ML17334B504

Annual Environ Operating Rept Jan-Dec 1993 DC Cook Nuclear Plant Units 1 & 2. W/940419 Ltr

ML17334B504
Person / Time
Site:	Cook
Issue date:	12/31/1993
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0806N, AEP:NRC:806N, NUDOCS 9404250247
Download: ML17334B504 (319)

Text

acemzm r ooCmvrmm Orsr mrs Sassy REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9404250247 -

DOC.DATE: ~IQ@ygkk NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 ~

AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E.

RECIP.NAME Indiana Michigan Power Co.

RECIPIENT AFFILIATION i w ~dam~~

Sc wI/J RUSSELL,W.T. Document Control Branch (Document Control Desk)

SUBJECT:

"Annual Environ Operatin Plant Units 1 & 2." W 9 419 ltr.

t Jan-Dec 1993 DC Cook Nuclear DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR

'TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

+ ENCL f SIZE: 0 RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 3 3 PD3-1 PD 1 1 HICKMAN,J 1 1 D INTERNAL: NRR/DRSS/PRPB11 2 2 EG FILE 01 1 1 RGN3 DRSS/RPB 1 1 FILE 02 1 1 EXTERNAL: EGGG AKERS,D 1 1 NRC PDR 1 1 D

A D

D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12

Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 NMEMAlHSl f'MCMEGQH PSALM AEP:NRC:0806N Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 ANNUAL ENVIRONMENTAL OPERATING REPORT - 1993 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: W. T. Russell April 19, 1994

Dear Mr. Russell:

Enclosed is the Donald C. Cook Nuclear Plant Annual Envt.ronmental Operating Report for the year 1993. This report was prepared in accordance with Section 5.4.1 of Appendix B, Part II and Section 6.9.1.6 of Appendix A Technical Specifications of Donald C. Cook Nuclear Plant.

Sincerely, E. E. Fitzpatrick Vice President bib Enclosure c: A. A. Blind - Bridgman (10 encl.)

G. Charnoff J. B. Martin - Region III Aministrator (2 encl.)

NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett 9400250247 93i23i PDR ADGCK 050003i5 PDR

TABLE OF CONTENTS

~Pa e I. Introduction II. Changes to the Environmental Technical Specifications III. Non-Radiological Environmental Operating Report A.l Plant Design and Operation A.2 Non-Routine Reports A.3 Environmental Protection Plan A,4 Potentially Significant Unreviewed Environmental Issues B. Environmental Monitoring-Herbicide Applications C. Macrofouler Monitoring and Control Program, and Whole Effluent Toxicity Testing IV. Solid, Liquid, and Gaseous Radioactive Waste Treatment Systems 3 V. Radiological Environmental Monitoring Program (REMP) 3 A.l Changes to the REMP 3 A.2 Radiological Impact of Donald'C. Cook Nuclear Plant Operations 3 B. Land Use Census and Well Report 4 VI. Conclusion 9404250247

LIST OF APPENDICES Appendix Title Non-Routine Reports - 1993 Environmental Evaluations - 1993 Herbicide Application Report - 1993 IV Macrofouler Monitoring Control Program, and Whole Effluent Toxicity Testing - 1993 Annual Report: Radiological Environmental Monitoring Program - 1993 Radiological Environmental Monitoring Program Summary - 1993 Data Tables Analytical Procedures Synopsis Summary of EPA Interlaboratory Comparisons REMP Sampling and Analytical Exceptions Land Use Surveys Summary of the Preoperational Radiolog'ical Monitoring Program Summary of the REMP Quality Control Program Summary of the Spike and Blank Sample Program TLD Quality Control Program

I. INTRODUCTION Technical Sp ecification Section 6.9.1.6 and Appendix B, Part II, 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 serves 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, 1993.

During 1993, bas'ed 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) "9,079,300 7,853,870 Unit Service Factor (X) 100.0 96.6 Unit Capacity Factor - MDC* Net (X) 100.0 81.3

• Maximum Dependable Capacity II. CHANGES TO THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS There were no environmental Technical Spe'cification changes in 1993.

III. NON-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A.l Plant Design and Operati'on During 1993, 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 five environmental evaluations during the reporting period. Copies of these evaluations are located in Appendix II of this report. The evaluations determined that there were no unreviewed environmental questions.

A.2 Non-Routine Reports A summary of the 1993 non-routine events is located in Appendix I of this report. No long-term, adverse environmental effects were noted.

A.3 Environmental Protection Plan There were no instances of Environmental Protection Plan noncompliance in 1993.

A.4 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 five environmental evaluations during the reporting period. Copies of these evaluations are located in Appendix II of this report. The evaluations determined that there were no unreviewed environmental questions.

B. Environmental Monitoring - Herbicide Application Technical Specifications Appendix B, Subsection 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 Subsection 4.2 of this Environmental Protection Plan for the report period, including a compari'son 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 Subsection 4.2. There were no preoperational herbicide studies to which comparisons could be made. Herbicide applications are controlled by plant procedure 12THP6020.ENV.104.

A summary of the 1993 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 herbicides.

C. Macrofouler Monitoring and Control Program, and Whole Effluent Toxicity Testing Macrofouler Monitoring and Control Activities, and Whole Effluent Toxicity testing during 1993 are discussed in Appendix IV of this report. 'Zebra Mussels remained under control in 1993 'hole effluent toxicity testing studies showed no adverse environmental impact.

IV. SOLID LI UID AND GASEOUS RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes in the solid, liquid, or gaseous radioactive waste treatment systems during 1993. However, an advanced liquid processing system was installed which added coagulant to the system. This system still uses the same media.

V. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REMP The Radiological Environmental Monitoring Program annual report is located in Appendix V of this report.

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

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.

A.l Changes to the REMP There was one change to the REMP during 1993. A ground water well (W14) was added. The location of well W14 can be found on page 12 of Appendix V.

A.2 Radiological Impact of Donald C. Cook Nuclear Plant Operations

This report summarizes the collection and analysis of various environmental sample media in 1993 for the Radiological Environmental Monitoring Program for the Donald C. Cook Nuclear Plant.

The various analyses of most sample media suggest that there was no discernable impact of the 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 attributable ground water does not provide a direct dose pathway to man.

B. Land Use Census and Well Report 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. No such changes were identified during the 1993 Land Use Census' further discussion of the Land Use Census can be-found in Appendix V (F) of this report.

VI. CONCLUSION Based upon the results of the radiological environmental monitoring program and the radioactive effluent release reports for the 1993 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.

1 993 Non-Routine Events January 4, 1993 An on-site contractor released approximately 1 1/2 gallons of 504 ethylene glycol solution (six pounds pure compound) to the Plant's wastewater treatment plant.

February 15, 1993 A thin oil sheen was discovered at stormwater Outfalls 001S and 002S while performing the weekly environmental surveillance tour.

March 4, 1993 Plant personnel discovered a small oil sheen at stormwater Outfall 001S while collecting storm water samples.

March 22, 1993 Plant personnel discovered a small oil sheen at stormwater Outfall 001S.

May 21, 1993 - During intermittent chlorination of the plant service water systems, Total Residual Chlorine (TRC) analysis of Outfall 002, indicated a daily maximum value of 0.22 mg/1. Limit is 0.2 mg/l.

July 28, 1993 Plant personnel discovered sodium hypochlorite leaking to circulating water intake forebay. Approximately 25.4 lbs. were released.

July 30, 1993 Plant personnel estimated that a 4,800 gallon batch of treated water was released and contained approximately 2,400 ppm glycol (approx. 11 gal.). The calculated concentration at the

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discharge to Lake Michigan was estimated to be 0.04 ppm glycol.

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August 8, 1993 During intermittent chlorination of the Unit 1 circulating water and the plant nonessential service water systems, a Total Residual Chlorine (TRC) analysis at Outfall 002 (Unit 2) indicated a value of 0.53 mg/l. Limit is 0.2 mg/l.

August 15, 1993 Two samples were missed at Outfall OOD (turbine room sump) for sulfate and total dissolved solids.

October 3, 1993 During intermittent chlorination of the plant service water systems, the Total Residual Chlorine (TRC) analysis of the Outfall 002 discharge indicated a daily maximum value of 0.22 mg/l. Limit is 0.2 mg/l.

December 14, 1993 An estimated 30 gallons of ethylene glycol was released to the soil while changing tires on a front-end loader.

APPENDIX II ENVIRONMENTAL EVALUATION REPORTS 1993

4, AMERICAN ELECTRIC POWER Data October 13, 1993 Sub)ecc Environmental Screening 12-PM-858, Modification of Selected Secondary Sample Points Fry G. P. Arent ro 12-PM-858 Packet Introduction Plant Modification 12-PM-858 proposes to install sample coolers for key secondary chemistry parameters for the purpose of installing corrosion product monitors and monitor sample coolers. The systems affected are located on both Unit One and Two and include: 1) heater drain pump discharge, 2) feed pump discharge, 3) final feedwater and 4) main steam.

Non-essential service water (NESTS) will be utilize as the cooling medium.

Review Action Taken Final Environme ntal Statement (FES),- National Pollutant Discharge

'he Elimination S y stem (NPDES) Permit and Appendix B of Technical Specifications were reviewed and determined not to be impacted by the proposed plant modification.

In discussions with the Mike O'Keefe of the Chemical Engineering and Performance Section, it, was determined that the return lines from both the corrosion monitors and the sample coolers would be returned to the turbine room sump via floor drains. Mr. O'Keefe stated that the monitor/coolers will not be in continuous operation, however, as a conservative measure, the amount of water being returned'to the turbine room sump was calculated assuming all six monitors were in continuous operation. Based on the following calculation, the assumed flow of sample and cooler water to the turbine room sump was determined to be 40,565 gallons per day.

Calculation:

Assumptions: Six (6) monitors/coolers in service, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.

Monitor flow: 2 liters/minute per monitor Cooler flow: 25 gallons/minute total Corrosion Monitor Flow (1 hr) x( 1 day) x (1 min) x (1 liter) x (1) day AII-1 Intra-Systom

12-PM-858 Environmental Screening Page 2 of 3

'ay Cooler Flow 25 allons x 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> x 60 minutes = 36 000 allons (1 min) x (1 day) x (1 hr)

Total Flow = 4,565 (Monitor flow) + 36,000 (Cooler flow) = 40,565 gpd*

• gallons per day I

While the existing NPDES permit does not place specif ic limits on the effluent flowrate from the turbine room sump to the absorption pond, the FES states that an average of 516 gallons per minute (or 743,040 gpd) is assumed. This average assumed flowrate was compared to the average plant flowrate to determine if the addition of 40,565 gallons per day would result in exceeding the FES assumed average. Based on discussions with Diane Fitzgerald, General Supervisor-Chemistry Support (Plant), the actual average effluent flowrates for July and August 1993 were 277,000 gallons per day and 345,000 gallons per day respectively. Assuming that these are indicative of the average effluent flowrate to the turbine room sump, the addition of 40,565 gallons per day would not result in exceeding the FES assumed average.

A review of the NPDES Permit was also performed to determine if the additional effluent being discharged to the absorption pond met the limits specif ied in the permit. The NPDES Permit does not speci fy chemic, limitations for ef fluent discharged from the turbine room sump to absorption pond. As part of the NPDES Groundwater Discharg Authorization, sample parameter, frequency and type is specified. These sample requirements are not affected by the proposed PM.

Comments Zt is the opinion of this reviewer that measures should be taken during the design change process (whether AEPSC or Plant initiated) to return sample streams and cooling water to the systems which supply them. Zn the case of 12-PM-858, at a minimum the NESW flow from the monitor cooler could be returned to the system. This would have the potential of reducing the flow to the absorption pond by 36,000 gallons per day or 13,140,000 gallons annually.

Conclusion Based on this review of 12-PM-858, the Assessment Section concludes that an environmental evaluation is not required and that an unreviewed environmental question does not exist.

AZ Z-2

12-PM-858 Environmental Screening Page 3 of 3 References

1) Unit 1 and 2 Technical Specifications Appendix B

2) NPDES Permit No. MI0005827, September 20, 1990

3) Final Environmental Statement, August 1973

4) 12-PM-858 Packet

~Ke ozds turbine room sump corrosion monitor 12-PM-858 Approved by:

R. L. mms, Manager Assessment c: D. I. Eads M. J. O'Keefe D. M. Fitzgerald/J. Carlson DC-N-6370.1 AII-3

ANERlCAN ELECTRIC Date October 25, 1993 sub)act Environmental Screening Site Utilization Storage Yard From G. P. Aren W. C. Rigg Introduction The Site Utilization Plan has identified the need to clean up certain exi,sting areas on the site property and develop a site utilization storage yard. Zn support of this need, an activity has been proposed to clean up

, five identified site areas and to construct a new insulation storage building and a dumpster/satellite scaffold area.

Review Action Taken The Final Environmental Statement (FES), Appendix B of Technical Specifications and the Site Utilization Master Plan Report were review and determined not to be impacted by the proposed changes.

A review of the proposed cleanup areas (areas currently identified as laydown/storage areas includings steam generator storage facilities, laydown area north east of 345 Kv yard, areas (2) south east of 765 Kv yard and laydown area near service road off Thorton Road) and the proposed locations of the insulation warehouse and the dumpster/satellite scaffold area has determined that these areas have been previously disturbed.

Additionally, based on draft site location plans, dunes located in these areas would not be impacted by the proposed changes. Discussions with D.

M. Fitzgerald, General Supervisor-Chemistry Support at D. C. Cook, confirmed these observations.

Conclusion Based on this review of the proposed cleanup of five specific site areas and the construction of a new insulation building and designation of a dumpster/satellite scaffold area, the Assessment Section concludes that an environmental evaluation is not required and that an unreviewed environmental question does not exist.

AII-4 Intra-Syatom

Site Utilization Storage Yard Environmental Screening Page 2 of 2 References

1) Unit 1 and 2 Technical Specifications Appendix B

2) Final Environmental Statement, August 1973

3) Site Utilization Master Plan Report, April 1, 1993

~KB ozls site utilization plan insulation building laydown area Approved by:

R. L. S s, Manager Assessm nt c: D. L. Eads D. M. Fitzgerald/J. Carlson R. F. Kroeger/T. G. Harshbarger DC-N-6370.1 AII-5

ANERfCAN ELECTRlC POWER Date October 25, 1993 subject Environmental Screening Change Sheet No. 22, 12-THP 6020 LAB.041 Data Sheet Instructions yam G. P. Arent 12-THP 6020 LAB.041, CS-22 Packet Introduction Change Sheet No. 22, to procedure 12-THP 6020 LAB.041 "Data Sheet Instructions" proposes to change certain cation conductivity action levels to allow for the use of ethanolami.ne(ETA) also known as monoethanolamine at D. C. Cook for secondary side pH control for Uni.t 1 and 2. The purpose of this proceduz'e change is to allow for the initial use of ETA to determi.ne the optimum level to be utilized. A safety evaluation by the Nuclear Safety Section has been completed wi.th no open items.

Review Action Taken The Final Environmental Statement (FES), National Pollutant Dischar Elimination System (NPDES) Permit and Appendix B of Technica Specifications were reviewed in support of this scz'eening to determine the potential impact of the use of ETA.

Zn accordance with RS-34, Revision 1 "Preparation and Distribution of Environmental Evaluations, an Envi.ronmental Evaluation Check Sheet (Attachment No. 2) was performed. The conclusions of this check sheet follow:

Will the proposed activity result in a significant inczease in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) 2 No. The use of morpholi.ne as a water treatment additive was not identi.fied as a contributor to an adverse environmental impact in the FES. Addi.tionally, a revi.ew of the Material Safety Data Sheet states that ETA is not an "Extremely Hazardous Substance (as defined in 40CFR 355)" and is not listed on the "List of Toxic Chemicals (as identified in 40CFR 372).

AZZ-6 Tetra-System

Environmental Screening: 12-THP 6020 LAB.041, CS-22 Page 2 of 3 Zs the proposed activity a matter not previously evaluated in the Final Environmental Statement ?

No While ETA was not originally identified as a water treatment addit ive in the FES, morpho line (o f which ETA is a breakdown product) was identified. Morpholine was added as a corrosion inhibitor, ETA will be utilized in the same manner and has been shown to perform in a superior manner for pH adjustments.

Hill the proposed activity result in a significant change in constituent or quantity of effluent  ?

No. The FES identified a morpholine concentration of 20 ppm, as being the maximum value expected in the plant steam generator blowdown effluent. Estimates during initial testing of ETA indicate that the highest level expected in the steam generator blowdown is 2.0 to 2.5 ppm.

Will the proposed activity result in a significant change in authorized power level  ?

No. Authorized power level will not be changed by utilizing ETA for secondary pH and corrosion control.

Will a previously undisturbed area be impacted by this activity  ?

No. Site grounds will not be disturbed by this change.

Hill initiation or implementation of the proposed activity require modification to existing permits  ?

No.

'fThe NPDES Permit ETA.

will not be formally changed to allow for the use Notification of the use of ETA was provided to the Michigan Department of Natural Resources '(MDNR) in accordance with Part ZZ.A.2 of our permit. Zt was stated in this notification (reference

5) that the addition of ETA would comply with the ef fluent limitations as specified in the NPDES Permit.

Based on the above screening, it has been determined that the use of ETA for pH control at D. C. Cook does not result in a condition inconsi.stent with the existing environmental assumptions made for D. C. Cook. The findings of the above screening were discussed with Messrs. J. P. Novotny of the Environmental Engineering Section and M. J. O'Keefe of the Chemical Engineering and Performance Section, who concurred with the conclusions.

AZZ-7

Environmental Screening: 12-THP 6020 LAB.041, CS-22 Page 3 of 3 During this review it. was determined that a potential existed for ETA to be released via Outfall "C" {Plant Heating Boiler). Based on conversations with Diane Fitzgerald, General Supervisor-Chemistry Support a letter of notification will be initiated and sent to the MDNR.

Conclusion Based on this review of the use of ETA for secondary system pH and corrosion control, the Assessment Section concludes that an environmental evaluation is not required and that an unreviewed environmental question does not exist.

References

1) Unit 1 and 2 Technical Specifications Appendix B

2) NPDES Permit No. MI0005827, September 20, '1990

3) Final Environmental Statement, August 1973

4) Memo, M. J. O'Keefe to E. E. Fitzpatrick, et al, "Field Evaluation of Ethanolamine for Secondary Side pH Control for Unit 1 and 2", August 16, 1993.

5) Memo, D. L. Baker to Mr. Fred Morley and Mr. Thomas Leep, "NPDES Pe No. MI0005827 Cook Nuclear Plant, Bridgman, Michigan", March 15, 199

~Ra ozds turbine room sump steam generator blowdown ETA Approved by:

R. L imms, Manager Assessment c: D. L. Eads M. J. O'Keefe D. M. Fitzgerald/J. Carlson/B. Zordell J. P. Novotny DC-N-6370 1 F AII-8

ANERiCAN ELECTRIC POWER Date December 15, 1993 sun)oct Environmental Screening Procedure 12-THP SP.225 Containment Spray Heat Exchanger Chemical Cleaning Fron G. P. Arent To 12-THP SP.225 Packet Introduction Procedure 12-THP SP.225, Revision 0, "Containment Spray Heat Exchanger Chemical Cleaning" provides direction for the removal of iron deposits on the tube bundle secondary side tube surfaces of the Unit 1 and Unit 2 Containment Spray Heat Exchangers. The cleaning process will utilize a Citric/Ascorbic acid solvent to dissolve iron deposits within the heat exchangers. A safety evaluation screening checklist performed at the Cook Nuclear Plant identified no further safety review requirements.

Review Action Taken The Final Environmental Statement (FES), National Pollutant Discharge Elimination System (NPDES) Permit 'nd Appendix B of Technical Specifications were reviewed in support of this screening to determine the potential impact of performing the chemical cleaning of the containment spray heat exchangers.

A review of the special procedure was performed to determine how the proposed chemical cleaning process would be conducted. Briefly, the essential service water (ESW) system supply to the containment spray heat exchanger to be cleaned will be isolated. Iron solvent will then be introduced into the heat exchanger and be circulated for a period of approximately twenty four (24) hours. The solvent solution will then be rinsed from the heat exchanger to waste holding tanks for processing and disposal.

Discussions related to this process were held with Mr. Bob Claes, AEPNO Radiation Support and Mr. Jeff Novotny of AEPSC Environmental Engineering.

Based on these discussions, and a subsequent telecon on December 15, 1993, it was determined that due to the nature of the isolation valves utilized in the ESW system (butterfly valves), positive closure of the ESW lines would be required to preclude the potential discharge of chemical via the ESW system to the lake. Specifically, on the ESW supply, positive system pressure, greater than the chemical cleaning process pressure, must exist upstream of the ESW supply isolation valve. In the event pressure cannot be assured, a blind flange should be installed. On the outlet side of the heat exchanger, a blind flange must be 'installed.

Based on this determination, this environmental evaluation is predicated on the positive closure requirements described above. Failure to provide positive closure for the ESW valves voids this review.

Intra-Systam AII-9

Environmental Screening 12-THP SP.225 page 2 of 3 Zn accordance with 661000-LTG-2200-01, Revision 0 "Preparation and Distribution of Environmental Evaluations, an Environmental Evaluation Check Sheet (Attachment No. 2) was performed. The conclusions of this check sheet follow:

Will the proposed activity result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) ?

No. The use of positive closure requirements ensures that, the solution uti.lized to chemically clean the contai.nment spray heat exchangers will not be i.nadvertently discharged to Lake Michigan.

Zs the proposed activity a matter not previously evaluated in the Final Environmental Statement  ?

No. The chemical cleaning solvent and rinse water wi.ll be prevented from entering any Cook Nuclear Plant waste stream by the positive closure controls described previously. Additionally, all solvent and rinse water will be directed to tankers whi.ch will be removed from site following the cleaning process. As a result, no impact on the Final Environmental Statement wi.ll be realized.

Will the proposed activity result in a significant change in constitue or quantity of e ffluent  ?

No. No see Item 2.

Will the proposed activity result in a significant change in authorized power level  ?

No. Authorized power level wi.ll not be changed as a result of the chemical cleaning process.

Will a previously undisturbed area be impacted by this activity  ?

No. Site grounds will not be di.sturbed by this activity.

Will initiation or implementation of the proposed activity require modification to existing permits  ?

No. Based on the positive closure requirements and the removal of all solvent and rinse water from the Cook Nuclear Plant Site, no impact on the NPDES Permit will be realized.

Based on the above screening, it has been determined that, the containment spray heat exchanger chemical cleaning process will not result in a condition inconsistent with the existing environmental assumptions made for the Cook Nuclear Plant.

Environmental Screening: 12-THP SP.225 Page 3 of 3 0 en Item s Positive closure requirements as described in the Review Action Taken Section, must be in place to perform chemical cleaning of the containment spray heat exchangers. Additionally, sampling of the final rinse water to ensure residual chemicals are not present shouldbe completed prior'o the removal of the blind flanges.

Conclusion Based on this review of the containment spray chemical cleaning process proposed for Cook Nuclear Plant, the Assessment Section conclud'es that an environmental evaluation is not required and that an unreviewed environmental question does not exist.

References

1) Unit 1 and 2 Technical Specifications Appendix B

2) NPDES Permit No. MI0005827, September 20, 1990

3) Final Environmental Statement, August 1973

4) Memo, Richard D. Reid, Ph.D. to D. Fitzgerald, "Donald C. Cook Nuclear Plant Containment Spray Heat Exchanger Chemical Cleaning; Process Description", November 9, 1993.

5) Pacific Nuclear Proposal PN93-087, Rev. 1, "Chemical Cleaning Services of the Unit 1 and Unit 2 Containment Spray Heat Exchangers", September 1993.

~Ke or de containment spray heat exchanger chemical cleaning Approved by:

R. L. s, Manager Asses ment c: D. L. Eads R. M. Claes D. M. Fitzgerald/J. Carlson/B. Zordell J. P. Novotny DC-N-6370 1 F

AMERICAN ELECTRIC POWER Date December 21, 1993 sub)oct Environmental Screening Plant Modi.fication 12-PM-865 Installation of Outage and Special Projects Power Supply From G. P. Arent To 12-PM-865 Packet Introduction Plant Modification 12-PM-865, Revision 0, proposes to install both a 480 volt, three phase and 120 volt single phase electrical power supply with distribution panels located on either side of the radiati.on protection access control building (RPAC). The purpose of this proposed modification is to reduce the cost of leasing diesels to provide outage and special projects power needs.

r Review Action Taken The Final Environmental Statement (FES), National Pollutant Discharg Elimination System (NPDES) Permit. and Appendix B of Technic, Specifications were revt.ewed in support of this scieening to determine th

'potential env'ronmental impact of installing a transformer in the proposed location. Additionally, plant modification 12-PM-1234, which installs transformer spill contai.nments was reviewed for applicability.

Plant modification 12-PM-865 proposes to install a 12kV/480 volt, three phase transformer north west of the existi.ng containment access building (CAB) . In discussions with R. J. Roman of NEEP, it was determined that the actual locati.on of the transformer and cable conduit trenches had not been finalized. However, it was indicated that the transformer would be located i.n the general area northwest of the CAB near the refueling water, primary water and condensate storage tanks. Discussions related to trenching in support of cable and conduit, runs indi.cated that all trenching would occur within the security area.

Based on the above information, it is concluded that the candidate placement locations of the transformer and the proposed cable and conduit trenches are located i'nside of the security fence. The area within the security fence is pre-disturbed ground and is considered not to negatively impact the existing environment.

A second issue related to the type of transformer to be used was also discussed with Mr. Roman. At this time, the type of transformer is still unknown. It was requested, however, that the option to utilize an oil filled transformer be provi.ded. The use. of an oil filled transforme would be allowed provided an oil spill containment be designed a installed prior to the installation of the 12-PM-865 transformer. Thi requirement will be identified as an action item later in this memo.

AII-l2 Lntra-System

Environmental Screening: 12-PM-865 Page 2 of 3 In accordance with 661000-LTG-2200-01, Revision 0 "Preparation and Distribution of Environmental Evaluations, an Environmental Evaluate:on Check Sheet (Attachment No.') was performed. The conclusions of this check sheet follow:

Will the proposed activity result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) 2 No. The installation of a transformer and distribution services does not increase the environmental impact previously evaluated in the FES.

This determination assumes that, in the event an oil filled transformer is utilized, an appropriately designed oil pill containment is installed.

Zs the proposed activity a matter not previously evaluated in the Final Environmental Statement 2 No. Installation of transformers and electrical distribution systems were previously, evaluated in the FES.

Will the proposed activity result in a significant change in constituent or quantity of effluent 2 No. This proposed plant modificatio'n will not result in a change to the effluent released from the plant. In the event. an oil filled transformer is utilized, an oil spill containment will prevent the transmission of the oil to the storm drain system.

Will the proposed activity result in a significant change in authorized power level 2 No. Authorized power level will not be changed as a result of the installation of the outage and special projects power supply.

Will a previously undisturbed area be impacted by this activity 2 No. As discussed previously, the candidate placement locations of the transformer and the proposed cable and conduit trenches are located inside of the security fence. The area within the security fence has been previously disturbed. Therefor, this modification does not negatively impact the existing environment.

Will initiation oz implementation of -,the proposed activity require modification to existing permits 2 No. Based on the installation of an oil spill containment, in the event an oil filled transformer is utilized; no impact on the NPDES Permit will be realized.

AIZ-13

Environmental Screening: 12-PM-865 Page 3 of 3 Based on the above screening, it has been determined that the installatio of a 480 volt, three phase transformer and associated distribution system as defined by 12-PM-865 will not result in a condition inconsistent with the existing environmental assumptions made for the Cook Nuclear Plant.

0 en Item s In the event an oil filled transform is utilized in this application, the installation of an oil spill containment will be mandatory. Failure to t

install an oil spill containment, if one is required, voids this environmental evaluation.

A plant modification (12-PM-1234) has been developed for the design and installation of oil spill containments for various transformers located at the site. It is recommended, that this plant modification be used if an oil spill containment is required in support of 12-PM-865.

Conclusion Based on this review of plant modification 12-PM-865, installation of an outage and special po)ects power supply, for Cook Nuclear Plant, the Assessment Section concludes that an environmental evaluation is not required and that an unreviewed environmental question does not exist.

References

1) Unit 1 and 2 Technical Specifications Appendix B

2) NPDES Permit No. MI0005827, September 20, 1990

3) Final Environmental Statement, August 1973

4) 12-PM-865, Revision 0, Installation of a 12kV/480 volt, three phase transformer and associated distribution system.

K~eor8s electrical power supply 480 volt 120 volt outage Approved by:

R. L. s, Manager Assessment c: D. L. Eads R. M. Claes D. M. Fitzgerald/J. Carlson J. P. Novotny R. J. Roman DC-N-6'R&~

~@Rid AII-14

APPENDIX III HERBICIDE APPLICATION REPORT 1993

5 INOlANA MtCHlGAN POWER Date February 8, 1994 subject 1993 Herbicide Spray Report - Cook Nuclear Plant From J.S. Lewis>

To J.P. Carlson From July 26 -30, 1993, Tree Preservation applied Pathway herbicide as a stump treatment on trees cut within the Plant Right-Of-Way, except in highly erodible areas.

A total of one gallon of Pathway was used on 400-425 tree stumps. Pathway was applied in accordance with the manufacturer's .label. Mr. Frederick H. Meyer, Inspector for Indiana Michigan Power Company, performed the inspection and found that the areas treated with Pathway herbicide were satisfactory and no signs of overspray existed. No adverse environmental effects or concerns were found.

Attachment AIII-1 Intn-System

APPENDIX IV MACROFOULER MONITORING CONTROL PROGRAM, AND WHOLE EFFLUENT TOXICITY TESTING 1993

Aquatic Issues - 1993 Zebra Mussel Monitoring and Control Report The following reports detail the 1993 zebra mussel monitoring and control activities performed at the Cook Nuclear Plant. Specific reports from LMS, our biological monitoring contractor; and Brand Utilities Services, our diving contractor are provided.

Indiana Michigan Power Company Cook Nuclear Plant 1993 Zebra Mussel Monitoring and Control Report March 30, 1994 INTRODUCTION The Plant's Zebra Mussel Monitoring and Control Program has progressed from a detection based program to a monitoring and control program. Through the Plant's control efforts utilizing plant design changes, preventive maintenance enhancements, mechanical cleaning, chlorination, and proprietary molluscicides, zebra mussel densities were maintained at manageable levels which did not significantly affect plant operation.

Monitoring efforts continue to assess the threat of zebra mussel infestation and determine the effectiveness of plant control techniques. A report on bio-monitoring studies by LMSi a diver report of zebra mussel infestation in the intake forebay, and a diver assessment of zebra mussel mortality in the intake forebay in the aftermath the September 1993 Clam-trol treatment is attached.

Design and mechanical problems of the chlorination system in 19 made it difficult to assess the effectiveness of intermittent chlorination of the service water systems. Colonization in lo

. or no flow areas remains a concern as experienced in the aftermath of the Sept. 11-12, 1993 Clam-trol treatment where pluggage occurred in components of the service water systems.

Cumulative settlement data collected from the sidestream samplers located on the service water systems showed that zebra mussels settled and developed until shell lengths reached 1.5 mm, then either died or translocated elsewhere in the systems.

Intermittent chlorination of the circulating water system was ineffective in controlling colonization in those systems which draw water from the circulating water system. Zebra mussels which slough off from the intake pipelines present. a challenge to the screenwash and traveling screen system, and service water pump strainers.

ERADICATION AND CONTROL MEASURES The 1993 control strategy consisted of the use of a proprietary molluscicide (Clam-trol), intermittent chlorination of the service and circulating water systems, and mechanical cleaning.

MECHANICAL CLEANING Mechanical cleaning of the intake forebays using new scrubber technology was performed to supplement the Sept. 11-12, 1993 AIV-2

Clam-trol treatment. In the aftermath of the "Clam-trol

~

treatment, cleaning and flushing of small bore piping and

~ ~ ~ ~

strainers in the miscellaneous seal & cooling water system,

~ ~ ~ ~

screenwash and lawn sprinkler pump strainers, NESW cooling to the

~ ~

Unit 2 air compressor, ESW to the Unit 1 North Control Room Air

~ ~ ~ ~

Conditioning Chiller Condenser, and the Unit 2 Main Turbine Lube Oil Coolers was performed. All three intake cribs were cleaned of zebra mussels to minimize the impact of the intakes on wild ducks. No wild ducks were entrained into the plant's intake structures in 1993.

CLAM-TROL TREATMENT RESULTS A single treatment of the intake forebay and circulating water system using Betz Clam-trol CT-1 was performed in 1993. Because the service water systems, misc: seal 6 cooling, and screenwash pump systems draw from this treated water, they also received benefit from the treatment.

On September 11-12, 1993, the entire circulating water system was treated for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using Clam-trol at a target feed rate of 15 ppm. Bentonite clay was injected into the discharge as a detoxicant at a ratio of at least 3:1 clay:Clam-'trol before being discharged to Lake Michigan. Zebra mussel mortalities measured by bio-boxes placed throughout the plant ranged from 4-1004.'

Subsequent intake forebay inspections by divers two weeks after

~ ~ ~

the application (See attached report), indicated a 5-954 kill on

~ ~

the walls and surfaces of the forebay. The area which experienced a low kill rate represented a small portion (<54)'f

~ ~

the total forebay area. This area was mechanically cleaned by divers. A total of 636 cubic yards of zebra mussel shell relics were removed from the intake forebay in the aftermath of the Clam-trol treatment.

CHLORINATION TREATMENT RESULTS In 1993, the essential service water (ESW)'nd non-essential service water (NESW) systems received daily intermittent sodium hypochlorite treatments of 1.5-2.0 ppm total residual chlorine (TRC) for 155 minutes from May until early December. The circulating water system received daily intermittent sodium hypochlorite treatments of 0.2 ppm (TRC). A,detailed discussion and availability of the chlorination system is included in the attached report from LMS.

Plant systems are fouled as a result of larval, juvenile, and adult zebra mussels being allowed to infest areas due to lack of, or insufficient physical and chemical control methods. Clam-trol

. treatments can exacerbate the problem by killing mussels residing in plant systems with the resultant sloughing of shells which can overwhelm traveling screens, plug strainers, heat exchangers, and small bore piping systems.

AIV-3

Systems exposed to high, and especially turbulent flow, which are also routinely chlorinated as in the main condenser water boxe and CCW heat echangers, are virtually mussel free. Sargent &

Lundy performed a special study for Commonwealth Edison which showed that systems exposed to flow velocities of )= 5 feet/sec.

in the absence of a biocide, displayed no zebra mussel settlement. This can be confirmed at Cook Plant by the plant's trash racks in high flow areas of the intake forebay being clear of zebra mussel settlement. The combination of flow and chlorine in the plant's service and circ. water systems appears to have a positive effect on keeping these piping systems clean.

Attempts were made in 1993 to chlorinate the service water systems continuously at 0.5-1.0 ppm to ensure colonization did not occur in the ESW and NESW systems. Due to certain design deficiencies, continuous operation of the system was unsuccessful. System upgrades have been made over this past winter and continuous chlorination of the service water systems will be attemped again in 1994.

CHANGES IN PLANT DESIGN Fire Protection System The Plant's fire protection system was converted to chlorinated municipal drinking water in the Spring of 1993. Zebra mussels longer pose a threat to this system.

FOULING FROM THE INTAKE PIPELINES The intake pipelines have been treated in the past with Clam-trol when necessary and plant conditions allow. The North and the Center Intake pipelines were treated with Clam-trol in 1992.

