ML20079M573

Annual Operating Rept,1982

ML20079M573
Person / Time
Site:	Kewaunee
Issue date:	02/28/1983
From:	MADISON GAS & ELECTRIC CO., WISCONSIN POWER & LIGHT CO., WISCONSIN PUBLIC SERVICE CORP.
To:
Shared Package
ML20079M571	List: ML20079M568 ML20079M573
References
NUDOCS 8303030088
Download: ML20079M573 (97)

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KEWAUNEE NUCLEAR POWER --PL ANT l

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ANNUAL OPERATING REPORT

. 1982:

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WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN P.0W E R a LIGHT COMPANY M A DISON GAS S ELECTRIC COMPANY-

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. TABLE OF CONTENTS l

Page No.

1.0 Introduction 1 3

2.0 Sunnary of Operating Experience 3 3.0 Plant Modifications, Tests and Experiments 12 >

!- 4.0 Licensee Event Reports 20 >

l 5.0 Fuel Inspection Report 32

!' 6.0 Challenges to and Failures of Press'urizer Safety and Relief Valves 33 l 7.0 Steam Generator Tube Inspection 34  !

8.0 Personnel Exposure and Monitoring Report 35 1

i 9.0 Environmental Technical Specifications (Appendix B) 37 l 10.0 Radiological honitoring Program 38 1

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1.0 INTRODUCTION

The Kewaunee Nuclear Power Plant is a pressurized water reactor licensed. at 1650 MWt. It is located in Kewaunee County along Lake Michigan's northeast Wisconsin shoreline and is jointly owned by Wisconsin Public Service Corporation, Wisconsin Power and Light Company and Madison Gas and Electric Company. The nuclear steam supply system was purchased from Westinghouse Electric Corporation and is rated for a 1721.4 MWt output. The turbine-generator was also purchased from Westinghouse and is rated at 535 MWe net. The architect / engineer was Pioneer Service and Engineering (PSE) from Chicago.

The Kewaunee Nuclear Power Plant achieved initial criticality on March 7, 1974.

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Initial power generation was reached. April 8,1974, and the plant was declared commercial on June 16, 1974. Since being declared commercial, Kewaunee has generated 31,967,600 MW hours of electricity as of December 31, 1982, with a net plant capacity factor of 75.9% (using net DER).

1.1 Highlights During the year, the Kewaunee Nuclear Plant was primarily base loaded. The unit was operated at 84.9% capacity factor (using net MDC) with a gross efficiency of 31.06%. The unit and reactor availability were 87.6% and 88.5% respectively. Table 2.1 is a compilation of the monthly sunnaries of the operating data, Table 2.2 contains the yearly and total summaries of the operating data, and Figure 1.1 provides a histogram of the ON / average daily electrical output of the Kewaunee Plant for 1982.

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s On April 10, 1982, the unit was removed from service for its seventh annual refueling. Thirty-six fresh assemblies were loaded for cycle VIII. The unit was returned to service on May 23, 1982.

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2.0

SUMMARY

OF OPERATING EXPERIENCE January ,

On January 6, unit load was reduced for condenser water box inspec-tion. The unit was returned to full load on January 7.

On January 25, unit load was reduced to complete the monthly turbine stop valve test. The unit was returned to full load on the same day.

PLANT SHUTDOWNS: There were no plant shutdowns during the month of January.

February

. On February 12, unit load was reduced for condenser water box inspcc-tion. The unit was at full load again on February 13.

On February 16, unit load was again reduced for condenser water box

/O inspection.

U/ The unit was at full load again on February 17.

PLANT SHUTDOWNS: There were no plant shutdowns during the month of February.

March Plant generation was maintained at 100%.

1 PLANT SHUTDOWNS: There were no plant shutdowns during the month of

March.

April J On April 9, the unit was shutdown for refueling.

i On April 20, fuel movement was started.

On April 28, fuel movement was completed.

PLANT SHUTDOWNS: April 9, scheduled shutdown-504.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Commenced J Cycle VII-VIII refueling outage.

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May On May 15, the reactor coolant system was filled and vented.

On May 17, the reactor was in hot shutdown.

On May 17, the reactor coolant system integrity test was completed.

On May 20, initial criticality was achieved for Cycle VIII.

On May 22, zero power physics tests were completed.

On May 23, the unit was returned to service, however, t'e reactor tripped on 10-10 steam generator level during startup. The unit was returned to service later on May 23.

On May 24, the unit was removed from service for turbine overspeed and torsion tests. Later on May 24 the unit was returned to service.

The unit was at 90% reactor power at the end of the month.

PLANT SHUTDOWNS: May 1, scheduled shutdown-540.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Continued Cycle VII-VIII refueling outage. The outage was concluded on 05/23/82.

May 23, forced shutdown-6.6 hours. A reactor / turbine trip occurred on lo-lo S/G level i

during power ascension while transferring S/G 1evel control from manual to automatic.

May 24, scheduled shutdown-5.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. A short outage was taken to perform turbine overspeed and i

l torsion tests.

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Q June On June 1, upon completion of the 90% power physics testing, power was-increased to 100%.

On June 20, the monthly turbine stop valve operability test was per-formed.

1 i From June 14 to June 21, power .was reduced to 95% for repair of

! Feedwater Heater 158.

The unit was at full load at the end of the month.

PLANT SHUTDOWNS: There were no plant shutdowns during the month of 1 June.

July i n On July 18, the monthly turbine stop valve operability test was per-formed. The unit was then returned to full load.

PLANT SHUTDOWNS: There were no plant shutdowns during the month , of 1

July.

f August 3

. On August 15, unit generation was reduced to perform the monthly tur-bine stop valve test. The unit was then returned to full load.

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PLANT SHUTDOWNS

There were no plant shutdowns during the month of i-August.

September On September 12, unit generation was reduced to perform the monthly turbine stop valve test. The unit was then returned to full load.

! PLANT SHUTDOWNS: There were no plant shutdowns during the month of j ,

September.

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October On October 10, unit generation was reduced to perform the monthly turbine stop valve test. The unit was then returned to full load.

PLANT SHUTDOWNS: -There were no plant shutdowns during the month of ,

October.

November On November 7, unit generation was reduced to perform the monthly tur-bine stop valve test. The unit was then returned to full load.

PLANT SHUTDOWNS: There were no plant shutdowns during the month of November.

December On December 6, load was decreased to 50% to remove FWP 1A from service to inspect a noisy speed increaser. The monthly turbine stop valve O

L/ operability test was also completed. FWP 1A was returned to service on December 8, and generation was increased to 100%.

On December 27, a laak in an elbow on the drain line from MSR 181 to the heater drain tank forced a manual trip of the turbine. The unit was returned to service on December 28.

1 On December 30, a leak in an elbow on the MSR 181 drain to FWH 158 forced a reduction to 50% power to remove the FWH from service.

Later the same day, the unit was returned to 100% power and FWH ISB was put back in service.

PLANT SHUTDOWNS: Deceniber 27, forced shutdown-33.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The reac-tor and turbine were manually tripped due to a steam leak in a line between a moisture separator and the r

U heater drain tank.

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o-i JANUARY FEBRUARY MARCH APRIL MAY JUNE q 1982 5 4

Figure-1-1 (Page 1 of 2) KEWAUNEE POWER HISTORY

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Figure .1-1 (Page 2 of 2) --- KEWAUNEE POWER HISTORY r 4 . AVER AGE DAILY MWE - NET

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TABLE 2.1 (Page 1 of 2) ,

ELECTRICAL. POWER GENERAlI0N DATA (1982) .

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January February March April May June Hours RX was critical 744.0 672.0 744.0 216.0 247.5 720.0 0.0 0.0 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0

, Hours Generator On-Line 744.0 672.0 744.0 215.3 191.1 720.0 0.0 0.0 Unit Reserve Shutdown Hours 0.0 O.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1,203,474 1,075,185 1,224,649 326,008 208,610 1,163,350 ,

Gross Elec. Energy Generated (MWH) 392,700 350,400 399,200 106,400 68,900 382,600 e

Net Elec. Energy Generated (MWH) 374,918 334,378 - 381,464 101,354 64,587 364,237 RX Service Factor 100.0 100.0 100.0 30.0 33.3 100.0 RX Availability Factor 100.0 100.0 100.0 30.0 33.3 100.0 Unit Service Factor 100.0 100.0 100.0 29.9 25.7- 100.0 l Unit Availability Factor 100.0 100.0 100.0 29.9 25.7 100.0 i Unit Capacity Factor (using MDC net) 97.8 96.6 99.6 27.3 16.9 98.2 l

Unit Capacity Factor (using DER net) 94.2 93.0 95.8 26.3 16.2 94.6 i Unit Forced. Outage Rate 0.0 0.0 0.0 0.0 3.3 0.0

! Hours in Month 744 672 744 720 744 720 i

I Net MDC (Mv1) 515 515 515 515 515 515 i

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ELECTRICAL POWER GENERATION DATA (1982)

MONTHLY July August September October November December Hours RX was critical 744.0 744.0 720.0 745.0 720.0 733.3 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744.0 744.0 720.0 745.0 720.0 710.3 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1,218,118 1,222,402 1,180,708 1,214,805 1,178,287 1,077,471 Gross Elec. Energy Generated (MWH) 399,900 396,600 385,100 396,400 386,200 350,800 Net Elec. Energy Generated (MWH) 380,766 377,408 366,655 377,319 367,723 334,042 RX Service Factor 100.0 100.0 100.0 100.0 100.0 98.6 RX Availability Factor 100.0 100.0 100.0 100.0 100.0 98.6 Unit Service Factor 100.0 100.0 100.0 100.0 100.0 95.5 Unit Availability Factor 100.0 100.0 100.0 100.0 100.0 95.5 l

Unit Capacity Factor (using MDC net) 99.4 98.5 98.9 99.1 99.9 87.4 Unit Capacity Factor (using DER net) 95.7 94.8 95.2 94.7. 95.5 83.9 Unit Forced Outage Rate 0.0 0.0 0.0 0.0 0.0 4.5 744 744 720 745 720 744 Hours in Month 515 515 515 511 511 514 Net MDC (Mwe)

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TABLE 2.2 i ELECTRICAL POWER GENERATION DATA

.1982 Year Cumulative Hours RX was critical 7,749.7 -63,751.6 RX Reserve Shutdown Hours 0.0 2,330.5 Hours Generator On-Line 7,669.8 62,476.6 Unit Reserve Shutdown Hours 0.0 10.0 Gross Thermal Energy Generated (MWH) 12,293,067 97,100,001 Gross Elec. Energy Generated (MWH) 4,015,200 31, % 7,600 Net Elec. Energy Generated (MWH) 3,824,851 30,425,108 RX Service Factor 88.5 85.1 RX Availability Factor 88.5 88.2 i

Unit Service Factor 87.6 83.4 Unit Availability Factor 87.6 83.4 Unit Capacity Factor (using MDC net) 84.9 77.8 Unit Capacity Factor (using DER net) 81.6 75.9 Unit Forced Outage Rate 0.5 4.3 Hours in Reporting Period 8,760 74,905 O

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3.0 . PLANT MODIFICATIONS, TESTS AND EXPERIMENTS (O

s This section is ,provided in accordance with the requirements of Part 50.59 (b) to title 10, Code of Federal Regulations (10CFR50.59(b)). This regulation allows licensees to make changes in the facility as described in the Safety Analysis Report, make changes in procedures as described in the Safety Analysis Report, and conduct tests and experiments not described in the Safety Analysis Report wi thout prior NRC approval provided the change, test or experiment does not involve a change in the Technical Specifications or an unre-viewed safety question. 10CFR50.59(b) requires that such changes be reported on an annual basis.

3.1 PLANT MODIFICATIONS, 10CFR50.59 g There were no modifications during 1982 which introduced an unre-V viewed safety question and, therefore, prior NRC approval was not required.

The following sumary of modifications includes those significant modifications completed during 1982 and not previously reported.

Many of these modifications are not specifically required to be reported by 10CFR50.59(b) since they do not constitute a change in the f acility "as described in the Safety Analysis Report,"

however, they are considered to be of significance, warranting mention in this report.

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Boric Acid Heat Tracing Alarm The Boric Acid Heat Tracing Trendscan Alarm units were modified to allow alarm setpoints at two different temperatures. Safety related zones will alarm at a higher temperature than non-safety related zones. (DCR 1113)

Surmiary of Safety Evaluation The change reduced the number of nuisance alarms, allowing opera-tors to respond more rapidly to safety related alarms.

Auxiliary Feedwater The DC power supply was modified to provide different trains of safe-guard power to the AFW pump discharge cross-connect motor valves.

(DCR 1039)

Summary of Safety Evaluation Separate power sources ensures the ability to remotely isolate the AFW trains in case of an AFW pipe break and loss of one train of power.

Reactor Coolant Pumps The automatic Reactor Coolant Pump trip on Safety Injection was removed. (DCR 1128)

Surmiary of Safety Evaluation Removal of the automatic trip will prevent unnecessary natural 4

circulation cooldowns. The pumps can be tripped manually if necessary.

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The. safety injection pumps were modified to prevent axial movement of the impeller- during abnormal modes of operation. (DCR 693)

Summary of Safety Evaluation The modification of the pumps increases their reliability by eli-minating an identified failure mode.

Containment A containment wide range pressure indicatior, system was installed as part of the post-accident monitoring capabilities requested by the NRC as a result of the accident at Three Mile Island. (DCR 885)

Summary of Safety Evaluation Tnis instrumentation provides additional information for dealing

-~ with a post-accident situation.

Containment The Integrated Leak Rate Test (ILRT) instrumentation was sent to the vendor so the Data Acquisition System portion could upgraded to the requirements of ANSI /ANS 56.8-1981. The modification will be completed, a calibration performed and the unit returned to Kewaunee immediately prior to the next ILRT. (DCR 1206)

Summary of Safety Evaluation The modified system will be more reliable and will produce better data than the old system.

Environmental Qualification Electrical equipment in various systems was upgraded to improve its environmental qualifications. These upgrades included:

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- Installation of Conax seals on the limit switches for several valves in CVCS, PS, SS, and RC systems. (DCR 1038)

- Inspection of and replacement of parts in some limitorque valve

' actuators and/or the associated limit switches in CVCS, SI, MS and RBV systems. (DCR's 1148, 1149, 1150 and 1151)

- Replacement of several limit switches in RBV, ASV and CVCS systems. (DCR's 1161, 1185 and 1186)

- Replacement of several pressure and differential pressure transmitters in CS, MS, RCS, RHR, SI and RBV systems. (DCR's 1118, 1119, 1120, 1121, 1122, 1132 and 1134)

- Replacement ~ of motors in the RHR pump pit fan coi? units.

(DCR 1182)

- Replacement,. relocation or addition of several OT2 switches and/or Clark relays in R3V, ACA, and MJS systems (DCR's 1125 and 1126)

- Addition of an environmentally qualified motor control center (MCC 1-62J) and shif ting of safeguards loads from MCC 1-62F to MCC 1-62J. (DCR 1117)

Sumary of Safety Evaluation In each case the modification increases the reliability and operability of the associated system by having components more qualified for operation in a post-LOCA environment.

Diesel Generator - Mechanical l Air coolers and dryers were installed in the diesel generator air 1

start system. (DCR 975) lO I

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F Summary of Safety Evaluation j Moisture in the air will be reduced. This will diminish the ,

moisture induced corrosion and associated component failures which had affected system reliability.

i 4160V Supply Transformers Tap Change Due to a tap change on Transformer Bank 10 in the substation, tap changes were made on the Reserve and Tertiary Auxiliary Transformers.

This maintained the station 4160V distribution voltage near nominal.

