Text

Annual Operating Rept,1984
	ML20099D732
Person / Time
Site:	Kewaunee
Issue date:	12/31/1984
From:	; MADISON GAS & ELECTRIC CO., WISCONSIN POWER & LIGHT CO., WISCONSIN PUBLIC SERVICE CORP.
To:	James Keppler; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
	NUDOCS 8503130441
	Download: ML20099D732 (53)
	v • d • e

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O KEWAUNEE NUCLEAR POWER PLANT ANNUAL OPERATING REPORT O 1984 WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER a LIGHT COMPANY j M A DISON GAS a ELECTRIC COMPANY O

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L13-1.0

-O TABLE OF CONTENTS Page No.

1.0 Introduction 1 2.0 Summary of Operating Experience 3 3.0 Plant Modifications, Tests and Experiment's 12 4.0 Licensee Event Reports 24 5.0 Fuel Inspection Report 35 6.0 Challenges to and Failures of Pressurizer Safety.and Relief Valves 36 7.0 Steam Generator Tube Inspection 37 8.0 Personnel Exposure and Monitoring Report 41 9.0 Radiological Monitoring Program 45 0 .

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L13-1.1

1.0 INTRODUCTION

i t V 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. 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 39,857,300 MW hours of electricity as of December 31, 1984, with a net plant capacity factor of 76.7% (using net DER).

1.1 Highlights During the year, the Kewaunee Nuclear Plant was primarily base loaded. The unit was operated at 86.2% capacity factor (using net MDC) with a gross efficiency of 33.1%. The unit and reactor availability were 85.7% and 86.2% respectively. Table 2.1 is a compilation of the monthly summaries 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 f\ average daily electrical output of the Kewaunee Plant for 1984 v

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L13-1.2 On March 16, 1984, the unit was removed from service for its ninth annual refueling. Thirty-six fresh fuel assemblies were loaded for cycle X. The unit was returned to service on May 7, 1984.

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SUMMARY

OF OPERATING EXPERIENCE O January Normal power operation continued through the entire month of January.

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

January.

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February l

Normal power operation continued through the entire month of February.

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

March On March 16, the unit was shutdown for refueling.

O PLANT SHUT 00WNS: March 16 scheduled shutdown - 360.5 hours.

! Commenced Cycle IX-X refueling outage.

April In April, the Cycle IX-X refueling outage continued.

PLANT SHUTOOWNS: April 1, scheduled shutdown - 719.0 hours.

Continued Cycle IX-X refueling outage.

i May On May 7, the Cycle IX-X refueling outage was concluded.

On May 8, the unit was released for operation. <

PLANT SHUTDOWNS: May 1, scheduled shutdown - 157.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Continued Cycle IX-X refueling outage. The outage was l concluded on May 7.

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L13-1.4 May 7, forced shutdown -

3.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Due to an incorrectly wired Auto Stop Trip Pressure Switch a turbine / reactor trip was initiated during testing of the Turbine Thrust Bearing trip circuitry.

May 7, forced shutdown - 5.0 hours. A reactor / turbine trip occurred on "lo-lo" Steam Generator level during unit startup while trans-ferring from manual to automatic feedwater_ regula-tion valve control.

May 8 scheduled shutdown - 2.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . A short outage was taken to perform Turbine overspeed trip tests.

June On June 2 load was reduced to 44% power due to circulating water leakage into the condenser. Inspection of the condenser revealed a leaking instrument line which was repair *J and the plant was returned to 100% power.

Normal power operations continued through the month of June.

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

July On July 3, the unit tripped as a result of an instrument bus inverter failure.

PLANT SHUTOOWNS: . July 3, forced shutdown - 7.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . An instrument bus inverter failed, causing low voltage on one 4

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L13-1.5 instrument bus; this resulted in a reactor / turbine trip on low steam generator level coincident with feed flow / steam flow mismatch.

August

. On August 5, unit load was reduced for the performance of the monthly turbine stop valve test. The unit was returned to full power the same day.

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

September On September 3, unit load was reduced for the performance of the monthly turbine stop valve test. The unit was returned to full power the same day.

O PLANT SHUTOOWNS: There were no plant shutdowns during the month of September.

October On October 5, unit load was reduced to allow maintenance on an off-site transmission system line. The monthly turbine stop valve test was also conducted during this time. The unit was returned to full power on October 6.

PLANT SHUTOOWNS: There were no plant shutdowns during the month of '

October.

November i

On November 4 unit load was reduced for the performance of the O I 5

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l monthly turbine stop valve test. The unit was returned to full power the same day.

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

November, t

j December On December 2, enit load was reduced for the performance of the monthly turbine stop valve test. The unit was returned to full power -

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i j i PLANT SHUTOOWNS: There were no plant shutdowns during the month of i December. l t

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KEWAUNEE POWER HISTORY AVER AGE D AILY MWE - NET J

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O O TABLE 2.1 (Page 1 of 2)

OL13-1.5 ELECTRICAL POWER GENERATION DATA (1984)

MONTHLY January February March April May June Hours RX was critical 744.0 696.0 383.7 0.0 614.0 720.0 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744.0 696.0 385.5 0.0 575.3 720.0 1

Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0

' Gross Thermal Energy Generated (MWH) 1,225,897 1,139,329 532,963 0.0 837,414 1,114,593 Gross Elec. Energy Generated (MWH) 403,000 374,200 175,100 0.0 276,900 379,800 Net Elec. Energy Generated (MWH) 384,993 357,376 166,154 0.0 262,749 361,333 RX Service Factor 100.0 100.0 51.6 0.0 82.5 100.0 RX Availability Factor 100.0 100.0 51.6 0.0 82.5 100.0 Unit Service Factor 100.0 100.0 51.5 0.0 77.3 100.0

, Unit Availability Factor. 100.0 100.0 51.5 0.0 77.3 100.0 Unit Capacity Factor (using MDC net) 102.9 102.1 44.4 0.0 70.2 99.8 4

Unit Capacity Factor-(using DER net) 96.7 96.0 41.7 0.0 66.0 93.8 Unit Forced Outage Rate. 0.0 0.0 0.0 0.0 1.4 0.0 Hours in Month 744 696 744 719 744 720

- Net MDC (Mwe) 503 503 503 503 503 503

O O O TABLE 2.1 (Page 2 of 2) L13-1.6 ELECTRICAL POWER GENERATION DATA (1984)

MONTHLY July- August September October November December Hours RX was critical 739.8 744.0 720.0 745.0 720.0 744.0-RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 736.6 744.0 720.0 745.0 720.0 744.0 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1,199,335 1,222,297 1,183,431 1,205,018 1,183,532 1,222,229

- Gross Elec. En':rgv Generated (MWH) 398,400 401,200 392,300 399,900 393,000 405,400 N t Elec. Energy Generated (MWH) 379,308 381,602 373,485 380,555 375,244 387,201 RX Service Factor 99.4 100.0 100.0 100.0 100.0 100.0 RX Availability Factor 99.4 100.0 100.0 100.0 100.0 100.0 Unit Service Factor 99.0 100.0 100.0 100.0 100.0 100.0 Unit Availability Factor 99.0 100.0 100.0 100.0 100.0 100.0 Unit Capacity Factor (using MDC net) 101.4 102.0 103.1 101.6 103.6 103.5 Unit Capacity Factor (using DER net) 95.3 95.9 97.0 95.5 97.4 97.3 Unit Forced Outage Rate 1.0 0.0 0.0 0.0 0.0 0.0 744 744 720 745 720 744 Hours in Month 503 503 503 503 503 503 Net MDC (Mwe) j

L13-1.7 TABLE 2.2 '

ELECTRICAL POWER GENERATION DATA 1984 Year Cumulative Hours RX was critical 7,570.6 78,750.5 RX Reserve Shutdown Hours 0.0 2,330.5

Hours Generator On-Line 7,528.3 77,340.7 Unit Reserve Shutdown Hours 0.0 10.0 Gross Thermal Energy Generated (MWH) 12,096,038 121,067,124

, Gross Elec. Energy Generated (MWH) 3,999,200 39,857,300 i

Net Elec. Energy Generated (MWH) 3,810,000 37,942,036 l

l RX Service Factor 86.2 85.2 i RX Availability Factor 86.2 87.7 Unit Service Factor 85.7 83.7 Unit Availability Factor 85.7 83.7

, Unit Capacity Factor (using MDC net) 86.2 79.1 Unit Capacity Factor (using DER net) 81.1 76.7 Unit Forced Outage Rate 0.2 3.6 Hours in Reporting Period 8,784 92,449 4

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l L13-1.7A 7s 3.0 PLANT MODIFICATIONS. TESTS AND EXPERIMENTS This section is provided in accordance with the requirements of Port !

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 Updated Safety Analysis Report, make changes in pro-cedures as described in the Updated Safety Analysis Report, and con-duct tests and experiments not described in the Updated Safety Analysis Report, without prior NRC approval, provided the change, test or experiment does not involve a change in the Technical Specifications or an unreviewed safety question. 10CFR50.59(b) requires that such changes be reported on an annual basis.

3.1 Plant Modifications 10CFR50.59 There were no modifications during 1984 which introduced an unre-() viewed safety question and, therefore, prior NRC approval was not required.

The following summary of modifications includes those significant modifications completed during 1984 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 facility "as described in the Updated Safety Analysis Report." However, they are considered to be of significance, warranting mention in this report. !

Reactor Control and Protection Reactor Trip and Bypass Breaker overcurrent trip brackets were removed from the. trip bar as recommended by Westinghouse. (DCR 1378)

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L13-1.13 Summary of Safety Evaluation The brackets were unnecessary since the breakers were not equipped with overcurrent devices. Westinghouse testing showed that additional margin on the trip interaction of the undervoltage attachment was gained by removing the brackets.

Engineered Safeguards Logic relay circuits for the main feedwater control valves were modified to allow proper continuity verification using the test light.

Resistors were added to the test light circuit for SI Block / Reset relays to prevent inadvertent actuation of the relays when in test. (DCR 1360)

Summary of Safety Evaluation The test light in the original design tested the seal-in relay in parallel with the main relay and thus only verified that one of the two relays was operable. The new design allows individual testing of the main relay and individual tesing of the seal-in relay. The resistors do not affect normal operation of the SI Block / Reset relays since they are in the circuit only when the

" push to test" lamp is depressed.

4160-V and 480V Supply and Distribution A tap change was made on substation transformer B-10. Consequently tap changes were made on the Reserve and Tertiary Auxiliary Transformers and several station transformers. Setpoints on second level and instantaneous undervoltage relays on the safeguard buses were lowered by 21%. (DCR 1434)

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L13-1.14 Summary of Safety Evaluation s/ The tap changes increased the voltage on the most limiting safe-guard motors. This, along with a computer loadflow program, which more accurately predicts safeguard bus voltages, allowed the undervoltage relay setpoint change. Technical Specification Amendment 53 was granted for the setpoint change.

480V Supply and Distribution Installed trip guards on safety related 480V switchgear. These guards prevent accidental tripping of switchgear breakers by personnel and equipment moving through the area. (DCR 1401)

Summary of Safety Evaluation These trip guards were designed by the breaker manufacturer and are being used on new switchgear breakers. They are attached to the breaker covers and will not affect the operation of the breakers.

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

- Replacement of several limit switches and installation of Conax seals on these limit switches for valves in Main Feedwater and Main Steam systems. (DCR's 1394 and 1416)

- Replacement of four (4) level transmitters in the Reactor Coolant Systems (DCR-1136)

- Replacement of six (6) damper actuators in the Shield Building Ventilaticn system. (DCR 1243)

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L13-1.15

- - Replacement of several solenoid valves in Reactor Building Ventilation, Radiation Monitoring, Main Feedwater, Pressurifer Spray, Secondary Sampling, Chemical and Volume Control, Auxiliary Building Special Ventilation, Main Steam, and Miscellaneous Drains and Sumps systems. (DCR's 1143, 1144, 1145, 1154, 1242, 1285, 1286, 1369, and 1416).

Summary of Safety Evaluation In each case the modification resulted in the component being more qualified for postaccident operation, hence reliability was i

upgraded, j Reactor Building Ventilation The Containment Fan Coil Unit discharge ductwork was modified to assure a post accident cooling air flow path. (DCR 1291)

O Summary of Safety Evaluation The addition of emergency discharge dampers and pressure relief dampers in the ductwork downstream of the Containment Fan Coil Units ensures a flow path through the fan coil units postacci-dent.

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1 Reactor Building Ventilation The Post-LOCA Hydrogen Recombiner piping was modified to allow for relief of containment pressurc during plant operation. (DCR 1327)

Summary of Safety Evaluation Originally containment pressure was relieved through 36-inch Pratt butterfly valves whose operation against a large differen-l 15 i

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tial pressure (i.e. post LOCA) was suspect. The new design pro-vides a separate 2-inch diameter system affording containment 4

pressure relief without using the 36 inch diameter system.

Reactor Building Ventilation The control circuitry for the CRDM Cooling Fans was modified to allow both fans to run at the same time. (DCR 1349)

Summary of Safety Evaluation The purpose of this modification was to increase the vessel upper head forced convective cooling during a natural circulation cooldown.

Auxiliary Building Special Ventilation Seventy-two Clark 120VAC, normally energized, Steam Exclusion logic relays were replaced with GE CR1208 relays to eliminate a design problem in the Clark relays which prevented them from dropping out on de-energization. (DCR 980)

Summary of Safety Evaluation l

The 72 affected relays are now qualified to IEEE-323-1974 and IEEE-344-1975. Replacing the Clark relays increases the safety and reliability of the Plant. The modification did not change the function of the relays.

Turbine Building and Screenhouse Ventilation

-Battery room ventilation ductwork and controls were modified to ensure-that the average room temperature will not exceed the room design tem-perature. The modification will improve _ battery cell - cooling pro-longing battery life. (DCR-1184) 16

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. Summary of Safety Evaluation

- . The modification provides a more suitable environment for the batteries increasing their reliability.

