ML20147B292
| ML20147B292 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 12/31/1987 |
| From: | Hintz D MADISON GAS & ELECTRIC CO., WISCONSIN POWER & LIGHT CO., WISCONSIN PUBLIC SERVICE CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CON-NRC-88-26 NUDOCS 8803020059 | |
| Download: ML20147B292 (132) | |
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O KEWAUNEE NUCLEAR POWER PLANT ANNUAL OPERATING REPORT 1987 O
wlSCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER LIGHT COMPANY MADISON GAS ELECTRIC COMPANY O
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O TABLE OF CONTENTS 1.0 Introduction 2.0 Summary of Operating Experience 3.0 Plant Modifications, Tests, and Experiments 4.0 Licensee Event Reports 5.0 Fuel Inspection Report 6.0 Challenges to and Failures of Pressurizer Safety and Relief Valves l
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7.0 Steam Generator Tube Inspection 8.0 Personnel Exposure and Monitoring / Report 9.0 Radiological Monitoring Program 10.0 Results of Land Use Census 4
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1.1 i
1.0 INTRODUCTION
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The Kewaunee Nuclear Power Plant is_a pressurized water reactor licensed at 1650 MWt.
It is located in Kewaunee County, Wisconsin, along Lake Michigan's northwest 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).
i 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 49,504,510 MW hours of electricity as of December 31, 1987, with a net plant capacity factor of 80.9 (using net MDC).
P) v 1.1 Highlights During the year, the Kewaunee Nuclear Power Plant was primarily base loaded. The unit was operated at 91% capacity factor (using net MDC) with a gross efficiency of 33.3%.
The unit and reactor availability were 89.2% and 89.7% 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 average daily electrical output of the Kewaunee Plant for 1987.
On February 24, 1987 the unit was removed from service for its twelfth annual refueling maintenance overhaul. Ferty fresh fuel assemblies were loaded for Cycle XIII. The unit was returned to service on April 4,1987.
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2.1 2.0 SLM4ARY OF OPERATING EXPERIENCE January Normal power operation continued during the month of January.
Because the RCS boron concentration was less than 150 ppm, the turbine stop and governor valve test was not performed this month as allowed by Technical Specifications.
PLANT SHUT 00WNS: There were no shutdowns during the month of January.
February The start of the Cycle 12-13 refueling outage on February 24 ended the unit's second longest continuous run at 287 days.
PLANT SHUTDOWNS:
February 24: Scheduled shutdown of 102.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. An automatic reactor
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trip occurred from subcritical condition after the unit was taken off line; the cause of the trip was erratic operation of one source range channel which resulted in a high flux level trip.
March The Cycle 12-13 refueling outage continued during the month of March.
PLANT SHUTDOWNS:
Scheduled shutdown of 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
April On April 4, the unit was returned to operation ending the Cycle 12-13 refueling outage.
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2.2 PLANT SHUTOOWNS:
April 1:
Scheduled shutdown of 73.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Continued Cycle 12-13 refueling outage. The outage was concluded on April 4.
April.4: Scheduled shutdown of 10.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. A short outage was taken to perform turbine overspeed trip tests and a torsion test.
!$D' Normal power operation continued for the month of May.
May 10:
Unit load was reduced to 60 percent to perform the scheduled turbine stop and control valve test.
May 25:
Unit load was reduced to 30 percent to maximize steam generator water chemistry cleanup following contamination of the condensate system with corrosion-inhibitor from the.
Secondary Analytical Panel chiller unP..
The unit was returned to full load on May 27.
PLANT SHUTOOWNS:
There were no shutdowns during the month of May.
June Normal power operation continued during the month of June except for one plant trip.
The monthly turbine stop and control valve test was satisfied by taking credit for the turbine trip.
PLANT SHUTOOWNS:
June 26:
Forced shutdown of 8.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. A turbine / reactor trip, on indicated loss of main generator excitation, occurred when a plant electrician mistakenly opened a potential transformer cabinet for the main generator.
During the outage, a failed power range NI detector was replaced.
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2.3 July Normal operation continued during the month of July except for one plant trip.
The monthly turbine stop and control valve test requirement was satisfied by the forced outage on July 10.
PLANT SHUTOOWNS:
July 10: Forced shutdown of 10.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. An electrical fault in the common aluminum bus from the Main Auxiliary Transformer (MAT) 'X' winding to buses 3,4,5, and 6 caused a voltage dip on buses 1 and 2 which supply the Reactor Coolant Pumps from the MAT 'Y' winding. This voltage drop was suf-i ficient to initiate a reactor protection system anticipatory loss of RCS flow reactor / turbine trip.
i August i
Normal power operation continued during the month of August.
On August 9, unit load was reduced to 385 MW gross for the performance of the monthly turbine stop and control valve test. The unit was returned to full load the same day.
PLANT SHUTDOWNS: There were no shutdowns during the month of August.
September Normal power operation continued during the month of September.
On September 6, unit load was reduced to 385 MW gross for the perfor-mance of the monthly turbine stop and control valve test. The unit j
was returned to full load the same day.
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2.4 On September 12, unit load was reduced to 286 MW gross for replacement of a condensate pump motor. The unit was returned to full load on September 13.
PLANT SHUT 00WNS:
There were no shutdowns during the month of September.
October Normal power operation continued during the month of October.
On October 11, unit load was reduced to 390 MW gross for the perfor-mance of the monthly turbine stop and control valve test.
The unit was returned to full load the same day.
PLANT SHUTDOWNS: There were no shutdowns during the month of October.
November Normal power operation continued during the month of. November.
On November 8, unit load was reduced to 390 MW gross for the perfor-
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mance of the monthly turbine stop and control valve test.
The unit was returned to full load the same day.
PLANT SHUTOOWNS:
There were no shutdowns during the month of November.
December 4
Normal power operation continued during the month of December.
On December 13, unit load was reduced to 385 MW gross for the perfor-mance of the monthly turbine stop and control valve test and perfor-mance of a lithium tracer feedwater flow measurement test. The unit was returned to full load the same day.
PLANT SHUTDOWNS:
There were no shutdowns during the month of December.
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O 2.4 TABLE 2.1 (Page 1 of 2)
ELECTRICAL POWER GENERATION DATA (1987) 4 MONTHLY January February March April May June Hours RX was critical 744.0 570.3 0.0 677.8 744.0 713.8 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0
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Hours Generator On-Line 744.0 569.8 0.0 635.1 744.0 711.9 1
Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1,215,680 924,655 0.0 959,357 1.185,857 1,146,829 Gross Elec. Energy Generated (MWH) 406,200 308,400 0.0 318,800 398,500 383,900 Net Elec. Energy Generated (MWH) 388,069 294,511 0.0 303,405
~ 379,595 365,677 RX Service Factor 100.0 84.9 0.0 94.3 100.0 99.1 RX Availability Factor 100.0 84.9 0.0 94.3 100.0 99.1 Unit Service Factor 100.0 84.8 0.0 88.3 100.0 98.9 Unit Availability Factor 100.0 84.8 0.0 88.3 100.0 98.9 Unit Capacity Factor (using MDC net) 103.7 87.1 0.0 83.9 101.4 101.0 Unit Capacity Factor (using DER net) 97.5 81.9 0.0 78.9 95.4 94.9 Unit Forced Outage Rate 0.0 0.0 0.0 0.0 0.0 1.1 Hours in Month 744.0 672.0 744.0 719.0 744.0 720.0 Net MOC (Mwe) 503.0 503.0 503.0 503.0 503.0 503.0
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O 2.5 TABLE 2.1 (Page 2 of 2)
ELECTRICAL POWER GENERATION DATA (1987)
MONTHLY July August September October November December Hours RX was critical 738.0 744.0 720.0 745.0 720.0 744.0 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 733.2 744.0 720.0 745.0 720.0 744.0 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1,183,725 1,219,047 1,168,054 1,219,759 1,176,994 1,215,302 Gross Elec. Energy Generated (MWH) 395,600 405,400 387,800 405,700 391,000 403,200 Net Elec. Energy Generated (MWH) 376,469 386,117 369,190 386,950 373,458 385,183 RX Service Factor 99.2 100.0 100.0 100.0 100.0 100.0 RX Availab11ity Factor 99.2 100.0 100.0 100.0 100.0 100.0 Unit Service Factor 98.6 100.0 100.0 100.0 100.0 100.0 Unit Availability Factor 98.6 100.0 100.0 100.0 100.0 100.0 Unit Capacity Factor (using MOC net) 100.6 103.2 101.9 103.3 103.1 102.9 Unit Capacity Factor (using DER net) 94.6 97.0 95.8 97.1 97.0 96.8 Unit Forced Outage Rate 1.4 0.0 0.0 0.0 0.0 0.0 Hours in Month 744.0 744.0 720.0 745.0 720.0 744.0 Net MDC (Mwe) 503.0 503.0 503.0 503.0 503.0 503.0
2.6 TABLE 2.2
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r ELECTRICAL POWER GENERATION DATA 1987 Year Cumulative Hours RX was critical 7,860.9 101,462.2 RX Reserve Shutdown Hours 0.0 2,330.5 Hours Generator On-Line 7,811.0 99,881.6 Unit Reserve Shutdown Hours 0.0 10.0 Gross Thermal Energy Generated (MWH) 12,615,259 157,428,973 Gross Electrical Energy Gen. (MWH) 4,204,500 51,987,100 Net Elec. Energy Generated (MWH) 4,008,624 49,500,510 RX Service Factor 89.7 85.5 l
RX Availability Factor 89.7 85.5 Unit Service Factor 89.2 84.1 Unit Availability Factor 69.2 84.1 Unit Capacity Factor 91.0 80.9 (using HDC net)
Unit Capacity Factor.
85.5 77.9 (using DER net)
Unit Forced Outage Rate 0.2 2.9 Hours in Reporting Period 8,760.0 118,729.0 I
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3.1 3.0 PLANT MODIFICATI0hS, TESTS AND EXPERIMENTS This section is provided in accordance with the requirements of Part 50.59(b) to Title 10,. Code of Federal Regulations (10CFR50.59(b)).
This regulation allows licensees to make changes in the facility as described in the Updated Safety Analysis Report, and conduct 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.
Plant Modifications, 10CFR50.59 There were no modifications during 1987 which introduced an unreviewed safety question and, therefore, no modifications required prior NRC approval.
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modificetions completed evrins 1987 end not previousix.renorted. seny 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 sum-mary report.
Reactor Coolant System The steam generator tube plugging limit was increased to 10 percent.
The USAR safety analysis, including plant transient and ECCS analyses, were evaluated for the effect of steam generator tube plugging levels up to 10 percent (DCR 2014).
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3.2 Summary of the Safety Evaluation V
The effects of additional tube plugging on non-LOCA accident analy-ses are adequately accommodated by primary system design flow margins. The LOCA analysis assumptions were verified to encompass a plugging level of 10 percent.
Reactor Coolant System Modifications were made to the steam generator primary nozzles to allow temporary installation of nozzle dams.
The use of nozzle dams permit steam generator channel head work, such as eddy current testing and tube sleeving, to occur simultaneously with a flooded reactor cavity.
(DCR1873)
Summary of Safety Evaluation The nozzle dam design provides complete redundancy. Two nozzle dams are installed in series in each nozzle.
The steam generator
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nozzle modifications meet the requirements of Section III of the ASME Boiler and Pressure Vessel Code.
Failure modes of the system components were evaluated, and it was concluded that no credible failure could cause a significant leak past the nozzle dams.
Shield Building Ventilation This modification changed the control scheme for the modulating check dampers in the recirculation fan flow paths (exhaust and recirculation). The original control scheme modulation signal was provided by the differential pressure across each damper. The new control scheme has one differential pressure transmitter per train which senses the differential pressure between the Shield Building and the Auxiliary Building. This transmitter provides the signal which modulates the recirculation fan's recirculation damper and exhaust damper to maintain a preset vacuum in the Shield Building post-accident.
(DCR944)
3.3 Summary of Safety Evaluation gV This modification will enhance plant safety by improving the reliability of the Shield Building Ventilation System. This is accomplished by reducing the cycling of the dampers' hydraulic actuators with the new control scheme. This modification does not change the licensing basis for the Shield Building Ventilation System.
Substation A new spare cable storage yard was constructed to make room for the addition of four 16 MVA capacitor banks and their associated breakers and bus connections to the 138KV substation. The East Krok 138KV line was rerouted around an existing dead-end tower in the Point Beach 345KV line. Also, a spare Tertiary Auxiliary Transformer (TAT) was purchased and provisions were made for installation of a WPSC system spare 138KV to 13.8KV transformer in the substation to supply the TAT in case of failure of transformer bank 10.
(DCR 1571)
Summary of Safety Evaluation The capacitor banks will increase the voltage reliability of the 138KV substation bus thereby decreasing the probability of actuation of the second level undarvoltage relays on the safeguard buses.
The line reroute will decrease the probability of loss of offsite power by making the East Krok and Shoto 138KV lines physically independent.
Purchase of a spare TAT and provisions to install a spare system transformer will prevent this equipments failure from causing an extended shutdown due to KNPP Technical Specifications.
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3.4 Environmental Qualification The NAMC0 limit switches, model series D-2400X, mounted on IE valves were replaced with NAMCO EA-180 series limit switches. This design change was done to assure environmental qualifications.
(DCR 1522)
Summary of Safety Evaluation This design change did not affect the USAR or Technical Specifications. The probability of occurrence or consequences of an accident or malfunction of equipment important to safety was reduced by assuring the use of environmentally qualified components.
Environmental Qualification The electrical conduit connection on four containment fan coli I
emergency discharge damper solenoid valves were sealed. This was required by the NRC during their 1987 audit of environmentally qualified equipment.
(DCR 2012)
Summary of Safety r. valuation The conduit seal increases the probability that-the solenoid valves I
will function properly in a post-accident environment by preventing moisture intrusion into the solenoid valve coil.
Diesel Generator Electrical i
The existing diesel generator differential relays, GE model CFD, were replaced by new seismically qualified relays, GE model IJD. The j
seismic qualification documentation of the old relays was not available.
Spurious operation of these relays could have blocked the diesel generators from being loaded onto the bus.
The new relays will preclude this type of occurrence.
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3.5 Summary of Safety Evaluation This modification maintained the seismic criteria that was part of the original plant aesign.
The replacement relays were func-tionally and physically identical to the original. This change eliminated the possibility of a single seismic event preventing both diesels fron loading.
DC Supply and Distribution The four 7.5KVA instrument bus inverters were replaced due to obso-lescence, the unavailability of spare parts, and the fact that the parallel Constant Voltage Transformer (CVT) design of tSese inverters was causing the majority of the instrument bus failures at KNPP.
The new inverters provide the same function as the old and have an improved design that increases reliability.
(DCR 1832)
Summary of Safety Evaluation The new inverters were a one for one replacement with the old inver-l ters. They incorporate several improvements that increase reliabi-lity, such as the elimination of parallel CVT's and the use of a static switch for a bumpless transfer to the alternate source on i
inverter failure, The new inverters were built to an equipment specification that defined critical characteristics and allowable tolerances. Tests verified these design criteria were met.
Feedwater The trim in the main feedwater regulating valves was replaced with "hush trim".
The new trim is smaller which provides better stability and control at low flow conditions and should result in fewer reactor trips associated with feedwater flow.
(DCR 1877)
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3.6 Summary of Safety Evaluation O
v The modification improves valve reliability and feedwater flow control and has no effect on plant safety.
Control Rod Drive System
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The overcurrent trip unit for the Westinghouse AC circuit breakers on the output of the control rod drive MG sets was upgraded. The ilectro-mechanical tripping unit was replaced with an Amptector solid state trip unit. The instantaneous and time delay breaker settings did not change.
(OCR 1854)
Summary o'f Safety Evaluation This change was per the Westinghouse technical manual.
Installation and testing was done with a Westinghouse represen.
tative involved. This does not create a. change in the USAR or i
Technical Specifications. There breakers are not the safeguards q
breakers for reactor protection and are fed from non-safety related buses 1-33 and 1-43.
Fire Protection The modifications required by 10CFR50, Appendix R, Fire Protection Program have been completed in accordance with the NRC approved sche-dule.
The modifications completed in 1987 include the following i
- The dedicated shutdown panel has been put into service with all required components operational from the panel.
- The installation of required instrumentation on the dedicated shut-down panel is complete.
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3.7 Summary of Safety Evaluation
.b, These modifications enhance both automatic and manual control of the plant in the unlikely event of a fire.
The Appendix R modifi-cations preclude a fire from affecting the capability to bring the plant to a safe shutdown condition.
Chemical and Volume Control This DCR re-routed the instrument air to valves CVC200 and CVC203B in the seal water injection line. Valves CVC200 and CVC2038 have a minimum air pressure required that equaled the meximum air pressure rating of other valves on the same instrument air line.
This condition could have resulted in valve malfunctions.
This condition has been elimi-nated by the instrument air line reroute.
(DCR 2015)
Summary of Safety Evaluation This DCR will enhance plant safety by ensuring proper operation of all control valves on the air line.
The DCR will not affect the designed operation of the control valves.
Chemical and Volume Control The boric acid storage tanks' (1A/18) low level alarm setpoints were raised from 68 percent to 75 percent. This was done to compensate for drifting in the level transmitters which supply inputs to the alarms.
This drift has been as much as 5%. Due to this drift, actual tank levels could have dropped below Technical Specification limits before receiving the low alarm.
(DCR 1981)
Summary of Safety Evaluation This modification will enhance plant safety by ensuring adequate levels of borated water exist in the storage tanks during normal plant operation.
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3.8 Circulating Water The circulating water hypochlorite system was removed from service, along with its associated piping, valves and controls. The hypoch-lorite system was never used at Kewaunee because the amount of sodium hypochlorite that would have to be added to control condenser biofouling would exceed our allowable circulating water discharge limits. Due to the deteriorated condition of the storage tank, it was decided to remove this system from service.
(OCR 1893)
Summary of Safety Evaluation The circulating water hypochlorite system is mentioned on page 10.2-21 of the USAR and is shown on figure 10.2-7 of the USAR.
The circulating water hypochlorite system is not a plant safety system and is classed QA type 3.
The circulating water hypoch-lorite system is an independent system and its removal will not affect any other plant system.
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The waste disposal piping was modified to permit the transfer of spent -
resins to a High 11tegrity Container (HIC) for offsite shipments.
Spent resins that are temporarily being held in the spent resin storage tank or the waste metering tank may now be transferred directly to the HIC.
(OCR 1414)
Summary of Safety Evaluation The design and construction of the piping modification was per-formed to the same quality of material and workmanship as the existing piping. No new hazards to the plant from spills were introduced. This modification will lead to less radiation exposure to the waste operator thereby enhancing the KNPP ALARA program.
3.9 Reactor Building Ventilation Two backdraft dampers in the ductwork from Containment Fan Coil Units 1A and IB to Reactor Coolant Pump 1B vault were replaced due to excessive leakage.
The replacement minimizes backflow through the idle fan coil unit.
(DCR1291' Summary of Safety Evaluation By replacing the leaking backdraft dampers the idle fan coil unit is isolated from the energized fan coil unit. This lowers the starting current for the fan coil unit thereby incriasing reliabi-lity. This modification completes a series of upgrades to the duct work downstream of the Containment Fan Coil Units. These upgrades ensure a QA-1 post-LOCA flow path through the fan coil units.
Reactor Building Ventilation Existing tubing supports for containment air sampling valves AS1, A52, and AS32 were replaced with supports designed for seismic and post-LOCA conditions. Also, all @ 1 sample tubing associated with radiation monitors R11, R12, and R21 was reviewed for. seismic loading, and support modifications were made as necessary.
(DCR 1945)
Summary of Safety Evaluation The modifications did not affect the USAR or the Technical Specifications.
The new restraints are designed for the loads indi-cated in the analysis for the tubing systems and, therefore, enhance plant safety.
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4.1 4.0 LICENSEE EVENT REPORTS This section is a summary of the 12 Licensee Event Reports (LER) sub-mitted to the NRC in 1987 in accordance with the requirements of 10CFR50.73. None of the events described in the 1987 LERs posed a j
threat to the health and safety of the public.
LER 85-015-01 On June 17, 1985, Fluor Engineers, Inc. notified Wisconsin Public Service Corporation that the seismic qualification of the emergency diesel generator differential relays could not be conclusively deter-mined. The relays are General Electric Model 12CF022B1A.
With this information and additional details provided in INPO SER 18-84, Supplement 1, "Diesel Generator Differential Relays Not Seismically Qualified," a management decision was made to defeat the differential relays' trip function. This was completed by 1600 on June 17, 1985.
Q' On January 20 and 21, 1987, the diesel generator differential relays were replaced with relays which are seismically qualified per IEEE 344-1975. The qualified relays are General Electric Model 12IJD52A12A.
