared in accordance with procedure 12 PMP 6010 OSD.001, "Offsite Dose Calculation Manual", section 4.8.1, and technical specification, appendix B, part 2, section 5.4.1.

Sincerely, E. E. Fitzpatrick Vice President

/vlb Attachment J. A. Abramson A. B. Beach MDEQ - DW & RPD NRC Resident Inspector R. Sampson goOI

' DRj 9805i80427 97i23i tT PDR ADOCK 050003i5

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Annual Environmental Operating Report January 1 through December 31, 1997 Indiana Michigan Power Company Bridgman, Michigan Docket Nos. 50-15 8 50-16 License Nos. DPR-58 8 DPR-74

~,98Q5180427

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TABLE OF CONTENTS Pacae I. Introduction II. Changes to the Environmental Technical Specifications .......... 1 III. Non-Radiological Environmental Operating Report A. Plant Design and Operation . ~

1 B. Non-Routine Reports 1 C. Environmental Protection Plan . 2 D. Potentially Significant,Unreviewed Environmental Issue 2 E. Environmental Monitoring-Herbicide Applications ....... 2 F. Mollusc Biofouling Monitoring .

G. Special Reports IV. Radiological Environmental Operating Report A. Changes to the REMP 4 B. Radiological Impact of Cook Nuclear Plant Operations ... 5 C. Land Use Census 5 D. Solid, Liquid, and Gaseous Radioactive Waste Treatment Systems

I LIST OF APPENDICES Appendix Title Non-Routine Reports 1997 Environmental Screening Reports 1997

'III. Herbicide Application Report - 1997 IV. Special Reports A. Pollution Prevention Report 1997 Annual Report: Radiological Environmental Monitor'ing Program 1997 Radiological Environmental Monitoring Program Summary 1997 B. Data Tables C. Analytical Procedures Synopsis D. Summary of EPA Interlaboratory Comparisons E. REMP Sampling and Analytical Exceptions F. Land Use Census G. Summary of the Preoperational Radiological Monitoring Program H. Summary of the Spike and Blank Sample Program I. TLD Quality Control Program

INTRODUCTION Procedure 12 PMP 6010 OSD.001, " Offsite Dose Calculation Manual", Section 4.8.1 and Technical Specification, Appendix B, Part 2, Section 5.4.1 require that an annual report, which details the results and findings of ongoing environmental radiological and non-radiological surveillance programs, be submitted to the Nuclear Regulatory Commission. This report sexves to fulfill these requirements and represents the Annual Environmental Operating Report for Units 1 and 2 of the Donald C. Cook Nuclear Plant for the operating period from January 1 through December 31, 1997.

During 1997, based on the monthly operating reports for Unit 1 and Unit 2, the annual gross electrical generation, average unit service factors, and capacity factors were:

Parameter Unit 1 Unit 2 Gross Electrical Generation (MWH) 4,546,279 5, 875, 213 Unit Service Factor (0) 52.7 65. 1 Unit Capacity Factor MDC* Net (%) 51. 9 63. 3 CHANGES TO THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS There were no environmental Technical Specification changes in 1997.

NON-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Plant Design and Operation During 1997, no instances of noncompliance with the Environmental Protection Plan occurred, nor were there any changes in station design, operations, tests, or experiments which involved a potentially significant unreviewed environmental issue.

There were no environmental screenings during the reporting period.

Non-Routine Reports A summary of the 1997 non-routine events is located in Appendix I of this Report. No long-term, adverse environmental effects were noted.

Environmental Protection Plan There were no instances of Environmental Protection Plan noncompliance in 1997.

Potentially Significant Unreviewed Environmental Issues There were no changes in station design, operations, tests or experiments which involved a potentially significant unreviewed environmental issue.

There were no environmental screenings during the reporting period.

Environmental Monitoring - Herbicide Application Technical Specifications Appendix B, Part 2, Section 5.4.1, states that the Annual Environmental Operating Report shall include: summaries and analyses of the results of the environmental protection activities required by Section 4.2 of this Environmental Protection Plan for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.

Herbicide applications are the activities monitored in accordance with Section 4.2. There were no preoperational herbicide studies to which comparisons could be made.

Herbicide applications are managed by plant procedure 12 PMP 2160 HER.001.

A summary of the 1997 herbicide applications is contained in Appendix III of this report. Based on observations, there were no negative impacts or evidence of trends toward irreversible change to the environment as a result of the herbicide applications. Based on our review of application records and field observations, the applications conformed with EPA and State requirements for the approved use of herbicide.

Mollusc Biofouling Monitoring Program Macrofouler monitoring and control activities continued in 1997. The peak period of abundance of veligers present in the forebay was between August 14 and September 11, with the major peak occurring on August 28. This peak period occurred about one month earlier than is typical for the

lower Great Lakes and immediately preceded the seven week shut down of the chlorination system.

Settlement in the forebay occurred on all sampling dates except May 8. Density data indicate that settlement was low for the first two months and the last two months of the program. Peak settlement was observed between the first part of August and the middle of September. Those observed during the first two months of the program were primarily translocators.

Xt was fortunate that peak spawning occurred during June and August in 1997 when chlorine was delivered rather than the more typical September-October period. This would have put the peak densities of postveligers, in the service water systems during the period when chlorine was not being administered, possibly causing serious clogging problems.

Special Reports Two special reports covering environmental-related activities have been included in Appendix V.

The Pollution Prevention report discusses efforts at the Cook Nuclear Plant in 1997 to prevent generation of waste.

The report summarizes the types and amounts of wastes generated on-site and the cost savings attributed to pollution prevention efforts.

The Cook Nuclear Plant Site Survey was produced by a contractor at AEP's request to provide a preliminary review of habitat information to update previous data regarding species and habitats on-site.

To summarize existing habitat conditions at the Cook Nuclear Plant, plant communities have matured and evolved significantly, especially in the areas disturbed by the original construction. Habitat was assessed for two State Threatened species and six Special Concern species thought to occur on or near the site, and all species of concern listed as occurring in Berrien County. Through an analysis of habitat requirements and existing site conditions, some of the listed species known to occur in Berrien County were eliminated from consideration, since appropriate habitat conditions are not present on this site and occurrence is highly unlikely.

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IV. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Radiological Environmental Monitoring Program annual report is located in Appendix VI of this report.

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 material.

3. Provide reasonable assurance that the predicted doses, based on radiological 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.

Changes to the REMP As indicated in Appendix VI, there were several identified changes to the ODSM during 1997 as follows:

Deleted Technical Specification Clarification 514, Revision 6, Changed compensatory sampling interval, Added 25% grace period for surveillance requirements, Clarified need for compensatory sampling of ESW system when respective radiation monitors are inoperable unless the containment spray heat exchangers are in service, Added note on attachment for determination of start-up flash tank flow rate to improve documentation and changed this flow rate based on estimated steam generator blowdown flow vs. dry value position, Incorporated new Eberline liquid radiation monitors that replaced Westinghouse monitors, Added table allowing plant to use RMS readings in lieu of sampling gland seal exhaust since operational data indicates routine sampling is non-productive, and Added clarification to attachment 3.4 for purging or venting.

Radiological Impact of Donald C. Cook Nuclear Plant Operations This report summarizes the collection and analysis of various environmental sample media in 1997 for the Radiological 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 nuclear plant on the environment. The analysis of air particulate filters, charcoal cartridges, direct radiation by thermoluminescent dosimeters, fish, water, mild and sediments from Lake Michigan, drinking water, and food products, either did not detect any radioactivity or measured only naturally occurring radionuclides at normal background levels.

The only radionuclide which appears attributable to the Donald C. Cook Nuclear Plant operation is tritium, which was measured at low levels in onsite wells.

Land Use Census The Land Use Census is performed to ensure that significant changes in the immediate vicinity of the Donald C. Cook Nuclear Plant are identified. Any identified changes are evaluated to determine whether a modification must be made to the REMP or other related programs. A further discussion of the land use can be found in Appendix VI of this report.

D. Solid, Liquid, and Gaseous Radioactive Waste Treatment Systems There were no changes in the solid, liquid, or gaseous radioactive waste treatment systems during 1997.

CONCLUSION Based upon the results of the radiological environmental monitoring program and the radioactive effluent release reports for the 1997 reporting year, it can be concluded that there were no adverse affects to the environment or to the general public due to the operation of the Donald C. Cook Nuclear Plant.

APPENDIX I NON-ROUTINE REPORTS 1997

1997 Non-Routine Events November 8, 1997 - During continuous Chlorination of the Service Water systems, personnel inadvertently discharged a portion of chlorination Service Water to Outfall 002 for approximately nine hours without performing the required sampling and analysis for Total Residual Oxidant. These samples were missed due to a valve lineup error made during the startup of continuous chlorination after a short shutdown for general maintenance on the circulating water system.

July 13, 1997 - An exceedence occurred during intermittent chlorination when the Outfall 001 analyzer was found to have drifted in a non-conservative direction, resulting in readings actually 20 times lower than they should have been.

APPENDIX II ENVIRONMENTAL SCREENING REPORTS 1997

There were no environmental screenings to report in 1997.

APPENDIX III HERBICIDE APPLICATION REPORT 1997

I AMERICAN KLECTRlC POWER Date March 27, 1998 Subject 1997 Herbicide Spray Report - Cook Nuclear Plant From E. C. Mallen To J. P. Carlson The following herbicides were applied on Cook Nuclear Plant property during 1997:

Round -Up Pro Round - Up Oust Riverdale Solution Howard Johnson's Weed and Feed Preen with Tri-mec From June 30, to July 3, 1997, a mixture of Round-Up Pro, Oust, and Riverdale Solution was used for total plant control in the switch yards, railroad right-of-way, around buildings, parking lots, the sewage and absorption ponds, and within the plant's protected area. The application was performed by DeAngelo Brothers, a licensed herbicide applicator on contract to the AEP Western Division. A total of 118.75 ounces of Oust 712.5 ounces of Riverdale Solution, and 142.5 quarts of Round-Up Pro were used for the application and spread over 40.52 acres.- The following are the application rates used compared to the allowable application rates.

Product Name Quantity Used Quantity Used/Acre Quantity Allowed/Acre Round-Up pro 142.5 qt. 3.52 qt. 5 qt ol Riverdale Solution 712.5 oz. 17.58 oz. 45 oz.

Oust 118.75 oz. 2.93 oz. 8 oz.

O) Baaed on application rata ror Dandcuon, Curly dock, tacody bruah and tract.

On September 9, 1997, the mortality of this herbicide application was assessed at 90%. The following discrepancies were noted:

~ Some vegetation growth near the center of fenced-in area at meteorological tower.

~ Application not performed in new CESA yard.

~ Large tufts of grass south of cable spools in fenced-in area south of Warehouse ¹6.

~ Grape vines and small oaks along inside of fence between 765 & 345 KV yards.

~ Small maples in railroad tracks in 765 KV yard, also in SE corner of yard by small transformers.

~ Training Building transformer and A/C unit area did not receive an application.

~ PM&IS steel yard needs treatment under steel racks; some small trees growing.

l Round-Up mixed with water in a backpack sprayer was used to spot spray weeds in the landscaped stone areas around the plant site and under the racks in the PM&IS steel yard. A total of 68 ounces of Round-Up was used for spot spraying in 1997. The applications were performed by a licensed applicator from the Maintenance ANR Buildings and Grounds Crew.

Page 2 1997 Herbicide Spray Report Two applications of Preen were used for weed control in planting beds around the North Guardhouse entrance and Training Building in 1997. Twelve pounds of Preen granules were spread over 2,703 square feet during the first application on June 10, 1997 and twelve pounds were spread over the same area during the second application on October 1, 1997. This amounted to an application rate of 0.71 ozlIOsq. ft per application. The allowed label rate was 1 oz./10sq. ft. per application. The herbicide was applied by a licensed applicator from the Maintenance ANR Buildings and Grounds crew. The herbicide was 90%

effective and controlled weeds in the planting beds cutting back on weeding time.

A single application of Howard Johnson's Weed //r. Feed with Tri-mec was applied to the plant lawns for weed control on May 14, 16, 20, 22, 28, and June 5, and 9, 1997. A total of 1,900 pounds was spread over 12.88 acres. This amounted to an application rate of 3.41bJ1,000 sq. A. The allowed label rate was 4lb./1,000 sq. A.. The herbicide was applied by the licensed applicator from the Maintenance ANR Buildings & Grounds crew.

The plant lawns were inspected on June 20, and Sept. 9, 1997. The results of the inspection are as follows:

~ A patch of clover and two strands of English Ivy were noted on the north side of the plant office buildings.

~ A clover patch, dandelion, and crab weed, were present on the south side of the north guardhouse.

~ The SGRP (old CESA yard) office building area showed a large reduction in the numbers of dandelions and weeds present from previous years.

~ Large patches of clover were noticed on the hill behind the Training Center.

~ The lawn between the sidewalks and building on the south side of the Training building (below the libraiy) had dandelions starting and spurge present.

In summary, based upon our review of the application records, manufacturer specifications, material safety data sheets (MSDSs) and observations of the treated areas, the herbicides were applied according to the manufacturer's labeled instructions and according to Federal and State requirements. A certified applicator was used as required. Detailed maps and application records are filed in 12 PMP 2160 HER.001, Guidelines for the Application of Approved Herbicides. No signs of over spray or spillage were observed or noted.

No adverse environmental effects occurred.

c: W. Tucker W. Hannah

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APPENDIX IV SPECIAL REPORTS

APPENDIX IV.A 1997 POLLUTION PREVENTION REPORT.

AMERICANELECTRIC POWER DONALD C. COOK NUCLEAR PLANT 1997 POIJ.UTIONPREVElVTIONREPORT

Table of Contents SECTION 1 EXECUTIVE

SUMMARY

SECTION 2 INTRODUCTION 2.1 Policy and Goals 2.2 Pollution Prevention Process SECTION 3 GENERIC POLLUTION PREVENTION ACTIVITIES 3.1 1997 Goals 3.2 Training and Awareness 3.3 Projects 3.4 Chemical Use Review Board 3.5 Sequencing Batch Reactor 3.6 P2 Technology Transfer t SECTION 4 4.1 4.2 HAZARDOUS AND MIXED WASTE General Description Flammable Solvents i 4.3 4.4 4.5 Paint-Related Material Laboratory Solvent and Oil Out-of-Specification/Expired Shelf-Life Material SECTION 5 LIQUID INDUSTRIALWASTE 10 l 5.1 5.2 5.3 General Description Non-Hazardous Solvent Oily Water 10 11 11 SECTION 6 USED OIL 12 6.1 General Description 12 6.2 Used Lubricating Oil 14 6.3 Electro-Hydraulic Control {EHC) Fluid 14 6.4 Radioactive Oil SECTION 7 LOW LEVEL RADIOACTIVEWASTE 15 7.1 General Description 15 SECTION 8 BULKWASTES 17 8.1 Trash 17 8.2 Radioactive Sewage Sludge 18 8.3 Asbestos 18 8.4 Empty Drums 19

ECTION 9 UNIVERSAL WASTE 20

.1 Lead-Acid Batteries 20 9.2 Dry Cell Batteries 21 9.3 Lighting Waste 21 9.4 Nickel-Cadmium Batteries 22 9.5 Lithium Batteries 22 SECTION 10 RECYCLABLE MATERIAL 22 10.1 Scrap Metal 22 10.2 Paper Products 23 i 10.3 Scrap Tires and Rubber 23

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Foreword The Environmental Compliance personnel at the Donald C. Cook Nuclear Plant assembled this Pollution Prevention (P2) report. The waste reduction and cost savings achieved'in 1997 refiect the dedication of AEPNG employees'ommitment to environmental principals and cost efficiency in pursuit of environmental excellence.

Copies of this report can be obtained by calling (616) 465-5901 ext. 1153 or sending a request to Environmental Compliance, One Cook Place, Bridgman, Michigan, 49106.

American Electric Power Nuclear Generation 1997 Pollution Prevention Report 1.0 EXECUTIVE

SUMMARY

1.1 Waste generation data is tracked using the Electric Power Research Institute's Accounting Sofhvare Application for Pollution Prevention (ASAPP) to determine trends and assess benefits of pollution prevention efforts and to evaluate reduction goals.

1.2 The AEP Nuclear Generation Group met our goal of reducing hazardous and mixed waste (78% - the highest ranking pollutant according to the Environmental Protection Agency) and used oil (8%) by more than 5% per year in 1997.

1.3 Liquid Industrial Waste (-6%) and Trash (-25%) goals were not met for 1997 due to extended outages and associated work scope increases. However, Liquid Industrial Waste and Trash generation decreased from the baseline by 95% and 41%, respectively.

1.4 " Over $ 823,000 in avoided costs were achieved in 1997 due to hazardous waste and contaminated sewage sludge prevention measures.

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2.0 INTRODUCTION

2.1 Policy and Goals The American Electric Power Nuclear Generation Group (AEPNG) Pollution Prevention (P2) policy is implemented through our Pollution Prevention Plan (12 PMP 2160 CWM.001). Our 1997 goal was to meet the Environmental Protection Agency's (EPA) recommended industry standard of reducing all categories of waste by 5% per year. Our P2 policy states:

"We will continue to reduce and, where practical, eliminate waste through the use of source reduction, recycle/reuse and treatment techniques. The handling and disposal of all waste will be conducted in a safe and responsible fashion in accordance with regulatory requirements."

Our plan reflects the hierarchy for managing wastes included in the U.S. Pollution Prevention Act of 1990.

MOST Source Reduction PREFERRED Toxicity Reduction Reuse LEAST Recycling PREFERRED Treatment/Volume Reduction Disposal This report documents progress toward our reduction goals and attempts to identify reasons goals were met or not met. Although two refueling outages were planned for 1997, an additional three months of unplanned unit shutdowns contributed to significant increases in several waste streams as discussed under specific sections. Despite the extended outages, many waste streams were reduced significantly despite the added burden of the extended plant shutdown.

2.2 Pollution Prevention Process No significant changes in our P2 process were implemented from what was discussed in the 1992-1996 Pollution Prevention Report. Twelve high priority waste streams were listed for potential action in 1997. All of these waste streams were evaluated by the recommended lead departments to determine the status of the issues and the need for follow up action. These are discussed under specific waste stream headings.

3.0 GENERIC POLLUTION PREVENTION ACTIVITIES 3.1 1997 Goals Waste generation was tracked for five categories of waste: hazardous, liquid industrial used oil, low level radioactive and trash (Table 3.1.1 and Figure 3.1.1). In addition, asbestos and radioactive sewage sludge was included in Table 3.1.1. Universal wastes are discussed under Section 9.0.

Table 3.1.1 1992-1997 Total Cook Nuclear Plant Waste Generation

% Reduced Waste Category Units 1992 1993 1994 1995 1996 1997 1996 to 1997 Hazardous Waste Lbs 7,294 8,095 Lf77+ 7>383 6,775 1,595 76%

Mixed Waste Lbs 867 617 211 563 27 95%

Hazardous Ec Mixed Lbs 11,155 8,962 12,975 7,594 7,338 1,622 78%

Liquid Industrial Gal 206 2,317 1,894 2,020 1,716 15%

Radioactive Liq. Ind. Gal 14,765,;, 1,940 686 199 644 -324%

Rad 4 Clean LIW Gal 14,971 '.,+$ 1%8-- 12,753 2,580 2,219 2,360 -6%

Used Oil Gal 2,760 3,860 5,040 5,050 4,915 3%

Rad. Used Oil Gal 2,255 1,045 1,485 1,090 27%

Rad Ec Clean Used Oil Gal 2,760 6,115 6,085 6,535 6,005 8%

Low Level Rad. CuFt 7,000 3,900 1,467 1,034 1,201 -17%

~

Trash CuYd 11,564 9,406 6,800 6,556 8,192 -25%

Asbestos CuYd 300 60 ., 80 40 40 0%

Rad Sewage Sludge Gal 0 F'~Qg 48,506 60,000 31,534 0 100%

Shaded areas reflect established baselincs to evaluate P2 accomplishments.

The 5% annual reduction goals were achieved for two of the five waste categories including hazardous waste (78%), and used oil (6%). Due to the six months of extended plant outages in 1997, liquid industrial waste, low level radioactive waste and general trash generation increased from 1996 levels.

The significant hazardous waste reductions were largely due to the reclassification of lighting waste and batteries as universal wastes. However, when these waste streams are removed from the 1996 and 1997 calculations, we still achieved a 38% reduction for the year as discussed later in Section 4.0. Used oil reductions occurred due to better container management and daily review of used oil generation.

In addition to the standard categories that were reduced, the elimination of 112,000 gallons of radioactive sewage sludge also resulted in savings of at least $ 320,000.00 in 1997. Reductions in costly radioactive wastes include substantial decreases in both mixed waste and radioactive used oil.

The low level radioactive waste reduction goal would have been met with the exception of the fibrous materials (insulation, etc.) required to be removed from both containment buildings in 1997. The liquid industrial waste reduction goal was not met due to the replacement of non-hazardous solvent in all parts cleaners throughout the plant due to the increased workload associated with the extended outages. Also, office fioor stripping solutions are no longer permitted to be discharged to'he turbine room sump and now create liquid industrial waste.

