IR 05000409/1999001
| ML20206H685 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/05/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20206H681 | List: |
| References | |
| 50-409-99-01, 50-409-99-1, NUDOCS 9905110284 | |
| Download: ML20206H685 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGIONlli i
Docket No:
50-409 i
License No:
DPR-45 Report No:
50-409/99001(DNMS)
Licensee:
Dalryland Power Cooperative 3200 East Avenue South La Crosse, WI 54602 Facility:
La Crosse Boiling Water Reactor Location:
La Crosse Site, Genoa, Wisconsin Dates:
April 14-16,1999
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Inspectors:
D. Nelson, M.S., Radiation Specialist P. Lee, Ph.D., CHP, Radiation Specialist Approved By:
Bruce L. Jorgensen, Chief Decommissioning Branch Division of Nuclear Materials Safety
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9905110204 990505 PDR ADOCK 05000409
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EXECUTIVE SUMMARY j
i La Crosse Boiling Water Reactor NRC Inspection Report 50-409/99001(DNMS)
i This routine decommissioning / safe storage inspection covered aspects of licensee
management and control, spent fuel safety, and radiological safety.
l Overall, the licensee's performance during decommissioning activities was good. All
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activities insp 3cted were conducted in compliance with the Decommissioning Plan, the Quality Assurance Program and the Technical Specifications.
Facility Manaoement and Control The licensee performed appropriate safety reviews prior to conducting limited
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dismantling of reactor components and systems.
A Quality Assurance vendor audit of the facility's waste processor indicated good
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management involvement in the radioactive waste program.
Computer failures due to the Y2K issue would not affect the safety of the spent fuel or
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compromise facility security, i
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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.
Radioloalcal Safety The Radiation Protection Program was effective in implementing the requirements of the
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Decommissioning Plan, the Quality Assurance Program and the Technical Specifications.
Housekeeping and the material condition of components throughout the facility was
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excellent.
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Report Details Summarv of Plant Activities Activities during the inspection period were limited to routine ongoing safe storage (SAFSTOR)
activities. There was some limited dismantlement of plant systems during the first quarter of 1999.
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 below.
1.2 (Open) LER 50-409/99-01(DNMS)
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On March 5,1999, the licensee reported to the NRC that during annual testing the Fuel Element Storage Well (FESW) retum line check valves were found to be bact leaking beyond their design bases. The acceptable back leakage rate for the valves was 0.005 gallons per minute (gpm) and the back leakage measured during the ter t!ng was 16 gpm. The return line enters the bottom of the FESW and the check valves, were installed on the retum line to restrict back flow from the FESW if the line ruptures during a seismic event. Since the 16 gpm leak rate was 9 gpm greater than the makeup capacity of the FESW, a rupture in the retum line upstream from the check valves could theoretically dra!n the FESW and uncover the spent fuel.
During followup testing, the licensee discovered that gently tapping the retum line with a metal object would ressat the valves and reduce flow to less than 0.005 gpm. During a seismic event the seismic shock waves would likely ressat the valves. In spite of this finding, the licensee initiated a modification plan to isolate the FESW retum line by capping the line upstream of the check valves and rorouting the FESW retum line to the top of the FESW. This modification would preclude the possibility of a FESW retum line rupture causing rapid draining of the FESW.
The modification plan had not been formally reviewed prior to the inspection. Therefore, this License Event Report (LER) will remain open pending NRC review of the approved modification package and cap installation.
1.3 Oraanization. Manaaement and Cost Controls at Permanentiv Shut Down Reactors a.
Insoection Scooe (36801)
The inspection evaluated whether the licensee's SAFSTOR organization, staffing and qualifications met the requirements of the Technical Specifications, the Quality Assurance Program (QAP) and the Decommissioning Plan.
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Observations and Findinos The' licensee's SAFSTOR organization has remained unchanged 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.
1.4 ~
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Insoection Scope The inspectors interviewed La Crosse Boiling Water Reactor (LACBWR) management to determine if the Y2K computer issue had been examined and addressed, b.