LER87-001-g On February 23 and 24, 1987, a series of high radiation alerms were received in the control room on R-15, the condenser air ejector radiation monitor, and R-19, the Steam Generator Blowdown Radiation
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Monitor. High radiation levels on R-15 and R-19 are generally indica-4 tive of a primary to secondary leak. Per system design, the high radiation alarms resulted in Steam Generator Blowdown and Blowdown l
Sampling Isolation. At 0530 on February 24, chemistry samples indi-cated a primary to secondary leak rate of 266 gallons per day, i
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- J 4.2 Although the Technical Specification limit for primary to secondary leakage is 500 gallons per day, a plant power reduction was initiated at 0930 to limit the amount of leakage from the 1A Steam Generator.
At 1820, control room operators began berating the Reactor Coolant System to cold shutdown for the 1987 refueling outage.
The cause of the event was a primary to secondary leak in the 1A Steam Generator. Eddy Current testing on the Steam Generator tubes during the refueling outage determined the area in the 1A Steam Generator that resulted in the primary to secondary leak, allowing corrective actions to be implemented.
This event was reported as required by 10 CFR 50.73(a)(2)(iv) as an event that resulted in the automatic actuation of an Engineered Safety Feature. Results of the Eddy Current testing on the 1A and 1B Steam Generators have been submitted pursuant to Technical Specification 4.2.b.5, which include the cause of the primary to secondary leak.
LER 87-002-00 O
On February 24, 1987, the plant was in the process of shutting down for its annual refueling outage. At 1818, with the plant in hot shutdown and the reactor subcritical, a reactor trip occurred. The reactor was automatically tripped when 1 of 2 source range nuclear flux detectors erroneously reached the nominal reactor trip setpoint 4
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of 1.0E05 counts per second. This satisfied the required coincidence for a source range high flux reactor trip.
The operators took immediate actions in accordance with the reactor trip emergency operating procedure. When conditions stabilized, the orderly shutdown for the refueling outage was continued.
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4.3 It is believed that this event was caused by the seepage of borated
,,U refueling water into the source range detector's instrument port.
The borated water damaged the detector, which caused it to give erratic and erroneous indication.
The safety implications of this event are minimal because the reactor was suberitical, the redundant source range channel was operable, and the operators took the appropriate actions.
The failed source range detector was replaced with a spare detector.
To prevent a similar occurrence, an "0" ring has been installed bet-ween the instrument port and its cover to minimize or eliminate water infiltration into the port during refueling when the cavity is flooded.
This event was reported in accordance with 10 CFR 50.73(a)(2)(iv) as an unplanned automatic actuation of the reactor protection system.
LER 87-003-00
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At 2155 on March 3, 1987, a reactor operator identified that the Containment Fan Coil Unit Emergency Discharge Dampers were open and annunciator "CNTMT EMERG DISCH DMPRS ACTIVATED" activated. Upon veri-fication that the initiation signal was erroneous, immediate actions were taken by control room personnel to manually reset the containment high pressure signal and close the dampers.
Subsequent investigation indicated that activation of the dampers occurred at 1406 the same day, when power to Instrument Bus I was lost.
Loss of the bus caused numerous annunciators to activate in the control room.
The root cause of the event was an error in a procedure developed for a Design Change Request to replace Instrument Bus Inverter BRA-111 with a new Solidstate Controls Unit. As a result, when the electri-cian closed the preferred main breaker, the source breakers tripped, which resulted in a loss of power to Instrument Bus I.
Since Instrument Bus I is the source of power for Channel I of the logic for (l
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4.4 opening of the emergency discharge dampers, and Channel II was out of service for maintenance, the 2 out of 3 logic for actuation of the dampers was satisfied.
Since the dampers were found in their safeguards position and the plant was in the refueling shutdown mode at the time of the event, there were no safety concerns.
-This event was reported as required by 10 CFR 50.73(a)(2)(iv) as an event that resulted in the automatic actuation of an Engineered Safety Feature.
LER 87-004-00 On April 1, 1987, the plant was in hot shutdown preparing for startup f
from the 1987 refueling outage. At 2145, while plant operators ware reestablishing blowdown for the 1A Steam Generator, R-19, the Steam j
Generator Blowdown Radiation Monitor, reached its high alarm setpoint of 5000 cpm. As a result, Steam Generator Blowdown and Blowdown O
s =915a9 were auto tic 117 isoi ted > required by exstem desi9a-The root cause of the event was residual-contamination resulting from a tube leak which occurred in the 1A Steam Generator prior to the 1987 refueling outage. When blowdown from the 1A Steam Generator was i
manually isolated earlier in the evening, a build up of residual con-tamination occurred due to deposits of contaminated sludge in the blowdown line. As a result, when blowdown was reestablished, R-19 3
detected an increased level of radiation, which resulted in automatic isolation of Steam Generator Blowdown and Blowdown Sampling.
1 To reduce the frequency of this event, on April 4 the high alarm set-point for R-19 was increased to 80,000 cpm, which by conservative anal-
.ysis would correspond to 80 percent of the Radiological Effluent
)
Technical Specification default release limit.
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4.5 This event was reported as required by 10 CFR 50.73(a)(2)(iv) as v
an event that resulted in the automatic actuation of an Engineered-Safety Feature. Since the plant was at hot shutdown at the time of the event and the level of residual contamination detected was below the release limit established in Radiological Effluent Technical Specifications, there were no safety concerns.
i LER 87-005-00 At 2310 on April 3, 1987, with the' plant at 4 percent reactor-power and the turbine speed being increased to 1800 rpm, the 1A Main Feedwater Pump tripped. As required by plant design, with the IB Main Feedwater Pump not operating, the 1A Main Feedwater Pump trip resulted in a turbine trip and the~ automatic-start of the 1A and IB Diesel Generators and the 1A and 1B Motor Driven Auxiliary Feedwater Pumps.
j Immediate actions were taken by plant operators to start the 1A Main Feedwater Pump and secure the Diesel Generators and Auxiliary Feedwater Pumps. At 2320, the turbine was relatched and a turbine load increase was initiated.
The root cause of the event was personnel error.. After receiving ver-bal instructions from Operations to investigate the cause of annun-ciator "FW PUMP 1A ABNORMAL" in the control room, an Instrument and i
Control man exercised the 1A Main Feedwater Pump low lube oil pressure pump trip pressure switch. As a result, the 1A Main Feedwater Pump tripped on a low lube oil pressure signal.
i Plant personnel involved in the event were made aware of the impor-tance of identifying components and determining their possible impact
[
on plant operation prior to performing maintenance on equipment.
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4.6 This event was reported as required by 10 CFR 50.73(a)(2)(iv) as an event that resulted in the automatic actuation of an Engineered Safety 4
~ Feature. Since the reactor was at 4 percent reactor power prior to the event and all plant systems performed as required, there were no 4
safety concerns.
LER 87-006-00 On June 18, 1987, while the plant was operating at 100 percent power, Westinghouse Electric Corporation notified Wisconsin Public Service Corporation (WPSC) of a 10 CFR 21 item with regard to Westinghouse-supplied Component Cooling Water-System (CCWS).
l Due to a recommendation made by Westinghouse, WPSC removed the inter-nals from the relief valve on the CCW surge tank in July of 1984.
Westinghouse made the recommendation to prevent the possible overpressurization of the CCWS during a leak in a reactor coolant pump thermal barrier. Upon reevaluation of their recommendation, Westinghouse determined that the removal of the valve's internals could result in a violation of the containment integrity design basis for some plants, including Kewaunee.
WPSC immediately began evaluating the applicability of the June 18, 1987, 10 CFR 21 notification with the assistance of Westinghouse and 3
Fluor Engineers, Inc., the KNPP architectural engineering firm.
This evaluation determined that the Part 21 notification did not apply to the Kewaunee Plant. Therefore, no further corrective action was required.
This event was reported by WPSC in response to the 10 CFR 21 report sent to the NRC by Westinghouse.
I
4.7 LER 87-007-00 At 1148 on June 22, 1987, Steam Generator Blowdown and Blowdown Sampling were automatically isolated during performance of a Surveillance Procedure to calibrate R-19, the Steam Generator Blowdown Line Radiation Monitor. The event occurred as a result of a sticky contact on a relay, which failed to close, erroneously indicating a high radiation signal from R-19 and isolating Steam Generator Blowdown and Blowdown Sampling. After verifying that high radiation did not exist in the Steam Generator Blowdown lines, the operators reestablished Steam Generator Blowdown.
In addition to the isolation signal, R-15, the Condenser Air Ejector Radiation Monitor, and R-16, the Containment Fan Coil Unit Radiation Monitor, alarmed in the control room.
Since neither alarm was reini-tiated after control room operators reset the alarms, it was concluded that high radiation in the lines did not exist.
The root cause of the isolation was a sticky contact in the relay that controls the Steam Generator Blowdown and Blowdown Sampling Isolation valves. Actuation of R-15 and R-16 was a result of a voltage spike-that occurred during the event in the circuit which powers R 15, R-16 and R-19.
Immediately following the event, e jumper was installed, bypassing the faulty relay to allow Steam Ger.erator Blowdown to be reestablished.
At 1445 on June 23, the relay containing the sticky contact was replaced.
i This event was reported as required by 10 CFR 50.73(a)(2)(iv) as an event which resulted in the automatic actuation of an Engineered Safety Feature.
Since isolation of Steam Generator Blowdown and Blowdown Sampling performed as designed, assuming its safeguards posi-tion, there were no safety concerns, j
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4.8 LER 87-008-00
- 0n June 26, 1987, at 1115, with the plant at 100 percent power, a plant electrician pulled out the drawer of the upper phase B Main Generator Potential Transformer cabinet. This caused a loss-of-excitation signal to the Main Generator resulting in a generator trip,
~
followed by a turbine / reactor trip.
Information was needed on the electrical size of the Potential Transformers located in the Emergency Diesel Generator Control and Excitation Cabinet. A plant electrician was asked to collect this information by opening the cabinet door and reading the nameplate data. The electrician misunderstood the instructions and pulled out the Main Generator Potential Transformer Cabinet drawer. When the Potential Transformer was pulled out, an open circuit resulted, and the voltage signal to the loss-of-excitation relay was disconnected.
This loss of input caused the loss-of-excitation relay to be energized, resulting in a loss-of-excitation generator trip.
The root cause of the event was personnel error. The electrician misunderstood his job task.
To prevent recurrence, the Main Generator Potential Transformer cabinet will be locked and a caution sign will be placed on the front of the drawer.
The plant systems responded as designed, and the operators followed appropriate procedures for plant stabilization.
This event was reported as required by 10 CFR 50.73(a)(2)(iv).
LER 87-009-00 At 1143 COT on July 10, 1987, with the plant at full power, a reactor / turbine trip occurred due to an undervoltage (UV) transient on the 4160 volt electrical buses, designated as 1-1 and 12, which supply the Reactor Coolant Pumps and Main Feedwater Pumps.
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i 4.9 During normal power operation, the Main Auxiliary Transformer (MAT) powers the 4160 volt buses 1-1 and 1-2 from its "Y" windings and 4160 volt buses 1-3 and 1-4 from its "X" windings. A section of the Bus Bar running from the MAT to buses 1-3 and 1-4 was badly damaged due to insulation failure and a subsequent ground fault. The fault on the "X" windings caused the voltage on the "Y" windings to decrease resulting in a coincident undervoltage condition of less than 77 per-cent of rated voltage for greater than 0.1 seconds on buses 1-1 and 1-2, causing a reactor trip.
Immediately after the trip, operators implemented the appropriate Emergency Operating Procedures and stabilized the plant at Hot Shutdown. Plant systems performed as designed.
Prior to startup, the damaged section of the Bus Bar was isolated.
Buses 1-3 and 1-4 were being powered from the Reserve Auxiliary
}
Transformer (RAT), while the MAT continued to feed Buses 1-1 and 1-2.
Additional corrective actions included contacting the manufacturer to I C provide an in-depth analysis and a consultant for an independent assessment. The damaged section of the Bus Bar will be replaced.
There was no other equipment damage as a result of this event.
This event was reported per 10 CFR 50.73(a)(2)(iv) as an actuation of the Reactor protection System and actuation of Engineered Safety Features.
LER 87-010-01 i
On September 4, 1987, at 0226 CDT with the plant at 100% power, Technical Specifications pertaining to containment integrity provi-sions were violated. The redundant containment isolation (CI) sump A j
discharge control valves (MD(R)-134 and MD(R)-135) were opened for 2.9 minutes while valve MD(R)-134 was considered inoperable. The Reactor Operator opened both valves in response to a high containment sump level alarm per operating procedure A-MDS-30. ValveMD(R)-134was j
administrative 1y inoperable because it had not been completely j
retested following replacement of its associated solenoid valve.
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After satisfactorily completing the retest requirements without any O
further adjustments, the valve was declared operable at 1210 the same day.
L This event occurred because clear instructions addressing the valve's inoperable status and the reasons for the inoperable status were not included on the DANGER tag.
In addition Design Change Procedure d
1544-15 failed to adequately identify valve MD(R)-134 and MD(R)-135 as redundant containment isolation valves which have operability require-ments defined in the Technical Specifications.
Closure of valve MD(R)-135 to allow retest cycling of valve MD(R)-134 was not covered by the procedure.
Immediate corrective actions included an informal review with the personnel involved. Other corrective actions will include revising the applicable Administrative Control Directive pertaining to Design Change personnel, and reviewing the incident with Plant Operations personnel to stress the importance of providing detailed status infor-
,Q mation on the DANGER tags.
LER 87-011-00 i
On December 8, 1987, while the plant was operating at 100 percent power, Wisconsin Public Service Corporation (WPSC) was advised by another utility of a concern regarding the premature failures of cer-tain relays in Foxboro 62H controllers.
These same relays were installed at KNPP as part of an overall controller refurbishment pro-ject for both the reactor protection (RPS) and plant process control
]
systems.
Included in the scope of refurbishment is the changeout of a l
non-hermetically sealed relay to a hermetically sealed unit 'u elimi-
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nate failures caused by contact corrosion.
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4.11 The investigation into the cause of the relay failures is not complete; however, initial investigations strongly suggest that the relays failed due to an overvoltage condition. Presently, the voltage across both the originally installed and the recently installed replacement relays is higher than their rated voltage.
However, the original i
relays do not appear as susceptible to premature failures.
i Although the replacement relays are susceptible to premature failure, they are operable and capable of performing their safety related func-tion. Periodic surveillance testing provides continued assurance of relay operability.
In addition, a letter which identifies the systems which use the 62H controller and provides contingent instructions has been made required reading for all operators.
Final corrective actions are still being investigated. However, a solution to resolve the RPS circuitry concerns, as a minimum, is expected to be implemented during the next refueling outage in March of 1988.
' Q This report was submitted to supplement the 10CFR 21 report which Foxboro provided to the NRC on December 21, :.987.
LER 87-012-00 On November 28, 1987, with the plant at full power, two independent, containment isolation control valves failed to close from the control room during performance of their inservice testing (IST). The two valves, MU-1010-1 and RC-507, failed to close because their respective solenoid valves were unable to block the instrument air flow to the control valves when de-energized.
The solenoid valves, which have a maximum operating pressure differential (MOPD) of 70 psi, were found to have their corresponding air line regulators set at 80 psi. This resulted in the solenoid valves being overpressurized. These solenoid valves had been replaced as a part of a recent design change during which time the incorrect models, with too low an MOPD, were purchased i
and installed, i
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1 4.12 g-A field walkdown of other safety related solenoid valves in the plant and their air regulator settings was performed. No other cases were found where the air regulator setting would have prevented the sole-I f
noid from operating properly. However, other cases were found where i
the solenoid valves had an M0PD less than instrument air pressure.
Planned corrective actions include replacing solenoid valves and establishing a program to formalize instrument air regulator settings.
e i
This event not required by 10 CFR 50.73 to be reported but is being I
reported in the "other" category'because of its potential interest to other licensees, r
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I 5.1 5.0 FUEL INSPECTION REPORT Forty (40) fresh Region 0 assemblies were loaded for Cycle XIII. Startup i
physics testing was performed and reported in the Cycle XIII Startup
- Report, i
The irradiated fuel inspection was performed with an underwater TV camera.
i All peripheral fuel rods were examined using one-half face scans. Three assemblies were inspected, including one in region J and two in region N.
All assemblies exhibited rod slippage to various degrees, with the region J assembly having rods in contact with the bottom nozzle. Numerous scrapes te the rodlets, grids, and top and bottom nozzles were noted. However, no damage to the cladding or supporting structures was observed. All assemblies exhibited axially varying crud deposits. Overall condition of the fuel was very good, with no evidence of fuel cladding degradation on l
the fuel rods examined. Video tapes were made of all examinatioris.
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6.0 CHALLENGES 10 AND FAILURES OF PRESSURIZER SAFETY AND RELIEF VALVES There were no challenges to or failures of pressurizer safety or relief l
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1 4
valves during 1987.
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7.1 1
7.0 SlM MRY OF THE 1987 STEAM GENERATOR ED0Y CURRENT EXAMINATION 0 7 During the Kewaunee Nuclear Power Plant's 1987 refueling outage the t
following steam generator services were performed.
d' Eddy Current Inspection j
All unplugged accessible steam generator tubes were inspected to varying extents *. Two tubes, row 1, column 24 and row 33, column 40, had visible water leaks during the inspection. The tube in row 33, column 40 was temporarily plugged to allow the inspection to continue.
All base program testing was performed using a 0.720-inch diameter bobbin coil probe (0.680 inch probe in rows 1-3 U-bends) and test frequencies of 400 KHz, 200 KHz, 100 KHz and 10 KHz in both absolute and differential modes.
In addition to the base program, 119 tubes were reinspected using rotating pancake probe techniques. This selection included tubes with distorted indications, multiple indications and tubes without indications.
Mechanical Plugg13 Steam Generator A Total of 44 tubes were fitted with mechanical plugs. One tube, row 32, column 24, had a plug installed in the outlet side that projected 5/16 i
of an inch frem the tube end. All installation parameters were met.
Steam Generator B 4
Total of 79 tubes were fitted with mechanical plugs. All installation
)
parameters were met.
APPLICABLE DEFINITIONS:
Degraded Tube: A tube with greater than a 20 percent thru-wall indication.
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Defective Tube: A tube with greater than a 50 percent thru wall indication.
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If significant tube thinning has occurred in the area of the l
indication, the defective tube criterion is reduced to greater i
than 40 percent thru-wall.
These tubes require plugging.