Chemical and Volume Control The AC vari-drive on one of the three positive displacement charging pumps was replaced with a DC drive to provide more reliable service.

(DCR 819)

Summary of Safety Evaluation This modification, though not nuclear safety related, improved the

' reliability of the charging pumps.

Replace Plant Process Computer The original plant process computer, Westinghou.;e P-250, was replaced ,

with a Honeywell -4500C computer. In addition to replacing the

! existing functions of the P250, the new computer provides dat'a access i

to the Technical Support Center and the Emergency Operations Facility.

The Honeywell also provides the Safety Parameter Display System (SPDS) i required by NUREG-0737, Supplement 1.- (DCR 1174)

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! Summary of Safety Evaluation No safety related functions are performed by the plant- process .I

. computer. Margin to saturation in' the reactor coolant system, i

thermal power, and nuclear flux calculations, all subject to l Techncial Specification limits, are performed on-this computer as i

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they had been - on . the -P-250.

A separate Safety Analysis Report l was issued for .the SPDS ' concluding that - this change did not-F V;o r

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L13-1.18 introduce any unreviewed safety questions.

(./ Fire Protection Significant work was completed on many modifications required by 10CFR50, Appenclx R Fire Protection Program including the following:

- The dedicated shutdown panel has been partially put into ser-vice with approximately thirty components operational from the panel.

- The installation of required instrumentation on the dedicated shutdown panel is 50% complete.

- The three hour fire wall installation and penetration sealing is 75% complete throughout the plant,

, - Four Containment Fan Coil Units and Service Water Return Motor Valves were repowered to gain cable separation through various fire zones.

l - Cable pulling required for separation of safeguard bus trains is approximately 80% complete.

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- Fire detection system modifications are 90% complete.

- HVAC system modifications are 95% complete.

(DCR's 1189, 1191, 1192, 1193, 1194, 1195, 1197, 1361)

J Summary of Safety Evaluation These modifications enhance both automatic and operator control of the plant in the event of a fire. They will preclude l a fire f*om affecting the capability to bring the plant to safe shutdown. .I i

Turbine The turbine supervisory instrumentation was replaced with a 1

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L13-1.19 Bentley-Nevada system to provide improved monitoring of the turbine. !

The . electrical generator monitoring was also improved by adding a radio frequency monitor and additional RTD's. (DCR's 891, 1152, 1240)

Summary of Safety Evaluation i These' modifications improve the capability to detect problems f with the turbine and generator thereby reducing the probability

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i. of severe secondary plant transients.

Cranes

! Auxiliary Building Crane ' movement was prevented over the last four feet of its eastward travel by installation of redundant limit i

I switches. (DCR 1328) i i

Summary-of Safety Evaluation The limit switches will prevent operation of the Auxiliary t Building Crane above the RHR -heat exchanger discharge piping.

1 These limit switches create an exclusion area preventing'an acci-

-dental load drop from damaging the RHR heat exchanger discharge

{ piping. ,

} Cranes i -

l' A bridge-travel limit switch was added to the Turbine Building Crane to l prevent movement . of the crane over the Battery Rooms. . The limit 1

switch can be. bypassed under certain circumstances with .a key l .'

! controlled by the~ Shift Supervisor. (DCR 1393) ;

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L13-1.20 Summary of Safety Evaluation

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Adding the Turbine Building Crane bridge limit switch will pre-vent the transport of heavy loads over safety related equipment thereby increasing the safety of the plant.

Lighting Battery operated lights were added to provide emergency lighting from the Control Room to the Dedicated Shutdown Panel, at buses 1-5,1-51, 1-52, and at the Diesel Generator 1A Local Control Panel. Some clean up work remains to be done in 1985. (DCR 1542)

Summary of Safety Evaluation Addition of these battery powered lights increases safety by pro-viding a dependable light source on the path to and at safe shut-i down equipment.

Miscellaneous

Numerous equipment changes were required as a result of vendors dropping out of the nuclear market or equipment obsolesence. (DCR's i

1407, 1430, 1504, 1532, 1557, 1592)

Summary of Safety Evaluation These changes involved finding equivalent or better replacement equipment from qualified suppliers and update of the associated documentation, therefore, there were no adverse safety consequen-ces.

Structures

, A 67,000 square foot warehouse and office building was constructed to 20

L13-1.21 increase staff office areas and to provide increased warehouse storage t

facilities for the plant. (DCR 1273)

The plant Security System was modified to allow for control of access to the new office warehouse and office building. (DCR 1356)

The Health Physics group facilities were expanded to provide more space and increase the laundry capability for processing controlled I area clothing. (DCR 1272)

Summary of Safety Evaluation These modifications are not nuclear safety related.

Health Physics Equipment Replaced one of the two portal monitors at the Security Building with a new ' state-of-the-art' monitor, and installed a second at the access O point to the controlled area. (DCR 1422)

Summary of Safety Evaluation The new portal monitors consist of eleven gas flow proportional detectors yielding excellent sensitivity. Contamination control is enhanced by early screening and increased sensitivity of detection.

Pressurizer Relief Valve Repair The pressurizer vault' missile shield was temporarily removed to allow repair.of a small leak on a pressurizer power operated relief valve.

Summary of Safety Evaluation Repair of the leak prevented further degradation thus improving 21

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i L13-1.22 operational safety. Removal of the missile shield allowed this work to be performed at power, eliminating the need for a'tran-sient on the RCS.

Full Power Control Rod Position Change Flow induced vibration wear between the control rod cluster rodlets and the upper internal guide cards was observed at Kewaunee as well as other Westinghouse plants. To prevent clad perforation and distribute the wear the control rods were repositioned from their tra-ditional all rods out position of 228 steps to 226 steps.

Summary of Safety Evaluation

, Conservative analyses were p6rformed for repositioning the control rod banks to 222 steps at full power and no adverse affects on core performance, safety limits, or safety system set-points were determined. The bounding safety analyses assumption remain inviolate and no changes to the Kewaunee Technical Specifications are required for control rod repositioning at 225 steps or above.

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L13-1.23 3.2 Plant Procedures. 10CFR50.59 I

. O There were no procedure revisions during 1984 which introduced an unreviewed safety question or which changed procedures as described in the Updated Safety Analysis Report.

3.3 Tests And Experiments. 10CFR50.59 Core Reload / Physics Testing Thirty-six (36) fresh region L assemblies were loaded for cycle

, X. Routine start-up physics testing was performed and reported j

, in the Cycle X start-up report.

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Summary of Safety Evaluation j A 10CFR50.90 reload safety analysis was performed and sub-

{ mitted 02/14/84.

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L13-1.8 4.0 LICENSEE EVENT REPORTS N

(G This section is a summary of the 21 Licensee Event Reports (LER) sub-mitted to the NRC in 1984 in accordance with the requirements of Technical Specifications. None of the LER's in 1984 posed a threat to plant operation or public safety.

LER 84-01 1

With the plant at 83% power both trains of the Shield Building Ventilation (SBV) system were out of service for approximately 75 minutes. With 1B SBV exhaust. fan tagged out of service for perfor-mance of the Charcoal Filter Heat Detector Surveillance Test, the sur-ve111ance test was mistakenly initiated on train A of the SBV system. Train B had not been demonstrated operable prior to work on train A; although Train B remained in the automatic mode. Both trains of the SBV system were conservatively considered out of service when surveillance testing began on train A. Upon discovery, train B was returned to its normal configuration, demonstrated operable, and returned to service. To prevent recurrence of this event the SBV system filter housings have been clearly marked Train A & B, the sur-ve111ance procedure was revised to more clearly distinguish the system components to be tested, requirements for operator verification of changes in status lights on- the SI active status panel have been included in the above mentioned surveillance procedure, and provisions for signoff and independent verification of steps which affect the operability of the charcoal. filter deluge system have been included in the above mentioned surveillance procedure.

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L13-1.25 LER 84-02

! Just prior to the 1984 refueling outage, at 2% reactor power with the i main generator offline, during the turbine overspeed trip test, a turbine / reactor trip occurred. Low electro-hydraulic control oil pressure, due to leaking turbine control valves, caused the start of the second EHC-oil pump. Manual isolation of the leak resulted in an EHC pressure spike causing rapid opening of #4 turbine control valve.

Increased steam demand caused steam generator 1B level to swell to the hi-hi setpoint which' coincident with P-7 (at power trip permissive) resulted in a turbine / reactor trip, P-7 was enabled by the high impulse pressure caused by the rapid opening of #4 turbine control valve. Immediate operator actions for turbine / reactor trip were taken and systems verified stable.

LER 84-03 During refueling shutdown, underwater inspection of rod cluster control assemblies (RCCA's) revealed three RCCA's with apparent wear marks on the cladding surface. The wear correlated with the full power ' parked' rod position and the control rod guide cards.

Vibration of the rodlets against the guide cards was the suspected wear mechanism. The wear did not exceed Westinghouse criteria for RCCA cladding imperfections and it was determined the three affected RCCA's could be used safely through cycle XI. At full power the control rods are now parked at 226 steps rather than 228 steps to spread the wear area. This LER was reported under "other" as one that may be of generic interest.

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L13-1.26 LER84-04 q

s/ With the plant in refueling shutdown mode, an inadvertent actuation of 18 Shield Building Ventilation (SBV) recirculation fan occurred. An electrician was changing a normally closed (SBV) system relay to a normally open relay. Removal of the relay face plate released the internal springs of the upper tier causing four contacts i to change to the closed position. This contact closure activated the 1B SBV recirculation fan. A descri ptio'n of this event was entered into the Information and Operational Experience Review Program i

and circulated to appropriate plant and corporate supervisors to review with their people. The Plant Operating Review Committee 1

reviewed equipment control practices during modifications to determine if changes would be appropriate LER 84-05 With the Plant in refueling shutdown mode during performance of the Diesel Generator Sequence Loading Panel Slave Relay Monitor test, two slave relays inadvertently picked up actuating 4 valves (SI-11A, 1

SI-20A, SI-302, and SW-1300A) and the 1A Control Room Postaccident Recirculation Fan. The same components actuated during the previous test and again during three subsequent tests. The cause of this event was unknown. Subsequent investigations have not revealed any reason 4

for this event. The test was performed six times daily for a short period and the event did not recur. The test is back on its original schedule; monthly.

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L13-1.27 LER 84-06

/1 U During refueling operating mode, while performing local leak rate surveillance tests, containment isolation valves LD-4A and LD-4B (in parallel) both in series with LD-6, were found to have leakage rates i greater than the upper measuring limit of the local leak rate tester.

Corrective maintenance was performed including replacement of the seat I

ring gaskets in LD-4A and LD-4B and adjustment of the stroke of LD-6.

I A -technical evaluation was performed reviewing this and previous failures to determine proper long term corrective action.

LER 84-07 i

During refueling shutdown, the control room operators noticed that ,

both diesel generators were running. Investigation revealed the start l was caused by an electrician bumping the 1A Turbine Equipment Terminal Box while installing a conduit. Jarring the terminal box caused a Mercoid switch to actuate the " Reactor Auto Stop Trip" relay resulting in a diesel generator automatic start. The diesel generators were secured and the involved parties cautioned. This was considered an isolated event, hence no further follow-up action was required.

l LER 84-08 j During post refueling physics testing, an intermediate range hi-flux reactor trip was received on channel N35. The operators performsd the immediate actions prescribed in the reactor / turbine trip procedure, placed channel N35 out of service and continued with physics testing.

1 The intermediate range hi-flux reactor trip was due to a detector failure which is a recurring problem following refueling outages. An 4

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L13-1.28

, engineering study was initiated to determine possible long term

(- corrective actions.

LER 84-09 At 25% power, during power escalation following the refueling outage, a turbine / reactor trip occurred during the Turbine Thrust Bearing Trip simulation procedure. Another attempt was made to simulate the tur-bine thrust bearing trip at 0% power; resulting in a turbine trip.

Further investigation revealed an Auto Stop Oil pressure switch incorrectly wired, completing the logic for the direct generator trip when the thrust bearing oil pressure instrument indicates >60 psig.

The pressure switch was rewired and returned to normal configuration.

LER 84-10 During plant power escalation from 10% to 25%, the control operator was controlling main feedwater flow in manual. While trying to stabi lize a steam generator level oscillation, the 10-10 set point (17%

NR) was reached causing a reactor trip. The reactor / turbine trip pro-cedure was followed and stable conditions verified. Sensitivity of manual steam generator level control is being addressed in the control room design review program.

LER 84-11 At 59% power, the 1A Shield Building Recirculation Fan was found to be operating with its associated dampers open. No apparent cause for the fan actuation was evident' An auxiliary contact on the fan motor starter was-replaced and the event has not recurred. Incident reports were circulated to operations personnel to make them aware of the possibility of this type of event.

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L13-1.29 LER 84-12 t \

V During full power operation both trains of the Auxiliary Duilding Special Ventilation (ABSV) System were inadvertently started. An Instrument and Control Technician was returning train B of the Steam Exclusion System back to service. The I&C Technician mistakenly requested the control room operator to depress " Zone SV Area Steam Exclusion Train B" instead of " Steam Exclusion Train B Reset"; and as designed, both trains of the ABSV system started. The error was 4

instantly recognized and both trains of the ABSV system were secured and realigned for normal operation. The persons involved were made aware of the significance of this incident.

4 LER 84-13

, During full power operation, train 'B' of the Auxiliary Building Special Ventilation System (ABSV) was found operating with no apparent cause. The control operator attempted to secure the system, and disco-vered a blown fuse for the solenoid valve on the ABSV exhaust filter 1B inlet damper. The-solenoid failed in the closed position automati-cally opening the damper and starting the IB ABSV exhaust fan. Due to similar failures a design change was implemented to replace Johnson

solenoid valves with ASCO solenoid valves.