Observations and Findinas The licensee investigated the potential effects of multiple failures of the onsite computers due to the Y2K issue. The areas addressed included security, spent fuel safety and radiation monitoring. The licensee concluded from the investigation that the facility had sufficient resources to address any problem that could arise following multiple failures of the onsite computers, c.
Conclusions Computer failures due to the Y2K issue would not affect the safety of the spent fuel, prevent monitoring of effluents or compromise facility security.
1.5 Safety Reviews. Deslan Chanoes. and Modificeuens at Permanentiv Shutdown Readars a.
Insoection Scoos (37801)
The inspection evaluated whether the licensee t)ad established an adequate program to identify unresolved safety questions resulting from any facility design change, test, experiment, or modification during SAFSTOR.
b.
Observations and Findinos The inspectors reviewed three safety reviews (evaluations) that had been completed since the last inspection. Those safety reviews addressed the removal of the condensate pumps and piping, the partial removal of the full flow demineralizer system, and the removal of the emergency diesel generator and fuel oil storage tanks. The inspectors' reviews indicated that the licensee had applied the appropriate rigor of
ergineering and management review required for each activity. There were no unreviewed safety questions identified or changes required to the Technical Specifications.
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On March 5,1999, the licensee notified the NRC that during testing the FESW retum line check valves, the valves had not seated properly and were leaking beyond their design bases. Subsequent to the notification, the licensee discovered that the valves would seat properly if the retum line was gently tapped with a metal object. Despite this finding, LACBWR management made the decision to permanently cap and isolate a section of the line, rerouting retum flow to the top of the FESW. Although a modification package had been developed prior to the inspection, that package had not been formally reviewed by the licensee. The inspectors did, however, review the draft package and Interview the project engineer.
The FESW retum line check valves are physically located in the middle of a 12-foot section of the retum line that extends from the bottorn of the reactor vessel to the bioshield. The 12-foot section of pipe is seismically qualified and the check valves are designed to restrict backflow from the FESW if the retum line ruptures upstream of the valves during a seismic event. Because questions had been raised conceming the reliability of the check valves, management made the decision to cap the retum line upstream of the bioshield and reroute the retum line to the top of the FESW. This would eliminate the retum line as a potential leak pathway. Management conciuded that this modification would leave the plant in a safer configuration and the inspectors. agreed with that conclusion. At the exit meeting, the licensee indicated that work on the modification was due to begin in late spring or early summer of 1999.
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Conclusions The licensed configuration of the facility was not changed without the appropriate licensee safety reviews.
After reviewing the draft FESW retum line modification package and interviewing the project engineer, the inspectors concluded that the retum line modification would leave the plant in a safer configuration, q
1.6 Self-Assessment. Auditina. and Corrective Action at Permanentiv Shutdown Reactors a.
Inspection Scope (40801)
The inspectors reviewed the three incident Reports (irs) generated since the last inspection. The inspectors also reviewed a selection of Quality Assurance Audits
performed since the same 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 three irs had been generated since the last inspection. Those irs addressed a flash bum to hand (OSHA concem),
the excessive back leakage through the FESW retum line check valves, and a 1 B Emergency Diesel Generator 18 month test failure (not required by Technical Specifications). The excessive leakage was reported to the NRC and documented in Licensee Event Report No.99-001. The small number of irs appeared to be due in large part to the lack of activities within the plant.
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There were no Radiological Occurrence Reports (ROR) generated since the last inspection. Again, the number of RORs was due in large part to the lack of activities within the plant.
The inspectors reviewed four audits that had been completed since the last inspection.
Three of those audits addressed the Operational Manual / Technical Specifications.
Emergency Plan / Meteorological Monitoring, and Training. The audits had adequate range and depth and the auditors identified a number of Open items and Nonconformances. Follow up by the auditors of previous audit findings were also performed and documented. No safety significant findings were identified in any of these three audits.