L HISTORICAL Sl204ARY OF TUBES PLUGGED IN THE KEWAUNEE STEAM CF.NERATORS t
Number of Tubes Plugged in:
Steam Generator 1A Steam Generator 1B 1983 23 50 1984 8
17
- l 1985 27 22 1986 26 46 1987 44 79 i
TDTXL T2B YIT
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l TOTAL AS PERCENT i
(3388 tubes / generator) 3.8%
6.3%
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7.2 Table 7.1 O
Summary of the 1987 Steam Generator Eddy Current Examination Inspection Extent l
STEAM GENERATOR 1A i
Extent of Inspection Hot Leg Cold Leg Full Length 365 259 U-Bend (1)
- 7 TSP 1
- 2 TSP 31 2648
- 1 TSP (2)
TTS 1
TOTALS 3304 1
STEAM GENERATOR 1B Extent of Inspection Hot leg Cold leg O
Full Length 351 U Bend 272
- 2 TSP 8
- 1 TSP 2622 TOTALS 3253 F
(1) Tube support plate, counted up from the tube sheet l
(2)Topoftubesheet I
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i 7.3 TABLE 7.2 (Page 1 of 5)
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1987 Eddy Current Examination Reportable Indications Steam Generator 1A
% THRU WALL INDICATION (U ROW COLUMN PENETRATION PLUGGED LOCATION 5
2 56 X
H - TSP #1 13 4
38 H
TSP #1 i
9 8
56 X
H - TSP #1 5
9 59 X
H - TSP #1 24 9
74 X
H - TSP #2 24 10 26 H - TSP #4 l
3 11 91 X
H - TE + 7.5 j
2 12 D'.( 2)
X H - TSP #1 25 13 82 X
H - TE + 7.7
! O lU 5
14 21 H - TS + 0.8 6
16 21 H
TS + 0.7 14 16 34 H
TSP #1 i
l 32 16 27 H - TSP #1 1
i 1
33 16 21 H - TSP #1 I
5 17 28 H - TS + 1.2 i
8 19 22 H - TS + 1.0 1
19 21 98 X
H - TE + 7.1 j
8 22 31 H - TS + 0.2 8
23 28 H
TS + 2.8 j
1 24 99 X
H - TE + 10.5 2
24 52 X
H - TSP #3 32 24 77 X
H TE + 6.4 l
4
7.4 TABLE 7.2 (Page 2 of 5)
' O 1987 Eddy current Examination Reportable Indications Steam Generator 1A i
% THRU-WALL INDICATION (U R0W COLUMN PENETRATION PLUGGEO LOCATION 37 24 92 X
H - TE + 7.7 i
10 30 33 H - TS + 1.9 23 30 24 H - TS + 3.6 2
32 76 X
H - TE + 4.3 3
32 37 H - TS + 0.8 6
32 90 X
H - TE + 2.3 28 33 29 H - TS + 1.7 35 33 38 H - TS + 0.3 4
35 71 X
H - TE + 2.8 10 35 79 X
H - TE + 6.9 i
17 35 27 H - TS + 2.6 i
40 36 31 H - V3 I
]
2 37 84 X
H - TE + 5.0 9
37 60 X
H - TE + 12.0 l
10 37 76 X
X H
TE + 7.1 l
l i
29 39 21 H - TS + 0.7 l
18 40 85 X
H - TE + 4.4 33 40 98 X
H - TE + 10.2 34 40 71 X
H - TE + 10,9 i
j 29 41 20 H - TS + 0.5 13 42 67 X
H - TE + 3.4
't
7.5 j
4 TABLE 7.2(Page3of5)
O 1987 Eddy Current Examination Reportable Indications Steam Generator 1A r
% THRU WALL INDICATION (U R0W COLUMN PENETRATION PLUGGEO LOCATION 20 43 82 X
H - TE + 5.9 30 43 22 H
TS + 0.3 5
45 94 X
H - TE + 3.1 7
46 SQR(3)
X H - TE + 4.2 9
46 47 X
H - TE + 10.9 19 46 77 X
H - TE + 9.8 30 46 33 H - TS +-0.4 j
32 46 28 H - TS + 0.5 i
I 3
47 94 X
H - TE + 2.1 16 47 26 H - TS + 2.9 22 47 23 H - TS + 0.4 11 48 32 H - TS + 1.0 24 48 26 H - TS + 0.8 25 48 30 H - TS + 0.6 26 48 48 X
H - TS + 0.5 30 48 66 X
H - TS + 0.3 31 48 60 X
H - TS + 0.8 9
49 34 H - TS + 0.5 24 49 30 H - TS + 2.3 13 50 24 H - TS + 1.5 j
l 22 50 27 H - TS + 1.8 14 51 44 X
H - TS + 3.2 1
7.6 TABLE 7.2 (Page 4 of 5) 1987 Eddy Current Examination Reportable Indications Steam Generator 1A
% THRU-WALL INDICATION (U ROW COLUMN PENETRATION PLUGGEO LOCATION 23 51 31 H - TS + 1. 8 29 52 28 H - TS + 0.6 11 53 25 H
TS + 0.9 11 54 20 H - TS + 0.9 34 54 80 X
H - TE + 5.7 18 55 23 H - V2 10 56 31 H - TS + 0.7 13 58 86 X
H - TE + 2.7 11 59 38 H - TS + 1.6 O
23 59 29 H. TS. 0.5 7
60 83 X
H - TE + 20.4 2
61 80 X
H - TE + 6.2 13 62 24 H - TS + 1. 9 23 65 30 H - TS + 0.8 9
66 31 H - TS + 0.7 23 66 28 H - TS + 0.6 18 67 36 H - V2 28 67 82 X
X H - TE + 6.8 8
68 32 H - TS + 0.6 19 70 31 H - TS + 0.5 23 73 96 X
H - TE + 12.0
7.7 TABLE 7.2(Page5of5)
>O 1987 Eddy Current Examination Reportable Indications 4
% THRU-WALL INDICATION (U d
ROW COLUMN PENETRATION PLUGGED LOCATION i
35 73 28 H - TSP #7 12 74 23 H - TS + 0.8 4
18 74 28 H - TS +=0.7 4
75 28 H - TS + 0.4 6
75 33 H - TS + 0.3 t
9 76 28 H - TS + 0.8 2
77 30 H - TS + 0.5
)!
6 80 37 H - TS + 0.7 1
20 81 87 X
H - TE + 4.6 i O 27 81 52 X
H - TE + 4.3 7
90 75 X
H - TSP #1 j
31 16 25 C - TSP #1
+
r 7
1 (1) H - Inspected from Hot Leg i
C - Inspected from Cold Leg TSP - Tube Support Plate TS - Tube Sheet i
TE - Tube End i
V2 - #2 Antivibration Bar l
j V3 - #3 Antivibration Bar l
Note that numbers added to TSP, TE, etc. are distances in inches above the l
indicated reference point in the indicated leg.
(2) DI - Distorted Indication i
(3) SQR - Squirrel, unquantifiable defect signal within the tube sheet.
7.8 TABLE 7.3 (Page 1 of 12) 0 1987 Eddy Current Examination Reportable Indications Steam Generator IB q
% THRU WALL INDICATION (U ROW COLUMN PENETRATION PLUGGED LOCATION l
10 9
92 X
H - TE + 10.6 30 12 32 H - TSP #3 19 14 96 X
H - TE + 7.4 i
4 15 84 X
H - TE + 10.3 5
17 23 H - TS + 0.8 J
8 17 29 H - TS + 0.9 11 18 24 H - TE + 4.5 3
20 22 H - TS + 0.8 i
)
4 20 24 H - TE + 4.2 5
20 30 H - TS + 0.2 5
22 53 X
H - TE + 3.1 9
22 36 H - TS + 0.4 I
{
33 22 24 H - TSP #1 3
23 26 H - TS + 0.5 l
2 9
23 28 H - TS + 0.4 27 23 89 X
H - TE + 10.0 l
6 24 61 X
H - TE + 7.1 j
9 24 34 H - TS + 0.4 i
19 24 SQR(2)
X H - TE + 5.7 1
23 24 37 H - TS + 0.6 1
2 25 78 X
H - TE + 3.2 8
25 77 X
H - TE + 3.7 4
7.9 TABLE 7.3 (Page 2 of 12)
O 1987 Eddy Current Examination Reportable Indications Steam Generator 18
% THRU WALL INDICATION (i)
ROW COLUMN PENETRATION PLUGGEO LOCATION
]
11 25 31 H - TS + 0.5 i
16 25 40 H - TS + 2.1 24 25 42 H - TS + 0.8 l
33 25 76 X
H - TE + 13.3 i
4 26 43 H
TE + 3.4 11 26 34 H - TS + 0.6 l
12 26 28 H - TS + 0.5 24 26 71 X
H TE + 3.1 1
5 27 74 X
H - TE + 3.1
' O 7
27 54 X
H TE + 3.6 l
9 28 SQR(2)
X H - TE + 7.4 i
12 28 32 H - TS + 0.4 1
15 28 20 H - TS + 1.0
'3 28 31 H - TE + 3.6 1
24 28 37 H - TE + 3.3 i
25 28 39 H - TS + 1.0 4
26 28 67 X
H - TE + 3.4 27 28 36 H - TS + 1.1 J
6 29 73 X
H - TE + 4.6 1
12 29 35 H - TS + 0.8
]
16 29 26 H - TE + 5.0 22 29 21 H - TE + 5.6 1
)
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7.10 TA8LE 7.3 (Page 3 of 12) p v
1987 Eddy Current Examination Reportable Indications Steam Generator 1B
% THRU WALL INDICATION (O ROW COLUMN PENETRATION PLUGGED LOCATION I
23 29 33 H
TS + 1.2 26 29 40 H - TS + 0.8 27 30 24 H - TS + 1.0 t
28 30 21 H - TE + 3.2 1
31 88 X
H - TE + 10.0 26 31 40 X
H - TE + 3.8 28 31 63 X
H - TS + 0.8 3
32 SQR(2)
X H - TE + 5.7 24 32 34 H - TE + 3.5 O
27 32 42 x
H. TE. 3.4 28 32 34 H - TS + 1.8 30 32 95 X
H - TE + 2.9
)
5 33 44 H - TE + 3.9 26 33 43 X
H - TE + 11.2 l
l 29 33 32 H - TS + 1.3 i
I 4
34 85 X
H - TE + 3.9 j
6 34 85 X
H - TE + 3.3 l
11 34 47 X
H - TE + 3.5 16 54 53 X
H - TS + 2.3 i
30 34 70 X
H - TE + 3.3 j
3 35 24 H - TS + 0.3 13 35 61 X
H - TS + 0.5 O
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7.11 i
TABLE 7.3 (Page 4 of 12) 1987 Eddy Current Examination Reportable Indications Steam Generator 18
% THRU WALL INDICATIONU)
ROW COLUMN PENETRATION PLUGGEO LOCATION
[
16 36 91 X
H - TE + 3.4 i
31 36 43 H - TS + 0.3 38 36 29 H - TSP #4 9
37 28 H - TE + 3.7 22 37 85 X
H TE + 3.3 23 37 29 H - TE + 5.3 t
28 37 45 X
H - TE + 4.4 l
29 37 91 X
H - TE + 5.0
[
30 37 24 H - TS + 2.2 32 37 22 H
TS + 1.6 33 37 21 H - TS + 0.7 11 38 38 H - TS + 0.3 l
31 38 42 H
TS + 2.6 8
39 32 H - TE + 7.5 25 39 80 X
H - TE + 4.1 30 39 26 H - TS + 2.0 31 39 35 H - TS + 0.2 32 39 28 H - TE + 3.6 11 40 52 X
H TS + 0.4 26 40 38 H
TE + 6.1 7
41 48 X
H TE + 2.9 1
6 42 32 H - TE + 3.8 1
1
i 7.12 TABLE 7.3 (Page 5 of 12) o 1947 Eddy Current Examination Reportable Indications Steam Generator 18 i
% THRU WALL INDICATION (U ROW COLUMN PENETRATION PLUGGED LOCATION j
13 1
76 X
H TS + 2.8 16 43 42 X
H - TE + 4.4 21 43 29 H - TS + 2.4 29 43 44 X
H - TS + 2.3 4
30 43 25 H - TS + 2.1 31 43 32 H - TS + 1.9 32 43 29 H - TS
- 1.4 6
44 55 X
H - TE + 3.3 11 44 44 H - TE + 3.2 l
13 44 67 X
H TS + 2.2 I
4 1
14 44 43 X
H TE + 3.0 j
30 44 29 H - TS + 1. 9 14 45 42 H
TS + 2.7 1
j 28 45 69 X
H TE + 4.7 1
29 45 32 H
TE + 3.6 1
32 45 91 X
H TE + 3.4 2
46 70 X
H - TE + 4.2 a
10 46 47 H - TS + 0.7 17 46 31 H - TS + 4.0 27 46 56 X
H TS + 4.6 28 46 33 H
TS + 4.7
- O
)
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.-y
7.13 TABLE 7.3(Page6of12)
- q 1987 Eddy Current Exaaination Reportable Indications
[
Steam Generator IB i
I I
% THRU WALL INDICATION (U 1
{
ROW COLlNN PENETRATION PLUGGED LOCATION 38 46 42 H - TSP #7 i
j 6
47 88 X
H - TE + 4,2 10 47 66 X
H - TS + 0.4 11 47 31 H - TS + 1.2 i
13 47 42 H - TS + 2.5 i
i 4
14 47 59 X
H TS + 4.9 i
20 47 31 H
TS + 4.8 t
21 47 35 H - TS + 3.2 1
i 22 47 31 H
TS + 2.6 O
j 23 47 39 H - TS + 5.2 28 47 51 X
H TE + 3.9 i
30 47 51 X
H TS + 0.2 i
17 48 34 H - TS + 4.6 18 48 45 H
TS + 3.1 j
19 48 23 H
TS + 4.9 1
24 48 47 H - TS + 4.0
)
31 48 53 X
H - TS + 0.0
- l 33 48 36 H - TS + 0.7 l
4 49 31 H
TS + 1.0 l
13 49 30 H - TS + 2.8 14 49 33 H - TS + 4.6 Q
17 49 39 H
TS + 5.3 N
7.14 TABLE 7.3 (Page 7 of 12)
O V
1987 Eddy Current Examination Reportable Indications Steam Generator 1B
% THRU-WALL INDICATIONU)
R0W COLUMN PENETRATION PLUGGED LOCATION 18 49 34 H - TS + 4.1 19 49 25 H - TS + 4.6 23 49 52 X
H - TE + 4.2 29 49 35 H - TS + 3.4 31 49 70 X
H - TS + 2.6 32 49 27 H - TE + 8.5 33 49 54 X
R - TS.+ 0.0 18 50 31 H - TS + 3.6 23 50 60 X
H - TE + 3.7 O
25 50 34 H - Te + 5.4 30 50 90 X
H - TE-+ 2.9 31 50 52 X
H - TE + 4.3 32 50 37 H - TS + 0.7 30 51 30 H - TSP #2 32 51 46 H - TE + 6.5 22 52 21 H - TE + 2.9 27 52 24 H - TE + 3.4 6
53 24 H - TE + 4.5 11 53 77 X
H - TE + 3.0 21 53 36 H - TE + 4.6 i
23 53 42 H - TE + 4.4 24 53 71 X
H - TE + 2.9
,---,r-.
1
7.15 TABLE 7.3 (Page 8 of 12)
O 1987 Eddy Current Examination Reportable Indications Steam Generator 1B
% THRU-WALL INDICATION (l>
RDW COLUMN PENETRATION PLUGGED LOCATION 25 53 57 X
H - TE + 5.5 32 53 30 H - TE + 3.7 7
54 51 X
H - TE + 5.4 33 54 45 H - TS + 0.2 30 55 33 H - TS + 7.1 31 55 30 H - TS + 6.1 32 55 54 X
H - TS.+ 6. 0 9
56 79 X
H - TE + 3.3 26 56 32 H - TS + 4.4 33 56 39 H - TS + 0.0 8
5.
29 H - TE + 3.7 9
57 39 H - TE + 3.9 26 57 63 X
H - TE + 3.4 29 57 42 H - TS + 5.9 30 57 24 H - TS + 2.5 9
58 83 X
H - TE + 2.7 14 58 31 H - TS + 0.8 23 58 57 X
H - TE + 3.4 30 58 32 H - TS + 1.0 33 58 52 X
H - TS + 0.0 6
59 46 H - TE + 3.9 8
Co 65 X
H - TE + 2.6
()
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H 7.16 TABLE 7.3 (Page 9 of 12) i b-y 1987 Eddy Current Examination Reportable Indications Steam Generator 1B
% THRV-WALL-INDICATIONU)
R0W COLUMN PENETRATION PLUGGED LOCATION i
25 59 33 H - TE + 2.8 29 59 39 H - TSP #4 33 59 33 H - TS + 2.6 24 60 33 H - TE + 4.8 33 60 24 H - TS + 1.7 4
61 45 H - TS + 0.6 14 61 41 H - TSP #1 26 61 64 X
H - TE + 3.3 30 61 49 X
H - TS + 1.1 0
14 62 50 X
H - TS + 0.7 9
63 90 X
H - TE + 2.8 23 63 23 H - TS + 3.2
~
24 63 29 H - TS + 3.1 25 63 21 H - TS + 3.2 27 63 36 H - TSP #1 31 63 34 H - TSP #1 17 64 27 H - TS + 1.0 25 64 24 H - TSP #1 37 64 38 H - V4 2
65 87 X
H - TE + 12.4 11 65 85 X
H - TE + 2.8 14 65 24 H - TS + 1.2 Q
7.17 TABLE 7.3 (Page 10 of 12) 1987 Eddy Current Examination Reportable Indications Steam Generator 1B
% THRU WALL INDICATION (U R0W COLUMN PENETRATION PLUGGED LOCATION 17 65 27 H - TE + 3.0 25 65 32 H - TS + 0.9 26 65 34 H - TS + 0.7 27 65 24 H - TS + 2.3 27 66 24 H - TS + 0.9 10 67-21 H - TS + 0.9 1
68 SQR(2)
X H - TE + 5.5 11 69 50 X
H - TS + 1.0 30 69 26 H - TSP #1 0
21 70 26 H - TS + 1.7 7
71 24 H - TS + 1.2 33 71 28 H - TSP #3 35 71 37 H - TSP #1 10 72 67 X
H - TS + 0.8 15 72 31 H - TE + 4.5 33 73 40 H - TSP #3 6
74 30 H - TS + 0.8 8
74 29 H - TS + 0.9 4
75 41 H - TS + 0.9 31 76 42 H - TSP #3 33 76 53 X
H - TSP #1 Q
16 89 25 H - TSP #1
7.18 e
TABLE 7.3 (Page 11 of 12)
( ).
1987 Eddy Current Examination Reportable Indications Steam Generator IB
% THRU-9ALL INDICATION (1)
R0W COLUMN PENETRATION PLUGGED LOCATION 19 90 33 H - TSP #4 9
2 24 C - TS + 2.1 25 12 42 C - TSP #6 43 42 39 C - TSP #7 21 43 37 C - TSP #5 44 44 38 C - TSP #6 43 45 26 C - TSP #7 17 47 26 C - TS + 0.6 38 48 21 C - TSP #6 4
49 40 C - TSP #3 21 49 34 C - TSP #1 38 49 20 C - TSP #6 38 51 23 C - TSP #7 43 53 39 C - TSP #7 17 57 23 C - TSP #7 39 62 26 C - TSP #7 36 64 23 C - TSP #7 37 64 29 C - TSP #6 39 65 27 C - TSP #6 35 72 45 C - TSP #6 33 73 40 C - TSP #7 35 73 36 C - TSP #7
()
7.19 a
TABLE 7.3 (Page 12 of 12) 1987 Eddy Current Examination Reportable Indications Steam Generator 1B
% THRU-WALL INDICATIONW1
_ R0W COLUMN PENETRATION PLUGGED LOCATION 24 75 31 C - TSP #6 33 76 36 X
C - TSP #7 (See Hot Leg) 16 88 46 C - TSP #7 19 89 27 C - TSP #1 19 90 26-C - TSP #7 (1)
H - Inspected from Hot Leg C - Inspected from Cold Leg TSP - Tube Support Plate O
TS - Tube Sheet TE - Tube End V4 - #4 Antivibration Bar Note that numbers added to TSP, TE, etc. are distances in inches aaove the indicated reference point in the indicated leg.
(2) SQR - Squirrel, unquantifiable defect signal within the tube sheet.
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8.1 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, 8.3.and 8.4 povide 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 1987 Range (mR)
No. of Individuals No Heasurable 160
< 100 329 100 -
249 141 250 -
499 124 500 -
749 87 750 -
999 31 1000 -
1999 40 2000 - 2999 2
3000 - 3999 1
4000 - 4999 0
5000 -
5999 0
6000 - 6999 0
7000 - 7999 0
8000 - 8999 0
9000 - 9999 0
10000 - 10999 0
11000 - 11999 0
> 12000 0
915 O
8.2 Table 8.2 TOTAL NUMBER OF CONTRACTORS PROVIDED WITH PERSONAL DOSE MONITORING DEVICES Range (mR)
No. of Individuals No Measurable 98
< 100 211 100 -
249 85 250 - 499 90 500 -
749 68 750 - 999 27 1000 - 1999 33 2000 - 2999 1
3000 - 3999 0
613 Table 8.3 TOTAL NUMBER OF WPSC PLANT STAFF PROVIDED WITH PERSONAL DOSE MONITORING DEVICES Range (mR)
No. of Individuals No Heasurable 44
< 100 71 100 -
249 38 250 - 499 28 500 -
749 15 750 - 999 4
1000 - 1999 7
2000 2999 1
3000 - 3999 1
209 0
8.3 i
Table 8.4 TOTAL NUM ER OF PERSONNEL (WPSC NON-PLANT STAFF) PROVIDED WITH PERSONAL DOSE MONITORING DEVICES Range (mR)
No. of Individuals No Heasurable 18
< 100 47 100 -
249 18 250 - 499 6
500 -
749 4
750 - 999 0
1000 - 1999 0
2000 - 2999 0
3000 - 3999 0
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V 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 Section 6.9.1.b of the Kewaunee Nuclear Power Plant Technical Specifications. The total actual dose at the Kewaunee Plant for 1987 was 226.383 man-rem.
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9.1 9.0 RADIOLOGICAL MONITORING PROGRAM Attached is the report from Teledyne Isotopes'on the Radiological i
' Monitoring Program for the Kewaunee Nuclear Plant for 1987..
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W TELEDYNE ISOTOPES MIDWEST LABORATORY O-i
~ 1508 FRONTAGE RD.~
NORTHBROOK,IL 60062 4197 Q12) 564 0700 REPORT TO-
-WISCONSIN PUBLIC SERVICE CORPORATION WISCONSIN POWER AND LIGHT COMPANY MADIS0N GAS AND ELECTRIC COMPANY RADIOLOGICAL MONITORING PROGRAM FOR THE KEWAUNEE NUCLEAR POWER PLANT KEWAUNEE, WISCONSIN ANNUAL REPORT - PART I
SUMMARY
AND INTERPRETATION O
January - December 1987 e
i i
PREPARED AND SUBMITTED BY TELEDYNE IS0 TOPES MIDWEST LABORATORY PROJECT NO. 8002 Approved by:
( /J pijft.,
" L ffs. Huei>ner G&fleral Manager O
26 February 1988
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PREFACE 6
The staff members of the 'ieledyne : Isotopes Midwest Laboratory were responsible for the acquisition of data presented in this : report.