(DCR 1167) i Summary of Safety Evaluation j The tap changes that were made offset the . substation tap change  ;

and prevented a potential overvoltage problem.

4160V-Supply and Distribution i Bus 1-1 and 1-2 were reconductored from 3000A aluminum to 4000A copper bus. (DCR 989)

Summary of Safety Evaluation This change decreases the probability of bus failures and the j associated plant transient.

Safeguard Motor Overload Protection Safeguard motor overload protection heaters were changed as necessary i

l to ensure proper sizing. (DCR 1160)

Summary of Safety Evaluation Proper sizing of the heaters ensures that all safeguard motors will start and run when required even with a degraded supply voltage. It also protects motors from long term overload damage.

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Emergency Lighting and Heating Boiler Auxiliaries Lights, receptacles, heating boiler auxiliaries and various other motors were shifted from buses 1-3 and 1-4 to bus 1-46. This bus will be powered by a diesel generator in case of a plant blackout. The Jockey Fire Pump was moved from normal to safeguard power. (DCR 1010)

Sumary of Safety Evaluation Safety related portion of the DCR was transfer of the Jockey Fire Pump. The transfer improved the capacity margin of the Safeguard Diesels by allowing the fire system water. pressure to be main-tained without running the fire pumps.

Fire Protection The reactor coolant pump vault foam fire suppression system was removed and a reactor coolant pump oil collection system was installed in each of the pump vaults. (DCR 1024)

Summary of Safety Evaluation Appendix R to 10CFR50 required this' modification. The fire control afforded by this modification assures that safe shutdown capability will not be degraded by a reactor coolant pump oil fire.

Cranes The auxiliary building 125/10 ton fuel handling crane was modified electrically from intermittent duty to a continuous duty rating. The electrification system was upgraded from insulated bar to a flat cable festoon system. (DCR 860)

Summary of Safety Evaluation Both the reliability and operability of the crane have been enhanced.

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t Steam Generator Blowdown Treatment

) A filter system was added in the blowdown discharge piping to ensure the copper and iron in the blowdown effluent are within the limits of our WPDES permit. (DCR 1096)

Summary of Safety Evaluation This modification is not nuclear safety related.

Warning System A siren system was installed to notify the population around the plant of an emergency. This warning system is a combined system of the Point Beach fluclear Plant and the Kewaunee Nuclear Plant systems, because of their overlapping emergency planning zones. The sirens were installed as a part of 10CFR50 Appendix E.

Summary of Safety Evaluation

! /7 The sirens will be sounded when an emergency is in progress in

V which protective action is required or is imminent. This alerting sound should remind people hearing it to turn their radio to an Emergency Broadcast System.

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} l-j i r i i i 3.2 TESTS AND EXPERIMENTS, 10CFR50.59 There were no tests or experiments performed in 1982 which have :

i i not been described in the safety analysis, i

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4.0 LICENSEE EVENT REPORTS This section is a sumary of the 36 Licensee Event Reports (LER) sub-mitted to the NRC in 1982 in accordance with the requirements of Technical Specifications. None of the LER's in 1982 posed a threat to plant operation or public safety.

LER 82-01 During an operability check of zone special ventilation, exhaust fan 1B failed to start. The solenoid valve failed as result of the sole-noid sticking. The solenoid valve was replaced and the system tested operable within Technical Specification time limits.

LER 82-02 During normal operation, a deviation in pressurizer level indication was noted. A calibration check found pressurizer level transmitter LT 427 out of specification, low; the reactor trip signal for that channel would have occurred at 91.8%. This is 1.8% higher than allowed by Technical Specifications. The redundant channels would have initiated the required protective action. The cause of this incident was attributed to instrument drift of the Barton transmitter.

The' transmitter was recalibrated and returned to service.

LER 82-03 During normal operations, lA zone SV fan started automatically. The f an operation was determined to be unnecessary and was taken out of p service after demonstrating 18 train of zone SV operable. The sole-l noid valve failed in the closed (safe) position due to a burned out l

coil, automatically opening the damper and starting the fan. The coil ,

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was replaced and the system tested operable within Technical

!.s _) Specification time limits.

LER 82-04 During RHR pump and valve testing, valve SI 3008 failed to close.

The redundant train was demonstrated operable. Valve sticking in this system has not been a recurring problem. The cause is unknown, since manual operation of the valve was successful, and multiple cycling of the valve from the control room revealed no further difficulties.

LER 82-05 During quarterly surveillance testing of service water pumps, lA2 ser-vice water pump failed to start on demand. The remaining service water pumps were available. The circuit breaker failed to close by remote auto or manual initiation, due to a failed open closing coil.

%- The coil was replaced, the circuit breaker was tested satisfactorily, and the service water pump was returned to service within Technical Specification time limits.

LER 82-06 During normal' operation, valve SI-209 (SI recirculation line to the refueling water storage tank) was taken out of service for minor corrective maintenance. The redundant valve was demonstrated operable. The valve was returned to service within Technical Spacification time limits.

LER 82-07 During the refueling outage, leak repair procedures on valve PS-1A (pressurizer spray) revealed significant boric acid corrosion wastage

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of the body-to-bonnet . bolts. Valve failure did not occur. Bolt p

'd degradation was caused by boric acid induced corrosion wastage. All bolts on this valve were visually inspected and the affected bolts replaced in kind.

LER 82-08 During the refueling outage, leak repair procedures on valve SI-138 (cold leg SI check valve) revealed significant boric acid corrosion wastage of body-to-bonnet bolts. Valve failure did not occur. Bolt a

degradation was caused by boric acid induced corrosion wastage. All bolts on this valve were visually inspected and the affected bolts replaced in kind.

LER 82-09 With the unit at hot shutdown prior to a scheduled refueling outage both _ source range nuclear instruments were inoperable. The source range detector failures were attributed to an accumulation of water in the instrument cannisters. A spare detector was installed until replacement of the normal channel detectors was made.

LER 82-10 During the refueling outage, surveillance testing indicated that one RCS flow transmitter was out of calibration. This instrument was out of calibration due to normal instrument drif t. The transmitter was recalibrated and tested satisfactorily.

LER 82-11 During the refueling outage, surveillance testing indicated that one RCS temperature transmitter was out of calibration. This transmitter 22

T was out of calibration due to normal instrument drift. The

) transmitter was recalibrated and tested satisfactorily.

LER 82-12 During the refueling ou tage, MS-1A (mainsteam header 1A isolation valve) was found to have a closure time in excess of Technical Specifications. Slow closure time was attributed to the valve having been closed and essentially dry, since the start of cold shutdown.

The valve shaft was cleaned and lubricated externally. The valve was tested and the closure time of the valve was within Technical Specification time limits.

LER 82-13 Preliminary analysis of piping load evaluation done in accordance with NUREG 0737, indicates that allowable stresses will be exceeded on the pressurizer safety loop seal piping when a safety valve opens.

This event occurs as a result of assuming the cold loop seal water clears the safety valve in an overpressure transient and the valve lifts with steam to accelerate the slug of water through the downstream piping. The analysis conservatively assumes that the pressurizer safety loop seal temperature is at 120 F and a cold slug of water is passed through the safety valve. Measurements at power show the temperature in the pressurizer vault in excess of 150 F, this could possibly change the results of the analysis. Final analysis and recommendations are being evaluated to determine the necessary long term corrective action.

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LER 82-14 m

(d During the refueling outage, surveillance testing indicated that the Turbine Driven AFW pump, 10, would not reach the required speed. The two motor driven AFW pumps were available. The pump's turbine governor valve was exercised. The governor was adjusted per manufacturer's technical manual, the pump was tested satisfactorily and returned to service within Technica!' Specification time limits.

LER 82-15 When trying to borate the RCS during physics testing, it was found that no boric acid flow could be obtained through the blender due to hardening of boric acid in the BAT to blender line at valve CVC-401.

The hardening in CVC-401 was caused by a failure of one train of heat tracing tape combined with removal of some insulation on that valve.

New heat tracing tape was installed and the insulation replaced in accordance with approved maintenance procedures.

LER 82-16 Charcoal adsorber test samples from one train of the Auxiliary Building Special Ventilation System indicated that filter efficiency was below 90% as required by Technical Specifications. Both trains of safeguards ventilation were available for operation and would have j removed iodine during discharges to the atmosphere, although one train l

l-at slightly less than 90% efficiency. The marginal efficiency was due to the charcoal adsorber cells having reached their natural end-of-life. Fifteen of the twenty-seven charcoal adsorber cells were i replaced which increased the overall filter efficiency to greater than 90%.

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LER 82-17 During a review of the health physics equipment testing schedule, it was noticed that a Strontium-90 calibration source was listed as having a 60.0 month frequency for leak testing instead of a 6.0 month frequency as required by Technical Specifications. Subsequent leak testing showed the source to be intact. A revision was submitted to the test :chedule to correct the error in testing frequency.

LER 82-18 During steady state operation, the 1A RHR pump was taken out of ser-vice to repair excessive shaf t seal leakage. Shaft seal leakage was due to a scored shaf t and excessive clearance on pump wear rings. A new impeller, shaf t, shaf t sleeve, and mechanical seal were installed; the pump was tested satisfactorily and placed back into service within

. Technical Specification time limits.

LER 82-19 The 1B shield building ventilation recirculation fan was taken out of service to perform corrective maintenance. Maintenance was required due to repeated trips of the circuit breaker during fan runs.

Circuit breaker tripping was attributed to a loose contactor block; the block was replaced and tightened down.

LER 82-20 The control rod deviation monitor failed to operate while performing a control rod exercise. The control rod deviation monitor failed to operate because the red positions had not been updated on the plant process computer following the last failure of the computer. The pro-O 25

cedure for performing a control rod exercise has been updated to d clarify actions that must be taken when the control rod deviation monitor fails.

LER 82-21 While performing a test on the containment fan coil units and asso-ciated duct work, it was found that measured flows were less than expected. An equivalent flow of three fan coil' units was demonstrated placing the plant in an LC0 per Technical Specifications. This is

~

reportable per Technical Specifications as a system requiring correc-

! tive measures to prevent operation in a manner less conservative than assumed in the accident analysis. A temporary change was made to fix the position of the containment fan coil unit dampers. However, further measurements have demonstrated that all four containment f an coil units will operate in accordance with their design requirements.

The low flow measurements were a result of fan interactions between the two fans feeding the common containment ring header duct work.

LER 82-22 With the plant operating under a LC0 per Technical Specifications, the 1A containment fan coil unit failed to restart during a test of the systems heat removal and flow capabilities. This failure placed the plant in a condition less conservative than the least conservative condition allowed by limiting conditions for operation and is repor-I table per Technical Specifications. The fan coil unit 1A tripped due to high instantaneous current caused by the f an having to overcome back pressure from the system which was increased by reconfiguration of damper positioning accomplished in a temporary change. The breaker was reset and the fan was started successfully.

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.. LER 82-23 V,-m During steady full power operation the 1A diesel generater was declared out of service because the associated start up air compressor was not maintaining proper pressure. The low air pressure was due to the suction valve on the secondary stage of the air compressor having a cracked leaf. The suction and relief valves were replaced, the diesel generator tested operable and was placed back in service within Technical Specification time limits.

LER 82-24 t While at full power operation it was observed that the overpower Delta-T channel 3 rod stop alarm was cycling in and out. The over '

power Delta-T rod stop alarm was due to a malfunction of the T AVG signal conditioner which caused the' channel to drif t. A spare signal-

[] conditioner box was installed, calibrated, and the channel returned to v

service.

LER 82-25 During a document review it was discovered that the waste disposal liquid effluent monitor was indicating low. Low count indication on the waste disposal monitor was due to a weak detector tube. Upon discovery no further discharges were made until the detector tube was replaced and detector calibrated.

LER 82-26 During steady full power operation, the IB boric acid transfer pump was taken out of service to repair an apparent seal leak. The seal leak was caused by a corroded carbon steel (CS) plug. The CS plug was O

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- _, . _ , , , . ~..,-w,i,, - - . - . , < . e - ,

replaced with a stainless steel plug. The pump was tested and returned to service within Technical Specification time limits.

LER 82-27 While performing a monthly surveillance test on the Shield Building Vent System, the train A recirculation damper, SBV 21A, failed to open and draw a vacuum within two minutes. The unsuccessful attempt to open the. recirculation damper was due to a failed static pressure controller. The controller was replaced and the damper placed in ser-vice within Technical Specification time limits.

LER 82-28 While at full power operation, a damper on Train A of the Auxiliary Building Special Ventilation System f ailed open (Safe) causing the zone SV fan to start automatically. The redundant train was tested O

V- operable prior to removing the affected train from service. One bad coil was replaced on the solenoid controlling the exhaust filter inlet damper. The system was tested and placed back in service within Technical Specification time limits.

LER 82-29 During a management review of plant surveillance requirements, it was

, discovered that the monthly testing requirements were exceeded for the containment radiation monitors R-ll and R-12. The backup radiation monitor to R-ll and R-12, R-21, was out of service waiting for parts.

With this monitor out of service, the automatic actions to be tested l

l by the surveillance were defeated. The surveillance procedure was set aside until R-21 was back in service, and by a personnel oversight,

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the testing period was exceeded. When the LC0 was discovered R-21 was V jumpered out allowing the test on R-ll and R-12 to be performed. The monitors were tested satisfactorily and declared back in service.

LER 82-30 Sensing lines for all six containment pressure transmitters were found capped inside containment. This rendered the transmitters inoperable and resulted in ~not having the minimum channels required for hi-containment pressure safety injection actuation and hi-hi contain-ment pressure for containment spray and steam line isolation.

Redundant instrumentation for safety injection and steam line isola-tion remained operable. During the local leak rate testing performed during the previous refueling outage, caps were inadvertently placed on the ends of the sensing lines. Upon discovery the caps were imme-7 diately removed.

(J The local leak rate testing procedure has been upgraded and the penetrations tagged to prevent future occurrence.

LER 82-31 During surveillance testing, the 18 train of Shield Building Vent (SBV) failed to switch over to recirculation mode af ter drawing a vacuum. The SBV Fan 1B recirculating damper failed to open due to a broken hydraulic pump on the electro-hydraulic damper actuator. The motor operator was replaced, the actuator was disassembled, inspected and refilled with fluid. The system was tested operable and placed back in service within Technical Specification time limits.

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LER 82-32

(/ During surveillance testing it was discovered that the outer door of-the containment personnel airlock exceeded leak rate specifications.

Since the inner airlock door remained tight, containment integrity was -

lost only momentarily as personnel entered through the inner door. A one-sixteenth inch thick shim was installed under the outer seal and the door was retested satisfactorily.

LER 82-33 During surveillance testing, valve SW-903B, containment fan coil unit service water outlet valve, would not open electrically. Prior to the test the valve was open and the fan coil unit was operating properly.

The Surveillance Procedure requires closing the valve to perform the test. The gear limit switch was adjusted and the valve was cycled

() satisfactorily.

LER 82-34 While performing a surveillance test on the AFW system, valve MS-100A (main steam to turbine driven AFW pump), torqued out when closing.

The torque switch was found to be sticking and the manual de-clutch unit was out of adjustment. The torque switch, grease and tripper assembly were replaced and the operator rebuilt. The valve was retested satisfactorily.

LER 82-35 During full power operation a pinhole leak was discovered in the suc-tion line from the VCT to the charging pumps. This event is report-able per Technical Specifications as an abnormal degradation of a D

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system designed to contain radioactive materials. Th'e Chemical and t

( Volume Control System remained operable. The piping leak was attri-buted to vibrations and pulsations in the associated piping. The leak was plugged using a standard maintenance procedure and visually inspected. This section of piping is scheduled to be replaced during

< the upcoming refueling outage.

