ML17334B472

DC Cook Nuclear Plant,Units 1 & 2 Annual Environ Operating Rept,920101-1231. W/930421 Ltr

ML17334B472
Person / Time
Site:	Cook
Issue date:	12/31/1992
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0806M, AEP:NRC:806M, NUDOCS 9304290174
Download: ML17334B472 (240)

Text

A.CCELERATED DOCUlVIEYT DIST r BUTION SYSTEM REGULA'Il INFORMATION DISTRIBUTIOh. YSTEM (RIDE)

ACCESSION NBR:9304290174 DOC.DATE: kQh~" NOTARIZED: NO FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 DOCKET N 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana a Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Document Control Branch (Document Control Desk) I

SUBJECT:

"DC Cook Nuclear Plant 'ts 1 & 2 Annual Environ Operating Rept,920101-1231." W 930421 ltr. D DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per TechMpecs) 4 ENCL SIZE:

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 D DEANFW 1 1 INTERNAL: NRR/DRSS/PRPB11 2 2 REG FILE 01 1 1 RGN3 DRSS/RPB 1 1 RGN3 FILE 02 1 1 EXTERNAL: EGGG SIMPSON,F 2 2 NRC PDR 1 1 S

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT TI.IE DOCUMEN'I CONTROL DISK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 13

Indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 N

AEP:NRC:0806M 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 - 1992 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley April 21, 1993

Dear Dr. Murley:

Attached is the Donald C, Cook Nuclear Plant Annual Environmental Operating Report for the year 1992. 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.

Sincerely, ZE~p~

Vice President edg Attachment cc: A. A. Blind - Bridgman NFEM Section Chief J. R. Padgett G. Charnoff A. B. Davis - Region III Administrator (2 encl.)

NRC Resident Inspector - Bridgman

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Annual Environmental Operating Report January 0, through December 34, 1992 Indiana Michigan Power Company Bridgman, Michigan Docket Nos. 50-315 & 50-316 License Nos. DPR-58 & DPR-74

TABLE OF'ONTENTS

~Pa e Introduction Changes to the Environmental Technical Specifications III. Non-Radiological Environmental Operating Report A.l Plant Design and Operation A.2 Non-Routine Reports A.3 Environmental Protection Plan A.4 Potentially Significant Unreviewed Environmental Issues B. Environmental Monitoring-Herbicide Applications C. Macrofouler Monitoring and Treatment IV. Solid, Liquid, and Gaseous Radioactive Waste Treatment Systems V. Radiological Environmental Monitoring Program (REMP) 3 A.

A.2 l Changes to the REMP Radiological Impact of Donald C. Cook Nuclear Plant Operations B. Land Use Census and Well Report VI. Conclusion

LIST OF APPENDICES appendix Title Non-Routine Report - 1992 Environmental Evaluation - 1992 Herbicide Application Report - 1992 IV Macrofouler Monitoring Program - 1992 Annual Report: Radiological Environmental Monitoring Program - 1992 Radiological Environmental Monitoring Program Summary - 1992 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 H Summary of the REMP Quality Control Program Summary of the Spike and Blank Sample Program TLD Quality Control Program

I. 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, 1992 through December 31, 1992.

During 1992, 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:

arameter U~nit Unit 2 Gross Electrical Generation (MwH) 5,197,600 1,485,880 Unit Service Factor (8) 64.8 19.5 Unit Capacity Factor - MDC* Net (0) 55.7 14.9

• Maximum Dependable Capacity II.~ CHANGES TO THE ENVIRONMENTAL TECHNICAL SPEC FICATIONS There were no environmental Technical Specification changes in 1992.~

III. ON-RADIOLOGICAL ENVIRO ENT L0 I G EPORT A.l Plant Design and Operation During 1992, 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 seven environmental evaluations during the reporting period. Copies of these evaluations are located in Appendix II of this report. The evaluations determined that there were no unreviewed environmental questions.

A.2 Non-Routine Reports A summary of the 1992 non-routine events is located in Appendix I of this report. No long-term, adverse environmental effects were noted.

A.3 Environmental Protection Plan There were no instances of Environmental Protection Plan noncompliance in 1992.

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

B. Environmental Monitoring - Herbicide Application Technical Specifications Appendix B, Subsection 5,4.1, states that the Annual Environmental Operating Report shall include: summaries and analyses of the results of the environmental protection activities required by Subsection 4.2 of this Environmental Protection Plan for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.

Herbicide applications are the activities monitored in accordance with 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 1992 herbicide applications is contained in Appendix III of this report. Based on observations, there were no negative impacts or evidence of trends toward irreversible change to the environment as a result of the herbicide applications. Based on our review of application records and field observations, the applications conformed with EPA and State requirements for the approved use of herbicides.

C. 'acrofouler Monitoring and Treatment Macrofouler studies and activities during 1992 are discussed in Appendix IV 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 1992.

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

The objectives of the operational radiological environmental monitoring program are:

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

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

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

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

A.l Changes to the REMP There were no changes to the REMP during 1992.

A.2 Radiological Impact of Donald C. Cook Nuclear Plant Operations This report summarizes the collection and analysis of various environmental sample media in 1992 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

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fi'sh, water, and sediment from Lake Michigan, drinking water, milk, and food products, either did not detect any radioactivity or measured only naturally occurring radionuclides at normal background levels.

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 1992 Land Use Census. A further discussion of the Land Use Census can be found in Appendix V (F) of this report.

VI. CONCLUSION Based upon the results of the radiological environmental monitoring program and the radioactive effluent release reports for the 1992 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 1992

1992 Non-Routine Events February, 1992 The NPDES Permit limit of 30 mg/l for the monthly average Total Suspended Solids (TSS) on Outfall OOC (Plant Heating Boiler) was exceeded. The analyses indicated an average value of

41. 4 mg/l.

First Quarter, 1992 An internal review of our records revealed that the first quarter 1992 samples for Stormwater Outfall 001S had not been collected.

June 6, 1992 During intermittent chlorination of the plant service water systems, our NPDES Permit limit of 0.30 mg/l, for a grab sample of Total Residual Chlorine (TRC) was exceeded. The analysis indicated a TRC concentration of 0.76 mg/l.

June 24, 1992 During intermittent chlorination of the plant service water systems, our NPDES Permit limit of 0.30 mg/l, for a grab sample of Total Residual Chlorine (TRC) was exceeded. The analysis indicated a TRC concentration of 0.33 mg/l.

June 30, 1992 A minor, inadvertent discharge of the mollusicide

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Clam-trol CT-1 may have occurred into surface waters.

September 16, 1992 Noticeable turbidity was visualized in

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Outfalls 001 and 002 during a forebay Clam-trol treatment,

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. resulting from the initial dosage of bentonite clay which is used

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as a Clam-trol detoxicant.

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Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridriman. Ml 49106 616 465 5901 INDIANA MICHIGAN POWER Michael D. Moore Deputy Director Department of Natural Resources Stevens T. Mason Building P. O. Box 30028 Lansing, MI 48909 October 30, 1992

Dear Mr. Moore:

Re: Summary of Scaup Events Per your request, the following is a summary of the sequence of events which led to the unfortunate loss of approximately 400 lesser and greater scaups last winter at the Cook Nuclear Plant.

The Cook Plant is located in Bridgman, Michigan on the southeastern shores of Lake Michigan. We operate two 1100 megawatt Westinghouse Pressurized Water Reactors. Cooling water is supplied via three sixteen foot diameter corrugated steel pipelines located approximately 2250 feet offshore. Three octagonal intake cribs approximately 75 feet in diameter with velocity caps (see Attachments ¹1, ¹2, and ¹3) take suction in approximately 22 feet of water. Design flow at the bar racks on the structures is one foot per second with all three pipelines in use and all seven circulating water pumps in operation. Total flow through the once-through main condenser cooling water system is 1.6 million gallons per minute.

The surrounding lake bottom consists of mostly sand. A limestone rip-rap stabilization zone surrounds the intake cribs, discharge limestone structures and pipeline paths in front, of the plant. The and intake cribs have formed a perfect substrate for, zebra mussels to attach and provide an abundant food source for lesser and greater scaups.

All seven circulating water pumps were screenhouse running, when the first scaups were discovered in the plant's forebay. The plartt was operating in the de-ice mode in which the center intake pipeline was aligned as a discharge pipeline. This alignment necessary for repair work scheduled for the center intake valve.

Michael D. Moore October 30, 1992 Page 2 Initial Scau Si htin s On December 5, 1991, plant personnel noted that over a 2 to 3 day period, approximately 90 to 100 dead scaups had collected in the screenhouse trash baskets after the screen wash pumps were run. The birds were not mangled or disfigured in any way. Plant personnel investigating the incident dissected one of the scaups in an attempt to determine the cause of death. Zebra mussels (Dreissena proventriculus of the animal. The gizzard was found to contain a number of zebra mussel shell fragments. Death appeared to have occurred by drowning. It was hypothesized that the scaups were feeding on the abundant zebra mussel 'population established on the circulating water intake cribs and surrounding rip rap. The MDNR Plainwell Office was notified by phone of the incident.

Cook Plant Zebra Mussel Histor Zebra mussels were first detected at the plant on July 18, 1990 in the plant screenhouse forebay. Initial density estimates ranged from 0.25-0.67 individuals per square meter in the plant screenhouse forebay and intake cribs. In late fall of 1990, zebra mussel densities had increased to approximately 100 individuals per square meter. No migratory ducks were seen around the area of the intake cribs on Lake Michigan or found in the screenhouse trash baskets in 1990.

In the spring of 1991, again, no migratory ducks were seen or found in the plant. During the summer of 1991, southern Lake Michigan underwent a population explosion of zebra mussel's. This was confirmed by bio-monitoring studies performed at the plant. By the fall of 1991, zebra mussel densities at the intake cribs had increased to approximately 180,000 to 200,000 per square meter.

The Plant utilizes a number of techniques to control zebra mussel infestation. Presently these include the use of intermittent chlorination and targeted molluscicide treatments to the service and circulating water systems. Divers are contracted to physically remove zebra mussels using water blasters and scrapers from areas where chemical treatment was impossible or not effective with water blasters.

Michael D. Moore October 30, 1992 Page 3 Initial Corrective Actions to Deter Scau s On December 6, 1991, approximately 250 scaups were seen diving near the intake cribs. Plant biologists attempted to scare the birds away using a small inflatable boat. The scaups left the immediate area, only to return soon after the boat. had left the water.

Blanks were fired from shore in an attempt to frighten the birds away, but the blasts were drowned out due to the distance to the birds, and the sound of the surf.

On December 7, 1991, plant biologists attempted to scare the scaups (approximately 250) again, utilizing shotgun blanks, fired from the small inflatable boat located at the intake cribs themselves.

Again, the birds returned after the boat left the water.

At the request of Mike Bailey of the MDNR Plainwell Office, .86 scaups that had been collected in the trash baskets were stored in the plant freezers for further study by U. S. Fish and Wildlife biologists.

By December 9, 1991, the number of scaups discovered in the screenhouse trash baskets had reached approximately 280. Plant engineers determined that a circulating water pump could be turned off in an attempt to decrease the water velocity at the intake cribs, without reducing reactor power. It was hoped that this would prevent the scaups from being sucked into the plant forebay.

Only ten scaups were found in the plants screenhouse trash baskets during the next four days. This reduced number could have been attributed to the fact that the majority of the scaups had left the immediate area on the 9th. As opposed to over "200 scaups being seen on December 8, only 5-12 scaups were seen the next four days near the intake cribs. Hence, we could not conclude whether operating at a reduced flow using six vs. seven circulating water pumps had made a positive difference.

Numerous bird scare tactics were employed by plant biologists in accordance with permission given by Mike Bailey of the MDNR. Plant biologists deployed Bird Scare Eyes (balloons painted with predatory eyes and reflective ribbons). The balloons were attached to the buoys marking the intake crib locations. Rafts were also deployed and attached to the buoys to simulate boats. These devices seemed to frighten the scaups from the intake crib area temporarily, but high winds, cold water temperature, and wave action soon ended all attempts to keep any type of floating scare device out at the intakes for any extended period of time.

Michael D. Moore October 30, 1992 Page 4 Furthermore, the buildup of shore ice made further deployments of these devices too hazardous for work crews. A utility in Wisconsin that had a similar experience cormorants at their surface level intake structures noted that visual tactics are temporary at best.

The birds become accustomed to the objects and soon ignored them.

On December 13, 1992, the plant went off de-ice mode to further reduce the velocity at the intake crib. Cooling waster was therefore drawn from three pipelines instead of two.

From about December 15, 1991, to the end of February, scaup populations seen rafting near the plant's intake cribs ranged from 1 to over 200. From the 15th of December until January 21, 1992, only two scaups were discovered in the trash baskets and no additional ducks have been collected to date (see Attachments ¹4 and ¹5). Zn addition to the scaups, four buffleheads were seen close to shore diving in approximately 10 to 15 feet of water.

Plant personnel made daily observations of migratory birds rafting near the. intake crib area, in an attempt to better learn the birds habits to help in mitigating the problem.

On January 19, 1992, the plant was returned to the de-ice mode of operation, taking suction from two pipelines and discharging through the center intake. This became necessary to prevent frazzle ice from blocking the intake crib flow pathway.

On February 4, 1992 in an attempt to permanently relocate the scaups, a helicopter was chartered to herd the ducks, and force them to another less dangerous feeding ground. Unfortunately, the scaups did not cooperate. However, we did discover that the birds found another site where they would congregate. One mile north of the plant on Lake Michigan in front of the Grand Mere Lakes, over 100 scaups were seen on several days rafting and diving in a specific area. We assumed that there must be another colony of zebra mussels in this area that the scaups feed on. We attempted to drive the scaups toward this area with the helicopter with little success. The birds appear to fly back and forth between the two area to feed.

From February 21, 1992 until March 11, no scaups were seen near the intake crib area. ~

On March 12, 1992, approximately 30 scaups were seen rafting at the intake cribs.

Michael D. Moore October 30, 1992 Page 5 On April 1, 1992, a plant biologist notedarea over 500 scaups, the intake mergansers and a few loons rafting in the near cribs. No scaups had been seen since March 12, and none had been found in the screenhouse trash baskets since January 21. The waterfowl were seen again on April 2, 10 and 13 in approximately the same numbers.

The fishing traffic near the intakes became heavy in mid-April, and the scaups were not seen again until October 13, 1992.

Plant biologists believe the scaups are feeding on the intake structures themselves, and may in fact swim right into the tunnels in search of zebra mussels. Plant biologists dove on the intake structures in January to ascertain whether the scaups were making any impact on the zebra mussel population, or if any grazing patches could be seen on the actual cribs themselves. Unfortunately no definitive conclusions could be made.

The autopsy results indicated a high percentage of yearling scaups.

They may become disoriented, and simply cannot find their way out against the current. We had hoped by varying the number of operating circulating water pumps and/or the number of pipelines being utilized as suctions, we could determine whether the scaups

.were sucked in or whether they would just swim in and could not find their way out. A conclusion could not be reached because the number of birds feeding in the area at the time of the plant modifications was relatively small and had little effect.

Future Preventative actions To prevent further losses of migrating waterfowl, the intake structures will be cleaned of zebra mussels prior to the fall migration of 1992. According to U. S. Fish and Wildlife biologists the scaup migration should begin around November.

When possible, Cook Nuclear Plant will continue to configure the plant's circulating water system in a manner to minimize flow at the intake structures during periods of duck migration. Divers will clean the structure as late in the season as possible (weather permitting), to remove all settled zebra We mussels including the 1992 believe by removing the newly settled Dreissena post veligers.

food source near the area where the ducks may become disoriented or swim to close to the plant suctions, the ducks will not become entrapped in the tunnels. The birds will still be able to feed on rip-rap that is covered the mussels on the surrounding half-mile of with zebra mussels, but they will be away from the danger

Michael D. Moore October 30, 1992 Page 6 associated with the intake cribs. Buoys with predator owls have also been .deployed.

The Plant has also purchased numerous aviary scare devices to be used if the need arises to frighten the birds away from the intake cribs. These include a multi-detonation LP gas cannon; a 6mm hand held launcher with screaming sirens, bird bangers; shot-tells (bird scaring blanks for shotguns); predator-eye balloons; and a AVA-2 Scare Alarm.

To employ many of these devices, good lake conditions are required to work out near the intake cribs. When the wave heights exceed two feet, or when shore ice is formed, the conditions become too hazardous to perform work. However, the use of scare devices may not become necessary because of the removal of the food source (zebra mussels) from the intake cribs.

In summary, we are confident that the measures being taken to remove zebra mussels from the intake structures will greatly minimize any future duck losses. We will continue to monitor the populations rafting at our intakes.

Sincerely, A. A. Blind Plant Manager

/js c: M. Bailey, MDNR'lainwell

Michael D. Moore October 30, 1992 Page 7 bc: E. E. Fitzpatrick J. E. Rutkowski K. R. Baker L. S. Gibson J. T. Wojcik D. M. Fitzgerald J. P. Carlson D. L. Baker A. J. Ahern A. E. Gaulke

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Atta'chment 2 COLLAPSIBLE RACK VIEW. TWO (2) PER SIDE OF OCTAGON 16 TOTAL RACK. 7" X 7" OPENING.

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Attachment 4 0 B OF D ZD 12-02-91 30 12-03 30 91'2-04-91 30 12-05-91 3 >250 12-06-91 AN 59 >250 12-06-91 PM 3, >250 12-07-9I. AM 86 >250 12-07-91 PM 6 >200 12-08-91 AM 51 >100 12 08-91 PH 22 >200 12-09-.91 AM 52 <50 12-09-91 PM 1 4 12-I.0-91 AM 1 12 12-I.0-91 PM 2 5 12-11-91 AM 6 10 12-11-91 PH 0 2 12-12-91 AM 0 3 12-12-91 PM 0 0 12-3.3-91 AM 0 4 12-13 91 PM 1 2 12-14-91 AM 0 0 12-I.4 91 %K .0 0 12-15 91 AM 0 >60 12-15 91 PM 1 53 12-16 91 AM 0 >30 12-3.6 91 PH 0 57 12-17 91 AM 0 0 12-17 91 PH 0 >60 12-I.8-91 0 >73 12-19 91 0 >110 12-21 91 0 >80 12-22-91 0 >80

'12-23 91 0 >100 12-27 91 0 2 12-30 91 0 >120 01 02 92 0 3 01-20 92 0 >50 01-21-92 1 >50 01-22-92 0 >30 01-23-92 0 >20 01-25-92 0 2 01-27-92 0 >3QQ**

01-28-92 0 >15 01-29-92 0 >20 01 30 92 0 >40 02-03-92 0 >40 02-04-92 0 >2QQ***

02-05-92 0 >45 02-06-92 0 >70 02-12-92 0 >100

Attachment 5 02-3.3-92. 0 >125 02-3.7-92 0 02-19-92 0 02-21-92 0 03-12-92 0 '3O 04-01-92 0 >500 04-02-92 0 >500 04-3.0-92 0 >400 04-13-92 0 >400 10-19-92 50

.otal number of scauys killed 385 No Lake observations made

>* Observations via helicopter over plant and Grand Mere area

+** Observations at Grand Mere area

APPENDIX II ENVIRONMENTAL EVALUATION REPORTS 1992

There were seven environmental evaluations during the reporting period. The following documents are copies of these evaluations. These environmental evaluations determined that there were no unreviewed environmental questions.

ANKRICAN KLECTRlC POll%R Date February 5, 1992 Subject Donald C. Cook Nuclear Plant Environmental Evaluation PM-837 From S. L. Colvis 'S~

To J. J. Satin/PM-837 DC-RS-7915 As requested, I have reviewed PM-837 for its environmental impact.

After discussions with plant personnel, I have determined that this design change does ~o require an environmental evaluation. This memo is to serve as documentation of this decision as required by Radiological Support Section Procedure RS-34.

The modification only allows for the installation of the diffusers.

It does not include the actual in]ection of any chemical (molluscide, etc.) as part of its scope. It is assumed that this will be dealt with in the development of the procedure for the chemical addition.

At that time, an environmental evaluation will be prepared by this section to determine the environmental impact due to the chosen chemical.

If you have any questions regarding this determination, please contact Dane.

Approved by' Radiological Support Section C; D. M. Fitzgerald/J. Carlson R. M Claes'.

R. Satyan-Sharma

APR 14 '93 18:33 D C COOK P.2 February La, le92 6U>J<< Xca Machine Glycol Header Modification, 12-%.-267 From R. M. Claas To J, E, Trader Fur<<uant to Radfologfcsl Support Section Procedur>> RS-34, this memo <<hall serve to document that an Environmenta1 Evaluation i<<not required to b>>

performed for the proposed modification of the ice machina glycol header a<<described in 12 MM-267.

The Des fgn Change Proposal will modify the glycol return and <<upply header to the ice machine to accommodate supplemental cooling, The fnstallatfon will require a tfe-in utilizing a tee on a six inch diameter <<ection of pipe with a flange and a valve to f<<clat>> flow.

Since the proposed location of the modfficatfon is the Unit 1 afdo of the 650'levation, the concern-arises in Oat any 1>>aks-from the system would have a direct route to the environment. It is therefore recommended that a contafnment structure encompass the proposed modification to mitigate the potential oi a glycol Leat'rom the system..

As described above, it can ba concluded that there app>>ars to b>> no unxevfewed environmental que<<tion as defined in Section 3.1 of Appendix B of the Facilfty Operating License. The propo<<ad activity would po<<>> no significant adverse eH>>ct on the environment. From the <<cope and respon<<ibilf ty of the Radiological Support Section, an Environmental Evaluation is not required and the activity defined in 12-MM-267 may proceed, Approved by: Z /d'~

D, R. Williams, Manager Radiological Support Section Concurrence by:

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z./p Nuclea censing Section Concurrence by; D, C. C nvfronmenta Se tion

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Oate February 18, 1992 Ice Machine Glycol Header Modification, 12-Kf-267 From R. M. Claes To J. E. Trader Pursuant to Radiological Support Section Procedure RS-34, this memo shall serve to document that an Environmental Evaluation is not required to be performed for the proposed modification of the ice machine glycol header as described in 12-MM-267.

The Design Change Proposal will modify the glycol return and supply header to the ice machine to accommodate supplemental cooling. The installation

'will require a tie-in utilizing a tee on a six inch diameter section of

,pipe with a flange and a valve to isolate flow.

Since the proposed location of the modification is the Unit 1 side of the 650'levation, the concern arises in that any leaks from the system would have a direct route to the environment. It is therefore recommended that a containment structure encompass the proposed modification to mitigate the potential of a glycol leak from the system.

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 not required and the activity defined in 12-MM-267 may proceed.

4 Approved by:

D. R.

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Williams, Manager Z

Radiological Support Section Concurrence by: cA M 2./ey g~

NuclearCLicensing Section Concurrence by:

D. C. C nvir'onmenta Se tion edg c: S. Hover 12-MM-267 Packet DC-RS-7915

AMKRlCAN ELECTR%

POWKR Date April 15, 1992 Subject Environmental Evaluation of the Sodium Hypochlorite Inj ection System From R. M. Claes To J. J. Satin 12-PM-801 Package Pursuant to Radiological Support Section Procedure RS-34, this memo shall serve to document that an Environmental Evaluation is not required to be performed for the proposed installation of a sodium hypochlorite injection system as described in 12-PM-801.

This modification will install a permanent liquid sodium hypochlorite injection system to replace the .existing gaseous chlorination system. The system shall be used to control microbiological growth and macrofouling infestation in the Circulating Water, ESW, NESW, and Make-up Water systems.

Environmental concerns. inherent in this modification have been satisfactorily addressed. The Material Safety Data Sheet for the use of sodium hypochlorite on site is approved and on file.

Station personnel cognizant of this system and its function are experien'ced in the precautions and handling of this chemical solution. Mitigation of significant environmental impact by the installation of this system has been satisfied by the construction of a concrete containment structure surrounding an installed sodium hypochlorite storage tank. The containment

.structure will retain approximately 100% of the contents of the tank in the event of a breech of integrity. Drainage of the containment structure will be to the Turbine Room Sump preventing a direct release pathway to Lake Michigan. In addition, this modification includes construction of a practical bulk chemical unloading area. This area will be constructed of a poly liner under asphalt with a valved drain. It is graded and curbed to contain approximately 150% of a standard delivered volume ~

In accordance with Technical Specification, environmental concerns i'dentified in the Final Environmental Statement which relate to water quality matters are regulated by way of the licensee's NPDES permit. The current NPDES revision recognizes the use of and has established effluent concentration limits for sodium hypochlorite in this application.

J. J. Satin April 15, 1992 Page 2 The proposed activity will only affect areas of the environment that have been previously disturbed or which have been evaluated for significant adverse environmental impact. 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 not required and the activity defined in 12-PM-801 may proceed.

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Approvsa sy: ~+Id" D. R..

A~K .6<6<

Williams, Manager I/~~

Radiological Support Section Concurrence By: 4 IS'2-uc ear icensing t

Concurrence By:

Donald C. o Nuclear Plant Environment Section c: DC-RS-7915

AMERICAN ELECTRlC POWER pate June 12 1992 Stjbjaot Environmental Evaluation Assessment

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From J. L L ichneruio'o J. P. Garison Radiological Support Section File DC-RS-7915 Re: Letter to DNR Dated April 27, 1992 from J ~ P. Garison Pursuant to Radiological Support Section procedure RS-34, this memorandum shall serve to document the environmental evaluation for the proposed nature trails in the vicinity of the visitor center.

Mr. Garison requested approval from the DNR to construct nature trails located north of the Energy Information Center. A small wooden platform to overlook Lake Michigan and an observation tower near a wetlands area will also be included.

This assessment is based on whether or not this proposed activity involves an unreviewed environmental question. That is, will this 0previously evaluated

"'mpact in the final environmental statement (FES).

.Secondly, does this activity have a significant change in effluents or power level which may have a significant adverse environmental impact.

. It is stated in the FES (V-1) Section 2, there was no specific plan for permitting public access to any part of the 650 acre property, except for the Visitor Center grounds and parking lot,. These nature trails are nothing more than an extension of the visitor center and the impact of constructing the trails is not significant in comparison to the impacts originally considered in the FES for visitor'enter construction. It is therefore concluded that addition of the proposed nature trails and observation deck is consistent with the assumptions made in the original FES evaluation of the Visitor's Center facilities.