Assistance. in sample i
collection was provided by Wisconsin Public Service Corporation: personnel, i
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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TABLE OF CONTENTS Page Prefa'ce..-.................-.........
ii L i s t o f Fi g ure s........................
iv List of Tables v-
1.0 INTRODUCTION
1 P
2.0
SUMMARY
2~
i 3.0 RADIOLOGICAL SURV3ILLANCE 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 Prog ram Ex ec ut io n.................
6 3.1.5 Program Modifications................
6 s
3.2 Results and Discussion..................
7 3.2.1 Atmospheric Nuclear Detonations and Nuclear Accidents................
7
- 3. 2. 2 Th e Ai r E nv i ro nmen t................
7 3.2.3 The Terrestrial Environment.
8 3.2.4 The Aquatic Environment.
11 j
4.0 FIGURES AND TABLES 14
5.0 REFERENCES
31 APPENDICES A
Interlaboratory Comparison Program Results A-1
'B Statistical Notations.....................
B-1 C
Maximum Permissible Concentrations of Radioactivity in Air and Water above Natural Background in Unrestr ic ted Areas....................-
C-1 O
iii
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O LIST OF FIGURES No.
Caption Page 4-1 Sampling locations, Kewaunee Nuclear Power Plant.......
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.O LIST OF TABLES No.
Title
-Page 4.1 Sampling locations, Kewaunee Nuclear Power Plant,.......
16:
.l 4.2 Type and frequency of collection................
17 4.3 Sample codes used in Table 4.2.................
18 4.4 Sampling sumary, January - December,1987...........-
19 4.5 Environmental Radiological Monitoring Program Summary......
20 In addition, the following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results, 1984-1987 A-3 A-2 Interlaboratory Comparison Program Results, (TL0s)....... A-14 A-3.
In-house Spiked Samples A-17 A-3 In-house "Bl ank" Sampl es.................... A-20 Attachment B:
Acceptance criteria for spiked samples A-22 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas...................... C-2 O
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b
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 1987.
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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SUMMARY
Results of sample analyses during the period January - December 1987 are i
summarized in Table 4.5.
Radionuclide concentrations measured at indicator l
locations are compared with ' levels. measured. at control locations 'and in i
preoperational studies.
The comparisons. indicate background-level radio-activities in all samples collected with the following exceptions:
l 4
1.
Trace amounts of Co-58 (mean 0.089 pCi/g dry weight) were detected in two bottorr, sediment samples and trace amount of Co-60 (0.065 pCi/g dry weight) was detected in one bottom sediment sample near the condenser discharge.
The levels are insignificant.
2.
Trace amounts of Co-58 (mean 0.047 pCi/g wet weight) were i
detected in two periphyton samples and trace amount of Co-60 j
(0.062 pCi/g wet weight) was detected in one periphyton sample at condenser discharge and at Location.K-le, South Creek onsite.
The levels are insignificant.
Presence of Co-58 and Co-60 in bottom sediments and periphyton is probably plant related, j
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3.0 RADIOLOGICAL SURVEILLANCE PROGRAM Following is a description of the Radiological Surveillance Program and its execution.
3.1 Methodology The sampling locations are shown in Figure 4-1.
Table 4.1 describes the locations, lists for each its direction and distance from the reactor, and indicates which are indicator and which are control locations.
The sampling program monitors the air, terrestrial, and. aquatic envi-ronments.
The types of samples collected at each location and the frequency of-collections are presented in Table 4.2 using sample codes i'
defined in Table 4.3.
The collections and analyses that comprise the program are described below.
Finally, the execution ' of the program in the current reporting year is discussed.
)
3.1.1 The Air Program Airborne Particulates The airborne particulate samples are collected on 47 m diameter glass fiber filters at a volumetric rate of approximately one cubic foot per minute.
The filters are collected weekly _ from six locations (K-1f, K-2, K-7, K-8, K-15, and K-16), and dispatched by mail to TIML for radiometric analysis.
The material. on the filter is counted for gross beta activity approximately five days after receipt to allow for decay of naturally-occurring short-lived radionuclides.
Quarterly composites from each sampling location are analyzed for' gamma-emitting isotopes by a germanium detector.
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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 imediately af ter arrival at the laboratory.
Ambient Gamma Radiation - TLDs The integrated gamma-ray background is measured at six air sampling locations (K-1f, K-2, K-7, K-8, K-15, and K-16), at four milk sam-pling locations (K-3, K-4, K-5, and K-6), and at ' two additional locations (K-17, located 4.25 miles west of the plant; and K-27, located 1.5 miles northwest of the plant) with thermoluminiscent dosimeters (TL0s).
CaF :Mn bulb TLDs are exchanged quarterly and 2
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 O
Miik Milk samples are collected semimonthly (one gallon from each location) from May through October and monthly (two gallons from l
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 i
K-19) from two herds that graze between four and ten miles from the reactor site (K-3 and K-6), and from a dairy in Green Bay (K-28).
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 X-10, K-11, K-12, and K-13 and from two on-site wells located at K-19 and K-lh.
The gross beta and gamma spectroscopic analyses are performed 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.
Additionally, samples of water from two on-site wells (K-1g and K-lh) are also analyzed for gross alpha.
Water from one on-site well (K-1g) is also analyzed for tritium, strontium-89, and dg strontium-90.
4
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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, garmia scanned, and ' analyzed for gross. alpha, and gross beta activities.
E_g.g s
-Eggs are collected quarterly at ~ Location 'K-27.
The samples are gamma scanned and analyzed for gross beta,: strontium-89, and strontium-90 activities.
Vegetables Vegetable samples (5 varieties) are collected at locations K-18 and K-26, and two varieties of grain, if available, at location K-23.
The samples are gamma scanned and analyzed for gross beta, strontium-89, and strontium-90 activities.
Grass and Cattle Feed Grass samples are collected during the second, third and fourth quarters from two on-site locations (K-lb and K-1f) and from six i
dairy farms (K-3, K-4, K-5, K-6, K-12, and K-19).
The samples m
are gamma scanned and analyzed for gross beta, strontium-89, 4
U and strontium-90 activities.
During the first quarter cattle feed is collected from the same six dairy farms, and the same 4
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 gamma scanned and analyzed for gross alpha, gross beta, j
strontium-89, and strontium-90 activities.
3.1.3 The Aquatic Program j
Surface Water i
One-gallon water samples are taken monthly from three locations on 1-Lake Michigan:
- 1) at the point where the condenser water is dis-charged into Lake Michigan (K-1d); 2) at Two Creeks Park (K-14) located 2.5 miles south of the reactor site; and 3) at the Rostok water intake (K-9) located 11.5 miles north of the reactor site.
Additionally, one-gallon water samples are taken monthly)from three creeks that. pass through the site (K-la, K-lb, and K-le.
Samples from North.and Middle Creeks (K-la, K-lb) are collected near the mouth of each creek.
Samples from the South Creek (K-le) are O
collected about ten feet downstream from the point where the out-v flows from the two drain pipes meet.
Water samples at K-14 are collected and analyzed in duplicate.
5-
O w
The water samples are gama scanned and analyzed for - gross beta activity in the total. residue, dissolv~ed. solids, - and suspended-solids, and potassium-40.
The concentration of potassium-40 is
)
calculated from total potassium, which is determined by flame photometry.
The tritium activity is determined by liquid scin-tillation technique.
Quarterly composites of monthly grab samples j
are also analyzed. for tritium, strontium-89 and strontium-90.
Fish Fish samples are collected in the second, third, and fourth quarters at Location K-Id.
The flesh is separated from the bones, gamma scanned and analyzed for gross beta activity.
Ashed bone samples are ' analyzed for gross beta, strontium-89 and strontium-90 3
activities.
Slime Slime samples are collected during the second and third quarters from three Lake Michigan locations (K-1d, 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 beta activity. If the quantity is sufficient, they are also gamma scanned and analyzed for strontium-89 and strontium-90 activities.
O Bottom Sediments j
i Bottom sediments are collected in May and November from five loca-tions (K-1c, K-1d, K-lj, K-9, and K-14).
The samples are analyzed 4
for gross beta activity 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 sumarized in Table 4.4.
The program was executed as described in the preceding sections.
i 3.1.5 Program Modifications There were no program modifications in 1987.
O
~,
0 3.2 Results and Discussion The results for the reporting period January to December 1987 are-presented in sumary form li. Table 4.5.
For each type of analysis of each sampled medium, this table shows the annual mean and range for all indicator locations and for all control -locations.
The 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 ca tegory, 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 predecessor, Hazleton Environmental Sciences.
The tabulated results of all measurements made in '1987 are not included' in this section, although references to these results will be made in the discussion.
The complete tabulation of the 1987 results is contained in Part II of the 1987 annual report on the Radiological Monitoring Program for the Kewaunee Nuclear Power Plant.
3.2.1 Atmospheric Nuclear Detonations and Nuclear Accidents O
There were no reported atmospheric nuclear tests in 1986.
The last reported test was conducted by the People's Republic of China on October 16, 1980.
The reported yield was in the 200 i
kiloton to 1 megaton range.
There were no reported accidents at nuclear facilities in 1987.
3.2.2 The Air Environment Airborne Particulates In air particulates, the annual gross beta concentration was nearly identical at indicator and control locations (0.020 and l
0.019 pCi/m3, respectively).
Gamma spectroscopic analyses of quarterly composites of air 2
particulate filters yielded similar results for indicator and control locations.
Beryllium-7, which is produced continuourly in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples.
All other gamma-emitting isotopes were below their respective LLO limits during the first, third and fourth quarters.
!O 1
I
O Airborne Iodine Bi-monthly levels of airborne iodine 3 at all-locations.
131 were below the lower.
limit of detection (LLD) of 0.03 pCi/m
- Thus, there is no indication.of an effect of the plant operation on the local air environment.
Ambient Gamma Radiation - TLDs Ambient gamma radiation was monitored by TLDs at twelve locations:
six indicator and six control.
The quarterly TLDs at the indicator locations measured a-mean dose equivalent of (15.8i2.6)* mR/91 days, in agreement. with the mean at the control locations of (15.7i2.7) mR/91 days, and were about the same as the means obtained in 1985 (16.1'and 15.5 mR/91 days, respectively) and in 1986 (16.0 and 14.8 mR/91 days, re-spectively).
All these. values are slightly lower than the United States average value of 19.5 mR/91 days due to natural background radiation (National Council on Radiation Protection and Measure-ments, 1985).
The highest annual mean was 18.6 mR/91 days at indicator location K-17.
O Precipitation Precipitation was monitored only at an indicator location, K-11. The tritium concentration was below the LLO level of 330 pCi/1 in all samples.
3.2.3 The Terrestrial Environment I
Milk Of the 126 analyses for iodine-131 in milk, all were below the LLO level of 0.5 pCi/1.
l Strontium-89 concentration was below the LLO level of 1.7 pCi/l in all samples.
Strontium-90 was found in all samples.
The mean values were identical for indicator and control locations (2.1 pCi/1).
- Unless otherwise indicated, uncertainties of average values are standard Q
deviations of the individual measurements over the period averaged.
Oncer-tainties of individual measurements represent probable counting errors at 1
4 the 95% confidence level.
i 8
'l O
Barium-140 concentration was below the-LLD of'10 pCi/1 in all
~
samples.
Cesium-137 concentration was also below the LLO of 10 pCi/1 in all samples.
Potassium-40 results were nearly. identical at both the indicator l
and control. locations and-were essentially identical to the' i
levels observed in 1978 through 1986s i
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 raios were observed. The i
measured concentrations of stable potassium and calcium are in agreement with previously determined values of 1.5010.21 g/l and 1.16i0.08 g/1, respectively (National Center for Radiological Health,1968).
Well Water O
cross eipne concentretioa ia weii weter was 8elow the ot0 1evei i
of 2.9 pCi/l in all but two samples.
The mean value in two samples was very close to the detection level and averaged 3.2 t
pCi/1.
J Gross beta concentration in well water was 1.0 pCi/l in samples i
1 from the control location.
The mean value for all indicator locations was 2.1 pCi/1 and was nearly identical to the values observed in 1977 through 1986 (3.3, 3.4, 3.0, 3.0, 3.6, 3.2, 2.9, 2.3, 2.6 and 2.5 pCi/1, respectively).
Tritium concentration in the on-site well (K-1g) was below the LLD of 330 pC1/1 in all samples.
All gama-emitting isotopes were below their respective LLDs in i
all samples.
j i
The concentrations of strontium-89 and strontium-90 in well water were below their respective detection limits.
Potassium-40 levels were quite low (under 3.1 pCi/1), in agree-ment with the previously measured values.
1 i
0 i
l 9
i
\\
Domestic Meat i
In - meat (chickens), gross alpha concentration was similar at both indicator and control locations (0.06 and 0.10 pCi/g wet weight, respectively).
Gross beta concentration averaged 2.22 pCi/g wet weight for indicator locations and 3.06 pCi/g wet weight for control locations.
Gama-spectroscopic. analyses showed that most of the beta activity was due to naturally occurring potassium-40.
All' other gama-emitting isotopes were below their respective LLO limits.
El95 In egg samples, gross beta concentration averaged 0.69 pCi/g wet weight, similar to the concentration of the naturally-occurring potassium-40 observed in the samples (1.01 pCi/g).
All other gama-emitting isotopes were below their raspective LLO's.
The level of strontium-89 was below the LLO of 0.007 pCi/g wet weight in all samples.
Strontium-90 was below the LLO level of 0.010 pCi/g wet weight in all samples.
Vegetables In vegetables, gross beta concentration was about the same at the v
indicator location (2.36 pCi/g wet weight) as at the control location (2.34 pCi/g wet weight) and was due primarily to the potassium-40 activity (2.04 pCi/g wet weight). Strontium-89 was below the LLO level of 0.034 pCi/g wet weight in all samples.
a i
Strontium-90 activity -was detected in one indicator sample (0.069 i
)
pCi/g wet weight) and two control samples (average 0.021 pCi/g wet j
weight).
All other gama-emitting isatapes were below their re-spective LLO 1691<
j
\\
The samples of oats and clover were of similar coxMtion but the i
concentration of radionuclides was sliohtly blo6-due to the lower j
water content of the grain in comparlsr. with the vegatables.
I i
Grass and Cattle Feed In grass, gross beta concentration was similar at both indicator 4
and control locat.ons (U4 and 7.61 pCi/g wet weight, respectively) and in both cases was predominantly due to naturally occurring potassium-40 and beryli tum-7.
All other gama-emitting isotopes i
were below their respe tive LLO's.
Strontium-89 was below the LLO j
of 0.035 pCi/g wet weight in all samples. Strontium-90 activity was detected in two samples and averaged 0.030 pCi/g wet weight.
The presence of radiostrontium in grass samples is attributed to the l
fallout from the previous nuclear tests.
10 1
O For cattlefeed, the mean gross beta concentration was slightly higher at control locations (9.4 pCi/g wet weight) than at indicator locations (7.2 pCi/g wet weight).
The highest gross beta level was in the sample from the control location K-6 (15.1 pCi/g wet weight),
and reflected the high potassium-40 level (12.7 pCi/g wet weight) observed in the sample.
The pattern was similar to that observed in 1978 through 1986.
Strontium-89 levels were below the LLO level of 0.02 pCi/g wet weight in all samples.
Strontium-90 activity was lower at control locations than at indicator locations (0.023 and 0.033 pCi/g wet weight, respectively).
The presence of the radio-strontium is attributable to the fallout from the previous nuclear tests.
All other gamma-emitting isotopes were below their respective LLO levels.
Soil No significant differences were found between indicator (4.8 pCi/g dry weight) and control (5.0 pCi/g dry weight) values in soil samples. The difference of 0.2 pCi/g dry weight in mean gross alpha concentration 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 p
locations (15.3 and 19.9 pC1/g dry weight, respectively), and is y
primarily due to the potassium-40 activity.
Strontium-89 was below the LLD level of 0.024 pCi/g dry weight in all samples. Strontium-90 was detected in eight of fourteen samples and was higher at control than at indicator locations (0.172 and 0.085 pCi/g dry weight, respectively).
Cesium-137 was detected in all samples and was higher at control locations than at indicator locations (0.47 and 0.26 pCi/g dry weight, respectively).
Berillium-7 was detected in one sample (1.02 pCi/g dry weight).
Potassium-40 was detected in all samples and averaged 13.51 am 17.20 pCi/g dry weight at indicator and control locations, respM1vely.
All other gama-emitting isotopes were below their respective LLO 3.
The levels of detected activities were similar to those observed in 1979 through 1985.
4 3.2.4 The Aquatic Environment Surface Water In surface water, mean gross beta activity in suspended solids was below the LLO level of 0.8 pCi/1 in all samples.
Mean gross beta concentration in dissolved solids was higher by a factor of two at indicato. locations (5.3 pCi/1) as compared to the control locations (2.5 pC1/1) 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
- O 2 7 ac'./1) 1981 (4 3 a",d 2 7 aci/i>
1982 (4 9 ead 2 4 ac'/1).1984 (5.0 and 2.7 pCi/1),
1983 (51 and 2.6 pCi/1) 2 11
L 2.5 pCi/1) and in 1986 (4.1 and 2.5 pCi/1).
The control ' sample is
~
Lake Michigan water which varies very little in concentration during the year, while indicator samples include two creek locations (K-1c and K-le) which are much higher in concentrations and exhibit large month-to-month variations in gross beta concentration. The K-la creek draws its water from the sui rounding fields which are heavily fertilized and the K-le creek draws its water mainly from the Sewage Treatment Pond No.1.
In general, grost, beta concentration levels were high when potassium-40 levels were high and low when potassium-40 levels.were low, indicating that the fluctuations in beta concentration were due to variations in potassium-40 concen-trations and not to ~ plant operations.
The fact that similar fluctuations at these locations were observed in the pre-operational studies conducted prior to 1974 supports this assessment.
i Tritium concentration was below the LLD level of 300 pCi/1 in all samples.
Stro Jium-89 concentration was below the LLD of 1.6 pCi/1 in all samples.
Strontium-90 concentration was below the LLD level of 0.9 t
pC1/1 in all samples.
All gamma-emitting isotopes were below their respective LLDs in all samples.
=
Fish In fish samples, the gross beta concentration averaged 3.1 pCi/g wet weight in muscles and 0.6 pCi/g wet weight in bone fractions.
In muscle, the gross beta concentration was primarily due to po tassium-40 activity.
The average beta concentration of 1.85 pC1/g wet weight was near the average of the 1973 range of 2.26 to 3.62 pCi/g wet weight. The cesium-137 concentration in muscle averaged 0.11 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)'0.14 pC1/g wet weight),
1981 (0.15 pCi/g wet weight), 1982 (0.17 pCi/g wet weight),
1983 (
1984 (0.10 pCi/g wet weight),1985 I
(0.11 pCi/g wet weight) and 1986 (0.11 pCi/g wet weight).
The strontium-89 concentrations were below the LLD of 0.09 pCi/g wet weight in all samples.
Strontium-90 was detected in all samples
~
and averaged 0.10 pCi/g wet weight.
j Periphyton (Slime)
In periphyton (slime) samples, mean gross beta cone.entration was higher at indicator than at control locations (4.0 and 2.0 pCi/g wet weight, rcipec tively).
Strontium 89 concentration was below the LLO level of 0.055 pCi/g wet weight in all samples. Strontium-90 concentrations were similar at indicator and control locations, O
12 4
_~.
I i
O averaging 0.039 and 0.027 pC1/g wet weight,:respectively.
A trace quantity of Co-58 (mean 0.047 pCi/g wet. weight) was detected in two samples at Locations K-id and - K-le and trace quantity of Co-60 (0.062 pCi/g wet weight) were detected in one sample collected ~at indicator-Location _K-le.
Cs-137 was detected in one sample, at -
control-Location K-9 (0.044 pCi/g wet weight). - All other ganna--
emitting isotopes, ex 'nt naturally-occurring beryllium-7 and potassium-40, were below Nir respective LLDs.
Bottom Sediments In bottom sediment samples, the mean ' gross-beta concentration was lower at indicator locations than at the control location (7.8 and
+
9.5 pCi/g' dry weight, respectively) and_ was due mostly to potassium-
- 40. The difference is not statistically significant.
Cesium-137 was detected in six of ten samples and averaged 0.038 pCi/g dry weight at indicator locations and was below the LLD level of 0.029 pCi/g dry weight at control locations.
Cs-134 was below the LLD level at 0.019 pCi/g dry weight in all samples. The cesium-137 level was slightly lower than the levels obser#ed in 1979 0.12
~
pCi/g dry weight, in 1980 (0.19 pCi/g dry weighD, in 1981 0.18 1
pCi/g dry weight, in 1987 (0.13 pCi/g dry weight), in 1983 0.16 O
pCi/g dry weight, in 1984 (0.07 pCi/g dry weight), in 1985 0.05 i
4 pCi/g dry weight), and in 1986(0.037 pCi/gdryweight). Strontium-89 and strontium-90 levels were below their respective LLDs-(0.030 i
and 0.023 pCi/g dry weight, respectively) in all ~ samples.