LER 82-36 During startup operations following a reactor trip, the level in the 5

condensate water storage tank (CST) . went below the Technical -

i Specification limit. Normal CST water usage during plant startup caused the CST level to go below the Technical Specification limit.. A Technical Specification proposed revision has been submitted (02-20-81), and is under NRC review, to permit the CST level to drop

( below 75,000 gallons during plant startup.

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5.0 FUEL INSPECTION REPORT During Refueling #7, thirty six (36) fresh Region J assemblies were loaded for Cycle VIII. Startup physics testing was performed and reported in Cycle VIII Startup Report.

The irradiated fuel inspection was performed with an underwater TV camera. All peripheral fuel rods were examined using one-half face scans. Nine assemblies were inspected, including one each of regions E and F, three region G, and two each of regions H and I. All assemblies exhibit rod slippage to various degrees. Numerous scrapes to the rodlets, grids, and top and bottom nozzles were also noted.

However, no damage to the cladding or supporting structures was observed. All assemblies exhibited axially varying crud deposits with deposits on the I assemblies being light to negligible. On the

( others, it was moderate' to heavy. Overall condition of the fuel was excellent with no evidence of fuel cladding degradation on the fuel rods examined. Complete video tapes were made of all examinations.

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6.0 CHALLENGES TO AND FAILURES OF PRESSURIZER SAFETY AND RELIEF VALVES There were no challenges to or failures of pressurizer safety or relief valves during 1982.

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7.0 STEAM GENERATOR TUBE INSPECTION 7.1 Eddy Current Testing There . was no eddy current testing performed on steam generator tubes during 1982.

The next scheduled eddy current testing, in accordance with the Kewaunee Inservice Inspection Program, will be during the 1983 1 refueling outage.

7.2 Sludge Lancing 'r Tubesheet cleaning was performed on both steam generators during i

the Kewaunee Nuclear Plant outage in April, 1982, using the full recirculation method in accordance with Westinghouse Procedure MRS 2.2.2 GEN-9.

V Sludge lancing began on April 14, 1982, af ter all water balance

measurements were completed. Steam Generator "A" was completed during the night shift of April 14, 1982. The equipment was then moved to Steam Generator "B" and sludge lancing' was completed on "B" generator during the night shift of April 15, 1982.

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E 8.0 PERSONNEL EXPOSURE AND MONITORING REPORT Pursuant to 10CFR20.407(a)(2), and 20.407(b), a tabulation of the number of individuals for whom monitoring was provided is shown on the following table:

1982 NUMBER OF INDIVIDUALS FOR WHOM PERSONNEL MONITORING WAS PROVIDED Exp. Range (mR) No. of Personnel _

No Measurable 300

< 100 161 100 - 249 65 250 - 499 61 500 - 749 29 750 - 999

~

25 1000 - 1999 11 2000 - 2999 1 Grand Total 653 A tabulation of numbers of personnel exposure and man-rem received by work and job function is shown on the following table in accordance with Section 6.9.1.b of the Kewaunee Nuclear Power Plant Technical-Specification. The table shows the total man-rem exposure for the i year was 89.367.

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9.0 ENVIRONMENTAL TECHNICAL SPECIFICATIONS (APPENDIX B) 3 The Environmental Technical Specifications (Appendix B) to the (G

Kewaunee Nuclear Plant's Technical Specifications were deleted by Amendment 47, November 29, 1982. This information is reported monthly to the State of Wisconsin under the Wisconsin Pollution Discharge Elimination System (WPDES) Permit Number WI-00001571 issued by the State of Wisconsin, Department of Natural Resources for the Kewaunee Nuclear Power Plant.

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10.0 RADIOLOGICAL MONITORING PROGRAM Attached is the report from Hazleton Environmental Sciences Corporation on the Radiological Monitoring Program for Kewaunee Nuclear Plant for 1982.

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$ HAZLETON ENVIRONMENTAL SCIENCES A OlVISION OF HAZLETON LABORATORIES AME AICA. INC.

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} 1500 FAONTAGE ACAD. NOATHBAOOK. lLLINCIS 60082. U S A REPORT TO WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADISON GAS AND ELECTRIC COMPANY r RADIOLOGICAL MONITORING PROGRAM FOR THE KEWAUNEE NUCLEAR POWER PLANT KEWAUNEE, WISCONSIN ANNUAL REPORT - PART I

SUMMARY

AND INTERPRETATION January - December 1982

^

(,)

, HAZLETON ENVIRONMENTAL SCIENCES PROJECT NO. 8002-100 PREPARED AND SUBMITTED BY HAZLETON ENVIRONMENTAL SCIENCES CORPORATION

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Report Approved by: , , LL '

L. G. Hueb'ner, M.' S.

Director, Nuclear Sciences p

V 11 February 1983 PHONE (31Pi S6 4 -0 700 o TE LE M 20 94H3(HA/E S NHFml

HAZLETON ENVIRONMENTAL SCIENCES O

PREFACE The staff members of the Nuclear Sciences Department of Hazleton Environmen-tal Sciences, a Division of Hazleton Laboratories America, Inc (HES), were responsible for the acquisition of data presented in this report Assistance in sample collection was provided by Wisconsin Public Service Corporation personnel.

The report was prepared by C. R. Marucut, Section Supervisor, under the direction of 1.. G. Huebner, Director, Nuclear Sciences. She was assisted in repcrt preparation by L. Nicia, Group Leader, and other staff members of the Nuclear Sciences Department (HES).

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HAZLETON ENVIRONMENTAL SCIENCES

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TABLE OF CONTENTS Page Preface . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii

List of Figures . . . . . . . . . . . . . . . . . . . . . . . . iv List of Tables ........................ v

1.0 INTRODUCTION

......................... 1 2.0

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.0 RADIOLOGICAL SURVEILLANCE PROGRAM . . . . . . . . . . . . . . . 3 3.1 Methodology ....................... 3 3.1.1 The Ai r Progr am . . . . . . . . . . . . . . . . . . 3 3.1.2 The Terrestrial Program . . . . . . . . . . . . . . 4 3.1.3 The Aquatic Program . . . . . . . . . . . . . . . . 5 3.1.4 Progr am Execution . . . . . . . . . . . . . . . . . 6 3.1.5 Program Modifications . . . . . . . . . . . . . . . 7 3.2 Results and Discussion . . . . . . . . . . . . . . . . . . 7 3.2.1 The Effect of Chinese Atmospheric Nuclear Detonation . . . . . . . . . . . . . . . . . . . . 7 3.2.2 The Air Environment. . . . . . . . . . . . . . . . . 8 3.2.3 The Terrestrial Environment. . . . . . . . . .... 9 3.2.4 The Aquatic Environment. . . . . . . . . . . . . . . 12

4. 0 FIGURES AND TABLES . . . . . . . . . . . . . . . . . . . . . . . 15

5.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . 32 APPENDICES

, A. Cros sch ec k Progr am Res ul t s . . . . . . . . . . . . . . . . . A-1 B. Statistical Notations. . . . . . . . . . . . . . . . . . . . B-1 C. Maximum Permissible Concentrations of Radioactivity in Air and Water above datural Background in Unrestricted Areas . . . . . . . . . . . . . . . . . . . . . . . . . . C-1 l

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HAZLETON ENVIRONMENTAL SCIENCES  ;

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LIST OF FIGURES No. Caption gqe 4-1 Sampling locations, Kewaunee Nuclear Power Plant . ...... 16 l

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T HAZLETON ENVIRONMENTAL SCIENCES O

LIST OF TABLES 4

i . No. Title Page, 41 Sampling locations, Kewaunee Nuclear Power Plant .... . . 17 4.2 Type and frequency of collection ... .... ... .. 18 4.3 Sample codes used in Table 4.2 ............... . 19 4.4 Sampling Summary . . . . . ........ ... . ... 20 4.5 Environmental Radiological Monitoring Program Summary. . . . . . . 21 In addition, the following tables are in the Appendix:

Aypendix A A-1 Crosscheck program results, milk and water samples, 1975-82. . . . A-3 I A-2 Crosscheck program results, thermoluminescent dosimeters (TLDs). . A-9 Appendix C C-1 Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas . . . C-2 i

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3 HAZLETON ENVIRONMENTAL SCIENCES O

3

1.0 INTRODUCTION

1 The Kewaunee Nuclear Power Plant is a 540 megawatt pressurized water reactor located on the Wisconsin shore of Lake Michigan in Kewaunee Coun ty. The Kewaunee Nuclear Power Plant became critical on March 7,1974. Initial power 4

generation was achieved on April 8,1974, and the Plant was declared commer-cial on June 16, 1974. This report summarizes the environmental operation data collected during the period January - December 1982.

Wisconsin Public Service Corporation, an operating company for the Kewaunee Nuclear Power Plant, assumes the responsibility for the environmental program i at the Plant and any questions relating to this subject should be directed to them.

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SUMMARY

Results of sample analyses during the period January - December 1982 are summarized in Table 4.5. Radionuclide concentrations measured at indicator locations are compared with levels measured at control locations and in preop-erational studies. The comparisons indicate background-level radioactivities in all samples collected with the following exceptions:

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l. Results obtained for gross beta in airborne particulates collected during the first quarter of 1982 show a moderate residual effect of f allout from atmospheric nuclear detonationo' f a 200 kiloton to 1 megaton range device on 16 October 1980. Presence of other fission products, mostly strontium

-90 and cesium-137 in some of the sampling media indicates a long range effect on the environment from f allout resulting from previous atmospheric nuclear tests.

2. Trace amounts of manganese-54, cobalt-58, and cobalt-60 were detected in a two of ten periphyton samples and trace amounts of cobalt-58 and cobalt-60 were detected in five of twenty bottom sediment samples. Presence of these isotopes in these samples is probably plant related.

3. Four water samples collected at the discharge (K-1d) on January 6, April 1, July 6, and December 6,1982 had tritium levels of 1,240 pCi/1, 530 pCi/1, 440 pCi/1, and 2190 pCi/l above the background level of 420 pCi/1.

The elevated levels in samples collected at the discharge are attributable

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to the Kewaunee Nuclear Plant operation, but constitute 0.07% or less of the maximum permissible concentration of 3,000,000 pCi/l established in the 10 CFR 20 Document. ,

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3.0 RADIOLOGICAL SURVEILLANCE PROGRAM Following is a description of the Radiological Surveillance Program and its execution.

3.1 Methodology The sampling locations are shown in Figure 4-1. Table 4.1 describes the-locations, lists for each its direction and distance from the reactor, and indicates which are indicator and which are control locations.

The sampling program monitors the air, terrestrial, and aquatic envi-ronments. The types of samples collected at each location and the.

frequency of collections are presented in Table 4.2 using sample codes defined in Table 4.3. The collections and analyses that comprise the program are described below. Fi nally, the execution of the program in the current reporting year is discussed.

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'u J 3.1.1 The Air Program The airborne particulate samples are collected on 47 mra diameter membrane filters of 0.8 micron porosity at a volumetric rate of approximately one cubic foot per minute. The filters are col-lected weekly from six locations (K-1f, K-2, K-7, K-8, K-15, and K-16), and dispatched by n' ail to Hazleton Environmental Sciences for radiometric analysis. The material on the filter is counted for gross alpha and beta activity approximately five days after receipt to allow for decay of naturally-occurring short-lived radionuclides.

i Quarterly composites from each sampling location are analyzed for gamma-emitting isotopes by Ge(Li) detector.

The integrated gamma-ray background is measured at air sampling locations (K-1f, K-2, K-7, K-8, K-15, and K-16) and at four milk sampling locations (K-3 through K-6) with ion chambers and thermoluminescent dosimeters (TLDs). Ion chambers are placed in duplicate and read monthly. CaF2 :Mn bulb TLDs are exchanged quarterly and annually.

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'v l Charcoal filters are located at locations K-1f, K-2, K-7, K-8, K-15, and K-16. The filters are changed bi-weekly and analyzed for iodine-131 immediately after arrival at the laboratory.

Monthly composites of precipitation samples collected at K-11 are analyzed for tritium activity by liquid scintillation technique.

3.1.2 The Terrestrial Program Milk samples are collected weekly (one gallon from each location) from May through October and monthly (two gallons from each location) during the rest of the year from four herds that graze within four miles of the reactor site (K-4, K-5, K-12, and K-19) and from two herds that graze between four and ten miles from the reactor site (K-3 and K-6). The milk samples are analyzed for fodine-131, strontium-89 and -90, cesium-137, barium-140, potas-stum-40, calcium, and stable potassium.

One-gallon water samples are collected quarterly from four p

V off-site wells located at K-10, K-11, K-12, and K-13. Monthly one-gallon w Aer samples are collected from two on-site wells located at K-1g and K-lh.

The gross alpha and beta activities are determined on the total

residue of each water sample. The concentration of potassium-40 is calculated from total potassium, which is determined by flame photometry on all samples. The tritium levels in quarterly composites of monthly on-site samples from K-19 are detennined by liquid scintillation technique.

i Quarterly composites of monthly grab samples of water from onc on-site well (K-19) are analyzed for strontium-89 and strontium-90.

Domestic meat samples (chickens) are obtained annually (in the third quarter) at locations K-17, K-20, K-2 4 ', and K-25. The flesh is separated from the bones, gamma scanned, and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activi ties. .

Eggs are collected quarterly at Location K-17. The samples are gamma scanned and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.

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Vegetable samples (5 varieties) are collected at locations K-17 and K-18, and two varieties of grain, if available, at location K-23. The samples are gamma scanned and analyzed for gross al pha , gross beta, strontium-89, and strontium-90 activities.

Grass samples are collected during the second, third and fourth quarters from two on-site locations (K-lb and K-1f) and from six dairy farms (K-3', K-4, K-5, K-6, K-12, and K-19). The samples are gamma scanned and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities. During the first quarter cattle feed is collected from the same six dairy farms, and the same analyses are perfonned.

Soil samples are collected twice a year on-site at K-if and from the six dairy farms (K-3, K-4, K-5, K-6, K-12, and K-19).

The samples are gamma scanned and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.

3.1.3 The Aquatic Program D

d One-gallon water samples are taken monthly from three scations on Lake Michigan: 1) at the point where the condenser water is discharged into Lake Michigan (K-id); 2) at Two Creeks Park (K-14) located 2.5 miles south of the reactor site; and 3) at the Rostok water intake (K-9) located 11.5 miles north of the reactor site. Additionally, one-gallon water samples are taken monthly from three creeks that pass through the site. (K-la, K-lb, and K-le). Samples from North and Middle Creeks (K-la, l K-lb) are collected near the mouth of each creek. Samples from l the South Creek (K-le) are collected about ten feet downstream from the point where the outflows from the two drain pipes meet.

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The water samples are analyzed for gross alpha and gross beta activity in the total residue, dissolved solids, and suspended solids. The concentration of potassium-40 is calculated from total potassium, which is determined by flame photometry. The tritium activity in the Lake Michigan samples is determined by liquid scintillation technique. Quarterly composites of monthly grab samples from Lake Michigan are also analyzed for strontium-89 and strontium-90.

Fish samples (2 species) are collected in the second, third, and fourth quarters at Location K-1d. The flesh is separated l9 V

from the bones, gamma scanned and analyzed for gross alpha and gross beta activity. Ashed bone samples are analyzed for gross 5

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4 alpha, gross beta, strontium-89 and strontium-90 activi ties.

Bottom organisms are collected in the second, third and fourth quarters from the discharge canal area (K-Id), Rostok water intake (K-9), and Two Creeks Park (K-14). Samples are analyzed for gross alpha and gross beta activities and are also gamma scanned if available in sufficient quantity.