The fourth audit was a 1999 Quality Assurance vendor audit of the facility's waste processor, U.S. Ecology - Oak Ridge Division. The inspectors noted that the Quality Assurance group had also audited the company in 1994 when the company was named the Quadrex Recycle Center. Six Dalryland Power Cooperative employees participated in the 1-day audit. The auditors examining all aspects of the vendor's operations including design control, procurement document control, procedures, identification and control of materials, test controls and intemal audits. The audit team found no concems or weaknesses in the vendor's processes or controls. By conducting these audits, corporate management demonstrated strong support for the La Crosso Bolling Water Reactor (LACBWR) radioactive waste program.
At the exit meeting, management acknowledged the findings of the audits.
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Conclusions The number of RORs and irs accurately reflected the level of activity in the plant during the first quarter of 1999. The four Quality Assurance audits reviewed appeared to have met the requirements and guidance in the Quality Assurance Plan.
- 2.0 Spent Fuel Safety 2.1 General The inspection verified the safe wet storage of spent fuel at LACBWR. Specific findings are detailed in the sections below.
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2.2 Soent Fuel Pool Safety at Permanentiv Shutdown Reactors a.
Insoection Scooe (60801)
The inspection evaluated the systems associated with the storage, control and maintenance of spent fuel in a safe manner.
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Observations and Findinos The inspectors reviewed the calibration records for the water level transmitter and the
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daily logs of water level observations made by the operators.
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I A review of the 1999 FESW water chemistry and gamma spectrum analyses results indicated that all parameters were within the limits specified in HSP-7.2," Sampling of FESW."
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Conclusions The spent fuel pool water level, chemistry and cleanliness control programs appeared adequate to ensure the safe wet storage of spent fuel.
3.0 Radlological Safety 3.1 General i
The inspectors conducted reviews of ongoing activities in order to assess the overall Radiation Protection (RP) Program. Specific findings are detailed in the sections below.
3.2 Occupational Radiation Exoosure a.
!Diggetion Scooe (83750)
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, and maintaining occupational exposure as-low-as-reasonably-achievable (ALARA).
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Observations and Findings There were no changes in the staffing or management of the RP Program since the last Inspection.
A review of the extemai dosimetry records for the fourth quarter of 1998 indicated that personnel exposures, individually and collectively, accurately reflected the level of actMty within the facility. A review of the 1998 Annual ALARA Review indicated that total accounted and unaccounted dose for 1998 was 1,101 millirem (mrem) or about 470 mrom less than 1997. A majority of the individuals who were issued dosimetry received little if any dose during 1998. This again accurately reflected the reduction in workload in 1998 from 1997 as well as the decline in dose rates due to the decay of Co-60. Station dose for 1999 is expected to be higher due to additional work being
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done in the containment building.
The inspectors reviewed a sampling of direct radiation survey results and smear sample results for the first quarter of 1999.
Station procedures require that direct radiation surveys be performed quarterly in all accessible areas within restricted areas. The records of the first quarter results
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indicated that the licensee had complied with these requirements and exposure rates within the facility had not changed significantly.
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
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contaminated areas within restricted areas. The records of a sampling of the first quarter 1999 results indicated that the licensee had complied with these requirements and the spread of contamination had been contained and contamination lavels within the facility had been kept to a minimum.
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.Qonclusions Staffing had been maintained in accordance with station procedures. The licensee had
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Station dose accurately reflected the amount of work performed at LACBWR during 1998.
3.3 Radioactive Waste Treatment. and Effluent and Environmental Monitorina
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Insoection Scooe (84750)
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The inspectors reviewed the 1998 Radioactive Effluent Report and the Radiological Environmental Monitoring Report. The inspectors also reviewed the changes made to
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Observations and Findinas
- A review of the 1998 Radioactive Effluent Report and the Radiological Environmental Monitoring Reports indicated that all calculated offsite doses due to effluents were below the ODCM limits based on 10 CFR Part 50, Appendix 1, and 10 CFR Part 20, Appendix B, Table 2, Column 2. For gaseous effluent releases the maximum organ dose from all radionuclides was 3.96 E-5 mrem and for liquid effluent releases the cumulative annual total dose was approximately 4.97 E-1 mrem. The Radiological Environmental Monitoring Report reported that there.was some minimal activity in sediment collected from the discharge outfall and there were no significant plant-attributable radionuclides in any of the other samples coliected (air, milk, fish, vegetation and river water).