Over 400 gallons were generated in 1997.

Trash levels increased due to the increased workload associated with the extended outages.

Figure 3.1.1 1992-1997 Waste Generation 16,000

~Hazardous 14,000 ~Liquid Industrial 12,000

~e

~Used Oil

~ t ~Low Level Rad 10,000 - 4- Trash 8 8,000 V a e ~ I r r 6,000 4,000 .

2,000 1992 1993 1995 1996 Year 199'aste goals and tracking have been based on year to year comparison, which do not completely convey the significant progress we have made in the last five years. Table 3.1.2 compares the projected waste reductions from the baseline years, 5% per year, to actual reductions achieved.

Future goals may have to be adjusted to reflect the very low levels of generation we have achieved in some categories. Goals relating to specific waste streams may be more appropriate, in some cases.

Table 3.1.2 1992-1997 Projected (5%/Yr) vs. Actual Waste Reductions Waste Category Units 1992 1993 1994 1995 1996 1997 Reduction From Baseline Hazardous Ec Mixed Projected Lbs 12,326 11,678 11,029 Actual 11,155 8,962 12,975 7,594 7,338 1,622 87%

Rad 8c Clean LIW Projected Actual Gal 14,971

~g44,508 42,283 12,753 40,057 2,580 37,832 2,219 35,606 2,099 20%

95%

Rad 8c Clean Used Oil Projected Gal

~6~6] 9,362 8,870 8,377 15%

Actual 2,760 6,115 9,855 6,085 6,535 6,133 38%

Low Level Rad.

Projected Actual CuFt

~38,000 7,600 7,000 7,200 3,900 6,800 1,467 6,400 1,034 6,000 1,201 25%

85%

Trash Projected Cu Yd Actual

~in 13,926 13,230 11,564 12,533 9,406 11,837 6,800 11,141 6,556 10,445 8,192 25%

41%

Shaded areas reflec established baselines to evaluate P2 accomplishments 3.2 Training and Awareness Environmental training related to pollution prevention included contractor orientation during outages. A chemical and waste management guidebook was piepared by the Environmental Affairs Section and distributed to contractor supervisors prior to the outages. The books give guidance on waste minimization, proper disposal, and proper approval and storage of chemicals.

3.3 Projects Improved pre-planning of projects continues to improve waste management efforts for projects with high generation potential. The construction of the new paint and blast shack will reduce waste and cost by reuse and recycling blast grit. A recyclable steel shot blasting system replaced the previous blast grit system and a solvent recovery system was installed to recycle solvents used for paint gun cleaning.

3.4 Chemical Use Review Board The Chemical Use Review Board (CURB) reviews all new chemicals before they are brought on site for health hazards, system compatibility, waste disposal, and fire codes. In addition, the CURB addresses issues such as chemical overstocking, alternative uses for chemicals, other facilities that may be able to use a chemical that is no longer used on site, and miscellaneous chemical control issues. These issues are conveyed to the workforce that waste reduction starts at the source.

Efforts continued to reduce the number and toxicity of chemicals used on site. Removal of excessive quantities of chemicals from storage and chemicals no longer needed on site continued with the majority of the materials shipped for beneficial reuse options. Progress was made on flammable solvent usage with the long-term goal to eliminate open-access to bulk drums of solvents including isopropanol and acetone.

3.5 Sequencing Batch Reactor The new sequencing batch reactor (SBR) allows for digester sludge to be isolated in small batches versus continuous concentration that occurred with the "package plant" digester it replaced. This lowers the concentration of the digester sludge to levels below environmental release limits for radioactivity. Over $ 320,000 in disposal cost savings were realized in 1997.

3.6 P2 Technology Transfer The Environmental Affairs Section participated in two workshops to present P2 information in 1997. These included: 1) presenting,"Mixed Waste Prevention through Chemical Control Programs: Chemical Use Review Board" at the Electric Power Research Institute's (EPRI)

International Low-Level Waste Conference in Providence, Rhode Island, and 2) serving as industrial table facilitator at the annual Michigan Pollution Prevention Roundtable in Lansing, Michigan.

4.0 HAZARDOUS AND MIXEDWASTE 4.1 General Description Total hazardous waste decreased significantly (78%) in 1997 primarily due to the reclassification of lighting waste as a universal waste. However, when hazardous waste totals are adjusted to account for the 4,186 pounds of lighting waste, there is still a 38% decrease in hazardous waste for 1997 from 1996 levels.

The most significant decreases were paint (50%), out-of-spec (OOS) / expired materials (85%),

and lead-contaminated clothing (100%). The changes in the firing range to upgrade the bullet

and debris collection system were directly responsible for the reductions in lead-contaminated clothing and debris from 1996 levels. Better chemical control and completion of the major chemical inventory reduction in 1996 also resulted in OOS waste reduction.

Flammable solvent contamination of a parts washer was responsible for the largest quantity of hazardous waste. Since a solvent contamination incident in March 1997, hazardous waste generation has remained under the conditionally exempt limit of 100 kg per month and a change in generator status may occur in the near future.

Hazardous waste management costs continued their decline in 1997 to an estimated $ 16,000

&om the $ 63,000 spent in 1996. The substantial reduction was due to the overall decrease in generation as well as specific reductions in mixed waste; 563 pounds to 27 pounds in 1997.

With no mixed waste being shipped off site during 1997, a significant cost saving was achieved.

The current cost of handling mixed waste is approximately $ 10,000 per shipment.

Table 4.1.1 1992-1997 Hazardous and Mixed Waste Generation and Costs Baseline (BL) Accum. %in 1992 1993 1994 1995 1996 1997 Savings 1996/1997 Hazardous (lbs) 7494 8,095 7,383 6,775 1,595 $ 21/21 76%

Mixed Waste (lbs)

Hazardous Sc Mixed (lbs)

II~I 11,155 867 8,962 617 211 7,594 563 7,338 27 1,622

$ 7,132

$ 16,990 95%

78%

Management Costs (S) $ 126327 $ 102,381 $ 70,585 $ 63,117 $ 15,946 $ 88,537 75%

Avoided Costs (S) $0 $ 76,167 $ 73,123 $ 93,620 $ 99,176 $ 125,457 $ 467,543 Shaded areas reflect established baselines to evaluate P2 accomplishments Figure 4.1.1 1992-1997 Mixed and Hazardous Waste G eneration 14,000 CIM ixed 12,000 mH azardous 10,000 8,000 6,000 4,000 2,000 0

1992 1993 1994 1995 1996 1997 Year

4.2 Flammable Solvents Solvent contamination of oil and non-hazardous solvents continues to be an issue with 25% of the total hazardous waste generation being caused by isopropanol contamination of non-hazardous parts washer solvent. This is similar to previous years when freon contamination of oil created considerable quantities of hazardous waste. Continued efforts to eliminate employee access and use of bulk solvents (isopropanol and acetone) are being pursued to resolve the issue.

Flammable solvent generation in 1997 increased by more than 100% from 1996 levels due to two incidents where acetone and isopropanol contaminated used oil and a non-hazardous EPA-2000 parts washer. One incident occurred in the screenhouse during traveling water screen maintenance and the other incident occurred performing turbine work.

Flammable solvent management costs remained the same as last year at $ 2,494. Better management of the amount of solvent sent for disposal and waste container size has enabled us to dispose more solvent at the same price.

4.3 Paint-Related Material Figure 4.3.1 1992-1997 Paint Waste Generation 700 600 0 Radioactive Paint 500 a Paint 4oo-300 200 .

100 0

1992 1993 1994 1995 1996 1997 Year Waste paint related material continues to decline due to better managerial techniques such as using scales to weigh out portions of paint kits instead of mixing entire kits (use only what you need concept). In addition, expired nuclear shelf life coatings were at other AEP fossil facilities.

4.4 Laboratory Solvent and Oil Figure 4.4.1 1992-1997 Freon~ntaminated Oil Generation 500 400 I Radioactive Freon 8 Ol 0 freon 8 QI XO gg 200

+ 100.

0 1997 Year Freon contaminated oil has been reduced since 1992 from 456 gallons to 55 gallons in 1997.

Educating the work force involved with Freon contamination has eliminated cross contamination of other waste streams.

Costs associated with Freon management has been reduced from $ 12,921 in 1992 to $ S,723 in 1996 to $ 1,402 in 1997.

4.5 Out-of-Specification / Expired Shelf-Life Materials Figure 4.5.1 1992-1997 OOS I Expired Material Hazardous Waste 2000 e 1500 1000 0

rx 500-1992 1993 1994 1995 1996 1997 Year

Out of Specification (OOS) material and expired shelf life chemical waste production was reduced to only 12.8 pounds in 1997. The Chemistry department has implemented tighter controls on ordering bulk volume of reagents and extending shelf life when possible to reduce this waste stream. In addition, expired nuclear grade lab reagents, paints, and storeroom supplies were shipped to other divisions of AEP for their use in non-nuclear applications.

5.0 LIQUIDINDUSTRIALWASTE 5.1 General Description Table 5.1.1 1992-1997 Liquid Industrial Waste Generation and Costs Baseline (BL) Reduced %of %in 1992 1993 1994 1995 1996 1997 From BL BL 1996 Liq. Industrial (gal) 206 Rad LIW (gal)

Rad 8r, Clean LIW 14,765 14,971 r

...2,317 4'

1,940 12,753 1,894 686 2,580 2,020 199 2)219 1,716 644 2@60 27,070 165,295 234,774 13%

2%

5%

7%

324%,

5%

g Management Costs $ 775,691 $ 54,241 $ 23,903 $ 14)310 $ 9)804 $ 256,312 4% 31%

Avoided Costs 0 ($ 509+75) $ 211/75 $ 242@ 13 $ 251/06 $ 256@12 $ 452,631 Shaded areas reflect established baselines to evaluate P2 accomplishments Figure 5.1.1 19924997 Uquid Industrial Waste Generation 50,000 GRad UW 40,000 G LIW c0 30,000 g 20,000 10,000 Liquid industrial waste (LIW) generation increased in 1997 due in part to replacing non-hazardous solvent in all part washers. This represents an increase from 1996 when no parts washer solvent was replaced. In addition, office building stripper was diverted from being discharged to the Turbine Room Sump and now is disposed as LIW increasing the volume by approximately 500 gallons.

10

Although the amount of LIW increased in 1997, the cost to dispose of the normally expensive radioactive LIW decreased due to the plant's ability to use the BTU rich non-hazardous solvent as a fuel source in our heating boiler when CAA fuel specifications are met.

Figure K2,1 1992-1997 800 C

g 600 400 5.2 Non-Hazardous Solvent Non-hazardous solvent generation increased as stated earlier in Section 5.1 due to increased outage duration and parts washer use.

5.3 Oily Water Figure 5.3.1 1993-1997 Oily Water Generation 2,500 2,000 1,500 1,000 500 1993 1994 1995 1996 1997 Year Oily water generation continues to decrease from 1994. OiVwater separation techniques have contributed to the elimination of much of our oily water waste. The use of an oiVwater separator installed on the unit one feed pump eliminated a large amount of oily water generation from a 11

continuous leak. Skimming oil and oil removal techniques continue to be applied in order to reduce the amount of oily water waste generation.

6.0 Used Oil 6.1 General Description Used oil generation has decreased 62% from the baseline year of 1994 as depicted in the Table 6.1.1 and Figure 6.1.1.

The cost of management of the used oil has reduced by $ 28, 742 from $ 61,257 in the year 1994.

There was a 14% cost reduction 1997 from 1996.

Table 6.1.1 1992-1997 Used Oil Generation and Costs Baseline (BL) %Reduction in 1992 1993 1994 1995 1996 1997 1997 Used Oil 2,760 3,860 5,040 5,050 4,915 3%

Rad. Used Oil 2,255 1,045 1,485 1,090 27%

Rad/Clean Used Oil 2,760 6,115 I 6,085 6,535 6,005 8%

Management Costs $ 11,969 $ 41,631 $ 33,267 $ 37,920 $32/15 14%

Avoided Costs $ 27,990 $ 23,337 $ 28 742 Shaded areas reflect established basclines to eva! uate P2 accomplishments t'

Re d ucioninuse i generation in 1997 was accomplished by implementation of an aggressive d oil leak control and repair program. Plant management established a zero leak philosop y an e results were seen in both radioactive and non-radioactive oil generations. Environmental performed daily reviews of ongoing work where oil generation could occur to ensure reuse of t e oil where possible. In addition, Preventative Maintenance Engineering effectively save generating radioactive Reactor Coolant Pump used oil by using an innovative filtering technique extending the life of the oil for another 18 month cycle.

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Figure 6.1.1 1992-1997 Used Oil Generation 12,000 10,000 .

co 8,000.

C 6,000 4,000 2,000 0

1993 1996 Year 6.2 Used Lubricating Oil Used oil generation increased slightly in 1997 due to the extended outage and associated work activities performed. However, the increase was limited due to a new program used to store and reuse lubricating oil. The use of 275-gallon intermediate bulk containers was implemented to store oil while maintenance is performed on various systems. The containers are specific to a designated system and can be sealed and stored for reuse when needed.

Figure 6.2.1 1992-1997 Lubricating Oil Generation 7,000 6,000 5,000 4,000 m 3,000 2,000-1,000 0

1992 1993 1994 1995 1996 1997 Year 13

6.3 Electro-Hydraulic Control (EHC) Fluid The use of Electro-Hydraulic Control (EHC) fluid was also reduced from about 900 gallons in the year 1994 to 165 gallons in the year 1997. The plant uses approximately 4,000 gallons of synthetic, phosphate-based oil for turbine valve control.

All used EHC fiuid is recycled through a supplier-approved vendor. The majority of EHC fluid is generated during outages when the fluid is removed and storage tanks and filters are inspected and cleaned. The value of the recycled fluid normally offsets transportation costs to the recycler.

The use of the new Flexsorb filtration system also decreased the generation of EHC fluid in 1997 by extending the fiuid's life.

Figure 6.3.1 1992-1997 EMC Fluid Generation 1000 g 500 U

1992 1993 1994 1995 1996 1997 Year 6.4 Radioactive Oil Radioactive used oil was also reduced 40% from the baseline 2,750 gallons to 1,660 gallons in 1997. There was a 27% reduction from 1996 to 1997. Most of the radioactive used oil came from. reactor coolant pump oil change outs, component cooling water pump work, and the restricted area oil collection drum. The engineering oil program optimized the reactor coolant pump oil as previously discussed in 1997.

All radioactive used oil is added to the plant heating boiler fuel oil tanks and burned for energy recovery. The oil is tested to ensure it meets used oil specifications and air permit limits prior to incineration.

14

Figure 6.4.1 1993-1997 Radioactive Used Oil Generation I 3,000 2,500 2,000-

~

o 1 500 (g 1,000 .

500 ~

0-I 1993 1994 1995 1996 1997 I Year I 7.0 LOW LEVEL RADIOACTIVEWASTE 7.1 General Description I Table 7.1.1 1992-1997 Low Level Radioactive Waste Generation and Costs Baseline (BL) Baseline  % Of % In I Volume (Cu.Ft) .

1992 1993 7,000 1994 3,900 1995 1,467 1996 1,034 1997* <<<<<<ion BL 1997 1,201 6799 15% -17%

Cost (Thousands) $ 4,144 $ 2,449 $ 1,118 $ 881 $ 1,023 $ 3665 22% -17%

Avoided Costs $0 $ 544 $ 2,239 $ 3,570 $ 3,807 $ 3,665 $ 13,825

~86,000 pounds of generated DAW was adjusted using 71.6 lbs/fO, which was used in 1996.

Shaded areas reflect established baselines to evaluate P2 accomplishments 15

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Figure 7.1.1 19924997 Low Level Radioactive Waste Generation 10,000 8,000 .

6,000 O

4,000 .

O 2,000 ~

I 1993 Year I Low level radioactive waste (LLW) generation increased slightly in 1997 from 1996 levels.

However, levels showed an S5% reduction from 1992 baseline levels of 8000 cubic feet.

Increased outage length and insulation removal identified in the Architect and Engineering (A &

E) inspection increased LLW generation in 1997. A combination of volume reduction I technologies, including source reduction, contributed to these continued low levels of generation.

Source reduction efforts have included replacing disposable items with washable bags, clothing and tarps. Wooden scaffolding has been replaced with metal scaffolding since radioactively contaminated wood cannot be effectively contaminated.

Radioactive low-level wastes are segregated by the Cook Plant Radioactive Materials control section into various categories to optimize management options. Categories have included reusable materials, incinerable trash, metal meltable (scrap metal), compactable, and radioactively clean (Green is clean) materials. Most disposal costs for low level radioactive wastes have historically been based on volume. Off-site incineration, supercompaction, and additional sorting have been used to reduce these volumes as much as possible to reduce cost.

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I 8.0 BULKWASTES 8.1 Trash Trash generation in 1997 increased 25% from 1996 levels. This increased waste generation is due to the extended outages and work scope increase performed in response to the NRC A & E inspection. Overall, trash generation was reduced by 59% from the baseline year in 1992.

Another contributing factor to the increase in trash was the amount of zebra mussels that had to be land filled as a result of forebay cleaning and traveling water screen impingement.

Figure 8.1.1 1992-1997 Trash Generation 16,000 14,000 12,000 ~

10,000 .

o 8,000-6,000 O 4ppp .

2,000-0 1992 1993 1994 1995 1996 1997 Year Table S.1.1 1992-1997 Trash Generation and Costs Baseline (BL) Reduced  % of % in 1992 1993 1994 1995 1996 1997 From BL BL 1997 Trash (Cu. Yds.) .' 11,564 9,406 6,800 6,556 8,192 5,734 59% -25%

Management Cost '107,545 $ 87,476 $ 63,240 $ 60,971 $ 75,871 $ 53,641 5&% -24%

Avoided Costs $0 $ 21,967 $ 42,036 $ 66,272 $ 68,541 $ 53,641 $ 252,457 Shaded areas reflect established baselines to evaluate P2 accomplishments 17

S.2 Radioactive Sewage Sludge The new sequencing batch reactor (SBR) allows for digester sludge to be isolated in small batches which are not contaminated with radioactivity that was generated by the continuous concentration technique used in the old "package plant" it replaced.

Figure 8.2.1 1993-1997 Radioactive Sewage Sludge Generation 70,000 60,000 50,000 ~

40,000 ~

30,000 L 20,000 ~

i 10,000 0

gi 1993 1994 1995 1996 1997 Year t Table 8.2.1 1993-1997 Radioactive Sewage Sludge Generation and Management Costs 1993 1994 1995 1996 1997 Rad Sewage Sludge Volume (gal) 48,506 60,000 31,534 0 Management Costs $ 189,304 $ 199,670 $ 168,587 0 Avoided Costs $ 320,320 Shaded areas reflect established baselines to evaluate P2 accomplishments S.3 Asbestos Asbestos waste generation remained constant for 1997 from 1996 levels. However, there was an 81% reduction from the 1992 baseline figures. Generation is primarily dependent on abatement efforts planned for the outage length and,equipment scheduled to be worked.

1992 1993 1994 1995 1996 1997 Volume (Cu Yds) 300 60 Q~~.~i~) 80 40 40 Management Costs $ 10,452 $ 1,640 $ 1,640 $ 2,900 $ 1,900 $ 1,900 18

Figure 8.3.1 1992-1997 Asbestos Waste Generation 400 300 ~

o 200 .

oD 100 .

0 1992 1993 1994 1995 1996 1997 Year Asbestos containing material (ACM) insulation is being replaced with calcium silicate material when the asbestos is damaged or removed for maintenance activities.

8.4 Empty Drums There was a 32% reduction in empty drum generation from 1996. This effort was led by the Environmental Affairs Section's drum management program and reuseable tote program for lubricating oils discussed earlier in this report. Over $ 30,000 was saved by reducing the amount of drums being issued and then discarded after use by this program.

Table 8.4.1 1993-1997 Empty Steel Drums and Management Costs Reduced  % From  % in From BL 1993 1994 1995 1996 1997 BL 1996/1997 Total ¹ of Barrels 351 '.'> 348 265 179 328 35% 32%

Management Cost $ 35,802 $ 35,496 $ 27,030 $ 18,258 $ 33,456 35% 32%

Avoided Costs $0 $0 $ 16,218 $ 24,684 $ 33,456 $ 74358 Another major reduction in empty drum generation resulted from the purchase of intermediate-bulk container by Engineering and Environmental Affairs for system and equipment fluid draining during refueling outages, maintenance and inspections. The use and reuse of intermediate-bulk containers has reduced empty drum waste by up to 75%. Bulk tanks have also been used to successfully replace drums during ice condenser system ethylene glycol draining, saving up to 40 drums per glycol outage.

A new drum management procedure was implemented by Environmental Affairs. The procedure developed to better control issuance and reuse of drums. The program has coordinated job planning; labeling, drum issue, and control of drained fluids to minimize waste generation. The procedure also established for reusing empty waste drums, which reduced usage by 15% in 1997.

