ML17334B420

DC Cook Nuclear Plant Units 1 & 2 Annual Environ Operating Rept,1991. W/920424 Ltr

ML17334B420
Person / Time
Site:	Cook
Issue date:	12/31/1991
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0806L, AEP:NRC:806L, NUDOCS 9204300315
Download: ML17334B420 (281)

Text

'ACCELERATE'D DI< BUTION DEMONS'HQTION SYSTEM 4

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9204300315 DOC.DATE: 91/12/31 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 FIRZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

"Annual Environ Operating Rept,1991." W/920424 ltr.

DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR J ENCL SIZE: 0 D TITLE: Environmental Monitoring Rept (per Tech Specs)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 3 3 PD3-1 PD 1 1 STANG( J 1 1 INTERNAL: NRR/DREP/PRPB11 2 2 G F 1 1 1 RGN3 DRSS/RPB 1 1 GN3 FILE 02 1 1 EXTERNAL: EGGG SIMPSON,F 2 2 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 13

0 0 r

Indiana Michigan Power ComPanY P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0806L Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 ANNUAL ENVIRONMENTAL OPERATING REPORT - 1991 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley April 24, 1992

Dear Dr. Murley:

Attached is the Donald C. Cook Nuclear Plant Annual Environmental Operating Report for the year 1991. 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 the Donald C.

Cook Nuclear Plant.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, E'8'.

E. Fitz atrick Vice President edg CC: D. H. Williams, Jr.

A. A. Blind - Bridgman NFEM Section Chief J. R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman gpP

-%if A W.~mQ 9204300315 911231 PDR ADOCK 05000315 R

~ .

4

nn 4B nvironmenta era in e January 1, Through December 31, 1 991 indiana & Michigan Electric Company Bridgman, Michigan Docket Nos. 50-31 5 & 50-31 6 License Nos. DPR-58 & DPR-74 92Q43QQ315

i 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 A.5 Cook Nuclear Plant Act 307 Remedial Status Report B. Environmental Monitoring-Herbicide Applications C ~ Macrofouler Monitoring and Treatment IV. Solid, Liquid, and Gaseous Radioactive Waste Treatment Systems V. Radiological Environmental Monitoring Program (REMP) 3 A. l Changes to the REMP A.2 Radiological Impact of Donald C. Cook Nuclear Plant Operations A.3 Tritium Migration in the Aquifer B. Land Use Census and Well Report VI. Conclusion

LIST OF APPENDICES

~Aendix Title I Non-Routine Report - 1991 Cook Nuclear Plant Act 307 Remedial Status Report Environmental Evaluation - 1991 IV Herbicide Application Report - 1991 Macrofouler Monitoring Program - 1991 VI Annual Report: Radiological Environmental Monitoring Program - 1991 Radiological Environmental Monitoring Program Summary - 1991 Data Tables Analytical Procedures Synopsis Summary of EPA Interlaboratory Comparisons REMP Sampling and Analytical Exceptions Land Use Surveys Summary of the Preoperational Radiological Monitoring Program Summary of the Blind Duplicate Sample Program Summary of the Spike and Blank Sample Program TLD Quality Control Program VII A Summary of the Evaluation of Tritium Migration in the Aquifer of the Cook Nuclear Plant and Surrounding Communities

1 ~

INTRODUCTION Technical Specification Section 6.9.1.6 and Appendix B, Part II, Section 5.4.1 require that an annual report be submitted to the Nuclear Regulatory Commission which details the results and findings of ongoing environmental radiological and non-radiological surveillance programs. 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, 1991 through December 31, 1991.

During 1991, based on the monthly operating reports for Unit 1 and Unit 2, the annual gross electrical generation, average unit service factors and capacity factors were:

Parameter Unit 1 Unit 2 Gross Electrical Generation (MwH) 7,614,530 8,481,310 Unit Service Factor (%) 85.9 91.5 Unit Capacity Factor - MDC* Net (8) 83.2 85.7

• Maximum Dependable Capacity II. CHANGES TO THE ENVIRONMENTAL TECHNICAL SPECIFICATIONS There were no environmental Technical Specification changes in 1991.

III. NON-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT A.l Plant Design and Operation During 1991 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 construction activities during the reporting period which required environmental assessments. In all cases, it was concluded that there were no significant adverse environmental impacts. Copies of the environmental evaluations are located in Appendix III of this report.

A.2 Non-Routine Reports A summary of the 1991 non-routine events, including corrective actions, is located in Appendix I of this report.

A.3 Environmental Protection Plan There were no instances of Environmental Protection Plan noncompliance in 1991.

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 construction activities during the reporting period which required environmental assessments. In all cases, it was concluded that there were no significant adverse environmental impacts. Copies of the environmental evaluations are located in Appendix III of this report.

A.5 Cook Nuclear Plant Act 307 Remedial Status Report An underground fuel oil storage tank release status report was sent to the Michigan Department of Natural Resources. A copy of this report is located in Appendix II.

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 comparison with preoperational studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation "on the environment.

Herbicide applications are t'e 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 1991 herbicide applications is contained in Appendix IV 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 Treatment Macrofouler studies and activities during 1991, are discussed in Appendix V of this report.

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 1991.

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

The objectives of the operational radiological environmental monitoring program are:

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

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

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

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

A.l Changes to the REMP There were no changes to the REMP during 1991.

A.2 Radiological Impact of Donald C. Cook Nuclear Plant Operations This report summarizes the collection and analysis of various environmental sample media in 1991 for the Radiological Environmental Monitoring Program for the Donald C. Cook Nuclear Plant.

Analyses of sample media suggest that there were no discernable impacts associated with operation of the Donald C. Cook Nuclear Plant on the environment. The analyses of air particulate filters, charcoal cartridges, direct radiation by thermoluminescent dosimeters, samples of

fish, water, milk and sediment 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 Donald C. Cook Nuclear Plant operations'owever, the associated aquifer does not provide a direct dose pathway to man.

A.3 Tritium Migration in the Aquifer An evaluation of tritium migration in the aquifer of the Donald C. Cook Nuclear Plant and surrounding communities was performed. It was concluded that any offsite impact is minimized and there is no threat to the safety and welfare of the public. The summary of this report is in Appendix VII.

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 1991 Land Use Census. A further discussion of the Land Use Census can be found in Appendix VI (F) of this report.

VI. CONCLUSION Based upon the results of the radiological environmental monitoring program and the radioactive effluent release reports for the 1991 reporting year, it can be concluded that there were no adverse affects to the environment or to the general public due to the operation of the Donald C. Cook Nuclear Plant.

APPENDIX I NON-ROUTINE REPORTS 1991

1991 NON-ROUTINE REPORTS VENT CORRECTIVE ACTION February 20 and 21, 1991 Turbine Room Sump discharge was Discharges from the sump were not monitored for pH on three manually sampled for pH until the occasions, due to an inoperable meter was repaired and placed pH meter. back into service.

April 26 to May 5, 1991 An estimated 860 gallons of The leaking heat exchanger was lubricating oil was discharged to isolated and plugged. The heat Lake Michigan. exchanger has since been replaced.

June .

3, 7, 8 and 10, 1991 Turbine Room Sump pH monitoring No corrective action possible was performed but not available the strip chart paper was for reporting. inadvertently discarded when the meter was replaced by a new unit.

July 1 through 5, 1991 The NPDES Permit limit. for heat Unit power was reduced to bring addition to Lake Michigan was the heat addition within permit exceeded. limits. Administrative controls were established to ensure thermal discharge calculations are performed promptly and unit operation necessary.

is reduced if July 4, 1991 Turbine Room Sump discharge was not monitored for The pH meter was cleared and pH while the meter was valved out valved into service. Engineering of service. measures were taken to reduce the potential for clogging or unintentional closure of the valve.

November 29 to December 2, 1991 Sodium nitrite and glutaraldehyde The leaking heat exchanger was were discharged to Lake Michigan isolated and repaired. It will be when a heat exchanger failed. inspected for integrity in 1992.

Beginning December 5, 1991 Diving ducks were collected in See attached correspondence dated the circulating water system January 3, 1992.

screenwash baskets.

Page 1

Indiana Michigan Power Company P.O, Box 16631 Co/umbus, OH 43216 INDIANA NICHIGiAN POWER AEP:NRC:1171 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENT APPROXIMATELY 400 DIVING DUCKS COLLECTED IN THE CIRCULATING WATER SYSTEM SCREENWASH BASKETS U. S. Nuclear Regulatory Commission "

Attn: Document Control Desk Washington, D. C. 20555 January 3, 1992 Gentlemen:

The purpose of this report is to inform you that as of December 19, 1991 approximately 400 diving ducks (lesser and great scaups) were collected in the circulatin= water system screenw baskets at Cook Nuclear Plant. This event constitutes an "Unusual o Important Environmental Event" per Cook Nuclear Plant Technical Specifications (T/Ss) Appendix B, Paragraphs 4.1 and 5.4.2. As such, a verbal notification was made to Nuclear Regulatory Commission (NRC)

Resident Inspector, David Passehl, and to the Michigan Department of Natural Resources (MDNR) on December 5, 1991. In addition, Cook Nuclear Plant T/Ss stipulate that a written report to the NRC is due within 30 days of occurrence. As such, we are submitting the attached report.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature of the undersigned.

Sincerely, E. E. Fitzpatrick Vice President tow Attachment

Document Control Desk AEP:NRC:1171 CC: D. H. Williams, Jr.

A. A. Blind - Bridgman A. B. Davis, Region III P. A..Barrett B. F. Henderson R. F. Kroeger B. Walters - Ft. Wayne NRC Resident Inspector T. Colburn - NRC J. G. Keppler J. R. Padgett G. Charnoff D. Hahn ANI Library INPO B. A. Svensson

Document Control Desk bc: S. J. Brewer/J. B. Kingseed/D. F. Walker/R. A. Gree M. L. Horvath - Bridgman - w/o attachment J. J. Markowsky J. B. Shinnock - w/o attachment W. G. Smith, Jr.

S. H. Steinhart/S. P. Hodge AEP:NRC:1171 DC-N-6015.1

Attachment 1 to AEP:NRC:1171 Page 1 Re ort of U usual or Im ortant E vironmental Event Conditions Prior to Occurrence Unit 1 and 2 in Mode 1 (Power Operation) at 100$ power.

Descri tion of Event On December 5, 1991, lesser and greater scaups it was noted that approximately 90 to 100 dead (diving ducks) had been collected in the screenhouse fish baskets (EIIS/NN-SCN). It was found that a zebra mussel population, which provided an abundant food supply for the ducks, had been established on the circulating water intake structures and surrounding rip rap. The ducks became caught up in the intake water flow while diving to feed on the zebra mussels.

Cause of Event The event was caused by the abundant food supply and warm water environment provided by the circulating water discharge. As ducks dove down to feed on the zebra mussels, they became caught up in the circulating water intake flow. The presence of zebra mussels in the digestive tract of the ducks was verified by dissection.

It should be noted that this is the first occurrence of this type and is related to the fact that the past summer was the first season of major zebra mussel infestation.

A factor contributing to the event was the closure of the circulating water intake shutoff valve (12-WMO-30) for repair work. This reduced the circulating water intake pathway from three sixteen foot intake pipes to two sixteen foot pipes, resulting in an increase in the flow velocity from the other two intake pipes.

Anal sis of Event This event is considered reportable pursuant to Technical Specification Appendix B, paragraphs 4.1 and 5.4.2 as an unusual or important environmental event which indicates or could result in a significant environmental impact related to plant operation.

In response to the event, one of the Nuclear Regulatory Commission's resident inspectors at Cook Nuclear Plant, David Passehl, was verbally notified on December 5, 1991. Other agencies notified include the Michigan Department of Natural Resources (MDNR), and the US Department of Fish and Wildlife (DFW). Both the MDNR and the DFW responded to the site to retrieve duck remains for research purposes. In addition, the DFW evaluated the site for a possible observation station.

Attachment 1 to AEP:NRC:1171 Page In the summer months, the combined numbers of lesser and greater scaups form a population larger than any other species of duck in North America, with the exception of the mallard. Frank C. Bellrose states in his book Ducks Geese and Swans of North America that the average population of the scaups is about 7,415,000. The total number of ducks recovered from the screenhouse fish baskets was 400, representing 0.00545% of the total scaup population. Consequently, the effect of this event on the scaup population has been negligible.

Corrective Action Several interim actions have been taken to discourage ducks from populating the area. These measures include chasing the ducks with a boat, firing blank shells at the ducks, and locating rafts and predator-eye balloons at the circulating water intake structures. In addition, to reduce flow rates at the intake structure screens, circulating water pump 821 was removed from service on December 9, 1991 and 12-WMO-30 was returned to its fully open position on December 13, 1991.

Since these measures have been taken, a dramatic decrease has been noted in duck impingement. No ducks have been found in the fis baskets since 12/15/91.

As a more permanent solution to prevent recurrence, the intake structures will be thoroughly hydrolazed during the 1992 refueling outages to remove the zebra mussels. This should prevent the ducks from accumulating at the intake structures. The effectiveness of hydrolazing the intake structures will be evaluated to determine whether it is necessary to take additional measures to prevent recurrence of this problem.

Failed Com onent Identification None.

Previous Simila Events None.

APPENDIX II COOK NUCLEAR PLANT ACT 307 REMEDIAL STATUS REPORT

IIIUIOllcl IllIVIII'Jjdll Power Company One Summn Square P.O. Box 60 Fort Wayne. IN 46801 219 425 2111 INDMNA MICHIGAN Lorraine Pockrandt POWER Environmental Response Division Michigan Department of Natural Resources 621 N. 10th Street Plainwell, MZ 49080 November 14, 1991

Dear Ms. Pockrandt:

RE: Cook Nuclear Plant Act 307 Remedial Status Report On August 28, 1991, Pat Crowley sent an information request letter to Diane Fitzgerald, Environmental Supervisor at the Zndiana Michigan Power Company (Z&M) Cook Nuclear Plant regarding the underground fuel oil storage tank release which occurred during the mid-1970's. We understand that you have recently assumed the duties of Ms. Crowley as they relate to this issue and, therefore, we are responding directly to you.

Each of Ms. Crowley's six items noted in her letter are addressed in the following enclosures:

1. "Status Report for the Mid 1970's Fuel Oil Release at the Cook Nuclear Plant"

• American Environmental Services'Subsurface Fuel Oil Contamination Assessment and Demonstration Recovery Technology" Z6M's voluntary remedial actions have been effective and will continue as described in the status report. We would be glad to answer any questions you might have either in a meeting or by telephone at your convenience. Peel free to call me at (219) 425-2118 or Dave Shipe at (219) 425-2123.

Very truly yours, Donald L. Baker Environmental Affairs Director DLB/sdb/009 Attachments

• This report is not included in the Annual Environmental Operating Report. However, it can be made available upon request.

wells was left over from the auxiliary oil tank system release.

The results of this assessment are included in their final report which is attached.

The contaminated area in the vicinity of the auxiliary boiler l tanks was selected for the operation of a small scale, demonstration oil recovery system. The system was designed to depress the water table, recover free product, and treat the discharge for free, emulsified and dissolved product. An NPDES discharge permit w-s obtained from the Michigan DNR to operate the system. The small amount of free and dissolved product within the depression cone was removed within a short time after operation began on 9/20/89. The system continued to operate for two months but did not affect .the isolated pocket of free product by RP Nell

¹5 since it was outside the depression cone. AES recommended recovering the free product in this well by using a narrow well, pneumatic pump.

AES also investigated fuel oil contamination of the beach area.

Soil samples were collected at 20 locations and were analyzed for oil and grease by an independent lab. A contamination plume approximately 40 feet wide was identified in the area west of RP Well ¹4 that extended west just beyond the second sheet piling wall. The contamination consisted of oil saturated soil close to the east wall with no noticeable free product present. The plume ended. approximately 70 feet east of the Lake Michigan water line.

AES concluded that this was old oil.

Recent monitoring and remediation efforts have consiste sampling and analysis of well water and continued bailing of ee product from RP Well ¹5. The most recent well water analysis results are attached for your review. The results indicate a continued degradation of the oil as shown by reduced BTX concentrations in Recovery Well samples when compared to 1989 data from the AES report. In addition, there are no traces of free product in any of the wells except RP Well ¹5 and Dry Well ¹2.

Only an oil sheen remains in the dry well.

Soil contamination levels range from isolated pockets of oil saturated soil to relatively clean soil due to remediation efforts and natural degradation. The soil gas maps indicate that the majority of the area has petroleum hydrocarbon soil gas levels below 10 ppm.

Remediation and Monitorin Goals The company has assessed the historical aspects of the spill, remediation progress, and the current status of the fuel oil contamination. AES's report recommendations were also considered when developing our future course of action. The following actions were determined to be essential:

November 14, 1991 Lorraine Pockrandt Page 2 bc: A. J. Ahern/T. E. Webb Status Report Attachment only A. A. Blind II M. Fitzgerald/R. Beem D E. Heydlauff ~I D W. Kemp/K. D. Mack M. R. Robida/C. E. Hawk .

W E. Walters/D. A. Shipe

STATUS REPORT FOR THE MID 1970's FUEL OIL RELEASE AT THE COOK NUCLEAR PLANT November 14, 1991 Site Descri tion The Cook Nuclear Plant is located three miles north of Bridgman, Michigan on the shores of Lake Michigan. The plant was placed on the Michigan Act 307 list of contaminated sites due to tho release of fuel oil to subsurface soils in the mid 1970's. The fuel oil tank system is located on the west side of the plant within the Protected Area (fenced security zone). A detailed map of the site is attached to the back of the American Environmental Services Co.,

Inc. (AES) report which will be discussed later. The tanks are identified in the report as Auxiliary Boiler Fuel Oil Storage Tanks, but may also be identified as heating boiler tanks on drawings and in correspondence.

Approximately 50 feet west of the tanks is a sheet piling wall which separates the plant from the Lake Michigan beach area. A second, parallel sheet piling wall is located about 45 feet west of the first wall. The Service and Turbine Buildings border the tank site on the north and east sides, respectively. The four tanks are connected to form two sets, an east set and a west set. The pipes for the two sets of underground tanks were remotely located fill on the east side of the plant in the mid 1970's and were relocated adjacent to the tanks to reduce the likelihood of fu r overfills. Two vent pipes with an overflow catch basin are o located adjacent to the tanks.

Site Histor The oil release was discovered in September 1976 by a diver who found oil in a water intake tunnel manway. Approximately 130 gallons of oil were removed from the manway and core borings were immediately initiated to determine the boundaries of the contamination. The Auxiliary Boiler Fuel Oil Storage Tank system was determined to be the source of the release. An oil plume extended west to the sheet piling wall and then south along the wall possibly as far as RP Well ¹6. The quantity of oil released was not known since it apparently occurred over several years during tank filling and oil transfer operations.

Recovery of free product continued by digging a recovery trench parallel and just east of the first sheet piling wall. Oil was removed as it accumulated in the trench. The trench was located between Dry Wells ¹1 and ¹2. The two dry wells were constructed to continue recovery operations once the majority of oil had been recovered and the trench was backfilled. Oil has also been removed from RP Well ¹5 since the release.

Oil recovery efforts have been successful in limiting oil migration in the groundwater. The amount of oil recovered has continued to decline over the years. To date, approximately 8, 000 gallons of oil have been recovered from the site. Currently, oil is being bailed from RP Well <<5, the only known area of recoverable oil.

Approximately 3 gallons per month are being removed from the well by this method. While excavating for system repair and oil recovery, an undetermined quantity of contaminated soil was removed from the site; Several techniques were employed to determine the cause o". the oil release. Initially, a static fluid level test was performed on the auxiliary boiler oil tank system. The tests indicated a manhole cover and a fill line gasket located underground were tw sources of the release which were subsequently repaired. Follow-up hydrostatic testing conducted in 1979, 1980 and every two years since then has indicated the tanks are leak-free as defined by NFPA 329. The west set of tanks was also visually inspected in 1979 and was found to be in good condition.

The point where the tank vent pipes project through the bottom of the overflow catch basin was also found to be leaking. Whenever overfilling the tanks occurred, leakage from the vent catch basin may have contributed to the problem. The tanks were overfilled when trucks were off-loaded at the remote location on the east side of the plant and when oil was recirculated to a full set of tanks.

To preclude recurrence, the leak was sealed, fill lines were relocated next to the tanks tto ensure closer monitoring and formal procedures operations.

were issued to direct filling and recirculating Following our initial report submitted to the Michigan Department of Natural Resources in October 1976, the company has kept the DNR informed of the status of our remediation efforts. Follow-up reports were submitted which described our clean-up efforts and tank testing results. In 1981, the Michigan DNR agreed to the company's plan to continue monitoring the site and the collecting any recoverable oil. The Michigan DNR recommended the Cook Plant for inclusion on Michigan's Act 307 list of pollution sites in 1984 due to this oil release.

In 1987, the company formed a task force to identify the extent of the oil contamination onsite and to research alternatives for remediating contaminated areas. As a result of the task force's recommendations, the company employed the services of AES. In May 1989, AES began using soil gas survey techniques and constructing observation wells (OW) in potentially contaminated areas as part of a hydrogeological assessment. The goal was to determine the location, quantity and thickness of any free product on site.

Samples from RP Wells g4, 5 and 6 and Dry Wells t1 and 2 were also cross-matched with fuel oil standards to determine the type of oil and its relative age. The well samples were identified as fuel oil but were obviously aged oils based on the loss of the more volatile fuel oil components over time. AES concluded that the oil in the

~ accelerate the removal of free product from RP Nell P5 0 continue monitoring wells in the area to demonstrate the effectiveness of our remediation efforts

~ develop a beach monitoring program to trend the degradation and/or migration of oil contamination

~ continue to leak-test the Auxiliary Boiler Fuel Oil Storage Tanks to ensure that additional releases do not occur Our proposed specific actions and schedule are as follows:

Establish a beach monitoring program incorporating a formal sampling grid, which will be used to track the degradation and/or migration of oil, and from which we can determine what actions need to be taken to remediate the area. Establish contracts for needed analytical and sample collection support.

Date: Sampling Plan: Completed Initial sample collection: 12/1/91

2. Install a small diameter oil recovery pumping system in RP Nell g5.

Date: Target operational date is 12/1/91

3. Continue quarterly groundwater monitoring of selected onsite wells. Results will be used to build a data base to demonstrate the effectiveness of past remediation work.

Date: Ongoing Use the improved tank leak testing technology developed by Tanknology Corporation to again verify the Auxiliary Boiler Fuel Oil Storage Tanks are leak free. This sytem was tested on our underground waste oil tank and found to be very effective.

Date: Second Quarter 1992 Conclusion From the time of the spill discovery in 1976 to the present, the company has taken positive steps to deal with the oil release.

Over the years, we communicated verbally and in writing with the Michigan DNR on the nature of the release and progress in remediation. Oil collection efforts have continued and achieve an ongoing reduction in the amount of product retrieved. The he boiler oil tank system was repaired early in the process an s

integrity has been demonstrated several times since. The company actively sought to accelerate oil collection with the 1989 demonstration project, which indicated that recoverable product has

~ ~

diminished significantly and the remainder appears to be localized.

~ ~

The past responses together with our future course of action will ensure =ontinued remediation and monitoring of the site. We believe that our voluntary action to remediate the site is a demonstration of our commitment to the long term environmental protection of the area.

APPENDIX III ENVIRONMENTAL EVALUATION REPORTS 1991

DONALD C. COOK NUCLEAR PLANT ENVIRONMENTAL EVALUATION FOR THE CLAM-TROL ADDITION HEATUP PROCEDURE March 11, 1991 r

Prepared by:

Steven L. Colvis Date 3')~i Radiological Support Section Date C

Approved by:

Dane R. Williams, Manager Da Radiological Support Section Concurred by:

Diane Fi aid Da e Donald . ook Environmental Coordinator 1

TABLE OF CONTENTS Title Page Table of Contents I. Executive Summary II. Purpose of Environmental Evaluation III. Description of Activity IV. Description of Affected Area A. Location and Size B. Geology and Soils C. Groundwater and Surface Water D. Biological Resources

1. Terrestrial Ecology Aquatic Ecology E. Cultural Resources

1. Land Use Archaeology 3.'ater Use V. Environmental Impacts A. Geology and Soils B. Surface and Groundwater C. Biological Resources

1. Terrestrial Ecology

2. Aquatic Ecology D. Cultural Resources

1. Land Use

2. Archaeology E. Noise 2

Table of Contents (cont'd.)

VI. Alternatives to the Proposed Activity VII. Summary Cost-Benefit Analysis VIII. Environmental Controls IX. Conclusion X. References 3

Executive Summar Zebra mussels (Dreissna polymorpha), a known macro-biofouler, were discovered at the Cook Nuclear Plant in July 1990. Without treatment, the mussel population is expected to multiply in 1991 to the point as to cause unacceptable blockage of the Cook Nuclear Plant intake systems.

To preclude such an event from occurring, a proprietary molluscicide (Betz Clam-Trol) is to be added to the affected systems. Experience has shown that the chemical is not effective unless the water temperature is above 60 F.

Therefore, the temperature of the circulating water discharge is to be increased to enhance the effectiveness of the process (per procedure 12 OHP 4021.057.008, Operation of the Circulating Water System to Increase Forebay Temperature).

This environmental evaluation was conducted to determine if an increase in discharge temperature would constitute an unreviewed environmental question or a change to the Environmental Protection Plan.

Based on the research conducted, it is concluded that the heatup activities do not constitute an unreviewed environmental question or a change to the Environmental Protection Plan.

Based on this conclusion, no NRC approval is required prior to beginning the program.

4

II. Pu ose of the Environmental Evaluation The purpose of this environmental evaluation is to determine the proposed heatup procedure constitutes an unreviewed safety if question as defined by Part II, Section 3.1 of the Donald C.

Cook Nuclear Plant Technical Appendix B Technical Specifications. The procedure does not involve a change to the Environmental Protection Plan.

III. Descri tion of Activit Indiana Michigan Power Company proposes to artificially increase the temperature of the circulating water system. This heatup is being performed to increase the effectiveness of the Clam-trol chemical addition. The ambient water temperature is not sufficient to allow the Clam-trol to effectively kill the zebra mussel population now infesting the Cook Nuclear Plant systems.

IV. Descri tion of the Affected Area A. Location and Size The area affected by the increas'ed temperature program is shown on Attachment 1. This drawing was taken from a memo issued by the Environmental Engineering Division. Only the plume area in Lake Michigan will be affected.

B. Geolo and Soils No effect will be seen on the geology and soils, since the only affected area is in Lake Michigan.

C. Groundwater and Surface Water No effect will be seen on groundwater and surface water, since the plume is only exiting to Lake Michigan.

D. Biolo ical Resources

1. Terrestrial Ecolo No effect on terrestrial ecology will be seen because the only affected area is Lake Michigan.

2. A uatic Ecolo The main concern with this program is the possibility of killing large numbers of fish due to the change in temperatures. Based on the analysis provided by the AEPSC Environmental Division in their March 4, 1991 memo (attached), no fish kills of any significance should occur if the guidelines provided are followed.

Procedure 12 OHP 4021.057.008 does follow the guidelines delineated in this memo.

5

The memo mentions the possibility of a large scale fish kill if one of the Units is tripped. However, based on the operating history of the plant and discussions with Nuclear Safety & Licensing, concluded that a trip is not considered to be a it is likely occurrence. Therefore, no significant fish kill is probable based on the analysis performed.

E. Cultural Resources

1. Land Use No impact on the use of land is anticipated since the area affected only includes Lake Michigan.

Only the area of the thermal plume in Lake Michigan will be affected; therefore, no disturbances to any possible archaeological finds are possible.

3. Water Use As stated earlier, the only possible impact anticipated is on the fish population. Based on the previously referenced analysis, no impact is expected Environmental Im acts Lakes'.

A. Geolo and Soils No impact is expected, since the affected area is restricted to the Surface and Groundwater No impact is expected, since the affected area is restricted to the Lake.

C. Biolo ical Resources

1. Terrestrial Ecolo No impact is expected, since the affected area is restricted to the Lake.

2. A uatic Ecolo As stated previously, no significant effect to the aquatic ecological system is expected.

6

D. Cultural Resources

1. Land Use No effect is expected on any land use.

No effect is expected on any archaeological finds.

E. Noise The increased temperature program should not provide any increased noise levels to the area.

VI. Alternatives to the Pro osed Activit Four alternatives were considered.

The first alternative was to proceed with the Clam-trol addition without the associated heatup of the water. However, experience has shown that Clam-trol additions at low temperatures are not effective in killing the mussel population.

The second alternative considered was to delay the Clam-trol addition until the ambient temperature of the water reaches'a point where the Clam-trol addition would be effective. Zebia mussel reproduction occurs at about the same water temperature as is needed for Clam-Trol effectiveness. Delaying the Clam-Trol application (eradication strategy) until this time would mean that the control strategy (use of low level chlorine/bromine) must immediately follow to prevent a reestablishment of a zebra mussel population. This cannot practicably be done, as both the eradication and control strategies require separate and demanding resource outlays, equipment installations, etc. Therefore, this alternative was rej ected because it poses too great a resource outlay.

Chlorine additions were also considered as a measure to eliminate the mussels. However, there is a major concern regarding stress corrosion cracking that is associated with large chlorine infusions into a system. Also, the current Cook Nuclear Plant National Pollutant Discharge Elimination System (NPDES) permit does allow discharges of chlorine at the concentrations required for eradication of adult mussels, but the plant is not equipped with dechlorination equipment.

Therefore, because of the concern for the integrity of the plant systems and the inability to dechlorinate to discharge permit requirement levels, this option is not being pursued presently.

7

The final option considered was to do nothing. As with option 2, there is a very real danger of the mussel population increasing in size to the point that plant water systems (such as the Essential Service Water System) could become blocked.

Therefore, this option will not be pursued.

VII. Summar Cost-Benefit Anal sis The environmental impact of the heatup program will be minimal.

The main concern is with the likelihood of killing a significant number of fish. Using the environmental controls described below, this is highly unlikely. The benefit of the continued operation of Cook Nuclear Plant far outweighs the small potential for a large scale fish kill.

VIII. Environmental Controls The following controls are to be implemented during the heatup procedure at Cook Nuclear Plant. These controls are designed to minimize the impact to the environment from the heatup process and are contained in Procedure 12 OHP 4021.057.008.

1. The plant is to be operated at or below the NPDES-permitted discharge limit of 15.5E+09 BTU/hr. This limit will not be exceeded under the plant's forebay heat-up plan.

2. All seven of the circulating water pumps should be operated at maximum pumping capacity. This will ensure that the water velocity of the thermal discharge is high enough to exceed the swimming speeds of fish. This, in turn, will exclude them from the warmest portion of the plume.

3. The temperature of the discharge should be increased (and subsequently decreased) at a gradual rate of no more than ll F/24 hr and no more than 0.5 F/hr. The analyses performed by the Environmental Division also assume that the maximum discharge temperature is increased to about 82 F. The analysis also assumes that the variations in the ambient water temperatures could push the discharge temperatures as high as 87 F.

4. The water temperatures are to be held at the maximum only as long as absolutely required for the Clam-trol process to be completed effectively. The higher temperatures will create a larger thermal plume. This increases the probability that fish will become acclimated to the increased temperatures, which increases the likelihood of problems occurring.

The increased temperature program will not cause Cook Nuclear Plant to exceed the limits of our NPDES.permit. However, a notice is to be sent to the Michigan Department of Natural Resources to inform them of our treatment plans.

8

IX. Conclusion American Electric Power Service Corporation concludes that the above environmental controls are followed, the proposed if heatup program will not cause a significant environmental impact. Based upon this determination, it is concluded that the activity does not constitute an unreviewed environmental question. Therefore, it will not be necessary to obtain approval from the Nuclear Regulatory Commission prior to the start of the process.

This Environmental Evaluation shall be included as part of the 1991 Annual Environmental Operating Report.

