Text

Semiannual Report of Operations, Number 9, for Period of January 1 Through June 30, 1975
	ML18353B475
Person / Time
Site:	Palisades
Issue date:	08/29/1975
From:	; Consumers Power Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML18353B475 (128)
	v • d • e

CONSUMERS POWER r.OMPANY PALISADES PLANT SEMIANNUAL REPORT OF OPERATIONS NUMBER 9 January 1 Through June 30, 1975 CJ3f3

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SEMIANNUAL OPERATING REPORT No 9 January 1, 1975 Through June 30, 1975 I.

INTRODUCTION II.

OPERATIONS

SUMMARY

III.

IV.

v.

A.

CHANGES IN FACILITY DESIGN B.

PERFORMANCE CHARACTERISTICS

1.

Equipment

2.

Fuel C.

CHANGES IN PROCEDURES D.

IN-SERVICE SURVEILLANCE TESTS AND INSPECTIONS E.

CONTAINMENT LEAK RATE TESTS F.

CHANGES, TESTS AND EXPERIMENTS REQUIRING NRC AUTHORIZATION G.

ORGANIZATION CHANGES POWER GENERATION SHUTDOWNS A.

OUTAGE 75-1 B.

OUTAGE 75-2

c.

OUTAGE 75-3 D.

OUTAGE 75-4 MAINTENANCE A.

COMPONENT COOLING SYSTEM

1.

Component Cooling Heat Exchanger E-54A

2.

Component Cooling Heat Exchanger E-54B

1.

Component Cooling Heat Exchanger E-54A i

B.

CONTAINMENT BUILDING AND CRANE

1.

Personnel Air Lock Doors

2.

Emergency Air Lock Doors C.

CONTROL ROD DRIVES (CRDM)

1.

CRDM #44 Secondary Position Indicator

2.

CRDM #12, #28 and #39 Seal Housings

3.

CRDM #36 Clutch

4.

Twenty-Three CRDM Seal Housings

5.

CRDM #30 Seal Housing

6.

CRDM #48 Seal Housing

7.

CRDM #30 D.

CHEMICAL AND VOLUME CONTROL SYSTEM

1.

Relief Valve RV-2203

2.

Charging Pump Discharge Check Valve

3.

Charging Line Elbow

4.

Charging Pump Suction Valves

5.

Relief Valve RV-2013

6.

Charging Line Hangers

7.

Makeup Water Control Valv.e CV-2165

8.

Charging Pump P-55B

9.

Piping Hangers

10.

Control Valve CV-2155

11.

Charging Pump P-55A

12.

Purification Filter F-54B

13.

Charging Pump P-55B

14.

Charging Pump P-55A ii

E.

DATALOGGER

1.

Secondary Datalogger

2.

Primary Datalogger

3.

CRDM Secondary Position Indication

4.

Sequence Error Buzzer F.

EMERGENCY POWER SYSTEM

1.

Lube Oil Pump

2.

Diesel Generator Cooling

i. Number 1 Inverter l~.

Solo Transformer

5.

Lube Oil Pressure Alarm

6.

Lube Oil Pump

(.

Prelube Oil Relief Valve

8.

Exhaust Temperature Indicator

9.

Lube Oil Pump

10.

Diesel Generator Governor

11.

Synchronizing Switch

12.

Pyrometer G.

ENGINEERED SAFEGUARDS SYSTEM

1.

Relief Valve RV-3165

2.

Pressure Indicating Alarms PIA-0363 and PIA-0371

3.

Safety Injection Control Valve CV-3042

4.

Shutdown Sequencer

5.

Minimum Flow Check Valve H.

FEEDWATER SYSTEM

1.

Auxiliary Feed-Water Pump Turbine iii

I.

MAIN STE.AM SYSTEM

1.

Pressure Control Valve PCV-0521.A

2.

Piping Hangers

3.

Piping Hangers J.

NEUTRON MONITORING SYSTEM

1.

Reactor Protective Calibration and Indication Amplifier

2.

Power Range Nuclear Indicator K.

PRIMARY COOLANT SYSTEM

1.

Pressurizer Sample Control Valves CV-1902 and CV-1903

2.

S~eam Generator E-50A

3.

Pressurizer Level Indicator LIA-0102A

4.

Pressure Switch PS-0103 L.

RADIATION MONITORING SYSTEM

1.

Process Monitor

2.

Process Monitor RE-1810 3.. Radiation Monitors RIA-1805 M.

REACTOR PROTECTIVE SYSTEM

1.

Steam Generator Level Alarm LA-0751C

2.

RPS Channel D

3.

Pressure Indicator PIA-0102A N.

RADWASTE SYSTEM

1.

Solenoid Valves O.

SERVICE WATER SYSTEM

1.

Service Water Pump P-7A

2.

Control Valves CV-0838, CV-0843 and CV-0872

3.

Service Water Pump P-7B iv

P.

WASTE GAS SYSTEM:

1.

Relief Valve RV-1111

2.

Oxygen Analyzer

3.

Compressor C-54 VI.

CHANGES, TESTS AND EXPERIMENTS A.

FACILITY CHANGES

1.

FC-199, Boric Acid Safety Valve Flanges

2.

FC-200, Engineered Safeguards Relief Valves

3.

FC-204, Containment Ventilation

4.

FC-217, In-Core Neutron Detectors

5.

FC-219, Safety Injection Relief Valves

6.

FC-227, Radwaste Evaporator Conductivity Cell

7.

FC-242, 125VDC Alarm Relazs B.

TESTS AND EXPERIMENTS

1.

T-60, Flux Oscillation Data Ac~uisition

2.

T-61, Core 11P Flow

3.

T-69 2 Low Flow TriJ2 Calibration

4.

T-74, Test of CV-0734 and CV-0735

5.

T-75, Hydrostatic Pressure Test

6.

T-77, CRDM Position Indication 2 Limit Switch Operation VII.

REFUELING INFORMATION VIII.

RADIOACTIVE EFFLUENT RELEASES A.

LIQUID RADIOACTIVE EFFLUENTS

1.

Liquid Release Summary

2.

Liquid Effluent Calculational Methods v

B.

GASEOUS RADIOACTIVE RELEASES

1. Gaseous Effluent Releases

2.

Effluent Calculational Methods C.

SOLID WASTES IX.

ENVIRONMENTAL MONITORING A.

RADIOLOGICAL ENVIRONMENTAL MONITORING

1. Introduction

2.

Discussion and Interpretation of Results

3.

Conclusions B.

NONRADIOLOGICAL ENVIRONMENTAL MONITORING

1. Introduction

a. Effluent Release

b.

Environmental Monitoring Program Appendix A - Monthly Operating Reports Appendix B - An Investigation of the Meteorological Impact of Mechanical-Draft Cooling Towers at the Palisades Nuclear Plant - Data Report No 1 (February 1975)

Appendix C - An Investigation of the Meteorological Impact of Mechanical-Draft Cooling Towers at the Palisades Nuclear Plant - Third Annual Report (June 1975)

Appendix D - Environmental Noise Survey (July 22, 1975) vi

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I.

INTRODUCTION CONSUMERS POWER COMPANY PALISADES PLANT SEMIANNUAL REPORT OF OPERATIONS No 9 January 1 Through June 30, 1975 The first half of this reporting period was a continuation of Outage 74-4.

Retubing of the main condenser was completed and additional Eddy Current Testing in the steam generators was accomplished.

On April 2, 1975 the unit returned to service to conduct the Steam Generator Flushing Program as specified in Appendix C to the license.

From April 2 through June 20, 1975 the plant operated at power levels up ~o 90%, with two brief outage interruptions.

On April 6, the turbine was tripped because of a leak in the flow instrument tap located in the drain line from 5A feedwater heater to the moisture separator drain tank and on Aprill 22, the turbine tripped due to low oil pres-sure in the electrohydraulic control system caused by a cracked fitting in the piping to No 4 governor valve.

In both instances, the plant was returned to service in a matter of a few hours.

The plant was removed from service from June 20 until June 30, 1975 for control rod drive seal repair.

The plant resumed operation on June 30, 1975.

After a few hours' operation, an erratic feedwater control system tripped the unit from service; however, the unit returned to service the same day.

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L Several notable factors affected plant operation.

An all volatile treatment program for secondary water has achieved reasonable water chemistry stability.

Continuous blowdown has removed small quanti-ties of phosphate from the steam generators.

Operation continued with two low pressure feedwater heaters and drain cooler bypassed in each train, pending retubing of the feedwater heaters.

The two rows of blading that had been removed from a low pressure turbine were re-placed.

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II.

OPERATIONS

SUMMARY

A.

CHANGES IN FACILITY DESIGN Seven facility changes were completed during this reporting period, as described in Section VI. A of this report.

None re-quired NRC authorization.

B.

PERFORMANCE CHARACTERISTICS

1.

Equipment Routine performance testing and special tests were conducted throughout the period to monitor equipment performance.

Testing results include:

a.

Reactor internals vibration continues to be virtually absent, as monitored by special test T-60 (Section VI. B).

b.

Core flow was measured by special test T-61 and results were as predicted.

c.

Additional ~ddy Current Testing of the steam generators in February resulted in the plugging of tubes indicating 50% or greater degradation.

Eighty-one (81) tubes were plugged in "A". steam generator and two hundred and five (205) were plugged in "B" steam generator, respectively.

d.

Additional Eddy Current Testing in the high pressure feed-water heaters resulted in plugging a small number of tubes.

e.

Scheduled Technical Specification testing of the CRDM revealed several problems which were resolved.

f.

The cause of tube leaks in the Component Cooling Water Heat Exchanger was identified as flow induced vibration.

Repairs were accomplished.

g.

The annual hydrostatic leak test on the suction piping of the safety injection pump was satisfactorily completed.

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h.

Procedural changes should eliminate low power plant trips caused by low suction pressure of the feedwater pumps.

i. Governor repair and adjustment resolved the problems asso-ciated with the starting and loading of the turbine driver for the steam driven auxiliary feedwater pump.

2.

Fuel The unit essentially operated in the period from March 31 through June 30, 1975.

Power level changes were originally made in 10% increments to finish the necessary agitation for

the Steam Generator cleanup program.

These changes in power

.were administratively restricted to maximum rates of 10% per day and the subsequent power decreases were limited to 6%

per hour.

Once power level was stabilized at 80% of full power from May through the end of the reporting period, the Iodine 131 equi-librium level was about 0.08 µCi/cc with an Iodine 131 to Iodine 133 ratio (131/133) of about 1.0.

These levels are felt to correspond to about 0.05% failed fuel.

Continued surveillance was conducted on the core as a result of the replacement of fuel assembly C-14 with B-69.

The re-

sults of these studies are consistent with.those reported to DOL on November 15, 1974 entitled "Core Performance Testing and ~pecial Start-Up Report."

During operation at equilibrium at 80% of full power a reac-

. tivity anomaly of about +o.6% ok/k was noted in the core.

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This deviation is from the calcul,ated boron versus burnup curve to the actu~l all rods out observed boron concentration.

This anomaly in overall core reactivity was also accompanied by a change in the axial flux shape from a predominant peak in the lower half of the core to an upper core peak.

The latter event was reported to DOL on November 15, 1974 in a report entitled "Core Performance Testing and Special Start-Up Report."

A thor-ough investigation was conducted to determine the cause of the anomaly.

It has been reported by others(a) that changes in reactivity of up to 0.6% ok/k have been experienced at Yankee Rowe and Saxton as a result of pH and crud changes in the coolant system.

A physics study using the present Palisades axial fuel exposure distribution and accounting for moderator temperature, doppler and Xenon feedback was conducted.

The calculated (ie., pre-dieted) axial flux shape was in excellent agreement with the present incore generated axial flu:ic.

An attempt was made to calculate the axial flux shape from previous operation in August of 1973.

(NOTE:

Palisades Shutdown in August 1973 with a core expo3ure of about 6,800 MWD/.MTU.

The unit operated about one month in October 1974 and resumed operation in April 1975 to date.

During the August 1973 outage, the entire core was unloaded for fuel inspection and subsequently, reloaded with the same fuel except in the case of assembly B-69, addressed in the previous semiannual report.)

(a)Sjostrand, N. G., "The Effect of Coolant pH on Reactivity,"

Nuc Sci & Engr, 35, P 394, March 1969.

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This was accomplished by assuming an axially dependent "crud-related" poison which was large at the top-of-core and de-

creased to zero at about mid-core.

The reactivity defect in assuming such a poison distribution present in August 1973 and removed prior to May 1975 was calculated to be about 0.5% 6k/k.

This is in good agreement with the observed reactivity anomaly.

The axial power at Palisades is limited by linear heat rate considerations for fuel densification and also recently for

ECCS criteria. In both cases (in August 1973 and to date in 1975), the axial peaking has been well below license limits.

Presently, this matter is still being studied.

C.

CHANGES IN PROCEDURES Procedure or Section A5 Bl B2 Chan e General Index, Section Index, Record of Revision and List of Effective Pages brought up-to-date.

Change the order of steps start-up from cold shutdown in the procedure and checksheets.

Change Safety Injection (SI) bottle, Safety Injection Actuation Signal (SIAS) and Main Steam Isolation Valve (MSIV) operating points in the proce-dure and checksheets.

Change operational setpoint of SI bottle MOVs.

Change PCS Leak Test pressure and authority.

Eliminate operation of evaporator's vent to the Waste Gas System Tank (WGST) when venting the Volume Control Tank (VCT) during a purge operation.

II-4 l**

Procedure or Section B4 B9 Bl2 Bl3 Bl4 Bl7 Bl8 B26 B30 B32 Chi:i.nge The spray header and nozzles test was deleted from the pro-cedure. It is now a Technical Specifications Test Procedure.

Operation and reset of the pilot wire-rela.y was added.

Editorial only.

Add a new step to evacuate only one side of the main condenser.

Cooling tower and main condenser procedures changed to re-fleet needs dictated by operating experience, such as chem-ical injection, single side operation, thermal discharge

limits, operation of pumps and fans, cold weather operation and chemistry sampling.

Checksheets editorially changed.

Resin sluicing procedure changed to reflect the best operating experience to date.

Editorial changes were made on valve num-bers.

Usage of the laundry filter and authorization of same were made.

Operational changes were made to the evaporator procedures.

Change Waste Gas Decay Tank (WGDT) operations to reflect the new valving and electrical scheme.

Also, add new sampling procedures.

Operation of the new temporary demineralizers was added to procedure, to include tables, figures and graphs.

Add plant requirement - position of control switches after auto-operation.

New protective control switch added.

New test procedure added.

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Procedure or Section Chan e Cl New Technical Specifications requirements added.

Operation of the data logger alarm clarified.

Changes to procedure to meet new Technical Specifications incore alarms and action clarified D4 Steam Generator tube rupture procedure clarified to expedite shutdown and minimize steam and water leakage to the environs.

F special Sample frequency changed.

Chemistry limit changed.

FM Addition of new control switch and the operating modes added to procedure.

D.

IN-SERVICE SURVEILLANCE PROGRAM Scheduled surveillance tests and samples were conducted as required by Section 4.0 of the Technical Specifications.

There were no primary coolant system structural surveillance tests, or containment tendon tests performed during this period.

Contain-ment leak rate testing is described in Section II. E of this report.

Reactor internals vibration monitoring is described in Section VI. B.

In-service inspection of the Steam Generators was completed in February as described in the report to DOL dated March 25, 1975.

E.

CONTAINMENT LEAK RATE TESTS Local leak testing was completed on January 13, 1975.

The total leak rate before maintenance was 322,314 cc/min compared to 39,402 cc/min after maintenance, or approximately 63% of the total allowable 62,700 cc/min.

Abnormal Occurrence Report A0-75-1 to NRC dated January 31, 1975 describes the occurrence and corrective action.

II-6*

Only the purge air supply (penetration #1) required maintenance.

It was found to have an excessive leak rate of 283,421 cc/min.

The packing for the valve, CV-1808, was greased and the penetration was retested with a resultant leak rate of 509 cc/min.

F.

CHANGES, TESTS AND EXP.ERIMENTS REQUIRING NRC AUTHORIZATION During this reporting period, there were no facility changes, tests, or experiments conducted which required prior authorization from the NRC.

G.

ORGANIZATION CHANGES Some. of the organizational changes listed below occurred prior to this reporting period but were inadvertently not reported in pre-vious semiannual reports. All of these changes have been the sub-ject of special letter reports and are listed below for record purposes.

1.

Maintenance Superintendent Mr. D. R. Hughes was transferred to the General Office with Mr. G. H. Hein ~ssuming the responsibilities of this position.

This change was effective March 1, 1975.

Mr. Hein came to Palisades Plant in June 1971 following grad-uation from Michigan Technological University with a BS Degree in Mechanical Engineering.

Prior to this, he served for seven years in the Navy Nuclear program where he gained valuable ex-perience in the nuclear power field.

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2.

Administrative Supervisor Mr. J. M. Bielinski was assigned to the Administrative Super-visor position effective on July 1, 1974.

Mr. Bielinski has over 27 years of Company clerical administra-tion experience in Generating Plant, Region Office and General Office operations.

He is a high school graduate and has supple-mented his educational background with two ICS Certificates in Business Administration and Office Management and approximately two years of college credit in Business Administration.

3.

Health Physicist Mr. R. W. Sinderman was returned to the General Office with Mr. V. E. Shockley assuming the responsibilities of this position.

This change was effective March 1974.

Mr. Shockley graduated from Idaho State College, Pocatell0, Idaho, with a BS Degree in Geology in 1958.

He spent five years with the Phillips Petroleum Company in the Health Physics Group.

This experience included assignments at the Chemical Processing Plant and the Material Testing Reactor.

In February of 1964, Mr. Shockley accepted a staff position as a Health and Safety Engineer with the Health and SafetJ.

Department of the University of California, Lawrence Radiation Laboratory at the Nevada Test Site.

As a Health and Safety Engineer, he directed re-entry and recovery operation and performed hazards analysis for specific assigned weapons development tests.

He held this position until accepting employment with Consumers Power Company as the Palisades Plant Health Physicist.

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4.

Quality Assurance Superintendent Consistent with our letter to DOL dated Oct*ober* 1, 1974, the Quality Assurance Engineer was*chariged to the Quality Assurance Superintendent and reports directi.Y -to the Qttality Assurance Administrator (Operation). Mr. R. E. McCaleb continues to fill this position.

5.

Operations Supervisor A riew position, Operations Supervisor, has *been created.

This.position reports to the Operations Superintendent and is responsible for the ongoing activities of the.Plant Operating Department.

Overall direction still rests with the Operations Superintendent; however, this riew position will allow better

*day-to-day coordination of the operating shifts.

Mr. R. L. Beardsley assumed this position effective March 1, 1975*

Mr. Beardsley has been a Shift Supervisor a~ Palisades since

. the original staffing in 1968.

Prior to that time, he was a

. licensed Control Operator* at Big Rock Point Plant for seven years and a fossil plant*operator for three years.

Mr. Beardsley holds*a Se:riior Operator License (SRO) at-Palisades and has been intimately-involved in -all plant operations sin:ce original start-up.

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6."

Shift Supervisor Mr. S. Ghidotti, Jr. was promoted to Shift Supervisor effec-tive April 1, 1974.

Mr. Ghidotti joined the Company in 1960, working on the operation staff at a number of our conventional plants.

He joined the Palisades staff in February 1969, re-ceived his Reactor Op~rator License (RO) in September 1972 and his SRO in March 1974.

7.

Plant Superintendent

Mr. J. G. Lewis has succeeded Mr. R. B. DeWitt as Superintendent of the Palisades Plant, effective May 1, 1975.

Prior to his promotion, Mr. Lewis served as Palisades Plant Operations Super-intendent for two years and as Palisades Plant Technical Engineer for five years prior to that.

His nuclear experience at Consumers Power Company dates back to 1962.

Mr. Lewis holds a BSEE Degree and holds a Senior Reactor Operator License on the Palisades Plant.

8.

Operations Superintendent Mr. G. B. Slade has succeeded Mr. Lewis as Operations Super-intendent, effective May 1, 1975.

Prior to his promotion, Mr. Slade served as Technical Superintendent at Palisades for 1-1/2 years and prior to that as Reactor Engineer at Palisades for 1-1/2 years.

His nuclear experience at Consumers Power Company dates back to 1969.

Mr. Slade holds a BSME Degree and an MSNE Degree.

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9.

Technical Superintendent Mr. K. w. Berry has succeeded Mr. Slade as Technical Super-intendent, effective May 1, 1975.

Prior to his promotion, Mr. Berry was Instrument and Control Engineer at Palisades for 3-1/2 years.

Mr. Berry's nuclear experience at Consumers Power Company dates back to 1969.

Mr. Berry holds a BSEE Degree and holds a Senior Reactor Operator license on the Palisades Plant.

10.

Instrument and Control Engineer Mr. H. J. Palmer has succeeded Mr. Berry as. Instrument and Control Engineer effective May 1, 1975.

Prior to his promo-tion, Mr. Palmer held the position of General Engineer in the Electric Operations Department of the General Office for two years, with responsibilities in the instrumentation and con-trol area.

Mr. Palmer holds a BSEE Degree and an MSNE Degree.

Prior to college, he served in the Nuclear Navy for seven years as an Electronics Technician.

Mr. Palmer held an Operators License on the University of Illinois Nuclear Re-actor

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III.

POWER GENERATION The following table and graph shows the thermal and electrical gener-ation for the plant during this reporting period and cumulative totals since initial criticality:

TABLE I January 1 Through June 30, 1975 Gross Thermal Power Generated (MWht)

Gross Electrical Power Generated (MWh )

e Net Electrical Power Generated (MWh )

e Reporting Period Cumulative To Date Number of Hours Reactor was Critical (hrs) 3,175,872 952,840 881,977 1,976.5 17,289,432 5,457,090 5,135,682 12,213.4 Number of Hours Generator was On-Line (hrs) 1,887.3 11,208.4 III-1

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PALISADES THERMAL POWER GENERATION FIRST HALF. 1975 (NOTE: POWER LEVELS SHOWN ARE TWO DAY AVERAGES)

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IT I

JANUARY FEBRUARY MARCH APRIL MAY JUNE

IV.

SHUTDOWNS The reporting period began with the plant shutdown under Outage 74-4 for retubing the main condenser and other items as described in the Eighth Semiannual Report.

This outage continued for an additional 2252.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months for a total of 3679.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months duration.

The unit was re-turned to service on April 2, 1975 and operated at power levels up to 60% full power until on April 6th when the unit was forced off the line.

A.

OUTAGE 75-1

1.

Cause of the Outage:

Forced outage after power was reduced to repair a steam leak on feedwater heater E5A drain flow element.

Unit had to be removed from service to allow repairs to be made.

2.

Method of Shutdown:

Manual trip of the turbine generator.

3.

Duration of the Outage:

2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4.

Plant Status During the Outage:

Hot Standby.

5.

Corrective Action Taken to Prevent Repetition:

Repair of the leak was effected.

The unit was returned to service on April 6th and operated at power levels up to 90% full power.

Power levels varied between 60% and 90% full power in accordance with the required Steam Generator Secondary Flush Program.

The unit tripped off the line on April 22nd.

B.

OUTAGE 75-2

1.

Cause of the Outage:

Forced when a turbine E-H control fluid fitting failed causing a unit trip from 86% full power.

IV-1

2.

Method of Shutdown:

Auto trip of the turbine generator and reactor.

3.

Duration of the Outage:

14. 0 hours0 days 0 hours 0 weeks 0 months .

4.