19

9.0 Universal Waste The state of Michigan implemented the federal universal waste regulations in late 1996 and included lead acid batteries, dry cell batteries, nickel-cadmium batteries, lighting waste and mercury as universal wastes. All this waste is sent to a recycle vendor for recycling.

9.1 Lead-Acid Batteries Table 9.1.1 1995-1997 Lead-Acid Battery Waste Generation 1995 1996 1997 Lead-Acid Batteries 12,000 16,810 64,900 In 1997, several battery replacement projects took place at the Cook Plant. We replaced the U-2 CD batteries (42,900 lbs.) for the first time in the plant's history. We also replaced 20,000 lbs.

of emergency lighting batteries with a longer life battery supplied free by the manufacturer due to short lived battery incidents.

Figure 9.1.1 Lead-Acid Battery Recyciing 80,000 4 60,000 g 40,000.

20,000 0

1995 1996 1997

. Year Allthe lead acid batteries were shipped directly to Exide for recycling. Lead acid battery waste is expected to decline in future years, due to longer life battery installation.

Reusable plastic battery boxes have been purchased to provide safe collection and shipping containers. The boxes also provide spill containment in the event of battery leaks. The boxes are returned after each shipment and reused.

20

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I

9.2 Dry Cell Batteries Table 9.2.1 1994-1997 Dry Cell Battery Waste Generation

%of 1994 1995 1996 1997 1997 Battery Waste 161 1,206 933 2,665 285%

Figure 9.2.1 1994-1997 Dry Cell Battery Generation 3,000 2,500 2,000 1,500 1,000 500 0

1994 1995 1996 1997 Year The 1997 increase (285%) in dry cell battery waste is due to accumulation of five months of 1996 generation being added to this total. The shipment of dry cells was delayed for cost saving reasons to enhance two shipments to one. In addition, the 1997 increased outage time and workload added to the waste generation.

9.3 Lighting Waste Figure 9.3.1 1994-1997 Lighting Waste Generation 7,000 6,000 5,000 4,000 o 3,000 2,000

',000 0

1994 1995 1996 1997 Year 21

Generation of lighting waste now falls under Universal waste category. Lighting waste includes the waste fluorescent light lamps, incandescent light lamps and High Intensity Discharge (HID) lamps. Efforts are in progress to reduce the lighting waste by replacing them with long life lamps, especially in the radiologically controlled areas.

9.4 Nickel-Cadmium batteries Nickel-Cadmium batteries were also categorized under universal waste rule. Approximately 291 pounds of Nickel-Cadmium battery waste was generated in the year 1997. This generation was primarily due to the elimination of old instrumentation that was powered by Nickel Cadmium batteries.

9.5 Lithium batteries Lithium battery waste was also counted under universal waste since they are recyclable. Only 23 pounds of Lithium battery waste was generated in the year 1997.

10.0, Recyclable Material 10.1 Scrap Metal Pouods ~

Table 10.1.1 Summary of Scrap Metal Generation 1995 1996 229,937 1997 205,864

% from % from 1997 10%

Baseline 20%

Shaded areas reflect established baselines to evaluate P2 accomplishments Figure 10.1.1 1995-1997 Scrap Metal Generation 300,000 250,000 200,000 150,000 O

100,000 50,000 0

1995 1996 1997 Year 22

I l

Scrap metal generation decreased by 10% in 1997 from 1996 levels due to less waste metal production in 1997. Scrap metal waste has been reduced from 258,516 pounds in 1995 to 205,864 pounds in 1997. Scrap metal is segregated by metal type, such as electrical cable and stainless steel, in dumpsters set by the scrap metal vendor. Pieces with obvious value are not scrapped. Lead sheets and brass shell casings are still sold for reuse.

10.2 Paper Products Table 10.2.1 1994-1997 Quarterly Paper Recycling Summary (Pounds) 1994 1995 1996 1997 Recycled Paper 26,165 230,709 220,881 179,475 Recycled Paper Used 104,398 191,915 205,394

% Recycled Products 83% 87% 88%

Total Cost of Purchased Recycleables $ 94,452 American Electric Power is committed to the Environmental Protection Agency WasteWi$ e program and encourages paper recycling and use of recycled paper products. Table 10.2.1 shows the amount of paper products recycled in the year 1997. It also shows the amount of recycled paper products purchased by the company for use on site.

The AEP Nuclear Generation Group uses a local paper recycler that employs disabled individuals for the collection, sorting and shipping of our paper. Separate recycle bins have been established for cardboard collection and each office has a separate container for collecting the paper. Employees are encouraged to print double-sided copies and the increased use and distribution of electronic files is having long-term benefits for paper reduction.

10.3 Scrap Tires and Rubber During 1997 scrap rubber levels increased due to a cleanup of the site and several tires were collected and sent off for recycling. This project will continue in 1998. One of the largest sources of rubber, reactor press ray seals, which at one time had a shelf life has now been eliminated. With no shelf life there will be no more scrap rubber Rom these seals.

Approximately 700 pounds of rubber was recycled in 1997.

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APPENDIX V ANNUAL REPORT:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1997

DONALD C. COOK NUCLEAR PLANT UPSETS 1 &2 OPERATIONAL RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM 1997 ANNUAL REPORT JANUARY 1 to DECEMBER 31, 1997 Prepared by Indiana Michigan Power Company aIld Teledyne Brown Engineering April 15, 1998

TABLE OF CONTENTS SECTION TITLE PAGE S ummary o ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ o o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ . 5 Introduction .................... ~ ~ ~ ~ 7 II. Sampling and Analysis Program......................... 10 III. Summary and Discussion of 1997 Analytical Results ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 9 A. Airborne Particulates.... 20 B. Airborne Iodine ....... 22 C Direct Radiation - TLDs............... 23 D Surface Water .................................... 23 E. Groundwater......... 25 F Drinking Water..................................... 25 G. Sediment . 29 H Milk ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 3I I. Broadleaf Vegetation ................................ 31 J Ml o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 31 K Food Products ...................................... 32 IV. Conclusions . ~ ~ ~ ~ ~ ~ ~ o ~ 33 V. R eferences ..........:................................... 37

TABLE OF CONTENTS (Cont)

APPENDICES APPENDIX A - Radiological Environmental Monitoring.............. 39 Program Summary - 1997 APPENDIX B - Data Tables .'.............................'.......... 44 APPENDIX C - Analytical Procedures Synopsis..................-...... 70 APPENDIX D - Summary of EPA Interlaboratory Comparisons ........... 81 APPENDIX E - REMP Sampling and Analytical Exceptions............. 102 APPENDIX F - Land Use Census ............... 106 APPENDIX G - Summary of the Preoperational Radiological............ 113 Monitoring Program APPENDIX H- Summary of the Spike and Blank Sample Program........ 117 APPENDIX I - TLD Quality Control Program .................. 130

I I

TABLE OF CONTENTS (Cont)

LIST OF FIGURES Onsite REMP Monitoring Locations ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ I6 Offsite REMP Monitoring Locations ~ ~ ~ ~ ~ ~ ~ ~ I7 Fish Sampling Locations .............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I8 Milk Farm Survey Table .. 109 Milk Farm Survey Map...................................... 110 Residential Survey Map ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o III Residental Land Use Survey Table 112 LIST OF TRENDING GRAPHS Average Monthly Gross Beta in Air Particulates................ 21 Direct Radiation - Quarterly TLD's ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 24 Tritium in Groundwater ..................................... 26 Tritium in Drinking Water ...................... . 30 EPA Cross Check Program . ~ ~ ~ ~ ~ ~ ~ 87 Quality Control TLDs ............... 132

LIST OF TABLES TITLE PAGE B-1 Concentrations of Gross Beta Emitters in Weekly................... 45 Airborne Particulates B-2 Concentrations of Gamma Emitters in Quarterly.................... 49 Composites of Airborne Particulate Samples B-3 Concentrations of Iodine-131 in Weekly Air Cartridge............... 51 Samples B-4 Direct Radiation Measurements - Quarterly TLD Results............. 55 I as Concentrations of Iodine, Tritium and Gamma in Surface Water Emitters............. 56 Concentrations of Tritium and Gamma Emitters in Groundwater

.............. 58 B-7 Concentrations of Gross Beta, Iodine, Tritium and.................. 61 Gamma Emitters in Drinking Water B-8 Concentrations of Gamma Emitters in Sediment ................... 63 B-9 Concentrations of Iodine and Gamma Emitters in Milk ... 64 B-10 Concentrations of Iodine and Gamma Emitters in . ~ ~ o ~ ~ ~ ~ ~ 65 Broadleaf Vegetation in Lieu of Milk B-11 Concentrations of Gamma Emitters in Fish ........ - - - ~ - . - - ~ - - ~ - - ~ - 66 B-12 Concentrations of Gamma Emitters in Food/Vegetation ............. 67 B-13 Gamma Spec LLDs and Reporting Levels ................. 68 iv

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INDIANAMICHIGAN POWER COMPANY DONALD C. COOK POWER NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM

SUMMARY

This report summarizes the collection and analysis of various environmental sample media in 1997 for the Radiological Environmen-tal 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 and sediments from Lake Michigan, drinking water, and food products, either did not detect any radioactivity or measured only naturally occurring radionuclides at normal background levels.

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 man.

I. INTRODUCTION I

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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 II, Sampling and Analysis Program. This report represents the Annual Radiological Environmental Operating Report for Units 1 and 2 of the Donald C. Cook Nuclear Plant for the operating period from January 1, 1997 through December 31, 1997.

A. The Donald C. Cook Nuclear Plant of American Electric 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:

l. 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.

During 1997 the following changes were made to the Offsite Dose Calculation Manual (ODCM)

The following changes became effective on Ol/24/97 and included:

Deleted Technical Specification 014 revision 06 per NSRA request.

Changed compensatory sampling interval per Chemistry request.

Added 25% grace period for surveillance requirements.

Clarified need for compensatory sampling of ESW system when respective radiation monitors are inoperable unless'the containment spray heat exchangers are in service, since these are only for post LOCA leak detection and have no associated trip functions.

Added note on attachment for determination of start-up flash tank flow rate to improve documentation and changed this flow rate based on estimated steam generator blowdown flow vs. DRY value position.

Changes to the ODCM made effective on 10/15/97 included:

Incorporated new Eberline liquid radiation monitors that replaced Westinghouse monitors.

Added table allowing plant to use RMS readings in lieu of sampling gland seal exhaust since operational data indicates routine sampling is non-productive.

Revised attachments to reflect RFC 3076 changes.

Changes to the ODCM made effective on 10/30/97 included:

Added clarification to attachment 3.4 for purging or venting.

II. SAMPLING AND ANALYSIS PROGRAM 10

II. SAMPLINGAND ANALYSIS PROGRAM Table 1 summarizes the sampling and analysis program for the Donald C. Cook Nuclear Plant for 1997. 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.

11

T DONALD C. COOK NUCLEAR PLANT- 1997 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Direction De rees Fre uenc Anal is/Fre uenc Environmental (TLD's)

ONS-I (T-01) 1945 ft. 18o Quarterly Direct Radiation/Quarterly

. ONS-2 (T-02) 2338 ft. 48o ONS-3 (T-03) 2407 ft.

ONS-4 (T-04) 1852 It. 90'18'89'100 ONS-5 (T-05) 1895 ft.

ONS-6 (T-06) 1917 ft.

(T-07) 2103 It. 36o (T-08) 2208 ft. 82'49o (T-09) 1368 ft.

(T-10) 1390 ft. 1270 (T-1 1) 1969 ft. I lo (T-12) 2292 63o New Buffalo (NBF) 15.6 mi SSW South Bend (SBN) 26.2 mi SE Dowagiac (DOW) 24.3 mi ENE Coloma (COL) 189 mi NNE Intersection of Red Arrow Hwy. & Marquette (OFT- I) 4.5 mi NE Woods Rd, Pole OB294-44 Stevensville Substation (OFT-2) 3.6 mi NE Pole IIB296-13 (OFT-3) 5.1 mi NE Pole ffB350-72 (OFT-4) 4.1 mi E Intersection of Shawnee & Cleveland, Pole (OFT-5) 42 mi ESE IfB387-32 Snow Rd., East of Holden Rd., (OFT-6) 4.9 mi SE ffB426-1 Bridgman Substation (OFT-7) 25 mi S California Rd.. Pole IIB424-20 (OFT-8) 4.0 mi S Ruggles Rd., Pole B369-214 (OFT-9) 44 mi ESE Intersection of Red Arrow Hwy., & (OFT-10) 3.8 mi S Hildebrant Rd.,Pole ffB422-152 Intersection of Snow Rd. & Baldwin Rd., (OFT -11) 38 mi Pole ffB423-12

TABL t.l DONALD C. COOK NUCLEAR PLANT- 1997 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Direction De rees Fre enc Anal Is/Fre enc Air Charcoal/Particulates ONS-I (A- I) 1945 ft. 180 Weekly Gross Beta/Weekly ONS-2 (A-2) 2338 ft. I-131/Weekly ONS-3 (A-3) 2407 It Gamma Isotopic/

ONS-4 (A-4) 1852 ft. Quarterly Composite ONS-5 (A-5) 1895 ft.

ONS-6 (A-6) 1917 ft.

New Buffalo (NBF) 15.6 mi SSW 48'0'18'89'10'1'3'07 South Bend (SBN) 26.2 mi SE Dowagiac (DOW) 24.3 mi ENE Coloma (COL) 18.9 mi NNE Groundwater Onsite (W- I) 1969 ft. Quarterly Gamma Isotopic/Quarterly Onsite (W-2) 2292 ft. Tritium/Quarterly Onsite (W-3) 3279 ft.

Onsite (W-4) 418 ft. 301'90o Onsite (W-5) 404 ft.

Onsite (W-6) 424 ft. 2730 Onsite (W-7) 1895 ft. 189o Onsite (W-8) 1279 ft.

Onsite (W-9) 1447 ft. 53'2'29o Onsite (W-10) 4216 ft.

Onsite (W- 1 1) 3206 ft. 1530 Onsite (W-12) 2631 It. 162'820 Onsite (W-13) 2152 ft.

Onsite (W-14) 1780 ft. 1640 Steam Generator Groundwater Steam Generator Storage Facility (SG-1) 08 mi Quarterly Gross Beta/Quarterly Steam Generator Storage Facility (SG-2) 0.7 mi 95'2'3'2o Gross Alpha/Quarterly Steam Generator Storage Facility (SG-4) 07 mi Gamma Isotopic/Quarterly.

Steam Generator Storage Facility (SG-5) 07 mi

TABL nt.)

DONALD C. COOK NUCLEAR PLANT- 1997 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Direction De rees Fre uenc Drinkin Water St. Joseph Public Intake (STJ) 9.0 mi NE Daily Gross Beta/14 Day Composite Gamma Isotopic/14 Day Composite 1-131/14 Day Composite Lake Township Public Intake Station (LTW) 0.4 mi Tritium/Quarterly Composite Surface Water Condenser Circulating Water Intake SWL-1 Intake Daily Gamma Isotopic/Monthly Lake Michigan Shoreline SWL-2 500 ft. S Composite Lake Michigan Shoreline SWL-3 500 ft. N Tritium/Quarterly Composite

~Sediment Lake Michigan Shoreline SI 2 500 ft. S Lake Michigan Shoreline SL-3 500 ft. N Semi-annually Gamma Isotopic/Semi-Annually Milk-Indicator (a) 1-131/Sample Milk-Back ound (a)

Broadleaf Ve etation (a) 3 Indicator Samples Within 8 miles of plant Highest D/Q Land Sector . Monthly when Gamma Isotopic/Monthly 1 Control Sample 15-25 miles distant Less prevalent wind direction available 1-131/Monthly (a) No milk samples were obtained ln 1997 as 2 of 3 Indicator farms dropped from program at the end of 1995 and no replacements have been found.

Broadleaf vegetation samples were obtained In lieu of milk In 1997.

TABL ont.)

DONALD C. COOK NUCLEAR PLANT- 1997 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Direction De rees Fre uenc Anal s/ uenc

~Fish Lake Michigan ONS-N .3 mi N 2/year Gamma Isotopic/

Lake Michigan ONS-S .4 mf S 2 per year Lake Michigan OFS-N 3.5mi N Lake Michigan OFS-S 5.0 mi S Gra /Broadleaf Nearest sample to Plant Sector D At time of harvest Gamma Isotopic at in highest D/Q land sector time of harvest.

containing media.

Gra es In a land sector containing grapes Sector K At time of harvest Gamma Isotopic at approximately 20 miles from the Plant time of harvest.

in one of the less prevalent D/Q land sectors.

Composite samples of Drinking and Surface water shall be collected at least daily.

ParUculate sample filters should be analyzed for gross beta activity 24 or more hours following Alter 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 performed on the individual samples.

Please note the following defenitions:

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

Figure 1 O~-site REMP Morlito<~ln err/< ~

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-4 SG-5) REMP Nonn T/S Groundsoter r Hells e SWL-I, 2,: 2 3: Surfoce u Woter Somp ng SL-2),3)I S e diment Sompling Iin Stotions o

Figure 2 LEGEND OFFSITE REHP HONITORIHG LOCATIOH ckor ovnd Alr/TLD locotlons Ite TLO (scot(one Orovnd NI(k Fores lnO Woter locot(ons lcotor H(lk Fores COLOMA SUBSTAT ION BACKGROUND AIR / TI.O HMKI (COL(

cao BEH'ION HARBOR

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'cess a~ DOWAGIAC 5UBSTATIOH BACKGROUND TLO OFT B TLO OFT BI SODUS AIR / ILD (DOWI II TLD OFT B2 5'IEYENSYILLE TLP OF T B4 1 TLD OFT BR LLAIRE TLD OFT B5 Dr Co COOK LAKE TOWNSHIP TLW ~Q ICE I

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III.

SUMMARY

AND DISCUSSION OF 1997 ANALYTICALRESULTS 19

III.

SUMMARY

AND DISCUSSION OF 1997 ANALYTICALRESULTS A discussion of the data from the radiological analyses of environmental media collected during the report period is provided in this section. Analyses of samples for 1997'were analyzed by Teledyne Brown Engineering, Inc. (TI) in Westwood, New Jersey. The procedures and specifications followed at Teledyne Brown Engineering are in accordance with the Teledyne Brown Engineering Quality Assurance Manual and are A

M explained in the Teledyne Brown Engineering Analytical Procedures.

synopsis of analytical procedures used for the environmental samples are proved in Appendix C. In addition to internal quality control measures L performed by Teledyne, the labo'ratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program, Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in t environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix D.

C Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. 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.

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 1 on. January 12, 1975. A brief summary of the preoperational program is found in Appendix G.

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 20

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Trending Graph - 1 AVERAGE MONTHLYGROSS BETA IN AIR PARTICULATES 40 35

a. 30 O

25 O

Q 20 0

0 jf

$ 9d'4 D

0 ~l O 15 6

0 10 5

1/89 7/89 1/90 7/90 1/91 7$ 1 1/92 7$ 2 1/93 7/93 1 $ 4 7$ 4 1/95 7$ 5 1/96 7/96 1/97 7/97 Indicators ~ .-O- -" Controls

gross beta activities are presented in Table B-l. 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 0.019 pCi/m with a range of individual values between 0.008 and 0.048 pCi/m. The average gross beta concentration of the four control locations was 0.019 pCi/m~ with a range between 0.008. and 0.051 pCi/m~. 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 particulate filters in 1997 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 0.126 pCi/m~ and the values ranged from 0.086 to 0.174 pCi/m~. The average concentration for the indicator locations was 0.125 pCi/m with a range of 0.087 to 0.175 pCi/m~. These values are typical of beryllium-7 measured at various locations throughout the United States. Naturally occurring potassium-40 was measured in three of the twenty-four indicator quarterly composites with an. average concentration of 0.004 pCi/m~ and a range of 0.003 to 0.007 pCi/m.

Potassium-40 was measured in six of the sixteen control quarterly composites with a concentration of 0.004 pCi/m and a range of 0.003 to 0.006 pCi/m~. No other gamma emitting radioactivity was detected.

B. Air'borne 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 22

below the lower level of detection of 0.07 pCi/m~ with no positive activity detected.

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 rec'ord exposure from all of the'se 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 Acid exposure period for response to a known,.exposure and for transit exposure) are presented in Table 8-4. 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 4.51 mR/standard month with a range of 3.1 to 6.3 mR/standard month.

The annual accumulation of indicator samples had a measurement of 4.25 mR/standard month with a range of 2.7 to 6.8 mR/standard month. The 1997 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.

Surface Water A 125 milliliter surface water sample is collected from the intake forebay and from two shoreline locations, all within 0.3 mile of the two reactors and were composited daily over a monthly period.