Trace amounts of Co-58 (two samples. 0.089 pCi/g dry weight) and Co-60 (one sample 0.065 pCi/g dry weight) were detected near the con-denser discharge.
The presence of trace amounts of these i
activation products in bottom sediments is probably plant related.
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44 Kewaunee f
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K-3 Green Eey (K-16)
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- 25 Miles I. A NE K-24 E 1
(K-28) q
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,$K-4. ',a sie.se.Nilte
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Q K-21 o
K-ew W-207 O
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y K 27 F' f-TW K-17 b"
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) Kewcunee Co.
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/
Tisch Milk.\\g\\
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2 3
4 Figure 4-1.
Sampling locations, Kewaunee Nuclear Power Plant.
l 15
O Tab b 4.1.
Sampling locations, Kewaunee Nuclear Power Plant.
Distance (miles)b and 4
a Sector Location Code Type K-1 Onsite 1
la I
0.62 N North Creek lb I
0.12 N Middle Creek Ic I
0.10 N 500' north of condenser discharge i
ld I
0.10 E Condenser discharge le I
0.12 S South Creek If 1
0.12 S 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 J
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 Pap 1 ham Farm, Route 1, Kewaunee 4
K-6 C
6.7 WSW Novitsky Farm K-7 I
2.75 SSW Earl Bruemmer Farm, Route 3. Two Rivers 5
K-8 C
5.0 WSW Saint Mary's Church, Tisch Mills K-9 C
11.5 NNE Rostok Water Intake for Green Bay, Wisconsin two miles north of Kewaunee K-10 1
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 l
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 I
2.5 N Carl Struck Farm, Route 1, Kewaunee K-23 I
0.5 W 0.5 miles west of plant, Kewaunee Site r
K-24 C
5.45 N Fectum Farm, Route 1, Kewaunee i
K-25 1
2.75 WSW Wotachek Farm, Route 1, Denmark K-26c 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-11 K-28 C
26 NW Hansen Dairy, Green Bay, Wisconsin I = indicator; C = control b
i O
Distances are measured from reactor stack.
V c Location K-18 was changed because Schmidt's Food Stand went out of business and was replaced by Bertler's Fruit Stand (K-26).
16
T h 4.2.
Type and frequency of collection.
Frequency Location Weekly Biweekly Monthly Quarterly Semiannually Annually K-la SW SL K-lb SW GRa SL K-Ic BSb K-Id SW FIa BSb SL K-le SW SL K-lf AP AI GRa TLD S0 TLD K-lg WW K-lh WW K-lj BSb K-2 AP AI TLD TLD K-3 MIc GR3 TLD CFd SO TLD K-4 MIc GRa TLD CFd S0 TLD K-5 MIc GRa TLD CFd 50 TLD K-6 MIc GRa TLD CFd S0 TLD K-7 AP AI TLD TLD K-8 AP AI TLD TLD K-9 SW BSb SL K-10 WW
~"
K-Il PR WW K-12 MIC GRa CFd WW SO K-13 WW K-14 SW BSb SL K-15 AP AI TLD TLD K-16 AP AI TLD TLD K-17 TLD TLD 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 TLD EG TLD DM K-28 MIc a Three times a year, second ( April, May, June), third (July, August, September), and fourth (October, N vember December) quarters.
b To be collected in May and November.
c Monthly from November through April; semimonthly from May through October.
d First (January February, March e Replaced by K-6 in summer of 18guarter only.
]
Table 4.3.
Sample codes used in Table 4.2.
Code Description AP Airborne Particulate AI Airborne Iodine TLD Thermoluminescent 00simeter PR Precipitation MI Milk WW Well Water DM Domestic Meat i
EG Eggs 4
VE Vegetables g-)s
(_
l 4
GRN Grain GR Grass CF Cattlefeed S0 Soil SW Surface Water FI Fish SL Slime BS Bottom Sediments i
O
~18
O V
Table 4.4.
Sampling sumary, January - December 1987.
Collec tion Number of Number of Sample Type and Number of Samples Samples Type Frequencya locations Collected Missed Air Environment Airborne particulates C/W 6
305 7
Airborne iodine C/BW 6
149 7
TLD's C/Q 12 48 0
Precipitation C/M 1
12 0
Terrestrial Environment Milk (May-0ct)
G/SM 7
84 0
(Nov-Apr)
G/M 7
42 0
Well water G/Q 6
24 0
Domestic meat G/A 4
4 0
Eggs G/Q 1
4 0
Os Vegetables - 5 varieties G/A 2
7 0
Grain - oats G/A 1
1 0
- clover G/A 1
1 0
Grass G/TA 8
24 0
Cattle Feed G/A 6
8 0
Soil G/SA 7
14 0
Aquatic Environment Surface water G/M 7
84 0
Fish G/TA 1
4 0
Slime G/SA 6
12 0
Bottom sediments G/SA 5
10 0
a Type of collection is coded as follows: C = continuous; G = grab.
Frequency is coded as follows: W = weekly; SM = semimonthly; M = monthly; Q = quarterly; SA = semi-annually; TA = three times per year; FA = four times per year; A = annually; BW = bi-weekly.
O 19
Y(~%
%J rJ Table 4.5 Environmental Radiologit 1 Monitoring Program Sussary.
Name of facility Kewaunce Nuclear Power Plant Docket No.
50-305 Location of Facility Kewaunee County, Wisconsin Reporta.g Period January - December 1987 (County, State) l Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F)
Mean (F)
Non-routine (Units)
Analysesa Ltob RangeC Locationd Range Range Resultse Airborne G8 305 0.005 0.020 (101/101)
K-li, Meteorological 0.020 (50/51) 0.019 (193/204)
O part ic yla tes (0.004-0.039)
Tower, On Site (0.008-0.039)
(0.003-0.040)
(pC4/m )
0.12 mi 5 3
K-2, WPS Op. Building 0.020 (50/50) 9.5 mi NNE (0.007-0.031)
GS 24 Be-7 0.022 0.059 (8/8)
K-2, WPS Op. Bu11 ding 0.074 (4/4) 0.065 (16/16) 0 (0.034-0.031) 9.5 mi NNE (0.066-0.081)
(0.041-0.131)
Nb-95 0.0029
<LLD (LLD 0
Zr-95 0.0042
<LLD
<tLD 0
Ra-103 0.0025
<LLD
<tLD 0
Ru-106 0.016 (LLD
<LLO O
Cs-134 0.0016
<tLD
<LLD 0
<tLD 0
Ce-141 0.0033
<LLD
<tLD 0
Ce-144 0.0079
<LLD
<LLO O
Airborne 1-131 149 0.03
<tLD
<tLD 0
todine (pC1/m3)
TLD -Quarterly Gamma 48 1
15.8 (24/24)
K-3, Stangel Farm 18.1 (4/4) 15.7 (24/24) 0 (mR/91 days)
(10.8-19.4) 3.0 mi N (13.9-21.4)
(11.2-21.4) 0
V u/
v Table 4.5 Environmental Radiological Monitoring Program Summary (continued)
Name of Facility Kewaunee Nuclear Power Plant Docket No.
50-305 Location of factitty Kewaunee County, Wisconsin Reporting Period January - Decenber 1987 (County. State)
Indic a tor Location with Highest Control Sample Type and Locations Annual Mean Locations Nunber cf Type Nunber of Mean (F)C Mean U )
Mean (F)
Non-rout ine C
Loc a t tor.d Range Range Result 1 8
LL0b Range (Units)
Analyses Precipitation H-3 12 330
<LLD None 0
(pC1/1)
Milk I-131 126 0.5
<tLD (LLD 0
Sr-89 84 1.7 (LLD
<LLD 0
Sr-90 84 0.5 2.1 (48/48)
K-12. Lecaptain Farm 2.6 (12/12) 2.1 (36/36) 0 (1.0-3.6) 1.5 at WSW (1.4-3.6)
(1.2-3.0)
G5 126 K-40 50 1350 (72/12)
K-3. Stangel Farm 1440 (18/18) 1340 (54/54) 0 (1150-1560) 3.0 ri N (1300-1640)
(1040-1640)
Cs-134 10
<LLD
<tLD 0
ro Cs-137 10
<LLD
<tLD 0
Ba-La-140 15
<LLD
<tLD 0
(g/1)
K-stable 84 1.0 1.53 (48/48)
K-3 Stangel Farm 1.65(12/12) 1.53(36/36) 0 (1.36-1.75) 3.0 mi N (1.48-1.86)
(1.23-1.78)
(g/1)
Ca 84 0.5 0.86 (48/48)
K-6. Novitsky farm 0.96 (12/12) 0.90 (36/36) 0 (0.63-1.17) 6.7 at WSW (0.84-1.06)
(0.62-1.11)
Well Water GA 8
2.9 3.2 (2/8)
K-lh, North Well 3.3 (1/4)
None Q
(pct /I)
(3.1-3.3)
Onsite, 0.12 mi NW G8 24 1.7 2.1 (14/20)
K-lh. North Well 2.7 (3/4) 1.0 (4/4) 0 (0.8-3.4)
Onsite, 0.12 al NW (2.1-3.4)
(0.8-1.1)
H-3 4
330
<tLD None 0
K-40 24 0.10 2.06 (20/20)
K-Ig. South Well 2.85 (4/4) 1.45 (4/4) 0 (flame)
(1.06-3.10)
Onsite, 0.06 at W (2.67-2.98)
(1.36-1.51)
Sr-89 4
1.6 (LLO None 0
Sr-90 4
1.0 (LLD None 0
(V f)
(~)
3 V
t,,/
Table 4.5 Environmental Radiological Moritoring Program Sununary (continued)
Name of Facility Kewaunee Nuclear Power Plant Docket No.
50-305 Location of fac11 Tty Kewaunee County, Wisconsin Reporting Period January - December 198I (County, State)
Ind 'c ator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)C Mean (F)
Mean (F)
Non-routine C
Locationd Range Range Results' (Units)
Analyses 8 LLDb Range Well Water G5 24 (pCi/1)
<LLD 0
(continued)
Ph-54 15
<tLD Fe-59 30
<tLD
<tLD 0
Co-58 15
<LLD
<LLD 0
Co-60 15
<tLD
<LLD 0
2r-Nb-95 15
<LLD
<LLD 0
Cs-134 10
<tLD
<LLD 0
Cs-137 10
<tLD (LLD 0
y Ba-La-140 15
<tLD
<LLD 0
Domestic Meat GA 4
0.04 0.06 (3/3)
K-24, Fectum fara 0.10 (1/1) 0.10 (1/1) 0 (chickens)
(0.05-0.07) 5.45 mi N (pC1/g wet)
G8 4
0.03 2.22 (3/3)
K-24, rectum Fara 3.06 (1/1) 3.06 (1/1) 0 (1.82-2.64) 5.45 mi N GS 4
Be-7 0.18
<LLD (LLD 0
K-40 0.5 2.34 (3/3)
K-20, Struck Farm 2.88 (1/1) 2.75 (1/1) 0 (1.76-2.88) 2.5 ml N Nb-95 0.029
<LLD (LLD 0
2r-95 0.047
<tLD
<LLD 0
Ru-103 0.023
<tLD
<LLD 0
Hu-106 G.095
<LLD
<tLD 0
Cs-134 0.023
<LL D
<LLD 0
Cs-131 0.025
<LLD
<LLD 0
Ce-141 0.042
<LLD (LLD 0
Ce-144 0.16
<tLD
<LL D 0
/
Q
/ ~N N]'
%)
)
Table 4.5 Environmental Radiological Monitoring Program Surnary (continued)
Name of Factitty Kewaunee Nuclear Power Plant Docket No.
50-305 Location of Facility.
Kewaunee County, Wisconsin Reporting Period January - December 1987 (County, State)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations turber of Type Number of Mean (F)c Mean (F)
Mean (F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Resultse E995 GB 4
0.01 0.69 (4/4)
K-21, Schlies Farm 0.69 (4/4)
None 0
(pCf/g wet)
(0.13-1.18) 1.5 mi NW (0.13-1.18)
Sr-89 4
0.007 (LLO None 0
Sr-90 4
0.010
<LLD None O
G5 4
Be-7 0.058 (LLD None 0
K-40 0.01 1.01 (4/4)
K-27, Sch11es Farm 1.01 (4/4)
None 0
(0.88-1.20) 1.5 ml NW (0.88-1.20)
Nb-95 0.0082
<LL D None 0
Zr-95 0.015
<llD None O
Ru-103 0.0073
<LLD None O
Ru-106 0.065
<LLO None O
Cs-134 0.0070
<LLD None O
Cc-141 0.0094
<tLD None O
Cc-144 0.040
<tLD None O
Vegetables GB 7
0.1 2.36 (2/2)
V-17, Jansky rare 2.36 (2/2) 2.34 (5/5) 0 (pC1/g wet)
(1.15-3.56) 4.25 at W G 15-3.56)
(1.41-3.06)
Sr-89 7
0.034 (LLD
<tLD 0
Sr-90 7
0.0020 0.069 (1/2)
K-17, Jansky Fare 0.069 (1/2) 0.0021 (2/5) 0 4.25 ml W (0.0010-0.0032)
m V
V C
Table 4.5 Errstronmental Rtdiological Monitoring Program Sumary (continued)
Name of f acility Kewaunee Nuclear Power Plant Docket No.
50-305 Location of Facility Kewaunee County, Wisconsin Reporting Period January - December 1967 (County, State) l Indicator Location with Highest Control 8
Locations Annual Mean Locations Number of Sample Type and Type Number of Mean(F)C Mean (F)
Mean (F)
Non-routine a
LLDb Range 0 Locationd Range Range Resultse (Units)
Analyses Vegetables GS 7
(pCl/g wet)
(continued)
Be-7 0.14 (LLD
<LLD 0
K-40 0.75 2.22 (2/2)
K-17 Jansky Farm 2.22 (2/2) 1.97 (5/5) 0 (1.95-2.49) 4.25 mi W (1.95-2.49)
(1.25-3.39)
Nb-95 0.018
<tLD
<LLD 0
Zr-95 0.035
<LLD
<LLD 0
Ru-103 0.016
<tLD
<LLD 0
Ru-106 0.13
<tLD
<tLD 0
<tLD 0
Cc-141 0.017 (LLD
<tLD 0
Ce-144 0.068
<LLD
<tLD 0
Grain - Oats.
GB 2
0.1 5.61 (2/2)
K-23. Kewaunee Site 5.61 (2/2)
None O
Clover (4.23-6.99) 0.5 at W (4.23-6.99)
Sr-89 2
0.010 (LLD None 0
Sr-90 2
0.002 0.016 (2/2)
K-23, Kewaunee Site 0.016(2/2)
None 0
(0.012-0.020) 0.5 at W (0.012-0.020)
G5 2
Be-7 0.2 0.90 (2/2)
K-23 Kewaunee Site 0.90 (2/2)
None 0
(0.72-1.09) 0.5 mi W (0.72-1.09)
K-40 0.1 4.60 (2/2)
K-23. Kewaunee Site 4.60 (2/2) kne 0
(4.16-5.04) 0.5 at W (4.16-5.04)
Nb-95 0.0094
<LLO None 0
ir-95 0.016
<LLD None O
Ru-103 0.0093
<LLO None O
Ru-106 0.086
<tLD None O
Cs-137 0.0098
<LLD None O
Ce-141 0.017
<LLD None O
Ce-144 0.072 (LLD None 0
N N
-w Table 4.5 Environmental Radiological Monitoring Program Summary (continued)
Name of facility Kewaunee Nuclear Power Plant Docket No.
50-305 Location of Fact!ity _ Kewaunee County. Wisconsin Reporting Period January - Deccaber 1987 (County. 5 Late)
Indicator location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean(F)C Mean (F)
Mean (F)
Non-mut ine (Units)
Analysesa LLDb RangeC Locationd Range Range Results*
Cattlefeed GB 8
0.1 7.2 (4/4)
K-6, Novitsky Farm 15.1(1/1) 9.4 (4/4) 0 (pCl/g wet)
(3.6-11.3) 6.7 at W$w (3.3-15.1)
Sr-89 8
0.02
<tLD
<LLO O
Sr-90 8
0.008 0.033(3/4)
K-4. Stangel Fara 0.07 (1/1) 0.023 (3/4) 0 (0.01-0.07) 3.0 mi N (0.01-0.04)
G5 8
Be-7 0.20 0.56 (3/4)
K-4. Stangel Fara 0.73 (1/1) 0.46 (3/4) 0 (0.43-0.73) 3.0 ml N (0.37-0.61)
K-40 1.0 5.80 (5/5)
K-6, Novitsky Fars 12.70 (1/1) 7.92 (4/4) 0 (2.66-9.50) 6.7 at WSW (2.31-12.70)
Nb-95 0.035
<tLD
<LLD 0
g Zr-95 0.060 (LLD
<tLD 0
Ru-103 0.039
<tLD
<tLD 0
Ru-106 0.26
<tLD (LLO O
Cs-134 0.030
<tLD
<LLD 0
Cs 137 0.034 (LLD
<tLD 0
Cc-141 0.056
<tLD
<tLD 0
Cc-144 0.23
<tLD
<LLD 0
Grass GB 24 0.1 6.74 (18/18)
K-6. Novitsky Farm 7.61 (3/3) 7.57 (6/6) 0
!(pCi/gwet)
(3.89-10.63) 6.7 at WSW (6.58-9.45)
(4.55-9.45)
Sr-89 24 0.035
<LLD (LLD 0
Sr-90 24 0.020 0.030 (2/18)
K-12. Lecaptain Farm 0.040(1/3)
<tLD 0
(0.020-0.040) 3.5 mi WSW G5 24 Be-1 0.40 2.07(18/18)
K-19. Paral Fara 2.69 (3/3) 1.31 (6/6) 0 (0.46-5.58) 1.75 mi NNE (0.48-5.58)
(0.38-2.69)
K-40 0.1 6.0?(18/18)
K-5. Paplham Farm 6.96 (3/3) 6.49 (6/6) 0 (4.01-7.27) 3.5 al NNW (6.56-7.27)
(5.36-7.84)
Nb-95 0.030
<LLD
<tLD 0
s
1 rs q
U J
o i
Table 4.5 Invironmental Radiological Monitoring Program Sumary (continued)
Name of Facility Kewaunee Nuclear Power Plant Docket No.
50-305 Location of Fact 1 Tty Kewaunee Count. Wisconsin Reporting Pe Wod JanWry - December 1987 (Coun fate) l Indicator location with Highest Control Sample Type and i Locations Annual Mean Locations Nunber of l
Type Number of 844n (F)C Mean (F)
Mean (F)
Non-rout ine (Units)
Analv'esa LL0b gang,c locationd Range Range Results' Grass Ir-95 0.051 (LLD
<LLD 0
(pCl/g wet)
<LLD 0
(continued)
Re-103 0.055
<tLD i
l Ru-l%
0.23
<tLD
<LLD 0
Cs-134 1 0.928 (LLD
<LLO O
<tLD 0
ro Ce-141 0.049 (LLD
<tLD 0
cn Cc-144 0.18
<LLD
<LLD 0
Soll GA 14 2.2 4.8 (7/10)
K-6. Novitsky Farm 5.2(2/2) 5.0 (4/4) 0 (pC1/g dry)
(2.5-7.8) 6.7 mi WSW (4.3-6.2)
(3.6-6.2) j G8 14 2.0 15.3 (10/10)
K-3. Stangel Fars 21.8 (2/2) 19.9 (4/4) 0 (4.4-22.3) 3.0 mi N (18.8-24.8)
(13.6-24.8)
- Sr 14 0.024
<tLD
<LLD 0
iiSr-90 14 0.015 0.085 (8/10)
K-6. Invitsky Farm 0.156 (2/2) 0.102 (4/4) 0 l
(0.035-0.110) 6.7 al W5W (0.14-0.17)
(0.059-0.172; G5 14 lBe7 1.5 mi W5W 0.42 1.02 (1/10)
K-12. Lecaptain Farm 1.02(1/2)
<LLD 0
l K-40 1.4 13.51 (10/10)
K-3. Stangel Farm 18.42 (2/2) 17.20 (4/4) 0 (8.02-18.40) 3.0 mi N (17.30-19.54)
(15.70-15.54:
} Nb-95 0.053
<tLD
<tLD 0
lZr-95 0.10
<LLD
<LLD 0
I Ru-103 0.065
<LLD "LLD 0
Ru-106 0.41
<tLD
<LLD 0
l
O O
O l
Table 4.5 Envirofonental Radiological Monitoring Program Sununary (continued)
Name of Factitty Kewaunee Nuclear Power Plant Docket No.