X. References Memo, T. E. Webb to S. J . Brewer, et. al. dated March 4, 1991 9

INDIANA& MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT ENVIROMENTAL EVALUATION FOR THE INSTALLATIONOF A MAKE-UP FLINT NNOTNALITATION NYNTI!M 12-PM-0818 Prepared by: W( + P7 C~c /2 gr e' Date

/ /z Approved by: r~ p/

adiological Support Section Date Concurred by: Ja z~ g)

D.C. Coo onmental Coordinator Date

TABLE OF CONTENTS Executive Summary Purpose of the Environmental Evaluation Decription of the Proposed Activity Description of the AQ'ected Area Environmental Impacts Alternatives to the Proposed Activity Summary Cost-Benefit Analysis Environmental Controls Conclusion References

Executive Summary Proposed modiQcations to Donald C. Cook Nuclear Plant require this Environmental Evaluation due to construction of a one hundred and ten thousand gallon waste neutralization tank, the transposition of a waste stream to an

=

alternative point of discharge and necessary NPDES permit modiQcation dictated thereby. Waste water &om the make-up plant demiaeralizers willbe neutralized and diverted from the present pathway into the station absorption Qeld process waste pond to a point directly into the circulating water discharge tunnel. 'Hds configuration will elimiaate the turbine room sump corrosion concern and, in addition, be of a direct beneQt to the station absorption Qeldprocess waste pond loading as well as the hydrogeological aspects of that immediate area. A waste characterization study of the demineralizer eKuent is being conducted and:he results will be presented to the Michigan Department of Natural Resources.

Considering the large volume of water in the circulating water discharge tunnel into which the demineralizer waste water will be expelled, the proposed activity should not present a signiGcant increase in an adverse environmental impact previously evaluated in the FinalEnvironmental Statement. Utilizationofthe proposed activity is contingent upon approval of all required permits by the State of Michigan and other regulatory bodies.

Purpose of this Environmental Evaluation Pursuant to Section 3.1 of Appendix B of the Donald C. Cook Nuclear Plants Unit Nos. 1 and 2 Facility Operating License, before engaging in any changes in the Donald C. Cook design. or operation or performing any test or experiment, it must be determined if the proposed activity has the potential for affecting the environment. In accordance with Radiological Support Section Procedure RS-34, the purpose of this environmental evaluation is to determine ifthe proposed activity deQned in 12-PM-818 involves an unreviewed environmental question which may signiQcantly iacrease any adverse environmental impact previously evaluated in the Final Environmental Statement.

Description of the Proposed Activity Described in 12-PM-818 is the installation of a system to receive and neutralize the acid and caustic wastes Rom the make-up plant regeneration process prior to these wastes being discharged. Currently, the waste stream is causing a consistent decimation of the turbine room sump resultiag in Sequent and costly repair. The system willconsist of a small intermediate sump tank to accept the waste drainage and pump it to a large holding tank. The liquidwillbe neutralized ia the large tank with appropriate acid or caustic solutions. Subsequently, the Qnal disposition of this waste stream willbe to Lake Michigan via the Unit1 or Unit2 circulating water system.

IV. Description of the Affected Area The areas that are directly affected by the proposed activity are Lake Michigan, station absorption Qeld process waste pond, and a small area on the plant where the proposed tank is to be installed (see attached).

Lake Michigan is the third largest of the Great Lakes with an area of 22,400 square miles and a volume of 173 trillioncubic feet. The southern basin of the lake has a mean depth of approximately 276 feet and a maximum depth of 540 feet. The thirty foot depth contour, which is the outer limitof the beach water zone, lies approximately one half mile offshore. Process waste streams currently discharged to the lake derive Rom the circulating water system, the liquidradwaste processing system, the heating boiler blowdown, and the steam generator blowdown treatment system.

The station absorption Qeldprocess waste pond has an approximate gross area of 31,100 square feet with depths of 7 to 10 feet inthe depressions. The pond is located about 1000 feet from the shoreline of Lake Michigan (see attached). The site lies on former dunelands on the southwest Qank of the Michigan Basin and within the Grand Marais Embayment, formerly a huge bay coextensive with the meltwaters which formed Lake Chicago. Potable water supplies exist in unconsolidated Pleistocene drift deposits which lie at depths of 19 to 54 feet.

These sediments are Qne dune and lake sands which are underlain by thick impermeable clays with occasional sand or gravel lenses and a shale bedro The water table gradient is nearly Qatwith ground water Qow averaging one to feet per day in the direction of Lake Michigan.

An area within the protected area, south of the station pump house willbe the proposed site of a one hundred and ten thousand gallon holding and neutralization tank The structure will require a poured, concrete foundation approximately twenty Qve feet in diameter and situated""'6n'ground that is in the vicinity of an access road, existing structures and trailers. Excavation for a foundation should not penetrate the water table and no other virgin aquatic or terrestrial ecologies will be perturbated.

V. Environmental Impacts During normal operation, it is estimated that a maximum of approximately 3200 pounds per day of salts Rom the regeneration process will constitute the discharge. - These salts will contain about 80 percent sodium sulfate with the remainder of the ionic species originating from the constituencies of present day Lake Michigan water. The maximum concentration of the waste is estimated to be around 9600 milligrams per liter total dissolved solids. The daily volume of regeneration waste discharged to the turbine room sump is estimated at fo thousand gallons with a maximum daily volume of 1,000,000 gallons. Conside

l the proposed activity, directing the waste stream to the Unit or Unit2 circulating water discharge, which has a nominal Qow rate of 935,000 gallons per minute, will in effect diminish the waste stream concentration suKciently such that the chemical concentration of the circulating water is approximately the same as that of Lake Michigan.

The system design of the station absorption Geld process waste pond was developed on the basis of inQltration considering the topography of the speciGc area and the operational demands of the plant. The absorption Geld inventory includes two sanitary waste ponds in addition to the process waste pond.

Itis believed by some agencies that a ground water mounding phenomena exists beneath the absorption Geld site. Ground water monitoring wells have indicated elevated constituent concentrations of several parameters. Elimination of the make up plant regeneration process waste stream will greatly enhance the water quality of the absorption Geldand could remedy the concerns of offsite potentially contaminated water migration.

Though Lake Michigan will experience an environmental impact, the potential consequences presented by the regeneration waste willbe of lesser detriment if the waste is directed to this pathway.

The neutralization tank will be sited on an area that has previously been disturbed.

Construction of the tank willnot degrade the immediate ecology further.

Alternatives to the Proposed Activity 1

One option exists as an alternative to the proposed activity. Afterneutralization, the make up plant regeneration waste could be directed to the turbine building sump and succeedingly to the station absorption Qeldprocess waste pond. Inthis case ground water quality would continue to be a concern. To subsequently remedy the ground water concern may require the station to meet the speciQed eQluent limits for the station absorption Qeldprocess waste pond or to seek a variance permit contingent upon receiving deed restrictions and easements from neighboring property owners, in conjunction with a comprehensive hydrogeological site assessment of the ground water mounding.

Summa'ost-Benefit Analysis The Civil Engineering Department has calculated that approximately $ 1.4 million could be saved over the life of the plant by installing the neutralization system.

This is based on conservative estimates of the repair frequency and repair cost of the turbine room sump with and without the proposed neutralization system.

Redirection of the neutralized waste stream to the circulating water discharge will

represent a virtualno cost remedy to the station absorption Qeldprocess waste pond concern. Other viable solutions to this concern willdemand multi-dollar cost estimates.

VIII. Environmental Controls Utilization of the system installed in the proposed activity is strictly contingent upon approval of a revised NPDESpermitby the State of Michigan Department of Natural Resources since the constituencies of the circulating water discharge will be modiQed to some degree.

To mitigate the consequences of a neutralization tank rupture, a containment structure willbe erected around the tank site (see attached).

IX. Conclusion The proposed activity deQned in 12-PM-818 should not present a signiQcant increase in an adverse environmental impact previously evaluated in the Final Environmental Statement. The physical structure and location of the neutralization tank does not present a signiQcant environmental impact. By neutralizing and discharging the make-up plant regeneration waste to Lake Michigan, this system willeliminate the major source of the station absorption Qeldprocess waste p inventory. Therefore, the potential migration of these wastes to the ground w concurrent with the station absorption Qeldprocess waste pond willbe eliminated.

The general environmental impact to Lake Michigan willnot be profound and in considering the alternatives willbe the best option for presenting the least adverse inQuence to the environment.

It is concluded that the proposed activity does not involve an unreviewed environmental question. Consequently, approval by the NRC will not be necessary to initiatethe project.

X References Nuclear Operations Division Procedures, RS-34 Donald C. Cook Nuclear Plant Technical SpeciQcations, App. B Donald C. Cook Nuclear Plant Final Environmental Statement

INDIANA& MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT ENVIROMENTAL EVALUATION FOR THE NEW PROJECT ENGINEERING AND SITE DESIGN OFFICE BUILDING 12-PM-1159 Prepared by: ZL '+ ~ 1l-3~t Date u'.EM>~~~i.~~

r Approved by:

adiological Support Section Date Concurred by: // I//pg D.C. Coo onmental Coordinator Dat

TABLE OF CONTENTS Executive Summary II. Purpose of Environmental Evaluation III. Description of the Activityand Affected Area IV. Environmental Impacts VI. -Conclusions

Executive Summary This Environmental Evaluation was conducted to determine ifconstruction of the proposed new office building for the Project Engineering/Site Design Group constitutes an unreviewed environmental question pursuant to Part IISection 3.1 of the Donald C. Cook Nuclear Plant Appendix B, Environmental Technical Specifications.

The new office building is necessary to accommodate Project Engineering/Site Design Group personnel who are being displaced due to RFC-DC-12-3065, which requires dedicated fire protection tanks to be installed where the Project Engineering/Site Design Group is presently located.

The construction of the new building willhave minimal environmental impact due to locating the building in a previously disturbed area. Allexcavation will be minimal and take place in an existing gravel parking lot and roadway. The Michigan Department of Natural Resources has granted a permit so the building can be built in the CriticalDune area at the Cook Nuclear Plant.

Based on this Environmental Evaluation, itis concluded that the construction of the new office building does not constitute an unreviewed environmental question.

Therefore, it willnot be necessary to obtain approval from the Nuclear Regulatory Commission prior to the start of construction.

Purpose of the Environmental Evaluation The purpose of this Environmental Evaluation is to determine ifthe proposed new office building construction constitutes an unreviewed environmental question as defined by Part II, Section 3.1 of the Donald C. Cook Nuclear Plant Appendix B, Environmental Technical Specifications. The change does not involve a change in the Environmental Protection Plan.

Description of Activity and Affected Area Indiana Michigan Power Company proposes to construct a two-story office building at its Cook Nuclear Plant. The building willhouse Project Engineering Department and the Site Design Group personnel. Electricals'ervice, fireprotection, potable water, sewer connections and tele-communications are included in the environmental evaluation. The building is necessary because RFC-DC-12-3665. 9< 4 <

requires dedicated fire protection tanks to be installed where the Project Engineering Department and Site Design Group Building is presently located.

The proposed location of the New Project Engineering and Site Design Group shown on Attachment 1. The site is located next to the A-36 Steel Yard. Th proposed site had been used to store miscellaneous parts used on the plant site, as a roadway, and as a parking lot. The building willcover an area approximately 10,000 square feet. Itis a pre-fabricated building which willbe placed on 2 feet by 3 feet. deep concrete footers. The dimensions of the two story building are 60 feet by 153 feet (Attachment 2). Electrical service will be connected via two oil-free 167 KVtransformers. All sewage, fire protection, and potable water connections willbe made via underground connections in the existing gravel parking lot. There will be minimal impact to the geological, hydrological, biological and cultural resources associated with the underground connections.

IV. Environmental Impacts e 1 ical and oils The building site was previously used as a parking lot, storage area, and roadway, therefore, storage compaction of the soils beneath the area has already occurred. Since the building willbe placed on concrete pads, no further compaction willtake place. In addition, all excavation for service connections to the building will be done in the existing roadway. Therefor there willbe no impact to the geological formations or soils in the area the building.

B.. urface Wa er an r n w er The building willnot have an impact on either the water table or surface water in the area of the building.

C. Bi 1 ic 1Re o rce There willbe no impacts to the terrestrial ecology as a result of the upgrade because no habitat willbe removed and the area is already subjected to the intrusion of man and machinery, therefore animals residing in the area adjacent to the construction should not be disturbed by the increased activity. The approved Dunes Permit has been received from the Michigan Department of Natural Resources with limitations and conditions which apply to construction (Attachm'ent 3).

D. I r IR rc There willbe no change in land use as a result of the proposed building.

No archaeological resources are known to exist in the area based on previous construction excavations.

E. ~Ni e Noise levels generated by construction are considered to be minimal due to prefabrication, and only a temporary impact due to the short construction time.

V. Environmental Controls The following environmental controls shall be utilized to minimize impact to the environmental resulting from the construction of the building. These environmental controls will be reviewed and enforced by Cook Nuclear Plant Environmental Section.

A. Construction of this building shall correspond to the site plan received by the DNR.

B. No construction equipment or materials shall impact the dune slopes east of the proposed site project site.

C. Alldisturbed areas shall be re-stabilized following project completion.

D. Excess excavated soil willbe deposited offsite in a legal manner and out of regulated critical dune areas or wetlands.

VI. Conclusions Through proper mitigation practices, as outlined in the Environmental Controls Section of this evaluation, it can be concluded that significant adverse environmental impact willnot result from the proposed construction.

It is further concluded that the construction of this building does not involve an unreviewed environmental question. Therefore, itwillnot be necessary to obtain approval from the Nuclear Regulatory Commission to construct the new office building.

However, it should be noted that this Environmental Evaluation shall be included as part of the 1991 Annual Environmental Operating Report.

tjw cc: DC-RS-7915

~Z WC+

~. e/zopf( l.. ~+cg ~yE.

~gb A.ci C',

L 0"

O OOI 7I~~4/

f~( /4

'"ffr ~>o I/fearg% kxyg~<ka ~

Ig) i eg"~4eIy 0~

a~Vf( / 0 II~ II I I

~

oo o PARR>a(I

/

o 4v gV L

+I%~

I EF~ 3r.-S (0

o. i ling

~c

~wg~R ~~4y (red~>S hq 7 ">N7<

Wq7S, I "57og"

~e r

'~s I4 ~

eAJyS Skj4PP e ooo

~ wtl tv Cg ~

~e STA'eT SW TSpaaa Sf+~~

ieS, 't p) C'64 7'biaI.

'btaRC Ieeiae Sell%

CR.Q TRAlol~

CL4TLL SIT% PCCS%%

I CCeeTROl. IhiCIr.

/ / AIR RKgEF'SL~%

>S7 l

st'veoR. T RtATtli<T z.~

I (55 I'D aMCRPT OFF <g4, lH&

sx TIE,LC

" (ear clRI ~QChhL CgoPC. t4oT W PARKlM sg, imehcT&D <~

c~%~ c.~ ~

r/

MICHIGANDEPARTMENT OF NATUIVL,RESOUR PE1VrKI'ndiana/Michigan Power Co. Permit No. 91-BR-275- SC Cook Nuclear Plant Date Issued OB/29/9" One Cook Place Extended Bridgman, Ml 49106 OB 29 92 Attn: John Carlson, Environmental Section Expires Under the provisions of:

[ ]The Shorelands Protection and Management Act, 1970 PA. 245 as amended

[X]Thc Sand Dunes Protectl" n and Management Act, 1989 P 4. 146 and 1989 P. A. 147, amending 1976 PW 222 Permission is hereby granted, based on permittee assurance of adherence to State requirements and permit o"ditions to: Construct, a 153' 60'emporary modular office building according to the attached plans and subject to the following conditions.

Property

Description:

County Berrien Township Lake Sect[on 6 proportp Tax No. 11 11 0005 0002 00 8 This permit ls granted under tke conditions and requlmments marked with an (x) below and limitations and conditions appearing on the attached sheet: und

[X] 1. This permit does not fulfillrequirements of other state and local construction regulations.

[X] 2. This permit expires 365 days after the Date Issuedo

[X] 3. Notification shall be provided to the Department by telephone 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to:

[X]commencingconstructlon Contact Steve Sutton at 517-$ 7$ -1950

[ ]commencing vegetation removal or grading activity

[ ] 4. Location of structure, including any septic tank and tile field must be feet or more landward of the blumlne on the date construction begins.

[X] 5. See attached sheetsfs) foi additional limitations and conditions.

Director, Department of Natural Resources By James G. Rlbbens, In C e Coastal Programs Unit Great Lakes Shorelands Section cc: Lowell Bruce, CEA Leslie Ha~Ps 7, -""D Richard Kading, BC=-

Plainwe'1 Distri '; Office, LNMD Interim form s/Ss

Endiana/Michigan Power Co.

Page 2 August 29'991 91-BR-275-C Additional limitations and conditions:

)xJ Construction of this 153' o0'uilding shall correspond to site plan received by the DNR on S/20/91 (Attachment 2 of 2) ~

LxJ No construction equipment or materials snail impact the dune slopes east of the proposed project site.

IxJ All disturbed areas shall be restabilized following project completion.

[xJ Excess excavated soil shall be deposited off-site in a legal manner and out of regulated critical dune areas or wetlands.

AUTHORITY GRANTcO BY THIS PERHIT IS SUBJECT TO THE FQ NING I.IHITATIONS:

A. Initiation of any work on the permi .ed project confirms the permittee's acceptance and agreement comply with all terms and conditions of this permit. Non-compliance with these terms and condition and/or the initiation of other regulated ac ivltles. not specifically authorized by this permit shall cause for the modification, suspension or revocation of this permit, in whole or in part. Further, Oeoartment of Natural Resources may initiate criminal and/or civil proceedings as may be deemed necess to correct project deficiencies to protect natural resource values, and secure compliance with statutes B. This permit shall be kept at the site of the work and available for inspection at el I times during duration ot the project cr until its cate ot expiration and authorizes representatives of the Oepartme to enter upon said property in crcer to Inspect project progress'.

This permit does not convey property rights In either real estate or material, nor does it authorize a injury to private property cr Invasion of public or private rights, nor does it waive the necessity seeking el I local permits or complying with other State statutes O. This permit s'nail not be assigned or transferred without the written approval of the ent Natural Resources.

In issuing this permit, the Oeoartment of Natural Resources has relied on the information and data >>I tne permittee has provided ln connection with the permit application It, subsequent to the issuance this permit, such Information and data prove to be false, Incomplete, or Inaccurate, .he Department modify, revoke, or suspend the permit, tn whole or in part, in accordance with the new information.

Authority granted by this permit does not waive permit requirements under the Soil Erosion Sedimentatlon Control Act (1972, P.A. 347).

DONAID C. COOK NUCLEAR PLANT ENVIRONMEPZAL EVAIIJATION

/ISIVEUM Pre~~ By:

H. W. J 2l Radiol 'cal Support Section Approved By: CPS 4C'.lzEF(~

D. R. Williams, Manager Radiological Support Section Concurred By:

(Safety Review Only) S.

S J. Brewer, 5 u (M~

Manager

~ S/n(Si SW Skvlfl Date Nuclear Safety & Licensing Concurred By: .5,27 D. M.

Envir Coordinator Donal . Cook Nuclear Plant

TABLE OF CXRZEÃZS I. Executive Summary II. Purpose of the Environmental Evaluation III. Description of the Activity IV. Description of the Affected Area A. Location and Size B. Geology and Soil C. Biological Resources

1. Terrestrial Ecology

2. Aquatic Ecology D. Cultural Resources

1. Land Use

2. Archaeology V. Environmental Impacts A. Geology and Soils B. Surface and Ground Water C. Biological Resources

1. Terrestrial Ecology

2. Aquatic Ecology D. Cultural Resources

1. Land Use

2. Archaeology E. Noise F. Dust VI. Environmental Controls A. Final Grading Plan B. Noise C. Dust D. Slash Disposal E. Environmental Stop Work Orders F. Permits VII. Conclusion

Executive Sundry We Donald C. Cook Nuclear Plant requires an on-site vehicle refueling station so that facility vehicles are assured a readily a~ible fuel supply at all times. In addition, the previously underground gasoline tank is several years old and presents a potent,ial problem with respect to leakage, thereby presenting a potentially significant environmental hazard. By EPA regulations, the Cook Plant has been required to remove or upgrade, by Decanber 1, 1990, the underground gasoline tank.

%he underground gasoline tank was removed from the Plant site on Septeaher 24, 1990 in compliance with EPA regulations. At the time of the removal of the underground gasoline tank, an above ground diesel fuel tank was also removed to be upgraded with a new above ground tank in an improved refueling facility.

thus the use of containerized above ground storage tanks in a curbed base slab will significantly reduce the potential for significant environmental impacts either from construction or operation over the replacement of the underground storage tank a new underground tank. Replacement of old underground 'ith tanks with new underground tanks, while not resulting in any additional enviroranental impact due to the construction activities, would impose a significant cost penalty due to the need to install additional monitoring devices as well as special type tanks in order to meet the current Environmental Protection Agency requirements for underground tank usage.

'Ihus the most cost effective, as well as environmentally benign, method of ensuring a readily available on-site fuel

~

supply for facility vehicles is the construction and use of containerized above ground diesel fuel and gasoline storage tanks/refueling island.

'lhis environmental evaluation was conducted to detexndae construction and utilization activities associated with a if the containerized above ground diesel fuel and gasoline storage tanks/refueling island would constitute an unreviewed envirornnental question pursuant to Part II, Section 3.1 of Appendix B to the Donald C. Cook Nuclear Plant Technical Specifications (Environmental Technical Specif ications) .

Based on this environmental evaluation, it is concluded that the activities associated with the constxuction of the refueling station does not constitute an unreviewed envirormental question. Consequently, it will not be necessary to obtain approval from the NRC prior to the start of the construction of the refueling station.

In the initial environmental evaluation, the impact of over-pressurization pulse following an explosion of the gasoline tank on the Radioactive Material Storage Building's (RMSB) stxuctual integrity was identified as a partial concern which could result in a significant increase in the potential for an accidental release of radioactive material to the environment due to the failure of the exterior surfaces of the RMSB. Based on an evaluation of the proposed scenario by the AEPSC

Technical Assessment (TA) Department, it has been demonstrated that the over-pressurization pulse resulting fram an explosion of the above ground gasoline tank would nat result in a over-pressure in excess of the limit specified in Regulatory Guide 1.91. %he calculations and supporting documentation to substantiate the conclusions of the Technical Assessment Department's evaluation have been reviewed hy Nuclear Safety and Licensing (NS&L) Section and their conclusions are docunented in the Safety Review Memorandum for this project.

Purpose of this Environmental Evaluation We purpose of this envirornrental evaluation is to determine if the proposed construction of the above ground fuel storage t-mks/refueling station for the Donald C. Cook Nuclear Plant constitutes an unreviewed envirorunental question as defined by Part II, Section 3.1 of Appendix B of the Donald C. Cook Nuclear Plant's Technical Specifications.

As stated in Part II, Section 3.1 of Appendix B of the Donald C. Cook Nuclear Plant's Technical Specifications:

A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question a matter which result in a if it significant concerns:

increase in any (1) may adverse environmental impact previously evaluated in the final environmental statement (FES) as modified by staff 's testimony to the Atomic Safety and Licensing Board, or (2) a significant change in effluents or power level [in accordance with 10 CFR Part 51.5(b) (2) ], or (3) a matter not previously reviewed and evaluated in the documents specified in (1) of the Subsection which may have a significant adverse environmental impact.

Description of Activity Indiana Michigan Power Company (IMPCo) proposes to construct and operate an on-site above ground containerized diesel fuel and gasoline storage tank refueling island at its Donald C.

Cook Nuclear Plant. 'Ihis facility will be used to ensure that facility vehicles have a readily available source of fuel at all times. 'Ibis facility is intended to replace the previous above ground diesel fuel and underground gasoline storage tanks

'Ihe underground gasoline storage tank which presented a potential for significant envirormental impact due to underground tank leakage and con~nination of ground water supplies was removed on September 24, 1990 in compliance with EPA regulations concerning underground tank storage facilities.

'Ihe above ground diesel fuel storage tank was also removed at this time to be incorporated into an improved unified refueling islarxl which can provide both types of fuel.

Description of Affected Area A. Location and Size

'Ihe proposed location of the above ground storage tanks/

refueling island is shown on Figures 1 and 2. %he site is that of the former concrete batch plant, that was used during the original construction of the Donald C. Cook Nuclear Plant; and is located south of the Cook Plant Training Building and southe~ of the proposed Radioactive Material Storage Building. 'Ihe base plate of the structure will cover an area

of approximately 1224 square feet. Access to the facility will be via the acct road for the 345 EV switch-yard.

B. Geology and Soils Soils in the location of the proposed refueling station are comprised of dune sards, glacial and lake till deposits.

Underlying the sands and till is bedrock consisting of shale, limestone, sandstone, and dolomite.

C. Surface and Ground Water lhe groundwater table generally rises gradually eastward away the level of the lake and ~s from Lake Michigan. The water table is less than 30 feet above within the dune sand or beach sand which overlays imp~able glacial lake clays. 'Ihe overall direction of groundwater flow is toward Lake Michigan.

%here are no significant surface water resources associated with the proposed refueling island.

D. Biological Resources

1. Terrestrial Ecology The area of the proposed refueling island was the previous site of a concrete batch plant and lay-down area during original construction of the Cook Plant. The area is currently being used as a laydown area and storage for construction of the Radioactive Material Storage Building. As such, the only vegetation is dune grass and scattered bushes. %his vegetation offers only a very limited wildlife habitat, and no namnels have been observed to reside in the area. 'Ihe dune grass does provide minimal cover for small animals as they transverse the area.

2. Aquatic Ecology As stated earlier in this evaluation, no significant surface water resources are associated with the proposed refueling station.

E. Cultural Resources

1. Land Use

%he entire site of the proposed refueling island is owned by IK~ and is the site of the former concrete batch plant. None of the area is previously undisturbed.

2. Archaeology Previous const~ction excavations in the immediate area of the proposed refueling island have not unearthed any artifacts or other exanples of archaeological significance. 'Ihese previous excavations include the construction of the Donald C. Coak Nuclear Plant, the constxuction of the access roads, the installation of ~ity lights, the construction of the Training Building, the construction of the Steam Generator Lower Internals Storage Facility, and the on-going constxwction of the Radioactive Material Storage Building.

V. Environmental Impacts A. Geology and Soils

'Ihe building will be constructed on a mat, type foundation thus limiting the extent of excavation. Soil removal during excavation will be stored in the immediate area and used for backf ill and grading purposes.

B. Surface and Ground Water The excavation is not expected to be deep enough to cause any impact to the area water table. Surface run off from the site will be handled by the in-place storm drainage system that was .

installed during the const~ction of the Training Building.

C. Biological Resources

1. ~estrial Ecology As the entire construction area of the proposed Refueling Island wil'e confined to previously disturbed areas, no significant impact to the terrestrial ecology is anticipated.

'Ihe area is already subject to the continual intxusion of man and machinery, therefore wildlife in adjacent areas should not be disturbed by any increased activity.

2. Aquatic Ecology No significant surface water resources exist close enxgh to the construction site to be affected by the proposed project.

D. Cultural Resources

1. Land Use

%he site is currently used as a layMown area and for storage.

%he refueling island and associated activities should not significantly alter the permanent impact to the area.

2. Archaeology No archaeological resources are known to exist in the area based on previous construction activities.

E. Noise Appropriate noise reduction measures will be employed so that noise levels from construction activities should not exceed the EPA's recaaanendations for rural areas. As the construction site is well within the confines of IMPCo property, noise levels should not be such as to create any annoyance to local residents.

VI. Environmental Controls

'Ihe following environmental controls shall be utilized to aunimize construction impacts. These environmental controls shall be reviewed by the contractor prior to the start of any construction in the area discussed by this assessment. In addition, it be included as is recommended that these environmental controls part of the construction contract.

A. Final Grading Plan

'Ihose areas disturbed by the proposed excavation and construction shall be contoured to meet the original grade and elevation that existed prior to construction. Any area disturbed outside of the marked construction zone will also be revegetated.

B. Noise hW 'ty, majority of construction activities shall only take place during the day shift in this area. Noise will also be controlled from internal cxxkastion engines by the use of exhaust mufflers. If blasting is r~ed shall be done during the day shift only.

for construction, it C. Slash Disposal Any vegetation slash materials will be stored onmite on the edges of wooded areas to provide wildlife habitat.

In no case will burning or incineration of solid trash or waste be permitted.

D. Environtnental Monitoring

'Ihe D. C. Coak Environmental Section shall conduct and document periodic inspections of the affected area. If any of the construction activities appear to be causing significant enviroranental impacts, appropriate action will be taken.

E. Perau.ts After reviewing the applicable Federal, State, and local requirements ard regulations, it has been detained that the only perau.t required to conduct this construction activity is the Critical Dune Area Permit as requixed per the 'Ihe Sand Dunes Protection ard Management Act, 1980 P. A. 146 and 1989 P.

A. 147. All requirements of said pened.t shall be strictly adhered to. Permit g90-BR-413M was issued by the Michigan Department of Natural Resources to the Cook Plant on January 28, 1991 for the construction of the refueling island.

As indicated in the Executive Summary of this evaluation, prior to utilizirg this facility, calculations ard associated documentation demonstrated that the peak over-pressure resulting from a design basis explosion of the gasoline storage tank will not exceed the limit specified in Regulatory Guide 1.91. NSGL has reviewed the Technical Assessment's evaluation and their conclusions have been documented in the Safety Review Memorardum for this project, which is included in this Environmental Evaluation as Attachment 1.

Conclusions American Electric Power Service Corporation concludes that with the proper mitigation practices as outlined in the Environmental Controls Section of this evaluation, no significant adverse environmental impact will result fram the proposed construction of the above grourd diesel fuel/gasoline storage tanks refueling island.

It is further concluded that the proposed refueling island ard associated construction activity does nat involve an unreviewed envirorunental question. Consequently, it will nat be necessary to obtain prior NRC approval to construct this facility.

'Ibis environmental evaluation shall be included in the 1991 Annual Enviroranental Operating Report.

DONALD C. COOK NUCLEAR PLANT ENVIRONMENTAL EVALUATION FOR THE RADIOACTIVE MATERIAL BUILDING February 8, 1991 Prepared by ~.g ft Walter T. MacRae, Radiological Support Section Date

n. i""

Approved by: dr ~ C C.d d'c~ z~r Dane R. Williams, Radiological Support Section

~ e Concurred by:

Diane tz aid ~SPy Donal C. ook Environmental Coordinator

Table of Contents Title Page Table of Contents I. Executive Summary II. Purpose of Environmental Evaluation III. Description of Activity IV. Description of Affected Area A. Location and Size B. Geology and Soils C. Groundwater and Surface Water D. Biological Resources

1. Terrestrial Ecology

2. Aquatic Ecology E. Cultural Resources

1. Land Use

2. Archaeology Environmental Impacts A. Geology and Soils B. Surface and Groundwater C. Biological Resources

1. Terrestrial Ecology

2. Aquatic Ecology D. Cultural Resources

1. Land Use

2. Archaeology 2

Table of Contents E. Noise VI. Alternatives to the Proposed Activity VII. Summary Cost-Benefit Analysis VIII.Environmental Controls A. Final Grading Plans B. Noise C. Slash Disposal D. Environmental Monitoring E. Permits F. Dose Limits IX. Conclusion X. References 3

I. Executive Summar O

Under federal law, on January 1, 1993 the three present low level radioactive waste disposal facilities will be closed. In November 1990, access to these facilities to Michigan radioactive waste generators was denied because the State of Michigan did not move forward to meet its obligations. The facility where the Cook Plant is to dispose of its low level waste is to be built in Michigan, but it will not be available until, at the earliest, 1996. The Cook Plant is responsible for temporarily storing all the radioactive waste generated by the plant until an offsite facility is available. To do this we will need a facility to be built on site capable of storing the waste generated. Because of uncertainties in the ability of the State of Michigan to meet its schedule and complete a facility by 1996, it is intended to build the maximum size facility allowed by the NRC. The size allowed by the NRC is based on five years of waste generation. For the Cook Plant this would be a building with a low level radioactive waste capacity of about 80,000 cubic feet.

This environmental evaluation was conducted to determine construction activities and subsequent use of the Radioactive if the Material Building would constitute an unreviewed environmental or a change in the Environmental Protection Plan. 'uestion Based on this environmental evaluation activities associated with it is concluded that the the Radioactive Material Building are

'not an unreviewed environmental question or a change in the Environmental Protection Plan. Therefore, it will not be necessary to obtain approval from the NRC prior to the start of construction.

4

II. Pur ose of Environmental Evaluation The purpose of this environmental evaluation is to determine the proposed Radioactive Material Building for the Donald C. Cook if Nuclear Plant constitutes an unreviewed environmental question as defined by Part II, Section 3.1 of the Donald C. Cook Plant Appendix B Environmental Technical Specifications. The change does not involve a change in the Environmental Protection Plan, As stated in Appendix B, Part II, Section 3.1 of the Donald C.

Cook Nuclear Plant Environmental Technical Specifications, "A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental statement (FES) as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any decision of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level [in accordance with 10 CFR part 51.5(b)(.2)] or (3) a matter not previously reviewed and evaluated in the documents specified in (1) of the Subsection which may have a significant adv erse environmental impact.