The thirty-two samples were analyzed for iodine-131 by the radiochemical technique described on page 76. All results were less than the lower limit of detection of 1 pCi/1. The quarterly composite was analyzed for tritium by liquid scintillation method described on page 75. Results are presented in Table 8-5. Tritium was detected in 23

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W W M M M % M M M Trending Graph - 2 DIRECT RADIATION- QUARTERLYTLD RESULTS 01/90 07/90 01/91 07/91 1/92 7/92 1/93 7/93 1/94 7/94 1/95 7/95 1/96 7/96 1/97 7/97 ts TLD Controls TLD Indicators

5 of the 12 samples analyzed with an average concentration of 1214 pCi/liter and a range of 200 to 4800 pCi/liter. This is higher than the 2 measurements in 1996 which had an average concentration of 520 pCi/liter. During the preoperational period tritium was measured in surface water samples at concentrations of approximately 400 pCi/liter. Naturally occurring potassium-40 and cesium-137 were not measured during 1997. Naturally occurring gamma emitting isotopes were detected using gamma ray spectroscopy.

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. A two liter sample is then obtained. The samples are analyzed for gamma emitters and tritium.

The results are presented in Table B-6. Naturally occurring potassium-40 was measured in one sample with a concentration of 44.4 pCi/liter. There were no other gamma emitting isotopes measured. The groundwater wells W-4, W-5, W-6, and W-14 had measurable tritium activity throughout 1997. Tritium was measured in 16 of the 56 samples at the locations with an average concentration of 3618 pCi/liter and a range of 210 to 19000 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.

F. ~Dk W Daily samples are collected at the intake of the purification plants for St. Joseph and Lake Township. The 500 ml daily samples at each location are composited and analyzed for gross beta, iodine-131, and gamma emitters. 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.

TrendIng Graph - 3 TRITlUM IN GROUNDWATER 1980 1982 1984 1988 1988 1990 1992 1994 4$ 5 10$ 5 4$ 8 10$ 8 4$ 7 10$ 7

- ~ ~ Well-1 ~ Well-2 ~ Wells

Trending Graph - 3 (Cont.)

TRITIUM IN GROUNDWATER 10000 C

GJ 0

l O 6000 CL O

0 O

O 4000 CI O 2000 CL 1980 1982 1984 1986 1988 1990 1992 1994 4/95 1 $ 95 496 10$ 6 4)97 10)97 Well-4 -0 Well-5 Well-6 Well-7

M W W & W W W W W W Trending Graph (Cont.)

TRITIUM IN GROUNDWATER 20000 C

16MO L

0 CL 12000 0

0 O

0I 8000 4000 C

1/92 1i93 1i95 1iS7 Well 14 added to the program in 1993.

~

No sample collected January 1994.

Well-8 0 Well-9 M Well-10 ~ Well-11 l-l Well-12 -E3 Well-13 ~ Well-14

Gross beta activity was measured in all twenty-six samples from the Lake Township intake with an average concentration of 2.97 pCi/liter and a range from 2.0 to 3.9 pCi/liter. Gross beta activity was measured in all twenty-six sa'mples from the St. Joseph intake with an average concentration of 2.97 pCi/liter and a range from 1.6 to 5.6 pCi/liter. No gamma emitting isotopes or iodine-131 were detected.

Tritium was measured in one of the four samples from the Lake Township location at a concentration of 350 pCi/liter. Tritium was not measured at the St. Joseph intake location. 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 April one sample was collected from location SL-2 and SL-3. In October, only location SL-2 was sampled as location SL-3 was covered with lake water. Gamma ray spectroscopy detected naturally occurring potassium-40 in all three samples. The average potassium-40 concentration was 4613 pCi/kg (dry weight) with a range from 3190 to 6810 pCi/kg (dry weight). Thorium-228, also naturally occurring was measured in two samples with an average concentration of 478 pCi/kg (dry weight) with a range from 211 to 745 pCi/kg (dry weight). Radium-226 was measured in one sample with an activity of 614 pCi/kg (dry weight). All other gamma emitters were below the lower limits of detection.

29

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Trending Graph - 4 TRITIUM IN DRINKING NATER 2000 0$

o.

L a) 1500 O-O 1000 500 pw

+I~I~II~~

0

~

og 4f 4 C- 4 4h~W ct' pampa Cr ~

01/89 07/89 01/90 07/90 01/91 10$ 1'$ 2 10$ 2 4$ 3 10/93 4$ 4 10/94 4/95 10/95 4$ 6 10$ 6 4/97 10/97

~ ~ ~ ~ ~

0 ~~~~~ ~

Lake Township St. Joseph

H.

During 1997, the requirements of two samples from different locations was not met. The sampling of food samples was increased to offset the milk.

I. Broadleaf Ve etation Broadleaf vegetation wa's collected in lieu of milk during 1997.

Twenty-four samples were collected and results are presented in Table B-10. Naturally occurring potassium-40 was measured in the six control samples with an average concentration of 5705 pCi/kg (wet weight) and a range of 4750 to 7620 pCi/kg (wet weight). Potassium-40 was measured in the eighteen indicator samples with an average concentration of 3888 pCi/kg (wet weight) and a range of 1770 to 6010 pCi/kg (wet weight). Cosmogenically produced beryllium-7 was measured in the six control samples with an average concentration of 1835 pCi/kg (wet weight) and a range of 548 to 5430 pCi/kg (wet weight). Beryllium-7 was measured in the eighteen indicator samples with an average of 1092 pCi/kg (wet weight) and a range of 382 to 2180 pCi/kg (wet weight). Cesium-137 was not detected during 1997. Radium-226 was measured in one indicator sample at a concentration of 687 pCi/kg (wet weight). Thorium was measured in three indicator samples with an average concentration of 101 pCi/kg (wet weight) and a range of 66.6 to 138 pCi/kg (wet weight).

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-l l. Naturally occurring potassium-40 was measured in the four control samples with an average concentration of 3075 pCi/kg (wet weight) and a range of 2690 to 3820 pCi/kg (wet weight). Potassium-40 was measured in the four indicator samples with an average concentration of 2998 pCi/kg (wet weight) and a range of 2720 to 3330 pCi/kg (wet 31

weight). Cesium-137 was measured in one control fish samples with a concentration of 23.5 pCi/kg (wet weight). Cesium-137 was measured in one indicator samples with a concentration of 21.0 pCi/kg (wet weight).

K Food Products Food samples are collected annually at harvest, as near the site boundary as possible, and approximately twenty miles from the plant.

Each sample consists of 3 pounds of grapes and 3 pounds of broadleaves. There were four food samples collected during 1997 and results are presented in Table B-12. Naturally occurring potassium-40 was measured in the two control samples with an average concentration of 2790 pCi/kg (wet weight) and a range of 1960 to 3620 pCi/kg (wet weight). Potassium-40 was measured in the two indicator food samples with an average concentration of 2920 pCi/kg (wet weight) and a range of 2070 to 3770 pCi/kg (wet weight).

Cosmogenically produced beryllium-7 was measured in one indicator sample with a concentration of 3010 pCi/kg (wet weight). "Beryllium-7 was also measured in one indicator samples with a concentration of 5140 pCi/kg (wet weight). All other gamma emitters were below the lower limits of detection.'2

IV. CONCLUSIONS 33

IV. CONCLUSIONS The results of the 1997 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 1997 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 1997. No iodine-131 was detected in charcoal filters in 1997.

Thermolumine scent 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. No gamma emitters were detected during 1997. Tritium was measured in five samples. In four of the five samples the tritium concentration was at a normal background level. One sample had a tritium result of 4800 pCi/liter which is attributed to operation of the plant.

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 34

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highest concentration measured in 1997 was 19000 pCi/liter while the highest concentration measured during 1996 was 14000 pCi/liter. The increased tritium concentration is attributed to draining portions of the Component Cooling Water (CCWI system to the turbine room sump which discharges into the onsite absorption pond. Well W-14 is adjacent to the pond and monitors the aquifer at this location. Potassium-40, a naturally occurring nuclide was not observed during 1997. No other gamma emitting isotopes were detected.

Samples are collected daily at the intakes of the'drinking 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.

No iodine-131 or gamma emitting isotopes were detected. Gross beta was measured in all fifty-two samples at normal background concentrations.

Tritium was measured in one of the eight quarterly composite samples collected during 1997.

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.

Milk samples were not analyzed during 1997 due to lack of participants in the program. Broadleaf sampling was performed in lieu of milk collection in 1997. Cesium-137 was not measured in broadleaf samples during 1997. No other gamma emitting isotopes were measured in broadleaf samples in 1997.

Fish samples collected in Lake Michigan in the vicinity of the nuclear plant were analyzed by gamma ray spectroscopy. The only gamma emitting isotope measured was cesium-137 which was found in low concentrations in two samples.

35

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Food products, consisting of grapes, and broadleaf vegetation were collected and analyzed by gamma ray spectroscopy. The only gamma emitting isotopes measured during 1997 were potassium-40 and beryllium-7.

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 man.

36

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V. REFERENCES 37

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V., 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. American Electric Power, 12 PMP 6010 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, April 1974.

6. United States Nuclear Regulatory Commission, Regulatory Guide 1.4 "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

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APPENDIX A RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

39

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 50-315/50-316 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1997 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER W I M CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES MEAN (a/b) NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Air Iodine 1-131 530 -(0/318) -(0/212)

(pCI/m3)

Airborne Gross Beta 530 19.2(318/318) ONS-5 Onsitc 1895 ft. 19.9(53/53) 19.1(212/212)

Particulates (1Veekly) (7.9-48) (10-48) (8.3-51)

(1E-03 pCI/m3)

Gamma 40 Be-7 40 125(24/24) ONS-6 Onsite 1917 ft. 134(4/4) 126(16/16)

(87.4-175) (1 1 1-160) (86.3-174)

K-40 40 4.38(3/24)

(2.93-6.94)

'NS-1 Onsite 1945 ft. 6.94(l/4) 4.31(6/16)

(2.68-6.35)

Direct Radiation Gamma 107 (mR/Standard Dose 4.25(91/91) SBN 26.2 mi SE 5.28(4/4) 4.51(16/16)

Month) Quarterly (2.7-6.8) (4.4-6.3) (3.1-6.3)

(a/b) Ratio of samples with detectable activity to total number oi samples analyzed.

W SIR a

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 50-315/60-316 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1997 ANALYSIS AND NUMBER OF TOTAL NUMBER L I I NW HI EA CONIROL LOCATION NONROUTINE MEDIUM OR PATHWAY SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORTED PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS IUNIT OF MEASUREMEÃA Surface Water Gamma 32 (0/12) N/A (0/20)

(pCI/liter) '2 H-3 2600(2/4) SWL-I Intake 2600(2/4) 290(3/8)

(400-4800) (400-4800) (200-390)

Groundwater Gamma 56 (pCI/liter) 3-K-40 56 44.4(1/56) Well 44.4(1/4) -(0/0)

Th-228 56 -(0/56) N/A -(0/0)

H-3 56 3618(16/56) Well 14 1780 A.. 10850(4/4) -(0/0)

(210-19000) (1100-19000)

Drinking Water Gross Beta 52 2.97(52/52) St. Joseph 9.0 mi NE 2.97(26/26) -(0/0)

(pCi/liter) (1.6-5.6) (1.6-5.6) 4 1-131 52 -(0/52) N/A N/A -(0/0) 0 Gamma 52 -(0/52) N/A N/A -(0/0)

H-3 350(1/8) LTW 0.4 mi S 350(1/4) -(0/0)

(a/b) Ratio of samples with detectable activity to total number of samples analyzed.

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 50-315/50-316 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1997 ANALYSIS AND NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LL INDI A R W H I CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES MEAN (a/b) NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENTI PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Sediment Gamma 3 (pCi/kg dry)

K-40 3 4613(3/3) SL-3 6810(1/1) -(0/0)

(3190-6810) 0.3 mi S Cs-137 3 -(0/3) N/A -(0/0)

Ra-226 3 614(1/3) SL-2 614(1/2) -(0/0) 0.2 mi N Th-228 3 478(2/3) SL-2 478(2/2) -(0/0)

(21 1-745) 02mi N (21 1-745)

Broadleaf/ Gamma 24 Vegetation (pCi/kg wet)

Be-7 1092(18/18) Sector J 1835(6/6) 1835(6/6)

(382-2 180) (548-5430) (548-5430)

K-40 24 3888(18/18) Sector J 5705(6/6) 5705(6/6)

(1770-60 10) (4750-7620) (4750-7620)

Cs-137 24 -(0/18) N/A N/A -(0/6)

Ra-226 24 687(1/18) Sector A 687(1/24) -(0/6)

Th-228 24 101(3/18) Sector A 101(3/24) -(0/6)

(66.6-138) (66.6-138)

(a/b) Ratio of samples with detectable activity to total number of samples analyzed.

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RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 50-315/50-316 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1997 ANALYSIS AND NUMBER OF MEDIUM OR PATEAVAY TOTAL NUMBER L~ A R A N W I CONIROL LOCATION NON ROUTINE SAMPLED OF ANALYSES MEAN (a/b) NAME MEAN MEAN REPORTED PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS (UNIT OF MEASUREMENTI Gamma (pCi/kg wet)

K-40 2998(4/4) OFS-South 3415(2/2) 3075(4/4)

(2720-3330) 5.0 mi S (30 10-3820) (2690-3820)

Cs-137 21.0(1/4) OFS-South 23.5(1/2) 23. 5(1/4) 5.0 mi S Food/Vegetation Gamma (pCi/kg wet) 5140(1/2) 3010(1/2)

Be-7 5140(1/2) Sector D K-40 2920(2/2) Sector D 2920(2/2) 2790(2/2)

(2070-3770) (2070-3770) (1960-3620)

Cs-137 -(0/2) -(0/2)

(a/b) Ratio of samples with detectable activity to total number of samples analyzed.

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APPENDIX B DATATABLES 44

TABLE B-1 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10-s pCI/ms 2 2 sigma STATION CODES COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW Average DATES f 2s.d.

JANUARY 97 01/02/97 36k 4 3715 3224 3714 35 2 4 37 2 5 4125 59 2 10 (a) 36 2 4 38 2 5 37k 5 01/08/97 22k 3 25 2 3 25 2 3 27 + 3 23 a 2 30 2 3 26 23 27 23 28 k 3 27+ 3 26+ 5 01/15/97 272 2 2422 2222 2722 2322 24 2 3 2322 29 k3 29 2 2 24 2 2 25+ 5 01/22/97 25k 2 2322 1922 2212 21+2 19 2 2 23 2 2 22 a 2 26+ 2 24 2 2 22K 5 01/29/97 162 2 1522 2022 2522 17 t2 22 k 2 22+ 2 20 2 2 22 2 2 2022 202 6 FEBRUARY 02/05/97 02/12/97 02/19/97 02/26/97 282 182 2 25k 23k 2

2 2

2522 17+2 2022 1822 2022 1622 1822 1812 282 19i 30%

17i 2

2 3

2 2522 1622 24k2 2022 2312 1612 23+2 1722 2522 1822 2322 1722 25k2 1642 21%2 1922 2722 21R2 22+ 2 2122

'02822 1822 k2 2022 25+

18+ 3 23k 192 4 5

7 MARCH 03/05/97 16k 2 15 k 2 14+ 2 1522= 172 2 14 2 2 1822 1722 15 2 2 152 2 16+ 3 03/12/97 22k 2 20 k 2 20% 2 2022 22+ 2 23 2 2 2122 23k2 22 2 2 211 2 21+ 2 03/19/97 202 2 18 22 192 2 2022 21k 2 18 k2 21 k 2 21 2 2 20 2 2 202 2 202 2 03/26/97 152 2 14 2 2 132 2 1422 15% 2 17+ 2 12 + 2 17 2 2 17 2 2 16k 2 152 4 04/02/97 182 2 16 2 2 14 2 2 15 2 2 17+ 2 15 22 1322 1622 15 a 2 182 2 162 3 QuarterAvg. 22k 12 212 12 19% 10 23 2 13 21 2 10 212 13 22k 14 21 2 8 23%12 22%12 22k 13 (a) Pump off: reset. Low sample volume and not included tn averages.

TABLE B-1 ICont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMIT1'ERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10-s pCi/m3 2 2 sigma STATION CODES COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW Average DATES 2 2 s.d.

04/09/97 18 22 14 2 2 16 2 2 18 2 2 19 2 2 20+ 2 13+ 2 17 k2 152 2 18 2 2 172 5 04/16/97 24 2 2 2022 1922 2112 2022 2322 1822 1822 192 2 20 2 2 202 4 04/23/97 15 22 15 t 2 14 2 2 17+ 2 17+ 2 17 + 2 t

17 2 15 2 2 18 2 2 17+ 2

'142 2 15 2 2 162 3 04/30/97 14 2 2 15 2 2 13 2 2 15 0 2 19 2 2 14 2 2 15 2 2 14 2 2 152 4 05/07/97 16 2 2 14 2 2 (2 18 2 2 16 2 2 15 k2 17 22 182 2 142 2 1622 162 3 05/14/97 11 f2 12 2 2 ll k2 13 2 2 13 k 2 ll k2 1121 ll k2 13 2 2 112 2 1222 122 2 05/21/97 9.3 2 1.5 9.7 2 1.5 7.9 2 1.4 10%1 9.6 R 1.4 9.0 2 1.4 12 2 2 10 2 2 9.5J 1.5 9.82 2.2 05/28/97 11 k2 9.9 2 1.5 9.3 2 1.5 9.1 2 1.4 10 2 2 , 9.0 2 1.4 8.4 k 1.4 9.5 2 1.5 10 2 2 8.3k 1.4 9.4k 1.C JUNE 06/04/97 13 2 2 13 2 2 1122 14 2 2 1222 13+ 2 13+ 2 1122 122 2 13 k2 ~ 132 2 06/11/97 15 2 2 1612 15 42 1612 18 2 2 16+ 2 15 2 2 1622 142 2 1422 162 2 06/18/97 06/25/97 132 2 192 2 14 2 2 17 2 2 10 15 k2 k2 132 2 18k 2 132 2 192 2 122 172 2

2 14 2 2 17 22 1412 18 2 2 132 182 2

2 ll 18%

k 2 2

132 182 3

2 07/02/97 162 2 15 22 15 22 182 2 192 2 182 2 18 22 1822 162 2 152 2 172 3 QuarterAvg. 1528 1426 1326 1527 1627 15%8 14%6 15%6 142 6 1427 152 7

TABLE B-1 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10-s pCI/ms k 2 sigma STATION CODES COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW Average DATES 2 2 s.do 07/09/97 Ilk 22 1022 1922 87216 1722 13% 2 17k 2 1322 2022 11+ 2 13+ 2 1222 1622 1422 1622 122 151 2

2 112 2 152 2 12l 172 4 3

07/16/97 182 07/23/97 202 2 1822 2122 211 2 2322 192 2 1822 1922 182 2 182 2 20% 3 07/30/97 24k 2 1522 20%2 22k 2 2222 22k 2 1622 2322 ,212 2 212 2 212 6 AUGUST 08/06/97 23k 2 22 2 2 26 2 2 23+ 2 25%2 22+ 2 21 k2 22 2 2 212 2 192 2 22k 4 J 08/13/97 162 2 16 2 2 1722 16+ 2 1722 152 2 1722 15 2 2 15 2 2 152 2 162 2 08/20/97 08/27/97 09/03/97 202 21K 2 162 2 2 15 2 2 2022 16% 2 14 k 2 17 2'2 14 2 2 142 15+

162 2

2 2

17%2 1922 1522 13+ 2 192 2 17* 2 16 k2 21 k2 20 2 2 12 2 2 1922 19 0 2 16k 16% 2 2,

13 2 2 14 k 2 182 2 15% 2 152 5 19+ 4 162 4 SEPTEMBER 09/10/97 262 2 2322 23f2 23+ 2 2122 212 2 2222 2222 212 2 20l 2 22k 3 09/17/97 25' 2422 2222 242 2 2522 24k 2 2822 2822 24k 2 24k 2 25k 4 09/24/97 10/01/97 13 i 2 16 2 2 12 2 2 17 2 2 13 2 2 15 2 2 15 2 2 19 2 2 14 k2 20 2 2 15 + 2 16 2 2 14 k 2 16 2 2 14 k 2 16 k 2 142 2 15k 2 12 2 2 14 2 2 13 2 2 16 2 4 QuarterAvg. 192 9 1728 1729 182 8 1928 182 8 1828 1829 172 7 172 7 18% 8

TABLE B-1 (Cont.I INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA EMITIERS IN WEEKLYAIRBORNE PARTICULATES Results in Units of 10 s pCI/m3 2 2 sigma STATION CODES COLLECTION ONS-1 ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 NBF SBN DOW Average DATES %2s.d OCTOBER 10/08/97 34k 2 2823 3322 33k 2 34k 2 32k 2 3522 34 2 2 33k 2 33k 2 33k 4 10/15/97 24k 2 2522 23%2 22k 2 25k 2 23k 2 2622 25 2 2 23 2 2 19 2 2 23 2 4 10/22/97 142 2 1522 1642 142 2 17+ 2 14k 2 16%2 16 2 2 122 2 152 2 152 3 10/29/97 172 2 16 2 2 16 2 2 17 2 2 18 + 2 16 2 2 18 2 2 18+ 2 .16+ 2 152 2 174 2 NOVEMBER 11/05/97 132 2 16+ 2 17 2 2 172 2 172 2 162 2 1522 14 22 16 2 2 13 2 2 152 3 11/12/97 132 2 15 2 2 15 22 14k 2 15+ 2 14+ 2 1722 15 2 2 15 2 2 15 2 2 152 2 ll/19/97 22k 2 21 2 2 22 a.2 23k 2 212 2 202 2 1722 19 2 2 182 2 202 2 202 4 11/26/97 482 3 46 23 45 2 3 47k 3 482 3 482 3 4723 51 k3 4723 - 4423 472 4 12/03/97 202 2 21 k2 20+ 2 201 2 21+ 2 192 2 23%2 19 22 22k 2 22k 2 212 3 DECEMBER 12/10/97 9.2k 1.6 1022 9.6 2 1.6 102 2 112 2 912 15 1222 1122 102 2 9.6t 1.6 102 2 12/17/97 28 k 2 29 2 2 31 k2 282 2 32k 2 29k 2 3322 3122 32k 3 30% 2 302 4 12/24/97 24k 2 26k2 25 2 2 24k 2 26t 2 27k 2 27k2 2522 24k 2 26k 2 25k 2 12/31/97 192 2 2122 20 2 2 21 2 2 19 2 2 21 2 2 21 2 2 22 4 2 212 2 192 2 20k 2 Quarter Avg. 22 2 21 22218 23219 22k 19 23k 20 22k 20 24220 23%21 22k 20 22k 19 22k 19 Annual Avg. 20 k 14 19213 18214 202 14 202 13 192 14 19215 19214 19 2 14 19 2 14 19 i 14

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TABLE B-2 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS'N QUARI'ERLY COMPOSITES OF AIRBORNE PARTICULATES Results in Units of 10 3 pCi/ms 2 2 sigma Stations Nuciides First Quarter Second Quarter Third Quarter Fourth Quarter Average 12/30/9644/02/97 04/02/97~/02/97 07/02/97-10/01/97 10/01/97-12/31/97 2 2 s.d.