Zebra Mussel sloughage still occurs from the intake pipelines and is most apparent when flow velocities are changed by cycling the

. Center Intake gate valve, WMO-30. This operation presents a challenge to the traveling screens and screenwash system in their ability to handle the, influx of zebra mussels sloughing off from the intake tunnels. Any carryover that occurs, must be handled by the service water pump strainers or is impinged on the condenser tube sheets. A molluscicide treatment to the South Intake pipeline is planned for 1994 and plans to upgrade the traveling screenwash system to more effectively handle zebra mussel sloughage are in progress.

CONCLUSION Shock treatments of a proprietary molluscicide to remediate juvenile and adult zebra mussels in conjunction with the use of sodium hypochlorite to control veliger settlement, has been an effective method in controlling zebra mussels. Mechanical cleaning can be effective in areas where chemical means are

impossible or uneconomical. Chemical methods for controlling

~ ~ ~

zebra mussels in low or no flow areas of the service water

~

systems can be improved with continuous chlorination. Switching the fire protection system from raw lake water to municipal

~

drinking water in 1993 eliminated the threat of zebra mussel

~ ~

infestation in the fire protection system. A bio-monitoring program utilizing side-stream and artificial substrate monitors along with diver and heat exchanger inspections will continue to be used to evaluate the effectiveness of chemical and physical control measures.

AjV-5

Prepared for INDIANAMICHIGAN POWER COMPANY One Cook Place Bridgman, Michigan MOLLUSC BIOFOULING MONITORING DURING 1993 Donald C. Cook Nuclear Plant March 1994 Prepared by LAWLER, MATUSKY & SKELLY ENCINEERS Environmental Science & Engineering Consultants One Pierce Place Suite 500E Itasca, Illinois

~

A?V-6

Prepared for INDIANAMICHIGANPOWER COMPANY One Cook Place Bridgman, Michigan MOLLUSC BIOFOULING MONITORING DURING 1993 Donald C. Cook Nuclear Plant March 1994 LMSE-94/0181&673/001 Prepared by:

LAWLER, MATUSKY& SKELLY ENGINEERS Environmental Science & Engineering Consultants One Pierce Place Suite 500E Itasca, Illinois 60143 AIV-7

TABLE OF CONTENTS Page No.

LIST OF FIGURES LIST OF TABLES EXECUTIVE

SUMMARY

ES-1 1 INTRODUCTION 1.1 Past History 12 Objectives 2 METHODS 2.1 Whole-Water Sampling 2.2 Artificial Substrates 3 RESULTS AND DISCUSSION 3.1 Whole-Water Sampling 32 Artificial Substrate Sampling 32.1 Circulating Water System 3~2 322 Service Water System 3~3 4

SUMMARY

AND RECOMMENDATIONS 4-1 4.1 Summaxy 4-1 42 Recommendations 4-2 APPENDIX A Lawler, Matusky, & Skelly Engineers AIV-8

LIST OF FIGURES Following Figure No. Title Page 3-1 Whole-Water Sampling Program Veligers per Cubic Meter-D.C. Cook 1993 I

3-2 Artificial Substrate Settlement-Forebay Location Settlement 3-2 per Square Meter, D.C. Cook 1993 3 3 Artificial Substrate Settlement-Forebay Location Average 3~3 Daily Settlement per Square Meter, D.C. Cook 1993 3-4 Post-Veliger Settlement, Number per Square Meter, 3~3 Essential Service Water System, D.C. Cook Plant 1993 3-5 Post-Veliger Settlement, Number per Square Meter, 3-3 Nonessential Service Water System, D.C. Cook Plant 1993 Lawler, MatusKy, & SKeHy Engineers AIV-9

LIST OF TABLES Table No. Title Page No.

3-1 Whole-Water Sampling Program Veligers per Cubic Meter 3-1A D.C. Cook, 1993 3-2 Artificial Substrate Settlement - Periodic Post-Veliger Density 3-2A per Square Meter, D.C. Cook, 1993 3-3 Artificial Substrate Settlement - Cumulative Post-Veliger 3-3A Density per Square Meter, D.C. Cook, 1993 3-4 Summary of Dates Chlorination System Was Out of Service or No 3-4A1 TRC Data Available 3-5 Percent Availability of Chlorination System for Service Water 3MB Systems May-November 1993 Lawler, Matusky, 8 Skelly Engineers AT.V-3.0

EXECUTIVE

SUMMARY

Indiana Michigan Power Company has been conducting biofouling studies at the Donald C.

Cook Nuclear Plant since 1983. In 1990, monitoring of zebra mussels in the circulating water, essential service water (ESW), and nonessential service water (NESW) systems was added to the program. The objectives of this monitoring are to detect the presence and density of zebra mussel veligers in the circulating water system and post-veliger settlement in the forebay and service water systems.

Veligers were present in the forebay from the first sampling date (27 May 1993) through November sampling. Peak densities occurred on 24 June and 11 October 1993, with the major peak occurring on the October date (108,950/m~), along with high winds (25+ mph). This disturbance of the water column contributed not only high numbers of veligers, but also high numbers of post-veligers to the whole-water samples. This effect of storms may impact plant water systems adversely.

I Settlemerit of post-veligers first occurred in the forebay on 30 July and continued for the remainder of the sampling season. Settlement peaked between 11 and 21 October, at an average daily settlement rate estimated at 72,197/m2. Heavy post-veliger settlement extended from 9 September to 18 November 1993. Many of the individuals examined during the latter part of this period were relatively large, suggesting that they were translocators.

Cumulative post-veliger densities in the forebay generally increased during the season, but remained less than 25,000/m"- until after the ClamTrol treatment. Twelve days after this treatment, densities had increased to approximately 135,500/m-. After 40 days, densities were about 2 million/m2. Translocators then moved onto the substrates, making further estimates impractical. This increase in densities was attributed to the absence of predator mussels in the forebay to control veligers, churned-up lake conditions in September, and an abundance of clean substrate upon which the veligers settled following the ClamTrol Treatment.

AIV-11 CF/032894/2:14 pm/H 23494 Lawler, Matusky & Skelly Engineers

Settlement first appeared on the artificial substrates located in the service water systems on 1 July. Peak settlement occurred on the supply and return sides of the ESW and NESW systems at different times. Peak settlement dates and densities were as follows:

~

ESW supply: 9-23 September (3,040/m )

ESW return: 30 July - 12 August (6,613/mz)

NESW supply: 12-26 August (1,973/m2)

NESW return: 23 September - 11 October (9,066/mz)

These periods of settlement generally followed extended periods when the chlorination system did not deliver chlorine to the service water systems. Availability-ofthe chlorination system ranged from 29 to 70% during peak settlement periods. In addition, on most sampling dates, more settlement took place on the return side of the systems, which indicates that not as much chlorine was reaching this portion of the systems.,

Cumulative settlement data collected from the sidestream samplers located on the service water systems produced the following results. Development proceeded until shell lengths reached 1.5 mm. This "size limit" was maintained throughout the season. Larger zebra mussels did not find the conditions in the samplers suitable for continued growth and either died or translocated to avoid perceived stress. The design of the 1993 monitoring program did not permit identification of the causes of the observed phenomenon.

AIV-12 CF/032894/2: i 4pm/H 23494 Lawler, Matusky dt Skelly Engineers

CHAPTER 1 INTRODUCTION 1.1 PAST HISTORY Indiana Michigan Power Company (I&M), a subsidiary of American Electric Power Company (AEP), has been conducting biofouling studies at the Donald C. Cook Nuclear Plant since 1983.

These studies were initially directed toward Asiatic clams. Because of the recent appearance of zebra mussels in Lake Michigan, however, the studies were expanded in 1990 to include zebra mussels. The purpose of the studies was to detect the presence of biofouling molluscs in the circulating water, essential service water (ESW), and nonessential service water (NESW).

The 1993 monitoring program conducted by Lawler, Matusky & Skelly Engineers (LMS) was designed to detect when spawning and settling of zebra mussels occur at the Cook Nuclear Plant and to collect and analyze (1) whole-water samples for planktonic veligers and (2) artificial substrates set within the circulating water, ESW, and NESW systems for periodic and cumulative post-veliger settlement.

1.2 OBJECTIVES Specific objectives for the 1993 biofouling monitoring program were as follows:

~ Whole-water sampling of the circulating water system was conducted weekly (June-August), bimonthly (September-October), or monthly (November-December) to determine the presence and density of larval zebra mussels.

~ Artificial substrates were deployed in the intake forebay and service water systems to detect settlement of post-veligers. Samples were collected every two weeks from May through October and once per month during November and December.

AIV-13 q reumn: iymniuie Lawler, Matusky & Skelly Engineers

CHAPTER 2 METHODS 2.1 WHOLE-WATER SAMPLING Whole-water sampling of the circulating water system was conducted from 27 May to 16 December 1993. Samples were collected from the intake forebay by pumping lake water through an in-line flowmeter into a plankton net. Two replicates (2000 liters each) were collected during each sampling event.

A JABSCO utility pump, rated to deliver 26 gpm, was connected to a flowmeter assembly consisting of a Cole-Parmer ACCUM-U-FLO model digital flowmeter/accumulator, ROTOR-X paddle wheel flow sensor, and a PVC 80 installation fitting. To minimize organism abrasion, measured flow was directed into a No. 20 plankton net that was suspended in a partially filled 55-gal plastic barrel. Valves were adjusted to reduce flow, thus preventing the plankton net from overflowing when heavy sediment loads or plankton concentrations were present.

Samples were washed down gently into the cod-end bucket and then transferred into a 1 liter plastic jar. If needed, filtered water was added to the jar to ensure that a full liter was analyzed. After the second replicate was taken, both samples were packed on ice for transport to the laboratory and refrigerated until analyzed (within 48 hrs of collection).

Samples were initially mixed thoroughly for 5 min. Then, using a calibrated disposable Pasteur pipette, a 1-ml aliquot of mixed sample was placed into a Sedgewick-Rafter cell for counting, using a low-power binocular microscope (10-40X) with cross-polarizing filters. Five replicates were counted, and the average was extrapolated to determine the number of individuals per cubic meter. This process was repeated for the second replicate and the two values were averaged to yield a final value.

AIV-14 rtmmunaop~e Lawler, Matusky & Skelly Enginee

I 2.2 ARTIFICIALSUBSTRATES To determine-zebra mussel settlement in the circulating water, ESW, and NESW systems, artificial substrates were placed in the intake forebay upstream of the trash racks; sidestream samplers were set on the supply and return sides of both systems. Monitors were equipped with modified test-tube racks designed to hold slides for periodic and cumulative sampling. (Periodic settlement is defined'as short-term monitoring, either two- or four-week periods, depending on the month. Cumulative settlemenr is long-term monitoring that extends from initial deployment

[20 May) to the end of the sampling season.) A sufficient number of substrates were placed in the samplers initially to allow 10 slides to be removed on each sampling date. Cumulative monitoring was designed to provide information on accumulated infestation throughout the growing season.

Qn each sampling date 10 slides from each location were retrieved and replaced with clean slides. These were labeled as periodic settlement. A second set of 10 slides placed in the monitor on 20 May was retrieved from each location and used for the cumulative monitoring.

These slides were not replaced. Slides were placed in labeled racks, covered with a plastic bag, and kept on ice during transport to the laboratory. They were then refrigerated until analysis began.

Artificial substrates placed in the intake forebay consisted of cinderblocks with test-tube racks secured inside the openings. These samplers were deployed by rope in the north, central, and south locations approximately 1 meter from the bottom.

Sidestream monitors were placed on the supply and return sides of the service water systems (ESW and NESW). Each monitor contained two modified test-tube racks that held all slides above the monitor base. This allowed silt and sediment to fall out before they could influence post-veliger settlement. Monitors were covered with an 18>M-approved fireproof fabric to limit light exposure. Plant personnel checked the monitors periodically to ensure that adequate flow was available, and flow was adjusted as necessary.

AIV-15 rf/032494/I:13pm/h23494 Lawler, Matusky & Skelly Engineers

Analysis was conducted with a low-power binocular microscope (10MX) equipped with cross polarizing filters. After one side of the slide was cleaned, the slide was placed on the C

microscope so that the attached post-veligers could be counted. When slides became heavily infested, a subsampling technique was followed:

~ The first slide was counted in its entirety.

~ The remaining nine slides were subsampled using a splitter that permitted either half or a quarter of the slide to be counted. Counts were then extrapolated and adjusted, depending on the fraction used.

f Settlement rates were computed by taking the average value of the 10 slides and multiplying this value by 533.34 to obtain the density of zebra mussels per square meter. (One post-veliger/microscope slide equals 533.34 veligers per square meter.)

Shell diameters were measured on selected and random individuals to obtain maximum, minimum, and average sizes. Diameters were measured using an ocular micrometer calibrated to a stage micrometer.

AIV-16 rf$32294f2:20pm/b23494 Lawler, Matusky & Skelly Enginee .

CHAPTER 3 RESULTS AND DISCUSSION 3.1 WHOLE-WATER SAMPLING Sampling of planktonic veligers in the circulating water system was initiated on 27 May 1993 and completed on 16 December 1993. Thirty-six samples were taken (two per sampling date) from the station's intake forebay. The monitoring system, which was redesigned for this season, performed up to expectations. The addition of an electronic flowmeter provided data comparable to those of other researchers on the lake. As a result, direct comparisons with 1991 and 1992 data are difficult to make.

Results of sampling are presented in Figure 3-1 and Table 3-1. With the exception of the December sampling date, veligers were present in all samples collected. Two major peaks were observed: the first on 24 June (86,500/m ), the second on 11 October (108,950/m.).

Veliger presence throughout the monitoring program (except for December) suggests substantial densities of veligers in the water column for more than six months of the year. Heaviest spawning activity occurred in late fall, when lake temperatures were between 50'nd 60'F.

During the six weeks from early September to mid-October, veliger densities were consistently over 50,000/m, peaking at just over 100,000/m .

The effect of wind and wave action on the planktonic occurrence of zebra mussels was observed this season. The highest whole-water density (on October 11) was during 25+ mph westerly winds. Wave activity extended the mud line approximately half a mile offshore, which carried high sediment loads into the intake structure. Whole-water samples contained unusually large quantities of sand, silt, veligers, and post-veligers. Shell length data indicated that over 70%

of zebra mussels in the water column were of post-veliger size () 225 /im). This is indicative of the influence that storms can exert on veliger occurrence and the abundance of post-metamorphic zebra mussels. These larger mussels, which were physically detached from their AIV-17 rpf//02294/3:S1 pm/H 23494 Lawler, Matusky & Skelly Engineers

Figure 3-1 WHOLE-WATER SAMPLING PROGRAM VELIGERS PER CUBIC METER - D.C. COOK 1993 5/27 6/10 6/24 7/08 7/22 8/12 10/11 11/18 6/04 6/17 7/01 7/15 /30 10/21 12/16 Sa Date

TABLE 3-1

%HOLE-WATER SAMPLING PROGRAM VELIGERS PER CUBIC METER, D.C. COOK, 1993 DATE DENSITY (No./m3) 5/27/93 4,000 6/04/93 6/IQ/93 6/17/93 6/24/93 86,350 7/Ol/93 8550 7/08/93 12,900 7/15/93 11,200 7/22/93 3,700 7/30/93 7,400 8/12/93 '5,300 8/26/93 15,500 9/09/93 98,800 9/23/93 91,500 10/1 1/93 108,950 10/21/93 50,050 1 1/18/93 12/16/93 AIV-19

previous location, could impact water systems adversely by quickly resettling following a stor event.

3.2 ARTIFICIALSUBSTRATE SAMPLING 3.2.1 Circulating Water System Artificial substrate monitoring was conducted from 20 May to 16 December 1993. Periodic settlement rates for the circulating water system (forebay) are shown in Figure 3-2 and Table 3-2. The north and south locations are not shown because the artificial substrates placed at these locations, were damaged or destroyed by heavy water turbulence during two-unit operation. The center location, which is protected by a deflector wall, provided the most reliable location for settlement monitoring in the forebay.

Settlement of post-veligers first appeared in the forebay on 30 July and continued for th remainder of the sampling season. Post-veliger settlement peaked between 11 and 21 October, with an estimated average daily settlement rate of 72,197/mz (Figure 3-3). Average settlement rates in excess of 10,000 mz/day were observed between 23 September and 18 November.

There was no evidence of settlement on 15 July in the forebay from the cohort observed in the whole-water samples on 24 June. The heaviest spawning activity was first seen on 9 September and continued to 21 October. Heavy post-veliger settlement of the forebay was first observed on 23 September (sampling period from 9 to 23 September) at 165,274/mz. This equates to a daily settlement rate of 11,805/mz/day. These settlement rates continued to increase to a peak of over 72,000/mz/day between 11 and 21 October. Settlement remained relatively high between 21 October and 18 November at 31,086/m-/day. The larger size of these individuals suggests that either settlement occurred during the latter part of October or that many had translocated from elsewhere. Whole-water samples from 18 November showed light densities of primarily post-veliger-size mussels (approximately 200 pm) in the water column. Slides retrieved on 16 December were colonized at densities of over 90,000/mz. Based on size, these individuals were almost exclusively translocators that averaged 600 pm. The smallest AIV-20 rp//t02294/3:5ipm/H25494 Lawler, Matusky & Skelly Enginee

Figure 3-2 ARTIFICIALSUBSTRATE SETTLEMENT - FOREBAY LOCATION SETTLEMENT PER SQUARE METER, D.C. COOK 1993 June 4 July 1 July 30 Aug 26 Sept 23 Oct 21 Dec 16 June 17 July 15 Aug 12 Sept 9 Oct 11 Nov 18 Date Sampled

TABLE 3-2 ARTIFICIALSUBSTRATE SETTLEMENT-PERIODIC POST-VELIGER DENSITY PER SQUARE METER, D.C. COOK, 1993 DATE ESW-S ESW-R NESW-S NESW-R FOREBAY 6/04/93 6/17/93 7/01/93 320 320 1,547 7/15/93 5,013 373 7/30/93 427 12,267 NA'07 8/12/93 6,613 1,280 15,467 8/26/93 2,074 1,653 1,973 2,240 26,209 9/09/93 427 1,333 1,173 19,787 9/23/93 3,040 2,027 267 267 165,274 10/11/93 320 1,013 320 619,733 10/21/93 1,280 747 4,480 721,973 NA'67 11/18/93 213 320 533 870,411 12/16/93 53 53 107 92,908

'No sample - monitor disconnected or valve blocked, no water flow available.

AIV-22

e 3-3 ARTIFICIALSUBSTRATE SETTLEMENT - FOREBAY LOCATION AVERAGE DAILYSETTLEMENT PER SQUARE METER, D.C. COOK 1993 6$

o L

0) 0)

5 0) gJ 8

CtSco 4 (g

to 3

Q)

O L

0)

CD

)0) 2 7/15 to 7/30 8/1 2 to 8/26 9/9 to 9/23 10/11 to 10/21 11/18 to 12/16 7/30 to 8/12 8/29 to 9/9 9/23 to 10/11 10/21 to 11/18 Date Deployed to Date Recovered

individuals were about 350 pm, perhaps the result of the small spawn observed on I November.

Cumulative settlement rates are shown in Table 3-3. Forebay post-veliger densities generally increased during the season, but remained less than 25,000/m until the Clam Trol treatment on 11 September. Twelve days after the treatment, the density had increased to about 135,500/mz.

Densities increased to approximately 2 million/mz by 21 October. Substrates were then colonized by translocating adults, making accurate counts impossible in November and December. Translocating adults and juveniles also attached to the slides early in the program, before post-veliger settlement began. This additional surface area made assessment of early post-veliger settlement difficult. The accelerated settlement following the ClamTrol treatment exhibited the same trend noted on the periodic substrates for the following reasons:

~ Lack of predator adult mussels in the forebay to control veligers

~ Churned-up lake conditions in September, which brought more post-veligers into the intake,forebay from the open lake An abundance of clean substrate upon which to settle following the ClamTrol treatment Following the ClamTrol treatment, which coincided closely with the beginning of the heavy. fall spawn, post-veliger settlement in the center forebay location increased rapidly. Only 12 days after treatment, post-veliger densities had exceeded 100,000/mz. Over the next four weeks, post-veligers ranging in size from 175 to 500 pm settled on the artificial substrates at densities estimated at over 2 million/mz. As these individuals grew and larger individuals translocated into the sampling area, the resulting settlement densities made cumulative estimates impractical because the settlement racks had become completely encrusted.

3.2.2 Service Water Systems Periodic settlement densities for the service water systems are shown in Table 3-2 and Figures 34 and 3-5. Post-veligers first appeared on substrate collected from ESW return and NESW AIV-24 spf$ 32294I3:5 1 pmAl23494 Lawler, Matusky & Skelly Enginee

TABLE 3-3 ARTIFICIALSUBSTRATE SETTLEMENT-CUMUL4TIVE POST-VELIGER DENSITY PER SQUARE METER, D.C. COOK, 1993 DATE ESW-S ESW-R NESW-R FOREBAY 6/04/93 6/17/93 0 7/01/93 427 1,439 267 7/15/93 6,773 479 1,439 0 7/30/93 5,173 320 12,853 8/12/93 NA',333 5,280 586 693 11,786 8/26/93 6,133 3,040 2,346 24,053 9/09/93 9/23/93 NA'67 1,333 2,933 2,559 2,027 1,279 267 427 21,066 135,413 10/11/93 533 427 587 4,960 1.112M 10/21/93 NA* 3,093 2.059M 11/18/93 1,333 NA"

'No sample - monitor disconnected or valve blocked, no water flow.

Substrates colonized by translocated adults - post-veliger counts not possible. Many adults fell off during retrieval of apparatus; therefore, unable to make an accurate count.

rp//032994/I: 1 opm/H 23494/lbl-3-3 AZV-25

Figure 3-4 POST-VELIGER SETTLEMENT, NUMBER PER SQUARE METER ESSENTIAL SERVICE WATER SYSTEM, D.C. COOK PLANT 1993 700 100 Return 90 600 Supply 80 500 70 l6 tD 6$

60 400 /o Availability U

IE to (0 50 o.

(8 CL C 300 0 40 6$

C E 1 0

Z.'00 30 O

~O 20 100 10 June 4 July 1 July 30 Sept 23 Oct 21 Dec 16 June 17 July 15 Aug 12 Sept 9 Oct 11 Nov 18 t

Flg 3-5 POST-VELIGER SETTLEMENT, NUMBER PER SQUARE METER NON-ESSENTIAL SERVICE WATER SYSTEM, D.C. COOK PLANT 1993 M

Return C3 Supply t

70 >

t0 60

% Availability E

U) 50 CO C

0 CG 40 C

0 30 ao 10 June 4 July 1 July 30 Aug 26 Sept 23 Oct 21 Dec 16 June 17 July 15 Aug 12 Sept 9 Oct 11 Nov 18 Date Sampled

supply and return on 1 July. They did not appear in the ESW supply, however, until 1 August.

Peak settlement on the return side of the ESW system occurred between 30 July and 12 August (6613/m2). Peak settlement for the supply side was observed between 9 and 23 September (3040/m2). The highest post-veliger densities observed on the return side of the NESW systems occurred between 23 September and 11 October (9066/m2). Peak for the supply occurred during the latter half of August (1973/m2).

Both systems are scheduled to be chlorinated for one 155-min period per day at 1.5 to 2.0 ppm TRC.'his schedule is not always met because of mechanical breakdowns and other problems.

During the 1993 sampling season, the chlorination schedule was interrupted on a number of occasions. Days without chlorination or with no TRC data for the ESW and NESW of both Unit 1 and Unit 2 are summarized in Table 3P. (The full data set is presented in Appendix A.)

This table indicates that the chlorination system operated well during May and June. However, for 21 and 15 days in July, there was no chlorination in the ESW and NESW systems, respectively. This continued in the ESW system for 18 of the first 19 days in August. The NESW chlorination system was out of service for the first few days in August (Unit 1) and the last eight days of, the month (both units). Chlorination in September was unreliable during the first half of the month, but was more reliable in both service water systems during the latter half. During the first 10 days of October, there was no chlorination in the NESW system and

'at least five days were missed in the ESW system. Chlorination in both systems was fairly reliable for the remainder of the sampling season.

Another method of presenting the problems encountered by the chlorination system is to assess it in terms of percent availability for each month. Table 3-5 shows this availability to each service water system for both Unit 1 and Unit 2 and reflects the number'f days during which chlorination occurred each month. As can be seen, all systems operated between 90 and 94%

during May and June. Settling rates in the service water systems during these two months reflect the effectiveness of the chlorination system during periods of low densities. As the chlorination schedule was increasingly missed during July, August, September, and October, AIV-28 rpM)32494/2A)7pm/H23494 Lawler, Matusky & Skelly Enginee

TABLE 34 (Page 1 of 3)

SUMMARY

OF DATES CHLORINATIONSYSTEM WAS OUT OF SERVICE OR NO TRC DATA AVAILABLE DATE May 1 NC NC NC NC 2 NC NC NC NC 10 ND'C~

11 NC NC NC 12 ND 18 ND 20 ND June 1 NC NC NC NC 14 ND ND ND ND 15 ND ND 16 ND ND 17 ND ND 18 NC NC NC NC July 1 NC NC 2 NC NC NC NC 6 NC NC NC NC 7 NC NC NC NC 8 NC NC 12 NC NC 13 NC NC 14 NC NC 15 NC NC 16 NC NC 17-25 NC NC NC NC 28 NC NC NC NC 29 NC NC NC NC 31 NC NC August 1 NC NC NC 2 NC NC NC

'ND No TRC.data, but chlorination occurred.

~NC No chlorination.

AIV-29

TABLE 34 (Page 2 of 3)

SUMMARY

OF DATES CHLORINATIONSYSTEM WAS OUT OF SERVICE OR NO TRC DATA AVAILABLE UNIT 1 DATE August (Conlt'nued) 3 NC NC NC 4 NC NC 5 NC NC 6 NC NC 7 NC NC 8 NC NC NC 9 NC NC NC 10 NC NC 11 NC NC 12 NC NC 13 NC NC 15 NC NC 16 NC NC 17 NC NC 18 NC NC 19 NC NC 24-27 NC NC NC NC 28 NC NC 29 NC NC 30 NC NC 31 NC NC September 1 NC NC NC NC 2 NC NC 3 NC NC 4 NC NC NC NC 5 NC NC 6 NC NC 8 NC NC 9 NC NC NC NC

'10 NC NC NC NC 11 NC NC NC NC o c orlnauon.

AIV-30

TABLE 34 (Page 3 of 3)

SUMMARY

OF DATES CHLORINATIONSYSTEM WAS OUT OF SERVICE OR NO TRC DATA AVAILABLE UNIT 1 UNIT 2 DATE NESW September (Conrinued) 12 NC NC NC NC 'C 13 NC NC NC ~

14 NC NC NC NC 15 NC NC NC NC 16 NC NC 17 NC NC NC NC 27 NC 28 NC NC 29 NC NC 30 NC NC October 1' NC  :

NC NC NC 3 NC NC 4 NC NC NC NC 5-10 NC NC NC NC 12 NC NC NC NC 15 NC NC 18 NC 29 NC NC NC NC November 18 NC NC NC NC 19'0 NC NC NC NC NC NC 21-23 NC NC 24 NC NC 29 NC NC AIV-31

TABLE 3-5 PERCENT AVAILABILITY OF CHLORINATION SYSTEM FOR SERVICE WATER SYSTEMS May-November 1993 UNIT I UNIT 2 MONTH NESW NESW May June 93.3 93.3 93.3 93.3 July 32.3 51.6 32.3 51.6 29.0 64.5 29.0

'7.7 August September 63.3 40.0 63.3 36.7 October 67.7 58.1 70.0 58.1 November 73.3 93.3 73.3 93.3 AIV-32

chlorination system availability ranged from 29 to 68% in the ESW system and from 36 to 68%

in the NESW system. Settling increased in both service water systems during this same period.

This reduction in chlorine availability occurred during the peak spawning period and enhanced the vulnerability of the service water systems to post-veliger settling.

The bioboxes were placed in the chlorinated service water systems at locations carrying low flows (less than 5 cfs), which allowed post-veliger settlement if chlorination was ineffective.

The settlement rates observed on the substrates examined periodically thus reflect the effectiveness of the chlorination program as administered during the 1993 sampling season.

The service water systems data presented in Table 3-2 reflect the problems experienced in delivering chlorine to these systems during 1993: peak settlement densities in the ESW return system between mid-July and mid-August; in the ESW supply system between the end of August and the end of September; in the NESW return system between the third week of September and the third week of October; and in the NESW supply system between the month of August and early September. These periods of peak. densities generally followed periods when the chlorination system was out of service for extended periods in the respective service water systems. It is also evident that as the chlorination system became more reliable (third week of October to mid-December), post-veliger settlement in the service water systems was controlled.

Post-veligers were available in the water column as settlement rates in the forebay remained high (92,908 to 870,411/m2) during this same period.

A comparison of densities on the return side of the service water systems with those on the supply side shows that on most sampling dates more settlement occurred on the return side.

This suggests that the concentration of chlorine reaching the return side was reduced and less effective. This was most likely the result of chlorine uptake in the water column before the dosage reached the return side.

Review of the settlement rates in the service water systems (all sampling locations combined) indicates that rates were in excess of 1000/m"- in 16 of the 50 samples (32%). These rates are cause for concern in the operation of the service water systems. Considering the chlorination AIV-33 rpf/032494/2 cpm/H 23494 Lawless, Matusky dk Skelly Engineers

schedule followed in 1993, settlement rates between 0 and 100 are the best that could be expected. One reason is that the 155 min of continuous, i.e., interrupted, chlorine injection was followed by 21 hrs 25 min of no treatment. To be most effective, chlorination should be administered in four or five doses at 5 to 6-hr intervals. At these time intervals chlorine agitates post-veligers throughout the day, causing them not to put out bysal threads or to detach their temporary bysal threads and resuspend in the water column. To eliminate settling, a continuous (24 hrs/day) chlorination schedule may be necessary in light of the high number of veligers and post-veligers present in the intake water during the sampling season.

Cumulative settlement data collected from the side stream samplers located on the service water systems did not meet expectations. The increase in post-veliger densities followed by an increase in shell length over the course of the sampling season occurred only to a limited extent.

Post-veliger/juvenile development proceeded until shell lengths attained 1.5 mm. No live juveniles with greater shell lengths were found inside the samplers or on the artificial substrates until the last sampling date, when three individuals ranging from 3 to 5 mm were observed in

the NESW return sampler. The 1.5-rtim "size limit" continued after peak densities were observed in the two systems (15 July on the return side of the ESW system and 11 October on the NESW system). It was obvious that larger zebra mussels found the samplers unsuitable habitat and either translocated or died. Mortality inside the samplers was difficult to estimate because of the silt accumulation and the transport of shells and shell fragments into the samplers from other locations in the system. Possible causes of this observed size limit phenomenon are chlorination activities, temperature fluctuations, light intensity, high noise levels, or some combination of these factors. Others have observed that post-veligers and juveniles can relocate to avoid stress. Irrespective of the reasons for the observed phenomenon, continued growth over the course of the season did not occur. It has been assumed that conditions in the sidestream samplers reflect conditions in the low-velocity-flow service water systems; therefore, the results reported here can be transferred to these systems. However, as a practical matter, the problem resulting from the 1993 ClamTrol treatment in the control room air conditioning system and plant air compressor suggests that continued growth may occur in some areas of service water systems despite chlorination. Therefore, the results of the cumulative substrate studies are promising but should be used with caution until more information has been collected.

AIV-34 CfN32894/2: i6pm/fi23494 Lawler, Matusky & Skelly Enginee .

CHAPTER 4,

SUMMARY

AND RECOMMENDATIONS 4.1

SUMMARY

Whole-water and artificial substrate sampling was initiated on 27 May 1993 and continued to 16 December 1993. Two spawning peaks occurred, in the third week of June and again in the period from September to mid-October. The second peak was the peak spawning period of the season.

Peak post-veliger settlement, as indicated by average daily settlement, occurred during the 11-21 October period. Considering the peak period of veliger density in the whole-water samples, this was expected. The following conditions also contributed to settlement:

~ Churned-up lake conditions resulting from high winds

~ Lack of predator adult mussels and uninhabitated substrate resulting from the September Clam Trol treatment I

The timing of the ClamTrol treatment, the peak spawning activity, and lake conditions coincided to produce heavy post-veliger settlement in the forebay.

Post-veliger settlement in the service water, systems depended more on chlorination frequency than on availability of post-veligers. Periods of heaviest settlement (mid-July to the third week of October) in the ESW and NESW systems corresponded to periods of no chlorination (see Tables 3-2 and 3Q). When the chlorination system was functioning properly, settlement in,the service water systems was controlled as well as it could be, considering the chlorine delivery schedule. Specifically, the period of heaviest settlement in the forebay (which is not chlorinated) occurred between 21 October and 16 December 1993. During this same period, the chlorination schedule was maintained and settlement in the service water systems was low (less than 600/m~).

AIV-35 Lawler, Matusky A Skelly Engineers

Results stemming from the cumulative settlement element of the monitoring program showed that initial post-veliger settlement took place as expected, but that growth of individuals during the course of the season did not occur. A maximum shell length of approximately 1.5 mm was reached but not exceeded. Possible explanations include mortality and/or stress-induced translocation of the juveniles out of the samplers. This was caused by a hostile environment that included chlorination among other potentially adverse factors. With the exception of chlorine, these factors could not be measured by the program as designed.

4.2 RECOMMENDATIONS Based on observations made during the course of this program, LMS makes several recommendations:

~ Whole-water sampling should be initiated in April to determine the presence of veligers in the water column.

~ Studies of post-veliger settlement substrates should be conducted from May (substrate set in April) through December. A special study currently being conducted will determine the need for winter post-veliger settlement sampling.

~ The chlorination system and schedule should be upgraded to ensure appropriate intermittent or continuous delivery of chlorine to control post-veliger settlement.

~ An observation made during 1993 (no treatment of the intake tunnels) suggests that the Cook plant can expect to see potentially heavy densities of veligers and post-veligers in the circulating and service water systems. It is reasonable to conclude that a substantial portion of these mussels come from spawning adults currently living in the intake tunnels. 1&M should consider continuous treatment of these tunnels to prevent post-veliger settlement in these areas.