III. Descri tion of Activit Indiana Michigan Power Company proposes to construct a Radioactive Material Building at its Donald C. Cook Nuclear Plant. The facility will be used to temporarily store radioactive material, primarily low level radioactive waste that is prepared for transport to a disposal site in accordance with applicable regulations. The building is necessary for the storage of waste during an interim period when disposal will not be available.

IV. Descri tion of Affected Area A. Location and Size The proposed location of the Radioactive Material building is shown on Attachment 1. The site is directly behind the Training Facility on the site of the former concrete batch mixing plant, that was used during the original construction. The radioactive yaterial building covers an area of approximately 20,000 ft 5

BE Geolo and Soils Soils in the area are comprised of dune sands, and glacial and lake till deposits. Underlying the sands and bedrock consisting of shale, limestone, sandstone and till is dolomite.

C. Groundwater and Surface Water The groundwater table generally rises gradually eastward away from Lake Michigan. The water table is less than 30 feet above the level of the lake and occurs within the dune sand or beach sand which overlays impermeable glacial lake clays. The overall direction of groundwater flow is toward Lake Michigan. There are no significant surface water resources in the vicinity of the new construction.

D. Biolo ical Resources

1. Terrestrial Ecolo y The area of the Radioactive Material Building was the previous site of a concrete batch plant and lay-down area during original construction. The area is currently used for storage and as a lay-down area for major projects associated with the Plant. As such, the only vegetation is dune grass and scattered bushes.

This vegetation offers a very limited wildlife habitat, and no mammals have been observed to reside in the area. The vegetation does provide minimal cover for small animals as they travel to the lake shore.

2. A uatic Ecolo As stated, no significant surface water resources are associated with the area.

E. Cultural Resources

1. Land Use The entire site is owned by Indiana Michigan Power Company, and it is the site of the former concrete batch plant. The site is centrally located on the property among existing buildings. None of the areas are previously undisturbed.

0 6

Previous construction excavations in the immediate area have not unearthed any artifacts or other examples of archae'ological significance. These previous excavations include the construction of the Training Building, the Donald C. Cook Nuclear Plant, and various other facilities used to support the Plant.

Environmental Im acts A. Geolo and Soils The building will be constructed, on a mat type foundation thus limiting the extent of excavation. Soil removed during the excavation will be stored in the immediate area and used for backfill and grading.

B. Surface and Groundwater The excavation is not expected to be deep enough to cause any impact to the area water table. Surface run off from the site will be handled by installing a storm drainage system and directing the flow to existing natural drainage ravines. The building is designed with a closed sump system. The packages anticipated to be placed in this building are to be prepared for transport and disposal in accordance with applicable regulations'hey should be packaged in strong tight containers and free of standing liquids. If any liquids are released in the building they would drain to a closed sump. If a large amount of water were collected in the sump, it would to be trucked back to the plant to the plant's water processing systems.

Biolo ical Resources

1. Terrestrial Ecolo The entire area will be confined to previously disturbed areas. No significant impact to the terrestrial ecology is anticipated. The area is already subject to the continual intrusion of man and machinery, therefore wildlife in adjacent areas should not be disturbed by any increased activity. The external building dose rate will be closely monitored and controlled such that it is kept below 10% of the minimum allowed by federal regulation for access to an unrestricted area. The allowable dose rate for any external surface of the building is 0.2 mrem/hr. This 7

is the same limit used for other facilities not within the plant protected area.

2. A uatic Ecolo No significant surface water resources exist close enough to the site to be affected by the project.

D. Cultural Resources

1. Land Use The site is currently used as a lay-down area and for storage. The Radioactive Material Building should'ot significantly alter the permanent impact to the area.

No archaeological resources are known to exist in the area based on previous excavation activity.

Noise Appropriate noise reduction measures will be employed, so that noise levels from construction should not exceed the U. S. Environmental Protection Agency recommendations for rural areas. The site is well within the confines of the plant property. Noise levels shoul'd not be such to create any annoyance to local residents.

VI. Alternatives to the Pro osed Activit Two alternatives were considered.

First was the alternative of finding an offsite location to store the wastes. Finding a location to store our waste offsite is not feasible because there is no place today that will accept our waste for temporary storage. Vendors were contacted and either they are unable to do it or they could only store a very limited volume. Some that are unable to do it, are considering opening a storage facility but they do not have any definite plans. There are many legal, regulatory and political conditions that could deter a vendor from establishing their own storage facility.

Since no facility exists today, a new facility would have to be built somewhere. The impact to the environment is minimum at a location selected, and because of other concerns, built on the plant property.

it is best 8

The second alternative considered was to use temporary on site storage containers for highly radioactive material. These containers are typically concrete. They are used to store liners or 55 gallon drums temporarily. Their intended design use is short term, on the order of months not years. Depending on the amount of shielding required they could be very large and would be difficult to move without some kind of crane. Their exposure to the environment has not been proven, so they would have to be stored inside existing buildings or in their own warehouse.

Transporting them would be very difficult. The largest are designed with 23 inch walls. It has been determined that the maximum thickness that would be required for the Cook Plant is 30 inches' 23 inch walled container unloaded would weigh over 40 tons' The second alternative was not chosen for the following reasons.

First, the maximum dose rate they are designed to shield against is 50 R/hr. Based on our operating experience, it is expected to have material with a dose rate of greater than 100 R/hr. They would have to be kept out of the weather, so a building will still have to be built. They could weigh in excess of 40 tons.

They will need a special system to move them, such as the crane planned for the proposed project. The design required for the proposed project allows for uncontrolled access to the exterior wall of the building. Since the same shielding is not available with the storage containers a buffer zone would have to be maint'ained around the building to limit radiation exposures.

This requirement would increase t'e area needed for the storage of waste by about a factor of four. There is a requirement to inspect routinely the waste containers; it would be impractical to inspect the waste containers within the storage containers.

From an environmental impact viewpoint, the second alternative may appear to have a lesser impact, but there are many factors that show that the impact is nbt minimized. Using the second alternative will require more space. The use of individual containers,to store the waste makes it mor difficult to control water that could get into the containers. The containers would havde to be protected from the weather, therefore some construction would still be required. The packages will have to be inspected. Without the use of the remote cameras or shield walls ohter than the containers, the dose to the worker, the public and the environment would be higher. The impact from the second alternative would be greater than the planned project.

9

VII. Summar Cost-Benefit Anal sis The environmental impact of the project are minimal. No dollar amount has been assigned the impact, and the impact is small.

THe benifits include the continued operation of the plant, and a specially designed facility for the greater control of the waste and control of exposures. The benefits greatly out weigh the environmental cost.

VIII.Environmental Controls The following environmental controls shall be used to minimize construction and operational impacts on the environment. The environmental controls for the construction impact shall be reviewed by the contractor prior to the start of any construction in the area discussed by this assessment.

A. Final Gradin Plans Those areas disturbed by the proposed excavation and construction shall be contoured to meet the original grade and elevation that existed prior to construction or to meet the requirements set forth in the construction drawings.

Any area disturbed outside the marked construction zone will also be revegetated.

B.- Noise To reduce the impact of noise on the surrounding community, most of the construction activity shall only take place during the day shift in this area. Noise will also be controlled from internal combustion engines by exhaust mufflers. If blasting is required for construction, it shall be done during the day shift only.

C. Slash Dis osal Any vegetation slash materials will be stored on-site on the edge of wooded areas to provide wildlife habitat. Burning of solid trash or waste will not be permitted. This material shall be disposed of in dumpsters and waste receptacles.

D. Environmental Monitorin During construction the Donald C. Cook Nuclear Plant Environmental Section shall conduct periodic inspections of the affected area. If any of the construction activities appear to be causing significant environmental impacts, appropriate actions will be taken.

10

During the operation of the facility, it shall be the responsibility of the Radioactive Material Control Section to assure that the building maintains a minimum impact on the environment. They shall conduct periodic inspections of the sump and external building surfaces to document the impact on the environment. They shall conduct an inspection of the external surface of the building after the placement or movement of the packages put in storage in the building.

E. Permits No Federal permits or licenses are required for the construction or first five years of use. There are four State permits required. Three state permits are for construction and the fourth permit is an environmental permit required for work in a critical dune area. Two local construction permits are required. Concerning the affect on the environment, only one plant permit is required for digging. Other permits may be required (i.e welding) but these have no affect on the environmental requirements.

Dose Limits All external surfaces of the Radioactive Material Building shall be less than 0.2 mrem/hr on contact at closest easily accessible points.

IX. Conclusion American Electric Power Service Corporation concludes that with the proper mitigation practices as outlined in the Environmental Controls Section of this evaluation no significant adverse environmental impact will result from the proposed activity.

It is further concluded that the proposed project, associated construction activity and operation does not involve an unreviewed environmental question. Therefore, it will not be necessary to obtain approval from the Nuclear Regulatory Commission prior to the start of construction.

This Environmental Evaluation shall be included as part of the 1991 Annual Environmental Operating Report.

X. References

1. The Donald C. Cook Nuclear Plant Updated Final Safety Analysis Report, Volume 1, July 1990, Section 2.3

2. The Donald C. Cook Nuclear Plant Environmental Report, February 1971, Appendix A 12

' aw R<<W>>

NW>>fl tt I>>Nit\A

~

W PNI Ptw<<RNW N a>>NI

~ ~

Wl W

~ IPIW I P ~ ~ W lt N f

~ ~

~

NWI P>> I ~ I<<W W lt N tlWI IWN

~ ~,

~

w VNe p>>ww aw <<wa w apw I\Iwww, Ia

.I

'A'P.-

.I ~y I I~

I <<<<.

~ LCICO N<<N~

RIRNNHT I

~ 'rt I Llp '

N L

~ 'a>> ~

I/I +"<<W

~

+la Owl w

~ w el Wt

<<Ie

~ lf>>

I ta I I >>

<>

~

~ I

<<ww <>IW If

~ ~

Pf RW

<<R w w <<pp aw ~ aw l

I, C SCAPI I

~ I N IN ~ fl IIATCAIALS Pf ~

N ~ >>I itw IRIWWIII I lf ~ ~ 'W Nl N ~ I NRIN N r

>>T LfV IW P<<f ACTCACtfOC AAtfOIIT

/ ~ N awtfNP<<tfw

~ NN <<<>w ap

~f a N ~

wwwwwww~ w<<t

~ wa

a. Ifft fwa<< s wat NLL //

~ I/

/I'a

/

aaaa Rw pafa e~

w.

a p v<<

~ew

~ wv<<a Naaap aIIINIIa OOAALO C OOOO NOLLRA ILAIII

~ awaw TAAMtfOCCWTlR O TAIOLAIOAtALOfWO LITT LATOOT TLAO l2 504 ID vat ~ r wl ~ QKN OOINt M WPIO W,

/

~ C N ~

fat~If I Qa J fata w a w v L ~ II ~ ~ ft

OIOOt Zl ew ICIICOLL IIOTCI RW~>> IIIINN rt

~ ttN<< I o>> N<<2 N N>>

~ ~ ~ ONIN

~

<>tt>> I.rtr~

NN<<t t>>>>>> t>> IO>>

N>>l rr>>>> riot>> r>>N

~

<<->>r ~,N <<>>ur>>>>O>>

Nt o>> NNN

+RP' t r /

~ e>>N>>t >>rt>>>>

/

IIII>>

"~NktkNG RT I kk t

~ ~ e>>>> It >>N

~ NNPO Nl W

>>Rer

/ >>>>It>>t I>>

/ I~ ~

rt ~ >>r <<<< RN>>//<<>>I O<<r>>ttt t>>>>It>> Nr >>N~

NNN t<<r <<>> ~ 4>>

N>> <<>> N>> I/N>>t 'I

~ ~I OLICOILLS

~I ~ >>>>Irt ~ R<<or<<N lie(I ~ >>RNI>> rot>>>>o>>

~ I>>I Nt N ~ INI<<tN l>>tar I

~a, No>>NQI OCICOCOCC OMNs0$

I N<<r<<r to>>t>>>>

R~~ '

~

~

ttlr o<<o>> ~ INN>> NN

~

Ittr N>>et~<<IN 1

Nr ~ r>>t&t<<>>N

$1

~ No>>>>>> r>>o

~ I r,>>>>

I I

~

/

I i/I, Tfg ~4

~ r>> ew N>>~

~kre Ea>>>> IW>>OIS N>> <<r>>>>m N>>rr

~$ ~ >>>>>>>>>>t ~

>>>>>>~t>>WA

~ >>NIN ~ Nkoo>>N ant>>o o>>

OCIIIIO O, OOOO

>>CLIIO III<> IR 50OID ~ 2

>> ~

o>>QN>> N J N E P ~ ONOO II ~ ~ ~ Ir

p- ~

oo ow

~~

~~

tv pov>> w oe ee e<<le twww w wetvavwvt owo Ol t

I <<ov>>

~

~

oo oe p

~ I' IOW te

~wvopwwoav wwo

~ ~

PWt a>> or toow Iwt g, 'rPPP ~ va a>>oo h

9=-K

-./H h

Ih I ~

~ or C

r I

~

/

~

~ ~lf4NHG of R R4%UEB ~ atW \ W o>>r t<>

wwo OtWN WIW

~ RW ~ ~ ~ >>We <>We>>WOWOW op~

pao are <<w I/two I

o P wt ~

~ vo OI ~ V WTtkULC r l ~ I~ I~ v Hto ~ looaettv IN I <<V>> th<<WV

, ~...> loe ~ aw otv ~ loawv r o fr W IVW IfttttCICC OCWIICC

~ I fo

~ v ~op oe taw I aao

~ ttw aWV I WOW OV e ovr <<wow opoe ~ oow wo r.ooo r otot ~

ovo too aw owowhowoa wv Io I

eo oee

//

~ ~

T te w 4

oooo ow ww w o vo o o \o oo v~ o owvr ovo e r \ O orwww ~ ~

Woe o

~ oo<<a eeoww oWew w OOIALD C OXX

~ CLIRR II/ol

~ vore TtllCC CCNTCl ~

CrtffLCTOC CICCWC CIT C LATOIT CLCII

~ et a IR 'SOCIO 2 V ~ O W rw et ~ o / Voa oe a S O L It ~

. ~ ~ ~ /

OIDOR CI ew SCIICSJL DOTCS

~ a>> w<<e w N ee Iten I Ne W IWI>><<N I~ ~ Ia>> Nt r V

~

I >>WIN W Wl

~ It>>et>>I I.ree<<e

~ r' >>>>IW N ~ >> K KWN lett

'Y . eT ~ N >>1 ~ e>>e>> <<Nw>>

t' yP

/

I l aa D

~ I K>>wNeeew let <<e ~ NIW \ era\I NNKIIWe j-"-~

~

e C~~Ii4OI~DI ~ rr r <<lee>>ea>>e N<<K NIIW

~

i

//

~ I >>I N>> NWacre<< I

-I>>tee Ne

~

~

Del e>>e ew NrNe >>e~ ~ e>> l e>>

I~ ~ l wt e>> Ir eeet ewe

~ Ilwee IICCCSICLS r EKSL. 'tl ~ NW>> tl<<>>tet gl I ~ Iae.t IN.'>>I>> I'eeeaee>>

~ le ~ I' I<<t. >>I N ~ I el a>> N l

I I

er

~

e ~ ~

Sleete<> Ia>> I>>e I Ne I. PF~

~

h rL . ~

/ ~

~

NN w<<e eww e>>

NN Nweww>>w e.teel ~

>>tact I Ke>>

~ Ne ~ Iwt ewe>> ewe

>>eeet>>ea ~

i/(//

F/ <~. j'8,:/ ~e

}

e>>w I<<N>>e e>>

ee wa e>>e e>>aew>>e

~ >>

e e N ae Nee Ne N e e e ww ww>> e Ne ew\

~

~ Neat ~ It>>teel NNI>>e M DOKACD C OXC K/S//D tVW

~ e>>e>>

VSCSKO CCCICD ~

SSCLCIOD Mls%

SllC CDIRT KID ~

IR 50410.0 N ~ e N SIR%DC

~ wl I'>>I

~ ~ teat>> ckwt Iwe wew we C e >> ~ e ~ e ~ eee I ~ ~ ~ ~ /

Z ANERICAM ELKCTRlC PCS ER Date September 24, 1991 Subject Environmental Assessment of Plant Modification 12-PM-1158; Installation of New Anchor Bolts for the Circulating Mater Intake Structures Collapsible Racks From R. M. Claes To 12-PM-1158 Packet Radiological Support Section File DC-RS-7915 Pursuant to Radiological Support Section Procedure RS-34, the purpose of this memo is to document that there is no need to perform an Environmental Evaluation of the installation of new anchorage bolts for the circulating water intake structures collapsible racks as delineated in Plant Modification 12-PM-1158.

Plant modification 12-PM-1158 proposes to install new bolts to secure the collapsible racks to the circulating water intake. The racks were collapsing prematurely due to the cycle loading effects of lake surges and currents. This permitted rocks and other debris to enter the intake pipeline and screenhouse intake forebay. Accumulation of debris affects flow in the pipeline and impacts the operation of the travelling screens.

Specifically, the proposed modification includes. replacing the existing 1/4" A307 bolts with 7/16" A307, Grade B bolts. This modification should not diminish the screens intended capabilities as detailed in 12-PM-1158 Safety Review Packet.

Because the premise of the project merely replaces undersized bolts and associated reinforcements that have been accounted for in the Final Environmental Statement with larger bolts of the same type and composition, there should be no significant environmental impact associated with this activity.

As described above, it can be concluded that there appears to be no unreviewed environmental question as defined in Section 3.1 of Appendix B of the Facility Operating License. The described project should pose no adverse affects on the environment and will, in all practicality, serve as an enhancement to the system. From the scope and responsibility of the Radiological Support Section, an Environmental Evaluation is not required and the project as herein described may proceed as planned.

Intra-System

September 24, 1991 DC-RS-7915 File Page 2 Prepared by:

Robert M. Claes, Radiological Support Section Approved by:

D n R. Willi s, Manager, Radiological Support Section Concurance bg'.

Steven J Brewer, Manager, Nuclear Safety and Licensing cc: K. Tamms T. Zelina D. Fltzderald

Z ANERKAN ELEClRK POWER Date October 22, 1991 Subject Environmental Evaluation for 12-PM-1000, Revision and Upgrade of the Yard Drainage System From R. M. Claes To 12-PM-1000 Package Radiological Support Section File DC-RS-7915 Pursuant to Radiological Support Section Procedure RS-34, this m'emo shall serve to document that an Environmental Evaluation is not required to be performed for the proposed revision of the yard drainage system as described in 12-PM-1000.

With the recent additions of the new guard house, training center, and paved lots, the current yard drainage system is overloaded during heavy and seasonal precipitation. The system requires this upgrade to prevent frequent localized flooding during these events. A cursory review by Mechanical Design Plumbing identified some problem areas, subsequent to which 12-PM-641 was issued. The proposed activity will upgrade the 15" diameter line from catch basins "AL to "F"and the line from catch basins "U-3" to "F". In addition, the proposed activity will add two new drainage lines to the system. One line will extend from the North East corner of the Unit 1 Turbine Building to catch basin "AM" and the other will extend from the Unit 1 Turbine Building near the overhead door to catch basin "202".

These segments of the yard drainage system are confined within the boundaries of the protected area. The new drainage lines will traverse previously disturbed ecologies and existing structures. (See attached drawing, SK-1)

As the proposed activity involves an area previously disturbed and evaluated for, there would be no further significant associated environmental impacts.

The proposed activity will serve as a site enhancement by reducing the potential for soil erosion and any additional detriment to the dunes area.

As described above, it can be concluded that there appears to be no unreviewed environmental question as defined in .Section 3.1 of Appendix B of the Facility Operating License. The proposed activity would pose no significant adverse effect on the environment. From the scope and responsibility of the Radiological Support Section, an Environmental Evaluation is quired andI the activity defined in 12-PM-1000 may proceed.

A,... b: r' P,

i Manager, adio ogical Support Section Concurrence By:

c ear Safe an censing Intra System

0 APPENDIX IV HERBICIDE APPLICATION REPORT 1991

5 fND(AMA MKNGAN POWER Date February 11, 1992 Subject 1991 Herbicide Spray. Report Cook Nuclear Plant From S. R. Watkins To H. E. Brooks

SUMMARY

OF PROGRAM From April 22-May 1, 1991, Townsend Tree Service applied a mixture of Karmex, Amizine and Oust to control grass and weed growth on the plant site.

A total of 48 lbs. of Karmex, 560 lbs. of Amizine and 2 lbs. of Oust was applied over 36 acres.

In August, the areas treated were inspected and the following observations were made:

1. Sewage Ponds:

Weeds are growing on the sides of both sewage ponds. The herbicides were applied only to the water's edge.

2 ~ Road to absorption pond:

No weeds found.

3 ~ 765 KV Switchgear Yard:

Sparse patches of grass growing throughout yard.

Perimeter fence is clear of grass and weeds.

4 ~ 345 KV Switchgear Yard:

Sparse patches of grass growing throughout yard.

Perimeter fence is clear of grass and weeds.

5. Railroad Tracks east of Training Center:

Good weed control.

6. Parking Lot B:

Patches of grass growing along the east fence.

7. 69 KV Switchgear Yard:

No grass or weeds growing in the yard or along the fence.

I

1991 Herbicide Spray Report February 11, 1992 Page 2

8. North Protected Area Fence:

Good weed control.

9. South Protected Area Fence:

Weeds growing along fence.

10. East Protected Area Fence:

Weeds growing along the fence.

11. ICMS Office Trailer:

Good weed control. No weeds found at all.

12. ICMS Fab Shop:

Moderate weed control, weeds growing around building.

13. Southwest Side of Turbine Building:

Good weed contxol. No weeds found at all.

14. South End of Turbine Building:

Moderate weed control. Patches of weeds growing throughout the area.

15. Unit 1 RWST Area: Moderate weed control. Sparse pa es of weeds growing.

16. Unit 2 RWST Area: Moderate weed control. Patches of growing weeds throughout the area.

17. Hydrogen/Nitrogen Storage Tank Area:

Moderate weed control. Sparse patches of weeds growing in area.

18. Construction Fab Shop:

Grass is growing on north and west sides of the building.

19. Road to Met Towers:

Patches of weeds on the road. Gravel along access road-no weeds found.

Based on,our review of application records and observations of the treated areas, it appears that the herbicides were applied in accordance with herbicide label requirements, and no adverse environmental effects occurred.

1991 Herbicide Spray Report February 11, 1992 The following additional areas were identified for the 1992 treatment program:

Barrel and Scrap Metal Yards Fire Protection Training Area South Guard House Portal CESA East Sewage Plant Sewage Plant 'outh Site Design Building Contractors Trailer Complex Met Tower Building Air Stations Environmental Warehouse Environmental Polebarn Please ensure that the 1992 contract takes into consideration these additional areas.

'I

=/js c: D. M. Fitzgerald

APPENDIX V MACROFOULER MONITORING PROGRAM 1991

INDIANA MICHIGAN POWER COMPANY Cook Nuclear Plant 1991 Zebra Mussel and Asiatic Clam Monitoring and Control Report April 8, 1992 Since 1982, Cook Nuclear Plant has had in place a macrofouler monitoring program to detect the presence of asiatic clams.

In 1990, a program was instituted to detect the presence of zebra mussels (Dreissena ol mor ha) as well as asiatic clams. By late 1990, zebra mussel populations on the walls and structures in the Screenhouse intake forebay were estimated to be 100 individuals per square meter. In 1991, a population explosion of zebra mussels was noted in the Screenhouse intake forebays and offshore intake structures.

Densities were measured between 180,000 to 200,000 individuals per square meter. A report on the bio-monitoring studies by Environmental Resources Management (ERM) is attached.

ERADICATION AND CONTROL MEASURES A joint plant/corporate task force was formed in late 1990 to develop a zebra mussel eradication/control plan which was implemented in 1991. This program centered around'argeted treatments to the Circulating Water, Essential Service Water

~

and Non-Essential Service water systems with a proprietary

~

molluscicide (Betz Clam-trol, CT-1) for control of juveniles and adults, followed by intermittent chlorination treatments using sodium hypochlorite to control veliger settlement. The Fire Protection system was given periodic treatments of Clam-trol but not treated with chlorine.

CLAM-TROL TREATMENT RESULTS Essential Service Water System (ESW)

The ESW System was treated with Clam-trol at a concentration of 10-15 ppm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from 4/4 to 4/5/91. Critical heat exchangers that received the treatment included the Unit g1 and g2 Component Cooling Water, Containment Spray, and Diesel Generator heat exchangers. The critical piping from ESW to Auxilliary Feedwater also received treatment. Bio-box mortality results ranged from 84-100:.

Non-Essential Service Water System (NESW)

The NESW System was treated with Clam-trol at a concentratio of 15 ppm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from 4/10 to 4/11/91. Bio-box mortality results ranged from 81-100:.

Fire Protection System The plant's Fire Protection syStem was flushed with Clam-trol at approximately 6 week intervals from April to November with a target feed of 15 ppm Clam-trol. When mortality studies were performed, bio-box results were 100% in all flushes.

Circulating Water System The Circulating Water system was treated with Clam-trol which was fed at the offshore intake structures at a concentration of 15 ppm for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 9/13 to 9/14/91. Bio-box mortality results were 99%. Though not targeted during the treatment, sufficient Clam-trol residuals were achieved in the ESW and NESW systems. Diver assessment of the zebra mussel mortality in the intake forebay of 99% compared favorably to the Circulating Water bio-box results. Diver assessment of mortality in the first 350 ft. of travel from the structures inward in the plant's center intake pipeline averaged 40'o. This could be attributed to inadequate mixing of chemical within the first 350 ft. of travel in the 2,250 ft. pipeline. It is interesting to note that those zebra mussels which survived the treatment both in the intake forebay and pipeline were at least 3/4" or longer in length.

CHLORINATION TREATM1WT RESULTS In 1991, the ESW and NESW systems received daily intermittent sodium hypochlorite treatments of 1.5-2.0 ppm total residual chlorine (TRC) for 155 minutes from May thru mid-October.

During the same period, the Circulating Water system received daily intermittent sodium hypochlorite treatments of 0.2 ppm (TRC). A temporary feed system was used to deliver the sodium hypochlorite while a permanent feed system was being designed and constructed. This permanent sodium hypochlorite feed system will be operational in 1992. Monitoring of artificial substrates in side-stream monitors placed within the ESW and NESW systems revealed that the chlorination program was effective in reducing zebra mussel settlement within these systems by approximately 95% downstream of the pump inlets. This was confirmed by visual inspections of heat exchangers within these systems.

CONCLUSION Shock treatments by a pr'oprietary molluscicide -o remediate juvenile and adult zebra mussels in conjunction with the use of sodium hypochlorite to control veliger settlement has been an effective method for controlling macrofouling in the Cook Plant raw water systems., Capital upgrades to improve the delivery and dispersal o molluscicides in 1992 along with the construction of dedicated fire protection water tanks (1993) will urther minimize the risks associated with macrofouling in the plant.

The plant will also utilize mechanical cleaning during unit outages in 1992 to control infestation. 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.

MOLLUSC BIOFOULING MONITORING AT THE DONALD C. COOK NUCLEAR PLANT DURING 1 99 I April 1992 Robert L. Dwye, Ph.D. Christine Blundell Project Manager Project Scientist Prepared for:

American Electric Power Service Corporation 1 Riverside Plaza Columbus, Ohio Prepared by:

Environmental Resources Management, Inc.

116 Defense Highway, Suite 300 Annapolis, Maryland

SECTION INTRODUCTION 1.1 Background Indiana Michigan Power Company (I&M), a wholly owned subsidiary of the American Electric Power Service Corporation (AEP), owns and operates, under license from the Nuclear Regulatory Commission (NRC), the Donald C. Cook Nuclear Plant.

The NRC issued IE Bulletin 81-03 regarding Asiatic clam (Corbicula Jluminea) biofouling in 1981 and IE Notice 89-13 regarding zebra mussel (Dreissena polymorpha) biofouling in 1989. I&M and AEP responded to the NRC on both occasions that monitoring programs would be conducted to detect the presence of either of these bivalve molluscs. The Asiatic clam monitoring began in 1982 and the zebra mussel monitoring in 1990. Asiatic clams had caused biofouling problems at a number of power plants, prompting NRC to issue IE Bulletin 81-03. Only about a dozen Asiatic clam shells and shell fragments have been found at the Cook Plant since monitoring began in 1982.

The zebra mussel, indigenous t'o Europe and Asia. entered the Great Lakes probably as a result of ship traffic. Since being introduced to the Great Lakes in the mid-1980s. zebra mussels have caused serious biofouling problems at a number of water intakes. Zebra mussels were first found at the Cook Plant in 1990.

In September, 1990, AEP contracted with Environmental Resources Management, Inc. (ERM) to undertake an abbreviated monitoring program beginning in October 1990. Some qualitative evidence of the presence of both the zebra mussel and the asiatic clam was found in water systems within the Cook Nuclear Plant, but the late initiation of the program in the first year of monitoring prevented a systematic assessment of the abundance and distribution of the organisms (ERM. 1990).

1,2 1991 Objectives ERM initiated a second year of monitoring in July 1991. The objectives of the 1991 monitoring program were to complete

the following tasks:

O

~ Task 1: Circulating and Service Water Sampling - intensive daily sampling over four weeks for the presence of planktonic veliger stages of the zebra mussel ~

~ Task 2: Fire Protection Sampling - sampling of one fire hydrant monthly from July through November for the presence of adults or shells.

~ Task 3: Artificial Substrates - deployment of quantitative artificial substrates in the intake forebay and in locations in the essential and nonessential service water systems in the plant, and sampling of these locations at 3-week and 6-week intervals.

Task 4: Beach Walk Sampling - monthly qualitative examination of hard substrates along the Lalie Michigan shore for the presence of attached adults.

Task 5: Inspection Sampling Analyses - analysis of up to six samples collected by plant personnel.

1-2 Group

SECTION 2 METHODS AND PROCEDURES 2.1 Circulating and Service Water Sampling The circulating and service water sampling occurred over a four-week period between July 17 and August 13. Samples were collect.ed from the intake forebay and from the Essential Service Water (ESW) and Non-essential Service water (NESW) systems.

A total of 16 samples at each of three locations were collected and counted. Each sample consisted of a 24-hour sampling of flow; a 24-hour sample would integrate any diel periodicities or patchiness exhibited by the organisms in Lake Michigan and manifested in the intake circulating water supply.

ERM constructed two of the water sampling and filtration systems (see Appendix A).

The samples of circulating and service waters were collected by filtering a measured volume of water over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> through a No.

20 plankton net. In the circulating water sampling. water volume was measured using a totalizing water meter that recorded the total amount of water discharged by the sampling apparatus. For the service water samples. period ic flow measurements. using bucket and stopwatch. were inade during the 24-hour interval.

The fine mesh No. 20 plankton net is needed because the early life stages of zebra mussels and asiatic clams are very small. on the order of 70 to 80 pm. However, the fine mesh net also collected a large amount of extraneous material such as sediment entrained by the plant's pumps, zooplankton, and filamentous algae. Because of the large amounts of this material, it was necessary to use subsampling techniques. Enough multiple subsamples were taken (using a standard Stempfel plankton pipette) so that the plankton from at least 500-1000 liters of water were analyzed. The experience of Dr. Peter McCall (an expert on the population dynamics of the zebra mussel and a subcontractor on this project) and other zebra mussel researchers indicates that larval densities of less than 1-2 per 1000 liters are not accompanied by detectable adult fouling densities on hard substrates (Greenberg & McCall.

1991).

2-1

Samples were collected daily from each location, and generally counted live within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Those that could not be counted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> were preserved in ethanol for later counting.

I Because of the large volumes of the filtered samples, all were subsampled using a Stempfel pipette to examine a series of 1 ml aliquots in a Sedgewick-Rafter cell, or 5 ml in a Circular Counting Chamber. Counting methods generally followed the provisional sampling methods recommended by Marsden (1991). Raw counts of the organism in the subsaniple(s) were multiplied by the concentrated volume of the sample, and then divided by the volume of water filtered by the apparatus. to yield the number of organisms per m3 of water filtered.

In addition to direct quantitative counting. a semiquantitative method, differential settling through a dense sugar solution (Marsden 1991, pp. 11-12) was attempted. The method involves the addition of a plankton subsample to the top of the solution in a separatory pipette, and counting of the fast-settling veligers in an aliquot taken from the bottom of the separatory column. In practice, however, since all samples had varying amounts of sand and sediment drawn into the water by the system pumps, the rapidly settling sediment obscured the settling of any veligers, making the method ineffective for samples taken in the plant's water systems.