ONS-I Be-7 105 k 10 150+ 15 137 2 14 87.4 2 8.7 120 2 57 K-40 <4 6.94 2 2.44 <5 <4 6.94 + 2.44 Cs-134 < 0.2 < 0.3 < 0.3 < 0.3 Cs-137 < 0.2 < 0.3 < 0.3 < 0.3 ONS-2 Be-7 K-40 114 + 11

<5 175 2 18

<4 119 + 12

< 7 88.0

< 7 t 8.8 124 + 73 Cs-134 < 0.3 < 0.2 < 0.3 < 0.3 Cs-137 < 0.2 < 0.2 < 0.2 < 0.3 ONS-3 Be-7 101 k 10 159 2 16 127 R 13 88.6 2 8.9 119 1 62 K-40 < 7 <5 < 10 < 10 Cs-134 < 0.3 < 0.2 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 ONS-4 Be-7 112

• 11 156 2 16 138 2 14 105 2 11 128 2 47 K-40 2.93 2 1.59 <9 <4 <4 2.93 2 1.59 Cs-134 < 0.2 < 0.4 < 0.2 < 0.2 Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 ONS-5 Be-7 101 2 10 159 R 16 138 2 14 93.9 2 9.4 123 2 62 K-40 <5 3.27 2 1.71 <6 <5 3.27 2 1.71 Cs-134 < 0.2 < 0.3 < 0.2 < 0.2 Cs-137 < 0.2 < 0.3 < 0.2 < 0.2 Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.

TABLE B-2 (cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS'N QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results in Units of 10 3 pCI/m3 2 2 sigma Stations Nuclides First Quarter Second Quarter Third Quarter Fourth Quarter Average 12/30/9644/02/97 04/02/97~/02/97 07/02/97-10/01/97 10/01/97-12/31/97 2 2 s.d.

ONS-6 Be-7 111 2 11 160 1 16 153 2 15 111 2 11 134 + 53 K-40 <4 <5 <5 <5 Cs-134 < 0.2 < 0.3 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 NBF Be-7 102 2 10 144 k 14 147 2 15 97.5 2 9.8 123 2 53 K-40 4.24 2 2.31 <6 4.23 2 1.96 <4 4.24 2 0.01 Cs-134 < 0.4 < 0.2 < 0.2 < 0.2 Cs-137 < 0.3 < 0.2 < 0.2 < 0.2 SBN Be-7 114 2 11 168 2 17 138 1 14 89.6 2 9.0 127 2 67 K-40 < 7 <9 < 4 2.68 2 1.57 2.68 2 1.57 Cs-134 < 0.3 < 0.3 < 0.2 < 0.3 Cs-137 < 0.3 < 0.3 < 0.2 < 0.2 DOW Be-7 124 2 12 174 2 17 124 2 12 86.3 2 8.6 127 2 72 K-40 <5 <4 4.37 2 1.94 < 7 4.37~~"'1.94 Cs-134 < 0.2 < 0.2 < 0.2 < 0.2 Cs-137 < 0.2 < 0.3 < 0.2 < 0.3 Be-7 115 k 11 169 2 17 121 k 12 94.9 2 9.5 125 2 63 K-40 6.35 2 2.42 <5 4.01 2 2.04 <5 5.18 2 3.31 Cs-134 < 0.3 < 0.2 < 0.2 < 0.2 Cs-137 < 0.2 < 0.2 < 0.3 < 0.3 Typical LLDs are found in Table B-12. All other gamma emitters were <LLD.

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TABLE B-3 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10-s pCI/m~ 2 2 sigma STATION CODES COLLECTION ONS-I ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 SBN DOW DATES JANUARY 97 01/02/97 < 30 < 30 < 30 < 30 < 10 < 30 < 30 < 50 (a) < 30 < 30 01/08/97 < 20 < 10 < 10 < 20 < 7 <8 <8 <9 <8 <6 01/15/97 < 10 < 10 < 10 < 10 <6 < 10 <8 <.8 < 7 <5 01/22/97 <8 <8 <8 <8 <6 <8 <8 <9 <8 <6 01/29/97 < 10 < 10 < 10 < 10 <5 < 7 < 7 <8 < 7 <5 FEBRUARY 02/05/97 < 10 < 10 < 10 < 10 < 7 <8 <8 <8 <8 <5 02/12/97 < 10 < 10 < 10 < 10 <8 < 7 < 7 < 7 < 7 <5 02/19/97 <9 <8 <8 < 10 < 7 <9 <8 <9 <9 <6 02/26/97 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 <8 MARCH 03/05/97 < 10 < 10 < 10 < 10 <6 <8 < 7 <8 < 7 <6 03/12/97 < 20 < 20 < 20 < 20 < 10 < 20 < 20 < 20 < 20 < 10 03/19/97 < 20 < 10 < 20 < 20 < 7 <9 <9 <9 <9 <6 03/26/97 <9 <9 <9 <9 <6 < 10 < 10 < 10 < 10 <8 04/02/97 < 10 < 10 < 10 < 10 < 10 <8 <8 <8 <8 <6 (a) Power oA', reset. Low sample volume.

TABLE B-3 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10 s pCi/ms 2 2 sigma STATION CODES COLLECTION ONS-I ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 SBN DOW DATES 04/09/97 < 10 <9 < 10 < 10 <8 <9 < 10 < 10 <9 <8 04/16/97 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 < 10 < 10 04/23/97 <8 <8 <9 <9 <6 < 10 < 10 < 10 < 10 < 7 04/30/97 < 10 < 10 < 10 < 10 < 7 <9 <8 <9 <8 <6 05/07/97 < 10 < 10 < 10 < 10 <8 < 10 < 10 < 20 < 10 < 7 05/14/97 < 10 < 10 < 10 < 10 <9 <6 < 7 < 10 <5 < 7 05/21/97 < 20 < 20 < 20 < 10 < 10 < 10 < 10 < 20 < 20 < 7 05/28/97 < 20 < 20 < 20 < 10 <8 <8 <9 <9 < 7 <6 JUNE 06/04/97 < 20 < 20 < 10 < 10 <8 <8 <9 <9 < 10 <6 06/11/97 < 20 < 20 < 20 < 20 <9 < 10 < 10 < 10 < 30 <8 06/18/97 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 <9 06/25/97 < 10 < 10 < 10 < 10 < 7 <8 <8 <8 <8 <6 07/02/97 < 20 < 20 < 20 < 20 < 10 < 20 < 20 < 20 < 20 < 10

TABLE B-3 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10 s pCi/ms 2 2 sigma STATION CODES COLLECTION ONS-I ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 SBN DOW DATES 07/09/97 < 10 < 10 10 < 10 <6 < 7 <8 < 7 < 10 <5 07/16/97 < 20 < 10 < 10 < 10 < 7 <9 <9 <9 <9 <6 07/23/97 <8 <8 <8 <8 <5 < 10 < 10 < 10 < 10 <9 07/30/97 < 10 < 10 < 10 < 10 <6 < 7 < 7 <'7 < 7 <5 AUGUST 08/06/97 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 < 10 <8 08/13/97 < 10 < 10 < 10 < 10 < 7 < 10 < 10 < 10 < 10 <9 08/20/97 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 <9 08/27/97 < 10 < 10 < 10 < 10 < 7 < 10 < 10 < 10 < 10 <6 SEPTEMBER 09/03/97 <8 <8 <8 <9 < 7 <8 <9 <8 <9 <6 09/10/97 < 10 < 10 < 10 < 10 < 7 < 10 < 10 < 10 < 10 <9 09/17/97 < 10 < 10 < 10 < 10 <6 < 7 < 7 < 7 <8 <5 09/24/97 < 10 < 10 <9 < 10 < 7 < 10 < 10 < 10 < 10 < 7 10/Ol/97 <8 < 7 <8 <9 < 7 <8 <8 < 9 <9 < 7

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T LE B-3 (Cont)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10-s pCI/m3 + 2 sigma STATION CODES COLLECTION ONS-I ONS-2 ONS-3 ONS-4 ONS-5 ONS-6 SBN DOW DATES OCTOBER 10/08/97 < 10 < 20 < 10 < 10 < 7 < 10 < 10 < 10 < 10 <9 10/15/97 < 10 < 10 < 10 < 10 < 7 < 20 < 20 < 20 < 20 < 10 10/22/97 <8 < 7 <8 <8 <6 <9 <8 <.10 <9 <6 10/29/97 < 10 < 10 < 20 < 20 < 7 < 20 < 20 < 20 < 20 <8 NOVEMBER ll/05/97 < 10 < 20 < 20 < 20 < 7 < 10 < 9'9 < 10 < 10 < 7 11/12/97 < 10 < 10 < 20 < 20 < 7 <9 < 9 <9 <6 ll/19/97 <8 <8 <9 <9 <6 <8 <8 <9 <9 <6 11/26/97 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 12/03/97 <8 < 7 <8 <8 <5 < 10 < 10 < 10 < 10 <8 DECEMBER 12/10/97 < 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 < 10 <9 12/17/97 < 10 < 10 < 10 < 10 <5 <6 <6 < 7 < 7 < 4 12/24/97 < 7 < 7 < 7 < 7 <5 <6 <6 <6 <6 <5 12/31/97 < 20 < 20 < 20 < 20 <9 < 20 < 20 < 20 < 10 <9

I B-4 INDIANAMICHIGANPOWER 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 (b) FOURTH QUARTER AVERAGE CODES 01/02/97-04/02/97 04/02/97%7/02/9? 07/02/97-10/01/97 10/01/97-01/05/98 2 2 s.d.

T-01 4.2 2 0.5 3.3 2 0.4 5.1 2 0.1 3.4 2 0.2 4.0 2 1.7 T-02 4.4 2 0.2 3.3 2 0.4 5.1 + 0.3 3.4 2 0.3 4.1 2 1.7 T-03 4.1 i 0.6 2.9 2 0.2 4.7 2 0.3 5.2 0.8 3.1 2 0.2 3.3 2 0.3 3.7 2 1.7 4.1 2 1.7 T-04 4.3 2 0.1 3.5 2 0.5 R T-05 4.5 2 0.1 3.3 2 0.2 5.3 R 0.2 3.4 k 0.4 4.1 2 1.9 T-06 4.4 2 0.4 3.3 2 0.5 5.2 2 0.2 3.3 2 0.2 4.1 + 1.9 T-07 4.1 2 0.4 3.2 2 0.4 5.2 + 0.3 3.2 2 0.2 3.9 2 1.9 T-08 4.4 2 0.4 3.6 2 0.5 5.2 2 0.7 t 3.4 0.3 4.2 2 1.6 T-09 4.3 2 0.3 3.2 2 0.2 5.2 2 0.4 3.3 2 0.1 4.0 2 1.9 T- 1,0 4.2 1 0.2 2.7 2 0.4 4.7 2 0.4 3.0 2 0.3 3.7 + 1.9 T-11 4.5 i 0.2 3.4 2

1 0.3 0.4 5.4 5.5

+ 0.5 2 0.4 3.4 R 0.2 3.7 2 0.7 4.2 2 1.9 4.4 2 1.9 T-12 4.9 2 0.4 3.5 OFT-1 4.4 2 0.3 (a) 5.2 + 0.7 3.3 4 0.3 4.3 2 1.9 OFT-2 4.3 2 0.1 3.2 2 0.3 5.1 t 0.3 3.6 2 0.2 4.1 2 1.7 OFT-3 4.7 2 0.4 3.2 2 0.3 5.6 R 0.6 3.7 1 0.4 4.3 4 2.1 OFT-4 4.5 2 0.2 3.7 2 0.6 5.4 2 0.5 3.6 2 0.5 4.3 2 1.7 OFT-5 4.7 2 0.3 3.6 2 0.5 5.9 2 0.7 3.8 2 0.3 4.5 2 2.1 OFT-6 5.3 2 1.6 4.3 2 0.7 6.8 2 0.7 4.3 2 0.5 5.2 2 2.4 OFT-7 4.5 2 0.1 3.5 2 0.4 5.4 2 0.5 3.5 2 0.1 4.2 2 1.8 OFT-8 5.4 k 0.4 4.1 + 0.5 6.3 2 0.7 4.2 2 0.7 5.0 2 2.1 OFT-9 4.9 1 0.5 3.7 2 0.5 5.7 2 0.3 3.9 1 0.5 4.6 2 1.9 OFT-10 4.3 2 0.4 3.3 2 0.3 5.2 2 0.5 3.4 2 1.0 4.1 2 1.8 OFT-11 5.3 i 0.7 4.3 2 0.7 6.2 2 0.3 5.9 2 0.4 4.3 1 0.4 4.2 1 0.2 5.0 + 1.8 4.7 R 1.8 NBF 4.9 2 0.5 3.9 2 0.3 SBN 5.6 R 0.5 4.8 2 0.4 6.3 + 0.4 4.4 2 0.1 5.3 1 1.7 DOW 4.4 2 0.1 3.4 2 0.5 5.3 2 0.4 3.7 k 0.7 4.2 2 1.7 COL 4.1 i 0.7 3.1 2 0.3 5.0 + 0.5 3.2 2 0.2 3.9 + 1.8 Average 2 2 s.d. 4.6R 0.8 . 3.5k 0.9 5.4k 1.0 3.6 2 0.8 4.32 1.8 Standard month = 30.4 days.

ia) TLD mlsslng.

Ib) Transit dose not subtracted from totals as transit had not been placed ln shielded TLD holder.

TABLE B-5 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITl'ERS'N SURFACE WATER Results in Units of pCI/liter 2 2 sigma STATION CoHection Date I-131 K-40 SWL-1 Ol/31/97 < I < 50 4800 R 300 (Condenser Circ.) '02/28/97 < 0.9 < 60 03/31/97 < I < 60 04/30/97 < 0.5 < 70 50 400 t 150 05/31/97 < 0.9 <

06/30/97 < 0.5 < 50 07/31/97 < 0.5 < 100 <'200 08/31/97 < 0.5 < 50 09/30/97 <1 < 90 10/31/97 < 0.6 < 80 < 300 ll/30/97 <1 < 50 12/31/97 <1 < 70 SWL-2 01/31/97 (a) < 200 (South Comp) 02/28/97 (a) 03/31/97 <1 < 70 04/30/97 < 0.5 < 100 390 2 150 05/31/97 < 1 < 50 06/30/97 < 0.7 < 60 07/31/97 < 0.6 < 50 200 2 120 08/31/97 < 0.5 < 90 09/30/97 < I < 50 10/31/97 < 0.5 < 100 280 2 180 11/30/97 <1 < 100 12/31/97 < 1 < 50 Ia) Sample not collected.

Typtcal LLDs are found In Table B-12. All other gamma emltters were below <LLD.

LE B-5 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE. TRITIUM AND GAMMA EMITIERS'N SURFACE WATER Results in Units of pCI/liter 2 2 sigma STATION Collection Date I-131 K-40 SWL-3 01/31/97 (a) < 200 (North Comp) 02/28/97 (a) 03/31/97 <1 < 90 04/30/97 < 0.7- < 50 < 200 05/31/97 < 0.9 < 60 06/30/97 < 0.5 < 50 07/31/97 <1 < 50 < 200 08/31/97 < 0.5 < 100 09/30/97 <1 < 70 10/31/97 < 0.6 < 40 < 300 ll/30/97 < I < 50 12/31/97 < 0.5 < 40 (a) Sample not collected.

Typical LLDs are Iound ln Table B-12. Al! other gamma emltters were below <LLD.

ABLE B-6 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS'N GROUNDWATER Results in Units of pCI/liter 2 2.sigma STATION ,Collection Date I-131 K-40 Well W-l 01/23/97 < 0.4 < 50 < 100 04/24/97 < 0.4 < 40 < 100 07/25/97 < 0.4 < 50 < 200 10/23/97 < 0.4 < 50 < 200 Well W-2 01/23/97 < 0.3 < 60 < 100 04/24/97 < 0.4 < 50 < 100 07/24/97 < 0.4 < 60 < 300 10/23/97 < 0.4 < 50 < 200 Well W-3 01/23/97 < 0.3 < 90 < 100 04/24/97 < 0.5 < 90 < 100 07/24/97 < 0.4 < 40 < 200 10/23/97 < 0.3 44.4 2 24.8 < 200 Well W-4 01/27/97 < 0.2 < 50 1300 k 100 04/24/97 < 0.4 < 70 1500 2 100 07/25/97 < 0.8 < 100 1500 2 200 10/23/97 < 0.4 < 50 1200 2 200 540 2 80 Well W-5 01/27/97 04/24/97 0.3 0.4 0.3 60 50 100 960 j 340 2 90 120 07/25/97 <

10/23/97 < 0.4 < 60 210 2 130 Well W-6 01/27/97 < 0.3 < 50 840 2 100 04/24/97 < 0.5 < 100 1200 2 100 07/25/97 < 0.4 < 60 2200 2 200 10/23/97 < 0.4 < 50 2700 2 200

'ootnotes located at end of table.

LE B-6 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITl'ERS'N GROUNDWATER Results in Units of pCi/liter k 2 sigma STATION Collection Date I-131 K-40 Well W-7 01/23/97 < 0.4 < 100 < 100 04/24/97 < 0.6 < 70 < 100 07/24/97 < 0.4 < 80 < 200 10/23/97 < 0.4 < 100 < 200 Well W-8 01/24/97 < 0.4 < 90 < 100 04/24/97 < 0.6 < 60 < 100 07/25/97 < 0.5 < 50 < 300 10/23/97 < 0.4 < 90 < 200 Well W-9 01/23/97 < 0.5 < 60 < 100 04/24/97 < 0.6 < 50 < 100 07/25/97 < 0.3 < 50 < 200 10/23/97 < 0.4 < 70 < 200 Well W-10 01/23/97 < 0.4 < 70 < 100 04/24/97 < 0.5 < 50 < 200 07/24/97 < 0.4 < 50 < 200 10/23/97 < 0.4 < 50 < 200 Well W-ll 01/23/97 < 0.4 < 50 < 100 04/24/97 < 0.6 < 60 < 200 07/24/97 < 0.5 < 50 < 300 10/23/97 < 0.4 < 50 < 200 01/23/97 < 0.4 < 100 < 100 Well W-12 <.200 04/24/97 < 0.6 < 90 07/24/97 < 0.5 < 100 < 300 10/23/97 < 0.3 < 50 < 200

'ootnotes located at end of table.

LE B-6 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS'N GROUNDWATER Results in Units of pCI/liter 2 2 sigma STATION Collection Date I-131 K-40 Well W-13 01/23/97 < 0.4 < 40 < 100 04/24/97 < 0.6 < 50 < 200 07/24/97 < 0.5 < 90 < 300 10/23/97 < 0.4 < 50 < 200 Well W-14 01/23/97 < 0.4 < 50 7300 + 200 04/24/97 < 0.4 < 60 19000 2 1000 07/24/97 < 0.5 < 60 16000 + 1000 10/23/97 < 0.6 < 100 1100 2 100 Average 44,4 k 24.8 3618 2 11376 k 2 s.d.