Plant Status During the Outage:

Hot Standby.

5.

Corrective Action Taken to Prevent Repetition:

a.

The failed hydraulic fitting was replaced.

b.

Other fittings were inspected for leakage.

The unit was returned to service on April 23rd and operated at 80% full power until forc.~d off the line on June 20th.

C.

OUTAGE 75-3

1.

Cause of the Outage:

Forced outage a~er CRDM seal leak-off temperature became excessive.

Power ~as reduced to 30% and an *unsuccessful attempt was made to reseat the seals by dropping the rod.

Power was further reduced and the unit taken off the line.

2.

Method of Shutdown:

Manual trip of the turbine generator.

3.

Duration of the Outage:

227.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

4.

Plant Status During the Outage:

Cold Shutdown.

5.

Corrective Action Taken to Prevent Repetition:

a.

CRDM seal was replaced.

b.

CRDM motor was replaced.

c.

CRDM seal thermocouple was replaced.

d.

Minor secondary side steam leaks were repaired.

The unit was returned to service on June 30th and remained on line for 4.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The unit was forced off the line when erratic feed-water control tripped the feedpump.

IV-2

D.

OUTAGE 4

1.

Cause of the Outage:

Forced outage on loss of a feedpump and the resulting low steam generator ;level reactor trip.

2.

Method of Shutdown:

Auto trip of the reactor.

3.

Duration of the Outage: 7.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

4.

Plant Status During the Outage:

Hot Shutdown.

5.

Corrective Action Taken to Prevent Repetition:

a.

The main feedpump which was placed in-service was the non-operating pump at the time of the trip.

b.

Feedwater control was placed in Auto at a lower power level.

The unit was returned to service on June 30th and remained on-line for the remainder of the reporting period

IV-3

V.

MAINTENANCE The following is a list of safety-related maintenance performed during this reporting period.

These items are described in the following format:

The system or component involved, the Maintenance Order number (M.0.#) and date.

a.

The cause of the malfunction.

b.

The results and effect on safe operation.

c.

Corrective action taken to prevent repetition.

d.

Precautions taken' to provide for reactor safety during, repair.

A.

COMPONENT COOLING SYSTEM

1.

Component Cooling Heat Exchanger, E-54A under M.O. #CCS-75-05 and dated 2/3/75 and

a.

Malfunction caused by flow induced mechanical failure of a tube.

b.

Resulted in leak, but redundant heat exchanger was available and release path was monitored for radiation.

c.

The leaking tube was plugged.

d.

Reactor in cold shutdown.

2.

Component Cooling Heat Exchanger, E-54B under M.O. #CCS-75-06 and dated 5/17/75

a.

A malfunction caused by flow induced mechanical failure of a* tube.

b.

Resulted in leak, but redundant heat exchanger was available and release path was monitored for radiation.

c.

The leaking tube was plugged~

d.

Reactor in cold shutdown.

/

V-1

3.

Component Cooling Heat Exchanger, E-54A under M.O.'s #CSS-75-10 and #CSS-75-12 and dated 5/17/75 for both

a.

Old plug weld leak.

b.

Leak developed during hydro test after plugs were installed as Preventive Maintenance.

c.

Leaking plug was rewelded.

d.

Reactor in cold shutdown.

B.

CONTAINMENT BUILDING AND CRANE

1.

Containment air lock doors under M.O. #CLP-74-15 and dated 2/24/75

a.

Misalignment and need of lubrication.

b.

Difficult door operation.* This problem did not hamper the integrity of the containment.

c.

Adjustments were made and all moving parts were lubricated.

d.

Reactor in cold shutdown.

2.

Emergency air lock door under M.O. #CLP-75-15 and dated 5/17/75

a.

Misalignment of door and need of lubrication.

b.

Difficult door operation.

No effect on safe operations because door could be closed.

c.

Door was realigned and lubricated.

d.

Reactor in cold shutdown.

C.

CONTROL ROD DRIVES

1.

Control Rod Drive Mechanism (CRDM) #44 secondary position indicator under M.O. #CRD-74-10 and dated 5/17/75

a.

Shorted out secondary switch.

b.

Indicator was inoperable.

No effect on safe operations because primary rod indicator was operable.

V-2

c.

Replaced indicator with a new unit.

d.

Reactor in cold shutdown.

2.

Rebuild CRDM seal housings #12, #39 and #28 under M.O.

CRD-74-023 and dated 5/13/75

a.

Seal failures.

b.

Seal leak.off.

No effect on safe operations because within allowable Technical Specifications limits for normal operation.

c.

Mechanical seals were replaced.

d.

No effect on Reactor safety because maintenance done during cold shutdown.*

3.

Control Rod Drive Mechanism #36 under M.O. #CRD-74-025 and dated 5/3/75

a.

Clutch coil on CRDM #36 was open circuited for unknown

reason.

b.

Rod #36 could not be moved, but was in dropped position so there was no effect on safe operations.

Other rod drives were operable.

c.

Replaced the entire drive package.

d.

Reactor was in cold shutdown.

4.

Rebuild 23 seal housings, #01, 02, 03, 05, 08, 10, 11, 13, 15, 18, 21, 22, 23, 25, 27, 31, 34, 35, 37, 38, 41, 42 and 45 under M.O. #CRD-74-028 and dated 5/3/75

a.

Several seal failures.

b.

Excessive leaking in prior operation prompted changing these 23 seals to the chrome oxide type while in cold shutdown.

c.

Rebuilt the housings with chrome oxide seals.

d.

Reactor was in cold shutdown.

V-3

5.

Repair CRDM #30 seal housing under M.O. #CRD-75-007 and dated 5/17/75

a.

Gasket failures.

b.

Leaky seal housing.

No effect on safe operations because leakoff was within allowable Technical Specifications limits for normal operation.

c.

Rod drive housing gasket and CRDM access flange gasket were replaced.

d.

Reactor in cold shutdown.

6.

CRDM seal housing #48 under M.O. #CRD-75-11 and dated 5/17/75

a.

Seal failures.

b.

Seal leakoff, but within allowable Technical Specifications limits for normal operation.

c.

Replaced vapor seal, mechanical seal and repacked bearings.

d.

None - was not being used at this time.

7.

CRDM #30 torque trace under M.O. #CRD-75-15 and dated 6/2/75

a.

Cause is unknown.

b.

CRDM #30 gave an erratic torque trace.

Control rod was still operable.

c.

Removed, inspected and replaced.

d.

Reactor in cold shutdown.

D.

CHEMICAL AND VOLUME CONTROL SYSTEM

1.

Repair and place letdown line Relief Valve, RV-2203 in upright position under M.O. #CVC-711-057 and dated 2/24/75

a.

A faulty ball and disc.

b.

Valve leaked internally, but was still operable so there was no effect on safe operations.

V-4

c.

Replaced ball and disc, moved from horizontal to vertical position and adjusted for proper operation.

d.

Reactor in cold shutdown.

2.

"C" Charging Pump Discharge Check Valve under M.O. #CVC-74-070 and dated 5/3/75

a.

Crack in the check valve.

b.

Resulted in a leaking check valve.

No effect on safety because two other charging pumps were available.

c.

Repaired by grinding out crack and fill welding.

d.

Two other charging pumps were available.

3, Elbow downstream of CV-2110 in charging line to PCS under M.O. #CVC-74-75 and dated 5/3/75

a.

Crack in elbow weld.

b.

Resulted in leak at the elbow.

No effect on safe operations because two other charging lines were available.

c.

Ground out crack and rewelded.

d.

Two other charging lines were available.

4.

"A" Charging Pump suction valves under M.O. #CVC-74-78 and dated 5/17 /75

a.

Several valves broke in the past.

No present malfunction.

b.

Changed to new design to avoid future problem.

No effect on safe operation.

Work completed to improve reliability of pump.

c.

Replaced suction valves with redesigned ones.

d.

Reactor in cold shutdown.

V-5

5, Repair RV-2013 on letdown line under M.O. #CVC-75-008 and dated 2/15/75

a.

Bad gaskets.

b.

Valve was operable, but had external leakage.

There was system redundancy available so there was no effect on safe operations.

c.

Replaced bad gaskets and set relief point.

d.

Reactor in cold shutdown.

6.

Charging line hangers under M.O. #CVC-75-0ll and dated 5/3/75

a.

Cause was unknown.

b.

Broken and loose hangers.

Did not affect safe operations.

c.

Installed new U bolts and fastened hangers to floor.

d.

System was operable so was not endangering reactor safety.

7.

Control Valve, CV-2165 under M.O. #CVC-75-021 and dated 5/16/75

a.

Bad gaskets and packing.

b.

Caused external leakage, but did not effect the safe operation of the plant because valve was still operable.

c.

Cleaned the valve and replaced packing and gaskets.

d.

Did not affect the safety of the reactor.

8.

Charging Pump, P-55B under M.O. #CVC-75-25A and dated 5/17/75

a.

Dirty oil and filter.

b.

Tripped off from low oil pressure, but two other pumps were available so no effect on safe operations.

c.

Oil and filter were changed.

d.

Two other pumps were available.

V-6

9.

Pipes and hangers under M.O. #CVC-75-25B and dated 5/17/75

a.

Pipe wear.

b.

No effect on operations because system was still operable.

c.

Measurements were taken for closer investigation.

d.

No effect on Reactor safety.

10.

Chemical and Volume Control Valve CV-2155 under M.O. #CVC-75-27 and dated 5/17/75

a.

CV-2155 seemed to have a bent stem.

b.

Valve was operable so no effect on safe operations.

Corrected to prevent a future failure.

c.

Stem was slightly bent so it was straightened and seat was lapped.

d.

No effect on Reactor safety because valve was operable.

11.

Charging Pump P-55A Breaker 52-1205 under M.O. #CVC-75-28 and dated 5/17 /75

a.

Charging spring fuses were in upside down.

b.

Pump could not be started from Control Room, but two other pumps were verified operable.

c.

Charging spring fuses were placed in the correct position.

d.

No effect on Reactor safety because two other pumps were available.

12.

"B" Purification Filter under M.O. #CVC-75-33 and dated 5/15/75

a.

Normal use.

b.

Filter 'B' became inoperable, but Fi'lter 'A' was operable so it did not effect safe operations.

c.

Replaced filter.

d.

Filter 'A' was used during repair.

V-7

13.

Charging Pump P-55B under M.O. #CVC-75-34 and dated 6/2/75

a.

Dirty oil and filter.

b.

Tripped off because of low oil pressure.

No effect on safe operations because two other pumps were available.

c.

Changed oil and filter.

d.

No effect on Reactor safety because two other pumps are available.

14.

Charging Pump P-55A under M.O. #CVC-75-40 and dated 6/2/75

a.

Seal packing was worn from normal use.

b.

Internal leaking and low discharge pressure.

No effect on operations because two other pumps were available.

c.

Replaced packing.

d.

No effect on Reactor safety because two other pumps were available.

E.

DATALOGGER

1.

Secondary Datalogger under M.O. #DTA-75-002 and dated 5/17/75

a.

Improper cooling of Datalogger Systems.

b.

Excessive heating of mercury relay causing erroneous indica-tions.

There was no effect on safe operations because primary Datalogger was available and operable.

c.

New cooling was being installed to Dataloggers at this time to prevent this reoccurrence.

d.

The safety of the Reactor was upheld because primary Data-logger was available.

V-8

2.

Primary Datalogger under M.0.#DTA #75-06 and dated 5/3/75

a.

Faulty coil on multiplexer relay 8-3.

b.

Primary Datalogger was inoperable.

No effect on safe operations because secondary Datalogger was available and operable.

c.

Replaced faulty coil.

d.

No effect on Reactor safety because secondary Datalogger was available.

3.

Secondary position indication on CRDM #36 under M.O. #DTA 75-08 and dated 5/16/75

a.

Input voltage to computer was off.

b.

Secondary position indicator gave erratic readings.

No effect on safe operations because primary rod indicator

36 was operable.

c.

Computer range was checked and adjusted.

d.

No effect on Reactor safety because primary rod indicator

36 was ?perable.

4.

Sequence error buzzer to Primary Datalogger under M.O. #DTA 75-10 and dated 5/15/75

a.

Deficiency in Primary Datalogger software and alarms.

b.

Primary Datalogger did not update readout (A0-75-10).

No effect on safe operations because main function is for alarms which were operable.

c.

Sequence error buzzer was wired to Primary Datalogger alarm light for audio alarm.

d.

None - Secondary Datalogger was operable for rod.

Position indicator and primary datalogger were out of service for less than two hours.

V-9

F.

EMERGENCY POWER SYSTEM

1.

Lube oil pumps of emergency Diesel Generators under M.O.

EPS74-035 and dated 5/3/75

a.

Cause unknown at present time.

b.

Impeller keyway cracked.

No effect on safe operations as one Diesel was alway~ available and operable.

c.

Pump impeller, seals and bushings were replaced.

d.

Operability of Diesel not being repaired was checked.

2.

Diesel Generator cooling under M.O. #EPS75-002 and dated 5/3/75

a.

No malfunction occurred.

b.

A sampling point was needed.

No effect on safe operations as one Diesel was always available and operable.

c.

Installed fittings for the purpose of sampling.

d.

One Diesel was always available and operable.

3.

1 Inverter of Diesel Generators under M.O. #EPS75-002 and dated 3/15/75

a.

Faulty oscillator control card.

b.

Voltage, amperage and frequency were erratic.

2-2 Diesel Generator was available and operable so there was no effect on safe operations.

c.

Replaced oscillator control card.

d.

2-2 Diesel Generator was available and operable.

4.

Solo transformer to emergency power supply under M.O. #EPS75-003 and dated 1/31/75

a.

Faulty capacitor.

b.

Transformer was inoperable.

The backup system was operable so there was no effect on safe operations.

V-10

c.

After troubleshooting a capacitor was replaced.

d.

Backup system was operable.

No effect on Reactor safety.

5.

Low Lube Oil Pressure Alarm on Diesel Generator 1-1 under M.O.

E:PS 75-04 and dated 5/15/75

a.

Faulty pressure switch of Diesel-Generator 1-1.

b.

Resulted in an oil leak.

The backup Diesel Generator wa<'

operable and available so there was no ef*fect on safe operations.

Pressure switches were replaced for Generator 1-1 and then Generator 1-2.

d.

Did not affect safe operation because one Diesel Generator was always operable.

6.

Oil lube pump to Diesel Generator 1-1 under M.O. #EPS 75-06 and dated 5/17 /75

a.

Generic problem was found.

Improper heat treating caused keyway to crack.

b.

No malf1inction.

Changed because of generic problem.

Diesel Generator 1-2 was operable and available so there was no effect on safe operations.

c.

The lube oil pump was replaced with a rebuilt spare with improved impeller material.

d.

Diesel Generator 1-2 was check for operability.

7.

Diesel Generator 1-1 Prelube.Pump Relief Valve Under M.0. #EPS75-009 and dated 5/17/75

a.

Internal relief was set greater than the specified 100 psig.

b.

Did not relieve at 100 psi during check.

There was no effect on safe operations because the generator was still operable and generator 1-2 was also operable for backup.

V-11

c.

Cleaned and set relief for 100 psig.

d.

Operability of Diesel 1-2 was checked.

8.

Exhaust.temperature indicator Diesel Generator 1-1 under M.O. #EPS 75-12 and dated 5/17/75

a.

Loose selector knob.

b.

Gave erratic readings.

There was no effect on safe operations be~ause Diesel Generator 1-2 was operable and available.

c.

Filed a flat spot on sha~ for set screw.

d.

Operability of Diesel 1-2 was checked.

9.

Lube oil pump to 1-1 Diesel Generator under M.O. #EPS75-013 and dated 5/15/75

a.

Faulty gauge and tee in pump line.

b.

Resulted in an oil leak.

System was still operable under these conditions so there was no effect on safe operations.

c.

Replaced tee and gauge, and checked for leaks.

d.

Operability of Diesel 1-1 was checked.

10.

Governor of Diesel Generator 1-1 under M.O. #EPS 75-14 and dated 6/3/75

a.

Defective E-6A circuit board.

b.

Power oscillation during test. Diesel Generator 1-1 was removed from service, but 1-2 was operable so there was no effect on safe operations.

c.

E-6A circuit board was replaced.

d.

Operability of Diesel 1-2 was checked.

V-12

11.

Synchronizing switch to Diesel Generator 1-1 linder M.O.

EPS75-015 and dated 5/15/75

a.

Loose set screw.

b.

Knob couid be moved without switching.

There was no effect on safe operations because Generator 1-2 was available.

c.

Set screw was tightened.

d.

Diesel 1-2 was checked for operability.

12.

Pyrometer to Diesel Generator 1~1 under M.O. #EPS75-019 and dated 7/7/75

a.

Dirty contacts.

b.

Gave erratic temperature readings.

There was no effect on safe operations.

Generator 1-1 was still operable.

operable.

c.

Cleaned contact and tested.

d~ *Operability of Diesel l'-2 was checked:

G.

ENGINEERED SAFEGUARDS SYSTEM L

RV-3165 in high pressure safety *injection system under M.O.

ESS74-081 and dated 1/3/75

a.

Faulty disc in valve.

b.

Resulted in internal leakage.

Redundant hi~h pressure line was operable so there was no effect on safe operations.

c.

The valve seat was lapped and new disc installed.

d.

Reactor in cold shutdown.

2.

PIA-0371 and PIA-0363 of high pressure safety injection system under M.O. #ESS74-086 and M.O. #ESS74-087 and dated 1/25/75

a.

Gauges need calibration.

b.

Resulted in erroneous readings.

Systems were still operable so there was no effect on safe operations.

V-13

c.

Gauges were calibrated.

d.

None - Systems were still operable.

3.

CV-3042 in safety injection system under M.O. #ESS 75-07 and dated 5/16/75

a.

Gasket and packi~g failed.

b.

Resulted iri external leakage.

There was no effect on safe operations because valve was operable and system redundancy was operable.

c.

Lapped seat and replaced bonnet gasket and packing.

d.

Reactor in. cold shutdown.

4.

Left channel normal shutdown sequencer under M. 0. #ESS75-015 and dated 6/5/75 a;

Dirty contact.

b.

It started and stopped on first try, but it operated properly on two successive tries.

System was still operable and backup

available.

c.

After troubleshooting and cleaning a dirty contact, Technical Speci.ficatiOns Test R0-13 was run.

d.

Backup system was checked for operability.

5.

Check Valve in mini-flow header under M.O. #ESS 75-30 and dated 5/17/75

a.

Faulty bonnet seal and gaskets.

b.

Although it showed leakage the valve was still operable so there was no effect on safe operations.

c.

New bonnet seal and gaskets were installed.

d.

System redundancy assured the safety of the Reactor.

V-14

H.

FEEDWATER SYSTEM

1.

Turbine driver for auxiliary feedwater pump P-8A under M.O.

FWS 75-31 and dated 6/5/75 a.. Governor and overspeed trip were out of adjustment.

b.

Not starting and loading properly.

Pump was still operable and motor driven P-8A was also operable.

c.

Adjusted speed governor and overspeed trip.

d.

Operability of motor driven P-8A was checked.

I.

MAIN STEAM SYSTEM

1.

Steam to auxiliary feedwater pump pressure control valve PCV-0521A under M.O. #MSS74-059 and dated 1/8/75

a.

Failure of bonnet gasket.

b.

Resulted in steam leak from under lagging.

There was no effect on safe operations because valve was operable.

c.

Seating surface was cleaned and the gasket was replaced.

d.

Reactor was in cold shutdown.

2.

Containment spring hangers under M.O. #MSS75-021 and dated 5/15/75

a.

No malfunction occurred.

b.

Hangers were to be tightened and adjusted to prevent a possible future failure.

The system was still operational so there was no effect on safe operations.

c.

All clamps were tightened and all. spring hangers adjusted for the cold position.

d.

Reactor in cold shutdown.

V-15

3.

VH16-10 and VH16:...2 Spring Hangers under M.O. #MSS75-026 and dated 6/3/75

a.

Spring hangers were at wrong setting.

Did not malfunction.

b.

All systems were still operable so there was no effect on safe operations.

c.

Pipe hangers were set to hot position because plant was on-line.

d.

Adjustments had no immediate effect on the safety of the Reactor.

J.

NEUTRON MONITORING SYSTEM

1.

RPCIC nulcear power signal adjustment under M.O. #NMS 75-04 and dated 5/17/75

a.

Amplifiers needed adjusting.

b.

Gave erroneous indications.

Did not have an effect on the safe operation of the plant because they were operable.

c.

UIC amplifiers for the four (RPS) split detectors NI-05 and NI-08 were adjusted.

d.

Did not have an effect on the safety of the Reactor because the system was operable.

2.

Nuclear Instrument (NI) Power Range Meters Under M.O. #NMS 75-06 and Dated 6/5/75

a.

The positive 15 volt power supply failed for unknown reason.

b.

One channel meter inoperable.

Did not have an effect on safe operation of the plant because three other channels were operable.

c.

Meters were calibrated according to a specified procedure and power supply checked.

V-16

d.

Did not have an effect on safety of the Reactor because three NI power range meters were operable.

K.

PRIMARY COOLANT SYSTEM

1.

Control valves CV-1902 and CV-1903 in Primary Coolant Systems pressurizer water phase sample and loop sa:mpl~respectively under M.O. #PCS74-042 and dated 2/7/75

a.

Sticky from normal use.

b.

Difficult to operate.

Valves were still operable so there was no effect on safe operation.

c.

Lubricated sha.ft and retightened packing unit.

d.

None because valves were still operable.

2.

Plug tubes in 'A' Steam Generator under M.O. #PCS 74~64 and dated 3/15/75

a.

Corrosion due to chemical attack.

b.

Leaks in tubes caused primary to secondary leaks.

c.

Tubes that were determined to have leaks were plugged as per procedure.

d.

Reactor was in cold shutdown.

3.

LIA-0102A pressurizer level indicators under M.O. #PCS 75-08 and dated 2/7 /75

a.

Improperly wired.

b.

Low indicator light stays on for normal level because light is a low level indicator, but used as a high level indicator which gave a light with no alarm.

Three other backup indicators were operable so there was no effect on safe operations.

c.

The wiring was changed so it would indicate a low level.

d.

None because three other backup indicators were available.

V-17

4.

PS-0103 pressure switch for shutdown cooling motor operated valve under M.O. #PCS 75-14 and dated 3/15/75

a.

Pressure switches were out of calibration.

b.

Pressure switch failed to give permissive signal to motor operated valve during shutdown to 230 psi.

System operated properly even though th~ indication was lower than the actual so there was no effect on safe operations.

d..

PT-0103 and PI-0103 A and B were calibrated and checked the input to the PDP computer.

This showed indicator had read low about 70 psi.

d.

Reactor in cold shutdown.

L.

RADIATION MONITORING

1.

Process monitor calibrations under M.O. #RIA 75-11 and dated 5/17/75 *

a.

Out of calibration.

b.

Monitor gave erroneous indications. *Systems were operable before the outage.

c.

Calibrated monitors according to procedures.

d.

Reactor in cold shutdown.

2.

Process monitor RE-1810 under M.O. #RIA 75-37 and dated 5/16/75

a.

Pump failed on the monitor.

b.

Monitor gave erroneous readings. It was not pertinent to safe operation of the plant, but was fixed immediately for monitoring purposes.

c.

Pump was replaced.

d.

The safety of the Reactor was not immediately affected by loss of the monitor.

V-18

3.

Radiation Monitors 1805 and 1806 llllder M.O.. #RIA 75-43 and dated 6/13/75

a.