Slime samples are collected during the second and third quar-ters from three Lake Michigan locations (K-id, K-9, and K-14),

and from three creek . locations (K-la, K-lb, and K-le), if available. The samples are analyzed for gross alpha and gross beta activities. If the quantity is sufficient, they are also gamma scanned and analyzed for strontium -89 and strontium-90 activities.

Bottom sediments are collected four times a year from five locations (K-ic, K-1d, K-lj, K-9, and K-14). The samples are analyzed for gross alpha and gross beta activities and for strontium-89 and strontium-90. Each sample is also gamma Q

b scanned. Since it is known that the measured radioactivity per unit mass of' sediment increases with decreasing particle size, the sampling procedure is designed to assure collection of very fine particles.

3.1.4 Program Execution Program execution is sunmarized in Table 4.4. The program was executed as described in the preceding sections with the following exceptions:

(1) One of the two ion chambers at location K-7 for the month of May could not be read because the chamber read full l scale.

l (2) No buckwheat was collected at location K-23 because it was j not grown there in 1982.

l (3) No gamma-spectroscopic data could be obtained on all three bottom organi sm samples. Attempts were made to collect bottom organisms during this sampling period but the popula-tion of bottom organisms at the sampling location was very sparse and it was not possible to collect samples of suf-ficient quantity for gamma-spectroscopic analysis.

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l 3.1.5 Program Modifications In compliance with Amendment 44 to the Technical Specifications, dated May 4,1982, collection of bottom organisms and deployment of ion chambers was dropped from the program effective June 1, 1982.

3.2 Results and Discussion The results for the reporting period January to December 1982 are presented in :ummary form in Table 4.5. For each type of analysis of each sampled medium, this table shows the annual mean and range for all indicator locations and for all control locations. The loca-tion with the highest annual mean and the results for this location are also given.

The discussion of the results has been divided into three broad cate-gories: the air, terrestrial, and aquatic environments. Within each category, samples will be discussed in the order listed in Table 4.4.

Any discussion of previous environmental data for the Kewaunee Nuclear Power Plant refers to data collected by Hazleton Environmental Sciences,

-tO- NALC0 Environmental Sciences, or Industrial BIO-TEST Laboratories, Inc. .

The tabulated results ;f all measurements made in 1982 are not included in this section, although references to these results will be made in the discussion. The complete tabulation of the 1982 results is con-tained in Part II of the 1982 annual report on the Radiological Moni-toring Program for the Kewaunee Nuclear Power Plant.

3.2.1 'The Effect of Chinese Atomspheric Nuclear Detonation '

There were no reported atmospheric nuclear tests in 1982. The last reported test was conducted by the People's Republic of China on 16 October 1980. The reported yield was in the 200 kiloton to 1 megaton range.

There was a moderate residual effect of this test on the gross beta levels in airborne particulates. The annual mean gross beta activity was about two times higher than in 1980. The highest ,

activity was reached in the first quarter and declined gradually ,

to the 1980 level by mid-summer. It then rose by the end of the year to approximately twice the activity observed in 1980. Also, o the presence of fission products, such as strontium -89 and -90, t

' and cesium-137 in some of the sampled media is attributable to the most recent (16 October 1980) and previous tests in the atmosphere.

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f 3.2.2 The Air Environment For air particulates, both gross alpha and gross beta measurements yielded annual means that were nearly identical for the indicator and control locations. The annual mean activity for gross alpha was about the same as in 1981. Mean gross beta level decreased by a factor of two and a half in comparison to the 1981 level, but was still higher by approximately a factor of two to the pre-bomb test in October 1980. The highest annual means for both gross alpha and gross beta, were measured at control location K-16, 26 miles NW of the station.

Gross alpha and beta activities at all locations were also anal-yzed by quarters. The highest averages for gross alpha and beta were for the first quarter. The activity declined gradually to the 1980 level by mid-summer, then rose slightly by the end of the year. The elevated activity in the first quarter was due to an early spring peak, which has been observed almost annually (1976 and 1979 were exceptions) for many years (Wilson et al . ,

1969). The spring peak has been attributed to fallout of nuclides O from the stratosphere (Gold et al .,1964).

< V Gamma spectroscopic analysis of quarterly composites of air particulate filters - yielded similar results for indicator and control locations. Beryllium-7 which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955) was detected in seven of twenty-four samples. A trace of cerium-141 was detected in one sample. There was no indication of a station effect on the data.

All other gamma-emmitting isotopes were below their respective LLD limits.

Bi-monthly levels of airborne iodine-131 were below the lower

limi t of detection (LLD) of 0.01 pCi/m3 at all locations.

Thus, there is no indication of an effect of the plant operation on the local air environment.

Ambient gamma radiation was monitored by ion chambers and TLD's at eleven locations: four indicator and seven control.

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V For the ion chambers at the indicator locations, the radiation exposure averaged (5.510.7)* mR/30 days, while the control loca-tions averaged (5.810.8) mR/30 days. In both cases, the range was approximately 15% of the mean. The two means may be considered to be in agreement since their difference is smaller than the sum of their estimated uncertainties. The location with the highest annual mean (6.710.3) mR/30 days was the control location K-8, 5 miles WSW of the plant. Since .this location is so distant from the plant and since it typically yielded the highest monthly ion-chamber readings during the pre-operational studies prior to 1974, the high result is not attributable to the plant operation.

The quarterly TLDs at the indicator locations measured a mean dose equivalent of (55.217.8) mrem /365 days, in agreement with the mean at the control 1ccations of (56.116.1) mrem /365 days, and were slightly lower than the means obtained in 1979 (69.3 and 73.1 mrem /365 days, respectively), in 1980 (72.0 and 75.8 mrem /365 days, respectively), and in 1981 (61.2 and 63.1 mrem /365 days, respectively). The quarterly measurements agreed with the annual measurements which were (67.115.8) mrem /365 days, for the indicator and (68.9t9.1) mrem /365 days for the control locations.

All of these values are slightly lower than the United States O

V average value of 78 mrem / year due to natural background radiation (National Council on Radiation Protection and Measurements,1975).

The highest mens for the quarterly and annual TLDs were 65.0 and 79.0 mrem /365 days and occurred at control location K-8.

Precipitation was monitored only at an indicator location, K-11.

Tritium was detected in one sample (January 1982) and was 2310 pCi/l or 2210 pCi/l above the LLD of 100 pCi/1. The origin of the elevated activity is not known; however, in the past this level of

. activity was not unusual in the precipitation and was attributable to the nuclear tests explosions.

3.2.3 The Terrestrial Environment Of the 192 analyses for iodine-131 in milk all were below the LLD level of 0.5 pCi/1.

Strontium-89 activity was below the LLD level of 2.0 pCi/l in all samples.

• Unless otherwise indicated, uncertainties of average values are standard deviations of the individual measurements over the period averaged. Uncer-tainties of individual measurements represent probable counting errors at b"

the 95% confidence level.

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U Strontium-90 was found in all samples. The mean values were essentially identical for all indicator and control locations (2.3 and 2.2 pCi/1, respectively).

Barium-140 activity was below the LLD of 10 pCi/l in all sam-ples. Cesium-137 activity was also below the LLD of 10 pCi/1 in all samples.

Potassium-40 results were identical at both the indicator and control locations and were essentially identical to the levels observed in 1978, 1979, 1980 and 1981.

Due to the chemical similarities between strontium and calcium, and cesium and potassium, organisms tend to deposit cesium 137 in the soft tissue and muscle and strontium-89 and -90 in the bones. Consequently, the ratios of strontium-90 activity to the weight of calcium in milk and cesium-137 activity to the weight of potassium in milk were monitored in order to detect potential environmental accumulation of these radionuclides. No statisti-cally significant variations in the ratios were observed. The 6 measured concentrations of stable potassium and calcium are in k agreement with previously determined values of 1.50 0.21 g/l and 1.1610.08 g/l, res'pectively (National Center for Radiological Heal th , 1968 ) .

Gross alpha activity in well water was below the LLD level at 2.6 pCi/l in all samples.

Gross beta activity in well water was 3.0 pCi/1 in samples from

, the control location. The mean value for all indicator locations t

was 3.2 pCi/l and was identical or nearly identical to the values

, observed in 1977, 1978, 1979, 1980, and 1981 (3.3-pCi/1, 3.4

pCi/1, 3.0 pCi/1, 3.0 pCi/1,-3.6 pCi/1, respectively).

Tritium activity in the on-site well (K-lg) was below the LLD of r 100 pCi/l in all samples. ,

i The activities of strontium-89 and strontium-90 in well water ,

were below their respective detection limits.

p Potassium-40 levels were quite low (under 3.0 pCi/1), in agree-d ment with the previously measured values.

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In meat samples (chickens), gross alpha activity was below the LLD of 0.032- pCi/g wet weight in all sampl es. Gross beta activities averaged 2.40 pCi/g wet weight for indicator locations and 2.48

. pCi/g wet weight for control locations. Strontium-89 and stron-tium-90 activity was below the LLD level of 0.013 pCi/g wet weight in all samples. Gamma-spectroscopic analysis showed that most of the beta activity was due to naturally occurring potassium-40.

All other gamma-emi tting isotopes were below their respective LLO limits.

In egg samples, the gross alpha activity averaged 0.089 pCi/g wet weight. Gross beta activity averaged 1.10 pCi/g wet weight, about equal to the activity of the naturally occurring potassium-40 observed in the samples (1.40 pCi/g). The levels of strontium-89 and strontium-90 and all other gamma-emitting isotopes were below their respective LLD's.

In vegetables, alpha activity averaged 0.022 and 0.070 pCi/9 wet weight in indicator and control samples, respectively. Gross 'eeta activity was slightly higher at the control location than at the indicator location and was due primarily to the potassium-40 f) activi ty. Strontium-89 activity was below the LLD of 0.004 pCi/g v wet weight in all but one sample. The detected activity was barely above the LLD and was 0.006 pCi/g wet weight in a control sample. Strontium-90 activity was similar at both the indicator and control locations (0.008 pCi/g wet weight and 0.005 pCi/g wet weight, respectively). All other gamma-emitting isotopes were below their respective LLD levels. The sample of oats was of similar composition but the activity was slightly higher due to the lower water content of the grain in comparison with the vegetables.

In grass, gross alpha activity was essentially identical at both indicator and control locations (0.34 and 0.35 pCi/g wet weight, respectively). Gross beta activity was slightly higher at control locations (7.64 pCi/g wet weight) than at the indicator locations (6.69 pCi/g wet weight) and in both cases was predominantly due to naturally occurring potassium-40 and beryllium-7. All other gamma-emi tti ng isotopes were below their respective LLD's.

Strontium-89 was detected in ene of twenty-four samples and was 0.156 pCi/g wet weight. Strontium-90 activity was detected in twenty-three of twenty-four samples and was nearly identical at both indicator and control locations (0.042 and 0.036 pCi/g wet weight, respectively). Presence of radiostrontium in some of the samples is attributable to the fallout from nuclear tests.

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O For cattlefeed, the mean gross alpha activity at indicator loca-tions was 0.52 pCi/g wet weight and 0.42 pCi/g wet weight at control locations. Mean gross beta activity was higher at . indica-tor locations (7.49 pCi/g wet : weight) than at control locations (5.12 pCi/g wet weight). The highest gross beta level was in the sample from indicator location K-19 (11.8 pCi/g wet weight), and reflected the high potassium-40 level (7.49 pCi/g wet weight) observed in the sample. The pattern was similar to that observed in 1978, 1979, 1980 and 1981. Strontium-89 levels were 0.059 pCi/g wet weight at indicator locations, and less than the LLD (0.Q17 pCi/g wet weight) at control locations. Strontium-90 activity was slightly higher at the indicator locations than at the control locations (0.080 and 0.069 pCi/g wet weight, respec-tively). Cerium-144 was detected in one of six samples and the activity was 0.55 pCi/g wet weight. The presence of the radio-strontium is attributable to the fallout from the previous nuclear tests. All other ge.ma-emitting isotopes were below their respec-tive LLD levels.

No significant differences were found between indicator and control values in soil samples. The difference of 2.7 pCi/g dry weight in mean gross alpha activity between indicator loca-tions and control . locations is not statistically significant because the counting uncertainties of the individual measurements C are typically 3-5 pCi/g dry weight. Mean-gross beta levels were nearly identical at both indicator and control locations (26.3 and 28.0 pCi/g dry weight, respectively), and is primarily due to the potassium-40 activity. Strontium-89 was below the LLD level of 0.18.pCi/g dry weight in all samples. Strontium-90 was detected in all samples and was higher at control locations than at indica-tor locations (0.225 and 0.133 pCi/g dry weight, respectively).

Cesium-137 was detected in all samples and was higher by a factor-of two at control locations than at indicator locations (0.67 and 0.32 'pCi/g dry weight, respectively). All other gamma-emitting isotopes were below their respective LLD's. Except for a trace amount of niobium-95 in one of fourteen samples the levels of detected activities were very similar to those observed in 1979, 1980, and 1981.

3.2.4 The Aquatic Environment '

In surf ace water, the gross alpha activity in suspended solids was detected in one of seventy-two samples and was 1.1 pCi/1. In dissolved solids gross alpha activity was below the LLD of 3.2 '

pCi/l in all samples.

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Mean gross beta activity in suspended solids was below the LLD of 1.2 pCi/l at all locations. Mean gross beta activity in dissolved solids was higher by a factor of two at indicator locations (4.8 pCi/1) as compared to the control locations (2.4 12

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pCi/l) and was nearly identical to the activities observed in 1978 (5.4 and 2.7 pCi/1),1979 (5.7 and 2.7 pCi/1),1980 (5.1 and 2.7 pCi/1), and 1981 (4.3 and 2.7 pCi/1). The control sample is the Lake Michigan water which varies very little in activity during the year, while indicator samples include two creek locations (K-la and K-le) which are much higher in activities and exhibit large month-to-month variations in gross beta activities. The K-la creek drains its water from the surrounding fields which are heavily fertilized and K-le creek draws its water mainly from the Sewage Treatment Pond No. 1. In general , gross beta activity levels were high when potassium-40 levels were high and low when potassium-40 levels were low indicating that the fluctuations in beta activity were due to variations in potassium-40 concentra-tions and not to plant operation. The fact that similar fluctua-tions at these locations were observed in the pre-operational studies condu::ted prior to 1974 supports this assessment.

Annual mean tritium activity was higher at the indicator loca-tions than at the control location (1160 and 420 pCi/l, respec-tively). The elevated mean activity at the indicator locations was primarily due to the activity in five samples as compared to the activity level of 420 pCi/l in Lake Michigan; four collected n at discharge on January 6,1982 (1,660 pCi/1), April 1,1982 (970 ts~) pCi/1), July 6,1982 (860 pCi/1), and December 6, 1982 (2610 pCi/1), and one collect.ed at K-14 on December 6, 1982 (460 pCi/1).

The elevated annual mean of 1300 pCi/1 (or 880 pCi/l above back-ground level) in the discharge water is attributable to the plant operation but constitutes less than 0.03% of the maximum permis-sible concentration of 3,000,000 pCi/l established in the 10 CFR 20 Document. The highest level of 2,190 pCi/l above background level detected in the sample collected 6 December 1982 constitutes 0.07% of the permissible level. The difference between activity in control sample (420 pCi/1) and activity in one sample collected at indicator location K-14 (460 pCi/1) is not st~atistically i significant because the counting uncertainties of the individual measurements are typically 120-180 pCi/1.

Strontium-89 activity was below the LLD of 1.6 pCi/l in all samples. Strontium-90 activity was detected in three samples and was slightly higher at control location than at indicator loca-tions (2.0 and 1.4 pCi/1, respectively).