Typtcal LLDs are found ln Table B-12. Alt other gamma emit ters were LLD.

LE B-7 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, TRITIUM AND GAMMA EMITIERS'N DRINKING WATER Results in Units of pCI/liter 2 2 sigma COLLECTION DATE Gamma S Iodine-131 LTW 01/15/97 3.2 2 1.1 < LLD < 0.3 350 2 140 01/29/97 3.1 2 1.1 < LLD < 0.2 02/12/97 3.6 2 1.0 < LLD < 0.3 02/26/97 3.7 2 0.9 < LLD < 0.3 03/12/97 2.6 2 0.9 < LLD < 0.3 03/26/97 3.9 2 1.0 < LLD < 0.3 04/09/97 3.8 R 1.0 < LLD < 0.5 < 200 04/23/97 3.5 2 1.0 < LLD < 0.4 05/07/97 3.7 2 1.0 < LLD < 0.3 05/21/97 3.3 2 1.0 < LLD < 0.4 06/04/97 2.1 + 1.0 < LL'D < 0.4 06/18/97 2.4 + 0.9 < LLD < 0.4 07/02/97 2.5 i 0.9 < LLD < 0.8 < 300 07/16/97 2.9 2 1.0 < LLD < 0.2 07/30/97 3.2 2 1.0 < LLD < 0.4 08/13/97 2.6 2 1.0 < LLD < I 08/27/97 2.0 R 0.9 < LLD < 0.3 09/10/97 2.8 2 1.0 < LLD < 0.4 09/24/97 2.5 2 1.0 < LLD < 0.3 10/08/97 2.7 + 1.0 < LLD < 0.3 < 300 10/22/97 3.1 2 0.9 < LLD < 0.5 11/05/97 2.5 2 0.9 . < LLD < 0.5 11/19/97 2.9 i 0.9 < LLD < 0.4 12/03/97 2.8 1 0.9 < LLD < 0.3 12/17/97 3.1 2 0.8 < LLD < 0.4 12/31/97 2.6 2 0.9 < LLD < 0.4 Average 2 3.0 2 1.0 2s. d.

~leal LLDs are found In table B-12.

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TABL (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA. IODINE, TRITIUM AND GAMMA EMIT1ERS'N DRINKING WATER Results in Units of pCI/liter 2 2 sigma COLLECTION DATE Gross Beta Gamma S Iodine-131 STJ 01/15/97 4.2 + 1.1 < LLD < 0.3 < 200 01/29/97 5.6 2 1.3 < LLD < 0.4 02/12/97 2.6 2 0.9 < LLD < 0.3 02/26/97 3.1 2 0.9 < LLD < 0.3 03/12/97 4.9 k 1.1 < LLD < 0.3 03/26/97 2.5 2 0.9 < LLD < 0.2 04/09/97 4.3 2 1.0 < LLD <'0.3 < 200

. 04/23/97 3.2 i 1.0 < LLD < 0.4 05/07/97 4.1 2 1.0 < LLD < 0.2 05/21/97 2.9 2 1.0 < LLD < 0.4 06/04/97 2.0 2 1.0 < LLD < 0.4 06/18/97 2.5 2 0.9 < LLD < 0.4 07/02/97 2.1 2 0.9 < LLD < 0.6 07/16/97 2.6 2 0.9 < LLD < 0.2 < 300 07/30/97 2.0 2 0.9 < LLD < 0.4 08/13/97 2.4 + 1.0 < LLD < 0.9 08/27/97 3.1 2 1.0 < LLD < 0.5 09/10/97 2.4 2 1.0 < LLD < 0.4 09/24/97 1.6 R 0.9 < LLD < 0.4 10/08/97 2.1 t 1.0 < LLD < 0.3 < 300 10/22/97 3.6 2 1.0 < LLD < 0.3 11/05/97 2.3 2 0.9 < LLD < 0.4 11/19/97 2.6 2 0.9 < LLD < 0.4 12/03/97 2.5 R 0.9 < LLD < 0.3 12/17/97 3.1 + 0.9 < LLD < 0.4 12/31/97 2.9 2 1.0 < LLD < 0.3 Average 2 3.0 2 1.9 2 s. de Typical LLDs are found In table B-12.

TABLE B-8 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS'N SEDIMENT Results in Units of pCI/kg (dry) 2 2 sigma Station Collection Date Be-7 K-40 Cs-137 Ra-226 Th-228 SL-2 04/18/97 < 200 3840 2 380 < 30 < 400 211 2 23 SL-3 04/18/97 < 200 6810 2 680 < 30 < 400 < 50 SL-2 10/16/97 < 200 3190+ 320 < 20 614 2 292 745 2 74 SL-3 10/16/97 (a)

Average 4613 2 3860 614 2 292 478 2 755 2 2 s.d.

(a) Sample not collected.

'ypical LLDs are found in table B-12. All other gamma emitters were <LLD.

I ABLE B-9 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA EMITI'ERS'N MILK Results in Units of pCI/liter k 2 sigma STATION CODES COLLECTION ANALYSIS DATES There were no milk analyses completed during 1997 due to lack of participants to meet the minimum requirements of the REMP program. In lieu of milk, broadleaf vegetation samples were collected.

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TABLE B-10 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITl'ERS'N BROADLEAF VEGETATION COLLECTED IN LIEU OF MILK Results in Units of pCI/kg (wet) 2 2 sigma COLLECTION DATE Station: Descrl tion Be-7 K-40 I-131 Cs-137 05/28/97 Sector-J Broadleaf 548 + 138 5600 2 560 < 10 < 20 05/28/97 Sector-A Broadleaf 462 2 93 5450 2 550 < 10 < 10 05/28/97 Sector-A Broadleaf 385 2 90 5020 2 500. < 7 < 10 05/28/97 Sector-A Broadleaf 424 2 110 5380 2 540 <9 < 20 06/25/97 Sector-A Broadleaf 382 2

+

93 3500 i 350 < 50 < 10 06/25/97 Sector-A Broadleaf 439 71 6010 2 600 < 20 < 10 06/25/97 Sector-A Broadleaf 864 2 86 3190 2 320 < 20 < 10 06/25/97 Sector-J Broadleaf 976 2 120 5690 2 570 < 10 < 20 07/23/97 Sector-J Broadleaf 733 2 86 5610 2 560 < 10 < 10 07/23/97 Sector-A Broadleaf 780 2 125 2240 2 220 < 20 < 20 07/23/97 Sector-A Broadleaf 704 2 86 4270 2 430 < 10 < 10 07/23/97 Sector-A Broadleaf 818 2 97 2950 2 290 < 10 < 10 08/20/97 Sector-J Broadleaf 2010 2 200 7620 2 760 < 20 <8 08/20/97 Sector-A Broadleaf 1680 + 170 1770 2 180 < 20 < 10 08/20/97 Sector-A Broadleaf 1920 2 190 4820 2 480 < 20 < 20 08/20/97 Sector-A Broadleaf 2180 0 220 5530 2 550 < 20 < 20 09/17/97 Sector-J Broadleaf 1310 2 130 4960 2 500 < 20 < 20 09/17/97 (a) Sector-A Broadleaf 1220 t 120 3200 + 320 < 10 < 10 09/17/97 (b) Sector-A Broadleaf 626 2 128 3830 2 380 < 20 < 20 09/17/97 (c) Sector-A Broadleaf 1960 k 200 2630 2 260 < 30 < 30 10/15/97 Sector-J Broadleaf 5430 l 540 4750 + 480 < 20 < 10 10/15/97 Sector-A Broadleaf 1880 2 190 2370 2 240 < 20 < 20 10/15/97 Sector-A Broadleaf 1380 2 140 3970 + 400 < 20 < 20 10/15/97 Sector-A Broadleaf 1550 2 160 3850 2 380 < 20 < 10 Average 2 2 s.d.

1278 2 2130 4342 i 2867 (a) Radium-226 was measured at 687 k 164 and thorium-228 was measured at 99.3 k 11.8 pCI/kg (wet).

(b) 'lhorlum-228 was measured at 66.6 k 28.8 pCI/kg (wet).

(c) lhorlum-228 was measured at 138 k 31.

Typical LLDs are lound In table B-12. All other gamma emltters were <LLD.

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TABLE B-11 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITFERS'N FISH Results in Units of pCI/kg (wet) t 2 sigma Collection Date Station Descri tion Be-7 K-40 Cs-137 Ra-226 Th-228 08/01/97 OFS-N Sucker < 100 2780 2 280 < 20 < 300 < 30 07/31/97 ONS-N Sucker < 100 2940 2 290 < 10 < 200 < 20 08/01/97 ONS-S Walleye < 100 3330 + 330 < 10 < 200 < 20 08/01/97 OFS-S Sucker < 200 3820 2 380 < 20 < 300 < 30 08/26/97 OFS-N Drum < 100 2690 2 270 < 10 < 200 < 20 08/26/97 ONS-N Sucker < 100 3000 2 300 < 10 < 300 < 20 08/26/97 ONS-S Drum < 100 2720 4 270 21.0 2 9.4 < 300 < 30 08/26/97 OFS-S Sucker < 100 3010 k 300 23.5 2 11.2 < 200 < 20 Average 3036 2 755 22.3k 3.5 2 2 sado Vyptcal LLDs are found tn table B-12. All other gamma emltters were <LLD.

TABLE B-12 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITI'ERS'N FOOD/VEGETATION Results in Units of pCi/kg (wet) 2 2 sigma COLLECTION DATE Station Descri tion Be-7 K-40 I-131 Cs-137 09/25/97 Sector-J Grapes < 30 1960 2 200 <6 < 4 09/25/97 Sector-D Grapes < 50 2070 + 210 <9 <5 09/25/97 Sector-J Leaves 3010 2 300 3620 2 360 < 30 < 10 09/25/97 Sector-D Leaves 5140 2 510 3770 2 380 < 20 < 10 Average 2 4075 2 3012 2855 2 1857 2 s.tL

~teat LLDs are found In table B-12. Allother gamma emltters were <LLD.

TABLE B-13 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DETECTION AND REPORTING LEVELS Isoto e TI LLD ODCM LLD Re t Level TI LLD ODCM LLD Re t Level Ve etation- i K -wet Water - i Hter 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 Cobalt-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- Ci Hter 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-137 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 '/A Iron-59 15 N/A N/A 0.002 N/A N/A Zinc-65 10 N/A N/A 0.002 N/A N/A Cobalt-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-032-11.

Charcoal Trap

TABLE B-13 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DETECTION AND REPORTING LEVELS Isoto e TI LLD ODCM LLD Re t Level TI LLD ODCM LLD Re t Level FISH- Ci K -wet Sediment Soil- Ci K-Cerium-144 200 N/A N/A 150 N/A N/A Barium/La-140 200 N/A N/A 5 N/A N/A Cesium-134 20 130 1000 30 150 N/A Ru,Rh-106 200 N/A N/A 200 N/A N/A Cesium-137 20 150 2000 30 180 N/A Zr,Nb-95 40 N/A N/A 40 N/A N/A Manganese-54 20 130 30000 9 N/A N/A Iron-59 40 260 10000 50 N/A N/A Zinc-65 40 260 20000 60 N/A N/A Cobalt-60 20 130 10000 20 N/A N/A Cobalt-58 20 130 30000 20 N/A N/A Iodine-131 100 N/A N/A 30 N/A N/A Gross Beta/Tritium LLDs and Re

~Gross Be Air Particulates 0.01 pCi/m3 0.01 pCi/m3 N/A Drinking Water 2 pCi/I 4.0 pCi/I N/A Tritium - Ci 1 Surface Water 200 2000 20,000 Ground Water 200 2000 20,000 Drinking Water 200 2000 20,000 (b) Based on the assumptions in procedure PRO-042-5.

APPENDIX C ANALYTICALPROCEDURES SYNOPSIS 70

ANALYTICALPROCEDUM~W SYNOPSIS Appendix C is a synopsis of the analytical procedures performed during 1997 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 Regulatory Guide 4.8,BTP, Rev. 1, November 1979.

ANALYSIS TITLE PAGE Gross Beta Analysis of Air Particulate Samples.......................... 72 Gross Beta Analysis of Water Samples ............ ..... 73 Analysis of Samples for Tritium (Liquid Scintillation).................... 75 Analysis of Samples for Iodine-131 .... ..... 76 Milk or Water ................. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 76 Gamma Spectrometry of Samples ... ..... 77 Milk and Water....................................... 77 Dried Solids other than Soils and Sediment ...................... 77 F1Sll o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 77 Soils and Sediments .................................... 77 Charcoal Cartridges (Air Iodine) ..... 77 Ai'rborne Particulates.......................................... 78 Environmental Dosimetry............... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o 80 71

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GROSS BETA ANALYSIS OF SAMPLES Airborne 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 fpCi/ms) ((S/T) - (B/t))/(2.22 V E)

TW'0 SIGMA ERROR (pCi/m3) = 2((S/T2) + (8/t2))>/>/(2 22 V E)

LLD (pCi/m3) 4.66 (B/t/T) ~/>/(2.22 V E) where:

S Gross counts of sample including blank 8 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) 72

DETERMINATIONOF GROSS BETA ACTIVITYIN WATER SAMPLES

1.0 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. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.

After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchet 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 planchet before and after mounting the sample. The planchet 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 efAciency caused by the residue mass.

73

2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually represented on the planchet, 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/1 at the 2.83 sigma, level), assuming that 1 liter of sample is used and that >1 gram of sample residue is mounted on the planchet. 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.

I 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 efflciency of 0.38.

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/1:

RESULT (N-B)/(2.22 V E)

TWO SIGMA ERROR = 2((N + B)/ht) >/2/ (2.22 V E)

LLD 4.66 (B/dt)>/2/(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 b,t counting time for the sample 75

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, reduced with hydroxylamine hydrochloride and extracted into toluene as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet 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/I:

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

TWO SIGMA ERROR 2((N/d,t+B)/d,t) ./ (2.22 E V Y DF)

LLD = 4.66(B/d,t) 1/2/(2.22 E V Y DF) where: N = total counts from sample (counts) b,t = .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 I-131, corrected for self absorption effects by the formula Es(exp-0.0085M) /(exp-0.0085Ms)

Es = efficiency of the counter determined from an I-131 standard mount Ms = mass of Pdl2 on the standard mount, mg mass of PdI2 on the sample mount, mg 76

(xA1VQdA 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 Ge(Li) detector coupled to a mini-computer-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'C. As m'uch as possible (up to the total sample) is loaded into a tared I-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-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 Ge(Li) detector L coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Soils and Sediments Soils and sediments are dried at,a low temperature, less than 100'C.

The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

Charcoal Cartrid es Air Iodine Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined 77

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(assuming no positive I-131) uniquely from the volume of air which passed 0 through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartirdge is then counted separately, positioned on the face of the detector.

Airborne Particulates 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 Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

A mini-computer 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:

78

RESULT (S-B)/2.22 t E V F DF)

TWO SIGMA ERROR 2(S+8) / /(2.22 t E V F DF)

LLD 4.66(B) / /(2.22 t E V F DF) where: S Area, in counts, of sample peak and background (region of spectrum of interest)

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

DF decay factor from the mid-collection date to the counting date 79

ENVIRONMENTALDOSIMETRY Teledyne Brown Engineering uses a CaS04.Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.

Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner.

Calculations of results and the two sigma error in net milliRoentgen (mR):

RESULT D (D y+D2+D3+D4) /4 TWO SIGMA ERROR g((D) D)2+( 2 )2+(D D)2+(D4 D)2)/3) 1/2 WHERE: D1 the net mR of area 1 of the TLD, and similarly for D2, D3, and D4 Dl I1 K/R1 -A the instrument reading of the field dose in area 1 K the known exposure by the Cs-137 source R1 the instrument reading due to the Cs-137 dose on area 1 average dose in mR, calculated in similar manner as above, of the transit control TLDs D the average net mR of all 4 areas of the TLD.

80

APPENDIX D

SUMMARY

OF EPA INTERLABORATORYCOMPARISONS 81

EPA lnterlaboratortI Comparison Program Teledyne Brown Engineering participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. Beginning with 1997, the US EPA discontinued providing milk and air particulate filter samples. For replacements, we have purchased comparable spiked samples from Analytics, Inc.

In this section 1997 data summary tables are presented for isotopes in the various sample media applicable to the Donald C. Cook Nuclear Plant's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.

82

EPA INTERLABORATORYCOMPARISON PROGRAM 1997 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result(a) En ineerin Result(b) Deviation(c) 01/17/97 Water Sr-89 12.0 + 5.0 10.00 + ~

1.00 -0.69 Sr-90 25.0 2 5.0 25.00 2 1.00 0.00 01/31/97 Water Gross Alpha 5.2 2 5.0 8.10+ 0.89 1.00 Gross Beta 14.7 2 5.0 15.00 2 1.00 0.10 02/07/97 Water 1-131 86.0 2 9.0 106.00 2 4.36 3.85 (d) 02/14/97 Water Ra-226 5.9 2 0.9 5.27 2 0.23 -1.22 Ra-228 . 8.2 2 2.1 8.40 2 0.30 0. 16 03/07/97 Water H-3 7900.0 2 790.0 7366.67 2 378.59 -1. 17 04/15/97 Water Gr-Beta 102.1 R 15.3 103.33 + 5.77 0.14 Sr-89 24.0 2 5.0 23.00 R 1.00 -0.35 Sr-90 13.0 2 5.0 12.67 2 1.15 -0.12 Co-60 21.0 2 5.0 22.67 2 0.58 0.58 Cs-134 31.0 2 5.0 28.67 2 0.58 -0.81 Cs-137 22.0 2 5.0 24.67 2 1.53 0.92 Gr-Alpha 48.0 2 12.0 54.67 2 1.53 0.96 Ra-226 13.0 2 2.0 13.00 + 1.00 0.00 Ra-228 3.1 2 0.8 4.87 k 0. 12 3.82 (e) 06/06/97 Water Co-60 18.0 2 5.0 19.00 2 0.00 0.35 Zn-65 100.0 2 10.0 99.33 2 1.15 -0.12 Cs-134 22.0 2 5.0 18.67+ 1.15 -1. 15 Cs-137 49.0 2 5.0 48.67 2 0.58 -0. 12 Ba-133 25.0 k 5.0 22.33 2 2.52 -0.92 06/13/97 Water Ra-226 3.0 2 0.5 3.43 + 0.49 1.50 Ra-228 3.1 2 0.8 3.43 k 0.23 0.72 06/18/97 Water Gr-Alpha 3.1 2 5.0 2.93 2 0.25 -0.06 Gr-Beta 15.1 2 5.0 14.00 2 1.00 0.38 07/11/97 Water Sr-89 44.0 2 5.0 38.33 2 1.53 -1.96 Sr-90 16.0 2 5.0 25.00 2 0.00 3.12 (f) 08/08/97 Water H-3 11010+ 1101.0 12000.00 2 0.00 1.56 09/12/97 Water Ra-226 20.0 2 3.0 20.00 2 1.73 0.00 Ra-228 8.0 2 2.0 7.40 2 0. 17 -0.52 09/19/97 Water I-131 10.0 2 6.0 11.00 2 0.00 0.29

'ootnotes are located at end of table.

83

I EPA INTERLABORATORYCOMPARISON PROGRAM 1997 Environmental Date 'edia Collection Nuclide EPA Result(a)

Teledyne Brown En ineerin Result(b) Deviation(c) 10/21/97 Water Gr-Beta 143.4 + 21.5 136.67 2 5.77 -0.54 Sr-89 36.0 2 5.0 36.00 2 1.00 0.00 Sr-90 22.0 2 5.0 21.67 + 2.08 -0.12 Co-60 10.0 2 5.0 10.67 2 0.58 0,23 Cs-134 41.0+ 5.0 41.33 2 0.58 0.12 Cs-137 34.0+ 5.0 36.00 2 1.00 0.69 Gr-Alpha 49.9 2 12.5 45.67 2 1.15 -0.59 Ra-226 5.0 2 0.8 5.90 2 0.10 1.95, Ra-228 5.0 2 1.3 4.27 2 0.12 -0.98 10/31/97 Water Gr-Alpha 14.7 2 5.0 19.67 2 1.53 1.72 Gr-Beta 48.9 2 5.0 50.67 2 3.51 0.61 11/07/97, Water Co-60 27.0+ 5.0 25.00 2 1.00 -0.69 Zn-65 75.0+ 8.0 71.00 2 3.61 -0.87 Cs-134 10.0 2 5.0 10.67 2 0.58 0.23 Cs-137 74.0+ 5.0 76.00 2 1.00 0.69 Ba-133 99.0 2 10.0 78.67 2 0.58 -3.52 (g)

Footnotes:

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

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

(c) Normalized deviation from the known.

(d) Erroneously high reading of the stable iodine content by ion specific electrode occurred, causing an erroneously low chemical yield. If the electrode reading is ignored, the average I-131 result becomes 90 pC1/I, in good agreement with the given value. An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulIIde. We will investigate suspiciously high electrode readings by performing a gravimetric yield on the sample without the addition of iodide carrier or the I-131 content of active samples can also be verified by performing a gamma spectral analysis.