2.2 Fire Protection Sampling The fire protection system was sampled using a No. 35 sieve to filter the first 10 minutes of hydrant flow during flow testing.

The presence of any juvenile or adult Asiatic clams on the sieve indicates whether or not any of the organisms have in fact invaded the fire protection system and pose a danger to the safe operation of the plant. The contents of the sieve were decanted and examined at the site, or if time was not available. the sample was placed into a container of buffered formalin. Later, the entire contents would be examined under a dissecting microscope at low power to identify the presence of any organisms or shells.

Although sampling of fire hydrants was intended to be done monthly between July and November, plant management in practice prohibited the testing and flushing of any fire protection systems unless a molluscicide could also be

..e 2-2

introduced with the replacement water drawn from Lake Michigan as a protective measure. This requirement reduced the number of times that fire protection samplin<<could be performed.

2.9 Artificial Substrates In order to assess the rate of settling of zebra mussel larvae within the circulating and service water water systems, ERM deployed three artificial substrate samplers in the intake forebay area upstream of the trash racks and travelling screens. and two more in sidestream.biomonitors on the Essential and Non-essential Service Water systems. The samplers were designed similar to those used by Peter Fraleigh of the University of Toronto (Marsden 1991). They consisted of cinder blocks containing test tube racks secured within the voids in the blocks. As settling surfaces, 24 microscope slides were secured to each test tube rack with rubber bands, and changed on a regular basis. Deployment of all the samplers followed approved I R M plant equipment installation procedures.

The artificial substrates within the samplers and biomonitors were examined every three weeks from July to November for settled molluscs. After visual examination. the devices were gently washed or brushed clean of molluscs in a bucket or tank.

and replaced.

In addition. ERM also deployed and monitored artificial substrates in Lake Michigan (this was an out-of-scope activity.

but was undertaken because ERM perceived the importance of interpreting in-plant mollusc abundances with respect to abundances in the lake near the intake structures as a baseline).

A cinder block sampler was deployed on a three-week schedule from July until October using boat traffic to and from the dive barge moored near the intake structure on an as-available basis.

The recovery of this sampler was discontinued in mid-October because of adverse weather conditions.

Two test tube racks were deployed in each cinder block holder at each location. One rack was recovered and replaced on a three-week cycle. while the second rack was recovered on a six-week cycle. The two deployment lengths were used in order to determine which deployment interval provided the best estimate of the sparse settlement rates expected during 1991.

2-3

Each rack held 24 microscope slides. After recovery, sample O

racks were placed in a water bath until the individual slides could be removed and counted under a dissecting microscope using 30-50X magnification. At low settling densities (less than 100 per slide), the whole area of one side of the slide (25 cm x 75 cm) was counted and the value multiplied by a conversion factor to estimate the number of settled organisms per square meter. At higher densities, five random 1 cm2 subsamples were counted on each slide. The five subsamples were added, and multiplied by a conversion factor to calculate the number of settled organisms per m>. These estimates were averaged for the 24 slides per rack to obtain the average settling density for each location and sampling interval.

2.4 Beach Walk Sampling Beach walk sampling was conducted monthly from July to November. The major areas monitored were the beach adjacent to the plant, and the jetty and rock riprap at the mouth of the St. Joseph River in St. Joseph, Michigan. Localized areas where zebra mussels were likely to settle were identified in July. In order to maintain consistency, the same ERM scientist monitored the undersides of the same rocks in the areas over the duration of the project, with Dr. Peter McCall of Geo-Science Associates providing QA/QC for the examination o>> September 26, 1991 (see Section 2.6 below).

2.5 Inspection Sampling Analyses Plant personnel submitted three samples taken in the plant for analysis. These consisted of shells, whole molluscs, and shell fragments. These samples were submitted to Cove Corporation.

ERM's taxonomy subcontractor, for identification to the lowest practical taxon.

2.6 Quality Assurance/Quality Control (QA/QC) Procedures Quality Assurance/Quality Control (QA/QC) continued to be an extremely important aspect of the program. Quality assurance was designed into the project at several points. Initially, all primary and backup ERM personnel were trained on site in proper methods for the collection, preservation, and storing of all samples. A standard operating procedure was adhered to on Ki The 2-4

a day-by-day basis by the personnel performing the sampling and by laboratory personnel processing the samples. After counting, all data were entered into spreadsheets for reduction. All spreadsheet algorithms were checked by two scientists, and data entries were compared to original data sheets for accuracy.

On September 26, 1991, Dr. Peter McCall of Geo-Science Associates, visited the Cook Nuclear Plant to conduct an independent audit of ERM's procedures. A copy of his report is attached as Appendix B.

During the circulating and service water sampling, the large amount of sediment in the samples and the presence of ostracods in the sample, made identification difficult. In order to confirm the identification of zebra mussel veligers in the sample, a fresh unpreserved sample was sent to Dr..Ellen Marsden, a taxonomist with the Illinois Natural History Survey.

for confirmatory identification.

In addition, ten percent of all of the samples were split and were sent to another laboratory, Cove Corporation of Lusby.

Maryland, for independent verification of both the counts and taxonomic identifications of the two individual organisms.

However, the delicate veliger valves apparently deformed after preservation, and became curled up and clumped with the sediment in the samples. Despite prolonged efforts, Cove Corporation taxonomists were unable to obtain reliable counts.

Subsequently. the effort was abandoned.

Finally, type specimens of individual species and individual life stages were preserved and permanently archived for later confirmation of species identifications, in order to ensure the quality of data submitted to the NRC.

2-5

SECTlON 3 RESULTS 3.1 Circulating and Service Water Sampling Sampling of planktonic veligers in the circulating and service water systems was begun on July 22 and completed on August

15. A total of 16 samples were taken in the circulating water intake (a pump apparatus withdrawing water from the intake forebay near Travelling Screen l-l), the Non-Essential Service Water (NESW) system, and the Essential Service Water (ESW) system.

Sampling of the circulating water system was plagued by mechanical problems. The pump for the system had apparently been rebuilt over the previous winter, and its flow had been markedly increased over its 1990 operating flow. The new flow rate was about 150-230 L/min. This large flow rate. combined with the fine mesh size of the No. 20 net. caused frequent hydraulic overloading of the system's capacity. The hydraulic overloading of the net resulted in the bypass of water around the net and underestimates of the veliger density. High Flow velocities in the circulating water system also caused mechanical abrasion or tearing of the plankton net. This also bypassed unfiltered water around the net, causing underestimates of veliger densities. Because of these problems. the circulating water data must be interpreted with caution.

No apparent problems were observed during the ESW and NESW sampling.

The results of the sampling are presented in Figure 1. Both the ESW and NESW data show major peaks about August 8-9 with densities in excess of 5,000/m>. Although no measurements of veliger densities in Lake Michigan were made as part of this monitoring program densities recorded elsewhere in southern Lake Michigan by other investigators were over 30,000/m~ at about the same time (E. Marsden, pers. comm.). Densities in the circulating water system were always less than 1.000/m3.

The low densities in the circulating water samples may be the result of the low filtering efficiency of the circulating water sampler.

3-1

7000 6000-

~

4 5000-E o 4000- )c 3000-E v~

2000 1000- .'4;l

'l>,C 0- V Ol Ol

0) Cll NESW CV CC) Ch CV CJl

0) ESW ao o) C7l CIRCULATING WATER OO C) oo cn lA ao ao co

The service water results indicate that veliger densities in the systems are significant, and can probably result in dense attachment of adults, especially in areas of reduced flow in the system.

3.2 Fire Protection System Sampling Four hydrants were sampled on September 25, 1991. The four hydrants were 2A, ll, 12, and 21.

Each hydrant was flushed for 10 minutes. with the discharge collected in a 208 L drum. The flows of the hydrants over the 10-minute discharge was estimated to be about 2000 to 4000 L.

The discharge was sieved through a No. 35 benthos sieve and the material was examined under a dissecting microscope for the shells of the zebra mussel and the asiatic clam. In addition.

water in the drum was sieved and examined for organisms.

No organisms were observed in any of the samples.

3.3 Artificial Substrate Sampling 3.3. 7 Lake Settling Substrates were deployed and recovered from Lake Michigan (a location about 100 m inshore of the intake structure) between July and mid-October (when the effort was suspended because of weather conditions). Settling densities varied between 5,000 and 311,000/m~ (Table 1), with the peak occurring in August (i.e.. settling in the weeks prior to the September 3 sampler recovery; Figure 2). These densities provide a baseline dataset against which the densities measured within the plant can be compared.

Length ranges of the settled adults are shown in Figure 3. In general, shells less than about 2 mm can be considered to have settled on the slides over the 3-week deployment interval. This is based on early growth rates of 06 to 0.9 mm/week.

Conversely, larger organisms probably migrated onto the slide from adjacent substrates, and are obviously too old to have settled during the deployment interval.

3-2

r Figure 2 Forebay and Lake Settling 350,000 300,000-250,000-200,000-150,000-100,000-50,000-LAKE CV Cll I

6 wk AVERAGE CD I

CL CV l/1 I 3 wk AVERAGE CL

~J CII Date Removed

Figure 3 Lake Size Ranges 3.5 E

E 25.

2.

1.5 0.5 Jul-22 Aug-12 Sep-03 Sep-25 Oct-14 Nov-25

3.3.2 Forebay Settling Settling rates for the average of the three forebay locations are also shown on Figure 2. Both the 3-week and 6-week deployment show similar patterns, with a peak that corresponds to the peak lake settling, and the peak abundance of veligers in plankton sampling (Fig. 1).

The averages of the three forebay locations mask significant spatial differences (Figure 4).

3.3.3 Service Water Settling Zebra mussel settling rates in the service water systems are presented in Figure 5, with the lake settling rate data also presented for comparison. Note that the lake settling rates for September 3 and September 25 have been truncated on the figure in order to expand the scale for the service water samples; actual settling in the lake was 311.333/m2 on September 2, and 36,155 on September 25.

In the service water systems, settling rates dropped dramatically after the deployment recovered on September 25. Some of the decrease is attributable to decreased spawning of the organism as water temperatures decreased in the fall. However.

significant settling rates were still observed on the forebay substrates after September 25, indicating that the organism was still capable of settling.

Another contributor to the decreased counts in the service water systems was due to clogging of the sidestream ports feeding the biomonitors on the two systems. Based on material found in the bottom of the biomonitors, it appeared that sand and other sediment were significant sources of clogging material. However, it was also not possible to rule out biofouling by attached zebra mussels in the systems as contributors to the flow reduction, since at that time the systems had not been opened for visual inspection. Because of the flow reduction due to sediment and debris restricting flow in the sample line, ESAV and NESW settling data after September 25 should be treated qualitatively. Absence of evidence of zebra mussel settling does not conclusively indicate that no zebra mussel settling is occurring in the service water systems. At the same time. the 3-3

~

Figure q Fprebey $ ellling, by 2pp,ppp- .cr"2

~Ap-160,000 160,000 140,000-120,000 100 000 E 80,000  :-e@

60,000-Pe~'

40,000- jv C4'44 20,000- ICE",')I4 14<

+4 It'(<

0 4'44 4 CD I

I CD CJ I CD-

presence of small, newly settled postveligers is an indication of potential settling within the systems.

Data for the ESW on November 25 did show an indication of recent settling. Small postveligers, about 0.5 mm in length.

were observed on the artificial substrate on the Essential Service Water system. The presence of newly spawned mussels so late in the fall, when ambient water temperatures would be too low to permit lake populations to spawn, suggests that organisms somewhere inside the plant's water systems were finding favorable conditions for spawning and thus may serve as a continued source of settling organisms over the winter, or veligers spawned late in the normal spawning period in the lake may be maturing very slowly due to the cooler water temperatures.

3.3.4 Qualitative Effects of Biocide Treatments Two types of biocides were used to control the zebra nzussel within the Cook Nuclear Plant. Chlorine, presently permitted under the facility's Michigan state discharge permit. was added to all systems beginning in April, and extending into November (E. Mallen, Pers. comm.). Although chlorine was added throughout the monitoring period of this project. the dosages were evidently not sufficient to completely control the settling of the zebra mussel. since mussels still settled throughout the plant. Plant personnel conducted inspections of heat exchangers and piping in the ESW and NESW systems and found no zebra mussels.

ClamTrol, a proprietary molluscicide, was added as a 12-hr treatment on September 13-14. Substrates recovered on September 25 showed marked decreases in settling (Figures 2.

4, and 5), and some of the subsequent settling rates increased.

This may be an indication of at least a temporary period of effectiveness for this pulse treatment.

3.4 Beach Wa/k Sampling Beach walk analyses were conducted from July to November.

Two primary locations were examined on a regular basis. The first location is the beach adjacent to the Cook Nuclear Plant.

Since there is little hard substrate present on this beach. the type of substrate required for successful settlement of zebra 3-4

Figure 5 Service Water Lake Settling 20000 18000 16000-14000- X,V'C 12000-10000-O 8000-6000 4000 2000-0- LAKE NESW,3 wk Jul- ESW,3 wk Au Se NESW,6 wk g Se p

0 ESW,6 wk 03 No ct-V- No 14 V-05 25 Note: Lake settling data truncated at 20.000 for clarit

mussel post-veligers, the beach examination focused on searching for loose shells, or shells attached to loose stones or other debris. The second location is an area of limestone riprap along the south side of the south jetty at the mouth of the St.

Joseph River in St. Joseph.

On July 2, a 500 meter reach of the beach near the plant was walked. No zebra mussels or asiatic clams were obsess ed.

On July 30, the beach was again walked, but no organisms were observed. On August 1, the St. Joseph jetty was examined.

Zebra mussels were observed in crypts in the rocks in densities up to about 5 or 6 per cm>. Sizes ranged froni 700 pm to 3mm.

On August 14, the beach near the plant was examined, but no organisms were observed. At the St. Joseph jetty, zebra mussels in the same locations as seen on August 1 were observed in slightly increased densities (zero to 8-10 per cm>). No appreciable increase in size was observed.

On September 26, Christine Blundell of ERM. accompanied by Dr. Peter McCall of Geo-Science Associates, Inc.. examined both locations. On the beach, a large log about 300 m south of the plant revealed some zebra mussels, averaging 4mm in length.

with the largest at 8 mm. At the St. Joseph jetty, the mussels averaged 5 mm in length, and the largest were 8 mm.

Qualitatively, about 200 mussels covered a 20 x 25 cm rock.

Dr. McCall made recommendations to systematize the beach walk analyses; these are presented in his audit report (Appendix B). The recommendations were followed in subsequent beach walks.

On October 16, rocks north of the steel pilings by the plant revealed the sparse presence of zebra mussels, averaging 8 mm in length. At the St. Joseph jetty, mussels remained relatively rare, with the largest up to 1 cm in length.

On November 26, mussels were not observed on the rocks by the steel pilings, and may have been dislodged by the heavy surf during the preceding weeks. Drift wood on the beach revealed rare mussels, averaging 8 mm in length. At the St. Joseph jetty.

mussel abundances decreased relative to sumnier densities. but the survivors averaged 1 cm in length.

3-5

The beach walk examinations, although necessarily qualitative in nature because of the irregular nature of the sparse hard substrate, did,reveal valuable information. First, zebra mussels were observed beginning in late July. In the future, the zebra mussel will likely be a ubiquitous presence in the southern portion of Lake Michigan. The data also indicate that the mussels appeared to settle mainly on protected surfaces like the undersides or crypts of rocks. This would imply that areas of low flow or dead spots in the plant (e.g., the forebay area between Units I and 2) may experience the greatest fouling.

3.5 Inspection Samp/es Three inspection samples were collected by plant personnel and shipped 'o ERM for taxonomic analysis. Results of the inspection sampling analyses are presented in Appendix C.

3-6

SECTION 4 DISCUSSION AND CONCLUSIONS The results of the 1991 sampling of veliger densities in the circulating and service water systems, and adult settling rates in the same locations, clearly demonstrate the invasion of the zebra mussel in large numbers, relative to 1990 observations. Veliger densities in the service water systems (to some extent an indicator of planktonic veliger abundances in the nearby lake) showed densities exceeding 5,000/m~. Similarly, the settling of postveligers on artificial substrates in the forebay and in the service water systems exceeded 300,000/m>, and mirrored settling rates measured in the lake near the intake structures.

The seasonal pattern of abundance is reflected in the data on settling. Significant settling was observed in the first samples in July, and continued through October. Afterwards. measurable settling was observed through the last samples in late March 1992. Two possible sources for these winter-settling mussels were postulated. This late settling could have been derived from residual veliger populations in the lake that had spawned there late in the natural spawning season and were developing slowly because of the low water temperatures. Alternatively, the veligers could have been spawned from spawning adult populations within the plant water systems. The data were not sufficient to allow a discrimination between these possible causes. In any case, the winter settling densities were low. and the possibility of a major biofouling event (sufficient to restrict plant flows) is considered remote.

4-1

S ECTION 5 REFERENCES Greenberg, A., and P. McCall. 1991. Zebra mussel settling rates in municipal water supply intakes in southern Lake Erie. 1991 International Zebra Mussel Conference, Toronto, Ont. Canada.

February 1991.

Marsden, E. 1991. Standard Sampling Protocols for Monitoring and Sampling Zebra Mussels. Illinois Natural History Survey.

Center for Aquatic Ecology, Zion, Illinois.

5-1

Appendix A Directions for Construction of Plankton Collection Apparatus (for ES W and NES W Systems)

Directions for Assembling tne PlazQrton Collector The Plankton Collector is in three basic parts (Figure 1):

1. Top steel frame assembly

2. Bottom steel frame assembly with roller dolly

3. 55 gallon polyurethane can with 3 inch side drain (Note: Package contains two full assemblies plus a box with wheels, nuts, screws and tools. Read through each step before proceeding to assemble.)

Step 1 Steel Frame Assembly a) Lay top and bottom steel assembly on their sides.

b) Place the wheels in using the pins provided.

Note: On one steel bar on both the top and bottom sections, there are white lines; make sure that they line up. Each set of frames is uniquely fitted to each other. There is duck tape on the white marked pieces of one set.

Step 2 Attach the Top and Bottom Sections a) Place the bottom bar on the inner side and the top bar on the ou (Figure 2).

b) Attach 3 sets of bars onlvt c) Turn assembly upright.

Step 3 Fit 55 Gallon Can into Steel Assembly a) Place the 55 gallon can into the steel assembly through the opening by pushing the unattached bars aside.

b) Once the can is in the steel assembly, pull out on each bar so that the bottom bar clears the top of the can (Figure 3).

c) Attach the fourth set of bars with two screws and nuts. Place the top screw in Qrst and tighten. Then place the bottom in and tighten.

d) Once the can is in place and all the bars are attached, tighten all screws and nuts.

Figure 1: Three Mdn Sections of Qxe Plankton Collector I. Top Steel FrameAssembly , 2. Bottom Steel Frame Assembly with dolly

3. 55 Gallon Polyurethane Can with 3 inch drain 3 inch drain

Figure 2: Attachment of the top and bottom steel assemblies Top Steel Assembly Bar 0, Bottom-St."el Assembly.Kar

F~igure 3: Fitting Can into the Steel Frame Assembly Top Steel Bar Bottom Steel Bar Polyurethane Can

Step 4 Attach the 6 Foot Drain Hose a) Place one end of the 6 foot hose over the 3 inch bottom drain of can (Figure 4 - Diagram A).

b) Attach 2 hose clamps marked "Drain Hose Clamps" as shown in Figure 4 - Diagram B. Tighten screws in clamps.

c) Check for leaking around the pipe drain before the plankton collector is in full operation. If it does leak, make sure that the clamps are tightened. If the leak develops around the pipe itself, there is a tube of pipe corking enclosed which can be used to stop pipe leaks.

Step 5 Attach Pipe Inlet a) Using the 2 pipe clamps marked "Inlet Pipe Clamps", place them around the 2 inch PVC pipe and one of the top steel horizontal bars.

The PVC pipes were taped inside one of the cans. The pipe will have to be placed to one side of the vertical steel bar (Figure 5).

b) Place the clamp closest to the vertical bar between the two screws that attach the top steel bar to the "L" bracket (Figure 5).

c) Tighten the clamp screws.

d) Use the clamps marked "Inlet Hose Clamps" to attach the inlet pipe to the inlet hose at the facility. Note that there is a small and large hose clamp for each set. There are two sizes so that if the larger clamp does not fit completely around the pipe and hose, use both clamps together to increase its size.

Step 6 Attach Plankton Net a) Tie the strings from the plankton net to the "I" loop on the top center of the steel bars.

Figure 4: Drain Hose Connection

- Diagram A Drain Drain Hose Diagram B

~Clamps Drain Hose Drain

Figure 5: Inlet Pipe Attachment Horizontal Bar Pipe Clamps Quet Pipe Flow Vertical Bar

Appendi.x B Repor t o~s Cook Pla>>t Quality Visit prepared by Peter McCall, Ph.D.

GeoScie>>ce Associates, I>>c.

Report on Cook Power Plant Visit I visited the Cook Nuclear Power Plant in Bridgman, Michigan on September 26, 1991 and met with Christine Blendel to review procedures used in the examination of zebra mussel distribution in and around the plant. Christine appears to be a competent, careful, conscientious worker who is doing a very good job.

ettlement Plate Pr cedures The construction of the microscope slide plate holders is adequate. I was unable to see their operation in the field because all the plates had been pulled by the time that I mived. The only potential difficultyI saw was that all the glass microscope slides appear to be oriented in the same direction in their holder, and this may or may not be the most efficient orientation to promote settlement. However, since quite large numbers of veligers are settling out on the slides this year, this is most likely not going to be a problem. It is important of course that in the absence of evidence concerning the effect of slide orientation all comparisons be made of slides with the same orientation.

Christine's counting is accurate, but it could be made more efficient. She counts entire slides when the total mussel population is less than 50, and counts 'randomly'elected portions of the slide when the population is more than 50. I agree with the procedure, bu) I have a few suggestions. The delineation and selection of counted regions should be regularized. I suggest gluing some graph paper with numbered square regions to the underside

of a petri dish, and putting the glass slide into the petri dish. Now the slide is easily regionated and can still be moved around for counting. A random number table should be used to pick the regions to be counted.

I think at least 100 individuals should be sized (unless you size them all I neglected to discover this ) per sampler to get good length-frequency histogiams. Probably the first 100 individuals encountered should be selected for sizing to prevent bias. It is important to get Christine an ocular eyepiece micrometer for the dissecting scope. It is a large waste of tirade to pick individuals off the slide and place them onto your stage micrometer. These eyepiece inserts are pretty cheap. Fewer individuals can be counted maybe 30 if all you want is a decent estimate of maximum and mean size.

With regard to size-age relations, I have told Christine the following based on observations of Lake Erie populations: 1) ifyou find mussels greater than 7 mm or so at the beginning of the summer, they are from an overwintering population; 2) during the first two months after settling, we find growth rates of 0.7-0.9 mm/wk; 3)" this rate slows with time after settlement; 4) one year old individuals are commonly less than 20 mm maximum size; two year olds are commonly less than 30 mm; after this its difficult to say how old the individuals are axcept that they are 3+ years old. By the way, we find that the maximum size of individuals on the slides is about twice the mean size, which would mean that growth rates are linear over the sampling time (3 wks-2mos.), ifwe assume settling rate is constant. See ifyou find the same thing. Growth rates aren't really linear of course, but approximately piecewise linear over short time spans. I hope this is helpful for your age determinations.

Beach Wal The weather was pretty awful for beach walks gale force winds, 8-10 'eas, in the St. Joseph's river channel but we got some things accomplished nevertheless.

6'wells As before, there were no zebra mussels discovered in the immediate vicinity of the plant along the high water debris zone of the beach. We did find a 12'ong 9 inch diameter log washed ashore about 200 yards south of the plant that did have mussels attached to one side of it (

maximum size -10mm). We did locate a new site adjacent to the plant property that is worth visiting on a regular basis . It is a rubble zone of boulders located just nonh of the steel sea wall on the noah boundary of the plant's beach. There are some paicially submerged boulders that provide a suitable substrate for settling. We couldn't get a close look at these rocks because of the high waves.

The rubble zone on the south side of the St. Joseph river mouth is a good location to examine mussel growth. As you know, there is a population of mussels there. The largest individual was 12 mm, which indicates that all have settled within the last few months.

Coverage on the rocks is such that the use of meter square wads or point counts along linear transects to get percent cover are useless. The mussels are relatively few and crowded onto sheltered pcs of rocks in cryptic habitats. The best technique I can suggest is a variation of what paleontologists sometimes do to estimate fossil abundance at rock outcrops: Search for a fixed time at a site ( -30 minutes), estimate abundances, and use log abundances for comparisons. Maximum individual shell length can be measured and mean shell length can be estimated. A site like the St. Joseph River site south of the plant wouls be useful. I drove several miles south of the plant at the end of the day and searched the shoreline, but I found no good locations. I think we might have to go all the way to Michigan City to find a suitable

southern site at which to monitor in situ growth, unless there are some rivers with jetties at their mouths in between.

Plankton Work We did no plankton work on this visit. The net was not available, and anyway, it would have been unsafe to use it in those seas.

Appendix C Data Report on Taxonomy of Three Inspection Samples p>'epa>'ed by Cove Co~ potation Lushy, MD

'I '*

Rypy<

I I

E~ - PC C~eo ~>/a~ l)A'I'I::

V~I,e of I

hTIOH HO: I.N:A'I'1OI(;

I)I'.I "I'l; Zo~~4 or<,P JM stalls ov; Curl) Hv.

P5 j 90/ ~JSI O XA c;PI'.( I I.'S c-n 4 0 r ~ ~

~ r

/ ro t

,+ ('~ e~J44zg

~ ~ ~ ~ ~ e

~ M r rI /

a I I i ~

a-, o(= .S~ ~pl 7y scr..l- dg /

~)~hajj S~plp .. u'pg; P'l<<

2p SYrIIc At 5'7/)/Pg 4/ ..@8~.. @ac c

~ I

)(

~ ~ a

~ r

~ ~

'I ~ + . ~

~ ~

APPENDIX VI ANNUAL REPORT: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1991

DONALD C. COOK NUCLEAR PLANT UI%1TS 1 &2 OPERATIONAL RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM 1991 ANNUAL REPORT JANUARY 1 to DECEMBER 31, 1991 Prepared by INDIANAMICHIGAN POWER COMPANY BXld TELEDYNE ISOTOPES April 15, 1992

TABLE OF CONTEN QE(~TIQN TITLE PAGE Sun1IIlary o ~ ~ o ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~

o ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ 1 I Introduction ..........'.................................... 3 II, Sampling and Analysis Program.............................. 5 III. Summary and Discussion of 1991 Analytical Results ~ o o ~ ~ ~ ~ ~ e ~ ~ 1 5 A. Airborne Particulates . 16 R AllbOn1e IOdine ~ ~ ~ o o ~ o o ~ o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ o 1 8 C Direct Radiation - TLDs.......................... 19 D. Surface Water ........................

E.

F Ground/Wen Water.............................

Drinking Water................................

0 G. Sediment............ ~ ~ ~ o ~ ~ ~ o ~ ~ ~ o o o ~ ~ ~ ~ ~ ~ 25 H ~ Milk ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ o o ~ ~ o ~ 25 I

I FiSll o ~ ~ ~ o ~ ~ ~ ~ ~ o o ~ ~ o ~ ~ o e ~ ~ ~ ~ o o o o ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ e o 26 J. Food Products........... ~ e o ~ ~ ~ o ~ ~ o ~ o ~ o o 26 Conclusions.............. ~ ~ o ~ ~ ~ ~ ~ ~ ~ o ~ o ~ o ~ e ~ ~ o ~ 28 V. R eferences .............................................. 32

TABLE OF ONTENTS (Cor.t)

A~PPENDE IE APPENDIX A - Radiological Environmental Monitoring................. 34 Program Summary - 1991 APPENDIX B - Data Tables ......................................... 39 APPENDIX C - Analytical Procedures Synopsis ........................ 66 APPENDIX D - Summary of EPA Interlaboratory Comparisons ........ 80 APPENDIX E - REMP Sampling and Analytical Exceptions............. 107 APPENDIX F - Land Use Surveys................................... 110 APPENDIX G - Summary of the Preoperational Radiological......... 117 Monitoring Program APPENDIX H - Summary of the Blind Duplicate Sample Program ....... 121 APPENDIX I - Summary of the Spike and Blank Sample Program....... 123 APPENDIX J - TLD Quality Control Program ......................... 135

F'4 ish Locations ..

TABLE OF CONTENTS (Cont)

Land Based Locations TLD Locations MlkAnlmalSurvey531e LIST OF FI URES Air, Well and Lake Water

~ ~

Locations.......................

~ ~

Residental Land Use Survey Table Milk Farm Survey Map Residential Survey

~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ ~ ~

~ ~ ~

~ ~ o o ~ o o o ~ ~ o ~ ~ o ~ ~ o ~ ~ o ~

~ ~ ~

Map...................................

~ . ~ ~ ~ ~ o ~ o ~ ~ o 1

11 12 1

13 114 115 116 3

LIST OF TRENDING GRAPHS Average Monthly Gross Beta in Air Particulates .................. 17 Direct Radiation - Quarterly TLD's............................. 20 Tritium in Ground/Well Water ..............-... . 22 Tritium in Drinking Water ................................... 24 U.S. EPA Cross Check Program ............................... 86 Quality Control TLDs .................................. 137

LIST OF TABLES ABLE TITLE PAGE B-1 Concentrations of Gross Beta Emitters in Airborne Particulates Weekly............ 40 B-2 Concentrations of Gamma Emitters in Quarterly..................

Composites of Airborne Particulate Samples 44 B-3 Concentrations of Iodine-131 in Weekly Air Cartridge............. 46 Samples B-4 Direct Radiation Measurements - Quarterly TLD Results........... 50 B-5 Concentrations of Iodine, Tritium and Gamma Emitters........... 51 in Surface Water Concentrations of Tritium and Gamma Emitters in Quarterly Groundwater

............... 54 B-7 Concentrations of Gross Beta, Iodine, Tritium Gamma Emitters in Drinking Water and................ 55 B-8 Concentrations of Gamma Emitters in Sediment ................. 57 B-9 Concentrations of Iodine and Gamma Emitters in Milk............ 58 B-10 Concentrations of Gamma Emitters in Fish ...................... 62 B-11 Concentrations of Gamma Emitters in Food Products ............. 63 B-12 'Pypical LLDs Achieved.................................... 64

INDIANAMICHIGAN POWER COMPANY DONALD C. COOK POWER NUCLF~ PLANT I L I AL ENVIR NMENTAL M NIT RIN PR RAM This report summarizes the collection and analysis of various environmental sample media in 1991 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 ground water does not provide a direct dose pathway to man.

NTR D TI N The Donald C. Cook Nuclear Power Station's Radiological Environmental Monitoring Program (REMP) is conducted in compliance with NRC Regulatory Guide 1.21 and 4.1, licensing commitments, and Technical Specificagons. 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. 'Ihis 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, 1991 through December 31, 1991.

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 hGVE and Unit 2, 1100 MVE. Unit 1 achieved initial criticality on January 18, 1975 and Unit 2 achieved initial criticality on March 10, 1978.

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

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

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

3. Provide reasonable assurance that the predicted doses, based on eQluent 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 compl'.ance.

II. SAMPLING AND ANALYSIS PROGRAM Table I summarizes the sampling and analysis program for the Donald C. Cook nuclear plant for 1991. For each sample medium, the table lists the sample locations, including distance and direction from the center of the two units, and the station identification. The station identiQcations for many of the sampling locations are shown on the maps, Figures 1, 2, and 3. Also for each sample medium the sample collection frequency, type of analysis, and frequency of analysis are listed.