Out of calibration.

b.

Monitors giving high, erratic readings.

There was no effect on safe operations.

The trip function was still operable and would have tripped if radiation had gotten around 5R.

c.

Monitors were checked and recalibrated.

d.

Reactor safety was not impaired because trip function was operable.

M.

REACTOR PROTECTIVE SYSTEM

1.

LA-0751C for alarm on Steam Generator Low Pressure of Reactor protection system under M.O. #RPS74-004 and dated 6/14/75

a.

15V power supply failed.

b.

Alarm was inoperable.

Other sensors and alarms were operable so there was no effect on safe operations.

c.

Replaced and ran check on the 15V power supply.

d.

None - other sensors and alarms were operable.

2.

RPS Channel D llllder M.O. #RPS74-019 and dated 1/25/75

a.

Calibration was found to be off during monthly Technical Specifications Test.

b.

Channel D gave incorrect indications..

Three channel re-dundancy was available for safe operation.

c.

Channel D was recalibrated.

d.

The system redur;idancy was sufficient for the safety of the Reactor.

3.

Thermal margin low pressure trip PIA-0102A under M.O. #RPS 75-01 and dated 5/19/75

a.

Out of calibration.

V-19

b.

Setpoint increased from 1650 psi to 1960 psi.

There was no effect on safe operations because system redundancy was operable.

c.

PIA-0102A was set back to correct setting of 1650 psi.

d.

System redundancy operable and higher setting would only result in it tripping sooner while it was still in safe operation.

N.

RADWASTE SYSTEM

1.

Inspect solenoid valves under M.O. #RWS75-104 and dated 5/17/75

a.

These valves were inspected because of possible generic problems located in other plants.

b.

No malfunction had occurred.

There was no.effect on safe operations because all valves were operable at the time of the inspection.

c.

All safety-related solenoid valves were inspected and one was adjusted.

d.

No effect on Reactor safety because all valves were operable.

O.

SERVICE WATER SYSTEM

1.

Service Water Pump P-7A under M.O. #SWS74-007 and dated 6/2/75

a.

Motor bearing failure.

b.. Motor was inoperable.

There was no effect on safe operations

be.cause another pump, p..;7B, was available*.*

c.

Motor bearings were replaced.

d.

Another pump, P-7B, was available and checked for operability.

V-20

2.

Valves CV-0843, CV-0838 and CV-0872 for containment air cooler lines of Service Water System under M.O. #SWS74-016 and dated 3/15/75

a.

One badly eroded valve noted.

b.

Checked because of previous failure.

There was no effect on safe operations because there were no present failures.

c.

Checked all three and replaced one badly eroded valve.

d.

Reactor in cold shutdown.

3.

Service Water Pump P-7B under M.O. #SWS 75-05 and dated 5/9/75

a.

Worn bushings and gaskets.

b.

Low discharge pressure.

Standby pump, P-7A, was used while P-7B was out-of-service so there was no effect on safe operation.

c.

Replaced 1st and 2nd sections of shaft and six rubber bushings.

d.

Reactor safety was assured by standby pump, P-7A.

P.

WASTE GAS SYSTEM

1.

Waste gas relief valve RV-1111 under M.O. #WGS74-034 and dated 1/13/75

a.

Gaskets and 0 rings were bad.

b.

Valve operated, but had slight leakoff.

It operated so it did not have an effect on safe operations.

c.

Replaced old gaskets and 0 rings.

d.

Reactor in cold shutdown.

2.

Auxiliary Building o2 analyzer under M.O. #WGS75-07A and dated 6/2/75

a.

A magnetic cell failed.

b.

C-103 gas analyzer would not register.

Safe operations was assured by grab sampling.*

V-21

c.

The magnetic cell of this unit was replaced.

d.

Did not effect the safety of the Reactor.

3.

Waste Gas Compressor C-54 under M.O. #WGS 75-11 and dated 6/13/75

a.

Setpoints were off on motor starter.

b.

C-54 would not start automatically.

C-54 was still able to be operated manually so there was no effect on safe operations.

c.

Adjusted PIC-1111.sets to make it operate automatically.

d.

The pump could be started manually so there was no effect on Reactor safety.

V-22

VI.

CHANGES, TESTS AND EXPERIMENTS This section contains facility changes and special tests that were completed during this reporting period, which are related to safe op-eration of the facility, but which did not r.equire. NRC authorization.

A.

FACILITY CHANGES

1.

FC~l99 - Inlet Flanges for Boric Acid.Safety Valve Discharge Discharge piping for RV-2230 and RV-2232 - RV-2240 was cut out of line and routed to the atmosphere.

This was completed because the relief valves were discharging back into the system~ This allowed boric acid to sit on the discharge side of the valve creating back pressure on valves, thus increasing the lift point and allowing external leakage through the bonnet.

2.

FC-200 -*Install Flanges on ESS RVs Inlet and outlet flanges were added to RV-3165, 3264, 3266 and 3267.

The addition of flanges will allow cal.ibration of valve set points and valve internal repairs.

3.

FC-204 - Containment Ventilation Flow Adjustment Vortex breakers were installed in the inlets to the main ex-haust fans and the blades on the main e~aust fans were ad-justed.*

VI-1

This was completed to produce a negative pressure in the main exhaust plenum during all recognized modes of ventilation system operation.

4.

FC-217.;.. Replacement.of In-Core Neutron Detectors FOrty (40) of the forty-five (45) in-core neutron detectors were replaced with a new design (solid sheath) in-core.

One (1) was replaced with an in-core of the old design (penflex sheath).

Four (4) of the new in-cores could not be installed, but this did not present an unreviewed safety problem.

The replacement of the in-cores was necessitated by the failure of many in~cores and the anticipated future failures.

The new design of in-cores used is expected to improve the life of the in-cores.

5.

FC-219 - Reroute Discharge of RV 3162, 3164 and 3165 The discharge piping of relief valves 3162 (low-pressure injec-tion), RV-3164 (redundant high-pressure injection), and RV-3165 (high-pressure injection) was rerouted from the quench tank to a floor drain, which drains to the containment sump.

This was required because the quench tank is located at an ele-vation higher than the valves, thus allowing liquid to sit on the.discharge side of the valves creating internal and external leakage.

VI-2

6.

FC-227 - Radwaste Evaporator Distillate Conductivity Cell The existing conductivity cell (0.020 constant) was replaced with a (0.20 constant).

This was done to increase the range of the monitor to an adequate level.

7.

FC-242 - Alarm Relays for 125 V D-C Breakers 72-102 and 72-202 Normally closed (energized to open) relays were installed in the 2400 V lC and lD switchgear buses for use with the 125 V d-c control power to the incoming breakers 72-102 and 72-202, The addition of these r~lays allows prompt notification in the event of the loss of d-c control power to the incoming breakers, thereby reducing the possibility of equipment damage involving these buses.

B.

TESTS AND EXPERIMENTS

1. T Flux Oscillation Data.Acquisition Subsequent to Reactor Internals Repair PURPOSE:

In compliance with Section 4.13 of the Technical Specifications, nuclear noise surveillance was conducted on the core.

Measurements of amplitude probability distributions (APD), power spectral densities (PSD), coherence and phase angle relationships of excore neutron flux detectors were recorded.

RESULTS:

The findings substantiate that the maximum core barrel motion is no greater than 1.0 mil peak-to-peak.

There is no VI-3

indication of wearing, rubbing or unanticipated motion.

(Reference report to NRG dated May 22, 1975.)

SAFETY EFFECTS:

Plant safety was not compromised during this test since data acquisition did not interfere with normal plant or Control Room functions.

The signals are taken from buffered outputs of the excore detectors.

2.

T Core ~P, Flow PURPOSE:

This test was conducted to measure primary coolant system flow after steam generator tube plugging, and to measure core differential pressure to determine core lift.

RESULTS:

Primary coolant system flow was measured to be 130 x 106 lb/h at 532°F, which is greater than the Technical Specifi-cations limit of 125 x 106 lb/h.

Core differential pressure (measured from D cold leg to the head vent) was 19.4 psi, which is below that predicted necessary for core lift.

SAFETY EFFECTS:

This test had no adverse effects on plant safety as it was performed per an approved procedure during hot shut-down and no safety limits were exceeded.

3.

T Low-Flow Trip Calibration PURPOSE:

To obtain the summed ~p voltages (flow indicators) required to calibrate the low-flow trip units for all expected primary coolant pump configurations.

Also, to calculate the low flow pretrip and trip set points using the data obtained.

VI-4

RESULTS:

The desired set of data was obtained and calculations accomplished.

SAFETY EFFECTS:

This test was performed during hot shutdown using an approved procedure which required no abnormal valving or switching.

4.

T Test of CV-0734 and CV-0735 PURPOSE:

To determine the flow control adequacy of the feed-water regulating valves bypass control valves (CV-0734 and cv-0735).

RESULTS:

The test indicated that the valves would not adequately control flow in the desired range.

Dynamic response was slightly unstable.

SAFETY EFFECTS:

The test was performed using an approved proce-dure and all safety-related operating parameters were kept within limit.

5.

T Hydrostatic Pressure Test of the Suction Piping on the Safety Injection Pumps PURPOSE:

This te'st was conducted to detect any leakage from the suction piping of the containment spray, low-pressure safety injection and high-pressure safety injection pumps to fulfill the requirements of Section 4.5.3 of the Technical Specifications.

It was also conducted to determine whether or not it was desirable to conduct this test during plant operation.

VI-5

RESULTS:

The test demonstrated system integrity and has since been changed to an annual Technical Specifications test.

SAFETY EFFECTS:

The test was conducted in such a manner that all safety-related equipment was available for use during the test, so plant safety was not affected.

6.

T CRDM Position Indication, Limit Switch Operation PURPOSE:

This test was performed to exercise and check the primary and secondary position indicators. Also, to verify the proper limit switch operation.

The procedure was used after the seal failure on CRDM #21 to determine if other CRDMs were affected by the leakage.

RESULTS:

Two of the CRDMs showed inconsistent secondary to primary indication comparisons.

The two motors were subse-quently repaired.

SAFETY EFFECTS:

Plant safety was not affected because the plant was in cold shutdown and acceptable boron concentration was maintained.

VI-6

VII.

REFUELING INFORMATION The following information is provided as a result of the NRC request dated July 1, 1975.

A.

Scheduled Date for Next Refueling Shutdown December 1975, based upon approval of the licensing submittal for an extended 45 effective full power days of operation.

B.

Scheduled Date for Restart Following Refueling February/March 1976.

C.

Will refueling or reswnption of operation thereafter require a Technical Specifications change or other license amendment?

Yes.

What in general will the Technical Specifications changes be?

A Technical Specifications change will be required to revise the linear heat rate limitations and a new ECCS analysis submittal will be necessary.

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associ-ated with the core reload (Ref 10 CFR, Section 50.59)?

If no such review has taken place, when is it scheduled?

VII-1

D.

Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting Information November 1, 1975.

E.

Important licensing considerations associated with refueling, eg, new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

Core reload will encompass a new fuel supplier as well as new fuel design, without any significant mechanical design changes, but with prepressurized fuel and fixed poison rods.

VII-2

VIII.

RADIOACTIVE EFFLUENT RELEASES Calculated off-site doses are not presented in this report since, per Technical Specification 6.6g(4), levels of radioactive materials in environmental media due to plant origin do not indicate the likeli-hood of public exposure in excess of 5% of those that would result from continuous exposure to the concentration values listed in Appendix B, Table II (10 CFR 20).

However, dose estimates covering the entire year's effluents will be presented in the next Semiannual Report.

A.

LIQUID RADIOACTIVE EFFLUENTS

1. Liquid Release Summary During the period a total of 0.44 curie of liquid radioactive material, less tritium and dissolved noble gases, was released to Lake Michigan at an average concentration of 7.lE-09 µCi/ml.

Of the total, 0.117 curie was released through the modified liquid waste system and 0.326 curie was discharged as laundry waste.

Laundry waste also contained 0.09 curie of tritium.

The volume of waste from the modified liquid waste system totaled l.7E+07 liters while laundry waste totaled 2.3E+05 liters. Dilution water amounted to 6.2E+l0 liters.

Effluents from the modified radwaste system averaged 1.3% and 10.2% of Technical Specifications for the first and second quarters.

Laundry waste averaged 21% of allowable for the period.

VIII-1

Monthly releases, identified by isotope, and average concentra-tions for the modified liquid waste system are given in Table VIIIA-I(a).

Laundry effluents are given in Table VIIIA-II(a).

2.

Liquid Effluent Calculational Methods All liquid releases enter Lake Michigan through the cooling tower mixing basin outlet. Dilution water flow ranged from approximately 8,000 gpm (house service water pumps) to approxi-mately 75,000 gpm (house service water and cooling tower dilu-tion pumps).

Each liquid batch, radwaste system and laundry, was sampled, analyzed for radioactive content and subsequently discharged at a controlled rate to assure that permissible concentrations were not exceeded in the mixing basin, prior to dilution in Lake Michigan, during the time of discharge.

Each sample is analyzed by gamma spectrometry to identify as many of the component nuclides as possible.

Permissible concentrations in the discharge mixing basin are based on the most restric-tive or limiting MPC (for each identified isotope) as shown in Table II, Column 2, of 10 CFR 20.

Also, per 10 CFR 20, the unidentified portion of the monthly releases was assigned an MPC of 3 x 10-7 µCi/ml.

(3 x lo-6 µCi/ml when an SR-90 analysis is performed.)

In the case of the dissolved noble gases for which no MPC exists in Part 20, an MPC was calculated whereby continuous submersion in liquid of the calculated MPC value results in the limiting whole body dose.

VIII-2

B.

GASEOUS RADIOACTIVE RELEASES

1.

Gaseous Effluent Releases A total of 747 curies of noble gases were released during the period.

The release was 0.0003% of the annual average limit.

Halogen releases totaled 0.35 curie or 1.4% of the annual limit.

Of this, 0.34 curie was released during the month of June due to a CRDM seal failure.

Iodine-131 measurements in milk taken after this release are presented in Section IX.d.

Particulate releases totaled 5.13E-04 curies or 3.36E-05% of the annual limit.

2.

Effluent Calculational Methods Table VIIIB-I(a) presents a summary of the atmospheric releases, by month, for the period.

Inert gas releases were measured by sample analysis of each tank released.

Particulate and halogen releases were determined by weekly analysis of the continuous stack sample monitoring system.

The particulate and charcoal filters collect stack effluent continuously at a rate of ap-proximately four cubic feet per minute.

Determination of re-lease rates in this manner assumes radioactivity is continuously and uniformly being deposited throughout the week on the fil-ters and, hence, a decay correction to the time of analysis is applied, depending on the half-life of the nuclide observed.

The net unidentified beta activity (ie, gross beta activity minus the identified beta emitting isotopes) is not corrected for continuous deposition and decay due to the lack of a known half-life. This method of analysis is conservative as it assumes an infinite half-life.

VIII-3

C.

SOLID WASTE A total of 114 curies of mixed fission and activation products were shipped off site during the period.

At the end of the per-iod, 150 curies (38 cf) of high level waste and 4.04 curies (1,590 cf) of low level waste was stored on site.

A sU!ilmary of all off-site shipments is contained in Table VIIIC-I(a).

VIII-4

TABLE VIII-A - I(a)

Consumers Power Company Palisades Nuclear Plant, Docket No 50-255 Liquid Radioactive Effluents - Modified Liquid Waste System

~ Janua:;:;y:

Februar;i:

March 1st g,uarter ApriL Ma;i:

June 2nd 9,uarter Six Month Total Total Radioactivity Released (Except Tritium, Dissolved Noble Gases and Alpha)

Curies 2.44E-03 l.19E-03 6.78E-02 7.14E-02 5.66E-03 6.43E-03 3.40E-02 4.61E-02 l.17E-Ol Volume of Waste Discharged Liters 4.91E+05 l.63E+o6 1.04E+o6 3.l6E+o6 4.56E+o6 7.81E+o6 l.61E+o6 1.40E+07

1. 72E+07 Average Concentration of Waste Prior to Release (Except Tritium, Dissolved Noble Gases and Alpha)

µCi/ml 4.97E-o6 7.30E-07 6.52E-05 2.26E-05 1.24E-06 8.23E-07 2.llE-05 3.29E-o6 6.80E-o6 Volume of Circulating Discharge Water Liters l.llE+lO l.04E+l0 l.19E+l0 3.34E+l0 8.18E+09 9.96E+09 l.o6E+10 2.87E+l0 6.21E+l0 Average Concentration Released (Except Tritium, Dissolved Gases and Alpha)

µCi/ml 2.20E-10 3.74E-ll 3-59E-09 l.16E-09 6.92E-10 6.45E-10 3.21E-09 l.61E-09 l.88E-09 Percent of Technical Specifications "lo l.33E+OO l.02E+Ol Tritium Released - MPC *.01 Curies l.89E+OO 8.59E-01 l.58E+OO 4.33E+OO 3.74E-Ol 2.32E+o0 4.28E-01 3.12E+OO 7.45E+OO Average Tritium Concentration Released

µCi/ml l.69E-07 2.70E-08 8.36E-08 7.0lE-08 4.57E-08 2.32E-07 4.04E-08 l.09E-07 l.20E-07 Isotopes Curies 57co 2.36E-04 2.36E-04 2.36E-04 5lcr 3.61E-04 3.61E-04 3.61E-04 58co 3.98E-04 4.00E-o6 9.00E-03 9.41E-03 2.51E-04 8.28E-04 9.o6E-04 l.99E-03 1.14E-02 54Mn 2.77E-04 6.93E-03 7.20E-03 6.14E-04

1. 73E-03 2.34E-03 9.54E-03 65Zn 3.36E-04 3.36E-04 3.36E-04 131I 3.50E l.57E-03 7.00E-04 5.77E-03 5-77E-07 132I 5.90E-05 5.90E-05 5.90E-05 134cs l.60E-04 l.96E-03 2.12E-03 2.50E-05 2.50E-05 2.15E-03 133I l.27E-03

1. 76E-04 L45E-03 L45E-03 137cs 3.26E-04 6.22E-03 6.55E-03 8.00E-05 L99E-04 2.79E-04 6,83E-03 135I l.50E-04

1. 50E-04 l.50E-04 95Nb 5.40E-05 5.40E-05 5.40E-05 59Fe 1.00E-04 1.00E-04 l.OOE-04 6oco 4.llE-04 5.00E-06 l.80E-02 1.84E-02 4.35E-04 3.15E-03 4.77E-03 8.36E-03 2.68E-02 63Ni 4.49E-04 1.14E-03 2.46E-02 2.62E-02 2.55E-02

2. 55E-02 5.17E-02 Net Unidentified Beta 4.23E-04 3.70E-05 5.90E-05 5.19E-04 1.82E-04 1.82E-04 7.0lE-04 Dissolved Noble Gases - 133xe - 3 x 10-9 l.94E-03

1. 94E-03 l.94E-03 Percent of Total Identified (Except Tritium, Dissolved Gases and Alpha) 83

,,.95

>95

,,.95

.95

>95

,,.95

>95

TABLE VIII-A - II(a)

Consumers Power Company Palisades Nuclear Plant, Docket.No 50-255 Liquid Radioactiv~ Effluents - Laundry System Drains Units Januar;;:

Februar.y:

March AJ2ril Ma;;:

June Six Month Total Total Radioactivity Released (Including Tritium)

Curies 2.UE-02 4.34E-02 7.07E-02 5.50E-02 5.52E-02 8.02E-02 3.26E-Ol Volume of Waste Discharged Liters 2.87E+04 6.71E+04 7.95E+04 l.93E+04 l.o6E+04 2.07E+o4 2.26E+05 Average Concentration of Waste Prior

µCi/ml to Release 7.35E-04 6.47E-04 8.89E-04 2.85E-03 5.21E-03 3.87E-03 l.44E-03 Volume of Circulating Discharge Water Liters l.llE+lO 1.04E+l0 l.19E+l0 8.18E+09 9.96E+o9 l.o6E+l0 6.21E... 10 Average Concentration Released

µCi/ml l.90E-09 4.17E-09 5.94E-09 6.72E-09 5.54E-09 7-57E-09 5.25E-09 Percent of Technical Specifications 7.60E+Ol 5.44E+OO l.50E+Ol 2.69E+Ol 2.22E+Ol 3.03E+Ol 2.lOE+Ol Isotopes Curies 57co l.12E-05 9.lOE-05 l.45E-04 9.00E-05 4.00E-05 3-77E-04 51Cr 2.lOE-04 4.73E-04 9.20E-05 7-75E-04 58Co 2.25E-03 5.38E-03 6.0lE-03 3.00E-03 2.40E-04 1.47E-03 l.84E-02 54Mn 7.41E-04 3.80E-03

. 4.17E-03 2.45E-03 l.70E-04 l.35E-03 l.27E-02 65Zn 7.30E-05 4.70E-05 l.20E-04 131I 8.54E-04 2.76E-03 l.44E-02 1.80E-02 133I

1. 74E-04 7.60E-04

9.34E-o4 134cs 9-77E-04 l.20E-03 l.56E-03 7.53E-04 1.60E-04 8.00E-04 5.45E-03 136cs l.OOE-05 3.60E-04 3.70E-04 137cs 2.85E-03 3.54E-03 4.89E-03 2.24E-03 4.90E-04 2.18E-03 l.62E-02 133xe 1.02E-02 6.07E-03 2.95E-03 l.92E-02 95zr 2.40E-05 2.40E-05 133Mxe 2.69E-04 3.63E-03 3.90E-03 95Nb 2.40E-05 3.lOE-05 3.80E-05 9.30E-05 135xe 2.66E-04 3.00E-05

'2.96E-04 59Fe 9.00E-o6 4.50E-05 3.50E-05 7.50E-05 5.00E-05 2.14E-04 6oco l.37E-03 6.88E-03 l.03E-02 6.llE-03 3.40E-04 3.34E-03 2.83E-02 63Ni 6.91E-03 l.32E-02 3.26E-02 6.52E-03 9.00E-04 l.81E-02 7.82E-02 Net Unidentified Beta l.61E-03 3.07E-03 i.62E-03 6.24E-03 l.99E-02 3.25E-02 3H 4.20E-03 5.72E-03 9.19E-03 l.57E-02 4.41E-02 1.08E-02 8.97E-02 Percent of Total Identified 92 93

=-95 89

... 95 75 90 VIII-6 *

_J

TABLE VIII-B - I(a)

Consumers Power Company Palisades Nuclear Plant, Docket No 50-255 Atmospheric Radioactive Effluents Units Janua!::£ Februa!:iz'.

March 1st Quarter A~ril Ma;y June 2nd ~uarter Six Month Total Total Noble Gases Curies 6.66E-04 6.66E-04 5.90E-01 3.83E+Ol 7.07E+02 7.47E+02 7.47E+02 Total Halogens 4.05E-o6 4.05E-o6 7.66E-03 3.05E-03 3.41E-01 3.52E-01 3.52E-Ol Total Particulates (Beta and Gamma}

8.51E-05 1.04E-04 l.04E-05 l.99E-04 4.00E-05 1.42E-04 l.32E-04 3.14E-o4 5.13E-04 Percent of Applicable Limits

"/o Noble Gases l.66E-07 5.71E-08 l.90E-04 9.54E-03 1.82E-Ol 6.33E-02 3.18E-04 Halogens l.o6E-04 3.64E-05 l.34E-Ol 6.94E-02 8.08E+OO 2.73E+OO l.37E+OO Particulates 3.55E-03 3.45E-03 8.72E-04 2.60E-03 3.60E-03 l.63E-03 7.24E-03 4.l2E-03 3.36E-05 Isotopic Releases Curies Noble Gases 133xe 6.66E-04 6.66E-04 5.02E-Ol 3.82E+ol 7.07E+o2 7.46E+02 7.46E+02 133Mxe 1.62E-02 8.68E-03 2.49E-02 2.49E-02 l35xe 6.84E-02 4.17E-02 7.68E-02 1.87E-Ol 1.87E-Ol 41Ar 4.09E-04 4.09E-04 4.09E-04 85Kr 2.l?E-03 2.09E-04 3.20E-Ol 3.22E-Ol 3.22E-Ol 8~

2.32E-04 1.20E-04 6.08E-04 9.60E-04 9.60E-04 88Kr 5.55E-04 5-55E-04 5.55E-04

. Halogens 131!