In fish samples, gross alpha activity was below detection limits 1

in all muscle and bone fractions. In muscle, gross beta activ-ity was primarily due to potassium-40 activity. The average beta activity of 2.26 pCi/g wet weight was near the minimum of the 1973 range of 2.26 to 3.62 pCi/g wat weight. The cesium-137 l) activity in muscle averaged 0.17 pCi/g wet weight and was nearly V identical to the level observed in 1979 and 1980 (0.12 pCi/g wet weight in both ,yaors ), and 1981 (0.15 pCi/g wet weight). The 1

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HAZLETON ENVIRONMENTAL SCIENCES O strontium-89 . level in bones was below the LLD of 0.34 pCi/g wet weight in all but one sample (1.33 pCi/l wet weight) while stron-tium-90 averaged '0.58 pCi/g wet weight. This activity was near the lower limit of the 1973 range of 0.40 to 1.09 pCi/g dry weight and was similar to the level found in 1980 (0.31 pCi/g wet weight) and in 1981 (0.58 pCi/g wet weight).

Only small amounts of bottom organisms were collected, resulting in rather high LLDs. Gross alpha levels were below the LLD of 12.0 pCi/g dry weight in all samples. Gross beta activity was algp below the LLD level of 16.0 pCi/g dry weight in all samples.

The quantities of bottom organisms collected were insufficient for gamma-spectroscopic analysis.

In periphyton (slime) sampl es, gross alpha activity was below the LLD of 0.70 pCi/g wet weight in all samples. Mean gross beta activity was similar at both indicator and control locations (2.81 and 3.05 pCi/g wet weight respectively). Strontium-89 activity was below the LLD level of 0.11 pCi/g wet weight in all samples. Strontium-90 levels were slightly higher at indicator locations than at control locations, 0.077 versus 0.050 pCi/g wet weight. Trace amounts of fission products-, e.g. niobium-95, g cerium-141, and cesium-137 were detected in one sample. Presence of these isotopes is attributable to'the fallout from the latest nuclear test conducted 16 October 1980. Trace amounts of mangan-ese-54, cobalt-58, and cobalt-60 were detected in two of ten samples. Presence of these isotopes in slime is probably plant related. All other gamma-emitting isotopes were below their respective LLDs.

In bottom sediment samples, gross alpha levels were below .the LLD of 4.5 pCi/g dry weight'in all samples.

The mean gross beta activity was slightly higher at indicator locations than at the control location (6.27 and 5.46 pCi/g dry weight, respectively) and was due mostly to potassium-40.

The difference is not statistically significant.

The mean cesium-137 levels were essentially identical at both indicator and control locations (0.13 and 0.12 pCi/g dry weight respectively), and similar to the levels observed in 1979 (0.17 and 0.08 pCi/g dry weight, respectively), in 1980 (0.24 and 0.14 pCi/g dry weight, respectively), and in 1981 (0.23 and 0.14 pCi/g dry weight, respectively). Strontium-89 and strontium-90 levels were below their respective LLDs (0.017 and 0.014 pCi/g dry weight, respectively) in all samples. Trace amounts of cobalt-58 and cobalt-60 were detected in five out of twelve bottom sediment samples collected near the condenser discharge. Presence of trace amount of these ' activation products in bottom sediments is prob-ably plant related.

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4.0 FIGURES AND TABLES O

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/

SCALE IN MILES l

O O I 2 3 4 Figure 4-1. Sampling locations, Kewaunee Nuclear Power Plant.

16

HAZLETON ENVIRONMENTAL SCIENCES O

V Table 4.1 Sampling locations, Kewaunee Nuclear Power Plant.

Distance (miles)b Code Typea and Sector Location K-1 Onsite la I 0.62 N North Creek Ib I 0.12 N Middle Creek Ic I 0.10 N 500' north of condenser discharge Id I 0.10 E Condenser discharge le I '

O.12 S South Creek If I 0.12 5 Meteorological tower j Ig 1 0.06 W South Well lh I 0.12 NW North Well lj I 0.10 5 500' south of condenser discharge K-2 C 9.5 NNE WPS Operations building in Kewaunee K-3 C 6.0 N Lyle and John Siegmund f arm, Route 1, Kewaunee K-4 I 3.0 N Dan Stangel f arm, Route 1, Kewaunee K-5 I 3.5 NNW Ed Paplham farm, Route 1. Kewaunee K-6C C 6.5 WSW Leonard Berres farm, Route 1 Denmark K-7 I 2.75 SSW Earl Bruemmer farm, Route 3. Two Rivers K-8 C 5.0 WSW Saint Mary's Church, Tisch Mills K-9 C 11.5 NNE Rostok Water Intake for Green Bay, Wisconsin two miles north of Kewaunee K-10 I 1.5 NNE Turner farm, Kewaunee site K-11 1 1.0 NW Harlan Ihlenfeld farm K-12 I 1.5 WSW 'Lecaptain f arm, one mile west of site K-13 C 3.0 SSW Two Creeks general store L K-14 I 2.5 S Two Creeks Park, 2.5 Miles south of site K-15 C 9.25 NW Gas. Substation,1.5 miles north of Stangelville .

K-16 C 26 NW WPS Division Office Building, Green Bay, Wisconsin K-17 I 4.25 W Jansky farm, Route 1 Kewaunee K-18 C 7.0 SSW Schmidt's Food Stand, Route 163 (3.5 miles south of B8")

K-19 I 1.75 NNE Wayne Paral farm, Route 1, Kewaunee K-20 1 2.5 N Carl Struck farm Route 1. Kewaunee .

K-21d I 3.25 NNW Bill Hardtke farm, Route 1, Kewaunee K-22e C 6.25 WSW Alvin Zahorik farm, Route 1 Denmark K-23 1 0.5 W 0.5 miles west of plant, Kewaunee Site K-24 I . 45 N Fectum farm, Route 1. Kewaunee K-25 C 2.75 WSW Wotachek farm, Route 1, Denmark K-26f C 10.7 SSW Bertler's Fruit Stand (8.0 mi south of "BB").

I = indicator; C = control b

C Distances are measured from reactor stack.

The K-6 sampling location was changed on October 27, 1980, because the operator of Berres Farm retired. Berres farm has been replaced by Novitski Farm, located d

0.2 miles west of Berres Farm.

Replaced by K-24 in September 1978.

8 Replaced by K-25 in September 1979.

Bertler's Fruit Stand (K-26) replaces Schmidt's food stand (K-18) which went out of business in the summer of 1982.

4 O

17

.~. . . - - . .

HAZLETON ENVIRONMENTAL. SCIENCES

\

Table 4.2. Type and frequency of collection.

I Frequency .

Monthly AiinIia'lly

• _ Location Weekly B1-weekly Quarterly Semi-annually l K-1 1 K-la SW SL K-lb SW GRa St b

K-1c BS i K-Id SW BS b B0a pga SL I

K-le ~

SW SL K-If AP AI RC GRa TLD 50 TLD

K-1g WV

, K-lh e WW K-lj BSb K-2 AP AI RC . TLD TLD

K-3 RC MIC . GRa TLD CF d 50 TLD GRa TLD CF d K-4 RC M!c 50 TLD K-5 RC MIC GRa TLD CF d 50 TLD i K-6 RC M!c GRa TLD CF d 50 TLD

! K-7 AP AI RC TLD TLD K-8 AP AI RC TLD TLD i~ K-9 SW BSb B0a SL l K-10 WW K-11 PR WW K-12 MIC GRa CFd WW SO K-13 WW K-14 SW BSb B0a st K-15 AP Al RC TLD TLD K-16 AP Al RC TLD TLD K-17 EG DM VE l K-189 VE i v K-19 MIC GRa CFd 50 K-20 DM K-218 DM K-22f DM K-23 GRN K-24 DM K-25 K-26

• DMV _ E

• Three times a year, 2nd (April, May, June), 3rd (July, Aug, Sept), and 4th (Oct, Nov, Dec) quarters.

i-C To be collected in May, July, Sept, Nov.

1 Monthly from November tnrough April; weekly from May through October. ~

e First (January, February, March) quarter only.

Replaced by K-24 in September 1978.

f Replaced by K-25 in September 1979.

t 9 Replaced by K-26 in summer of 1982.

4 d .

18 I

HAZLETON ENVIRONMENTAL SCIENCES O .

Table 4.3. Sample codes used in Table 4.2.

Code Description 3 AP Airborne Partiuclate ,

< r.

AI Airborne Iodine RC '

Radiation Chamber

^

.i TLD Thermoluminescent Dosimeter PR Precipitation MI Milk WW Well Water DM Domestic Meat EG Eggs

. VE Yegetables GRN Grain GR Grass CF Cattlefeed i

i S0 Soil

, SW Surface Water I

FI Fish B0 Bottom Organisms SL Slime BS -

Bottom Sediments O .

- 19

HAZLETON ENVIRONMENTAL SCIENCES O

Table.4.4. Sampling summary, January - December 1982.

Collection Number of Number of Sample Type and a Number of Sampl es Samples .

Type Frequency Locations Collected Missed Remarks Air Environment Airborne particulates .C/W 6 318 0 Airborne iodine C/BW 6 162 0 Ion chambersD C/M 10 100 0 TLD's C/Q 10 40 0 C/A 10 10 0 Precipits.fon C/M 1 12 0 Terrestrial Environment Milk (May-Oct) G/W 6 156 0 (Nov-Apr) G/M 6 36 0 Well water G/M 2 24 0 G/Q 4 16 0 Domestic meat G/A 4 4 0 Eggs G/Q 1 4 0 Vegetables-5 varieties G/A 2 6 0

(~} Grain-oats G/A 1 1 0 V -buckwheat G/A 1 0 1 See text p.7 Grass G/TA 8 24 0 Cattle Feed G/A 6 6 0 Soil G/SA 7 14 0 Aquatic Environment Surface water G/M 6 72 0 Fish-2 varieties G/TA 1 6 0 Bottom organisms b G/TA 3 3 0 Slime G/SA 6 12 0 Bottom sediments G/FA 5 20 0 i

• Type of collection is coded as follows: C/= continuous; G/= grab. Frequency is coded l as follows: /W= weekly; /M= monthly; /Q= quarterly; /SA= semi-annually; /TA=three times l b per year; /FA=four times per year; /A= annually; /BW=bi-weekly.

In accordance with the Amendment 44 to the Technical Specifications dated 4 May 1982 deployment of ion chambers and collection of, bottom organisms was dropped from the program effective June 1,1982.

O 20

, i t  : I a

\_) Lj O Table 4.5 Environmentri Radiological Monitoring Program Summary.

Name of fact:ity Kewaunee Nuclear Po.cr Plant Occhet No. 50-305 Location of f aulity Kewaunee County, Wisconsin Reporting Period January-Decenter 1982 (C~ounty, State)

Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Ntr.ber of Type Nteber of Mean(F) Mean(F) Mean(F) Non-rout ine (Units) Analysesa LLDb Rang,c locationd Range Range Results*

Airborne .

GA 318 0.004 C.0047 (55/106) K-16, Green Bay 0.0059 (18/53)' O.0043 (94/21'2] O Particylates (0.0020-0.0094) 26 mi NW (0.0024-0.0125) (0.0020-0.0146)

(pC1/m3)

G8 318 0.004 0.018 (104/106) K-8, St Mary's Church 0.019 (1/53) 0J)16 (202/212) 0 (0.004-0.038) 5.0 mi WSW (0.006-0.043) (0.004-0.043)

I GS 24 )

N Be-7 0.056 0.088 (2/8) K-15, Gas Substation 0.109 (1/4) 0.097 (7/16) 0 F (0.082-0.093) 9.25 mi NW -

(0.063-0.109) m Nb-95 0.0026 <LLD - - <tLD 0 Zr-95 0.0045 <LLD - - <LLD 0 m

~

Z Ru-103 0.0037 <LLD - - <LLD 0 $

Ru-106 0.018 <LLD - - <LLD 0 Cs-131 0.0015 <LLD <LLD 0

[ - -

Ce-141 0.0085 0.014 (1/8) K-If, Meteorological 0.014 (1/8) (LLD 0 m

- Tower 0.12 mi S - 2 Ce-144 0.012 <LLO - - <tLD 0 g-

<LLD 0 Ell Airborne '

I-131 162 0.01 <LLD - -

U lodine fpC1/m3) m

' ' Z Ion Ch a r Gdma 99 1.0 5.5 (39/33) K-8, St Mary's Church 6.7 (10/10) 5.8 (60/60) 0 I O

' A (mR/30 days) (4.6-7.2) 5.0 mi WSW ( 6. 4- 7.1) (4.6-7.5)

(f)

TLD-Quarterly Gamma 44 5 13.9 (16/16) K-7, Bruemmer farm 16.6 (4/4) 14 0 (28/28) 0 (mrem /91 days) (11.0-17.4) 2.75 mi SSW (15.3-17.4) (11.9-17.6)

TLD-Quarterly Gamma 11 5 55.2 (4/4) K-7, Bruemmer Farm 66.2(1/1) 56.1 ( 7/ 7) 0 (mrem /365 days) (47.8-66.2,i 2.75 mi SSW -

(48.7-65.0)

TLD-Annual C.amma 11 5 67.1 (4/4) X-8, St Mary's Church 19.0 (1/I) 68.9 (7/7) 0 (61.0-74.9) 5.0 mt WSW -

(56.7-79.0)

(mren/365 days)h '

. _ _ _ . _ _ . _ _ _ _ _ _ _ _ - . _ _m.. - ._ . . _ _ . _ . . . _ , . _ _ _ _ _ _ _ . _ .__

O  : O O ,

Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant Indicator Loca' t ion wi thWes t Control e Sampl e Type and Locationg Annual Mean Locations Number of Type humber of Hean(F) MeantF) Mean[F) Non-routine ,

(Units) , Analyses a Llob Rangec locationd Range Range Resultse Precipitation H-3 12 100 2310 (1/12) K-11, Inlenfeld Fam 2310 (1/12) None 6 (pCi/1) - 1.0 mi NW - ,

Milk 1-131 192 0.5 <LLD - - <tLD 0 (pCi/1)  ;

Sr-89 72 2.0 <LLD - - <tLO O I

> i Sr-90 72 0.5 I 2.3 (48/48) K-12, Lecaptain Fam 2.6 (12/12) 2.2 124/24) 0 N (1.2-3.8) 1.5 mi W5W (1.6-3.5) (1.6-2.9)

GS 72 h K-40 50 1310 (48/48) K-3, Siegmund Fam - 1310 (24/24) 0 I

' 1360 (12/12)

(1100-1590', 6.0 mi N (1240-1600) (1060-1560) m K-4, Stangel Fars 1360 (12/12) Z 3.0 mi H (1210-1570) {

Cs-137 10 i (LLD - - (iLD 0 g

m .