AIV-36 CF/022894/2: l8pm/ll22494 Lawler, Matusky & Skelly Enginee

APPENDIX A AXV-37

i%AY CHLORINATION - VMT 1 End of Pi e Avera e TR - 155 min/da Date irc ave m ~ESW m NEW m 5/3/93 0.17 1.57 2.90 5/4/93 0.15 7.54 5/5/93 0.17 1.20 6.12 5/6/93 0.14 0.85 5.04 5/7/93 0.19 0.72 1.00 5/8/93 0.19 1.81 2.97 5/9/93 0. 18 1.08 1.20 5/10/93 0.14 ND 6.45 5/11/93 5/12/93 0.16 ND 1.81 5/13/93 0.12 3.75 2.33 5/14/93 0.12 ND 1.53 5/l5/93 0.17 1.25 3.55 5/16/93 0.16 2.35 4.87 5/17/93 0.14 0.96 2.14 5/18/93 0.16 ND 6.65 5/19/93 0.14 4.68 6.37 5/20/93 0.10 ND 3.30 5/21/93 0.11 4.75 2.13 5/22/93 0.14 0.40 2.22 5/23/93 0.09 0.43 3.85 5/24/93 0.08 0.27 3.18 5/25/93 0.09 0.44 3.02 5/26/93 0.07 3.62 6.03 5/27/93 0.10 2.32 8.14 5/28/93 0.08 0.58 1.10 5/29/93 0.12 0.70 5.50 5/30/93 0.11 4.23 1.30 5/31/93 0.10 0.48 4.38 Average 0.13 1.72 3.80 Comments: 1) No chlorination performed on 5/11/93 due to low supply NaOCL

2) ND - No Data - however, chlorination performed AXV-38

iVIAY CHLORINATION - UNIT 2 End of Pi e Avera e TRC - 155 min/dav Date Circ ave m ~ESW m NEW m 5/3/93 , 0.18 3.07 7.75 5/4/93 0.16 3.34 4.87 5/5/93 0.18 2.83 1.32 5/6/93 0.16 1.90 1.12 5/7/93 0.19 1.90 1.75 5/8/93 0.20 2.89 3.13 5/9/93 0.18 3.10 5.90 5/10/93 0.16 3.65 1.75 5/11/93 5/12/93 0.16 1. 16 4.50 5/13/93 0.14 1.76 6.49 5/14/93 0.16 1. 15 5.24 5/15/93 0.18 1.98 3.12 5/16/93 0.18 1.11 1.41 5/17/93 0.19 0.40 5.79 5/18/93 0.19 1.70 1.80 5/19/93 0.23 2.10 2 26 5/20/93 0.18 4.80 3.20 5/21/93 0.20 2.26 3.38 5/22/93 0.17 0.88 4.50 5/23/93 0.19 4.22 1.33 5/24/93 0.14 1.07 3.05 5/25/93 0.19 5.30 0.65 5/26/93 0.18 3.55 1.50 5/27/93 0.19 2.11 2.10 5/28/93 0.18 5.56 4.08 5/29/93 0.18 4.90 1.95 5/30/93 0.20 0.40 3.18 5/31/93 0.20 1.48 4.74 Average 0.18 2.52 3.28 Comments: I) No chlorination performed on 5/11/93 due to low supply NaOCL AIV-39

JUNE CHLORINATION - MilT 1 End of Pi e Avera e TRC - 155 min/dav Date Circ ave m ~E~>~W)g) m ~NESW m 6/2/93 0.14 0.55 0.76 6/3/93 0.18 3.10 5.30 6/4/93 0.15 0.95 2.70 6/5/93 0.11 P 2P 1.50 6/6/93 0.13 0.36 0.85 6/7/93 0.14 0.75 6.90 6/8/93 0.16 1.40 5.70 6/9/93 0.13 0.45 5.00 6/10/93 0.13 0.83 2.55 6/11/93 0.11 0.35 1.75 6/12/93 0.17 2.50 0.70 6/13/93 0.11 0.25 6.50 6/14/93 .045 ND ND 6/15/93 .085 ND 2. 10 6/16/93 .097 ND 1.54 6/17/93 0.07 ND 4.40 6/19/93 0.11 3.80 4.20 6/20/93 0.10 0.20 3.05 6/21/93 0.04 0.30 1.55 6/22/93 0.07 0.20 2.10 6/23/93 0.12 0.15 3.50 6/24/93 0.08 . 0.20 1.40 6/25/93 0.09 0.16 2.10 6/26/93 .075 0.10 1.80 6/27/93 0.08 0.08 2.45 6/28/93 .063 0.02 0.50 6/29/93 0.08 0.05 8.50 6/30/93 0.10 0.30 0.62 Average .106 0.72 2.96 Comments: 1) ND - no data - however, chlorination was performed Ajv-40

JUNE CHLORINATION - UNIT 2 End of Pi e Avera TRC - 155 min/da Date Circ ave ~ESW m NEW m

.6/2/93 0.16 0.42 4.80 6/3/93 0. 17 0.85 1.45 6/4/93 0.16 1.10 0.85 6/5/93 0.16 1.00 0.90 6/6/93 0.18 0.40 1.50 6/7/93 0.16 1.00 3.40 6/8/93 0.18 9.80 2.10 6/9/93 0.20 0.85 3.60 6/10/93 0.19 5.25 3.20 6/11/93 0.20 3.20 4.50 6/12/93 0.19 1.40 2.90 6/13/93 0.18 0.25 1.50 6/14/93 0.19 ND ND 6/15/93 0.18 ND 3.70 6/16/93 .183 ND 4.62 6/17/93 0.17 ND 2.60 6/19/93 0.16 2.90 3.80 6/20/93 0.18 0.20 4.04 6/21/93 0.17 0.55 5.25 6/22/93 0.18 0 27 5.10 6/23/93 0.20 0.18 3.80 6/24/93 0.20 0.15 3.40 6/25/93 0.17 0.15 2.70 6/26/93 0.16 0.13 2.40 6/27/93 0.14 0.09 2.68 6/28/93 .122 0.03 1.38 6/29/93 .165 0.07 4.31 6/30/93 .185 0.35 2. 12 Average .174 1.27 3.06 Comments: 1) ND - no data - however, chlorination was performed AIV-41

JULY CHLORINATION - UNIT 1 En f Pi Av ra TR -1 min D~

7/1/93 i v 0.05 m E$ W~)m 7.00

~cpm 7/3/93 0.09 0.06 1.71 7/4/93 0.08 '0.04 14.64 7/5/93 0.06 0.02 0.64 C

7/8/93 0.02 4.95 7/9/93 .065 0.60 0.69 7/10/93 0.13 4.20 10.0 7/11/93 0.03 '0.21 '7.70 C

7/12/93 0.02 4.49 7/13/93 0.02 4.30 7/14/93 0.02 2.31 7/15/93 0.02 7.23 7/16/93 '0.02 3 43 7/26/93 .065 0.02 3.35 7/27/93 0.04 0.01 0.75 7/28/93 '0.02 7/30/93 .033 c1.75 1.80 7/31/93 .063 1.60 Average 1.39 4.23 Comments: ~ 'SW chlorination lasted 65 mins. due to flowmeter fouling ESW/NESW chlorination only - line break

'ot chlorinated 4

Duration 105 minutes

'SW secured afler 40 min. (Circ water 115 minutes) r Duration 10 minutes Note: No chlorination performed on 7/2, 7/6, 7/7, 7/17-25, 7/29 "

AIV-42

JULY CHLORINATION - UNIT 2 En FPi Av ra e TR -1 min i v m ~E~m 7/1/93 0.07 11.4 7/3/93 0.11 0.06 0.15 7/4/93 0.13 .05 0.81 7/5/93 0.18 0.03 4.56 C

7/8/93 0.02 , 4.28 7/9/93 0.15 0.02 9.49 7/10/93 0.16 1.00 1 40 7/11/93 0.02 '0.21 '0.73 C

7/12/93 0.02 4.77 7/13/93 0.02 3.00 7/14/93 0.02 6.53 7/15/93 0.02 4.28 7/16/93 '0.02 '6.80 7/26/93 0.13 0.02 1.30 7/27/93 0.14 0.01 6.37 7/28/93 '0.02 7/30/93 0.12 '0.45 2.40 7/31/93 0.16 2.70 Average ,088 1.33 3.72 Comments: t 'SW chlorination lasted 65 mins. due to flowmeter fouling ESW/NESW chlorination only - line break

'ot chlorinated 1

~

Duration 105 minutes

'SW secured after 40 min. (Circ water 115 minutes) r Duration 10 minutes Note: No chlorination performed on 7/2, 7/6, 7/7, 7/17-25, 7/29 Ajv-43

AUGUST CHLORINATION - UNIT 1 End of Pi e Avera e TRC - 155 min/dav Date Circ ave m ~ESW m ~NESW m 8/1/93 .025 8/2/93- .025 8/3/93 . .025 8/4/93 .045 .47 8/5/93 .043 1.8 8/6/93 .065 5.2 8/7/93 .143 5.4 8/8/93 .14 2.66 8/9/93 .165 1.8 8/10/93 0:07 .15 8/11/93 0.12 3.15 8/12/93 0.06 2.3 8/13/93 'o.o5 2.3 8/14/93 0.09 5.0 8/15/93 0.10 2.89 8/16/93 0.076 5.5 8/17/93 0.074 7.96 8/18/93 0.042 .59 8/19/93 .068 5.0 8/20/93 .10 .25 8/21/93 .03 11.0 8/22/93 .08 2.65 8/23/93 .05 1.55 .20 8/28/93 .035 .55 (.00001 8/29/93 .14 1.65 8/30/93 .17 1.07 8/31/93 .15 1.92 Average .13 2.58 4.05 Comments: 'SW system leak - no chlorination NESW system leak - no chlorination

'ESW system maintenence - no chlorination Note: No chlorination performed on 8/24-27 due to system maintenence AIV-44

AUGUST CHLORINATION - UNIT 2 End of Pi e Avera e TRC - 155 min/dav Date ~EWE ~NESW m 8/1/93 .188 1.65 8/2/93 .175 4.35 8/3/93 .2 5.7 8/4/93 .18 7.6 8/5/93 .193 5.3 8/6/93 '.145 d2 4 8/10/93 0. 18 ~ 3 8/11/93 b0. 15 2.25 8/12/93 0.18 2.0 8/13/93 '0.19 1.37 8/14/93 '0.20 r85 24 C

8/15/93 0.15 1.63 8/16/93 0. 184 2.42 8/17/93 0. 172 .78 8/18/93 0.184 "7 30 8/19/93 .170 8/20/93 .20 2 20 1.0 8/21/93 '7 8.80 .07 8/22/93 '. 13 1272 3.70 8/23/93 .168 1.10 8.0 I

8/28/93 .12 .40 8/29/93 .11 1.88 8/30/93 .09 2.20 8/31/93 .11 1.62 Average .15 2.31 3.22 Comments:

• 2-GRV-521 only diffuser open on U-2 2-GRV-522 only diffuser open on U-2

'-GRV-523 only diffuser open on U-2 4 2-GRV-524 only diffuser open on U-2

'ESW system down - broken valve

'RV-530 busted after daily clorination d 2-CL-132 just barely cracked open

" Bias flow to 2 NESW

'o data Note: No chlorination performed on 8/7-9. and 8/24-27 due to system maintenence AIV-45

1 SEPTEMBER CHLORINATION - UNIT 1 End of Pi e Avera e TRC - 155 min/dav Date Circ ave m ~ESW m 9/2/93 0.15 1.62 9/3/93 0.06 1.33 9/5/93 0. 12 4.58 9/6/93 0.11 1.90 9/6/93 0.14 1.72 9/7/93 .115 1.67 1.71 9/8/93 .088 2.16 9/16/93 .055 4.21 9/18/93 .185 1.86 21.5 9/19/93 0.14 1.26 15.8 9/20/93 .130 1.23 '.67 9/21/93 .118 1.81 5.38 9/22/93 .143 8.02 2.93 9/23/93 .120 1.28 2.34 9/24/93 '0.1 1 0.95 2.34 9/25/93 .17 2.65 6.56 9/26/93 .155 4.65 6.89 9/27/93 d

.14 .56 d

9/28/93 13 88 9/29/93- d

.14 .42 9/30/93 d

.13 2 4 Average .13 2.15 6.94 Comments: 'hlorination for 60 minutes only on CIRC

~

Chlorination for 80 minutes

'ESW system down for maintenance d

No data Note: No chlorination Sept:1,4,9-15,17 due to maintenance or repairs AIV-46

SEPTEiVBBER CHLORINATION - UNiIT 2 End of Pi e Avera e TRC - 155 min/dav irc ave ~ESW m ~NESW m 9/2/93 0.09 1.91 9/3/93 0.08 P2 9/5/93 0.10 3.63 9/6/93 ')

0.08 2P 9/6/93 0.10 .12 9/7/93 .073 1.65 3.55 9/8/93 .085 'l '75 9/16/93 . 108 23.0 9/18/93 .18 1.95 2.89 9/19/93 0.16 1.47 2.77 9/20/93 .17 .74 2.15 9/21/93 .16 2.43 1.87 9/22/93 .173 .10 2.78 9/23/93 .180 .05 3.82 9/24/93 '0.21 P 22 2.51 9/25/93 .18 1.65 1.39 9/26/93 .20 2.56 1.45 9/27/93 .17 .46 d

9/28/93 b.ls b 1.03 9/29/93 d

.15 4.75 9/30/93 .15 2.75 Average .14 1.60 Comments: 'hlorination for 60 minutes only on CIRC Chlorination for 80 minutes

'ESW system down for maintenance d

No data Note: No chlorination Sept:1,4,9-15, 17 due to maintenance or repairs Ajv-47

OCTOBER CHLORINATION - UNIT 1 End of Pi e Avera e TRC - 155 min/dav Date irc ave E!~Wpgm ~NESW m 10/1/93 0.10 3.78 10/2/93 0.11 1.88 10/3/93 0.15 2.75 10/4/93 '0.10 10/1 1/93 bo.lS 0 07 b8 2 10/13/93 .17 0.68 5.35 10/14/93 .20 3.02 4.6 10/15/93 .19 3.19 10/16/93 .19 4.8 5.6 10/17/93 0.18 3.86 5.65 10/18/93 .17 2.45 10/19/93 .152 2.18 3.89 10/20/93 '. l l cl 97 '3.21 10/21/93 .15 3.72 4 74 10/22/93 0.14 1.44 4.73 10/23/93 .186 4.15 4.65 10/24/93 .14 1.49 4.5 10/25/93 .11 2.41 3.3 10/26/93 .11 3.3 .65 10/27/93 .16 .5 4.2 10/28/93 .14 1.64 6.05 10/30/93 .17 5.2 2.95 10/31/93 .15 4.2 3.22 Average .15 2.68 4.33 Comments 'hlorination stopped after 30 minutes due to massive failure of GRV Chlorination for 130 minutes

'hlorination for 133 minutes 4

NESW down for repair Note: No chlorination Oct 5-10 due to a control valve leak On October 12, Circ not treated, ESW and NESW treated cominuous On October 29, whole system treated for 15 minutes only AIV-48

OCTOBER CHLORINATION - UNIT 2 End of Pi e Avera e TRC - 155 min/dav lrc ave m ~ESW m ~NESW m 10/1/93 .19 3.15 10/2/93 0.19 2.58 10/3/93 0.22 2.15 10/4/93 '0.14 10/11/93 b0.16 '2.0 b.82 10/13/93 .17 1.90 0.98 10/14/93 .19 3.20 .1.42 10/15/93 20 3.45 10/16/93 .187 2.95 3.25 10/17/93 0.17 3.56 4.21 10/18/93 .16 .35 4.92 10/19/93 .073 3.07 3.21 10/20/93 '. l l c2 87 '2.89 10/21/93 .135 3.87 4.05 10/22/93 0.16 1.85 .72 10/23/93 .19 2.45 3.25 10/24/93 .17 2. 12 1.48 10/25/93 .13 3.13 2.55 10/26/93 .15 3.05 8.20 10/27/93 .15 1.32 3.15 10/28/93 . .16 2.80 2.48 10/30/93 .15 1.85 5.69 10/31/93 .17 0.98 5.85 Average .16 2.48 3.28 Comments. 'hlorination stopped after 30 minutes due to massive failure of GRV Chlorination for 130 minutes

'hlorination for 133 minutes 4

NESW down for repair Note: No chlorination Oct 5-10 due to a control valve leak On October 12, Circ not treated, ESW and NESW treated continuous On October 29, whole system treated for 15 minutes only 4

AIV-49

NOVEiVBBER CHLORINATION - UNIT 1 End of Pi e Avera e TRC - 155 min/dav Date Circ ave m ~ESW m ~NESW m 11/1/93 0.10 .22 3.62 11/2/93 0.11 .10 4.80 11/3/93 0.11 0.11 7.84 11/4/93 0.10 0.14 7.90 11/5/93 0.11 0.09 5. 12 11/6/93 .11 . 0.14 3.3 11/7/93 .12 0.30 4.11 I .13 0.12 2 40 1/8/93'1/9/93

.10 .15 4.10 11/10/93 0.10 3.1 3.05 11/11/93 .08 3.39 4.59 11/12/93 .13 2.29 4.45 11/13/93 .11 2.36 8.26 ll/14/93 .10 1.25 2.05 11/15/93 0.15 2.40 5.82 11/16/93 .13 0.51 3.72 11/17/93 .16 0.46 4. 34 b

11/18/93 '.02 11/19/93 .15 b

6.04 U

11/20/93 .11 11/24/93 .12 12.5 11/25/93 .15 .72 5.88 11/26/93 .14 .56 2.98 11/27/93 .11 .90 3.27 11/28/93 .16 1.42 6.12 11/29/93 .15 7.89 11/30/93 .13 .73 2.75 Average .12 .98 5.08 Comments: 'hlorination run for 91 minutes ESW control valve leak - no chlorination Note: No chlorination Nov 21-23, ran low on chlorine AIt/-50

NOVEMBER CHLORINATION - UNIT 2 End of Pi e Avera e TRC - 155 min/dav Date Circ ave m ~ESW m ~i~SW m 11/1/93 .14 14 6.85 11/2/93 .14 .05 5.41 11/3/93 .11 .10 3.84 11/4/93 .11 .14 .26 11/5/93 .14 .09 6.44 11/6/93 .14 14 8.5 11/7/93 .17 .07 8.01 11/8/93 .18 .16 9.65 11/9/93 .16 .10 7.30 11/10/93 .15 3.1 6.85 11/11/93 .16 2.65 6.25 11/12/93 1.42 4.60 11/13/93 .15 2.12 1.50 11/14/93 .17 1.8 7.22 11/15/93 .19 2.92 4.75 11/16/93 .19 0.10 9.30 11/17/93 .19 0.27 7.76 s b 11/18/93 04 b

11/19/93 .16 b

11/20/93 .17 4.76 11/24/93 .11 6.9 11/25/93 .19 .78 3.98 11/26/93 .18 .65 7.06 11/27/93 .18 1.55 5.27 11/28/93 .17 1.48 3.58 11/29/93 .17 3.30 11/30/93 ~ .20 1.75 9.71 Average .16 .98 5.96 Comments: 'hlorination run for 91 minutes ESW control valve leak - no chlorination Note: No chlorination Nov 21-23, ran low on chlorine AIV-51

DECEMBER CHLORINATION End of Pi e Avera e TR -155 min/da Date irc ave m ~ESW m NEW m UNIT 1 12/1/93 .13 .16 2.65 12/2/93 .16 .56 6.42 12/3/93 .11 .96 6.75 12/4/93 (.02 .03 1.25 12/5/93 (.02 (.02 (.02 Average .08 .34 3.41 UNIT 2 12/1/93 .20 2.05 8.50 12/2/93 .17 .88 4.35 12/3/93 .12 1.32 .93 12/4/93 (.02 .02 .27 12/5/93 (.02 (.02 (.02 Average .10 .85 2.81 AIV-52

Srand Utility Services, Inc Quality Results from Quality People 28 June 1993 Eric Mallen, Senior Performance Engineer Indiana Michigan Power Company D.C. Cook Nuclear Power Station One Cook Place Bridgman, MI 49106

Subject:

Zebra Mussel Infestation Report The attached report represents the completion of the underwater Zebra Mussel inspection performed within the screenhouse, west of the T .H.S . and Trash-racks Units 1 &'. If you have any questions or comments with respect to this report, please feel free to contact either Todd Miller or myself at your convenience.

Sincerely,'homas E. Owczarzak BUSI Site Coordinator Underwater Construction Division cc: J. Carlson I&M K. Tamms AEP J. Lawton BUS I B. Feeley BUS I T. Miller BUS I Job File 80021 AZV-53 740 W. Western Avenue Muskegon, Michigan 49440 (6l 6) 726-4016 Fax (616) 722-7200

Indiana and Michigan Power Company D.C. Cook Nuclear Power Station Units 1 and 2 Zebra Mussel Infestation Report 28 June 1993 Indiana and Michigan Power Company Contract Number C-8484 Brand Uti.lity Services, Inc. Job Number 80021 Site Coordinator: Thomas E. Owczarzak Foreman/Shift Supervisor: Todd Miller AIV-54

TABLE OF CONTENTS

1. 0 Purpose

2. 0 L imitations 3.0 Enspection Techique

4. 0 F indings 4.1 T.H.S. Bays 4.2 Trashracks 4.3 Keyways 4.4 Deflector Halls 5.0 Comments and Recommendations AlV-55

Indiana and Michigan Power Company D.C. Cook Huclear Power Station Units 1 and 2 Zebra. Mussel Infestation Report 28 June 1993 1.0 Pgzpggy The specific areas of concern were as follows:

T .H .S . Bays

-Vertical walls

-Hest(lake side) face of T.H.S .

-East(pump side) back of trashracks/columns Trashracks

-Hest(lake side) face of trashracks

-Hest(lake side) face of support columns Keyways

-Vertical face north/northwest side

-Vertical face south/southwest side Deflector Halls

-Vertical face west(lake side)

-Vertical face east(pump side)

This report is intended to be used-in coniunction with the detailed videotape documentation of the inspections which is being submitted along with this report.

2.0 Limitations Visibility:

THS Bays 5-7 Trashracks Keyways 5-6 3-5 ft ft..

Deflector Halls- 5-7 ft.

Current: .

THS Bays Trashracks 1-2 1-3 ft. p/sec.

p/sec .

Keyways 1-3 p/sec .

Deflector Halls f west side 4 t . p/sec .

east side negligible

I & M Power Company D.C.Cook Nuclear Station

~ ~

Zebra Mussel Report 28 June 93 Hater Temperature:

THS Bays 56 degrees +/-

Trashracks 56 degrees +/-

Keyways .56 degrees +/-

Deflector Halls 56 degrees +/-

Operating Status:

THS Bays Units 1 &: 2 generating power Trashracks Units 1 & 2 generating power Keyways Units 1 Bc 2 generating power Deflector Halls Units 1 &: 2 generating power Access:

THS Bays Permanent plant access ladders Trashracks Temporary Divers ladder Keyways Temporary Divers ladder Def lector Temporary Divers ladder 3.0 Znspsaf~an Tsahaiuuo Crew:

1 'Shif t Foreman 1 - Inspection Diver 1 - Tender Equipment:

1 -.. Set surface-supplied di'ving equipment 1 - U/H video camera/surface support equipment 1 Divers hot-water system 1 - Back-up/emergency air supply system Method: ~

THS,Bays - The diver enters the THS bay through the permanent manways in the screenhouse floor descending down the access ladder to the water level, at this point the diver begins his/her dive, leaves surface and continues to bottom of THS bay. The diver now begins the detailed inspection by sight, touch, and measuring. Next the diver performs an U/H (underwater) video inspection of the findings .

AIV-57

I & M Power Company D.C.Cook Nuclear Station Zebra Mussel Report 28 June 93 Method (continued):

Trashracks, Keyways, Deflector Halls The diver entezs the main-forebay through the removable-grating descending down the temporary divers ladder which is secured to the trashracks and support members. Once the diver reaches the water level he/she has appzox: 10'. of ladder left to use in the descending process, at this point the diver physically climbs down the trashrack until reachin'g bottom. The diver now begins a detailed inspection by sight, touch, and measuring. Next the diver performs an U/H (underwater) video inspection of the findings.

Huis: The ahba maiha¹a aza uazfazmad azar sod mar agaiu uoiil alj, iaaueciiao'a are aamplaia

4.0 Findings

The zebra mussel inspection revealed a high percentage of mussel growth, 90% of the mussel coverage was a make up mussels on y /8" to 1/2" in size. Generally the heaviest mussel covezage is in the areas with moderate to high flow, with the extremely high and flow areas heing less populated. What the diver found was that in the most populated azeas the mussels were several layers thick.

NOTE: All areas inspected were completely water blasted clean approx: 1 year ago.

4.1 T.H.S. Bays:

From the bottom of the bay (elevation 546) up approx:

15'elevation 531) the walls have 100% coverage and in many areas the mussels are several layers thick.

Prom the 15'ark (elevation 531) the mussel coverage decreases to approx: 80% and continues to thin out until there is no apparent mussel growth.

1-2 Relativity the same conditions exsists as in THS 1-1

8c H Power Company D.C.Cook Nuclear Station Zebra Mussel Report 28 June 1993 4.1 T.H.S. Bays (continued):

1-3 From the bottom of the bay (elevation 546) up approx:

15'elevation 561) the walls have 100% coverage and several layers thick. From the 15'ark there is 80%

single layer coverage, at the 25'ark there is very little growth.

1-4 From the bottom of the bay (elevation 546) up approx:

18'elevation 564) the walls are covered approx: 95%

with mussels which are 'several layers thick. From the 18'ark there is 80% mussel coverage with oust the single layer coverage, from this point to the surface there is very little growth.

1-5 From the bottom of the bay (elevation 546) up approx:

15'elevation 561) the walls have 100% coverage, as in THS bay 1-3 and several layers thick. From the there is single layer coverage, a'nd again at 15'ark approx: 25'ark there is nominal growth.

1-6 From the bottom of the bay (elevation 546) ascending upward at approx: 15'elevation 561) the walls have 100% mussel coverage and, they are a few layers thick and at the 17'ark upward towards the 22'ark there is approx: 80% coverage, above that there is no very little growth.

1-7 Almost all the areas in this bay had 50% coverage, several layers thick. He believe this is coused by the main deflector wall causing differant flow patterns within this bay.

2-1 Starting from the bottom (elevation '546) moving in an upward, direction there is 80% coverage until the 15 'ark (elevation 561) . From the 15 'ark upward to the 20'mark there is only 40% coverage from then on very sparse growth exsists. He believe this is caused'gain because of the main deflector wali' 2-2 From the bottom (elevation 546) upward to the the mussel coverage is approx: 80%, from the 15'ark 15'ark upward until the 22'ark there is 40%

mussel coverage, and continuing upward there is very little growth.

AXV-59

I & M Power Company D.C.Cook Nuclear Station Zebra Mussel Report 28 June 93 4;1 T.H.S. Bays (continued) 2-3 From the bottom of the bay upward until the there is 80% mussel coverage, between the 21'ark bottom and the 21'mark, the mussels are several layers thick. Above the 21'mark sparse growth.

From the bottom (elevation 546) until the there is 85% coverage with the mussels being 15'ark several layers thick. At the 15'ark ascending to the 20'ark there is 40% mussel coverage.

Again above the 15'ark there is little growth.

2-5 From the bottom of the bay there is 100% mussel growth only upward appxox: 6'and between the and the 15'ark the coverage is 80%, above 6'ark the 15'ark the growth of zebra mussels thins out to zero.

2-6 From the bottom of the bay up to the 20'ark the coverage varys from 80-100%

with some area's having growth approx: 1/2 thick.

2-7 From the bottom there are patches of adult mussels upward to the 10'mark with these axeas being 70%

covered. From the 10'ark the mussel coverage is 100% up to the 25'ark and from there the growth is very sparce.

4.2 Trashracks

The trashracks extend from bottom elevation their top elevation of 591'throughout the entire 546'o screenhouse main forebay. All the racks had moderate zebra mussel growth, not as dense as was seen in the THS bays . Most of the growth was noted as being between the 4'ark (elevation 550') and the 20'mark (elevation 566'). En 'these areas the mussel coverage was approx: 80% or less again not as dense as in the TNS bays. From the 20'ark and above there was very little growth. The extremely high flow areas had only sparse mussel growth and in the areas that have very low flow the higher the density of mussel growth with algea also being part, of the mediun in some areas .

I & M Power Company D.C.Cook Nuclear Station Zebra Mussel Report 28 June 93

4.3 Keyways

The keyways between the trashracks had a very dense population of mussels, From the bottom of the main forebay (elevation 546') upward to approx: the (elevation 570') the zebra mussel coverage was 24'ark 100% and several layers thick in many locations. The makeup .of the population was 90%-95% immature mussels and again the flow patterns play an important part in the mussel buildup.

4.4 Deflector Halls:

There are five (5) deflector walls. One (1) main in front of THS bays 1-7/2-1 centerline of the Center Intake Tunnel. Two (2) walls infront of THS bays 1-'3/1-4 which are offset North Intake Tunnel.

Two (2) walls infront of THS bays 2-4/2-5 offset South Intake, Tunnel. All deflector walls had 80% 100%

mussel coverage on their north, south, and east sides from the bottom (elevation 546) upward to approx:

(elevation 566). The west sides of the deflector 20'ark walls (facing the flow) was only sparsely populated.

NOTE: The remaining walls within the screenhouse main-forebay had 80% mussel coverage from the bottom upward to the 20'ark, these were immature mussels.

Above the 20'. mark there was sparse growth. At the mouth of the Intake Tunnels there was 100% mussel coverage with the makeup being 40% adults and 60%

being immature zebra mussels.

5.0 Comments and Recommendations It is recommended that the chemical treatments continue, physical removal of mussels by divers from all components within the screenhouse, to dispose of the mussels into dumpsters, and the addition of a spray-wash system that adequately removes mussels from the THS basket mesh. A,iso

a. spray-wash system that can remove mussels that attach themselves to the face of the THS baskets, since these mussels are being carried over because there is no mechanical means of removal.

He welcome the opportunity to discuss any new modifications nessessary, any asspect of this report.

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October 19, 1993 Indiana Michigan Power Company D.C. Cook Nuclear Station One Cook Place Bridgman, MI 49106 Attention: Mr. Eric Mallen Regarding: Molluscicide Treatment Assessment AEP Contract No. C-8484 BUSI Job No. 80021.12

Dear Mr. Mallen:

BUSI is pleased to submit the following inspection report detailing the effectiveness of the molluscicide treatment of the units one and two forebays and traveling water screen bays.

The report consists of a written section of detailed findings and a videotape illustrating the conditions of the treated areas.

If you have any questions or comments regarding this information, please feel free to contact us at your earliest convenience.

Sincerely, SP&

Douglas.T. %eaver Underwater Construction Division DTW/jjm Attachment(s)

AZV-64

INDIANAMICHIGANPOWER COMPANY D.C. COOK NUCLEAR PLANT MOLLUSCICIDE TREATMENT ASSESSMENT AEP Contract No. C-8484 BUSI Job No. 80021.12

. Date of Treatment: 9/11/93 Date of Assessment: 9/22/93 Submitted By:, Douglas T. Weaver AIU-65

TABLE F ONTENTS 1.0 Detailed Findings 1.1 Unit One Forebay 1.2 Unit Two Forebay 1.3 Trash Racks and Key Ways 1.4 Unit One Traveling Water Screen Bays 1.5 Unit Two Traveling Water Screen Bays 2.0 Conclusions 3.0 Attachments 4.0 Uideotape (25 min.)

AIV-66

93 Molluscicide Treatment Assessment tober 19, 1993 age 1 of 8 1.0 Detailed Findings

~Ui F 1.1.1 At the west wall between the center intake and north intake tunnels, the estimated kill ratio is ninety-five percent, with a seventy percent covering of dead mussels attached by their bissel threads. On the floor, there is a build up of loose mussels covering an area of two feet in width at the wall expanding to eight feet wide toward the trash racks. The depth of the pile Janges from 6" to three feet.

(Please refer to Attachment 3..)

1.1.2 The wall running across the northwest corner dividing the forebay from the Unit 1 trash trap has an estimated kill ratio of ninety-five percent. Approximately ninety percent of the area is covered by mussels attached by the bissel threads. A concentration of loose mussels runs the length of the floor covering an area of two feet in width. by one foot deep. (Please refer to Attachment 3..)

1.1.3 Deflector Wall "A" On the pump side, the wall is 100% covered with attached mussels 1'hick. Additionally, the floor is covered with mussels along the entire length of the wall to the key way @1. The build up measures approximately four feet wide by two feet in depth. The kill ratio here is approximately ninety-five percent. The lake side of the wall is clear due to the high flow. (Please refer to Attachment 3..)

1.1.4 Deflector Wall "B" The wall has a one hundred percent kill ratio. On the pump side, approximately sixty percent of the wall is covered with attached mussels. On the lake side, there are no attached mussels due to the high flow.

AIV-67

1993 Molluscicide Treatment Assessment October 19, 1993 Page 2 of 8 1.0 Detailed Findings (Continued) 1,2 ~iT P h 1.2.1 The west wall between the center intake and the south intake tunnels has a kill ratio of approximately ninety-five percent. Ninety percent of the dead mussels are still attached to the walls. On the floor, there is a pile of mussels which runs the length of the wall, extending into the,bay up to deflector wall "D". The area measures ten feet in width and varies between eight inches and five feet in depth. (Please refer to Attachment 3.,)

1.2.2 The wall running across the southwest corner dividing the forebay from the Unit Two trash trap has an estimated kill ratio of ninety-five percent. 90% covering of the mussels are attached by their bissel threads. On the floor there is an accumulation of mussels which extends along the length of the wall covering an area of two feet in width by one foot in depth.

1.2.3 Deflector Wall "C" The pump side of deflector wall "C" has an estimated kill ratio of ninety-five percent. 100% covering of the mussels are attached to the wall. The floor there is an accumulation of mussels which extends to the south from key way 83 to key way 84, and to the east from the wall through the trash racks. The lake side of the wall is clean due to the high flow.

1.2.4 Deflector Wall "D" There is an estimated kill ratio of approximately ten percent on the pump side of the deflector wall. A 100% covering of live mussels which are firmly attached. There is a build up of mussels on the floor which extends the length of the wall, covering an area of two feet wide by one foot deep. (Please refer to Attachment 3..) The lake side of the wall is clean due to the high flow.

0

1993 Molluscicide Treatment Assessment tober 19, 1993 ge3 of 8 1.0 Detailed Findings (Continued) 1.2 Unit Two Foreba 1.2.5 Deflector Wall "E" The pump side of the wall has an estimated kill ratio of ninety-five percent. Ninety percent of the area is covered with attached mussels. There are no loose mussels on the floor. The lake side of the wall is clean.

1.3 Tr h Rack and Ke Wa 1.3.1 The trash racks in front of traveling water screens 1-1 and 1-2, trash racks along the north wall and key way 41 are covered by a six foot wide strip of mussels extending from the floor to the water surface.

The kill ratio for this area is ninety-five percent. (Please refer to Attachment 3..)

f 1.3.2 There is an estimated kill ratio of ninety-five percent on key way

@1. A pile of loose mussels extends out to deflector wall "A", and there is a ninety-percent covering of dead mussels which are still attached.

1.3.3 The trash racks in front of traveling water screen's 1-3 and 1-4 have a 6'ide strip of mussels from the floor to the water surface along keyway @1 and keyway 82. This area is 100% covered with hanging dead mussels. The approximate kill ratio for this area is 95%. No loose mussel build up.

1.3.4 Key way P2 has an estimated kill ratio of approximately ninety-five percent on both the north and south sides. Attached mussels cover approximately ninety-five percent of the area. There is no accumulation of loose mussels in the area.

1.3.5 Due to high flow, divers were unable to assess trash racks 1-5 and 1-6.

AIV-69

1993 Molluscicide Treatment Assessment October 19, 1993 Page 4 of 8 1.0 Detailed Findings (Continued) 1.3 Tra h Racks and Ke Wa . Continued 1.3.6 On both the north and south sides of key way @3, there is a kill ratio of approximately ninety-five percent. Attached mussels cover ninety-five percent of the area, and there is an accumulation of dead mussels on the floor. (Please refer to Section 1.2,3 for location and measurements.)

1.3.7 Trash racks 1-7 and 2-1 are approximately fifty percent covered with attached mussels. There are loose mussels accumulated (please refer to Section 1.2.3 and Attachment 3. for location and measurements.) There is an estimated kill ratio of ninety-five percent in this area.