LER 84-14 During full power operation, loss of power occurred on Instrument Bus IV resulting in a partial loss of instrumentation, various al' arms, and steam generator (S/G) level control problems. Operators took manual control of S/G levels but could - not prevent a reactor trip from lo I

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L13-1.30

~

.. S/G 1evel coincident with steam flow / feed flow mismatch on S/G 1B.

The loss of power on Instrument Bus IV resulted from a loose connec-tion on the line side of its AC output breaker. Vibration over a period of time caused this loose connection to momentarily separate, dropping the instrument bus voltage approximately 100 V. Preventive maintenance procedures on DC equipment have been revised to include

! instrument bus inverters to prevent recurrence of this type of event.

LER 84-15 !

During full power operation, the Refueling Water Storage Tank (RWST) u was found to be approximately 11% below the minimum level required by l Technical Specifications. The low tank level was caused by a valve misalignment which occurred when an operator was isolating the spent fuel pool demineralizer post filter for maintenance. Filling opera tions were started and an orderly shutdown initiated. RWST level was recovered 40 minutes following discovery, and the plant was returned to full power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 12 minutes af ter discovery. All people 1

involved were informed of the significance of this incident. A memo clarifying equipment status control requirements for the Auxiliary Building Filters was written and circulated to the operations personnel.

LER 84-16 During-full power operation, investigation of a work request on RM-14, auxiliary building ventilation radiation monitor, lead an I&C Technician to believe there was a loose connection in the control room instrument drawer. By pulling the control and power cable out of the i

drawer, he unknowingly generated a start signal for train "B" of the l Auxiliary Building Special Ventilation ( ABVS) system. The control room l O l 30 a

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L13-1.31 p_ operators verified the cause, secured the system, and realigned it for

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s- normal operation. A copy of the event was routed to the appropriate personnel stressing the importance of communication before work is initiated.

LER 84-17

^

During full power operation, both fire pumps were without power for approximately two minutes. While performing the annual Fire Pump Flow Test, the equipment operator overlooked a procedural step to close 1B Fire Pump breaker before opening the 1A Fire Pump breaker. The control room operators recieved an alarm and notified the equipment operator to immediately close one fire pump breaker. The fire header pressure remained above the 100 psig Technical Specification limit throughout the incident. The equipment operator was made awar,c of the significance of the incident and reminded of the importance of proce-(d' dural adherence.

LER 84-18 During refueling shutdown mode, several Fan Coil Units (FCU) serving ESF equipment were found to have airflows less than rominal design.

It was suspected that the reduced airflow was caused by cooling fin fouling. The fins were cleaned and the air flow increased, but was still less than nominal design values. An analysis was performed to determine whether existing airflows provided sufficient cooling capa-bilities, it was found that some of the FCU's were undersized for normal temperature conditions. Although some units were found to be undersized, and post accident ambient temperatures determined to be IQ

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L13-1.32 g higher than first anticipat'ed, the FCU's perf'ormance was determined acceptable. Six months later, during power operation. tubeside silt deposits were found and immediately cleaned resulting in increased cooling performance. The FCU's providing cooling for ESF equipment have been included in the Preventive Maintenance Program to prevent recurrence of the heat transfer area fouling. Also an engineering study was initiated to increase cooling capabilities or to provide additional fan coil units. Although not explicitly reportable under the requirements of 10CFR50.73, this event is being reported under OTHER as an item of generic interest.

LER 84-19 f

During full power operation, there was an inadvertent actuation of f train 'B' Auxiliary Building Special Ventilation (ABSV) system, 1

- Control Room Postaccident Recirculation Fan 18, and train 'B'

Safeguards Fan Coil Units. The actuation occurred while calibrating the battery room steam exclusion RTD loops when an I&C Technician lifted a single lead which should have resulted in j a control room alarm only. However a steam exclusion relay had-t been miswired, resulting in a 1 of 2 logic for the steam exclusion signal to actuate ESF ventialtion rather than 2 of 3 logic. The miswired relay was rewired. A procedure was developed to check each channel of the-steam exclusion system for similar problems.

1 LER 84-20 During full power operation, the auxiliary operator discovered that the IB Exhaust Fan of the Auxiliary Building Special Ventilction (ABSV) system was running. Investigation revealed that the coil on the 32

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L13-1.33 solenoid valve controlling the exhaust damper had burned out, failing

(-

O the solenoid in the closed position, opening the exhaust damper and starting the IB Exhaust Fan. Due to similar failures of Johnson Controls solenoid valves a design change was initiated to replace these with ASCO solenoid valves.

LER 84-21 With the plant at full power operation, the Control Room supervisor noticed that the " Boric Acid Tank Out of Service" monitor light was

" bright" on the Safety Injection Ready Status Panel. The " bright" t

light was indication of an abnormal condition. Investigation revealed the Boric Acid Tank selector switch was in the "TK A" position, f however the "B" tank was physically aligned to provide suction to the safety injection pumps. Immediate action was taken to position the

> switch to the "TK B" position. This switch misalignment would have prevented the automatic switchover of the safety -injection pump suc tion to the refueling water storage tank after the boric acid tank was emptied. Factors contributing to the switch misalignment included procedural inadequacies, human error, and 1,ack of communications.

Short term corrective action included immediately returning the TANK SELECTOR SWITCH to the"TK B" position, investigation and iden tifica-tion of why the incident occurred, and discussions among the shift operating crew on the reporting requirements and safety signifi cance.

The- Plant Manager held meetings with deparment heads and plant super-4 visors the following morning to stress the importance of avoiding similar situations. The maintenance and operations superintendents l stressed to their people the importance of job attentiveness ^ and O

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L13-1.34 avoiding personnel errors. Long term corrective action included revising the; procedure that -caused the event, reviewing plant e

Surveillance Procedures to eliminate any similar -inadequacies,

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reviewing SI hardware to determine if any modifications are necessary, f j

the - control modified to allow clear distinction between bright and

. dim, and an independent Technical Review will be performed to investi- '

gate incidents resulting -from personnel error. This event was

[ reported as a 30 day report per 50.73(a)(2)(1) as operation prohibited l 1

j by the plant's Technical Specifications and per 50.73(a)(2)(v) as an j 1

j event that could have prevented the fulfillment of a safety function. f i

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L13-1.16 5.0 FUEL INSPECTION REPORT

() Thirty six (36) fresh Region L assemblies were loaded for Cycle X.

Startup physics testing was performed and reported in the Cycle X 1

Startup Report.

The irradiated fuel inspection was performed with an underwater TV camera. All peripheral fuel rods were examined using one-half face scans. Eight assemblies were inspected, including one each of regions A, G, H and I, two region J and two region K. All assemblies except the two from region K exhibited rod slippage to various degrees with the majority having rods in contact with the bottom nozzle. Numerous i

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.

() The A and one J region ass,emblies showed slight rod bowing. Overall condition of the fuel was very good with no evidence of fuel cladding degradation on the fuel rods examined. 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 1984. j i

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L13-1.18 7.0- STEAM GENERATOR TUBE INSPECTION The Kewaunee Nuclear Power Plant (KNPP) steam generator tubes were eddy current inspected during April, 1984 in accordance with KNPP Technical Specifications and Section XI of the ASME Boiler and Pressure Vessel Code.

The initial inspection program was designed to inspect 100% of the tubes in both steam generators. As a result of the inspection 25 tubes were mechanically plugged.

Five tubes in the 1A steam generator exhibited greater than 50%

through wall indications. The 18 steam generator had 8 tubes with

>50% in,11 cations (>50% through wall requires plugging by KNPP Technical Specifications).

O Following analysis of the eddy current' data, WPSC management decided I to plug three tubes with indications <50% in the 1A steam generator l

and 9 tubes with indicaticns <50% in the IB steam generator.

l The results of the 1984 steam generator eddy current inspection main-tain the Kewaunee Nuclear Power Plant ir 19 C-2 category, requiring the next inspection within 24 months.

I i e Tables 7.1 and 7.2 summarize the 1984 eddy current inspection of the 4

Kewaunee Nuclear Power Plant steam generators.

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l L13-1.19 TABLE 7.1-1A. STEAM GENERATOR

() 1984 EDDY CURRENT EXAMINATION :

% THRU-WALL R0W COLUI-:N PENETRATION PLUGGED GENERAL INFORMATION 18 6 26 DEGRADED TUBE: A tube with % thru-wall 13 4 20 penetration >20%.

32 16 33 33 16 31 DEFECTIVE TUBE: A tube with % thru-wall 11 23 26 penetration >50%; or, if significant 3 36 75 X general tube thinning occurs a defective 7 36 37 X tube is any tube with % thru-wall 23 36 55 X penetration >40%.

46 43 23 17 44 81 X EXTENT OF 1A STEAM GENERATOR INSPECTION 20 46 39 X # of tubes inspected up 20 47 52 X inspected to 21 47 43 X 3100 full length 25 '47 27 174 U-bend 21 48 50 X 85 #7 tube support plate 24 48 26 2 #1 tube support plate 29 49 24 11 52 21 Tubes Plugged in Steam 18 52 26 i Generator 1A (1984) = 8 11 53 21 11 55 21 Tubes Plugged in Steam 11 59 27 Generator.1A (1983) = 23 O- 11 60 30 25 63 20 TOTAL PLUGGED TUBES IN 6 80 25 1A STEAM GENERATOR = 31 38 ;

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L13-1.20 TABLE 7.2 (g

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(PAGE 1 0F 2) 18 STEAM GENERATOR 1984 EDDY CURRENT INSPECTION

% THRU-WALL R0W COLUMN PENETRATION PLUGGED GENERAL INFORMATION 32 45 33 DEGRADED TOBE: A tube with % thru-wall 13 46 40 X penetration >20%.

6 47 39 10 47 39 DEFECTIVE TUBE: A tube with % thru-wall 14 47 23 penetration >50%; or, if significant general 25 47 35 X tube thinning occurs a defective tube is 33 47 30 X any tube with % thru-wall penetration >40%.

24 48 20 27 48 42 EXTENT OF IB STEAM GENERATOR INSPECTION 30 48 27 32- 48 59 X # of tubes Inspection up 33 48 27 inspected to:

15 49 21 3142 Full len9th 31 49 22 187 U-bend 27 51 26 1 #1 tube support plate 29 52 33 31 54 50 X 33 54 31 Tubes plugged in IB Steam 33 56 36 Generator (1984) = 17

("N 27 63 25

(. 17 64 20 Tubes plugged in IB Steam 26 64 57 X Generation (1983) = 49 37 64 37 23 67 63 X TOTAL PLUBBED TUBES IN 1B 23 68 54 X STEAM GENERATOR = 76 33 73 34 9 19 28 5 20 -33 8 22 22 9 23 25 16 26 35 26 27 52 X 16 28 33 25 31 25

, 24 32 33 25 32 47 X

. 24 33 27 X 3

25 33 30 X 7 37 45 X 26 37 49 X 31 39 26 39

()

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L13-1.20a TABLE 7.2 (PAGE 2 0F 2) 4 1B STEAM GENERATOR

j. 1984 EDDY CURRENT INSPECTION i

% THRU-WALL R0W COLUMN PENETRATION PLUGGED GENERAL INFORMATION 11 40 36 i- 15 40 25 See page 1 of 2.

25 41 33 2 42 90 X i 13 42 29

! 16 -42 33 25 42 31 42 30 30 4 31 42 43 X 32 42 36 X l 16 43 21 l 32 43 27 19 89 23 I

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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 in table 8.1. Tables 8.2, 8.2, and 8.4 provide a breakdown of the total number of individuals for whom personnel monitoring was provided.

Table 8.1 TOTAL NUMBER OF INDIVIDUALS FOR WHOM PERSONNEL MONITORING WAS PROVIDED IN 1984 Exp. Range (mR) No. of Personnel No Measurable 332

< 100 194 100 - 249 95 250 - 499 75 500 - 749 65 750 - 999 34 1000 - 1999 16 3

2000 - 2999 2 3000 - 3999 1 Grand Total 814 i

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Table 8.2

() TOTAL NUMBER OF CONTRACTORS PROVIDED WITH PERSONAL DOSE MONITORING DEVICES Exp. Range (mR) No. of Personnel No Measurable 211

< 100 103 100 - 249 63 250 - 499 48 500 - 749 42 750 - 999 26 1000 - 1999 11 2000 - 2999 0 3000 - 3999 0 Total 504

() Table 8.3 TOTAL NUMBER OF WPSC PLANT STAFF PROVIDED WITH PERSONAL DOSE MONITORING Exp. Range (mR) No. of Personnel No Measurable 75

< 100 56 l

100 - 249 26 l

250 - 499 25 l

I 500 - 749 21 i

750 - 999 7

. 1000 - 1999 4 2000 - 2999 2 I 3000 - 3999 1 Total 217 e

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- TOTAL NUMBER OF PERSONNEL (WPSC NON-PLANT STAFF) PROVIDED WITH PERSONAL DOSE MONITORING DEVICES 4

j Exp. Range (mR) No. of Personnel

No Measurable 46

< 100 35 f

100 - 249 6 1 250 - 499 2 500 - 749 2 r 750'- 999 1 l'

1000 - 1999 1 2000 - 2999 0 i'

3000 - 3999 0 i- Total 93 i

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A tabulation of numbers of personnel exposure and man-rem received

! by work and job function is shown in Table 8.5 in accordance with j Section 6.9.1.b of Kewaunee, Nuclear Power Plant Technical l Specificaiton. The table shows the total man-rem exposure for-the l

l year was 139.172.

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9.0 RADIOLOGICAL MONITORING PROGRAM Attached is the report from Teledyne Isotopes on the Radiological -

Monitoring Program for Kewaunee Nuclear Plant for 1984.