<LLO O Z

Ba-140 10 <LLD - -

g (g/1) K-stable 72 1.0 1.48 (48/48) K-3, Siegmund Fars 1.55 (12/12) 1.50 (24/24) O m (1.25-1.81) 6.0 mi N (1.41-1.82) (1.20-1.82) Z ,

(g/1) Ca 72 0.5 1.2 (48/48) K-5, Paplham Fam 1.3 (12/12) 1.2 (24/24) 0 r" (0.8-1.6) 3.5 mi NNW (0.9-1.6) (0.8-1.4) E K-6, Novitsky Farm 1.3 (12/12) 0.2 mi W (1.1-1.5) 0 K-19, Paral Farm 1.3 (12/12) m 1.75 mi NNE (0.9-1.5) Z O

"Well Water GA 40 2.6 <LLD - - <tL13 0 m (pCi/1) E GB 40 2.4 3.2 (18/36) K-lh, North Well 3.4 (8/12) 3.0 (1/4.) 0 (2.5-4.7) Onsite, 0.12 mi NW (2.5-4.7) -

H-3 4 100 (LLD - - None 0 K-40 40 0.10 1.9 (36/36) K-lh, North Well 2.4 (12/12) 1.3 (4/4) 0

(flame) (0.6-2.7) Onsite, 0.12 mi NW (2.1-2.51 (1.2-1.4) t

) None O

Sr-89 4 2.2 <LLD - -

Sr-90 4 0.6 (LLD - - None 0 e

O Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F) Meaitt t ) Mean(F) Non-routine (Units) Analysesa Llob RangeC Locationd Range Range

• Resultse Domestic Meat GA 4 0.03? <tLD - - <LLD 0 (chickens)

(pC1/g wet) G8 4 1.0 2.40 (3/3) K-24. Fectum Fars 2.81 (1/1) 2.48 (1/11 0 (1.79-2.81) 5.45 mi N -

Sr-89 4 0.013 <tLD - - <LLD 0 y Sr-90 4 0.013 <LLD - - (LLD 0 r

GS 4 M

-t Be-7 0.48 (LLD - - <tLD 0 0 2

K 40 0.5 4.91 (3/3) K-20. Struck Farn 5.58 (1/1) 2.72 (1/1) O m (4.11-5.58) 2.5 mi V - -

g Nb-95 0.066 (LLD - - <tLD 0 b 21 Zr-95 0.088 <LLD - - <LLD 0 0 m i 2 W Ru-103 0.066 <LLD - - . <LLD 0 {

m Ru-106 0.39 <LLD - - <LLD 0 2 0.040 - <tLD 0 )

Cs-134 <LLD -

e e Cs-137 0.040 (LLD - - <LLD 0 m G

, Ce-141 0.093 <LLD - - <LLD 0 g 0

2 Ce-144 0.23 <LLD - - (LLD g l 3 ,

m Eggs GA 4 0.016 0.089 (3/4) K-17. Jansky Fars 0.089 (3/4) None 0 g (pCf /g wet) (0.061-0.140) 4.25 mi W (0.061-0.140)

GB 4 0.01 1.10 (4/4) K-17 Jansky Farm 1.10 (4/4) None 0 (0.82-1.28) 4.25 mi W (0.82-1.28)

None 0 S r-89 4 0.007 <LLD - -

Sr-90 4 0.004 <LLD - - None C GS 4 None C Be-7 0.26 <LLD - .-

K-17, Jansky Farm 1.40 (4/4) None 0 K-40 0.01 1.40 (4/4)

(1.16-1.49) 4.25 mi W (1.36-1.49)

(

Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant

~

LocItion wIth'IIIghTsl Contr01 Ind W tor Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F) mann1 Mean(F) Non-routine (Units) Analysesa Llob Rangec Locationd Range Range _ _ ._ Resultse _

Eggs Nb-95 0.025 <LLD -

- None 0 (pCi/9 wet) None O (ccat d) Zr-95 0.042 <LLD - -

Ru-103 0.044 <LLD - - None O Ru-106 0.13 <LLD - -

• None 0 I

Cs-134 0.093 <LLD - - None 0 )-

N.

None 0 Cs-137 0.018 <LLD - -

h Ce-141 0.064 <tLD - -- Noi.e 0 h Wone 0

'Z Ce-144 0.10 <LLD - -

m Vegetables GA 6 0.020 0.022 (1/1) K-26, Bertler's Fruit 0.070 (5/5) 0.070 (5/5) 0 2 (pC1/g wet) Stand 10.7 mi SSW (0.024-0.160) (0.024-0.160) $

31 GB 6 1.0 2.31 (1/1) U26, Bertler's Fruit 2.64 (5/5) 2.64 (5/5) 0 0

$tand 10.7 mi SSW (1.23-4.72) (1.23-4.72)

Sr-89 6 0.004 <LLD K-26, Bertler's Fruit 0.006 (1/5) 0.006 (1/5) O Stand 10.7 mi SSW - -

Sr-90 6 0.001 0.008 (1/1) K-26, Bertler's Furit 0.005 (5/5) 0.005 (5/5) 0 l

- Stand 10.7 mi SSW (0.002-0.008) (0.002-0.007) r-GS 6 Be-7 0.16 <tLD - - <tLD 0 m Z

K-40 O.74 1.07 (1/1) K-26, Sertler's Fruit 2.31 (5/5) 2.45 (5/5) 0 l 0

- Stand 10.7 mi SSW (1.08-5.06) (1.08-5.06) i- 1.

]

Nb-95 0.017 <tLD - - <LLD 0 Zr-95 0.038 <tLD - - <LLD 0 Ru-103 0.038 <LLD - - <LLD 0 i

Ru-106 0.19 <LLD - - (LLD 0 Cs-137 0.023 <LLD - - <tLD 0 Ce-141 0.041 <LLD - - <LLD 0 Ce-144 0.13 <LLD - - <LLD 0

, . . - - . - _ . _ - .. ~. . - . . ... .- . _ . - - - _ . . . _ . .c - . -- .. . . , _ _~ .~.

O O O i

Table 4.5 (Continued) 4 Name of facility Kewaunee Nuclear Power Plant IndTc~ator Location with Highest. E t'rol Sample Type and Locationg Annual Mean Locations Number of Type Nutr.ber of Mean(F) rie~a~nir i Mean(F) Non-routine (Units) Analygsa LLDb RangeC Locationd Range Range Resul t_se i Grain - Dats '

GA 1 0.25 <LLD - - None O t " (pCi/g wetl 1 GB 1 0.1 6.36 (1/1) K-23, Kewaunee Site 6.36 (1/1) None 0 0.5 at W -

Sr-89 1 0.036 (LLD - - None- 0 1

Sr-90 1 0.01 0.079 (1/1) K-23. Kewaunee Site 0.079 (1/1) None 0 I

. - 0.5 mi W ~ - D i .N GS -1 h

, d Be-7 0.50 1.37 (1/1) K-23, Kewaunee Site - None 0 0

- 0.5 mi W Z K-40 0.1 5.74 (1/1) K-23, Kewaunee Site 5.74 (1/1) None 0 m

• - 0.5 mi W - 2

) g.

1 Nb-95 0.048 <tLD - -

None 0 3 i m O m Zr-95 0.062 (LLD - - None 0 Z Ru-103 0.040 <LLD - - None O Ru-106 0.23 <LLD - - None 0 2 f Y Cs-137 0.028 (LLD - -

None. 0 r-Ce-141 0.060 <LLD - - None 0 Ce-144 0.16 <tLD - - None O E Z

Cattlefeed GA 6 0.10 0.52 (4/4) K-19, Paral Fars 1.01 (1/1) 0.42 (2/2) 0 0 (pC1/g wet) (0.24-1.01) 1.75 mi NNE -

(0.029-0.54) l t GB 6 0.2 7.49 (4/4) K-19. Paral Fars 11.8 (1/1) 5.12 (2/2) 0

(3.70-11.80) 1.75 mi NNE -

(4.03-6.21)

Sr-89 6 0.017 0'.059 (4/4) K-19, Paral ~ Fars 0.083 (1/1). <LLD 0

, (0.026-0.083) 1.75 mi NNE - -

i Sr-90 6 0.01 0.080 (4/4) K-5. Pap 1 ham Fars 0.128 (1/1) 0.069 (2/2) 0 (0.015-0.128) 3.5 mi NNW (0.024-0.114)

GS 6 ,

i Be-7 0.51 <LLD - -

<LLD 0 1 .

i 4

-- . - s

O O 0 Table 4.5 (Continued)

Name of facility Kewaunce Nuclear Power Plant

~

Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations. Number of Type Number of Mean(F) rfean tt 1 Mean(F) Non-routine

_ _ (Units) __ Analysesa LLDb RangeC Locationd Range Range ._ Resultse _

Ca ttl efeed K-40 1.0 4.53 (4/4) K-19, Peral Farm 6.78 (1/1) 3.54 (2/2) 0

( pC1/9 wet) (2.67-7.49) 1.75 mi NNE -

(3.00-4.07)

(cont d)

Nb-95 0.039 (LLD - - (LLD 0 Zr-95 0.059 <LLD - - ' <LLD 0 i

Ru-103 0.050 (LLD - - <LLD . O I I

)-

Ra-106 0.19 <tLD - - <LLD O N r"

(LLD 0 Cs-134 0.018 <LLD - -

Cs-137 0.029 <LLD .

- <LLD 0 Ce-141 0.090 <LLD - - <LLD O m Z

Ce-144 0.18 <LLD K-3, Siegmund Fam 0.55 (1/1) 0.55 (1/2) 0 $

6.0 mi N - -

3 m _ - _ _ _ _ .

O

<n Grass i GA . 24 .0.08 0.34 (9/18) K-3, Siegmund Fam 0.58 (1/3) 0.35 (3/6) 0 Z

(pci/g wet) (0.10-0.57) 6.0 mi N -

(0.15-0.58) g 1.0 K-5, Pap 1 ham Fam 8.02 (3/3) 7.64 (6/6) O m GB 24 6.69 (18/18) Z 1 (4.18-11.27) 3.5 mi NNW (5.71-11.27) (5.73-9.60) i Sr-89 24 0.058 0.156 (1/18) K-lb, Middle Creek 0.156 (1/3) <LLD 0 r-Onsite, 0.12 mi N -

Sr-90 24 0.011 0.042 (17/18) K-lb, Middle Creek 0.058 (3/3) 0.036 (6/6) 0 O'

! (0.012-0.119) Onsite, 0.12 mi N (0.017-0.119) (0.017-0.075) m

' Z

! GS 24 O m

l 50 Be-7 0.59 2.33 (4/18) K-Ib, Middle Creek 3.42 (1/3) <LLD 0

.l i' (0.94-3.42) Onsite, 0.12 mi N -

l

} K-40 0.1 4.68 (18/18) K-6, Novitsky Fam 7.32 (3/3) 5.90 (6/6) 0 j (2.92-7.13) 6.5 mi WSW (5.60-9.40) (4.68-7.48)

Nb-95 0.10 <LLD - , <LLD 0 l i

Zr-95 0.11 <tLD <LLD 0 l!

Ru-103 0.09 (LLD

- <LLD 0

Ru-106 0.37 <tLD - - <LLD 0 i

I .

O O O Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant Indlcator. Location with Highest Control

' Sampl e  : Type and -Locationg Annual Mean Locations Number of Type . Number of Mean(F) 14dTnit 3 Mean(F) Non-routine (Units) Analyses 8 LLDb RangeC Locationd Range Range- Resultse Grass Cs-137 0.04 (LLD - -

<LLD 0 (pC1/g dry)

(cont'd) Ce-141 0.12 <LLO - -

<LLD 0 Ce-144 0.29 <tLD - -

<LLD 0 Soll GA 14 3.8 6.4 (5/10) K-6, Novitski Fam 12.5 (1/2) 9.J (2/4) 0 (pCf /g dry) (4.0-8.6) 6.5 mi WSW -

(5.7-12.5)

I GB 14 1.4 26.3.(10/10) K-12 Lecaptain Fam 30.0 (2/2) . 28.0 (4/4) 0 >

(16.5-34.2) 1.5 mi WSW (25.9-34.2)- (24.9-31.6) N Sr-89 14 0.18 <tLD 0

<LLD h Sr-90 0.04 K-12, Lecaptain Fam 0 14 0.133 (10/10) 0.288 (2/2) 0.225 (4/4) 0 g (0.041-0.357) 1.5 mi WSW (0.218-0.357) (0.122-0.274) m GS 14 2 De-7 0.49 <LLD - - <LLD 0 5 0

K-40 1.4 21.3 (10/10) K-If, Meteorological 23.3 (2/2) 21'.6 (4/4) 0 l 2 y (15.2-27.8) Tower, 0.12 mt 5 (23.1-23.5) (20.2-23.4) -

g' K-12 Lecaptain Fam 23.3 (2/2) m 1.5 mi WSW (21.2-25.4) 7 Nb-95 0.06 0.16 (1/10) K-1f, Meteorological 0.16 (1/2) <LLD 0 p Tower, 0.12 mi S r-Zr-95 0.11 <LLD - -

<LLD 0 Ru-103 0.12

<LLD - -

<LLD 0 Ru-105 0.44 <LLO - -

<LLD 0 i Cs 137 0.10 0.32 (10/10) K-3, Siegmund Fam 0.71 (2/2) 0.67 (4/4) O E i (0.15-0.59) 6.0 mi N (0.25-1.18) (0.25-1.18)

Ce-141 0.12 <LLD - -

<tLD 0 Ce-144 0.32 (LLD - -

<LLD 0 i

l l

1 l

O O O Table 4.5 (Continued) l Name of facility Kewaunee Nuclear Power Plant Iridicator location with Highest Control Sample Type and Locationg Annual Mean -Locations Number of .

Type Number of Mean(F) MeinTF) Mean(F) ' Non-rou tine (Units) Analysesa Llob Rangec Locationd Range Range Resultse

. Surface Water i GA(SS) 72 1.0 1.1 (1/60) K-lb. Middle Creek, 1.1 (1/12) (LLD i 0 (pC1/1)  !

- Onsite, 0.12 mi N -

GA(DS) 72 3.2 (LLD - - <LLD 0 GA(TR) 72 3.6 <LLO - - - <LLD 0.

, GB(SS) 72 1.2 <LLD - - <LLJ 0 l I i

? GM DS) 72 O.5 4.B (60/60) K-la, North Creek , 8.1 (12/12) 2.4 (12/12) 0  ; >

(1.2-15.8) Onsite, 0.62 mi N (2.8 15.8) (1.9-3.2) y GB(TR) 72 1.0 4.9 (60/60) K-la, North Creek, 8.2 (12/12) 2.4 (12/12) 0 $

. -( 1. 2-15. 8 ) Onsite, 0.62 mi N (2.8-15.8) (1.9-3.2) - 0 H-3 36 330 1160 (6/24) K-Id, Condenser Dis- 1300 (5/12) 420 (1/12) 0 (400-2610) charge, Onsite (400-2610) . m 0.12 mi E 2 1

Sr-89 12 1.6 <LLD - - <LLD 0 5

@ O 5 Sr-90 12 0.9 1.4 (2/8) K-14 Two Creeks Park 1.5 (1/8) 2.0 (1/4) 0 Z I

, (1.3-1.5) 2.5 mi 5 - -

g 0.5 K-la . North Creek 7.5 (12/12) 1.1 (12/12) m 5 K-40 72 3.6 (60/60)' O 2

(flame) (0.9-16.5) Onsite, 0.62 mi N (1.4-16.5) (1.0-1.3)

Y Fish-Muscle GA 6 0.038 -0.161 (5/6) K-Id, Coridenser Dis- 0.161 (5/6) None 0 r- .

(pti/g wet) (0.070-0.254) charge, Onsite (0.070-0.254) y 0.10 mi E g

> GB 6 1.0 3.49 (6/6) K-1d, Condenser Dis- 3.49 (6/6) None 0 m (2.71-4.10) charge, Onsite. (2.71-4.10) 2 0.10 mi E h

GS 6 E

Be-7 0.32 (LLD - . None 0 K-40' 1.05 5.64(6/6) K-1d, Condenser Dis- 2.64 (6/6) None 0 (2.08-3.84) charge, Onsite (2.08-3.84) 0.10 mi E l Nb-95 0.043 (LLD - -

None 0 Zr-95 0.057 <tLD - - None 0

. . . -..-. -. - . . - ,- - ~. . . .-. .- . - .. . - . . .. . . , .

O O O ,

Table 4.5 '(Continued) .