1.3.& Key way @4 has an approximated kill ratio of one hundred percent. Eighty-five percent of the are'a on both the north and south sides is covered with attached mussels. For locations and measurements of loose mussels, please refer to Section 1.2.3 and Attachment 3..

1.3.9 Trash rack 2-2 has no signs of mussel growth or dead mussels as it is an area of very high flow. Trash rack 2-3 is approximately fifty percent covered by attached dead mussels. There is no accumulation of loose mussels. The estimated kill ratio in this area is ninety-five percent.

1.3.10 On the south side of key way 85, coverage is estimated at eighty percent. On the north side, approximately fifty percent of the area is covered. There are no loose mussels on the floors of either side.

The kill ratio for both sides is ten percent.

1.3.11 There is coverage of about thirty percent on both trash racks 2-4 and 2-5 with an estimated kill ratio of twenty percent for both.

There is no accumulation of loose mussels on the floor.

'IV-70

93 Molluscicide Treatment Assessment ober 19, 1993 ge5of8 1.0 Detailed Findings (Continued) 1.3 Tra h Racks and Ke Wa . Continued 1.3.12 Key way 46 has coverage estimated at seventy percent with a kill ratio of ninety-five percent on both the north and south sides.

There are no loose mussels on the floor.

1.3.13 There is an estimated kill ratio of one hundred percent for both trash racks 2-6 and 2-7. Approximately twenty percent of the area is covered with dead mussels attached by their bissel threads. An accumulation of loose mussels covers an area of approximately two feet wide by one foot in depth at the south end of 2-7.

Travelin Wa er Screen Ba . T.W.S.B.,

To provide a more accurate assessment of the kill ratio in the traveling water screen bays, the kill ratios and coverages were noted at three points in each bay: the surface, the mid-way point and at floor level.

1.4.1 T.W.S.B. 1-1 has approximately one hundred percent coverage at the surface, with an estimated kill ratio of eighty percent. At the midway point, coverage decreases to about eighty percent with a kill ratio of fifty percent. At floor level, there is one hundred percent coverage with a kill ratio of seventy-five percent. All of the mussels are attached, with the exception of loose mussels which have

" accumulated in the northeast corner with a depth of about two feet.

1.4.2 At all three points in T.W.S.B. 1-2,'there is estimated coverage of one hundred percent with a kill ratio of ninety-five percent. The dead mussels are still attached by the bissel threads. There is an accumulation of about three feet of loose mussels on the floor in the southeast corner.

AIV-71

1993 Molluscicide Treatment Assessment October 19, 1993 Page 6 of 8 1.0 Detailed Findings (Continued) 1.4 Travelin Water creen Ba s T.W.S.B. ntinued 1.4.3 T.W.S.B. 1-3 has coverage of approximately ninety percent at the surface with a kill ratio of ninety-five percent. At the midway point, coverage decreases to approximately twenty percent, with a kill ratio of Gfty percent. At floor level, the coverage is about twenty percent with.a kill ratio of twenty percent. The majority of the dead mussels are loosely attached. In the northeast corner, there is a three foot pile of loose mussels.

1.4.4 T.W.S,B. 1-4 has 'pproximated coverage of eighty percent throughout. At the surface, the, kill ratio is about eighty percent.

At the midway point, the kill ratio decreases to approximately seventy-five percent. On the bottom, the kill ratio is estimated at fiftypercent. In the southwest corner there is a build up of mussels about five feet deep. Most of the dead mussels are still attached by the bissel threads.

1.4.5 T.W.S.B. 1-5 has about ninety percent coverage at the surface, with a kill ratio of approximately ninety-five percent. At the midway point, coverage approaches seventy percent, with a kill ratio of eighty percent. At the bottom, there is eighty percent coverage with a kill ratio of ninety-five percent. An accumulation of loose mussels runs the entire length of the bay with a depth of three feet.

1.4.6 T.W.S.B. 1-6 shows coverage of approximately eighty percent at the surface with a kill ratio of ninety-five percent. At the midway point, the coverage decreases to ninety percent with a kill ratio of ninety percent. At floor level coverage is estimated at eighty percent with a ninety-Gve percent kill ratio. There are no accumulations of loose mussels on the floor.

AIV-72

1993 Molluscicide Treatment Assessment ober 19, 1993 e7 of 8 1.0 Detailed Findings (Continued) r 1.4 Travelin Wa er Screen Ba s T.W,S.B. Continued 1.4.7 At the surface, T.W.S.B. 1-7 exhibits coverage of approximately twenty percent with a kill ratio of ninety percent. At the midway point, coverage increases to ninety percent with at kill ratio of ten percent. At floor level, coverage is complete with approximately ninety percent of the mussels surviving. Across the trash rack, there is an accumulation of loose mussels covering an area four feet wide by two feet in depth.

1.4.8 2-1 has eighty percent coverage at the surface with a kill

'.W.S.B.

ratio of fiftypercent. At the midway point, coverage is one hundred percent with a twenty percent kill ratio. At floor level, there is eighty percent coverage with an estimated kill ratio of twenty percent. There are loose mussels built up across the trash rack covering an area of four feet wide by two feet in depth.

1.4.9 There is ninety percent coverage at the surface of T.W.S.B. 2-2 with an estimated kill ratio of thirty percent. There is one hundred percent coverage at the midway and floor level points, with five percent and zero percent kill ratios, respectively. Along the north wall, there is an accumulation of mussel debris covering an area measuring three feet wide by two feet deep. The area of coverage begins at the trash rack, extending across the front of the traveling water'creen.

1.4.10 At the surface of T.W.S.B. 2-3, there is coverage of approximately eighty percent with a kill ratio of fifty percent. At the midway and floor level points, coverage increases to one hundred percent with kill ratios of thirty and twenty percents respectively. There is an accumulation of loose mussels measuring approximately eight feet wide. by eight feet deep in front of the traveling water screen.

1.4.11 Divers were unable to assess the conditions of T.W.S.B. 2-4 due to high flow.

AIV-73

1993 Molluscicide Treatment Assessment October 19, 1993 Page 8 of 8 1.0 Detailed Findings (Continued) 1.4 Travelin Water creen Ba s T.W.S.B. Continued 1.4.12 T.W.S.B. 2-5 has approximately twenty percent coverage at the surface with a kill ratio of about ninety-five percent. At the midway point, coverage is about fifty percent with a survival rate of twenty percent. The floor level exhibits one hundred percent coverage with a kill ratio of fifty percent. At the southeast corner of the bay, there is a concentration of mussel debris about two feet deep.

1.4.13 At the surface and midway points, T.W.S.B. 2-6 exhibits coverage of ninety percent, with kill ratios of eighty and ninety-five percents respectively. At floor level, there is eighty percent coverage with a ten percent survival rate. The entire floor of the bay is covered by a two inch layer of loose mussels.

1.4.14 There is one hundred percent coverage at the surface of T.W.S.B.

2-7 with an estimated kill ratio of ninety-five percent. At the midway point, coverage decreases to ninety percent with a kill ratio of ninety-five percent. At the floor level there is ninety percent coverage with a fifty percent survival rate. At the south wall, there is an accumulation of dead mussels about three feet deep.

2.0 Conclusion The over all effectiveness of the molluscicide treatment breaks down in this way. In the unit one and unit two forebay area's the molluscicide was eighty-five percent successful.

In the unit one traveling water screen bay's the, over all successfulness decreases to seventy percent, and decreases further in the unit two traveling water screen bay's to fifty-five percent.

As referred to earlier and seen in the video tape. There is some accumulation of loose mussel shells through out the treated area with a more substantial amount of dead mussels that have no fallen or been washed away by flow. A greater accumulation of loose mussel shells should be anticipated in the nest several weeks.

It should also be noted several weeks once the mussels has fallen leaving behind it's bissel threads. The attached bissel thread could excelerate reinfestation of the thread area's.

Attachment 3.1.0 Loose Mussel Build Up'nit 2 Tcash ~ thit 1 'Ikash I

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Aquatic Issues - Whole Effluent Toxicity Testing Whole effluent toxicity testing was performed by the Plant during Clam-trol treatments to the North and South Intake Tunnels and the Circulating Water System in 1992, and included in its zebra mussel

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control report, to the Michigan DNR in April of 1993. A whole effluent toxicity test was also performed in September of 1993 with sulfur hexafluoride (SF6) gas in Lake Michigan water. The results of the whole effluent toxicity testing are included in the following reports and prove that the plant's discharges were non-toxic as a result of the treatments.

AIV-77

Indiana Michigan Power Company One Summit Square P.O. Box 60 Fort Wayne. IN 46801 219 425 2111 INDlANA AllCHIGAN POWER Fred P. Morley District Supervisor Surface Water Quality Division Michigan Department of Natural Resources P. 0. Box 355 Plainwell, MI 49080 April 27, 1993

Dear Mr. Morley:

The 1992 zebra mussel control program, which was a combination of chlorination and Clam-Trol treatments, has been completed and the results evaluated. This letter reviews the correspondence we have had regarding zebra mussel treatment and NPDES permit compliance plans and reports on the compliance status of the entire zebra mussel control program with the NPDES Permit effluent limits, the success oi the program, the results of the whole effluent toxicity ("WET") testing, other signifi'cant'vents. My letter to you'dated July 30, 1992 state written report covering these four areas would be submitted to 'you.

Your letter of April 24, 1992 responded to I&M's request of December 3, 1992 to use the Betz Industrial molluscicide, Clam-Trol, CT-1, for zebra mussel control and to use bentonite clay to detoxify the Clam-Trol treated water before being discharged to Lake Michigan. Your letter imposed these conditions on the approval to use Clam-Trol:

The daily maximum effluent limit for Clam-Trol is 0.05 mg/l at outfalls 001 and 002.

A plan to assure that the maximum effluent limit for Clam-Trol of 0.05 mg/l is met at outfalls 001 and 002 is submitted to and approved by the Surface Water Quality Division, Plainwell District Supervisor before the first application of Clam-Trol.

A plan to conduct 48-hr. WET tests on each outfall, 001 and 002, during the application of Clam-Trol, is submitted to and approved by the Surface Water Quality Division, Plainwell District Supervisor before the first application of Clam-Trol.

These tests must be conducted when the effluent is detoxified with bentonite, as well as when it is not detoxified.

Notification of the Surface Water Quality Division, Plainw District Supervisor, one week before each application of Clam-Trol.

Fred Morley Letter Page 2 April 27, 1993 My letter of June 9, 1992 transmitted the WET testing study plan to you.

The WET testing plan described how and where the effluent samples were to be taken, how they would be shipped to the bioassay testing labora-tory, how the toxicity tests would be conducted in the laboratory, how the WET test results would be interpreted, and how I&M would respond to a variety of possible WET test results.

Mr. Bantjes responded to the WET testing study plan on July 16, 1992.

His letter approved the study plan with a few modifications. Mr.

Bantjes also expressed concern that I&M would be spot treating certain components of the Cook Nuclear Plant that were not part of the original request to use Clam-Trol. He stated approval was to treat the circu-lating water and essential service water systems three times a year each, for a total of six treatments per year for the life of the NPDES permit. If spot applications were in addition to the plan for intermit<<

tent treatments, then Cook Nuclear Plant would need to submit a modified plan for chronic WET testing.

In my letter of July 30, 1992, I described four phases of treatment, two less than the six treatments a year approved earlier by MDNR.

Phases 1 & 2 - Treat the center and north intake tunnels.

Phase 3 - Treat the Units 1 and 2 circulatory water system.

Phase 4 Spot treat components of the essential service water system (rather than treating the entire system, which would require far more Clam-Trol).

1 My letter included a schedule for conducting these four phases of treatment in 1992 and explained how the treatments would be carried out.

I also included an example to illustrate how treating components of the essential service water system rather than the entire system would reduce the amount of Clam-Trol used. The major benefit to reducing the amount of Clam-Trol used is that far less of this chemical is discharged into Lake Michigan.

Compliance with Effluent Limits Compliance with effluent limits was determined by chemical analyses of the detoxified effluent. Water samples were pumped from the discharge tunnel manways and analyzed spectrophotometrically (Attachment 1) in a laboratory set-up in the plant screenhouse. All water samples collected from the Unit 1 and Unit 2 discharge tunnels during treatment Phases 1, 2, and 3 (conducted August 12-13, September 11-12, and September 16, 1992, respectively) showed Clam-Trol concentrations were less than detectable. Attachment 2 is a set of the laboratory data sheets of all Clam-Trol analyses during these treatments and the calibration curves.

The detection limit is 0.2 mg/1 of Clam-Trol active ingredient.

AIV-79

Fred Morley Letter Page 3 April 27, 1993 is a set of the Phase 4, essential service water system components treatments, (December 17', 1992) chemical feed logs.

Discharge concentrations were calculated to be less than 0.034 mg/l of Clam-Trol active ingredient. These calculated values are higher than the actual values, because they do not account for the Clam-Trol demand of the lake water.

Therefore, chemical analyses and discharge concentration calculations all showed that 'he 0.05 mg/1 effluent limit for Clam-Trol was met at all times during all four phases of the Clam-Trol treatments.

Effectiveness of Zebra Mussel Control The effectiveness of the zebra mussel control was measured by diver inspections of underwater equipment and structures and by sidestream biobox monitors connected to 'the circulating water and non-essential service water systems. Diver reports showed zebra mussel infestations from one to four inches thick were completely removed except for some widely scattered zebra mussels following the Clam-Trol treatments. The bioboxes, contained about 100 zebra mussels per box, and between 87 a 99X zebra mussels were killed by the Clam-Trol treatment. Based upon these results,'he. treatment program was rated as producing 95X mortality to zebra mussels settled within the plant. or'igher The success of the essential service water system Phase 4 treatments was measured by comparing water flow rates through the treated heat exchanges and the inlet vs. outlet pressure differential before and after the treatments. Three containment spray heat exchangers were treated with Clam-Trol in Phase 4, two heat exchangers showed improved performance and the third showed no change.

WET Testin Results testing study results are presented in detail in Attachment 4.

1 The WET Acute 48-hout toxicity tests wete conducted with ~De hnie 8ulex on 100y, 50X, 25X, 12.5X, 6.25X, and OX effluent. The median effective concen-tration (EC50) was calculated for all tests. No tests resulted in effluent toxxcity greater than EC50 Using 100X effluent.

Other Si nificant Events During the Phase 3 circulating water system treatment, the cooling water discharge had a slight color difference from the natural lake water color. This observation was reported by telephone to your office.

AIV-80

Fred Morley Letter Page 4 April 27, 1993 As always I will be happy to answer any questions or 'listen to any comments you have regarding this letter and the attachments. The treatment program effectiveness and negative WET test results were pleasing. As stated in our WET testing plan (page 5) and approved in Mr. Bantjes's letter of July 16, 1992, we will discontinue the WET testing on future Clam-Trol treatments. We will comply with all other conditions of your letter of April 24, 1992 and Mr. Bantjes's letter of July 16, 1992.

Very truly yours, Donald L. Baker Environmental Affairs Director DLB/AEG/wfv/01 Enclosures AIV-81

Fred Morley Letter Page 5 April 27, 1993 bcc: A. J. Ahern/T. E. Webb A. A. Blind

~D. M. Fitzgerald E. E. Fitzpatrick D. E. Heydlauif K. D. Mack M. R. Robida/A. E. Gaulke/J. P. Vi ovotny W. E. Walters AIV"82

ATTACHMENT CLAM-THOL CT-1 MollUsk Control Agent METHYLORANGE METHOD APPARATUS REQUIRED CT-1 Buffer Reagent 1591 Beaker, glass, 50 mL (2 required) Code Methanol (reagent grade or equivalent) 322 Cylinder, graduated, 25 mL 2622 Drying Reagent, with a plastic dipper 1271 Funnel Rack, separatory 936

SUMMARY

OF METHOD Funnel, separatory, wiN a Teflon stopcock, 250 mL *

(2 required) Inthls procedure the dye in the CT-1 Buffer Reagent com-plexes with the active ingredients in Clam-Trol CT-1. This Glass Rod 114 complex is extracted into 1, 2- dlchloroethane. The or-Optical Cell, (2 required) *0 . ganic layer containing the complex is separated from the aqueous layer and drledwith a dying reagentcontaining Safety Bulb, rubber 1575 anhydrous sodium sulfate. The color intensity of the 1, 2 8pectrophotometer ** dichioroethane layer ls then measured ln a spectropho-tometer at 415 nm.

GENERAL APPARATUS

• This method must be customized to each specific appli-Cylinder, graduated, 100 mL Code 121 cation. Vary the volumes of sample, CT-1 Bulfer Reagent, Cylinder, graduated, 250 mL 917 and 1, 2- dlchloroethane according to the test range (see Table 1). If a higher absorbance is needed, increase Flask, volumetric, 1 L, glass (4 required) 935 the volume of sample or decrease the volume of 1, 2-Pipet, glass, graduated, 1 mL 140 dlchloroethane. When increasing the sample volume it Plpet, glass, volumetric, 1 mL 866 may be necessary to increase the volume of CT-I Buffer Reagent used. For samples <150mLuse10mLof CT-1 Plpet, glass, volumetric, 3 mL *P Buffer Reagent; for samples between 150 and 300 mL Pipet, glass, volumetric, 5 mL 124 use 15 mL of CT-1 Buffer Reagent. Make sure that enough 1, 2- dlchloroethane is used to leave a smail Pipet, glass, volumetric, 10 mL 123 plug of solvent ln the separatory funnel when the bottom Pipet, glass, volumetric, 15 mL 861 layer of solvent Is removed and to fill the optical cell properly.

Plpet, glass, volumetric, 20 mL 1278 Pipet, glass, volumetric, 25 mL 117 GENERAL PROCEDURE AO Plpet, glass, volumetric, 30 mL

~ The general Use a well-ventilated or hooded area to run the test.

apparatus required for the test is deter- Always use a safety bulb when pipetting liquids.

mined by the specific test procedure used.

<<* Apparatus not available through Betz Lab Supply 1,2- Dichloroethane (also known as Elhylene Dichlo-should be obtained through a local supplier. ride) is a priority pollutant and a specNcally-listed RCRA<egulatedmaterial subJect to specific disposal re-CHEMICALS REQUIRED strictions and(or prohibitions. For this reason, all used t

1,2- dichloroethane should be segregated from other 1, 2- Dlchloroethane (reagent Code 1666 waste streams. Dispose of waste 1,2- dlchloroethane ln grade or equivalent) an approved manner (e.g., labpacklng or incineration).

AIV-83 o1990 BETZ V BORATORIES. INC. ALLRIGHTS RESERVED.

NOTES 7. It is imperative that the sample cells are kept ciea during the running of the test. It ls reco dth

1. For maximum accuracy the calibration curve should . the cells are cleaned after each meas usin be checked by every operator using this test and the followIng procedure:

should be verified a minimum of twice per monthus-ing a freshly prepared CT-1 standard. a) Rinse the cell three times with distilled (

2. A blank measurement (the blank should be a sam- deionized} water.

ple of the system water prior to CT-I treatment) must be recorded for each set of samples. The blank b} Rinse the cell three times with methanol.

reading may vary slightly; however, the absolute dif-ference between the sample and the blank remains c} Rinse the cell three times with 1, 2- dichloro-relatively constant. ethane to remove methanol from the cell.

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3. Chlorine causes a negative interference in the test. 8. Turbidity can interfere with this test procedur This can be eliminated by adding 0.1 N Sodium Turbidity may:

Thiosulfate (Code 235) to the water sample before ~ create an emulsion in the 1,2, - dlchloro-tunning the test. The amount added is based on the ethane layer that does not separate atter concentration of chlorine in the system. For a standing for 10 min when the funnel is 1$ HnL water sample containing 0.3 mglL chlorine, shaken .

acid 10 drops of 0.1 N Sodium Thiosulfate to remove the interference. ~ create a positive interference. ( A yellow color is extracted into the 1,2- dlchloro-

4. A slightemulsionmayformwhenusingnatural water ethane layer. )

samples. When this happens, vary step 5 of the procedure. Shake the funnel for 30 sec, vent It, then These problems can be removed by centrifuging t allow it to stand for 5 min. Gently invert the funnel sample (1 0 min at3500rpm or30min at2500rpm) befo once then allow the funnel to stand for 5 min. performing step 1 of the procedure.

5. It ls important to vent the separatory funnel both be- 9. Ifyouneedto change test conditions (l.e., use diff fore and after shaking it. Otherwise, a pressure will entvolumesthanthoseinTable1),co eAn buildup in the funnel that can cause the stopper to lytlcal Testing and Development Gro evo be forced out of the top of the funnel ~ for assistance.

6. Use caution when inserting or removing the sample 10. ThismethodisadaptedfromWang, I K.; Langly, cell in the photometer. The 1, 2- dlchloroethane can F. Ind. Eng. Chem., Prod. Res. Dev., 1975, 14, damage the cell compartment. 210-212.

AIV-84 AP 368 9009 O1990 8ETZ LA8ORATDRIES,INC. AU. RIGHTS RESERVED.

AIIg<(St 11, 1992 North and Center Intake CT-1 High Range Calibration Curve (1cm cell) 1.2 o 0.8 .

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~ 0.6-0.4 0.2 4 6 10 12 14 16 18 20 ppm

August 11, 1992 North and Center Intake CT-1 Low Range Calibration Curve (Gcm cell) 0.3 H

co 0.25 0.2 0

C 0.15

.D 0.1 0.05 0 0,1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 ppm

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REPORT ON THE WHOLE EFFLUENT TOXICITY TEST FOR DETOXIFIED

'LAM-TROL EFFLUENT AT DONALD C. COOK NUCLEAR PLANT American Electric Power Service Corporation and Indiana Michigan Power Company February 22, 1993 AXV-110

WHOLE EFFLUENT TOXICITY TEST Introduction The Michigan Department of Natural Resources (MDNR) issued a letter modifica-tion for the Donald C. Cook Nuclear Plant approving the use.of the propri-etary molluscicide Clam-Trol, CT-1 (Betz Industrial). The letter, dated April 24, 1992, from Mr. Fred Morley to Mr. Donald Baker, Indiana Michigan Power Company (I&M), allowed the use of Clam-Trol if the effluent contained Clam-Trol concentrations equal to or less than 0.05 mg/l. Since the detec-tion limit for Clam-Trol is 0.2 mg/l, the MDNR required whole effluent toxicity (WET) testing to assure compliance with the state water quality standard provision prohibiting the discharge of toxic materials in toxic amounts.

The MDNR al'so required I&M to submit a study plan describing how the WET testing would be performed. Mr. Baker sent I&M's study plan to Mr. Morley by letter dated June 9, 1992. I&M's study plan described ho'w and where the effluent streams would be sampled from Outfalls 001 and 002, and how the samples would be shipped,'nalyzed, and reported to'the MDNR. This plan also described how the data would be evaluated and specified testing to be con-ducted 'should any single test produce an EC>0 less than 100K effluent.,

The letter modification of the Cook Plant NPDES Permit was conditional on the study plan being approved by the MDNR. MDNR notified I&M by letter dated July 16, 1992 that the study plan was acceptable.

AIV-111

Treatment of the Cook Plant for zebra mussel control has evolved from attempts to treat the entire plant in one operation to treating components the plane in separate operations. The intake tunnels are treated individu-ally, the circulating water system is treated as one system and components of the essential service water (ESW) and non-essential service water (NESW) systems are treated as needed.

Treatment Pro ram Com leted In 1992 The north and center intake water tunnels were treated with Clam-Trol on August 12 and 13 and September 11 and 12, 1992, respectively. The circula-ting water system was treated on September 16 with Clam-Trol. Water samples were collected during each of these three periods as described in the ap-proved study plan. These samples of detoxified effluent were split and t shipped to a contract laboratory and to the MDNR toxicity testing laboratory for analyses. The contract laboratory conducted a 48-hour acute toxicity test using ~pa hnia culex on each, oi the three water samples. At the same time the detoxified effluent samples were being analyzed, a series of ben-tonite clay solutions were being tested for impact on the test organisms.

~pa hnia sp. and other zooplankters can be adversely affected by mechanical (rather than chemically toxic) means when exposed to excessive amounts of suspended clay. These clay blank test series were conducted using Lake Michigan water and the same clay used to detoxify the Clam-Trol. Lake Michigan water used for dilution of the detoxified effluent tests and the clay blank tests was collected before the Clam-Trol treatments began.

Methods Water samples were collected from the discharge tunnel manways using a submerged pump at the beginning of the treatment, at the fourth hour, at the eighth hour and at the twelfth hour of treatment. Samples were collected from Unit 2 discharge manway and composited in one container. At the end of the test, a sample was removed from the composited sample container and shipped to the contract laboratory. During treatments to 'the north and center intake tunnels on August 12-13 and September 11-12, 1992, there was no effluent from the Unit 1 discharge tunnel. During the circulating water system treatment on September 16, samples were collected from both the Unit 1 and Unit 2 discharge tunnel manways and composited into one container, from which the water for WET testing was taken.

The laboratory followed the procedure for conducting 48-hour EC50 acute toxicity tests according to the EPA protocol, "Method for Measuring the Acute Toxicity of Effluent to Freshwater and Marine Organisms," EPA/600/4-85/013.

A dilution series of 100X, 50Z, 257,,12.5X, 6.25X and OZ (control) effluent was set up. Lake Michigan water filtered to remove native zooplankton was used for dilution. Four 30 ml beakers were set up for each test concentra-tion and 25 nl of test solution uas Fut in each beaker. Five ~oa hnia Fulex juveniles ((24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> old) were placed in each beakers Temperature was..

maintained at 25'+ 1'C. Temperature, DO, and conductivity were measured every 24" hours. The effects were recorded every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Organisms that failed to remain in the water column for five seconds after a gentle prod or swirling the beaker were considered effected. Results are reported as acute 48-hour EC values.

AZV-113

A test series of bentonite clay blanks was conducted the same as the detoxi-fied Clam-Trol effluent. Filtered Lake Michigan water was mixed with the same concentration of bentonite clay used to detoxify the Clam-Trol. This concentration of bentonite clay was tested at 100X, 50Z, 25X, 12.5Z, 6.25X and OX (control).

Results Whole Effluent Toxicity tests were conducted August 15 through 17, September 13 through 15, and September 17 through 19, 1992. Table 1 shows the immobility percentages of the detoxified Clam-Trol effluent and the bentonite clay blank test concentrations. Immobility results exceeded the I.

EC50 for 100Z effluent at all detoxified effluent and clay blank test concen-trations. The highest- immobility result was 30X for the detoxified Clam effluent samples and 25X for the bentonite clay blanks at the 100X effluent concentration. One test series was technically invalid because the control (OX effluent) had >10X immobility. Except for the immobility observed at the control concentration in the detoxified effluent test conducted on September 13-15, toxicity was low and the immobilities that were observed followed a similar pattern as the clay blank test series. Immobility per-centage differences between the detoxified Clam-Trol and clay blank test concentrations were usually 5X or less.

Discussion The 70Z immobility value obtained for the control test on September 13-1 would appear to be an anomolous value, since the bentonite clay blank control AIV-114

using Lake Michigan water supplied to the contract laboratory in the same shipment showed OX immobility. Three of the foui control replicates sho~ed all or nearly all test organisms were immobilized and in one of the four replicates none of the organisms were immobilized during the 48-hour test.

An examination of the laboratory sheet for the treatment concentrations shows that the organisms in the replicates'ere immobilized in nearly equal num-bers, e.g., the 50X and 100X effluent replicates had one or two immobilized organisms. None of the treatment replicates individually accounted for all of the immobilities, which would indicate a contaminated replicate. The immobilities were equally distribute4 among the replicates. There is no water quality parameter that was measured before, during, or after the toxicity test thee indicates a problem for ~Da hnia Eulex's well being.

Given the general lack of immobilization response of organisms in the dig-ferent treatment concentrations tested on any given date and the similarity of test results from one test date to the nest, there was little difference between the detoxified Clam-Trol effluent and the bentonite clay blanks effects on the test organisms. All tests were in compliance with the re-quirement that the 48-hour EC for ~Da hnia exceed 1007. effluent. in other words the tests showed that effluent toxicity was less than the toxicity needed to produce an EC>0 in 100X effluent. The lack of toxicity indicates the detoxified effluent had little impact on the Lake Michigan aquatic-community.

AIV-115

TABLE 1

~Da hnia culex 48-hour Percent Immobility Values Obtained from Whole Effluent Toxicity Tests Conducted with Detoxified Clam-Trol in Lake Michigan Water and Bentonite Clay Blank Test Run in Lake Michigan Water (clay blank immobility percentages in parentheses)

Control Test Date (OX) 6.25X 12.5X 25X 50X 100X Aug 15-17 OX OZ OX 15X OX 25Z (OX) (OX) (10X) ( OZ) (10X) ( 5Z)

Sep 13-15 70Z OX 15Z 20X 30X (OZ) (5X) (10X) (25X) (20X)

Sep 17-19 OX OX 10Z 10Z 5Z 15X (5X) (5X) ( 5Z) ( 5X) ( OX) ( 5X)

AIV-116

GREAT 'AKES ENVIRONMENTAL CENTER 739 Hastings Sv=-et 1030 King Avenue Tra!cise City. Michigan 49684 Cclumous Ohio 43212 Fhcne t616) 941.2230 Phone t61 4) 297-8801 Fax (61 6) 941-2240 Fax l614) 297-8866.

October 12, 1993 Mr. John Carlson Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, MI 49106

Dear John:

i h I I <<

TOXICITYTEST M'2'ORT FOR SULFUR HEXAFLUORIDE GAS (SF6)

~

CKhgBI i Mi d96 f ILrra~lg) static renewal-acute toxicity tests performed with sulfur hexafluoride (SF6) in Lake Michigan water. The Lake Michigan water sample was collected by Indiana Michigan gas Company personnel on September 28, 1993. The sample was transported overnight to Great Lakes Environmental Center (GLEC), and we received the sample in good condition on September 29, 1993.

The g. ~du i and fathead minnow tests were conducted in accordance with GLEC Standard Operating Procedures, which are based on procedures developed by U.S. EPA (Peltier and Weber, 1990, Method f r Me rin e Acute Toxici of Effl en Fr hwater and Marine Or ani ms, Fourth Edition, EPA/600/4-90/027) and ASTM andard Guide for nductin Acute Toxicit Test with Fi h inve a r t nd Am hi i n, E729-88a, 1993).

It is our understanding that the Cook Nuclear Plant currently injects SF6 into approximately 690,000 gpm of noncontact cooling water at a rate of 5 cfm, which is equivalent to a rate of 54 /il/L of SF6 gas. The fathead minnow acute toxicity test was initiated on October 1, 1993, using an undiluted Lake Michigan water sample that was injected with sulfur hexafluoride gas at a rate of 108 /rl/L (twice the plant's injection rate). The gas was injected into a sealed airtight chamber using a gas injection syringe. After injection, the sample was shaken and thoroughly mixed for one minute. This sample was then used as the highest test concentration. A reconstituted laboratory water (Hardness =

172 mg/L CaCO>) was used to prepare nominal test concentrations of 54, 27, 14, and 7 /rl/L SF6 gas.

Twenty fathead minnows (3 days old at test initiation) were exposed for 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> in groups of ten, in 250 ml glass beakers, each containing 200 ml of test solution (65 x 60 mm of solution in the eakers). Each day the test solutions were carefully renewed by siphoning most of the old solutions om the beakers; freshly prepared solutions were added back to each test chamber daily and the number of surviving fish was recorded. The SF6 concentrations in the test chambers were not measured analytically.

AIV-117

~

Applied Water Quality and Environmental Sciences

Mr. John Carlson Indiana Michigan Power Company 2 October 12, 1 Y idU fhd using identical exposure concentrations. In each Q~ test concentration we exposed 20 animals

(<24 hours old at test initiation) in groups of five in 30 ml glass beakers, each containing 25 mls of test solution (40 x 45 mm of solution in the beakers). After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the animals were transferred to fresh solutions using a wide bore pipet, and the number of surviving or dead animals was recorded.

The reconstituted water used in Q, EPA methods e d f

~ and fathead minnow toxicity testing is prepared according to r M rin e Acute T xici f ENuen Fr hwa er and Marine

~n~i~, Fourth Edition, EPA/600/4-90/027). We used dechlorinated reverse osmosis (R/O) for culturing our g. ~.

treated municipal water for the culture of fathead minnows, and Boardman River water (headwaters)

Deionized reverse-osmosis (R/0) treated municipal water is the base water, to which reagent-grade salts are added to prepare each batch of reconstituted water.

The results of the g.

into the Lake Michigan

~i water and fathead minnow tests indicate that the sulfur hexafluoride gas injected sample was not acutely toxic. There was 100 percent survival of the g.

in the 7, 14, 27, and 108 pl/L SF6 concentrations, and 95 percent survival in the laboratory greater than 108 pl/L SF6 gas. The water chemistry data for the g.

Table 2.

~

water controls and the 54 /il/L SF6 concentration (Table 1). Therefore, the 48-hour LC~~ value was test are summarized in In the fathead minnow test there was 100 percent survival in the 7, 54, and 108 /il/L SF6 concentrations and in the laboratory water controls gable 3). There was 95 percent survival in the 14 and 27 /il/L test concentrations. Because there was less than 50 percent mortality in the 108 pl/L test concentration, the 96-hour LC>~ for fathead minnows was also greater than 108 pl/L SF6 gas.

The water chemistry data for the fathead minnow test are summarized in Table 4.

In summary, neither Q. ~du i nor fathead minnow survival was affected by any of the SF6 concentrations we tested, including the 108 pl/L (highest test concentration) and 54 /il/L (present application of SF6) test concentrations.

Copies of the raw data sheets and standard reference toxicant data for the acute eNuent toxicity tests are included with this report in Appendices A and B.

If you have any questions or comments concerning the results of these toxicity tests, please contact either me or Mick DeGraeve at (616) 941-2230.

Thank you for the opportunity to provide this service to the Indiana Michigan Power Company. We appreciate your business and hope we can be of further service to you in the future. I will be in contact with you to arrange for the visit we have discussed.

cerely,

(,,'.,

Dennis J. McCauley Research Scientist DJM:din Enclosures AIV-118

TABLE 1. RESULTS OF A 48-HOUR CERIOOAPNHIA QUUBA STATlC RENEMAL ACUTE TOXIClTY TEST MITH SULFUR HEXAFLUORIDE GAS (SF6) INJECTED INTO A SAMPLE OF LAKE HICHIGAH MATER (GLCH 1765) RECEIVED ON SEPTEHBER 28, 1993, FROH COOK NUCLEAR PLANT NEAR BRIDGHAN, HICHIGAN USING RECOHS'IITUTED LABORATORY MATER AS DILUTIOH MATER (TEST DATES: OCTOBER 1-3, 1993)

Test Concentration Percent Surv val N ~ 20 (AI/L) 24hr 48hr laboratory Mater Control 95 95 M

l gi/L 100 100 14 AIIL 100 100 27 pl/L 100 100 54 HIIL 95 95 108 pl/L 100 100 48-hour LCso value was not calculable (Greater than 108 HI/L).