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T TELEDYNE '

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- ISOTOPES MIDWEST LABORATORY 1509 FRONTAGE RD.

NORTHBROOK,lL 600624197 l

(312)564 4700 REPORT TO WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY i MADISON GAS AND ELECTRIC COMPANY l

RADIOLOGICAL MONITORING PROGRAM FOR THE KEWAUNEE NUCLEAR POWER PLANT KEWAUNEE, WISCONSIN ANNUAL REPORT - PART I O

SUMMARY

AND INTERPRETATION January - December 1984 PREPARED AND SUBMITTED BY TELEDYNE IS0 TOPES MIDWEST LABORATORY PROJECT NO. 8002 l l

Approved by: , . _ . ]f L/4// _

L. G." Hug 6/e'r' General Mnager 1

O 8 February 1985 1

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PREFACE The staff members of the Teledyne Isotopes Midwest Laboratory 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 L. G. Huebner, General Manager. He was assisted in report preparation by other staff members of the laboratory.

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O TABLE OF CONTENTS Page Preface . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii Li s t of Fi gure s . . . . . . . . . . . . . . . . . . . . . . . . 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 Air Program . . . . . . . . . . . . . . . . . . 3 3.1.2 The Terrestrial Program . . . . . . . . . . . . . . 4 3.1.3 The Aquatic Program . . . . . . . . . . . . . . . . 5 3.1.4 Program Execution . . . . . . . . . . . . . . . . . 6 3.1.5 Program Modifications . . . . . . . . . . . . . . . 7 3.2 Results and Discussion . . . . . . . . . . . . . . . . . . 7 3.2.1 Atmospheric Nuclear Detonation .......... 7 3.2.2 The Air Environment . . . . . . . . . . . . . . . . 7 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

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A. Crosscheck Program Results. . . . . . . . . . . . . . . . . A-1 B. Statistical Notations . . . . . . . . . . . . . . . . . . . B-1 C. Maximum Permissible Concentrations of Radioactivity in Air and Water above Natural Background in Unrestricted Areas . . . . . . . . . . . . . . . . . . . . . . . . . . C-1 O

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LIST OF FIGURES j

No. Caption Page 4-1 Sampling locations, Kewaunee Nuclear Power Plant . . . . . . . 16 1

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

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!O LIST OF TABLES No. Title Page 4.1 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 1

4 4.4 Sampling Summary . . . . . . . . . . . . . . . . . . . . . . . . . 20 4.5 Environmental Radiological Monitoring Program Summary. . . . . . . 21 l

In addition, the following tables are in the Appendix ,

, Appendix A A-1 Crosscheck program results, milk and water samples, 1980-84. . . . A-3 ,

I A-2 Crosscheck program results, thermoluminescent dosimeters (TLDs). . A-11 Appendix C 4

C-1 Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas . . . C-2 I

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1.0 INTRODUCTION

The Kewaunee Nuclear Power Plant is a 535 megawatt pressurized water reactor located on the Wisconsin shore of Lake Michigan . in Kewaunee County. The Kewaunee Nuclear Power Plant became critical on March 7,1974. Initial power 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 1984.

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

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2.0

SUMMARY

i Results of sample analyses during the period January - December 1984 are summarized in Table 4.5, Radionuclide concentrations measured at indicator locations are compared with levels measured at control locations and in preoperational studies. The comparisons indicate background-level radio-activities in all samples collected with the following exceptions:

l 1. Trace amounts of cobalt-58 and cobalt-60 were detected in several bottom sediment samples. The presence of these isotopes in bottom sediment samples is probably plant related.

2. Nine samples collected at discharge (K-Id) and six samples collected at Two Creeks Park (K-14) had elevated tritium levels. The annual mean tritium i

concentration at the discharge was 1840 pCi/l above background level. The highest concentration was d

measured in the sample collected on August 6, 1984 and yielded 3730 pC1/1 above background level. The presence of tritium in the discharge water is attrib-utable to the Kewaunee Nuclear Plant operation, but the highest discharge rate measured constitutes only 0.12% of the maximum permissible concentration of 3,000,000 pCi/l established in the 10 CFR 20 Document.

The annual mean tritium concentration in lake water

' collected at Two Creeks Park was 2470 pCi/l above background level and the maximum was measured in the sample collected on February 1, 1984 (13,690 pCi/1 above background level). The source of the elevated levels in samples collected at Two Creeks Park is not clear since this point is equidistant from the Kewaunee and Point Beach Nuclear Plants, either one of which, or both, could have been the sourcefof the elevated tritium level.

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l 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 loca-tions.

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 l program are described below. Finally, the execution of the program in '

the current reporting year is discussed.

l 3.1.1 The Air Program Airborne Particulates The airborne particulate samples are collected on 47 mm diameter glass fiber filters at a volumetric rate of approximately one cubic foot per minute. The filters are collected weekly from six locations (K-lf, K-2, K-7, K-8, K-15, and K-16), and dis-patched by mail to TIML for radiometric analysis. The material on the filter is counted for gross alpha and beta activity approximately five days af ter receipt to allow for decay of naturally-occurring short-lived radionuclides.

Quarterly composites from each sampling location are analyzed for gama-emitting isotopes by a germanium detector, u

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Airborne Iodine 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 af ter arrival at the laboratory.

Ambient Gamma Radiation - TLDs The integrated gama-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, K-4, K-5, and K-6) with thermoluminiscent dosimeters (TLDs). CaF 2 :Mn bulb TLDs are exchanged quarterly and annually.

Precipitation 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 b 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 iodine-131, strontium-89 and -90, cesium-137, barium-140, potassium-40, calcium, and stable potassium.

Well Water One gallon water samples are collected quarterly from four off-site wells located at K-10, K-11, K-12, and K-13. Monthly one-gallon water samples are collected from two on-site wells located at K-19 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 determined by liquid scintillation technique.

Quarterly composites of monthly grab samples of water from one n on-site well (K-1g) are analyzed for strontium-89 and strontium-90.

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Domestic Meat Domestic meat samples (chickens) are obtained annually (in the third quarter) at locations K-20, K-24, K-25, and K-27. The flesh is separated from the bones, gama scanned, and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.

Eog.s Eggs are collected quarterly at Location K-27. The samples are gama scanned and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.

Vegetables Vegetable samples (5 varieties) are collected at locations K-17 and K-26, and two varieties of grain, if available, at location K-23. The samples are gama scanned and analyzed for gross alpha, gross beta, strontium-89, and strontium-90 activities.

Grass and Cattle Feed Grass samples are collected during the second, third and fourth c) 6 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 gama 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 performed.

Soil Soil samples are collected twice a year on-site at K-1f and from the six dairy farms (K-3, K-4, K-5, K-6, K-12, and K-19).

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

I 3.1.3 The Aquatic Program i

Surface Water l One-gallon water samples are taken monthly from three locations 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 f3 monthly from three creeks that pass through the site (K-la,

(

') K-lb, and K-le). Samples from North and Middle Creeks (K-la, K-lb) are collected near the mouth of each creek. Samples from i

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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G 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 Fish samples are collected in the second, third, and fdurth quarters at Location K-Id. The flesh is separated from the bones, gama scanned - and analyzed for gross alpha and gross beta activity. Ashed bone samples are analyzed for gross alpha, gross beta, strontium-89 and strontium-90 activities.

Slime Slime samples are collected during the second and third quarters 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 activi-ties. If the quantity is sufficient, they are also gamma scanned O

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and analyzed for strontium -89 and strontium-90 activities.

Bottom Sediments Gottom sediments are collected four times a year from five locations (K-lc, K-Id, 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 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 summarized in Table 4.4. The program was executed as described in the preceding sections with the following exceptions:

(1) Precipitation samples were not collected in March and December 1984 because they were not available.

(2) No buckwheat was collected at location K-23 because it was not grown there in 1984, p

Q (3) There was no air particulate data from Location K-15 for the collection period ending Janury 24, 1984 because the filter paper was lost in the field.

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J 3.1.5 Program Modifications There were no program modifications during 1984.

3.2 Results and Discussion l The results for the reporting period January to December 1984 are presented in sumary form in Table 4.5. For each type of analysis of i each saapled medium, this table shows the annual mean and range for all indicator locations and for all control locations. The location 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 Teledyne Isotopes Midwest Laboratory or its prececessor, Hazleton Environmental Sciences.

, The tabulated results of all measurements made in 1984 are not included in this section, although references to these results will be made i in the discussion. The complete tabulation of the 1984 results is contained in Part II of the 1984 annual report on the Radiological 1

Monitoring Program for the Kewaunee Nuclear Power Plant.

3.2.1 Atmospheric Nuclear Detonations There were no reported atmospheric nuclear tests in 1984. The last reported test was conducted by the People's Republic of China on October 16, 1980. The reported yield was in the 200 kiloton to 1 megaton range. l l

l 3.2.2 The Air Environment l Airborne Particulates !

I For air particulates, both gross alpha and gross beta measure- '

ments yielded annual means that were nearly identical for the indicator and control locations. Mean gross alpha activity was slightly higher than in 1983 while mean gross beta activity was indentical to that in 1983. The highest annual means for gross alpha and gross beta were measured at control location K-16, 26 miles NW of the station, and at control location K-9, 9.5 miles NNE of the station, respectively.

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V Gross alpha and beta activities at all locations were also analyzed by quarters. The activity was higher in the first quarter, declined during the second quarter, and rose slightly during the third and fourth quarters. There was no clear cut evidence of the 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 from the stratosphere (Gold et al., 1964).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Berylium-7, which is produced continously in the upper atmosphere by cosmic radiation ( Arnold and Al-Salih,

, 1955), was detected in nine of twenty-four samples and was the only gama-emitting isotope detected. There was no indication of a station effect on the data.

All other gama-emitting isotopes were below their respective LLD limits.

Airborne Iodine J

Bi-monthly levels of airborne iodine-131 gere below the lower t limit 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.

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Ambient Gamma Radiation - TLDs Ambient gamma radiation was monitored by TLDs at ten locations:

four indicator and six control.

The quarterly TLDs at the in dose equivalent of (53.817.2)gicator mR/365locations days, inmeasured agreementawith mean the mean at the control locations of (51.715.0) mR/365 days, and were nearly identical to the means obtained in 1983 (50.4 and 51.3 mR/365 days, respectively). The quarterly measurements agreed within the error with the annual measurements which were (59.2i3.7)-mR/365 days, for the indicator and (58.916.4) mR/365 days for the control locations. All these values are slightly lower than the United States average value of 78 mR/ year due to natural background radiation (National Council on Radiation Protection and Measurements,1975). The highest means for the quarterly and annual TLDs were 63.9 and 67.8 mR/365 days and occured at control locations K-3 and K-8, respectively.

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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 the 95% confidence level.

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l Precipitation l

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

Tritium was detected in four samples and averaged 140 pCi/1, This level of activity is expected in the precipitation and is attributable to the previous nuclear tests in the atmosphere.

3.2.3 The Terrestrial Environment Milk Of the 198 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 2.9 pCi/1 in all samples.

Strontium-90 was found in all but one sample. The mean values were nearly identical for indicator and control locations (1.7 pCi/l and 1.8 pCi/1, respectively).

Barium-140 activity was below the LLD of 10 pCi/1 in all samples.

Cesium-137 activity was also below the LLD of 10 pCi/1 in all Os samples.

Potassium-40 results were nearly identical at both the indicator.

and control locations and were essentially identical to the levels observed in 1978, 1979, 1980, 1981, 1982, and 1983.

Due to the chemical similarities between strontium and calcium, and cesium and potassium, organisms tend to deposit cesium-137 in the sof t 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 statis-tically significant variations in the ratios were observed. The measured concentrations of stable potassium and calcium are in agreement with previously determined values of 1.5010.21 g/l and 1.1610.08 g/1, respectively (National Center for Radiological Health,1968).

Well Water ,

Gross alpha activity in well water was below the LLD level of '

2.8 pCi/1 in all samples.

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Gross beta activity in well water was 1.9 pCi/l in samples from the control location. The mean value for all indicator locations l was 2.3 pCi/l and was nearly identical to the values observed in 1977, 1978, 1979, 1980, 1981, 1982, and 1983 (3.3 pCi/1, 3.4 pci/1, 3.0 pCi/1, 3.0 pCi/1, 3.6 pCi/1, 3.2 pCi/1, and 2.9 pCi/1, respectively).

Tritium activity in the on-site well (K-1g) was below the LLD of 100 pCi/1 in all samples.

The activities of strontium-89 and strontium-90 in well water were below their respective detection limits.

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

Domestic Meat In meat (chickens), gross alpha activity was similar at both indicator and control locations (0.26 and 0.32 pCi/g wet weight, respectively). Gross beta activity averaged 2.33 pCi/g wet weight for indicator locations and 2.79 pCi/g wet weight for O

V control locations. Gamma-spectroscopic analysis showed that most of the beta activity was due to naturally occurring potassium-40.

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

5.995 In egg samples, the gross alpha activity averaged 0.010 pCi/g wet weight. Gross beta activity averaged 1.14 pCi/g wet weight, about equal to the activity of the naturally occurring potassium-40 observed in the samples (1.15 pCi/g). The levels of stron-tium-89 and strontium-90 and all other gamma-emitting isotopes were below their respective LLD's.

Vegetables In vegetables, alpha activity averaged 0.58 and 0.23 pCi/g wet weight in indicator and control samples, respectively. Gross beta activity was slightly higher at the indicator location than at the control location and was due primarily to the potassium-40 activity. Strontium-89 activity was below the LLD of 0.028 pCi/g wet weight in all samples. Strontium-90 activity was lower at the control locations than at indicator locations (0.015 pCi/g

(~T wet weight and 0.005 pCi/g wet weight, respectively). All other U gama-emitting isotopes were below their respective LLD levels.

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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.