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Renge Resultse Fish Muscle Ru-103 0.037 <LLD - - iL .*

(pC1/g wet)

(Cont'd) Ru-106 0.20 <LLD - - fiune ~0 Cs-137 0.02 0.17(6/6) K-1d, Condenser Dis- 0.17(6/6) . None 0-(0.07-0.23) charge, Onsite (0.07-0.23) 0.10 mi E ,

Ce-141 0.070 <LLD - - None O D N

Ce-144 0.16 <LLD - - None 0 h

. Fish-Bones GA F 1.76 <tLD - - None 0 h (pC1/g wet) g GB 6 1.38 3.06 (3/6) K-1d, Condenser Dis- 3.06 (3/6) None 0 (2.39-4.11) charge, Onsite (2.39-4.11) m 0.10 mi E Z Sr-89 6 0.34 1.33. (1/6) K-1d, Condenser Dis- 1.33(1/6) None 0 5

@ - charge, Onsite -

0 g

1 0.10 mi E Sr-90 6 0.01 0. M (6/6) K-Id, Condenser Dis- 0.58(6/6) None O E I

(0.39-1.08) charge, Onsite (0.39-1.08) m 0.10 mi E 2 Bottom GA 3 12.0 <LLD - - <LLD 0 g-J Organisms g (pci/g dry) <tLD 0 I GB 3 16.0 <LLD - -

g

! Periphyton GA 12 0.70 <LLD - - <LLD 0 m 2

slime) 2

! pCi/g wet) GB 12 0.50 2.81(10/10) K-la, North Creek, .4.84(2/2) 3.05 (2/2) - 0' O

! (1.04-4.85) Onsite, 0.62 mi N (4.84-4.85) (1.64-4.46)

Sr-89 12 0.11 (LLD - -

<LLD- 0 Sr-90 12 0.010 p.077 (10/10) K-la, North Creek, 0.181(2/2) 0.050(2/2) 0 (0.007-0.159) Onsite, 0.62 mi N (0.203-0.158) (0.027-0.072)

GS 12 Be-7 0.49 1.36 (1/10) K-lb, Middle Creek, 6.95 (1/2) <LLD 0

- Onsite, 0.12 mi N -

K-40 0.50 2.95 (10/10) K-la, North Creek, 4.31 (2/2) 3.37 (2/2) 0 (1.17-4.99) Onsite, 0.62 mi N (3.63-4.99) (1.83-4.90)

. _ = , . , __ .____ _ _ _ _ _ _ _ _ _

I n - w

, N. N.s Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest C~on~tr61 Sampl e Type and Locatforg Annual Mean Locations Number of Type Number of Mean(F) tieInit ) Mean(F) Non-routine (Units) Analysesa LLDb Rangec locationd Range Range Resultse Periphyton Mn-54 0.048 0.083 (1/10) K-id, Condenser Dis- 0.083 (1/2) <LLD 0 (Slime) . charge, Onsite -

(pC1/g wet) 0.10 mi E (Cont'd)

Co-58 0.065 0.46 (2/10) K-Id. Condenser Dis- 0.70 (1/2) <tLD 0 (0.22-0.70) charge, Gnsite -

0.10 mi E -

Co-60 0.056 0.23 (1/10)

K-Id Condenser Dis-charge, Onsite 0.23 (1/2)

(LLD 0 f

N 0.10 mi E ~

g-m Nb-95 0.071 0.16 (1/10) K-la, North Creek 0.16 (1/2) <LLD 0 -4

- Onsite, 0.62 mi N - O 2

Zr-95 0.10 <LLD - <LLD 0 m

Ru-103 0.085 <LLD - -

<LLD 0 Ru-106 0.44 <tLD - -

<LLD 0 I3 0

$ Cs-134 0.050 <LLD - -

<LLD 0 2 Cs-137 0.054 0.11 (2/10) K-1d, Condenser Dis- 0.15 (1/2) <LLD 0 m (0.C7-0.15) charge, Onsite -

7 0.10 mi E Ce-141 0.11 0.30 (1/10) K-la, North Creek 0.30 (1/10) <LLD 0 F

- Onsite, 0.62 mi N -

(!)

O Ce-144 0.30 <LLD - - <LLD 0 g

<LLD ' 0 Bottom GA 20 4.5 (LLD - I -

Sediments j g (pCi/g dry) GB 20 1.4 6.27 (16/16) K-1d, Condenser Dis- 6.87 (4/4) 5.46 (4/4) 0 (f3 (4.50-9.06) charge, Onsite (5.49-9.06) (4.62-6.15) 0.10 mi E Sr-89 20 0.017 (LLD - - <LLD 0 Sr-90 20 0.014 <LLD - -

<tLD 0 GS 20 K-40 1.4 7.00 (16/16) K-14. Two Creeks 7.32 (4/4) 6.73 (4/4) 0 (5.18-8.35) Park, 2.5 mi S (5.37-8.34) (5.46-8.57)

Co-58 0.07 0.14 (5/16) K-Id, Condenser Dis- 0.14 (3/4) (LLD 0 (0.09-0.18) charge, Onsite (0.12-0.18) 0.10 mi E

a w O, U Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant IndicTtor Location with Highest Control Sample Type and Locationg Annual Mean Locations Number of Type Number of Mean(F) r4ffntt ) Hean(F) Non-routine (Units) Analy_ses a Ltob RangeC Locationd Range Range Resultse Bottom Co-60 0.050 0.09 (3/16) K-Id, Condenser Dis- 0.09 (2/4) <LLD 0 Sediments (0.08-0.10) charge, Onsite (0.08-0.10)

(pCi/g dry) 0.10 mi E .

(Con't) .O Cs-134 0.095 <LLD - - <tLD I

Cs-137 0.07 0.13 (11/16) K-14. Two Creeks 0.78 (1/4) 0.12 (1/4) 0 >

(0.08-0.20) Park, 2.5 mi 5 - - N r

M

-4 agg , gross alpha, GB = gross beta, GS = gamma spectroscopy SS = suspended solids. DS = dissolved solids TR = total residue. O btLD = nominal lower limit of detection based on 3 sigma counting error for background sample. Z cMean based upon detectable measurements only. Fraction of detectable measurements at speciff e<'

I is indicated in parentheses (F).

m dLocations are specified by station code (Table 4.1), distance (miles) and direction relative ti, e. Z

'Nonroutine results are those which exceed ten times the control station value. If no control 51 s is available, C the result is considered nonroutine if it exceeds ten times the pre-operational value for the loc. j Ef O

- Z K

m Z

Y r

W D

N Z

n m

W 1

HAZl.ETON ENVIRONMENTAL SCIENCES b

v

5.0 REFERENCES

Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 produced by cosmic rays'. xience 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, and 276.

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn. 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Radiation Environment, University of Chicago Press, Chicago. Illinois, 369-382.

Hazleton Environmental Sciences, 1979. Annual Report. Radiological Monitor-ing Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, Data Tabulations and Analysis, January -

December 19i8.

1980. Annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report -

Part II, Data Tabulations and Analysis, January - December 1979.

. 1981. Annual Rep',rt. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report -

Part II, Data Tabulations and Analysis, January - December 1980.

. 1982. Annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report -

Part II, Data Tabulations and Analysis, January - December 1981.

. 1983. Annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report -

Part II, Data Tabulations and Analysis, January - December 1982.

Industrial BIO-TEST Laboratories, Inc.1974. Annual Report. Pre-operational Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin. January - December 1973.

. 1975. Semi-annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin. January -

June 1975.

NALC0 Environmental Sciences. 1977. Annual Report. Radiological Monitoring

,,T (d Program for the Kewaunee Nuclear Power Plant, Kewaunce, Wisconsin, January - December 1976. -

32

HAZLETON ENVIRONMENTAL SCIENCES O

. 1978. Annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, Data Tabulations and Analysis, January - December 1977.

National Center for Radiological Health. 1968. Section 1. Milk surveil-lance. Radiological Health Data Rep., December 9:730-746.

National Council on Radiation Protection and Measurements. 1975. Natural Radiation Background in the United States. NCRP Report No. 45.

Solon, L. R. , W. M. Lowder, A. Shambron, and H. Blatz. 1960. Investigations of Natural' Environmental Radiation. Science. 131: 903-906.

Wilson, D. W., G. M. Ward, and J. E. Johnson, 1969. In Environmental Con-tamination by Radioactive Materials, International Atomic Energy Agency, p. 125.

e O

33

HAZLETON ENVIRONMENTAL SCIENCES O

Appendix A Crosscheck Program Results O

e O

A-1 1

HAZLETON ENVIRONMENTAL CCIENCE3 p

LJ '

Appendix A Crosscheck Program Results The Nuclear ' Sciences Department of Hazleton Environmental Sciences has parti-cipated in interlaboratory comparison (crosscheck) programs since the fonnula-tion of its quality control prcgram in December 1971. These p(rogramsare operated by agencies which supply environmental-type samples e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not tg participant laboratories. The purpose of such a program is to provice an independent check on the laboratory's analytical procedures and to alert it to any possible problems.

Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. <everal months later, the agency reports the known values to the participant laboratories and specifies control-limits. Results consistently higher or 10wer than the known values or outside the control limits indicate a need to check the instruments or procedures used.

O The results in Table A-1 were obtained through. participation in the environ-mental sample crosscheck program for milk and water samples during the period 1975 through 1982. This program has been conducted by the U. S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.

The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980, and 1981 through participation in the Second, Third, Fourth, and Fifth International Intercomparison of Environmental

, Dosimeters under the sponsorships listed in Table A-2. ,

e U

A-2

HAZLETON ENVIRONMENTAL SCIENCEL3 7'As j-Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Hazleton ES results for milk and water samples, 1975 through 1982a, .

Concentration in 3Ci/lb Lab Sample Date HES Result EPA lesult Code Type Coll. Analysis i20 c i30 , n=1 d STM-40 Milk '

Jan. 1975 Sr-89 <2 0 15' Sr-90 73i2.5 75 11.4 I-131 99i4.2 101t15.3

Cs-137 7610.0 75t15 Ba-140 <3.7 Ot15.0

, K(mg/1) 1470i5.6 1510i228 STW-45 Water Apr. 1975 Cr-51 <14 0 Co-60 42116 425 63.9 Zn-65 48716 497i74.7 Ru-106 505i16 497i74.7 Cs-134 385i3 400i60.0 Cs-137 468i3 450167.5 m

STW-47 Water Jun. 1975 H-3 1459i144 1499i1002 STW-48 Water Jun. 1975 H-3 2404 34 2204i1044 STW-49 Water Jun. 1975 Cr-51 <14 0 Co-60 344f1 350153 Zn-65 330t5 327i49 Ru-106 315 7 325t49 Cs-134 291t1 304146 Cs-137 38712 378157 STW-53 Wat'er Aug. 1975 H-3 3317i64 3200i1083 STW-54 Water Aug. 1975 Cr-51 223111 225i38 Co-60 305t1 307i46 ,

Zn-65 289 3 281i42 Ru-106 346i5 279157 Cs-134 238il 256i38 Cs-137 292i2 307 46 STW-58 Water Oct. 1975 H-3 1283180 1203 988 A-3

1 HAZLETON ENVIRONMENTAL SCIENCE 3

/m

.b Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date HES Re.sult EPA Result Code Type Coll. Analysis *2a c i30 , n=1d

~

STM-61 Milk Nov. 1975 Sr-90 68.9i2.1 74.6til.2 I-131 64.613.8 75115

, Cs-137 75.6i20 75t15 Ba-140 <3.7 0 K(Mg/1) 1435i57 15491233 STW-63 Water Dec. 1975 H-3 1034f39 1002i972 STW-64 Water Dec. 1975 Cr-51 <14 0 Co-60 22111 203i30.5 Zn-65 21516 201130.2 Ru-106 171 9 181i27.2 Cs-134 198 2 202i30.3 Cs-137 15214 151i22.7 STW-68 Water Feb. 1976 H-3 1124i31 10801978

'^)

STW-78 Water Jun. 1976 H-3 2500144 250211056 STW-84 Water Aug. 1976 H-3 3097i21 310011080 STM-91 Milk Nov. 1976 I-131 83i0.6 85t15 Ba-140 <4 0 Cs-137 1211.7 11i15 K(mg/1) 1443131 1510i228 STW-93 Wat.cr Dec. 1976 Cr-51 105i15 104i15 Co-60 <4 0 Zn-65 9714 102115 Ru-106 8713 99115 Cs-134 85i4 93115 Cs-137 103i4 101i15 STW-94 Water Dec. 1976 H-3 2537i15 230011049 l- STM-97 Milk Mar. 1977 I-131 5512.5 51f15 Ba-140 <6 0 i Cs-137 34i1 29 15 K(mg/1) 1520i35 1550i233 STW-101 Water Apr. 1977 H-3 1690162 1760i1023 A-4

HAZLfSON CNVIRONM2NTAL CCGNC33 O

U Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Coll. Analysis i20 c' i30 , n=1 d STM-130 Milk May 1977 Sr-89 38 2.6 44 15 Sr-90 12 2.1 10 4.5 I-131 5912.1 50il5 Ba-140 5314.4 72 15 Cs-137 14 1.2 10 15 K(mg/1) 1533i21 1560i234 STW-105 Water Jun. 1977 Cr-51 <14 0 Co-60 29t1 29i15 Zn-65 74t7 74 15 Ru-106 64 8 62il5 Cs-134 41t1 44t15 Cs-137 35i3 35t15 STW-107 Water Jun. 1977 Ra-226 4.7i0.3 5.li2.42

(') STW-113 Water Aug. 1977 Sr-89 Sr-90 1310e 10i2e 14i15 10i4.5 STW-116 Water Sep.1977 Gross Alpha 12iS 10 15 Gross Beta 32i6 30i15 STW-118 Water Oct. 1977 H-3 1475 29 1650x1017 STW-119 Water Oct. 1977 Cr-51 132i14 153 24 Co-60 39i2 38i15

. 2n-65 51i5 53t15 Ru-106 6316 74t15 Cs-134 3013 30il5 Cs-137 26 1 25t15 STW-136 Water Feb. 1978 H-3 16901270 168011020 STW-137 Water Feb. 1978 Cr-51 <27 0 Co-60 36 2 34 15 Zn-65 3214 29i15 Ru-106 41i2 36i15 Cs-134 47i2 52 15 Cs-137 <2 0 A-5

HAZLGTON RNVIRONM2NTAL CCISNCHO Table A-1. (continued)

Concen'tration in pCi/lb Lab Sample Date HES Result EPA Res it i

Code Type Coll. Analysis i20 c 13o , n=1 STW-1389 Water

• Mar. 1978 Ra-226 5.410.1 5.5i0.6 Ra-228 NAf 16.7t2.5 STW-150 Water Apr. 1978 H-3 21501220 222011047 STW-151 Water Apr. 1978 Gross Alpha 20i1 20i15 Gross Beta 56i4 59115 Sr-89 1912 21i15 Sr-90 811 10i4.5 Co-60 19i3 20il5 Cs-134 16il 15 15 Cs-137 <2 0 STM-152 Milk Apr.1978 Sr-89 85i4 101i15

() Sr-90

.I-131 811 78 1 9i4.5 82115 Cs-137 2913 23115 Ba-140 <11 0 K(mg/1) 1503i90 1500i225 STW-154g Water May 1978 Gross Alpha 1211 13i15 i Gross Beta 21td 18t15 STW-1579 Water Jun. 1978 Ra-226 4.0il.0 3.7i0.6 Ra-228 NAf 5.6i0.8 STW-1599 Water Jul. 1978 Gross Alpha 1913 2216 Gross Beta 28i3 3015 STW-162 Water Aug. 1978 H-3 1167138 12301990 STW-1659 Water Sep. 1978 Gross Alpha 411 515 Gross Beta 13f1 1015 h

f A-6

HAZLETON ENVIRONM2NTAL GCI~lNC3G

/ g V

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date HES Result' EPA Result Code Type Coll. Analysis i20 c i3 o , n=1d STW-167 Water Oct. 1978 Gross Alpha 19i2 19115 Gross Beta 36 2 34il5

• Sr-89 911 10t15 Sr-90 410 Si2.4 Ra-226 5.510.3 5.0 2.4 Ra-228 NAf 5.4*2.4 Cs-134 10t1 10115 Cs-137 15t1 13i15 STW-170 Water Dec. 1978 Ra-226 11.510.6 9.2il.4 Ra-228 NAf 8.914.5 STW-172 Water Jan. 1979 Sr-89 11i2 14i15 Sr-90 Si2 614.5 STW-175 Water Feb. 1979 H-3 1344i115 12801993

('")

~

STW-176 Water Feb. 1979 Cr-51 <22 0 Co-60 1012 9t15 Zn-65 26i5 21115 Rn-106 <16 0 Cs-134 8i2 6 15 Cs-137 1512 12il5 STW-178 Water Mar. 1979 Gross Alpha 6.3i3 10il5 Gross Beta 15i4 16115 STW-195g Water Aug. 1979 Gross Alpha 6.3*1.2 Si5 Gross Beta 42.7i7.0 4014 STW-193 Water Sep. 1979 Sr-89 5.0il.2 3.0il.5 Sr-90 25.0i2.7 28.014.5 STW-196 Water Oct. 1979 Cr-51 13515.0 113i18 Co-60 7.011.0 65 Cs-134 7.310.6 7t15 Cs-137 12.7tl.2 11t15 .