4.05E-o6 4.05E-o6 4.91E-03 2.65E-03 2.99E-Ol 3.07E-Ol 3.0?E-01 1331 2.59E-03 3.98E-04 3-97E-02 4.27E-02 4.27E-02 1351 l.45E-04 l.43E-03 l.58E-03 l.58E-03 132!

l.15E-05 5.62E-04 5.74E-04 5.74E-04 Particulates 54Mn l.61E-o6 l.43E-05 l.59E-05 4.39E-07 6.82E-o6 7.26E-o6 2.32E-05 58Co l.62E-o6 1.62E-o6 1.23E-04 l.03E-05 l.33E-04 l.35E-04 6oco 4.05E-o6 3.80E-05 4.20E-05 l.97E-o6 7.12E-o6 9.09E-ct 5.llE-05 134cs 2.05E-o6 l.19E-o6 3.24E-o6 4.62E-o6 4.62E-o6 7.86E-o6 l37cs

3. 79E-05 2.o6E-05 3-79E-07 5.89E-05 l.85E-05 l.85E-05

7. 74E-05 95zr 6.70E-o6

6. 70E-o6 6.70E-o6 Net Unidentified Beta 3-79E-05 3.02E-05 9.99E-06 7.81E-05 4.00E-05 1.67E-05 7.76E-05 l.34E-04 2.12E-04 Alpha 3.04E-07 l.77E-07.

2.0lE-07 6.82E-07 2.22E-07 2.21E-07 5.02E-07 9.45E-07 l.63E-o6

Date/Number Shij?meri.ts 75001S 1/ 3/75 75002S 1/ 3/75 75003s 1/ 6/75 75004S 1/ 7/75 75005s 1/10/75 75006s 1/15/75 75007s 2/11/75 75008s 2/17/75 75009s 2/18/75 75010S 2/24)75 75011s 2/28/75 75012s 3/i8/75 75013S 3/20/75 TABLE VIIIC-I(a)

PALISADES PLANT Solid Radioactive Waste Shipments January 1, 1975 to June 30, 1975 To License #

Expiration Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Morehead, KY 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78 Atcor-Morehead, KY 31-11640-01, 12/31/78 Atcor-Sheffield, IL 31-11640-01, 12/31/78

NECO Sheffield, IL 13-10042-1 NECO, Sheffield, IL 13-10042-1 Description of Contents Ten 50 Cu Ft Liners of Solidified Radwaste One LL-50-100 Lead Cask With Liner of High Level Waste Ten 50 Cu Ft Liners of Solidified Rad.waste Ten 50 Cu Ft Liners of Solidified Radwaste Ten 50 Cu Ft Liners Solidified Radwaste Ten 50 Cu Ft Liners of Solidified Radwaste Ten 50 Cu Ft Liners of Solidified Radwaste Ten 50 Cu Ft Liners of Solidified Radwaste Ten 50 Cu Ft Liners of Solidified Radwaste One LL-50-100 Lead Cask With Liner of High Level Waste Ten 50 Cu Ft Liners of Solidified Radwaste 119 - 4 Cu Ft Boxes 49 - 7.5 Cu Ft Drums 15 - 10 Cu Ft Liners Ten 50 Cu Ft Liners of Solidified Radwaste

NECO is Nuclear Engineering Company.

VIII-8 Total Curies Total Cu Ft 2.36E-Ol Ci 5E+02 Cu Ft 2.89E+Ol Ci 1E+02 Cu Ft 9.8E-02 Ci 5E+02 Cu Ft 9.6E-02 Ci 5E+02 Cu Ft 2.38E-Ol.Ci 5E+02 Cu Ft l.87E-Ol Ci 5E+02 Cu Ft 2.95E-Ol Ci 5E+02 Cu Ft 2.84E-Ol Ci 5E+02 Cu Ft 2.70E-Ol Ci 5E+02 Cu Ft l.31E+Ol Ci 1E+02 Cu Ft 7.6lE-Ol Ci 5E+02 Cu Ft 4.llE-01 Ci 9.94E+02 Cu Ft 3.58E-Ol Ci 5.0E+02 Cu Ft

Date/Number Shipments 750014S 3/25/75 750015S 4/15/75 75016s 4/15/75 75017s 4/17/75 75018S 4/24/75 75019s 4/28/75 75020S 4/29/75 75021S 4/29/75 75022S 5/ 2/75 75023S 5/ 6/15 75024S 5/13/75 75025s 5/15/75 TABLE VIIIC-I(a) (Contd)

To License #

Expiration NECO, Sheffield, IL 13-10042-1 NECO, Sheffield, IL 13-10042-1 CE, Windsor, CT 06-00217-06 NECO, Sheffield, IL 13-10042-1 NECO, Sheffield, IL 13-10042-1 NECO, Morehead, KY 16-NSF-l Mich Public Health 21-05199-03 NRC NECO, Morehead, KY 16-NSF-l NECO, Morehead, KY 16-NSF-l NECO, Sheffield, IL 31-10042-1 NECO, Sheffield, IL 31-10042-1 Description of Contents Ten 50 Cu Ft Liners of Solidified Radwaste 11 DOT 7A, 50 Cu Ft Liners With Solidified Evaporator Concentrates 3 Boxes Eddy Current Testing Equipment 11 DOT 7A, 50 Cu Ft Liners With Solidified Evaporator Concentrates 13 DOT 7A, 50 Cu Ft Liners With Solidified Evaporator Concentrates One L-3-181 Cask With 90 Cu Ft Spent Resin Liquid and Gas Samples Liquid and Gas Samples One DOT Cask Containing Dewatered Spent Resin One L-3-181 Cask Con-taining Dewatered Spent Resin 12 DOT 7A, 50 Cu Ft Liners Containing Solidified Evaporator Concentrates 12 DOT 7A, 50 Cu Ft Liners Containing Solidified Evaporator Concentrates VIII-9 Total Curies Total. Cu Ft 6.66E-02 Ci 5.0E+02 Cu Ft 2.44E-Ol Ci 5.5E+02 Cu Ft

<l.OE-03 Ci

5. OE+Ol Cu Ft l.66E-Ol Ci 5.5E+02 Cu Ft 2.06E-Ol Ci 6.5E+02 Cu Ft 7.53E+OO Ci 9.0E+o2 Cu Ft 2.lE-05 Ci

<l Cu Ft*

1.lE-05 Ci

<l Cu Ft l.36E+Ol Ci 4.2E+Ol Cu Ft 3.76E+Ol Ci 9.0E+Ol Cu Ft l.2E-01 Ci 6.0E+02 Cu Ft 7.0E-02 Ci 6.0E+02 Cu Ft

Date/Number Shipments 75026s 5/20/75 75027S 5/28/75 75028S 5/29/75 75029s 5/31/75 75030S 6/ 3/75 75031S 6/11/75 75032S 6/19/75 75033S 6/18/75 75034s 6/19/75 75035s 6/26/75 TABLE VIIIC-I(a) (Contd)

To License #

Expiration NECO, Sheffield, IL 31-10042-1 Amer Air Filter Shelbyville, KY NECO, Morehead, KY 16-NSF-l CE, Windsor, CT 06-00211-06 NECO, Sheffield, IL 31-10042-1 NECO, Sheffield; IL 31-10042-1 NECO, Morehead, KY 16-NSF-l NECO, Morehead, KY 16-NSF-l NECO, Sheffield, IL 31-10042-1 NECO, Sheffield, IL 31-10042-1 Description of Contents 11 DOT 7A, 50 Cu Ft Liners Containing Solid-ified Evaporator Con-centrates & 30 2 1x2'x.5' Prefilter Elements 30 Carbon Trays One L-3-181 Cask Con-taining Dewatered Spent Resin 200 ml Sample of Steam Generator Crud & Liquid 11 DOT 7A, 50 Cu Ft Liners Containing Solid-ified Evaporator Con-centrates 11 DOT 7A, 50 Cu Ft Liners Containing Solidified Evaporator Concentrates 135 - 55 Gal DOT Drums

& 4 - 10 Cu Ft Liners With Solidified Radwaste DOT Casks Containing Dewatered Spent Resin 11 DOT 7A, 50 Cu Ft Liners Containing Solidified Evaporator Concentrates 11 DOT 7A, 50 Cu Ft Liners Containing Solidified Evaporator Concentrates VIII-10 Total Curies Total Cu Ft

1. 3E-Ol Ci 6.1E+02 Cu Ft

<l.OE-06 Ci l.28E+Ol Ci 9.5E+Ol Cu Ft l.OE-06 Ci 7.0E-02 Ci 5.5E+02 Cu Ft l.5E-Ol Ci 5.5E+02 Cu Ft 4.55E-Ol Ci

1. 05E+03 Cu Ft 8.lE+OO Ci

1. 50E+02 Cu Ft 5.7E-02 Ci 5.5E+02 Cu Ft 5.8E-02 Ci 5.5E+o2 Cu Ft

IX.

ENVIRONMENTAL MONITORING A.

RADIOLOGICAL ENVIRONMENTAL MONITORING

1.

Introduction The data obtained by analysis of samples, taken during the re-porting period, are evaluated in this section to determine if there has been any increase in radioactivity levels in the environment which can be attributed to operation of the plant.

Comparisons are made with the remote reference locations for given sample types since the absolute levels of radioactivity in the environment vary as a function of time, meteorological conditions and nuclear device testing.

Comparisons with pre-operational data and predicted levels, based on effluent data, are also included.

2.

Discussion and Interpretation of Results

a.

Air Gross beta activity levels in surface air particulate samples are shown in Figure IX A-1.

Values shown are monthly averages for (a) station ST (site), (b) inner ring stations 2-9 (three to seven miles away), and (c) reference stations 10-12 (20-50 miles).

As can be seen by Figure IX A-1, there is no significant difference between the site, inner ring and background stations.

The average values of gross beta activity for the site, inner ring and background stations are also consistent with preoperational levels.

IX-1

The analytical sensitivity for air particulate samples is 0.01 pCi/m3 while the average site boundary concentration, based on effluent releases and annual meteorology, is cal-culated to be l.5E-04 pCi/m3.

The calculated values are small compared to the analytical sensitivity obtainable in the surveillance program and normal background levels.

On this basis, the conclusion of no difference between the re-mote, inner ring and site air sampling stations was expected.

During the period, only two air samples showed detectable concentrations of I-131.

During the week of April 6 through April 13, the sample from location No 2 had an I-131 concentration of 0.04 +/- 0.03 pCi/m3 and location No 4 a concentration of 0.25 +/- 0.23 pCi/m3.

Both loca-tions had low volumes for the week, location No 2 with 1,620 cubic feet and location No 4 with 225 cubic feet.

Normal volumes range from 8,000 to 11,000 cubic feet, de-pending on the dust loading on the particulate filter.

Additionally, the average site boundary I-131 concentra-tion for the month of April is calculated to be 8.7E-04 pCi/m3.

This value is well below the two off-site mea-sured concentrations indicating that the two measured values are statistically not real.

IX-2

E u 0.

z H

0

~

I I-w c::r:

0:::

I-z LLI u z 0 u J. 0 0.9 o.8 0.7 o.6 0.5 0.4 0.3 0.2

o. lQ.

0.09 0.08 0.07 0.06 0.05 0.04 0.03 0.02 0.01 A

~ L/

W""

JAN FEB MAR

It FIGURE IX A-l PALISADES PLANT MONTHLY AVERAGE RADIOACTIVITY CONCENTRATION IN AIR

--~-

~

~\\_

~

I i

APR MAY JUN JUL AUG SEP e SITE STATION 0 INNER RING STATIONS

BACKGROUND STATIONS OCT NOV DEC

Problems associated with the analysis of the carbon fil-

ter, as described in the last Semiannual Report, appear to have been eliminated by spectra examination to determine if a peak actually exists in the 0.36 MeV region.

b.

Lake Water Monthly composites of intake, discharge and South Haven water are measured for gross beta radioactivity.

The results of the gross beta analysis are given in Figure IX A-2.

The intake and discharge samples for April showed abnor-mally high gross beta activity (304 pCi/l and 103 pCi/l, respectively).

Subsequent isotopic analysis showed signif-icant concentrations of I-131, Cs-134 and Cs-137.

Results are presented in Table IX A-1.

The samples were collected over the period of April 20 through 27, not the entire month as normally done, due to the lack of adequate sample con-tainers.

Subsequent investigation concluded that the activity was the result of cross contamination.

it was determined that only 0.006 milliliter of primary coolant introduced into the sample would result in the reported activity.

This amount could have been introduced from contaminated collection bottles or bottle caps, hands or a dirty pipette.

During the period of April 20 through 27, a total of 3.5 millicuries of I-131 were released which could not have resulted in the high activity detected in the samples.

Additionally, it was calculated that approxi-

mately 1,800 gallons of primary coolant would have to have IX-4

been lost to result in the sample activities.

The pri-mary coolant inventory for the period showed no such loss.

TABLE IX A-1 Isotopic Analysis of Lake Water Samples With Gross Beta Activity >10 pCi/l pCi/l Intake - 4/75 Discharge - 4/75 I-131 1,550 +/- 150 1,450 +/- 145 Cs-134 145 +/- 15 90 +/-

9 Cs-137 328 +/- 33 236 +

24 Zn-65

<15

<15 Mn-54

<10

<9 Co-58

<6

<6 Co-60

<6

<6 Fe-59

<6

<6 Sr-90

<3

<3 With the.exception of the April intake and discharge samples, all lake water samples are consistent with pre-operational levels of 5 to 15 pCi/l.

Figure IX A-3 contains tritium concentrations.measured at the plant's intake and discharge and the South Haven Municipal intake.

All values are consistent with preoper-ational data, which ranged from about 270 pCi/l to about 850 pCi/l.

IX-5

00 90 80 70 60

~o 40; 30 u 0.

~Q__:

I z H

0 I-0\\

~:

I-z LLJ.

U*

z 10 0 u i

8

- 7 6"

~

5

~

"\\. ~) i--

t"'I....

~

I\\.

3

/

',V/

\\7 2

JAN FEB MAR t

I

\\

~ '.:.

\\ \\

\\

1 r-... -1\\.

\\

FIGURE IX A-2 PALISADES PLANT LAKE WATER GROSS BETA ACTIVITY

\\

\\_ _,, ~-

("\\

I

~ -\\ (;-

/ l\\

\\ y

~

: J APR MAY JUN JUL O INTAKE e DISCHARGE

6. SOUTH HAVEN-RAW A SOUTH HAVEN-TREATED AUG SEP OCT NOV DEC

c.

Well Water Well water samples from the site, Covert Township Park and and the Palisades State Park are analyzed monthly for gross beta activity.

Results are plotted in Figure IX A-4 and are consistent with preoperational levels of 5 to 21 pCi/l.

d.

Milk Cs-137, BaLa-140 and I-131 are measured quarterly by specific nuclide analysis; analysis for Sr-90 is performed monthly.

The results of these analyses are given in Table IX A-2.

In addition, monthly samples are analyzed by gamma spectrometry for the same three nuclides.

None of the latter analyses have shown concentrations greater than the 30 pCi/l detection limit.

Preoperational analyses ranged from 2 to 42 pCi/l for Cs-137 and 4 to 22 pCi/l for Sr-90.

The preoperational detection limits for BaLa-140 and I-131 were 'both 30 pCi/l and all samples were below this de*tec-tion limit.

TABLE IX A-2 Monthly Milk Analysis (pCi/l)

BaLa-140 Cs-137 I-131 Location 1st 2nd 1st 2nd 1st 2nd HS

<2

<2 9.8 16.5

<0.3 SDF

<3

<2 7.3 4.8 0.5 SD

<2

1. 5 9.9 o.4 KZ

<2

<2 12.4 6.4

~0.3 IX-7

u a.

I z 0 -I-

~

H I-z I

uJ

<X>

u z 0 u

~

I-c::

I-104 9

8 7_

6 FIGURE IX A-3 PALI SADES PLANT LAKE WATER TRITIUM CONCENTRATION 0 INTAKE e DISCHARGE SOUTH HAVEN-TREATED r-----.------,-----:-----.------,------.-------.-----r-----r-----,----.-----.----~*~**=--~**'--=*****~--=***=-~*~* --

* --+----+----+-----4-----4-----+------'

+-----~-----+--*--***--+--------*--.... -*+ *-------

5

+-----*** +---*-----

I

+*.., *--.. --* -+** *--* -..

I*

+

I 4 r------.. ----*----*- + ---*.... +

- - - --**+-****

+--** *-**-** ***-----*--+ *-.

3 2 1-----t------t-----t- ---+-------+--~----+--

~----+-----i--.. ---+-*-****-**------<--*---+------+--

--*-- --------+------+----+--------

1031-----1------t-----t-

****--+----~~-=~:.-=+/-***=~*~ -*-*-** +---+------

9 8

7 6

5 4

3 2

i-----+-----*-+--

-******r

. I

-+--

I

- --+-* -. -** - -+---** -*---*+*- __ _J

-+..

--* --*+-*----**-+--*---***--*+--*-------

+--*--+----*---4-----*----+---* *-- ***----*--*.

...i *-

-+*--*--

I 1~---~----1---~----+-----+------+-----+----*+. **--+----+-----+----~

102~~~~~1-.. _l __ L ____ _

NOV DEC JAN FEB MAR APR MAY JUN JUL AUG SEP OCT

H

~

I u

\\0

c.

10.0 9.0 a.oi

].O 6.0 5.0 4.0 3.0.

2.0 l~O.

0.9

-O:S:

0.7 o.6 0.5 o.4 0.3 0.2

0. l

~

... ~

..... "79"

..,\\

" I \\

-r

\\

I -n--

\\

I.

J

\\ I v JAN FEB MAR V\\

\\

/ v APR FIGURE IX A-4 WELL WATER GROSS BETA ACTIVITY

,,,/0

/

\\/,

I r\\ l v

~

v

~

MAY JUN JUL AUG SEP O SITE e _UAT~_l'AR(S_

TOWNSHIP PARK OCT NOV DEC

Monthly Sr-90 Analysis (pCi/l)

Location Nov Dec Jan Feb Mar Apr May June HS SDF SD KZ Location JW HS SD SDF KZ 3.2 5.2 11.8 11.8 4.8 5.3 2.8 20.0 4.4 5.2 3.5 10.6 4.1 7.6 9.2 8.1 4.5 4.o 6.4 8.5 3.8 8.1 8.2 6.o 4.4 4.3 6.9 3.1 4.9 6.o 1.2 7.0 During the period of June 20 through July 7, 1975, 0.305 9urie of Iodine-131*was released from the stack due to a control rod drive seal leak. It was decided to collect an additional series of milk samples to monitor the effects of this release in the environment.

Results of these samples in pCi/l are as follows:

6/26/75 6/28/75 7 /9/75 7 /18/75 7 /24/75 11 +/- 1 14 + 1 5.0 +/- o.4 o.6 + 0.3 o.4 +/- 0.1

<0.3 o.4 +/- 0.1 0.3 +/- 0.1

<0.2

<0.3 0.3 +/- 0.1 0.3 +/- 0.2 1.2 + 0.2

<0.2

<0.3 o.4 +/- 0.1 0.5 +/- 0.1 0.3 +/- 0.2 0.2 +/- 0.1

<0.3 0.7 + 0.1 0.1 + 0.1

<0.2

<0.2 Location JW is approximately 3-1/4 miles east of the site.

The milk from the one cow is consumed entirely by the owners, an elderly couple.

Assuming a consumption rate of 1 liter per day at the measured concentrations would re-sult in a total of 155 picocuries being ingested.

Use of a 1,890 mRem/~Ci ingestion dose commitment factor (WASH 1209) gives a thyroid dose of 0.29 millirem.

Even though no infant resides at this location, the hypothetical dose to the nonexistent infant would be 2.65 millirem using the methodology of Regulatory Guide 1.42.

IX-10

e.

Gamma Dose Results from gamma dose measurements are given in the table below.

Dose values given are doses received in are (stored in a lead shield while the other dos,imeters) are in the field.

The control dosimeters are shipped to and from the laboratory with the field dosimeters.

Gamma Dose (mR/Month)

Month Site Bounda!X Inner Ring Stations Reference Stations January 2.7 + 0.9 3.1 +/- o.4 2.5 +/- 0.2 February 2.8 +/- 2.8

. 2. 2 +/- 0.9 3.6 +/- 3.7

March 2.8 +/- o.8 4.2 +/- 2.7 2.4 +/- 0.1 April 3.5 +/- 3.3 3.2 + 2.9

1. 7 + - 0.5 May 2.2 +/- 1.4 4.o +/- 3.1 3.1 + 0.9 June 4.o +/- 0.5 6.4 + 5.5

.3.5 + 0.3 The net values reported are not meant to be a measurement of ambient dose levels.

Control dosimeters do not receive zero dose while stored in the lead cave.

The control dosi-meter's dose (transit plus "lead cave") is used as a base-line for the comparison of the field dosimeters.

After subtraction of this baseline value, the monthly dose at the site, inner ring and reference stations is compared, at the 95% confidence level using the standard F and t tests.

For the reporting period, no significant differences were noted between the sa.mpl.ing locations.

Several dosimeters had unusually high readings during the month of June.

These dosimeters were excluded from the IX-11

_J

Gross Beta Th-228 Ra-226 Cs-137 Cs-134 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 I-131 BaLa-140 K-40 statistical comparison until the analytical contractor can check the *inherent backgrounds to determine if this was the cause of the high readings.

f.

Aquatic Biota, Sediment and Crops Table.IX A-3 contains the results of analysis of sediment and fruit.

These levels are consistent with preoperational levels as reported in the Palisades Plant "Special Report No 4, Environmental Impact of Plant Operation Up to July 1, 1972."

TABLE IXA-"3 Sediment and Crops pCi/gm Sediment N Site s Site Boundary. Dischare;*e Bounda~

13.0 13.2 15.5 0.21 0.11 0.14 0.14 0.17 0.14 0.14 0.08 0.07

<0.04

<0.02

<0.03

<0.02

<0.08

<0.05

<0.03

<0.02

<0.05

<0.02

<O.l

<0.05

<0.07

<0.04

<0.03

<0.02

<0~03

<0.02

<0.1

<0.05

<0.05 9.0 8.6 11.7 IX-12 South Haven 26.3 0.96 0.57 0.07

<0.03

<0.06

<0.03

<0.07

<0~06

<0.03

<0.02

<0.08 13.6 Strawberries JS 1.2

<0.02

<0.04

<0.02

<0.05

<0.04

<0.02

<0.03

<0.04 2.1

g.

Sampling and Analysis Summary Table IX A-4 summarizes the radiological sampling program.