TABLE 2. IIATER CHEIIISTRY SIHHNRY FOR A AH-IICUR ~CERIOOAPSH A OUSIA STATIC REHEHAL.ACUTE TOXICITY TEST II!TH SULFUR IIEXAFLUORIOE HAS ISFAI TNJECTED INTO A SANPLE OF LAKE HlCHlGAN MATER (GLC¹ 1765) RECEIVEO ON SEPTEMBER 28, 1993, FROH COOK NUCLEAR POMER PLANT NEAR BRIOGHANH HICHlGAN USlNG RECONSTlTUTEO LABORATORY MATER AS 0ILU'llON MATER (TEST DA'TES OCTOBER 1 3H 1993)

Oissolved'xygen Speci f ic Test Teaperature'c Conducti vi ty Concentration H L os cm ~AI st n I Hardness'mg/L (Al/L) Hean Range Hean Range Hean Range Hean CaCOs) (mg/L CaCOs)

Laboratory 8.2 (8.1-8.4) 8.6 (8.0-9.0) 24.6 (24.1-25.0) 537 104 172 Mater Control 7 Al/L 8.3 (8.2.8.4) 8.6 (8.0-9.0) 24.6 (24.1-25.0) 557 14 Al/L 8.3 (8.2-8.4) 8.6 (8.0-9.2) 24.6 (24.1-25.0) 543 27 ALII. 8.3 (8.3.8.4) 8.7 (8.0-9.4) 24.6 (24.1-25.0) 511 54 Al/L 8.3 (8.2-8.4) 8.7 (8.0-9.4) 24.7 (24.2-25.0) 445 108 Al/L 8.2 (8.1-8.4) 9.0 (8.0-9.8) 24.8 (24.3-25.0) 304 128 Heasurements were made daily in each test chamber.

A single measurement was made at the beginning of the test on a cottposite saapie before distribution to the test chaahers and at the end of the test on a cerposite sasple.

Alkalinity and hardness measurements were made upon preparation of the reconstituted laboratory water and upon arrival at the laboratory of the effluent.

TABLE 3. RESULTS OF A 96-HOUR FATHEAD HINNOM STATIC RENEMAL ACUTE TOXICITY TEST M(TH SULFUR HEXAFLUORIDE GAS (SF6) INJECTED INTO A SAHPLE OF LAKE HICHIGAN MATER (GLC¹ 1765) RECEIVED ON SEPTEHBER 28, 1993, FROH COOK NUCLEAR POMER PLANT NEAR BRIDGHAH, HICHIGAN USING RECOHSTITUTED LABORATORT MATER AS DILUTION MATER (TEST DATES: OCTOBER 1-5 ~ 1993)

Test Concentration Percent Surv val N ~ 20 (Ni/L) 24hr 48hr - 72hr 96hr Laboratory Mater Control 100 100 100 100 7 NI/L 100 100 100 100 l

14 NI/L 100 95 95 95 27 NI/L 100 100 95 95 54 /El/L 100 100 100 100 108 Nl/L 100 100 100 100 96-hour LCso value was not calculable (greater than 108 HI/L)~

TABLE 4. IJATER CHEHISTRY SUHHAR'T FOR A 96-HOUR FATHEAD HINNit StATIC REHEMAI. ACUTE TOXICITY TEST MITH SULFUR HEXAFLUORIDE GAS INJECTED INTO A lAKE HICHIGAN IJATER SAMPLE (GLECg 1?65) RECEIVED ON SEPTEHBER 28, 1993, FROH COOK NUCLEAR PLANT NEAR BRIDGHAN, HICHIGAII USING RECONSTITUTED LABORATORY MATER AS DILUTION MATER (TEST DATESI OCTOBER 1-5, 1993)

Dissolved'xygen Speci f Test Temperature'C ic'onductivity Concentration L os clll ~A[kal n t Hardness (Al/L) New Old Hew Old New Old New Old (mg/L CaCO>) (mg/L CaCO>)

Laboratory 8.2 8.1 8.8 6.9 25.0 24.6 537 539 104 1?2 IJater Control (8.2-8.4) (7.9.8.2) (8.8 8.9) (6.2-7.5) (25.0-25.0) (24.2-25.3) . (494-566) (539-539) (104-104) (1?2.1?2) 7 Al/L 8.3 ~

8.1 8.9 7.5 25.0 24.6 556 547

(&.Z-&.4) (?.9.8.2) (8.8-9.0) (7.1.8.0) (25.0-25.0) (24.2-25.2) (537-58?) (547-547) 14 JII/L 8.3 8.2 9.0 7.4 25.0 24.6 539 531 (8.2-8.3) (8.1.8.2) (9.0-9.2) (6.6.8.0) (25.0-25.0) (24.2-25.1) (531-557) (531-531) 27 Al/L 8.3 8.1 9.1 7.1 25.0 24.6 514 502 (8.2-8.3) (8.0.8.2) (8.9-9.4) (6.5.8.0) (Zs.o-Zs.a) (24.3-25.1) (502-516) (502-516) 54 Al/L 8.2 8.1 9.2 7.2 25.0 -

24.6 444 438 (8.2-8.3) (8.1-8.2) (9.0 9.4) (6.9-7.6) (25.0.25.0) (24.0-25.1) (440-450) (438-438) 108 Al/L 8.1 8.0 9.8 7.5 25.0 24.6 311 304 10& 128 (8.1.8.2) (7.4-8.2) (9.6.10.2) (7.4.7.6) (25.0.25.0) (24.1.25.2) (303-316) (304-304) (106-106) (12&-128)

Heasurements were made on new test solutions and old test solutions. The nurbers represent the mean and range (in parentheses) of measurements observed during the test.

b Alkalinity and hardness measurements were made upon preparation of the reconstituted laboratory water and qmn arrival of the saaqle.

RAN'ATA HEETS AIV"123

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~ RERR5 585555 HRHSRHSHHHHRHHHSRIRHSRRWR 5$ 85QKIRRQMRQESRQERSQRSS

FISII 96-IIOUR STATIC ACUTE TOXICITYTEST

/7 2 I <<it FIJI<<nJI L/C. Type of Test: Dilution Water:

l lu/<<<<l Nu No. Fish/Chantbcr: GLC and/or Batch No.: /t I <<sl bp<<4I<<J No. of Chambers: z- Tcntpclaturc:

/) 4 0~

c I I ~ lull<<lJltJ hgc of Fisht Incubator 4t I aIi T<<<<h. Treatntent Lcv<<l . Contml Tins DJ Replicate Number Tcm cralure P(.o DO m/L S .Cond. umhos/cnt No. Live 0 /0 l0 rr0 /0

.'0 Omrvuiens 'Covs

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$ ~re P. c'~ ~ W DO m/L g C

/Z 8R. l. i Tcm cralure ZQ.2 '2>.v', "/ 0 No. Live 0 0 5Y n'\

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gp g 8'~ g'> 7 DO m/L f. $ ".0 ,S" 0 Tcm cralure 't C,Q n ) I

'l~igl( 5 No. Live '0 ID lo yO Observations /~ re'nJs'p DO m/L Tent cralun:

7,/ 7. D cp

/S.C 7 7, I I

7Q'.! 7 No. Live iO 0 JO Observations zo DO m /l. /. Cj 7.

S .Cord. umhos/<<m

()bi<<rvatnnt R<<y: DOB - Drie Out un B<<aLcr PM - Particulate Matter ERR - Ertetic Swimming FS - Film on Surface F - Floater IMM - Immobile Rcvicwcd by:

EFFLUENT AND RECEIVING WATER CHECK-IN FORM Client:FC'C'I- l4 rC Net-i project No.: -cC Investigators INITIALWATER CHEMISTRY (UPON RECEIPT)

Date Initials GLC No. i7( 5 Collection Date (time interval)

Temperature WATER CHEMISTRY AT TEST TEMPERATURES Date: Initials CcnQ

/Udc/ez 6 GLC No.

Temperature pH $

Dissolved Oxygen (mg/L)

Conductivity (umhos's/cm)

Hardness (mg/L) t /2. (0 Alkalinity (mg/L)

Total Chlorine (mg/L)*

Total Ammonia (mg/L)*

Check with project manager to see if necessary AjV-126

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APPENDIX B Ah'DARD REFERENCE TOXICANT DATA AIV-129

GREAT LAKES ENVIRONMENTAL CENTER Sodium Chloride (NaCI) Toxicity Data 1992 - 1993 grams/Liter 3.5 3.

2.5 M

I 1.5 o

0.5 0

APR MAY JUN JUL AUG OGT OGT NOV DEG JAN FEB MAR APR MAY JUN JUL AUG SEP I 1992 I 1993 I 48-hour LG50 ~ Mean plus

-El- Mean plus 2 S.D. ~ 1 S.D.

Mean minus 2 S.D.

Mean minus 1 S.D.

Ceriodaphnia dubia Survival

GREAT LAKES ONMENTAL CENTER Sodium Chloride (NaCI) Toxicity Data 1992 1993 grams/Liter 10 6:

0 APR MAY JUN JUL AUG OGT OGT NOV DEG JAN FEB MAR APR MAY JUN JUL AUG SEP I 1992 I 1993 I 48-hour LG50 Mean plus 1 S.D. ~ Mean minus 1 S.D.

Mean plus 2 S.D. Mean minus 2 S.D.

Fathead Minnow Survival

APPENDIX V ANNUAL REPORT'ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1993

DONALD C. COOK NUCLEAR PLANT UNITS 1 R 2 OPERATIONAL RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM 1993 ANNUAL REPORT JANUARY 1 to DECEMBER 31, 1993 Prepared by Indiana Michigan Power Company aIld Teledyne Isotopes April 15, 1994

TABLE OF CONTENTS SECTION TITLE PAGE Summary... ~ ~ ~ ~ ~ ~ ~ ~

I. Introduction II. Sampling and Analysis Program............................ 5 III. Summary and Discussion of 1993 Analytical Results ~ ~ ~ o 1 7 A. Airborne Particulates.................... 18 B. Airborne Iodine .. 20 C. Direct Radiation - TLDs 21 D. Surface Water ........ ~ ~ ~ ~ ~ ~ 2 1 E. Groundwater................ '.. 0 ~ 23 F. Drinking Water... ~ ~ ~ ~ 0 23 G. Sediment ~ ~ ~ ~ o ~ ~ ~ 28 H. Milk .. 29 I. FISl1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .......... 29 J. Food Products... ....... ~ . 30 IV. Conclusions..... ~ ~....... ~ . .31 R eferences ....................... ~... ~........ . 35

TABLE OF CONTENTS (Cont)

APPENDICES APPENDIX A - Radiological Environmental Monitoring... . 37 Program Summary - 1993 APPENDIX B - Data Tables .... ~ ~ ~ ~ ~ 42 APPENDIX C - Analytical Procedures Synopsis ................. . 69 APPENDIX D - Summary of EPA Interlaboratory Comparisons ........... 84 APPENDIX E - REMP Sampling and Analytical Exceptions.......... 113 APPENDIX F - Land Use Census ... 117 APPENDIX G - Summary of the Preoperational Radiological............ 124 Monitoring Program APPENDIX H - Summary of the REMP Quality Control Program ........ 12 APPENDIX I - Summary of the Spike and Blank Sample Program....... 130 APPENDIX J - TLD Quality Control Program ......... 142

TABLE OF CONTENTS (Cont)

LIST OF FIGURES Onslte TLD Locations o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ 1 1 Onsite - Groundwater Wells ................... 12 Onsite - Air Stations .................... 13 Onsite - Steam Generator Groundwater Wells ................... 14 Offsite - Air/TLDand Dnnking Water Locations.................. 15 Fish Locations 16 Milk Farm Survey Table 120 Residental Land Use Survey Table .. 121 Milk Farm Survey Map . o o o o ~ ~ o ~ o ~ ~ ~ ~ o ~ ~ ~ 122 Residential Survey Map . 123 LIST OF TRENDING GRAPHS Average Monthly Gross Beta in Air Particulates 19 Direct Radiation - Quarterly TLD's .. 22 Tritium in Groundwater 24 Tritium in Drinking Water ... 27 EPA Cross Check Program ... 89 Quality Control TLDs 144

LIST OF TABLES TABLE TITLE PAGE B-l Concentrations of Gross Beta Emitters in Weekly..... .... 43 Airborne Particulates B-2 Concentrations of Gamma Emitters in Quarterly.

Composites of Airborne Particulate Samples

........ 47 B-3 Concentrations of Iodine-131 in Weekly Air Cartridge........ . 49 Samples B-4 Direct Radiation Measurements - Quarterly TLD Results............. 53 B-5 Concentrations of Iodine, Tritium and Gamma Emitters...

in Surface Water B-6 Concentrations of Tritium and Gamma Emitters in ~ ~ ~ ~ ~ ~ ~ ~ ~ 57 Quarterly Groundwater B-7 Concentrations of Gross Beta, Iodine, Tritium and....... 59 Gamma Emitters in Drinking Water B-8 Concentrations of Gamma Emitters in Sediment ... 61 B-9 Concentrations of Iodine and Gamma Emitters in Milk ... ~ 62 B-10 Concentrations of Gamma Emitters in Fish 65 B-11 Concentrations of Gamma Emitters in Food/Vegetation ...... 66 B-12 'typical LLDs Achieved

SUMVIARY 0

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

SUMMARY

This report summarizes the collection and analysis of various environmental sample media in 1993 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 discernable impact of the 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 0

t. ~IIITRODUCTt N Qs 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 Environmental Operating Report for Units 1 and 2 of the Donald C.

Cook Nuclear Plant for the operating period from January 1, 1993 through December 31, 1993.

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

~

~

2 achieved initial criticality on March 10, 1978.

~ ~

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II 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.

II. SAMPLING AND ANALYSIS PROGRAM II. SAMPLING AND ANALYSIS PROGRAM Table 1 suaUnarizes the sampling and analysis program for the Donald C. Cook Nuclear Plant for 1993. For each sample medium, the table lists the r

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 through 6. Also for each sample medium the sample collection frequency, type of analysis, and frequency of analysis are listed.

Cl TAB DONALD C. COOK N PLANT- 1993 RADIOLOGICAL SA NG STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station DIstance Direction De rees Fre uen AnaI sis/Ae en Environmental (TLD's)

ONS-1 (A-1) 1945 18'80 ONS-2 (A-2) 2338 fL ONS-3 (A-3) 2407 fL 904 ONS-4 (A-4) 1852 fL 1 18'894 ONS-5 (A-5) 1895 fL ONS-6 (A-6) 1917 IL 2100 ONS-7 (A-7) 2103 fL 360 ONS-8 (A-8) 2208 fL 820 ONS-9 (A-9) 1368 fL 149'270 ONS-10 (A-10) 1390 fL ONS-11 (A-1 I) 1969 fL 114 ONS-12 (A-12) 2292 IL 630

~ New Buflalo (NBF) 15.6 ml SSW Quarterly Direct Radlatlon/Quarterly South Bend (SBN) 26.2 ml SE Dowaglac (DOW) 24.3 nl I ENE Coloma (COL) 18.9 ml NNE Intersection of Red Arrow Hwy. & Marquelte (OFS-1) . 4.5 NE Woods Rd, Pole NB294-44 Stevensvllle Substatlon (OFS-2) 3.6 ml NE Pole N B296-13 (OFS-3) 5.1 nl I NE Pole ¹B350-72 (OFS-4) 4.1 ml E Intersection of Shawnee & Cleveland, Pole (OFS-5) 4.2 ml ESE N B387-32 Rd., East of Holden Rd..

'now (OFS-6) ml SE

¹B426- I Brldgman Substatlon (OFS-7) 2.5 nl I S Callfornla Rd., Pole NB424-20 (OFS-8) 4.0 ml S Rlggles Rd., Pole B369-214 (OFS-9) 4.4 nl I ESE Intersection of Red Arrow Hwy., & (OFS-10) 3.8 ml S Illldebrant Rd..Pole N B422-152 Intersect!on of Snow Rd. & Baldwin Rd.. (OFS-11) 3.8 ml S Pole ¹B424-12

TABLE 1 (Cont.)

DONALD C. COOK NUCLEAR PLANT- 1993 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station DIstance Direction De rees Fre uenc Analysis/Fre uen Air Charcoal/Particulates ONS-I . (A-I) 1945 fL ONS-2 (A-2) 2338 fL 18'8'0o ONS-3 (A-3) 2407 fL ONS-4 (A-4) 1852 fL 1 ONS-5 (A-5) 1895 fL 18'89'10 ONS-6 (A-6) 1917 fL Weekly Gross Beta/Weekly New Buffalo (NBF) 15.6 ml SSW I-131/Weekly South Bend (SBN) 262 ml SE Gamma Isotopic/

Dowaglac (DOW) 24.3 ml ENE Quarterly Composite Coloma (COL) 18.9 ml NNE 00 Groundwater Onslle (W- I) 1969 fL 114 Onslte (W-2) 2292 fL Onslte (W-3) 3279 fL 63'07'01'90O Onslle (W-4) 418 fL Quarterly Gamma Isotopic/Quarterly Onslle (W-5) 404 ft. Trltlum/Quarterly Onslle (W-6) 424 fL Onslte (W-7) 1895 fL Onslte (W-8) 1279 fL 273'89'3'2'29o Onslte (W-9) 1447 fL On site (W-10) 4216 ft.

Onslte (W-11) 3206 fL 1534 Onslte (W-12) 2631 fL 1620 Onslle (W-13) 2152 fL 1820 Onslte (iV-14) 1780 fL 1640 Non Technical S clflcatton Related Wells Steam Generator Storage Facility (SGRP- I) 0.8 111 I 950 Steam Gerrerator Storage Faclllly (SGRP-2) 0.7 ml Gross Beta/Qr rly Steam G r Storage Faclllty (SGRP-4) 0.7 ml 92'3'24 Quarterly Gross Alpha erly Steam Ge or Storage Faclllty (SGRP-5) 0.7 mI Gamma Isolo uarterly

TABLE .)

DONALD C. COOK NU PLANT- 1993 RADIOLOGICALSAM NG STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Direction De rees Fre uency Anal Is/Fre uen Drlnkln Water St. Joseph Public Intal<e (STJ) 9.0 ml Gross Bela/14 Day Composite Gamma Isotopic/14 Day Composite 1-131/14 Day Composite Lake Township Public Intake Station (LTD) 0.4 ml S Trltlum/Quarterly Composite Surface Water Condenser Clrculallng IVater Intake L-I Intake Lal<e -hllchlgan Shoreline L-2 0.3 ml S Dally Gamma Isotopic/Monthly I eke Mlchlgan Shoreline L-3 0.2 ml N Composite Lal<e Mlchlgan Shoreline L-4 500 ft S Tritium/Quarterly Composite I eke Mlchlgan Shoreline L-5 500 ft N Sedhnent Lake Mlchlgan Sliorellne L-2 0.3 ml S I ake Mlchlgan Shoreline 1.-3 0.2 ml N Semi-annually Gamma Isotopic/Seml-I ~ke Mlchlgan Shoreline 500 ft S Annually I eke Mlchlgan Shorelh>e L-5 500 ft N Milk-Indicator Totzke Farm Baroda To tzke 5.1 Int ENE Schuler Farm Baroda Schuler 4.1 ml SE oaf mblen Farm Three Oaks Warmblen 7.7 ml S 14 Days 1-131 Sample Freeh ling Farm Buchanan Freehllng 7.0 ml SE Milk-Back round IVyant Farm Dowagalc IVyant 20.7 ml Once every Gamma Isotopic/Sample Llvlnghouse Farm La Porte Llvlnghouse 20.0 ml 14 Days 1-131/ Sample

TABLE 1 IC(n)t.)

DONALD C. COOK NUCLEAR PLANT- 1993 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station DIstance Direction De rees Fre uenc Anal sls/Fre uen

~Bah Lake Michigan ONS-N .3 ml N 2/year Gamma Isotopic Lake Michigan ONS-S .4 ml S 2/year I eke Michigan OFS-N 3 .5ml N I eke Michigan OFS-S 5.0 mt S Gra es/Broadleaf Nearest sample to Plant. Sector A At time of harvest, Gamma Isotopic at in hlghesl. D/Q land sector time of harvest.

Gra es In a land sector conialnlng grapes Sector J At time of harvest Gamma Isotopic at, approximately 20 miles lrom the Plant time of harvest.

and 180'rom the sector with the highest D/Q.

Approximately 20 mlles from the Plant Sector A At time of harvest Gamma Isotopic at time of harvesL Composite samples of Drinking and Surface water shall be collected at least dally.

Particulate sample Alters 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 ln air or water ls greater than 10 times the yearly mean of control samples for any medium. gamma isotopic analysis shoukl be performed on the individual samples.

Please note the lollowlng dcfenltlons:

Weekly at least once every seven (7) days Monthly - at. least once every (31) days Quarterly - at least once every nlncty-two (92) days Semi- ally - at least once every one hundred eighty-four (184) da

v IJQ I.I GI ND D A1 Oi>site 'I'LI) Loc;itious>s Al Tl>roiigh AI2 4 Qy I

~ 0 p 0 0

TLD A11 ~TLD A2 LP A12 LD A7

/ Pn~- ~c

)

( ~

TLD A10 'LD A3 I'P TLD A5 TLD A9~ ~ TLD A4

/ Q ilp TLD AB (W~

h

l 0

~ O o 0 WELL l~~~ LL 2 WELL 9 WELL 4 I I

WELL 5 ELL 8 /

WEI L 0

'i a~ /

~>o 1

'4 L4 WElL >~~<

7 WELL IB i'X ~P 0

~WELL 1 .u~)~ fD Q

r LAKP ~P . WELL 12 8 WELQ 8

! / /

WELL 14 /

E1 LL 11 I/ O

Ll 8

AIR A1 dQ

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~

0 0 g 0 0 0

Oi>site Air SInti~>>is A I TI>rough A6 AIR A2

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/ ) 0

)

A(P A3 AIR A5 .g(

Alg A4 AIR A6 -e~)),

yo ~i SGRP SELL 2 Oy+

5o SGRP M/ELL 5 - SGRP QUELL

/////1// /~ ll Wo VK 'GRP ECI 5

Cl

)~ ~W o ( ~LEGE D Steani Gener:itor Gronn~livnter Wells SGRP 1, SGRP 2, SGRP 4 and SGRP 5

/

FIGURE 5 LEGEND SITE REMP MONITORING LOCATIONS ground Air/TLD locations COLOMA site TLD locations SUBSTATION BACKGROUND Background Milk Farms AIR / TLD II Drinking Water locations Indicator Milk Farms BENTON HARBOR ST. JOSEP ST. JOSEPH WATER TREATLIENT i PLANT (DRINKING DOWACIAC SUB STATIO,

TlD WATER)'fJIV SOIIU S BACXGROUII

/ TA 'I TLD 1 TLD- 2 TLD -4 l

TLD 9 fg TLD- 5 CAAAAO lOlAICS erma I IAKS COAl LAKE TOWNSHIP WATER TREATLIEN I PLANT PO H

!AROOA (DRIHIONG WATER)

\ I TLD 11 /

TLD- 8

~

DOWAGIAC FARMS TLD- 8 VIC WYANT J~NINhl NCV 1IIQY / A

~RS NM'" ~ /

/

EW BUFFALO BSTATIOH CKCROUND R / TLD HCV %ITALO A

U 0

ROSLlNQ tRAOAIS IAPORTE FARM RAY UVINGHOUSE SOUTH BEND ANKAKEE STATION BACKGROUND AIR / TLD 15

~

I '

I

~

I I I

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'gfgp-~~

<g',(KFii,.;.i.a@ ~ e~

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l Ei t-.-

.>l

III. SURVEY AND DISCUSSION OF 1993 ANALYTICALRESULTS 17

III.

SUMMARY

AND DISCUSSION OF 1993 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 1993 were analyzed by Teledyne Isotopes, Inc. (TI) in Westwood, New Jersey. The procedures and specifications followed at Teledyne Isotopes are in accordance with the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples are proved in Appendix C. In addition to internal quality control measures performed by Teledyne, the laboratory 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 environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix D.

Radiological analyses of environmental media characteristica approach and frequently fall below the detection limits of state-of-the-measurement methods. Teledyne Isotopes 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 a constant flow oil less pump ai 56 LPM using a 47 mm particulate filter. Results gross beta activities are presented in Table B-1. The measurement 18

~ ~

e ~ ~ 0

~ ~ g 0

G G

G

~ ~

~ ~

the gross beta activity on the weekly air particulate filters is a good indication of the levels of natural and or manmade radioactivity in environment. The average gross beta concentration of the s indicator locations was 0.018 pCi/m3 with a range of individual values between 0.003 and 0.036 pCi/m3. The average gross beta concentration of the four control locations was 0.018 pCi/m3 with a range between 0.006 and 0.035 pCi/m3. In Trending Graph 1 the monthly average gross beta concentrations for the indicator locations and for the control locations are plotted. The gross beta concentrations in air particulate filters in 1993 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. Beryllium-7 which is produced continuously in the upper atmosphere by cosmic radiation was measured in all forty samples. The average concentration for the control locations was 0.112 pCi/m3 and th values ranged from 0.083 to 0.135 pCi/m3. The, average concentrati for the indicator locations was 0.118 pCi/m3 with a range of 0.090 to 0.149 pCi/m3. These values are typical of beryllium-7 measured at various locations throughout the United States. Naturally occurring potassium-40, probably from dust, was measured in seven of the twenty-four indicator quarterly composites with an average concentration of 0.012 pCi/m3 and a range of 0.004 to 0.032 pCi/m3.

Potassium-40 was measured in four of the sixteen control quarterly composites with a concentration of 0.005 pCi/m3 and a range of 0.004 to 0.006 pCi/m3. No other gamma emitting radioactivity was detected.

B. Airborne Iodine Airborne particulate samples are collected with a constant flow oil less pump at 56 LPM using a 47 mm particulate filter. Teda-3B 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.

20

results were below the lower level of detection 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 record exposure from all of these potential sources. The TLDs are deployed quarterly at 27 locations in the environs surrounding the D. C. Cook Nuclear Plant. The average value of the four areas of each dosimeter (calibrated individually after each field exposure period for response to a known exposure and for transit exposure) are presented in Table B-4. Those exposure rates are quite typical of observed rates at many other locations in the country. The average annual measurement for the control samples was 3.71 mR/standard month with a range of 2.7 to 5.0 mR/standard month.

The annual accumulation of indicator samples had a measurement of 3.98 mR/standard month with a range of 2.4 to 5.9 mR/standard month. The 1993 annual average in the environs of the D. C. Cook 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 One liter surface water samples from the intake forebay and from four shoreline locations, all within 0.3 mile of the two reactors were collected and composited daily over a monthly period. The samples were analyzed for iodine-131 by the radiochemical technique described on page 79. No iodine-131 was detected. The quarterly composite was analyzed for tritium by liquid scintillation method described on page 74. Naturally occurring potassium-40 and cesium-II 21

"Trending Graph - 2 DIRECT RADIATION- QUARTERLY TLD RESULTS Q.;'

0 Q.

O A.

0

-'0 O ~

-==-'- 4

/ -A

'a":

C O' /

~ f/=

• 2 Q)

K,

~ .,,1 1

,'C: ~

0 i 01/9 0 07/90 -

. 01/91 07/91 ~ ~

1/92 , 7/92 ,

. 1/93. 7/93 ;1/94 TLD ntrois TLD Indicators

137 were not measured during 1993. Tritium was detected in 7 of the 20 samples analyzed with an average concentration of 166 pCi/liter and a range of 140 to 190 pCi/liter. This is lower than the 12 measurements in 1992 which had an average concentration of 554 pCi/liter. During the preoperational period tritium was measured in surface water samples at concentrations of approximately 400 pCi/liter. Naturally occurring gamma emitting isotopes were detected using gamma ray spectroscopy.

E. Groundwater Water samples are collected quarterly from fourteen wells, all within 3300 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. A one gallon 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 58.8 pCi/liter.

Thorium-228 was measured in one sample with a concentration of 10.9 pCi/liter. No other gamma emitting isotopes were detected. The groundwater wells W-4, W.-5, W-6, W-7, W-8, W-ll, W-12, W-13 and W-14 had measurable tritium activity throughout 1993. Tritium was measured in 23 of the 56 samples at the locations rwith an average concentration of 647 pCi/liter and a range of 200 to 1200 pCi/liter.

The annual concentrations of tritium in wells W-1 through W-7 are plotted in Trending Graph 3. An additional six wells were added to the program during 1992 and one well in 1993. The results are plotted quarterly for 1993 in Trending Graph 3.

Tritium concentration in groundwater wells during the preoperational period typically averaged 400 pCi/liter.

r. ~ki Daily samples are collected at the intake of the purification plants for St. Joseph and Lake Township. The 500 ml daily samples at 23

I ~ ~ ~

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~ ~ ~ ~ ~ ~

~ ~ e ~

~ ~ ~ ~ ~ ~

I

Trending Graph - 3 (Cont.)

TRlTIUN lN GROUNDNATER 4000 Q

I O

CL 0 2000 ro Q Ch C 1000.

th 0-1$ 2 4i92 7$ 2 10$ 2 1J9S 6$ S 11$ 8 ~,

Well-8 ~ Well-9 ~ Well-10 Well-11 -E}- Well-12 ~ Welt-13 ~ Well-14 Well 14 added to the program in 1993.

0

~~

each location are composited and analyzed for gross beta, iodine-131, and gamma emitters. On a quarterly basis the daily samples composited and analyzed for tritium. The results of analyses drinldng water samples are shown in Table B-7.

Gross beta activity was measured in all twenty-six samples from the Lake Township intake with an average concentration of 3.4 pCi/liter and a range from 2.0 to 5.0 pCi/liter. Gross beta activity was measured in aQ twenty-six samples from the St. Joseph intake with an average concentration of 3.9 pCi/liter and a range from 2.5 to 7.3 pCi/liter. No gamma emitting isotopes or iodine-131 were detected.

Tritium was not measured in any of the four samples from either location. Tritium in drinking water is plotted in Trending Graph 4.

The're were no drinking water analyses performed in the preoperational program.

G. Sediment Sediment samples are collected semiannually along the 0

shoreline of Lake Michigan at the same four 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 May and November one sample was collected from each location L2, L3, L4 and L5. Gamma ray spectroscopy detected naturally occurring potassium-40 and in all samples. The average potassium-40 concentration was 5609 pCi/kg (dry weight) with a range from 3660 to 6930 pCi/kg (dry weight).

Thorium-228, also naturally occurring was measured in all samples with an average concentration of 129 pCi/kg (dry weight) with a range from 96.5 to 158 pCi/kg (dry weight). All other gamma emitters were below the lower limits of detection.

28 ~

H. Milk Milk samples of one gallon are collected from a 500 gallon bulk tank every fourteen days from six farms located between 4.1 miles and 20.7 miles from the site. Milk samples are preserved by adding 40 grams per gallon of sodium bisulfate when the samples are collected.

The samples are analyzed for iodine-131 and other gamma emitters.

The results are shown in Table B-9. Iodine-131 was not measured in any of the 156 samples analyzed.

During the preoperational period potassium-40 was measured in all samples with a range from 520 to 2310 pCi/liter, a range comparable to that in 1993. Iodine-131 was measured in four samples with concentrations between 0.2 and 0.9 pCi/liter. Cesium-137 was measured in numerous samples with concentrations between 7 and 64 pCi/liter.

During 1993 the average potassium-40 concentration for the control locations was 1342 pCi/liter with a range of 1120 to 1610 pCi/liter. The indicator locations had an average concentration of 1393 pCi/liter and a range of 1080 to 1790. There were no detections of iodine-131 during 1993. Cesium-137 was not detected during 1993.

I. Fish Using gill nets in approximately twenty feet of water in Lake Michigan, 4.5 pounds of fish are collected 2 per/year from each of four locations. The samples are then analyzed by gamma ray spectroscopy.

Naturally occurring potassium-40 was measured in all samples with an average concentration of 3174 pCi/kg (wet weight) and a range of 2520 to 3870 pCi/kg (wet weight). Cesium-137 was measured in three of the eight fish samples with an average concentration of 68.3 pCi/kg (wet weight) and a range of 58.6 to 74.3 pCi/kg (wet weight).

29

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

They consist of 5 pounds of grapes, 1 pound of grape leaves and 5 pounds of broadleaves. Naturally occurring potassium-40 was measured in all five samples with an average concentration of 3102 pCi/kg (wet weight) and a range of 1890 to 6460 pCi/kg (wet weight).

Cosmogenically produced beryllium-7 was measured in all samples with an average concentration of 1978 pCi/kg (wet weight) and a range of 131 to 3980 pCi/kg (wet weight).

30

IV. CONCLUSIONS 31

IV. CONCLUSIONS The results of the 1993 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 1993 appears 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 sampl identified the gamma emitting isotopes as natural products (beryllium-7 an potassium-40). No man-made activity was found in the particulate media during 1993. No iodine-131 was detected in charcoal filters in 1993.

Thermoluminescent'osimeters (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 mgosure levels.

I Surface water samples are collected daily from the intake forebay and four locations in Lake Michigan. The samples are analyzed quarterly for tritium, and monthly for gamma emitting isotopes. No gamma emitters were detected during 1993. Tritium was measured and the concentrations were at normal background levels.

Groundwater samples were collected quarterly at fourteen wells, all within 3300 feet of the reactors. The three wells within 500 feet h measurable tritium which is attributed to the operation of the plant. Th 32

tritium levels in 1993 compare well with those measured in 1992. The highest concentration measured in 1993 was 1200 pCi/liter while the highest concentration measured during 1992 was 1500 pCi/liter. The tritium levels in groundwater have been plotted for the last decade and are shown in trending graph 3. Potassium-40, 'a naturally occurring nuclide was observed in one sample during 1993. 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 for gamma emitting isotopes and 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 four of the eight quarterly composite samples with background levels that were lower than those measured during 1992.

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 four 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 collected every fourteen days from six farms up to a distance of 20.7 miles from the site. The samples were measured for iodine-131 and other gamma emitting isotopes. Although I-131 was CI measured during 1989 there were no measurements of iodine-131 in milk during 1993, 1992 or 1991. Potassium-40 was measured in all milk samples at normal background levels. Cesium-137 was not detected in 1993.

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

33

Food products, consisting of grapesgrape leaves, and broadle vegetation were collected and analyzed by gamma ray spectroscopy.

only gamma emitting isotope measured was cesium-137.

The results of the analyses have been presented. Based on the t

evidence of the Radiological Environmental Monitoring Program the Donald C. Cook Nuclear Plant is operating within regulatory limits. Tritium in five 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.

34

V. REFERENCES 35

V. REFERENCES

l. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants", December 1975.

2. Indiana Michigan Power Company, D. C. Cook Technical Specifications, Units 1 and 2.

3. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program", Rev. 1, November 1979.

4. Eberline Instrument Company. Indiana Michigan Power Company, "D. C. Cook Nuclear Plant Radiological Environmental Monitoring Program - 1974 Annual Report",

May 1975.

5. Data Tables from 1985-1988 CEP-AEPSC Annual Radiological Environmental Monitoring Program Reports.

6. United States Nuclear Regulatory Commission, Regulatory Guide 1.4 "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants", April 1975.

7. 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.

36

APPENDIX A RADIOLOGICALEFPTIRONMENTAL MONITORING PROGRAM SUEBdARY

'37

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 60-S16/60-S16 BERRlEN COUNTY JANUARY 1 to DECEMBER 31. 1993 YSIS hIEDIUM OR PATIIWAY TOl'ALNUMBER CONmOL LOCATION NONROUIINE SAhIPk,ED OF ANALYSES hIEAN ta/b) NAME MEAN MEAN REPORIED IUNITOF MEASUREMENII PERFORMED RANGE DISTANCE AND DIRECI1ON RANGE RANGE MEASUREMENIS Air Iodine 1-131 518 -(0/310) N/A N/A -(0/208)

(pCI/m3)

Airborne Gross Beta 518 17.7(310/310) A-3 Onslte 2407 fL 18.5(52/52) 17.8(208/208)

Particulates (tVeekly) (3.2-36) (8.1-33) (5.7-35)

(IE-03 pCI/m )

Gamma 40 Be-7 40 118(24/24) A-3 Onslte 2407 fL 122(4/4) 112(16/16)

(90.4-149) (96.2-137) (83.2-135)

K-40 40 11.9(7/24) A-5 Onslte 1895 ft. 19.1(2/4) 4.85(4/16)

(4.27-32.2) (6.07-32.2) (3.92-5.91)

Direct Radiation Gamma 107 (mR/Standard Dose 3.98(91/91) OFS-8 4.0 ml S 4.58(4/4) 3.71(16/16)

Mont)1) Quarterly (2.4-5.9) (3.7-5.2) (2.7-5.0)

(a/b) f samples with detectable acttvlty to total number of samples d.