Grass and Cattle Feed In grass, gross alpha activity was essentially identical at both indicator and control locations (0.7 and 0.6 pCi/g wet weight, respectively). Gross beta activity was slightly higher at indicator locations (6.8 pCi/g wet weight) than at the control locations (6.0 pCi/g wet weight) and in both cases was predomi-nantly due to naturally occurring potassium-40 and bery111um-7.

All other gama-emitting isotopes were below their respective LLD's. Strontium-89 was below the LLD of 0.09 pCi/g wet weight in all samples. Strontium-90 activity was detected in seventeen of twenty-four samples and was higher at indicator than at control locations (0.032 and 0.025 pCi/g wet weight, respec-tively). Presence of radiostrontium in some of the samples is attributed to the f allout from the previous nuclear tests.

For cattlefeed, the mean gross alpha activity at indicator loca-p)

(

tions was 0.68 pCi/g wet weight and 0.44 pCi/g wet weight at control locations. Mean gross beta activity was slightly higher at indicator locations (8.80 pCi/g wet weight) than at control locations (7.58 pCi/g wet weight). The highest gross beta level was in the sample from indicator location K-19 (15.96 pCi/g wet weight), and reflected the high potassium-40 level (10.5 pCi/g wet weight) observed in the sample. The pattern was similar to that observed in 1978, 1979, 1980, 1981, 1982, and 1983. Strontium-89 levels were below the LLD level at 0.19 pCi/g wet weight in all samples. Strontium-90 activity was higher at indicator locations than at control locations (0.066 and 0.046 pCi/g wet weight, respectively). The presence of the g radiostrontium is attributable to the fallout from the previous "4 nuclear tests. All other gamma-emitting isotopes were below their respective LLD levels.

Soil No significant differences were found between indicator and control values in soll samples. The difference of 0.1 pCi/g dry weight in mean gross alpha activity between indicator locations and control locations is not statistically significant because the counting uncertainties of the individual measurements are typically 3-5 pCi/g dry weight. Mean gross beta levels were similar at both indicator and control locations (24.6 and 26.8 (n) v pCi/g dry weight, respectively), and is primarily due to the potassium-40 activity. Strontium-89 was below the LLO level of 11

l 0.29 pCi/g dry weight in all samples. Strontium-90 was detected in six of fourteen samples and was slightly higher at control than at indicator locations (0.18 and 0.15 pCi/g dry weight, respectively). Cesium-137 was detected in all samples and was higher at control locations tnan at indicator locations (0.62 and 0.30 pCi/g dry weight, respectively). All other gamma-emitting isotopes were below their respective LLD's. The levels of detected activities were similar to those observed in 1979, 1980, 1981, 1982, and 1983.

l 3.2.4 The Aquatic Environment Surface Water In surface water, the gross alpha activity in suspended solids was below the LLO of 1.0 pCi/l in all samples. In dissolved solids, gross. alpha activity was detected in five of seventy-two samples and averaged 3.0 pCi/1.

Mean gross beta activity in suspended solids was detected in thirteen samples and averaged 0.6 pCi/1, barely above the detec-tion limit of 0.5 pCi/1. Mean gross beta activity in dissolved A solids was higher by a factor of two at indicator locations (5.0 l V pCi/1) as compared to the control locations (2.7 pCi/1) 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 pC1/1),

1981 (4.3 and 2.7 pCi/1), 1982 (4.9 and 2.4 pCi/1), and 1983 (5.1 and 2.6 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 l 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 fluctua-tions in beta activity were due to variations in potassium-40 concentrations and not to plant operations. The fact that similar fluctuations at these locations were observed in the l pre-operational studies conducted prior to 1974 supports this assessment.

Annual mean tritium activity was 2310 pCi/l at indicator loca-tions and was below LLD of 220 pC1/1 at control locations. The l mean activity at the discharge (K-1d) was 1840 pCi/1 above the background level of 220 pCi/1 and 2470 pCi/l above the background level at Two Creeks Park, located 2.5 miles south of the plant.

The elevated annual mean of 1840 pC1/1 above background in the

, discharge water is attributable to the plant operation, but l

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constitutes about 0.06% of the maximum permissible concentration l of 3,000,000 pCi/l established in the 10 CFR 20 Document. The !

highest level of 4730 pCi/l above background level detected in l the sample collected August 6,1984 constitutes less tSan 0.16%

of the permissible level.

The highest level measured at Two Creeks Park was 13,690 pCi/l and constitutes about 0.46% of the permissible level. However, since the Two Creeks ' Park location is equidistant from the Kewaunee and Point Beach Nuclear Plants, it could not be deter-mined which plant was the source of this activity.

Strontium-89 activity was below the LLD of 1.9 pCi/l in all sam-ples. Strontium-90 activity was detected in one of twelve samples and was 3.2 pCi/1.

Fish In fish samples, gross alpha activity averaged 0.17 pCi/g wet weight in muscles and was below detection limit in all bone fractions. In muscle, gross beta activity was primarily due to potassium-40 activity. The average beta activity of 2.34 pCi/g wet weight was near the average of the 1973 range of 2.26 to 3.62 s pCi/g wet weight. The cesium-137 activity in muscle averaged 0.10 pCi/g wet weight and was nearly identical to the level observed in 1979 and 1980 (0.12 pCi/g wet weight in both years),

1981 (0.15 pCi/g wet weight), in 1982 (0.17 pCi/g wet weight),

and in 1983 (0.14 pCi/g wet weight). The strontium-89 and strontium-90 levels were below their respective LLDs.

, Periphyton (Slime) i In periphyton (slime) samples, gross alpha activity was nearly identical at both indicator and control samples (0.7 and 0.8 pCi/g wet weight, respectively). Mean gross beta activity was higher at indicator than at control locations (2.1 and 0.8 pCi/g wet weight, respectively). Strontium-89 activity was below the

, LLD level of 0.41 pCi/g wet weight in all samples. Strontium-90

activity was below the LLD level of 0.10 pCi/g wet weight in all

samples. All gamma-emitting isotopes, except naturally-occurring potassium-40, were below their respective LLDs..

Bottom Sediments In bottom sediment samples, gross alpha levels were below the LLD l of 4.2 pCi/g dry weight in all samples but five. The mean s") detected activity was 6.1 pCi/g dry weight, about the same as in

! 1983(6.2 pCi/g dry weight).

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O The mean gross beta activity was slightly higher at indicator locations than at the control location (8.4 and 7.4 pCi/g dry weight, respectively) and was due mostly to potassium-40. The difference is not statistically significant.

i Cesium-137 was detected in sixteen of twenty samples and averaged 0.07 pCi/g dry weight. The level was slightly lower than the levels observed in 1979 (0.12 pCi/g dry weight), in 1980 (0.19 pCi/g dry weight), in 1981 (0.18 pCi/g dry weight), in 1982 (0.13 pCi/g dry weight), and in 1983 (0.16 pCi/g dry weight).

Strontium-89 and strontium-90 levels were below their respec-tive LL0s (0.20 and 0.10 pCi/g dry weight, respectively) in all samples. Trace amounts of cobalt-58 (eleven samples) and cobalt-60 (seven samples) were detected near the condenser discharge. Presence of trace amount of these activation products in bottom sediments is probably plant related.

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4.0 FIGURES AND TABLES l

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SCALE IN MILES -

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Figure 1. Sampling locations, Kewaunee Nuclear Pcwer Plant.

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O O O 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 ld I 0.10 E Condenser discharge le I 0.12 S South Creek

'If I 0.12 5 Meteorological tower lg I- 0.06 W South Well lh I 0.12 NW North Well lj I 0.10 S 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 farm, Route 1, Kewaunee K-4 I 3.0 N Dan Stangel farm, 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

'd north of Kewaunee K-10 I 1.5 NNE Turner farm, Kewaunee site K-11 I 1.0 NW Harlan Ihlenfeld farm K-12 I 1.5 WSW Lecaptain farm, one mile west of site K-13 C 3.0 SSW ' Rand's general ' store 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 "BB")

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-23 1 0.5 W 0.5 miles west of plant, Kewaunee Site K-24 I 5.45 N Fectum farm, Route 1, Kewaunee K-25 C 2.75 WSW Wotachek farm, Route 1, Denmark K-26d C 10.7 SSW Bertler's Fruit Stand (8.0 miles south of "BB")

K-27 I 1.5 NW Schlies Farm, 0.5 miles west of K-ll a I = indicator; C = control b Distances are measured from reactor stack.

c The K-6 sampling location was changed on October 17, 1980 because the operator of Berres Farm retired.

Berres Farm has been replaced by Novitski Farm, located 0.2 miles West of Berres Farm.

d Location K-18 was changed because the Schmidts Food Stand went out of business and was replaced by Bertler's fruit Stand (K-26).

p m y

. Tabic 4.2 Type and frequency of collection.

Frequency Location Weekly Bi-weeklyl Monthly Quarterly Semi-Annually Annually K-1 K-la SW SL K-lb SW GRa SL K-Ic BSb K-Id SW BSb FIa SL K-le SW SL K-lf AP Al GRa TLD. 50 TLD K-Ig WW K-lh WW K-lj BSb K-2 AP AI TLD TLD K-3 MIC GRa TLD CFd 50 TLD K-4 MIc GRa TLD CFd SD TLD K-5 MIc GRa TLD CFd 50 TLD K MIc GRa TLD CFd 50 TLD K-7 AP AI TLD TLD K-8 AP Al TLD TLD E K-9 SW BSb st K-10 WW K-11 PR WW.

K-12 MIc GRa CFd WW S0 K-13 WW K-14 SW BSb SL K-15 AP Al TLD TLD K-16 AP Al TLD TLD K-17 DM,VE K-18e VE K-19 MIc GRa CFd so K-20 DM K-23 GRN K-24 DM K-25 DM K-26 VE K-27 EG

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

b To be collected in May, July, Sept., Nov.

c Monthly from November through April; weekly from May through October.

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

e Replaced by K-26 in summer of 1982.

O Table 4.3 Sample cddes used in Table 4.2.

Code Description AP Airborne Particulate AI Airborne Iodine TLD Thermoluminescent Dosimeter PR Precipitation MI Milk WW Well Water DM Domestic Meat EG Eggs VE Vegetables GRN Grain O GR p

Grass CF Cattlefeed 50 Soil SW Surface Water FI Fish SL Slime BS Bottom Sediments a

O- l

.19

^

m______.___. . . _ . . _ _ . _ . _ . , . _ _ . _ . . , , _ . _ . _ _ . .

O O O Table 4.4. Sampling sunenary, January - December 1984.

Collection Number of Nunter of Sample Type and Nunber of Samples Samples Type Frequencya Locations Collected Missed Remarks Air Environment Airborne particulates C/W 6 311 1 See text Page 6.

Airborne iodine C/BW 6 157 0 TLD's C/Q 10 40 0 l C/A 10 10 0 l Precipitation C/M 1 10 2 See text Page 6. j l

Terrestrial Environment Milk (May-Oct) G/W 6 162 0 (Nov-Apr) G/M 6 36 0 Well water G/M 2 24 0 G/Q 4 16 0 m

o 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

- buckwheat G/A 1 0 1 See text Page 6.

Grass G/TA 8 24 0 Catt!e Feed G/A 6 6 0 Soil G/SA 7 14 0 Aquatic Environment Surface water G/M 6 72 0 Fish G/TA 1 4 0 Slime G/SA 6 12 0 Bottom sediments G/FA 5 20 0 a

Type of collection is coded as follows: C = continuous; G = grab. Frequency is coded as follows:

W = weekly; M = monthly; Q = quarterly; SA = semi-annually; TA = three times per year; FA = four times per year; A = annually; BW = bi-weekly.

O U

d V

. Table 4.5 Environmental Radiological Monitoring Program Sumary.

Name of facility Kewaunee Nuclear Power Plant Docket No. 50-305 Location of facility Kewaunee county, Wisconsin Reporting Period January - December 1984 (County,5 tate)

Indicator Location witn Highest Control Sample Type and Locations Annual Mean Locations Nunter of Type Nunter of Mean(F)C Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Airborne GA 311 0.003 0.0046 (85/104) K-16, Green Bay 0.0058 (49/52) 0.0050 (177/207) O particulates (0.0008-0.0156) 26 mi NW (0.0010-0.0125) (0.0001-0.0196)

(pCi/m3)

G8 311 0.002 0.018 ( % /104) K-2, Kewaunee 0.019 (45/52) 0.019 (193/207) 0 (0.002-0.062) 9.5 mi NNE (0.003-0.058) (0.002-0.068)

K-7, Bruemer Farm 0.019(47/52) 2.75 et SSW (0.003-0.062)

K-15, Gas Substation 0.019 (45/51) 9.25 mi NW (0.005-0.046)

GS 24 Be-7 0.040 0.081 (5/8) K-7, Bruemer Farm 0.093 (2/4) 0.078 (4/16) 0 ro

" (0.051-0.121) 2.75 mi SSW (0.065-0.121) (0.061-0.093)

Nb-95 0.0062 <LLD - - (LLD 0 Zr-95 0.0068 (LLD - - <LLD 0 Ru-103 0.0069 <LLD - - <LLD 0 Ru-106 0.016 <LLD - - <LLD 0 Cs-137 0.0020 <LLD - - <LLD 0 Ce-141 0.011 <LLD - -

<LLD 0 Ce-144 0.015 <LLD - - <LLD 0 t

Airborne 1-131 157 0.01 <LLD - - 0 lodine (pCl/m3)

TLD -0jarterly Gama 40 5 13.4 (16/16) .K-7, Bruemer Farm 15.8 (4/4) 12.9 (24/24) 0 (mR/91 days) (10.4-17.6) 2.75 mi SSW (13.7-17.6) (10.7-16.1) 0 Gama 10 5 53.8 (4/4) K-7, Bruemer Farm 63.9 (1/1) 51.1 (6/6) 0 TLD-Ojarterly (mR/365 days ) (46.4-63.5) 2.75 mi SSW -