The number of samples collected, type of analysis and frequency of analysis for the different sampling media are given.

Table IX A-5 gives the high, low and average concentrations for the highest average sampling locations.

3.

Conclusions Available data have been examined to determine any increase in radioactivity in the environment that can be attributed to the operation of the Palisades Nuclear Power Station.

Except for the small I-131 release mentioned above, there is no evidence of any increases in air particulates, lake water, well water, sediment, crop and/or gamma dose.

IX-13

Medium Description Air Continuous at Approximately l Cf'm Lake Water l Gallon Composite H

I f-1 +

Well Water l Gallon Grab Milk l Gallon Grab Gamma Dose Continuous Sediment Grab Crops Grab TABLE IX A-4 Consumers Power Company Palisades Nuclear Plant January l, 1975 to June 30, 1975 Sampling and Analysis Summary Number of Samples Location Collected All 310 Intake, Discharge, 24 South Haven Site, ST, TP

18.

HS, SDF' SD, KZ 24 All 124 Site, N & S Site 4

Bdry, 5 Miles N

JS l

Type of Analysis Gross Beta, I-131 Gross Beta, Gross

Gamma, Tri ti um, Sr-90, Cs-137 Gross Beta Sr-90, Cs-137, I-131, BaLa-140 TLD Dose Gross Beta,

Isotopic Gross Beta, Isotopic Frequency of Analysis Weekly Monthly Monthly Monthly Monthly As Sent As Sent

H I

I-'

\\Jl Medium Air Lake Water Well Water TLD Dose( 2)

Type of Anal;y:sis Gross Beta I-131 Gross Beta(l)

H-3 Gross Beta TABLE IX A-5 Consumers Power Company Palisades Nuclear Plant January 1, 1975 to June 30, 1975 High, Low and Average Concentrations for Highest Average Sampling Location Location High Low KZ 0.24 Ci/m3 0.03 pCi/m3 JS 0.25 pCi/m3

<0.02 pCi/m3 Discharge 6.0 pCi/l 3.6 pCi/l Discharge 1300 pCi/l 260 pCi/l State Park 11.8 pCi/l 3.4 pCi/l

7 19.6 2.0 mR (l)Excluding the April intake and discharge samples.

Average 3

0.11 pCi/m 5.2 pCi/l 668 pCi/l 5.8 pCi/l 7.9 mR (2)Locations utilizing new "low background" dosimeters are excluded due to lack of control dosimeters for transit dose.

B.

NONRADIOLOGICAL ENVIRONMENTAL MONITORING

1.

Introduction The nonradiological environmental monitoring program was con-tinued during the period January 1, 1975 to June 30, 1975 generally in accordance with Amendment 6 to Facility Operating License No DPR-20 and Change No 10 to the Technical Specifica-tions.

a.

Effluent Release - Technical Specifications Section 3.9 Nonradiological.. liquid effluents subject to Technical Specifications restrictions are limited to chlorine re-siduals, pH and temperature in cooling tower blowdown and associated releases to Lake Michigan.

This section de-scribes chlorination procedures and effects and blowdown and discharge characteristics during this reporting pe~iod.

(1)

Chlorination The following Technical Specifications require infor-mation describing chlorination procedures and chlorine concentrations.

Data are summarized in Table IX B-1.

3.9.6 Residual Chlorine into Lake Michigan After Chlorination Samples were taken at the cooling towers and mixing basin during and after chlorine injec-tion to determine chlorine decay before resum-ing blowdown.

Results of samples taken at each cooling tower and the mixing basin are summarized in Table IX B-1.

IX-16

Date Tech Spec !'lo 4-T 4-8 4-15 4-16 4-17 4-19 4-20 4-21 4-23 4-24 4-25 4-26 4-27 4-28 4-29 4-30 5-1 5-2 5-3 5-4 5-6 5-T 5"8 5-9 5-10 5-13 5-lli 5-15 5-16 5-lT 5-18 5-20 5-21 5-22 5-23 5-24 5-25 5-26 5-27 5-28 5-29 5-30 5-31 Simu.1taneous Blowdown

'Ind Cbl.orinati<>n 3.9.7 Nolle:(l)

Ditto NOTE:

See Page 2 for footnotes.

Total Time Cl in Circulating water ~stem

'!.9 (Mfu) 60<21 60 30 30 60 60 60 60 6o 6o 6o 60 60 70 60 6o 65 6o

'tilt:

Ci&*

~*'.

6o 60 60 60 6o 60 6o 6o 6o 60 6o 60 25 6o 45 60 30 52 6o 30 30 6o 6o Total Cl Compound Used 3.9.8 c (Gill) 495' 3*

.592,5 247.5 48 96 96 96 l'IA(7)

!'IA

!'IA NA NA.

lfA lfA lfA

!'IA liA II&

195 lSO m

1" 195 195 195 195 g6 g6 96 96 96 96 ll!l(T) 62.5 lo6.5 1<77.4 145.5 163.B 1112.5 150 75 150 150 161.5 Blowdown Rate 31~>d NI. (4)

Ditto TABLE IX B-1 Chlorination Circulating Water System Coolin!< Tower A Holdup Total Residual Cl

~

---L-

. 2

____i__

~ r

- lMinl Ppm) 0'5) 0

.q.o'6 ~

.oo

.40(61

.oo (6)

.35

.oo O

- Not Chlorinated -

0

.86 l.45

.95 0

l.10

.59

.1;2 0

0 0

o*

0 0

~

2.70 1.46 l.46

.66

.51

.61

.33

.63

.65

.77

.36

.45

.38

.41

15,;. -

.68

.44

.36 l.39

.58

.70

,59

.31

.30 l.67

.23

,55 1.31 1.22 l.42 l.16 1.90 2.Bo

.91*

l.J.8

.96

.80 l.09.

.63

.CJ7

.85

.93

.49

.75

.56.

.57

i..ao

.95 2.50

.60

.92

.68

.65

.57

.lio

.58

.41

.56

36

.35

.27

.47

.50

~.,,,...,"""**

"1.J.f l.29

.90 l.lT

.53 l.15 1.05 1.07

.92

.49

.38 1.55

.16

.25 1.90

.58 1.05 l.70

.85

.72

.82

.42

.90

.72

. 84

.Bl

.28

.29

.90

.13

.21

,73

.44

.48

.44

- Not Chlorinated -

.85 l.o6

.20 1.46 1.05 IX-17 2.10 1.40 l.02

.46 Mixilijl; ~*in Total Residual Chlorine 3.9.li f:ppmJ NA(7)

Ditto

.26

<.05

.07

.OS

<.05

!IA(7)

<.05

.oa

<.05

.08

<.05

<.05 Coolino: Tower B Total Residual Cl Blotniown

_1_

2

____i__

~

1&.l

. 70(6)

.40(6)

.35(6)

NA (4)

.oo 4.30

.00 4.10

.oo 3.60

- !'lot Chlorinated -

1.40 1.10

,95

.65

.95

.50

.90

.50 1.26

.16

.92

-~9

.72 liA(7)

.51

.Jl

.68

.!O

.21

.30..

.!J..

.:>.f

.65

,55

.52

.34

.69

.10

.47

-~

°'

L.30

.79 l.OT

.15

.76

.85 l.17 llA ('7)

.57

.68

.811

.28

.35

.50 l.~.,.

.ft

.so

.82

.70

.44

.93

.98

.75

.ii,

.25 0.70

.47

.CJ7

.10

.59

.41

.63 JIA(7)

.31

.34

.l9

.20

.30

4t

.~.*

.65

.* "6

.48

.26

.65

.70

.6o

.19

.20

- Not Chlorinated -

,23

.33

,59

.39

.86

.35

.49

l15 1.26

.73

.39

.55

- Not Chlorinated -

.94 1.38

.70

.82

.36

.30

- Jfot Chlorinated -

.90

.62 l.30 1.15

.96

.32 Ditto ft

~~--"'..

Holdup

~

n(5) 0 0

0 0

0 0*

0 0

b 0

0 0

0

i I

I 2

Total Time Cl Simultaneous Blowdown in Circul.ating Total Cl Date Cooling Tower A MiXiBS Basin Cooling Tower B Holdup Total Residual Cl Total Residual

,rotal Residual Cl Slowdown and Chlorination Water ~stem Cq~:12ound Used Tec6 Spec ilo 3,9,7 3.9.B c 3.9.

a Blowdown Rate 3.9.8 d (Gpm)

Time 3.9.'.8 e 1

2

---L_

Chlorine

__].__

2

__J__

Rate

~

3.2.i!i

~

3.2.8 d (Min)

(Gal)

(Min)

(Ppm)

(Ppm) 6-1 None(l) 60(2) 135<3>

NA(4) 0(5) 1.45(6) i.1ol6l

.42(6)

<. 05

.15

<.05 1.55(6 )

1.35(6 )

50(6) 6-2 Ditto 60 138.8 Ditto 0

75 1.50

.38

<.05

.84 1.15

.21.

6-3 60 150 0

.63

.96 1.60

<.05

.46

.75 l.22 6-4 60 150 0

LOO 1.35

.211

<.05

.44 l.10 1.6 6-5 60 150 0

.45 1.45

.28

<.05

.90 1.45

.16 6-6 60 150 0

1.1, 1.80

.15

<.05

.90 l.23

.24 6-7 60 150 0

1.30 1.65

.18

<,05

<.05

.70 1.22

.15 6-8 60 150 0

1.15 1.68

.47

<.05

.85 1.18

.21 6-9 50 125 0

.81 1.11

.72

<.05

.75

.93

.47 6-10 50 125 0

.82 1.33

.82

<.05

.57

.85

.39 6-11.

50 125 0

.Bo 1.29

.64

<.05

.36

.53

.21 6-12 54 135 0

2.o4 1.20

.63

<.05

.67

.73

.32 6-13 50 273 0

.60 l.o8

.6!

<.05

<.05 2.70 1.66 l.o4 6-14 50 125 0

.56

.81

.69

<.05

<.05 1.90 1.10

.89 6-15 50 125 0

1.58 1.27

.95

<.05

.31

.49

.39 6-1.6 50 125 0

.76 1.05

.44

<.05

<,05

.40

.60

.23 6-17 50 125 0

'3

-9'

.41

<.05

.38

.47

.17 6-18 40 100 0

.30

.54

.31

<.05

.20 32

.12 6-19 50 125 0

.47

.78

.60

<.05

.19

.28

.13 6-<ao 50 125 0

.73 1.28

.74

<.05

,39 58

.24 6-22 25 62.5 0

.93 1.34

.ea

<.05 Not ChlariDmted

6-23 25 62.5 0

.91 1.29

.73

<.05

- Not Chlorinated *

(l)Blcwdown from both towers is secured during chlorination. However, duril:ig the 11erlo4 Januaey l to June 30, 1975 a seemid, prerlous:cy-um.dentified, source of bl..ovdow......, di~d.

Mixing was occurring between the cooling tower water and the service water. A..tudy of this outfall is being done to detund.ne the f:Ja*"'14 ta aal.llllJAte the c~lm ot ilhlal'illp in the water* inadvertently relee*ed to Lake Michigan during chlorination.

(2)Time of chlorination is usually shared equally between the two towers; eg, on 4/7 Tower A was chlorinated for 30 minutes, as was Tover B, for a total of 60 ml.nutes.

(3)161. sodium hypachlorite.

<4lAccurate data are not available.

As mentioned in Note 1 above, mixing is occurring between cooling tower water and service water in the makeup basin and, consequently, a portion of the outfall over the wier should be considered as blowdown.

Th.is overflow is not currently monitored.

\\5)Because a portion of the cooling.tower blowdown was continuously discharged over the wier, no holdup time can be assumed to allow for chlorine decomposition. - It should be noted, however.

that only part of the chlorinated water was continuously discharged, while the remainder was held up to allow the chlorine to dissipate.

No data are available to describe the rate of now over the wier or its chlorine concentration.

(6)Measurements were taken near or after the co~letion of chlorination at 5-or 10-minute intervals.

(7)Data not available; measurements were not ~n on this date.

IX-18 (Gpm)

NA(4)

Ditto Holdup Time 1.2.8 e (Min) 0(5) 0 0

0 0

0

3.9.7 Time of' Simultaneous Blowdown and Chlorination

The blowdown is secured during each chlorination ot the cooling towers; however, during this semi-a.nilual period a second, previously unidentified, source of blowdown was recognized. It was deter-inined that mixing was occurring between circulat-ing cooling tower water and the service water in the makeup basin and therefore, a portion of the

~

outt.-i.1 over the weir should be considered as bl.owdown.

Adequ.e.te data are not yet available to describe the proportion of this discharge to the total blowdown flow; however, studies are under wa:y to determine this flow to calculate the resulting concentration of chlorine in the

water released to Lake Michigan during chlorina-tion.

3.9.8a Total Time Chlorine in Condenser Cooling System The total time, as recorded on Table IX B-1, corresponds to the total period of chlorine in-jection which is usually split equally between the two.towers. Prior to April 7, 1975 the plant was shut down and no chlorination took place.

3.9.8b Total Time Chlorine in Service Water System On June 18, 1975, beginning at 1445 hours0.0167 days 0.401 hours 0.00239 weeks 5.498225e-4 months and continuing for 15 minutes, a total of 3.3 gallons

IX-19

1440

<.05 Begin 2.2 Chlorination of 16% NaOCl was injected into the service water system.

The following total residual chlorine concentrations (in ppm) were taken at the north service water discharge.

10.0 Complete 13.0 Chlorination 1.2

<.05 Mixing Basin Sample

.30 3.9.Bc Total Quantity of Chlorine Compound Used Total quantitiy of chlorine used is reported in Table IX B-1 as gallons of 16% sodium hypochlorite.

3.9.8d Cooling Tower Blowdown Rate As explained under 3.9.7, the cooling tower blowdown line is normally secured during chlorina-tion; however, due to the mixing basin overflow, some discharge was occurring.

Because this was not a recognized discharge, flow data are not available.

3.9.Be Time of Holdup to Allow Chlorine Decomposition The usual procedure is to secure cooling tower blowdown until the chemistry technician feels the levels of total residual chlorine are low enough to insure the chlorine concentration in the mix-ing basin is less than 0.05 ppm.

Often, blowdown from one tower remains secured while the other tower is being chlorinated, resulting in holdup times much longer than required by this criterion.

IX-20

However, considering the continuous unrecognized blowdown discussed previously, it is not accurate to assume any holdup time.

Therefore, none is reported in Table IX B-1.

Nevertheless, holdup of a portion of the total cooling tower blowdown did occur for at least the length of time indi-

cated above.

(2)

Blowdown Characteristics 3.9.9a Chlorine Concentration in Blowdown During Chlorination Prior to Dilution As previously discussed, some chlorinated blow-down was discharged over the weir, although the cooling tower blowdown line was normally secured.

Chlorine concentrations measured at the cooling towers are given in Table IX B-1.

3.9.9b pH During Blowdown Prior to Release to Lake Michigan The pH of cooling tower blowdown prior to release to Lake Michigan is listed in the Monthly Operat-ing Reports contained in Appendix A.

3.9.9d Calculated Heat Rejection to Lake Michigan The calculated heat rejection to Lake Michigan is *tabulated in Table IX B-2.

3.9.9e Temperature at Edge of Mixing Zone A thermal plume survey was conducted on May 20, 1975.

During the survey, the plant gross electrical output averaged 537 MWe, with a 76,000 gpm discharge flow 3°F above the 50°F IX-21

r TABLE IX B-2 Heat Rejection to Lake Michigan Date Heat Load 6.

BtuLday x 10 Date Heat Load 6 BtuLday x 10 Date Heat Load 6 BtuLday x 10 3-1 407.8 4-16 719.7 6-1 719.7 3-2 3,262.4 4-17 1,439.4 6-2 1,439.4 3-3 4,678.o 4-18 719.7 6-3 1,439.4 3-4 1,631.2 4-19' 2,159.1 6-4 2,159.1

' 3-5 4-20 1,439.4 6-5 2,878.8 3-6 0

4-21 1,439.4 6-6 2,878.8 3-7 407.8 4-22 719.7 6-7 719.7 3-8 815.6 4-23 719.7 6-8 2,878.8 3-9 815.6 4-24 1,439.4 6-9 2,878.8 3-lO 0

4-25 1,439.4 6-10 3,598,5 3-11 0

4-26 719.7 6-11 1,439.4 3-12

o.

4-27 1,439.4 6-12 719.7 3-13 1,223.4 4-28 1,439.4 6-13 1,439.4 3-14 407.8 4-29 1,439,4 6-14 719.7 3-15 3,670.2 4-30 1,439.4 6-15 0

3-16 2,039,0 5-1 1,439.4 6-16 719.7 3-'.!-7 407.8 5-2 1,439.4 6-17 0

3-18 1,631.2 5-3 1,439.4 6-18 719.7 3-19 815.6 5-4 719.7 6-19

-719.7**

3-20 5-5 719.7 6-20

-719.7**

3-21

-815.6**

5-6 719.7 6-21 0

3-22

-1,631.2**

5-7 719.7 6-22 719.7 3-23 5-8 719,7 6-23 719.7 3-24 5-9 719.7 6-24 3-25 5-10 719.7 6-25 3-26 5-11

.719.7 6-26 3-27 5-12 719.7 6-27 2,878.8 3-28' 3,262.4 5-13

' 719. 7 '

6-28 2,878.8 3-29 4,078.0 5-14 719.7 6-29 3-30 4,485.7 5-15 719.7 6-30 6,477.3 3-31 6,821.3 5-16 713.0*

4-1 719.7

.5-17 3,548.6* '

4-2 1,439.4 5-18 719.7 4-3 28,644.5 5-19 719.7 4-4 17,129.1 5-20 2,878.8 4-5 719.7 5-21 719.7 4-6 2,878.8 5-22 348.2 4-7 1,439.4 5-23 0

4-8 719.7 5-24 2,154.1 4-9 719.7

.5-25 719.7 4-10 719. 7' 5-26 719.7 4-11 1,439.4 5-27 0

4-12 1,439.4 5-28 719.7 4-13 1,439.4 5-29 719.7 4-14 1,439.4 5-30 6,477.4 4-15 2,159.1 5-31 719.7

Average daily value not recorded.

- A negative value for heat rejection results from a negative value for AT.

IX-22

intake temperature.

Surface water temperatures and vertical profiles measured at 14 stations indicated that essentially no thermal.Plume existed.

These data indicate that the discharge and mixing zone criteria are being met.

Addi-tional thermal plume surveys are planned for this year and will be reported in the next semiannual report.

Analysis of records of intake and discharge temperatures reveals that most discharge temp-0 eratures are within 5 F of the corresponding intake temperature; therefore, on nearly all occasions the discharge temperature is within

5°F of the ambient temperature of the receiving waters at the shoreline.

These maximum discharge temperatures are also usually within the monthly maximum temperature range allowed at the edge of the mixing zone.

Thus, since these temperatures prevail at or near the discharge, it can be assumed that the temperatures at the edge of the mixing zone fall within the allowed maximums.

Verification of compliance with mixing zone limitations will be made after additional thermal plume surveys have been conducted.

IX-23

(3)

Effects of Chlorine on Aquatic Life 3.9.10 Record observations of any dead or distressed fish during simultaneous chlorination and blow-down.

Before the discharge of chlorinated water over the weir was recognized, no record of dead or distressed fish was made since it was assumed that no simultaneous chlorination and blowdown was occurring.

Since the recognition of the chlorinated discharge, the following observations were made regarding dead or distressed fish in the discharge area:

5/24 - Many dead fish at discharge of mixing basin before, during and after chlorina-tion, but not related to chlorination effects.

The fish were identified as alewives.

5/25 - Observed about six dead fish at discharge to lake prior to chlorinating.

5/26 - There were 16-18 dead fish at the mixing basin discharge on the lakeside prior to chlorination.

6/18 - Trout in the mixing basin showed distress due to service water system chlorination.

Three were floating on the surface.

IX-24

b.

Environmental Monitoring Program - Technical Specifications Section 4.ll (l) Meteorological Network Observations (4.ll.6)

Thirteen meteorological stations were established, as described in Amendment No 6 to Facility Operating License DPR-20 (change No lO to Appendix A) to document effects of cooling tower operation on meteorological variables.

The stations were established by and are serviced under contract with the Dep~rtment of Atmospheric and Oceanic Science, the University of Michigan.

Data collected from October 1972 through June 1973 are pre-sented in Data Report No 1 included as Appendix B.

Additional details of the study, including computations of potential cooling tower fog, an analysis of lake breezes and a description of plume observation programs are discussed in the Third Annual Report, included as Appendix C.

(2)

Noise Survey (4.11.6)

In accordance with the Palisades Technical Specifications (change No 10), surveys were conducted to determine noise levels with and without the cooling towers in operation.

Points on the outer perimeter of the site generally showed no significant change in noise level that could be related to operation of the plant or cooling towers.

On all occasions, every sampling point, except those adjacent IX-25

to the cooling towers, were within the normally acceptable range as defined by the HUD criteria for noise. (l)

Details of the noise surveys are included in Appendix D.

( 3)

Cooli.ng Tower Drift Study ( 4. ll. 6)

During January 1975, a report summarizing the Palisades Drift Study Preoperational Data covering the period of January 1973 - September 1974 was submitted. ( 2 )

Since that time, data collections have continued with the cooling towers in operation (Aprill, 1975).

This dis-cussion summarizes the data collected from October 1974 through June 1975.

Complete data are available for the samples collected from October 1974 through January J975 and are summarized in Table IX B-3.

Mean precipitation amounts listed in Table IX B-4 are the only data available for the remainder of the period.

From June l6, 1975 through June 30, 1975, vegetation com-position was analyzed and leaf and soil samples were collected for chemical analysis.

Results are not yet available.

Table IX B-3 shows the mean sulfate and calcium concen-trations and conductivity of the precipitation for four months.

The cooling towers were not operating during this period except during October when the plant was (l)"Noi"se Abatement and C t l

D t

t Pl" I

t t" on ro -

epar men o icy, mplemen a ion, (2)

Responsibilities and Standards," HUD Circular No 1290.2, August 4, 197l.

Rochow, J. J., 1975.

Palisades Nuclear Plant Cooling Tower Drift Study:

Preoperational Study Report.

Consumers Power Company Submittal With Letter of January 3l, 1975 to Directorate of Licensing, NRC.

IX-26

TABLE IX B-3.

PALISADES DRIFT STUDY - PREOPERATIONAL DATA:

SUMMARY

OF PRECIPITATION ANALYSES.

Al.1 25 Pl.ots Combined OCTOBER 1974 - JANUARY 1975 Sulfate CaJ.cium Conductivity Month*

(ppm)

(µmho/cm)

October 1974 Mean 5.7.

7.2 39.4 Standard Error of Mean 1.4.

1.5 6.1 951' CI*

2.9 3.0 12.6 Mean Precipitation (mm) 46 November 1974 Mean o.o 16.2 28.5 Standard Error of Mean o.o 1.7 1.3' 95% CI o.o

. 3.6 2.7 Mean Precipitation (mm).

68 December 1274 Mean o.o 7.5 23.2 Standard Error of Mean o.o 2.1 l.O 95% CI o.o 4.2 2.0 Mean Precipitation.(mm) 43 January 1275 Mean o.o 3.9 25.0 Standard Error of Mean o.o o.5 1.2 95% CI o.o 1.0 2.5 Mean Precipitation (mm) 118 IX-27

TABLE IX B-4.