J. P. Garison June 12, 1992 Page 2 Furthermore, the State of Michigan is reviewing and will need to approve this activity and the necessary critical dune permit before we can proceed. Therefore, an unreviewed environmental question does not exi.st.

Approved by: . / .'~ 4&LE~

D. R. Williams, Manager Radiological Support Section Concurrence:

Nuclear Li ing Section Concurrence:

General M

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. 8 4 /'P fZ~

isor, Environment Section p

edg

5 AMERICAM EMClRlC POWER Oate September 15, 1992 Subject Environmental Evaluation of the Underground S torage Tank Replacement Pro ectj From R. M. Claes To D, P. Ritzenthaler 12-RFC-4113 Package Pursuant to Radiological Support Section Procedure RS-34, this memo shall serve to document that an Environmental Evaluation has been performed for the proposed replacement of the underground storage tanks as proposed in 12-RFC-4113.

The underground tanks proposed for removal and replacement are all located within previously disturbed areas and no further significant environmental impacts should be experienced. The RFC package comprehensively details provisions that will mitigate the potential for future environmental degradation due to any associated system failure.

The removal of dry wells affected by this pro]ect will be rectified under a separate design change packager Transformer J)eck Drain Oil Water Separator Modification, for which an environmental evaluation will be performed.

The proposed activity will serve as a site-enhancement. by reducing the potential for environmental degradation due to on site fuel storage requirements. As described ebon, 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. Initiation of the proposed activity defined in 12-RFC-4113 will be contingent upon obtaining any required permits and authorizations which may include the following items to ensure that there are no adverse environmental effects. Activity, such as concrete work, that will be performed in areas previously disturbed and will impose insignificant environmental impact may proceed as necessary prior to satisfying the contingencies.

HPDES permit for discharging water from dewatering operations Permission from Michigan DNR to perform work on the plant heating boilers which are located in a known Act 307 oil contamination site Obtaining Critical Erosion permits e

Dune and

September 15, 1992 Page 2 Notifying the State Fire Marshall Developing a disposal plan for potentially oil contaminated soil Approved by:

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

ucle Lice~ g Concurrence by:

Donald C. C Nuclear Plant, Environmental Section edg c: ~

~DC-'RS=.7915 ':: 8

AMERICAN ELECTRIC POWER Oate October 9, 1992 Subject Environmental Evaluation of the Transformer Deck Drain Ofl/Mater Separator Modification From R. M. Claes To R. O. Beem 12-PM-1201 Package Pursuant Co Radiological SuPPort Section Procedure RS-34, Chfs memo shall serve co documeac that an Environmental Evaluation has been Performed for the ProPosed transformer deck dzain oil/water separator modification as described fn 12-PM-1201.

This modification will serve to eahance the Perfozmance of the oil/water separators and thereby mitigate the consequences of fire water deluge combined with a transformer oil spill. No significant adverse environmental impact is identified by the use of this system after Che modification is complete.

The dzy wells proposed for removal as part of the modification are all located within previously disturbed areas aad no further significant environmental impacts should be experienced. The RFC package details pzovisfons that will mitigate the potential for future environmental degradation due to any associated system failure.

The proposed activity will serve as a site enhaacement by reducing the potential for environmental degradation due to normal water/oil waste and oil/water deluge to the transformer deck drain. As it can be concluded that there appears to be no unreviewed described'bove, 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. Initiation of Che proposed activity defined in 12-PM-1201 will be contingent upon obtaining any required permits and auchorizatfonslwhfch may include the followfag items to ensure Chat Chere are no adverse environmental effects. Actfvity, such as concrete work, that will be performed in areas previously disturbed and will impose insignificant environmental impact may proceed as necessary prior to satisfying the contingencies:

NPDES permit for directing ofl/water separator effluent to the storm water drainage system i ~ 0 ~ ~ ~ I I

~ ~ 'A I 1 1

October 8, 1992 Page 2 NPDES permit for discharging water from dewatering operations Developing a disposal plan for potentially oil contaminated soil Approved by:

D. R. Williams, Hanager, Radiological Suppo'rt Section Concurrence By:

lear m ng Concurrence by:

Donal . k Nucle'ar Plant, Eavironmental Section edg c:  :.-DC-RS-7915

AMERICAN ELECTRIC POWER Date March 1, 1993 Environmental Evaluation of the Proposed Installation of Dedicated Fire Water Storage Tanks, RFC 12-3065 R. M. Claes P. J. Russel 12-PM-3065 Package Pursuant to Radiological Support Section Procedure RS-34, this memo shall serve as the Environmental Evaluation for the proposed installation of dedicated fire water storage, tanks as detailed in 12-PM-3065. The RFC is deemed necessary to replace the Lake Michigan supply source. This source has become infested with Zebra Mussels which could potentially pose adverse affects on the fire protection system.

The tanks proposed for installation are located within previously disturbed areas and no further significant environmental impacts should be experienced. The RFC package comprehensively details provisions that will mitigate the potential for future environmental degradation due to any associated system failure.

Each of the two diesel. driven pumps will have an associated 250 gallon fuel oil tank within the pump house. Each tank will be located within a concrete block dike inside the individual fire pump rooms. The dikes will sufficiently contain the volume of the associated tank. The pump house internal floor drains will be routed to the condenser pit sump pumps to mitigate any spills within the pump house. In addition, a fuel unloading area will be provided which will be capable of containing the entire volume of the largest compartment of a tanker unloading to the system. A storm water drain in the vicinity of the pump house will be relocated to preclude the potential for fuel oil to enter the drainage system.

In addition, the Michigan Department of Natural Resources'ritical Sand Dunes Permit has been obtained for this work. The MDNR was also notified of a facility modification which will result in a change in conditions, per NPDES Permit MI0005827. Specifically, diesel pump cooling water will be discharged to Lake Michigan via outfall 002S.

This modification will not result in a new, different, or increased discharge of pollutants. (See attached memo of January 14, 1992 to MDNR.)

P. J. Russel March 1, 1993 Page 2 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, the activity defined in 12-PM-3065 may proceed.

\

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

PSC unclear Li ing Concurrence By:

onald C. ook Nuclear Plant, vironmental Section c: DC-RS-79 5

Or,s Cook P!aca Biidgman, Ml 4910S 616 465 5901 Js"CIA JCL Fred Morley, District Supervisor Michigan Department of Natural Resources 62K North Tonth Street P.O, Box 355 Plainwell, Michigan 49080 January 14, 1992

Dear Mr. Morloy,

Re: NPDES Permit No. HI0005827 Cook Plant, Bx'idgman, Michigan As required by part XX.A.2 of the Cook plant National pollutant Discharge Elimination System (NpDRs) permit Ho. Ml0005827, we..axe providing notification of a facility modification which wil3...

result in a.change of. conditions. Me do not believe that this modification will result in a new, different, or increased discharge of pollutants for reasons discussed below.

Specifically, the Cook plantis Fire protection System is being modified as a xeeult of the infestation of Preissena polymorpha (Zebra mussel) in Lake Michigan. The system which nov dravs supply water fx om Lake Michigan, will ba modif ied to use chlorinatod T.aka Township drinking water as the water source.

Electrical pumps will serve as the pximaxy means for maintainin adocpxate pressure in the fire protection headexs. Diesel backup pumps vill be installed to ensure adequate system pressure in the .

event of loss of electrical power ox extremely high water demand.

Mhen each diesel pump operates, a design flow of appxoximately 60.

gallons per minute of the discharge water is pumped to cool the engine block via a heat exchanger. (Bee Attachment g1.) This cooling water will be discharged to the plant stormvater system and reach Lake Michigan via Stormwatlr Outfall 002S The current cook plant Fire protection system configuration is similax in that the initial response pumps aro electrically dx'ivan, and the diesel driven pumps essentially serve aa backups.

To date tha diesel pumps have never been used to fight a fire at Cock P'ant. The pumps are infrequently used to maintain water pressure due to system pressure loss, Should this trend continue, the new diesel pumps will be operated for testing purposes only.

Tests are run monthly fox approximately 30 minutes per pump. Once evexy 18 months tha pumps are run simultaneously for approximately 15-20 minutes, also fax testing purposes. Assuming. this schedule, approximately 45,600 gallons per year would he discharged to Lake Michigan. Monthly discharges would be approximately 3,600 gallons.

6164656161 PRGE. 882 MAR 1 '93 15:38

Prod Morley, District Suyezvisor January, 14, 1992 Page 2 41 Due to the relatively small amount of water being dischar9'ed/

the fact that it ia Lake Township drinking water', we believe that thez'e will Qe no adverse change in the cpxality of the discharg4 flow from Stormwater Outfall 0028. The chlorine content of the water at the point of discharge should ba negligible, due t'o Curing the time it will romain in onsite storage tanks prior to discharge, and the chlorine demand which wi11 be

'issipation encountered in the stormwater system, Please let me know notification.

if you need further information regarding this Sincerely, Diane: i er aid Znviro ental Supervisor Fx;ed Morley, District Supervisor J'anuary 14, 1992 Page 3 bc: A.A. Ilind 0 oRo Rutkbwiki J.T. Mogcik D.L. Sa3cer P.J. Russell c.i.

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~ Car isbn P e Ho Stathakis MAR 1 '93 15:39 6164656861 PAGE. 883

19 17 16 15 14 1 Intake manifold aad V. Peassure cay p psi) 1B. Coolant Sly intercooler (25000 NK I! oalg Bi meat exchs5gtr 14. %ster pump Q. Interior outlet 0. To inlet of 15< V/ster manifold.

B. Iatercooler inlet iateroooler 1S OQ cooler

4. Thermostats M. Customer supplied 17. Bleed tub>>

5. Prom iatsrcoolsr scurc>> of ravr eater 1B. Water inlet maaifoM outlot 11. Raw water yumy 19. %ster cooled exhaust S. Expansion tank 1L Ravr water discharge manifold Figure Q. CooUag System Schematic Diagram (Hoat Exchanger Type)

NRR 1 '93 15: 48 61646S6861 PAGE. 884

APPENDIX III HERBICIDE APPLICATION REPORT 1992

5 lNblANA MIC8lGAN POWER Date February 2, 1993 sub)cot 1992 Herbicide Spray Report - Cook Nuclear Plant From J, S. Lewl To D. M. Fitzgerald From June 3 - 7, 1992, Townsend Tree Service applied a mixture of Stomp and Oust to control grass and weed growth on the plant site.

A total of 91.2 quarts Stomp and 91.2 ounces of Oust were applied over 33.4 acres.

The manufacturer's label recommends that Stomp be applied at a rate of between 24 quarts per acre. Stomp was applied at a rate of 2.7 quarts per acre. The manufacturer's label recommends that Oust be applied up to 12 ounces per acre.

Oust was applied at a rate of 2.7 ounces per acre.

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

1. Sewage Ponds:

~ Sparse patches of weeds growing on the sides of both sewage ponds.

Herbicides were only applied to the water's edge. No evidence of overspray was found in or around the sewage ponds.

2. Road to Absorption Pond:

No weeds or signs of overspray were found.

3. 765 kV Switchgear Yard:

~ No weeds were found.

4. 345 kV Switchgear Yard:

~ No weeds or signs of overspray were found.

5. Railroad Tracks east of the Training Center:

~ Small patches of weeds were growing, No visible signs of overspray were found.

6. Parking Lot B:

~ Patches of grass were found growing inside the fenced-in area.

Intra4ystem

Herbicide Spray Report February 2, 1993 Page 2

7. 69 kV Switchgear Yard:

~ No signs of weeds or overspray were found.

8. North Protected Area Fence:

~ Good weed control.

9. South Protected Area Fence:

Weeds are growing along the fence.

10. East Protected Area Fence:

~ Good weed control.

11. ICMS Office Trailer:

~ No weeds were found. No visible signs of overspray were found.

12. ICMS Fabrication Shop:

~ Sparse patches of weeds are growing. No signs of overspray were found.

13. Southwest side of Turbine Building:

~ No weeds were found.

14. South end of Turbine Building:

~ Sparse patches of weeds were found growing. No signs of overspray were found.

15. Unit 1 RWST Area:

~ Moderate weed control. Some areas were not sprayed .due to radiation protection restrictions. 80% kill in areas sprayed.

16. Unit 2 RWST Area:

~ Moderate weed control. Some areas were not sprayed due to radiation protection restrictions. 90% kill in areas sprayed.

17. Hydrogen/Nitrogen Storage Tank Area:

No signs of weeds or overspray were found.

18. Construction Fabrication Shop:

~ No weeds were found.

19. Road to the Meteorological Towers:

~ Patches of grass were found growing on the roads. No signs of overspray were found.

tntra4ystem

Herbicide Spray Report Februaxy 2, 1993 Page 3 Based on our review of the 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.

The following additional areas were identified for the 1993 herbicide treatment progralQ:

~ Oil Barn

~ Paint Storage Building

~ Sandblast Shack

~ The road leading to and around the tower from the employee parking lot.

~ East sewage plant parking lot.

Intra4ystem

APPENDIX IV MACROFOULER MONITORING PROGRAM 1992

Indiana Michigan Power Company Cook Nuclear Plant 1992 Zebra Mussel and Asiatic Clam Monitoring and Control Report March 18, 1993 INTRODUCTION The large densities of zebra mussels (180,000 200,000 per square meter) reported in 1991 actually decreased in 1992 (67,000 per square meter) due to the increase in the average size of the mussels and the formation of clumps on untreated intake structures and components within the circulating water intake forebay areas.

A cool summer season in 1992 may have led to a smaller recuitment of zebra mussels in lower Lake Michigan as compared to the 1991 spawning season. (Schloesser & Nichols, East Lansing, MI zebra mussel conference Jan. 11-12, 1993)

A report on the bio-monitoring studies by LMS"and data collected by ERM are attached. Of particular note is the revelation that intermittent chlorination of the service water systems at 1.5 2.0 ppm for one, 155-minute period each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was ineffective in controlling zebra mussel infestation in low or no flow areas.

Intermittent chlorination of the circulating water system at 0.2 ppm for one, 155-minute period each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was also ineffective in controlling zebra mussel infestation in low or no flow areas.

ERADICATION AND CONTROL MEASURES The 1992 control strategy consisted of the use of a proprietary molluscicide (Clam-trol), intermittent chlorination of the service and circulating water systems, and mechanical cleaning.

MECHANICAL CLEANING Both Unit 1 and Unit 2 underwent refueling outages during the year.

This allowed the mechanical cleaning of zebra mussels by divers in the circulating water intake forebay. Hydrolasers and dredge pumps were used.to remove 1-2" of zebra mussel growth from the walls and components within the intake forebay. The circulating water intake cribs were also cleaned of zebra mussels.

As a result of targeted molluscicide treatments to the north and center intake pipelines, and a large scale treatment to the. intake forebay in 1992, the plant experienced a large influx of dead mussels from these sources when the units were brought up in power in the fall. Over 1,100 cubic yards of zebra mussels were removed from the Cook Nuclear Plant circulating water intake forebays as a result of. mechanical cleaning during outages and in the aftermath sloughage from the South of molluscicide treatments. Zebra mussel molluscicide intake tunnel, which was not treated with in 1992, is still occuring. The mussels from this source are being removed

from the circulating water by the traveling screens.

CLAM-TROL TREATMENT RESULTS Clam-trol (Betz Industrial, Inc.) treatments involving discharges to the surface waters were performed in four phases in 1992 and discussed below. The fire protection system was flushed with Clam-trol involving a groundwater discharge four times in 1992. Whole effluent toxicity testing was performed to demonstrate compliance with water quality standards for treatments to the north and center intake tunnels, and circulating water system. This testing was conducted as a requirement, of the Michigan DNR Clam-trol authorization letter of April 24, 1992.

Phases 1 6 2 - Treatments to the North and Center Intake Pipelines Low demand for circulating water as a result of plant outages allowed for the intake pipelines to be removed from service and target treated with Clam-trol. As a result, chemical usage of both the Clam-trol and the bentonite clay detoxicant was greatly reduced with good results. The north intake pipeline was treated at a target feed 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 /> on August 12-13, 1992 and the center intake pipeline was treated on September 11-12, 1992. Zebra mussel mortalities were determined to be >954 as determined by diving inspections performed following the treatments.

Phase 3 Circulating Rater System Treatment On September 16, 1992, the entire circulating water system was treated for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using'lam-trol at a target feed rate of 15 ppm. Bentonite clay was injected into the discharge as a detoxicant at a ratio of at least 3:1 clay:Clam-trol before being discharged to Lake Michigan. Zebra mussel mortalities measured by bio-boxes placed throughout the plant ranged from 87-994.

Subsequent intake forebay inspections by divers two weeks after the application, indicated a >95% kill with clean walls and forebay components.

Phase 4 - Spot,.Treatment of the Containment Spray Heat Exchangers Routine inspections of the Containment Spray Heat Exchangers during plant outages revealed light colonization of zebra mussels. Three of the four Containment Spray Heat Exchangers were treated for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> each at 50 ppm Clam-trol. Circulating water dilution flows were adequate to ensure that discharge concentrations of active Clam-trol were below the 0.05 ppm at plant outfalls 001 and 002.

The Unit 1 and 2 West Containment Spray Heat Exchangers were treated from 11/23/92 to 11/25/92. The Unit 1 East Containment Spray Heat Exhanger was treated from 12/9/92 to 12/11/92. The Unit 2 East Containment Spray Heat Exchanger was not treated due to the need for availability of the heat exchanger during unit start-up.

Also falling lake temperatures may have rendered the treatment ineffective if performed at a later date.

Zebra mussel mortalities were not assessed from these spot treatments. Instead, pressure gauges were installed at the inlet and outlet piping to measure the pressure drop across each heat exchanger. A flow improvement of 100 gpm with a corresponding increase in delta P was measured after the treatments to the Unit 1 and Unit 2 Nest Containment Spray Heat Exchangers. This data showed a slight improvement in heat exchanger performance when hydraulic flow resistance was analyzed. No performance im rovements were detected after the treatment to the Unit 1 East improveme Containment Spray Heat Exchanger.

Pire Proteection System The plant's fire protection system was flushed with a target feed of 15 ppm Clam-trol four times during 1992. No mortality studies were performed. Construction of dedicated fire protection water tanks and a pumphouse was begun in 1992 under RFC-3065. The fire protection system water source will be switched to municipal drinking water in 1993, thus eliminating the threat of zebra mussel infestation.

CHLORINATION TREATMENT RESULTS In 1992, the essential service water (ESN) and non-essential service water (NESN) systems received daily intermittent sodium hypochlorite treatments of 1.5-2.0 ppm total residual chlorine (TRC) for 155 minutes from May until late November. During the same period, the circulating water system received daily intermittent sodium hypochlorite treatments of 0.2 ppm (TRC). The construction of a permanent sodium hypochlorite feed system under PM-801 was completed before the 1992 treatment program. From heat exchanger, condenser water box, and various piping inspections, was determined that the intermittent chlorination program was it effective in areas of adequate flow. In areas of low or no flow, colonization was detected.

Inspections of the circulating water system revealed that the low levels of chlorine at 0.2 ppm (TRC) were effective in slime control, but had little or no effect in controlling zebra mussel colonization in areas of little or no flow. Systems taking suction from the circulating water system which are exposed to this low level of chlorination, including the office building air conditioning, miscellaneous seal 6 cooling, screenwash pumps, lawn sprinkler pump, and chlorine injector water supply pump, were sub'ect to'olonization of zebra mussels. After Clam-trol treatments, mussels residing within these systems would die and cause plugging problems.

The 1993 chlorination strategy calls for the service water systems to be treated continuously at 0.5 ppm to ensure colonization does not occur in the ESW and NESN. Filtration, chlorination, chlorine/bromine and multiple Clam-trol treatments, are being studied for systems which take suction from the circulating water

system.

CONCLUSXON Shock treatments of a proprietary molluscicide to remediate juvenile and adult zebra mussels, in conjunction with the use of sodium hypochlorite to control veliger settlement, has been an effective method in controlling zebra mussels. Mechanical cleaning can be effective in areas where chemical means are impossible or uneconomical. Chemical methods for controlling zebra mussels in low or no flow areas of the service water systems can be improved with continuous chlorination. Switching the fire protection system from raw lake water to municipal drinking water in 1993 will eliminate the threat of zebra mussel infestation in the fire protection system. A bio-monitoring program utilizing side stream and artificial substrate monitors along with diver and heat exchanger inspections will continue to be used to evaluate the effectiveness of chemical and physical control measures.

DONALD C. COOK NUCLEAR PLANT MOLLUSC BIOFOULING MONITORING DURING 1992 Prepared For.

AMERICAN ELECTRIC POWER SERVICE CORPORATION One Riverside Plaza Columbus, Ohio April 1993 Prepared By:

LMSE-93/0201&652/001 LAWLER, MATUSKYSc SKELLY ENGINEERS Environmental Science & Engineering Con ultants One Blue Hill Plaza Pearl River, New York 10965

CHAPTER 1 INTRODUCHON 1.1 PAST HISTORY Indiana and Michigan Power Company (I&M), a subsidiary of American Electric Power (AEP), has been conducting bio-fouling studies at the Donald C. Cook Nuclear Plant (Cook Nuclear Plant) since 1983. Initially, the studies were directed toward Asiatic clams. However, with the recent appearance of zebra mussels in Lake Michigan, the studies were expanded in 1990 to include zebra mussels. The purpose of the studies was to detect the presence of bio-fouling mollusks in the circulating water, essential service water (ESW), nonessential service water (NESW), fire protection system, and proximal Lake Michigan.

The purpose of the 1992 monitoring program conducted by Lawler, Matusky & Skeiiy Engineers (LMS) was to determine when spawning and settling of zebra mussels occur at the Cook Nuclear Plant and nearby Lake Michigan.

'Ihe monitoring program was designed to collect and analyze whole-water samples for

~

planktonic veligers, and artificial substrates set within the circulating water, ESW, and NESW systems for juveniles. In addition, samples were collected from the Gre protection system and other randomly selected locations. Beach surveys were conducted along the shoreline of Lake Michigan near the'ook Nuclear Plant and near the conQuence of the St. Joseph River and Lake Michigan.

1.2 OBJECTIVES Specific objectives for the 1992 bio-fouling monitoring program were as follows:

~ Whole-water sampling of the circulating and service water systems was conducted on a semi-weekly basis during a four-week period (mid-July to mid-August). The sampling was conducted to determine the presence and concentration of planktonic zebra mussel veligem.

Lawler, Matusky & Skelly Engineers

~ Fire protection water sampling was conducted for the presence of zebra mussel shells during flow tests.

~ Artificial substrates were deployed in the intake forebay and service water systems to detect settlement of postveliger zebra mussels. Samples were taken every two weeks from July through October and every three weeks in November and December.

~ Beach inspections were conducted during July, September, and November to detect adult zebra mussel presence and colonization near Cook Nuclear Plant and at the mouth of the St. Joseph River.

~ To check on suspected infestations, plant personnel collected samples from within the plant at locations and times that were outside the sample design of the program.

~ Temperature and pH were recorded during each whole-water and artiflcial substrate sampling period.

1-2 Lawler, Matusky & Skelly Engineers

CHAPTER 2 METHODS 2.1 CIRCULATING AND SERVICE WHOLE-WATER SAMPLING Whole-water sampling of the circulating and service water systems was conducted over a four-week period between 21 July and 14 August 1992. Samples were taken from the intake forebay and ESW and NESW systems. Eight 24-lir samples from each of the three systems were collected and analyzed. Samples were initiated on Monday and Thursday morning and concluded Tuesday and Friday mornings during the four-week period.

The whole-water sampling procedure for the circulating water system was modified during the four-week sampling period. Initially, a diaphram pump was used to pump water from the Unit 2 discharge forebay. Because of the high flow rate and pulsing action of this pump, the pump was replaced and the sampling location changed. A JABSCO brand centrifugal'pump rated at 26 gpm was used to pump water from the plant intake forebay. The JABSCO was able to deliver 13 gpm in use. Both the ESW and NESW whole-water samples were taken from the biomonitor discharge hoses.

Measured flow was directed into No. 20 nets that were suspended in a partially filled 55-gal barrel to minimize organism abrasion. Samples were gently washed from the cod-end into a sample jar and put on ice. For all systems, flow calculations were determined by fllling a bucket and timing the filling with a stop watch. This procedure was performed at the beginning and end of each sampling period. Samples were counted live within 24 hrs of collection. Those not analyzed within 24 hrs were first preserved on ice and then with ethanol. Due to the large sample volumes, all samples were subsampled using calibrated disposable Pasteur pipets. Five, 1-ml aliquots were examined in a Sedgewick-Rafter cell.

Counting methodologies followed those recommended by Marsden (1992). Raw counts in the aliquots were multiplied by the concentration value, then divided by the total volume to yield number of veligers per 1000 l.

2-1 0

Lawler, Matusky & Skelly Engineers

2.2 FIRE PROTECTION SAMPLING The fire protection systems were sampled by directing the Qrst 3 to 5 min of hydrant flow through a No. 35 sieve during flow testing. The contents of the sieves were examined on-site for the presence of shell or shell fragments. No microscopic examination was required for these samples.

Although a monthly sampling plan was originally scheduled, plant management prohibited low testing without the introduction of a molluscicide into the system. Mis requirement restricted the frequency of fire protection sampling to those treatment times.

23 ARTIFICIALSUBSTRATES A number of artificial substrates were deployed. To assess the degree of zebra mussel settlement within the circulating water, ESW, and NESW systems, three artificial substrates i were placed in the intake forebay upstream of the trash racks and two biomonitors were set in the ESW and NESW systems respectively. The forebay samplers consisted of Plexiglass racks (Figure 2-1) designed to hold 40 standard microscope slides that could be removed for analysis. Two slides were placed back to back in each slot, which eliminated the need for scraping, Racks were deployed by ropes to approximately 0.5 m from the bottom, anchored with a cinder block, and oriented such that flow was perpendicular to the vertically placed slides. Deployment of racks followed approved I&Mplant equipment installation procedures.

Artificial substrates placed in the ESW and NESW systems consisted of test tube racks equipped with 12 microscope slides each. Two racks were placed within each biomonitor (Figure 2-2).

The slides were examined every two weeks during the months of July, august, September, and October. The set time was extended to three weeks during November and December.

