IR 05000409/1998005
| ML20198E531 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/17/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20198E442 | List: |
| References | |
| 50-409-98-05, 50-409-98-5, NUDOCS 9812240079 | |
| Download: ML20198E531 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGIONlli Docket No:
50-409
~ License No:
DPR-45 i
Report No:
50409/98005(DNMS)
Licensee:
Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602 Facility:
La Crosse Boiling Water Reactor
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J Location:
La Crosse Site, Genoa, Wisconsin Dates:
December 7-10,1998 Inspectors:
D. Nelson, M.S., Radiation Specialist R. Landsman, Project Engineer Approved By:
Bruce L. Jorgensen, Chief Decommissioning Branch Division of Nuclear Materials Safety i
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9812240079 981217 PDR ADOCK 05000409
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EXECUTIVE SUMMARY
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La Crosse Boiling Water Reactor NRC Inspection Report 50-409/98005(DNMS)
This routine decommissioning inspection covered aspects of licensee management and control,
. spent fuel safety, and radiological safety.
. Overall, the licensee's performance during decommissioning activities was good. All
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activities inspected were conducted in compliance with the Decommissioning Plan, the Quality Assurance Program (QAP) and the Technical Specifications.
Facility Manaoement and Control
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The licensee performed appropriate safety reviews prior to conducting limited
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dismantling of reactor components and systems.
A minor violation of an Radiation Protection (RP) procedure indicated a need for closer
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monitoring of site contractors / visitors.
Soent Fuel Safety Fuel Element Storage Well water level, chemistry and cleanliness control programs
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appeared adequate to ensure the safe wet storage of the spent fuel.
Training and qualification of staff designated as certified fuel handlers were being
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properly implemented.
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Radioloalcal Safety The RP Program was effective in implementing the requirements of the
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Decommissioning Plan, the QAP and the license.
Housekeeping and the material condition of components throughout the facility was
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excellent.
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Report Details Summary of Plant Activities
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Activities during the inspection period were limited to routine ongoing safe storage (SAFSTOR)
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activities. There was little if any dismantlement of plant systems.
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1.0 Facility Management and Control 1.1 General The inspectors conducted reviews of ongoing activities in order to assess overall management and controls. Specific events and findings are detailed in the sections
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below, i-1.2 Oraanization. Manaaement and Cost Controls at Permanentiv Shut Down Reactors l
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a.
Inspection Scope (36801)
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i The inspection evaluated whether the licensee's SAFSTOR organization, staffing and qualifications met the requirements of the Quality Assurance Program (QAP) and the
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Decommissioning Plan.
a b.
Observations and Findinas There have been no changes in the licensee's SAFSTOR organization since the last Inspection. The plant manager, the technical staff, members of the Operations Review Committee and the Safety Review Committee remain unchanged from that inspection.
c.
Conclusions The licensee's SAFSTOR organization, staffing and qualifications continued to meet the requirements of the QAP and the Decommissioning Plan.
1.3 Safety Reviews. Desian Chanaes. and Modifications at Permanent!v Shutdown Reactors a.
Inspection Scooe (37801)
The inspection evaluated whether the licensee had established an adequate program to identify unresolved safety questions resulting from any facility design change, test,
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experiment, or modification during SAFSTOR.
b.
Observations and Findinas During the inspection the licensee was working on and finished sealing / repairing a leak
. in a Dresser Coupling on the 60 inch circulating water intake line in the switchyard area for which the safety review was completed during the last inspection.
The inspectors reviewed the one safety review (evaluation) that had been completed since the last inspection which addressed the removal of the reactor coolant post
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accident sampling system which is no longer required because there is no fuel in the reactor vessel.