PALISADES DRIFT STUDY MEAN PRECIPITATION AMOUNTS (mm) FOR PERIOD OF FEBRUARY - JUNE 1975 February March April May June 72 75 152*

113

The actual amount of precipitation is probably larger than indicated by this value because many of the rain gauges were overflowing

IX-28

operating between 30% and 60% full power for 24 days.

As compared with the same period one year earlier, the average mean sulfate concentration is considerably lower due to the zero values recorded for November, December and January.

The presently employed barium sulfate method for sulfate analysis is being compared to the specific ion electrode method to determine if the zero values are real.

Overall mean calcium concentration of 8.7 ppm is considerably higher than the 2.8 ppm for the same period one year earlier.

November'1974 had very high calcium levels with 19 of the 25 plots having concentrations of 10 ppm or greater.

No explanation can be offered for these high levels as canopy leaching should be negligible during this month.

October and December levels were also considerably higher than a year earlier.

Mean conductivity of the precipitation compares favorably with the same period one year earlier, 29.0 µmho/cm versus 25.4 µmho/cm.

Mean monthly precipitation amounts for the nine months included in this report are shown in Tables IX B-3 and IX B-4.

Precipitation amounts during the first six months of 1975 were higher than normal in the State.

Six hundred and twenty-four millimeters (24.5 inches) of precipitation fell during this period at the Palisades site.

Since the cooling towers began operating on IX-29

April 1, the high values during April, May and June may be partially attributed to cooling tower drift.

However, no conclusions can be drawn at this early stage of the investigation.

(4)

Unusual Environmental Effects Related to Aquatic Study ( 4.11. 7)

Ta~ulation of fish observed on the intake screen is shown on Table IX B-5.

Several counts were missed due to procedural problems; however, it appears these problems have now been resolved.

IX-30

TABLE IX B-2 lMAKE-scREEN COUNTS Da.te 1-8 ~ 1-15 1-16 1-21.

1-23*

1-28 1-30 2-3 2-5 2-ll 2-12*.

2-18 2-19 2-25 2-26 3-4*

Duration of Sampl.e (hrs) ll ll.5 12.5 12.5 13 9.5 ll 10 ll.5 10 12.5 ll.5 ll.25 ll ll ll.5 ll Al.ewif e 2

1 1

6 3-5" 4"

5" 5-7" Gizzard Shad 1

1 5"

4" Smel.t 1

4" Spotta.il Shiner 1

1 1

3" 3"

3" H

Channel. Catfish

~

I.

~

Trout-perch Sl.i~ Scul.pin 1

1 1

3" 3"

3" Perch: Adul.t Perch: Young 1

1 3"

3" Crfzyf ish 3

2 3

2 1

Bl.a.cit Bul.l.hea.d Bur bot

Nothing was collected on the travel.ing screens.during this sampl.ing period.

X - Species present, but not quantifiable.due to state of decomposition

TABLE IX B-5 INTAKE:-SCREEN -COUNTS Date 3-5 3-6 3-11 3-12*

3-17*

3-18 3-24 3-25*

5-1 5-8 5-15 5-22 5-27 6-2 6-9 6-16 6-23 6-30 Duration of Sample (hrs) 11.5 12 11 11.5 12 11.5 11.5 10.5 24 24 24 24 24 24 24 24 24 24 Alewife 28 17 5

1 18 61 8

36 116 x

4-8" 4-8" 4-8" 4-8" 4-9" 4-8" 4-9" Gizzard Shad Smelt 1

3" Spottail Shiner 1

1 1

1 3"

3" 3"

~

Channel Catfish 1

1 I

3" 3"

w I\\)

Trout-perch 3

1 3"

3" Slim;y Sculpin 1

2 7

14 3

3

l.

7'

l.

15 x

3" 3"

2-4" 2-4" 2-4" 2-4" 2"

2-4" 2-4" Perch: Adult 7

x 8-11" Perch: Young

l.

3" 3"

Cra;v:fish 2

9 18 11 7

20 30 6

67 x

Black Bullhead 4

3-6" Burbot 1

17 11

Nothing was collected on the traveling screens during this sampling period.

X - Species present, but not quantifiable due to state of decomposition.

rceERS p(')~!ER CO,.,PAf\\:Y 2\\2 kEsT ~ICHIGAN AVE~uE MONTHLY OPERATING.PORT FOR Jr}_lfvMW J!j_l:)

I n11s IS YOUR MONT PORT FORM FOR MONrH VLAA r: 2 ll 91 c" s l 5 01 Ll Is TR I c T

CONDENSER l~LET ~ATER SEE REVERSE SIDE FOR RETURN MAIL I CONSt.wr RS PGV;ER COt<PANY

_J l-p-ALISACES PLANT, SOUTH rAVEN TO: STATE OF MICHIGAN If data is collected once daily, enter the value as a DAILY WATER RESOURCES COMMISSION AVERAGE. If data is collected more frequently, compute the 49201 CnNSU~ERS POhER CG~PANY D, r, ?RANDT 11945 1-., FARN.ALL L.J.~CKSCh nci-;,

srA.r1cN ~o.

arC.\\l,49 R01 119201 _J Please complete and submit two copies of this form at the end of each month. This report must reach our Lansing office by the 10th of the month.

IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY: *REMARKS CODE: 1=LESS THAN, 2=GREATER THAN

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Coliform data, if reported, should be a geometric ilVCrage.

Please use units specified. At end of month compute the '

Monthly Average and record Number of Determinations for Month, Monthly Average, Monthly High, and Monthly Low as Monthly Summary.

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DUP PUNCH

!07*68!

CUP PUNCH m 68!'

-~-------1--1---1------~--*t---t-t------t---r--*t-+-----+---+---1 CUP PUNCH 157651 NUt.1ili*n llMf!;

t'184!ll 1,u1,w1 n 11t.~1.$

1484!)1 0

t-,,lJ\\,l1l 11 fl~'lS 143 ~lf1 (XC:ffllHl l-XC:CH1rfl r-.:crr orn

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Of ANALYSIS OF ArML YSIS nF :..~;AL YSrS CUP PUNCH fS7 681 DUPPUNCH 157*681 DUP PUNCH IS7*~0l

~-

. ~~~~ /*1....

SIGNATURE OF CERTIFIED OPERATOR-------,,...---.-7.(;'-79""'<-"'~~~*==~-+-~~='~~~-~,2~-J~~;-/,~7~.S __ _

SIGNATURE OF PRINCIPAL EXECUTIVE OFFICER

_c;w-<i):; =

~

f,-;:J/4/1 J CERTIFICATION NUMBER--------------

A451S REV. 1Q.°7l

lc *.

,EPS POWER COfl.PNAY 212 WEsT MJCHir.AN AVENUE C[1NSUMERS PC'iWER D. H, RRANDT I 194~ '<. PARNALL COl-lPANV RD, MONTHLY OPERATlNG~PORT FOR ::u,.,v,,JZ.t 1'77:>-

i

__ "0

_rn_" __

v*-:IAA~G; 2 491 CMSl5 51 DISTRICT

l THIS IS YOUR MON

PORT FORM FOR COOLING H20 R RAD, WASTES D H1 SEE REVERSE s10E FOR RETURN MAIL LCONSUl'EHS Pov.ER *co~Pt.NY s~

~ALISAOES PLANT, SOUTH HAVEN 49201 TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION l...J-<I er.~ n *.1 '

M I c H

P!'°l' STATION f.10.

~

8"~\\\\(,05 IMPORTANT-COLUMNS DESIGNATED 492(;1 _J Please complete itnd submit two copies of this form at thC! end of each rnonth. This rl.'purt must n:ach our Lunsing office by tlic 10th of the mo111h.

If d<1tJ is collected once daily, enter the v;;lue as a DAILY AVERAGE. If dota is collected morn frequently. compuw the DAILY AVERAGE (arithmetic). and record it. In addition record the highr.st val11e and lowest value found each day.

Coliform d,1tJ, if rl'portcU. should I"~.l Qt!Ornctr ic <Jvr*r ;1~c.

Plt!ase us1! uni!s srwcifil'd. At end of month compult.: the Monthly Avcr,1gt1

~ind rec:ord NurniJl?r o1 O~tcrm.n;,t1or.~ tor Month, Monthly AV<" age, Monthly High, o:'ld *Monthly Le.vi as l'l1JJ

.,r.tr?lRNO

.r'*'\\Ol.\\\\I ~.o 114-181 NAME 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARl<S CODE: l=LESS THAN, 2=GREATER THAN Monthly Summary.

l'J \\JJ

'J 1 *11

,., I]\\

. '1 I*

a 0 9 3 1 cno1s c..0016 r;.35nl

'5oC.6n soo6fl Qor.69 nr.aon Jq 1JI t-1 1 TU/ Ii~

11.. ~* t' LJ l r H. E I A* I 0 I CL 2 ~ 1.. RS HRS" CL ID H 3 TOT to: ET pH

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HR~/-D_A_.Y._ _______ P.C/I

.s.u ___ --t I

~-----'l'-r---

(l_._?..

I l

6 I i:; <

9 "

DAILY AVG. HIGH LOW DAILY AVG. HIGH LOW 1 DAILY AVG. HIGH LOW 1

DAILY AVG. HIGH LOW DAILY AVG. HIGH I LOW

.lDAILYAV*G~[Hi'GH\\ LOW 1 DAILY AVG I HIGI" I LG~....

UNITS STD.

DATE J

2 3

4 5

6 7

8 9

10 11 12 I-*

13 14 15 16 17 18 19 20 21 22 23 24 f---

25 26 27 28 11 I MONTH DAY Y(AR 1636al SIGNATUAEOFCEATIFIEDOPERATOR__

_: -,;- ~-

>.0d~,,,_e/_~.:i/yjzL SIGNATURE OF PAINCIPA~ EXECUTIVE OF FICEA _

_..r:r""3/:."-'-"W~:::.....:<!..'=..'-'1.J~.'---./"'q"=--..i.n:i...i...::*==:;., _:_*&,=::::,.p-!1.=---"".1._.,/._'f.4/......c..l_S:,__

CERTIFICATION NUMBER---~"'"'---------

RU1~ R£V. 11l'7l

Jcr.Ns. POWER COMPN_AY 212 WEST MICHIGAN AVENUE J~CKS~N, ~!CH, MONTHLY OPERATING R.RT FOR ~1.1111M-f 1'71~-

I MONTH YEAR I

..ii THISISYOURMONTHLY TFORMFOR I 6 2 491 0 1s1s 51 Lll~TRICT 03 CUOLING H20

~ RAO. WASTES DISC,

SEE REVERSE SIDE FOR RETURN MAIL I CONSU1'EHS P01-:ER COMPANY SH I C r I\\ S U *: E R S P 0 *~ER O. H,

'<~AMOT I 1 Oll5 '. f-ARNALL LJ.,~ C I\\ S r~ r.:,

M ! C H

STATION NO, A ~*~*JiQS COMPANY HD I 492'.J 1 __J TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Please complete and submit two copies of this form at the end of each month. This report must reach our Lansing office by the 10th of the month.

IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODE: l=LE~S THAN, 2=GREATER THAN

'~~n~oi:-.o*~IJ)

.1.-~jl t'.1131

.;tJ"'IJJ.

1!.11.ll

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JIJI 1'.*IJ1

..,;..,,,~.,NO 11418) l.i7t117 fl"IBI 5QQ~C) 114101 9l;Q67 11-4181 114181 NAME UNITS Nl:.T*"E.TA

>C/L.

FLCv.-r;GQ

~, r; D L..r>ALISAO~S PLANT, SOUTH HAVEN

__J If data is collected once daily, enter the value as a DAILY AVERAGE. If data is collected more frequently, compute the DAILY AVERAGE (arithmetic) and record it. In addition record tile highest value and lowest value found each day.

Coliform data, if reported. should l>c a geometric **crage.

Plr.asc use units specified. At' ~nd of month cornpu1c the Monthly Average and record Numbt'r of Determinations for Month, Monthly Average, Mon1hly High. and Monthly Low as Monthly Summ:iry.

,-,1.n

.*.1

.t1J11 1<

7 4 1:

1< -----s L

DATE 1

DAILY AVG. HIGH LOW DAl_L_Y_A_V_G-*.~H-l_G_H~-LO-W *-~O-A-IL_Y_A_V_G~.~H-IG-H~-L-0_\\V lD-A-IL_Y_A_V-G.fi*H--IG-H~-L-0-W STD.

k

. DAIL y Avd. HIGH LOW "1"0Ali.. y Avd. HIGH I LOW 11 DAILY AVG 1

. H:Gf' LOI'/

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3 o

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0 1

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I 0

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-~~_x_'t/_ . t._-~-cfr_o_'f ~.~-2.+-o-_-~-+----+--+--+--1----:--1---11---1---1-----1---1---i-1------11----1r---i 23 ~ o __ i:J2~11 i+-_o~'---+--~---1-+----+---1---i-+----+--+---+--+-----+---+---+--+-----+---+--1 ~ 3 ___ () --.7/L{~

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- - C/._7-i_?_ I

. _'t-+-__ o __ +--*+----*--+-----+---1--+--+-----+---1--+-+-----+----1--1--+------+---+---1 -~ _q _______, '771 ?/_~ _ ___:_ 3 ___ Q - ----------1-+----+--+--+-+----+--.+---+-+----+--'--+---I ___E_ !L __ 9 __ -*** -- --.'l 21.2/_ f--- l/.. __ Q_ ___ ---+-~f-l-----+---+---l*-1-----+---+----l~l------+---+--t---+----+---+----1 -2~ 7 _Q.l~L o_d_sr _fl__ *- _9 7r C!L __ *-- ___ 7_ --~--~-~.JL !m1 -9 _ _ --*-*-+---+---1--+-----1---1---+--+-----+----1r--+-+-----1----+---; -~~. }=~3= -=~- ~179~~-";*-- _:~= =: ?. =-~~-- *--===----f----==-==- -----+---<--*1------+---+--;--+-----+--+-~-1 ~.b_ ,,,,.,j_-'_z.i:i?f"AvtRAGD~i -._s~~~t3.7 -~~1 1 ~*;, !1-'~'i.e.o_.i,3 AVERAG~_I'..:' =-~"'..L.l.... L..1.....L~~J'~~ -'-~~~ A,VErlAGE 1 11**;...L. '.::_'81 AVERAC.E \\'"' _ _,_ """ 'AV(Rt.GE \\*" MONTHLY t Tf.it:-~tc-: cr.-TH1GH--*r)tli t iu.o3'l o~,,t,~ HIGH -li:l'J' t !JO.'ti. o-;,1, ~ T'JHJ t iJOJ/I HIGH !'JUI t l:JOJ71 HIGH l'Jtl;* t ::io:i~1 HIGH 1131:* t 11ud11 HIGH in~,

zJIN.i'.J.l>I

~-"J ~':uJ --L.J....J.....L...I....

SUMMARY

~ !3;14,i,1 /) LOW 11..i1. ~ IJ'J.Sf,1_,);l,/S LOW 11-i11 ~~ IJfJ4Ci1 -1....l~- LOW fMll ~g ~~L LOW 11411

~ U!J4*JI LOW 11411
~ U'i461 LOW

['411 !~ tTJ*b* LOW j*

REMARKS CODE.._,,I

[:REMARKS CODE ---./

REMARKS CODE...__,/

.**REMARKS CODE....._.,

REMARKS CODE..__.,/

"REMARKS CODE---./ "RErMRKS CODE.._,,I ~~~{;;E~l~.lt.~ WH'1P 0 t!J ~~;~~*~\\;~:>'P.ll~i f4ti-4~0 ~~~~'~\\;~11\\llS 14!1-t*J! 0 -*c; ~~~~~.;,1l:j l41H!ll ~~~~l~L{~~~IW:S l484!JI ~~;.1::!1111~~'~1Mi5 14d*91 !.~;;**.1~*=-*~f),r:l~. 1<1!140.1 $,t...\\1PLE TYPE l!or.!olll q.lR.Sl\\MPl.E TYPE l!o()!>I~ v I SAMPLE TYPE t!>O 51 'LG~::. 5/\\MPLE TYPE 1 ~s11 SAMPLE TYPE {5U*!>ll ~~.~~"yc.,;s ~~I 7 7 /.;Ll_ ~i~ 1 AuNu~t~S~s ~~I \\* / /

)~il~~~\\~~~~

~~I 7 7 / 3 / ~1~i~~:~i~~\\~s ~~I ~~*~1~,,,,_~~'"-'-'~'"-*~.__ l.....__._-J'--.J.---l"~"-~-" 1 ,~."'~~"- 1 1 1 _,_~\\,,.~s,__'"'-~~... 1_.__.J.-.....___,,---j'"~'~-'"*"' 1 ~~'~"- 1 ~-.~.:_,_, -~~~:I_~~--.---; ~)~~f'E' 1 1 :.0G 151 ti,1 l 0 (!;>> 'I 7 ~ - OUP PUNCH 1~7 c.81 OUP PUNCH 151 GBl DUP PUNCH 151-\\lOJ DUP PUNCH l'j1 r.e. OUP PUNCH IS.7-681 DUP PUNCH 1.57 601 SAMPLE TYPE $AMPLE TYPE . CERTIFICATION NUMBER---~'----~-"-- R.C~ti REV 10'73

. 4,.,ERS PO~*E:R COMPA~Y 212 ~EsT ~JCHIGAN AvEl\\uE Jt.CKSOr-.*, ~!CJ-., MONTHLY OPERATlN.PORT FOR£W_ ~ MOr.lH Yr.AR I THISISYOURMON REPORTFORMFOR '6 2 491 0'Sl5 01 UISTRICT COMllEl\\sER H*LET ~A Tl:.R CnNSU"'E~S PO~ER CO~PANY 0, H, oRANOT I 1Q45 ~. PAR~ALL R01 l...,J.A C K S C ~*, M I C H,

eorio f""""**a I

.~; ~~~J,49 49201 492Gl _J SEE REVERSE SIDE FOR RETURN MAIL TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Please complete and submit two copies of this form at the end of each month. This rnport must reach our Lansing office by the 101h of the 01011111. IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODE: l=LESS THAN, 2=GREATER THAN 19131 .;RDrR r.rJ 19131 con1 l 001:00 NAME Tl:."Pt<2DF Fr UNITS f'\\EG;:;EES FAHREr-.: SL HI 131 ! ~J I Ji 114181 114191 I CUNSu.**EHS FO:*,ER COMPANY ~ALIS~cEs PLANT, SDUT~ HAVEN _J If data is collt:cted once daily, enter the value as a DAILY AVERAGE. If data is collected more frequently, compute the DAILY AVERAGE (arithmetic). and record it. In addition record the highest value and lowest value found each day. Coliform data, if reported, should be a geometric average. Plea~e USC units specified. At end of month compute the Monthly Average and record Number of Determinations for Month. Monthly Average, Monthly High, and Monthly Low as Monthly Summary. 1.1 i:o rtJ\\j) 1141RI C141SI -sto-:---~- I ---~+---~~~~,~~---<*~~~~l~~~-*-~~~-~l~~-*~~~~I~~~-*- I I ~~~~~-'--,-~~~--1-~~~~--'-~~-,-~-l DATE 1 DAILYAVG. HIGH LOW DAILYAVG. HIGH LOW 1 DAILYAVG. HIGH LOW DAILYAVG. HIGH LOW DAILYAVG. HIGH LOW DAILY AVG. HIGH LOW DAILY AVG. HIGll LO\\V 1 2 fl '/O 'l..'L. _ __ !'~U_,~ ____. T-3-7-- j9*- 3z* ~ 1~

+--+--

-}-- ~=r~== ff= :va~ ~~~~+--+-- -t-----+---t-- I -*l--~~~~1--~- 5 I ijo ~Q___ff2 _ _ 1_,8~*~/~9-:c----+---r--~i--1-----+---r----1-r----+---+---i--+------+--t---*~--+-----+---1--r-+-----r---;--__, 6 ~ fl ~.z_LJ'./_,_,_~g_._z_g-+~--+-~~--t--~-*~--+-~-~-+-~---<---+-~-*---t-~-~*--+~ 7 f() .f.!.___ j"_Q__ [{,_'2:_"'-3__,,___-+----1-+-----+--+---I --+-----+---+--l-+-----+---+---l-+-----+---l----jf--T-------1f----t----1 a 3 .If o 'Io ~o ~ 15 ---9-** L-- ----:;~ ---,r -y9- -~8.o"ir-+---+-- --l-----f----- ---i*-----*---+---*--+------+---+--~ --+------+---1----. }__ -*-- ------~+---t---i--+-----+---+-- 10 3 J~ J? J~' 81/~0--;--..,~----'t---<1----+---+----i-+----+---+----t --1------"--+--+-+----+--+--+-+---"---+--+---i -11 __ :?___ _2 'J ____ f 0*- -"f 9__ *= f.i_~-*l----<----t--1'--------1----l---l--l-----~--1---4--1-----+----+--1-+------l--+---I -+------1--+---l __!_2 _ J_ :J? L~ 3 ff' __ --+-~~*-'~ '1-t--+---*--<-----+---t----i -t-----+----t---+---+----+----<*-- 13::;: .?'7 Jr 3~ ?.;;.c =14-= ~ ~) 9 J9 ~~-:-2::-: _ ___3_-L!.....=.-,* -y-*---+---*--+------1---t--- -r--+-----+---+--1 15 "5~ ~~ J~-' 8,17 16 3,_37 }<'/ TV -- --'if-~. ~,-o_.,._ _ _,_ __, ~~ -~~_!ft_ Er __.'IP-_ =-~=-'? -1_1__ -+-----1*---t--f -+----1---11---~-+-----+---+---*--+-----1*-,_,r----t-+----+---+---; _la ___,) _3'.1 ___ lo. __ TL --~!* __ c;_z __, ___.. -r-----+--+-- _-1_!! ___ ~ _ _]_'/ __ t<2._.. ?.J<... _ ___:?_~o_7~*--* +---**--+-----*-- .--ii--- ~ 3! -~ -~*$-:_"-if~ ~~ ~~i_: ;~-r---- -~-+-----l--;---- 22 3 1/ '/I J 8' B. '/.. t; ~ j ___ '/_0 ___ -w-- -'1?= - Y. I,:20..,-,.:..-.;-+---\\-- ___3'!..__ J. _!/J ~'/_,_tq --~~1~+~--+-~-l--t---~--+--+---+-~-4-~+---4--+-~-+----1--1-+--~-t-~-1--1--+~~~+--t---1 25 1 0 'r 0 ., 0 [{, :;i. b -+*-----f*-- -- ---*!-----*--t---+---t --~~-

2. __ )L ___ fe; ___ ; l.. = __ fLL ----**>-----

-~?.__ 3. __ ]_'?_ ____ _ ;n_ "? K __ __ __?.~j_z._ __ __ _ ______ __, _ __,r--- -~~-- ~~---.!Lt? __.J:.'l...,, _.E..!~ -- - 30 .-- __ _:__~~ =-~~- *-= ~--= =~. ______,____ __. -*.:__ ,_2!_ 1~1 1mT.1~ei~s -;;:.;*[-,.;";?-r.;ir. -- ;;'"'f;-1;;- -;:;~;;-~~ AV(r<AGE I"". -.-J. -.* J"_J*m1-_ --~v~AAGE -~~~ -.-_""'"_;_,_'""'**- ._,_A_V_E_"_"~Ge-.1*01i....L*- -~ 2R, AV[AA(jE 11* ** f-'-..JJ..L1/.1_ .. L....J....L1".J.J.J.J<_i___ ......1.. µ..LLL ~ ~ MONTHLY f W~S':"!.P.. HIGH i:JP.1 f ~~~~!ll HLGH t:i;~* t 1:111:111 HIGH j/Jln t IJUJll HIGH t:ltll t IJOJ7J HIGH llJH* t IJO:lll HIG~t Jll'*