(47.2-59.5)

Gama 10 5 59.2 (4/4) K-J. Stangel Farm 67.8 (1/1) 58.9 (6/6) 0 TLD-Annual (mR/365 days) (55.1-63.9) 3.0 mi N -

(51.3-67.8) ,

f\

V \

t V

Tab'e 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sanple Type and Locationg Annual Mean Locations Nusber of Type Number of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Precipitation H-3 10 100 140'(4/10) K-11 In'eafald Jarm 140(4/10) None 0 (pCl/1) (100-180) 1.0 mi NW (100-180)

Milk I-131 198 0.5 <LLD - - <LLD 0 (pC1/1)

Sr-89 72 2.9 <LLD - - <LLD 0 Sr-90 72 0.6 1.7 (48/48) K-12, Lecaptain Farm 2.4 (12/12) 1.8 (23/24) 0 (0.7-3.7) 1.5 mi WSW (1.5-3.7) (0.9-2.9)

GS 72 K-40 50 1310 (48/48) K-12. Lecaptain Farm 1340 (12/12) 1260(24/24) 0 (1070-1540) 1.5 mi WSW (1070-1480) (940-1730)

Cs-137 10 <LLD - -

<tLD 0 y Ba-140 10 <tLD - -

<LLD 0 l (g/1) K-stable 72 1.0 1.48 (48/48) K-12, Lecaptain Fars 1.52(12/12) 1.42 (24/24) 0 l (1.22-1.75) 1.5 mi WSW (1.22-1.68) (1.01-1.97)

(g/1) Ca 72 0.5 1.1 (48/48) K-6. Novitsky Farm 1.3 (12/12) 1.2 (24/24) 0 l (0.6-1.3) 6.7 et WSW (1.0-1.4) (1.0-1.4)

Well Water ; M 40 2.8 <LLD - i - <LLD 0 (pC1/1) l G8 40 0.5 2.3 (36/36) K-lh, North Well 2.8(12/12) 1.9 (4/4) 0 (0.6-4.1) Onsite, 0.12 mi NW (1.9-4.0) (1.5-2.1) l K-Ig, South Well 2.8 (12/12)

Onsite, 0.06 mi W (1.4-4.1) i H-3 4 100 <LLD - - None 0 K-40 40 0.10 1.7 (36/36) K-Ig, South Well 2.0 (12/12) 1.2 (4/4) 0 (flame) (0.6-4.1) Onsite, 0.06 mi W (1.8-2.7) (1.0-1.4)

Sr-89 4 2.1 <tLD - -

None O Sr-90 4 0.5 <tLD - - None 0 f

.__._ _______________...__-_._____._m_.

O O O.

Table 4.5 (continued)

Name of facility Kewaunee % clear Power Plant-Indicator Location with tiighest Control Nueer of Sample Type and Locationg Annual Mean Locations Type Neer of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Domestic Meat GA 4 0.03 0.26 (3/3) K-24 Fectum Fara 0.36 (1/1) 0.32(1/1) 0 (chickens) (0.16-0.36 5.45 mi N - -

(pC1/g wet)

G8 4 0.5 2.33 (3/3) K-27, Sch11es Fars 2.42 (1/1) 2.79 (1/1) 0 (2.26-2.42) 1.5 mi W - -

GS 4 Be-7 0.51 <LLD - - <LLD 0 K-40 0.5 2.20 (3/3) K-27, Schites Fars 2.35 (1/1) 2.03(1/1) 0 (2.16-2.35) 1.5 mi W - -

Nb-95 0.15 <LLD - -

<LLD 0 Zr-95 0.086 <LLD - - <LLD 0 Ru-103 0.13 (LLD - -

<LLD 0 Ru-106 0.11 <LLD - - <LLD 0

. Cs-134 0.014 (LLD - -

<LLD 0 Cs-137 0.012 <tLD - -

<LLD 0 Ce-141 0.20 <LLD - - <LLD 0 Ce-144 0.11 <LLD - - <LLD 0 Eggs GA 4 0.05 0.10 (4/4) K-27, Sch11es Farm 0.10 (4/4) None- 0 (pC1/g wet) (0.08-0.14) 1.5 mi W (0.08-0.14)

G8 4 0.01 1.14 (4/4) K-27, Sch11es Farm 1.14 (4/4) None 0 (1.00-1.38) 1.5 mi W (1.00-1.38)

Sr-89 4 0.017 CLLD - - None 0 Sr-90 4 0.002 (LLD - - None O G5 4 Be-7 0.33 <LLD - - None 0 K-40 0.01 1.15 (4/4) K-27 Schlies Farm 1.15 (4/4) None 0 (0.82-1.40) 1.5 mi W (0.82-1.40)

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

O f)\

% Y o

v.

Table 4.5 (continued)

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control Sag le Type and Locationg Annual Mean Locations Nueer of.

Type Nu eer of Mean(F) Mean[F) Mean(F) Non-routine (Units) Analysesa Llob RangeC Locationd Range Range Resultse Eggs Nb-95 0.063 <LLD - -

None 0 (pCi/g wet)

(cont 'd) Zr-95 0.065 <LLD - - None O Ru-103 0.051 RLD - -

None O Ru-106 0.26 (LLD - - None O Cs-134 0.019 <LLD - -

None O Cs-137 0.021 <tLD - -

None O Ce-141 0.089 (LLD - -

None O Ce-144 0.13 <LLD -- -

None 0 y Vegetables GA 6 0.02 0.58 (1/1) j K-17. Jansky Farm 0.58 (1/1) 0.23 (5/5) 0 a (pC1/g wet) 4.25 mi W .

(0.12-0.30)

GB 6 1.0 4.93(1/1) K-27, Jansky Farm 4.93(1/1) 2.02(5/5) 0 4 4.25 mi W -

(1.19-2.90)

Sr-89 6 0.028 <LLD - -

<LLD 0 Sr-90 6 0.003 0.015 (1/1) K-26. Bertler's Fruit 0.015 (1/1) 0.005 (1/5) 0 Stand, 10.7 mi SSW - -

GS 6 Be-7 6 0.10 <LLD - - <tLD 0 K-40 0.75 2.40 (1/1) K-17, Jansky Farm 2.40 (1/1) 2.36 (5/5) 0 4.25 mi W -

(1.37-4.00)

Nb-95 0.022 <tLD - -

<LLD 0 Zr-95' O.025 <tLD - - <LLD 0 Ru-103 0.015 <tLD - - <LLD 0 Ru-106 0.08 <LLD - - <LLD 0 Cs-137 0.008 <tLD - - <lLD 0 Ce-141 0.026 (LLD - - <LLD 0 Ce-144 0.05 <LLD - - <LLD 0 i

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

O O O Table 4.5 (continued)

Name of faellity Kewaunee Nuclear Power Plant Indicator Location with Highest control ,

Sasple Type and Locationg Annual Mean Locations Nue er of Type Nueer of Mean(F) Mean(F) Mean(F) hon-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Grain - Cats GA 1 0.1 0.3 (1/1) K-23, Kewaunee Site 0.3 (1/1) None 0 (pC1/g wet) - 0.5 mi W -

GB '1 0.1 4.4 (1/1) K-23, Kewaunee Site 4.4 (1/1) None 0

- 0.5 mi W -

Sr-89 1 0.009 <LLD - - None 0 Sr-90 1 0.01 0.040(1/1) K-23, Kewaunee Site 0.040 (1/1) None 0

- 0.5 mi W -

4 GS 1 0.026 - - None 0

, Be-7 0.29 <LLD - - None . 0 k-40 0.1 4.15 (1/1) K-23. Kewaunee Site 4.15 (1/1) None 0

- 0.5 at W -

Nb-95 0.049 (LLD - - None 0 0

y ;

2r-95 0.056 <LLD - - None Ru-103 0.045 <LLD - - None 0 Ru-106 0.20 G.LD - - None O Cs-137 0.020 <LLD - -

None O Ce-141 0.096 <LLD - - None O Ce-144 0.18 <LLD - - None 0

Cattlefeed GA 6 0.1 0.68 (4/4) K-4, Stangel Farm 1.11 (1/1) 0.44 (2/2) 0 (pCi/g wet) (0.18-1.11) 3.0 mi N -

(0.43-0.44)

G8 6 0.2 8.80(4/4) Ke19, Paral Farm 15.96 1/1) 7.58 (2/2) 0 (2.97-15.96) 1.75 mi NNE -

(7.57-7.58)

Sr-89 6 0.19 <LLD - - <LLD 0 4 Sr-90 6 0.01 0.066 (3/4) K-19. Paral Fare 0.111 (1/1) 0.046 (1/2) 0 (0.020-0.111) 1.75 mi NNE _

os 6 8e-7 0.15 0.43 (1/2) K-19, Paral Farm 0.64 (1/1) <LLD 0 (0.22-0.64) 1.75 mi NNE K-40 1.0 6.19(4/4) K-19, Paral Farm 10.5 (1/1) 5.10 (2/2) 0 (1.55-10.50) 1.75 mi NNE -

(4.49-5.71)

/~' . /7 FN Table 4.5 (continued)

Name of facility Kewaunee Nuclear Power Plant

. Indicator Location with Highest Control Sample Type and Locationg Annual Mean Locations Nuiter of Type Numer of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RanaeC Locationd Range Range Resaltse Cattlefeed' Nb-95 0.022 <LLD - - <LLD 0 (pCi/g wet)

(cont *d) Zr-95 0.034 <LLD - - <LLD 0 Ru-103 0.018 <LLD - - <LLD 0 Ru-106 0.15 <LLD - - (LLD 0 Cs-134 0.017 (LLD - - <LLD 0 Cs-137 0.020 (LLD - - (LLO O Ce-141 0.026 <LLD - - <LLD 0 Ce-144 0.091 <tLD - - <LLD 0 Grass GA '24 0.2 0.7 (18/18) K-5, Pap 1 ham Farm 0.9(3/3) 0.6 (6/6) 0 g (pC1/g wet) (0.3-1.2) 3.5 mi NNW (0.4-1,2) (0.2-1.1)

K-19, Paral Farm 0.9 (3/3) 1.75 mi NNE (0.3-1.2)

G8 24 1.0 6.8 (18/18) K-5, Paplham Farm 7.5(3/3) 6.0 (6/6) 0 (5.0-8.5) 3.5 mi NNW (6.8-8.0) (4.6-7.5)'

K-12, LeCaptain Farm 7.5 (3/3) 1.5 mi WSW (6.3-8.3)

Sr-89 24 0.090 <LLD - -

<LLD 0 Sr-90 24 0.006 0.032 (12/18) K-19 Paral Farm 0.067(2/3) 0.025 (5/6) 0 (0.009-0.090) 1.75 mi NNE (0.044-0.090) (0.007-0.051)

GS 24 8e-7 0.31 4.41 (9/18) K-lb, Middle Creek 9.75 (1/3) 3.10(3/6). 0 (1.43-9.75) (h site, 0.12 mi N -

(0.60-6.31)

K-40 0.1 5.44 (18/18) K-5, Pap 1 ham Farm 6.72 (3/3) 5.74 (6/6) 0 (3.61-8.50) 3.5 mi hNW (4.69-8.50) (3.94-8.54)

Nb-95 0.1 <tLD - - <LLD 0 Zr-95 0.1 <LLD - - <tLD 0 Ru-103 0.1 <LLD - - <LLD 0 Ru-106 0.16 (LLD - - <tLD 0

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

.~

O O O g

Table 4.5 '(cont'inued)

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control "agle Type and Locationg Annual Mean Locations Number of Type. Nun 6er of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa ttob RangeC Locationd Range Range Resultse Grass Cs-137 0.02 (LLD - - <LLD 0 (pCl/g dry)

(cont'd) Ce-141 0.13 (LLD - - <LLD 0 Ce-144 0.15 (LLO - - <LLD 0 Soil GA 14 4.0 9.4 (10/10) K-If, Metrecrological 12.4 (2/2) 9.5 (4/4) 0 (pC1/g dry) (4.8-8.6) Tower, 1.12 at 5 (10.7-14.1) (6.6-11.6)

GB 14 1.4 24.6 (10/10) K-5, Pap 1 ham Farm 31.4 (2/2) 26.8 (4/4) 0 (16.4-35.5) 3.5 at WSW (27.2-35.5) (25.5-27.9)

Sr-89 14 0.29 (LLO - -

<LLD 0 N Sr-90 14 0.05 0.15 (5/10) K-12 Lecaptain Farm 0.20 (1/2) 0.18 (1/4) 0 (0.09-0.20) 1.5 mi WSW - -

GS 14 Be-7 0.33 <LLD - - <LLD D K-40 1.4 14.4 (10/10)- K-5, Pap 1 ham Farm 17.8 (2/2) 15.5(4/4) 0 (10.0-19.3) 3.5 mi NNW (16.2-19.3) (13.6-16.7)

Nb-95 0.06 <LLD - .