~

Slides removed from the forebay racks and biomonitors were examined using a low-power

~ ~ ~

(10-40x) dissecting microscope. Mussels that settled on the entire area

~ of one side of a slide 2-2 Lawler, Matnsky & Skelly Engineers

FIGURE 2-1 SLIDE RACK FOR DEPLOYMENT lN INTAKE FOREBAY Donald C. Cook Nuclear Plant 1992 DOUBLE RACK OF SUDES REMOVABLELUCITE STRIP NYLON WING NUT (TYPICAL) (L) 34.8cm x(W) 2.5cm x (H) 0.6cm 3.7 cm SUTS TO MOUNT SUDE FRAMES 4mm (TYPICAL)

EACH SUT FITS 2 SUDES 20 SUTS 40 SUDES NOT TO SCALE

FIGURE 2-2 ARTIFICIALSUBSTRATE BIOMONITOR Donald C. Cook Nuclear Plant 1992 3/4-IN. DISCHARGE DISCHARGE TOP WITH BOLTS FOR INSPECTION

.I 1 I I I I I

I I 6-IN. DIAMETER I

APPROXIMATELY3 FT TALL I

I I 1 t I I I I I SLIDES WITH I TEST TUBE RACKS I

I I 1 I I I I I I I I I I I I INTAKE CLEANING, FLUSH VALVE 3/4-IN. PIPING

(25 mm x 75 mm) were counted. This value was multiplied by a conversion factor (533) to calculate the number of settled mussels per square meter. These numbers were then averaged for all slides contained within a sampler to compute average settling densities during each sampling interval at each location.

2.4 BEACH WALKSAMPLING Beach walk sampling was conducted once during each of the months of July, September, and November. The major areas examined were the beach adjacent to the plant and the jetty and riprap at the mouth of the St. 'Joseph River in St. Joseph, Michigan. Beach walks were limited to 45 min in each area per sampling period.

2.5 INSPECTION SAMPLING ANALYSES Plant personnel submitted two samples taken from or near the plant for analysis. Sample analysis consisted of inspection for whole mussels and shell fragments.

2.6 RANDOM SAMPLING ANALYSES Plant personnel deployed substrates treated with experimental protective coatings for a six-week study period (mid-July to early September), Substrates were examined for visible settled juveniles, with the degree of infestation being noted as heavy, medium, light, or none. Those with light or no juvenile settlement were further analyzed under magnification to determine quantitative postveliger settlement densities, if necessary.

2.7 WATER QUALITYMONITORING During each sampling event (whole water and artificial substrate), water temperatures and pH measurements were taken with calibrated certiGed ASTM thermometers and pH pens, giving the precision level of + 0.1'C and + 0.1 pH units, respectively.

2-3 Lawler, Matusky & Skelly Engineers

2.8 NONRADIOLOGICALQUALITYASSURANCE/QUALITYCONTROL Nonradiological quality assurance/quality control (QA/QC) was an important aspect of the program. QA was incorporated into the program in several areas. LMS personnel assigned to this project were trained on-site in proper collection and handling techniques. Standard procedures were developed and followed. Laboratory techniques were supervised by Ms.

Bardygula-Norm, our in-house expert. Ms. Bardygula-Norm served as the QC inspector throughout the study. Field audits were performed on whole-water sampling, artificial substrate sampling, and one beach walk. Laboratory QC inspections showed an average outgoing quality level (AOQL) of <0.05.

The AOQL is based on quality control statistical probability. It denotes the number of defective units (errors) that can be expected in the product. In this case, the accuracy of the product is predicted to be greater than 95% based on inspection of samples and the measures

- taken to correct defects (errors).

Lawier, Matusky 8c Skelly Engineers

CHAPTER 3 RESULTS 3.1 CIRCULATINGAND SERVICE WHOLE-WATER SAMPLING Sampling of planktonic veligers in the circulating, ESW, and NESW systems was initiated on 20 July and completed 14 August. A total of 24 samples were taken in the three different systems.

The circulating water system sampler was susceptible to mechanical failure. On two occasions, the pump's thermal protector shut down the unit during the 24-hr sampling period. Causes were actual pump failure and a clogged intake. High plankton densities in forebay on 11 and 14 August caused the net to clog and overflow during the night hours. As a result, samples on these dates represent 8 hrs of sampling. All changes were made after approval by I&M personnel. In light of these problems, care must be taken when interpretating the circulating water data, as early counts are likely underestimated.

No similar problems were encountered on the ESW and NESW systems because they were equipped with valves capable of adjusting flow rates. The 21 July sample from the NESW system was not taken because no flow was available at the sampling point. This was a result of an outage. The sampling apparatus was moved to a new location in the system for the next sample period, thereby solving the problem.

Results of sampling are presented in Table 3-1 and Figure 3-1. ESW results showed one major peak on 11 August, when densities were in excess of 7000/ms. The NESW system exhibited a peak during each sampling date during the 4-11 August period. Densities in the circulating water system did not exceed 2000/ms during the sampling season but did peak on 11 August.

3-1 Lawler, Matusky 4 Skelly Engineers

TABLE 3-1 WHOLE-WATER SAMPLING VELIGERS/1000 l, TEMPERATURE, AND pH Donald C. Cook Nuclear Plant 21 July - 14 August 1992 VELIGER DATE LOCATION ABUNDANCE 'C pH 21 July Forebay 8 21.9 8.4 ESW 1395 28.9 8.3 NESW a a a 24 July Forebay 7 15.6 8.1 ESW 1693 16.2 8.2 NESW 1049 19.0 8.0 28 July Forebay 68 18.5 7.9 ESW 753 18.7 8.1 NESW 1280 22.9 7.9 30 July Forebay b 185 8.2 ESW 32 21.5 8.4 NESW 148 25.0 8.2 4 August Forebay 546 19.8 8A ESW 1925 20.0 8.5 NESW 5350 21.5 8.5 7 August Forebay b 193 8.2 ESW 1610 19.5 8.2 NESW 6300 20.4 8.2 11 August Forebay 21.8 8.5 1967'043 ESW 22.2 8.7 NESW 5595 223 8.7 14 August Forebay 18.9 8.1 1438'291 ESW 19.3 8.1 NESW 2373 19.9 8.1

'No sample due to inadequate Qow.

No sample due to pump clogging or failure.

'Represents 8 hrs of sampling.

Figure 3-1 Whole Water Sampling Veligers Per 1000 Liters Donald C. Cook Nuclear Plant1992 I FOREBAY ESW NESW 5000 3000 2000 NESW 1000 ESW FOREBAY 07/21 07/24 07/28 07/30 08/04 08/07 08/11 08/14

3.2 FIRE PROTECTION SYSTEM SAMPLING No mollusks were found in any of the hydrant samples.

'.3 ARTIFICIALSUBSTRATE SAMPLING 3.3.1 Forebay Settling Settling rates for the circulating water system (forebay) are shown in Table 3-2 and Figure 3-2. Averages for the three forebay locations are not presented so that spatial differences in settlement resulting from different flow velocities within the baffles installed in the forebay can be shown.

Peak settlement occurred on 6 October with slightly over 100,000/m~ detected in the sheltered central forebay location. Other forebay locations peaked simultaneously but at much lower densities (6000 to 8000 m~). These peaks occurred after the whole-water sampling program had ended; therefore, no inferences can be made. A late peak that occurred on 10 November at the central forebay location was the result of larger juveniles translocating from the Plexiglass frame to the slides. This phenomenon continued until 22 December, suggesting active movement even at low lake temperatures.

No data are presented for the forebay south location for 10 November to 22 December. As

. the unit came on line successive circulating pumps were turned on, creating the high water velocities and heavy turbulence. This turbulence shattered all slides held at this location.

3.3.2 Service Water Settling Settling rates for the service water systems are shown in Table 3-2 and F;gure 3-2. An early peak (more than 45,000/m~) occurred on 25 August in the ESW system, while densities over 5000/m~ occurred sporadically from early August to the beginning of December. The NESW system exhibited a much lower peak of approximately 8700/m~ on 8 September.

3-2 Lawler, Matushy & Skelly Engineers

TABLE 3-2 GI POSTVELIGER SEITLEMENT - No/ma Donald C. Cook Nuclear Plant July - December 1992 FOREBAY FOREBAY FOREBAY DATE NESW SOUTH CEREAL NORTH 28 July 2873 0 0 4,160 2@11 11 August 6,044 1,467 461 1,067 313 25 August 5,237 45,262 486 1,397 338 8 September 8,693 6,719 526 871 379 22 September 2,469 1,621 4,101 3,754 3,797 1 6 October 7,176 5,478 6,019 102,099 8,037 20 October 2,711 a 106 239 133 10 November 711 7,422 b 13,493 5,165 1 I

1 December 667 7,155 b 2@20 533 22 December 274 4/22 b 1/73 338

'Result of no flow through biomonitor; flow restriction caused by accumulation of zebra mussel shells.

Slides broken by turbulence.

Figure 3-2 Post Veliger Settlement Individuals Per Square Meter Donald C. Cook Nuclear Plant 1992 I~

~ Forebay North Forebay Central 120 100 I Forebay South ESW iiIIIl NEsw 80 4

Crt D 60 O

40 Forebay Nohh Forebay Central Forebay South 20 ESW NESW 07/28 08/11 08/25 09/08 09/22 10/06 0/20 11/10 12/01 12/22

These relatively high values may not be representative of actual settling within the system because of design problems with the biomonitors used to house the slides. Having low flow rates and an upflow design, these biomonitors easily clogged with sand, silt, and zebra mussel shells and shell fragments. Because of the reduced flow, settling data for NESW and ESW should be considered qualitatively.

Visual inspections showed that live juveniles were regularly present inside the biomonitors prior to the Clam-Trol, CT-1 treatment. They reappeared in early October to late December.

Juveniles of 3 to 5 mm were abundant during the final inspection on 22 December, indicating survival and growth of zebra mussels within low-flow areas of the service water systems. No zebra mussel settling was observed on the heat exchanger in the condenser tubes at these stations.

3.3.3 Qualitative Effects of Biocide Treatments Two types of biocides were used to control the zebra mussel within the Cook Nuclear Plant.

Chlorine as sodium hydrochlorite, presently permitted under the facility's National Pollutant Discharge Elimination System Permit, was injected into all systems throughout the period of this project. Chlorine was injected continuously for 2 hrs during each 24-hr period. Based on the observations,'his was not effective.

Clam-Trol, CT-1, a proprietary molluscicide, was added as a 12-hr treatment on 16 September.

Substrates examined on 22 September indicated >90% mortality. This effective treatment was, however, short lived; three weeks later, peak settlement occurred in the forebay.

~ 3.4 BEACH WALKSAMPLING Two locations were examined as part of the beach walk sampling effort. The first location was'he beach adjacent to the Cook Nuclear Plant. Because there is minimal hard substrate present on this beach, the examination focused on searching for loose shells. The second 3-3 Lawler, Matushy & Skelly Engineers

location was an area of riprap along the south side of the south jetty at the mouth of the St.

Joseph River in St. Joseph, Michigan.

On 23 July the beach near the plant was examined. Numerous clumped and single dead zebra mussel adults and shell fragments were found along the storm wash line. Examination along the south jetty in St. Joseph also revealed beach-washed dead adults and shells.

The walks were repeated on 22 September and 10 November with similar Gndings.

3.5 INSPECTION SAMPLE ANALYSES Two inspection samples were collected by plant personnel and shipped to LMS for analysis.

Results are shown in Table 3-3.

3.6 RANDOM SAMPLE ANALYSES A test was conducted from July 17, 1992 to September 8, 1992 on several coatings that are marketed as antifouling coatings. Metal coupons with various coatings were placed in the intake forebay for the test period, retrieved, and the settlement rate evaluated. The company is reviewing these data and the results from other research on coatings to determine the usefulness of antifouling coating on intake structures such as trash racks and traveling screen assemblies.

3.7 WATER QUALHT MONITORING Water temperatures and pH were recorded during each whole-water and artiGcial substrate sampling period. Values recorded during the collection of whole-water samples are presented in Table 3-1. Those values recorded during the postveliger settlement collections are shown in Table 34.

Lawler, Matushy 8c Skelly Engineers

TABLE 3-3 INSPECTION SAMPLE ANALYSES Donald C. Cook Nuclear Plant July and September 1992 DATE SITE DESCRIPTION RESULTS 7 July Traveling Screen Bay 1-2 Adults (8+ mm)

Temp: 18.8 'C Juveniles (3-8 mm) 216 pH: 8.1 Shell Fragments Abundant 30 September North Side Center Intake Adults (8+ mm)

Crib - Lake Bottom Juveniles (3-8 mm) 17 Temp: 12.2 'C Shell Fragments 30 pH: 8.1 Small Snails

TABLE 34 TEMPERATURE AND pH VALUES, POSTVELIGER SEITLEMENT COLLECTIONS Donald C. Cook Nuclear Plant July - December 1992 FOREBAY NES%

DATE pH 'C pH oC pH 'C 28 July 8.2 18.2 8.1 18.7 7.9 22.9 11 August 8.5 21.3 8.7 22.2 8.7 22.3 25 August 8.1 22.0 8.2 22.9 8.1 22.7 8 September 7.9 215 8.1 22.5 8.1 21.9 22 September 8.1 15.0 8.2 16.7 8.2 182 a a 15.1 6 October 8.1 14.6 8.1 a a 8.1 12.7 20 October 8.1 12.5 0 November 8.0 10.4 8.0 113 8.0 115 December 8.0 7.2 8.1 8.5 8.1 8.7 22 December 8.0 3.7 8.0 43 8.0 5.7

'Not available from plant personnel.

CHAPTER 4 DISCUSSION OF RESULTS 4.1 CIRCULATINGAND SERVICE WHOLE-WATER SAMPLING Veliger abundance data presented in Table 3-1 must be viewed with caution. The many mechanical problems encountered sampling the forebay greatly influenced the results. Even though the data reported for 11 and 14 August represent 8- rather than 24-hr samples, these results, when extrapolated to a 24-hr period, may be the most representative of the concentration of veligers in the forebay during the four-week period. These forebay data may reflect the beginning of the spawning peak that resulted in peak settlement during September throughout the region (reported by numerous investigators during the Third International Zebra Mussel Conference, Toronto, February 1993).

Comparison of the extrapolated forebay veliger concentrations to the veliger concentrations reported for the service water systems on 11 and 14 August suggests that forebay and service water concentrations were similar. Based on this comparison, concentrations of veligers in the forebay may have been similar to those reported for the service water systems on the earlier sampling dates. when mechanical problems occurred with forebay sampling.

'.2 ARTIFICIALSUBSTRATE SAMPLING 4.2.1 Forebay In the forebay, postveliger settlement was low until September, with the exception of the

. central and north locations on 28 July. These higher concentrations most likely reflect a spawning spate that occurred during the flrst half of July, before the whole-water monitoring program was initiated. The higher concentrations reported for September follow the trend reported by numerous other investigators working in the southern Lake Michigan region (Third International Zebra Mussel Conference).

Lawler, Matusky & Skelly Engineers

The highest concentrations recorded at each location in the forebay occurred on 6 October, approximately three weeks after the Clam-Trol treatment. While reasons for the high settlement are not known at this time, this phenomenon has been observed in previous years.

The secondary peak of settlement recorded at the central and north locations on 10 November reflects the translocation of juveniles rather than settling of a new cohort during the sampling period. This translocation continued at reduced rates until the end of the sampling program in December.

4.2.2 Service Water Systems Settlement occurred throughout the sampling season on the artificial substrates placed in the NESW and ESW systems. During the period covering the sets made on 28 July through those collected on 8 September, the concentrations in the service water system biomonitors exceeded the concentrations reported in the forebay. At a minimum, this indicates that the chlorine injection that occurred upstream of the biomonitors was ineffective at preventing settling. This is most likely attributable to the 2-hr continuous injection during each 24-hr period rather than intermittent injections throughout each day. A second confounding factor was the low flow, upfiow design of the biomonitors. This design was amenable to easily clogging and may not have accurately represented the actual flow conditions in the systems at the monitoring locations, i.e. high velocities in service water pipes. Taken together, these two factors contributed to the high concentrations.

4.3 BEACH WALKS Beach walk inspections in the vicinity of the plant and St. Joseph's harbor revealed no indication of live, attached adult zebra mussels in these areas. Observations made near the plant revealed that a lack of suitable substrate was available for zebra mussel attachment.

Numbers of dead or detached shells in the drift line were observed in both locations. These had washed on shore during storm events.

Lawler, Matusky 4 Skelly Engineers

4.4 WATER QUALITYMONITORING Water temperatures in the forebay followed expected seasonal trends. Temperatures recorded at the NESW and ESW stations were slightly higher than those reported for the forebay with NESW temperatures being the highest.

Values reported for pH indicate that pH generally ranged between 7.9 and 8.2. Exceptions occurred on 4 and 11 August when recorded pH values were between 8.4 and 8.7. All these values are basic, suggesting that water conditions are conducive to zebra mussel life history success. Actual water concentrations of calcium would be required to verify this condition.

4.5 RECOMMENDATIONS Based on observations made during the course of this program, several recommendations are being presented to eliminate certain problems and to acquire a more complete data base.

These include the following:

~ Plate samplers rather than slide samplers are recommended for the forebay stations.

~ In-line flowmeters are recommended for all biobox installations. This will eliminate inaccurate fiows being estimated when clogging or other mechanical problems prematurely end the sampling.

~ Commercially constructed bioboxes should be used for in-plant service water system sampling. These should be located in areas where pipeline flow is slow enough to permit postveliger settling.

~ Whole-water sampling should be initiated during the early part of May or when forebay temperatures are 10'C and continue to September. According to Ellen Marsden (pers. commun.), portions of southern Lake Michigan were reported to have veliger densities of approximately 30,000/m3 by mid-May 1992. This is important to make decisions regarding initiation of preventive control programs.

~ Postveliger settlement sampling needs to be conducted from mid-May through December at a minimum. 'I%is will allow monitoring of settlement times and preventative control success within the service water or other systems.

Lawler, Matnsky 4 Skelly Engineers

APPENDIX A EXPERIMENTALCOATINGS TEST Donald C. Cook Nuclear Plant Forebay 17 July - 8 September 1992 JUVENILE POSTVELIGER NAME INFESTATION SETTLEMENT (Norm~)

Rhino-textured red None 1,599 Rhino-grey mesh Light Rhino-grey triangle None 1,599 Porter HKA 800 Sys 2000 None 12,799 Epotech 2000 None none Dow Envelon Heavy Wisconsin C-793 Medium Porter Multi Light 3,733-5,333 Easy-On Light 34,133 Zebra Wax None 5,866 Plastic Bar Grill Light

APPENDIX V ANNUAL REPORT'ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1992

DONALD C. COOK NUCLEAR PLANT UNITS 1 & 2 OPERATIONAL RADIOLOGICAL ENVIRONMENTALMONITORING PROGRAM 1992 ANNUAL REPORT JANUARY 1 to DECEMBER 31, 1992 Prepared by Indiana Michigan Power Company axld Teledyne Isotopes April 15, 1993

TABLE F EN SECTI N TITLE PAGE S uInmary o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ o o ~ o ~ o ~ ~ ~ ~ o ~ o ~ ~ ~ ~ o e o o o o o o o o o o o o o o 1 I. Introduction oooo ~ oooo ~ ~ oo ~ ~ o ~ oo ~ o ~ oo ~ oo ~ o ~ ~ ~ oo ~ ~ ~ o ~ ~ o ~ ~ o ~ o 3 II. Sampling and Analysis Program.............................. 5 III. SuIIImary and Discussion of 1992 Analytical Results ........... 18 A. Airborne Particulates................................ 19 E Airborne Iodine .................................... 21 C. Direct Radiation - TLDs.............................. 22 D. Surface Water ...................................... 22 Eo G03und/WCIIWat5 o e o ~ e e ~ o o o o ~ o o ~ o o o o o o o o o o ~ e o ~ ~ ~ ~ ~ o 24 F. Drinking Water..................................... 28 G. Sediment.................. o o o o o o e e o ~ o o o o o ~ o ~ o o ~ o 28 H ~ Milk ~ o o o o o ~ o o o ~ o e o o o ~ o ~ ~ ~ o o ~ ~ o ~ o ~ o o o ~ o o o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 30 I HShe ~ o o ~ o o e e o ~ o o o o o o ~ e ~ ~ o o o ~ ~ e o o ~ ~ e o o ~ ~ e o o o o o o e ~ ~ o 31 J. Food Products ...................................... 31 IV. Conclusions.............................................. 32 V. References .............................................. 36

TABLE OF CONTENTS {Cont)

A~PPENDI E APPENDIX A - Radiological Environmental Monitoring................. 38 Program Summary - 1992 APPENDIX B - Data Tables ........................................ 43 APPENDIX C - Analytical Procedures Synopsis ........................ 71 APPENDIX D - Suznmazy of EPA Interlaboratory Comparisons ........... 87 APPENDIX E - REMP Sampling and Analytical Exceptions............. 117 APPENDIX F - Land Use Census ................................... 120 APPENDIX G - Summary of the Preoperational Radiological............ 127 Monitoring Program APPENDIX H - Summaxy of the REMP Quality Control Program ........ 131 APPENDIX I - Summary of the Spike and Blank Sample Program....... 133 APPENDIX J - TLD Quality Control Program ......................... 146

TABLE OF CONTENTS (Cont)

LIST F FI

l. Onsite K)Locations o ~ o ~ o ~ ~ o ~ ~ o ~ o ~ o ~ ~ o o o o ~ ~ o o ~ o o s o ~ o ~ ~ o ~ ~ o 11

2. Onsite - Groundwater Wells .................................. 12 Onsite - Air Stations. o ~ ~ o ~ o o ~ o o o ~ ~ o ~ o o ~ ~ o ~ o ~ ~ o o o ~ o ~ o ~ ~ ~ ~ ~ 13 4, Onsite - Steam Generator Groundwater Wells ................ 14

5. Air, Well and Lake Water Locations ............................ 15 TLD Locations 00000100\0 ~ 0 ~ ~ 0 ~ 1010t ~ 11 ~ 10 F 000 0 0 0 ~ ~ ~ ~ ~ 0 0 ~ ~ ~ ~ 16

7. Fish Locations ............... o o ~ o o o o o ~ ~ ~ ~ ~ ~ o ~ ~ 17

8. MilkAnimal Survey'Ihble.............................. 123

9. Residental Land Use Survey Table ............................ 124

10. Milk Farm Survey Map..................................... 125 Residential Survey Map ................................... 126 LIST OF TRENDING GRAPHS Average Monthly Gross Beta in Air Particulates .................. 20

2. Direct Radiation - Quarterly TLD's............................. 23

3. Tritium in Groundwater ..................................... 25 4 Tritium in Drinking Water ................................... 29 EPA Cross Check Program ... ~ o ~ ~ ~ ~ ~ ~ o ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ 92

6. Quality Control TLDs ..... ooooooooeooo ~ ~ ~ ~ ~ oo ~ ~ ~ oo ~ ~ ~ ~ ~ o 148

LIST OF TABLES TABLE TITLE PA E B-l Concentrations of Gross Beta Emitters in Weekly................... 44.

Airborne Particulates B-2 Concentrations of Gama'mitters in Quarterly.................... 48 Composites of Airborne Particulate Samples B-3 Concentrations of Iodine-131 in Weekly Air Cartridge............... 50 Samples B-4 Direct Radiation Measurements - Quarterly TLD Results............. 54 B-5 Concentrations of Iodine, Tritium and Gamma Emitters............. 55 in Surface Water t

B-6 Concentrations of Tritium and Gamma Emitters in 58 Quarterly Groundwater B-7 Concentrations of Gross Beta, Iodine, Tritium and.................. 60 Gamma Emitters in Drinking Water B-8 Concentrations of Gamma Emitters in Sediment ................... 62 B-9 Concentrations of Iodine and Gamma Emitters in Milk.............. 63 B-10 Concentrations of Gamma Emitters in Fish ........................ 67 B-11 Concentrations of Gamma Emitters in Food/Vegetation ............. 68 B--12 7giC(QLLDsAchicvCdooo oooooo ~ ~ oooooooo ~ o ~ ~ ~ ooo ~ ooo ~ oooooo ~ oo 69

SUMMARY

INDIANAMICHIGAN POWER COMPANY DOITED) C. COOK POWER NUCLF~ PLA'NT RADI L GI AL ENVIRONMENTALM NITORIN PR GRAM I

SUMMARY

This report summarizes the collection and analysis of various environmental sample media in 1992 for the Radiological Environmen-tal Monitoring Program for the Donald C. Cook Nuclear Plant.

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

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

I. INTRODUCTION

~INTR D TI N The Donald C. Cook Nuclear Plant's Radiological Environmental Monitoring Program (REMP) is conducted in compliance with NRC Regulatory Guide 1.21 and 4.1, licensing commitments, and Technical Specifications. The REMP was developed in accordance with the NRC Radiological Assessment Branch Technical Position (BTP), Rev. I, November 1979. A synopsis of the sampling program and maps can be found in Section II, Sampling and Analysis Program. This report represents the Annual Environmental Operating Report for Units 1 and 2 of the Donald C.

Cook Nuclear Plant for the operating period from January 1, 1992 through December 31, 1992.

,A. The Donald C. Cook Nuclear Plant of Indiana Michigan Power Company is located on the southeastern shore of Lake Michigan approximately one mile northwest of Bridgman, Michigan. The plant consists of two pressurized water reactors, Unit 1, 1030 MWE and Unit 2.

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

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

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

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

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

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

4

II. SAMPLING AND ANALYSIS PROGRAM II. AMPLIN AND ANALY I PR RAM Table 1 sunUnarizes the sampling and analysis program for the Donald C. Cook Nuclear Plant for 1992. For each sample medium, the table lists the sample locations, including distance and direction from the center of the two units, and the station identiQcation. The station identifications 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 1 DONALD C. COOK NUCLEAR PLANT- 1992 RADIOLOGICALSAMPLING Sl'ATIONS DISTANCE AND DIRECTION FROM PLANT AXIS Collec on Location Station Direction De rees Fre uen Environmental 's)

ONS-1 (A- I) 1945 A. 180 ONS-2 (A-2) 2338 A 480 ONS-3 (A-3) 2407 A 90'180 ONS-4 (A-4) 1852 A.