50-305 Location of facility Kewaunee County, Wisconsin Reporting Period January - December 1987 (County State) l l
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)C Mean (F)
Mean (F)
Non-routine (Units)
Analysesa LLDb RangeC Locationd Range Range Resultse l
Soll Cs-131 0.01 0.26 (10/10)
K-6, Novitsky Fara 0.68 (2/2) 0.47 (4/4) 0 (pCl/g dry)
(0.025-0.63) 6.7 at WSW (0.62-0.75)
(0.20-0.75)
(continued) l Cc-141 0.089 (LLD
<LLD 0
Ce-144 0.23 (LLD
<tLD 0
Surf ace Water G8(55) 84 0.8
<tLD
<tLD 0
l GB(DS) 84 1.0 5.3 (72/72)
K-la, North Creek, 11.0 (12/12) 2.5 (12/12) 0 (1.6-26.9)
@ site, 0.62 mt N (6.3-26.9)
(1.9-3.8)
G8(TR) 84 4.0 5.3 (71/72)
K-la, North Creek.
11.0 (12/12) 2.5(12/12) 0 (1.6-26.9)
Onsite, 0.62 al N (6.3-26.9)
(1.9-3.8)
GS 84 Mn-54 15
<tLD
<tLD 0
y Fe-59 30
<tLD (LLD 0
Co-58 15
<tLD
<LLD 0
Co-60 15
<tLD
<LLD 0
Zr-Nb-95 15 (LLD
<LLD 0
Cs-134 10
<tLD
<LLD 0
Cs-137 10
<LLD
<LLD 0
Ba-La-140 15 (LLD
<tLD 0
<LLD 0
K-40 84 0.5 4.67 (72/72)
K-14 North Creek 9.56 (12/12) 1.67 (12/12) 0 (flame)
(1.41-24.6)
Onsite. 0.62 at N (4.58-24.6)
(1.36-2.39) 1 1
1 I
I O
O O
l Table 4.5 Env tronmental Radiological Monitoring Program Suramary (continued)
Name of Factilty Kewaunee Nuclear Power Plant Docket No.
50-305 Location of fac titty Kewaunee County, Wisconsin heporting Period January - December 1987 l
(County, State) l Ind icator Location with Highest Control l
l Sample Type and
- Locat ions Annual Mean Locations
! h aber of I
Mean (F)C Mean (F)
Mean (F) lNon-routine Type Number of t
l (Units)
Analysesa ttob RangeC Locationd Range Range Resultse 1
Fish - Muscle GB 4
1.0 3.1 (4/4)
K-Id, Condenser 3.1 (4/4)
None 0
(pCl/g wet)
(2.3-3.5) 1 Discharge Onsite (2.3-3.5) l 0.10 mi E G5 4
Fe-59 0.088
<tLD None j
O Co-58 0.023 (LLD None O
Co-60 0.011
<LLO None 0
i Cs-134 0.010
<LtD None l
0 ru Cs-137 0.027 0.11 (4/4)
K-Id Condenser Dis-0.11 (4/4)
None 0
(0.059-0.16) charge. Onsite (0.059-0.16) 0.10 mi E Fish - Bones (pct /g wet)
G8 5
0.1 0.6 (4/4)
K-Id Condenser Dis-0.6 (4/4)
None 0
(0.11-0.9) charge. Onsite (0.11-0.9) 0.10 at E Sr-89 5
0.09
<LLD None 0
Sr-90 5
0.02 0.10 (4/4)
K-Id Condenser Dis-0.10 (4/4)
None 2
0 (0.026-0.245) charge Onsite (0.026-0.245) j 0.10 ml E Periphyton GB 12 0.1 4.0 (10/10)
K-14. Two Creeks 5.6 (2/2) 2.0 (2/2) 0 (51tme)
(1.4-8.5)
Park, 2.5 al 5 (2.6-8.5)
(1.4-2.5)
Sr-89 12 0.055
<tLD
<tLD 0
Sr-90 12 0.007 0.039 (7/10)
K-le, South Creek 0.130 (1/2) 0.027 (1/2) 0 (0.007-0.130)
Onsite, 0.12 al 5 (0.008-0.045)
~.
. _. _. ~..
m
.___s_
m.
O O
O Tab:S 4.5 Environmental Radiological Monitoring Program Sunusary (continued)
Name of Factitty Kewaunce Nuclear Power Plant Docket No.
50-305 location of Facility Kewaunee County, Wiwonsin Reporting PeTod January - Dectober 17F (County State)
Ind icator Location with Highest Control Sample Type and Locations Annual Mean Locations Nweber of Type Number of Mean (F C Mean (FF Mean (F)
Non-routine (Units)
Analyses
- LLDb Rang.
Locationd Range Range Results' Periphyton G5 12 (Slime)
(pct /g wet)
Be-7 0.063 0.52 (9/10)
K-9. Rostok Water 0.83 (2/2) 0.83 (2/2) 0 (continued)
(0.27 1.05)
Intake 11.5 mi NNE (0.76-0.90)
(0.76-0.90)
K-40 0.67 1.60 (9/10)
K-lb Middle Creek 2.11 (2/2) 1.45 (2/2) 0 (0.67-2.86) m stte 0.12 mi N (1.37-2.86)
(0.60-2.30)
Co-58 0.040 0.047 (2/10)
K-Id. Condenser Dis-0.047 (1/2)
<tLD 0
(0.046-0.047) charge Onsite. 0.10 E Co-60 0.042 0.062 (1/10)
K-le. South Creek O.062 (1/2)
(LLD 0
Onsite, 0.12 at 5 Nb-95 0.038
<tLD
<LLO O
Zr-95 0.069
<tLD
<tLD 0
Ru-106 0.32
<tLD
<LLD 0
Cs-134 0.032 (LLD
<LLD 0
Cs-137 0.038
<tLD K-9. Mostok Water 0.044(1/2) 0.044 (1/2) 0 Intake. 11.5 al NNE Ce-141 0.041
<tLD (LLD 0
Ce-144 0.17 (LLD
<tLO O
mm _. _ _.. _.
%)
q)
Table 4.5 Environmental Radiolog6 cal Monitoring Program Sumary (continued) kame of Facility Kewaunee Nuclear Power Plant Docket No.
50-305 Location of fact 1 Tty kewaunce County, W6sconsin Reporting Period January - December 1967~
[Co3ty, State)
Ind icator Location with Highest Control Sample Type and Locations Annual Mean Locations Nuncer of Type number of Mean (F)C W an (F)
Mean (F) mon-routine (Units)
Analyseia LLDb RangeC Locationd Range Range Results' Bottom G8 10 1.0 7.8 (8/8)
K-14, Two Creeks 12.2(2/2) 9.5 (2/2) 0 5ediments (3.0-15.1)
Park, 2.5 al 5 (9.2-15.1)
(8.8-10.2)
(pCl/g dry)
Sr-89 10 0.030
<LLD
<tLD 0
<LLD o
Sr-90 10 0.023 (LLD GS 10 K-40 1.0 5.59 (8/8)
K-Ic, 500* N of Con-7.28 (2/2) 5.30(2/2) 0 (3.62 7.34) denser Discharge (7.23-7.34)
(4.52-6.09) 0.10 at N Co-58 0.028 0.089 (2/8)
K-lj, 500* 5 of Cen-0.091 (1/2)
<tLD 0
(0.0R7-0.091) denser Discharge, g
Onsite, 0.10 et S o
Co-60 0.035 0.065 (1/8)
K-Id. Condenser Dis-0.065 (1/2)
<tLD 0
charge. 0.10 ml E.
Cs-134 0.019
<tLD
<LLD 0
Cs-137 0.029 0.038 (6/8)
K-Ic, 500* N of Con-0.043 (1/2j
<tLD 0
(0.022-0.049) denser Discharge.
Onstte, 0.10 mi N 8 GA = gross alpha, G8 = gross beta, GS = gama spectroscopy, 55 = suspended solids. DS = dissolved solids TR = total residue, b LLD = nominal lowar limit of detection based on 3 sigma counting error for background sample.
c Mean based upon detectable measurements only. Traction of detectable measurements at specified locations is indicated in parentheses (F),
d Locations are specified by station code (Table 4.1), distance (miles) and direction relative to reactor site.
e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten times the pre-operational value for the location.
.~ -
O
5.0 REFERENCES
Arnold, J. R. and H. A. Al-Salih.
1955.
Beryllium-7 Produced by Cosmic Rays, Science 121: 451-453.
l Eisenbud, M.
1963.
Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, and 276.
a l
- Gold, S.,
H. W. Barkhau, B. Shlein, and B. Kahn, 1964.
Measurement of
[
[
Naturally Occurring Radionuclides in Air, in the Natural. Radiation q
Environment. University of Chicago Press, Chicago, Illinois, 369-382.
Hazleton Environmental Sciences,1979.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part !!, Data Tabulations and Analysis, January - December 1978.
3 1980.
Annual Report.
Radiological - Monitoring Program for the f
O xewaunee Nucieer eower eiant, xewaenee, Wisconsin, rinai ae m et - eart u,
Data Tabulations and Analysis, January - December 1979.
4 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, i
1982.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, l
Data Tabulations and Analysis, January - December 1981.
l 1983.
Annual Report.
Radiological Monitoring Program for the
[
j Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, j
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.
j 1975.
Semi-annual Report.
Radiological Monitoring Program for j
the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin.
January - June, j
1975.
I i
NALC0 Environmental Sciences.
1977.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin,
(
O aenuery - oece eer 1976.
i i
31 4
3
5.0 REFERENCES
Arnold, J. R. and H. A. Al-Salih.
1955.
Bery111um-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 Plant, Kewaunee, Wisconsin, Final Report - Part !!, Data Tabulations and Anal; sis, January - December 1978.
r]
1980.
Annual Report.
Radiological Monitoring Program for the (j
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 - Part II, Data Tabulations and Analysis, January - December 1981.
1983.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, Data Tabulations and Analysis, January - December 1982.
Industrial BIO-TEST Laboratories, Inc. 1974.
Annual Report. Pre-operational Radiological Monitoring Program for the Kewaunee huclear 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 Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, O
aenvers - oecember 1978.
31
l O
I 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.
j i
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 i'
-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. Sc ience.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.
t 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.
1986.
Annual Report.
Radiological Monitoring Program for the f
Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II.
O oeta tabuietioas aad ^aaissis. Jaauery - oece der 198s.
i 1987.
Annual Report.
Radiological Monitoring Program for the l
Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part II, i
Data Tabulations and Analysis, January - December 1986.
i 1988.
Annual Report.
Radiological Monitoring Program for the Kewaunee Nuclear Power Plant, Kewaunee, Wisconsin, Final Report - Part 14 Data Tabulations and Analysis, January - December 1987.
Wilson, D. W., G. M. Ward, and J. E. Johnson,1969.
In Environmental Contamina-tion by Radioactive Materials, International Atomic Energy Agency, p.125.
(
l t
O
'32
O Appendix A Interlaboratory Comparison Program Results l
l
?
i, i
NOTE: Appendix A is updated twice a year and the complete Appendix is included in January and July monthly reports only.
Please refer to January and July Reports for information.
i k
I
[
i
! O oanuary, 1988 i
i A-1 l
t i
i O Appendix A I
I i
l Interlaboratory Comparison Program Results f
Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) l
)
has participated in interlaboratory comparison (crosscheck) programs since the I
formulation of its quality control program in December 1971.
These programs t
i are operated by agencies which supply environmental-type samples (e.g., milk. or i
water) containing concentrations of radionuclides known to the issuing agency j
but not to participant laboratories.
The purpose of such a program is to provide i
an independent check on the. laboratory's analytical procedures and to alert it to
{
any possible problems.
l a
J i
i Participant laboratories measure the concentrations of 'specified radionuclides l
and report them to the issuing agency.
Several months later, the agency reports
}
the known values to the participant laboratories and specifies control limits.
i 4
Results consistently higher or lower than the known values or outside the control i
limits indicate a need to check the instruments or procedures used.
i in The results in Table A-1 were obtained through participation in the environmental U
sample crosscheck program for milk, water, air filters, and food samples during the i
period May 1984 through December 1987. This program has been conducted by the U.S.
Environmental Protection Agency Intercomparison and Calibration Section, Quality
}
)
Assurance Branc h, Environmental Monitoring and Support Laboratory, Las Vegas, j
j Nevada.
t 1
I The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) l during the period 1976, 1977, 1979, 1980, 1984, and 1985-1986 through participation l
in the Second, Third. Fourth, Fifth, Seventh, and Eighth International Intercompar-l ison of Environmental Dosimeters under the sponsorships listed in Table A-2.
l 4
l j
Table A-3 lists results of the analyses on in-house spiked samples.
i 2
Table A-4 lists results of the analyses on in-house "blank" samples.
l Attachment B lists acceptance criteria for "spiked" samples.
lO i
A-2 1
1 i
k 1
O Table A-1.
U.S. Environmental Protection Agency's crosscheck program, com-V parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1984 through 1987.4 Concentration in pCi/lb a
Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis t2cC 15, N=1 Control Limits STW-358 Water May 1984 Gr. alpha 3.0t0.6 3t5.0 0.0-11.7 l
Gr. beta 6.7tl.2 615.0 0.0-14.7 STM-366 Milk June 1984 Sr-89 21t3.1 25t5.0 16.3-33.7 Sr-90 13t2.0 17tl.5 14.4-19.6 I-131 46t5.3 43t6.0 32.6-53.4 Cs-137 3814.0 35t5.0 26.3-43.7 K-40 1577i172 1496t75 1336-1626 STW-368 Water July 1984 Gr. alpha 5.1tl.1 6t5.0 0.0-14.7 i
Gr. beta 11.912.4 1315.0 4.3-21.7 STW-369 Water August 1984 I-131 34.3t5.0 34.0i6.0 23.6-44.4 STW-370 Water August 1984 H-3 3003t253 2817t356 2240-3434
- O STr-371 rood Juis 1984 sr-89 22.0*5.3 25.015.0 14.3-33.7 Sr-90 14.7t3.1 20.0tl.5 17.4-22.6 1-131
<172 39.0t6.0 28.6-49.4 Cs-137 24.0t5.3 25.015.0 14.3-33.7 K-40 25031132 2605t130 2379-2831 j
STAF-372 Air August 1984 Gr. alpha 15.3tl.2 1715.0 8.3-25.7 i
rilter Gr. beta 56.0t0.0 5115.0 42.3-59.7 j
Sr-90 14.3tl.2 18 1.5 15.6-20.4 Cs-137 21.022.0 15t5.0 6.3-23.7 STW-375 Water Sept 1984 Ra-226 5.110.4 4.910.7 3.6-6.2 i
l Ra-228 2.210.1 2.310.4 1.7-2.9 i
STW-377 Water Sept 1984 Gr. alpha 3.3tl.2 5.015.0 0.0-13.7 Gr. beta 12.712.3 16.0t5.0 7.3-24.7 STW-379 Water Oct 1984 H-3 2860t312 2810t205 2454-3166 STW-380 Water Oct 1984 Cr-51
<36 4015.0 31.3-48.7 Co-60 20.3tl.2 20t5.0 11.3-28.7 i
l Zn-65 150t8.1 14715.0 138.3-155.7 Ru-106
<30 47t5.0 36.3-55.7 Cs-134 31.317.0 3115.0 22.3-39.7 1
Cs-13) 26.7tl.2 24t5.0 15.3-32.7 i O-1 1
A-3
i Table A-1.
(continued, l
Concentratip in pCi/l b l
Lab Sample Date TIML Result EPA Resultd Code Type Collected Analytis t2cC 15, N=1 Control Limits STM-382 Milk Oct 1984 Sr-89 15.714.2 22i5.0 13.3-30.7 Sr-90
- 12. 7tl. 2 1611.5 13.4-18.6 I-131 41.7 3.1 4216.0 31.6-42.4 Cs-137 31.3t6.1 3215.0 23.3-40.7 K-40 1447166 1517f76 1386-1648 STW-384 Water Oct 1984 Gr. alpha 9.711.2 1415.0 5.3-22.7 (Blind)
Sample A Ra-226 3.310.2 3.010.5 2.2-3.8 4
f; Ra-228 3.411.6' 2.110.3 1.6-2.6 Uranium nae 0.0-15.4 1
i Sample B Gr. beta 48.315.0 6415.0 55.3-72.7 Sr-89 10.714.6 11t5.0 2.3-19.7 e
Sr-90 7.3tl.2 12tl.5 9.4-14.6 Co-60 16.311.2 1415.0 5.3-22.7 l
Cs-134
<2 215.0 0.0-10.7 t
Cs-137 16.711.2 1415.0 5.3-22.7 4
O Star-387 Air nov 1984 Gr. einha 18.7*i.2 15*5.0 6.3-23.7 Filter Gr. beta 59.015.3 52i5.0 43.3-60.7 Sr-90 18.311.2 21tl.5 18.4-23.6 Cs-137 10.311.2 10t5.0 1.3-18.7 STW-388 Water Dec 1984 I-131 28.012.0 36t6.0 25.6-36.4
]
STW-389 Water Dec 1984 H-3 3583t110 31822360 2558-3806 l
STW-391 Water Dec 1984 Ra-226 8.411.7 8.611.3 6.4-10.8 j
4 Ra-228 3.110.2 4.li0.6 3.0 5.2 STW-392 Water Jan 1985 Sr-89
<3.0 3.0i5.0 0.0-11.7 Sr-90 27.315.2 30.011.5 27.4-32.6 STW-393 Water Jan 1985 Gr. alpha 3.311.2 515.0 0.0-13.7 Gr. beta 17.3t3.0 1515.0 6.3-23.7 i
STS-395 Food Jan 1985 Gr. alpha 4.712.3 6.015.0 0.0-14.7 j
Gr. beta 11.311.2 15.0i5.0 6.3-23.7 i
Sr-89 25.316.4 34.015.0 25.3-42.8 Sr-90 27.0i8.8 26.0tl.5 23.4-28.6 J
I-131 38.0t2.0 35.016.0 24.6-45.4 Cs-137 32.712.4 29.015.0 20.3-37.7 K-40 1410i212 13821120 1174-1590 O
A-4 j
m
,. -.. _ _ _,i
[
]
Table A-1.
(continued)
Concentration in pCi/10 l
Lab Sample Date TIML Result EPA Resultd i
Code Type Collected Analysis 12oc 15, N=1 Control Limits STW-397 Water Feb 1985 Cr-51
<29 48t5.0 39.3-56.7 Co-60 21.3t3.0 20t5.0 11.3-28.7 Zn-65 33.7t5.0 55t5.0 46.3-63.7 Ru-106
<23 25t5.0 16.3-33.7 Cs-134 32.3tl.2 3515.0 26.3-43.7 i
Cs-137 25.3t3.0 2515.0 16.3-33.7 i
STW-398 Water Feb 1985 H-3 3869t319 3796t634 3162-4430 i
STM-400 Milk March 1985 I-131 7.312.4 9.0t0.9 7.4-10.6 STW-402 Water March 1985 Ra-226 4.6t0.6 5.0t0.8 3.7-6.3 Ra-228
<0.8 9.0tl.4 6.7-11.3 Reanalysis Ra-228 9.0t0.4 STW-404 Water March 1985 Gr. alpha 4.7t2.3 6t5.0 0.0-14.7 Gr. beta 11.3tl.2 1515.0 6.3-23.7 O
STAF-405 Air Maren 1985 Gr. ainha 9.3*1.0 10.0t5.0 1.3-18.7 Filter Gr. beta 42.0tl.1 36.015.0 27.3 44.7 Sr-90 13.3tl.0 15.0tl.5 12.4-17.6 Cs-137 6.3tl.0 6.0t5.0 0.0-14.7 STW-407 Water April 1985 I-131 8.0 0.0 7.510.8 6.2-8.8 i
STW-408 Water April 1935 H-3 3399t150 3559i630 2929-4189 STW 409 Wat -
April 1985
{
(Blind).
Gr. alpha 29.711.8 32.0t5.0 23.3-40.7 Sample A Ra-226 4.410.2 4.110.6 3.1-5.1 i
Ra-228 NA8 6.210.9 4.6-7.8 Uranium nae 7.016.0 0.0-17.4 Sample B Gr. beta 74.3111.8 72.0t5.0 63.3-80.7 Sr-89 12.317.6 10.0t5.0 1.3-18.7 Sr-90 14.7t2.4 15.0tl.5 12.4 17.6 Co-60 14.712.4 15.015.0 6.3-23.7 Cs-134 12.0t2.0 15.0t5.0 6.3-23.7 Cs-137 14.0t2.0 12.0t5.0 3.3-20.7 O
A-5 j
i a
I l
j 4
Table A-1.