TABLE i DONALD C. COOK NUCLEAR PLANT- 1991 RADIOLOGICALSAMPLING Sl'ATIONS DISI'ANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Direction De rees Fre uen en Environmental TLD's ONS-1 (A- I) 1945 fL 180 ONS-2 (A-2) 2338 fL 48'04 ONS-3 (A-3) 2407 fL ONS-4 (A-4) 1852 IL 1180 ONS-5 (A-5) 1895 IL ONS-6 (A-6) 19'17 IL 189'10'60

.ONS-7 (A-7) 2103 IL ONS-8 (A-8) 2208 IL 820 ONS-9 (A-9) 1368 fL 149o ONS-10 (A-10) 1390 fL 1270 ONS-11 (A-11) 1969 fL I 14 ONS-12 (A-12) 2292 IL 63'ew Buffalo (NBF) 16.0 ml SSW Quarterly Direct Radlatlon/Quarterly South Bend (SBN) 24.0 ml SE Dowaglac (DOWJ 24.3 ml ENE Coloma (COL) 18.9 ml NNE Intersection of Red Arrow Hwy. 8c Marquette (OFS-1) 9.5 ml NNE Woods Rd, Pole ¹B294-44 Stevensville Substatlon (OFS-2) 3.6 ml NE Pole ¹B296-13 (OFS-3) 5.1 ml NE Pole ¹B350-72 (OFS-4) 4.1 ml E Intersection of Shawnee Bc Cleveland, Pole (OFS-5) 4.2 ml ESE

¹B387-32 Snow Rd., East of Holden Rd.. (OFS-6) 4.9 ml SE

¹B426-1 Brldgman Substatlon (OFS-7) 2.5 ml S Callfornla Rd., Pole ¹B424-20 (OFS-8) 4.0 ml S Rlggles Rd.. Pole B369-214 (OFS-9) 4.4 ml ESE Intersection of Red Arrow Hwy., 8c (OFS-10) 3.8 ml S Hlldebrant Rd..Pole ¹B422-152 Intersection of Snow Rd. 6 Baldwin Rd., (OFS-11) 3.8 ml Pole ¹B423-12

TABLE 1 {Cant.l DONALD C. COO PLANT- 1991 RADIOLOGIC PLING STATIONS DISTANCE AND DIRECTION FROM PIANT AXIS Collection Location Station Distance Direction De rees uen Is/Ebe n Air Charcoal/Particulates ONS-I (A- I) 1945 fL ONS-2 (A-2) 2338 fL 18'8'04 ONS-3 (A-3) 2407 fL ONS-4 (A-4) 1852 fL 118'890 ONS-5 (A-5) 1895 fL ONS-6 New Buflalo (A-6)

(NBF) 1917 16.0 ml IL-SSW 210'eekly Gross Beta/Weekly 1-131/Weekly South Bend (SBN) 24.0 ml SE Gamma Isotopic/

Dowaglac (DOW) 24.3 ml ENE Quarterly Composite Coloma (COL) 18.9 ml NNE Ground/Well Water Onslte (W- I) 1969 fL 11'3o Onsltc (W-2) 2292 fL Onsltc (W-3) 3279 fL 1074 Onslte (W-4) 418 fL Gamma Isotopic/Quarterly Onslte Onslte (W-5)

(W-6) 404 424 fL fL 189'uarterly 301'900 2730 Trltlum/Quarterly .

1-131/Quarterly Onslte (W-7) 1895 fL Non Technical S ciflcation Related%'elis Steam Generator Storage Faclllty (SGRP- I) 0.8 mlle 950 Steam Generator Storage Faclllty (SGRP-2) 0.7 mlle Steam Generator Storage Faclllty (SGRP-4) 0.7 mlle 92'3'20 Quarterly Gross Beta/Quarterly Gross Alpha/Quarterly Steam Generator Storage Faclllty (SGRP-5) 0.7 mlle Gamma Isotopic/( uarterly I-131/Quarterly

TABLE 1 {can<.I DONALD C. COOK NUCLEAR PLANT- 1991 RADIOLOGICALSAMPLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Station Distance Direction De rees Fxe uen /Pre en Drinki Water St. Joseph Public Intake (STJ) 9.0 ml NE Gross Beta/14 Day Compos l te Gamma Isotopic/14 Day Composite I-131/14 Day Composite Lake Township Public Intake Stat!on (LTW) 0.40 ml S Trlttum/Quarterly Composite Surface Water Condenser Ctrculatlng Water Intake Ll Lake Mlchlgan Shoreline L-2 0.3 ml S Dally Gamma Isotopic/Monthly Lake Mlchlgan Shoreline L-3 0.2 ml N Composite Lake Mlchlgan Shoreline L-4 0.1 ml S Trltlum/Quarterly Composite Lake Mlchlgan Shoreline L-5 0.1 ml N 1-131/Monthly Composite Sediment Lake Mlchlgan Shoreline L-2 0.3 ml S Lake Mlchlgan Shoreline L-3 0.2 ml N Semi-annually Gamma Isotopic/Seml-Lake Mlchlgan Shoreline L-4 0.1 ml S Annually Lake Mlchlgan Shoreline I 5 0.1 ml N Milk Totzke Farm Bared a Totzke 5.1 ml ENE Wyant Farm Dowagalc Wyant 20.7 ml Schuler Farm Bared a Schuler 4.1 ml SE Llvlnghouse Farm La Porte Llvlnghouse 20.0 ml S Once per every Gamma Isotopic/per Sample Warmblen Farm Three Oaks Warmblen 7.7 ml S 14 Days l-131 per Sample Zelmer Farm Brldgman Zelmer 4.8 ml SSE Gallen Lozmack 9.5 ml

T (Cmt.)

DONALD C. COO PLANT- 1991 RADIOLOGICAL PLING STATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Dlrectlon De rees uen Lake Michigan ONS-N .3 mi N Semi-annually Gamma Isotopic/

Lake Michigan ONS-S .4 ml S Semi-annually Lake Michigan OFS-N 3 .5ml N Lake Michigan OFS-S 5.0 ml S Grapes, Grape Leaves, Olfslte Indicator Plant site Determined from,offsite Grapes. Grape Leaves. Offsite Control 20 mlles Dose CalculaUon manual At Ume of harvest Gamma Isotopic/

Broadleaf Vegetation Onsite Plant site At time of harvest Composite samples of Drinking and Surface water shall be collected at intervals not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ParUculate sample filter should be analyzed for gross beta activity 24 or more hours following filte removal. This will allow for radon and daughter decay. If gross beta acUvity In air or water is greater than 10 Umes the yearly mean of control samples for any medium, thoron analysis should be performed on the individual samples. gamma isotopic Please note the following deienlUons:

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

Figure 1 20 MILE'S P Air, TLD Stations L Lake Water Sample Stations (lntakes)

A'qWatervliet M Milk Sample Stations BENTON HARBOR. ia~:

ST. J PH. <

Stev~ensvt e Eav I D. C. COOK Claire DOWAGIAC PLANT I r Bridgrnan 8errien M Springs I

44 4'I

/

ss

/

/

/

p /

New Buffal NILES @ /

Vs

!2 A MIC'HIGAN

,'A

~r'Ve I/VDIAA'A h1ICHIGAhk,'. New CITY,:",".'~,.:,, Carlisle 20 pp us 20 ',

It!02 Ng . "~.,'. "o.

SOUTH "@k@j BEND IO 20 SCALE OF MILES 11

TRuE PLANT NORTH NORTH UNR E STRICTEO A R EA PROPERT Y LINE

= L3 - " -"~y Lola h-7 R0AO O'Ich/ gan 1 5 h-I2 LI N2

=-N TRACV A-8 IA ~A('AILROAO I

~EW PLANT

/

I I

t A~

SGRP-5 SGRP-g SGRP-2 SGRP-1

+

js""

SHORE LINE r65av rr N-S YARD PLAINT L2 h-9 A-la g~4 CHESAPEAKE 8 OHIO R.R.

r r.

A6 ] ~ 2,DOQ FQQT e-:.@m.,;;.,:,:,. -A5 RADIUS A - Air, 'I'I,D BamPIc'. Stations

~A-7 thru A-I2 are TI.D M Mel I Mat,er Stations OcIIy)

Sample Stations 0 Iooo I ake M tt.er Sedimc.nt 2000 3000 S Implc Oooo vEn (I I is a I akc. Matc I stat>on Only)

B()III' Non Tcwh Spe>> Mel I Mater

! XAI,I'. Stations

Figure 3 OFS-1 TLD Stations Within 1-5 Mile Radius of Plant eo OPS-3 R C

OFS-3 I

I I

VILL, z OKRSY IIOCKY WACO IIOAO 0 VR I4 2.0 miles OPS-4 MA DICHO I

I Hl AN R I

IIOAO OPS-9 I 0

C CRE KA OPS-5 OFS-7 Z

laJ 0 bRIDOMA I 0 I gg 4 I I

8 0 q SXAI.A ROAO I

J M I

OPS-1 li~

0 ~ c geg A OPS-8 OFS-.6 I0

/ PS-1 x

0 OTT RO.

0 CC 8 IIOWN TOWN ROAO 13

I I

I II I I

-lRSPFl" II .<il,B (WANjr%%~

i . ".t.'8, ~ > g t

.i/ Ku"-,~

I~

e I

~i~

I El&

~

a

III.

SUMMARY

AND DISCUSSION OF 1991 ANALYTICALRESULTS 15

MMARYAND Dl C S I N OF 1 1 ANALYTI AL RES L 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 1991 were analyzed by Teledyne Isotopes, Inc. (TI) in Westw'ood, 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 characteristically

~

approach and frequently fall below the detection limits of state-of-the-art 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 I, 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. Air pm P i ul e Airborne particulate samples are collected with a constant flow oil less pump at 2.0 CFM using a 47 mm particulate filter. Results of gross beta activities are presented in Table B-1. The measurement of 16

Trending Graph - 1 AVERAGE MONTHLY GROSS BETA IN AIR PARTICULATES 25

/

O~'g tg ~ '/ '. ~

.'+

15 10 5

0 89 '9 01/, 04/ 07/

89 10/

89

. 01/

90 04/

90 07/

90 10/

90 1/

91 4/

91 7/

91 10/

91 1/

92 Indicators ---4--- Controls 0 0

the gross beta activity on the weekly air particulate filters is a good indication of the levels of natural and or manmade radioactivity in the environment. The average gross beta concentration of the six indicator locations was 0.017 pCi/m3 with a range of individual values between 0.002 and 0.033 pCi/m3. The average gross beta concentration of the four control locations was 0.018 pCi/m3 with a range between 0.004 and 0.039 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 1991 were lower than at the end of the preoperational period when the effects of the 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 0.100 pCi/m3 and the values ranged from 0.058 to 0.136 pCi/m3. The average concentration for the indicator locations was 0.102 pCi/m3 with a range of 0.063 to 0.137 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 three of the twenty-four indicator quarterly composites with an average concentration of 0.009 pCi/m3 and a range of 0.004 to 0.012 pCi/m3.

Potassium-40 was not measured in any of the sixteen control quarterly composites. No other gamma emitting radioactivity was detected.

B Airborne Iodine Airborne particulate samples are collected with a constant flow oil less pump at 2.0 CFM using a 47 mm particulate filter. Charcoal cartridges are installed downstream of the particulate filters and are used to collect airborne radioiodine. The results of the weekly analysis of the charcoal cartridges are presented in Table B-.3. All results were below the lower level of detection with no positive activity detected.

18

C Direct Radiation - Thermolumines ent Dosimeters Thermoluminescent dosimeters (TLDs) measure exter 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 the exposure from all of these potential sources.

The TLDs are deployed quarterly at 27 locations in the environs of the D. C. Cook Nuclear Plant site. The average value of the readings of the four areas of each dosimeter (calibrated individually after each field exposure period for response to a known exposure and for intransit 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 measurement for the 16 control samples was 4.07 mR/standard month and a range of 2.8 to 5.4 mR/standard month.

The 92 indicator samples had a measurement of 4.28 mR/standard month and a range of 2.3 to 6.5 mR/standard month. The 1991 annual average in the environs of the D. C. Cook plant is at the l range of the exposure rates (1.0 to 2.0 mR/week) measured during th preoperational period. The results of the indicator and control TLDs are in good agreement and are plotted in Trending Graph 2.

D. S~DW Lake Michigan one liter surface water samples from the condenser circulating water intake 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 76. The quarterly composite was analyzed for tritium by gas counting according to the procedure described on page 71 No iodine-131 was detected.

~

Naturally occurring potassium-40 was measured in one sample with an activity of 40.6 pCi/liter. Cobalt-60 was also measured in one sample with an activity of 3.71 pCi/liter. Tritium was detected in 15 of the 20 samples analyzed with an average concentration of 239 pCi/liter and 19

0 Tren Graph - 2 DIRECT RADIATION- QUARTERLY TLD RESULTS

,6

'4 0

01/90 04/90,, 07/90 10/90 01/91 04/91 07/91 10/91 0 TLD Controls TLD tndicators

range of 130 to 400 pCi/liter. This is slightly lower than the average concentration in 1990 of 254 pCi/liter. During Ae preoperation period tritium was measured in surface water samples concentrations of approximately 400 pCi/liter. Naturally occurring gamma emitting isotopes were detected by gamma ray spectroscopy.

E. Gr un ell Water Water samples are collected quarterly from seven 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 an air driven bladder style pump. A one gallon sample is then obtained. The samples are analyzed for gamma emitters and for tritium. The results are presented in Table B-6. Naturally occurring potassium-40 was measured in one sample with a concentration of 57.2 pCi/liter. No other gamma emitting isotopes were detected. The on-site wells 4, 5, and 6 had measurable tritium activity throu'ghout 1991. However, these measurements are lower than those detected during 1989 and 1990. Tritium was measured in three of the sixte samples at the off-site locations with an average concentration of 103 pCi/liter and a range of 210 to 1700 pCi/liter. The annual concentrations of tritium in the seven wells are plotted from 1979 through 1991 in Trending Graph 3.

Tritium concentration in wells in the preoperational period were typically about 400 pCi/liter.

F.

Daily samples are collected at the intake of the purification plants for St. Joseph and Lake Township. The 500 ml daily samples at each location are composited and analyzed for gross beta, iodine-131, and for gamma emitters. On a quarterly basis the daily samples are composited and analyzed for tritium. The results of analyses of drinking water samples are shown in Table B-7.

21

Trendi aph - 3 TRITIUM IN GROUNDhhfELL WATER

.5000

'000 3000 O-0 ~

20,00 Po s 0"

L

=

1000

": 0'9SO

": 1981 1982 =

1983 . 19S4, 1985 1986 19S7 =

1988 1989 -

1990 ', 1991

Trending Graph - 3 (Cont.)

TRITIUM IN GROUND/WELL WATER 10000 8000 6000 4000 2000 0

19SO 1981 1982 1983 1984 1986 1986 1987 19SB -

1989 1990 1991 Well< Well-6 Well< Well-7

ding Graph-4 .

TRITIUM IN DRINKING WATER 2000 1500 1000 r

r r

r rr rr 500 r

+I serrr I ~ ~ ~ ~ I~ ~ ~~

IllI ~~ ~ ~ ~ ~ ~

~~ pry>

A We al ~ ~~ ~ ~ 'LO

~ ~

~ ~ ~

INg qadi ~~

tr@os 0

01/89 '4/89' 07/89. 10/89 '1/90 04/90" ~

07/90 '0/90 '1/91'4/91 10/91

~ -- 6 --- Lake Township A St. Joseph

Gross beta activity was measured in all twenty-six samples from the Lake Township intake with an average concentration of pCi/liter and a range from 2.8 to 8.3 pCi/liter. Gross beta activity measured in all twenty-six samples from the St. Joseph intake with an average concentration of 4.1 pCi/liter and a range from 2.2 to 6.9 pCi/liter. No gamma emitting isotopes or iodine-131 were detected.

Tritium was measured in three of the four samples from Lake Township intake with an average concentration of 197 pCi/liter and a range of 180 to 230 pCi/liter. Tritium was measured in two samples from St. Joseph intake with an average activity of 185 pCi/liter and a range of 160 to 210 pCi/liter. Tritium in drinking water is plotted in Trending Graph 4.

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

G. +.dim~~n Sediment samples are collected semiannually along t shoreline of Lake Michigan at the same four locations as the surfac 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 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 5861 pCi/kg with a range from 4960 to 6740 pCi/kg. Thorium-228, also naturally occurring was measured in seven of the eight samples with an average concentration of 121 pCi/kg with a range from 89.0 to 157 pCi/kg. Cesium-137, attributed to fallout from previous atmospheric nuclear tests, was detected in one of the eight samples with an activity of 37.5 pCi/kg. That activity level is often observed in soils and sediments. All other gamma emitters were below their detection levels.

25

H. Milk Milk samples of one gallon are collected every fourteen days from seven farms located between 4.1 miles and 20.7 miles from the site. The samples are analyzed for iodine-131 and for gamma emitters. The results are shown in Table B-9. Iodine-131 was not measured in any of the 175 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 1991. Iodine-131 was measured in four samples collected soon after an atmospheric nuclear test with concentrations between 0.2 and 0.9 pCi/liter. Cesium-137 was measured in numerous samples after the nuclear test with concentrations between 7 and 64 pCi/liter.

During 1991 the average potassium-40 concentration for the control locations during was 1243 pCi/liter with a range of 688 to 1410 pCi/liter, The indicator locations had an average concentration of 1315 pCi/liter and a range of 881 to 1600. There were no detections of iodine-131 during 1991. Cesium-137 was detected in one control sample with an activity of 4.73 pCi/liter. There were two measurements of cesium-137 in indicator samples with an average of 6.11 pCi/liter and a range of 3.29 to 8.93 pCi/liter.

I. Fish Using gill nets in twenty feet of water in Lake Michigan, 4.5 pounds of fish are collected semiannually from each of the 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 2609 pCi/kg (wet weight) and a range of 2040 to 3190 pCi/kg (wet weight). Cesium-137, attributed to previous atmospheric nuclear tests was measured in one of the eight fish samples with a concentration of 65.8 pCi/kg (wet weight).

26

J. F Pro uc Food samples are collected annually at harvest, as near the s boundary as possible, and approximately twenty mQes 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 samples with an average concentration of 2852 pCi/kg (wet weight) and a range of 1710 to 3880 pCi/kg (wet weight).

Cosmogenically produced beryllium-7 was measured in three of the five samples with an average concentration of 914 pCi/kg (wet weight) and a range of 906 to 920 pCi/kg (wet weight). Cesium-137 was measured in one sample with a concentration of 45.1 pCi/kg (wet weight).

?7

IV. CONCLUSIONS 28

N I The results of the 1991 Radiological Environmental Monitor 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 signiQcant dose consequence. Specific acarnples of sample media with positive analysis results are discussed below.

Air particulate gross beta concentrations of all the indicator locations for 1991 appears to follow the gross beta concentrations at the control locations. The concentration levels are actually lower than during the preoperational period when the inQuence of atmospheric nuclear tests was being detected. Gamma isotopic analysis of the particulate samp identified the gamma emitting isotopes as natural products (beryllium-7 potassium-40). No man-made activity was found in the particulate media during 1991. No iodine-131 was detected in charcoal fQters in 1991.

Thermoluminescent dosimeters (TLD) 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 potential radioactive airborne releases and direct radiation from the power station. The average annual TLD results were at normal background exposure levels.

Surface water samples collected monthly from five locations in Lake Michigan were analyzed for iodine, tritium, and gamma emitting isotopes.

Only one gamma emitter, cobalt-60 was detected in one sample during 1991. Tritium was measured and the concentrations were at normal background levels.

29

Ground water samples were collected quarterly at seven wells, all within 1009 meters of the reactors. The three wells within 130 meters had measurable tritium which is attributed to the operation of the plant. The tritium levels in 1991 compare well with those measured in 1990. The highest concentration measured in 1991 was 1700 pCi/liter which was also the highest measured in 1990. The tritium levels in ground water have been plotted for the last decade and indicate decreasing levels of tritium.

Potassium-40, a naturally occurring nuclide was observed in one sample during 1991. 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 samples with background levels that were lower than those measured during 1990.

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, Cesium-137 was measured in one sample during 1991. No other 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 seven farms up to a distance of 20.7 miles from the site, The samples were measured for iodine-131 and for gamma emitting isotopes. Although I-131 was measured during 1989 there were no measurements of iodine-131 in milk in 1990 or 1991. Potassium-40 was measured in all milk samples at normal background levels. Cesium-137 was detected in two samples.

Fish samples collected in Lake Michigan in the vicinity of the nuclear plant were analyzed by gamma ray spectroscopy. The only gamma emitting

'sotope measured was cesium-137 which was in very low concentrations, 30

typical of those found in other parts of the country and which are attributed to previous atmospheric nuclear tests.

Food products, consisting of grapes, grape leaves, and broadleaf vegetation were collected and analyzed by gamma ray spectroscopy. The only gamma emitting isotope measured was cesium-137, again attributed to previous atmospheric nuclear tests.

The results of the analyses have been presented. Based on the evidence of the radiological environmental monitoring program the Donald C. Cook nuclear plant appears to be 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 ground water does not provide a direct dose pathway to man.

31

V. REFERENCES 32

V. REFERENCES

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

2. Indiana Michigan Power Company, D. C. Cook Technical SpeciQcations. 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 EQluents from Light-Water-Cooled Nuclear Power Plants, April 1974.

33

APPENDIX A RADIOLOGICALENV'IRONMENTALMONITORING PROGRAM

SUMMARY

34

RADIOIAMIChLENVIRONMENTALMONITORINO PROGRhM SUMMhRY INDIhNh MICHIGhNPOWER COMPANT - DONhLD C. COOK NUCLEhR PLANT DOCKET NO. QUIS/50-316 BERRIEN COUNIY JANUARY 1 to DECEMBER 31. 1991 MEDIUM OR PATHWAY TOTAL NUMBER CONTROL LOCATION NONROImNE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REpo RIED (UNIT OF MEASUREMENII PERFQRMED RANGE DISI'ANCE AND DIRECIION RANGE RANGE MEASUREMENT!

hir Iodine 1-131 519 -(0/311) N/A N/A -(0/208)

(pCI/m3) hirborne Gross Beta 519 17. 1(31 1/31 1) SBN 24 ml SE 18. 1(52/52) 17.8(208/208)

Particrrlates (Weekly) (2.4-33) (8.6-35) (4.2-39)

(lE-03 pCl/m3)

Gamma 40 Bc-7 40 101.7(24/24) ONS-5 578 m 1 13.4 (4/4) 99.8(16/16)

(63. 1-137) (82.4-137) (57.8- 136)

K-40 40 8.87(3/24) ONS-6 12.4(1/4) -(0/16)

(3.82-12.4)

Direct Ibldlation Gamma 108 (mR/Standard Dose 4.28(92/92) OFS-6 5.25(4/4) 4.07(16/16)

Month) Quarterly (2.3-6.5) (4.4-5.7) (2.8-5.4)

(a/b) of samples with detectable acthrlty to total number of samp yzed.

RhDIOLOGICALENVIRO MONITORING PROGRAM

SUMMARY

INDIhNAMICHIGANPOWER COMPANY - DO C. COOK NUCLEAR PLhNT DOCKET NO. 60-316/

BERRIEN COUNIY JANUARY I to DECEMBER 31. 1991 MEDIUM OR PATIPVAY TVI'ALNUMBER CONIROL LOCAIION NON ROIJIINE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORTED IUNTI'F MEASUREMENI) PERFORMED RANGE DISI'ANCE AND DIRECTION RANGE RANGE MEASUREMENI".

Surface Water Gamma 57 (pCl/liter)

K-40 57 40.6(1/57) I 5- 0.1 ml NNE 40.6(1/11) -(0/0)

Co-60 57 3.71(1/57) 3.? 1(1/13) -(0/0)

H-3 20 239(15/20) L-3 0.44 ml N 303(3/4) -(0/0)

(130-400) (200-400)

Ground Water Gamma 28 (p Cl/1lter)

K-40 57. 2(1/28) Well 6 57.2(1/4) -(0/0)

H-3 28 783(11/28) Well 7 1450(2/4) -(0/0)

(210-1700) (1200-1700)

Drinking Water Gross Beta 52 4.2(52/52) LTW 0.40 ml S 4.3(26/26) -(0/0)

(pCl/liter) (2.2-8.3) (2.8-8.3) 1-131 52 -(0/52) N/A N/A -(0/0) 52 -(0/52) N/A N/A -(0/0)

H-3 192(5/8) LTW 0.40 ml S 197(3/4) -(0/0)

(1 60-230) (180-230)

(a/b) Ratio of samples wtth 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 I to DECEMBER 31. 1991 MEDIUM OR PATIIWAY TIALNUMBER CONTROL LOCATION NONROtrnNE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORIED IUNK OF MEASUREMEND PERFORMED RANGE DISTANCE AND DIRECFION RANGE RANGE MEASUREMENT!

Sedtment Gamma 8 (pCI/kg dry)

K-40 8 586 1(8/8) L-5 6450(2/2) No Control (4960-6740) 0.1 ml NNE (6160-6740)

Cs-137 8 37.5(1/8) L-4 37.5(1/2) No Control 0.1 ml SSW Th-228 8 121(7/8) L-5 153(1/2) No Control (89.0-157) 0.1 ml NNE MHk Gamma 182 (pCI/liter)

K-40 182 1315(130/130) Totzke 1374 (26/26) 1243(52/52)

(881-1600) 5.1 ml ENE (931-1600) (688-1410) 1-131 182 -(0/130) N/A -(0/52)

Cs-137 182 6. 1 1(2/130) Zelmer 6. 1 1(2/26) 4.73(1/52)

(3.29-8.93) 4.8 ml SSE (3.29-8.93)

(a/b o of samples wtth detectable acttvlty to total number of sa nalyzed.

RADIOLOQICALENVIRONHE ONITORINQ PROQRAH SUHHhRF INDIANAHICHIQANPOWER COHPANY - DO ~ COOK NUCLEAR PLANT DOCKET NO. ~16/60-BERRIEN COUNIY JANUARY 1 to DECEMBER 31, 1991 MEDIUM OR PATHWAY 1X7I'AL NUMBER coNmoL LocATloN Noi'RQUriNE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORIED IUNIl'FMEASUREMENII PERFORMED RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Hsh (pCI/kg wet)

K-40 2609(8/8) OFS-North 2875(2/2) -(0/0)

(2040-3190) 35ml N (2800-2950)

Cs-137 65.8(1/8) OFS-North 65.8(1/1) -(0/0) 5.0ml N Food/Vegetation GaItuna (pCl/kg wet)

Be-7 914(3/5) Sector J 914(3/5) -(0/0)

(906-920) Variable (906-920)

K-40 2852(5/5) Sector J 2852(5/5 -(0/0)

(1710-3880) Variable (1710-3880)

Cs-137 45.1(1/5) Sector J 45. 1(1/5) -(0/0)

Variable (a/b) Rauo of samples with detectable acUvlty to total number of samples analyzed.

APPENMX B DATATABLES 39

LE B-1 INDIANAMICHIGANPOWER C ANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMITIERS IN WEEKLY AIRBORNE PARTICULATES Results in Units of 10 3 pCI/m~ 2 2 sigma STATION CODES COLLECTION A-1 A-2 A-3 A-4 A-5 A-6 Colo ma Dowaglac New Buff South Bend Average DATES 2 2 sod, JJQU+gg~

01/07/91 27k 2 27%2 24%2 27k 2 2822 26 k 2 28 2 2 22%2(a) 25k 2 30 % 2 26' 01/14/91 01/21/91 26k 2 301 2 27%2 33%2 27%2 33%2 28k 25k 2

2 26t2 31%2 t

23 2 29 2 2 25 k 2 33%2 3923 27k 2 24 k 2 27% 9 34 2 2 35 k 2 35 k 2 32k 6 01/28/91 22k 2 2322 21%2 23k 2 23%2 21 k2 23 2 2 t 24 2 24 2 2 19 a 2 22 t 3 02/04/91 21% 2 22 k 2 21t2 22+ 2 2222 22 k 2 23%2 23 t2 22 2 2 23 k 2 22k 2 02/11/91 02/18/91 23k 2 13% 2 23 k 2 12 k 2 24t2 11%2 22k 131 2 2 19t2 1312 8a2 11%2 23%2 13 k 2 19 + 2 12 k 2 19 i 2 13 2 2 20m 2 14 R 2 20% 9 13k 2 c0 02/25/91 03/04/91 23k 2

.Ijx t

20 2 16%2 18k 2 19%2 17 X 2 19%2 1812 20% 2 16 k 2 19% 4 2 20 R 2 19%2 14% 2 18%2 14 2 2 18 k 2 24%3 (b) 17% 2 16+ 2 182 6 03/11/91 23k 2 26%2 23%2 26% 3 24%2 2122 23%2 27 2 2 26k 2 24+2 24k 4 03/18/91 11+ 2 10%2 (c) IOX 2 12%2 922 8%2 13 2 2 12% 2 10 k2 11% 3 03/25/91 ISa 2 17+2 15%2 17% 2 16%2 16t2 17%2 17 k 2 20% 2 15+ 2 17% 3 04/Ol/91 11% 2 20t2 19%2 20% 2 1712 16%2 17%2 16 k2 17% 2 17' 17% 5 QuartetAvg. 202 12 22k 12 21% 12 20% 11 21% 11 18% 13 21% 13 22k 16 21t 12 202 14 21% 2 (a) Timer malfunction; low sample volume.

(b) Unit Serviced.

(c) Sample was not placed.

TABLE B-1 (cant.l INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMI1TERS IN WEEKLY AIRBORNE PARTICULATES Results In Units of 10-s pCI/m~ i 2 sigma STATION CODES COLLECTION A-1 A-2 A-3 A-4 A-5 A-6 Coloma Dowaghc New Buff South Bend Average DATES i 2 s.d.

20t2 18i2 20i2 21i 27i3 04/08/91 04/15/91 04/22/91 22 k 2 11 22 13%2 10%2 13i2 19%2 10i2 15i2 19%2 lli2 13i2 9%2 13%2 1812 10i2 k2 19 k 2 12 it 2 2

ll k2 132 2 11 i 13i 2 2

2 6i I 14%2 (a) lli 201 5 2

04/29/91 16 2 2 13t 1 15%2 13%2 17 i2 11 14 E 2 13 16i2 16 i2 16% 2 15i2 13% 2 15i 3 05/06/91 7%1 ii 22 7i I 7il 6i t2 1 7t I t I (b)

St 2 7k I 8% I i 8i 16i I 9%1 7k 2 05/13/91 18 16%2 15%2 13 8 4 I 16 E 2 2 16%2 16t 05/20/91 05/27/91 13 12 ii 22 16i2 10t2 16i2 11%2 24 i 3 loi2 15 k2 11%2 11 E

k3 ll i2 (b) i 16 2 13% 2 15 9i2 i2 2

11 N 3 (b) ll i 15 i2 12%2 Il i 15 i 3 8

06/03/91 12 13i2 14i2 1312 1422 12%2 12 i 2 11 13 k2 14% 2 2

14%2 13t 2

2 06/10/91 06/17/91 9%2 1612 822 15i2 9k2 15+2 8%2 19i3 1012 18%3 822 16%2 29 8%2 4

10 i 14%2 2 4i 13k 2 2 10 k 2 16 2 2 8i 17% 9 4

06/24/91 07/Ol/91 18%2 20 X 2 15i2 21i2 16i2 24i2 18 i 2 9i 16%2 2k (a)

I (a)

I (a) 15%2 11 L2 17 R

t 19%2 2 15i2 20 i 2 17 23 ii 22 18i2 22 i2 16 i 20% 8 2

QuarterlyAvg. 14i 9 14 i8 14% 9 14 i 10 13% 8 11 % 7 16% 11 13 t8 14i 10 16% 10 14k 3 (a) Tim mali'uncUon; result In total pCI and not included In averages.

(b) B e: unit found ofL Results In total pCI.

B-1 {nnt.)

INDIANhMICHIQhN POWER C hNY - DONALD C. COOK NUCLEAR PIJlNF GROSS BETA EMITTERS IN WEEKLY AIRBORNE PARTICULATES Results In Units of 10-s PCI/m3 k 2 sigma STATION CODES COILRCTION h-1 h4 h-3 h-4 h-6 h-B Cobma Dowaghc New BuIf South Bend hverage DhTES k 2 a.d.