<LLD 0 Zr-95 0.07 <LLD - - <LLD 0 Ru-103 0.05 <LLD - '2 (LLD 0-Ru-106 0.22 (LLD - -

<LLD 0 Cs-137 0.05 0.30 (10/10) K-6, Novitsky Farm 1.02 (2/2) 0.62 (4/4) 0 (0.04-0.95) 6.7 at WSW (1.00-1.05) (0.14-1.05)

Ce-141 0.11 <LLD - - <LLD 0 Ce-144 0.21 <LLD - - <LLD 0

A O (/

m 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 Nunber of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Surface idater GA(55) 72 1.0 <LLD - -

<LLD 0 GA(DS) 72 2.1 3.0 (5/60) K-la, North Creek, 3.0(2/12) <tLD 0 (2.4-3.7) Onsite, 0.62 mi N (2.4-3.7)

K-le, South Creek, 3.0 (3/12)

Onsite, 0.12 mi 5 (2.6-3.6)

GA(TR) 72 2.7 3.3 (2/60) K-le, South Creek, 3.3 (2/12) <LLD 0 (3.0-3.6) Onsite, 0.12 mi 5 (3.0-3.6) g G8(SS) 72 0.5 0.6 (13/60) K-Id. Condenser 0.8 (3/12) <LLD 0

, (0.5-1.2) Discharge, Onsite .(0.6-1.2) 0.10 mi E G8(DS) 72 0.5 5.0 (60/60) K-la, North Creek, 9.2 (12/12) 2.7 (12/12) 0 (1.6-15.4) .Onsite, 0.62 mi N (6.6-13.1) (2.0-3.2)

GB(TR) 72 1.0 5.2 (60/60) K-la, North Creek, 9.4 (12/12) 2.8 (12/12) 0 (1.6-15.8) Onsite, 0.62 mi N (6.6-13.1) (2.0-3.2)

$ H-3 36 220 2310 (15/24) K-14, Two Creeks Park, 2.5 mi 5 2690 (5/12) <LLD 0 (270-13910) (270-13910).

Sr-89 12 1.9 <tLD - -

<LLD 0 Sr-90 12 0.9 3.2(1/8) K-Id. Condenser 3.2 (1/4) <LLO O (1.3-1.5) Discharge, Onsite -

0.10 mi E K-40 72 0.5 3.7 (60/60) K-la, North Creek 7.0 (12/12) 1.1 (12/12) 0 (flame) (0.6-19.2) Onsite, 0.62 at N (2.4-9.6) (1.0-1.4)

Fish-Muscle GA 4 0.05 0.17(4/4) K-Id. Condenser 0.17 (4/4) None 0 (pCl/g wet) (0.10-0.24) Discharge, Onsite (0.10-0.24) 0.10 mi E GB 4 1.0 2.34 (4/4) K-1d, Condenser 2.34 (4/4) None 0 (1.02-3.60) Discharge, Onsite (1.02-3.60) 0.10 mi E GS 4 Be-7 0.59 4.L D - - None 0 K-40 1.05 2.61 (4/4) K-Id, Condenser 2.61 (4/4) None 0 (2.28-3.16) Discharge, Onsite (2.28-3.16) 0.10 mi E Nb-95 0.14 (LLD - - None 0 Zr-95 0.12 (LLD - - None 0

i l

O . O O .

Ir l

Table 4.5 (continued) l

' Lee of facility Kewaunee Nuclear Power Plant l l

Indicator Location with Highest Control Sag le .-Type and Locationg Annual Mean Locations Nueer of Type Nueer of Mean(F) Mean[F) Mear(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Fish-Muscle Ru-103 0.11 <tLD - - None 0 (pCl/g wet)

(Cont'd) Ru-106 0.24 <LLD - - None O Cs-137 0.02 0.10 (2/4) K-id, Condenser Dis- 0.10 (2/4) Ene 0

,' (0.09-0.12) charge Onsite (0.09-0.12)

O.10 mi E Ce-141 0.19 <LLD - -

None O Ce-144 0.14 <LLD - - None 0

, Fish-Bones GA 5 0.95 (LLD - -

None 0

l. (pCi/g wet) y G8 5 1.00 2.04 (4/4) K-Id Condenser Dis- 2.04 (4/4) None 0 (1.18-3.13) charge, Onsite (1.41-1.94) 0.10 mi E Sr-89 5 0.12 <LLD - -

None O Sr-90 5 0.10 <tLD - - None O Periphyton GA 12 0.2 1.1(10/10) K-lb, Middle Creek 3.1 (2/2) 0.2 (2/2) 0 (slime) . ( 0.2-4.8) Onsite, 0.12 mi N (1.4-4.8) (0.2-0.3)

(pC1/g wet)

G8 12 0.50 2.1 (10/10) K-Ib, Middle Creek 3.6 (2/2) 0.8 (2/2) 0 (0.3-4.7) Onsite, 0.12 mi N (2.4-4.7) (0.7-0.8) l Sr-89 12 0.41 (LLD - -

<LLD 0 Sr-90 12 0.10 <LLD - - <LLD 0 l , GS 12 Be-7 1.42 <tLD 4 - - <LLD 0 l K-40 0.50 2.29 (9/10) K-le, South Creek, 4.31(2/2) 1.99 (2/2) 0 l (0.95-5.28) Onsite, 0.12 mi 5 (3.33-5.28) (1.63-2.35) l l

l

O .

O O Table 4.5 (Continued)

Name of facility Kewaunee Nuclear Power Plant Indicator Location with Highest Control

Sagle Type and Locationg Annual Mean Locations Numer of Type Nu e er of Mean( ). Mean(F) Mean(F) Non-routine (Units) Analyses 8 LLDb Range Locationd Range Range Results' Periphyton Mn-54 0.062 (LLD - - <LLD 0 (Slime)

(pC1/g wet) Co-58 0.15 <LLD - - <LLD 0 (Cont'd)

Co-60 0.068 (LLD - - <tLD 0 Mb-95 0.45 <LLD - - <LLD 0 Zr-95 0.28 (LLD - - <LLD 0 I '

Ru-103 > 0.32 <LLD - -

<LLD 0 Ru-106 0.48 <LLD - -

<LLD 0 l'y Cs-134 0.054 <LLD - - <LLD 0 0 Cs-137 0.049 (LLD - - <LLD 0 Ce-141 0.82 <LLD - -

<LLD 0 Ce-144 0.26 <LLD - -

<LLD 0 Bottom GA 20 4.2 6.3(4/16) K-lj, Condenser 8.1(1/4) 5.2 (1/4) 0 Sediments (5.0-8.1) Discharge. Onsite - -

(pCl/g dry) 500' S G8 20 1.4 8.4 (16/16) K-14. Two Creeks 10.0 (4/4) 7.4 (4/4) 0 (5.1-11.7) Park, 2.5 mi S (7.8-11.7) .(5.6-8.8)

Sr-89 20 0.20 <tLD - -

<LLD 0 Sr-93 20 0.10 <LLD - - <LLD 0 GS 20 K-40 1.0 4.73 (16/16) K-14 Two Creeks 5.45(4/4) 4.16 (4/4) 0 (2.%-7.02) Park, 2.5 mi 5 (4.14-7.01) (3.40-5.19)

Co-58 0.02 0.23(11/16) K-Ic, Condenser Dis- 0.39(2/4) <tLD 0 (0.04-0.50) charge. Onsite (0.28-0.50) 0.10 mi N

m.. - . _. _ _ . _ . . . . _ _ . . _ _ _ _ _ _ _ _ _ . -_. _ ___. _ _ . _ __ _.m _. . . _ . - -._ . _ _. . _ _ . _ _ . . _ _ ,. - _ _ _ _ _ - _ _ - - -

/")/

(V Table'4.5 (continued)

Name of facility Kewaunee Nuclear Power Plant Indicator. Location with Highest Control Sample Type and Locationg' Annual Mean Locations Nueer of Type Nueer of Mean(F) Mean(F) Mean(F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Botton Co-60 0.016 0.085 (7/16) K-Ic, Condenser Dis- 0.109 (1/4) <LLD 0 ,

Sediments (0.066-0.109) charge, Onsite. -

(pCl/g dry) 0.10 mi N (Con't) <tLD 0-Cs-134 0.012 (LLD - -

Cs-137 '0.010 0.077 (14/16) K-lj, Condenser Dis- 'O.098 (3/4) 0.023 (2/4) 0 (0.027-0.106) charge, Onsite (0.057-0.106) (0.016-0.030) 0.10 mi 5 ,

d GA '= gross alpha, G8 = gross beta, GS = gama spectroscopy, SS = suspended solids, DS = dissolved solids. TR = total residue.

b LLD = nominal lower limit of detection based on 3 sigma counting error for background sample.

C Mean based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in w parentheses (F).

.-.. d

Locations Nonroutine are specified results by station are those which code exceed(Table ten4.1),

timesdistance (miles) the control and value.

station direction If no relative controltostationreactorvalue site. is available, the result is considered nonroutine if it exceeds ten times the pre-operational value for the location.

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/7 '

V

5.0 REFERENCES

Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 produced by cosmic rays. Science 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 Monitoring Program for the Kewaunee Nuclear Power Plar,t, Kewaunee, Wisconsin, Final Report - Part II, Data Tal slations and Analysis, January - December 1978.

. 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 Report. 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 -

l Part II, Data Tabulations and Analysis, January - December 1981. 1

. 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 O Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, January - December 1976.

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32

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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 surveillance. I 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.

Teledyne Isotopes Midwest Laboratory. 1984. Annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report, Part II, Data Tabulations and Analysis, January - December 1983.

. 1985. Annual Report. Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report, Part II, Data Tabulations and Analysis, January - December 1984.

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

125.

33

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Appendix A Crosscheck Program Results i

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O N_) l Appendix A Crosscheck Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide 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. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environ-O- mental sample crosscheck program for milk and water samples during the period 1980 through 1984. 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 parti-cipation in the Second, Third, Fourth, and Fifth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.

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A-2

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Table A-1. U.S. Environmental Protection Agency's-crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for. milk and water samples, 1980 through 1983a, Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i2cc 130, n=1d STW-206 Water Jan. 1980 Gross Alpha 19.0i2.0 30.0i8.0 Gross Beta 48.012.0 45.015.0 STW-208 Water Jan. 1980 Sr-89 6.lil.2 10.0 0.5 Sr-90 23.9tl.1 25.511.5 STW-209 Water Feb. 1980 Cr-51 112114 101i5.0 Co-60 12.7i2.3 11i5.0 Zn-65 29.7i2.3 2515.0 Ru-106 71.7tl.5 51i5 Cs-134 12.0i2.0 1015.0 Cs-137 30.012.7 3015.0 STW-210 Water Feb. 1980 H-3 1800il20 17501340 STW-211 Water March 1980 Ra-226 15.710.2 16.0i2.4 Ra-228 3.510.3 2.610.4 STM-217 Milk May 1980 Sr-89 4.4i2.69 515 Sr-90 10.011.0 12il.5 STW-221 Water June 1980 Ra-226 2.010.0 1.7i0.8 Ra-228 1.610.1 1.710.8 STW-223 Water July 1980 Gross Alpha 31i3.0 3815.0 Gross Beta 4414 3515.0 STW-224 Water July 1980 Cs-137 33.910.4 35i5.0 Ba-140 <12 0 K-40 1350160 1550178 I-131 <5.0 0 STW-225 Water Aug. 1980 H-3 1280150 1210 329 STW-226 Water Sept. 1980 Sr-89 2211.2 2418.6 Sr-90 1210.6 1512.6 STW-228 Water Sept. 1980 Gross Alpha nae 32.0i8.0 Gross Beta 22.510.0 21.015.0 STW-235 Water Dec. 1980 H-3 2420130 22401604 O

A-3

O Table A-1. Wontinued)

Concentration in pCi/lb

-Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i2ac i30, n=1d STW-237 Water Jan. 1981 Sr-89 13.0il.0 16 8.7 Sr-90 24.0i0.6 3412.9 STM-239 Milk Jan. 1981 Sr-89 <210 0 Sr-90 15.7 2.6 20 3.0 I-131 30.9 4.8 26i10.0 Cs-137 46.912.9 43 9.0 Ba-140 <21 0 K-40 1330iS3 1550t134

, STW-240 Water Jan. 1981 Gross alpha 7.3 2.0 9 5.0 Gross beta 41.013.1 44 5.0 STW-243 Water Mar. 1981 Ra-226 3.510.06 3.410.5 Ra-228 6.Si2.3 7.311.1 STW-245 Water Apr. 1981 H-3 32101115 2710i355 STW-249 Water May 1981 Sr-89 5113.6 36 8.7 Sr-90 22.710.6 22i2.6 STW-251 Water May 1981 Gross alpha 24.015.3 21 5.2 Gross beta 16.lil.9 1415.0 STW-252 Water Jun. 1981 H-3 2140i95 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.lil.0 23 5 Sr-90 10.310.9 1111.5 STW-265 Water Oct. 1981 Gross alpha 71.2119.1 80120 Gross beta 123.3i16.6 111 5.6 Sr-89 14.912.0 2115 Sr-90 13.lil.7 14.411.5 Ra-226 13.012.0 12.711.9 STW-269 Water Dec. 1981 H-3 2516i181 2700 355 A-4

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis tasc i3o, n=1d STW-270 Water Jan. 1982 Sr-89 24.312.0 21.015.0 Sr-90 9.410.5 12.011.5 STW-273 Water Jan. 1982 1-131 8.6i0.6 8.411.5 STW-275 Water Feb. 1982 H-3 15801147 18201342 STW-276 Water Feb. 1982 Cr-51 <61 0 Co-60 26.013.7 20 5 Zn-65 <13 1515 Ru-106 <46 20 5 Cs-134 26.810.7 22i5 Cs-137 29.711.4 23i5 STW-277 Water Mar. 1982 Ra-226 ll.9tl.9 11.6fl.7 STW-278 Water Mar. 1982 Gross alpha 15.6tl.9 1915 O' . Gross beta 19.2i0.4 19i5 STW-280 Water Apr. 1982 H-3 2690180 28601360 STW-281 Water Apr. 1982 Gross alpha 7517.9 85 21 Gross beta 114.115.9 10615.3 Sr-89 17.411.8 2415 Sr-90 10.Si0.6 12*1.5 Ra-226 11.4t2.0 10.911.5 Co-60 <4.6 0 STW-284 Water May 1982 Gross alpha 31.516.5 27.517 Gross beta 25.913.4 2915 STW-285 Water. June 1982 ' H-3 1970i1408 18301340 STW-286 Water June 1982 Ra-226 12.611.5 13.413.5 i