(continued) j Concentration in pCi/lb i
Lab Sample Date TIML Result EPA Result 0 Code Type Collec teo Analysis t2ac is. N=1 Control Limits l
i STW 413 Water May 1985 Sr-89 36.0t12.4 39.0t5.0 30.3-47.7 Sr-90 14.314.2 15.0tl.5 12.4-17.6 l
STW-414 Water' May 1985 Gr. alpha 8.314.1 12.015.0 3.3-20.7
[
Gr. beta 8.711.2 11.015.0 2.3-19.7 i
STW 416 Water June 1985 Cr-51 44.7t6.0 44.0:5.0 45.3-52.7 f
Co.60 14.3tl.2 14.015.0 5.3-?2.7
[
Zn-65 50.3t7.0 47.0t5.0 38.3-55.7 j
Ru-106 55.3tS 8 62.0t5.0 53.3-70.7 i
j Cs-134 32.7tl.2 35.0t5.0 26.3-43.7 l
1 Cs-137 22.7f2.4 20.0t5.0 11.3-28.7 STW-418 Water June 1985 H-3 2446t132 2416t351 1807-3025 a
STM-421 Milk June 1985 Sr-89 10.3f4.6 11.0th.0 2.3-19.7 f
Sr-90 9.0t2.0 11.0tl.5 8.4-13.6 1-131 11.7tl.2 11.0i6.0 0.6-21.4 I
i'Q Cs-137 12.711.2 11.0t5.0 2.3-19.7 l
j K-40 1512t62 1525t132 1393-1657 STW 423 Water July 1985 Gr. alpha 5.010.0 11.0i5.0 2.3-19.7 i
Gr. beta 5.0t2.0 8.0t5.0 0.0-16.7 f
1 j
STW-425 Water August 1985 I-131 25.7t3.0 33.026.0 22.6-43.4
[
t i
STW-426 Water August 1985 H-3 4363t83 4480t447 3704-5256 i
STAF-427 Air August 1985 or, alpha 11.310.6 13.0t5.0 4.3-21.7 I
Filter Gr. beta 46.0tl.0 44.0t5.0 35.3-52.7 Sr-90 17.7t0.6 18.0fl.5 15.4-20.6 i
l Cs-137 10.3t0.6 8.0t5.0 0.0-16.7 l
1 STW-429 Water Sept 1985 Sr-89 15.7t0.6 20.015.0 11.3-28.7 l
Sr-90 7.0t0.0 7.0*1.5 4.4-9.6 l
i i
STW-430 Water Sept 1985 Ra-226 8.2t0.3 B 9tl.3 6.6-11.1
]
Ra-228 4.lio.3 4.6t0.7 3.4-5.8 l
l STW-431 Water Sept 1985 Gr. alpha 4.710.6 8.0t5.0 0.0-16.7 i
Gr. beta 4.7tl.2 8.0t5.0 0.0-16.7 i
l!O
)
A-6 i
1
n Table A-1.
(continued)
U Concentration in pCi/lb 1.ab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 120C 1s, N=1 Control Limits STW-433 Water Oct 1985 Cr-51
<13 21.0t5.0 12.3-29.7 Co-60 19.310.6 20.0t5.0 11.3-28.7 Zn-65 19.7t0.6 19.0t5.0 10.3-27.7 Ru-106
<19 20.015.0 11.3-28.7 Cs-134 17.011.0 20.0t5.0 11.3-28.7 Cs-137 19.3tl.2 20.0 5.0 11.3-28.7 STW-435 Water Oct 1985 H-3 1957t50 1974t345 1376-2572 STW-436 Water Oct 1985 437 (Blind)
Sample A Gr. alpha 53.0t1.0 52.0213 29.4-74.6 Ra-226 5.9t0.1 6.3t1.0 4.1-7.9 Ra-228 8.210.1 10.1tl.5 7.5-12.7 Uranium nae 8.0t10.4 0.0-18.4 Sample B Gr. beta 85.712.5 75.0t5.0 76.3-83.7 O
sr-89 at 3*t s 27 c*s o 28 3-35 7 g
Sr-90 10.310.6 9.011.5 6.4-11.6 Co-60 18.311.2 18.015.0 9.3-26.7 Cs-134 16.3tl.2 18.015.0 9.3-26.7 Cs-137 19.0il.0 18.015.0 9.3-26.7 STM-439 Milk Oct 1985 Sr-39 50.3t0.6 48.015.0 39.3-56.7 Sr-90 23.310.6 26.011.5 23.4-28.6 1-131 45.7t3.2 42.016.0 31.6-52.4 Cs-137 60.710.6 56.015.0 47.3-64.7 K-40 1547129 1540t77 1406-1674 STW-441 Water Nov 1985 Gr. alpha 5.310.6 10.015.0 1.3-18.7 Gr. beta 11.7tl.2 13.015.0 4.3-21.7 STW-443 Water Dec 1985 1-131 46.7t2.1 45.016.0 34.6-55.4 STW-444 Water Dec 1985 Ra-226 6.St0.1 7.1tl.1 5.2-9.0 Ra-228 6.lt0.1 7.3tl.1 5.4-9.2 STW-445 Water Jan 1986 Sr-89 29.7t2.5 31.015.0 22.3-39.7 Sr-90 13.7t0.6 15.011.5 12.4-17.6 STW-446 Water Jan 1986 Gr. alpha 3.0t0.0 3.0t5.0 0.0-11.7 Gr. beta 5.310.6 7.015.0 0.0-15.7 i
/m WL wome ene A-7
a.
{
Tat,ie A-1.
(continued)
Concentration in pCi/lb Lab' Sample Date TIML Result EPA Resultd Code Type Collected Analysis t2ac 15, N=1 Control Limits
~STW-447 Food Jan 1986 Sr-89 24.3t2.5 25.0i5.0 16.3-33.7 Sr-90 17.310.6 10.Dil.5 7.4-12.6 I-131 22.722.3 20.Di6.0 9.6-30.4 Cs-137 16.3t0.6 15.0i5.0 6.3-23.7 K-40 927146 950i144 701-1199 STW-448 Water Feb 1986 Cr-51 45.013.6 38.015.0 29.3-46.7 Co-60 19.7tl.5 18.0i5.0 9.3-26.7 Zn-65 44.0i3.5 40.0i5.0 31.3-48.7 Ru-106
<9.0 0.015.0 0.0-8.7 Cs-134 28.312.3 30.0i5.0 21.3-38.7 Cs-137 23.7f0.6 22.015.0 13.3-30.7 STW-449 Water Feb 1986 H-3 5176i48 5227iS25 4317-6137 i
STW-450 Water Feb 1986 U total 8.010.0 9.0i6.0 0.0-19.4 STW-451 Milk Feb 1986 I-131 7.0f0.0 9.016.0 0.0-19.4 STW-452 Water March 1986 Ra-226 3.810.1 4.110.6 3.0-5.2 Ra-228 11.0i0.5 12.4fl.8 9.2-15.5 STW-453 Water March 1986 Gr. aloha 6.7i0.6 15.0*5.0 6.3-23.7 Gr. beta 7.310.6 8.015.0 0.0-16.7 1
STW-454 Water April 1986 I-131 7.0i0.0 9.026.0 0.0-19.4 STW-455 Water April 1986 456 (Blind)
Sample A Gr. alpha 15.0il.0 17.0i5.0 8.3-25.7 Ra-226 3.li0.1 2.9i0.4 2.1-3.7 Ra-228 1.5i0.2 2.0t0.3 1.5-2.5 Uranium 4.7i0.6 5.0i6.0 0.0-15.4 Sample B Gr. beta 28.7tl.2 35.0i5.0 26.3-43.7 Sr-89 5.7i0.6 7.015.0 0.0-15.7 Sr-90 7.010.0 7.011.5 4.4-9.6 Co-60 10.7tl.5 10.015.0 1.3-18.7 Cs-134 4.0il.7 5.015.0 0.0-13.7 Cs-137 5.310.6 5.0i5.0 0.0-13.7
(~ )
v A-8
--4
Table A-1.
(continued) pJ Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 12cc 15, N=1 Control Limits STAF-457 Air April 1986 Gr. alpha 13.7f0.6 15.015.0 6.3-23.7 Filter Gr. beta 46.310.6 47.015.0 38.3-55.7 Sr-90 14.7f0.6 18.011.5 15.4-20.6 Cs-137 10.710.6 10.015.0 1.3-13.7 STU-458 Urine April 1986 Tritium 4313i70 44231189 4096-4750 STW-459 Water May 1986 Sr-89 4.310.6 5.015.0 0.0-13.7 Sr-90 5.0f0.0 5.0il.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.3i0.6 8.0i5.0 0.0-16.7 Gr. beta 11.3fl.2 15.015.0 6.3-23.7 STW-461 Water June 1986 Cr-51
<9.0 0.0i5.0 0.0-8.7 Co-60 66.0il.0 66.015.0 57.3-74.7 Zn-65 87.311.5 86.0 5.0 77.3-94.7 Ru-106 39.712.5 50.0 5.0 41.3-58.7 Cs-134 49.3i2.5 49.015 2 40.3-57.7 O
cs-137 to.3*t.s to.o*s.o 1.3-18.7 STW-462 Water June 1986 Tritium 3427f25 31251361 2499-3751 STM-464 Milk June 1986 Sr-89
<1.0 0.015.0 0.0-8.7 Sr-90 15.310.6 16.0il.5 13.4-18.5 I-131 48.3i2.3 41.016.0 30.6-51.4 Cs-137 43.7tl.5 31.0i5.0 22.3-39.7 K-40 15671114 1600i80 1461-1739 STW-465 Water July 1986 Gr. alpha 4.710.6 6.015.0 0.0-14.7 Gr. beta 18.7tl.2 18.015.0 9.3-26.7 STW-467 Water August 1986 I-131 30.3i0.6 45.0i6.0 34.4-55.4 STW 468 Water August 1986 Pu-239 11.3i0.6 10.lil.0 8.3-11.9 STW-469 Water August 1986 Uranium 4.010.0 4.0i6.0 0.0-14.4 STAF-470 Air Sept 1986 Gr. alpha 19.3fl.5 22.015.0 13.3-30.7 471 Filter Gr. beta 64.0i2.6 66.0i5.0 57.3-74.7 472 Sr-90 22.0il.0 22.0i5.0 19.4-24.6 Cs-137 25.7*1.5 22.015.0 13.3-30.7 STW-473 Water Sept 1986 Ra-226 6.0f0.1 6.110.9 4.5-7.7
/]
Ra-228 8.711.1 9.111.4 6.7-11.5 A-9
]
Table A-1.
(continued).
Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis f2ac 1s, N=1 Control Limits STW-474 Water Sept 1986 Gr. alpha 16.3f3.2 15.015.0 6.3-23.7 Gr. beta 9.0fl.0 8.015.0 0.0-16.7 STW-475 Water Oct 1986 Cr-51 63.3i5.5 59.015.0 50.3-67.7 Co-60 31.012.0 31.0t5.0 22.3-39.7 Zn-65 87.3i5.9 85.015.0 76.3-93.7 Ru-106 74.7 7.4 74.015.0 65.3-82.7 Cs-134 25.710.6 28.015.0 19.3-36.7 Cs-137 46.311.5 44.0i5.0 35.3-52.7 STW-476 Water Oct 1986 H-3 5918160 59731597 4938-7008 SPW-477 Water Oct 1986 478 (Blind)
Sample A Gr. alpha 34.0i6.0 40.015.0 31.3-48.7 Ra-226 5.8i0.2 6.010.9 4.4-7.6 Ra-228 2.7tl.0 5.0i0.8 3.7-6.3 O
Urenium 11.010.0 10.016.0 0.0 20.4 Sample B Gr. beta 38.7tl.2 bl.015.0 42.3-59.7 Sr-89 5.0t0.0 10.015.0 1.3-18.7 Sr-90 3.0i0 0 4.0il.5 1.4-6.6 Co-60 24.7tl.2 24.0i5.0 15.3-32.7 Cs-134 11.012.0 12.0i5.0 3.3-20.7 Cs-137 9.3tl.2 8.015.0 0.0-16.7 STM-479 Milk tuv 1986 Sr-89 7.711.2 9.015.0 0.3-17.7 Sr-90 1.010.0 0.011.5 0.0-2.6 I-131 52.3i3.1 49.016.0 38.6-59.4 Cs-137 45.7i3.1 39.015.0 30.3-47.7 K-40 1489i104 1565i78 1430-1700 STU-480 Urine Nov 1986 H-3 5540i26 5257t912 4345-6169 STW-481 Water Nov 1986 Gr. alpha 12.0t4.0 20.0i5.0 11.3-28.7 Gr. beta 20.013.5 20.015.0 11.3-28.7 STW-482 Water Dec 1986 Ra-226 6.710.2 6.8i1.0 5.0-8.6 Ra-228 5.2i0.2 11.lil.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.7f5.0 25.0i5.0 16.3-33.7-Sr-90 21.0*2.0 25.0il.5 22.4-27.6 U,
A-10
Table A-1.
(continued).
Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 120c 15, N=1 Control. Limits STW-484 Water Jan 1987 Pu-239 17.012.3 16.7tl.7 13.8-19.6 STF-486 Food Jan 1987 Sr-90 36.014.0 49.0110.0 31.7-66.3 I-131 78.0i3.4 78.018.0 64.1-91. 9 Cs-137 89.7t3.0 84.0*5.0 75.3-92.7 K-40 942156 980i49 895-1065 STF-487 Food Jan 1987 SR-90 2.0f0.0 (Blank)
<3 Cs-137
<2 K-40 9931102 STW-488 Water Feb 1987 Co-60 49.0i0.0 50.0i5.0 41.3-58.7 Zn-65 96.0i7.2 91.015.0 82.3-99.7 Ru-106 92.0i20.2 100.0f5.0 91.3-108.7 Cs-134 53.013.4 59.015.0 50.3-67.7 Cs-137 89.314.6 87.0i5.0 78.3-95.7 O
STw-489 water Fe8 1987 s-3 4130i140 4209*420 3479-4939 STW-490 Water Feb 1987 Uranium 8.311.2 8.0i6.0 0.0-18.4 i
STM-491 Milk Feb 1987 I-131 10.0i0.0 9.010.9 7.4-10.6 STW-492 Water Mar 1987 Gr. alpha 3.7tl.2 3.0i5.0 0.0-11.7 Gr. beta 11.3fl.2 13.015.0 4.3-21.7 STW-493 Water Mar 1987 Ra-226 7.0i0.1 7.3fl.1 5.4-9.2 Ra-228 7.112.3 7.5fl.1 5.5-9.5 STW-494 Water Apr 1987 I-131 8.0i0.0 7.010.7 5.8-8.2 j
STAF-495 Air Apr 1987 Gr. alpha 15.010.0 14.0i5.0 5.3-22.7 1
Filter Gr. beta 41.0t2.0 43.0i5.0 34.3-51.7 l
Sr-90 16.3tl.2 17.0il.5 14.4-19.6 Cs-137 7.0f0.0 8.015.0 0.0-16.7 STW-496 Water Apr 1987 497 (Blind)
Sample A Gr. alpha 30.7*1.2 30.0f8.0 16.1-43.9 Ra-226 3.9i0.2 3.910.6 2.9-4.9 Ra-228 4.9i0.9 4.010.6 3.0-5.0 O
ureeium 5.010.0 5.01e.0 0.0 15.4 A-11 1
.j
Table A-1.
(continued)
Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis f2cc Is, N=1 Control Limits STW-496 Water Apr 1987 497 (Blind)
Sample B Gr. Beta 69.3i9.4 66.0*5.0 57.3-74.7 Sr-89 16.313.0 19.0i5.0 10.3-27.7 Sr-90 10.0f0.0 10.Dil.5 7.4-12.6 Co 8.313.0 8.0t5.0 0.0-16.7 Cs-134 19.0i2.0 20.015.0 11.3-28.7 Cs-137 14.7tl.2 15.0i5.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 60171494 5620i795 4647-6593 STW-499 Water May 1987 Sr-89 38.0i6.0 41.0i5.0 32.3-49.7 Sr-90 21.0i2.0 20.0fl.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.013.4 11.015.0 2.3-19.7 Gr. beta 10.311.2 7.015.0 0.0-15.7 STW-501 Water June 1987 Cr-51 40.018.0 41.0f5.0 32.3-49.7 O
co-so so 3*3.o 64 ois.o ss 3-72.7 Zn-65 11.315.0 10.015.0 1.3-18.7 l
Ru-106 78.316.4 75.015.0 66.3-83.7 Cs-134 36.713.0 40.0i5.0 31.3-48.7 Cs-137 80.3f4.2 80.0i5.0 71.3-88.7 STW-502 Water June 1987 H-3 2906186 2895t357 2277-3513 STW-503 Water June 1987 Ra-226 6.9i0.1 7.3fl.1 5.4-9.2 Ra-228 13.311.0 15.2*2.3 11.2-19.2 STW-504 Milk June 1987 Sr-89 57.014.3 69.0i5.0 60.3-77.7 Sr-90 32.0il.0 35.0il.5 32.4-37.6 i
1-131 64.0i2.0 59.0i6.0 48.6-69.4 Cs-137 77.7i0.6 74.0i5.0 65.3-82.7 K
1383t17 1525i76 1393-1657 STW-505 Water July 1987 Gr. alpha 2.3i0.7 5.015.0 0.0-13.7 Gr. beta 4.0il.0 5.0i5.0 0.0-13.7 STF-506 Food July 1987 I-131 82.7f4.6 80.0t8.0 66.1-93.9 Cs-137 53.713.0 50.015.0 41.3-58.7 K
1548i57 1680i84 1534-1826 STW-507 Water Aug 1987 I-131 45.714.2 48.016.0 37.6-58.4 O'V STW-508 Water Aug 1987 Pu-239 5.8 0.2 5.310.5 4.4-6.2 j
]
A-12
i Table A-1.
(continued) v)
Concentration in'pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis f20c is, N=1 Control Limits STW-509 Water Aug 1987 Uranium 13.310.3 13.0i6.0 2.6-23.4 STAF-510 Air Aug 1987 Gr. alpha 9.7i0.4 10.015.0 1.3-18.7 Filter Gr. beta 28.310.6 30.015.0 21.3-38.7 Sr-90 10.010.9 10.0il.5 7.4-12.6 Cs-137 10.0il.0 10.015.0 1.3-18.7
/
STW-511 Water Sept 1987 Ra-226 9.910.1 9.7tl.5 7.2-12.2 Ra-228 8.lil.4 6.3tl.0 4.6-8.0 STW-512 Water Sept 1987 Gr. alpha 2.010.6 4.0f5.0 0.0-12.7 Gr. beta 11.321.3 12.015.0 3.3-20.7 STW-513 Water Oct 1987 H-3 4473i100 4492f449 3714-5270 STW-514 Water A Oct 1987 Gr. alpha 29.3i2.6 28.0t7.0 15.9-40.1 Ra-226 4.910.1 4.810.7 3.6-6.1 Ra-228 4.2il.0 3.610.5 2.7-4.5 Uranium 3.010.1 3.016.0 0.0-13.4 O
STW-515 Water 8 Oct 1987 Gr. beta 72.3f2.7 72.0i5.0 63.3-80.7 Sr-89 14.311.3 16.0f5.0 7.3-24.7 Sr-90 9.7f0.4 10.011.5 7.4-12.6 Co-60 16.7t3.0 16.015.0 7.3-24.7 Cs-134 16.7f2.3 16.015.0 7.3-24.7 Cs-137 24.313.3 24.0i5.0 15.3-32.7 STW-516 Water Oct 1987 Cr-51 80.3f17.5 70.0i5.0 61.3-78.7 Co-60 16.012.3 15.015.0 6.3-23.7 Zn-65 46.315.6 46.0i5.0 37.3-54.7 Ru-106 57.3115.4 61.0i5.0 52.3-69.7 Cs-134 23.712.5 25.015.0 16.3-33.7 Cs-137 51.713.2 51.0f5.0 42.3-59.7 STU-517 Urine Nov 1987 H-3 7267i100 7432i743 6145-8719 STW-519 Water Dec 1987 I-131 26.013.0 26.0i6.0 15.6-36.4 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 Brar.cn, Environmental Monitoring and Support Laboratory, U. S. Environmental Protection Agency (EPA), Las Vegan, Nevada, b All results are in the pCi/1, except for elemental potassium (K) data, which are O
c Unless otherwise indicated, the TIML results are given as the mean i2 standard in mg/1; air filter samples, which are in pCi/ filter; and food, which is in pCi/kg.
deviations for three determinations.
A-13 g
O O
O i
Table A-2.