07/08/91 19k 2 18%2 16%2 17% 2 07/15/91 07/22/91 15% 2 27k 2 14 k 2 27%2 13 k 2 28%2 12 i 26k 2 2

18% 2 14 k 2 21% 2 18% 2 14 4 2 32k 2 18 10 30%2 k2 k2 18%2 14 2 2 (a) 26%2 18% 2 15 2 2 19% 2 16% 2 18% 2 14' ll ll k 2 30% 2 29% 2 28+ 6 07/29/91 k 2 ll t 2 ll k 2 12 k 2 12 k 2 11 k2 9%2 11% 2 10+ 2 ll + 2 08/05/91 08/12/91 102 2 t 13 2 14 k2 13 k 2 14% 2 26k 3 13% 2 13%2 13+2 15% 2 14m 2 14% 9 14% 2 12 k 2 14% 2 67k 9(b) 15% 2 11%2 13+2 13' 15% 2 132 3 08/19/91 21% 2 21 k2 15x2 21+ 2 78 k 7 (b) 17 k 2 19 k 2 19 k2 22k 2 23k 2 20% 5 08/26/91 16+ 2 16 %2 17x2 16% 2 16% 2 16+ 2 16%2 15+2 17% 2 17% 2 16% I 09/02/91 20% 2 19a2 19 k2 18% 2 24k 2 18% 2 12%2 ll k2 16% 2 162 2 17% 8 09/09/91 09/16/91 22k 2 15% 2 22%2 16%2 18%2 17t2 19%

16%

2 2

18% 2 13% 2 21% 2 18% 2 21%2 15%2 20 t2 17 k2 21% 2 22k 2 20% 3 18% 2 16% 2 161 3 09/23/91 12% 2 11%2 11%2 14% 2 12% 2 ll k 2 13%2 12 k2 13' 13% 2 12+ 2 09/30/91 10% 2 10%2 9%2 11% 2 102 2 11% 2 11%2 12 %2 13% 2 14+ 2 ll a 3 Quartedyhvg. IBR 10 1BR 10 16% 10 1BR 9 17% 10 17% 11 18% 11 18%9 17 k 10 17 k 10 1B i2 (a) Clock disconnected.

(b) Elevated result due to low volume. Not Included in averages.

TABLE B-1 tccat.)

INDIANhMICHIGANPOWER COMPhNY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMlTIERS IN WEEKLY AIRBORNE PARI1CULATES Results tn Untts of 10-3 PCt/ms k 2 stgma STATION CODES COLLISION h-1 h-2 h-3 h-4 h-5 h-6 Cobma Dowaghc New Buff South Bend hverage DhTES k 2 a.d.

10/07/91 17% 2 19a2 14+2 18% 2 23k 3 18% 2 18%2 21 k2 192 2 19+ 2 19% 5 10/14/91 20% 2 21%2 12%2 20%2 14%2 20% 2 23k 12t 2 2 21% 2 22 k 2 13 k 2 22 t2 14+2 22k 2 15% 2 15% 1 14% 2 21% 4 131 2 10/21/91 13% 2 13% 2 12% 2 10/28/91 15+ 2 14%2 16%2 17 k 2 14 2 2 16% 2 16% 2 14 k2 14% 2 152 2 15% 2 ll/04/91 15% 2 12%2 1312 14% 2 15% 2 141 2 ll k2 17 2 2 15k 2 162 2 14% 4 11/ll/91 18% 2 18%2 17%2 20% 2 18+ 2 21% 2 21%2 20 k 2 21% 2 20% 2 192 3 11/18/91 29% 2 26%2 25%2 28% 2 29k 2 27k 2 28%2 27 k 2 28% 2 32k 2 282 4 (A 11/25/91 15% 2 15%2 15%2 14%2 9%2 14% 2 1512 15+2 15' 15+ 2 14% 4 12/02/91 17% 2 18%2 18%2 17% 2 17% 2 192 2 19 k2 19 k 2 19% 2 182 2 18% 2 12/09/91 17% 2 20%2 18%2 17% 2 20% 2 20% 2 21 k2 19 2 2 21% 2 221 2 19+ 3 12/16/91 23k 2 23%2 23+2 22k 2 23k 2 26+ 2 24 k 2 23 k 2 22k 2 23k 2 23k 2 12/23/91 18% 2 16%2 15%2 17 4 2 17 k 2 17% 2 17 k 2 16 k 2 17* 2 18% 2 172 2 12/30/91 24k 2 22%2 2412 24k 2 26k 2 26k 2 26 k 2 23 k 2 26k 2 22k 2 24' Quater hag. 19 k 9 18% 9 18%8 19% 9 19% 12 19% 10 19% 10 19% 8 20m 9 19% 10 19' hnnaal hag. 17% 11 17% 11 17k 11 17% 11 17% 13 16% 12 18% 12 18% 12 182 12 18* 11 17% 11

LE B-2 INDIANAMICHIGANPOWER hNY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITfERS'N QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results In Units of 10-3 pCI/m3 f 2 sigma Nucildes Hrat Quarter Second Quarter Third Quarter Fourth Quarter hve rage 1Q/slfQool/ol/Ql CN/01/01~/ol/91 Ol/ol/9149/so/Ol N/so/91-12/so/01 i Sad.

h-1 Bc-7 97.9 k 9.8 98.9 X. 9.9 86.2 k 8.6 64.6 k 6.5 86.9 k 31.9 K-40 <4 <4 <4 3.82 k 2.12 3.82 2 2.12 Cs-134 < 0.2 < 0.2 < 0.2 < 0.3 Cs-137 < 0.2 < 0.3 < 0.3 < 0.3 h-2 Bc-7 129 R 13 119 k 12 99.6 k 10.0 63.1  % 6.3 103 K 58 K-40 <5 <5 <9 <8 Cs-134 < 0.3 < 0.3 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 h-3 Be-7 K-40 115

<9

% 12 117 k 12

< 10 98.8 k 9.9

< 10 74.4 t

< 10 7.4 101 k 39 Cs-134 < 0.3 < 0.3 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.4 < 0.3 h-4 Be-7 122 k 12 121 k 12 114 2 11 77.9 2 7.8 109 R 42 K-40 <5 <5 <5 <4 Cs-134 < 0.3 < 0.3 < 0.2 < 0.2 Cs-137 < 0.3 < 0.2 < 0.2 < 0.2 h-5 Be-7 137 k 14 125 2 13 109 k 11 82.4 2 8.2 113 2 47 K-40 Cs-134

<6

< 0.3

< 20

< 0.5 10.4 2 4.1

< 0.4

<5

< 0.3 104 t 4.1 Cs-137 < 0.3 < 0.5 < 0.4 < 0.3 Typical LLDs are found In Table B-12.

TABLE B-2 ICcat.l INDIhNAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLRhR PLANT CONCENmATIONS OF GAMMA EMlTIERS'N QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results ln Units of 10-3 PCI/ms k 2 sigma NucHdes Plllt Quarter Second Quarter Third Quarter Fourth Quarter Average 12/Sl/9004/Ol/91 04/Ol/91'/Ol/91 07/01/91'/SO/91 09/80/91-L?/SO/91 %9i.d.

A-6 Bc-7 112 k 11 97.4 + 9.7 109 2 11 70.9 k 7.1 97.3 k 37.4 K-40 < 10 <6 <5 12.4 % 3.5 12.4 X 3.5 Cs-134 < 0.4 < 0.3 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 Bc-7 111 k 11 101 k 10 87.1 k 8.7 76.9 2 7.7 94.0 k 30.1 K-40 < 10 <4 <4 < 3 Cs-134 < 0.3 < 0.2 < 0.2 < 0.2 Cs-137 < 0.3 < 0.2 < 0.2 < 0.2 Be-7 130 k 13 113 k 11 87.8 k 8.8 61.0 k 6.8 98.0 X 60.2 K-40 < 10 <6 < 7 <4 Cs-134 < 0.4 < 0.3 < 0.3 < 0.3 Cs-137 < 0.4 < 0.3 < 0.3 < 0.3 New Buffalo Be-7 K-40 136 R 14

<5 101 k 10

<5 107 2 11

<5 57.8

<4 R 5.8 100 i 65 Cs-134 < 0.3 < 0.3 < 0.3 < 0.2 Cs-137 < 0.4 < 0.4 < 0.4 < 0.2 South Bend Bc-7 123 X 13 117 k 12 110 k 11 76.6 2 7.7 107 R 42 K-40 <5 <9 <9 <8 Cs-134 < 0.3 < 0.3 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 LLDs are found ln Table B-12.

IZ~

INDIANAMICHIGANPOWER ANY - DONALD C. COOK NUCLEAR PLANT IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results In Units of 10-~ pCI/ms k 2 sigma STATION CODES COLLECTION A-I A-2 A-3 A-4 A-5 A-6 Coloma Dowaglac New Buffalo South Bend DATES JAN~UIK~

01/07/91 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 200 (a) < 10 < 20 Ol/14/91 < 10 < 10 < 10 < 10 <9 < 10 < 20 -<20 < 10 < 20 01/21/91 < 10 < 10 < 10 < 10 < 10 < 20 < 20 < 20 < 10 < 20 01/28/91 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 < 10 < 10 02/04/91 < 10 < 10 < 10 < 30 < 10 < 20 < 20 < 20 < 10 < 20 02/11/91 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 <6 < 10 02/18/91 < 20 < 20 < 20 < 20 < 10 < 20 < 20 < 20 < 10 < 10 02/25/91 < 20 < 10 < 10 < 10 < 10 < 20 < 20 < 20 < 10 < 20 03/04/91 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 20 (b) <6 < 10 EBBMCi 03/ll/91 < 20 < 20 < 20 < 20 < 10 < 10 < 10 < 10 < 10 < 10 03/18/91 < 20 < 20 (c) < 20 < 10 < 10 < 10 < 10 < 10 < 10 03/25/91 < 10 < 10 < 10 < 10 <9 < 20 < 20 < 20 < 10 < 20 04/01/91 < 10 < 10 < 10 < 10 <9 <9 < 0.6 < 10 <6 <9 (a) Timer malfunction; Iow sample volume.

(b) Untt serviced.

(c) Sample was not placed.

TABLE B-3 tcont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results In Untts of 10 ~ pCI/ms k 2 stgma STATION CODES COLLECTION A-1 A-2 A-3 A-4 A-5 A-6 Coloma Dowaglac Neer Buffalo South Bend DATES 04/08/91 < 10 < 10 < 10 < 10 <8 < 10 < 20 < 20 < 10 < 20 04/15/91 <9 <9 <9 <9 <5 < 10 < 10 < 10 < 10 < 8 (a) 04/22/91 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 <6 < 10 04/29/91 < 10 <9 < 10 < 10 <6 < 10 < 10 < 10 < 10 < 10 05/06/91 <6 < 7 <6 <6 <4 < 10 <8 <8 < 7 <8 05/13/91 < 20 < 20 < 20 < 20 < 5 (b) < 6 (b) < 10 < 10 <5 < 10 05/20/91 < 10 <9 <9 < 20 < 7 < 10 < 10 < 10 < 20 (b) < 10 05/27/91 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 7 < 10 06/03/91 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 10 <5 < 10 06/10/91 < 10 < 10 < 10 < 10 < 9 < 20 < 20 < 20 < 10 < 20 06/17/91 < 10 < 10 < 10 < 10 <9 (a) < 20 < 20 < 20 < 10 < 20 06/24/91 < 10 < 10 < 10 < 10 < 5 (a) < 9 <9 <9 <5 <9 07/01/91 < 10 < 10 < 10 < 10 <3 (a) < 10 < 10 < 10 <9 < 10 (a) Ttmer malfunctton; results tn total pCI.

(b) fuse; unit I'ound off. Results In total pCI.

LE B-3 (Cant.l INDIANAMICHIGANPOWE ANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of IO-~ PCI/m~ 2 2 sigma STATION CODES COILECTION A-I A-2 A-3 A-4 A-5 A-6 Coloma Dowagiac New Buffalo South Bend DATES 07/08/91 < 10 < 10 < 10 < 10 < 7 < 20 < 20 < 20 < 10 < 20 07/15/91 < 10 < 10 < 20 < 10 < 6 < 20 < 20 < 20 (a) < 10 < 20 07/22/91 < 10 < 10 < 10 < 10 < 10 < 10 < 10 < 20 <6 < 10 07/29/91 < 10 < 10 < 10 < 10 <9 < 10 < 10 < 10 <6 < 10 AUGUST 08/05/91 < 10 < 10 < 10 < 10 <8 < 10 < 10 < 10 <9 < 10 08/12/91 < 20 < 20 < 20 < 20 < 50 (b) < 10 < 10 < 10 <9 < 10 08/19/91 < 10 < 10 < 10 < 10 < 30 (b) < 10 < 10 < 10 < 20 < 10 08/26/91 < 20 < 10 < 20 < 20 <5 < 20 < 20 < 20 < 10 < 20 09/02/91 < 10 < 10 < 10 < 10 < 6 < 10 < 10 < 10 <6 < 10 09/09/91 < 10 < 10 < 10 < 10 <9 < 10 < 10 < 10 <6 < 10 09/16/91 < 10 < 10 < 10 < 10 <9 < 10 < 10 < 10 <6 < 10 09/23/91 < 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 <5 < 10 09/30/91 < 10 < 10 < 10 < 10 <5 < 10 < 10 < 10 <9 < 10 (a) Clock disconnected.

(b) Elevated result due to low volume.

ThBLE ~ {C0nt.I INDIANhMICHIGhN POWER COMPhNV - DONALD C. COOK NUCLEhR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results ln Untts of 10-3 PCI/m3 k 2 sigma STATION CODES COLL'N h-I h-2 h-S h-4 h-5 h-6 Coloma Dowagtac New Buffalo South Bend DhTES 10/07/91 <9 <9 <9 <9 <8 < 10 < 10 < 10 <6 < 10 10/14/91 < 10 < 10 < 10 < 10 ( 20 ( 20 ( 20 < 20 < 10 < 10 10/21/91 < 20

<9

< 20

<9

< 20 ( 20 <6 < 20 ( 20 ( 20 < 10 ( 20 10/28/91 <9 <9 <5 < 10 < 10 < 10 <9 < 10 11/04/91 < 10 < 10 < 10 < 10 <8 <-10 < 10 < 10 <9 < 10 11/11/91 < 10 < 10 < 10 < 10 <5 <9 <9 <9 <6 ( 10 11/18/91 < 10 < 10 < 10 < 10 <9 < 10 < 10 < 10 <5 < 10 11/25/91 ( 20 ( 20 < 20 ( 20 < 7 <6 <6 <6 < 3 <6 12/02/91 < 10 < 10 ( 20 ( 20 <8 ( 20 ( 20 < 10 < 10 ( 20 12/09/91 ( 20 ( 20 ( 20 ( 20 <<10 < 10 < 10 < 10 ( 60 < 10 12/16/91 < 10 < 10 < 10 < 10 <5 < 10 < 10 < 10 <9 < 10 12/23/91 ( 20 ( 20 < 20 ( 20 <9 < 10 < 10 < 10 <5 <9 12/30/91 < 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 < 7 < 10

hBLE B-4 INDIANAMICHIGANPONER - DONALD C. COOK NUCLEAR PLANT DIRECI'EASURE - gUARIERLY TLD RESULTS Results in Units of mR/standard month STATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER AVERAGE CODES 01/27/91~/28/91 04/28/91~/28/91 0?/28/91-10/13/91 10/13/91&1/04/92 i 2 a.d.

A-1 6.5 R i

0.5 3.0 J 0.3 i

4.5 + 0.6 3.9 i 0.5 4.5 i 3.0 A-2 5.7 6.1 i 0.6 3.1 0.2 i 4.4 0.2 4.0 i 0.3 4.3 E 2.2 A-3 0.7 3.0 S 0.4 4.2 R 0.2 4.1 I 0.2 4.4 2.6 4.6 i E

A-4 0.7 2.6 i 0.3 i 4.2 0.3 4.0 i 0.2 3.9 i 1.7 A-5 6.0 i 0.3 2.8 R 0.5 i 4.1 0.4 3.9 0.2 4.2 i 2.7 5.1 i A-6 0.4 2.3 R 0.2 4.2 A 0.2 3.9 i 0.2 3.9X 2.3 A-7 5.0 i 0.4 3.1 i 0.4 4.4 R 0.2 4.2 i 0.3 4.2 I 1.6 A-8 4.5 i 0.6 3.1 t 0.5 i 4.1 0.3 4.0 0.5 S 3.9 1.2 5.1 i R

A-9 1.2 3.2 i 0.4 i 4.9 1-0 4.2 i 0.2 4.4 i 1.7 A-10 4.4 i 0.6 2.5 i 0.2 i 4.0 0.3 3.6 i 0.3 3.6 i 1.6 A-11 4.2 R 0.5 4.5 i 0.9 3.2 % 0.4 4.4 k 0.4 4.1 i 0.2 4.0% 1.1 A-12 4.4 i 0.7 3.3 i 0.4 i 4.5 0.5 4.2 i 0.4 4.1 i 1.1 OFS-1 2.9 i 0.4 4.4 X 0.3 3.9 i 0.8 3.9 i 1.4 OFS-2 4.5 i 0.5 4.7 i 0.6 3.1 i 0.2 4.5 E 0.5 4.1 i 0.2 4.1 i 1.3 OFS-3 3.3 i 0.3 4.7 k 0.5 4.2 i 0.5 4.2k 1.3 OFSX 5.0 A 0.9 3.3 R 0.2 i 5.0 0.6 4.4 i 0.4 4.4 i 1.6 OFS-5 4.7 X 0.6 3.3 i 0.4 4.9 E 0.3 4.5 i 0.4 4.4 i 1.4 OFS-6 5.3 i 0.6 4.4 W 0.6 i 5.7 0.7 5.6 i 0.9 5.3 i OFS-7 4.5 i 0.5 2.9 i 0.2 i 4.5 0.3 4.0 J O.l 4.0 1.2 OFS-8 4.9 i 0.6 4.1 i 0.7 i 5.5 0.7 5.1 i 0.4 4.9 i 1.5 OFS-9 6.5 i 0.3 3.4 i 0.2 5.0 J 0.5 4.6 R 0.2 1.2 4.9 i 2.6 OFS-10 6.1 S 0.5 3.0 i 0.3 i 4.7 0.8 3.9 2 0.2 4.4 i 2.6 OFS-11 5.5 i i

0.8 3.9 i 0.4 i 5.6 0.5 i 4.8 0.6 5.0 i 1.6 NBF 4.9 i

1.1 3.2 i 0.4 i 4.6 0.5 i 4.2 0.6 4.2 i 1.5 SBN 5.4 0.9 3.4 A 0.3 i 5.2 0.5 i 4.1 0.2 4.5 i 1.9 DON 4.4 A 0.7 i

2.9 I 0.3 i 4.6 0.7 i 3.5 0.1 3.9 i 1.6 COL 4.4 0.6 2.8 i 0.3 I 4.0 0.2 i 3.5 0.1 3.7 + 1.4 Average i 2 a.d. 5.1 i 1.4 3.2 I 0.9 4.6 i 0.9 4.2 X 0.9 4.3R 1.6 Standard month ~ 30.4 days.

TABLE B-5 INDIhNh MICHIGANPOWER COMPhm - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMI'ITERS'N SURFACE WATER Results In Untts of pCI/liter t 2 sigma STATION Collection Date K-40 L-1 Ol/10/91 < 0.2 < 90 < 100 (Condenser Circ.) 02/07/91 < 0.2 < 100 03/07/91 < 0.2 < 100 04/04/91 < 0.3 < 100 170 k 90 05/02/91 < 0.3 < 10 (a) 05/30/91 < 0.2 < 40 06/27/91 < 0.1 < 70 07/25/91 < 0.09 < 50 220 R 80 08/22/91 < 0.2 < 40 09/19/91 < 0.2 < 50 10/17/91 < 0.2 < 100 130 k 70 11/14/91 < 0.1 < 100 12/12/91 < 0.5 < 90 I 2 01/10/91 < O.l < 60 < 100 (South Comp) 02/07/91 (b) 03/07/91 (b) 04/04/91 < 0.3 < 200 200 k 110 05/02/91 < 0.2 < 20 05/30/91 < 0.2 < 60 06/27/91 < 0.2 < 100 07/25/91 < 0.1 < 100 320 R 80 08/22/91 < O.l < 100 09/19/91 < 0.2 < 50 10/17/91 < 0.2 < 100 230 R 70 11/14/91 < 0.2 < 100 12/12/91 < 0.3 < 100

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

(a alt-60 was measured at 3.71 k 0.95 pCI/I and conArmed by nd aliquot.

( pie not available due to Ice on the shoreline.

TABLE B-5 {can.}

INDIANAMICHIQhN PO hNY - DONALD C. COOK NUCLRhR PLhNT CONCENTRATIONS OF IODINE, UM AND GAMMA EMITIERS'N SURFACE WATER Results ln Units of pCl/liter 2 2 sigma SThTION Collection Date 1-181 K-40 L-S 01/10/91 < 0.2 < 50 < 100 (North Comp) 02/07/91 (a) 03/07/91 (a) 04/04/91 < 0.2 < 100 400 A 80 05/02/91 < 0.2 < 20 05/30/91 < 0.2 < 100 06/27/91 < 0.2 < 60 07/25/91 < 0.1 < 100 200 X 80 08/22/91 < 0.1 < 100 09/19/91 < 0.2 < 200 10/17/91 < 0.2 < 100 310 k 80 ll/14/91 < 0.1 < 50 12/12/91 < 0.2 < 100 01/10/91 < 0.2 < 100 < 100 (South 500) 02/07/91 (a) 03/07/91 (a) 04/04/91 < 0.2 < 60 180 k 80 05/02/91 < 0.3 < 50 05/30/91 < 0.2 < 50 06/27/91 < 0.2 < 100 07/25/91 < 0.1 < 60 180 k 110 08/22/91 < 0.1 < 50 09/19/91 < 0.1 < 100 10/17/91 < 0.2 < 50 200  % 110 ll/14/91 < 0.1 < 50 12/12/91 < 0.2 < 80

~teal LLDs arc found In Table B-12. All other gamma emltters werc below <LLD.

(a) Sample not avatlable due to ice on the shoreline.

TABLE B-5 {Cna.l INDIANAlHICHIGANPOWER COMPhNT - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE. TRITIUM AND GAMMA EMIITERS'N SURFACE WATER Results tn Units of pCI/liter k 2 sigma STATION Collection Date 1-131 K-40 L-6 Ol/10/91 < 0.2 < 100 < 100 (North 500) 02/07/91 (a) 03/07/91 (a) 04/04/91 < 0.2 < 100 320 2 80 05/02/91 05/30/91 0.2 0.2 40.6 t

< 100 12.8 06/27/91 < 0.2 < 100 07/25/91 < 0.1 < 60 310 2 110 08/22/91 < O.l < 40 09/19/91 < O.l < 60 10/17/91 < 0.2 < 100 210 k 110 ll/14/91 < O.l < 60 12/12/91 < 0.3 < 90 Typical LLDs are tound in Table B-12.

(a) pie not avatlable due to tce on the shoreline.

TABLE B-6 INDIANAMICHIGANPO MPANY - DONALD C. COOK NUCLRAR PLANT CONCENTRATIONS OF TRlllVM MA EMITTERS'N QUARTERLY GROUND WATER Results in Units of pCl/liter k 2 sigma STATION Collection Date I-1S1 Gamma 8 c Well - 1 02/03/91 < O.l < LLD < 200 Rosemary Beach 05/05/91 < 0.1 < LLD 210 2 110 08/04/91 < O.l < LLD < 200 11/02/91 < 0.2 < LLD < 100 Well -2 02/03/91 < 0.1 < LLD < 200

'I?alnlng Center 05/05/91 < 0.1 < LLD < 200 08/04/91 < 0.1 < LLD < 200 11/02/91 < 0.2 < LLD < 200 Well - S 02/03/91(9) < 0.2 < LLD < 100 Firearms Range 05/05/91 < O.l < LLD < 200 08/04/91 < 0.1 < LLD < 200 11/02/91 < 0.2 < LLD < 200 Well - 4 02/03/91 < 0.1 < LLD < 2000 Onslte 05/05/91 < O.l < LLD 350 2 120 08/04/91 < O.l < LLD 1200 R 100 11/02/91 < 0.3 < LLD 1300 2 100 Well - 5 02/03/91 < 0.2 < LLD < 2000 Onslte 05/05/91 < 0.1 < LLD 570 % 120 08/04/91 < 0.1 < LLD 560 R 140 11/02/91 < 0.2 < LLD 686 k 160 Well - 6 02/03/91 < 0.1 < LLD < 2000 Onstte 05/05/91 < 0.1 < LLD 610 R 130 08/04/91 < 0.1 K-40 = 57.2 A 27.3 < 200 11/02/91 < 0.2 < LLD 230 k 100 Well - 7 02/03/91 < O.l < LLD < 100 Livingston Beach 05/05/91 < O.l < LLD < 200 08/04/91 < 0.1 < LLD 1200 R 100 11/02/91 < 0.2 < LLD 1700 a 200 Average k 2 a.d.

K-40 = 67.2 R 27.S 783 t 982 Typical LLDs are found ln Table B-12.

(a) Hole tn sample container. Bottle was empty upon arrtval at TI. Substitute sample recetved 2/11/92.

TABLE B-7 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEhR PLhNT CONCENTRATIONS OF GROSS BETA. IODINE, TRITIUM AND GAMMA EMITIERS'N DRINKING WATER i

Results tn Units of pCI/liter 2 sigma COLLEC'IDION DATE Gamma 8 c Iodine-1S1 Like Township 01/10/91 5.5i 3.0i 1.1 < LLD < 0.3 180 i 110 01/24/92 1.0 < LLD < 0.2 02/07/91 3.6R 1.0 < LLD < 0.4 02/21/91 3.2 1.0 < LLD < 0.3 03/07/91 7.3 2 1.3 < LLD < 0.2 03/21/91 4.9 i 1.1 < LLD < 0.3 04/04/91 3.2 R 1.0 < LLD < 0.4 04/18/91 3.6 2 0.9 < LLD < 0.3 < 100 05/02/91 6.4 i 1.2 < LLD < 0.3 05/16/91 3.7 i 1.0 < LLD < 0.2 05/30/91 i 4.3 0.9 < LLD < 0.2 06/13/91 4.4 i 1.1 < LLD < 0.2 06/27/91 4.4 i 1.0 < LLD < 0.2 07/11/91 4.3 i 1.1 < LLD < 0.3 180 i 100 07/25/91 8.3 i 1.3 < LLD < 0.2 08/08/91 2.8 i 1.0 < LLD < 0.2 08/22/91 3.9 i 1.0 < LLD < 0.2 09/05/91 3.2 2 1.0 < LLD < 0.2 09/19/91 6.1 k 1.2 < LLD < 0.1 10/03/91 3.4 k 0.9 < LLD < 0.2 230 i 100 10/17/91 5.4 a 1.1 < LLD < 0.2 10/31/91 3.2 2 1.1 < LLD < 0.2 ll/14/91 4.1% I.l < LLD < 0.2 11/28/91 2.8 X 0.9 < LLD < 0.1 12/12/91 3.9 i 1.0 < LLD < 0.5 12/26/91 2.8 2 0.9 < LLD < 0.2 hve e k 4.S k 2.9 197% 68 2

cal LLDs are found tn table B-12.

TABLE B-7 lcoot I INDIANAMICHIGANPOWER C - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, UM AND GAMMA EMITIERS'N DRINKING WATER Results ln Units of pCl/Ilter k 2 sigma COLUM:TION DATE Gamma 8 c Iodtne-131 St. Joseph 01/10/91 5.1 k 1.1 < LLD < 0.3 < 200 01/24/91 3.0 i 1.0 < LLD < 0.3 02/07/91 4.9 k 1.7 < LLD < 0.3 02/21/91 2.2 R 1.0 < LLD < 0.3 03/07/91 6.9 R 1.3 < LLD < 0.3 03/21/91 5.9 2 1.2 < LLD < 0.3 04/04/91 3.1 k 1.1 < LLD < 0.4 04/18/91 5.7 k 1.1 < LLD < 0.4 < 200 05/02/91 4.4 i 1.1 < LLD < 0.3 05/16/91 3.4 k 1.0 < LLD < 0.2 05/30/91 5.4 x 1.0 < LLD < 0.3 06/13/91 3.2 X 1.0 < LLD < 0.2 06/27/91 2.6 R 0.9 < LLD < 0.2 07/ll/91 5.6 i 1.2 < LLD < 0.3 210 k 100 07/25/91 5.9 4 1.1 < LLD < 0.2 08/08/91 2.5 R 1.0 < LLD < 0.2 08/22/91 3.6 R 0.9 < LLD < 0.2 09/05/91 4.0 a 1.0 < LLD < 0.2 09/19/91 3.5 k 1.0 < LLD < 0.1 10/03/91 3.3 k 1.0 < LLD < 0.2 160 2 90 10/17/91 3.1 i 0.9 < LLD < 0.2 10/31/91 3.4 a 1.1 < LLD < 0.3 11/14/91 4.5 a 1.1 < LLD < 0.3 11/28/91 3.8 R 1.0 < LLD < 0.4 12/12/91 3.9 k 1.0 < LLD < 0.2 12/26/91 3.7 2 1.0 < LLD < 0.4 Average k 4.1 2 185 4 71 2s. d.

7yptcal LLDs are found ln table B-12.

TABLE B-8 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITlERS'N SEDIMENT Results tn Units of pCI/kg (dry) k 2 sigma Station Collection Date Be-7 K-40 Cs-137 Ra-226 TI1-228 05/18/91 < 200 4980 R 500 < 30 < 400 107 R 18 05/18/91 < 200 6450 E 650 < 30 < 400 112 k 36 L-4 05/18/91 < 200 5640 2 560 37.5 k 19.0 < 500 153 k 37 L-5 05/18/91 < 200 6160 k 620 < 30 < 400 108 k 22 L-2 ll/17/91 < 200 5710 k 570 < 20 < 300 157 2 30 L-3 11/17/91 < 200 6250 k 620 < 20 < 400 118 k 20 L-4 11/17/91 < 200 4960 2 500 < 30 < 400 < 50 ll/17/91 < 200 6740 X 670 < 20 < 300 89.02 14.7 Average 6861 k 1314 37.6 k 19.0 121 k 50 k 2 a.d.

cal LLDs are found tn table B-12.

LE B-9 INDIANAMICHIGANPOWER C - DONALD C. COOK NUCLEhR PLANT CONCENTBA'11ONS OF lODINE AND GAMMA EMIITERS'N MILK Results tn Units of pCI/ltter k 2 sigma SI'ATION CODES COLU&TION hNhLYSIS SHULER LOZMACK WARMBIEN ZE LIER LIVINGSTON DATES 01/11/91 K-40 1230 R 120 1530 % 150 1290 R 130 1290 R 130 1350 2 130 1200

• 120 1030 k 100 1-131 < 0.3 < 0.3 < 0.3 < 0.4 < 0.2 < 0.3 < 0.3 01/25/91 K-40 1420 + 140 1390 k 140 1300 k 130 1390 k 130 1450 k 150 1360 X 140 1240 R 120 1-131 < 0.1 < 0.2 < 0.1 < 0.2 < 0.2 < 0.1 < 0.2 02/08/91 K-40 1360 k 140 1270 1 130 1300 k 130 1340 k 130 881 2 88 911 R 91 945 k 94 1-131 < 0.3 < 0.3 < 0.3 < 0.4 < 0.4 < 0.3 < 0.3 02/22/91 K-40 1-131 927  %

< 0.1 93 1180 k 120

< 0.1 1230 2 120

< 0.2 1360 t 140

< 0.2 1260 k 130 1410 k 140 1320 k 130

< 0.2 < 0.2 < 0.1 03/08/91 K-40 1250  % 130 1360 R 140 1300 k 130 1280 k 130 1380 k 140 1250 R 130 1210 k 120 1-131 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < O.l < 0.1 03/22/91 K-40 1150 k 120 1360 R 140 1310 k 130 1270 2 130 1400 k 140 1200 4 120 1220 k 120 1-131 < 0.2 < 0.2 < 0.2 < 0.1 < 0.1 < O.l < 0.1 Typtcal LLDs are found tn table B-12. All other gamma emttters were <LLD.

TABLE B-9 tccat.)

INDIANAMICHIQhN POWER COMPhNY - DONALD C. COOK NUCLEAR PLANT CONCEVPRA1IONS OF IODINE AND GAMMA EMITFERS'N MILK Results tn Untts of pCt/Itter k 2 stgma SI'ATION CODES COLLECTION hNhLYSIS SHULER IDZIEhCK WARMBIEN ZELMER LIVINGSTON DATES 04/05/91 K-40 1370 k 140 1280 k 130 1320 4 130 1310 k 130 1260 k 130 1030 2 100 1270 k 130 1-131 < 0.5 < 0.3 < 0.3 < 0.2 < 0.5 < 0.2 < 0.5 04/19/91 K-40 1-131 1190 + 120

< 0.2 1520 t 150

< 0.2 1270 t

< 0.2 130 1320 2 130

< 0.2 1430 k 140 1310 k 130 1130 + 110

< 0.2 < 0.2 < 0.2 05/03/91 K-40 1-131 1310 X 130

< 0.2 1500 k 150

< 0.2 1270 2 130

< 0.2 1290 A 130

< 0.1 1210 t

< 0.2 120 (a) 1400 t 140 1400 k 140

< 0.2 < 0.2 05/17/91 K-40 1200 t 120 1330 k 130 1400 k 140 1420 k 140 1230 2 120 1400 k 140 1340 k 130 l-131 < 0.1 < 0.1 < 0.2 < 0.1 < 0.1 < 0.2 < 0.2 05/31/91 K-40 1320 k 130 1400 k 140 1380 k 140 1240 2 120 1310 2 130 1400 k 140 1180 k 120 I-131 < 0.1 < 0.1 < 0.1 < 0.09 < 0.1 < 0.1 < 0.1 06/14/91 K-40 1-131 1300 t

< 0.1 130 1210 k 120

< 0.6 1320 R 130

< 0.5 1400 k 140 1430 k 140 1270 % 130 688 k 69

< 0.6 < 0.2 < 0.1 < 0.2 06/28/91 K-40 I-131 1380 k 140

< 0.1 1390 k 140

< 0.1 1340 k 130

< 0.1 1320 k 130

< 0.1 1250 1 120

< 0.1 1320 2 130

< 0.1 1300 t

< 0.1 130 Ds are found tn table B-12. All other gamma emttters wer (a) C 37 was measured at 3.29 2 1.63 pCt/ltter.