ONS-5 (A-5) 1895 A. 1890 ONS-6 (A-6) 1917 A. 2100 ONS-7 (A-7) 2103 IL 36o ONS-8 (A-8) 2208 lt. 820 ONS-9 (A-9) 1368 A.

ONS-10 (A-10) 1390 A. 149'27'14 ONS-11 (A-11) 1969 A.

ONS-12 (A-12) 2292 A. 630 New Buffalo (NBF) 16.0 ml SSW Quarterly Direct Radiation/Quarterly South Bend (SBN) 24.0 mi SE Dowagiac (DOW) 24.3 ml ENE Coloma (COL) 18.9 mi NNE Intersection of Red Arrow Hwy. & Marquette (OFS-1) 4.5 mi NE Woods Rd, Pole ¹B294-44 Stevensville Substation (OFS-2) 3.6 mi NE Pole ¹B296-13 (OFS-3) 5.1 ml NE Pole ¹B350-72 (OFS-4) 4.1 mi E Intersection of Shawnee & Cleveland, Pole (OFS-5) 4.2 mi ESE

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

¹B426-1 Bridgman Substation (OFS-7) 2.5 mi S California Rd., Pole ¹B424-20 (OFS-8) 4.0 mi S Riggles Rd.. Pole B369-214 (OFS-9) 4.4 ml ESE Intersection of Red Arrow Hwy., & (OFS-10) 3.8 mi S Hildebrant Rd.,Pole ¹B422-152 Intersection of Snow Rd. & Baldwin Rd., (OFS-11) 3.8 mi Pole ¹B423-12

TAB t.l DONALD C. COOK PLANT- 1992 RADIOLOGICALSAMPLING STA'11ONS DISI'ANCE AND DIRECTION FROM PLANT AXIS Collection Location Station Distance Direction De rees uen Is/ n Air Charcoal/Particulates ONS-I (A- I) 1945 A. 184 ONS-2 (A-2) 2338 ft.

ONS-3 (A-3) 2407 A.

ONS-4 (A-4) 1852 A. 48'0'18'89'104 ONS-5 (A-5) 1895 A.

ONS-6 (A-6) 1917 A. Weekly Gross Beta/Weekly New Bullalo (NBF) 16.0 ml SSW 1-131/Weekly South Bend (SBN) 24.0 ml SE Gamma Isotopic/

Dowagiac (DOW) 24.3 ml ENE Quarterly Composite Coloma (COL) 18.9 ml NNE Groundwater Onsite (W-1) 1969 A.

Onslte (W-2) 2292 A. 11'3'074 Onsite (W-3) 3279 A.

Onsite (W-4) 418 A. Quarterly Gamma Isotopic/Quarterly Onsite (W-5) 404 A. 301'90'734 THtium/Quarterly Onslte (W-6) 424 A.

Onslte (W-7) 1895 'A. 1894 Onslte (W-8) 1279 A. 53'24 Onsite (W-9) 1447 A.

Onslte (W-10) 4216 A. 1294 Onslte (W-11) 3206 A. 153'624 Onslte (W-12) 2631 A.

Onslte (W-13) 2152 A. 1824 Non Technical 8 cification Related Wells Steam Generator Storage Faclllty (SGRP-1) 0.8 mi 95'24 Steam Generator Storage Facility (SGRP-2) 0.7 mi Gross Beta/Monthly Steam Generator Storage Facility (SGRP-4) 0.7 mi 934 Quarterly Gross Alpha/Monthly Steam Generator Storage Facility (SGRP-5) 0.7 mi 924 Gamma Isotopic/Monthly

TABLE 1 (Cont.)

DONALD C. COOK NUCLEAR PLANT- 1892 RADIOLOGICALSAMPLING STA'HONS DISTANCE AND DIRECHON FROM PLANT AXIS Co ec on Distance DIrection De rees lIen Water St. Joseph Public Intake (STJ) 9.0 ml NE Gross Beta/14 Day Compost te Gamma Isotopic/14 Day Composite 1-131/14 Day Composite Lake Township Public Intake StaUon (LTW) 0.4 ml TrtUum/Quarterly Composite Sruface Water Condenser ClrculaUng Water Intake Ll Intake Lake Michigan Shoreline L-2 ~

0.3 ml S Gamma Isotopic/Monthly Lake Michigan Shoreline L-3 0.2 ml N Composite Lake Michigan Shoreline I 4 0.1 ml S 'MUum/Quarterly Composite Lake Michigan Shoreline L-5 0.1 ml N Sediment Lake Michigan Shoreline L-2 0.3 ml S Lake Michigan Shoreline L-3 0.2 ml N Semi-annually Gamma Isotopic/Semt-Lake Michigan Shoreline I 4 0.1 ml S Annually Lake Michigan Shoreline I 5 0.1 ml N RHIk-Indicator Totzke Farm Baroda Totzke 5.1 ml ENE Schuler Farm Baroda Schuler 4.1 ml SE Wannblen Farm Three Oaks Warmblen 7.7 ml S 14 Days 1-131 Sample Zelmer Farm Bridgman Zelmer 4.8 ml SSE Lomzack Farm Galien Lozmack 9.5 mi SSE Freehling Farm Bucharmm Freehllng 7.0 ml SSE MIIk-Bac ormd Wyant Farm Dowagaic Wyant 20.7 mi E Once every Gamma Isotopic/Sample Llvln e Farm La Porte Livlnghouse 20.0 mi S 14 Days 1-131/ Sample

TAB t.)

DONALD C, COOK N EAR PLANT- 1992 RADIOLOGICALSAMPLING STA'11ONS DISTANCE AND DIRECTION FROM PLANT AXlS CollecUon Location Station Distance Direction De ees uen Lake Michigan ONS-N .3 ml N 2/year Gamma Isotopic Lake Michigan ONS-S .4 ml S 2/year Lake Michigan OFS-N 3 .5ml N Lake Mlchlgan OFSN 5.0 ml S Gra /Broadleaf Nearest sample to Plant Sector J At Ume of harvest Gamma Isotopic at ln highest D/Q land sector Ume of harvest.

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

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

Approximately 20 miles from the Plant Sector B At time of harvest Gamma Isotopic at Ume of harvest.

Composite samples of Drinldng and Surface water shall be collected at least dally.

ParUculate sample Alters should be analyzed for gross beta acUvity 24 or more hours following filter removaL This will allow for radon and thoron daughter decay. Ifgross beta acUvity in air or water is greater than 10 times the yearly mean of control samples for any medium. gamma isotopic analysis should be performed on the individual samples.

Please note the following defenitions:

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

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III. SU5HCARY AND DISCUSSION OF 1992 ANALYTICALRESULTS MMARYAND DISC S I N F 19 2 ANALYTICAL 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 1992 were analyzed by Teledyne Isotopes, Inc. (TI) in Westwood, New Jersey. The procedures and specifications followed at Teledyne Isotopes are in accordance with the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples are proved in Appendix C. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix D.

Radiological analyses of environmental media 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 1, November 1979.

The following is a discussion and summary of the results of the environmental measurements performed during the reporting period.

Comparison is made where possible with radioactivity concentrations measured in the preoperational period of August 1971 to the initial criticality of Unit 1 on January 12, 1975. A brief summary of the preoperational program is found in Appendix G.

A. Airb rn P i ul 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 ..

AVERAGE MONTHLY GROSS BETA IN AIR PARTICULATES

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-+ Indicators ---a--- Controls

'4

the gross beta activity on the weekly air particulate liters 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/m~ with a range of individual values between 0.003 and 0.035 .pCi/m~. The average gross beta concentration of the four control locations w'as 0.017 pCi/m> with a range between 0.007 and 0.035 pCi/m. In Trending Graph 1 the monthly average gross beta concentrations for the indicator locations and for the control locations are plotted. The gross beta concentrations in air particulate liters in 1992 were lower than at the end of the preoperational period when the effects of recent atmospheric nuclear tests were being detected.

Air particulate filters were composited by location on a quarterly basis and were analyzed by gamma ray spectroscopy. 'Beryllium-7 which is produced continuously in the upper atmosphere by cosmic radiation was measured in all forty samples. The average concentration for the control locations was 0.108 pCi/m> and the values ranged from 0.088 to 0.177 pCi/m~. The average concentration for the indicator locations was 0.108 pCi/m> with a range of 0.085 to 0.153 pCi/m>. 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 six of the twenty-four indicator quarterly composites with an average concentration of 0.006 pCi/m~ and a range of 0.003 to 0.011 pCi/m~. Potassium-40 was measured in one of the sixteen control quarterly composites with a concentration of 0.008 pCi/m>. 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. Teda-3B charcoal cartridges are installed downstream of the particulate filters and are used to collect airborne radioiodine. The results of the weekly analysis of the charcoal cartridges are presented in Table'B-3. All

results were below the lower level of detection with no positive activity detected.

Dir R ia on-Thrm lumin n D im r Thermoluminescent dosimeters (TLDs) measure external radiation exposure from several sources including naturally occurring radionuclides in the air and soQ, radiation from cosmic origin, fallout from atomic weapons testing, potential radioactive airborne releases from the power station and direct radiation from the power station.

The TLDs record exposure from all of these potential sources. The TLDs are deployed quarterly at 27 locations in the environs surrounding the D. C. Cook Nuclear Plant. The average value of the four areas of each dosimeter (calibrated individually after each field exposure period for response to a known exposure and for transit exposure) are presented in Table B-4. Those exposure rates are quite typical of observed rates at many other locations in the country. The average annual measurement for the control samples was 3.68 mR/standard month with a range of 3.3 to 4.4 mR/standard month.

The annual accumulation of indicator samples had a measurement of 3.94 mR/standard month with a range of 3.1 to 5.1 mR/standard

. month..The 1992 annual average in the environs of the D. C. Cook Plant is at the low range of the exposure rates (1.0 to 2.0 mR/week) measured during the preoperational period; The results of the indicator and control TLDs are in good agreement and are plotted in Trending Graph 2.

Surf c W ter One liter surface water samples from the intake forebay and from four shoreline locations, aQ within 0.3 mile of the two reactors were collected and composited daily over a monthly period. The samples were analyzed for iodine-131 by the radiochemical technique described on page 79. No iodine-131 was detected. The quarterly composite was analyzed for tritium by gas counting, described on page 73, during the Qrst and second quarters when this method was 22

DIRECT RADIATION- QUARTERLY TLD RESULTS I h

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discontinued. The third and fourth quarterly composites were analyzed the by liquid scintillation method described on page 74.

Naturally occurring potassium-40 was measured in three samples with an average concentration of 61.5 pCi/liter and a range of 55.9 to 68.0 pCi/liter. Cesium-137 was measured in one sample with an activity of 7.19 pCi/liter. Tritium was detected in 12 of the 20 samples analyzed with an average concentration of 554 pCi/liter and a range of 170 to 1400 pCi/liter, This is higher than the 15 measurements in 1991 which had an average concentration of 239 pCi/liter. During the preoperational period tritium was measured in surface water samples at concentrations of approximately 400 pCi/liter. Naturally occurring gamma emitting isotopes were detected using gamma ray spectroscopy.

Groundwat r Water samples are collected quarterly from thirteen 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 tritium.

The results are presented in Table B-6. Naturally occurring potassium-40 was measured in four samples with an average concentration of 76.6 pCi/liter and a range of 39.1 to 161 pCi/liter.

No other gamma emitting isotopes were detected. The groundwater wells W-4, W-5, W-6, W-7, W-10, W-12 and W-13 had measurable tritium activity throughout 1992. Tritium was measured in three of the sixteen samples at the locations with an average concentration of 662 pCi/liter and a range of 120 to 1500 pCi/liter. The annual concentrations of tritium in wells W-1 through W-7 are plotted from in Trending Graph 3. An additional six wells were added to the program during 1992. The results are plotted quarterly for 1992 in Trending Graph 3.

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

24

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

Gross beta activity was measured in all twenty-six samples from the Lake Township intake with an average concentration of 3.6 pCi/liter and a range from 1.9 to 6.2 pCi/liter. Gross beta activity was measured in all twenty-six samples &'om the St. Joseph intake with an average concentration of 3.7 pCi/liter and a range from 2.6 to 5.1

'pCi/liter. No gamma emitting isotopes or iodine-131 were detected.

Tritium was measured in one of the four samples from Lake Township intake with a concentration of 150 pCi/liter. Tritium was measured in one samples from St. Joseph intake with a concentration of 180 pCi/liter. Tritium in drinking water is plotted in Trending Graph 4.

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

G. Sediment Sediment samples are collected semiannually along the shoreline of Lake Michigan at the same four locations as the surface water samples. Two liters of lake sediment are collected using a small dredge in an area covered part time by wave action. The sediment samples are analyzed by gamma ray spectroscopy, the results of which are shown in Table B-8. In May and November one sample was collected from each location L2, L3. L4 and L5. Gamma ray spectroscopy detected naturally occurring potassium-40 and in all samples. The average potassium-40 concentration was 5628 pCi/kg (dry weight) with a range from 4390 to 6470 pCi/kg (dry weight).

Thorium-228, also naturally occurring was measured in seven of the 28

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Thorium-228, also naturally occurring was measured in seven of the eight samples with an average concentration of 130 pCi/kg (dry weight) with a range from 95.3 to 150 pCi/kg (dry weight). Cesium-137, attributed to fallout from previous atmospheric nuclear tests, was not detected during 1992. All other gamma emitters were below the lower limits of detection.

MQk samples of one gallon are collected from a 500 gallon bulk tank every fourteen days from seven farms located between 4.1 miles and 20.7 miles from the site. Milk samples are preserved by adding 40 grams per gallon of sodium bisulfate when the samples are collected. The samples are analyzed for iodine-131 and 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 1992. 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 1992 the average potassium-40 concentration for the control locations during was 1347 pCi/liter with a range of 1110 to 1890 pCi/liter. The indicator locations had an average concentration of 1379 pCi/liter and a range of 1020 to 1870. There were no detections of iodine-131 during 1992. Cesium-137 was detected in one background sample with a concentration of 9.34 pCi/liter and one indicator sample with a concentration of 13.4 pCi/liter.

30

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

Naturally occurring potassium-40 was measured in all samples with an 1 average concentration of 3113 pCi/kg (wet weight) and a range of 2340 to 4160 pCi/kg (wet weight). Cesium-137 was measured in one of the eight Qsh samples with a concentration of 48.0 pCi/kg (wet weight).

J. Food Products Food samples are collected annually at harvest, as near the site .

boundary as possible. and approximately twenty miles from the plant.

They consist of 5 pounds of grapes, 1 pound of grape leaves and 5 pounds of broadleaves. Naturally occurring potassium-40 was measured in all eight samples with an average concentration of 2401 pCi/kg (wet weight) and a range of 1630 to 3850 pCi/kg (wet weight).

Cosmogenically produced beryllium-7 was measured in six of the eight samples with an average concentration of 1976 pCi/kg (wet weight) and a range of 58.2 to 4030 pCi/kg (wet weight). Cesium-137 was measured in two samples with an average concentration of 28.1 pCi/kg (wet weight) and a range of 19.9 to 36.2 pCi/kg (wet weight).

31

IV. CONCLUSIONS 32

IV. CttNGL IOIIS The results of the 1992 Radiological Environmental Monitoring Program for the Donald C. Cook Nuclear Plant have been presented. The results were as expected for normal environmental samples. Naturally occurring radioactivity was observed in sample media in the expected activity ranges.

Occasional samples of a few media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence. Specific examples of sample media with positive analysis results are discussed below.

Air particulate gross beta concentrations of all the indicator locations for 1992 appears to follow the gross beta concentrations at the control locations. The concentration levels are actually lower than during the preoperational period when the influence of atmospheric nuclear tests was being detected. Gamma isotopic analysis of the particulate samples identified the gamma. emitting isotopes as natural products (beryllium-7 and potassium-40). No man-made activity was found in the particulate media during 1992. No iodine-131 was detected in charcoal filters in 1992.

Thermoluminescent dosimeters (TLDs) measure external gamma radiation from naturally occurring radionuclides in the air .and soil, radiation

~ from cosmic'origin and fallout from atmospheric nuclear weapons testing, and radioactive airborne releases and direct radiation from the power plant.

The average annual TLD results were at normal background exposure levels.

Surface water samples are collected daily from the intake forebay and four locations in Lake Michigan. The samples are analyzed quarterly for tritium, and monthly for gamma emitting isotopes. Only one gamma emitter, cesium-137, was detected in one sample during 1992. Tritium was measured and the concentrations were at normal background levels.

Groundwater samples were collected quarterly at thirteen wells, all within 3300 feet of the reactors. The three wells within 500 feet had 33

measurable tritium which is attributed to the operation of the plant. The tritium levels in 1992 compare well with those measured in 1991. The highest concentration measured in 1992 was 1500 pCi/liter while the highest concentration measured during 1991 was 1700 pCi/liter. The tritium levels in groundwater have been plotted for the last decade and indicate decreasing levels of tritium. Potassium-40, a naturally occurring nuclide was observed in four samples during 1992. No other gamma emitting isotopes were detected.

Samples are collected daily at the intakes of the drinking purlQcation plants for St. Joseph and Lake Township. Samples composited daily over a two week period are analyzed for iodine-131, gross beta, and for gamma emitting isotopes and analyzed quarterly for tritium. No iodine-131 or gamma emitting isotopes were detected. Gross beta was measured in all fifty-two samples at normal background concentrations. Tritium was measured in four of the eight quarterly composite samples with background levels that were lower than those measured during 1991.

Sediment samples can be a sensitive indicator of discharges from nuclear power stations. Sediment samples are collected semiannually along the shoreline of Lake Michigan at four locations in close proximity of the reactors. The samples were analyzed by gamma ray spectroscopy and only naturally occurring gamma emitters were detected. There is no evidence of station discharges affecting Lake Michigan, either in the sediments or in the water, as previously discussed.

Milk samples were collected every fourteen days from 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 during 1992 or 1991. Potassium-40 was measured in all mQk 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 isotope measured was cesium-137 which was in a very low concentration in one sample.

Food products, consisting of grapes, grape leaves, and broadleaf vegetation were cellected and analyzed by gamma ray spectroscopy. The only gamma emitting isotope measured was cesium-137.

The results of the analyses have been presented. Based on the evidence of the Radiological Environmental Monitoring Program the Donald C. Cook Nuclear Plant is operating within regulatory limits. Tritium in Qve on-site wells appears to be the only radionuclide which can be directly correlated with the plant. However the associated groundwater does not provide a direct dose pathway to man.

35

V. REFERENCES 36

V. REFERENCES

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

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

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

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

May 1975.

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

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

7. United States Nuclear Regulatory Commission, Regulatory Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, April 1974.

37

APPENDIX A RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

38

RADIOLOGICALENVHtONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 6&816/NM16 BERRIEN COUNTY'ANUARY 1 to DECEMBER 31, 1992 MEDIUMOR PATHWAY 'IIALNUMBER CONIROL LOCATION NONROUIINE SAMPLED OF ANALYSES MEAN la/b) NAME MEAN MEAN REPORTED IUNII'FMEASUREMENII PERFORMED RANGE DISI'ANCE AND DIRECIION RANGE RANGE MEASUREMENIS Air Iodine 1-131 631 -(0/317) N/A N/A -(0/214) 0 (pCl/m3)

Airborne Gross Beta 531 16.7(317/317) South Bend 17.3(54/54) 16.6(214/214)

Particulates (Weekly) (2.9-35) 24.0ml SE (7.2-32 (6.6-35)

(IE-03 pCl/m3)

Gamma 40 Be-7 40 107.8(24/24) Dowaglac 24.3 ml ENE 117.9(4/4) 108.4(16/16)

(84.5-163) (91.0-177) (87.6-177J K-40 40 6.31(6/24) A-5 Onslte 1895 (t. 10.0(2/4) 8.31(1/16)

(3. 16-10.7J (9.21-10.7)

Direct Radiation Gamma 108 (mR/Standard Dose 3.94(92/92) OFS-6 4.9 mi SE 4.90(4/4) 3.68(16/16)

Month) Quarterly (3. 1-6. 1) (4.8-5.1) (3.3-4.4)

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

RADIOLOGICALENVlRONME ONITORINQ PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY DONALD C. COOK NUCLEAR PIANT DOCKET NO. 6&418/NM16 BERRIEN COUNIY JANUARY I to DECEMBER 31, 1992 MEDIUMOR PATHWAY 'IOTALNUMBER CONIROL IDCATION NONROVIINE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORfED IUNIl'OFMEASUREMEml PERFORMED RANGE DISI'ANCE AND DIRECIION RANGE RANGE MEASUREMENIS Surface Water Gamma 65 (pCI/liter)

K-40 65 61.5(3/65) I 5 0.1 mi N 62.0(2/13) -(0/0)

(55.9-68,0) (55.9-68.0)

Cs-137 7.19(1/65) L-I Intake Forebay 7.19(l/13) -(0/0)

H-3 20 554(12/20) L-5 O.l mi N 670(2/4) -(0/0)

(170-1400) (340-1000)

Groundwater Gamma 51 (pCI/liter)

K-40 76.6(4/51 Well 10 161(1/4) -(0/0)

(39.1-161)

H-3 51 666(21/51) Well 7 1148(4/4) -(0/0)

(120-1500) (840-1500)

Drlnlrlng Water Gross Beta 52 3.60(52/52) SI J 9.0 mi NE 3.65(26/26) -(0/0)

(pCI/liter) (1.9-6.2) (2.6-5. 1) 1-131 52 -(0/52) N/A N/A -(0/0)

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

H-3 165(2/8) SI J 9.0 mi NE 180(1/4) -(0/0)

(150-180)

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

RADIOLOGICALENVIRONMENTALMONITORING PROGRAM

SUMMARY

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT DOCKET NO. 60-316/60-316 BERRIEN COUNTY JANUARY 1 to DECEMBER 31, 1992 MEDIUM OR PATHWAY 1QTAL NUMBER CONIROL LOCATION NONROUTINE SAMPLED OF ANALYSES MEAN Ia/b) NAME MEAN MEAN REPORIED IUNIT OF MEASUREMEÃQ PERFORMED RANGE DISI'ANCE AND DIRECTION RANGE RANGE MEASUREMENIS Sediment Gamma 8 (pCI/kg dry)

K-40 8 5628(8/8) L-2 5965(2/2) No Control (4390-6470) 0.3mt S (5790-6140)

Ra-226 8 . 506(1/8) L-5 506(1/2) No Control 0.1 ml N

'Ih-228 8 130(7/8) I4 144(2/2) No Control (95.3-150) 0.1ml S (138-150)

MIIk Gamma 155 (pCI/liter)

K-40 155 1379(104/104 Warmbten 1407(26/26) 1347(51/51)

(1020-1870) 7.7ml S (1210-1850) (1110-1890) 1-131 155 -(0/104) N/A N/A -(0/51)

Cs-137 155 13.4(1/104) Freellng 13.4(1/21) 9.34(1/51)

(a/b) Rauo of samples wtth detectable activity to total number of samples analyzed.

RADIOLOGICALENVIRONME MONITORING PROGRAM 8UMMARY INDIANAMICHIGANPOWER COMPANY DONALD C. COOK NUCLEAR PLANT DOCKET NO. 60%16/6016 BERRIEN COUlfIY JANUARY I to DECEMBER 31, 1992 MEDIUMOR PATHWAY 1%7l'AL NUMBER CONIROL LOCATION NONROUHNE SAMPLED OF ANALYSES MEAN [a/b) NAME MEAN MEAN REPORIED IUNITOF MEASUREMENII PERFORMED RANGE DISPANCE AND DIRECTION RANGE RANGE MEASUREMENIS Pish Gamma (pCI/kg wet)

K-40 3113(8/8) ONS-North 3610(2/2) -(0/0)

(2340-4160) 0.3ml N (3060-4160)

Cs-137 48.0(1/8) OFS-North 48.0(l/2) -(0/0) 3.5ml N Pood/Vegetation (pCl/kg wet) 1976(6/8) Sector B 2360(1/2) -(0/0)

(58.2-4030) Variable K-40 2401(8/8) Sector J 2680(4/4 -(0/0)

(1630-3850) Variable (1820-3850)

Cs-137 28. 1(2/8) Sector A 28.1(2/2) -(0/0)

(19.9-36.2) Variable (19.9-36.2)

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

I

APPENDIX B DATATABLES 43

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMITIERS IN WEEKLY AIRBORNE PARIICULATES Results tn Units of 10-s PCI/m~ 2 2 sigma STATION CODES COLUM:TION A-2 A-3 A-4 A-5 A-B Coloma Dowaghc New Buff South Bend Average DATES k 2 s.d.

JANUAR 9 01/06/92 24+ 2 23 k 2 25%2 25% 2 27%2 25%2 24+2 27%2 25+ 2 25%2 25+ 3 01/13/92 24k 2 21 2 2 21%2 26% 2 24%2 23%2 -23+2 20%2 26k 2 19 k 2 23k 5 01/20/92 19+ 2 16 k 2 20%2 21% 2 18%2 20%2 19%2 18%2 19% 2 18 k 2 19% 3 01/27/92 27k 2 21%2 27%2 25+ 2 27%2 28%2 27%2 28%2 25k 2 25 k 2 26+ 4 02/03/92 20% 2 20k 2 2022 19k 2 2022 14%2 20%2 20%2 192 2 18% 2 19% 4

~~BU gf 02/10/92 20% 2 16%2 18%2 19k 2 17+2 18 k2 1912 20 22 )9k 2 192 2 19' 02/17/92 15% 2 I9+2 16%2 18% 2 16%2 19 k 2 20 k 2 18 k 2 18% 2 16 k 2 18% 3 02/24/92 16% 2 8.8% 1.5 15 k 2 16% 2 16%2 16 %2 18 k 2 16 2 2 17% 2 17+ 2 16' 03/02/92 13% 2 17%2 16+2 15+ 2 14%2 15a2 18a2 16%2 14+ 2 18 + 2 16% 3 gAI~C 03/09/92 20% 2 17%2 18+2 19% 2 19%2 18 k2 22 4 2 17a2 19% 2 20 2 2 19% 3 03/16/92 19% 2 19%2 18%2 19% 2 17%2 15%2 20 k 2 17 2 2 18% 2 19 2 2 18% 3 03/23/92 12% 1 16%2 17%2 15% 2 16%2 19 k 2 15+2 13 k 2 19% 2 17 k 2 16% 5 03/30/92 13% 2 14%2 15%2 15% 2 14+2 17 4 2 17+2 13 k 2 13% 2 14 + 2 15% 3 19% 9 18%7 19%7 '19% 8 19%9 19% 8 20% B 19% 9 19*8 19% B 19k 1

TABLE B-1 {c INDIANAMICHIGANPOlVER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMIITERS IN WEEKLY AlRBORNE PARTICULATES Results in Units of 10-3 pCI/ms k 2 sigma STATION CODES COLLECMON A-1 A-2 A-S A-4 A-6 A-6 Co)orna Dowaglac New Buff South Bend Average DATES k 2 s.d.