RADIOLOGICALENVIRONMEN NITORING PROGRAM

SUMMARY

INDIANAhIICHIGAN POWER COMPANY - DONAL . COOK NUCLEAR PLANT DOCKET NO. 60-316/60-3 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1993 ANALYSISAND NUMBER OF MEDIUM OR PAT) IWAY mfALNUMBER CONfROL LOCATION NONROUllNE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORfED (UNITOF MEASUREMEVF) PERFORMED RANGE DISfANCE AND DIRECfION RANGE RANGE M EASUREM ENfS Surface Water Gamma 65 (0/65) N/A (0/0)

(pCI/IIter)

H-3 20 166(7/20) I 2 0.3ml S 190(1/4) -(0/0)

(140-190)

Groundwater Gamma (pCI/IIter)

K-40 58.8(1/56) Well 3 3279 ft. 58.8(1/4) -(0/0)

'fh-228 10.9(1/56) Well 12 2631 A. 10.9(l /4) -(0/0)

H-3 647(23/56) Well 4 418 ft. 980(3/4) -(0/0) 0 (200-1200) (790-1200)

Drinking Water Gross Beta 52 3.66(52/52) STJ 9.0ml NE 3.93(26/26) -(0/0)

(pCI/IIter) (2.0-7.3) (2.5-7.3) 1-131 52 -(0/52) N/A N/A -(0/0)

Gamma 52 -(0/52) N/A N/A -(0/0)

H-3 -(0/8) N/A N/A -(0/0)

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

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 60-316/60-316 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1993 ANALYSISAND N MUER MEDIUM OR PATIIWAY TOI'AL NUMBER CONTROL LOCATION OI'ONROIJnNE SAMPLED OF ANALYSES MEAN ta/b) NAME MEAN MEAN REPORPED IUNrl'oF MEAsUREMENf) PERFoRMED RANGE DISTANCE AND DIRECIlON RANGE RANGE MEASUREMENfS Sediment Gamma 8 (pCI/kg dry)

K-40 - 8 5609(8/8) I 2 6250(2/2) -(0/0)

(3660-6930) 0.3ml S (5570-6930)

Ra-226 8 -(0/8) -(0/0)

Th-228 8 129(8/8) L-2 157(2/2) -(0/0)

(96.5-158) 0.3mt S (155-158)

Milk Gamma 156 (pCI/IIter)

K-40 156 1393(104/104) Totzke 1449(26/26) 1342(52/52)

(1080-1790) 5.1 mt ENE (1240-1630) (1120-1610) 1-131 156 -(0/104) N/A N/A -(0/52) 0 Cs-137 156 -(0/104) N/A N/A -(0/52)

(a/b) f samples with detectable actlvtty to total number of samples red.

RADIOLOGICALENVIRONMENT NITORING PROGRAM

SUMMARY

INDIANAMICHIGAN POWER COMPANY DONALD C. - COOK NUCLEAR PLANT DOCKET NO. 60-816/60-S1 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1993 ANALYSISAND 0 hll'.DIUM OR PAT) IWAY lmALNUhll)F.R '

r CONfROL LOCATION NONROINE REPOKfED SAMPI.F I> OF ANAI.YSES MB% Ia/I>) NAhlE MEAN MEAN IUNfl'OF MEASUIIEMENf) PEI\FORhIED RANGE DISfANCE AND DIRECllON RANGE RANGE hIEASUREhIENfS Fish Gamma (pCI/kg wet)

K-40 3174(8/8) OFS-North 3460(2/2) -(0/0)

(2520-3870) 3.5 ml N (3050-3870)

Cs-)37 68.3(3/8) OFS-North 74.3(1/2) -(0/0)

(58.6-74.3) 3.5 ml N Food/Vegetation Gan)ma (pCI/kg wet)

Be-7 1978(5/5) Sector B 2144(2/2) -(0/0)

(131-3980) Variable (807-3480)

K-40 5 3102(5/5) Sector B 4330(2/2) -(0/0)

(1890-6460) Variable (2200-6460)

Cs-137 -(0/0) N/A N/A -(0/0)

(a/b) Ratio of samples with delectable actlvlty to total'number of samples analyzed.

APPENDIX B DATATABLES 42

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMI'ITERS IN WEEKLY AIRBORNE PARTICULATES Results ln Units of IO-s pCI/m3 k 2 sigma STATION CODES COLLECTION A-1 A-2 A-3 A-4 A-5 A-6 New BuN South Bend 'verage DATES CoIoma Dowagtac i2 s.d.

JANUARY 93 01/04/93 15+ 2 14 2 2 15 2 2 18% 2 15+2 14 k2 16% 2 14 k 2 16% 2 14 k 2 15% 3 01/11/93 29+ 2 29 2 2 31 k2 27k 2 31+2 31 k2 26 k 2 29 2 2 29k 2 27 k 2 29+ 4 01/18/93 21% 2 2122 22 2 2 22k 2 21%2 22 k 2 20 R 2 22 k 2 22k 2 25 k 2 22k 3 01/25/93 15' 16 22 16 2 2 16% 2 15%2 18 k 2 15%2 15 2 2 15% 2 17 2 2 16% 2 02/01/93 20% 2 20 2 2 21 f2 201 2 18 2 2 21%2 20 2 2 20 k 2 20% 2 20,% 2 20% 2 FEBRUARY 02/08/93 18 k-2 20%2 192 2 19+ 2 17 k 2 22k 2 18% 2 2122 17% 2 18 k 2 19% 3 02/15/93 21% 2 21 k2 1922 18% 2 22 k2 20 k 2 20 k 2 20 k 2 21% 2 23 2 2 20% 3 02/22/93 25k 2 22 2 2 25 2 2 26k 2 25+2 24 a 2 2422 26 2 2 24k 2 20 k 2 24k 4 03/01/93 202 2 18 22 21 k2 182 2 18 2 2 19 2 2 20 f2 21%2 21% 2 21 k 2 20% 3

~RCH 03/08/93 30 2 2 1.3 k 0.7la) 29 2 2 24+ 2 2722 26 k 2 24%2 29 k 2 25k 2 30+2 27% 5 03/15/93 17% 2 (b) 1622 142 2 19%2 17 k 2 18% 2 16%2 15% 2 - 17%2 17% 3 03/22/93 19+ 2 (b) 18 +2 15% 2 19%2 18a2 17 k 2 17 2 2 19% 2 17%2 03/29/93 8.7 2 1.5 10 2 2 8.1 k 1.4 6.9 2 1.4 7.1 R 1.4 7.5k 1.4 6.2 k 1.3 7.0 k 1.4 8.5 i 1.5 7.8 i 1.4 18% 3 8k 2 QuarterAvg. 201 12 191 10 20k 12 19k 11 20% 12 201 11 19 2 10 20 k 12 19 k 11 20% 12 202 1 la) Power I'allure: results In total pCI and not Included In averages.

Ib) Power Iallure: sample unavailable.

TABLE B-1 tCont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMITIERS IN WEEKLY AIRBORNE PARTICULATES Results ln Units of 10 3 pCI/m3 2 2 sigma STATION CODES COLLECTION A-1 A-2 A-3 A-4 A-5 A-6 Coloma Dowagfac New Buff South Bend Average DATES 2 2 s.d.

04/05/93 1622 15%2 15-k2 12%2 14%2 13%2 12%2 13%2 14% 2 14%2 14% 3 04/12/93 1042 1122 11%2 9.3 k 1.7 9.4 2 1.7 9.0 k 1.7 9.0 k 1.7 12 k2 7.9 2 1.6 12 + 2 10% 3 04/19/93 14 k2 14+2 16%2 15 % 2 2 12 2 2 14%2 14%2 142 2 13%2 04/26/93 05/03/93 161 2 1512 21%2 1422 1722 18%2 i

15 2 ll k2 14 18 i 18%2 2 16 2 2 33k 1.1 16%2 10%2 15%2 2312 15+ 2 1.72 0.7(a) 16%2 17%2 14%

16%

14%

2 4

11 05/10/93 16 2 2 15 k 2 15 2 2 15 k2 14 k2 13 2 2 10%2 16 %2 15% 2 15%2 14% 3 45 05/17/93 8221.6 I3i2 1222 15%2 12%2 12%2 11%2 24 k 2 ilk 2 15%2 132 9 05/24/93 05/31/93 11%2 10 k 2 1122 8.82 1.5 1122 9.9k 1.5 12%2 9.8k 1.5 32%08(a) 12%2 8.4k 1.4 8.3% 1.4 9.7 k 1.5 7.6 i 1.4 10 +2 10 k 2 9.6k 1.5 5.7 2 1.0 12 k 2 6.1

• 1.0 ll + 2 9k 3 JUNE 06/07/93 06/14/93 9.9 11%2 i 1.6 7.7k 1322 1.5 12+2 1722 9.2%1.6 1322 10%2 15%2 12+1 15%2 9.3 R 14a2 1.6 13 k2 9.3k 1.6tb) 14 2 2 11% 4 15%2 12+ 2tb) 15%2 15% 2 06/21/93 10% 2 6.7k 1.4 8.5% 1.5 10 k2 7.9k 1.5 8.8k 1.5 12% 2 8.8% 1.6 8.0+ 1.7 13 k 2 9k 3 06/28/93 12%2 12%2 13%2 1322 13%2 14%2 12 2 2 12%2 13% 2 12%2 13% I QuarterlyAvg. 12%6 12%7 13%6 1225 12t8 11%7 11%4 14%9 11% 7 1SR 5 12% 2

[a) Power results In total pCI and not Included In averages.

lb) Powe: e; low volume. Not Included In averages.

T 1 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMITI'ERS IN WEEKLY AIRBORNE PARTICULATES Results ln Untts of 10 s pCI/m3 2 2 s)gma STATION CODES COLLECTION A-1 A-2 A-3 A-4 A-6 A-6 Colo ma Dowaghtc New Buff South Bend Average DATES k 2 s.d.

07/05/93 07/12/93 14% 2 14% 2 14 1.2 14 k 2 15 16 k2

% 2 14 12 i 22 15 k 2 14 2 2 14 2 2 14 % 2 16%2 13 2 2 1421 12 k2 13%

16%

2 2

'174 16% 2 2 15+ 2 14% 3 07/19/93 142 2 14 2 2 1322 14% 2 12% 2 13% 2 loa2 13 k 2 13% 2 14% 2 13% 2 07/26/93 14% 2 10 k 2 13%2 14% 2 14k 2 14% 2 15+2- 24 k 3 (a) 16% 7 08/02/93 19+ 2 16 a Stb) 18 R 2 17 k 2 16 i 2 16 k 2 17 2 2 14 k 2 16%

2 2

15% 2 1?k 2 15%

17% 3 AUGUST 08/09/93 13k 2 11%5(b) 1412 13% 2 13% 2 13% 2 11%2 12%2 13% 2 13% 2 13% 2 08/16/93 19% Stb) <7(b) 2912 27k 2 24k 2 26k 2 2042 2222 25+ 2 27k 2 24k 7 08/23/93 IS% 2 <20(b) 2022 20% 2 22k 2 17% 2 2122 18%2 18% 2 22k 2 20% 4 08/30/93 22 k 2 2.5k 0.8tb)2602 3(c) 17 k 2 23 k 2 22k 2 22%2 2222 22k 2 22k 2 22+ 4 SEPTEMBER 09/06/93 192 2 1612 16%2 14% 2 15+ 2 13% 2 15%2 14 2 2 14% 2 14% 2 15% 3 09/13/93 182 2 17%2 16%2 19% 2 172 2 16% 2 17% 2 18 2 2 19% 2 17% 2 17+ 2 09/20/93 22k 5tb) 1822 1822 142 2 16% 2 17% 2 17% 2 16 %2 16k 2 18% 2 17% 4 09/27/93 18 k 2 0.79 2 0.54tc)21 k 2 192 2 172 2 172 2 17% 2 18 2 2 18% 2 18% 2 18% 3 10/04/93 14% 2tb) 14%2 1722 142 2 14% 2

• 14% 2 14 2 2 13 2 2 16% 2 16% 2 15k 3 QuarterlyAvg. 17 ~ 6 16 ~ 6 17 ~ 9 16% 8 172 8 16a 7 16a7 1628 17% 7 18% 8 17% 2

[a) Low sample volume; unit replaced.

tb) Power I'allure: Iow sample volume. Not Induded In averages.

(c) Total pCI and not Included In averages. No measurable satnple volume.

TABLE B-1 (Gont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMITI'ERS IN WEEKLY AIRBORNE PARTICULATES Results In Units of 10 s pCI/m3 k 2 s)gma COLLECTION DATES

'-1 A-2 A-3 A-4 A-5 STATION CODES A-6 Coloma Dowaglac New Buff South Bend Average

% 2 S.ch OCTOBER 10/ll/93 22k 2 2222 21 k2 202 2 22k 2 22k 2 22 k 2 22 k 2 20% 2 22k 2 -

22%2 10/18/93 10/25/93 20% 2 24k 2 19 2 2 2722 22 23k2 k2 -20% 2 26k 2 21% 2 23k 2 20% 2 23k 21 t 2 18 k 2 19% 2 26k 18% 2 20% 3 25+4 Il/01/93 10% 2 12%2 14%2 16% 2 Ilk 2 lit 2 2

26 k 2 13% 2 27 k 2 ll +2 Ilk 22 23+ 2 12% 2 12% 4

~OVRMBER 11/08/93 202 2 18%2 22%2 20% 2 <1 (a) -<1 (a) 1942 20 k 2 19% 2 212 2 20% 3 11/15/93 27% 2 2922 30%2 27k 2 312 3 282 3 28+2 3313 29k 2 29k 2 29k 4 11/22/93 19% 2 1922 2022 20% 2 24k 2 22k 2 25+2 23 k 2 22k 2 20% 2 21k 4 11/29/93 26k 2 3023 3123 31% 3 35k 3 29k 2 31%3 30%3 31% 3 212 2 30% 7 DECEMBER 12/06/93 302 2 28 a 2 33%2 32k 2 36k 3 . 33' 29%2 32 k 2 35k 3 29k 2 32k 5 12/13/93 21% 2 19+2 24%2 21% 2 22k 2 21% 2 22%2 24 k 2 22k 2 22k 2 22k 3 12/20/93 27k 2 21 k2 22 k 2 22k 2 282 2 22k 2 22%2 20 2 2 23k 2 18+ 2 23k 6 12/27/93 26k 2 20 2 2 2122 20% 2 24k 2 202 2 22%2 25*2 26k 2 22k 2 23k 5 Quarter Avg. 23% 11 22%11 24*11 2SR 10 25% 14 23% 11 23%10 24%1S 24k 1S 212 9 23% 2 Annual Avg. 18% 12 171 12 19% 12 17% 11 18% 14 17 k 12 17% 12 18% 1S 18k -1S 18% 10 18% 12 (a) Powe .: results tn total PCI and not included In averages.

TABLE B-2 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITfERS'N gUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results In Units of 10-S pCI/ms k 2 sigma StatIons Nuclldes FIrst Quarter Second Quarter Third Quarter Fourth Quarter Average 12/28/9203/29/QS os/29/Qsos/28/Qs 08/28/QSCQ/27/QS 09/27/9$ 01/OS/94 i 2'.

/

t A-I Be-7 K-40 Cs-134 Cs-137 130 a 13 4.27 2 2.42

< 0.2

< 0.3 110 k 11

< 7

< 0.3

< 0.2 111 2 11

<9

< 0.3

< 0.3 126

<4 0.3'19

< 0.3 13 2 20 4.27 a 2.42 A-2 Be-7 87.3 X 8.7 101 k 10 113 k 11 106 2 11 102 k 22 K-40 <6 < 10 11.5 2 3.5 4.52% 2.13 8.01 ~ 9.87 Cs-134 < 0.3 < 0.3 < 0.6 < 0.2 Cs-137 < 0.3 < 0.3 < 0.6 < 0.2 A-3 Be-7 96.2 X 9.6 137 k 14 137 k 14 119 k 12 122 R 39 K-40 < 7 < 4 <5 < 10 Cs-134 < 0.4 < 0.2 < 0.2 < 0.3 Cs-137 < 0.3 < 0.2 < 0.2 < 0.3 A-4 Be-7 90.4 2 9.0 97.4 k 9.7 146 R 15 125 2 13 115 k 51 K-40 <5 < 7 <5 <4 Cs-134 < 0.3 < 0.3 < 0.3 < 0.2 Cs-137 < 0.4 < 0.3 < 0.3 < 0.2 A-5 Be-7 106 k 11 116 2 12 134 2 13 120 X 12 119 2 23 K-40 <5 <5 6.07 2 2.18 32.2 2 3.5 19.1 k 37.0 Cs-134 < 0.3 < 0.3 < 0.3 < 0.3 Cs-137 < 0.4 < 0.3 < 0.3 < 0.2 Typical LLDs are found tn Table B-12. All other gamma emltters were <LLD.

TABLE B-2 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMI1TERS'N QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results In Units of 10 S pCI/mS 2 2 sigma Stations Nuclldes First Quarter Second Quarter Third Quarter Fourth Quarter Average 12/28/9208/29/QS OS/29/9808/28/QS 08/28/9809/27/QS 09/27/9$ 01/OS/94  % 2 I.d.

A-6 Be-7 100 2 10 102 2 10 109 k 11 149 2 15 115 R 46 K-40 < 10 <9 12.9 k 2.8 <6 12.9 k 2.8 Cs-134 < 0.4 < 0.3 < 0.3 < 0.3 Cs-137 < 0.4 < 0.3 < 0.3 < 0.3 Colo ma Be-7 K-40 104 2 10 4.62 k 2.42 108 2 11

<5 ill

'- <10 k 11 117 k 12 3.92 k 2.22 110 + 11

4. 27 2 0.99 Cs-134 < 0.3 < 0.2 < 0.4 < 0.2 Cs-137 < 0.3 < 0.4 < 0.3 < 0.2 Dowagtac Be-7 83.2 2 8.3 121 k 12 108 k 11 135 4 13 112 E 44 K-40 5.91 2 2.39 <4 <4- <6 5.91 2 2.39 Cs-134 < 0.3 < 0.2 < 0.2 < 0.3 Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 New Buffalo Be-7 99.5 k 9.9 120 2 12 113 k 11 118 2 12 113 k 18 K-40 <5 <5 <9 <5 Cs-134 < 0.3 < 0.3 < 0.3 < 0.2 Cs-137 < 0.3 < 0.3. < 0.3 < 0.3 South Bend Be-7 107 2 11 116 k 12 125 R 13 110 k 11 115 2 16 K-40 <4 < 7 <4 4.93 2 2.23 4.93 X 2.23 Cs-134 < 0.3 < 0.4 < 0.2- < 0.3 Cs-137 < 0.2 < 0.3 < 0.2 < 0.3 Typical LLDs are found In Table B-12. All other gamma eml re <LLD.

B-3 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT IODINE-131 IN WEEKLY-AIR CARTRIDGE SAMPLES Results ln Un)Is of 10 3 PCI/nt3 i 2 sigma STATION CODES COLLECTION A-I A-2 A-8 A-4 A-5 A-6 Coloma Dowaglac New Buffalo South Bend DATES JANUARY 93 01/04/93 < 20 < 20 < 20 < 20 < 7 < 10 < 10 < 10 <8 < 10 01/11/93 < 10 < 10 -< 10 < 10 <9 < 10 <9 <9 < 7 <9 01/18/93 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 <8 < 10 01/25/93 < 20 < 20 < 20 < 20 < 10 < 20 < 20 < 20 <8 < 20 02/01/93 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 <8 < 10 FEBRUARY 02/08/93 < 10 < IO 10 < 10 <6 < 20 < 20 < 20 < 10 < 20 02/15/93 < 10 -< 10 < 10 < 10 < 5 (a) < 20 < 20 < 20 < 10 < 20 02/22/93 < 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 <8 < 10 03/Ol/93 < 20 < 20 < 20 < 20 < 7 < 20 < 20 < 20 < 10 < 20 MARCH 03/08/93 < 20 <9(a) <20 < 20 <8 <9 <9 <9 <9 <6 03/15/93 < 10 (b) < 10 < 10 < 10 < 10 <9 <9 <9 <9 03/22/93 < 10 (b) < 10 < 10 < 10 <6 < 20 < 20 < 20 < 20 03/29/93 < 10 < 10 < 10 < 10 < 7 < 20 < 20 < 20 < 10 < 20 Ia) Power fatlure: results tn total pCt.

Ib) Power fatlure; sample unavatlable.

TABLE B-3 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-)31 IN WEEKLY AIR CARTRIDGE SAMPLES Results In Un(Is of 10 s PCI/ms f 2 sigma STATION CODES COLLECTION A-I A-2 A-3 A-5 A-6 Co)orna Dowaglac New Buffalo South Bend DATES 04/05/93 < 10 < 10 < 10 < 10 <6 < 20 < 20 < 20 < 10 < 20 04/12/93 < 20 < 20 < 20 < 20 < 7 < 20 < 20 < 20 < 10 < 20 04/19/93 < 10 < 10 < 10 < 10 < 7 < 20 < 20 < 20 < 10 < 20 04/26/93 < 20 < 20 < 20 < 20 < 7 < 20 < 20 < 20 < 10 < 20 05/03/93 < 20 < 20 < 20 < 20 < 7 < 20 < 20 < 20 < 7 (a) < 20 05/10/93 < 20 < 20 < 20 < 20 <9 < 20 < 20 < 20 < 10 < 20 05/17/93 < 10 < 10 < 10 < 10 < 7 < 10 < 10 < 10 <8 < 10 05/24/93 < 20 < 20 < 20 < 20 <4 (a) <9 <8 <8 <5 <9 05/31/93 < 10 < 10 < 10 < 10 <8 <9 <9 < 10 < 7 < 10 JUNE 06/07/93 < 30 < 10 < 10 < 20 < 9 < 20 < 20 < 20 < 10 (b) < 20 06/14/93 < 10 < 10 < 10 < 10 <8 < 10 < 10 < 10 < 8 (b) < 10 06/21/93 < 20 < 20 < 20 < 20 < 10 < 10 < 20 < 10 < 10 < 20 06/28/93 < 20 < 20 < 20 < 20 < 7 < 20 < 20 < 20 < 10 < 20 (a) P ure: results!n total pCt.

(b) P ure: low volume.

T -3 (Co>>l.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results In Vnlts of 10 3 PCI/m> 2 2 sigma STATION CODES COLLECTION A-I A-2 A-3 A-4 A-5 A-6 Coloma Dowagfac 'New Buffalo South Bend DATES 07/05/93 . < 20 < 20 < 20 < 20 <8 < 20 < 20 < 20 < 10 < 20 07/12/93 < 10 < 10 < 10 < 10 < 7 < 20 < 20 < 20 < 10 <. 20 07/19/93 < 10 < 10 < 10 < 10 <6 < 20 < 20 < 20 < 10 < 20 07/26/93 < 20 < 20 < 20 < 20 < 7 < 20 < 20 < 30(a) < 10 < 20 08/02/93 < 20 < 100 (b) < 20 < 20 < 7 < 20 < 20 < 20 < 10 < 20 AUGUST 08/09/93 < 10 <40(b) < 10 < 10 < 8 < 10 < 10 < 10 < 7 < 10 08/16/93 < 60 (b) < 500 (b) < 10 < 10 <8 < 10 < 10 < 10 <9 < 10 08/23/93- < 20 <60(b) < 20 < 20 < 8 < 20 < 20 < 20 < 10 < 20 08/30/93 < 20 <8(tt) < 300(c) < 20 < 10 < 20 < 20 < 20 < 10 < 20 SEPTEMBER 09/06/93 < 20 < 20 < 7 < 20 < 20 < 10 < 10 < 10 < 7 < 10 09/13/93 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 <8 < 10 09/20/93 < 50 (b) < 20 < 20 < 20 < 7 < 10 < 20 < 20 <9 < 20 09/27/93 < 10 < 9 (c) < 20 < 20 <6 < 10 < 10 < 10 <9 < 10 10/04/93 < 10 (b) < 10 < 10 < 10 <6 < 10 < 10 < 10 <8 < 10 (a) Low sample volume: ur>tt replaced.

(b) power failure: low sample volume. I.LD couM not l>e met.

(c) Total pCI. LLD could not be met due to no measurable sample volume.

TABLE B-3 tco>>t.)

INDIANAMICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results In Un)Is of 10" PCI/ms 4 2 sigma STATION CODES COLLECTION A- I A-2 A-3 A-4 A-5 A-6 Coloma Dowaglttc New BuII'alo South Bend DATES OCTOBER 10/ll/93 < 20 *,

< 20 < 20 < 20 <8 < 20 < 20 < 20 < 10 < 20 10/18/93 < 20 < 20 < 20 < 20 < 7 < 20 < 10 < 20 <9 < 20 10/25/93 < 10 < 10 < 10 < 10 <9 <9 < 10 < 10 < 7 < 10 II/01/93 < 20 < 20 < 20 < 20 <8 < 20 < 20 < 20 < 10 < 20

~OVRMBE 11/08/93 < 20 < 20 < 20 < 20 < 5ta) <10ta) <20 < 20 < 20 < 20 I I/15/93 < 10 < 10 < 10 < 10 < 10 < 30 < 20 < 20 < 10 < 20 11/22/93 < 10 < 10 < 10 < 10 < 6 <8 <8 <8 <6 <8 11/29/93 < 20 < 20 < 20 < 20 < 10 < 20 < 20 < 20 < 10 < 20 DECEMBER 12/06/93 < 10 < 10 < 10 < 10 < 7 < 20 < 20 < 20 < 7 < 20 12/13/93 < 20 < 20 < 20 < 20 < 7 <8 <8 <8 <6 <8 12/20/93 < 10 < 10 < 10 < 10 <8 < 20 < 20 < 20 ~ < 10 <.20 12/27/93 < 20 < 20 < 20 < 20 < 10 < 20 < 10 < 10 <9 < 10 ta) Pov . age; results In total pCI.

TABLE BX INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD RESULTS Results ln Units of mR/standard month STATION FIRST QUARTER SECOND gUARTER THIRD gUARTER FOURTH gUARTER AVERAGE CODES 01/03/93-04/04/93 04/04/93417/11/93 07/11/93-10/03/93 10/03/93%1/02/94 2 2 sod.

A-I 2.8 2 O.l 4.0 k 0.0 3.4 k 0.4 5.9 X 2.8 4.02 2.7 A-2 3.1 S 0.3 4.2 X 0.6 3.4 k 0.5 4.5 k 0.4 3.8 X 1.3 A-3 2.4 R 0.1 3.6 2 0.3 2.9 2 0.4 4.1 2 0.6 3.3i 1.5 A-4 3.1 R 0.2 4.3 k 0.4 3.6 2 0.2 4.6 R 0.4 3.9 + 1.4 A-5 2,9 2 0.2 4.2 2 0.2 3.1 2 1.0 4.7 2 0.9 3.7 4 1.7 A-6 A-7 2.7 2 0.1 3.1 2 0.5 4.7X 0.9 3.2 2 0.6 4.2 2 0.3 i 3.7 1.8 4.7 k 0.5 3.6 X 0.4 4.5 X 0.6 4.0 k 1.5 A-8 A-9 3.1 X 0.3 4.52 0.4 3.3 E 0.6 4.6 R 0.5 i 3.9 1.6 3.1 2 0.2 4.0 k 0.5 3.6 X 0.5 4.7 2 0.4 3.9X 1.4 A-10 2.5 i 0.2 4.1 R 0.7 3.0% 0.6 3.9 k 0.5 3.4 4 1.5 A-11 3.2X 0.3 4.7 k 0.9 3.7 k 0.7 4.6 2 0.4 4.1 2 1.4 A-12 OFS- I 3.2 i 0.2 3.0 4 0.5 4.6 2 0.8 3.8 X 0.6 4.4 2 1.8 4.0 2 1.3 4.8 X 0.9 3.6 2 0.7 4.2 2 0.5 3.9 a 1.5 OFS-2 3.2X 0.3 4.9 2 0.9 3.7 2 0.7 4.6 2 0.3 4.1 2 1.6 OFS-3 3.1 2 0.4 5.1 2 0.6 3.7 X 0.6 4.7k 0.9 4.2X 1.8 OFS-4 3.6 X 0.5 5.0 k 0.4 4.3 2 0.8 (b) 4.3% 1.4 OFS-5 OFS-6 3.4 4 0.2 3.9 X 0.4 4.6 E 0.4 3.8 X. 0.6 4.6 X 0.4 4.1 i 1.2 (a) 4.3 2 1.0 5.5 1 0.3 4.6X 1.7 OFS-7 3.1 I 0.2 4.0 2 0.3 3.5 k 0.3 4.4 X 0.2 3.8 k I.l OFS-8 3.7 4 0.2 5.2 4 0.2 4.2X 0.7 5.2 4 0.3 4.6 + 1.5 OFS-9 3.3 2 0.2 4.6 2 0.3 4.4 k 2.2 t 4.9 0.5 4.3 + 1.4 OFS-10 3.0 i 0.2 4.8 k 0.5 3.6 x 0.5 4.5 k 0.4 4.0  % 1.7 OFS-11 3.8 E 0.2 5.1 x 0.4 4.0 X 0.8 . 5.3 x 0.8 4.6 ~ 1.5 NBF 2.9 k 0.2 4.2 X 0.8 3.4 x 0.4 4.5 k 0.8 3.8 i 1.5 SBN 3.1 i 0.2 5.0 2 0.8 3.82 0.3 4.8 X 0.4 4.2 + 1.8 DOW 2.7 i 0.4 4.0 k 0.4 i 2.9 0.6 4.1 2 0.2 34 i 1.5 COL 2.7 i 0.3 4.0 k 0.3 3.1 2 0.6 4.2 2 0.4 3.5k 1.4 Average i 2 s.d. 3.1 k 0.7 4.5k 0.9 3.6 X 0.8 4.6 2 0.9 3.9 J 1.5 (a) TLD mlsslng along with pole ll wns attached to.

(b) TLD mlsslng.

Standard month = 30.4 days.

TABLE B-5 INDIANAMICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITIERS'N SURFACE WATER Results ln Units of pCl/liter k 2 sigma STATION Collectton Date 1-131 K-40 I I 01/07/93 < 0.3 < 70 150 2 80 (Condenser Ctrc.) 02/04/93 < 0.2 < 100 03/04/93 < 0.7 < 70 04/01/93 < 0.4 < 60 < 200 04/29/93 < 0.3 < 100 05/27/93 < 0.1 < 60 06/24/93 < 0.2 < 80 07/22/93 < 0.4 < 60 < 100 08/19/93 < 0.5 <90 09/17/93 < 0.4 < 60 10/14/93 < 0.4 < 90 < 200 11/11/93 < 0.4 < 90 12/09/93 < 0.4 < 60 I 2 01/07/93 < 0.3 < 50 190 X 80 (South Comp) 02/04/93 < 0.2 < 70 03/04/93 < 0.6 < 70 04/01/93 < 0.5 < 50 < 200 04/29/93 < 0.3 < 100 05/27/93 < 0.2 < 50 06/24/93 < 0.2 <90 07/22/93 < 0.4 < 50 < 100 08/19/93 < 0.4 <,90 09/17/93 < 0.4 < 50

-10/14/93 < 0.4 < 60 < 200 11/11/93 < 0.3 <90 12/09/93 < 0.5 < 60 Q'pleat Lt.os arc fmnd In Table 33. 32. All other gamma cmt t ters werc below 9

TABLE B-5 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITfERS'N SURFACE WATER Results ln Units of pCl/liter k 2 sigma STATION Collection Date KRO I S 01/07/93 < 0.3 < 100 140 2 80 (North Comp) 02/04/93 < 0.2 < 70 03/04/93 < 0.7 < 100 04/01/93 < 0.5 < 70 < 200 04/29/93 < 0.3 < 200 05/27/93 < 0.2 < 70 06/24/93 < 0.2 < 80 07/22/93 < 0.4 < 60 170 2 100 08/19/93 < 0.4 < 50 09/17/93 < 0.3 < 90 10/14/93 < 0.4 < 100 < 200 11/ll/93 < 0.3 < 100 12/09/93 < 0.4 < 70 L-4 01/07/93 < 0.3 < 100 190 R 80 (South 500) 02/06/93 < 0.2 < 100 03/04/93 < 0.6 < 50 04/01/93 < 0.5 < 50 < 200 04/29/93 < 0.3 < 60 05/27/93 < 0.2 < 50 06/24/93 < 0.2 < 60 07/22/93 < 0.4 < 100 180 2 100 08/19/93 < 0.4 < 50 09/17/93 < 0.4 < 60 10/14/93 < 0.4 < 50 < 200 11/ll/93 < 0.3 < 60 12/09/93 < 0.5 < 50 Typtcal Lt&s are found tn Table 8-12. All other gamma emtt ters were below <LLD.