The inspectors also attended Operations Review Committee Meeting 98019 held on December 8 which addressed two additional safety reviews. The first review addressed the proposed forced air cooling of the fuel element storage well (FESW) suction piping which is the first step in alleviating the necessity for keeping the component cooling water (CCW) system operable. This was approved in concept. The second review addressed the removal of the 18 static inverter from service because there are no longer any essential reactor instrumentation control circuits left. This design change was approved in final and a job coordinator was assigned to implement the modification.
c.
Conclusions The licensed configuration of the facility was not changed without the appropriate
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licensee safety reviews.
1.4 Sgtf-Assessment. Auditina. and Corrective Action at Permanentiv Shutdown Reactors a.
Inspection Scope (40801)
The int,vectora reviewed the two Incident Reports (irs) generated since the last inspection.
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Observations and Findinas irs are used by the licensee to document deficiencies and to describe and track the actions taken to correct them The inspectors noted that two irs had been generated since the last inspection. One IR reported an industrial accident (non-radiological flash bum to the hand) and the other, a draft, reported a minor violation of a Radiation Protection (RP) procedure. The violated procedure requires that RP be notified before contaminated compartments or components are breached. The interior of the main stack is minimally contaminated and a mechanic violated the procedure when he removed an inspection plate from the south side of the stack. The plate was removed to allow a contracted inspector to examine the interior of the stack. This was seen as a minor violation, however, because the interior surfaces of the main stack were only minimally contaminated, the inspection was only done once every 5 years.' The inspection did not involve penetration of the open portal and there was no contamination found on the mechanic or the inspector after the inspection. Plant management indicated that the violation reaffirmed management's need for exercising greater oversight of contractors and visitors to the site. Since the IR was still in draft form, the licensee's corrective actions to address the incident will be examined during the next onsite inspection.
There were no Radiological Occurrence Reports generated since the last inspection.
This was due in part to the lack of activities within the plant.
Since the last inspection the licensee reviewed and made modifications to the form used to conduct audits of the RP Program. The new format was under review during the inspection and was not available for NRC review.
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. Conclusions A violation of RP procedures indicated the need for close monitoring of contractors and visitors to the site.
2.0 Spent Fuel Safety 2.1 -
General The inspection verified the safe wet storage of spent fuel at the La Crosse Boiling Water Reactor (LACBWR). Specific findings are detailed in the sections below.
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Soent Fuel Pool Safety at Permanentiv Shutdown Reactors
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Insoection Scope (60801) -
The inspection evaluated the systems associated with the storage, control and maintenance of spent fuelin a safe manner.
b.
Observations and Findinas The fuel poolinventory consists of: 333 fuel bundles; 10 control rods; approximately 70 fuel bundle shrouds which are not attached to the fuel bundles but are bolted individually to the fuel pool floor; 2 startup sources (used for initial instrumentation indication) and their associated structural support pieces; 2 hanging aluminum buckets with miscellaneous pieces of hardware including two pieces of fuel rod; and 1 piece of
' fuel rod on the floor of the pool. There is no other debris in the pool.-
Water cleanliness controls continue to be maintained by the cover over the pool which has been enhanced by the addition of a rope barrier fence around the pool. Water
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Earlier this year, the licensee raised their pool temperature administrative limit from 110 degrees Fahrenheit (*F) to 115'F, in an attempt to determine the steady state pool temperature. This allowed them to investigate the need to continue required monthly surveillance of the CCW pumps, and to pursue the cause of the apparent increase in
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The increase in loss was determined to be from the higher evaporation rate caused by the higher fuel pool temperatures due to not continuously running fuel pool cooling.
They also determined that the CCW system need not be run monthly and should only be run when required (temperature of fuel pool approaching 115'F). Due to inspector questioning, the licensee recognized the need to revise Section 12 of the Operating Manual to delete the monthly requirement. The in-service testing requirements will be performed whenever the pumps are run. The CCW has been operated nine times this
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year to date. The licensee is in the process of preparing a design change to allow for:
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- the heating / air conditioning system to cool a portion of the fuel pool pump suction line by enclosing it in one of the ducts. This would allow the plant to remove the CCW system
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from service since it would no longer be needed.