B-9 (Cont.)

INDIANhMCHIGANPOWER C - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA EMITTERS'N MILK Results tn Untts of pCI/ltter k 2 stgma STATION CODES COIL1KTION h%lLYSIS SHULER LOZHACE WhRHBIEN ZELMER LIVINGSTON DhTES 07/12/91 K-40 I-131 1050 i

< O.l 100 1390 k 140

< 0.1 1210 k 120

< 0.1 1400 a 140

< Q.l 1520 R

< 0.1 150 1330 k 130

< 0.1 1170 2 120

< 0.1 07/26/91 K-40 919 k 92 931 k 93 1190 4 120 1320 X 130 1310 a 130 1320 2 130 1300 k 130 I-131 < 0.1 < 0.1 < O.l < O.l < 0.1 < 0.1 << 0.1 08/09/91 K-40 1230 k 120 1320 k 130 1290

• 130 1360 k 140 1450 + 150 (a) 1250 k 130 1090 k 100 1-131 ( 0.1 < 0.1 ( 0.1 < O.l < 0.1 < 0.2 < 0.1 co 08/23/91 K-40 1-131 1350 k 130

< O.l 1370 k 140

< 0.1 1350 + 140

< 0.2 1330 k 130

< O.l 1280 k 130

< O.l 1310 k 130

< O.l 1320 t

( 0.2 130 (b) 09/06/91 K-40 1-131 1400 4 140

< O.l 1290 4 130

<*0.1 1260 k 130

< O.l 1330 k 130

< 0.1 1340 k 130

< 0.1 1180 k 120

< 0.2 1330 t 130

< 0.1 Q9/2Q/91 K-40 1350 k 140 1460 4 150 1310 k 130 1270 k 130 1170 2 120 1400 + 140 1260 k 130 1-131 ( 0.1 < O.l < 0.2 < 0.1 < 0.1 < 0.2 < 0.1

~

Typical LLDs are found tn table B-12. All other gamma emttters were <LLD.

(a) Cesium-137 was measured at 8.93 k 4.82 pCI/ltter.

(b) Cestum-137 was measured at 4.73 k 2.72 pCI/liter.

TABLE B-9 (care.}

INDIANAMICHIGANPONER COMPANY - DONALD C. COOK NUCLEhR PI%MT CONCENTRA'HONS OF IODINE AND GAMMA EMilTERS'N MILK Results ln Units of pCl/liter k 2 sigma STATION CODES COLLISION llHhLYSIS SHULER LOZMACK WARlHBIEN ZELMER LIVINGSTON DATES 10/04/91 K-40 1140 + 110 1440 k 140 1490 k 150 1130 k 110 1260 k 130 1370 k 140 1210 k 120 1-131 < 0.1 < 0.2 < 0.1 < 0.1 < 0.1 < 0.1 < 0.2 10/18/91 K-40 1370 k 140 1520 + 150 1200 k 120 1180 2 120 1340 + 130 1270 k 130 1340 k 130 1-131 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.2 11/01/91 K-40 1380 a 140 1480 k 150 1040 k 100 1420 k 140 1480 k 150 1250 k 130 1100 2 110 1-131 < 0.1 < 0.1 < 0.2 < 0.2 < 0.1 < 0.2 < 0.2 11/15/91 K-40 1380 k 140 1600 k 160 1160 k 120 1500 + 150 1480 k 150 1300 k 130 1240 k 120 1-131 < 0.2 < 0.2 < 0.2 < 0.1 < 0.1 < 0.2 < 0.2 11/29/91 K-40 1160 k 120 1420 R 140 1300 % 130 1380 R 140 1400 k 140 1320 4 130 1230 k 120 1-131 < 0.4 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 12/13/91 K-40 1390 k 140 1450 k 140 1230 k 120 1340 k 130 1390 + 140 1250 k 130 1240 k 120 1-131 < 0.1 < 0.2 < 0.1 < 0.1 < 0.2 < 0.1 < 0.1 12/27/91 K-40 1250 k 130 1330 k 130 1180 k 120 1410 k 140 1400 k 140 1370 k 140 1200 k 120 1-131 < 0.2 < 0.1 < 0.1 < 0.3 < 0.1 < 0.2 < 0.1 s are found ln table B-12. All other gamma emltters we ll

LR B-10 INDIhNAMICHIQANPOWER hNY - DONALD C. COOK NUCLEhR I ANT CONCENTRATIONS OF GAMMA EMITjKRS'N FISH Results ln Units of pCl/kg (wet) k 2 sigma Collection Date 8tation Be-7 K-40 CQ-187 Ra-228 Th-228 05/22(91 ONS-North White Sucker < 4QQ 210Q k 460 < 40 < 700 < 60 05/16/90 OFS-North Long Nose Sucker < 300 2800 k 530 65.8 R 25.9 < 500 < 50 05/16/90 ONS-South Yellow Long Nose < 400 2040 R 350 -< 40 < 900 < 70 05/16/90 OFS-South Yellow Long Nose < 400 2450 4 480 < 40 < 700 <<70 10/03/91 ONS -North White Sucker < 400 3010 k 390 < 40 < 500 < 50 10/03(91 OFS-North Lake Trout < 30Q 2950 2 380 < 30 ( 500 < 40 10/03/91 ONS-South White Sucker < 400 2330 R 330 < 30 < 600 <<50 10/03/91 OFS-South Long Nose Sucker < 400 3190 k 470 < 40 < 600 < 60 borage 2809% 8?4 68.8+ 28.9 k 2 s.d.

'yplcal LLDs are found ln table B-12.

TABLE B-11 INDIANAMICHIQANPOWER COMPhNY - DONALD C. COOK NUCLEAR PLANT CONCENI'RATIONS OF GAMMA EMITIERS'N FOOD/VEGETATION Results tn Unfts of pCI/kg (wet) k 2 sfgma COLLATIONDATE 8tation Desert tton Be-7 KKO I-131 Cs-IS7 08/10/91 SECTORS Broad Leaves 906 X 126 3790 2 380 <5 45.1 2 12.3 08/11/91 SECTORS Grapes < 100 2170 2 240 < 40 < 20 08/11/91 SECTORS Grapes < 100 1710 k 190 < 40 < 20 08/11/91 SECTORS Leaves 915 X 127 3880 2 390 < 60 < 10 08/11/91 SECIQRV Leaves 920  % 1-75 2710 k 280 < 50 < 20 Average k 914 k 14 2862 k 1930 46.1 2 12.S 2 SAL cal LLDs are found in table B-12.

B-I2 INDIANAMICHIGANPOWER CO - DONALD C. COOK NUCLEAR PLANT GAMMA SPECTROMETRY LOWER LIMITS OF DEIECTION AND REPORTING LEVELS Isoto TI LLD Tech S ec LLD Re t Level TI LLD Tech S c LLD Re t Level Ve etatlon- Cl K -wet Cerium-144 60 N/A N/A 30 N/A N/A Barium/La-140 10 N/A N/A 50/10 60/15 200 Cesium-134 10 60 1000 7 15 30 Ru.Rh-106 80 N/A N/A 50 N/A N/A Cesium-137 10 60 2000 6 18 50 Zr.Nb-95 10 N/A N/A 10/15 30/15 400 Manganese-54 10 N/A N/A 5 15 1000 Iron-59 15 N/A N/A 15 30 400 Zinc-65 20 N/A N/A 10 30 300 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 I 2 Iodine-131 (a) I I MI]R- Cl liter Cerium-144 30 N/A N/A 0.007 N/A N/A Barium/La-140 50/10 60/15 300 0.005 N/A N/A Cesium-134 7 15 60 0.002 0.06 10 RU,Rh-106 50 N/A N/A 0.010 N/A N/A Cesium-137 6 18 70 0.002 0.06 20 Zr,Nb-95 20 N/A N/A 0.002 N/A N/A Manganese-54 5 N/A N/A 0.002 N/A 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) I I (a) Analysis by radlockemlstry and based on the assumptions ln 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 FISH - Ci -wet Sediment Soil - Cl 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 Cobal t-60 20 130 10000 20 N/A N/A Cobalt-58 20 130 30000 20 N/A N/A Iodine-131 100 N/A N/A 30 N/A N/A Gross Beta/Tritium LLDs and Report Levels Gross Beta Alr Particulates 0.01 0.01 pCI/m3 N/A Surlace Water (c) 2 4.0 pCI/I N/A Ground Water 2 4.0 pCl/I N/A Drlnklng Water 2 4.0 pCI/I N/A Surlace Water 200 2000 20,000 Ground Water 200 2000 20,000 Drlnklng Water 200 2000 20,000 (b) Bas he assumptions ln procedure PRO-042-5.

(c) Base the assumptions ln procedure PRO-032-1.

APPENDIX C ANALYTICALPROCEDURES SYNOPSIS 66

ANALYTICALPROCEDURES SYNOPSIS Appendix C is a synopsis of the analytical procedures perforrr during 1991 on samples collected for the D.C. Cook Power Statio 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.

O~OLT l Tl L PAGE Gross Beta Analysis of Air Particulate Samples............. ~ ~ ~ ~ ~ ~ ~ 68 Gross Beta Analysis of Water Samples ................................ 69 Analysis of Samples for Tritium ................................ .. 71 Water ............................ . ....................... 71 Analysis of Samples for Strontium-89 and -90............. ~ ~ ~ ~ ~ ~ ~ 72 Total Water .................... .. 72 Milk ......

Soil and Sediment Organic SOMS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ o ~ ~ ~ o ~ o o o o 73 Air Particulates.......'........ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ o ~ ~ ~ o ~ o ~ 73 Analysis of Samples for Iodine-131 ............ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 76 Milk or Water ...................... o ~ ~ ~ ~ ~ ~ ~ o o ~ o ~ o o ~ 76 Gamma Spectrometry of Samples ~ ~ ~ ~ o o ~ o o o o ~ o o ~ ~ ~ 78 M'lk and Water......... ~ ~ ~ ~ \ ~ ~ ~ o o o o ~ ~ ~ ~ ~ o o ~ ~ o ~ ~ ~ o 78 Dried Solids other than Soils and Sediment ..................... 78 Hsh ~ o ~ o ~ ~ ~ o ~ o o ~ ~ ~ o ~ ~ o ~ ~ o ~ o o ~ ~ ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ o o ~ ~ o ~ ~ ~ o 78 Soils and Sediments ............ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 78 Charcoal Cartridges (Air Iodine) . o ~ o o ~ o ~ o o ~ ~ o ~ ~ o 78 Airborne Particulates .............

Environmental Dosimetry.................

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

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

RESULT (pCi/m3) ((S/T) - (B/t))/(2.22 V E)

TWO SIGMA ERROR (pCi/m3) = 2((S/T2) + (B/t2)) I/2/(2.22 V E)

LLD (pCi/m3) 4 66 (Bl/2)/(2.22 V E t) where:

S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 68

DETEREHNATION OF GROSS BETA ACTIVITY'NWATER SAMPLES 1.0 INTR D TION The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.

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

After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel 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.

69

2.0 DETE TI N CAPABILITY Detection capability depends upon the sample volume actually represented on the'lanchet, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time.

The minimum detectable level (MDL) for water samples is nominally 1.6 picocuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/1 at the 2.83 sigma level), assuming that 1 liter of sample is used and that gram of sample residue is mounted on the planchet. These Qgures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.

The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picocuries per liter, These values reflect a beta counting efficiency of 0.38.

70

ANALTSIS OF SAMPLES FOR TRITIUM W~t'r Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400'. 'The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.

The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays.

Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/1:

RESULT 3.234 TN VN(CG - B)/(CN VS)

TWO SIGMA ERROR = 2(3.234) TN VN(E) 1/2/(CN VS)

LLD 3 3 (3 234) TN VN(E) 1/2/(CN VS) where: TN tritium units of the standard 3.234 conversion factor changing tritium units to pCi/1 VN volume of the standard used to calibrate the efficiency of the detector in psia VS volume of the sample loaded into the detector in psia CN the net cpm of the standard of volume VN CG the gross cpm of the sample of volume VS B the background of the detector in cpm dt counting time for the sample E S/N + B/t2 71

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -SO Water Stable strontium carrier is added to 1 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/cm2 aluminum absorber for low level beta counting.

Mi11t Stable strontium carrier is added to 1 liter of sample and the sample s first evaporated, then ashed in a muNe furnace. The ash is dissolved and I

strontium is precipitated as phosphate, then is dissolved and precipitated as SrN03 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon 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/cm2 aluminum absorber for low level beta counting.

S j1 fm n The sample is Qrst dried under heat lamps and an aliquot is take Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NOg)2 using fuming (90@ nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO~ 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 1i A wet portion of the sample is dried and then ashed in a muf furnace. Stable strontium carrier is added and the ash is leached i hydrochloric acid. The sample is Qltered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NOg) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrCO~ 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.

Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then fOtered an 73

the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (RP/o) nitric acid. A barium scavenge is used to emove some interfering species. An iron (ferric hydroxide) scavenge is performed. followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide.

dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon 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 low 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 89 ESR 89)

TWO SIGMA ERROR Sr-89 2((N/Dt+BC+BA)/At) / /(2.22 V YS DFSR 89 ESR 89 LD Sr-89 4 66((BC+HA)/ht)1/2/(2.22 V YS DFSR 8g ESR 89)

SULT Sr-90 (N/bt - B)/(2.22 V Y1 Y2 DF IF E)

TWO SIGMA ERROR Sr-90 2((N/5t+B)/5t) 1/2/(2.22 V Y1 Y2 DF E IF))

LLD Sr-90 4 66(B/gt) 1/2/(2 22 V Y1 Y2 IF DF E) 74

where: N total counts from sample (counts) counting time for sample (min)

BC background rate of counter (cpm) using absorber conQgur 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 gp) ys chemical yield of strontium SR-89 decay factor from the mid collection date to the counting date for SR-89 ESR-89 efQciency of the counter for SR-89 with the 80 mg/cm.sq.

aluminum absorber K (Nht - BC)y gp/(Ey gp IFy gp DFy gpY1)

DFY g0) 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 milking ti IGY-90 the ingrowth factor for Y-90 into the strontium mount fro "milk" time to the mid count time 0.016 the eQiciency of measuring SR-90 through a No. 6 absorbe the efficiency of counting Y-90 through a No. 6 absorber background rate of counter (cpm)

Y1 chemical yield of yttrium Y2 chemical yield of strontium DF decay factor of yttrium from the radiochemical milking tim 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 75

ANALYSIS OF ~'DIMPLES FOR IODINE-131 hLlklw Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon 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/1:

RESULT (N/d,t-B)/(2.22 E V Y DF)

TWO SIGMA ERROR 2((N/b,t+B)/b,t) 1/2(2.22 E V Y DF)

LLD = 4.66(B/LM) 1/2/(2.22 E V Y DF) where: N total counts from sample (counts) counting time for sample (min) background rate of counter (cpm) 2.22 dpm/pCi volume or weight of sample analyzed chemical yield of the mount or sample counted decay factor from the coQection to the counting date efficiency of the counter for I-131, corrected for self absorption effects by the formula E Es(exp-0.0061M) /(exp-0.0061Ms)

E efficiency of the counter determined from an I-131 standard mount Ms = mass of Pd12 on the standard mount, mg mass of PDI2 on the sample mount, mg 76

A~IP The thirteen airborne particulate Qlters for a quarterly composite f each Qeld station are aligned one in front of another and then counted for a 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 deQnes 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 efQciency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume of pCi/mass:

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

TWO SIGMA ERROR 2(S+B) / /(2.22 t E VF DF) 4.66(B) 1/ /(2.22 t, E V F DF) where: S Area, in counts, of sample 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 efQciency for energy of interest and geometry of sample sample aliquot size (liters, cubic meters, kilograms, or grams) fractional gamma abundance (speciQc for each emitted gamma) decay factor from the mid-collection date to the counting date 77

GAIXASPECTROMETRY OF SAMPLES M~1k ~ W 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.

Drie Soli 0 rTh n il S im n 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.

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

oil d im n 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.

h r ri Air I in 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 (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.

78

ENVIRONMENTALDOSIMETRY Teledyne Isotopes uses a CaS04.Dy thermoluminescent dosime (TLD) which the company manufactures. This material has a high ligh 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 = (Dg+D2+D3+D4)/4 TWO SIGMA ERROR = 2((D)-D) +(D2-D) +(D3-D) +(D4-D) )/3) >/2 WHERE'1 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 the known exposure by the Cs-137 source R1 the instrument reading due to the Cs-.137 dose on area average dose in mR, calculated in simOar manner as above, of the transit control TLDs D the average net mR of all 4 areas of the TLD.

79

APPENDIX D SKLQKARYOF EPA INTERLABORATORYCOMPARISONS 80

EPA INTERLABORATORYCOMPARISON PROGRAM Teledyne Isotopes participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availabQity. In this section trending graphs (since 1981) and the 1991 data summary tables are presented for isotopes in the various sample media applicable to the Donald C. Cook Power Stations 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.

81

US EPA INTERLABORATORYCOMPARISON PROGRAM 1991 (Environmental)

Collection Teledyne Date Media Nuclide EPA Result(a) Isoto es Result(b) 0 1/11/91 Water- Sr-89 5.00 2 5.0 5.00 2 0.00 Sr-90 5.00 2 5.0 5.00 2 0.00 01/25/91 Water Gr-Alpha 5.0 2 5.0 9.00 2 1.00 Gr-Beta 5.0 2 5.0 7.00 2 0.00 02/08/91 Water Co-60 Zn-65 40.0 149.0 2

2 5.0 15.0 39.33 147.00 2 i 3.06 1.00 RQ-106 186.0 2 19.'0 176.67 2 17.56 Cs-134 8.0 2 5.0 7.33 2 0.58 Cs-137 8.0 2 5.0 7.67 2 3.21 Ba-133 75.0 2 8.0 75.67 2 5.51 02/15/91 Water I-131 75.0 2 8.0 80.00 2 5.29 02/22/91 Water H-3 4418.0 2 442.0 4500.0 2 173.21 03/08/91 Water Ra-226 31.8 2 4.8 28.33 2 4.73 Ra-228 21.1 2 5.3 16.67 2 2.08 03/29/91 Air Filter Gr-Alpha 25.0 2 6.0 42.67 2 0.58 (c)

Gr-Beta 124.0 2 6.0 126.67 2 5.77 Sr-90 40.0 2 5.0 37.00 2 1.00 Cs-137 40.0 2 5.0 43.00 2 5.29 04/16/91 Lab Perf. Gr-Alpha 54.0 2 14.0 59.67 2 4.04 Water Ra-226 8.0 2 1.2 7.33 2 0.81 Ra-228 15.2 2 3.8 10.00 2 0.00 (d)

Gr-Beta 115.0 2 17.0 110.00 2 0.00 Sr-89 28.0 2 5.0 31.00 2 1.00 Sr-90 26.0 2 5.0 21.00 2 0.00 Cs-134 24.0 2 5.0 25.00 2 1.00 Cs-137 25.0 2 5.0 24.00 2 1.73 04/26/91 Milk Sr-89 32.0 k 5.0 24.00 2 3.00 (e)

Sr-90 32.0 2 5.0 26.33 2 2.08 I-131 60.0 2 6.0 53.33 2 2.31 Cs-137 49.0 2 5.0 52.67 2 1.53 K 1650.0 2 83.0 1590.00 2 81.85 See footnotes at end of table.

82

US EPA INTERKdLBORATORYCOMPARISON PROGRAM 1991 (Environmental)

Collection Teledyne Date Media Nuclide EPA Result(a) Isoto es Result(b) 05/10/91 Water Sr-89 39.0 2 5.0 38.67 2 4.51 Sr-90 24.0 2 5.0 22.00 2 1.73 05/17/91 Water Gr-Alpha 24.0 k 6.0 24.33 k 2.52 Gr-Beta 46.0 2 5.0 50.33 2 1.53 06/07/91 Water Co-60 10.0 2 5.0 10.33 2 0.58 Zn-65 108.0 2 11.0 106.00 2 2.65 Ru-106 149.0 2 15.0 136.67 2 3.79 Cs-134 15.0 2 5.0 13.67 2 1.53 Cs-137 14.0 2 5.0 13.67 2 1.53 Ba-133 62.0 2 6.0 56.33 2 1.53 06/21/91 Water H-3 12480 2 1248.0 12833.33 2 115.50 07/12/91 Water Ra-226 15.9 2 2.4 15.0 k Ra-228 16.7 2 4.2 14.33 2 2

08/09/91 Water I-131 20.0 2 6.0 19.33 2 0.58 08/30/91 Air FQter Gr-Alpha 25.0 2 6.0 27.00 2 2.00 Gr-Beta 92.0 2 10.0 100.00 2 0.00 Sr-90 30.0 2 5.0 27.67 2 2.89 Cs-137 30.0 2 5.0 33.33 2 3.21 09/13/91 Water Sr-89 49.0 2 5.0 50.67 2 2.89 Sr-90 25.0 2 5.0 26.00 2 1.00 09/20/91 Water Gr-Alpha 10.0 2 5.0 11.67 2 0.58 Gr-Beta 20.0 2 5.0 21.00 2 0.00 09/27/91 Milk Sr-89 25.0 2 5.0 21.00 2 2.65 Sr-90 25.0 2 5.0 19.00 2 0.00 (e)

I-131 108.0 2 11.0 113.33 2 5.77 Cs-137 30.0 2 5.0 29.00 2 3.61 K 1740.0 2 87.0 1503.33 2 75.06 See footnotes at end of table.

83

US EPA INTERLABORATORYCOMPARISON PROGRAM 1991 (Environmental)

Collection Teledyne Date Media Nuclide EPA Result(a) Isoto es Result(b) 10/04/91 Lab Perf. Co-60 29.0 2 5.0 30.33 2 2.08 Water Zn-65 73.0 2 7.0 72.67 2 7.09 Ru-106 199.0 2 20.0 197.67 2 7.51 Cs-134 10.0 2 5.0 10,33 2 0.58 Cs-137 10.0 2 5.0 11.33 k 0.58 Ba-133 98.0 2 10.0 97.00 2 8.72 10/18/91 Water H-3 2454.0 2 353.0 2333.33 2 57.74 10/22/91 Lab Perf. Gr-Alpha 82.0 2 21.0 55.00 2 4.36 (g)

Water Ra-226 22.0 2 '.3 21.00 2 2.65 Ra-228 22.2 2 5.6 18.00 2 1.00 Gr-Beta 65.0 2 10.0 56.00 2 1.00 Sr-89 10.0 2 5.0 10.67 2 2.08 Sr-90 10.0 2 5.0 9.33 2 0.58 Co-60 20.0 k 5.0 19.67 2 0.58 Cs-134 10.0 2 5.0 10.33 2 2.08 Cs-137 11.0 2 5.0 13.67 2 0.58 11/08/91 Water Ra-226 6.5 2 1.0 5.37 2 0.32 Ra-228 8.1 2 2.0 7.90 2 1.20 See footnotes at end of table.

84

Footnotes:

(a) EPA Results-Expected laboratory precision (1. sigma). Units are pC for water and milk except K is in mg/liter. Units are total pCi f 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) The sample presents a different counting geometry. The EPA deposits activity in a 3/4 inch diameter circle, on a plastic disk approximately 3/32 inch thick. A special calibration for EPA filters will be performed. The laboratory has obtained blank filters from the Las Vegas facility, and will simulate their deposits.

(d) The lowest three results out of nine analyses were chosen. Other results in the group were close to the given value. Subsequent EPA analyses were accepted without selection, leading to acceptable results.

(e) The cause for the deviation is believed to be erroneously high strontium yields, probably caused by incomplete separation of calcium. The laboratory has investigated carrier concentrations and pipeting techniques, and have found them to be correct. Further aspects of analysts'echniques are being tested, The laboratory has received strontium extraction material developed at Argonne National Labor Experiments with this method to achieve better separation of calc um were completed and procedure PRO-032-105 was implemented on 2/1/92.

There is no apparent cause for the low K-40 results. Two other isotopes spiked in the'ample were in good agreement with EPA value's. Unit conversions were reviewed and found to be correctly applied. Possible background errors in geometry were investigated and found to have an insignificant effect.

(g) Probable failure to transfer all sample residue to the counting planchet.

Analysts are being tested using in-house and other EPA spikes.

85

TR NUING GRAPH 5 US EPA CRO CHECK PROGRAM STRONTIUM-90 IN WATER 1981 1982 1983 1984 1985 1988 198? 1988 1989 1990 1991 1992 Tl k3 sigma 4 EPA k3 sigma

US EPA CROSS CHECK PROGMLM STRONTIUM-89 IN WATER (cont.)

40 A

1985 1986 1987 1988 1989 1990 1991 1992 Tlf 3S 4 EPA% 3 S

US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER a 60 1981 1982 1983 1984 1985 Tl 13 sigma 4 EPA 13 sigma

US EPA CROSS CHECK PROGKVM TihITHMIN WATER (cont.)

1985 1988 1987 1988 1989 1990 1991 1992 Tl*3S 4 EPA% 3 S

US EPA CRO CHECK PROGRAM TRITIUMIN WATER 1981 1982 1983 1984 1985 Tl 1 3 sigma EPA %3 sigma

US EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (c4~t.)

~ 80 0

60 1987 1988 1989 1990 1991 1992 TI 23 sigma 4 EPA k 3 sigma

Us EPA CRO CHECK PROG%4QIC TRITIUMIN WATER (co nt.)

1985 1986 1987 1988 1989 1990 1991 1992 TI%3S 4 EPAX3S

US EPA CROSS CHECK PROGEUQLX GROSS BETA IN WATER L>>

100 O

cL 80 1984 1985 1988 1987 Tl % 3 sigma 4 EPA k 3 sigma

US EPA CROSS CHECK PROGRAM GROSS BETA Bf WATER L

120 Q

100 1981 1982 1983 1984 Tl %3sigma o EPA k 3 sigma

US EPA CROSS CHECK PROGRAM GROSS ALPHAIN WATER 0

a. 100 1981 1982 1983 1984 Tlt3sigma 4 EPA i 3 sigma

US EPA GROS CHECK PROGR/M GROSS ALPHAIN WATER 1984 1985 1988 1987 1988 1989 1990 1991 1992 Tt k 3 Sigma 4 EPA k3 Sigma

US EPA CROSS CHECK PROGXVM IODINE-131 IN WATER

-20 1981 1982 1983 1984 1986 1986 1987 1988 1989 1990 1991 1992 TI k 3 sigma o EPA i3 sigma

US EPA CRO HECK PROGRAM IODINE-131 IN MILK 1981 1982 1983 198'985 1988 1987 1988 1989 1990 1991 1992 Tl k 3 sigma EPA k3 sigma

US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK S

CJ t

I 4

47 CL 1981 1982 1983 1984 1985 1986 - 1987 1988 1989 1990 1991 1992 Tl k 3 sigma 4 EPA i3 sigma

US EPA CRO HECK PROGRAM STRONTIUM-90 IN MILK 5

QJ I

40 CL 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 Tl %3 sigma EPA i3 sigma

US EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK 1800 V

CL 1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 Tl k 3 sigma o EPA +3 sigma

US EPA CRO CHECK PRONOUN CESIUM-137 IN MILK 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 Tl t3 sigma EPA k3 sigma

US EPA CROSS CHECK PROGMM STRONTIUM-90 IN AIR PARTICULATES 70 0

o 40 10 1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 0 Tl k3 sigma o EPA g 3 sigma

US EPA C CHECK PROGMM CESIUM-1S7 IN AIR PARTICULATES O

CL 0

I 1981 1982 1083 1984 1985 1988 1987 19SS 19S0 1000 1991 1092 Tl %3sigma 4 EPA a 3 sigma

US EPA CROSS CHECK PROGRAM GROSS AH'IKAIN AIR PHOAE'ICULATES 40 O

CL 0

0

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 Tl 1 3 Sigma 4 EPA k 3 Sigma 0

US EPA C S CHECK PROGRAM GROSS BETA IN AIR PA$ tTICULATES O

CL e

O 80 I-1981 1982 1983 1984 1985 1988 1987 1988 1989 1990 1991 1992 Tl k 3 Sigma 08/25/89 EPA test Invalid. 4 EPA 2 3 Sigma

APPENDIX E REMP SAMPLING AND ANALYTICALEXCEPTIONS 107

PROGRAM EXCEPTIONS REMP deviations for 1991 are listed at the end of this appendix.

Where possible, the causes of the deviations have been corrected to prevent recurrence.

During 1991 the majority of REMP exceptions from the sampling requirements involved periods of inoperability of air samplers. They are listed individually in the following Exceptions table. The frequency of air sampler failures observed during 1991 appears to be fairly typical.

In some cases the units were removed, serviced, recalibrated and returned to service. To prevent recurrence, Procedure 12 THP 6010 ENV.051 was revised to include an Environmental Instrument Discrepancy sheet to determine the root causes of failures.

Broadleaf samples were collected in land sector J when in fact sector A had the highest D/Q value. The D/Q Deposition table in the Offsite Dose Calculation Manual, PMP 6010 OSD,001 has been revised to

~

be more "user friendly". The table now clearly identifies the land sector

~

with the highest D/Q value and will prevent any recurrence of this

~

problem.

Several surface water samples could not be collected due to ice on the shoreline. Since harsh and extreme weather conditions seldom impedes environmental sampling no action will be taken at this time.

108

REMP EXCEPTIONS FOR SCHEDULED SAMiPLING AND ANALYSIS DUMNG 1991 Date of O

Reason(s) for Loss/

Station Descri tion Sam lin Exce tion

'I Dowagiac Air Particulate/ Ol/07/91 Timer malfunction.

Air Iodine A-3 Air Particulate/ 03/18/91 Sample inadvertently Air Iodine was not placed.

Dowagiac Air Particulate/ 03/04/91 Unit serviced.

Air Iodine South Bend Air Particulate/ 04/15/91 Timer -malfunction.

Air Iodine A-5/A-6 Air Particulate/ 05/13/91 Blown fuse; unit found off.

Air Iodine A-5 Air Particulate/ 06/17/91 Timer malfunction, Air Iodine 06/24/91 07/Ol/91 Dowagiac Air Particulate/ 07/15/91 Clock disconnected.

Air Iodine A-5 Air Particulate 08/12/91 Elevated result due to 08/19/91 low air volume.

L-2/L-3 Surface Water 02/07/91 Samples not available due L-4/L-5 03/07/91 to ice on the shoreline.

Site Boundary Broadleaf 08/10/91 Collected in land sector J when in fact Sector A had the highest D/Q value.

109

APPENDIX F 1991 LAND USE CENSUS 110

APPENDIX F

SUMMARY

OF THE 1991 LAND USE CENSUS The Land Use Census is performed to ensure that significant changes in the areas in the immediate vicinity of the plant site are identified. Any identified changes are evaluated to determine whether modifications must be made to the REMP or other related programs. No such changes were identified during the 1991 Land Use Census. The following is a summary of the 1991 results.

Milk Farm 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 8, 1991.

In 1991 there were two additions and two deletions from the list of area milk farms. None of the deleted milk farms were involved in the Co Plant milk sampling program.

The previously identified milk animal continues to be the closest milk animal to the plant. The milk animal is located 2.2 miles from the plant's centerline axis to the closest edge of the animal's pasture. This distance was verified by Wightman 6 Associates, an independent surveying firm.

Residential Surve The residential survey is performed to identify the closest residence to the plant in each land sector. The closest residences in each sector were unchanged for 1991. A table identifying each residence is included at the end of this appendix, 111

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 1991 were <LLD.