04/06/92 18 k2 18%2 19%2 20%2 15%2 18%2 21%2 16 k2 13% 2 19 2 2 18k 5 04/13/92 04/20/92 14 t2 13%2 16%2 14 k 2 15%2 14 + 2 15%2 11 k 2 14%2 11 k 2 16%2 14 k 2 16%2 12 k 2 14 10 k2 k2 16% 2 12% 2 17 k 2 13 k 2 15+ 2 12+ 3 04/27/92 7.1 k 1.4 10 k 2 7.5% 1.4 7.4k 1.4 6.4k 1.3 6.9C 1.4 6.6k 1.4 7.3+ 1.4 7.0 k 1.4 7.2 2 1.4 7k 2 05/04/92 16 k 2 16%2 17+2 69%09(a) 17%2 14%2 16%2 15 k 2 14% 2 18 k 2 15% 6 05/08/92 Ib) 21 k3 21% 3 05/15/92 lb) 24 k 4 24k 4 05/11/92 15 k2 16%2 15%2 18%2 16%2 14%2 15%2 15 + 2 14+ 2 16%3 15+ 2 05/18/92 16% 2 l7i2 18%2 19%2 15+2 15%2 14%2 15%2 13% 2 24 k 3 17% 6 05/25/92 13 k 2 1212 14%2 14%2 13 k 2 12%2 11%2 11 %2 12% 2 14 k 2 13% 2 06/01/92 14 k 2 15%2 15%2 1512 15a2 12%2 14%2 13%2 14% 2 18 + 2 15' 06/08/92 16%2 13%2 16%2 15+2 13%2 16%2 15%2 11%2 15% 2 15%2 15% 3 06/15/92 14i2 14+2 14+2 16+2 14%2 15%2 14%2 14%2 14% 2 14%2 14% 1 06/22/92 11 % 2 9.3k 1.6 11 +2 13% 2 3.2k 0.8(a) 10 % 2 11 k 2 9.2k 1.5 9.2i 1.5 9.8% 1.6 10 k 5 06/29/92 13%2 13%2 12%2 . 14%2 13%2 14%2 16%2 14%2 13% 2 -

15%2 14* 2 QiauterIyAvg. 14% 6 14% 6 14% 6 16% 7 1SA 8 14% 6 142 7 1Sa6 1316 16% 9 14% 2 (a) Equipment malfunctfon: results In total pCI and not Included ln averages.

(b) Extra samples collected due to heavy dust.

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMBERS IN WEEKLY AIRBORNE PARTICULATES Results ln Units of 10-3 pCI/m~ k 2 sigma STATION CODES COLQ~ ON A-1 A-2 A-3 A-6 Coloma Dowaglac New Buff South Bend Average DATES k 2 sod 07/06/92 16% 2 18%2 17%2 18% 2 15% 2 16% 2 14%2 18%2 15k 2 '19% 2 17% 3 07/13/92 12% 2 17%2 17+2 18% 2 16% 2 17% 2 18%2 18%2 16% 2 19% 2 17% 4 07/20/92 8.0% 1.3 8.6% 1.4 9.3k 1.4 9.7k 1.4 8.6% 1.4 9.0% 1.4 7.6k 1.3 7.2k 1.3 8.9R 1.3 8.3 k 1.3 9R 2 07/27/92 11% 2 9.1%1.5 9.8%1.6 Ilk 2 9.7k 1.6 13% 2 11%2 11%2 12%2 IOR 2 13+ 2 12% 2 11% 2 14+ 3 08/03/92 17% 2 13%2 14%2 15% 2 14% 2 13% 2 13%2 14% 2 bUG~S'g 08/10/92 18+ 2 17+2 16%'2 16+ 2 17% 2 16+ 2 16%2 16%2 16% 2 18+ 2 17% 2 08/17/92 14% 2 13+2 13%2 13+ 2 13+ 2 13% 2 12%2 11%2 10% 2 11% 2(a) 12% 3 08/24/92 20% 2 17%2 17%2 17% 2 17% 2 17% 2 15%2 16+2 18% 2 19+ 2 17% 3 08/31/92 12% 2 11 k 2 11 k 2 8.7% 2.2 9.7k 2.2 8.0% 2.1 8.3% 2.1 8.6%2.2 10 2 2 12% 2 10+ 3 SEPTEMBER 09/07/92 20% 2 20%2 20%2 21% 2 21% 2 20% 2 20%2 19 k 2 20% 2 20% 2 20% 1 09/14/92 16k 2 16%2 17%2 2.0% 0.5lb)16+ 2 16% 2 14%2 13 %2 16% 2 182 2 16+ 3 09/21/92 20% 2 21%2 22%2 (c) 22k 2 21+ 2 20+2 22 k 2 22k 2 20% 2 21% 2 09/28/92 14% 2 2.9%1.2 15%2 12% 2 12% 2 16% 2 14%2 14 k2 15+ 2 14% 2 13% 8 QuarttrlyAvg. 16% 8 14% 10 16% 8 14% 8 16% 8 16% 8 14%8 14%'9 16% 8 16% 8 16% 1 (a) Equipment malfunction; low sample volume.

(b) Loss of power to air stauon; results ln total pCl and not Included ln averages.

(c) Loss of power to air stauon; sample not available.

TABLE B-1 {Cant.l INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GROSS BETA EMITIERS IN WEEKLY AIRBORNE PAKI1CULATES Results tn Units of 10-3 pCI/m3 k 2 sigma STATION CODES COILECTION A-1 A-2 A-3 A-4 A-6 A-B Coloma Dowaglac New Buff South Bend Amnge DATES 2 2 S.d.

CXQQ~BI$

10/05/92 21% 2 20 k 2 20 k 2 19% 2 21% 2 21% 2 19 k2 20 k2 22k 2 19% 2 20% 2 10/12/92 18% 2 17 + 2 18 k 2 16% 2 17% 2 16% 2 17%2 14 k 2 16% 2 15% 2 16% 3 10/19/92 19% 2 16%2 15 k 2 I?% 2 15% 2 16% 2 15% 2 15 %2 20% 2 16% 2 16% 4 34 k 2 32 k 2 34k 3 30% 2 31% 2 27 k 2 31 k2 35% 2 25+ 2 31% 6 10/26/92 11/02/92 30%

15% 2 2

12 k 2 11 %2 12% 2 10% 2 12% 2 t 10 2 11%2 ll k 2 11+ 2 12% 3

~OL~B~E 11/09/92 8.3k 1.5 7.6% 1.5 8.4% 1.5 9.12 1.6 ?.3k 1.5 8.1% 1.5 7.4+ 1.4 25%2 8.5% 1.5 16%2

'.8,k 18%

1.4 2

8.5k 18% 2 1.5 8k 19k 5 1

11/16/92 18% 2 17+2 18%2 19% 2 20% 2 20% 2 11/23/92 17+ 2 15%2 18%2 16% 2 15% 2 16% 2 16+2 14+2 16% 2 17% 2 162 2 11/30/92 16% 2 16%2 15%2 15% 2 15% 2 16+ 2 16%2 16%2 17% 2 17% 2 16% 1 DECEMBER 12/0?/92 18% 2 17%2 18%2 18% 2 16% 2 20% 2 18+2" 18%2 18k 2 18% 2 18% 2 12/14/92 11% 2 11%2 11%2 9.8% 1.6 9.4k 1.6 13% 2 12+2 12+2 10+ 2 13% 2 11% 3 12/21/92 28% 2 30%2 32%2 28k 2 28k 2 31+ 2 28%2 31+2 32k 2 31% 2 30+ 4 12/28/92 33k 2 33%2 35%2 31% 2 29k 2 31% 2 29%2 31%2 29k 2 32k 2 31% 4 QmeterAvg. 19% 14 19% 17 19% 17 19% 16 18+ 18 19% 16 18% 14 18% 16 19% 17 191 14 19% 18 Annual Avg. 17% 11 16% 11 17% 11 17% 11 1BA 11 17% 11 17% 10 1BR ll 17% 12 17% 10 172 11

LE B-2 INDIANAMICHIQANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMfITERS'N QUARTERLY COMPOSITES OF AIRBORNE PARTICULATES Results ln Untts of 10-3 pCt/m3 k 2 stgma Stations Nuciides First Quarter Second Quarter Third Quarter Fourth Quarter Avenge 11/so/91~/80/9$ OS/so/9246/20/QQ Os/29/92OQ/28/sa 09/28/9012/2s/02 RQad.

A-1 Be-7 92.9  % 9.3 120 k 12 118 2 12 99.7 k 10.0 108 2 27 K-40 <4 <4 <4 <5 Cs-134 < 0.2 < 0.3 ( 0.2 < 0.3 Cs-137 < 0.2 < 0.3 ( 0.2 < 0.3 A-2 Be-7 91.0 k 9.1 125 % 13 101 2 10 96.2 j: 9.6 103 + 30 K-40 <6 < 7 3.16  % 1.75 <8 3.16 k 1.75 Cs-134 < 0.3 < 0.3 < 0.2 < 0.3 Cs-137 < 0.3 ( 0.2 < 0.2 < 0.3 A-3 Be-7 117 k 12 127 R 13 107 k 11 99.7 k 10.0 113+ 24 K-40 <5 < 10 < 3 5.22 2 2.70 5.22 a 2.70 Cs-134 < 0.3 < 0.3 ( 0.2 < 0.4 Cs-137 < 0.3 < 0.3 < 0.2 < 0.4 Be-7 90.4 k 9.0 153 + 15 95.8 + 9.6 101 k 10 110 2 58 K-40 2.95 A 1.70 <5 <4 <5 .2.95 A 1.70 Cs-134 < 0.2 < 0.3 ( 0.2 < 0.3 Cs-137 < 0.2 < 0.3 ( 0.2 < 0.2 A-5 Be-7 84.5 k 8.5 110 k 11 102 + 10 87.0 R 8.7 95.9 R 24 K-40 <8 9.21 k 2.89 < 7 10.7 k 3.4 10.0 + 2.1 Cs-134 << 0.3 < 0.3 < 0.3 < 0.4 Cs-137 < 0.3 < 0.3 < 0.3 < 0.3 Typical LLDs are found fn Table B-12. All other gamma emttters were <LLD.

TABLE B-2 tcont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITIERS'N QUARTERLY COMPOSIIES OF AIRBORNE PARI1CULATES Results in Units of 10-8 pCI/m~ k 2 sigma NucHdes Hrst ~r 12/80/91~/80/92 Second Quarter 08/80/9248/29/92 Third Quarter 08/29/9249/28/92 Fourth Quarter 09/28/92 12/28/92 Average i2 ad.

A-6 Be-7 92.1 % 9.2 147  % 15 120 k 12 110 k 11 117 R 46 K-40 6.59 R 2.01 <6 < 7 <6 6.59 R 2.01 Cs-134 < 0.3 ( 0.2 < 0.3 < 0.3 Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 Be-7 93.9 k 9.4 123 + 12 93.6 R 9.4 96.7 + 9.7 102 k 28 K-40 <4 <5 < 10 <4 Cs-134 < 0.3 < 0,3 < 0.3 < 0.3 Cs-137 < 0.3 < 0.2 < 0.3 ( 0.2 Dowagtac Be-7 K-40 93.4 k 9.3

< 20 177  % 18

< 10 110

<4 t 11 91.0 k 9.1

<6 118 k 81 Cs-134 < 0.5 < 0.4 ( 0.2 < 0.3 Cs-137 < 0.4 < 0.4 (0,2 < 0.3 New IhdI'alo Be-7 88.6 k 8.9 126 k 13 124 R 12 93.9 + 9.4 108 R 39 K-40 < 10 <4 <5 <5 Cs-134 < 0.3 ( 0.2 < 0.2 < 0.3 Cs-137 < 0.3 ( 0.2 < 0.3 < 0.4 South Bend Be-7 96.1 R 9.6 137 k 14 102 R 10 87.6 k 8.8 106 k 43 K-40 <4 <9 8.31 A 2.99 < 10 8.31 % 2.99 Cs-134 < 0.2 <<0.3 < 0.3 < 0.4 Cs-137 < 0.3 <<0.3 < 0.3 < 0.3

~Ical LLDs are found in Table B-12. All other gamma emitters were <LLD.

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results in Units of 10-3 PCI/m3 k 2 sigma STATION CODES COLLECTION A-1 h-2 A-4 A-5 A-6 Coloma Dowagfac New Buffalo 8outh Bend DATES 01/06/92 < 10 < 10 <<10 < 10 <6 < 10 < 10 < 10 <9 < 10 01/13/92 <<10 < 10 < 10 <<10 <8 < 10 < 10 < 10 <5 < 10 01/20/92 < 10 < 10 < 10 < 10 <9 < 10 < 10 < 10 <5 < 10 01/27/92 <<10 <<10 < 10 < 10 <5 < 10 < 10 < 10 <9 < 10 02/03/92 < 20 ( 20 < 20 ( 20 < 10 ( 20 < 20 < 20 < 10 < 20 02/10/92 < 10 < 10 < 10 < 10 <6 < 20 < 20 < 20 < 10 < 20 02/17/92 < 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 <9 <<10 02/24/92 < 10 < 10 < 10 < 10 <8 < 20 < 20 < 20 ( 10 < 20 03/02/92 <<10 < 10 < 10 < 10 <9 < 10 < 10 (10 (8 < 10

~R~g 03/09/92 < 20 < 10 < 10 < 10 <9 < 10 ( 10 < 10 <8 < 10 03/16/92 ( 20 ( 20 < 20 ( 20 < 7 < 10 < 10 <. 10 <9 < 10 03/23/92 <6 < 7 < 10 <5 < 7 < 10 < 10 < 10 < 7 < 10 03/30/92 < 20 ( 20 < 20 ( 20 < 10 < 10 < 10 < 10 <9 < 10

TABLE &8 tcont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results ln Units of 10-3 pCI/m3 k 2 sigma STATION CODES COLIECTION A-1 A-2 A-4 A-5 AW Coloma Dowagiac New BufXalo South Bend DATES 04/06/92 < 20 < 20 ( 20 ( 20 <9 < 20 < 20 ( 20 < 10 < 20 04/13/92 < 20 < 20 ( 20 < 20 <8 < 10 < 20 < 20 <<10 < 20 04/20/92 < 20 < 20 < 20 < 20 < 10 ( 20 < 20 < 20 < 10 ( 20 04/27/92 < 20 < 20 < 20 ( 20 <8 < 20 ( 20 < 20 < 10 ( 20 05/04/92 < 20 < 20 ( 20 <10 (a) <9 < 20 < 20 < 20 < 10 < 20 05/08/92 tb) < 10 05/14/92 tb) < 30 05/ll/92 ( 20 ( 20 <20 < 20 <9 ( 20 ( 20 < 20 < 10 < 50 05/18/92 < 20 ( 20 <20 <20 <9 ( 20 ( 20 ( 20 < 10 <40 05/25/92 < 20 < 20 < 20 (20 < 10 < 30 < 30 < 30 < 20 < 30 06/01/92 ( 20 ( 20 <20 (20 < 10 ( 20 ( 20 ( 20 <9 ( 20 06/08/92 ( 20 ( 20 ( 20 < 20 < 10 <<30 < 30 < 30 ( 20 < 30 06/15/92 ( 10 < 10 < 10 < 20 <6 < 10 ( 20 < 20 <7 ( 20 06/22/92 < 20

( 20

< 10 < 10 < 10 <4 (a) < 20 ( 20 ( 20 < 10 < 20 06/29/92 < 20 < 20 < 30 < 10 < 20 ( 20 < 20 < 10 ( 20 (a) Equipment malfunctton.

(b) Extra samples collected due to heavy dust.

B-3 (Cont.)

INDIANAMICHIGANPONER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF 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-5 A-6 Coloma Dowaglac New BuIMo South Bend DATES 07/06/92 < 20 < 20 < 20 ( 20 < 10 <9 < 10 < 10 <8 < 10 07/13/92 < 20 < 20 < 20 ( 20 < 10 < 10 < 10 < 10 <6 < '10 07/20/92 < 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 <9 < 10 07/27/92 ( 20 < 20 ( 20 < 20 <7 < 10 < 10 < 10 <8 < 10 08/03/92 < 20 < 20 ( 20 < 20 < 10 < 20 ( 20 ( 20 <8 < 20 AUGUST 08/10/92 ( 20 < 20 < 20 ( 20 < 7 < 10 < 10 < 10 <9 < 10 08/17/92 < 20 < 20 ( 20 < 20 < 10 < 10 < 10 < 10 < 10 < 10 (a) 08/24/92 < 10 < 10 < 10 < 10 < 7 < 10 < 10 ( 10 <<10 < 20 08/31/92 < 20 < 20 < 20 ( 20 <8 < 20 < 20 ( 20 < 10 < 20 SEPTEMBE 09/07/92 < 20 ( 20 ( 20 ( 20 <8 <9 <9 <9 <6 <9 09/14/92 < 20 < 20 ( 20 <<10 Ib) <9 < 20 ( 20 < 20 < 10 ( 20 09/21/92 <<10 < 10 < 10 (c) < 10 <6 < 10 < 10 < 10 < 10 09/28/92 < 20 < 10 < 20 < 10 < 7 ( 20 < 20 ( 20 < 7 < 20 (a) Equipment mal funct)on; low sample volume.

(b) Loss of power to air stat)on.

(c) Loss of power to atr stat)on; samaple not available.

TABLE B-3 [cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE-131 IN WEEKLY AIR CARTRIDGE SAMPLES Results In Units of 10-3 PCI/m3 k 2 sigma STA'11ON CODES COLLECTION h-I A-2 A-4 A-6 A-6 Coloma Dowaglac New Bulfalo South Bend DATES 10/05/92 < 20 < 20 ( 20 < 20 <<10 ( 20 < 20 ( 20 <8 < 20 10/12/92 ( 20 ( 20 < 20 ( 20 < 7 < 10 < 10 < 10 <8 < 10 10/19/92 < 20 < 20 ( 20 ( 20 <8 < 10 < 10 < 10 < 10 < 10 10/26/92 < 10 < 10 < 10 ( 20 <9 < 10 < 10 < 10 < 7 ( 10 11/02/92 < 20 < 20 < 20 < 20 < 7 < 10 < 10 < 10 <9 < 20 11/09/92 < 20 ( 20 < 20 ( 20 < 10 < 10 <<10 < 10 < 7 < 10 11/16/92 < 10 < 10 < 10 < 10 <<9, < 20 ( 20 ( 20 < 10 ( 20 vl 11/23/92 ( 10 < 10 < 10 < 10 <6 < 10 < 10 < 10 < 7 < 10 11/30/92 < 10 < 10 < 10 < 10 < 7 < 20 ( 20 < 20 < 7 < 20 12/07/92 < 20 < 20 ( 20 < 20 < 7 < 10 < 10 ( 10 <9 < 10 12/14/92 < 20 ( 20 ( 20 ( 20 < 7 < 10 < 10 < 10 <9 < 10 12/21/92 < 20 ( 20 ( 20 ( 20 < 10 < 30 < 30 < 30 ( 20 < 30 12/28/92 < 10 < 10 ( 10 < 10 <9 <9 <9 <9 < 6 <9

B-4 INDIANAMICHIGANPOWER CO - DONALD C. COOK NUCLEAR PLANT DIRECT RADIATION MEASUREMENTS - gUARTERLY TLD RESULTS Results!n Units of mR/standard month STATION FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER AVERAGE CODES 01/04/92-04/05/92 04/05/92~/05/92 07/05/92-10/04/92 10/04/92%1/OS/93 + 2 s.d.

A-1 3.8 R 0.7 3.6A 0.3 3.7 k 0.1 3.5 R 0.2 3.7 k 0.3 A-2 3.8 4 0.5 3.8R 0.6 3.7 k 0.2 3.6 2 0.2 3.7 2 0.2 A-3 3.2i 0.3 3.2R 0.6 3.2 t 0.1 3.1 R 0.2 3.2 E 0.1 A-4 3.8 % 0.3 4.0% 0.5 3.9 k 0.2 3.8 A 0.2 3.9 R 0.2 A-5 A-6 3.5 i 0.4 3.7 % 0.5 , 3.5 k 0.1 3.4 R 0.2 3.5 + 0.3 3.4 A 0.6 3.7% 0.2 3.5 k 0.1 3.3 R 0.2 3.5 a 0.3 A-7 3.8 R 0.4 3.8% 0.3 3.9 2 0.1 3.6 R 0.3 3.8 % 0.3 A-8 3.6 R 0.4 3.8% 0.7 3.7 i 0.2 3.6 2 0.3 3.7 % 0.2 A-9 4.2 A 0.8 4.1 k 0.5 4.0 k 0.2 3.8 A 0.3 4.0 k 0.3 A-10 3.2 i 0.4 3.5 % 0.6 3.2 k 0.1 3.2R 0.2 3.3 2 0.3 A-11 4.1 k 0.7 4.2 A 0.5 4.0 k 0.2 3.8 % 0.4 4.0 2 0.3 A-12 4.0

• 0.4 4.1 i 0.5 4.2 k 0.1 3.8 A 0.2 4.0 % 0.3 OFS-1 3.8 R 0.3 3.7 % 0.6 3o7 k 0.3 3.7 A 0.2 3.7 i 0.1 OFS-2 4.2% 0.3 4.1 + 0.8 4.0 k 0.2 3.8 R 0.1 4.0 2 0.3 OFS-3 4.0 k 0.4 4.2 % 0.4 4.0 i 0.3 3.8 2 0.4 4.0 k 0.3 OFSX 4.3a 0.3 4.3 k 0.9 4.3 + 0.3 4.3k 0.3 4.3 k 0.0 OFS-5 4.3k 0.3 4.2A 0.8 4.2 k 0.1 4.0 k 0.3 4.2 i 0.3 OFS-6 4.8 i 0.4 5.1 k 0.9 4.9 k 0.6 4.8R 0.5 4.9 k 0.3 OFS-7 3.8 % 0.3 3.8% 0.6 3.7 k 0.1 3.8R 0.1 3.8 A 0.1 OFS-8 4.9i 0.4 4.7% 0.6 4.7 k 0.3 4.6 2 0.3 4.7

• 0.3 OFS-9 4.2R 0.4 4.5k 1.0 4.3 k 0.3 4.2R 0.5 4.3 k 0.3 OFS-10 3.8 + 0.4 3.8A 0.7 3.8 k 0.2 3.9 k 0.1 3.8 R 0.1 OFS-11 4.6 k 0.5 4.7k 0.7 4.5 k 0.3 4.4 A 0.2 4.6 E 0.3 NBF 3.9 2 0.5 4.1 + 0.7 3.8 k O. 1 3.7

• 0.2 3.9 k 0.3 SBN 4.4 k 0.9 4.0 % 0.8 4.0 a 0.4 4.0 2 0.2 4.1 k 0.4 DOW 3.5 % 0.1 3.4 % 0.6 33 2 0.2 3.3 2 O.l 3.4 R 0.2 COL 3.4 2 0.3 3.5 k 0.3 3.3 k 0.3 3.3 2 0.2 3.4 2 0.2 Average 2 2 s.d. 8.9 2 0.9 4.0% 0.9 3.9+ 0.9 3.8 A 0.8 8.9% 0.9 Standard month ~ 30.4 days.

TABLE B-5 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITTERS'N SURFACE WATER Results ln Units of pCl/liter k 2 sigma STATION Collection Date I-131 K-40 L-1 01/09/92 < 0.3 < 100 < 100 (Condenser Circ.) 02/06/92 < 0.4 < 100 03/05/92 (a) < 0.3 < 80 04/02/92 < 0.4 < 50 < 100 04/30/92 < 0.2 < 50 05/28/92 <1 < 50 06/25/92 < 0.4 < 80 07/23/92 < 0.3 < 60 170 k 70 08/20/92 < 0.3 < 70 09/17/92 < 0.4 < 90 10/15/92 < 0.4 < 70 11/12/92 < 0.3 < 60 170 R 80 12/10/92 < 0.3 60.5 + 2.71 I 2 01/09/92 < 0.3 < 100 < 200 (South Comp) 02/06/92 < 0.3 < 200 03/05/92 < 0.3 < 100 04/02/92 < 0.4 < 100 < 100 04/30/92 < 0.2 < 50 05/28/92 <1 < 60 06/25/92 < 0.4 < 80 07/23/92 < 0.2 < 60 220 R 70 08/20/92 < 0.3 <?0 09/17/92 < 0.3 < 200 10/15/92 < 0.3 < 90 11/12/92 < 0.3 < 90 1100 k 100 12/10/92 .< 0.3 < 100 Typtcal LLDs are found ln Table B-12. All other gamma emltters were below <LLD.

(a) Cesium-137 was measured at 7.19 k 2.52 pCI/1 and confirmed by additional measurements.

LE B-5 (cont.l INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCElfIRAT1ONS OF lODINE, TRITIUM AND GAMMA EMITIERS'N SURFACE WATER Results ln Units of pCI/liter k 2 sigma STATION Collection Date K-40 01/09/92 < 0.3 < 100 190 R 80 (North Comp) 02/06/92 < 0.3 < 80 03/05/92 < 0.3 < 50 04/02/92 < 0.5 < 50 < 100 04/30/92 < 0.3 < 60 05/28/92 < 0.7 < 70 06/25/92 < 0.8 < 80 07/23/92 < 0.3 < 100 310 k 70 08/20/92 < 0.3 < 70 09/17/92 << 0.3 < 70 10/15/92 < 0.5 < 70 11/12/92 < 0.3 < 50 1400 k 100 12/10/93 < 0.3 < 50 01/09/92 < 0.3 < 90 190 k 90 (South 500) 02/06/92 < 0.3 < 100 03/05/92 < 0.3 < 80 04/02/92 < 0.4 < 50 < 100 04/30/92 < 0.3 < 50 05/28/92 <1 < 60 06/25/92 < 0.5 < 50 07/23/92 < 0.2 < 80 360 + 70 08/20/92 < 0.4 < 80 09/17/92 < 0.3 < 70 10/15/92 < 0.5 < 80 1200 k 100 11/12/92 < 0.4 < 80 12/10/92 < 0.3 < 100 Typtcal LLDs are found in Table B-12. All other gamma emltters were below <LLD.