SUMMARY

~ ~ .. 8~ LOW 1-111 ~ ~_j5, LO'N \\1-111 ~~ il'.J4U1 LOW )1471 ~ ~~.L..l.......L.. LOW 11-111 ~~ ~.! LOW 11411

~ 1J*J-i&1 LOW 11*1*

'REMARKS CODE..__;JI 'REMARKS CODE... __.:~' 'REMARKS CODE~ 'REMARKS CODE..__;r 'REMARKS CODE~ 'REMARKS CODE~

* --- - ------+---+---t---+------+---t-----t--"-----,1------+---i

--If------- ---*-- -*-+-----+---t----t--'f------1----t---I -+-----+---+----1 111;,*,, AVERAGE 1 *:*, t *JO :t, ~ 1))401 LO'h 11* 1* 'Rf MARKS CODE..__;JI_ HICH [*36 ~1... *.tHtl 1.1~:, !dfj~m .. *a-*-o :il1,,1~11Ml;S l4t1*!iiT*CJ o*- 1h'i::ii.tlttilf17ils 14B4~! r~ur.,Ul*I; rn.11:; 1484!.ll r.11r.11iill1Ti.lrs l.. 1!491 rn1r.~f.[ll llt.. l~ 14tl*O:,* ':"=:"";l: I.l,'i:. ~>'~!*_!.l.!JJ _______ ~~~ __ :..._i ___ _ 1_~_tllll1

--1 1 D:r.(_l_U[l) tXr.HllfD l}(Cl_fll((l 1'xr:11nl{l I ~fll'.*ri..'

h~~~~~:-~~~,~-,~*-:-PE _______ 1!.i1_1 !.Ii };'__i._i_ SAMPLE. TYPE l!ioll ~II :J... 'I ~/~Ml'Ll TYPE 1~"' 11 !i/*l\\H,l[ 1 YrE l!:oli ~II SJ\\MPLE TYl'C: l!".O!:>ll

SAMPLE" TYPE l!IO ~ 11

!:;A',,PLE c-TY_P_E----.,,-,,-,+, -~-1 ~i!,.~~~ 1 tNYG~1s ~~I 3Jr I 1 ~~\\~5 :~ / //(/ 1 ~~~~~v~~s ~ / 11~ 1 ~:~~1~~:~.. ~r1I ~ 1 ~'.?;~I\\\\~\\~~--'~:::**;,__ !__,__'--'--'--'--+ ~... ~-" 1 '~"'-ty,."'*,*-'-~c"":;:s,__"'~'-':l_,__....___,___,'--+!"-,r;r'1"'~-'-~'~"c~'~'"~~._*~~~~ l~_._...._...._-i ~Mt IS/621 10 ~ 0 J '") ~ DUPPUNCH lt17-68J DUPPUNCH 1~7CiBI DUPPUNCH 1~7CiH1 DUPPUNCH i!..olri81 OUPPUNCH IU.(ittl lJIJPPUNCli '°"'"81 ,..,,,9. I MONTH DAV Y.EAft

::::::: ::::::.,:::=~~/; t a<C21~1J-~*~(---;:')~~"':t,_l'!'-~7'~~7~~,_:-.-----

163681 IO ;t 'l.)? 75 CERTIFICATION NUMBER---'l~-:ol"'-.__ _______

~~N5LJ~*POl"F'.Fl COMPNAY MONTHLY OPERATING RE.T FOR ;.=et, LJJ.i.1-:_ I rn1s1svour:MONTHLYr1E FORMFOR--M-"N_;_" ___ v_EA-1".,..l 6 2 49 1 C~S15 51 UISTRICT 03 'ARO tlO 89 11;1 212 hEST ~IC~JGAN AVENUE JAC~sc~. MICH, ~Q?01 C"~SU~FRS POhER CD~PA~Y D, ti, EJRAf\\DT I 1 9 4 5 I'*, f A fl~* f<L L L.J..1C~SCt*1 ~!Cr:, r:=~95 RO, _J SEE Rl;Vi:RSE SIDE FOR Rt:TUAN MAii. TO: STATE OF MICHIGAN WATER flESOUflCES COMMISSION Please complete and s1Jhmit two copin1 of thi' form at lhc encl of each month. Thi* rnporr must reach our Lansing offico by llin 10!11 of the month. IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODE.: l=LESS THAN, 2=GREATER THAN 191ll IUIJ) 1Q\\J1 ('.llJ) COOLING H~n ~*RAU1 hASTES OISCHa L rn N ~ u ~. F R s f' n l'i E. R c w ~ t' A r-. v s ~ PALISADES PLANT, SOUTH HAVE~ If data is cnilui:Jccf llnr.e d;iily, cntur tho vo1lirn as a DAILY AV[flf\\CiE. If c1<1ta is collecwll morn f1r.qurcn1ly, compu1e the DAILY AVERAGE (arithmetic) and rc:rnrd it. In arfd1tion record 1hc hiuhcst vnl1rn and lowc1t y;,lue found each day. Colifoicn di!ta, if reported, sho1;ld be a geometric ayerage. Please uc.c units spnc:ifi!!d, At rnd of month corDpute the Monthly Avcrugc and record Number of Dc1.:rn1ina1inns for Monl11, Monthly Average, Monthly High, and Monthly Low as Monthly Summary. 00931 "'AilM*'Mi IHI 181 l14'1BJ (;0016 1,..,., r35('1 1"*'"' 500.60 '""1 5(10611 "'"1 9nnn9 nnqnn cno 15 NAME MbTU/hR Hi-1-L;JF Bf::lf.*TOT C.L2*T*RS. hR~*CLID H3TOTNET f'H u5~';.s tJ R TU CE G fl E. ES Ct.NT l G f' C ! l '-' r.1 L ~ fi S (-U"-'A-'--Y,__ __. =-__ :*Cf-1: ____ > __ ¢_, ;j~----Q-t'i DATE 1 DAILY AV~. HIGH LOW 1 DAILY AV~. HIGH LOW 1 DAILY~~'HiGfi LOW 1 DAILY AV~~ HiGHlL~~_? ~,.~D-A-1-LY_A_V_,G~.,-H_l_G_H-r-L-D-W 1 DAILY AVG. HIGH LOW 1 DAILY AVG. HIGH LOI'/ I MONTH OAV YEAR r i /J IJ: SIGNATUREOFCERTIFIEOOPE.RATOR~'t""".'~0.~ f:'/u.et.., !/, ../!!...~ _ S\\GNATUREOFPRINCIPALEXECUTIVEOFF\\CER ~1(-*n 7'\\ o J A,,_,/ 71 ri-+2r -~- dr/ 7;( CERTIFICATION NUMBER---~~ul!L-------- J~ F 3h*(?s-l 163*6BI R461i RCV. IQ/7l

4 --~r.:Rs PC~l[R CO~~PNAY MONTHLY OPERATING.ORT FOR F~ 127.:J I THIS IS YOUR MONTH PORT FORM FOR MONTH YEAR r: ~ 4 91 c ~ s 15 51 lJ Is T Fi I c T cu o LI r-. c; H 2 n & *RA u, 1. As n: s o Is c H, LCONSUVEHS PO~(R CllkPANY 212 hEST ~!CHIGAN AVENUE J f. C K S L r*!, ~ I C f;, Cn~SU~[RS PO~ER CGMPANY DI H. Pf:U.t\\OT 11045 \\1, fARNALL Rn, LJ..~ C K S 0 r., M I C H

SfATION NO 49~(j1

'<92C1 _j SEE REYERSE SIDE FOR RETURN MAIL TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Please completr. and submit two copies of this form at the end of each month. This report must reach our Lansing office by the 10th of the month. IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY* 'REMARKS CODE,' 1=LESS THAN 2=GREATER THAN r~RCCR r.o l91JI '* " _, l 19 IJI L ll~* j l HllJJ (.; 1.19.; l 19 131

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~0050 <;t;(16 7 114 181 114*1R) 114181 {14 181 114-lA) NAME ~; r-T- f* I:.. TA f LU~*-FliD HOf; I C.-AC: UNITS PC/L ~GD l"G /l STD. ~ 31' ~ 7 4 t:, I< 5 I I PALI5t.(.[:i PLANT, SOL:lH HAvEN If data is cnllr.cted once daily, enter the value as a DAILY AVERAGE. If data is collected more frequently, com[l*Jtc the DAILY AVERAGE (arithmetic). and record it. In addition record the highest value and lowest value found each day. Coliform data, if reported, should b~ a geometric average. Please use units specified. At end of month compute the Monthly Average and record Number of Determinations for Month, Monthly Average, Monthly High, and Monthly Low as Monthly Summary. i'l lll !!.o 1l1 114181

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~ONs~ POWER COMPANY 212 WEST MICHIG~N AVENUE JACKSON, MICH, jMONTHLYOPt:RATING R.RT FOR_4,¥:,c;;L u.z_.j-:_ 91 THISISYOUllMONTHLY HFOHMFOR------Y-,A-i"~r 6 2 491 CMS15 01. DISTRICT 03 1 CONSU~ERS POWER CO~PANY O, H. BRANDT I 1945 w. PARNALL RD* o;~ 9 ,,oJ pt1~&~0SObll' MICH, Li_J Lao_cull~ l:9201 49201 _J SEE REVERSE SIDE FOR RETURN MAI~ TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Please complete and submit two coi>ies of this form at the end of each month. This report must reach our Lansing office by the 10th of the month. IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODE: 1~LESS THAN, 2=GREATER THAN

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_!,f~}_., THISISY~URMONTHL PORTFORMFOR '6 2 491 Ct.-515 54 DISTRICT 0 I 212 WEST ~ICHIGAN AVENUE JACKSON, MICH, 49201 CONSUMERS pOwE~ COMPANY O, Ho BRANDT ~ 945 W* PARNA*LL ROAD l.-u~o:01* MI c H. Lli ac.a * ~ 49201 _J SEE REVERSE SIDE FOR RE.TURN MAIL TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Please ~ompletc and submit two copir.s of this form at the end of each month. This rcpot t mu:;t re.Jch our Lansing office by the 10th of the month. IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS Dl\\ILY; "REMARKS CODE: 1~LESS THAN, 2*GREATER THAN COOL,TOWER SLWOWN PRIOR TO OI~UT£ LCONSU~ERS PowER COMPANY _J eoVERT PALISADES PLANT If clo.1t.:i is Ct)!lr.ct1~d on<.:*.? 11.1:ly. rnter lti~ vahJc u a O,\\IL Y AVER/\\GE. If d.ot~ i* coli"."Ct*"l more frcriurntly. com1.,1r 1t.c DAILY AVERAGE (Jr11111n1.!tic) <mcJ,,_.c.vrd i: In *<!.1.t1vn record the higtw~t value i:ltid l{.t*.... 1*s.t valu(' found r~<"h d~*,. Coliform di1tJ, it rcportc,s. ~houlcS t~ a 9f 0Grnt*1r*C

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!MONTHLY OPERATl!'..EPORT FOR/;f,gi;.~ IJ.?) THISISYOURMONTHLYflEf'ORTFORMFOR '6 2 491 CMS15 51 DISTRICT 03 * ~DNSUHERS POWER CDMPNAY 212 WEST MICHIGAN AVENUE JACKSON, MICH, CONSUMERS POWER COMPANY De He BRANOT 49201 I l945 Wt PARNA~~ RD1 .*," '"' ~~"~ ~.. S ONJ' HJ CH 1 119201 _J a;i 001122 SEE REYERSE SIDE FOR RETURN MAIL TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Pll~~se complete and rnbrnit two copius of lhis forrn

t tho end of each rnonrh. This report rn1is1 reach o~r 1-an<inQ office PY the lOlh of lhr. 111onth.

IMPOATANT-COLllMNS P~SIONAHP 1: rnnn NIJM~FR OF PHf.f!MINATIONS DAILY; *R~Mt.RK$ WP~: 1"L~SS THAN. ~=CiREATFR THAN DISCHARGE TD ~AKE MICHIGAN 001

I CONSUMERS POio.ER COMPANY S~

'-covERT PALISADES ~LANT If rl.it,1 is collcct*?d once rtaily, enter t11e value as a DAILY AVERAGE. If dJla is collected more frequently, compute the DAILY AVERAGE (orithrncticl and rcco1d it. In *ddition record the highest value and lowest value found e*ch day. Coliform (fata, if reported, shoul<l be a oeornciric ave,.*ac. Please use units specified. At end of month cornriuu: lhe Monll1ly Avmoe *ml record N~mPr.r cf Pc1erniin111ion~ fcr MPnlh. Manihly AvmQP, M'mthly Hiah. anq Monthly 1-nw ill M'mrlily S11mm*ry.

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POWER COMP.\\NV "°lMONTHLY OPERATIN.PORT FOR-11£;,~I, I'(.?.:?, rn1s1sYolrnMoNTHLYR~PoRTFoRMFoR I 6 2 ~91 c"s15 52 u1siRicT o3 I 212 WEST MICHIGAN AVENUE JACKSON~ MICH, . 49201 CDNSUHERS POWER COMPANY De H, BRANOT . L1945 w. PARNALL ROAD 49201 _J SEE RE~ERSE SIDE FOR RETURN MAIL TO: STATE OF MICHIGAN WATER RESOURCES COMMISSION Please complete and submit two ccpics of this form. at the rmd of each month. This. report must reach our Lan-;ing office by the 10th of the month. ~.. rACK~()JN MICH C:frJ G~,~s IMPORTANT-COLUMNS DESIGNATED l' ENTER NUMBER OF DETERMINATIONS DAILY; "REMARKS CODE: l=LESS THAN, 2=GREATEH THAN

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0 1115 7 0 14 5 7 0 1 4 5 7 0 l 4 5 7. r;nnc;n nnnl 1 c;nn~n ""h"n DISC~ARGE TD ~~XE MICHIGAN 002 L coNsuHERs Po~:E.R co,..PANY _J 1;r;p_~E,~L11cct.~lA~.. t~~,9,~~er~.~A,~} vJ!~e ** ~ or.1LY AVE. Rt"'G E. If dJta is co!l*:ctcct more f rl."ciut*nt!y. cc.,rn~]'!J~~ tnc 0/1.ILY AVERf,GE (arithmetic) ond rl'omd ir. In *:!*:*:.. -.n r1..:cord tnc highl!H *vc::uc Jr.d fo:,*.c~t va:=.. ~ fo~nc'! each ~:i*1. Cot:furm d.:ita, if rcpcrtcd. ~hou:c be a 1.;c:.r.-*tt~1c ~.. cr:.'fl'. PieJ'iC u~c units spl'c;fitd. At end r.if momh curr.pu~e 1iie Mcnthly AvcrJUC and record Numbo~r of Dctc1mir.cst1')n\\ tor Month, r.1on1hly Average, Monthl'{ H,gh, ond Monthly Lo" ;i~ Monthly Summary. NAME F'LOl->*MGD TEMPH2CJF' CL2*T-RS PH I u5~ 1 ~_s ~.Gf' _.:__o_E:G.flJJ;s1_Hf:!.RE.fL_ t:<GkL_-__ s.>-.---.--*~~'---- -----.....,.-----+-----..-----*-----~ 1 -----*1 DA re i DAILY AVG. ]HIGH I Low 0A1LY AVG. HIGH LOW-DAILY AVG. HIGH -£i~/***,- -o"'A!LY61.'vci. TH/Gtl LOI~~ -:i10-A-1L_Y_AvJ* HIG"H' _L_o_w_ ll_O_A_1_L_Y_A_v_~~.~-H-1G-H--...-L-o-w-1 1l DAILY AVG.! HIGH I Lov/1 ,___:_i_t_~ ---*-* - --**---*~ *-- --~-----* __,,_

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JACKSON, MICH, 49201 CONSUMERS POWER cOHPANY 0 I H, BRANOT

~ f.<.f-~.ory MICH, ~ 945 w, PARNALL ROAD ~.o.nn.s.J 49201 _J SEE REVERSE SIDE Fon RETURN MAIL TO: STATE OF MICHiGAN WATER RESOURCES COMMISSION Plcaso comple1e and submit 1wo copies of 1his form at the end of each month. This report muH reach our Lansing office IJy the 10th of the month. IMPORTANT -COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; "REMARKS CODE: 1"L°ESS THAN. 2*GREA TER THAN H20 TREAT,SVST£M fRIOR TO DILUTION LCONSU~ERS POWER COMPANY 1 COVERT PALISADES PLANT ~ If d.u-. i~ collcc1L*cJ ur1c..c c:1o1ily, cnt1.:r 1t1c v'-iluc a~ a DAILY AVERAGE. If. <l*IJ i1 collec1c<l more frcqurn:ly. cornir.. :o th~ DAILY f,V[flAGE (;,ri1~.1111:1;c) and r*:cord ii. In o<h!*l*on reocorU the: high<*~t vulut* arid IU\\.'.'CH \\";i!uc fr,ur*<1 (',;.r.h *!;,,y. Coliform cl11,1. if r!'i.-ott1*d, ~hould bl-a ge<Hl'CH*C avr*:Jr~. Plc;::is.1: use uni a sprr.ih*.*ct. At f'1'\\d ot mor'\\"1 cr 11*1r;u ;r tt Mnnthly /\\"v"1~r.'.l~ll.' JncJ rc*cr,rd Numbc*r of Oct**rrru.. 1:*:*':*. tor Month, r.1on~hly /\\'t'l'r,1r;1!. t.io:ithl't' High. anl~ Mv11thl*1 L(lw J:. Monthl.,.. Summ'-iP/. O'*D[R '<0 '~"' Cl 14 5 7 l'llJJ 014 5 7 0 14 5 7 00 " 1 0145 7. 0 145 7 0 l A 5 7 011; 5 7 o;nnc;n 00401) nt n22 nnc'if.5 nnol!C:. nr,o:;<n

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WATER RESOURCES COMMISSION I ffi corv:PREHENSIVE STUDIES SECTION

c STEVENS T. MASON BUILDING i ~

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l* 2 ll91 Ct-<515 1 lJ s R c 212 WEST HICHIGAN AVENUE

JACKSON,

~IICH, 49201 . 49201 _J SEE HEVERSE SIDE FOR RETUllN MAIL TO: STATE Oi- ~>1!CHIGAI~ WATl.'.R RESOURCES COMMISSION Plca;e complete and submit two copies of this form at *the end of rach rnu11th. Thi~ rcrort 11~u;t rcuch our Lansing of lice lly 1hc I 0th of lhc month. INTAKE I COt~SUME.RS P01o;ER COMt'.\\NY I. L.COVERT PALISAU£S PLANT If d *l.J 1"; co:!-.r:t* c: 1;1~CI! ~1., :y, 1~11:1.r ~i-:c v~li.!c &J:i a D/\\!LV AVL n1,G [. i; (!.1t.1 j~ r.uli<*r..t-:tl mor '! frcq*JC11~ly, UJm(JUtC lhe D/l.ILY Al/Eil.~.c,;: (a*i1:.n*:.,ti*:l tr.d. rrcorORT FOR}f;t;~iJh THIS IS YOUR MON rHLY HEPUI\\ r FOllM FOfl CDDL.TGW[R HLWD~N PRICR TO DILUTE l CONSUMERS POWER CUKPANY _j