TABLE B-5 tCont.l INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITIERS'N SURFACE WATER Results ln Units of pCI/liter 2 2 sigma STATION Collection Date I-1S1 K-40 L-5 01/07/93 . < 0.2 < 100 < 100 (North 500) 02/04/93 < 0.2 < 70 03/04/93 < 0.8 < 40 04/01/93 < 0.6 < 60 < 200 04/29/93 < 0.3 < 60 05/27/93 < 0.2 < 100 06/24/93 < 0.2 < 100 07/22/93 < 0.4 < 50 140 1 100 08/19/93 < 0.3 < 40 09/17/93 < 0.4 < 100 10/14/93 < 0.4 < 50 < 200 Il/11/93 < 0.4 < 50 12/09/93 < 0.5 < 100 Qylcal LLDs are I'ound In Table 8-l2. Alt other gamma emltters were bel 0

TABLE B-6 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITI'ERS'N QUARTERLY GROUNDWATER Results In Units of pCI/liter k 2 sigma STATION Collection Date KRO Trltlum Well - I 01/31/93 < O.l < 50 < 100 05/02/93 < 0.1 < 60 < 200 08/01/93 < 0.2 < 50 < 100 11/07/93 < 0.2 < 50 < 200 Well -2 01/31/93 < 0.1 < 70 < 100 05/02/93 < 0.1 < 90 < 200 08/01/93 < 0.2 < 70 < 200 11/07/93 < 0.2 < 60 < 200 Well - 3 01/31/93 < 0.2 < 100 < 200 05/02/93 < 0.2 < 60 < .200 08/01/93 < 0.2 58.8 2 25.3 < 200 11/07/93 < 0.2 80 < 200 Well - 4 02/03/93 < 0.2 .< 50 < 100 05/03/93 < 0.1 < 100 790 2 140 08/01/93 < 0.2 <40 950 k 130 11/07/93 < 0.2 < 50 1200 2 100 Well - 5 02/03/93 < 0.1 < 60 310 + 80 05/03/93 < 0.2 < 50 1000 4 100 08/01/93 < 0.2 < 50 860 + 130 11/07/93 < 0.2 < 50 580 k 120 Well - 6 02/03/93 < 0.1 < 100 410 k 80 05/03/93 < 0.1 < 70 1100 k 100 08/01/93 < 0.2 < 50 1200 k 120 11/11/93 < 0.2 < 50 670 2 120 Well - 7 01/31/93 < 0.2 < 70 650 2 100 05/02/93 < 0.1 < 70 400 k 120 08/01/93 < 0.2 < 60 340 k 110 11/11/93 < 0.2 < 100 < 100 Qpleal I U)s are Ianral In Tahle D-I2. All orher gamma emI(Irrs were <I I IX

TABLE B-6 ICont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITTERS'N QUARTERLY GROUNDWATER t

Results In Units of pCI/liter 2 sigma STATION Collection Date 1-131 K-40 Well - 8 01/31/93 < 0.1 < 50 330 k 100 05/02/93 < 0.1 <40 < 200 08/01/93 < 0.2 < 90 < 100 11/07/93 < 0.2 < 60 < 200 Well -9 01/31/93 < 0.1 < 40 < 100 05/02/93 < 0.1 < 100 < 200 08/01/93 .< 0.3 < 50 < 100 ll/07/93 < 0.3- < 50 < 200 Well - 10 01/31/93 < 0.1 < 60 < 100 05/02/93 < 0.1 < 300 < 200 08/01/93 < 0.2 <40 < 100

'l/07/93

< 0.2 <40 < 200 Well - ll 01/31/93 05/02/93 0.1 0.1

< 80

< 90 370 2 100

< 200 08/01/93 < 0.2 < 80 < 200 11/07/93 < 0.2 <40 < 200 Well - 12 01/31/93 < 0.1 <40 410 4 100 05/02/93 < 0.1 <80 < 200 08/01/93 (a) < 0.2 <80 < 100 11/07/93 < 0.2 <80 < 200 Well - 13 01/31/93 < 0.1 < 50 410 k 100 05/02/93 < 0.1 <80 200 k 120 08/01/93 < 0.2 < 50 < 200 11/07/93 < 0.2 < 70 170 k 110 Well - 14 01/31/93 < 0.1 < 80 < 100 05/03/93 < 0.1 < 100 480 s 130 08/01/93 < 0.2 <40 950 k 130 11/11/93 < 0.2 < 100 1100 t 100 Average 58.8 2 28.3 647 4 670 t 2 s.d.

Ia) Thohum-228 was measured at 10.9 C 3.2 pCI/liter.

Typical ILDs are found In Table 0 12. Ail other gamma emit ters ere <LLD.

TABLE B-7 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, TRITIUM AND GAMMA EMITPERS'N DRINKING WATER Results in Units of pCI/liter k 2 sigma COLLECTION DATE Gamma 8 c Iodine-131 Lake Towashlp 01/07/93 2.7 i 0.9 < LLD < 0.3 < 100 01/21/93 4.1 2 1.0 < LLD < 0.2 02/04/93 3.7 a 0.9 < LLD < 0.5 02/18/93 3.7 2 0.9 < LLD < 0.2 03/04/93 3.6 X 1.3 < LLD < 0.3 03/18/93 3.3 k 1.0 < LLD < 0.3 04/Ol/93 3.3 2 1.0 < LLD < 0.4 < 100 04/15/93 2.0 2 1.0 < LLD < 0.2 04/29/93 4.2 2 1.3 < LLD < 0.3 05/13/93 3.2 X 1.0 < LLD < 0.3 05/27/93 3.4 2 1.1 < LLD < 0.2 06/10/93 3.3 2 1.0 < LLD < 0.3 06/24/93 3.4 i 1.0 < LLD < 0.3 07/08/93 4.2R 1.3 < LLD < 0.3 < 200 07/22/93 3.6 2 1.0 < LLD < 0.2 08/05/93 5.0 2 1.1 < LLD < 0.4 08/19/93 2.9 2 1.0 < LLD < 0.3 09/02/93 2.7 X 1.0 < LLD < 0.3 09/16/93 3.0 k 1.0 < LLD < 0.3 09/30/93 2.5 k 1.0 '< LLD < 0.2 10/14/93 3.5 X 1.1 < LLD < 0.3 < 100 10/28/93 3.6 R 1.0 < LLD < 0.3 11/11/93 3.0 t 1.0 < LLD < 0.7 11/25/93 4.2 2 1.2 < LLD < 0.3 12/09/93 3.2 2 1.0 < LLD < 0.3 12/23/93 2.8 2 1.0 < LLD < 0.2 Average 2s. d.

i S.4 2 1.3 Typical LLDs are found in table B-12.

TABLE B-7 (cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, TRITIUM AND GAMMA EM11TERS'N DRINKING WATER i

Results ln Units of pCI/liter 2 sigma COLLECTION DATE Gamma S Iodtne-131 St. Joseph 01/07/93 4.7 i 1.0 < LLD < 0.2 < 100 01/21/93 4.2 i 1.0 < LLD < 0.2 02/04/93 4.9 i < LLD < 0.4 02/18/93 4.5 i 1.0 < LLD < 0.3 03/04/93 3.6 i 1.4 < LLD < 0.4 03/18/93 3.6 i "1.1 < LLD < 0.3 04/01/93 3.2 i 1.0 < LLD < 0.3 < 100 04/15/93 3.5 i 1.2 < LLD < 0.3 04/29/93 4.6 i < LLD < 0.2 05/13/93 2.5 i 1.0 < LLD < 0.3 05/27/93 3.0 i 1.1 < LLD < 0.2 06/10/93 2.5 i 1.0 < LLD < 0.3 06/24/93 4.0 i < LLD < 0.3 07/08/93 4.1 i 1.3 < LLD < 0.4 < 200 07/22/93 3.8 i 1.1 < LLD < 0.2 4.3 i 1.1 < LLD < 0.4 4.0 i 08/05/93'8/19/93 1.1 < LLD < 0.2 09/02/93 2.9 i < LLD < 0.3 09/16/93 4.7 i 1.2 < LLD < 0.3 09/30/93 -7.3 i 1.5 < LLD < 0.3 10/14/93 3.1 i 1.0 < LLD < 0.4 < 100 10/28/93 4.5 i 1.1 < LLD < 0.3 11/11/93 3.0 i 1.0 < LLD < 0.6 11/25/93 3.7 i 1.2 < LLD < 0.4 12/09/93 3.2 i 1.0 < LLD < 0.3 12/23/93 4.6 i 1.1 < LLD < 0.2 verage

s. d.

i 3.9i 2.0 Qq)leal LLDs are found ln table B-12.

TABLE B-8 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS'N SEDIMENT Results in Untts of pCI/kg (dry) 2 2 sigma Station Collectton Date Be-7 K-40 Cs-137 Ra-226 Th-228 L-2 05/16/93 < 200 6930 R 690 < 30 < 400 155 k 24 L-3 05/16/93 < 100 6060 2 610 < 20 < 300 96.5 R 16.7 L-4 05/16/93 < 200 6870 k 690 < 20 < 400 155 R 28 L-5 05/16/93 < 200 5440 k 540 < 20 < 400 107 2 23 L-2 11/14/93 < 200 5570 R 560 < 20 < 400 158 % 30 L-3 ll/14/93 < 200 3660 R 400 < 30 < 600 103 R 29 L-4 11/14/93 < 200 5230 2 520 < 20 < 400 130 0 28 L-5 11/14/93 < 200 5110 k 510 < 30 < 400 124 2 21 Average 6609 2 2106 1292 60 k 2 s.d.

'Fyptcal LLDs are found In table B-12. All other gamma emttters were <LLD.

TABLE B-9 INDIANAMICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EM]1TERS'N MILK Resulls In Unlls of pCI/Ilier k 2 sigma STATION CODES COLLECTION ANALYSIS " SHULER TOTZKE FREEHLING WARMBEIN LIVINGHOUSE DATES 01/08/93 K-40 1190 2 120 1380 X 140 1290 E 130 1230 E 120 )360 X 140 1260 k 130 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.1 01/22/93 K-40 1-131 1280 k 130

< 0.2

)410 k ]40

< 0.2 1260 i 130

< 0.2

]450 k 150

< 0.3 1290 k 130

< 0.2 1230 k 120

< 0.2 02/05/93 K-40 1250 2 130 1430 k 140 1280 2 130 1410 k 140 1370 % 140 1330 X 130 1-131 < 0.4 < 0.1 < 0.6 < 0.2 < 0.1 < 0.1 02/19/93 K-40 1080 X 110 1460 k 150 1400

• 140 1540 k 150 1220 k 120 1120 4 110 1-131 < 0.2 < 0.2 < 0.1 < 0.2 < 0.1 < 0.4 03/05/93 K-40 1390 R 140 1490 2 150 1430 X 140 1440 2 140 1300 k 130 1190 2 )20 1-131 < O.l < 0.1 < 0.1 < 0.1 < 0.) < 0.2 03/19/93 K-40 1-131

]550 2 150

< 0.3 1400 f 140

< 0.2 1400 R 140 1290 k 130 1240 X 120 1380 k 140

< 0.3 < 0.2 < 0.2 < 0.1 04/02/93 K-40 1-131

)320 i 130

< 0.2 1530 2 150

< 0.3 1200 k 120

< 0.2 1370 2 140

< 0.2 1340 2 130 1140 2 110

< 0.2 < 0.2 04/16/93 K-40 1650 2 160 1320 2 130 1790 a 180 1430 2 140 1400 2 140 1350 k 140 1-131 < 0.2 < 0.1 < 0.1 < 0.2 < 0.2 < 0.2 04/30/93 K-40 1-131

)190 i 120

< 0.1 1410 2 140

< 0.2 1430 2 140

< 0.1

~ ]320 X 130

< 0.2 1400 k 140

< 0.2

) 180 X )20

< 0.2 yptrat I.I.Ds arc fouial ln table ll- l2. hll otlter gaatma emltlers werc <I.I.D.

TABLE B-9 I(.'oi>l.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITIERS'N MILK Resulls ln Unlls of pCI/liter 2 2 sigma STATION CODES COLLECTION ANALYSIS SHULER TOTZKE FREE HLING WARMBEIN LIVINGHOUSE DATES 05/14/93 K-40 I-131 1290 i 130

< 0.1 1410 k 140

< 0.1 1220 k 120

< 0.1 1470 k 150

< 0.2 1340 2 130

< 0.2 1300 k 130

< 0.2 05/28/93 K-40 1280 2 130 1320 X 130 1370 2 140 1240 k 120 1410 k 140 1330 2 130 1-131 < 0.2 < 0.2 < 0.1 < 0.2 < 0.2 < 0.2 06/11/93 K-40 1160 k 120 1530 k 150 1450 2 140 1450 2 150 1260 4 130 1290 k 130 1-131 < 0.2 < 0.1 < 0.3 < 0.3 < 0.2 < 0.2 06/25/93 K-40 1-131 1260 i 130

< 0.2 1540 2 150

< 0.1 1240 2 120

< O.l 1540 k 150

< 0.1 1500 t

< 0.2 150 1290 X 130

< 0.2 07/09/93 K-40 1400 2 140 1310 2 130 1340 2 130 1440 k 140 1400 2 140 1470 4 150 1-131 < 0.2 < 0.1 < 0.2 < 0.1 < 0.2 < 0.2 07/23/93 K-40 1290 4 130 1450 2 150 1230 2 120 1420 2 140 1380 k 140 1280 k 130 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.1 08/06/93 K-40 1290 k 130 1440'2 140 1240 k 120 1680 2 170 1510 2 150 1270 k 130 1-131 < 0.2 < 0.2 < 0.2 < 0.3 < 0.2 < 0.2 08/20/93 K-40 1260 k 130 1540 X 150 1240 2 120 1370 k 140 1610 2 160 1250 4 130 1-131 < 0.2 < 0.2 < 0.5 < 0.2 < 0.3 < 0.2 09/03/93 K-40 I-131 1500 2 150

< 0.2 1450 2 150

< 0.2 1390 2 140

< 0.2 1480 X 150

< 0.2 1330 i

0.2 130 1280 t

< 0.2 130 09/17/93 K-40 I-131 1380 k 140

< 0.1 1240 i

< 0.2 120 1200 k 120

< 0.1 1320 k 130

< 0.2 1360 i

< 0.2 140 I460 i

< 0.2 150

'i%1>leal I.LOsare (ou>><l I>> lal>le 0-12. hll on>er ga>>>ma emlllers ~ere <I.I.I).

TABLE B-9 IConhl INDIANAMICHIGAN POWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMI1TERS'N MILK Results In Units of pCI/liter k 2 sigma STATION CODES COLLECTION ANALYSIS SHULER TOTZKE FREEHLING WARMBEIN LIVINGHOUSE DATES 10/Ol/93 K-40 1290 k 130 1630 k 160 1360 k 140 1390 k 140 1380 R 140 1330 2 130 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 10/15/93 K-40 1380 k 140 1440

• 140 1410 k 140 1430 k 140 1440 k 140 1490 2 150 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 10/29/93 K-40 1630 X 160 1580 2 160 1290 2 130 1490 k 150 1290 R 130 1430 k 140 1-131 < 0.2 < 0.3 < 0.4 < 0.4 < 0.2 < 0.3 ll/12/93 K-40 1480 2 150 1500 k 150 1450 k 150 1460 k 150 1290 X 130 1260 4 130 1-131 < 0.2 < 0.2 < 0.3 < 0.2 < 0.3 < 0.2 11/26/93 K-40 1-131 1450 a 140 Ial

< 0.7 1580 2 160

< 0.1 1470 k 150

< 0.1 1370 k 140

< 0.2 1550 i

< 0.2 150 1340 4 130

< 0.2 12/10/93 K-40 1410 "2 140 1430 a 140 1510 k 150 1410 2 140 1440 k 140 1300 k 130 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 12/24/93 K-40 1290 2 130 1450 k 150 1410 k 140 1560 2 160 1450 k 340 1350 k 130 1-131 < 0.3 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 all/)Ie sl)libel ln I ransu.

~

. I'yl>leal LI.Ds are low>din lahle 9-l2. hll olher gannna emlucrs vere <I.l.D

~

TABLE B-10 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITIERS'N FISH Results ln Units of pCI/kg (wet) 2 2 sigma Collection Date Station Descrl tlon Be-? K-40 Cs-1S7 Ra-226 T?1-228 06/23/93 OFS-South Long Nose Sucker < 300 2650 2 400 < 40 < 500 < 50 06/23/93 ONS-South Red Horse Carp/Sucker < 200 2990 R 380 < 30 < 500 < 40 r

06/23/93 ONS-North Red Horse Carp < 400 3520 2 490 < 40 < 700 < 60 06/24/93 OFS-North Long Nose Sucker/Perch < 200 3870 k 410 < 30 < 500 < 40 09/17/93 OFS-South WhlteAsh < 100 2520 2 250 < 20 < 200 < 20 09/17/93 ONS-South < 100 3440 2 340 71.9 R 12.3 < 200 < 20 09/17/93 ONS-North Walleye/Sucker < 200 3350 k 340 58.6 R 15.1 < 300 < 30 09/17/93 OFS-North WhlleAsh/Walleye < 200 3050 2 300 74.3 k 14.0 < 300 < 20 Average 3174 2 913 68.3 2 16.9 k 2 s.d.

'n plcal ll.f)s arc (oun<I In lahlc Il Is. hll oilier ganesa emlucrs werc (I.ll).

~

TABLE B-11 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITIERS'N FOOD/VEGETATION Results ln Untts of pCl/kg (wet) t 2 sigma COLLECTION DATE Station Descri tion Be-7 K-40 I-131 09/29/93 SECTOR-B Grapes 807 R 102 6460 2 650 < 30 09/29/93 SECTORS Grapes 131 2 31 2640 k 260 <8 09/29/93 SECTOR-B Grape Leaves 3480 2 350 2200 2 220 < 20 09/29/93 SECTORS Grape Leaves 3980 2 400 2320 + 230 < 30 10/07/93 SECTOR-A Broadleaf 1490 2 190 1890 R 230 < 40 Average 2 2 s.d.

1978 i 3359 3102 i 3793

~teal ILDs are found tn table 8-12. All other gamma emttters were <ILD.

. TABLE B-12 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DEIECTION AND REPORTING LEVELS Isoto TI LLD Tech S ec LLD Re t Level Tech S ec LLD Re t Level Ve etat on- Cl K -wet liter Ccrlum-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 Cobal t-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 Cerium-144 30 N/A -. N/A 0.007 N/A N/A Barium/La- 1 40 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 N/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 radlochemlshy and based on the assumptions In Procedure PRO-032-11.

Charcoal Trap

TABLE B-12 (Cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DETECTION AND REPORTING LEVELS Isoto TI LLD Tech S ec LLD Re t Level TI LLD Tech S ec LLD Re t Level ISH - Ci K -wet Sedl e t Sol- ClK4 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 lodlne-131 100 N/A N/A 30 N/A N/A Gross Beta/Trltlum LLDs and Re ortln Levels Alr Particulates Drlnklng Water 0.01 pCI/m3 2 pCI/1 '.0 0.01 pCI/m3 pCI/l N/A N/A C

Surface Water 200 2000 20,000 Ground Water 200 2000 20.000 Drlnklng Water 200 2000 20,000 Based on the assumptions In procedure PRO-042-5.

APPENDIX C ANALYTICALPROCEDURES SYNOPSIS 69

ANALYTICALPROCEDURE SYNOPSIS Appendix C is a synopsis of the analytical procedures performed d 1993 on samples collected for the D.C. Cook Plant's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by Indiana Michigan and Teledyne Isotopes 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.................... 71 Gross Beta Analysis of Water Samples ................. 72 Analysis of Samples for Tritium (Liquid Scintillation).... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ 74 Analysis of Samples for Strontium-89 and -90 ~ ~ o o ~ o ~ ~ ~ 75 Total Water .......... ~ ~ ~ ~ ~ ~ ~ 75 M'lk ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ ~.... 75 Soil and Sediment .............

Oqpnic Solids...

Air Particulates 76 Analysis of Samples for Iodine-131:. ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ 79 Milk or Water ........ ~ ~ ~ ~ ~ ~ 79 Gamma Spectrometry of Samples ~ ~ ~ ~ ~ ~ ~ 80 Milk and Water ~ ~ ~ ~ ~ ~ ~ ~

'0 Dried Solids other than Soils and Sediment . 80 Hsh ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 80 Soils and Sediments .. ~ o ~ ~ 80 Charcoal Cartridges (Air Iodine) . .............. 80 Airborne Particulates .. ........ 81 Environmental Dosimetry . ~ ~ ~ ~ ~ ~ ~ ~ 83 70

GROSS BETA ANALYSISOF SAMPLES r rn Particul 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 I

gas-flow proportional counter. An unused air particulate filter, supplied by the customer, is counted as the blank.

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

RESULT (pCi/m3) ((S/T) - (B/t))/(2.22 V E)

'IWO SIGMA ERROR (pCi/m3),= 2((S/T2) + (B/t2)) >/2/(2,22 V E)

LLD (pCi/m3) 4.66 (B/t/T) 1/2/(2 22 V E) where; C

S Gross counts of sample including blank B Counts of blank E Counting efficiency T Number of minutes sample was counted t Number of minutes blank was counted V Sample aliquot size (cubic meters) 71

DETERMINATION OF GROSS BETA ACTIVITYIN WATER SAMPLES

.0 ~OO 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.

'fter 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 efficiency caused by the residue mass.

72

2.0 DETE ON CAPABILFIY 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 1

the 2.83 sigma level), assuming that 1 liter of sample is used and that >

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 efllciency and background of 0.2 and 1.2 cpm, respectively.

The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, li the 4.66 sigma MDL for gross beta is 0.9 picocuries per liter. These values reflect a beta counting efficiency of 0.38.

73

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/I:

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

TWO SIGMA ERROR 2((N + B)/ht) 1/2/ (2 22 V E) 4.66 (BQ,t)1/2/(2.22 V E )

where: N the gross cpm of the sample B the backgr'ound of the detector in cpm 2.22 conversion factor changing dpm to pCi volume of the sample in ml

'fficiency of the detector counting time for the sample

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 W~~r'table strontium carrier is added to l liter of sample and the volume

. is reduced by evaporation. Strontium is precipitated as Sr(NO3)g using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm> aluminum absorber for low level beta counting.

Mi11t Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muQle furnace. The ash is dissolved and strontium is precipitated as phosphate, then'is dissolved in 3M HN03. This solution is passed through a crown ether extraction column to isolate elemental strontium. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate.

The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm~ aluminum absorber for low level beta counting.

Soil and Se imen The sample is first dried under heat lamps and an aliquot is taken.

Stable strontium carrier is added and the sample is leached in hydrochloric acid. The mixture is filtered and strontium is precipitated from the liquid 75

portion as phosphate. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (fe hydroxide) scavenge are, then performed. Stable yttrium carrier is ad and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated "as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon'planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is .determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.

r ni S li A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N03) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 d period for yttrium ingrowth. Yttrium is then precipitated, as hydro dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted o a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity.'trontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm~ aluminum absorber for low level beta counting.

Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, 76

dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer stron-tium-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting.

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

RESULT Sr-89 (N/dt-BC-BA)/(2.22 V YS DFSR 6g ESR 8g)

TWO SIGMA ERROR Sr-89 2((N/b,t+BC+BA)/ht) /(2.22 V YS DFSR 8g ESR 8g LLD Sr-89 4.66((BC+BA)/alt) >/ /(2.22 V YS DFSR 89 ESR 89)

RESULT Sr-90 (N/ht - B)/(2.22 V YI Y2 DF IF E)

TWO SIGMA ERROR Sr-90 2((N/b,t+B)/bt) I/2/(2 22 V YI Y2 DF E IF))

LLD Sr-90 4.66(B/8 t) I/2/(2.22 V YI Y2 IF DF E) 77

where: N total counts from sample (counts) counting time for sample (min)

BC background rate of counter (cpm) using absorber c augur 2.22 dpm/pCi volume or weight of sample analyzed BA background addition from Sr-90 and ingrowth of Y-90 BA 0.016 (K) + (K) (EY/abs) (IGY go)

YS chemical yield of strontium DF SR 8g decay factor from the mid collection date to the counting date for SR-89 ESR-89 efficiency of the counter for SR-89 with the 80 mg/cm.sq.

aluminum absorber (N/bt - BC)Y go/(EY go IFY go DFY goY1)

DFY-9O the decay factor for Y-90 from the "milk" time to the mid count time EY-90 efficiency of the counter for Y-90 IFY-go ingrowth factor for Y-90 from scavenge time to m t'he IGY-90 ingrowth factor for Y-90 into the strontium mount fro "milk" time to the mid count time 0.016 the efficiency of measuring SR-90 through a No. 6 absorbe EY/abs the efficiency of counting Y-90 through a No. 6 absorber background rate of counter (cpm) chemical yield of yttrium Y2 chemical yield of strontium DF decay factor of yttrium from the radiochemical milking time to the mid count time efficiency of the counter for Y-90 IF ingrowth factor for Y-90 from scavenge time to the radio-chemical milking time 78

V ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water 4

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 Gee 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/5t-B)/(2.22 E V Y DF)

TWO SIGMA ERROR 2((N/ht+B)/ht) / (2.22 E V Y DF) 4 66(B/Qt) 1/2/(2.22 E V Y DF) where: N total counts from sample (counts) counting time for sample (min)

B background rate of counter (cpm) 2.22 dpm/pCi volume or weight of sample analyzed chemical yield of the mount or sample counted DF decay factor from the collection to the counting date efficiency of the counter for I-131, corrected for self absorption effects by the formula E Es(exp-0.0085M) /(exp-0.0085Ms)

E efficiency of the counter determined from an I-131 standard mount Ms mass of Pdl2 on the standard mount. mg mass of Pdl2 on the sample mount. mg 79

GAINMASPECTROMETRY OF SAMPLES Milk and Water 0 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.

j Dri li rTh n oil S imn a

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

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 t counted for approximately 1000 minutes with a shielded Ge(Li) detec 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 and analysis.

Charco C rid s 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 80

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

81

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

VVO SIGMA ERROR 2(S+B) / /(2.22 t E V F DF) 4.66(B) 1/2/(2 22 t E V F DF) where: S Area, in counts, of sampIe peak and background (region of spectrum of interest)

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) decay factor from the mid-collection date to counting date 82

ENVIRONMENTALDOSIMETRY Teledyne Isotopes 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 )+D2+Ds+D4) /4

'IWO SIGMA ERROR ((D y D) 2 + (D2 ) 2 + ( Ds 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 A = 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.

83

APPENDIX D SURGERY OF EPA INTERLABORATORYCOMPARISONS

EPA INTERLABORATORYCOMPARISON PROGRAM Teledyne Isotopes participates in the 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. In this section trending graphs (since 1981) and the 1993 data summary tables are presented for isotopes in the various sample media applicable to the Donald C. Cook 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.

85

EPA INTERLABORATORYCOMPARISON PROGRAM 1993 Environmental Collection Teledyne Date Media Nuclide EPA Result(a) Isotopes Result(b) Deviation(c)

Ol/15/93 Water Sr-89 15.0+ 5.0 12.67 + 1.15 -0.81 Sr-90 10.0+ 5.0 8.33 2 1.15 -0.58 01/29/93 Water Gr-Alpha 34.0+ 9.0 17.33 + 1.15 -3.21 (d)

Gr-Beta 44.0+ 5.0 52.00 + 1.00 2.77 (e) 02/05/93 Water 1-131 100.0 2 10.0 106.67+ 5.77 1. 15 03/05/93 Water Ra-226 9.8 + 1.5 7.67 + 0.12 -2.46 (0 Ra-228 18.5 2 4.6 19.33 + 2.31 0.31 04/20/93 Water Gr-Alpha 95.0 + 24.0 94.33 + 1. 15 -0.05 Ra-226 24.9 + 3.7 19.00 + 1.00 -2.76 (0 Ra-228 19.0 + 4.8 18.33 + 0.58 -0.24 Gr-Beta 177.0+ 27.0 150.0 + 0.00 -1.73 Sr-89 41.0 + 5.0 35.33 + 1.53 -1.96 Sr-90 29.0 + 5.0 27.33 + 0.58 -0.58 Co-60 Cs-134 Cs-137 39.0+

27.0+

32.0+

5.0 5.0 5.0 40.67 +

23.67 +

34.33 i 3.51 1.53 2.08 -i 06/04/93 Water H-3 9844.0+ 984.0 9366.67 + 152.75 -0.84 06/11/93 Water Co-60 15.0 + 5.0 16.33 + 1.53 0.46 Zn-65 103.0 + 10.0 121.33 + 20.09 3.18 (g)

RU-106 119.0+ ~

12.0 106.33+ 15.89 -1.83 Cs-134 5.0 + 5.0 5.67 + 0.58 0.23 Cs-137 5.0+ 5.0 6.67 + 0.58 0.58 Ba-133 99.0+ 10.0 104.33+ 9.29 0.92 07/16/93 Water Sr-89 34.0 + 5.0 31.67 + 2.52 -0.81 Sr-90 25.0 + 5.0 24.00 + 0.00 -0.35 07/23/93 Water Gr-Alpha 15.0 + 5.0 18.67 + 2.08 1.27 Gr-Beta 43.0 + 6.9 42.67 + 2.52 -0.08 08/27/93 Air Filter Gr-Alpha 19.0 + 5.0 17.00 + 0.00 -0.69 Gr-Beta 47.0 + 5.0 49.00+ 1.73 0.69 Sr-90 19.0 + 5.0 17.67 + 0.58 -0.46 Cs-137 9.0 + 5.0 9.67 + 0.58 0.23 09/09/93 Water Ra-226 14.9 + 2.2 15.33 + 0.58 0.34 Ra-228 20.4 + 5.1 20.67 + 1.15 0.09 86

EPA INTERLABORATORYCOMPARISON PROGRAM 1993 Environmenta1 Collection Teledyne Date Media Nuclide EPA Result(a) Isotopes Result(b) 09/24/93 Milk Sr-89 30.0 + 5.0 35.67 + 3.51 1.96 Sr-90 25.0 2 5.0 24.00+ 1.73 -0.35 1-131 120.0+ 12.0 126.67+ '.77 0.96 Cs-137 49.0 2 5.0 50.67 + 1.15 0.58 K .1679.0 2 84.0 1620.00 + 17.32 -1.22 10/08/93 Water 1-131 117.0 2 12.0 103.33 + 5.77 -1.97 10/19/93 Water Gr-Beta 58.0+ 10.0 51.33 + 3.21 -1.15 Sr-89 15.0 2 5.0 15.00+ 1.00 0.00 Sr-90 10.0 2 5.0 10.00 2 0.00 0.00 Co-60 10.0 2 5.0 12.00 2 1.00 0.69 Cs-134 12.0 2 5.0 9.00 2 1.00 -1.04 Cs-137 10.0 2 5.0 12.67 + 2.52 0.92 Gr-Alpha 40.0+ 10.0 39.67 + 0.58 -0.06 Ra-226 9.9 + 1.5 10. 10 + 0.79 0.23 Ra-228 12.5 + 3.1 14.67 + 1.15 1.21

'.0 10/29/93 Water Gr-Alpha 20.0+ 20.33 + 2.08 0.12 Gr-Beta 15.0 + 5.0 15.67 + 2.08 0.23 5/93 Water H-3 7398.0 2 740.0 6900.00+ 100.00 -1.17 11/12/93 Water Co-60 30.0 + 5.0 28.67 + 2.89 -0.46 Zn-65 150.0 2 15.0 152.00+ 9.17 0.23 RU-106 201.0+ 20.0 177.33 + 5.51 -2.05 (h)

Cs-134 59.0+ 5.0 53.33 + 4.93 -1.96 Cs-137 40.0+ 5.0 41.33 + 3.06 0.46 Ba-133 79.0 2 8.0 69.33+ 3.06 -2.09 (0 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 + one sigma. Units are pCi/liter for water and milk except K is in mg/liter. Units are total pCi for air particulate filters.

(c) Normalized deviation from the known.

(d) The EPA switched from Am-241 to Th-230 alpha spike. We calibrated with Th-230.

using sodium nitrate to generate a self-absorption curve. The EPA water, however has minerals which have greater self-absorption than the sodium nitrate matrix. The EPA has agreed to send us a gallon of their water which we can use to prepare a self-absorption curve with Th-230.

87

EPA INTERLABORATORYCOMPARISON PROGRAM 1993 Collection Date Media Nuclide Environmenta1 EPA Result(a)

Teledyne Isotopes Result(b) 0 (e) By oversight, we did not use the special self-absorption curve which we had previously derived using EPA water and Cs-137 standard. We will use the EPA curve in the future. We may also re-derive this curve using a water sample which the EPA has agreed to send us.

(fl The counting data and backgrounds were verified. Possibly some efficiencies used were erroneously high, causing low values. A less likely cause is an error in dilution.

New Ra-226 standards will be prepared. Closer monitoring of out of control efficiencies will be done and extra care in preparation of the sample will be maintained.

The calculations were checked and found to be correct. The results of six gamma emitting isotopes were reported to the EPA. The results of four were within 1 normalized deviation: a fifth. within 2 normalized deviations. Only the Zn-65 average was outside the control limits. There is no obvious reason why one isotope should be outside the control limits, while five other isotopes were within control limits.

(h) Although the Tl average (177,3) was 2.05 deviations low compared to the EPA val the agreement was good with the average (175.2) of 173 participants. The data reviewed for accuracy including half life and branching intensity used. No probl were found. No corrective. action anticipated because of the good agreement with the average of all participants.

(i) No problems were found with the calculations. Three other isotopes were within 1 deviation, so it's unlikely that a general problem exists. If compared to the average of all participants, the TI results would undoubtedly be within 2 deviations. The Ba-137 results were within +1 deviaUon for the past two cross checks, thus there is not a trend. No corrective action anticipated at this time.

March 28, 1994 88

EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICULATES (pg. 1 of 1) 80 60 O

a. 40 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl+3 Sigma o EPA13Sigma

EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg. 1 of 1) 160 140 120 O 100 Q.

EO 80 60 40 20 0

1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 8/25/89 EPA test invalid.

Tl k 3 Sigma - o EPA+ 3 Sigma 0

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES (pg. 1 of 1) 80 60 O

n. 40 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl 2 3 sigma o EPA m 3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg. 1 of 1) 80 60 O

a. 40 C

0 I-20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl k 3 sigma o EPA*3 sigma 0

EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK (pg. 1 of 1) 100 80 60 40 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl 2 3 sigma o FPA g3 sigma

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg. 1 of 1) 80 60 I

o 40 0

CL 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl k 3 sigma o EpA i3 sigma

EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg. 1 of 1) 2600 2400 2200 2000 I 1800 1600 1400 1200 1000 800 600 1981 1982 1983 1984 1985 1986, 1987 1988 1989 1990 1991 1992 1993 1994 Tl t 3 sigma o EPA a3 sigma

EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg. 1 of 1) 160 140 120 100 I

80 0,

'L 60 40 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl k 3 sigma o EPA a3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK (pg. 1 of 1) 100 80 O

60 0

CL 40 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl 2 3 sigma o EPA X3 sigma

EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER (pg. 1 of 1) 180 160 140 120 I

I 100 80 60 40 20 20 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 o Tl a 3 Sigma o EPA a 3 Sigma

EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 1 of 2) 220 200 180 160 140 I

120 100 80 60 40 20

-20 1981 1982 1983 1984 1985 1986 Tl 2 3 sigma > EPA k 3 sigma

EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 260 220 180 l

Cl 140 O

CL 100 60 20

-20 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl t 3 sigma o EPA a 3 sigma 0 9

EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 1 of 2) 5000 4000 3000 2000 O

1000 0

-1000 1981 1982 1983 1984 1985 0 Tl %3 sigma o EPA a3 sigma

EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 16000 14000 12000 10000 8000 6000 4000 2000 1984 1985 1986 1987 1988 1989 .1990 1991 1992 1993 1994 Tl k 3 Sigma o EPA+ 3 Sigma

EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 160 140 120 100 I

80 0

CL 60 40 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Ti i 3 sigma o EPA+3 sigma

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

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

EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg. 2 of 2)--

100 80 60 I

0 40 20

-20 1988 1989 1990 1991 1992 1993 1994 Tl 1 3 sigma EPA t3 sigma

EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 1 of 2) 100 80 60 40 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 D Tl 2 3 sigma o fPA i3 sigma

EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 2 of 2) 100 80 60 I

0 40 20

-20 1988 1989 1990 1991 1992 1993 1994 TI 2 3 sigma o EPA k3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 1 of 2) 80 60 40 O6 00 20

-20 1981 1982 1983 1984 1985 1986 1987 a Tl i3 sigma o EPA X3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 2 of 2) 120 100 80 O

60 O

CL 40 20 0

-20 1988 '1989 1990 1991 1992 1993 1994 Tl k3 sigma < EPA i3 sigma

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

40 O

CL 20

-20 1981 1982 1983 1984 1985

0. TIX3sigma o EPA i3 sigma

EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2 of 2)-

80 60 Cl 40 0

CL 20

-20 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 Tl+3Sigma o EPA+3 Sigma

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER (pg. 1 of 1) 80 60 I 40 0

CL 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 '1989 1990 1991 1992 1993 1994 Tl k 3 sigma o EPA k3 sigma

f APPENDIX E REMP SAMPLING AND ANALYTICALEXCEPTIONS 113

PROGRAM EKCEPTIONS REMP deviations for 1993 are listed at the end of this append Where possible, the causes of the deviations have been corrected to prevent recurrence.