Environmental thermoluminesent dosimeters (TLD) posted within and around the facility during 1998 indicated that the doses from direct radiation measured were within the limits specified in the regulations. The highest doses were found in areas that had been previously identified by the licensee.
The interlaboratory Comparison Program results indicated that LACBWR's analytic laboratory results closely matched those of the contractor's.
The Offsite Dose Calculation Manual was last revised in October 1998 (Revision 5). A review of the changes made to Revision 4 of the ODCM indicated that they were minor in nature and accurately reflected the current SAFSTOR status of the facility, c.
Conclusions A review of the 1998 Radioactive Effluent Report and the Radiological Environmental Monitoring Report and a review of the results from the Interlaboratory Confirmatory Measurements Program indicated that the Effluent and Environmental monitoring
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programs at LACBWR had been implemented in accordance with the ODCM and NRC regulations. Changes made to Revision 4 of the ODCM were minor in nature and accurately reflected the current SAFSTOR status of the facility.
3.4 Solid Radioactive Waste Manaaement and Transportation of Radioactive Materials a.
Insoection Scooe (86750)
The inspectors interviewed the individual responsible for the radioactive materials shipping program. The inspectors also reviewed the shipping documents for the two radioactive materials shipments made by LACBWR during the first quarter of 1999.
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Observations and Findinas Due to some limited dismantlement of the facility during the first quarter of 1999, a small volume of dry active radioactive waste was generated. The inspector noted the container housing the waste was in a secure location and the container had been properly posted.
During the first quarter of 1999, the licensee made two shipments of radioactive materials from the LACBWR facility. The shipments contained low activity air filters and water samples. The samples were shipped to an offsite laboratory for analyses. The shipments was made without incident and the shipping documents indicated that the shipments had been made in full compliance with the applicable NRC and Department of Transportation (DOT) requirements.
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Conclusions
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Reviews of the shipping documents for the radioactive materials shipments made during the first quarter of 1999 indicated that the shipment had been made in compliance with NRC and DOT requirements.
3.5 Tours of the Facility a.
Inspection Scooe (83750 and 86750)
The inspectors toured the grounds immediately surrounding the facility as well as the reactor building, the turbine building, and the 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 and regulatory requirements. The material condition of the equipment and components observed was excellent.
The inspectors did find an environmental TLD housed in a protective case that had dislodged from its support and had fallen to the ground. The inspectom retumed the TLD to the licensee and it was immediately reattached to its support.
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' No significant problems were noted during tours of the grounds, the reactor building, the turbine building, and the containment building.
4.0 Exit Meeting The inspectors presented the inspection results to members of the licensee's staff at the conclusio(i of the inspection on April 16,1999. 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
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- R. Christians, Plant Manager
- R. Cota, Training / Security Supervisor
- D._Egge, Quality Assurance j
- J. Jiracek, Plant Maintenance
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- M. Johnson, Tech Support Engineer
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- L. Nelson, Health and Safety Supervisor
Denotes those attending the eint meeting on April 16,1999.
The inspectors also interviewed other licensee personnel in various departments in the course of the inspection.
INSPECTION PROCEDURES USED IP 36801:
Organization, Management and Cost Controls at Permanently Shut Down Reactors IP 37801:
Safety Reviews, Design Changes and Modifications at Permanently Shut Down Reactors j
IP 40801:
Self-assessment, Auditing, Corrective Action l
.lP 60710:
Refueling Activities IP 83750:
Occupational Radiation Exposure
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IP 84750 Radioactive Waste Treatment, and Effluent and Environmental Monitoring IP 86750:
Solid Radwaste Management and Transportation of Radwaste Materials 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 HSP 7.2," Sampling of FESW" Direct Exposure Rate Surveys (January 1999)
i Smear Survey Results (April 1999)
Shipping Documents for first quarter 1999 1998 Annual ALARA Review
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