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Conclusiong The FESW cleanliness, chemistry, level, and temperature control programs are
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2.3 Refuelina Activities a.
Insoection Scope (60710)
The inspection evaluated whether the licensee was meeting their certified fuel handler training program requirements.
b.
Observations and Findinas Periodic proficiency training is used to maintain the qualifications of fuel handlers. As a minim:em, subjects included in the initial certification program are covered at least once every two years; subjects such as fire protection, facility equipment design and characteristics, radiation safety, and administrative controls are covered. This is accomplished through classroom training, self-study, or on-the-job actual manipulation of the equipment. A blannual written exam combined with an oral examination administered in the year that there is no written examination is used to demonstrate proficiency of certified personnel. There are currently ten certified fuel handlers.
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Conclusions The training program has been implemented to maintain a staff properly qualified to maintain the fuel and to perform any fuel movements that may be required.
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3.0 Decommissioning Support Activities 3.1 General The inspectors conducted reviews of LACBWR's decommissioning support activities.
Specific findings are detailed in the section below.
3.2 Cold Weather Preparations a.
Insoection Scope (71714)
The inspection evaluated whether the licensee had effectively implemented a cold weather program to protect required systems against extreme cold weather,
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Observations and Findinas The air handlers in the containment building and the station heating boiler that supplies steam to the air handlers are being maintained and are supplying the required heat to the containment building. Since the last cold weather inspection, the licensee has installed a cover over the containment freight door to make it more weather-tight. The cover over the turbine truck bay door, which was not examined during the last inspection was also in place.
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Conclusions The licensee program to maintain the temperature in the containment building is
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4.0 Radiological Safety
4.1 General i
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The inspectors conducted reviews of ongoing activities in order to assess the overall RP Program. Specific findings are detailed in the sections below.
4.2 Occupational Radiation Exposure
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a.
Inspection Scooe (83750)
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The inspection examined and evaluated aspects of the RP Program. Specific areas evaluated included staffing, extemal exposure control, radiological surveying, control of radioactive materials and contamination, calibration of effluent monitors and maintaining occupational exposure as-low-as-reasonably-achievable, i
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Observations and Findinas There were no changes in the staffing or management of the RP Program since the last inspection.
A review of the extemal dosimetry records for the third quarter of 1998 indicated that personnel exposures reflected the lack of activity within the facility. O". '
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approximately 50 personnel who were issued extemal dosimetry (film dews), the highest individual dose during the third quarter was 60 millirem (mreim) and he highest total individual dose for the first three quarters was 150 mrem. Total stab dose for the third quarter was approximately 300 mrem. A majority of the individuals who were issued dosimetry received no dose during the first three quarters of 1998.
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The inspector reviewed the calibration records for the facility's effluent monitors. The inspector also observed station personnel testing the control room alarma for the 15 area radiation monitors (ARM) stationed within the turbine building and containment.
The primary, secondary and conta;nment air effluent monitors appeared to heve been calibrated and source checked per the requirements of station procedures. The waste water effluent monitor also appeared to have been calibrated and source checked per the requirements of sation procedures. No problems were noted during the testing of the ARM alarms.
The inspectors reviewed a sampling of direct radiation survey results and smear sample
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results for the fourth quarter of 1998.
Station procedures require that direct radiation surveys be performed quarterly in all accessible areas within restricted areas. The records of the fourth quarter results indicated that the licensee had complied with these requirements and exposure rates within the facility had not changed significantly.
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Station procedures require that smear surveys be performed once a week in normally contamination-free areas of the restricted areas and once a month in identified contaminated areas within restricted areas. The records of a sampling of the fourth quarter results indicated that the licensee had complied with these requirements and the spread of contamination had been contained and contamination levels within the facility had been kept to a minimum.