112

Figure 5 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLF~ P Milk and Animal Survey - 1991 Distance Year Miles Sxmrey'ector Name Address N/A No milk animals N/A N/A No milk animals N/A N/A No mf1k animals N/A N/A No milk animals N/A N/A No milk animals N/A N/A No milk animals N/A D 5.1 Gerald Totzke 6744 Totzke Rd., Baroda 5.1 Gerald Totzke 6744 Totzke Rd., Baroda D (a) 2.2 Sue Dorman Holden Rd., Stevensville 10.5 Andrews Univ. Berrien Springs 10.5 Andrews Univ, Berrien Springs 6.8 Lee Nelson RFD 1, Box 390A, Sno 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 Br. Sons RFD 1, Snow Rd., Baroda 4.8 Norman Zelmer 11701 S. Gast Rd., Bridgman 4.8 Norman Zelmer 11701 S. Gast Rd., Bridgman 7.7 Jerry Warmbein 14143 Mill Rd.. Three Oaks 7.7 Jerry Warmbein 14143 Mill Rd., Three Oaks K 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.

113

6

'treet INDIANAMICHIGANPONER CO - DONALD C. COOK NUCLEhR PLhNT Resldenoal Land Use Survey - 1991 Sector Year House (1) Pro rt Address" 2161 1 1-1 1-0006-0004-01-7 lier Drive, Rosemary Beach 2161 6-4.1 Rt. I 1, Rosemary Rd.

a 2165 1 1-1 1-0006-0004-09-2 lier Drtve, Rosemary Beach b 2165 6-4.9 Rt. l)1, Rosemary Rd.

3093 11-1 1-6800-0028-00-0 Lake Road, Rosemary Beach 3093 6-28 Rt. 81, Rosemary Rd.

D 5733 I 1-1 1-0005-0036-01-8 7500 Thorton Drive 5733 5-36 7500 1%orton Drive 5631 I 1-1 1-0005-0009-07-0 7927 Red Arrow Highway 5631 5.25.5 7927 Red Arrow Highway 5392 11-11-0008-0015-03-1 8197 Red Arrow Highway 5392 8-10.3 3900 Llvlngston Rd.

G 3728 11-1 1-0007-0013-01-4 Llvlngston Road 3728 7-4 4212 Llvlngston Rd.

H 4944 11-1 1-8600-0004-00-1 Wildwood 4944 7-7+8 Wildwood Subdlvlslon (8700 Red Arrow Hwy.)

3366 1 1- 1 1-0007-0010-02-3 Llvlngston Hills 3366 7-1 0.3 4600 W. Ltvlngston Rd.

Llvlngston Hills Subdlvlslon)

K 10 3090 1 1-1 1-0007-0010 1 Ltvlngston Hills 10 3090 7-10.3 4600 W. Llvlngston Rd.

(Llvlngston Hills Subdlvlslon)

(1) All other sectors are over water.

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

SpedAc property numbers as listed on the tax rolls were used to ldentlfy houses.

Prevtous year's report used lot numbers. The lot numbers remained the same.

House N6 was Incorrectly addressed the previous year. All other address changes are minor modlocatlons reAecttng updated address format.

~

I

~ ~ 4 i%1 0 0

~

P ~

I i%~~~'g E~P' PQ~

~

~+('i~~>'4Wj:,'Ã4'-~ Easa~IP' .%l

%;.".'"-'=-,"if'> ~ere%

~A>%h~i5~aÃ~ h%+~QIR gg~4~%Vr~'".. ~)(p~~gj'j)gyp. " q~.

'y'~gin

@k~l> i4>$

~ORIISH<~jgjgjg@g,~.,

~~ <<IF> '~gg

@elk~~~

.;.-",':~e meum iymamraH.'4i-'~fje.-:>4j

- ~<5~458ae ~ 7 memmee-'"~IVI

a<llllh

I'i

~

r 5

I Da

' ~

0 ~ ~r 1

~ 'I ~

P~

'L

~~

ar; Cg I I

t I

oe

+~

O

~

CI C

APPENDIX G SUbflNARY OF THE PRE-OPERATIONAL RADIOLOGICALMONITORING PROGRAM 117

SUbQEARY OF THE PREOPERATIONAL RADIOLOGICAL MONITORING PROGRAM A preoperational radiological environmental monitoring program was performed for the Donald C. Cook Nuclear Plant from August 1971 until the initial criti'cality 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 sun+nary 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 1991.

As stated in the report for the period of July 1 to December 31, 1971, the purposes of a preoperational radiological monitoring program include:

(a) '"To yield average values of radiation levels and concentrations of radioactive material in various media of the environment.

(b) To identify sample locations and/or types of samples that deviate from the averages.

(c) To document seasonal variations that could be erroneously interpreted when the power station is operating.

(d) To indicate the range of values that should be considered "background" for various types of samples.

(e) To "proof test" the environmental monitoring equipment and procedures prior to operation of the nuclear power station.

(h) To provide baseline information that w01 yield estimates of the dose to man, if any, which will result Rom plant operation."

The discussion that follows is for the various sample media collected and analyzed in both the preoperational period and during 991. Analyses, such as strontium-89 and strontium-90 in milk and air 118

particulates performed during the preoperational but not required in 1991, are not discussed.

The gross beta activity in air particulate filters ranged from 0.01 to 0.17 pCi/m> from the middle of 19?1 to the middle of 19?3. In June of 1973 and in June of 1974 the People's Republic of China detonated atmospheric nuclear tests. As a result there were periods during which the gross beta results were elevated to as high as 0.45 pCi/m3 with no statistically significant differences between indicator and background stations. By the end of the preoperational period the values were approximately 0.06 pCi/m3.

The gamma ray analyses of composited air particulate filters showed "trace amounts" of Qssion products, Ce-144, Ru-106, Ru-103, Zr-95, and Nb-95, the results of fallout from previous atmospheric nuclear tests.

Cosmogenically produced beryQium-7 was also detected.

T he direct radiation background as measured by thermoluminescent dosimeters (TLD) ranged between 1.0 and 2.0 mRem/week during the three and one-half years period.

Milk samples during the preoperational period were analyzed for iodine-131 and by gamma ray spectroscopy (and for strontium-89 and strontium-90). All samples had naturally occurring potassium-40 with values ranging between 520 and 2310 pCi/liter. Cesium-137 was measured in many samples after the two atmospheric nuclear tests mentioned above. The cesium-137 activity ranged horn 8 to 33 pCi/liter.

Iodine-131 was measured in four mQk 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.

119

Gamma ray spectroscopy analyses of lake sediment detected natural abundances of potassium-40, uranium and thorium daughters, and traces of cesium-137 below O.l pCi/g which is attributed to fallout, Gamma spectroscopy analyses of fish detected natural abundances of potassium-40 and traces of cesium-137, the latter attributed to fallout.

Drinking water analysis was not part of the preoperational program.

120

APPENDIX H SUlÃlKARYOF THE BLIND DUPLICATE SAMPLE PROGRAM 121

SUhHRLRY PF THE BLIND DUPLICATE SAINPLE PRPGRAM The Plant procedure for implementing the blind duplicate sampling program references Regulatory Guide 4.15. The program utilizes blind, duplicate and spiked samples within four different parameters; gamma isotopic, tritium, iodine and gross beta. The samples are prepared by D.C.

Cook's analytical lab, Teledyne Isotopes.

Ten blind, duplicate and spiked analyses were performed during 1991.

Eight of the ten samples were within acceptable limits. The first quarter tritium water sample did not meet the acceptable criteria, however it did fall within 2 2 sigma of the control solution.

The second quarter gross beta sample did not meet the acceptance criteria. Teledyne Isotopes conducted an acceptable investigation to determine the root cause. The analysis was repeated with acceptable results.

122

APPENDIX I SUMHLGQLY OF THE SPIKE AND BLANKSAMPLE PROGRAM 123

SUMMARY

OF THE SPIKE AND BLhNK RLMPLE PROGRAM The following tables list the blanks and spiked water samples analyzed during 1991 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 reported outside the speciQed 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 speciQed in the Environmental Radioactive Laboratory Studies Program EPA-600/4 004, Table 3. Page 8". For gross beta activity below 100 pCi/1 the control level at which corrective action must be taken is 2 15 pCi/1. The quality assurance department operationally investigates gross beta spike results which exceed the one standard deviation, one determination levels (2 5 pCi/1). because of previous experience in reporting results within that level.

Techniques in transferring spiked liquids to the counting planchet and analysis methodology are under investigation to determine the cause for a Iow bias in the gross beta spikes.

124

Teledyne Isotopes In-House Blanks Sample Results 1991 - Water GROSS AIBA 23844 01/02/91 L. T. 6. E-01 23845 01/09/91 L. T. 4. E-01 23846 01/16/91 L. T. 4. E-01 23847 01/23/91 L. T. 4. E-01 23848 01/30/91 L. T. 4, E-01 27138 02/06/91 L. T. 7. E-01 27139 02/13/91 L. T. 4. E-01 27140 02/20/91 L. T. 4, E-01 27141 02/27/91 L. T. 5. E-01 30065 03/06/91 L. T. 7. E-01 30066 03/13/91 L. T. 4. E-01 30067 03/20/91 L. T. 4. E-01 30068 03/27/91 L. T. 7. E-01 33116 04/03/91 L. T. 5 E-01 33117 04/10/91 L. T. 4. E-01 33118 04/17/91 L. T. 5. E-01 33119 04/24/91 L. T. 4. E-01 36606 05/01/91 L. T. 6. E-01 36607 05/08/91 L. T. 5. E-01 36608 05/15/91 L. T. 6. E-01 36609 05/22/91 L. T. 7. E-01 36610 05/29/91 L. T. 6. E-01 40327 06/05/91 L. T. 6. E-01 40328 06/12/91 L. T. 4. E-01 40329 06/19/91 L. T. 5. E-01 40330 06/26/91 L. T. 6. E-01 43205 07/03/91 L. T. 7. E-01 43206 07/10/91 L. T. 7. E-01 43207 07/17/91 L. T. 5. E-01 43208 07/24/91 L. T. E-01 43209 07/31/91 L. T. 7. E-01 47097 08/07/91 L. T. 7. E-01 47098 08/14/91 L. T. 4. E-01 47099 08/21/91 L. T. 5. E-01 47100 08/28/91 L. T. 8. E-01 49738 09/04/91 L. T. 5. E-01 49739 09/ll/91 L. T. 7. E-01 49740 09/18/91 L. T. 7. E-01 49741 09/25/91 L. T. E-01 52791 10/02/91 L. T. 7. E-01 52792 10/09/91 L. T. 5. E-01 52793 10/16/91 L. T. 4. E-01 125

GROSS ALPHA(mnt.)

10/23/91 L. T. 6. E-01 10/30/91 L. T. 6. E-01 56540 11/06/91 L. T. 5. E-01 56541 11/13/91 L. T. 8. E-01 56542 11/20/91 L. T. 7. E-01 56542 11/27/91 L. T. 4. E-01 59179 12/04/91 L. T. 7. E-01 59180 12/11/91 L. T. 6. E-01 59181 12/18/91 L. T. 6. E-01 59182 12/26/91 L. T. E-01 GROSS BETA 23844 01/02/91 L. T. 8. E-01 23845 Ol/09/91 L. T. 8. E-Ol 23846 01/16/91 L. T. 7. E-01 23847 01/23/91 L. T. 8. E-OI 23848 01/30/91 L. T. 8. E-01 27138 02/06/91 L. T. 7. E-01 27139 02/13/91 L. T. 7. E-01 27140 02/20/91 L. T. 8. E-01 27141 02/27/91 L. T. 8. E-01 30065 03/06/91 L. T. 8. E-01 30066 03/13/91 L. T. 7. E-01 30067 03/20/91 L. T. 7. E-01 30068 03/27/91 L. T. 7. E-01 33116 04/03/91 L. T. 8. E-01 33117 04/10/91 L. T. 9. E-01 33118 04/17/91 L. T. 8. E-01 33119 04/24/91 L. T. 8. E-01 36606 05/Ol/91 L. T. 9. E-01 36607 05/08/91 L. T. 7. E-01 36608 05/15/91 L. T. 7. E-01 36609 05/22/91 L. T. 7. E-01 36610 05/29/91 L, T. 8. E-01 40327 06/05/91 L. T. 7. E-01 40328 06/12/91 L. T. 9. E-01 40329 06/19/91 L. T. 8. E-01 40330 06/26/91 L. T. 8. E-01 43205 07/03/91 L. T. 7. E-01 43206 07/10/91 L. T. 7. E-01 126

GROSS BETA (cont.)

43207 07/17/91 L. T. 8. E-01 43208 07/24/91 L. T. 8. E-01 43209 07/31/91 L. T. 7. E-01 47097 08/07/91 L. T. 9 E-01 47098 08/14/91 L. T. 8. E-01 47099 08/21/91 L, T. 7. E-01 47100 08/28/91 L. T. 8. E-01 49738 09/04/91 L. T. 7. E-01 49739 09/11/91 L. T. l. E 00 49740 09/18/91 L. T. 8. E-01 49741 09/25/91 L. T. 7. E-01 52791 10/02/91 L. T. 7. E-01 52792 10/09/91 L. T. 8. E-01 52793 10/16/91 L. T. 8. E-01 52794 10/23/91 L. T. 9. E-01 52795 10/30/91 L. T. 7. E-01 56540 11/06/91 L. T, 8. E-01 56541 11/13/91 L. T. 7. E-01 56542 11/20/91 L. T. 9 E-01 56543 11/27/91 L. T. 7. E-01 59179 12/04/91 L. T. 1. E 00 59180 12/11/91 L. T. 7. E-01 59181 12/18/91 L. T. 7. E-01 59182 12/26/91 L. T. 8. E-01 TRITIUM - QX-S) 23874 01/02/91 L. T. 2. E 02 23875 Ol/09/91 L. T. 1. E 02 23876 01/16/91 L. T. l. E 02 23877 01/23/91 L. T. l. E 02 23878 01/30/91 L. T. 1. E 02 27162 02/06/91 L. T. l. E 02 27163 02/13/91 L. T. l. E 02 27164 02/20/91 L. T. 9. Eol 27165 02/27/91 L. T. l. E 02 30089 03/06/91 L. T. 1. E 02 30090 03/13/91 L. T. l. E 02 30091 03/20/91 L, T. l. E 02 30092 03/27/91 L, T. l. E 02 33140 04/03/91 L. T. l. E 02 22141 04/10/91 L. T. 1. E 02 33142 04/17/91 L. T. l. E 02 33143 04/24/91 L. T. 1. E 02 127

TRITIUM - (H-S) (Cont.)

36638 05/01/91 L. T. 2. E 02 36637, 05/08/91 L. T. 2. E 02 36638 05/15/91 L. T. 2. E 02 36639 05/22/91 L. T. I. E 02 36640 05/29/91 L. T. 2. E 02 40351 06/05/91 L. T. l. E 02 40352 06/12/91 L. T. l. E 02 40353 06/19/91 L. T. l. E 02 40354 06/26/91 L. T. l. E 02 43302 07/03/91 L. T. 1. E 02 43303 07/10/91 L. T. l. E 02 43304 07/17/91 L. T. l. E 02 43305 07/24/91 L. T. 1. E 02 43306 07/31/91 L. T. 1. E02 47121 OS/07/91 L. T. 1. E02 47122 08/14/91 L. T. 1. E02 47123 08/21/91 L. T. l. E02 47124 08/28/91 L. T. l. E 02 49762 09/04/91 L. T. 1. E02 49763 09/11/91 L. T. 9. Eol 49764 09/18/91 L. T. 1. E02 49765 09/25/91 L. T. l. E02 52821 10/02/91 L. T. 1. E02 52822 10/09/91 L. T. l. E02 52823 10/16/91 L. T. 1. E02 52824 10/23/91 L. T. 2. E02 52825 10/30/91 L. T. 1. E02 56564 ll/06/91 L. T. 1. E02 56565 11/13/91 L. T. l. E 02 56566 11/20/91 L. T. 9. E01 56567 11/27/91 L. T. 1. E02 59203 12/04/91 L. T. 2. E02 59204 12/11/91 L. T. 2. E02 59205 12/18/91 L. T. l. E 02 59206 12/26/91 L. T. 2. E02 128

Teledyne Isotopes In-House Spiked Sample Results 1991 - Water ike Levels O

Ana?ysis S Ci L Acce table Ran e Ci l Gross Alpha Gross Beta ilk 55 212 6-16 16- 26 2262 5>> 17 - 27>>

Gamma (Eu-154) 1.4 2 0.2 E 05 1.2 - 1.6 E 05 H-3 (G) 2.7 2 0.3 E 03 2.4 - 3.0 E 03 4.5+ 0.5 E 03" 4.0 2 5.0 E 03>>>>

GROSS ALPHA A~ID t Activi Ci 1 23854 01/02/91 1.3+ 0.2 E Ol 23855 Ol/09/91 1.2+ 0.2 E 01 23856 01/16/91 9.7+ 1.5 E 00 23857 01/23/91 1.1 + 0.2 E Ol 23858 Ol/30/91 7.0+ 1.3 E 00 27146 02/06/91 1.1 2 0.2 E Ol 27147 02/13/91 1.1+02 E01 27148 02/20/91 9.4 2 1.6 E 00 27149 02/27/91 1.1 + 0.2 E Ol 30073 03/06/91 9.2 2 1.6 E 00 30074 03/13/91 1.2 + 0.2 E Ol 30075 03/20/91 1.6 2 0.2 E 01 30076 03/27/91 9.8 2 1.6 E 00 33124 04/03/91 1.4 + 0.2 E 01 33125 04/10/91 8.0+ 1.6 E 00 33126 04/17/91 1.1 2 0.2 E Ol 33127 04/24/91 9.6 2 1.6 E 00 36616 05/Ol/91 9.8 + 1.6 E 00 36617 05/08/91 1.1 2 O.l E 01 36618 05/15/91 9.2+ 1.5 E 00 36619 05/22/91 9.6+ 1.6 E 00 36620 05/29/91 1.2+ 0.2 E Ol 40335 06/05/91 1.3+ O.l E Ol 40336 06/12/91 1.1 + 0.2 E Ol 40337 06/19/91 99+ 17 EOO 40338 06/26/91 1.4+ 0.2 E 01 43215 07/03/91 9.4 + 1.6 E 00 43216 07/10/91 1.3+ 0.2 E 01 43217 07/17/91 1.1 + 0.2 E 01 Beginning 3/1/91 Beginning 5/1/91 129

GROSS ALPHA (cont.)

~r>>

43218 07/24/91 1.1 2 0.2 E 01 43219 07/31/91 1.1 2 0.2 E 01 47105 08/07/91 1.0 2 0.2 E 01 47106 08/14/91 1.3 2 0.2 E 01 47107 08/21/91 1.3 2 0.2 E 01 47108 08/28/91 1.1 2 0.2 E 01 49746 09/04/91 1.2 2 0.2 E 01 49747 09/11/91 9.3 2 1.5 E 00 49748 09/18/91 9.5 2 1.6 E 00 49749 09/25/91 1.1 2 0.2 E 01 52801 10/02/91 8.5 2 1.5 E 00 52802 10/09/91 1.1 2 0.2 E 01 52803 10/16/91 1.1 2 0.2 E 01 52804 10/23/91 9.7 2 1.7 E 00 52805 10/30/91 9.6 2 1.5 E 00 56548 Il/06/91 1.0 2 0.2 E 01 56549 11/13/91 1.1 2 0.2 E 01 56550 11/20/91 56551 59187 11/27/91 12/04/91 1.1 l 1.1 2 0.2 0.2 1.1 2 0.2 E 01 E 01 E 01 59188 12/11/91 9.0 2 1.5 E 00 59189 12/18/91 1.1 2 0.2 E 01 59190 12/26/91 8.8 2 1.5 E 00 GROSS BETA TI >>

23849 01/02/91 1.7 2 0.1 E Ol 23850 01/09/91 1.9 2 0.1 E 01 23851 01/16/91 1.7 2 0.1 E 01 23852 01/23/91 1.9 2 0.1 E 01 23853 01/30/91 1.9 2 0.1 E 01 27142 02/06/91 1.9 2 O.l E 01 27143 02/13/91 2.1 2 0.1 E Ol 27144 02/20/91 1.6 2 0.1 E 01 27145 02/27/91 1.9 2 0.1 E 01 30069 03/06/91 2.6 2 0.2 E 01 30070 03/13/91 2.0 k O.l E Ol 30071 03/20/91 2.0 2 O.l E Ol 30072 03/27/91 2.1 2 0.1 E 01 33120 04/03/91 1.9 2 O.l E Ol 33121 04/10/91 2.1 2 0.2 E Ol 33122 04/17/91 2.0 2 0.1 E 01 33123 04/24/91 2.1 2 0.2 E 01 130

GROSS BETA (cont.)

TI 4I 36611 05/01/91 1.7 2 0.1 E 01 36612 05/08/91 2.1 2 0.2 E Ol 36613 05/15/91 1.8 2 0.1 E 01 36614 05/22/91 2.1 2 0.1 E Ol 36615 '5/29/91 2.0 2 0.2 E 01 40331 06/05/91 1.9 2 O.l E Ol 40332 06/12/91 1.5 2 0.1 E 01 40333 06/19/91 2.2 2 0.2 E Ol 40334 06/26/91 1.7 2 0.1 E 01 43210 07/03/91 2.1 2 0.2 E Ol 43211 07/10/91 1.8 2 O.l E Ol 43212 07/17/91 2.1 2 0.2 E 01 43213 07/24/91 1.9 2 0.1 E 01 43214 07/31/91 2.02 O.l E 01 47101 08/07/91 1.8 2 0.1 E Ol 47102 08/14/91 2.2 2 0.2 E Ol 47103 08/21/91 1.8 2 0.1 E Ol 47104 08/28/91 2.4 2 0.2 E Ol 49742 09/04/91 1.9 4 0.1 E Ol 49743 09/ll/91 2.1 2 0.2 E Ol 49744 09/18/91 2.2 2 0.2 E 01 49745 09/25/91 1.8 2 0.1 E Ol 52796 10/02/91 1.8 2 O.l E 01 52797 10/09/91 2.3 2 0.2 E Ol 52798 10/16/91 2:020.1 E01 52799 10/23/91 2.0 2 0.2 E Ol 52800 10/30/91 2.0 2 0.1 E Ol 56544 11/06/91 1.9 2 0.1 E Ol 56545 11/13/91 1.6 2 0.1 E 01 56546 11/20/91 1.8 2 0.1 E Ol 56547 11/27/91 1.7 2 0.1 E 01 59183 12/04/91 2.0 2 0.1 E 01 59184 12/11/91 2.0 2 0.1 E Ol 59185 12/18/91 1.9 2 0.2 E Ol 59186 12/26/91 2,0 2 0.1 E 01 131

GAMMA (Eu-154)

TI ¹ idio Activi 23879 Ol/02/91 1.47 + 0.15 E 05 23880 Ol/09/91 1.43 2 0.14 E 05 23881 01/16/91 1.47 + 0.15 E 05 23882 01/23/91 1.40 + 0.14 E 05 23883 Ol/30/91 1.40 2 0.14 E 05 27166 02/06/91 1.40 + 0.14 E 05 27167 02/13/91 1.39 k 0.14 E 05 27168 02/20/91 1.42 2 0.14 E 05 27169 02/27/91 1.43 2 0.14 E 05 30093 03/06/91 1.49 + 0.15 E 05 30094 03/13/91 1.37 2 0.14 E 05 30095 03/20/91 1.41 + 0.14 E 05 30096 03/27/91 1.45 + 0.15 E 05 33144 04/03/91 1.37 2, 0.14 E 05 33145 04/10/91 1.45 2 0.15 E 05 33146 04/17/91 1.45 + 0.15 E 05 33147 04/24/91 1.40 2 0.14 E 05 36641 05/Ol/91 1.39 + 0.14 E 05 36642 05/08/91 1.39 + 0.14 E 05 36643 05/15/91 1.45 + 0.15 E 05 36644 05/22/91 1.45 2 0,15 E 05 36645 05/29/91 1.43 + 0.14 E 05 40355 06/05/91 1.43 + 0.14 E 05 40356 06/12/91 1.41 + 0.14 E 05 40357 06/19/91 1.40 2 0.14 E 05 40358 06/26/91 1.40 + 0.14 E 05 43307 07/03/91 1.42 + 0.14 E 05 43308 07/10/91 1.36 + 0.14 E 05 43309 07/17/91 1.43 2 0.14 E 05 43310 07/24/91 1.44 + 0.14 E 05 43311 07/31/91 1.39 + 0.14 E 05 47125 '08/07/91 1.34 + 0.13 E 05 47126 08/14/91 1.48 + 0,15 E 05 47127 08/21/91 1.42 + 0.14 E 05 47128 08/28/91 1.42 + 0.14 E 05 49766 09/04/91 1.39 + 0.14 E 05 49767'9768 09/ll/91 1.46 + 0.15 E 05 09/18/91 1.41 + 0.14 E 05 49769 09/25/91 1.45 + 0.15 E 05 52826 10/02/91 1.43 + 0.14 E 05 52827 10/09/91 1.42 + 0.14 E 05 52828 10/16/91 1.36 + 0.14 E 05 52829 10/23/91 1.42 + 0.14 E 05 52830 10/30/91 1.44 + 0.14 E 05 132

GAEA (Eu-154) (Cont.)

TI ¹ 56568 11/06/91 1.40 2 0.14 E 05 56569 ll/13/91 1.45 2 0.15 E 05 56570 11/20/91 1.40 k 0.14 E 05 56571 11/27/91 1.47 2 0.15 E 05 59207 12/04/91 1.38 2 0.14 E 05 59208 12/11/91 1.43 2 0.14 E 05 59209 12/18/91 1.41 2 0.14 E 05 59210 12/26/91 1.37 2 0.14 E 05 TRITIUM - (H-S) 23864 01/02/91 '2.6 2 0.1 E 03 23865 Ol/09/91 2.8 2 0.1 E 03 23866'3867 01/16/91 2.6 2 O.l E 03 01/23/91 2.5 2 O.l E 03 23868 01/30/91 2.3 2 0.1 E 03 27154 02/06/91 2.6 2 0.2 E 03 27155 02/13/91 2.5 2 0.2 E 03 27156 02/20/91 2.7 2 0.1 E 03 27157 02/27/91 2.3 2 0.1 E 03 30081 03/06/91 2.4 2 0.1 E 03 30082 03/13/91 2.6 2 0.1 E 03 30083 03/20/91 2.6 2 0.1 E 03 30084 03/27/91 2.4 2 0.2 E 03 33132 04/03/91 2.7 2 O.l E 03 33133 04/10/91 2.5 2 0.1 E 03 33134 04/17/91 2.6 2 0.1 E 03 33135 04/24/91 2.5 2 O.l E 03 36626 05/Ol/91 4.8 2 0.2 E 03 36627 05/08/91 4.8 2 0.1 E 03 36628 05/15/91 4.3 2 0.2 E 03 36629 05/22/91 4.6 2 O.l E 03 36630 05/29/91 4.3 2 0.1 E 03 40343 06/05/91 4.5 2 O.l E 03 40344 06/12/91 4.5 2 0.1 E 03 40345 06/19/91 4.7 2 0.1 E 03 40346 06/26/91 4.4 2 0.1 E 03 43225 07/03/91 4.3 2 0.3 E 03 43226 07/lo/91 4.4 2 0.2 E 43227 07/17/91 2 0.3 E 03 03'.4 43228 07/24/91 4.5 2 0.1 E 03 43229 07/31/91 4.2 2 0.1 E 03 47113 08/07/91 4.5 2 O.l E 03 47114 08/la/91 4.4 2 0.1 E 03 133

TRITIUM - (H-8) (cont.)

47115 08/21/91 4.3 2 0.4 E 03 47116 08/28/91 4.5 2 0.3 E 03 49754 09/04/91 4.2 2 0.3 E 03 49755 09/ll/91 4.5 2 O.l E 03 49756 09/18/91 4.7 2 0.1 E 03 49757 09/25/91 4.7 2 0.1 E 03 52811 10/02/91 4.5 2 0.1 E 03 52812 10/09/91 4.4 2 0.2 E 03 52813 10/16/91 4.5 2 0. 1 E 03 52814 10/23/91 4.5 2 0.1 E 03 52815 10/30/91 4.6 2 0.1 E 03 56556 11/06/91 4.2 2 0.1 E 03 56557 11/13/91 4.3 2 0.2 E 03 56558 11/20/91 4.3 2 0.2 E 03 56559 11/27/91 4.2 2 O.l E 03 59195 12/04/91 4.7 2 0.1 E 03 59196 12/11/91 4.6 2 0.1 E 03 59197 12/18/91 4.1 2 0.1 E 03 59198 12/26/91 4.4 k 0.2 E 03 134

APPENDIX J

'LD QUALXTFCONTROL PROGRAM 135

TLD QUALXTTCONTROL PROGRAM Teledyne Isotopes performs an in-house quality assurance testing program for the environmental TLD laboratory. Qn a quarterly basis the QA manager 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 readout 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 1991 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 30O/0.

The accompanying graphs show the normalized deviations of the measured doses to the exposure doses for each of the three readers.

136

QUALITYCONTROL - TLDS TLD READER 205 0.5 Is J l Is l

0 r

\ I 1

1

-0.5 01/89 04/89 07/89 . 10/89 01$ 0 04/90 07/90 10$ 0 01/91 04$ 1 07/91 10$ 1 0 ~ - Low Dose 0- Middle Dose 8 High Dose

0 QUALI CONTROL - TLDS '

TLO READER 211 1.5 I

j '/0 II g

~

~

0.5 0 li li pew~ 0 0

r'

~ r r

~

~~8

-0.5 01IBQ 04IBQ 07IBQ 10IBQ - 01IQO 04IQO 07/00 10I90 01IQ1'4I91 07I91 10IQ1 0- ~ - Low Dose Q ~

Middie'Dose 8 High Dose

QUALITYCONTROL - TLDS TLD READ.ER 242 0.5 I

II II gl 0

~ <<gran

• 0' o

~

4 01$ 9 04N9 07N9 10N9 01$ 0 04$ 0 07$ 0 10$ 0 01$ 1 04$ 1 07$ 1 10$ 1 0 ~ - Low Dose Middle Dose High Dose

APPENDIX VII A

SUMMARY

OF THE EVALUATION OF TRITIUM MIGRATION IN THE AQUIFER OF THE COOK NUCLEAR PLANT AND SURROUNDING COMMUNITIES

QUALI ONTROL - TLDS TLD READER 9150 0.5

-0 ~ ~-

~ egg

~

~ ~ ~ ~ ~ ~

-0.5 10$ 0 01$ 1 04$ 1 07$ 1 10$ 1 0- ~ - Low Dose 9- Middle Dose 8 High Dose

SUMMARY

OF THE EVALUATION OF TRITIUM MIGRATION IN THE AQUIFER OF THE COOK NUCLEAR PLANT AND SURROUNDING COMMUNITIES Groundwater samples obtained from environmental monitoring wells within the Donald C. Cook Nuclear Plant's site boundary have been found to contain levels of tritium greater than preoperational levels. The level of tritium in these samples raised a concern that offsite users of well water from the affected aquifer could be impacted and prompted an evaluation of this potential dose pathway to the offsite population. As part of the evaluation, an investigation to determine the source of the tritium detected in the environmental monitoring well samples was also initiated.

Eight active and two inactive offsite domestic wells were identified for sampling purposes to determine if the wells were subjected to the affected aquifer. All eight active wells and the two inactive wells were sampled and analyzed for tritium, iodine and gamma emitting radionuclides. In all but one case, no detectable radioactivity was found. The sample with detectable activity showed a tritium concentration consistent with documented preoperational groundwater tritium concentrations. The presence of tritium in the onsite environmental monitoring well samples is therefore concluded to have no impact on public health and safety.

The source of tritium in the environmental monitoring well samples was determined to be the onsite Absorption Pond which is upgradient from the wells and receives effluent from the Turbine Room Sump. Having determined the tritium source, the Radiological Environmental Monitoring Program (REMP) was revised to include monitoring of additional wells. The locations of the added monitoring wells are based on a detailed hydrogeologic study of the groundwater system in the vicinity of the plant site and was performed as a part of the evaluation to determine the potential offsite impact.

It was concluded that any offsite impact is minimized and there is no threat to the safety and welfare of the public.

This evaluation was sent to the U.S. Nuclear Regulatory Commission (NRC) on September 24, 1991 (AEP:NRC:1164). An update to the September 24, 1991, report was sent to the NRC on December 23, 1991 (AEP:NRC:1164A).