TABLE B-5 {cant.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE, TRITIUM AND GAMMA EMITTERS'N SURFACE WATER Results in Units of pCl/liter k 2 sigma STATION Collection Date I-131 KRO L-5 01/09/92 < 0.4 68.0 k 29.6 < 100 (North 500) 02/06/92 < 0.4 < 60 03/05/92 < 0.3 < 100 04/02/92 < 0.4 55.9 2 25.2 < 100 04/30/92 < 0.3 < 90 05/28/92 <<I < 100 06/25/92 < 0.5 < 70 07/23/92 < 0.2 < 90 340 k 70 08/20/92 < 0.5 < 100 09/17/92 < 0.5 < 80 10/15/92 < 0.4 < 60 11/12/92 < 0.3 < 50 1000 k 100 12/10/92 < 0.3 < 60 Typtcal LLDs are found ln Table B-12. All other gamma emltters were below <LLD.

ABLE B-B INDIANAMICHIGANPOWER ANY- DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF 'IRITIUM AND GAMMA EMITIKRS'N QUARIERLY GROUNDWATER Results in Units of pCI/liter k 2 sigma STATION Collection Date I-131 K-40 Well - 1 02/09/92 < 0.1 < 100 < 200 04/28/92 < 0.2 < 60 < 100 07/31/92 < 0.2 < 50 < 100 10/31/92 < 0.2 < 50 < 100 Well -2 02/09/92 < 0.1 < 100 < 200 04/28/92 < 0.2 < 90 120 R 80 07/31/92 < 0.2 < 50 < 100 10/31/92 < 0.1 < 50 < 100 Well - S 02/09/92 < O.l < 50 < 200 04/28/92 < 0.2 < 100 < 100

. 07/31/92 < 0.2 < 90 < 200 10/31/92 < 0.1 < 60 < 100 Well - 4 02/09/92 < 0.1 < 200 1200 A 110 04/28/92 < 0.2 < 50 1100 k 100 07/31/92 < 0.2 < 50 1100 k 100 11/01/92 < 0.1 < 80 840 k 100 Well - 5 02/09/92 < 0.4 < 100 720 R 160 04/28/92 < 0.2 < 90 580 % 100 07/31/92 < O.l < 50 410 k 100 11/01/92 < 0.1 < 50 280 k 110 Well- B 02/09/92 < 0.1 < 60 300 k 100 04/28/92 < 0.2 < 70 540 k 100 07/31/92 < 0.1 < 50 540 k 100

< O.l < 40 450 k 90 11/01/92'2/09/92 Well - 7 < 0.1 < 100 1300 k 100 04/28/92 < 0.2 < 60 1500 k 100 07/31/92 < 0.3 < 50 1200 k 100 10/31/92 < 0.2 < 80 950 k 110 Typical LLDs are found in Table B-12. Ail other gamma emitters were <LLD.

TABLE B-6 {coot.l INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF TRITIUM AND GAMMA EMITIERS'N QUARIERLY GROUNDWATER Results in Units of pCI/liter k 2 sigma STATION Collection Date I-181 K-40 Well - 8 02/09/92 < 0.1 < 50 < 200 04/28/92 < 0.2 < 60 < 100 08/10/92 (a) < 0.1 <40 < 100 10/31/92 < 0.1 < 50 < 100 Well -9 02/18/92 < 0.3 <50 < 200 04/28/92 < 0.1 R 24.8

'7.0

< 100 07/31/92 < 0.2 < 50 < 100 10/31/92 < 0.1 < 60 < 100 Well - 10 02/11/92 < 0.4 < 90 < 200 04/28/92 < 0.2 < 60 < 100 07/30/92 < 0.2 < 60 140 + 80 10/31/92 < 0.1 161 k 25 140 R 80 Well - 11 02/11/92 < 0.4 < 100 < 200 04/28/92 < 0.2 < 50 < 100 07/30/92 < 0.1 < 90 < 100 10/31/92 < 0.2 < 70 < 100 Well - 12 02/11/92 < 0.5 < 90 < 200 04/28/92 < 0.2 < 100 120 k 80 07/30/92 < 0.2 < 50 < 100 10/31/92 < O,l 39.1 % 15.5 < 100 Well - 1S 02/11/92 < 0.4 < 100 950 k 140 04/28/92 < 0.2 < 100 650 k 110 07/31/92 < 0.2 < 50 490 k 100 10/31/92 < 0.2 59.1 + 20.6 260 R 90 Average 76.6% 114 662% 836

%2 S.d

'Pgpical LLDs are found ln Table B-12. All other gamma emltters werc <LLD.

Sample unavailable: substitute sample collected 08/10/92.

0 (a)

LE B-7 INDIANAMICHIGANPOWER ANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE. TRITIUM AND GAMMA EMIITERS'N DRINKING WATER Results In Units of pCI/ltter k 2 sigma COLLECTION DATE Iodine-1S1 Lake Township 01/09/92 3.0 k 1.0 < LLD < 0.3 < 100 01/23/92 2.6 x 1.0 < LLD < 0.3 02/06/92 4.3 s 1.1 < LLD < 0.3 02/20/92 4.1 k 1.0 < LLD < 0.4 03/05/92 6.2 k 1.2 < LLD < 0.3 03/19/92 3.3 k 1.0 < LLD ( 0.2 04/02/92 3.4 k 1.0 < LLD < 0.3 < 100 04/16/92 5.9 k 1.2 < LLD < 0.5 04/30/92 3.7 i 1.1 < LLD < 0.3 05/14/92 2.3 4 1.0 < LLD < 0.4 05/28/92 3.7 k 1.0 < LLD < 0.4 06/11/92 3.3 k 1.0 < LLD < 0.2 06/25/92 3.4 + 1.0 < LLD < 0.3 07/09/92 2.9 k 1.0 < LLD < 0.3 < 100 07/23/92 4.7 + 1.1 <<LLD < 0.5 08/06/92 3.5 k 1.0 < LLD < 0.3 08/20/92 2.9 k 0.9 < LLD < 0.1 09/03/92 3.5 k 1.0 < LLD < 0.4 09/17/92 3.6 i 1.0 < LLD < 0.4 10/01/92 4.2 k 1.1 < LLD < 0.3 160 k 80 10/15/92 3.5 k 0.9 < LLD << 0.4 10/29/92 2.4 + 0.9 < LLD < 0.3 11/12/92 2.8 k 0.9 < LLD < 0.3 11/26/92 3.8 k 0.9 < LLD < 0.5 12/10/92 1.9 k 1.2 < LLD ( 0.2 12/24/92 3.4 + 1.0 < LLD < 0.3 Average k S.B k 2.0 150 k 80 2s. d.

Typtcal LLDs are found In table B-12,

TABLE B-7 tcant.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GROSS BETA, IODINE, TRITIUM AND GAMMA EMITIERS'N DRINKING WATER Results in Units of pCI/liter k 2 sigma COILECTION DATE Gamma 8 c Iodine-191 St. Joseph Ol/09/92 3.1 a 1.1 < LLD < 0.3 ( 200 01/23/92 3.1 a 1.1 < LLD < 0.2 02/06/92 3.1 + 1.0 < LLD < 0.3 02/20/92 3.9 k 1.0 < LLD < 0.4 03/05/92 4.6 % 1.1 < LLD < 0.4 03/19/92 2.9 i 1.0 < LLD < 0.2 04/02/92 4.0 k 1.1 < LLD < 0.3 180 k 90 04/16/92 2.6 k 1.0 < ILD < 0.3 04/30/92 3.3 + 1.1 < LLD ( 0.2 05/14/92 4.2 % 1.2 < LLD < 0.2 05/28/92 4.7 a 1.1 < LLD < 0.4 06/11/92 3.2 i 1.0 < Il.D ( 0.2 06/25/92 3.9 1 1.0 < LLD ( 0.2 07/09/92 4.4 k 1.1 < LLD < 0.3 < 100 07/23/92 2.6 R 1.0 < LLD < 0.5 08/06/92 5.1 k 1.1 < LLD <<0.3 08/20/92 3.0 % 1.0 < LLD ( 0.2 09/03/92 5.1 k 1.1 < LLD < 0.5 09/17/92 3.7 k 1.0 < LLD < 0.3 10/01/92 4.7 k 1.1 < LLD < 0.4 < 100 10/15/92 3.9 k 1.0 < LLD < 0.4 10/29/92 2.6 % 1.0 < LLD < 0.3 11/12/92 3.4 k 0.9 < LLD < 0.3 11/26/92 3.4 k 0.9 < LLD < 0.4 12/10/92 3.3 k 1.3 < LLD < 0.2 12/24/92 3.2 R 1.0 < LLD < 0.2 Average 4 3.7% 1.8 2$ od Ical LLDs are found in table B-12.

INDIANhMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITIRRS~ IN SEDIMEÃ1'esults tn Untts of pCl/kg (dry) + 2 stgma Statton Collection Date Be-7 KKO Ca-137 Ra-226 Th-228 05/17/92 < 200 6140 k 610 <30 < 400 141 k 25 05/17/92 < 200 5170 R 520 < 20 < 300 133 k 19 05/17/92 < 200 4390 k 440 < 20 < 400 138 R 32 05/17/92 < 200 5800 k 580 < 20 < 400 < 40 11/19/92 < 200 5790 k 580 < 20 < 300 139 R 28 11/19/92 < 200 6470 k 650 < 30 << 400 116 k 21 I 4 11/19/92 < 200 6040 k 600 < 20 < 400 150 2 22 L-5 11/19/92 < 200 5220 k 520 < 30 506 R 297 95.3 k 21.7 hvaage 8628 % 1332 806 2 297 130 % 37

%2 S.d Typtcal LLDs are found in table B-12. All other gamma emltters were <LLD.

TABLE B-9 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCElfFRATIONS OF IODINE AND GAMMA EMITIERS'N MILK Results in Units of pCi/liter k 2 sigma STATION CODES COLLISION ANALYSIS SHULER TOTZEE FREEHLING (a) WARMBEIN ZELMER LIVINGHOUSE WYANT DATES 01/10/92 K-40 1140 k 110 1640 k 150 1290 k 130 1430 k 140 1180 k 120 (b)

I-131 < 0.2 < 0.2 < 0.1 < O.l < 0.2 01/26/92 K-40 1120 X 110 1490 a 150 1460 2 150 1280 k 130 1360 % 140 1350 k 140 I-131 < 0.2 < O.l < O.l < 0.2 < O.l < 0.2 02/07/92 K-40 1200 k 120 1370 2 140 1340 k 130 1240 R 120 1310 k 130 1280 k 130 1-131 < 0.1 < 0.1 < 0.2 < 0.1 < 0.1 < O.l u) 02/21/92 K-40 1-131 1020 i 100

< 0.2 1280 k 130

< 0.2 1440 k 140

< 0.1 1420 2 140

< 0.2 1200 k 120

< 0.4 1120 t 110

< 0.2 03/06/92 K-40 1-131 1220 1 120

< 0.2 1470 t 150

< 0.2 1400 k 140

< O.l 1390

• 140 1360 k 140 1200 k 120

< 0.2 < 0.1 < 0.2 03/20/92 K-40 1360 k 140 1340 k 130 1420 k 140 1210 120 (c) 1380 k 140 1330 2 130 (d:

I-131 < 0.2 < 0.2 < 0.1 < 0.2 < O.l < 0.2 (a) Added to the program 03/20/92 to replace Lozmack.

(b) Sample not available.

(c) Zelmer out of business 03/16/92.

(d) Cesium-137 was measured at 9.34 + 4.63 pCi/liter.

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

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA EMITIERS'N MILK Results in units of pCi/liter k 2 sigma STATION CODES COILECTION ANALYSIS 8 HULE R TOTZEE FREEHLING WARMBEIN ZELMER LIVINGHOUSE WYANT DATES 04/03/92 K-40 1170 k 120 1440 k 140 1230 k 120 1300 k 130 1420 k 140 1260 k 130 1-131 < 0.1 < 0.2 < 0.2 < 0.2 < 0.1 < 0.1 04/17/92 K-40 1-131 1870 j 190

< 0.1 1430 k 140

< 0.2 1330 k 130

< 0.2 1710 k 170

< 0.2 1370 k 140

< 0.2 1450 2 140

< 0.1 05/01/92 K-40 1510 k 150 1320 k 130 1470 k 150 1850 k 190 1770 k 180 1690 + 170 1-131 < 0.1 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 05/15/92 K-40 1290 % 130 1350 k 140 1280 k 130 1300 k 130 1320 % 130 1290 k 130 1-131 < 0.1 < 0.2 < 0.1 < 0.1 < 0.2 < 0.1 05/29/92 K-40 1700 k 170 1480 k 150 1320 k 130 1370 k 140 1310 k 130 1290 % 130 1-131 < O.l < 0.1 < 0.1 < 0.2 < O.l < 0.1 06/12/92 K-40 1340 k 130  ! 1510 k 150 1400 k 140 1400 2 140 1890 R 190 1460 2 150 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.1 < 0.2 06/26/92 K-40 1-131 1300 k 130

< 0.2 1440 k 140

< 0.2 1580 k 160

< 0.2 1360 k 140

< 0.1 1310 t

< 0.2 130 1420 k 140

< O.l Typical LLDs are found in table B-12. All other gamma emitters were <LLD.

TABLE B-9 (cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF IODINE AND GAMMA EMITIERS'N MILK Results in Units of pCi/liter k 2 sigma STATION CODES COLLMON ANALYSIS SHULER TOTZKE FREEHLING WARMBEIN ZELMER LIVING HOU8E WYANT DATES 07/10/92 K-40 1680 k 170 1510 k 150 1400 k 140 1330 k 130 1320 2 130 1310 k 130 1-131 < 0.3 < 0.2 < 0.2 < 0.2 < 0.3 < 0.2 07/24/92 K-40 I-131 1370 k 140

< 0.2 1430 k 140

< 0.2 1470 k 150

< 0.1 1340 t

< 0.2 130 1410 k 140 1460 k 150

< 0.2 < 0.2 08/07/92 K-40 1470 k 150 1230 k 120 1480 k 150 1470 k 150 1450 k 140 1310 k 130 1-131 < 0.2 < 0.1 < 0.1 < 0.2 < 0.2 < 0.3 08/21/92 K-40 1400 k 140 1450 k 150 1160 k 120 (a) 1380 % 140 1340 k 130 1260 k 130 1-131 < 0.1 < 0.09 < 0.1 < 0.1 < 0.1 < 0.1 09/04/92 K-40 1250 k 130 1160 k 120 1340 % 130 1450 k 140 1550 k 160 1290 k 130 1-131 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 09/18/92 K-40 1770 k 180 1460 k 150 1330 k 130 1460 k 150 1310 k 130 1110 2 110 1-131 < 0.1 < O.l < 0.1 < O.l < 0.1 < 0.1 Typical LLDs are found in table B-12. All other gamma emitters were <LLD.

B-9 {cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCElfHVLTIONS OF IODINE AND GAMMA EMITIERS'N MILK Results ln Units of pCl/liter k 2 sigma STATION CODES COLu&TION ANALYSIS SHULER TOTZKE FREEHLINQ WARMBEIN ZELMER LIVINQHOUSE WYANT DATES 10/02/92 K-40 1-131 1220 i

< 0.1 120 1480 k 150

< 0.3 1300 k 130

< 0.2 1210 k 120

< 0.2 1400 k 140

< 0.2 1180 k 120

< 0.2 10/16/92 K-40 1380 k 140 1490 2 150 1270 + 130 1440 k 140 1390 k 140 1290 k 130 I-131 < 0.7 < 0.2 < 0.3 < 0.2 < 0.2 < 0.4 10/30/92 K-40 1370 k 140 1260 k 130 1290 k 130 1330 2 130 1400 A 140 1290 4 130 1-131 < 0.2 < 0.5 < 0.2 < 0.2 < 0.4 < 0.2 11/13/92 K-40 1370 k 140 1220 k 120 1160 k 120 1360 A 140 1430 k 140 1160 k 120 I-131 < 0.4 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 11/27/92 K-40 1-131 1440 1 140

< 0.2 1390 k 140

< 0.2 1320 i 130

< 0.2 1510 k 150

< 0.2 1390 R 140

< 0,3 1270 R 130

< 0.3 12/11/92 K-40 1070 k 110 1360 k 140 1410 k 140 1490 k 150 1410 2 140 1280 % 130 1-131 < 0.1 < 0.2 < 0.2 < 0.2 < 0.1 < 0.2 12/26/92 K-40 1580 2 160 1460 R 150 1130 k 110 1380 k 140 1200 k 120 1180 R 120 1-131 < 0.1 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 Typical LLDs are found ln table B-12. All other gamma emltters were <LLD.

TABLEB-10 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITTERS'N FISH Results in Units of pCi/kg (wet) k 2 sigma Collection Date Station Descrl tion Be-7 K-40 Cs-187 Ra-226 Th-228 05/07/92 OFS-South Red Horse Sucker < 300 3000 A 460 < 30 < 600 < 50 05/07/92 OFS-North Red Horse Sucker < 200 2340 k 370 48.0 k 24.3 < 400 < 40 05/07/92 ONS-South Red Horse Sucker < 200 2970 k 370 < 30 < 500 < 40 05/07/92 ONS-North. Red Horse Sucker < 300 3060 R 390 <40 < 500 < 50 10/06/92 OFS-South Red Horse Sucker < 300 2930  % 340 < 30 < 400 < 40 10/06/92 OFS-North Red Horse Sucker < 300 3330 k 390 < 30 < 500 < 40 10/06/92 ONS South Red Horse Sucker < 200 3110 k 310 < 30 < 400 < 30 10/06/92 ONS-North Red Horse Sucker < 300 4160 R 430 <<40 ( 600 < 50 Average SllS k 1017- 48.0% 24.S

%2s,cL

~

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

T 11 INDIANAMICHIQANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT CONCENTRATIONS OF GAMMA EMITIERS'N FOOD/VEGETATION Results ln Units of pCl/kg (wet) k 2 sigma COLLECTION DATE Station Descri tion Be-7 K-40 I-181 Cs-1S7 08/09/92 SECTOR-A Broad Leaves 1460+ 150 1630 % 170 < 30 36.2+ 14.5 08/09/92 SECIQR-A Broad Leaves 1180 k 120 2730 R 270 < 20 19.9 + 10.5 09/27/92 SECTORS (close) Grape Leaves 2770 k 280 3220 % 320 < 40 < 20 09/27/92 SECTORS (20 M) Grape Leaves 4030 k 400 3850 k 390 < 40 < 20 09/27/92 SECTORS (close) Grape 58.2 k 26.2 1820 k 180 < 10 <5 09/27/92 SECTORS (20 M) < 30 1830 k 180 <8 <4 10/09/92 SECIQR-B Grape < 40 1660 k 170 <8 <4 10/09/92 SECTOR-B Grape Leaves 2360 k 240 2470 R 250 < 30 < 10 Average k 197BR 2788 2401 k 1BS7 28.1 k 2S.1 2 s.d.

Typical LLDs are found ln table B-12. All other gamma emltters were <LLD.

TABLE B-12 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT GAMMASPECIROMETRY LOWER LIMlTS OF DEIECTION AND REPORTING LEVELS Isoto Tech S ec LLD Re t Level TI LLD Tech S c LLD Re t Level e etatlo -we Water - l te 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-69 15 N/A N/A 15 30 400 Zinc-65 20 N/A N/A 10 30 300 Cobalt-60 10 N/A N/A 5 15 300 Cobalt-58 10 N/A N/A 5 15 1000 iodine-131 20 60 100 10 1 2 1 1 Iodine-131 (a) te Filter - Ci 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) 1 1 (a) Analysts by radiochemistry and based on the assumptions in Procedure PRO-032-11.

' l~p

TABLE {cont.)

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR HANT GAMMASPECTROMETRY LOWER LIMITS OF DETEC11ON AND REPOKIING LEVELS Isoto Tech 8 c LLD 'e t Level Tech 8 eo ILD Re t Level Cerium-144 200 N/A N/A 150 N/A N/A Barium/La-140 200 N/A N/A 5 N/A N/A Cesium-134 20 130 1000 30 150 N/A Ru,Rh-106 200 N/A N/A 200 N/A N/A Cesium-137 20 150 2000 30 180 N/A Zr,Nb-95 40 N/A N/A 40 N/A N/A Manganese-54 20 130 30000 9 N/A N/A Iron-59 40 260 10000 50 N/A N/A Zinc-65 40 260 20000 60 N/A N/A Cobalt-60 20 130 10000 20 N/A N/A Cobalt-58 20 130 30000 20 N/A N/A Iodine-131 100 N/A N/A 30 N/A N/A Qross Beta/Trttlum LLDs and Re Air Particulates Drinking Water

'.01 pCI/m3 2 pCI/l 0.01 pCI/m3 4.0 pCI/l N/A N/A Surface Water 200 2000 20,000 Ground Water 200 '000 20,000 Drinking Water 200 2000 20,000 (b) Based on the assumptions ln procedure PRO-042-5.

I

APPENDIX C ANALYTICALPROCEDURES SYNOPSIS 71

ANALYTICALPROCEDURE SYNOPSIS Appendix C is a synopsis of the analytical procedures performed during 1992 on samples collected for the D.C. Cook Plant's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by Indiana Michigan and Teledyne Isotopes and include those recommended by the USNRC Regulatory Guide 4.8,BTP, Rev. 1, November 1979.

AIMLYSISTITLE PAGE Gross Beta Analysis of Air Particulate Samples.......................... 73 Gross Beta Analysis of Water Samples ................................. 74 Analysis of Samples for Tritium (Gas) ................................. 76 Water eee ~ ~ ~ ~ oee ~ oe ~ ~ ~ e ~ e ~ ee e ~ eeeeee ~ eeee ~ eeee ~ ~ ee ~ ee ~ e ~ ee ~ o 76 Analysis of Samples for Tritium (Liquid Scintillation).................... 77 Analysis of Samples for Strontium-89 and -90.......................... 78 Total Water .................................................. 78 Milk o o o o o o o o ~ o o o o ~ o o o o o o o o ~ o o o o o o o o o o o o o ~ o ~ o o o ~ o o o o o o ~ o ~ ~ ~ o o 78 Soil and Sediment ............................................ 78 Orga nic Sottids o o ~ o o o ~ ~ o o ~ o o o o e ~ ~ o ~ ~ o ~ e ~ ~ o ~ ~ ~ ~ ~ o o ~ o ~ o ~ o ~ o o o ~ ~ ~ e 79 P~~4~culates...............................................

r p~ 79 Analysis of Samples for Iodine-131 ................................... 82 Milk or Water .. o o o o o o ~ o o o ~ o o o ~ o ~ ~ o e ~ o o o o o o o o o o o ~ o ~ o o o ~ 82 Gamma Spectrometry of Samples .................................... 83 Milk and Water............................................... 83 Dried Solids other than Soils and Sediment ...................... 83 Hsh e ~ o o o o o o o o o o o ~ ~ o o o o o o o o o o o o o o o o o o o ~ o o o ~ o o o ~ ~ ~ ~ ~ ~ e ~ ~ o ~ ~ o o o 83 Soils and Sediments .................,......................... 83 Charcoal Cartridges (Air Iodine) ................................ 83 Airborne Particulates... e e e e ~ e e e e e ~ o o o ~ e ~ e e o e ~ ~ e e e ~ e 84 Environmental Dosimetry.... o o e o o e ~ ~ ~ e o ~ ~ ~ ~ o ~ ~ ~ ~ o ~ ~ ~ o ~ o o o o o ~ o o ~ ~ ~ ~ ~ 86

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

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

RESULT (pCi/m3) ((S/T) - (B/t))/(2.22 V E)

'IWO SIGMA ERROR (pCi/m3) = 2((S/T2) + (B/t2))1/2/(2 22 V E)

LLD (pCi/m3) 4 66 (B/t/T) 1/2/(2.22 V E) where:

S Gross counts of sample including blank B Counts of blank E Counting efficiency T Number of minutes sample was counted Number of minutes blank was counted V Sample aliquot size (cubic meters) 73

DETERMINATI N F ROSS BETA ACTIVITYIN WATER LE I.D I~NTN D TI N The procedures described in this section are used to measure the overall radioactivity of water samples without identiiying the radioactive species present. No chemical separation techniques are involved.

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

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

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

74

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

The minimum detectable level (MDL) for water samples is nominally 1.6 picocuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/1 at 1

the 2.83 sigma level), assuming that 1.liter of sample is used and that >

gram of sample residue is mounted on the planchet. These 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.

75

ANALYSIS OF SAMPL FOR TRIT (Gas Counting)

Water 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)

I TWO SIGMA ERROR = 2((CG + B)ht) >/23.234 TN VN/((CN Vs) (CG-B))

4.66 (3.234)TN VN(CG) >/2/(ht 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 cpm activity of the standard of volume VN CG the gross activity in cpm of the sample of volume VS and the detector volume B the background of the detector in cpm h,t counting time for the sample

ANALYSIS OF SAMPLES FOR TRITIUM (Liquid Scintillation)

Water Ten miiiiiiters of water are mixed with 10 mi of a liquid scintillation "cocktail" and then the mixture is counted in an automatic liquid scintiQator.

Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/1:

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

TWO SIGMA ERROR = 2((N + B)/bt)>/2/ (2.22 V E) 4.66 (B/LIIt)1/2/(2 22 V E )

where: N the gross cpm of the sample B the background of the detector in cpm 2.22 conversion factor changing dpm to pCi V volume of the sample in ml E efficiency of the detector counting time for the sample 77

ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 W~~r Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO3)2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon 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.

Milk Stable strontium carrier is added to 1 liter of sample and the sample is first evaporated, then ashed in a muQle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolvedin 3M HN03. This solution is passed through a crown ether extraction column to isolate elemental strontium. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate.

The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating 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.

il d im n The sample is first dried under heat lamps and an aliquot is taken.