There were nine incidences involving air samplers during 1993.

Seven incidences were due to tripped breakers resulting from voltage surges. These power surges are attributed to thunderstorm activity where lightning strikes a power line, initiating a sure of power to the air sampler, tripping the breaker.

I I

Surge protectors were installed in all REMP air stations on 10/ll/93 to prevent damage to the equipment, however the incoming power is not "conditioned" to prevent tripping the breakers.

On 3/8/93 air station A2 was without power due to a defective section of underground power cable. The damaged section of this cable was replaced and continuous sampling resumed until August/Septemb of 1993. The underground cable was reinspected and.determined to in sound condition. All electrical components at this air station were replaced in an effort to rectify the situation. In February 1994 a similar situation occurred involving lack of power to air station A2. The root cause has been determined to be a "supplemental section" of underground cable joining the main underground power line to an associated electrical meter. The section of underground cable was replaced and there have been no indications of power problems at air station A2.

In May 1993, the New Buffalo air sampler was identified to have a defective fuse holder. This air sampler was immediately replaced with a functional air sampler and continuous sampling resumed.

It should be noted that all REMP air samplers were upgraded in June 1993. The new air samplers have more sophisticated data collection capabilities and are more efFicient than the previous models. During the interim some of the volumes from the new air samplers were calculated manually until all quality control issues had been resolved.

114

There were two incidences involving missing TLDs from offiste locations. The TLDs are placed in a wire mesh holder approximately 4

~

feet above grade. The Plant has since relocated the TLDs 8 feet above

~

grade and placed a more visible label on the TLD holders identifying them as Cook Plant property.

All of the milk samples were collected during 1993, however one sample was collected the day after it was scheduled. On 1/22/93 the milk wholesaler arrived at the Warmbein Dairy Farm earlier than scheduled and emptied the collection tank. The sample collector returned on 1/23/93 and collected the sample within the allowable Technical Specifications grace period.

115

REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DUPING 1993 Date of;-. Reason(s) for Loss Station Descri tion Sam lin Exce tion QC Gross Beta 01/14/93 Gross beta replicate sample Program 499805 reanalyzed, acceptable results.

Warmbein Milk 01/22/93 Tank empty, sample collected 01/23/93.

A-2 03/08/93/ 'nderground cable supplying 03/22/93 power to air station was damaged.

New Buffalo Air 05/03/93/ Defective fuse holder/blown fuse.

A'5 Air 05/24/93 Tripped breakers attributed to thunderstorm activity.

Dowagiac Air 05/31/93 Tripped breakers attribu o thunderstorm activity.

Air 08/02/93- Tripped breakers. Electrical 08/30/93 components replaced. Possible 09/20/93- voltage surge due to thunder-09/27/93 storm activity.

Air 08/16/93 Tripped breakers attributed to 09/20/93 thunderstorm activity. Surge protectors installed 10/11/93.

A3 08/30/93 Tripped breakers attributed to thunderstorm activity. Surge protectors installed 10/11/93.

A5/A6 11/08/93 Primary fuse in overhead power lines tripped.

OFS-6 TLD 2nd Qtr. TLD missing.

OFS-4 TLD 4th Qtr. TLD missing.

116

APPENDIX F 1993 LAND USE CENSUS 117

APPENDIX F

SUMMARY

OF THE 1993 LA'ND USE CENSUS O

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. No such changes were identified during the 1993 Land Use Census. The following is a summary of the 1993 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 Cook Power Plant was conducted on August 30, 1993.

In 1993 there were two deletions and one addition to the Michigan Department of Agriculture's list of dairy farms in Berrien County Michig The deleted farms were not part of 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 Cook 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 is performed to identify the closest residence in each land sector surrounding the Plant. The residential survey was completed on September 15, 1993 using an updated list of all new residential building permits issued during the previous year. The closest residence to the Plant in each sector remains unchanged from the previous year.

118

Broadleaf Surve In accordance with Technical Specification (T/S) 3.12.2, 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 1993 were less than the Technical Specification LLDs.

119

Figure 7 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR P Milk Farm Survey - 1993 Survey Distance Sector Year MiIes Name Address N/A No milk farms N/A N/A No milk farms N/A a N/A No milk farms N/A b N/A No milk farms N/A a N/A No milk farms N/A b N/A No milk farms N/A D 5.1 Gerald Totzke 6744 Totzke Rd., Baroda

5. Gerald Totzke 6744 Totzke Rd., Baroda 1'0.5 Andrews University Berrien Springs 10.5 Andrews University Berrien Springs

'a 6.8 Lee Nelson RFD 1, Box 390A, Snoi Baroda 6.8 Lee Nelson RFD 1, Box 390A, Snow Rd.

Baroda 4,1 G. G. Shuler 8. Sons RFD 1, Snow Rd., Baroda 4.1 G. G. Shuler R Sons RFD 1, Snow Rd., Baroda 7.0 George Freehling 2221 W. Glendora Rd., Buchana 7.0 George Freehling 2221 W. Glendora Rd., Buchana 7.7 Jerry Warmbein 14143 Mill Rd., Three Oaks 7.7 Jerry War mbein 14143 Mill Rd., Three Oaks 12 Kenneth Tappan Rt. 2, Kruger Rd, Three Oaks 12 Kenneth Tappan Rt. 2, Kruger Rd, Three Oaks All other sectors are over water.

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

0 120

Figure 8 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT Resl<lentlal Land Use Survey - 1993 Sector House tt) In Feet Pro ert Street Address a 2161 11-] 1-0006-0004-01-7 lier Drive, Rosemary Beach b 2161 I 1-1 1-0006-0004-01-7 lier Drive, Rosemary Beach a 2 2165 1 1-1 ] -0006-0004-09-2 lier Drive, Rosemary Beach b 2 2165 11-1 1-0006-0004-09-2 lier Drive. Rosemary Beach S.

a 3 3093 1 I - ] 1-6800-0028-00-0 Lake Road, Rosemary Beach b 3 3093 1 I - I 1-6800-0028-00-0 Lake Road, Rosemary Beach D a 4 5733 ] 1-11-0005-0036-01-8 7500 Thorton Drive b 4 5733 I 1-1 1-0005-0036-01-8 7500 Thorton Drive 5 5631 I 1-11-0005-0009-07-0 7927 Red Arrow Highway 5 5631 11-11-0005-0009-07-0 . 7927 Red Arrow Hlgltway 6 5392 11-11-0008-0015-03-1 8197 Red Arrow Highway 6 5392 11-1 1-0008-0015-03-1 8197 Red Arrow fllghway G a 7 3728. I 1-1 1-0007-0013-0] -4 Llvlngston Road

.b 7 3728 I 1-11-0007-0013-01-4 Llvlngston Road 8 4944 11-] 1-8600-0004-00-1 Wildwood b 8 4944 11-1 1-8600-0004-00-1 Wildwood 3366 1 1-1 1-0007-0010-02-3 I.lvlngston HI)is 3366 1 I - I 1-0007-0010-02-3 Llvlrtgston ]fills a ]0 3090 1 ] 0007-0010-03-1 Llvlngston ]fills b 10 3090 11-11-0007-0010-03-1 Llvlttgston flllls f l) )louse tt l<t<ficate<l ls thc referet<e< nun<)>er use<I o<t utap when obtat<ttt<g th< raw flehl <lata.

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APPENDIX G

SUMMARY

OF THE PRE-OPERATIONAL RADIOLOGICALMONITORING PROGRAM 124

SUMMARY

OF THE PREOPERATIONAL RADIOLOGICAL MONITORING PROGRAM f

A preoperational radiological environmental monitoring program was performed for the Donald C. Cook Nuclear P}ant from August 1971 until the initial criticality of Unit 1 on January 18, 1975. The analyses of samples collected in the vicinity of the nuclear power 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 plant during the pre-start up of Unit 1 and the radioactivity measured in 1993.

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 location's 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 125

1993. Analyses performed during the preoperational but not required in 1993, are not discussed.

The gross beta activity in air particulate filters ranged from 0.01 to 0.17 pCi/m3 from the middle of 1971 to the middle of 1973. In June of 1973 and in 'June of 1974 the People's Republic of China detonated atmospheric nuclear tests. As a result there were periods during which the gross beta results were elevated to as high as 0.45 pCi/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 Alters showed "trace amounts" of Qssion 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 f 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.

126 e

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.

Drinldng water analysis was not part of the preoperational program.

127

APPENDIX H

SUMMARY

OF THE REMP QUALITYCONTROL PROGRAM 128

SUMKARY OF THE REMP QUALITYCONTROL PROGRAM The plant procedure for implementing the quality control program references Regulatory Guide 4.15. The program utilizes blank, replicate and spiked samples within four different parameters; gamma isotopic, tritium, iodine and gross beta. The blank and replicate samples are prepared at the D.C. Cook Plant and the spiked samples are prepared by Teledyne Isotopes.

Twenty-seven quality control samples were performed during 1993.

Twenty six samples had acceptable results. One of the gross beta replicate samples was slightly outside the acceptable range. This sample was reanalyzed and gave acceptable results. Teledyne conducted an investigation and could not determine a root cause.

129

APPENDIX I

SUMMARY

OF THE SPIKE AND BL'ANKSAMPLE PROGRAM j30

SUMMARY

OF THE SPIKE AND BLANKSAMPLE PROGRAM The following tables list the blanks and spiked water samples analyzed during 1993 for the Teledyne Isotopes In-house Quality Assurance Program.

Analysis date is analogous to collection date to identify weekly analysis of samples.

Two analyses for gross beta activity were marginally outside the specified acceptable ranges, If the counting errors were included in the assessment of spike results all measurements would be within acceptable ranges. No documented corrective action was taken because in accordance with Section 9.1 of our Quality Control Manual (IWL-0032-365), the acceptance criteria for a particular analysis "is within 3 standard deviations of the EPA one sigma, one determination as specified in the Environmental Radioactive Laboratory Studies Program EPA-600/4-81-004, Table 3, Page 8". For gross beta activity below 100 pCi/I the control level at which corrective action must be taken is+

15 pCi/l. The quality assurance department operationally investigates gross beta spike results which exceed the one standard deviation, one determination levels (+ 5 pCi/I), because of previous experience in reporting results within that level. Control charts for gross alpha and beta spikes did not indicate any bias in results.

If For the tritium spikes by liquid scintillation counting (10 ml aliquots) the three, standard deviations of the EPA one sigma, one determination would be greater than 1000 pCi/I for a spike level of 1400 pCi/1. The quality assurance department operationally investigates tritium spike results which exceed+ 200 pCi/l. Control charts indicated a slight low bias in tritium spike results with one measurement outside the 15% operational acceptance criteria.

If the counting errors were included in the assessments of spike results all measurements would be within acceptable ranges.

131

Teledyne Isotopes In-House Spiked Sample Results - 1993 Water S ik Levels Acce table Gross Alpha 1.1 2 0.5 E Ol 0.6 - 1.6 E 01 Gross Beta 2.2+ 0.5 E Ol 1.7 - 2.7 E 01 Gamma (Cs-137) 22k 03E04 1.9 - 2.5 E 04 H-3 (LS) 1.4 2 0.2 E 03 1.2 - 1.6 E 03 GROSS ALPEXA Tl ll An i D A vi i 1 00868 01/06/93 1.2 + 0.2 E 01 01769 01/13/93 9.3 2 1.6 E 00 02250 01/20/93 1.4+ 0.2 E 01 02959 01/27/93 1.1 + 0.2 E Ol

-03556 02/03/93 1.1 2 0.2 E Ol 04474 02/10/93 1.3 + 0.2 E 01 04837 02/17/93 1.5 + 0.2 E 01 05584 02/24/93 1.4 + 0.2 E Ol 05928 03/03/93 1.5 + 0.2 E Ol 07149 03/10/93 1.2 + 0.2 E Ol 07516 03/17/93 1.4+ 0.2 E Ol 08360 03/24/93 1.1 2 0.2 E 01 08580 03/31/93 1.4 + 0.2 E 10729 04/07/93 02 E Ol Ol'.1+

10755 04/14/93 1.2 + 0.2 E Ol 11628 04/21/93 1.0+ 0.2 E Ol 12255 04/28/93 .1.2 + 0.2 E Ol 12799 05/05/93 1.4+ 0.2 E Ol 13458 05/12/93 1.3 2 0.2 E Ol 14174 05/19/93 1.3 + 0.2 E 01 15071 05/26/93 78+ 1.4 E 00 15408 06/02/93 1.2 + 0.2 E Ol 16236 06/09/93 1.1 + 0.1 E 16785 06/16/93 + 0.2 Ol'.3 E Ol 17644 06/23/93 l."2 + 0.2 E Ol 17981 06/30/93 1,1 + 0.2 E Ol 18513 07/07/93 7.4 + 1.0 E 00 19897- 07/14/93 1.5 + 0.2 E 01 20410 07/21/93 1.1 2 0.2 E Ol 21017 07/28/93 1.3 + 0.2 E Ol 21812 08/04/93 1.3+ 0.2 E Ol 22449 08/11/93 1.1 + 0.2 E Ol 23386 08/18/93 1.0+ 0.2 E Ol 23750 08/25/93 1.2 + 0.2 E 01 132

GROSS ALPHA (Cont.)

TI 0 is Date 24641 09/01/93 1.4 2 0.2 E 01 25441 09/08/93 1.5 + 0.2 E Ol 26420 09/15/93 9.3 + 1.6 E 00 26679 09/22/93 1.3 + 0.2 E Ol 27679 09/29/93 1.1 + 0.2 E Ol 28285 10/06/93 1.1 2 0.2 E Ol 29164 10/13/93 1.3 + 0.2 E 01 30479 10/20/93 1.2 2 0.2 E Ol 31367 10/27/93 1.2 + 0.2 E Ol 31803 11/03/93 1.2 + 0.2 E Ol 32600 11/10/93 1.4 2 0.2 E Ol 33742 11/17/93 1.3+ 0.2 E Ol 34049 11/24/93 1.2+ 0.2 E 01 34805 12/01/93 9.7+ 1.5 E 00 35615 12/08/93 1.1 + 0.2 E Ol 36167 12/15/93 94+ 1.5 E 00 36993 12/22/93 9.6+ 1.5 E 00 37568 12/29/93 9.6+ 1.5 E 00 GROSS BETA TI 4 Activi Ci 1 00868 "

01/06/93 2.0 + 0.1 E Ol 01769 01/13/93 2.0 + 0.2 E 01 02250 01/20/93 2.0 2 0.2 E Ol 02959 01/27/93 2.0+ O,l E Ol 03556 02/03/93 2.4+ 0.2 E Ol 04474 02/10/93 2.3+ 0.2 E Ol 04837 02/17/93 2.1 + 0.2 E Ol 05584 02/24/93 1.8+ 0.1 E Ol 05928 03/03/93 2.3 2 0.2 E Ol 07149 03/10/93 2.1 2 0.'2 E Ol 07516 03/17/93 2.0 2 O.l E Ol 08360 03/24/93 1.6+ O.l E Ol 08580 03/31/93 2.5 2 0.2 E Ol 10729 04/07/93 1.9 + 0.1 E Ol 10755 04/14/93 2.3 2 0.2 E Ol 11628 04/21/93 2.1 + 0.2 E Ol 12255 04/28/93 2.0+ 0.1 E Ol 12799 05/05/93 2.5 + 0.2 E Ol 13458 05/12/93 1.9+ 0.1 E Ol 14174 .

05/19/93 2.1 2 0.2 E Ol 15071 05/26/93 2.3 2 0.2 E 01 133

GROSS BETA (Cont.)

TI ¹ is Date 15408 06/02/93 1.8 + O.l E 01 16236 06/09/93 1.7 + 0.1 E 01 16785 06/16/93 1.7 + 0.1 E 01 17644 06/23/93 2.7 + 0.2 E 01 17981 06/30/93 2.0 + 0.2 E 01 18513 07/07/93 2.6 + O.l E 01 19897 07/14/93 2.1 + 0.2 E 01 20410 07/21/93 2.2 + 0.2 E 01 21017 07/28/93 2.4 + 0.2 E 01 21812 08/04/93 1.7 + 0.'1 E 01 22449 08/11/93 1.6 + O.l E 01 23386 08/18/93 2.6 + 0.2 23750 24641 08/25/93 09/Ol/93 l

2.4 0.2 2.5 + 0.2 E

E E

01 01 01 25441 09/08/93 2.2 + 0.2 E 01 26420 09/15/93 2.1 + 0.2 E 01 26679 09/22/93 2.5 + 0.2 E 01 27679. 09/29/93 2.0 + O.l E 01 28285 10/06/93 2.4 + 0.2 E 01 29164 10/13/93 1.7 + O.l E 01 30479 10/20/93 1.8 + 0.1 E 01 31367 10/27/93 2.5 + 0.2 E 01 31803 11/03/93 2.1 + O.l E 01 32600 . 11/10/93 2.4 + 0.2 E 01 33742 ll/17/93 2.5 + 0.2 E 01 34049 11/24/93 1.9 + 0.1 E 01 34805 12/01/93 1.8 + 0.1 E 01 35615 12/08/93 1.9 + 0.1 E 01 36167 12/15/93 2.1 + 0.2 E 01 36993 12/22/93 1.9 + 0.1 E 01 37568 12/29/93 2.0 + 0.1 E 01

, GAMMA (Cs-137)

TI ¹ 00873 01/06/93 2.24 + 0.22 E 04 01774 01/13/93 2.02 2 0.20 E 04 02255 01/20/93 2.26 + 0.23 E 04 02964 01/27/93 2.07+ 0.21 E 04 03561 02/03/93 2.16 + 0.22 E 04 04479 02/10/93 2.26 + 0.23 E 04 04842 02/17/93 2.26 + 0.23 E 04 05589 02/24/93 2.21 + 0.22 E 04 05933 03/03/93 2.23 + 0.22 E 04 134

GAMBIA (Cs-137)

TI ¹ is Date 07154 03/10/93 2.22 + 0.22 E 04 08365 03/24/93 '.15 0.22 E 04 08585 03/31/93 2.20 + 0.22 E 04 10734 04/07/93 ~

2.18 + 0.22 E 04 10760 04/14/93 2. 17 + 0.22 E 04 11633 04/21/93 2.23 + 0.22 E 04 12260 04/28/93 2.22 2 0.22 E 04 12804 05/05/93 2.26 2 0.23 E 04 03463 05/12/93 2.17 2 0.22 E 04 14179 05/19/93 2.15 + 0.22 E 04 15076 05/26/93 2.25 + 0.23 E 04 15413 06/02/93 2.19 +022E04 16241 06/09/93 2.20 + 0.22 E 04 16790 06/16/93 2.23 2 0.22 E 04 17649 06/23/93 2.16 + 0.22 E 04 17986 06/30/93 '2.20 + 0.22 E 04 18518 07/07/93 2.21 2022E04 19902 07/14/93 2.23 2 0.22 E 04 20415 07/21/93 2.18 + 0.22 E 04 21022 07/28/93 2.20 2 0.22 E 04 21817 08/04/93 2.24 + 0.22 E 04 22454 08/11/93 2.17 + 0.22 E 04 23391 08/18/93 2.22 + 0.22 E 04 23755 08/25/93 2.23 + 0.22 E 04 24666 09/Ol/93 2.28 2 0.23 E 04 25546 09/08/93 2.21 + 0.22 E 04 26425 09/15/93 2.25 + 0.23 E 04 26684 09/22/93 2.20 + 0.22 E 04 27684 09/29/93 2.20 + 0.22 E 04 28290 10/06/93 2.08 + 0.21 E 04 29169 10/13/93 2.23 + 0.22 E 04 30484 10/20/93 2.22 + 0.22 E 04 31372 10/27/93 2.23 + 022 E04 31808 ll/03/93 2.21 + 0.22 E 04 32605 ll/10/93 2. 17 2022E04 33747 11/17/93 2.21 + 0.22 E 04 34054 11/24/93 2. 19 + 0.22 E 04 34810 12/01/93 2.25 + 0.23 E 04 35620 . 12/08/93 2.23 + 0.22 E 04 36172 12/15/93 2. 17 + 0.22 E 04 "36998 12/22/93 2.20 + 0.22 E 04 37573 12/29/93 2.28 + 0.23 E 04 135

TRITIUM - (H-3) 10ml TI ff 00870 Ol/06/93 1.4 2 O.l E 03 01771 Ol/13/93 1.3 + O.l E 03 02252 01/20/93 1.4 + 0.1 E 03 02961 01/27/93 1.5 + O.l E 03 03558 04476 02/03/93 02/10/93 1.3 t+ O.l E 03 04839 05586 02/17/93 02/24/93 1.5 1.4 1.3 2 i 0.2 E 03 O.l E 03 O.l E 03 05930 03/03/93 1.4 2 O.l E 03 07151 03/10/93 + O.l E 03 07518 08362 03/17/93 03/24/93 1.2 1.6 1.2 i

2 0.2 E 03 O.l E 03 08582 03/31/93 1.3 k O.l E 03 10731 04/07/93 1.3 2 O.l E 03 10757 04/14/93 1.2 R 0.1 E 03 11630 04/21/93 1.2 2 O.l E 03 12257 04/28/93 1.3 + O.l E 03 12801 05/05/93 1.2 2 0.1 E 03 13460 05/12/93 1.2 + 0.1 E 03 14176 05/19/93 1.3 + 0.1 E 03 15073 05/26/93 1.3 + 0.1 E 03 15410 06/02/93 1.5 + 0.2 E 03 16238 06/09/93 1.3 + O.l E 03 16787 06/16/93 1.2 + 0.1 E 03 17466 06/23/93 1.3 2 0.1 E 03 17983 06/30/93 1.3 2'O.l E 03 18515 07/07/93 1.4 + 0.1 E 03 19899 07/14/93 1.4 + 0.2 E 03 20412 07/21/93 1.5 + 0.2 E 03 21019 07/28/93 1.4 + 0.2 E 03 21814 08/04/93 1.4 + 0.2 E 03 22451 08/11/93 1.4 2 O.l E 03 23388 08/18/93 1.4 + 0.1 E 03 23752 08/25/93 1.3 k O.l E 03 24643 09/Ol/93 1.4 + O.l E 03 25543 09/08/93 1.4 + O.l E 03, 26422 09/15/93 1.4 + O.l E 03 26681 09/22/93 1.4 + O.l E 03 27681 09/29/93 1.3 + 0.2 E 03 28287 10/06/93 1.4+ 0."1 E 03 29166 10/13/93 1.5 + 0.2 E 03 30481 10/20/93 1.2 + O.l E 03 31369 10/27/93 1.4 + 0.1 E 03 136

TI 8 ~tl Cl 31805 ll/03/93 1.4 2 O.l E 03 32602 ll/10/93 1.4 + 0.1 E 03 33744 ll/17/93 R.2+ O.l E 03 34051 11/24/93 1.3 + 0.1 E 03 34807 12/01/93 1.3 + 0.1 E 03 35617 12/08/93 1.4+ 0.1,E 03 36169 12/15/93 1.3+ O.l E 03 36995 12/22/93 1.4+ 0.1 E 03 37570 12/29/93 1.2 + 0.2 E 03 137

Teledyae Isotopes In-House Bhmhs Sample Results - 1993 Water TI ff 00867 Sasla GROSS ALE'H'A-BLA'NKS

'1/06/93 L. T. 6. E-01 01768 Ol/13/93 L. T. 5. E-01 02249 01/20/93 L, T. 6. E-01 02958 01/27/93 L. T. 4. E-01 03555 02/03/93 L. T. 5. E-01 04473 02/10/93 L. T. 4. E-01 04836 02/17/93 L. T. 9 E-01 05583 02/24/93 L. T. 6. E-01 05927 03/03/93 L. T. l. E 00 07148 03/10/93 L. T. 6. E-01 07515 03/17/93 L. T. 5. E-01 08359 03/24/93 L. T. 5, E-01 08579 03/31/93 L. T. 5. E-01 10728 04/07/93 L. T. 4, E-01 10754 04/14/93 L. T. 2. E 00 11627 04/21/93 L. T. 6. E-01 12254 04/28/93 L. T. 6. E-01 12798 05/05/93 L. T. E-01 13457 05/12/93 L. T. 5. E-01 14173 05/19/93 L. T. 6. E-01 15070 , 05/26/93 L. T. 5. E-01 15407 06/02/93 L. T. 7: E-01 16235 06/09/93 L. T. 4, E-01 16784 06/16/93 L. T. 6. E-01 17643 06/23/93 L. T. 8. E-01 17980 06/30/93 L. T.'.

8. E-01 18512 07/07/93 T. 4. E-01 19896 07/14/93 L. T. 4, E-01 20409 07/21/93 L. T. 5. E-01 21016 07/28/93 L. T. 7. E-01 21811 08/04/93 L. T. 4, E-01 22448 08/11/93 L. T. 5. E-01 23385 08/18/93 L. T. 6. E-01 23749 08/25/93 L. T. 6. E-01 24640 09/01/93 L. T. 4. E-01 25540 09/08/93 L. T. 7. E-01 26419 09/15/93 L. T. 8. E-01 26678 09/22/93 L. T. 7. E-01 27678 09/29/93 L. T. 7. E-01 28284 10/06/93 L. T. 7. E-01 29163 10/13/93 L. T. 5. E-01 30478 10/20/93 L. T. 6. E-01 138

GROSS ALPHA-BLA'NKS (Cont.)

TI ¹ ttllttht" ~tl 31366 10/27/93 L. T. 6. E-01 31802 ll/03/93 L. T. 6. E-01 32599 11/10/93 L. T. 8. E-01 33741 11/17/93 L. T. 7. E-01 34048 11/24/93 L. T. 6. E-01 34804 12/01/93 L. T. 7. E-01 35614 12/08/93 L. T. 7. E-01 36166 12/15/93 L. T. 4. E-01

,36992. 12/22/93 L. T. 5. E-01 37567 12/29/93 L. T. 7. E-01 GROSS BETA-BMNKS TI ¹ Activi Ci 1 00867 01/06/93 L. T. 8. E-01 01768 01/13/93 L. T. l. E 00 02249 01/20/93 L, T, 9. E-01 02958 01/27/93 L. T. 8. E-01

'2/03/93 03555 L. T. 7. E-01 04473,. 02/10/93 L. T. 7. E-01 04836 02/17/93 L. T. 9 E-01 05583 02/24/93 L. T. 8. E-01 05927 03/03/93 1,3+ 0.7 E 00 07148 03/10/93 L. T. 9 E-01 07515 03/17/93 L. T. 9 E-,01 08359 03/24/93 L. T. 1. E 00 08579 03/31/93 L. T. 8. E-01 10728 04/07/93 L. T. 5. E-01 10754 04/14/93 L. T. 9. E-01 11627 04/21/93 L. T. 1 ~ E 00 12254 04/28/93 L. T. 7. E-01 12798 05/05/93 L. T E-01 13457 05/12/93 L. T. 8. E-01, 14173 05/19/93 L. T. 8. E-01 15070 05/26/93 1.1 +0.6 E 00 15407 06/02/93 L. T. 8. E-01 16235 06/09/93 L. T. 6. E-01 16784 06/16/93 L. T. 8. E-01 17643 06/23/93 L. T. 8. E-01 17980 06/30/93 L. T. 8. E-01 18512 07/07/93 L. T. 6. E-01 19896 07/14/93 L. T. 7. E-01 20409 07/21/93 L. T. 7. E-01 21016 07/28/93 L. T. 8. E-01 139'

GROSS BETA -BLANKS (Cont.)

is Date Activi Ci 21811 08/04/93 L. T. 7.

22448 08/11/93 L. T. 7.

23385 08/18/93 L. T. 8. E-01 23749 08/25/93 L. T. 9 E-01 24640 09/01/93 L. T, 8. E-01 25540 09/08/93 L. T. 8. '-01 26419 09/15/93 L. T. 8. E-01 26678 09/22/93 L. T. 7. E-01 27678 09/29/93 L. T. 8. E-01 28284 '0/06/93 L. T. 8. E-01 29163 10/13/93 L. T. 9 E-01 30478, 10/20/93 L. T. l. E 00 31366 10/27/93 L. T. 1. E 00 31802 11/03/93 L. T. 8. E-01 32599 11/10/93 L. T. 9. E-01 33741 11/17/93 L. T. 8. E-01 34048 11/24/93 L. T. 9 '-01 14804 12/01/93 'L. T. 7. E-01 35614 12/08/93 L. T. 8. E-01 36166 12/15/93 L. T. l. E 00 36992 12/22/93 L. T. 9. E-01 37567 12/ 29/93 L. T. 8. E-01 TRITIUM - (H-3) - BLANKS TI ¹ Activi 00871 01/06/93 L. T. l. E 02 01773 Ol/13/93 L. T. l. E 02 02254 01/20/93 L. T. 2. E 02 02963 01/27/93 L. T. 1. E 02 03560 02/03/93 L. T. l. E 02, 04478 02/10/93 L. T. l. E 02 04841 02/17/93 L. T. 2. E 02 05588 02/24/93 L. T. l. E 02 05932 03/03/93 L. T. 2. E 02 07153 03/10/93 L. T. l. E 02 07520 03/17/93 L. T. 2. E 02 08364 03/24/93 L. T. 1. E 02 08584 03/31/93 L. T. 1. E 02 10753 04/07/93 L. T. 1. E 02 10759 04/14/93 L. T. l. E 02 11632 04/21/93 L. T. l. E 02 12259 04/28/93 L. T. l. E 02 12803 05/05/93 L. T. 1. E '02 13462 05/12/93 L. T. 1. E 02 140

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

TI 0 is Date 14178 05/19/93 L. T. l. E 02 15075 05/26/93 L. T. l. E 02 15412 06/02/93 L. T. 2. E 02 16240 06/09/93 L. T. l. E 02 16789 06/16/93 L. T. l. E 02 16789 06/16/93 L. T. l. E 02 17648 06/23/93 L. T. l. E 02 17985 06/30/93 L. T. l. E 02 17985 06/30/95 L. T. l. E 02 18517 07/07/93 L. T. l. E 02 19901 07/14/93 L. T. 2. E 02 20414 07/21/93 L. T. 2. E 02 21021 07/28/93 L. T. 2. E 02 21816 08/04/93 L. T. 2. E 02 22453 08/11/93 L. T. 2. E 02 23390 08/18/93 L. T. 2. E 02 23754 08/25/93 L. T. 2. E 02 24645 09/Ol/93 L. T. 1 ~ E 02 25545 09/08/93 L. T. 2. E 02 26424 09/15/93 L. T. 2. E 02 26683 09/22/93 L. T. l. E 02 27683 09/29/93 L. T. 2. E 02 28289 10/06/93 L. T. 2. E 02 29168 10/13/93, L. T. 1. E 02 30483 10/20/93 L. T. '2. E 02 31371 10/27/93 L. T. l. E 02 31807 ll/03/93 L. T. 1 ~ E 02 32604 ll/10/93 L. T. 2. E 02 33746 11/17/93 L. T. 2. E 02 34053 11/24/93 L. T. 2. E 02 34809 12/01/93 L. T. 2. E 02 35619 12/08/93 L. T. 2. E 02 36171 12/15/93 L, T. 2, E 02 36997 12/22/93 L. T. l. E 02 37571 12/29/93 L. T. 2. E 02 141

APPENDIX J TLD QUALITYCONTROL PROGRAM 142

TLD QUALITYCONTROL PROGRAM Teledyne Isotopes 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 cesium-137 exposure rate.

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 labs.

For 1993 all results were within the requirements of Regulatory Guide 4.13, Section C. The standard deviations were less than 7.5% and the variations from the known were less than 30%. The accompanying graphs show the normalized deviations of the measured doses to the exposure doses for each'of the three readers.

143

QUALITYCONTROL - TLDS TLD READER 205 Ag 0.5 /g O

O.

X O

O ~. /

I-

/

O C . r~ / I I /

tD I /

~ J'

'~//

/

E O

C

/ F I o -05 X/ 8 CS 5 I C)

D I

'D Ql N I Cgg E I s

0 -1 Z ~

I

~

1

~ ~

1I 0

-1.5 1/89 4/89 7/89 10/89 1/90 4/90 7/90 10/90 1/91 4/91 7/91 10/91 1/92 7/92 9/92 11/92 1/92 3/93 7/93 10/93 Low Dose Middle Dose High Dose

QUALITYCONTROL - TLDS

-TLD READER 211 1.5

/X

/.X 0.5

// '

0 0 /

-0.5 '

y/ ~

/ /

/

/

(I

-1.5 0

-2 1/89 4/89 7/89 10/89 1/90 4/90 7/90 10/90 1/91 4/91 7/91 10/91 1/92 7/92 9/92 11/92 1/93 3/93 7/93 10/93 Low Dose Middle Dose High Dose

QUALITYCONTROL - TLDs TLD READER 242 0.8 0.6 0 P~

O 0.4 (/ i~

,/

CO O

CL 0.2 / ~

o (

I s

X &

0 r 8 I- I C -0.2

~ I ] s 0 c) Ig

    -0.4                                                                          to
    -0.6
                                                                            /

E 0 ] ~ I C 0

    -0.8                                                                (/                         1
                                                                                                    ~

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}}l

'a -1.2 I 'D 1,

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    -1.4                                                                                                'I

(}} E 0 -1.6

    -1.8
      -2 1/89 4/89   7/89 10/89 1/90 4/90 7/90 10/90 1/91  4/91  7/91 10/91 1/92   7/92 9/92 11/92 1/93 3/93 7/93 10/93 Low Dose                Middte Dose       E}      High Dose

QUALITYCONTROL - TLDs LOW DOSE ID 0.5 5C 0 0 I O O I- IQ C \ 0 C LI Cl

                          . 0
    -0.5                                                                                                                   I E
                                                                                                               ,j L

0 ) Cl

 )

Cl I '0 Cl N

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0 R

      -2
                                                                     ~                             ~

01/89 04/89 07/89.10/89 01/90 04/90 07/90 10/90 01/91 04/91 07/91 10/91 1/92 7/92 9/92 11/92 1/93 3/93 7/93 10/93 Reader-205 Reader-211 Reader-242 Reader-9150 Reader-9150 was permanently removed from service during Ihe first quarter 1993.

QUALITYCONTROL - TLDs MIDDLE DOSE O 1.5 O Q. X O Q I-c /y 0 C

                     /<  t 0.5            /

I / E O I / a 5 0 25d c--g O -0.5 'U 'D Cl N R5 E O

    -1.5 1/89 4/89 7/89 10/89 1/90 4/90 7/90 10/90 1/91 4/91 7/91 10/91 1/92 7/92 9/92 11/92 1/93 3/93 7/93 10/93 Reader-205  =  Reader.2'11          ~ ~            Reader-242          Reader.9150 Reader-9150 was permanently removed from service during the first quarter 1993.

QUALITYCONTROL - TLDs HIGH DOSE 0.8 0.6 I O) 0.4 0 fL I / O 0.2 I/ I- / C C' O / .

):
    -0.2                                                                               /

0) E X / \

    -0.4 O
                                                                                                     ~Q /
)

C)

    -0.6                                                                      A.

II)

)

ID 'D 'D -0.8 I)) N E 0 R -1.2

    -1.4 1/89 4/89 7/89 10/89 1/90 4/90 7/90 10/90 1/91 4/91 7/91 10/91 1/92 7/92 9/92 11/92 1/93 3/93 7/93 10/93 Reader-205     Reader-211           ~ ~         Reader-242 Reader-9150 permanently removed from service during the first quarter 1993.

Reader-0150}}