Ra-228 11.112.5 8.7t2.3 STW-287 Water June 1982 I-131 6.510.3 4.4 0.7 STW-290 Water Aug. 1982 H-3 3210i140 2890 619 STW-291 Water Aug. 1982 I-131 94.612.5 87115 O

A-5

, v

1 Table A-1. (continued)

Concentration in pCi/lb j

. Lab Sample Date TIML Result EPA Result Code Type- Collected Analysis i2ac 130, n=1d STW-292 Water Sept 1982 Sr-89 22.7i3.8 24.Si8.7 Sr-90 10.9i0.3 14.St2.6 STW-296 Water Oct. 1982 Co-60 20.0il.0 2018.7 Zn-65 32.315.1 2418.7 Cs-134 15.311.5 19.0i8.7 Cs-137 21.0il.7 20.0i8.7 STW-297 Water Oct. 1982 H-3 2470i20 25601612 STW-298 Water Oct. 1982 Gross alpha 32i30 55124 Gross beta 81.7i6.1 81 8.7 Sr-89 <2 0 Sr-90 14.110.9 17.2i2.6 Cs-134 <2 1.818.7 Cs-137 22.710.6 20 8.7 Ra-226 13.610.3 12.513.2 O- Ra-228 3.911.0 3.610.9 STW-301 Water Nov. 1982 Gross alpha 12.Dil.0 19.0i8.7 Gross beta 34.012.7 24.018.7 STW-302' Water Dec. 1982 I-131 40.010.0 37.0i10

, STW-303 Water Dec. 1982 H-3 1940120 1990 345 STW-304 Water Dec. 1982 Ra-226 11.710.6 11.0il.7 Ra-228 <3 0 STW-306 Water Jan. 1983 Sr-89 20.018.7 29.2 5 Sr-90 21.7i8.4 17.2il.5 STW-307 Water Jan. 1983 Gross alpha 29.014.09 29.0113 Gross beta 29.310.6 31.0 8.7 STM-309 Milk Feb. 1983 Sr-89 3512.0 37 8.7 Sr-90 13.710.6 18 2.6 I-131 55.713.2 55110.4 Cs-137 2911.0 2618.7

Ba-140 <27 0 K-40 163715.8 15121131

()

A-6

(v)

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis 12ac i3o, n=1d STW-310 Water Feb. 1983 H-3 2470180 2560i612 STW-311 Water March 1983 Ra-226 11.911.3 12.713.3 Ra-228 <2.7 0 STW-312 Water March 1983 Gross alpha 31.614.59 31i13.4 Gross beta 27.0i2.0 2818.7 STW-313 Water April 1983 H-3 3240 80 33301627 STW-316 Water May 1983 Gross alpha 94i7 64i19.9 Gross beta 13315 149 12.4 Sr-89 19il 2418.7 Sr-90 1211 1312.6 Ra-226 7.910.4 8.512.25 Co-60 3012 3018.7 Q~ Cs-134 2712 33 8.7 V Cs-137 2911 2718.7 a

STW-317 Water May 1983 Sr-89 59.7i2.1 5718.7 v Sr-90 33.7tl.5 3813.3 STW-318f Water May 1983 Gross alpha 12.811.5 1118.7 Gross beta 49.413.9 5718.7 STM-320 Milk June 1983 Sr-89 20 0 25i8.7 Sr-90 10i1 1612.6 I-131 3011 30110.4

Cs-137 5212 4718.7 K 1553157 1486i129 STW-321 Water June 1983 H-3 1470189 15291583 STW-322 Water June 1983 Ra-226 4.310.2 4.8 1.24 Ra-228 <2.5 0 STW-323 Water July 1983 Gross alpha 311 718.7

! Gross beta 2110 2218.7 STW-324 Water August 1983 I-131 13.310.6 14 10.4 f

b) 'a N A-7

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i2ac 130, n=1d STAF-326 Air August 1983 Gross beta 42 2 3618.7 Filter Sr-90 1412 10i2.6 Cs-137 19il 1518.7 STW-328 Water Sept. 1983 Gross alpha 2.310.6 518.7 Gross beta 10.7tl.2 9i8.7 STW-329 Water Sept. 1983 Ra-226 3.010.2 3.110.31 Ra-228 3.2i0.7 2.010.52 STW-331 Water Oct. 1983 H-3 1300130 1210i570 STW-335 Water Dec. 1983 I-131 19.611.9 20 10.4 STW-336 Water Dec. 1983 H-3 28701100 23891608 STAF-337 Air Nov. 1983 Gross alpha 18.010.2 1918.7 Filter Gross beta 58.6 1.2 5018.7 O' Sr-90 10.910.1 15i2.6 Cs-137 30.112.5 20 8.7 STW-339 Water Jan. 1984 Sr-89 47.211.9 36 8.7 .

Sr-90 22.514.0 24i2.6 l STW-343 Water Feb. 1984 H-3 2487176 23831607 ,

STM-347 Milk March 1984 I-131 5.3fl.1 6tl.6 STW-349 Water Ma,ch 1984 Ra-226 4.010.2 4.111.06 l Ra-228 3.610.3 2.0 0.52 I STW-350 Water March 1984 Gross alpha- 3.811.1 5 8.7 Gross beta 24.212.0 20 8.7 STW-354 Water April 1984 H-3 3560150 35081630 STW-355 Water April 1984 Gross alpha 21.014.1 35115.2 l Gross beta 127.814.1 147 12.7 Sr-89 29.312.0 23 8.7 Sr-90 16.6i0.7 26 2.6 l Ra-226 4.0il.0 4.011.04 Co-60 32.311.4 '3018.7 Cs-134 ; 33.6i3.1 3018.7 O. Cs-137 f

33.3f2.2 2618.7 s

A-8

(~)

\~J Table A-1. (continued)

' Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis i2ac i3o, n=1d STW-358 Water May 1984 Gross alpha 3.010.6 318.7 Gross beta 6.7 1.2 618.7 STM-366 Milk June 1984 Sr-89 21i3.1 25 8.7 3r-90 1312.0 1712.6 I-131 46i5.3 43 10.4 Cs-137 38i4.0 3518.7

. K-40 1577t172 1496t130 STW-368 Water July 1984 Gross alpha 5.lil.1 618.7 Gross beta 11.912.4 13 8.7 STW-369 Water August 1984 I-131 34.315.0 34.0 10.4 STW-370 Water August 1984 H-3 30031253 3817i617 STF-371 Food July 1984 Sr-89 22.0i5.3 25.018.7 Sr-90 14.7 3.1 20.012.6 I-131 <172 39.0110.4 Cs-137 24.015.3 25.018.7 K-40 2503 132 26051226.0 STAF-372 Air August 1984 _ Gross alpha 15.3tl.2 1718.7 Filter Gross beta 56.0 0.0 51i8.7 Sr-90 14.311.2 1812.4 Cs-137 21.012.0 15 8.7 STW-375 Water Sept. 1984 Ra-226 5.110.4 4.911.27 Ra-228 2.210.1 2.310.60 STW-377 Water Sept. 1984 Gross alpha 2.7 1.2 5.018.7 Gross beta 11.010.0 16.018.7 STW-379 ' Water Oct. 1984 H-3 28601312 28101356 STW-380 Water Oct. 1984 Cr-51 <36 40 8.7 20.3tl.2 Co-60 2018.7 Zn-65 150i8.1 147i8.7 l Ru-106 <30 47 8.7 :

Cs-134 31.317.0 3118.7 i Cs-137 26.7tl.2 2418.7 b

a A-9 P

O Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis f2ac 130, n=1d STM-382 Milk Oct. 1984 Sr-89 15.714.2 2218.7 Sr-90 12.7 1.2 1612.6 I-131 41.7 3.1 42110.4 Cs-137 31.3t6.1 32 8.7 K-40 1447166 1517i131 STW-384 Water Oct. 1984 Gro'ss alpha 9.711.2 14 8.7 (Blind) Sample A Ra-226 3.310.2 3.020.8 Ra-228 3.411.6 2.110.5 Uranium nae 5 10.4 Sample B Gross beta 48.3i5.0 64 8.7 Sr-89 10.7i4.6 1118.7 Sr-90 7.311.2 12 2.6 Co-60 16.3tl.2 1418.7 Cs-134 <2 2 8.7 Cs-137 16.711.2 1418.7

. . STW-389 Water Dec. 1984 H-3 3583t110 ,

31821624 a

Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck 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.

b All results are in pCi/1, except for elemental po*assium (K) data which are c

in mg/l, and air filter samples which are in pCi/ filter.

Unless otherwise indicated, the TIML results are given as the mean 12 standard d

deviations for three determinations.

e USEPA results are presented as the known values i control limits of 3 for n=3.

NA = Not analyzed. l Analyzed but not reported to the EPA. - 1 9 Results after calculations corrected (error in calculations when reported to l EPA), l

\

O-l A-10

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Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).

mR Teledyne Average 120 I Lab TLD Result Known (all Code Type Measurement i2o a Value participants) 2nd International Intercomparisonb 115-2b CaF2:P.n Gama-Field 17.011.9 17.lc 16.417.7 Bulb Ganna-Lab 20.814.1 21.3c 18.817.6 3rd International Intercomparisone 115-3e CaFp:Mn Gamma-Field 30.713.2 34.914.8f 31.513.0

> BuTb g Gamma-Lab 89.616.4 91.7114.6f 86.2124.0 4th International Intercomparison9 115-49 CaFp:Mn Gamma-Field 14.111.1 14.lil.4f 16.09.0 Bulb Gama-Lab (Low) 9.311.3 12.2i2.4f 12.017.6 Gama-Lab (High) 40.4fl.4 45.819.2f 43.9113.2

< Sth International Intercomparison h

, 115-5Ah CaF2:Mn Gamma-Field 31.411.8 30.016.0i 30.2i14.6 Bulb ,

Gamma-Lab 77.415.8 75.217.61 75.8140.4 at beginning Gamma-Lab 96.615.8 88.418.81 90.7131.2 at the end 1

e

Table A-2. (Continued) mR Average i 20 d Teledyne Lab TLD Result Known (all Code Type Measurement 12aa Value participants) 115-5Bh LiF-100 Gama-Field 30.314.8 30.0161 30.2114.6

' Chips Gamma-Lab 81.117.4 75.217.61 75.8140.4 at beginning Gama-Lab 85.4i11.7 88.418.8i 90.71131.2 at the end

> a Lab result given is the mean 12 standard deviations of three determinations, g b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of Texas, Houston,' Texas.

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

d Mean 12 standard deviations of results obtained by all laboratories participating in the program.

e Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.

f Value 12 standard deviations as determined by sponsor of the intercomparison using continuously' operated pressurized ion chamber.

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

h Fifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, 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.

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1 Appendix B l

] Data Reporting Conventions l

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

2.0. Single Measurements Each single measurement is reported as follows:

xis where x = value of the measurement; s = 20 counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is found to be below the lower limit of detection L it is reported as

<L where L = is the lower limit of detection based on 3a uncertainty for a background sample.

3.0. Duplicate Analyses 3.1. Individual result ;: xi i si x2 i s2 Reported result: xis where x = (1/2) (xi + x2) s = (1/2) s 2+s 2 '

3.2. Individual results: <L1

<l2 Reported result: <L where L = lower of Li and L2 3.3. Individual results: xis

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

<L otherwise O

, B-2

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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 exanple, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviations of a set of n numbers x1, x2, Xn are defined as follows:

, o x=fIx 3, 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 l raised by 1. As an example,11.446 is rounded off to 11.45. l 4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is

. increased by one if it is an odd number or it is kept unchanged if an even number. As an example,11.435 is l

rounded off to 11.44, while 11.425 is rounded off to 11.42.

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B-3

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! Appendix C- t I

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I Maximum Permissible Concentrations !

4 of Radioactivity in Air and Water [

Above Background in Unrestricted Areas ;

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l Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a i

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 pC1/m3 Cesium-137 20,000 pCi/1

[

Barium-140 20,000 pCi/l Iodine-131 300 pCi/l Potassium-40c 3,000 pCi/l Gross alpha 30 pCi/l Gross beta 100 pCi/l Tritium 3 x 106 pcj/1 a

Taken from Code of Federal Regulations Title 10, Part 20, Table II and appro-priate footnotes. Concentrations may be averaged over a period not greater b

than one year.

From 10 CFR 20 but adjusted by a factor of 700 to reduce the dose resulting c

from the air-grass-cow-milk-child pathway.

A natural radionuclide.

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g WISCONSIN PUBLIC SERVICE CORPORATION P.O. Box 1200, Green Bay, WI 54305 l

1 1

FP.IO11TY I.0UTING First "pmL v .

ps et

- 2 51 _

oaA alm 4__._

FILL [tl.)

March 1, 1985 1

I I Mr. J. G. Keppler, Regional Administrator Region III l

U.S. Nuclear Regulatory Commission t 799 Roosevelt Road Glen Ellyn, IL 60137 Gentlemen:

Docket 50-305 )

Operating License DPR-43 Kewaunee Nuclear Power Plant 1984 Annual Operating Report Enclosed are forty (40) copies of the 1984 Kewaunee Nuclear Power Plant (KNPP)

Annual Operating Report. This report is being submitted in accordance with Section 6.9.1.b of the KNPP Technical Specifications.

The 1984 KNPP Annual Operating Report also satisfies the reporting requirements of 10 CFR 20.407(a)(2) and 10 CFR 20.407(b) (personnel monitoring), KNPP Technical Specification 4.2.b.5.b (steam generator inspection), and KNPP Technical Specification 6.9.3.a (environmental monitoring).

Very truly yours, D. C. Hintz Manager - Nuclear Power GWH/js Enc.

cc - Mr. Robert Nelson, US NRC Mr. S. A. Varga, US NRC ER 6198$

t

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ML20099D732

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1.0 INTRODUCTION

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