coVERT PALISADES ?LANT.
212 WEST MICHIGAN AVENUE JACKSON, MICH, 49201 SEE REVEflSE SIDI! FOB RETURN MAIL TO: STATE OF MICHIGAN If 1:Jl, is collo*cl*:tl .,,.~,,,:.i:1*1. 1*nl* 1 11:c v;.l11c _as a DAILY C ONSU~!ERS POWER CDl~PANY WATER RESOURCES COMMISSION /\\VEliJ\\Gt:. _If d.:lil is co!lcclru '""'c lreqtJcnli~-. compu:~ the DAILY AVEfll<GE (aritl1mc*il) and rcccmJ it. In adurtit*n D ' H' 8 RANDT Please complete and suiJrr.h two r.opies of this form rccuru the higl:i:st VJ!on: illld lowc~t 1*alu~ f cunt! c.ich d<:y. Ll 945 W
PAR NALL ROAD
__J at the end of each month. This rcpoirt must rdach our* Coli!urm data, if rcportcu, should L>c a geometric "'~rage. L ,~~0£ ~"S ONJ' MICH t 49201 Lansing office l>y the 11JU1 of the munlh. Please use units srir:cifi.~rl. At c*nd of month com;iute the L Monthly Avcr;19c and rrcord Number of DdcrminJt;on~ for 8.0.0.1]_3 P )-/ ~ont~j r~onthly Avefil~c. Monthly I ligh, and Monlhl*( Low as ? ~ 1r,:PORTANT-COLllMNS DESIGNATED 1: ENTF.R Nll~llJER OF DETERMINATIONS DAILY; "REMARKS CODE: l;LESS THArJ, 2=GREA'TEB Tli/\\IJ onl y ummary. 1**;11!*.01'*"'* 01457 01457 01457 01457 01457 01457 '~'"'*' "r. """' no4no on665 n1 OJ2 n..o.9.45-
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~o~;su. PO~ER COMPNAJ 212 WEST MICHIGAN AVENUE JHKSQN, HI CH, "IMONTHL Y OPEB/\\TiNG R.BT FOR!J._f'~.~~
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49201 I lilUMP Tl llS IS YOUR,.,ON TH LY He. OP.T l'Of!M rOn - SEE REVEflSE S!OE For. Fit:l 1mr J MAIL I 2 49) CHS15 51 UlSTRICT 03 DISCHARGE TO LAKE HIC~IGAN 001 CONSUMERS PO~EH CDHP~NY S~j -cnvERT PALISADES PLANT TO: STATE OF MICH!G.'.IN If rJ;t;, '" cvllr*i;1r,,: t:***:~,1;.,:\\*, r.nt*:r ::1c *1:i!uc a< DAILY WATEH HESOURCESCOfo.l~ilJSSION 'V~"~Gr-
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C1Jt:i 1~c.. cctou111~"~11cq,;,:r.1y,cumpuc11c DAILY i\\VER/.Gf: (.,;i1hm"tic) and r~corJ i;, In
~c!<.:;1io:*, D 1 H 1 BRANDT Please cornµlcte and subniit two copi"S of this fom record tile liir.lic5\\ *1;,lu~ and lu1*1csl value fu11ncJ each di>;., L 1 9 4 5 W
PAR NALL RD*
_J ar tho end of each month. Thi* report muu reach o\\J' CtJliform c!:i1;1: if rcpcrterl, sho11!r1 tie a ~"omctric aver Jr,*!. ~1-ACKSON1 ~IICH 49201 l~nsing office by the 101h of the month. l'lca~1! u:.c units sp~r;ilicd. At ~nd of noonth COJllflUl~ the l-, ,_*_~--*~._-'_*_J*1 r* __ *8:l __ *o"_*c*_*. Q
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11 'j t I lcoN.S POWER COMPANY 212 HEST MICHIGAN AVENDE JACKSON, HICH, 49201 MONTHLY OPER.C\\TlNG *-nORT FORJ*?.r1/ J.(_z;- l {/.;;Jiii y l't"I ~ THIS IS YOUR MONTH IJRTFORr.1r-OR
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N HER~ PQh*ER CUMPAn . I -coVERT PALISADES PLANT _J TO: STATE OF MICHIGAN If <i.1;~ 1~ co1i<:< i*:c! v.,,,. t:.0.1*1. toi:cr 1.10 *:J!uo JI a DAILY CONSU!~ERS ?0WER COMPANY WATER RESOUHCES COMMISSION AVf:.Hl<GE. H r!,11:1 is c11':cc:1:cl """" frri;u*:n:ly, '"~*:i:.: ::*~ DAILY /1VERl\\GL l~11tl:ic. 0!tir.).1nd r**cord it. In ;;dd*:*un D 1 H
BRANOT Plr.asc complete nnd submit t\\*10 copir>s of this form reco1<1 the hii:Jhc~t v.:;fi1.: Jnd lo*::i:H \\.'Jluc 1vlmG c~-11 C~y.
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~I IC H 492O1 L"nsing office by the 10th of tho month. Plrasc usa units sp~cifrv!. At end o! month cornp:il~ 11,e r ... -~"~.**j' Lil""".... Mon1hly Avc1 oUC ::nd rr;1'.ord Numl~r or Dctcrr11in:1tion> fc.r
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.f' (' i rj. r-- I CON.RS POWER COMPANY lMOr-.!THLY OPERATING R[FORT FOR-4..f.~ 1J7i'.
THIS IS YOIHl MONTl.'011T Fonr.1 F!::n
.. _*_*;~.;*-... r~ 2 1191 c "'s ! 5 55 LJ Is TR! er
J 212 WEST MICHIGAN AVENUE JACKSCN1. MICH, 49201 CONSU~ERS PbHER COMPANY D, H, ERANDT l_1945 w, PARNALL ROAD c*~;*" rs~f..Huso:r MI c HI Laoo1L 49201 _J SEE REVEflSE SIDE 1*
R RETURN r-.1A.IL 10: STATE OF MICH1GAN WATER RESOUHCES COMMISSION Plc~sc complete and submit two copil'S of this f.:>rm at the cntl of C'.'.lch month. This rl?port must rPach our LDnsing office by the 10th of the month. ? )-/ H*.1PORTANT-COLUi\\~NS DESIGNATED 1: ENTEll NUMOER OF DETERMINATIONS DAILY; "REMARl<S CODE: 1,LESS Hl-'N. 2~GR EATER THAN Lt.u~:DHY ~*ASTfS PRIOr< TO OIL
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r-~~E~S PO~ER COMPANY ~WEST MI~H!GAN AVENUE JACKSON, MICH. IMONTHL Y. OPERATING~-PORT FOR_fl,~~.f-- fq7{ THISISYOURMO flEPORTFOHMFOR--------"_ ... "-_'6 2 091 C"1S15 01 DISTRICT I INTAKE 49201 CONSUMERS POWER COMPANY De H, BRANDT I 1945 w, PARNALL RD, c*~g**o prn.f!S.S OJ' MI c H ' Laoo149 49201 _J SEE REVERSE SIDE FOR RETURN MAIL TO: STATE OF MICHIG,;N WATER RESOURCES COMMISSION Please cornplc:tc and suhmit two copit!s of this form at the end of e.:ich montll. This report must rt:Jch our Lansing office by the 10th of lhc month. LCDNSUl'ERS POliER COMPANY _J 11t:;P,~,E',~L,11,,c1f.i'\\~.. !J~9fv\\,ri.~*\\f~.T v*lue a'* DAILY AVEFV\\~[. If cl.HJ ;, collected more frcquenliy, comput" the DAILY AVERAGE (Jrithrn*!lid and rer.ord it. In ad<!1tion ft'C(Jrd tin.: hii:;hcst v.;luc and lo*.***:~1 Vl)lU{l found CJch day. Califorrn d*ta. rf reported.,1i,,.,;d l;e a g<:omctr;c *vcragc. PfeJ~~ u~e unfts ~pecd11:d. At end of month compute the ~/.onthly Avcrag'~ ~nd record ~u~~r cf Ort*.:rminJt.ons. for r:.r,ntll, Munthly Avt*r"~'!. ~~on:~ily H1~'1. and 1,l'Jnthly Low as IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODI;: 1*LESS THAN. 2:GREATER THAN Monthly Summ"ry.
1i1:1,."-0i"'11.

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01057 r.nn 1 1 JIJ) NA~1~ I TEl-!Pt-'20F' UNIT:~ £ £ h ~0.-°-'- -~0-~~~-~l r'-~-~~~= - I DATE I 1 I DAILY AVG. HIGH I LOW 1 DAILY AVG. HIGH LOW t!J llJ !'1 lJI l'Jl)I !'11t1 114 IBI !14*1BI 1141HI --,~~~-~1,-~-,r-~-i-..,...~--~-._,_1 _ __, ____ 1--..-~~--._,_1~--,---i--.~~--I \\~~~~~ DAIL v AVG. HIGH Low DAILY AVG. HIGH Low 1 1 0A1LY AvGlHiG"H 1 Low - 1 1 DAIL y,;vG., HIG'i: Lo*.... DAILY AVG. HIGH LOW I I

-_-_.. _-_-_-_----=-----~--<>-------.... ~=-- ~T------+----+--- -- -----1--1..

i iii.,~, AV(RAGE 17!11 121;'RI AVERAGE ! L~'li 111 :181 AVERAGE j1;:'J !"10311 HIGH !Jill t 1:10:111 HIGH 11JU1 t llOJ11 HIGH I" tl!l*Hil LOW 141),. IJ'J-161 LOW ll4}J " IJJ*61 LOW J'"; JO ,0
REMARKS CODE...__/
---.---------__,,~,,~J.".~'-*~li~I .~,,'~n~S f )((If :>I()
!MONTHLY.OPERATING REPORT FOR_J({.§.,~ 1a7~ THIS IS YOUR MO.REPORT FORM FOR _____ -_'_fr-l,,~ I: 2 ti 91 c lo! s 1 5 5 ti 0 Is TR I c. I COOL.TOWER BL~D~N PHIDR LUTE SEE REVERSE SI OR HETURN MAIL L CONSUMERS POWER COMPANY _J. TO: STATE Of MICHi GA"~ lfi:;P,~Ei; ~o:l,*ct*'.} ~"~~ ~!~l~,S "'~"~At~} v;,I*;~ 0, 0 o.~r '-y
CONSU~*ERS POWER COt-iPANY WATER RCSOUFlCESCOMMISSION AVERAGE. If <bt,1 is cull*xtcd m<Jrc fr1)qucntly, compu:e the
~.UMERS POWER CO~PANY WEST MICHIGAN AVENUE 49201 ~!CH, O, H, BRANDT DAILY AVERAGE {orithmc:ic).and record it. In Jddrtion ARN O PIP.ase complete and submit two copit"S of this form record the highest value and lowest value found each day. E 9 4 5 I-' 1 p ALL ROA _J at the end of each munVr. This report must reach our Colilorm dJta, if reported, *hould bt! a geometric a*;crJge. ACICS~J, MICH 49201 Lansing office l>y the 10th of tho month. Pl.,a<e use units sne.cified. At end of month com*,iu:c the ~ 1 , ""e[j 9 '0 '"" ;.u Monthly Avcra!r-and record Number of Dct.,rminations for L~* C*011.3 l.1u'1th, Monthly Avcro~c. ~/:onrhly High, and Monthly Low as j;,",?O<'!TANT-COLU~t.NS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAIL V; "REMARKS CODE: 1=1.HS THAN, 2~GREATER THM*~ Mo'>:hly Su<llr1'Jry. CERTIFICATION NUMBER~ - (? J 7 fl4!!15 fl£V 10.*n
r.--'SUMERS PO:.:ER COMPNAy !MONTHLY OPERATING REPORT FORL1.iX- /0;7~
THIS IS YOUR r.y RE.PORT FORM FOR ______
,_,-,-';,;... -_!: 2 4 9] C >-' S 15 51 D l ST RI. CISC~ARGE TO LA~E "'!CHI~ 01 ~ WEST MICHIGAN AVENUE SEE REVERSES FOR RETURN MAIL I CO"iSU"ERS POWER COl-'l'At-;Y S~j \\r.,,.,...,..,,, "".... r,...iv,; J CCNSUMERS PDwER COMPANY O, H, BRANOT 11945 w. PARNALL RO,
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rsa'~"S ~f ~' MICH* r 89.- L J 11]1 § Q_QJ.l-2. ~ 49201 _J TO: STATE OF MICHIGAN WA rm HESOURCf.S COMMISSION Please complete and submit two copies of this form at the end of each month. This report must reach our Lansing office by the 10th of the month. ll\\1PORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; "REMARKS CO,DE: 1~LESS THAN, 2=GREATER THAN ., *" ',0 !,.,.,, 0 14 5 7 "' IJ* 0 1457 IO*IJJ 0 l 4 5 7 (O IJJ 0 145 7 IO*l'I ..,,,~**'""i'"'"' 5111150 001111 50060 00400 LCOVERT PALISAC~S ~~'~; If d.i:.i is co'f{*1.:nl <11*(~* *:.. ;*y. * '*"*r ' 1'.:* vile..:~~~ J DA!LY AVERAGE. It d-J*a is co!lo:cted r.111r~ fri:ot1..,r:nt!y, corr.P'Jt~ the DAILY AVF.f11\\C1E (;nilh.,*ctic) ~rn! rcc:urd it. In ad1J1!ion record the hi91J~:.t v.:1luc -.ind lowest 'IJiuc ft.Jund '!ac~ d"'I* Coliform data, if reported, !.hou:d be a ~i!or:ietric ~... era-;~. Plcos*:" -us!! unit~ ~pccifi<..'J. At (:nd of mon!h co~pu~i:- the Monthly Avcrl.lue 0:1<.! record Number of Di:tcrrnir..11.0:--:. for Month, Mon:hly Average, Monthly High, and ;,1onth:y Low as Monthly Summary.
J*JI 114 IRl NAME I FLOW*MGO TEHPH20F CL2*T*RS PH
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_STD:_j_.--__ L - --~--- ______ J-,-- - ~~---0.__:: ~-~- 6. 5: -- _9_._ :i I ~-- I J OATE I 1 I DAILY AVG. HIGH LOW 1 iDAILYAVG.:HIGH LOW 1 DAILY AVG. HIGH LOW 1 DAILY AVG. HIGH LOW 1 DAILY AVG. HIGH1 LOW 1 DAILY AVG. HIGH LOW 1 \\DAILYllVG.IHiGH\\ LO\\'I I
~~N.RS POWER COMPANY 212 ST MICHIGAN AVENUE J~CKSrN, MICH, 49201 CONSUMERS POWER COMPANY O. H, ERANDT -,MONTHLY OPERATING REPORT FOR fL~,~I (7.IS-,_ I I 6 2 491 Cl-'515 56 DISTRICT THIS IS YOUR MONT OAT FORM FOR-------)::..... H20 TREAT,SYSTEM PRIOR TO SEE REVERSE SIDE F RETURN MAIL I CONSUl-'ERS PD"ER COll.PANY TO: STATE OF MICH!GJ\\N WA1 ER RESOURCES COMMISSION -covERT PALISADES PLANT It 1:.. :.1.o:: c.-,:it-c::... :,! 1,.ic,i: <!.Jd*1. ~nt.*r
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.:,~.; Ct ... ! LY AVERAGE. 11,!.* t~ 1s. colkct1!d mor~ fr~qucr.tly, C{.m;,...it*: t.~e DAILY AV£R/.,GE (Mitnmctic} 3nd rccard i!. In oc!*!*t:on L1945 w. PARNALL ROAD J~C~SD!'J, MICH, "'~~*"'I I"""",.. J
49201 _J Pica~c complr.:tc <1nd submit two copil~ of this form at the end of each month. Thilli rL'PCJrt rnuu rcJch our Lansing offictJ by the 10th of thtJ mouth.
rccorr1 the f'li<Jht. \\t vJll1C' J"'.d lo.vc!;t..-alc..:c fc.10.:ri~ e.:*:ri da*1. Co!ifor::1 l~O:.tJ, d Fl".'i"'"':d, shv... lrJ t..e ~ ~l*or:-.~H *C... c*r.:'je. ?h:J~<* U!.C uma ~p._.,_,f,1:d At cr.l! c,f mor.:h cv*.*;1... :e-ti'le L~u Le12011_s McJ:1:hl*1 f4**~rJ<y: ;,r11J rt**:or1! N~lrr.:....., o' Drtctl"!'l*f*.lH*,.,,, for IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODE: l*LESS THAN, 2*GRFAHR THAN r.~(.r.:h, ~.~Ol\\:~ily IHlt.:"/'!. *.~~r.:.,ly H*j~. :..r.cJ ~:-:..**~*.I*; Le.....-.JS ~.~or.th!,. s~m:!o.,ry. .'.;*.::;: '.::.'.f" "' 0 145 7 0 145 7 0 145 7 0 145 7 0 l 4 5 7 0 l:.) 7 I""" r:.l'l'IC,I'\\ ('\\l'\\llf11'\\ q""" 1'11 l'I?? l'\\l'\\f..I.."\\ ""01.1c; "',..o;c; ... ~~.!-"---- ~~;*~~.. 1--~e~.D-~-~~---- *---- ~8 ____ --~~~,;~G ~;1~_pr ~.~~J. ____ ----~N.~~~1* .... u_G __ ---~~~~;c~~----.. ._s_:r:~. I . > ~ ~.! 5~< 3_, 5 "-~ t _J -* ______ *_J1 __ ~-- ___ <
__ *-- 3 C < _.. _ -* ! C ~
DATE I 1 I DAIL y,we. HIGH LOW 1 I DAILY. AVG. rHIGH LOlfj- "i DAIL y AVG. HIGH LOW 1 DAIL y AVG. I HIGH I LOW DAIL y AVG. I HIGH I LOVI l I DAIL y AVG. H:GH ! LO','/
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l~c~;su.PDWER co1-1PANY 212 ~FST ~ICHIGAN AVENUE fl '[! y*""- IM O NTH LY Q~ 1~::: 1l~o~H~Y~~*:R:~~-~-z_;.=:_'1- -4_.-..... f~-)'6 2 491 C>-1S15 55 DISTRICT 03 LAUNDRY WASTES PRIOR TO OILUTlON JhCKS:~, H!CH, 49201 SEE REVERSE SIDE FOR RETURN MAIL LCONSUt-'ERS PDr.ER CO~PANY I covE~T PALISAD£S PLANT ~* cCNSU~ERS POwER CO~PANY O, H, BRANDT l_!.9~5 ~. PARNALL ROAD .,*ACKS~, MICH, (~"!;u f'**Uu* *u. J .,,. Lacon* 49201 ~ TO: STATE or-r.11CHIGAN WATER RESOURCES COl\\1MISSION PlcJse compll*tc and sul..unit two (Ojl;l."S of this form et the end ot each month. Thi<s report must re;ich our Lansing olfico by the 10th of tho month. li.l?ORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; 0 REMARKS CODE: \\=LESS THAN, 2=GREATER THAN If tl.il.i 1r, colkc~*.:d 11;:'~*: <:,,r:y. cn:cr till! value~~ a DAlLY' AVERAGE. If d.11a i' C'*ilec:cd rnore frcq*Jently, co'1'lpu;c the DAILY AVEHAG[ (<ir1thmcticl and rr:r.ord it. In eda1:ion record the llighc': *Jaluc and lowcs: value found each day. Coliform data, if reported, should be a geometric avera~c. Plea~e u~e unit~ sp~cifictl. At end of month compu:e the Monthly Average and record Number of Determinations for r-.:unth, ~onthl*t Avc1aqc, Monthly High, and Monthly Low as Monthly s.,mmary. ., I~'
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01457 "1 " 1 01457 l9DI Ql457
*'Ji Ql457
""J' 01457 011157 l'ln3Q '""1 0053n llf'*QOO n11'?::> nl'6t-s nnn'>6 NA~~E I CRTOT*UG SOL I DSUS PH BTOT* UG p.. TOT fLO lol*GPO ~TS I UGJ.- 1 ---f* HG(1 S,U _______ -1lG./.L----t-----~".G.l.L--- -----GA.LSPERDA _ ___:>_!~: _l_ __ < _____ 30.< __ --~.10C >_~6.~ 5'.< ___ 9_, 5 *- _____,_I <. ___ 3, {:j ! _ *-. ~ -*- DATE/ 1 !DAILYAVG HIGH LOW 1 DAILYAVG. lllGH LOW 1 IDAILYAVG. lllGH LOW 1 DAILYAVG. HIGH LOW-DAILYAVG. HIGH LOW 1 DAILYAVG. HIGH LO\\'/ I -iTDAILY AVG. HIGH LC\\'I --+-- ------- 0 ------ -- --- __, ______ L._l __ A =--------=---= =---=-==~-
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!MONTHLY OPERATING.ORT FOR~!M::~- '~1.:.< 1:6 2 491 C"S15 01 DIS¥1HICT THIS IS YOUR MmJTHL: 1.EPORT FORM FOR -------,fl-r 212 ~EST M!CHIGAN AVENUE JACKSON, MICH, 49201 CONSUMERS POHER COMPANY O. H, BRANOT I 1945 k. PARNALL RO, ~ t.. C KS.Dlj* 1-1 I C H l ~**~~r,u !""'\\"" *o I .-!2.C:.._ ~.6.0.0B.Q... 49201 _J SEE REVEHSE SIDE FOR RETUR~ MAIL TO; STATE OF MICHIGAN WATER RESOURCES COMMISSION Please complete and ~ubmit tv:o copies of this form 'at the end ot r.uch month. Thi:. rcpon must reach our Lansing office by lho 10th of ti** month. li\\1P0::\\TANT-CGLUW~S DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; "flEMARKS CODE: f" LESS THAN, 2~GREATER THAN
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!11 IJJ ...i... ;.*,l.~.IJ 11.i11t1 r.nn,, 114U:U 1141HI 111\\181 114161 U;TAKE. L CO:-!SL!l-'EPS PO>-::R CO>-Wt.l\\V j C8VERT PALISACE.5 PLANT If U.J~~ is tollcct.-*..! unt.;? C.:... d*1. c.r1:1..c tf'IC vJ:u,! as J DAILY AVf:11/>.GE. It <bto is coller.:1*d mo'e frc-q~c:itly, c0m;;;;:o th~ DAILY AVERAGE (<Jrith,1v*:icl.:.nd rccor:I it. :n od<i1'.io:i record the higlwH value and lc... *.-* .:~.t v.:.J~c found (.*Jch c~ay. Coliform dutil, i! rl'.:>JUrtt..d, shu;.Jid l.h! a ~*:01":1etr 1 c aver~s~. Pic(j":f! 1.;'lC ur.its spl.!cifit:d. At 1!11d of m.:.nth cc-1~*11ut~ the Montnly.t\\vcrae::;e Jnd record ~um~r of D*~t.-.:rmir.dt;:ln~ tor Mo,ith, Monthl*t Avcraac. Mont~.ly Hi~h. ;mu Mon:h!y Lo*:1 ;;s Monthly Summ"ry. ~* l '* ~"----. ~'.."1.-1.'~:'.... YI"." --to-::r;, (/. I 1::'" lD (,.' ~, {)., *r SICNATUREGI CERTIFIEDOPrnA10R.~T;6....//_'_,- __..zu ~-- I. i..',.,- CLRTlflCATIONNUMBi:A-;.i55:.. SiCNAlURf 'll PRINCIPAL EHCUTIV( OFflCEil________ .z l?_d~- ,',J ~-
~ONSUH~OWER CD~PANY 212 WEST MICHIGAN AVENUE JACKSnN1 HICH, 49201 CONSUMERS P0wER COMPANY O, H. BRANOT !MONTHLY OP-ERATl:'~G P. EP.T THIS IS YOUR MONTHL '(RE ORM FOR SEE.REVERSE SIDE FOR' RETURN MAIL TO: STATE OF MICHIGAN WATER RESOURGES COMMISSION G 945 W, PARNALL ROAD MD"" f,,£!S,SJ, f.! I c H. 49201 _J Please complete and submit two copies of this form ut the end of each month. lhis report must reach our Lan*ing oflico by tho 10th a' tho month. 89 1111 .00_11z IMPORTANT-COLUMNS DESIGNATED 1: ENTER NUMBER OF DETERMINATIONS DAILY; *REMARKS CODE: 1=LESS THAN, 2=GREATER THAN 2 491 C~S15 54 ~!STRICT 03 COOL,TOWER BLHDWN PRIOR TO DILUTE LCONSUf.!ERS POWER CDf.!PANY _J CpVERT PALISADES PLANT If ua:J :s coilectcd once,:;,1ly, r.ntc.:r the value a< a DAILY AVERAGE. If cfatJ ls collected more fr~c;*Jcntly, compute the DAILY AVER,\\GE (arithmet:c). and rccorJ it. In *edition record the h;!]hc:it value and IO\\.\\.Cst va.lua-foL.nd c:ic:i Cay. Cv!iform di::ta, i! repqrted, ~hould lx: a <j(*ornr:tric a*:~rjg~. Please u<u units spccifi.:d. At end of month compu:e the Monthly Averaric Jnd rccurd Number of Determinations for Montll, Monthly Aver*~"* ~onthly High,.ond l.l<inthly Low as Monthly Summary.
'*~E.RS PD~1ER COMPNAY 212 WEST HICHIGAN AVENUE JACKSON, M!CH, 49201
1 1 i I lo ~ONS~ POWER COMPANY 212 WEST MICHIGAN AVENUE JACKSON, MICH, 4920( MONTHLY OPEr1f-.i.TING Rr.: *. 0 RT FOR *y.;i1c I MONTh THIS IS YOUR MONTHLY T FORM FOR SEE REVERSE SIDE F011 RETURN MAIL TO; STATE OF MICHi.GAN WATER RESOURCES COMMISSION 2 491 CMSI5 56 DISTRICT H20 TREAT.SYSTEM PRIOR TO LCONSU~ERS POWER CDMPA~Y 03.1 OIL .uN _J ~OVEPT PALISADES PLANT If d~ra ;5 coll*~ctr.*d 011<.1.." d.'.illy, cr:tr:r t~c *.*::iluc JS a Q,.\\1 LY AVERAGE. If d;,ta is co!!1*c1cc! r.1crc !rcqur*ntly, c01:;i*c:o* :t'c DAILY AVERAGE (~ritliin.,1,c) ""d rccc:d it. ir, **X t<on r* 1* \\ * '* k f
lcoNs. POWER COMf'"NY 212 WEST MICHIGAN JACKSQt-;, HICH. AVENUE 49201 !MONTHLY OPERATll\\JG n EPORT FOR :fl),,~-:_ .EJC. rH1s 1s vouR ;1oo*H~iLv. Fo;ir.1 FoR--""-**_'" ___ *'_'*"i>"_/; 2 491 CMS 15 55 ur STR r c r OJ.~ SEE REVERSE SIDE FOR RETURN MAIL Lt.U~()RY WASTE"S Pk I Di< TO DlLUT LCGNSU~[RS POkER COMPANY TO: STA TE OF MICHi GArJ WATER nESOU.r.CES cor.1~.~1ss1mJ Plc:1u? comp:*:tl: ;1111J nJm11! t""*O cc;.i.r'S o~ :h.\\ fv*m <it 1hr. c*nd r1f **act. mnn:n. fiiilli rrport rnuo,t rro.11.:h our Lan-,in~ ofli.:1: lJY !he 10th 11f the mor1th. cpvERT. PALISADES PLA~T If,.. :...i. *\\ l-.. :\\*":"'* II t,*,,
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ML18353B475

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