Crosscheck program results, thermo%minescent dosimeters (TLDs).
mR d
Teledyne Average 12 o Lab TLD Result Known (al1-Code Type Measurement 120a Valuec
. articipants) p 2nd International Intercomparisonb CaF :Mn Field 17.0 1.9 17.1 16.417.7 115-2 2
Bulb Lab 20.814.1 21.3 18.817.6 P
3rd International Intercomparisone CaF :Mn Field 30.713.2 34.914.'8 31.513.0 115-3 2
Bulb Lab 89.616.4 91.7114.6 86.2124.0 4th International Intercomparisonf CaF :Mn Field 14.111.1 14.111.4 16.019.0 115-4 2
Bulb Lab (Low) 9.311.3 12.212.4' 12.017.6 Lab (High) 40.411.4 45.819.2 43.9113.2 5th International Intercomparison9 CaF :Mn Field 31.411.8 30.016.0 30.2114.6 115-5A 2
Bulb Lab at 77.415.8 75.217.6 75.8140.4 beginning Lab at 96.615.8 88.418.8 90.7131.2 end
O O
0 Table A-2.
(Continued)
[
mR-Teledyne Average 120 d Lab TLD Result Known (all Code Type Measurement 12oa Valuec participants) i 115-58 Lif-100 Field 30.314.8 30.016.0 30.2t14.6 Chips Lab at 81.117.4 75.217.6 75.8140.4 beginning Lab at 85.4111.7 88.418.8 90.7131.2
}-
the end h
7th International Intercomparison 115-7A LiF-100 Field 75.4i2.6 75.816.0 75.1129.8 Chips Lab (Co-60) 80.013.5 79.914.0 77.9127.6 Lab (Cs-137) 66.612.5 75.0t3.8 73.0t22.2 CaF :Mn Field
- 71. Si2. r>
75.816.0 75.1129.8 115-78 2
Bulbs Lab (Co-60) 84.816.4 79.914.0 77.9127.6 Lab (Cs-137) 78.811.6 75.013.8 73.0122.2 I
CaSO :Dy Field 76.812.7 75.816.0 75.1129.8 115-7C 4
Cards Lab (Co-60) 82.513.7 79.914.0 77.9t27.6 Lab (Cs-137 79.0i3.2 75.013.8 73.0122.2 I
l
O O
O Table A-2.
(Continued) mR d
Teledyne Average 12o Lab TLD Result Known (all Code Type Measurement 12oa Valuec participants) i 8th International Intercomparison 115-8A LiF-100 Field Site 1 29.511.4 29.711.5 28.9112.4 Chips Field Site 2 11.310.8 10.410.5 10.119.06 Lab (Cs-137) 13.710.9 17.210.9 16.216.8 CaF :Mn Field Site 1 32.311.2 29.711.5 28.9112.4-115-88 2
Bulbs Field Site 2 9.011.0 10.410.5 10.119.0 Lab (Cs-137) 15.810.9 17.210.9 16.216.8 l.
115-8C CaSO :Dy Field Site 1 32.310.7 29.711.5 28.9112.4 4
Cards Field Site 2 10.610.6 10.410.5 10.119.0 Lab (Cs-137 18.110.8 17.210.9 16.216.8 a Lab result given is the mean 12 standard deviations of three determinations.
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.
4 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 Fourth International Intercomparison of Environmental Dosimeters conducted in sumer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.
9 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.
h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and sumer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.
j Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.
d 1
j Table A-3.
In-house spiked samples.
Concentration in pC1/1 Lab Sample Date TIML Result Known Expec ted Code Type Collected Analysis n=3 Ac tivity Precision is, n=3a QC-MI-6 Milk Feb. 1986 Sr-89 6.0il.9 6.4f3.0 8.7 Sr-90 14.2il.7 12.912.0 5.2 I-131 34.2f3.8 35.213.5 10.4 Cs-134 32.011.8 27.3t5.0 8.7 Cs-137 35.8i2.1
'35.0i5.0 8.7 QC-W-14 Water Mar. 1986 Sr-89 1.610.4 1.6tl.0 7.1 Sr-90 2.410.2 2.412.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9i2.4 41.Si7.0 10.6 Co-60 10.6i1.7 12.115.0 7.lb Cs-134 30.212.4 25.818.0 7.lb Cs-137 21.9il.9 19.9i5.0 7.lb O'
QC-MI-7 Milk Apr. 1986 I-131 39.7f3.3 41.517.0 10.4 Cs-134 28.7f2.8 25.8i8.0 8.7 Cs-137 21.2*2.8 19.9f5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8tl.8 18.0i5.0 Sc QC-W-16 Water June 1986 Gross alpha 16.2i0.7 16.9i2.5 8.7 Gross beta 38.413.5 30.2t5.0 8.7 QC-MI-9 Milk June 1986 Sr-89
<1.0 0.0 7.lb Sr-90 12.6fl.8 13.3i3.0 4.2b I-131 38.917.0 34.817.0 10.4 Cs-134 33.0i3.4 36.115.0 8.7 Cs-137 38.512.8 39.0f5.0 8.7 SPW-2 Water June 1986 Gross alpha 16.811.8 18.0i5.0 Sc SPW-3 Water June 1986 Gross alpha 17.7i0.8 18.015.0 Sc QC-W-18 Water Sep. 1986 Cs-134 34.7f5.6 31.3i5.0 8.7 Cs-137 51.117.0 43.318.0 8.7 QC-W-19 Water Sep. 1986 Sr-89 13.614.1 15.6i3.5 7.lb Sr-90 6.4fl.6 6.2f2.0 4.2b O
A-17
Table A-3.
In-house spiked samples (continued)
V Concentration in pCi/l Lab Sample Date TIML Result Known Expec ted Code Type Collec ted Analysis n=3
. Activity Precision 1s, n=3a QC-W-21 Water Oc t. 1986 Co-60 19.212.2 18.513.0 8.7 Cs-134 31.715.2 25.618.0 8.7 Cs-137 23.8tl.0 21.615.0 8.7 QC-MI-11 Mil k Oct 1986 Sr-89 12.3tl.8 14.313.0 8.7 QC-W-20 Water Nov. 1986 H-3 38551180 3960i350 520b QC-W-22 Water Dec. 1986 Gross. al pha 9.8tl.4 11.214.0 8.7 Gross beta 21.7f2.0 23.815.0 8.7 QC-W-23 Water Jan. 1987 I-131 29.8i2.5 27.913.0 10.4 QC-MI-12 Milk Jan. 1987 I-131 36.511.3 32.615.0 10.4 Cs-137 32.6i4.2 27.418.0 8.7 SPM-13 Milk Jan 1987 Sr-89 10.412.1 12.2f4.0 8.7 O
sr-9o 14 sit 6 12 s*3 o s2 I-131 49.511.2 54.918.0 10.4 Cs-134
<1.6 0.0 8.7 Cs-137 33.3i0.6 27.418.0 8.7 SPW-24 Water Mar 1987 Sr-89 24.7i3.6 25.915.0 8.7 Sr-90 23.9i3.8 22.818.0 5.2 SPW-25 Water Apr 1987 I-131 28.0il.9 29.315.0 10.6 SPM-14 Milk Apr 1987 I-131 25.0i2.2 23.915.0 10.4 Cs-134
<2.1 0.0 8.7 Cs-137 34.2t2.0 27.217.0 8.7 SPW-26 Water Jun 1987 H-3 3422i100 3362i300 520 Co-60 24.8tl.4 26.5i7.0 8.7 Cs-134
<2.0 0.0 8.7 Cs-137 21.210.5 21.6t7.0 8.7 SPW-27 Water Jun 1987 Gr. alpha 8.Sil.9 10.114.0 8.7 Gr. beta 22.6tl.9 21.2i5.0 8.7 SPW-28 Water Jun 1987 Gr. alpha 8.7*1.3 10.li4.0 8.7 Gr. beta 12.215.2 9.413.0 8.7 O
A-18
i l
Table A-3.
In-house spiked samples (continued)
Concentration in pCi/l Lab Sample Date TIML Result Known Expec ted Code Type Collected Analysis n=3 Ac tiv ity Precision is, n=3a SPW-29 Water Jun 1987 Gr. alpha 16.4tl.3 18.915.0 8.7 Gr. beta 15.9i4.0 11.814.0 8.7 SPM-15 Milk Jul 1987 Sr-89 19.411.6 18.813.5 5.2 I-131 43.5i0.7 45.3t7.0 10.4 Cs-134 17.9i2.2 16.0f5.3 8.7 Cs-137 25.4tl.8 22.7i5.0 8.7 SPW-30 Water Sep 1987 Sr-89 17.Si3.0 14.315.0 8.7 Sr-90 18.4i2.2 17.512.2 5.2 SPW-31 Water Oct 1987 H-3 2053193 2059i306 520 a n=3 unless noted otherwise.
b n=2.
c n=1.
l O
A-19
i Table A-4.
In-house '"blank" samples.
I O
Concentration in pC1/1 Acceptance -
Lab Sample-
'Date Results Criteria Code Type Collected Analysis (4.66o)
(4.660)
BL-1 D.I. Water Nov. 1985 Gross alpha
<0.1
<1 Gross beta
<0.4
<4 BL-2 D.I. Water Nov. 1985 Cs-137 (gama) _
<1.9
<10 BL-3 D.I. Water Nov. 1985 Sr-89
<0.5
<5 Sr-90
<0.6
<1 BL-5 0.I. Water Nov. 1985 Ra-226
<0.4
<1-Ra-228
<0.4
<1 SPW-2265 D.I. Water Apr. 1985 Gross alpha
<0.6
<1 Gross beta
<2.2
<4 Sr-89
<0.2
<5 Sr-90
<0.4
<1 I-131
<0.2
<1 Cs-137 (gamma)
<7.4
<10 BL-6 D.I. Water Apr. 1986 Gross alpha
<0.4
<1 BL-7 0.I. Water Apr. 1986 Gross o'.pha
<0.4
<1 BL-8 0.I. Water June 1986 Gross alpha
<0.4
<1 BL-9 0.I. Water June 1986 Gross 41pha
<0.3
<1 SPW-3185 0.I. Water Jan 1987 Ra-226
<0.1
<1 Ra-228
<0.9
<1 SPS-3292 Milk Jan 1987 I-131
<0.1
<1 Cs-134
<6.2
<10 Cs-137
<6.4
<10 SPW-3554 D.I. Water Feb 1987 H-3
<180
<300 Gross beta
<2.6
<4 SPS-3555 Milk Feb 1987 Sr-89
<0.6
<5 Sr-90 1.910.4a
<1 SPS-3731 Milk Mar 1987 Cs-134
<2.2
<10 Cs-137
<2.5
<10 a low level (1 - 4 pC1/1) of Sr-90 concentration in milk is not unusual.
i A-20 I
Table A-4.
In-house "blank" samples (continued).
.)
Concentration in pCi/l Acceptance Lab Sample Date Results Criteria Code Type Coll ected Analysis (4.66a )
(4.66o )
SPS-3732 0.I. Water Mar 1987 Sr-89
<0.9
<5-Sr-90
<0.8
<1 1-131
<0.3
<1 Co-60
<2.3
<10 Cs-134(G)
<2.2
<10 Cs-137(G)
<2.4
<10 Ra-226
<0.1
<1 Ra-228
<1.0
<1 Np-237
<0.04
<1 Th-230
<0.05
<0.1 Th-232
<0.02
<0.1 U-234
<0.05
<0.1 U-235
<0.03
<0.1 U-238
<0.03
<0.1 SPS-4023 Milk May 1987 I-131
<0.1
<1 f~) '
SPS-4203 D.I. Water May 1987 Gross alpha
<0.7
<1 Gross beta
<1.7
<4 SPS-4204 Milk May 1987 Sr-89
<0.5
<5 Sr-90 2.4i0.6a
<1 SPS-4390 Milk Jun 1987 Cs-134
<4.7
<10 Cs-137
<5.2
<10 SPS-4391 D.I. Water Jun 1987 Sr-89
<0.4
<5 Sr-90
<0.4
<1 '
I-121
<0.1
<1 Co-60
<3.8
<10 Cs-137
<5.7
<10 Ra-226
<0.1
<1 Ra-228
<0.9
<1 SPW-4627 D.I. Water Aug 1987 Gross alpha
<0.6
<1 Gross beta
<1.4
<4 Tritium
<150 SPS-4628 Milk Aug 1987 Sr-89
<0.6
<5 Sr-90 2.4f0.6
<1 i
SPS-4847 Milk Sep 1987 Cs-134
<4.4
<10
(])
<5.3
<10 l
a tow leye) (1. 4 pCi/1) of Sr-90 concentration in milk is not unusual.
j A-21
~
Table'A-4.
In-house "blank" samples (continued).
Concentration in pCi/l Acceptance Lab -
Sample Date Results Criteria Code Type Collec ted Analysis (4.66o)
(4.66o)
SPS-4848 0.I. Water Sep 1987 I-131
<0.2
<1 SPW-4849 0.I. Water Sep 1987 Co-60
<4.1
<10 Cs-134
<4.8
<10 Cs-137
<4.0
<10 Sr-89
<0.7-
<5 Sr-90
<0.7
<1 SPW-4850 D.I. Water Sep 1987 Th-228
<0.04
<1 Th-232
<0.8
<1 U-234
<0.03
<1 U-235
<0.03
<1 U-238
<0.02
<1 Am-241
<0.06
<1 Cm-242
<0.04
<1 Ra-226
<0.1
<1 Ra-228
<1.0
<2 SPW-4859 0.I. Water Oct 1987 Fe-55
<0.5
<1 SPS-5348 Milk Dec 1987 Cs-134
<2.3
<10 Cs-137
<2.5
<10 SPW-5384 Water Dec 1987 Co-60
<2.8
<10 Cs-134
<2.6
<10 Cs-137
<2.8
<10 1-131
<0.2
<1 Ra-226
<0.1
<1 Ra-228
<1.2
<2 Sr-89
<0.5
<1 Sr-90
<0.4
<1 SPW-5385 Water Nov 1987 Gr. alpha
<0.4
<1 Gr. beta
<2.2
<4 Fe-55
<0.3
<1 SPS-5386 Milk Jan 1988 I-131
<0.1
<1 SPW-5448 "Dead" Water Jan 1988 H-3
<177
<300 i
O
TIML-BLIND-01 Revision 0, 12-29-86
(]
ATTACHMENT B ACCEPTANCE CRITERIA FOR "SPIKE 0" SAMPLES LABORATORY PRECISION:
ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One Standard Deviation Analysis Level for Single Determination Ganrna Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-89b 5 to 50 pCi/ liter or kg 5 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-90b 2 to 30 pCi/ liter or kg 3.0 pCi/ liter
>30 pCi/ lite: of kg 10% of known value Potassium
>0.1 g/ liter or kg 5% of known value Gross Alpha
<20 pCi/ liter 5 pCi/ liter
>20 pCi/ liter 25% of known value Gross Beta
<100 pCi/ liter 5 pCi/ liter
>100 pCi/ liter 5% of known value Tritium
<4,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known).0933
>4,000 pCi/ liter 10% of known value Radium-226,
<0.1 pCi/ liter 15% of known value Radium-228 Plutonium 0.1 pCi/ liter, gram, 10% of known value or sample Iodine-131, b
<55 pCi/ liter 6 pCi/ liter Iodine-129
>55 pCi/ liter 10% of known value Uranium-238,
<35 pCi/ liter 6 pCi/ liter Nickel-63b,
>35 pCi/ liter 15% of known value Technetium-996 Iron-55b 50 to 100 pCi/ liter 10 pCi/ liter 10% of known value j
1 a From EPA publication, "Environmental Radioactivity Laboratory Intercompari-son Studies Program, Fiscal Year 1981-1982. EPA-600/4-81-004.
b TIML limit.
A-23
O t
Appendix B Data Reporting Conventions P
1 O
I 1
~
i B-1
--a w_n,,,e,w.r,-r-a,-e--
,-e-.--e_n----,
,m,n_
~.-
,--.,e n
rw,ww ww.e-
-,~~ w we -
J
O Data Reporting Conventions 1.0.
All activities, except gross alpha and gross-beta, are decay corrected to collection time or the end of the collection period.
2.0.
Single Measurements Each single measurement is reported as follows:
xis where x = value of the measurement; s = 20 counting uncertainty (corr'asponding to the 95% confidence level).
In cases where the activity is fo'ma to be below the lower limit of detection L it is reported as
<L where L = is the lower limit of detection based on 4.660 uncertainty for a background sample.
O 3.0.
Duplicate Analyses 3.1.
Individual results: x1 i si x2 t sg Reported result:
xis where x = (1/2) (x1 + x2) i 2
s = (1/2) s # 3 3.2.
Individual results: <li
<Lg Reported result:
<L i
where L = lower of Li and L2 3.3.
Individual results:
xis
<L Reported result:
x i s if x > L;
<L otherwise B-2
4.0.
Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements.over. the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard are defined deviation (s) of a set of n numbers x1, x2,... xn as follows:
x=fIx E (*~ )2 s=
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 LLO, the highest LLO is reported.
O 4.4 If eii but one of the values are less then ene hishest LLO. tne 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 1
5, the figure is dropped, and the last retained figure is raised by 1.
As an example,11.446 is rounded off to 11.45.
4.5.3. If the figure following those 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 rounded off to 11.44, while 11.425 is rounded off to 11.42.
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Appendix C Maximum Permissible Concentrations 1
of Radioactivity in Air and Water 1
i Above Background in Unrestricted Areas 1
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LJ Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water Gross alpha 3
pCi/m3 Strontium-89 3,000 pCi/1 Gross beta 100 pCi/m3 Strontium-90 300 pCi/1 Iodine-131b 0.14 pCi/m3 Cesium-137 20,000 pCi/1 Barium-140 20,000 pCi/1 lodine-131 300 pCi/l Potassium-40c 3,000 pCi/l Gross alpha 30 pCi/1 Gross beta 100 pCi/1 Tritium 3 x 106 pCi/1
(]
a Taken f rom Code of Federal Regulations Title 10, Part 20, Table II and appro-priate footnotes.
Concentrations may be averaged over a period not greater than one year.
b From 10 CFR 20 but adjusted by a f actor of 700 to reduce the dose resulting f rom the air-grass-cow-milk-child pathway.
c A natural radionuclide.
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C-2 i
10.1 10.1 LAND USE CENSUS The Land Use Census satisfie: the requirements of Kewaunee Nuclear Power Plant Technical Specification 7.7.2 which states:
A bnd use census shall be conducted and shall identify within a distance of 8 Km (5 miles) the location in each of the 10 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft.2) produc'ing broad leaf vegetation.
This census is conducted annually during the growing season.
The 1987 Land Use Census was done by surveying families in the 10 meteorological sectors within 5 miles of the Kewaunee Nuclear Power Plant. The survey was administered by phone with a majority of the families, and a door-to-door survey was used to collect the remaining information. Of the families surveyed only 18 met the Technical O
Specification criteria for inclusion in the Land use Census.
Table 10.1 lists the results of the census and Figure 10.1 shows the loca-tions of the meteorological sections and the township section numbers.
The 1937 Land Use Census was compared to the 1986 Land Use Census to see if any changes were made. There were no significant differences between the two surveys.
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AOR10.2 rnV Table 10.1 Land Use Census Inventory of residence, gardens > 500 sq. ft. and milk animals found nearest to the plant in each of the 10 meteorological sections within a 5 mile radius of the Kewaunee Nuclear Power Plant.
Milk Oistance from Sector Section#
Residence Garden Animals plant (in miles)
J 11 X
X (Note 1) 2.7 K
35 X
X 0.8 K
2 X
1.4 d
L 35 X
X 0.9 L
35 X
1.3 j
M 35 X
X 1.3 M
34 X
1 ~. 7 ~
N 26 X
X 0.9 Q
N 34 X
1.6 P
26 X
X 1.4 P
27 X
2.0 Q
23 X
X X
1.2 R
26 X
X 1.0 R
23 X
2.1
)
A 24 X
X 2.0 i
A 13 X
2.9 B
24 X
1.1 B
24 X
X 1.7 i
2 Note 1:
There were no milk animals located in sector J within 5 miles
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of the Kewaunee Nuclear Power Plant.
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i NRC-SS, WPSC (4141433-1598
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_ TELECOPIER (414) 433-1297 EASYLINK 62891993 wisconsuu pusuc saumcecomposanom l
A 600 North Adams
- P.O. Box 19002
- Green Bay, WI 543o7-9002 l
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February 29, 1988 10 CFR 50.36 10 CFR 50.59 U. S. Nuclear Regulatory Commission ATTN: Document Control Oesk Washington, D.C.
20555
(
Gentlemen:
Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant 1987 Annual Operating Report Enclosed is a copy of the-1987 Kewaunce Nuclear Power Plant (KNPP) Annual Oper-ting Report.
This report is being C.ced in accordance with Section 6.9.1.b cf the KNPP Technical Specifications.
[
The 1987 KNPP Annual Operating Report also satisfies the.'eporting requirements 1
l of 10 CFR 20.407(a)(2) and 10 CFR 20.407(b) (personnel monitoring), KNPP t
Technical Specification 4.2.b.5.b (steam generator inspection), KNPP Te hnical Specift:ation 6.9.3.a (environmental monitoring), and KNPP Technical Specification 8.7.2 (land use census).
Finally, Section 3 of the report i
describes those facility changes allowed by 10 CFR 50.59(a)(1).
Ve y truly yours, H
D. C. Hintz Vice President - Nuclear Power Ath/jms Enc.
cc - Mr. Robert Nelson, US NRC US NRC, Region 172 l
INP0 Records Center, Suite 1500, i
1100 Circle 75 Parkway,
.]
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Atlanta, G4 30339 i
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.