(e) An investigation discovered a low chemical yield on one sample and the loss of another during analysis. In the future we will repeat analyses of samples with yields less than 85%.

Error apparently caused by insufficient training. The strontium separation chemistry was performed on 7/22/97 by a summer employee. Initial results-for the three samples did not agree well, so all were remilked by a senior analyst. This was insufficient to correct the problem. In-house QC samples showed satisfactory results at this time. There will be additional qualiAcatfon of analysts according to performance on in-house blanks and spikes.

No apparent cause for the discrepancy could be identiIIed. No corrective action has been taken. The investigation is continuing. An update will be provided, if a cause is determined and corrective action taken.

84

ANAIYTICS CROSS CHECK COMPARISON PROGRAM 1997 Teledyne Brown Analytics Sample ID Media Nuclide En ineerin Result (a) Result Ratio (b)

E0975-396 Milk 1-131 182, 1 20+ 1 0.90 TI ¹41238 Ce-141 L.T. 1. 232 2 12 03/20/97 Cr-51 381 2 38 387 2 19= 0.98 Cs-134 132 k 13 143 2 7 0.92 Cs-137 128 k 13 114 2 6 1. 12 Co-58 892 9 79k 4 1. 13 Mn-54 195 2 20 176 2 9 l. 11 Fe-59 161 2 16 144 2 7 1.12 Zn-65 171 2 17 165 2 8 1.04 CO-60 179 2 18 176 2 9 1.02 E0976-396 Milk Sr-89 13% 25k 0.52 (c)

TI ¹41239 Sr-90 162 192 0.84 03/20/97 E1092-396 Air Filter Ce-141 143 2 8 132 k 7 1.08 TI ¹49899-901 Cr-51 229 2 17 198 2 10 1.16 06/19/97 Cs-134 74k 812 4 0.91 Cs-137 143 2 8 115 2 6 1.24 Co-58 892 5 77k 4 1.16 Mn-54 102 2 6 842 4 1.21 Fe-59 98% 6 75k 4 1.31 Zn-65 Co-60 188 2 113 2 ll7 139 2 104 2 7

5 1.35 1.09 EI093-396 Cartridge I-131 106 2 88+ 1.20 TI ¹49902-04 06/19/97 E1094-396 Air Filter Sr-90 882 96k 0.92 TI ¹49893-95 06/19/97 E1095-396 Air Filter Gross Alpha 103 2 93k 5 1:ll TI ¹49896-98 Gross Beta 210 2 193 k 10 1.09 06/19/97 E 1204-396 Milk I-131 97k 10 87k 1.11 TI ¹57520 Ce-141 832 8 77k 4 1.08 09/18/97 Cr-51 323 2 40 304 2 15 1.06 Cs-134 982 10 102 2 5 0.96 Cs-137 117 2 12 107 2 5 1.09 Co-58 64k 6 602 3 1.07 Mn-54 99k 10 882 4 1. 13 Fe-59 132 k 13 119 2 6 1.11 Zn-65 218 2 22 196 2 10 1.11 Co-60 209 2 21 197 2 10 1.06 85

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ANALYTICSCROSS CHECK COMPARISON PROGRAM 1997 Teledyne Brown Analytics Sample ID Media Nuclide En ineerin Result (a) Result Ratio (b)

E 1203-396 Milk Sr-89 14+ 1 152 1 0.93 Tl ¹57517 Sr-90 182 1 142 1 1.29 09/18/97 Footnotes:

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

(b) Ratio of Teledyne Brown Engineering to Analytics results.

(c) Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted on 9/5/97 and was documented in the analyst's training Ale. Subsequent tests on two milk samples spiked with Sr-89 produced good results.

86

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EPA CROSS CH PROGRAM GROSS ALPHA IN V/ATER (pg. 1 of 1) 180 160 140 120 100 80 60 8

j 40 20

-20 1983 1985 1987 1989 1991 1993 1995 1997 1999 Tl 2 3 Sigma 0 EPA 2 3 Sigma

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EPA CROSS CHECK PROGRAM GROSS BETA lN WATER (pg. 1 of 2) 220 200 180 160 140 120 100 80 60 40 20

-20 1981 1982 1983 1984 1985 1986 TI k 3 sigma < EPA 2 3 sigma

EPA CROSS CH PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 260 220 180 140 100 60

-20 1986 1988 1990 1992 1994 1996 1998 0 Tl k 3 Sigma 0 EPA 2 3 Sigma

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EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 30000 25000 20000 15000 10000 5000 1984 1986 1988 1990 1992 1994 1996 1998 Tlt3Sigma o EPA 2 3 Sigma

EPA CROSS CHECK PROGRAM IODINE-131 IN VfATER (pg. 0 of 1) 200 180 160 140 120 100 80 60 40 20 m 5 a

-20 1980 1982 1984 1986 1988 1990 1992 1994 1996 1998 Tl 2 3 Sigma 0 EPA23Sigma

EPA CROSS CHECK PROGRAM COBALT-60 IN VfATER {pg 1 of 2) 100 80 60 40 20 0 0

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-20 1981 1982 1983 1984 1985 1986 1987 1988 a Tl k 3 sigma o EPA k3 sigma

EPA CROSS CHE K PROGRAM CESlUM-434 lN WATER {pg. 2 of 2) 100 80 60 40 20

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EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 1 of 2) 100 80 60 40 O

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APPENDIX E REMP SAMPLING AND ANALYTICALEXCEPTIONS 102

PROGRAM EXCEPTIONS AIR PARTICULATES On 1/02/97, the South Bend air station was found off after a pump run time of only 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />, 40 minutes. On 1/15/97, electric power was found off at air station ONS-6 after a run time of 105 hours0.00122 days <br />0.0292 hours <br />1.736111e-4 weeks <br />3.99525e-5 months <br />, 9 minutes. This was due to a tripped breaker. In both cases, sample results were not considered valid.

On 5/7/97, the ONS-3 sample result was considered to be invalid as the filter media was found off-center.

On 10/8/97, the ONS-2 sample was considered invalid as the flow rate indicated was 81 LPM and the run time was only 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />, 13 minutes. The actual total volume could not be determined.

Throughout the year the air particulate gross beta results did not meet the ODCM LLD of .01 pCi/m3. This is consistent with historical results.

SURFACE WATER Winter icing conditions on Lake Michigan prevented surface water sample collections at beach locations (SWL-2 and 3) from Ol/Ol/97 - 03/04/97.

Winter ice cleared and sampling resumed again on 03/05/97. Other dates when surface water samples were not collected because of inclement weather conditions included:

SWL-2: 03/06, 03,15, 04/07, 04/08, 04/09, 05/01, 05/15, 09/10, 09/25, 09/30, 12/06 SWL-3: 03/07, 03/08, 03/16, 03/17, 03/18, 03/23, 04/07, 04/08, 04/09, 05/01, 05/15, 09/10, 09/25, 09/30, 12/06 The first quarter tritium result from SWL-1 was 4,800 pCi/I which exceeded the ODCM LLD of 2;000 pCi/1.

GROUND WATER On Ol/23/97 well samples W4, W5, W6, and W7 were not collected due to inclement weather. All were subsequently sampled within the 25% grace period.

Gross beta results from SGl, 2, 4, and 5 on Ol/24 were >ODCM LLD of 4.0 pCi/1. This is consistent with historical data.

On Ol/23/97, groundwater well W-14 had a tritium result of 7,300 pCi/1 which exceeded the ODCM LLD of 2,000 pCi/l.

103

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On 04/24/97, groundwater well W-14 had a tritium measurement of 19,000 pCi%1 which exceeded the ODCM LLD of 2,000 pCi/l.

On 07/24/97, groundwater well W-14 had a tritium result of 16,000 pCi/I and Well-6 had a measurement of 2,200 pCi/1 which exceeded the ODCM LLD of 2,000 pCi/1.

DRINKINGWATER On different occasions the 'gross beta LLD failed to meet the ODCM LLD of 4.0 pCi/I at the St. Joseph and Lake Township facilities. This is consistent with historical information Specific dates were:

~ 12/31/96-01/15/97 St. Joseph composite sample

~ 01/16/97-01/29/97 St. Joseph composite sample

~ 02/26/97-03/12/97 St. Joseph composite sample

~ 03/26/97-04/09/97 St. Joseph composite sample 4 04/23/97-05/07/97 St. Joseph composite sample The 12/31/96-01/15/97 composite sample from the St. Joseph location exceeded the 14 day collection day frequency but was within the 25% grace period.

The Lake Township drinking water samples from 05/15/97 and 09/15/97 and the 11/13/97 St. Joseph sample were not collected. In all cases the sample collector failed to obtain the samples and the incidents were attributed to water lab technician oversight.

LAIMSEDIMENT The 10/16/97 lake sediment sample from location SL-3 was unable to be collected due to the sample area being submerged in approximately 6 feet, of water and covered with rocks. At the latter part of 1997, Lake Michigan waters were high and there was no beach area from the plant centerline to approximately 0.5 north of the plant.

BROADLEAF SAMPLES IN LIEU OF MILKSAMPLES During 1997 milk samples were not obtained since no replacement faims were found for the two indicator farms which dropped from the program in 1996. However, per ODCM, broadleaf samples were obtained in lieu of milk samples. Monthly broadleaf samples were not obtained during the first quarter of 1997 and in April, due to season unavailability. In May, broadleaf sampling resumed.

Broadleaf samples were unavailable in November and December due to end of season.

104

Location OFT-1 was found to be missing in the second quarter, the cause of incident was attributed to vandalism.

The transit does was not-subtracted from totals for the third quarter. The transit TLD was inadvertently not placed in the shielded TLD holder.

105

APPENDIX F 1997 LAND USE CENSUS 106

APPENDIX F

SUMMARY

OF THE 1997 LAND USE CENSUS The Land Use Census is performed to ensure that significant changes in the areas in the immediate vicinity of the plant site are identified. Any identified changes are evaluated to determine whether modifications must be made to the REMP or other related programs. The following is a summary of the 1997 results.

MilkFarm Surve The milk farm survey is performed to update the list of milk farms located in the plant area, to identify the closest milk farm in each land sector, and to identify the nearest milk animal whose milk is used for human consumption. The milk farm survey for the Donald C. Cook Nuclear Plant was conducted on August 4, 1997.

In 1997 there were four deletions to the Michigan Department of Agriculture's list of dairy farms in Berrien County Michigan. One of the deleted farms had previously participated in the REMP Milk Sampling Program.

The previously identified milk animal, a goat owned by Sue Dorman continues to be the closest milk producing animal to the Donald C. Cook Nuclear Plant whose milk is used for human consumption. The closest edge of the animals pasture is 13,425 feet from the Plant's centerline axis.

Residential Surve The residential survey was performed to identify the closest residence in each land sector surrounding the Donald C. Cook Nuclear Plant. The residential survey was completed on August 4, 1997. There were three new residential building permits issued by Lake Township between 06/Ol/96 and 06/Ol/1997. In addition a door-to-door survey was then conducted using a local area map. The closest residence to the Donald C. Cook Nuclear Plant in each sector remains unchanged from the previous year except for Sector 0 where the previous closest residence burned to the ground.

107

Broadleaf Surve In accordance with Offsite Dose Calculation Manual, 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 are obtained at the site boundary. The broadleaf analytical results for 1997 were less than ODCM LLDs.

108

Figure 4 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT Milk Farm Survey - 1997 Survey Distance Sector Year Miles Name Address N/A No milk farms N/A N/A No milk farms N/A B N/A No milk farms N/A N/A No milk farms N/A C N/A No milk farms N/A N/A No milk farms N/A I 13.9 13.9 William Nimtz William Nimtz 3445 Park Rd., Eau Claire 3445 Park Rd., Eau Claire E 10.5 Andrews University Berrien Springs 10.5 Andrews University Berrien Springs F 8.5 6.8 Keith & Charles Brohman 1637 Mt. Tabor Rd., Berrien Lee Nelson .

Springs RFD 1, Box 390A, Snow Rd.

t 4.1 G. G. Shuler & Sons Baroda RFD 1, Snow Rd., Baroda 4.1 G. G. Shuler & Sons RFD 1, Snow Rd., Baroda H 7.0 George Freehling 2221 W. Glendora Rd., Buchana 7.0 George Freehling 2221 W. Glendora Rd., Buchana J 7.7 Jerry Warmbein 14143 Mill Rd., Three Oaks 7.7 Jerry Warmbein 14143 Mill Rd., Three Oaks K N/A No milk farms N/A 12 Kenneth Tappan Rt. 2, Kruger Rd, Three Oaks AH other sectors are over water.

(a) Reporting Year (b) Year prior to reporting year.

109

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W N Figure 7 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT Residential Land Use Survey - 1997 Sector House (z) In Feet Pro e ¹ Street Address 2161 11-1 1-0006-0004-01-7 lier Drive. Rosemary Beach 2161 11-11-0006-0004-01-7 lier Drive, Rosemary Beach 2165 1 1-1 1-0006-0004-09-2 lier Drive, Rosemary Beach 2165 1 1-1 1-0006-0004-09-2 lier Drive, Rosemary Beach 3093 1 1-1 1-6800-0028-00-0 Lake Road, Rosemary Beach 3093 1 1-1 1-6800-0028-00-0 Lake Road, Rosemary Beach D a 5733 11-1 1-0005-0036-01-8 7500 Thorton Drive b 5733 1 1-1 1-0005-0036-01-8 7500 Thorton Drive 5631 11-1 1-0005-0009-07-0 7927 Red Arrow Highway 5631 11-1 1-0005-0009-07-0 7927 Red Arrow Highway a 5392 11-1 1-0008-0015-03-1 8197 Red Arrow Highway b 5392 1 1-1 1-0008-0015-03-1 8197 Red. Arrow Highway G a 5382 11-1 1-0008-0010-03-0 8345 Red Arrow Highway b 3728 11-11-0007-0013-01-4 Livingston Road 4944 1 1-1 1-8600-0004-00-1 Wildwood 4944 11-1 1-8600-0004-00-1 Wildwood a 3366 11-1 1-0007-0010-02-3 Livingston Hills b 3366 11-1 1-0007-0010-02-3 Livingston Hills 10 3090 1 1-1 1-0007-0010-03-1 Livingston Hills 10 3090 1 1-1 1-0007-0010-03-1 Livingston Hills (1) House ¹ indicated is the reference number used on map when obtaining the raw iield data.

(a) Reporting Year (b) Year prior to reporting year.

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APPENDIX G

SUMMARY

OF THE PRE-OPERATIONAL RADIOLOGICALMONITORING PROGRAM 113

I

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 1997.

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 114

1997. Analyses performed during the preoperational but not required in 1997, are not discussed.

The gross beta activity in air particulate filters ranged from 0.01 to 0.17 pCi/m~ 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/m3 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 mrem/week during the three and one-half years period.

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. Cesium-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.

115

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 abundances of potassium-40 and traces of cesium-137, the latter attributed to fallout.

Drinking water analysis was not part of the preoperational program.

APPENDIX H

SUMMARY

OF THE SPIKE AND BLANKSAMPLE PROGRAM 117

TELEDYNE BROWN ENGINEERING QUALITYCONTROL PROGRAM The goal of the quality control program at Teledyne Brown Engineering is to produce analytical results which are accurate, precise and supported by adequate documentation. The program is based on the requirements of 10CFR50, Appendix B, Nuclear Regulatory Guide 4.15 and the program as described in Quality Assurance Manual IWL-0032-39'5 and Quality Control Manual IWL-0032-365.

All measuring equipment is calibrated for efficiency at least annually using standard reference material traceable to NIST. For alpha and beta counting, check sources are prepared and counted every day the counter is in use.

Control charts are maintained with three sigma limits specified. Control of the alpha-beta counting equipment is described in procedure PRO-032-27, "Calibration and Control of Alpha/Beta Counters". Backgrounds are usually measured at least once per week.

The gamma spectrometers are calibrated annually with a NIST traceable standard reference material selected to cover the energy range of the nuclides to be monitored and to include all of the geometries measured.

Backgrounds are determined every other week and check sources are counted weekly. The energy resolution and efficiency were plotted at two energy levels on charts and held within three sigma control limits. From January 1, 1996 December 31, 1996 the energy levels were 59.5 and 1332 KeV. This procedure is described in PRO-042-44, "Calibration and Control of Gamma Ray Spectrometers",

The efficiency of the liquid scintillation counters is determined at least annually by counting NIST traceable standards which have been diluted in a known amount of distilled water and various amounts of quenching agent.

The procedure is described in PRO-052-35, "Determination of Tritium by Liquid Scintillation". The background of each counter is measured with each batch of samples. A control chart is maintained for the background arid check source measurements as a stability check.

Preparation of carrier solutions and acceptability criteria are contained in procedure PRO-032-49 "Standardization of Radio-chemical Carrier 118

Solutions". Preparation of efficiency calibration standards and check sources is described in procedure PRO-032-27, "Calibration and Control of Alpha/Beta Counters".

Results are reviewed before being entered into the data system by the Quality Assurance or Laboratory Manager, or supervisors for reasonableness of the parameters (background, efficiency, decay, etc.). Any results which are-suspect, being higher or lower than results in the past, are returned to the laboratory for recount. If a longer count, decay check, recount on another system or recalculation does not give acceptable results based on experience, a new aliquot is analyzed. The complete information about the sample is contained on the work sheet(s).

No deviations from written procedures occurred during 1997.

119

Results of Duplicate Analyses for 1997 Sam le e Anal sis First Anal sis Second Anal sis Air Particulates Gr-Beta 3.6 + 0.4 E-02 3.6+ 0.5 E-02 Results in Units of 2.9+ 0.3 E-02 1.6+ 0.2 E-02 10- pCi/m3 2.0 2 0.2 E-02 2.3 2 0.2 E-02 1.8+ 0.2 E-02 2.0+ 0.2 E-02 1.8 2 0.2 E-02 1.8+ 0.2 E-02 2.0+ 0.2 E-02 2.0+ 0.2 E-02 1.4+ 0.2 E-02 1.4+ 0.2 E-02 1.9 2 0.2 E-02 .1.9 + 0.2 E-02 1.7 2 0.2 E-02 1.5+ 0.2 E-02 1.7+ 0.2 E-02 1.4+ 0.2 E-02 1.2+ 0.2 E-02 1.2+ 0.2 E-02 1.2+ 0.2 E-02 1.3+ 0.2 E-02 1.1+ 0.2 E-02 1.1+ 0.2 E-02 1.6+ 0.2 E-02 1.7+ 0.2 E-02 1.9+ 0.2 E-02 1.8+ 0.2 E-02 2.0+ 0.2 E-02 1.9 + 0.2 E-02 1.5+ 0.2 E-02 1.6+ 0.2 E-02 1.5+ 0.2 E-02 1.6+ 0.2 E-02 2.1+ 0.2 E-02 2.1+ 0.2 E-02 1.5+ 0.2 E-02 1.5+ 0.2 E-02 3.5+ 0.2 E-02 3.4 2 0.2 E-02 1.6+ 0.2 E-02 1.6 2 0.2 E-02 1.6+ 0.2 E-02 1.6+ 0.2 E-02 1.6+ 0.2 E-02 1.7+ 0.2 E-02 2.0+ 0.2 E-02 2.0+ 0.2 E-02 2.0+ 0.2 E-02 2.3 2 0.2 E-02 2.9+ 0.2 E-02 3.0+ 0.2 E-02 2.0+ 0.2 E-02 1.9+ 0.2 E-02 Air Particulates/ Iodine-13 1 L. T. 3. E-02 L. T. 2. E-02 Charcoal Filters L. T. 8. E-03 L. T. 1. E-02 Results in Units of L. T. 5. E-03 L. T. 8. E-03 10-3 pCi/m3 L. T. 1. E-02 L. T. 7. E-03 L. T. l. E-02 L. T. 1. E-02 L. T. 2. E-02 L. T. 1. E-02 L. T. 9. E-03 L. T. 2. E-02 L. T. 8. E-03 L. T. 2. E-02 L, T. 1. E-02 L, T. 2. E-02 L. T. 1. E-02 L. T. 2. E-02 L. T. 2. E-02 L. T. 2. E-02 L. T. 1. E-02 L. T. 2. E-02 L. T. 9. E-03 L. T. 1. E-02 L. T. 2. E-02 L. T. 1. E-02 L. T. 1. E-02 L. T. l. E-02 Footnotes located at end of table.

120

Results of Duplicate Analyses for 1997 (cont.)