Stable strontium carrier is added and the sample is leached in hydrochloric acid. The mixture is filtered and strontium is precipitated from the liquid 78

portion as phosphate. Strontium is precipitated as Sr(N03)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 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.

Or ani Soli A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N03) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 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 SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

Air Particulat s Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth, Yttrium is then precipitated as hydroxide, 79

dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer stron-tium-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting.

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

RESULT Sr-89 (N/4t-BC-BA)/(2.22 V YS DFSR-89 ESR-89)

TWO SIGMA ERROR Sr-89 2((N/ht+BC+BA)/ht) / /(2.22 V YS DFSR8g ESR 8g LLD Sr-89 4 66((BC+BA)/ht) 1/2/(2.22 V YS DFSR-89 ESR-89)

RESULT Sr-90 (N/b,t - B)/(2.22 V Y1 Y2 DF IF E)

TWO SIGMA ERROR Sr-90 2((N/h,t+B)/ht) 1/2/(2.22 V Y1 Y2 DF E IF))

LLD Sr-90 4.66(B/bt) 1/2/(2 22 V Y1 Y2 IF DF E)

So

where: N total counts from sample (counts) counting time for sample (min) background rate of counter (cpm) using absorber conQgurati 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 90)

YS chemical yield of strontium DF SR-89 decay factor from the mid collection date to the counting date for SR-89 ESR-89 efficiency of the counter for SR-89 with the 80 mg/cm.sq.

aluminum absorber K (N/bt - BC)Y 90/(EY 90 IF> 90 DFY 90Y1)

DFY-90 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-90 ingrowth factor for Y-90 from scavenge time to milking tim<

IGY-90 the ingrowth factor for Y-90 into the strontium mount from "milk" time to the mid count time 0.016 the efficiency of measuring SR-90 through a No. 6 absorber 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 decay factor of yttrium from the radiochemical mQking time to the mid count time efficiency of the counter for Y-90 IF ingrowth factor for Y-90 from scavenge time to the radio-chemical milking time

ANALYSIS OF SAMPLES FOR IODINF 131 Milk or Water Two liters of sample are Qrst equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, reduced with hydroxylamine hydrochloride and extracted into toluene as free iodine. It is then back-extracted as iodide into sodium bisulQte 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/jR-B)/(2.22 E V Y DF)

VVO SIGMA ERROR 2((N/ht+B)/b,t) 1/2(2.22 E V Y DF)

= 4.66(B/5t) 1/2/(2.22 E V Y DF) where: N = total counts from sample (counts) b,t = counting time for sample (min)

B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor'from the collection to the counting date E = efficiency of the counter for I-131, corrected for self absorption effects by the formula E Es(exp-0.0085M) /(exp-0.0085Ms)

Es efficiency of the counter determined from an I-131 standard mount Ms = mass of Pdl2 on the standard mount, mg mass of Pdl2 on the sample mount, mg 82

GAMBIASPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is fQled 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.

ried li r Th Soils im nt 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.

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

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

Char al rid e Air Iodin 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 83

(assuming no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed fn the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector Air pm P ul The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.

A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume of pCi/mass:

84

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

'IWO SIGMA ERROR 2(S+B) / /(2.22 t E V F DF) 4.66(B) / /(2.22 t E V F DF) 0 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 eQiciency for energy of interest and geometry of sample sample aliquot size (liters, cubic meters, kilograms.

or grams) fractional gamma abundance (specific for each emitted gamma) decay factor from the mid-collection date to the counting date

ENVIRONMENTALD SIMETRY Teledyne Isotopes uses a CaS04.Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible thermaQy 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.

FoQowing 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 Geld use. The transit controls are read in the same manner.

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

R ESULT D = (Dl+D2+D3+D4)/4 TWO SIGMA ERROR 2((D > D)2+(D2 D)2+(D3-D)2+(D4"D)2)/3) 1/2 WHERE: D1 the net mR of area 1 of the TLD, and similarly for D2, D3, and D4 Dl I1 K/R1 -A

~ \

the instrument reading of the field dose in area 1 K the known exposure by the Cs-137 source RI the instrument reading due to the Cs-137 dose on area Q

1 average dose in mR, calculated in similar manner as above, of the transit control TLDs D the average net mR of all 4 areas of the TLD.

86

APPENDIX D SUMNARY OF EPA INTERLABORATORYCOMPARISONS 87

EPA INTERLABORATORYCOMPARISON PROGRAM Teledyne Isotopes participates in the EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of avaQability. In this section trending graphs (since 1981) and the 1992 data summary tables are presented for isotopes in the various sample media applicable to the Donald C. Cook Plant's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.

88

US EPA INTERLABORATORYCOMPARISON PROGRAM 1992 Environmental Collection Teledyne Date Media Nuclide EPA Result(a) Isoto es Result(b) 01/17/92 Water Sr-89 51.0 2 5.0 45.67 2 1.53 Sr-90 20.0 2 5.0 18.67 2 1.53 Ol/31/92 Water Gr-Alpha 30.0 2 8.0 25.00 2 4.00 Gr-Beta 30.0 2 5.0 31.67 2 0.58 02/07/92 Water I-131 59.0 2 6.0 61.00 2 1.73 02/14/92 Water Co-60 40.0 2 5.0 38.00 2 2.65 Zn-65 148.0 2 15.0 145.00 2 1.73 Ru-106 203.0 2 20.0 191.00 2 21.66 Cs-134 31.0 2 5.0 29.00 2 2.00 Cs-137 49.0 2 5.0 53.67 k 2.52 Ba-133 76.0 2 8.0 75.67 2 7.51 02/21/92 Water H-3 7904.0 2 790.0 7800.00 2 100.00 03/06/92 Water Ra-226 10.1 2 1.5 5.30+ 0.95 Ra-228 15.5 2 3.9 20.00 k 2.00 (c) 03/27/92 Air Filter Gr-Alpha 7.0 2 5.0 11.33 2 0.58 Gr-Beta 41.0 2 5.0 43.00 2 1.00 Sr-90 15.0 2 5.0 , 12.67% 0.58 Cs-137 10.0 2 5.0 11.00 2 1.73 04/14/92 Water Gr-Beta 140.0 2 21.0 98.00 2 2.00 (d)

Sr-89 15.0 2 5.0 16.00 2 1.00 Sr-90 17.0+ 5.0 14.33 2 1.15 Co-60 56.0 2 . 5.0 55.00 2 1.73 Cs-134 24.0 2 5.0 22.67 2 1.53 Cs-137 22.0 2 5.0 24.67 2 3.06 Gr-Alpha 40.0 2 10.0 34.33 2 2.08 Ra-226 14.9 2 2.2 13.33 2 2.08 Ra-228 14.0 2 3.5 15.33 2 0.58

US EPA INTERLABORATORYCOMPARISON PROGRAM 1992 Envh onmental Collection Teledyne Date Media Nuclide EPA Result(a) Isoto es Result(b) 04/24/92 Milk Sr-89 38.0 2 5.0 36.00 2 4.58 Sr-90 29.0 2 5.0 26.00 0.00 I-131 78.0 2 8.0 2

'1.67 4.04 Cs-137 39.0 k 5.0 46.67 2 2.31 (e)

K 1710.0 2 86.0 1680.00 2 72.11 05/08/92 Water Sr-89 29.0 k 5.0 24.00 2 1.73 Sr-90 8.0 2 5.0 6.33 2 0.58 05/15/92 Water Gr-Alpha 15.0 2 5.0 10.00 2 1.00 Gr-Beta 44.0 2 5.0 44.67 2 1.15 06/05/92 Water Co-60 20.0 2 5.0 21.33 2 0.58 Zn-65 99.0 2 10.0 107.00 2 3.61 Ru-106 141.0 2 14.0 127.00 2 11.53 Cs-134 15.0 2 5.0 15.00 2 1.00 Cs-137 15.0 2 5.0 16.00 2 1.00 Ba-133 98.0 2 10.0 93.33 2 6.03 06/19/92 Water H-3 2125.0 2 347.0 2100.00 2 0.00 07/17/92 Water Ra-226 24.9 k 3.7 23.33 2 1.15 Ra-228 16.7 2 4.2 17.33 2 0.58 08/07/92 Water I-131 45.0 2 6.0 43.33 + 6.03 08/28/92 Air Filter Gr-Alpha 30.0 2 8.0 27.33 2 0.58 Gr-Beta 69.0 2 10.0 69.00 2 1.00 Sr-90 25.0 2 5.0 22.67 2 1.15 Cs-137 18.0 2 5.0 16.67 k 2.31 Co-60 10.0 2 5.0 11.00 2 1.00 Zn-65 148.0 2 15.0 156.67 2 0.58 RQ-106 175.0 2 18.0 164.33 4 7.51 Cs-134 8.0 2 '5.0 8.67 2 0.58 Cs-137 8.0 2 5.0 8.67 2 0.58 Ba-133 74.0 2 7.0 75.67 2 9.29 90

US EPA, INTERLABORATORYCOMPARISON PROGRAM 1992 Environmental Collection Teledyne Date Media Nudide EPA Result(a) Isoto es Result(b) 09/18/92 Water Gr-Alpha 45.0 2 11.0 45.00+ 2.00 Gr-Beta 50.0 2 5.0 45.00 2 1.73 09/11/92 Water Sr-89 20.0 2 5.0 16.00 2 1.00 Sr-90 15.0 2 5.0 13.00 2 1.0 09/25/92 Milk Sr-89 15.0 2 5.0 16.00 2 2.00 Sr-90 15.00 2 5.0 12.67 2 1.15 I-131 100.0 2 10.0 99.00 2 7.21 Cs-137 15.0 2 5.0 15.67 2 1.15 K 1750.0 2 88.0 1660.00 2 85.44 10/23/92 Water H-3 5962.0 2 596.0 5666.67 2 57.74 Footnotes:

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

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

(c) All lab data sheets were veriAed for accuracy. Three different detectors were used with aliquot ingrowth times of 9 and 19 days. Results ranged from 4 to 6 pCi/l.

Dilution error has been determined to be the probable cause for the deviation from the spike value. Internal biweekly spike analyses have been in control. Corrective action includes implementation of a dilution form to record aliquot and solvent volumes. Entries will be made by the technician and reviewed by the supervisor.

(d) There was large fraction of low energy beta emitters (Co-60 and Cs-134) in the sample. Detector emciency decreases with decreasing energy. We are required to calibrate with the high energy beta emitters (Cs-137 and Sr-90). No corrective action necessary.

(e) There is no apparent reason for the high Cs-137 results. The sample geometry and detector efficiencies were veriQed to be correct. The Total K and 1-131 by gamma spectroscopy were in good agreement with EPA values. There is no trend and results were within 2 3 sigma so no action taken.

91

TREND1NG GRAPH 5 EPA CROSS CHECK PROGRAM GROSS BETA IN A)R PARTICULATES 160 140 120 O

1OO C!

0 80 60 40 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993

'8/25/89 EPA test invalid.

Tl k 3 Sigma 4 EPA k 3 Sigma

EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICULATES O

40 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl 2 3 Sigma 4 EPA 2 3 Sigma

EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES 160 140 120 100 C$

P 80 60 40 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993

'8/25/89 EPA test invalid.

Tl k 3 Sigma 4 EPA t 3 Sigma

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN AIR PARTICULATES 80 60 O

40 t5 0

I-20

-20 1981 1982 1983 1984 . 1985 1986 1987 1988 1989 1990 -

1991 1992 1993 Tl k 3 sigma o EPA+ 3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES 60 O

40 20 EPACT 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl 23sigma 4 3 sigma

EPA CROSS CHECK PROGRAM STRONTIUM-89 IN MILK 100 80

~w 60 O

0 40 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl k3 sigma 4 EPA k3 sigma

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK I

Im 40 0

CL 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl k 3 sigma 4 EPA k3 sigma

EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK 2600 2400 2200 I

Le 1800 0 1600 1400 1200 1000 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 o Tl g g sigma o EPA i3 sigma

EPA CROSS CHECK PROGRAM IODINE-131 IN MILK 140 120 100

~a e 80 Q

60 40 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl k 3 sigma 4 EPA k3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK 100 80 Lo O

60 O

CL 40 20 1981 1982 1983 1984 1986 1986 1987 1988 1989 1990 1991 1992 1993 TI13sigma 4 EPAR3sigma

EPA CROSS CHECK PROGRAM GROSS ALPHA IN NATER 140 120 100

~e 80 0 60 40 20

-20 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl k 3 Sigma 4 EPA k 3 Sigma

EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 220 200 180 160 140 O

120 O

100 80 60 40 20

-20 1986 1987 1988 1989 1990 1991 1992 1993 Tl AS sigma o EPA%3sigma

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

-20 1981 1982 1983 1984 1985 1986 Tl k 3 sigma 4 EPA k 3 sigma

EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 18000 16000 14000 12000 I

10000 0

CL 8000 6000 4000 2000 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl k 3 sigma o EPA k 3 sigma

EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 1 of 2) 5000 4000 3000 2000 CL 1000

-1000 1981 1982 1983 1984 1985 D Tl k3 sigma o EPA k3 sigma

EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg. 2 of 2) 100 80 60 40 20

-20 1988 1989 1990 1991 1992 1993 0 Tl k3 sigma o EPA k3 sigma

EPA CROSS CHECK PROGRAM COBALT-60 IN WATER (pg 1 of 2) 100 80 60 40 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 D Tl k3 sigma o EPA k3 sigma

EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 2 of 2) 100 80 60 40 20

-20 1988 1989 1990 1991 1992 1993 a Tl %3 sigma o EPA %3 sigma

EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg. 1 of 2) 100 80 60 I

iw 40 O

CL 20

-20 1981 1982 1983 1984 1985 1986 1987 1988 0 TI%3sigma o EPA k3 sIgma

EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 160 140 120 100 O

80 0

0 60 40 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 Tl %3sigma o EPAf3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 2 of 2) 120 100 80 60 40 20

-20 1988 1989 1990 1991 1992 1993 0 Tl k3 sigma EPA i3 sigma

EPA CROSS CHECK PROGRAM CESIUM-137 IN WATER (pg. 1 of 2) 80 60 40 20

-20 1981 1982 1983 1984 1985 1986 1987 a Tl k 3 sigma 4 EPA k3 sigma

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

V 40 20

-20 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 a f Tl 3 Sigma o EPA k 3 Sigma

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

40 0

CL 20

-20 1981 1982 1983 1984 1985 0 Tl k3 sigma EPA k3 sigma

EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER 80 60 40 O

0 20 20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 0 Ti + 3 sigma o EPA k3 sigma

APPENDIX E REMP BASH'LINGAND ANALYTICALEXCEPTIONS 117

PROGRAM EXCEPTIONS REMP deviations for 1992 are listed at the end of this appendix.

Where possible, the causes of the deviations have been corrected to prevent recurrence.

There were five incidents in 1992 involving air samplers. Three of the five incidents involved actual malfunction of air sampling equipment. This is a marked improvement over 1991 and is weQ below the industry average. The remaining two incidents resulted from a power surge during a thunderstorm which disabled the power supply to the air station.

On 1/10/92 a milk sample was not obtained Gom the Wyant Farm.

The wholesaler, who collects milk from dairy farmers, changed his route and arrived at the Wyant Farm earlier than usual. The REMP sample collector modified his collection route to prevent recurrence.

The Zelmer Farm notified the D.C. Cook Plant of their intention to go out of the dairy business. The Freehling Farm agreed to participate in the REMP Milk Sampling Program, thus replacing the Zelmer Farm.

The Lozmack Farm was discontinued to prevent redundant sampling in the same land sector.

During 1992 there were three occurrences involving the change in differential pressure (Delta 'P') measured across air sample filter media. Two of these occurrences involved "settling" of the charcoal inside the TEDA charcoal cartridges. This issue was resolved by utilizing more efficient TEDA cartridges, which are less prone to "settling".

An increase in the Delta 'P'as measured at the South Bend air station and was attributed to dust loading. The sampling frequency was increased to semi-weekly for two sample periods which resolved the issue. Each of the air samplers are equipped with a pressure compensated regulator which adjusts the differential pressure when flow is impeded.

118

REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANAI.YSIS DURING 1992 Date of Reason(s) for Loss/

Station Descri tion Sam lin Exce tion A-2 Air Particulate/ 02/24/92/ Low Delta 'P'eadings due Air Iodine 03/02/92 to "settling" of charcoal media.

South Bend Air Particulate/ 03/09/92 High Delta 'P'eadings due Air Iodine to "settling" of charcoal media.

A-4 Air Particulate/ 05/04/92 Blown fuse; low sample Air Iodine volume.

South Bend Air Particulate/ 05/08/92/ Collection &equency semi-Air Iodine 05/14/92 weekly due to dust loading.

A-5 Air Particulate/ 06/22/92 Unit found off.

Air Iodine South Bend Air Particulate/ 08/17/92 Blown fuse; low sample Air Iodine volume.

A-4 Air Particulate/ 09/14/92 Electricity off; low sample Air Iodine volume.

A-4 Air Particulate/ 09/21/92 Power outage; no sample Air Iodine available.

I Lozmack Milk 01/01/92 Sampling at Lozmack Farm discontinued. Freehling Farm closer to Plant.

Wyant Milk 01/10/92 Sample unavailable.

Zelmer Milk 03/20/92 Sample unavailable due to farmer going out of dairy business. Replaced by Freehling Farm.

119

APPENDIX F 1992 LAND USE CENSUS 120

AE'PENDIX F

SUMMARY

OF THE 1992 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 1992 Land Use Census. The following is a summary of the 1992 results.

MilkFarm Surve The milk farm survey is performed to update the list of milk farms located in the plant area, to identify the closest milk farm in each land sector, and to identify the nearest milk animal whose milk is used for human consumption. The mQk farm survey for the Cook Power Plant was conducted on September 24, 1992.

In 1992 there were no additions and five deletions from the list of area milk farms. None of the deleted milk farms were involved in the Cook Plant milk sampling program.

The previously identified milk animal continues to be the closest milk animal to the plant. The milk animal is located 2.5 miles from the plant's centerline axis to the closest edge of the animal's pasture.

Residential Surv The residential survey is performed to identify the closest residence to the plant in each land sector. The 1992 Annual Residential Land Use Survey was completed on September 28, 1992. This survey was conducted per procedure 12 THP 6010 ENV.059, using an updated list of new residential building permits from Lake Township and previous survey maps.

The residence closest to the Plant in each land sector remains unchanged from the previous reporting year.

121

Broadleaf Surv In accordance with Technical SpeciQcation (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 1992 were less than the Technical SpeciQcation LLDs.

122

Figure 8 INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLF~ P Milk and Animal Survey - 1992 Sxmrey Distance Sector Year Miles Name Address N/A No milk animals N/A N/A No mQk animals N/A N/A No mQk animals N/A N/A No milk animals N/A N/A No milk animals N/A N/A No mQk animals N/A D 5.1 Gerald Totzke 6744 Totzke Rd., Baroda 5.1 Gerald Totzke 6744 Totzke Rd., Baroda 10.5 Andrews University Berrien Springs 10.5 Andrews University Berrien Springs 6.8 Lee Nelson RFD 1, Box 390A, Snow Rd, Baroda 6.8 Lee Nelson RFD 1, Box 390A, Snow Rd.

Baroda G 4.1 G. G. Shuler & Sons RFD 1, Snow Rd., Baroda 4.1 G. G. Shuler & Sons RFD 1, Snow Rd., Baroda 7.0 George Freehling 2221 W. Glendora Rd., Buchanan 7.0 George Freehling 2221 W. Glendora Rd., Buchanan 7.7 Jerry Warmbein 14143 Mll Rd., Three Oaks 7.7 Jerry Warmbeln 14143 Mll Rd., Three Oaks 12 Kenneth Tappan Rt. 2, Kruger Rd, Three Oaks 12 Kenneth Tappan Rt. 2, Kruger Rd, Three Oaks All other sectors are over water.

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

123

INDIANAMICHIGANPOWER COMPANY - DONALD C. COOK NUCLEAR PLANT Resident)a) Land Use Survey - 1992 Sector House (t) In Feet Street Address 2161 11-11-0006-0004-01-7 lier Drive, Rosemiy Beach 2161 11-11-0006-0004-01-7 lier Drive, Rosemiy Beach 2165 11-11-0006-0004-09-2 lier Drive, Rosemary Beach 2165 1 1-1 1-0006-0004-09-2 lier Drive, Rosemary Beach 3093 1 1-1 1-6800-0028-00-0 Lake Road. Rosemaxy Beach 3093 1 1-1 1-6800-0028-00-0 Lake Road, Rosematy Beach D 6733 11-11-0005-0036-01-8 7500 Thorton Drive 5?33 11-11-0005-0036-01-8 7500 Thorton Drive 5631 11-11-0005-0009-07-0 7927 Red Arrow Highway 5631 11-11-0005-0009-07-0 7927 Red Arrow Highway 5392 11-11-0008-0015-03-1 8197 Red Arrow Highway 5392 1 1-1 1-0008-001 6-03-1 8197 Red Arrow Highway 3728 11-11-0007-0013-01-4 Livingston Road 3728 11-11-0007-0013-01-4 Livingston Road H 4944 1 1-1 1-8600-0004-00-1 Wildwood 4944 11-11-8600-0004-00-1 Wildwood 3366 11-11-0007-0010-02-3 Livingston Hills 3366 11-11-0007-0010-02-3 Livingston Hills 10 3090 11-11-0007-0010-03-1 Livingston Hills 10 3090 11-11-0007-0010-03-1 Livingston Hills (I) House s indicated Is the reference number used on map when obtatnlng the raw Acid data.

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

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APPENDIK G SU5HdARY OF THE PRE-OPERATIONAL RADIOLOGICALMONITORING PROGRAM 127

SUMMARY

OF THE PREOPERATIONAL RADIOLOGICAL, MONITORING PROGRAM I

A preoperational radiological environmental monitoring program was performed for the Donald C. Cook Nuclear Plant from August 1971 until the initial criticality of Unit 1 on Januaxy 18, 1975. The analyses of samples collected in the vicinity of the nuclear power plant were performed by Eberline Instrument Corporation. The summaxy of the preoperational program presented in this appendix is based on the seven semi-annual reports covering the period. The purpose of this suxxxmaxy 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 1992.

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 wiO yield estimates of the dose to man. if any, which will result 5om plant operation."

The discussion that follows is for the various sample media collected and analyzed in both the preoperational period and during

1992. Analyses performed during the preoperational but not required in 1992, are not discussed.

The gross beta activity in air particulate Qlters ranged from 0.01 to 0.17 pCi/m3 from the middle of 1971 to the middle of 1973. In June of 1973 and in June of 1974 the People's Republic of China detonated atmospheric nuclear tests. As a result there were periods during which the gross beta results were elevated to as high as 0.45 pCi/m3 with no statistically significant differences between indicator and background stations. By the end of the preoperational period the values were approximately 0.06 pCi/m3.

The gamma ray analyses of composited air particulate fQters showed "trace amounts" of Qssion products, Ce-144, Ru-106, Ru-103, Zr-95, and Nb-95, the results of fallout from previous atmospheric nuclear tests.

Cosmogenically produced beryllium-7 was also detected.

The direct radiation background as measured by thermoluminescent dosimeters (TLD) ranged between 1.0 and 2.0 mRem/week during the three and one-half years period.

Milk samples during the preoperational period were analyzed 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 &om 8 to 33 pCi/liter.

Iodine-131 was measured in four milk samples collected July 9, 1974.

The values ranged between 0.2 and 0.9 pCi/liter.

Lake water samples were collected and analyzed for tritium and by gamma ray spectroscopy. Tritium activities were below 1000 pCi/liter and typically averaged about 400 pCi/liter. No radionuclides were detected by gamma ray spectroscopy.

129

Gamma ray spectroscopy analyses of lake sediment detected natural abundances of potassium-40, uranium and thorium daughters, and traces of cesium-137 below 0.1 pCi/g which is attributed to fallout.

Gamma spectroscopy analyses of fish detected natural abundances of potassium-40 and traces of cesium-137, the latter attributed to fallout.

Drinking water analysis was not part of the preoperational program.

130

APPENDIX H

SUMMARY

OF THE REMP QUALITYCONTROL PROGRAM 131

SUIHlHARYOF THE REMP QUALXXYCONTROL PROGRAM The plant procedure for implementing the quality control program references Regulatory Guide 4.15. The program utilizes blank, replicate and spiked samples within four diferent parameters; gamma isotopic, tritium, iodine and gross beta. The blank and replicate samples are prepared at the D.C. Cook Plant and the spiked samples are prepared by Teledyne Isotopes.

Twenty five quality control analyses were performed during 1992. Over ninety percent (23) of the samples analyzed gave acceptable results, however two samples did not meet the acceptance criteria of 2 two standard deviations from the known value.

The third quarter tritium sample did not meet the acceptance criteria.

Teledyne conducted an investigation which included reviewing lab procedures.

technician protocol and verificatio of instrument control charts. A new sample was prepared and gave acceptable results.

The fourth quarter gross beta sample did not meet the acceptance criteria. Teledyne Isotopes conducted an acceptable investigation to determine the root cause. The analyses was repeated with acceptable results.

132

APPENDIX I SUMEGQtY OF THE SPIKE AND BLANKSAMPLE PROGRAM 133

SUMMARY

OF THE SPIKE AND BLANKSdQMPLE PROGRAM The following tables list the blanks and spiked water samples analyzed during 1992 for the Teledyne Isotopes In-house Quality Assurance Program.

Analysis date is analogous to collection date to identify weekly analysis of samples.

Three analyses for gross beta activity were reported outside the specified acceptable ranges. No documented corrective action was taken because in accordance with Section 9.1 of our Quality Control Manual (IWL-0032-365), the acceptance criteria for a particular analysis "is within 3 standard deviations of the EPA one sigma. one determination as specified in the Environmental Radioactive Laboratory Studies Program EPA-600/4-81-004, Table 3, Page 8".

For gross beta activity below 100 pCi/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. Control charts for gross alpha and beta spikes did not indicate any bias in results.