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Conclusions Staffing had been maintained in accordance with station procedures. The licensee had also complied with procedural requirements for conducting surveys and had been successfulin controlling extemal exposures and containing the spread of contamination.
Station dose accurately reflected the amount of work performed at LACBWR during the first two quarters of 1998.
4.3 Solid Radioactive Waste Manaaement and Transportation of Radioactive Materials j
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Insoection Scope (86750)
The inspectors interviewed the individual responsible for radioactive waste management and the radioactive materials shipping program. The inspectors also reviewed the shipping documents for one radioactive materials shipment made by LACBWR during
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the third quarter of 1998, b.
Observations and Findinas
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Very little dry active radioactive waste was generated or stored onsite during the
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third quarter of 1998. The licensee indicated that the approximately 130 cubic feet of
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radioactive resin stored onsite would be shipped for disposal in the summer of 1999.
I This would be the first shipment of radioactive resin from the site since 1987.
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During the third quarter of 1998, the licensee made one shipment of radioactive materials from the LACBWR facility. The shipment contained low activity air filters and
i water samples and had been shipped to an offsito laboratory for analyses. The j
L shipment was made without incident and the shipping documents indicated that the shipment had been made in full compliance with the applicable NRC and Department of Transportation (DOT) requirements.
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' Conclusions Reviews of the shipping documents for the radioactive materials shipment made during a
the third quarter of 1998 indicated that the shipment had been made in compliance with
NRC and DOT requirements.
4.4 Tours of the Facility l
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Inspection Scope (83750 and 86750)
i The inspectors toured the reactor building, the turbine building, the pump house and the
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containment building.
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Observations and Findinas Housekeeping in all of the buildings was excellent, all areas appeared to be clean and well maintained. Radiological controls and posting appeared to be in full compliance with procedural requirements. The material condition of the equipment and components observed was excellent.
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Conclusions No problems were noted during tours of the reactor buildirig, the turbine building, the pump house and the containment building.
5.0 Exit Management Meeting The inspectors presented the inspection results to members of the staff at the conclusion of the inspection on December 10,1998. The licensee acknowledged the findings as described in this report. The licensee did not identify any of the documents or processes reviewed by the inspectors as proprietary.
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PARTIAL LIST OF PERSONS CONTACTED l
- R. Christians, Plant Manager l
- R. Cota, Training / Security Supervisor
- D. Egge, Quality Assurance l
- J. Jiracek, Plant Maintenance
- M. Johnson, Tech Support Engineer
- L. Nelson, Health and Safety Supervisor
- Denotes those attending the exit meeting on December,1998.
The inspectors also interviewed other licensee personnel in various departments in the course of the inspection.
l lNSPECTION PROCEDURES USED IP 36801:
Organization, Management and Cost Controls at Permanently Shut Down Reactors
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lP 37801:
Safety Reviews, Design Changes and Modifications at Permanently Shut Down Reactors IP 40801:
Self-assessment, Auditing, Corrective Action IP 60710:
Refueling Activities IP 60801:
Spent Fuel Poo! Safety at Permanently Shut Down Reactors IP 71714:
Cold Weather Preparations IP 83750:
Occupational Radiation Exposure IP 86750:
Solid Radwaste Management and Transportation of Radwaste Materials Using Tl 2515/133, ' implementation of Revised 49 CFR 100-179 and 10 CFR Part 71" DOCUMENTS REVIEWED ACP-04.1, " Design and Facility Change Control," Revision 23, dated 10/17/97 Memorandum from Mike Johnson to the ORC, " Response to ORC-97-01, Assignment 1:
Corrective Action for LER 97-01 (Incident Report DPC 97-01, "Less than Required A.C. Power Sources")," July 15,1998 ORC /SCR Commitment Tracking document, August 25,1998 HSP 7.2," Sampling of FESW" Direct Exposure Rate Surveys (October 1998)
Smear Survey Results (November 1998)
Shipping Documents for third quarter 1998 l
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