Sam le e Anal sis First Anal sis Second Anal sis Air Particulates/ Iodine-131 L. T. 1. E-02 L. T. l. E-02 Charcoal Filters L. T. 1. E-02 L. T. 8. E-03 Results in Units of L. T. 1. E-02 L. T. 2. E-02 10-3 pCi/m3 L. T. 1. E-02 L. T. 2. E-02 L. T. 7. E-03 L. T. 9. E-03 L. T. 1. E-02 L. T. 2. E-02 L. T. 1. E-02 L. T. 1. E-02 L. T. 1. E-02 L. T. 7. E-03 L. T. 1. E-02 L. T. 1. E-02 L. T. 6. E-03 L. T. 7. E-03 L. T. 8. E-03 L. T. 5. E-03 L. T. 1. E-02 L. T. 2. E-02 L. T. 2. E-02 L. T. 1. E-02 Surface Water H-3 L. T. 2. E02 2.2 + 1.2 E 02 Results in Units of Gamma (a) (a)

Gamma (a) (a) pCi/liter Ground Water Gamma (a) (a)

Results in Units of H-3 L. T. 1. E02 L. T. 2. E02 pCi/liter Gr-Alpha (a) (a)

Gamma (a) (a)

Gamma (a) (a)

H-3 1.5 + 0.2 E 03 1.3+ 0.2 E 03 t Drinking Water Results in Units of Gr-Beta I-131 3.9+ 1.0 E 00 (a) 2.5 2 0.9 E 00 (a) pCi/liter Gamma (a) (a)

L Gr-Beta 2.4+ 1.0 E 00 2.7 + 1.0 E 00 I-131 (a) ( )

Gamma (a) (a)

Gr-Beta 2.6 2 0.9 E 00 3.5+ 1.0 E 00 Footnotes located at end of table.

121

Results of Duplicate Analyses for 1997 (cont.)

Sam le e Anal sis First Anal sis Second Anal sis Food Gamma (a) (a)

Results in Units of I-131 L. T. 2. E01 L. T. 6. EOl pCi/kg (wet) Be-7 +

2.01 0.20 E 03 1.57+ 0.16 E 03 K-40 7.62+ 0.76 E 03 6.53+ 0.65 E 03 Be-7 7.58 + 0.88 E 02 3.28+ 0.91 E 02 Cs-137 (b) (b)

(a) All gamma results less than the detection limit (LLD).

(b) Result positive but associated error made it suspect.

(c) Confirmed by a reanalysis.

122

Teledyne Brown Engineering In-House Spiked Sample Results - 1997 Water Analysis ike Levels Ci L Acce table Ran e Ci l Gross Beta 2.2+ 0.7 E Ol 1.5 - 2.9 E 01 Gamma (Cs-137) 2.0 + 0.3 E 04 1.7 - 2.3 E 04 H-3 (LS) 1.4+ 0.4 E 03 1.0 - 1.8 E 03 H-3 (LS) 1.7 + 0.5 E 03 1.2 - 2.2 E 03 (11/19/97)

Analysis Gross Beta TI ¹ Date Activi Ci 1 34189 01/02/97 2.5+ 0.2 E 01 34785 01/08/97 2.1 2 0.2 E Ol 35543 Ol/15/97 2.4+ 0.2 E Ol 36158 01/22/97 2.4 + 0.2 E Ol 37933 02/12/97 2.1+ O.l E Ol 38440 02/19/97 2.2 2 0.2 E Ol 39038 02/26/97 1.8 + 0.1 E 01 39759 03/05/97 2.2 + 0.1 E 01 40212 03/12/97 1.9 + 0.1 E 01 40954 03/19/97 2.2+ O.l E Ol 41553 03/26/97 2.2+ O.l E Ol 42142 04/02/97 2.2+ 0.1 E'Ol 43031 04/09/97 1.9+ O.l E Ol 43702 04/16/97 1.8 + 0.1 E Ol 44448 04/23/97 1.8 + O. 1 E Ol 45448 04/30/97 1.6+ 0.1 E Ol 45942 05/07/97 2.0+ O.l E Ol 46576 05/14/97 2.2 + 0.1 E 01 47795 05/21/97 1.9 + 0.1 E Ol 47773 05/28/97 1.8+ 0.1 E Ol 48303 06/04/97 2.0 + 0.2 E Ol 49030 06/11/97 2.2+ O.l E Ol 49537 .06/18/97 2.2 + 0.2 E Ol 50124 06/25/97 2.3+ 0.2 E Ol 50765 07/02/97 2.3 + 0. 1 E Ol 51130 07/09/97 2.2 + 0.1 E Ol 51817 07/16/97 2.2+ O.l E Ol 52390 07/23/97 1.7 + 0.1 E 01 53126 07/30/97 2.5 2 0.2 E Ol 53640 08/06/97 2.2 + 0.2 E Ol 54225 08/13/97 '2.4 + 0.2 E Ol 54778 08/20/97 2.2+ O.l E 01 55392 08/27/97 1.9 2 O.l E Ol 55773 09/03/97 2.4 + 0.2 E Ol 123

I I

I I

I

Analysis Gross Beta TI ¹ Date D 56366 09/10/97 1.8+ O.l E Ol 57064 09/17/97 2.6+ 0.2 E Ol 57712 09/24/97 2.4 + 0.2 E Ol 58418 10/01/97 2.2 + 0.2 E Ol 59200 10/08/97 2.3 + 0.2 E Ol 59741 10/15/97 2.1 + 0.2 E Ol 60440 10/22/97 2.3 + 0.2 E Ol 61039 10/29/97 2.2 + 0.2 E Ol 61492 ll/05/97 1.9+ 0,1 E Ol 62298 11/12/97 1.9+ O.l E Ol 62816 11/19/97 2.0+ O.l E 01 63311 11/26/97 2.0+ O.l E Ol 63776 12/03/97 2.2 + 0.2 E 01 64245 12/10/97 2.0+ 0.2 E 01 64812 12/17/97 2.1 + 0,2 E 01 SPIKES - GAMMA {Cs-137)

TI ¹ D Activi Ci 1 34186 Ol/02/97 2.11 + 0.21 E 04 34781 01/08/97 2.08 + 0.21 E 04 35540 Ol/15/97 2.12+ 0.21 E 04 36155 01/22/97 2.10+ 0.21 E 04 37930 02/12/97 2.09+ 0.21 E 04 38437 02/19/97 2.05+ 0.21 E 04 39035 02/26/97 2.03 + 0.20 E 04 39756 03/05/97 2.02 + 0.20 E 04 40209 03/12/97 2.05+ 0.21 E 04 40951 03/19/97 2.06+ 0.21 E 04 41550 03/26/97 2.06+ 0.21 E 04 42139 04/02/97 2.02+ 0.20 E 04 43028 04/09/97 2.02+ 0.38 E 04 43699 04/16/97 2.07+ 0.21 E 04 44445 04/23/97 2.00+ 0.20 E 04 45445 04/30/97 2.08+ 0.21 E 04 45939 05/07/97 2.08+ 0.21 E 04 46573 05/14/97, 2.05+ 0.21 E 04 47792 05/21/97 2.09 + 0.21 E 04 47770 05/28/97 2.12+ 0.21 E 04 48300 06/04/97 2.08+ 0.21 E 04 49027 06/11/97 2.05+ 0.21 E 04 49534 06/18/97 g.05 + 0.21 E 04 50121 06/25/97 2.09+ 0.21 E 04 50762 07/02/97 2.09 + 0.21 E 04 124

I SPIKES - GAMMA (Cs-137)

TI ¹ ~l A~G'1127 07/09/97 2.06 + 0.21 E 04 51814 07/16/97 2.02+ 0.20 E 04 52387 07/23/97 2.04 + 0.20 E 04 53123 07/30/97 2.07+ 0.21 E 04 53637 08/06/97 2.00+ 0.20 E 04 54222 08/13/97 2.07+ 0.21 E 04 54775 08/20/97 2.05+ 0.21 E 04 55389 08/27/97 2.05+ 0.21 E 04 55770 09/03/97 2.08+ 0.21 E 04 56363 09/10/97 2.05+ 0.21 E 04 57061 09/17/97 2.04 + 0.20 E 04 57709 09/24/97 2.11 2 0.21 E 04 i 58415 59197 59738 10/01/97 10/08/97 10/15/97 2.05+

2.08+

2.02+

0.21 0.21 0.20 E 04 E 04 E 04 t 60437 61036 61489 10/22/97 10/29/97 ll/05/97 2.05+

2.06+

2.14+

0.21 0.21 0.21 E 04 E 04 E 04 i 62295 62813 63308 64242 11/12/97 11/19/97 11/26/97 2.05+

1.98+

2.11 +

2.10+

0.21 0.20 0.21 E 04 E 04 E 04 12/10/97 0.21 E 04 64809 12/17/97 2.05+ 0.21 E 04 65877 12/24/97 2.08+ 0.21 E 04 SPIKES - TRITIUM - (H-3) 10ml TI ¹ ~l Activi Ci 1 34193 01/02/97 1.51 + 0.17 E 03 34789 01/08/97 1.50 + 0.17 E 03 35547 01/15/97 1.38+ 0.17 E 03 36162 01/22/97 1.28 + 0.16 E 03 37937 02/12/97 1.53 + 0.18 E 03 38444 02/19/97 1.22 + 0.17 E 03 39042 02/26/97 1.43+ 0.17 E 03 39763 03/05/97 1.41 + 0.18 E 03 40216 03/12/97 1.57 + 0.18 E 03 40958 03/19/97 1.70 + 0.20 E 03 41557 03/26/97 1.47 + 0.18 E 03 42146 04/02/97 1.34+ 0.13 E 03 43035 04/09/97 1.64 + 0.18 E 03 43706 04/16/97 1.47 + 0.20 E 03 44452 04/23/97 1.51 2 0.22 E 03 45452 04/30/97 1.86+ 0.23 E 03 125

I TI ¹ 45946 A~H' 05/07/97 A~

SPIKES- TRITIUM - (H-3) 10ml 1.57+

Ci 1 0.21 E 03 46580 05/14/97 1.47+ 0.20 E 03 47799 05/21/97 1.55+ 0.20 E 03 47777 05/28/97 1.51+ 0.21 E 03 48307 06/04/97 1.52+ 0.21 E 03 49034 06/11/97 +

1.45 0.22 E 03 49541 06/18/97 1.43 + 0.21 E 03 50128 06/25/97 1.47 + 0.22 E 03 50769 07/02/97 1.82+ 0.22 E 03 51134 07/09/97 1.45 + 0.20 E 03 51821 07/16/97 1.40 + 0.20 E 03 52394 07/23/97 1.55+ 0.22 E 03 53130 07/30/97 1.50+ 0.21 E 03 53644 08/06/97 1.39 + 0.22 E 03 54229 08/13/97 1.27+ 0.21 E 03 54782 08/20/97 1.51 + 0.22 E 03 55396 08/27/97 1.59+ 0.21 E 03 55777 09/03/97 1.50 + 0.20 E 03 56370 09/10/97 1.58 + 0.22 E 03 57068 09/17/97 1.44+ 0.21 E 03 57716 09/24/97 1.59+ 0.23 E 03 58422 10/Ol/97 1.53 + 0.22 E 03 59204 10/08/97 1.45 + 0.22 E 03 59745 10/15/97 1.40 + 0.24 E 03 60444 10/22/97 1.35 + 0.22 E 03 61043 10/29/97 1.30 + 0.22 E 03 61496 ll/05/97 1.30 + 0.23 E 03 62302 11/12/97 1.34 + 0.22 E 03 62820 ll/19/97 2.02 + 0.25 E 03 63315 11/26/97 2.10+ 0.25 E 03 63780 12/03/97 1.44+ 0.23 E 03 64249 12/10/97 1.93 + 0.25 E 03 64816 12/17/97 1.50+ 0.23 E 03 65884 12/24/97 1.78 + 0.25 E 03 126

I I

I I

Teledyne Brown Engineering In-House Blanks Sample Results - 1997 Water GROSS BETA BLAMES Analysis Gross Beta TI ¹ Date Activi Ci I 34188 01/02/97 L. T. l. E 00 34784 Ol/08/97 L T. l. E 00 35542 01/15/97 L. T. 8. E-01 36157 01/22/97 L. T. 8. E-Ol 37932 02/12/97 L. T. 7. E-01 38439 02/19/97 L. T. l. E 00 39037 02/26/97 L. T. 7. E-01 39758 03/05/97 L. T. 7. E-01 40211 03/12/97 L. T. 8. E-01 40953 03/19/97 L. T. 8. E-01 41552 03/26/97 L. T. 8. E-01 42141 04/02/97 L. T. 8. E-01 43030 04/09/97 L. T. 7. E-01 43701 04/16/97 L. T. 7. E-01 44447 04/23/97 L. T. l. EOO 45447 04/30/97 L. T. 8. E-01 45941 05/07/97 L. T. 8. E-01 46575 05/14/97 L. T. 8. E-Ol 47794 05/21/97 L. T. 7. E-01 47772 05/28/97 L. T. 9, E-Ol 48302 06/04/97 L. T. l. E 00 49029 06/11/97 L, T. 7. E-01 49536 06/18/97 L. T. l. E 00 50123 06/25/97 L. T. l. E 00 50764 07/02/97 L. T. 7. E-01 51129 07/09/97 L. T. 7. E-01 51816 07/16/97 L. T. 6. E-01 52389 07/23/97 L. T. 7. E-01 53125 07/30/97 L. T. l. E 00 53639 08/06/97 L. T. l. EOO 54224 08/13/97 L. T. 8. E-01 54777 08/20/97 L. T. 8. E-01 55391 08/27/97 L. T. l. E 00 55772 09/03/97 L. T. l. EOO 56365 09/10/97 L. T. 8. E-01 57063 09/17/97 L. T. l. E 00 57711 09/24/97 L. T. 9. E-01 58417 10/Ol/97 L. T. 8. E-Ol 59199 10/08/97 L. T. l. E 00 59740 10/15/97 L. T. 9. E-01 61038 10/29/97 L. T. 7. E-01 127

GROSS BETA - BLANKS (Cont.)

Analysis Gross Beta TI ¹ Date Activi Ci 1 61491 11/05/97 L. T. 8. E-Ol 62297 11/12/97 L. T. 7. E-01 62815 11/19/97 L. T. 7. E-Ol 63310 11/26/97 L. T. 8. E-Ol 63775 12/03/97 L. T. 1. EOO 64244 12/10/97 L. T. 6. E-OI 64811 12/17/97 1.9+ 0.2E Ol (a)

TRITIUM - (8-3) - BLANKS TI 4 34191 01/02/97 L. T. 1.70 E 02 34787 01/08/97 L. T. 1.74 E 02 35545 01/15/97 L. T. 1.61 E 02 36160 01/22/97 L. T. 1.50 E 02 37935 02/12/97 L. T. 1.65 E 02 38442 02/19/97 L. T. 1.68 E 02 39040 02/26/97 L. T. 1.68 E 02 39761 03/05/97 L. T. 1.78 E 02 40214 03/12/97 L. T. 1.69 E 02 40956 03/19/97 L. T. 2.13 E 02 41555 03/26/97 L. T. 1.86 E 02 42144 04/02/97 L. T. 1.40 E 02 43033 04/09/97 L. T. 2.24 E 02 43704 04/16/97 L. T. 2,07 E 02 44450 04/23/97 L. T. 2.23 E 02 45450 04/30/97 L. T. 2.09 E 02 45944 05/07/97 L. T. 2.26 E 02 46578 05/14/97 L. T. 2.17 E 02 47775 05/28/97 L. T. 2.35 E 02 47797 05/21/97 L. T. 1.87 E 02 48305 06/04/97 L. T. 2.18 E 02 49032 06/11/97 L. T. 2.36 E 02 49539 06/18/97 L. T. 2 34 E 02 50126 06/25/97 L. T. 239 E02 50767 07/02/97 L. T. 2.00 E 02 51132 07/09/97 L. T. 2.12 E 02 51819 07/16/97 L. T. 2.46 E 02 52392 07/23/97 L. T. 2.24 E 02 53128 07/30/97 L. T. 2.21 E 02 53642 08/06/97 L. T. 2.45 E 02 (a) Teledyne sample 464811 was inadvertently spiked. A blank was not performed.

128

I I

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I

TRITIUM - (8-3) - BLANKS (Cont.)

TI 4 D Activi Ci 1 54227 08/13/97 L. T. 2.44 E 02 54780 08/20/97 L. T. 2.34 E 02 55394 08/27/97 L. T. 2.49 E 02 55775 09/03/97 L. T. 3. E02 56368 09/10/97 L. T. 2.24 E 02 57066 09/17/97 L. T. 2.46 E 02 57714 09/24/97 L. T. 2.46 E 02 58420 10/01/97 L. T. 2.21 E 02 59202 10/08/97 L. T. 2.2 E 02 59743 10/15/97 L. T. 2.75 E 02 60442 10/22/97 L. T. 2.31 E 02 61041 10/29/97 L. T. 2.58 E 02 61494 ll/05/97 L. T. 2.64 E 02 62300 11/12/97 L. T. 2.50 E 02 62818 11/19/97 L. T. 2.39 E 02 63313 11/26/97 L. T. 2.29 E 02 63778 12/03/97 L. T. 2.60 E 02 64247 12/10/97 L, T. 2.54 E 02 64814 12/17/97 L, T. 2.61 E 02 65882 12/24/97 L. T. 2.74 E 02 129

APPENDIX I TLD QUALITYCONTROL PROGRAM 130

I TLD QUALITYCONTROL PROGRAM Teledyne Brown Engineering performs an in-house quality assurance testing program for the environmental TLD laboratory. On a quarterly basis the QA manager or a qualified designate exposes groups of TLDs to three different doses using a known exposure rate from a cesium-137 source.

Typical exposures are between 20 and 80 mR. The TLDs are read on each of the three Model 8300 Readers in the environmental TLD laboratory and the calculated results are reported to the QA manager. The QA manager evaluates the results and writes a report discussing the performance of the laboratory.

For 1997 all results were within the requirements of Regulatory Guide 4.13, Section C. The standard deviations of three measurements at each exposure for each reader was less than 7.5%. The percent deviation of the average of the three measurements from the known exposure at each exposure for each reader was less than 30%. The accompanying graphs indicate the normalized deviations of the average measurements from the known exposures at each exposure for each reader.

131

QUAL1TYCONTROL-TLDs HIGH DOSE 0.8 0.6 I

CO 0

0.4 l~ @

D.

X I

O O

0.2 I I-c ~~a O -0.2 E

O -0.4

/

c 0

-0.6 a y,'I

)dl C5

'U

-0.8 8

C5 E

R 0 Reader N242 malfunctioned during

-1.2 testing in 3/96. Test repeated in 4/96

-1.4

~

1/93 3/93 7/93 10/93 2/94 5/94 9/94 12/94 3/95 6/95 10/9512/95 3/96 4/96 6/96 7/96 9/96 12/96 3/97 7/97 12/97 Reader-205 -e Reader-211 E3 Reader-242 Reader-9150 Reader-9150 permanently removed from service during the first quarter 1993.

I QUALlTYCONTROL-TLDs LOW DOSE 2.5 Reader ¹205 test invalid in I 3/96. Test repeated in 4/96.

VJ 0 I CL X

Cl Reader ¹242 malfunotioned during I D 1.5 I

testing in 3/96. Test repeated in 4/96. I I

I t

e O

c Cl 0.5 E

0 a

p t 0

C5 0 -0.5 Q

'D 8

CO E

-1.5 zO

-2

~ ~

1/93 3/93 7/93 10/93 2/94 5/94 9/94 12/94 3/95 6/95 10/95 12/95 3/96 4/96 6/96 7/96 9/96 12/96 3/97 7/97 12/97 Reader-205 -8 Reader-211 Reader-242 Reader-9150 Reader-9150 was permanently removed from service during the first quarter 1993.

QUALITYCONTROL - TLDs MIDDLE DOSE Q

Reader N242 malfunctioned during 1.5 0 testing in 3/96. Test repeated in 4/96 Q.

)C, Q

O I-C 0

C 0.5 Q

E

/

0 a b c e 0

Q Q -0.5

'D 8

er'/93 E

0 R

-1.5

~

3/93 7/93 10/ 2/94 5/94 9/94 12/ 3/95 6/95 10/ 12/ 3/96 4/96 6/96 7/96 9/96 12/ 3/97 7/97 12/.

93 94 95 95 96 97 Reader-205 -e Reader-211 l3 Reader-242 Reader-9150 Reader-9150 was permanently removed from service during the first quarter 1993.

I I

I I

QUALI ONTROL-TLDS TLD READER 205 2.5 ii 3/96 Test Invalid. Repeated 4/96.

CO O

O.

D I

X

~

I

~

1.5 I I-C I

O s C

I s

I E

0.5 I C I O

C5 I

'S s O p N e 65 E -0.5 O- I z I I

-1.5 1/93 3/93 7/93 10/93 2/94 5/94 9/94 12/94 3/95 6/95 10/95 12/95 3/96 4/96 7/96 9/96 12/96 3/97 7/97 12/97 Low Dose Middle Dose Ei High Dose

QUALITYCONTROL - TLDS TLD READER 211 1.5 0.5

//

I *gx

-0.5 I'

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-1.5 1/93 3/93 7/93 10/93 2/94 5/94 9/94 12/94 3/95 6/95 10/95 12/95 3l96 4/96 7/96 9/96 12/96 3l97 7/97 12/97 Low Dose Middle Dose High Dose

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