For the tritium spikes by gas analysis the three standard deviations of the EPA one sigma, one determination would be greater than 1000 pCi/1 for a spike level of 1500 pCi/1. The quality assurance department operationally investigates tritium spike results which exceed k 200 pCi/1. Control charts indicated a low bias in tritium spike results with only five out of thirty-seven measurements outside the 15% operational acceptance criteria. In August 1992 the gas counters were removed from service (not as a consequence of the quality control sample results) and was not returned to service. Samples were counted ori the liquid scintillation counter which exhibited excellent performance without any obvious bias in quality control sample results throughout 1992.

Teledyne Isotopes In-House Spiked Sample Results - 1992 Water Ana~s S ike Levels Acce table Ran Ci Gross Alpha 112 5 6- 16 Gross Beta 22k 5 17-27 Gamma (Eu-154) 1.4 2 0.2 E 05 1.2 - 1.6 E 05 H-3 (G) 1.42 0.3 E 03 1.1 - 1.7 E 03 H-3 (LS) 1.42 0.3 E 04 1.1 - 1.7 E 04 GROSS ALHEA An i D Ac vi i 1 62037 01/02/92 1.3 2 0.2 E Ol 62372 01/08/92 1.1 2 0.2 E 01 63240 01/15/92 8.8 2 1.6 E 00 64223 01/22/92 1.5+ 0.3 E Ol 64802 01/29/92 9.5 2 1.8 E 00 65404 02/05/92 9.0 2 1.9 E 00 66201 02/12/92 1.0 2 0.2 E Ol 66965 02/19/92 1.1 2 0.2 E 01 67704 02/26/92 9.4k 1.7 E 00 68187 03/04/92 1.3 2 0.2 E Ol 68967 03/11/92 1.1 2 0.2 E Ol 69941 03/18/92 1.4 2 0.2 E 01 70399 03/25/92 1.6 2 0.2 E 01 71154 04/01/92 9.5 2 1.6 E 00 71804 04/08/92 8.9 2 1.5 E 00 72815 04/15/92 8.6 2 1.7 E 00 74501 04/22/92 9.8 2 1.6 E 00 75113 04/29/92 1.2 2 0.2 E Ol 76137 05/06/92 1.2 2 0.2 E 01 75706 05/13/92 1.2 2 0.2 E Ol 76686 05/20/92 1.4 2 0.2 E Ol 77458 05/27/92 1.62 0.2 E Ol 78081 06/03/92 1.4 2 0.2 E 01 79224 06/10/92 1.3 2 0.2 E 01 79918 '6/17/92 1.4 2 0.2 E 01 80653 06/24/92 8.3 2 1.6 E 00 81487 07/01/92 1.2 2 0.2 E 01 82604 07/08/92 1.2 2 0.2 E 01 83361 07/15/92 1.1 2 0.2 E Ol 84237 07/22/92 1.3 2 0.2 E Ol 84256 07/29/92 1.2 2 0.2 E Ol 85164 08/05/92 1.0+ 0.2 E 01 135

Teledyne hotopes in-House Spiked Sample Results - 1992 Water Analyds ice Level e table Ran Gross Alpha 112 5 6- 16 Gross Beta 22k 5 17-27 Gamma (Eu-154) 1.4 2 0.2 E 05 1.2 - 1.6 E 05 H-3 (G) 1.5 2 0.3 E 03 1.3 - 1.7 E 03 H-3 (LS) 1.5 2 0.3 E 04 1.3 - 1.7 E 04 GROSS ALPHA An is D e Activi i 1 62037 01/02/92 1.3 2 0.2 E 01 62372 01/08/92 1.1 2 0.2 E 01 63240 01/15/92 8.8 2 1.6 E 00 64223 01/22/92 1.5 2 0.3 E Ol 64802 01/29/92 9.5 2 1.8 E 00 65404 02/05/92 9.0 2 1.9 E 00 66201 02/12/92 1.0 2 0.2 E Ol 66965 02/19/92 1.1 2 0.2 E 01 67704 02/26/92 9.4k 1.7 E 00 68187 03/04/92 1.3 2 0.2 E 01 68967 03/11/92 1.1 2 0.2 E Ol 69941 03/18/92 1.4 2 0.2 E Ol 70399 03/25/92 1.6 2 0.2 E Ol 71154 04/01/92 9.5 2 1.6 E 00 71804 04/08/92 8.9 2 1.5 E 00 72815 04/15/92 8.6 2 1.7 E 00 74501 04/22/92 9.8 2 1.6 E 00 75113 04/29/92 1.2 2 0.2 E 01 76137 05/06/92 1.2 2 0.2 E 01 75706 05/13/92 1.2 4 0.2 E 01 76686 05/20/92 1.4 2 0.2 E,01 77458 05/27/92 1.62 0.2 E 01 78081 06/03/92 1.4 2 0.2 E Ol 79224 06/10/92 1.3 2 0.2 E 01 79918 06/17/92 1.4 2 0.2 E 01 80653 06/24/92 8.3 2 1.6 E 00 81487 07/01/92 1.2 2 0.2 E 01 82604 07/08/92 1.2 2 0.2 E Ol 83361 07/15/92 1.1 2 0.2 E 01 84237 07/22/92 1.3 2 0.2 E 01 84256 07/29/92 1.2 2 0.2 E Ol 85164 08/05/92 1.0 2 0.2 E Ol

GROSS ALPHA (Cont.)

TI ¹ Acti 86554 08/12/92 1.2 2 0.2 E 01 87756 08/19/92 1.2 2 0.2 E Ol 87896 08/26/92 1.8 2 0.3 E 01 88926 09/02/92 1.3 2 0.2 E 01 88943 09/09/92 1.3 2 0.2 E Ol 90049 09/16/92 1.3 2 0.2 E 01 90712 09/23/92 1.1 2 0.2 E 01 91019 09/30/92 8.7 2 1.4 E 00 91750 10/07/92 1.2 2 0.2 E Ol 93281 10/14/92 1.42 0.2 E Ol 93449 10/21/92 1.0 2 0.2 E Ol 93958 10/28/92 6.1 2 1.4 E 00 94594 11/04/92 1.4 2 0.2 E 01 95282 11/11/92 1.3 2 0.2 E 01 96008 11/18/92 1.0 2 0.2 E Ol 96803 11/25/92 9.1 2 1.5 E 00 97309 12/02/92 1.4 2 0.2 E Ol 98048 12/09/92 1.2 2 0.2 E Ol 99065 12/16/92 1.1 2 0.2 E 01 00109 12/23/92 1.1 2 0.2 E Ol 00123 12/30/92 1.3 2 0.2 E Ol GROSS BETA TI ¹ is Date 62036 01/02/92 1.9 2 0.1 E 01 62371 01/08/92 1.8+ 0.1 E Ol 63239 01/15/92 2.1 2 0.2 E 01 64222 01/22/92 2.6 2 0.2 E Ol 64801 01/29/92 1.6 2 O.l E 01 65403 02/05/92 1.5 2 O.l E 01 66200 02/12/92 2.7 2 0.2 E 01 66964 02/19/92 1.7 2 0.1 E 01 67704 02/26/92 2.1 2 0.2 E Ol 68187 03/04/92 1.8 k 0.2 E 01 68967 03/11/92 2.0 2 O.l E 01 69941 03/18/92 2.1 2 0.2 E Ol 70399 03/25/92 2.5 k 0.2 E Ol 71154 04/01/92 1.9 2 O.l E Ol 71804 04/08/92 2.0 2 O.l E 01 72815 04/15/92 2.3 2 0.2 E Ol 74501 04/22/92 2.3 2 0.2 E Ol 75113 04/29/92 2.4 2 0.2 E Ol 76137 05/06/92 2.1 2 O.l E Ol 137

GROSS BETA (Cont.)

TI ¹ Activi 75706 05/13/92 2.6 + 0.2 E 01 76686 05/20/92 1.9 2 0.1 E Ol 77458 05/27/92 2.3 2 0.2 E Ol 78081 06/03/92 2.5 k 0.2 E Ol 79224 06/10/92 1.9 2 O.l E Ol 79918 06/17/92 1.8 2 0.1 E Ol 80653 06/24/92 2.3 2 0.2 E 01 81487 07/01/92 1.2 2 O.l E Ol 82604 07/08/92 2.0 2 0.2 E Ol 83361 07/15/92 2.3+ 0.2 E Ol 84237 07/22/92 2.3 2 0.2 E 01 84256 07/29/92 2.1 2 0.2 E 01 85164 08/05/92 1.9 2 O.l E 01 86554 08/12/92 2.3 2 0.2 E Ol 87756 08/19/92 2.3 2 0.2 E 01 87896 08/26/92 2.5 2 0.2 E Ol 88926 09/02/92 2.3 2 0.2 E Ol 88943 09/09/92 2.3 2 0.2 E Ol 90049 09/16/92 2.5 2 0.2 E 01 90712 09/23/92 2.3 2 0.2 E Ol 91019 09/30/92 2.0 2 0.1 E Ol 91750 10/07/92 2.2 2 0.2 E 01 93281 10/14/92 2.4 2 0.2 E Ol 93449 10/21/92 2.5 2 0.2 E Ol 93958 10/28/92 2.0 k 0.2 E Ol 94594 ll/04/92 2.3 2 0.2 E 01 95282 11/11/92 2.2 2 0.2 E 01 96008 11/18/92 2.9 2 0.2 E 01 96803 11/25/92 2.0 2 O.l E 01 97309 12/02/92 2.02 0.1 E Ol 98048 12/09/92 1.7+ O.l E 01 99065 12/16/92 2.3 2 0.2 E Ol 00109 12/23/92 2.2 2 0.2 E 01 00123 12/30/92 2.3 2 0.2 E 01 GAMIN%A (Eu-154)

TI ¹ ~A~

62042 Ol/02/92 1.41 2 0.14 E 05 62377 01/08/92 1.36 2 0.14 E 05 63245 01/15/92 1.43 2 0.14 E 05 64228 01/22/92 1.38 2 0.14 E 05 64807 01/29/92 1.44 k 0.14 E 05 65409 02/05/92 1.46 2 0.15 E 05 66206 02/12/92 1.45 2 0.15 E 05

GAMMA (Eu-154)

TI ¹ i~ii o i Activi 66970 02/19/92 1.36 2 0.14 E 05 67709 02/26/92 1.43 2 0.14 E 05 68192 03/04/92 1.40 2 0.14 E 05 68972 03/11/92 1.40 2 0.14 E 05 69946 03/18/92 1.43 k 0.14 E 05 70404 03/25/92 1.48 2 0.14 E 05 71159 04/01/92 1.41 + 0.14 E 05 71809 04/08/92 1.40 2 0.14 E 05 72820 04/15/92 1.42 2 0.14 E 05 74506 04/22/92 1.42 2 0.14 E 05 75118 04/29/92 1.46 2 0.15 E 05 76142 05/06/92 1.41 2 0.14 E 05 75711 05/13/92 1.46 2 0.15 E 05 76691 05/20/92 1.39 2 0.14 E 05 77463 05/27/92 1.43 2 0.14 E 05 78086 06/03/92 1.46 2 0.15 E 05 79229 06/10/92 1.42 2 0.14 E 05 79923 06/17/92 1.46 2 0.15 E 05 80658 06/24/92 1.50 2 0.15 E 05 81492 07/01/92 1.46 k 0.15 E 05 82609 07/08/92 1.44 2 0.40 E 05 83366 07/15/92 1.48 2 0.15 E 05 84242 07/22/92 1.47 k 0.15 E 05 84531 07/29/92 1.48 2 0.15 E 05 85169 08/05/92 1.45 2 0.15 E 05 86559 08/12/92 1.36 2 0.14 E 05 87761 08/19/92 1.49 2 0.15 E 05 87901 08/26/92 1.47 2 0.15 E 05 88931 09/02/92 1.40 2 0.14 E 05 88948 09/09/92 1.46 2 0.15 E 05 90054 09/16/92 1.45 2 0.15 E 05 90717 09/23/92 1.49 k 0.15 E 05 91024 09/30/92 1.28 2 0.13 E 05 91755 10/07/92 1.45 2 0.15 E 05 93286 10/14/92 1.48 2 0.15 E 05 93454 10/21/92 1.39 2 0.14 E 05 93961 10/28/92 1.48 2 0.15 E 05 94597 ll/04/92 1.49 2 0.15 E 05 95285 11/11/92 1.48 2 0.15 E 05 96806 11/25/92 1.48 2 0.15 E 05 97312 12/02/92 1.43 + 0.14 E 05 98052 12/09/92 1.51 2 0.15 E 05 00112 12/23/92 1.50 2 0.15 E 05 00126 12/30/92 1.45 + 0.15 E 05 139

TRITIUM% - (H-3)

TI 0 A~i 62039 01/02/92 1.4 2 0.1 E 03 62374 01/08/92 1.4 k 0.1 E 03 63242 01/15/92 1.3 2 0.1 E 03 64225 01/22/92 1.2 2 0.1 E 03 64804 01/29/92 1.3 2 0.1 E 03 65406 02/05/92 1.5 2 0.1 E 03 66203 02/12/92 1.4 2 0.1 E 03 66967 02/19/92 1.3 2 0.1 E 03 67706 02/26/92 1.4 2 O.l E 03 68189 03/04/92 1.4 2 0.1 E 03 68969 03/11/92 1.4 2 0.1 E 03 69943 03/18/92 1.4 2 0.2 E 03 70401 03/25/92 1.4 2 0.1 E 03 71156 04/01/92 1.4 2 0.1 E 03 71806 04/08/92 1.3 2 0.1 E 03 72817 04/15/92 1.3 2 0.1 E 03 74503 04/22/92 1.5 2 0.1 E 03 75115 04/29/92 1.2 2 0.1 E 03 75708 05/13/92 1.3 2 0.2 E 03 76139 05/06/92 1.3 k 0.1 E 03 76688 05/20/92 1.4 2 0.1 E 03 77460 05/27/92 1.4 2 0.1 E 03 78083 06/03/92 1.2 2 0.1 E 03 06/10/92 79226 79920 80655 06/17/92 06/24/92 1.3 1.2 1.3 i

2 0.3 0.1 2 O.l E 03 E 03 E 03 81489 07/01/92 1.4 2 0.1 E 03 82606 07/08/92 1.3 2 0.1 E 03 83363 07/15/92 1.4 2 0.1 E 03 84239 07/22/92 1.2 2 0.3 E 03 84528 07/29/92 1.3 2 0.2 E 03 85166 08/05/92 1.3 2 0.1 E 04 (a) 86556 08/12/92 1.4 2 O.l E 04 87758 08/19/92 1.4 2 0.1 E 04 87898 08/26/92 1.5 2 0.1 E 04 88927 09/02/92 1.5 2 0.1 E 04 88944 09/09/92 1.3 2 0.1 E 04 90050 09/16/92 1.5 2 0.1 E 04 90713 09/23/92 1.6 2 0.1 E 04 91020 09/30/92 1.4 2 0.1 E 04 91751 10/07/92 1.3 2 0.1 E 04 93282 10/14/92 1.4 2 0.1 E 04 93450 10/21/92 1.6 2 0.1 E 04 93959 10/28/92 1.4 2 0.1 E 04 (a) The me asu rem ent of a weekly spiked tritium sample was disconUnue d afte r July 29, 1992.

In its pla cew as substituted the liquid scintillaUon meth od. The spik ed a cUvity fs ten times greater in the liquid scintillation sam ples.

>40

TRITHHN - (H-S)

TI 8 Activi 94595 11/04/92 1.4 2 0.1 E 04 95283 11/11/92 1.6 2 0.1 E 04 96009 11/18/92 1.4 2 0.1 E 04 96804 11/25/92 1.4 2 0.1 E 04 97310 12/02/92 1.4 2 0.1 E 04 98049 12/09/92 1.4 2 0.1 E 04 99066 12/16/92 1.4 2 0.1 E 04 00110 12/23/92 1.3 2 0.1 E 04 00124 12/30/92 1.5 2 0.1 E 04 141

Teledyne Isotopes In-House Blanhs Sample Results - 1992 Water TI ¹ A~ED t 62035 01/02/92 L. T. 9 E-01 62370 01/08/92 L. T. 5. E-01 63238 01/15/92 L. T. l. E 00 64221 01/22/92 L. T. 1. E 00 64800 01/29/92 L. T. 9. E-01 65402 02/05/92 L. T. 9 E-01 66199 02/12/92 L. T. 2. E 00 66963 02/19/92 L. T. 4 E-01 67703 02/26/92 L. T. 6. E-01 68186 03/04/92 L. T. 9 E-01 68966 03/11/92 L. T. 7. E-01 69940 03/18/92 L. T. 9 E-01 70398 03/25/92 L. T. 8. E-01 71153 04/01/92 L. T. 6. E-01 71803 04/08/92 L. T. 7. E-01 72814 04/15/92 L. T. 3. E-01 74500 04/22/92 L. T. 6. E-01 75112 04/29/92 L. T. 7. E-01 76136 05/06/92 L. T. 7. E-01 75705 05/13/92 L. T. 7. E-01 76685 05/20/92 L. T. 9 E-01 77457 05/27/92 L. T. 6. E-Ol 78080 06/03/92 L. T. 6. E-01 79223 06/10/92 L. T. 7. E-01 79917 06/17/92 L. T. 9 E-01 80652 06/24/92 L. T. 7. E-01 81486 07/01/92 L. T. 9. E-01 82603 07/08/92 L, T."8. E-01 83360 07/15/92 L. T. 8. E-01 84236 07/22/92 L. T. 7. E-01 84525 07/29/92 L. T. 8. E-01 85163 08/05/92 L. T. 8. E-01 86553 08/12/92 L. T. 6. E-01 87755 08/19/92 L, T. 6. E-01 87895 08/26/92 L. T. 6. E-01 88925 09/02/92 L. T. 5. E-01 88942 09/09/92 L. T. 7. E-OI 90048 09/16/92 L. T. l. E 00 90711 09/23/92 L. T. 7. E-01 91018 09/30/92 L. T. 7. E-01 91749 10/07/92 L. T. 6. E-01 93280 10/14/92 L. T. 5. E-01 93448 10/21/92 L, T. 8. E-01

GROSS AIZEQL (Cont.)

TI ¹ An is Date Activi 93957 10/28/92 L. T. 4. E-01 94593 11/04/92 L. T. 8. E-01 95281 11/11/92 L. T. 4. E-01 96007 ll/18/92 L. T. 5. E-01 96802 11/25/92 L. T. 6. E-01 97308 12/02/92 L. T. 7. E-01 98047 12/09/92 L. T. 5. E-01 99064 12/16/92 L. T. 6. E-01 00108 12/23/92 L. T. 7. E-01 00122 12/30/92 L. T. 8. E-01 GROSS BETA TI ¹ Activi 62035 01/02/92 L. T. 7. E-01 62370 01/08/92 L, T. 8, E-01 63238 01/15/92 L. T. 1.'E 00 64221 01/22/92 L. T. 1. EOO 64800 01/29/92 L. T. 1. E 00 65402 02/05/92 L. T. 9. E-01 66199 02/12/92 L. T. l. E 00 66963 02/19/92 L. T. 7. E-01 67703 02/26/92 L. T. 8. E-01 68186 03/04/92 L. T. l. E-00 68966 03/11/92 L. T. l. E-00 69940 03/18/92 L. T. 9. E-01 70398 03/25/92 L. T. 8. E-01 71153 04/01/92 L. T. 8. E-01 71803 04/08/92 L. T. 7. E-01 72814 04/15/92 L. T. 8. E-01 74500 04/22/92 L. T. 8. E-01 75112 04/29/92 L. T. 8. E-01 76136 05/06/92 L. T. 7. E-01 75705 05/13/92 L. T. 9. E-01 76685 05/20/92 L. T. 8. E-01 77457 05/27/92 L. T. 9 E-01 78080 06/03/92 L. T. 8. E-01 79223 06/10/92 L. T. 8. E-01 79917 06/17/92 L. T. 8. E-01 80652 06/24/92 L. T. 9. E-01 81486 07/01/92 L. T. 8. E-01 82603 07/08/92 L. T. 9. E-01 83360 07/15/92 L. T. 8. E-01 84236 07/22/92 L. T. 9 E-01 84525 07/29/92 L. T. 8. E-01 85163 08/05/92 L. T. 8. E-01 86553 08/12/92 L. T. 8. E-01 87755 08/19/92 L. T. 7. E-01

GROSS BETA (Cont.)

TI 4 An s Date Activi 87895 08/26/92 L. T. 8. E-01 88925 09/02/92 L. T. 9 E-01 88942 09/09/92 L. T. 8. E-01 90048 09/16/92 L. T. 9 E-01 90711 09/23/92 L. T. 8. E-01 91018 09/30/92 L. T. 9 E-01 91749 10/07/92 L. T. 8. E-01 93280 10/14/92 L. T. 8. E-01 93448 10/21/92 L. T. 8. E-01 93957 10/28/92 L. T. l. E 00 94593 11/04/92 L. T. 8. E-01 95281 11/11/92 L, T. 7. E-01 96007 11/18/92 L. T. 8. E-01 96802 11/25/92 L. T. 7. E-01 97308 12/02/92 L. T. 8. E-01 98047 12/09/92 L. T. 7. E-01 99064 12/16/92 L. T. l. E 00 00108 12/23/92 L. T. 7. E-01 00122 12/30/92 L, T. 8. E-01 TarTruM - (8-3)

TI 4 Activi Ci 62041 01/02/92 L. T. 1. E 02 62376 01/08/92 L. T. l. E 02 63244 01/15/92 L. T. 8. E 01 64277 01/22/92 L. T. 7. E 01 64806 01/29/92 L. T. l. E 02 65408 02/05/92 L. T. l. E 02 66205 02/12/92 L. T. 2. E02 66969 02/19/92 L. T. .2. E 02 67708 02/26/92 L. T. 1. E 02

.68191 03/04/92 L. T. l. E 02 68971 03/11/92 L. T. l. E 02 69945 03/18/92 L. T. 2. E 02 70403 03/25/92 L. T. 1. E 02 71158 04/01/92 L. T. 1. E 02 71808 04/08/92 L. T. 2. E 02 72819 04/15/92 L. T. l. E 02 74505 04/22/92 L. T. l. E 02 75117 04/29/92 L. T. l. E 02 76141 05/06/92 L. T. l. E 02 75710 05/13/92 L. T. 2. E 02 76690 05/20/92 L. T. 2. E 02 77462 05/27/92 L. T. 2. E 02 78085 06/03/92 L. T. 9 E 02 (a) 79227 06/10/92 L. T. 9. E 02 (a)

(a) Tritium by 11qutd sctnUllation.

i44

TRITIUM - (H-S) (Cont,)

TI ¹ An s Dat 79922 06/17/92 L. T. E 02 80657 06/24/92 L. T. l. E 02 81491 07/01/92 L. T. 3. E 02 82608 07/08/92 L. T. 8. E 01 83365 07/15/92 L. T. 2. E 02 84241 07/22/92 L. T. 2. E 02 84530 07/29/92 L. T. 2. E02 85168 08/05/92 L. T. 2. E02 86558 08/12/92 L, T. 1. E02 87760 08/19/92 L. T. 2. E 02 87900 08/26/92 L. T. l. E 02 88929 09/02/92 L. T. l. E 03 g))

88947 09/09/92 L. T. 9. E 02 90053 09/16/92 L. T. 1. E 03 90716 09/23/92 L. T. l. E 03 91023 09/30/92 L. T. l. E 03 91754 10/07/92 L. T. l. E03 93285 10/14/92 L. T. 2. E 03 93435 10/21/92 L. T. 1. E 03 93960 10/28/93 L. T. 2. E 03 94596 11/04/92 L. T. 2. E 03 95284 11/11/92 L. T. 1. E 03 96010 11/18/92 L. T. 1. E 03 96805 11/25/92 L. T. l. E 03 97311 12/02/92 L. T. 1. E 03 98050 12/09/92 L. T. E 03 99067 12/16/92 L. T. l. E 03 00111 12/23/92 L. T. l. E 03 00125 12/30/92 L. T. l. E 03 A

(b) The gas counting method for tritium analysis was discontinued as of September 1, 1992. It was replaced by a liquid scintillation method which has the equivalent measurement sensitivity. However, the weekly blank measurements continued with the lower measurement sensitivity until the end of the year. In 1993 the tritium blank analysis will be performed by the more sensitive liquid scintillation method.

145

APPENDIX J TLD QUALITYCONTROL PROGRAM i46

TLD QUALITYCONTROL PROGRAM Teledyne Isotopes performs an in-house quality assurance testing program for the environmental TLD laboratory. On a quarterly basis the QA manager or a qualiQed designate exposes groups of TLDs to three different doses using a known cesium-137 exposure rate. The performance of the second quarter test in the early part of the third quarter had no impact on TLD results reported throughout the year.

Due to an increased workload, the QA manager performed the second quarter exposures on July 14, 1992. Subsequent third and fourth quarter exposures were performed in September and November to ensure four tests would be performed for 1992.

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 1992 all results were within the requirements of Regulatory Guide 4.13, Section 'C. The standard deviations were less than 7.5% and the variations from the known were less than 30%. The accompanying graphs show the normalized deviations of the measured doses to the exposure doses for each of the three readers.

TREND I APH 6 QUALITYCONTROL,- TLDS TLD READER 205 0.5 I

li

~

I I

I /

I I I I

/

-0,5 X/

01/89 04/89 07/89 10/89 01/90 04/90 07/90 10/90 01/91 04/91 07/91 10/91 1/92 7/92 9/92 11/92 Low Dose 9- Middle Dose H High Dose

QUALITYCONTROL - TLDS TLD READER 21$

1,5 0.5 /

0

/

/

/

/

/

-0.5 i/

01/89 04/89 07/89 10/89 8-01/90 04/90 Low Oose Middle Oose 07/90 10/90 H

01/91 04/91 High Dose 07/91

~

10/91 1/92 7/92 Reader-211 9/92 11/92

QUALlTY TROL - TLDs TLD READER 242 0.8 0.6 CO O

CL 0.4 0.2 c

E O

aO /

W.4 /

/

/

/ I I / I

%.8

%/

01/89 04/89 07/89 10/89 01/90 04/90 07/90 10/90 01/91 04/91 07/91 10/91 1/92 7/92 9/92 11/92 Low Dose 8- Middle Dose ~ High Dose

QUALlTYCONTROL - TLDs TLD READER 9150 0.5

-1.5 10/90 01/91 04/91 07/91 10/91 1/92 7/92 9/92 11/92 Low Dose 8- Middle'ose H High Dose