STW-198 Water Oct. 1979 H-3 1710i140 1560i1111 O

v A-7

HAZLGTON RNVIRONM~lNTAL CCIENC2O

()

Table A-1. (continued)

Concentration in pCi/lb Lab- Sample Date HES Result EPA Result Code Type Coll. Analysis *2a e i3o , n=1d STW-199 Water Oct. 1979 Gross Alpha 16.0i3.6 21115 Gross Beta 36.311.2 49 15 Sr-89 10.7i0.6 12*15 Sr-90 5.7 0.6 7i15 Ra-226 11.li0.3 11i5 Ra-228 1.610.7 0

, Co-60 35.0il.0 33t15 Cs-134 50.712.3 56i15

) Cs-137 <3 0 STW-206 Water Jan. 1980 Gross Alpha 19.012.0 30.018.0 Gross Beta 48.012.0 45.015.0

() STW-208. Water Jan. 1980 Sr-89 Sr-90 6.111.2 23.9tl.1 10.010.5 25.5tl.5 STW-209 Water Feb. 1980 Cr-51 112114 10115.0 Co-60 12.7i2.3 11i5.0 Zn-65 29.7i2.3 25i5.0 Ru-106 71.7il.5 51 5 Cs-134 12.012.0 1015.0 Cs-137 30.012.7 3015.0 STW-210 Water Feb. 1980 H-3 18001120 1750i340 STW-211 Water March 1980 Ra-226 15.710.2 16.012.4 Ra-228 3.510.3 2.6i0.4

STM-217 Milk May 1980 Sr-89 4.4f2.69 Si5

, Sr-90 10.011.0 1211.5 STW-221 Water June 1980 Ra-226 2.010.0 1.710.8 i

Ra-228 1.610.1 1.710.8 O

3 A-8

-_ __ w -- -_ p-, . , m ,, . , _ , . , ,

HAZLETON ENVIRONMENTAL SCIENCE 3 Table A-1. (continued)

Cohcentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type- Coll. Analysis i2o c 13o , n=1 d STW-223 Water ,

July 1980 Gross Alpha 31i3.0 38 5.0 Gross Beta 44i4 3515.0 STW-224 Water July 1980 Cs-137 33.910.4 35i5.0 Ba-140 <12 0 K-40 1350160 1550i78 I-131 <5.0 0 STW-22b Water Aug. 1980 H-3 1280150 1210 329 STW-226 Water Sept. 1980 Sr-89 22 1.2 24i8.6 Sr-90 12i0.6 15 2.6 Sept. 1980 Gross Alpha 32.0 8.0

() STW-228 Water Gross Beta NAf 22.5 0.0 21.0i5.0 STW-235 Water Dec. 1980 H-3 2420i30 22401604 STW-237 Water Jan. 1981 Sr-89 13.011.0 16i8.7 Sr-90 24.0i0.6 34i2.9 STM-239 Milk Jan. 1981 Sr-89 <210 0 Sr-90 15.7t2.6 20t3.0 1-131 30.914.8 26 10.0 Cs-137 46.9i2.9 4319.0 Ba-140 <21 0 K-40 1330153 1550i134 STW-240 Water Jan. 1981 Gross alpha 7.312.0 9 5.0 Gross beta 41.013.1 44 5.0 STW-243 Water Mar. 1981 Ra-226 3.5 0.06 3.410.5 Ra-228 6.5 2.3 7.311.1 V

A-9

. HAZLETON ENVIRONM2NTAL CCIENCED 7

V Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Coll. Analysis .i2o c i3o , n=1d STW-245 Water Apr. 1981 H-3 3210 115 2710:355 36i8.7 STW-249 Water May 1981 Sr-89 51i3.6

, Sr-90 22.7i0.6 22i2.6 STW-251 Water Mr.y 1981 Gross alpha 24.015.29 2115.25 6eoss beta 16.lil.9 14f5.0 STW-252 Water Jun. 1981 H-3 2140195 1950iS96 STW-255 Water Jul. 1981 Gross alpha 20il.5 2219.5 Gross beta 13.0i2.0 ,15i8.7 STW-259 Water Sep. 1981 Sr-89 16.111.0 2315 Sr-90 10.310.9 11tl.5 STW-265 Water Oct. 1981 Gross alpha 71.2i19.1 80 20

(T s, / Gross beta 123.3 16.6 11115.6 Sr-89 14.912.0 21 5 Sr-90 13.lil.7 14.4tl.E Ra-226 13.012.0 12.7tl.9 STW-269 Water Dec. 1981 H-3 2516i181 2700i355 STW-270 Water Jan. 1982 Sr-89 24.3i2.0 21.015.0 Sr-90 9.410.5 12.011.5 STW-273 Water Jan. 1982 1-131 8.610.6 8.4il.5 STW-275 Water Feb. 1982 H 74 15801147 18201342 STW-276 Water Feb. 1982 Cr-51 <61 0 Co-60 26.0 3.7 2015 Zn-65 <13 1515 Ru-106 <46 20 5 Cs-104 26.8 0.7 22 5 4

Cs-137 29.711.4 23 5 STW-277 Water Mar. 1982 Ra-226 11.911.9 11.611.7 STW-278 Water Mar. 1982 Gross alpha 15.6tl.9 19 5 Gross beta 19.210.4 1915 A-10

HAZL'ITON CNVIRONMENTAL CCIENC^20 0 Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date HES Result EPA Result Code Type Coll. Analysis 120 e i30 , n-1d STW-280 Water Apr. 1982 H-3 2690i80 2860i360 STW-281 Water Apr. 1982 Gross alpha 7517.9 85t21 Gross beta 114.115.9 106i5.3 Sr-89 17.4tl.8 2415 Sr-90 10.510.6 12il.5 Ra-226 11.4f2.0 10.9tl.5 Co-60 <4.6 0 STW-284 Water May 1982 Gross alpha 31.5i6.5 27.3i7 Gross beta 25.913.4 29i5 STW-285 Water June 1982 H-3 1970i1408 18301340 STW-286 Water June 1982 Ra-226 12.6il.5 13.4i3.5 Ra-228 11.li2.5 8.7 2.3 O STW-287 Weter Jene 1982 1-131 e.510.3 4.410.7 STW-290 Water Aug. 1982 H-3 3210t140 28901619 STW-291 Water Aug. 1982 I-131 94.612.5 87t15 STW-292. Water Sept 1982 Sr-89 22.7i3.8 24.5i8.7 Sr-90 10.9 0.3 14.5i2.6 STW-296 Water ~

Oct. 1982 Co-60 20.0tl.0 ~ 20f8.7 Zn-65 32.3i5.1 2418.7 15.3fl.5 Cs-134 19.0i8.7 Cs-137 21.0il.7 20.018.7 STW-297 Water Oct . 1982 H-3 2470i20 2560i612 STW-298 Water Oct. 1982 Gross alpha 32i30 55 24 Gross beta 81.716.1 8118.7 Sr-89 <2 0 Sr-90 14.110.9 17.2 2.6 Cs-134 <2 1.8i8.7 Cs-137 22.7 0.6 20i8.7 -

Ra-226 13.610.3 12.Si3.2 Ra-228 3.911.0 3.6 0.9 0 .

A-11

HAZLETON GNVIRONMENTAL CCIENO23 Q

Table A-1. (continued)

Concentration.in pCi/lb l Lab Sample Date lies Resuit EPA Result Code Type Coll. Analysis ,i20 c i30 , n=ld STW-301 Water Nov. 1982 Gross alpha 12.0il.0 19.0i8.7 Gross beta 34.0i2.7 24.0i8.7 STW-302 Water ,

Dec . 1982 I-131 40.010.0 37.0i10 m aResults obtained by the Nuclear Sciences Department of Hazleton Environ-mental Sciences as a participant in the environmental sample crosscheck U program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.

Environmental Protection Agency, (EPA), Las Vegas, Nevada.

ball results are in pCi/1, except for elemental potassium (K) data which cre in mg/1.

cunless otherwise indicated, the HES results given as the mean i20 standard deviations for three determinations, dVSEPA results are presented as the known values i control limits of 30 for n=1.

eMean i 20 standard deviations of two determinations.

fNA = Not an'alyzed.

9 Analyzed but not reported to the EPA.

e V .

A-12

O O O Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLD's).

mR Hazleton Average 12o d Lab TLD Result Known (all Code Type Measureme'nt 12 o a Value participants) 2nd International Intercomparisonb 115-2b CaF2:Mn Gamma-Field 17.0il.9 17.lc 16.417.7 N Bulb E Gamma-Lab 20.814.1 21.3c 18.81 - y 3rd International Intercomparisone Z 115-30 CaF2 :Mn Gamma-Field 30.7t3.2 34.914.8f 31.513.0 k Bulb 5 p Gamma-1.ab 89.616.4 91.7114.6f 86.2124.0 0 4th International Intercomparison9 g m

Z 115-49 CaF2:Mn Gamma-Field 14.111.1 14.111.4f 16.09.0 g Bulb r-Gamma-Lab (Low) 9.311.3 12.2 2.4f 12.017.6 m n

Gamma-Lab (High) 40.4 1.4 45.819.2f 43.9113.2 l

i Sth International Intercom 0arisonh 0 m

115-5Ah CaF2:Mn Gamma-Field 31.411.8 30.016.0i 30.2i14.6 Bulb Gamma-Lab 77.4i5.8 75.217.6i 75.8 40.4 at beginning Gamma-Lab 96.615.8 88.418.8I 90.7131.2 at the end

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l Table A-2. (Continued) mR Average i 20 d Hazleton Lab TLD . Result Known (all Code Type Measurement 12aa Value participants)-

115-5Bh LiF-100 Gamma-Field 30.314.8 30.016i 30.2114.6 Chips 75.217.61 75.8140.4 f-N Gamma-Lab 81.117.4 at beginning m 4

Gamma-Lab 85.4111.7 88.418.8.i 90.71131.2 O 2

at the end Z

alab result given is the mean i20 standard deviations of three determinations. 5 b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health 0 3, 2 g and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas. h cValue determined by sponsor of the intercomparison using continuously operated pressurized ion chamber. z dMean i20 standard deviations of results obtained by all laboratories participating in the program. g eThird International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge r-National Laboratory and the School of Public Health of the University of Texas, Houston, Texas, m fValue f20 standard deviations as determined by sponsor of the intercomparison using continuously operated Q m

pressurized ion chamber.

9 Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.

lm hFifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, a Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and

. Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.

I Value determined by sponsor of the intercomparison using continuously operated pressurized -ion chamber.

_..-___-. - ___--.-.---__. _.~..- -_. ...--._.. -

HAZLETON ENVI AONMENTAL SCIENCES O

1 i

Appendix B Data Reporting Conventions 1

1 O

i e

O I

l B-1 i

t

-. . . - ~ _ - - --. -. - . --.

l HAZLETON ENVIRONMENTAL SCIENCES l O

r Data Reporting Conventions 1.0. . All activities are decay . corrected to collection time.

S.0. Single' Measurements ,

Each single measurement is reported'as follows:

xis where x = v51ue of'the measurement; s = 20 counting uncertainty (corresponding to the 95% c,onfidence level)

In cases where the activity is found to be below the lower limit of

-detection L it is reported as .

<L .

4 ~

where L = is the lower limit of detection based on 3a uncertainty 4

.for a background sample. ._

h 3.0. Duplicate Analyses:

i d 3.1. Individual results: -x1 i s1

- ~

s2 x2 ,

-s

.~-

Reported result: xis

,- ~-l where x = (1/2) (x1 + x2) '

s=-(1/2).fsf+sf 3.2. I^dividual n results: <Li  :.

I <L2 Reported result: <L t

where L = lower of L1 and L2

[

3.3. Individual results: xis ,

1 . /

<s

<L > ,.

[

' Reported result: x i s if x < L;

<L'otherwise >

y ,

O 1

/

? .

I e , -

4 B-2 .

l i h, j

HAZLETON ENVIRONMENTAL SCIENCES O

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly star 43rd deviations. The average x and standard deviations of a set of n numbers x1, x2 Xn are defined i as follows:

x= hex

,, I(x-x)2 n-1 -

4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.

O 4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5. In rounding off, the following rules are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded off to 11.44.

4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is

} raised by 1. As an example,11.446 is rounded off ~to 11.45.

4.5.3. If the figure following those c'o be retained is 5, and if there are no figures other '1an zeros beyond the five, the figure 5 is dropped, and F last-place figure retained is p increased by one if it i', '.,1 odd number or it is kept unchanged if an even number. As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.

p]

L B-3

. . . - - _ _ _ - . . - . - _ . _ , - . - _ _ - . - . . . ~ - - . . . . . - - - . . . . . . . - . - . . - . -

. . . - -_ - - . . . . - - - - ~ . - .

i T

t-

HAZLETON ENVIRONMENTAL SCIENCES ,

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i i f

t i

i-  !

I i

5 i

t

. Appendix C I

1 Maximum Pennissible Concentrations ,

i

, . of Radioactivity in Air and Water i j -Above Background in Unrestricted Areas  !,

t

! t 1 l

\

f i

4 i

a !

. i

.Y ,

. I 6 l l

4 i C-1 1

w= < --- - -.w.eee ve nnem n-~~ +~+--m+m wevms-.mw,me-, ,vngr e w v , w .w . -,- v -w--+. ,

, a v -g

4 HAZLETON ENVIRONMENTAL SCIENCES O

Maximum permissible concentrations of radioactivity in air and

~

< Table C-1.

water above natural background in unrestricted areas.a Air Water Gross alpha 3 pCi/m3 Strontium-89 3,000 pCi/l Gross beta ,

100 pCi/m3 Strontium-90 300 pCi/l Iodine-131b 0.14 pCi/m 3 Cesium-137 20,000 pCi/l Barium-140 20,000 pCi/1 j Iodine-131 300 pCi/l l Potassium-40c 3,000 pCi/1 Gross alpha 30 pCi/l Gross beta 100 pCi/l Tritium 3 x 106 pCi/1 aTaken from Code of Federal Regulations Title 10, Part 20, Table II and appropriate footnotes. Concentrations may be averaged over a period not greater than one year.

bFrom 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

cA natural radionuclide. -

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C-2

_.